ML20217K059
| ML20217K059 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/31/1997 |
| From: | DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20217J993 | List: |
| References | |
| PROC-971231, NUDOCS 9804070109 | |
| Download: ML20217K059 (306) | |
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..- Unit 1 and 2 Offsite Dose Calculation Manual
- issue 3, Revision 2 Effective May 30,1997 and-Issue 3, Revision 3 Effective Juna 9,1997
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In an effort to reduce over.tll costs associated with this report, only the following have been c=t a complete copy of the ODCM:
r United States Nuclear Regelatory Commission Document Contrc t Desk Washington, DC 20555 United States Nuclear Regulatory Commission Regional Administrator, Region 1 475 Allendale Road King of Prussia, PA 19406 if your organization desires a complete copy of the ODCM, contact Mr. AT Lonnett at 412-393-5860 for resolution.
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Beaver Valley Power Station BV-1 and 2 ODCM Copy Holders Lou BV-1 and 2 ODCM Issue No. 3 Revision No. 3 Effective Date 6-9-97 Controlled Copies Unit 1 Control Room (NSS) No. 1 HP Manager No. 2 Unit 2 Control Room (NSS) No. 3 Effluent Control (SHPS) No. 4 Unit 1 Rad Operations Director No. 5 licensing No. 6 Unit 1 Operations Manacer No. 7 Unit 2 Operations Manacer No. 8 Operations Procedure Group No. 9 I&C Procedures Groun No. 10 Unit 1 Operators Console No. 11 Unit 2 Operators Console No. 12 SPED No. 13 Trainine Manacer No. 14 Unit 1 Simulator No. 15 Unit 2 Simulator No. 16 Uncontrolled Copies PA-DEP (BRP) No. 1 NRC Resident Inspector No. 2 No. 3 ODCM Historical File No. 4 RE File 6.101-02 No. 5 Document Control (RTL A9.621B) No. 6 ARERR File (Document control Desk) No. 7 ARERR File (Reelon 1) No. 8 No. 9 j Effluent Control Offsite Use (SHPS) No. 10 REMP Administrator No. 11 Effluent Control Offsite Use (HPS) No. 12 )
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No.- No. - Issued Meeting No. Date Meeting No. Date _ Signature Date Date Title 3- 3- xxvi BV-RSC-97-14 6/9/97 OSC Poll 3101 6/9/97 ' 6/9/97 4 6)9M
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No. No. Issued Meeting No. Date Meeting No. Defe Signature Date Date 3 2 i BV-RSC-97-11 5/13/97 OSC Poll 3099 5/17/97 A sje,):n 5/30/97 XXVI l 19 I-20 1-27 1-32 3-2 33 C-10 C-13 C-14 6
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DUQUESNE LIGHT COMPANY INCLUDED
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No. Issd. Meeting No. Date Meeting No. Date No. Sign. Date Date 2 2 Title 2
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No. Issd. Sign. Date Review Date Sign. Date Date O TITLE PGS BV-RSC-11-87 BV-OSC-17-87
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No. Issd. Sign. Date Review Date Sign. Date Date 1 TITLE PGS BV-RSC-11-87 BV-OSC-17-87 y i thru viii BV-RSC-12-87 June 12, 1987 -
7/24/87 1-1 thru 1-18 BV-RSC-14-87 7/M/37 2-1 thru 2-98 May 29, 1987 3-1 thru 3-14 &4 4-1, 5-1 A-1 thru A-7 l B-1 and B-2 2 2-12 BV-RSC-38-87 BV-1-OSC-25-87 g 12/22/87 2-15 12/3/87 12/15/87
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B'eaver Valley Power Station Unit 1 Docket No. 50-334 2
License No. DPR-66 Beaver Valley-Power. Station Unit 2 I Docket No. 50-412- !
License No. NPF-73 4
i BEAVER VALLEY POWER STATION UNIT 1 (BV-1)
BEAVER VALLEY POWER STATION UNIT 2 (BV-2)
.OFFSITE DOSE CALCULATION MANUAL (ODCM)
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. ,O ISSUE 3
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Revision 3 l.
4
BV-1 and 2 ODCM TABLE OF CONTENTS
, SECTION TITLE PAGE NO.
.) Table Of Contents................................... i List Of Tab 1es....................................... .iii List Of Figures..................................... vii ODCM Equation Cross Reference....................... vili ODCM Table Cross Reference..................,........ x Preface............................................. xiii H i s t o ry O f ODCM Ch an ge s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . xiv 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 I
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.......... 4....... 1-10 References For Liquid Alarm Setpoints............... 1-15 1.2 Compliance With 10 CFR 20 EC Limits............. 1-16
,- 1.2.1 Batch Releases................................ 1-16
) 1.2.2 Continuous Releases........................... 1-18 1.3, Compliance With 10_CFR 50 Dose Limits........... 1-21 1.3.1 Cumulation of Doses.................... ...... 1-21
- 1. 3. 2 Proj ec t ion Of Doses . . . . . . . . . . . . . . . . . . . . . . . . . . 1-23 1.4 Liquid Radvaste System.......................... 1-27 1.4.1 BV-1 Liquid Radvaste System Components........ 1-28 1.4.2 BV-2 Liquid Radvaste System Components........ 1-29 2.0 - GASEOUS EFFLUENTS................................... 2-1 2.1 Alarm Setpoints................................. 2-2 2.1.1 BV-1 Monitor Alarm Setpoint Dete_aination..... 2-2 2.1.1.1 BV-1 Setpoint Determination Based On A Calculated Mix (Ground Releases)............ 2-5 2.1.1.2 BV-1 Setpoint Determination Based On Analysis Prior To Release (Ground Releases). 2-10 2.1.2 BV-2 Monitor Alarm Setpoint Determination..... 2-13 2.1.2.1 BV-2 Setpoint Determination Based On A Calculated Mix (Ground Releases)............ 2-13 2.1.2.2 BV-2 Setpoint Determination Based On Analysis Prior To Release (Ground Releases). 2-19 p
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i ISSUE 3 Revision 1
BV-1 cnd 8 ODCH TABLE OF CONTENTS SECTION TITLE PAGE NO.
2.1.3 BV-1/2 Monitor Alarm Setpoint Determination... 2-22 2.1.3.1 BV-1/2 Setpoint Determination Based On A Calculated Mix (Elevated Releases).......... 2-22 2.1.3.2 BV-1/2 Setpoint Determination Based On Analysis Prior To Release (Elevated Releases) 2-26 References For Gaseous Alarm Setpoints...........-.... 2-33 2.2 Compliance Vith 10 CFR 20 Dose Rate Limits...... 2-34 2.2.1 Dose Rate Doe 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 of Doses . . . . . . . . . . . . . . . . . . . . . . . . . 2-65 2.3.2 Doses Due To Radioiodines And Particulates.... 2-66 2.3.2.1 Cumulation of Doses......................... 2-66
- 2. 3. 2. 2 Proj ec tion Of Dos es . . . . . . . . . . . . . . . . . . . . . . . . . 2-78 2.4 Gaseous Radvaste System......................... 2-117 2.4.1 BV-1 Gaseous Radvaste System Components....... 2-118 2.4.2 BV-2 Gaseous Radvaste System Components....... 2-119 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM....... 3-1 4.0 INFORMATION RELATED TO 40 CFR 190................... 4-1 1 5.0 SITE BOUNDARY FOR GASE0US AND LIQUID EFFLUENTS...... 5-1 l
i Appendix A Summary 0* Dispersion Calculational Procedures...... A-1 Appendix B Inputs To Computer Codes For Generation Of Source Terms.....................................,.. B-1 Appendix C ODCM Controls........................................ C-1 l Appendix D Bases For ODCM Controls............................. D-1 Appendix E Annual Reports...................................... E-1 Appendix F ODCM Control Procedure Matrix....................... F-1 l
l f
11 ISSUE 3 Revision 1
BV-1 cnd 2 ODCM a
LIST 0)' TABLES
[m_,) . TABLE NO. TITLE , ,
.PAGE NO.
LIQUID EFFLUENT TABLES 1.1-la' BV-1 Liquid. Source Term.............................. 1-12 1.1-1b- BV-2 Liquid Source Term.............................. 1-13 1.2-la BV-1 Recirculation Times Raquired Before Sampling of Liquid Discharge. Tanks............................... 1-19 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 q ' CASEOUS 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 Caseous Effluents.......... 2-46 2.2-2b BV-2 Radionuclide Mix For Gaseous Effluents.......... 2-47
(s) 2.2-3 Distances Of Limiting Maximum Individual Receptors To Release Points For Annual X/0 Values.............. 2-48 ANNUAL AVERAGE X/0 VALUES FOR CONTINUOUS RELEASES (SPECIAL DISTANCES AND CONTROL LOCATIONS)~
2.2 BV-1 And 2 Containment Vents (Ground Release)........ 2-49 2.2 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 EV-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 1 1
!- DOSE FACTORS AND DOSE PARAMETERS FOR GASEOUS EFFLUENTS l
2,2-11 Dose Factors For Noble Gases And Daughters........... 2-56 l 2.2-12 Dose Parameters For Finite Elevated Plumes, Beaver Valley Site................. ........................ 2-57 2.2-13 P g7 Values For A Child For The Beaver Valley Site.... 2-58 I
-MODES OF GASEOUS RELEASES d
2.3-1 Modes Of Gaseous Release Form The Beaver Valley Site Vents For Implementation Of 10 CFR 20 And 10 CFR 50.. 2-79 fm iii ISSUE 3 Revision 1 o -
^j BV-1 cnd 2 ODCH f '
< LIST OF TABLES TABLE NO. TITLE PAGE NO.
R VALUES FOR BEAVER VALLEY SITE 2.3-2 Inhalation - Adu1t................................... 2-80 2.3-3 Inhalation - Teen.................................... 2-81 2.3-4 Inhalation - Child................................... 2-82 2.3-5 Inhalation - Infant.................................. 2-83 2.3-6 Ground............................................... 2-84 2.3-7 Vegetation - Adult................................... 2-85 2.3-8 Vegetation - Teen.................................... 2-86 2.3-9 Vegetation - Chi 1d................................... 2-87 2.3-10 Heat - Adult......................................... 2-88 2.3-11 Heat - Teen.......................................... 2-89 2.3-12 Heat - Chi 1d......................................... 2-90 2.3-13 Cow Hilk - Adult..................................... 2-91 2.3-14 Cow Hilk - Teen...................................... 2-92 2.3-15 Cov Hilk - Chi 1d..................................... 2-93 2.3-16 Cow Hilk - Infant.................................... 2-94 2.3-17 Goat Hilk - Adult.................................... 2-95 2.3-18 Goat Hilk - Teen..................................... 2-96 2.3-19 Goat Hilk - Chi 1d.................................... 2-97 2.3-20 Goat Hilk - 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 O 2.3-22 BV-1 And 2 lontainment Vents-(Ground Release)........ 2-100 l- 2.3-23 BV-1 And 2 'lentilation Vents (Ground Release). . . . . . . . 2-101 l 2.3-24 BV-1 And 2 Turbine Building Vents (Ground Release)... 2-102 2.3 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)... 2-205 ANNUAL AVERAGE D/0 VALUES FOR CONTINUOUS RELEASES (SPECIAL DISTANCES) l 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 O
iv ISSUE 3 Revision 1
BV-1 cnd 2 ODCM LIST OF TABLES i TABLE NO. TITLE PAGE NO.
ENVIRONMENTAL MONITORING 3.0-1 Radiological Environmental Monitoring Program........ 3-4 DISPERSION CALCULATION PROCEDURES A1 BV-1 And 2 Release Conditions........................ A-3 INPUTS TO COMPUTER CODES FOR GENERATION OF SOURCE TERMS Bila Inputs To GALE Code For Generation Of BV-1 Liquid Source Term Mixes.................................... B-2 B:1b Inputs To SVEC LIQ 1BB Code For Generation Of BV-2 Liquid Source Term Mixes............................. B-3 B:2a Inputs To SVEC GAS 1BB Code For Generation Of BV-1 Gaseous Source Term Mixes............................ B-4 B:2b Inputs To SWEC GAS 1BB Code For Generation of BV-2 Gaseous Source Term Mixes............................ B-3 ODCM CONTROLS FOR INSTRUMENTATION, SAMPLING, AND ANALYSIS REQUIREMENTS C:1.1 Operational Modes.................................... C-5 w C:1.2 Frequency Notation................................... C-6
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' 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 Waste 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 Lower Limits Of Detection (LLD) C-52 FORMAT FOR ANNUAL REPORT E:6.9-1 Environmental Radiological Monitoring Program Summary E-2 g
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v ISSUE 3 Revision 1
BV-1 Cnd 2 ODCM LIST OF TABLES TABLE NO. TITLE PAGE NO.
O ODCM CONTROLS PROCEDURE MATRIX F:la BV-1 Liquid Effluent Monitor Surveillances................. F-2 F:1b BV-2 Liquid Effluent Monitor Surveillances................. F-3 F:2a BV-1 Gaseous Effluent Monitor Surveillances................ F-4 F:2b BV-2 Gaseous Effluent Monitor Surveillances................ F-5 F:3 BV-1 and 2 Liquid Effluent Concentration Surveillances..... F-7 F:4 BV-1 and 2 Liquid Effluent Dose Surveillances.............. F-8 F:5 BV-1 and 2 Liquid Effluent Treatment Surveillances......... F-9 F:6 BV-1 and 2 Gaseous Effluent Dose Surveillances............. F-10 F:7 BV-1 and 2 Gaseous Effluent Air Dose Surveillances......... F-11 F:8 BV-1 and 2 Gaseous Effluent Particulate and Iodine......... F-12 Dose Surveillances..............................
F:9 BV-1 and 2 Gaseous Effluent Treatment Surveillances........ F-13 F:10 BV-1 and 2 Total Dose Surveillances. . . . . . . . . . . . . . . . . . . . . . . . F-14 F:11 BV-1 and 2 REMP Surveillances.............................. F-15 F:12 BV-1 and 2 Land Use Census Surveillances................... F-16 F:13 BV-1 and 2 Interlaboratory Comparison Program.............. F-17 i
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, vi ISSUE 3 Revision 1
BV-1 cnd 2 0DCH 1 i
}~ LIST OF FIGURES
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\) FIGURE NO. TITLE PAGE NO.
LIQUID EFFLUENT-FIGURES ~
1.4 BV-1 Liquid Radvaste System......................... 1-30 1.4-2 BV-2 Liquid Radvaste System.......................... 1-31 1.4-3 BV-1 and 2 Liquid Effluent Release Points........... 1-32 GASEOUS EFFLUENT FIGURES' 2.4-1 BV-1 And 2 Gaseous Radvaste System.................. 2-121 2.4-2 BV-1 And 2 Gaseous Effluent Release Points.......... 2-122 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM FIGURES i )
3.0-1 Air Sampling Locatiors.............................. 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 Vater, And Drinking Vater Sampling Locations............................ 3-13 3.0-7 Milk Sampling Locations............................. 3-14 3.0-8 Foodcrop Sampling Locations......................... 3-15 7 ~s 3.0-9 Fish Sampling Locations............................. 3-16 i )
~ SITE BOUNDARY FIGURES 5-1 Site Boundary For Gaseous And Liquid Effluents...... 5-1 f
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t vii ISSUE 3 Revision 2 l.
BV-1 cnd 2 ODCM ODCM EQUATION CROSS REFERENCE FOR LIQUID EFFLUENTS FROM: T0: FROM:
PREVIOUS CURRENT PREVIOUS BV-1 ODCH BV-1 AND 2 ODCM BV-2 ODCM ISSUE 2, REV. 2 ISSUE 3 ISSJE 1, REV. 3 AND EARLIER AND LATER AND EARLIER 1.1-1 1.1(1)-1 --
1.1-2 1.1(1)-2 --
1.1-3 1.1(1)-3 --
1.1-4 1.1(1)-4 --
1.1-5 1.1(1)-5 --
1.1-6 1.1(1)-6 --
1.1-7 1.1(1)-7 --
1.1-8 1.1(1)-8 --
1.1(2)-1 1.1-1 1.1(2)-2 1.1-2 1.1(2)-3 1.1-3 1.1(2)-4 1.1-4 1.1(2)-5 1.1-5 1.1(2)-6 1.1-6 1.1(2)-7 1.1-7 1.1(2)-8 1.1-8 1.2-1 1.2-1 1.2-1 Thru Thru Thru 1.2-4 1.2-4 1.2-4 1.3-1 1.3-1 1.3-1 Thru Thru Thru 1.3-8 1.3-8 1.3-8 l
l l
viii ISSUE 3 Revision 1 t
BV-1 cnd 2 ODCM ODCM EQUATION CROSS REFERENCE
( 'N FOR GASEOUS EFFLUENTS x__
FROM: TO: FROM:
PREVIOUS' CURRENT PREVIOUS BV-1.0DCM 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 2.1-4 211(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 I)
\'
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 --
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 l 2.1-24 2.1-24 2.1-24 l
i 2.2-1 2.2-1 2.2-1 l- 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
(^3 L) ix ISSUE 3 Revision 1 J
BV-1 Gnd 2 ODCH i
ODCH TABLE CROSS PIFERENCE FOR LIQUID EFFLUENTS FROM: T0: 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 1.1-1 1.1-la --
-- 1.1-lb 1.1-1 1.2-1 1.2-la --
-- 1,2-1b 1.2-1 1.3-1 1.3-1 1.3-1 O
3 0
x ISSUE 3
' Revision 1
m
. BV-L and L 2 ODCM; 1 ObCMTABLE.CROSSREFERENCE-
/"'S1 -FOR GASEOUS EFFLUENTS Oj,
- FROM
- ' !TO: FROM': -
7 PREVIOUS CURRENTL PREVIOUS:-
BV-1..'0DCM . -BV-1 AND 2'0DCM-BV-2 0DCM LISSUE'2,"REV.c2" ' ISSUE 3- ISSUE 1,:REV. 3 AND EARLIER. AND LATER- AND EARLIER
( l 2.1-1~ 2.1-la --
1
- -1 2.1-1b' 12.1-1 2.1-2 2.1-2a.
-- . 2.1-2b 2.1-2
.2.2 2.2-1 2.2 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 lI I
.~
A-2 A-3 2.3-35 2.3-35 A-2 A-3 A-4 2.3-37 A-4
% e. A-5 2.3-38 A-5 3.0-1 3.0-1 3.0-1.
t
,l(~.
b 7,y ..
xi ISSUE 3 Revision 1
BV-1 ond 2 ODCM ODCM TABLE CROSS REFERENCE FOR ODCM AFFENDICES FROM: T0: FROM:
FREVIOUS CURRENT FREVIOUS BV-1 ODCM BV-1 AND 2 ODCM BV-2 ODCM ISSUE 2, REV. 2 ISSUE 3 ISSUE 1, REV. 3 AND EARLIER AND LATER AND EARLIER A-1 A:1 A-1 (Unnumbered) B:la --
-- B:1b (Unnumbered)
(Unnumbered) B:2a --
l -- B:2b (Unnumbered)
-- C:1.1 --
-- C:1.2 --
-- C:3.3-12 --
-- C:4.3-12 --
-- C:3.3-13 --
-- C:4.3-13 --
C:4.11-1 --
-- C:4.11-2 --
-- C:3.12-1 --
l
-- C:3.12-2 --
-- C:4.12-1 --
-- E:6.9-1 --
f l
-- F:la --
-- F:1b' --
-- F:2a --
-- F:2b --
-- F:3 --
I --
F:4 --
F:5 -- 15
-- F:6 --
F:7 --
-- F:8 --
j -- F:9 --
! -- F:10 --
F:11 --
F:12 --
F:13 --
l l
l l
9 l
xii ISSUE 3 Revision 1 1
1
BV-1 cnd 2 ODCM PREFACE (ml' V
~a Thisj oFFSITE- DOSE CALCULATION MANUAL (ODCH) provides .the' information and methodologies to be used by Beaver Valley Power Station Unit 1 and Unit 2 (BV-1) and (BV-2) to assure compliance with the Administrative controls Section of the operating Technical Specifications. They .are. intended ~te show ccmpliance with 10 CFR 20.106:or 10 CFR 20.1302 as appropriate, 10 CFR 50.36a, Appendix I of 10 CFR 50, and 40 CFR 190.
This ODCM is based on the following United States Nuclear Regulatory Commission (USNRC). documents:
- NUREG-0472, Draft. 7 for Rev. 3, September, 1982, Standard Radiological
-Effluent Technical Specifications For PVRs.
- NUREG-0133, October, 1978, Preparation Of Radiological Effluent Technical Specifications For Nuclear Power Plants.
- Generic Letter 89-01, January 31, 1989, Implementation Of Programmatic
, Controls For Radiological Effluent Technical Specifications In The i Administrative Controls Section Of The Technical Specifications And The Relocation Of Procedural Details Of RETS To The'0DCM Or To The PCP.
- NUREG-1301, April, 1991, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls For Pressurized Vater Reactors, Generic Letter 89-01, Supplement No. 1.
(, - 3!
' Other miscellaneous inputs from the USNRC.
Specific plant procedures for implementation of this manual are included in the Health Physics Manual (BVPS-EPM) and the Radiological Engineering Administrative Manual (REAM). These procedures are utilized by the operating staff to assure ccmpliance.vith Technical Specifications and the Appendix C CONTROLS of the ODCM.
The ODCM has been prepared as generically as possible in order to minimize the need for future versions. However, some changes to the ODCM may be necessary'in the future. Any such changes vill be properly prepared, reviewed, and approved l as indicated in the Administrative Control Section of the Technical' i Specifications. An implementation procedure for control of the ODCM is included l in the REAM. In summary, any ODCM changes vill be properly justified to ensure i that ODCM changes will maintain the level of radioactive effluent control !
required by 10 CFR 20.106 or 10 CFR 20.1302 as appropriate, 40 CFR Part 190, 10 CFR 50.36a and Appendix I to 10 CFR 50 and not adversely impact the accuracy or reliability of effluent dose, or setpoint calculation.
1
/-
(a )
l xiii ISSUE 3 Revision 1
BV-1 cnd 2 ODCM HISTORY OF ODCM CHANGES (1) BV-1 ODCM, Issue 1 (Effective January, 1984)
This is the initial issue of the BV-1 ODCM, as prepared for implementation of the Radiological Effluent Technical Specifications (RETS).
Implementation of this manual was commensurate with Amendment No. 66 to the Unit 1 Technical Specifications as approved by the NRC on March 28, 1983.
(2) BV-1 ODCM, Issue 1, Revision 1 (F2fective October, 1984)
A description of the changes that vere implemented with this revision are as follows:
- Table 1.3-1 was revised to include liquid dose factors for nuclides presently identified at BVPS and not included in the original table.
- Equations 2.1-19 and 2.1-22 were revised as approved at RSC Meeting No. BVPS-RSC-1-84 on January 31, 1984. The equations were revised to clarify flow rate terminology.
- Section 2.2.2 was revised to delete the food and ground pathvays for f gaseous dose rate calculations of I-131, tritium, and radionuclides in particulate form with half lives greater than 8 days.
- Table 2.2-13 was revised to include 7 organs rather th'an only the maximum organ. Also, the receptor vas changed from infant to child, and addition / deletion of nuclides to be consistent vith the Technical Specifications and nuclides identified at BV-1.
(3) BV-1 ODCM, Issue 1, Revision 2 (Effective July, 1986) ;
A description of the changes that vere implemented with this revision are as follovs:
- Provide a flow based monitor setpoint adjustment factor in Section 1.1.2. This change makes Section 1.1.2 consistent with Section 1.1.1 and current procedures.
- Revise the 31-day dose projection limits and methodology in Sections 1.3.2, 2.3.1.2, and 2.3.2.2. This change corrected the 31-day dose projection limits and changed the dose projection methodology to be consistent with proposed software.
- Revise the Gaseous Effluent Monitor Setpoints in Sections 2.1.1 and L 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.
t O xiv ISSUE 3 Revision 1
BV-1 cnd 2 ODCH (4) BV-1 ODCM, Issue 2,'(Effective July, 1987)
[] BV-2 ODCM, Issue 1, Revision 1 (Effective July, 1987)
LI Vith the start-up of BV-2 in the second half of 1987, the BV-1 ODCM required revision and the BV-2 ODCM required initial implementation. A description of the changes are as follows:
' Produce functionally compatible BV-1 and BV-2 ODCMs which address site dose rate limits and meet regulatory requirements. Note that due to the. l scope of the revisions to the Unit 1 ODCM, it was re-issued as Issue 2.
Also, for clarity, the draft BV-2 ODCM previously submitted to the NRC was regarded as Issue 1 (historical) and operation of BV-2 began with j Issue 1, Revision 1 of the BV-2 ODCH.
'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 !
I gaseous radvaste and the apportionment of dose, according to NUREG-0133 was incorporated into both ODCMs. -
- Separate ground level gaseous releases were maintained. The BV-1 ODCM was updated to incorporate the BV-2 five year meteorology base. Gaseous source terms were revised to that calculated for BV-1 in the BV-2 FSAR, )
and terms vere added for calculation of a turbine building release.
( )
- The gaseous effluent monitor alarm setpoints of both ODCMs vere revised
as required by revisions to meteorology, source terms, monitor i
. efficiencies, and revised percentages of site dose rate limits. j
' 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 Containment air volume change time period is
~
60 minutes, then the maximum value for "T".is 16 (i.e., 960 minutes / l 60 minutes - 16). {
(5) BV-1 ODCM, Issue 2, Revision 1 (Effective December, 1987)
BV-2 ODCH, Issue 1, Revision 2 (Effective December, 1987)
Sections 2.1.3 and 2.1.4 of both ODC'is were changed to delete a note j 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 ODCH, Issue 2, Revision 2 (Effective June, 1989)
BV-2 ODCM, Issue 1, Revision 3 (Effective June, 1989) i f
i A description of the changes that were implemented with this revision are l as follows:
O ' Both ODCMs were revised for addition of Sections 1.4 and 2.4. This I
' i,/ addition gives a description of and includes flow diagrams of the Liquid '
Radvaste System and the Gaseous Radvaste System. (See justification 1) xv ISSUE 3 l Revision 1 ;
BV-1 Cad 2 ODCM
' Correct the following typos to BV-1 ODCM Equation 1.1-8:
A. Show differentiation between the two f's. (See Justification 1)
B. Add the division sign. (See Justification 1)
- Re-define F in equatica 1.3-1 of both ODCMs, as allowed by the k
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 ODCri equat'.on 1.3-8, add a division sign between the brackets.
(See Justifice. tion 1)
C. Add the verds "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 ODCHs. "his ensures compliance with the current requirements of the Technical Specifications. (See Justification 2)
D. Equation 2.1-20 of both ODCMs, change the HHSP to HSP mul:iplier from 0.70 to 0.33. (See Justification 1)
E. Equation 2.1-24 of both ODCHs, change the HHSP to HSP multiplier from 0.70 to 0.33. (See Justification 1)
F. Cor.ect punctuation in Section 2.3.2.1 of the BV-1 ODCM.
(See Justification 2)
G. Correct typos in Table 3.0-1 of both ODCMs. (See Justification 2)
H. Correct typos in Figure 3.0-3 of both ODCMs. (See Justification 2)
- Add Reference (7) to Se: tion 2 of the BV-1 ODCH. (See Justification 3)
- Add the words "from the site" to Section 2.2.2 of both ODCMs. This ensures compliance with the current requirements of the Technical Specifications. (See Justification 2)
- Revise BV-1 ODCM Table 2.2-2 to change the particulate and iodine radionuclide mix for the Unit 1 Ventilation Vent and to correct a typo for Xe-135m in the Containment Vacuum Pumps. (See Justification 3) f
' Provide re-verified P values for the Beaver Valley site in Table 2.2-13 of both ODCMs. (See Justification 1) l
- Correct the definition forODCMs.
the t f(value in the cow-meat pathway in Section 2.3.2.1 of both See ustification 1) l l
!
- 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 E of the
.M-1 ODCH. (See Justification 3) xvi ISSUE 3 l Revision 1 l
l
BV-1 cnd'2 ODCM
'The' justification used'for Change (6) to the ODCMs are as follovs:
il 1. . A letter dated March 2, 1989 (from the NRC) vas received by Duquesne Light regarding' acceptance of the Offsite Dose Calculation Manuals.-
The NRC acceptance of the BV-1 :and BV-2 ODCMs was based on Technical ~
Evaluation Reports (TER No. EGG-PHY-8194 and EGG-PHY-8217) provided by.
the Idaho National-Engineering Laboratory.
~ .
As stated in the letter, minor concerns are delineated in.Section 4 of the TER. In general, these concerns are considered typos or additions and in.-one vay Impact any of the- calculations currently being performed for dose contributions. However, one of these concerns is regarding the inability to reproduce the ODCM R values for'the cov-meat; cov-milk and goat-milk pathways when.using the ODCM/NUREG-0133 methodology. These R values (along with all other ODCM R values) vere re-validated VIA Calculation Package No. ERS-ATL-89-014. The results
'of this package showed that the R values for the three aforementioned pathways were-in error. Since the R valves 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. Ae requested by DLC letters ND3NSM:3431, NDINSM:3522, and ND1NSM:3652, 7echnical Specifications were required to be verified in all plant
. ,q . implementing procedures. As part of this effort, vording errors / typos This revision
(') : -
vtre identified in various sections of the ODCM.
ccrrects 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 vere identified between ODCM Table 2.2-2 and similar tables of the BVPS-2 i FSAR. Evaluation showed that apparent credit was given for continuous filtration of SLCRS releases which is invalid at Unit 1. However, the calculation package on which the BVPS-2 FSAR' expected release tables are based,- is correct (i.e.; no credit was taken for routine filtration for Unit l' releases). Except for revising the ODCM, no further corrective action is necessary because the particulates and iodines.in the ODCM were not used for gaseous effluent alarm setpoint.
Therefore, thfs change does' not adversely impact the accuracy.or
. reliability of setpoint calculations.
- (7) BV-1 and 2 ODCM, Issue 3 (Effective August, 1995) j 4 i
'The combined ODCM, as implemented by ISSUE 3, contains the following- I 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 l maintain the level of radioactive effluent controlrequiredby10CFRagg -
20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part
-()
f'% - 50. Also, this merger vill not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
j xvii ISSUE 3 Revision 1
BV-1 end 2 ODCM
- Revised Section 1.0 (Liquid Effluents) to show compliance with 10 CFR 20 Appendix B (20.1001 - 20.2401), Table 2, Col. 2 EC's. This includes the following:
- Revising the alarm setpoints for monitors (RM-LV-104, RM-LV-116, and 2SGC-RQ100)
- Updating the BV-1 monitor detection efficiencies
- Updating discharge rate and dilution rate parameters for BV-1 and BV-2
- Adding the alarm setpoints for monitors (RM-RV-100, RM-DA-100, 2SVS-R0101, and 2SVS-R0102)
- Revised Section 1.0 (Liquid Effluents) and Section 2.0 (Gaseous Effluents) to merge the SV-1 alarm setpoint calculations with the BV-2 alarm setpoint calculativas. For all practical purposes, when Tables, Figures, and Equations were transferred to the combined ODCM, the numbering was kept generically equal. The only exception to this are as follovs:
- If a table var contained iu both ODCMs, but each had data specific ,
to BV-1 or BV-2, then an a or b was. added to the table. For ' '
example, Table 1.1-1 was previously included in the BV-1 ODCM and the BV-2 ODCM. These tables are now numbered 1.1-la and 1.1-1b denoting BV-1 and BV42 respectively. A cross reference for ODCM tables is provided in the Table of Contents.
- If an equation was contained in both ODCMs, but each had data specific to BV-1 or BV-2, then a (1) or (2) was added to the -
equation. For example, Equation 1.1-1 was previously included in the BV-1 ODCM and the BV-2 ODCM. These equations are nov numbered 1.1(1)-1 and 1.1(2)-1, denoting BV-1 and BV-2 respectively. A cross reference for ODCM equations is provided in the Table Of Contents.
- Revised Section 3.0 (Radiological Environmental Monitoring Program) to list the program requirements from the Radiological Assessment Branch Technical Position (Revision 1, 1979).
- Revised Section 4.0 (Information Related To 40 CFR 190) to provide clarified reporting requirements for the Special Report. The clarifications were taken from Generic Letter 89-01, Supplement No. 1 (NUREG-1301).
j
- Revised Appendix A to transfer the Batch Release dispersion parameters i 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 j 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).
O xviii ISSUE 3 e Revision 1
i-4 BV-1 cnd 2 ODCM b
I! 'This . Appendix also includes -selected Definitions and Tables as delineated inJ the ~ Technical Specifications. (Section 1) and-selected
/7 ' Applicability and Surveillance ' Requirement' statements as delineated in i
h:
'the Technical Specifications (Section -3/4 0). These vere added to
-Appendix-C for reference purposes, -even though they are currently described in the Technical Specification.
' Added' Appendix D:_ The bases for'0DCM Controls were transferred from the Bases.Section of'the Technical Specifications. to Appendix D of the ODCM per. Generic Letter 89-01.. o
- Added Appendix E: The ' Annual- Radioactive Effluent Release Report:and
'the-Annual Radiological Environmental Report reporting requirements are-
. listed in this appendix to the ODCM.
' There.are.three differences (i.e., non-editorial changes) in this ODCM revision when- compared to the previous BV-1 _and BV-2 Technicaln Specifications. These are- the only changes that are identified by revision bars. These differences are as follows:
First Difference (LLD Definition Clarification):
F There was a sentence removed in- the LLD Standard. Deviation
~ Definitions delineated in, Appendix C Tables 4.11-1 and 4.'1-2.1 This I
-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 X the samples (e.g.,-potassium in milk samples)." )
i
- (V) It should be noted that this' sentence was. removed by justification of NUREG-0472, Rev. 2.(i.e., this revision to the NUREG removed the sentence from Tables 4.11-1 and 4.11-2). It-should.be noted that at !
BV-1 and 2, there are no other radionuclides normally present in' j effluent _ samples. However, there_is applicability to environmental' j LLD calculations due to the existence of other radionuclides in environmental samples. This sentence, therefore, vill not be removed from Appendix C, Table 4.12-1. s l 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 i past effluent LLD calculations. This change maintains the level of l
- . radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a', and Appendix I to 10 CFR Part 50, and does not adversely-impact the accuracy or reliability of effluent, dose, or setpoint. calculations. l This' change brings ODCM Appendix C, Tables 4.11-1 and 4.11-2 in l generic agreement with NRC guidance (i.e., NUREG-0472) and industry standard.
~,
xix ISSUE 3
,A Revision 1
'Q
BV-1 cnd 2 ODCM
- Second Difference (Change From Semi-Annual Report To Annual Report:
The frequency of the RadioactiveThis Effluent Release Report was changed l I from Semi-Annual to Annual. change is justified by Federal Register, Rules And Regulations (Vol. 57, No. 169, Monday, August 31, 1992), where as; 10 CFR Part 50.36a(a)(2) states, in part:
"Each licensee shall submit a report to the Commission annually that specifies the quantity of each of the principal radionuclides released to unrestricted areas in liquid and in gaseous effluents i
during the previous 12 months of operation...the time between i
! submis= ion of the teports must be no longer than 12 months..."
This change maintains the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50, and does not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
- Third Difference (Implementation Of Nev 10 CFR 20):
The definition for MEMBER (S) 0F THE PUBLIC vas revised to agree with the definition in New 10 CFR 20.1003.
The definition for UNRESTRICTED AREA vas modified from the definition that was in the Technical Specifications prior to transferring to the ODCM. This modification was necessary to ensure that the ODCM dose model for gaseous releases is not affected. The modification involved adding the following sentence: "For gaseous release dose calculations, the UNRESTRICTED AREA should exclude any j )
public road, railway, or waterway adjacent to or crossing the site that is not occupied continuously by MEMBER (S) 0F THE PUBLIC".
The limits for liquid effluent concentration vere changed from 1 times Old 10 CFR 20 Appendix B (20.1 - 20.601), Table II, Col. 2 MPC's to 10 times Nev 10 CFR 20 Appendix B (20.1001 - 20.2401),
Table 2, Col. 2 EC's. This limit vill now be referred to as the ODCM Effluent Concentration Limit (OEC). 8 For gaseous effluents, no changes were made to implement the Nev 10 CFR 20. As justification. When the utility adopted the RETS (1/1/84), compliance to 10 CFR 20 shifted from the MPC concept to the Unrestricted Area Dose Rate concept. The Dose Rate concept is the preferred method of controlling gaseous effluent relerse rate, and vill continue to be used in-lieu of the MPC or EC concept.
Changing to the OEC limit for liquid effluents accommodates needed operational flexibility to facilitate implementation of the Nev 10
- j. CFR 20 requirements.
For information, the general intent of the New Part 20 is that radiation doses to members of the public not exceed 100 mrems per year, which is more restrictive than the 500 mrems per year limit in the Old Part 20, and that fuel cycle licensees also comply with 40 CFR 190. The New Part 20 does not include a requirement on limiting radioactivity concentrations in effluents, which is less restrictive l I
than the Old Part 20.
xx ISSbE 3 Revision 1
BV-1 and 2 ODCM
~The. basic requirements for RETS (i.e.; nov the ODCH Appendix C
. Controls) are stated in 10 CFR 50.36a. These requirements-indicate-(] that compliance with the RETS will keep average annual releases of U radioactive material in effluents to small perc~entages of the limits specified in.the Old 10. CFR .20.106 (New 10 CFR 20.1302). These requirements also indicate l that operational flexibility is allowed j' t (with- considerations for public' health and safety) which may temporarily result in releases higher than such,small percentages, but still within the MPC limits specified in the Old 10 CFR 20.106.
The MPC's relate-to an annual dose of 500 mrem. Also', 10 CFR 50.36a indicates that when using operational -flexibility, best efforts shall be exerted to keep levels of radioactive materials in effluents to ALARA as set forth in.10 CFR'50 Appendix I.
As stated in the Introduction to Appendix B of the Nev 10 CFR 20, the liquid EC's are based on an annual dose of 50 mrem.- Since a release concentration corresponding to a limiting dose rate of 500 mrem / year has been acceptable as a RETS limit for liquid effluents, it should not be necessary to reduce this limit by a-factor of-ten.
BV-1 and BV-2 has demonstrated that the use of the MPC's associated with the Old 10 CFR 20.106 has resulted' in calculated maximum individual doses to a member of the public that are small percentag% of the limits of 10 CFR 50 Appendix I. Therefore, the use of the OEC's, which correspond to. an annual dose of 500 mrem (i.e.; 10 times the Nev 10 CFR 20 EC's) should not have a negative impact on the ability to continue to operate within the limits of 10 CFR.50 Appendix I, and 40 CFR 190.
.p)-
- ('
operational flexibility is also necessary n. establishing a basis for effluent monitor setpoint calculations. .As previously discussed, the EC's stated in the New 10 CFR 20 relate to a dose of 50 mrem-in a year. This is too restrictive to base effluent monitor setpoint calculations. For many liquid effluent release situations, the monitor background is high, which could result in a monitor setpoint that is approximately equal to the monitor background.
In summary, to accommodate operational flexibility needed for effluent releases, the limits associated with the liquid release concentration (i.e.; the OEC) are based' on 10 times the EC's stated in the New 10 CFR 20. The multiplier of 10 is used because the annual dose of 500 mrem (Old 10 CFR 20 MPC bases) is a factor of 10 higher than the annual dose of 50 mrem (New 10 CFR 20 EC bases).
Compliance with the 100 mrem dose limit of the Nev 10 CFR 20.1302 vill be demonstrated by operating within the dose limits of 10 CFR 50 Appendix I, and' 40 CFR 190 (which are also ODCM Controls for liquid and gaseous' effluents). Implementation of the New 10 CFR 20 for liquid effluents maintai'ns the level 'of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50, and does not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
.m-xxi ISSUE 3 Revision 1
- BV-1 and 2 ODCH
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. r.ather, the intent is to provide programmatic controls for RETS (as delineated in-Technica gg Specification 6.8.6) and allow for relocation of the procedural details of the RETS to the ODCH.
(8) BV-1 AND 2 ODCM,. Issue 3, Revision 1 (Effective October, 1995)
A description of the changes that vere implemented with this revision are as follows:
- Index: Editorial changes were made for clarity. (See justification 1)
- Section 1.0: Revised Nb-95 and Nb-97 dose factors in Table 1.3-1 due to changing the niobium bioaccumulation factor. (see justification 2)
- Appendix A: A change was made to Table 1.1 so that the letter A vould proceed the table number. (See justification 1)
- Appendix B: A descriptive paragraph was added at the front of this Appendix. Also, changes were made to the tables so that the letter B vould proceed the table numbers. (See justification 1)
- Appendix C: Descriptive paragraphs were added at the front of the Appendix (See justification 1). Removed the process flow rate operability and surveillance requirements for gaseous effluent radiation monitors 2RM0-R0301, 2RM0-R0303 and 2HVL-R0112 from Tables 3.3-13 and 4.3-13 (See justification 3). Added alternate system effluent flow rate measuring devices for the three gaseous effluent pathways to Tables 3.3-13 and 4.3-13 (See justification 4). Revised Surveillance Requirements 4.11.1.1.3 and 4.11.1.1.4 and notes e and g of Table 4.11-1 to clarify Turbine Building sump sampling requirements (See justification 5). ,o
- Appendix D: Descriptive paragraphs were added at the front of the Appendix. (See justification 1)
- Appendix E: Desriptive paragraphs were added at the front of the Appendix. (See justification 1)
- Appendix F: This is a new Appendix to the ODCM. It contains plant procedure references for Radiological Effluent Technical Specification (RETS) that vere transferred from the Technical. Specification Procedure Matrix. (See justification 1) xxii ISSUE 3 Revision 1
BV-1 cnd 2 ODCM The justification used for change (8) to the ODCM are as follows:
i
)
- 1. These changes are considered editorial in nature. Therefore, these
/
editorial changes vill maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR 50. Also the editorial changes vill not adversely impact the accuracy or reliability of effluent dose or setpoint calculation.
- 2. This change resulted from revising the bioaccumulation factor (BF) for niobium from the value posted .in Table A-1 of Regulatory Guide 1.109, Revision 1, 1977 (30,000 pCi/kg per pCi/1). Since this change in niobium BF (as documented and justified in Appendix A to ,
Calculation Package No. ERS-ATL-83-027) merely removes the conservatism associated with organism uptake, then the change vill maintain the level of radioactive effluent control required by 10 ,
CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR 50. Also, removing the conservatism vill not adversely impact the accuracy or reliab'ility of effluent dose or setpoint i calculation. i
- 3. This change removes the process flov -rate operability and l surveillance requirements for BV-2 Gaseous Effluent Radiation !
Monitors 2RM0-R0301, 2RM0-R0303 and 2HVL-R0112 from Appendix C l Tables 3.3-13 and 4.3-13. These items were removed from the ODCM by I justification provided in Calculation Package No. ERS-ATL-90-021. j
, ~ It should be noted that a safety analysis and a no significant hazards evaluation vere prepared and approved on this change prior l
.\ '
to submitting it to the NRC via TSCR No. 2A-61 in 1992 However, the TSCR vas withdrawn in 1993 in an effort to alleviate any further delays associated with approval of TSCR No. 1A-175/2A-37 (Generic j Letter 89-01 implementation). ;
Removal of these items from the ODCM vill maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a and Appendix I to 10 CFR 50. Also removal of these items will not adversely impact the accuracy or reliability of effluent dose or setpoint calculation. The following i.s 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 flow rates observed during normal plant operation.
BVPS-2 UFSAR Section 11.3.3 indicates that the source term for these three pathways are not significant.' These pathways are not included in UFSAR Tables 11.3-1 through 11.3-4 that list the expected and design releases for each potentially radioactive pathway.
I f ,
) xxiii ISSUE 3 Revision 1
BV-1 and 2 ODCM
- The DLC commitment to Regulatory Guide 1.97, Rev. 2 (Section 1.8-1 of the BVPS-2 UFSAR) is not affected. This RG applies to instrumentation used curing and after postulated accident conditions. These three process flow rate instruments vere not I used in any accidnet analysis, nor are they used to assess plant conditions during and following an accidnet.
- The DLC commitment to Regulatory Guide 1.21, Rev. 1 (Section 1.8-1 of the BVPS-2'UFSAR) is not affected. RG 1.21, Section C.2 (Location of Monitoring) states in part: "All maj or and potentially significant paths for release of radioactive material during normal reactor operation, including anticipated operational occurrences, should be monitored. Measurements of effluent volume, rates of release, and specific radionuclides should be made, insofar as practical .. " As previously stated, the three process flow rate instruments are located on effluent pathways that do not have a significant source term.
BVPS-2 UFSAR Sections 9.4.13 and 9.4.16 indicate that the building ventilation system for these three pathways are non-safety related and are not required to perform any safety-related function.
There is no effect to the Noble Gas Monitors located on these three pathvan. The Noble Gas Monitors are still capable of performing ti . ir intended functions as described in BVPS-2 UFSAR Section 11.5.2.4.
- 4. This change adds alternate system effluent flovrate measuring ( )
devices for the three BV-1 Gaseous Ef fluent Pathways to Appendix C Tables 3.3-13 and 4.3-13. A 10 CFR 50.59 safety evaluation has concluded that no unreviewed safety question is involved by adding the alternate measuring devices to Appendix C Tables 3.3-13 and 4.3-
- 13. This conclusion is based on the following:
- There is no increase in the probability or consequences of accidents or malfunctions of equipment Soortant to safety.
- There is no creation of a possiblity for an accident or malfunction of a different type than any evaluated previously.
- There is no reduction in the margin of safety Also, since this change merely adds alternate measuring devices that meet the same surveillance requirements of the primary channel, then
'the change vill maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR 50. Also, addition of the alternate flow rate measuring devices vill not adversely impact the accuracy or reliability of effluent dose or setpoint calculations.
xxiv ISSUE 3 Revision 1
BV-1 cnd 2 ODCM
requirements and clarifies effluent related actions associated with detection of radioactivity in the secondary system. These
( )
v' clarifications are documented and justified in Calculation Package No. ERS-ATL-95-006. Also, since these clarifications were shown to meet the intent of NUREG-1301 (superceeding NUREG-0472) and the BVPS-1 and 2 UFSAR's, then the clarification vill maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a and Appendix I to 10 CFR 50. Also, the clarifications vill not adversely impact the accuracy or reliability of effluent dose or setpoint calculation.
Also, a 10 CFR 50.59 safety evaluation has concluded that no unreviewed safety question is involved by clarifying these actions.
This conclusion is based on the following:
- There is no increase in the probability or consequences of accidents or malfunctjons of equipment important-to safety.
- There is ru creation of a possiblity for an accident or malfunction of a different type than any evaluated previously.
- There is no reduction in the margin of safety.
(9) BV-1 and 2 ODCM, Issue 3, Revision 2 (Effective May 1997)
^
A description of the changes that wereimplementedwiththi[revisionare
() as follows:
- Index: Editorial changes were made for clarity. (See Justi (cfon1)
- Section 1.0: Clarifying statements were added to Tables 1.2-la and 1.2-Ib to show that the recirculation times listed are based on historical recirculation rates. Figure 1.4-3 was added to shov BV-1 and 2 Liquid Effluent Release Points. (See Justification 1)
- Section 3.0: . Removed the option to perform broad leaf vegetation sampling at the site boundary in a sector with the highest D/0 (See ,
Justification 2)
- Appendix C: Added plant specific Marx Numbers to Tables 3.3-12, 4.3-12, 3.3-13 and 4.3-13 (See Justification 1). Corrected typographical errors on Surveillance Requirement 4.11.4.1.1 (See Justification 1). Added clarifying statements from NUREG-1301 and the Radiological Assessment Branch Technical Position to Tables 3.12-2 and 4.12-1 (See Justification 1). Removed the option to perform broad leaf vegetation sampling at the site boundary in a sector with the highest D/0 (See Justification 2).
c, i xxv ISSUE 3 D: Revision 2 A
~
BV-1 Cnd 2 ODCH
- Appendix E: Corrected typographical error on Table 6.9-1. (See Justification 1)
- Appendix F: Added procedure detail to Tables 11, 12 and 13. (See Justification 1)
The justification used for Change (9) to the ODCH are as follows:
- 1. These changes are considered editorial in nature. The changes either correct typographical errors or add editorial details from previously approved station documents. Therefore, these changes vill maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a and Appendix I to 10 CFR 50. Also, the editorial changes will not adversely impact the accuracy or reliability of effluent dose or setpoint calculations.
- 2. This change removes the option to perform broad leaf vegetation sampling at the site boundary (in a sector with the highest D/0) in lieu of the garden census. Per NUREG-1301 and the Radiological Branch Technical Postion, this option does not apply to plants with elevated releases. Since BV-1 and_.2 have elevated releases, the option should not be exercised. A review of past garden census shoved that the option was never exercised at BV-1 and 2.
Since this change removes an option that should not be exercised, then the change vill maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a and Appendix I to 10 CFR 50. Also, removal of the option vill not adversely impact the accruacy or reliability of effluent dose or setpoint calculations.
(10) BV-1 and 2 ODCM. Issue 3. Revision 3 Effective June 1997)
A description of the change that was implemented with the revision is as follows:
- Section 2.0: A release point for the BV-2 Turbine Building Vent was added (for editorial purposes) to Figure 2.4-2.
l The justification used for Change (10) to the ODCM k as follows:
I
!
- This change is considered editorial in nature. The change adds an equivalent item that was previously located on BV-2 Technical Specification Figure 5.1-2. Since BV-2 Technical Specification Amendment 83 removed this figure, then the gaseous release point for the BV-2 Turbine Building Vent needed transferred to the ODCM.
Therefore, since this change is considered editorial, the change will maintain the level l of radioactive effluent control required by 10 CFR 20.1302,40 CFR Part 190,10 CFR t '
50.36a and Appendix 1 to 10 CFR .50. Also, the editorial change will not adversely
{ impact the accuracy or reliability of effluent dose or setpoint calculation.
l xxvi ISSUE 3 Revision 3 l
. r, ,
+.BV I cad'2'0DCM
?N
(( ' j.li0. LIQUID EFFLUENTS.'
a
> ' monitor setpoints for analysis prior.'.to:: release 1 permit use:of-'the total' '
, dilution flow'available'at the' site.
" 'DNferences Eexist' betweenL isetpointi presentations; fof: the -radiation
.monitoringJsystems of BV-1 andE BV-2.!. -There:isa; difference. ins.etpoint/
'
- terminology. Where'BV-1 uses HIGH-fand HIGH-HIGH,1 the BV-2' equivalents'areu W - s ALERT and HIGH.- .Also,t'there gis) theLdifference that.BV-2 setpoints-are
- presented'in uCi/ml rather than epm as' in BV-1 ..This difference ~is'due>tc6 i
JBV-2 software which' applies a 'conversioni-factor:rto the rav. data -(cpm).-
Note'that thel uCi/mla presentation lis ~ technically (correctL only;for'.;the
. specific isotopic mix used in."the determination of;the conversion factorst-
Therefore..BV-2 setpoints determined.on analysis prior'to. release will be
. j correct for properly controlling dose rate, but the indicated uCi/ml value may; differ from the. actual value. _
s x
l I I
(
r O
e 1-1 ISSUE 3
f W', , ,
%a
- BV-1 ands 2'ODCM +
- i' * ,
'w
?1.17/Alara Setpoints'_.,
w ...m ii :
1.1.1p BV-1' Monitor Alarm Setpoint Determination
'Ky
<i This procedure Edetermines the monitor HIGH-HIGH1 Alarm Setpoint'that W dp < indicates if'the concentration of radionuclides in the liquid effluent
_i ,Lreleased from the: site'to ' unrestricted areas .-exceeds.10 times the EC's,
,% :specified(in'10 CFR 20h Appendix 1 B (20.1001-20.2401),LTable 2,LColumn;21
<for radionuclidescotherc than dissolved or4-entrained: noble; gases or:
, ' exceeds alconcentration of 2E-4-~uCi/al for' dissolved or' entrained; noble /
gases,(see Reference 1.1;5).
i The methodology described.in Section 1.1.1.2 is antalternat'ive method to'.
beiused to determine the'(RM-LV-104-or RM-LV-116) monitor HIGH-HIGH Alarm n% :Setpoint:(HHSP); lThe methodology in-~Section'1.1'.1.2:may be used for any.
batch release and shall.be'used when the res,>ective total gamma activity :
concentration lof the liquid effluent l prior to' dilution exceeds'4.26E-3.:
.y uCi/al'aad 1;49E-2 uCi/ml. This.. concentration'.Is equivalent 1to the' P . respective'HHSP's derived in Section 1.1.1.1.1and allows'for respect $ve:
tritium concentrations up'to'4.33E+0 uCi/ml.and 1.52E+1 uCi/ml.: 3 y (1.1.1.1 BV-1 Setpoint Determination Based On A-Conservative Mix-1
~
W The Alarm Setpoints for the liquid monitors should be set at'the' values, t
p : listed.as follows: 1 BV-l'LIOUID MONITOR SETPOINTS cpm Above Background
'1 Monitorr CR -HHSP 'HSP M' ' Liquid. Waste Effluent RM-LV-104 .4.84E+5- 4.84E+5' -3.39E+5 w, Monitor >
~gf '* Laundry And Contami- RM-LV-116 1.69E+6- 1.69E+6. 1.19E+6
~nated' Shower. Drains-t Monitor L* Component Cooling /- RM-RV-100 2.57E44 L2.57E+4 1.80E+4.
7 '
. Recirculation Spray.Ex- ~
- River Vater Monitor- ,
- Aux. Feed Pump Bay' RM-DA-100 1.22E+4- '1.22E+4 8.55E+3'-
F' '
-Drain Monitor
, X 1The setpoints for RM-LV-104 and- RW-LV-116 are bas'ed'on t'he-following conditions,:however,.the setpoint bases for RM-RV-100 and RM-DA-100 can-
.be found'in Reference ~1.1.5:
~
"gA
- Source terms given in _ Table 1.1-la. These source terms have~been-
- generated from the. computer code. GALE, Revision 0.(NUREG-0017). The Jinputs to. GALE are given in Appendix B.
- ! Dilution vater flow rate of 22,800 gpa s (15,000 gpm BV-1 + 7,800 gpa
'4 JBV-2).
Discharge flow rate prior to dilution. of 35-gpm for the Liquid vaste Effluent Monitor (RM-LV-104).
$
- Discharge flow rate prior to dilution of 15 gpm for the Laundry and ,
7 Contaminated Shower Drains Monitor (RM-LV-116).
- 1-21 ISSUE 3 1
, , , 4~ _
)
s q
- = ;
RV-1 End 2 ODCH-The above setpoints for (PJf-LV-104 and RH-LV-116) can be varied based on actual operating conditions resulting in changes in the discharge and dilution flow rates as follows:
HHSP = 743 F
[1.1(1)-1]
f !
where:
HHSP = Honitor HIGH-HIGH Alarm Setpoint above background (nepm).
743 = Host restrictive proportionality constant based on nominal flow conditions:
743 = 4.84E+5 nepm x 35 gpm + 22,800 gpm (RM-LV-104) 1112 - 1.69E+6 nepm x 15 gpm + 22,800 gpm (RM-LV-116)
F = Dilution water flow rate -(gpm), BV-1 plus BV-2 Cooling Tower Blowdown Rate (not including release through the Emergency Outfall Structure).
f = Discharge flow rate prior to dilution (gpm).
1.1.1.1.1 BV-1 Hix Radionuclides The " mix" (radionuclides and composition) of the liquid effluent was determined as follows:
- a. The liquid source terms that are representative of the " mix" of the liquid effluent were determined. Liquid source terms are the radioactivity levels of the radionuclides in the effluent from Table 1.1-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:
S g,EA b .
[1.1(1)-2]
I i
vhere:
A f = Annual release of radionuclide "i" (Ci/yr) in the liquid effluent from Table 1.1-la.
1.1.1.1.2 BV-1 Haximum 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(1)-3]
S i OEC g 1-3 ISSUE 3
l i;
'BV-1'and 2 ODCM
' V where:- <
.. . s L 'F ,= Dilution water flow rate (gpa), BV-1-plus BV-2 Cooling- m Tower Blowdown Rate (not. including release ~through the Emergency Outfall Structure).
~
- = 22,800 gpa = (15,000 gpm BV-1 +-7,800 gpm BV-2) f =. Maximum' acceptable discharge flow rate prior to dilution (gpm). .
= 35. gpa - for Liquid Vaste Effit:ent Monitor- (RM-LV-104). .
= 15 gpa for Laundry and Contaminated' Shower Drains Monitor n (RM-LV-116). '
OECi - The 0DCM liquid effluent concentration limit for radionuclide."i" (uci/al) from Table 1.1-la. The OEC is set at.10 times the new 10 CFR'20, Appendix B (20.1001-20.2401) Table 2, Col. 2 EC values.
.S.g' .= The fraction of total radioactivity attributed to radionuclide "i", from Equation [1.1(1)-2].
1.1.1.1.3 BV-1 Maximum Acceptable Concentration (Individual Radionuclide) f The maximum acceptable radioactivity concentration (uCi/ml) of
-radionuclide "i" in'the liquid ~ effluent prior t'o dilution (C ) was-g determined by:
Cg=SgC t II
- 1II)~'I' 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. = I Cg Ej [1'.1(1)-5 ]
where:
E g = Detection efficiency of the monitor for radionuclide "i" (cpa/uci/ml) from Table 1.1-la. If not listed there, from
/ >
Reference:
1.1.4.
1.1.1.1.5 BV-1 Monitor HHSP L
< The monitor HIGH-HIGH Alarm Setpoint above background (nepm) should Since only one tank can be released at a be set at the C.R. value.
time, adjustment of this value is not necessary to coopensate for y
. release from more than one source.
1 ,
1-4 ISSUE 3
. I
BV-1 and 2 ODCM 1.1.1.2 BV-1 Setpoint Determination Based On Analysis Prior To Release The following method applies to liquid releases when determining the setpoint for the maximum acceptable discharge flow rate prior to dilution and the associated HIGH-HIGH Alarm Setpoint based on this flow rate for the Liquid Vaste Effluent Monitor (RM-LV-104) and the Laundry and Contaminated Shower Drains Monitor (RM-LV-116) during all operational conditions.
The monitor alarm setpoint is set slightly above (a factor of 1.25) the count rate that results from the concentration of gamma emitting radionuclides in order to avoid spurious alarms. To compensate for this increase in the monitor alarm setpoint, the allovable discharge 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 Flov Rate The maximum acceptable discharge flow rate (f) prior to dilution (gpm) is determined by:
g, F [1.1(1)-6]
i a 1.25 I i OEC g where:
F = Dilution water flow rate, BV-1 plus BV-2 Cooling Tower Blowdown (gpm).
