ML20205F696
| ML20205F696 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 11/30/1998 |
| From: | DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20205F687 | List: |
| References | |
| PROC-981130, NUDOCS 9904060378 | |
| Download: ML20205F696 (300) | |
Text
{{#Wiki_filter:_. __ _ _ _ _ . DUQUESNE LIGHT COMPANY Beaver Valley Power Station - Units 1 & 2 Annual Radioactive Effluent Release Report Calendar Year- 1998 Attachment 2 Unit 1 and 2 Offsite Dose Calculation Manual Changes Attachment 2-Attached is a complete copy of the ODCM that includes: Issue 3, Revision 4, Effective March 13,1998 and issue 3, Revision 5, Effective November 30,1998
' Attachment 2 Clarification in an effort to reduce overall costs associated with this report, only the following have been sent a complete copy of the ODCM:
United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 United States Nuclear Regulatory Commission / Regional Administrator, Region 1 475 Allendale Road King of Prussia, PA 19406 For a complete copy of the ODCM, contact Mr. Anthony T Lonnett at 412-393-5860. 9904060378 990319 PDR
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1 i DUQUESNE LIGHT COMPANY Beaver Valley Power Station - Units 1 & 2 Annual Radioactive Effluent Release Report Calendar Year - 1998 Attachment 2 Unit 1 and 2 Offsite Dose Calculation Manual Changes "U Attachment 2 Attached is a complete copy of the CDCM that includes: Issue 3, Revision 4, Effective March 13,1998 and issue 3, Revision 5, Effective November 30,1998 EM ' l Attachment 2 Clarification In an effoit to reduce overall costs associated with this report, only the following have been sent a complete copy of the ODCM-United States Nuctear Regulatory Commission Document Control Desk Washington, DC 2C555 j United States Nuclear Regulatory Commiss<on Q Regional Administrator, Region 1 475 ANerda'e Road i K;ng of Prcss a, PA 194C6 l For a complete copy of the ODCM, contact Mr. Anthony T Lonnett at 412-393-5860. 9904060378 9905T9 ~~~
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RTL A9.621B Form RE 6.101-03 (08/98) , DUQUESNE LIGHT COMPANY g Beaver Valley Power Station W j BV-1 and 2 ODCM Cony Holders Log BV-1 and 2 ODCM Issue No. 3 Revision No. 5 Effective Date 11/30/98 Controlled Copies Unit 1 Control Room (NSS) No. 1 HP Manager No. 2 IJnit 2 Control Room (NSS) No. 3 Efiluent Control (SHPS) No. 4_. Unit i Rad Operations Director No. 5 Licensine No. 6 Unit 1 Operations Manager No. 7 Unit 2 Operations Manager No. R Operations Procedure Group E9o I&C Procedures Group No. 10 Unit 1 Operators Console No. 11 Unit 2 Operators Console No. 12 SPED No. 13 Training Manager No. 14 . Unit 1 Simulator No. 15 Unit 2 Simulator No. 16 SER Library No. 17 GEBCO Engineerine No. I8 OSC Meetine Room No. 19 Information 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 (Region 11 No. 8 No. 9 Effluent Control Offsite Use (SHPS) No. 10 REMP Administrator No. I1 Efflueo* Control Offsite Use (HPS) No. 12 DLC-OA No. 13 Effluent Control Offsite Use (HPS) No. 14 No. No.
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OSC Review l Pages RSC Review and Aproval Approved By Effective. J Issued Meeting No. Date Meeting No. Date Signature Date Date j title BV-RSC-20 98 11/1268 BV-OSC-46-98 11/1868 11/30/98 I i viii xxvil thru xxxi 1-17 thru l-18 I 3-4 thru I 3 14 O C-2 thru C-4 C-19 C-37 u 23 f6 C-39 C-47 Manager, thru Health Physics C-48 F-10 (}'
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RTL A9.02iB Form RE 6.101-01 (05/96) DUQUESNE LIGHT COMPANY Beaver Valley Power Station BV-1 and 2 ODCM Review and Approval Record OSC Review Plant Manager or Issue Rev. Pages RSC Review and Approval Designee Approval Eff. No. No. Issued Meetmg No. Date Meeting No. Date Signature Date Date 3 4 title BV-RSC-98-05 3/6/98 Poll 3162 3/10/98 3/13/98 i vii Xiii XXVii thru XXIX 3-4 thru ) 3-14
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DUQUESNE LIGHT COMPANY Nuclear Group INCLUDED FOR Q HISTORICAL Review and Approval Sheet PURPOSES UNIT 1 - OFFSITE DOSE CALCULATION MANUAL ISSUE 2 Rev. Pgs. Tech. Rev. OSC Approv. Eff. No. Issd. Sign. Date Review Date Sign. Date Date 0 TITLE PGS BV-RSC-11-87 BV-0SC-17-87 C Y i thru viii BV-RSC-12-87 June 12, 1987 7/24/87 1-1 thru 1-17 BV-RSC-14-87 h/6[18') 2-1 thru 2-96 May 29, 1987 3-1 thru 3-14 ggpg 4,1, 5-1 i ) A-1 thru A-7 B-1 thru B-4 l 1 2-11 BV-RSC-38-87 BV-1-OSC-25-87 y 12/22/87 2-14 12/3/87 12/15/87 l t . v2W.44 /2/zz/87 l
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Rev. Pgs. Tech. Rev. OSC Approv. ilEff. No. Issd. Sign. Date Review Date Sign. Date Date Rev. 1 111 O U ' AM V' fY-00f 1-17,18,19 E45-hhp 1-ff-/7
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BV-1 cnd 2 ODCM DUQUESNE LIGrr CNPANY-Y Beaver Valley Poer Staticn Unit 1 ~ Docket No. 50-334 License No. DPR-66 Beaver Valley Power Staticn Unit 2:
. Docket No. 50-412
' License No. NPF-73 BRAVER VALLEY PONER STATICN IEIT 1.(BV-1)
BEAVER VALLEY PONER STATIN IMIT 2 (BV-2) orrsrrE pose chranATIm MANUAL (CDCM) 1 l l j i 1
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BV-1~and 2 ODCM l LIST OF TABLES I SECTICN TITLE PAGE 10. lk Table of contents....................-............... 1 List Of Tables...................................... iii List Of Figures..................................... vii ODO4 Equaticn Cross Reference. . . . . . . . . . . . . . . . . . . . . . . viii OXM Table Cross Reference. . . . . . . . . . . . . . . . . . . . . . . . . . x Preface............................................. xiii History Of ODQ4 Changes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . xiv
- References for CDCM Changes . . . . . . . . . . . . . . . . . . . . . . . . . Jooc i
1.0 LIQUID EFFLUENIS.................................... 1-1 1.1 Alarm Setpoints................. ............... 1-2 1.1.1 BV-1 Mcnitor ?.larm Setpoint Determination. . . . 1-2
' 1.1.1.1 BV-1 Setpoint Determinaticn based On A Cbnservative Mix............................ 1-2 1.1.1.2 BV-1 Setpoint Determinaticn Based On Analysis Prior To Release . . . . . . . . . . . . . . . . . . . 1-5 1.1.2 BV-2 Monitor Alarm Secpoint Determinaticn. . . . . 1-7 .
1.1.2.1 BV-2 Setpoint Determinaticn Based On A Conservative Mix............................ 1-7 1.1.2.'4 }3V-2. Setpoint Determinaticn Based On Analysis Prior To Release. . . . . . . . . . . . . . . . . . . 1-10 References For Liquid Alarm Setpoints............... 1-15 1.2 Cortpliance With 10 CFR 20 EC Limits............. 1-16 1.2.1 Batch Releases................................ 1-16 ( 1.2.2 Continuous Releases........................... 1-18 1.3 Ccnpliance With 10 CFR 50 Dose Limits. . . . . . . . . . . 1-21
- 1. 3 .1 CLmulaticn Of Doses . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-21
- 1. 3 . 2 Proj ecticn Of Doses . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-23 1.4 Liquid Radwaste System.......................... 1-27 1.4.1 BV-1 Liquid Radwaste System Cugssts. . . . . . . . 1-28 1.4.2 BV-2 Liquid Radwaste System Cugsants. . . . . . . . 1-29 2.0 GASEOUS EFFLUENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-1 2.1 Alarm Setpoints................................. 2-2 Ig 2.1.1 BV-1 Mcnitor Alarm Setpoint Determinaticn. . . . . 2-2 2.1.1.1 BV-1 Setpoint Determinaticn Based On A Calculated Mix (Ground Releases) . . . . . . . . . . . . 2-5 2.1.1.2 BV-1 Setpoint Determinaticn Based On Analysis Prior To Release (Grotted Releases) . 2-10 2.1.2 BV-2 Mcnitor Alarm Setpoint Determinaticn. . . . . 2-13 2.1.2.1 BV-2 Setpoint Determimticn Based On A Calculated Mix (Ground Releases) . . . . . . . . . . . . 2-13 l
i 2.1.2.2 BV-2 Setpoint Determinaticn Based On
- j. Analysis Prior' To Release '(Ground Releases) . 2-19 sm
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( l l 1 ISSUE 3 i Revision 5 , k- _ J
BV-1 Gnd 2 ODCM LISTP OF TABIFE SECTION TITLE PAGE 10. 2.1.3 BV-1/2 Monitor Alarm Setpoint Determination. . . 3-22 O 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 (Glevated Releases) 2-26 References For Gaseous Alarm Setpoints.............. 2-33 2.2 Compliance With 10 CFR 20 Dose Rate Limits...... 2-34 2.2.1 Dose Rate Due To Noble Gases.................. 2-34 2.2.2 Dose Rate Due To Radioiodines And Particulates 2-41 2.3 Compliance With 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 ection Of Doses . . . . . . . . . . . . . . . . . . . . . . . . . 2-65 2.3.2 Doses Due To Radiciodines And Particulates.... 2-66 2.3.2.1 Cumulation Of Doses......................... 2-66 2 . 3 . 2 . 2 Proj ection Of Doses . . . . . . . . . . . . . . . . . . . . . . . . . 2-78 2.4 Gaseous Radwaste System......................... 2-117 2.4.1 BV-1 Gaseous Radvaste System Cwgents. . . . . . . 2-118 2.4.2 BV-2 Gaseous Radwaste System (1rponents. . . . . . . 2-119 3.0 RADIOLO3ICAL EtWIRCNGNTAL FCNI'IORIl0 PROGRAM. . . . . . . 3-1 4.0 INFORMATION RELATED 'IO 40 CFR 190. . . . . . . . . . . . . . . . . . . 4-1 5.O SITE BOUNDARY FOR GASEOUS AND LIQUID EFFLUENTS. . . . . . 5-1 Appendix A Surmary Of Dispersion Calculational Procedures. . . . . . A-1 Apperniix B Inputs To Ctmputer Cbdes For Generation Of Source Terms........................................ B-1 l
Appendix C ODCM Controls....................................... C-1 j Agadh D Bases For ODCM Ox1trols............................. D-1 Appendix E Annual Reports...................................... E-1 k Appendix F CDCM Control Procedure Matrix. . . . . . . . . . . . . . . . . . . . . . F-1 O ii ISSUE 3 Revision 1
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?BV-li nCe 2'ODCM- ,
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TITLE [.' h.-. [n, . .. - !' , LIQUID EFFLUENT TABLESl r , < O< g ] 1-12 i p 1.1-la i: BV-1; Liquid Source Term.................'............. e 1.1-1b- 1BV-2 Liquid Source Term...............;......'........ 1-13 l< ,
$ 2- la - 3BV-1IRecirculation' Times Required Before"Sampli'ng.Of.
Liquid Discharge' Tanks............................... 1 .. ,
- 1.2-lbi :BV-2. Recirculation Times Required Before-Sampling'Of' 1 + Liquid Discharge'T6nks...... ]
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I' W ;1.3-1 lA y Values For M Adult ~For:The Beaver. Valley l Site... i1-24 0 (GASEOUS EFFLUENT TABLESL
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L BV-1; Radionuc'. ide - Mix i For Gaseous Ef fluents. . . . . . . . . . 2-29 -- j L L2.1-laL 2-30 ! L2.1-1b .BV-2.Radionuetide Mix For Gaseous Effluents.......... 2.1-2a: BV-1 Monitor: Detector' Efficiencies................... 2-31 l. L 2.1-2b- BV-2 Monitor Detector Efficiencies................... 2-32 c' ,
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'2.2-1= : Modes;Of Ganeous Release From Beaver. Valley Site L Vents For!Ioplementation ofL10.CFR-20 And-10'CFR 50.. 2-45 2.2-2a.
"V-1 Ra'dior.uclide Mix' foe Gaseous . Ef fluents. . . . . . . . . .
.2-46 l ~
2-47 l 2.2--25 L , BV-2 Radienuclide. Mix For Gaseous Effluents..........
; Distances Of; Limiting Maximum Individual. Receptors-L-(
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- To: Release Points For Annual X/0 Values..............
2 E ANNUAL" AVERAGE.X/0' VALUES.FOR CONTINU0US RELEASES (SPECIAL DISTANCES
'AND CONTROL LOCATIONS) 2-49
"} 2.214U,
- 2.2-5
;BV-17 And 2 Containment Vents (Ground Release)........
BV-1-And 2 Ventilation Vents (Ground Release)........ 2-50 2.2-6 BV-1 And 2 Process Vent (Elev'ated. Release)........... 2-51 c2.2-71 1BV-1 And 2 Turbine Building Vents (Ground Release)... 2-52 l 2-53 BV-2 Decontamination Building Vent-(Ground Release).. 1 72.2-8 2-54 l 2.219 .BV-2-Vaste Gas Storage Vault. Vent (Gt;ound helease)...
'2.2-10i BV-2 Condensate Polishing Building (Ground Release).. 2-55 i 4 4
DOSE FACTORS AND DOSE PARAMETERS FOR GASEOUS EFFLUENTS ) .. x
- - '2'.2-111 Dose Factors'For Noble Gases And Daughters........... 2-56 '
- 2.2-12 ' Dose Parameters For Finite' Elevated Plumes, Beaver l Valley-Site.......................................... 2-57 l l 2-58 j p 2.2-13 PyValuesForAChildFor-TheBeaverValleySite....
L MODES OF GASEOUS' RELEASES l L'
'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 V:
ISSUE 3 '" lii Revision 1 o j
'BV-1 end 2 ODCM LIST OF TABLES
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TITLE- Pl.GE NO. TABLE NO.
-R VALUES FOR BEAVER VALLEY SITE 2-80 2.3-2 Inhalation - Adult...................................
2-81 2.3-3 Inhalation - Teen.................................... Inhalation - Child................................... 2-82
-2.3-4 Inhalation - Infant.................................. 2-83 2.3-5 2-84 2.3-6 Ground...............................................
2-85 2.3-7 Vegetation - Adult................................... Vegetation - Teen.................................... 2-86 2.3-8 Vegetation - Child................................... 2-87 2.3-9 2-88 2.3-10 Heat - Adult......................................... Heat - Teen.......................................... 2-89 2.3-11 Heat - Chi 1d......................................... 2-90 2.3-12 Coy Milk - Adult..................................... 2-91 2.3-13 Cov Milk - Teen...................................... 2-92 2.3-14 2-93 2.3-15 Cow Milk - Chi 1d...................................... Cow Milk - Infant.................................... 2-94 2.3-16 Goat Hilk - Adult.................................... 2-95 2.3-17 Goat Hilk - Teen..................................... 2-96 2.3-18 Goat Milk - Child........ ........................... 2-97 2.3-19 Goat Milk - Infant................................... 2-98 2.3-20 ANNUAL AVERAGE D/0 VALUES FOR CONTINUOUS RELEASES (CONTROL LOCATIONS) BV-1 And 2 Process Vent (Elevated Release)........... 2-99 - 2.3-21 BV-1 And 2 Containment Vents (Ground Release)........ 2-100 2.3-22 BV-1-And 2 Ventilation Vents (Ground Release)........ 2-101 2.3-23 BV-1 And 2 Turbine Building Vents (Ground Release)... 2-102 2.3-24 BV-2 Condensate Polishing Building (Ground Release).. 2-103 2.3-25 BV-2 Decontamination Building Vent (Ground Release).. 2-104 2.3-26 BV-2 Vaste Gas Storage Vault Vent (Ground Release). . 2-105 2.3-27 ANNUAL AVERAGE D/0 VALUES FOR CONTINU0US RELEASES (SPECIAL DISTANCES) BV-1 And 2 Process Vent (Elevated Release)........... 2-106 2.3-28 BV-1 And 2 Containment Vents (Ground Release)........ 2-107 2.3-29 BV-1 And 2 Ventilation Vents (Ground Release)...... . 2-108 2.3-30 BV-1 And 2 Turbine Building Vents (Ground Release)... 2-109 2.3-31 BV-2 Condensate Polishing Building (Ground Release).. 2-110 2.3-32 BV-2 Decontamination Building Vent (Ground Release).. 2-111 2.3-33 BV-2 Veste-Gas Storage Vault Vent (Ground Release)... 2-112 2.3-34 SHORT TERM X/0 VALUES FOR BATCH RELEASES 2.3-35 BV-1 And 2 Containment Vents (Ground Release)........ 2-113 BV-1 And 2 Ventilation Vents (Ground Release)........ 2-114 2.3-36 BV-1 And 2 Process Vent (Elevated Release)........... 2-115 2.3-37 BV-1 And 2 Process Vent (Elevated Release)........... 2-116 2.3-38 e iv ISSUE 3 Revision 1
BV-1 cnd 2 ODCM LIST OF TABLES. TABLE NO. TITLE PAGE NO. ENVIRONMENTAL MONITORING-1 3.0-1. Rediological Environmental Monitoring Program........ 3-4
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DISPERSION CALCULATION PROCEDURES A1 BV-1 And 2 Release Condition. .................... A-3
-INPUTS TO COMPUTER CODES FOR CENERATIOh ~J (CE TERMS .,
Bila Inputs To GALE Code For Generati i 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. 4 .......................... B-3 B:2a Inputs To SVEC GAS 1BB Code For Generation Of BV-1 Gaseous Source Term Mixes............................ B-4
'B:2b Inputs To SVEC GAS 1BB Code For Generation of BV-2 Gaseous Source Term Mixes............................ B-5 ODCM CONTROLS FOR INSTRUMENTATION, SAMPLING, AND ANALYSIS REQUIREMENTS !
C:1.1 Operational Mod s.................................... C-5 ry C:1.2 Frequency Notation................................... C-6 i )
"' C 3.3-12. Radioactive Liquid Effluent Monitoring Instrumentation C-10 C:4.3-12 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements............................ C-12 C:3.3-13 Radioactive Gaseous Effluent Monitoring Instrumentation C-19 C 4.3-13 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements............................ C-25 C:4.11-1 Radioactive Liquid Vaste Sampling And Analysis Program C-31 C:4.11-2 Radioactive Gaseous 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 i!0RMAT FOR ANNUAL REPORT
.E:6.9-1 Environmental Radiological Monitoring Program Summary E-2 l
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v ISSUE 3 Revision 1
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.BV-1 cnd 2 ODCM LIST OF TABLES ;
TITLE PAGE NO. Gl TABLE NO. i ODCM CONTROLS PROCEDURE MATRIX i F:la BV-1 Liquid Effluent Monitor Surveillances................. F-2
'1 F:1b BV-2 Liquid Effluent Monitor Surveillances................. F-3 {
l F:2a BV-1 Gaseous Effluent Monitor Surveillances................ F-4 1 F:2b BV-2 Gaseous Effluent Monitor Surveillances................
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F-5 ! I F:3 BV-1 and 2 Liquid Effluent Concentration Surveillances..... F-7 i F:4 BV-1 and 2 Liquid Effluent Dose Surveillances.............. F-8 M F:5 BV-1 and 2 Liquid Effluent Treatment Surveillances......... F-9 1 F:6 BV-1 and 2 Gaseous Ef_ fluent Dose Surveillances............. F-10 F:7 -BV-1 and 2 Gaseous Effluent iir Dose Surveillances......... F-11 F-12 j F:8 BV-1 and 2 Gaseous Effluent Particulate and Iodine......... i Dose Surveillances............... .............. F:9 BV-1 and 2 Gaseous Effluent Treatment Surveillances........ F-13 ei { 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 l F 13 BV-1 and 2 Interlaboratory Comparison Program.............. F-17 l
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1 vi ISSUE 3 Revision 1
O' ' BV-1. F.nd '2 : ODCM
-LIST OF FIGURES
- FIGURE M). TITLE PAGE NO.
;fm, i
V)- LIOUID EFFLUDrr FIGURES . i ( 1 l
- l'. 4 -1. BV-1 Liquid Radwaste System . . .'. . . . . . . . . . . . . . . . . . . . . . . . . . 1-30 l 1.4-2 'BV-2 Liquid Radwaste System.............................. ,1-31 l'.4-3 BV-1 and 2 Liquid Effluent Release Points ................ 1-32 anSs0cS EFFwEur FIGURES 2.4-1 BV-1 And 2 Gaseous Radwaste System...............,........ 2-121 2.4-2 BVal And 2 Gaseous Effluent Release Points ................ 2-122 RADIOIOGIChL E1NIR0ROTTAL MONITORING PROGRAM FIGURES .i s
3.0-l' Air Sanpling Iocaticns '. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-8 ; 3.0-2 Tm Locations............................................ 3-9 1 3.0-3 Shoreline Sediment, Surface Water, And Drinking l Water Sanpling Iccaticos . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-11 ) 3.0-4 Milk Ramn14 ng Iccaticms . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 MS 3.0-5 Fv0Ca % Sanpling Iccations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-13 3.0-6 Fish Sanpling Iccations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 ) I StrE saatoav FIGURES l' Site M wviary For Gaseous And Liquid Effluents ........... 5-l'
. -p J
/
1 t[u vil ISSUE 3 . Revision 4 V:
r *
- BV-1 Gnd 2 ODCM ODCM EOUATION CROSS unwnTCS FOR LIOUID EFFU2fTrS I
i FRCM: 'IO: FRCH: PREVIOUS CURRENT PREVIOUS BV-1 ODCN BV-1 AND 2 CDO4 BV-2 ODCM ISSUE 2, REV. 2 ISSU2 3 ISSUE 1, REV. 3-AND EARLTER AND, IATER AND EARLIER 1.1-1 1.1 (1) -1 -- 1.1s2 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. 3,- 6 1.1 (2) -7 1.1-7 1.1 (2) -8 1.1-8 1.2-1 1.2-1 1.2-1 .3 1.2-2 1.2-2 1.2-2 ff/tg -- 1.2-3 -- 1.2-3 1.2-4 2.2-3 1.2-4 1.2-5 1.2-4 1.3.1 1.3-1 1.3-1 Thru Thru Thru 1.3-8 1.3-8 1.3-8 O viii ISSUE 3 Revision 5
1
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% ca :
# Ot.
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~ BV-1-cnd 2 ODCMD
~ ~ ~
g _' , l
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'. 0DCM EQUATION CROSS REFERENCE!..
- 'FOR GASEOUS EFFLUENTS:
y FROM:: -L TO: ' :FROM:-
! PREVIOUS': CURRE!n PREVIOUS
.BV' f ODCM . .BV-1 AND 2"0DCM: BV-2 ODCM.
- ISSUE,2,- REV.-2. 5
- ISSUE 3: : ISSUE 1,LREV.;3
'AND EARLIERL :AND LATER- 'AND EARLIER
'g i 2.1- 1( .
2.1(1)hlh -- 2.1(1)-2/ 2 .1- 2 '.-
.211-3 m.2.1(1)-3 ~
!,2.1-41 , 2.1(1)-4' .--.
,.2.1-5 s
.2.1(1)-5' .--
.2.1-6' 2.1(1)-6 --.
.2.1-7: ~
'2.1(1) '
, 2.1-8 ~2.1(1)-8 --
E w- , 2.1(2)-1. :2.1-13
' ~
-- 2.1(2) 2.1-2'
-.- 7.1(2)i3; :2.1-3
'N -- '2.1(2)-4. 21-4
'--- 2.1(2)-5j 2.1-5' L ,
2.1-6
--- 2.1(2) ~
-- -2:1(2)-7' ' 2 ;.1-7, - 1=
--- .2.1(2)-81 '2.1-8 L-
'2 1-9 2.1-9" L 2.1-9 L- '
Thru-
~
. .- Thru -..Thru '
,< ;2.1-16 2.1-16. 2.1-16 l '2.1-17 -" T2.1(1)'-17 ---
'2.1-18. .
2.1(1)-.18
. - 2.1-19. 2.1(1)-19 --
2.1-20'- .2.1(1) --
- - . - 2.1(2)-17 2.1-17.
-. 2.1(2)-18 2.1-18
-- 2.1(2)-19 2.1-19
-- 2.1(2)-20 2.1-20
-2.1-21 2.1-21 2.1-21 Thru Thru Thru
'2.1-24 2.1-24 2.1-24 l
2.2-1E 2.2-1 2.2-1 Thru;
.Thru- Thru 2.2-14.- 2.2-14 2.2-14 2.3-1 2.3-1. 2.3-1 Thru: Thru: Thru
'2.3-36' 2.3-36 2.3-36 I
,~ .
I
-ix ISSUE 3 Revision 1 .x
c: BV-1 ond 2 ODCM ODCM TABLE CROSS REFERENCE FOR LIQUID EFFLUENTS FROM: TO: FROM: PREVIOUS CURRENT PREVIOUS BV-1 ODCH BV-1 AND 2 ODCM BV-2 ODCM ISSUE 2, REV. 2 . ISSUE 3 ISSUE 1, REV. 3 AND EARLIER AND LATER AND FJLRLIER 1.1-1 1.1-la --
-- 1.1-1b 1.1-1 1.2-1 1.2-la --
-- 1.2-1b 1.2-1 1.3-1 1.3-1 1.3-1 ,
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x ISSUE 3 Revision 1 ;
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~ODCM TABLE' CROSS REFERENCE b'? ,,
l'it9 . .
- FOR GASEOUS EFFLUENTS
$._f: R l .' ' FROM:
?
' TO: ' FRON:-
g 1 PREVIOUS . e i F -- :-CURRENT . PREVIOUS [ - BV ODCM ' .BV-1 AND 2 ODCM.c BV-2 ODCMi ? ISSUE ~ 2, REV.' . 2 - / ISSUE 3"_' . ISSUE 1,'REV.:3f AND EARLIER ~: --AND LATER1 .AND EARLIER-2.'l-12: > L 2.1-Ir i: -- y .e ; .. ' 2.1-1b- 2'.1-1
;2.1-2~ L2.1-2a --
l: ; .- . -2.1-2bi ' 2.1-2! x 2.2-1: 2.2-1 :2.2 l 2.2-2 2.2-2a -- e. 1 - - - 2.2-2b 2.2-2 L 2.2-3 '2.2-3 2.2-3. Thru 1Thru Thru-2.2-13 2.2-13~ 2.2 l- 2.3-1 2'.3-1 2.3-1 h Thru . 7Thru Thru. .,
=2.3-34
- 2. 3-34 ,
. 2. 3-34 '-
bO 'V A-2 ~2.3-35 A-2
..' A-3 2.3-36 A-3
.~ A-4 . ^2.3-37. A-4'
- A 2.3-38 A-5' ,
- 1 i
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l 1 i l i l-1 i i l. I 0 ? l l-l- I
, l L. JF
- i. ,
l;n , K- > xi- ISSUE 3 I7 .
' Revision 1 ;
's . w- ! b.i 1 u j
U BV-1 cnd 2 ODCM ODCM TABLE CROSS REFERENCE FOR ODCM AFFENDICES , 1 j FROM: TO: FROM: FREVIOUS CURRENT FREVIOUS
\
l BV-1 ODCM BV-1 AND-2 ODCM BV-2 ODCM ) ISSUE 2, REV. 2 ISSUE 3 ISSUE 1, REV. 3 ) i AND EARLIER AND LATER AND EARLIER A-1 A:1 A-1 f
-(Unnumbered) B:la --
-- B:1b (Unnumbered)
(Unnumbered) B:2a --
-- B:2b (Unnumbered)
-- C:1.1 --
-- C:1.2 --
-- C:3.3-12 --
-- C:4.3-12 --
-- C:3.3-13 --
-- C 4.3-13 --
-- C:4.11-1 --
-- C:4.11-2 , --
-- C:3.12-1 --
-- C: 3.12-2 --
-- C:4.12-1 --
-- E:6.9-1 --
-- F:la --
-- Filb --
l
-- F:2a --
-- F:2b --
l -- F:3 --
-- F:4 --
-- F:5 -- 15
-- F:6- --
l -- F:7 -- l -- F:8 -- j
-- F:9 --
l
-- F:10 --
- i. -- F:11 --
-- F 12 --
-- F:13 --
O xii ISSUE 3 Revision 1
E. . t , BV-1-r_nd 2 ODCM PREFACE O
- U L This - OFFSITE - DOSE CAICOIATION MANUAL (ODCM) provides the information and nethodologies to be used by Beaver Valley Power Station thit 1 and Unit 2 (BV-1)
- and (BV-2) to assure conpliance with the Administrative Ctutrols Secticn of the operating- Technical Specificaticris. They are intended to show compliance with 10 CFR 20.106 or 10 CFR 20.1302 as appropriate,10 CFR 50.36a, Appendix I of 10 Cm 50, and 40 CFR 190. {
'Ihis ODCM is based cn the following thited. States Nuclear Regulatory 0:mnission j (USNRC) Amits: I
- NUREG-0472, Draft 7 for Rev. 3, September,1982, Standard Radiological Effluent Technical Specifications For PWRs.
- NURB3-0133, October, 1978, Preparaticn Of Radiological Effluent' Technical )
Specifications For Nuclear Power Plants.
- Generic letter 89-01, January. 31, 1989, Inplementaticn Of Pivgicamatic Controls ,
For Radiological Effluent Technical Specifications In The Administrative j Controls Section Of The Tcebnical Specifications And The Relocaticn Of l Procedural Details Of REI'S To The CDCM Or % The PCP.
- NUREG-1301, : April, 1991, Offsite Dose Calculaticn Marnaal G WFe: Standard Radiological Effluent Controls For Pressurized Water Reactors, Generic letter 89-01, Supplement No. 1.
. .Other miscellaneous inputs from the.USNRC.
Specific plant procedures for inplementaticn of this manual are ' included in various site manuals and documents. Procedures from the following manuals and documents are utilized by the operating staff to assure ccupliance with Technical
~
Specificaticos and the Appendix C OCNIROLS of the ODCM:
- Health Physics Manual (BVPS-HIM) ,
- Radiological Engineering Administrative Manual (REAM) .$/g I
- Environmental Program Manual (EPM)
- Operating Manuals (CN)
- Maintenance surveillance Procedures (MSP)
- Operational Surveillance Tests (OST)
The ODCN has been prepared as generically as possible in order to minimize the need'for future versions. However, scme changes to the ODCM may be necessary in the future. Any such changes will be properly prepared, reviewed, and approved as indicated in the Administrative Ctntrol Sectico of the Technical Specifications. An implementaticn procedure for centrol of the ODO4 is included in the REAM. In summary, any ODCM changes will be properly justified to ensure that ODO4 changes will maintain the level of radioactive effluent cnitrol required by 10 CFR 20.106 or 10 CFR 20.1302 as apprcpriate, 40 CFR Part 190,10 CFil 50.36a and Appendix I to 10 CFR 50 and not adversely inpact the accuracy or reliability of effluent dose, , or setpoint calculatien. i U 1 xiii ISSUE 3 i Revision 4
BV-1 Ond 2 ODCM
-HISTORY OF ODCM CHA?TE9 (1) BV-1 ODCN Issue 1 (Effective January. 1984)
This is the initial issue of the BV-1 ODCN, as prepared for inplerantation of the . Radiological Effluent Technical Specifications sREIS). Implementation of this manual was wmcasurate with Aiurdent No. 66 to the Unit 1 Technical Specificatians as approved by the NRC cn i March 28, 1983. (2) BV-l' ODCM, Issue 1. Revision 1 (Effective October,1984) A description of the changes that were implemented with this revision are as follows:
- Table 1.3-1 was revised to include liquid dose factors for nuclides presently identified at BVPS and not included in the original table.
- Equations 2.1-19 and 2.1-22 were revised as approved at RSC Meeting No. BVPS-RSC-1-84 cn January 31, 1984. The equations were revised to clarify flow rate terminology.
Secticn 2.2.2 was revised to delete the food and ground pathways for gaseous dose rate calculations of I-131 triti'2n, and radianuclides in particulate fonn with half lives greater than 8 days.
- Table 2.2-13 was revised to include 7 organs rather than cnly the maximum organ. Also, the receptor was changed fran infant to child, and addition /deletian of nuclides to be consistent with the Technical Specifications and nuclides identified at BV-1.
(3) BV-1 ODCN, Issue 1 Revision 2 (Effective July, 1986) A description of the changes that were implemented with this revision are as follows:
- Provide a flow based monitor setpoint adjustment factor in Sectica 1.1.2. This change makes Section 1.1.2 consistent with Section 1.1.1 and current procedures.
Revise the 31-day dose projectica limits and methodology in Sections 1.3.2, 2.3.1.2, and 2.3.2.2. This change corrected the 31-day dose projecticn limits and changed the dose projection methodology to be consistent with proposed software. Revise the Gaseous Effluent Monitor Setpoints in Sections 2.1.1 and 2.1.2. They were revised due to pressure corrections determined for the detectors, changes in isotcpic literature, and the addition of SPING Channel 5 alternate nonitor data. The calculations supporting this item are cantained in Calculaticn Packages ERS-SFL-85-031 and ERS-ATL-86-008. xiv ISSUE 3
*1 l Revision 1 t _ _ _ . _ _ _ _ _ i
g- . 1 BV-1 and 2 0DCH. [. .
-(4)'* BV-1 ODCM, Issue 2, (Effective July, 1987)
BV-2 ODCM, Issue 1, Revision 1 (Effective July,' 1987) fT. LQ[ With-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 ODCHs which address site dose rate limits and meet regulatory requirements. -Note that due to the scope'of the revisions to the Unit-.1'0DCM, it.was re-issued as Issue 2.
Also,:for clarity,.the draft BV-2 :ODCH previously submitted'tb.the NRC was regarded as Issue 1- (historical) and operation of BV-2 beran vith
. Issue 1, Revision 1 of the BV-2 ODCM.
*A shared liquid radvaste system, permitting mixing of vaste for
; processing, the sharing of dilution water, and the' apportionment of doce according to NUREG-0133 va's incorporated into both'0DCMs.
' A shared elevated- gaseous radvaste system, permitting the aixing of-gaseous radvaste and the apportionment of dose, according to NUREG-0133 was, incorporated into both ODCMs.
'* Separate ground level gaseous releases, were maintained. The BV-1 ODCM was updated to incorporate.the BV-2 five year meteorology base. Gaseous source terms were revised to'that calculated for BV-1 in the BV-2 FSAR, and terms vere added for calculation of a turbine building release.
, {Mj '
- The gaseous effluent monitor alarm setpoints of both ODCMs were revised as required by revisions' to meteorology, source terms, monitor efficiencies, and revised percentages of site dose rate limits.
- Formal' justification vas 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 fe. "T" is 16 (i.e., 960 minutes /
60 minutes = 16). (5) -BV-1 ODCM, Issue 2, Revision 1 (Effective December, 1987) i BV-2 ODCM, Issue 1, Revision 2 (Effective December, 1987) Sections 2.1.3 and 2.1.4 of both ODCHs were changed to delete a note concerning noble gas nuclides as requested by a NRC letter dated l July 14, 1987 titled Beaver Valley Unit 2 - Offsite Dose Calculation ' l Nanual, ODCM (TAC 63996). (6) BV-1 ODCM, Issue 2, Revision 2 (Effective June,1989)
- BV-2 ODCM, Issue 1, Revision 3 (Ef fective June,1989) l
- A description of the changes that were implemented with this revision are as follows
..O
- Both ODCHs were revised for addition of Sections 1.4 and 2.4. This addition gives a description of and includes flow diagrams of the Liquid f;V Radvaste System and the Gaseous Radvaste System. (See justification 1) !
xv ISSUE 3 Revision 1 L
F BV-1 end 2 ODCM
- Correct the foll'oving typos to BV-1 ODCM Equation 1.1-8:
A. Shnv differentiation between the two f's. (See Justfrication 1) . B.. Add the division sign. (See Justification 1)
- Re-define F in equation 1.3-1 of both ODCMs, as allcaed by the ,
k NRC. (See Justification 1) i
- 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-l'0DCM equation 1.3-8, add a division sign between the brackets. (See' Justification 1) { C. Add'the words "from each reactor unit" to five places (Sections 1.3.1, 1.3.2, 2.3.1.1, 2.3.1.2, and 2.3.2.2) of both ODCMs. This ensures compliance with the current requirements of the Technical Specifications. (See Justification 2) D. Equation 2.1-20 of both ODCMs, change the HHSP to HSP multiplier from 0.70 to 0.33. (See Justification 1) E. Equation 2.1-24 of botS ODCMs, change the HHSP to HSP multiplier from 0.70 to 0.33. (See Justification 1) F. Correct punctuation in Section 2.3.2.1 of the BV-1 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) i
- Add Reference (7) to Section 2 of the BV-1 ODCH. (See Justification 3) e
- Add the words "from the site" to Section 2.2.2 of both ODCMs. This ensures compliance with the current requirements of the Technical Specifications. (See Justification 2)
- Revise BV-1 ODCM Table 2.2-2 to change the particulate and iodine radionuclide mix for the Unit i Ventilation Vent and to correct a typo for Xe-135m in the Containment Vacuum Pumps. (See Justification 3)
- Provide re-verified P gT values for the Beaver Valley site in Table 2.2-13 of both ODCMs. (See Justification 1)
- Correct the definition forODCMs.the t f(value in the cov-meat pathway in Section 2.3.2.1 of both See Justification 1)
- Provide re-verified R values for the Beaver Valley site in Tables 2.3-2 through 2.3-20 of both ODCMs. (See Justification 1)
- Change the particulate and iodine release fractions in Appendix B of the BV-1 ODCM. (See Justification 3) xvi ISSUE 3 Revision 1 l I
BV-1 and 2 ODCM The justification used for Change (6) to the ODCMs are as follows:
/ \
V 1. A letter dated March 2, 1989 (from the NRC) was received by Duquesne Light regarding acceptance of th_e 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 concerr,'s are considered typos or additions and in one way impact any of the calculations currently being j 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 i methodology. These R values (along with all other ODCM R values) were ) re-validated VIA Calculation Package No. ERS-ATL-89-014. The results i of this package showed that the R values for the three aforementioned l pathvays were in error. Since the R values in error do not involve the controlling receptor for gaseous release (i.e.; the controlling receptor is VIA the Inhalation, Ground, and Vegetation pathways, not the pathways subject to error) than these chr,nges to the ODCM will not adversely impact the accuracy or relialility of effluent dose calculations. , l
- 2. As requested by DLC letters ND3NSM:3431, ND1NSM:3522, and ND1NSM:3652, Technical Specifications were required to be verified in all plant
.g3 inplementing procedures. As part of this effort, wording errors / typos i ; vere identified in various sections of the ODCM. This revision
" corrects the anomalies identified during the verification effort.
- 3. As delineated in letter ND1SHP:776, dated February 12, 1988 (BVPS-1 ODCM Table 2.2-2, Appendix B) a series of apparent discrepancies were identified between ODCM Table 2.2-2 and similar tables of the BVPS-2 FSAR. Evaluation showed that apparent credit was given for continuous filtration of SLCRS releases which is invalid at Unit 1. However, the calculation package on which the BVPS-2 FSAR expected release tables are based, is correct (i.e.: no credit was taken for routine filtration for Unit i release.). Except for revising the ODCH, no further corrective action is necessary because the particulates and iodines in the ODCM vere not used for gaseous effluent alarm setpoint.
Therefore, this change docs not adversely impact the accuracy or reliability of setpaint calculations. (7) BV-1 and 2 ODCM, Is_sae 3 (Effective August, 1995) The combined ODCH, as implemented by ISSUE 3, contains the following-changes:
" Prior to ISSUE 3, BV-1 and BV-2 had individual ODCMs that were generically equal. In an effort to simplify the implementing documents, the ODCMs have been combined. This merger of the individual ODCMs vill maintain the level of radioactive effluent controlrequiredby10CFRs/9g 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part
[]
\ m/ 50. Also, this merger vill not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
! xvii ISSUE 3 Revision 1
7 BV-1 and 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 2 SUS-R0102)
- Revised Section 1.0 (Liquid Effluents) and Section 2.0 (Gaseous Effluents) to merge the BV-1 alarm setpoint calculations with the BV-2 alarm setpoint calculations. For all practical purposes, when Tables, Figures, and Equations were t reasferred to the combined ODCM, the numbering was kept generically equal. The only exception to this are as follows:
- If a table was contained in both 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 ODCH. These tables are now numbered 1.1-la and 1.1-1b denoting BV-1 and BV-2 respectively. A cross reference for ODCM tables is provided in the Table Of Contents.
- If an equation was contained in both ODCMs, but each had data specific to BV-1 or BV-2, then a (1) or (2) was added to the equation. For example, Equation 1.1-1 was previously included in the BV-1 ODCM and the BV-2 ODCH. 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 providad in the Table Of Contents. ! I
- Revised Section 3.0 (Radiological Environmental Monitoring Program) to i list the program requirements from the Radiological Assessment Branch !
Technical Position (Revision 1, 1979). l
- 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, Supp ? ment No. 1 (NUREG-1301).
- Revised Appendix A to transfer the Batch Release dispersion parameters from Appendix A (Tables A-2 through A-5) to Section 2.3 (Taoles 2.3-35 through 2.3-38). This revision was done for clarification. For example, all dispersion parameters are now included in one area of the ODCM.
i
- Added Appendix C: Procedural details for the Radiological Effluent Technical Specifications (RETS) were transferred from the Technical Specifications to Appendix C of the ODCM per Generic Letter 89-01 and Generic Letter 89-01, Supplement No. 1 (NUREG 1301).
O' xviii ISSUE 3 Revision 1
r BV-1 and 2 ODCH This Appendix also includes selected Definitions and Tables as delineated in the Technical Specifications (Section 1) and selected Applicability and Surveillance Requirement statements as delineated in _V_[] - 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 ODCM Controls were transferred ~from the Bases Section of the Technical Specifications to Appendix D of the ODCM per Generic Letter 89-01.
- Added Appendix E: The Annual Radioactive Effluent Release Report and the Annual Radiological Environmental Report reporting requirements are listed in this appendix to the ODCH.
- There are three differences- (i.e.,- non-editorial changes) in this ODCM revision' vhen compared to the previous BV-1 and BV-2 Technical Specifications. These are the only changa that are identified by revision bars. These differences are as follows:
First Difference (LLD Definition Clarification): There was a sentence removed in the LLD Standard Deviation Definitions delineated in Appendix C Tables 4.11-1 and 4.11-2. This sentence stated: "In calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., potassium in milk samples)." It should be noted that this sentence was removed by justification of NUREG-0472, Rev. 2 (i.e., this revision to the NUREG removed the sentence from Tables 4.11-1 and 4.11-2). It should be noted that at BV-1 and 2, there are no other radionuclides normally present in effluent samples. Hovover', there is applicability to environmental LLD calculations due to the existence of other radionuclides in i environmental 'semples. This sentence, therefore, vill not be removed from Appendix C, Table 4.12-1. 8 Removal of the sentence from Appendix C, Tables 4.11-1 and 4.11-2 does not adversely impact the accuracy or reliability of current or past effluent LLD calculations. This change maintains the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50, and does not adversely lupact the accuracy or reliability of effluent, dose, or setpoint calculations. This change brings ODCM Appendix C, Tables 4.11-1 and 4.11-2 in generic agreement with NRC g.nidance (i.e., NUREG-0472) and industry standard. xix ISSUE 3
/'~'T Revision 1 U
i 4 BV-1 Gnd 2 ODCM - Secor.d Difference (Change From Semi-Annual Report To Annual Report: , The frequency of the Radioactive Effluent Release Report was changed l from Semi-Annual to Annual. This change is justified by Federal I 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 Cormission annually that f specifies the quantity of each of the principal radionuclides )
released to unrestricted areas in liquid and in gaseous effluents j during the previous 12 months of operation...the time between i submission of the reports must be no longer than 12 months..." This change maintains the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and , Appendix I to 10 CFR Part 50, and does not adversely impact the j 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 Nev 10 CFR 20.1003. The definition for UNRESTRICTED AREA vns modified from the definition that was in the Technical Specifications prior to transferring to the ODCH. This modification was necessary to ensure that the ODCM dose model for gaseous releases is not affected. The modification involved adding the following sentence: "For gaseous release dose calculations, the UNRESTRICTED AREA should exclude any public road, railway, or vaterway 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), { i Table 2, Col. 2 EC's. This limit vill now be referred to as the I ODCM Effluent Concentration Limit (OEC). 8 For gaseous effluents, no changes were made to implement the New 10 CFR 20. As justification, when the utility adopted the RETS (1/1/84), compliance to 10 CFR 20 shifted from the MPC concept to the Unrestricted Area Dose Rate concept. The Dose Rate concept is j the preferred method of controlling gaa,cous effluent release rate, { and vill continue to be used in-lhu of the MPC or EC concept. ) l Changing to the OEC limit for 1. quid effluents accommodates needed { operational flexibility to facilitate implementation of the Nev 10 l CFR 20 requirements. I 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 I CFR 190. The New Part 20 does not include a requirement on limiting ( radioactivity concentrations in effluents, which is less restrictive l than the Old Part 20. i xx ISSUE 3 Revision 1 i
i BV-1. c.nd ' 2 ODCM n v , (i.e.;' nov the ODCM Appendix.C
~The, basic' requirements 1 forLRETS -
! . , D,- Controls)'are~ stated in'10 CFR 50.36a. These requirements indicate '/ [ l(
. that. compliance with :the RETS i vill. keep average annual releases of radioactive material in effluents to'small.perc'entages of the limits specified,in the Old.110 CFR';20.106;f(New '10 CFR.20.1302). These requirements.alsoJindicateLLthat'coperational flexibility'is1 allowed
((with;.considerationsc for: publicohealth; and; safety)_- whichl may-temporarily result in release's higher: than'such small percentages, but still<vithin;the MPC limits' specified in'the Old 10 CFR 20.106. The MPC's relate to.an annual dose of 500 mrem.L 'Also, 10 CFR 50.36a
~
indicates.that when iusinc operational ' flexibility, lbest efforts j
- shall .be' exerted, to keep' levels ;of radioactive materials in j effluents to ALARA as set forth in 10 CFR 50 Appendix I.- )
As stated-in-the Introduction to ~ Appendix. B..of the lev 10 CFR 20,. the liquid EC's.are based on~Ean annual dose of 50 mrem. Since:at release concentration corresponding to1 a limiting dose-rate'of 5007
' mrem / year has been acceptable'as a'RETS limit for liquid effluents.
it should-not be necessary to reduc'e this. limit ~by a factor of ten. BV-1.and BV-2 has. demonstrated that the use ofcthe MPC's associated with the Old 10 CFR 20.106 has resulted in calculatcd maximum individual doses to a member of- the_ public -that are small percentages of the limits of 10 .CFR 50 Appendix I. .Therefore, the use of the OEC's, which correspond to an. annual dose of 500 mrem (i.e.; 10 times the New 10 CFR 120 EC's) should not have a negative impactLon the ability to continue to-operate within the. limits of 10 ) p- .CFR 50 Appendix I, and 40 CFR-190. V Operational flexibility is also necessary in establishing a basis: for effluent monitor ' setpoint calculations. . As previously discussed,.the.EC's stated in the Nev 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 (Nev 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 Nev 10 CFR 20 for liquid effluents maintains the level of radioactive effluent
. control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, l and Appendix I to 10 CFR Part 50, and does not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
J xxi ISSUE 3 Revision 1
e BV-1 cnd 2 ODCH
SUMMARY
Per Generic Letter 89-01, the transfer of RETS procedural details O-fulfills the goal of the USNRC Policy Statement for Technical Specification improvements. It is not .the UShTC's (or DLC's) intent to reduce the level of radioactive effluent control. Rather, the intent is to provide programmatic controls for RETS (asdelineatedinTechnicalgg Specification 6.8.6) and allow for relocation of the procedural details of the RETS to the ODCH. (8) BV-1 AND 2 ODCH, Issue 3, Revision 1 (Effective October, 1995) A description of the changes that were 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 numbeu. (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 2RMQ-R0301, 2RM0-R0303 and 2HVL-R0112 from Tables 3.3-13 and 4.3-13 (See justification 3). Added alternate system effluent flow rate measuring devices for the three gaseous effluent pathways to Tables 3.3-13 and 4.3-13 (See justification 4). Revised Surveillance Requirements 4.11.1.1.3 and 4.11.1.1.4 and notes e and g of Table 4.11-1 to clarify Turbine Building sump sampling requirements (See justification 5).
- Appendix D: Descriptive paragraphs were added at the front of the Appendix. (See justification 1)
- Appendix E: Desriptive paragraphs 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 were transferred from the Technical Specification Procedurc Matrix. (See justification 1) xxii ISSUE 3 Revision 1 l
BV-1 end 2 ODCM The justification used for change (8) to the ODCM are as follows: Y 1. These changes are considered editorial in nature. Therefore, these A],/ . -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, T CFR 50.36a, and Appendix I to 10 CFR 50. Also, removing the ,onservatism vill not adversely impact- a of effluent dose or setpoint~ j the accuracy or reliab'ility calculation.
- 3. This change ruaoves the process flow rate operability _ and surveillance requirements for BV-2. Gaseous Effluent Radiation Monitors 2kM0-R0301, 2RM0-R0303 and 2HVL-R0112 from Appendix C Tables 3.3-13 and 4.3-13. These items were removed from the ODCM by justification provided in Calculation Package Nc. ERS-ATL-90-021.
n It should be. noted that a safety analysis and a.no significant hazards evaluation were prepared and approved on this change prior
.Q 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 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 vill not adversely impact the accuracy or reliability of effluent dose or setpoint calculation. The following is a summary of the justification.
- BVPS-1 and BVPS-2 As currently using, and vill continu? 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. xxiii ISSUE 3 Revision 1 f l l I _ J
~ BV-1 end 2 ODCH
- The DLC commitment to Regulatory Guide 1.97, Rev. 2 (Section 1.8-1 of the BVPS-2 UFSAR) is not affected. This RG applies to instrumentation used during and after postulated accident conditions. These three process flow rate ins'ruments were not 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, Bev. 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 major and potentially significant paths for release of radioactive material .
during normal reactor operation, including anticipated 4 operational occurrences, should be monitored. Measurements of i effluent volume, rates of release, and specific radionuclides should be made, insofar as practical . . " As previously stater, the three process flow rate instruments are located on effluent pathways that do not have a significant source term.
- BVPS-2 UFSAR Sections 9.4.13 and 9.4.16 indicate that the building ventilation system for these three pathways are non-safety related and are not required to perform any safety-related function.
There is no effect to the Noble Gas Monitors located on these three pathways. The Noble Gas Monitors are still capable of performing their intended functions as described in BVPS-2 UFSAR Section 11.5.2.4.
- 4. This change adds alternate system effluent flovrate measuring devices for the three BV-1 Gaseous Effluent Pathways to Appendix C Tables 3.3-13 and 4.3-13. A 10 CFR 50.59 safety evaluation has concluded that no unreviewed safety question is involved by adding the alternate measuring devices to Appendix C Tables 3.3-13 and 4.3-
- 13. This conclusion is based on the following:
- There is no increase in the probability or consequences of accidents or malfunctions of equipment important to safe +v.
- There is no creation of a possiblity for an accioent or malfunction of a different type than any evaluated previously. jo
' There is no reduction in the margin of safety Also, since dis r?ange merely adds alternate measuring devices that meet the ssme su*ve.11ance requirements of the primary channel, then the changt. u nl ma.ntain the level of radioactive effluent control required by 10 CFA 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
f BV-1 and 2 ODCM-i
- 5. 'This change to the ODCM clarifies Turbine Building sump sampling k
. requirements'and clarifies effluent related actions associated with .O. 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 l- meet the intent of 'NUREG-1301 (superceeding NUREG-0472) and the l
BVPS-1 end 2 UFSAR's, then the clarification vill maintain the level i of radioactive effluent control required by 10 CFR 20.1302, 40 CFR l Part 190, 10 CFR 50.36a and Appendix I. to 10 CFR 50. Also, the j -clarifications will 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 l 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 accidenta or malfunctions of equipment important to safety.
- There is no creation. of. a possiblity for~ an accident m-malfunction of a different type than any evaluated previously.
* - There is no reduction in the margin of safety.
i (9) BV-1 and 2 ODCM, Issue 3, Revision 2 (Effective May 1997) i A description of the changes that. vere implemented with this revision are G as follows:
- Index: Editorial changes vere made for clarity. (See Justification 1)
- Section 1.0: Clarifying statements were added to Tables 1.2-la and 1.2-
- 1b to show that the recirculation times listed are based on historical recirculation rates. Figure 1.4-3.vas added to show 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 Mark 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 perforr broad leaf vegetation sampling at :he site boundary in a sector with the highest D/0 (See Justification 2).
IL D xxv ISSUE 3
'O Revision 2
g E BU-1-ond 2 ODCH
- Appendix E: Corrected typographical error on Table 6.9-1. (See LJustification 1) 4
- Appendix F: 'Added procedure detail .to Tables 11, 12 and 13. (See Justification 1)
The justification used for Change (9). to the ODCM 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 con'.rol required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a and Appendix I to 10 CFR 50. Also, the i editorial changes vill not adversely impact the accuracy or I reliability of erfluent dose or setpoint calculations.
r
- 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 showed 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. Thejustification used for Change (10) to the ODCM is as follows: i g
- This change is considered editorial in nature. The change adds an ecuivalent item that was previously located on BV-2 Technical Specification Figure 5.1-2. Sin e BV-2
)7 Technical Specification Amendment 83 removed this figure, then the gasmus release i point for the BV-2 Turbine Duilding Vent needed transferred to the ODC%
Therefore, since this change is considered editorial, the change will mi ain 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 change will not adversely L !- impact the accuracy or reliability of effluent dose or setpoint calculation. g xxvi ISSUE 3 Revision 3
~ ~
- BV-1 And 2 ODCM (11) BV-1 and 2 ODCM, Issue 3. Revisi n 4 (Effective March 1998)
A descripticn of the changes tilat were implemented with this revisicn are l'_'1 t ; as follows: 1 v !
- Index: Editorial changes were made for clarity.
- Sectica 3.0: The distances for the environnental rrcnitoring sample points were revised to shcw a nere accurate neasurement frcm the center of the Unit 1 Containrent Building. The actual sample locaticos and descripticos remain unchanged. Also, the 4 individual quadrant maps shcwing TLD locaticns were consolidated into 1 unp. This is a i Corrective Acticn to Ctx1diticn Paport CR 980353. I
- Section 4.0: Added clarifying statarents as to how doses due to radioactive effluents for MEMBERS OF THE R1BLIC conducting activities I inside the site boundary are derived and reported. This is a Corrective I Acticn to Ctnditicn Report CR 971578.
- Appendix C: Added statenents to Acticu 23 of Table 3.3-12 to clarify that batch liquid releases may also be initiated with the same Acticn needed for resum.tng the release. This is a reccmrendaticn frcm the 1997 RETS Self-Assessment. A note was also added to this table to clarify that independent signatures cn the discharge permit satisfy the requirement for "two technically qualified nembers of the Facility Staff i;x$ependently verify the release rate calculaticn..." Added Acticn 29 to RM-W-108B cn Table 3.3-13. This addition ensures consistency with ,
the other 7 continuous gaseous effluent pathway Acticos for Noble Gas l Mcnitor incperability. Added plant specific Mark Numbers for primary and alternate instrumentaticn to Tables 3.3-13 and 4.3-13 as follows: pl
\
- For Noble Gas Activity Mcnitors, RM-VS-109 Channel 5 was added as an alternate to RM-VS-101B.
RM-VS-110 Channel 5 was added as an alternate to RM-VS-107B. RM-W-109 Channel 5 was pol added as an alternate to RM-W-108B because it does not perform cn auto-isolaticn of gaseous waste decay tank release upcn upper activity alarm.
- For Particulate Activity Mcnitors, RM-VS-109 Channel 1 was added as an alternate to RM-VS-101A.
RM-VS-110 Channel 1 was added as an alternate to RM-VS-107A. RM-W-109 Channel 1 was added as an alternate to RM-G-108A. l
- Appendix E: Corrected typographical errors cn Table E:6.9-1 l
- Appendix F: Updated the procedure details for primary and alternate instrumentaticn included in Appendix C Tables 3.3-13 and 4.3-13.
Reduced the amount of detail contained in reference to the Operating Manual L-5 logs so that the positicn of the surveillance cn the logs can be changed without having a need to change the Tables in this Appendix. This is a Corrective Acticn to Ocoditicn Report CR 980129. p
)
xxvii ISSUE 3 Revision 5
BV-1 cnd 2 ODCM
'Ibe justificatica used for Change (11) to the OD04 is as follows:
- 1. These charges are considered editorial in nature. The changes either correct typographical errors or add editorial details frcm previously approved station documents. Therefore, these changes will minuin 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 alarm setpoint calculations.
(12) BV-1 and 2 ODO4 Issue 3 Revisicn 5 (Effective November 1998) A descripticn of the changes that were inplemented with this revision are as follows.
- Index: Editorial changes were made for clarity. (See Justification 1.)
- Section 1.0: Added clarificaticn for calculaticn of radianuclide concentraticn when the Post Dose Correcticn Factor is >1. (See Justification 1).
- Secticn 3.0: Added an additional site locatico for the upstream environmental surface water sample. Added additional method after collecting and ccnpositing this sanple. (See Justificaticn 2.)
- Appendix C: Revised the definiticos for MD!BER(S) OF THE PUBLIC and UNRESTRICTED AREA to ensure ccnpliance with 10 CFR 20.1003. (See Justification 1.) Added a definiticn for MEMBER (S) OF 'IEE EUBLIC to ensure ccupliance with 40 CFR 190.02(k) . (See Justificaticn 1.) Added plant specific Mark Numbers for primary and alternate instrunentaticn to Table 3.3-13 that were inadvertently cmitted ft Tange (11) to the ODO4. (See Justificatica 1.) Added clarificaticn to Table 4.11-2 as to where and when H-3 samples of Waste Gas Storage Tanks are to be obtained. 'Ihis is a 03rrective Action to Condition Report CR 981489.
(See Justificaticn 1.) Added clarificaticn to note "e" of Table 4.11-2 J as t the appropriate ventilaticn release path. This is a corrective n Acticn to CR 981490. (See Justificaticn 1.) . Cbrrected an obvious caissicn cn Table 3.12-1 to ensure that 2 TID's are used for determinaticn of Direct Radiaticn. (See Justificaticn 1.) Incorporated the appropriate changes to Table 3.12-1 that are described above for Section 3.0. (See Justificatica 2.)
- Appendix F: Added procedure details frcm the Chemistry Manual to Table
- 6. This is a Corrective Acticn to Conditicn Report CR 981488. (See Justificaticn 1.)
'Ihe justificaticns used for Change (12) to the CDQ4 are as follows:
- 1. These changes are ccnsidered editorial in nature. The changes either correct typographical errors or add editorial details frcm previously approved staticn docunents. Therefore, these changes will maintain the level of radioactive effluent ccntrol required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR 50. Also, the I editorial changes will not adversely impact the accuracy or reliability '
of effluent dose or alarm setpoint calculaticos. l
- 2. These changes involve the upstream environmental surface water sample method and sanple site. Since these changes were shown to meet the intent of NUREG-1301, and BVPS-1 and 2 UFSAR's, then the change will maintain the level of radioactive effluent ccntrol IEgaired by 10 CFR !
20.1302, 40 CFR Part 190, 10 CFR 50.36a and Appendix I to 10 CER 50. ) Also, the change will not adversely inpact the accuracy or reliability ; of effluent dose or alarm setpoint calculations. l l xxviii ISSUE 3 i Revision 5 j I l l
.BV.-1'and 2 ODCM
_ Also, a 10 CFR 10.50 safsty evaluation has. concluded'that no unreviewed
, safety questicn . is -involved by adding an additimal sanple site and I. .
sanple nothod. This cvaluaticn is based on the following. NY V e hre is no increase in the probability or casequences of accidents or malfuncticris of equipnent inportant to safety.
- There is no' creaticn of a possibility-for an accident T malfunction
(' . of.a different type than any evaluated previously. l
- l.
- There is no reducticm in the margin of safety. sik l-I r
l l 1 xxix ISSUE 3 Revision 5
O , BV-1 and 2 ODCM References for OD04 Chances
- 1. BVPS-1 and 2 UFSAR:
- BVPS-1 UFSAR Section 11.2.3; Gaseous Waste Disposal Systen
- BVPS-1 UFEAR Section 11.2.4; Liquid Waste Disposal System o BVPS-2 UFSAR Section 11.2; Liquid Waste Fhnagement Systems
- BVPS-2 UFSAR Section 11.3; Gaseous Waste Managatent Systems
- 2. Condition Reports:
a G 971578, MEMBERS OF 7HE PUBLIC Discrepancies
- G 980129, ODCM Procedure Matrix Discrepancies s
- G 980353, ER4P 2.01 Discrepancies for Envircrsnental Sanpling Iccations
- G 981488, Chemistry Related OD04 Procedures and ODCM Appendix F References llM
- G 981489, ODCM Table 4.11-2 Row. A (Waste Gas Storage Tank Discharge Tritiun)
- G 981490, ODCM Table 4.11-2 Note e, and Related Chemistry Department Procedures
- 3. DIf Calculaticn Packages:
- ERS-ATL-83-027; Liquid Waste Dose Pactor Calculaticn for HEM-RP 6.5, Issue 3 and later
- ERS-SFL-85-031; Gaseous Effluent Mcnitor Efficiency Data
- ERS-ATL-86-008; ODCM Alarm Setpoint Revisions for Gaseous Mcnitors
- ERS-HHM-87-014; Unit 1/2 CDCN Gasecus Effluent Monitor Alarm Setpoint Determinations
- ERS-ATL-87-026; BVPS-1 and BVPS-2 ODCM T Factor Justificaticn
- EPS-ATL-89-014; Verificaticn/Validaticn of CDQ4 R Values
- ERS-ATL-90-021; Justification for Removal of Technical Specificaticn Process Flowrate Measurenent Requirements for 2RIQ-RQ301, 2RMQ-RQ303 and 2HVL-RQ112
- ERS-ATL-95-006; Re-evaluaticn of TS/CDCM SR's 4.11.1.1.3, 4.11.1.1.4 and Notes e and g of TS/ODCM Table 4.11-1
- 4. 'DIf letters: l 1
- ND1SHP;776, BVPS-1 CDCM Table 2.2-2, Appendix B, Febnnry 12, 1988
- ND3N5M:3431; Technical Specificaticn Verificaticn Effort, August 11, 1988.
- NDIlG4:3522; Technical Specificaticn Verificaticn Effort Checklist, l Septenber 14, 1988. 1 xxx ISSUE 3 Revision 5
BV-1 cnd 2 ODCM o ND1NSM:3652; Technimi Specificaticn Verificaticn Effort, November 21, 1988
- NPD3SHP:3466, Self Assessment cf the Liquid and rhels Effluent Processes
[.)
%)
. at BVPS - Final Report, July 16; 1997
- NPD3SHP:2257; ODCM Liquid Waste Recirculaticm Rates, February 11, 1998
- 5. EG&G Technical Evaluaticn Reports:
- EGG-PHY-8194; TWim1 Evaluaticn Report for < the ' Evaluaticn of COCM Updated through Issue 2, Revisicn 1, Beaver Valley Power Staticn, thit 1, September 1988
- EGG-PHY-8217; Techni m1 .Evaluaticn Repott for the Evaluation of CDCM
. updated through Issue 1, Revisicn 2, Beaver Valley Power Staticn, Unit 2, j September 1988
- 6. NRC I.etters:
- Beaver Valley thit. 2 - Offsite Dose Calculatica Manual, CDCM (TAC 63996),
Atly 14,1987
- Beaver Valley thits 1 and 2 - Acmpeance of the Offsite Dose Calculaticn Manuals (TAC 93996 and 67421), March 2, 1989
- 7. NUREG's:
- NUREG 0133; Preparaticn of. Radiological Effluent Technical Specificaticn for Nuclear Power Plants ]
* . NURB3-0172; Age-Specific Radiaticn Dose Connitent Factors for a One-Year Chrcnic Intake l i
1
- NUREG-0472; Radiological Effluent Technical Specificaticn for PWR's.
- NUREG-13 ' Offsite Dose Calculaticn Manual GTanm:
i Standard i Radiologk '. Mfluent Crntrols for Pressurized Water Reactors (Generic Ietter 89-01, dupplement No.1)
- 8. Regulatory Guide:
- RG-1.109; Calculaticn of Annual Doses to Man Frcm Routine Releases of ,
Reactor Effluents for the Purpose of Evaluat3m; Ocxtpliance with 10 CFR Part 50, Appendix I. 1 f3 xxxi ISSUE 3 Revision 5
B < l BV-1~End 2 ODCH' 1
, $0$-LIQUIDEFFLUENTS '
ll , ,
\- 'BV-l'andlBV-2'u'tilize' the . concept Jof ,a ' shared' liquid radioactive vaste system according to NUREG.0133. :This. pernitsithe mixing of liquid radvaste -
for processing and allocating.of-dose due to release as defined in j Section 1.4. .In Section'1.1,' effluent monitor.setpointsLfor.a' conservative c l mix are based on the~' individual: Units' specific: parameters,1but effluent'
- monitor setpoints. for: analysis . prior to . release : permit use of 4he totalT dilution flow available at the site.
Differences:jexist between ~ setpoint presentations of 'the . radiation
' monitoring systems lof 31-1 and BV-2.- There-.is'a difference in setpoint-terminology. Where BV-1 uses HIGH oand HIGH-HIGH, the BV-2 equivalents are '
. ALERT and.HIGH. iAlso, there. is. the difference thatlBV-2 setpoints are l presented.inLuC1/ml rather:than epm as in BV-1.,:This difference is due to !
'BV-2 software whichiapplies a Econversion factor. toi the rav data'(cpm).: ,
~ Note'that thei uC1/ml- presentation 11s' technically correct .only for the t .
l specific isotopic' mix used in :the determination of-the conversion' prior.to releasefactors. vill be Therefore,._BV-2 setpoints determined on' analysis l correct'for properly' controlling dose rate, but;the indicated uCi/ml.value-I may differ from the actual value-i l i i a t LA 1-1 ISSUE 3
f , 5, , F. [% , > 9: .i
,.BV-1:endJ2.0DCM-by4 g ,
~jl;14AlarmSetpoints?
q I ' ( ' .., L1.1.1ILBV-lMonitorAlarmSetpointDe' termination
'7 s - 1This proceduref:[determinesD the monitor? HIGH-HIGHE Alarm Setpoint<that:h '
iddicates:if the:concentrationJ of. radionuclides :'in the liquid effluent
? released 5from the. site;to1 unrestricted areas; exceeds 10 times'the EC's 7
K Tspecified'inL10,CFR 20, Appendixi Bf(20'.1001-20.2401), Table 2, Column 2:. ~
. for, radionuclides ' other! ,than' l dissolved ~ or- entrained . noble gases or ,
p ,
' exceeds a concentration of 2E _41,uci/al~ for dissolved or. entrained noble l s ,
3 gases (see Reference-1.1.5).; y 19
% The' methodology ' described in SectionV1.1.1.2 is an alternatis method to
-m : bef used to ~ determine, the (RM-LV-104 or. RM-LV-116) monitor. HICH-HIGH : Alarm -
l, '
.Setpoint:(HHSP). 4The methodology in Section 1.1.1.2f may be.used for any-batch release and shall;be used'/when the respective. total # gamma activity concentration.of thel liquid effluent 1 ~ prior to dilution' exceeds 4.26E-31
'uCi/ml'and-1.49E-2e uCi/ml; This . concentration is ' equivalentto th~ei respective HRSP's derivediin' Section: 1;1.1.1 'and allows for respective
- tritium concentrations-up to 4.33E+0 uCi/ml and 1.52E+1-uCi/ml.'
