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'.2-'iquid Effluent Concentration Calculation
'.2-'iquid Effluent Concentration Calculation
~Pa e~-10 2.3 2.3.1 3.0 3.1 3.1.1 3.1.2 3.1.3 Dose Determinations Maximum Dose Equivalent Pathway GASEOUS EFFLUENTS'Setpoint Determinations Basis Stack Monitor Setpoints Recombiner.
~Pa e~-10 2.3 2.3.1 3.0 3.1 3.1.1 3.1.2 3.1.3 Dose Determinations Maximum Dose Equivalent Pathway GASEOUS EFFLUENTS'Setpoint Determinations Basis Stack Monitor Setpoints Recombiner.
Discharge (Off Gas)Monitor Setpoints 12 12 17 17 17 18 21 3.1.4 Emergency Condenser Vent Monitor Setpoint 22 3.1.5 3.1.5.1 3.1.5.2 Discussion Stack Effluent Monitoring System Description Stack.Sample Flow Path-RAGEHS 23 23.3.1.5.3.Stack Sample Flow Path-OGESHS 25 Ae, f/''f,i I 4)"4'pa't k W ODCM-NINE MILE POINT UNIT 1 TABLE OF CONTENTS (Cont'd)3.1.5.4-Sample Frequency/Sample Analysis=3.1.5.5 I-133 Estimates 3,1.5.6 Gaseous Radwaste Treatment System Operation~Pa e 26 27 27 3.2 3.2.1 Dose and Dose Rate Determination Dose Rate 28 31 3.2.1.1 Noble Gases 3.2.1.2 Tritium, Iodines and Particulates 31 33 3.2.2 Dose 35 3.2.2.1 Noble Gas Air Dose 3.2.2.2 Tritium Iodines and Particulates 3.2.2.3 Accumulating Doses 36 37 38 3.3 Critical Receptors 39 e 4.O 4.1 40 CFR 190 REQUIREMENTS Evaluation of Doses From Liquid Effluents 3.4 Refinement of Offsite Doses Resulting From Emergency Condenser Vent Releases 41 42 4.2'.3 4.4 5.0 5.1 5.2 5.3 Evaluation of Doses From Gaseous Effluents i Evaluation" of Doses From Direct Radiation Doses to Members of the Public Nithin the Site Boundary ENVIRONMENTAL MONITORING PROGRAM Sampling Stations Interlaboratory Comparison Program Capabilities for Thermoluminescent Dosimeters Used for Environmental Measurements.
Discharge (Off Gas)Monitor Setpoints 12 12 17 17 17 18 21 3.1.4 Emergency Condenser Vent Monitor Setpoint 22 3.1.5 3.1.5.1 3.1.5.2 Discussion Stack Effluent Monitoring
 
===System Description===
Stack.Sample Flow Path-RAGEHS 23 23.3.1.5.3.Stack Sample Flow Path-OGESHS 25 Ae, f/''f,i I 4)"4'pa't k W ODCM-NINE MILE POINT UNIT 1 TABLE OF CONTENTS (Cont'd)3.1.5.4-Sample Frequency/Sample Analysis=3.1.5.5 I-133 Estimates 3,1.5.6 Gaseous Radwaste Treatment System Operation~Pa e 26 27 27 3.2 3.2.1 Dose and Dose Rate Determination Dose Rate 28 31 3.2.1.1 Noble Gases 3.2.1.2 Tritium, Iodines and Particulates 31 33 3.2.2 Dose 35 3.2.2.1 Noble Gas Air Dose 3.2.2.2 Tritium Iodines and Particulates 3.2.2.3 Accumulating Doses 36 37 38 3.3 Critical Receptors 39 e 4.O 4.1 40 CFR 190 REQUIREMENTS Evaluation of Doses From Liquid Effluents 3.4 Refinement of Offsite Doses Resulting From Emergency Condenser Vent Releases 41 42 4.2'.3 4.4 5.0 5.1 5.2 5.3 Evaluation of Doses From Gaseous Effluents i Evaluation" of Doses From Direct Radiation Doses to Members of the Public Nithin the Site Boundary ENVIRONMENTAL MONITORING PROGRAM Sampling Stations Interlaboratory Comparison Program Capabilities for Thermoluminescent Dosimeters Used for Environmental Measurements.
48 48 49 53 55 56  
48 48 49 53 55 56  
<<Y I U'', L'b4Qtg I ODCH-NINE MILE POINT UNIT 1 TABLE OF CONTENTS (Cont'd)~Pa e Table l-l Average Energy Per Disintegration Tables 2-1 Aiat Values for the NMP-1 Facility to 2-8 Table 3-1 Critical Receptor-Dispersion Parameters for Ground.Level and Elevated Releases Table 3-2 Gamma Air and Hhole Body Plume Shine Dose Factors for Noble Gases (Bi and Vi)Table 3-3 Immersion Dose Factors for Noble Gases Tables 3-4'''to 3-22">>Organ Dose and Dose Rate Factors (Ri)Table 5-1 NMP-1 Radiological Environmental Monitoring Program Sampling Locations Figure 5.1-1 Nine Mile'oint On-S/te Hap Figure 5.1-2.Nine Mile Point Offsite Hap 59 60.68 69 70 71 90 94 95 Appendix A Liquid Dose Factor Derivation (Aiat)Appendix B Plume Shine Dose Factor Derivation (Bi and Vi)...Appendix C.Organ Dose and Dose Rate Factors for Iodine-131 and 133, Particulates and Tritium Derivation (Ri)Appendix D Diagrams of Liquid and Gaseous Radwaste Treatment Systems 97 100 104 115 l>d I 1 a  
<<Y I U'', L'b4Qtg I ODCH-NINE MILE POINT UNIT 1 TABLE OF CONTENTS (Cont'd)~Pa e Table l-l Average Energy Per Disintegration Tables 2-1 Aiat Values for the NMP-1 Facility to 2-8 Table 3-1 Critical Receptor-Dispersion Parameters for Ground.Level and Elevated Releases Table 3-2 Gamma Air and Hhole Body Plume Shine Dose Factors for Noble Gases (Bi and Vi)Table 3-3 Immersion Dose Factors for Noble Gases Tables 3-4'''to 3-22">>Organ Dose and Dose Rate Factors (Ri)Table 5-1 NMP-1 Radiological Environmental Monitoring Program Sampling Locations Figure 5.1-1 Nine Mile'oint On-S/te Hap Figure 5.1-2.Nine Mile Point Offsite Hap 59 60.68 69 70 71 90 94 95 Appendix A Liquid Dose Factor Derivation (Aiat)Appendix B Plume Shine Dose Factor Derivation (Bi and Vi)...Appendix C.Organ Dose and Dose Rate Factors for Iodine-131 and 133, Particulates and Tritium Derivation (Ri)Appendix D Diagrams of Liquid and Gaseous Radwaste Treatment Systems 97 100 104 115 l>d I 1 a  
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&E w'4 I ill a~otal C V'I IO ISOKINETIC PROBE RN 21 11241 RAG EMS RAGEMS Ditution Return 112-52 112-131]Sample Return Drain 112-55 11243 112-132 112.57 OGESMS Intet 112.30 112-56 112-133 OGESMS Outtet Figure D-9 Stack Sample and Sample Return NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 1 OFFSlTE DOSE CALC.MANUAL 126-S lit F'~~J tel RAG EMS inlet OVS 112-173 OV3 112-169 OV2 112-167 PCV 112-106 112-110 Ne Supply OV8 112-178 1 2-1 Pl 112-21 OV4 112-171 OFS1 112-101A C 112.130 112-51 OV1 OV13 112-165 t 1248 RAG EMS Dilution Inlet OFC4 112-104 OFS4 112-04A PCV 112-107 OFC1 112-101 112-111 Pl 11-122 OFC3 112-103 OFS3 112-103A 112-116 OCF2 112-102 OFS2 112-102A 112-151 OV16 112-150 112-112 Pl"11-23 OV12 Senlpte 112+7 Return RAG EMS Outlet 112-113 Pl 112-24 112-117 112-118 OP2 OP1 OV6 112-175 Figure 0-1 0 11-44 RAGEMS Dilution Schematic NIAGARA MOHAWK POWER CORPORATION NINE MlLE POINT-UNIT 1 OFF SITE DOSE CALC.MANUAL 127 IP'~)~ir 14 gl g 112-114 1FS1 112-129 Pl 112-125 1V3 1V4 112-183 112-185,'V3 2V4 112-199 112-201 3V3 112.7 3V16 112-218 3V 112-96 Qalhn2 Tritium 112-73 112-72 112-74 3FS1 112-105A 1V1 112-1 1V2 12-'I81 2VI 112-195 2 112-197 3VI 3VS 112 3 3 2.77 6 Uter-95 112-99.75 Pl 112-126 3GVI 112-105 1V5 112-186 1V6 2VS 112-187 112-202 2V6 112-203 2V11 112-208 11 76 I-78 3 3 3V4 112.98 112-119 3V6 3V7 112-100 112-211 Pl 11247 1V11 112-192 Pl 11244 1V17 11249 3V11 112-215 3VI 112-217'l12-108 3PI 3VIO 112-21 I 3VI2 112-109 112-216 Fi Ure D-11 RAGEMS Schematic NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 1 OFFSITE DOSE CALC.MANUAL 128 P+A.J a tA t'a'~<<a 1 0 11242 FS 11 43 112-10 11249 AM43A 67 11266 112-11 Inlet 112-146 112-147 112-59 FL1 112-58 112-148 12-149 11261 11240 u 112-137 112-152 Pl 112-u u 112 62 63 1 12-153 BA-G-3 112-154'l 1244 11245 u u 112-161 11248 11244 FGV 112-91 112-137 112-163 112-134 BR G-3 PS2 11 4i 11-135 1'l2-135 112-139 112-138 112-140 FS 112-94 Fl 11246 Tritium V/Pl 11245 12-158 q 112-156 112-155 112-142 l12-141 112-22 FL3 112-20 112.21 11240 112-159 112-'157 112-3 112-19 112-1 12 112.14 112.18 11249 112-70 112-15 12-1 112-12 11247 11248 Fi ure D-12 OGESMS Schematic NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 1 OFFSITE DOSE CALC.MANUAL 129-  
&E w'4 I ill a~otal C V'I IO ISOKINETIC PROBE RN 21 11241 RAG EMS RAGEMS Ditution Return 112-52 112-131]Sample Return Drain 112-55 11243 112-132 112.57 OGESMS Intet 112.30 112-56 112-133 OGESMS Outtet Figure D-9 Stack Sample and Sample Return NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 1 OFFSlTE DOSE CALC.MANUAL 126-S lit F'~~J tel RAG EMS inlet OVS 112-173 OV3 112-169 OV2 112-167 PCV 112-106 112-110 Ne Supply OV8 112-178 1 2-1 Pl 112-21 OV4 112-171 OFS1 112-101A C 112.130 112-51 OV1 OV13 112-165 t 1248 RAG EMS Dilution Inlet OFC4 112-104 OFS4 112-04A PCV 112-107 OFC1 112-101 112-111 Pl 11-122 OFC3 112-103 OFS3 112-103A 112-116 OCF2 112-102 OFS2 112-102A 112-151 OV16 112-150 112-112 Pl"11-23 OV12 Senlpte 112+7 Return RAG EMS Outlet 112-113 Pl 112-24 112-117 112-118 OP2 OP1 OV6 112-175 Figure 0-1 0 11-44 RAGEMS Dilution Schematic NIAGARA MOHAWK POWER CORPORATION NINE MlLE POINT-UNIT 1 OFF SITE DOSE CALC.MANUAL 127 IP'~)~ir 14 gl g 112-114 1FS1 112-129 Pl 112-125 1V3 1V4 112-183 112-185,'V3 2V4 112-199 112-201 3V3 112.7 3V16 112-218 3V 112-96 Qalhn2 Tritium 112-73 112-72 112-74 3FS1 112-105A 1V1 112-1 1V2 12-'I81 2VI 112-195 2 112-197 3VI 3VS 112 3 3 2.77 6 Uter-95 112-99.75 Pl 112-126 3GVI 112-105 1V5 112-186 1V6 2VS 112-187 112-202 2V6 112-203 2V11 112-208 11 76 I-78 3 3 3V4 112.98 112-119 3V6 3V7 112-100 112-211 Pl 11247 1V11 112-192 Pl 11244 1V17 11249 3V11 112-215 3VI 112-217'l12-108 3PI 3VIO 112-21 I 3VI2 112-109 112-216 Fi Ure D-11 RAGEMS Schematic NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 1 OFFSITE DOSE CALC.MANUAL 128 P+A.J a tA t'a'~<<a 1 0 11242 FS 11 43 112-10 11249 AM43A 67 11266 112-11 Inlet 112-146 112-147 112-59 FL1 112-58 112-148 12-149 11261 11240 u 112-137 112-152 Pl 112-u u 112 62 63 1 12-153 BA-G-3 112-154'l 1244 11245 u u 112-161 11248 11244 FGV 112-91 112-137 112-163 112-134 BR G-3 PS2 11 4i 11-135 1'l2-135 112-139 112-138 112-140 FS 112-94 Fl 11246 Tritium V/Pl 11245 12-158 q 112-156 112-155 112-142 l12-141 112-22 FL3 112-20 112.21 11240 112-159 112-'157 112-3 112-19 112-1 12 112.14 112.18 11249 112-70 112-15 12-1 112-12 11247 11248 Fi ure D-12 OGESMS Schematic NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 1 OFFSITE DOSE CALC.MANUAL 129-  
'1 y l,ll if~8 J A N M P I T N SUPERSKOEQ Ol4 REPLICA General Superintendent Nuclear Generation K.A.Dahlberg for L.Will 1 s 3 1 1,2,5,6,8,9,11-13,15-18, 36-44,47-49, 52-63,65-76,79-81,86-116 3,4,7,10,14,20,23 27-28,30-35 45,46,50,51,82-85
'1 y l,ll if~8 J A N M P I T N SUPERSKOEQ Ol4 REPLICA General Superintendent Nuclear Generation K.A.Dahlberg for L.Will 1 s 3 1 1,2,5,6,8,9,11-13,15-18, 36-44,47-49, 52-63,65-76,79-81,86-116 3,4,7,10,14,20,23 27-28,30-35 45,46,50,51,82-85
*29*64,77,78 i,19,21,22A,22B,24,25 26,112 February 1987 December 1987 January 1988 May 1988 (Reissue)May 27, 1988 (Reissue)February 1990 THIS PROCEDURE NOT TO BE USED AFTER March 1992 SUBJECT TO PERIODIC REVIEW 9PP9110036 e.~l V 1.0 2.0 2~1 INTRODUCTION LIQUID EFFLUENTS Setpoint Determinations 2.1.1 Basis 2.1.2 Service Water System Effluent Alarm Setpoint 2.1.3 2.1.4 Liquid Radwaste Effluent Alarm Setpoint Discussion 2.1.4.1 Control of Liquid Effluent Batch Discharges 2.1.4.2 Simultaneous Discharges of Radioactive Liquids 2.1.4.3 Sample Representativeness 2.1.4.4 Liquid Radwaste System Operation 2.1.4.5 2.2 2.3 2.3.1;3.0 3.1 3.1.1 3.1.2 3.1.'3 3.1.4 3.1.5 3.1.5.1 3.1.5.2 Service Water System Contamination Liquid Effluent Concentration Calculation Dose Determinations Maximum Dose Equivalent Pathway"-GASEOUS EFFLUENTS Setpoint Determinations Basis Stack Monitor Setpoints Recombiner Discharge-(Off Gas)Monitor Setpoints Emergency Condenser Vent Monitor Setpoint Discussion Stack Effluent Monitoring System Description Stack Sample Flow Path-RAGEHS 10 12 12 19 19 19 20 22B I~'3 24 24 3.1.5.3 Stack Sample Flow Path-OGESHS 26  
*29*64,77,78 i,19,21,22A,22B,24,25 26,112 February 1987 December 1987 January 1988 May 1988 (Reissue)May 27, 1988 (Reissue)February 1990 THIS PROCEDURE NOT TO BE USED AFTER March 1992 SUBJECT TO PERIODIC REVIEW 9PP9110036 e.~l V 1.0 2.0 2~1 INTRODUCTION LIQUID EFFLUENTS Setpoint Determinations 2.1.1 Basis 2.1.2 Service Water System Effluent Alarm Setpoint 2.1.3 2.1.4 Liquid Radwaste Effluent Alarm Setpoint Discussion 2.1.4.1 Control of Liquid Effluent Batch Discharges 2.1.4.2 Simultaneous Discharges of Radioactive Liquids 2.1.4.3 Sample Representativeness 2.1.4.4 Liquid Radwaste System Operation 2.1.4.5 2.2 2.3 2.3.1;3.0 3.1 3.1.1 3.1.2 3.1.'3 3.1.4 3.1.5 3.1.5.1 3.1.5.2 Service Water System Contamination Liquid Effluent Concentration Calculation Dose Determinations Maximum Dose Equivalent Pathway"-GASEOUS EFFLUENTS Setpoint Determinations Basis Stack Monitor Setpoints Recombiner Discharge-(Off Gas)Monitor Setpoints Emergency Condenser Vent Monitor Setpoint Discussion Stack Effluent Monitoring
 
===System Description===
Stack Sample Flow Path-RAGEHS 10 12 12 19 19 19 20 22B I~'3 24 24 3.1.5.3 Stack Sample Flow Path-OGESHS 26  
/j W'-7 4 v v~, lk l r~P~I h 4".II<OA TAB F T (Cont'd)3,1.5.4 Sample Frequency/Sample Analysis 3.1.5.5 I-133 Estimates 3.1.5.6 Gaseous Radwaste Treatment System Operation 27 27, 28 3.2 3.2.1 Dose and Dose.Rate Determination Dose Rate 29 31 3.2.1.1 Noble Gases 3.2.1.2 Tritium, Iodines and Particulates
/j W'-7 4 v v~, lk l r~P~I h 4".II<OA TAB F T (Cont'd)3,1.5.4 Sample Frequency/Sample Analysis 3.1.5.5 I-133 Estimates 3.1.5.6 Gaseous Radwaste Treatment System Operation 27 27, 28 3.2 3.2.1 Dose and Dose.Rate Determination Dose Rate 29 31 3.2.1.1 Noble Gases 3.2.1.2 Tritium, Iodines and Particulates
'3.'2.2 Dose 3.2.2.1 Noble Gas Air Dose 3.2.2.2 Radioiodine, Tritium and Particulates 3.2.2.3 Accumulating Doses 3.3-" Critical Receptors 32 32 34 34 36 37 38 3.4 4.0 4.1 4.2 4.3'.4 5.0 5.1 5.2 5.3 Refinement of Offsite Doses Resulting From Emergency Condenser Vent Releases 40 CFR 190 REQUIREMENTS
'3.'2.2 Dose 3.2.2.1 Noble Gas Air Dose 3.2.2.2 Radioiodine, Tritium and Particulates 3.2.2.3 Accumulating Doses 3.3-" Critical Receptors 32 32 34 34 36 37 38 3.4 4.0 4.1 4.2 4.3'.4 5.0 5.1 5.2 5.3 Refinement of Offsite Doses Resulting From Emergency Condenser Vent Releases 40 CFR 190 REQUIREMENTS
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====3.1.5 Discussion====
====3.1.5 Discussion====
3.1.5.1 Stack Effluent Monitoring System Description The NMP-1 Stack'Effluent Monitoring System consists of two-subsystems; the Radioactive Gaseous Effluent Monitoring System (RAGEHS)and the old General Electric Stack Monitoring System-(OGESHS).During normal operation, the OGESHS shall be used to monitor station noble gas effluents and collect particulate and iodine samples in compliance with Technical Specification
3.1.5.1 Stack Effluent Monitoring
 
===System Description===
The NMP-1 Stack'Effluent Monitoring System consists of two-subsystems; the Radioactive Gaseous Effluent Monitoring System (RAGEHS)and the old General Electric Stack Monitoring System-(OGESHS).During normal operation, the OGESHS shall be used to monitor station noble gas effluents and collect particulate and iodine samples in compliance with Technical Specification
,.requirements.
,.requirements.
The RAGEHS is des1gned to be promptly activated from the Main Control Room for use in high range monitoring during acc1dent situations in compliance with,NUREG 0737.crtter1a.Overall system schematic for the OGESHS and RAGEHS are shown on Figure S-9.A simplified view of RAGEHS Showing Unit 0, 1, 2, 3 and 4 can be found on Figure S-8.'''he'AGEHS can provide continuous accident monitor1ng and on-line isotopic analysis of NMP-1 stack effluent noble gases at Lower Levels of Detection less than Technical Specificat1on Table 4.6.15-2 lim1ts..Activities as low as 5 X 10 and as h1gh as 2-X 10 pCi/cc for noble gases are detectable by the'system.
The RAGEHS is des1gned to be promptly activated from the Main Control Room for use in high range monitoring during acc1dent situations in compliance with,NUREG 0737.crtter1a.Overall system schematic for the OGESHS and RAGEHS are shown on Figure S-9.A simplified view of RAGEHS Showing Unit 0, 1, 2, 3 and 4 can be found on Figure S-8.'''he'AGEHS can provide continuous accident monitor1ng and on-line isotopic analysis of NMP-1 stack effluent noble gases at Lower Levels of Detection less than Technical Specificat1on Table 4.6.15-2 lim1ts..Activities as low as 5 X 10 and as h1gh as 2-X 10 pCi/cc for noble gases are detectable by the'system.

Revision as of 04:43, 9 September 2018

Forwards Semiannual Radioactive Effluent Release Rept Jan- June 1990 & Revs 6-8 to Odcm. Radioactive Effluent Release Rept Includes Summary of Liquid,Gaseous & Solid Effluents & Justification for Revs to ODCM
ML18038A323
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 08/30/1990
From: FIRLIT J F
NIAGARA MOHAWK POWER CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17056A964 List:
References
NMP67505, NUDOCS 9009110036
Download: ML18038A323 (513)
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Text

ACCELERATED DISTSJBUTION DEMONSTFWTION SYSTEM REGULATOR INFORMATION DZSTRIBUTZONeSTEM (RIDE)/~, ACCESSION NBR:9009110036 DOC.DATE: 90/08/30 NOTARIZED:

NO DOCKET FACIL:50-220 Nine Mile Point Nuclear Station, Unit 1, Niagara Powe 05 00220 AUTH.NAME AUTHOR AFFILIATION FIRLITFJ.F.

Niagara Mohawk Power Corp.RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Forwards"Semiannual Radioactive Effluent Release Rept for Jan-June 1990"&Rev 6-8 of ODCM.I DISTRIBUTION CODE: ZE48D COPIES RECEIVED:LTR

)ENCL g SIZE: 4'f TITLE: 50.36a(a)(2)

Semiannual Effluent Release Reports NOTES: RECIPIENT ID CODE/NAME PD1-1 LA MARTIN,R.INTERNAL: ACRS TECH ADV RE~01 RGN1 DRSS/RPB EXTERNAL: BNL TICHLER,J03 NRC PDR COPIES LTTR ENCL 1 11 1 2 2 1 1 1 1 RECIPIENT ID CODE/NAME PD1-1 PD AEOD/DSP/TPAB NRR/DREP/PRPB11 RES BROOKS,B RGN1 FILE 02 EG&G SIMPSON,F COPIES LTTR ENCL 1 1 1 1 2 2 1 1 1 1 2 2 D D D NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WAS'ONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LINIS FOR DOCUMENTS YOU DON'T NEED!D D TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL

'v" gg~sw r~0 L Ir f*(4) i4 NINE MILE POINT NUCLEAR STATION/P.O.

BOX 32, LYCOMING, N.Y.13093/TELEPHONE (315)343-2110 August 30, 1990 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 RE: Nine Mile Point Unit g1 Docket No.50-220 DPR-63 Gentlemen:

In conformance with the Nine Mile Point Nuclear Station Unit gl Techni~cal Specifications, we are enclosing the Semi-Annual Radioactive Effluent Release Re ort for the period January 1, 1990, through June 30, 1990.Included in this report is a summary of liquid, gaseous and solid effluents released from the station during the reporting period (Tables 1-3), a description of and justification for recent revisions to the Offsite Dose Calculation Manual (ODCM)(Table 4), an explanation as to the cause and corrective actions regarding the inoperability of any Station Liquid and/or Gaseous Effluent Monitoring instrumentation (Table 5, and Attachment 1), a description of recent revisions to the Process Control Program (PCP)(Table 6), and an update of actual data for the month of December used in the fourth quarter of the July-December 1989 Semi-Annual Radioactive Effluent Release Report (Table 7).Copies of revision 6, 7 and 8 of the Unit 1 ODCM and required technical review documentation are also enclosed.I The format used for the effluent data is outlined in Appendix B of Regulatory Guide 1.21, Revision 1.Dose assessments were made in ,accordance with the NMP-1 Off-Site Dose Calculation Manual.Distribution is in accordance with Regulatory Guide'0.1, 10CFR50.4 (b)(1)and the Technical Specifications.

If you have any questions concerning the attached report, please contact Gary Corell, Chemistry Unit Supervisor, at Nine Mile Point Unit 1 (315)349-2070.Very truly yours, 900911003b 900830 PDR ADQCN, 05000220 R PNU JFF/lmc Enclosures (3 copies)oseph F Firlit Vice President-Nuclear Generation I~r t , Page 2 U.S.Nuclear Regulatory Commission August 30, 1990 xc: Director, Office of Nuclear Reactor Regulation (1)Director, Office of Inspection and Enforcement (1)Mr.Thomas T.Martin, Regional Administrator, United States Nuclear Regulatory Commission, Region I, Allendale Rd., King of Prussia, Pennsylvania 19406 (1)NRC Resident Inspector, Nine Mile Point Nuclear Station Unit 51 (1)New York State Energy Office, 2 Rockefeller Plaza, Albany, NY 12223 Attn: Ms.Donna Ross OFF-SITE DOSE CALCULATION MANUAL NINE MILE POINT UNIT.1

~v r"<<.J'qw(,W~Pg ODCH-NINE MILE POINT UNIT 1 TABLE OF CONTENTS

1.0 INTRODUCTION

2.0 LIQUID EFFLUENTS 2.1 Setpoint Determinations 2.1.1 Basis 2.1.2 Service Water System Effluent Alarm Setpoint 2.1.3 Liquid Radwaste Effluent Alarm Setpoint 2.1.4 Discussion 2.1.4.1 Control of Liquid Effluent Batch Discharges

'::2:1-'."4:2'>.Simultaneous:

Discharges.of'Radioactive Liquids 2.1.4.3 Sample Representativeness 2.1.4.4 Liquid Radwaste System Operation 2.1.4.5 Service Water System Contamination

'.2-'iquid Effluent Concentration Calculation

~Pa e~-10 2.3 2.3.1 3.0 3.1 3.1.1 3.1.2 3.1.3 Dose Determinations Maximum Dose Equivalent Pathway GASEOUS EFFLUENTS'Setpoint Determinations Basis Stack Monitor Setpoints Recombiner.

Discharge (Off Gas)Monitor Setpoints 12 12 17 17 17 18 21 3.1.4 Emergency Condenser Vent Monitor Setpoint 22 3.1.5 3.1.5.1 3.1.5.2 Discussion Stack Effluent Monitoring

System Description

Stack.Sample Flow Path-RAGEHS 23 23.3.1.5.3.Stack Sample Flow Path-OGESHS 25 Ae, f/f,i I 4)"4'pa't k W ODCM-NINE MILE POINT UNIT 1 TABLE OF CONTENTS (Cont'd)3.1.5.4-Sample Frequency/Sample Analysis=3.1.5.5 I-133 Estimates 3,1.5.6 Gaseous Radwaste Treatment System Operation~Pa e 26 27 27 3.2 3.2.1 Dose and Dose Rate Determination Dose Rate 28 31 3.2.1.1 Noble Gases 3.2.1.2 Tritium, Iodines and Particulates 31 33 3.2.2 Dose 35 3.2.2.1 Noble Gas Air Dose 3.2.2.2 Tritium Iodines and Particulates 3.2.2.3 Accumulating Doses 36 37 38 3.3 Critical Receptors 39 e 4.O 4.1 40 CFR 190 REQUIREMENTS Evaluation of Doses From Liquid Effluents 3.4 Refinement of Offsite Doses Resulting From Emergency Condenser Vent Releases 41 42 4.2'.3 4.4 5.0 5.1 5.2 5.3 Evaluation of Doses From Gaseous Effluents i Evaluation" of Doses From Direct Radiation Doses to Members of the Public Nithin the Site Boundary ENVIRONMENTAL MONITORING PROGRAM Sampling Stations Interlaboratory Comparison Program Capabilities for Thermoluminescent Dosimeters Used for Environmental Measurements.

48 48 49 53 55 56

<<Y I U, L'b4Qtg I ODCH-NINE MILE POINT UNIT 1 TABLE OF CONTENTS (Cont'd)~Pa e Table l-l Average Energy Per Disintegration Tables 2-1 Aiat Values for the NMP-1 Facility to 2-8 Table 3-1 Critical Receptor-Dispersion Parameters for Ground.Level and Elevated Releases Table 3-2 Gamma Air and Hhole Body Plume Shine Dose Factors for Noble Gases (Bi and Vi)Table 3-3 Immersion Dose Factors for Noble Gases Tables 3-4'to 3-22">>Organ Dose and Dose Rate Factors (Ri)Table 5-1 NMP-1 Radiological Environmental Monitoring Program Sampling Locations Figure 5.1-1 Nine Mile'oint On-S/te Hap Figure 5.1-2.Nine Mile Point Offsite Hap 59 60.68 69 70 71 90 94 95 Appendix A Liquid Dose Factor Derivation (Aiat)Appendix B Plume Shine Dose Factor Derivation (Bi and Vi)...Appendix C.Organ Dose and Dose Rate Factors for Iodine-131 and 133, Particulates and Tritium Derivation (Ri)Appendix D Diagrams of Liquid and Gaseous Radwaste Treatment Systems 97 100 104 115 l>d I 1 a

1.0 INTRODUCTION

'he Offsite Dose Calculation Manual (ODCM)provides the methodology to be used for demonstrating compliance with the Radiological Effluent Technical Specifications (RETS), 10 CFR 20, 10 CFR 50, and 40 CFR 190.The contents of the ODCM are based-on.,Draft NUREG-0472, Revision 3,"Standard Radiological

'Effluent Technical;Specifications for Pressurized Hater...Reactors,"'September 1982;DraftNUREG-0473, Revision 2."Radiological Effluent Technical Specifications for BNR's","July 1979;NUREG 0133,"Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978;the several Regulatory Guides referenced in these documents; and, communication with the NRC staff.Section 5 contains a detailed description of the Radiological

.Environmental Monitoring,(REM) sampling locations.

Should it be necessary to revise the ODCM, these revisions wi 11 be made in accordance with Technical Specifications.

'p I t I'0 I IH g 2.0 LIQUID EFFLUENTS 2.1 Setpoint Determinations 2.1.1 Basis Monitor setpoints will be established such that the concentration of radionuclides in the liquid effluent releases in the discharge canal will not exceed those concentrations as-specified in 10 CFR 20, Appendix 8, Table II, Column 2.Setpoints for the Service Hater System Effluent Line will be calculated quarterly based on the radionuclides identified during the previous year's releases from the liquid radwaste system or the isotopes identified in the most recent radwaste I release or other identified probable source.Setpoints for the Liquid Radwaste Effluent Line will be based on the radionuclides identified in each batch of liquid waste prior to its release.After release, the Liquid Radwaste monitor setpoint may remain as set, or revert back to a setpoint based on a previous<;-Semi-Annual, Radioactive Effluent Release Report, or install blank flange in the discharge line and declare inoperable in accordance with the technical specification.

Since the Service Hater System effluent monitor and Liquid Radwaste effluent monitor can only detect gamma radiation, the.alarm setpoints are calculated by using the concentration of gamma emitting isotopes only (or the corresponding MPC values for the same isotopes, whichever are higher)in the X>(uC1/mi)i>

expression (Section 2.1.2, 2.1.3).

0 kj'-, l IPh'L Ill 4 v'h (\~T~t.+f I+y 4g~~~q+~f Ca l44 2.1.1 (Cont'd)The Required Dilution Factor is calculated using concentrations of all isotopes present (or the corresponding HPC values for-the same isotopes, whichever are higher)including tritium and'other non-gamma emi tters to ensure that all radionuclides in the discharge canal do not exceed 10 CFR 20 limits~2.1.2.::-Service Water System Effluent Line Alarm Setpoint The detailed methods for establishing setpoints for the Service Water System Effluent Line Monitor shall be contained in the Nine Mile Point Station Procedures.

These methods shall be in accordance with the following:

~Setpoint (Hi alarm)<0.9 Setpoint (Alert alarm)<6.7 (uC1/m1>sy

<CF)l TDF/Fsw 2-[(uCi/ml)iT/MPCi]

il (UCi/ml)i~(CF)TOF/Fsw Z;[(uCi/ml)iT/HPCi]

+background

+background (uCi/ml)ig concentration of gamma emitting isotope i in the sample, or the.."-.-'corresponding MPC of, gamma emitting isotope i (HPC)ig , whichever is higher (units uCi/ml).(uCt/ml)iT concentration of any radioactive isotope i in the sample including tritium and other non-gamma emitters or corresponding MPC of isotope i, MPCi, whichever is higher (units uCi/ml).'OF.'Total Oilution Flow (units gallons/min)

Fsw CF HPCi Service Water Flow (units gallons/min) monitor calibration factor (units net cpm/uCi/ml) liquid effluent radioactivity concentrations limit for radionuclide i as specified in 10 CFR 20, Appendix B, Table II, Column 2.

4<<~6 5~1q~~

2.1.2 (Cont'd)Sample (MPC)i 0.9 and 0.7[(uCi/ml)iT/MPCi]

TDF/Fsw Those nuclides present in the previous batch release from the liquid radwaste effluent system or those nuclides present in the last Semi-annual Radioactive Effluent Release Report (units uCi/ml)or those nuclides present in the service water system.**same as MPCi but for gamma emitting nuclides only.factors of conservatism to account for inaccuracies.

Required Dilution Factor.If MPC values are used in the Z(uCi/ml)i y, they must also be used in calculating ROF (numerator).

Actual Dilution Factor 2.1.3 Liquid Radwaste Effluent Line Alarm Setpoint The;detailed methods for establishing setpoints for the Liquid Radwaste'ffluent Line Monitor shall be contained in the Nine Mile Point Station Procedures.

These methods shall be in accordance with the following:

Setpoint (Hi-Hi alarm)<0.9 (uCi/ml)ig (CF)Setpoint (Hi alarm)<0.7 (uCi/ml)ig (CF)TDF/Fre[(uCi/ml)iT/MPC

]TDF/Fre Z;[(uCi/ml)iT/HPCi]

background

+background (uCi/ml)i y concentration of gamma emitting isotope i in the sample or , the corresponding MPC of gamma emitting isotope i (HPC)i." whichever is higher.(uCi/ml)iT concentration of any radioactive isotope i in the sample including tritium and other non-gamma emitters or the corresponding HPC of isotope i HPCi whichever is high'er.(units uCi/ml)TDF Fre CF Total Dilution Flow (units gallons/min).Radwaste Effluent Flow (units gallons/min) monitor calibration factor (units net cps/uCi/ml)

    • For periods with known reactor water to RCLC system leakage, RCLC maximum permissible concentration may be prudently substituted for the above.

4.C(I Mpci (HPC)i.0.9 and 0.7 liquid effluent radioactivity concentration limit for radionuclide i as specified in 10 CFR 20, Appendix B, Table II, Column 2, for those nuclides detected by spectral analysis of the contents of the radwaste tanks to be released.(units uCi/ml)same as HPCi but for gamma emitting nuclide only.factors of conservatism to account for inaccuracies.

X;[(uCi/ml)iT/HPCi]

Required Dilution Factor.If HPC values are used in the X (uCi/ml)ix', they must also be used in calculating RDF (numerator).

Notes:(a)If TDF/Fre gf(uCi/ml)iT/MPCi]

the discharge could not be made, since the monitor would be continuously in alarm.To avoid this situation, F will be reduced (normally by a factor of 2)to allow setting the alarm point at a concentration higher than tank concentration.

Thi's.wil.l also'result in a discharge canal concentration at approximately 50K maximum permissible concentration.(b)The value used for TDF will be reduced by the fractional quantity (1-FT),.where FT is,tempering fraction (i.e., diversion of some fraction of discharge flow to the intake canal for the purpose of temperature control).

8+4%II'tr f~x.C'

2.1.4 Discussion

2.1.4.1 Control of Liquid Effluent Batch Discharges At Nine Mile Point Unit 1 Liquid Radwaste Effluents are released only'n a batch mode.To prevent the inadvertent release of any liquid radwaste effluents, radwaste discharge is mechanically isolated (blank flange installed or discharge valve chain-locked closed)following the completion of a batch release or series of batch releases., This mechanical isolation remains in place and will only be removed prior to the next series of liquid radwaste discharges after all analyses required in station procedures and Technical Specification Table 4.6.15-1A are performed and monitor setpoints have been properly ad]usted.2.1.4.2 Simultaneous Discharges of Radioactive Liquids..'<<"If.during the discharge of any liquid radwaste batch, there is an indication that the service water canal has become contaminated (through a service water monitor alarm or through a grab sample analysis in the event that the service water monitor is inoperable) the discharge shall be.terminated immediately.

The liquid radwaste discharge shall not be continued until the cause of the service water alarm (or high grab sample analysis result)has been determined and the appropriate corrective measures taken to ensure 10CFR20, Appendix 8, Table II, Column 2 (Technical Specification Section 3.6.15.a(1))

limits are not exceeded.

ALi/A~

2.1.4.3 Sampling Representativeness This section covers Technical Specification Table 4.6.15-1 Note b concerning thoroughly mixing'f each batch of liquid radwaste prior to sampling.Liquid Radwaste Tanks scheduled for discharge at Nine Mile Point Unit 1 are'isolated (i.e;inlet valves:marked up)and.-at.least two , tank volumes of entrained fluids are recirculated prior to sampling.Minimum recirculation time is calculated as follows:-Minimum Recirculation Time 2.0(T/R)Hhere: 2.0 Plant established mixing factor, unitless Tank volume, gal Recirculation flow rate, gpm.Additionally.

the Hi Alarm setpoint of the Liquid Radwaste Effluent Radiation Monitor is set at a value corresponding to not more than--""'.70'L of-~its calculated response to the grab sample or corresponding MPC values.Thus, this radiation monitor will alarm if the grab sample, or corresponding MPC value, is significantly lower in activity than any part of the tank contents being discharged.