The dilution water flow rate may include the combined cooling tower blowdown flow from both units exiting the discharge structure (but excluding emergency outfall structure flow) vhen simultaneous liquid discharges are administratively prohibited.
Cy = 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.
OECg - The ODCM liquid effluent concentration limit for radionuclide "i" (uCi/ml) from Table 1.1-la. The OEC is set at 10 times the nev 10 CFR 20, Appendix B (20.1001-20.2401) Table 2, Col. 2 EC values.
) 1-5 ISSUE 3
BV-1 and 2 ODCM 1.1.1.2.2 BV-1 Monitor Count Rate
- p. n
( ) The calculated monitor count rate (nepm) above background attributed to the radionuclides (C.R.) is determined by:
C.R. - 1.25 I Cy Eg [1.1(1)-7]
i vhere:
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 facter to prevent spurious alarms caused by deviations in the mixture of radionuclides which affect the monitor response. Mrs 1.1.1.2.3 BV-1 Monitor HHSP The liquid effluent monitor HIGH-HIGH Alarm Setpoint above background (nepm) should be set at the C.R. value adjusted by any excess dilution factor provided as defined in the following equation:
HHSP = C.R. f, [1.1(1)-8]
I where:
e]
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 l discharge. The reduced value of f may be due to pump 3,
, limitations or administrative selection.
!~
.i 6
~
1-6 ISSUE 3 l
BV-1 and 2 ODCM 1.1.2' BV-2 Monitor Alarm Setpoint Determination This procedure determines the monitor HIGH Alarm Setpoint that indicates if the concentration of radionuclides in the liquid effluent released from the site to unrestricted areas exceeds 10 times the EC's specified in 10 CFR 20, Appendix B (20.1001-20.2401), Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases or exceeds a concentration of 2E-4 uCi/ml for dissolvcd or entrained noble gases (see Reference 1.2.6).
The methodology described in Section 1.1.2.2 is an alternative method to be used to determine the (2SGC-RQ100) monitor HIGH Alarm Setpoint (HSP).
The methodology in Section 1.1.2.2 may be used for any batch release and shall be used when the total gamma radioactivity concentration of the liquid effluent prior to dilution exceeds 9.55E-4 uCi/ml. This concentration is equivalent to a monitor response and HIGH Alarm Setpoint derived in Section 1.1.2.1 and allows for a tritium concentration of up to 2.19E+0 uCi/ml. The setpoint was obtained by use of a conversion factor o.f 5.09E-9 uCi/ml/ cpm determined for the nuclide mix (see Reference 1.2.5).
~
1.1.2.1 BV-2 Setpoint Determination Based On A Conservative Mix The HIGH Alarm Setpoint for the liquid monitors shoult' be set at the values listed as follows:
BV-2 LIQUID MONITOR SETP0 lfts uCi/ml Above Background Monitor DV HSP ASP
- Liquid Vaste Effluent. 2SGC-RQ100 9.84E-4 9.84E-4 6.89E-4 Monitor
- Service Water Monitor 2SVS-R0101 4.28E-5 4.28E-5 2.99E-5
- Service Vater Monitor 2SVS-R0102 4.28E-5 4.28E-5 2.99E-5 The setpoint for 2SGC-R0100 is based on the following conditions, however, the setpoint bases for 2SVS-R0101 and 2SVS-R0102 can be found in Reference 1.2.6:
- Source terms given in Table 1.1-1b. These source terms have been generated by using models and input similar to NUREG-0017. The inputs are given in Appendix B.
- Dilution water flow rate of 22,800 gpm - (15,000 gpm BV-1 + 7,800 gpm BV-2).
- Discharge flow rate prior to dilution of 80 gpm for the Liquid Vaste Effluent Monitor (2SGC-R0100).
- A software conversion factor of 5.09E-9 uCi/ml/ cpm associated with Liquid Vaste Effluent Monitor (2SGC-R0100).
The above setpoint for (2SGC-R0100) can be varied based on actual operating conditions resulting in the discharge and dilution flow rates as follows:
1-7 ISSUE 3 i
BV-1 and 2 ODCM L
[1.1(2)-1] ^
g3p[3.50E-6F g i k' where:-
HSP _ = Monitor HIGH Alarm Setpoint'(uCi/ml) above background.
f., 3.50E-6-'= Proportioulity. constant based on nominal flov-
> conditions:
.3.50E-6 = 9.9BA-4 net uci/ml x 80 gpm + 22,800 gpm P = Dilution water flow rate, BV-1 plus BV-2 Cooling Tower' , 1 Blovdown Rate (gpm).
f --Discharge flow rate prio to dilution (gpm).
1.1.2.1.1 'BV-2 Mix Radionuclides \
The " mix" (radionuclides and composition) of the liquid effluent was determined as follows:
- a. The liquid source terms that are representative of the " mix" of 2
the liquid effluent were determined. Liquid source , terms are' the radioactivity levels of the radionuclides in the< effluent from Table 1.1-1b.
- b. The fraction.of the total radioactivity in the liquid effluent comprised' by radionuclide "i" (Sg ). for each . individual H p-:). ,
radionuclide in the liquid effluent was determined as follows:
A' [1.1(2)-2]
S i l 1,EA '
i g
where:
1
~d A g = Annual release of radionuclide "i" (Ci/yr) in the liquid effluent from Table 1.1-lb.: ,
h 1.1.2.1.2 BV-2 Maximum Acceptable Concentration (All Radionuclides) f; The maximum acceptable total radioactivity concentration baci/ml) of all radionuclides in the liquid effluent prior: to dilutica (C ) was t determined by:
C F [1.1(2)-3]
t- S i
f-I i OEC g
.vhere:
F = Dilution vater flow rate (gpm), BV-1 plus BV-2 Cooling Tower Blowdown Rate (not including release out through the y f~~)Y
( Emergency Outfall Structure). ]
j 1-8 ISSUE 3
.b
BV-1 and 2 ODCM
= 22,800 gpm - (15,000 gpm BV-1 + 7,800 gpm BV-2).
f - Maximum acceptable discharge flow rate prior to dilution (gpm).
- 80 gpm for Liquid Waste Process Effluent Monitor (2SGC-R0100).
OEC g = The ODCM liquid effluent concentration limit for radionuclide "i".(uCi/ml) from Table 1.1-lb. The OEC is set at 10 times the nev 10 CFR 20, Appendix B (20.1001-20.2401) Table 2, Col. 2 EC values.
Sg - The fraction of total radioactivity attributed to radionuclide "i", from Equation [1.1(2)-2].
1.1.2.1.3 BV-2 Maximum Acceptable Concentration (Individual Radionuclide)
The maximum acceptable radioactivity concentration (uCi/ml) of radionuclide "i" in the liquid effluent prior to dilution (C g) vas determined by:
Cg-Sg C [1.1(2)4]
t 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:
[1.1(2)-5]
D.V. - 5.09E-9 I C yE g i
where:
5.09E Conversion factor (uci/ml/ cpm), an average determined for the source term mix.
Eg - Deter. tion efficiency of the monitor for radionuclide "i" (cpm /uci/ml) from Table 1.1-1b.
1.1.2.1.5 BV-2 Monitor HSP The monitor HIGH Alarm Setpoint above background (uCi/ml) should be set at the D.V. value.
l L e 1-9 ISSUE 3
BV-1 cnd 2 ODCH 1.1.2.2 BV-2 Setpoint Determination Based On Analysis Prior To Release m
A I
) The following method applies to liquid releases when determining the v 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-R0100) 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 will be proportionally adjusted based upon the excess dilution factor provided. 6/7 1.1.2.2.1 BV-2 Maximum Acceptable Discharge Flow Rate The maximum acceptable discharge flow rate (f) prior to dilution (gpm) is determined by:
f" F [1.1(2)-6]
c 1
7s 1.25 I
( i OEC g m
) .
where:
F = Dilution water flow rate, EV-1 plus BV-2 Cooling Tover Blovdown (gpm).
The dilution water flow rate may include the combined cooling tover blovdown flow from both units exiting the discharge structure (but excluding emergency outfall structure flov) when simultaneous liquid discharges from both plants are administratively prohibited.
Cg = Radioactivity concentration of radionuclide "i" in the liquid effluent prior to dilution (uci/al) 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.
OEC g = The ODCH liquid effluent concentration limit for
( radionuclide "i" (uCi/ml) from Table 1.1-lb. The OEC is set at 10 times the new 10 CFR 20, Appendix B (20.1001-20.2401) Table 2, Col. 2 EC values. '[
LJ 1-10 ISSUE 3
BV-1 and 2 ODCM 1.1.2.2.2 BV-2 Monitor Display Value The calculated monitor Display Value- (uci/ml) above background attributed to the radionuclides (D.V.) is determined by:
D.V. - (1.25) (5.09E-9) I Cy Eg [1.1(2)-7]
i where:
Eg - The detection efficiency of the monitor for radionuclide "i" (epm /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 (uci/ml/ cpm), an average determined for the source term mix.
1.1.2.2.3 BV-2 Monitor HSP The liquid effluent monitor HIGH Alarm Setpoint above background (uCi/ml) should be set at the D.V. value adjusted by any excess dilution factor vided as defined in the following equation:
HSP = D.V. f, [1.1(2)-8]
vhere:
S BSP = Monito HIGH Alarm Setpoint above background.
D.V. - Calculated monitor concentration reading (uCi/ml) from equation [1.1(2)-7].
f - Maximum acceptable discharge flow rate prior to dilution determined by equation [1.1(2)-6).
f' = Actual maximum discharge flow rate,to be maintained for the discharge. The reduced value of i may be due to pump limitations or administrative selection.
1 I
~
l O
i 1-11 ISSUE 3 1
i
/
BV-1 and 2 ODCM TABLE 1.1-1c BV-1 LIQUID SOURCE TERM y .
(_-. Eg h A
l DETECTION OEC ANNUAL RELEASE i EFFICIENCY
~NUCLIDE (Ci)** (uCi/ml)*** (cpm /uC1/ml)****
Cr-51 9.00E-5 SE-3 1.18E+7
Fe-55 8.00E-5 1E *****
Fe-59 5.00E-5 ~ 1E-4' 9.17E+7-Co-58 7.70E-4 2E-4 1.16E+8 Co-60 1.00E 4 3E-5 l'.73E+8
'Np-239 5.00E-5 2E-4 8.49E+7 Br-83 6.00E-5 9E-3 1.36E+6 Rb-86 1.00E-5. 7E-5 3****
Sr-89 2.00E-5 8E-5 **r**
Sr-91 1.00E-5 2E-4' 6.9FE+7 Mo-99 3. 90E--s 2E-4 2.E4E+7-Tc-99m 5.37E-3 1E-2 8.16E+7 Te-127m 1.00E-5 9E-5 4.09E+4 Te-127l 3.00E-5 1E-3 1.38E+6 Te-129s: 7 00E-5 7E-5 4.02E+6 ,
-Te-129' 5.00E-5 4E-3 1.12E+7 r j I-130 2.50E-4 2E-4 3.08E+8 Te-131m 9.00E-5 8E-5 1.82E+8
[ -Te-131 2.00E-5 8E-4 1.20E+8 L 'b I-131 6.03E-2 1E-5 1.11E+8 )
Te-132 1.15E-3 9E-5 1.17E+8 I-132 5.38E-3 1E-3 2.66E+8 I-133' 5.77E-2 7E-5 9.90E+7 I-134- 1.00E-5 4E-3 2.70E+8 Cs-134:. 3.80E-3 9E-6 1.99E+8 '
I-135 1.34E-2 ~
3E-4 1.19E+8
'Cs-136 1.90E-3 '6E-5 '
2.80E+8 Cs-137 2.70E-3 1E-5 8.01E+7-Ba-140 1.00E-5 8E-5 4.37E+7 La-140 1.00E-5 9E-5 2.00E+8
.B-3 1.60E+2 1E-2 *****
All Others* ~4.00E-5 IE-7 *****-
I TOTAL
- 1.57E-1 I
. *Excluding Tritium and Entrained Noble Gases
- Source Term for (RM-LV-104 and RM-LV-116) from Reference (1.1.2) l
- 0DCM Effluent Concentration Limit = 10! times the EC values of Reference ;
j .(1.1.3)
G ' **** Detection Efficiency for (RM-LV-104 and RM-LV-116) from Reference (1.1.4) y' C
/
.***** Insignificant l
1-12 ISSUE 3 L
BV-1 cnd 2 ODCH TABLE 1.1-1b BV-2 LIQUID SOURCE TERM E
A DETECTION i
OEC EFFICIENCY ANNUAL RELEASE i NUCLIDE (Ci)*** (uCi/ml)** (cpm /uCi/ml)****
Cr-51 1.00E-4 SE-3 2.01E+7 Mn-54 2.50E-5 3E-4 1.27E+8 Fe-55 1.30E-4 1E-3 *****
Fe-59 6.50E-5 1E-4 1.26E+8 Co-58 1.10E-3 2E-4 1.82E+8 Co-60 1.60E-4 3E-5 2.38E+8 Np-239 3.20E-5 2E-4 1.65E+8 Br-83 2.90E-5 9E-3 2.42E+6 Br-84 5.90E-9 4E-3 1.38E+8 Rb-86 3.70E-5 7E-5 1.04E+7 Sr-89 2.20E-5 BE-5 1.83E+4 St-90 8.50E-7 SE-6 *****
Sr-91 5.30E-6 2E-4 1.-04E+8 Mo-99 2.30E-3 2E-4 4.473+7 Tc-99m 2.10E-3 1E-2 1.403+8 Te-125m 1.90E-6 2E-4 3.94E+5 Te-127m 2.10E-5 9E-5 1.26E+5 Te-127 2.50E-5 1E-3 2.43E+6 Te-129m 8.20E-5 7E-5 6.53E+6 Te-129 5.30E-5 4E-3 1.96E+7 I-130 2.30E-4 2E-4 5.18E+8 Te-131m 5.20E-5 8E-5 2.85E+8 Te-131 9.40E-6 8E-4 1.88E+8 I-131 1.00E-1 IE-5 1.96E+8 Te-132 7.80E-4 9E-5 1.76E+8 I-132 2.30E-3 1E-3 4.22E+8 I-133 6.50E-2 7E-5 1.73E+8 I-134 4.60E-6 4E-3 4.06E+8 Cs-134 3.00E-2 9E-6 3.25E+8 I-135 9.20E-3 3E-4 1.71E+8 Cs-136 3.90E-3 6E-5 4.28E+8 Cs-137 2.20E-2 1E-5 1.28E+8 Ba-140 9.30E-6 8E-5 7.50E+7 La-140 8.40E-6 9E-5 3.0BE+8
- Excluding Tritium and Entrained Noble Gses
- 0DCM Effluent' Concentration Limit = 10 times the EC values of Reference (1.2.1)
- Source Term for (2SGC-R0100) from Reference (1.2.3) l
- Detection Efficiency for (2SGC-R0100) from Referenc'es (1.2.2) l and (1.2.4) l
- Insignificant 1-13 ISSUE 3 l I
BV-l'and 2 ODCM
- n . TABLE 1.1-lb (continued).
.1 BV-2. LIQUID SOURCE TERM
(,,/ -
E )(
i DETECTION OEC
' ANNUAL RELEASE i EFFICIENCY.
NUCLIDE (Ci)*** (uCi/ml)** .(cpm /uci/ml)****
Y-91m 3.60E-6 2E-2 1.59E+8 s -Y-91 4.40E-6 8E 3.55E+5
~Y-93 3.00E '2E-4 2.03E+7 Zr-95 4.00E-6 2E-4. 1.35E+8 Nb-95 4.00E-6 3E-4 1.33E+8 0/b Ru-103 '2.70E-6 3E-4 1.71E+8
- Ru-106 8.20E-7 3E-5 *****
Rh-103m ~ 2.70E-6 6E-2 *****
Rh-106- 8.20E-7 -- 5.65E+7 Ce-141 4.00E-6 3E-4 7.75E+7 Ce-143 8.60E-7 2E-4 l'.20E+8 Ce-144- 2.60E-6 .3E-5. 1.87E+7 Pr-143 2.30E-6 2E-4 1.63E+0 Pr-144' 2.60E-6 6E-3 3.40E+6 H-3 5.50E+2- 1E-2 *****
TOTAL
- 2.40E-1
, pr .
k~.) .
l
-l i
i l
l l
I 1
- Excluding Tritium and Entrained Noble Gses
- 0DCM Effluent Concentration Limit = 10 times the EC values of Reference (1.2.1) . __
- Source Term for (2SGC-R0100) from Reference (1.2.3)
- Detection Efficiency for (2SGC-R0100) from References (1.2.2) y and (1.2.4)'
[/,
(_, ***** Insignificant Y l 1-14 ISSUE 3
BV-1 and 2 oDCM l
REFERENCES BV-1 LIQUID EFFLUENT MONITOR SETPOINTS' l.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, (20.1001-20.2401) Table 2, Column 2 EC's 1.1.4 Isotopic Efficiencies For Unit 1 Liiquid Process Monitors; DLCo Calculation Package No. ERS-SFL-92-039 1.1.5' Process Alarm Setpoints For Liquid Effluent Monitors; DLCo Calculation Packge No. ERS-ATL-93-021 I
I REFERENCES l BV-2 LIQUID EFFLUENT MONITOR SETPOINTS l 1.2.1 10 CFR 20, Appendix B,-(20.1001-20.2401) Table 2, Column 2 EC's l 1.2.2 Unit 2 DRMS Isotopic Efficiencies; DLCo Calculation Package No.
ERS-SFL-86-026 1.2.3 Stone and Webster Computer Code LIO1BB; " Normal Liquid Releases From A Pressurized Water Reactor" I 1.2.4 Isotopic Efficiencies For 2SGC-ROIL 00; DLCo Calculation Package No.
ERS-JW-87-015
(
1.2.5 Conversion Factor for 2SGC-ROIL 00; DLCo Calculation Package No.
ERS-VFV-87-021 1.2.6 Process Alarm Setpoints For Liquid Effluent Monitors; DLCo Calculation Packge No. ERS-ATL-93-021 0
1-15 ISSUE 3
r BV-1 and 2 ODCM l
1.2 Compliance With 10 CFR 20 EC Limits (0DCM Appendix C CONTROL 3.11.1.1) 7 i ) 1.2.1 Batch Releases --
wi 1.2.1.1 Pre-Release *
{
The radioactivity content of each batch release vill be determined prior to release in accordance with ODCM Appendix C, Table 4.11-1. In order to assure representative samples, at least two tank volumes of- l 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. EV-1 and BV-2 vill show compliance with ODCM Appendix C CONTROL 3.11.1.1 in the following manner:
The activity of the various radionuclides in the batch release, determined in accordance with ODCM Appendix C, Table'4.11-1, is divided by the minimum dilution flow to obtain the concentration at the unrestricted area. This calculation is shown in the following equation:
Cg R
[1.2-1]
Cone ig where:
Coney - Concentration of radionuclide "i" at the unrestricted area m (uci/ml).
('") Cg - Concentration of radionuclide "i" in the potential batch release (uCi/ml).
R - Release rate of the batch (gpm).
MDF = Minimum di'lution flov (gpm). (May be combined BV-1/BV-2 flow when simultaneous liquid discharges are administrative 1y prohibited).
The projected concentrations in the unrestricted area are compared to A the OEC's. Before a release is authorized, Expression [1.2-2] must be satisfied.
Ig (Coneg /0ECg ) < 1 [1.2-2]
where: */ff OEC g - The ODCM effluent concentration limit of radionuclide "i" (uCi/ml) from Table 1.1-la and 1.1-1b.- The OEC is set at 10 times the new 10 CFR 20, Appendix B, (20.1001-20.2401)
Table 2, Col. 2 EC values.
g y
1-16 ISSUE 3
BV-1 cnd 2 ODCH !
i 1.2.1.2 Post-Release The concentration of each radionuclide follow!.ng release from the batch tank vill be calculated in the unrestricted area in the following manner:
The average activity of radionuclide "i" during the time period of release is divided by the actual dilution flow during the period of release to obtain the' concentration in the unrestricted area. This calculation is shown in the following equation:
Y Conc ik tk [1.2-3]
ik -
ADF k
where:
Concik - unrestricted The concentration of radionuclide area, during "i" period the release (uci/ml)ofattime thek.
Note: Since discharge is from an isolated well-mixed tank at essentially a uniform rate, the difference 'setween average and peak concentration within any discharge period is minimal.
C ik
- Concentration of'radionuclide "i" (uCi/ml) in batch release during time peirod k.
V - V lume of tank released during time period k (gal).
tk ADF = Actual volume of dilution flow during the time period of k release k (gal).
To show compliance with ODCH Appendix C CONTROL 3.11.1.1, the following Bfg relationship must hold:
Ei (Concik/0ECf ) < 1 [1.2-4]
O 1-17 ISSUE 3
i
' BV-l'cnd 2 ODCM
'1.2.2'. cantinuous Releases c Continuous releases of liquid affluents do not presently occur at BV-1 or-V BV-2. If-they did occur, the concentration of varioas radionuclides.in~
the unrestricted area vould be calculated using Equation [1.2-1] with C ik' the concentration of isotope 1 in'the continuous release. To.show-compliance with ODCM Appendix C CONTROL 3.11.1L1, Expression [1.2-4] must.
.again hold.
i "l
1..
l l l
1-18 ISSUE 3
BV-1 ::nd 2 ODCM TABLE 1.2-la BV-1 RECIRCULATION TIMES REQUIRED BEFORE SAMPLING OF LIQUID DISCHARGE TANKS APPROXIMATE RECIRCULATION TIME
- ffII TANK DESCRIPTION MARK NO. (Based on Historical Recirc. Rates) i Laundry And Contaminated 1LV-TK-6A/6B 2.5 hrs = (1200 gal)(2)/(16 gpm)
Shower Drain Tanks Lov Level Waste Drain Tanks 1LV-TK-3A/3B 1.5 hrs - (2000 gal)(2)/(45 gpm)
High Level Vaste Drain Tanks ** 1LV-TK-2A/2B 3.4 hrs - (5000 gal)(2)/(50 gpm)
Evaporator Test Tanks ILV-TK-5A/SB 1.4 hrs = (3000 gal)(2)/(73 gpm)
Steam Generator Drain Tanks 1LV-TK-7A/7B 17.2 hrs =(35000 gal)(2)/(68 gpm)
Boron Recovery Test Tanks 1BR-TK-2A/2B 9.7 hrs =(13;000 gal)(2)/(45 gpm)
O
- The times listed are those approximated for two recirculations of a full tank with one recirculation pump in operation (using historical
" airculation rates). Partially full tank recirculation times are directly T proportional to the fraction of the tank capacity occupied by the entrained Actual recirculation times are determined j7 liquid vaste after isolation.
prior to sampling using actual tank volumes and actual recirculation rates available in the BV-1 Control Room.
- Not normally a direct source of discharge.
1-19 ISSUE 3 l Revision 2
BV-1 rnd 2 ODCM TABLE 1.2-lb BV-2 RECIRCULATION TIMES REQUIRED BEFORE SAMPLING OF LIQUID DISCHARGE TANKS
( ,
~s APPR0XIMATE RECIRCULATION TIME
- TANK DESCRIPTION MARK NO. (Based on Historical Recire. Rates) #[f7 Liquid Vaste Tanks 2LVS-TK21A/21B 11.5 hrs (10,000 gal)(2)/(29 gpm)
Steam Generator Blowdown 2SGC-TK21A/21B 25.8 hrs - (51,000 gal)(2)/(66 gpm)
Hold Tanks Steam Generator Blowdown 2SGC-TK23A/23B 9.1 hrs - (18,000 gal)(2)/(66 gpm)
Test Tanks p
!a!
I i
i i
l
'
- The times listed are those approximated for two recirculations of a full tank with one recirculation pump in operation (using historical' recirculation rates). Partially full tank recirculation times are directly proportional to the fraction of the tank capacity occupied by the entrained J,. 's liquid vaste after isolation. Actual recirculation times are determined
/ prior to sampling using actual tank volumes and actual recirculation rates available in the BV-2 Control Room.
1-20 ISSUE 3 Revision 2
BV-1 cnd 2 ODCM 1.3 Compliance Vith 10 CFR 50 Dose Limits (ODCM Appendix C CONTROLS 3.11.1.2 es And 3.11.1.3) i i M 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 Cumulation Of Doses, (0DCM Apyendix 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 E A g7 E*atkCik Fk [1.3-1]
i k=1
~
where:
DT = The cumulative dose commitment to the total body or any organ, T, from the liquid effluents for the total time period m
em I atk (*#8")
k=1 i \
atk = The length of the kth release over which Cik and Fk are averaged
^
for all liquid releases (hours).
Cik - The average concentration of radionuclide, "i" (uCi/ml), in undiluted liquid effluent during time period ot., from any liquid release.
A = The site related ingestion dose commitment factor to the total IT body or any organ T for each identified principal gamma and beta enitter (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. Definedastheratihoftheaverage l undiluted liquid vaste flow to the product of the average flov
! from the site discharge structure during the report period to l
unrestricted receiving vaters, times 3. (3 is the site specific applicable factor for the mixing effect of the BV-1 and BV-2 discharge structure). I (S
) = Vaste Flov (3)(Dilution Vater Flow) 1-21 ISSUE 3 l f
L
BV-1 Cnd 2 ODCM The site specific applicable factor of 3 results in a conservative estimate of the near field dilution factor based upon Regulator /
Guide 1.113 methodology and is a factor of 10 belov the limit specified in MUREG-0133, Section 4.3.
The dose faz. :A vas calculated for an adult for each isotope using thefollowingequlfionfromNUREG-0133.
(1.3-2]
Ah = 1.14E5 (730/Dy+ 21BF g)DF h vhere:
1.14E5 = 1E6 pCi x 1E3 ml x 1 yr uCi T- 8760 hr 730 - Adult water consumption rate (liters /yr).
D V
= Far field dilution factor from the near field area vithin 1/4 mile of the release point to the potable water intake for adult water consumption.
21 - Adult fish consumption (kg/yr).
BF 3
= Bioaccumulation factor for radionuclide "i" in fish from j Table A-1 of Regulatory Guide 1.109 Rev. 1 (pCi/kg per pCi/l). Bovever, if data was not available from that i reference, it was obtained from Table 6 of UC RL-50564, Revision 1.
The bioaccumulation factor for niobium (300 pCi/kg per pCi/1) was not obtained from either of the above references noted. It was '>tained from IAEA Safety Series No. 57.
Justification for use of this value is documented in Appendix A to Calculation Fackage No. ERS-ATL-83-02?.
DF = Dose conversion factor for radiongelide "i" for adults for a h particular organ r from Table E-11 of Regulatory Guide 1.109, Rev. 1 (mrem /pCi). If none, from NUREG-0172 or Regulatory Guide 1.109, Rev. O.
A table of A h values for an adult it BV-1 and BV-2 are presented in Table 1.3-1 The far field dilution factor (D y) for BV-1 and BV-2 is 200. This value factor of 600 applicable to the Midland is based on a total dilution 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 exist for the radioactive effluent to be transported to the intake.
O 1-22 ISSUE 3 Revision 1
BV-1 cnd 2 ODCH.
.. 1-
~The cumulative doses (from each reactor unit) for a calendar quarter and f~N -a calendar year are.-compared. to ODCM Appendix C CONTROL 3.11.1.2 as
( ,) -
follows:.
For'the calendar quarter,.
D7 f 1.5 mrem total body 11.3-3]
y D73 5 mrem any organ. [1.3-4]
For the calendar. year, Dr f 3 mrem total body [1.3-5) 1 D7f 10 mrem any organ [1.3-6]
1 If any of the limits in Expressions [1.3-3] through [1.3-6] are exceeded, a Special Report pursuant to both.Section IV.A of Appendix I of 10 CFR 50
< and Technical Specification 6.9.2f must be filed with the NRC at the i
' identified locations.
I'.3.2 ProjectionOfDoses(ODCHAppendixCCONTROL3.11.k.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
.radiocctive materials in each liquid vaste batch prior to its discharge, 7, .when the projected doses: due to liquid effluent releases.from each i reactor unit, when averaged over 31 days vould exceed 0.06 mrem to the
, total body or 0.2 mrem'to any organ. Doses used in the projection are obtained according to equation [1.3-1]. The 31-day dose projection shall be performed according to the following equations:
y .
When. including pre-release data,
[1.3-7]
D A+B 31 + C 37 = T, When not including pre-release data,
[1.3-8]
D 31 = 31 + C where:
D Projected 31 day dose (mrem).
A 31 =
= Cumulative dose for quarter (mrem).
4 B = Projected dose from this release (mrem).
A T = Current days into quarter.
()- C = Value which may be used to anticipate plant trends (mrem).
( 1-23 ISSUE 3 l
Revision 1
BV-1 Cnd 2 ODCM TABLE 1.3-1 A VALUES FOR THE ADULT FOR THE BEAVER VALLEY SITE it (mrem /hr per uCi/ml)
NUCLIDE BONE LIVER T-BODY THYROID KIDNEY , LUNG GI-LLI H-3 0.00E-01 2.70E-01 2.70E-01 .2.70E-01 2.70E-01 2.70E-01 2.70E-01 C-14 3.13E 04 6.26E 03 6.26E 03 6.26E 03 6.26E 03 6.26E 03 6.26E 03 Na-24 4.08E 02 4.08E 02 4.08E 02 4.08E 02 4.08E 02 4.08E 02 4.08E 02 Pbb bbbbb7 b.87E06 1.79E 06 0.00E-01 0.0bE-01 0.00E-01 5.19E 06 Cr-51 0.00E-01 0.00E-01 1.27E 00 7.62E-01 2.81E-01 1.69E 00 3.21E 02 Hn-54 0.00E-01 4.38E 03 8.35E 02 0.00E-01 1.30E 03 0.00E-01 1.34E 04 kn5b bIbbb b5 5I5bb bb 1.95E 01 b bbb bk 1.40E bb b bbb b[ b bbb bb Fe-55 6.59E 02 4.56E 02 1.06E 02 0.00E-01 0.00E-01 2.54E 02 2.61E 02 Fe-59 1.04E 03 2.45E 03 9.38E 02 0.00E-01 0.00E-01 6.83E 02 8.15E 03
- = - - - - __
Co-57 0.00E-01 2.10E 01 3.50E 01 0.00E-01 0.00E-01 0.00E-01 5.33E 02 Co-58 0.00E-01 8.95E 01 2.01E 02 0.00E-01 0.00E 0.00E-01 1.81E 03 Co-60 0.00E-01 2.57E 02 5.67E 02 0.00E-01 0.00E-01 0.00E-01 4.83E 03 Ni-63 3.12E 04 2.16E 03 1.05E 03 0.00E-01 0.00E-01 0.00E-01 4.51E 02 Ni-65 1.27E 02 1.65E 01 7.51E 00 0.00E-01 0.00E-01 0.00E-01 4.17E 02 Cu-64 0.00E-01 1.00E 01 4.70E 00 0.00E-01 2.52E 01 0.00E-01 8.53E 02 knb5 h$bbb bk 7.37b bh 3.33E b4 0.00Eb1 4.93E 04 0.00E-01 4.64E 04 Zn-69 4.93E 01 9.43E 01 6.56E 00 0.00E-01 6.13E 01 0.00E-01 1.42E 01 Br-83 0.00E-01 0.00E-01 4.04E 01 0.00E-01 0.00E-01 0.00E-01 5.82E 01 Br8k b.00E-01 b$00E-01 5.2kE bk b.bbE-01 b$bbb bk 0. bob bk k ((b b$
Br-85 0.00E-01 0.00E-01 2.15E 00 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Rb-86 0.00E-01 1.01E 05 4.71E 04 0.00E-01 0.00E-01 0.00E-01 1.99E 04 Rb-88 0.00E-01 2.90E 02 1.54E 02 0.00E-01 0.00E-01 0.00E-01 4.00E-09 Rb-89 0.00E-01 1.92E 02 1.35E 02 0.00E-01 0.00E-01 0.00E-01 1.12E-11 Sr-89 2.22E 04 0.00E-01 6.39E 02 0.00E-01 0.00E-01 0.00E-01 3.57E 03-
_= ------------ ---------------
Sr-90 3.48E 05 0.00E-01 1.34E 05 0.00E-01 0.00E-01 0.00E-01 1.58E 04 Sr-91 4.10E 02 0.00E-01 1.65E 01 0.00E-01 0.00E-01 0.00E-01 1.95E 03 Sr-92 1.55E 02 0.00E-01 6.77E 00 0.00E-01 0.00E-01 0.00E-01 3.08E 03 b-90 b$8bb-01 0.bbE bk 1.5bb bb b.0bE-01 0.00Eb1 b.bOE bk 6 55b b5 Y-91m 5.48E-03 0.00E-01 2.12E-04 0.00E-01 0.00E-01 0.00E-01 1.61E-02 Y-91 8.50E 00 0.00E-01 2.2/E-01 0.00E-01 0.00E-01 0.00E-01 4.68E 03 b-9b 5.b9bb2 0bOE-01 1.49E-Ob b.00E bk b bbb b b bbb bk 8 bbb b Y-93 1.62E-01 0.00E-01 4.46E-03 0.00E-01 0.00E-01 0.00E-01 5.12E 03 Zr-95 2.53E-01 8.11E-02 5.49E-02 0.00E-01 1.27E-01 0.00E-01 2.57E 02
= --------_--------------
Zr-97 1.40E-02 2.82E-03 1.29E-03 0.00E-01 4.26E-03 0.00E-01 8.73E 02 Nb-95 4.47E 00 2.49E 00 1.34E 00 0.00E-01 2.46E 00 0.00E-01 1.51E 04 Nb-97 3.75E 02 9.49E-03 3.46E-03 0.00E-01 1.11E-02 0.00E-01 3.50E 01
-- _- _- .------.= _ ._= -
1-24 ISSUE 3 Revision 1 e
BV_1 cnd 2 ODCM TABLE 1.3-1 A gg VALUES FOR THE ADULT FOR THE BEAVER VALLEY SITE
'~'$> (mrem /hr per uCi/ml) v 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 0.00E-01 1.48E-01 0.00E-01 4.85E 00 0.00E-01 2.29E 02 Ru_106 6.70E 01 9.00E-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
_____________________ - _ -_==____ ___________________________________ j Te-125m 2.57E 03 9.30E 02 3.44E 02 7.72E 02 1.04E 04 0.00E_01 1.03E 04 Te_127m 6.49E 03 2.32E 03 7.90E 02 1.66E 03 2.63E 04 0.00E-01 2.17E 04 Te-127 1.05E 02 3.78E 01 2.28E 01 7.81E 01 4.29E 02 0.00E-01 8.32E 03
___________- _==__________________________-_____-__________________________
Te_129m 1.10E 04 4.11E 03 1.74E 03 3.78E 03 4.60E 04 0.00E-01 5.55E 04 l Te-129 3.01E 01 1.13E 01 7.33E 00 2.31E 01 1.26E 02 0.00E-01 2.27E 01 l Te-131m 1.66E 03 8.10E 02 6.75E 02 1.28E 03 8.21E 03 0.00E-01 8.05E 04
{
T 535 k.89E Ok h.88E 00 5$96Eb0 $bbE01 8 hhE b 0$00b_bk 2$6hb 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 ^1 6.87E 03 1.26E 02 0.00E-01 6.97E 01 i I-131 1.51E 02 2.16E 02 1.24E J2 7.08E 04 3.71E 02 0.00E_01 5.70E 01 j
.. ._=_______________________
l I-132 7.37E 00 1.97E 01 6.90E 00 6.90E 02 3.14E 01 0.00E_01 3.71E 00 I 133 5.16E 01 8.97E 01 2.74E 01 1.32E 04 1.57E 02 0.00E-01 8.06E 01 !
I-134 3.85E 00 1.05E 01 3.74E 00 1.81E 02 1.66E 01 0.00E-01 9.12E_03 j 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./9E 05 0.00E-01 2.29E 05 7.61E 04 1.24E 04 i Cs_136 3.12E 04 1.23E 05 8.86E 04 0.00E_01 6.85E 04 9.39E 03 1.40E 04 i
____________________.__-_= - -______________________________________________
Cs_137 3.82E 05 5.22E 05 3.42E 05 0.00E-01 1.77E 05 5.89E 04 1.01E 04 Cs-138 2.64E 02 5.22E 02 2.59E 02 0.00E-01 3.84E 02 3.79E 01 2.23E-03 Ba-139 9.69E_01 6.90E_04 2.84E-02 0.00E-01 6.45E-04 3.92E-04 1.72E 00 ;
____===_ ________. _=__________________.._______________-_____________
i Ba_140 2.03E 02 2.55E-01 1.33E 01 0.00E-01 8.66E_02 1.46E-01 4.18E 02 Ba_141 4.71E-01 3.56E-04 1.59E-02 0.00E-01 3.31E-04 2.02E-04 2.22E-10 ,
Ba_142 2.13E-01 2.19E-04 1.34E-02 0.00E_01 1.85E-04 1.24E-04 3.00E-19 La_140 1.51E-01 7.59E-02 2.01E-02 0.00E-01 0.00E-01 0.00E-01 5.57E 03 l La_142 7.71E-03 3.51E-03 8.74E-04 0.00E-01 0.00E-01 0.00E-01 2.56E 01 1
,~ Ce-141 2.63E-02 1.78E-02 2.02E-03 0.00E-01 8.26E-03 0.00E-01 6.80E 01 '
___________ ________________________________________= ==
( ) ______________
ss 1_25 ISSUE 3
BV-1 cnd 2 ODCM TABLE 1.3-1 A VALUES FOR THE ADULT FOR THE BEAVER VALLEY SITE it (mrem /hr per uCi/ml)
NUCLIDE BONE LIVER T-BODY THYROID KIDNEY LUNG GI-LLI Ce-143 4.64E-03 3.43E 00 3.79E-04 0.00E-01 1.51E-03 0.00E-01 1.28E 02 Ce-144 1.37E 00 5.73E-01 7.36E-02 0.00E-01 3.40E-01 0.00E-01 4.64E 02 Pr-143 5.54E-01 2.22E-01 2.75E-02 0.00E-01 1.28E-01 0.00E-01 2.43E 03 Pr-144 1.81E-03 7.53E-04 9.22E-05 0.00E-01 4.25E-04 0.00E-01 2.61E-10 Nd-147 3.79E-01 4.38E-01 2.62E-02 0.00E-01 2.56E-01 0.00E-01 2.10E 03 V-187 2.96E 02 2.47E 02 8.65E 01 0.00E-01 0.00E-01 0.00E-01 8.10E 04 N 59 b$9bb-02 2.85E-03 1.57E-03 0.00E-01 8.89E-03 b.bbb-01 585bb5 O
O 1-26 ISSUE 3 I
9
y~ . .
BV-1?cnd'2~0DCM"
'l.4 h " Liquid ' RSdvas te ' System' f,g.,
SJ iThe. liquid'radvaste' system has the capability to control', collect, process,. ~
store / recycle,'.and.~ dispose of- Iliquid radioactive Hvaste' generated'as a result of plant ~ operations, ; including anticipated operational. occurrences.
-This; system also uses-a some. of thel components Lof' the steam' generator
'lblovdown system for processing.
- Simplif'edi flow. diagrams'of the ' liquid Jradvaste systems for BV-1 anBV-2d are.provided as' Figures 1,4-1. and 1.4-2 respectively. 'A diagram showing
'the liquid? effluent. release' points'is' provided'as Figure 1.4-3. 1Since the
. concept of a^ shared liquid.radvaste system is used, then any liquid vaste.
s generated can'be stored, processed and discharged from either BV-l'or-BV-2.-
~
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.r i
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'l-27 ISSUE 3 Revision 2-L -
BV-1 and 2 ODCM 1.4.1 BV-1 Liquid Radvaste System Components 1.4.1.1 LV-TK-2A & 2B: High Level Vaste Drain Tanks There are two of these tanks, each tank has a capacity of 5,000 gallons. They are located on the northwest vall of the Auxiliary Building (elevation 735'). They receive liquid vastes from the vent and drain system with activity concentrations above 4E-4 uCi/ml.
1.4.1.2 LV-TK-3A & 3B: Lov Level Vaste Drain Tanks There are two of these tanks, each tank has a capacity of 2,000 gallons. They are located in the northwest corner of the Auxiliary Building (elevation 735'). They receive liquid vastes from the vent and drain system with activity concentrations less than 4E-.4 uCi/ml.
1.4.1.3 LV-I-2: Liquid vaste Demineralizer The main purpose of the demineralizer is to clean liquid vaste water of particulate and dissolved radioactive contaminants. There are four resin beds and a filter associated with this demineralizer. Each of the beds can be customized with different resins so that we can effectively remove chemical contaminants along with radioactive contaminants. Generally, beds 1 and 2 contain a Cation Resin and beds 3 and 4 contain a Mixed Bed Resin. This demineralizer is located in the Decon Building (elevation 735').
1.4.1.4 LV-TK-7A & 7B: Steam Generator Drain Tanks There are two of these tanks, each tank has a capacity of 34,500 gallons. They are located in the Fuel Pool Leakage Monitoring Room (elevation 735'). They rec.eive liquid vaste that has been processed through the liquid vaste demineralizer. Once this tank is full, it is put on recirculation through the demineralizer (for a minimum of two tank volumes) until the radioactivity concentration is acceptable for discharge.
1.4.1.5 RM-LV-104: Liquid Vaste Discharge Radiation Monitor This off-line gamma scintillator radiation monitor continuously analyzes liquid vaste as it is being discharged. The upper activity alarm on this radiation monitor has a setpoint that would indicate ve are approaching OEC limits for radioactive water leaving the site. If an upper activity alarm on this radiation monitor is received, it automatically terminates the discharge by closing the discharge line isolation valves.
O 1-28 ISSUE 3
BV-1 cnd 2 ODCM 1.4.2 BV-2 Liquid Radvaste System Components
,c .
) 1.4.2.1 2LUS-TK21A & 21B: Vaste Drain Tanks There are two of these tanks, each tank has a capacity of 10,000 gallons. They are located in the northeast corner of the Auxiliary Building (elevation 710'). They receive. liquid vastes from the vent and drain system.
1.4.2.2 2SGC-IOE21A & 21B: Steam Generator Blovdown Cleanup Ion Exchangers The main purpose of the ion exchangers is to clean liquid vaste water of particulate and dissolved radioactive contaminants through an ion exchange process. There is a resin bed, outlets strainer, and cleanup filter associated with each of these ion exchangers. They are located in the Waste Handling Building (elevation 722').
1.4.2.3 2SGC-TK23A & 23B: Steam Generator Blowdown Test Tanks There are two of these tanks, each has a capacity of 18,000 gallons.
They are located in the Auxiliary Building (elevation 755'). They receive liquid vaste that has been processed through the cleanup ion exchangers. Once this tank is full, it is put on recirculation through the cleanup ion exchanger (for a minimum of two tank volumes) until the radioactivity concentration is acceptable for discharge.
1.4.2.4 2SGC-TK21A & 21B: Steam Generator Blowdown Hold Tanks (g)
There are two of these tanks, each has a capacity of 50,000 gallons.
They are located in the vaste Handling Building (elevation 722').
These tanks are used to store liquid vaste .en the radioactive concentration of the steam generator blowdown est tank is not acceptable for discharge. The contents of this tank is then processed through the Unit 1 or Unit 2 Liquid Radvaste Treatment System until the radioactivity concentration is acceptable for discharge.
1.4.2.5 2SGC-RO-100: Liquid Vaste Effluent Monitor j
This off-line gamma scintillator radiation monitor continuously analyzes liquid vaste as it is being discharged. The upper activity alarm on this radiation monitor has a setpoint that vould indicate ve are approaching OEC limits for radioactive water leaving the site. If an upper activity alarm is received, it automatically terminates the l l discharge by closing the discharge line isolation valves. I l
i
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1-29 ISSUE 3 L
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u8M - 2.0 fGASEOUS EFFLUENTS' :) L
[ / ODCM AppendixC' CONTROLS a liedble to:!dosel_ rate;Espply.to)the.' site.. The
{b. 'siteJdose. rate is' due; to the summation' of releases' from both units.' . '0DCM -
' Appendix C CONTROLS applicablento accumulated; dose' apply ~. individually to; Qf ,Jeach' unit.v Releases at. thef Beaver . Valley; site amay,;be: ground llevelsor;:L
~, ,y : elevated in' nature. >A111.fground; level.' releases are identified:with a.
T '
.specificLunit.zin'the determination'of site dose rate'and' dose attributed to 1 ,
- that unit.J Elevated releases--from---both' units;are considered to originate-Lfrom a shared.radvaste 1 system Eandn are ~ discharged from a common' release-1 t
y' ;pointR the Process Vent,lat the top ~of the--BV-1 cooling; tower. At BV-1 andi t
BV-2,cthe dose from the ' shared radvaste.-system via'the ProcessgVent is
% normally~ apportioned; equally.to: the units. However,'a containment purge'-
-vianthe Process Vent'shall<be attributed-to;a' specific unit. . >
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2-1 ISSUE 3 y
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'BV-1 cnd 2 ODCM
, (
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2.1 Alarm Setpoints
/ h 2.1.1 - BV-1 Monitor Alarm Setpoint Determination-1DCM 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 5 500 mrem /yr to the total body and to f 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 which 3 are located in BV-1 (alternates exists for these monitors), and 5 are located in BV-2. As previously noted, BV-2 elevated releases are via the BV-1 Process Vent.
Differences exist between the setpoint presentations of ihe 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 j 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
_f 7 difference is due to BV-2 software which applies a conversion factor to the BV-2 rav 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-HIGHj(BV-1) or HIGH (BV-2) Alarm Setpoints established at 30i percent of the site limit, and except 3 monitors noted below, HIGH (BV-1) or ALERT (BV-2) Alarm Setpoints established at 10 percent of the site limit.
o 77 2-2 ISSUE 3 s
BV-1 Cnd 2 ODCM Monitor Setpoint Specifications Based On Fraction Of Site Limit UNIT, RELEASE POINT AND MONITOR FRACTION OF SITE LIMITING DOSE P 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. BN-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)
Vith the monitor setpoints based on fractions of the site limit as defined above, the following criteria may be applied to determine that the dose rate due to noble gas released from the site complies with ODCM Appendix C CONTROL 3.11.2.1:
- The site dose rate is less than 50% of the site limit when all monitors are below the HIGH (BV-1) and ALERT (BV-2) Alarm Setpoints.
- Vith all monitors below the normal HIGH-dIGH (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 rato limit may have been exceeded.
[
2-3 ISSUE 3
-BV-1 and?2 0DCM~
.A release may be batch or continuous-in nature. Batch refers to releases
' f-sq-that'are intermittent in. radionuclide concentrations or flow,-such as 3
releases from gas ~: storage' tanks, containment. ventings and purges, and~
systems or components with infrequent;use. .. Batch releases may.be due toz operational variations:vhich result in radioactive releases greater than 50% of: the ' releases. normally c 1 considered as continuous. . Batch releases
- from these sources
- during- normal. operation,1-including anticipated; operational occurrences ~, are defined as thoseLlvhich. occur for a total of c500 hours orLless in'a' calendar year,s but notlmore:than 150. hours'in any.
. quarter. iThe batch relative concentration value has been calculatedlin-accordance with ,the : guidelines .provided in NUREG-0324,for short-term zg release. If simultaneous batch and continuous. release out of one vent
. occurs,:use .the- lowest 'setpoint obtained- according to theifollowing; Sections 2.1.1.l'through-2.1.3.2.
F
)-
\LJ ,
.j
{!
l: m- a i
I' i
h1 l l 11 ,
i .l s
i l' , ,
I b L i i
~!
i 24 ISSUE 3 m
i i;
I BV-1 cnd 2 ODCH BV-1 Setpoint Determination Based On A Calculated Mix For Ventilation 2.1.1.1 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 ABOVE BACKGROUND (P) PRIMARY
- 30% 10%
MONITOR SITE SITE (A) ALTERNATE LIMIT LIMIT MONITOR C.R. HHSP HSP I
' Continuous Release Via The (P)RM-VS-101B 3.00E3 9.00E2 3.00E2
)-
BV-1 Ventilation Vent (A)RM-VS-109(5) 1.47E3 4.40E2 1.47E2
' Batch Release Of Containment (P)RM-VS-101B 3.90E2 1.17E2 3.90E1 Purge Via The BV-1 Ventila- (A)RM-VS-109(5) 4.68E2 1.40E2 4.68E1 tion Vent
' Continuous Release Via The (P)RM-VS-107B 6.44E3 1.93E3 6.44E2 BV-1 Containment Building (A)RM-VS-110(5) 3.38E3 1.01E3 3.38E2 Vent
- Batch Release Of Containment (P)RM-VS-107B' 1.93E3 5.80E2 1.93E2 Purge Via The BV-1 Contain- (A)RM-VS-110(5) 1.01E3 3.04E2 1.01E2 ment Building Vent
- Vhen the primary monitor is out of service, and ODCM Appendix C CONTROL 3.3.3.10 can be met for the respective alternate monitor, the alternate setpoints may be utilized.
The setpoints were determined using the following conditions and information:
- Source terms given in Table 2.1-la. These gaseous source terms 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 lodines, which are not used in site noble gas dose rate calculations.
- Onsite meteorological data for the period January 1, 1976 through December 31, 1980.
- Discharge flow rate of 62,000 cfm for the BV-1 Ventilation Vent (Continuous).
- Discharge flow rate of 92,000 cfm for the BV-1 Ventilation Vent (Batch release of containment purge).
O 2-5 ISSUE 3
BV-1 cnd 2 ODCH
- Discharge flow rate of 49,300 cfm for the BV-1 Containment Vent (Both 7, continuous and batch release of Containment Purge).
! j d
- Information listed under References - Gaseous Effluent Monitor Setpoints.
The calculation method given in Sections 2.1.1.1.1 through 2.3.1.1.7 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.
c
- Batch release of BV-1 Containment Purge via the BV-1 Containment Building Vent.
1 2.1.1.1.1 BV-1 Hix Radionuclides -
{
o i 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. Gaseous source terms are the ;
(N radioactivity of the noble gas radionuclides in the effluent. !
! Gaseous source terms can be obtained fr9m Table 2.1-la.
- b. The fraction of the total radioactiviky in the gaseous effluent -
comprised of noble gas radionuclide "i" (S ) for each individual 4
noble gas radionuclide in'the gaseous effluent was determined by: l A
S i [2.1(1)-1]
g,IA 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.
2.1.1.1.2 BV-1 Maximum Acceptable Release Rate (Vhole Body Exposure)
The maximum acceptable total release rate (uci/sec) of all noble gas radionuclides in the gaseous effluent (O ) tbased upon the whole body exposure limit was calculated by:
O 500 [2.1(1)-2]
i t-i
,-m
~
l 2-6 ISSUE 3 J
s a
BV-1 ond 2 ODCM vhere:
(X/0)" - The highest calculated annual average relative concentration of affluents released via the Ventilation Vent for any area at or beyond 3 the unrestricted area boundary for all sectors (sec/m ) from Table 2.2-5.
- 1.03E-4 sec/m for continuous releases.
(X/q)" - The short term relative concentration of effluents released via the Ventilation Vent for any ares at or l
beyond 3 the unrestricted area boundary for a7.1 sectors (sec/m ) from Table 2.3-36.
3
= 3.32E-4 sec/m for batch release of containment purge. ;
(X/0)cv - The highest calculated annual average relative concentration of effluents released via the Containment Building Vent for any area at or beyond the 3 unrestricted area boundary for all sectors (sec/m ) from Table 2.2-4.
- 9.24E-5 sec/m3 for continuous releases.
(X/q)** - The short via released termtherelative concentration containment of effluents 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 3emissions from noble gas radionuclide "i" (mrem / year /uCi/m )
from Table 2.2-11.
Sg - From equation {2.l(1)-1] above.
2.1.L l.3 BV-1 Maximum Acceptable Release Rate (Skin Exposure}
O was also determined based upon the skin expesure limit by:
t 0 3000 [2.l(1)-3]
t = (X/0) I (L3 + 1.lM 3) Sg i
where i Lg = The skin dose factor due to beta emissions 3
from noble gas radionuclide "i"(mrem / year /uCi/m ) from Table 2.2-11.
Hg - The air dose factor due to gamma 3emissions from noble gas radionuclide "i"(mrad / year /uci/m ) from Table 2.2-11.
O 2-7 ISSUE 3
( BV-1 cnd 2 ODCM n
1.1 - The ratio of the tissue to air absorption coefficients r- s over the energy range of the photons of interest, (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 (0g ) for each individual noble gas radionuclide in the ganeous effluent was determined by:
Og-Sg O t [2.1(3)-4]
(NOTE: Use the lover of the 0 values obtained in t
Section T.1.1.3.2 as.d 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 tb.e gaseous effluent (C4 ) for each individual noble gas radionuclide "i" in the gaseous effluent was determined by:
2.12E-3 0 1 C f, [2.1(1)-5]
F vhere:
,1 ) F - The maximum acceptable effluent flow rate at the point
[ of release (cfm).
000 cfm (BV-1 Ventilation Vent)
- 49,300 cfm (BV-1 Containment Building Vent) 3 2.12E Unit conversion factor (60 sec/ min x 3.5.7-5 ft fec),
2.1.1.1.6 BV-1 Monitor Count Rate The calculated monitor count rate (nepm) above background attributed to the noble gas radionuclide (C.R.) was determined by:
1 C.R. - E Cg Eg [2.1(1)-6)]
- i vhere
Ey . The detection efficiency of the monitor for noble gas radionuclide "i" (cpm /uci/cc) from Table 2.1-2a.
'gm ,
j
\ g 1
2-8 ISSUE 3
BV-1 and 2 ODCM 2.1.1.1.7 BV-1 Monitor Setpoints The monitor alarm setpoints, above background vere determined as follows:
- a. The monitor HIGH-HIGH Alarm Setpoint above background (nepm) was determined by:
HHSP = 0.30 C.R. [2.1(1)-7]
- 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.
O O l l
I 2-9 ISSUE 3
[
BV-1 cnd 2 ODCH 2.1.1.2 BV-1 Setpoint Determination Based On Analysis Prior To Kelease For 73 Ventilation Vent And Centainment Building Vent Releases (Ground (u- ) Releases)
When the setpoints established using "the calculated mix" for ground releast:s 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 the Containment Buildine Gas Honitor (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 j Vent. j
~
2.1.1.2.1 BV-1 Haximum Acceptable Release Rate The maxiaum acceptable discharge flow rate from Containment Vent or Ventilation Vent during purging is determined as follows:
- a. The a ximum acceptable gaseous discharge flow rate (f) from the !
Containi:ent Vent or Ventilation Vent (cfm) during purging based :
(]
(,/ upon the whole body exposure limit is calculated by: ;
i 1.06 S T [2.1(1)-17) f" (X/q) EKgCg i
where ;
i 1.06 - 500 mrem /yr x 2.12E-3 j 500 mrem /yr - dose rate limit '
2.12E-3 - unit conversion factor 3
- (60 sec/ min x 3.53E-5 ft /cc)
S - Percent of site dose rate released via this pathway. Up to 60% of the site dose rate is permissible for one release point under the alarm set point rules of Section 2.1.1. To exceed 60% of the site limit from one release point, the remaining release point limits must be correspondingly reduced or secured to provide the necessary margin below the site dose rate limit.
T - Maximum valve for T is 16 based on the limiting restriction in ODCH 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; l
'J T - 960/60 - 16). See Reference 2.1.6.
2-10 ISSUE 3
BV-1 cnd 2 ODCM (X/q)## = The highest calculated short term relative concentration of effluents released via the Ventilation Vent for any area at or beyond3 the unrestricted area boundary for all sectors (sec/m ) from Table 2.3-36.
- 3.32E-4 sec/m (X/q)C# = of The highest calculated short term relative concentration effluents released via the Containment Building Vent for areas at or beyond3the unrestricted area boundary for all sectors (sec/m ) from Table 2.3-37.
- 3.08E-4 sec/m Kg = The total whole body dose factor due to gamma 3emissions from noble gas radionuclide "i" (mrem / year /uci/m )
from Table 2.2-11.
Cg - The undiluted radioactivity concentration of noble gas radionuclide "i" in the gaseous source (uCi/cc) as determined by analysis of the gas to be released.
- b. The flov rate (f) is also determined based upon the skin exposure limit as follows:
6.36 S T [2.l(1)-18]
I " (X/q) E (Lg + 1.1M g) Cg i
where:
6.36 - 3000 mrem /yr x 2.12E-3 3000 mrem /yr - dose rate limit 2.12E-3 = unit conversion factor 3
= (60 sec/ min x 3.53E-5 ft fec)
Lg - The skin dose factor due to beta emissions 3 I#
- noble gas radionuclide "i" (mrem / year /uCi/m ) from Table 2.2-11.
Mg - The air dose factor due to gamma emissions 3 from noble gas radionuclide "i" (mrad / year /uci/m ) from Table 2.2-11.
(X/q) = Same as in Section 2.1.1.2.1.a.
(
- c. The flow rate (f) is determined by selecting the smaller of the calculated (f) values based on the whole body exposure limit (Section 2.1.1.2.1.a) and based on the skin exposure limit (Section 2.1.1.2.1.b). The actual purge flow rate (cfm) must be maintained at or below this calculated (f) value or the discharge cannot be made from the vent.
O 2-11 ISSUE 3
~
J t;'- '
-g.1
- - BV-1. cndt2 0DCM '
c 1 . :; v . .
~
,. . . . + .
-2.1.1.2.2 LBV-1 Monitor Setpoints
. The " monitor. . alarm y'setpoints .above : background -are ' determined as E
t
}
' follows:--
~
'a.';Thec'alculated monitor HIGH-HIGH Alarm Setpoint-above' background W~
l(nepm)' attributed'to the noble gas radionuclides.is determined bye ;
f _ E Cg'Eg *
[2.1(1)-19]
- HHSP = ,
n F' wheres:
f; = Th'e' maximum acceptable gaseous discharge flow rate (cfm) determined in Section 2.1-1;2.1. .
- c F - The' maximum actual or design effluent flow rate (cfa).at' the point of release. s F
= 92,000 cfm.(BV-1 Ventilation Vent -- design)
= 49,300 cfm (BV-1 Containment Vent -- design)
Cg '= The undiluted radioactivity concentration of noble gas radionuclide "i" in the gaseous: source (uci/ce) as determined by analysis of.the gas to be' released.