1.1.1.1 :BV-1 Setpoint Determination Based On A Conservative Mix-
~
i
'The Alarm Setpoints for.the: liquid monitors should be set at'the values listed as follows:.
.BV-1 LIQUID MONITOR SETPOINTS-
~
cpm Above Background ((~
" ' Monitor: 3 HHSP. HSP R
- Liquid Waste Effluent" RM-LV-104 Tht+5 4.84E+5 3.39E+5 7N Monitor
- Laundry And.Contami- RM-LV-116 1.69E+6 1.69E46 '1.19Et6~*
nated Shower Drains.
, Monitor'-
- Component Cooling / RM-RV-100 2.57E+4 2.57E+4 1.80E+4 m . Recirculation Spray Hx a' River Vater Monitor
- Aux Feed Pump Bay RM-DA : 1.22E+4 1.22E+4 8.55E+3
- . Drain' Monitor-The'setpoints for RM-LV-104 and RM-LV-116 are based on the following conditions, however,'the setpoint basas for RM-RV-100 and RM-DA-100 can
,' - U be found:in Reference 1.1.5:
Source terms given in. Taole 1.1-la. These source terms have been generated from the computer code GALE, Revision 0 (NUREG-0017). The L . inputs to. GALE are given in Appendix B.
t
- Dilution water flow rate of 22,800 gpm - (15,000 gpm BV-1 + 7,800 gpm
- BV-2).
.
- Discharge flow rate prior to dilution of 35 r - for the Liquid Vaste Effluent Monitor (RM-LV-104).
D ' Discharge-flow-rate' prior to dilution of 15 gpm for the Laundry and , , Contaminated Shower Drains Monitor (RM-LV-116).
-/. 1-2 ISSUE 3 F
h . g.;i, W.i L+
_ ~ _ SV-1 Ond 2 ODCH The above setpoints for (RM-LV-104 and RM-LV-116) can be varied based on actual operating conditions resulting in changes in the discharge and dilution flow rates as follows: 3F [1.1(1)-1] HHSP = f where: HHSP = Honitor HIGH-HIGH Alarm Setpoint above background (nepm). 743 = Host restrictive proportionality constant based on norainal flow conditions: 743 = 4.84E+5 nepm x 35 gpm + 22,800 gpm (RM-LV-104) 1112 - 1.69E+6 ncpm 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 follovs:
- a. The liquid source terms that are representative of the " mix" of the liquid effluent vere determined. Liquid source terms are the radioactivity levels of the radionuclides in the effluent from Table 1.1-la.
- b. The fraction of the total radioactivity in the liquid effluent comprised by radionuc13de "i" (Sg ) for each individual radionuclide in the liqu'd effluent was determined as follows:
S A i [1.1(1)-2] g,IA i i where: A g = Annual release of radionuclide "i" (C1/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 ) vas t determined by: 1 C 7, F [1.1(1)-3} Sg i OEC 1 1-3 ISSUE 3 1 i l J ~
7: l BV-1 cnd 2 ODCM wheres f^~Y F. ' = Dilution water flow rate (gpm), BV-1 plus BV-2 Cooling h
~
t J- Tower Blowdown Rate (not including release through the Emergency Outfall Structure). i l
= 22,800 gpm = (15,000'gpm'BV-1 + 7,800 gpm BV-2) .l I
= Maximum acceptable discharge flow rate prior to dilution f
.(gpm).
- 35 gpm for Liquid Vaste Effluent Monitor (RM-LV-104).
15.gpm for Laundry and; Contaminated Shower Drains Monitor (RM-LV-116). OEC g = The.0DCM 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. S. = The fraction of total radioactivity attributed to g radionuclide "i", from Equation [1.1(1)-2]. 1.1.1.1.3 BV-1 Maximum Acceptable Concentration (Individual Radionuclide) The maximum acceptable < radioactivity concentration (uci/ml) of radionuclide "i" in the liquid effluent prior to dilution (C )1 was O determined by: [1.1(1)-4] Cg=S.Ct g 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 deterained by: C.R. = I CgE g [1.1(1)-5] i where: E g - Detection efficiency of the monitor forlisted If not radionuclide "i" there, from
-(cpm /uCi/ml) from Table 1.1-la.
Reference 1.1.4. 1.1.1.1.5 BV-1 Monitor HHSP The monitor HIGH-HIGH Alarm Setpoint above background (nepm) should be set at the C.R. value. Since only one tank can be released at a time, adjustment of this value is not necessary to compensate for y ' release from more than one source. 1-4 ISSUE 3
BV-1 and 2 ODCH 1.1.1.2 BV-1 Setpoint Determination Based On Analysis Prior To Release I The following method applies to liquid releases when determining the setpoint for the maximum acceptable discharge flow rate prior to dilution and the associated BIGH-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 allowable 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 allowable flow rate determined form activity concentration, the alarm setpoint vill be proportionally adjusted based upon the excess dilution factor provided. 1.1.1.2.1 BV-1 Maximum Acceptable Discharge Flow Rate The maximum acceptable discharge flow rate (f) prior to dilution (gpm) is determined by: f, F [1.1(1)-6] i C 3 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 blovdown flow from both units exiting the discharge structure (but excluding emergency outfall structure flov) when simultaneous liquid discharges are administratively prohibited. Og = Radioactivity concentration of radionuclide "i" in the liquid effluent prior to dilution (uci/ml) from analysis of the liquid effluent to be released. 1.25 - A factor to prevent spurious alarms caused by deviations in the mixture of radionuclides which affect the monitor response. OEC g = The ODCM liquid effluent concentration limit for radionuclide "i" (uCi/ml) 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. 1-5 ISSUE 3 - J
P' , y. n BV-1ctnd;2ODCM L k'. . .1.1.1.2.2- BV-1-Monitor CountLRate u r >
- The: calculated monitor _ count' rate (nepm) above background' attributed r
- -to the radionuclides (C.R.),is determined bys i y , ..
C.R. =' 1;25 I C E [1.1(1)4]
- a. 1g g ,
~
- vliere:
. E."=lTheIdetection.efficiencyof,themonitorfor:radionuclide
'g "i".(cpa/uci/ml) from Table 1.1-la. .If not listed'there,.
-from Reference l'.1.4.. ,
1125 = A factor to prevent spurious. alarms' caused by deviations in'
'the mixture of radionuclides which affect the monitor' response. 6/f5 1.1.1.2.3-'BV-l' Monitor HHSP'
!' ;The liquid effluent monitor HIGH-HIGH Alarm Setpoint.ab'ove background
-(nepm)'should be set at 'the' C.R. value.l adjusted; by any excess 3
dilution factor provided ss defined in the following equation: HHSP = C.R.' f, _- [1.1(1)-8] I where:- HHSP = Monitor HIGH-HIGH Alarm Setpoint'above background. C.R.'= CalculatedJmonitor count. rate (nepm)-from equation .- [1.1(1)-7]. f - Maximum acceptable discharge flow rate prior to dilution determined by equation {1.1(1)-6]. f' = Actual maximum discharge flow rate,to.be maintained for the discharge. The reduced value of f may-.be due to pump- y' limitations or administrative selection. I l 1 s l l-i g Ifk 1-6 ISSUE 3
- i; ,
l 4
BV-1 cnd 2 ODCM l i l l 1.1.2 BV-2 Monitor Alarm Setpoint Determination This procedure determines the monitor HIGH Alarm Setpoint that indicates j 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 CPR 20, Appendix B (20.1001-20.2401), Table 2, Column 2 for radionuclides other than dissolved or ' entrained noble gases or exceeds a 3 concentration of 2E-4 uCi/ml for dissolved or entrained noble gases (see ' Reference 1.2.6). The methodology described in Section 1.1.2.2 is an alternative method to be used to determine the (2SGC-R0100) monitor HIGH Alarm Setpoint (HSP). ' 1 The methodology in Section 1.1.2.2 may be used for any batch release and shall be used when the total gamma radioactivity concentration of the liquid; effluent prior to dilution exceeds 9.55E-4 uCi/ml. This concentration is equivalent to a monitor response and HIGH Alarm Setpoint derived in Section 1.1.2.1 and allows for a tritium concentration of up to 2.19E+0 uCi/ml. The setpoint was obtained by use of a. conversion factor of 5.09E-9 uCi/ml/ cpm determined for the nuclide~ mix (see Reference 1.2.5). q 1.1.2.1. BV-2 Setpoint Determination Based On A Conservative Mix The HIGH Alarm Setpoint for the liquid monitors should be set at the j values listed as follows: j l
'BV-2 LIQUID MONITOR SETPOINTS uCi/ml Above Background Monitor DV HSP ASP L
- Liquid Vaste Effluent 2SGC-R0100 9.84E-4 9.84E-4 6.89E-4 {
Monitor -
- Service Water Monitor 2 SUS-R0101 4.28E-5 4.28E-5 2.99E-5 f
- Service Water Monitor 2SVS-R0102 4.28E-5 4.28E-5 2.99E-5 )
I The setpoint for 2SGC-R0100 is based on the following conditions, l however, the setpoint bases for 2SVS-R0101 and 2SWS-R0102 can be found l f in Reference 1.2.6:
- Source terms given in Table 1.1-lb. 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 gpu - (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). l
' 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 1 operating conditions resulting in the discharge and diluti 'n flow rates as follows: i 1-7 ISSUE 3
7 m , g"l; BV-1 cnd 2 ODCH.: A-
>HSP j 3.50E-6.F
[1.1(2)-1]
;f.
IkE ' vheres.- ]
= Monitor HIGH Alarm Setpoint (uci/ml)'above background.
j
-HSP-o f
"3.50E-6 T= Proportionality constant' based on nominal flow conditions:-
3.50E-6 := 9.98E-4 net' uCi/ml x 80 gpm .+ 22',800 gpm F- ... Dilution water' flow rate, BV-1 plus BV-2 Cooling Tower Blowdown Rate;(gpm). f, ' Discharge flow' rate r for to dilution (gpm)..
'1.1.2.1.1 LBV-2 Mix Radionuclides-The'" mix" (radionuclides and composition):tof-the liquid effluent vas
~ determined as.followst'.
- a. The' liquid source terms.that: are'_. representative of the " mix"'of' o ,
'the liquid effluent were determined. -Liquid source terms are the radioactivity levels of the radionuclides in the effluent'from Table.l.1-1b.
- b. 'The fraction of the total ' radioactivity- in the liquid affluent-comprised' by radionuclide "i" .(Sg)- for each .individualf radionuclide in the liquid effluent was determined as:follows:
(( S ^1 [1.1(2)-2] i EA i g where: q A g = Annual release'of radionuclide "i"'(Ci/yr) in the liquid effluent from Table 1.1-1b.
-1.1.2.1.2 BV-2 Maximum Acceptable Concentration (All Radionuclides)
The maximum acceptable total radioactivity concentration (uCi/ml) of all radionuclides in the liquid effluent prior to dilution (C ) was t determined'by: i C F [1.1(2)-3] t- 3 fI i OEC , where: F = Dilution. water flow rate (gpm), BV-1 plus BV-2 Cooling Tower Blowdown Rate (not including release out through the y
'O Emergency Outfall Structure). i 1-8 ISSUE 3
BV-1 and 2 ODCH
- 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 Vaste Process Effluent Honitor (2SGC-R0100).
OEC g - The ODCH liquid effluent concentration limit for radionuclide "i" (uci/ml) from Table 1.1-1b. The OEC is set at 10 times the new 10 CFR 20, Appendix B (20.1001-20.2401) Table 2, Col. 2 EC values. 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 )1 was determined by: Cg=SgC t [1.1(2)-4] 1.1.2.1.4 BV-2 Honitor Display Value The calculated monitor Display Value (uCi/ml) above background attributed to the radionuclides, D.V., was determined by: D.V. - 5.09E-9 I CgEg [1.1(2)-5] i where: 5.09E Conversion factor (uCi/ml/ cpm), an average determined for the source term mix. Eg = Detection efficiency of the monitor for radionuclide "i" (cpm /uci/ml) from Table 1.1-1b. 1.1.2.1.5 BV-2 Honitor BSP The monitor HIGH Alarm Setpoint above background (uCi/ml) should be set at the D.V. value. t O1 i l 1-9 ISSUE 3 < a
BV-1 and 2 ODCM
' 1.1. 2.~ 2 BV-2 Setpoint Determination Based On Analysis Prior To Release A
The following method applies .to liquid releases when determining the setpoint'for the ' maximum ' acceptable discharge flov ~ rate prior to dilution and the associated HIGH Alarm Setpoint based on this flov rate for -thet Liquid Waste Effluent Monitor (2SGC-R0100) during all operational conditions.. The monitor alarm setpoint is set slightly aboveL(a factor of 1.25) the concentration reading that results from the concentration of gamma emitting radionuclides in order to avoid spurious alarms. To compensate. for; this increase in the. monitor. alarm. setpoint, the allowable discharge flow rate is reduced by_the same factor.
~
When the discharge flow rate is . limited by.the Ladvaste discharge pump-rate capacity or by administrative selection rather than the allovable flow rate determined ' form activity concentration,lthe alarm setpoint vill--be proportionally adjusted based upon the excess dilution factor provided. 6/ 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 bys F [1.1(2)-6] f, Cg 1.25 E O i OECg . where F = Dilution water flow rate, BV-1 plus BV-2 Cooling Tover Blowdown (gpm). The dilution water flow rate may include the combined cooling tower blowdown flow from both units exiting the discharge structure (but excluding emergency outfall structure flow) when simultaneous liquid discharges from both plants are administratively prohibited. Og - Radioactivity concentration of radionuclide "1" 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.
OEC g - The ODCM liquid effluent concentration limit for radionuclide "1" (uCi/ml) from Table 1.1-1b. The OEC is set at 10 times the new 10 CFR 20, Appendix B (20.1001-20.2401) Table 2, Col. 2 EC values. 'f O 1-10 ISSUE 3
BV-1 Cnd 2 ODCH 1.1.2.2.2 BV-2 Honitor Display Value ; f The calculated ' monitor Display Value (uC1/ml) above background attributed to the radionuclides (D.V.) is determined by: D.V. - (1.25) (5.09E-9) I Cg Eg [1.1(2)-7] where: Eg - The detection efficiency of the monitor for radionuclide "i" (cpm /uci/ml) from Table 1.1-1b. If not listed there, from Reference 1.2.4. 8 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 Honitor HSP i The liquid effluent monitor HIGH Alarm Setpoint above background (uci/ml) should be set at the D.V. value adjusted by any excess dilution factor provided as defined in the following equation: HSP = D.V. f, [1.1(2)-8] 9 where: HSP = Honito 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 f may be due to pump limitations or administrative selection. O 1-11 ISSUE 3
E ,., TBV-1-cnd 210DCM' TABLE 1.1-la y + IY ? i, ' BVil LIQUID-SOURCE TERM-h-f Eg _ A. t' il OEC
~
DETECTION
~'ANNbAL RELEASE. i EFFICIENCY L
(cpm /uCi/ml)**** l- ..
~NUCLIDE (Ci)** (uCi/ml)***'
Cr -t 9.00E-5 SE-3 1.18E+7' L .Mn-54 l2.00E-5" 3E-4.- 8.59E+7-L ?Fe-55 '8.00E-5: - 4 1E-3 ***** l Fe-59: 5.00E 1E-4 9.17E47
- Co-58
-7.70E-4L - 2E '
'1.16E48
-Co160J 1.00E-4. 3E-5 1.73E+8 Np-239 ' 5. 00E-5 :- ' 2E '8.49E+7-
- -Br-83 .6.00E-5' '9E-3 1.36E+6-
-1.00E 7E-5 -- *****t
.Rb-86' t Sr-89 1 2.00E-5. 8E-5 ' *****'
Sr-91' 1.00E-5' 2E-4 6.97E+7 ' Mo 3.90E-3: 2E-4 2.84Et7: Tc-99m 5.37E-3 1E-2 8.96E+7 3
-Te-127m -1.00E-5 -9E-5 4.09E+4
..Te-127 -3.00E 1E-3 . - 1.38E46' .
Te-129m'. 17.00E-5 7E-5 -.4.02E+6 .
. .- Te-129 - 5.00E 4E-3 1.12E+7 Mr -i
- I-130 2.50E-4 2E-4 3.08E+8' l'
Te-131m 9.00E-5 8E-5 1.82E+8' Te-131. 2.00E-5 8E-4 1.20E+8-lI-131 6.03E 1E-5 1.11E+8 iTe-132- 1.15E-3 9E-5 1.17E+8
-I-132 -5.38E-3 1E-3 2.56E+8
- I-133' 5.77E-2 7E-5 9.90E+7-7-134 1.00E-5 ' 4 E 2.70E+8 Cs-134 3.80E-3 9E-6 1.99E48 I-135 1.34E-2 3E-4 1.19E+8
- Cs-136 1.90E-3 6E-5 2.80E+8 j Cs-137 2.70E-3 1E-5 8.01E+7 j Ba-140 1.00E-5 8E-5 4.37E+7
-La-140 1.00E-5 9E-5 2.00E+8 H-3 1.60E+2J 1E-2 *****
All Others* 4.00E-5 .1E-7 ***** l l
- TOTAL
- 1.57E-1 1 2
i
- Excluding Tritium and Entrained Noble Cases
, ** Source Term for.(RM-LV-104 and RM-LV-116) from Reference (1.1.2)
***0DCM Effluent Concentration Limit = 10 times the EC values of Reference (1.1.3)
[ .
**** Detection' Efficiency for (RM-LV-104 and RM-LV-116) from Reference (1.1.4) y i/ : ***** Insignificant
' 1-12 ISSUE 3
c BV-1 Ond 2 ODCM TABLE 1.1-1b BV-2 LIQUID SOURCE TERM E.g O A DSTECTION-i- ,
<OEC ANNUAL RELEASE i ,I TICIENCY NUCLIDE -(Ci)*** .(uCi/ml)** (cpm /uci/~1)****
Cr 1.00E-4 5E-3 2.( /1 Mn 2.50E-5 3E 1.24d+8 1E-3 ***** Fe-55 1.30E-4 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 SE-6 ***** Sr 8.50E-7
- Sr-91 5.30E-6 2E-4 1.04E+8 Mo-99 2.30E-3 2E-4 4.47E+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 i Te-131 9.40E-6 8E-4 1.88E+8 )j
-I-131 1.00E-1 1E-5 1.96E+8 Te-132 7.80E-4 9E-5 1.76E+8 I-132 2.30E-3 1E-3 4.22E+8 I-133 6.50E-2 7E-5 1.73E+8 I-134 4.60E-6 4E-3 4.06E+8 Cs-134 3.00E-2 9E-6 3.25E+8 I-135 9.20E-3 3E-4 1.71E+8 Cs-136 3.90E-3 6E-5 4.28E+8 Cs-137 2.20E-2 1E-5 1.28E+8 Ba-140 9.30E-6 8E-5 7.50E+7 La-140 8.40E-6 9E-5 3.08E+8
- Excluding Tritium and Entrained Noble Gses ,
l
**0DCM Effluent Concentration Limit - 10 times the EC values of Reference (1.2.1)
*** Source Term for (2SGC-R0100) from Reference (1.2.3)
**** Detection Efficiency for (2SGC-R0100) from References (1.2.2) and (1.2.4)
***** Insignificant 1-13 ISSUE 3
Q
'N
' ' s
;}
BV-1 cnd:2(ODCH i
'\
- u- ,, .
- - TABLE ' 1.1-lb: (cont'inU. ,dd).
1 W LBV-2 LIQUID-SOURCZ TERM O j q< 90
- gh
+
Eg;. ( q IV DETECTION
. OEC .
. " fANNUAL'. RELEASE. 1l EFFICIENCY ~' NUCLIDE : '(C1)*** l(uci/ml)** ' (cpm /uci/ml)****' ] 1 6.00E-7 *****- u ie .Yl90 < f 7E-5 ~:: i, , Y-91mt i3.60E-6' -sl' \.2E-2 '1.59E+8 . lc i* :Y-911 4.40E26 CE-5. 3.55E+5
-2.03E+7 l .k . Y-931 - 3~00E-7.
. .2E Zr-95: -4.00E-6' '2E-4 -1'.35E+8 B
-Nb-95 -
E4;00E-6 ?3E-4': 1.33E+8 o ., Ru-103 '2.70E-6' ~ 3E- 4 1.71E+8 . I L .Ru-106. - 8 . 20E-7.- .3E-5; , ~ 2.70E-6' ***** tRh-103m: ,'6E-2l " .
- 5.65E+7 l .Rh-106? 8.20E-7 --
- l. , 'Co-141. :4.00E-6.
. 3E-4 7.75E47-E .. Ce-143 - 8.60E 2E--4 1.20E+8 Ce-144:- 2.60E 3E-5 ~1.87E+7-Pr-143- 2.30E-6 2E 1.63E+0 EPr-.144 ' .2.60E 6E-3 -3.40E+6 H-34 5.50E+2' 1E-2 *****:
l
> TOTAL * -- 2.40E-1 4 L6 l
J 1' L* Excluding Tritium and Entrained Noble'Gses
**0DCM Effluent Concentration Limit.= 10 times the EC values of Reference
'(1.2.1)-
c..
, L*** Source Term for: (2SGC-RQ100) from Reference (1.2.3)
**** Detection Efficiency for (2SGC-R0100) from References (1.2.2)
Ei A- and,(1.2.4) '
- ~***** Insignificant i Y 1-14 ISSUE 3 p:'
? j ,
BV-1 ond 2 ODCH REFERENCES BV-1 LIQUID EFFLLENT HONITOR SETPOINTS 1 1.1 *
- aver Valley Power Station, Appendix I Analysis - Docket No. 50-334 and Su-412"; Table 2.1.3 1.1.2 " Beaver Valley Power Station, Appendix I Analysis - Docket No. 50-334 and 50-412"; Table 2.1.2 1.1.3 10 CFR 20, Appendix B, (20.1001-20.2401) Table 2, Column 2 EC's 1.1.4 Isotopic Efficiencies For Unit, 1 Liquid Process Monitors; DLCo
.alculation rackage No. ERS-SFL-92-039 1.1.5 Process Alarm Setpoints For Liquid Effluent Monitors; DLCo Calculation Packge No. ERS-ATL-93-021 BEFERENCES BV-2 LIQUID EFFLUENT HONITOR SETPOINTS 1.2.1 10 CFR 20, Appendix B, (20.1001-20.2401) Table 2, Column 2 EC's 1.2.2 . Unit 2 DRHS Isotopic Efficiencies; DLCo Calculation Package No.
ERS-SFL-B6-02C 1.2.3 Stone and Vebster Computer Code LIQ 1BB; " Normal Liquid Releases From A Pressurized Vater Reactor" 1.2.4 Isotopic Efficiencies For 2SGC-ROIL 00; DLCo Calculation Package No. ERS-JVV-87-015 1.2.5 Conversion Factor for 2SGC-R0Il00; DLCo Calculation Package No. ERS-VFV-87-021 1.2.6 Process Alarm Setpoints Fc- Liquid Effluent Monitors; DLCo Calculation Packge No. ERS-ATL-93-021 l f O 1-15 ISSUE 3
E, s 4 . 4
^ ~
BV-1 cnd 2 ODCM l q
, = .
'1.2-1 Compliance Vith 10 CFR 20 EC Limits (ODCM-Appendix C CONTROL-3.11.1.1)
[1.21LBatchReleases-7 - 1.2.1.1JPre-Release
;The. radioactivity content. of 'each-' batch -release vill be determined prior to release.in accordance-vith~. ODCM Appendix C, Table 4.11-1. In order.to assure representative. samples, at..lesst two tank volumes of'
- entrained fluid from each tank to. be discharged shall be. recirculated through the'. : mixing : .. eduetors. , This. vill,lbe accomplished; by.
recirculating ~ the tank contentsifor_ at:least the time periods indicated in Table 1.2-la and 1.2-1b.- :BV-1 ,and'BV-2. vill show compliance with ODCM Appendix C CONTROL 3.11.1.1 in the following manner: 0 .The activity);of the'1various radionuclides in .the batch release, determined _in accordance with'0DCM Appendix C, Table 4.11-1, is dividad-by theE minimum' dilution- flow. to' obtain the -concentration at the unrestricted area. This. calculation is: shown .in 'the- following. equation: Cone C.R 1 gg.2-1) i-= y
'where:
Cone g = Concentration of radionuclide "i" at the unrestricted area-(uci/ml). Cj ,=. Concentration of radionuclide "i" in the potential batch release'(uci/ml). R '- Release rate of the batch (gpm). MDF = Minimum dilution. flow (gpm)._ (May be combined BV-1/BV-2 flow when simultaneous liquid discharges are
. administratively 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. r y(Conc g/0ECg ) f 1 [1.2-2] vhere: h 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 nev 10 CFR 20, Appendix B, (20.1001-20.2401) y Table 2, Col. 2 EC values. .O.
1-16 ISSUE 3 a-
'u
BV-1 cnd 2 ODCM
-1.2.1.2 Post-Release Following release frm the batch tank, the Post Dose Cbrrection Factor i
will be calculated in the following manner: PDCF , (VAt )/(DFA) [1.2-3] (VIt)/(DFI) where: PCDF = Post Dose Cbrrection Factor. vat = Actual Volune of tank released (gal) . DFA = Actual dilution flow during release (ggn) . VIt = Initial volume authorized for release (gal) . DFI = Initial dilution flow authorized for release (gpn) . The concentration of each radiorniclide following release from the batch tank will be calculated in the unrestricted area in the following manner when the Post Dose Correction Factor shown in equaticn [1.2-3) is >1: 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:
#[O Cancik Cik Vtk [1.2-4) aDFk where:
Ococik = The concentration of radionuclide "i" (uci/ml) at the unrestricted area, during the release period of time k. Note: = Since discharge is frcm an isolated well-mixed tank at essentially a uniform rate, the difference between average and peak ccccentraticn within any discharge period is min 4=1. Cik = Concentration of radicnuclide "i" (uci/ml) in batch release during tine period k. Vtk - Volumg of tank released ching time period k (gal) . ADFk = Actual volume of diluticn flow during the time period of l release k (gal) . To show ccxTplian.:e with ODCM AreHx C COtHROL 3.11.1.1, the following relaticnship nust hold:
"In [1.2-5]
Ti(Cdncik/OEC 1 ) 51 O 1-17 ISSUE 3 Revision 5
BV-1 and'2 ODCN 1.2.2' . Ocntinucos Releases ! Continuous releases of liquid Cffluents do Ixt presently occur at BV-1 or ! -BV-2. If they did occur, the concentraticn of various radicmuclides in the unrestricted area would be' calculated usiry F.quation (1.2-1) with C ly,, O the ccncentration of isotope i in the continuous release. To show i.-U conpliance with CIXN Appvibc C CENIML 3.11.1.1, Expression . (1.2-5]
.nust again hold.
# TO O
4 l v 1-18 ISSUE 3 Revision 5
~
BV-1 and 2 ODCM TABLE 1.2-la BV-1 RECIRCULATION TIMES REQUIRED BEFORE SAMPLING OF LIQUID DISCHARGE TANKS O APPROXIMATE RECIRCULATION TIME
- g/U TANK DESCRIPTION MARK NO. (Based on Historical Rec 3: . Rates)
Laundry And Contaminated ILV-TK-6A/6B 2.5 hrs - (1200 gal)(2)/(16 gpm) Shower Drain Tanks Low Level Vaste Drain Tanks ILV-TK-3A/3B 1.5 hrs - (2000 gal)(2)/(45 gpm) High Level Vaste Drain Tanks ** ILV-TK-2A/2B 3.4 hrs - (5000 gal)(2)/(50 gpm) Evaporator Test Tanks 1LV-TK-5A/5B 1.4 hrs - (3000 gal)(2)/(73 gpm) Steam Generator Drain Tanks 1LV-TK-7A/7B 17.2 hrs -(35000 gal)(2)/(68 gpm) Boron Recovery Test Tanks 1BR-TK-2A/2B 9.7 hrs -(13,000 gal)(2)/(45 gpm) O
- The times listed are those approximated for two recirculations of a full tank with one recirculation pump in operation (using historical recirculation rates). Partially full tank recirculation times are directly proportional to the fraction of the tank capacity occupied by the entrained
~
}7
) liquid vaste after iso?.ation. Actual recirculation times are determined prior to sampling using actual tank vol ,9es and actual recirculation rates available in the BV-1 Control Room.
** Not normally a direct source of discharge.
1-19 ISSUE 3 Revision 2
y ($
- M t :BV-i tnd~2.0DCM TABLE'1?2-lb Si h -BV-2 RECIRCULATION TIMES-REQUIRED BEFORE SAMPLING OF LIQUID' DISCHARGE TANKS-jLvy
[I s. l 4 APPROXIMATE RECIRCULATION TIME
- U
' TANK-DESCRIPTION MARK NO..: (Based'on Historical Recirc. Rate's). f1 b
Liquid Waste Tanks. 2LVS-TK21A/21B 11.5 hrs:= (10,000 gal)(2)/(29-gpm): Steam Generat'or Blowdown. 2SGC-TK21A/21B 25.8 hrs.e'(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 _ , l O t:* The times-listed are those ' approximated for two recirculations of a full l' . tank :with one recirculation- pump in operation (using historical L-recirculation 3 tes). Partially full' tank recirculation times are directly i- : proportional to the fraction of.the tank capacity occupied by the entrained l., liquid waste after. isolation.- -Actual recirculation times are determined l % prior to sampling using actual tank volumes and actual recirculation rates available in the.BV-2 Control Room. 1-20 ISSUE 3 Revision 2
f BV-1 cnd 2 ODCM 1.3 Compliance With 10 CFR 50 Dose Limits (0DCM Appendix C CONTROLS 3.11.1.2 D And 3.11.1.3) [O 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 (ODCM Appendix C CONTROL 3.11.1.2) The dose contribution 'from the release of liquid effluents vill be calculated monthly for each batch release during the month and a cumulative summation of the total body and organ doses vill be maintained for each calendar month, current calendar quarter, and the calendar year to date. The dose contribution vill be calculated using the following equation: DT = UAF E A h EatkCik Fk [1.3-1] i k-1 where: DT = The cuiwlative dose commitment to the tota". body or any organ,
~
T, from the liquid effluents for the totai time period m E 6tk (*#**) k-1 / \ L) and F are averaged at k = The length of the kth release over which C ik k for all liquid releases (hours). C ik - The average concentration of radionuclide, "i" (uci/ml), in undiluted liquid effluent during time period 6tk fr m 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 emitter (mrem-m1 per br-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 - The near field average dilution factor for C during any k liquid effluent release. Definedastheratibkof the average undiluted liquid vaste flow to the product of the average flow from the site discharge structure during the report period to unrestricted receiving waters, times 3. (3 is the site specific applicable factor for the mixing effect of the BV-1 and BV-2 discharge structure). ! ) V = Vaste Flov (3)(Dilution Vater Flov) 1-21 ISSUE 3
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 Regulatory Guide 1.113 methodology and is a factor of 10 below the limit specified in NUREG-0133, Section 4.3. The dose factor A was calculated for an adult for each isotope using thefollowingequkfionfromNUREG-0133. A (1.3-2] h = 1.14E5 (730/D y+ 21BF g)DF h where: 1.14E5 = 1E6 pCi x 1E3 ml x 1 yr uCi T 8760 hr 730 = Adult water consumption rate (liters /yr). D"
= Far field dilution factor from the near field area within 1/4 mile of the release point to the potable water intake for adult water consumption.
21 - Adult fish consumption (kg/yr). BF g = Bioaccumulation factor for radionuclide "i" in fish from Table A-1 of Regulatory Guide 1.109 Rev. 1 (pCi/kg per pCi/1). However, if data was not available from that reference, it was obtained from Table 6 of UC RL-50564, Revision 1. The bioaccumulation factor for niobium (300 pCi/kg per pCi/l) was not obtained from either of the above references noted. It was otained from IAEA Safety Series No. 57. Justification for use of this value is documented in Appendix A to Calculation Package No. ERS-ATL-83-027. DF IT
= Dose ccnversion factor for radionuclide "i" for adults for a particular organ T f rom Table E-11 of Regulatory Guide 1.109, Rev. 1 (mrem /pC1). If none, from NUREG-0172 or Regulatory Guide 1.109, Rev. O.
A table of A values for an adult at BV-1 and BV-2 are presented in Table 1.3-1.IT The far field dilution factor (D") factor for BV-1 andapplicable of 600 BV-2 is 200. This to the value Midland is based on a total dilution vater intake located 1.3 miles downstream and on the opposite bank from BV-1 and BV-2 (i.e., 200 = 600 + 3). The total dilution factor of 600 represents a conservative fully mixed annual average condition. Since the Midland intake is located on the opposite bank and is below the water surface, essentially fully mixed conditions vould have to exist for the radioactive effluent to be transported to the intake. O 1-22 ISSUE 3 Revision 1
['. BV-1 and 2 ODCM The cumulative doses (from each reactor unit) for a caler. Jar quarter and [)
\_f a calendar year are . compared to 0DCM Appendix C CONTROL 3.11.1.2 as follows:
For the calendar quarter, D $ 1.5 mrem total body [1.3-3] D f 5 mrem any organ [1.3-4] For the calendar year, D73 3 mrem total body [1.3-5] D $ 10 mrem any organ [1.3-6] If any of the limits in Expressions [1.3-3] through [1.3-6] are exceeded, a Special Report pursuant to both Section IV.A of Appendix I of 10 CFR 50 and Technical Specification 6.9.2f must be filed with the NRC at the identified locations. 1.3.2 Projection Of Doses (ODCM Appendix C CONTROL 3.11.1.3) Doses due to liquid releases shall be projected at least once per 31 days in accordance with ODCM Appendix C CONTROL 3.11.1.3 and this section. The Liquid Radvaste Treatment System shall be used to reduce the n radioactive materials in each liquid vaste batch prior to its discharge, ( ) when the projected doses .due to liquid effluent releases from each
'v' reactor unit, when averaged over 31 days vould exceed 0.06 mrem to the total body or 0.2 mrem to any organ. Doses used in the projection are obtained according to equation [1.3-1]. The 31-day dose projection shall be performed according to the following equations:
When including pre-release data, [1.3-7] D 31 - A+B T 31 + C When not including pre-release data,
-. [1.3-8)
D A 31 + C 31 - T vhere: D Projected 31 day dose (mrem). 31 Cumulative dose for quarter (mrem). l A = l B = Projected dose from this release (mrem). O T = Current days into quarter.
- () C = Value which may be used to antic' ste plant trends (mrem).
1-23 ISSUE 3 Revision 1
.BV-1 and 2 ODCM.
TABLE 1.3-1 A ALUES FOR THE ADULT FOR THE BEAVER VALLEY SITE lt (mrem /hr per uCi/ml) NUCLIDE BONE LIVER T-BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E-01 2.70E-01 2.70E-01 2.70E-01 2.70E-01 2.70E-01 2.70E-01 C-14 3.13E 04 6.26E 03 6.26E 03 6.26E 03 6.26E 03 5.26E 03 6.26E 03 Na-24 4.08E 02 4.08E 02 4.08E 02 4.08E 02 4.08E 02 4.08E 02 4.08E 02 P-32 4.62E 07 2.87E 06 1.79E 06 0.00E-01 0.00E-01 0.00E-01 5.19E 06 Cr-51 0.00E-01 0.00E-01 1.27E 00 7.62E-01 2.81E-01 1.69E 00 3.21E 02 Hn-54 0.00E-01 4.38E 03 8.35E 02 0.00E-01 1.30E 03 0.00E-01 1.34E 04
----------==. _-_-----------_-------.--------------------------------------
Hn-56 0.00E-01 1.10E 02 1.95E 01 0.00E-01 1.40E 02 0.00E-01 3.52E 03 Fe-55 6.59E 02 4.56E 02 1.06E 02 0.00E-01 0.00E-01 2.54E 02 2.61E 02 Fe-59 1.04E 03 2.45E 03 9.38E 02 0.00E-01 0.00E-01 6.83E 02 8.15E 03 Co-57 0.00E-01 2.10E 01 3.50E 01 0.00E-01 0.00E-01 0.00E-01 5.33E 02 Co-58 0.00E-01 8.95E 01 2.01E 02 0.00E-01 0.00E-01 0.00E-01 1.81E 03 Co-60 0.00E-01 2.57E 02 5.67E 02 0.00E-01 0.00E-01 0.00E-01 4.83E 03
------------------~---_-------------------------------------_----_-----_---_
Ni-63 3.12E 04 2.16E 03 1.05E 03 0.00E-01 0.00E-01 0.00E-01 4.51E 02 Ni-65 1.'7E i 02 1.65E 01 7.51E 00 0.00E-01 0.00E-01 0.00E-01 4.17E 02 Cu-64 0.00E-01 1.00E 01 4.70E 00 0.00E-01 2.52E 01 0.00E-01 8.53E 02 Zn-65 2.32E 04 7.37E 04 3.33E 04 0.00E-01 4.93E 04 0.00E-01 4.64E 04 Zn-69 4.93E 01 9.43E 01 6.56E 00 0.00E-01 6.13E 01 0.00E-01 1.42E 01 Br-83 0.00E-01 0.00E-01 4.04E 01- 0.00E-01 0.00E-01 0.00E-01 5.82E 01 Br-84 0.00E-01 0.00E-01 5.24E 01 0.00E-01 0.00E-01 0.00E-01 4.11E-04 Br-85 0.00E-01 0.00E-01 2.15E 00 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Rb-86 0.00E-01 1.01E 05 4.71E 04 0.00E-01 0.00E-01 0.00E-01 1.99E 04 Rb-88 0.00E-01 2.90E 02 1.54E 02 0.00E-01 0.00E-01 0.00E-01 4.00E-09 Rb-89 0.00E-01 1.92E 02 1.35E 02 0.00E-01 0.00E-01 0.00E-01 1.12E-11 Sr-89 2.22E 04 0.00E-01 6.39E 02 0.00E-01 0.00E-01 0.00E-01 3.57E 03 Sr-90 5.48E 05 0.00E-01 1.34E 05 0.00E-01 0.00E-01 0.00E-01 1.58E 04 Sr-91 4.10E 02 0.00E-01 1.65E 01 0.00E-01 0.00E-01 0.00E-01 1.95E 03 Sr-92 1.55E 02 0.00E-01 6.72E 00 0.00E-01 0.00E-01 0.00E-01 3.08E 03 Y-90 5.80E-01 0.00E-01 1.55E-02 0.00E-01 0.00E-01 0.00E-01 6.15E 03 Y-91m 5.48E-03 0.00E-01 2.12E-04 0.00E-01 0.00E-01 0.00E-01 1.61E-02 , Y-91 8.50E 00 0.00E-01 2.27E-01 0.00E-01 0.00E-01 0.00E-01 4.68E 03 Y-92 5.09E-02 0.00E-01 1.49E-03 0.00E-01 0.00E-01 0.00E-01 8.92E 01 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
,j Nbe95 4.47E 00 2.49E 00 1.34E 00 0.00E-01 2.46E 00 0.00E-01 1.51E 04 th Nb-97 3.75E'02 9.49E-03 3.46E-03 0.00E-01 1.11E-02 0.00E-01 3.50E 01 l
1-24 ISSUE 3 Revision 1 l v l
BV-1 cnd 2 ODCM TABLE 1.3-1 A VALUES FOR THE ADULT FOR-THE BEAVER VALLJl SITE
, lt (mrem /hr per uCi/ml) j NUCLIDE BONE LIVER T-BODY THYROID KIDNEY LUNG GI-LLI a Ho-99 0.00E-01 1.05E 02 2.00E 01 0.00E-01 2.38E 02 0.00E-01 2.43E 02 Tc-99m 8.97E-03 2.54E-02 3.23E-01 0.00E-01 3.85E-01 1.24E-02 1.50E 01 Tc-101 9.23E-03 1.33E-02 1.30E-01 0.00E-01. 2.39E-01 6.79E-03 4.00E-14
'Ru-103 4.51E 00 0.00E-01 1.94E 00 -0.00E-01 1.72E 01 0.00E-01 5.26E-02 Ru-105 3.75E-01 0.00E-01 1.48E-01 0.00E-01 4.85E 00 0.00E-01 2.29E'02 Ru_106 6.70E 01 0.00E-01 8.48E 00 0.00E-01 1.29E 02 0.00E-01 4.34E 03 l Ag-110m 9.48E-01 8.77E-01 5.21E-01 0.00E-01 1.72E 00 0.00E-01 3.58E 02 Sb-124 7.87E 00 1.49E-01 3.12E 00 1.91E-02 0.00E-01 6.13E 00 2.23E 02 Sb-125 5.03E 00 5.62E-02 1.20E 00 5.11E-03 0.00E-01 3.88E 00 5.54E 01
------- =--_------_--_---_------_-------_---------_-----------------__---_--
Te-125m 2.57E 03 9.30E 02 3.44E 02 7.72E 02 1.04E 04 0.00E-01 1.03E 04 Te-127m 6.49E 03 2.32E 03 7.90E 02 1.66E 03 2.63E 04 0.00E-01 2.17E 04 Te-127 1.05E 02 3.78E 01 2.28E 01 7.81E 01 4.29E 02 0.00E-01 8.32E 03 Te-129m 1.10E 04 4.11E 03 1.74E 03 3.78E 03 4.60E 04 0.00E-01 5.55E 04 Te-129 3.01E 01 1.13E 01 7.33E 00 2.31E 01 1.26E 02 0.00E-01 2.27E 01 Te-131m 1.66E 03 8.10E 02 6.75E 02 1.28E 03 8.21E 03 0.00E-01 8.05E 04
,s Te-131 1.89E 01 7.88E 00 5.96E 00 1.55E 01 8.27E 01 0.00E-01 2.67E 00
( ) Te-132 2.41E 03 1.56E 03 1.47E 03 1.72' 03 1.50E 04 0.00E-01 7.39E 04
Te-134 3.10E 01 2.03E 01 1.25E 01 2.7 E 01 1.96E 02 0.00E-01 3.44E-02 k-29 k [9b b5 [ bhb bh b b5b bh h$65b b5 h 59E bh b bbb bk 6bbk '
I-130 2.75E 01 8.10E 01 3.20E 01 6.87E 03 1.26E 02 0.00E-01 6.97E 01 I-131 1.51E 02 2.16E 02 1.24E 02 7.08E 04 3.71E 02 0.00E-01 5.70E 01 I-132 7.37E 00 1.97E 01 6.90E 00 6.90E 02 3.14E 01 0.00E-01 3.71E 00 I-133 5.16E 01 8.97E 01 2.74E 01 1.32E 04 1.57E 02 0.00E-01 8.06E 01 I-134 3.85E 00 1.05E 01 3.74E 00 1.81E 02 1.66E 01 0.00E-01 9.12E-03 ----
]
----------_------__-----_-____-----------__---_---_--------_--___---___-_6E01 I_135 1.61E 01 4.21E 01 1.55E 01 2.78E 03 6.76E 01 0.00E-01 4.7 Cs-134 2.98E 05 7.09E 05 5.79E 05 0.00E-01 2.29E 05 7.61E 04 1.24E 04 Cs-136 3.12E 04 1.23E 05 8.86E 04 0.00E-01 6.85E 04 9.39E 03 1.40E 04 1 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 l i
Ba-139 9.69E-01 6.90E-04 2.84E-02 0.00E-01 6.45E-04 3.92E-04 1.72E 00 Ba-140 2.03E 02 2.55E-01 1.33E 01 0.00E-01 8.66E-02 1.46E-01 4.18E 02 3 l Ba-141 4.71E-01 3.56E-04 1.59E-02 0.00E-01 3.31E-04 2.02E-04 2.22E-10 I Ba-142 2.13E-01 2.19E-04 1.34E-02 0.00E-01 1.85E-04 1.24E-04---------- 3.00E-19
---------_--------------_-----------------------------------------1 La-140 1.51E-01 7.59E-02 2.01E-02 0.00E-01 0.00E-01 0.00E-0 5.57E 03
( La-142 7.71E-03 3.51E-03 8.74E-04 0.00E-01 0.00E-01 0.00E-01 2.56E 01 f' x Ce-141 2.63E-02 1.78E-02 2.02E-03 0.00E-01 8.26E-03 0.00E-01 6.80E 01 Qj ----------------------------------------- ----------------------------- ----- 1-25 ISSUE 3 L J
h BV-1 ind 2 ODCM TABLE 1.3-l' e j A ALUES FOR THE ADULT'FOR THE BEAVER VALLEY SITE it (mrem /hr por 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 ----
------------------------------------------------------------------------1E-10 Pr-144 1.01E-03 .7.53E-04 9.22E-05 0.00E-01 4.25E-04 0.00E-01 2.6 Nd-147 3.798-01 4.38E-01 2.62E-02 0.00E-01 2.56E-01 0.00E-01 ?.10E 03 V-187 2.96E 02 2.47E 02 8.65E 01 0.00E-01 0.00E-01 0.00E-01 8.10E 04 Np-239 2.90E-02 2.85E-03 1.57E-03 0.00E-01 8.89E-03 0.00E-01 5.85E 02 1
O O 1-26 ISSUE 3
w:.
, .- ! / ,
BV-l'and 2-ODCH.
. 1
.. ; , /1.4 : Liquid- Padwaste System
- (.,, ' 3:. . :The liquid radvaste system has the' capability to control,. collect, process, store,: recycle,;and; disposel of liquid radioactive : waste' generated as a iresult of plant' operations, -including anticipated operational' occurrences.
.This system also uses 'some "of the ' components of'~the steam generator
.. blowdown system;for processing.
- Simplified.flov diagrams of_-the liquid.:radvaste" systems:for BV-1 and BV-2 are provided as Figures .l.4-1 andL 1.4-2. <respectively. = A diagram showing
-the' liquid effluent release points is _provided~as Figure.1.4-3. Since the
~
concept of:a shared liquid radvaste _ system' is used, then any liquid vaste generated can be stored,: processed and discharge,i from'either BV-1 or BV-2.. y k _ I I e < k U l
- l. 1-27 ISSUE 3 Revision 2
BV-1 Cnd 2 ODCH l l 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 l gallons._ They are located on the northwest vall of the Auxiliary j Building >(elevation 735'). _They. receive -liquid wastes from the vent j and drain system with activity concentrations above 4E-4 uCi/ml. 1.4.1.2 LV-TK-3A & 3B: Low 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. i 1.4.1.3 LV-I-2: Liquid Vaste Demineralizer j 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 j 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 receive liquid vaste that has been processed through the liquid vaste demineralizer. Once this tank is full, it is j put on recirculation through the demineralizer (for a minimum of tve J 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 setpoin* - %t would indicate ve are approaching OEC limits for radioactive Vati h: ring the sitc. If i an upper activity alarm on this radiation mi ~ +3 is received, it I automatically terminates the discharge by clon e discharge line ! isolation valves. O 1-28 ISSUE 3
Unyax , 4 .
- g. 9 g y ..
s ,, gy,g. nd 2-0DCMS 1 . g <
, L1.4.2"BV-2' Liquid Radvaste-System Components c
i f.~412;11 ? 2LVS-TK21A- & 218: E Vaste Drain Tanks? J:s]-4 '
~
There are Y oof; these:' tanks,' :each . tank;. has a capacityiof 10,000' i gallons.h ;They ares located -in the'Lnortheast corner of,the Auxiliary LBuildingf(elevation 710').: " ' They receive ' liquid'vastes from the vent. and; drain' system.; . g 4154.2.2' 2SGC-IOE21A & 21Bt"? Steam' Generator-Blowdown Cleanup Ion-Exchangers. L Theimain' purpose;ofLthefion exchangers-Lis--to clean ~ liquid waste vater of particulate and . dis' solved radioactive! contaminants through an. ion , exchange process.:LThere:is W resin bed,Loutlets straineri and cleanupi 'l l 1
< filter. associated with each ofthese;Jion excha'gers. n -They~are located
'in the Vaste Handling Building:(elevation 722'),.
1.4.2.3' 2SGC-TK23A & 23Bt-1 Steam Generator Blowdown Test Tanks l I There are two'of these tanks,- each -.has a capacity of 18,000 gallons. They are ' located' iin- ithe . 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 lon exchanger (for a minimum of two tank voh.mes) until the-radioactivityi. concentration.is acceptable for discharge. 1.4.2.4 2SGC-TK21A & 21B:' Steam Generator Blowdown Hold Tanks
.There are two of these tanks, each has'a capacity of 50,000l gallons.
= They are located : in the .Vaste Handling Building.(elevation 722').
These tanks are used to store liquid 'v'aste when the radioactive concentration 7 of ,the' steam generator' blowdown test tank' is not - Occeptable for dischargc. 'The contents .of this: tank is.then processed j
.through.the Unit'I or Unit 2 Liquid Radvaste Treatment System until the radioactivity' concentration is acceptable for discharge. i 1.4.2.5 2SGC-RQ-100: Liquid Waste 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 we are approaching OEC limits for radioactive water leaving'the site. If an upper activity alarm is' received, it automatically terminates the i discharge by closing the' discharge line isolation valves. i i 1-29 ISSUE 3 s
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- 2.0 JGASEOUS EFFLUENTS 0DCM Appendix'C CONTROLS applicable',to;" dose-: rate. apply to'the site. The
. site dose rate;is due to the summation Jof releases from both units. 0DCH-j accumulatedl dose apply' individually to {
-'each; Appendix;C_ CONTROLS, applicable.
unit.1 Releases at (the; to:BeaverLValleyi site;Lmay be' ground level'or- ;
? elevated _in nature'.._ AllL; ground, level releases 'are- identified'vith a 1 cspecific1 unit in:the determination of' site' dose rate'and dose' attributed to
'that unit.'; Elevated' releases from- both units are considered to originate _;
discharged ofrom~a common release-
- from a' shared radwaste ~ system and are At'BV-l'and-point,: ~t he Process Vent, at the top of the BV-1' cooling'tover.
y.. 4 P BV-2, the dose from ;the : shared!'radvaste system via thel rocess Vent-is normally' apportioned equally 1to the_ units.- However, a' containment purge.
'via the Process Vent,shall be. attributed _to a specific unit.
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i a l I Vi ! 2-1 ISSUE 3 ; (} '\
- , f
"'- I #
.BV-l'end 2 ODCMj 1 /- '
i i , 1271dAlarmISetpoints- . 4 D' ... . . lfQ 32;1.lj BV-1"Honitor Alarm Setpoint Determination
.frequire. that 'the dose:1 rate'1in i 4
'3DCMIAppendixiC;[C0'NTROLf3.11.2.1 unrestricted ~ areas du'e'to: ~ nob,J released 1from the site shall- be limited'.to. T 500 arem/yr:to the total
- body and to 1 3000 mrem /yr;to,the skin.
This'section describesithe= methodologyi usedt to' maintain the; release of noble' gas' radionuclides'vithin.ODCM EAppendix;.C CONTROL:3.11.2.1 for the c, .
- site'and. determines; monitor setpoints for BV-1.
7 '
~
a s. ~ , ..
' The meth'odologies.-described 'in iSeetion:-2.1.1.2, 2.1;2.2,fand 2.1.3.2
' l provide;an: alternate meansfof: ' determining;Jmonitorlalarm setpoints thatJ i
imay be used-when'an analysis.is~ performed or or"to re ease.
-l
' Control of the site dose rate limitz :due to noble" gases is exercised by a:
' total of.8 effluenta streamt' monitors, of- which E3 are: located in'BV 1 V <
. (alternates' exists for: these monitors), : and 15i are located.in BV-2. ' As l,
previously;noted .s BV-2. elevated releases are via.the~BV-1 Process Vent.
-Differences' exist-between .the setpoint . presentations . of the radiation' First, !there is a difference in: 1 p ~
monitoring'systemslof:BV-1.Wheres setpoint terminology. and. BV-2.BV-1. usesHIGH-landi HIGH-HIGH:the BV-2' l equivalents are ALERT and HIGH. ~The! second difference:is.that the BV-2 rather' than ... cpm .'as Einj-BV-1. This setpoint'is'^ presented' in .uci/cc .- A ' difference:is!due.to BV-2: software 'which applies'a conversion factor to They user is: 1 cautioned 1that.- the uCi/cc U ithe BV-2. raw data' (cpm).
- presentation is technically correct 1
'only.. ' f or the specific isotopic: mix
-In practice,
.used'in :the ' determination : of' the- conversion . factor. for that mix.'.
'setpoints determined <for f a . calculated.
mix Hare correct.to; release will be corr Serpoints determined.on analysis: prior ~ properly. controlling dose' rat'e. but.the_ indicated uCi/cc.value.may differ-
- from the actualLvalue.
~ All effluent monitors specified herein have HIGH-HIGH (BV-1) or HICH
'(BV-2) Alarm Setpoints! established at 30 percent'of the site' limit, and ,
l except 3 monitors noted -below, HIGH (BV-1) or/ ALERT (BV-2) Alarm j Setpoints' established at 10 percent of the site limit.- 1
~
i t
'1 '
7 l ' v ,: ; 4 _4 , l I
' ISSUE 3
.2-2 3'
4
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m v
BV-1 ond 2 ODCM Honitor Setpoint Specifications Based On Fraction Of Site Limit UNIT, RELEASE POINT AND MONITOR FRACTION OF SITE LIMITING DOSE RAT Unit 1, Ventilation Vent 30% (HIGH-HIGH) 10% (HIGH) RM-VS-101B (Alt. RM-VS-109 CH #5) Unit 1, Containment Vent 30% (HIGH-HIGH) 10% (HIGH) RM-VS-107B (Alt. RM-VS-110 CH #5) Units 1/2, Process Vent 30% (HIGH-HIGH) 10% (HIGH) RM-GV-108B (Alt RM-GV-109 CH #5) Unit 2, Containment Vent 30% (HIGH) 10% (ALEP.T) 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) lh 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 l are below the HIGH (BV-1) and ALERT (BV-2) Alarm Setpoints. j
)
- Vith all monitors below the normal HIGH-HIGH (BV-1) and HIGH (BV-2) )
Alarm Setpoints, a combination of 3 HIGH (BV-1) or ALERT (BV-2) Alarms j 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 I l rate limit may have been exceeded. 2-3 ISSUE 3 i _ g
e BV1
- and 2 ODCH A release may be batch or continuous in nature. Batch refers to releases m that are intermittent in _radionuclide concentrations or flow, such as releases from gas storage tanks,. containment ventings and purges, and Q.,
Batch releases may be due to
?- -
systems-or components with infrequent.use. operational variations which result- in radioactive releases greater than 50% of.the_ releases- normally considered as continuous. Batch releases 1from' these sources during- normal operation, including anticipated operational occurrences, are defined as those which occur.for a total of 500 hours or less in~a calendar. year, but not more than 150 hours in any quarter. The batch relative; concentration value has been calculated in
.accordance with the' guidelines' provided in NUREG-0324 for short-term release.- If simultaneous batch and continuous release out of one vent-occurs, use the lovest 'setpoint. obtained' according to'the'following.
Sections 2.'1.1.1'through 2.1.3.2. O 6 i O 24 ISSUE 3 1
BV-1 and 2 ODCM , 4 2.1.1.1 BV-1 Setpoint Determination Based On A Calculated Mix For Ventilation Vent And Containment Building Vent Releases _(Ground Releases) The calculated monitor count rate above background (C.R.), in nepm, the monitor HIGH-HIGH alarm setpoint above background (HHSP), and the monitor HIGH alarm setpoint above background (HSP) for each vent and operational condition should be as follows: BV-1 ALARM SETP0INTS FOR GROUND RELEASES cpm AB0VE BACKGROUND 30% 10% (P) PRIMARY
- MONITOR SITE SITE LIMIT LIMIT (A) ALTERNATE MONITOR C.R. HHSP HSP
" Continuous Release Via 1he (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 &
W 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 g-:seous source terms were derived from Stone & Vebster computer codes GAS 1BB (which is similar to the NRC CODE GALE, NUREG-0017) and DRAGON 4 (for the containment vacuum pump sources). Table 2.1-la does not irclude particulates and iodines, which are not used in site noble gas cose 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
" ~ 4
=,
f BV-1 cnd 2 ODCM
- Discharge' flow rate of 49,300 cfm for the BV-1 Containment Vent (Both continuous and batch release of Containment Purge).
q ,.
' Information -listed under Ref'erences - Gaseous Effluent Monitor Setpoints.
The calculation method given in Sections 2.1.1.1.1 through 2.1.1.1.7 was used to derive the monitor setpoints for-the following operational conditions: }
- Coniinuous release via the BV-1 Ventilation Vent. f
- Continuous release via the BV-1 Containment Building Vent. (
- Batch release of BV-1 Containment Purge via the BV-1 Ventilation
. Vent.
'l
- Batch release of BV-1 Containment Purge. via the BV-1 Containment Building Vent.
2.1.1.1.1 BV-1 Mix Radionuclides The " mix" (noble gas radionuclides and composition) of the r,aseous effluent was determined as follows:
- a. The gaseous source terms that are representative of the haix" of ,
the gaseous effluent were selected. Gaseous source terms are the )
/~ radioactivity of'the noble ~ gas radionuclides in the effluent.
Gaseous source terms can be obtained from Table 2.1-la. (Sf
- b. The fraction of the total radioactivity in the gaseous effluent I comprised of noble gas radionuclide "i" (5 ) for each individual 4
noble' gas radionuclide in the gaseous effluent was determined by: S Ag [2,1(3)_1j g,IA 1-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: 0 500 [2.1(1)-2] E " (X/0) I KgSg i
.g-- .A 2-6 ISSUE 3
BV-1 cnd 2 ODCM vheres (X/0) " - The highest calculated annual average relative concentration of effluents released via the Ventilation Vent for any area at or beyond 3 the unrestricted area boundary for all sectors (sec/m ) from Table 2.2-5.
= 1.03E-4 sec/m for continuous releases.
(X/q)" - The short term relative concentration of effluents released via the Ventilation Vent for any area at or beyond 3 the unrestricted area boundary for all sectors (sec/m ) from Table 2.3-36.
- 3.32E-4 sec/m for batch release of containment purge.
(X/0)"" - 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. 3
= 9.24E-5 sec/m for continuous releases.
(X/q)C# = released The shortvia term the relative concentration containment building vent of effluents for any area at or beyond the3unrestricted area boundary for any sectors (sec/m ) from Table 2.3-35.
- 3.08E-4 sec/m for batch release of containment purge.
Kg - The total whole body dose factor due to gamma 3 emissions from noble gas radionuclide "i" (mrem / year /uci/m ) from Table 2.2-11. S g
= From equation [2.1(1)-1] above.
2.1.1.1.3 BV-1 Haximum Acceptable Release Rate (Skin Exposure) O was also determined based upon the skin exposure limit by: t 0 3000 [2.1(1)-3] '
" TX/0) I (Lg + 1.1M g) Sg <
i { vhere: Lg = The skin dose factor due to beta 3emissions from noble gas radionuclide "i"(mrem / year /uCi/m ) from Table 2.2-11. ) Hg = The air dose factor due to gamma3 emissions from noble gas radionuclide "i"(mtad/ year /uci/m ) from Table 2.2-11. O 2-7 ISSUE 3
- - - _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____ 3
I i f~ BV-1 End 2 ODCM l l
' ~
[ 1.1 = The ratio of the tissue'to air absorption coefficients ! X- 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 Maxirum Acceptable Release Rate (Individual Radionuclide) The maxirum acceptable releue rate (uci/sec) of noble gas radionuclide "i" in the gaseous _ effluent (0 3) for each individual noble gas radionuclide in the gaseous effluent was determined by: O-S g Qg [2.1(1)-4] l t (NOTE: Use the lover of the 0 values obtained in t Section 2.1.1.1.2 and 2.1.1.1.3.) i 2.1.1.1.5 BV-1 Maximum Acceptable Concentrations (Individual Radionuclide) ] The maximum acceptable radioactivity concentration (uci/cc) of noble gas radionuclide "i" in the gaseous effluent (C ) for each individual 4 noble gas radionuclide "i" in the gaseous effluent was determined by: C g, 2.12E-3 0 1 [2.1(1)-5] F vhere: im F - The maximum acceptable effluent flow rate at the point of release (cfm).
- 62,000 cfm (BV-1 Ventilation Vent)
= 49,300 cfm (BV-1 Containment Building Vent) 3 2.12E Unit conversion factor (60 sec/ min x 3.53E-5 ft /cc). f I
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: t C.R. - I Cy Ey [2.1(1)-6)] i where Eg - The detection efficiency of the monitor for noble gas radionuclide "1" (cpm /uci/cc) from Table 2.1-2a. l t J^
-f 2-8 ISSUE 3
h BV-1 end 3 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] l
- b. The monitor HIGH Alarm Setpoint- above background (nepm) vas determined by:
HSP = 0.10 C.R. [2.1(1)-8] NOTE: The values 0.3 for the HHSP and 0.1 for the RSP are fractions of the total radioactivity concentration that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded due to simultaneous releases from both units. O O 2-9 ISSUE 3
n ) BV-1 r_nd 2 ODCM 2.1.1.2 BV-1 Setpoint Determination Based On Analysis Prior To Release For
~'y Ventilation Vent And Containment Building Vent Releases (Ground
) Releases) l When the setpoints established using "the calculated mix" for ground releases do not provide adegr. ate 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 care, the results of sample t.nalysis are used to determine the source tera " mix." This calculational method applies to gaseous releases via che Ventilation Vent and via the Containment Building Vent when de'.ermining 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 Building Gas Monitor (RM-VS-107B) during the following ,
operational conditions: }
- Batch release of Containment Purge via the BV-1 Ventilation Vent.
j
- Batch re'. ease of Containment Purge via the BV-1 Containment Building j
Vent. 2.1.1.2.1 BV-1 Maximum Acceptable Release Rate The maximum acceptable discharge flow rate from Containment Vent or Ventilation Vent during purging is determined as follows: ;
- a. The maximum acceptable gaseous discharge flow rate (f) from the i
(") Containment Vent or Ventilation Vent (cfm) during purging based I g i upon the whole body exposure limit is calculated by: 1.06 S T [2.1(1)-17) f " (X/q) EKgCg i vhere: 1.06 = 500 mrem /yr x 2.12E-3 500 mrem /yr - dose rate limit 2.12E-3 = unit conversion factor
- (60 sec/ min x 3.53E-5 ft /cc)
S = Percent of site dose rate released via this pathway. Up to 60% of the site dose rate is permissible for one release point under the alarm set point rules of Section 2.1.1. To exceed 60% of the site limit from one release point, the remaining release point limits must be correspondingly reduced or secured to provide the necessary margin below the site dose rate limit. g T = Maximum valve for T is 16 based on the limiting restriction in ODCM Appendix C CONTROL 3.11.2.1.a where the dose rate for a containment purge may be averaged over a time period not to exceed 960 minutes. (As
'l containment air volume change time period is 60 minutes;
% /
T = 960/60 = 16). See Reference 2.1.6. 2-10 ISSUE 3
BV-1 end 2 ODCH (X/q)" = The highest calculated short term relative concentration of effluents released via the Ventilation Vent for any area at or beyond 3 the unrestricted area 8 W boundary for all sectors (sec/m ) from Table 2.3-36.
. 3.32E-4 sec/m (X/q)cv - The highest calculated short term relative concentration of 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
- 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. Og - The undiluted radioactivity concentration of noble gas radianuclide "i" in the gaseous source (uci/cc) as determined by analysis of the gas to be relsesed.
- b. The flow rate (f) is also determined based upon the skin exposure limit as follows:
6.36 S T [2.1(1)-18] f " (X/q) E (Lg + 1.1M g) Cy i vhere: 6.36 - 3000 mrem /yr x 2.12E-3 3000 mrem /yr - dose rate limit 2.12E-3 = unit conversion factor 3
- (60 sec/ min.x 3.53E-5 ft fcc)
Lg - The skin dose factor due to beta emissions 3f#
- noble gas radionuclide "i" (mrem / year /uci/m ) from Table 2.2-11.
Hg - The air dose factor due to gamma emissions 3 I# " noble gas radionuclide "i" (mrad / year /uCi/m ) from Table 2.2-11. (X/q) = Same as in Section 2.1.1.2.1.a.
- c. 'he 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 l at be made from the vent.
0 2-11 ISSUE 3
k ~ b' iBV-1 and 2 ODCM p g, _ L2.1.1.2.22'bV-1 Monitor'Setpoints monitor . alarm:.setpoints.:above background- are -determined'as-8
--The .
'follows:- :
4 a.yLThe calculated monitor HIGH-HIGH Alarm Setpoint.above background 1
- (nepm). attributed to' the noble gas.radionuclidas is determined
- . by -
fECjEg '[2.1(1)-19] Lj
~
HHSP = ,. I -Fi wh$rei-f - The maximum acceptable gaseous' discharge flow rate'(cfm)- , determined'in Section'2.1.1-.2.1. l F -- The maximum actual.or. design effluent flow rate (cfm) at the point of. release.- 192,000'cfm (BV-l' Ventilation Vent -- design)
= 49,300 cfm (BV-1 Containment Vent -- design)
Cg .= The undiluted radioactivity' concentration.of noble gas
- radionuclide "i" in the gaseous source (uci/cc)~as determined by analysis of;the gas to be released.
Eg = The' detection efficiency of the_ monitor.for' noble gas
- radionuclide "i" (cpm /uci/cc) from Table 2.1-2a.
b .- When a HIGH-HIGH set. point has been calculated according to this section,.the monitor HIGH Alarm Setpoint above background (nepm) is determined as follows: HSP.= HHSP x 0.33 [2.1(1)-20] [
?
2 ISSUE 3
BV-1 cnd 2 ODCM-2.1.2 BV-2 Monitor Alarm Setpoint Determination of Monitor Alarm Setpoint See Section 2.1.1 for a description Determinations. 2.1.2.1 BV-2 Setpoint Determination Based On A Calculated Polishing Mix For Ventilation Building Vent, Vent, Containment Vent, Condensate Decontamination Building Vent, and Vaste Gas Storage Vault Vent Releases The table below gives the calculated monitor count rate above backgrouad (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 Via The BV-2 Ventilation Vent
' Batch Release Of 2HVS-R0101B 1.13E3 4.13E-5 1.24E-5 4.13E-6 Containment Purge Via The BV-2 Ventilation Vent l l
i
' Continuous 2HVS*R0109B 4.32E3 1.06E-4 3.17E-5 1.06E.5 Release Via The BV-2 Containment Vent
' Batch Release Of 2HVS*R0109B 2.09E3 4.05E-5 1.21E-5 4.05E-6 Cor.tainment Purge Via The BV-2 Containment Vent
' Continuous 2HVL-R0112B 2.89E4 1.61E-3 4.82E-4 9.63E-6 j Release Via The BV-2 Condensate Polishing Building Venc
' Continuous 2RM0-R0301B 5.66E4 3.15E-3 9.44E-4 9.44E-6 Release Via The BV-2 Decontamination Building Vent
' Continuous 2RM0-R0303B 8.03E5 2.24E-2 6.71E-3 2.24E-5 Release Via The BV-2 Vaste Gas Storage Vault Vent
- Alert Setpoint from Section 2.1.2 Fraction Of Site Limiting Dose Rate.
2-13 ISSUE 3
ft [. i v . . . . BV-1 and 2 ODCM The setpoints were determined usingthe'following conditions: lfy Source terms given.in Table 2.1-1b. These. gaseous source terms were 'g.
'; derived from Stone in Webster; computer codes GAS 1BB:(which is similar l
1tofthe NRC CODE GALE, NUREG-0017) and DRAGON-4 (for the containment
. vacuum pump sources). Table 2.1-1b.does not include particulates and iodines, which are'not.used.in site. noble gas dose rate calculations.