IWl*A'I O'"S~'o ma gr~'P(~,,~~~~i~)r+

k'g4>i'I 2.1.4.4 Liquid Radwaste Systems Operation Technical Specification 3.6.16.a requires that the liquid radwaste system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge, as necessary, to meet the concentration and dose requirements of Technical Specification 3.6.15.Utilization of-the radwaste"system will be based on the capability of the indicated components of each process system to process contents of the respective low conductivity and high conductivity collection tanks: 1)Low Conductivity (Equipment Drains): Radwaste Filter and Radwaste Demin.(See Fig.B-1)2)High Conductivity (Floor Drains): Haste Evaporator (see Fig.B-1)Cumulative dose contributions from liquid effluents for the current l-'alendar'quarter and the current calendar year shall be determined as described in Section 2.3 of this manual prior to the release of each batch of liquid waste.This same dose pro]ection of Section 2.3 will also be performed in the event that untreated liquid waste is.discharged, to ensure that.the dose limits'of.Technical Specification 3.6.15.a(2) are not exceeded.(Thereby implementing the requirements of 10CFR50.36a, General Design Criteria 60 of Appendix A and the Design Ob)ective given in Section II-D of Appendix I to 10 CFR50).

~P 1"J~W+

2.1.4.4 (Cont'd)For the purpose of dose pro]ection, the following assumptions shall be made with regard to-concentrations of non-gamma emitting radionuclides subsequently analyzed off-site: a)[H-3]>H-3 Concentration found recent condensate storage tank analysis.b)[Sr-89]>4 x Cs-137 Concentration c)[Sr-90]>0.5 x Cs-137 Concentration d)[Fe-55]>1 x Co-60 Concentration Assumed Scaling Factors used in b, c, and d above represent conservative estimates derived from analysis of historical data from process waste streams.Following receipt of off-site H-3, Sr-89, Sr-90 and Fe-55 analysis information, dose estimates shall be revised---using actual radionuclide concentrations and actual tank volumes discharged.

F p, cyb)}I', t'i ,j>p<, pgb~iwp4'"r

If contamination is suspected, as indicated by a.significant increase in service water effluent monitor response, grab samples will be obtained from the service water discharge lines and a gamma isotopic analysis meeting the LLO requirements of Technical Specification Table 4.6.15-1 completed.

If it-'is-determined.

that an inadvertent radioactive discharge is occurring from the service water system, then: a)A 50.59 safety evaluation shall be performed (ref.IEE Bulletin 80-10), b)Oaily service water effluent samples shall be taken and analyzed for principal gamma emitters until the release is terminated, c)An incident composite shall be prepared for H-'3, gross alpha, Sr-89, Sr-90 and Fe-55 analyses and I-'d)" Oose projections shall be performed.in accordance with Section 2.3 of this manual (using estimated concentrations for H-3, Sr-89, Sr-90 and Fe-55 to be conservatively determined by supervision at the time of the incident).

Additionally, service water effluent monitor setpoints may be recalculated using the actual distribution of isotopes found from sample analysis.

1 I~L g C 4 t*'A tt t E I'E 2.2 Liquid Effluent Concentration Calculation This calculation documents compliance with Technical Specification Section 3.6.1.5.a (1).The concentration of radioactive material released in liquid effluents to unrestricted areas (see Figure B-7)shall be limited to the'concentrations specified in 10CFR20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained noble gases.For dissolved or entrained noble gases, the concentration shall be limited to 2 E-4 microcurie/milliliter (uCi/ml)total activity.The concentration of radioactivity from Liquid Radwaste batch releases and, if applicable, Service Hater System and emergency condenser start-up vent discharges are included in the calculation.

The calculation is performed for a specific period of time.No credit taken for averaging over the calendar year as permitted by 10CFR20.106.

The limiting concentration is calculated as follows:~PC Fr ti" 11<~s((" i/ml)is*Fs)/(P i*Z s(Fs Hhere: HPC Fraction The limiting concentration of 10 CFR 20, Appendix 8, Table II, for radionuclides other than dissolved or entrained noble gases.For noble gases, the concentration shall be limited to 2 E-4 microcurie/ml total activity.

IV@.1,, S'Ilk Wih~pter t I.g k A~~

2.2 (Cont'd)(uCi/ml)i The concentration of nuclide i in particular is effluent stream s, uCi/ml.F The flow rate of a particular effluent stream s, gpm.MPCi The limiting concentration of a specific nuclide i from.'10CFR20, Appendix b, Table-II, Column 2 (noble gas limit is 2E-4 uCi/ml)X ((uCi/ml)i

  • F)The total activity rate of nuclide i, in all effluent streams s, uCi/ml*gpm

$(F)".The total flow rate of all effluent streams s, gpm (including those streams which do not contain radioactivity).

A value of less than one for MPC fraction is considered acceptable for compliance with Technical Specification Section 3.6.15.a.(1).

2.3 Dose Determination

-,2.3.1, Maximum Dose Equivalent Pathway A dose assessment report was prepared for the Nine Mile Point Unit 1 facility by Charles T.Main, Inc., of Boston, MA.This report presented the calculated dose equivalent rates to individuals as well , as the.,population within a 50-mile radius of the facility based on the radionuclides released in-liquid.and=gaseous effluents-during.

the time periods of 1 July 1980 through 31 December 1980 and from January 1981 through 31 December 1981;The radwaste liquid'releases are based on a canal di.scharge rate of 590 ft/sec which affects near field and far field dilution;therefore, this report is specific to this.situation.

Utilizing the effluent data contained in the 12 r P A g4J<7 2.3.1 (Cont'd)Semi-Annual Radioactive Effluent Release Reports as source terms, dose equivalent rates were determined using the environmental pathway models specified in Regulatory Guides 1.109 and 1.111 as incorporated in the NRC computer codes LADTAP for liquid pathways, and XOQDOQ and GASPAR for gaseous effluent pathways.Dose equivalent rates were-calculated for the'total'ody as well as seven organs and/or tissues---

for the adult, teen, child, and infant age groups.From the standpoint of liquid effluents, the pathways evaluated included fish and drinking water ingestion, and external exposure to water and sediment.The majority of the dose for a radwaste liquid batch release was received via the fish pathway.However, to comply with Technical Specifications for dose projections, the drinking water and sediment pathways are included.Therefore, all doses due to-liquid effluents are calculated monthly for the fish and drinking water ingestion pathways and the sediment external pathway from all detected nuclides"<<in liquid effluents released to the unrestricted areas to each organ.The dose projection for liquid batch releases will also include discharges from the emergency condenser vent as applicable, for all pathways.Each age group dose factor, Ai t, is given intables 1-1 to 1-8.To expeditetime the, dose is calculated for a maximum individual instead of each age group.This maximum individual will be a composite of the highest dose factor of each age group for each organ, hence Ait.The following expression from NUREG 0133, Section 4.3 is used to calculate dose: Dt gi[Alt$1(dT1CilF1)]

13

  • W~h II+'I gc~4.

2.3.1 (Cont'd)Nhere: Ot The cumulative dose commitment to the total body or any organ, from the liquid effluents for the total time period (dT1), mrem dT1 The length of the 1 th time period over which Cil and Fl are averaged for all liquid releases, hours Cil The average concentration of radionuclide, i, in undiluted liquid effluents during time period dT1 from any liquid release, uCi/ml Ait The site related ingestion dose commitment factor to the total body or any organ t for each identified principal gamma or beta emitter for a maximum individual, mrem/hr per uCi/ml Fl The near field average dilution factor for Cil during any liquid effluent release.Defined as the ratio of the maximum undiluted liquid waste flow during release to the.average flow from the site discharge structure to unrestricted receiving waters, unitless.Ai t values for radwaste liquid batch releases at a discharge rate of 295 ft/sec (one circulating water pump in operation) are presented in table's 1-1 to 1-4.Ai t values for an emergency iat condenser vent release are presented in tables 1-5 to 1-8.The'mergency condenser vent releases are assumed to travel to the perimeter drain system and released from the discharge structure at a rate of.33 ft/sec.See Appendix A for the dose factor Ai t 3 derivation.

To expedite time the dose is calculated to a maximum individual.

This maximum individual is a;composite'of-the highest-." dose factor Ai t of each age group a for each organ t and each nuclide i.If a nuclide"is detected for which a factor is not listed, then it will be calculated and included in a revision to the OOCN.

f 0 i~i 4 , e+$'a,,C'(<>>5 Y" ztl$'~,

2.3.1 (cont'd)All doses calculated in this manner for each batch of liquid effluent will be summed for comparison with quarterly and annual limits, added to the doses accumulated from other releases in the quarter and year of interest.In all cases, the following relationships will hold: For a calendar quarter: 0t<1.5 mrem total body 0<5 mrem for any organ For the calendar year: Ot<.3.0 mrem total body 0t<10 mrem for any organ-"<~where 0'otal;dose received due to liquid effluent releases to the total body or any organ,

+p v Ep1 e 2.3.1 (Cont'd)If these limits are exceeded, a special report will be submitted to-'the NRC identifying.the..cause,and,,proposed corrective actions.In addition, if these limits are exceeded by a factor of two, calculations shall be made to determine if the dose limits contained in 40 CFR 190 have been exceeded.Dose limits, as contained in 40 CFR 190 are total body and organ doses of 25 mrem per year and a thyroid dose of 75 mrem per year.=These calculations will include doses as a result of liquid and gaseous pathways as well as doses from direct radiation.

The liquid pathway analysis will only include the fish and sediment pathways since the drinking water pathway is insignificant.

This pathway is.only included in the.station's effluent dose projections to comply'""with Technical Specifications.

Liquid, gaseous and direct radiation.

pathway doses will consider the James A.FitzPatrick and Nine Mile Point Unit II facilities as well as Nine Mile Point Unit I Nuclear.Station.In the event the calculations demonstrate that the 40 CFR 190 dose limits, as defined above, have been exceeded, then a report shall be prepared and submitted to the Commission within 30 days as specified in Section 3.6.15.d of the Technical Specifications.

I'"",i.'Section, 4.,0'of the ODCM contains more information concerning calculations for an evaluation of whether 40 CFR 190 limits have been exceeded.

I.~0 1 C.a I*)I t1 l'E 3.0 GASEOUS EFFLUENTS 3.1 Setpoint Determinations 3.1.1 Basis~~Stack gas and off gas monitor setpoints will be established such that the instantaneous release rate of radioactive materials in gaseous effluents does not exceed the 10 CFR 20 limits for annual release.rate.The setpoints will be activated if the instantaneous dose rate at or-beyond the (land)site'boundary would.exceed 500 mrem/yr, to.the..whole body or 3000 mrem/yr to the skin from the continuous release of radioactive noble gas in the gaseous effluent.Emergency condenser vent monitor setpoints will be established such"that the release rate for radioactive materials in gaseous effluents do not exceed the 10 CFR 20 limits for annual release rate over the projected longest period of release.Monitor setpoints from continuous release points will be determined once per quarter under normal release rate conditions and will be based on'the'isotopic composition of the actual release in progress, or an offgas isotopic distribution or a more conservative default composition specified in the pertinent procedure.

If the calculated setpoint ts higher than the existing setpoint, it is not mandatory that the setpoint be changed.Monitor setpoints for emergency condenser vent monitors are conservatively fixed at 5 mr/hr for reasons described in Sections 3.1.4 and therefore do not require periodic recalculations.

Under abnormal site release rate conditions, monitor.alarm setpoints.

from continuous release points will be recalculated and, if necessary, reset at more frequent intervals as deemed necessary by.CORM Supervision.

In particular, contributions from both JAF and NMP-2 and the Emergency Condenser Vents shall be assessed: "During outages and until power.operation is again realized, the last operating stack and off gas monitor alarm setpoints shall be used.

k 7i'tZ F<~P 3.1.1 (Cont'd)Since monitors respond to noble gases only, monitor alarm points are set to alarm prior to exceeding the corresponding total body dose'rates.The skin dose rate limit is not used in setpoint calculations because it is never limiting.3.1..2, Stack Monitor Setpoints The detailed methods for establishing setpoints shall be contained in the station procedures.

These methods shall apply the following general criteria: (1)Rationale for Stack monitor settings is based on the general equation: release rate actual corresponding dose rate, actual release rate max.allowable corresponding dose rate, max.allowable ()max 500 mrem/yr where: Vi release rate for each isotope i, uCi/sec gamma'hole body dose factor in units of mrem/yr per uCi/sec (See Table 3-2)(Q)max instantaneous release rate limit uCi/sec 18

+a'v'1~I I Q%ltl 3.1.2 (Cont'd)(2)To ensure that 10 CFR 20 and Technical Specifications dose rate limits are not exceeded, the hi hi alarms on the stack monitors shall be set lower than or equal to (0.9)(Q).Hi alarms max'hall be set lower than or equal to (0.5)(Q)max'3)Based on the above conservatism, the dose contribution from JAF and NMP-2 can usual,ly be ignored..During Emergency Classifications at JAF or NMP-2 due to airborne effluent, or after emergency.condenser vent;releases.of-significant proportions, the 500 mrem/yr value may be reduced accordingly.

(4)To convert monitor gross count rates to uCi/sec release rates, the following general formula shall be app'lied: (C-B)K Q uCi/sec release rate where: 'B Ks Cm monitor gross count rate in cps or cpm;cps counts per second, cpm counts per minute monitor background count rate stack monitor efficiency factor with units of uCi/sec-cps or uCi/sec-cpm (5)Monitor K factors shall be determined using the general formula: K QiQi/(C-8)where: individual radionuclide stack effluent.release rate as determined by isotopic analysis.K factors more conservative than those calculated by the-above methodology may be assumed.-19

,b t'4 r~II 4U 3.1.2 (Cont'd)Alternatively, when stack release rates are near the lower limit of detection, the following general formula may be used.to calculate k: 1/Ks E~(i i~kYkEk)3.7E4d f f'-uCi where: f stack flow in cc/sec E efficiency in units of cpm-cc/uCi or cps-cc/uCi (cpm counts per minute;cps counts per second)Ek cpm-cc/bps or cps-cc/ps From energy calibration curve produced during NBS traceable primary gas calibration or transfer source calibration (bps beta per second;ps gammas per second)Yk b/d (betas/disintegration) or V/d (gammas/d)

Fi Activity fraction of nuclide i in the mixture i nuclide counter k.discrete energy beta or gamma emitter per nuclide counter s i~seconds This monitor calibration method assumes a noble gas distribution typical of a recoil release mechanism.

To ensure that the calculated efficiency is conservative, beta or gamma emissions whose energy is above the range of calibration of the detector are not included in the calculation.

Q}4 3.1.3 Recomb)ner Discharge<Dff Gas)Monitor Setpoints (1)The hi hi alarm points shall activate with recombiner discharge rates equal to or less than 500,000 uCi/sec.This alarm point may be set equal-.to or less than 1 Ci/sec for a period of time I not to exceed 60 days provided the offgas treatment system is in operation.

(2)The hi alarm points shall activate with recombiner discharge rates equal to or less than 500,000 uCi/sec (3)To convert monitor mR/hr readings to uCi/sec, the formula below shall be applied:<R)(KR)QR uCi/sec recombiner discharge release rate"where: R mR/hr monitor indicator KR efficiency factor in units of uCi/sec/mR/hr determined prior to setting monitor alarm points (4)Monitor KR factors shall be determined using the general formula: KR Qi/R where: Qi-individual radionuclide recombiner discharge release rate as determined by isotopic analysis and flow rate monitor.KR factors more conservative than those calculated by the above methodology may be assumed.

J 4 jC I f 4/Qi'la g'I~pp A l 3.1.3 (Cont'd)(5)The setpoints chosen provide assurance that the total body exposure to an individual at the exclusion area boundary will not exceed a very small fraction of the limits of 10CFR Part 100 in the event this effluent is inadvertently discharged directly to the environment without treatment (thereby implementing the requirements of General Oesign Criteria 60 and 64 of Appendix A to 10CFR Part, 50)..Additionally, these setpoints serve to,limit buildup of fission product activity within the station.systems which would result if high fuel leakage were to be permitted over extended periods.3.1.4 Emergency Condenser Vent Honitor Setpoint The monitor setpoint was established by calculation

(" Emergency ,Condenser Vent Honitor Alarm Setpoint", January 13, 1986, NHPC File Code¹'l61*99).

Assuming a hypothetical case with (1)reactor water t iodine concentrations higher than the Technical Specification Limit, (2)reactor water noble gas concentrations higher than would be expected at Technical Specification iodine levels, and (3)leakage of reactor steam into the emergency condenser shell at 300'A of rated flow (or 1.3 E6 lbs/hr), the calculation predicts an emergency condenser vent monitor response of 20 mR/hr.Such a release would result in less than'0 CFR 20.dose rate values at the site boundary and beyond for typical"emergency condenser cooldown periods.Since a 20 mR/hr mon'itor response can, in theory, be achievable only when reactor water iodines are higher than permitted by Technical Specifications, a conservative monitor setpoint of 5 mr/hr has been-adopted.

IIC of~h VWII, a IT WI r'T r~'t.I T l\I T tt I 0

3.1.5 Discussion

3.1.5.1 Stack Effluent Moni tori ng System Description-The NMP-1 Stack'EffluentaMonitoring System consists of two subsystems; the Radioactive Gaseous Effluent Monitoring System (RAGEMS)and the old General Electric Stack Monitoring System (OGESMS).During normal operation, the OGESMS shall be used to monitor station noble'as effluents and collect particulates and iodine samples in compliance with Technical Specification requirements.

The RAGEMS.is designed to be promptly activated from the Main Control" Room for use in high range monitoring during accident situations in compliance with NUREG 0737 criteria.Overall system schematic for the OGESMS and RAGEMS are shown on Figure B-9.A simplified view of RAGEMS Showing Unit 0, 1, 2, 3 and 4 can be found on Figure B-S.The RAGEMS can provide continuous accident monitoring and on-line isotopic analysis of NMP-1 stack effluent noble gases at Lower Levels of Detection less than Technical Specification Table 4.6.15-2 limits.Activities as low as 5.0E-B and as high as 2.0E5 uCi/cc for noble gases are detectable by the system.

i&jan" JP~.0-y~y I I~*'I le t gled bl 4 II 3 T.5.2 Stack Sample flow Path-RAGEHS'" The effluent sample is obtained inside the stack at elevation 530'sing an isokinetic probe with four orifices.The sample line then bends radially out and back into the stack;descends down the stack and out of the stack-at approximately elevation 257';runs horizontally (enclosed in heat tracing)some 270'long the off gas.tunnel;and enters the RAGEHS located on the Turbine Building 250'Dilution cabinet-Unit 0)and Off Gas Building 247'Particulate, Iodine, Noble Gas stations-Units 1-3).'In the'Dilution cabinet'of the RAGEHS, the stack gas may be diluted during accident situations approximately 100-200X (first stage)or 10000-40000 X (first and second stage)with gaseous nitrogen supplied from an on-site liquid nitrogen storage tank (see Figure 8-9).From Unit 0, the sample gas enters Unit 1-3 of RAGEHS and flows thru in-line particulate and iodine cartridges and then thru either a 6 liter (low range)or 30 cc (high range)noble gas chamber.The sample gas next flows back thru Unit 0 and the off gas tunnel;and back into the stack.

I 1+4g VL 4 1 w p fT J'1 S k t I' 3.1.5.3 Stack Sample Flow Path-OGESHS The OGESHS sample is obtained from the same stack sample probe as the RAGEHS.From the exit of the stack at elevation 257', the sample line runs east approximately 20'nd then vertically approximately 8'o the OGESMS skid.In the OGESMS, sample flows thru a particuate/,.iodine cartridge housing and.four noble gas scintillation detectors (i.e..07 and 08 low range-beta detectors and RN-03A and RN-038 high range gamma detectors).

From OGESHS, the stack sample flows back into the stack at approximately elevation 257'.All OGESMS detector outputs are monitored and recorded remotely in the Hain Control Room.Alarming capabilities are provided to alert Operators of high release rate conditions prior to exceeding Technical Specification 3.6.15.b (1)a dose rate limits., Stack particulate and iodine samples are retrieved manually from the OGESMS and analyzed in the laboratory using gamma spectroscopy at frequencies and LLOs specified in Table 4.6.15-2 of the Technical Specifications.

I't I*P't F 3.1.5.4 Sampling Frequency/Sample Analysis Regardless of which stack monitoring subsystem is utilized, radioactive gaseous"wastes.shall be sampled and analyzed in accordance with the sampling and analysis program specified in Technical Specification Table 4.6.15-2.Particulate samples are saved and analyzed for principal gamma emitters, gross alpha, Fe-55, Sr-89, Sr-90 at monthly intervals minimally.

The latter three analyses are performed off-site from a composite sample.Sample analysis frequencies are increased during elevated release rate conditions, following startup, shutdown and in conjunction with each drywell purge.Consistent with Technical Specification Table 4.6.15-2, stack effluent tritium is sampled monthly, during each drywell purge, and.weekly when fuel is off loaded until stable release rates are demonstrated.

Samples are analyzed off-site.Line loss correction factors are applied to all particulate and"*"i ,iodine.results.-Correction factors of 2.0 and 1.5 are used for data obtained from RAGEHS and OGESHS respectively.

These correction factors are based on empirical data from sampling conducted at NHP-1 in 1985 (memo from J.Blasiak to RAGEHS File, 1/6/86,"Stack Sample Representativeness Study: RAGEHS vs.In-Stack Auxiliary Probe Samples").

~k(1 I~'i 3.1.5.5 I-133 Estimates Monthly, the stack effluent shall be sampled for iodines over a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period-and the I-135/I-131,and the I-133/I-131 ratios calculated.

These ratios shall be used to calculate I-133, I-135 release for longer acquisition samples collected during the month.Additionally, the I-135/I-131 and I-133/I-131 ratios should also be determined after a significant change-in the ratio is suspected (eg, plant status changes from prolonged shutdown to power operation or fuel damage has occurred).

3.1.5.6 Gaseous Radwaste Treatment System Operation Technical Specification 3.6.16.b requires that the gaseous radwaste treatment system shall be operable and shall be used to reduce radioactive materials in gaseous waste prior to their discharge as necessary to meet the requirements of Technical Specification 3.6.15.b.To ensure Technical Specification 3.6.15.b limits are not exceeded, and to confirm proper radwaste treatment system operation as applicable, cumulative dose contributions for the current calendar quarter and current calendar year shall be determined monthly in accordance with section 3.2 of this manual.Initial dose calculations shall incorporate.

the following-assumptions with, regard to release rates of non-gamma emitting radionuclides subsequently analyzed off-site:

$l 4 gP">>'"wh'w'N~y'~~

~'oi"pt, 3.1.5.6 (Cont'd)a)H-3 release rate 2 4uCi/sec b)Sr-89 release rate Z 4 x Cs-137 release rate c)Sr-90 release rate Z 0.5 x Cs-137 release rate d)Fe-55 release rate 2 1 x Co-60 release rate Assumed release rates represent conservative estimates derived from analysis of historical data from effluent releases and process waste streams (See NAP 34023, C.Hare to J.Blasiak, April 29, 1988,"Dose Estimates for Beta-Emitting Isotopes").Following receipt of off-site H-3, Sr-89, Sr-90,,Fe-55 analysis information, dose estimates shall be revised using actual radionuclide concentrations.

3.2 Dose and Dose Rate Determinations In accordance with specifications 4.6.15.b.(1), 4.6.15.b.(2), and 4.6.15.b.(3) dose and dose rate determinations will be made monthly to determine:

(1)Total body dose rates and gamma air doses at the maximum X/Q'land sector site boundary interface and beyond.(2)Skin dose rates and beta air doses at the.maximum X/Q land sector site'boundary interface and beyond.(3)The critical organ dose and dose rate at the maximum X/Q land sector site boundary interface and at a critical receptor location beyond the site boundary..

28

'p Ev 3.2 (Cont'd)Average meteorological data (ie, maximum five year annual average X/Q and D/Q values in the case of elevated releases or 1985 annual average X/Q and D/Q values, in the case of ground level releases)shall be utilized for dose and dose rate calculations.

Where average meteorological data is assumed, dose and dose rates due to noble gases at locations beyond the site boundary will be lower than equivalent site boundary dose-and dose rates.Therefore, under these conditions, calculations of noble gas dose and dose rates beyond the maximum X/Q land sector site boundary locations can be neglected.

The frequency of dose rate calculations will be upgraded when elevated release rate conditions specified in subsequent sections 3.2.1.1 and 3.2.1.2 are realized.r Emergency condenser vent release contributions to the monthly dose and dose rate determinations will be considered only when the emergency condenser return isolation valves have been opened for reactor cooldown or if Emergency Condenser tube leaks develop with or without the system's return isolation valve opened.Without tube leakage or opening of the return isolation valves, releases from this system are negligible and the corresponding dose contributions do not have to be included.I I*me'q<a<~"<~,q"".'l t F gv, 3.2 (Cont'd)Hhen releases from the emergency condenser have occurred, dose rate and dose determinations shall'be performed using methodology in 3.2.1 and 3.2.2.Furthermore, environmental sampling may also be initiated to refine any actual contribution to doses.See Section 3.4.Critical organ doses.and dose rates may be conservatively calculated..

by assuming.the existence of a maximum individual.

This individual is a composite of the highest dose factor of each age group, for each organ and total body, and each nuclide.It is assumed that all pathways are applicable and the highest X/Q and/or 0/Q value for actual pathways as noted in Table 3-1 are in effect.The maximum individual's dose is equal to the same dose that person would receive if they were simultaneously sub]ected to the highest pathway dose at each critical receptor identified for each pathway.The pathways include grass-(cow and goat)-milk, grass-cow-meat, vegetation, ground plane and inhalation.

To comply with Technical Specifications we will calculate the maximum individual dose rate at the site boundary and"'eyond at the critical residence.

If dose or dose rates calculated, using the assumptions noted above, reach Technical Specification limits, actual pathways will be evaluated, and dose/dose rates shall be calculated at separate critical receptor locations and compared with applicable limits.30 eked AI 6'lt II I, 3.2.1 Dose Rate'ose'rates will be-calculated.

monthly, at a minimum, or when the Hi-Hi stack monitor alarm setpoint is reached, to demonstrate that dose rates resulting from the release of noble gases, tritium, iodines, and particultes with half lives greater than 8 days are'ithin the limits specified in lOCFR.20.These limits are: Noble Gases Hhole Body Dose Rate 500 mrem/yr Skin Dose Rate 3000 mrem/yr Tritium Iodines and Particulates Organ Dose Rate 1500 mrem/yr 3.2.1.1 Noble Gases The following noble gas dose rate equation includes the contribution from the stack (s)elevated release and the emergency condenser vent (v)ground level release when applicable (See.section 3.2).31 P f~

for total body dose rates (mrem/sec):

OR g (mrem/sec)

-3.17E-8 Zi.[ViQi ,+Ki (X/Q)Qi]ii is'v iv For skin dose rates (mrem/sec):

OR~+8(mrem/sec)-

3.17E-8 Zi[(Li(X/Q)s+1.118i)Qis+(Li+1.11Ni)<X/Q)vQiv~

where: OR~total body gamma dose rate (mrem/sec).

OR~+6 skin dose rate from gamma and beta radiation (mrem/sec).

=='he.constant, accounting for the gamma whole body dose rate from stack radiation, for an elevated finite plume releases for each identified noble gas nuclide, i.Listed on Table 3-2 in mrem/yr per uCi/sec..Ki the constant accounting for the gamma whole body dose rate from immersion in the semi-infinite cloud for each identified noble gas nuclide, i.Listed in Table 3-3 in mrem/yr per uCi/m3 (from Reg.Guide 1.109)Qi the release of isotope i;(uCi;s stack, v vent).X/Q-the relative plume concentration

<in units of sec/m3)at the land sector site boundary or beyond.'Average meteorological data (Table 3-1)is used.'"Elevated" X/Q values are used for stack releases (s",'stack);"Ground" X/Q values are used for Emergency Condenser Vent releases (v vent).the constant accounting for the beta skin dose rate from immersion in the semi-infinite cloud for each identified noble gas nuclide, i.Listed in Table 3-3: in mrem/yr per uCi/m3 (from Reg.Guide 1.109),.the constant.accounting for, the'air gamma radiation from the elevated Finite plume resulting from stack releases for each identified noble gas nuclide, i.Listed in Table 3-2 in mrad/yr per uCi/sec.Hi the constant accounting for the gamma air dose rate from-immersion in the semi-infinite cloud for each identified noble gas nuclide, i.Listed in Table 3-3 in mrem/yr per uCi/m3 (from Reg.Guide 1.109)See Appendix 8 for derivation of Bi,and Vi.32 sr f P.Ag<

3.2.1.2 Tritium, lodines and Particulates To ensure that the'500'mrem/year site dose rate limit is not exceeded, offsite dose rates for tritium, iodine and particulates with half lives greater than 8 days shall be calculated monthly and when release rates (Q).exceed 0.34 uCi/sec using the following equation.Oak (mrem/sec) 3.17E-8$~(~i Rijak[Ws is+Wv iv Where: oak Total dose to each organ k of an individual in age group a (mrem/sec).

dispersion parameter either X/Q (sec/m3)or 0/Q (1/m2)depending on pathway and receptor location assumed.Average meteorological data is" used (Table 3-1)."Elevated" W~values are used for stack releases (s stack);"Ground" Wg values are used for Emergency Condenser Vent releases (v vent).Qi Ri]ak 3.17E-.S the total quantity of isotope i released, (uCi/sec;s stack, v vent)the dose factor for each isotope i, pathway], age group a, and organ k (Table 3-4, through 3-22;m2-mrem/yr per uCi/sec for all pathways except inhalation, mrem/yr per uCl/m3.the inverse of the number of seconds in a year.,The R.values contained in Tables 3-4 through 3-22.were calculated using the methodology defined in NUREG-0133 and parameters from Regulatory Guide 1.109, Revision 1;as presented in Appendix C.When-the release rate exceeds 0.34 uCi/sec, the dose rate assessment shall also include JAF and NMP-2 contribution.

33 Pp4 S A+v, 1<

The use of the 0.34 uCi/sec release rate threshold to perform dose rate calculations is justified as follows: (a)The 1500 mrem/yr organ dose rate limit corresponds to a minimum release rate limit of 0.34 uCi/sec calculated using the equation: 1500 (Q/sec)x (Ri)N))where: 1500 site boundary dose rate limit (mrem/year)(Ri]"])max the maximum curie-to-dose conversion factor equal to 4.45E3 mrem-sec/uCi-yr for Sr-90, child bone at the critical residence receptor location beyond the site boundary.(b)The use of 0.34 uCi/sec release rate threshold and the 4.45E3 mrem-sec/uCi-yr curie-to-dose conversion factor is conservative since curie-to-dose conversion factors for other isotopes likely to be present are significantly lower.

b f I s'4 3.2.2 Dose-Calculations will be performed.

monthly at a minimum,.to demonstrate that doses resulting from the release of noble gases, tritium, iodines, and particulates with half lives greater than 8 days are within the limits specified in 10 CFR 50, Appendix I.These limits are: Noble Gases 5 mR gamma/calendar quarter'0 mrad beta/calendar quarter 10 mR gamma/calendar year'0 mrad beta/calendar year Tritium Iodines and Particulates 7.5 mrem to any organ/calendar quarter 15 mrem to any organ/calendar year l+%i'I d4 II'Pt I 1' 3.2.2.1 Noble Gas Air Dose The following Noble Gas air dose equation includes contributions from the stack (s)elevated.release.and the emergency condenser vent (v)ground level release when applicable (see section 3.2): For gamma radiation.(mrad): Dg (mr d)3 17E 8~i Hi(X Q)v Qiv+Bi Qis For beta radiation (mrad): 08(mrad)3.17E-S X)Ni (X Q)v iv+s is where: 0 y gamma air dose (mrad)0>beta air dose (mrad)the constant accounting for the air gamma radiation from the elevated finite plume resulting from stack releases for each identified noble gas nuclide, i.Listed in Table 3-2 in mrad/yr, per uCi/sec.Ni The constant accounting for the air beta dose from immersion in the semi-infinite cloud for each identified noble gas nuclide, i.Listed on Table 3-3 in mrad/yr per uCi/m3 (from Reg.Guide 1.109).Qi the total quantity of isotope i released, (uCi/sec.)

Note that the units for the gamma air dose are in mrad compared to the units for the limits are in mR.The NRC recognizes that 1 mR 1 mrad, for gamma radi'ation.

36 4 q(gi 3.17E-S the inverse of the number of seconds in a year.the constant accounting for the air gamma dose from immersion in the semi-infini te cloud for each identified noble gas nuclide, i.Listed on Table 3-3 in mrad/yr per uCi/m3<from Reg.Guide 1.109).All other parameters are as defined in section 3.2.1.1.3.2.2.2 Tritium, Iodines and Particulates

'o ensure that the 15 mrem/yr facility dose limit is not exceeded, offsite doses for tritium, iodines, and particulates with half lives greater than 8 days shall be calculated monthly using the following.<<equation: 0ak (mrem)3.17E-8 Z~(Si Ri]ak Ws is+Wv iv Where: 0ak Wg Qi Ri~ak 3.17E-8 Total dose to each organ k of an individual in age group a(mrem).dispersion parameter either X/Q (sec/m3)or 0/Q (1/m2)depending on pathway and receptor location assumed.Average meteorological data is used (Table 3-1)."Elevated" W~values are used.for stack releases (s stack);"Ground" W~values are used for Emergency Condenser Vent releases (v vent).the total quantity of isotope i released,<uCi/sec;s-stack, v vent)the dose factor for each isotope i, pathway], age group a, and organ k (Tables 3-4, through 3-22;m2-mrem/yr per uCi/sec)'the inverse of the number of seconds in a year 37 f I I~0 h ly CE' The R values contained in Tables 3-4 through 3-22 were calculated using the methodology defined in NUREG-0133 and parameters from Regulatory Guide 1.109, Revision 1;as presented in Appendix C.3.2.2.3 Accumulating Doses Doses will be calculated monthly, at a minimum, for gamma air, beta air, and the critical organ for each age group.Dose estimates will, also, be calculated monthly prior to receipt of any offsite analysis data i.e., strontium, tritium, and iron-55.Results will be summed for each calendar quarter and year.The critical doses are based on the following:

noble gas plume air dose direct radiation from ground plane deposition inhalation dose cow milk ingestion dose goat milk ingestion dose'cow meat ingestion dose vegetation (food crops)ingestion dose The quarterly and annual results shall be compared to the limits listed in paragraph,3.2.2.

If, the limits are exceeded, special reports, as required by Section 6.9.3 of the Technical-Specification, shall be submitted.

38 A~" I 3.3 Critical Receptors In accordance with the provisions of 10 CFR 20 and 10 CFR 50, Appendix I, the critical receptors have been identified and are"contained in Table 3-1.For elevated noble gas releases the critical receptor is the site boundary.Hhen 1985 average annual X/Q values are used for ground level noble gas releases, the critical receptor is the maximum X/Q land sector site boundary interface.

For tritium, iodines, and particulates with half lives greater than eight days, the critical pathways are grass-(cow and goat)-milk, grass-cow meat, vegetation, inhalation and direct radiation (ground plane)as a result of ground deposition.

The grass-(cow and goat)-milk, and grass-cow-meat pathways will be based on the greatest 0/Q location.This location has been determined in con]unction with the land use census (technical specification 3.6.22)and is sub]ect to change.The vegetation (food crop)pathway is based on the greatest 0/Q garden location from which ,samples are taken.This location may also be modified as a result of-vegetation sampling surveys.39

$*P C4 gi+1 3.3 (Cont'd)To comply with Technical Specifications, the inhalation and ground'lane dose pathways will.be.,calculated at the site boundary and beyond at the critical residence.

Because the Technical Specifications state to calculate"at the site boundary and beyond", instead of"at the site boundary or beyond", such as Unit 2, the doses and/or dose rates must be calculated for a maximum individual who is exposed to all pathways at the site boundary and at the critical residence.

The maximum individual is a composite of the highest dose factor of each age group, for each'rgan and total body, and each nuclide.Since the critical residence location would have the greatest occupancy time, the resultant dose at the residence including all pathways is limiting.However, due to the technical specif1cation wording, the inhalat1on and ground plane dose at the site boundary along with all other pathway's, will be calculated assuming a continuous occupancy time.t In 11eu of correcting the landsite boundary ground plane and inhalation dose factors for occupancy t1me, a Technical Specif1cation change will be submitted to change the requirement from calculating"at the site boundary and beyond" to"at the site boundary or beyond".Unit l will then calculate at the critical'res1dence since this should be the 11mit1ng dose.Until this change is effective, the dose and/or dose rate calculations for trit1um, iodines, and particulates with half lives greater than 8 days will conservatively assume that the ground plane and inhalation pathway cr1tical receptors are at the site boundary, i.e.X/Q and 0/Q, respectively,~are calculated at the s1te boundary.40 V f I V IC'*

3,4 Refinement of Offsite Doses Resulting from Emergency Condenser Vent Releases.The doses resulting from.the operation of the emergency condensers and calculated in accordance with 3.2.2 may be refined using data from actual environmental samples.Ground deposition samples will be obtained from an area or areas of maximum projected deposition.

These areas are anticipated to be at or near the site boundary and.near projected plume centerline.

Using the methodology found in Regulatory Guide 1.109, the dose will be calculated to the maximum exposed individual.