'1' -E* g = The detection efficiency of the monitor for noble gas-radionuclide "i" (cpm /uci/cc) from Table 2.1-2a.
i . b. When a HIGH-HIGH set point. has been calculated according to this
.)
section, the monitor HIGH . Alarm Setpoint above background (nepm)
't- is determined as follows:
BSP = HHSP x 0.33 .(2.1(1)-20]
y w
2-12 ISSUE 3
'= .,.
t y .
BV-1 Cnd 2 ODCH.
2.1.2 BV-2 Monitor Alarm Setpoint Determination See Section 2.1.1 for a description of Monitor Alarm Setpoint Determinations.
2.1.2.1 BV-2 Setpoint Determination Based on A Calculated Mix For Ventilation Vent, Containment Vent, Condensate Polishing Building Vent, Decontamination Building Vent, and Vaste Gas Storage Vault Vent Releases
.The table below gives the calculated monitor count rate above background (C.R.) in nepm, and provides the equivalent monitor indication (D.V.) in net uCi/cc associated with the most limiting site dose rate limit (i.e., 500 mrem /yr Total Body or 3000 mrem /yr Skin).
The HIGH alarm setpoint (HSP) in uCi/cc above background, and the ALERT alarm setpoint (ASP) in uCi/cc above background for each vent and operational condition should be as follows:
BV-2 ALARM SETPOINTS FOR GROUND RELEASES uCi/cc ABOVE BACKGROUND 30%
- SITE SITE C.R. D.V. LIMIT LIMIT MONITOR nepm uCi/cc HSP ASP
' Continuous 2HVS-R0101B 8.26E3 3.01E-4 9.04E-5 3.01E-5 Release Vla 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*RO109B 4.32E3 1.06E-4 3.17E-5 1.06E-5 Release Via The BV-2 Containment Vent
' Batch Release Of 2BVS*R0109B 2.09E3 4.05E-5 1.21E-5 4.05E-6 Containment Purge Via The BV-2 Containment Vent
' Continuous 2HVL-R0112B 2.89E4 1.61E-3 4.82E-4 9.63E-6 Release Via The BV-2 Condensate Polishing Building Vent
' Continuous 2RM0-RQ301B 5.66E4 3.15E-3 9.44E-4 9.44E-6 Release Via The BV-2 Decontamination Building Vent
' Continuous 2RH0-R0303B 8.03E5 2.24E-2 6.71E-3 2.24E-5 Release.
Via The BV-2 Waste Gas Storage Vault Vent
- Alert Setpoint from Section 2.1.2 Fraction Of Site Limiting Dose Rate.
2-13 ISSUE 3
BV-1 cnd 2 ODCM The setpoints were determined using the following conditions:
}.
- Source terms given in Table 2.1-1b. These gaseous source terms vere
.v' derived from Stone & Vebster computer codes GASlBB (which is similar to the NRC CODE GALE, NUREG-0017) and DRAGON 4 (for the containment vacuum pump sources). Table 2.1-lb does not include particulates and iodines, which-are not used in site noble gas dose rate calculations.
The Containment Building Purge radionuclide mix was utilized for the purposes of determining an alarm setpoint for the Ventilation Vent on the basis of the proximity of the contiguous areas. The Decontamination Building and Condensate Polishing Building ventilation exhaust are not expected to be radioactive. However, for purposes of determining an alarm setpoint, it is conservatively.
assumed that Xe-133 is in the ventilation exhaust at concentrations that would result in the appropriate dose rate limits. The Vaste Gas ,
Storage Vault ventilation exhaust is also not normally radioactive. J However, the monitor alarm setpoint is based on the assumption that !
the ventilation exhaust radionuclide spectrum is similar to the ]
gaseous inventory in the system housed by the vaste gas storage j vault. This spectrum is listed in Table 2.1-lb under Gaseous Veste !
System. _
' Onsite meteorological data for the period January 1, 1976 through I' December 31, 1980.
- Discharge flow rate of 23,700 cfm for the BV-2 Ventilation Vent (Continuous).
,m ,
)
- Discharge flow rete of 53,700 cfm for the BV-2 Ventilation Vent l (Batch release of containment purge). ]
- Discharge flow rate of 59,000 cfm for the BV-2 Containment Vent (Both I continuous and batch release of containment purge). !
- Discharge flow rate of 30,556 cfm for the BV-2 Condensate Polishing i Building Vent.
o
- Discharge flow rate of 12,400 cfm for the BV-2 Decontreination Building Vent.
- Discharge flow rate of 2,000 cfm for the BV-2 Vaste Gas Storage Vault Vent.
The calculation method given in Sections 2.1.2.1.1 through 2.1.2.1.7 was used to derive the alarm setpoints for the Ventilation Vent Gas Monitor (2HVS-R0101B), Containment Vent Gas Monitor (2HVS*R0109B),
Condensate Polishing Building Vent Gas Monitor (2HVL-RQ112B),
Decontamination Building Vet Gas Monitor (2RM0-R0301B), and Vaste Gas Storage Vault Vent Gas Monitor (2RM0-R0303B) during the following operational conditions:
- Continuous release via the BV-2 Ventilation Vent.
/^'N
- Continuous release via the BV-2 Containment Vent.
(-. /
2-14 ISSUE 3
'BV-1 cnd 2 ODCM
- Batch release of BV-2 Containment Purge via the BV-2 Ver.tilation Vent.
Batch release of BV-2 Containment Purge via the BV-2 Containment Vent.
- Continuous release via the BV-2 Condensate Polishing Building Vent.
- Continuous release via the BV-2 Decontamination Building Vent.
- Continuous release via the BV-2 Vaste Gas Storage Vault Vent.
2.1.2.1.1 BV-2 Mix Radionuclides The " mix" (noble gas radionuclides and composition) of the gaseous effluent was determined as follows:
- a. The gaseous source terms that are representative of the " mix" of the gaseous effluent vere selected based on the relative stream composition and volumetric flovrate. Gaseous source terms are the radioactivity of the noble gas radionuclides in the effluent.
Gaseous source terms can be obtained from Table 2.1-1b.
- b. The fraction of the total radioactivity in the gaseous effluent comprised of noble gas radionuclide "i" (S ) for each individual 4
noble gas radionuclide in the gaseous effluent was determined by:
A S i [2.1(2)-1) g fA where:
Ag - The radioactivity concentration of noble gas radionuclide "i" in the gaseous effluent from Table 2.1-1b.
2.1.2.1.2 BV-2 Haximum Acceptable Release Rate (Vhole Body Exposure)
The maximutt acceptable total release rate (uCi/sec) of all noble gas radionuclides in the gaseous effluent (O ) tbased upon the whole body exposure limit was calculated by:
500 [2.1(2)-2]
0* " (X/0) I Kg Sg -
i where:
(X/0)" - The highest calculated annual average relative concentration of effluents released via the Ventilation Vent for any area at or beyond3the unrestricted area boundary for all sectors (sec/m ) from Table 2.2-5.
- 1.03E-4 sec/m for continuous releases.
O 2-15 ISSUE 3
BV-1 cnd 2 ODCM (X/q)" = The short term relative concentration of effluents 7 s releas2d via the Ventilation Vent for any area at or
- i. I beyond3 the unrestricted area boundary for all sectors
'v' (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 area at or beyond the unrestricted area boundary for all sectors (sec/m )3 from Table 2.2-4.
- 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 3 the unrestricted area boundary for all sectors (sec/m ) from Table 2.3-35.
3
- 3.08E-4 sec/m for batch release of containment purge.
(X/0)CP - The highest calculated annual average relative concentration of effluents released via the Condensate Polishing Building Vent for any area at or beyond 3the unrestricted area boundary for all sectors (sec/m ) from Table 2.2-10.
3
= 7.35E-5 sec/m for continuous releases.
- b (X/0)dy - 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/m for continuous releases.
(%/0)" - The highest calculated annual average relative concentration of effluents released via the Waste Gas Storage Vault Vent for any area at or beyond the 3 unrestricted area boundary for all sectors (sec/m )
from Tnble 2.2-9.
- 9.24E-5 sec/m3 for continuous releases.
Kg - The total whole body dose factor due to gamma 3 emissions from noble gas radionuclide "i" (mrem / year /uCi/m )
from Table 2.2-11.
S g
= From equation [2.l(2)-1].
2-16 ISSUE 3
BV-1 r_nd 2 ODCM 2.1.2.1.3 BV-2 Maximum Acceptable Release Rate (Skin Exposure)
O was also determined based upon the skin exposure limit by:
t 0 3000 [2.1(2)-3]
E " (X/0) I (Lg + 1.1Mg ) Si i
vhere:
Lg = The skin dose factor due to beta emissions from noble gas radionu:lide "i"(mrem / year /uci/m3 ) from Table 2.2-11.
Hg - The air dose factor due to gamma 3emissions from noble gas radionuclide "i"(mrad / year /uci/m ) from Table 2.2-11.
1.1 = The ratio of the tissue to air absorption coefficients over the energy range of the photons of interest, (mrem / mrad).
(X/0) = Same as in Section 2.1.2.1.2. .
2.1.2.1.4 BV-2 Maximum Acceptable Release Rate (Individual Radionuclide)
The maximum acceptable release rate (uci/sec) of noble gas radionuclide "i" in the gaseous effluent (0 3 ) for each noble gas radionuclide in the gaseous effluent was determined by:
Og=Sg O [ 2'. l(2 )-4 ]
t (NOTE: Use the lover of the Qt values obtained in Section 2.1.2.1.2 and 2.1.2.1.3.)
2.1.2.1.5 BV-2 Maximum Acceptable Concentrations (Individual Radionuclide)
The maximum acceptable radioactivity concentration (uci/cc) of noble gas radionuclide "i" in the gaseous effluent (C ) for each individual 4
noble gas radionuclide in the gaseous effluent Oas determined by:
C g, 2.12E-3 0 1 [2.1(2)-5]
F vhere:
F = The maximum acceptable effluent flow rate at the point of release (cfm) as listed in Section 2.1.2.1.
3 2.12E-3 = Unit conversion factor (60 sec/ min x 3.53E-5 ft fcc),
i O
2-17 ISSUE 3
BV.-l cnd -2 ODCM 2.1.2.1.6- BV-2 Monitor' Count Rate The calculated monitorfcount rate (nepm) above background attributed
.- to.the noble gas radionuclide (C.R.) was determined by:
C.R. - I Cg Eg [2.1(2)-6)]
i where '
E g'= The' detection efficiency of the. monitor for noble gas radionuclide "i" (cpm /uci/cc) from Table 2.1-2b.
2.1.2.1.7 BV-2 Monitor Setpoints The monitor alarm setpoints .above background vere determined as.
follows:
- a. The monitor HIGH Alarm Setpoint above background (uci/cc) was determined by:
[2.1(2)-7]
HSP = 0.30E C.R.
g .,y,
- b. The monitor ALERT Alarm Setpoint above background (uCi/cc) was determined by:
[2.1(2)-8j ggp ,.FR x C.R.
E g ,y, where FR = Fraction of: limiting dose rate for the respective radiation monitor (from Section 2.1.2).
E g *** - The C.R. of equation [2.1(2)-6] divided by the sum of the Cg for the respective mix.
2-18 ISSUE 3
BV-1 cnd 2 ODCM 2.1.2.2 BV-2 Setpoint Determination Based On Analysis Prior To Release (Ground Releases)
When the setpoints established using "the calculated mix" do not 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 accepte51e discharge flow rate and the associated HIGH Alarm Setpoint basuu 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) EK gC g i
where:
1.06 - 500 mrem /yr x 2.12E-3 500 mrem /yr = dose rate limit, whole body exposure 2.12E-3 = unit conversion factor 3
= (60 sec/ min x 3.53E-5 ft /ce)
S - Percent of site dose rate released via this pathvay. Up to 60% of the site dose rate is permissible for one release point under the alerm 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 ODCH Appendix C CONTROL 3.11.2.1.a where the dose rate for a containment purge may be averaged over a time period not to exceed 960 minutes. (As containment air volume change time period is 60 minutes; T = 960/60 = 16). See Reference 2.2.4.
O 2-19 ISSUE .*
BV-1 cnd 2 ODCM (X/q)** - The highest calculated short term relative s
concentration of effluents released via the Ventilation Vent for any area at or beyond3the unrestricted aren
-('*) boundary for all sectors (sec/m ) from Table 2.3-36.
- 3.32E-4 sec/m (X/q)CV - of Theeffluents highest calculated short term relative concentration 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 (uCi/ce) as determined by analysis of the gas to be released. )
- b. The flow rate (f) is also determined based upon the skin exposure ;
limit as follows: 1 6.36 S T [2.1(2)-18]
g * (X/q) E (Lg + 1.1H g) Cg i
7 -m t>
) vhere: j i
6.36 .- 3000 mrem /yr x 2.12E-3 3000 mrem /yr - dose rate limit, skin exposure 2.12E-3 = unit conversion factor 3 ^
- (60 sec/ min x 3.53E-5 ft /cc)
- The skin dose factor due to beta emissions 3 from I
L i
noble gas radionuclide "i" (mrem / year /uci/m ) from i Table 2.2-11.
Mg - The air dose factor due to gamma emissions 3 f#
- l noble gas radionuclide "i" (mrad / year /uci/m ) from l 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.h). The actual purge flow rate (cfm) must be .
maintained at or below this calculated (f) value or the discharge {
i cannot be made from the vent.
p l
2-20 ISSUE 3
BV-1 cnd 2 ODCH 2.1.2.2.2 BV-2 Honitor Setpoints The monitor alarm setpoints above background are determined as follows:
- a. The calculated monitor HIGH Alarm Setpoint above background (net uCi/ce) attributed to the noble gas radionuclides is determined by:
fEC gE g [2.1(2)-19]
HSP =
F' Ei ave where:
f = The maximum acceptable containment purge flow rate (cfm) determined in Section 2.1.2.2.1.
F' = The maximum actual or design effluent flow rate (cfm) at the point of release.
~
- 53,700 cfm (BV-2 Ventilation Vent -- design)
= 59,000 cfm (BV-2 Containment Vent -- design)
C - The undiluted radioactivity concentration of noble gas 3
radionuclide "i" in the gaseous source (uci/cc) as determined by analysis of the gas to be released.
Eg - The detection efficiency of the monitor for noble gas radionuelide "i" (cpm /uci/cc) from Table 2.1-2b.
Ei ave = The C.R. of equation [2.1(2)-6] divided by the sum of the Cg for the respective mix.
NOTE: To enable maintaining a constant conversion factor from cpm to uCi/cc in the Digital Radiation Monitoring System software, the " calculated mix" is used rather than the analysis mix to calculate E i ave above. This does not cause any change in the function of the monitor setpoint to properly control dose rate. However, the monitor indicated uCi/cc value may differ from the actual value.
- b. When a HIGH Alarm Setpoint has been calculated according to this section, the monitor ALERT Alarm Setpoint above background (net uCi/cc) is determined as follows:
ASP = BSP x 0.33 [2.1(2)-20]
O 2-21 ISSUE 3
L _BV-1.tnd 2 ODCM
~
2.1.3 _BV-1/2 Monitor Alarm Setpoint Determination
' 'd'
- Q '
.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 i Vent Releases (Elevated Releases)
The calculated; monitor count rate above background-(C.R.), in nepm, the' monitor HIGH-HIGH alarm setpoint- above background (HHSP), _and the monitor HIGH alarm setpoint above background (HSP) for each operational condition are as'follows:
'BV-2'AND ALARM SETPOINTS FOR ELEVATED RELEASES cpm ABOVE BACKGROUND (P)P'RIMARY* 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 l J(jf)' ' Batch Release Of BV-2 Decay (P)RM-GV-108B 2.11E5 6.33E4 2.11E4 (A)RM-GV-109(5) 7.75E6 2.32E6 7.75E5
~
Tanks
- Batch Release Of BV-1 (P)RM-GV-108B 5.55E6 1.67E6 5.55ES 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:
- 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.
( -y
.w' l
2-22 ISSUE 3 l
1
BV-1 cnd 2 ODCM ;
2.1.3.1.1 BV-1/2 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 evaluated. Gaseous source terms are the radioactivity of the noble gas radionuclides in the effluent.
The gaseous source terms can be obtained from Tables 2.1-la. and 2.1-1b.
- b. The fraction of the total radioactivity in the gaseous effluent comprised by noble gas radionuclide "i" (S3 ) for each individual noble gas radionuclide in the gaseous effluent vas calculated-by:
A S i [2.1-9]
g,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 50 [2.1.10]
t = g y,03, i
where:
Vg - 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 3000 [2.1-11]
0* " E [Lg (X/0)py+ 1.1Bg]S3 0
2-23 ISSUE 3
, BV-1 end 2.0DCM
-n 1
- where:
hk Lg - The skin dose factor due to beta' emissions I#""
A noble gasLradionuclide "i"(mrem / year /uci/m3 ) from Table 2.2-11.
p (X/0)Pv-- The highest calcialated annual average relative L'. concentration of effluents. releases via the Process Vent for:any area at or,beyond the unrestricted-area 3
y : boundary for all sectors (sec/m )cfrom Table =2.2-6.-
I ,
- 2.31E-6 seb/m b n -(X/q)PV-- released The.short term relative concentration of effluents L-
, via'the Process Vent-for any ' area at'or, E .beyond3 the unrestricted area boundary for all sectors (sec/m )-from Table.2.3-38.
- 1.07E-5 sec/m3.
-i Bg = The constant for long. term releases (greater than:
l 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.
c2.1.3.1 4 BV-1/2 Maximum Acceptable Release Rate (Individual Radionuclide)
The maximum acceptable . release ' rate (uci/sec) of noble gas-
, b=
e radionuclide "i" in,.the gaseous effluent (0 for'each individual
.J
- noblegas'radionuclide-in.thegaseous'effluentha)sdeterminedby:
[2.1-12]-
~
Og - S[ Ot-
'(NOTE: Use the lower of.the 0 t-values obtained in Section 2.1.3.1.2 and'2 l.3.1.3.)-
l2.1.3.1.5 BV-1/2 Maximum Acceptable Concentrations ~~(Individual Radionuclide)
- The maximum acceptable radioactivity . concentration (uci/ce) of noble.
, gas.radionuclide.*i" in the gaseour effluent (C F for each-individual noble gas radionuclide in=the gaseous effluent 1has determined byr.
C g, 2.12E-3 0 1 [2.1-13]
F 4 l
where:
~
3 2.12E Unit conversion factor (60 sec/ min x 3.53E-5 ft /ce).
b' -F' = The maximum acceptable effluent flow rate at the point q i - of release (cfm).
L
= 1450 cfm (BV-1/2 Process Vent) :
,0
- V 1 .
2-24 ISSUE 3 -!
r '
r s
l
BV-1 Cnd 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. - I Cf Eg [2.1-14]
i vhere:
E g = The detection efficiency of the monitor for nobli 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 vere determined as follows:
- a. The monitor HIGH-HIGH Alarm Setpoint above background (nepm) was determined by:
HHSP = 0.30 C.R. [2.1-15]
- b. The monitor HIGH Alarm Setpoint above background (nepm) was determined by:
HSP = 0.10 C.R. [2.1-16]
O O
2-25 ISSUE 3
BV-1 cnd 2 ODCM 2.1.3.2 BV-1/2 Setpoint Determination Based On Analysis Prior To Release For g Process Vent Releases (Elevated Releases)
! )
'd 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 Waste Gas Monitor (RM-GV-108B) or alternate (RM-GV-109 CH #5) during the following operational conditions:
- Continuous release via the BV-1/2 Process Vent.
- Batch release of BV-1 or BV-2 Vaste Gas Decay Tank via the BV-1/2 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 flov' rate for the release from the Process Vent for the analyzed mix.
- a. The maximum acceptable gaseous discharge flow rate (f) from the Process Vent (cfm) based upon the whole body exposure limit is determined by:
i'.
t / f " 1.06 [2.1-21]
IV SC-g g i
vhere:
1.06 - 500 mrem /yr x 2.12E-3 J 500 mrem /yr - dose rate limit, whole body expo;ure 2.12E-3 - unit conversion factor 3
- (60 sec/ min x 3.53E-5 ft /cc)
S - Percent of site dose rate released via this pathvay. Up to I 60% of the site dose rate is permissible for one release I point under the alarm setpoint rules of Section 2.1.3. To l exceed 60% of the site limit from one release point, the l remaining release point limits must be correspondingly !
reduced or secured to provide the necessary margin below the site dose rate limit. j Vg - The constant for noble gas radionuclide "i" accounting for the gamma radiation from the elevated plume ;
(mrem / year /uCi/sec) from Table 2.2-12. i Cg - The undiluted radioactivity concentration of noble gas 1 radionuclide "i" in the gaseous source (uci/cc) as
/~N determined by analysis of the gas to be released.
!' ()
2-26 ISSUE 3 l
BV-1 Cnd 2 ODCM
- b. Based upon the skin exposure limit, (f) is calculated by:
6.36 S [2.1-22]
g , I [Lg (X/0)py + 1.1Bg] C g where:
6.36 - 3000 mrem /yr x 2.12E-3 3000 mrem /yr = dose rate limit, skin exposure 2.12E-3 = unit conversion factor 3
= (60 sec/ min x 3.53E-5 ft /cc)
Lg - The skin dose factor due to beta emissions 3from-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 released via the Process Vent for any area at or beyond the unrestricted area boundary for all sectors (sec/m )3 ffom Table 2.2-6.
- 2.31E-6 sec/m (X/q)pv = The short term relative concentration of' effluents released via the Process Vent for any area at or beyond 3 the unrestricted area boundary for all sectors (sec/m ) from Table 2.3-38.
- 1.07E-5 sec/m 3 Bg = The constant for long-term releases (greater than 500 hrs / year) for noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume (mrad / year /uci/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:
fEC gE g [2.1-23]
HHSP = '
F 2-27 ISSUE 3 l
_BV-1 cnd 2 ODCH l
where:
7 ,,
f '= The maximum acceptable gaseous discharge flow rate (cfm)
' .. ('v) 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)
Cg = The undiluted radioactivity of noble gas radionuclide "i" in the gaseous source (uci/cc) as determined by analysis of the gas to be released.
Eg = The detection efficiency of the respective monitor (RM-GW-108B) or (RM-GV-109 CH 5) for noble gas radionuelide "i" (cpm /uci/cc) from Table 2.1-2a and 2.1-2b.
- b. When a HIGH-HIGH Alarm Setpoint has been calculated according to this rection the monitor HIGH Alarm setpoint above background (nepm) is determined by: .
ESP = HHSP x 0.33 [2.1-24]
m
'y.
1 i
2-28 ISSUE 3 i
BV-1 cnd 2 ODCM TABLE 2.1-in BV-1 RADIONUCLIDE MIX FOR GASEOUS EFFLUENTS (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 VENTTLf.T70N VENTILATION AIR EJECTOR PUMPS SYSTEM Short Terni Long Term Long Term Long Term Long Term Short Term Kr-83m 2.2E-02 4.2E-01 3.9E-05 2.7E-01 3.7E-04 0.0 Kr-85m 1.5E-01 1.9E+00 .1.7E-04 1.2E+00 3.9E-03 7.3E-02 Kr-85 6.1E+01 2.5E+00 2.3E-04 1.6E+00 7.2E-01 2.3E+02 Kr-87 5.4E-02 1.3E+00 1.1E-04 8.2E-01 7.8E-04 0.0 Kr-88 2.4E-01 3.8E+00 3.5E-04 2.4E+00 ~ 5.0E-03 0.0 Kr-89 4.7E-04 1.2E-01 1.1E-05 7.7E-02 3.1E-06 0.0 ,
Xe-131m 7.4E-01 1.3E-01 1.2E-05 8.0E-02 1.3E-02 1.3E+00 Xe-133m 8.9E-01 8.9E-01 8.1E-05 5.6E-01 2.2E-02 0.0 Xe-133 8.9E+01 3.6E+01 3.4E-03 2.3E+01 1.9E-00 2.3E+01 Xe-135m 4.5E-03 3.2E-01 2.9E-05 '2.0E-01 4.4E-05 0.0 Xe-135 7.0E-01 4.5E+00 4.2E-04 2.8E+00 1.9E-02 0.0 Xe-137 1.0E-03 2.1E-01 2.1E-05 1.3E-01 6.3E-06' O.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 (2.1.8) l 2-29 ISSUE 3 I
BV-1.cnd 2 ODCM TABLE 2.1-1b
~3 BV-2 RADIONUCLIDE MIX FOR GASEOUS EFFLUENTS (u )- (Ci/yr)**
TURBINE VENTILATION CONTAINMENT BUILDING VENT VENT VENT PROCESS VENT Long Term And AUXILIARY TURBINE'- MAIN CONTAINMENT GASEOUS
' CONTAINMENT BUILDING BUILDING CONDENSER / VACUUM VASTE NUCLIDE BUILDING VENTILATION VENTILATION AIR EJECTOR PUMPS SYSTEM Short Term Long Term Long Term Long Term Long Term Short Term Kr-83m '4.0E-05 4.2E-01 3.9E-05 '2.7E-01 3.7E-04 0.0 Kr-85m l'.4E-02 1.9E+00 1.7E-04 1.2E+00 3.9E-03 1.2E-02 Kr-85 6.1E+01 2.5E+00 2.3E-04 1.6E+00 7.2E-01 2.3E+02 Kr-87 5.3E-06 1.3E+00 1.1E-04 8.2E-01 7.8E-04 0.0 Kr-88 4.1E-03 3.8E+00 3.5E-04 2.4E+00 5.0E-03 0.0 Kr-89 0.0 1.2E-01 1.1E-05 7.7E-02 ~ 3.1E-06. 0.0 Xe-131m 7.2E-01 1.3E-01 1.2E-05 8.0E-02 1.3E-02 8.3E-01 Xe-133m 7.6E-01 8.9E-01 8.1E-05 5.6E-01 2.2E-02 0.0 Xe-133 8.4E+01 3.6E+01 3.4E-03 2.3E+01 1.9E-00 8.2E+00 Xe-135m 0.0 3.2E-01 2.9E-05 2.0E-01 4.4E-05 0.0 Xe-135 2.4E-01 4.5E+00 4.2E-04 2.8E+00 1.9E-02 0.0 Xe-137 0.0 2.1E-01 2.1E-05 1.3E-01 6.3E-06 0.0-
- (,,
f)s Xe-138 0.0 1.1E+00 9.7E-05 6.6E-01 0.0 1.2E-04 0.0 0.0 0.0
'Ar-41 2.5E+01 0.0 0.0
- Containment can be purged via Ventilation Vent, Containment Vent, or Process Vent
(,-<) ** Reference (2.2.3)
's / *** Reference (2.2.5) J 2-30 ISSUE 3 l
I
1 BV-1 cnd 2 ODCM TABLE 2.1-2e BV-1 MONITOR DETECTOR EFFICIENCIES (cpm /uCi/ce, CORRECTED)*
VENTILATION PROCESS CONTAINMENT NUCLIDE VENT VENT VENT PRIMARY ALTERNAIE PRIMARY ALTERNATE PRIMARY ALTERNATE MONITOR MONITOR MONITOR MONITOR MONITOR MONITOR RM-VS-101B RM-VS-109 RM-GV-108B RM-GV-109 RM-VS-107B RM-VS-110 Channel 5 Channel 5 Channel 5 Kr-83m -- -- -- --
Kr-85m 9.80 E7 2.39 E7' 9.00 E7 2.43 E7 5.16 E7 2.57 E7
'Kr-85 3.88 ES 2.47 E7 3.56 E3 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 /.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)*
[
VASTE GAS CONDENSATE STORAGE DECON POLISHING VENTILATION l CONTAINMENT VAULT- BUILDING BUILDING
'NUCLIDE VENT VENT VENT- VENT- VENT 2HVS-RQ16TII 2HVS-R0109B L 2RM0-R0303B 2RMO-R0301B 2HVL-RQ112B l lKr-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 LKr-89 3.72E7 8.73E7 3.72E7- 3.72E7 3.72E7
- s. Kr-90 3.86E7 8.80E7 3.86E7 3.86E7 3.86E7
'I Xe-131m 2.44E7 4.61E4 2'44E7 . 2.44E7 2.44E7 4 '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 O
/
.e
- Re'ference (2.2.1) 2-32 ISSUE 3 p
BV-1 cnd 2 ODCH REFERENCES BV-1 GASEOUS EFFLUENT MONITOR SETPOINTS O
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. EhS-ATL-87-026 ,
Letter NDISHP 776, dated February 12, 1988, BVPS-1 OLCM Table 2.2-2, 2.1.7 Appendix B 2.1.8 Gaseous Releases From Containment Vacuum Pumps; Stone and Webster Calculation No. UR(B)-262 O
REFERENCES BV-2 GASE0US EFFLUENT HONITOR SETPOINTS 2.2.1 Unit 2 DRMS Isotopic Efficiencies; DLCo Calculation Package No.
ERS-SFL-86-026 2.2.2 Unit 1/ Unit 2 ODCM Gaseous Alarm Setpoint Determinations; DLCo Calculation Package No. ERS-HHM-87-014 2.2.3 " Beaver Valley Power Station, Unit 2 FSAR"; Table 11.3-2 2.2.4 BVPS-1 and BVPS-2 ODCM T Factor Justification; DLCo Calculation Package No. ERS-ATL-87-026 2.2.5 Gaseous Releases From Containment Vacuum Pumps; Stone and Webster Calculation No. UR(B)-262 O
2-33 ISSUE 3
BV-1 and 2 ODCM 2.2 Compliance With 10 CFR 20 Dose Rate Limits (0DCM Appendix C CONTROL
,3 3.11.2.1)
! l v' 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 r;round 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 3.11.2.1.a.
E [Vgg o , + K (X/0)y g Ogy) < 500 mrem /yr [2.2-1]
i I [Lg(X/0), + 1.1B f] Og + [Lg + 1.1Mg ](X/0)y O gy 3 3000 mrem /yr 1
[2.2-2]
where:
Kg - The total body dose factor due to gamma emissions for each identified noble gas radionuclide "i", mrem / year /uci/m3 .
Lg = The skin dose factor due to beta emissions for each. 3
. ,m identified noble gas radionuclide "i", mrem / year /uCi/m .
I
' ]
= The air dose factor due to gamma emissions for each Mg identified noble gas radionuclide "i", mrad / year /uci/m3.
Vg - The constant for each identified noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume, mrem / year /uCi/sec.
By - The constant for long-term releases (greater than 500 hrs /
year) for each identified noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume, mrad / year /uCi/sec.
1.1 - The ratio of the tissue to air absorption coefficients over the energy range of the photon of interest, mrem / mrad.
O - The release rate of noble gas radionuclide "i" in gaseous is effluents from free-standing stack, uCi/sec.
l O* g - The release rate of noble gas radionuclide "i" in gaseous effluents from all vent releases, uCi/sec.
(X/0)s = The highest calculated annual average relative concentration for any area at or beyond the3 unrestricted area boundary for :
elevated releases (sec/m ). )
t p' !
J 2-34 ISSUE 3 L
BV-1 cnd 2 ODCH
-)
1 (X/0)y - The highest calculated annual average relative concentration for any area at or beyond the 3unrestricted area boundary for ground level releases (sec/m ).
At the Beaver Valley site gaseous releases may occur from:
- 1. The Containment Vents atop the Containment Domes
- 2. The Ventilation Vents atop the Auxiliary Buildings
- 3. The Process Vent atop the BV-1 Cooling Tower
'4. The Turbine Building Vents
- 5. The BV-2 Condensate Polishing Building Vent
- 6. The BV-2 Decontamination Building Vent
- 7. The BV-2 Vaste Gas Storage Vault Vent Effluent from the Containment Vents are assumed ground level in nature.
At BV-1 the source of these releases is the Supplementary Leak Collection and Release System (SLCRS). At BV-2 the source of these releases is normal Auxiliary Building Ventilation. It is also possible to release Containment Purges from these vents. The Ventilation Vent Releases are ground level in nature. At BV-1 the sources of these releases are Containment Purges and normal Auxiliary Building Ventilation. At BV-2 the sources of these releases are 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.
Noble gas releases may normally occur from release points 1 through 3 above. To show compliance with the site limits of ODCM Appendix C CONTROL 3.ll.2.1.a, Expressions [2.2-1]-and [2.2-2] are nov expressed in terms of the actual _ release points for the site. Note that the expressions for release points 4, 5, 6, and 7 are included for use if radioactive releases via these release points are identified in the future.
For The Total Body Dose Rate:
EV0 gg +EKg g [(X/0)cy O g + (X/0)yy O g + (X76)tv O i tvl + (X/0)cy i pv cyl vvl Og +I I tv Oi '
dv S dv2 ev2 vv2 tv2 CP i cp2 (X/0)yy 0 3 ] f 500 mrem /yr [2,2-3]
2 O
2-35 ISSUE 3 L- - _-
,-_BV-1 cnd 2 ODCM '
E For The Skin Dose Rate:
(%;. I [L (X/0)py i \+ 1.1Bgl_0 g + I g[ y + 1.1M gl [(X/0)cv O g py evl "
.- :)l t 0g
+ (X/0)'tv O g tvl *( }CV i cv2 ( }"" I vv2 + ^'
}tv O g tv2 (X/0)cp'og + (X/0)dv o g dv2 + W O)yy Og ] 1 3000 mrem /yr cp2 vv2' [2.2-4J where:
Og - Release rate of radionuclide "i" from the BV-1/2 Process pv Vent,'uCi/sec.
Op = Release rate of radionuclide "i" from the BV-1 Containment evl Vent, uCi/sec.
0g - Release rate of radionuclide "i" from the BV-2 Containment L cv2 Vent, uCi/sec.
l- Og - Release rate of radionuclide "i" from the BV-1 Ventilation vvl Vent, uCi/sec.
Og = Release rate of radionuclide "i" from the BV-2 Ventilation vv2 Vent, uCi/sec.
p-
't og = Release rate of radionuclide "i"'from the BV-1 Turbine
!p tvl 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.
L Og = Release rate of radionuclide "i" from the BV-2 dv2 Decontamination Building Vent, uCi/sec.
Og = Release rate of radionuclide "i" from'the BV-2 Vaste Gas vv2 Storage Vault Vent, uCi/sec.
(X/0)Py - Highest calculated annual average relative 3concentration
.for releases from the Process Vent,- sec/m (X/0),y = Highest calculated annual average relative3 c neentration for releases-from the Containment Vent, sec/m (X/0)yy = Highest calculated annual average relative3 c neentration for
. releases from the Ventilation Vent, sec/m (X/0)tv = Highest calculated annual average relative 3concentration for j releases for the Turbine Building Vent, sec/m ;
k_/ ,
2-36 ISSUE 3 I
BV-1 cnd 2 ODCH i
(X/0)cp = Highest calculated arnual average relative concentration for releases f r the BV-2 Condensate Polishing Building vent, sec/m 3 (X/0)dy - Highest calculated annual average relative concentration 3 I#
releases.for the BV-2 Decontamin8 tion Building Vent, sec/m .
(X/0)y, - Highest calculated annual average relative concentration3 for releases for the BV-2 Vaste Gas Storage Vault Vent, sec/m .
No~et that the release rate for a containment purge is based on an averaged release rate in uC1/see for the entire purge (not to exceed 960 min in accordance vith ODCH 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 3.11.2.14 s 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 +EKy [9.24E-5 Og + 1.03E-4 O g + 7.35E-5 O g + 9.24E-5 i pv i evi vv1 tv1 0 + 1.03E-4 O g + 7.35E-5 O g + 9.24E-5 O i I dv2 vv2 7.35E-5 O g ] < 500 mrem /yr [2.2-5)
For The Skin Dose Rate:
E [7.0E-10 Lg + 1.1Bg] Og + E [L 3 + 1.1M'g ] [9.24E-5 Og + 1.03E-4 i pv i cv1 Og + 7.35E-5 O g + 9.24E-5 O g + 1.03E-4 0 + 7.35E-5 O g +
1 9.24E-5 0 I + 9.24E-5 0 I + 7.35E-5 0 2 ] < 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/0's from Tables 2.2-4 through 2.2-10 for this location, Expressions [2.2-3 and 2.2-4] become:
l l
2-37 ISSUE 3 l >
l i
- 1
'BV-1 cnd-2 ODCM For The Total Body Dose Rate:
i 7 c, --
IV0 + I K g-[3.95E-6 O g + 4.99E-6 O g
(-) ~ 4 i
gg pv i- cv1 vv1
+ 4.26E-6 O g tv1 4 3.95E-6 Og +4 + 4.26E-6 0 + 3.95E-6 O g + 3.95E-6 0 + i I
ev2- vv7 4.26E-6 0 ] $ 500 mrem /yr [2.2-7]
For The Skin' Dose Rates y E [2.31E-6 Lg + 1.1Bg ] 03 + E [L g + 1.1Mg ] [3.95E-6 Og + 4.99E-6 pv evi i i Og + 3.95E-6 O g + 4.99E-6 O g .
+ 4.26E-6 O g + 4.26E-6 O g +
v2 3.95E-6 O g dv
+MMq + W4 g vV cp .
[2.2-8]
The' determination .of controlling' location for implementation of ODCM )
Appendix C CONTROL 3.11.2.1.a for noble gases is a function of the following parameters: -
- 1. Radionuclide mix and their isotopic release rate gg 2. Release mede
- 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 Webster Engineering i Corporation computer code GAS 1BB vhich is similar to the NRC GALE code. l Inputs were based on operating modes of the respective plants. The code 1 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 utilizeo in the equations for implementation of ODCM Appendix C CONTROL 3.1'.E.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 j average (X/0) values for the Process Vent, Containment Vent, Ventilation Vent, Turbine Building Vent, and if applicable for BV-2, Decontamination f ,
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 !
T'i Appendix A. !
O 2-38 ISSUE 3 I l
l I
BV-1 cnd 2 ODCH I For release modes 1, 2, and 3, dose calculations were performed using the highest calculated site boundary X/0 values applicable to the release points involved and the projected radionuclide mix applicable to the release source. In that a simultaneous, continuous elevated release could contribute to the dose at a given location, the selection of the two highest sector X/0 values at the site boundary considered this contribution. From these results, the distanea and sector associated with the highest calculated site boundary dose vere selected as the controlling location.
For Modes 1, 2, and 3 the controlling location is 0.35 miles NV. In Mode 1, the dominant release is the Auxiliary Building Ventilation (BV-1 '
Ventilation Vent and BV-2 . Containment Vent). In Modes 2 and 3, the dominant release is a containment Purge from the respective Ventilation Vent or Containment Vent.
For release Mode 4, a similar evaluation was performed. Long-term annual average X/0 values were calculated at the mid-point of the 10 standard distances listed in Table 2.2-4 through 2.2-10. In that a simultaneous, ground level release could contribute to the dose at a given location, the selection of the two highest X/0 values at the-controlling distance considered this contribution. Since the two maximum X/0 values occurred in the 0.5 - 1.0 mile radial band, the controlling distance was selected at 0.75 miles. From the calculated dose results, the controlling sector was shown to be North. In this mode, the dominant release is a Containment Purge via the Process Vent. Neither of the controlling receptor locations are presently inhabited.
Values for K , L , and M, which vere used in the determination of the controllinghecehtorlocakionandwhicharetobeusedin Expressions [2.2-5] through [2.2-8] to show compliance with ODCH Appendix C CONTROL 3.11.2.1.2, are presented in Table 2.2-11. Values taken from Table B-1 of NRC Regulatory Guide 1 l were multiplied by 1E6 to convert picoeuries~1 109, Revisionto microcuries"y ,for use in Table 2.2-11.
Values for V, and B for the finite plume model can be expressed as shown in Equation [2.I2-9] and [2.2-10). Values were calculated using the NRC code RABFIN at the site boundary location which would receive the highest total' dose from combined Process Vent, Ventilation Vent, and Turbine Building Vent, and Containment Vent releases. These values are presented in Table 2.2-12 and calculated from the following relation:
BK IIIjk1jk yg Au, Ey g
f I
[2.2-9]
u j
vhere: i I = The results of numerical integration over the plume spatial f distribution of the airborne activity as defined by the !
meteorological condition of vind speed (u ) and atmospheric i stability class "k" for a particular vind 3direction.
O 2-39 ISSUE 3
L >
L '- .I
.BV-1 and 2 ODCM
.K - A numerical constant representing unit conversions.
3
- (260 mrad)(radians)'(m ) (transformation). 16 sectors
, .(sec)(Mev)(Ci) 2n radians 1E-6 C1 3.15E7 sec uCi yr~
3
- l. , - 2.1E4 mrad.(m ) (transformation)/yr(Mev)(uci).
[. ,
.r d - The distance from the release point to the receptor 1cention, meters.
u) - The mean vind speed assigned to the "j" th wind speed class, l meters /sec.
l' fjk'.= The joint frequency of . occurrence of the "j" th vind speed class and kth stability class (dimensionless).
Ayg - The' number of photons of energy' corresponding to the "1" th energy group emitted per transforrration of the "i" th radionuclide, number / transformation.
Ey - The energy assigned to the "1" th energy group, Mev..
u, - The energy ,y absorption coefficient in air for photon energy q ,
-Hy , meters 1 The V -factor is' computed with conversion from air dose to tissue depth dose,Ithun K I I I .Ijk ygA u, Ey I,_-uT d [2.2-10]
.yi ,y,y rd ') 'l "j-where:
-uT :
- The tissue energy 2 absorption coefficient for photons of energy Ey,, em /gm.
T d " The . tissue 2density thickness taken to represent the total body dose (5gm/cm ).
4 1.1'- The ratio of the tissue to air absorption coefficients over the energy range of photons of interest, mrem / mrad.
i
,g
./ l l
(3)[
2.-40 ISSUE 3
- (-
l.
BV-1 Cnd 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 Jives greater than 8 days released in gaseous effluents from the site shall be limited to 1,500 mrem /yr to any organ. Based upon NUREG-0133, the following basic expression is used to show compliance with ODCH Appendix C CONTROL 3.11.2.1.b:
IPh [(X/0), O , + g (X/0)y Ogy] $ 1,500 mrem /yr [2.2-11]
i where:
P = Dose parameter for any organ T for each identified h
radionuclide "i", mrem /yr per uCi/m 3 O g8 = 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 ground level releases, uCi/sec.
(XTO)8 = The highest calculated annual average relative concentration at3the unrestricted area boundary for elevated releases, sec/m (X/0)y = The highest calculated annual average relative concentration at the unrestricted 3
area boundary for ground level releases, sec/m NOTE: The dispersion parameters specified in Section 2.2.2 are limited to the site boundary as defined above.
Releases may occur from any of the site vents in the release modes listed in Table 2.2-1. To show compliance with ODCM Appendix C CONTROL 3.11.2.1.b, Expression [2.2-11] is nov expressed in terms of the actual release points for the site.
IP h [(X/0)py O g + (X/0)cy 0 3 + (X/0)yy 0 3 +
i pv cv1 vv1
+ (X/0)tv O g tv1 (X/0)cy O g +( }"# I vv2 *I )tv 0 3 tv2 +
cp Oi +I )dv ev2 cp2 Og + (X/0)yy O g j f 1500 mrem /yr [2.2-12) where:
(X/0)py = Highest calculated annual average relative3 c ncentration for releases from the Process Vent, sec/m (X/0)cy - Highest calculated annual average relative3 c ncentration for releases from the Containment Vents, sec/m 2-41 ISSUE 3
n .;
BV-1 cnd 2 ODCM '
(X/0),y = Highest calculated annual average relative C "C*"I#**I " I #
3 releases from the Ventilation Vents, sec/m V
(X/0)tv = Highest calculated annual average relative concentration3 for~ releases for the Turbine Building Vents, sec/m (X/0)cpL= Highest calculated annual average relative concentration for releases 3f r the BV-2 Condensate Polishing Building l Vent, sec/m (X/0)dv = Highest calculated annual average relative concentration for releases 3f r the BV-2 Decontamination Building Vent, sec/m (X/0)" = Highest. calculated annual average relative concentration for'relesse from the'BV-2 Vaste Gas Storage Vault 3
Vent, sec/m 0.
3
- Long-term release rate of radionuclide "i" from-the BV-1/2-pv ' Process Vent, uCi/sec. )
Og , = Long-term release' rate of radionuclide "i" from the BV-1 cvl Containment Vent, uCi/sec.
Og - Long-term release rate of radionuclide "i" from the BV-2 cv2 Containment Vent, uCi/sec. l
.-l l ;(a 3- Og .- Long-term release rate of radionuclide "i" from-the BV-1 M- vvl Ventilation Vent, uCi/sec.
Og = Long-term' release rate of radionuclide "i" from.the'BV-2 'l vv2 'Ventilat!on Vent, uCi/sec. l i
Og - Long-term release rate of radionuclide "i" from the BV-1 tvl Turbine-Building Vent, uCi/sec.
,, Og -= Long-term release rate of radionuclide "i" from the BV-2 I tv2 Turbine Suilding. Vent, uC1/sec. l u
Og = Long-term release rate of radionuclide "i" from the BV-2 I cp2 Condensate Polishing Building Vent, uCi/sec.
- Og = Long-term release rate of radionuclide "i" from the BV-2 dv2 Decontamination Building Vent, uCi/sec.
Og - Long-term release rate of radionuclide "i" from the BV.2 vv2 Waste Gas Storage Vault Vent, uCi/sec.-
-All-other terms are the same as those plefined previously.
h;-g 2-42 , ISSUE 3 L
(f
BV-1 Cnd 2 ODCM
, The Turbine Building Vent, Cendensate Polishing Building Vent, I
Decontamination Building Vent, and Vaste Car, 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 shoti compliance with ODCM Appendix C CONTROL 3.11.2.1.b only the inhalation rathway is considered.
Values of the organ dose parameters, P vere calculated using methodology given in NUREG-0133. ?or the h,hild c age group, the following ,
equation was used for all nuclider.. The Ph, values are presented in l Table 2.2-13.
Ph = 3.7E9 DFAh 12.2-13]
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 IT USNRC NUREG-0172, Nov. 1977, for organ T, ~
nuclide "i'!, in units of mrem /pCi.
For release modes 1 through 4, the controlling location is the site boundary, 0.35 miles NV.
Expression [2.2-12] becomes:
EPh [7.00E-10 Og + 9.24E-5 O g + 1.03E-4 O g + 7.35E-5 O g +
i pv cyl vv1 tv1 9.24E-5 O g + 1.03E-4 0 + 7.35E-5 O g + .35E4 O g tv2 ep2 Og + 9.24E-5 O g < 1500 mrem /yr [2.2-14]
The determination of the controlling location for implementation of ODCM Appendix C CONTROL 3.11.2.1.b for radiciodines and particulates is a function of the same 3 parameters as for noble gases plus a fourth, the actual receptor pathways. The incorporation of these parameters into Expression [2.2-12] results in the respective equations for each release mode at the site boundary controlling locations. The radionuclide mix was again based upon the source terms presented in Tables 2.2-2a and 2.2-2b as a function of release type and release point.
In the determination of the controlling site boundary for each release l
mode, the highest 2 site boundary X/0 values for each release point were 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.
O 2-43 ISSUE 3
(
13 --
BV-l'and 2 ODCM~
The.X/Q; 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.-:
.s.
s i, :.
i
,,.N jf i'
- . p
[/
r.
ll : k.
i I
i 4 b 1
,.y I
t f f
,4 l
I!
}
w O
2-44 ISSUE 3
=-_ .,
BV-1:ond 2 ODCH 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 H0DE 1 MODE 2 MODE 3 H0DE' 4 2
BVPS BVPS-2 Main Cond. Air Same As Same As Same As Process Vent (pv) Ejector, Vaste Mode 1 Hode 1 Mode 1 And Gas, Contain- Containment ment Vacuum Purge BVPS-1 Ventilation Aux. Bldg. Contajnment Same As Same As Vent (vv1.) Ventilation Purge Mode 1 Mode 1 BVPS-1 Containment Leakage Same As Same As Same As Vent (evi) Collection Mode 1 Mode 1 And Mode 1 Exhaust Contajnment Purge BVPS-1 Turbine Bldg.' Turbine Bldg. Same As Same As Same As Vent (tv1) Exhaust
- Mode 1* Mode 1* Hode 1*
BVPS-2 Ventilation Contiguous Contajnment 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.1 Turbing Bldg. Same As Same As Same As Vent (tv2) Exhaust
- Mode 1* Hode 1* Mode 1*
BVPS-2 Condensate * * *
- Polishing Bldg. Vent (cp2) 1
- BVPS-2 Decontamination * *
- Bldg. Vent (dv2) 1 BVPS-2 Vaste Gas * * *
- Storage Vault Vent (vv2)
- Not normally a radioactive release point NOTE: For the purpose of implementing 10 CFR 50, batch discharges may use continuous meteorology since short term meteorology is used at the time of the annual report.
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
i BV-1 cnd 2 ODCM TABLE 2.2-23 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 CONTAINMEN" 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 2.26-02 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 1.9"-02 0.0
, Xe-137 1.0E-03 2.1E-01 2.1E-05 1.3E-01 6.3E-06. 0.0
'l 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 Mn-54 2.2E-04 1.8E-02 0.0 0.0 4.9E-06 0.0 Fe-59 7.5E-05 6.0E-03 0.0 0.0 1.6E-06 0.0 Sr-89 1.7E-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 'oe purged via Ventilation Vent, Containment Vent, or Process Vent
- Reference 2.1.2 J ***See Sectica 2.1.1.1 2-46 ISSUE 3
BV-1 cnd 2 ODCM TABLE 2.2-2b BV-2 RADIONUCI'.JE MIX FOR GASEOUS EFFLUENTS (Ci/yr)** ;
TURBINE VENTILATION CONTAINMENT BUILDING VENT VENT VENT PROCESS VENT Long Term And AUXILIARY TURBINE MAIN CONTAINMENT GASEOUS CONTAINMENT BUILDING BUILDING CONDENSER / VACUUM VASTE NUCLIDE BUILDINC VENTILATION VENTILATION AIR EJECTOR PUMPS SYSTEM Short Term
~
Long Term Long Term Long Term ag Term Short. Term Kr-83m 4.0E-05 4.2E-01 3.9E-05 2.7E-01 3.7E-04 0.0 Kr-85m 1.4E-02 1.9E+00 1.7E-04 1.2E+00 3.9E-03 1.2E-02 Kr-85 6.1E+01 2.5E+00 2.3E-04 1.6E+00 7.2E-01 2.3E+02 Kr-87 5.3E-06 1.3E+00 1.1E-04 8.2E-01 7.8E-04 0.0 Kr-88 4.1E-03 3.8E+00 3.5E-04 2.4E+00 - 5.0E-03 0.0 Kr-89 0.0 1.2E-01 1.1E-05 7.7E-02 3.1E-06 0.0 Xe-131m 7.2E-01 1.3E-01 1.2E-05 8.0E-02 1.3E-02 8.3E-01 Xe-133m 7.6E-01 8.9E-01 8.1E-05 5.6E-01 2.2E-02 0.0 Xe-133 8.4E+01 3.6E+01 3.4E-03 2.3E+01 1.9E-00 8.2E+00 Xe-135m 0.0 3.2E-01 2.9E-05 2.0E-01 4.4E-05 0.0 Xe-135 2.4E-01 4.5E+00 4.2E-04 2.8E+00 1.9E-02 0.0 Xe-137 0.0 2.1E-01 2.1E-05 1.3E-01 6.3E-06 0.0 Xe-138 0.0 1.1E+00 9.7E-05 6.6E-01 1.2E-04 0.0 I-131 2.7E-05 4.6E-03 6.5E-04 0.1E-02 4.7E-04 0.0 I-132 0.0 0.0 0.0 0.0 2.5E-06 0.0 I-133 2.6E-06 6.7E-03 8.7E-04 3.0E-02 8.4E-05 0.0 I-134 0.0 0.0 0.0 0.0 4.7E-07 0.0
, I-135 0.0 0.0 0.0 0.0 1.4E-05 0.0 Co-58 7.5E-02 6.0E-04 0.0 0.0 1.6E-05 0.0 Co-60 3.4E-02 2.7E-04 0.0 0.0 7.4E-06 0.0 Mn-54 2.2E-02 1.8E-04 0.0 0.0 4.9E-06 0.0 Fe-59 7.5E-03 6.0E-05 0.0 0.0 1.6E-06 0.0 Sr-89 1.7E-03 1.3E-05 0.0 0.0 3.7E-07 0.0 Sr-90 3.0E-04 2.0E-06 0.0 0.0 6.6E.08 0.0 Cs-134 2.2E-02 1.8E-04 0.0 0.0 4.9E-06 0.0 Cs-137 3.8E-02 3.0E-04 0.0 0.0 8.4E-06 0.0 C-14 1.0E+00 0.0 0.0 0.0 0.0 7.0E+00 Ar-41 2.5E+01 0.0 0.0 0.0 0.0 0.0
- Containment can be purged via Ventilation Vent, Containment Vent, or Process Ven
- Reference 2.2.3
- See Section 2.1.2.1 2-47 ISSUE 3
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34 05 3211 0000 4974 2633 1000 0007 0269 3019 1124 0000 9439 4946 7088 22 0000 2000 3001 D /EN T 33 4222 1110 1135 9540 XCO A 231 E NI C T ,AT O - 2454 3371 0872 0000 _
LTA I 50 8450 8474 1437 7235 ESC _
VIO L 23 5333 1111 2247 1123 O EDL O 1341 -
I
' L R LL T - 8014 9511 4350 0000 N DAO N 05 6681 4949 8383 4606 O NIR O I UCT C 22 7444 2121 2350 5057 T OEN 1 1451 U RPO E B GSC H - 0290 5040 1040 0000 T
I R
T GF
,R EOw O I
50 12 8697 1665 1
6153 3333 1896 4494 0283 1996
' 1 3572 M
W C
A R ,
u s 0005 8696 7300 0000 C
D O
92 VEm)
ES ASS n N t
t 05 7865 8019 0184 6555 7815 6763 0108 9230 V-
- 2. B A
LED c A A T
11 111 12 4924 1 -
4 ALN e S
-I M2EO L
F UEA NR N
s 7
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50 0000 5864 0000 7500 0000 5928 0000 0004 5
2 AL) 9618 1 BN A
TI TV E3 E l
01 3221 5022 1111 7999 1124 3326 0068 122 V- T NE2 (
A B EL 0000 L V 2 0000 5192 9000 0000 U D 5 C TNE - 3803 9957 9003 5007 L LUL 00 3420 8566 9168 1914 _
A UOB 2111 112 6275 _
C ARA 11 VGT N 0600 0201 1000 0000 I ESN E 5112 6970 8393 7703 GUI IC D AO SN 3792 2669 5939 5002 E RUD EE 1 44 3 111 1409 S ONE RD 2 U ' II I
STF 720 1240 7100 0000 T -
Y SWT ACN I
S AIL ENA 242 661 -
9975 1626 5337 5627 0754 3005 L G E R MAM 11 1441 N
O RD v uOI 0050 0042 00 000 KT N
O A mF( m L
LA IO 6464 3022 1197 9093 45 70 162 867 I
T W E R
MG 5201 1300 19 181 A 2 7 40 00 0 00 M L K 0 0 93 90 2 40 R V- A LN 8 90 07 51
)
T E
B U D
I O MC
- 2 1
- 0 01 33
- 57 90 N I 3 I V I N 0200 6208 0100 0000 R D 8945 1976 O
F N
I TEE LD BR 2672 6666 4393 3639 7700 5043 b,A A hTG 1 41 11 1496 1
0000 0000 0000 0000
_ \Y ENY 0208 5181 5830 0000 b TUR IOA SBD 5025 2508 1 1 4174 5322 7323 2226 1
8742 7820 2493 ND -
WNCR E E E E N W N N OIEO NEN SES SWS NNN SSSW WWNN DWS'I NNNE EESS
3 E
U S
S 0000 8957 5482 3257 6000 6450 0000 9008 IO 50 3520 7565 8082 7979
~
. 45 2111 0000 0113 5275 11 S
T I
0000 1196 0000 0000
- 7787 7277 2375 6005 M S 05 7842 8676 0217 7069 I S E L E L 44 2111 0000 1123 6506 U I 12 E L M T A 0000 0958 0000 0000 A V N - 4550 0241 3273 4008 R I 50 6299 0898 2688 0018 Q
E / , 34 3211 1000 1124 8208 S X N 23 O ,SS 0 D EN - 5828 2382 3043 2000 E
LCO ENI 9
A 05 4743 3010 5,059 8768 T VAT C 33 4222 1111 1235 9660 I ETA n 231 S LSC r IO - 5649 7615 7749 0000 O DDL L 50 1560 8484 1550 4696 T N O ULL R 23 6333 1111 2248 2354 N OAO T 1341 RIR N I GCT O - 8953 5077 4600 0000 T EN C 05 1792 5049 9418 p232 U ,PO .
B ESC E 22 8444 2221 2360 6409 I G H 1 1461 R AR T T
N RUw EE t. O 50 0445 7928 5941 7164 9300 2046 0000 5489 O V t T M
C C A ,E SL ) S 12 2675 1
3333 4505 3588 11 3682 D 02 LEE E C 1 ASS m C 0009 2621 3100 0000 V- UA N 2
- 2. B NED /c NLN e A
T 05 5418 3317 1323 9009 5
O 0129 6565 7875 3405 5 d 2F AIA s S 11 211 12 5044 -
n O T P', I 11 2 a E 7 D LN NL) - - 6804 6167 6326 0000 1 BO EE3 E 50 AI VV - I 2839 6122 8113 1894 V- TT E2 ( 01 4221 1111 1235 1172 B A GL 1229 L N 2 U ID 0000 2852 0000 0000 C DNE 5 L LUL - 4125 9534 9041 6007 A IOB 00 4631 9677 0270 3125 C URA 2111 1113 6375 BGT 11 N
I GSN 0400 0569 7000 0000 NUI - E 8683 7206 2988 9504 D IO IC E HUD SN 4736 5779 6040 6429 S SNE EE 1 54 3 212 1429 U III RD 2 LTF I
Y OWT P
CN S T -
AIL 433 782 8556 9289 0300 0711 0000 9590 L E TRD E H ENA MAM 661 - 1726 6639 11 3437 w 1441 W AOI N
SF(
N r KT 0080 4368 0004 8028 00 05 090 702 O E u LA 7122 9103 - 85 818
- I T
D R
- - 191 A
M W
C L 0 9 00 00 0 00 R A K 3 2 27 19 1 00 O 2 U LN 8 00 38 F
N V-D I
IO MC
- 2-1 11 33
- 60 15 02 I B V I
13 R D N 0700 9566 4300 0000 N ,EE 0392 4201 6788 9500 M I ELD
- d. B R 4713 6777 3640 6461 tAA 1 51 12 1417 VTG 2
'- 0061 7180 7710 0000 ENY TUR IOA SBD 5264 0098 11 0714 6343 2949 3225 1
4457 6034 2472 O ND WNCR E E E E N W N N OIEO DWST NNt NE2 E
SES EESS SWS SSSW WNNN NNN
I o .