The Containment" Building; Purge radionuclide . mix was utilized for the purposes of: determining an alarm setpoint' for -the Ventilation ' Vent on the basis .of the; proximity. ofl 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 Waste. Gas
~
Storage Vault ventilation exhaust is also not normally radioactive. However, the monitor alarm setpoint- is based.on the assumption'that the ventilation' exhaust radionuclide spectrum' is similar .to'the gaseous. inventory in the- system housed by the vaste gas scorage vault.. This spectrum is listed' in Table 2.1-1b under~ Gaseous Waste System.'
- Onsite meteorological data.-for the period January 1,.1976 through December 31, 1980.
- Discharge flow rate of 23,700 cfm. for the BV-2 Ventilation Vent (Continuous).
- Discharge flow rate .of 53,700- cfm. for the BV-2 Ventilation Vent j (Batch release of containment purge).
- Discharge flow rate of 59,000 cfm for the BV-2 Cont'ainment Vent (Both continuous and batch release of containment purge).-
- Discharge flow rate of 30,556 cfm for the BV-2 Condensate Polishing Building Vent.
- Discharge flow rate' of 12,400 cfm for the BV-2-Decontamination Building. Vent.
- Discharge flow rate of 2,000 cfm for the BV-2 Vaste cas Storage Vault Vent.
I 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 i l l
Monitor (2HVS-R0101B), Containment V7nt Gas Monitor (2HVS*R0109B), Condensate Polishing Building Vent Gas Monitor (2HVL-R0112B), j Decontamination Building Vet Gas Monitor (2RM0-R0301B), and Waste Gas Storage Vault Vent Gas Monitor (2RM0-R0303B) during the following l operational conditions: i
- Continuous release via the BV-2 Ventilation Vent.
- Continuous release via the BV-2 containment Vent.
2-14 ISSUE 3 l
BV-1 end 2 ODCM
- Batch release of BV-2. Containment Purge via the BV-2 Ventilation Vent.
- Batch release of BV-2 Containment Purge via the BV-2 Containment Vent.
- Continuous release via the BV-2 Condensate Polishing Building Vent.
- Continuous release via the BV-2 Decontamination Building Vent.
- Continuous release via the BV-2 Vaste Gas Storage Vault Vent.
2.1.2.1.1 BV-2 Mix Radionuclides The " mix" (noble gas radionuclides and composition) of the gaseous effluent was determined as follows:
- a. The gaseous source terms that are representative of the " mix" of the gaseous effluent were selected based on the relative stream composition and volumetric flovrate. Gaseous source terms are the radioactivity of the noble gas radionuclides in the effluent.
Gaseous source terms can be obtained f rom Table 2.1-lb.
- b. The fraction of the total radioactivity in the gaseous effluent comprised of noble gas radionuclide "i" (S ) for each individual 4
noble gas radionuclide in the gaseous effluent was determined by: S A i [2.1(2)-1] i*EA g vhere: A g - The radioactivity concentration of noble gas radionuclide "i" in the gaseous effluent from Table 2.1-lb. 2.1.2.1.2 BV-2 Maximum Acceptable Release Rate Juhole 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 calculated by: 0 500 [2.l(2)-2] E " (X/0) E KgSg i where: (X/0)" = The highest calculated annual average relative concentration of effluents released via the Ventilation Vent for any area at or beyond 3 the unrestricted area boundary for all sectors (sec/m ) from Table 2.2-5. 3
= 1.03E-4 sec/m for continuous releases.
O 2-15 ISSUE 3
( n _. , BV-1 and 2 ODCH j (X/q)" = The short' term
. released via therelative concentration Ventilation Vent for any of effluents area at'or beyond'theLunrestricted area boundary'for all sectors O- 3 (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 vent for any area at.or beyond 3 the unrestricted area boundary for all sectors-(sec/m ).from Table 2.2-4.
- 9.24E-5 1sec/m3 for' continuous releases.
(X/q)C* - The short term relative concentration of effluents released via the containment. vent for any area at or
.beyond 3 the unrestricted area boundary for all sectors
.(sec/m ) from. Table 2.' 3-35.
- 3.08E-4 sec/m for batch release ~of containment purge.
~
' - The highest calculated annual average relative (X/0)CP . concentration'of effluents released via the Condensate Polishing Building Vent.for any area at or beyond3the
-unrestricted area boundary for all sectors (sec/m ) f,,,
Table 2.2-10. 3
= 7.35E-5~sec/m for continuous releases.
(X/0)d" - The highest calculated annual average relative concentration of' effluents released via the
' Decontamination Building Vent for.any area at or beyond 3 the unrestricted area boundary for'all' sectors (sec/m ) from Table 2.2-8.-
3
.- 9.24E-5 sec/m for continuous releases.
(X/0)" .- The highest. calculated annual average relative-concentration of effluents released via the Waste Gas Storage unrestricted Vaultarea Ventboundary for any area for at all or beyond sectors the 3)_ (sec/m ! from Table 2.2-9. 3
= 9.24E-5 sec/m for continuous releases.
- The total vhole body dose factor due to gamma 3emissions
~
Kg from noble gas radionuclide "i" (mrem / year /uci/m ) from Table 2.2-11. 5 - From equation [2.1(2)-1]. 3 n..
.v r
2-16 ISSUE 3 l p
p - BV-1 ond 2 ODCH j j 1 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 3000 [2.1(2)-3]- 0* * (X/0) E (Li + 1.lHg ) Si )
.i f
<here Lg - The skin dose factor due to beta emissions from noble gas radionuclide "i"(mrem / year /uci/m3 )-from Table 2.2-11.
H-g
- 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 r1elease rate (uci/sec) of noble gas
-radionuclide "i" in the gaseous effluent. (0 ) for each noble gas 4
radionuclide in the gaseous effluent was determined by: 03-Sg O t [2.1(2)-4] (NOTE: Use the lover of the 0 values obtained in 8 Sectics 2.1.2.1.2 an6 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. j 1 3 2.12E Unit conversion factor (60 sec/ min x 3.53E-5 ft /cc). l I t L e ; 2-17 ISSUE 3 j 1 1 u
l h BV-1 and 2:ODCM.
- p. _
2.1.2.1'.6jBV-2MonitordountRate p.; The calculated monitor count.- rate (nepm) above background attributed l
' Q' to_the noble ~ gas radionuclide (C.R.) was determined by:
C.R. = I C 'E .g' g. [2.1(2)-6)]
.g.
where -
- l. ,
- Ej='The-detectionefficiency'ofthemo'nitorfornoblegas radionuclide "i" (cpm /uci/cc);from. Table 2.1-2b.
2.1. 2._1. 7 : :BV-2 Monitor- Setpoints The monitor alarm L setpoints' above. background -were. determined asi follows: a .' The monitor HIGH -Ilarm Setpoint- above' background (uci/cc) was
~
determined by: [2.1(2)-7] HSP = 0.30 E C.R. i-ave
- b. The monitor ALERT Alarm Setpoint' above background (uci/cc) was determined by:
- p. ASP =.FR x C.R.
.[ 2.1( 2 )-8 ]
Q E g ,y, where: j j FR = Fraction of limiting. dose rete for the respective radiation monitor (from Section 2.1.2). E I """ = The C.R. of equation [2.1(2)-6] divided by the sum of the Cg lfor the respective' mix. I l 4 i I l LO l 2-18 ISSUE 3 1 i C
y 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 acceptable discharge flov' rate and the associated HIGH Alarm Setpoint based on respective vent flow rate during the following operational conditions:
- Batch release of Containment Purge via the BV-2 Ventilation Vent.
- Batch release of Containment Purge via the BV-2 Containment Vent.
2.1.2.2.1 BV-2 Maximum Acceptable Release Rate The maximum acceptable discharge flow rate from the Containment Vent or Ventilation Vent during purging is determined as follows:
- a. The maximum acceptable gaseous discharge flow rate (f) from the Containment Vent or Ventilation Vent (cfm) during purging based upon the whole body exposure limit is calculated by:
1.06 S T [2.1(2)-17] f " (X/q) EK gC g i vhere: 1.06 - 500 mrem /yr x 2.12E-3 500 mrem /yr - dose rate limit, whole body exposure 2.12E-3 = unit conversion factor 3
- (60 sec/ min x 3.53E-5 ft /cc)
S - Percent of site dose rate released via this pathway. Up to ' 4 of the site dose rate is permissible for one release point under the alarm setpoint rules of Section 2.1.2. To exceed 60% of the site limit from one
- elease 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 l over a time period not to exceed 960 minutes. (As containment air volume change time period is 60 minutes; T = 960/60 - 16). See Reference 2.2.4. l 2-19 ISSUE 3
y p BV-1 and'2 ODCM a v (X/q) " = The' highest _ calculated short term relative .
-A' iconcentratio'n of effluents released via the Ventilation d)
Vent for.any boundary for area at or beyond. all sectors (sec/m 3)the fromunrestricted Table 2.3-36.area 3
=.3.32E-4 sec/m
\ (X/q)cv = Th'e highest'calcul'ated short term relative concentration of effluents released via the' Containment Vent.for any area'at.or beyond ,the unrestricted area boundary for all sectors (sec/m ) from Table 2.3-37.
= 3.08E-4 sec/m l K- g
= The. total whole body dose factor due to gamma 3emissions from noble gas radionuc1!.de "i" (mrem / year /uci/m )
from Table 2.2-11. j Cg - The undiluted radioactivity concentration of noble gas ' radionuclide "i" in the gaseous. source _(uCi/cc) as l determined by analysis of the gas to be released. l
- b. The flow rate (f) is also determined based upon the skin exposure limit as follows:
6.36 S T [2.1(2)-18] f "_ (X/q) E (Lg + 1.1H g) C1 i
. /N where:
1 1 6.36 = 3000 arem/yr x 2.12E-3 I 3000 mrem /yr = dose rate limit, skin exposure 2.12E-3 - unit conversion factor 3
= (60 sec/ min x 3.53E-5 ft fcc)
Lg - The skin dose factor due to beta emissions 3 f# " noble gas radionuclide "i" (mrem / year /uci/m ) from Table 2.2-11. Mg = The air dose factor due to gamma emissions 3 f noble gas radionuclide "i" (mrad / year /uci/m ) from Table 2.2-11. (X/q) = Same as in Section 2.1.2.2.1.a.
- c. The flow rate (f) is determined by selecting the smaller of the calculated (f) values based on the whole body exposure limit-(Section 2.1.2.2.1.a) and based on the skin exposure limit (Section 2.1.2.2.1.b). The actual purge flow rate (cfm) must be maintained at or below this calculated (f) value or the discharge cannot be made from the vent.
.[t v
2-20 ISSUE 3 I w Y
BV-1 cnd 2 ODCH 2.1.2.2.2 BV-2 Honitos Setpoints The monitor alarm' setpoints above background are determined as- .
.follows: ,
- a. The calculated. monitor HIGH Alarm Setpoint above background (net uCi/cc) attributed to the . noble gas radionuclides is determined by:,
fIC g E g [2.1(2)-19] HSP = I
,E F i ave' where:
f = The maximum acceptable containment purge flow rate (cfm) determined in Section 2.1.2.2.1. F = The maximum actual or design effluent flow rate (cfm) at the point of release.
- 53,700 cfm (BV-2 Ventilation Vent -- design)
- 59,000 cfm (BV-2 Containment Vent -- design)
Cg - The undiluted radioactivity concentration of noble gas radionuclide "i" in the gaseous source -(uCi/cc) as determined by analysis of the gar to be released. Eg = The detection efficiency of the monitor for noble gas radionuclide "i" (cpm /uci/cc) from Table 2.1-2b. E I *** = The C.R. of equation [2.l(2)-6]. divided Lj the sum of the C for the respective mix. i 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 uC1/cc) is determined as follows:
ASP 6 HSP.x 0.33 [2.1(2)-20] O 2-21 ISSUE 3 .m
W Q4 <
^ BV-1 sad 2 ODCH :
;g ,
m , j I 2.1.3.-BV-1/2 Monitor Alarm S'etpoint Determination 1 See ~ Section 2.1,1 for. a description of; Monitor. Alarm .Setpoint-
~
'.1 4 1 Determination.
~
L2.113.1 'BV-1/2'Setpoint'Det'erminationL Based ^ 0n" A ^ Calculated Mix For Process- .i 1 Vent Releases (Elevated. Releases):
.c
'The calculated. monitor count' rate above background (C.R.), in nepm,Jthe monitor'HIGH-HIGH..' alarm :setpoint.Labove :backgroundi (HHSP), :and.the O monitor:HIGH' alarm setpoint above background (HSP) for each operational-condition'are as"follows:
- a. > .-
d l
'BV-2 AND' ALARM'SETPOINTS FOR ELEVATED RELEASES
' ' ' cpm ABOVE BACKGROUND
[ 1 (P) PRIMARY
- 30%l 10%' l
' ' , 'HONITOR> SITE , -SITE l (A) ALTERNATE- : LIMIT. LIMIT *
'HONITOR= '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 i
- Batch Release Of BV-l' Decay ~ (P)RM-GW-108B 3.93E5 1.18E5. 3.93E4- []
Tanks (A)RM-GV-109(5) 7.87E6 2.36E6. 7.87E5 :1 j
- Batch Release Of BV-2' Decay' (P)RM-GV-108B 2.11ES 6.33E4 2.11E4 ;l Tanks .(A)RM-GV-109(5) 7.'75E6 2.32E6 7.75E5 i
- Batch Release Of:BV-1 (P)RM-GV-108B' 5.55E6 1.67E6L 5.55E5- l Containment Purge (A)RM-GV-109(5) 7.37E6 2.21E6 7.37E5
- Batch Release Of BV-2 (P)RM-GV-108B 5.38E6 1.16E6 5.38E5 Containment. Purge (A)RM-GV-109(5) 7.34E6 2.20E6 .7.34E5 ,
*Vhen the primary monitor is out of service, Land'0DCM Appendix C CONTROL 3.3.3.10 can be met.for=the respective alternate monitor, the alternate setpoints'may be utilized:-
j 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 conditionsi-
, ,
- 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 7 Process Vent.
2-22 ISSUE 3
- a ,
a BV-1 cnd 2 ODCH 2.1.3.1.1 BV-1/2 Hix Radionuclides The " mix" (noble gas radionuclides and composition) of the gaseous effluent was determined as follows:
- a. The gaseous source terms that are representative of the " mix" of the gaseous effluent were 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" (S ) for each individual 4
noble gas radionuclide in the gaseous effluent was calculated by: S A i [2.1-9] g,EA I i where: A g - The total radioactivity or radioactivity concentration of noble gas radionuclide "i" in the gaseous effluent from Iable 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 (O ) tbased upon the whole body exposure limit was determined by: 0 500 [2.1.10] t gy 3 i i i where V3 - 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) Og vas also determined based upon the skin exposure limit as follovs:
- t. 3000 [2.1-11]
' " I [L (X/0)py g + 1.1B g]Sg O
2-23 ISSUE 3 i
?
f
'BV-1 and 2 ODCM i
where em
'( f L - The skin dose' factor due to beta emissions 3from I
noble gas radionuclide "i"(mrem / year /uci/m ) from Table 2.2-11. (X/0)Pv = The highest'. calculated annual average relative concentration of effluents releases via the Process Vent for any area'at or beyond 3 the unrestricted area boundary for all sectors (sec/m ) from Table 2.2-6. 3
- 2.31E-6 sec/m (X/q)Pv -. The shortvia released term relative the._ concentration Process of effluents Vent for any area at or beyond 3 the unrestricted area boundary for all sectors (sec/m ) from_ Table 2.3-38.
3
- 1.07E-5 sec/m
-B g - The constant for long term releases (greater than 500 hrs / year) for noble gas radionuclide "i" accounting for the gamma radiation dose from the elevated finite plume (mrad / year /uci/sec) from Table 2.2-12.
2.1.3.1.4 BV-1/2 Maximum Acceptable Release Rate (Individual Radionuclide) The maximum acceptable release rate (uci/sec) of noble gas q radionuclide "i" in the gaseous effluent (0 for each individual tU i noblegasradionuclideinthegaseouseffluentha)sdeterminedby: Og-SgOt [2.1-12] (NOTE: Use the lover of the 08 values obtained in Section TT.l.1.2 and 2.1.3.1.3.) 2.1'.3.1.5 BV-1/2 Maximum Acceptable Concentrations (Individual Radionuclide) The maximum acceptable radioactivity concentration (uci/cc) of noble gas radionuclide "i" in the gaseous effluent (C ) for each individual noblegasradionuclide!nthegaseouseffluentdasdeterminedby: Cg 2 g .12E-3 0 1 [2.1-13] F vhere: 3 2.12E Unit conversion factor (60 sec/ min x 3.53E-5 ft /cc). F - The maximum acceptable effluent flow rate at the point of release (cfm).
- 1450 cfm (BV-1/2 Process Vent)
,m 2-24 ISSUE 3 I
._ s
, t. BV-1 end 2 ODCH l 2'.1.3.1.6 BV-1/2 Monitor Count Rate The calculated monitor count rate (nepm) above background attributed to.the noble gas radionuclide (C.R.) was determined by: C.R. = E CgEy 12.1-14] ) i where: E g - The detection"i"efficiency radionuclide of the (cpm /uci/ce) monitor from Tablefor nobleand 2.1-2a gas2.1-2b. 2.1.3.1.7 BV-1/2 Monitor Setpoints The monitor alarm setpoints above background vere determined as follows: l I
- a. The monitor HIGH-HIGH Alarm Setpoint above background (nepm)-vas l
determined by: HHSP = 0.30 C.R. [2.1-15]
- b. The monitor HIGH Alarm Setpoint above background (nepm) was i determined by: j HSP = 0.10 C.R. [2.1-16]
g) l 2-25 ISSUE 3 i i a L !
BV-1 and 2 ODCH 2.1.3.2 BV-1/2 Setpoint Determination Based on Analysis Prior To Release For ; m Process Vent Releases (Elevated Releases) The following calculation method applies to gaseous releases via the BV-1/2 Process Vent when the " calculated mix" does not provide adequate , I 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 j Vaste Gas Monitor (RM-GV-108B) or alternate (RM-GV-109 CH #5) during i the following operational conditions: i
- Continuous release via the BV-1/2 Process Vent.
- Batch release of BV-1 or BV-2 Vaste Gas Decay Tank via the BV-1/2 Process Vent.
- Batch release of BV-1 or BV-2 Containment Purge via the BV-1/2 l Process Vent.
2.1.3.2.1 BV-1/2 Maximum Acceptable Release Rate Determine the maximum acceptable discharge flow rate for the release from the Process Vent for the analyzed mix.
- a. The maximum acceptable gaseous discharge flow rate (f) from the Process Vent (cfm) based upon the whole body exposure limit is determined by:
s [2.1-21] ( ,l g , 1.06 S 4 Ev ic i i vhere: 1.06 = 500 mrem /yr x 2.12E-3 ! I 500 mrem /yr - dose rate limit, whole body exposure 2.12E-3 = unit conversion factor 3 <
= (60 sec/ min x 3.53E-5 ft /cc) f S = Percent of site dose rate released via this pathvay. Up to l 60% of the site dose rate is permissible for one release l 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.
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. C = The undiluted radioactivity concentration of noble gas f radionuclide "i" in the gaseous source (uci/cc) as i
'd determined by analysis of the gas to be released.
2-26 ISSUE 3 1 E
F ] BV-1 ent. 2 ODCM i 1
. \
- b. Based upon tne skin' exposure limit,-(f) is calculated by: ]
6.36 S [2.1-22] g , I [Lg (X70)py + 1.1B gj Cg where: J 6.36 - 3000 mreni/yr x 2.12E-3 l 3000 mrem /yr - dose rate limit, skin exposure 1 2.12E-3 - unit convrersion factor 3 i
- (60 sec/ min x 3.53E-5 ft /ce) {
i Lg - The skin dose factor.due to beta emissions 3'* I j noble gas radionuclide "i" (mrem / year /uCi/m ) from. Table 2.2-11. I 1 (X/0)PV - The highest calculated annual average relative concentration of effluents released via the Process i Vent for any area at or beyond 3the unrestr.icted area { boundary for all sectors (sec/m ) from Table 2.2-6. l
- 2.31E-6 sec/m i
(X/q)PV - released The'shortvia term relative concentration of effluents the Process Vent for any area at or beyond 3 the unrestricted area boundary for all sectors (sec/m ) from Table 2.3-38. 3
- 1.07E-5 sec/m l
Bg - The constant for long-term releases (greater than i 500 hrs / year) for noble gas radionuelide "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.n) and based on the skin j 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 j (nepm) attributed to the noble gas radionuclides is determined l by: l
\
[2.1-23) fEC gE g HHSP - , O 2-27 ISSUE 3 . I l b -- _
p?.
-BVil:and 2 ODCM ,.
I. where:
- 'O .f' = The maximum acceptable gaseous discharge flow. rate (cfm)
Qf ' . - s 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)'
L Gj =:The undiluted radioactivity of noble gas radionuclide "i" in the gaseous source (uCi/cc) as determined.by analysis of the L gas to be. released.. Eg _= The. detection efficiency of the-respective monitor (RN-GV-108B).or (RM-GV-109 CH 5).for noble gas radionuclide "i" (cpm /uci/cc).from Table 2.1-2a and 2.1-2b'
- b. .Vhen a HIGH-HIGH f.larm Setpoint has been calculated according to this sectio'n the~ monitorc HIGH. Alarm setpoint.above. background l '(nepm) is determined by:
HSP = HHSP x 0.33 [2.1-24] I O 2-28 ISSUE 3 t:
' BV-1 cnd 2 ODCM -
TABLE 2.1-la BV-1 RADIONUCLIDE MIX FOR GASEOUS EFTLUENTS ' (Ci/yr)** TURBINE CONTAINMENT VENTILATION ' BUILDING i VENT VENT PFOCESS VENT __ VENT _ Long Term And ' AUXILIARY TURBINE MAIN CONTAINMENT GASEOUS CONTAINMENT BUILDING BUILDING CONDENSER / VACUUM VASTE BUILDING VENTILATION VENTILATION AIR EJECTOR PUMPS SYSTEM NUCLIDE Short. Term Long Term Long Term Long Term "Long Term Short Term Kr-83m 2.2E-02 4.2E-01 3.9E-05 2.7E-01 3.7E-04 0.0 Kr-85m 1.5E-01 1.9E+00 1.7E-04 1.2E+00 3.9E-03 7.3E-02 Kr-85 6.1E+01' 2.5E+00 2.3E-04 1.6E+00 7.2E-01 2.3E+02 Kr-87 5.4E-02 1.3E+00 1.1E-04 8.2E-01 7.8E-04 0.0. Kr-88 2.4E-01 3.8E+00 3.5E-04 2.4E+00 5.0E-03 0.0 Kr-89 4.7E 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 r'. 8.9E-01 8.1E-05 5.6E-01 2.2E-02 0.0 Xe-133 8.9Esel 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 1.1E-05 1.3E-01 6.3E-06 0.0 Xe-138 1.5E-02 1.1E+00 9.7E-05 6.6E-01 1.2E-04 0.0 ,
Ar-41 2.5E+01 0.0 0.0 0.0 0.0 0.0 l J l l
- 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 L _
ib > , O BV-1 and 2 ODCML A TABLE 2.1-lb ./ 7' , ,.h BV-2 RADIONUCLIDE MIX FOR GASEOUS EFFLUENTS li( ) (Ci/yr)**
, TURBINE 4 ' VENTILATION' CONTAINMENT- ' BUILDING
' VENT, ' VENT VENT PROCESS VENT ~
l ' Long Term a
,;And 4_
1 AUXILIARY- ' TURBINE ! MAIN'- CONTAINMENT. GASEOUS L l CONTAINMENT. -BUILDING BUILDING- CONDENSER // VACUUM VASTE ~ NUCLIDE- BUILDING VENTILATION VENTILATION: AIR EJECTOR PUMPS SYSTEM l
. Short Term . Long-Term. Long Term .Long Term Long. Terme Short Term
- Kr-83mr -4.0E-05 4.2E-01 L3.9E-05 .2.7E-01 3.7E-04' O.0
'Kr-85m' 1.4E-02: 1.9E+00 1.7E-04 1;2E+00 3.9E-03 -1.2E Kr 6.1E+01' 2.5E+00 2.3E-04 ,1.6E+00 7.2E-01~ 2'.3E+02 Kr-871 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 17.7E-02 .3.1E-06 0.0 Xe-131mL 7.2E-011 1.3E 1.2E-05. 8. 0E-02 -- 1.3E-02 8.3E-01 Xe-133m- .7.6E-01 8.9E-01 :8.1E 5.6E 2.2E-02' O.0
.Xe-133 8.4E+01 3.6E+01. 3~4E . 2.3E+01 1.9E-00i 8.2E+00 Xe-135m2 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 0.0
/"'N . :Xe-137 'O.0- 2.1E-01z -2.1E-05 1.3E-01 .6.3E-06' O.0
( ,) Xe-138 0.01 .1.1E+00 .9.7E-05
-0.0 6.6E-01 0.0
-1.2E-04 0.0-0.0 0.0 1Ar-41 2.5E+01 0.0'
~
L ' L
- Containment-can be purged via Ventilation Vent, Containment Vent, or Process Vent f-
- Reference'(2.2.3)
[-(-}3 *** Reference (2.2.5) i 1 2-30 ISSUE 3 ! T
r: BV-1 cnd 2 ODCH TABLE 2.1-2a I BV-1 MONITOR DETECTOR EFFICIENCIES (cpm /uci/cc, CORRECTED)* VENTILATION PROCESS CONTAINHENT VENT VENT VENT NUCLIDE ALTERNATE PRIMARY ALTERNATE PRIMARY ALTERNATE PRIMARY. HONITOR HONITOR HONITOR HONITOR HONITOR MONITOR RM-VS-101B RM-VS-109 RM-GV-108B RM-GV-109 RM-VS-107B RM-VS-110 Channel 5 Channel 5 Channel 5 Kr-83m -- -- -- Kr-85m 9.80 E7 2.39 E7 9.00 E7 2.43 E7 5.16 E7- 2.57 E7 Kr-85 3.88 E5 2.47 E7 3.56 E5 2.51 E7 5.04 E7 2.67 E7 Kr-87 7.38 E7 2.95 E7 6.78 E7 3.00 E7 9.60 E7 3.19 E7 Kr-88 L1.14 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 j 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 f Xe-135 1.12 E8 2.91 S7 1.03 E8 2.96 E7 6.42 E7 3.14 E7 Xe-137, 3.16 E7 2.96 E7 2.91 E7 3.01 E7 1.05 E8 3.19 E7 Xe-138 1.15 E8 2.66 E7 1.06 E8 2.70 E7 7.35 E7 2.87 E7 Ar-41 7.17 E7 3.00 E7 6.59 E7 3.05 E7 7.19 E7 3.23 E7 9i l l
- The listed detector efficiencies for the respective primary monitors (Victoreen)
! are- corrected for the reduced pressures observed and documented during l 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 Honitors.) See Reference (2.1.4) for additional information. - 2-31 ISSUE 3 L_
b BV-1 cnd 2 ODCH-I- TABLE 2.1-2b-l- g-~y. BV-2. MONITOR DETECTOR EFFICIENCIES ,
-(cpm /uci/cc)* ' .( )
s
'VASTE. GAS CONDENSATE STORAGE DECON~ POLISHING
-VENTILATION CONTAINMENT VAULT. BUILDING . BUILDING NUCLIDE. VENT ' VENT VENT VENT ' VENT 2HVS-R0101B- 2HVS-RQ109B 2RMQ-R0303B 2RMQ-RQ301B 2HVL-RQ112B Kr-83m- .-- - - - --
Kr-85m 3.20E7 ~5.83E7 3.20E7 3.20E7 3.20E7 Kr-85 3.60E7 17.19E7 .3.60E7 3.60E7 3.60E7 Kr-87 3.73E7. 8.85E7- '3.73E7~ 3.73E7 3.73E7 Kr 3.05E7 6.80E7 3.05E7- 3.05E7 '3.05E7 Kr-89 3.72E7- 8.73E7 3.72E7 -3.72E7- '3.72E7. Kr 3.86E7 8.80E7 3.86E7 3.86E7 3.86E7 Xe-131m- 2.44E7 -4.61E4- 2.44E7 2.44E7 2.44E7
=Xe-133m 2.86E7' 6.06E4 2.86E7- 2.86E7 2.86E7 Xe-133 1.80E7 2.94E7- 1.80E7 1.80E7 1.80E7
<Xe-135m L7.22E6 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-1381 3.52E7 7.74E7 3.52E7 3.52E7 3.52E7
.Ar 3.79E7 7.90E7 3.79E7 3.79E7- 3.79E7
[u ;
.r.
t: l
.*Reference (2.2.1) l f k -) %
2-32 ISSUE 3 j
m 1
"' BV-1 and 2 ODCM j
REFERENCES BV-1 GASE0US EFFLUENT HONITOR SETP0INTS O I 2.1.'1 _" Beaver Valley Power Station, Appendix I Analysis - Docket No. 50-334 and 50-412"; Table 2.1.3 j
;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 Unit 1 Gaseous Effluent Monitor Efficiency Data; DLCo Calculation Package !
2.1.4 No.-'ERS-SFL-85-031
'2.1.5 . Unit 1/ Unit 2 ODCH Gaseous ' Alarm Setpoint Determinations; DLCo Calculation Package No. ERS-HHM-87-014 2.1.6 BVPS-1 and BVPS-2 ODCH T Factor-Justification; DLCo Calculation Package No. ERS-ATL-87-026-2.1.7 Letter NDISHP:776, dated February 12, 1988, BVPS-1 ODCM Table 2.2-2, Appendix B 2.1.8 Gaseous Releases From Containment Vacuum Pumps; Stone and Webster Calculation No. UR(B)-262 O
REFERENCES BV-2 GASE0US EFFLUENT HONITOR SETP0INTS 2.2.1 linit 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 0 2-33 ISSUE 3 L
y c g s i . _]
, BV-1 cnd'2 ODCH-- {
l l
'2.2! Compliance.
! Vith 10!CFR-20' Dose Rate Limits (ODCH Appendix C CONTROL f% T 11.2.1) ~
Q; '~ a 2.2.1 ' Dose ~ Rate Due To Noble Gases ) The dose rate'in;:unrestrictedi areas; resulting from' noble gas-effluents
- from the. site is limited to 500 mrem /yr'tolthe total ~ body and l 3,000 mrem /yr to.the skin. Site gaseous effluents are-the: total.of'BV-1 and'BV-2 specific' ground. releases'andLa. shared = elevated release,-the 3 i> .
BV-1/2 ' Process, Vent. l Based Jupon.- NUREG-0133~ the' following basic 'j i a- fexpressionsi are used to show. compliance vith -0DCH Appendix C CONTROL 3.11.2.1.a.- I[k/gg 0 +K(X/0)p0gy]
.g < 500 mrem /yr 1[2.2-1]~
- 1 l
- o. ,
3000 mrem /yr [Li (576);.+-1.1Bj] Og ,,+ [L{ + 1.1Hg ](X/0)y Ogy _' I
- 1 I
.[2.2-2]
r "where e Kg =-identified The total: body nobledose gas factor due to gamma radionuclide'"i", mrem emissions for .3.ach
/ year /uci/m -
.L i = The skin dose; factor due to beta emissions for each 3
- identified noble' gas radionuclide '. i", mrem / year /uci/m _,
Hj .The air dose factor due to gamma emissions for'each: 3
- identified noble gas radionuclide "i", mrad / year /uci/m ..
V- g
=TNeconstantforeachidentifiednoblegasradionuclide i "i" accounting.for the-gamma radiation from the elevated ~l finite plume,-mrem / year /uci/sec.
Bg = The constant-for.~1ong-term releases (greater than 500 hrs / i T j
. year) for'each identified noble gas radionuclide'"i" accounting for the gamma radiation from the elevated finite l
plume, mrad / year /uci/sec.
~ l' .1
= The ratio of the tissue to air absorption coefficients l over the energy range of the photon of interest, mrem / mrad.
l i O gs - The release rate of noble gas radionuelide "i" in gaseous effluents from free-standing stack, uCi/sec. f O gy' - The release rate of noble gas radionuclide "i" in gaseous
. effluents from all vent releases, uCi/sec. :
=(576)s.= The highest calculated annual. average relative concentration for any area at or beyond3 the unrestricted area boundary for elevated releases (sec/m ).
2-34 ISSUE 3 E
BV-1 cnd 2 ODCM l (X/0)y - The highest calculated annual average relative concentration f for any area at or beyond the, unrestricted area boundary for ground level releases (sec/m'). At the Beaver Valley site gaseous releases may occur from:
- 1. The Containment Vents atop the Containment Domes
- 2. The Ventilction Vents atop the Auxiliary Buildings 1
- 3. The Process Vent atop the BV-1 Cooling Tower. I
- 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. l' 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 ODCil Appendix C CONTROL 3.ll.2.1.a, Expressions [2.2-1] and [2.2-2] are now expressed in terms of the actual release points for the site. Note that the expressions for release points 4, 5, 6, and 7 are included for use if radioactive releases via these release points are identified in the future.
For The Total Body Dose Rate: EVo gg +EKg g [(X/0)cv O g cyl + (X/0)yy O g vvl + (X/0)tv O g tvl + (X/0)cy i pv 0 + (X/0)yy 0 3 +I )tv O g tv2 Cp b 1 2 v2 ep2 dv2 (XTC)yy O g ] f 500 mrem />. [2.2-3] O 2-35 ISSUE 3
[ l BV-1/and'2 ODCH E )q :j.; 'LFor The Skin Dose Rates- [ [(W ' I [L (UQ)py +' ' 1.1B ] . O g g
+Eg Bg[+ 1.M g) [(UQ)cy O g
+ (UQ)yy i cv1
. !; a ,ir , +
pv?
+
Og +-(X/0)tvL0g. j+.(UQ)cy- Og . . + WQ)yy O g + (UQ)tv>03 -. tv2 vv1 tv1 cv2 vv2~
+-(X/0)dy O. C (U Q)yy O g ] $-3000 mrem /yr (X/0(p:Op.
g cp2 dv2 vv2- [2.2-4) where: O, g
- = Release rate of radionuclide "i"'from the BV-1/2 Process.
pv. Vent, uC1/sec. Og = Release rate of radionuclide "i" from'the BV-1 Containment ev1 ' Vent, uCi/sec. Og - Release rate of radionuclide~"i" from the BV-2 Containment ev2 Vent, uCi/sec.
- Release rate of radionuclide "1" from the BV-1 Ventilation O- g vv1. Vent, uCi/sec.
l
.0 3 = Release rate of radionuclide."i" from the BV-2 Ventilation.
vv2 Vent, uCi/sec.
.fr - Release rate of radionuclide "i" from the BV-1 Turbine ;
V Og tv1 Building. Vent, uCi/sec.-
.1
-O g - Release rate of radionuclide "i" from the BV-2 Turbine l tv2 Building Vent,'.uCi/sec.
l Og - Release rate of radionuclide "3" from the BV-2 Condensate ep2 Polishing Building Vent, uCi/sec. O- g
= Release rate of radionuclide "i" from the BV-2 dv2 Decontamination Building Vent, uCi/sec.
O = Release rate of radicauclide "i" from the BV-2 Vaste
- Gas g*ev2 Storage Vault Vent, uCi/sec.
(X/0)Py - Sfor hhest calculated releases annual from the Process average Vent,-relative sec/m concentration 3
.(X/0)cv = Highest calculated annual average relative3 c neentration for releases from the~ Containment Vent, sec/m (X/0)yy~- Highest calculated annual average relative 3 c ncentration for L releases from the Ventilation Vent, sec/m j
(X/0)tv = Highest calculated annual average relative 3e neentration for releases for the Turbine Building Vent, sec/m 2-36. ISSUE 3 p u
BV-1 cnd 2 ODCH (576)CP - forHighest calculated releases annual f r the BV-2 average relative Condensate concentration Folishing Building 3 Vent, sec/m (276)dy - Highest calculated annual average relative concentration3 f# releases for the BV-2 Decontamination Building Vent, sec/m . I# ( M )yy - Highest calculated annual average relative concentration 3 releases for the BV-2 Vaste Cas Storage Vault Vent, sec/m . Note that the release rate for a containment purge is based on an averaged release rate in uCi/see for the entire purge (not to exceed 960 min in accordance with ODCM Appendix C CONTROL 3.11.2.1). All other terms remain the same as those defined previously. j l For the site, 4 potential modes of release are possible. The release i 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 1.2-1. For Modes 1, 2, and 3, the controlling location for implementation of ODCM Appendix C CONTROL 3.11.2.1.a is 0.35 miles NV. Inserting the appropriate X/0's from Tables 2.2-4 through 2.2-10 for this location, Expressions [2.?-3] and [2.2-4] become: For The Total Body Dose Rate:
-EV0 + 1.03E-4 O g + 7.35E-5 O g + 9.24E-5 gg +EKg [9.24E-5 Og vv1 tv1 i pv i evi Og + 1.03E-4 O g + 7.35E-5 0 < 9. .4-5 0 + 9.24E-5 O g vv2 7.35E-5 O g ] f 500 mrem /yr [2.2-5]
For The Skin Dose Rate:
+ E [L 3 + 1.lM g] l9.24E-5 Og + 1.03E-4 E [7.0E-10 L1 + 1.1Bg] Og evi i pv i i
I Og + 7.35E-5 O g + 9.24E-5 0 3 + 1.03E-4 0 + 7.35E-5 O g + 9.24E-5 0 + 9.24E-5 O g + 7.35E-5 O g ) $ 3000 mc-m/yr For the release Mode 4, the controlling location is 0.75 miles N. Inserting the appropriate X/0's from Tables 2.2-4 through 2.2-10 for this location, Expressions [2.2-3 and 2.2-4] become: O 2-37 ISSUE 3 I J
o .' i' '
- j> .BI-1 and 2 ODCH
;g s
7-2 For The' TotaliBodh Dose Ratet 4 EK
+ 3.95E-6 TE_Vgg g +;i;3,[3.95E.6.0j_1l+4.99E-6Oj. . 0 4.'26E-6 Oj.tv1 n.- -i< pv c .cv vv1 O: g _. + 4.99E16 O g + 4.26E-6 0 3
+'3.95E-6 O g + 3.95E-6~0'3 +
cv25 vv2- tv2 dv2 vv2
^
2 5 :. ., 3] J 500_ mrem /yr [2.2-7], f 4.26E-6Op,2 cp 1
'For The Skin' Dose' Rate: 1
-E + : E [L1 + 1.1Mj]"[3.95E-6 Og . + 4.99E-6 g
, - y
' .il[2.31E-6Lg+1.1B')O g
pv i __ evi-
+ 3.95E-6-O g + 4!99E-6.0 3 . +4.26E-6Oj i 4.26E-6 0 3- +.
,, (..
Op vv2- tv2' tv1-i - vv1; cv2 's, .
- 3.95E-6 O g g ).$ 3000 mrem /yr- . .
+ 3.95E-6 0(vv + - 4. 26E- cp O (2.2-8]
, dv m '
The' determination._.of -' controlling. location-.for _ implementation of'0DCM Appendix C CONTROL. 3.11.2.1.a')for noble gases 'is a- function of.the
, f ollowing l parameters.:
, s
- 1. Radionuclide mix and their isotopic release rate j j .2... Release mode
- 3. --Meteorology.
4 .. The incorporation of these: 3 . parameter.s into Expressions [2.2-3] and-
- 12.2-4) 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 vith the Stone and'-Vebster . Engineering Corporation computer code GAS 1BB vhich is similar to the NRC GALE code. ~
Inputs vere-based _on operating: modes of.the respective. plants. The~ code
-inputs utilized are presented in Appendix B. The source . term is 4
presented in' Tables '2.2-2a and 2.2-2b as -a funetion of: release type and-release point. L
~ The X/0 values ' utilized' in the equations for implementation of ODCM 7
Appendix-C CONTROL 3.11.2.1.a are based upon the maximum long-term annual avecage X/0 in-the unrestricted area. Table 2.2-3' presents the distances
.fron'_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 t beef animal. ' Tables 2.2-4 . through 2.2-10 present the long-term annual h- ' average;(X/0) values for the. Process Vent, Containment Vent, Ventilation L
Vent, Turbine Building Vent, and if applicable for BV_-2, Decontamination
~ Building: Vent, Vaste Gas Storage Vault Vent, and the Condensate Polishing Building Vent release points to.the special locations presented in TableL2.2-3. ~A description of their derivation is provided in f.
' Appendix A.
2-38 ISSUE 3 9 t i, .
m BV-1 cnd 2 ODCM For release modes 1, 2, and 3, dose calculations were performed using the ' highest calcult.ted 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 edues at the site boundary considered this contribution. From thest resulcs, the distance and sector associated with the highest calculateu site boundary dose vere selected as the controlling location. For Modes 1, 2, and 3 the controlling location is 0.35 miles NV. In Mc4e 1, the dominant' release is the Auxiliary Building Ventilation (BV-1
%9 tilation Vent and BV-2 Containment Vent). In Modes 2 and 3, the dominant release is a Containment Purge from the respective Ventilation Wnt 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.*-4 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 were used in the determination of the controllinghecehtorlocakionandwhicharetobeusedin Expressions [2.2-5] through [2.2-8] to show compliance with ODCM Appendix C CONTROL 3.11.2.1.2, are presented in Table 2.2-11. Values taken from Table B-1 of NRC Regulatory Guide 1 1 were multiplied by 1E6 to convert picocuries~1 109, Revisionto microcuries~ in Table 2.2-11. Values for V and B for the finite plume model can be expressed as and [2.2-10]. Values were calculated using the 4 3 shown in Equation [2.2-9] 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: K EII jk I A yg au 1E I [2.2-9] i" { j k 1 u) where: I = The results of numerical integration over the plume spatial distribution of the airborne activity as defined by the
) and atmospheric meteorological condition stability class "k" for a of wind speed particular vind(u) direction.
O 2-39 ISSUE 3
pr .
'BV-1 and 2 ODCM o
l- !; K = A numerical constant representing unit conversions. !-y'p ' 3
~. (260 mrad)(radians) (m ).-(transformation)- 16 sectors
-(sec)(Hev)(C1)' 2n radians 1E-6 Ci 3.15E7 see uCi yr:
- f. 2.1E4 mrad.(m ) (transformatiori)/yr(Hev)(uC1).
! .r'd . The distance-from-the release point.'to the receptor location,. L- meters.
-u = The mean vind spee'd assigned to.the "j" th vind speed class,
~
3 meters /sec. f jk = The jointstability and.kth frequency classof occurrence (dimensionless).of .the "j" th vind speed class. The number'of photons of' energy corresponding to the "1" th
~
A gg'.- energy group emitted per transformation-of the "i"'th p radionuclide, number / transformation. l Ey - The energy assigned to the "1".th energy group, Mev. u, = The energy ,y absorption coefficient in air for photon energy. H y , meters The.V ~ factor is. computed with : conversion from air dose to tissue depth l ' dose,3.thus: K E I E!jk Ayg. u, E1 I,-uT d [2.2-10]
-V i = 1.1 r_d j k 1 u) where:
u T The tissue energy 2 absorption coefficient for photons ; of energy Ey , em /gm. { Td .- The tissue density 2 thickness taken to. represent the total body dose (5gm/cm ). l 1.li. The ratio of the tissue to air absorption coefficients over the l energy range of photons of interest, mrem / mrad. I i l i ! 2-40 ISSUE 3 l l t F.
w 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 lives greater _ than 8 days released in gaseous effluents from the site shall be limited to 1,500 mrem /yr to any organ. Based upon NUREG-0133, the following basic expression is used to show compliance with ODCM Appendix C CONTROL 3.11.2.1.b: IPh [(X/0), O , g+ (X/0)y Ogy] f 1,500 mren/yr [2.2-11] i where: P h = Dose parameter for any organ T for 3each identified radionuclide "i", mrem /yr per uCi/m O gs - The release rate of radionuclide "i", in gaseous effluents l from elevated releases, uCi/sec. 0 3y - The release rate of radionuclide "i", in gaseous effluents from ground level releases, uCi/sec. (X76)8 = The highest calculated annual average relative concentration at the unrestricted area boundary for elevated 3 releases, sec/m (f76)y - The highest calculated annual average relative concentration at the unrestricted area boundary for ground 3 level relcases, 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 Appt dix C CONTROL 3.11.2.1.b, Expression [2.2-11] is nov expressed in terms of the actual release points for the site.
+
EPh [(X/0)py O g pv + (X/0)cy 0 3 cyl + (X/0)yy O gv ,1 + (X/0)tv 0 3 tv1 i (X/0)cv O g ev2 "" +( I tv Og +( }cP i cp2 dv vv2 2 Og + (X76)yy 0 ) $ 1500 mrem /yr [2.2-12] where: (X/0)PV = forHighest calculated annual average relative. oncentration releases from the Process Vent, sec/cf. (X76)cv = Highest calculated annual average relative 3 c ncentration for releases from the Containment Vents, sec/m 2-41 ISSUE 3
h . BV-1 gnd 2 ODCM l (X/0)yy - Highest calculated egnual average relative3 c neentration for l n- releases from the Ventilation Vents, sec/m
^I]'
l (X/0)tv - Highest calculated annual average relative concentration or releases.for the Turbine Building 3 Vents, sec/m (X/0)cP = Highest calculated annual average relative' concentration for releases f r the BV-2 Condensate Polfshing Building 3 Vent, sec/m
-(X/0)dv ' Highest calculated annual average relative concentration
. for releases f r the BV-2 Decontamination Building 3
Vent, sec/m (X/0)"V -Hikhestcalculatedannualaveragerelativeconcentration for release fr m 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 cv1 Containment Vent, uCi/sec. Og - Long-term release rate of radionuclide "i" from the BV-2 ! cv2 Containment Vent, uC1/sec. I J' 0I - Long-term release rate of radionuclide "i" from the BV-1 D vv1 Ventilation Vent, uCi/sec. Og - Long-term release rate of radionuclide "i" from the BV-2 i vv2 Ventilation Vent, uCi/sec. j i 03 - Long-term release rate of radionucl:.de "1" from the BV-1 l tv1 Turbine Building Vent, uCi/sec. l Og = Long-term release rate of radionuclide "i" from the BV-2 tv2 Turbine Building Vent, uCi/sec. Og - Long-term release rate of radionuclide "i" from the BV-2 l cp2 Condensat.e Polishing Building Vent, uCi/sec. l Og - Long-term release rate of radionuclide "i" from the BV-2 dv2 Decontamination Building Vent, uci/sec. Og - Long-term release rate of radionuclide "i" from the BV-2 vv2- Vaste Gas. Storage Vault Vent, uCi/sec. All other terms are the same as those defined previously.
/")
(/ 2-42 ISSUE 3
e BV-1 cnd 2 ODCM The Turbine Building Vent, Condensate Polishing Building Vent, Decontamination Building Vent, and Vaste Gas Storage Vault Vent are not normal radioactive release points. These release points are included only for use if radioactive releases via these vents are identified in the future. In the calculation to show compliance with ODCH Appendix C CONTROL 3.11.2.1.b only the inhalation pathway is considered. Values of the organ dose parameters, P were calculated using methodology given in NUREG-0133. For the h,hild c age group, the following equation was used for all nuclides. The Ph, values are presented in Table 2.2-13. [2.2-13] Ph - 3.7E9 DFAh where: 3.7E9 - Breathing rate of child (3,700 m3 /yr) x unit conversion factor (IE6 pCi/uCi). DFA = The organ inhalation dose factcc 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. Expressf t n [2.2-12] becomes:
+ 9.24E-5 O g + 1.03E-4 O g + 7.35E-5 O g + !
EPh [7.00E-10 Og cv1 vv1 tv1 1 pv 9.24E-5 0 + 1.03E-4 0 + 7.35E-5 O g + 7.35E-5 O g ep2 0 + 9.24E-5 O g f 1500 mrem /yr [2.2-14] The determination of the tc.9 ralling location for implementation of ODCM Appendix C CONTROL 3.11.2.1.b for raeloiodines and particulates is a function of the same 3 parameters as for noble gases plus a fourth, the actual receptor pathways. The incorpcration of these parameters into Expression [2.2-12] results in the respective equations for each release mode at the site boundary controlling locations. The radionuclide mix was again based upon the source terms presented in Tables 2.2-2a and 2.2-2b as a function of release type and release point. In the determination of the controlling site boundary for each release mode, the highest 2 site boundary X/0 values for each release point were utilized in conjunction with the radionuclide mix and the release rate for each release point to determine the controlling location. The P values are presented in Table 2.2-13. h O 2-43 ISSUE 3
- u. ,
i BV-l and2 ODCM- l
,e '
The .X/0' values in) Expression' [2.2-14]~ vere obtained from Tables 2.2-4 L, through 2.2-10.
.A description of;the' derivation of the X/0 values ~is provided.in 4 Appendix.A..
t d 1
)
l
'l e
1
- h. -
i i i 2-44 ISSUE 3 f
BV-1 end 2 ODCM TABLE 2.2-1 MODES OF GASEOUS RELEASE FROM BEAVER VALLEY SITE VENTS FOR IMPLEMENTATION OF 10 CFR 20 AND 10 CFR 50 RELEASE POINT MODE 1 MODE 2 MODE 3 MODE 4 2 BVPS4 - BVPS-2 Main Cond. Air Same As Same As Same As Process Vent (pv) Ejector, Vaste Mode 1 Mode 1 Mode 1 And Gas, Contain- Containment ment Vacuum Purge BVPb-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.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 Eame As Vent (vv2) Areas Purge Mode 1 Mode 1 1 BVPS-2 Containment Aux. Bldg. Same As Same As Same As Vent (ev2) Ventilation Mode 1 Mode 1 And Mode 1 Contajnment Purge BVPS-2 Turbine Bldg. Turbing Bldg. Same As Same As Same As Vent (tv2) Exhaust
- Mode 1* Mode 1* Mode 1*
BVPS-2 Condensate Polishing Bldg. Vent (cp2) 1 , , , , BVPS-2 Decontamination Bldg. Vent (dv2) BVPS-2 Vaste Gas * * *
- 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 Continuous elevated meteorology is applicable 3 Mode established by purge from one unit, all other release points remain same as Mode 1 2-45 ISSUE 3 l 1
fE BV-1 cnd 2 ODCM TABLE 2.2-2a BV-1 RADIONUCLIDE HIX FOR GASEOUS EFFLUENTS 7'~S ( ,) (Ci/yr)** TURBINE CONTAINHENT VENTILATION BUILDING VENT VENT VENT PROCESS VENT
~
Long Term And-AUXILIARY TURBINE MAIN CONTAINHENT GASEOUS CONTAINHENT BUILDING BUILDING CONDENSER / VACUUM VASTE NUCLIDE BUILDING VENTILATION VENTILATION AIR EJECTOR PUMPS SYSTEM Short Term Long Term Long Term Long Term Long Term Short Term Kr-83m 2.2E-02 4.2E-01 3.9E-05 2.7E-01 3.7E-04 0.0 Kr-85m 1.5E-01 1.9E+00 1.7E-04 1.2E+00 3.9E-03 1.2E-02 Kr-85 6.1E+01 2.5E+00 2.3E-04 1.6E+00 7.2E-01 2.3E+02 Kr-87 5.4E-02 1.?E+00 1.1E-04 8.2E-01 7.8E-04 0.0 Kr-88 2.4E-01 3.8E+00 3.5E-04 2.4E+00 5.0E-03 0.0 Kr-89 4.7E-04 1.2E-01 1.1E-05 7.7E-02 3.1E-06 0.0 Xe-131m 7.4E-01 1.3E-01 1.2E-05 8.0E-02 1.3E-02 8.3E-01 Xe-133m 8.9E-01 8.9E-01 8.1E-05 5.6E-01 2.2E-02 0.0 Xe-133 8.9E+01 3.6E+01 3.4E-03 2.3E+01 1.9E-00 8.2E+00 Xe-135m 4.5E-03 3.2E-01 2.9E-05 2.0E-01 4.4E-05 0.0 Xe-135 7.0E-01 4.5E+00 4.2E-04 2.8E+00 1.9E-02 0.0 r~~x Xe-137 1.0E-03 2.1E-01 2.1E-05 1.3E-01 6.3E-06 0.0 9.7E-05 6.6E-01 1.2E-04 0.0 (), Xe-138 I-131 1.5E-02 1.2E-03 1.1E+00 4.6E-02 6.5E-04 2.1E-02 4.7E-04 0.0 I-132 0.0 0.0 0.0 0.0 2.5E-06 0.0 I-133 2.0E-04 6.7E-02 8.7E-04 3.0E-02 8.4E-05 0.0 I-134 0.0 0.0 0.0 0.0 4.7E-07 0.0 I-135 0.0 0.0 0.0 0.0 1.4E-05 0.0 Co-58 7.5E-04 6.0E-02 0.0 0.0 1.6E-05 0.0 Co-60 3.4E-04 2.7E-02 0.0 0.0 7.4E-06 0.0 Hn-54 2.2E-04 1.8E-02 0.0 0.0 4.9E-06 0.0 Fe-59 7.5E-05 6.0E-03 0.0 0.0 1.6E-06 0.0 Sr-89 1.7E-05 1.3E-03 0.0 0.0 3.7E-07 0.0 Sr-90 3.0E-06 2.0E-04 0.0 0.0 6.6E-08 0.0 Cs-134 2.2E-04 1.8E-02 0.0 0.0 4.9E-06 0.0 Cs-137 3.8E-04 3.0E-02 0.0 0.0 8.4E-06 0.0 C-14 1.0E+00 0.0 0.0 0.0 0.0 7.0E+00 Ar-41 2.5E+01 0.0 0.0 0.0 0.0 0.0 I l l
- Containment can be purged via Ventilation Vent, Containment Vent, or Process Vent
** Reference 2.1.2 f (x,_s'
)
***See Section 2.1.1.1 j
2-46 ISSUE 3
p -
- BV-1 rnd 2 ODCM-TABLE 2.2-2b
.BV-2 RADIONUCLIDE MIX FOR GASEOUS EFFLUENTS (C1/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 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 8.33-01 Xe-133m 7.6E-01 8.9E-01 8.1E-05 5.6E-01 2.2E 0.0 Xe-133. 8.4E+01 3.6E+01 3.4E-03 2.3E+01 1.98-00 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 0.0 Xe-137 0.0 2.1E-01 2.1E-05 1.35-01 6.3E-06 0.0 Xe-138 0.0 1.1E+00 9.7E-05 6.6E-01 1.2E 0.0 I-131 2.7E-05 4.6E-03 6.5E-04 2.1E-02 4.7E-04 0.0 I-132 0.0 0.0 0.0 0.0 2.5E-06 0.0 I-133 7.6E-06 6.7E-03 8.7E-04 3.0E-02 8.4E-05 0.0 I-134 0.0 0.0 0.0 0.0 4.7E-07 0.0 I-135 0.0 0.0 0.0 0.0 1.4E-05 0.0 Co-58 7.5E-02 6.0E-04 0.0 0.0 1.6E-05 0.0 l Co-60 3.4E-02 2.7E-04 0.0 0.0 7.4E-06 0.0 {
Hn-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 l Sr-90 3.0E-04 2.0E-06 0.0 0.0 6.6E-08 0.0 i Cs-134 2.2E-02 1.8E-04 0.0 0.0 4.9E-06 0.0 i 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 Vent
** Reference 2.2.3 1
***See Section 2.1.2.1 2-47 ISSUE 3 I
3 E _ U . S S
. 5102 2018 3693 5033 sy I 2636 3985 ir V 9696 2562 a E 2,4,7 5, -
9,6,9,6, 4,4,4,4, 6,5,3,2, ed T L -
- N E 22 1 1 1.1 1 2122. 3311~ tsm nat E
D eeo I mlb S D - ne ire _ E N 7988 6752 9311 6523
.R U 2300 5733 8220 5034 a t O 5,6,7 7 7 5,8,4, 1,2,2,3, 5,6,4,1, tdi R .
neS G 22 111 2122 3311 ot cav. _ _ 2es 0904 7028 6014 V
. 956 102 0126 8630 6967 VltEn B i S
E L 9,6,5,- 2,6,4,9, 4131 4,5,6,6, 2222 1,5,4,7, 4343 d .op u T L E 327 nr - N TA I AM aee ws O EI 1oa . P MN D VTe A 281~ 5790 3746 8509 E M I 544 6797 5114 8075 Bgeg l . S A O R 1,8,7,- 2,5,2,7, 2,3,4,4, 0,6,5,9, nrn i G 427 4131 2222 4343 ei E hl rd L E R 8351 0986 90 722_ toel nCt u ohi _ _ 51' 036 e oB O T' T V E
. 1347 4
; 0,5,6, 0946 2,8,8,1, - 8, 2, - 5, 8, 2, 205 e1 w
tVln l g u _ 4606 4250 53 S A L t G T C G E 2 1 211 eBai b - thti eos h _ P K 5597 63 .940 nt l , E* L D 1604 19 245 i eo CS I N 5762 6627 omlP M EE RU M U O 6,2,7,8, 2,8,7,5, -
- 6,9,- - 5, 9, 4, pob rrae R 4606 4259 52 205 C L 211 ef ct D 3 LA G 2 t ia O
2
- AV U )
ndl eepns 8 DQs 6 8 84 90 1 51 crpe 4 _ 2 I/r . 39 4 .uad - _ hasos 2 9 44 VXe es n 2 E L I DLe t N W - 5, - 9, 8, 2, 5, 5, 53, 92 1, 5, -- - 54 t eiCr p 1 B A nam IU( O C M 7 6 55 33 m m ed _ T 4 K oesne rraas V-B EMA L D N 1 5 93 77 2 88 f ae l ge a M IR I M U .4 6 _25 44 8 13 deenl KO AF O R - 7, - 0, 7, 0, 3, 3, 1, 1,5,- - esrie ra dr 7 - 55 33 5 54 M G 7 uedl slnid G aeuun _ N 3118 2913 2093 5055 eroBu r o I V 2605 2163 7636 3918 m T 6,5,4,2, dGer ng I E L E L 4,4,9 6, 9,6,9,9, 3,5,4,4, ee M E 1111 3222 3311 rt .i I BN 22 1 aa br L AE vtre TD senuh _ F ER el eTt _ O GA D N 3444 9758 8711 6544 seV 2 o _ EG 7733 3120 5066 a S V U 2027 9,5,8,7, ers l E C O R 6,7,7 6, 1,3,2,3, 5,6,4,4, 3311 l osVl efeBA G 22 .1 1111 3222 r c N A so)) _ T der 12 S 1252 4640 1620 ncP( ( I V
. 3274 1329 5711 5276 8782 un oae .
D E 4633 56P9 d, 2, 5, 6 6644 rth: Y L 111' gsts R E i e A D 7491 0178 rDos o ta 9228 6712 4065 f e M I
) 7944 4006 8636 6755 .el O 2 5744 5677 8 0,4,5 ssl e B D ( e gb r E
N U 11 cna _ nicd _ T O 5555 0555 5055 adin I R 0500 4775 5739 8154 tllu F G ) 7399 6866 si p o - 1 ( 6544 5556 894,5 iupr DBag _ 1
- R :
4- DI O E _ R E E E E W W W W T 0 NC NEN SES SWS NWN O _ 0IE EESS sSSW WWNN N DWS NNNE
qe 3 E U S e S I
- 0000 6793 8000 0000 50 8636 2146 4209 5006 2520 7565 8080 5276 45 5265 2111 0000 0113 11
- 0000 9285 9000 0000 05 6356 5166 9912 6006 6842 8676 9116 4245 44 S 2111 0000 0123 6496 E 11 L 0513 0000 0000 I - 0000 6005 M 50 8918 4130 0895 4198 0898 2576 6723 S N 34 1000 1124 7088 E I 3211 22 U
L , 0000 0000 A N - 0000 0007 0269 9439 2000 VSS O 05 4974 3019 4946 3001 EN I 2633 QCO T 33 9540
/NI A 4222 1110 1135 231 _
XAT C TA
,SC O 2454 3371 0872 0000 L -
50 8450 8474 1437 7235 LID EDI L V O 23 5333 1111 2247 1123 ELL R 1341 LAO T 4350 0000 IR N - 8014 9511 D CI C 05 6681 4949 8383 4606 N e. tf C 2121 2350 5057 - owcC U R t u 22 7444 1 1451 G R u. T 5040 1040 0000
,O t - 0290 F O 50 8697 6153 1896 0282 E I_ T 12 1665 3333 4494 1996 M
C D 6,N a S RE S. 1 1 3572 O 4 2
- ESS VA
)m N t
u 05
- 0005 7865 8696 0184 7300 7815 0000 0108 9
2 AED /c A d n a 2 E L B AR U NL) LN e LEA s
, 7 T
S I D 11 8019 111 5864 6555 7500 6763 5928 12 9230 4924 0004 1 4 2 9 1 A NE3 E- 50 9618 5022 7999 3326 T AVE2- l ( 3221 1111 1124 0068 V- 01 122 B SL T 2 5192 9000 0000 ND 0000 ENE 5 9957 9003 5007 VUL - 3803 3420 8566 9168 1914 OB 00 2111 112 6275 Tt A NGT E 11 - 0201 1000 0000 MSN E 0600 5112 6970 8393 7703 NUI IC IO 2669 5939 5002 AUD SN 3792 3 111 1409 _ TNE EE 1 44 2 NII RD - OTF 720 1240 7100 0000 CNICT T - 242 9975 5337 0754 2CN S AIL E R ENA 661 - 1626 5627 11 3005 1441 DRD w MAM N A m (I m KT 0054 6462 0042 1197 00 45 000 162 1' LA 3021 9093 70 867 r i IO - 19
- 181 V- F MG 5200 1300 B 0 7 40 00 0 00 L
A KN 0 0 93 90 2 40 51 U LO 8 90 07 I D IC M
- 2-1 0 01 33
- 57 90 3
V I D N 0200 6208 0100 0000 N EE 8945 1976 4393 7700 I ELD 3639 5043 GBR 2672 6666 1496 EAA 1 41 11 1 VTG
- 0208 5181 5830 0000 ENY TUR IOA SBD 5025 2508 1 1 41 53 542 7323 2226 1
8742 7820 2493 9 ND - . E E E N W W N WNCR E NNN OIEO NEN SES SWS DWSS NNNE EESS SSSW WWNN
i N - _ a% r i.." 3
^y _
/
s E U S S H ;t i I o
'. ,'- 0000 4161 5 0' 00 0000
_ o- . 50 7378 7363 8700 4001 4620 7565 8093 0683
- s. . 45 2111 0000 0113 6386
.11 ii 2 -
0000 3008 000'0 0000 05 0209 8398 5638 6006 0228 0993
' , S
. 44 9952 8676 0000 1123 7517 E
L I .. --
. 1 2111 :
0000 0203 0000 0000 _12 f _ M 50 1283 7463 6762 4006 S _N .34 8399 0898 2690 4434 E . I 3211 1000 1125 8329 i U 23'
, - ~
C_LVSSEN . A N - 977'1 4504 7769 0000 . ( . 05
. 6844 3020 5061 4756 I
)CO T .33 4222 1111 1236 0891 m ANI XAT A
C 1231 TA D : - - lSC I -- 2934 0948 3619 2674 0000 2418 LIO 50 5671 9484 EDI L 3605. V O 23 6333 1111 2248 ELL B 1351 LAO I IR N - 5991 1532 4080 0000 U DCT I . 05 7 9. ;0 3 6050 0 6 3 4._ 7560 NEN C 7861 UPO OSC .E 22 8454 2222 33611 1462 R H 0000_ GRD I
' 0111 7350 6953 8275 8800 4246 5002
',OE R
E FTr O I 50 3776 3333 4516 6302 G 11 3703 2 M ,y 12 1'- - 1 C AS ) S D '5 ' RE E C - ESmh t C -- 0000 7978 6700 5847 0000 3008 2 . 2 VA N 05 7272 5539 . _ AED c/ A T 656$ 7887 0042 0 5 2E
- LEA hR LN e s -
S I 11 2220 2111 12 6265 11' 2 L u ,7 D ' 3683 0000 B l eL) 9086 7957 E3 E - 1 A 50 T-- t AV - 1 9240 7133 0341 2904 V- E2 ( 01 4322 1111 2236 3651 B SL 1231 _T 2 - 0000 ND 0000 0720 0000 _ EME VL L
~
5 6965 6667 7047 5001 1120 OB 00 7853 1788 2404 NRA 2111 1~ 1123 7486 - OGT 11 I 0000 TSN 0500 0470 8000 . AUI E 9924 8621 3974 0600 - IO IC IUD SN 5700 8770 6252 8811 TNE EE 1 65 3' 1 212 1472_ NII RD 21 ETF 9489 0800 0000 VMI 684 002 9681 1084 7681 X T TL ; 2C N S AI E R ENA 771 - 1727 6730 12 4878 1441
~D R' D O MAM N) t I I 1
Af( P E C
.KT
.LA 0090 8567 9122 0002 9038 9203 00~
58 89 000 224 958 E IO 19
- 191 V-B R .MG 5201 1310 1 L 0 8 00 00 0 00 A . KN 4 - 2 38 04 3 00 LO 00 30 2 60 U
D
~
IC
- - _12 - 8 0 11 34 6 05 I M 13 V
I D - N 0600 6471 5800 0000 N 0696 6624 6074 0604 I EEE GBR LD 5773 6777 3752 8823 m EAA 1 51 12 1468 . VTG 2 - 8720 0000 ENY TUR IOA
- 0500 2220 5631 8031 7839 6332 2861 3220 5805 4934 m _
SBD 1 - 11 '2 3503 _ 1 _ MDN C- R E E .E E W W R N _ OIE]t i EN SES SWS NWN _ DWSI ' Nl@NE EESS SSSW WWNN . 3 c . m 3 _.
a r, 3 E U S S O
~
I 6000 0766 5471 5139
- 4070 0384 5878 9389 50 8151 2765 6697 7765 45 0111 1000 0000 0000 S 6000 0016 4700 1145 E - 9981 8314 7 0 5 '2 5900 L 05 9287 2886 7819 8787 I
M 44 0111 1000 0010 . 0000 . N 0000 0007 0400 0639 e S I - 0393 3683 1361 2804 z E 50 2400 7119 1802 1698 i U , m L 1122 1110 1011 1000 i ASS N C 34 x VEE I 0000 0000 0010 1000 a CC T - 8782 9667 8306 4115 m QNI A 05 4786 1341 3024 7120 s
/AT C XTA O 33 1122 2111 1111 0111 Q
,SC L /
IO - 1982 3059 7674 4499 X EDI L 50 9662 8208 4556 8864 S O e ALL R 23 1233 2221 2111 1111 s EAO T a L I R' i - 6785 7098 7176 0003 e ECI Q 05 5237 6075 3173 5539 l e REN PC C 22 2354 3322 3212 2221 r DSC E 0856 8123 8766 l E H - 2702 e TRD I' 50 3410 2740 9115 6069 ve AOE VFT 4333 3332 F C D I 12 5576 6444 l M T
,E 0000 0000 0000 0900 C FSL S - 0000 0000 0000 0070 d n
i D 6 EE E 05 7838 6473 9330 3812 C ,SS m C 2922 8159 4099 2010 u 2 EA N 11 o r 2 GED /c A 86 7 7876 8444 6005 1 d n a 2 2 ALN e REA s ER V , 7 T S I D - 0000 0061 0013 0000 0000 0004 1744 0000 0000 1000 5198 0900 0450 2568 7007 g e r e 5 2 O 1 AL) -E3 E f. 0 1513 h V-G LV AE2
- 1
( 01 3400 21 7279 11 8957 11 8006 w B UL n N 2 9595 4800 0000 7245 o ND 8763 2073 6007 4083 i 1270 9008 1201 t ANr Ur - 5 2101 0000 0043 7113 0000 a ton 00 c NRA 0000 0000 0660 0000 o EGT 23 l V 0030 y SN E 0055 9952 0000 0097 0000 1205 9379 r SUI 3893 4505 a SO IC 7805 3287 EUD SN d CNE EE 6600 8179 6534 2206 n OII RD 1 u RTF o PNI 741 7050 6178 2371 b OT T - 216 8602 0649 0568 2CN S AIL e E R ENA 261 - 2137 6333 2211 i t DRD m MAM 1 s NOI 0000 0007 20 354 AF( 602 t 1 w KT LA 1357 9437 7735 8523 76 85 132 a m IO - 02 000 e V- i MG 1101 2410 u B 00 00 0 40 l J, 0 0 a P KN 1 4 36 94 2 68 v u LO 2 21 41 - 4 77 i v IC M
- 6 1
- 1 11 32 1 01 Q V /
I N 0040 0000 0000 0040 X D EE 2979 0099 3683 6105 7693 9376 4504 e N :LD
- 7600 s I b.