This dose will then be compared to the dose calculated in accordance with 3.2.2.The comparison wi 1 1 result in" an adjustment factor of less than or greater than one which will be used to adjust the other doses from other pathways.Other environmental samples may also be collected and the resultant calculated doses to the maximum exposed individual compared to the dose calculated per 3.2.2., Other environmental sample media may.include milk, vegetation (such as garden broadleaf vegetables), etc.The adjustment factors from these pathways may be applied to the doses calculated per 3.2.2 on a pathway by pathway basis or several pathway adjustment factors may be averaged and used to adjust calculated doses.Doses calculated'from actual environmental sample media will be based on the methodology presented in Regulatory Guide 1.109.The regulatory guide equations may be slightly modified to account for short intervals of time (less than one year)or modified for simplicity purposes by deleting decay factors.Deletion of decay factors woul'd yield more conservative results.

c~1*III 4.0 40 CFR 190 REQUIREMENTS The"Uranium Fuel Cycle" is defined in 40 CFR Part 190.02 (b)as follows: "Uranium fuel cycle means the operations of milling of uranium ore, chemical conversion of uranium, isotopic enrichment of uranium, fabrication of uranium fuel, generation of electricity by a light-water-cooled nuclear power plant using uranium fuel, and reprocessing of spent uranium fuel, to the extent that these directly support the production of electrical power for public use utilizing nuclear energy, but excludes mining operations, operations at waste P disposal sites, transportation of any radioactive material in support of these operations, and the reuse of recovered non-uranium special nuclear and by-product materials from the cycle." Section 3.6.15.d of the Technical Specifications requires that when the calculated doses associated with the effluent releases exceed twice the limits of sections 3.6.15.a.(2)(b), 3.6.15.b.(2)(b) and 3.6.15.b.(3)(b), then calculations shall be made including direct radiation contributions from the reactor units and outside storage tanks (as applicable) to determine whether the 40 CFR 190 dose limits have been exceeded.

$1%

4.0 (Cont'd)If such is the case, Niagara Mohawk shall submit a Special Report to th'e'NRC and limit"subsequent releases such that the dose commitment to a real individual from all uranium fuel cycle sources is limited to<25 mrem to the total body or any organ (except the thyroid, which is limited to<75 mrem)over the calendar year.This report=is to demonstrate that.radiation exposures to all real individuals from all uranium fuel cycle sources (including all liquid and gaseous effluent pathways and direct radiation) are less than the limits in 40 CFR Part 190.If releases that result in doses exceeding the 40 CFR 190 limits have occurred, then a variance from the NRC to permit such releases will be requested and if possible, action will be taken to reduce subsequent releases.The report to the NRC shall contain: 1)'dentification of,all uranium fuel cycle facilities or operations within 5 miles of the nuclear power reactor units at.the site that contribute to the annual dose of the maximum exposed member of the public.2)Identification of the maximum exposed member of-the public and a determination of the total annual dose to this person from existing pathways and sources of radioactive effluents and direct radiation.

~-

4.p (Cont'd)The maximum total body and organ doses resulting from radioactive material in liquid effluents"from Nine Hile Point Unit 1 will be summed with the maximum doses resulting from the releases of noble gases, radioiodines, and particulates for the other calendar quarters (as applicable) and from the calendar quarter in which twice the'imit was exceeded.The direct dose components will be-determined by either calculation or actual measurement.

Actual measurements will utilize environmental TLO dosimetry.

Calculated measurements will Utilize engineering calculations to determine a projected direct dose component.

In the event calculations are used, the methodology will" be detailed as required in Section 6.9.3.e of the Technical Specifications.

The doses from Nine Hile Point Unit 1 will be added to the doses to the maximum exposed individual that are contributed from other uranium fuel cycle operations within 5 miles of the site.For the purpose of calculating doses, the results of the Radiological Enviromental Honitoring Program may be included for providing more refined estimates of doses to a real maximum exposed individual.

Estimated doses, as calculated from station effluents, may be replaced by doses calculated from actual enviromental sample results..44 p~if1 E)It\I ,*%l P Cq Evaluation of Ooses From Liquid Effluents For the evaluation of doses to real members of the public from liquid effluents, the fi'sh consumption and shoreline sediment ground dose will be considered.

Since the doses from other aquatic pathways are insignificant, fish consumption and shoreline sediment are the only two pathways'that will be considered.

The dose associated with fish consumption may be calculated using effluent data and Regulatory

~Guide 1.109 methodology or by calculating a dose to man based on actual fish sample analysis data.The dose associated with shoreline sediment is based on the assumption that the shoreline would be utilized as a recreational area.This dose may be derived from liquid effluent data and Regulatory Guide 1.109 methodology or from actual shoreline sediment sample analysis data.Equations used to evaluate doses from actual fish and shoreline sediment samples are based on Regulatory Guide 1.109 methodology.

Because of the sample medium type and the half-lives of the radionuclides historically observed, the decay corrected portions of'---the-equations are.deleted., This does not reduce the conservatism of the calculated doses but increases the simplicity from an evaluation point of view.The dose from fish sample media is calculated as: (1)Rwb~Zi[Cif x U x 1000 x Oiwb x fl Nhere: Rwb The total dose to the whole body of an adult in mrem per year.

l 8 k.1 l r"Ui i g-f4" 4%9,v v t f,V S (Cont'd)Ci f 1000 Diwb (2)Rl Where: The concentration of radionuclide i in fish samples in pCi/gram.The consumption rate of fish for an adult (21 kg per year).Grams per kilogram-The dose factor for radionuclide i for the whole body of an adult (R.G.1.109, Table E-11).I The fractional portion of the year over which the dose is applicable.

gi (Cif x U x 1000 x Dil x f]Rl The total dose to the liver of an adult (maximum exposed organ)in mrem per year.Cif The concentration of radionuclide i in fish samples in pCi/gram.The consumption rate of fish for an adult (21 kg per year).1000 Dil The dose Rwb Rsk Where: Grams per kilogram The dose factor for radionuclide.

t for the liver of an adult (R.G.1.109, Table E-11)-The fractional portion of the year over which the dose is.applicable.

from shoreline sediment sample media is calculated as: I~X[iCis x U x 40,000 x 0.3 x Diwb x f]and XhiCis x U x 40,000 x 0.3 x Disk x f]Rwb Rsk Cis The.total dose to.the whole body of a teenager or.adult (maximum exposed age group)in mrem per year.The total: dose to the skin of a.teenager or adult (maximum exposed age group)in mrem per year.The concentration of radionuclide i in shoreline sediment in pCi/gram.

Ci'L k (Cont'd)The usage factor.This is assumed as 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> per year by a teenager or adult.40,000 The product of the assumed density of shoreline sediment (40 kilogram per square meter to a depth of 2.5 cm)times'the number of grams per kilogram.0.3 The shore width factor for a lake.Diwb 0is-The'ose factor for radionuclide i for the whole body (R.G.1.109, Table E-6)-The dose'actor for radionuclide i for the skin (R.G.1.109, Table E-6)='The-fractional portion of the year over which the dose is applicable.

NOTE: Because of the nature of the receptor location and the extensive fishing activity in the area, the critical individual may be a teenager or an adult.47 Qfl vp~4'4.l P

4.2 Evaluation

of Doses From Gaseous Effluents For the evaluation of doses to real members of the public from gaseous effluents, the pathways contained in section 3.2.2.3 of the ODCM will be considered.

These include the deposition, inhalation and ingestion pathways.However, any updated field data may be utilized that concerns locations of real individuals, real time meteorological data;location of critical receptors,-etc..Data.from'he most-recent census and sample location surveys should be utilized.Doses may also be calculated from actual enviromental sample media, as available.

Enviromental sample media data such as TLO, air sample, milk sample and vegetable (food crop)sample data may be utilized in lieu of effluent calculational data.Doses to member of the public from the pathways contained in OOCM section 3.2.2.3 as.a result of gaseous effluents will be calculated

'sing the dose factors of Regulatory Guide 1.109 or the methodology of the ODCM, as applicable

.Doses calculated from environmental sample media will utilize the methodologies found in Regulatory Guide:,1.109.4.3 Evaluation of Doses From Direct Radiation Section 3.6.15.d of the'echnical-Specificationsrequires that the.dose contribution as a result of direct radiation be.considered when evaluating whether the dose limitations of 40 CFR 190 have been.exceeded.

Cg I P I'1L 4 A Direct radiation doses as a result of the reactor, turbine and radwaste buildings and outside radioactive storage tanks (as applicable) may be evaluated by engineering calculations or by evaluating enviromental

'TLD results at critical receptor locations, site boundary or other special interest locations.

For the evaluation of direct radiation doses utilizing environmental TLDs, the critical receptor in question, such as the critical residence, etc., wi 11 be'ompared to.the control locations.

The comparison-involves the difference'in environmental TLD results between the receptor location and the average control location result.4,4 Doses to Members of the Public Within the Site Boundary.Section 6.9.l.e of the Nine Mile Point Unit 1 Technical Specifications requires that the Semiannual Radioactive Effluent'Release Report include an assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the publi'c due to their activi,ties inside the site boundary as defined by Figure 5.1-1 of the specifications.

A member of the public, as defined by--=the Technical Specifications, would be represented by an individual who visits the sites'nergy Information Center for the purpose of observing the educational displays or for picnicing and associated activities..

49 1'4 g' 4.4 (Cont'd)Fishing is a major recreational activity in the area and on the Site as a result of the salmonid and trout populations in Lake Ontario.Fishermen have been observed fishing at the shoreline near the Energy Information Center from April through Oecember in all weather conditions

.Thus, fishing is the major activity performed by members of the public within the site boundary.Based on the nature of the-.fishermen.

and.undocumented observations, it is conservatively assumed that the maximum exposed individual spends an average of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per week fishing from the shoreline at a location between the Energy Information Center and the Unit 1 facility.This estimate is considered conservative but not necessarily excessive and accounts for occasions where individuals may fish more on weekends or on a few days in March of the year.The pathways considered for the evaluation include the inhalation pathway with the resultant lung dose, the ground dose pathway wi th the resultant whole body and skin dose and the direct radiation dose;, pathway wi th the associated whole body dose.The direct radiation dose pathway, in actuality, includes several pathways.These include: the direct radiation gamma dose to an individual from an overhead plume, a gamma submersion plume dose, possible direct radiation dose from the facility and a ground plane dose (deposition).

Because the location is in close proximity to the site, any beta plume submersion dose is felt to be insignificant.

WS 4 I 1 6 U II I fI p 4.4 (Cont'd)Other pathways, such as the ingestion pathway, are not applicable.

In addition, pathways associated with water related recreational activities, other than fishing, are not applicable here.These include swimming, boating and wading which are prohibited at the facility.-The 1nhalation pathway is evaluated by identifying the applicable radionuclides (radioiodine, tritium and particulates) in the effluent for the appropriate t1me per1od.The radionuclide concentrations are~:then multiplied by the appropriate X/Q value, 1nhalatton dose factor, air intake rate, and the.fractional portion of the year in question.Thus, the inhalation pathway is evaluated using the following equation adapted from Regulatory Guide 1.109.NOTE: The following equation 1s adapted from equations C-3 and C-4 of Regulatory Guide 1.109.Since many of the factors are in units of pCi/m , m/sec., etc., and since the 3 3.-radionuclide decay.expressions have been deleted because of the short distance to the receptor location, the equation presented here is not ident1cal to the Regulatory Guide..equations.

R~gi['CiF X/Q DFA 1)R t]where: R'the maximum dose for the period in question to the lung (])for all radionuclides (1)for the adult age group (a)in mrem per time period.

l t" r$C 1 w w, CA'f~I Tk P k 4.4 (Cont'd)X/Q The average concentration in the stack release of radionuclide 1 in pCi/m3 for the period in question.Unit l average stack flowrate in m3/sec.The.plume;dispersion parameter for a location approximately 0.50 miles west of NHP-1 (The plume dispersion parameter is 8.9E-06 and was obtained from the C.T.Hain five year average annual X/Q tables.The stack (elevated)

X/Q is conservat1ve when based on 0.50 miles because of the close proximity of the stack and the receptor location).

OFAiga.the inhalation dose factor for radionuclide 1, the lung], and adult age group a in mrem per pCi found on 6 Table E-7 of Regulatory Guide 1.109.Ra annual air intake for individuals in age group a in m3 per year (this value is 8,000 m3 per year and was obtained from Table E-5 of Regulatory Guide 1.109).fractional portion of the year f'r which radionuclide 1 was detected and for which a dose is to be calculated (in years).The ground dose pathway (deposition) will be evaluated by obtaining at least one soil or shoreline sediment sample in the area where" fishing occurs.The dose will then be calculated us1ng the sample results, the time period in question, and the methodology based on Regulatory Guide 1;109 as presented in Section 4.1.The resultant dose may be ad)usted for a background dose by subtracting the"'applicable off-site control soil or shorel1ne sediment sample rad1onuclide activities.

In the event it is noted that fishing is not performed from the shoreline, but is instead performed in the'water (i.e., the use of waders), then the ground dose pathway.(depos1t1on) will not be evaluated.

52 1<<l l I~'*A The direct radiation gamma dose pathway includes any gamma doses from an overhead plume, submersion in the plume, possible radiation from the facility and ground plane dose (deposition).

This general pathway will be evaluated'y average environmental TLD readings.At least two environmental TLDs will be utilized at one location in the approximate area where fishing occurs.The TLOs will be placed in the field on approximately"the beginning of each calendar.'quarter-.and removed on approximately the end-of each calendar quarter (quarter 2, 3, and 4).The average TLD readings will be ad]usted by the average control TLD readings.This is accomplished by subtracting the average quarterly control TLD value from the average fishing location TLO value.The applicable quarterly control TLD values will be utilized after ad]usting for the appropriate time period (as applicable).

In the event of loss or theft of the TLDs, results from a TLD or TLOs in the area may be utilized.

E V 1 P t 4 pl+{I%')ll~1

5.0 ENVIRONMENTAL

MONITORING PROGRAM 5.1 Sampling Stations The current sampling locations are specified in Table 5-1 and Figures 5.1-1, 5.1-2.The meterological tower is shown in Figure 5.1-1.The location is shown as TLD location 17.The Radiological Environmental Monitoring Program is a'joint effort between the Niagara Mohawk Power, Corporation and the New York Power Authority, the owners and operators of the Nine Mile Point Unit 1 and the James A.FitzPatrick Nuclear Power Plant, respectively.

Sampling locations are chosen on the basis of histo'rical average dispersion or deposition parameters from both units.The environmental sampling location coordinates shown on Table 5-1 are based on the NMP-2 reactor centerline.

The average dispersion and deposition parameters have been calculated for a 5 year period, 1978 through 1982.These dispersion calculations are attached as Appendix E.""""'->The calculated, dispersion or.deposition parameters will be compared to the results of the annual land use census.If.it is determined that a milk sampling location exists at a location that yields a significantly higher (e.g.50'4)calculated 0/Q rate, the new milk sampling location will be-added to the monitoring program within 30 days.If a new location is added, the old location that yields the lowest calculated D/Q may be dropped from the program after October 31 of that year.

g..~'t

5.2 Interlaboratory

Comparison Program Analyses shall be performed on samples containing known quantities of radioactive materials that are supplied as part of a Commission approved or sponsored Interlaboratory Comparison Program, such as the EPA Crosscheck Program.Participation shall be only for those media, e.g., air, milk, water,'tc., that are included in the Nine Nile Point Environmental Monitoring-Program and for which crosscheck

"=samples are available.

'An attempt will be made to obtain a QC sample to program sample ratio of 5'L or better.The site identification symbol or the actual guality Control sample results shall be reported~in the Annual Radiological Environmental Operating Report so that the'ommission staff may evaluate the results.a Specific sample media for which EPA Cross Check Program samples are..available include the following:

, 0 gross beta in air particulate filters',gamma emitters in air particulate filters gamma emitters in milk , gamma emitters in water tritium in water I-131 in water l JPP l~V~K'K II 0

5.3 Capabilities

for Thermoluninescent Dosimeters Used for Env/ronmental Measurements Required detection capabilities for thermoluminescent dosimeters used for environmental measurements required by Table 4.6.20-1, footnote b of the Technical Specifications are based on ANSI Standard N545, section 4.3.TLOs are defined as phosphors packaged for field use.In regard to the"detection capabilities for thermoluminescent dosimeters, only, one determination is required to evaluate the above capabilities per type of TLD.Furthermore, the above capabilities may be determined by the vendor who supplies the TLDs.Required detection capabilities are as follows:5.3.1 Uniformity shall be determined by giving TLOs from the same batch an exposure equal to that resulting from an exposure rate of 10 uR/hr during the field cycle.The responses obtained shall have a relative standard deviation of less than 7.5'A.A total of at least 5 TLOs shall be evaluated.

--;5.3.2-~'-",Reproducibility shall-.be determined.

by giving TLDs repeated exposures equal.to that resulting from an exposure rate of 10 uR/hr during the field cycle.The average of the relative standard deviations of the,.responses.

shall be less than 3.0'X.A total of at least 4 TLOs shall be evaluated.

'11p,,A l j 1!-Cf Wf

5.3.3 Dependence

of exposure interpretation on the length of a field cycle shall be examined by placing TLDs for a period equal to at least a field cycle and a period equal to half the same field cycle in an area where the exposure rate is known to be constant.This test shall be conducted under approximate average winter temperatures and approximate average summer temperatures.

For these tests, the ratio of the response obtained in the field cycle to twice that obtained for half the field cycle shall not be less than 0.85.At least 6 TLDs shall be evaluated 5.3.4 Energy dependence shall be evaluated by the response of TLDs to photons for several energies between approximately 30 keV and 3 HeV.The response shall not differ from that obtained with the calibration source by more than 25%for photons with energies greater than 80 keV and shall not be enhanced by more than a factor of two for photons with energies less than 80 keV.A total of at least 8 TLDs shall be evaluated.

5.3.5 The directional dependence of the TLD response shall be determined by'omparing.the response of the TLD exposed in the routine orientation with respect to the calibration source with the response obtained for different orientations.

To accomplish this, the TLD shall be rotated through at least two perpendicular planes.The response averaged over all directions shall not differ from the response obtained in.the standard calibration position by more than 10K.A total of at least 4 TLDs shall be evaluated.

V~(I~lg s S 5.3.6 Light dependence shall be determined by placing TLDs in the field for a period equal to the field cycle under the four conditions found in ANSI N545, section 4.3.6.The results obtained for the unwrapped TLOs shall not differ from those obtained for the TLDs wrapped in aluminum foil by more than 10K.A total of at least 4 TLOs shall be evaluated for each of the four conditions.

5.3.7 Moisture dependence shall be..determined by placing TLDs (that ls, the phosphors packaged for field use)for a period equal to the field cycle in an area where the exposure rate is known to be constant.The TLDs shall be exposed under two conditions:

(1)packaged in a thin, sealed plastic bag, and (2)packaged in a thin, sealed plastic bag with sufficient water to yield observable moisture throughout the field cycle.The TLD or phosphor, as appropriate, shall be dried before readout.The response of the TLD exposed in the plastic bag containing water shall not differ from that exposed in the regular plastic bag by more than 10'L.A total of at least 4 TLOs shall be evaluated for each condition.

.,'.3.8.=,Self irradiation shall-be determined.

by placing TLOs for a period equal to the field cycle in an area where the exposure rate is less than 10 uR/hr and the exposure during the field cycle is known.If necessary,.

corrections shall be applied for the dependence of exposure interpretation on.the length of the field cycle (ANSI N545, section 4.3.3).The average exposure inferred from the responses of the TLDs shall not differ from the known exposure by more than an exposure equal to that resulting from an exposure rate of 10 uR/hr during the field cycle.A total of at least 3 TLDs shall be evaluated.

I~'+I I I~ll ltd~~l&III&R I fl" l.I+I I~l~P II+5" IIllI I I If I'r C TABLE 1-1 Average Energy Per Disintegration ISOTOPE Ar-41 Kr-83m Kr-85 Kr-85m Kr-87 Kr-88 Kr-89 Kr-90 Xe-'131M Xe-133 Xe-133m Xe-135 Xe-135m Xe-137 Xe-138~Emev/di s 1.294 0.00248 0.0022 0.159 0.793 1.95 2.22 2.10'0.0201 0.0454 0.042 0.247 0.432 0.194 1.18 (Ref)(3)(2)(2)EGmev/dis<4) 0.464 0.0371 0.250 0.253 1.32 0.377 1.37 1.01 0.143 0~135 0.19 0.317 0.095 1.64 0.611 (Ref)(3)(2)(2)(1)ORNL-4923, Radioactive Atoms-Su lement I, M.S.Martin, November 1973.(2)NED0-12037,"Summary of Gamma and Beta Emi tters and Intensity Data";M.E.Meek, R.S.Gilbert, January 1970.<The average energy was computed from the maximum energy using the ICRP II equation, not the 1/3 value.: assumption used, in this reference).

(3)NCRP Report No.58,-,"A-Handbook of.Radioactivity Measurements Procedures";

1978 (4)The average energy includes conversion electrons.

59 Q, Vk C$, ag 2 sp I 4 I't'4\A 4 A\p g yA~lb~la-,I S&

NUCLIDE BONE LIVER H3-2.90E-1 Cr 51 TABLE 2-1 Ai t VALUES-LIQUID*RADHASTE TANK INFANT , mrem-ml hr-uCi T BODY THYROID KIDNf Y 2.90E-1 2.90E-1 2.90E-1 1.29E-2 8.39E-3 1.83E-3 LUNG GI-TRACT 2.90f-l 2.90E-1 1.63E-2 3.75E-1 Cu 64 Mn 54 1.13E-l 1.87E+1 5.23E-2 1.91E-l 4.23-4.14 2.32 6.86 4.13 1.07 1.47E+1 2.37E+1 8.33 2.42E+1 5.00E+1 4.77E+1~-2.17E+2 2.32E+1 2.18E-2.7.71 2.37 2.37 1.28 1.04 1.15E-2 2.60E-4 2.26 FE 55 1.31E+1 8.44 1.96E+1 Fe 59 2.84E+1 4.96E+1 8.34 2.40E+1 Co 58-3.34 Co 60-1.02f+1 Zn 65 1.72f+1 5.91E+1 Sr 89*2.32E+3 2.73E+1-2.87E+1 6.66E+1 4.43E+3 Sr 90 1.74E+4 Zr 95 1.91E-l 4.66E-2 5.02E-2 2.07E-4 3.30E-2'.15E-5 2.40E-4 Mn 56 3.50E+1 2.37 4.17E+1 2.34E+1 4.57 Mo 99 Na 24 I 131 I 133 2.37'2.37 2.37 1.57E+1 2.37 3.54E+1 6.15 1.17E+4 3.03E+1 4.22 1.80 1.12E+3 7.23 1.33E-3 1.51E-4 6.85E-5 Ni 65 I 132's'134 1.58E-4 3.21E-4 1.14E-4 1.50E-2 3.58E-43.54E+2-.6.60E+2 4.05f+1 1.19f+2 6.67E+1 4.45E+1 1.70E+2 6.97E+1 1.79 4.75E+1 9.71E+1 1.81 1.54E+2 6.24E+1 1.80 3.57E-2 9.23E-2 3.69E+1 Cs 136 Cs 137 Ba 140 Ce 141 Nb 95 4.91E+2 5.75E+2 4.07E+1 1.50E+2 1.SOE-1 7.74 7.21E-2'.4.40E-2 5.17E-3 3.85E-2 1.59E-2 9.18E-3 2.27E+1 1.34E+1 5.48E+1 1.60E+2 1.36E-2 1.14E-2 1;and Regulatory La 140 1.18E-2 4.67E-3 1~20E-3 Ce 144 2.79 1.14 1.57E-1-4.62E-l*Calculated in accordance with NUREG 0133, Section 4.3.Guide 1.109, Regulatory position C, Section 1.60 kV t~.VQ Q I'p 9 g'0%(V>>sQ/

TABLE 2-2 Ai t VALUES-LIQUID*RADHASTE TANK CHILD mrem-ml hr-uCi LIVER T BODY THYROID.KIDNEY 4.39E-1 4.39E-l 4.39E-1 4.39E-1 NUCLIDE BONE H3 Cr 51 2.13E-2 CU 64 2.51E-6 Mn 54 6.92 Fe 55 9.21E+2 Fe 59 1.30E+3 Co 58 1.89 Co 60 1.12E+2 Zn 65 2.15E+4'r 89'" 3.'26E+4 Sr 90 4.26f+5 Zr 95 1.70 Mn 56 Mo 99 5.35E-3 Na 24 1.52E+2 I 131 2.09E+2 I 133 3.39E+1 Ni 65 2.67E-l I 132 6.13E-3='Cs 134~;3.68E+5 Cs 136 3.52E+4 Cs 137 5.15E+5 Ba 140 3.61E+2 Ce.141 1.50f-l Nb 95 5.21E+2 La 140 1.50E-l Ce 144 5.00 Calculated in Guide 1.109, Regu LUNG 4.39E-1 GI-TRACT 4.39E-l 7'1E+1 2.13E-2 1.40 7.86E-1 2.30E-1 1.42 2.51E-6 1.27E+2 2.70 1.63 2.51E-6 6.52 9.53E+2 3.38E+3 9.06E+2 6.92 4.88E+2 1.51E+2 2.11E+3 1.05E+3 1.34 7.46E+1 2.24E+2 1.89 6.92.2.84E+3 2.76E+2 9.05E+1 2.19E+3 4.26E+2 6.12E+2 1.34 1.&9 1.89 3.28E+2 7.4&E+2 1.12E+2 1.12E+2 1.,12E+2 1.31E+3 3.61E+4 1;10E-4 5.73E+4 3.56E+4 3.85'1.10E-4 9.32E+2 1.10E-4 1.0&f+5 1.01E+4 3.85 1.10E-4 1.26E+3 5.74E+3 1.23 1.08E+2 2.39E+1 1.33 1.32 1.38 1.23 2.00E-1 1.65E-l 3.73E-2 7.91E+1 1.52E+2 9.57E+1 2.37E+1 5.35E-3 2.04E+2 5.35E-3'1.52E+2 1.52E+2 1.52E+2 1.52E+2 1.52E+2 2.10E+2 1.19E+2 6.94E+4 3.45E+2 5.60E-2 1.87E+1 4.19E+1 1.59E+1 7.7&E+3 2.51E-2 1.47E-2 6.98E+1 1.38f-4 1.69E+1 3.08 1.32E-2 1.13E-2 5.18E-3 5.22E-1 1.72E-2 9.67E+4 6.26E+4 6.21E-1 4.93E+5 7.28E+4 5.37E+1 3.96E-1 2.11E+1 7'6E-2: 1.07E-1 6.99E-Z 6.34E-Z 2.03E+2 1.45f+2 6.39E-l 5.93E-2 2.6&E-2 1.03E-2 1.81 6.06f-l 3.58E-1 accordance with NUREG 0133, S latory posi'tion C, Section l.5.15E+4 7.68E+3 3.40f+3 1.61E+5 5.78E+4 3.14E+3 1.82E-1 8.24E-2 1.91E+2 1.03E-2 2.68E-l 1.83E+2 6.34E-2.5.40E+1 6.39E-1 3.75E+5 1.03E-2 1.36E+3 3.58E-l 3.80E+2 1;and Regulatory 1.16 ection 4.3.;,6.04E+5 1..27E+53.54E+1 1.87E+5 6.72E+4 3.29E+3 61 b~4 TABLE 2-3 Ai t VALUES-LIQUID*RADHASTE TANK TEEN mrem-ml KIDNEY LUNG GI-TRACT 3.28E-1 3.28E-1 3.28E-1 1.20E-S 2.24E+2 7.89E+2 5.87E+3 1.24E+3 3.93E+3 9.03 4.66E+4 1.84E+1 3.08E+4 5.24E-4 5.24E-4 2.90E+3 1.31E+4 5.90 2.28E+2 1.19E+1 2.29E-l 2.11E+2 2.56E-2 1.65E+2 1.39E+2 1.39E+2 1.39E+2 2.68E-l 4.30E+1 6.60E-4 3.25E+1 1.44 5.59E-3 8.73E+4 9.10E+3 1.01E+4 9.44E+3 7.21E+4 7.99E+3 5.75E-l 3.63E+2 3.04E-1.8.16E+1 3.06 1.05E+6 4.94E-2 3.05E+3 1.71 5.74E+2;and Regulatory hr-uCi NUCLIDE BONE LIVER T BODY THYROID H3-3.28E-1 3.28E-1 3.28E-1 Cr 51 1.02E-l 1.02E-l 1.39.8.16E-l 3.84E-l 1:94 2.1'6E+2 Cu 64 1.20E-S 2.89 1.36 1.20E-5 7.32 Hn 54-3.3lf+1 4.34E+3 8.87E+2 3.31E+1 1.32E+3 3.'31E+1 8.86E+3 Fe,55-;6.94E+2 4.92E+2 1.15E+2--3.12E+2 2.13E+2 fe 59 1.07E+3 2.49E+3 9.64E+2 6.41 6.41 Co 58 9.03 9.82E+1 2.15E+2 9.03 9.03 Co 60 5.36E+2 7.96E+2 1.12E+3 5.36E+2 5.36E+2 5.36E+2 Zn 65 2.10E+4 7.28E+4 , 3.40E+4 1.84E+1'r 89" 2.44E+4'.24E-4 6.98E+2 5.24E-4, Sr 90 4.66E+5 1.15E+5 Zr 95 6.20 6.00 5.97 5.90 6.04 Hn 56-1.81E-1 3.22E-2 Ho 99 2.56E-2 9.22E+1 1.76E+1 2.56E-2'Na 24 1.39E+2'1':39E+2 1.39E+2 1.39E+2 I 131 1.55E+2 2.17E+2 1.16E+2 6.31E+4 3.73E+2 I 133 2.53E+1 4.29E+1 1.31E+1 5.99E+3 7.52E+1 Ni 65 2.08E-l 2.66E-2 1.21E-2 I 132 4.90E-2 1.28E-2 4.60E-3 4.32E-1 2.02E-2'Cs'34'3.05f+5'7.18E+5"3.33E+5 1.69E+2 2.28E+5 Cs 136 2.98E+4 1.17E+5 7.88E+4 2.97 6.38E+4 Cs 137 4.09E+5 5.44E+5 1.90E+5 2.57E+2 1.85E+5 Ba 140 2.35E+2 4.10E-l 1.55E+1 3.81E-l 4.79E-1 Ce.141 3.46E-1'-3.32E-l 3.07E-1, 3.04E-1 3.17E-l Nb 95 4.44E+2.2.48E+2.1..18E+2 3.06 2.40E+2 La 140 1.57f-l 1.02E-l 6.35E-2'.94E-2'.94E-2 Ce 144 3.99 2.65 1.83 1.71 2.27*Calculated in accordance with NUREG 0133, Section 4.3.1 Guide 1.109, Regulatory posi tion C, Section 1.62

~4 V f,)E n J sl$k-Pi'w TABLE 2-4 Ai t VALUES-LIQUID*RADWASTE TANK ADULT mrem-ml hr-uCi GI-TRACT LUNG KIDNEY 4.45E-l 2.93E-1 T BODY THYROID NUCLIDE BONE LIVER 4.45E-l 4.45E-1 H3 Cr 51 CU 64 4.45E-1 4.45E-1 4.45E-1 1.27 7.64E-1 1.82E-2 3.14E+2 2.35E+2 1.34E+4 2.63E+2 1-82E-2 1.67 6.94 2.75 1.29 1.31E+3 5.94 Mn 54 5.94 4.38E+3 8.41E+2 5.94 2.56E+2 6.79E+2 1.62 9.60E+1 1.07E+2 4.58E+2 6.64E+2 1.03E+3 Fe 55 Fe 59 8.09E+3 1.82E+3 1~15 1.15 9.31E+2 2.43E+3 1.62 1.62 2.03E+2 9.15E+1 Co 58 1.62 Co 60 9.60E+1 4.99E+3 4.63E+4 3.60E+3 1.62E+4 9.60E+1 9.60E+1 6.71E+2 2.57E+2 4.92E+4 3.30 3.30 Zn 65 Sr 89 SI 90 Zr 95 Mn 56 Mo 99 Na 24 I 131 I 133 Ni 65 I 132 2.31E4 2.25E+4 5.60E+5 1.36 4.58E-3'.35E+2 1.45E+2 2.35E+1 1.93E-l 4.68E-3 7.36E+4 3.32E+4 9.39E-5 6.45E+2 9.39E-5 9.39E-S 9.39E-5 1.37E+5 1.15E 1.12 1.06 1.21 3.06E+2 5.52 2.02E+2 1.35E+2 1.06 1.73E-1 3.07E-2 2.20E-1 8.70E+1 1.97E+2 4-58E-3 1.66E+1 4.58E-3 1.35E+'2 1.35E+2 1.35f+2 1.35E+2 1.35E+2 2.51E-2 1.14E-2 6.36E-1 2.35E-3 1.24E+4 1.33E+4 1.25E-2 4.38E-3 4.38E-l 2.00E-2 7.61E+4 8.93E+3 Cs"134 Cs 136 Cs 137 Ba 140 Ce..141 Nb 95 La 140 Ce 144.5.79f+5 8.42E+4'7".OBE+5 1.17E+5 5.22E+5 3.49E-l-2:98E+5 2.96E+4 3.82E+5 2.24E+2 9.53E-2 4.39E+2 l.llf-l 2.48 2.29E+5 6.51E+4 3.03E+1 5.32E-1 4.60E+1 6.83E-2 1.02E+4 1.77f+5 5.90E+4 3.42E+5 1.47E+1 4.61E+2 1.64E-1 2.29E-1 8.20E-2 5.75E-2 5.44E-2 1.06E+2 1.48E+6 6.72E-2 5.44E-2 2.41E+2 5'7E-1 2.44f+2 1.32E+2 5.47E-1, 6.03E-2 2.24E-2 8.84E-3 1.22 4.24E-1 3.07E-1 accordance with NUREG 0133, S latory position C, Section 1.8.84E-3 8.84E-3 3..78E+3 8.47E-l 3.07E-l 7.37E+2 ection 4.3.1;and Regulatory Calculated in Guide 1.109, Regu 2.07E+2 1.19E+2 6.79E+4 3.55E+2 4.80E-2 5.47E+1 4.09E+1 1.25E+1 6.02E+3 7.14E+1 1.18E-4 3.68E+1 63

~a 0 NUCLIDE BONE LIVER H3-7.43E-4 TABLE 2-5 Ai t VALUES-LIQUID*EHERGENCY CONDENSER VENT INFANT mrem-ml hr-uCi T BODY THYROID KIDNEY LUNG GI-TRACT 7.43E-4 7.43E-4 7.43E-4 7.43E-4 7.43E-4 Cr 51 Cu 64 Hn 54 2.89E-4 1.34E-4 4.89E-4 5.94E-3 4.79E-2 1.'08E-2 1.06E-2 1.76E-2 3.30E-5 2.15E-5 4.70E-6 4.18E-5 9.61E-4, Fe 55 , 3.35E-2 2.16E-2 5.78E-3 Fe 59 7.29E-2 1.27E-1 5.02E-2 1.06E-2 2.75E-3 3.76E-2 6.08E-2 2.14E-2 6.19E-2 1.28E-l 1.22E-1 5.57E-l 5.95E-2 5.60E-5 1.98E-2 Co 58 Co 60 8.58E-3 2.14E-2 2.60E-2 6.15E-2 7.35E-2 Zn 65 4.42E-2 1.52E-1 6.99E-2 Sr 89 5.95 Sr 90 4.46E+1 1.71E-l 1.14E+1 1.19E-4 Zr 95 4.90E-4 Hn 56 Ho 99 Na 24.6.07E-3 I 131 7.77E-Z I 133 1.08E-2 Ni 65 3.41E-6 I 132 4.05E-7'Cs'134'.'OBE-1 Cs 136 1.04E-1 Cs 137 1.26 Ba 140 3.85E-l Ce 141 1.85E-4 Nb 95 9.88E-5 La 140 3.03E-5 Ce 144 7.16E-3*Calculated in Guide 1.109, Regu 8.47E-5 1.29E-4 5.30E-7 8.97E-2 6.17E-7 1.06E-7 1.17E-2 6.00E-2 6.07E-3 6.07E-3 6.07E-3 6.07E-3 6.07E-3 6.07E-3 3.27E-3 2.67E-3 2.94E-5 6.66E-7 9.16E-2 3.01E+1 1.07E-1 2.87 1.85E-2 4.03E-2 1.58E-2 4.62E-3 1.76E-7 3.86E-7 8.22E-7 2.93E-7 3.85E-5 9.17E-7 3.06E-1 1.14E-l 1.22E-1 2.49E-2 4.64E-3 1.47 1.04E-1-3.95E-I 1.60E-1 4.61E-3 1.99E-2 3.85E-4 9.15E-5 2.37E-4 9.47E-2 5.82E-2 1.13E-4 1.33E-5 3.48E-5 2.92E-5 4.07E-5 2.35E-5--3.43E-2 1.41E-l 4.11E-l Regulatory 3.08E-6 1.20E-5 2.93E-3 4.02E-4-1.19E-3 accordance with NUREG 0133,=Section 4.3.1;and A latory position C, Section l.'.1.69"'.71E-l'-4.36E-1 1.79E-1 4.60E-3 64 lp'l",>>'t I Ig~'U Q"," ht TABLE 2-6 Ai t VALUES-LIQUID*EMERGENCY CONDENSER VENT CHILD ,mrem-ml hr-uCi LIVER T BODY THYROID KIDNEY 1.44E-1 1.44E-l 1.44E-l 1.44E-l GI-TRACT 1.44E-l LUNG 1.44E-1 1.23E+2 2.63 8.88E+1 2.15E+3 1.03E+3 2.15E+2 6.14E+2 3.56E+4 2.38E-3 2.38E-3 6.00E+2 3.36E-3 3.36E-3 3.36E-3 1.99E-1 1.99E-1 1.99E-1 6.84E-3 3.61E+4 6.84E-3 4.09E+2 1.15E+3 1.01E+4 1.19E+3 3.07E+4 4.01E+5 3.01E-1 5.40E+3 6.84E+1 2.39E+1 6.75E+1 1.50E+2 1.67E+1 1.53E+1 9.61E-2 2.00E-1 6.06E-2 3.73E-2 1.74E+2 1.50f+2 3.08E+2 6.35E+1 1.50E+2 1.50E+2 1.06E+2 1.44E+1 2.50E-2 1.30E-2 6.71E+4 3.25E+3 7.67E+3 3.40E+3 9.66E+4 4.92E+5 5.77E+4 3.08E+3 1.30E-1 1.26E+2 2.17E-1'1.54E-2 2.39E-3 1.13E-4 6.83E-3 2.03E+2 1.45E+2 1.14E-3 1.90E+2 4.59E-2 1.55E-2 1.83E-S 1.83E-5 5.15E-1 8.81E-2 6.36E-4 2.85E-1 accordance with NUREG 0133, Section 4.latory position C, Section l.1.91E+1 3.75E+5 1.28E+3 1.34E+2 3.1;and Regulatory NUCLIDE BONE H3 Cr 51 3.78E-5 3.78E-5 1.37 7.58E-1 2.07f-l 1.38 7.24E+1 Cu 64 1.59-6.35 Mn 54 1.23E-2 3.36E+3 8.95f+2 1.23E-2 9.42E+2 1.23E-2 2.82E+3 fe 55 9.04E+2 4.79E+2 1.49E+2 2.71E+2 Fe 59 1.28E+3 2.07E+3 Co 58 3.36E-3 7.01E+1 Co 60 1.99E-l 2.08E+2 Zn 65 2.15E+4 5.73E+4" Sr 89 8.78E+2 Sr 90 1.02E+5 Zr 95 6.78E-2 2.19E-3 2.19f-3 Mn 56 1.65f-l Mo 99 8.16f+1 2.02E+1 Na 24 1.50E+2 l.'50E+2 1.50E+2 I 131 1.86E+2 1.87E+2 6.19E+4 I 133 3.08E+1 3.81E+1 7.07E+3 Ni 65 2.66E-1 1.46E-2---3.07 I 132 6.01E-3 1.10E-2 5.08E-3 5.12E-1 1.69E-2 Cs 134"3"68E+5 6:04E+5 1.27E+5 6.29E-2.1.87E+5 Cs 136 3.51E+4 6.25E+4 1.10E-3 5.14E+4 Cs 137 5.14E+5 7.27E+4 9.55E-2 1.60E+5 Ba 140 2.48E+2 1.45E+1 1.42E-4 7.09E-2 Ce'141 3.OBE-2 1.13E-4 Nb 95 5.21E+2 1.14E-3 La 140 1.31f-l 1.83E-5 Ce 144 1.64 6.36E-4 Calculated in Guide 1.109, Regu 65 I R'+v t>5>of~