BV-1. and 2 ODCM TABLE 2.2-111 .
, DOSE FACTORS FOR NOBLE GASES ~AND DAUGHTERS
- Q)
'L-
~
K{ g Hy Ny TOTAL BODY- GAMMA AIR BETA AIR a ENUCLIDE. DOSE FACTOR- SKIN DOSE FACTOR DOSE FACTOR DOSE FACTOR.
mrem /yr mrem /yr mrad /yr mrad /yr Per Per Per Per-uCi/m 3 uci/m 3 uci/m 3 uci/m 3
-Kr-83m 7.56E-02 --
1.93E+01: 2.88E+02' Er-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03
.Kr 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+031 1.52E+04 .2.93E+03 Kr-89 1.66E+04' 1.01E+04 1.73E+04 1.06E+04 Kr 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xo-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 4 Xe-133 2.94E+02 3.06E+02 .3.53E+02. '1.05E+03 l Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 l Ke-135. 1.81E+03 lj86E+03 1.92E+03 2.46E+03
.XeJ137. 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 l:;fa g . Ar-41 8.84E+03_ 2.69E+03- 9.30E+03 3.28E+03
!q_,) I l ,
l I
b
.1 l
l 1 !
i i
1/~'N *The listed dose' factors are for; radionuclides that may be detected in gaseous
.(,)[ effluents.
I 2 ISSUE 3 i
BV-1 cnd 2 ODCM TABLE 2.2-12 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES BEAVER VALLEY SITE
- 1 l,2 3 Vg Bg y{3 Bg N0BLE 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 k
- The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
I Vg and Bg values used to implement Modes 1, 2, and 3 of Section 2.2.1 (10CFR20) 2 Bg values usec to implement Modes 1, 2, 3, and 4 of Section 2.3.1 (10CFR50) 3 57 and B values to implement Mode 4 of Section 2.2.1 (10CFR20) and to implementi monitor setpoint determinations of Section 2.1.2 and 2.1.4 2-57 ISSUE 3
BV-1and20D011 Table 2.2-13
.v
-P VALUISFORACHILDFORTHEBI6VIIVALLIISITI
'if (ares /yrpernCl/cuneter)
Buelide Bone Lint f. Body Thyroid lidney Lang GI-LLI 1 H-3 0.00t+00 1.12bO3 1.12bO3 1.12E+03 1.12bO3 1.128+03 1.12 bO3 2P-32 2.60h06 1.14t+05 9.86b04 0.00b00 0.00l+00 0.00!d0 4.22b04 3Cr-51 0.00E+00 0.00l+00 1.54t+02 8.55I+01 2.43b01 1.70t+04 1.08t+03 4Hn-54 0.00E+00 4.29t+04 9.51bO3 0.00h00 1.00h04 '1.58I+09 2.29E+04 5Fe-59 2.078+04 3.34b04 1.67b04 0.00b00 0.00 BOO 1.27bo6 7.07b04 6Co-57 0.00h00 9.03h02 1.07b O3 'O.00b 00 0.00D00 5.07b05 1.32b04 700-58 0.00D 00 1.771+03 3.16bO3 0.00l+00 0.00h00 1.11b06 3.48+04 800-60 0.00l+00 1.31E+04 2.26b04 0.00l+00 0.00D00 7.07b06 9.62I+04 9Zn-65 4.25E+04 1.13I+05 7.03b04 0.00D00 7.14b04 9.95b05 1.63b04 10lb-86 0.00!+00 1.98t+05 1.14b05 0.00b00 0.00D00 0.00D00 7.99b03 11St-89 5.99t+05 0.00!+00 1.72t+04 0.00b00 0.00b00 2.161+06 1.67bo5 12Sr-90 1.011+08 0.00l+00 6.44b06 0.00b00 0.00D00 1.48bO7 3.43b05 p 13T-91 9.14b05 0.00E+00 2.44b04 0.00h00 0.00l+00 2.63X+06 1.84I+05 14Zr-95 1.90b05 4.18t+04 3.70D04 0.00b00 5.96b04 2.23I+06 6.11td4 15lb-95 2.35I+04 9.18bO3 6.55bO3 0.00h00 8.62X+03 6.14E+05 3.70b04-16Rb-97 4.291-01 7.70I-02 3.601-02 0.00I+00 8.55I-02 3.42bO3 2.78b04 1750-99 0.00h00 1.72t+02 4.26t+01 0.00b00 3.92bO2 1.35I 4 5 1.271+05 18fc-99: 1.78I-03 3.481-03 5.77I-02 0.00l+00 5.071-02 9.51bO2 4.81bO3 19En-103 2.79b03 0.00t+00. 1.07 D 03 0.00l+00 7.03b O3. 6.62t+05 4.48I+04 20Ra-106 1.36t+05 0.00h00 1.69b04 0.00b00 1.88+05 1.43bO7 4.29b05 21Ag-110s 1.69t+04 1.14E+04 9.14bO3 0.00b00 12E+04. 5.48I66 -1.00l+05 22Sb-124 5.74b04 7.40l+02 2.00b04 1.26b O2- 0.00 b00 3.2 G+06. 1.64R+05 23Sb-125 9.04I+04 7.59bO2 2.07b04 9.10b01 0.00h00 2.32bo6 4.03b04 24fe-127a 2.4M+04 8.55bO3 3.02bO3 6.07bO3 6.36b04 1.48t+06 7.18+04 25fe-129s 1.92b04 6.85bO3 3.04bO3 6.33t+03 5.03D04 1.76t+06 1.82bo5 26I-131 4.81b04 4.81b04 2.73b64 1.62bO7 7.88t+04 0.00I 40 2.84b O3 27I-133 1.661+04 2.03h04 7.70bO3 3.85tM6 3.38b04 0.00b00 5.48t+03 28Cs-134 6.51b05 1.01b06 2.25b05 0.00b00 3.30 b 05. 1.211 45 3.85bO3 29Cs-136 6.51t+04 1.71bo5 1.16t+05 0.00b00 9.55b04 1.45b04 4.1BbO3 t
30Cs-137 9.07b05 8.25b05 1.28t+05 0.00b00 2.82b05 1.04I+05 3.62bO3 31Ba-140 7.40E+04 6.48h01 4.33t+03 0.00It00 2.11b01 1.74E+06 1.02bo5 32La-140' 6.44bO2 2.25bO2 7.55b01 0.00b00 0.00b00 1.83b05 2.26I45 33Ce-141 3.92144 1.95b04 2.90bO3 0.00h00 8.55bO3 5.44b05 5.66b04 7 34Ce-144 6.77b06 2.12b06 3.61bo5 0.00h00 1.17b06 1.2CbO7 3.89b05 CalenlatedperODCllegnation2.2-13 I
ISSUI3 l 2-58 i-
BV-1 cnd 2.0DCM-
- 2.3. Compliance With 10 CFR 50> Dose' Limits (ODCM Appendix C CONTROLS 3.11.2.2 ,
And 3.11.2.3) (Gaseous)
,m d j 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'shown throughout this section with the apportionment set at 0.5.
2.3.1 -Dose Due To Noble Gases 2.3.1.1 Cumulation of- DosesSection II.B.1 of Appendix I of 10 CFR 50 (ODCM Appendix C CONTROL 3.11.2.2) limits the releases of gaseous effluents from each reactor such that the estimated annual gamma a2r 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 effluento are defined by the following expressions:
During Any Calendar Quarter, For Gamma Radiation:
p i '
~
r -
3.17E-8 I lHi g [(U Q)y0gy + (Uq)yg gy] + [Bg3 0 , + b gq3,)-
< 5 mrad
. [2.3-1]
During Any Calendar Quarter, For Beta Radiation:
3.17E-8 I N g (FO)y0gy + (M)y g gy + (U Q)s0 g, +(U 4),qi s < 10 mrad 1 _ -
[Y.3-2 ]
During Any Calendar Year, For Gamma Radiations i.
3.17E-8 I Mg [(X/0)y0 gy + N)y g gy] + IBg30 , + bg qi,)- < 10 mrad i .
12.3-3]
During Any Calendar Year, For Beta Radiation.
3.17E-8 I N g (X/0)y0gy + (%)yggy + (U Q),01s + (# }s 9 19s < 20 mrad 1 -[7.3-4]
rs (v) ,
1 2-59 ISSUE 3
BV-1 cnd 2 ODCM Averaged Over 31 Days, For The Gamma Radiation Projection:
i 3.17E-8 I Mg [(X/0)y0 gy + (X/q)yg gy) + [B330 , + b3 qi,]- < 0.2 mrad 1 -
[2.3-5]
Averaged Over 31 Days, For The Beta Radiation Projection:
3.17E-8 I N g (X/0)y0 $y + 6/l)y ggy + (X/0),0g , + (X/q),qi, < 0.4 mrad 1 -
[7.3-6]
where:
Mg - The air dose factor due to gamma emissions for each identified n ble gas radionuclide "i" (mrad /yr 3
per uCi/m ).
Ng = The air dose factor due to beta emissions for each identified noble 3 gas radionuclide "i" (mrad /yr per uCi/m ). _
(X/0)y - The annual average relative concentration for areas at or beyond the unrestricted area boundary for 1ong-term vent releases greater than 500 hrs / year (sec/m3 ).
(X/q)y = The relative concentration for areas at or beyond thw unrestricted area boundary for short-term vent releases equal to or less than 500 hrs / year (sec/m 3).
(X/0)s = The annual average relative concentration for areas at or beyond the unrestricted area boundary for long-term free standing 3 stack releases greater than 500 hrs / year (sec/m ).
(X/q), . 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 ),
q,g = 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).
0,3
= 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-tera vent releases greater than 500 hrs / year (uci).
2-60 ISSUE 3
-___7_.
BV-1 end 2 ODCH Bg - The constant for long-term releases (greater than n 500 hrs / year) for each identified noble gas radionuclide
,d
) "i" accounting for the gamma radiation from the elevated finite plume (mrad /yr per uCi/sec).
b 3
- The constar.t 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-8 = The inverse of the number of seconds in a year.
NUREG 0133 permits eliminating the short-term release term and short-term meteorological terms in the determination of doses when short-term releases are sufficiently random in both time of day and duration to be represented by annual average dispersion conditions.
This special consideration is applied in Expressions [2.3-1] through
[2.3-6], however, a summary of the "real time" meteorological data coupled with the corresponding releases shall be included in the Semi-Annual Radioactive Effluent Release Report. .
Short-term releases are also evaluated annually in computer codes technically consistent with X00D00 and GASPAR for inclusion in the Annual Radiological Environmental Report.
The incorporation of this option and the release modes of Table 2.3-1
,r results in the following expressions to show compliance with 10 CFR 50
(]) for the calendar quarter or year.
For Release Modes 1, 2, 3, And 4 During Any Month, Calendar Quarter, Or Year:
Gamma Radiation:
3.17E-8 I Hg [(X/0)cv0 g + (X/0)yy0 g + (X/0)cp0 gcp+ (X/0)dv 01 +
i cv vv dv (X/0) ,03 ] + 0.5 B g30 vv pv 0.2 mrad (per 31 days) [2.3-7]
< 5.0 mrad (per quarter) 10.0 mrad (per year) i n
v 2-61 ISSUE 3 i
i i
BV-1 end 2 ODCM Beta Radiations-3.17E-8 I N g (X/0)cy 0g ' + (X/0)yy0 g + (X/0)cp0 1 + (X/0)dv 0g +
0 i- cv vv cp dv (X/0),y0 g + 0.5 (X/0)py0 g py 0.4 mrad (per 31 days) [2.3-8]
< 10.0. mrad'(per quarter) 20.0 mrad (per year) where (X/0)cv.= Annual average relative concentration3 for releases from the Containment Building Vent (sec/m ),
(X/0)" = Annual average relative concentration for3 releases from the Ventilation Vent (sec/m ),
~
(X/0)Pv = Annual average relative3 concentration for releases from the Process Vent (sec/m ),
(X/0)tv - Annual average relative concentration3 f r releases from the Turbine Building Vent (sec/m ).
Og - Release of radionuclide "i" from the Containment Building cv Vent (uci).
Og - Release or radionuclide "i" from the Ventilation Vent vv (uci).
Og = Release of radionuclide "i" from the Process Vent pv (uci).
Og = Release of radionuclide "i" from the Turbine Building tv Vent (uCi).
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 [2.3-7]-and
[2.3-8] results in the following:
O 2-62 ISSUE 3
BV-1 cnd 2 ODCM Release Modes 1, 2, 3, And 4 v;) During Any Month, Calendar _ Quarter, Or Year:
Gamma Radiations 3.17E-8 I Mg [9.24E-5 O g + 1.03E-4 O g + 7.35E-5 O g + 7.35E-5 O g +
i cv vv tv cp j I
9.24E-5 O g + 9.24E-5 0 3 ] + 0.5 B gg o j dv vv pv .
0.2 mrad (per 31 days) [2.3-9]
f 5.0 mrad (per quarter) ;
10.0 mrad (per year) {
Beta Radiation:
- . l 3.17E-8 I N g 9.24E-5 O g + 1.03E-4 O g + 7.35E-5 O g + 7.35E-5 O g +
i cv vv tv cp i 9.24E-5 O g + 9.24E-5 O g + (0.5) 7.0E-10 0 y
0.4 mrad (per 31 days) [2.3-10] j q f 10.0 mrad (per quarter)
~
,(j 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 i (2) Release mode (3) Meteorology The incorporation of these parameters into Expressions [2.3-7] and
[2.3-8] resulted in the expressions for the controlling locations as.
I presented in Expressions [2.3-9] and [2.3-10]. The radionuclide mix-vas 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 l as a function of release type and release point.
l l As in Section 2.2.1, for each release mode, the two highest boundary 5-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 were obtained for the midpoint of the 10 standard d distance intervals previously presented in Tables 2.2-4 through 2.2-10.
2-63 ISSUE 3
BV-1 cnd 2 ODCM For each release mode, a particular combination of release point mix and meteorology dominates in the determination of the controlling location. For Release Modes 1, 2, 3, and 4 the controlling release is the Ventilation Vent. For Release Mode 3, the controlling release is the Containment Building Vent.
Values for H 3 and N controlling locatibn,whichwereusedinthedeterminationofthe and which are to be used by BV-1 and BV-2 in Expressions [2.3-9] and [2.3-10] to show compliance with 10 CFR 50 were presented in Table 2.2-11. Values taken from Table B-1 of Regulatory Guide 1.109, yRevision 1 vere multiplied by 1E6 to convert from picoeuries~ to mic.rocuries-3 for use in Table 2.2-11.
In the determination of the controlling location for Modes 1, 2, 3, and 4, Tables 2.2-4 through 2.2-7 are utilized for X/0 values. The B 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 f 5 mrad [2.3-11]
Dg f 10 mrad [2.3-12]
For The Calendar Year:
D f 10 mrad [2.3-13]
Dg f 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 ODCH Appendix C CONTROL 3.11.2.2.a must be filed with the NRC at the identified locations.
In addilicn, ODCH 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 f 0.2 mrad [2.3-15]
D6 f 0.4 mrad [2.3-16]
1 2-64 ISSUE 3 l
l
_ I
. .BV-1,and 2 ODCM f
"2.3.1'.2 , Projection Of Doses (Noble Gas) i l
~
Doses duejto gaseous' releases from BV-1 and BV-2-shall be projected ~
!at least'once per 31Ldays in accordance with ODCM Appendix C l
' CONTROL = 14.11.2.4' and.-this- section. -(See also Section 2.3.2.2
- Projection Of Doses).. :The' Gaseous -Radvaste Treatment System and the.
. Ventilation. Exhaust ~ Treatment' . System lshall: be used' to Dreduce 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 gasaous effluent releases from each
. reactor l 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 Expressionse
'[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 Aj B (31) +.C .. [2.3-17]
- 37. =
When Not Including Pre-Release Data,
.D (31) + C I2*3~10I 31 =
where:
D31 = Projected 31 day dose (mrad)'.
A = Cumulative dose'for quarter (mrad).
iB --Projected dosesfrom this release (mrad)..
T = Current days into quarter.
C = Value which may be used to anticipate plant trends (mrad).
l l
.!j l
i 2-65 ISSUE 3 l'
1:
~
t
BV-1 cnd 2 ODCM 2.3.2 Dose Due Te Radioiodines And Particulates 2.3.2.1 Cumulation Of Doses Section IIC of Appendix I of 10 CFR 50 (ODCM Appendix C CONTROLS 3.11.2.3 and 3.11.2.4) limits the release of radioiodines and radioactive material in particulate form from each reactor unit such that estimated dose or dose commitment to an individual in an unrestricted area from all pathways of exposure is not in excess of 15 mrem to any organ. In addition, ODCM Appendix C CONTROL 3.11.2.4 requires the use of gaseous radvaste treatment system when the projected dose due to gaseous effluent releases from each reactor unit, when averaged over 31 days, would exceed 0.3 mrem to any organ. Based upon NUREG-0133, the dose to an organ of an individual from radiciodines and particulates, and radionuclides other than noble gases with half-lives greater than 8 days in gaseous effluents released to unrestricted areas, can be determined by the following expression:
During Any Month, Calendar Quarter, Or Year:
3.17E-8 I R g [V,0g ,+ v,q$,+ V0gy y + v yq3y] -
1 0.3 mrem (per 31 days) [2.3-19]
< 7.5 mrem (per quarter) 15.0 mrem (per calendar year) where:
O g8 - Belease of radionuclide "i" for long-term free standing stack releases greater than 500 hrs /yr (uci).
0 3y = Release of radionuclide "i" for long-term vent releases greater than 500 hrs /yr (uci).
q,g = 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 at the controlling location for long-term free standing stack releases greater than 500 hrs /yr.
3
= sec/m for the inhalation pathway, (W/0),.
-2
= meters for the food and ground plane pathway, (D/0),.
V - The dispersion parameter for estimating the dose to an y
j individual at the controlling location for long-term vent i
releases greater than 500 hrs /yr.
3
= sec/m for the inhalation pathway, (X70)y.
-2 l = meters for the food and ground plane pathway, (D/0)y.
2-66 ISSUE 3 L
BV-1 cnd 2 ODCM l
I y
s = Dispersion parameter for estimating the dose to an 7 -. 3 individual at the controlling location for short-term stack releases equal to or le s than 500 hrs /yr.
t
\__ )
3 '
= sec/m for the inhalation pathway, (X/q),.
= meters
-2 for the food and ground plane pathway, ( R ),.
vv = 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. I J
3
= sec/m for the inhalation pathway, (X/q)y. l
= meters
-2 for the food and ground. plane pathway, (D/q)y.
3.17E The inverse of the number of seconds in a year.
R IT = The dose factor for each identified radionuclide "i" for the organ "T" of interest (mrem /yr per uCi/see per m-2 or mrem /yr per uCi/m3 ).
Radionuclides and particulates may be released from any of the BV-1 and l 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 l long-term annual average dispersion calculations which with the release '
modes of Table 2.3-1 results in the following expressions to show n compliance with ODCM Appendix C CONTROLS. 3.11.2.3 and 3.11.2.4. For a
- particular organ, Expression [2.3-19] becomes
C/
3.17E-8 I R 0.5 Vpy0g +V cy0g +V yy0g +V 0 +V cp0g + l tv 3 i pv cv vv tv cp Ydv0i "
dv vv 0.3 mrem (per 31 days) [2.3-20] i
< 7.5 mrem (per quarter) 15.0 mrem (per calendar year) where:
V py
= Dispersion parameter for releas's from the Process Vent.
V = Dispersion parameter for relestes from the Containment CV
- Building Vent.
Vyy = Dispersion parameter for releases f am the Ventilation Vent.
V - Dispersion parameter for releer_s from the Turbine Building g
l Vent.
g3 p
2-67 ISSUE 3
BV-1 cnd 2 ODCH V - Dispersion parameter for releases from the Condensate cp Polishing Building Vent.
U - Dispersion parameter for releases from the Decontamination dv Building Vent.
Vyy - Dispersion parameter for releases from the Vaste Gas Storage Vault Vent.
O i
p - Release of radionuclide "i" from the Process Vent (uCi).
01 CV = Release of radionuclide "i" from the Containment Building Vent (uci).
O i
yy - Release of radionuclide "i" from the Ventilation Vent (uci).
0 1tv - Release of radionuclide "i" from the Turbine Building Vent (uci).
01 CE
- Release of radionuclide "i" from the Condensate Polishing Building Vent (uCi).
0 1 = Release of radionuclide "i" from the Decontamination Building Vent (uci).
0 1" - Release of radionuclide "i" from the Vaste Gas Storage Vault Vent (uCi).
The Turbine Building Vent is not normally a 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 pathvay, 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 iT +R 0 +V 0 + Vvv0l +
g g ig+ Rig + Ritg][0.5 Vpv i py cv i cy yy
+U +V +R g7 [0.5 (X/0)py0 g "tv 03 y cp0g ep dv03 y
+ Vyy03 pv
+ (X/0)cy0 g + (X/0)yy0 g +MtvS tv+ cp0g
+
y vv cp (X/0)dv0g "
dv vv 0.3 mrem (per 31 days) [2.3-21]
$ 7.5 mrem (per quarter) 15.0 mrem (per year) 2-68 ISSUE 3 L
.p n E BV-1 cnd 2 ODCM vheres
- >~N R
!! iTg = Dose.' factor for an organ "T"-for radionuclide "i" for-the A -
ground plane exposure pathway (mrem /yr per uCi/sec per m-2).
R iTg = Dose factor for:an organ "T" for radionuclide "i" for:
m either.the uCi/see per cow'2) m' ilk or goat milk pathway.(mrem /yr per.
R it - Dose' factor for an. organ "T" for radionuclide vegetable pathway (arem/yr per uCi/see per m-2")i" ,
for the R gT B - D se factor for an organ "T" for the meat pathway (mrem /yrfor.radionuclide per uci/see per m "i"2).
R iTy = Dose factor for. an organ "T" ;for. radionuclide3 "i" for the inhalation pathway (mrem /yr per uCi/m ),
, It should be noted that V cv, V , V
,Vcp, Vdv,/0 and 1
Vyy in Expression [2.3-21]Pv, ue V in " terms *"of D 5-2),
Values of the dose factor, R vere calculated ssing the methodology.
of NUREG-0133. The follovikd, equations. vere used for all nuclides except tritium:
iTy = K'(E3),(DFA g f
= mrem /yr per uti/m 3 [2.3-22]
D' where i
K'
- A constant of unit conversion (lE6 pCi/uCi).
(BR), = The breathing 3 rate f the receptor of age-group "a" (m /yr).
(DFAh}a = Each organ inhalation dose factor for the receptor of age group "a" for the "i" th radionuclide (mrem /pci).
Inhelation dose factors (DFA g age groups are given in Table 3) 7bythrough organ E-10 for the of various Regulatory Guide 1.109, Rev. 1 or Tables 5 through 8 of i NUREG-0172.
1 used for the various age groups are tabulated )
The belov, breathing as givenrates (BR),E-5 of the Regulatory Guide 1.109.
in Table i
3 Age Group (a) B_r,eathing Rate (m /yr) I Infant 1400 I Child- 3700 Teen 8000 ,
Adult 8000 l
/ .
'( .
1
( .- ;
i l
2-69 ISSUE 3 ;
l l i- l
[_
BV-1 cnd 2 ODCM t
iTg;= K'K" (SF)DFGg [(1 - e i )fy,)
= m2 -mrem /yr per uCi/sec [2.3-23]
vhere:
K' = A constant of unit conversion (IE6 pCi/uCi).
K" = A constant of unit conversion (8760 hr/ year).
i - The decay constant for the "i" th radionuclide (see-1).
t .- The exposure time (4.73E8 see or 15 years).
DFG g - The groundplane dose conversion factor f r rgan "T" f r the "i"'th radionuclide (mrem /hr per pCi/m2 ). A tabulation of DFG values is presented in Table E-6 of Regulatb[yGuide1.109.
SF = The shielding factor (dimensionless). A shielding factor of 0.7 as suggested in Table E-15 of Regul_atory Guide 1.109 is used.
O I N - I ps I )*
R iTg = K' F(. ap)F,(r)(DFLh)aIps
- l' Y Y 3
2
= m -mrem /yr per uCi/sec [2.3-24]
where O K' = A constant of unit conversion (1E6 pCi/uCi).
Op - The animal's consumption rate, vet weight (kg/ day).
U ap = The receptor's milk consumption rate, for age "a" (liters /yr).
Y p = The agricultural2 productivity by unit area of pasture feed grass (kg/m ).
Tg - The agricultural 2 productivity by unit area of stored feed (kg/m ).
F, = The stable element transfer coefficients (days / liter).
r = Fraction of deposited activity retained on animals feed grass.
(DFLg g = The maximum organ ingestion dose factor for the "i" th radionuclide for the receptor in age group "a" (mrem /pci). Ingestion dose factors (DFL for the various age groups are given in Tableg3)8 11 through E-14 of Regulatory Guide 1.109 or Tables 1 through 4 of NUREG-0172.
a, 2-70 ISSUE 3
> l BV-l'cnd'2LODCM k = Thel _ decay constant for the'"1" th radionuclide,(see-1).-
' ~
[y D tM - The' decay constant:.for removal.of activity on 31eaf.
and~ plant surfaces by weathering 5.73E-7 sec~
X (corresponding to a:14-day half-life).
,fI - The= transport-time from.past'ure, to animal, to milk,_to-receptor;(sec).:
t h - The' transport time'from pasture, to harvest,:to animal, to_ milk, to: receptor'(sec).
I -
n .= i'raction of the year that-the animal is on pasture:
-(dimensionless).-
I s - Fraction of the animal feedithat.is pasture grass,while the animal is'on pasture (dimensionless).
Tabulated below areithe parameter values' used-for' cow's milk'and their reference to Regulatory Guide 1.109.
Parameter Value Table r (dimensionless) 1.0 for radiciodine. E-15
'~ '
O.2 for particulates E-15 F,(days / liter)- each stable element :E-1 (cow milk) j E-2 (goat' milk)
O '
'U*P (liters /yr) - infant 330 '
E-5' child 330' E . teen 400 E-5 9.
adult 310 E-5 (DLFg y , (ares /pci). each radionuclide E-11 to E-14 2
YP-(kg/m ) 0.7 E-15 2
4: Y, (kg/m ) 2.0. E-15 l t g (seconds) 1.73E5 (2 days) E-15 7.78E6 (90 days) E-15 th (seconds).
07 (kg/ day) 50 E-3 f 0.5 -
p
-f -1.0 --~
3 m
For goat's milk, all values remain the same except for 07 which is 6 kg/ day.
10,
!- 2-71 ISSUE 3 l
l4.
(
}: >
i.
1 BV-1 cnd 2 ODCM I
t -A t O (U ff (1 - f f )e i h if iTB=K, ap)F (r)(DFL ]*
. f h)al *
- m2-mrem /yr per'uC1/sec [2.3-25] !
vhere F
f the stable element transfer coefficients (days /kg).
U,p - The receptor's meat consumption rate for. age "a" (kg/yr).
t f
. The average time from slaughter of meat animal to consumption (sec).
t h = The transport time from crop field to receptor (sec).
All parameter values are the same as the milk pathway parameter values except F, which is obtained from Table E-1,- t which is obtained from Table E-IS and U vhichisobtainedfromTabibE-5. The values as obtained from8pRegulatory 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 ig -Atgh
( U y.= K' ly ) ](DLFh)aIU ILe +Ufe ]
2
= m -mrem /yr per uCi/sec [2.3-26]
where:
K' = A constant of unit conversion (1E6 pCi/uci).
U = The consumption rate of fresh leafy vegetation by the receptor in age group "a" (kg/yr).
S U* = The consumption rate of stored vegetation by the receptor in <
age group "a" (kg/yr),
fg = The fraction of the annual intake of fresh leafy vegetation j grown locally.
2-72 ISSUE 3 O
BV-1 cnd 2 ODCM f g= The fraction of the annual intake of stored vegetation grown
, locally.
i !
V tg = The average time between harvest of leafy vegetation and its consumption (seconds),
th - The average time between harvest of stored vegetation and its consumption (seconds).-
Yy = The vegetation area density (kg/m2 ), {
l all other factors are defined previously, i Tabulated below are the appropriate parameter values and their ;
reference to Regulatory Guide 1.109. j i
Parameter Value Table r (dimensionless) 1.0 for radioiodines E-15 0.2 for particulates E-15 )
(DFLgT), (mrem /pci) each stable element 5-11 to E-14 U,b (kg/yr) - infant 0 E-5 I child 26 E-5 teen 42 E-5 1 adult 64 E-5
( US (kg/yr) - infant. 0 E-5 k_)-
child 520 E-5 l
teen 630 E-5 adult 520 E-5 fg (dimensionless) 1.0 E-15 i
Fg (dimensionless) 0.76 E-15 tg (seconds) 8.6E4 (1 day) E-15 th (seconds) 5.18E6 (60 days) E-15 2
Yy (kg/m ) 2.0 E-15 o
As discussed in Section 2.2.2 for tritium, the parameter V for the food pathway is based upon X/0. The ground plane pathway is not appropriate for tritium. Therefore, the left-hand portion of Expression (2.3-20]
may be expressed for purposes of implementation of 40 CFR 190, discussed in Section 4.0, as:
For Tritium:
3.17E-8 (R 0
+ (X/0)cv0T cv Tg+ RTg* RTg+ RT g) [0.5 (X/0)py T
,-m (X/0)yy0 Tvv+ (X/0)tv0 Tvv+ (X/0)cp0 7 + (X/0)dv07dv+ (X/0)yy07vv ]
(v ) cp
[2.3-27]
2-73 ISSUE 3
BV-1 cnd 2 ODCH I
l vhere: .
R - Dose factor for organ "f for3tritium f r the milk T3 pathway (mrem /yr per uCi/sec ). j{
R = Dose factor for organ "f f r tritium for the vegetable 3
T3 pathway tmrem/yr per uCi/m ).
for tritium f.r the beef R = Dose factor for organ "f 3
l T3 pathway (mrem /yr per uCi/m ),
R = Dose factor for organ " 3f 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 thars the deposition. Therefore, the R is based on [X/0]: T3 R
Tg- K'K' F,0 UF ap(DLFh)a[0.75(0.5/H)]
= mrem /yr per uCi/m [2.3-28]
where:
K'" = A constant of unit conversion (1000 gm/kg).
3 H = Absolute humidity of the atmosphere (8 gm/m ),
0.75 - The fraction of total feed that is water.
0.5 - The ratio of the specific activity of the feed grass water to the atmospheric water.
and other parameters and values are the same as for R .
The concentration of tritium in vegetation is based on the airborne i
concentration rather than the deposition. Therefore, the RE% s based on [X/0):
8 R
Tg=K'K' [U fg + U f E](DFLg ),[0.75(0.5/H)]
- mrem /yr per uci/m 3 [2.3-29]
vhere all terms have been defined above.
The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore, the R is based on (X/0]: T3 ,
4 O'
2-74 ISSUE 3
BV-1 cnd 2 ODCH R
T g= K'K'"F g7 0 U,p(DFLh)a[0.75(0.5/H)]
- mrem /yr per uCi/m [2.3-30]
(O) vhere all terms have been defined above.
To shov compliance with ODCH Appendix C CONTROLS 3.11.2.3 and 3.11.2.4, Equation [2.3-21] is evaluated at the controlling pathway location.
F(t 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 [R gT +RgT ][(0.5)4.22E-10 Og + 1.56E-8 0,y + 1.56E~8 Og + 1.55E-8 O g + 1.55E-8 O g + 1.% E-8 O g + 1.56E-8 vv tv I cp dv Og ]+R g [(0.5) 7.30E-9 O g + 2.00E-5 O g + 2.71E-5 O g
+ 2.22E-5 O g + 2.22E-5 O g + 2.00E-5 O g + 2.00E-5 O g ]
tv cp dv vv 0.3 mrem (per 31 days) [2.3-31]
< 7.5 mrem (per quarter gm) 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 [RTTV + RT3][(0.5)7.30E-9Og pv + 2.00E-5.03 cv + 2.71E-5 Ogvv 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 ODCH 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 i (3) Heteorology i (4) Exposure pathway ]
(5) Receptor's age ;
The incorporation of these parameters into Expression [2.3-19] results in the respective equations for each release mode at the controlling location.
,m
{V I I
~
2-75 ISSUE 3
)
BV-1 end 2 ODCM In the determination of the controlling location for each release mode, the radionuclide mix of radioiodines and particulaten vem hamad upon l the source terms calculated using the GALE code. This mix was {
presented in Tables 2.2-2a and 2.2-2b as a function of release mode and release point. For the ground plane exposure pathway, all radionculides (excluding H-3 and C-14) vere considered in the determination of the controlling location. For the inhalation and food pathways H-3 and C-14 vere also considered in determination of the controlling location.
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 pathway locations. A child was assumed to be present at all vegetable garden and beef animal locations. The ground plane and inhalation exposure pathways were considered to be present at all locations.
Fcr the determination of the controlling location, the highest D/0 and X/0 values for each release point and release mode for the vegetable garden, cov milk, and goat milk pathways were selected. The organ dose was calculated at each of these locations using the radionuclide mix and release of Tables 2.2-2a and 2.2-2b Based upon these calculations, it was determined that the controlling location for Release Modes 1 through 4 is the residence (vegetable garden)/ child pathway.
For Release Modes 1 through 4, the controlling release point and mix is the Ventilation Vent.
values for the total body, Tables GI-tract,2.3-2 through bone, 2.3-20 liver, present-R,id, kidney, thyro 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 appropriate to the pathways. These values were calculated using the methodology described in NUREG-0133 using a grazing period of 6 months.
In the determination of the controlling location for Release Modes 1-4, Tables 2.2-4 through 2.2-10 are utilized for X/O'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.
2-76 ISSUE 3
-BV-1 cnd 2 ODCM
.The following relationship should hold ,for BV-1 or- BV-2. to show s, compliance with ODCM Appendix C CONTROL 3.11.2.3.
1\m.
l'%f Y
For.The Calendar Quarter:
.D f 7.5 mrem to any organ [2.3-33]
l For The Calendar Year:
-D f 15 mrem to any organ [2.3-34]
where:
D7 - The dose to any organ from radioiodines and particulates-(mres).
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.
W 2-77 ISSUE 3
BV-1 and 2 ODCH 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 proj ected dosc: due to gaseous effluent releases from each reactor unit, when averaged over 31 days, vould exceed 0.3 mrem to any organ. (See also Section 2.3.1.2 Projection Of Doses for additional specifications). Doses resulting from the gaseous effluent release of radioiodines and particulates vill be calculated for use in the 31-day dose projection using Expression [2.3-31]. The 31-day dose projection shall be performed according to the following equations:
When Including Pre-Release Data, D
31 =
A+B (31) + C -
[2.3-35]
T When Not Including Pre-Release Data, D
31 = (31) + C [2.3-36]
there:
D31 - Projected 31 day dose (mrem).
A = Cumulative dose for quarter (mrem).
B = Projected dose for this release (mrem).
T = Current days into quarter.
C = Value which may be used to anticipate plant trends (mrem).
O 2-78 ISSUE 3
BV-1 end 2 ODCM TABLE 2.3-1
,2% MODES OF GASEOUS-RELEASE FROM BEAVER VALLEY SITE VENTS FOR l
u) . 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,lVaste 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 (evi). 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 1 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 (cv2) Ventilation Mode 1 Mode 1 And' Mode 1
[yJ- Contajnment b Purge BVPS-2 Turbine Bldg.I Turbing Bldg. Same As Same As Same As Vent (tv2) Exhaust
- Mode 1*~ Mode 1* Mode 1*
1 * * *
- BVPS-2 Condensate Polishing Bldg. Vent
-(ep2)
BVPS-2 Decontamination I
Bldg.' Vent (dv2)
BVPS-2 Vaste Gas 1 * * *
- 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 C ntinu us elevated meteorology is applicable
,-~y 3 Mode established oy purge from one unit, all other release points remain same
-Q as Mode 1 2-79 ISSUE 3 l~
i l
l BV-1and2ODCH Table 2.3-2 I
IVALUISFORBIAVIEVALLIISITI (ares /rrperiC1/enmeter)
Pathear: Inhalation AgeGroup: Adult
-Nuclide Bone Liver f. Body Thyroid Ildney Lung GI-LLI 1H-3 0.00!t00 1.26Et03 '1.26t+03 1.26t+03 1.26I+03 1.26I+03 1.26I+03 2P-32 1.32E+06 7.711+04 5.01E+04 0.00l+00 0.00!+00 0.00E+00 B.64Et04 3Cr-51 0.00!+00 0.00E+00 1.00E+02 5.95E+01 2.28t+01 1.44E+04 3.32E+03 4Hn-54 0.00E+00 3.96I+04 6.30E+03 0.00!+00 9.84t+03 1.40!+06 7.74E+04 5 Fe-59 1.181+04 2.7BI+04 1.06t+04 0.00!+00 0.00E+00 1.02I+06 1.881+05 6Co-57 0.00l+00 6.92E+02 6.71E+02 0.00!+00 0.00l+00 3.70E+05 3.1G+04 700-58 0.00!+00 1.58t+03 2.07t+03 0.00l+00 0.00l+00 9.281+05 1.06t+05 8C0-60 0.00l+00 1.15E+04 1.48I+04 0,00E+00 0.00I+00 5.97I+06 2.85E+05 9In-65 3.24E+04 1.03E+05 4.66I+04 0.00E+00 6.90!+04 8.64E+05 5.34E+04 10Rb-86 0.00!+00 1.35E+05 5.90I+04 0.00E+00 0.00R+00 0.00E+00 1.661+04 11Sr-89 3.04E+05 0.00!+00 8.72E+03 0.00!+00 0.00!+00 1.40E+06 3.50E+05 12Sr-90 9.92E+07 0.00I40 6.10E+06 0.00!+00 0.00E+00 9.60!+06 7.22t+05 13Y-01 4.62E+05 0.00R+00 1.24E+04 0.00!+00 0.00E+00 1.70E+06 3.85E+05 14Zr-95 1.071+05 3.44It04 2.33E+04 0.00l+00 5.42E+04 1.77I+06 1.50!+05 15Nb-95 1.41E+04 7.82E+03 4.21X+03 0.00l+00 7.74E+03 5.05Ed5 1.0G+05 16lb-97 2.221-01 5.62I-02 2.'051-02 0.00E+00 6.56-02 2.40!+03 2.42It02 17He-99 0.00!+00 1.21E+02 2.30E+01 0.00l+00 2.91E+02 9.12E+04 2.48t+05 18 fe-99 1.03I-03 2.91E-03 3.701-02 0.00t+00 4.421-02 7.64E+02 4.16I+03 19Ru-103 1.53E+03 0.00E+00 6.58I+02 0.00E+00 5.83E+03 5.05E+05 1.10!+05 20Ru-106 6.91E+04 0.00E+00 8.72E+03 0.00Et00 1.34E+05 9.36I+06 9.12E+05 21Ag-110s 1.0BI+04 1.00!+04 5.94t+03 0.00l+00 1.971+04 4.63E+06 3.02E+05 j 22Sb-124 3.12E+04 5.89t+02 1.24E+04 7.55t+01 0.00E+00 2.4BI+06 4.06I05 l 23Sb-125 5.3G+04 5.95E+02 1.26t+04 5.40E+01 0.00I40 1.74E+06 1.01t+05 24fe-127s 1.26t+04 5.77I+03 1.57I+03 3.29t+03 4.581+04 9.60t+05 1.50X+05 25fe-129s 9.76t+03 4.671+03 1.5BI+03 3.4G+03 3.66t+04 1.16t+06 3.83E+05 26I-131 2.521+04 3.5 bid 4 2.05I64 1.191+07 6.13E+04 0.00t+00 6.28t+03 1 271-133 8.64t+03 1.481+04 4.52E+03 2.15E+06 2.58I+04 0.00l+00 8.86t+03 )
28Ce-134 3.73t+05 8.48t+05 7.281405 0.00E+00 2.871+05 9.76t+04 1.0G+04 !
1 29Cs-136 3.90!+04 1.46t+05 1.10l+05 0.00I40 8.56t+04 1.20E+04 1.17Et04 30Cs-137 4.7BI+05 6.21E+05 4.281+05 0.00l+00 2.22R+05 7.52E+04 8.40!+03 31Ba-140 3.90E+04 4.90l+01 2.571+03 0.00E+00 1.671+01 1.271+06 2.1BI+05 32La-140- 3.4G+02 1.74E+02 4.58I+01 0.00!+00 0.00I400 1.36t+05 4.581+05 ,
f 33Ce-141 1.99I+04 1.35E+04 1.53E+03 0.00I+00 6.26t+03 3.62E+05 1.20Id5 ;
l 34Ce-144 3.43E+06 1.43I+06 1.84I+05 0.00!+00 8.48145 7.78t+06 8.161+05 l CalculatedperODCHegnation2.3-22 ISSUI3 2-80 l
BV-1and2ODCtf fable 2.3-3 If l
L/
1VALUISFORBIAVIIYALLITSITI (ares /yrpernC1/enseter) l Pathway: Inhalation AgeGroup: Teen Nuclide- Bone Liver T. Body Thyroid Ildney Lung GI-LLI 1H-3 0.00l+00 1.27I+03 1.27I+03 1.27t+03 1.271+03 1.271+03 1.271+03 2P-32 1.891+06 1.10l+05 7.16I+04 0.00E+00 0.00l+00 0.00E+00 9.28I+04 3Cr-51 0.00l+00 0.00E+00 1.35E+02 7.50l+01 3.075+01 2.10E+04 3.00l+03 4Hn-54 0.00E+00 5.11E+04 8.40t+03 0.00t+00 1.27t+04 1.98I+06 . 6.681+04 5 Fe-59 1.59t+04 3.70E+04 1.438+04 0.00E+00 6.00!+00 1.53I 4 6 1.78I+05 6Co-57 0.00l+00 9.44X+02 9.20I+02 0.00l+00 0.00!+00 5.86I+05 3.14t+04 7Co-58 0.00E+00 2.07I+03 2.78t+03 0.00l+00 0.00E+00 1.34E+06 9.521+04 800-60 0.00E+00 1.51E+04 1.988+04 0.00E+00 0.00l+00 8.72f+06 2.598+05 9Zn-85 3.861+04 1.34I+05 6.24I+04 0.00!+00 8.64E+04 1.24t+06 4.661+04 10Ib-86 0.00E+00 1.90l+05 8.40l+04 0.00t+00 0.00E+00 0.00I40 1.771+04 11St-89 4.34E+05 0.00E+00 1.25I+04 0.00l+00 0.00l+00 2.42E+06 3.71E+05 12Sr-90 1.088+08 0.00l+00 6.688+06 0. 0!+00 ' O.00!+00 1.65E+07 7.65E+05 ;
13T-91 6.61E+05 0.00E+00 1.771+04 0.00l+00 0.00t+00 2.94E+06 4.09t+05
' (m) "
-15Ib-95 1.46t+05 4.581+04 3.151+04 0.00l+00 6.74E+04 2.69I+06 1.491+05 1.861+04 1.03t+04 5.66t+03 0.00!+00 1.00t+04 7.51545 9.68I+04 i
16Nb-97 3.14I-01 7.781-02 2.84I-02 0.00I40 9.121-02 3.93E+03 2.17I+03 17N0-99 0.00t+00 1.698+02 3.22I+01 0.00E+00 4.111+02 1.54f+05 2.698+05 l 18fc-99s 1.38I-03 3.86I-03 4.99I-02 0.00t+00 5.76I-02 1.151+03 6.13It03 19 In-103 2.10t+03 0.00!+00 8.961+02 0.00!+00 7.43t+03 7.83E+05 1.09t+05 20In-106 9.84It04- 0.00!+00 1.24R+04 0.00I+00 1.90E+05 1.61847 9.60l+05 21Ag-110s 1.38I+04 1.31t+04 7.99t+03 0.00t+00 2.50l+04 6.75t+06 2.73t+05 22 Sb-124 4.30I44 7.94E+02 1.68144 9.76t+01 0.00l+00 3.34E+06 3.981@5 23Sb-125 7.38t+04 8.08t+02 1.72X+04 7.04t+01 0.00t+00 2.74I46 9.92E+04 24fe-127s 1.80I 4 4 8.16t+03 2.18t+03 4.38t+03 6.54t+04 1.66t+06 1.591+05 25fe-129s 1.39t+04 6.581+03 2.25I+03 4.58t+03 5.19I+04 1.98I 6 6 4.05E+05 26I-131 3.54E+04 4.91E+04 2.64t+04 1.468+07 8.40l+04 0.00B+00 6.49t+03 27I-133 1.22t+04 2.05t+04 6.22E+03 2.92E+06 3.59t+04 0.00l+00 1.03f+04 28Cs-134 5.02E+05 1.13t+0S 5.49t+05 0.00E+00 3.75E+05 1.46I+05 9.76I+03 29te-136 5.15E+04 1.94E+05 1.37I+05 0.00l+00 1.10l+05 1.788+04 1.09t+04 ;
30Cs-137 6.70l+05 8.48t+05 3.11E+05 0.00140 3.04I+L5 ' 1.21E+05 8.48I+03 31Ba-140 5.471+04 6.70E+01 3.52!+03 0.00l+00 2.28I+01 2.03Id6 2.29I+05 32La-140 4.798+02 2.36t+02 6.26t+01 0.00!+00 0.00!+00 2.14E+05 4.87t+05 33Ce-141 2.84t+04 1.90l+04 2.17I+03 0.00l+00 8.88t+03 6.14E+05 1.26I+05 34Ce-144 4.891+06 2.02E+06 2.62E+05 0.00I+00 1.21E+06 1.34t+07 8.64t+05
!V Calen1stedperODCHequation2.3-22 ISSUI3 2-81
BV-1 and 2 ODCM fable 2.3-4 RVALUISFORBIAVIIYALLEYSITI (ares /yrpernCi/enmeter)
Pathway: Inhalation AgeGroup: Child Ruelide Bone Lier f. Body !hyroid Eidnry Lung GI-LLI 1E-3 0.00E+00 1.12E+03 1.12It03 1.12E+03 1.12t+03 1.12I+03 1.12E+03 2P-32 2.60E+06 1.14t+05 9.88I+04 0.00E+00 0.00!+00 0.00E+00 4.22E+04 3Cr-51 0.00!+00 0.00E+00 1.5G+02 8.55E+01 2.43E+01 1.70E+04 1.06t+03 4En-54 0.00E+00 4.291+04 9.51E+03 0.00E+00. 1.00!+04 1.58t+06 2.29t+04 5Fe-59 2.071+04 3.3d+04 1.671+04 0.00l+00 0.00l+00 1.271+06 7.07t+04 6Co-57 0.00E+00 9.03t+02 1.07t+03 0.00E+00 0.00!+00 5.071+05 1.32E+04 70058 0.00E+00 1.77I+03 3.16t+03 0.00E+00 0.00l+00 - 1.11E+06 3.4H+04 800-60 0.00!+00 1.31E+04 2.26I+04 0.00E+00 0.00!+00 7.07t+06 9.62E+04 9Zn-65 4.25E+04 1.13E+05 7.03E+04 0.00!+00 7.1d+04 9.95E+05 1.63E+04 10Rb-86 0.00E+00 1.98t+05 1.16+05 0.00!+00 0.00!+00 0.00E+00 7.99I+03 11Sr-89 5.991+05 0.00!+00 1.72E+04 0.00!+00 0.00!+00 2.16t+06 1.67I+05 12Sr-90 1.01It08 0.00!+00 6.44t+06 0.00E+00 0.00E+00 1.48I+07 3.43t+05 13 Y-91 9.16+05 0.00l!+00 2.4H+04 0.00E+00 0.00!+00 2.63E+06 1.84E+05 14Zr-95 1.90!+05 4.181+04 3.70E+04 0.00!+00 5.961+04 2.23E+06 6.111+04 15Rb-95 2.35E+04 9.181+03 6.55E+03 0.00E+00 8.62E+03 6.14E+05 3.70l+04 16Nb-97 4.291-01 7.10E-02 3.60I-02 0.00E+00 8.551-02 3.42E+03 2.78I+04 17Ho-99 0.00!+00 1.72E+02 4.26I+01 0 MI+00 3.92I+02 1.35E+05 1.27It05 18fc-99s 1.781-03 3.4BI-03 5.77I-02 0.11+00 5.071-02 9.51E+02 4.81E+03
- 19Rn-103 2.79I+03 0.00Et00 1.071+03 0.00E+00 7.03I+03 6.62E+05 4.48I+04 20En-106 1.361+05 0.00E+00 1.69I+04 0.00E+00 1.88+05 1.43E+07 4.29I+05 l
21Ag-110s 1.69I+04 1.1d+04 9.14I+03 0.00E+00 2.12t+04 5.4BI+06 1.00!+05 22Sb-124 5.7(I+04 7.40!+02. 2.00E+04 1.26t+02 0.00!+00 3.2G+06 1.60+05 23Sb-125 9.86+04 7.59t+02 2.07I+04 9.10!+01 0.00!+00 2.32t+06 4.03E+04 24fe-127s 2.49t+04 8.55E+03 3.02E+03 6.071+03 6.361+04 1.481+06 7.1G+04 25fe-129s 1.92E+04 6.85t+03 3.04E+03 6.33E+03 5.03E+04 1.76I+06 1.82E+05 26I-131 4.81t+04 4.81E+04 2.73E+04 1.62E+07 7.88I+04 0.00E+00 2.84Et03 27I-133 1.66t+04 2.03E+04 7.70E+03 3.85E+06 3.3BI+04 0.00E+00 5.481+03 28Cs-134 6.51E+05 1.01t+06 2.25I+05 0.00E+00 3.30!+05 1.21E+05 3.85E+03 29Cs-136 6.51t+04 1.71E+05 1.16t+05 0.00l+00 9.55I+04 1.45E+04 4.18t+03 30Cs-137 9.07t+05 8.25E+05 1.28I+05 0.00E+00 2.82E+05 1.04E+05 3.62E+03 31Ba-140 7.40!+04 6.48I+01 4.33E+03 0.00l+00 2.11t+01 1.74E+06 1.02t+05 32La-140 6.4E+02 2.25E+02 7.551+01 0.00E+00 0.00It00 1.83E+05 2.261+05 33Ce-141 3.92E+04 1.95t+04 2.90E+03 0.00E+00 8.55I+03 5.46t05 5.661+04 34Ce-144 6.77I+06 2.12E+06 3.61E+05 0.00l+00 1.17I+06 1.20!+07 3.891+05 Calculated per ODCH egnation 2.3-22 ISSUI3 2-82
n
~
i.
~
[, N-1and2DDON b(~y J fable'2.3-5:
I (./ i ' '
L; [IHLDISFORBIAVIIRLI2!Slft ,
- (area /Frpersci/csseter) -
i Pathuey:Imbalat' ion--
.AgeGroup: Infant '
1 l -Inclide. ~ Bone ~ Livers 7. Body Thyroid Eidner - Lens iGI-LLI
, 1 E 0.00840:.'6.475+02: 6.478+02 ~6.47842: 6.47842 6.475+02: 6.47I42:
2P-32. 2.05+06 1.12545 ~ . 7.7644 0.00E+00 ' O.00B+00 ; 0.00E+00 1.61I44 -
3 Cr-51 0.00I+00 0.00540 8.95I+01 5.7584 1 '1.32541: 1.28544: 3.57I+02
.Iun-54 .: 0.00l+00 2.53B+04 . 4.988+03 ' O.00E+00 ' 4.988+03 L 1.00546 < 7.06dA3 5Fe-59L 1.365 44 2.355 44 9.468+03 ~ 0.00840 ; ~ 0.00840 - 1.01I46 2.485+04
- 6 Co-57 : 0.00540 6.511+02'-6.411 42 0.00840~ 0.00I40 1 3.798+05: 4.MI+03
!7Co-58 O.00E+00 - 1.22t+03 ::1.82E+03 0.00E+00 0.00I40 7.77545 1.11B+04 1 8Co-60 0.00E+00. 8.028+03 ' 1.181+04 - 0.00840, 0.00840 . 4.51546 3.195+04 92n-65 1.93544 L 6.268+04 3.1154410.00540 3.25844 6.475+05 5.16 44:-
10lb-86. 0.00l+00 .1.90E+05 :8.82544 0.00I40 0.00840';0.00l+00 3.0G+03 -
11Sr-89 -3.98B45-10.00I40 1.14I44 . 0.00E+00 0.00I 4 0 2.03t+06.'6.40l+04 12Sr '4.09I47 0.00B+00 2.59846: 0.00540 . 0.00I40: 1.125+07' 1.31E+05
- ' 1
. 137 5.88845 0.00l+00 1.57544 0.005d0 0.00l+00 :2.458 4 6~ 7.0 5 4 4 143r-95' 4 1.15845 2.798+H 2.03t+04 . 0.00E+00 3.11544 ' 1.75846 2.175+04 E- ?