- BAAR 66 9 8177 3334 2206 a t
VTG 1 e l 2000 0000 e
* - 8811 6256 0006 9378 r ENY TUR IOA SBD 0211 0000 0000 3470 0002 0000 4402 7651 5760 2300 0000 0000 d
t a e O
- ve ND - E E N W N N l WNCR E E E OIEO NEN SES SWS NNN DWS' I NNNE EESS SSSW WWNN r,
~
~
k f-
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'0000
' ' 5482 6000 0000
- 8957 3257 6450 9008 3520 7565 8082 7979
- 5. ~0' .
1- 45 2111 ' O000 0113 5275 11 ~ . 1 0000 '1196 0000 0000 7787 7277 2375 6005
- S 05 7842 8,676 0217 7069 E
L 44 2111 000O 1123 S E I M _
~
6506
.1 2 ' .
U 0000 0 0 5'8 0000 0000 L N .'- 4550 6241 3273 4008 I 50 6299 0898 2688 0018 A - V~ T 34 3211 1 0' 00 1124 8208
.23'
)SS AEN G I _~
5828 2382 3043 2000 XCO T 05 4743 3010 5059 8768
,NIT A C
LBA ESC D I 33 4222 1111 1235 l 9660 231 VIO -~ 5649 7615 7749 C000 EDL L 50 1560 8484 1550 4696 L O LL 23 6333 1111 2248 2354 DAO M 1341 I 3 CM N t O -
- 8953 5077 4600 0000 uEN RPG C 05 1792 5049 9418 5232 G. S O E 22 8444 2221 2360 6409 H 1 1463
,RD t EOE 0445 5941 9300 0000 1 GFT O 50 7928 7164 2046 5489
_ A C I R',E 12 2675 3333 4505 3588 c ESL ') S 'l 11 3682 VEE E 7- ASS n C 0009 2621 3100 0000 A
=
2 A N - 5418 3317 1323 9009 LED c 05 2 _ ALNh B 0129 6565 7876 3405 5 UEA s S 11 211 12 5044 _ 42 E i -
@R , I 11 2 _
L l 7 D
~
B AL) 6804 6 1. f.,1 6326 00.A0 E-i E3 - 50
- B SV - 1 2839 6122 8113 1894
- TE NL E
- 2. ' ( 01 4221 1111 1235 1172 1229 _
2 - . ~ VO E . 5 0000 2852 0000 0000 _ - GGL NOB 00
- 4125 9534 9041 6007 IR 4631 9677 0270 3125 DGM L
2111 1113 6375 11 ISN UUI 0' 400 0569 7000 0000
- - E 8683 7206 2988 9504 BO - IC
_ EME NII J D
.RD SN EE 4736 1 54 5779 3
6040 212 6429 1429 2 IIF BNI 433 8556 0300 0000 _ R X T UCN [
' E S
R TL AI ENA 782 661 - 9289 1726 0,711 6639 9590 3437
- RD O MAM 11 1441 2OI I '
F( P' 0080 0004 00 000 D KT - E 4368 8028 05 702 N C LA 7122 9103 85 818 _ A E IO - - - -191 _ i l R MG 5201 1310 19 L 0 9 00 00 0 00 _ V- _ Ts .K 3 2 27 19 1 00 B U LN 8 00 38 0 15 D I IO MC
- 2 1
- 11 33 6 02 i
V I - 13 D N 0700 9566 4300 0000 N EE 0392 4201 6788 9500 I ELD GBR 4713 6777 3640 6461 _ EAA 1 51 12 1417 _ - VTG 2
- 0061 7180 7710 0000 O r ENY TUR IOA SBD 5264 0098 11 ~
0714 6343 2 9 4' 9 3225 1 4457 6034 2472 ND - NNCR E E E E W W N N _ OIEO NEN SES SWS NNN NNNE EESS SSSW WWNN DWSI' - 2 _
3
. E U
S S O 0000 6793 8000 0000 I
- 8636 2146 4209 5006 50 2520 7565 8080 5276 45 2111 0000 0113 5265 11 0000 9285 9000 0000 S
T I M S E 05 44
- 6356 6842 2111 5166 8676 0000 9912 9116 0123 6006 4245 6496 11 I L 0000 0513 0000 0000 L I - 8918 4130 0895 6005 S M 50 4198 0898 2576 6723 E E T U N 34 3211 1000 1124 7088 A L I 22 R A E
V , 0000 0007 0000 0000 N - 4974 0269 9439 2000 S Q C 05 2633 3019 4946 3001 O
~
/ I D X s:. NS T 33 4222 1110 1135 9540 E ,hI uO A C
231 T LAT D - 2454 3371 0872 0000 I S ETA VSC T 50 8450 8474 1437 7235 EIO L 23 5333 1111 2247 1123 O LDL O 1341 I
' R 4350 0000 DLL I - 8014 9511 N NAO R 05 6681 4949 8383 4606 O UIR O I OCI C 22 7444 2121 2350 5057 T
U REN GPO E 1 1451 B ,SC H - 0290 5040 1040 0000 I T 50 8697 6153 1896 0283 R T erar O 12 1665 3333 4494 1 996 N O GM A R u I
' 1 1 3572 M C E , 0005 8696 7300 0000 C VS - 7865 0184 7815 0108 D
O 82 A SSE N )m 6 N 05 8019 6555 6763 9230 2 V-
- 2. B LA A D /c A
T 11 111 12 4924 1 3 d a n 2 EO L BN F UN N NF A L) N e A s 7 S I D 50 0000 5864 9618 0000 7500 5022 0000 5928 7999 0000 0004 3326 5 2 O 1 AC TE3 E 01 3221 1111 1124 068 TI NV - 1 ( .22 V- T EE2 B A VL 0000 L 2 0000 5192 9000 0000 U GD 5 C L NNE - 3803 9957 8566 9003 9168 5007 1914 IUL 00 3420 A DOB 2111 112 6275 C LRA 11 IGT N U 0600 0201 1000 0000 I BSN - E 5112 6970 8393 7703 UI IC D NO SN 3792 2669 5939 5002 E OUD EE 1 44 3 111 1409 S INE RD 2 U TII ATF 720 1240 7100 0000
- NNI T - 242 9975 5337 0754 IOT AIL Y
L MCN A E S u ENA MAM 661 - 1626 5627 11 3005 1441 - N TRD w O NOI 0050 0042 00 000 OF( KT 6464 1197 45 162 N O C E w LA IO 3022 9093 70 867 I D 9 MG 5201 1300 19 181 T P A 2 7 40 00 0 00 i L K 0 0 93 90 2 40 w V- A LN 8 90 07 51 wB U D IO MC
- 2 1
- 0 01 33
- 57 90 N I 3 I V I N 0200 6208 0100 0000 R D EE 8945 1976 4393 7700 N LD M I h BR 2672 6666 3639 5043 AA 1 41 11 1496 WTG 1 0000 0000 0000 0000
- 0208 5181 5830 0000 ENY TUR IOA SBD 5025 2508 1 1 4174 5322 7323 2226 1
8742 7820 2493 O ND N WNCR E E E E N W W OIEO NEN SES SWS NNN DWSI ' NNNE EESS SSSW WNNN L
3 - E U _ S 0000 6793 8000 0000 S I -
- 8636 2146 4209 5006 50 2520 7565 8080 5276 45 2111 0000 0113 5265 11 0000 9285 9000 0000
- 6356 5166 9912 6006 05 6842 8616 9116 4245 S - .
0123 6496 T 44 2111 0000 11 I S M E 0513 0000 0000 I L 0000 L I - 8918 4130 0895 6005 M 50 4198 0898 2576 6723 E S 1124 7088 T E N 34 3211 1000 A U I 22 R L 0000 0000 A , 0000 0007 E S O D V QSS
/ EN N
O I T 05 33 4974 2633 4222 0269 3019 1110 9439 4946 1135 2000 3001 9540 XCO A 231 E NI C 0872 0000 T ,AT O 50
- 2454 8450 3371 8474 1437 7235 I LTA L S ESC 1111 2247 1123 VIO L 23 5333 O EDL O 1341 T L R -
4350 0000 _ LL T - 8014 9511 DAO N 05 6681 4949 8383 4606 _ N I NIR UCT O C 22 7444 2121 2350 5057 r f t OEN RPO E 1 1451 - B GSC H - 0290 5040 1040 0000 I T 50 8697 6153 1896 0283 R ,RD 4494 1996 T N EUE GET O T 12 1 1665 3333 1 3572 O A . C R ,CE S 0005 8696 7300 0000 . ESL ) E - 7865 0184 7815 0108 92 VEE C 05 9230 _
- V-ASS A m N A 11 8019 111 6555 6763 12 4924 _
- 2. B LED /c T 1 4 5
2 ALN e S 0000 0000 - F UEA s I 0000 0000 2 EO NR D ~ 5864 7500 5928 0004 L N , 7 50 7999 3326 BN AL) 9618 5022 1111 1124 0068 _ AO E3 E- 01 3221 122 - TI TV - 1 ( T NE2 0000 _ A EL 5192 9000 0000 L V D 2 0000 - U 5 9957 9003 5007 C TNE 00
- 3803 3420 8566 9168 1914 L LUL 112 6275 _
A UOB 2111 11 . C ARA _ VGT 0201 1000 0000 _ N 0600 _ I ESN E 5112 6970 8393 7703 - GUI IC 5939 5002 D AO SN 3792 2669 - E RUD EE 1 44 3 111 1109 RD 2 S U ONE TII _ STF 720 1240 7100 0000 T - 242 9975 5337 0754 Y SNT ACN I S AIL ENA 661 - 1626 5627 3005 L G E R MAM 11 1441 _ N RD w 0050 0042 00 000 - O EUI TE( KT 6464 1197 45 162 LA 3022 9093 70 867 t O I S A W E m IO MG 5201 1300 19
- 181
_ T < t 00 0 00 _ A 2 7 40 90 2 40 M L K 0 0 93 51 R V- A LN 8 90 07
- 57 --
D E B U D IO MC
- 2 1
- 0 01 33 90 ._
3 N I _ I V I N 0200 6208 0100 0000 R D - EE 8945 1976 4393 7700 - D N ELD 3639 5043 I GBR 2672 6666 EAA 1 41 11 1496 1 VTG 0000 0000 0000 0000
- 0208 5181 5830 0000 ENY 8742 TUR 5025 4174 5322 7323 2226 7820 IOA 2508 SBD 1 1 1 2493 ND - E E E W W W W HNCR E NEN SES SWS NNN OI EO NNNE EESS SSSW WWNN DWST
3 - 3 2 E U S S O I 0000 5482 6000 0000
- 8957 325 6450 9008 50 3520 756 _. .
8082 7979 45 2111 0000 0113 5275 11 S _ . T 0000 1196 7277 0000 2375 0000 6005 I - 7787 M S 05 7842 8676 0217 7069 I S E 1123 6506 L E L 44 2111 0000 U I 12 E L M 0000 T A 0000 0958 0000 A V N - 4550 0241 0898 3273 2688 4008 0018 R 6299 Q I
~,
30 E / 34 3211 1000 1124 8208 S X N 23 O , 5. S C 2000 D r. N I - 5828 2382 3043 L CO T 05 4743 3010 5059 8768 E ENI A T I VAT ETA C O 33 4222 1111 1235 96G0 231 S LSC L 0000
- IO - 5649 7615 7749 O DDL L 50 1560 8484 1550 4696 I
' N O 2248 2354 ULL R 23 6333 1111 N OAO T 1341 O RIR N I GCT O - 8953 5077 4600 0000 5232 T EN C 05 1792 5049 9418 U ,PO B ESC m 22 8444 2221 2360 6409 1461 I G 1 R A R u. u 0000 T RO - 0445 5941 9300 N EF 2046 5489 O V n.
t O I 50 7928 7164 M C C A ,E SL ) S 12 2675 1 3333 4505 11 3588 3682 D 02 LEE E C 1 ASS m C 0009 2621 3100 0000 V- UA N 5418 3317 1323 9009 2
- 2. B Nr D /c A 05 5
d n a 2F E L O Nr N e A r-F A s T NL) - 7 T S I D 11 0129 211 6804 6565 6167 7875 6326 12 3405 5044 0000 11 5 2 O 1 BN AI EE3 E VV - l 50 2839 6122 8113 1894 V- TT E2 ( 01 4221 1111 1235 1172 B A GL 1229 L N 2 0000 0000 U ID 0000 2852 C D N E' 5 4125 9534 9041 6007 L LUL - A IOB 00 4631 9677 0270 3125 C URA BGT 2111 1113 6375 11 N I GSN - E 0400 8683 0569 7206 7000 2988 0000 9504 NUI IC IO w HUD SN 4736 5779 6040 6429 d SNE EE 1 54 3 212 1429 2 U III RD LTF 433 8556 0300 0000
- ONI POT 782 9289 0711 9590 -
Y L E CN E S R TL AI ENA 66 1 - 1726 6639 3437 N TRD w MAM 11 1441 O AOI SF( 0080 0004 01 000 N O N E w KT LA 4368 7122 8028 9103 0' 85 702 818 I D m IO - - T N s MG 5201 1310 19 191 A O 9 00 00 0 00 M C L 0 R A K 3- 2 27 19 1 00 2 U LW 8 00 38 15 M N V-D I IO MC
- 2 1
- 11 33
- 60 02 I B V 13 I
R D N 0700 9566 4300 0000 U N EE 0392 4201 6788 9500 E I ELD 6461 - GBR 4713 6777 3640 EAA 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 - WUCR OIEO I DWS' E NEN NNNE E E SES EESS E N SWS SSSW W W NWN WNNN N
y y .
.g o.
BV-1fand;2.0DCH. - IABLE'2.2-11' i
, 4 /~~~ DOSE FACTORS,FOR' NOBLE G1SES AND' DAUGHTERS
- l ds./ ~
'K g .L g LM g Ng TOTAL BODY GAMMA AIR DETA AIR
.NUCLIDE DOSE' FACTOR SKIN DOSE FACTOR DOSE FACTOR -DOSE FACTOR E ,
i sram/yr mrem /yr' mrad /yr' mrad /yr U Per Per Per .Per ny' -uci/m 3 tCi/m 3 3 3: , uCi/ft,__. UCi/m
, Kr-83m :7.56E-02 -- '1.93E+01 2.88E+02, I Kr-85m- 1!17E+03 '1.46E+03 1.23Et03 '
1.97E+03
.Kr-85 '1.61E+01. 1.34E+03L 1.72E+01~ 1.95E+03
-Kr-871 - 5'. 92E+03 '9.73E+03 6.17E+03. .1.03E+04-Kr-88 1.47E+04 2.37E+03 -1.52E+04 2.93E+03 Kr 1.66E+04: 1.01E+04' 1.73E+04 1.062+04
'Kr-90
-Xe-131m 1~.56E+04 9.15E+01 7.29E+03:
4.76E+02 1.63E+04' 1.56E+02 7.83E+03 1.11E+03
)
=Xe-133m 2.51E+02 9.94E+02 3.27E+02- .1.48E+0?. 1 Xe-133 2.94E+02 3.05E+02 3.53E+02 . 1.05E+03 ;
Xe-135m. 3.12E+03 7.11E+02 3.35E+03 ' 7.39E+02 I
< Xe-135 1.81E+03 1sB6E+03' ~1192E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 -1.27E+04 Xe-138 8.83E+03 4.13E+03 9.'21E+03 4.75E+03 i Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 \ ; l l
j l
/ 'i : *The listed dose factors are for radionuclides that may be detected in gaseous j k/. effluents.
i 2-56 ISSUE 3
'BV-1Ltnd 2 ODCh'
- TABLE 2.2212 i.
DOSE PARAMETERS FOR FINITE ELEVATED PLUMES i LEAVER' VALLEY OITE* s y 1. 1,2 y -3 B 3
.B i i i i i N0BLE GAS TOTAL BODY GAMMA AIR TOTAL BODY GAMMA'IR A 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-33m 3.19E-10 l'.75E-8 4.58E-8 3.96U-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 l Kr-88 1.39E-3 2.098-3 4.09E-3 6.16E-3 Kr-89 7.99E-4 ?.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 e.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 1
1 I
* *The listed-dose parameters are for radionuclides that may be detected in gaseous effluents.
V and B values used to implement Modes 1,.2, and 3 of Section 2.2.1 (10CFR20) i 3 Bg values used to implement Modes 1, 2, 3, and 4 of Section 2.3.1 (10CFR50) 3 V and B y values to implement Mode 4 of Section 2.2.1 (10CFR20) and to , imhlementmonitorsetpointdeterminationsofSection2.1.2and2.1.4 2-57 ISSUE 3 L -
' ^
, J: ^~'
%> q j ,
,x i
- BV-1 and 2 ODCH
- Yable2.2-131
/N .
- P IALUIS FOR A CIILD #0E THE BIAVII VALLIf SITI-t If . ..
(area /prpernCi/cuseter)-
.o
,y [ '
Incl 1de Gne - Liver. f. Body i fbyrold lidner Lang. ~GI-LLI
- e a.,
.1B-3' .0.00l+ M '1.12B+03 .;1.128+03' 1.12B+03' 1.12X+03 1.12E+03 1.12I43.
2P-32T 2.60546 >1.1845 9.2516410.MIdo 0.00l+00 ' 0.MI+00 ' 4.22144 : 3Cr-51.. : 0.00I 4 0 0. M I+00 11.54I 02~ 8.55t+01 L2.43E+01 1.70l+04 1.08143
- 4un-54 J0.00l+00 4.29144 9.51E+03 0.00B+00 1.00I 44 .1.58546 2.2914 4
'5Fe 2.078+04 3.34R+04 1.675+04 0.00E+00 0.00X+00 1.n I+06~ 7 07t+04 -
6Co 0.061+00 9.03B+02 .1.07I43 0.MIdo '0.00I40 5.075+05 1.32844
-7Co-58; 'O.00B+00 1.778+03 3.16Ed3 0.00540 0.00I40 '1.11I46 3.44td4 !
*Ce-60 10.MI+00' 1.31E+04 ' L26I44 ' O.00ldC 0,00l+00 7.07146 9.62F+04 1
- 6 In-65 ' 4.25I+0 ' 1.13t+05: 7.03E+04 0.Mt+00 7.14X+04 ' 9.95I45 1.63E+04 10Ib-96 000X+00::1.98I+05 1.14E+05 0.00I 4 0 0.00840 . 0.00140 7.991+03'
.11St 5.tSit05' 0.00l+00 ~ 1.728+04 0.00I40 0.00I40 2.161+06 1.67845
.. . 12Br .1.01148 0.00I40 6.44I46 .0.00I40 0.00l+M 1.485+07 3.43I 4 5 A l 13 T-91: 9.11B+05 0.00l+M , 2.44E+04t 0.00I40. 0.M I+00- 2.63B+06 1.86+05 V 14Ir-951 15lb-95, 1.90E+05 4.18Ed4 . 3.70l+04- 0.00B+00- 5.961+04 2.23E+06 6.11I 4 4 2.36544 .9.18I+03'<6.55I43 0.M I+00 8.62E+03 6.1 G+05 ' 3.70l+04 16Ib ,17Ho-99
,4.291-01 . 7.70I-02 3.608-02 ' O.00l+00 8.558-02 3.42Id3 2.78144 ]
0.00E+00 1.72I42: 4.26t+01 0.00B+00 3.92t+02 1.35I45 . 1.275+05
.18fc-99 '1.78I-03 3.481-03 5.777-02 ':0.003+00 5.071-02 9.511+02, 4.811+03 19In-103 2.79t+03. 0.00I40 1.07I43 0.00I40 7.03t+03< 6.62I45. 4.48I+04 20In-106 1.36I+05 0.MIdo- 1.69I44 0.00l+00 1.84X+05 1.431 4 7 4.298+05 1
21Ag-110s 1.698+04 1.14t+04 9.14I43 0.00l+00 2.12f+04- 5.48t+06 1.00I45 1 22Eb-124 5.74t+04 7.40l+02 2.00l+04 1.26I+02 0.00I40 3.24I,06 1.64t+05 '
. 23Sb-125 9.88+04 7.598+02' 2.07I 44 9.10l+01' O.00l+00 2.32146 4.0?bo4
'24fe-127m 2.49144 8.55t+03' 3.02E+03. 6.071+03 6.36t+04 1.48t+06 7.1G+04 ;
25fe-129s 1.92t+04: 6.85t+03 3.04t+03 6.33I+03 - 5.03X+04 1.76Ed6 1.82I 4 5 ; 26I-131- 4.811t04 - 4.815 44 2.73E+04 1.62I+07 7.88I 44- 0.00l+00 2.84I+03 27.1-133 J.668+04 2.03E+04 7.70l+03 3.85t+06 3.381+04 0.00E+00 5.488+03 28Cs-134 6.51E+05 1.011 46 2.251+05 0.00E+00 3.30!d5 1.21B+05 3.85I+03 29Cs-136 8.51144' 1.71145J 1.16I45 0 M I do 9.551 44 1.45E+04 4.18t+03 l
'30Cs-137 9.071+05 L 8.25I+05 1.28t+05 0.00l+00 2.823+05 1.04E+05 3.62143
.31Ba-140 7.40t+04 6.488+01 4.33E+03 0.00l+00 . 2.11t+01 1.7846 1.02E+05 32La-140. 6.44t+02 2.25I4 2 7.55I+01 0.00500 0.00l+00 1.83I+05 2.26145 ,
'33Ce-141 3.92I 4 4 1.95t+04- 2.905 43 0.00t+09 8.55E+03 5.44I45 5.66tt04 M 34Ce-144- - 6.77I+06 2~12I d6 3.61B+05 0.00l+00 1.171+06 1.20E47 3.891605 ;
.CalculatedperODCEegnat!on2.2-13 l
ISSUI3 2-58 l
h i I BV-l'and 2 ODCM 2.3 Compliance With 10 CFR 50 Dose Limits (0DCM~ Appendix C CONTROLS 3.11.2.2 And 3.11.2.3) (Gaseous). ,V At the Beaver Valley site' all elevated gaseous' releases are considered to
. originate from a shared radvaste system. The effluent from both units are L <
mixed and discharged from a common' release point, the Process Vent, at the-l top of the' Unit 1 Cooling Tower. The resulting dose for the purpose of E implementing 10 CFR 50 is normally apportioned ' equally to each unit. The lt ' only exception would bel a Containment Purge via the Process Vent..Since The resulting dose shall;be. attributed to the contributing reactor unit. 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 Doses Section II.B.1 of Appendix I of .10 CFR 50 (0DCM Appendix C CONTROL (~ ! 3.11.2.2) limits the releases of gaseous effluents-from each reactor such that the. estimated annual gamma air dose is limited to"10 millirad In addition, ODCM j
< and the beta air dose' is . limited to 20 millirad.
Appendix C CONTROL 3.11.2.4 requires .use of radvaste system if air l- -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 )
l ' unrestricted area due to noble gases released in gaseous effluents are defined by the following expressions: During Any Calendar Quarter, For Gamma Radiation: f - { f-3.17E-8 I Mg [(X/0)y0gy + (XTg')yg gy] + [Bgg g ,]- f 5 mrad 0 , + b ig l 1 - [2.3-1] j During Any Calendar Quarter, For Beta Radiation:
~
< 10 mrad (X/0)y0gy + (X/q)yggy + (X/0),0 g,+ (X/q)s 19s [Y.3-2]
l 3.17E-8 I N g - 1 During Any Calendar Year, For' Gamma Radiations 3.17E-8 E Hg [(X/0)y0gy + (X/q)yg gy] -
+ [Bgg0 , + bg qi,]- f 10[2.3-3)mrad 1 -
Durin1 ny A Calendar Year, For. Beta Radiation: i
< 20 mrad 3.17E-8 I N g (X/0)y0gy + (XTq)yggy + (X/0),01 , + (X/q),q gs [7.3-4]
f I O l 2-59 ISSUE 3 !
l 1 l f BV-1 cnd 2 DDCH I l Averaged Over 31 Days, For The Gamma Radiation Projection: 3.17E-8 I Hg [(X/0)y0gy + (X/q)yg gy] + [Bgg 0 , + b gqi,1- < 0.2 mrad l 1 - [2.3-5] Averaged Over 31 Days, For The Beta Radiation Projection: l
. J
+ (X/0),01 , + ( % ),qi, < 0.4 mrad l 3.17E-8 1I N{ (X/0)y0gy + (X/q)yqiy
[7.3-6] l vheres , Hg = The air dose factor due te gamma emissions for each identified n ble gas radionuclide "i" (mrad /yr 3 ; per uCi/m ). l l Ng - The air dose factor due to beta emissions for each identified n ble gas radionuclide "i" (mrad /yr l 3 j per uCi/m ), ! l
- The annual average relative concentration for areas at or i (X/0)V beyond the unrestricted area boundary for3long-term vent releases greater than.500 hrs / year (sec/m ).
(X/q)V
- The relative concentration for areas at or beyond the unrestricted area boundary for short-term 3vent releases equal to or less than 500 hrs / year (sec/m ),
l
- The annual average relative concentration for areas
.(570)8 at or beyond the unrestricted area boundary for long- ]'
term free standing 3 stack releases greater than 500 hrs / year (sec/m ). ( M )8 - The relative concentration unrestricted area boundary forfor areas at orfree short-term beyond the standing stack releases equal to or less than 500 hrs / year 3 (sec/m ).
- Release of noble gas radionuclide "1" in gaseous effluents qgs for short-term stack releases equal to or less than s 500 hrs / year (uci). 1
= Release of noble gas radionuclide "i" in gaseous effluents qgy for short-term vent releases equal to or less than 500 hrs / year (uci). .
O gs
= 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 effluent. l for long-term vent releases greater than 500 hrs / year ,
(uCi). 2-60 ISSUE 3 _ J
e
< BV-1 cnd'2-0DCH:
B =The..constantforlong-termreleases{greaterthan n' ! L7 I. ~' 500 hrs / year) for: each': identified noble gas radionuclide i "i" accounting for the gamma radiation.from the elevated 2 finite plume;(mrad /yr,per uCi/sec). b y' = The constant for short-term releases: (equal. to or less
.than' 500 hrs / year) for- .each 11dentified Lnoble gas-radionuclide "i" accounting.. for 'the~ gamma. radiation from
'the-elevated finite plume'.(mrad /yr per-uCi/sec).
l
; 3;17E The inverse 'of: the number' of seconds in' a year.
L NUREG 0133 permits eliminating 'the short-term release term and'short-1 - . 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 lis applied in Expressions [2.3-1]-through ' [2.3-6],.however, a summary ofL the "real time"-meteorological data
-coupled"vith the corresponding releases shall be included.in the Semi-
' Annual Radioactive Effluent Release Report.-
'.[ t. Short-term releases' are also evaluated annually in computer codes technically' consistent with X00D00 and GASPAR- for inclusion in the Annual Radiological-Environmental ~ Report. The incorporation of this option- and the release modes of Table 2.3-1
~
- results in the following expressions to show compliance lvith.10 CFR.50~
O !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 E Mg [(X70)cy0 3 + (X/0)yy0 g + (X/0)cp0 3cp+ (X/0)dv0g dv+ 1 cv vv (X/0),y0 3 ] + 0.5 B oig y py 0.2 mrad (per 31 days) 12.3-7] f 5.0 mrad (per quarter) 10.0 mrad -(per year) (_.)[ 2-61 ISSUE 3
i BV-1 and 2 ODCM' { f Beta Radiation: 3.17E-8 E N (X/0)cv0g + (X/0)yyo g + (X/0)cp0 1 + (X/0)dv01 dv
+ j i.g cv vv cp j i
(X/0)yy0 3 + 0.5 (X/6)py 0 3 y 0.4 mrad (per 31 days) -[2.3-8]
< 10.0 mrad (per quarter)
.20.0 mrad (per year) l l
vhere (X/0)C# = Annual average relative concentration3 for releases from the Containment Building Vent (sec/m ), 1 1 Annual average relative concentration for 3 (X/0)" releases from the Ventilation Vent (sec/m ), j
- Annual average relative3concentration for releases from ]
(X/0)PV the Process Vent (sec/m ). 9 (X/0)IV = Annual average relative concentration3 for releases from the Turbine Building Vent (sec/m ), l I
~0
= Release of radionuclide "i" from the Containment Building 3
cv Vent (uCi). Og = Release or radionuclide "i" from the Ventilation Vent vy (uCi). l Og = Release of radionuclide "i" from the Process Vent pv (uci). Og = Release of radionuclide "1"~from the Turbine Building tv Vent (uci). Og
= Release of radionuclide "i" from the Condensate Polishing cp Building Vent (uCi). l i
Og = Release of radionuclide "i" from the Decontamination dv Building Vent (uC1). Og = Release of radionuclide "i" from the Vaste Gas Storage vv Vault Vent (uC1). For Modes 1, 2, 3, and 4 the controlling location is 0.35 miles NV. j Substitution cf the appropriate X/0 values into Expressions [2.3-7] and [2.3-8] results in the following: O 2-62 ISSUE 3
Q } s og W , m
.. v.
i=
~
- BV-1 and 2.0DCM5 jg X !R'elease Modes:l',12,C3, And 4 I
Q , .. .
.,During Any1 Month,- Calendar Quarter, Or Year:'
~.
A d.f ,
, , EGamma' Radiations ,
, a 5
1 1 .
+
.3.17E-8'E Hg [9.24E-5;0 3 (+il.03E-4 gg !+'.7.35E-5 O g tv +L7.35E-5 O g cp !
4 i .cv vv
^ 1 9;24E-5 O g- 9.24E-510 3 .-]-+-0.5~B33 0 dv vv- '
pv :. <
;0'2 mrad (per 31(days)l
[2.3-9]-
'<c-5.0 mradJ(per quarter)
' 10.0'erad;(per year)
N Beta Radiation: 3.17E-8.E N 9.24E-5 O g .T+ 1.03E-4 Og , + 7.35E-5 Og + 7.35E-5 O g + cv vv' tv cp
- i.
9.24E-5.O g + 9.24E-5 O g + (0.5);7.0E-10 Og 0.4 mrad [(per:31 days) {2.3-10] . OP
< 10.0' mrad:(per quarter) 20.0 mrad (per year)
The determination.of the controlling locations for implementation of- ,
'10 CFR;50 is a function of the following parameters: l (1) Radionuclide mix andJtheir isotopic release j (2) Release mode (3) Meteorology The incorporation of these parameters into Expressions [2.3-7] and
-[2.3-8] resulted in theRexpressions for the controlling locations as presented in Expressions [2.3-9] and [2.3-10]. The radionuclide mix l
vas based upon source terms calculated using the NRC GALE Code (inputs l presented in Appendix B) and :is presented in Tables 2.2-2a and 2.2-2b as'a function of release type and release point. As in Section 2.2.1, for each release mode, the two highest boundary l X/0. values'for each release point and release duration were utilized-in conjunction.with the radionuclide mix and release for each release Since point to -determine the controlling site boundary location.
' 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 l
+ highest X/0 values), the two highest. X/0also values for those distances, considered in conjunction greater than the' site boundary, were with the radionuclide mix to determine the controlling location. These values of X/0 were obtained for the midpoint of the 10 standard
' -distance intervals previously presented in Tables 2.2-4 through 2.2-10.
2-63 ISSUE 3 4 d
b 7 l BV-1 gnd 2 ODCM f 1 i For each release mode, a particular combination of release point mix- l and meteorology dominates in the determination of the controlling l
' location. For Release Mcdes 1, 2, 3, and 4 the controlling release is j l
the Ventilation Vent. For Reletse Mode 3, the controlling release is the Containment Building Vent. )
}
Values for M I locatibn,whichwereusedinthedeterminationoftheand which are to and N controlling Expressions [2.3-9] and [2.3-10] to show compliance with 10 CFR 50 4 j vere presented in Table 2.2-11. Values taken from Table B-1 of Regulatory Guide 1.109, 1 Revision 1 vere multiplied by 1E6 to ! convert from picoeuries- to microcuries-1 for use in Table 2.2-11. i i In the determination of the controlling location for Modes 1, 2, 3, and 4, Tables 2.0-4 through 2.2-7 are utilized for X/0 values. The B g values to be utilized are the same values which were presented in Table 2.2-12. A description of the derivation of the various X/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: [2.3-11] D f 5 mrad Dg [2.3-12] f 10 mrad For The Calendar Year: D f 10 mrad [2.3-13] Dg [2.3-14] f 20 mrad where: D - The air dose from gamma radiation (mrad). y 4 < rad). Dp - The air dose from beta radiat The quarterly limits given above represent one-half the annual design objective of Section II.B.1 of Appendix I of 10 CFR 50. If any of the limits of Expressions [2.3-11] through [2.3-14] are exceeded, a special report pursuant to both Section IV.A of Appendix I of 10 CFR 50 and ODCM Appendix C CONTROL 3.11.2.2.a must be filed with the NRC at the identified locations. In addition, ODCM Appendix C CONTROL 3.1.2.4 requires that the gaseous radvaste system must be used to reduce radioactive materials in that vaste when projected doses from each reactor unit when averaged over 31 days exceed any of the following: [2.3-15] Dy3 0.2 mrad Dg [2.3-16] f 0.4 mrad 2-64 ISSUE 3
Isb
- fij
-BV-1and'2ODCH[ ,
( 2.3.1.2) Projection Of Doses (Noble Gas):
~
yy [_d Doses;due'to gaseous releases from BV-1 and BV-2'shall-be, projected Lat least once per 31. days:in accordance vith'ODCM Appendix C; CONTROL '4.11.2.4~ and ?this section. .(See also' Section 2.3.2.2 Projection-Of Doses)./ -The -Gaseousi Radvaste' Treatment System and the~ Ventilation ; Exhaust Treatrent- System' shall be used to reduce radioactive materials In- gaseous; was'te prior..to. their discharge in accordance with' 0DCM : Appendix. C . CONTROL 3.11.2.~4 when the projected gaseous effluent air: dose due to.' gaseous effluent releases from each reactor. unit, when averaged Lover' 31' days', vould exceed 0.2-mrad for gamma radiation-and 0.4' mrad fori beta radiation. :(See also Section
~2.3.2.2 Projection Of Doses:for additional' specifications)..'The doses-usedlin the 31-day dose. projection will be calculated using Expressions
-[2.3-9]'and. [2.3-10] as appropriate.- The: 31-day dose projection shall be performed ~according-to the following equations:-
When Including Pre-Release Data,- i N' M
-D 31 - (31)'+ C J
.When Not' Including Pre-Release Data,
[2.3-18]
.D31 - - (31)l+C where:
.D 33 - Projected 31 day dose"(mrad).
A - Cumulative dose for quarter (mrad).
'B Projected dose from.this release (mrad).
;T = Current days into quarter.
C = Value which may be used to anticipate plant trends (mrad). ! j O 2-65 ISSUE 3
m BV-1 and 2 ODCM-2.3.2 Dose Due To Radiolodines And Particulates 2.3.2.1 Cumulation Of Doses
.\
Section IIC of. Appendix I of 10 CFR 50 (ODCM Appendix C > l CONTROLS 3.11.2.3 and 3.11.2.4) limits the release of radiciodines and radioactive material in particulate form from each reactor unit such that estimated dose or dose commitment to an individual in an unrestricted area from all pathways of exposure is not in excess of i 15 mrem to any-organ. In addition, ODCM Appendix C CONTROL 3.11.2.4 requires' the use 'o f gaseous radvaste treatment system when the j projected dose due to gaseous ef fluent releases' from each reactor unit, l vhen averaged over 31 days, vould exceed 0.3 mrem to any organ. Based ) upon .NUREG-0?33, the dose- to an organ of an in61vidual from l radiotodines and particulates, and radionuclides other than noble gases j with half-lives greater than 8 days in gaseous effluents released to I unrestricted areas, can be determined by the following expressions j l During Any Month, Calendar Quarter, Or Year: q l 3.17E-8 E R h Iv s0g3 +v9s 1s + Y 0v gy +vggy]y i 0.3 mrem (per 31 days) [2.3-19]
< 7.5 mrem (per quarter) 15.0 mrem (per calendar year) where:
= Release of radionuclide "i" for long-term free standing 0,1 stack releases greater than 500 hrs /yr (uci).
0 - Release of radionuclide "i" for long-term vent releases IV greater than 500 hrs /yr (uci). qgs
- Release of radionuclide "i" for short-term free standing stack releases equal to or less than 500 hrs /yr (uCi).
qIV = Release of radionuclide "i" for short-term vent releases equal to or less than 500 hrs /yr (uci). v - Dispersion parameter for estimating dose to an individual 8 at the controlling location for long-term free standing stack releases greater than 500 hrs /yr. 3
= sec/m for the inhalation pathway, (V/0)s*
-2 for the food and ground plane pathway, (b75),.
= meters V*
= The dispersion parameter for estimating the dose to an individual at the controlling location for long-term vent releases greater than 500 hrs /yr.
= sec/m3 for the inhalation pathway, (276)y.
-2
= meters for te food and ground plane pathway, (D/0)y.
2-66 ISSUE 3
r, q x BV-1 and 2 ODCH ! ( L l'l' 'v s , Dispersion parameter .for estimating the dos'e to an , individual at the controlling location for short-term
/N-h.. stack releases equal.to or less than 500 hrs /yr.
3 l = sec/m for the inhalation pathway, (X/q),.
- meters
-2 for the food and ground plane pathway, ( M ),.
l
-1 v = The dispersion parameter for estimating the dose to an V individual at-the controlling location for short-term vent releases equal to or less than.500 hrs /yr.
3
= sec/m for the inhalation pathway,-(X/q)y.
-2 forthe'foodandgroundplanepathway,(57ii)y.
= meters 3.17E The inverse of the number of seconds in a year.
R II = The dose factor for each identified radionuclide "i" 2for the organ "r"'of 3 interest (mrem /yr per uCi/see per m- or mrem /yr per uCi/m ). Radionuclides and particulates may be released from any of the BV-1 and BV-2 vents in the release modes identified in Table 2.3-1. As described previously in Section 2.3.1.1, NUREG 0133 permits use of 4 hng-term annual average dispersion calculations which with the release wodes of Table 2.3-1 results in the following expressions to show compliance with ODCH Appendix C CONTROLS 3.11.2.3 and 3.11.2.4.- For a A particular organ, Expression [2.3-19] becomes: l y1
+V yy 01 +V
+V cy01 tv 01 tv Ve.0g cp 4 +
3.17E-8 E R g 0.5 Vpy0g ; i pv cv vv Idv0g +V yy 03 y y 0.3 mrem (per 31 days) [ .3-20) f 7.5 mrem (per quarter) 15.0 mrem (per calendar year) where: U = Dispersion parameter for releases from the Process Vent. py V = Dispersion parameter for releases from the Containment cv Building Vent. V yy
- Diepersion parameter for releases from the Ventilation Vent.
V = Dispersion parameter for releases from the Turbine Building tv Vent. I (~h y 2-67 ISSUE 3
l BV-1 cnd 2 ODCM i 1 V - Dispersion parameter for releases from the Condensate cp Polishing Building Vent. U dv
- Dispersion parameter for releases from the Decontamination Building Vent.
Vyy = Dispersion parameter for releases from the Vaste Gas Storage Vault Vent. O l py
- Release of radionuclide "i" from the Process Vent (uCi).
O - Release of radionuclide "i" from the containment Building i C# Vent (uci). O l yy - Release of ediotuclide "i" from the Ventilation Vent (uci). O - Release of radionuc3ide "i" from the Turbine Building Vent i tv (uci). 01 - Release of radionuclide "i" from the Condensate Polishing cp Building Vent (uCi). 0 1dv - Release of radionuclide "i" from the Decontamination Building Vent (uC1). 0 1"Y - 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 carticular location, dispersion parameter V, is a function of the pathway. For the food and ground plane pathway, V is in terms of D/0 If the inhalation pathway is considered, V is in terms of X/0., Incorporation of the various pathways into Expression [2.3-20] results in the following expression for a particular organ: 3.17E-8 I i [RgTG + R3h
+R g3
+R h B][0.5 Vpy01 pv +V cv03 cv +V yy 01 vv +
tv 0g
+
cp i dvSdv+ "Y I l+ IT [0.5 (X/0)py0 g tv cp vy I
+ (X/0)cv 0g +( }** I vv +0 )tv 01 +
(X/0)cp0 g ev ep (X/0)dv0 i dv "" vv 0.3 mrem (per 31 days) [2.2-21]
< 7.5 mrem (per quarter)
~ 15.0 mrem (per year) ]
2-68 ISSUE 3 u__ -- - - -- - -._ ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - - - _ _
BV-1 and 2 ODCH
-where: .gm R "t" for radionuclide "i" for the ,,
iTg - Dose factor for an organ ground plane exposure pathway (mrem /yr pec uCi/see per m ~). for organ "T" for radionuclide "1" R itg = Dose factor for an either the cow -2) ilk or goat milk pathway (mrem /yr per m uci/see per.m . iTy - Dose factor for an organ "T" for radionuclide -2")i" R vegetable pathway (mrem /yr per uCi/see per m . f r the an organ "T"/yrfor R gT B - Dose for thefactor meat for pathway-(mrem perradionuclide uCi/see per m "i"2). R ity
~
= Dose organ "T" for radionuclide3 "i" for thefactor for anpathway inhalation (mrem /yr per uCi/m ),
V V and It should be'noted that V V ev,n V
"termstv,,
f cp, V dv,/0(m-2), D Vyy in Expression [2.3-21]pv, are i Values of the dose factor, R vere calculated using the methodology of NUKEG-0133. The follovibd, equations were used for all nuclides except tritium: R gT, , g,(BR),(DFAh)a 3 [2.3-22]
- mrem /yr per uCi/m 7,
vhere: K' = A constant of unit conversion (1E6 pCi/uC1). (BR)"
- The breatl..,g3 rate of the receptor of age group "a" (m /yr). j (DFA M)a - Each organ inhalation dose factor for the receptor th radionuclide (mremof/pci).
age grour "a" for the "i" Inhalation dose factors (DFA g by organ for the various i age groups are given in Table 3)-7 through E-10 of Regulatory Guide 1.109, Rev. 1 or Tables 5 through 8 of l NUREG-0172. The breathing rates (BR)a used for the various age groups are tabulated below, as given in Table E-5 of the Regulatory Guide 1.109. Age Group (a) Breathing Rate (m /yr) Infant 1400 Child 3700
-Teen 8000 Adult 8000
{ r~s 2-69 ISSUE 3 L
BV-1 end 3 ODCM. t iTg = K'K" (SF)DFGg [(1 - e~ i )f
- m2-mrem /yr per uCi/sec [2.3-23]
where K' - A constant of unit conversion (1Eo pCi/uci). K" - A. constant of unit conversion (8760 hr/ year). A 1 - The decay. constant for the "i" th radionuclide (see-1).
't - The exposore time (4.73E8 see or 15 years).
DFG gT - The groundplane dose conversion factor 2 f r rgan "T" f r the "i" th radionuclide (mrem /hr per pCi/m ). A tabulation of DFG values is presented in Table E-6 of Regulatb[yGuide1.109. SF - The shielding factor (dimensionless). A shielding factor of 0.7 as suggested in Table E-15 of Regulatory Guide 1.109 is used. A 0 (U ) ff (1 - f f )e~ i h - if t t iTH " K' i+ y F,(r)(DFLh)aI
+ l' p S
- m2-mrem /yr per uCi/sec [2.3-24]
vhere: O K' - A constant of unit conversion (1E6 pCi/uci). . l Q - The animal's consumption rate, vet weight (kg/ day). F U - The receptor's milk consumption rate, for age "a" ap (liters /yr). Y = The agricultural2productivity by unit area of pasture P feed grass (kg/m ). Y 3
- The agricultural 2pr ductivity by unit area of stored feed (kg/m ).
. The stable element transfer coefficients (days / liter).
F, r - Fraction of deposited activity retained on animals feed grass. (DFLgT)a - The maximum organ ingestion dose factor for the "1" th radionuclide for the receptor in age group "a" (mrem /pci). Ingestion dose factors (DFL for the various age groups are given in. Table iT)"11 E through E-14 of Regulatory Guide 1.109 or Tables 1 through 4 of NUREG-0172. 2-70 ISSUE 3 _________.__________________--_u
BV-1 and 2 ODCM i
- The decay constant for the'"i" th radionuclide (sec~1).
1 f h,-m b- - The decay constant for removal of activity onand_ plant s
-(corresponding to a 14 day ha. 2-life).
t - The transport-time from pasture, to animal, to milk, to 'j f i receptor (sec).
= The-transport time'from pasture, to harvest,.to animal,
~
t h to milk, to receptor (sc' l f p ,= Fraction of the year th.c the animal is on pasture (dimensionless). I s - Fraction of the animal. feed that is pasture grass while.
)
the animal is on pasture (dimensionless). Tabulated below are the parameter values used for cow's milk and their , reference to Regulatory Guide 1.109. ) Value Table Parameter r (dimensionless) 1.0 for radioiodine E-15 0.2 for particulates E-15 each stable element E-1 (cow milk) F,(days / liter) E-2 (goat milk) 330 E-5 U ap (liters /yr) - infant child 330 E-5 teen 400 E-5 adult 310 E-5 each radionuclide E-11 to E-14
-(DLFh)a (mrem /P Ci) 0.7 E-15 Y
p (kg/m ) 2.0 E-15 Y,.(kg/m ) 1.73E5 (2 days) E-15 t g (seconds) 7.78E6 (90 days) E-15 t h (seconds) 50 E-3 Op (kg/ day) fp 0.5 -- 1.0 -- f, For goat's milk, all values remain the same except for 0 p which is 6 kg/ day. O 2-71 ISSUE 3 l
l 1 BV-1 cnd 2 ODCH l
-At R 0 (U ff (1 - f f )e-A tih if gTB " E' P)F + ~I*
+ 4 f(r)(DFLh)a!
- m2-mrem /yr per uCi/sec [2.3-25]
where: F = The stable element transfer coefficients (days /kg). , f 1
"a" (kg/yr).
U,p - The receptor's meat consumption rate for age t - The average time from slaughter of meat animal to consumption f (sec). t h
- The transport time from crop field to receptor (sec).
All parameter values are the same as the milk pathway parameter values i except F vhich is obtained from Table E-1, t which is obtained from ! Table E- 5 and U which is obtained from Tabl E-5. The values as obtained fromapRegulatory Guide 1.109, are as follows: Parameter Value Table Ff (days /kg) each stable element E-1 t 1.73E6 (20 days) E-15 f (seconds) 0 E-5 U ap (kg/yr) - infantchild 41 E-5 teen 65 E-5 adult 110 E-5 Han is considered to consume 2 types of vegetation (fresh and stored) l that differ only in the time period between harvest and consumption; f l therefore: () ](DLFg ),[U f ge + U,8f g ] y = K' ly ,
- m2-mrem /yr per uci/sec [2.3-26]
vhere: K' = A constant of unit conversion (1E6 pCi/uCi). Ub - The consumption rate of fresh leafy vegetation by the receptor ' a in age group "a" (kg/yr). US - The consumption rate of stored vegetation by the receptor in l a age group "a" (kg/yr). f g = The fraction of the annual intake of fresh leafy vegetation grown locally. Oli 2-72 ISSUE 3 l
.1 s ^
BV-1 and 2 ODCH , L .- . f - The fraction of the annual' intake of stored vegetation grovn-
-E : loe,11 7 l r,q .
! g' ' g - The average time between harvest of leafy vegetation and its t consumption:(seconds). t g - The average time between harvest of stored vegetation and its consumption :(seconds). :
- Yy..- The. vegetation area' density.(kg/m2 ),
all other factors are defined previously.. Tabulatedbelow are, the - ' appropriate parameter.-values and .their
. reference to Regulatory Guide 1.109.- )
Parameter Value Table r (dimensionless) 1.0 for:radioiodines 'E-15 0.2'for particulates E-15
'(DFLH)g (mrem /P Ci) each' stable element E-11 to E-14 l U (kg/yr) - infant 0 'E child 26 E-5 teen 42 E-5 l adult 64- E-5 8 0 E-5 U* (kg/yr) - infant E-5 child- 520 teen. 630 - E-5 adult 520 E-5 1.0 E-15 fg (dimensionless)
F 0.76 E-15
, . E (dimensionless) !
'tg (seconds) 8.6E4 (1 day) E-15 t
5.18E6 (60 days) E h (seconds)' 2 2.0 E-15 Y,(kg/m ) As discussed in Section 2.2.2 for tritium,-tha 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 'o f implementation of 40 CFR 190, discussed in Section 4.0, as: For: Tritium: ! l 0 0 3.17E,-8 (RTg+ RTg+ R- B TT7 + RTT ) [0.5 (X/0)py T + (X/0)cy ev T 0 ] (p -(X/0)yy0 T + (X/0)gy0 T + (X/0)cp0 7cp+ (X/0)dv Tdv+ (X/0),y0 Tvv vv vv iG L [2.3-27] ) 2-73 ISSUE 3 l I; i
BV-1 cnd 2 ODCH 1 vhere ) l R Dose f actor for organ "T" for tritium for the milk j T3 pathway (mrem /yr per uCi/sec ). i
- Dose f actor for organ "T" 3 f r tritium for the vegetable l
R,73 pathway (mrem /yr per uCi/m ). ]
- Dose f actor for organ "T" 3 f r tritium for the beef R,73 pathway (mrem /yr per uci/m ).
- Dose factor for organ "T" 3 f r tritium f r the inhalation R.73 pathway (mrem /yr per uCi/m ).
Expression [2.3-27) is used to show compliance with 40 CFR 190, as i j discussed in Section 4.0. The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the R,77 is based f H I on [X/0): ! R.7 = K'K'"F,0 7U,p(DLFg )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 ), l 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 Rg The concentration of tritium in vegetation is based on the is airborne concentration rather than the deposition. Therefore, the R"Y based on [X/0): b R < T g= K'K'"[U fg + Ug f ](DFLg ),[0.75(0.5/H)] !
= mrem /yr per uCi/m 3 [2.3-29}
where all terms have been defined above. The concentration of tritium in meat is based on its airborne is based concentration rather than the deposition. Therefore, the R,73 on [X/0): 0 2-74 ISSUE 3
-te:
c- . BV-1 and 2-0DCM'. .i I - l R = g
- l. .
T h 'K'K'"Ffp 0 U,p(DFL ,3 4);[0.75(0.5/H)] \' (2.3-30J , jP{} l .
--mres/yr-per uci/m b cvhere all' terms have been: defined above.-
'To sh'ov-compliance with'0DCM Appendix'C CONTROLS 3.11.2.3 and'3.11.2.4, I
- Equation [2.3-21];isf evaluated at the controlling pathway location.
.For' Release Modes'1^through 4, the controlling location is a residence l
'0.89 miles in theJ NV . sector.- ' Inserting appropriate X/0ivalues from.
! Tables 2.2-4 to 2.2.1_0'fand..D/0 ' values from Tables 2.3-28 to 2.3-34, ;
Expression [2.3-21]:-becomess'
' Release Mo' des 1 Yhrough 4 Fer Mon?.h,' Calendar Quarter, Or Years .
- 3. -8 ' I [R +R ][(0.5)4.22E-10 0 + 1.56E-8 Ocv + 1.56E-8 ;
Og + 1.55E-8 Og . + 1.55E-8 Og + 1.56E-8 O g + 1.56E-8 vv tv I. cp dv Og ]+Rh [(0.5) 7.30E-9 Og .+ 2.00E-5.0g cv+ 2.71E-5 O g vv vv I pv ,
+ 2.00E-5 O g
+ 2.22E-5'Og .+ 2.22E-5.0 g- + 2.00E-5 O g dv ] i tv. cp vv 0.3 mrem (per 31 days) [2.3-31] j
< 7.5 mrem.(per quarter. ,
15.0'erem (per year)' l Q For tritium, for purposes of implementation'of 40 CFR 190, as discussed in Section 4.0, Expression [2.3-28] reduces to 2.00E-5'O 2.71E-5 O g +
'3.17E-8 [RTT +R Tg][(0.5)7.30E-9Og +v p gc +v vv 7
j 2.22E-5 Og - + 2.22E-5 Og . + 2.00E-5 13 dv + 2.00E-5.0g vv'] J tv cp [2.3-32] l The determination of a controlling locating for implementation of ODCM ' Appendix C CONTROLS 3.11.2.3 and 3.11.2.4 for radioiodinen and
--particulates is a function of:
(1) Radionuclide mix and their isotopic release (2) Release mode (3) Meteorology (4) Exposure pathway
.(5)' Receptor's age i s
l The incorporation of these parameters into Expression [2.3-19] results l 'in the respective equations for each release mode at the controlling location. 2-75 ISSUE 3
m BV-1 cnd 2 ODCH In the determination of the controlling location for each release mode, the radionuclide mix of radiciodines and particulates was based upon the source terms calculated using the GALE, code. This mix was & W presented in Tables 2.2-2a and 2.2-2b as a function of release mode and release point. For the ground plane exposure pathway, all , radionculides (excluding H-3 and C-14) were considered in the 3 determination of the controlling location. For the inhalation and food pathways H-3 and C-14 vere also considered in determination of the g controlling location. In the determination of the controlling location for each release mode, 2.2-3, were all of the exposure pathways, as presented in Table beef and vegetable evaluated. These include cow milk, goat milk, An infant was . ingestion and inhalation. and ground plane exposure. A child was j assumed to be present at all milk pathway locations. l assumed to be present at all vegetable garden ano beef animal ! locations. The ground plane and _ inhalation exposure pathways ver e J considered to be'present at all locations. For the determination of the controlling location, the highest D/0 and X/0 values for each release point and release mode for the vegetable garden, cov milk, and goat milk pathways were selected. The organ dose ) was calculated at each of these locations using the radionuclide mix l and release of Tables 2.?-2a and 2.2-2b Based upon these calculations, i it was determined that the controlling location for Release Modes 1 -l through 4 is the residence (vegetable garden)/ child pathway. l For Release F-des 1 through 4, the controlling release point and mix is f the Ventilation Vent. values for the total body, Tables 2.3-2 through 2.3-20 present GI-tract, bone, liver, kidney, thyro R,id, and lung organs for the vegetable, and meat l ground plane, inhalation, cow milk, goat milk, ingestion pathways for the infant, child, These teen,were values and adult age groups calculated as using the appropriate to the pathways. methodology described in NUREG-0133 using a grazing period of 6 months. , l j In the determination of the controlling location for Release Hodes 1-4, Tables 2.2-4 through 2.2-10 are utilized for X/0's l 1 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. These values may be The values appear in Tables 2.3-21 through 2.3-27. utilized if an additional special location arises different from those l l presented in the special locations of Table 2.2-3. 2-76 ISSUE 3
(. Y BV-1 and'.2 ODCM I. The'following. relationship' should; hold for BV-1 or BV-2 to shov N compliance with ODCM Appendix C CONTROL 3.11.2.3. ,.dds7 ~ [~ For'The Calendar 0uarter: D f7.5 mrem'to'anyforgan- [2.3-33] For The Calendar' Year: Dy f 15 mrem to any organ- [2.3-34] fwhere:1 D - The: dose'to any organ'from radioiodines and parsiculates
~
.(arem). ,
;The quarterly limits given above r epresent 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 ce filed with the NRC at the identi2ied locations. O 4 I> 2-77 ISSUE 3
BV-1 end 2 ODCM 2.3.2.2 Projection Of Doses (Radioiodines And Particulates) Doses due to gaseous releases from BV-1 or BV-2 shall be projected at l least once per 31 days in accordance with ODCH Appendix C CONTROL 4.11.2.4 and this section. (See also Section 2.3.1.2 Projection Of Doses). The appropriate portions of the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous vaste prior to their discharge in accordance with ODCM Appendix C CONTROL 3.11.2.4 when the projected doses due to gaseous effluent releases from each reactor unit, when averaged over 31 days, would exceed 0.3 mrem to any organ. (See also Section 2.3.1.2 Projection Of Doses f/ additional roccifications). Doses resulting from the gaseous effluent release of radioiodines and particulates vill be calculated for use in the 31-day dose projection using Expression [2.3-31]. The 31-day dose projection shall be performed according to the following equations: When Including Pre-Release Day , (2.3-35} D 31 - A+B T (31) + C When Not Including Pre-Release Data, D A (31) + C [2.3-36] 31 - where: D31 - Projected 31 day dose (mrem). A - Cumulative dose for quarter (mrem). B = Projected dose for this release (mrem). T - Current days into quarter. i C - Value which may be used to anticipate plant trends (mrem). O 2-78 ISSUE 3
I a. BV-1 cnd 2 ODCH TABLE 2.3-1 A MODES OF GASEOUS RELEASE FROM. BEAVER VALLEY SITE VENTS FOR IMPLEMENTATION OF 10 CFR 20 AND 10 CFR 50 L .. , M'0DE 1 MODE 2 H0DE 3 MODE 4 RELBASE POINT 2 Main Cond ' Air Same As Same As Sane As' BVPS BVPS-2 Mode 1 And
. Process. Vent (pv) Ejector, Vaste Mode 1 Mode 1 l
Gas, Contain- Containment ment Vacuum Purge Aux. Bldg. Same As Same As j BVPS-1 Ventilation Contajnment ) Ventilation Purge Mode 1- Mode 1 Vent (vv1) i Leakage- Same As Same As Same As BVPS-1 Containment Mode 1 Collection Mode 1 Mode 1 And Vent (cv1)' Exhaust Contajnment Purge BVPS-1 Turbine Bldg.1 Turbine Bldg. Same As Same As Same As l Exhaust
- Mode 1* Mode 1* Mode 1* l Vent (tv1)
Contiguous Same As Same As BVPS-2 Ventilation Contajnment Areas Purge Mode 1 Mode 1 l Vent (vv2) 1 ' Aux. Bldg. Same As Same As Same As BVPS-2 Containment Mode 1 l Ventilation Mode 1 Mode 1 And n Vent (cv2) l Contajnment Purge BVPS-2 Turbine Bldg.1 Turbing Bldg. Same As Same As Same As Exhaust
- Mode 1* Mode 1* Mode 1* ,
Vent (tv2) BVPS-2 Condensate Polishing Bldg. Vent (cp2) BVPS-2 Decontamination Bldg. Vent (dv2) 1 * * *
- f '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. l 1 Continuous ground level meteorology is applicable 2 Continuous elevated meteorology is applicable
~
3Hode established by purge from one unit, all other release points remain same as Mode 1-2-79 ISSUE 3 (- L
BV-1and2ODCd Table 2.3-2 R VAWIS FOR BIAVER TALLEY S175 (ares /yrpernC1/enseter) Pathway: Inhalation AgeGroup: Adult hellde ' Bons ther f. Body Thyroid Ildney Lung GI-LLI
~1H O.00b00 1.26bO3 1.26bO3 1.26bO3 1.26bO3 1.26bO3 1.26bO3 2P-32 1.32It06 7.71b04 5.0lb04 0.00b00 0.00b00 0.00b00 8.64b04 3Cr-51 0.00D00 0.00h00 1.00!+02 5.95b01 2.28b01 1.44E+04 3.32bO3 4Mn-54 0.00D00 3.96b04 6.30bO3 0.00D00 9.84bO3 1.40D06 7.74b04 5Fe-59 1.181+04 - 2.78 b 04 1.06b04 0.00b00 0.00b00 1.02b06 1.88b05 6Co-57 0.00Et00 6.92E+02 6.71D02 0.00D00 0.00b00 3.70D05 3.14b04 7C0 0.00D00 1.58b03 2.07bO3 0.00h00 0.00b00 9.28b05 1.06b05 8Co-60 0.00b00 1.15Et04 1.4Bb04 0.00b00 0.00b00 5.97b06 2.8bb05 9 h-65 3.24b04 1.03b05 4.66b04 0.00b00 6.90!+04 8.64b05 5.34b04 10lb-86 0.00b00 1.35b05 5.90D04 0.00b00 0.00b00 0.00b00 1.66b04
'11St-89 3.04b05 0.00b00 8.72b03 0.00b00 0.00b00 1.40b06 3.50D05 12Sr-90 9.92bO7 0.00D00 6.10D06 0.00b00 0.00D00 9.60D06 7.22b05 13T-91 4.62b05 0.00b00 1.24b04 0.00b00 0.00b00 1.70D06 3.85b05 143r-95 1.071+05 3.44h04 2.33b04 0.00D00 5.42b04 1.77b06 1.50D05 15Eb-95 1.41b04 7.82003 4.21bO3 0.00D00 7.74bO3 5.05b05 1.04b05 16 lib-97 2.221-01 5.621-02 2.051-02 0.00b00 6.541-02 2.40bO3 2.42bO2 17Mo-99 0.00D00 1.21bO2 2.30b01 0.00D00 2.91bO2 9.12b04 2.4Bb05 18fe-99: 1.03bO3 2.91I-03 3.701-02 0.00b00 4.421-02 7.64bO2 4.16bO3 19En-103 1.53bO3 0.00D00 6.58bO2 0.00b00 5.83b03 5.05b05 1.10D05 20 h-106 6.91b04 0.00b00 8.72bO3 0.00h00 1.34b05 9.36b06 9.12b05 21st-110s 1.08b04 1.00b04 5.94bO3 0.00D00 1.97h04 4.63b06 3.02h05 22Sb-12( 3.12b04 5.89b02 1.24b04 7.55b01 0.00b00 2.48b06 4.06b05 23Sb-125 5.34b04 5.95bO2 1.26b04 5.40b01 0.00!C 1.74b06 1.01b05 24fe-127: 1.26b04 5.77bO3 1.57bO3 3.29b03 4.58b04 9.60b05 1.50D05 25fe-129: 9.76bO3 4.67D03 1.58b03 3.44b O3 3.66b04 1.16b06 3.83b05 26I-131 2.52b04 3.58b04 2.05b04 1.19bO7 6.13b04 0.00 BOO 6.28003 J 271-133 8.64bO3 1.4Bb04 4.52bO3 2.15b06 2.58b04 0.00b00 8.88bO3 28Cs-134 3.73b05 8.48b05 7.28b05 0.00b00 2.67b05 9.76b04 1.04b04 29Cs-136 3.90D04 1.46b05 1,10b05 0.00b00 8.5Bb04 1.20b04 1.17b04 30Cs-137 4.78b05 6.21b05 4.28b05 0.00D00 2.22b05 7.52b04 8.40D03 l i 31Ba-140 3.90D04 4.90b01 2.57bO3 0.00b00 1.67b01 1.27b06 2.18b05 32La-140 3.44b02 1.74bO2 4.58b01 0.03b00 0.00D00 1.36005 4.58b05 33Ce-1(1 1.99b04 1.35D04 1.53b03 C.00D00 6.26bO3 3.62b05 1.20D05 34Ce-144 3.43b06 1.43b06 1.84b05 0.00b00 8.4Bb05 7.7Bb06 8.16b05 l CalculatedperODCMequation2.3-22 ISSUI 3 { 2-80 l l l _-___-____ __-_ _ ___ _ _ a
y ; i BT-l'and2ODCH c'7 . fable 2.3-3 X.,] '
.RVALUISFORBIAVIIVALLIISif!L (ares /yrpernC1/cuseter) i' Pathway: Inhalation AgeGroup: feen Inclidel Bone . Line f. Body Thyroid tidney Long 01-LLI L1B-3 :0.00E+00' 1.271+03: 1.278+03 '1.27I403 1.271+03 1.271+03 1.271+03 l 2 P-32 : 1.89I+06' 1.10l+05.'7.165+04 0.00l+00 ' O.00l+00 0.00l+00 9.28I+04 1 1
3Cr-51 -0.00l+00 0.00l+00 1.35E+02 7.50l+01 3.078+01 2.10l+04 3.00l+03 4Mn-54 0.00l+00 5.11E+04 8.40ft03 ' 0.00l+00 1.27t+04 1.98t+06 6.68I+04 5Fe-59 1.59t+04 3.70E+04 . 1.43I+04 0.00t+00 - 0.00l+00 1.53t+06' 1.78t+05 l 6Co-57 0.00E+00 9.44E+02 9.20l+02 0.00!+00 -0.00E+00 5.86t+05 3.14E+04 70o58 0.00l+00 - 2.071+03 2.78t+03 0.00t+00 0.00t+00 1.34E+06 9.52I+04 8Co-60 0.008400- 1.51t+04 1.98I+04' O.00t+00 0.00l+00 8.72I+06 2.59I+05 9Zn-65 3.868+04 1.34t+05 6.24X+04 0.00E+00 8.64B+0L 1.24I+06 4.661+04
.10lb-86 0.00lt00 1.90t+05 8.40l+04 . 0.00l+00 0.00E+00 0.00t+00 1.771+04 11St-89 4.34t+05 0.00t+00 1.25E+04 0.00t+00 0.00t+00 2.42E+06 3.71E+05 12St-90 1.081+08 0.00t+00 6.68I+06 0.00E+00 0.00E+00 1.65t+07 7.65t+05 13T-91 6.611+05 . 0.00l+00 1.778+04 0.00t+00 0.00l+00 2.94t+06 4.098+05 14Zr-95 1.46t+05 4.581+04 3.15t+04 0.00t+00 6.74t+04 2.691+06 1.491+05 s" 15Hb-95 1.86t+04 1.03B+04 5.668+03 0.00l+00 1.00l+04 '7.511+05 9.688+04-16Hb-97 3.141-01 7.78I-02 2.84t-02 0.00t+00 9.128-02 3.93E+03 2.171+03 17No-99 0.00t+00 1.69t+02 3.22X+01 0.00t+00 4.111+02 .1.54t+05 2.69I+05 1 18fc-99: 1.381-03 3.868-03 4.99t-02 0.00l+00 5.768-02 1.15I+03 6.13It03 l
19lu-103 2.10t+03' O.00l+00 8.96t+02 0.00E+00 7.43I+03 7.83E+05 1.091+05 20in-106 9.84E+04 0.00E+00 1.24E+04 0.00l+00 1.90l+05 1.61E+07 9.60E+05 21As-110s 1.381+04 1.311+04 7.99t+03 0.00140 2.50E+04 6.75I+06 2.73t+05 ) 22Sb-124 4.30l+04 7.94R+02 1.681+04 9.761+01 0.00l+00 3.34I+06 3.98I+05 l I 23Sb-125 7.388+04 8.08t+02 1.72t+04 7.041+01 0.00t+00 2.74E+06 9.92t+04 24Te-127s 1.80l+04 8.161+03 2.18I+03 4.38tt03 6.54t+04 1.66t+06 1.59t+05
-25fe-129s 1.391+04 6.58I+03 2.25t+03 4.581+03 5.19t+04 1.9BI+06 4.05E+05 ,
26I-131 3.54t+04 4.91E+04 2.64E+04 1.46t+07 8.40l+04 0.00t+00 6.49t+03 27I-133 1.22E+04 2.05t+04 6.22t+03 2.92t+06 3.59t+04 0.00!+00 1.03E+04 26Ca134 5.02It05 1.13E+06 5.491+05 0.00t+00 3.75E+05 1.46I+05 9.76t+03 , 29Ce-136 5.15It04 1.94I+05 1.371+05 0.00l+00 1.10tt05 1.781+04 1.091+04 30Cs-137 6.70t+05 8.48t+05 3.11t+05 0.00!+00 3.04E+05 1.211+05 8.48I+03 31Ba140 5.471+04 6.70t+01 3.52E+03 0.00l+00 2.281+01 203E+06 2.29t+05 32La-140 4.791+02 2.36Et02 6.261+01 0.00E+00 0.00It00 2.14I+05 4.87t+05 33Ce-141 2.84E+04 1.90!+04 2.171t03 0.00!+00 8.881+03 6.14E+05 1.26I+05 34Ce-144 4.89I+06 2.02t+06 2.62t+05 0.00!+00 1.21E+06 1.34E+07 8.641+05 CalenlatedperODCWegntion2.3-22 ISSUI3 2-81
EV-1and2ODCM fable 2.3-4 RVALUESFORBIAVIIVALLITS171 (ares /yrperaC1/cuseter) Pathvas: Inhalation AgeGroup: Child
. helide' Bone Liver f. Body Thyroid Eidney Lung GI-LLI-1H-3 0.00R+00 1.12E+03 1.12It03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 2P-32 2.60It06 1.14E+05 9.88E+04 0.00E+00 0.00l+00 0.00!+00 4.22E+04 3Cr-51 0.00l+00 0.00E+00. 1.54t+02 8.55E+01 2.43E+01 1.70E+04 1.08t+03 4Mn-54 0.00E+00 4.29E+04 9.51E+03 0.00E+00 1.00E+04 1.58I+06 2.%E+04 5Fe-59 2.07I+04 3.34Er04 1.671+04 0.00l+00 0.00E+00 1.27t+06 7.07E+04 6Co-57 'O.00l+00 9.03E+02 1.07E+03 0.00!+00 0.00!+00 5.07tt05 1.32E+04 7Co-58 0.00E+00 1.77t+03 3.16E+03 0.00E+00 0.00E+00 1.111+06 3.44E+04 8Co-60 0.00E+00 1.31E+04 2.261+04 0.00E+00 0.00l+00 7.071+06 9.62t+04 9Zn-65 4.25E+04 1.13E+05 7.03E+04 0.00E+00 7.14E+04 9.95E+05 1.63E+04 <
10Rb-86 0.00E+00 1.981+05 1.14E+05 0.00!+00 0.00!+00 0.00!+00 7.991+03 11Sr-89 5.991+05 0.00E+00 1.72E+04 0.00E+00 0.00Et00 2.161+06 1.671+05 i 12Sr-90 1.011108 0.00E+00 6.443+06 0.00Et00 0.00E+00 1.481+07 3.43E+05 { i 13 T 91 9.14E+05 0.00I+00 2.44E+04 0.00E+00 0.00E+00 2.63E+06 1.84Et05 14Zr-95 1.90E+05 4.18I+04 3.70E+04 0.00E+00 5.96t+04 2.23E+06 . 6.11E+04 15 lib-95 2.35E+04 9.181+03 6.55t+03 0.00!+00 6.62E+03 6.14E+05 3.70E+04 16Eb-97 4.298-01 7.70E-02 3.60E-02 0.00E+00 8.551-02 3.42t+03 2.78I+04 17Mo-99 0.00E+00 1.72It02 4.261+01 0.00!+00 3.92E+02 1.35E+05 1.271+05 18fc-99: 1.788-03 3.4C-03 5.77E-02 0.00E+00 5.071-02 9.511+02 4.81E+03 19Ra-103 2.79t+03 0.00!+00 1.07E+03 0.00E+00 7.03E+03 6.62E+05 4.48E+04 20Ru-106 1.36E+05 0.00E+00 .1.691+04 0.00l+00 1.84E+05 1.43E+07 4.291+05 21Ag-110s 1.691+04 1.141+04 9.14E+03 0.00Et00 2.12E+04 5.48E+06 1.00E+05 22Sb-124 5.74E+04 7.40E+02 2.00E+04 1.26t+02 0.00l+00 3.24E+06 1.64H+05 23Sb-125 9.84E+04 7.59E+02 2.071+04 9.10!+01 0.00E+00 2.32I+06 4.03R+04 24fe-127s 2.491+04 8.55E+03 3.02It03 6.07E+03 6.368+04 1.48t+06 7.14E+04 j
~
25fe-129s 1.921+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 26I-131 4.81E+04 4.81E+04 2.73H+04 1.62t+07 7.88t+04 0.00E+00 2.84E+03 ; 27I-133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.381+04 0.00l+00 5.48Et03 3 28 Cs-134- 6.51E+05 1.011+06 2.25E+05 0.00E+00 3.30f*05 1.21E+05 3.85Et03 i 29Cs-136 6.51E+04 1.71E+05 1.16E+05 0.00E+00 9.55It04 1.45H+04 4.181+03 ! 30Cs-137 9.07E+05 8.25E+05 1.281+05 0.00E+00 2.82E+05 1.04E+05 3.62E+03 l 31Ba'-140 7.40E+04 6.48E+0! 4.33E+03 0.00E+00 2.11E+01 1.74E+06 1.02E+05 l 32La-140 6.44E+02 2.25E+02 7.55E+01 0.00!+00 0.00!+00 1.83X+05 2.26E+05 33Ce-141 3.92It04 1.95E+04 2.90E+03 0.00!+00 8.55E+03 5.4(I+05 5.66E+04 f 6.77I+06 2.12t+06 3.61E+05 0.00l+00 1.17E+06 1.20!+07 3.89E+05 ! 34Ce-144 CalculatedperODCHequation2.3-22 Oi iSSo!3 l 2-82 j i i
p. ?; 1' I EV-1and2ODCH
' fable 2.3-5 L IVALDISFORBIAVIIVALLIYS171 l
(ares /yr.peruC1/cuseter) Pathway: Inhalation AgeGroup: Infant luclide' Bone Liver f. Body Thyroid tidney Lung GI-LLI 1H-3 0.00l+00 6.47I+02 6.471+02 6.475+02 6.47I+02 f.47bO2 6.47t+02
.2P-32 2.03t+06 1.12t+05 7.74E+04 0.00t+00 0.00l+00 0.00b 00 '1.61t+04 3Cr 0.00l+00 0.00B+00 8.95t+01 5.75t+01 1.32 b 01 1.28b04 3.57bO2 4Ma-54 0.00b00 ~ 2.53h04 4.98b O3, 0.00l+00 4.98bO3 1.00D06 .7.06bO3 5Fe-59 1.36t+04 2.35b04 9.48bO3 0.00D00 0.00b00 1.0lb06 2.48t+04 60o-57 0.00b00 6.51bO2 6.41E+02 0.00b00 0.00h00 3.79b05 4.86bO3 700-56 0.00l+00 1.22t+03 1.82bO3 0.00b00 ' O.00I+00 7.77b05 1.11b04 8C0-60 0.00b00 8.02bO3 ~1 .18h04 0.00l+00 0.00B+00 4.51b06 3.191+04 9Zn-65 1.93b o4' 6.26b04 3.11b04 0.00 h 00. 3.25b 04 6.47I+05 5.14t+04 10lb-86 0.00b00 1.90E+05 0.82t+04 0.00b00 0.00l+00- 0.00l+00 3.04bO3 11Sr-89 3.98t+05 0.00D00 1.14h04 0.00b00 0.00t+00 2.03h06 6.40b04 12Sr-90 4.09bO7 0.00b00 2.59b06 0.00b00 0.00b 00 . 1.12bO7 1.31h05 p :13T-91 5.88b05 0.00b00 1.57b04 0.00b00 0.00b00 2.45b06 7.03t+04
( 14Zr-95 1.15E+05 2.79b04 2.03b04 0.00D00 3.11E+04 1.75b06 2.17b04 15Nb-95 1.57t+04 6.43b 03' 3.78 bO3 0.00E+00 4.72bO3 4.79t+05 1.27b04 16Bb-97 3.421-01 7.29I-02 2.63I-02 0.00b00 5.70I-02 9.32t+03 2.69b04 17Ho-99 0.00E+00 1.65bO2 3.23b01 0.00t+00' 2.65I+01 1.35E+05 4.87b04 18Tc-99: 1.401-03 2.881-03 3.72I-02 0.00b00 3.111-02 8.31I+02 2.03h03 19Ru-103 2.02bO3 0.00l+00 6.791+02 0.00E+00 4.24It03 5.5W05 1.61b04 20Ru-106 8.681+04 0.00b00 1.09I+04 0.00D00 1.07h05 1.168+07 1.64It05 21As-110s 9.98t+03 7.22I+03 5.00bO3 0.00b00 1.09h04 3.67b06 3.30 h04 22Sb-124 3.79b04 5.56b O2 1.20b 04 1.01bO2 0.00h00 2.65b06 ' 5.91b04 23Sb-125 5.17b04 4.778+02 1.09b04 6.23t+01 0.00D00 1.64t+06 1.47It04 24fe-127a 1.07I+04 6.90t+03 2.07bO3 4.67bO3 3.75b04 1.31b06 2.73b04 25fe-129s 1.41b04 6.09b03 2.23bO3 4.21bO3 3.18b04 1.68b06 6.90b04 26I-131' 3.79t+04 4.44b04 1.96b04 1.48bO7 5.18b04 0.00l+00 1.06t+03 27I-133 - 1.32b04 1.92h04 5,60bO3 3.56b06 2.24h04 0.00l+00 2.16bO3 28Cs-134 3.96b05 7.03bo5 7.45b04 0.00D00 1.90t+05 7.97b04 1.33bO3 29Cs-136 4.83b04 1.35b05 5.29b04 0.00D00 5.64t+04 1.18b04 1.43bO3 l 30Cs-137 5.49b05 6.12bo5 4.55t+04 0.00h00 1.72b05 7.13b04 1.33b03 31Ba-140 5.60It04 5.60b01 2.90t+03 0.00D00 1.34E+01 1.60b06 3.84b04 32La140 5.05bO2 2.00bO2 5.15b01 0.00b00 0.00b00 1.68b05 8.481+04 ; 33Ce-141 2.77b04 1.67h04 1.99b03 0.00h00 5.25b03 5.17b05 2.16b04 i 34Ce-144 3.19b06 1.21h06 1.76b05 0.00D00 5.38b05 9.84b06 1.48t+05 Ih V CalculatedperODCHequation2.3-22 l ISSUI3 i 2-83
BV-1and2OpCH fable 2.3-6 RVALDISFORBEAVERVALLI7SITI (egseter-ares /yrperuCi/see) Pathway: Ground l lluclide: Bone Liver f. Body Thyroid Ildney Lung GI-LLI 1H-3 0.00t+00 0.00t+00 0.00b00 0.00E+00 0.00D00 0.00D00 0.00b00 2P-32 0.00b00 0.00b00 0.00b00 0.00D00 0.00D00- 0.00E+00 0.00b00 3Cr-51 4.66b06 4.66b06 4.66b06 4.66b06 4.66b06 4.66b06 4.66b06 4Hn-54 1.39b09 1.39D09 1.39D09 1.39h09 1.39D09 1.39b09 1.39b09 5Fe-59 2.73D08 2.73b08 2.73D08 2.73b08 2.73t+09 2.73bO8 2.73bO8 600-57 0.00b00 0.00b00 0.00b00 0.00b00 0.00D00 0.00D00 0.00b00 7Co-58 .3.79bO8 3.79b08 3.79b 06 ' 3.79 BOB 3.79b08 3.79bO8 3.79bO8
.800-60 2.15b10 2.15b10 2.15b10 2.15b10 2.15b10 2.15b10 2.13b10 9Zn-65 7.47b08 7.47bO8 7.47bO8 7.47bO8 7.47bO8 7.47bO8 7.47bO8 10Hb-86 8.99b06 8.99b06 8.99b06 8.99b06 8.99b06 8.99b06 8.99 DOS 11Sr-89 2.16b04 2.16h04 2.16b04 2.16b04 2.16b04 2.16 bot 2.16b04 12St-90 0.00b00 0.00D00 0.00D00 0.00D00 0.00b00 0.00D00 0.00b00 13Y-91 1.07b06 1.07b06 1.07b06 1.07b06 1.07b06 1.07b06 1.07b06 14Zr-95 2.45 BOB 2.45bO8 2.45 BOB 2.45bO8 2.45bO8 2.45bO8 2.45bO8 15Nb-95 1.37bO8 1.37bO8 1.37D08 1.37D08 1.37bO8 1.37 BOB 1.371+08 16 lib-97 0.00b00 0.00b00 0.00b00 0.00h00 0.00E+00 0.00b00 0.00b00 17Ho-99 4.00D06 4.00b06 4.00b06 4.00b06 4.00b06 4.00h06 4.00b06 16fc-99: 1.84b05 1.84b05 1.84b05 1.84b05 1.8(b05 1.84b05 1.84b05 19Ru-103 1.08b08 1.08bO8 1.08bO8 1.08bO8 1.08bOS 1.08bOS 1.0BbO8 20Ha-106 4.22bO8 4.22bO8 4.22b08 4.22bO8 4.22 BOB 4.22D08 4.22bO8 21Ag-110s 3.44D09 3.44h09 3.44h09 3.44b09 3.44b09 3.44E+09 3.44b09 22Sb-124 0.00D00 0.00h00 0.00D00 0.00D00 0.00D00 0.00D00 0.00D00 l l
23Sb-125 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00 b00 'O.00 b00 24fe-127: 9.17b04 9.17b04 9.17b04 9.17b04 9.17b04 9.17b04 9.17b04 25fe-129s 1.9BbO7 1.98bO7 1.98bO7 1.98bO7 1.98bO7 1.98b07 1.98bO7 1 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 6.86b09 6.86h09 6.86b09 6.86b09 6.86b09 l 29Cs-136 1.51 BOB 1.51b08 1.51b08 1.51bO8 1.51bO8 1.51bO8 1.51 BOB 30Ce-137 1.03b10 1.03b10 1.03b10 1.03b10 1.03D10 1.03D10 1.03D10 31Ba-140 2.05bO7 2.05bO7 2.05bO7 2.05bO7 2.05bO7 2.05bO7 2.05bO7 32La-140 1.92bO7 1.92bO7 1.92bO7 1.92bO7 1.92bO7 1.92bO7 1.92bO7 33Ce-141 1.37bO7 1.37bO7 1.37D07 1.37bO7 1.37bO7 1.37bO7 1.37bO7 34Ce-144 6.96bO7 6.96bO7 6.96bO7 6.96bO7 6.96bO7 6.96bO7 6.96bO7 CalenlatedparODCHequation2.3-23 ISSUE 3 2-84 =
F i i
.t1 BV-1and2ODCM h]( Table 2.3-7 RVALUISFOIBIAVIRVALLITSITI j
l _semeter-area ( /rrperuC1/sec) {
'Pathwar: Vegetation AgeGroup:Adlt'
) !