'I TABLE 2-7 Ai t VALUES-LIQUID*EMERGENCY CONDENSER VENT TEEN ,...mrem-ml hr-uCi T BODY THYROID GI-TRACT LIVER LUNG KIDNEY 1.74E-l NUCLIDE BONE H3 Cr 51 1.81E-4 Cu 64 Mn 54 5.89E-2 Fe.55 6.89E+2 Fe 59 1.05E+3 Co 58 1.61E-2 Co 60 9.53E-l Zn 65 2.10E+4 Sr 89'.'38E+4 Sr 90 4.54E+5 Zr 95 2.56E-l Mn 56 Mo 99 Na'24 1.38E+2 I 131 1.47E+2 I 133 2.42E+1 Ni 65 2.08E-1 I 132 4.86E-3's:134'" 3!05E+5 Cs 136 2.98E+4 Cs 137 4.09E+5 Ba 140 1.96E+2 Ce-141 2.43E-2 Nb 95 4.41E+2 La 140 1.05E-1 Ce 144 1.27*Calculated in Guide 1.109, Regu 1.74E-1 1.74E-1 1.74E-1 1.74E-1 1.74E-1 2.15E+2 2.81E-l 1.83 1.81E-4 1.28 7.12E-l 2.86 1.35 7.24-2.22E+2 1.28E+3-5.89E-2=-

-8.81E+3 3.10f+2 2.11E+2 4.29E+3 8.52E+2 5.89E-2 1.14f+2 4.88E+2 5.82E+3 1.21f+3 2.46E+3 8.78E+1 9.50E+2 1.14E-2 2.02E+2 1.61E-2 1.14E-2 7.76E2 1.61E-2 1.61E-2 9.53E-1 9.53E-1 4.66E+4 3.28E-2 2.57E+2 5.78E+2 9.53E-1 3.34E+3 3.08E+4 2.83E+3 7.28E+4 3.39E+4 3.28E-2 6.81E+2 1.12E+5 1.27E+4 8.80E-2 6'8E-2 1.05E-2 1.24E-l 1.05E-2 1.79E+2 1.19E+1 1.54E+2 2.29E-1 1.96E+2 3.22E-2 1.81E-1 8.57E+1 1.63E+1 1.38E+2 1.38E+2 4.77E-4 4.07E+1 1.38E+2'.38E+2 1.38E+2 1.38E+2 3.54E+2.7.21E+1 2.0642 4.11E+1 1.10E+2 1.25E+1 6.00E+4 5.74E+3 3.11E+1 1.44 1.21E-2 2.66E-2 5.54E-3 4.56E-3 4.29E-1.2.00E-2 1.27E-2 i'"7:1 8E+5 3.33E+5, 3.01E-1 2.28E+5 8.71E+4 8.93E+3 6.38E+4 1.01f+4 9.43E+3 1.85E+5 7.19E+4 7.73E+3 8.23E-2 1.62E-l 3.03E+2 8.02E-3 5.40E-4 4.54E+1 7.87E+4 5.28E-3 1.89E+5 4.57E-l 1.27E+1 6.77E-4 2.36E-3 5.40E-4 1.15E+2 5.43E-3 1'.38E-2'.78E-5 7.12E-2 3.04E-3 1.17E+5 5.44E+5 2.47E-2 1.64E-2.2.45E+25.17E-2 5.28E-1 2.37E+2 8.78E-5'.17E-l 5.43E-3 1.05E+68.78E-5 2.96E+3-3.04E-3 3.19E+2 latory position C, Section l.accordance with NUREG 0133, Section'4.3.1;and Regulatory 66 AS~l~I Q'ki tS S'tS c, LOCATION Residences Dairy Cowsf Milk Goatsf Heat Animals Gardens Site Boundary.DIR E (98')SE (130')SE (130')ESE (115')E (97')ENE (67')MILES 1.4 2.6 2.6 1.8 1.8 0.4 TABLE 3-1 Critical Receptor Dispersion Parameters>

For Ground Level and Elevated Releases ELEVATED ELEVATED~0/(m-X)5.2 E-09b 7.0 E-10c 7.0 E-10c 1 7 E 09c 3.5 E-09c 4 4 E 08c,d~XI (sec/m3)1.8 E-07b 2.2 E-08c 2.2 E-08c 5.1 E-08c 1 0 E 07c~2 4 E-06b,d GROUNDe XA/(sec/m~)

4.02 E-07 6.00 E-08 6.00 E-08 1.16 E-07 2.53 E-07 6.63 E-06 GROUNDe D/(/(m X)8.58 E-09 1.64 E-09 1.64 E-09 8 3.54 E-09 5.55 E-09 6.35 E-08 a.These values will be used in dose calculations beginning in April 1986 but may be revised periodically to account for changes in locations of farms, gardens or critical residences.

b.Values based on 5 year annual meteorological data (C.T.Main, Rev.2)I c.Values based on 5 year average grazing season meteorological data (C.T..Main Rev.2)d.Value are based on most restrictive X/9 land-based sector (ENE).(C.T.Hain, Rev.2)e.Values are based on average annual meteorological data for the year 1985.f.Conservative location based on past dairy cow and goat milk history.68

'Cl IIlÃgL f t 1 Nuclide Kr-85 Kr-85m Kr-87 Kr-88 Kr-89 Kr-83m Xe-133 Xe-133m Xe-135 Xe-135m Xe-137 Xe-138 Xe-131m Ar-41 TABLE 3-2 Gamma Air and Whole Body Plume Shine Dose Factors'or Noble Gases Gambia Air Bi~mrad/r uCi/sec 2.23E-6 1.75E-3 1.02E-2 2.23E-2 2.50E-2 2.26E-6 2.80E-4 2.27E-4 2.62E-3 5.20E-3 2.30E-3 1.32E-2 1.74E-S 1.64E-2 Gamma Whole Body Vi m~rem/r uCi/sec 1.68E-3 9.65E-3 2.17E-2 2'1E-4 1.87E-4 2.50E-3 4.89E-3 2.20E-3 1.26E-2 1.47E-6 1.57E-2*Calculated in accordance with Regulatory Guide 1.109.(See Appendix B) k f-4g f TABLE 3-3 IMMERSION DOSE FACTORS*Nuclide K>~(l-Bad>'" Li(6-Skin)**

H>~(-Alr>***N>0>-A>r>*'*

Kr 83m Kr 85m Kr 85 Kr 87 Kr 88 Kr 89 Kr 90 Xe 131m Xe 133m Xe 133 Xe 135m Xe 135 Xe 137 Xe 138 Ar 41 7.56E-02 1.17E3 1.61El 5.92E3 1.47E4 1.66E4 1.56E4 9.15El':51E2 2.94E2 3.12E3 1.81E3 1.42E3 8.83E3 8.84E3 1.46E3 1.34E3'9.'73E3 2.37E3 1.01E4 7.29E3 4.76E2 9.94E2 3.06E2 7.11EZ 1.86E3 1.22E4 4.13E3 2.69E3 1~93E1 1.23E3 1.72E1 6.17E3 1.52E4 1.73E4 1.63E4 1.56E2 3.27E2 3.53E2 3.36E3'1.92E3 1.51E3 9.21E3 9.30E3 2.88E2 1.97E3 1.95E3 1.03E4 2.93E3 1.06E4 7.83E3 1.11E3 1.48E3 1.05E3 7.39E2 2.46E3 1.27E4 4.75E3 3.28E3*from, Table B-l.Regulatory Guide 1.109 Rev.1~**mrem/yr per uCi/m.***mrad/yr per uCi/m.70

~'5%.A<~c>lh~1%I NUCLIDE..BONE TABLE 3-4 Ri VALUES-INHALATION

-INFANT*~mreml r uCi/m LIVER, T.BODY TNYROID KIDNEY LUNG GI-LLI H 3 C 14 Cr 51 Mn 54 6.47E2 6.47E2 6.47E2 2.65E4 5.31E3 5.31E3 5.31E3 8.95E1.5.75E1 2.53E4 4.98E3 6.47f2 6.47E2 6.47E2 5.31E3 5.31E3 5.31E3 1.32El 1.28E4 3.57f2 4.98E3 1.00E6 7.06E3 Fe 55 1.97E4 1.17E4 3.33E3 Fe 59 1.36E4 2.35E4 9.48E3 Co 58 Co 60 1.22E3 1.82E3 8.02E3 1.18E4"Zn"65'.93E4-6.26E4"'3.11E4 8.69E4 1.09E3 1.01E6 2.48E4 7.77E5 1.11E4 4.51E6 3.19E4 3.25E4 6.47E5 5.14E4 Sr 89 3.98ES Sr 90 4.09f7 1.14E4 2.59E6 2.03E6 6.40E4 1.12E7 1.31E5 Zr 95 1.15E5 2.79E4 2.03E4*Nb 95 1.57E4 6.43E3 3.78E3 Mo 99 I 131 3.79E4 1.65E2 4.44f4 3.23E1 1.96E4 1.48E7'La 140 5.05E2'.00E2 5.15E1 Ce 141 2.77E4 1.67E4 1.99E3 Ce 144 3.19E6 1.21E6 1.76E5 Nd 147 7.94E3 8.13E3 , 5.00E2 I 133 1.32E4 1.92E4 5.60E3 3.56E6 Cs 134 3.96ES 7.03f5'.45E4 Cs 137 5.49E5 6.12E5 4.55E4 Ba 140 5.60E4 5.60E1 2.90E3 3.11E4 1.75E6 2.17E4 4.72E3 4.79E5 1.27E4 2.65E2 1.35ES 4.87E4 5.18E4 2.24E4 1.06E3 2.16E3 1.34El 1.60E6 3.84E4 1.68E5 8.48E4 5.25E3 5.17E5 2.16E4 5.38E5 9.84E6 1.48E5 3.15E3 3.22E5 3.12f4 1.90ES 7.97E4 1.33E3 1.72E5 7.13E4 1.33E3*Daughter Decay Product.**This and following Ri Tables Calculated in accordance with NUREG 0133, Section 5.3.1, except C 14 values in accordance with Regulatory Guide 1.109 Equation C-8.71 N" 1 I>>

TABLE 3-5 R)VALUES-INHALATION

-CHILD m~reml r uCf/m NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H 3 1.12E3 1.12E3 1.12E3 1.12E3 1.12E3 1,12E3 C 14 3'9E4 6.73E3 6.73E3 6.73E3.6.73E3 6.73E3.6.73E3" Cr 51'1.54E2 8:55E1 2.43E1 1.70E4 1.08E3 Hn 54 4.29E4 9.51E3 1.00E4 1.58E6 2.29E4 Fe 55 4.74E4 2.52E4 7.77E3 Fe 59 2.07E4 3.34E4 1.67E4 Co'58 Co 60 1.77E3 3.16E3 1.31E4 2.26E4 Zn 65 4.25E4 1.13ES 7.03E4 1.11E5 2.87E3 1.27E6 7.07E4 1.11E6 3.44E4 7.07E6 9.62E4 7.14E4 9.95E5 1.63E4 Sr 89 5.99E5 Sr 90 1.01EB Zr 95 1.90E5*Nb 95 2.35E4 Ho 99 4.18E4 9.18E3 1.72E4 6.44E6 3.70E4 6.55E3 1.72E2 4.26El 2.16E6 1.67E5 1.48E7 3.43E5 5.96E4 2.23E6 6.11E4 8.62E3 6.14E5 3.70E4 3.92E2 1.35ES 1.27E5 I 131 4.81E4 4.81E4 2.73E4 1.62E7 7.88E4 I 133 1.66E4 2.03E4 7.70E3 3.85E6 3.38E4 2.84E3 5.48E3 Cs 134 Cs 137 6.51ES 1.01E6 2.25E5 9.07E5'8.25E5 , 1.28E5 Ba 140 7.40E4 6.48E1 4.33E3*La 140 6.44E2 2'5E2 7'SEl Ce 141 3.92E4 1.95E4-2.90E3'Ce 144 6.77E6.2.12E6 3.61E5 Nd 147 1:OBE4'8.73E3 6.81E2 3.30E5 1.21E5 3.85E3 2.82E5 1.04E5 3.62E3 2.11E1 1.74E6.1.02E5 1.83ES 2.26E5 8.55E3 5.44E5 5.66E4 1.17E6 1.20E7 3.89ES 4.81E3 3.28E5 8.21E4*Daughter Decay Product.72 IJ I~a I I~I f If~II-I-" I~'I I I"I'I I I*'f 4 rI~I TABLE 3-6 Rt VALUES-INHALATION

-TEEN~mreml r uC)/m NUCLIDE" BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H 3-1.27E3 1.27E3 l.'27E3 1.27E3 1.27E3 1.27E3 C 14 2.60E4 4.87E3 4.87E3'4.87E3 4.87E3 4.87E3'4.87E3 Cr Sl 1.35E2 7.50E1 3.07E1'.10E4 3.00E3 Mn 54-5.11E4 Fe 55 3.34E4 2.38E4 Fe 59 1.59E4 3.70f4 Co 58-'.07E3 8.40E3 5.54E3 1.43E4 2.78E3 Co 60-1.51E4 1.98E4 Zn 65 3.86E4 1.34E5 6.24E4 1.27E4 1.98E6 6.68E4 1.24fS 6.39E3 1.53E6 1.78E5 1.34E6 9.52E4'.72E6 2.59E5 8.64E4 1.24E6 4.66E4 Sr 89 4.34f5 Sr 90 1.08EB Zr 95 1.46E5 4.58E4*Nb 95 1.86E4 1.03E4 Mo 99--1.69E2 1.25E4 6.68E6 3.15E4 5.66E3 3.22El 2.42E6 3.71E5 1.65E7 7.65fS 6.74E4 2.69E6 1.49E5 1.00E4 7.51ES 9.68E4 4.11E2 1.54E5 2.69E5 I 131 3.54E4 4.91E4 2.64E4 1.46E7 8.40E4 I 133 1.22E4 2.05E4 6.22E3 2.92E6 3.59E4 6.49E3 1.03E4 Cs 134 5.02E5 Cs 137 6.70E5 1.13E6 5.49E5 8.48E5 3.11E5 Ba 140 5.47E4 6.70El 3.52E3*La 140 4.79E2 2.36E2 6.26El Ce 141 2.84E4 1.90E4" 2.17E3 Ce 144 4.89E6 2.02E6 2.62ES Nd 147 7.86E3 8.56E3 5 13E2*Daughter Decay Product.73 3.75ES 1.46E5 9.76E3 3.04E5 1.21E5 8.48E3 2.28E1 2.03E6 2.29ES 2.14E5 4.87ES 8.88E3 6.14E5 1.26E5 1.21E6 1.34E7 8.64E5 5.02E3 3.72E5 1.82E5

~r'~fbi J TABLE 3-7 R)VALUES-INHALATION

-AOULT~mreml r uC)/m NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI"C 14'.82E4 3.41E3" Cr 51 3.41E3'.41E3 3.'41E3 1.00E2 5.95E1 2.28E1 H 3 1.26E3'.26E3 1.26E3 1.26E3 1.26E3 3.41E3 1.26E3 3.41E3" 1.44E4 3.32E3 Co 58-1.58E3 Co 60-1.15f4'.07E3 1.48E4 Zn 65 3.24f4 1.03ES 4.66f4 Mn S4-3.96E4 6.30E3 Fe 55 2.46f4 1.70E4 3.94E3 Fe S9 1.18E4 2.78E4 1.06E4 9.84E3 1.40E6 7.74E4 7.21E4 6.03E3 1.02E6 1.88ES 9.28E5 1.06E5 5.97E6 2.85E5 6.90E4 8.64E5 5.34E4 Sr 89 3.04E5 Sr 90'.92E7 Zr 95 1.07ES*Nb 95 1.41E4 3.44E4 7.82E3 8.72E3 6.10E6 2.33E4 4.21E3 7.74E3 5.05E5 1.04E5 1.40E6 3.50E5 9.60E6 7.22E5 5.42E4 1.77E6 1.50E5 Mo 99 1.21E2 2.30E1 2.91E2 9.12E4 2.48ES I 131 2.52E4 3.58E4 2.05E4 1.19E7 6.13E4 I 133 8.64E3 1.48E4 4.52E3 2.15E6 2.58E4 6.28E3 8.88E3 Cs 134 3.73ES Cs 137 4.78E5 8.48E5 7.28ES 6.21ES 4.28E5 Ba 140 3.90E4 4.90El 2.57E3'La 140 3.44E2 1~74E2 4.58E1 Ce 141 1.99E4 1.35f4 1.53E3 Ce 144 3.43E6 1.43E6 1.84ES'Nd'147'.27E3 6.10E3'3:65E2*Daughter Oecay Product.74 2.87ES 9.76E4 1.04E4 2.22E5 7.52E4 8.40E3 1.67E1 1.27E6 2.18E5 1.36ES 4.58ES 6.26E3 3.62ES 1.20E5 8.48E5 7.78E6 8.16E5 3.56E3 2.21E5 1.73E5 F li C sQ~-'I TABLE 3-8 R)VALUES-GROUND PLANE ALL AGE GROUPS m~mreml r 2 uC)/sec NUCLIDE H 3 C 14 Cr 51 Hn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65" Sr 89 Sr 90 Zr 95*Nb 95 Ho 99 I 131 I 133 Cs 134 Cs 137 Ba 140:*La 1.40 Ce 141 Ce 144 Nd 147..*Daughter Decay Product.TOTAL BODY 4.68E6 1.39E9 2.75E8 3.82E8 2.15E10 7.49E8 2.26E4 2.50E8 1.36EB 4.04E6 1.72E7 2.39E6 6.81E9 1.03E10 2.06E7 ,1.92E7 1.37E7 6.95E7 8.46E6 SKIN 5.53E6 1.63E9 3.23EB 4.47E8 2.53E10 8.62E8 2.62E4 2.90E8 1.61E8 4.67E6 2.09E7 2.91E6 7.94E9 1.20E10 2.35E7 2.18E7 1.54E7 8.03E7 1.01E7 75 tr NUCLIDE BONE LIVER TABLE 3-9 R)VALUES-CON MILK-INFANT m~mreml r uCi/sec T.BODY THYROID KIDNEY LUNG GI-LLI*H 3-3.10E3 3.10E3 3.10E3 3.10E3 3.10E3 3.10E3*C 14 3.23E6 6.89E5 6.89E5 6.89E5 6.89E5 6,89E5.'6.89E5 Cr 51 8.37E4 ,5.46E4.1.19E4 1.06E5 2.44E6 9.22E6 Mn 54-2.51E7 5.69E6 Fe 55 8.98E7 5.80E7 1.55E7 Fe 59 1.22EB 2.14ES 8.42E7 Co 58-1.39E7 3.47E7 5.56E6 2.83E7 7.36E6 6.31E7 1.02EB 3.47E7 1.40E8'.02E10 1.45E8 1.02E9 4.71E5 1.09E8 3.47E7 5.73E7 4.20E6 Co 60 5.90E7 1.39E8 Zn 65 3.53E9 1.21E10 5:58E9 5.87E9 2.02E&2.09E10 Sr 89 7.04E9 Sr 90 8.19E10 Zr 95 3.88E3 9.45E2 6.70E2*+Nb 95 3.14E5 1.29E5 7.48E4 Mo 99-1.05E8 2.06E7 1.02E3 9.27E4 1.58E8 I 133 1.70E7 2.48E7 Cs 134 2.41E10 4.49E10 7.27E6 4.51E9 2.92E7 1.16E10 4.74E9 1.22EB 1.09E10 4.41E9 1.27E8 2.87E4 7.42E4 2.97E7 4.54E9 2.88E9 6.23E6 Cs 137 3.47E10 4.06E10 Ba 140 1;21E8 1.21E5 I 131 1.36E9 1.60E9 7.06E8 5.27E11 1.87E+9**La 140 2;03El 7.99 Ce 141 2.28E4 1.39E4 Ce 144 1.49E6 6.10E5 2.06 1.64E3 8.35E4 Nd 147 4.43E2.4.55E2 2.79E1*mrem/yr per uCI/m3.**Daughter Decay Product.76 4.29E3 2.46E5 1.76E2 9;39E4-7.18E6 8.55E7 2.89E5

NUCLIOE BONE LIVER TABLE 3-10 Ri VALUES-CON MILK-CHILD m~mreml r 2 uCi/sec T.BODY THYROID KIDNEY LUNG GI-LLI*H 3-2.05E3 2.05E3 2.05E3 2.05E3 2.05E3 2.05E3*C 14 1.65E6 3.29E5 3.29E5 3.29f5 3.29E5 3.29E5 3.29E5 Cr 51 5-29E4 2.93E4 8.02E3 5.36E4 2.&OE6 Mn 54-1.35E7 3.59E6 Fe 55 7.43E7 3.94E7 1.22E7 Fe 59 6.55E7 1.06EB 5.28E7 Co 58-6.96E6 2.13E7 3.78E6 Co 60 2.89E7 8.52E7 Zn 65 2.63E9 7'OE9 4.35E9 4.41E9 Sr 89 3.70E9 SI 90 7.53E10 1.06EB 1.91E10 Zr 95 2.18E3 4.&OE2 4.27E2**Nb 95 1.6&E5 6.55E4 4.68E4 Mo 99 4.13E7 1.02E7 6.87E2 6.15E4 8.81E7 I 131.6.52EB 6.56EB , 3.73EB 2.17Ell 1.08E9 I 133 8.07E6 9.98E6 3.78E6 1.85E9 1.66E7 1.13E7 2.23E7 7.30E6 3.07E7 1.10E&4.06E7 1.60EB 1.23E9 1.43EB 1.01E9 5.01E5 1.21EB 3.41E7 5.84E7 4.02E6 Cs 137 2.17E10 2.08E10 Ba 140 5.&BE7 5.15E4 3.07E9 3.43f6 Cs 134 1.50f10 2.46E10 5.18E9 7.61E9 2.73E9 1.32E&6.78E9 2.44E9 1.30EB 1.68E4 3.07E4 2.98E7.**La 140 9.70 3.39 1.14 Ce 141 1.15E4 5.74E3 8.52E2 5.55E4 1.40EI Ce 144 1.04E6 3.26E5 Nd 147 2.24E2 1.8lf2 e*mrem/yr per uCi/m3.**Daughter Oecay Product.77 2.51E3 1.80E5 9.94E1 9.45E4 7.15E6 8.50E7 2.87E5 0 AT\>r 4 4 A 4 4 TABLE 3-11 Ri VALUES-CON MILK-TEEN m~mrem/r 2 uCi/sec NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI*H 3 1.29E3 1.29E3 1.29E3 1.29E3 1.29E3 1.29E3'C 14 6.70E5 1.34E5 1.34E5 1.34E5 1.34E5 1.35E5 1.34E5 Cr 51 2.59E4 1.44E4 5.68E3 3.70E4 4.35E6 Mn 54 9.02E6 1.79E6 Fe 55 2.96E7 2.10E7 4.89E6 Fe 59 2.82E7 6.59E7 2.55E7 2.69E6 1.85E7 1.33E7 9.08E6 2.08E7 1.56EB Co 58 4.55E6 1.05E7 Co 60 1.86E7 4.19E7 Zn 65 1.34E9 4.65E9 2.17E9 2.98E9 Sr 89 1.50E9 Sr 90 4.46E10 4.28E7 1.10E10 Zr 95 9.40E2 2.97EZ 2.04E2**Nb 95 7.45E4 Mo 99 4.13E4 2.27E7 2.27E4 4.32E6 4.36E2 4.01E4 5.19E7 , I 131 2.69EB*3.77EB 2.02E8 1.10E11 6.48EB I 133 3.32E6 5.64E6 1.72E6 7.87E8 9.88E6 6.28E7 2.42E8 1.97E9 1.78E8 1.25E9 6.85E5 1.77E8 4.06E7 7.45E7 4.26E6 Cs 134 6.49E9 1.53E10 7.08E9 Cs 137 9.02E9 , 1.20EIO Ba 140 2.43E7 2.98E4**La 140 4.05 1.99 4.18E9 1.57E6 5.30E-1 Ce 144 4.22E5 1.74E5 Nd 147 9.12E1 9.91E1*mrem/yr per uCi/m3.**Daughter Decay Product.2.27E4 5.94EO Ce 141 4.67E3 3.12E3 3.5&E2 78 4.85E9 1.85E9 4.08E9 1.59E9 1.90E8 i 1.71EB 1.47E3 1.04E5 5.82E1 1.14E5 8.92f 6 1.06E8 3.58E5 1.01E4 2.01E4 3.75E7 I'~i Jl~~'

TABLE 3-12 Ri VALUES-CON HILK-ADULT m~mreml r 2 uCi/sec NUCLIDE BONE LIVER*H 3 9.94E2 T.DODY THYROID KIDNEY LUNG 9.94E2 9.94E2 9.94E2 9.94E2 GI-LLI 9.94E2*C 14 3.63E5 7.26E4:.7.26E4 7.26E4 7.26E4 7.26E4 7.26E4 Cr 51 1.48E4 8'7E3 3.27E3 1.97E4 3.73E6 Hn 54-5'1E6 1.03E6 Fe 55 1.67E7 1.15E7 2.69E6 Fe 59 1.62E7 3.80E7 1.46E7 Co 58 2.70E6 6.06E6 Co 60 1.10E7'2.42E7 Zn 65 8.72E8 2.78E9 1.25E9 1.61E6 1.86E9 Sr 89 8.11E8 Sr 90 3.15E10 2.33E7 7.74E9 Zr 95 5.38E2 1.72E2 1.17E2**Nb 95 4.37E4 2.43E4 1.31E4 Ho 99 1.26E7 2.39E6 2.71f2 2.40E4 2.84E7 I 131 1.48E8;2.12E8=.1.22E8~6.95E10 3.63E8 I 133 1.82E6 3.16E6 9.64E5 4.65E8 5.52E6 1.66E7 6.43E6 6.6lf6 1.06E7 1.27E8 5.48E7 2.06E8 1.75E9 1.30E8 9.11E8 5.47E5 1.47E8 2.91E7 5.59E7 2.84E6 Cs 134 3.74E9 8.89E9 7.27E9 Cs 137 4.98E9 6.80E9 Ba 140 1.35E7 1.69E4**La 140 2.26 1.14 4.46E9 8.83E5 3.01E-1 Ce 141 2.55E3 1.72E3 1.95E2 Ce 144 2.29fS 9.58E4'.23E4 Nd 147 4.74E1 5.48E1 3.28EO*mrem/yr per uCi/m3.**Daughter Decay Product.79 8.00E2 5.68E4 3.20E1 8.35E4 6.58E6 7.75E7 2.63f5 2.88E9 9.55E8 1.56E8 2.31E9 7.68E8 1.32E8 5.76E3 9.70E3 2.78E7 Qlt~7f~

TABLE 3-13 Ri VALUES-GOAT MILK-INFANT m~mreml r uCi/sec NUCLIDE BONE LIVER T.BODY THYROID KIONEY LUNG GI-LLI<<H 3 6.33E3 6.33E3 6.33E3 6.33E3 6.33E3 6.33E3*C 14 3.23E6 6.89E5.6.89E5.6.89E5 6.89E5 6.89E5 6.89E5 Cr 51 1.00E4 6.56E3 1.43E3 1.28E4 2.93E5 Mn 54-3.01E6 6.82f5 Fe 55 1.17E6 7.54E5 2.01E5 Fe 59 1.59E6 2.78E6 1.09E6.Co 58-.1.67E6.4.16E6 Co 60-7.08E6 1.67E7 Zn 65 4.24E8 1.45E9 6.70E8 6.67E5 7.04E8 Sr 89 1.48f10 Sr 90.1.72E11 4.24E8 4.38E10 Zr 95'.66E2 1.13E2 8.04EI 1.22E2 1.11E4 1.89E7**Nb 95 3.77E4 1.55E4 8.97E3 2.47E6 Mo 99-1.27f7 le"I'131--1.63E9-',1.93E9'.47EB, 6.33E11 2.25E9-I 133 2.05E7 2.98E7 8.72E6 5.42E9 3.50E7 1.11E6 3'9E5 , 9.57E4 8'1E5 1.33E6 4.16E6 1.68E7 1.23E9 3.04E8 2.15E9 5.65E4 1.31E7 4.17E6 6.87E7 5.04E6 Cs 134 7.23E10 1.35E11 1.36E10..Cs 137 1.04E11" 1.22E11 8.63E9 Ba 140 1.45E7 1.45E4'7.48E5**La 140 2.430 9.59E-l 2.47E-l Ce 141 2.74E3 1.67E3 1.96E2 Ce 144 1.79E5 7.32E4 1.00E4 Nd 147 5.32E1 5.47E1 3.35EO*mrem/yr per uCi/m3.'*Daughter Decay Product.80 5.14f2 2.96E4 2.11El 1.13E4 8.62E5 1.03E7 3.46E4 3.47E10 1.42E10 3.66E8 3.27E10 1.32E10 3.81E8 3.44E3 8.91E3 3.56E6 f 4~W, i i I i A'*i fI~: f f k/i~'f~'"~<LQ'~)f I fg if fQ, NUCLIDE BONE LIVER TABLE 3-14 Ri VALUES-GOAT MILK-CHILD m~mreml r uCi/sec T.BODY THYROID KIDNEY LUNG GI-LLI*H 3-4.17E3 4.17E3 4.17E3 4.17E3 4.17E3 4.17E3*C 14 1.65E6 3.29E5 3.29E5 3.29ES 3.29E5 3.29E5 3.29E5 Cr 51 6.34E3 3.52E3 9.62E2 6.43E3 3.36E5 Hn 54-1.62E6 4.31E5 Fe 55 9.65E5 5.12E5 1.59E5 Fe 59 8.52E5 1.38E6 6.86E5 Co 58-8.35E5 2.56E6 Co 60 3.47E6 1.02E7 4.54E5 1.36E6 2.90E5 9.49E4 3.99E5 1.43E6 4.87E6 1.92E7 Zn 65 3.15E8 8.40EB 5.23EB 5.29E8 Sr 89 7.77E9 Sr 90.1.58E11 2.22E8 4.01E10 Zr 95 2.62E2 5.76E1 5.13El**Nb 95 2.02E4 7.86E3 Mo 99 4.95E6 5.62E3 1.22E6..I 131..7.83EB..7.87EB.4.47EB 8.25E1 7.38E3 1.06E7, 2.60E11 1.29E9 I 133 9.69E6 1.20E7 4.53E6 2.23E9 2.00E7 1.48E8 3.01E8 2.13E9 6.01E4 1.45E7 4.09E6 7.01E7 4.83E6.Cs 137 6.52E10..6.24E10 Ba 140 7.05E6 6.18E3 9.21E9 4.12E5 Cs 134 4.49E10 7.37E10 1.55E10 2.28E10 8.19E9 3.97E8 2.03E10 7.32E9 3.91E8 2.01E3 3.68E3 3.57E6**La 140 1.16 4.07E-1 1.37E-1 1.13E4 Ce 144 1~25E5 3.91E4 Nd 147 2.68E1 2.17E1*mrem/yr per uCi/m3.**Daughter Decay Product.6.66E3 1.68EO Ce 141 1.38E3-6.88E2 1.02E2 81 3.02E2 2.16E4 1.19E1 8.59E5 1.02E7 3.44E4 AA I II rp A Vf TABLE 3-15 Ri VALUES GOAT MILK TE N m~mreml r uCi/sec NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG*H 3-'.64E3 2.64E3 2.64E3 2.64E3 2.64E3*C 14 6.70E5 1.34E5 1..34E5 1.34E5 1.34E5 1.35E5 GI-LLI 2.64E3 1.34E5.Cr 51 3.1.1E3 1.73E3...6.82E2 4.44E3.5.23E5 Mn 54 1.08E6 2.15E5 Fe 55 3.85E5 2.73E5 6.36E4 Fe 59 3.67E5 8.57E5 3.31E5 Co 58-5.46E5 1.26E6 Co 60 2.23E6 5.03E6 Zn 65 1.61E8 5.58E8 2.60EB 3.23E5 3.57E8 Sr 89 3.14E9 Sr 90 9.36E10 8.99E7 2.31E10, Zr 95 1.13E2 3.56El 2.45E1**Nb 95 8.94E3 4.96E3~~Mo 99 2.72E6 2.73E3 5.19E5 5.23E'1 4.81E3 6.23E6 I I131:'.3.23E8 R 4.52EB.2.43E8 1.32E11 7.78EB I 133 3.99E6 6.76E6 2.06E6 9.44E8 1.19E7 2.22E6 1.73E5 1.18E5 2.70E5 2.03E6 7.53E6 2.91E7 2.36E8 3.74E8 2..63E9 8.22E4'2.12E7 4.87E6 8'4E7 5.12E6.Cs 137 2.71E10..3.60E10 Ba 140 2.92E6 3.58E3 1.25E10 1.88E5 Cs 134 1.95E10 4.58E10 2.13E10 1.46E10 5.56E9 5.70EB 1.23E10 4.76E9 5.12EB 1.21E3 2.41E3 4.50E6 Ce 144 5.06E4 2.09E4 Nd 147 1.09El 1.19El*mrem/yr per uCi/m3.**Daughter Decay Product.2.72E3 7.13E-1**La 140 4.86E-1 2.39E-l 6.36E-2 Ce 141 5.60E2 3.74EZ 4.30El 82 1.76E2 1.25E4 6.99EO 1.37E4 1.07E6 1.27E7 4.29E4

~4.k jg\~A I'l F4 TABLE 3-16 R)VALUES-GOAT MILK-ADULT m~mreml r uCl/sec NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG i GI-LLI*H 3.-2.03E3 2.03E3 2'3E3 2.03E3 2.03E3 2.03E3*C 14 3.63E5 7.26E4 7.26E4 7'6E4 7.26E4 7.26E4 7.26E4 Cr 51 1.78E3 1.06E3 3.92E2 2.36E3 4.48E5 Mn 54 6.50E5 1.24E5 Fe 55 2.17E5 1.50E5 3.49E4 Fe 59 2.10E5 4.95E5 1.90E5 Co 58-.-3.25E5 , 7.27E5 Co 60-1.32E6 2.91E6 Zn 65 1.05E8 3.33E8 1.51E8 1.93E5 2.23EB Sr 89 1.70E9 Sr 90 6.62E10 Zr 95 6.45E1 2.07E1**Nb 95 5.24E3 2.92E3 Mo 99 1.51E6~qI 131 41:78E8"., 2.54EB 4.89E7 1.63E10 1.40E1 1.57E3 2.87E5 3.25EI 2.88E3 3.41E6~1.46E8.8.34E10 4.36EB I 133 2.18E6 3.80E6 1.16E6 5.58EB 6.62E6 1.99E6 8.36E4 8 60E4 1.38E5 1.65E6 6.58E6 2.48E7 2.10E8 2.73E8 1.91E9 6.56E4 1.77E7 3.49E6 6.71E7 3.41E6 Cs 134 1.12E10 2.67E10 2.18E10.Cs 137 1.49E10" 2.04E10 1.34E10 Ba 140 1.62E6 2.03E3 1.06E5**La 140 2.71E-l 1.36E-1 3.61E-2 Ce 141 3.06E2 2.07E2 2.34E1 Ce 144 2.75E4 1.15E4 1.48E3 Nd 147 5.69EO 6.57EO 3.93E-1*mrem/yr per uCf/m3.**Daughter Decay Product.83 9.60E1 6.82E3 3.84EO 1.00E4 7.90E5 9.30E6 3.15E4 8.63E9 2.86E9 4.67E8 6.93E9 2.30E9 3.95E8 6.91EZ 1.16E3 3.33E6 I q p)'I 1~~C'I~4 4 NUCLIDE BONE LIVER TABLE 3-17 Ri VALUES-COW MEAT-CHILD m~mreml r 2 uCi/sec T.BODY THYROID KIDNEY LUNG GI-LLI*H 3 3.04EZ 3.04E2 3.04E2 3.04E2 3.04E2 3'4E2*C 14 5.29ES 1.06E5 1.06E5.1.06E5.1.06E5 1.06E5 1.06E5 Cr 51 4'.57E3 2.54E3 6.93E2 4.63E3 2.42E5 Mn 54 5.36E6 1.43E6 Fe 55 3.04ES 1.61EB 4.99E7 Fe 59 2.06E8 3.33E8 1.66ESCo 58 9.43E6 2.89E7 Co 60-4.67E7 1.38ES Zn 65 2.39ES 6.36E8 3.96E8 1.50E6 4.01E8 Sr 89 2.72ES Sr 90 7.01E9 7.77E6 1.78E9 Zr 95 1.53E6 3.35E5 2.98E5**Nb 95 1.64E6 Mo 99 6.38E5 6.11E4 4.56E5 1.51E4 4.80ES 5.99E5 1.31E5 I 133 1.88E-1 2.32E-1 8.78E-2 4.31E1 3.87E-1 I,131, 8.30E6<<8.35E6--4.75E6 2.76E9 1.37E7 4.50E6 9.11E7 2.98E7 9.64E7 3.46ES 5.50E7 2.59E8 1.12E8 1.05E7 9.44E7 3.50E8 1.18E9 5.06E4 7.43E5 9.35E-2 Cs 137 8.99E8 8.60E8 Ba 140 2.20E7 1.93E4 1.27ES 1.28E6 Cs 134 6.09E8 1.00E9 2.11ES 3.10ES 1.11ES 5.39E6 2.80ES 1.01ES 5.39E6 6.28E3 1.15E4 1.12E7**La 140 2.80E-2'.78E-3 3.30E-3 Ce 141 1.17E4 5.82E3 8.65E2 Ce 144 1.61E6 5.04E5" 8.57E4 Nd 147 5.93E3 4.80E3 3.72E2*mrem/yr per uCi/m3.**Daughter Decay Product.84 2.55E3 2.79E5 2.64E3 2.73E2 7.26E6 1.31E8 7.61E6