15Ib-95 1.57544 6.43543 .3.78843 0.00E+00 4.7543 4.798+05 - 1.27544
! 16Ib . 3 525-01 7.298-02 2.68-02 . 0.00B+00= 5.705-02 3.32543: 2.698+04 17 No-99~ 0.00l+00 1.65t+02 3.23E+01 ' O.00B+00 2.65842' 1.35545 4.875+04' 18fc-99m 1.GI-03 2.na!^3 3.72542 0.00540: 3.115-02 8 11I42 2.03B+03
'19In-103 2.02E+03 ' O.00l+00 : ti.?91+02 ~ 0.00E+00 4.2G+03 5.55 45' 1.61844 e 20In-106 8.68B44. 0.00l+00 1.00544 0.00E+M 1.07I 45 '1.168 47 1.68+05-
'23Sb125-3.79544 5.56I 4 2 1.10544 1.01142 0.00E+00 2.658 46 5.91544-5.175+04 t4.775+02 1:d9144 6.23I41. 0.00540 1.66 46 1.475+04 i
'" fi '
24 fe-127s. '1.67I 44 6.90l+03 2.07843' 4.87543 3.75844 1.31E+06 2.75 44 23 fe-129s - 1.41I 4 4: 6.095+03 2.23843 4.21I43' 3.18844 1.685+06 6.90544 1
26I-131 3.795+04 14.48 44 1.968+04 1. GI+07 5.18I44- 0.00540 1.06t+03 27I-133 1.32B+N -1.92144- 5.605 43 3.568+06 2.248 44 0.00I4 0 2.1 S+03'
-28Cs-134: 3.96845 7.03I45 7.45I 4 4 0.00540 1.90545 7.97I44 1.33I43 A 29Co-136- 4.85+N 1.35B+05 5.29544 0.00540 5.68 44 1.18544 1.43B+03 30Co-137- 5.495+05 ' 6.12E+05 - 4.55I4 4 :0.00540 1.72145 7.15 44 1.33B+03 l l
31Ba-140 5.60544 5.00B+01' 2.90543 -0. M I40 1.34841 1.60546 3.66 44 32La-140' 5.05I 4 2 2.00I42 5.1584 1 .0.00B+00 0.00840 1.68545 8.465+04 e
- 33Ce-141 2.77544 1.67t+04 1.998+03 0.00B+00 5.25543 5.17I 4 5 2.165+H 1.34Ce-144 3.19t+06 1.21546 1.76t+05 0.00I40' 5.385+05 9.84846 1.485+05 l
Calculatedper0D05egnation2.3-22 ISSUI3 b 2-83
o BV-1and2ODCH l 1
fable 2.3-6 RVALDISFORBIAVERVALLIISITI j (sqseter-ares /yrperuCi/sec) 1 Pathway: Ground i helide Bone Liver f. Body fbyroid lidney Lung GI-LLI 1H-3 0.00t+00 0.00!+00 0.00b00 0.00E+00 0.00l+00 0.00b00 0.00l+00 2P-32 0.09b00 0.00D00 0.00E+00 0.00D00 0.00D00 0.00h00 0.00D 00 3Cr-51 4.66b06 4.66b 06' 4.66b 06 4.66t+06 4.66b06 4.66b06 4.66b06 4Mn-54 1.39b09 1.398+09 1.39I+09 1.39h09 1.39b09 1.39b09 1.39b09 l 5Fe-59 2.73E+08 2.73D08 2.73b 08 2.73h 08 2.73E+0B 2.73h08 2.73 BOB 600-57 0.00l+00 0.00000 0.00t+00 0.00b 00 0.00h00 0.00b00 0.00b00 7Cc-58 3.79b08 3.79bO8 3.79b08 3.79 BOB 3.79 BOB 3.79b08 3.79b08 8 00-60 2.15b10 2.'5b10 2.15b10 2.15b10 2.15b10 2.15b10 2.15b10 9 Zn-65 7.47 BOB 7.471+08 7.47 BOB 7.47bO8 7.47bO8 7.47bO8 7.47bO8 10 Rb-86' 8.99b06 8.99b06 8.99b06 8.99b06 8.99b06 8.99b06 8.99b06 11Sr-89 2.16b04 2.16b04 2.16b04 2.161+04 2.16b04 2.16b04 2.16b04 12Sr-90 0.00t+00 0.00h00 0.00b00 0.00D00 0.00b00 0.00h00 0.00D00 13Y-91 1.07b06 1.07t+06 1.07D06 1.07b06 1.07b06 1.07bo6 1.07b06 14Ir-95 2.45bO8 2.45b08 2.45 BOB 2.45b68 2.45bO8 2.45bO8 2.45bO8 15Rb-95 1.37bO8 1.37bO8 1.37 BOB 1.37bO8 L37 BOB 1.37bO8 1.37bO8 16Nb-97 0.00h00 0.00t+00 0.00E+00 0.00E+00 0.00t+00 0.00b00 0.00t+00 17Ho-99 4.00b06 4.00b06 4.00D06 4.00b06 4.00b06 4.00D06 4.00b06 18fc-99 1.84b05 1.84b05 1.84b05 1.84D05 1.84b05 1.84b05 1.84h05 19Rn-103 1.0BbO8 1.08 BOB 1.08bO8 1.08bO8 1.08bO8 1.08bO8 1.08b06 20Rn-106 4.22bO8 4.22 BOB 4.22 BOB 4.22bO8 4.22bO8 4.22h08 4.22bO8 21Ag-110s 3.44b09 3.4H+09 3.44t+09 3.44bo9 3.44b09 3.44b09 3.4G+09 22Sb-124 0.00b00 0.00b00 0.00b00 0.00D00 0.00b00 0.00b00 0.00D00 23Sb-125 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 24fe-127: 9.17b04 9.17b04 9.17b04 9.17b04 9.17b04 9.17b04 9.17D04 25fe-129s 1.98bO7 1.98bO7 1.98bO7 1.98bO7 1.98bO7 1.98bO7 1.98bO7 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 28Cs-134 6.86b09 6.86b09 6.86h09 6.86b09 6.86b09 6.86b09 6.86b09 29Cs-136 1.51 BOB 1.51t+08 1.51 BOB 1.51bO8 1.51bO8 1.51 BOB 1.51bO8 30Cs-137 1.03D10 1.03D10 1.03b10 1.03D10 1.03b10 1.03D10 1.03D10 31Ba-140 2.05bO7 2.05bO7 2.05t+07 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 CalenlatedperODCHequation2.3-23 ISSUI3 2-84
K BV-1and2ODCH
[h fable 2.3-7
'%)
RVALUISFORBIAVIRVALLEYSlft (89 meter-area /yrpernCi/sec)
Pathway:, Vegetation AgeGroup: Adult luellde Bone Liver f. Body .Thyrold lidney Lang GI-LLI 1H-3 0.00l+00 2.26I+03 2.261+03 2.261+03 2.261+03 2.261+03 2.261+03 2P-32 1.40E+09 8.74t+07 5.43I+07 0.00l+00 0.00l+00 0.00l+00 1.58t+08 3Cr-51 0.00t+00- 0.00l+00 4.64t+04 2.78t+04 1.02t+04 6.16I+04 1.171+07
< 4Hn-54 0.00l+00 3.13t+08 5.971+07 0.00E+00 9.311+07 0.00E+00 9.591+08 5Fe-59 1.261+08 2.96I+08- 1.14H+08 0.00t+00 0.00l+00- 8.281+07 9.888+08 6Co-57' O.00l+00 1.171+07, 1.95t+07 0.00E+00 0.00l+00 0.00E+00 2.971+08 7Co-58 0.00l+00 3.071+07 6.898+07 0.00l+00 0.00l+00 0.00E+00 6.23E+08 8Co-60 0.00l+00 1.678+08 3.69I+08 0.00l+00 0.00l+00 0.00E+00 3.14R+09 9Zn-65 3.178+08 1.01t+09 4.56t+08 0.00E+00 6.75I+08 0.00l+00 6.36I+08 10Ib-86 0.00l+00 2.19t+08 1.02I+08 0.00t+00 0.00l+00 0.00l+00 4.33E+07 11Sr-89 9.971+09 0.00l+00 2.865+08 0.00!+00 0.00l+00 0.00E+00 1.60l+09 ,
12Sr-90 6.05t+11 0.00l+00 1.48E+11 0.00l+00 0.00l+00 0.00!+00 1.75t+10 f3 13Y-91 5.11t+06 0.00It00 1.371+05 0.00!+00 0.00E+00 0.00E+00 2.81I+09 V 14Zr 15lb-95 1.171+06~ 3.778+05 2.55E+05 0.00l+00 5.91E+05 0.00l+00 1.19I+09 1.42E+05 7.92E+04 4.26t+04 0.00l+00 7.83I+04 0.00E+00 4.811+08 l
16Nb-97 2.161-06 5.461-07 1.99I-07 0.00E+00 6.371-07 0.00l+00 2.021 17H0-99 0.00l+00 6.15t+06 1.171+06 0.00l+00 1.39E+07 0.00E+00 1.43t+07 18fe-99a 3.10E+00 8.77t+00 1.12E+02 -0.00l+00 1.33E+02 4.30l+00 5.19t+03 19Ra-103 4.77t+06 0.00l+00 2.06I+06 0.00E+00 1.82t+07 0.00l+00 5.571+08 ;
20Rn-106 1.93E+08 0.00E+00 2.441+07 0.00E+00 3.72t+08 0.00l+00 1.251+10 j 21Ag-110s 1.05E+07 9.75E+06 5.79t+06 0.00!+00 1.92t+07 0.00l+00 3.98t+09 ;
22Sb-124 '1.04E+08 1.96t+06 4.11E+07 2.51t+05 0.00E+00 8.071+07 2.94I+09 ,
23Sb-125 1.371+08 1.53E+06 3.25t+07 1.391+05 0.00l+00 -1.05E+08 1.50l+09 24 fe-127: 3.498+08 1.25t+08 4.26t+07 8.92X+07 1.42t+09 0.00l+00 1.171+09 25fe-129s 2.511+08 9.38I+07 3.98I+07 8.64E+07 1.05I+09 0.00l+00. 1.27I+09 j i
26I-131 8.08t+07 1.16t+08 6.62t+07 3.79I+10 1.985+08 0.00l+00 3.05I+07 i 27I-133 2.091+06 3.63t+06 1.111+06 5.33t+08 6.33I+06- 0.00l+00 3.261+06 )
28Cs-134- 4.67I+09 1.11E+10 9.08I+09 0.00l+00 3.591+09 1.19I+09 1.94I+08 1 29Ce-136 4.27I+07 -1.691+0B 1.211+08 0.00It00 9.38I+07 1.29I+07 1.91t+07 30Cs-137 6.36I+09 8.70l+09 5.70l+09 0.00E+00 2.95I+09 9.811+08 1.681+08 l' 31Ba-140 1.29I+08 1.61t+05 8.42t+06 0.00l+00' 5.49t+04 9.24E+04 2.65E+08 i
j 32La-140 1.981+03 9.971+02- 2.63t+02 0.00E+00 0.00l+00 0.00l+00 7.32E+07
! 33Ce-141 1.971+05 1.33E+05 1.51E+04 0.00!+00 6.19I+04 0.00l+00 5.10l+08 3(Ce-144 3.291+07 1.38t+07 1.778+06 0.00l+00 8.16t+06 0.00lt00 1.111+10 h l l Allnuclides(exceptH-3)calenlatedperODCHequation2.3-26 H-3calculatedperODCHegnation2.3-29 ISSUI3 2-85 !
Bi-1and2ODCH Table 2.3-8 1VALUESFOR!EAVERVALLEYS1fE (sqseter-ares /yrperuCi/see)
Pathway-Vegetation AgeGroup: Teen Nuclide Bone Liver f. Body Thyroid Eldney Lung GI-LLI 1 E-3 0.00E+00 2.59E+03 2.59E+03 2.59E+03 2.59t+03 2.59E+03 2.59E+03 2P-32 1.61E+09 9.98E+07' 6.24E+07 0.00E+00 0.00E+00 0.00E+00 1.35E+08 3Cr-51 0.00!+00 0.00E+00 6.17t+04 3.43E+04- 1.35E+04 8.81E+04 ' 1.04E+07 4Ha-54 0.00E+00 4.54E+08 9.01E+07 0.00E+00 1.36E+08 0.00E+00 9.32E+0B 5Fe-59 1.79E+08 4.19E+0B 1.62E+08 0.00E+00 0.00E+00 1.32E+0B 9.90E+0B 600-57 0.00E+00 1.79E+07 3.00E+07 0.00E+00 0.00E+00 0.00E+00 3.33E+08 700-58 0.00E+00 4.361+07 1.00!+08 0.00E+00 0.00E+00 0.00E+00 6.01E+08 8Co-60 0.00E+00 2.49t+08 5.60E+08 0.00E+00 0.00E+00 0.00E+00 3.24E+09 9Zn-65 4.24E+08 1.47E+09 6.87E+08 0.00E+00 9.(2E+08 0.00E+00 6.23E+08 10Rb-86 0.00E+00 2.74E+08 1.29E+08 0.00E+00 0.00E+00 0.00E+00 4.05E+07 11St-89 1.51E+10 0.00E+00 4.34E+08 0.00E+00 0.00E+00 0.00E+00 1.80E+09 12Sr-90 7.51E+11 0.00E+00 1.85E+11 0.00E+00 0.00E+00 0.00E+00 2.11E+10 13Y-91 7.84E+06 0.00E+00 2.10E+05 0.00E+00 0.00E+00 0.00E+00 3.21E+09 14Zr-95 1.72E+06 5.43E+05 3.74E+05 0,00E+00 7.98E+05 0.00E+00 1.25E+09 15 lib-95 1.92E+05 1.07t+05 5.87E+04 0.00E+00 1.03E+05 0.00E+00 4.56E+08 16Eb-97 2.00E-06 4.97E-07 1.81E-07 0.00E+00 5.818-07 0.00E+00 1.19E-02 17Ho-99 0.00E+00 5.65E+06 1.08E+06 0.00E+00 1.29t+07 0.00E+00 1.01E+07 18fe-99: 2.74E+00 7.64E+00 9.90E+01 0.00E+00 1.14I202 4.24!+00 5.02E+03 19Bu-103 6.82E+06 0.00E+00 2.92E+06 0.00E+00 2.41E+07 0.00E+00 5.70!+08 20En-106 2.35E+08 0.001,00 3.90E+07 0.00!+00 5.97E+08 0.00E+00 1.48E+10 21Ag-110s 1.52E+07 1.43E+07 8.72E+06 0.00!+00 2.74E+07 0.00E+00 4.03E+09 22Sb-124 1.54E+08 2.84E+06 6.02E+07 3.50E+05 0.00E+00 1.35E+08 3.11E+09 23Sb-125 2.1(E+08 2.3(E+06 5.01E+07 2.05E+05 0.00E+00 1.88E+08 1.67E+09 24fe-127: 5.52E+08 1.96E+08 6.56Et07 1.31E+0B 2.24E+09 0.00E+00 1.37t+09 25fe-129s 3.62E+08 1.34E+0B 5.73E+07 1.17t+08 1.51E+09 0.00E+00 1.36E+09 26'l-131 7.69E+07 1.08t+0B 5.78E+07 3.14E+10 1.85E+08 0.00E+00 2.13E+07 271-133 1.94E+06 3.2SE+06 1.00E+06 4.59E+0S 5.77E+06 0.00E+00 2.49E+06 28Cs-134 7.10E+09 1.671+10 7.75E+09 0.00!+00 5.31E+09 2.03E+09 2.08E+08 29Cs-136' 4.38E+07 1.72E+08 1.16E+08 0.00E+00 9.37t+07 1.48t+07 1.39E+07 30Cs-137 1.01E+10 1.35E+10 4.69E+09 0.00E+00 4.59E+09 1.78E+09 1.92E+08 31Ba-140 1.38E+08 1.69t+05 8.90E+06 0.00E+00 5.74E+04 1.1(E+05 2.13E+08 32La-140 1.81E+03 8.88E+02 2.36E+02 0.00E+00 0.00E+00 0.00E+00 5.10E+07 33 Ce-141 2.83E+05 1.69t+05 2.17E+04 0.00E+00 8.90E+04 0.00E+00 5.41E+08 34Ce-144 5.27E+07 2.1BE+07 2.83E+06 0.00E+00 1.30E+07 0.00!+00 1.33E+10 All nuclides (except H-3) calculated per ODCH egnation 2.3-26 H-3calculatedperODCHequation2.3-29 ISSUE 3 2-86
+
15.M h.
, , v
.r-W-1 and 2 0901 Table 2.3-9 ~ ,
.s.
- i ,
I 1&LOIS 705 IIATR VALLI 7 SITI y ,
- ist meter-arse /Fr per sci /see)
% f
~.. .
,. Fatheir:Yegetation-N 4AgeGroup: Child-R 4 Ine11de ? . Bone i ' . Liver. f. Body- Thyroid.. IidneyL .Lang .GI-LLI:
1E-3-- . 0.008+00 : 4.01543 ~ 4.01843 4.01E+03 4.01I43 L 4.01843. 4.01843 4
-2P-32 3.37549' 1.58548M 1.30848 0.00540 0.00l+00 - 0.00l+00 :9.32B+07' 3Cr-51L : 0.00l+00 : 0.00l+00 : 1.175+05 . 6.50544 - 1.7844 .1.19I45 , 6.21E+06
-4Ms-54 0.0Ht00 6.65E+08 1.77548 0.00540. : 1.8848 - 10.00E+00 - 5.58848 :
-5Fe-59 3.98I4816.4354813.20I48 0.00l+00 0.00B+00-' 1.878 4 8 6.70E+08.
-6Co-57 0.00E+00 2.99t+07 6.04t+07J 0.00E+00 0.00l+00: 0.00l+00 2.45B+08
,, =7Co 0.00I40 6.44B+07 1.97I+08 0.00t+00 ' ' 0.00I401 0.00540 3.7848, 8Co-001- 0.00l+00 3.788+085 1.12B+09. 0. M I+00 0.00l+00 0.00I 4 0 2.1H+49.
9In-65= 8.13t+08~ 2.17t+09 1.35I49 - 0.00l+00. 1.36B+09 . 0.00I40 3.80l+08
, 10Ib-86 :0.008 4 0 :4.52t+08' 2.78I+08 " 0.00l+00 0.005 40 0. M I+00 --2.91I 47 i
- 11Sr-89 : 3.60B+10 0.00l+00 1.03B+09 i 0.00E+00 - 0.00540. 0.00t+00 1.39549'
- 12 Sr-90 1.24B+12 0.00E+00 3.15!+11 0.00I40 0.00540.: 0.00E+00 1.675+10.
+ ' ' 13Y-91: - 1.NI+07 . 0.00I40 4.99I 4 5 0.00840: 0.00E+00 0.00E+00 2. # 84 9
~
14Zr-95 3.86t+06 ' 8.48845 ~ 7.55I45 0.00l+00 1.21546 0.00B+00 8.85548 15lb 4.11I451 1.80545' 1.14I4510.00t+00 ~ t 1.50545 0.00l+00 2.NI48 )
~16lb-97 3.858-06 6.595-07, 3.08I-07' O.00540 ' 7.318-07 ~ 0.00840 2.035-01 17No-99 0.00l+00 7.11t+06' 1.91E+ H 0.00l+00 1.6584 7 ~ 0.00E+00 6.385+06
~ tofc-99 4.71540 . 9.24B+00 1.53I+02: 0.00I 40~ 1.38 42: 4.88 +00 '5.2654 3
'19In-103 1.53B+07- 0 M I+00' 5. MI+06' O.00540 3. NI4 7. 0. MI+00. 3.978 48 20En-106_ 7.45E+08 . 0.00E+00 F 9.30E+07 0.00540 1.01I 4 9 0.00E+M 1.15+10 y '
21Ag.110m 3.21547 2.17I47 a 1.75+07: 0.00540 4.0 G+07 0.00B+00 2.585+09 22Sb-1241 3.52E+08 4.57I+N 1.28t+08: 7.77t+05 0.00540 .1.958 4 8 2.20E+09~
23 Sb-125 4.998+08 3.85t+06. 1.05I 48 4.63E+05 0.0H+00 . 2.78I+08. 1.19t+09 24fe-127aE 1.32B+09 3.56848 1.575+08 3.16t+08 3.77t+09 0.00E+00 1.07I49 u:'
- 25fe-129m 8.415+08 2.35t+M , 1.31E+08 2.71148 2.478+09 0.00B+00 1.03I+09 J26I-131 1.48t+08 1.44E+08 L8.17I 47 4.76I+10 2.368+08 0.00l+00 1.28t+07 m 27I-133 3.538+06 4.37I 4 6 1.65B+M 8.12B 48 7.28I+06' O.001 40 -1.7 5 +06
' @"' , 28Cs-134' -1.60t+10='2.63B+10 ' 5.55B+09 0.00t+00 8.15E+09 2.95+09 1.42I 4 8 29Co-136 8.2G+07 2.275 48 1.47I+08 0.00540 1.215+ M 1.80E+07 7.95 4 6 30Cs-137-- 2.3E+101 2.298+10 3.38549 0.00840 7.46I49 2.68I 4 9 1.45 48 31Ba-140 2.771+08 ' 2.42I47- 1.62E+07 ~ 0.00840' 7.89I44 '1.45I45 1.4H48 32La-140 3.25843 - 1.12 43' 3.83842 0.00840 0.00I 4 0 0.00I40 3.16I+07 l 33Co-141 6.568 45 3.275 45 4.86545 0.00l+M 1.43B+05 0.00I40 4.08848
.34Ce-144 1.27848' 3.98847 6.78I+M 0.00l+00 2.21t+07 0.00l+00 1.04B+10 Allnuclides(exceptH-3)calenlatedperODCUequation2.3-26
- I-3.calaisted per 0905 egnation 2.3-29 ;
ISSUI3 87
--G:-
BV-1and2ODCH Table 2.5-10 RVALUISFORBIAVIIVALLI7S1f!
(sqaeter-area /yrpernC1/sec)
Patbvay: Heat AgeGroup:Adolt Ruelide Bone Liver f. Body Ibyroid tiduey Lung GI-LLI 1E-3 0.00E+00 3.25bO2 3.25bO2 3.25E+02 3.25I+02 3.25t+02 3.25bO2 2P-32 3.95b09 2.46bO8 1.53b08 0.00 BOO 0.00D00 0.00D00 4.44bO8 3Cr-51 0.00b00 0.00b00 5.86bO3 3.50bO3 1.291+03 7.78bO3 1.47I+06 4En-54 0.00l+00 6.491+06 1.24b06 0.00D00 1.93b06 0.00D00 1.99b07-5Fe-59 2.14bO8 5.04f+0B 1.93bO8 0.00b00 0.00D00 1.41bO8 1.66b09 6Co-57 0.00b00 4.01b06 6.66h06 0.00!+00 0.00!+00 0.00b00 1.02 BOB 7 Co-58 0.00!+00 1.42bO7 3.1BbO7 0.00!+00 0.00b00 0.00h00 2.87bO8 800-60 0.00E+00 5.12bO7 1.13E+08 0.00!+00 0.00lt00 0.00!v00 9.61t+08 9Zn-65' 2.54E+08 8.03 BOB 3.66D08 0.00E+00 5.41bO8 0.00D00 5.10bO8 10Rb-86 0.00E+00 4.111+08 1.92bO8 0.00!+00 0.00!+00 0.00l+00 8.1H+07 11Sr-89 2.41 BOB 0.00t+00 6.92h06 0.00D00 0.00l+00 0.00b00 3.87bO7 12Sr-90 8.411+09 0.00h00 2.06h09 0.00D00 0.00!+00 0.00h00 2.43bO8 13Y-91 8.S4E+05 0.00D00 2.3Sb04 0.00b00 0.00b00 0.00h00 4.92E+08 14Zr-95 1.47t+06 4.71b05 3.19b05 0.00t+00 7.39b05 0.00b00 1.49t+09 15Ib-95 1.89b06 1.05t+06 5.64t+05 0.00b00 1.04t+06 0.00l+00 6.371+09 16Eb-97 titttttttttttttttttttttttttttttti 0.00l+00stsstststst 0.00E+00tttttttttts 17 h-99 .0.00b00 8.51h04 1.62h04 0.00b00 1.93h05 0.00!+00 1.97b05 18fe-99: 3.83I-21 1.081-20 1.38I-19 0.00b00 1.641-19 5.301-21 6.401-18 19Rn-103 8.571+07 0.00b00 3.69bO7 0.00D00 3.27bOS 0.00D00 1.00b10 20 h-106 1.97b09 0.00t+00 2.49t+08 0.00b00 3.80D09 0.00D00 1.27b11 21Ag-110m 4.77b06 4.41b06 2.62b06 0.00b00 8.67h06 0.00l+00 1.80h09 22Sb-124 0.00t+00 0.00b00 0.00b00 0.00t+00 0.00!+00 0.00b00 0.00b00 23Sb-125 0.00R+00 0.00D00 0.00b00 0.00E+00 0.00!+00 0.00b00 0.00t+00 24fe-127: 8.38bO8 3.00t+08 1.02t+08 2.141+08 3.40b09 0.00 BOO 2.81E+09 25fe-129a 9.33E+08 3.48t+08 1.48bO8 3.21 BOB 3.89b09 0.00b00 4.70D09 26I-131 9.13b06 1.31bO7 7.48b06 4.281+09 2.24bO7 0.00 BOO 3.45E+06 271-133 3.12E-01 5.42I-01 1.65t-01 7.96b01 9.461-01 0.00t+00 4.871-01 28Cs-134 4.53 BOB 1.06h09 8.81bO8 0.00b00 3.49b06 1.16bO8 1.89h07 29Cs-136 1.02bO7 4.0(I+07 2.91bO7 0.00E+00 2.25bO7 3.08I+06 4.59I+06 30Cs-137 5.90bO8 8.06t+08 5.26 BOB 0.00!+00 2.74bO8 9.10bO7 1.56bO7 31Ba-140 2.44bO7 3.06b04 1.60b06 0.00b00 1.04b04 1.75b04 5.02bO7 32 La-140 3.168-02 1.59E-02 4.21bO3 0.00b00 0.00b00 0.00b00 1.17bO3 33Ce-141 1.161+04 7.83bO3 8.88bO2 0.00b00 3.64bO3 0.00E+00 2.99h07 34Ce-144 1.03b06 4.32t+05 5.55b04 0.00!+00 2.56b05 0.00D00 3.50bO8 Allnuclides(exceptH-3)calenlatedperODCMegnation2.3-25 H-3calenlatedperODCMegnation2.3-30 ISSUI3 2-88 q
i
- i .
N-1and209C5-fable 2.3-11.
.V .
I.1ALUIS FOR IIATII1&LLIf SITI .
, (seseter-ares /yrpersci/sec)
- Pithesy:Best.
x.Ase'Groep:' feen .
Baclide- Bone Liverj f.' Body Thyrold Ildner .LeagL 'GI-LLI 1H-31 0.00E+00 1.96 4 2 1.98 4 2 1.94I42 1.94t+02. 1.9 6+02 1.s* N 2J
- 2P-32. 3.34I4 9 '2.075+08' 1.295+06 ' O.00l+00 :0.00l+00 0.00E+00 2.80E+08
.3Cr51 .0.00l+# 0.00E+00/ 4.69t+03. 2.60l+03 1.03I43.1.695+03 : 7.88545 -
4 h -54 0.00840 ' 4.95t+06 l t 9.81545 . 0.00I40 .1.4846 '0.00E+00' 1.015+07 5Fe-59 7 _1.71X+08 4.00l+08 "1.5848 . 0.00540 n 0.MI40 : 1.268+08 9 ' 1 45E+08 ~
.a ~
4- "
6Co-57 0.00E+00 3.228+06 5. GI+M 0.00I40 0.00540 0.00E+00 '6.01E+07
-7Co-581 0.00I 40. 1.098 47 2.52B+07 0.00t+00 - 0.005 4 0 0.00t+00 1.51B+08 - "I BCo-60c 0.00l+00 - 3.97547 : 8.95E+07 ' ' O.00l+00 0.005+00 0.00I40 5.17I48:
9Zn-65 1.79548 6.215+06 - 2.9054 8: -0.00E+00 3.978+08- 0.005 40 2.63848-10Ib-86 0.00l+00 - 3.43548 1.61848 -0.00I40 0.00840. 0.00B+00 5.08I 4 7 -
11Sr-89 2.03I48 - 0.00E+00 - 5.83t+06 0.00I40 0.00E+00 .0.0054 0 2.42t+07 12Sr-90 5.44E+09 0.00E+00. 1.34E+09 0.00l+00 0.00l+00 0.00l+00 .1.55 48' c '; 13Y 7.53t+05 0.00I40. 2.02I44. 0.00I40 0.00l+00 0.00840- 3.098+08 '
'l 14Zr-95 1.18846 3.71145 ' 2.55B+05: 0.00l+00 < 5.45I45 0'.00I40 : 8.56I 4 8 '
E '
15lb-95 1.47t+06 8.171+05 4.50545 .9.00l+00 7.92B+05 0.00l+00 - 3. 88+09 16 Ib47 ********************************* 0.00B+ M *********** 0.00I 40 ***********
17Ho-99: 0.00t+00 7.03t+04 '1.3G+04 0.00l+00 1.61E+05. 0.00E+00 ~ 1.268+05 -
18fe-99 .3.04I-21 8.481-21 1.108-19 0.00I 4 0 1.268-19 ' 4.711-21 5.571-18 19 h-103' 6.98I 47 .0.00t+00 2.98t+07' O.00t+00 2.48 48 0.00I 4 0 5.83849
- 20In-106
'j y - 1.28549 ' O.00I+00. 2.091+08 0.00l+00 3.198+09 0.00540 - 7.94t+10 -
21Ag-110s. 3.61E+06 3.42E+06 ' 2.08I46 0.00t+00:'6.52t+06 0.00l+M 9.60l+08 22Sb-124 0.00E+00 0.00E+001'O.00l+00 0.00E+00 -0.00I 40 0.00I 40L 0.00l+00 23Sb-125 0.00I 4 0 0.00I40 - 0.00l+00 0.00t+00 0.00l+00 - 0.00I40 0.00I 4 0 24fe-127s 7.078+08 , 2.515+08 8.415+07 1.688+08-- 2.8754 9 0.00t+00 1.76I49.
- 25fe-129s 7.82I48 2.90548 1.2G+M 2.52E+08: 3.27I49 0.00I+ M 2.93I+09 1
26I-131 7.59546 1. MI 47. 5.71R+M 3.10l+09 1.8M47 0.005 40 2.10l+06
'27.1-133 2.61I-01 4.42I41. 1.358-01 ' 6.175+01 7.755-01 0.00E+00 3.34I-01 28Cs-134 : 3.80l+08 ' 8.48848 : - 3.93E+08 . : 0.00l+00 2.69t+08 1.03E+08 1.05I+07 29Cs-136 7.98I46 3.18 47 2.11t+07 0.00B+00 1.71547' 2.69846 2.53E+06 30Cs-137 4.90l+08. 6.51148 f 2.27I48 0.00l+00 2.22I48 8.61E+07 9.27846
- m '
, '31la-140 2.02I47 2.475+04: 1.30546 0.00I 4 0 8.38543 1.66I+04 3.11t+07 32La-140 -2.605-02 1.288-02' 3.40I-03 0.00I40 0.00I40 0.00540. 7.338+02 L 33Ce-141:
9.72843' 6.49I43 7.46842 0.00I40 3.068+03 0.008+00 1.86t+07 34Ce-144 8.72345 3.61845 4.68I 4 4 0.00l+00 2.15t+05 0.00l+00 2.19I 4 8 Al'nuclides(exceptH-3)calculatedpertXBequation2.3-25 L "-3calculatedperODCBegnation2.3-30 ISSUI3 2-89 l
J
BV-1and2ODCM fable 2.3-12 RVALUISF01BIAVIRVALLifSITI (egmeter-ares /yrperuCi/see)
Pathway: Heat AgeGroup: Child hellde Bone Liver T. Body Thyroid Ildner Lung GI-LLI 1H-3 0.00E+00 2.34X+02 2.34I+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02
-2P-32 6.29E+09 2.94t+08 2.43E+08 0.00E+00 0.00E+00 0.00E+00 1.74E+08 3Cr-51 0.00t+00 0.00E+00 7.311+03 4.06I+03 1.11E+03 7.41E+03 3.88I+05 4Hn-54 0.00t+00 5.66t+06 1.51E+06 0.00!+00 1.591+06 0.00E+00 4.75I46 5Fe-59 3.04I+08 4.91t+08 2.45Et08 0.00E+00 0.00E+00 1.42E+08 5.12E+08 6Co-57 0.00E+00 4.21I46 8.52146 0.00l+00 0.00Id0 0.00l+00 3.45E+07 7Co-58 0.00t+00 1.28I+07 3.911+07 0.00t+00 0.00I00 0.00l+00 7.45E+07 800-60 0.00!+00 4.72E+07 1.39t+08 0.00t+00 0.00l+00 0.001100 2.61t+08 9Zn-65 2. * *08 7.15E+08 4.44E+08 0.00E+00 4.50l+08 0.00I40 1.25t+08 10Rb-86 0.00s00 4.87t+08 2.998+08 0.00E+00 0.00E+00 0.00l+00 3.13E+07 11St-89 3.85E+08 0.00!+00 1.10!+07 0.00E+00 0.00E+00 0.00l+00 1.491+07 12St-90 7.03t+09 0.00E+00 1.78I+09 0.00E+00 0.00l+00 0.00l+00 9.471+07 13T-91 1.42I+06 0.00t+00 3.81E+04 0.00!+00 0.00E+00 0.00E+00 1.90l+08 14Zr-95 2.09I+06 4.591+05 4.09t+05 0.00E+00 6.571+05 0.00l+00 4.798+08 15Rb-95 2.54I+06 9.90!+05 7.07td5 0.00E+00 9.30l+05 0.00E+00 1.83I+09 16Ib-97 ststststsstststsstssststsstssstst 0.00I40 steststssts 0.00ft)0 tttstssssst 1750-99 0.00X+00 9.791+04 2.42E+04 0.00E+00 2.09I+05 0.00I40 8.09t+04 18fc-99 5.33I-21 1.051-20 1.73I-19 0.00l+00 1.52I-19 5.311-21 5.95I-18 19Rn-103 1.26t+08 0.00l+00 4.85E+07 0.00!+00 3.18I 4 8 0.00!+00 3.2H+09 20 In-106 3.12E+09 0.00t+00 3.89t+08 0.00!+00 4.21E+09 0.00E+00 4.8!!+10 21Ag-110:. 5.991+06 4.04I+06 3.23E+06 0.00!+00 7.53I+06 0.00l+00 4.81t+08 22Sb-124 0.00l+00 0.00l+00 0.00!+00 0.00E+00 0.00I40 0.00l+00 0.00E+00 23Sb-125 0.00l+00 0.00l+00 0.00!+00 0.00E+00 0.00!+00 0.00l+00 0.00I40 24 fe-127s 1.33E+09 3.59t+08 1.581+08 3.19I+08 3.80E+09 0.00I+00 1.08I+09 25fe-129s 1.471+09 4.111+08 2.29t+08 4.75E+08 4.33t+09 0.00!d0 1.80!+09 26 I-131 1.411+07 1.42E+07 8.04tt06 4.68I+09 2.32I+07 0.00!+00 1.26t+06 271-133 4.8(I-01 5.991-01 2.27I-01 1.11E+02 9.98I-01 0.00E+00 2.411-01 28Cs-134 6.35E+08 1.04E+09 2.20t+08 0.00Edo 3.23I+08 1.16I+08 5.62Id6 29Cs-136 1.38I+07 3.78t+07 2.45E+07 0.00t+00 2.01E+07 3.00l+06 1.33Id6 30Cs-137 9.02I4B B.63t+08 1.271+08 0.00!+00 2.81I+08 1.01t+08 5.40806 l 31Ba-140 3.72t+07 3.261+06 2.17t+06 0.00E+00 1.06t+04 1.94E+04 1.89I+07 32La-140 4.76I-02 -1.66I-02 5.611-03 0.00t+00 0.00E+00 0.00!+00 4.63t+02 33Ce-141 1.83Id4 9.13E+03 1.36t+04 0.00E+00 4.00t+03 0.00!+00 1.14E+07 34 Ce-144 1.64t+06 5.15t+05 8.77I+04 0.00E+00 2.85E+05 0.00!+00 1.3@08 Allnuclides(exceptB-3)calenlatedperODCMequation2.3-25 H-3calculatedperODCHegnation2.3-30 ISS R 3 2-90
(
I L _
Bi-1and2ODCX i
'73 fable 2.3-13
- b RVALUISFORBIAVIIVALLifS1f!
(sg meter-ares /rr per Ci/see) 1 Pathway:CowHilk Age Group - Adult Inclide Bone Liver .f. Body Thyroid Ildney Lang GI-LLI 1H-3 0.00E+00 7.631+02. 7.63E+02 7.63E+02 7.63I+02 7.63E+02 7.63t+02 I 2 P-32 _ 1.45E+10 9.011+08 5.60148 0.00E+00 0.00l+00 0.00l+00 1.63I49 !
3Cr-512 0.00E+00 0.00l+00 2.381+04 1.42E+04 5.24I+03 3.15E+04 5.988+06 4Hn-54 0.00E+00 5.95I+06 1.13E+06 0.00t+00 1.77I+06 0.00E+00 1.82E+07 5Fe-59 2.40E+07 5.63E+07 2.161+07 0.00l+00 0.00E+00 1.57I+07 1.881+08 600-57 0.00E+00 9.10!+05 1.51I46 0.00E+00 0.00X+00 0.00I40 2.31E+07 7Co-58 0.00E+00 3.671+06 8.22I 4 6 0.00t+00 0.00l+00 0.00E+00 7.43E+07 8Cc-60 0.00E+00 1.12E+07 2.46tt07 0.00I 4 0 0.00l+00 0.00I40 2.10E+08 9Zn-65 9.80E+0B 3.12t+09 1.411+09 0.00t+00 2.091+09 0.00l+00 1.961+09 10Ib-86 0.00l+00 2.198+09 1.02149 0.00E+00 0.00l+00 0.008+00 4.32E+08 k .11Sr-89 1.16I+09 0.00l+00 3.33E+07 0.00I 4 0 0.00E+00 0.00t+00 1.861+08 j 12 Sr 3.16t+10 0.00E+00 7.76I 49 0.00l+00: 0.00l+00 0.00I40 9.14E+08 4
+ 1 13T-91 14Zr-95 6.78I+03 0.00l+00 1.81E+02 0.4+00 0.00!+00 0.00l+00 3.73I+06 7.40l+02 2.37I+02 1.61E+02 0.00000 3.72E+02 0.00E+00 7.52I+05 V 15Ib-95 6.77I+04 3.771+04 2.03I44 0.00l+w 3.72t+04 0.00l+00 2.298+08
]
16Ib-97 2.811-12 7.118-13 2.601-13 0.00E+00 8.30I-13 0.00I40 2.62I-09 ;
17No-99 0.00t+00 2.11E+07 4.01E+06 0.00t+00 4.77tt07 0.00E+00 4.88t+07 j 18fe-99: 2.83I+00 7.991+00 '1.021+02 0.00E+00 1.21E+02 3.91E+00 4.73X+03 l 19Rn-103 8.298+02 0.00l+00 3.57t+02 0.00I40 3.161+03. 0.00E+00 9.68I+04 !
20In-105 1.43E+04 0.00E+00 1.811+03 0.00l+00 2.77I+04 0.00l+00 9.27145 :
21Ag-110s 4.16t+07 3.84E+07 2.28I+07 0.00E+00 7.56t<07 0.00t+00 1.57I+10 22Sb-124 0.00E+00 0.00l+00 0.00!+00 0.00E+00 0.00l+00 0.00l+00 0.00E+00 23Sb-125 0.00l+00 0.00t+00 0.00E+00 0.00t+00 0.00l+00 0.00l+00 0.00I40 {
24fe-127a 3.44t+07 1.23I+07 4.19I+06 8.79546 1.40t+08 0.00l+00 1.15E+08 25fe-129s 4.95E+07 1.85E+07 7.84t+06 1.70l+07 2.07t+08 0.00E+00 2.491+08 I 26I-131 2.52t+0B 3.60l+08 2.06t+08 1.18I+11 6.17t+08 0.00l+00 9.50B+07 27I-133 3.29t+06 5.72t+06 1.75I 4 6 8.411+08 9.99t+06 0.00I 4 0 5.14t+06 .
28Cs-134 3.89t+09 9.271+09 7.58I+09 0.00E+00 3.00l+09 9.96t+08 1.62148 29 Cs-136 - 2.23E+08 8.82148 6.35t+08 0.00E+00 4.91E+08 6.73E+07 1.00R+08 30Cs-137 4.99t+09 6.82I+09 ~4.47t+09 0.00t+00 2.32E+09 7.70148 1.32E+08 31Ba-140 2.28t+07 287I+04 1.491+06 0.00l+00 9.74E+03 1.64t+04 4.70E+07 32La-140 3.84I+00 1.93E+00 5.11I-01 0.00E+00 0.00t+00 0.00!+00 1.42E+05 33Ce-141 3.99t+03 2.70l+03 3.061+02 0.00E+00 1.25E+03 0.00l+00 1.03E+07 34Ce-144 2.54E+05 1.06t+05 1.36I+04 0.00E+00 6.29144 0.00I40 8.58I47 (D
\_/ Allnuclides(exceptH-3)calculatedperODCHequation2.3-24 H-3calculatedperODCXegnation2.3-28 ISSUI3 2-91 2
BV-1 and 2 ODCM l fable 2.3 BVALUISFORBIATERVALLIISITI (sqmeter-ares /yrpersci/see)
Pathway:ConMilk AgeGroup: feen helide Bone Lint f. Body Thyroid Ildney Lung GI-LLI 1 F3 0.00t+00 9.94E+02 9.94I+02 9.94bO2 9.94bO2 9.94I+02 9.96+02 2P-32 2.67b10 1.66b09 1.04b09 0.00t+00 0.00b00 0.00D00 2.25b09 -
3Cr-51 0.00I+00 0.00b00 4.15b04 2.31b04 9.10bO3 5.93b 04' 6.97b 06 4Hn-54 0.00I+00 9.91006 1.96b06 0.00b00 2.95b06 0.00b00 ' 2.03bO7 5Fe-59 4.18bO7 9.761+07 3.77bO7 0.00b00 0.00b00 3.08bO7 2.31bO8 600-57 0.00 BOO. 1.60I+06 2.68b06 0.00h00 000D00 0.00b00 2.98bO7 7Co-58 0.00b00 6.171+06 1.42bC7 0.00D00 0.00b00 0.00b00 8.51bO7 8 Co-60 0.00b00 1.89bO7 4.26bO7 0.00b00 0.00D00 0.00E+00 2.46 BOB 9 Zn-65 1.51b09 5.23b09 2.44t+09 0.00 BOO 3.34h09 0.00 BOO 2.21b09 10Rb-86 0.00b00 3.99b09 1.871+09 0.00b00 0.00b00 0.00b00 5.91bO8 11Sr-89 2.14b09 0.00b00 6.12D07 0.00b00 0.00b00 0.00h00 2.55bO8 12Sr-90 4.47b10 0.00b00 1.10D10 0.00b00 0.00b00 0.00b00 1.251+09 13 Y-91 1.25b04 0.00b00 3.35bO2 0.00E+00 0.001^00 0.00D00 5.11b06 14Zr-95 1.29b03 4.08bO2 2.81bO2 0.00 BOO 6.00bO2 0.00b00 9.42h05 15Rb-95 1.16b05 6.41b04 3.53bo4 0.00b00 6.21b04 0.00b00 2.74bO8 16Bb-97 5.13I-12 1.271-12 4.651-13 0.00b00 1.49E-12 0.00b00 3.048-08 17Mo-99 0.00b00 3.80bO7 7.25b06 0.00h00 8.70bO7 0.00b00 6.81bO7 18fc-99: 4.90b OO 1.37b 01 1.77bO2 0.00b00 2.04bO2 7.59b00 8.98bO3 19 h-103 1.47t+03 0.00h00 6.30D02 0.00 BOO 5.20bO3 0.00b00. 1.23b05 20En-106 2.03b04 0.00b00 3.32bO3 0.00b00 5.08h04 0.00b00 1.26b06 21Ag-110s- 6.87bO7 6.50D07 3.95bO7 0.00b00 1.2G+08 0.00b00 1.83b10 22Sb-124 0.00 BOO 0.00 BOO 0.00 BOO 0.00 BOO 0.00h00 0.00b00 0.00b00 23Sb-125 0.00 b00 ' O.00b 00 0.00D00 0.00b00 0.00b00 0.00h00 0.00b00 24fe-127s 6.34bO7 2.25bO7 7.54b06 1.51bO7 2.57bO8 0.00h00 - 1.58bO8 25fe-129s 9.06h07 3.36bO7 1.43h07 2.92bO7 3.79bO8 0.00 BOO 3.40bO8 26I-131 4.57 BOB 6.39b08 3.43bO8 1.87b11 1.10b09 0.00b00 1.26bO8 27I-133 6.0lb06 1.02bO7 3.11b06 1.42b09 1.79bO7 0.00h00 7.71b06 28Cs-134 6.76b09 1.59b10 7.38b09 0.00b00 5.06b09 1.93b09 1.98 BOB 29Cs-136 3.80 BOB 1.50h09 1.01b09 0.00b00 8.15bO8 1.28b06 1.20bO8 30Cs-137 9.05b09 1.20b10 4.19D09 0.00h00 4.10b09 1.59b09 1.71 BOB 31Ba-140 4.12bO7 5.05b04 2.65b06 0.00b00 1.71b04 3.39b04 6.35b07 32La-140 6.89b00 3.39b00 9.01I 4 1 0.00b00 0.00b00 0.00h00 1.94b05 33Ce-141 7.32bO3 4.8SbO3 5.62bO2 0.00b00 2.30bO3 0.00b00 1.40bO7 34Ce-144 4.67b05 1.93b05 2.51b04 0.00b00 1.15b05 0.00b00 1.17bO8 All nuclides (ezcept F 3) calenlated per ODCM equation 2.3-24 H-3 calenlated per ODCM egnation 2.3 ISSUI3 2-92 ,
i
__o
p
, i l: ,
'C BV-1and2ODCM-
/~ fable 2.3-15:
k___.
RVALDISF0IBIAVIIYALLITSITI a (sqseter-ares /yrpersci/see)
Pathway:CowMilk 'i AgeGroup: Child helide Bone Liver 7. Body. Thyroid Ildney Lung GI-LL1 J '
1H-3 0.00I40 -1.571+03 1.57t+03 1.57143 1.57I+03 1.578+03 1.57t+03-2P-32 6.5SI+10 3.09I49. 2.54E+09 0.00E+00 0.00l+00 0.00I+C0 1.82t+09 3Cr 0.00B+00 0.00t+00 8.46I+04 . 4.70l+04 1.28t+04 8.588+04 4.491+06 4Hn-54 0.00I40 :1.481+07 3.95E+06 0.00E+00 4.16I 46 0.00I40 .1.24I+07 )
5Fe-59 .9.70l+07 1.571408 7.82R+07. 0.00l+00 0.00E+00 - 4.55t+07 1.63E+08 )
60o-57 0.00140 2.73t+06 5.52E+06 0.00t+00 0.00B+00 0.00I 4 0 2.24E+07 700-58 0.00!+00 9.43E+06 2.89147 0.00l+00' O.00I 40 0.00!+00 5.50l+07 8Co-60 0,00E+00 2.94t+07 8.671+07 0.00l+00 0.00t+00 0.00f+00 1.63I+08 1 9Zn-65 2.95It09 7.87t+09 4.89I+09 0.00B+00 4.96I+09 0.00t+00 1.38t+09 10lb-86 0.00E+00 7.40l+09 4.55E+09 ~ 0.00E+00 0.00t+00 0.00E+00 4.76I48 l
11Sr-89 5.29t+09 0.00l+00. 1.51t+08 0.00B+00 0.00l+00 0.00I40 2.05t+08 12Sr-90 7.55t+10 0.00E+00 1.91t+10 0.00l+00 0.00E+00 0.00l+00 1.02I+09 !
13Y-91 3.08t+04 0.00l+00 8.24t+02 0.00l+00 0.0d+00 0.00I 40' 4.111+06 b
V 14Zr 15lb-I5 3.00l+03 8.60t+02 5.88I+02 0.00t+00 9.45t+02 0.00840 6.89I+05 i
2.61t+05 1.02E+05 7.26t+04 0.00I40 9.54I+04 0.00l+00 1.888+08 l 16lb-97 1.255-11 2.25I-12 1.051-12 0.00l+00 2.50I-12 0.00l+00 6.94I-07 17No-99 0.00l+00 ' 6.92t+07 1.71E+07 0.00l+00 1.48I+08 0.00t+00 5.72t+07 18fe-99 1.12E+01 2.20l+01 3.65t+02. 0.00I40 3.20l+02 1.12E+01 1.25E+04 19In-103 3.49t+03 0.00l+00 1.34I+03 0.00l+00 8.788+03 0.00l+00 9.011+04 20In-106 6.49I+04 0.00l+00 8.10l+03 0.00l+00 8.76t+04 0.00I40 1.01t+06 21Ag-110s 1.49I+08 1.011+08 8.05I+07 0.00l+00 1.87t+08 0.00t+00 1.20E+10 22Sb-124 0.00E+00 0.00!+00 0.00E+00 0.00I+00 .0.00!+00 0.00E+00 0.00l+00 e 23Sb-125 0.00l+00 0.00t+00 0.00!+00 0.00l+00 0.00I+00 0.00l+00 0.00I40 24fe-127s 1.561+08 4.211+07- 1.86t+07 3.74B+07 4.461+08 0.00l+00 1.271+08 25fe-129s 2.23E+08 6.24I+07 3.47t+07 7.20t+07 6.56t+08 0.00l+00 2.72I48 261-131. 1.11t+09 1.11tv09 6.33I+08 3.68t+11 1.83t+09 0.00l+00 9.92t+07 27I-133 1.46t+07 1.81t+07 6.83I+06 3.36149 3.01t+07 0.00I 4 0 7.28t+06 28Cs-134 '1.56t+10 2.56t+10 5.40l+09 0.00l+00. 7.93I+09 2.85t+09 1.381+08 29Cs-136 8.58I+08 2.36I+09 1.53E+09 0.00t+00 1.26I49 1.87I+08 8.298+07 30Cs-137 2.1BI+10 2.091+10 3.08t+09 'O.00t+00 6.80!+09 2.45I 4 9 1.311+08
- 4. 31Ba-140 9.94I+07 8.711+06 5.80l+06 0.00l+00 2.84E+04 5.19I+04 5.04t+07 32La-140 1.65I+01 5.77t+00 1.941+00 0.00l+00 0.00l+00 0.00l+00 1.61E+05 33Ce-141 1.80I 4 4 8.998+03 1.34t+04 0.00!+00 3.94t+03 0.00t+00 1.12I+07
,. 34Ce-144 1.15I+06 3.61B+05 6.15t+04 0.00I40 2.00!+05 0.00l+00 9.41I+07 Allnac11 des (exceptH-3)calenlatedperODCHegiation2.3-24 l H-3calenlatedperODCHegnation2.3-28 ISSUI 3 2-93
, BY-1and2ODC8 fable 2.3-16 IVALUISFORBIAVERYALLI!SITI (sqseter-ares /yrpersci/see)
Pathway:CowHilk AgeGroup: Infant Buclide Bone- Liver f. Body Thyroid Ildney Lung GI-LLI i
1E-3 0.00!+00 2.38I+03 2.38t+03 2.38I+03 2.38I+03 2.38I+03 2.38t+03 2P-32 1.36t+11 7.93E+09 5.27I+09 0.00160 0.00E+00 0.00l+00 1.84E+09 3Cr-51 0.00E+00 0.00E+00 1.34E+05 8.75E+H 1.911+04 1.70!+05 3.91E+06 4 Hn-54 0.00l+00 2.761+07 6.25E+06 0.00! do 6.11Id6 0.00l+00 1.01E+07 5 Fe-59 1.81E+08 3.161+08 1.25E+08 0.00!+00 0.00!+00 9.35I+07 1.51E+08 6Co-57 0.00l+00 6.36I+06 1.03Et07 0.00!+00 0.00Edo 0.00E+0d 2.17I+07 700-58 0.00I40 1.89t+07 4.70E+07 0.00E+00 0.00140 0.00ft00 4.70E+07 8Co-60 0.00l+00 6.00E+07 1.42E+08 0.00E+00 0.00!+00 0.00t+00 1.43E+08 9Zn-65 3.97I+09 1.36t+10 6.27I+09 0.00E+00 6.60E+09 0.00E+00 1.15E+10 10Rb-86 0.00!+00 1.88t+10 9.281+09 0.00!+00 0.00!+00 0.00!+00 4.81E+08 11St-89 1.01E+10 0.00l+00 2.89f+08 0.00!+00 0.00E+00 0.00E+00 2.07t+08 12Sr-90 8.22E+10 0.00l+00 2.09I+10 0.00!+00 0.00!+00 0.00!+00 1.03Id9 13T-91 5.791+04 0.00E+00 1.54E+03 0.00!+00 0.00E+00 0.00E+00 4.15E+06 14Zr-95 5.33E+03 1.30E+03 9.22E+02 0.00E+00 1.40E+03 0.00l+00 6.47t+05 15Nb-95 4.87I+05 2.011t05 1.16t+05 0.00!+00 1.44I45 0.00E+00 1.69I+08 16Rb-97 2.63I-11 5.621-12 2.031-12 0.00t+00 4.39E-12 0.00E+00 1.77I-06 17Ho-99 0.00!+00 1.77t+08 3.45E+07 0.00!+00 2.64E+08 0.00t+00 5.83E+07 18fe-99: 2.34E+01 4.82E+01 6.211+02 0.00!+00 5.19I+02 2.52E+01 1.40E+04 19Rn-103 7.061+03 0.00It00 2.36I+03 0.00!+00 1.471+04 0.00E+00 8.59I+04 20Ru-106 1.34E+05 0.00!+00 1.67I+04 0.00E+00 1.581+05 0.00l+00 1.01E+06 21Ag-110s 2.75E+08 2.01E+08 1.33E+0B 0.00!+00 2.881+06 0.00E+00 1.04E+10 22Sb-124 0.00!+00 0.00!+00 0.00!+00 0.00X+00 0.00E+00 0.00It00 0.00!+00 23Sb-125 0.00E+00 0.00E+00 0.00!+00 0.00l+00 0.00!+00 0.60E+00 0.00l+00 24fe-127s. 3.16t+08 1.05E+08 3.83E+07 9.14E+07 7.19I 4 8 0.00I00 1.28I+08 25fe-129s 4.58t+08 1.571+08 7.061+07 1.761+0B 1.15I49 0.00E+00 2.74E+08 26I-131 2.31t+09 2.72I+09 1.20!+09 8.95E+11 3.1BI+09 0.00E+00 9.72E+07 27I-133 3.08t+07 4.49t+07 1.31E+07 8.17I+09 5.281+07 0.00!+00 7.60!+06 28Cs-134 2.51E+10 4.69t+10 4.73E+09 0.00l+00 1.211+10 4.95E+09 1.27I+0B 29Cs-136 1.68I+09 4.93E+09 1.84t+09 0.00!+00 1.97169 4.02E+08 7.49t+07 30Cs-137 3.488+10 4.071+10 2.891+09 0.00!+00 1.09I+10 4'3E+09 1.271+08 31Ba-140- 2.05I+08 2.05E+05 1.05E+07 0.00E+00 4.86t+04 1.261+05 5.02I+07 32La-140 3.45E+01 1.36t+01 3.50!+00 0.00!+00 0.00!+00 0.00!+00 1.60E+05 33Ce-141 3.57t+04 2.181+04 2.57t+03 0.00!+00 6.72t+03 0.00E+00 1.13E+07 34Ce-144 1.65E+06 6.75I+05 9.25E+04 0.00!+00 2.73I+05 0.00t+00 9.47t+07 Allsnelides(exceptH-3)calenlatedperODCMequation2.3-24 j H-3calculatedperODCHequation2.3-28 l
ISSUI3 l 2-94 l
l
,x W?"y -
o . .0 l ) '
=-
N-1 and 2 0DC5 p .- t
- T(3 '
4 1 >
-Table 2.3-17 u
V - :
, :I TALDIS FOIII4fB TALL 27 SITI ~
l(seseter-arse /rrper.uCi/sec)-
h/* '
lPathair:GoatHilk;
- AgeGroup: Adult g
h:
inclkie ' ~ lose : Liver: ~f. Body ' Thyroid.
tidner 'Long GI-LLI-1E-3 0.00I40 .1.5s+03 : 1.5 e 4 3 1.5 n 4 3 1 1.56843 .1.56843 1.5 eda 2P-32 1.74t+10 . 1.08I 49 8.728+06 0.00I40 0.00840 0.00I 4 0. 1.96t+09' 3Cr-51 0.00E+00 0.00E+00c 2.8243- 11.705d3= 6.28542 l3.75+03 7.175+05:
- ' ~
- 4 h-54 : 0.00E+00 . 7.1845 :1.3S+05 ~0.00540 2.13 45 0.00B+00 2.1 8 46:
, 5Fe-59J 3.15+05 - 7.32t+05 ' 2.811+05 ' O.00E+00. 0.00540 2.05E+05 - 2.44E+06 h[ '
. 6Co-57f 0.00E+00? 1.095+05 1.85+05 ' O.00E+00 0.00B+00 0.00I402.77546' -
h ~ ' '
i7Co-58' O.00E+00 4.#I45 9.868+05 . 0.00E+00 , 0.00l+00 0.00E+00' 8.91t+06' 8Co-M 0.00E+00. 1.38 46 9 2.9 8 46~ 0.00l+00 ~ 0.00E+00 0.00f+00 2.52547:
9In-85 -1.18848 3.7 6 4 8'.1.698+08. 0.00E+00 2.50E+08 0.00E+00 2.385+08 10Ib-86 0.00E+00. 2.63E+08' '1.22E+08 0.00E+00 0.005 40 0.00B+00 - 5.18t+07 E
=11Sr-89 l2.43B+09 - 0.00E+00. ~6.99I47. ' O.00E+00 0.0054 0 ~ 0.00E+00 '3.915+08'
'12Sr 6.68+10 0.00E+00 :1.63E+10 0.00E+00 0.00E+00--0.00B+00- 1.92E+09 :
13 741s 8.14I42 0.00l+00 2.18541 0.00I40 : ,0.00E+00 0.00E+00 4.#I45' O -
14tr-95 15lb-95i
.8.8754 1' 2.855 4 1 1.93841 0.00540-F4.47I4 1 .0.00B+00' 9.025+04.
8.13E+03 ~ 4.52I43 ' 2.43543 0.00!+00. 4.47843 0.00840 2.74td71
]
u .. . .
1
.16Ib-97 3.385 8.545-14 : 3.13-14 0.M I+00. 9.965-14.-. 0.008 4 0 3.155-10
- 17No-99 0.00I40 = 2.53I46 . 4.81E+05. 0.00B+00 5.72E+06 0.005 4 0 5.86546
' 18 fc49m 3.398-01 ' . 9.595-01 ' 1.2H+01 0.00E+00 -1.48411 4.70541 5.675d2 19 h-103 -9.99+01 0.005 40; 4.29t+01. 0. N I+00 3.00542. 0.00E+00 .1.16I44 7 [. 20la-106 1.72X+03 -0.00E+00 '2.18t+02 0.00E+00 3.325d 3 0.00E+00. 1.1184 5'
'21Ag-110s ,4.99t+06 4.61E+06 2.7 4 46. 0.00I40 9.07I 4 6 0.00I 4 0 1 1.88t+09-
@ 22$b-124 , 0.00I 4 0 0.00I 4 0 0.00l+00 0.00I40 'O.00E+00 0.00I 4 0 0.00l+00
- " 0.00I 4 0 0.00E+00 0.00t+00 0.00I 4 0 0.00E+00 0.00B+00 0.00B+00' 4 23 Sb125-X 24fe-127a 4.13E+06 1.#I+H 5.03B+05 1.05I46 1.68147 0.00E+00 1.38547 25fe-129s 5.94546 2.22I 4 6 -9.41845 2.04t+N 2.#I+07 0.00I 4 0 2.995+07
" '26I-131' 3.02E+08 ' 4.32E+08 2.48I46 1.42E+11 7.40t+08 'O.00I 4 0 ' 1.1G+08-127I-133- 3.95B+06 6.871+06 2.09t+06 1.01E+09 -1.20E+07 0.005 40. 6.171+06
,, 28Cs-134- 4.67I48 1.11849 9.095+08 0.00E+00 3.60E+08 1.195+08 1.95147
. '29Cs-136- 6.70848 2.65I+09 1.90549 0.00l+00 1.47849 2.02I 4 8 3.01E+08 j 30Cs-137' 1.50l+10 2.05E+10 ' 1.3G+10 -0.00B+00 6.95E+09 2.31849 3.965+08 C
31la-140- 2.7kI46' 3.448 4 3 1.79545' O.00E+00' 1.17543 1.97I+03 5.68+06 332La-140 4.605-01 2.32841 6.135-02 0.00l+00 0.00l+00 0.00540 1.70E+04
- 33Ce-141
- 4.79542 3.24B+02 3.68I+01 0.00140 1.51t+02 0.00540 1.24546 34Ce-144 3.05B44 1.275+04-.1.64E+03 0.00840 7.55E+03 0.00E+00 1.03I47 o-Allasc11 dss (exceptI-3)caleIntedper0D05ognation2.3-24
~I-3calenlatedper0D05ognation2.3-28
ISSUI3 2-95 L .
l H
EV-1and2ODCH I fable 2.3-18 EVALUISFORBIAVIIVALLIISITI (egseter-ares /yrperUCl/sec)
Pathway-GoatHilk AgeGroup-feen helide Bone Liver f. Body Thyroid lidney Lung. GI-LL1 1H-3 0.00l+00 2.03t+03 2.03E+03 2.03E+03 2.03E+03 2.03I+03 2.03E+03 2P-32 3.21t+10 1.998+09 1.2G+09 0.00!+00 0.00I40 0.00E+00 2.70!+09 3Cr-51 0.00!+00 0.00Et00 4.98t+03 2.771+03 1.09t+03 7.11E+03 8.37I+05 4Hn-54 0.00E+00 1.198+06 2.36I+05 0.00!+00 3.55E+05 0.00!+00 2.4G+06 5Fe-59 5.4G+05 1.271+06 4.90E+05 0.00!+00 0.00I+00 4.00!+05 3.00!+06 6Co-57 0.00!+00 1.92E+05 3.21E+05 0.00!+00 0.00E+00 0.00E+00 3.57I+06 7Co-58 0.00E+00 7.40!+05 1.71E+06 0.00E+00 0.00ft00 0.00It00 1.02E+07 i 8Co-60 0.00!+00 2.271+06 5.11146 0.00!+00 0.00f+00 0.00l+00 2.968+07 j' 9Zn-65 1.81E+08 6.27168 2.93E+08 0.00!+00 4.01E+08 0.00E+00 2.66I+08 10lb-86 0.00E+00 4.791+08 2.25E+08 0.00!+00 0.00E+00 0.00E+00 7.09t+07 11Sr-89 4.49t+09 0.00!+00 1.291+08 0.00l+00 0.00E+00 0.00X+00 5.35E+08 12St-90 9.39t+10 0.00l+00 2.32E+10 0.00!+00 0.00E+00 0.00!+00 2.64t+09 13T-91 1.50!+03 0.00!+00 4.01E+01 0.00E+00 0.00E+00 0.00E+00 6.14t+05 142r-95 1.55E+02 4.90t+01 3.37I+01 0.00E+00 7.19E+01 0.00t+00 1.13E+05 15 lib-95 1.391+04 7.69E+03 4.23E+03 0.00E+00 7.45t+03 0.00E+00 3.29E+07 16Nb-97 6.151-13 1.53I-13 5.57I-14 0.00E+00 '1.79I-13 0.00E+00 3.651-09 17Ho-99 0.00!+00 4.56t+03 8.70E+05 0.00E+00 1.04E+07 0.00E+00 8.171+06 18fc-99: 5.881-01 1.64E+00 2.13E+01 0.00E+00 2.45E+01 9.111-01 1.0BI+03 19Rn-103 1.771+02 0.00E+00 7.56t+01 0.00!+00 6.2!!+02 0.00!+00 1.4BI+04 20 h-106 2.44It03 0.00E+00 3.98t+02 0.00E+00 6.10!+03 0.00E+00 1.52E+05 21Ag-110m 8.2G+06 7.80!+06 4.75E+06 0.00E+00 1.49E+07 0.00E+00 2.191+09 22Sb-124 0.00!+00 0.00l+00 0.00!+00 0.00!+00 0.00l+00 0.00E+00 0.00E+00 23Sb-125 0.00!+00 0.00!+00 0.00Z+00 0.00E+00 0.00!+00 0.00!+00 0.00!+00 24fe-127:. 7.611+06 2.70846 9.05t+05 1.81t+06 3.08t+07 0.00E+00 1.90!d7 25fe-129s 1.0SI+07 4.03t+06 1.72I+06 3.51E+06 4.55E+07 0.00540 4.08t+07 26I-131 5.48t+08 7.671+08 4.12E+08 2.2G+11 1.32E+09 0.00l+00 1.52E+08 27I-133 7.21E+06 1.22t+07 3.73t+06 1.71t+09 2.15t+07 0.00l+00 9.26I+06 28Ce-134 8.11t+08 1.91E+09 8.861+08 0.00l+00 6.07I+08 2.32t+08 2.381+07 29Cs-136 1.16 49 4.491+09 3.02E+09 0.00I+00 2.44I+09 3.851+08 3.61E+08 30Cs-137 2.711+10 3.61E+10 1.26I+10 0.00!+00 1.23t+10 4.77I+09 5.1G+08
- 31Ba-140 4.96+06 6.06t+03 3.181+05 0.00It00 2.05E+03 4.07I+03 -7.62E+06-32La-140 8.278-01 4.061-01 1.08I-01 0.00!+00 0.00!+00 0.00l+00 2.33E+04 33Ce-141 8.79t+02 5.878+02 6.76+01 0.00!+00 2.76t+02 0.00E+00 1.68t+06 e
34Ce-144 5.60E+04 2.32I+04 3.011+03 0.00!+00 1.391+04 0.00Edo 1.41E+07 Allnuclides(exceptB-3)calenlatedperODCHequation2.3-24 H-3calenlatedperODCHegnation2.3-28 ISSUI3 2-96
i !
l BY-1and2ODCH fT fable 2.3-19 y j!