s J inclide'. Boo'e_ . Liver f. Body Thyroid 11dner Lang- GI-LL1 1H-3 :0.00It00 2.268+03 _ 2.26I+03 2.26I+03 2.261+03 2.26I+03 2.26t+03 1
'2P-32 -1.40l+09 :8.74R+07 -5.43E+07i 0.00E+00' O.00l+00 0.00l+00 1.588506 3Cr-51 0.00l+00 0.00l+00 . 4.64f+04 2.78t+04 L02t+04 6.161+04 1.17t+07 4Hn-54 0.00l+00 3.13I+08-'5.97I+07 0.00l+00 9.311+07 0.00E+00. 9.595+08 5Fe-59 1.26t+06 2.96I+08 1.14t+08 0.00B+00 0.00l+00 8.28I+07 9.881+08-600-57 0.00td0 . 1.171+07 1.95t+07 0.00It00 0.00l+00 0.00E+00 2.971+08 7Co 0.00E+00 3.071+07 6.895+07 0.00l+00 0.00E+00 0.00l+00 6.23t+08-8Co-60 0.00It00 1.67I+08 3.698+08 0.00l+00 0.00It00 0.00l+00 3.14X+09 9Zn-65 3.171+08 1.01E+09 4.56Ed8 0.00It00 6.751+08 0.00l+00 6.361+08 10kh-86 0.00l+00 2.19t+08 1.02X+08 0.00l+00 0.00l+00 0.00l+00 4.33t+07 11Sr-89 9.97I+09 0.00!+00 2.865408 0.00l+00 0.00l+00 0.00l+00 1.60!+09 12Sr-90 6.05E+11 0.00l+00 1.481+11 0.00l+00 0.00l+00 0.00l+00 1.75E+10.
'13f-91 5.11t+06 0.00l+00 1.371+05 0.00!+00 0.00l+00 0.00l+00 2.81I+09-p/
y 14Zr-95 1.175+06 8.771+05 2.55E+05 0.00It00 5.91E+05 0.00It00 1.19t+09 15lb-95 1.42t+05 7.92t+04 4.261+04 0.008t00 7.83I+04 0.MI+00 4.61X+08 16Ib-97 2.161-06 5.461-07 1.991-07 0.00l+00 . 6.371-07 0.MI+00 2.021-03 ; 17No-99 0.00l+00 6.15I+06 1.17I+06 . 0.00l+00 1.391+07 0.00t+00 1.43Eto' 18fe-99: 3.10l+00 ' 8.77t+0 1.12I+02' O.00E+00 1.33Et02 4.30l+00 5.19I+03
-19In-103 4.771+06 0.00It00 2.06t+06 0.00l+00 1.82t+07 0.HI+00 5.571+08 20Rn-106 1.93E+08 0.00l+00 2.44t+07 0.00l+00 3.72t+08 0.00140 1.25t+10 ,
21As-110s 1.05E+07 9.75I+06 5.798+06 0.00E+00 1.92X+07 0.00It00 3.981+09 22Sb-124 1.04It08 1.961+06 4.111+07 2.51E+05 0.00Et00 8.07I+07 2.94X+09 23Sb-125 1.371+08 1.53Et06 3.25t+07 1.398+05 0.00l+00 - 1.05I40S 1.50l+09 24fe-127 3.491+08 1.251+08 4.26t+07 8.%I+07 1.42E+09 0.00E+00 1.171+09 25fe-129s 2.511+08 9.38I+07 3.981+07 8.64E+07 1.05I+09 0.00l+00 1.27t+09 26I-131 6.08t+07 L161+08 6.62t+07 3.791410 1.98t+08 0.00l+00 3.05t+07 27I-133 2.09t+06 3.63t+06 1.111+06 5.33E+08 6.33E+06 0.00I40 3.268+06 28Ce-134 4.671+09 1.111+10 9.08t+09 0.00l+00 3.5DI+09 1.191+09 1.941+08 29Ce-136 4.271+07 1.698+08 1.211+08 0.MI+00 9.38It07 1.291+07 1.911+07 30Ca-137 6.36t+09 8.70E+09 5.70!+09 0.00l+00 2.95t+09 9.81t+08 1.691+08
'31Ba-140 1.29t d8 1.611+05 8.42146 0.00l+00 5.49I+04 9.24X+04 2.65E+08 32La-140 1.981+03 9.971+02. 2.63R+02 0.00It00 0.00l+00 0.00l+00 7.32t+07 33Ce-141 1.97I+05 1.33I+05 1.51E+04 0.00l+00 6.19t+04 0.00l+00 5.10l+08 34Ce-144 3.29t+07 1.38tt07 1.771t06 0.00l+00 8.161+06 0.00l+00 1.11E+10 ~V Allnue11 des (exceptH-3)calculatedperODCHegnation2.3-26 H-3calculatedperODCHequation2.3-29 1SSUI3 2-85 ,
BY-1and2ODCH Table 2.3-8 R VALUES FOR EIA HR VALLII SITI (sqseter-eres/yrperuC1/sec) Pathway : h getation AgeGroup: feen l Nuclide Bene Liver f. Body Thyroid Eldney Lung GI-LLI IH-3 0.00E+00 2.59E+03 2.591+03 2.591+03 2.591+03 2.59E+03 2.591+03 2P-32 1.611+09 9.98tt07 6.24E+07 0.00E+00 0.00l+00 0.00E+00 1.35Et08 3Cr-51 0.00E+00 0.00E+00 6.17E+04 3.43E+04 1.35I+04 8.81E+04 1.04E+07 4Ma-54 0.00l+00 4.54E+08 9.011+07 0.00E+00 1.36E408 0.00E+00 9.32E+08 5Fe-59 1.79E+08 4.19E+08 1.62E+08 0.00E+00 0.00E+00 1.32E+08 9.90E+08 6Co-57 0.00E+00 1.79E+07 3.00E+07 0.00f+00 0.00!+00 0.00l+00 3.33E+08 7Co-58 0.00E+00 4.36E+07 1.00E+08 0.00E+00 0.00E+00 0.00l+00 6.011+08 8Co-60 0.00E+00 2.49E+08 5.60E+08 0.00E+00 0.00E+00 0.00l+00 3.24E+09 9Zn-65 4.24E+08 1.471+09 6.87I+08 0.00l+00 9.42t+08 0.00E+00 6.23E+08 10Rb-86 0.00E+00 2.74E+08 1.291+06 0.00l+00 0.00l+00 0.00E+00 4.05E+07 11Sr-89 1.51E+10 0.00E+00 4.3Ht08 0.00It00 0.00E+00 0.00E+00 1.80E+09 12Sr-90 7.51E+11 0.00E+00 1.85t+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 3.741+05 0.00l+00 7.981+05 0.00!t00 1.251+09 15Nb-95 1.92Et05 1.078+05 5.878+04 0.00!+00 1.03E+05 0.00E+00 4.561+08 16lb-97 2.00E-06 4.97E-07 1.818-07 0.00E+00 5.81E-07 0.00l+00 1.191-02 17Ho-99 0.00E+00 5.65E+06 1.081+06 0.00E+00 1.29E+07 0.00!+00 1.011+07 18fe-99 2.74E+00 7.64E+00 9.90!t01 0.00E+00 1.14E+02 4.24E+00 5.02E+03 19Ru-103 6.82E+06 0.00E+00 2.92E+06 0.00E+00 2.41E+07 0.00E+00 5.70E+08 20In-106 2.38E+08 0.00E+00 3.90E+07 0.00E+00 5.97E+08 0.00E+00 1.481t10 l 21Ag110s 1.52E+07 1.43E+07 8.72E+06 0.00E+00 2.74E+07 0.00E+00 4.03E+09 l 22Sb-124 1.54E+08 2.84E+06 6.02E+07 3.50l+05 0.00E+00 1.35I+08 3.11E+09 ! l 23Sb-125 2.14E+08 2.34E+06 5.01E+07 2.05E+05 0.00E+00 1.88E+08 1.67E+09 24fe-127: 5.52F+08 1.96t+08 6.56Et07 1.31E+0B 2.24E+09 0.00E+00 1.37I+09 l l 25fe-129s 3.62E+08 1.34E+08 5.73E+07 1.171+08 1.51E+09 0.00E+00 1.36E+09 26I-131 7.69t+07 1.081+08 5.78E+07 3.14I+10 1.85E+0S 0.00E+00 2.13B+07 27I-133 1.94E+06 3.29E+06 1.00Et06 4.59E+08 5.77E+06 0.00E+00 2.491+06 28Cs-134 7.10l+09 1.671+10 7.75t+09 0.00E+00 5.31E+09 2.03E+09 2.08t+08 29Cs-136 4.38t+07 1.72E+08 1.16t+08 0.00l+00 9.371+07 1.48t+07 1.39E+07 30Cs-137 1.01E+10 1.35E+10 4.69E+09' O.00E+00 4.59E+09 1.78E+09 1.92E+08 31Ba-140 1.38t+08 1.695+05 8.90!+06 0.00E+00 5.74It04 1.14I+05 2.13E+0B 32La140 1.81E+03 8.88t+02 2.36E+02 0.00E+00 0.00!+00 0.00!+00 5.10E+07 33Ce141 2.83E+05 1.89E+05 2.17Et04 0.00E+00 8.90l+04 0.00E+00 5.41E+08 34Ce-144 5.27t+07 2.181+07 2.83E+06 0.00E+00 1.30E+07 0.00E+00 1.33H+10 Allnuclides(exceptH-3)calculatedperODCHequation2.3-26
'H-3calculatedperODCHequation2.3-29 ISSUI3 2-86
=-
g. 4
'Bf-1and20D05 s
.y<
p, sfable2.3-9. g%F ITALDISFOR3508IVALI.IYSITI
,' 1(semeter-stes/trperaC1/sec)
Patheir': Vegetation.
.Age Group : Child
- f. Bodt' . Thyrcid . ilidney Inc11de - ' lone- -Liver Lung GI-LLI o .
a 1H-3' l0.00l+00' 4.01t+031'4.011+03 ~ 4.01E+03l 4.01B+03.'4.01B+03^ 4.01t+03-
'2P-32: : 3.37I49 ; 1.585+08' 1.30l+08 : 0.MId0 0.00540 0.MI40'i9.32547' 3Cr-51L J 0.00l+00 '0.MIdo -1.17I45; - 8.50B+04 ' 21.78I44 j l.19td5 : 6.21846 -
.~4Ms-54 0.00l+00 6.65I 48 . 1 '7I48 0. M I 40 '1.88I 48 0.00E+00 ~5.581 48-
'5Fe-59 3.98I48 6.435+08 13.20I48 L .0.MI+00 : ' 030l+(0 : 1.87148 6.70l+08 6Co-57; 0.00l+00'. 2.998+07 ' 634147 ' ! 0'.MI+00 L 0? .00l+M 0.MI+00 .2.45E+08 7Co-58T f 0.00540 1 6.44t+07' 1.97t+08 0.00l+00 0.00I 4 0 10.00I 40 3.765 46 -
8Co-60 l0.00l+00- 3.78t+08 1.12E+09. 0.00l+00 - 0.00l+00: 0.M I+00 2.10I 4 9 9In-85 8.13I 4 8 2.175+09- 1.35E+09 0.00240 1.368+09 0.M id0 '3.MI+08 10lb 0.00I 4 0 4.52t+08 2.785+08O.00l+00 0.00540 0.00I 4 0 2.91I+07-11Sr-89' 8.60l+10 0.00l+00 ~.1.03I 49 .0.00I40 0. M I+00 ' O.00l+M 1.398+09 12Sr-90 - 1.24I+12' O.00l+00: 3.15B+11- 0.00E+C0 - 0.00540 0.005@ 1.671+10
% ,^ . 13T-91, '1.65E+07. 0.00l+00 4.99t+05' 0.00l+00 0.00I 4 0 0.00I40 .2.485+09
( L 14 Ir-95. 15lb-95 3.86I46 . ' 8.488+05 7.55E+05 0.00t+00 1.211+06 0.00I40 8.85t+083
.4.11I4 5. 1. HI4 5.~1.14I 45. 0.00I 40 1.50845 0.00X+M 2.96848 16Nb-97 '3.65I-06 6.598-074 3.088-07 0. M I+00 7.311-07 'O.00I @ 2.035-01 17No 0.00l+00.' 7.711 46 '1.91E+06 0.00I40' 1.65t+07 ' O.00E+00 '6.38I46.
18Yc-99s- 4.71B+00 9.24t+00 1.53E+02 ' O.00l+00 1.34E+02 4.69t+00 5.26I 4 3-19In-103 '1.53t+07 0.00l+00 5.90l+06 'O.00l+00 - 3.86I+07 0.00l+M 3.971+08
.20In-106 7.45B+08 0.00540 9.30l+07 0.00l+00 ~1.01B+09 0.00l+M 1.16t+10 21Ag-110s' 3.21E+07; 2.175+07 1.73I+07 0.MI40 4.04t+07 0.00100 . 2.58I49 22Sb-124> :3.52548 4.578+06 1 23I+08' 7.775 45 0.00I40 1.95148' 2.20I 49 23Sb-125 4.99I 4 8 3.8;146 1.05I 4 8 4.63I 4 5 0. M i do 2.78I48 1.191+09 :
24fe-127s, 1.32t+09 3.561+08 1.57I+08 3.16t+08 -3.77I+09 0.001@ 1.07149 25fe-129 8.41t+08 2.35E+08 1.31E+08 '2.71I+08 2.47I+09 0.00ld0 1.03E+09 4 1 261-131 1.43B+08 1.44t+08 8.17I+07 4.76I+10 2.36Ed8 0.00l+M 1.281+07 27I-133 3.53t+M t.Go6 1.65tt06 8.12I+08 7.28I 4 6 0.00l+00 1.78I 4 6 28Cs-134 1.60l+10' 2.63E+10 5.55I49 0.00l+00. 8.15E+09 2.93E+09 1.42t+08
~ 29 Cs-136 8.24I+07 2.27I48 1.47I+08 0.00l+00 1.21I48 1.80l+07 7.96546 30Cs-137 2.39t+10 2.298+10 3.38549 0.00l+M ' 7.46I+09 2.68I+09 1.43It08 31Ba-140~ 2.773 48 '2.421+07 1.62I47 0.00l+M 7.89t+04 1.45145 1.40l+08
'32La-140 3.25E+03 1.13t+03 3.83I+02 0.00l+00 0.00I 4 0 0.00l+00 3.168+07 33Ce-141-- 6.56I45 3.27t+05 4.868+05 0.00l+00 1.43I+05 0.00l+00 4.08I48 34Ce-144- 1.27I48 3.98t+07 6.78I+06~ 0.00E+00 2.21t+07 0.00l+00 1.041+10 Allnuclides(exceptH-3)calenlatedperODCNequation2.3-26
'I-3calculatedper0D05 equation 2.3 ISSUI3 2-87
BV-1and2ODCH Table 2.3-10 RVALUISFORBEAVIRVALLIISIf! (egseter-stes/yrpernC1/sec) Pathway: Heat AgeGroup: Adult Nuclide Bone- Liver f. Body fbyroid Ildney Lung GI-LLI 1H-3 0.00l+00 3.25b02 3.25bO2 3.25bO2 3.25bO2 3.25bO2 3.25bO2 2P-32 3.95b09 2.46bO8 1.53D08 0.00000 0.00D00 0.00b00 4.4(bc8 3Cr-51 'O.00b00 0.00D00 5.86bO3 3.50D03 1.29bO3 7.78bO3 1.47b06 4 Mn-54 0.00b00 6.495+06 1.24b06 0.00D 00 ~ 1.93b06 0.00It00 1.99bO7 = 5Fe-59 2.14bO8 5.04bO8 1.93E+08 0.00E+00 0.00b00 1.41b08 1.68D09 l-600-57 0.00b00 4.0!b06 6.66b06 0.00b00 0.00b00 0.00b00 1.02 BOB 700-58 0.00b00 1.42bO7 3.18h07 A.00 D00' O.00b00 0.00D00 2.87 BOB BCo-60 0.00b00 5.12bO7 1.13 BOB 0 00 0.00b00 0.00h00 9.61t+08 9Zn-65 2.54bO8 8.09b08 3.66bO8 0.00b00 5.41bO8 0.00b00 5.10 BOB 10Hb-86 0.00b00 4.11bO8 1.92bO8 0.00D00 0.00b00 0.00b00 611bO7 s 11St-89 2.41bO8 0.00b00 6.92b06 0.00b00 0.00b00 0.00b00 3.87bO7 12Sr-90 8.41b09 0.00D00 2.0Cb09 0.00b00 0.00D00 0.00D00 2.43b08 13Y-91 8.94b05 0.00D00 2.39b04 0.00D00 0.00b00 0.00b00 4.92bO8 14Zr-95 1.47h06 4.71b05 3.19b05 0.00b00 7.39D05 0.00h00 1.49b09 ' 15Nb-95 1.85b06 1.05b06 5.64b05 0.00b00 1.04b06 0.00b00 6.37b09 16Kb-97 stttttttusstststattttttttttttttts 0.00 b00 tttttttttts 0.00b00 tttttttttts 1780-99 0.00b00 8.51b04 1.62b04 0.00D00 1.93b05 0.00!t00 1.97b05 18fc-99s 3.838-21 1.081-20 1.381-19 0.00b00 1.64E-19 5.30!-21 6.40E-18 19 h-103 8.57bO7 0.00D00 3.69bO7 0.00D00 3.27 BOB 0.00D00 1.00E+10 20Ru-106. 1.97b09 0.00D00 2.49008 0.00b00 3.80b09 0.00b00 1.27b11 1
}
21Ag-110s 4.77b06 4.41b06 2.62h06 0.00b00 8.67b06 0.00100 1.80D09 j 22Sb-124 0.00b00 0.00b00 0.00h00 0.00b00 0.00b00 0.00b00 0.00b00 1 23Sh-125 0.00b00 0.00b00 0.00E+00 0.00b00 0.00b00 0.00b00 0.00b00 ) ' 24fe-127: 8.38bO8 3.00 BOB 1.02bO8 2.14 BOB 3.40D09 0.00b00 2.81bo9 25fe-129s 9.33 BOB 3.48 BOB 1.48bO8 3.21bO8 3.89b09 0.00b00 4.70b09 I 26 I-131 9.13D06 1.31bO7 7.48b06 4.28b09 2.24bO7 0.00b00 3.45b06 l 27l-133 3.121-01 5.421-01 1.651-01 7.96b01 9.468-01 0.00D00 4.87E-01 28Cs-134 4.53D08 1.08b09 8.81bO8 0.00D00 3.49h08 1.16bO8 1.89bO7 29Cs-136 1.02bO7 4.04bO7 2.91bO7 0.00b00 2.25bO7 3.08bs3 4.59b06 1 30Cs-137 5.90D08 8.06bO8 5.28 BOB 0.00b00 2.74b08 9.10bO7 1.56bO7 31Ba-140 2.4(b07 3.06b04 1.60D06 0.00b00 1.04b04 1.75b04 5.02bO7 32La-140 3.16bO2 1.591-02 4.21b03 0.00h00 0.00b00 0.00b00 1.17bO3 , 33Ce-141 1.16D04 7.83bO3 8.88bO2 0.00b00 3.64bO3 0.00D00 2.99b07 ! 34Ce-144 1.03b06 4.32b05 5.55b04 0.00D00 2.56b05 0.00D00 3.50bO8 ! Allnue11 des (exceptH-3)calenlatedperODCHequation2.3-25 H-3calculatedperODCHequation2.3-30 ISSOE3 2-88 l l l _______m____._.___. a
e
/. -
)
jte , u
'd i!
1%
, 39 1 and 2 ODCH [ ,
u ou. , - f l , N, '
, fable 2.3-11 (4 l s
in uns a mm mLIr sm u J(st' meter-ares /yrper301/see) g y . m
- Pathsay:deat . -
g AgeGroup:feeni 1 L... .
.. h .
m ,
)Inclide', Ione,~~; Liver ifiBody Thyroid lidneyL L Lang ' GI-LL1
- 1H-3 ? 0.00840 '1.94142 ~ ~ 1.94I42 - t 1.94I42 l .1.94I42 -' 1.94X+02 f1.945421
~2P-32: : 3.34E+09 , 2.078+08 ' o 1.298+08. 2 0.00l+0010.00l+M . 0.00l+M : 2.80848: 1 T3Cr-511' O.008 40. 0.00l+00 E 4.698 4 3 2.60l+03x 1.03B+03:.6.69I4 3 !7.88I45 I 4un54 : 0.00E+00 ' 4.95I+06 : ' 9.81545 i 0.MI+001 '1.485+06 0.00l+00 1.01847L "a :5Fe-59; L 1.71348 4.00l+08 D 1.54E+08 - 0.00l+00 ? 0.00l+M _1.268+08 9.45E+08 J6Co-57 0.00l+00 '3.225t06! 5.401 46 '0.00I 4 0 . 0.008+00 0.00t+00 .6.01B+07-0.00I40 .1.09I47- 2.52I47 .0.00540L 0.00540 ; 0.00l+M 1.51B+08 9 7 Co-58 :
800-60 0.00l+M':3.975+07 8.95E+07 . 0.00E+M ' 0.HI+00 0.00l+00 . 5.17I 48-l 9!a-65
'1.79I+08 . 6.21548 2.90l+08: 0.00t+00 3.97Ed8 0.00E+00 2.63I+08
- 10 lb-86 0.00E+00; 3.43I+08 :1,61I48 0.H I+00 0.M i do 0.00l+00 5.08147 11br-89 2.03I 48. 0.00l+00 L 5.838 46- 0.00l+00 0.00l+00 0.00I 4 0 2.42I47 12Sr 5.44E+09 0.00I 4 0: 1.34I 49 1 0.00l+00' 0.M I+00 0.00I40 1.531+08
.13Y-91 7.58t+05 0.00t @ 2.02Id4 0.MIdo 0.03t+M 0.00l+00 3.09E+06< !
l 14Ir-95 -1.188 46 3.711 45 2.55t+05 0.005 4 0 5.~45t d5 0.0M+00 8.56t+08-9" 15lb-95 1.47t+06 '8.17I45 4.50I45 ' O.00l+00 7.92E+05 : 0.HI+00 3.498+09-
.16lb-97 estettstetteststssssssstsettsstst'0:00l+00stestssstst 0.00540estesssstet
.17Ho-99 0.00I40 7.03t+04 '1.34B+04 0.H I+00 '1.61B+05 0.00I40 '1.26t+05 -
18fe-99s '3.041-21 , 8.48I-21 1.101-19 ' 0.00E+00 1.268-19: 4.71I-21 5.571-18, i
~19In-103 6.98t+07 0.00It00 .2.96t+07 0.00l+00 2.465+08. 0.00l+00 5.83B+09.- 1 20lu-106; 1.28t+09. 0.00I40 2.09I48 0.00l+00 - 3.198+09 0.00l+00 7.94I+10 21 As-110s '3.611+06 3.421 46. 2.088+06 0.00B+00 6.52546 0.00l+00 9.60l+08
' 22 Sb-124 0.00I40.'O.00E+M 0.00t+00 .0.00E+00 0.HI+M 0.00140 0.MI+00
-23Sb-125 0.00l+M 0.00l+00 0,00l+00 0.00l+00 0.00l+00 0.00l+M 0.00l+00 j 24fe-127a 7.07t+08 2.511+081 8.41B+07 1.68I+08 2.87549 0.00I40 1.76I 4 9 !
25fe-129s- 7.82E+08 -2.90t+08 1.24t+08'.2.52t+08 3.27t+09' O.00l+M .2.93I+09 26I-131 7.59t+06 1.068+07 5.711+06 3.10E+09 1.83E+07 0.00l+00 2.10I46 27I-133: 2.61I-01 4.425-01 1.358-01 6.178+01 7.75I-01 0.00I40 3.348-01 ! 28Co-134 3.60l+08 8.48I48 3.93E+08 ~0.00l+00 2.891+M 1.03E+08 1.05I+07 ; 29Co-136 7.988+06 3.14I+07 2.11t+07 0.MI+00 1.71E+07 2.89t+06 ,2.53E+06
~30Cs-137- 4 '!3t+08 8.51t+08 2.27t+08 '0. MI+00 2.22t+08 8.61E+07 9.27I+06 i
31Ba-140 ~ 2.02t+07 2.47t+04 1.30l+06 0.00t+00 8.38I+03 1.66d44 3.11E+07
-32La-140- 2.60I-02 :1.288-02 3.40I-03 0.MI+00 0.00I40 0.00I 4 0 7.33Id2 33Ce-141 9.72I 43 '6.495+03 7.46I+02 0.00l+00 3.06I+03 0.MI+00 1.86I+07
-34Ce-144 8.72B+05 3.61t+05 4.68t+04 0.00l+M 2.15B+05 0.00B+00 2.19t+08
'Allnuclides(exceptH-3)calculatedperODCHegnation2.3-25 1 1H-3calculatedperODCHegnation2.3-30 ISSUI3 ,
. 2-89
_ {
BV-1and2ODCM fable 2.3-12 R VALDIS FOR BIJER VALLEY S!!! (egseter-ares /yrperuC1/sec) Pathway: Heat AgeGroup: Child lluellde Bone Liver f. Body Thyroid Ildney Lung GI-LLI 1H-3 0.00E+00 2.34Et02 2.34I+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2P-32 6.291+09 2.94E+08 2.43Et08 0.00E+00 0.00E+00 0.00E+00 1.74E+08 3Cr-51 0.00l+00 0.00!+00 7.31E+03 4.08E+03 1.11X+03 7.41E+03 3.881+05 4Hn-54 0.00It00 5.661+06 1.51E+06 0.00E+00 1.591+06' O.00E+00 4.75E+06 5Fe-59 3.04I+08 4.911t08 2.45E+08 0.00E+00 0.00E+00 1.42E+08 5.12E+08 600-57 0.00E+00 4.21Et06 8.52t+06 0.00E+00 -0.00!+00 0.00!+00 3.45E+07 7Co-58 0.00!+00 1.28t+07 3.91E+07 0.00E+00 0.00E+00 0.00E+00 7.45E+07 800-60 0.00!+00 4.72E+07 1.39I+08 0.00!+00 0.00E+00 0.00E+00 2.61E+0B 4 9Zn-65 2.68tt08 7.15E+08 4.441+08 0.00E+00. 4.50E+08 0.00E+00 1.25E+08 10Rb-86 0.00l+00 4.871+0B 2.991+08 0.00l+00 0.00E+00 0.00!+00 3.13E+07 11Sr-89 3.85t+08 0.00!+00 1.10!+07 0.00H+00 000E+00 0.00E+00 1.491+07 12St-90 7.03E+09 0.00E+00 1.78I+09 0.00E+00 0.00l+00 0.00l+00 9.471+07 15T-91 1.42E+06 0.00!+00 3.81t+04 0.00E+00 0 E +00 0.00E+00 1.90E+08 14Zr-95 2.09E+06 4.591+05 4.09E+05 0.00E+00 6.57I+05 0.00E+00 4.791+08 15Nb-95 2.54E+06 9.90E+05 7.071+05 0.00E+00 9.30!+05 0.00!+00 1.83E+09 16lb-97 ********************************* 0.00E+00 *********** 0.00It00 *********** 17Ho-99 0.00!+00 9.791+04 2.42E+04 0.00!+00 2.091+05 0.00E+00 8.09E+04 . 18fc-99: 5.331-21 1.05I-20 1.73E-19 0.00!+00 1.521-19 5.31E-21 5.95E-18 ! 19Ra-103 1.261+08 0.00!+00 4.85E+07 0.00!+00 3.181+08 0.00!+00 3.26t+09 I 20Ru-106 3.12E+09 0.00l+00 3.89I+08 0.00E+00 4.21E+09 0.00E+00 4.85E+10 21Ag-110s 5.991+06 4.04E+06 3.23It06 0.00E+00 7.53E+06 0.00H+00 4.81E+0B 22Sb-124 0.00E+00 0.00!+00 0.00E+00 0.00E+00 0.00!+00 0.00E+00 0.00E+00 23Sb-125 0.00E+00 0.00!+00 0.00!+00 0.00l+00 0.00E+00 0.00!+00 0.00!+00 24fe-127a 1.33E+09 3.59tt08 1.581+08 3.191+08 3.80E+09 0.00E+00 1.061+09 25fe-129 1.471+09 4.11E+08 2.291+08 4.751+08 4.331+09 0.00l+00 1.80l+09 261-131 1.41E+07 1.42E+07 8.041+06 4.68t+09 2.32I+07 0.00!+00 1.26E+06 l 27I-133 4.841-01 5.991-01 2.27101 1.11E+02 9.981-01 0.00E+00 2.411-01 28Ce-134- 6.35t+08 1.04E+09 2.20!+08 0.00E+00 3.23I+08 1.16t+08 5.62E+06 29Ce-136 1.381+07 3.78I+07 2.451+07 0.00E+00 2.01E+07 3.00E+06 1.33E+06 j 30Cs-137 9.02E+08 8.631+08 1.27I+08 0.00E+00 2.815+08 1.011+08 5.40E+06 l 31Ba-140 3.72E+07 3.261+06 2.17Et06 0.00E+00 1.061+04 1.94E+04 1.891+07 l 32La-140 4.768-02 1.661-02 5.611-03 0.00E+00 0.00E+00 0.00E+00 4.63E+02 33Ce-141 1.83H+04 9.13H+03 1.36t+04 0.00l+00 4.00E+03 0.00!+00 1.14X+07 34Ce-144 1.64I+06 5.15t+05 8.77t+04 0.00E+00 2.85t+05 0.00E+00 1.34E+08 Allnuelldes(exceptH-3)calculatedperODCMequation2.3-25 H-3calculatedperODCHequation2.3-30 ISSOI3 2-90
F ) l l Bi-1and2ODCM Yable2.3-13 IVALUISFORBIAVIRVALLI7Slf! (etmeter-ares /rrperuC1/sec) ( Pathear:CowMilk AgeGroup: Adult helide Bone Lint . f. Body . Thyroid lidney Long GI-LLI 1H-3 0.00l+00 7.63I+02 7.63t+02 7.63E+02 7.631+02 7.63I+02 7.63E+02 2P-32 1.45t+10 9.01E+08 5.60l+08 0.00l+00 0.00l+00 0.00l+00 1.638409 3Cr-51 '0.00l+00 0.00l+00 2.381+04 1.42It04 5.24I+03 3.151+04 5.98I+0C 4Mn-54 0.00R+00 5.95t+06 1.13E+06 0.00t+00 1.77t+06 0.00l+00 1.82It07 5Fe-59 240l+07 5.63t+07 2.16t+07 0.00l+00 0.00l+00 1.57I+07 1.88I+06 6Co57~ 0.00t+00 9.10!+05 ~ 1.51t+06 0.00l+00 0.00l+00 0.00X+00 2.311+07 7 Co-58 0.00t+00 3.671+06 8.221+06 0.00t+00 0.00l+00 0.00l+00 7.43E+07 8Co-60 0.00t+00 1.121+07 2.46t+07 0.00l+00 0.00l+00 0.00l+00 2.10l+08 9Zn-65 9.80l+08 3.12X+09 1.41t+09 0.00E+00 2.09I+09 0.00l+00 1.968+09 10lb-86 -0.00l+00 2.191+09 1.02E+09 0.00t+00 0.00l+00 0.00l+00 -4.32I+06 11St-89 1.16I+09 0.00l+00 3.33t+07 0.00It00 0.00l+00 0.00l+00 1.861+08 12Sr-90 3.16t+10 0.00!+00 7.761+09 0.00E+00 0.00t+00 0.00E+00 9.14E+08 p i 13Y-91 14Zr-95 6.78t+03 0.00l+00 1.811+02 0.00E+00 0.00l+00 0.00E+00 3.73E+06 7.40l+02 2.37t+02 1.611+02 0.00t+00 3.721+02 0.00l+00 7.52I+05 15lb-95 6.77Et04 3.771+04 2.03I+04 0.00!+00 3.72E+04 0.00l+00 2.291+08 16Nb-97 2.811-12 7.111-13 2.601-13 0.00l+00 8.30I-13 0.00l+00 2.62I-09 17Mo-99 0.00l+00 2.11It07 4.01E+06 0.00t+00 4.77t+07 0.00t+00 4.881+07 18fc-99s 2.83E+00 7.991+00 1.02I+02 0.00It00 1.21t+02 3.911+00 4.73tt03 19in-103 8.291+02 0.00!+00 3.571+02 0.00l+00 3.161+03 0.00t+00 9.688+04 20In-106 1.43It04 0.00!+00 1.81t+03 0.00It00 2.771+04 0.00l+00 9.271+05 21Ar-110s 4.161+07 3.84E+07 2.281+07 0.00l+00 7.56I+07 0.00t+00 1.571+10 22Sb-124 0.00td0 0.00!+00 0.00!+00 0.00tt00 0.00l+00 0.00t+00 0.00E+00 23Sb-125 0.00!+00 0.00l+00 0.00!+00 0.00E+00 0.00l+00 0.00E+00 0.00l+00 24fe-127s 3.44t+07 1.23E+07 4.191+06 8.791+06 1.40l+08 'O.00l+00 1.15E+08 25fe-129s 4.95E+07 1.85t+07 7.84It06 1.70E+07 2.071+08 0.00l+00 2.491+08 l 261-131 2.521:08 3.60l+08 2.061+08 1.18t+11 6.17t+08 0.00l+00 9.50E+07 271-133 3.29I,06 5.72I+06 1.75t+06 8.411+08 9.99I+06 0.00E+00 5.14t+06 28Cs-134 3.891+09 9.27I+09 7.58t+09 0.00t+00 3.00l+09 9.96t+08 1.62I+08 29Cs-136. -2.23I+08 8.G2it08 6.35t+08 0.00E+00 4.911+08 6.73R+07 1.00E+08 30Cs-137 4.99t+09 6.821+09 4.471+09 0.00t+N 2.32E+09 7.70l+08 1.32E+08 31Ba-140 2.281+07 2.87I+04 1.49t+06 0.00E+00 9.74E+03 1.641+04 4.70It07 32La-140 3.84t+00 1.93t+00 5.111-01 0.00E+00 0.00l+00 0.00E+00 1.42t+05 33Ce-141 3.99t+03 2.70!+03 3.061+02 0.00l+00 1.25E+03 0.00l+00 1.03E+07
,_ 34Ce-144' 2.54t+05 1.061+05 1.36t+04 0.00l+00 6.291+04 0.00E+00 8.53t+07
. All nuclides (except H-3) calentated per ODCM egntion 2.3-24 H-3 calculated per ODCM equation 2.3-28 ISSUI3 2-91
~. . .. .
1
~
BV-1and2ODCM fable 2.3-14 RVALDISFORBIAVIRVALLifSifE (sqseter-ares /yrperuC1/sec) Patbaar:CowMilk AgeGroup: feen Nuclide~ Bone Liver f. Body Thyroid Ildney Lung G1-LLI 1H-3 0.00!+00 9.94t+02 9.94Xt02 9.94E+02 9.94E+02 9.94t+02 9.94E+02 2P-32 2.67tt10- 1.661+09 1.04I+09 0.00!+00 0.00l+00 0.00Et00 2.25E+09 3Cr-51 0.00!+00 0.00E+00 4.15E+04 2.31R+04 9.10It03 5.93tt04 6.971+06 4Ma-54 0.00t+00 9.911+06 1.96I+06 0.00E+00 2.95E+06 0.00E+00 2.03E+07 5Fe-59 4.181+07 9.76t+07 3.77t+07 0.00E+00 0.00!+00 3.081+07 2.311+08 600-57 0.00!+00 1.60l+06 2.68E+06 0.00E+00 0.00E+00 0.00!+00 2.98E+07 7Co-58 0.00E+00 6.17Et06 1.42E+07 0.00E+00 0.00E+00 0.00E+00 8.51E+07 600-60 0.00E+00 1.89E+07 4.26Et07 0.00E+00 0.00E+00 0.00E+00 2.46Et08 9Zn-65 1.51E+09 5.238t09 2.44R+09 0.00!+00 3.34I+09 0.00Et00 2.211+09 10Rb-86 0.00E+00 3.991+09 1.878+09 0.00E+00 0.00E+00 0.00E+00 5.91It08 11Sr-89 2.14E+09 0.00E+00 6.12Et07 0.00H+00 0.00E+00 0.00!+00 2.55E+08 12Sr-90 4.47I+10 0.00Et00 1.10l+10 0.00E+00 0.00It00 0.00!+00 1.25E+09 13Y-91 1.25E+04 0.00Et00 3.35Et02 0.00l+00 0.00Et00 0.00E+00 5.11E+06 14Zr-95 1.291+03 4.08t+02 2.81E+02 0.00Et00 6.00l+02 0.00E+00 9.42E+05 15Nb-95 1.16E+05 6.41E+04 3.53E+04 0.00E+00 6.21E+04 0.00E+00 2.74E+08 16Nb-97 5.13E-12 1.278-12 4.65E-13 0.00E+00 1.491-12 0.00E+00 3.041-08 17No-99 0.00Et00 3.80!+07 7.25H+06 0.00l+00 8.70l+07 0.00It00 6.81E+07 18fe-99: 4.90!+00 1.371+01 1.778+02 0.00E+00 2.04E+02 7.59Et00 8.98I+03 19Ha-103 1.47t+03 0.00ft00 6.30!+02 0.00Et00 5.20It03 0.00E+00 1.23E+05 20Ru-106 2.03Et04 0.00t+00 3.32It03 0.00E+00 5.08t+04 0.00!+00 1.261+06 21Ag-110 6.87I+07 6.50!+07 3.95tt07 0.00!+00 1.24H+08 0.00E+00 1.83E+10 22Sb-12( 0.00!+00 0.00!+00 0.00E+00 0.00Et00 0.00!+00 0.00!+00 0.00!+00 23Sb-125 0.00E+00 0.00l+00 0.00E+00 0.00E+00 0.00Et00 0.00t+00 0.00Et00 24fe-?27s 6.34t+07 2.25E+07 7.54It06 1.51Et07 2.571+08 0.00E+00 1.581+08 25fe-lus 9.081+07 136t+07 1.43E+07 2.92E+07 3.79E+08 0.00!+00 3.40!+08 26 1-131 4.571+08 6.39Et08 3.43E+08 1.87Et11 1.10E+09 0.00E+00 1.261+08 27I-133 6.01E+06 1.02E+07 3.11t+06 1.428t09 1.791+07 0.00!+00 7.71Et06 28Cs-134 6.76t+09 1.59Et10 7.38t+09 0.00l+00 5.06t+09 1.93E+09 1.981+08 29Cs-136 3.80E+08 1.50E+09 1.01It09 0.00E+00 8.15E+08 1.28E+08 1.20t+08 30Cs-137 9.05E+09 1.20E+10 4.191+09 0.00E+00 4.10l+09 1.591+09 1.71E+06 31Ba-140 4.12t+07 5.051t04 2.65tt06 0.00!+00 1.71E+04 3.39I+04 6.35E+07 32La-140 6.898+00 3.39E+00 9.011-01 0.00E+00 0.00E+00 0.00!+00 1.94E+05 33Ce-141 7.32E+03 4.89t+03 5.62E+02 0.00!+00 2.30!+03 0.00l+00 1.40E+07 34Ce-1H 4.67I+05 1.93E+05 2.51E+04 0.00E+00 1.151+05 0.00!+00 1.178+08 Allnuclides(exceptH-3)calculatedperODCMequation2.3-24 H-3calculatedperODCMequation2.3-28 ISSUI3 2-92
e ;. a BT-1and20D08 fable 2.315
'IVALUISF0IBIAVIIVALLI7Sitt (sqseter-ares /FrpernC1/sec) l Pathver:CoeHill AgeGroup:Ch!!d,
.Inclide' Bonei Liver: 17. Body Thyroid .Ildner Lung ~GI-LLI-1H-3 ' O.00l+M 11.57t+03 1.571+03 1.57I43 1.57I+03 1.57I+03 1.57I 4 3-2P-32' '6.59I+10 3.09t+09 2.548+09 - 0.00B+00 0.008 40' 0.00140. 1.82t+09 i
-3Cr-511 0.00E+00 !0.00E+00 . 8.46t+04 '4.70l+04 1,2854 4' 8.588+04 ' 4.495+06 4Hn-54 0.00E+00' 1.485+07 '3.95I46. 0.00l+00- 4.16I+06 0.HId0 '1.24I47 )
5Fe-59 l9.70I47 1.57td8 7.82t+07 0. M I+00 ; 0.00t+00 4.55I47 1.63I 4 8 - < i
.6Co 0.00l+00 ' 2.73t+06 5.52Id6 : 0.00I40 0.00t d0 0.00I40. 2.24I47 7Co-58' O.MIt00 9.43t+06- 2.895+07 0.008 40 - 0.00I 40 'O.00l+00 5.50t+07 1 8Co 0.00l+N 2.94X+07::8.671+07 0.00l+00 '0.00l+00 - 0.00B+00 1.63E+08 9Zn-65 2.95t+09 7.871+09 ; 4.891 49 0.00l+00. 4.96I 49 0.00l+00 '1.38t+09
'10lb-86 0.00l+00 7.40I49' 4.55I 49 0.00l+00 0.00l+M 0.00t+00 4.76I+08
- 11 St 5.29t+09 0.00l+00 1.511+08 0.M I+00. 0.00I 40. 0.00E+00 2.05t+08 12$r-90 7.55B+10 0.MI+00 1.91t+10 0.00l+00 0.00I40 .0.00840 1.02B+09 13Y-91' 3.08844 L 0.00840 ' 8.24X+02 .0.MI+00 : 0.00B+00 0.00l+M 4.11E+06
~14Zr-95' 3.00843 6.60B+02 '5.881+02 --0.00l+00~' 9.45E+02 0.00840 6.89I 4 5
(. L15lb-95 2.611+05 1.02E+05' 7.26I 44: 0.00E+00 9.54I+04 0.00l+00 -1.885+08-16Ib-97 1.25I-11 2.25I-12 1.058 0.00l+00 2.501 0.00l+M 6.94I-07
'17No-99 0.00I40 6.92X+07 1.711+07 ~ 0.00l+M 1.48I+08 0.00l+00 5.72E+07-18 fc-99 ' 1.12:t01 2.20It01- 3.65I 42 . 0.00B+00 3.20l+02- 1.12t+01 1.25t+04-19In-103 3.491+03 0.00B+00 1.34t+03 0.MI+00 8.78I+03 0.00l+00 -9.01t+04 20In-106 '6.49t+04.-0.00l+00 8.10l+03 0.00l+00 8.768+04 0.00l+00. 1.01E+06 21As-110a' 1.498+08 1.01t+08 8.05t+07 0. H I+00 ~1.87t+08 ' O.00E+00 =1.20l+10 22Sb-124 0.00ldo ' 0.00I40 ~ 0.00l+00 0.00l+00 0.00l+00 0.00l+00 0.00l+00
.23Sb-125 0.00l+00 0.00l+00 0.00l+00 0.00E+00 0.00l+00 0.00t+00 0.HI+00 124fe-127a- 1.56I48 4.21B+07 1.865+07 3.74I+07 4.46t+08 0.00l+M 1.27148 25fe-129s 2.23Id8 6.242+07- 3.47I+07 7.20l+07 6.56I+08 0.00I 4 0 2.72B+08
.261-131 -1.11B+09 1.11I 49 6.33I+08 3.68t+11 1.835+09 0.00l+00 9.92E+07 271-133~ ~1.46t+07. 1.21I 47 6.83It06 3.361+09 3.01t+07 0.00l+00 7.28I+06 28Cs-134 1.568+10 2.56h10 5.40I+09 0.00l+00- 7.93E+09 2.85t+09 1.38I+08 29Cs-136' 8.588+08 .2.368 03 1.53B+09 0.MI+00 1.26I+09 1.875+08 8.29t+07 30Cs-137 2.18t+10 2.098+10 3.08I+09 0.00l+00 6.80I+09 2.45E+09 1.311 48 31Ba-140 . 9.94I 4 7 8.71146 5.80146 0.00E+00 2.84I 4 4 5.19t+04 5.04I47 32La140 1.65E+01 5.77I+00 1.94E+00 0.00l+00 0.00t+00 0.00l+00 1.61E+05 ;
.33Ce-141- 1.80144 8.995+03 1.34t+04 0.00l+M 3.94t+03 0.MI+00 1.12E+07 34Ce-144. fl.15B+06 3.615+05- 6.15t+04. 0.00l+00 2.00l+05 0.00l+M 9.41t+07 ,
Allnue11 des (exceptH-3)calenlatedperODCNequation2.3-24
'H-3calculatedperODCHegnation2.3-28 ISSUI3 93
c BV-1and2ODCM fable 2.3-16 RVALUISFORBRAVIRVALLEYSifI (sgmeter-ares /yrperuC1/sec) Pathway:CowHilk AgeGroup: Infant helide Bone Liver f. Body Thyroid- tidney Lung GI-LLI 1H-3 0.00!+00 2.38Et03 2.381+03 2.381+03 2.381+03 2.381+03 2.38t+03 2P-32 1.361+11 7.99t+09 5.27E+09 0.00E+00 0.00E+00 0.00!t00 1.84E+09 3Cr-51 0.00t+00 0.00E+00 1.34H+05 8.75E+04 1.91E+04 1.70!+05 3.911t06 4Hn-54 0.00!+00 2.76t+07 6.25I+06 0.00E+00 6.111+06 0,00!+00 1.011:07 5Fe-59 1.811+08 3.161+08 1.25t+08 0.00E+00 0.00l+00 8.35t+07 1.51t+08 6Co .0.00!+00 6.368t06 1.03E+07 0.00t+00 0.00t+00 0.00!+00 2.171+07 700-58 0.00!+00 1.89t+07 4.70t+07 0.00t+00 0.00!+00 0.00!+00 4.70t+07 800-60 0.00Et00 '6.00!+07 1.42E+08 0.00t+00 0.00!+00 0.00!+00 1.43I+08 9Zn-65 3.978+09 1.36I+10 6.271+09 0.00t+00 6.60l+09 0.00l+00 1.15E+10 10Rb-86 0.00!+00 1.881+10 9.281+09 0.00E+00 0.00E+00 0.00E+00 4.81E+08 11Sr-89 1.01E+10 0.00!+00 2.891+08 0.00E+00 0.00!+00 0.00!+00 2.071+08 12Sr-90 8.22t+10 0.00!+00 2.0St+10 0.00l+00 0.00E+00 0.00!+00 1.03E+09 13T-91 5.795+04 0.00!+00 1.54t+03 0.00t+00 0.00!+00 0.00!+00 4.15E+06 14Zr-95 5.33t+03 1.30l+03 9.22t+02 0.00!+00 1.40!+03 0.00l+00 6.471+05 15Hb-95 4.878+05 2.01E+05 1.16I+05 0.00Et00 1.44t+05 0.00t+00 1.691+08 16Nb-97 2.631-11 5.621-12 2.03E-12 0.00E+00 4.391-12 0,00!+00 1.778-06 17Ho-99 0.00!+00 1.77Et08 3.45E+07 0.00t+00 2.64E+08 0.00!+00 5.83E+07 18fe-99: 2.34E+01 4.82E+01 6.21E+02 0.00E+00 5.191+02 2.52E+01 1.40!+04 19 h 103 7.061+03 0.00t+00 2.361+03 0.00E+00 1.471+04 0.00!+00 8.591+04 20Ru-106 1.34t+05 0.00E+00 1.671+04 0.00E+00 1.581+05 0.00t+00 1.011t06 21Ag-110s 2.75t+08 2.011+08 1.33H+08 0.00E+00 2.88t+08 0.00t+00 1.04t+10 22Sb-124- 0.00!+00 0.00!+00 0.00l+00 0.00!+00 0.00!+00 0.00!+00 0.00!+00 23Sb-125 0.00!+00 0.00!+00 0.00!+00 0.00t+00 0.00!+00 0.00l+00 0.00!+00 24fe-127 3.161+08 1.05t+08 3.83t+07 9.14E+07 7.791+08 0.00E+00 1.28t+08 25fe-129s 4.581+0B 1.571+08 7.061+07 1.761+08 1.15E+09 0.00!+00 2.74E+08 26I-131 2.31t+09 2.72E+09 1.20!+09 8.95t+11 3.18E+09 0.00!+00 9.72i+07 27I-133 3.081+07 4.49E+07 1.311+07 8.17t+09 5.28t+07 0.00t+00 7.60!+06 28Cs-134 2.51t+10 4.69t+10 4.73E+09 0.00t+00 1.21E+10 4.95t+09 1.271+08 29Cs-136 1.68t+09 4.93It09 1.84E+09 0.00t+00 1.971+09 4.021+08 7.49I+07 30Cs-137 3.48t+10 4.071+10 2.891+09 0.00t+00 1.091+10 4.43I+09 1.27t+08 31Ba-140 2.05t+08 2.051+05 1.05E+07 0.00Et00 4.86t+04 1.26tt05 5.02It07 32La-140 3.45E+01 1.368+01 3.50H+00 0.00!+00 0.00!+00 0.00!+00 1.60E+05 33Ce-141 3.571+04 2.181+04 2.57I+03 0.00E+00 6.72It03 0.00E+00 1.13t+07 34Ce-144 1.65t+06 6.75E+05 9.25E+04 0.00It00 2.73E+05 0.00t+00 9.471+07 Allnuclides(exceptB-3)calculatedperODCMequatica2.3-24 H-3calculatedperODCMequation2.3-28 ISSUI3 2-94
BV-1and2ODCM O fable 2.3-17 V. RVAl#tSFORBliVIRVALLEY51TI (H teter-stes/yr per sci /see) 1stbvar:GoatMilk AgeGroup: Adult Nuclide Bone Liver f. Body thyroid Ildney Lang GI-LLI ) 1 1H 0.00l+00 1.56t+03. 1.56I+03 1.56t+03 1.568+03 1.56E+03 1.561+03 2P-32 '1.74I+10 1.081+09 6.72t+08 0.00l+00 0.00t+00 0.00l+00 1.96t+09 3Cr51' O.00l+00 0.00l+00 2.dI+03 1.70tt03 6.28t+02 3.78t+03 7.17I+05 4Hn-54 _0.00t+00 7.14It05 1.36t+05 0.00t+00 2.12I+05 0.00l+00 2.19I+06 5Fe-59 3.12t+05 7.32t+05 2.81t+05 0.00l+00 _ 0.00t+00 2.05I+05 2.44t+06-6Co-57 0.00It00 1.09t+05 1.82t+05 0.00l+00 0.00t+00 0.00t+00 ?77I+06 7Co-58 0.00E+00 4.40l+05 9.861+05 0.00t+00 0.00l+00 0.00t+00 6.91t+06 8Co-80 .0.00l+00 1.34I+06 2.96I+06 0.00t+00 0.00t+00 0.00l+00 2.52E+07 9In-65 1.18t+08 3.74t+08' 1.69t+06 0.00t+00 2.50l+08 0.00l+00 2.36I+08 1 10Rb-86 0.00l+00 2.63t+08 1.22E+08 0.00l+C0 0.00t+00 0.00t+00 5.188+07 j 11St-89 2.43t+09 0.00l+00 6.99I+07 0.00t+00 0.00t+00 0.00t+00 3. f+08 12St-90 6.64t+10 -0.00t+00 1.63t+10 0.00t+00 0.00l+00 0.00t+00 1.92E+09 ! 13T-91 8.14I+02 0.00l+00 2.18t+01 0.00t+00 0.00t+00 0.001400 . 4.18t+05 ! O 14Ir-95 15lb-95 8.871+01 2.85t+01 1.93t+01 0.00t+00 4.47I+01 0.00t+00 9.02I+04
-8.13E+03 4.52t+03 2.43t+03 0,00t+00 4.47I+03 0.00l+00 2.74t+07 16Ib-97 3.367-13 8.5C-14 3.121-14 0.00E+00 9.961-14 0.00t+00 3.151-10 17Mo-99 0.00g+00 2.53I+06 4.81E+05 0.0nI+00 5.72t+06 0.00l+00 5.861+06
'18fe-99: 3.391-01 9.591-01 1.22It01 0.00t+00 1.46t+01 4.70E-01 5.678+02 19lu-103 9.95E+01 0.00t+00 4.291+01 0.00t+00 3.80l+02 0.00!+00 1.16I+04 l 20 Ra-106 1.72t+03 0.00It00 2.18t+02 0.00t+00 3.32t+03 0.00t+00 1.111+05 21Ag-110s 4.99t+06 4.811+06 2.74E+06 0.00t+00 9.071+06 0.00t+00 1.88t+09 22Sb-124 0.00R+00 0.00t+00 0.00!+00 0.00l+00 0.00E+00 0.00t+00 0.00E+00 23Sb-125 0.00l+00 0.00t+00 0.00tt00 0.00E+00 0.00l+00 0.00!+00 0.00t+00 24fe-127m 4.13t+06 1.481+06 5.03t+05 1.05t+06 1.68t+07 0.00l+00 1.381+07 25fe-129: 5.94t+06 2.22t+06 9.41E+05 2.04t+06 2.4BI+07 0.00l+00 2.99t+07 261-131 3.02E+0B 4.32t+08 2.481+06 1.42E+11 7.40!+08 0.00!+00 1.14I408 271-133 3.95t+06 6.87t+06 2.09t+06 . 1.011+09 1.20t+07 0.00!+00 6.17t+06 28Cs-134 4.675+08 1.11I+09 9.091+08 0.00!+00 3.60l+08 1.19t+08 1.95E+07 29Os-136- 6.70l+08 2.65I+09 1.90!+09 0.00t+00 1.47t+09 2.02t+08 3.01E+08 30Cs-137 1.50l+10 2.05E+10 1.34t+10. 0.00E+00 6.95t+09 2.311+09 3.96t+08 31Ba-140 2.74I+06 3.44E+03 1.79t+05 0.00t+00 1.171+03 1.971+03 5.64t+06 32La-140 4.608-01 2.321-01 6.13t-02 0.00t+00 0.00l+00 0.00l+00 1.70l+04 33Ce-141 4.791+02 3.24t+02 3.68t+01 0.00!+00 1.51t+02 0.00!+00 1.24t+06 34Ce-144 3.05t+04 1.27t+04 1.64I+03 0.00E+00 7.55t+03 0.00t+00 1.03t+07 C- Allnuelldes(exceptH-3)calculatedperODCMequation2.3-24 H-3calculatedperODCMequation2.3-28 1550I3 2-95
BV-1and2ODCM fable 2.3-18 RVALUESFORBEAVIIVALLIISITE (egseter-ares /yrperuC1/sec) Pathway:GoatMilk AgeGroup: feen hclide Bone Liver f. Body Thyroid lidney Lung GI-LL1 1H-3 0.00!t00 2.03I+03 203t+03 2.03E+03 2.03E+03 2.03E+03 2.03E+03 2P-32. 3.21E+10 1.99E+09 1.2(I+09 0.00!+00 0.00E+00 0.00E+00 2.70E+09 3Cr-51 0.00t+00 0.00E+00 4.981+03 2.771+03 1.091+03 7.11E+03 8.371+05 (Mn-54 0.00!+00 1.195+06' 2.361+05 0.00!+00 3.55I+05 0.00!+00 2.44t+06 5Fe-59 5.44t+05 1.27I+06 4.90l+05 0.00!+00 0.00!+00 4.00l+05 3.00E+06 600-57 0.00!+00 1.92E+05 3.211+05 0.00E+00 0.00E+00 0.00E+00 3.571+06 7Co-58 0.00!+00 7.40E+05 1.71E+06 0.00l+00 0.00E+00 0.00l+00 1.02E+07 8Co-60 0.00E+00 2.27I+06 5.11t+06 0.00l+00 0.00E+00 0.00E+00 2.96t+07 9Zn-65 1.81E+0B 6.271+08 2.93E+08 0.00E+00 4.01E+08 0.00E+00 2.661+08 10Rb-86 0.00E+00 4.79E+08 2.25E+08 0.00E+00 0.00E+00 0.00!+00 7.09t+07 11St-89 4.49E+09 0.00!+00 1.291+08 0.00E+00 0.00E+00 0.00l+00 5.35E+08 12Sr-90 9.39E+10 0.00E+00 2.32E+10 0.00E+00 0.00E+00 0.00E+00 2.64E+09 13Y-91 1.50t+03 0.00l+00 4.01t+01 0.00E+00 0.00E+00 0.00E+00 6.14E+05 14Zr-95 1.55E+02 4.90E+01 3.371+01 0.00E+00. 7.19E+01 0.00E+00 1.13E+05 15Nb-95 1.391+04 7.698+03 4.23E+03 0.00E+00 7.45E+03 0.00E+00 3.291+07 16Hb-97 6.151-13 1.531-13 5.571-14 0.00E+00 1.791-13 0.00E+00 3.65I-09 17Ho-99 0.00E+00 4.561+06 8.70l+05 0.00E+00 1.04H+07 0.00E+00 8.17I+06 18fc-99: 5.881-01 1.64E+00 2.13E+01 0.00E+00 2.45t+01 9.118-01 1.08E+03 19 h-103 1.771+02 0.00E+00 7.56I+01 0.00E+00 6.2(R+02 0.00E+00 1.481+04 20Ra-106 2.44E+03 0.00E+00 3.98t+02 0.00E+00 6.10E+03 0.00l+00 1.52E+05 21Ag-110s 8.2(I+06 7.80!+06 4.75H+0B 0.00E+00 1.49E+07 0.00E+00 2.191+09 22Sb-124 0.00E+00 0.001:00 0.00!+00 . 0.00E+00 0.00E+00 0.00E+00 0.00Et00 23Sb-125 0.00E+00 0.00E+00 0.00!+00 0.00E+00 0.00E+00 0.00l+00 0.00E+00 24fe-127: 7.61E+06 2.70t+06 9.05E+05 1.81E+06 3.08Et07 0.00E+00 1.90E+07 25fe-129s 1.091+07 4.03E+06 1.72Et06 .3.51E+06 4.55E+07 0.00E+00 4.08E+07 26I-131 5.481+08 7.67I+08 4.12E+08 2.2(E+11 1.32E+09 0.00l+00 1.52E+08 271-133 7.21E+06 1.22E+07 3.73I+06 1.71E+09 2.15E+07 0.00ft00 9.26F+06 28Cs-134 8.11E+0B 1.91t+09 8.86E+08 0.00l+00 6.07I+08 2.32X+08 2.38E+07 29Cs-136 1.1(E+09 4.491+09 3.02E+09 0.00!+00 2.44E+09 3.85E+08 3.61E+0B 30Cs-137 2.71E+10 3.61E+10 1.262+10 0.00E+00 1.23E+10 4.77E+09 5.14H+08 31Ba-140 f.94It06 6.061+03 ' 3.18t+05 0.00E+00 2.05E+03 4.071+03 7.62E+06 32La-140 8.27E-01 4.06E-01 1.08E-01 0.00E+00 0.00l+00 0.00t+00 2.33I+04 33Ce-141 8.79E+02 5.87E+02 6.74E+01 0.00!+00 2.76E+02 0.00E+00 1.6BE+06 34Ce-144 5.60l+04 2.32E+04 3.01E+03 0.00l+00 1.391+04 0.00E+00 1.41H+07 Allnuclides(exceptH-3)calculatedperODCHequation2.3-24 H-3calculatedperODCMequation2,3-28 ISSUE 3 2-96
a 7
' IV-1and2ODCU t
' fable 2.3-19; RVALUIS70IBIATIITALLI7S17I (seseter-stes/rrperuC1/sec)-
~Pathser: Goat 511k:
}AssGroup: Child-Nuclide_ lens : t Lint ' f. Body .Thrroid Ildner Lang. GI-LLI 1 E - 0.005 40-l3.20l+03 ' 3.20l+03 ~ 3.20E+03~~ 3.20I43 ~ 3.20l+03- 3.20l+03 2P-32',
7.91E+10 3.70849 L3.05td9 0.00I 40 - 0.00540 0.005@ 2.19t+09 13Cr-51 s0.00540 0.00540 :1.02E+04 .5.64E+03 -: 1.54I4 3 1.03t+04 . 5.39I45-
' 4Ma54 10.00I40 1.78146 4.7 G 45< 0.005 40 4.99I45 0.00I40 1~. 498+M
$Fe '1.265+06 0 2.04546 :1.02I+06 0.MI+00 0.00B+M : 5.915 4 5 2.12546 l'
- 6Co-57 0.00I00 3.278+05 6.638+05 0.005 40 .0.00l+00 0.00ld0 2.68I 4 6
. 7Co-58 0.00l+00: 1.13I46- 3.46t d6 0.00E+00 0.00I40 0.HI+00 .6.60I46 8Co 0.00l+001.3.53I43 1.0G+071 0.00l+M 0.00I 40 ' O.00l+00 1.95E+07.