~C CL.I~C I C NUCLIDE BONE LIVER TABLE 3-18 Rt VALUES-CON HEAT-TEEN m~mreml r 2 uCi/sec T.BODY TNYROIO KIDNEY LUNG GI-LLI'H 3-2.52E2 2.52E2 2.52E2 2.52E2 2.52E2 2.52E2*C 14 2.81E5 5'2E4 5.62E4.5.62E4 5'2E4 , 5.62E4 ,.5..62E4 Cr 51 2.93E3 1.63E3 6.42E2 4.19E3 Hn 54-4.69E6 9.30E5 Fe 55 1.58ES 1.12ES 2.62E7 Fe 59 1.16ES 2.71ES 1.04ES Co 58-8.07E6 1.86E7.Co 60 3.93E7 8.86E7 Zn 65 1.59E8 5.52ES 2.58ES 1.40E6 3.54E8 7.12E7 8.53E7 Sr 89 1.44E8 Sr 90 5.42E9 4.12E6 1.34E9 Zr 95 8.59E5 2:71E5 1.86E5**Nb 95 9.49E5 5.26E5 2.90E5 Ho 99 4.39E4 8.38E3 3.98E5 5.10ES 1.01E5 I 133 1.01E-1 1.71E-1 5.23E-2 2.39E1 3.00E-1 I.131 m 0 4.48E6 6.27E6 3.37E6-1.83E9 1.08E7 4.93E5 9.62E6 4.86E7 6.40E8 1.11ES 5.12E8 2.34E8 1.71E7 1.52E8 6.25E8 2.25E9 7.87E4 1.24E6 1.30E-1 Cs 137 4.88E8 6.49E8 Ba 140 1.19E7 1.46E4 2.26E8 7.69E5 Cs 134 3.46ES 8.13ES 3.77ES 2.58E8 9.87E7'1.01E7 2.21E8 8.59E7 9.24E6 4.96E3 9.83E3 1.84E7 Ce 144 8.52E5 3.53E5 Nd 147 3.16E3 3.44E3*mrem/yr per uC)/m3.**Oaughter Oecay Product." 4.58E4 2.06E2**La 140 1.53E-2 7.51E-3 2.00E-3 Ce 141 6.20E3 4.14E3 4.76E2 85.1.95E3 2.11E5 2.02E3 4.31E2 1.18E7 2.14ES 1.24E7 C,

NUCLIDE BONE LIVER TABLE 3-19 Ri VALUES CON HEAT ADULT m~mreml r uCi/sec T.BODY THYROID KIDNEY LUNG GI-LLI'H 3-4.22f2 4.22E2 4.22E2 4.22E2 4.22E2 4.22E2*C 14 3.33E5 6.66E4 6.66E4 6.66E4 6.66E4 6.66E4 6.66E4 Cr 51'3.67E3 2.19E3.8.08E2 4.86E3..9.22E5 Mn 54-6.15E6 1'.17E6 Fe 55 1.95ES 1.36ES 3.14E7 Fe 59 1.45ES 3.4lfS 1.31ES Co 58-1.05E7 2.35E7 Co 60-5.07E7 1.12fS Zn 65 2.26ES 7.20ES 3.25ES 1.83E6 4.81ES Sr 89 1.70E8.Sr 90 8.38E9 4.89E6 2.06E9 2r 95 1.07E6 3.44E5 2.33E5**Nb 95 1.22E6 6.76E5 Ho 99-5.31E4 3.63ES 1.01E4 5.40E5 6.68ES 1.20E5*I 131'.39E6 , 7.71E6 ,: 4.42E6.2'3E9 1.32E7 I 133 1.21E-1 2.10E-1 6.40E-Z 3.09E1 3.66E-1 1.88E7 7.51E7 7.72E7 9.53E7 1.14E9 2.12E8 9.52E8 4.53E8 2.73E7 2.42E8 1.09E9 4.10E9 1.23E5 2.03E6 1.89E-1 ,Cs 137 5.88E8..8.04E8 Ba 140 1.44E7 1.81E4 5.27ES 9.45E5 Cs 134 4.35ES 1.03E9 8.45E8 3.35E8 1.11ES 1.81E7 2.73E8 9.07E7 1.56E7 6.16E3 1.04E4.2.97E7 Ce 144 1.01E6 4.23E5 Nd 147 3.59E3 4.15E3*mrem/yr per uCi/m3.'*Daughter Decay Product.5.43E4 2.48f2**La 140 1.86E-2 9.37E-3 2.48E-3 Ce 141 7.38E3 4.99E3 5.66EZ 86 2.32E3 2.51E5 2.42E3 6.88EZ 1.91E7 3.42ES 1.99E7 l~~~Ai~

TABLE 3-20 Ri VALUES-VEGETATION

-CHILD m~Nrem/r uC1/sec NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI*H 3-5.22E3 5.22E3 5.22E3 5.22E3 5.22E3 5.22E3*C 14 3.50E6 7.01E5'.01E5 7;01ES'.01ES 7.01E5 7.01E5 Cr 51 1.18f5'*6;54E4.79E4 1.19E5 6.25E6 Mn 54-6.65E8 1.77E8 1.86E8 5.58E8 Fe 55 8.01E8 4.25E8 1.32E8 Fe 59 4.01f8 6.49E8 3.23E8 Co 58 6.47E7 Co 60-'.78E8 1.98E8 1.12E9 ZA 65 8.13E8 2.17E9 1.35E9 1.36E9 2.40E8 7.87E7 1.88E8 6.76E8 3.77E8 2.10E9 3.80E8 Sr 89 3.74E10 Sr 90 1.24E12 1.07E9 3.15E11 Zr 95 3.92E6 8.63E5 7.68ES**Nb 95 4.10ES 1.60E5 1.14E5 Mo 99 7.80E6 1.93E6 1.23E6 1.50ES 1.67E7 m I 131'1.43E8 1.44E8 8.18E7 4.76E10 2.36E8 I 133 3.39E6 4.19E6 1~58E6 7.78E8 6.98E6 1.45f9 1.67E10 9.00E8 2.95E8 6'5E6 1.28E7 1.69E6 Cs 137 2.39E10 2.29E10 Ba'40 2.77EB 2.43E5 3.38E9'1;62E7 Cs 134 1.60E10 2.63E10 5.55f 9 8.15E9 2.92E9 1.42E8 7.46E9 2.68E9 1.43E8 7.91E4 1.45E5 1.40EB Ce 144 1.27EB 3.98E7 Nd 147 7.23E4 5.86E4*mrem/yr per uC1/m3.**Daughter Oecay Product." 6.78E6 4.54E3**La 140'3.'25E3 1.13f3 3.83E2 Ce 141 6.56ES 3.27E5 4.86E4 87 1.43E5 2.21E7 3.22E4 3.16E7 4.08EB 1.04E10 9.28E7 4

TABLE 3-21 Rl VALUES-VEGETATION-m~mreml r uCi/sec TEEN NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI'H 3-3.37E3.3.37E3 3.37E3, 3.37E3 3.37E3 3.37E3'C 14 1.45E6 2.91E5 2'1E5 2.91E5 2.91E5 2.91E5.2.91E5 Cr 51 6.20E4 3.44E4 1.36E4 8.85E4 1.04E7 Mn 54-4.55E8 9.01E7 Fe 55 3.26ES 2.31ES 5.39E7 Fe 59 1.81ES 4.22ES 1.63E8 1.36ES'.32E8 1.47E8 1.00E8 1.33EB 9.99EB Co 58-4.38E7 1.01E8 Co 60-2.49ES 5.60ES Zn 65 4.24E8 1.47E9 6.87E8 9.42ES Sr 89 1.57E10 Sr 90.7.51Ell 4.50ES 1.85E11 8.11E5 1.03E5 1.31E7 Zr 95 1.75E6 5.52E5 3.80E5**Nb 95 1.92E5 1.06E5 5.86E4 1.09E6 Mo 99 5.71E6" I 131 ,".7.70E7.1.08E8-5.79E7.3.14E10 1.86EB I 133 1.86E6 3.15E6 9.61E5 4.40ES 5.52E6 6.04EB 3.24E9 6.24EB 1.87E9 2.11E10 1.27E9 4.55EB 1.02E7 2.13E7 2.38E6 Cs 137 1.01E10..1.35E10 Ba 140 1.38EB 1.70E5 4.69E9 8.91E6 Cs 134 7.10E9 1.67E10 7.75E9 5.31E9 2.03E9 2.08EB 4.59E9 1.78E9 1.92EB 5.75E4 1.14E5 2.13EB**La 140 1.81E3 8.88E2 2.36E2 Ce 141 2.83E5 1.89E5 2.17E4 Ce 144 5.27E7 2.18E7 2.83E6 Nd 147 3.66E4 3.98E4 2.38E3*mrem/yr per uCl/m3**Daughter Decay Product.88 8.90E4 1.30E7 2.34E4 5.10E7 5.41EB 1.33E10 1.44E8 t'))l%V I~i if lit~l V)V(~F-4 t)I I*<)')<<rkiP A)~C A aj t t)l e it E'l TABLE 3-22 Ri VALUES-VEGETATION

-ADULT m~mrem/r 2 uCi/sec NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI*H 3-2.26f3 2.26E3 2.26E3 2.26E3 2.26E3 2.26E3*C 14 8.97ES 1.79E5 1.79E5.1.79E5 1,79E5 1.79E5.1.79E5 Cr 51 4.67E4 2.79E4 1.03E4 6.'19E4 1.17E7 Mn 54-3.13f8 5.97E7 Fe 55 2.10ES 1.45ES 3.38E7 Fe 59 1.27ES 2.99ES 1.15E8 9.31E7 9.59f8 8.08E7 8.31E7 8.35E7 9.96E8 Co 58-, 3.09E7 6.92E7 Co 60-1.67E8 3.69ES Zn 65 3.18E8 1.01E9 4.57E8 6.76ES Sr 89 1.03E10 Sr 90 6.04Ell 2.96E8 1.48E11 Zr 95 1.19E6 3.83E5 2.59E5*Nb 95 1.42ES.7.91.E4 Mo 99-6.22E6 4.25E4 1.18E6 6.00E5 7.82E4 1.41E7 I'131 8;09E7', 1.16ES 6.63E7 3.79E10 1.98ES I 133 2.00E6 3.48E6 1.06E6 5.11ES 6.07E6 6.26EB 3.14E9 6.36EB 1.65E9 1.75E10 1.21E9 4.80ES 1.44E7 3.05E7 3.13E6 Cs 134 4.66E9 1.11E10 9.07E9 3.59E9 1.19E9 1.94EB.Cs 137 6.36E9..8.70E9 Ba 140 1.29ES 1.62ES 5.70f9 8.43E6 Ce 144 3.29E7 1.38f7 Nd 147 3.36E4 3.88E4*mrem/yr per uCi/m3**Daughter Decay Product.1.77E6 2.32E3**La 140 1~98E3 9.97E2.2.63E2 Ce 141 1.97E5 1.33ES 1.51E4&9 2.95E9 5.49E4 6.19E4 8.16E6 2.27E4 9.25E4 2.65ES 7.32E7 5.10EB 1.11E10 1.86E8 9.81EB 1.68f8 I'I 1 lk.w4 C4,'I$h f 5.g e"*F 8"~'*VI~C E Nine Mile Point Nuclear Station Radiological Environmental Monitoring Program Sampling Locations Table 5.1 Type of Sam le Radioiodine and Particulates (air)Radioiodine and Particulates (air)Radioiodine and Particulates (air)Radioiodine and Particulates (air)Radioiodine and Particulates (air)*Map Location (Env.Collection Site Pro ram No.)Location Nine Mile Point Road North (R-1)1.8 mi 9 88'Co.Rt.29 (R-3)1.5 mi 9 132'.SE Village of Lycoming, NY (R-4)1.8 mi 8 143'E Hontario Point Road (R-5)16.4 mi 9 42'E Co.Rt.29&Lake Road (R-2)1.1 mi 8 104'SE"Direct'Radiation

'(TLD)'6 Direct Radiation (TLD)7 Direct Radiation (TLD)8 Direct Radiation (TLD)Direct Radiation (TLD)Direct Radiation (TLD)Direct Radiation (TLD)10 ll 12 Direct Radiation (TLD)13 Direct Radiation (TLD)'4 Direct Radiation (TLD)15 Direct Radiation (TLD)16 Direct'Radiation (TLD)17 Direct Radiation (TLD)18 North Shoreline Area (75)North Shoreline Area (76)North Shoreline Area (77)North Shoreline Area (23)JAF East Boundary (78)Rt.29 (79)Rt.29 (80)Hiner Road (81)Miner Road (82)Lakeview Road (83)Lakeview Road (84)0.1 mi 9 5'~0.1 mi 9 25'NE 0.2 mi 9 45'E 0.8 mi 9 70'NE 1.0 mi 9 90 E 1.1 mi 9 115'SE 1.4 mi 8 133'E 1.6 mi 9 159'SE 1.6 mi 8 181'1.2 mi 9 200'SW 1.1 mi 8 225'W Site Meteorological Tower (7)0.7 mi 9 250 WSW Energy Information Center.(18)0.4 mi.8 265;W;*Map-See Figures 5.1-1 and 5.1-2 h I~I 4 E.0)~Cj Fc' Nine Mile Point Nuclear Station Radiological Environmental Monitoring Program Sampling Locations Table 5.1 (Continued)

Type of Sam le'Map Location (Env.Collection Site Pro ram No.)Location Direct Radiation (TLD)19 Direct Radiation (TLD)20 Direct Radiation (TLD)21 Direct Radiation (TLD)22 Direct Radiation (TLD)23 Direct Radiation (TLD)24 Direct Radiation (TLO)25'Direct Radiation.(TLD), 26 Direct Radiation (TLD)27 Direct Radiation (TLO)28 Direct Radiation (TLO)29 Direct Radiation (TLD)30 Direct Radiation (TLD)31 Direct Radiation (TLD)32 Direct Radiation (TLO)33 Direct Radiation (TLD)34 Direct Radiation<TLD)35 Direct Radiation (TLD)36 Direct'adiation (TLD)37 Surface Water 38 Surface Hater 39 North Shoreline (85)North Shoreline (86)-North Shoreline (87)Hickory Grove (88)Leavitt Road (89)Rt.104 (90)Rt.51A (91)Maiden Lane Road (92)Co.Rt.53 (93)Co.Rt.1 (94)Lake Shoreline (95)Phoenix, NY Control (49)S.W.Oswego, Control, (14)Scriba, NY (96)Alcan Aluminum, Rt.1A (58)Lycoming, NY (97)New Haven, NY<56)0.2 mi 9 294'NH 0.1 mi 8 315 NW.0.1 mi 8 341.'NNW 4.5 mi 9 97, E, 4.1 mi 8 ill'SE 4.2 mi 9 135'E 4.8 mi 8 156'SE 4.4 mi 8 183'4.4 mi 9 205'SH 4.7 mi 9 223'H 4.1 mi 8 237 WSH~19.8 mi 8 170'12.6 mi 8 226 SH 3.6 mi 8 199'SH 3.1 mi 9 220'H 1.8 mi 8 143'E 5.3 mi 9 123'SE Lake Road (98)OSS Inlet Canal (NA)JAFNPP Inlet Canal (NA)1.2 mi 9 101'7.6 mi 9 235'H 0.5 mi 8 70'NE H.Boundary, Bible Camp (15)0.9 mi 8 237'SH (NA)not applicable

  • Map See Figures 5.1-1 and 5."l-2 w't h 7 pV Nine Mile Point Nuclear Station Radiological Environmental Monitoring Program Sampling Locations Table 5.1 (Continued)

Type of Sam le*Map Location (Env.Collection Site Pro ram No.)Location'horeline Sediment Fish Fish Fish Hi lk Mi 1 k Mi 1 k Milk Food Product Food Product Food Product Food Product Food Product Food Product Food Product (CR)40 41 42 43 44 45 46 47 48 49 50>>51't 52 53 Sunset Bay Shoreline (NA)NMP Site Discharge Area (NA)NMP Site Discharge Area (NA)Oswego Harbor Area (NA)Milk Location¹50 Milk Location¹7 Milk Location¹16 Milk Location¹65 Produce Location¹6**(Bergenstock)(NA).Produce Location¹1**(Culeton)(NA)Produce Location¹2**(Vitullo)(NA)Produce Location¹5**(C.S.Parkhurst)(NA)Produce Location¹3**(C.Narewski)Produce Location¹4**(P.Parkhurst)(NA)Produce Location¹7**(Mc Hillen)(NA)1.5 mi 8 80'0.3 mi 9 315'N and/or 0.6 mi 8 55'E 6.2 mi 8 235'H 8.2 mi 9 93'5.5 mi 8 107'SE5.9 mi 8 190'17.0 mi 8 220'H 1.9 mi 8 141'E 1.7 mi 8 96'1.9 mi 9 101'1.5 mi 8 114'SE 1.6 mi 8 84'2.1 mi 9 110'SE 15.0 mi 8 223 SN Fb Nine Mile Point Nuclear Station Radiological Environmental Monitoring Program Sampling Locations Table 5.1 (Continued)

Type of Sam le*Map Location (Env.Collection Site Pro ram No.)Location Food Product (CR)Food Product Food Product Food Product Food Product 55 56 57 58 59 Produce Location¹8**(Denman)(NA)Produce Location¹9*'O'onnor)(NA)Produce Location¹10**(C.Lawton)(NA)Produce Location¹11**(C.R.Parkhurst)(NA)Produce Location¹12**(Johnson)(NA)12.6 mi 9 225'W 1.6 mi 8 171'2.2 mi 8 123 ESE 2.0 mi 8 112'SE 1.9 mi 8 103 ESE Food Product (CR)60" Produce Location¹13**(Flack)(NA)15.6 mi 8 225'W Food Product 61 Produce Location¹14*'Dickenson)(NA)1.7 mi 8 82'Food Product 62 Produce Location¹15**(Whaley)(NA)1.7 mi 9 136'E*Map-See Figures 5.1-1 and 5.1-2**Food Product Samples need not necessarily be collected from all listed locations.

Collected samples will be of the highest calculated site average D/Q.(N/A)not applicable CR Control Result (location) t)y II=-E%,$, 144=N~~r gk q1 hf t~Wy~y<a%~P~~(AI 0 N 10 12 16 16 1 6 LAK6 OH AR.gk 6 (C TOWER)/0 5 (l)W,ll~III Cwnasweel 5eeylo LecetNA 5W-~c (h9-~~160+tsaao lapis Iroa%n FIGURE 5.I-I Nine Mlle Point On-Site Nep p ch 3I I I%I~II%%~~~PIN oE'0 5 2 2 94

('I l 0 pl 0 Page of 2 cs o~a FIGURE 5.I"2 NINE MiLE POINT OFF-SITE MAP (Ii88)s 5*N D Y C a E~nnOODC sk lo ocnoc oo woco s I.EQEIID UO OossseNylasae

...,....~j Tera nesaa.coo o v assoc ones...nsoseeas Enslconosoncol Sosnol~Locoilon LAICE ONTARIO~~Oases beni Cs~s~assaa Oss Ossa s Sole ss S salsa C~s ss a ssN s~eaers Cassss*I.O I/s sr Seas I X~r!~i'CalgC~E 4'o I-.Jl I C s sarO~~O Sl~s I ic 5 w a, I Seas o V E H a)s\Noslso qX I c.W~...scales ssoss s~p h IIE, I'w!s-'r)g'@jan' osq cj~~s c a v s N I s M ke X I io C~0I I~sI/aloe see<<~sw~sole~<<ss o 0 oo lw ss<<ae 4" Sess'Cocos s I 4 Pe lea 1 44 P~R I as se o4 A R M~4s N v I oa s<<~444 s s N N I R A l R A H 4~Ceatral~aease s I loess R o o C 0 H s ee eea re SS a aSa COlaeH~e ao~e ae 4~4~W~~'IT Fe aoaee ae aso444 aseaa 0 ease o eeoc~e<<e44 a~I D Figure 5.i-2 Pape 2 of 2

-r APPENDIX A LIQUID DOSE FACTOR DERIVATION 97 1l" IP"==+**4 QVf p ly Appendix A Liquid Effluent Dose Factor Derivation, Aiat Aiat (mrem/hr per uCi/ml)which embodies the dose conversion factors, pathway transfer factors (e.g., bioaccumulation factors), pathway usage factors,'and dilution factors for the points of pathway origin takes into account the dose from ingestion of fish and drinking water.The total body and organ dose conversion factors for each radionuclide will be used from Table E-11 of Regulatory Guide 1.109.To expedite time, the dose is calculated for a maximum individual instead of each age group.The maximum individual dose factor is a composite of the highest dose factor, Aiat, of'ach age group a, organ t and nuclide i, hence Ait.The equation for calculating dose contributions given in Section, 2.3 requires the use of the composite dose factor Ait for each nuclide, i.It should be noted that the fish ingestion pathway is the most significant pathway for dose from, liquid effluents.

The water consumption and the external'sediment exposure pathways are included-for consistency with Unit 1 technical specifications.

The dose factor equation for a fresh water site is: Aiat Ko (Uw(e-i Pw)+UfBFi(e i Pf)](DFL)iat

+Dw t gt..:+69.3 UsW e~i Ps(1-e-i b)(DFS)i (Ds)(gi).Hhere: Aiat Ko Uw Uf Us (DFL)iat (DFS)i Dw Ds Is the dose factor for nuclide i, age group a, total body or organ t, for all appropriate pathways, (mrem/hr per uCi/ml)Is the unit conversion factor, 1.14E5 1E6pCi/uCi x 1E3 ml/kg-:-8760 hr/yr Hater consumption (1/yr);from Table E-5 of Reg.Guide 1.109 Fish consumption (Kg/yr);from Table E-5 of Reg.Guide 1.109 Sediment Shoreline Usage (hr/yr);from Table E-5 of Reg.Guide 1.109 Bioaccumulation factor for nuclide, i, in fish, (pCi/kg per pCi/1), from Table A-1 of Reg.Guide 1.109 Dose conversion factor for nuclide, i, age group a, total body or organ t, (mrem/pCi);

from Table E-ll of Reg.Guide 1.109 Dose conversion factor for nuclide i and total body, from standing on contaminated ground (mrem/hr per pCi/m2);from Table E-6 of Reg.Guide 1.109 Dilution factor from the near field area within one-quarter mile of the release point to the potable water intake for the adult water consumption.

This is the Metropolitan Hater Board, Onondaga County intake structure located west of the City of Oswego.(Unitless)

Di.lution factor from the near field area within one quarter mile of the release point to the shoreline deposit (taken at the same point where we take environmental samples 1.5 miles;unitless)98 4%4 k o~.v l, 7 pa":e II~

Appendix A (Cont'd)tpw tpf or tps tb Average transit time required for each nuclide to reach the point of'exposure for internal dose, it is the total time el,apsed from release of the nuclides to either ingestion for water (w)and fish (f)or shoreline deposit'(s), (hr)Length of time the sediment is exposed to the contaminated water, nominally 15 yrs (approximate midpoint of facility operating life), (hrs).decay constant for nuclide i (hr-1)Shore'width factor (unitless) from Table 1-2 of Reg.Guide 1.109 Example Ca 1 cu1 ation For I-131 Thyroid Dose Factor for an Adult from a Radwaste liquid effluents exposure: (OFS)i 2.80E-9 mrem/hr per pCi/m2 (DFL)iat 1.95E-3 mrem/pCi tpw 30 hrs.(w water)BFi 15 pCi/Kg per pCi/1 tpf 24 hrs.(f fish)Uf 21 Kg/yr tb 1.314E5 hr (5.48E3 days)Ow 40 unitless Uw 730 1/yr Ds 12 unitless Ko 1.14E5 (Ci/uCi)(ml/k

)Us 12 hr/yr (hr/yr)N~.3~i.3 61E-3hr-1 tps 5.5 hrs (s Shoreline Sediment)These values will yield an Aiat Factor of 6.79E4 mrem-ml per uCi-hr as listed in Table 2-4.It should be noted that only a limited number of nuclides are listed on Tables 2-1 to 2-8.These are the most common nuclides encountered in effluents.

If a nuclide is.detected for which a factor is not listed, then it will be calculated and includhd in a revision to the ODCH.In addition, not all dose factors for each age group are used for the dose calculations..

A maximum individual is used, which is a composite of the maximum dose factor"'of each age g'oup for each organ as reflected in the applicable chemistry procedures.

99 0

APPENDIX 8 PLUME SHINE DOSE FACTOR DERIVATION 100 X, tl"n+4 4.J+"

APPENDIX B For elevated releases the plume shine dose factors for gamma air (Bi)and whole body (Vi), are calculated using the finite plume model with an elevation above ground equal to the stack height.To calculate the plume shine factor for gamma whole body doses, the gamma air dose factor is ad)usted for the attenuation of tissue, and the ratio of mass absorption coefficients between tissue and air.The equations are as follows: Gamma Air sl-$<ua<la s R8 Vs~Whole Hod Vi 1.11SFBie-uatd where: K*conversion factor (see below for actual value).td tissue depth (g/cm2)ua energy absorption coefficient (cm-i;air for Bi, tissue for Vi)E Energy of gamma ray per disintegration (Mev)Vs average wind speed for each stability class (s), m/s e R'ownwind di,stance (site boundary, m)sector width (radians)SF shielding factor from structures (unitless) s subscript for stability class Is I function Il+kI2 for each stab)lity class.(unitless, see Regulatory Guide 1.109)Fraction of the attenuated energy that is actually absorbed in air (see Regulatory Guide 1.109, see below for equation)Ratio of mass absorption coefficients between tissue and air.l 1.6 E-6~er Mev 00~er g-ragd K conversion factor 3.7 E10 dis Ci-s 293 g I*m/3.46 k~u-ua ua where: u energy attenuation coefficient (cm-1;air for Bi, tissue for Vi)101 "2j APPENDIX 8 (Cont'd)There are seven stability classes, A thru F.The percentage of the year that each stability class occurs is taken from the U-2 FSAR.From this data, a plume shine dose factor is calculated for each stability class and each nuclide, multiplied by its respective fraction and then summed.The wind speeds corresponding to each stability class are, also, taken from the U-2 FSAR.To confirm the accuracy of these values, an average of the 12 month wind speeds for 1985, 1986, 1987 and 1988 was compared to the average of the FSAR values.The average wind speed of the actual data.is equal to 6.78 m/s, which compared favorably to the FSAR average wind speed equal to 6.77 m/s.,The average gamma energies were calculated using a weighted average of all gamma energies emitted from the nuclide.These energies were taken"fromthe handbook"Radioactive Decay Data Tables", David C.Kocher.These energies compared favorably to those given in Table 1-1.The absorption (ua)and attenuation (u)coefficients were calculated by multiplying the mass absorption (ua/g)and mass attenuation (u/P)coefficients given in the Radiation Health Handbook by the air density equal to 1~293 E-3 g/cc or the tissue density of 1 g/cc where applicable.

The downwind distance is the site boundary.102 5 i'~OL id' APPENDIX B (Cont'd)SAMPLE CALCULATION Ex.Kr-89 F STABILITY CLASS ONLY-Gamma Air-DATA E ua a U e-o~~k~u-ua~.871 ua R~644m k.46 Vf 5.55 m/sec 2.22 2.943 E-3m-1 5.5064E-3m-l

.39 19m.......vertical plume spread taken from"Introduction to Nuclear, Engineering", John R.LaMarsh-I Function U~-.06 I 1.33 I2~.45 I~Il+kI2~.33+(.871)(.45)~.72~er s Bi 0.46 (Ci-sec)(Mev

)(2.943E-3m-l)(2.22(Mev))(.72)(g/m)(~er s)(5.55 m/s)(.39)(644m)(g-rad)1.55(-6)rad/s (3600 s/hr)(24 h/d)(365 d/)(lE3mrad/rad)

Ci/s (1E6uCi)Ci 2.50(-2)~mrad/r uCi/sec 103 5'c APPENDIX C DOSE PARAMETERS FOR IODINE 131 and 133, PARTICULATES AND TRITIUM 104 p"'a eW V II Q: V IT"I~P+1I a<<,b,y,"

APPENDIX C DOSE PARAHETERS FOR IODINE-131 AND-133, PARTICULATES AND TRITIUH This appendix contains the methodology which was used to calculate the organ dose factors for I-131, I-133, particulates, and tritium.The dose factor, Ri, was calculated using the methodology outlined in NUREG-0133.

The radioiodine and particulate Technical Specification (Section 3.6.15)is applicable to the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposure occurs, i.e., the critical receptor.The inhalation and ground plane exposure pathways are considered to.exist at all locations but the landsite boundary critical location will be used for dose purposes.The grass-goat-milk, the grass-cow-milk, grass-cow-meat, and vegetation pathways are considered to exist at critical specific locations.

Hashout was calculated and determined to be negligible.

Ri values have been calculated

'~for,the-adult;,teen, child and infant age groups for all pathways.The methodology used to calculate these values follows: A.l Inhalation Pathwa Ri(I)where:~K(BR)a(DFA)iat Ri (I)(BR)a (DFA)iat dose factor for each identified radionuclide i of the organ of interest (units mrem/hr per uCi/m3);a constant of unit conversion, lE6 pCi/uCi Breathing rate of the receptor of age group a, (units m3/yr);The inhalation dose factor for nuclide i age group a, and total body or organ t (units mrem/pCi).

105 V l'U C$1 0 APPENDIX C (Cont'd)The breathing rates (BR)a for the various age groups, as given in Table E-5 of Regulatory Guide 1.109 Revision 1, are tabulated below.A e Grou (a)Infant Breathin Rate (m3~/r)1400 Chi 1 d 3700 Teen 8000 Adult 8000 Inhalation dose factors (DFAi)a for the various age groups are given in Tables E-7 through E-10 of Regulatory Guide 1.109 Revision 1.A.2 Ground Plane Pathwa-jilt Ri(G)K'K(SF)(DFG)i (1-e)where: Ri(G)dose factor for the ground plane pathway for each identified radionuclide i for the organ of interest (units-m2-mrem/yr per uCi/sec)K'l I a constant of unit conversion, 1E6 pCi/uCi;a constant of unit conversion, 8760 hr/year;it the radiological decay constant for radionuclide i, (units sec-1)li ," the exposure time, sec, 4.73EB sec (1S years);(DFG)i the ground plane dose conversion factor for radionuclide i(units mrem/hr per pCi/m2)SF the shielding factor (dimensionless);

106 J giga N ,(4 s i, wr+lcrc~~w i~: a.s t 4 44 APPENDIX C (Cont'd)A shielding factor of 0.7 is discussed in Table E-15 of Regulatory Guide 1.109 Revision 1.A tabulation of OFGi values is presented in Table E-6 of Regulatory Guide 1.109 Revision l.A.3 Grass-(Cow or Goat)-Milk Pathwa R<<C)K'()f~<U<)>Fe(r)(DFL)le fpfe+<)gaffe)e-<th e ltf<>~+qw)i"I where: Ri<C)K'f Uap Yp Ys e" (OFL)iat th dose factor for"the cow milk or goat milk.pathway, for=each-identified radionuclide i for the organ of interest, (units-m2-mrem/yr per uCi/sec)a constant of unit conversion, 1E6 pCi/uCi;The cow's or goat's feed consumption rate, (units Kg/day-wet weight)the receptor's milk consumption rate for age group a, (units-liters/yr);

'he agricultural productivity by unit area of pasture feed grass, (units kg/m2);the agricultural productivity by unit area of stored feed, (units kg/m2)the stable element transfer coefficients, (units pCi/liter per pCi/day);fraction of deposited activity retained on cow's feed grass;the ingestion dose factor for nuclide i, age group a, and total body or organ t (units mrem/pCi);

'the radiological'ecay constant for radionuclide i, (units sec-1);the decay constant for removal of activity on leaf and plant surfaces by weathering equal to 5.73E-7 sec-1 (corresponding to,a 14 day ha 1 f-1 i f e);th'e transport time from pasture to cow or goat, to milk, to receptor, (units sec);the transport time from pasture, to harvest, to cow or goat, to milk, to receptor (units sec);107 I'a>fig$p~k II'l'.M>1+'t tf APPENDIX C (Cont'd)fp fraction of the year that the cow or goat is on pasture (dimensionless);

fs fraction of the cow feed that is pasture grass while the cow is on pasture (dimensionless);

Milk cattle and goats are considered to be fed from two potential sources, pasture grass and stored feeds.Following the development in Regulatory Guide 1.109 Revision 1, the value of fs is considered unity in lieu of site specific information.

The value of fp is 0.5 based on 6 month grazing period.This value for fp was obtained from the environmental group.Table C-1 contains the appropriate values and their source,in Regulatory Guide 1.109 Revision l.The concentration of tritium in milk is based on the airborne concentration rather than the deposition.

Therefore, the RT(C)is based on X/Q: RT(C)~K'KmQfUap(DFL)iat 0.75(0.5/H)

'where: RT(C)dose factor for the cow or goat milk pathway.for tritium for the organ of interest, (uni ts mrem/yr per uCi/m3);Ka constant of unit conversion, lE3 g/kg;H-'bsolute humidity of the atmosphere, (units g/m3);0.75 the fraction of total feed that is water;0.5 the rati'o of the specific activity of the feed grass water to the atmospheric water.Other values are given previously.

A site specific value of H equal to 6.14 g/m3 is used.This value was obtained from the environmental group"using actual'site data.108 h'I f I'L 1',1,'I'>TV+~IV, 4 i/I<<AVHl-Wf I~'I Q'II V APPENDIX C (Cont'd)A.4 Grass-Cow-Meat Pathwa Ri(H)~K'QfUap Ff(r)(DFL)iat (s~+~)-4 tf 5 ff (1-ff)e p+e Ri(H)dose factor for the meat ingestion pathway for radionuclide i for any organ of interest, (units m~-mrem/yr per uCi/sec);Ff the stable element transfer coefficients, (units days/Kg);Uap the receptor's meat consumption rate for age group a, (units kg/year);th the transport time from harvest, to cow, to receptor, (units sec)tf the transport time from pasture, to cow, to receptor, (units sec)All other terms remain the same as defined for the milk pathway.Table C-2 contains the values which were used in calculating Ri(H).The concentration of tritium in meat is based"on airborne concentration rather than'deposition.

Therefore, the RT(H)is based on X/Q.RT(H)~K K FfQfUap(DFL) i at k0 75(0~5/H))where: RT(M)dose factor for the meat ingestion pathway for tritium for any organ of interest, (units mrem/yr per uCi/m3).All other terms are defined above.A.S Ve etation Pathwa"'.'",'"'The"i'n'tegrated'concentration in vegetation consumed by man follows the expression developed for milk.Han is considered to consume two types of vegetation (fresh and stored)that differ only in the time period between harvest and, consumption, therefore:

.'Ri(V)K'v(ki+Xw)(DFL)iat UL)aFLe+US)aFge 109 (k wlw 3 1)

APPENDIX C (Cont'd)where: Ri.<V)dose factor for vegetable pathway for radionuclide i for the organ of interest, (units m~-mrem/yr per uCi/sec);K'L)Us)th a constant of unit conversion, lE6 pCi/uCi;the consumption rate of fresh leafy vegetation by the receptor in age group a, (units kg/yr);the consumption rate of stored vegetation by the receptor in age group a (units kg/yr).the fraction of the annual intake of fresh leafy vegetation grown local ly;the fraction of the annual intake of stored vegetation grown locally;the average time between harvest of leafy vegetation and its consumption, (units sec);the average time between harvest of stored vegetation and its consumption, (units-sec);Yv*the vegetation area density,<units kg/m~);All other factors are defined previously.

Table C-3 presents the appropriate parameter values and their source in Regulatory Guide 1.109 Revision 1.In lieu of site-specific data, values for fL and fg of, 1.0 and 0.76, respectively, were used in the calculation.

These values were obtained from Table E-15 of Regulatory Guide 1.109 Revision l.110

'k g*II APPENDIX C (Cont'd)The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition.

Therefore, the RT(V)is based on X/Q: RT(V)~K'K")fL+Us)a f DFL)iat 0.75(0.5/H) where: RT(V)dose factor for the vegetable pathway for tritium for any organ of interest, (units mrem/yr per uCi/m3).All other terms are defined in preceeding sections.