RYALUISFORBIAYERVALLifSITI (etmeter-ares /yrpernCi/sec)
Pathway:GoatHilk j AgeGroup: Child Nuclide Bone Liver f. Body Thyroid tidney Lung GI-LLI 1H-3 0.00!+00 3.20E+03 3.20!+03 3.20!+03 3.20l+03 3.20E+03 3.20E+03 2P-32 7.91E+10 3.70E+09 3.05E+09 0.00E+00 0.00E+00 0.00E+00 2.191+09 3Cr-51 0.00!+00 0.00!+00 1.02E+04 5.64E+03 1.54E+03 1.03E+04 5.39E+05 4Hn-54 0.00!+00 1.781+06 4.74E+05 0.00!+00 4.99Et05 0.00I40 1.49E+06 j 5Fe-59 1.26D06 2.04E+06 1.02b06 0.00E+00 0.00H+00 5.91E+05 2.12E+06 6Co-57 0.00E+00 3.27t+05 6.63I+05 0.00E+00 0.00E+00 0.00!+00 2.6BI+06 7Co-58 0.00E+00 1.13I+06 3.46I+06 0.00I40 0.00E+00 0.00E+00 6.60E+06 800-60 0.00!+00 3.53t+06 1.04E+07 0.00!+00 0.00!+00 0.00b00 1.95E+07 9Zn-65 3.54E+08 9.44E+08 5.871+08 0.00E+00 5.95E+08 0.00E+00 1.66I48 10Ib-86 0.00!+00 8.88I+08 5.461+08 0.00!+00 0.00E+00 0.00E+00 5.71E+07 11Sr-89 1.11E+10 0.00!+00 3.17I+08 0.00E+00 0.00E+00 0.00!+00 4.30E+08 12Sr-90 1.59t+11 0.00!+00 4.02E+10 0.00!+00 0.00E+00 0.00E+00 2.14E+09
-m 13Y-91 3.70E+03 0.00E+00 9.89t+01 0.00E+00 0.00I00 0.00E+00 4.93E+05
() 14Zr-95 3.60E+02 7.92E+01 7.05E+01 0.00E+00 .1.13E+02 0.00I40 8.27I+04 15lb-95 3.13E+04 1.22E+04 8.71bO3 0.00E+00 1.14E+04 0.00!+00 2.25E+07 16Ib-97 1.491-12 2.70E-13 1.261-13 0.00E+00 2.991-13 0.00!+00 8.33!-08 !
17Ho-99 0.00E+00 8.30!t06 2.05E+06 0.00!+00 1.77I+07 0.00!+00 6.87I+06 18fc-99 1.35E+00 2.65E+00 4.391+01 0.00b00 3.64E+01 1.34I 4 0 1.51bO3 i 19Ro-103 4.181+02 0.00!+00 1.61E+02 0.00E+00 1.05E+03 0.00Edo 1.081+04 20In-106 7.791+03 0.00!+00 9.72E+02 0.00E+00 1.05E+04 0.00E+00 1.21E+05 21Ag-110s 1.79E+07 1.21bO7 9.65D06 0.00E+00 2.25E+07 0.00E+00 1.44b09 22Sb-124 0.00!+00 0.00b00 0.00E+00 0.00E+00 0.00E+00 0.00b00 0.00bOS 23Sb-125 0.00D00 0.00!d0 0.00b00 0.00b00 0.00!+00 0.00b00 0.00b00 24fe-127m 1.88bO7 5.05b06 2.23b06 4.48t+06 5.35E+07 0.00b00 1.52bO7 1 25fe-129s 2.68bO7 7.48I46 4.16b06 8.64I+06 7.87bO7 0.00D00 3.27bO7 !
26I-131 1.33b09 1.34E+09 7.60E+08 4.42b11 2.19D09 0.00b00 1.19b08 1 27I-133 1.75bO7 2.17bO7 8.20D06 4.03b09 3.61bO7 0.00b00 8.73b06 28Ce-134 1.87!+09 3.07b09 6.48bO8 0.00b00 9.52168 3.42 BOB 1.66bO7 29Cs-136 2.58D09 7.06t+09 4.58b09 0.00E+00 3.77b09 6.62 BOB 2.49b08 I 30Cs-137 6.5(I+10 6.26b10 9.24E+09 0.00b00 2.0st+10 7.38+09 3.92bO8 31Ba-140 1.19bO7 1.05E+06 6.96b05 0.00!+00 3.40bO', 6.23bO3 6.04b06 l 32La-140 1.98b00 6.921-01 2.33I-01 0.00 BOO 0.00 N 0 0.00D00 1.93h04
) 33Ce-141 2.16bO3 1.08bO3 1.60bO3 0.00b00 4.73f+02 0.00h00 1.35b06 .
l _ 34Ce-144 1.38b05 4.33144 7.37bO3 0.00b00 2.4fb04 0.00b00 1.13bO7 i b Allnuclides(ezeeptB-3)calculatedperODCHequation2.3-24 H-3calculatedperODCHegnation2.3-28 ISSUI3 2-97 1
BV 1 and 2 ODCM fable 2.3-20 RVALD?SFORBIAVERYALLifSITI (sgsettr-sres/yrpernC1/see) fathway:GoatHilk AgeGroup: Infant, Baclide Bone Liver f. Body Thyroid lidney Lung GI-LLI 1H-3 0.00!+00 4.86t+03 4.86t+03 4.86t+03 4.86t+03 ' 4.86I+03 4.861+03 2P-32 1.63E+11 9.59t+09 6.32E+09 0.00!+00 0.00!+00 0.00E+00 2.21E+09 3Cr-51 0.00E+00 0.00l+00 1.61t+04 1.05E+04 2.291+03 2.04E+04 4.69E+05 4Hn-54 0.00!+00 3.31E+06 7.50!+05 0.00X+00 7.33E+05 0.00!+00 1.21E+06 i 5 Fe-59 '2.35E+06 4.11E+06 1.62E+06 0.00E+00 0.00!+00 1.21E+06 1.96I+06 I 6Co-57 0.00E+00 7.64E+05 1.24E+06 0.00!+00 0.00l+00 0.00E+00 2.60E+06 7Co-58 0.00E+00 2.26t+06 5.64E+06 0.00E+00 0.00!+00 0.00E+00 5.64E+06 8 Co-60 0.00E+00 7.20E+06 1.70E+07 0.00l+00 0.00!+00 0.00t+00 1.71E+07 92n-65 4.761+08 1.63E+09 7.53I+0B 0.00l+00 7.92E+08 0.00E+00 1.385+09 10lb-86 0.00E+00 2.25E+09 1.11E+09 0.00E+00 0.00E+00 0.00E+00 5.77I+07 11Sr-89 2.11E+10 0.00E+00 6.06t+08 0.00E+00 0.00!+00 0.00!+00 4.34E+08 12 Sr-90 1.73E+11 0.00E+00 4.39E+10 0.00!+00 0.00E+00 0.00E+00 2.16E+09 13T-91 6.94E+03 0.00l+00 1.85E+02 0.00l+00 0.00!+00 0.00l+00 4.98I+05 14Zr-95 6.40!+02 1.56t+02 1.11E+02 0.00E+00 1.68t+02 0.00E+00 7.77I+04 15Rb-95 5.84E+04 2.41E+04 1.391+04 0.00!+00 1.72E+04 0.00E+00 2.03E+07 16Bb-97 3.161-12 6.74I-13 2.438-13 0.00E+00 5.275-13 0.00!+00 2.131-07 17 50-99 0.00E+00 2.12E+07 4.14t+06 0.00!+00 3.17t+07 0.00!+00 6.99t+06 18fc-99 2.81t+00 5.791+00 7.46I+01 0.00E+00 6.23E+01 3.03E+00 1.681+03 19In-103 8.47I+02 0.00E+00 2.83E+02 0.00!+00 1.76I+03 0.00E+00 1.03t+04 20En-106- 1.60E+04 0.00E+00 2.00E+03 0.00E+00 1.90E+04 0.00!+00 1.22E+05 I l
21Ag-110e 3.30E+07 2.41E+07 1.60E+07 0.00l+00 3.45t+07 0.00l+00 1.25f+09 22 Sb-124 0.00!+00 0.00!+00 0.00!+00 0.00!+00 0.00l+00 0.00E+00 0.00E+00 23Sb-125 0.00!+00 0.00!+00 0.00l+00 0.00!+00 0.00l+00 0.00E+00 0.00!+00 24fe-127s 3.80E+07 1.26t+07 4.591+06 1.10l+07 9.351+07 0.00!+00 1.53E+07 25fe-129 5.50E+07 1.891+07 8.47t+06 2.11t+07 1.3Bl+08 0.00E+00 3.26I+07 26I-131 2.77t+09 3.27t+09 1.44t+09 1.071+12 3.82E+09 0.00!+00 1.17t+08 I 271-133 3.70E+07 5.391+07 1.58I+07 9.80l+09 6.34E+07 0.00!+00 9.12E+06 )
28Cs-134 3.02E+09 5.62t+09 5.681+08 0.00E+00 1.45E+05 5.93E+08 1.53t+07 29Cs-136 5.03t+09 1.48I+10 5.52I+09 0.00!+00 5.90!+09 1.21t+09 2.25E+08 30Cs-131 1.04E+11 1.22E+11 8.66t+09 0.00E+00 3.28I+10 1.33t+10 3.82E+08 31Ba-140 2.45t+07 2.15Et04 1.261+06 0.00X+00 5.83t+03 1.51E+04 6.03E+06 32 La-140 4.14It00 1.63E+00 4.191-01 0.00E+00 0.00E+00 0.00l+00 1.02E+04 33Ce-141 4.291+03 2.62t+03 3.081+02 0.00E+00 8.071+02 0.00!+00 1.35E+06 ,
34 Ce-1H '1.981+05 8.11E+04 1.11E+04 0.00E+00 3.28t+04 0.00!+00 1.1(I+07 !
Allmuelldes(ezeeptB-3)calenlatedperODCMequation2.3-24 E-3 calculated per ODCM egnation 2.3-28 ISSUI3 l 2-98 I
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0 000 000 00000 00000 _
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PL T 5 756 214 96187 00711 E S 2 I 1 123 332 11288 11419 S D -
DU NO 5 999 99909 99009 _
AU 999 00010 00110 N 1 000 000 1I - - -
T - E E E- EEE EEEEE EEEEE 21635 64963 vN s C 0 482 193 990 604 50785 38086 1 311 344 33371 11321 R
O F 0 999 989 99999 99009 1 000 000 00000 00110
- EEE 047 EEE 585 EEEEE 16195 EEEEE-35395 5 665 528 46885 69100 0 851 117 64425 62442 5
009 990 99988 90000 0 110 001 00000 01111
- EEE EEE E E E E- E- EEEEE 063 352 62049 78420 0 060 138 72048 57554 0 661 119 22311 13443 R W N O E E E E W W NNN NE N S ES SW S
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5 4
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000 000 00000 00000 4 111 111 11111 11111
- EEE E E E- EEEEE EEEEE 149 858 55905 85939 0 996 502 59373 38785 4 235 642 21212 33573 a 0
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AR N f RY C 0 009 900 00000 00990 A/ I PS T 3 110 01 1 11111 11001 R A - - -
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EE L E 2 999 000 999 000 99909 00010 99999 00000 f C - - - - - - - - - - - - -
f IO N - EEE E E E- E E E E E- EEEEE A t A 197 422 55677 74062 TU T 5 884 614 41294 86681 NO S 12342 OR I 1 113 321 11181 CG D 2S 5 U 999 999 99999 99999 DQ 1 000 000 00000 00000
- U t - - - - - - - - - - - - -
ANI - EEE EE E- 5EEEE EEEEE 42389 471 194 96602 1T 0 232 575 50266 37467 N
VO 1 336 632 22212 34683 BC R 0 U
E 1 998 000 889 000 99999 00000 98889 00000
- EEE EEE EEEEE EEEEE 397 550 02720 73074 5 732 306 79353 91600 0 791 115 54645 71129 5
888 888 88888 88878 0 000 000 00000 00000
- EEE E E E- EEEEE EEE5E 622 783 94716 09592 0 443 702 28660 64212 0 457 763 32323 46915 R
O O E E E S ES E W SN w
s N
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_ - EEE EEE EEEEE I 826 927 92693 75514 5 326 338 05939 71749 4 234 531 21111 23462 _
5 4
000 111 000 111 00000 11111 00000 11111 EEE EEE EEEEE EEEEE 149 858 55905 85939 0 996 502 58373 38785 4 235 642 21212 33573 _
0 -
000 900 00000 00090 _
4 111 011 11111 11101
- EEE EE E- EEEEE EEEEE 52614 R 027 164 92944
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// 3 4i7e 153 32223 44814 DS _
( R S ._
H E 5 _
00990 S L 009 900 00000 R0 I 3 110 011 11111 11001 E5 M - - - - - - - - - - - - - - _
T1 - E E- E EEE EEEEE EEEEE _
L> N 650 145 350 29628 19801 72665 82152 M I 0 130 _
AR 42334 56116 _
RO ,3 561 164 _
A S -
PR N 8 Y O 0 00990 N/ I 009 900 00000 _
OS T 3 110 011 11110 11001 IR A - - - - - - - -
EEEEE- EEEEE SH C - EEE EEE R D 747 694 52162 56590 E0 I 5 555 759 54706 43510 M P0 195 64545 88129 C S5 L 2 781 D 3 I > O O 2 D ) R 1
- S T 5 99999 0 3 SE - N 999 990 00000 11111 00000 1 TS s O 2 000 001 -
2 NA r C - - - - - - - - - - - - - - 2 EE e - EEE E E- E EEEEE EEEEE 09198 E VL t E 824 076 29481 21292 L E e H 0 022 534 32170 1 B NR m ( T 11221 A O 2 112 218 96858 V- T IL O B TE T AV IE 0
999 999 99909 99999 000 000 00010 00000 IL T
ND N m2 -
E E- E EEE EEEEE EEEEE EN A 197 422 55677 74062 VU T 5 884 614 41294 86681 O S 12342 ER I 1 113 321 11181 TG D I
SS 5 99999 99999 U 999 999 00000 00000 2O 1 000 000 U - - - - - - - - - - - - - - -
DN - E E E- EEE EEEEE EEEEE NI 471 194 96602 42389 AT 0 232 575 50266 37467 N 336 632 22212 34683 1O 1 VC BR 0 O 998 889 99999 98889 F 1 000 000 00000 00000
- EEE EEE EEEEs EEEEE 397 550 02720 73074 5 732 306 79353 91600 0 791 115 54645 71129 5 88878 888 888 88888 0 000 000 00000 00000
- EEE EEE EEEEE EEEEE
_ 0 622 443 783 702 94716 28660 09592 64212 0 457 763 32323 46915 R E W W W W O E E E i NE N S ES SW S NWN C NNN EEE SSSSS WWNNN E
S
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~
3 0 E 000 000 00000 00000 U 5 111 111 11111 11111 S
- - - - - - - - - - - - - - - S
- EEE EEE EEEEE E E E- EE 75514 I
826 927 92698 5
4 326 234 338 531 05939 21111 71749 23462 O 5
000 000 00000 00000 4 111 111 11111 11111 E E E- E- EE - - -
EEEEE E- E 85939 E- EE 149 858 55905 0 996 502 58373 38785 4 235 642 21212 33573 0
000 900 00000 00090 4 111 011 11111 11101
- EEE EEE E E E E E- E- EEEE 52614
) I R 5 027 097 164 001 92944 13932 58928 T
Q/A 3 447 153 32223 44814 DS
( R S H E 5 S L 009 900 00000 00990 R0 I 3 110 011 11111 11001 E5 T1 M
EEE E E E- EEEEE- EEEEE-E> N 0 650 130 145 350 29628 19801 72665 82152 M- I '
AR RO , 3 561 164 42334 56116 A S _
PRY N .
O 0 00990 N/ I 009 900 00000 OS T 3 110 011 11110 11001 IR A - - -
EEE E- EE - - - -
EEEEE EEEEE-SH C -
52162 56590 R O 747 694 E0 I 5 555 759 54706 43510 M P0 64545 88129 C S5 L 2 781 195 D 4 I> O O 2 D ) R 2
- S I 5 0 2 3 N 999 990 00000 99999 SE TS ~s O
1 O 2 000 001 11111
- - - - - 04000 - - -
d n
2 ME A r e
C EEE E E E- EEEEE EEEEE-2 a E, VL t E 824 076 29481 09198 21292
! E e H 0 022 534 32170 1 a. GR m ( T 96858 11221 P N 2 112 218 V- T IL O B DE T LV S 0
999 999 99909 99999 IE 00000 UL E 2 000 000 00010 B C - - - - - - - -
D N - EEE E E- E EEEEE EEEEE EN A 197 422 55677 74062 NU T 5 884 614 41294 86681 IO S BR I 1 113 321 11181 12342 RG D U
TS 5 99999 99999 U 999 999 000 00000 00000 2O 1 000 U - - - - - - - - - - - - - -
DN - EEE E E E- 5EEEE EEEEE 42389 NI 471 194 96602 ATN 0 232 575 50266 37467 1O 1 336 632 22212 34683 VC BR 0 O 998 889 99999 98889
- F 1 000 000 00000 00000 E E E-397 EEE 550 EEEEE 02720 E- EEEE 73074 5 732 306 79353 91600 0 791 115 54645 71129 5
888 888 88888 88878 0 000 000 00000 00000
- EEE EEE EEEEE EEEEE 622 783 94716 09592
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5 326 338 05939 71749
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000 000 00000 00000 .
4 111 111 11111 11111 EEE 149 EEE 858 E E E E E-55905 EEEEE-85939 0 996 502 58373 38785 4 235 642 21212 33573 0
000 900 00000 00090 4 111 011 11111 11101
)
Q - EEE 027 E E E-164 EEEEE-92944 EEEEE-52614
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5 097 001 13932 58928
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RR S EB E 5 -
T L 009 900 00000 00990 E0 I 3 110 011 11111 11001 M5 M - - - - - - - - -
A1 - E E- E EE E- E E E E- E EEEEE -
R> N 650 145 29628 7266S 82152 A
PR I 0 130 350 19801 O ,3 561 164 42334 56116 N S OR N t IY O 0 S/ I 009 900 00000 00990 RS T 3 110 011 11110 11001 ER A - - - - - - -
PH C - EEE E E E- EEEEE EEEEE 56590 Y S O 5 747 555 694 759 52162 54706 43510 L I0 I M N D0 64545 88129 C O 5 L 2 781 195 D 5 T O C 2N
- C N>)
ES2 R
T 5 99999 3
0 VE - N 999 990 00000 1
- 3. IT S s [ 2 000 001 11111 00000 2E I GA NE r
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- E- EE- - - -
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ER IL t E 824 076 29481 09198 LO DE e H 0 022 534 32170 21292 1 BF LR m I 96858 11221 AN I ( 2 112 218 V- TI UL O B BE I' R V 0 9990' 9 99999 O GE S 999 999 00000 F NL E 2 000 000 00010 I C - - - - - - - - - -
HD N - E E E- EEE EEEEE EEEEE SN A 197 422 55677 74062 IU T 5 884 614 41294 86681 LO S 12342 OR I 1 113 321 11181 PG D _
1 999 000 999 000 99999 00000 93999 0C000 SU - - - - - - - - - - -
NN - EEE E E E- EEE E- E EEEE5 42389 -
EI 471 194 96602 DT 0 232 575 50266 37467 -
NN 632 22212 34683 OO 1 336 -
CC 2R 0 998 889 99999 98889 _
VO E 1 000 000 00000 00000 B
397 E E E- EEE 550 EEEEE-02720 EEEEE 73074 5 732 306 79353 91600 -
0 791 115 54645 71129 -
5 _
888 888 88888 88878 _
0 000 000 00000 00000 .
EEEEE-
- EEE E- E E- EEEEE 622 783 94716 09S92 -
0 443 702 28660 64212 0 457 763 32323 46915 -
R E W W N E E E O iE S ES SW S NN M N WWHNt e I
SSSSS C .N!@N EEE E
S _
3 E
6 00000 00000 U 000 000 11111 S 5 111 111 11111 S
- - - - - - - - - - I E E E- E E E- EEEEE E- E E E E-e
- 75514 826 927 92693 5 326 338 05939 71749 4 234 531 21111 23462 5 00000 000 000 00000 4 111 111 11111 11111
- EE E- EEE E E E- E- E- EEEEE 149 858 55905 85939 0 996 502 58373 38785 4 235 642 21212 33573 0 00090 000 900 00000 11101 4 111 011 11111 EEE EEE EEEEE 92944 EEEEE-52614 t 027 164
) u 5 097 001 13932 58928 Q v 3 447 153 32223 44814
//
DS S
( R H E 5 900 00000 00990 S L 009 11111 11001 0 I 3 110 011 n.
c 5 a1 M
EEE EEE 145 EEEEE 29628 EEEEE-72665 u> N I 0 650 130 350 19801 82152 r
, 3 APR N '
Y O 0 900 00000 00990 N/ I 009 11001 CS T 3 110 011 11110 IR SH A
C -
EEE EEE EEEEE 52162 EEEE- E-56590 Y R O 747 694 43510 L E0 L 5 555 759 54706 M P0 195 64545 88129 C
D 6 W S5 I>
L 2 O
781 O 2N D ) R 4 O S T 5 00000 99999 0 2 I TE N 999 990 1 NS ~s 11111 00000
- 3. T 001 d
1 n
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- - - 2 9
2 112 218 96858 11221 AN I V- TI DL O B LE I R IV 0 999 99909 99999 D UE S 999 00000 E BL E 2 000 000 00010 ND C
N -
EEE EEE 422 EEEEE-55677 EEEEE 74062 ON A 197 41294 86601 IU T 5 884 614 TO S 11181 12342 AR I 1 113 321 NG D I
MS 5 999 999 99999 99999 AU TO 1 000 000 00000 00000 NU - - - - - - - - - - - - - - - -
ON - EEE EEE EEEEE EEEEE CI 471 194 96602 42389 ET 0 232 575 50266 37467 DN 336 632 22212 34683 O 1 2C R 0 98889 VU B
E 1 998 000 889 000 99999 00000 00000
- EE E- EEE EEEEE EEEEE 397 550 02720 73074 5 732 306 79353 91600 0 791 115 54645 71129 i 5 88878 888 888 88888 0 000 000 00000 00000
- EEE EEE EEEEE EEEEE 622 783 94716 09592 0 443 702 28660 64212 0 457 763 32323 46915 t
v E E E E W W W W 9
r t
NNN DEES SSSSS WWWNN S
m
~
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3' 0 E 0 0' 0 000 00000 00000 U 5 111 111 11111 11111 S
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- 55E 5EE EEE5E E5EEE I 826 927 92693 75514
_ 5 326 338 05939 71749 4 234 531 21111 23462 '
J 000
~ 000 00000 00000 s 4 111 111 11111 11111
- EEE 149 E E E-858 EEEEE-55905 EEEEE 85939 s
0 996 502 58373 38785 4 235 642 21212 33573 0 - -
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- E 5 E- E E E- EEEEE E E E E E-R 5 027 164 92944 52614 -
) f f 097 001 13932 58928 Q;
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( R S H E 5 - .
S L 009 900 00000 00990 R0 I 3 110 011 11111 11001 E5 N - - - - - - - - -
T1 - E E- E- EEE EEEEE E E E E E-E>
W N
I 0 650 130 145 350 29628 19801 72665 82152 U O R i3 561 164 42334 56116 N
PR S
E N/
Y G I
0 009 900 00000 00990 f
C OS T 3 110 011 11110 11001 IR h - - - - - - - - - - - - - - -
SE C - EE5 E5E EEEEE E5EEE -
Y R D5 747 694 52162 56590 43510 LI E0 I 555 759 54706 P0 7
G S5 I
L 2 O
781 195 64545 88129 2N O
D> S2
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2 000 E E E-001 E E E-11111 EEEEE 00004 EEEEE 1
2 E E 824 076 29481 09198 LU TE e H 0 022 534 32170 21292 sF 3N LR m (
U T
2
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112 218 96858 11221 1I AL O R
VEV T 0
'w O EE S 999 999 99909 99999
=F GL E 2 000 000 00010 00000 A C - - - - - - -
RD ON N -
R EEE 197 EEE 422 EEEEE-55677 EEEEE 74062 TU 1 5 884 614 41294 86681 SO S ;
- R I 1 113 321 11181 12342 SG D
_ A -
GS 5 -
U 999 999 99999 99999 EO 1 000 000 00000 00000 TD -
E E E E E-EEEEE SN - EEE EEE AI 471 194 96602 42389 MTN 0 232 575 50266 37467 2O 1 336 632 22212 34683 VC BR 0 -
O 998 889 99999 98889 F 1 000 000 00000 00000
- E E E- EEE 550 EEEEE 02720 EEEEE 73074 397 5 732 306 79353 91600 0 791 115 54645 71129 5 -
888 888 88888 88878 _
0 000 000 00000 00000 _
- EEE EEE EEEEE EEEEE
- 622 783 94716 09592 ._
64212 0 443 702 28660 -
0 457 763 32323 46915 R N e O s E E E N W N NNN m T l E l S ES SW S r
c C E
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7
~
BV-1 cnd 2 ODCM TABLE 203-28 BV-1 AND 2 PROCESS VENT DISPERSION PARAMETERS (D/0)
FOR CONTINUOUS ELEVATED LEVEL RELEASES >500 ERS/YR OR >150 HRS /0TR FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3)
(IE-9 meters-2)
INDIVIDUAL RECEPTORS DOV! WIND SITE VEGETABLE SECTOR BOUNDARY GARDEN MILK COV MILK GOAT MEAT ANIMAL RESIDENCE N .600 2.340 -- .572 .707 2.510 NNE .673 3.220 -- .524 2.920 3.220 NE .766 1.280 .660 .111 .660 1.200 ENE 1.010 5.080 -- .702 -- 1.760 E 1.370 4.420 .401 1.290 1.290 4.420 ESE .984 6.390 -- 2.340 6.390 6.180 SE 11.000 3.680 .466 .466 1.300 3.680 SSE 7.060 3.220 .423 .105 3.140 4.320 S 5.780 1.540 1.410 -- 2.610 2.730 SSV 2.040 1.040 .578 .208 1.040 1.460 SV 1.610 1.120 -- .693 .979 1.120 USV 1.710 1.310 .370 -- 1.190 1.310 V .377 .659 .138 -- .518 .659 VNV .424 .746 .497 .029 .746 .746 NV .447 .425 -- .070 .488 .422 NNV .340 1.840 -- .043 .545 1.92 0
2-106 ISSUE 3
y I
BV-1 cnd'2 ODCM-
' TABLE 2.3-29
, _BV-1 AND 2 CONTAINMENT VENTS DISPERSION PARAMETERS (D/0)
,<t
,o]
_ .FOR CONTINUOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRS /QTR FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3)
_ _ (IE-9 meters ~).
INDIVIDUAL RECEPTORS
' DOWWIND 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 l'. 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 f- , V. 31.60 1.23 .645 -- .960 1.23 VNV 39.10 2.23 1.490 .045 2.230 2.23 k' . NV 70.60 ~1 5.00 -- .276 1.990 15.60
'NNV' 31.50 6.52 -- .068 1.090 9.91 i
w-Q 2-107 ISSUE 3
BV-1 and 2 ODCM TABLE 2.3-30 BV-1 AND 2 VENTILATION VENTS DISPERSION PARAMETERS (D/0)
FOR CONTINUOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRS /0TR FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3)
(IE-9 meters-2)
INDIVIDUAL RECEPTORS DOVNVIND SITE VEGETABLE SECTOR BOUNDARY CARDEN 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 63.90 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 -- k.860 1.95 SSW 5.59 1.26 .663 .266 1.260 4.42 SV 3.94 2.21 -- 1.320 1.920 2.21 VSV 27.50 2.65 .596 -- 2.380 ~2.65 V 31.60 1.23 .645 -- .960' 1.23-VNV 39.10 2.23 1.490 .045 2.230 2.23 NV 70.60 15.00 -- .276 1.990 15.60 NNV 31.50 6.52 -- .068 1.090 9.91 0
2-108 ISSUE 3 i
I BV-11cnd'2 ODCM TABLE 2,3 ,
Lk 7 I-
-BV-1'AND 2 TURBINE BUILDING VENTS DISPERSION PARAMETERS.(D/0) l FOR CONTINUOUS GROUND LEVEL RELEASES >500' HRS /YR: 0R >150 HRS /QTR:
A 'FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3)
~
0 -
.(IE-9 n,eters2) w INDIVIDUAL RECEPTORS DOWNVIND SITE VEGETABLE:
SECTOR BOUNDARY- CARDEN MILK COV= MILK GOAT MEAT ANIMAL. RESIDENCE
'N 20.20 2.'05 -- .693 .847 .2.190-NNE 34.90 2.02 -- . 45? 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 l'.020 22.700-ESE 18.60- 3.56 -- 1.380- 3.560 3.560-SE. 19.00 3.03 .351 .351 1.100 3.030 SSE 13.30 2.65 .318 .094- 2.570 3.690 S 11.30- 10.40 .934 -- '1.860 1.950 l 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 r
.V - 28.40 ~1.23 .646 --- .961 1.230-Lbh VNV- 30.90. 2.23 1.490 .045 2.230 1.980 2.230 15.500
, k/* NV. 56.10 14.90 -- .276 l NNV 25.10 6.53 -- .068 1.100 9.920 I
L 4
o ;
i - i
(' 2-109 ISSUE 3
BV-1 cnd 2 ODCH TABLE 2.3-32 FOR INFORMATION ONLY BV-2 CONDENSATE POLISHING BUILDING VENT DISPERSION PARAHETERS (D/0)
FOR CONTINUOUS GkOUND LEVEL PELEASES >500 HRS /YR OR >150 HRS /QTR FOR S?ECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3)
(IE-9 meters-2)
INDIVIDUAL RECEPTORS D0VNVIND SITE VEGETABLE SECTOR BOUNDARY GARDEN HILK COV HILK GOAT HEAT 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 4.570 3.690
'S- 11.30 10.40' .934 -- 1.860 1.950 SSV 6.44 1.26 .664 .266 1.260 4.430 SV 3.95 2.21 -- 1.320 1.920 2.210 vsV 25.10 2.65 .597 -- 2.380 2.650 V 28.40 1.23 .646 --> .961 1.230 VNV 30.90 2.23 1.490 .045 2.230 2.230 NV 56.10 14.90 -- .276 1.980 15.500 NNV 25.10 6.53- -- .068 1.100 9.920 i
O i 2-110 ISSUE 3 J
i a;. '
, ~ BV-l'end12 ODCM- >
- ' '+ . TABLE 2.3-33 E1.
" ~
.a. -
FOR)INFORMATION ONLY-
> BV-2 DECONTAMINATION' BUILDING VENT DISPERSION PARAMETERSI(D/0) 0- POR CONTINUOUS GROUND LEVEliRELEASES >500 HRS /YR OR >150 HRS /0TR '
a
~FOR:SPECIAL DISTANCES (IDENTIFIED.IN TABLE 2.2-3),
g '
'(1E-9 meters-2)
+ y .o , ,
INDIVIDUAL RECEPTORS-'
' DOVNVIND- SITE . VEGETABLE .
t.
-SECTOR' ' BOUNDARY -GARDEN ; MILK-COV ; MILK G0AT: ' MEAT-ANIMAL. RESIDENCE..
a' N :' 25.40' 2.05. -- -0 .693 .E47- -2.190
.NNE. L18.80' -2.02 -- . 459? 1.850 2.110 W '
- NE' ~63.40 29.30 .455 .078' .455^ 30.400 32.200; ENE 65.90 l8.92 -- .661 --
'E. '38.00. 3.90 .382. '1.020i 1.020 .22.700' ESE .17.10- 3.56- ,.-- 1.380 3.560, .3.560 e t ,
- 1SE- 13.80' 3.03 .350'- ;350- 1.100 '3.030-SSE. '10.50~ .2.65 . 317- .094 .-2.570 3.680 r .
'~
S: 10;60 ' 1. 05 .- . 934 -- l'.860' l'.950:
H -SSV. '5.59 ~1;26- .663 . 266 1.260 4.420
, SV' 3.94 L2.21 .-- 1.320~ '1.920 2.210
- 1VSV. <27.50 2.65. . 596 --- .2.380 2.650-!
V: 31.60- 11.23 . 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' s
\
. h. '
i 9
i <
l r l
l
( j O -
2-111 ISSUE 3
! :- { 5 :
BV-1 cnd 2 ODCH TABLE 2.3 FOR INFORMATION ONLY BV-2 VASTE GAS STORAGE VAULT VENT DISPERSION PARAMETERS (D/0)
FOR CONTINUOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 ERS/0TR FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3)
(IE-9 meters-2)
INDIVIDUAL RECEPTORS D0VNVIND SITE VEGETABLE BOUNDARY GARDEN HILK COV MILK GOAT MEAT ANIMAL RESIDENCE SECTOR 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 O
2-112 ISSUE 3
, i BV-1 cnd 2 0DCM.
TABLE 2.3-35
-n-
/
.'BV-1 AND 2 CONTAINMENT VENTS DISPERSION PARAMETERS (X/Q) l
'FOR BATCH' GROUND LEVEL RELEASES <500 RRS/TR 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 'RESIDFECE 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 1.38E-7 6.05E-7 2.28E-5~
ENE '3.72E-5 5.25E --
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-5 5,61E-6 --
2.34E-6 5.61E-6 5.61E-6 SE 2 '.14E-5 '5.00E-6 8.13E-7 8.13E-7 2.03E-6 5.00E-6 SSE 2.21E-5 6.31E 1.11E-6 3.92E-7 6.13E-6 8.49E-6 S 2.15E-5 3.03E-6 2.76E-6 L- 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 SW 1.82E-5 1.03E-5 --
6.67E-6. 9.12E-6 1.03E-5 u VSV 1.09E-4 1.29E-5 4.10E-6 --
1.19E-5 1.29E-5 V- 1.49E 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 s\~/- NV 3.08E-4 6.13E-5 --
3.80E-6 1.36E-5 6.36E-5 NNV -1.80E-4 3.54E-5 -- 1.35E-6 9.27E-6 5.29E-5 I,
. /~'s - i* Measured. relevant.to center point between BV-1 and BV-2 Containment Buildings
-(
Period-of Record: 1976 - 1980 2-113 ISSUE 3
I BV-1 and 2 ODCM l TABLE 2.3-36 BV-1 AND 2 VENTILATION VENTS DISPERSION' PARAMETERS (X/Q) . ,
FOR BATCH GROUND LEVEL RELEASES <500 HRS /YR OR <150 HRS /0TR FOR SPECIAL DISTANCES (IDENTTFIED IN TABLE Y.2-3) 3 (sec/m )
INDIVIDUAL RECEPTORS DOWNWIND 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.'.15 E-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-5 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 J2.33E-4 2.07E-5 1.49E-5 1.30E-6 2.07E-5 2.07E-5 NV 3.32E-4 8.57E-5 -- 4.24E-6 1.64E-5 8.85E-5 NNV 1.90E-4 4.69E-5 -- 1.45E-6 1.09E-5 6.75E-5
- Measured relevant to center point between BV-1 and BV-2 Containment Buildings Period of Record: 1976 - 1980 2-114 ISSUE 3
BV-1 cnd 2 ODCM.
TABLE 2.3-37 vi -BV-1 AND 2 PROCESS VENT DISPERSION PARAMETERS'(X/0)
{ l .FOR BATCH ELEVATED RELEASES <500 HRS /YR OR ~<150 HRS /0TR FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3)
(sec/m )
. INDIVIDUAL RECEPTORS D0VNVIND SITE VEGETABLE SECTOR * , BOUNDARY GARDEN- ' MILK COV MILK GOAT MEAT ANIMAL RESIDENCE N 3.09E-9 3.30E-6 --
1.13E-6 1.34E-6 3.36E-6 NNE ~ 2.85E-9 2.68E-6~ -- 6.52E-7 2.47E-6 2.68E-6 NE. 2.02E-10 7.42E-9 5.44E-7 1.24E-7 5.44E-7 5.51E ENE 1.02E-9 '3.21E-6 -- 6.29E-7 - 1. 67E--9 i
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 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 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 I SSV- .4.83E-6 2.52E-6 1.50E-6 6.60E-7 2.52E-6 3.96E-6 SV 4.82E-6 2.75E-6 -- 1.78E-6 2.44E-6 2.75E-6 VSV 5.77E-7 2.81E-6 8.79E-7 -- 2.57E-6 2.81E-6
- V 2.88E-9 1.68E-6 4.89E-7 -- 1.37E 1.68E-6 VNV 3.40E-9' 1.61E-6 1.13E-6 1.10E--7 1.61E-6 l'.61E-6
.[v) NV 1.34E-9 3.31E -- 2.03E-7 1.07E-6 3.10E-8 NNW 1.52E-9 3.73E-6 -- 1.73E-7 1.31E-6 3.81E-6 i
l' i
l
(-
1 l
{. l l
- Measured relevant to BV-1 natural c. raft cooling tower v
Period of Record: 1976 - 1980 m ,
2-115 ISSUE 3
3 0
E U
S 5
7777 EEEE 7777 EEEE
- - 7777-EEEE 7777 EEEE
- - S I
6122 2382 0757 8906 5
4 0838 5453 8863 4333 0780 4455 4865 5444 O
5 7 8
4 7777 7777 7777 7777 9
- - - - - - - - - - - 1
- E E- E E- EEEE EEEE EEEE ,
3446 1725 4299 0827 0 0 9630 1339 7689 8243 3 5555 .
4 5566 5443 4565 y r
0 a u
n 4 7777 E E E- E 7777 E E E- E 7777 EEEE
- - 7777-EEEE J a
3163 2644 4172 8128 1572 9772 2315 6614 n 5 o 3 7667 6555 6677 7466 1
- t 4 S 2
) u E 5 2 Q v L I 3 7777 7777 7777 7777 1
// - - - - - - -
XS M EEEE EEEE EEEE E- E E E- .
( R -
6593 B N 4585 8022 4045 7715 5396 7810 8700 O.
S I 0 J R0 4788 E5 ,3 8899 8676 7789 r T1 5 4 e E$ 4 d
M O 0 n AR I T 3 6666 6666 u RO 6666 6777 A A - - - -
EEEE EEEE EEEE EEEE
- - 1 PR C -
2382 7811 5788 8 Y O 3393 1954 1010 2100 9 N/ I 5 1111 9 M OS 1999 1111 1111 2 C IR L 2 1111 -
D 8 SH O S O 3 R R L 6
- E0 ) T 5 D 1 2 3 P03 N 2 1 6646 O
S5 O 2 6666 6666 6666 -
d /m C - - - - - - - -
r n
2 I<
D c - EEEE- -
E E- EE E- EEE 9856 EEEE 9960 e 2
a E S e E 1626 4419 5424 6544 t L IE T s E 0 5376 4332 t 1 B S ( I e
A DA '
2 1111 1111 1111 1111 l
V- T VE O B L I' .
SE 0 p SR S r E E 2 6666 6666 6666 6666 o CD C - - - - - - - - - - - - - -
OE N - EEEE EEEE EEEE EEEE C RT A 5 1981 3495 4899 9245 g FAV T 6122 2099 3112 4921 S i n
2E I 1 2222 2211 2222 2122 r L D e DE e N 5 n Ai 6666 6666 6886 i u 1 6686 g
1 t
- EEEE E E E E- E E E E- E E E- E- n VA B 0390 7883 7476 1676 E B 0 1836 7433 9841 2636 r R 2333 3233 4583 e O 1 4272 t F s 0 b e
1 5688 6666 6666 6886 W EEEE EEEE EEEE EEEE d 7977 0636 2215 2481 n 5 0368 1218 1213 5499 a 0 1518 5534 4699 4113 e n
t o
5 S 5765 53 7865 0 1111 1188 7558 1111
- - - - - - - - - - - - - a EEEE EEEE EEEE EEEE i 5052 4660 2586 4511 v 0 7949 8915 2705 4269 l
0 2541 1293 1128 5921 a t
R t
i m
s O
_ w E
NEN E
EESS E
SES E
sSSW N
SWS W
WNNN M
t WtM n
a r
A NNNE T t
- S
i ;
s l< . ,
BV-1 and 2 ODCMt
- ;
- r.
l \ :3 ;
' ~
..-;l2.4 Gaseous Radveste System
'/ 9 'TheR gaseous radvaste' system- has- the = capability. to control,fcollect, "sj 2
' process,. store,, recycle, and dispose'of gaseous. radioactive vaste generated' Las oa-: result:Lof ' plant operations, ' including anticipated operational; E occurrences.-
LA: simplified: flow diagram-of the' g'aseous %- Aste" system'for BV-1:and'BV-2; is provided act Figure L 2'.4-1. .- A s ; diagram 1 ~ showing the gaseous ef fluentJ
, releaseLpointsels.provided:as Figure 2.4-2.- Since'the concept of a shared' gaseous _radweste , system is .used, "thenl gaseous vaste generated'ean;be stored,J processed,J and discharged from - either. BV-1. or: BV-2.
g
.l 1
i
- /
% ),
i l
L i
I l
[
O A- / ,
L.' a: 2-117 ISSUE 3
1 i
BV-1 Cnd 2 ODCM 2.4.1 BV-1 Gaseous Radvaste System Components 2.4.1.1 BR-EV-2A & 2B Degasifiers There are two Degasifiers. They are designed to continuously process reactor coolant letdown for reducing entrained noble gases in the liquid.
1 2.4.1.2 GV-E-1A & IB: Vaste Gas-Chillers '
There are two Chillers. Non-condensable gases from the degasifiers are directed by system pressure to the Vaste Gas Chillers.
2.4.1.3 GV-TK-3A, 3B, 3C, & 3D: Gaseous Vaste Charcoal Delay Beds There are four Charcoal Beds. The dry effluent from the Chillers is directed to the Vaste Gas Charcoal Delay Beds for holdup of xenon and krypton and adsorption of radioiodines. When four beds are operated in ser:'as, they provide a holdup of xenon isotopes for about 30 days.
2.4.1.4 GV-lu A & SB: Overhead Gas Compressor Prefilters There are two Prefilters. The gaseous effluent (primarily-hydrogen) is directed from the Gaseous Waste Charcoal Delay Beds to one of the Overhead Gas Compressor Prefilters. The filters remove carbon solids from the gas stream.
2.4.1.5 GV-C-1A & IB: Gas Compressors There are two Compressors. The vaste gas enters one of the compressors after passing through the Prefilters.
2.4.1.6 GV-TK-2: Gaseous Vaste Surge Tank There is one Surge Tank. It has a capacity of 52 cuft. After compression to about 65 psig, the vaste gas is sent to the Surge Tank.
This can be done automatically or manually.
2.4.1.7 GV-TK-1A, 1B, & IC: Vaste Gas Decay Tanks There are three Decay Tanks. Each has a capacity of 132 cuft. The contents of the Surge Tank is transferred to the Decay Tanks for storage and decay. After 30 days of storage, all xenon and iodine l should have decayed, and the resulting predominant nuclide should be
} krypton 85.
0 l
2-118 ISSUE 3 1
j ..
( ,
BV-1 and 2'0DCM -
_l 22.4.1.8 RM-GV-108 And RM-GV-109: Gaseous Effluent Radiation Monitors L
(}> There are redundant , Radiation Monitors on the combined BVil and 2-l\'
~
gaseous vaste ~ release path. These Radiation Monitors continuously I
analyze gaseous vaste as it is being discharged.. Gaseous-Monitor RM-l~
- GV-108B:is-an off-line gamma scintillator, while RM-GV-109 Channel 5~is an off-line beta scintillator.. The upper activity: alarm =on the gaseous Channels-of..these Radiation Monitors have setpoints that would indicate ve are approaching 1the' Total Body Dose Rate,or Skin Dose Rate limits for radioactive gas leaving-the : site. :If.an upper activity alara on RM-GV-108 is received, :it.. automatically : terminates: the discharge by closing an. isolation valve downstream of the Decay Tanks.
i,.
y h
)
l l
x) 2-119 ISSUE 3 l- i
BV-1 cnd 2 ODCM 2.4.2 BV-2 Gasecus Radvaste System Components 2BRS-EV21A & 21B: Degasifiers 2.4.2.1 f
There are four Degasifiers (two at Unit I and two at Unit 2). They.are designed to continuously process reactor coolant letdown for reducing entrained noble gases in the liquid. ,
2.4.2.2 2GVS-E21A & 21B Vaste Gas Chillers There are four Chillers (two at Unit 1 and two at Unit 2). Non-condensable gases from the degasifiers are directed by system pressure to the Waste Gas Chillers.
2.4.2.3 2GVS-TK22A, 22B, 22C, & 22D: Vaste Gas Charcoal Delay Beds There are four Charcoal Beds (four at Unit 1 and four at Unit 2). The dry effluent from the Chillers is directed to the Vaste Gas Charcoal Delay Beds for holdup of xenon and krypton and adsorption of radiciodines. When four beds are operated in series, they provide a holdup of xenon isotopes.for about 30 days. _
2.4.2.4 2GVS-FLT24A & 24B: Overhead Gas Compressor Prefilters There are two Prefilters. The gaseous effluent (primarily hydrogen) is directed from the Vaste Gas Charcoal Delay Beds to one of the Overhead Gas Compressor Prefilters. The filters remove carbon solids from the gas stream.
2.4.2.5 2GVS-C21A & 21B: Gas Compressors There are two Compressors. The vaste gas enters one of the compressors after passing through the Prefilters.
2.4.2.6 2GVS-TK21: Gaseous Vaste Surge Tank .
There is one Surge Tank. It has a capacity of 52 cuft. After cocpression to about 65 psig, the vaste gas is sent to the Surge Tank.
This can be done automatically or manually.
2.4.2.7 2GVS-TK25A, 25B, 250, 25D, 25E, 25F, & 25G: Gaseous Waste Storage Tanks There are seven. Decay Tanks. Each has a capacity of 132 cuft. The contents of the Surge Tank is transferred to the Decay Tanks for storage and decay. After 30 days of storage, all xenon and iodine should have decayed, and the resulting predominant nuclide should be krypton 85.
2.4.2.8 RM-GV-108 And RM-CV-109: Gaseous Effluent Radiation Monitors Previously described in Section 2.4.1.
t O
2-120 ISSUE 3
'BV-1 cnd 2 ODCM j FIGURE 2.4-1
-g BV-1 AND 2 GASEOUS RADVASTE SYSTEM ,
l
($fn!dt ktY ' 10 Aino$NDE 1 ,
I j "
i i . . . .
,,g y '
UNIT 1 UMit 2 PRDILTDS QAl GAS l C0eRES$0R COMPRESSOR > '
n k k'
$ URGE fAMK SURGE 1AM (CHARCML 3D , .
.......... 15 6 I
DECAV TAMK QARCML BD , ,
DECAY TAME l
CCHARCML BD) DECAY IAMK
-(s I ;
" " " DECAv fAs m Ds II(AI IAE IEDY IAN D_ :
s nLTEts DECAf i m DECAY TA E l '
i DECAT TAMK DECAT TA * >
.c ,
X <
i=r as
=$ma
.mu .a *D +
Co mum +
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2-121 ISSUE 3
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.- .l BV-1 Ond 3 ODCH FIGURE 2.4-2 BV-1 AND 2 GASEOUS EFFLUENT RELEASE POINTS
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- 1. Unit 1: Ventftation vent 79 feet = 24 meters
- 2. Unit 1: Containment / SLCRs vent
- 3. Unit 112: Process vent 154 feet = 47 meters 475 feet = 145 meters g
- 4. Unit 2: Ventilation Vent 85 feet = 26 meters
- 5. Unit 2: Contairwent / SLCRs vent 154 feet = 47 meters
- 6. Unit 2: Condensate Polishing Building vent 80 feet = 24 meters 4[t 7 ,
- 7. Unit 2: Waste cas Storage Vault Vent 80 feet = 24 meters , l
- 8. Unit 2: Decontamination Bul1 ding vent 80 feet = 24 meters
- 9. Unit 2: Turbine Building vent 109 feet = 33 meters l l Note: The Release Point shown for the Unit 2 Turbine Building vent is l f7 a representative exhaust point for the to roof exhaust outlets. j 2-122 ISSUE 3 Revision 3
m BV-1 cnd 2 ODCH i
3.0- RADIOLOGICAL-ENVIRONMENTAL MONITORING PROGRAM
- i h)
", The following program requirements are . excerpts from the Radiological Assessment Br anch Technical Position,~ Revision 1,1979.
Table 3.0-1.contains the DLC site number, sector, distance, sample point description, sampling and collection frequency, analysis, and analysis
' frequency for various exposure pathways in the vicinity of the Beaver E _ Valley Power Station for the radiological environmental monitoring program.
Figures 3.0-1 through 3.0-9 -show the location of- the various sampling points.
PROGRAM REQUIREMENTS Environmental samples shall be collected and analyzed according to Appendix C, Table 3.0-1. Analytical techniques used shall be such that the.
detection capabilities in Appendix C, Table 4.12-1 are a hieved.
The results of the radiological environmental monitoring are intended to supplement the results of the radiological effluent monitoring by verifying that the measurable concentrations of 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
,(A) radiological environmental monitoring program should be conducted for the
.first 3 years of commercial operation (or other period corresponding to a 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.
The laboratories of the licensee and licensee's contractors which perform analyses shall participate in the Environmental Protection Agency's (EPA's)
Environmental Radioactivity Laboratory Intercomparisons Studies (Crosscheck) Program or equivalent program. This participation shall include all of the determinations (sample medium-radionuclide combination) that are offered by EPA and that also are included in the monitoring program. The results of analysis of these crosscheck samples shall be included in the annual report. The participants in the EPA crosscheck program may provide their EPA program code so that the NRC can review the EPA's participant data directly in lieu of submission in the annual report.
p)
.iv I
l' 3-1 ISSUE 3 l
l 4
BV-1 cnd 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). 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'(vith 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 lowest calculated dose may then be dropped from the surveillance program at the end of the grazing or growing season during which the census was conducted. Any location from which milk can no longer be obtained may be dropped from the surveillance program after notifying the NRC in writing that they are no longer obtainable at- that location. The results of the land-use census shall be reported in the annual report.
The census of milk animals and gardens producing broad leaf vegetation is based on the requirement in Appendix I of 10 CFR Part 50 to " Identify changes in the use of unrestricted areas (e.g., for agricultural purposes) to permit modifications in monitoring programs for evaluating doses to individuals from principal pathways 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.
f 3-2 ISSUE 3 Revision 2
BV-1 cnd 2 ODOM w
r The 50 square meter' garden, considering 20% used for growing broad leaf I
( '
- vegetation (i.e., sin'lar to lettuce and cabbage), and a vegetation yield
(/ _
of 2 kg/m ,2 vill produce the 26 kg/yr assumed in Regulatory Guide 1.109, Rev. 1, for child consumption of leafy vegetation. q47 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 radioectivity releases, of 10 CFR Part 50, Appendix A. The NRC vill place a similar amount of stations in the area between the two rings designated in Appendix C, Table 3.12-1.
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BV-1 Ond 2 ODCM FIGURE 3.0-5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TLD LOCATIONS - SOUTHVEST GUADRANT
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.4.01 5 FORMATION RELATED TO 40 CFR 190 "d. ,,) ..'cppendix. C . CONTROL 3.11.4.1 . requires thatL vhen the calculated doses
" associated with the'. effluent releases exceed twice the limits of Appendix C CONTROL '3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a. 3.11.2.2.b,. 3.11.2.3.a, or 3.11.2.3.b,. calculations shall be made including ' direct radiation contributions from the' units (including. outside storage tanks, etc.)'to determine whether the dose or-dose commitment .to any MEMBER OF THE PUBLIC s
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 f 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.ifo11oving. shall be -included.'in the Special' Report:
- Define the corrective ac' tion 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.
A V '
' Describe levels of radiation and concentrations of radioactive material
' involved, and the cause of exposure levels or concentrations.
- If the estimated dose (s) exceeds the limits of Appendix- C CONTROL 3.11.4.1, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, include a request for a variance in.accordance with +.he 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.
s AJ 4-1 ISSUE 3
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' APPENDIX A
SUMMARY
OF DISPERSION CALCULATIONAL PROCEDURES U
- - ^
AnnualjaverageTand'~grazingseasonaveragevaluesof!relativeconcentration(X/Q')-
and deposition-(D/0) -were?. calculated' for continuous and' intermittent gaseous ereleases:of.-l activity..from . the '. .' site > ' according to the straight-line airflow (Gaussian) model described.in NRC Regulatory Guidei 1.111; Revision 1. Undecayed'
'and:undepleted' sector _ average .X/0 and -D/0 values' were .obtained for each of-
' sixteen 22.5-degree .. sectors =at .the. siteJ-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 ,vas taken for.the effective release.heightLwhich.is comprised of the physical release height ~plus momentum' plume rise minus the terrain ' height at a given receptor. A' building wake. correction factor was..used to . adjust . calculations for^ ground-level -
releases. : Airflow reversals-vere 'also accounted for by/ applying site-specific terrain-recirculation factors for both. ground. and elevated releases at.theisite
'(Albersheim,-1978)., The methodology employed'in the calculation of intermittent release-X/0 and D/0 values' is that described in.NUREG/CR-2919.(Sagendorf, et. _
' al . "- 1982) . -
' The site continuous gaseous release: points : that have been ' evaluated include the process' vent attached to the BVPS-1 natural draft cooling tower, the Containment
. Vents,.i Ventilation - Vents, Turbine Building Vents, .the~ BVPS-2 . Condensate
' Polishing .: Building Vent,- Decontamination Building Vent, and Gaseous-Vaste Storage Tank Vault Vent.. The intermittent releases are from the Process Vent,.
Containment Vents,'and Ventilation Vents. Only the process vent was considered'
.O to be an elevated release with all other release points being treated as ground' d level releases. .A summary of the. release characteristics.and their locations is
.giventin Appendix A, Table 1.1.
E0nsite meteorological data for the period January 1,.1976 through-December 31,:1980 were used as' input .for the annual-average calculations. The grazing' season was represented by.a six-month period from May 1 through October.31-for each year of the 5-year meteorologica1' data. base. .This grazing ~
. season corresponds reasonably'ywell- with the growing- season.- The data vere
. collected according to guidance in. NRC Regulatory Guide 1.23 as described in 1- Seetion 2.3:of the BVPS-2.FSAR. The parameters used in the X/Q-D/0 calculations
% aconsist of vind speed, vind- direction,. and .AT as an_ indicator of atmospheric 1 stability. The lover. level vinds (35 ft) and AT (150-35.ft) vere used for all '
release: points except the process-vent ~ vhich- required the use of 500 ft vinds and 4T:(500-35 ft) which are representative of the. release height _(510 ft).
'The annual average and grazing season X/0 and D/0 values for the continuous and sinteraittent radioactive releases were calculated at the site boundary, nearest
' resident,. nearest vegetable garden,- nearest milk cow, nearest milk goat, and
' nearest meat animal. In the case of the process vent releases, several of each-
.receptoretype were evaluated;.in each downwind sector to determine the maximum i
.X/Q-D/0 values. ,The distances of the limiting maximum individual receptors from- ;
,the radioactive release points are given in Table 2.2-3. The continuous release j
. annual. average X/0 values at .the special locations for the Containment Vents, !