. - 9 !a-65 : 3.5Gd8 9.44B+08 5.87I+08'~0.00E+M 5.95E+08 0.00l+00' 1.865 48 toIb ' O.00E+00- 8.888 48 5.46t+08 0.00I40 0.00I40 0.00l+00 : ' 5.71147 .
11Sr-89 1.11E+10:'O.00l+M 3.17I+08 0.M I+00- 0.00l+00 0.00l+00 4.30E+08
- 12Sr-90 1.595+111 0.00l+00 4.02I+10 0.00l+00 0.00l+M 0.00l+M ~ 2.1G+09 13Y 3.705d3 ' O.00l+00 9.89I+01'. 0.00l+00 - 0.M I+00. 0.001 40 4.93I 4 5 O 14Ir-95.
15lb-95 3.605d2 7.92B+01 7.05I41 0.00l+00 1.13E+02 0.00!do 8.27544 3.13Id4 1.22t+04 8.71I+03 0.00l+00 1.14I44 0.00l+00 2.25t+07
- 16lb-97' 1.49I-12 2.708 1.265-13 0.00l+00 2.991-13 0.00l+M -8.33I-08 _
17No-99 0.00I<00 8.30I 46 2.05I 46. 0.M I d0 1.771+07 0.M I+00 ' 6.87546 ' 18fc-99s. 1.35I 40- 2.65t+00 4.398+01- 0.00t+00 3.84I+01 1.3Gt00 1.515+03 19In-103 4.18t+02 0 00l+00 1.61t+02 0.M I+00 1.05t+03 0.00l+00 1.08I+04 20In-106 -7.79t+03 0.00l+00 -9.72I42 0.00l+00 1.05t+04- 0.00It00 1.21t+05~ 21As-110s :1.79I47 - 1.21I47 9.65td6 0.00l+00 2.25I 4 7. 0.00I 4 0 1.44t+09 22Sb-124 0.00l+00 0.MI+00 0.MI+00 0.00l+00 0.HI+00 0.MI+M 0.MI+M
- 23Sb-125 0.00l+00 0.00l+00 0.00l+00 0.00l+00O.00l+00 0.00l+00 0.00I40 247e-127s 1.685+07 ' 5.05I46 2.23I46 4,48I+06 5.35I+07 0.00l+M 1.52E+07 257e-129s 2.685+07 7.48I46 4.168+06 8.64t+06 7.87I+07 0.00l+M 3.27I+07 j
~ 26I-131 1.33549 1.34t+09 7.60l+08. 4.42t+11 2.195+a9 0.00l+M 1-.195+08
- 27I-133. 1.75B+07 2.178+07 8.20I 46 4.03I 49 3.611 0.MI+M 8.73E+06 28Cs-134- 1.87I+09: 3.071+09 f.48I+08 - 0.0 H+M 9.52548 3.42t+08 1.665+07 29Cs-136" 2.585+0J - 7.088+09 4.58I 4 9 0.00B+00 3.77Id9 5.62148 2.49td6 30Cs-137 6.54I+10 6.28t+10 9.24I49 0.00l+00 2.04I+10 7.34t+09 3.92t+08 ,
31Ba-140- 1.19E+07 1.05E+06 6.96t+05 0.00l+M 3.40I 4 3 6.23t+03 6.04I+06 32La-140 1.98540 6.92I-01 2.33I-01 0.MIt00 0.HI40 0.00l+00 1.93E+04 l 33Co-141 2.16t+03 1.08I+03 1.60l+03 0.00l+00 4.73I+02 0.00l+00 1.35I 4 6 6 34Ce-144 1.38t+05^ 4.38t+04 7.37I+03 0.00l+00 2.40144 0.00l+00 1.13t+07 l i O. Allnuclides(exceptH-3)calesistedperODCMegnation2.3-24
~
H-3calesistedper0D0Hegiation2.3-28 k ISSUI3
?-97 .a..
BV-1and2ODCH fable 2.3-20 RVALUESVORBEAHRVALLEYSITE (etmeter-ares /yrperuC1/sec) Pathway:GoatM11k AgeGroup: Infant i luclide Bone Liver f. Body Thyroid Eidney les GI-LLI 1H-3 0.00F00 4.86003 4.86bO3 4.86bO3 4.86E+03 4.86003 (.86bO3 2P-32 1.63D11 9.59b09 6.32b09 0.00D00 0.00D00 0.00D00 2.21E+09 3Cr-51 0.00h00 0.00b00 1.61b04 1.05b04 2.29bO3 2.04b04 4.69b05 4Hn-54 0.00b00 3.31h06 7.50b05 0.00h00 7.33b05 0. N O 1.21b06 5Fe-59 2.35b06 4.11b06 1.62b06 0.00b00 0.00b00 1 1.96b06 600-57 0.00b00 7.64b05 1.24b06 0.00b00 0.00b00 0.00b00 2.60D06 700-58 0.00b00 2.26b06 5.64b06 0.00h00 0.00b00 0.00D00 5.64bM 8Co-60 0.00b00 7.20b06 1.70bO7 0.00D00 0.00b00 0.00D00 1.71bO7 9Zn-65 4.76h06 1.63h09 7.53b08 0.00b00 7.92bO8 0.00b00 1.36b09 10Rb-86 0.00b00 2.25b09 1.11b09 0.00h00 0.00b00 0.00D00 5.77bO7 11St-89 2.11b10 0.00h00 6.06bO8 0.00b00 0.00b00 0.00b00 4.34bO8 12Er-90 1.73b11 0.00h00 4.39b10 0.00h00 0.00h00 0.00D00 7.16b09 13T-91 6.9tbO3 0.00 BOO 1.85bO2 0.00h00 0.00b00 0.00b00 4.98b05 14Zr-95 6.40bO2 1.56bO2 1.11bO2 0.00D00 1.68bO2 0.00b00 7.77b04 15Bb-95 5.84b04 2.41b04 1.39b04 0.00b00 1.72b04 0.00b00 2.03h07 16Hb-97 3.16E-12 6.74E-13 2.43b13 0.00h00 5.27E-13 0.00b00 2.13E-07 , 17Ho-99 0.00b00 2.12bO7 4.14b06 0.00b00 3.17D07 0.00D00 6.99b06 18fe-99: 2.81b00 5.79b00 7.46b01 0.00D00 6.23b01 3.03b00 1.68bO3 19Ru-103 8.47bO2 0.00b00 2.83bO2 0.00D00 1.76bO3 0.00D00 1.03b04 20Ru-106 1.60b04 0.00b00 2.00bO3 0.00 BOO 1.90D04 0.00b00 1.22b05 21Ag-110s 3.30bO7 2.41bO7 1.60bO7 0.00b00 3.45bO7 0.00b00 1.25b09 22Sb-124 0.00D00 0.00b00 0.00b00 0.00b00 0.00h00 0.00b00 0.00 BOO 23Sb-125 0.00b00 0.00D00 0.00b00 0.00 BOO 0.00b00 0.00b00 0.00h00 24fe-127 3.80bO7 1.26bO7 4.59b06 1.10bO7 9.35bO7 0.00D00 1.53bO7 25fe-129s 5.50bO7 1.89b07 8.47h06 2.11bO7 1.38bO8 0.00D00 3.28bO7 l 26I-131 2.77b09 3.27b09 1.4(b09 1.07b12 3.82bo9 0.00b00 1.17bO8 27l-133 3.70bO7 5.39bO7 1.58bO7 9.80D09 6.34bO7 0.00000 9.12b06 I 28Ce-134 3.02bC3 5.62b09 5.6BbOB 0.00bO0 1.45b09 5.93 BOB 1.53bO7 29Cn-136 5.03b09 1.48b10 5.52b09 0.00D00 5.90D09 1.21h09 2.25 BOB 30Cs-137 1.04b11 1.22b11 8.66b09 0.00D00 3.28b10 1.33b10 3.82bO8 l 31Ba-140 2.(5bO7 2.45b04 1.26b06 0.00D00 5.83h03 1.51h04 6.03b06 32La-140 4.14b00 1.63b00 4.195-01 0.00000 0.00b00 0.00 BOO 1.92b04 33Ce-141 4.29bO3 2.62bO3 3.08bO2 0.00D00 8.07h02 0.00D00 1.35b06 34Ce-144 1.9Bb05 8.11b04 1.11b04 0.00D00 3.28b04 0.00b00 1.14bO7 Allnuclides(exceptB-3)calenlatedper00CHeguation2.3-24 ! H-3calculatedperODCHequation2.3-28 ISSUI3 l 2-98 t
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- 000 900 4 111 011 11111 11101 EEE E E E-164 EEEEE-92944 EEEEE 52614 k 027 58928 i 5 097 001 13932 vf 3 447 163 32223 44814
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S1 5 M EEE E E E-EEEEE 29628 EEEEE-72665 R> N 650 145 19801 82152 E I 0 130 350 IR EO ,3 561 164 42334 56116 M S AR E 0 RY C 900 00000 00990 A/ I 009 11001 PS T 3 110 011 11111 R A - - - - - - - - - - - - - NH C - EEE EEE EEEEE EEEEE O O 747 694 52162 56500 I0 L 5 555 759 54706 43510 M S0 195 64545 88129 C R5 L 2 781 D 2 E> O C 2 P SS
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990 00000 99999 0 N 999 2 3 IE - 9 11111 00000 1 DS s C 2 000 001 - d A r C - - - - - - - - n 2 SE e - EEE EEE E E E E E- EEEE E- 2 a E rL t E 824 076 29481 09198 L rE e H 0 022 534 32170 21292 1 B eR V m( I 2 112 218 96858 11221 V- H TE L O B T V 0 99999 E S 999 999 99909 E 2 000 000 00010 00000 C - - - - - - - - - - D N - EEE E E- E E E E E E- EEEEE 7mL oR CG N U O A T 5 S I 1 D 197 884 113 422 614 321 55677 41294 11181 74062 86681 12342 2S 5 999 999 99999 99999 U 00000 00000 DO 1 000 000 NU EEE EEE EEEEE EEEEE AN I 471 194 96602 42389 1T 0 232 575 50266 37467 N 22212 34683 VO 1 336 632 BC R 0 889 99999 98889 - 998 00000 m 1 000 000 00000 EEE EEE EEEEE E- EEEE 73074 397 55D 02720 5 732 306 79353 91600 0 791 115 54645 71129 5 88878 888 888 88888 0 000 000 00000 00000
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- E E E- EEE 422 EEEEE-55677 E E E E-0000W 7406 EN 197 41294 86681 VU B 5 884 614 -
O S 11181 12342 EB I 1 113 321 - - TG D - I SS 5 99999 U 999 999 99999 00000 2O 1 000 000 00000 - - DN U
- E E E- 194 E E E- EEEEE-96602 EEEEE 42389 -
NI 471 50266 37467 ATN 0 232 575 34683
~
1 336 632 22212 1G - VR B C 0 998 889 99999 98889 00000 P 1 000 000 00000 - - -
- EEE E E- E 550 EEEEE-02720 EEEEE 73074 397 79353 91600 5 732 306 0 791 115 54645 71129 5 88888 88878 888 888 00000 00000 _
0 000 000 -
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/
NS T 3 110 011 11110 11001 IR SH A C - EEE EEE 694 EEEEE-52162 E E E- E- E 56590 R O 747 54706 43510 E0 I 5 555 759 M P0 195 64545 88129 C S5 L 2 781 D 4 I> O O 2 D ) R T 5 2
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n a 2 E L TS NA E VN te re C O 2 t i 0 000 E E E-824 022 001 EEE 076 534 11111 EEEEE 29481 32170 EEEEE 09198 21292 2 O 1 B GP m u . 218 96858 11221 A N ( 2 112 V- T IL O B DE I' 0 LV 999 99909 99999 IE 999 00000 UL M 2 000 000 00010 B - EEE E E E- EE E- E E E E-D N - EEE 422 55677 74062 EN A 197 614 41294 86681 NU T 5 884 IC S 11181 12342 BB I 1 113 321 RG D U IS 5
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- E E E- E E- E- EEEEE EEEEE 622 783 94716 09592 0 443 702 28660 64212 0 457 763 32323 46915 R
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- PR ,3 561 164 42334 56116 N O. S OR IY I
G 0 - S/. I 009 900 00000 00990 t T 3 110 011 11110 11001 3 S - - ER PB. A C - E E E- E E E- EEEEE-52162 EEEEE-56590 Y S 0 5 747 694 43510 54706 L I0 1 555 759 M N D05 L 2 781 195 6'4545 88129 C O T O D 5 C 2N
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534 96858 1122l I 2 112 218 V-B BN I UL BEV O T a m R GE S 0 999 999 99909 99999 O F NL E 2 000 000 00010 00000 I HD C N - E E E-EEE E E E E E-55677 EEEEE-74062 SN 197 422 86681 IU B 5 884 614 41294 t LO S 11181 12342 _ OR I 1 113 321 ' PG D ES 5 999 999 99999 99999 TU 000 00000 00000 AQ 1 000 - SU NN - EEE E E E- EEEEE 96602 EEEEE-42389 EI 471 194 37467 50266 OT 0 232 575 m B N 1 336 632 22212 34633 _ O0 a C0 . 2R 0 998 889 99999 98889 00000 VO B F 1 000 000 00000 EEEEE- - EEEEE-w
- E E E- E E E- 02720 73074 m.
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622 783 64212 - 0 443 702 28660 _ u 46915 0 457 763 32323 - R E E N N N t w O T E E E E N S ES SN S NNca m C NteN EEE SSSSS WWNNf - E s e S . u m b _
li 3 E 0 00000 00000 U 000 000 11111 S 111 11111 S d 111 - - - - - - -
- I EEE E E E- EEEEE E E E- EE 75514 5
4 826 326 234 927 338 531 92693 05939 21131 71749 23462
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. 000 000 00000 11111 4 111 111 11111 EEE EEE EEEEE 55905 EEEEE-85939 149 858 0 996 502 58373 387_85 4 235 642 21212 33573 0 00000 00090 000 900 11101 4 111 011 11111 - -
EEE E E E- EEEEE EEEEE 027 164 92944 52614
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// 3 447 153 32223 44814 DS S
( R H E 5 L 009 900 00000 00990 S I 3 110 011 11111 11001 R0 - - - - - - - - - - E5 M EEE EEEEE EEEEE I1 - E E- E- 145 29628 72665 E> N I 0 650 130 350 19801 82152 M AR 561 164 42334 i6116 RC S
,3 A N PR O 0 Y 009 900 00000 00990 N/ I T 110 011 11110 11001 OS A 3
IR SH C - EEE EEE EEEEE E- E E E E-747 694 52162 56590 Y R D 5 555 759 54706 43510 L E0 I M P0 195 64545 88129 C W S5 L 2 O 781 D 6 I> R 4 O D ) 2N- S I
- 5 999 990 00000 99999 0 1
2 d n a
- 3. TI 2A E e L u B e TE ~s NS E
VM tre GM NF m e m C E H 0 T 2 000 E E E-824 022 001 EEE 076 534 11111 E 29481 32170 E- - - - EEE 00000 E E E E- E-09198 21292 2-1 2 112 218 96858 11221 nIN I ( V- DL D B LE I' R IV 0 999 999 99909 99999 O UE 00010 00000 F BL 9= 2 000 000 E- EEEE-- - E E E- E E-ND - E E E- EEE 74062 ON t A 197 422 55677 IU T 5 884 614 41294 86681 TO S 113 321 11181 12342 AR I 1 NG D I ML 5 999 999 99999 99999 AO 1 000 000 00000 00000 IO - - - TN U EEE E E- E-EEEEE 96602 EEEEE-42389 CI 471 194 37467 232 575 50266 EC Dt 0 336 632 22212 34683 0 1 2C R 0 99999 98889 VU B E 1 998 000 889 000 00000 00000 E E E-EEE EEEEE E- E- -EEE 73074 397 550 02720 5 752 306 79353 91600 0 791 115 54645 71129 5 88888 88878 888 888 00000 0 000 000 00000
- EEE E E E- EEEEE EEEEE 622 783 94716 09592 0 443 702 28660 64212 0 457 763 32323 46915 R
O E E E ES E W SW W S W NWN W T NE N S C NNN EEE SSSSS WWWNN E S
s ?
- 3 0 E 000 000 00000 00000 U 5 111 111 11111 11111 S
- - - - S ER 87 6 E-E E E-927 EEEEE-92693 EEEEE-75514 I
5 376 338 05939 71749
. t 4 234 531 21111 23462 5
000 000 00000 00000 4 111 111 11111 11111 _ c -- E E E-E E E-858 EEEEE-55905 EEEEE-85939 149 0 996 502 58373 38785 4 235 642 21212 33573 0 00090 000 900 00000 = 4 111 011 11111 11101 EEEEE-
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( R S H E 5 00990
- S L 009 900 011 00000 11111 11001 R0 I 3 110 E5 T1 M
E E E-E E E- EEEEE EEEEE-72665 - E> N 650 145 350 29628 19801 82152 M I 0 130 AR ',3 164 42334 56116 RO 561 A S PR N Y C 0 9' 0 00000 00990 _ N/ I T 009 11110 11001 OS 3 110 01 1- - - IR SB A C - E E E- EEE EEEEE 52162 EEEEE-56590 - Y R O 747 555 694 759 54706 43510 L E0 I 5 M .E P0 195 64545 88129 C C S5 L 2 781 0 7 I> O - 0 2N- C D S2
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TE 999 990 00000 99999 3. I T NS s N C 2 000 001 11111 00000 1 2A M EA r VEL et C
- EEE EEE EEEEE-29481 EEEEE-09198 2
ER E 824 076 32170 21292 1 LU BE TE e LR n ( H 0 T 022 534 AN U 2 __ 112 218 96858 11221 V- TI AL O B VEV T 0 R T EE S 999 999 99909 99999 E GL E 2 000 000 00010 00000 A RD C N - E E- E- E E E-422 rEEEE-55677 EEEEE 74062 OE TC A T 5 197 884 614 41294 86681 SO S 11181 12342 R I 1 113 321 SG D A GS 5 999 99999 99999 U 999 00000 00000 EO 1 000 000 - TU - - - - - - - SN - E E E- EEE EEEEE EEEEE AI 471 194 96602 42389 WT 0 232 575 50266 37467 N 2C 1 336 632 22212 34683 VC BET 0 998 889 99999 00000 98889 00000 E 1 000 000 E E E-397 550 E E E- EEEEE-02720 E E E E- E-73074 5 732 306 79353 91600 0 791 115 54645 71129 5 88878 888 888 88888 0 000 000 00000 00000 E E E-E E E-EEEE5 94716 EEEEE-09592 622 783 0 443 702 28660 64212 0 457 763 32323 46915 5) 0(, R E E E W W N N O E NNN T NE N S ES SW S C NNN EEE SSSSS WWNNN E S V
BV-1 cnd 2 ODCM TABLE 2.3-28 BV-1 AND 2 PROCESS VENT DISPERSION PARAMETERS (D/0) FOR CONTINU0US ELEVATED LEVEL REL!'ASES >500 HRS /YR OR >150 HRS /0TR FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3) (1E-9 meters ~) INDIVIDUAL RECEPTORS ___ DOVNVIND SITE VEGETABLE GARDEN HILK COV HILK GOAT MEAT ANIMAL RESIDENCE SECTOR BOUNDARY
.600 2.340 -- .572 .707 2.510 N
.673 3.220 -- .524 2.920 3.220 NNE
.766 1.280 .660 .111 .660 1.200 NE 1.010 5.080 -- .702 -- 1.760 ENE 1.370 4.420 .401 1.290 1.290 4.420 E
.984 6.390 -- 2.340 6.390 6.180 ESE 11.000 3.680 .466 .466 1.300 3.680 SE 7.060 3.220 .423 .105 3.140 4.320 SSE 5.780 1.540 1.410 -- 2.610 2.730 S
2.040 1.040 .578 .208 1.040 1.460 SSV 1.610 1.120 -- .693 .979 1.120 SV 1.310 .370 1.190 1.310 VSV 1.710 --
.659 .138 -- .518 .659 V .377
.424 .746 .497 .029 .746 .746 VNV
.425 .070 .488 .422 NV .447 --
1.840 .043 .545 1.92 NNV .340 --
'l 1
1 I 1
)
l I l O; 2-106 ISSUE 3
BV-1 cnd 2 ODCM TABLE 2.3-29 7% . -BV-1 AND 2 CONTAINMENT VENTS DISPERSION PARAMETERS (D/0) () ' FOR CONTINUOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRS /QTR FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3) (IE-9 meters" ) l INDIVIDUAL RECEPTORS DOWNVIND SITE VEGETABLE GARDEN- MILK COV MILK GOAT MEAT ANIMAL RESIDENCE SECTOR BOUNDARY. 25.40- 2.05 .693 . 847 2.19-N- -- 18.80 2.02 -- .459 1.850 2.11 NNE 63.40 29.30 .455 .078- .455- 30.40 NE ENE 65.90. 8.92 -- .661 -- 32.20 38.00 3.90 .382 1.020 1.020 22.70 E 17.10 3.56 -- 1.380 3.560 3.56 ESE 13.80 3.03 .350 .350 1.100 3.03' SE' 10.50 2.65 .317- .094 2.570 3.68 SSE 1.05 .934 1.860 1.95 S 10.60 -- 1.26 .663 .266 1.260 4.42 / SSV 5.59. 2.21 1.320 1.920 2.21 SV 3.94 -- 27.50 2.65 .596 -- 2.380 :2.65 WSW 1.23 .645' .960 1.23 g V 31.60- -- 2.23 i VNV 39.10 2.23 1.490 .045 2.230 15.00 .276 1.990 15.60 NV 70.60 -- 6.52 .068 1.090 9.91 -l NNV 31.50 -- l l i O Qi 2-107 ISSUE 3
l 1 BV-1 and 2 ODCM l TABLE 2.3-30' l l l BV-1 AND 2 VENTILATION VENTS DISPERSION PARAMETERS (D/0) l FOR CONTINUOUS GR0bND LEVEL RELEASES >500 HRS /YR OR >150 HRS /QTR FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3) j (IE-9 meters-) l I INDIVIDUAL RECEPTORS DOVNVIND SITE VEGETABLE GARDEN MILK COV MILK G0AT HEAT ANIMAL RESIDENCE SECTOR BOUNDARY 25.40 2.05 -- .693 .847. 2.19 l N 18.80 2.02 -- .459 1.850 2.11 . I NNE 63.40 29.30 .455 .078 .455 30.40 NE 65.90 8.92 -- .661 -- 32.20 ENE i 38.00 3.90 .382 1.020 1.020 22.70 l E 17.10 3,56 -- 1.380 3.560 3.56 } ESE 13.80 3.03 .350 .350 1.100 3.03 i SE 10.50 2.65 .317 .094 2.570 3.68 l SSE 10.60 1.05 .934 -- 1.860 1.95 S 5.59 1.26 .663 .266 1.260 4.42 SSV 3.94 2.21 -- 1.320 1.920 2.21 SV 27.50 2.65 .596 -- 2.380 2.65 VSV V 31.60 1.23 .645 -- .960 1.23 39.10 2.23 1.490 .045 2.230 2.23 , VNV 70.60 15.00 -- .276 1.990 15.60 j NV 31.50 6.52 -- .068 1.090 9.91 NNV i l 2-108 ISSUE 3
E b - BV-1Lsnd 2 ODCM-j' TABLE 2.~3-31 l.
- / BV-1 AND 2 TURBINE BUILDING VENTS DISPERSION PARAMETERS (D/0)
- T FOR CONTINUOUS GROUND LEVEL RELEASES >S00 HRS /YR OR >150 HRS /0TR l
,' JFOR:SPECIAL DISTANCES (IDENTIFIED.IN TABLE 2.2-3):
-(1E-9 meters ~)
INDIVIDUAL RECEPTORS DOWNVIND SITE VEGETABLE GARDEN MILK COU MILK GOAT- MEAT ANIMAL RESIDENCE SECTOR- BOUNDARY 20.20 2.~ 05 --- .693 .847 2.190
~N-34.90 2.02. -- .459 1.850 2.110 NNE NE 54.20 '29.30 .455 .078 .455 30.400 57.50 8.92 -- .661 --- 32.200 ENE 38.10 3.90 .382 1.020 1.020 22.700 E
18.60 3.56 --- 1.380 3.560 3.560 ESE 19.00. 3.03 .351 .351 1.100 3.030 SE 13.30 2.65 .318 .094- 2.570: 3.690 SSE 11.30 10.40 .934 -- 1.860 1.950
" S-1.26 .664 .266 1.260 4.430 SSV: 6.44 .2.210 SV 3.95 2.21- -- 1.320 1.920 2.65 .597 2.380- 2.650 VSV 25.10 --
1.23 .646 .961 1.230 V- 28.40- -- 2.230
.045 2.230 l
O, VNV NV 30.90 56.10 2.23 14.90 1.490
-- .276 1.980 15.500 ;
6.53 .068 1.100 9.920 NNV 25.10 -- l ' i I I I l 2-109 ISSUE 3 W
BV-1 cnd 2 ODCH TABLE 2.3-32 FOR INFORMATION ONLY BV-2 CONDENSATE POLISHING BUILDING VENT DISPERSION PARAMETERS (D/0) FOR CONTINUOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRS /0TR FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3) (IE-9 meters-2) INDIVIDUAL RECEPTORS D0VNVIND SITE VEGETABLE HILK COV HILK GOAT HEAT ANIMAL RESIDENCE SECTOR BOUNDARY GARDEN 2.05 .693 .847 2.190 N 20.20 -- 2.110 34.90 2.02 -- .459 1.850 NNE 29.30 .455 .078 .455 30.400 NE 54.20 8.92 .661 -- 32.200 ENE 57.50 -- 3.90 .382 1.020 1.020 22.700 E 38.10 3.560 ESE 18.60 3.56 -- 1.380 3.560 3.03 .351 .351 1.100 3.030 SE 19.00 3.690 13.30 2.65 .318 .094 2.570 SSE 10.40 .934 1.860 1.950 S 11.30 -- 1.26 .664 .266 1.260 4.430 SSV 6.44 2.21 1.320 1.920 2.210 SV 3.95 -- 2.650 USV 25.10 2.65 .597 -- 2.380 1.23 .646 .961 1.230 V 28.40 -- 2.23 1.490 .045 2.230 2.230 VNV 30.90 14.90 .276 1.980 15.500 l NV 56.10 - j 25.10 6.53 -- .068 1.100 9.920 NNV l l l l 1 l l O'l 2-110 ISSUE 3 i l
,c - a BV-1;and 2 ODCM TABLE l2'.3-33 FOR.INFORMATION ONLY . 3
/'T -
BV-2 DECONTAMINATION BUILDING VENT DISPERSION PARAMETERS (D/0) ] V FOR CONTINUOUS GROUND LEVEL RELEASES >500 HRS /YR'OR >150 HRC/QTR i i
'FOR'SPECIAL DISTANCES (IDENTIFIED IN TABLE-2.2-3)
(IE-9 meters-2) 1 INDIVIDUAL RECEPTORS
, D0VNVIND- SITE- VEGETABLE l BOUNDARY GARDEN. MILK COV MILK GOAT' MEAT ANIMAL RESIDENCE .j 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 5.59 1.26 .663 .266- 1.260- 4.420 SSV
-SV' 3.94 2.21 --
1.320 1.920 2.210 WSV. 27.50 2.65 .596 -- 2.380- 2.650 V 31.60 1.23 .645- -- .960 1.230 39.10 2.23 1.490 .045 2.230 2.230 VNV 70 15.00 -- .276 1.990 15.600 NV < 31.. 6.52 -- .068 1.090 9.910 NNV i a.
%)
2-111 ISSUE 3
- 'l BV-1 cnd 2 ODCH TABLE 2.3-34 FOR INFORMATION ONLY BV-2 VASTE GAS STORAGE VAULT VENT DISPERSION PARAMETERS (D/0) FOR CONTINUOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRS /QTR FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3) (IE-9 meters-2) INDIVIDUAL RECEPTORS D0VNVIND SITE VEGETABLE GARDEN HILK COV HILK GOAT HEAT ANIMAL RESIDENCE SECTOR BOUNDARY 25.40 2.05 -- .693 .847 2.190 N 18.80 2.02 -- .459 3.850 2.110 NNE NE 63.40 29.30 .455 .078 .455 30.400 ENE 65.90 8.92 -- .661 -- 32.200 38.00 3.90 .382 1.020 1.020 22.700 E 17.10 3.56 -- 1.380 3.560 3.560 1 ESE 13.80 3.03' .350 .350 1.100 3.030 l SE 10.50 2.65 .317 .094 2.570 3.680 i SSE l 10.60 1.05 .934 -- 1.860 1.950 S 5.59 1.26 .663 .266 1.260 4.420 SSV 3.94 2.21 -- 1.320 1.920 2.210 l SV 27.50 2.65 .596 -- 2.380 2.650 ( VSV 1.23 .645 .960 1.230 V 31.60 -- 39.10 2.23 1.490 .045 2.230 2.230 i VNV ' 70.60 15.00 -- .276 1.990 15.600 NV 6.52 .068 1.090 9.910 NNV 31.50 -- 0 2-112 ISSUE 3
I;
'BV-1 cnd 2 ODCM TABLE 2.3-35 . (~y BV-1 AND 2 CONTAINHENT VENTS DISPERSION ~ PARAMETERS (X/0) .Q. FOR BATCH GROUND LEVEL RELEASES $500 HRS /YR OR <150 HRS /QTR POR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3)
(sec/m }- INDIVIDUAL RECEPTORS DOWNWIND- SITE , VEGETABLE
, SECTOR
- BOUNDARY. GARDEN HILK COV HILK GOAT MEAT ANIMAL RESIDENCE N 8.'21E-5 8.38E -- 3.72E-6 4.34E-6 8.82E-6 NNE 3.04E-5 4.71E-6 .-- 1.40E-6 4.3 7-6 4.87E-6 NE 4.59E-5 2.21E-5 6.05E-7 1.38E-7 6.0.L-7 2.28E-5 ENE 3.72E-5 5.25E-6 .-- 5.66E-7 -- 1.88E 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 2.033-6 5.00E-6 SSE '2.21E-5 6.31E-6 1.11E-6 3.92E-7 6.13E-6 8.49E-6 S 2.15E-5 3.03E-6 2.76E-6 -- 4.93E-6 5.14E-6 SSV 2.18E-5 6.58E-6 3.81E-6 1.82E-6 6.58E-6 1.78E-5 SV- 1.82E-5 1.03E-5 -- 6.67E-6 9.12E-6 1.03E-5 VSW 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 1.72E-5 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
- 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 cnd 2 ODCH 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 (IDENTfFIED IN TABLE 2.2-3) (sec/m ) INDIVIDUAL RECEPT 0RS D0VNVIMD SITE VEGETABLE HILK COV HILK GOAT HEAT ANIHAL RESIDENCE SECTOR
- BOUNDARY GARDEN 9.75E-5 1.00E-5 -- 4.21E-6 4.95E-6 1.06E-5 N
5.11E-6 1.438-6 4.72E-6 5.30E-6 NNE 3.78E-5 -- 2.70E-5 6.20E-7 1.40E-7 6.20E-7 2.81E-5 NE 6.13E-5 4.83E-5 5.58E-6 -- 5.71E-7 -- 2.24E-5 ENE 3.99E-6 5.25E-7 1.19E-6 1.19E-6 2.10E-5 E 3.66E-5 6.13E-6 ESE 2.99E-5 6.13E-6 -- 2.43E-6 6.13E-6 2.55E-5 5.29E-6 8.24E-7 8.24E-7 2.13E-6 5.29E-6 SE 2.65E-5 6.72E-6 1.12E-6 3.95E-7 6.53E-6 9.22E-6 SSE 2.52E-5 3.14E-6 2.83E-6 -- 5.29E-6 5.53E-6 S 7.34E-6 4.15E-6 1.92E-6 7.34E-6 2.09E-5 SSV 2.60E-5 1.18E-5 SV 2.13E-5 1.18E-5 -- 7.41E-6 1.04E-5 1.51E-5 4.46E-6 1.38E-5 1.51E-5 1.34E-4 !' VSV 1.25E-5 7.40E-6 -- 1.02E-5 1.25E-5 V 1.77E-4 ' 2.07E-5 1.49E-5 1.30E-6 2.07E-5 2.07E-5 VNV 2.33E-4 8.85E-5 NV 3.32E-4 8.57E-5 -- 4.24E-6 1.64E-5 < 1.90E 4 4.69E-5 -- 1.45E-6 1.09E-5 6.75E-5 NNV l l
- Measured relevant to center point between BV-1 and BV-2 Containment Buildings Period of Record: 1976 - 1980 2-114 ISSUE 3
. BV-1 'cnd 2 ODCH :
. TABLE 2.3 BV-1 AND 2 PROCESS VENT DISPERSION PARAMETERS (X/0)
O, ~FOR BATCH ELEVATED RELEASES <500 HRS /YR OR'<150 HRS /0TR
.FORLSPECIAL DISTANCES (IDENTIFIED IN' TABLE 2.2-3)
~
(sec/m ). l INDIVIDUAL RECEPTORS ; j DOVNVIND SITE VEGETABLE j GARDEN MILK COV MILK GOAT MEAT ANIMAL RESIDENCE
-SECTOR
- BOUNDARY' N 3.09E-9' 3.30E-6' -- 1.13E-6' 1.34E-6 3.36E-6 2.68E 6.52E 2.47E-6 2.68E26 NNE- 2.85E-9 - - -
.NE 2.02E-10 . 7.42E-9 : "5.44E-7 -1.24E-7 5.44E '5.51E-9_ ll
'3.21E-6 6.29E-7 -- 1.67E-9 ENE. 1.02E-9 --
2.15E-9 "2.91E 4.96E 1.14E-6 1.14E-6 2.91E-6 E:
'6.90E-9 4.97E-6~ -- 1.95E-6 .4.97E-6 4.81E-6 ESE:
2.91E-6 3.52E 6.02E-7 6.02E-7 1.43E-6 3.52E-6 SE
'4.91E-6 3.56E-6 6.53E-7 2.18E-7' 3.47E-6 '4.71E-6 SSE-2.41E-6 1.78E-6 1.65E-6 -- 2.84E-6 2.96E-6
! :S 4.83E-6 -2.52E-6 1.50E-6 6.60E-7 2.52E-6 3.96E-6 L SSV 4.82E-6 2.75E-6 -- 1.78E-6 2.44E-6 2.75E-6 SV' l - 5.77E-7 '2.81E-6 8.79E-7 -- 2.57E-6 2.81E-6 l VSV. l
'1.68E-6 4.89E-7 -- 1.37E-6 1.68E-6 j V' 2.88E-9' O VNV-NV
-3.40E 1.34E-9 1.61E-6 3.31E-8 3.73E-6 1.13E-6
-1.10E-7 2.03E-7 l'.73E-7 1.61E-6 1.07E-6 1.31E-6 1.61E-6 3.10E-8 3.81E-6 1
NNV - 1.52E-9 --
)
l l l 1
- Measured' relevant'.to BV-1 natural draft cooling tower Period of Record:~ 1976 - 1980 2-115 ISSUE 3 L
3 E 0 U S 7777-5 7777 7777 7777 S e I EEEE E E E E-E E E E- EEEE 8906 6122 2382 0757 5 0838 8863 0780 4865 4 5453 4333 4455 5444 7 5 8 9 4 7777
- 7777- 7777 EEEE
- 7777-EEEE 1
- EEEE E E- EE 4299 0827 ,
3446 1725 0 0 9630 1339 7689 8243 3 4 5566 5443 4565 5555 y r a 0 u n 4 7777- 7777 7777 EEEE
- 7777-EEEE J a
- EEEE E E E E- 4172 8128 3163 2644 2315 6614 n 5 1572 9772 o 3 7667 6555 6677 7466 1
- 4 S 2
) d E 5 2 Qv L 7777- 1 -
//
KS I 3 M 7777-EEEE 7777-EEEE 7777 E E E E- EEEE . { R - 4045 5396 6593 O. B N 4585 7715 8700 S I 0 8022 7 8 1 0._ J
- n. 0 ,3 8899 8676 7789 4788 r a5 1 S e Er 3 N O 0 d
n M AR I T 3 6666 6777 6666 6666 u RO A - - - - A PR C - E- E E E- EEEE EEEE E- E E- E 1 8 3393 2382 7811 5788 Y D 5 1111 1954 1010 2100 9 N/ I 9 N OS L 2 1111 1999 1111 1111 2 C IR - D 8 SH O S C 3 R B L 6
- E0 ) I 5 D 1 N
9_ 2 3 P0 6666 2 1 O 2 6666 6666 6666 d n 2 I3 S5 D - c
/m C
- E E E E-E E E E-4419 EEEE-9856 EEE 9960 E- r e
2 a E S e E 1626 4332 5424 6544 t L TE s H 0 5376 t 1 B NS ( T 1111 1111 1111 e - A EA 2 1111 l V- T VF O B T . SM SF S 0 p r E 2 6666 6666 6666 6666 o E - - - Cw O C N - E E E E-EEEE 3495 EEEE-4899 E E E E-9245 C Rl A 5 1981 4921 g PAV T 6122 2099 3112 n S 2222 2122 i - 2R I 1 2222 2211 r D e DM N 5 e n Ai 6666 6886 i d 1 6686 6666 EEEE g n 1 i
- EEEE- EEEE 7883 EEEE 7476 1676 E V A'B 0 0390 1836 7433 9841 2636 r B
R 2333 3233 4583 e O 1 4272 t F s b 0 e - 1 5688 6666 6666 6886 W EEEE- EEEE EEEE d
- EEEE 2215 2481 n 7977 0636 a 5 0368 1218 1213 d.4 9 9 e 0
1518 5534 4699 4113 n o t - 5 7865 S 5765 53 1111 0 1111 1188 7558 - - a
- - - - - - - i EEEE EEEE EEEE EEEE v 5052 4660 2586 4511 -
0 7949 8915 2705 4269 l 1293 1128 5921 a 0 2541 t R E W W W W t i m s n 8 01 E E E SES SWS NWN a
; NEN EESS SSSW WWNN r NNNE T u
- S
Fil -" (f , * , , BV-1 end 2 ODCH h .., . 2.41 Gaseous Radvaste System J fD. The. gaseous radwaste1 syst'em' has the' capability to control,. collect, ds_,/ - process, store, recycle, and dispose of. gaseous radioactive vaste generated Eas J a- result iof. -plant . operations,' including ' anticipated operational occurrences. AEsimplified flov diagram of the. gaseous radwaste system for BV-l'and BV-2 is provided asL Figure ~ 2.4-1. 'A . diagram showing the. gaseous effluent Lrelease points is provided as Figure 2.4-2; SinceLthe. concept of a shared
. gaseous'radvasten system is used, 'then gaseous vaste generated'can be-stored,' processed,-and-discharged from either BV-1 or BV-2.-
t 9 O.- i 4
- D U-2-117 ISSUE 3 l
.j
? ; I BV-1 Cnd 2 ODCH f i BV-1 Gaseous Radvaste System Components
~ ~2.4.1 2.'4.1.1 BR-EV-2A & 2B: Degasifiers f There are two.Degasifiers. They are designed'to continuously procers reactor coolant letdown for reducing entrained noble gases in the liquid.
2.4.1.2 GV-E-1A & 1B: Vaste Gas. Chillers j i There are two Chillers. Non-condensable gases from the degasifiers are i directed by system' pressure to the Waste 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 i directed to the Waste Gas Charcoal. Delay Beds for holdup of xenon and ! krypton and adsorption of radioiodines. When four beds are operated in
. series, they provide a holdup of xenon isotopes for about 30 days.
2.4.1.4 GV-FL-SA & 5B: Overhead Gas Compressor Prefilters There are two Prefilters. The gaseous effluent (primarily hyu ogen) is directed from the Gaseous Vaste Charcoal Delay Beds to one of the overhead Gas Compressor Prefilters. The filters remove carbon solids i from the gas stream. 2.4.1.5 GV-C-1A & 1B: 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 1 f 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. J
]
2.4.1.7 GV-TK-1A, 1B, & 10: Vaste Gas Decay Tanks There are-three Decay Tanks. Each has a capacity of 132 cuft. The j 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. , i a l I I
)
O i, ; l 2-118 ISSUE 3 j _ 9
'BV-1 and 2 ODCM 2.'4.1.8 :RM-GV-108 And RM-GV-109: Gaseous Effluent Radiation Monitors pj .. .
;There are redundant? Radiation . Monitors on ,the combined BV-1 and'2 gaseous vaste ' release path. .. 'these ' Radiation Monitors continuously analyze gaseous vaste.as.it is Lbeing discharged. Gaseous Monitor RM-
.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 the== Radiation Monitors have setpoints that would indicate
.ve are approaching the Total . Body- Dose Rate or Skin Dose Rate limits for. radioactive gas leaving the site. If an upper activity. alarm on RM-GV-108'is-received, it automatically terminatesthe' discharge by closing-an isolation. valve downstream of the Decay Tanks.
q(^%. 2-119 ISSUE 3
)
i BV-1 cnd 2 ODCM-2.4.2 BV-2 Gaseous Radvaste System Components ; 2.4.2.1 2BRS-EV21A & 218: Degasifiers l There are four Degasifiers.(two at Unit 1 and two at Unit 2). They are ) designed to continuously process : reactor coolant letdown for reducing l 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 radioiodines. 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 Waste Gas Charcoal Delay Beds to one of the Overhead Gas Compressor Prefilters. The filters remove carbon solids from the gas stream. l 2.4.2.5~ 2GVS-C21A & 21B: Gas Compressors
'There are two Compressors. The vaste gas enters one of the compressors ,
I 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 compression to about 65 psig, the vaste gas is sent to the Surge Tank. This can be done automatically or manually.
'2.4.2.7 2GVS-TK25A, 25B, 25C, 25D, 25E, 25F, & 25G: Gaseous Vaste Storage Tanks There are seven Decay Tanks. Each has a capacity of 132 cuft. The contents of the Surge Tank is transferred to the Decay Tanks for ,
storage and decay. After 30 days of storage, all xenon and iodine I should have decayed, and the resulting predominant nuclide should be krypton 85. 2.4.2.8 RM-GV-108 And RM-GV-109: Gaseous Effluent Radiation Monitors i Previously described in Section 2.4.1. ' O, ; 2-120 ISSUE 3 l l l
1 BV-1 cnd 2 ODCH FIGURE 2.4-1 BV-1 AND 2 GASEOUS RADVASTE SYSTEM .%h) \ J Nfkft R ff f 70 Afno$NDI l t 7 I - m m I I
,,,,' c0.lfillan .
045 GAS ,3 PhDILTER$ " C. PRESSOR' Co@RESSOR f i i i i
.
- w '
i ( SURGE f_ .SURGE TAR m e , i j C.Anc0AL 3D) r- MS DECAT T M
...c t ,D) 4 ,_ ,_ j
~
o_ (__ .) , <- ! (- -) 4 - ,. )- l _ ,_ q__ ! , ,
> car um oscar i m
<__ p q__ p A
,g ,
=
X = 3:ensma "_" . ..um+g im co O
*C
====
com, . m mcm + +
.mu. .im , .
... -i c0.SM O
2-121 ISSUE 3
BV-1 a.3 TM FIGURE i BV-1 AND 2 GASEOUS EFFLUENT RELEASE POINTS
+ Ohio River
- P i
i o, 4.2 V x e x 5 g x/ =
-s 1 N. -
. 1 b' i i_ sm Unit 2
( 1 Unit i i 1 i O c-)
)
l Felease Point & Description Elevation
- 1. Unit 1: Ventilation Vent 79 feet = 24 meters
- 2. Unit 1: Containment / SLCRS Vent 154 feet = 47 meters
- 3. Unit 182: Process vent 475 feet = 145 eneters
- 4. Unit 2: Ventilation Vent 85 feet = 26 noters
.5. Unit 2: Contairvnent / SLCRS Vent 154 feet = 47 meters
- 6. Unit 2: Condensate Polishing Building Vent 80 feet = 24 meters d"' 7
- 7. Unit 2:. Waste cas Storage vault vent
- 8. Unit 2: Decontamination Building Vent 80 feet = 24 meters 80 feet = 24 meters
[
- 9. Unit 2: Turbine Building vent 109 feet = 33 meters i Note: The Rettase Point shown for the Unit 2 Turbine Building vent is f7 a representative exhaust point for the 10 roof exhaust outlets.
2-122 ISSUE 3 Revision 3
VL , , h/ ' m , LBV-1 End12 ODCM i3.0 L RADIOLOGICAL ENVIRONMENTAL MONITORING -PROGRAM L The'following ' program -requirements- area: excerpts from: the' Radiological 2 Assessment BranchjTechnical' Position,'_ Revision 1,,1979.- J
- Table'3.0-1 contains: thel DLC-..' site. number,-sector, distance, sample point
~
. ; description,'1 sampling ; and collection ; frequency, f analy' sis, and analysis!
.frequencyEforLvarious < exposure 'pathwaysL in fthei vicinity of.the Beaver
? Valley Power Station'for;the radiological environmental monitoring program.-
~
Figures (3.0-1 throughL3.0-9'..show -the . location .of.Lthe various-sampling. l points.
.. PROGRAM REQUIREMENTS. ,
TEnvironmental;samplesishall be collected and: analyzed according to. . Appendix ~C, Teble 3;0-1.' ' Analytical techniques used shall be_such that the detection' capabilities in Appendix C, Table 4.12-1 are achieved. i The results.of the' rediological -environmental-' monitoring are intended to l supplement the-results of'the radiological' effluent monitoring by verifying that the measurable concentrations of radioactive materials and ley?.ls of radiation are 'not' higher thanL expected on the- basis of the effluent
- measurements and modeling _ of the environmental _ exposure uathways. Thus, the;apecified; environmental;l 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: Lindividualsg resulting from .the. ' station operation.; .The'. Initial-x . 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 operationalLexperience.
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 ef fort.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 1 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 l 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.
- v. -
3-1 ISSUE 3
, \
- J
BV-1 and 2 ODCH j f 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 enironmental monitoring in order to demonstrate the results are reasonably valid. A census shall be conducted annuelly during the growing season to determine tne loce. tion of the nearest milk animal and nearest garden greater than 50 square meters (500 sq. ft.) producing broad lea' ,,.: station in each of For hthe16meteorologicalsectorswithin a distance or o km (5 miles).
/ elevated releases as defined in Regulatory Guide 1.111, Rev. 1, the census shall also identify the locations of all milk an;mals, 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 ODCH dose calculations, a vritten report shall be submitted to the Director of Operating Reactors, NRR (with a copy to the Director of the NRC Regional Office) within 30 days identifying the new Hilk animal or garden locations location f:istance and direction). 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 sor"e!H ance program after notifying the NRC in writing that they are no lont;er obtainable at that location. The results of the land-use census shall be reported in the annual report. The census of nilk 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 j contaminated by airborne radioiodine is a major potential source of i exposure. Samples from milk animals are considered a better indicator of l radioiodine in the environment than vegetation. If the census reveals milk { animals are not present or are unavailable for sampling, then vegetation 1 I must be s opled. O. 3-2 ISSUE 3 ) Revision 2 i l . - . .
. .. . I
BV-1 and 2 ODCM
'Ihe 50 square meter garden, considerire 20% used for growing broad leaf.' '
vegetation 2 (i.e., similar to' lettuce and cabbage),. and a vegetation yield of [f] 2 kg/m , . will produce the 26 kg/yr assuned in Regulatory Guide 1.109, Rev. L - () 1, '.for child cmstmption of leafy vegetatim. , //97
. 1 l - Ihe increase in the number of direct radiaticn stations is - to better
! characterize the individual exposure . (mrem) and perdatim exposure (man-rem) in accordance with Criterien 64 - mcnitoring radioactivity releases,' of 10 CFR Part 50, AppaMk A. The NRC will place a similar amount of statims in the area between the'two rings designated in Appendix C, Table 3.12-1. l-l i 1 t l i i M 1
- k 3-3 ISSUE 3 Revision 2 l
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BV-1 and 2 ODCN FIGURE 3.0-1 RADIOLOGICAL EN71RotNEtTTAL 10NITORIIG PROGRAM AIR SAMPLIIG IOCATIOtIS n~ - h arlington
% ) [F Q*- ' _
i
' rig l U' d
rs Negley ^- ' '
. I J7 l
*y @0 10 mile r'abus', ,4 gEastvfe
[ ,Bdaver alls Heights l 's Marion i d' port (MNew B nn .
\
f {t Fredericktown as a s. Nea ,,_,, "1 f .FairWw e Freedorr alem r t g#
# 46.1
';h " A *>
L asuippa. ,o ( 8 4
^
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"~ .New She g;i.raaius g
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, j er
, 7 , Bon M dew Manches.or f i -
\ \
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/ iWeirton Control Site, #48 Sector 10,16.3 miles, not shown] l ,_.../
)
y i New cumbertand i -
'- sinton 4
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./ .santi 'ff?
6 - Air Sampline Locations 5ccior bite # Distance Location (miles) 11 13 1.4 Meyer s Farm 4 30 U.) Shippmgport (5. b.) 13 32 U.5 Midiand (5.5.) J 46.1 2.3 Industry, Kt. ,3 Uarage 10 45 16.4 Wctrion, W. Va.,-W earton Water lowct, Collict Way 3-8 ISSUE 3 Revision 5 l
- 6 BV-1 and.2 ODCM FIGURE 3.0-2 RADIOILGICAL ENVIRONMENIAL f(EIIORIl0 PROGRAM TLD IOCTCICNS -
}ttr- -*
f
- f {
, arlington #
l l 6 rs Negley 'M ' a
)
LEastwh -
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,B ver alls O n Heights b
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- Freedom icutta hy 9 m g p $#70 Od 9I I
# 46 J A
' F
> # 93 M I
# 15 g Igpi
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>Ba s ,
Bea& alley , 30 3 b I j
*' #1 O# 6 O She l 10 Mile Radius] # 95 9 O, t
.#3 -
p . echanicsburgS#27 ' 'O ' '
* ~
+B00 M i 54 82 C
] Weirton Control Site, #48 Sector 10,16.3 miles, not shownl - -
New Cumberland 1 /
)
+ "
l 0 - -Y E ~ 3-9 ISSUE 3 Revision 5
- p. ~
BV-1 and 3 ODCM FIGURE 3.0-2 Ocntinued RADIOI4GICAL EtWIPftNENTAL MONI'IORIN3 PROGRAM TLD LOCATIONS Southeast Sector Site # Dirtance Location : - Sector $lte # Distance Location (miles) No5 (miles) 7 27 6.1 Brunton's Farm um 7 78 2.7 Raccoon Municipal Bldg. 6 45.1 1.9 Raccoon Twp., Kennedy 8 79 4.4 Rt.151 & Pross Ln. Corners 97 La 5 51 8.0 Aliquippa (S.S.) cg 9 80 8.2 Raccoon Park Otfice-Rt. ib 18 6 59 1.0 236 Green flill Road # 9 82 6.9 Ficnover Municipal Th Building 6 76 3.8 Raccoon Llementary 4 8 94 2.2 McCleary Road & Pole Cat School @h flollow Road 6 77 5.6 3614 Green Garden Road rx vi+ AN7 W +im - A m Northwest Sector Site # Distance Location , Sector Site # Distance Location - (miles) @ (miles) 14 15 3.7 Georgetown Post Ollice e 14 87 7.0 Calcutta, Oh. - Calcutta Smith's Ferry Rd & Valley j! 0 , Drive 15 32 0.8 Midland (S.S.) g;^ 15 88 2.8 Midland Fleights - 110 Summit Road i4 47 4.9 E. Liverpool, Oh. (Water 15 89 4.8 Ohioville - 488 Smith's Company) W Ferry Road 13 60 2.5 Hancy's Farm - 16 90 52 Opposite Fairview School 13 86 6.2 E. Liverpool, Oh.,1090 ._ 16 93 1.1 Midland -Sunrise Hills Ohio Avenue W4 Nortbeast Sector Site # Distance Location 4 Sector Site # Distance Location 4 (miles) R (miles) 4 10 1.0 Shippingport Boro fj i 70 3.4 North of Western Beaver 4 School- Engle Road i 28 8.6 Shermen's Farm y 2 71 6.0 Brighton Twp., First M Western Bank 3 29B 8.0 Beaver Valley Geriatric >g 3 72 33 Industry, Logan Park j Ctr. M j
"/tB 4 30 0.5 Shippingport (S.S.) m 4 73 2.5 618 Squirrel Run Road f 5 45 2.2 Rt.18 & Anderson Street p,;) 4 74 7.0 CCBC- 137 Poplar !
d Avenue 3 46 2.5 Industry, Midway Drive .n 5 75 4. i 117 Holt Road 3 46.1 2.3 Industry, Rt. 68 - Garage 7, 2 91 3.9 Pine Grove Rd. & Doyle P d. Southwest Sectre Site # Distance Location Sector Site # Distance Location (miles) 4 w (miles) ii 13 1.4 Meyer's Farm i1 84 8.3 Hancock Co. Parks & p< { Recreation Complex 11 14 2.5 Hookstown .m 12 85 5.7 Rts. 8 & 30:ntersection 10 48 16.3 Weirton, W. Va., Weirton . .. , 12 92 2.8 Georgetown Road WaterTower CollierWay W 9 81 36 Millcreek United Presb. 7ty; 10 95 23 832 McCleary Road Church _ 10 83 4.2 735 Mill Cred Road . 3-10 ISSUE 3 Revision 5
BV-1 and 2 ODCM l FIGURE 3.0-3 RADIOWGICAL DWIRONENIAL M2TrIORHG PROGRAM (j SHORLINE, SEDDENI', SURFACE WAIER, RU DRINKING WATER SAMPLING LOCATIOG v ~" /
) & '
- 9. I' '
. 7 Den .
0$ , Midland .SNppingport_ i
~
l 25 ' N ' 9 d ver.Vahty Power 'on ' 2A O 4 - i- . anlesburg r s e tm o.t-- s e an ts4 / de \ w - Water / Shoreline Sediment Sampling Locations l'/9)$ Sample T)pe Sector Site # Dtstance Locatim / (miles) Surface Water 14 2.1 1.5 Downstream, Midland . J&L Surface Water 3/4 49/49.1 50/5.3 Upstream side of Montomery Dam' NOVA Chemicals Seditmerd _ i3 2A 0.2 BVPS Outfall Dncharge Dnnking Water 15 4 1.3 Midland Water '. reatment Plant Drinkmg Water 14 5 4.9 E. Liverpool, Olt Water Treatment Plant 3-11 ISSUE 3 Revision 5
BV-1 and 2 ODCM FIGURE 3.0-4 RADIGOGICAL ENVIRCNETIAL ITNITORING PROGRAM MILK SAMPLING IDCM'ICUS f C f (
, ariington i N ..'
-Q ' l C d Negley >% / ,
e
'%j u g l Bdaver ans on Heights f .
l l r ,Marion
, M -A In w a ?p sport
$ f '** '
" East Roches: I Freedon'
~
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z-
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3* Midi
*"** ,l!
,shippir
[ f < verv by rowerstati # , y j ter q H n V .New She i s4 - i j *D . 4 , echanicsdura 1, - o
~
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s s
\ ) l New cumberiand . ,
'* won 4
. b y' e m eL . h .
Milk Sanpling Locations sector site # astance locauan 1 (miles) l 10 25* 2.1 scanght's tarm 10 96 10.4 Windshemxt f arm
*Three daines based on highest deposition factors.
G 3-12 ISSUE 3 Rev3.t, ion 5 , I l l
BV-1 and 2 ODCM l FIGURE 3.0-5 gs RADIGOGICAL ENVIIONENIAL MCNIIORING PROGRAM FOCDCROP SAMPLING IOCATICNS ( .r N 's s
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i Food Samoline Locations Site # Desenption 10 SEippingport Boro . O 15 46 Georgetown Post Office hiusty, Midway Dr. ow Cbi Wv l l 3-13 ISSUE 3 Revision 5 1
BV-1 and 2 ODCM ) l FIGURE 3.0-6 RADIOIOGICAL ENVIRONMENIAL FOTI'IORHG PROGRAM n, - _ vW G Hop o
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-,Mccleary Raccoon Grange, ,Groo iookstown Grange O 181 15 3*
l [ , anicsburg r W Harshavide g l CrD o iw % :-usi \ .. Fish Sampling Locations Sector Site # Distance (miles) LDCation 13 2A 0.2 EWPS Outtall Otscharte 3 49 5.0 Upstream side of Montgomerv Dam 3-14. ISSUE 3 Revision 5
i* . BV-1 cnd 2 ODCM i 4.0- INFORMATION RELATED 'IO 40 CFR 190
) Appendbc , C CmIROL 3.11.4.1 requires that when the calculated doses
' ' associated with the effluent releases exceed twice the limits of Appendix C i 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, cr 3.11.2.3.b, calculations shall be made including direct radiatian contributions frcm the units (including outside storage tanks, etc.) to determine whether the dose or dose ccumitnent to any MEMBER OF THE PUBLIC frcm all facility releases of radioactivity and to radiatica firm uranium fuel cycle sources exceeds the limits of 5 25 mrem to the total bcdy or any organ, except the thyroid, which is limited to s 75 mrem for a m1mde year. If any of these limits are exceeded, prepare and subnit to the 4 Ctnmissicn within 30 days a Special Report puruant to Technical Specificaticn 6.9.2f. 'Ibe following shall be included in the Special Report:
- Define the corrective actico to be taken to reduce subsequent releases to prevent recurrence of exMng the limits of Appendix C CmIROL 3.11.4.1.
- Include the schedule for achieving ccnformance within the lirrits of Appendix C CmIROL 3.11.4.1.
- Include an analysis that estimates the radiatica exposure (&se) to a MEMBER OF THE PUBLIC frun uranium fuel cycle sources, including all f effluent pathways and direct radiation, for the calendar year that {
includes the release (s) covered by this report. ! gs
- Describe levels of radiaticn and ccncentrations of rad'.oactive material
' involved, and the cause of exposure levels or ccncentrations.
m./
) ?
- If the estimsted dose (s) ext.eeds the limits of Appendix C CONTROL l 3.11.4.1, and if the release conditicn resulting in violation of 40 CFR i Part 190 has not already been corrected, include a requast for a variance l in accordance with the pmvisicns of 40 CFR Part 190. Suhrittal of the j report is considered a timely request, and a variance is granted until !
staff acticn on the request is ccmplete. i v 4-1 ISSUE 3
g-BV-1 and 2 ODCM 4.1 M IDE THE SITE BOUNDARY RADIATION DOSES A separate assessment of radiation doses frcm radioactive effluents to MEMBERS OF DE PUBLIC due to their activities inside the site boundary is generally not necessary because the exposure time for individuals not occupationally associated with the plant site is minimal in ca parison to the exposure time considered for the dose calculation at or beyond the site W. For reporting purposes, separate guidance for calculating radiation doses to a MENBER OF THE PUBLIC inside the site boundary is not needed because the dose assessments for an offsite MENBER OF THE PUBLIC is also assumed to be for a MENBER OF DE PUBLIC conducting activities onsite. This is verified by showing that the ground release %/Q dispersion parameter used for dose calculation at the site boundary (0.352 miles NW) are greater than the %/Q dispersion parameter at We location where a MEMBER OF THE PUBLIC would most likely have the maximum exposure time (0-0.5 miles N and NNh') . A cmparison of these y/Q dispersion para:reters is as follows: Site Bourrhry Inside Site Boundary. Inside Site Boundarv Xl-Q XI.Q XI.Q l (0.352 miles FM) (0-0.5 miles N) (0-0.5 miles FN4) y/O References e 9.24E-5 sec/m' 2.33E-5 sec/m' 5.47E-5 sec/m' CDCM Table 2.2-4 e 1.03E-4 sec/m' 2.76E-5 sec/m' 6.01E-5 sec/m' CEO4 Table 2.2-5 e 7.35E-5 sec/m' 2.44E-5 sec/m' 5.5'E-5 sec/m' COCM Table 2.2-7 e 9.24E-5 sec/m' 2.33E-5 sec/m' 5.47E-5 sec/m' COCM Table 2.2-8 e 9.24E-5 sec/m' 2.33E-5 sec/m' 5.47E-5 sec/m' CDCN Table 2.2-9 e 7.35E-5 sec/m' 2.44E-5 sec/m' 5.57E-5 sec/m' CD04 Table 2.2-10 i l i
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G! : i 4-2 ISSUE 3 ; Revision 4
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BV-1 cud 2 ODCM f APPENDIX A l b
\d
SUMMARY
OF DISPERSION CALCULA110NAL PROCEDURrS 1 Annual average and grazing season average values of relative concentration (X/0) and deposition (D/0) were calculated for continuous and intermittent gaseous l releases of activity from the site according to the straight-lineUndecayed airflov (Gaussian) model described in NRC Regulatory Guide 1.111, Revision 1. f and undepleted sector average X/0 .and D/0 values were obtained fot each of sixteen 22.5-degree sectors at the site boundaryoccurring and maximum . individual at:a height that is j receptors. For an elevated release, defined as j twice the height or more of a nearby structure, credit var.taken for the ' effective release. height which is comprised of at thea physical release height given receptor. plus A building momentum plume' rise minus the terrain ' height. vake . correction factor was used to adjust calculations for ground-level l releases. Airflow reversals were also accounted for.by applying site-specific and elevated releases at the site terrain recirculation factors for both groundThe methodology employed in the calculati (Albersheim, 1978). release X/Q.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 BVFS-1 natural draft cooling'tover, the BVPS-2 the Containment Condensate Vents, Ventilat' ion Vents, Turbine Building Vents, Polishing Building Vent, Decontamination Building Vent, and Gareous Vaste Storage Tank Vault Vent. The intermittent releases Only the are fromvent process the was Process Vent, considered j Containment Vents, and Ventilation Vents.other release points being treated as ground
-; to be an elevated release with allA summary of the release characteristics and their loc level releases.
given in Appendix A, Table 1.1. Onsite meteorological data for the period January 1, 1976 through ) December 31, 1980 vere used as input for the annual-average calculations. The l grazing season was represented by a six-month period from May 1 through ! October ~31 for each year of the 5-year meteorological data base.The This grazing data vere l season corresponds reasonably in well with the growing season. NRC Regulatory Guide 1.23 as described in collected according to guidance The parameters used in the X/Q-D/0 calculations Section 2.3 of the BVPS-2 FSAR. as an indicator of atmospheric consist of vind speed, wind direction, and 6T stability. The lover level vinds (35 ft) which and 4T (150-35 required theft)use vere of used 500 ftfor all vinds release points except the process vent ; and oT (500-35 ft) which are representative of the release height (510 ft). i 1 ' .The annual average and grazing season X/0 and D/0 at the values site for the boundary, continuous an nearest intermittent radioactive releases verenearest milk cow, nearest milk goat, and calculated
, resident, nearest vegetable In thegarden,of case the process vent releases, several of each I nearest me.at animal. each downvind sector to determine the maximum receptor type were evaluated inThe distances of the limiting maximum individual recep X/0-D/0 values. The continuous release L the radioactive release points are given in Table 2.2-3. locations for the containment Ve annual average X/0 values at the special Building Vents, Decontamination Ventilation Vents, Process Vent, Turbine Vent, and Condensate Polishing Building Vault
~ Building. Vent, Vaste Gas Storagethrough 2.2-10 respectively. Continuous release A)
( Vent are given in Tables 2.2-4 annual average X/0's for these same release points are also given at ten ISSUE 3 A-1
r BV-1 Cnd 2 ODCM APPENDIX A r
SUMMARY
OF DISPERSION CALCULA.TIONAL PROCEDURES (continued) O incremental downvind distances. Continuous release D/0 values for these same through 2.3-27 for the incremental release points are given in Tables 2.3-21 Due to distances and in Tables 2.3-28 through 2.3-34 for the special locations. their location adjacent to the . containment building, the BVPS-2 Decontamination X/0's and D/O's are the same as Building and Gaseous Vaste Storage Tank' VaultLikewise, the Turbine Building Vent X/O's the containment vent X/0's and D/0's. and D/O's apply to the BVPS-2 Condensate Polishing Building as well due to its location' adjacent to'the Turbine Building. Table 2.3-35 through 2.3-38 contain short term X/0 values for batch releases originadng from. the Containment Vent, Ventilation Vent, and Process Vent releaset respectively. The. values in these tables are based on 32 hours per year of Containment and Ventilation Vent purges and 74 hours per year of Process iTent purges. O i Albersheim,.S. R., Development Of Terrain Adjustment Factors For Use At the Beaver Valley Power Station For the Straight-Line Atmospheric Dispersion Model, NUS-2173, NUS Corporation, June 1978 Computer Program l Sagendorf, J. F. , Goll, J. T. and Sandusky, V. F. , X00D00: 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 l l l
U:.