Pjg 1'V V TABLE C-1 Parameters for Grass-(Cow or Goat)-Hilk Pathways Parameter Qf (kg/day)(OFL)iat (mrem/pCi)

Fm (pCi/liter per pCi/day)Ys (kg/m2)Yp (kg/m2)'h (seconds)tf (seconds)Uap (liters/yr)

Value 50 (cow)6 (goat)1.0 (radioiodines) 0.2 (particulates)

Each radionuclide Each stable element 2.0 0.7 7 78 x 106 (90 days)1.73 x 105 (2 days)330 infant 330 child 400 teen 310 adult Reference (Re.Guide 1.109 Rev.1)Table E-3 Table E-3 Table E-15 Table E-15 Tables E-11 to E-14 Table E-1 (cow)Table E-2 (goat)Table E-15 Table E-15 Table E-15 Table E-15 Table E-5 Table E-5 Table E-5 Table E-5 112 0 7~F h'l'h f'.

TABLE C-2 Parameters for the Grass-Cow-Heat Pathway Parameter ff (pCi/Kg per pCi/day)"ap (Kg/yr)<DFL)iat (mrem/pCi)

Yp (kg/m)Ys<kg/m2)th (seconds)tf (seconds)Qf (kg/day)Value 1.0<radioiodines) 0.2 (particulates)

Each stable element 0 infant 41 child 65 teen 110 adult Each radionuclide 0.7 2.0 7.78E6 (90 days)1.73E6 (20 days)50 Reference (Re.Guide 1.109 Rev.1)Table E-15 Table E-15 Table E-1 Table E-5 Table E-5 Table E-5 Table E-5 Tables E-ll to E-14 Table E-15 Table E-15 Table E-15 Table E-15 Table E-3 113

~A CA f i/'1 TABLE C-3 Parameters for the Vegetable Pathway Parameter r (dimensionless).Value 1.0 (radioiodines) 0.2 (particulates)

Reference (Re.Guide 1.109 Rev.1)Table E-1 Table E-1 (DFL)i at (mrem/pCi)UL)(kg/yr)-infant-child-teen-adult Each"radionuclide 0 26 42 64 Tables Table Table Table Table E-11 to E-14 E-5 E-5 E-5 E-5 Us)a (kg/yr)-infant-child-teen-adult tL.(seconds) th (seconds)Yv (kg/m2)0 520 630 520 8.6E4 (1 day)5.18E6 (60 days)2.0 Table E-5 Table E-5 Table E-5 Table E-5 Table E-15 Table E-15 Table E-15 114 r'I(e APPENDIX D DIAGRAMS OF LIQUID AND GASEOUS RADWASTE TREATMENT SYSTEMS 115 A*~~rP's, ll~~-t 1 4g,g'-1~e A-I E~0<<elle>I~<<P saa<<>le K v vec CK IC Kt n IS Cl~I~0 N CI~I I>>'rs~NI0N~~t<<lllho~IWS Ihs~Ic~N~1~I~~C Kt Ic~~0~I~I~1 lc~I~I tl N~><<<<III Wt N<<Ill~h>>No<<s C~I I~I PIP INCt INSTRUHENT ANO EOUIPHENT SYHBOLSN~0 I~K'<<N IN~K'~I~tl~N~N~as~~>I~I N ossa!ul~N Who~~~1 4 I la rl~s~1~0 N t!sh (Ss ts isa ft va-a=.'<<la Vvalt h>>>>I<<lo~VI I<<la 1st l<<la F<<I heh<<o~wwo g 0 I hase<<o~>>Ns wa~<NI~<<ll<<as ,I~hh sa>Lt>>I I>>a ol>>s~ao I<<<<Ul seas tpt s<<a t j)thh>W Sh>to>>soar o<<K.L IIIL STI!II!L'K ta<<ro Ilp ho>oars Io>>wp>>N teal>1<<0~<<l>>col lw<<a Ios~C<<>>I 0 lolls~ol<<0 a<>cc srh<>CII>0 CW>40~~P>><<tl~I<<Is>>~>>>lal h>>IS<<CIO>>Clo>01>>I 8)..Q)-Pl o<<K No<<ss>>Nh~l'I I'II-IKI<<0 h w&s>>Q 0<<~04l~<<col>>>>os>>ewos~I<<<<h~.~O<<ls 0~IC~\,<<os<<aces>14~>>(>>o h h<<0 4tl<>l I~<<0 N Q)IIIIIQLAS.K QKfSIIQH.vll'l0:N 0: PIww I I vwac t<<a 2 ILlIIGATI(QQLS.

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~~(~)OL)~(b)NIACARL QCN KPNQt C~afOR awe Li HACH (s)t (s)Mfner Road D"7 Sita Boundaries NINE MLLE POINT-123-NNGARA MOtNWK POWER CORPORAL lO>NINE MILE POINT-UNIT 1 OFFSlTE OOSS CAt.C MANUAL lC<<f~W I'k 0U i'~M NOTES TO FIGURE D">(a)NMP1 Stack (height is 350').(b)NMP2 Stack (height is 430')(c)JAFNPP Stack (height is 385')(d)NMP1 Radioactive Liquid Discharge (Lake Ontario, bottom)(e)NMP2 Radioactive Liquid Discharge (Lake Ontario, bottom)(f)JAFNPP Radioactive Liquid Discharge (Lake Ontario, bottom)(g)Site Boundary (h)Lake Ontario Shoreline (i)Meteorological Tower (j)Training Center (k)Energy Information Center Additional Information:

-NMP2 Reactor Building Vent is located 187 feet above ground level-JAFNPP Reactor and Turbine Building Vents are located 173 feet above ground level-JAFNPP Radwaste Building Vent is 112 feet above ground level-The Energy Information Center and adjoining picnic area are UNRESTRICTED

'-.-"".AREAS:.wi.thin, the SITE BOUNDARY that are accessible to MEMBERS OF THE PUBLIC-Lake Road, a private road, is an UNRESTRICTED AREA within the SITE BOUNDARY accessible to MEMBERS OF THE PUBLIC-l24-0'*~a, sac,r NV 4 r 41%

~5'>>I)~~I)I 8)l~~., Og~~~ill~I C~)I I~.I I I I 0~t Q~0~~0

&E w'4 I ill a~otal C V'I IO ISOKINETIC PROBE RN 21 11241 RAG EMS RAGEMS Ditution Return 112-52 112-131]Sample Return Drain 112-55 11243 112-132 112.57 OGESMS Intet 112.30 112-56 112-133 OGESMS Outtet Figure D-9 Stack Sample and Sample Return NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 1 OFFSlTE DOSE CALC.MANUAL 126-S lit F'~~J tel RAG EMS inlet OVS 112-173 OV3 112-169 OV2 112-167 PCV 112-106 112-110 Ne Supply OV8 112-178 1 2-1 Pl 112-21 OV4 112-171 OFS1 112-101A C 112.130 112-51 OV1 OV13 112-165 t 1248 RAG EMS Dilution Inlet OFC4 112-104 OFS4 112-04A PCV 112-107 OFC1 112-101 112-111 Pl 11-122 OFC3 112-103 OFS3 112-103A 112-116 OCF2 112-102 OFS2 112-102A 112-151 OV16 112-150 112-112 Pl"11-23 OV12 Senlpte 112+7 Return RAG EMS Outlet 112-113 Pl 112-24 112-117 112-118 OP2 OP1 OV6 112-175 Figure 0-1 0 11-44 RAGEMS Dilution Schematic NIAGARA MOHAWK POWER CORPORATION NINE MlLE POINT-UNIT 1 OFF SITE DOSE CALC.MANUAL 127 IP'~)~ir 14 gl g 112-114 1FS1 112-129 Pl 112-125 1V3 1V4 112-183 112-185,'V3 2V4 112-199 112-201 3V3 112.7 3V16 112-218 3V 112-96 Qalhn2 Tritium 112-73 112-72 112-74 3FS1 112-105A 1V1 112-1 1V2 12-'I81 2VI 112-195 2 112-197 3VI 3VS 112 3 3 2.77 6 Uter-95 112-99.75 Pl 112-126 3GVI 112-105 1V5 112-186 1V6 2VS 112-187 112-202 2V6 112-203 2V11 112-208 11 76 I-78 3 3 3V4 112.98 112-119 3V6 3V7 112-100 112-211 Pl 11247 1V11 112-192 Pl 11244 1V17 11249 3V11 112-215 3VI 112-217'l12-108 3PI 3VIO 112-21 I 3VI2 112-109 112-216 Fi Ure D-11 RAGEMS Schematic NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 1 OFFSITE DOSE CALC.MANUAL 128 P+A.J a tA t'a'~<<a 1 0 11242 FS 11 43 112-10 11249 AM43A 67 11266 112-11 Inlet 112-146 112-147 112-59 FL1 112-58 112-148 12-149 11261 11240 u 112-137 112-152 Pl 112-u u 112 62 63 1 12-153 BA-G-3 112-154'l 1244 11245 u u 112-161 11248 11244 FGV 112-91 112-137 112-163 112-134 BR G-3 PS2 11 4i 11-135 1'l2-135 112-139 112-138 112-140 FS 112-94 Fl 11246 Tritium V/Pl 11245 12-158 q 112-156 112-155 112-142 l12-141 112-22 FL3 112-20 112.21 11240 112-159 112-'157 112-3 112-19 112-1 12 112.14 112.18 11249 112-70 112-15 12-1 112-12 11247 11248 Fi ure D-12 OGESMS Schematic NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT 1 OFFSITE DOSE CALC.MANUAL 129-

'1 y l,ll if~8 J A N M P I T N SUPERSKOEQ Ol4 REPLICA General Superintendent Nuclear Generation K.A.Dahlberg for L.Will 1 s 3 1 1,2,5,6,8,9,11-13,15-18, 36-44,47-49, 52-63,65-76,79-81,86-116 3,4,7,10,14,20,23 27-28,30-35 45,46,50,51,82-85

  • 29*64,77,78 i,19,21,22A,22B,24,25 26,112 February 1987 December 1987 January 1988 May 1988 (Reissue)May 27, 1988 (Reissue)February 1990 THIS PROCEDURE NOT TO BE USED AFTER March 1992 SUBJECT TO PERIODIC REVIEW 9PP9110036 e.~l V 1.0 2.0 2~1 INTRODUCTION LIQUID EFFLUENTS Setpoint Determinations 2.1.1 Basis 2.1.2 Service Water System Effluent Alarm Setpoint 2.1.3 2.1.4 Liquid Radwaste Effluent Alarm Setpoint Discussion 2.1.4.1 Control of Liquid Effluent Batch Discharges 2.1.4.2 Simultaneous Discharges of Radioactive Liquids 2.1.4.3 Sample Representativeness 2.1.4.4 Liquid Radwaste System Operation 2.1.4.5 2.2 2.3 2.3.1;3.0 3.1 3.1.1 3.1.2 3.1.'3 3.1.4 3.1.5 3.1.5.1 3.1.5.2 Service Water System Contamination Liquid Effluent Concentration Calculation Dose Determinations Maximum Dose Equivalent Pathway"-GASEOUS EFFLUENTS Setpoint Determinations Basis Stack Monitor Setpoints Recombiner Discharge-(Off Gas)Monitor Setpoints Emergency Condenser Vent Monitor Setpoint Discussion Stack Effluent Monitoring

System Description

Stack Sample Flow Path-RAGEHS 10 12 12 19 19 19 20 22B I~'3 24 24 3.1.5.3 Stack Sample Flow Path-OGESHS 26

/j W'-7 4 v v~, lk l r~P~I h 4".II<OA TAB F T (Cont'd)3,1.5.4 Sample Frequency/Sample Analysis 3.1.5.5 I-133 Estimates 3.1.5.6 Gaseous Radwaste Treatment System Operation 27 27, 28 3.2 3.2.1 Dose and Dose.Rate Determination Dose Rate 29 31 3.2.1.1 Noble Gases 3.2.1.2 Tritium, Iodines and Particulates

'3.'2.2 Dose 3.2.2.1 Noble Gas Air Dose 3.2.2.2 Radioiodine, Tritium and Particulates 3.2.2.3 Accumulating Doses 3.3-" Critical Receptors 32 32 34 34 36 37 38 3.4 4.0 4.1 4.2 4.3'.4 5.0 5.1 5.2 5.3 Refinement of Offsite Doses Resulting From Emergency Condenser Vent Releases 40 CFR 190 REQUIREMENTS

-:Evaluations of Doses From Liquid Effluents Evaluation of Doses From Gaseous Effluents Evaluation of Doses From Direct Radiation Doses to Members of, the Public Hithin the Site Boundary ENVIRONMENTAL MONITORING PROGRAM Sampling Stations Interlaboratory Comparison Program Capabilities for'Thermoluminescent Dosimeters Used for Environmental Measurements.

39 40'6 46 47 52 53 54

'l l ,F ODCM-NINE MILE POINT MILE 1 TABLE OF CONTENTS (Cont'd)~Pa e Table 1-1 Table 1-2 Table 2-1 Table 3-1 Rapj 1 Values.for the NMP-1 Facility Parameters for the Liquid Effluent Pathway Average Energy Per Disintegration Critical Receptor Dispersion Parameters for Ground Level and Elevated Releases 57 58 59 60 Table 4-1 Dose Factors for Noble Gases 61-Tables 4-2 to 4-20 R Values 62 Table 5-1 NMP-1 Radiological Environmental Monitoring Progrem Sampling Locations 81 Appendix A Dose Parameters for Iodine-131 and 133, Particulates and Tritium 85 Appendix B Diagrams of Liquids and Gaseous Radwaste Treatments Systems 98 Appendix C Dispersion Calculation Tables 109

~/~hpp V 4 4 c~

1 o0 INTRODUCTION The Offsite Dose Calculation Manual (ODCM)provides the methodology to be used for demonstrating compliance"with the Radiological Effluent Technical Specifications (RETS), 10 CFR 20, 10 CFR 50, and 40 CFR 190'he contents of the ODCM are based on Draft NUREG-0472, Revision 3,"Standard Radiological Effluent Technical Specifications for Pressurized Water'eactors," September 1982;Draft NUREG-0473, Revision 2,-"Radiological

.Effluent Technical S'pecifications for BWR's," July 1979;NUREG 0133,"Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978;the several Regulatory Guides referenced in these documents; and, communication with the NRC staff.Section 5 contains a detailed description of the Radiological Environmental Monitoring (REM)sampling locations'hould it be necessary to revise the ODCM, these revisions will be made in accordance with Technical Specifications i5 i I~fr'4a) 2.0 LIQUID EFFLUENTS 2.1 Setpoint Determinations 2.1.1 Basis Monitor setpoints will be established such that the concentration of radionuclides in the liquid effluent releases in the discharge canal will not exceed those concentrations as specified in 10 CFR 20, Appendix B, Table II, Column 2.Setpoints for the Service Water System Effluent Line will be calculated'uarterly based on the radionuclides identified during the previous year's releases from the liquid radwaste system or the isotopes identified in the most recent radwaste release or other identified probable source.Setpoints for the Liquid Radwaste Effluent Line will be based on the radionuclides identified in each batch of liquid waste prior to its release.tl After release, the Liquid Radwaste monitor setpoint may remain as set, or revert back to a setpoint based on a previous Semi-Annual Radioactive Effluent Release Report, or install blank flange in the discharge line and declare inoperable in accordance.

with the technical specification.

Since the Service Water System effluent monitor and Liquid Radwaste effluent monitor can only detect gamma radiation, the alarm setpoints are calculated by-using the concentration of gamma emitting isotopes only (or the corresponding MPC values for the same isotopes, whichever are higher)E(Ci/ml)expression (Section 2.1.2, 2.1.3).-2-in the Pf1 I 8~-'f 4K 2.1.1 (Cont'd)The Required Dilution Factor is calculated using concentrations of all isotopes present (or the corresponding MPC values for the same isotopes, whichever are higher)including tritium and other non-gamma emitters to ensure that all radionuclides in the discharge canal do not exceed 10 CFR 20 limits.2.1.2 Service Water System Effluent Line Alarm Setpoint The detailed methods for establishing setpoints for the Service Water System Effluent Line Monitor shall be contained in the Nine Mile Point Station Procedures.

These methods shall be in accordance with the following:

+background (5 (liCi/ml)i

~concentration of gamma emitting isotope i in the sample, or the corresponding MPC of gamma emitting isotope i'MPC)i',whichever is higher (units~uCi/ml)-(vCi/ml)iT

~concentration of any radioactive isotope i in the sample including tritium and other non-gamma emitters or corresponding MPC of isotope i, MPCi, whichever is.higher (units~vCi/ml).Setpoint (Hi alarm)<0.9 z(nCi/ml)i CF)TDF/Fsw background

/Setpoint (Alert alarm)<0.7 E(pCi/ml)i (CF)TDF/Fsw E f (p Ci/ml)j T/MPCi J-Total Dilution Flow (units gallons/min)

Fsw Service Water Flow (units gallons/min)

CF~monitor calibration factor (units~net cpm/uCi/ml)

MPCi liquid effluent radioactivity concentrations limit for radionuclide i as specified in 10 CFR 20, Appendix B, Table II, Column 2.

gJ'V-'l k a~'Q W.Pll s ling~t gk rq 4/5

~~~2.1.2 Sample (VpC)i O.a and 0.7 (Cont'd)Those nuclides present in the previous batch release from the liquid radwaste effluent system or those nuclides present in the last Semi-annual Radioactive Effluent Release Report (units~pCi/ml)or those nuclides present in the service water system.**same as MPCi but for gamma emitting nuclides only.~factors of conservatism to account for inaccuracies., T f (uCi/ml)i T/MPCi]Required Dilution Factor.If MPC values are used in the~(uCi/ml)i, they must also be used in calculating RDF (numerator).)s TDF/Fsw~Actual Dilution Factor*+For periods with known reactor water to RCLC system leakage, RCLC maximum permissible concentration may be prudently substituted for the above.2-1.3 Liquid Radwaste Effluent Line Alarm Setpoint The detailed methods for establishing setpoints for the Liquid Radwaste Effluent Line Monitor shall be contained in'the Nine Mile Point Station Procedures.

These methods shall be in accordance with the following:

Setpoint (Hi-Hi alarm)<0.9>(uCi/ml)i (CF)TDF/Fxe Z[(pCi/ml)iT/MPCi]

+background Setpoint (Hi alarm)<0'7(pCi/ml)i (CF)TDF/Fre+background Z[(v Ci/ml)j T/MPC j](vCi/ml)i~concentration of gamma emitting isotope i in the sample or, the corresponding MPC of gamma emitting isotope i (MPC)i~whichever is higher.(<<Ci/ml)iT

~concentration of any radioactive isotope i in the sample including tritium and other non-gamma emitters or the corresponding MPC of isotope i MPCi whichever is higher.(units~pCi/ml)'TDF~Total Dilution Flow (units~gallons/min)

Fre CF Radwaste Effluent Flow (units~gallons/min) monitor calibration factor (units~net cps/pCi/ml) h n 4 4s MPCi liquid effluent radioactivity concentration limit for'radionuclide,i as specified in 10 CFR 20, Appendix B, Table II, Column 2, for those nuclides detected by spectral analysis of the contents of the radwaste tanks to be released.(units~yCi/ml)(MPC)ig~same as MPCi but for gamma emitting nuclide only.0.9=and 0.7~factors of.conservatism

.,to.account.for inaccuracies.

f(uCi/ml)iT/MPCij

~Required Dilution Factor.*If MPC values are used in the E(uCi/ml)i, they must also be used in calculating RDF (numerator).

Notes:(a)If TDF/Fre~E[(pCi/ml)iT/MPCi]

the discharge could not be made, since the monitor would be;continuously in alarm.To avoid this situation, F will re be reduced (normally by a factor of 2)to allow setting the alarm point at a concentration higher than tank concentration.

This will also result in a discharge canal'concentration at approximately 50'aximum permissible concentration.(b)The value used for TDF will be reduced by the fractional

'uantity (1-FT), where FT is tempering fraction (i.e., diversion of some fraction of discharge flow to the intake canal for the purpose of temperature control).

$/P,q*v*4$'.go r.ka

2.1.4 Discussion

2.1.4.1 Control of Liquid Effluent Batch Discharges At Nine Mile Point Unit 1 Liquid Radwaste Effluents are released only on a batch mode.To prevent the inadvertent release of any liquid radwaste effluents, radwaste discharge is mechanically isolated (blank flange installed or discharge valve chain-locked closed)following the completion of a batch release or series of batch releases.This mechanical isolation remains in.place and will only be removed prior to the next series of liquid radwaste discharges after all analyses required in station procedures and Technical Specification Table 4.6.15-1A are performed and monitor setpoints have been properly adjusted.2.1.4.2 Simultaneous Discharges of Radioactive Liquids.If during, the discharge of any liquid radwaste batch, there is an indication that the service water canal has become contaminated (through a service water monitor alarm or through a grab sample analysis in the event that the service water monitor.is inoperable),'the discharge shall be terminated immediately.

The'liquid radwaste discharge shall not be continued until the cause of the service water alarm (or high gr'ab sample analysis result)has been determined and the appropriate corrective measures taken to ensure lOCFR20, Appendix B, Table II, Column 2 (Technical Specification Section 3.6.15.a(1))

limits are not exceeded.

ir->i~+~C 2.1.4.3 Sampling Representativeness

-This section covers Technical Specification Table 4.6.15-1 Note b concerning thoroughly mixing of each batch of liquid radwaste prior to sampling.Liquid Radwaste Tanks scheduled for discharge-at Nine Mile Point Unit 1 are isolated (i.e.inlet valves marked up)and at least two tank volumes of entrained fluids are recirculated prior to sampling.Minimum recirculation time is calculated as follows: '-Minimum Recirculation Time 2.0(T/R)Where: 2.0 Plant established mixing factor, unitless Tank volume, gal Recirculation flow rate, gpm.Additionally, the Hi Alarm setpoint of the Liquid Radwaste Effluent Radiation Monitor is set at a value corresponding to not more than 70X of its calculated response to the grab sample or corresponding MPC values.Thus, this radiation monitor will alarm if the grab sample, or corresponding MPC value, is significantly lower in activity than any part of the tank contents being discharged.

J~,yi~,~~~~y>~Qy

~i~f-'~',"">"'~c"~~S,+i 2.1.4.4 Liquid Radwaste Systems Operation Technical Specification 3.6.16.a requires that the liquid radwaste system shall be used to reduce the radioactive materials in liquid~astes prior to their discharge, as necessary, to meet the concentration and dose requirements of Technical Specification 3.6.15~"Utilization of the radwaste system will be based on the capability of the indicated components of each process system to process contents of the respective low conductivity and high conductivity collection tanks: 1)Low Conductivity (Equipment Drains): Radwaste Filter and Radwaste Demin.(See Fig.B-1)2)High Conductivity (Floor Drains): Waste Evaporator (see Fig.~B-1)"-'">>""'>'Cumulative.dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined as described in Section 2.3 of this manual prior to the release of each batch of.liquid-waste.This same dose projection of Section 2.3 will also be performed in the event that untreated liquid waste is=.discharged, to ensure that the dose limits of Technical Specification 3.6.15.a(2) are not exceeded.(Thereby implementing the requirements of 10CFR50.36a, General Design Criteria 60 of Appendix A and the Design Objective given in Section II-D of Appendix I to 10 CFR50).

1 pC c I.-,"1, P4 g>>$C W4 1~~"k,*fdic'II 2.1.4.4 (Cont'd)For the purpose of dose projection, the following assumptions shall be made with regard to concentrations of non-gamma emitting radionuclides subsequently analyzed off-site: a)[H-3]>H-3 Concentration found recent condensate storage tank analysis.b)[Sr-89]>4 x Cs-137 Concentration c)[Sr-90]>0.5 x Cs-137 Concentration d)[Fe-55]>1 x Co-60 Concentration Assumed Scaling Factors used in b, c, and d above.represent conservative estimates derived from analysis of historical data from process waste streams.Following receipt of off-site H-3, Sr-89, Sr-90 and Fe-55 analysis information, dose estimates shall be revised using actual radionuclide concentrations and actual tank volumes discharged.

4 g!Pa 2.1.4.5 Service Water System Contamination Service water is"normally non-radioactive.

If contamination is suspected, as indicated by a sfgnificant increase in service water effluent monitor response, grab samples will be obtained from the service water discharge lines and a gamma isotopic analysis meeting the LLD requirements of Technical Specification Table 4.6.15-1 completed.

If'it is'determined that an inadvertent radioactive discharge is occurring from the service water system, then: a)A 50.59 safety evaluation shall be performed (ref.IGE Bulletin'0-10), b)Daily service water effluent samples shall be taken and analyzed for principal gamma emitters until the release is terminated, H c)An incident composite shall be prepared for H-3, gross alpha, Sr-89, Sr-90 and Fe-55 analyses and d)Dose projections shall be performed in accordance with Section 2.3 of this manual (using estimated concentrations for H-3, Sr-89, Sr-90 and Fe-55 to be conservatively determined by=supervision at the.time of the incident).

Additionally, service water effluent monitor setpoints may be recalculated using the actual distribution of isotopes found from sample analysis.

a AVC V C tl JQ I 2.2 Liquid Effluent Concentration Calculation This calculation documents compliance with Technical Specification Section 3.6.1.5.a (1).The concentration of radioactive material released in liquid effluents to unrestricted areas (see Figure B-7)shall be limited to.the concentrations specified in 10CFR20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained noble gases.For dissolved or entrained noble gases, the concentration shall be limited to 2 E-4 microcurie/ml total activity.The concentration of radioactivity from Liquid Radwaste batch releases and, if applicable, Service Water System inadvertent discharges are included in the calculation.

The calculation is performed for a specific period, of time.No credit taken for averaging over the calendar year as permitted by 10CFR20.106.

The"limiting concentration is calculated as follows: MPC Fraction~E.[Z

((yCi/ml)~F)/(MPC I (F))l 1 s is s i s s Where: MPC Fraction~The limiting concentration of 10 CFR 20, Appendix B, Table II, for radionuclides other than dissolved or entrained noble gases.For noble gases, the concentration shall be limited to 2 8-4 microcurie/ml total activity.

p 45.i;f C 4j 2.2 (Cont'd)(<<Ci/ml)is F s MPCi Z ((ICi/ml)"F)s is s The concentration of nuclide i in.particular effluent stream s, uCi/ml.The flow rate of a particular effluent stream s, gpm.The limiting concentration of a specific nuclide i from 10CFR20, Appendix b, Table II, Column 2 (noble gas limit is 2E-4 pCi/ml)The total activity rate of nuclide i, in all effluent streams s, pCi/ml"gpm

~The total flow rate of all effluent streams s, gpm (including those streams which do not contain radioactivity).

A.value of less than one for MPC fraction is'considered acceptable for compliance with Technical Specification Section 3.6.15.a.(1).

2.3 Dose Determination 2.3.1 Maximum Dose Equivalent Pathway.A dose assessment report was prepared for the Nine Mile Point Unit 1 facility by Charles T.Main, Inc., of Boston, MA.This report presented the calculated dose equivalent rates to individuals as well as the population within a 50~ile radius of the facility based on the radionuclides released in liquid and gaseous effluents during the time periods of 1.July 1980"through 31 December 1980 and.from,.l January'1981 through"'31'December:1981.

Utilizing the.effluent.data

+CDl i l'w'Ifqvvg~Ayp peg~-(y is'tA 8~>5',"v k 2.3.1 (Cont'd)contained in the Semi-Annual Radioactive Effluent Release Reports as source terms, dose equivalent rates were determined using the'environmental pathway models-specified in Regulatory Guides 1.109 and'.111 as incorporated-in the NRC computer codes LADTAP for liquid pathways, and XOQDOQ and" GASPAR for gaseous-effluent pathways.Dose=.equivalent rates were'calculated for the total body as well as seven organs and/or tissues for adults, teenagers, children, and infants.From the standpoint of liquid effluents, the pathways evaluated included fish ingestion, drinking water, and external exposure to water and sediment.Based on the findings of the above referenced report, the maximumtotal.body dose from all liquid pathways is received by an adult.Similarly, the maximum total dose to any organ is received by the teen liver.In both of these cases (i.e., adult whole body dose and teen liver dose), 99K and 98K respectively of these doses were"'""-~-".~"'received.via.the fish ingestion pathway.In order to determine the dose contribution from the release of liquid,effluents, the'nnual dose,to.an adult whole body and a,teen liver will be calculated for" each of, the significant nuclides, (see..Table 1-1)identified in the liquid waste based on the fish ingestion pathway utilizing the following formula: R..~1100U M Z B.D..(-g.t)/F apji ap P ip aipj exp i p yt, t'.'f jl t IK Where R total annual dose (per Curie released)to organ"j" of individuals of age group"a" from all of the nuclides"i" in pathway"p" (units~mrem/year-Ci)tJ ap usage factor specifying the exposure time or, intake rate for an individual of an age group"a" associated with pathway"p" (units kg/year)mixing rates (reciprocal of dilution factor)at'the point of exposure or point of harvest (units~dimensionless) flow rate of the liquid effluent (units ft/sec)3 ip equilibrium bioaccumulation factor for nuclide"i" in pathway"p"'units~liters/kg)

D aipj the dose factor, specific to a specific age group ,'"a", radionuclide"i", pathway"p", and organ"j", which can be utilized to calculate the radiation dose from an intake of a radionuclide (units~mrem/pCi)radioactive decay constant of nuclide"i" (units-1~hours) k 4i'yl~r+II cd MINI p I the average transit time required for nuclides to reach the point of exposure.For internal dose, t is the total time elapsed between the P release of the nuclides and the ingestion of the Eood and/or water (units~hours)1100~factor to convert from (Ci/year)/(Et

/sec)to pCi/liter 3 Values for R i are contained in Table 1-1.All of these values apj i of R.i are on a per Curie basis for each of the nuclides apj i released.Table 1-2 indicates those parameters used for selected Eactors of the formula.Prior to each radioactive liquid discharge, each liquid waste tank to be discharged will be analyzed for isotope content utilizing a gamma spectroscopy system.On the basis of this analysis, projected doses , to an adult whole body and a teen liver will be calculated using the following relationships:

PD i,1.05 R j i ()Ci PDLi 1.05 R ji(L)C Where PD Projected dose expected to the whole body of an adult due to the release of the identified concentration of nuclide"i".(units~mrem/year)

~M'C<'Qt e P, ty~\0~~

PD Projected dose expected to the liver of a teenager due to the release of the identified concentration of nuclide"i" (units~mrem/year R..(WB)apj 1 total annual dose (per Curie released)to the whole body of an adult caused by the ingestion of nuclide"i" (units~mrem/year-Curie)

R.(L)apj i total annual dose (per Curie released)to the liver of a teenager caused by the ingestion of nuclide"i" (units.~mrem/year-Curie) c quanity of nuclide"i" identified as present in the release (units~Curies)1.05~correction factor to account for 100%of dose, assuming that 95%of dose received is delivered via the fish ingestion pathway.The value of 1.05 is used in the equation as a conservative factor to increase the projected dose from an anticipated release to 100%.As long as the 1.05 factor is used, doses received via the drinking water pathway (eg, tritium)need not be accounted for separately.

r+I E ja t l,,'i All pro5ected doses calculated in this manner for each batch of liquid effluent will be'ummed for comparison with quarterly and annual limits, added to the doses accumulated from other releases in'he quarter and year of interest.In all cases, the following relationships will hold-For a calendar quarter: D<1.5 mrem total.body r D<5 mrem for any organ t-For the calendar year: D<3.0 mrem total body'-D<10 mrem for any organ where D total dose received due to liquid effluent releases If these limits are exceeded, a special report will be submitted to the NRC identifying the cause'and proposed corrective'actions.

In addition, if these limits are exceeded by a factor of two, calculations shall be made to determine if the dose limits-contained in"40 CPR 190 have.been exceeded.Dose limits, as contained in 40 CFR 190 are total body and organ doses of 25 mrem per year and a thyroid dose of 75 mrem per year.

r,'I P 2.3.1 (Cont'd)These calculations will include doses as a result of liquid and gaseous pathways as well as doses from direct radiation.

Liquid, gaseous and direct radiation pathway doses will consider the James A.Fitzpatrick and Nine Mile Point Unit II facilities as well as Nine Mile Point Unit I Nuclear Station.In the'event-the calculations demonstrate that the 40 CFR 190 dose limits, as defined above, have been exceeded, then a report shall be prepared and submitted to the Commission within 30 days as specified in Section 3.6.15.d of the Technical Specifications.

~:"'"Section 4.0 of the'DCM contains more information concerning calculations for anevaluation,of=whether 40 CFR 190 limits.have been exceeded.

Qtp N@i 3.0 GASEOUS EFFLUENTS 3.l Setpoint Determinations 3.1.1 Bas1s Stack gas and off gas monitor setpoints will be established such that the instantaneous release rate of rad1oactive materials in gaseous effluents does not exceed the 10 CFR 20 limits for annual release rate.The setpoints will be activated if the instantaneous dose rate at or beyond the (land)s1te boundary would exceed 500 mrem/yr to the whole body or 3000 mrem/yr to the skin from the continuous release of radioactive noble gas 1n the gaseous effluent.Emergency condenser vent monitor setpoints will be established such that the release rate for radioactive materials in gaseous effluents do not exceed the 10 CFR 20 limits for annual release rate over the pro)ected longest period of release.Monitor setpoints from continuous release points w111 be determined once per quarter under normal release rate cond1tions and will be based on the isotopic composition of the actual release in progress, or an offgas isotopic distribution, or a more conservative default compos1tion specif1ed in the pertinent procedure.

If the calculated

" setpoint's

'higher than the existing setpoint, it is not mandatory that the setpoint be changed.Monitor setpoints for emergency condenser vent monitors are'conservatively f1xed at 5 mr/hr for reasons described in Sections 3.1.4 and.therefore do not require.per1odic recalculations.

Under abnormal site release rate conditions, monitor alarm setpoints from continuous release points will be recalculated and, if necessary, reset at more frequent intervals as deemed necessary by CORM Superv1sion.

In part1cular, contr1butions from both JAF and'MP-2 and the Emergency Condenser Vents shall be assessed.Dur1ng outages and until power operation is again realized, the last operating stack and off gas monitor alarm setpoints shall be used.

"s~>j 3.1.1 (Cont'd)Since monitors respond to noble gases only, monitor alarm points are set to alarm prior to exceeding the corresponding total body dose rates.The skin dose rate limit is not used in setpoint calculations because it is never limiting.3.1.2 Stack Monitor Setpoints The detailed methods for establishing setpoints shall be contained in the station procedures.

These methods shall apply the following"general"criteria:

(1)Rationale for Stack monitor settings is based on the general equation: 'release rate actual corresponding dose rate, actual release rate max.allowable corresponding dose rate, max.allowable~E'X/Q E(e M)-Mnax 500 mr/yr where: ,yCi/sec released rate for each isotope, i X/Q highest land sector site boundary (elevated) dispersion parameter (see Table 3-1)Mi 3 gamma air dose factor in units of mr/yr/yCi/m (See Table 4-1)(9)instantaneous release rate limit.max k+i$Ql<<1 4 3.1.2 (Cont'd)(2)To ensure that 10 CFR 20 and Technical Specifications dose rate limits are not exceeded, the hi hi alarms on the stack monitors shall be set lower than or equal to (0.9)(Q).Hi alarms max'hall be set lower than or equal to (0.5)(Q)max (3)Based on the above conservatism, the dose'contribution from JAF and NMP-2 can usually be ignored.During Emergency'lassifications at JAF or NHP-2 due to airborne effluent, or after emergency condenser vent releases of significant proportions, the 500 mr/yr value may be reduced accordingly.

(4)To convert monitor gross count rates to pCi/sec release rates, the following general formula silall be applied: (C-B)K Q pCi/sec release rate where: C monitor gross count rate in cps or cpm B~-monitor background count rate K stack monitor efficiency factor with units of pCi/sec-cps or pCi/sec-cpm.

(5)Monitor K factors shall be determined using the general formula: K s Ei(Q)i (C-8)where: individual radionuclide stack effluent release rate as determined by isotopic analysis.K factors more conservative than those calculated by the above methodology may be assumed.

3.1.2 (Cont'd)Alternatively, when stack release rates are near the lower limit of detection, the following general formula may be used to calculate k f (Yf')~Hd s f where: f stack flow in cc/sec E-effic1ency 1n units of cpm cc/pC1 or cps cc/pC1 Ek cpm cc/bps or cps cc/gs from energy calibration curve produced dur1ng NBS traceable pr1mary gas calibration or transfer source calibration Yk b/d (betas/disintegration) or W/d (gammas/d)

I Fi Activity fraction of nuclide 1 in the m1xture nuclide counter k discrete energy beta or gamma emitter per nuc11de counter s"seconds This monitor cal1bration method assumes a noble gas.distribut1on-typical of a recoil release mechan1sm.

To-ensure that the calculated efficiency is conservative, beta or gamma emissions whose energy is above the range of calibration of the detector are not included in"*the calculation.

pl~S I

3.1.3 Recombiner

Discharge (Off Gas)Monitor Setpoints (1)The hi hi alarm points shall activate with recombiner discharge rates equal to or less than 500,000 pCi/sec.This alarm point may be set equal to or less than l Ci/sec for a period of time not to exceed 60 days provided the offgas treatment system is in operation.

(2)The h1 alarm points shall act1vate with recombiner discharge rates equal to or less than 500,000 pCi/sec (3)To convert monitor mR/hr readings to pCi/sec, the formula below shall be applied: (R)(KR)QR pCi/sec recombiner discharge release rate where: R mR/hr monitor indicator KR efficiency factor in units of pCi/sec/mR/hr determined pr1or to sett1ng monitor alarm points (4)Monitor KR factors shall be determined using the general""'formula:

KR where: Z Qi/R'-individual noble gas radionuclide recombiner

<<;discharge release rate as determined by isotop1c analysis and flow rate mon1tor.KR factors more conservative than those calculated by the above methodology may be assumed.

I lf+~~,cg~).gpg~y'g

-.e,+w'~"a~'I 3.1.3 (Cont'd)(5)The setpoints chosen provide assurance that the total body exposure to an individual at the exclusion area boundary will not exceed a very small fraction of the limits of 10CFR Part 100 in the event this effluent is inadvertently discharged directly to the environment without treatment (thereby implementing therequirements of General Design Criteria 60 and 64 of Appendix A to 10CFR Part'50).Additionally, these setpoints.serve to.limit buildup of fission product activity within the station systems which would result if high fuel leakage were to be permitted over extended periods.3.1.4 Emergency Condenser Vent Monitor Setpoint The monitor setpoint was established by calculation

(" Emergency ,Condenser Vent Monitor Alarm Setpoint", January 13, 1986, NMPC File Code 816199).Assuming a hypothetical case with (1)reactor water iodine concentrations higher than the Technical Specification Kimit, (2)reactor water noble gas concentrations higher than would be'!'~'expected at Technical Specificationiodine levels, and (3)leakage of reactor steam into the emergency condenser shell at 300%of rated 6 flow (or 1.3 x 10 lbs/hr), the calculation predicts an emergency.condenser vent monitor response of 20 mr/hr.Such a release would result in less than 10 CFR,20 dose rate.values at the site boundary-..-".and beyond for typical emergency condenser cooldown periods.Since a 20 mr/hr monitor response can, in theory, be achievable only when reactor water iodines are higher than permitted by Technical Specifications, a conservative monitor setpoint of 5 mr/hr has been adopted.

\la e'1 P K g~lqb+~'.~>~'/i Liat gr,'k\t

3.1.5 Discussion

3.1.5.1 Stack Effluent Monitoring

System Description

The NMP-1 Stack'Effluent Monitoring System consists of two-subsystems; the Radioactive Gaseous Effluent Monitoring System (RAGEHS)and the old General Electric Stack Monitoring System-(OGESHS).During normal operation, the OGESHS shall be used to monitor station noble gas effluents and collect particulate and iodine samples in compliance with Technical Specification

,.requirements.

The RAGEHS is des1gned to be promptly activated from the Main Control Room for use in high range monitoring during acc1dent situations in compliance with,NUREG 0737.crtter1a.Overall system schematic for the OGESHS and RAGEHS are shown on Figure S-9.A simplified view of RAGEHS Showing Unit 0, 1, 2, 3 and 4 can be found on Figure S-8.he'AGEHS can provide continuous accident monitor1ng and on-line isotopic analysis of NMP-1 stack effluent noble gases at Lower Levels of Detection less than Technical Specificat1on Table 4.6.15-2 lim1ts..Activities as low as 5 X 10 and as h1gh as 2-X 10 pCi/cc for noble gases are detectable by the'system.

a Ag pl Q,yr Iav i w w pa<~4)~'(~l'f~r~p h~l 17/N 3.1.5.2 Stack Sample Flow Path-RAGEHS The effluent sample is obtained inside the stack at elevation 530'sing an isokinetic probe with four orifices.The sample line then bends radially out and back into the stack;descends down the stack and out of the stack at approximately elevation 257';runs horizontally (enclosed in heat-tracing) s'ome 270'long the off gas tunnel;and enters the RAGEHS located on the Turbine Building 250'Dilution cabinet-Unit 0)and Off Gas Building 247'Particulate, Iodine, Noble Gas stations-Units 1-3).In the Dilution cabinet of the RAGEHS, the stack gas may be diluted during accident situations approximately 100-200X (first stage)or 10000-40000 X (first and second stage)with gaseous nitrogen supplied-': 'rom an on-site liquid nitrogen storage tank (see Figure 8-9).From Unit 0,'the sample gas enters Uni,t 1-3 of RAGEMS and flows thru in-line particulate and iodine cartridges and then thru either a 6".liter',(low'range) or 30 cc (high range)noble gas chamber.The sample gas next flows back thru Unit 0 and the off gas tunnel;and back into the stack.

4 Og a'%y gN l+y",,>h&g'4 3.1.5.3 Stack Sample Flow Path-OGESHS The OGESHS sample is obtained from the same stack sample probe as the RAGEHS.From the exit of the stack at elevation'257', the sample line runs east approximately 20'nd then.vertically approximately 8'o the OGESHS skid.In the OGESHS, sample flows thru a particulate/iodine cartridge'ousing and four noble gas scintillation detectors (ie, 07 and 08 low range beta detectors and 11 and 12 high range gamma detectors).

From OGESMS, the stack sample flows back into the stack at approximately elevation 257'.All OGESHS detector outputs are monitored and recorded remotely in the Hain Control Room.Alarming capabilities are provided to alert Operators of high release rate conditions prior to exceeding Technical Specification 3.6.15.b (1)a dose rate limits.Stack particulate and iodine s'amples are retrieved manually from the.OGESHS and analyzed in the laboratory using gamma spectroscopy at"'"frequencies and LLDs'specified in Table 4.6.15-2 of the Technical Specifications.

p4\/k'(=Np, He'L 4 s'e>'-6+~v 3.1.5.4, Sampling Frequency/Sample Analysis Regardless of which stack monitoring subsystem is utilized, radioactive gaseous wastes shall be sampled and analyzed in accordance with the sampling and analysis program specified in Technical Specification Table 4.6.15-2.-

Particulate.

samplesare.;, saved and analyzed for principal gamma emitters, gross alpha, Fe-55, Sr-89, Sr.-90 at monthly intervals minimally.

The latter three analyses are performed off-site from a composite sample.Sample".analysis frequencies are.increased during elevated release rate conditions, following startup, shutdown,and in con]unction witheach drywell purge.'-'onsistent with Technical Specification Table 4.6.15-2, stack effluent tritium is sampled monthly, during each drywell purge, and weekly when fuel is off loaded until stable release rates are demonstrated.

Samples are analyzed off-site.Line loss correction factors are applied to all particulate and iodine results.Correction factors of 2.0 and 1.5 are used for data-obtained from RAGEHS and.OGESHS respectively.

These correction factors are based on empirical.

data from-sampling conducted, at-NMP-1 in 1985 (memo from 3.Blastak to RAGEHS File, 1/6/86,"Stack Sample Representativeness Study: RAGEHS vs.In-Stack Auxiliary Probe Samples").

<<v~f t~t 1l~'W~"

3.1.5.5 I-133 Estimates Monthly, the stack effluent.shall be sampled for iodines over a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period and the I-135/I-131 and the I-133/I-131 ratios calculated.

These ratios shall be used to calculate I-133, I-135 release for longer acquisition samples-collected during the month.Additionally,-the I-135/I-131 and I-133/I-131 ratios should also be 5 determined after a significant change in the ratio is suspected (eg, plant status changes from prolonged shutdown to power operation or fuel damage has occurred).

3.1.5.6 Gaseous Radwaste Treatment System Operation Technical Specification 3.6.16.b requires that the gaseous radwaste treatment system shall be operable and shall be used to reduce radioactive materials in gaseous waste prior to their discharge as necessary to meet the requirements of Technical Specification 3.6.15.b.To ensure Technical Specification 3.6.15.b limits are not exceeded, and to confirm proper radwaste treatment system operation as'applicable, cumulative dose contributions for the current calendar quarter and'current-calendar."year shall be determined monthly in accordance with section 3.2 of this manual.Initial dose calculations shall incorporate the following assumptions with regard to release rates of non-gamma emitting radionuclides subsequently analyzed off-site:

/t 1"~=1 B~'IQ 3.1.5.6 (Cont'd)a)H-3 release rate)4uCi/sec b)Sr-89 release rate)4 x Cs-137 release rate c)Sr-90 release rate)0.5 x Cs-137 release rate d)Fe-55 release rate)1 x Co-60 release rate Assumed release rates represent conservative estimates derived from analysis of historical data from effluent releases and process waste streams (See NMP 34023, C.Mare to J.Blasiak, April 29, 1988,"Dose Estimates for Beta-Emitting Isotopes".).

Following receipt of V off-site H-3, Sr-89, Sr-90, Fe-55 analysis information, dose estimates shall be revised using actual radionuclide concentrations.

3.2 Dose and Dose Rate Determinations In accordance with specifications 4.6.15.b.(2) and 4.6.15.b.(3), dose and dose rate determinations will be made monthly in order to determine:

(1)Total body dose rates and gamma air doses at the maximum X/Q land sector'site boundary interface and beyond.(2)Skin dose rates and beta air doses at the maximum X/Q land sector site boundary interface and beyond.(3)The critical organ dose and dose rate at the maximum X/Q land sector site boundary interface and at a critical receptor location beyond the site boundary.~

f', 4*4 h 3.2 (Cont'd)Either average meteorological data (ie, maximum five year annual average X/Q and D/Q values in the case of elevated releases or 1985 annual average X/Q and D/Q values, in the case of ground level releases)or real time meteorological data shall be utilized for dose and dose rate calculations.

Where average meteorological data is assumed, dose and dose rates due to noble gases at locations beyond the'ite boundary will be lower than equivalent site boundary dose and dose rates.Therefore, under these conditions, calculations of noble gas dose and dose rates beyond the maximum X/Q land sector site boundary locations can be neglected-The frequency of dose rate calculations will be upgraded when elevated release rate conditions specified in subsequent sections 3.2.1.1 and 3.2.1.2 are realized.Emergency condenser vent release contributions to the monthly dose and dose rate determinations will be considered only when the emergency condenser return isolation valves have been opened for reactor cooldown or if Emergency Condenser tube leaks develop with or without the system's return isolation valve opened.Without tube leakage or opening of, the return isolation valves, releases from this system are negligible and the corresponding dose contributions do not have to be included.

~i'F 1(I k$C>>c!

3.2 (Cont'd)'hen releases from the emergency condenser have occurred, dose and do'se rate determinations shall be performed using methodology in 3.2.1 and 3.2.2.Furthermore, enviromental sampling may also be initiated to refine any actual contribution to doses.See Section 3.4.Critical organ doses and dose rates may be conservatively calculated by assuming the existence of a so-called"moving" critical receptor.At this"moving" critical receptor location, it is assumed that all'"*'pa'thways"are.applicable and the highest X/Q and/or D/Q value for r actual pathways as noted in Table 3-1 are in effect.A person's dose at the"moving" critical receptor locations is equal to the same dose that person would receive if they were simultaneously subjected to the highest pathway dose at each critical receptor identified for each pathway.If dose or dose rates calculated, using the assumptions noted above, reach Technical Specification limits, actual pathways will be evaluated, and dose/dose rates shall be calculated at separate critical receptor locations and compared with applicable limits.3.2.1 Dose Rate Not all pathways need be considered in dose and dose rate calculations at each critical receptor location.For example, when*--"'"calcul'ating land sector site.boundary doses and dose rates for particulates, iodines and tritium, only the ground deposition and inhalation pathways apply.

/jism 3.2.1.1 Noble Gases In'accordance with the-provisions.of 10 CFR 20 the dose rates from noble gas release from the site to unrestricted areas are to be limited to 500 mrem/yr to the skin.Dose rate calculation will be performed monthly, or when the Hi Hi stack monitor alarm point is reached, using the following equations:

For total body dose rates (in mr/yr): DR+~3.17 x 10 f[Mi(X/Q)Qi/

]For skin dose rates (in mRad/yr): DR/+a 3.17 x 10~[Ni(X/Q)Qi/sec]

+DR+where:-8 Mi, Ni, X/Q, Qi,.3.17 x 10 are as defined in section 3.2.2.1 3.2.1.2 Tritium, Zodines and Particulates (1)The dose rate in unrestricted areas'rom the'release of tritium, iodine-131, iodine-133 and all radionuclides in particulate form with half lives greater than 8 days is limited to 1500 mrem/year to any organ.

~!',1'I 3.2.1.2 (Cont'd)(2)En order to ensure that,.the 1500 mrem/year dose rate limit is not exceeded, particulate, iodine and tritium off site dose rate calculations shall be performed monthly and whenever particulate and iodine releaserates exceed 0.3 pCi/sec using the equation given in Section 3.2.2.2 with Q expressed in iiCi/sec.When the"release rate exceeds 0.3 uCi/sec, the dose rate assessment shall also include JAF and NMP-2 contribution.

(3)The use of the 0.3 vCi/sec release rate threshold to perform""""dose rate calculations is)ustified as follows: P (a)The 1500 mrem/yr organ dose rate limit corresponds to a minimum release rate limit of 0.30 nCi/sec calculated using the equation: 1500 (Q/sec)x (Ri)W))where: 1500 site boundary dose rate limit in mrem/year (Ri)W))" the maximum curie-to-dose'conversion factor equal to 4900 mrem-sec/uCi-yr for Sr-90, child bone at the"moving" critical receptor location beyond the site boundary.

T p(\pl 3.2.1.2 (Cont'd)(b)The use of 0.3 iiCi/sec release rate threshold and the 4900 mrem-sec/vCi~r curie-torose conversion factor is conservative since curie-torose conversion factors for other isotopes likely to be present are significantly

.lower.For example, I-131 has the second highest curie-to-dose factor equal to 465 mrem-sec/uCi-yr for the infant thyroid.This corresponds to a release rate limit of approximately 3nCi/sec.3.2.2 Dose Calculations will be performed monthly at a minimum, to demonstrate that doses resulting from the release of noble gases, tritium, I-131, I-133 and particulates with half lives greater than 8 days are within the limits specified in 10 CFR 50, Appendix I.These limits are: Noble Gas Air Dose 5 mr gamma/calendar quarter 10 mrad beta/calendar quarter 10 mr gamma/calendar year'0 mrad beta/calendar year Radioiodines, Tritium&Particulates 7.5 mrem to any organ/calendar quarter"'15'mrem-to any organ/calendar.

year 4 NQ Si I<<4.4 I 3.2.2.1 Noble Gas Air Dose--The-air'dose at the critical.receptor due to noble gas releases is determined as follows: For gamma radfation D g 3.17 x 10 7 Mi X/Q For beta radiation D<~3.17 x 10 E'i X/Q Qi where M air gamma dose factor in (mr/year per uCi/m)for 3 i.each isotope i (Table 4-1)3 N~air beta dose factor (mrad/year per uCi/m)for each isotope i (Table 4-1)X/Q the relative plume concentration (in units of sec/m)at the land sector site boundary or 3 beyond.Either average meteorological data (Table 3-1 or Appendix C), or real time values may be assumed."Elevated" X/Q values are used for stack releases;"Ground" X/Q values are used for;Emergency Condenser Vent releases.Q~the total quantity of isotope i released during.the period, (pCi)-8 3.17 x 10-~the inverse of the number of seconds in a year.

4 V'f e 3.2.2.2 Radioiodine, Tritium&Particulates The doses to an individual from I-131, I-133, tritium, and particulates with half lives greater than 8 days will be calculated as follows:-8 Dose 3.17 x 10 R~EiRi~akW~Qi Where WJ dispersion parameter either X/Q (sec/m)or D/Q 3 (1/m)depending on pathway and receptor location 2 assumed.Either average meteorological data (Table 3-1, or Appendix C)or real time values may be assumed."Elevated" W values are used for stack releases;"Ground" W values are used for Emergency Condenser Vent releases.the total quanity of isotope i released during the period, (uCi)izaak 3':17;x 10 the dose factor for each isotope i, pathway j, age group a, and organ k (Table 4-2, through 4-20)~the inverse of the number of seconds in a year The R values contained.in'Tables,4-2,through 4-20 were calculated using the methodology defined in NUREG-0133,and Regulatory Guide 1.109, Revision 1.

-~4 W 3.2.2.3 Accumulating Doses Doses will be calculated monthly, at a minimum, for gamma air and beta air, the identified critical organ, and age group.Results will be summed for each calendar quarter and year.It has been historically demonstrated that the critical pathway is usually the grass-cow-milk pathway and the critical organ is, the.,, infant',s thyroid.For this reason, monthly infant thyroid dose estimates will normally be made prior to receipt of all analysis data (i.e., strontium and tritium).The critical doses are based on the , following pathways: noble gas plume air dose ground plane dose (deposition) inhalation dose cow's milk dose goat's milk dose meat consumption dose vegetation (food crops)dose The quarterly and annual results shall be compared to the limits listed in'.paragraph 3.2.2.If the limits are exceeded, special reports, as required by Section.6.9.3 of-the Technical Specification, shall be submitted.

kl~A~4~gt 4 p~'J-4 If i 3.3 Critical Receptors In accordance with the provisions of 10 CFR 20 and 10 CFR 50, Appendix I, the critical receptors have been identified and are contained in Table 3-1..."For...noble gas:doses, one.of two critical receptor locations will be assumed.When maximum five year average annual X/Q values are used, the critical receptor is the maximum X/Q land sector site boundary 1 interface.

When real time meteorological X/Q values are used, the critical receptor may either be the maximum X/Q land sector site boundary location, or the downwind location of greatest X/Q residence (e.g., 1.5 miles east), whichever is higher.For I-133, I-131, tritium and particulate radionuclides with half life greater than eight days, the critical pathways are milk (cow and goat>, meat, vegetation, inhalation and direct radiation (ground plane)as a result of ground deposition.

The cow milk and goat milk pathway will be based on the greatest D/Q~...*'ilk,.cow and milk goat location as determined by technical specification'.3.6.22.',.The'inhalation

'dose pathway, will.be based-on the greatest X/Q residence as determined by technical specification 3.6.22 since this location would have the greatest potential occupancy time.The ground plane dose pathway will be calculated as the greatest D/Q residence because of the greatest potential occupancy time.-38" l p4 l\C i$il+i' 3.3 (Cont'd)For the meat consumption dose pathway, the critical receptor is the greatest D/Q meat animal location.This location has been determined in conjunction with the land use census (technical specification 3.6.22)and is subject to change.The vegetation (food crop)dose is based on the greatest-D/Q garden location from which samples are.taken.This location also.may be modified:as a result.of.vegetation sampling surveys.3.4 Refinement of Offsite Doses Resulting from Emergency Condenser Vent Releases The doses resulting from the operation of the emergency condensers and calculated in accordance with 3.2.2 may be refined using data from actual enviromental samples.Ground deposition samples will be obtained from an area or areas of maximum projected deposition.

These areas are anticipated to be at<,<or..near.

the site boundary and near projected plume centerline.

Using the methodology found in Regulatory Guide 1.109, the dose will be calculated to the maximum exposed individual.

This dose will then be compared to the dose calculated in accordance with 3.2.2.The comparison will result, in an adjustment factor of less than or.greater than one which will be used to adjust" the'other doses from other pathways.

+jl..L S 3.4 (Cont'd)Other environmental samples may also be collected and the resultant calculated doses to the maximum exposed individual compared to the dose calculated per 3.2.2.Other environmental sample media may include milk, vegetation (such as garden broadleaf vegetables), etc.'"."The adjustment:factors.

from.these.pathways may be applied to the doses calculated per 3;2.2 on a pathway by pathway basis or several pathway adjustment factors may be averaged and used to adjustcalculated doses.Doses calculated from actual environmental sample media will be based on the methodology presented in Regulatory Guide 1.109.The regulatory guide equations may be slightly modified to account for short intervals of time (less than one year)or modified for simplicity purposes by deleting decay factors.Deletion of decay factors would yield more conservative results.