I
> Ventilation -Vents, 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 annual average X/Q's for these same release points are also given at ten A-1 ISSUE 3 i
' l y ,
r ,
BV-1 Cnd 2 ODCH APPENDIX A
SUMMARY
OF DISPERSION CALCULATIONAL PROCEDURES (continued)
O incremental downvind distances. Continuous. release D/0 values for these same release points are given in Tables 2.3-21 through 2.3-27 for the incremental distances and in Tables 2.3-28 through 2.3-34 for the special locations. Due to their location adjacent to the containment building, the BVPS-2 Decontamination Building and Gascous Waste Storage Tank Vault X/0's and D/O's are the same as the containment vent X/O's and D/0's. Likewise, the Turbine Building Vent X/O'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 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> per year of Containment and Ventilation Vent purges and 74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br /> per year of Process Vent purges.
O Albersheim, S. R., Development Of Terrain Adjustment Factors For Use At the
. Beaver Valley Power Station For the Straight-Line Atmospheric Dispersion Model, NUS-2173, NUS Corporation, June 1978 Sagendorf, J. F., Goll, J. T. and Sandusky, V. F., X00D00: Computer Program 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 cnd 2 ODCH APPENDIX A TABLE A:1
~~
BV-l'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 Release Point 26 47 155 33 Height (m)
' Adjacent Building 19 44 155 - 33
' Height (m)
Relative Loca- E. Side Of Top Center Of Atop Cooling Turbine tion To Adjacent Primary Auxi- Containment Tower Building Structures liary Bldg Dome
( ) Exit Velocity NA NA 9.4 NA
~'
(m/sec)
Internal Stack NA NA 0.25 NA Diameter (m)
Building Cross- 2 1600 1600 NA NA Sectional Area (m )
Purge Frequency
- 32 32 74 NA (hours / year)
Purge' Duration 8 8 NA NA (hrs / release) l
\
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- 8.s
" Applied to Short Term 1culations only A-3 ISSUE 3 Revision 1 i I
J
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.BV-1 and 2 ODCM L-l APPENDIX B
- l. ..
' /NL INPUTS TO COMPUTER CODES FOR GENERATION OF SOURCE TERMS Yh ,
This gAppendix'contains the input parameters to the various computer codes.used
.by Duquesne Light Company and its subcontractors for determination of the Liquid and Gaseous source-term; mixes. The inputs are contained in' the _following Tables i
~o f this: Appendix:.
1 Table B:la Inputs To Gale 1' Code For- Generation Of BV-1 Liquid Source Term.
Mixes-Table B:1b ~ Inputs To SVEC' LIQ 1BB Code For Generation Of BV-2 Liquid Source Term Mixes .
4
- Table B:2a' _ Inputs To:SVEC GAS 1BB Code For.-Generation Of BV-1 Gaseous Source
,l Term Mixes ~
Table B:2b- Inputs To SVEC.GASIBB Code For Generation Of BV-2 Gaseous. Source Term Mixes f
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r-B-1 ISSUE 3 Revision 1
BV-1 sad 2 ODCM APPENDIX B TABLE B:la ,
INPUTS TO GALE CODE FOR GENERATION OF BV-1 LIQUID SOURCE TERM MIXES BV-1 PUR INPUTS VALUE Thermal Power Level (megavatts) 2766.000 Flant Capacity Factor .800 Mass Of Primary Coolant (thousand Ibs) 345.000 Percent Fuel With Cladding Defects .120 Primary System-Letdown Rate (gpm) 60.000 Letdown Cation Demineralizer Flow 6.000 Number Of Steam Generators 3.000 Total Steam Flov (million lbs/hr) 11.620 Mass Of Steam In Each Steam Generator (thousand lbs) 6.772 Hass Of Liquid In Each Steam Generator (thousand lbs) 97.000 Total Mass Of Secondary Coolant (thousand Ibs) - 1296.000 Mass Of Water In Steam Generator (thousand lbs) 291.000 Blowdown Rate (thousand lbs/hr) 33.900 Primary To Secondary Leak Rate (1bs/ day) 100.000 Fission Product Carry-Over Fraction .001 Halogen Carry-Over Fraction .010 Condensate Demineralizer Flov Fraction 0.000 Radvaste Dilution Flov (thousand gpm) 22.500 BV-1 LIQUID WASTE INPUTS COLLECTION DELAY DECONTAMINATION FLOV RATE FRACTION FRACTION TIME TIME FACTORS STREAM (gal / day) 0F PCA DISCHARGE (days) (days) I Cs OTHERS Shim Bleed 1.32E4 1.000 0.000 11.260 7.220 1E7 1E7 1E7 Rate Equipment 6.00E2 1.000 0.000 11.260 7.220 1E7 1E7 IE7 Drains Clean Vaste 7.50E1 1.000 1.000 0.071 0.648 1ES 2E4 1E5
- Input Dirty Vaste 1.35E3 0.035 1.000 0.071 0.648 1ES 2E4 lE5 Input Blowdown 9.75E4 --
1.000 0.071 0.648 1E5 2E4 1ES Ur.t reated 0.0 -- -- -- -- -- -- --
.Blovdown B-2 ISSUE 3 Revision 1
BV-1 gnd 2 ODCM APPENDIX B
( "N TABLE B:1b %r INPUTS TO SVEC LIQ 1BB CO:;E FOR GENERATION OF BV-2 LIQUID SOURCE TERM MIXES BV-2 PVR INPUTS VALUE Thermal Power Level (taigawatts) 2766.000 Plant Capacity Factor- .800 Mass Of Primary Coolant (thousand lbs) 385.000 Percent Fuel Vith~ Cladding Defects .120 Primary System Letdown Rate (gpm) 57.000 Letdown Cation Demineralizer Flow 5.700 Number Of Steam Generators 3.000 Total Steam Flov (million Ibs/hr) 11.600 Mass Of Steam In Each Steam' Generator (thousand Ibs) 8.700
' Mass Of Liquid In Each Steam Generator (thousand lbs) 100.000 Total Mass of Secondary Coolant (thousand lbs) - 2000.000 Mass Of Water In Steam Generator (thousand Ibs) 298.000 Blovdown Rate (thousand lbs/hr) 22.300 Primary To Secondary Leak Rate (lbs/ day) 100.000 Fission Product Carry-Over Fraction .001
,, Halogen Carry-Over Fraction .010 -!
( Condensate Demineralizer Flow Fraction .700
.V)
Radvaste Dilution Flov (thousand gpm) 7.800 BV-2 LIQUID VASTE INPUTS i 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 l
l Miscellaneous 700 0.010 1.0 35.5 6.2 1E3 1E4 1E4 l Sources l
! Rx Plant 35 1.000 1.0 35.5 6.2 1E3 1E4 1E4 i--
Samples Lab Drains 400 0.002 1.0 35.5 6.2 1E3 1E4 1E4 Cond. Demin. 2685 1.1E-4 1.0 35.5 6.2 1E3 1E4 1E4 Rinse Vater CVCS 60 -- 1.0 1300 173 1E4 4E3 1E5
(~
- ),
Turbine Bldg. 7200 --
1.0 -- -- -- -- --
Drains B-3 ISSUE 3 Revision 1
BV-1 Ond 2 ODCM APPENDIX B TABLE B:2a INPUTS TO SVEC GAS 1BB CODE FOR GENERATION OF BV-1 GASE0US SOURCE TERM MIXES BV-1 PVR INPUTS VALUE 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 Lerdown Rate (gpm) 57.000 Letdown Cation Demineralizer Flov 5.700 Number of Steam Generators 3.000 Total. Steam Flov (million lbs/hr) 11.600 Mass Of Steam In Each Steam Generator (thousand lbs) 8.700 Mass Of Liquid In Each Steam Generator (thousand lbs) 100.000 Total Mass Of Secondary Coolant (thousand lbs) 2000.000 Mass Of Vater In Steam Generator (thousand lbs) 298.000 52.000 Blovdown Rate (thousand Ibs/hr)
Primary To Secondary Leak Rate (1bs/ day) 100.000 Fission Product Carry-Over Fraction .001 Halogen Carry-Over Fraction .010 Condensate Demineralizer Flow Fraction 0.000 Radvaste Dilution Flow (thousand gpm) 15.000 BV-1 GASEOUS _VASTE INPUTS VALUE
/of There Is Not Continuous Stripping Of Full Letdown Flow Hold Up Time For Xenon (days) 39.000 Hold Up Time For Krypton (days) 2.000 Primary Coolant Leak To Auxiliary Building (1b/ day) 160.000 Auxiliary Building Leak Iodine Partition Factor 7.5E-3 Gas Waste System Particulate Release Fraction 0.000 Auxiliary Building Charcolodine Release Fraction 1.000 Particulate Release Fraction 1.000 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 I Frequency Of Containment Building High Vol Purge (times /yr)* 4.000 j Containment Volume Purge Iodine Release Fraction 1.000 j Particulate Release Fraction 1.000 l Steam Leak To Turbine Building (lbs/hr) 1700.000 J Fraction Iodine Released From Blovdown Tank Vent 0.000 )
Fraction Iodine Released From Main Condensate Air Ejector 0.440 There Is Not A Cryogenic Off Gas System
- 2 cold and 2 hot purges O
B-4 ISSUE 3 4 Revision 1 l i
_ _ _________ _ _ _ _ _ _ _ _________________ _________ ___. ._________j
[=
L:
BV-1 end 2 ODCM APPENDIX B TABLE B:2b Ig INPUTS TO SVEC GAS 1BB CODE FOR GENERATION OF BV-2 GASEOUS SOURCE TERM MIXES BV-2 PVR INPUTS VALUE l Thermal Power Level (megawatts) 2766.000
. Plant Capacity Factor .800
-Mass Of Primary Coolant (thousand lbs) 385.000 Percent Fuel With Cladding Defects
.120 Primary System Letdown Rate (gpm) 57.000 Letdown Cation Demineralizer Flow 5.700 Number Of Steam Generators 3.000 Total Steam Flow.(million lbs/hr) 11.600 Mass Of Steam In Each Steam Generator (thousand lbs) 8.700 Hass Of Liquid In Each Steam Generator (thousand lbs) 100.000 Total Hass Of Secondary Coolant (thousand lbs) 2000.000 Hass Of Water In Steam Generator (thousand lbs) 298.000 Blowdown kate (thousand Ibs/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 Flow (thousand gpm) 7.800
) BV-2 GASEOUS VASTE INPUTS VALUE aff There Is Not Continuous Stripping Of Full Letdown Flov Hold Up Time For Xenon (days) 45.800 Hold Up Time For Krypton.(days) 2.570 Primary Coolant Leak To Auxiliary Building (lb/ day) 160.000 Auxiliary Building Leak Iodine Partition Factor 7.5E-3 l Gas Vaste System Particulate Release Fraction 0.000 i Auxiliary Building Charcolodine Release Fraction 0.100 l Particulate Release Fraction 0.010 Containment Volume (million cu-ft) 1.800 Frequency Of Primary Coolant Degassing (times /yr) 2.000 Primary To Secondary Leak Rate.(1b/ day) 100.000 l There Is A Kidney Filter
. Containment Atmosphere Cleanup Rate (thousand efm) 20.000 l 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 Blowdown Tank Vent 0.000 l
Fraction Iodine Released From Main Condensate Air Ejector 0.270 l There Is Not A Cryogenic Off Gas System 1 !
, QJ
!, *2 cold and 2 hot purges B-5 ISSUE 3 Revision 1
BV-1 cmd 2 ODCM APPENDIX C ODCM CONTROLS f ;
C/ This appendix contains procedural details for the Radiological Effluent Technical Specification (RETS) that were transferred from the Technical Specifications per Unit 1/2' Amendments 188/70, and in accordance with Generic Letter 89-01 and Generic Letter 89-01, supplement No. 1 (NUREG 1301).
This appendix. also includes selected Definitions and Tables as delineated in Section .1 of the Technical Specifications and selected applicability'and surveillance requirement statements as delineated .in Section 3/40 of the Technical -Specification.c. These were added to Appendix C for reference purposes, even though they are currently described in the Technical Specification. ,,
The numbering of each specific Control, Surveillance Requirement and' Table contained in the appendix does not appear to be sequential. This is intentional, as all Control, Surveillance Requirement and Table numbers remained the same when they were transferred from the Technical Specifications. This vas done in an effort. to- minimize. the amount nf plant procedure changes and to eliminate any confusion associated with number:ng changes.
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C-1 ISSUE 3 Revision 1
BV-1 cnd 2 ODCM l APPENDIX C ODCM CONTROLS CONTROLS: DEFINITIONS The defined terms of this section appear in capitalized type and are applicable throughout these CONTROLS.
l THERMAL POWER 1.2 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
RATED THERMAL POWER 1.3 RATED THERHAL 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 ascorollarylh 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 instrumenta tion, controls, normal and emergency electric power sources, cooling or seal vater, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related safety function (s).
REPORTABLE EVENT 1.7 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.
CHANNEL CALIBRATIOff 1.9 A CHANNEL CALIBRATION shall be the adj ustment , ac necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be per'ormed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.
C-2 ISSUE 3 Revision 1
BV-1 cnd 2 ODCM APPENDIX C ODCH CONTROLS t 1 CONTROLS: DEFINITIONS (continued)
j 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 OPERABILITY including alarm and/or trip functions.
DOSE EQUIVALENT I-131 1.19 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (uci/ gram) which alone vould produce the same thyroid ' dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table E-7 of Regulatory Guide 1.109, Revision 1, 1977 or Table III of TID 14844.
( ) FREQUENCY NOTATION w/
1.21 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.2.
SOURCE CHECK 1.27 A SOURCE CHF'!K shall be the qualitative assessment of channel response whea the channel sensor is exposed to a radioactive source.
OFFSITE DOSB CALCULATi?N HANUAL (ODCM) 1.30 The OFFSITE DOSE CALCULATION MANUAL (ODCH) shall contain the methodology j and parameters used in the calculation of offsite doses resulting from )
radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of !
the Environmental Radiological Monitoring Program. The ODCM shall also i contain (1) the Radioactive Effluent Controls and Radiological i Environmental Honitoring 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.
- f. GASEOUS RADVASTE TREATMENT SYSTEM 1.31 A GASE0US RADVASTE TREAT!iENT SYSTEM is any system designed and installed
/]
b 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.
C-3 ISSUE 3 Revision 1
BV-1 cnd 2 ODCM e APPENDIX C ODCM CONTROLS CONTROLS: DEFINITIONS (continued)
LVENTILATION EXHAUST TREATMENT SYSTEM 1.32 VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing 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.
1.33 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating conditions, in such a manner that replacement air or gas is required to purify the confinement. ..
VENTING 1.34 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating conditions, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process. f MEMBER (S) 0F THE PUBLIC 1.36 MEMBER (S) 0F THE PUBLIC shall include all individuals in a controlled or unrestricted area. However, an individual is not a MEMBER OF THE PUBLIC during any period in which the individual receives occupational dose. [9 SITE BOUNDARY 1.38 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee. (See Figure 5-1)
UNRESTRICTED AREA 1.39 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes. For gaseous release dose calculations, the UNRESTRICTED AREA should exclude any public road, railway, or waterway adjacent to or crossing the site that is not occupied continuously by MEMBER (S) 0F TH PUBLIC.
C-4 ISSUE 3 Revision 1
- < u . BV-l'.rmd 2 ODCM ? ;
^
% m. 1.i APPENDIX'C-
- d" ~
ODCM. CONTROLS' TABLE.1.1 OPERATIONAL MODES
., t
- e ' REACTIVITY: -~% RATED- AVERAGE COOLANT MODE' ' CONDITION,.Kggf ' THERMAL POWER *' TEMPERATURE 11.--l Power Operation: >0'.99 >5% >350*F
). 2. . Startup' . >0.99 35%. >350'F.~
Hot Standby < 0.99 >35d'F
.-3. .
0 1 4;--Hot-Shutdown' <0.99 O 350*F >T"*I'
>200*F
-.5. Cold Shutdown- <
.0.99' O. f200*F
- 6. -
Refueling **- 30.95 0 $140*F s
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- Excluding decay heat.
..O' ** Reactor vessel head unbolted or removed and fuel in the vessel. l l
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-c , C-5. ISSUE 3 l.n %
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BV-1 cad 2 ODCM APPENDIX C
. 0DCM CONTROLS TABLE 1.2 FREQUENCY NOTATION NOTATION FREQUENCY S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> V At least once per 7 days M At least once per 31 days 0 At least once per 92 days SA At least once per 184 days R At least.once per 18 months ~
S/U Prior to each reactor startup P Completed prior to each release N.A. Not applicable O
- ,., C-6 ISSUE 3 g-
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( BV-1 cnd 2 ODCH l .
- . APPENDIX C j' ODCM CONTROLS
> T t
.N/ CONTROLS: APPLICABILITY 3.0.1 Compliance with the CONTROLS in the succeeding CONTROLS is required during tha 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 H0DE in which the CONTROL does not apply by- placing it, as applicable, in: _
- l. At least HOT STANDBY vithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,
- 2. At least HOT SHUTDOWN vithin the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and
- 3. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Where corrective measures are completed that permit operation under the e
r '3 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 H0DE or specified condition may be made in accordance with ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements. Exceptions to ,
these requirements are stated in the individual CONTROLS. !
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C-7 ISSUE 3
BV-1 cnd 2 ODCM APPENDIX C ODCM CONTROLS CONTROLS: SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL H0 DES 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 allowable extension not to exceed 25% of the surveillance interval.
I 4.0.3 Failure to. perform a' Surveillance Requirement within the allowed i 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 to to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the a.lavable outage time limits of the ACTION requirements are less than 24 h6urs. Surveillance Requirements do-not have to be performed on inoperaale equipment.
4.0.4 Entry into an OPERATIONAL H0DE or other speci)!1ed c.ondition shall not be made unless the Surveillance Requirement (s) associated with the CONTROL ;
has been performed within the stated surveillance interval or as !
otherwise specified. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.
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C-8 ISSUE 3
E o
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- BV-1 cnd-2 ODCH APPENDIX C
-ODCH CONTROLS
} .
' CONTROLS:
RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION
, ?1 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. Thei alarm / trip setpoints of the radiation monitoring channels shall be- determined in accordance'vith
- u. Section 1.1.1'and 1.1.2 of this manual.~
Applicability:
During releases through the flow path.
Action:
<( -
- a. With a radioactive liquid.-effluent monitoring instrumentation channel
-alarm / trip setpoint less conservative _ -than required by the= above
, specification,_ immediately suspend the release of radioactive liquid
- effluents monitored by the affected channel or correct the' alarm / trip foetpoint.
~u. With one :or more radioactive liquid effluent monitoring instrumentation f g-~ ' channels inoperable, take.the ACTION. shown 'in Appendix C, Table 3.3-12 or N Q' .
conservatively reduce the alarm setpoint. Exert a best effort to return the channel _to operable status.vithin 30 days, and if unsuccessful, explain in
'.the next Annual Radioactive- Effluent- Release Report why the inoperability was not corrected in a timely manner.
e.- The provisions of Appendix C CONTROL 3.0.3 are not applicable.
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.
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C-9 ISSUE 3 !
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BV-1 and 3 ODCM l
APPENDIX C ODCM CONTROLS f
TABLE 3.3-12 l BV-1 RADIGACTIVE LIQUID EFFLUENT HONITORING INSTRUMENTATION t
[
MINIMUM CHANNELS ]
INSTRUMENT OPERABLE ACTION l l
t
) 1. Gross Activity Monitors Providing Automatic ,
I I Termination Of Release i
l a. Liquid Vaste Erfluents Monitor (RM-LV-104) (1) 23 4
- b. Liquid Vaste Contaminated Drain Monitor (RM-LV-116) (1) 23 i
- c. Auxiliary Feed Pump Bay Drain Monitor (RM-DA-100) (1) 24 l 2. Gross Activity Monitors Not I'roviding Termination of ~
Release l a. Component _ Cooling-Recirculation Spray Heat (1) 24 -l Exchangers River Vater Monitor (RM-RV-100)
- 3. Flow Rate Measurement Devices
)
! a. Liquid Radvaste Effluent Line (1) 25 (1) FR-LV-103 for RM-LV-116 (2) FR-LV-104 for RM-LV-104
- b. Cooling Tover Blowdown Line (1) 25
[ (1) FT-CV-101 l (2) FT-CV-101-1 i
- 4. Tank Level Indicating Devices (for tanks outside plant building)
- a. Primary Water Storage Tsnk (1) 26 (LI-PG-115A for 3R-TK-6A)
- b. Primary Water Storage Tank (1) 26 (LI-PG-115B for BR-TK-6B)
- c. Steam Generator Drain Tank (1) 26 (LI-LV-110 for LV-TK-7A)
- d. Steam Generator Drain Tank- (1) 26 (LI-LV-111 for LV-TK-73)
O C-10 ISSUE 3 Revision 2
BV-1 cnd'2o0DCM
. APPENDIX C-ODCM CONTROLS
[D qj .
- TABLE 3.3-12 (continued)
- BV-2 RAbI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM =
CHANNELS
- INSTRUMENT OPERABLE ACTION-
- 1. ' Gross Radioactivity Monitor Providing Alarm And Automatic Termination Of Release
- a. . Liquid Vaste Fac, ness Effluent Monitor (2SGC-R0100) (1) 23 4
- 2. Gross Radioactivity Monitors Providing Alarm But Not b Providing:Termit:stion Of Release
-None
~
3.- Flow Rate Measurement Devices
-a. ' Liquid Radvaste Effluent _(2SGC-FS100)
(1) 25.
- b. Cooling Tower Blowdown Line_(2CVS-FT101) (1) 25 r'S 4. ' Tank' Level Indicating Devices (for tanks outside plant-buildings)_
None b
o C-11 ISSUE 3 4
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BV-1 cnd 2 ODCH APPENDIX C ODCH CONTROLS TABLE 3.3-12 (continued)
ACTION STATEMENTS Action 23 With 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.
Othervise, suspend release of radioactive effluents via this pathway.
Action 24 Vith the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, efflueht releases via this pathway may continue provided that at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> grab samples are analyzed for gross radioactivity (beta or gamma) at a Lover Limit of Detection (LLD) of at least lE-7 uCi/ml.
Action 25 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump curves may be used to estimate flow.
Action 26 Vith the number of ' channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continue provided the tank liquid level is estimated during all liruid additions to the tank.
O C-12 ISSUE 3
1 1 Qi:
4 'BV-1-cnd 2;ODCM APPENDIX C
% ..y ODCM CONTROLS-
/ \ +
d -
- TABLE 4.3-12
.a. :BV-1 RADI0 ACTIVE LIQUID EFFLUENT' MONITORING g.. , INSTRUMENTATION SURVEILLANCE REQUIREMENTS.-
~ CHANNEL' CHANNEL [ SOURCE . CHANNEL FUNCTIONAL, INSTRUMENT,- CHECK CHECK CALIBRATION- TEST-
.1.. Gross Beta Or Gamma Radioactivity Monitors Providing Alarm And
-Automatic Termination Of Release
- a. Liquid Radvaste Effluent Line' D' P(5) R(3) 0(1)
, (RM-LV-104)
- b. Liquid Vaste Contaminated D P(5) -
.R(3). 0(1)
Drain Line.(RM-LV-116). ,
- c. Auxiliary Feed Pump Bay 'D D. R(3). 0(6) p Drain Monitor (RM-DA-100)
'2. Gross Beta Or Gamma Radioactivity
. Monitors Providing Alarm But Not Providing Automatic Termination M() Of Release i
- a. Component Cooling -- D. M(5)- R(3)- 0(2)
Recirculation Spray. Heat-Exchangers River. Water Monitor (RM-RV-100)
- l. =3. Flow Rate Monitors :
in . .
! # a. Liquid Radvaste Effluent Lines D(4) NA R 0
' (1) FR-LV-103 for RM-LV-116 (2) FR-LV-104 for RM-LV-104 l: b.. Cooling Tower Blowdown Line D(4) NA R 0 L -(1) FT-CV-101 L(2) FT-CV-101-1 O
C-13 ISSUE 3 Revision 2
BV-1 Cnd 2 ODCM
. APPENDIX C ODCM CONTROLS TABLE 4.3-12 (continued) j BV-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING I
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 Water Storage Tank D* NA R 0 (LI-PG-115A for BR-TK-6A)
- b. Primary Water Storage Tank D* NA R 0 (LI-PG-115B for BR-TK-6B) .
- c. Steam Generator Drain Tank D* NA R 0 (LI-LV-110 for LV-TK-7A)
- d. Steam Generator Drain Tank D* NA R 0 (LI-LV-111 for LV-TK-7B)
O
- During liquid additions to the tank.
O C-14 ISSUE 3 Revision 2
BV-1 cnd 2 ODCM !
APPENDIX C
^
ODCM CONTROLS'
- /%-
! TABLE:4.3-12.(continued)
BV-2 RADI0 ACTIVE LIQUID EFFLUENT MONITORING-INSTRUMENTATION SURVEILLANCE REQUIREMENTS.
CHANNEL
' CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK ' CHECK CALIBRATION TEST.
- 1. . Gross Radioactivity s ' tor Providing Alarm And Automatic, Termination Of Release
- a. Liquid Waste Process' Effluent- D- P(5). R(8)(3) 0(7)
- 2. ' Flow Rate Measurement Devices
- a. Liquid Radvaste Effluent D(4) NA R 0 (2SGC-FS100)
- :b. Cooling Tower Blovdown Line D(4) NA R .0 (2CVS-FT101)
- 3. Tank Level Indicating Devices
' [1 W]. (for tanks outside plant buildings)
None-h L
r O
C-15 ISSUE 3
BV-1 cnd 2 ODCH APPENDIX C 1 ODCH CONTROLS TABLE 4.3-12 (continued)
TABLE NOTATION (1). The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control Room Alarm Annunciation occurs if any of the following conditions exist:
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Downscale failure.
- 3. Instrument controls not set in operate mode.
(2) The CHANNEL FUNCTIONAL TEST shall also demon' ate that Control Room Alarm Annunciation occurs if any of the following conditions exist:
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Downscale failure.
- 3. Instrument controls are not set in operate mode.
(3) The initial CHANNEL C/.LIBRATION for radioactivity measurement instrumentation shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards should permit calibrating the system over its intended range of energy and rate capabilities. For 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.
l (Existing plants may substitute previously established calibration procedures for this requirement).
(4) C5ANNEL 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 l vhich continuous, periodic, or batch releases are made.
(5) A SOURCE CHECK may be performed utilizing the installed means or flashing the detector with a portable source to obtain an upscale increase in the existing count rate to verify channel response.
O C-16 ISSUE 3
r.
BV-1 cnd-2~ODCM APPENDIX C ODCM CONTROLS TABLE 4.3-12 (continued)
TABLE NOTATION ,
(6) The CHANNEL FUNCTIONAL TEST shall also' demonstrate that automatic isolation.
of this . pathway'~and Control -Room Alarm Annunciation occurs when the-instrument indicates measured levels above the Alarm / Trip Setpoint.
The CHANNEL FUNCTIONAL TEST shall. also demonstrate that Control Alarm Annunciation occurs if any of the following conditions exists:
3.
- 1. Downscale failure.
2.. Instrument controls are not set in operate mode.-
(7) .The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation
~of this pathv.sy 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.-
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1 C-17 ISSUE 3
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS CONTROLS: RADI0 ACTIVE GASEOUS EFFLUENT HONITORINC INSTRUMENTATION
-r 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 accor;ance with Section 2.1 of this manual.
Applicability:
During releases through the flow path.
Action:
- a. Vith a radioactive gaseous process or effluent moni_toring 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.
SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated operable by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Appendix C, Table 4.3-13.
1 O
C-18 ISSUE 3
'BV-1 4nd 2'ODCM
- APPENDIX C 4
~ODCM CONTROLS-A.
- .A ( k.f 1
. TABLE 3.3-13
- BV-1 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
. MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY PARAMETER ACTION
'1. Gaseous Vaste) Process Vent System (RM-GV-108) a.: Noble' Gas- (1)
- Radioactivity Rate ~27,30***
. Activity Monitor Measurement.
(RM-GV-108B) t- (rlp}p
- b. Particulate 32
~
(1)
Activity Monitor (RM-GV-108A) c.. System Effluent '(1)
- System Flow Rate 28
. Flow Rate Measurement Measuring Device-(FR-GV-108) or
-(RM-GV-109 Ch 10)-
- (w} . Sampler Flow Rate'
~
- d. Sampler Flow (1)
- 28
.-- Rate Measuring Measurement-P Devicei
.(Rotometer)
I 2. Auxiliary Building Ventilation System-(RM-VS-101)-
i-I a. Noble Gas (1)
- Radioactivity Rate 29,30***
Activity Monitor Measurement (RM-VS-101B) b.- Particulate (1)
- 32 Activity Monitor
- (RM-VS-101A)
- c. System Effluent (1)
- System Flow Rate 28
+
Flow Rate _
Measurement
'_ Measuring Device
'(FR-VS-101) or t (RM-VS-109 Ch 10) 1 d.. Sampler Flow. (1) *. Sampler Flow Rate. 28 Rate Measuring Measurement Device z ., ' (Rotometer)
- p :'.
O *During Releases'via this pathway.
- During. purging _of Reactor Containment via this pathway.
C-19 ISSUE 3
'" Revision 2
l BV-1 and 2 ODCM l
APPENDIX C ODCM CONTROLS TABLE 3.3-13 (continued)
BV-1 RADI0 ACTIVE GASE0US EFFLUENT HONITORING INSTRUMENTATION l l
MINIMUL CHANNELS INSThUMENT OPERABLE APPLICABILITY PARAMETER ACTION
- 3. Reactor Building / Supplementary Leak Collection And Release System (RM-VS-307)
- a. Noble Gas (1)
- Radioactivity Rate 29,30***
Activity Monitor i (RM-VS-107B)
- b. Particulate (1)
- 32 Activity Monitor
~
(RM-VS-107A) f c. System Effluent (1)
- System Flov Rate 28 s Flow Rate Measurement Heasuring Device (FR-VS-112) or (RM-VS-110 Ch 16)
- d. Sampler Flov (1)
- Sampler Flow Rate 28 O
Fate Measuring MeasureLuc Device (Rotometer)
O c-20 ISSUE 3 Rev hion 2
1 ' BV-1~cnd 2 ODCM,
~ APPENDIX C.
ODCM CONTROLS M, iTABLE 3.3 13 (continued)- .
BV-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION:
a 4
- MINIMUM
- CHANNELS' INSTRUMENT: :0PERABLE APPLICABILITY PARAMETER' ACTION a
1.- SLCRS Unfiltered Pathway (2HVS-R0101);
a .' -
Noble Gas . 1
- Rad'ioactivity Rete- 29,30***
Activity Monitor Measurement l
(2HVS-R0101B)'
- b. Particulate 1 .* 32 ' <
. Activity' Monitor
'(2HVS-R0101A).
- c. Process Flov 1
- Process Flov Rate 28-Rate Monitor Measurement
, . (Monitor Item 29) _
- d. Sampler Flov 1
- _ Sampler' Flow Rate- . 28.
Rate Monitor. Measurement-(Monitor Item 28)
W . 2.. SLCRS Filtered Pathway (2HVS-R0109) .
- a. Noble Gas- .
1 * ' Radioactivity Rate 29,30***-
Activity' Monitor -Heasurement (2HVS-R0109B)
'b. Particulate- 1 * -32~
l- : Activity Monitor.
(2HVS-R0109A) p .c. ' Process Flov- 1
- Process'Flov-Rate 28;
- l. Rate' Monitor Measurement L (Monitor Item 29)
Sampler Flow- 1
- Sampler Flow-Rate 28' i
- d. . Rate Monitors Measurement j l
(Monitor item 28)
(Monitor-Item 72) l L ;3. ' Decontamination Building Vent (2RM0-R0301) '
. a.' : Noble Gas
- Radioactivity Rate 29 f:
1 Activity Monitor Measurement (2RM0-R0301B) ;
' b. Particulate. .1
- 32 l Activity Monitor )
'(2RMQ-R0301A). i
- c. : Process Flow' None None . Process Flow Rate None
- Rate Monitor Measurement
-(Monitor Item 29)-
s d. Sampler Flov 1
- Sampler Flow Rate 28 Rate Monitor Measurement )
(MonitorsItem 28).
m C-21 ISSUE 3 :
Revision 2 j
BV-1 and 2 ODCM !
APPENDIX C ODCM CONTROLS TABLE 3.3-13 (continued) i BV-2 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION )
MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY PARAMETER ACTION
- 4. Condensate Polishing Building Vent (2HVL-R0112)
- a. Noble Gas 1
- Radioactivity-Rate 29 Activity Monitor Measurement (2HVL-R0112B)
- b. Particulate 1
- 32 h Activity Monitor
'/ (2HVL-R0112A)
Precess Flov Rate None
- c. Process Flow None None Rate Monitor Measurement (Monitor Item 29)
- d. Sampler Flov 1
- Sampler Flov Rate 28 Rate Monitor Measurenent (Monitor Item 28)
- 5. Vaste Gas Storage Vault (2RM0-R0303)
- a. Noble Gas 1
- Radioactivity Rate 29 O
Activity Monitor Measurement (2RM0-R0303B)
- b. Particulate 1
- 32 Activity Monitor (2RMO-R0303A)-
- c. Process Flov None- None Process Flov Rate None Rate Monitor Mensurement (Monitor Item 29)
- d. Sampler Flov 1
- Supler Flow Rate 28 Rate Monitor Ecasurement (Monitor Item 28)
O C-22 ISSUE 3 Revision 2
BV-l'and 2 ODCM?
~ APPENDIX'C' LODCM CONTROL f3 TABLE 3.3-13 (continued).
S/
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 releases-
- 1. At least two 'ndependent i 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 .vith 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
,-Q 9] s Minimum Channels OPERABLE requirement, effluent releases via'this pathway may continue provided the flow rate' is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
L l
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:
l
- 1. Grab samples'are -taken' at least - once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and these l
samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or
- 2. - Initiate continuous monitoring with a comparable alternate monitoring channel. Surveillance requirements applicable to the inoperable channel shall apply to the comparable alternate monitoring channel when used to satisfy this ODCM CONTROL requirement.
Action 30 APPLICABLE FOR PURGES OF THE BV-1 REACTOR CONTAINMENT Vith the number of channels OPERABLE less than required by minimum Channels OPERABLE requirement, immediately suspend PURGING of Reactor Containment via this pathway if both RM-VS-104A and B are not operable with the purge / exhaust system in service.
vO C-23 ISSUE 3
BV-1 and 2 ODCM l APPENDIX C l ODCM CONTROLS l I
TABLE 3.3-13 (continued)
ACTION STATEMENTS l
Action 30 APPLICABLE FOR PURGES OF THE BV-2 REACTOR CONTAINMENT l Vith the number of channels OPERABLE less than required by Minimum Channels OPERABLE requirement, immediately suspend purging of Reactor Containment via this pathway.
Action 32 Vith the number of channels OPERABLE less than required by the
' Minimum Channels OPERABLE requirement, effluent releases via this >
pathway may continue provided samples are continuously collected with ;
auxiliary sampling equipment as required in Appendix C, Table 4.11-2 or sampled and analyzed once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
O i
C-2'. ISSUE 3
?
BV-1 end 2 ODCM APPENDIX C L ODCM CONTROLS
/ .
(s,,l' TABLI 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/Frocess Vent: System (RM-GV-108)
- a. Noble Gas-Activity Monitor P. P(4) R(3) 0(1)
(RM-GV-108B) (
- b. Particulate Activity Monitor. V NA NA NA (RM-GV-108A)
. System Effluent Flow Rate -P NA R 0 Measuring Device (FR-GV-108) or (RM-GV-109 Ch 10)
- d. Sampler Flow Rate Measuring D* NA R 0 Device (Rotometer) -
- 2. Auxiliary Building Ventilation System (RM-VS-101)
- a. Noble Gas Activity Monitor D M(4), R(3) 0(2)
(RM-VS-101B) F(4)***
r_s b. Particulate Activity Monitor V NA NA NA I
) (RM-VS-101A)
- c. System Effluent Flow Rate D NA R 0 _q Measurement Device (FR-VS-101) f or (RM-VS-109 Ch 10)
- d. Sampler Flow Rate Measuring D NA R 0 Device (Rotometer) >
- 3. Reactor Building / Supplementary Leak Collection And Release System (RM-VS-107)
- a. Noble Gas Activity Monitor D M(4), R(3) 0(2)
(RM-VS-107B) P(4)***
- b. Particulate Activity Monitor V NA NA NA (RM-VS-107A) l
- c. System Effluent Flow Rate D NA R 0 l Measuring Device (FR-VS-112) 1 or (RM-VS-110 Ch 10)
- d. Sampler Flow Rate Measuring D NA R 0 Device (Rotometer) J
- During releases via this pathway.
- During purging of Reactor Containment via this pathway.
l I,
a
)\ ~J C-25 ISSUE 3 Revision 2
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 4.3-13 (continued) lh BV-2 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK' CALIBRATION TEST
- 1. SLCRS Unfiltered Pathway (2HVS-R0101)
- a. Noble Gas Activity Monitor D M(4), R(3)(6) O(5)
(2HVS-R0101B) P(4)***
5g)7 b. Particulate Activity Monitor W NA NA NA
/ (2HVS-R0101A)
- c. Process Flov Rate Monitor D NA R 0 (Monitor Item 29)
- d. Sampler Flow Rate Monitor D NA -R 0 (Monitor Item 28)
- 2. SLCRS Filtered Pathway (2HVS-R0109)
- a. Noble Gas Activity Monitor D M(4), R(3)(6) 0(5)
(2HVS-R0109B) P(4)***
- b. Particulate Activity Monitor W NA NA NA (2HVS-R0109A)
- c. Process Flov Rate Monitor D NA R 0 (Monitor Item 29)
- d. Sampler Flow Rate Monitors D NA R 0 (Monitor Item 28)
(Monitor Item 72)
- 3. Decontamination Building Vent (2RM0-R0301) a .- Noble Gas Activity Monitor D M(4) R(3)(6) 0(5)
- b. Particulate Activity Monitor V NA NA NA (2RH0-R0301A)
- c. Process Flow Rate Monitor NA NA NA NA (Monitor Item 29)
- d. Sampler Flow Rate Monitor D NA R 0 (Monitor Item 28)
- 4. Condensate Polishing Building Vent (2HVL-R0112)
- a. Noble Gas Activity Monitor D M(4) R(3)(6) 0(5)
- b. Particulate Activity Monitor V NA NA NA (2HVL-R0112A)
- c. Process Flov Rate Monitor NA NA NA NA
_(Monitor Item 29)
- d. Sampler Flow Rate Monitor D NA R 0 (Monitor Item 28)
C-26 ISSUE 3 Revision 2
3' EV-l'cnd 2 ODCM
, . . . . APPENDIX C
'ODCH CONTROLSc
' TABLE 4.3-13-(continued)'
~U{'(.
~ ~
~BV-2 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING-
- INSTRUMENTATION SURVEILLANCE REQUIREMENTS.
- _ ' CHANNEL-
," " ~
~ CHANNEL: SOURCE' CHANNEL. FUNCTIONAL g .
-INSTRUMENT- CHECK CHECK CALIBRATION- TEST-
^
- 5. LVaste' Gas Storage Vault'(2RM0-R0303)5
- a. Noble Gas Activity Monitorc D. -M(4)- -R(3)(6) O(5)
..(2RM0-R0303B)
- b. Particulate Activity, Monitor- V- :NA' NA: NA T (2RMO-R0303A)
- c. : Process' Flow Rate Monitor. NA. NA' NA NA (Monitor Item-29)
.d. Sampler Flow Rate Monitor D . NA'- 'R- 0 l(Monitor Item 28) 1 i
f i\
i-L, -l l 1 l-1 l
57 1
.1
'I l
i C-27 ISSUE 3 !
Revision 2 e .
BV-1 Cnd 2 ODCH APPENDIX C ODCH CONTROLS TABLE 4.3-13 (continued)
TABLE NOTATION (1) The CHANNEL FUNCTIONAL TEST shall'also demonstrate that automatic isolation of this pathway and Control Room Alarm Annunciation occurs if any of the following conditions exist:
- a. Instrument indicates measured levels above the alarm / trip setpoint.
- b. Dovnscale failure.
- c. Instrument controls not set in operate mode.
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Room Alarm Annunciation occurs if any of the following conditions exist:
- a. Instrument indicates measured levels above the alarm / trip setpoint.
- b. Downscale failure.
- c. Instrument controls not set in operate mode.
(3) The initial CHANNEL CALIBRATION for radioactivity- measurement inatrumentation shall be performed using one or more of the reference s u.dards 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 l over its intended range of energy and rate capabilities. For subsequent CHANNEL CALIBRATION, sources that have been related to the' initial calibration should be used, at intervals of at least once per 18 months.
This can normally be accomplished during refueling outages.
(4) A SOURCE CHECK may be performed utilizing the installed means or flashing the detector with a' portable source to obtain an upscale increase in the existing count rate to verify channel response.
(5) The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Room Alarm Annunciation occurs if the instrument indicates measured levels above the alarm / trip setpoint.
(6) The CHANNEL CALIBRATION shall also demonstrate that control Room Alarm Annunciation occurs if either of the following conditions exist:
- 1. Downscale failure.
- 2. Instrument controls are not set in operate mode.
O C-28 ISSUE 3
g ,
E o
b,, <
BV-1 End-2'ODCH L; APPENDIX C-h .. 'ODCM CONTROLS.
yy
,; p ,
. CONTROLS: 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'10 times i : the' EC's specified in 10 CFR Part-20, Appendix B (20.1001-20.2401),
Table 2, Column 2 for;: radionuclides. other.than-dissolved orl entrained l- : noble gases; .This is referred :to as the ODCM Effluent Concentration.
. . . . . Limit' (OEC)'. - :For ~ dissolved or entrained ' noble' gases, th
^ concentration shall-be limited to 2E-4 uCi/ml' total activity.
Applicability -
7 ~At all times.
s ->
Action:
- a. With the concentration of-' radioactive material released from the site to unrestricted areas. exceeding the above limits; immediately restore the concentration within the above limits, and
- b. , Submit a Spr 1. Report to the Commission within 30 days in accordance rith 7- Technical S.t 4fication.6.9.2f.
i( m) b' " - c. The provis, ions of Appendix C CONTROL 3.0.3 are not applicable.
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 BV-1 primary to secondary leakage exceeds 0.1 gpm (142 gpd),
samples of the Turbine Building Sump shall be obtained every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
-to ensure that. the Turbine Building Sump concentr' tion does not exceed 1 OEC. Once it is determined that an OE 4 reached, the Turbine Building Sump shall be routed to the Chemical Vaste Sump. g f.
&(N.
C-29 ISSUE 3 Revision 1
BV-1 ond 2 ODCM APPENDIX C ODCH CONTROLS SURVFILLANCE REQUIREMENTS (continued) 4.11. When BV-2 primary to secondary leakage exceeds 0.1 gpm (142 gpd),
samples of the Turbine Building Sump shall be obtained every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to ensure that the Turbine Building Sump concentration does not
' NT exceed 1 OEC. Once it is determined that an OEC is reached, the Turbine Building Sump shall be routed to Steam Generator'blovdown hold tank (2SGC-TK21A or 2SGC-TK21B).
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. Water volume discharged shall be estimated from the number of pump operations unless alternate flow or volume instrumentation is provided.
O
- Radioactive liquid discharges are normally via batch modes. BV-l'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.
O C-30 ISSUE 3 Revision 1
s:
J
.}
s BV-1 cnd;2 ODCM.
T ii@i! ,
- APPENDIX C ODCM CONTROLS
<- f, ' TABLE 4.11 , RADIOACTIVE LIQUID WASTE SAMPLING.AND ANALYSIS PROGRAM MINIMUM 3 ' LIQUID RELEASE- SAMPLING' ANALYSIS TYPE OF ACTIVITY LOVER LIMIT'-
- TYPE FREQUENCY FREQUENCY ANALYSIS OF DETECTION
-(LLD) z; > (uci/ml)*.
R W A.; Batch Vaste4d I P- Principal Gamma h h g SE-7f Release Tanks Each Batch Each Batch ' Emitters c '
I-131- 'IE-6 q-. ,
' 4 P
.h M Dissolved And. 1E-5:
One Batch /M Entrained Gases (Gamma Emitters)
P h
M H-3! 1E-5 Each Batch - Composite b r
Gross' Alpha: 1E-7 f R.. "
P 0- Sr-89, Sr-90 SE-8 L , -}D ' Each Batchh - Composite b Fe-55 1E-6
- Grab. Sample s' V Principal Gamma SE-7:
B.ContinuogE-
C g
- 1
. Releases Composite Emitters li: -
I-131 .1E-6
- g B' Grab Sampie M: Dissolved And IE-5 Entrained Gases
-( ,
(Gamma Emitters) ,
g I.I Grab Sample M H-3. 1E-5 h '
Composite" Gross Alpha- 1E-7
" g
& Grab Sample 0 Sr-89, Sr-90 SE-8 c
[ %) -
C-31 ISSUE 3 Revision 1 l n.
BV-1 cnd 2 ODCH APPENDIX C ODCH CONTROLS TABLE 4.11-l (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(- AoT) i where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume); -
shis the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute);
E is the counting efficiency (as counts per transformation);
V is the sample size (in units of mass or volume);
2.22 is the number of transformations per minute per picoeurie; Y is the fractional radiochemical yield (when applicable);
A is the radioactive decay constant for the particular radionuclide; 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 of hs used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background 5f 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 calculations.
The LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement.
O C-32 ISSUE 3
BV-1 cnd 2 ODCM APPENDIX C.
ODCM CONTROLS TABLE 4.11-1 (continued)
TABLE NOTATION
- b. A composite sample is one in which the quantity of liquid sampled is proportional.to the quantity of liquid vaste . discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.
- c. To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior -to analyses, all samples taken for the composite -shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.
- d. A batch release exists when the discharge of liquid vestes 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 fnput flow during the continuous release. Releases from the Turbine Building drains r, and the AFV Pump Bay Drain System and chemical vaste sump are considered continuous when the primary to secondary leak rate exceeds 0.1 gpm (142 gpd). 8%g
- f. The principal gamma emitters for which the LLD specification vill apply are exclusively the following radionuclides: Hn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean
- that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall .
also be identified and reported. Nuclides which are below the LLD for the analyses should be reported as "less than" the nuclide's LLD, and should not ;
be reported as being present at the LLD level for that nuclide. The "less than" values should not be used in the required dose calculations. When unusual circumstances result in LLD's higher than required, the reason shall be documented in the Annual Radioactive Effluent Release Report. 6/9y
- g. When radioactivity is identified in the secondary system, a RVDA-L should be I prepared oa a monthly basis to account for the radioactivity that vil:
eventually be discharged to the Ohio River. i Yi
- h. Whenever the BV-2 Recirculation Drain Pump (s) are discharging to catch basin 16, sampling vill be performed by means of a grab sample taken every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during pump operation.
I m
C-33 ISSUE 3 Revision 1
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS CONTROLS: LIQUID EFFLUENT DOSE 3.11.1.2 In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Items'4 and 5, the dose or dose commitment to MEMBER (S) 0F THE PUBLIC from radioactive materials in liquid effluents released from the reactor unit (see Figure 5-1) shall be limited:
- a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and
- b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
Appli cability:
At all times.
Action:
- a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2f, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases, and the proposed corrective actions to be taken to assure the subsequent releases vill be within the above limits. (This Special Report shall also include (1) the results of radiological analyses of the drinking vater source and (2) the radiological impact en finished drinking water supplies with regard to the requirements of-40 CFR 141, Safe Drinking Vater Act).*
- b. The provisions of Appendix C CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.2.1 Dose Calculations. Cumulative dose contributions from liquid effluents shall be determined in accordance with Section 1.3 of this manual at least once per 31 days.
- Applicable only if' drinking water supply is taken from the receiving water body within three miles of the plant discharge (three miles downstream only).
C-34 ISSUE 3 Revision 1
[
BV-1 cnd 2 ODCM i
APPENDIX C ODCM CONTROLS CONTROLS: LIQUID RADVASTE TREATMENT SYSTEM 3.11.1.3 In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Item 6, the' Liquid Radvaste Treatment System shall be used to reduce the radioactive materials in each liquid vaste batch prior to its discharge when the projected doses due- to liquid effluent releases from the reactor unit (see' Figure 5-1) when averaged over 31 days vould exceed 0.06 mrem to the total body or 0.2 mrem to any organ.
Applicability:
At all times.
Action:
- a. With liquid vaste being discharged wit'.ou t 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 REQUIREMEffrS 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.
i
,,\
( )'
. v C-35 ISSUE 3 Revision 1
BV-1 cad 2 ODCM APPENDIX C ODCM CONTROLS CONTROLS: GASEOUS EFFLUENT DOSE RATE 3.11.2.1 In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Items 3 and 7, the dose rate in the unrestricted areas (see Figure 5-
- 1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following. values:
- a. The dose rate limit for noble gases shall be f 500 mrem /yr to the total body and 3 3000 mrem /yr to the skin *, and
- b. The dose rate limit, inhalation pathway only, for 1-131, tritium and all radionuclides in particulate form (excluding C-14) with half-lives greater than eight days shall be f 1500 mrem /yr to any organ.
Applicability:
At all times.
Actions
- a. With 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.
4 C-36 ISSUE 3 Revision 1 L
'BV-1 end'2.0DCM y -
-APPENDIX C ODCM CONTROLS Ll{Y
) ' TABLE 4.11-2
, i a.
.RADI0 ACTIVE GASEOUS VASTE SAMPLING-AND ANALYSIS PROGRAM HINIMUM LOWER' LIMIT OF SAMPLING:
4 ANALYSIS TYPE OF; DETECTION GASEOUS-RELEASE TYPE FREQUENCY . FREQUENCY ~ ACTIVITY ANALYSIS .(uCi/ml)"(LLD)
A.'Vaste Gas Storage .
P.. 'P . Principal' Gamma :1E-4
, .. Tank Each Tank Each Tank' . Emitters 8 L; Grab Sample 7' H-3^ 1E-6 B. Containment Purge -P P Princ!ipal Gamma IE b b Emittersg Each Purge Each Purge Grab. Sample H-3 - 1E-6 C.Ventilagion Mb ,c,e, MY Principal Gamma 1E-4 Systems ' Grab Sample, Emittersg '
1." Unit i Ventila-- ~
, 2.?. Unit 1 Contain-
! ', ment /SLCRS Vent
,A 3.' Unit 1/2 Process
- Vent: '
4.-Unit 2 Ventila .
i tion Vent-L 5. Unit.2 Contain-ment /SLCRS' Vent j 6.. Unit'2 Decon. >
Bldg. -- Ven t -
- 7. Unit 2 Waste Gas Storage Vault Vent. '
- 8. Unit 2 Condensate
. Polishing Bldg.
Vent-l l
]
- l. ;
i 4
C-37 ISSUE 3 l Revision 1
BV-1 cnd 2 ODCM APPENDIX C ODCM CONTROLS TABLE 4.11-2 (continued)
RADIOACTIVE GASEOUS VASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM LOVER LIMIT OF !
SAMFLING ANALYSIS TYPE OF DETECTION (LLD)
GASEOUS RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS (uCi/ml)"
d D. All Systems Continuous V I-131 1E-12 Listed Above Charcoal Which Produce Sample I-133 1E-10 Continuous Release I d Continuous V Principal Gamma 1E-11 Particulate EmittersE Sample (I-131, Others)
Continuous M Gross Alpha 1E-11 Composite Particulate Sample I
Continuous O Sr-89, Sr-90 1E-11 Composite Particulate Sample I
Continuous Noble Gas Noble Gases IE-6 Monitor Gross Beta And Gamma l
l l
l I
I O
C-38 ISSUE 3 Revision 1
BV-1 cnd 2 ODCM APPENDIX C ODCM CONTROLS 3 ;
(_,! TAbtE 4.11-2 (continued) 1 TABLE NOTATION 1
- a. The Lover Limit of Detection (LLD) is defined in Table Notation (a) of Appendix C, Table 4.11-1 of Appendix C CONTROL 4.11.1.1.
- b. Sampling and analysis shall' also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POVER within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period. This requirement does not apply if (1) analysis shows that the Dose Equivalent I-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.
- c. Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (from the appropriate ventilation release path) when the refueling canal is flooded.
- d. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler.
Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown,- startup, or THERM.\L POWER change exceeding 15%
of RATED THERMAL POWER vithin a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
_- are analyzed, the correspon{ing LLDs may be increased by a factor of 10.
l ) This requirement does not apply if: (1) analysis shovs that the DOSE C' 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, Zn-65, Ho-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions.
This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measureable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide. When unusual circumstances result in LLD's higher than required, the reasons shall be documented in the Annual Radioactive Effluent Release Report.
( h. Only when this release path is in use.
C-39 ISSUE 3 Revision 1
BV-1 and 2 ODCH APPENDIX C ODCM CONTROLS CONTROLS: DOSE-NOBLE GASES 3.11.2.2 In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Items 5 and 8, the air dose from the reactor unit in unrestricted areas' (see figure 5-1) due to noble gases released in gaseous.
effluents shall bc limited to the following:
- a. During any calendar quarter, to $_5 mrad for gamma radiation and f 10 mrad for beta radiation.
b .' During any calendar year, to $ 10 mrad for gamma radiation and f 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 correciive actions taken to reduce the releases and the proposed corrective actions to be taken to assure the subsequent releases vill be within the above limits,
- b. The provisions of Appendix C CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.2.1 Dose Calculations. Cumulative dose contributions shall be determined in accordance with Section 2.3 of this manual at least once every 31 days.
O C-40 ISSUE 3 Revision 1
BV-1 cnd 2 ODCH 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 PUBLIC from radiciodines and radioactive materials in particular form (excluding C-14), and radionuclides (other than noble gases) with half-lives greater than eight days in gaseous effluents releases from the reactor unit (see Figure 5-1) shall be limited to the following:
- a. During any calendar quarter to f 7.5 mrem to any organ, and
- b. During any calendar. year to f 15 mrem to any organ.
Applicability:
At all. times. -
Action:
- a. With the calculated dose from the release of radiciodines, radioactive materials in particulate form, (excluding C-14), and radionuclides (other
.m than noble gases) vith half-lives greater than eight days, in gaseous f'/ )-
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 {
1 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 ,
I once every 31 days.
I j /\ j U*
l C-41 ISSUE 3 i Revision 1 4
I
BV-1 cnd 2 ODCM APPENDIX C 1 I
ODCH CONTROLS 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 proj ected doses d.u e - to gaseous effluent releases from the reactor unit (see Figure 5-1) when averaged over.31 days would exceed 0.3 mrem to any organ.
Applicability:
At all times.
- 1 Action:
- a. With gaseous vaste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2f, a Special Report. which includes the following information.
- 1. Identification of the inoperable equipment or subsystems and the reason for inoperability,
- 2. Action (s) taken to restore the inoperable equipment to operational status, and
- 3. Summary description of action (s) taken to prevent a recurrence.
- b. The provisions of Appendix C CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with Section 2.3 of this 3
l l manual.
O C-42 ISSUE 3 Revision 1
BV-1 End-2 ODCM APPENDIX C ODCM CONTROLS l-
, )
K._,/
CONTROLS: TOTAL DOSE 3.11.4'.1 In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Item 10, the annual (calendar year). dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to 3 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to j 75 mrems.
Applicability:
At all times.
Actions
- a. With the calculated doses from the release of radioactive materials in i@M or pseous effleants 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 bc .nade 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 es Technical Specification 6.9.2f, a Special Report that defines the corrective
( action to be taken to reduce subsequent releases to prevent recurrence of
~ 's) exceeding the above limits and includes the schedule for achieving i conformance with the above limits. This Special Report, as defined in 10.CFR 20.405(c), shall include an analysis that estimates the radiation 3 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 level.s of radiation and concentrations of radioactive material involved, and the caure 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 l is complete.
- b. The provisions of Appendix C CONTROL 3.0.3 are not applicable.
- i, ,>
,J C-43 ISSUE 3 Revision 1
BV-1 cnd 2 ODCM APPENDIX C ODCM CONTROLS SURVEILLANCE REQUIREMENTS (continued) 4.11.4.1.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Appendix C SURVEILLANCE g.g7 REQUIREMENTS 4.11.1.2.1, 4.11.2.2.1 and 4.11.2.3.1.
4.11.4.1.2 Cumulative dose contributions from direct radiation from the units (including outside storage tanks, etc.) shall be determined in accordance with Section 4 of this manual. This requirement is applicable only under conditior.s set forth in Action a. of Appendix C CONTROL 3.11.4.1.
O O
C-44 ISSUE 3 Revision 2
BV-1 cnd 2 ODCM APPENDIX C
\
j' CONTROLS: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3.12.1 In accordance with BV-1 and BV-2 Technical Specification 6.8.6b,
-Item 1, the- radiological environmental monitoring program shall be conducted as specified in Appendix C, Table 3.12-1.
Applicability:
At all times.
Action:
- a. Vith the radiological environmental monitoring program not being conducted as specified in Appendix C, Table 3.12-1, prepare and submit' to the Commission, in the Annual Radiological Environmental Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence. ~ Deviations are permitted from the required i sampling schedule if specimens are unobtair.able 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 v' limits of Appendix C, Table 3.12-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of affected calendar quarter a Special Report pursuant to Technical Specification 6.9.2f-which includes an evaluation of any release conditions, environmental factors or other aspects which caused the limits of Appendix C,. Table 3.12-2 to be exceeded. This report is not required if_ the measured level of )
radioactive was not the result of plant effluents; however, in such an event, the condition shall be reported and_ described in the' Annual Radiological Environmental Report.
When more than one of the radionuclides in Table 3.12-2 are detected in the {
sampling medium, this report shall be submitted if:
Concentration (1) Concentration (2)
Limit Level (1) + Limit Level (2) + . . . > 1.0
- c. With milk or fresh leafy vegetable samples unavailable from the required i 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 were unavailable may then be deleted from those required by ;
Appendix C, Table 3.12-1 and the ODCM provided the locations from which the i replacement samples were obtained are added to the environmental monitoring program as replacement locations, if available.
(^T d. The provisions of Appendix C CONTROL 3.0.3 are not applicable.
t /
v j l-I C-45 ISSUE 3 l l Revision 1 !
L
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS SURVEILLANCE REQUIREMENTS (continued) 4.12.1.1 The radiological environmental monitoring samples shall be collected pursuant to Appendix C, Table 3.12-1 from the locations given in tha ODCM and shall be analyzed pursuant to be-requirements of Appendix C, Tables 3.12-1 and 4.12-1.