/4? BV-1 cnd 2 ODCH
~ APPENDIX A
,.3 TABLE A:1 K!...v)-
BV-1 AND 2 RELEASE CONDITIONS' TURBINE VENTILATION CONTAINMENT PROCESS BUILDING VENT' VENT- VENT' VENT-GROUND LEVEL- GROUND LEVEL ELEVATED GROUND LEVEL-TYPE OF RELEASE Long Term. Long Term Long Term And And- .And
.Short Term Short Term Short Term
.26 47' 155 33 Release Point Height (m)-
44 155 33 1 Adjacent Building 19 t
'deight'(m)'
Top' Center Of Atop Cooling' Turbine-Relative Loca-- 'E. Side Of 'Tover- Building tion 7o. Adjacent. Primary Auxi- Containment Structureu liary1 Bldg _ Dome'
' Exit Velocity- NA NA 9.4- NA (m/sec)
'NA. NA 0.25 NA Internal Stack
-Diameter (m) 1600 NA NA Building Cross- ,, 1600 Sectional Area-(e.')
32 74 NA Purge Frequency *-- 32 (hours / year): 8 NA NA Purge Duration 8
,-(hrs / release) m
\
p Od
- Applied to'Short Term' calculations only
)
A-3 ISSUE 3 Revision 1 . 1
,1
E) ,
.o j
;BV-1 dnd 2LODCM K 1
' APPENDIX B-
$ k ' l L/~'k '
. INPUTS;TO COMPUTER CODES FOR GENERATION OF' SOURCE TERMS LQ ,
LThis App'e'ndix contains:thel input: . parameters;,to:the variousicomputar' codes used-
, by Duquesne Light Company'and. Its subcontractors 1fo.r ' determination of qthe Liquid.
~
i
~
Land'. Gaseous, source. term mixes. .Tne inputs are contained in'the following. Tables 1 of:this' Appendix.; ' V "
--Inputs To Gale Code' ForJ. Generation. Of . BV-l 'Li'q'uld: Source Term
~
.TableLBalai ~
' Mixes-n 1 Table B:1bl > Inputs T6.SVEC LIQ 1BB. Code- Fort: Generation Of,BV-2 Liquid Source '
--Term Mixes Table'B:2a1 LInputs To.SWECTGAS1BB Code For Generation.0f:BV-1 Gaseous Source Term Mixes.
Table:B:2b Inputs To SVEC GAS 1BB Code, For ' ' Generation Of BV-2 Gaseous Source Term Mixes
-y
;Gi A
i s
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r B-1: ISSUE 3 Revision 1
( l BV-1 end 2 ODCM
' APPENDIX B TABLE B:la INPUTS TO GALE CODE FOR GENERATION OF BV-1 LIQUID SOURCE TERM MIXES VALUE !
BV-1 PVR INPUTS
-Thermal Power Level (megavatts) 2766.000
.800 Plant Capacity Factor Hass Of Primary Coolant (thousand Ibs)- 345.000 Percent Fuel Vith Cladding Defects .120 Primary System Letdown Rate (gpm) 60.000 6.000 Letdown Cation Demineralizer Flov 3.000 Number Gf Steam Generators 11.620 Total Steam Flov (million lbs/hr) 6.772 Mass Of Steam In Each Steam Generator (thousand lbs) 97.000 Hass Of Liquid In Each Steam Generator (thousand Ibs)
Total Mass Of Secondary Coolant (thousand lbs) 1296.000 291.000 Hass Of Vater In Steam Generator (thousand lbs) 33.900 Blovdown Re?.e (thousand Ibs/hr) 100.000 Primary To Secondary Leak Rate (1bs/ day) Fission Product Carry-Over Fraction .001
.010 Halogen Carry-Over Fraction 0.000 Condensate Demineralizer Flov Fraction 22.500 Radvaste Dilution Flov (thousand gpm)
BV-1 LIQUID VASTE INPUTS ' COLLECTION DELAY DECONTAMINATION FLOV RATE FRACTION FRACTION TIME TIME FACTORS (gal /dayJ __OF PCA DISCHARGE (days) (days) I Cs OTHERS _ STREAM i 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 1E7 } Drains 0.648 1E5 2E4 1E5 Clean Vaste 7.50E1 1.000 1.000 0.071 Input Dirty.Vaste 1.35E3 0.035 1.000 0.071 0.648 1E5 2E4 1E5 Input Blovdown 9.75E4 -- 1.000 0.071 0 648 1E5 2E4 1E5 Untreated 0.0 -- -- -- Blovdown ! I B-2 ISSUE 3 l Revision 1
r-BV-1 cnd 2 ODCN APPENDIX B TABLE B:1b $#r f ('-, y i INPUTS TO SVEC LIQ 1BB CODE FOR GENERATION OF BV-2 LIQUID SCURCE TERM MIXES BV-2 PVR INPUTS VALUE I Thermal,Pover Level (megawatts) 2766.000 Flasi. Capacity Factor .800 Mass 0f Pribary Coolant (thousand lbs) 385.000 1
-Percent Fuel Vith Cladding Defects .120 Primary System Letdown Rate (gpm) 57.000 5.700 Letdown Cation Demineralizer Flov 3.000 )
Number Of Steam Generators 11.600 } Total Steam Flov (million lbs/hr) 8.700 j Mass Of Steam In Each Steam Generator (thousand lbs) 100.000 j Mass Of Liquid In Each Steam Generator (thousand Ibs) Total Mass Of Secondary Coolant (thousand lbs) 2000.000 l 295.000 ) Mass Of Water In Steam Generator (thousand Ibs) ' 22.300 l Blovdown Rate (thousand Ibs/hr) 100.000 Primary To Secondary Leak Rate (1bs/ day) Fission Product Carry-Over Fraction .001
.010
)
Halogen Carry-Over Fraction .700
/ Condensate Demineralizer Flow Fraction 7.800 l Radvaste Dilution Flov (thousand gpm)
BV-2 LIQUID VASTE INPUTS COLLECTION DELAY DECONTAMINATION TIME- TIME FACTORS FLOV RATE FRACTION FRACTION (hrs) (hrs) I CsRb OTHERS STREAM (gal / day) 0F PCA DISCHARGE 40 1.000 1.0 35.5 6.2 1E3 1E4 1E4 Containment Sump 200 0.100 1.0 35.5 6.2 1E3 1E4 1E4 Auxiliary Building Sump 700 0.010 1.0 35.5 6.2 1E3 1E4 1E4 Miscellaneous Sources 35 1.000 1.0 35.5 6.2 1E3 1E4 1E4 Rx Plant Samples 400 0.002 1.0 35.5 6.2 1E3 1E4 1E4 Lab Drains 2685 1.1E-4 1.0 35.5 6.2 1E3 1E4 1E4 Cond. Demin. Rinse Water 60 1.0 1300 173 1E4 4E3 1E5 I I CVCS a -- Turbine Bldg. 7200 -- 1.0 -- -- -- -- Drains B-3 ISSUE 3 Revision 1
P BV-1 tnd 2 ODCM APPENDIX B TABLE B:2a INPUTS TO SVEC GAS 1BB CODE'FOR GENERATION OF BV-1 GASE0US SOURCE TERM MIXES BV-1 PWR INPUTS VALUE Thermal Power Level (megavatts) 276'6.000 Plant Capacity Factor .800 385.000 Mass Of Primary Coolant (thousand Ibs) Percent Fuel Vith Cladding Defects .120 Primary System Letdown Rate (gpm) 57.000 5.700 Letdown. Cation Demineralizer Flov 3.000 Number'0f Steam Generators 11.600 Total Steam Flov (million lbs/hr) 8.700 Mass Of team In Each Steam Generator (thousand Ibs)
' quid In Each Steam Generator (thousand Ibs) 100.000-Mass Of 2000.000 Total Ha of Secondary Coolant (thousand lbs)
Mass Of L In Steam Generator (thousand Ibs) 298.000 52.000 Blowdown Rate (thousand lbs/hr) Primary To Secondary Leak Rate (lbs/ day) 100.000 Fission Product Carry-Over Fraction .001 Halogen Carry-Over Fraction .010 Condensate Demineralizer Flow Fraction 0.000 Radvaste Dilution Flov (thousand gpm) 15.003 BV-1 GASE0US VASTE INPUTS VALUE 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 (lb/ 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 j Particulate Release Fraction 1.000 Containment Volume (million cu-ft) 1.800 Frequency Of Primary Coolant Degassing (times /yr) 2.000 i 100.000 ) Primary To Secondary Leak Rate (lb/ day) There Is A Kidney Filter containment Atmosphere Cleanup Rate (thousand cfm) 2.000 Purge Time Of Containment (hours) 0.000 There Is Not A Condensate Demineralizer Iodine Partition Factor (gas /lig) In Steam Generator 0.010 ! Frequency Of Containment Building High Vol Purge (times /yr)* 4.000 l Containment Volume Purge Iodine Release Fraction 1.000 l Particulate Release Fraction 1.000
' Steam Leak To Turbine Building (1bs/hr) 1700.000 Fraction Iodine Released From Blovdown Tank Vent 0.000 Fraction Iodine Released From Main Condensate Air Ejector 0.440 There Is Not A Cryogenic Off Gas System
*2 cold and 2 hot purges O
B-4 ISSUE 3 , Revision 1 !
7 , ' ngy _ .- , 7
, j' < ;y , ;c 1' , _
i s JBV i1Eand 2 0DCM1 s qg , 4 "t
~ APPENDIX B:
L'. .:
' to iTABLE B:2b yv;sh+
7, .
=
JINPUTS'TO SVEC GAS 1BB CODELFOR GENERATION OFlBV-2-GASE005 SOURCE TERM MIXES , 4 4 4
,s i , . ,
m ,
- BV-2/PVR-INPUTS -VALUE' L ,
- Thirmal-PowerLevelj(megawatts)- : 2766.000' .
LPlant;Capaci_y; t Factor.('...,. .. -._.<. _ _.. 800 a385.000' _ ~ g *Msss OfcPrimary; Coolant:(thousand:lbs).
..120 JPercent Fuel With;CladdingEDefects .
i Primary;(System Letdown Rate'(gpm)E 57.000: 5.700 y' JLetdown! Cation'Demineralizer Flow? 3.000 .' LNumberl0f1 Steam Generators- ' '; 4 :11.600:
- Total' Steam Flov-(million lbs/hr) E8.700L .j e Massi0f . Steam <In Each Steam Generator:(thousand.:1bs)
~
'100.000
; Mass 0fJLiquid.:In"Each Steam Generator:(thousand'lbs).
- TotalLHass;Of< Secondary Coolant-s(thousand lbs)1 2000.000 298.000 1 1 Hass: 0f .. Vater Ini Steam Generator .(thousand ' lbs)
'22.300-
~
,BlowdownLRate-(thousand?1bs/hr)
'100.000-Primary.To Secondary; Leak Rate (lbs/ day)
- Fission Product Carry-Over Fraction .001
- Halogen Carry-Over Fraction. .010 w .
.700' (Condensate Demineralizer Flow Fraction 7.800 Radvaste Dilution Flov_(thousand~gpm); >
g:
-BV42' GASEOUS VASTE INPUTS VALUE Gy 4 JThereLIs Not; Continuous. Stripping Of. Full Letdown Flov' Hold Up Time For Xenon-(days)- 45.800 :
l EheldLUp' Time _For Krypton-(days)1 . 2.570' Prin.a/ Coolant Leak To Auxiliary Building (Ib/ day)- '160.000
- Auxiliary Building Leak Iodine Partition Factor. 7.5E Gas Waste System Particulate Release Fraction 0.000 ,
) Auxiliary' Building Charcolodine Release; Fraction 0.100 l
-Particulate Release Fraction 0.010 1 I
; Containment Volume (million_cu-ft)._
~
1.800 2.000
~
TFrequency Of Primary Coolant Degassing (times /yr)
. Primary;To: Secondary. Leak Rate.(lb/ day) 100.000 The're Is A~ Kidney Filter Containment Atmosphere Cleanup Rate (thousand~cfm) 20.000 p~ 8.000
-_ Purge _ Time.0f Containment (hours)l There Is Not'A Condensate Demineralizer ,
Iodine Partition Factor (gas / liq) In Steam Generator 0.010 4.000 g Frequency;;0f Containment Building High Vol= Purge (times /yr)*
. Containment Volume Purge Iodine Release Fraction 1.000 Particulate Release Fraction 1.000 Steam Leak To Turbine.BuildingT(lbs/hr) 1700.000 0.000 Fraction: Iodine-Released From Blowdown Tank Vent 0.270 FractionLIodine Released From Main Condensate Air Ejector '
There Is Not A Cryogenic Off Gas System y7 p - 1 ; ,
'*2Lcold'and 2 hot purges B-5 ISSUE 3 v ,
Revision 1
; 1
P, y BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS f's . .
'7s,j . This appendix contains procedural details for the Radiological Effluent Technical
- Specification (RETS) . that were . transferred fran the Technical Specifications . per Unit 1/2 ~ Amendnents- 188/70, and ~in accordance with Generic Letter 89-01. and Generic Ietter 89-01, Supplement No.1 (NUREG 1301) .
This appendix also includes ' selected Definitions and Tables ' as delineated in Section :1 of the Technical Specifications and selected applicability and surveillance requirement. statements as delineated in Section 3/40 of the Technical Specifications. These were added to Appendix C for reference purposes, even though they are currently described in the Technical Specification. The ntrnbering 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 fran 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. V / O ' C-1 ISSUE 3 Revision 1
F . BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS COtEROLS: DEFINITIONS The defined terms of this section appear in capitalized type and are applicable throughout these COtEROLS. 1.5 ACTION shall be those additional requirements specified as corollary statements to each principal CONTROL and shall be part of the CONTROLS. 1.9 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBPATION shall enccxupass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The ~ CHANNEL CALIBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel' is calibrated. 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 frcxn independent instrument channels measuring the same parameter. 1.11 A CHANNEL EUNCTIONAL TEST shall be the injection of a sit.n ated signal into the channel as close to the primary sensor as practi:able to verify . OPERABILITY including alarm and/or trip functions. l l 1.19 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (uci/ gram) which j alone would produce the same thyroid dose as the quantity and isotopic j mixture of I-131, I-132, I-133, I-134, and I-135 actually presenti. The j thyroid dose conversion factors used for this calculation shall be those j listed in Table E-7 of Regulatory Guide 1.109, Revision 1, 1977 or Table l III of TID 14844. ' It[fg 1.21 The FREQUENCY NOTATION specified for the performance of Surveillance Requirenents shall correspond to the intervals defined in Table 1.2. 1 1.31 A GASEOUS RAIMASTE TREATMENT SYSTEM is any system designed and installed to l reduce radioactive gaseous effluents by collecting primary coolant system l offgases frcm the primary system and providing for delay or holdup for the ! purpose of reducing the total radioactivity prior to release to the environment. 1.36 MEMBER (S) OF THE PUBLIC means any individual except when that individual is receiving an occupational dose. This definition is used to show ~ = 14=nce to an CDCM Appendix C CCNrBOL that is tased on 10 CER Part 20. O C-2 ISSUE 3 Revision 5
1 4 i BV-1 and 2 ODCM 1 l l APPENDIX C ) ! ODCM CONTROLS l l[( x! CONTROLS: DEFINITIONS (continued) i 1.36 MEMBER (S) OF THE PUBLIC means any individual that can receive a radiation dose in the general environment, whether he my or my not also be exposed to radiation in an occupation associated with a nuclear fuel cycle. j However, an individual is not considered a MEMBER OF THE PUBLIC during any ) period in which he 'is engaged in carrying out any operation which is part of the nuclear fuel cycle. This definition is used to show c->%ce to ar. CDCM Appenduc C ONIROL that is based en 40 CER Part 190. l 1.30 The OFFSITE DOSE CALCULATION MANUAL (OD04) shall contain the methodology l and paramters used in the calculation of offsite doses resulting frcm j radioactive gaseous and liquid effluents, in the calculation of gaseous and l liquid effluent monitoring Alarm / Trip setpoints, and in the conduct of the 1 Environmental Radiological Monitoring Program. The ODCM shall also contain l (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.6 and (2) descriptions of' the ) infor m tion that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by TS 6.9.1.10 and 6.9.1.11. l 1.6 A system, subsystem, train, cmponent, or d.vice shall be OPEPABLE or have OPERABILITY when it is capable of performing its specified function (s) . Implicit in this definition shall be the assumption that all necessary r~'N attendant instrumentation, controls, normal and emergency electric power (') sources, cooling or seal water, lubrication or other auxiliary equignent that are required for the system, subsystem, train, cmponent, or device to perform its function (s) are also capable of performing their related safety function (s) . 1.4 An OPERATIONAL FDDE shall correspond to any one inclusive cmbination of core reactivity condition, power level, and average reactor ' coolant temperature specified in Table 1.1. 1.33 PURGE or PURGING is the controlled process of discharging air or gas frcm a confinement to mintain temperature, pressure, humidity, concentration, or other operating conditions, in such a manner that replacement air or gas is required to purify the confinement. 1.3 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2652 NWt. 1.7 A REPORTABLE EVENT shall be any of those conditions specified in Section fff93 50.73 to 10 CFR Part 50. l 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) 1.27 A SOURCE CHECK shall be the qualitative assessment of channel response when
,, the channel sensor is exposed to a radioactive source.
)
h ,- -[U 1.2 THERMAL POWER shall be the total reactor core heat transfer rate to the L reactor coolant. C-3 ISSUE 3 Revision 5
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS CONTROLS:~ DEFINITIONS (cot.cinued) 1.39 An UNRESTRICfED AREA means any area access to which is neither limited nor controlled by the licensee. l.32 VENTIIATION EXHAUST TREAIMENT 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 renoving iodines or particulates frm the gaseous exhaust ctream 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 VENTIIATION EXHAUST TREAD ETf SYSTFtd rigg cmponents. 1.34 VENTING is the controlled process of discharging air or gas frm 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 proo2ss. O l C-4 ISSUE 3 Revision 5
g- _BV-1:and 2 ODCH APPENDIX C ODCH CONTROLS 1,q i TABLE -1.1 ' /\._f , , OPERATIONAL MODSS
% RATED . AVERAGE COOLANT REACTIVITY:
-TEMPERATURE MODE. ~ CONDITION, K,gf . THERMAL POWER *
>0.99 ' >5% > 350'F ..
. li : Power. Operation.
>350'F,
. 2 .' Startup .>0.99- f5%
<0.99 0 >350'F f 3. - Hot Standby.
350*F >T 8vg f
<0.99 0 4.. ' Hot . Shutd'ovn - >200'F
<0. 9 9 '. 0 $200'F
- 5. Cold Shutdown.
0 3140'F
,6. Refueling ** 30.95-
)
0: l i
)
I l l
. /% . .
.* Excluding decay. heat..
'( ) .
'- ** Reactor' vessel head unbolted or removed and fuel in the vessel.
C-5 ISSUE 3
'l..
.BV-1 cod 2 ODCM APPENDIX C ODCM CONTROLS TABLE 1.2 FREQUENCY NOTATION.
l l j NOTATION FREQUENCY i S
.At least once per 12 hours D At least once per 24 hours V At least once per 7 days t
1 H At least once per 31 days O At least once per 92 days SA At least once per 184 days R At least once per 18 months S/U Prior to each reactor startup P Completed prior to each release N.A. Not applicable e i l ) 1
]
i e C-6 ISSifF 9 4 I i 1
r w l -BV-1 cnd 2 ODCM j APPENDIX C ._ ODCH CONTROLS a
' CONTROLS: APPLICABILITY 3.0.1;. Compliance ~vith' the CONTROLS. In the succeeding. CONTROLS is' required.
during the OPERATIONAL -HODES or. other conditions specified therein;. except1that 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 expirr. tion of the specified. Ltime intervals, completion of.the ACTION requirements is not required.. 3.0.3, When a CONTROL is not met except 'as provided in the associated ACTION requirements, within one hour action shall be initiated to place the unit in a MODE in which~ the CONTROL does not apply by. placing it, as applicable, ins
- 1. At least HOT STANDBY vithin the next 6 hours,
- 2. At least HOT SHUTDOWN within the following 6 hours, and
- 3. At least COLD SHUTD0VN vithin the subsequent 24 hours.
Where corrective measures are completed. that permit operation under the ACTION requirements,'the ACTION may be taken in accordance with'the C specified time limits as measured from the time of failure to meet the CONTROL. Exceptions to these ' requirements are stated in'the individual CONTROLS. i 3.0.4 Entry into an' OPERATIONAL MODE or other specified condition shall not be 1 made when the conditions for the CONTROL are not not met within met andtime a specified the associate
-l ACTION requires a shutdown if they are !
interval. Entry into an OPERATIONAL MODE or specified condition may be i 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 l MODES as required to coiply with ACTION requirements. Exceptions to l these requirements are stated in the individual CONTROLS. l z). C-7 ISSUE 3
aj; ' iBV-1iend'2 ODCM>
' APPENDIX Cr ODCM CONTROLS.
i
. CONTROLS:n SURVEILLANCE REQUIREMENTS-
* '4.0.1LSurveillan>:e,Reqbirementsshall'be:' mets during : 'the' OPERATIONAL MODES or i other D conditions l 'specified.. for:: individualL: CONTROLS .unless otherwise stated in an individual-Surveillance Requirement.
L Each'Surveillence'. Requirement- 'shall 'be performed:: within! the specified
'4.0.2
' time interval withea maximum allowable extension not to exceed 25%'of the surveillance interval.
4.0.3' Failure .-to ' perform 'a',fSurveillance . Requirement within the allowed
- surveillanceLinterval,! defined by' CONTROL 4.0.2, shall constitute r.an-
.Tha' time compliance with:the OPERABILITY . requirements .for limits'ofitheWACTION requirements:.are applicable a. CONTROL.:atL the . tim identified that a Surveillance'RequirementJ has: not been performed.'. Tae
- ACTION requirements may bel delayed for . up to :- 24 hours .toL permit l the
' completion'of'the' surveillance when- the allovable outage time limits of' Surveillance the~ ACTION. requirements are less 'than 24' hours.- ~
Requirements do not have to'.be performed on inoperable equipment. 4.0.4 Entry into.an OPERATIONAL MODE'or;-:other spec ified condition shall not be made unless.:the Surveillance-' Requirement (s) . associated with'the CONTROL interval or as has .been performed- within fthe -stated < surveillance otherwise specified.;:This provision'shall not prevent passage through or - to OPERATIONAL MODES'as required to comply-vith ACTION requirements. O C-8 ISSUE 3
p 3 BV-1 and 2 ODCH' APPENDIX C'
- i. .
'ODCH CONTROLS CONTROLS: RADICACTIVE LIQUID EFFLUENT MONITORING' INSTRUMENTATION 3.3.3.9- IIn accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Item 1.. .the radioactive liquid effluent monitoring instrumentation channels shown in Appendix. C, ' Table .3.3-12 shall be OPERABLE with
.their alarm / trip setpoints set to ensure that the limits of Appendix C CONTROL 3.11.1.1'.are not: exceeded. The alarm / trip setpoints of the radiation _ monitoring chtnnels shall: be ' determined-in accordance with Section-1.1.1 and 1.1.2.of this manual.
l
- Applicability:
. During releases through the flow path.
Act?,ons - a.. With a. radioactive ' liquid . effluent monitoring instrumentation 'ch:nnel alarm / trip setpoint less- conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored' by .the affected channel or correct the alarm / trip setpoint.
- b. With one .or more. radioactive liquid effluent monitoring instrumentation
/7 . channels inoperable, take the ACTION shown in . Appendix C, Table 3.3-12 or -Q conservatively reduce the alarm setpoint. Exert a best effort to return the N channel to operable status within 30 days,'and if unsuccessful, explain in the next Annual Radioactive' Effluent Release Report why the inoperability a was not corrected in a timely manner. /
The provisions of Appendix C CONTROL 3.0.3 are not applicable. N c. SURVEILLANCE REQUIREMENTS
'4.3.3.9 Each radioactive liquid . effluent monitoring instrumentation channel shall be denonstrated 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.
M.
- Id C-9 ISSUE 3 M
gn -
~BV-1 and 2 ODCH APPENDIX C ODCM CONTROLS TABLE 3.3-12 BV-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS OPERABLE ACTION INSTRUMENT
- 1. Gross Activity Monitors Providing Automatic Termination Of Release (1) 23
- a. Liquid Vaste Effluents Monitor (RM-LV-104)
- b. Liquid Vaste Contaminated Drain Monitor (RM-LV-116) (1) 23 (1) 24
- c. Auxiliary Feed Pump Bay Drain Monitor (RM-DA-100)
Gross Activity Monitors Not Providing Termination Of 1 2. Release -
- a. Component Cooling-Recirculation Spray Heat (1) 24 Exchangers River Vater Monitor (RM-RV-100) 3 Flow Rate Measurement Devices (1) 25
- a. Liquid Radvaste Effluent Line (1) FR-LV-103 for RM-LV-116 (2) FR-LV-104 for RM-LV-104 (1) 25
- b. Cooling Tower Blowdown Line (1) FT-CV-101 (2) FT-CV-101-1
- 4. Tank Level Indicating Devices (for tanks outside plant building)
- a. Primary Vater Storage Trnk (1) 26 ;
(LI-PG-115A for BR-TK-6A) (1) 26
- b. Primary Water Storage Tank (LI-PG-115B for BR-TK-6B)
(1) 26
- c. Steam Generator Drain Tank (LI-LV-110 for LV-TK-7A)
(1) 26
- d. . Steam Generator Drain Tank (LI-LV-111 for LV-TK-7B)
O.1 C-10 ISSUE 3 Revision 2
r* 1 . BV-1 cnd 2 ODCM APPENDIX C ODCM CONTROLS I
.V' TABLE 3.3-12 . (continued)
BV-2 PADIQACTIVE LIQUID EFFLUENT MONI'IORING INSTRUMENTATION MINIMUM CHANNELS INSTRC1 6 r OPEPABLE ACTION
- 1. Gross Radioactivity Monitor Providing Alarm And Automatic Termination Of Release
- a. Liquid Waste Process Effluent Monitor (2SGC-RQ100) (1) 23
- 2. Gross Radioactivity Ibnitors Providing Alarm But Not Providing Termination Of Release None
- 3. Flow Rate Measurement Devices .
a, ' Liquid Radwaste Effluent (2SGC-FS100) (1) 25 Cooling Tchr Blowdown Line (2CWS-ET101) (1) 25 b. I
~3 4. Tank level Indicating Devices (for tanks outside
( ) plant buildings) , None 1 t l I <
% _.] ~
C-11 ISSUE 3
t_ V . BV-1 cnd.2 ODCM l APPENDIX C ODCM CONTROLS TABLE 3.3-12'(continued) ACTION STATEMENIS' Action 23L With the number of channels OPEPABLE less than required by the Minimum Channels OPEPABLE requirement, effluent releases may be initiated or resumed provided that prior to release, the following two conditions are met:
- 1. At least two independent samples are analyzed in accordance with Appendix C SURVEILIANCE REQUIREMENT 4.11.1.1.1, and 3/93
- 2. At least two ; technically' qualified members of the Facility Staff independently verify the ' release rate calculations and discharge valving.
Note: Since the computer 'sofcware used for discharge permit generation autcxratically performs the release rate calculations, then the independent signatures on the discharge permit
" for preparer and reviewer satisfy the requhement for
...two technically qualified members of the Facility Staff independently verify the release rate calculations..."
Otherwise, su. spend release of radioactive effluents via this pathway. Action 24 With the number of channels OPEPABLE less than required by the Minimum Channels OPERABLE requirecent, effluent releases via this pathway may continue provided that at least once per 8 hours grab samples are ' analyzed for gross radioactivity (beta or gamra) at a Lower Limit of Detection (LLD) of at least lE-7 uCi/ml. Action 25 With the number of channels OPEPABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours during actual releases, b mp carves may be used to estimate flow. Action 26 With the number of channels OPEPABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continue provided the tank lic;uid level is estimated during all liquid additions to the tank. C-12 ISSUE 3 Revision 4
p
]
nm BV-12cnd 2.0DCM
- s ,
. APPENDIX C; .,
4
, 1 LODCM CONTROLS-
' ' ~i
, [. }' 7. l Q? 1 TABLE 4.3 -: e . , q
+ 7BV- RADIOACTIVE LIQUID EFFLUENT MONITORING ^ ;
LINSTRUMENTATION SURVEILLANCE REQUIREMENTS;
r
, d 4
,~
CHANNEL
- INSTRUMENTS '
, iCHANNEL SOURCE- . CHANNEL CHECK- CHECK 1 CALIBRATION-FUNCTIONAL:
TEST
- 1.^i Gross Beta.Or Gamma'RadioactivityJ
-Monitors'Providing Alarm ~And : ,
- j 1
!AutomaticiTermination Of Release d q.
P(5)- -R(3).
' a.; :' Liquid: Radvaste"r.f fluent Line . { D _Q(1)' '
(RM-LV-104) r b.<. LLigtiid Vas'te Contamin'ated .D .P(5)
~
R(3) 0(1) q. 7
,' : Drain Line (RM-LV-116)" .. .
.r ,
- c. 1 Auxiliary Feed Pump Bay' . .D -D R(3) Q(6)-'
d Drain Monitor (RM-DA-100) 2., Gross Beta Or Gamma: Radioactivity W; 4 Monitors"Providing Alarm But Not:. !
-Providing Automatic Termination' G' - Of Release;
- a. Compon'ent Cooling . D 'M(5) R(3) Q(2)-
. Recirculation Spray Heat.
- Exchangers-River Vater
. Monitor.L(RM-RV-100)
- 3. Flow Rate: Monitors
'a.- Liquid'Radvaste Effluent Lines D(4) NA 'R 0
.-:(1). FR-LV-!.03 ' for. RM-LV-116
.(2).FR-LV-104 ior RM-LV-104 D(4) .NA R 0 i
~b.;-Cooling Tower Blowdown '
Line.
' i-(1) . FT-CV-101~
_.(2) FT-CV-101-1 y
-i - .
a I
'l;
, i G , e u
)
C-13 ISSUE 3 l 1 , >
' Revision 2
.l
7.- BV-l'and 2 ODCM
-l APPENDIX C ODCM CONTROLS TABLE 4.3-12 (continued)
BV-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING l INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL-CHANNEL SOURCE CHANNEL FUNCTIONAL CHECK CHECK CALIBRATION TEST INSTRUMENT
- 4. Tank Level Indicating Devices (for tanks outside plant buildings)
D* NA R 0 I a. Primary Water Storage Tank (LI-PG-115A for BR-TK-6A) D* .NA R 0
- b. Primary Water Storage Tank-(LI-PG-115B for BR-TK-6B)
D* NA R 0
- c. Steam Generator Drain rank (LI-LV-110 for LV-TK-7A)
D* NA R Q
- d. Steam Generator Drain Tank (LI-LV-111 for LV-TK-7B)
*During liquid additions _to the tank.
Oi j l C-14 ISSUE 3 Revision 2
h BV-1 and-2 DDCM V:, ;;,:
' APPENDIX C;
" ODCM CONTROLS <
l(N . TABLE 4.3-12L(continued).
-%)(
t
~
BV-2 RADI0 ACTIVE LIQUID EFFLUENT MONITORING-
' INSTRUMENTATION SURVEILLANCE REQUIREMENTS y..
CHANNEL CHANNEL SOURCE . CHANNEL-. .. FUNCTIONAL CHECK' CHECK CALIBRATION : TEST
- INSTRUMENT
- 1. . Gross. Radioactivity Monitor Providing Alarm And Automatic '
Termination Of Release Liquid Vaste. Precess Effluent- D P(5)' R(8)(3) 0(7). a. (2SGC-R0100) 2 .- Flow Rate' Measurement Devices D(4) R O'
- a. Liquid Radvaste Effluent. .NA.
(2SGC-FS100)
.D(4) NA R. 'O
- b. . Cooling Tower Blowdown Line.
(2CVS-FT101). l I 3., Tan'/ Level l Indicating' Devices 1 (for~ tanks outside plant buildings) l
-None.
l1 I I t 1 i 4 l l l e
'O C ISSUE 3 i
N l l BV-1 cnd 2 ODCH APPENDIX C' ODCH CONTROLS TABLE 4.3 12 (continued) TABLE NOTATION
.(1) The.of thisCHANNEL pathway and FUNCTIONAL Control Room' AlarmTEST shall also Annunciation demonstrate occurs if any of the that auto
'tollowing conditions ~ exist:
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Sovnscale failure.
- 3. Instrument controls not set in operate mode.
also demonstrate that Control Room Alarm (2) .The CHANNEL FUNCTIONAL TEST shall
' Annunciatir.n 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.
for radioactivity measurement CHANNEL CALIBRATION
'(3) The initial 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 These standards should permit calibrating assurance activities with NBS.
the system over its intended range of energy and rate capabilities. For subsequent CHANNEL CAL 7BRATION, sources that at intervals of have beenonce at least related perto18 the initial calibration should be used, months. This can normally be accomplished during refueling outages. previously established calibration (Existing plants may substitute procedures for this requirement). (4) C$ANNEL CHECK shall consist of verifying indication of flow during period" of release. CHANNEL CHECK shall be made at least once daily on any day on which continuous, periodic, or batch releases are made. (5) A SOURCE CHECK may be performed utilizing obtainthe aninstalled means orinflashing upscale increase the the detector with a portable source to existing count rate to verify channel response. O C-16 ISSUE 3
1 BV-1-cnd.2LODCMp
' APPENDIX-C' ODCM CONTROLS TABLE 4.3-12.(continued)
SM TABLE NOTATION-L
'(6)N The' CHANNEL FUNCTIONAL TEST shall also ' demonstrate tha't au pathway 'and Control Roomi Alarm Annunciation ' occurs when the
-of;this
-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:
cl. Downscale failure.'.
- 2. ' Instrument controls are not' set'in operate mode.
(7) The '-1 of thisCHANNEL FUNCTIONAL pathway'.and~LControl LRoomTEST Alarm 'shall'also demonstrate.that Annunciation occurs if. the auto L . Instrument: indicates-measured levels above the. alarm / trip setpoint. that- Control Room. Alarm _(8) The CHANNEL' CALIBRATION' shall also' demonstrate Annunciation occurs:if either 'of the lfollowing conditions exist
- 1. Downscale failure.
-2. Instrument controls are not set in operate mode.
i i A 1 i i i l 1 l ISSUB 3 C-17
f! u ;_ BV-1 dnd 2 ODCM APPENDIX C
.ODCM CONTROLS CONTROLS: RADIOACTIVE GASEOUS EFFLUENT HONITORING INSTRUMENTATION 1
3.3.3.10' In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, 1 Item:1, the radioactive gaseous effluent monitoring instrumentation channels,shown in Appendix C, Table 3.3-13 shall be operable with
!their; alarm / trip setpoints set to ensure that the limits of Appendix C CONTROL 3.11.2.1 are not exceeded. The alarm / trip setpoints of the radiation monitoring channels shall be determined in accordance with Section 2.1 of this manual.
Applicability: During releases thr ugh the flow path. Actions
- a. With a radioactive gsseous process or effluent monitoring instrumentation channel alarm / trip setpoint less ceaservative than a value vnich 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. Vish one or more radioactive gaseous effluent monitoring instrumentation channels inopera ble, take the ACTION shown in Appendix C, Table 3.3-13 or conservatively reduce the alarm setpoint. Exert a best effort to return the Iddi channel to operable status within 30 days, and if unsuccessful, explain in l the next Annual Radioactive Effluent Release Report why the inoperability ,,
was not corrected in a timely manner.
- c. The provisions oE Appendix C CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREllENTS , I 4.3.3.10 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated operable by performance of the CHANNEL CHECK 3 SOURCE CHBCK, CHANNEL CALIBRATION, and CHAWEL FUNCTIONAL TEST operations at the frequencies shown in Appendix C, Table 4.3-13. s l l I i O C-18 ISSUE 3
m Q - P(.- o BV-1'and.2 ODCM
. APPENDIX-C i;:. ~~ODCM= CONTROLS jf}
bM '
, , TABLE 3.3-13. .
BV-l' PADIOT4TIVE GASEDUS' EFFLUENT MONI'IORING INSTRLEENTATION . P = Primary Instruments,. (A'= Alternate Instruments MINIMUM
< INSTRENENT OPEPABLE APPLICABILITY ACTION 4 1
.1. Gaseous Waste / Process Vent System. )
i
- a. Noble Gas ActiUity Monitor (1)' -* ' 27,29,30***
P: : (BM-GW-1088)-
; Particulate Activity Monitor
'b. .
(1)- 32 ' P: . (%GW-108A) or A: ( % GW-109 Ch 1); c... System Effluent Flow Bate -(1)' '*- 28 Measuring Device P: (FR-GW-108) or-A: '(%GW-109 Ch .10) f]- d. Sampler Flow Bate Measuring (1) -
- 28 Q Device
. P: . (Rotcmeter).
<2. Auxiliary Building Ventilation System a '. Noble Gas Activity Monitor (1) 29,30***
P: (BM-VS-101B) 'or
. A: . (%VS-109 Ch 5)
- b. Particulate Activity Monitor (1)
- 32 P: (BM-VS-101A)- or tijg
- A: ( % VS-109 Ch 1)
- c. System Effluent Flow Rate (1) 2'8 Measuring Device P: (ER-VS-101) or.
' A: ( % VS-109 Ch 10)
Ld. Sampler' Flow Rate Measuring '(1)-
- 28
-Device- :
P: (Rotmeter) -
- During Releans via this pathway.
***During purging of Reactor Containment via this pathway. !
i u - 1
. C-19 ISSUE 3 Revision 5 g
i ..
e . s BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 3.3-13 (continued)
- BV-1 PADICACTIVE GASEOUS EFFLUEta FONITORItG INSTRUMEtHATION P = Primary Instruments, A = Alternate Instruments MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACf10N
- 3. Reactor Building / Supplementary Leak Collection And Release System
- a. Noble Gas Activity Monitor (1)
- 29,30***
P: (RM-VS-107B) or A: (RM-VS-110 Ch 5)
- b. Particulate Activity Monitor (1)
- 32 P: (RM-VS-107A).
A: (RM-VS-110 Ch 1)
#d8 c. -System Effluent Flow Rate (1)
- 28 Measuring Device P: (FR-VS-112) or A: (RM-VS-110 Ch 10)
- d. Sampler Flow Rate Measuring (1) 28 >
Device P: (Rotometer) l l
)
i I I 1
*During Releases via this pathway.
***During purging of Reactor Containment via this pathway.
C-20 ISSUE 3 Revision 4
% q g- o r , BV -1 'and 2 i ODCM
- j. ,
APPENDIX C
-x .
ODCM' CONTROLS-
> l...l ): .
/-- 4 TABLE 3.3-13, (continued)
- BV-2 PADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRIMNTATION J:
-,= P = Primary Instrumentsi ~A~= Alternate Instruments MINIMUM-CHANNELS Y INSTRWENT . OPERABLE APPLICABILITY ACTION
'1. SICRS Unfiltered Pathway a.- Noble Gas Activity Monitor.- 1 29,30***-
'P: (2HVS-RQ101B) -
~
- b. Particulate Activity Monitor l 32 P: ' (2HVS-RQ101A)
*~ 28
- c. ' Process Flow Rate Monitor 1 P: (Monitor Item 29):
- 28
- d. Sampler Flow Rate Monitor 1 P: - (Monitor . Item 28)
W -2. : SICRS Filtered Pathway Y* )~ a. Noble Gas Activity tenitor "1
- 29,30***
P: . (2HVS-RQ109B)
,b. ' Particulate Activity tenitor - .1
- 32 P: (2HYS-RQ109A)
- c. Process Flow Rate Monitor- 1~
- 28 P: ' (!bnitor Item 29)
- d. Sampler Flow Rate Monitor 1
- 28 P: (Monitor Items 28 and 72)
-3. Decontaminacion Building Vent f
- a. ' Noble Gas Activity Monitor 1
- 29 P: (2RMQ-RQ301B)
- b. Particulate Activity Monitor i.
- 32 i 1
E: (2RE}-RQ301A)'
- c. Process Flcw Rate tenitor- None. None None
' P: None Required'
- 28 i d. Sampler Flow Rate tenitor 1 P: (lenitor Item 28) l
'f] 7
.M ~*During Releases via.this pathway. ]
l
-- ***During purging of Peactor' Containment via this pathway.
C-21 ISSUE 3 Revision 4 k,
V BV-1 and 2 ODCM APPENDIX C e ODCM CONTROLS TABLE 3.3-13 (continued) BV-2 PADICACTIVE GASEOUS EFFLUF1Tf MONITORING INSTRUMEtTfATION
; ~P = Primary Instruments, A = Alternate Instruments MINIMUM CHANIELS INSTRUME2Tf OPEPABLE APPLICABILITY ACTION
- 4. Condensate Polishing Lullding Vent
- a. Noble Gas Activity Monitor 1
- 29 P: (2HVL-RQ112B)
- b. Particulate Activity Monitor 1 * ,2 P: (2HVL '0112A)
- c. Process Flow Rate Monitor None None None P: None Required
- d. Sanpler Flow Rate Monitor 1
- 28 P: (Monitor Item 28)
- 5. Waste Gas Storage Vault
- a. Noble Gas Activity Monitor 1
- 29 P: (2FMQ-RQ303B)
- b. Particulate Activity Monitor 1
- 32 P: (2RMQ-RQ303A)
- c. Process Flow Rate Monitor None None None P: None Required
- d. Sanpler Flow Rate Monitor 1
- 28 P: (Monitor Item 28) e C-22 ISSUE 3 Revision 4
x h
~!
BV-1-and 2 ODCM'
-APPENDIE C ODCM CONTROLS ,4
(~N 4 A.] , . . TABLE 3.3-13 ' (continued) ACTION STATDiENTS Action-27 ' APPLICABLE FOR RELEASES OF THE BV-1 OR BV-2 GAS WASTE TANKS With; the number ' of channels OPERABLE ' less- than. required by the - s Wnbrn Channels OPERABLE requirement, the contenta of the Unit 1 Gaseous Waste Decay Tanks or the Unit 2 Gsseous Waste Storage Tanks may.be released to the environment provided that prior to initiating. the release:
-- 1. At ; least two L independent samples ~of the tank's ' content "are --
analyzed and at least two technically qualified trembers of the Facility Staff. independently. verify the release- rate calculations and discharge valve lineup, or
- 2. . Initiate continuous monitoring L with the camparable 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 f7 pathway. { 1 t i v
. Action'28 With the number of channels . OPERABLE less than. required by the f Minimum Channels OPEPABLE regttirement, effluent releases via' this 'i pathway; may continue provided. the flow rate' is estimated at. least
~
)
once per'4 hours. 4 With the number. of channels OPERABLE less than required by the
~
Action 29' i' Minimum . Channels OPERABLE requirement, effluent releases via this pathway may continue provided:
- 1. Grab samples are taken at 'least once- per 8 hours and these samples are analyzed for gross activity within 24 hours, or
- 2. Initiate continuous monitoring with the ccuparable alternate monitoring channel. Surveillance requirements applicable to the' inoperable channel shall apply to the ccuparable alternate monitoring channel - when used to satisfy this ODCM CONTROL requirement.
Action 30- - APPLICABLE mR PUfGES OF THE BV-1 REACTOR CONTAINMENT With the number 'of channels OPFSABLE less than required by minimum Channels OPERABLE requirement, imediately 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. } j~g [ t J- ;
%J i
C-23 ISSUE 3 Revision 4
~
BV-l cnd 2:ODCM APPENDIX C
,ODCM CONTROLS TABLE 3.3-13 (continued)
S ACTION STATD E ES Action 30- APPLICABLE EDR PURGES OF THE BV-2 REACHOR CONTAItNEtEL
- With the number of channels OPERABLE' less than required by Minimum Channels OPERABLE requirenent, imnediately . suspend purging of Reactor Contaircrent via this pathway.
Action 32 With the number of channels OPERABLE less than required by the Minimum Channels OPEPABLE requirement, (,ffluent releases via this pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Appendix C, Table 4.11-2 or sampled and analyzed once every 8 hours. O 9 C-24 ISSUE 3 i [
~
g-: , BV-1.and 2 ODCM- [. , . APPENDIX:C' C y-k,. 4 -ODCM CONTROLS hkM I TABLE 4.3 . . . BV-1 PADICACTIVE GASEOUS EFFLUENT IONITORING i:.
'INSTRCNENIATION SURVEILII41CE REQUIREMENTS
~
L' , P = Primary Instruments,: A = Alternate Instruments CHANNEL CHANNEL' SOURCE CHANNEL FUNCTIONALc l 4 INSTRUMENT CIECK CHECK CALIBRATION TEST L l -1. ' Gaseous Waste / Process Vent System
- a. : Noble Gas Activity Monitor P- " P(4) R(3) . Q(1)
P: (RM-G4-108B) Particulate' Activity Monitor
- b. W NA' NA NA-P: (BM-GW-108A)or
- A: (BM-GW-109 Ch 1)~
'R 'O 4
- c. System Effluent Flow Rate- P' NA Measuring Device 3 P: . (FR-GW-108) or A: (RM-GW-109 Ch 10)
- d. Sampler Flow Rate Measuring D* NA. R .Q.
Device P: (Rotcneter)
;2. ~ Auxiliary Building Ventilation System 3[f6 1tb a. Noble Gas Activity Monitor D M(4), R(3). Q (2) -- 4 A.f- -P: (RM-VS-101B) or P(4)*** l
- A: '(RM-VS-109 Ch 5) 4
. b. . Particulate Activity Monitor W NA NA- NA P: - (BM-VS-101A) or A: (PM-VS-109 Ch 1).
- c. System Effluent Flow Rate D 1R R- Q Measurement Device P: (FR-VS-101) or i A: (RM-VS-109 Ch 10) . .
R' Q j
- d. Sampler Flow Rate Measuring D NA i
Device P: 1 (Rotcraeter)
- 3. ' Reactor Building / Supplementary Leak Collection AM Release System
.a. Noble Gas Activity Monitor D M(4) , R(3) O(2)
. P: (RM-VS-1078)or - P(4) ***
. A: ' (RM-VS-110 Ch 5)
> b. ' Particulate Activity Monitor W NA NA la g j
' P: - (BM-VS-107A) or A: -(BM-VS-110 Ch 1) l'
- c. System Effluent Flow Rate- D NA R Q Measuring Device
' P: ' (FR-VS-112) or A: (PM-VS-110 Ch IO)
- d. Sampler Flow Rate Measuring D NA R O i 77 -Device
'.V P: (Rotometer)
'*During releases via this pathw.j.
***During purging of Reactor Cont hnent via this pathway.
C-25 ISSUE 3 Revision 4 j r
Si" . H,, t, , y - 4
+.
~
,< J ? BV--l' and 2: ODCM :
.L
]M ,
' APPENDIX'C'
,y 'ODCM CONTROLS O ' '
iTABLE 4.3-13L(continued) s -
/BV-2 RADIOACTIVE GASEOUS EFFLUENT 10NITORING .
INSTRUMENTATION SURVEILLANCE REQUIRDENTS , , , s . P = Prinury' Instruments,' :A = Alternate Instruments OL - CHANNEL CHANNEL' SOURCE CHANNE' FUNCTIONAL EINSTRUMENT- CHECK CHECK CALIBRA" TEST-1 '. - SICRSLUn' filtered P$thwaya
- a. . : Noble Gas' Activity Monitor. D' M(4), R(3) (6) Q(5) -
' 'P: . (2HVS-RQ101B)- .
P(4)***..
- b. -Particulate Activity Monitor' W- NA' NA IM '
~ P: (2HVS-RQ101A) . . . .
- c. : Process Flow Rate Monitor D. . NAL R Q
'P:- (Monitor Item 29)'
- d. Sampler Flow Rate Monitor D 'NA R Q
, : P: (tenitor' Item 28).
-: 2. SLCRS Filtered Pathway
. a. 1 Noble Gas Activity Monitor' D' M(4), R(3) (6) Q(5)
P: - (2HVS-RQ109B) . P(4) **
- Lb. ' Particulate Activity Monitor -W la !& NA P: (2HVS-RQ109A)' .
i c. Process Flow Rate Monitor - -D .NA R O :! P: (Monitor Item'29)?
' d.
Sampler Flow Rate Monitor' D NA' R Q P: ~ (Monitor Items 28 and 72)
- 3. Decontbamination Building Vent
- a. Noble Gas Activity Monitor D M(4) R(3) (6) Q(5)
P: (2RMQ-RQ3018)
- b. Particulate Activity Monitor W NA NA NA P: (2RMO-RQ301A) c., Process Flow Rate Monitor la NA NA la P: None Required
- d. Sampler Flow Rate Monitor D la R Q P: (Monitor Item 28)
- 4. Condensate Polishing Building Vent
- a. , Noble Gas Activity Monitor l D M(4) R(3) (6) Q(5)
P: (2HVL-RQll2B)
- b. _ Particulate Activity Monitor W }& NA NA P: (2HVL-RQll2A)
- c. Process Flow Bate Monitor NA NA NA NA
'P: None Required
. d. Sampler Flow Rate Monitor D NA R Q P: (Monitor. Item 28)
O C-26 ISSUE 3 Revision 4
%pr , c ' yS -
' y,
.ff W
- a
., y a ; ,
ik[n i
, e E .
' s
.BV-1and'2SODCMJ l:t . *t . . .i : .
, ' N i; 1 - .
s APPENDIX-' C --
- p .r^a:
. -LODCM ' CONTROLS '-
l-
/j >
LTABLE .'4.3'-13 ) (continued)':
,BV-2 BADIOACTIVE GASEOUS EFFLUENT MONITORIl#:
~
, .LINSTRtDENTATION SURVEILLANCE REQUIRDENIS!
. P = Primary Instruments,: 'A = Alternate Instruments- .l
?
.j
- r. ; CHANNEL CHANNEL SOURCE CHANNEL EUNCTIONAL-
, INSTRINENT CHECK CHECK CALIBRATIONJ ' TEST-
- \
rgy f :- f5. M Waste Gas. Storage Vault? q"
. D '. ' . M(4) ' . R(3) (6) - LQ(5)
M (a! .> Noble Gas Activity Monitor:
.P: , (2Ete-BQ303B)' . .
- 5- : b . .- Particulate' Activity Monitor .WL NA NA" NA.
/P: (2Bte-BQ303A) ~ ' .. .
- c. Process Flow Bate Monitor- ?NA! NA- NA. NA
.P: None Required:
~
.r Ed. Sanpler Flow Bate'Monitora. ?D 1NA :R' Q'
. P: T(Monitor Item 28); .
.g U! 3 i- .;
4 a l i-l 1
.c j 1
1 l l 1 , O
' (
r i < C-27 ISSUE 3 1 Revision 4 1
- c. ; ,
}. s
-l
m - BV-1 rnd 2 ODCM APPENDIX C ODCM CONTROLS TABLE 4.3-13 '(continued) Oi 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 neasured levels above the alarm / trip setpoint.
- b. Downscale failure,
- c. Instrument controls not set in operate node.
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Roan klarm ; Annunciation occurs if any of the following conditions exist: '
- a. Instrument indicates neasured levels above the alarm / trip setpoint.
- b. Downscale failure.
- c. . Instrument controls not set in operate node.
(3) The initial CHANNEL CALIBRATION for radioactivity measurement j instrumentation shall be perforned using one or more of the reference i standards certified be National Bureau of Standards or using standards that i have been obtained frcan suppliers that participate in measurement assurence i 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 accceplished 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 Roan 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 L
r, e b, , -- BV-11and 2' ODCM APPENDIX-C b , ODCM CONTROLS [p VW L 3 CONTROLS: ' LIQUID EFFLUENT CONCENTRATION 3211.1.1; '.In accordance 'vith BV-l' and BV-2 Technical Specification 6.8.6a, t.. Items 2'and 3,sthe. concentration; of radioactive material released at any' time from the site (see Figure '5-1) shall be limited to 10 times
?the EC's:specified in '10. CFR' Part 20,' Appendix'Bl(20.1001-20.2401),
l-
' Table?2, Column 2 fort radionuclides other than dissolved or entrained L . noble gases. 1This is referred _-to'as.the'ODCM Effluent Concentration LLimit.'(0EC). . ~For- dissolved 'or- entrained 1 noble gases, the l;
K Lconcentration'shall be limited.to'2E-4uCi/ml" total, activity. Applicability - ,
-At all? times.
Action:. a'..- With.the-concentration'of. radioactive material released. from the site to unrestricted areas exceeding the: above limits; .immediately restore'the concentration'vithin the above limits,:and-
- b. ' Submit a Special: Report to the Commission within 30 days in accordance~vith Technical Specification 6.9.2f.
~' - c. The provisions 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),
4 samples.of the Turbine Building Sump shall-be obtained every 8 hours
'to. ensure that the- Turbine Building.. Sump concentration does not exceed 1 OEC.. Once it is determined that an OEC is reached, th Turbine Building Sump shall be routed to'the Chemical Waste Sump.
l p A f. [ C-29 ISSUE 3 Revision 1
I] l
)
BV-1 end 2 0DCM APPENDIX C ODCH CONTROLS SURVEILLANCE REQUIREMENTS-(continued) 4.11.1.1.4 When'BV-2 primary to secondary leakage exceeds 0.1 gpm (142 gpd), , j samples of the Turbine Building Sump shall be obtained every 8 hours to ensure that' the Turbine Building Sump concentration does not l
' fif exceed 1 OEC. .Once~ it. 'is . determined - that an OEC is reached, the j Turbine Building Sump shall be routed to Steam Generator blevdown .,
j hold tank (2SGC-TK21A or 2SGC-TK21B). i 4.11.1.1.5 Prior to the BV-2 Recirculation Drain Pump (s) (2DAS-P215A/B) 1
- discharging to catch basin 16, a grap sample vill be taken. The samples will be analyzed for gross activity at a sensitivity of at least IE-7 uCi/ml. Vater volume discharged shall be estimated from i' the number of pump operations unless alternate flow or volume instrumentation is provided.
O
- Radioactive liquid discharges are normally via batch modes. BV-1 and BV-2 Turbine Building Drains shall be monitored as specified in Appendix C SURVEILLANCE REQUIREMENT 4.11.1.1.3 and 4.11.1.1.4. The BV-2 Recirculation drain pump discharge shall be monitored as specified in Appendix C SURVEILLANCE REQUIREMENT 4.11.1.1.5 respectively.
O C-30 ISSUE 3 Revision 1 l-
p4 , ..4 :P. ] P,* ;BV-11snd'2_ODCH
, x
? '
APPENDIX C-i6 .- 1-ODCM CONTROLS' ..A.. We
- c. , ..
jAf ' TABLE'4.11-1 E . , 'L .'RADI0 ACTIVE LIQUID VASTE' SAMPLING-AND ANALYSIS PROGRAM / MINIMUM >
. LIQUID: RELEASE: -SAMPLING : ANALYSIS TYPE OF ACTIVITY LOVER LIMIT l :' TYPE' -FREQUENCY. = FREQUENCY ANALYSIS OF DETECTION (LLD)
-(uci/ml)"
A. Batch Vaste d P' ~ h P-
.h PrincipaljGamma-SE-7.'
Release ~ Tanks Each Batch ~ Each' Batch .' Emitters I-131- 1E-6.
~
1P , .M Dissolved And 1E 1 h One Batch /M. Entrained Gases (Gamma Emitters) H-3 .1E-5 P' N' b ; h Each Batch composit'e 'l Gross Alpha 3 1E-7 :- b- 'P b :. 0- . Sr-89, Sr-90' SE-8 1
- l. Ed Each' Batch ' Composite Fe-55 11E -
g .~g. B.Continuogs Grab Sample Ptincipal Gamma' "5E-7 c f
. Releases E Composite Emitters l I-131 1E-6 g
Grab Sample M Dissolved And 1E-5 Entrained Gases: (Gamma Emitters) g ' Grab Sample M H-3 1E-5 c Composite Gross Alpha 1E-7 i: Grab Sampl'es 'O Sr-89, Sr-90 SE-8 c l, Composite !- i < Fe-55 1E-6 L. L l: Q 4 C-31 ISSUE 3 Revision 1
I 1% 1 cnd 2 ODCH APPENDIX C ODCH CONTROLS TABLE'4.ll-1 (continued) l TABLE NOTATION
- a. The LLD is the smallest concentration of radioactive material in a sampla that vill be detected with 95% probability with 5% probability of falsely ccncluding that a blank observation repre.sents a "real" signal.
For a- particular measurement system (which may include radiochemical separation): LLD - 4.66 S D (E)(V)(2.22)(D exp(- A6T) wheret LLD is the lover limit of detection as dafined 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 transforration); 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 de' cay constant for the particular radionuclide; oT is the elapsed time between sample collection (or end of the sample collection period) and time of counting (for environmental samples, not plant effluent samples). The value of gs used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background 8f counting rate or of the counting rate of the b'.ank samples (as appropriate) 'rather than on an unverified theoretically predicted variance. Typical values of E, V, Y and oT should be used in the calculations. The LLD is defined as an a priori (bet 0re the fact) limit representing the capability of a measurement sys t::m and not as a posteriori (after the fact) limit for a particular me wurement. l 9 i I C-32 ISSUE 3 ! i
w
, :BV-1 End 2 ODCH APPENDIX C L- .~ :ODCM' CONTROLS
.yS. t i < U , , TABLE.'4.ll-1 (continued) TABLE NOTATION d b.: ' A composite sample is - one in whichL the quanticy of. liquid sampled is proportionalfto the: quantity.,of ;1iquid vaste l discharged and in which the j method:ofJsampling employed results in a specimen whleh is representative of j
~the liquids released. '
q i c. ' To N representative of -the quantities- and-concentrations of radioactive ma'erials t in liquid. effluents, samples 'shall be collected continuously in proportion to the rate of flov -of the' effluent stream. Prior.to' analyses,- all samplesftaken for.the composite shall be thoroughly mixed in order'for the.. composite sample to be representative of the effluent release.
- d. 'A batch release exists when" the discharge of liquid vastes .is from a discrete volume. P -ior to sampling for analyses, each batch onall be isolated, and then thoroughly mixed to assure representative sampling, a
'e. lA' continuous release exists when the discharga of liquid 5 stes is from a !
non-discrete volume; e.g., from a volume of a. system having an input flow
~
~
during the continuous' release.
~
Releases from the Turbine Building drains
.and the'AFV Pump Bay Drain System and chemical vaste sump are considered 7 continuous when the nrimary to secondary leak rate exceeds 0.1 gpm (142 4
gpd). %g
- f. The principal gamma emitters for u m h the LLD specification vi]i 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/ hese t nuclides are to be detected and reported. Other peaks which Jare measurable and identifiable, logother with the above nuclides,.shall also be. identified-and reported. Nuclides which are below the LLD for the analyses'shouldLbe reported as."less than" the nuclide's LLD, and should not bel 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. og
- g. When radioactivity is identified in the secondary system, a RWDA-L should be i prepared on a. monthly basis to account for the radioactivity that vil {
eventually be discharged to the Ohio River. Y j
- h. Vhenever'the BV-2 Recirculation Drain Pump (s) are discharging to catch basin 16, sampling vill be performed by means of a grab sample taken every 4 hours during pump operation. j 1
l C-33 ISSUE 3 m in Revision 1 Y m,_ _ . .,
7 BV-1 end 2 ODCM APPENDIX C ODCM CONTROLS O CONTROLS: LIQUID EFFLUENT DOSE 3.11.1.2 In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Items 1 and 5, the dose or dose commitment to HEMBER(S) 0F THE PUBLIC from radioactive materials in liquid effluents released from the reactor unit (see Figurc 5-1) shall be limited:
- a. During any calendar quarter to less than or equal to 1.5 mren to the total body and to less than or equal to 5 mrem to any organ, and
- b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
Applicability: At all times. Action:
- a. With the calculated dose from the release of radicactive 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 'che subsequent releaces vill be within the above limits. (This Special Report shall also include (1) the results of radiological analyses of the drinking water source and (2) the radiological impar.t on finished drinking vater supplies with regard to the requirements of 40 CFR 141, Safe Drinking Vater Act).*
- b. The provisions of Appendix C CONTROL 3.0.3 are not applicable.
SURVEILLD CE REQUIREMENTS 4.11.1.2.1 Dose Calculations. Cumulative dose contributions from liquid effluents shall be determined in accordance tith Section 1.3 oL 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
W . -n s y
)::, ,
t U i;'4 J EV-l and'2'ODCM L sAPPENDIX C h'. ..
.ODCM CONTROLS-j l ;Q}
l, CONTROLS:' LIQUID RADVASTE TREATMENT' SYSTEM l-. r, I
'j I
3.11.1.3~'In accordanceivith'BV-1 an'd BV-2 Technical Specification-6.8.6a,: Item-6~, the Liquid'Radvaste Treatment ~ System shall be'.used.to reduc'e { the radioactive materials iin each liquid: vaste' batch prior to 1ts
~~
z 1
- l. jdischarge when the projected':dosesL due to liquid'. effluent releases :1
/ '
ifrom the'r'eactor-unit '(see Figure. 5-1) [vhen averaged over 31 days R vould'. exceed'0.06 mrem to.the: total body or 0.2 mrem to:any. organ. Applihaullity:. t eAtallhtimes.- iAction: L a.- Vith liquid vaste .being ' discharged vithout treatment and exceeding'the 'l limits specified, prepare and submit 'to 1 the' Commission vithin 30 days
},ursuant: to. Technical. Specification 6.9.2f a Special Report which includes the following information: j i
'1. Identification of the. inoperable equipment.:or subsystems and the reason
-for inoperability.;
2; Action (s) tak n toc-restore. the Linoperable. equipment to operational
~
- status, and-3... ' Summary description oflacticn(s) taken to prevent a recurrence.
- b. TheLprovisions~of Appendix C CONTROL 3.0.3 are not applicable.
\
. SURVEILLANCE REQUIREMENTS 4.11.1'3.1! Doses.due to liquid. releases'shall'be projected at.least once per 31
)
days; in accordance with.Section 1.3 of this manual. ! 3
.n
- m. .
C-35 ISSUE 3 Revision 1
r
-BV-1 and 2 ODCH APPENDIX C ODCM CONTROLS CONTROLS: GASE0US EFFLUENT DOS! RATE 3.11.2.1 In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, l Items 3 and 7,.the. dose rate in the unrestricted areas (see Figure 5-
- 1) due to radioactive materials released in gaseous effluents from the site shall be limited ~to the following values:
- a. The dose rate limit for noble gases shall be f 500 mrem /yr to the
. total body and f 3000 mrem /yr to the skin *, and b .- The dose rate limit, inhalation pathway only, for I-131, tritium <
and all radionuclides in particulate form (excluding C-14) with half-lives greater than eight days shall be f_1500 mrem /yr to any organ. Applicability: At all times. Action:
- 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 lommission within 30 days pursuant to Technical Specification 6.9.2f.
- c. The provisions of Appendix C CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREME"TS 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 gascous effluents, shall be determined to be within the above limits in accordance with the methods and procedures of the' ODCH by obtaining representative samples and performing analyre:, in accordance with the sampling and analysis program specified in Appendix C Table 4.11-2.
*During containment purge the dose rate may be averaged over 960 minutes.
C-36 ISSUE 3 Revision 1 j
Y-U l BV-1 and 2 ODCM-l! i L' : APPENDIX C
- j. ,
ODCM CONTRCLS. '-t 1p. 4
- . \ j. TABLE 4.11-2 RADICACIIVE GASECUS WASTE SAMPLIN3 AND ANALYSIS PROGRAM MINIMUM I4WER LIMIT OF l SAMPLING ANALYSIS TYPE OF DEIECI' ION (LLD) >
GASECUS RELEASE 'lYPE FREQUENCY tm:v>r.NCY ACI'IVITY ANALYSIS (uCi/ml)* 1 A. Waste Gas 'P P Principal Ganma 1E-4' l Storage Tank Each Tank Each Tank Bnitters' l Grab Sanple d Each Tank
- Each Tank
- H-3* 1E-6 g Grah Sanple B. Oxitainment ~ P P Principal Ganna 1E-4 Nrge Each Purge
- Each Purge" Bnitters' ,
G d Sanple H-3 1L-6 -
- i C. Ventilaticn d'"
# Principal Ganna 1E-4 i Systetd Grab Sanple Bnitters' ]
1.'Ubit 1 Ventila- H-3 1.E-6 tien Vee i
- 2. Unit 1 0.ntain- i ment /SLCRS Vent
- 3. Unit J./2 Process !
(~~\ . Vent
!Q 4. Unit 2 Ventila-tion Vent
- 5. Unit 2 N ain-
. ment /SIERS Vent I
- 6. Unit 2 Decon. 1 Bldg. " ant 7.'Ubit 2 daste Gas *
. Storage Vault
. Vent-I
- 8. Unit 2 M nr. ate Polishing Bldg.