~~~'a 4.0 40 CFR 190 REQUIREMENTS The"Uranium Fuel Cycle" is defined in 40 CFR Part 190.02 (b)as follows:-"Uranium fuel cycle'eans the operations of milling of uranium ore, chemical-conversion of uranium, isotopic-enrichment of uranium, fabrication of uranium fuel, generation of electricity by a light-water-cooled nuclear power plant using uranium fuel, and reprocessing of spent uranium fuel, to the extent that these directly support the production of electrical'ower for public use utilizing nuclear energy, but excludes mining operations, operations.at waste disposal sites, transportation of any radioactive material in support.of these operations, and the reuse of recovered non-uranium special r nuclear and by-product materials from the cycle." Section 3.6.15.d of the Technical Specifications requires that when~'.the calculated doses associated with the effluent releases exceed twice the limits of sections 3.6.15.a.(2)(b), 3.6.15.b.(2)(b) and 3.6.15.b.(3)(b), then calculations shall be made including direct radiation contributions from the reactor units and.outside storage tanks (as applicable)-

to determine whether the 40 CFR 190 dose-limits have been exceeded.

~~~" 0 E ff,ff E'~~I fk EI~'k I'I I~PIE Q', WEE,Wt~IFEIF JI fJj4 I'0 0 fIJ I~~F fF Qf 4.0 (Cont'd)If such is the case, Niagara Mohawk shall submit a Special Report to the NRC and limit subsequent releases such that.the dose commitment to a real individual from all uranium fuel cycle sources is limited to<'25 mrem to the'total body or-any organ--(except-the,.thyroid,'which'is limited to<..75 mrem)over the calendar year.This report is to demonstrate that radiation exposures to all real individuals from all uranium fuel cycle sources (including all liquid and gaseous effluent pathways and direct radiation) are less than the limits in 40 CFR Part 190.If releases that result in doses exceeding the 40 CFR 190 limits have occurred, then a variance from the NRC to permit such releases will be requested and if possible, action will be taken to reduce subsequent releases.""'" The" report to the NRC shall contain: 1)Identification of all uranium fuel cycle facilities or'perations within 5 miles of the nuclear power reactor units at the site that contribute to,the-annual dose of the maximum exposed member of the public.2)Identification of the maximum exposed member of the public and a determination of the total annual dose to this person from existing pathways and sources of radioactive effluents and direct radiation.

<<42-J'-~4~>f 4p 4.0 (Cont'd)The maximum total body and organ doses resulting from radioactive-material in liquid effluents from Nine Mile Point Unit 1 will.be summed with the maximum doses resulting from the releases of noble gases, radioiodines, and particulates for the other calendar quarters~>>~--(as.applicable)...and, from.the calendar.,quarter in, which twice the..limit was exceeded.The direct dose components will be determined by either calculation or actual measurement.

Actual measurements will utilize environmental TLD dosimetry.

Calculated measurements will utilize engineering calculations to determine a projected direct dose component.

Zn the event calculations are used, the methodology will be detailed as required in Section 6.9.1.e of the Technical Specifications.

The doses from Nine Mile Point Unit 1 will be added to the doses to the maximum exposed individual that are contributed from other uranium fuel cycle operations within 5 miles of the site.For the purpose of calculating doses,'he results of the Radiological Enviromental Monitoring Program may be included for providing more refined estimates of doses to.a real.maximum exposed individual;..

Estimated doses, as calculated from station effluents, may be replaced by doses calculated from actual enviromental sample results.

~e~~ee e e~~~ee e I e ee D Ee e eeeeee e Evaluation of Doses From Liquid Effluents For the evaluation of doses to real members of the public from liquid effluents, the fish consumption and shoreline sediment ground dose will be considered.

Since the doses from other aquatic pathways are insignificant, fi'sh'onsumption'and"shoreline'ediment>>

are the only'wo pathways that will-be considered.

The dose associated with, fish consumption may be calculated using effluent data and Regulatory Guide 1.109 methodology or by calculating a dose to man based on actual fish sample analysis data.The dose associated with shoreline sediment is based on the assumption that the shoreline would be utilized as a recreational area.This dose may be derived from liquid effluent data and Regulatory Guide 1.109 methodology or from actual shoreline sediment sample analysis data.Equations used to evaluate doses from actual fish and shoreline sediment samples are based on Regulatory Guide 1.109 methodology..Because.of the sample medium type and the half-lives of the radionuclides historically observed, the decay corrected portions of the equations are deleted.This does not reduce the conservatism of the calculated doses but increases the simplicity from an evaluation point of view.The dose from fish sample media is calculated as: (1)Rwb~Fi[Cif x u x 1000 x Diwb x f]Where:~The total dose to the whole body of an adult in mrem per year.

A<<+t%eA (Cont'd)Cif~The concentration of radionuclide i in fish samples in pCi/gram.~The consumption rate of fish for an adult (21 kg per year).1000~Grams per kilogram'Diwb~The dose factor for radionuclide::i for the whole body of an adult (R.G.1.109, Table E-11).~The fractional portion of the year over which the dose is applicable.

(2)Rl Where:~~i[Cif x y x 1000 x Dil x~The total dose to the liver of an adult (maximum exposed organ)in mrem per year.Cif=The concentration of radionuclide i in fish samples in pCi/gram.~The consumption rate of fish for an adult (21 kg per year).1000~Grams per kilogram Dil~The dose factor for radionuclide i for the liver of an adult (R.G.1.109, Table E-ll)~The fractional portion of the year over which the dose is applicable.

The dose from shoreline sediment sample media is calculated as: Where:-E[Ci, x ll x-40,000 x 0.3 x Diwb x f]and~g[Cis x y x 40,000 x 0.3 x Disk x f]~The total dose to the whole body of a teenager or adult (maximum exposed age group), in mrem per year.Rsk~The total dose to the skin of a teenager or adult (maximum exposed age group)in mrem per year.Cis~The-concentration of radionuclide i in shoreline sediment in pci/gram.

4" 0 A gR)i"I (Cont'd)~The usage factor.This is assumed as 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> per year by a teenager or adult.I 40,000~The product of the assumed density of shoreline sediment (40 kilogram per square meter to a depth of 2.5 cm)times the number of grams per kilogram.0.3~The shore width factor for a lake, Diwb=The'dose factor for'radionuclide i for the total, body (R.G.1.109, Table E-6)Disk~The dose factor for radionuclide i for the skin (R.G.1.109, Table E-6)~The fractional portion of the year over which the dose is applicable.

NOTE: "'ecause of the nature of the receptor location and the extensive fishing activity in the area, the critical individual-may be a teenager or an adult.

Qb.~ii I h'4*~~~'ial 4lhkg tlXf Cking il 0~ii i\f1 E1'h'4 gt 0 tl~i it 4

4.2 Evaluation

of Doses From Gaseous Effluents For the evaluation of doses to real members of the public from gaseous effluents, the pathways contained in section 3.2.2.3 of the ODCM will be considered.

These include the ingestion, inhalation and'deposition pathways'.

However, any updated field:data may.be utilized that concerns locations of real individuals, real time meteorological data, location of critical receptors, etc.Data from the most recent census and sample location surveys should be utilized.Doses may also be calculated from actual enviromental sample media, as available.

Enviromental sample media data such as TID, air sample, milk sample and vegetable (food crop)sample data may be utilized in lieu of effluent calculational data.Doses to member of the public from the pathwasy contained in ODCM section 3.2.2.3 as a result of gaseous effluents will be calculated using the dose factors of Regulatory Guide 1.109 or the methodology

"." of the ODCM, as applicalble.

Doses calculated from environmental sample media will utilize the methodologies found in Regulatory Guide 1.109.4.3 Evaluation of Doses From Direct Radiation Section 3.6.15.d of the Technical Specifications requires that the dose contribution as a result of direct radiation be considered when evaluating whether the dose limitations of 40 CFR 190 have been exceeded.

1 ,*i"Prf+'<w+X g'~It ply g Direct radiation doses as a result of the reactor, turbine and radwaste buildings and outside radioactive storage tanks (as applicable) may be evaluated by engineering calculations or by evaluating enviromental TLD results at critical receptor locations, site boundary or other special interest locations.

For the"evaluation of direct radiation-doses-utilizing environmental'-TLDs,-':the'ritical receptor in question, such as the critical residence, etc., will be compared to the control locations.

The comparison involves the difference in environmental TLD results between the receptor location and the average control location result.4~4 Doses to Members of the Public Mithin the Site Boundary.Section 6.9.l.e of the Nine Mile Point Unit 1 Technical Specifications requires that the Semiannual Radioactive Effluent Release Report~include an assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due.to.their=,activities inside the site boundary as defined by Figure 5.1-1 of the specifications.

A member of the public, as defined by the Technical Specifications, would be represented by an individual who visits"the sites'nergy Information Center for.the purpose of observing the educational displays or for picnicing.and associated

...activities.

>>r<<II I~>>r n<<>>y>>f04~>>4 s 0 V~<<.g<<g*W Wy--,'>>>>>><<

I~>><<,S>><<S'4 P~" gag,>>

4~4 (Cont'd)Fishing is a major recreational activity in the area and on the Site as a result of the salmonid and trout populations in Lake Ontario.Fishermen have been observed fishing at the shoreline near the Energy Information Center from April through"December in all weather'onditions."'Thus," fishing is-the'ajor activity performed by members of the public within the site boundary.Based on the nature of the fishermen and undocumented observations, it is conservatively assumed'hat the maximum exposed individual spends an average of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per week fishing from the shoreline at a location between the Energy Information Center and the Unit l facility.This estimate is considered conservative but not necessarily excessive and accounts for occasions where individuals may fish more on weekends or on a few days in March of the year.The pathways considered for the evaluation include the inhalation

""-pathway with the resultantlung dose, the ground dose pathway with the resultant whole body and skin dose and the direct radiation dose pathway with the associated total body dose.The direct radiation dose pathway, in.actuality, includes several pathways.These include: the direct radiation gamma dose to an individual from an overhead plume, a gamma submersion plume dose, possible direct radiation dose from the facility and a ground plane dose (deposition).

Because the location is in close proximity to the site, any beta plume submersion dose is felt to be insignificant.

'i AW'I I~4 I'I~.(-I.lI"~p~I I++II.>>l~Ili~g Wy rIN'i~" I wl~f I 4~4 (Cont'd)Other pathways, such as the ingestion pathway, are not applicable.

In addition, pathways associated with water related recreational activities, other than fishing, are not applicable here.These include swimming,'oating and wading which are prohibited at the~facility.The inhalation pathway is evaluated by identifying the applicable radionuclides (radioiodine, tritium and particulates) in the effluent for the appropriate time period., The radionuclide concentrations are then multiplied by the appropriate X/Q value, inhalation dose factor, air intake rate, and the fractional portion of the year in question.Thus, the inhalation pathway is evaluated using the following equation adapted from Regulatory Guide 1.109.NOTE: The following equation is adapted from equations C-3 and C-4 of Regulatory Guide 1.109.Since many of the factors are in units of pCi/m,, m/sec., etc., and since the 3 3 F radionuclide decay expressions have been deleted because of the short distance to the receptor location, the equation...presented here, is., not.identical.to the Regulatory Guide equations.

R~y.i[C F X/Q DFA.R t]i i]a a where: R the maximum dose for the period in question to the lung (j)for all radionuclides

<i)for the adult age group<a)in mrem per time period.

4~f P I II k~s, A 4'(Cont'd)The'average concentration in the stack release of radionuclide i in pCi/m for the period in question.3 F~Unit 1 average stack flowrate in m/sec.3'X/Q.The:plume dispersion"parameter for a location approximately 0.50 miles west of NMP-1 (The plume dispersion parameter is 8.9E-06 and was obtained from the C.T.Main five year average annual X/Q tables.A X/Q value based on real time meteorology may also be utilized for the period in question, if desired.The stack (elevator)

X/Q is conservative when based on 0.50 miles because of the close J proximity of the stack and the receptor location).

DFAi)the inhalation dose factor for radionuclide i, the lung j, and adult age group a in mrem per pCi found on Table E-7 of Regulatory Guide 1.109.R a annual air intake for individuals in age group a in M per year (this value is 8,000 m per year and 3 3 was obtained.from Table E-5 of Regulatory Guide 1.109).fractional portion of the year for which radionuclide-i was detected and for which a dose is to be calculated (in years).

I$t Vh H ,~t'r P 4)+'%Su' The ground dose pathway (deposition) will be evaluated by obtaining at least one soil or shoreline sediment sample in the area where fishing occurs.The dose will then be calculated using the sample results, the time period in question, and the methodology based on Regulatory Guide 1.109 as presented in Section 4.1.The resultant dose may be adjusted for a background-dose by subtracting the""-applicable-off-si'te control soil or=shoreline sediment sample radionuclide activities.

In the event it is noted that fishing is not performed from the shoreline, but is instead performed in the water (i.e., the use of waders), then the ground dose pathway (deposition) will not be evaluated.

The direct radiation gamma dose pathway includes any gamma doses from an overhead plume, submersion in the plume, possible radiation from the facility and ground plane dose (deposition).

This general pathway will be evaluated by average environmental TI,D readings.At least two environmental TIDs will be utilized at one location in the'approximate area where fishing occurs.The TIDs will be placed in the field on approximately the beginning of each calendar quarter and removed on approximately the end of each calendar quarter (quarter 2, 3, and 4),.The average TLD readings will be adjusted by the average control TLD readings.This is accomplished by subtracting the average quarterly; control TI.D value from the average fishing location TLD value.The applicable quarterly control TLD values will be utilized after adjusting for the appropriate time period (as applicable).

Zn the event of loss or theft of the TLDs, results from a TLD or TLDs in the area may be utilized.

l, R Ik-)L j'b gr jf

5.0 ENVIRONMENTAL

MONITORING PROGRAM 5'Sampling Stations The current sampling locations are specified in Table 5-1 and Figures S.l-l, 5.1-2.The meterological tower is shown in Figure 5.1-1.The.location is shown as"TLD'ocation 17.The Radiological Environmental Monitoring Program is a joint effort between the Niagara Mohawk Power Corporation and the New York Power Authority, the owners and , operators of the Nine Mile Point Unit 1 and the James A.FitzPatrick Nuclear Power Plant, respectively.

Sampling locations are chosen on the basis of historical average dispersion or deposition parameters from both units.The environmental sampling location coordinates shown on Table 5-1 are based on the NMP-2 reactor centerline.

The average dispersion and deposition parameters have been calculated for a 5 year period, 1978 through 1982.These dispersion

'"""-'calculations are attached as Appendix C.The calculated dispersion or deposition parameters will be compared to the results of the annual land use census.If it is determined that a milk sampling location exists at a location that yields a significantly higher (e.g.50%)calculated D/Q rate, the new milk sampling location will be added to the monitoring program within 30 days~If a new location is added, the old location that yields the lowest calculated D/Q may be dropped from the program after October 31 of that year.

~Ef

5.2 Interlaboratory

Comparison Program Analyses shall be performed on samples containing known quantities of radioactive materials that are supplied as part of a Commission approved or sponsored Interlaboratory Comparison Program, such, as the" EPA Crosscheck'Program."-Participation shall be only'or those media, e.g., air, milk, water, etc.,-that are included in the Nine Mile Point Environmental Monitoring Program and for which crosscheck samples are available.

An attempt will be made to obtain a QC sample to program sample ratio of 5%or better.The site identification symbol or the actual Quality Control sample results shall be reported in the Annual Radiological Environmental Operating Report so that the Commission staff may evaluate the results.Specific sample media for which EPA Cross Check Program samples are available include the following:

~gross beta in air particulate filters-~'amma emitters in air particulate filters I-131 in milk gamma emitters in milk-gamma emitters in food product gamma emitters in water tritium in water I-131 in water v'$g$A)I fan%f'~1

5.3 Capabilities

for Thermoluninescent Dosimeters Used for Environmental Measurements Required detection capabilities for thermoluminescent dosimeters used for environmental measurements required by Table 4.6.20-1, footnote b'*'-.of the Technical Specifications-,iare..based.;,on.

ANSI Standard.N545,';~..-.>

'", section 4;3."-'" TLDs are'efined as phosphors packaged for Field use.>,'n regard to the detection capabilities for thermoluminescent dosimeters, only one determination is required to evaluate the above.~capabilities per type of TLD.Furthermore, the above capabilities may be determined by the vendor who supplies the TLDs.Required detection capabilities are as follows: 5.3.1 Uniformity shall be determined by giving TLDs from the same batch an exposure equal to that resulting from an exposure rate of 10 uR/hr during the field cycle.The responses obtained shall have a relative standard deviation of less than 7.5%.A total of at least 5 TLDs 4 i,'~"shall be.evaluated.

5.3.2 Reproducibility

shall be determined by giving TLDs repeated exposures'" equal to,that resulting from an exposure rate of 10 uR/hr during the'ield cycle.The..average, of the relative'standard" deviations of, the responses shall be less than 3.0%.h total of at least 4 TLDs shall, be evaluated.

f}III l 4 e

5.3.3 Dependence

of exposure interpretation on the length of a field cycle shall be examined by placing TLDs for a period equal to at least a field cycle and a period equal to half the same field cycle in an area where the exposure rate is known to be constant.This test shall be conducted under approximate average winter temperatures, and,:approximate average..summer temperatures.

For these tests,.the ratio'of the response"-obtained in the field cycle to twice that obtained for half the field cycle shall not be less than 0.85.At least 6 TLDs shall be evaluated 5.3.4'nergy dependence shall be evaluated by the response.of TLDs to photons for several energies between approximately 30 keV and 3 MeV.The response shall not differ from that obtained with the calibration

'source by more than 25%for photons with energies greater than 80 keV and shall not be enhanced by more than a factor of two for photons with energies less than 80 keV.A total of at least 8 TLDs shall be evaluated.

5.3.5 The directional dependence of the TLD response shall be determined by comparing the response of the TLD exposed in the routine orientation

'*'" with respect to the calibration source with the response obtained for"'di'fferent-orientations;

  • To"accomplish this,-the, TLD-shall.be.,rotated through at least two perpendicular planes.'he response averaged-over all directions shall not differ from the response obtained in the standard calibration position by more than 1(C.A total of at least 4 TLDs shall be evaluated.

~<4~g.'t 5.3.6 Light dependence shall be determined by placing TLDs in the field for a period equal to the field cycle under the four conditions found in ANSI N545, section 4.3.6.The results obtained for the unwrapped TLDs shall not differ from those obtained for the TLDs wrapped in aluminum foil by more than 10K.A total of at least 4 TLDs shall be evaluated for each of the four conditions.

5.3;7'Moisture'dependence'shall"be-determined"by-placing=TLDs.(that is, the.phosphors~packaged"for field use)for a period equal to the field,...-

cycle in an area where the exposure rate is known to be constant.The TLDs shall be exposed under two conditions:

(1)packaged in a thin, sealed plastic bag, and (2)packaged in a thin, sealed plastic bag with sufficient water to yield observable'oisture throughout the.field cycle.The TLD or phosphor, as appropriate, shall be dried before readout.The response of the TLD exposed in the plastic bag containing water shall not differ from that exposed in the regular plastic bag by more than 10X.A total of at least 4 TLDs shall be evaluated for each condition.