\-
O C-46 ISSUE 3 Revision 1 b
BV-l'cnd 2 ODCM APPENDIX C ODCM CONTROLS
/ __ T
( ). TABLE 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING AND EXPOSURE PATHVAY NUMBER Of SAMPLES COLLECTION TYPE AND FREQUENCY (*)
AND/OR SAMPLE AND LOCATIO'4S** FREQUENCY OF ANALYSIS
- 1. AIRBORNE
- a. Radioiodine 5 locations. Continuous opera- Each radiciodine And tion of sampler canister.
Particulates 1. One sample from with sample col-a control loca- lection at least Analyze for I-131; tion 10-20 weekly.
miles distant Particulate sampler.
and in the least prevalent - Analyze beta veekly for gross (b);
vind direction.
Perform gamma isoto-
- 2. One sample from pic analysis on vicinity of composite (by loca-community tion) sample at
,_ ~x having the least quarterly.
( ) highest calcu-
's / ' lated annual average ground level D/Q.
- 2. DIRECT 40 locations. Continuous Gamma dose, RADIATION measurement with quarterly.
1 TLD or a pres- collection at surized ion least quarterly.
chamber at each location. ,
(a Analysis frequency same as sampling frequency _unless othervise specified.
I Particulate samples are not counted for 124 hours0.00144 days <br />0.0344 hours <br />2.050265e-4 weeks <br />4.7182e-5 months <br /> after filter change.
Perform gamma isotopic analysis on each sample when gross beta is >10 times e-S the yearly mean of control samples.
~.
- Sample locations are given on figures and tables in Section 3 of this manual.
L C-47 ISSUE 3 l Revision 1 i.
BV-1 cnd 2 ODCM APPENDIX C ODCM CONTROLS TABLE 3.12-1 (continued) l f_
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM sv SAMPLING AND COLLECTION TYPE AND FREQUENCY I ")
EXPOSURE PATHVAY NUMBfk 0F SAMPLES AND/0R SAMPLE AND LOCATIONS ** FREQUENCY OF ANALYSIS
- 3. WATERBORNE
- a. Surface 2 locations. Composite *~ sample- Gamma isotopic collected over a analysis of each
- 1. One sample period not to composite sample; upstream. exceed 1 month.
Tritium analysis of
- 2. One sample composite sample at downstream. least quarterly.
b.-Drinking 2 locations. Composite
- sample I-131 analysis of collected over a each composite period not to sample; exceed 2 weeks.
Gamma isotopic analy-sis of composite sample (by location) monthly; Tritium analysis of composite sample quarterly.
- c. Groundwater N/A - No wells in lower 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 hout?.
- Sample locations are given on figures and tables in Section 3 of this manual.
C-4t ISSUE 3 Revision 1
o 'BV-1 cnd'2 ODCH APPENDIX C ODCH CONTROLS i -
TABLE 3.12-1 (continued)
-RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING AND EXPOSURE PATHVAY NUMBER'0F SAMPLES COLLECTION TYPE AND FREQUENCY (")
AND/0R SAMPLE AND LOCATIONS ** FREQUENCY OF ANALYSIS
- 4. INGESTION
- a. Hilk 4 locations.(c) At least bi-veekly Gamma isotopic and when animals are I-131 analysis.of:
- 1. Three samples on pasture; at each sample, selected on. least monthly at basis of other times.
highest poten-- l tial thyroid dose using milch census data.
- 2. One local large dairy.
()
V-
- b. Fish 2 locations. Semi-annual. One sample'of avail-Gamma isotopic analysis on edible able species. portions.
- c. Food 4 locations. Annually at time Gamma isotopic Products c2 harvest. analysis and I-131 (Leafy 1. Three locations analysis on edible Vegetables) within 5 miles, portion.
- 2. One control location. ,
4 1
l h- Analysis frequency same as sampling frequency unless otherwise specified. l l Other dairies may be included as control station or for historical ,
continuity. These vould not be modified on basis of milch animal census.
l\
h j-g3
)
- Sample locations are given on figures and tables in Section 3 of this manual.
j C-49 ISSUE 3 Revision 1
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 3.12-2 1
REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS AIRBORNEP)RTICULATE BROAD LEAF VATER OR GASES FISH HILK VEGETABLES ANALYSIS (pCi/1) (pCi/m ) (pCi/kg, VET) (pCi/1) (pCi/kg, VET) a H-3' 2E+4 Hn-54 1E+3 3E+4 Fe-59 4E+2 1E+4 Co-58 1E+3 3E+4 Co-60 3E+2 1E+4 Zn-65 3E+2 2E+4 Zr/Nb-95 4E+2 D 1E+2
)
I-131 2 0.9 3 Cs-134 30 10 1E+3 60 1E+3 i
Cs-137 50 20 2E+3 70 2E*3 Ba/La-140 2E+2 3E+2
- a. For <!.rinking vater samples. This is a 40 CFR Part 141 value. If no f/f7 drinking vater pathway exists, a value of 3E+4 pCi/l may be used.
- b. If no drinking vater pathway exists, a value of 20 pCi/l may be used.
I C-50 ISSUE 3 Revision 2
.BV-1 cnd 2 ODCM APPENDIX C ODCM CONTROLS s ,/ TABLE 4.12-1 MAXIMUM VALUES FOR THE LOVER LIMITS OF DETECTION (LLD)a, e
' AIRBORNE PARTICULATE ANALYSIS VATER OR GAS FISH MILK FOOD PRODUCTS SEDIMENT (pCi/l) (pCi/m ) (pCi/kg, VET) (pCi/1) (pCi/kg, VET) (pCi/kg, DRY)
Gross Beta 4 1E-2 d
H-3 2000 [
Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 C
Zr-95 30
' C
( ; Nb-95 15 b
I-131 l 7E-2 1 60 Cs-134 15 SE-2 130 15 60 150 Cs-137 18 6E-2 150 18 80 180 C
Ba-140 60 60 c
La-140 15 15 l
l
! ,m- .
G'I i
C-51 ISSUE 3 Revision 2
1 BV-1 cnd 2 ODCH APPENDIE 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 S (E)(V)(2.22)(Y)Dexp(- AoT) where:
- LLD is the lover limit of detection as defined above (as pCi per unit mass or volume); -
Ss is the standard. deviation of the background counting rate or of the c5unting rate of a blank sample as-appropriate (as counts per minute);
E is the counting efficiency (as counts per transformation);
V is the sample size (in units of mass or volume);
2.22 is the number of transformations per minute per picocurie; Y is the fractional radiochemical yield (when applicable);
A is the radioactive decay constant for the particular radionuclide; AT is the elapsed time between sample collection (or end of the saidple collection period) and time of counting (for environmental samples, not plant effluent samples).
The value of Su used in the calculation of the LLD for'a detection system shall bM based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate ) rather than on an unverified theeretically predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples). Typical values of E, V, Y'and oT should be used in the calculations.
O C-52 ISSUE 3
BV-1 cnd 2 ODCM APPENDIX C.
ODCM CONTR0LSL y\
x _) TABLE 4.12-1 (continued)
TABLE NOTATION bh7
.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. Analyses shall.be performed.in such a manner that the stated LLD's vill be achieved under routine conditions. 0ccasionally, background fluctuations, unavoidable.
small sample sizes, the presence of interfering. nuclides, or other uncontrollable circumstances may render these LLD's unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Report.
- b. If no drinking water pathway exists, a value of 15 pCi/l may be used.
- c. If parent and daughter are totaled, the most restrictive LLD should be applied. ,
- d. If no drinking water pathway exists, a value of 3000 pCi/l may be used.
- e. .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 in the Annual Radiological
(/,_~s)
'- Environmental Report.
l l
i
.n l i xs /
C-53 ISSUE 3 Revision 2 l
L.
BV-1 ond 2 ODCM APPENDIX C ODCM CONTROLS CONTROLS:' RADIOLOGICAL ENVIRONMENTAL MONITORING - LAND USE CENSUS 3.12.2 In accordance with BV-1 and BV-2 Technical Specification 6.8.6b, Item 2, a land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles. For
'/f7 elevated releases as defined in Regulatory Guide 1.131, (Rev. 1), July, 1977,-the land use census shall also identify the locations of all milk animals and all gardens of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of three miles.
Applicability:
At all times.
Action:
- a. 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 4.11.2.3.1, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2f, a Special Report, which identifies the new location (s).
- b. With a lahd 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.
- Confirmation by telephone is equivalent to door-to-door.
C-54 ISSUE 3 j
Revision 2
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS i !
CONTROLS: RADIOLOGICAL. ENVIRONMENTAL MONITORING - INTERLABORATORY COMPARISON PROGRAM 3.12.3 In accordance with BV-1 and BV-2 Technical Specification 6.8.6b, Item 3,-
analyses shall be. performed.on radioactive materials supplied as part of an Interlaboratory Comparison Program.
Applicability:..
At all times.
Actions a.- 'With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual
-Radiological Environmental Report.
- b. The provisions of Appendix C CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMElfrS l' '; 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.
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C-55 ISSUE 3 Revision 1
BV-1 and 2 ODCH APPENDIX D BASES FOR ODCM CONTROLS
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This appendix aontains the Bases for the ODCM Controls that vere transferred from the Basa" ' etion of the Technical Specification per Unit 1/2 Amendments 188/70, and ir :ordance with' Generic Letter 89-01 and Generic Letter 89-01, Supplement No. 2 (NUREG-1301).
jof The numbering of each specific Bases contained in this appendix does not appear to be sequential. This is intentional, as all Bases numbers remained the same when they_ vere transferred from the Technical Specifications. This was done_in an effort to minimize the amount of plant procedure changes and to eliminate any confusion associated with numbering changes.
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BV-1 end 2 ODCM APPENDIX D BASES FOR ODCM CONTROLS BASES: INSTRUMENTATION 3/4.3.3.9 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of Aiquid effluents. The alarm / trip setpoints for these instruments shall be calculated in accordence with Section 1 of this manual to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
3/4.3.3.10 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 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 potentially explosive gas mixtures in the vaste gas holdup system.
The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
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D-2 ISSUE 3 Revision 1
BV-1 cnd 2 ODCM APPENDIX D BASES FOR ODCH CONTROLS
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BASES: LIQUID EFFLUENTS
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3/4'.11.1.1 LIQUID EFFLUENT CONCENTRATION .
This CONTROL is provided to ensure that the concentration of st radioactive materials released in Liquid vaste effluents from the site to unrestricted areas' vill. be less than 10 times the EC's specified in 10 CFR Part -20, Appendix B (20.1001-20-2401), Table 2,
. Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the_ site vill result 'in exposure within 3
(1) the~ Section II.A design objectives of Appendix I, 10 CFR .Part- 50, to an individual and (2) the limits 'of 10 CFR Part 20.1302 to the population.' The concentration limit for dissolved or entrained noble gases is based upon the assumption that"Xe-135 is the controlling radioisotope and its MPC in air (submersion) _vas converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2. sg 3/4.11.1.2 LIQUID EFFLUENT DOSE This CONTROL is provided to implement the requirements of x Sections II.-A, III.A, and IV.A of Appendix I, 10 CFR Part 50. The
- j i ~ Limiting Condition for Operation implements the guides set forth in M ~Section II.A of Appendix I. The ACTION- statements provide the required operating flexibility and at the same time implement the a
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 of the facility will not result .in radionuclide concentrations in
'the finished drinking water that are in excess of'the requirements of 40 CFR 141. The . dose calculations in'the Section 1.3'of this manual implement the requirements in Section III.A of Appendix I ,
that conformance with the guides ~of Appendix .I is to be shown by j calculational procedures based on- models and data such that the i actual exposure of an individual through appropriate pathways is unlikely to' be substantially underestinted. 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 .i
' Guide 1.109, " Calculation Of Annual Doses To Man From Routine Releases Of Reactor Effluents For The Purpose Of Evaluating Compliance With.10 CFR Part 50, Appendix I," Revision 1, October, j 1977, and Regulatory Guide 1.113, " Estimating Aquatic Dispersion Of j Effluents From Accidental And Routine Reactor Releases For The I Purpose ~ Of Implementing Appendix I," April, 1977. NUREG-0133 provides methods for dose calculations consistent with Regulatory f4 (f Guides 1.109 and 1.113.
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i D-3 ISSUE 3 l
Revision 1 '
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BV-1 and 2 ODCH
-APPENDIX D BASES FOR ODCM CONTROLS BASES: LIQUID EFFLUENTS (continued)
This CONTROL applies to the release of liquid effluents for Beaver Valley Power Station, Unit No. 1 or Unit No. 2. These units have shared radvaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.
3/4.11.1.3 LIQUID VASTE TREATMENT SYSTEM The CONTROL that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents vill be kept "as 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 obj ective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radvaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents. This specification applies .t o Beaver Valley Power Station, Unit No. 1 or Unit No. 2.
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D-4 ISSUE 3 Revision 1
BV-1 cnd 2 ODCM APPENDIX D BASES FOR ODCM CONTROLS i
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 withinLthe annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1.
These limits provide reasonable assurance that radioactive material discharged in gaseous effluents vill not result in the exposure of an individual in an unrestricted area, either within or outside the site boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)). For individuals who may at times be within the site boundary, the occupancy of the individual vill be sufficiently lov to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the site boundary to f 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
-s times, the corresponding thyroid dose rate above background to a
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j child via the inhalation pathway to f 1,500 nirem/ year, 3/4.11.2.2 DOSE, NOBLE GASES This CONTROL is provided to implement the-requirements of Sections II.B, III.A, and IV.A of Appendix ~ I, 10 CFR Part 50. The CONTROL implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in
- Section IV.A of Appendix I to assure that the release of radioactive material in gaseous effluents vill be kept "as lov as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based i' on models and data such that- the ' actual exporure of an individual through the appropriate pathvays is unlikely to be substantially j underestimated. The dose calculations established in Section 2.3 of I this manual for calculating the doses due to the actual release rates of' radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109,
" Calculation Of Annual Doses To Man From Routine Releases Of Reactor Effluents For The Purpose Of Evaluating Compliance Vith 10 CFR Part 30, Appendix I," Revision 1, October,1977 and Regulatory Guide 1.111, " Methods For Estimating Atmospheric Transport And Dispersion of Gaseous Effluents In Routine Releases From Light-Vater-Cooled
,~~ Reactors," Revision 1, July, 1977. The equations in Section 2.3 of I (1)~~
this manual are provided for determining the air doses at the exclusion area boundary, and are based upon the historical average i D-5 ISSUE 3 Revision 1
m BV-1 cnd 2 ODCH APPENDIX D BASES FOR ODCM CONTROLS BASES: GASEOUS EFFLUENTS (continued)
O atmospheric conditions. NUREG-0133 provides methods - for dose calculations consistent with Regulatory Guides 1.109 and 1.111, i This specifications applies to the release of gaseous effluents from '
l 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. j 1
The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents vill be kept "as lov as is reasonably achievable."
The calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be
- substantially underestimated. The calculational methods in Section 2.3 of this manaual are for calculating the doses due to the actual release rates of the subj ect materials are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation Of Annual Doses To Man From Routing Releases Of Reactor Effluents For The Purpose Of Evaluating Compliance With 10 CFR Part 50, Appendix I," Revision 1, October, 1977 and Regulatory Guide 1.111,
" Methods For Estimating Atmospheric Transport And Dispersion Of Gaseous Effluents In Routine Releases From. Light-Vater-cooled Reactors," Revision 1, July, 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for radioiodines, radioactive material in particulate form, and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which are examined in the development of these calculations are: 1) individual inhalation of airborne radionuclides,
- 2) deposition of radionuclides onto vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and~ 4) deposition on the ground with subsequent exposure of man. This CONTROL applies to radioactive L material in particulate form and radionuclides other than noble gases released from Beaver Valley Power Station, Unit No. 1 or Unit No.2.
f D-6 ISSUE 3 l Revision 1
BV-1 cnd 2 ODCM APPENDIX D BASES FOR ODCM CONTROLS 7--
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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 will 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 vere 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.
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BV-1 rnd 2 ODCM APPENDIX D BASES FOR ODCM CONTROLS BASES: TOTAL DOSE 3/4.11.4 TOTAL DOSE This CONTROL is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The CONTROL requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed.25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to 4 reactors, it is highly unlikley that the resultant dose to a MEMBER OF THE PUBLIC vill exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the units (including outside storages tanks, etc.) are kept small. The Special Report vill describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it .may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered. If the dose to'any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditior.s resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in
' CONTROLS 3.11.1.1 and 3.11.2.1. An individual is not considered a 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.
O D-8 ISSUE 3 Revision 1
i BV-1 End 2 ODCM APPENDIX D BASES FOR ODCM CONTROLS y
'A I
BASES: ' RADIOLOGICAL ENVIRONMENTAL MONITORING-3/4.12.1 MONITORING PROGRAM The- radiological monitoring program required by- this CONTROL
-provides measurements _of radiation ,and' of radioactive materials in those exposure pathways and for- those radionuclides which lead to the 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
, i materials and levels of radiation are not higher than expected on the basis- of the ~ effluent measurements and modeling 'of the environmental exposure. pathways. -The initially specified monitoring program vill be effective for -at least the first 3 -years of-commercial operation. Following this period, program changes'may be initiated based on operational experience. -
Thedekectioncapabilitiesrequiredby Appendix C, Table 4.12-1 are !
state-of-the-art; for routine environmental measurements in industrial-laboratories. The LLD's for drinking' vater meet the requirements of 40 CFR 141.
t 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 vith local agriculture authorities-shall be used. This census-satisfies the requirements of
. Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 500 square feet provides assurance
.that significant- exposure pathvays via. leafy vegetables vill be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions vere used: 1) that 20% of the garden was used for growing broad leaf 'l vegetation (i.e., similar to lettuce and cabbage), and 2) a j vegetation yield of 2 kg/ square meter. 1
, 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM v .,
The CONTROL- for participation in an Interlaboratory Comparison -l Program is provided to ensure that independent checks on the i precision and accuracy of the measurements of radioactive material j.. in environmental sample matrices are performed as part of a quality
- p. . assurance program for environmental monitoring in order to (f demonstrate that the results are reasonably valid. i r j
!? D-9 ISSUE 3 i Revision 1
BV-1 cnd 2 ODCH APPENDIX E ANNUAL REPORTS
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This appendix contains the reporting requirements for the Annual Radioactive Effluent Release Report and the Annual Radiological Environmental Report that vere transferred from the Technical Specification per Unit 1/2 Amendments 188/70 and in accordance with Generic Letter 89-01 and Generic Letter 89-01, Supplement rb. 1 (NUREG 1301). p The numbering of each specific Report contained in this appendix does not appear to be sequential. This is intentional, as all Report numbers remained the same when they were transferred from the Technical Specifications. This was done in an effort to minimize the amount of plant procedure changes and to eliminate any confusion associated.with numbering changes.
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E-1 ISSUE 3 )
Revision 1 '
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BV-1 and 2 ODCM APPENDIX E ANNUAL REPORTS ANNUAL REPORT 3
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 bc submitted prior to May 1 of each year and vill include reporting any devia nons not reported under 6.9.2f with respect to any Appendix C CONTROL. ,
The annual radiological environmental reports shall include:
- Summaries, interpretations, and statistical evaluation of the results of. the radiological environmental surveillance activities for the report period, including a comparison with pre-operational studies, operational controls (as appropriate), and previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.
- The results of the land use censuses required by Appendix C CONTROL 3.12.2.
l l
- If harmful effects or evidence of irreversible damage are detected l by the monitoring, the report shall provide an analysis of the ,
}
problem and a planned course of action to alleviate the problem.
- Summarized and tabulated results in the format of Appendix E, Table 6.9-1 of all radiological environmental samples taken during the report period. In the event that some results are not available -
for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.
- A summary description of the radiological environmental monitoring program.
- A map of all sampling locations keyed to a table giving distances and directions from one reactor.
- The results of licensee participation in the Interlaboratory Comparison Program required by Appendix C CONTROL 3.12.3.
3A single submittal may be made for a multiple unit site. The submittal should combine those sections that are common to both units.
E-2 ISSUE 3 Revision 1 i,
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BV-1 ond 3 ODCM APPENDIX E ANNUAL REPORTS ANNUAL REPORT O
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6.9.1.11 Routine radioactive effluent release reports covering the operation of the unit during the previous calendar year shall be submitted prior to April 1 of each year. This report is prepared and submitted in accordance with BVPS RCH Appendix 5, and at a minimum, shall contain the following:
- A summary of the quantities of radioactive liquid and gaseous effluent and solid vaste released from the unit as outlined in Regulatory Guide 1.21, Revision 1, June, 1974, " Measuring, Evaluating, And Reporting Radioactivity In Solid Vastes And Releases Of Radioactive Materials In Liquid And Gaseous Effluents From Light-Vater-Cooled Nuclear Power Plants," with data summarized on a quarterly basis following the format of Appendix B thereof.
- An assessment of radiation doses from the radioactive liquid and gaseous effluents released from the unit during each calendar quarter as outlined in Regulatory Guide 1.21. In addition, the unrestricted area boundary maximum noble gas gamma air and beta air doses shall be evaluated. The assestment of radiation doses shall be performed in accordance with this manual.
- Any licensee initiated changes to the ODCM made during the 12 month period.
- Any radioactive liquid or gaseous effluent monitoring instrumentation channels not returned to OPERABLE status within 30 days, and why the inoperability was not corrected in a timely manner. This applies to the liquid or gaseous effluent monitoring instrumentation channels required to be OPERABLE per Appendix C CONTROLS 3.3.3.9 and 3.3.3.10.
- Any 0DCM 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.
1
'A single submittal may be made for a multiple unit site. The submittal should combine those sections that are common to all units at ths site; however, for units with separate radvaste systems, the submittal shall specify the releases of radioactive material from each unit.
E-4 ISSUE 3 Revision 1 !
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BV-1 rnd 2 ODCH APPENDIX E -!
ANNUAL REPORTS l l
ANNUAL REPORT (continued) l i
- The following information for each type of solid vaste shipped offsite during the report period:
- container volume {
- total curie quantity (determined by measurement or estimate) !
- principal radionuclides (determined by measurement or estimate) I
- 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.
wt W ' An assessment of the radiation doses from radioactive effluents to HEMBER(S) 0F THE PUBLIC due to their activities inside the site boundary (Figure 5-1) during the report period. All assumptions used in making these assessments (e.g., specific activity, exposure time,.and location) shall be included in these reports. The assessment of radiation doses shall be performed in accordance with Section 4 of this manual.
- An assessment of radiation doses to the likely most exposed real individual from reactor releases for the previous calendar year to l show conformance with 40 CFR 190, Environmental Radiation Protection 4
! Standards For Nuclear Power Operation. Acceptable methods for l I calculating the dose contribution from liquid and gaseous effluents l are given in Regulatory Guide 1.109, Revision 1. The SKYSHINE Code f (available from Radiation Shielding Information Center, (ORNL)) is j acceptable for calculating the dose contribution from direct !
raoiation due to N-16.
- If quantities of radioactive materials released during the reporting period are signi.ficantly above design objectives, the report must cover this specifically.
j E-5 ISSUE 3 Revision 1
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FW44 = ' T ODC38 Controls Procedure Matrix l
- This'. appendix contains " plant' procedure references for Radiological Effluent Technical Specifications (RETS). that were transferred- from the Technical Specification Procedure Matrix.
16
-The' numbering of each specific Control, Surveillance Requirement'and Table contained in this Appendix, does not appear.to be sequential. This is intentional, as-all Control, Surveillance Requirement and Table numbers remained the-same when they were transferred from the Technical Specifications Procedure Matrix. This was done in an effort to minim.'.ze the ' amount of. plant procedure changes and to eliminate f atty confusion associated with numbering changes.
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.y N.f F-1 Issue 3 Revision 1 4
BV 1 and 2 ODCM APPENDIX F ODCM CONTROLS PROCEDURE MATRIX TABLE F:1a BV-1 LIQUID EFFLUENT MONITOR SURVEILLANCES Control Number 3.3.3.09 LlOUID EFFLUENT MONITORS IN APPENDIX C TABLE 3.3.12 OPERABLE APPLICABILITY: DURING RELEASES THROUGH WlE FLOW PATH ODCM SR DESCRIPTION PROCEDURE 4.3.3.09 TEST MONITORS AT TABLE 4.3-f2 FREQUENCY _
4.3.3.09.1. MONITORS PROVIDING ALARM AND AUTOMATICTERM 4.3.3.09.1.a LIQUID RADWASTE EFFLUENT MSP 43.18 CHANNEL CALIBRATION LINE (RM-LW-104) OM 1.54.3 (L5 ITEM 089) CHANNEL CHECK OM 1/217.4A.D SOURCF GiECK OST 1.43.09 FUNCTsONAL TEST 4.3.3.09.1.0 LlOUID WASTE MSP 43.23 CH ANNEL CALIBRATION CONTAMINATED DRAIN LINE - OM 1.54.3 - (L5 ITEM 106) CHANNEL CHECK (RM-LW-116) OM 1/2.17.4 A.D SOURCE CHECK OST 1.43.09 FUNCTIONAL TEST 4.3.3.09.1.c AUXILIARY FEED PUMP MSP 43.70 CHANNEL CALIBRATION BAY DRAIN MONITOR OM 1.54.3 (L5 ITEM 102) CHANNEL CHECK (RM-DA-100) OM 1.54.3 (L5 ITEM 102a) SOURCE CHECK OST 1.43.09 FUNCTIONAL TEST 4.3.3.f A.2 MONITORS PROVIDING ALARM BUT NO AUTO TERMINATION 4.3.3.09.2.a COMPONENT-COOLING MSP 43.10 CHANNEL CAtlBRATION RECIRCULATION SPRAY HX OM 1.54.3 (L5 ITEM 099) CHANNEL CHECK RIVER WATER MONITOR OST 1.43.09 FUNCTIONALTEST (RM-RW-100) OST 1.43.09A SOURCE CHECK 4.3.3.09.3 FLOW RATE MEASUREMENT 4.3.3.09.3a LIQUID RADWASTE EFFLUENT MSP 17.05 CHANNEL CALIBRATION LINES . MSP 17.06 F-LW-104-1 CHANNEL CALIBRATION (FR-LW-103/RM-LW-116) MSP 17.07 F-LW-104-2 CHANNEL CALIBRATION (FR-LW-104/RM-LW-104) MSP 17.08 F-LW-104-1 FUNCTIONAL TEST MSP 17.09 F-LW-104-2 FUNCTIONAL TEST MSP 17.10 F-LW-103 FUNCTIONAL TEST OM 1.54.3 (L5 ITEM 090) FR-LW-103 UNALHE! CHECK OM 1.54.3 (L5 ITEM 091) FR-LW-1041 CHANNEL CHEOK OM 1.54.3 (L5 ITEM 092) FR-LW-104-2 CHANNEL CHECK 4.3.3.09.3.b COOLING TOWER BLOWDOWN MSP 31.04 F-CW-101 CHANNEL CALIBRATION LINE MSP 31.05 F-CW 101 FUNCTIONAL TEST (FT-CW 101) MSP 31.06 F-CW-101-1 CHANNEL CALIBRATION (FT-CW-101-1) MSP 31.07 F-CW-101-1 FUNCTIONAL TEST OM 1.54.3 (L5 ITEM 095) FT-CW-101 CHANNEL CHECK OM 1.54.3 (L5 ITEM 096) FT-CW-101-1 CHANNEL CHECK 4.3.3.09.4 TANK LEVEL DEVICES 4.3.3.09.4.a PRIMARY WATER STORAGE TANK MSP 08.01 L-PG115A FUNCTIONAL TEST (BR-TK-6A) MSPre.65 L-PG115A CHANNEL CALIBRATION OM ' 54.3 (L5 ITEM 133) WHEN ADD TO TANK 4.3.3.09.4.b PRIMARY WATER STORAGE TANK MSP 08.02 L-PG-115B FUNCTIONAL TEST (BR-TK-68) MSP 08.04 L-PG-115B CHANNEL CAllBRATION OM 1.54.3 (L5 ITEM 135) WHEN ADD TO TANK 4.3.3.09.4.c STEAM GENERATOR DRAIN TANK MSP 17.01 L-LW110 FUNCTIONAL TEST (LW-TK-7A) MSP 17.03 L-LW110 CHANNEL CALIBRATION OM 1.54.3 (L5 ITEM 129) WHEN ADD TO TANK _ _ , _
4.3.3.09.4.d STEAM GENERATOR DRAIN TANK MSP 17.02 L-LW1111 FUNCTIONAL TEST (LW TK-78) MSP 17.04 L-LW111 CHANNEL CALIBRATION OM 1.54.3 (L5 ITEM 131) WHEN ADD TO TANK F-2 ISSUE 3 REVISION 1 i
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CV 1 cnd 2 ODCM APPENDIX F ODCM CONTROLS PROCEDURE MATRIX sof
.V- TABLE F:1b BV 2 LIQUID EFFLUENT MONITOR SURVEILLANCES ODCM NUMBER: 3.3.3.09 LlOUlD EFFLUENT MONITORS IN APPENDIX C TABLE 3.3.12 OPERABLE APPLICABILITY: DURING RELEASE THROUGH THE FLOW PATHS ODCM SR DESCRIPTION PROCEDURE 4.3.3.09- TEST MONITORS AT TABLE 4.3-12 FREQUENCY 4.3.3.09.1 MONITOR PROVIDING ALARM AND AUTOMATIC TERMINATION
~
4.3.3.09.1.a LlOUID WASTE PROCESS HPM RP 6.05A SOURCE CHECK EFFLUENTMONITOR MSP 2-43.39 CAllBRATION (2SGC-RQl100) . OM 2.54.3 (LOG L5 ITEM 81) CHANNEL CHECK OST 2.43.03 FUNCTIONAL TEST 1/20M-17.4A.C (SOURCE CHECK) 20M-25.4.L- (SOURCE CHECK) 20M 25.4.N (SOURCE CHECK) 1 4.3.3.09.2 FLOW RATE MEASUREMENT DEVICES
. 4.3.3.09.2.a LIQUID RADWASTE EFFLUENT MSP 2-25.01 2SGC-P26A,B CALIB/FUNCT (2SGC-FIS100) MSP 2-43.39 - CALIBRATION OM 2.54.3 (LOG L5 ITEM 82) CHANNEL CHECK 4.3.3.09.2.b COOLING TOWER MSP 2-31.04 CALIBRATION BLOWDOWN LINE MSP 2-31.05 FUNCTTEST (20WS-FT101) OM 2.54.3 (LOG L5 ITEM 83) CHANNEL CHECK t
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9 F-3 ISSUE 3 REVISION 1
BV-1 rnd 2 ODCM APPENDIX F ODCM CONTROLS PROCEDURE MATRIX TABLE F:2a BV 1 GASEOUS EFFLUENT F NITOR SURVEILLANCES CONTROL NUMBER: 3.3.3.10 GASEOUS EFFLUENT MONITORS IN APPENDIX C TABLE 3.3.13 OPERABLE APPLICABILITY: DURING RELEASE THROUGH THE FLOW PATHS ODCM SR DESCRIPTION PROCEDURE l 4.3.3.10 TEST MONITORS AT l TABLE 4.3-13 FREQUENCY I 4.3.3.10.1 GASEOUS WASTE (RM-GW-108A AND B) 4.3.3.10.1.t. NOBLE GAS ACTIVITY OM 1.19.4.E CHANNEL CHECK I MONITOR OM 1.19.4.E SOURCE CHECK MSP 43.22 CHANNEL CAllBRATION OM 1.54.3 (L5 ITEM OG3) RM-GW-108B CHANNEL CHECK ,
OM 1.54.3 . (L5 ITEM 206) RM-GW 109 CHANNEL CHECK {
OST 1.43.09 FUNOTIONAL TEST i 4.3.3.10.1.b PARTICULATE ACTIVITY OM 1.54.3 (L5 ITEM 062) CHANNEL CHECK MONITOR '
4.3.3.10.1.c SYSTEM EFFLUENT FLOW MSP 19.05 FUNCTIONAL TEST RATE MEASURING DEVICE MSP 19.0G CHANNEL CAllBRATION (FR-GW-108) OR OM 1.54.3 (L5 ITEM 094) CHANNEL CHECK ,
(RM-GW-109, CH.10) j 4.3.3.10.1.d SAMPLER FLOW RATE MSP 43.21 CHANNEL CAllBRATION MEASURING DEVICE MSP 43.71 ROTOMETER FUNCTIONAL TEST 4.3.3.10.2 AUXILIARY BUILDING (RM-VS-101 A and B) i 4.3.3.10.2.a NOBLE GAS ACTIVITY MSP 43.13 CHANNEL CALIBRATION MONITOR OM 1.54.3 (L5 ITEM 068) RM-VS-101B CHANNEL CHECK OM 1.54.3 (L5 ITEM 204) RM-VS-109 CHANNEL CHECK OST 1.43.09 OST 1.43.07A ALT NOBLE GAS MONITOR FUNCTIONAL TEST l FUNCTIONAL TEST ;
OST 1.43.09A SOURCE CHECK t 4.3.3.10.2.b PARTICULATE ACTIVITY OM 1.54.3 (L5 ITEM 067) CHANNEL CHECK MONITOR 4.3.3.10.2.c SYSTEM EFFLUENT FLOW MSP 44.07- FUNCTIONAL TEST RATE MEASUREMENT DEVICE MSP 44.08 CHANNEL CAllBRATION (FR-VS-101) OR OM 1.54.3 (L5 ITEM 0748) CHANNEL CHECK (RM-VS 109 CH 10) 4.3.3.10.2.d SAMPLER FLOW RATE MSP 44.07 FUNCTIONAL TEST MEASURING DEVICE MSP 44.08 ' CHANNEL CAllBRATION OM 1.54.? (L5 ITEM 074A) CHANNEL. CHECK 4.3.3.10.3 SLCRS (RM-VS-107A and B) 4.3.3.10.3.a NOBLE GAS ACTIVfTY MSP 43.20 CHANNEL CALIBRATION MONITOR OM 1.54.3 (L5 ITEM 072) RM-VS-1078 CHANNEL CHECK OM 1.54.3 (L5 ITEM 205) RM-VS-110 CHANNEL CHECK OST 1.43.07A ALT NOBLE GAS MONITOR FUNCTIONAL TEST OST 1.43.09 FUNCTIONAL TEST OST 1.43.09A SOURCE CHECK 4.3.3.10.3.b PARTICt, LATE ACTIVITY OM 1.54.3 (L5 ITEM 071) CHANNEL CHECK MONITOR 4.3.3.10.3.c SYSTEM EF-FLUENT FLOW MSP 44.09 CHANNEL CALIBRATION RATE MEASURING DEVICE MSP 44.10 FUNCTIONAL TEST (FR-VS-112) OR OM 1.54.3 (L5 ITEM 093) CHANNEL CHECK (RM-VS-110 CH 10) 4.3.3.10.3.d SAMPLER FLOW RATE MSP 43.19 CHANNEL CALIBRATION MEASURING DEVICE MSP 43.72 ROTOMETER FUNCTIONALTEST RADCON LOG CHANNEL CHECK F-4 ISSUE 3 REVISION 1
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BV 1 cnd 2 ODCM
-l APFENDIX F QT ODCM CONTROLS PROCEDURE MATRIX h,)
TABLE F:2b BV 2 GASEOUS EFFLUENT MONITOR SURVEILLANCES
' CONTROL NUMBER: 3.3.3.10 GASEOUS EFFLUENT MONITORS IN APPENDIX C TABLE 3 313 OPERABLE i APPLICABill1Y: DURING RELEASE THROUGH THE FLOW PATH I ODCM SR - DESCRIPTION PROCEDURE 4.3.3.10- TEST MONITORS AT TABLE 4.3-13 FREQUENCY i 4.3.3.10.1 SLCRS - UNFILTERED (2HVS-RQ101A and B) 4.3.3.10.1.a - NOBLE GAS ACTIVITY MONITOR MSP 2-43.36 CHANNEL CALBRATION -
OM 2.54.3 (LOG L5 ITEM 74) CHANNEL CHECK -
OST 2.43.09 FUNCTIONAL TEST.
DRMS SOURCE CHECK (DRMS AUTO FUNCTION)-
4.3.3.10.1.b PARTICULATE ACTIVITY OM 2.54.3
% (LOG L5 ITEM 74) CHANNEL CHECK MONITOR 4.3.3.10.1.c PROCESS FLOW RATE MSP 2-43.36 CHANNEL CALBRATION -
MONITOR MSP 2-43.36A FUNCTIONAL TEST ,
MWR VELOCITY PROBE CALBRATION .
OM 2.54.3 (LOG L5 ITEM 74) CHANNEL CHECK I SAMPLER FLOW RATE MONITOR MSP 2-43.36 : CHANNEL CALBRATION MSP 2-43.36A . FUNCTIONAL TEST
~ : OM 2.54.3 (LOG L5 ITEM 74) CHANNEL CHECK -
r 4.3.3.10.2: SLCRS - FILTEP40 (2HVS-RO109A and B) 4.3.3.10.2.a ' NOBLE GAS ACTIVITY MONITOR MSP 2-43.32 2HVS*RQ109A CHANNEL CALIBRATION
'* MSP 2-43.33 = 2HVS*RQ1098,C,D CHANNEL CAllBRATION OM 2.54.3 _ (LOG L5 ITEM 71) CHANNEL CHECK -
g ~ OST 2.43.08 FUNCTIONALTEST DRMS SOURCE CHECK (DRMS AUTO FUNCTION)'
4.3.3.10.2.b PARTICULATE ACTIVITY MSP 2-43.32 . CHANNEL CALBRATION j
i MONITOR OM 2.54.08 ' (LOG L5 ITEM 71) CHANNEL CHECK 4.3.3.10.2.c PROCESS FLOW RATE MSP 2-43.32s FUNCTIONAL TEST 1 MONITOR . MSP 2-43.33 ~ 2HVS*RQ1098,C,D, CHANNEL CALIBRATION MWR- VELOCITY PROBE CALERATON OM 2.54.3 (LOG L5 ITEM 71) CHANNEL CHECK 4.3.3.10.2.d SAMPLER FLOW RATE MONITOR MSP 2-43.32 2HVS*RO109A CHANNEL CALIBRATION MSP 2-43.32A FUNCTIONALTEST -
MSP 2-43.33 2HVS*RQ1098,C D, CHANNEL CALE OM 2.54.3 ' (LOG L5 ITEM 71) CHANNEL CHECK 4.3.3.10.3- DECONTAMINATION BUILDING (2RMO-RO301 A and B) 4.3.3.10.3.a NOBLE GAS ACTIVITY MONITOR MSP 2-43.35 ' CHANNEL CALERATION OM 2.54.3 ' (LOG L5 ITEM 73) CHANNEL CHECK OST 2.43.09 FUNCTIONAL TEST DRMS SOURCE CHECK (DRMS AUTO FUNCTION) 4.3.3.10.3.b - . PARTICULATE ACTIVITY OM 2.54.3 (LOG LS ITEM 73) CHANNEL CHECK MONITOR 1
F-5 ISSUE 3 REVISION 1 m' y J
APPENDIX F ODCM CONTROLO PROCEDURE MATRIX TABLE F:2b BV 2 GASEOUS EFFLUENT MONITOR SURVEILLANCES 1*Q CONTROL NUMBER: 3.3.3.10 GASEOUS EFFLUENT MONITORS IN APPENDIX C TABLE 3.3.13 OPERABLE APPLICABILITY: DURING RELEASE THROUGH THE FLOW PATH ODCM SR DESCRIPTION PROCEDURE 4.3.3.10.3.d SAMPLE FLOW RATE MONITOR MSP 2-43.35 CHANNEL CALIBRATION MSP 2-43.35A FUNCTIONAL TEST OM 2.54.3 (LOG L5 ITEM 73) CHANNEL CHECK 4.3.3.10.4 CONDENSATE POLISHING (2HVL-RO112A and B) 4.3.3.10.4.a NOBLE GAS ACTIVITY MONITOR MSP 2-43.38 CHANNEL CAllBRAT!ON OM 2.54.3 (LOG L5 ITEM 76) CHANNEL CHECK OST 2.43.09 FUNCTIONAL TEST DRMS SOURCE CHECK (DRMS AUTO FUNCTION) 4.3.3.10.4.b PARTICULATE ACTIVITY OM 2.54.3 (LOG L5 ITEM 76) CHANNEL CHECK MONITOR 4.3.3.10.4.d SAMPLE FLOW RATh MONITOR MSP 2-43.38 CHANNEL CALIBRATION MSP 2-43.38A FUNCTIONAL TEST OM 2.54.3 (LOG LS ITEM 76) CHANNEL CHECK 4.3.3.10.5 WASTE GAS STORAGE VAULT (2RMO-RQ303A and B) 4.3.3.10.5.a NOBLE GAS ACTIVITY MONITOR MSP 2-43.37 CHANNEL CALIBRATION OM 2.54.3 (LOG L5 ITEM 75) CHANNEL CHECK OST 2.43.09 FUNCTIONAL TEST DRMS SOURCE CHECK (DRMS AUTO FUNCTION) 4.3.3.10.5.b PARThCULATE ACTIVITY OM 2.54.3 (LOG L5 ITEM 75) CHANNEL CHECK MONITOR 4.3.3.10.5.d SAMPLE FLOW RATE MONITOR MSP 2 43.37 CHANNEL CALIBRATION MSP 2-43.37A FUNCTIONAL TEST OM 2.54.3 (LOG L5 ITEM 75) CHANNEL CHECK O
F-6 ISSUE 3 REVISION I
BV-1 and 2 ODCM APPENDIX F ODCM CONTROLS PROCEDURE MATRIX g.g
('; TABLE F:3
(,! BV-1 AND 2 LIQUID EFFLUENT CONCENTRATION SURVEILLANCES CONTROL NUMBER: 3.11.1.1 EFFLUENT CONCENTRATION WITHIN 10 TIMES 10CFR20 EC's APPLICABILITY: AT ALL TIMES ODCM SR DESCRIPTION PROCEDURE 4.11.1.1.1 SAMPLE AND ANALYZE HPM CP 1 LIQUID RADWASTE DISCHARGES RADIOACTIVE LIQUID WASTES PER TABLE 4.11-1 4.11.1.1.1.A BATCH WASTE RELEASE TANKS CHM CP 3 SAMPLING AND TESTING CHM CP 5 RADIOCHEMICAL PROC CHM CP8 LOGS AND FORMS (ANALYSIS)
CHM CP 9 CONDUCT OF OPERATION HPM CP 3 RP 6.01 LIQ WASTE TANK SAMPLING HPM CP 4 RIP 2.02 EFFLUENT MONITORS HPM CP 4 RIPS.17 ND-9900 COUNTING SYSTEM HPM CP 4 RIP 2.21 DRMS EFFLUENT MONITOR 4.11.1.1.1.B CONTINUOUS RELEASES CHM CP 3 SAMPLING AND TESTING CHM CP 5 RADIOCHEMICAL PROC CHM CP 8 ' .GGS AUD FORMS (ANALYSIS) '
CHM CP O CONDUCT OF OPERATION HPM CP 4 RIP 2.02 EFFLUENT MONITORS HPM CP 4 RIPS.17 ND-9900 COUNTING SYSTEM HMP CP 4 RIP 2.21 DRMS EFFLUENT MONITOR 4.11.1.1.2 USE ODCM METHOD TO HPM CP 3 RP 6.05 LW DISCHARGE AUTHORIZATION ASSURE COMPLIANCE HPM CP 3 RP6.05A LW DISCHARGE AUTHORIZATION
, .3 OM 1/2.17.4A.D LIQUID WASTE DISCHARGE (W/RP 6.5) i '
4.11.1.1.3 WHEN BV-1 PRIMARY TO CHM CP 1 SPECS & GUIDELINES
'\~ ) SFCONDARY LEAKAGE CHM CP 5 LEAK RATE CALCULATION EXCEEDS 0.1 GPM TAKE CHM CP 8 LOGS AND FORMS TURBINE SLDG GRAB SAMPLES HPM CP 3 RP6.05 LW DISCHARGE AUTHORIZATION HPM CP 3 RP6.05A LW DISCHARGE AUTHORIZATION ,
HPM CP 4 RIP 2.02 EFFLUENT MONITORS ~
4.11.1.1.4 WHEN BV-2 PRIMARY TO CHM-CP 1 SPECS & GUIDELINES SECONDARY LEAKAGE CHM CP 5 LEAK RATE CALCULATION EXCEEDS 0.1 GPM, TAKE OHM CP 8 LOGS AND FORMS TURBINE BLDG GRAB SAMPLES HPM CP 3 RP6.05 LW DISCHARGE AUTHO!RZATION HPM CP 3 RP6.05A LW DISCHARGE AUTHORIZATION HPM CP 4 RIP 211 EFFLUENT MONITORS 4.11.1.1.5 TAKE GRAB SAMPLES PRIOR TO HPM CP3 RP6.05 LIQUID WASTE GRAB SAMPLES I BV-2 RECIRC DRAIN PUMP OM 2.09.2 RX PLANT VENTS AND DRAINS (08-16)
DISCHARGE TO CATCH BASIN ' OM 2.09.4F DRAIN RSS PUMP CASING / PIT NO.16 OM 51-86 OM CLEARANCE 51-36 (2DAS-P215A/B)
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ISSUE 3 REVISION 1 E _-
BV 1 AND 2 ODCM APPENDIX F ODCM CONTROLS PROCEDURE MATRIX TABLE F:4 BV 1 AND 2 LIQUID EFFLUENT DOSE SURVEILLANCES Control Number 3.11.1.2 LIQUID EFFLUENT DObE APPLICABILITY: AT ALL TIMES ODCM SR DESCRIPTION PROCEDURE 4.11.1.2.1 EVERY 31 DAYS DETERMINE HPM CP 3 RP 6.05A LW DISCHARGE AUTHORIZATION CUMULATIVE DOSE FROM HPM CP 3 RP 6.05 LW DISCHARGE AUTHORIZATION LIQUID EFFLUENTS USING HP LETTER MONTHLY DOSE PROJECTION ODCM OM 1/2174A.D LIQUID WASTE DISCHARGE O
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F-8 ISSUE 3 REVISION 1 e_ ____ _ __
BV 1 AND 2 ODCM 4
(l APPENDlX F-ODCM CONTROLS PROCEDURE MATRIX a*k TABLE F:5 '
BV 1 AND 2 LIQUID EFFLUENT TREATMENT SURVEILLANCES Cortrol Number 3.11.1.3 LIQUID EFFLUENT TREATMENT SYSTEM < -)
APfitlCABILITY: AT ALL TIMES-
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ODCM SR DESCRIPTION PROCEDURE
~U1.1.3.1- EVERY 31 DAYS PROJECT THE HPM CP 3 RP 6.05 LW DISCHARGE AUTHORIZATION LIQUID RELEASE DOSE USING HPM CP 3 RP 6.05 A LW DISCHARGE AUTHORIZATION Tile ODCM HP LETTER MONTHLY DOSE PROJECTION p' OM 1/2174A.D LIOUlD WASTE DISCHARGE (W/RP 6.5) i I
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~F-9 ISSUE 3 REVISION 1
BV 1 AND 2 ODCM
)
APPENDIX F ODCM CONTROLS PROCEDURE MATRIX TABLE F:6 )
3V 1 AND 2 GASEOUS EFFLUENT DOSE SURVEILLANCES j Control Number 3.11.2.1 GASEOUS EFFLUENT DOSE RATES APPLICABILITY: AT ALL TIMES ODCM SR DESCRIPTION ,
PROCEDURE 4.11.2.1.1 DETERMINE NOBLE GAS HPM CP 3 RP 6.06 GW DISCHARGE AUTHORIZATION EFFLUENT DOSE RATE USING HPM CP 3 RP 6.10 CONTIN VENT PATH RELEASE THE ODCM HPM CP 3 RP 6.12 ABNORMAL GAS RELEASES HPM CP 3 RP 6.06A GW DISCHARGE AUTHORIZATION OM 1.19.4E BV-1 DECAY TANK DISCHARGE (W/RP 6.6)
OM 1/219.4A.B BV-2 DECAY TANK DISCHARGE (W/RP 6.6) ,
4.11.2.1.2 SAMPLE AND ANALYZE PER HPM CP 1 RADWASTE DISPOSAL TABLE 4.11-2 TO DETERMINE INHALATION PASTHWAY DOSE 4.11.2.1.2.A WASTE GAS STORAGE TANK- CHM CP 3 SAMPL!NG & TESTING GRAB SAMPLE EACH TANK CHM CP e LOGS & FORMS ,
HPM CP 3 RP 6.03 BV-1 GAS TANK SAMPLING i HPM CP 3 RP 6.04 BV-2 GAS TANK SAMPLING HPM CP 3 RP 6.06 GW DISCHARGE AUTHORIZATION l HPM CP 3 RP 6.06A GW DISCHARGE AUTHORIZATION {
HPM CP 4 RIP 2.02 EFFLUENT MONITORS HPM CP 4 RIP 2.20 DRMS PROCESS MONITORS HPM CP 4 RIP 2.21 DRMS EFFLUENT MONITORS 4.11.2.1.2.B CONTAINMENT PURGE-GRAB - CHM CP 3 SAMPLING & TESTING SAMPLE EACH PURGE CHM - CP 8 LOGS & FORMS q g HPM CP 3 RP 6.06 GW DISCHARGE AUTHORIZATION HPM CP 3 RP 6.06A GW DISCHKilGE AUTHORIZATION HPM CP 3 RP 7.03 AIR SAMPLING HPM CP 4 RIP 2.02 EFFLUENT MONITORS HPM CP 4 RIP 2.20 DRMS PROCESS MONITORS HPM CP 4 RIP 2.21 DRMS EFFLUENT MONITORS 4.11.2.1.2.C VENTILATION SYSTEMS 4.11.2.1.2.C.1 BV-1 GRAB AND CONTINUOUS CHM CP 3 SAMPLING & TESTING THRU SAMPLES CHM CP8 LOGS & FORMS 4.11.2.1.C.3 CHM CP9 CONDUCT OF OPERATION AND HPM CP 3 RP 6.08 RMS SAMPLE FLOW LINE-UP (NSA) 4.11.2.1.2.D.1 HPM CP 3 RP 6.09 RMS SAMPLE FLOW LINE-UP ( FILTER CHG)
THRU- HPM CP 4 RIP 2.02 EFFLUENT MONITORS I 4.11.2.1.2.D.3 HPM CP 4 RIP 2.08 SA-9/10 NOBLE GAS MONITOR l HPM CP 4 RIP 2.10 SPING-4 MONITOR HPM CP 5 REOP1.1 SA-9/10 EMERGENCY OPERATE HPM CP 5 REOP1.2 SPING-4 EMERGENCY OPERATE HPM CP 3 RP 6.10 (CONTIN VENT PA'lH RELEASE) 4.11.2.1.2.C.4 BV-2 GRAB AND CONTINUOUS CHM CP 3 SAMPLING & TESTING THRU SAMPl?S CHM CP 8 LOGS & FORMS 4.11.2.1.2.C.8 CHM CP 9 CONDUCT OF OPERATIONS AND HPM CP S REOP4.1 EMERG OPER OF WRGM ASSEM 4.11.2.1.'2.C.4 HPM CP 4 RIP 2.21 INSTRUMENT PROCEDURE THRU HPM CP 2 lire 6.10 CONTIN VENT PATH RELEASE 4.1.r.1.2.C.8 F-10 ISSUE 3 REVISION 1 o l C _
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.- APPENDIX F -
, ODCM CONTROLS PROCEDURE MATRIX
. TABLE F:7-l: .
BV 1 AND 2 GASEOUS EFFLUENT AIR DOSE SURVEILLANCES i-Control Norreber 3.11.2.2 GASEOUS EFFLUENT AIR DOSES L. APPLICABILITY: AT ALL TIMES -
l ODCM SR DESCRIPTION . PROCEDURE-4.11.2.2.1 EVERY 31 DAYS DETERMINE HPM CP 3 RP 6.06 GW DISCHARGE AUTHORIZATION CUMULATIVE DOSE HPM CP 3 RP 6.10 CONTIN VENT PATH RELEASE lp - CONTRIBUTIONS USING THE HPM CP 3 RP 6.06A . GW DISCHARGE AUTHORIZATION
'1 r ODCM HPM CP 3 RP 6.12 ABNORMAL GAS RELEASES L E
HPM CP 4 RIP 2.02 EFFLUENT MONITORS '
HPM CP 3 RP 6.12A ABNORMAL GAS RELEASES - 1
' OM 1.19.4E -- ' BV 1 DECAY TANK DISCHARGE (W/RP 6.6)
OM 1/219.4A.B BV-2 DECAY TANK DISCHARGE (W/RP 6.6)
HPM CP 4 RP 2.21 DRMS EFFLUENT MONITORS L-(.
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'F-11 ISSUE 3
, REVISION 1 ;
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l FV 1 AND 2 ODCM j APPENDIX F ODCM CONTROLS PROCEDURE MATRIX TABLE F:8 BV 1 AND 2 GASEOUS EFFLUENT PARTICULATE AND IODINE DOSE SUREILLANCES Control Number 3.11.2.3 GASEOUS EFFLUENT PARTICULATE AND LODINE DOSES APPLICABILITY: AT ALL TIMES ODCM SR DESCRIPTION PROCEDURE 4.11.2.3.1 EVERY 31 DAYS DETLf.MINE HPM CP 3 RP 6.06 GW DISCHARGE AUTHORIZATION CUMULATIVE DOSE HPM CP 3 RPG.06A GW DISCHARGE AUTHORIZATION CONTRIBUTIONS USING THE HPM CP 3 RP 6.10 CONTIN VENT PATH RELEASE ODCM HPM CP 3 RP 6.12. ABNORMAL GAS RELEASES HPM CP 4 RIP 2.02 EFFLUENT MONITORS HPM CP 4 RIP 2.21 DRMS EFFLUENT MONITORS HPM CP 6.12A ABNORMAL GAS RELEASES OM 1.19.4E BV-1 DECAY TANK DISCHARGE (W/RP 6.6)
OM 1/2.M.4A.3B BV-2 DECAY TANK DISCHARGE (W/RP 6.6)
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F-12 ISSUE 3 REVISION 1
BV 1 AND 2 ODCM APPENDIX F
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ODCM CONTROLS PROCEDURE MATRIX TABLE F:9 BV-1 AND 2 GASEOUS EFFLUENT TREATMENT SURVEILLANCES Control Number 3.11.2.4 GASEOUS EFFLUENT TREATMENT SYSTEM APPLICABILITY: AT ALL TIMES -
ODCM SR DESCRIPTION PROCEDURE-4.11.2.4.1 EVERY 31 DAYS PROJECT GAS - HPM CD 3 RP 6.06 . GW DISCHARGE AUTHORIZATION RELEASE DOSE FROM THE SITE HPM CP 3 RP 6.06A GW DISCHARGE AUTHORIZATION USING THE ODCM HPM CP 3 RP 6.10 CONTIN VENT PATH RELASE HPM CP 3 RP 6.12 ABNORMAL GAS RELEASES HPM CP 6.12A ABNORMAL GAS RELEASES HP LETTER MONTHLY DOSE PROJECTION OM 1.19.4E BV-1 DECAY TANK DISCHARGE (W/RP 6.6)
OM 1/219.4A.B BV-2 DECAY TANK DISCHARGE (W/RP 6.6) a l
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F-13 ISSUE 3 REVISION 1 l
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BV 1 cnd 2 ODCM APPENDIX F fe TABLE F 10 e
BV 1 AND 2 TOTAL DOSE SURVEILLANCES Control Number 3.11 A.1 LIQUID AND GASEOUS DOSES APPLICABILITY: AT ALL TIMES ODCM SR DESCRIPTION PROCEDURE 4.11.4.1.1 DETERMINE CUMULATIVE GAS & HPM APP 05 - COMP. WITH RG 1.21 & T.S. (40 CFR 190)
LIQUID DOSE PER APPENDIX C HPM CP 3 RP 6.05 LW DISCHARGE AUTHORIZATION CONTROL 3.11.1.2,3.11.2.2, HPM CP 3 RP6.05A LW DISCHARGE AUTHORIZATION 3.11.2.3 HPM CP 3 RP 6.06 GW DISCHARGE AUTHORIZATION HPM CP 3 RP6.06A GW DISCHARGE AUTHORIZATION HPM CP 3 RP 6.10 CONTIN VEfR PATH RELEASE HPM CP 3 RP 6.12 ABNORMAL GAS RELEASES HPM CP 3 RP6.12A ABNORMAL GAS RE.'.5ASES REAM REAP 6.105 EFFLUENT DATA PROCESSING (40 CFR 190) 4 O
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F-14 ISSUE 3 REVISION 1 l l
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BV-1 and 2 CDCM 4
APPENDIX F ODCM CONTROLS PROCEDURE MATRIX TABLE F:11 BV-1 AND 2 REMP SURVEILLANCES Control Numbar 3.12.1 REMP -
APPLICABILITY: AT ALLTIMES
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l ODCM SR ' DESCRIPTION PROCEDURE 4.12.1.1 COLLECT AND ANALYZE EPMP 2.01 DESCRIPTION OF REMP SAMPLES PER TABLES 3.12-1, - EPMP 3.01 ENVIRONMENTAL SAMPLING
[ 3.12-2 & 4.12-1: USE LOCATIONS IN ODCM Yhl l'
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i F-15 ISSUE 3 REVISION 2
CV-1 and 2 ODCM '
APPENDIX F
- ODCM CONTROLS PROCEDURE MATR X TABLE F:12 BV 1 AND 2 LAND USE CENSUS SURVEILLANCES Control Number 3.12.2 LAND USE CENSUS APPLICABILITY: AT ALL TIMES ODCM SR DESCRIPTION PROCEDURE 4.12.2.1 YEARLY BETWEEN 6/1 & 10/1 EPMP 2.01 DESCRIPTION OF REMP CONDUCT LAND CENSUS USING BEST AVAILABLE METHOD O
O F-16 ISSUE 3 REVISION 2
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! BV-1 and 2 ODCM APPENDIX F ODCM CONTROLS PROCEDURE MATRIX l(] TABLE F:13 l4 / BV-1 AND 2 INTERLABORATORY COMPARISON PROGRAM Crntrol Number 3.12.3 INTERLABORATORY COMPARISON PROGRAM '
APPLICABILITY: AT ALLTIMES l
l l Or,CM SR DESCRIPTION PROCEDURE-4,12.3.1 INCLUDE PROGRAM ANALYSIS EPMP 2.01 DESCRIPTION OF REMP
! RESULTS IN THE ANNUAL -
l RADIOLOGICAL ENVIRONM
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i F-17 ISSUE 3 REVISION 2