. Vent i
* 'Ihe H-3 concentraticn shall be estimated prior to release and followed up ggg with an H-3 grab sanple from the Ventilation System during zelease.
L l -: [r 1 !. L/ C-37 ISSUE 3 Revision 5
4 BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 4.11-2 (continued) PADIQACTIVE GASEOUS WASTE SAMPLING AND NRLYSIS PROGRAM MINIMLN IDER LIMIT OF SAMPLING ANALYSIS TYPE OF DETECTION (LLD) GASEOUS REI1ASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS (uCi/ml)* D. All Systems Continuous' # I-131 1E-12 Listed Above Charcosl Which Produce Sample I-133 1E-10 l Continuous Release Continuous' # Principal Gama 1E-11 Particulate Emitters' Sanple (I-131, Others) Continuous' M Gross Alpha 1E-11 Cctuposite Particulate Sample Continuous' Q Sr-89, Sr-90 1E-11 Ccrrposite Particulate Sample Continuous' Noble Gas Noble Gases 1E-6 Monitor Gross Beta And Gamma l l O, C-38 ISSUE 3 j Revision 1 ! I
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 4.11-2 (continued) TABLE NOTATION
- The Lower Lilnit of Detection (LLD) is defined in Table Notation (a) of l 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 PATED THERMAL PCWER within a ) 1 hour period. This requirement does not apply if (1) analysis shows that j 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 l effluent activity has not increased more than a factor of 3. j
- Tritium grab samples shall be taken et least once per 24 hours (from the 4 appropriate ventilation release path) when the refueling canal is flooded, d
Sartples shall be changed at least once per 7 days and analyses shall .be l mgleted within 48 hours after changing, or after removal frcm sampler. ' Sampling shall also be performed at least once per 24 hours for at least 7 days following each shutdown, startup, or THERMAL POWER change exceeding 15% of RATED THEBMAL POWER within a 1 hour period and analyses shall be ccnpleted within 48 hours of changing. When samples collected for 24 hours are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if: (1) analysis shows that the DOSE
, EQUIVALENT I-131 concentration in the reactor coolant has not increased more j than a factor of 3; and (2) the noble gas monitor shows that effluent o/ activity has not increased more than a factor of 3.
- Tritium grab samples shall be taken at least once per 7 days 'frcm the appropriate ventilation release path of the spent fuel pool area) whenever lihb spent fuel is in the spent fuel pool. <
f The average ratio of the sanple flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate l' calculation made in accordance with Appendix C CONTROLS 3.11.2.1, 3.11.2.2, $ and 3.11.2.3.
' The principal gamma emitters for which the LLD specification will 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, Ma-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.
' w _l C-39 ISSUE 3 Revision 5
(. - BV-1 and- 2 ODCM
. . APPENDIX.C g ODCM CONTROLS. ,
CONTROLSi DOSE-NOBLE' GASES I3.11'2.2
. . In accordance'with BV-land BV-2 Technical Specification 6.8.6a, Iterns 5 and 8, the:.an" dose- frcm the reactor unit in unrestricted'
~
areas 1(see : Figure-.5-1) due tof noble gases released - in gaseous-
. effluents shall be limited to the following:
.a. During any calendrr q:arter, to s 'S mrad for _gantaa ? radiation-
.and s 10 mrad for beta radiation.
- b. ' During any calendar year,' to s 10 mrad for gamma radiation and -
s 20 mrad for beta radiation. Applicability: At all times.
' Action:
'a. With the' calculated air dose frcm radioactive noble gases in gaseous
- effluents exceeding any of the above limits, prepare and submit to the :
Conmission with .in 30 days, ' pursuant to Techical Specification 6.9.2f, a Special Report which identifies the cause(s) for exceeding the limit (s) :and definos the corrective actions taken to reduce the releases and the proposed corrective actions to be. taken to assure the subsequent releases will be
<ith n the above limits. .
- b. 'The provisions of Appendix C CONTROL 3.0.3 are not applicable.
I TSURVEILIANC3 REQUIRDENTS ; q
)
4.11.2.2.1- Dose Calculations. Cumulative dose contributions shall be tietermined in accordance with Section 2.3 'of this manual at least ot.ce every 31 days. 1 l O C-40 ISSUE 3 Revision 1 t,_
7 BV-1 &nd 2 ODCM APPENDIX C ODCM CONTROLS n
)
< _,/
CONTROLS: DOSE-RADI0 IODINES, RADI0 ACTIVE MATERIAL IN PARTICULATE FORM, AND RADIONUCLIDES OTHER THAN N0BLE GASE5 3.11.2.3 In accordance with BV-1 and BV-2 Technical Specification.6.8.6a, Items 5 and 9, the dose to HEMBER(S) 0F THE PUBLIC from radioiodines and radioactive materials in 'particular form (excluding C-14), and radionuclides (other than noble gases) with half-lives greater than eight days in gaseous effluents releases from the reactor unit (see Figure 5-1) shall be limited to the following: a.- During any calendar quarter to $ 7.5 mrem to any organ, and
- b. During any calendar year to f 15 mrem to any organ.
Applicability:, At all times. Actior3:
- a. Vith the calculated dose from the release of radiciodines, radioactive materials in particulate form, (excluding C-14), and radionuclides (other 7-~s than noble gases) with half-lives greater than eight days, in gaseous
( ) effluents exceeding any of the above limits, . prepare and submit to the k' Commission within 30 days, pursuant to Technical Specification 6.9.2f, a l Special Report, which identifies the cause(s) for exceeding the limit and l defines the corrective actions taken to reduce the releases and t' roposed I corrective actions to be taken to assure the subsequent releas.. vill be l vithin the above limits.
- b. The provisions of Appendix C CONTROL 3.0.3 are not applicable.
SURVEILLANCF REQUIREMENTS 4.11.2.3.1 Dose Calculations.. Cumulative dose contributions shall be determined in accordance with Section 2.3 of this manual at least once every 31 days. I (- t V) ! C-41 ISSUE 3 Revision 1 [
BV-1 and 2 ODCM I APPENDIX C ODCM CONTROLS O1 I , CONTROLS: GASEOUS RADVASTE TREATMENT SYSTEM i 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 due to gaseous effluent releases from the reactor unit (see Figura 5-1) when averaged over 31 days vould exceed 0.3 mrem to any organ. Applicabilitv: , 3 At all times. Actions
- 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. are not applicable.
SURVEILLANCE REQUIREMENTS y l 4.11.2.4.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with Section 2.3 of this manual. O C-42 ISSUE 3 Revision 1
}
p ) i BV-1 cnd 2 ODCM APPENDIX C ODCM CONTROLS na CONTROLS: TOTAL DOSE
~3.11.4.1 Ir. accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Itnm 10, the annual (calendar year) dose or dose commitment to any -l ME)3ER OF THE PUBLIC due to releases of radioactivity and to radiation 4 j
from uranium fuel cycle sources shall be limited to < 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to ;
< 75 mrems. 1 Applicability:-
-At all times. i Action:
- a. Vith the calculated doses from the release of radioactive materials in !
liquid or gaseous effluents exceediag twice the limits of Appendix C CONTROL 3.11.1.2a, 3.11.1.2b, 3.11.2.2a, 3.11.2.2b, 3.11.2.3a, or 3.11.2.3b, ! calculations shall be made including direct radiation contributions from the units (including outside storage tanks, etc.) to determine whether the above limits of Appendix C CONTROL 3.11.4.; have been exceeded'. If such is the-case, prepare and submit to the Commission within 30 days, pursuant to l
,% Technical Specification 6.9.2f, a Special Report that defines the corrective l action to be taken to reduce subsequent releases to prevent recurrence of i
(' d) exceeding the above limits and inclndes the schedule for achieving l conformance with the above limits. This Special Report, as defined in l 10 CFR 20.405(c), shall include an analysis that estimates the radiation ; exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, { including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated ! dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected,~ the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
- b. The provisions of Appendix C CONTROL 3.0.3 are not applicable.
i y C-43 ISSUE 3 Revi.sion 1
BV-1 and 2 ODCM APPENDIX C
, ODCH CONTROLS SURVEILLANCE REQUIREMENTS (continued) 4.11.4.1.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Appendix C SURVEILLANCE ,./'I7 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 reauirement is applicable only under conditions set forth in Action a. of Appendix C CONTROL 3.11.4.1. O 1 9 C-44 ISSUE 3 Re"ision 2
BV-1 cnd 2 ODCM APPENDIX C ODCM CONTROLS q i t LJ 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 1 conducted as specified in Appendix C, Table 3.12-1.
Applicability: _
- At all times. ,
(
~Actiont' la. 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 l of the reasons for not conducting the. program as required and the plans for i preventing a recurrence. Deviations are permitted from the required j i
sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, or to malfunction of automatic sampling equipment. l
- Ii tte latter, every effort shall be made to complete corrective action prior to the end of the next sampling period. ,
,o 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
- d-i
' 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 vhich includes an evaluation of any release conditions, environmental factors or other aspects which caused the limits of Appendix C, Table 3.12-2
-to be exceeded. This report is not required if the measured level of radioactive was not the result- of plant effluents; however, in such an event, .the condition shall be reported and described in the Annual-Radiological Environmental Report.
When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if: Concentration (1) Concentration (2) Limit Level (1) + Limit Level (2) + . . . > 1.0
- c. With milk or fresh leafy. vegetable samples unavailable from the required number of locations selected in accordance with Appendix C CONTROL 3.12.2 and listed in the ODCM, obtain replacement samples. The locations from
-vhich samples vere unavailable may .then be deleted from those required by Appendix C, Table 3.12-1 and the ODCM provided the locations from which the replacement samples were obtained are added to the environmental monitoring program as replacement locations, if available.
The provisions of Appendix C CONTROL 3.0.3 are not applicable. Q d. V C-45 ISSUE 3 Revision 1
g-,- Bt'-1 and 2 ODCM . APPENDIX C ODCM CONTROLS O
. SURVEILLANCE REQUIREMENTS (continued) 4.12.1.1 The radiological environmental monitoring samples ~shall be collected pursuant to Appendix C, Table 3.12--I from ti,e locations given in the a ODCM and shall be analyzad pursuant to be requirements of Appendix C, Tables 3.12-1 and 4.12-1.
O
?
O C-46 ISSUE 3 Revision 1
f*
- l- BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS p
"' TABLE 3.12-1 .
PADIOLOGICAL ENVIROtNEtEAL MONITORING PROGRAM SAMPLING AND EXPOSURE PATHWAY I NUMBER OF SAMPLES COLLECTION- TYPE AND FREQUENCY '3 AND/OR SAMPLE AND II) CATIONS ** FREQUEbK'Y OF ANALYSIS
- 1. AIRBORNE ,
- a. Badioiodine 5 locations. Continuous opera- Each radiolodine j
'And tion of sanpler canister. 1 Particulates 1. One sanple frm with sanple col-a control loca- 1ection at least Analyze for I-131; tion 10-20 weekly.
miles distant Particulate sanpler, a;.d in the Analyze for gross least prevalent beta weekly (b3 h wind direction. Perfonn ganina isoto-2,. One sanple frcxn pic analysis on vicinity of canposite (by loca-community tion) sanple at having the least quarterly. 7 highest calcu-- lated annual
,(_/t average ground level D/Q.
- 2. DIRECT 4 locatior.s. Continuous Gantaa dose, RADIATICt1 measurement with quarterly.
2 2 TLDs or a pres- collection at II/16 surized ion least quarterly. . chamber at each location.
'*3 Analysis frequency same as sanpling frequency unless otherwise specified.
(*' Particulate samples are not counted for 2 24 hours after filter changt. Perform gamma isotopic analysis on each sanple when gross beta is >10 times the yearly mean of control sanples.
.** Sample locations are given on figures and tables in Section 3 of this $anual.
r
- .v C-47 ISSUE 3 Revision 5
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 3.12-1 (continued) PADIOIOGICAL ENVIRONMENTAL MONITORING PROGRAM 1 i SAMPLING AND EXPOSURE PATIMAY NUMBER OF SAMPLES COLLECTION TYPE AND FREQUENCY (*) i AND/OR SAMPLE AND IOCATIONS** FREQUENCY OF ANALYSIS l
)
- 3. WATERBORNE )
- a. Surface 2 locations. Composite
- sample Gama isotopic analy- l collected over a sis of cmposite )
- 1. One sattple period not to sample (by location) ]
upstream, exceed 1 month. monthly; l
.i
- 2. Oce sample Tritium analysis of downstream, cmposite sample at l least quarterly.
l t
- b. Drinking 2 locations. Cmposite* sample I-131 analysis of l collected over a each composite !
period not to sample; { exceed 2 wecks. Gama isotopic analy-sis of cmposite sample (by location) mnthly; Tritium analysis of cmposite sample quarterly. 9
- c. Groundwater N/A - No wells in lower elevations between plant and river.
- d. Sediment Frca 1 location. Semi-annually. Gama isotopic analy-Shoreline sis semi-annually.
G(hs (*3 Analysis frequency same as sampling frequency unless otherwise specified. 1
*Cm posite samples shall be collected by collecting an aliquot at intervals
.not exceeding two hours. For the upstream surface water location, a weekly grab sample, cmposited each mnth based on river flow at time of sa:tpling, is also acceptable.
** Sample locations are given on figures and tables in Section 3 of this manual.
O C-48 ISSUE 3 Revision 5
7:m ,
- y ,
'n[
n- > t .
, .BV-Itand 2 ODCM qy f ['
i^
' APPENDIX C
~ODCM CONTROLS lQ
<3 -< ,
. TABLE.3.12-1 (continued)-
g -- lc , > ' RADIOLOGICAL-ENVIRONMENTAL ' MONITORING PROGRAM s i 4
* ' SAMPLING AND ,
[
- EXPOSURE PATHWAY' ~ NUMBER 0F.' SAMPLES : COLLECTION; TYPE ANDLFREQUENCY(")
AND. LOCATIONS **t. .(FREQUENCY 10F ANALYSIS 1
, m.:
.. TAND/OR-SAMPLE: ,
l 4.SINGESTIONL
- a. Milk:' 4lo~citbns.(C)'s. At;1'ast[b'l-veekly e
Gamma;isotopiciand' 'l j when,animalsLare. I-131' analysis of- f' each sample.-
' li Three samplesL on. pasture;.at
'< s n .' selected o.4 least monthly ~at. m Ebasis of other times.
~
highest!poten- q c tial1 thyroid- l
'n cdose using. .
milch' census-
-data.
, 23 0ne locals.large l dairy. . l l
- b. Fish 2 locations. Semi-annual'. One Gamma. isotopic- l
( < sample of avail . analysis lo n edible ! able-species.1 portions. GammaLisotopic
~
.c. Fnod- 4' locations. Annua 11y'at time Products' ..
of harvest, analysis and.'I-131' (Leafy. 1.:Three_ locations analysis'on edible Vegetables) ,vithinL5. miles, portion.'
- 2. One control location. _
l i i j
. i n
r . i- " Analysis frequency same'as sampling frequency unless otherwise specified. c Other dairies may be included as control station or for historical continuity.--These would not be modified on basis of milch animal census. , 74' " th 1
** Sample locations are given on figures and tables in Section 3 of this manual.
C-49 IS3UE'3 t Revision 1
"'c c >
', ".[ ' 7' Li '
n
}
BV-1 end 2 0DCH APPENDIX'C ODCN CONTROLS TABLE 3.12-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS AIRBORNE' PARTICULATE BROAD LEAF VATER OR GASES - FISH HILK VEGETABLES-ANALYSIS (pCi/1) 3 (pC1/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
- 7 l Co-60 3E+2 3E+4 2E+4 )
Zn-65 3E+2 l j Zr/Nb-95 4E+2 b 1E+2 I-131- 2 0.9 3 10 1E+3 60 1E+3 Cs-134 30 50 20 2E+3 70 2E+3 Cs-137 Ba/La-140 2E+2 3E+2
-a. .
For drinking vater samples. This 'is a 40 CFR Part 141 value. If no th7 -drinking vater pathway exists, a vclue of 3E+4 pCi/l may be used.
- b. If no drinking water pathway exists, a value of 20 pCi/1 may be used. ,
i C-50 ISSUE 2 i Revision 2 1
( i,' 'l
,g c ; 3 '-
BV-1'end:2 ODCH 4 ,
"' ' I f: APPENDIX'C L .
I
-9': 5:i-
..ODCH CONTROLS py 7
' : TABLE 4.12-.1-
- HAXIMUM VALUES FOR THE LOVER LIMITS OF DETECTION (LLD)a,.e r
AIRBO'RNE : PARTICULATE . . . . ANALYSISl VATER' OR Gl.S'- FISH ""!~ !! ILK 1 FOOD PRODUCTS -SEDIMENT. (pCi/1) .(pCi/m ). (pCi/kg,IVET) (pCi/l)' (pCi/kg,-VET) (pCi/kg, DRY) [' 4 Gross Beta ..4 -1E-2 H-3' .2000 d , g Hn-54' 15 130: Fe'59 30' 260 Co-58,60 15 .130 4 Zn -65 , 30 260 C
+
Zr-95 30 C f# Nb-95L 15
. (. . '
b '60 I-131~ .I- 7E-2 1-Cs2134- 15 5E-2 130 15 60 150 Cs-137- 18- l6E-2 ,150 18 80' 180 Ba-140l : 60 C '60 c 15~ La-140'- ~ 4
.i
'i 1
-1 j l
i i l-C ISSUE 3 . 3~ Revision 2 a - - :)
p BV-1 and 2.ODCM )i APPENDIX C ODCH CONTROLS TABLE 4.12-1 (continued) TABLE NOTATION
- a. ,The LLD is the smallest concentration of radioactive material in a sample that vill.be detected with 95%. probability with 5% probability of falsely' concluding that a blank observation represents a "real" signal.
For a- particular measurement system (which' may include radiochemical separation): LLD = 4.66 Su (E)(V)(2.22)(Y)"exp(- AoT) where: LLD is the lover limit of detection as defined above (as pCi per unit mass or volume); Sh is the standard deviation of the background counting rate or of the. cDunting 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); , 1 A is the radioactive. decay constant for the particular radionuclide; ) oT is the elapsed time between sample collection (or end of the sample I 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 b5 based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate ) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples). Typical values of E, V, Y and oT should be used in the calculations. , 1 01 C-52 ISSUE 3
= , BV-1 cnd 2 ODCH-
)
APPENDIX C ODCM CONTROLS
- (
4 \. kM TABLE'4.12-1 (continued)
-TABLE NOTATION The LLD is dSfined 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 will be achieved.under-
~
routine conditions. Occasionally, background fluctuations, unavoidable small' sample sizes,. the, presence of interfering nuclides, or other uncontrollable circumstances'may render' these LLD's'unschievable.; In
- such. cases, thel contributing factors shall be identified and described'
,in the' Annual Radiological Environmental Report.
; b'. If nc; drinking water pathway exists, a value of 15 pC1/1 may be.used.
d
- c. If[parentand daughter are totaled, 7the. most-: restrictive LLD should be applied. %
- d. .If no drinking water pathway exists, a value of 3000 pC1/1 may be used.
e.-.This list does not mean that~ 'onlyL'these 'nuclides- are to be detected and q l reported. -Other peaks which are measurable and identifiable, together.vith ) Lthe above nuclides, 'shall also~ be ~ identified in the Annual Radiological I'
- y Environmentsl: Report.
.q a
l 6
)
uf.
-t C-53 ISSUE 3 Revision 2-
-.l'-
(7 i BV-1 cnd 2 ODCM APPENDIX C ODCM CONTROLS O 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 5/f7 elevated releases as defined in Regulatory Guide 1.111, (Rev. 1), July, 1977, the land use census shall also identify the locations of all milk animals and all gardens of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of three miles. Applicability: At all times. Action: ,
- a. 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. Vith a land use census identifying a milk animal location (s) which yields a !
calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Appendix C CONTROL 3.12.1 prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2f, a Special Report, which identifies the new location. The new location shall be added to the radiological environmental monitoring program within 30 days, if possible. The milk sampling program shall include samples from the three active milk animal locations, having the highest calculated dose or dose commitment. Any replaced location may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.
- c. The provisions of Appendix C CONTROL 3.0.3 a:.e 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. l C-54 ISSUE 3 Revision 2
x . , . .
;BV-1 end 2 ODCH a
-APPENDIX C
- ODCM CONTROLS
.p-Q)
' CONTROLS: RADIOLOGICAL ENVIRONMENTAL MONITORING'- INTERLABOPATORY COMPARISON iPROGRAM'
' 3.12.3 ? :In accordance with..BV-l and BV-2 Technical' Specification 6.8.6b, Item 3,
~
. analyses:shall be' performed on radioactive materials supplied as part of an'Interlaboratory Compailson Program Applicability:
- At' all.' times.;
Action:.
- a.- Vith~ analyses not being performed .as ~ required above, report the corrective; actions taken;to- prevent 'a recurrence to, the': Commission in the Annual
- Radiological Environmental Report.
- b. . The. provisions of A'ppendix C CONTROL 3.0.3 are not applicable. .
. SURVEILLANCE REQUIREMENTS A- 4.12.3.12,The'results of : analyses performed' as part .of the above required Interlaboratory Comparison Program shall be includei in the Annual' Radiological Environmental Report.
jj '
' \._./ 1 1
r .,
'jh 1 - .C-55 ISSUE 3 Revision 1 g
b, 1 x
, > :-, y
,BV-1 cndL2 ODCM APPENDIX D
/
BASES FOR ODCH CONTROLS n;ig .- This appendix contains-the Bases : 'for the ODCH Controls that vere transferred from the Bases Section of. the _ Technical Specification per Unit 1/2 Amendments 188/70,f and in: accordance with' Generic . Letter 89-01 and Generic, Letter 89-01,: j, Supplement No. 1.(NUREG-1301).
': 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 were transferred'from the Technical.. Specifications. This vas.done in
'an effort to minimize.the amount of plant procedure changes and to: eliminate any.
~
confusion associated vith' numbering changes. l
!uO).- &c in1
r~ 1 BV-1 cnd 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
. liquid effluents. The alarm / trip setpoints for these instruments
'shall be calculated in accordance with Section 1 of this manual to ensure that the alarm / trip vill occur prior to exceeding the limits 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 CASE 0US 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 the also includes concentrations of provisions for monitoring (and controlling) 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. l i l l i 1 l
' llll D-2 ISSUE 3 Revision 1 l
J
BV-1 end 2 ODCH' l I APFENDIX D l I BASES FOR ODCH CONTROLS 7
- J BASES: LIQUID EFFLUENTS 3/4.11.1.1 . LIQUID EFFLUENT CONCENTRATION This CONTROL is provided to ensure that the concentration of radicactive 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), Tabic 2, Column 2. This limitation provides additional assurance th;c the levels of radioactive materials in bodies _of water outside the site the Section II.A design vill result in exposure within (1) objectives of Appendix I,10 CFR Part 50,'to an individual and The (2) the limits of 10 CFR Part 20.1302 to the population.
concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its HPC in air (submersion) was converted to. an equivalent i concentration in water using the methods described in International l Commission on Radiological Protection (ICRP) Publication 2. 8g 3/4.11.1.2 LIQUID EFFLUENT DOSE This CONTROL is provided to implement the requirements of Sections II.A, III.A, and IV.A of Appendix I, 10 CFR Fart 50. The p) ('" Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid affluents' 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 vill not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculations in the Section 1.3 of this manual implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in Section 1.3 of this manual for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation Of Annual Doses To Man From Routine Releases Of Reactor Effluents For The Purpose Of Evaluating I," Revision 1, October, Compliance Vith 10 CFR Part 50, Appendix 1977, and Regulatory Guide 1.113, " Estimating Aquatic Dispersion Of Effluents From Accidental And Routine Reactor ReleasesNUREG-0133 For The Furpose Of Implementing Appendix I," April, 1977. provides methods for dose calculations consistent with Regulatory
/ ) Guides 1.109 and 1.113.
v/ D-3 ISSUE 3 Revision 1
r i BV-1 end 2 ODCH APPENDIX D BASES FOR ODCM CONTROLS BASES: LIQUID EFFLUENTS (continued) This CONTROL applies to the rele'ase of liquid effluents for Beaver Valley Power Station, Unit No. 1 orthe Unitliquid No. 2. These units have shared radvaste treatment systems, effluents from the shared system are proportioned among the units sharing that system. { 3/4.11.1.3 LIQUID VASTE TREATMENT SYSTEM The CONTROL that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive-materials in liquid effluents vill be kept "as lov as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radvaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents. -This specification applies to Beaver Valley Power Station, Unit No. 1 or Unit No. 2. f E O O D-4 ISSUE 3 Revision 1
W DV-l'en- )DCM-APPENDIX D BASES FOR ODCM CONTROLS
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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 J l
site boundary from gaseous effluents from all' units on the site vill be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual _ dose limits cre the doses a--9ciated with the B, Taule II, Column 1 concentrations of 10 CFR Part '20, Appendix
.These limits provide reasonable ~ assurance inat 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 withir. the site boundary,_the occupancy of the individual vill be sufficiently lov to compensate for any increase in the atmospheric diffusion facter 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 limjts also restrict, at all r's times, the corresponding thyroid dose ratt above background to a child via the inhalation pathway to < 1,500 miem/ year. (w/ i' - 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 radicactive
- material in gaseous effluents vill be kept "as lov as is reasonabl achievable." The Surveillance hequirements implement the rcquirements in Section IIT.A of Appendix I that conformance with the guides of Appendix I be shown by calculetional procedures based l
I on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in Section 2.3 of this manual for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent provided Regulatory Guide 1.109, with the methodology in
" Calculation Of Annual Doses To Man From Routine Releases of Reactor Effl ants Tor 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
( /,T - Reactors," Revision 1, July, 1977. The equations in Section 2.3 of V this manual are provided for determining the air doses at the exclusion area boundary, and are based upon the historical averr.ge D-5 ISSUE 3 Revision 1 o
pc ; i BV-1 cnd 2 ODCM APPENDIX D BASES FOR ODCM CONTROLS BASES: GASEOUS EFFLUENTS (continued) 9-atmospheric conditions. NUBEG-0133 provides methods for dose
-calculations consistent with Regulatory Guides 1.109 and 1.111.
This specifications applies to the release of gaseous effluents from Beaver Valley Power Station, Unit No. _ or Unit No. 2. 3/4.11.2.3 DOSE, RADI0 IODINES, ' RADIOACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES This CONTROL is provided to implement the requirements of Sections II.C, III.A, and IV.A of Appendix I, 10 CFR Part 50. The CONTROLS are the guides set forth in Section II.C of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of . Appendix I to assure that the releases of radioactive materials in gaseous effluents vill be kept "as lov as is reasonably achievable." i The calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendir I be shown ',/ calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlD.ely to '. substantially underestimated. The calculational methods in Section 2.3 of this manaus1 are for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Res;ulatory Guide 1.109, " Calculation of Annual Doses To Mar 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 Wseous Effluents In Routine Releases From ught-Vater-Cooled heactors," 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 9 articulate form, and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The
( pathvays which are examined in the development of these calculations are: 1) individual inhalation of airborne radionuclides,
- 2) deposition of radionuclides onto vegetation with subsequent consumption by maa, 3) deposition onto grassy areas where milk animals and meat producing animals graze s.:h consumption of the milk and meat
' man, and 4) deposition on the ground with subsequent exposure of ' man. This CONTROL applies to radioactive material in particulate form and radionuclides other than noble gases released from Beaver Valley Power Station, Unit No. 1 or Unit No.2.
O D-6 ISSUE 3 Revision 1
{ p , _ BV-1 5nd2ODCH 'i ' APPENDIX D J
; BASES FOR'0DCM CONTROLS-
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BASES: ' GiSEOUS E?FLUENTS- (continued) - 3/4'.11.2.4 . GASEOUS-RADVASTE TREATMENT SYSTEM-The CONTROL that"the appropriate 1.. portions of these. systems be used -{ when 7pecified provides '. reasonable. assurance. that the releases of radioactive mt terials in gaseous!ef fluents vill . be kept "as lov as
.isl reasonably-:. achievable." This' specification: implements the q requirements of 10 CFR Part 50.36a, General' Design Criterion 60 of 'j 2 Appendix-A to'10 CFR'Part 50, and .' design . objective . Section:.II.r of- l Appendix I to.10 CFR Part -50.- .The specifled-limits governing use of appropriate portions 'of the : systems vere specifieu as a-suitable fraction (of the dose design objectives" set forth in q 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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A,. l , i l i i y;v t . 1 D-7 ISSUE 3 Revision 1
B'l-1 cnd 2 ODCH APPENDIX D-BASES FOR ODCM CONTROLS O 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 mremn 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 des l;n 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 purpost:0 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 43 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC J staff action is completed. The variance only relates to the limits } of 40 CFR Part 190, and dcas not apply in any way to the other j 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 enraged in carrying out any operation that is part of the nuclear fuel .ycle. l t
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I O 1 D-8 ISSUE 3 Revision 1 , l ' _a
BV-1 cnd<2 ODCM APPENDIX D BASES FOR ODCM CONTROLS m ,Y BASES: RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 HONITORING PROGRAM The !:adiological monitoring program required by this CONTROL provida:: 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 s ta ?. ion. operation. This monitoring program thereby supplements the radiological effl ant monitoring program by verifying that the measurable conce.r.trations of radioactive materials and levels of radiation' are r.ot 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 operetional experience. The detection capabilities required by Appendix C, Table 4.12-1 are state-of-the-art- for routine environmental measurements in The LLD's for drinking water meet the industrial laboratories. requirements of 40 CFR 141. t ) 3/4.12.2 LAND USE CENSUS v This CONTROL is provided to ensure that changes in the use of l l
-unrestricted areas are identified and that modificatAons to the monitoring programs are made if required by the results of this census. The bust survey information from the door-to-doer survey, aerial survey, or by consulting with local agriculture authorities I shall be used. This censes satinfies 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 l
that significant exposure pathvays via leafy vegetables vill be i identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were , used: 1) that 20% of the garden was used for growing broad leaf l vegetation (i.e., similar tc lettuce and cabbage), and 2) a l i vegetation yield of 2 kg/ square meter. l 3/4.12.3 INTERLABORATORY C'OMPARISON PROGRAM The CONTROL for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a qua]ity assurance program for environmental monitoring in order to ( } demonstrate that the results are reasonably valid. i/ D-9 ISSUE 3 Revision 1
6: BV-1 end 2 ODCM APPENDIX E ANNUAL REPORTS' g x,;
- 'N--) - Thisl appendix contains ths reporting requirements for the Annual Radioactive Effluent Release Report: and 5e Annual . Radiological Environmental Report that were transferred from the Techn. eel Specification per Unit 1/2 Amendments 188/70 and in accordance with Generic Letter 89-01 and. Generic Letter 89-01, Supplement
~ No~. 1 (NUREG 1301).
The numbering of.each' specific Report contained in this appendix'does not appear
~
to be sequential. This is intentional, as all Report numbers remained the same
. wh en . they were transferred from the- Technical Specificatioiss. -This vas.doneLin an effort to minimize the amount of plant procedure changes and to eliminate any confusion associated with numbering changes.
a 4 l I ( ((() I l t jr~ - ' i- i
-N. .
1 E-1 ISSUE 3 Revision 1 f
BV-1 end 2 ODCM
-APPENDIX E
' ANNUAL REPORTS
. ANNUAL REPORT 3
ANNUAL RADIOLOGICAL' ENVIRONMENTAL REPORT 6.9.1.10 ' Routine radiological environmental. operating reports covering the j operation of the unit. during the previous calendar, year shall be i submitted prior to May 1 of each year and vill ~ include reporting any deviations not reported under 6.9.2f with respect to any Appendix C l j CONTROL. ( The annual radiological environmental reports shall include:
- Summaries, interpretations, and statistical evaluation of the l i
results of the radiological envirormental surveillance activities for the report period, including a comparison with pre-operational studies, operational controls (as appropriate), and previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment.
- The results of the land use censuses required by Appendix C CONTROL 3.12.2.
' If harmtol effects or evidence of irreversible damage are detected l by the monitoring, the report shall ' provide an analysis of the l problem and a planned course of action to alleviate the problem. l
' 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 availaole for inclusion with the report, the rem >rt shall ce aubmitted noting and explaining the reasons for the aissing recalts. 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. q l
( 3A single submittal may be made for a multiple unit site. The submittal should combine those sections that are common to both units. ! l E-2' ISSUE 3 ! Revision 1 l
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BU-1 and 2 ODCM APPENDIX E ANNUAL REPORTS ANNUAL REPORT-l ANNUAL PADICACTIVE EFFLUENT RELEASE REPORT
- 6.9.1.11- Routine rarticactive effluent release reports covering the operation of the unit during the previous calendsr year shall be submitted pric: to April 1 of each year. This report is prepared and suhaitted in accordance with BVPO Rm Appendix 5, and at a minimum, shall contain the following:
- A sunrnary of the quantities of radioactive liquid and gaseous effluent and solid waste released fran the tinit as outlined in Regulatory Guide 1.21, Revision 1, June, 19~14, " Measuring, Evaluating, And Reporting Radioactivity In Solid Wastes And Releases Of Radioactive Materials In Liquid And Gaseous Effluents Fran Light-Water-Cooled Nuclear Power Plants," with data sumarized on a quarterly basis following the format of Appendix B thereof.
- An assessment of radiation doses fran 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 eximum noble gas ganma air and beta air doses shall be evaluated. The assessment of radiation doses shall be perfor:ned in accordance witn this snual.
i e Any licensee initiated changes to the ODW made during the 12 rnonth period.
- Any radioactive liquid or gaseous effluent monitoring instrumentation channels not returned to OPEPABLE 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 ODW Appendix C SURVEILLANCE REQUIREMENr 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.
' A single subnittal raay be made for a multiple unit site. The submittal should ccrnbine those sections that are camon to all units at the site; however, for units with separate radwaste systems, the subnittal shall specify the relee.ses of radioactive raaterial fran each unit.
E-4 ISSUE 3 Revision 1 f i 1
3 h i { BV-1 cnd 2'ODCM APPENDIX E } ANNUAL REPORTS l r'
; i
'# ANNUAL REPORT (continued) 1 j
' The following information for each type of solid vaste shipped ;
offsite during the report period: 1
- container volume
- total curie. quantity (determined by measurement or estimate) ;
- principal radionuclides (determined by measurement ur estimate)
~
- type of vaste (e.g., spent resin, compacted dry vaste, evaporator l J
bottoms)
- _ type of container '..g., LSA, Type A, Type B, Large Quantity) i
- solidification agent (e.g., cement) !
- classification and other requirements specified by 10 CFR Part 61 l
~
- An annual summary of hourly meteorclogical 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 wind speed, vind
' direction, and atmospheric stability.
- An assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year.
[]
- An assessment of the radiation doses from radioactive effluents to i MEMBER (S) 0F THE PUBLIC due to their activities inside the site '
boundary (Figure S-1) during the report period. All assumptions used in making these assessments (e.g., specific activity, exposure The time, and location) shall be incluc'ed in these reports. assessment of radiation doses shall be performed in accordance with Section 4 of this manual.
- An assessment of radiation doses to the likely most expoced real individual from reactor releases for the previous calendar year to show conformance with 40 CFR 190, Environmental Radiation Protection Standards For Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Revision 1. The SKYSHINE Code (available from Radiation Shielding Information Center, (ORNL)) is acceptable for calculating the dose contribution from direct radiation due to N-16.
- If quantities of radioactive materials released during the reporting period are significantly above design objectives, the report must cover this specifically.
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.'j E-5 ISSUE 3
'evision 1
s,,- IV-1'Cndi2IODCM' C; . . 4 -
..ppendix F df,/]; '
L/ , LODCM Controls Procedure Matrix i y
- Thisi appendix Leontains plant : procedure references 1 for RadiologicalL. Ef fluent
.Technicalf Specifications' L(RETS) that were . transferred . from the Technical ;
' Specification Procedure Matrix. #
- .n " The- numbering - of each ' specific ' Control, . Surveillance ! Requirement and Table .j contained' :in i this Appendix - does not- appear .to' be' sequential. . This _ . is 1
- intentional, as 'all- Control', Surveillance Requirement . and Table numbers
. remained ' . the ~same when lthey: -were' transferred from the ' Technical-Specifications. Procedure. Matrix. This was done in an' effort to minimize the
; amount' of: plant procedure changes and to eliminate any: confusion associated' j t --with: numbering changes. l U
4 I l i g.
.o v , . .
4' (.. ', A.) - F-1 ISSUE 3 Revision 4 7
.g LV-1 cnd 2'ODCM
' APPENDIX F '
. ODCM CONTROLC PROCEDURE MATRIX r-
. TABLE F:1a !
BV 1 LIQUID EFFLUENT MONITOR SURVEILLANCES
' ODCM Appendix C Control 3 3.3.? Liquid Effluent Monitors in Appendix C Table 3.3-12 OPERABLE APPLICABILITY: Coring Releases Through The Flow Path
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f ODCM SR DESCRIPTION PROCEDURE i 4.3.3.9 . Test Monitors at Table 4.3-12 Frequency 4.3.3.9.1 Monitors Providing Alarm and _ . Automatic Termination 4.3.3.9.1.a Liquid Radwaste Effluent Line - MSP 1-43.18 Channel Calibration
~
, (RM-LW-104) . 10M-54.3 (Log L5) Channel Check 1120M-17.4A.D Source Check OST 1.43.9 FunctionalTest 4.3.3.9.1.b Liquict Wasta Contaminated Drain Line MSP 1-43.23 Channel Calibration (RM-LW 116) 10M-54.3 (Log L5) Channel Check 1/20M-17.4A.D Source Check OST 1.43.9 Functional Test 4.3.3.9.1.c Auxiliary Feed Pump Bay Drain MSP 1-43.70 Channel Calibration Monitor 10M-54.3 (Log L5) Channel Check (RM-DA-10bj 10M-54.3 (Log L5) Source Check i OST 1.43.9 Functional Test 4.3.3.9.2 Monitors Providing Alarm, but Not Prividing Auto Termination 4.3.3.9.2.a Component Cooling - Recirculation MSP 1-43.10 I Channel Calibration Spray Hx River Water Monitor 10M-54.3 (Log L5) Channel Check i (RM-RW-100) OST 1.43.9 Functional Test !
OST 1.43.9A Source Check 4.3.3.9.3 Flow Rat _e Measurement Devices 4.3.3.9.3a Liquid kadwaste Effluent Lines MSP 1-17.5 Channel Calibration (FR-LW-103 for RM-LW-116) MSP 1-17.6 F-LW-104-1 Channel Calibration (FR-LW-104 for RM-LW-104) MSP 1 17.7 F-LW-104-2 Channel Calibration MSP 1 17.8 F-LW-104-1 Functional Test MSP 1 17.9 F-LW-104-2 Functional Test MSP 1 17.10 F-LW-103 Functional Test 10M-54.3 (Log L5) FR LW-103 Channel Check 10M-54.3 (Log L5) FR-LW-104-1 Channel Check 10M-54.3 (Log L5) FR-LW-104-2 Channel Check 4.3.3.9.3.b Cooling Tower Blowdown Line. MSP 1-31.4 F-CW-101 Channel Calibration (FT-CW-101) MSP 131.5 F-CW-101 Functional Test (FT-CW-101 1) MSP 1-31.6 F-CW-101-1 Channel Calibration MSP 1-31.7 F-CW-101 1 e unctional Test 10M-54.3 (Log LS) FT-CW-101 Channel Check 10M-54.3 (Log L5) FT-CW-101-1 Channel Ct eck 4.3.3.9.4 Tank LevelIndicating Devices 4.3.3.9.4.a Primary Water Storage Tank MSP 1-8.1 L-PG115A Functional Test (Ll-PG-115A for BR-TK-6A) MSP 1-8.3 L-PG115/. Channel Calibration 10M-54.3 (Log L5) When Adding to Tank 4.3.3.9.4.b Primary Water Storage Tank MSP 1-8.2 L-PG-115B Functional Test (LI-PG-1158 for BR-TK-68) MSP 1-8.4 L-PG-115B Channel Calibration 10M-54.3 tLog LS) When Adding to Tank 4.3.3.9.4.c. Steam Generator Drain Tank MSP 1 17.1 L-LW110 Functional Test (L1-LW-110 for LW-TK-7A) MSP 1-17.3 L-LW110 Channel Calibration 10U M.3 (Log L5) When Adding to Tank 4.3.3.9.4.d Steam Generator Drain Tank M5r . - 17.2 L-LW111 Functional Test (LI-LW-111 for LW-TK-78) MSP 1-17.4 L-LW111 Channel Calibration y 10M-54.3 (Log LS) When Adding to Tank F-2 ISSUE 3 Revision 4
D : ,.
.3V-1 cnd 2 OPCM
,p s f! q k < APPENDIX F '-
)
iF + ODCM CONTROLS PROCEDURE MATRIX . I
' b. -TABLE F:1b I(f ..BV-2, LIQUID EFFLUENT MONITOR SURVEILLANCES .
l;,qLDCM Apoendix C Crintrol 3.3.3.9i Liquid Effluent Monitors in ,ippendix C Table 3.3-12 OPERABLE - ' J APPLICABILITY: During Releases Through The Flow Paths q
'y ODCM SR DESCRIPTION - PROCEDURE 'j b 4.3.3.9. Test Monitors at Table 4.3 Frequency I
4.3.3.9.1 Monitors Providing Alarm and - Automatic Termination : 4.3.3.9.1.a Liquid Waste Process Effluent Monitor HPM-RP 6.5 Source Check - (2SGC-RQ100) HPM-RP 6.5A . Source Check . MSP 2-43.39 ~ Channel Calibration . '! I z 1/20M-17.4A.C Source Check 20M-51.3 - (Log L5) Channel Check Jg 4 o 20M .25.4.L Source Check ~ 20M-25.4.N - Source Check OST 2.43.3 ' FunctionalTest ; 4.3.3.9.2 Flow Rate Measurement Devices Liquid Radweste Effluent MSP 2-25.1 - . 2SGC-P26A,B Calibration / Functional Test 4.3.3.9.2.a-MSP.243.39 Channel Calibration (2SGC-FIS100) - 20M-54.3 ' (Log L5) Channel Check ; 4.3.3.9.2.b Cooling TowerIMowdown Line MSP 2-31.4 . Channel Calibration . l j (2CWS-FT101) : MSP 2-31.5 FunctionalTest 20M-54.3 (Log L5) Channel Check -
.A l
i ys l F-3 ISSUE 3 ( Revision 4
n KV-1 cnd 2 ODCM APPENDIX F CDCM CONTROLS PROCEDURE MATRIX TABLE F:2a BV 1 GASEOUS EFFLUENT MONITOR SURVEILLANCES ODCM Appendix C Control 3.3.3.10 Gaseous Effluent Monitors in Appendix C Table 3.3-13 OPERABLE
. APPLICABillTY: During Releases Through The Flow Paths ~
ODCM SR DESCRIPTION PROCEDURE 4.3.3.10 Test Monitors at Table 4.3-13 Frequency
) 4.3.3.10.1 Gaseous Waste / Process Vent -
4.2.3.10.1.a Nobie Gas Activity Monitor : MSP 1-43.22 Channel Calibration Prl:(RM-GW-108B) 10M-19.4.E Channel Check 10M-19.4.E Source Check 10M-54.3 (Log LS) RM-GW-1088 Channel Check 10M-54.3 (Log L5) RM-GW-109 Channel Check OST 1.43.9 Functional Test 4.3.3.10.1.b Particulate Activity Monitor 10M-54.3 (Log LS) Channel Check Pri: (RM-GW-108A) 4.3.3.10.1.c System Effluent Ficw Rate Measuring MSP 1-19.5 Fun:tional Test . Device MSP 1 19.6 Channel Calibration Prl: (FR-GW-108) 10M-54.3 . (Log LS) Channel Check 1 i ' Alt: (RM-GW-109 Ch 10) 4.3.3.10.1.d Sampler Flow Rate Measuring Device MSP 1-43.21 Channel Calibration Prl: (Rotometer) MSP 1-43.71 Rotometer Functional Test 4.3.3.10.2 Auxiliary Building Vent 4.3.3.10.2.a Noble Gas Activity Monitor MSP 1-43.13 Channel Calibration Pri: (RM-VS-101B) 10M-54.3 (Log LS) RM-VS-101B Channel Check Alt: /RM-VS-109 Ch 5) 10M-54.3 (Log L5) RM-VS-109 Channel Check OST 1.43.7A . Altemate Noble Gas Monitor Functional Test OST 1.43.9 Functional Test OST 1.43.9A Source Check 4.3.3.10.2.b Particulate Activity Monitor 10M 54.3 (Log L5) Channel Check Pri: (RM-VS-101 A) Alt: (RM-VS-109 Ch 1) 4.3.3.10.2.c System Effluent Flow Rate Measuring MSP 1-44.7 Functional Test Device MSP 1-44.8 Channel Calibration l Pri: (FR-VS-101) 10M-54.3 (Log L5) Channel Check Alt: (RM-VS-109 Ch 10) l 4.3.3.10.2.d Sampler Flow Rate Measuring Device MSP 1-44.7 Functional Test ! Prl:(Rotometer) MSP 1-44.8 Channe! Calibration l _ 10M-54.3 (Log L5) Channel Check l 4.3.330.3 Rx Containment / SLCRS Vent 4.3.3.10.3.e Noble Gas Activity Monitor MSP 1-43.20 Channel Calibration Pri: (RM-VS-1078) 10M-54.3 (Log L5) RM-VS-107B Channel Check j Alt: (RM-VS-110 Ch 5) 10M-54.3 (Log L5) RM-VS-110 Channel Check 1 03T 1.43.7A Alternate Noble Gas Monitor Functional Test )' OST 1.43.9 Functional Test OST 1.43.9A Scarce Check 4.3.3.10.3.b Particulate Activity Monitor 10M-54.3 (Log LS) Channel Check Pri: (RM-VS-107A) Alt:(RM-VS-110 Ch 1) 4.3.3.10.3.c { System Effluent Flow Rate Measuring MSP 1-44.9 Channel Calibration ! Device MSP 144.10 Functional Test Pri: (FR-VS-112) 10M-54.3 (Log L5) Channel Check ; Alt: (RM-VS-110 Ch 10) 4.3.3.10.3.4 Sampler Flow Rate Measuring Device MSP 1-4319 Channel Calibration i Pri:(Rotometer) MSP 1-43.72 Rotometer Functional Test I i Radeon Log Channel Check F-4 ISSUE 3 i Revision 4 L.w . - .- . _. : . . _ _ _ _ . -
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.2,V-1Ecnd 2 ODCM N < .
APPENDIX F - ODCM CONTROLS PROCEDURE MATRIX
. TABLE F:2b c[ .
BV 2 GASEOUR EFFLUENT MONITOR SURVEILLANCES A ,
. QQQM Anoendix'C Control 3.'3.3.10 Gassous Emuent Monitors In' Appendix C Table 3.3-13 OPERABLE L 1 APPLICABILITY: During Releases Through The Flow Paths ;
J ODCM SR -- : DESCRIPTION 1 PROCEDURE 4.3.3.10 Test Monitors at Table 4.3-13, Frequency 1 SLCRS - Unfiltered Pathway :) 4.3.3.10.1-4.3.3.10.1.a i Noble Gas Activity Monitor . MSP 2-43.36 - ChannelCalibration 20M-54.3 ' . (Log L5) Channel Check - Pri:(2HVS-RQ101B) - OST 2-43.9 : . FunctionalTest- . HPM-RIP 2.18 Source Check (DRMS Auto Function) - " 4.3.3.10.1.b . Particulate Activity Monitor - 2OM-54.3 (Log LS) ChannelCheck t Pri:(2HVS-RQ101A) Channel Calibration l 4.3.3.10.1.c Process Flow Rate Monitor Prl:(Monitoritem 29) MSP 2-43.36 MSP 2-43.36a Functional Test . N MWR- , Velocity Probe Calibration - 20M-54.3 ' (Log U') Channel Check ' 4.3.3.10.1.d Sampler Flow Rate Monitor MSP 2 43.36 : . Channel Calibration Pri:(Monitoritem 28) MSP 2-43.36A FunctionalTest
' 2OM-54.3 '- (Log LS) Channel Check -
T3.3.10.2 - SLCRS - Filtered Pathway - 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 Calibration Prl:(2HVS-RQ1098) . 20M-54.3 (Log L5) Channel Check - OST 2.43.8 - FunctionalTest
.M HPM-RIP 2.18 Source Check (DRMS Auto Function) 4.3.3.10.2.b . Particulate Activity Monitor - MSP 2-43.32 . Channel Calibration 20M-54.8 - (Log L5) Channel Check :1 Pri:(2HVS-RQ109A)
MSP 2-43.32a Functional Test , i 4.3.3.10.2.c - Process Flow Rate Monitor MSP 2-43.33 2HVS-RQ1098,C,D, Channel Calibration l Prl:(Monitoritem 29) 20M-54.3 - -(Log L5) Channel Check ] 1 4.3.3.10.2.d Sampler FlofRats Monitor MSP 2-43.32 2HVS-RQ109A Channel Calibration Pri:(Monitoritems 28 & 72) MSP 2-43.32A FunctionalTest MSP 2-43.33 2HVS-RQ109B,C,D, Channel Calibrat'cn s 2OM-54.3 (Log L5) Channel Check - 4.3.3.10.3 Decontamination Building Vent Noble Gas Activity Monitor MSP 2-43.35 . Channel Calibration
; 4.3.3.10.3.a i 20M-54.3' (Log L5)ChannelCheck Prf:(2RMQ-RQ3018) -
OST 2.43.9 - FunctionalTest ; HPM-RIP 2.18 Sourco Check (DRMS Auto Function) j 4.3.3.10.3.b Particulate ActMty Monitor ' 20M-54.3 (Log L5) Channel Check l Prl: (2RMO-RQ301A) l t- ; i I i j
& l-F-5 ISS'71 3 Revision 4
m s BV-1'cnd 2 ODCM APPENDIX F ODCM CONTROLS PROCEDURE MATRIX - TABLE F:2b BV-2 GASEOUS EFFLUENT MONITOR SURVEILLANCES ODCM Appendix C Control 3.3.3.10: Gaseous Effluent Monitors in Appendix C Tabie 3.3-13 OPERABLE APPLICABILITY: During Reicases Through The Flow Paths
'~
ODCM SR DESCRIPTION PROCEDURE T3.3.10.3.d Sampler Flow Rate Monitor MSP 2-43.35 'hannel Calibration Pri:(Monitor item 28) MSP 2-43.35A Functional Test 20M-54.3 (Log L5) Uhannel Check 4.3.3.10.4 Condensate Polishing Building Vent 4.3.3.10.4.a Noble Gas Activity Monitor MSP 243.38 Channel Calibration g Pri:(2HVL-RQ112B) 2OM-54.3 - (Log L5) Channel Check
'/f$ OST 2.43 9 FunctionalTest HPM-RIP 2.18 Source Check (DRMS Auto Function) 4.3.3.10.4.b Particula.Uctivity Monitor 20M-54.3 (Log LS) Channel Check Prl: (2HVL-RQ112A) 4.3.3.10.4.d Sampler Flow Rate Monitor MSP 2-43.38 - Channel Calibration Pri:(Monitor item 28) 2OM-54.3 (Log L5) Channel Check 4.3.3.10.5 Waste Gas Storage Vault Vent 4.3.3.10.5.a $'oble Gas Activity Monitor MSP 2-43.37 - r',hannel Calibration Pri:(2RMQ-RQ3038) 20M-54.3 (Log LS) ChannelCheck 1 OST 2.43.9 FunctionalTest HPM-RIP 2.18 Source Check (DRMS Auto Function) 4.3.3.10.5.b - Particulate Activity Monitor 20M-54.3 (Log L5) Channel Check Pri:(2RMQ-RQ303A) 4.3.3.10.5.d Sampler Flow Rate Monitor MSP 2-43.37 Channel Calibration Pri:(Monitor item 28) MSP 2-43.37A Functional Test ,.
20M-54.3 (Log L5) Channel Check !! 4 I
)
l i I O F-6 ISSU'i' 3 !l Revision 4 !l J
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, , .BV-1 cnd 2 ODCM U'
s =i, IAPPENDIX F L '
. ODCM CONTROLS PROCEDURE MATRIX,_
TABLE F:3.
~
Aj-BV.1 AND 2 LIQUID EFFLUENT CONCENTRATION SURVEILLANCES a.
.s .
ODCM Accendix C Control 3.11.1.1: Effluent Concentration Within 10 Times 10CFR20 EC's - .; 4 g@. : APPLICABILITY: At AllTimes .
- ODCM SR - DESCRIPTION - PROCEDURE-4.11.1.1.1: . Sample and Analyze Radioactive HPM-CP 1 Liquid Radwaste Discharges 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 Procedures : j CHM CP 8 Logs and Forms (Analysis) CHM CP 9 Conduct of Operation .. HPM-RP 6.1, Liould We'ste Tank Sampling HPM-RIP 2.2 Effluent Monitors . . HPM-RIP 2.21 f DRMS Effluent Monitors . I HPM-RIPS.17 ' ND-9900 Counting System ') 4.11.1.1.1.8 Continuous Releases - CHM CP 3 > Sampling and Testing j CHM CP 5 .Radicct+Tkel Procedures d CHM CP 8 ' Logs and Forms (Analysis) . :1 CHM CP g ' Conduct of Operation - HPM-RIP 2.2 Effluent Monitors ,, HPM-RIP 2.21 DRMS Effluent Monitors j HPM-RIP 5.17 ND-9g00 Counting Syrtem
- 4.11.1.1.2 Use ODCM Methodology to Aesure . HPM-RP 6.5 Liquid Waste Discharge Authorization Compliance : HPM-RP 6.5A ' Liquid Waste Discharge Authorization ; . .
j 1/20M-17.4A.D Liquid Waste Discharge (with RP 6.5 or 6.5A) 4.11.1.1.3 , Take Turbine Building Grab Sample . CHM CP 3 Sampling and Testing
)'
When BV-1 Primary to Secondary . . CHM CP 5 Leak Rate Calculations . '1 k Leakage Exceeds 0.1 gpm (142 gpd) CHM CP 8 HPM-RP 6.5 - Logs and Forms (Analysis) . .. Liquid % to Discharge Authorization HPM-RP 6.5A Liquid Wasto Discharge Authorization HPM-RIP 2.2 Effluent Monitnrs - ' i 4.11.1.1.4 Take Turbine Building Grab Sample . CHMCP3- Sempting and Testing - .. When BV-2 Primary to Secondary . CHM CP 5 Leak Rats Calculations Leakage Exceeds 0.1 gpm (142 god) CHM CP 8 - Logs and Forms (Analysis) HPM-RP 6.5 ' Uquid Waste Discharge Authorization . r HPM-RP 6.5A Liquid Waste Discharge Authorization p HPM-RIP 2.21 DRMS Effluens Monitors 4.11.1.1.5. Take Grab Samples Prior to BV-2 HPM-RP 6.1 Liquid Waste Tank Sampling - Recirculation Drain Pump Discharge 20M-9.2 Rx Plant Vents and Drains (CB-16) to Catch Basin No.16 20M-g.4F Drain RSS Pump Caning / Pit . j OM 51-86 OM Clearance 51-86 (2DAS-P216/43) I l ;f
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APPENDIX 7 ODCM COi4TROLS PROCEDURE MATRIX'
-TABLE F:4
.] l BV-1 AND 2 LIQUID EFFLUENT DOSE SURVEILLANCES !
l ODCM Accendix C Control 3.11.1.2: Uquid'Emuent Dose l APPUCADit.lTY: At AllTimes- {
- , . ODCM SR DESCRIPTION PROCEDURE .
4.11.1.2.1 Using the ODCM Determine HPM-RP 6.5 Liquid Waste Discharge Authorization { h$ Cumulative Dose Frora Liqc::t HPM-RP 0.5A Uguid Waste Discharge Authorization j Emuents Every 31 Days HP Letter Monthly Cose Projection (with RP 6.5 or 6.5A) J 1/2OM-17.4A.D Ltquid Waste Discharge (with RP 6.5 nr 6.5A) ! i i f i O O F-8 ISSUE 3 Revision 4 N . . .
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-APPENDlX F'-:
g , - ODCM CONTROLS PROCEDURE MATRIX p TABLE F:5 :- l,[ . - .7'
~'
. BV 1 N!O 2 LIQUID EFFLUENT TREATMENT SURVElLLANCES
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, 1 DDCM Ancondix C Control 3.11.1.3: Uquid Emuent Treatment System
"- . APPUCABluTY: At AllTimes L ; 4
'\
ODCM SR DESCRIPTION - PROCEDURE l
, 4.11.1.3.1 -. Using the ODCM - Project the Uquid HPM-RP 6.5 - c_ Uquid Waste Discharge Authorization I JL. -l
'g, Release Dose Every 31 Days 7 _. HPM-RP 6.5A : Uquid Waste Discharge Authorization -- .,
M
' ~
HP Letter ; .
. Monthly Dose Projection (with RP 6.5 or 6.5A) 'q n ,
1/2OM-17.4A.D ' Uquid Waste Discharge (with RP 6.5 or 6.5A)
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l O . 1 l 1 m F-3 ISSUE 3 ! Revision 4 1
6 .- GV-1 and 2 ODCM APPENDIX F ODCM CONTROLS PROCEDURE MATRIX TABLE F:6 BV-1 AND 2 GASEOUS EFFLUENT DOSE SURVEILLANCES ODCM Anoendix C Control 3.11.2.1: Uaseous EF mse Rates
&PLICABlUD': At All Times ODCM SR DESCRIPTION PROCEDURE 4.11.2.1.1 Using the ODCM - Determine the HPM-RP 6.6 Gaseous Waste Discharge Authorization Noble Gas Effluent Dose Rate HPM.RP 6.6A Gaseous Waste Discharge Authorization HPM-RP 6.10 Continuous Ventilation Path Releases HPM-RP 6.12 Abnormal Gaseous Releases HPM-RP 6.12A Abnormal Gaseous Releases
. 10M-19.4E BV-1 Decay Tank Dischargo (with RP 6.6 or 6.6A) 1/2OM-19.4A.B BV-2 Decay Tank Discharge (with RP 6.6 or 6.6A) 4.11.2.1.2 Sample and Analyze per Table HPM-CP 1 Radwaste Disposal 4.112 to Determine Inhalation Mthway Dose 4.11.2.1.2.A Waste Gas Storage Tank - CHM CP 3 Sampling and Testing Gmg Sample Each Tank CHM CP 5 Radiochenlical Procedures CHM CP 8 Logs and Forms (Analysis) ,
CHM CP 9 Conduct of Operation i HPM RP 6.3 BV 1 Gas Tank Sampling HPM-RP 6.4 BV-2 Gas Tank Sampling HPM-RP 6.6 Gaseous Waste Discharge Authorization HPM-RP 6.6A Gaseous Waste Discharge Authorization HPM-RIP 2.2 Effluent Monitors HPM-RIP 2.20 DRMS Process Monitors HPM-RIP 2.21 DRMS Effluent Monitors 4.11.2.1.2.0 Containment Purge - CHM CP 3 Sampling and Testing Grag Sample Each Purge CHM CP 5 Radiochemical Procedures CHM CP 8 Logs and Forms (Analysis) CHM CP 9 Conduct of Operation HPM-RP 6.6 Gaseous Waste Discharge Authorization HPM-RP 6.6A Gaseous Waste Discharge Authorization HPM-RP 7.3 Air Sampling HPM-RIP 2.2 Effluent Monitors HPM-RIP 2.20 DRMS Process Monitors HPM-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 CHMCP3 Sampling and Testing thru Samp es CHM CP 5 Radiochemical Procedures 4.11.2.1.C.3 CHM CP 8 Legs and Forms (Analysis) and CHM CP 9 Conduct of Operation 4.11.2.1.2.D.1 HPM-RP 6.10 Continuous Ventilation Path Releases 6 thru HPM-RIP 2.2 Effluent Monitors 4.11.2.1.2.D.3 HPM-RIP 2.8 SA-9/10 Noble Gas Monitor HPM-RIP 2.10 SPING-4 Monitor HPM-RIP 2.32 RMS Sample Flow Valve Line-Up (normal) HPM-RIP 2.33 RMS Sample Flow Valve Line-Up (after sampling) HPM-REOP 1.1 SA-9/10 Emergency Operation HPM-REOP 1.2 SPING.4 Emergency Operation 4.11.2.1.2.C.4 BV-2 Grab and Continuous CHM CP 3 Sampling and Testing thru Samples CHM CP 5 Radiochemical Procedures 4.11.2.1.2.C.8 CHM CP 8 Logs and Forms (Analysis) and CHM CP O Conduct of Operation 4.11.2.1.2.D.4 ' HPM-RP 6.10 Continuous Ventilation Path Releases thru HPM-RIP 2.21 DRMS Effluent Monitors 4.11.2.1.2.D.8 HPM-REOP 4.1 Emergency Operation of WRGM Assembly e F-10 ISSUE 3 Revision 5 l
4 BV-1'cnd',2 ODCM '
- APPENDtX F -
ODCM CONTROLS PROCEDURE MATRIX : TABLE F:7
- i' A) BV-1 AND 2 GASEOUS EFFLUENT AIR DOSE SURVEILLANCES ^
% )'
. ODCM Anoendix C Control 3.11.2.2: Gaseous Efflu'e nt Air Doses
, APPLICABILITY: At AllTimes ODCM SR DESCRIPTION - PROCEDURE 4.11.2.2.1 ' Using the ODCM . Determine the HPM-RP 6.6 Gaseous Waste Discharge Authorization Noble Gas Cumulative Dose ' HPM-RP 6.6A . Gaseous Waste Discharge Authorization Contributions Every 31 Days HPM-RP 6.10 . Continuous Ventilation Path Releases HPM-RP 6.12 Abnormal Gaseous Releases .
HPM-RP 6.12A Abnormal Gaseous Releases Jg HPM-RIP 2.2 , ~ Emuent Monitors HPM-RIP 2.21 DRMS Emuent Monitors q 10M-19.4E BV-1 Decay Tank Discharge (with RP 6.6 or 6.6A) 1 1/20M-19.4A.B BV-2 Decay Tank Discharge (with RP 6.6 or 6.6A) HP Letter Month!y Dose Projection (with RP 6.6 or 6.6A) i 4
'\
l 4 (> F-11 ISSUE 3 Revision 4
i OV-1 and 2 ODCM ' APPENDIX F . ODCM CONTROLS PROCEDURE MATRIX TABLE F:8 BV-1 AND 2 GASEOUS EFFLUENT PARTICULATE AND IODINE DOSE SURVEILLANCES ODCM Appendix C Control 3.11.2.3: Gaseous Emuont Particulate And lodine Doses APPLICABILITY; At All Times
"~
ODCM SR - DESCRIPliON PROCEDURE 4.11.2.3.1 -, Using the ODCM - Detennine the HPM-RP 6.6 Gaeeous Waste Discharge Authorization Particulate & Radioiodine Cumulative HPM-RP 6.6A Gaseous Waste Discharge Authorization i Dose Contributions Every 31 Days HPM-RP 6.10 Continuous Ventilation Path Releases .l HPM-RP 6.12 Abnormal Gaseous Releases HPM-RP 6.12A Abnormal Gaseous Releases HPM-RIP 2.2 Et.luent Monitors HPM-RIP 2.21 DrtMS Emuent Monitors i 10M-19.4E BV-1 Decay Tank Discharge (with RP 6.6 or 6.6A) .
/
1/2OM-19.4A.B BV-2 Decay Tank Discharge (with RP 6.6 or 6.6A) HP Letter Monthly Dose Projection (with RP 6.6 or 6.6A) O, f l l 1 O\ l F-12 ISSUE 3 Revision 4
n . LV -1.cnd 2 ODCM APPENDIX F ODCM CONTROLS PROCEDURE MA'n RlX
,9"
()- I
.c- 4 TABLE P:9
' BV-1 AND 2 GASEOUS EFFLUENT TREATMENT SURVElLLANCES ODCM Aooendix C Control 3.11.2.4: Gaseous Effluent Treatment System
- APPLICABILITY:At All Times -
ODCM SR DESCRIPTION PROCEDURE ~ 4.11.2.4.1 Using the ODCM - Project the Gas - HPM-RP 6.6 Gaseous Waste Discharge Authorization 3 Release Dose from the Site Every 31 HPM-RP 6.6A , Gaseous Waste Discharge Authorization Days'. HPM-RP 6.10 - Continuous Ventilation Path Releases (hg/ j HPM-RP 6.12. . Abnormal Gaseous Releeses HPM-RP 6.12A Abnormal Gaseous Releases HP Letter Monthly Dose Projection (with RP 6.6 or 6.6A) . 10M-10.4E ' BV-1 Decay Tank Discharge (with RP 6.6 or 6.6A) j 1/20M-19.4A.B BV-2 Decay Tank Discharge (with RP 6.6 or 6.6A) J
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l I J l l
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N' F-13 ISSUE 3 Revision < R. -
f . BV-1 Cmd 2 ODCM APPENDIX F ODCM CONTROLS PROCEDURE MATRIX j TABLE F;10 BV 1 AND 2 TOTAL DOSE SURVEILLANCES l
. ODCM Apoendix C Control 3.11.4.1: Liquid And Gaseous Doses APPLICABILITY: At AllTimes ~
ODCM SR DESCRIPTION - PROCEDURE i 4.11.4.1.1 Using the ODCM - De'.ermhe HPM-APP 5 Compliance with RG 1.21 & T.S. (40CFR190) Cumulative Gas & Liquid Dose per HPM-RP 6.5 Uquid Waste Discharge Authorization Appendix C Control 3.11.1.2, HPM-RP 6.5A Liquid Waste Discharge Authorization 3.11.2.2,3.11.2.3 HPM-RP 6.6 Gaseous Waste Discharge Authorization HPM-RP 6.6A Gaseous Waste Discharge Authorization HPM-RP 6.10 Continuous Ventilation Path Releases HPM-RP 6.12 Abnormal Gaseous Releases HPM-RP 6.12A Abnormal Gaseous Releases REAM-REAP 6.105 Effluent Data Processing (40CFR190) O O F-14 ISSUE 3 Revision 4 a _
h 4
'BV-l' cad 2 ODCM
. l APPENDIX F -
~ ODCM CONTROLS PROCEDURE MATRIX
/~ TABLE F:11 -
tg}. BV-1 AND 2 REMP SURVEILLANCES ' ODCM Aooendix C Control 3.12.1: Radiological Environmental Monitoring Program (REMP) APPLICABILITY: At AllTimes - ODCM SR DESCRIPTION PROCEDURE 4.12,1,1; Using Locations in the ODCM - Collect and Analyze Samples per EPMP 2.01. EPMP 3.01 Description of REMP Environmental Sampling g Tables 3.12-1,3.12-2 & 4.12-1: i b v '
'a.
F-15 ISSUE 3 Revision 4
- m. ;
BV-1 cnd 2 ODCM APPENDIX F ODCM CONTROLS PROCEDURE MATRIX ' TABLE F:12 BV-1 AND 2 LAND USE CENSUS SURVEILLANCES ODCM Appendix Contro) 3.12.2: Land Use Census APPLICABILITY:At AllTimes
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ODCM SR DESCRIPTION PROCEDURE
~I 4.12.2.1_ Using the Best Available Method - EPMP 2.01 Description of REMP Conduct a Land Use Census Yearly Between 6/1 & 10/1 O
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BV-1,end 2'ODCM APPENDIX F , ODCM CONTROLS PROCEDURE MATRIX 1
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TABLE F:13 BW1 AND 2 INTERLABORATORY COMPARISON PROGRAM ODCM Aopendix C Control 3.12.3: Intedaboratory Comparison Program APPLICABILITY: At All Times . ODCM SR DESCRIPTION 4.12.3.1 PROCEDURE loclude Analysis Results of the. EPMP 2.01 Description of REMP Intertaboratory Comparison Program in the Annual Radiological Environmental Report O r I F-17 ISSUE 3 Revision 4 h , ..__ _ - - -}}