'."5;3".8.-"a'Self.irradiation shall be determined by placing TLDs for a period equal to the field cycle in an area where the exposure rate is less than 10 uR/hr and the exposure during the field cycle is known.If necessary,.corrections shall be applied for the dependence of'exposure interpretation on*the length of the field cycle (ANSI N545,.section 4.3.3).The'average exposure inferred from the responses of-the TLDs shall not differ from the known exposure by more than an exposure equal to that resulting from an exposure rate of 10 uR/hr during the field cycle.A total of at least 3 TLDs shall be evaluated.

IfI<<gr TABLE l-l R VALUES FOR THE NINE MILE POINT UNIT 1 FACILITY apj i NUCLIDE 89 Sr 90 Sr 134 Cs 137 Cs 58 Co 60 Co 54 H Cr-51 Fe-59 Zn-65 Zr-95 I-131 I-133 Cs-136 Ba-140 Ce-141'e-55 Ni-63 ADULT-TOTAL BODY R~i{MREM/YR-Cx 2.05 E-3 4.37 E-1 1.89 E+0 1.12 E+0 6.47 E-4 1.85 E-3 2.72 E-3 7.40 E-7 4.05 E-6 3.01 E-3 1.09 E-l 1.69 E-7 3'4 E-4 3.53 E-5 2'3 E-1 3..92 E-5 5.49 E-9 3.47 E-4 3.41 E-3 TEEN-LIVER-,I-" N/A N/A 2.35 E+0 1.78 E+0 2.87 E-4 8.38 E-4 1.40 E-2 5.69 E-7 N/A 8.03 E-3 2.37 E-1 2.53 E-7 6.65 E-4 1.22 E-4 3.80 E-1 7.81'-7 5.17 E-8.1.60 E-3 7.46 E-3<<58-

,1 t l 4 f (

TABLE 1-2 PARAMETERS FOR THE LIQUID EFFLUENT PATHWAY PARAMETER Uap Mp Bip Daipi VALUE Adult~21.0 Kg/yr Teen 16.0 Kg/yr 0.2 590,ft./second.Each Element Each radionuclide REFERENCE (REG.GUIDE 1.109)Table E-5 Site Specific Site Specific Table A-1 Tables E-ll to E-14 Tp 26.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> Site Specific I I', le Ac P~Ak.

TABLE 2-1 Average Energy Per Disintegration ISOTOPE Ar-41 Kr-83m Kr-85 Kr-85m Kr-87 E mev/dis 1.294 0.00248 0.0022 0.159 0.793~Ref (3)EBmev/dis(4 0.464 0.0371 0.250 0.253 1.32 5Ref)(3)Kr-88 1.95 0.377 Kr-89 Kr-90 Xe-131M Xe-133 Xe-133m Xe-135 Xe-135m 2.22'2.10 0.0201 0.0454 0.042 0.247 0.432 (2)(2)1.37 1.01 0.143 0.135 0.3.9 0.317 0.095 (2)(2)Xe-137Xe-138 0.194 l.18'.64 0.611 (1)ORNL-4923, Radioactive Atoms-Su lement I, M.S.Martin, November 1973.(2)NEDO-12037,"Summary of Gamma and Beta Emitters and Intensity Data";M.E.""',".Meek, R.S.'Gilbert, January 1970.(The.average energy..was computed from-'the maximum energy using.the ICRP II equation,.

not the.1/3 value..assumption used in this reference).

(3)NCRP Report No.58,"A Handbook of Radioactivity Measurements Procedures";

1978 (4)The average energy includes conversion electrons.

fI I" l Qa I 4" 4~~~

LOCATION Residences Dairy Cows Milk Goats Meat Animals Gardens Site Boundary DIR E (98O)SE (1300)E (88')ESE (115)E (97m)ENE (67)MILES 1.4 2.6 7.9 1.8 1.8 0.4 1.8 E-07b 2.2 E-08c 1.3 E-08c 5.1 E-08c 1.0 E-07c 2.4 E-06bDd D~/m-2 5.2 E-09b 7.0 E-10c 1.6 E-10c 1 7 E 09c 3.5 E-09c 4.4 E-08cDd TABLE 3-1 Critical Receptor Dispersion Parsmetersa For Ground Level and Elevated Releases ELEVATED ELEVATED GROUNDe'4.02 E-07 6.00 E-08 2.57 E-08 1.16 E-07 2.53 E-07 6.63 E-06 GROUNDe D/I/Dm~8.58 E-09 1.64 E-09 6.10 K-10 3.54 E-09 5.55 E-09 6.35 E-08 a.These values will be used in dose calculations beginning in April 1986 but may be revised periodically to account for changes in locations of farms, gardens or critical residences.

b.Values based on 5 year annual meteorological data (C.T.Main, Rev.2)c.Values based on 5 year average grazing season meteorological data (C.T.Main Rev.2)d.Value are based on most restrictive X/Q land-based sector (ENE).(C.T.Main, Rev.2)e.Values are based on average annual meteorological data for the year 1985.

~" q TABLE 4-1 DOSE FACTORS POR NOBLE GASES Radionuclides Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 Xe-139 Ar-41 Gamma Air Dose Factor Mi BIZ d pCi-yr 1.93E+01 1.23E+03 1.72E+01 6.17E+03 1.52E+04 1.73E+04 1.63E+04 1.56E+02 3.27E+02 3 53E+02 3.36E+03 1.92E+03 1.51E+03 9.21E+03 5.28E+03 9.30E+03 Beta Air Dose Factor Ni mrad m p Ci-yr 2.88E+02 1.97E+03 1.95E+03 1.03E+04 2.93E+03 1.06E+04 7.83E+03 1.11E+03 1.48E+03 1.05E+03 7.39E+02 2.46E+03 1.27E+04 4.75K+03 6.52E+04 3.28E+03*Regulatory Guide 1:109,"'Calculation of Annual Doses to Man From Routine.-.Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CPR Part 50, Appends.x I," dated October 1977, page 1.109-21.

4p$e l l~"I b$I I h e TABLE 4-2 R VALUES-COW'S MILK-INFANT 2 md~rem/r uCi-sec NUCLIDE H 3" Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 80 Sr 90 Zr 95 I 131 I 133 CH 134 Cs 136 Cs 137 Ba 140 Ce 141 em~rem/r uCi/m T.BODY 2.408 03 GI-TRACT 2.40E 03 1.458 07 7.218 07 2.888 07 1.11E 08 5.268 09 1.708 08 1.798 10 5.588 02 6.928 08 7.918 06 3.598 09 1.038 09 2.378 09 5.948 06 1.448 03 6.918 06 8.748 07 2.888 07 1.128 08 9.638 09 1.228 08 Se758 08 3.92E 05 5.628 07 4.578 06 9'5E 07 4.19E 07 1.048 08 2.838 07 6.30E 06 7.468 04 2.178 06 4.548 06 7.368 06 BONE 8.438 07 1.05E 08 3.32E 09 5.948 09 7.018 10 3.238 03 1.348 09 1.85E 07 1.908 10 9.37E 08 2.858 10 1.158 08 2.008 04 LIVER 2.408 03 2.008 07 5.448 07 1..158 07 4.71E 07 1.148 10 7.878 02 1.57E 09 2.708 07 3.558 10 2.768 09 3.348 10 1.158 05 1.228 04 KIDNEY 2.40E 03 1.06804 4.44E 06 5.53E 09 Be48E 02 1.848 09 3'78 07 9.14E 09 1.10E 09 8.968 09 2.74E 04 3.76E 03 THYROID 2.408 03 4.878 04 5.178 ll 4.918 09 LUNG 2.408 03 4.478 04 2.668 07)5.418 07 3.758 09 2.258.08 3.638 09 7.038 04

~S X4 4 IJ~~g tp ThBLE 4-3 R VhLUES-COM'S MILK-CHILD 2 m~~remj r QCi-sec NUCLIDE H 3>Cr 51 Mn 54 Pe 55 Pe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 I 131 I 133 Cs 134 Cs 136 CQ 137 Ba 140 Ce 141~m~reml r uCi/m 3 T.BODY 1.58E 03 4.71B 04 2.87E 06 1.15E 07 4.52E 07 1.77E 07 6.81S 07 4.10E 09 8.93E 07 1.63B 10 3.56B 02 3.66E 08 4.11S 06 4.09E 09 8.53E 08 2.52B 09 3.27E 06 7.47B 02 CI-TRhCT 1.58E 03 2.50S 06 9.04E 06 6.85E 06 9.45B 07 3.37E 07 1.28E 08 1.16S 09 1.21S 08 8.68E 08 4.17E 05 5.73E 07 4.38E 06 1.05B 08 4.63E 07 1.07B 08 2.84B 07 6.28E 06 BONE 6.97E 07 5.61E 07 2.47E 09 3.13E 09 6.44$10 1.82S 03 6.40E 08 8.78E 06 1.18E 10 4.80S 08 1.79E 10 5.60E 07 1.01E 04 LIVER 1.58E 03 1.08B 07 3.07E 07 9.08E 07 5.77S 06 2.31E 07 6.59E 09 4.00E 02 6.44E 08 1.09E 07 1.94E 10 1.32E 09 1.71E 10 4.91E 04 5.03E 03 KIDNEY 1.58E 03 7.14E 03 3.02S 06 4.15E 09 5.72E 02 1.06E 09 1.81E 07 6.01E 09 7.07S 08 5.57B 09 1.60E 04 2.21E 03 THYROID 1.58E 03 2.61E 04 2.13E ll 2.02E 09 LUHC 1.58S 03)<4.77E 04 2.09E 07 2.63E 07 2.16E 09 1.05E 08 2.00S 09 2.93E 04 I r," 8)\~ff 4/!,gt p4 TABLE 4-4 R VALUES-COW'S MILK-TEEN 2 m~~rciml e uCi-secNUCLIDE 8 3>Cc'1 Mn 54 Fe 55 Pe 59 Co 5&Co 60 Zn 65 Sr 89 Sr 90 Zr 95 I 131 I 133 Cs 134 Cs 136 Cs 137 Ba 140 Ce 141*miami uCi/m 3 T.BODY 1.00E 2.31E 03 04&.10E 3.35E 2.04E 3.62E 9.42E 06 07 09 07 09 1.70E 02 1.98E 1.87E 5.60E 5.62B 3.44E 1.5&E 08 06 09 08 09 06 3.14E 02 1.43B 06 4.59E 06 2.1&E 07 GI-TRACT 1.00E 03 3.88E 06 1.4&E 07 8.52B 06 1.34E 08 5.21E 07 1.94E 08 1.85E 09 1.50E 08 1.07E 09 5.70E 05 7.31E 07 4.64B 06 1.50E 08 6.73E 07 1.40E 08 3.5&E 07 7.83E 06 BONE , 1.5&E 03 2.7&E 07 2.42E 07 1.26E 09 1.26E 09 3.81E 10 7.83E 02 2.64B 08 3.61E 06 5.12E 09 2.13E 08 7.42E 09 2.32E 07 4.10E 03 LIVER 1.00E 03 1.20E 06 1.97E 07 5.65E 07 3.78E 06 1.49E 07 4.3&E 09 2.47E 02 3.69B 08 6.13E 06 1.21E 10 8.37E 08 9.87E 09 2.84E 04 2.74E 03 KIDNEY 1.00E 03 5.06E 03 2.15E 06 2.&OE 09 3.63E 02 6.36E 08 1~0&E 07 3.83E 09 4.55E 08 3.36E 09 9.65E 03 1.29E 03 THYROID 1.00E 03 1.2&E 04 1.0&E ll 8.56E 08 LUNG 1.00E 03 3.30E 04 1.25E 07 1.7&E 07 1.46E 09 7.1&E 07 1.30B 09 1.91E 04 ll I pl xg5.i J TABLE 4-5 R VALUES-COM'S MILK-ADULT 2 md~rem/uci-sec NUCLIDE H 3~Cr 51 Mn 54 Pe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 I 131 I 133 Cs 134 CQ 136 Cs 137 Ba 140 Ce 141>m~rsml r uci/m T.BODY 7.69E 02 1.32E 04 8.25E 05 2.52E 06 1.25E 07 5.03B 06 1.93E 07 1.18S 09 1.97B 07 6.62E 09 9.72E 01 1.19E 08 1.05E 06 5.74E 09 3.55E 08 3.65E 09 8.43E 05 1.71E 02 GI-TRACT" 7.69S 02 3.32E 06 1.32E 07 6.21E 06 1.09B 08 4.56B 07 1.65B 08 1.65E 09 1.10E 08 7.80S 08 4.55E 05 5.49E 07 3.09E 06 1.23E 08 5.60E 07 1.08E 08 2.65E 07 5.78E 06 SONS 1.57E 07 1.39E 07 8.21E 08 6.85E 08 2.70E 10 4.48E 02 1.45E 08 1.98E 06 2.95E 09 1.25E 08 4.09E 09 1.29E 07 2.24E 03 LIVER 7.69E 02 4.32E 06 1.08E 07 3.26E 07 2.24E 06 8.77E 07 2.81E 09 1.44B 02 2.08E 08 3.44E 06 7.02E 09 4.93E 08 5.59E 09 1.62E 04 1.51E 03 KIDNEY 7.69E 02 2.91S 03 1.29E 06 1.75E 09 2.25E 02 3.57E 08 6.01E 06 2.27E 09 2.74E 08 1.90E 09 5.49E 03 7.02E 02 THYROID 7.69E 02 7.90E 03 6.82E 10 5.06B 08 LUNG 7.69E 02 1.75E 04 6.04E 06 9.10B 06 7.54E 08 3.76E 07 6.31E 08 9.25S 03

~e l'V~,J/

TABLE 4-6 R VALUES-GOAT'S HILK-INFANT 2 mm~eeml e uCi-sec NUCLIDS H 3~Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 I 131 I 133 Cs 134 Cs 136 CQ 137 Ba 140 Ce 141 em~eeml e uCi/m 3 T.BODY 4.90E 03 8.95B 03 5.45E 05 1.89S 05 9.37E 05 3.45B 06 1.34E 07&.31S 08 3.58E 08 3.57E 10 6.70E 01 8.31E 08 9.49E 06 1.08E 10 3.09E 09 7.10S 09 e 7.13E 05 1.72E 02 GI-TRACT 4.90B 03 2.61E 05 8.83E 05 8.98E 04 1.14B 06 3.45E 06 1.35E 07 1.16E 09 2.57E 08 1.84E 09 4.70E 04 6.74E 07 5.48E 06 2.89E 08 1.26E 08 3.13E 08 3.40E 06 7.57E 05 BONE 1.10E 06 1.36E 06 3.99E 08 1.25E 10 1.47E 11 3.88E.02 1.60E 09 2.23E 07 5.71E 10 2.81E 09 8.55E 10 1.38E 07 2.40E 03 LIVER 4.90S 03 2.40E 06 7.08E 05 2.38E 06 1.38E 06 5.65S 06 1.37E 09 9.45E Ol 1.89E 09 3.24E 07 1.07E 11 8.27E 09 1.00E 11 1.38E 04 1.46E 03 KIDNEY 4.90E 03 1.28E 03 5.33S 05 6.63E 08 1.02E 02 2.21E 09 3.81E 07 2.74E 10 3.30B 09 2.69E 10 3.29S 03 4.52E 02 THYROID 4.90E 03 5.84B 03 6.21E ll 5.89S 09 LUNG 4.90E 03 1.14E 04 3.46B 05 7.03B 05 1.12E 10 6.74E 08 1.09E 10 8.50E 03 ql I 0 4i$:~I'<~r L OFT l g 1 I~N"'+i'5 1 TABLE 4-7 R VALUES-GOAT'S MILK-CHILD 2 m~~raml r uCi-sec NUCLIDE H 3" Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 I 131 I 133 Cs 134 Cs 136 Cs 137 Ba 140 Ce 141*m~rrmj r uCi/m T.BODY 3.23E 03 5.65E 03 3.44E 05 1.49E 05 5.88B 05 2.12E 06 8.17E 06 4.92S 08 1.87B 08 3.43E 10 4.27E 01 4.39E 08 4.93E 06 1.23E 10 2.56S 09 7.57E 09 3.92E 05 8.97E 01 GI-TRACT 3.23E 03 3.00B 05 1.08E 06 8.91E 04 1.23E 06 4.04E 06 1.53E 07 1.39E 08 2.54B 08 1.82E 09 5.01S 04 6.88E 07 5.25B 06 3.14E 08 1.39E 08 3.21B 08 3.41E 06: 7.54E 05 BONE 9.06E 05 7.29E 05 2.97B 08 6.56S 09 1.35E ll 2.18S 02 7.68E 08 1.05E 07 3.55E 10 1.44E 09 5.36E 10 6.72E 06 1.21E 03 LIVER 3.23E 03 i 1.29E 06 4.81E 05 1.18E 06 6.92E 05 2.77E 06 7.91E 08 4.80E 01 7.72E 08 1.30E 07 5.82E 10 3.96E 09 5.13E 10 5.89E 03 6.04E 02 KIDNEY 3.23E~03 8.57E 02 3.62E 05 4.98E 08 6.87E 01 1.27S 09 2.17E 07 1.80E 10 2.11E 09 1.67E 10 1.92E 03 2.65E 02 THYROID 3.23E 03 3.14E 03 2.55E ll 2.42E 09 LUNG 3.23E 03 5.73E 03 2.72E 05 3.42E 05 6.47E 09 3.14E 08 6.01E 09 3.51S 03 V&I kP*1 y E r1)~g ThBLE 4-8 R VhLUES-GOhT'S MILK-TEEN 2 m~~rmm/uCi-see NUCLIDB H 3" Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 I 131 I 133 Cs 134 CH 136 Cs 137 BR 140 Ce 141*m~ram/uCi/m 3 T.BODY 2.04E 03 2.77S 03 1.71E 05 5.97B 04 2.83E 05 1.04B 06 4.02E 06 2.45E 08 7.59S 07 1.98B 10 2.04E 01 2.38B 08 2.24S 06 1.68E 10 1.69S 09 1.03E 10 1.80E 05 3.77E Ol GI-TRhCT 2.04E 03 4.66B 05 1.77E 06 1.11E 05 1.74B 06 6.25E 06 2.32E 07 2.22S 08 3.16E 08 2.25E 09 6.84E 04 8.77E 07 5.57E 06 4.50E 08 2.02E 08 4.21E 08 4.30E 06 9.39E 05 BONE 3.61E 05 3.14E 05 1.51E 08 2.65E 09 8.81B 10 9.40E Ol 3.17B 08 4.34B 06 1.54E 10 6.38E 08 2.22E 10 2.97E 06 4.92E 02 LIVER 2.04E 03 8.64E 05 2.56E 05 KIDNEY 2.04E 03 6.07E 02 2.58E 05 2.97E 01 4.43E 08 7.36E 06 3.62E 10 2.51B 09 2.96E 10 3.41E 03 3.28E 02 4.36E Ol 7.63E 08 1.29E 07 1.15E 10 1.37E 09 1.01E 10 1.16E 03 1.55E 02 7.34E 05 4.63E 05 1.78E 06 5.25E 08 3.36E 08 THYROID 2.04E 03 1.54E 03 1.29E ll 1.03E 09 LUNG 2.04E 03 3.95E 03 1.62E 05I4 2.31E 05 4.39E 09 2.15E 08 3.91E 09 2.30E 03 II (1 J h J 0 TABLE 4-9 R VALUES-GOAT'S MILK-ADULT 2 mm~eeml uci-sec NUCLIDE H 3" Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 I 131 I 133 Cs 134 Cs 136 Cs 137 Ba 140 Ce 141 em~rem/uCi/m T.BODY 1.57E 03 1.59E 03 9.89E 04 3.28E 04 1.62E 05 6.03E 05 2.32E 06 1.42E 08 4.13E 07 1.39E 10 1.17E Ol 1.43E 08 1.26B 06 1.72E 10 1.06E 09 1.10E 10 1.01E 05 2.06E 01 GI-TRACT 1.57E 03 3.99E 05 1.59E 06 8.07E 04'1.41E 06 5.46E 06 1.98B 07 1.97E 08 2.31E 08 1.64E 09 5.46E 04 6.59E 07 3.71B 06 3.69E 08 1.68E 08 3.25E 08 3.18E 06 6.94B 05 BONE e 2.04E 05 1.80E 05 9.85B 07 1.44E 09 5.67E 10 5.37E.Ol 1.74E 08 2.37E 06 8.85E 09 3.75E 08 1.25E 10 1.54E 06 2.68E 02 LIVER 1.57E 03 e 5.19E 05 1.41E 05 4.23E 05 2.69E 05 1.05E 06 3.14E 08 1.72E 01 2.50E 08 4.13E 06 2.11E 10 1.48E 09 1.68E 10 1.94E 03 1.81E 02 KIDNEY 1.57E 03 3.49E 02 1.54E 05 2.10E 08 2.70E Ol 4.28E 08 7.21E 06 6.82E 09 8.23E 08 5.70E 09 6.59E 02 8.43E Ol THYROID 1.57E 03 9.48E 02 8.18E 10 6.07E 08 LUNG 1.57E 03 2.11E 03 7.85E 04I 1.18E 05 2.26E 09 1.13E 08 1.89E 09 1.11E 03 Pt r 1 C i TABLB 4-10 R VALUES-MEAT-CHILD 2 m~~reml r uCi-sec NUCLIDE H 3<Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 I 131 I 133 Cs 134 Cs 136 Cs 137 Ba 140 Ce 141 em~rem/r uCi/m 3 T.BODY 2.36B 02 4.07E 03 1.09E 06 4.74B 07 1.42E 08 2.39B 07 1.09E 08 3.72B 08.6.55E 06 1.52E 09 2.48E 05 4.64E 06 1.55B-01 1.67E 08 1.35B 07 1.04B 08 1.22B 06 7.57E 02 GI-TRACT 2.36B 02 2.16E 05 3.45B 06 2.84B 07 2.97B 08 4.56E 07 2.05E 08 1.05E 08 8.87E 06 8.08B 07 2.91E 08 7.29E 05 1.66E-Ol 4.26E 06 7.34B 05 4.43B 06 1.06B 07 6.36B 06 BONE 2.89B 08 1.76B 08 2.25E 08 2.29$08 6.00E 09 1.27B 06 8.14B 06 3.32B-01 4.81B 08 7.60E 06 7.39B 08 gelOE 07 1.02B 04 LIVER 2.36E 02 4.11E 06 1.53E 08 2.85E 08 7.82E 06 3.70E 07 5.99E 08 2.79E 05 8.19E 06 4.11B-01 7.90B 08 2.09E 07 7.07B 08 1.84E 04 5.10E 03 KIDNEY 2.36E 02 6.17E 02 1.15E 06 3.77E 08 3.99E 05 1.34B 07 6.85B-01 2.45E 08 1.11E 07 2.30E 08 5'8E 03 2.24E 03 THYROID 2.36B 02 2.26E 03 2.71B 09 7.63E-01 LUNG 2.36E 02 4.12B 03 8.66B 07)'.26E 07 8.78B 07 1.66E 06 8.29E 07 1.10E 04 J'WP wp,t g.yl'I p 4 TABLE 4-11 R VALUES-MBAT-TEEN 2 m~~reml r uCi-sec NUCLIDE Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 I 131 I 133 Cs 134 Cs 136 CB 137 Ba 140 Ce 141 em~rem/r uCi/m 3 T.BODY 1.95E 02 2.61E 03 7.12E 05 2.49E 07 8.95E 07 1.54E 07 7.03E 07 2.43B 08 3.47E 06 1.15E 09 1.55E 05 3.30E 06 9.25E-02 2.98E 08 1.16B 07 1.86B 08 7.33E 05 4.14E 02 GI-TRACT 1.95E 02 4.39E 05 7.37E 06 4.62E 07 5.48B 08 9.22E 07 4.06E 08 2.20E 08 1.44E 07 1.30E 08 5.20E 08 1.22E 06 2.30E-01 7.99E 06 1.40E 06 7.59E 06 1.75E 07 1.04E 07 BONE 1.50E 08 9.93E 07 1.50E 08 1.21E 08 4.64E 09 7.15E 05 4.39E 06 1.79E-01 2.73E 08 4.41E 06 4.01E 08 1.14E 07 5.43E 03 LIVER 1.95E 02 3.59E 06 1.07E 08 2.32E 08 6.69E 06 3.12E 07 5.20E 08 2.25E 05 6.14B 06 3.03E-01 6.42E 08 1.73E 07 5.34B 08 1.39E 04 3.63E 03 KIDNEY 1.95E 02 5.72E 02 1.07E 06 3.33E 08 3.31E 05 1.06E 07 5.32E-01 2.04E 08 9.44E 06 1.82E 08 4.72E 03 1.71E 03 THYROID 1.95E 02 1.45E 03 1.79E 09 4.23E 01 LUNG 1.95E 02 3.73E 03 6.77E 074 7.31E 07 7.78E 07 1.49E 06 7.06E 07 9'7E 03 t CAr 4r TABLE 4-12 R VALUES-MEAT-ADULT 2 md~rem/r uCi-sec NUCLIDE H 3~Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 I 131 I 133 CH 134 Cs 136 Cs 137 Ba 140 Ce 141*m~reml r uCi/m T.BODY 3.27E 02 3.26B 03 8.98E 05 2.98E 07 1.12E 08 1.95E 07 8.87B 07 3.06E 08 4.12E 06 1.76E 09 1.94E 05 4.33E 06 1.13E-Ol 6.68E 08 1.61E 07 4.33E 08 9.01B 05 4.96E 02 GI-TRACT 3.27B 02 8.21E 05 1.44E 07 7.34B 07 9.73B 08 1.76E 08 7.56E 08 4.27B 08 2.30E 07 2.07B 08 9.07E 08 1.99E 06 3.34E-01 1.43E 07 2.53E 06 1.28B 07 2.83E 07 1.67B 07 BONE 1.85E 08 1.24E 08 2.13E 08 1.43E 08 7.17E 09'.92E 05 5.28E 06 2.14E-01 3.43E 08 5.65E 06 4.83E 08 1.38K 07 6.47E 03 LIVER 3.27E 02 4.71E 06 1.28E 08 2.92E 08 8.68E 06 4.02E 6.78E 07 08 2.86E 05 7.55E 06 3.72E-01 8.15K 08 2.23E 07 6.61E 08 1.73E 04 4.38E 03 KIDNEY 3.27B 02 7.19E 02 1.40E 06 4.53E 08 4.49E 05 1.29E 07 6.49B-01 2.64E 08 1.24E 07 2.24E 08 5.87E 03 2.03E 03 THYROID 3.27E 02 1.95K 03 2.48E 09 5.46E 01 LUNG 3.27E 02 4.33$03 7.14B 07].8.16E 07 8.78E 07 1.70E 06 7.46E 07 9.89E 03 A T ThBLE 4-13 R VhLUES-VSGSThTION

-CHILD 2 md~rem/r uCi-sec NUCLIDE H 3*Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Se 90 Zr 95 I 131 I 133 Cs 134 Cs 136 Cs 137 Ba 140 Ce 141 em~rem/r uCi/m 3 T.BODY 4.048 03 1.168 05 1.73E 08 1.258 08 3.17E 08 1.928 08 1.118 09 1.70S 09 1.03E 09 3.498 ll 7.448 05 8.168 07 1.678 06 5.408 09 1.438 08 3.528 09 1.618 07 4.75E 04 GI-TRhCT 4.048 03 6.15E 06 5.44E 08 7.50E 07 6.628 08 3.668 08 2.088 09 4.818 08 1.408 09 1.868 10 8.718 08 1.288 07 1.788 06 1.388 08 7.77E 06 1.50E 08 1.408 08 3.998 08 BONE 7.638 08 3.938 08 1.03E 09 3.628 10'.388 12 3.808 06 1.438 08 3.578 06 1.568 10 8.048 07 2.488 10 2.768 08 6.42E 05 LIVER 4.048 03 6.498 08 4.05E 08 6.36E 08 6.278 06 3.768 08 2.748 09 8.358 05 1.44E 08 4'28 06 2.568 10 2.218 08 2.398 10 2.428 05 3.20E 05 KIDNEY 4.048 03 1.768 04 1.82E 08 1.738 09 1.208 06 2.368 08 7.368 06 7.93E 09 1.18E 08 7.78E 09 7.878 04 1.40E 05 THYROID 4.048 03 6.448 04 4.758 10 8.218 08 LUNG 4.048 03 1.188 05 2.298 0814 1.848 08 2.848 09 1.768 07 2.808 09 1.448 05 F4-0 c4~'r.elf/~'~

e ThBLE 4-14 R VhLUES-VEGEThTION

-TBEN 2.m~~eeml e uci-sec NUCLIDE H 3>Cr 51 Hn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 I 131 I 133 Cs 134 CQ 136 Cs 137 Ba 140 Ce 141*deem/e uCi/m 3 T.BODY 2.61E 03 6.11E 04 8.79E 07 5.13E 07 1.60E 08 9.79E 07 5.57E 08 8.68B 08 4.36E 08 2.05E ll 3.68E 05 5.77E 07 1.01E 06 7.54E 09 1.13E 08 4.90B 09 8.88E 06 2.12E 04 GI-TRhCT 2.61E 03 1.03E 07 9.89E 08 9.53B 07 9.78E 08 5.85E 08 3.22E 09 7.88E 08 1.81E 09 2.33E 10 1.23E 09 2.13B 07 2.51E 06 2.02E 08 1.35B 07 2.00B 08 2.12E 08 5.29E 08 HONE 3.10E 08 1.77E 08 5.36E 08 1.52E 10 8.32E ll 1.69E.06 7.68E 07 1.96E 06 6.96E 09 4.28E 07 1.06E 10 1.38E 08 2.77E 05 LIVER 2.61E 03 4.43E 08 2.20E 08 4.14E 08 4.25E 07 2.47E 08 1.86E 09 5.35B 05 1.07E 08 3.32E 06 1.62E 10 1.68E 08 1.41E 10 1.69E 05 1.85E 05 KIDNEY 2.61E 03 1.34E 04 1.32E 08 1.19E 09 7.86E 06 1.85E 08 5.83E 06 5.16E 09 9.16E 07 4.78E 09 5.72E 04 8.70E 04 THYROID 2.61E 03 3.39E 04 3.14E 10 4.64E 08 LUNG 2.61E 03 8.72E 04 1.40B 08I E 1.30E 08 1.97E 09 1.44E 07 1.86E 09 1.14E 05 S>>I'r I r Vt"i P 1 t S"4 k tAa J+ly t 0 e TABLE 4-15 R VALUES-VEGETATION

-ADULT 2 m~~reml r uCi-sec NUCLIDE N 3<Cr 51 Mn 54 Fe 55 Pe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 I 131 I 133 Cs 134 CB 136 Cs 137 Ba 140 Ce 141 em~rem/uCi/m 3 T.BODY 2.28E 03 GI-TRACT 2.28S 03 3.22S 07 1.12E 08 6.71E 07 3.67E 08 5.77S 08 2.87E 08 1.64E ll 2.51S 05 6.61E 07 1.12S 06 8.83E 09 1.19E 08 5.94E 09 8.40E 06 1.48E 04 7.91E 07 9.75S 08 6.07E 08 3.12$09 8.04E 08 1.60E 09 1.93S 10 1.17E 09 3.04E 07 3.30E 06 1.89E 08 1.88E 07 1.76E 08 2.64E 08 4.99E 08 4.60E 04 1.16E 07 5.83E 07 9.36E 08 BONE 2.00E 08 1.24E 08 4.01E 08 1.08E 10 6.70E ll 1.16E 06 8.07E 07 2.11E 06 4.54E 09 4.19E 07 6.63E 09 1..28E 08 1.93E 05 LIVER 2.28E 03 3.05S 08 1.38S 08 2.93E 08 2.99E 07 1.66E 08 1.28E 09 3.71E 05 1.15E 08 3.67E 06 1.08S 10 1.66E 08 9.07E 09 1.61E 05 1.$1E 05 KIDNEY 2.28E 03 1.01E 04 9.09E 07 8.54E 08 5.82E 05 1.98E 08 6.40E 06 3.49E 09 9.21E 07 3.08E 09 5.47E 04 6.07E 04 THYROID 2.288 03 2.75E 04 3.78E 10 5.39E 08 LUNG 2.28E 03 6.10E 04 7.69E 07<8.17E 07 1.16E 09 1.26E 07 1.02E 09 9.22E 04

~Ot kt l 4!a TABLE.4-16 R VALUES-INHALATION

-INFANT I~ram/r uCi/m 3 NUCLIDE H 3 Cr 51 Mn 54 Pe 55 Fe 59 Co Ss Co 60 Zn 65 Sr 89 Sr 90 Zr 95 I 131 I 133 CQ 134 Cs 136 Cs 137 Ba 140 Ce 141 T.BODY 6.468 02 8.938 01 4.988 03 3.338 03 9.468 03 1.82E 03 1.188 04 3.108 04 1.148 04 2.598 06 2.038 04 I 1.968 04 5.598 03 7.448 04 5.288 04 4.548 04 2.898 03 1.998 03 GI-TRACT 6.468 02 3.568 02 7.058 03 1.098 03 2.478 04 1.118 04 3.188 04 5.138 04 6.398 04 1.318 05 2.178 04 1.068 03 2.158 03 1.338 03 1.438 03 1.338 03 3.83E 04 2.158 04 BONE 1.978 04 1.358 04 1.938 04 3.978 05 4.OSS O7 1.158 05 3.798 04 1.328 04 3.968 05 4.828 04 5.4SS OS 5.59E 04 2.778 04 LIVER 6.468 02 2.538 04 1.178 04 2.368 04 1.228 03 8.018 03 6.258 04 2.788 04 4.438 04 1.92E 04 7.02E 05 1.348 05 6.118 05 5.598 01 1.668 04 KIDNEY 6.46E 02 1.328 01 4.98E 03 3.248 04 3.10E 04 5.178 04 2.248 04 1.908 05 5.638 04 1.728 05 1.348 Ol 5.248 03 THYROID 6.468 02 5.758 01 1.488 07 3.558 06 LUNG 6.468 02 1.288 04 9.98E 05 8.698 04 1.018 06 7.768 05 4.508 06 6.468 05 2.038 06 1.128 07 1.758 06 7.958 04 1.178 04 7.128 04 1.598 06 P 5.168 05

%W\4"p CC>4r ThBLB.4-17 R VhLUES-INHhLhTION

-CHILD masm/r uCi/m 3 NUCLIDB H 3 Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 I 131 I 133 CQ 134 CQ 136 CQ 137 Ba 140 Ce 141 T.BODY 1.128 03 1.548 02 9.508 03 7.778 03 1.678 04 3.168 03 2.268 04 7.028 04 1.728 04 6.438 06 3.698 04 2.728 04 7.688 03 2.248 05 1.168 05 1.288 05 4.328 03 2.898 03 CI-TRhCT 1.128 03 1.088 03 2.298 04 2.878 03 7.068 04 3.438 04 9.618 04 1.638 04 1.678 05 3.438 05 6.108 04 2.848 03 5.478 03 3.848 03 4.178 03 3.618 03 1.028 05 5.658 04 BONE 4.748 04 2.078 04 4.258 04 5.998 05 1.018 08 1.908 05 4.808 04 1.668 04 6.50E 05 6.508 04 9.058 05 7.398 04 3.92E 04 LIVER 1.128 03 4.298 04 2.528 04 3.348 04 1.778 03 1.318 04 1.138 05 4.178 04 4.808 04 2.038 04 1.01S 06 1.718 05 8.248 05 6.478 Ol 1.958 04 KIDNEY 1.128 03 2.43E 01 1.008 04 7.138 04 5.958 04 7.878 04 3.378 04 3.308 05 9.538 04 2.828 05 2.118 Ol 8.538 03 THYROID 1.128 03 8.538 01 1.628 07 3.848 06 LUNG 1.128 03 1.708 04 1.57S 06 1.118 05 1.278 06 1.10E 06 7.068 06 9.948 05 2.158 06 1.478 07 2.238 06 1.218 05 1.458 04 1.048 05 1 748 061*5.438 05 V 4'>>I~<<kA~I<<ff,*I fl>>'>>-<<Ar I<<4>>,~'>>>>N>>I 7g>>

TABLE 4-18 R VALUES-INHALATION

-TEEN m~mami m uCi/m 3 NUCLIDE H 3 Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 I 131 I 133 CH 134 Cs 136 Cs 137 Ba 140 Ce 141 T.BODY 1.27E 03 1.358 02 8.398 03 5.548 03 1.438 04 2.778 03 1.98E 04 6.238 04 1.25E 04 6.678 06 3.158 04 2.648 04 6.218 03 5.488 05 1.378 05 3.118 05 3.518 03 2.168 03 GI-TRACT 1.278 03 3.008 03 6.678 04 6.398 03 1.788 05 9.518 04 2.598 05 4.668 04 3.718 05 7.648 05 1.498 05 6.488 03 1.038 04 9.758 03 1.098 04 8.478 03 2.288 05 1.268 05 BONE 3.348 04 1.598 04 3.858 04 4.348 05 1.08E 08 1.458 05 3.548 04 1.218 04 5.028 05 5.148 04 6.698 05 5.468 04 2.848 04 LIVER 1.27E 03 5.108 04 2.388 04 3.698 04 2.078 03 1.518 04 1.338 05 4.588 04 4.908 04 2.05E 04 1.138 06 1.938 05 8.478 05 6.698 01 1.898 04 KIOMEY 1.278 03 3.078 Ol 1.278 04 8.63E 04 6.738 04 8.39E 04 3.59E 04 3.75E 05 1.108 05 3.048 05 2.248 Ol 8.878 03 THYROID 1.278 03 7.498 01 1.468 07 2.928 06 LUNG 1.27E 03 2.098 04 1.988 06 1.248 05'.538 06 1.348 06 8.718 06 1.248 06 2.41E 06 1.65E 07=-2.688 06 1.468 05 1.778 04 1.218 05 2.038 06 6.13E 05 k~I+vs.f1 TABLE 4-19 R VALUES-INHALATION

-ADULT m~rem/r uC1/m, 3 e NUCLIDE H 3 Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 I 131 I 133 Cs 134 Cs 136 Cs 137 Ba 140 Ce 141 T.BODY 1.268 03 9.998 Ol 6.29E 03 3.948 03 1.058 04 2.078 03 1.488 04 4.658 04 8.718 03 6.09E 06 2.328 04 2.058 04 4.518 03 7.278 05 1.108 04 GI-TRACT 1.268 03 3.32E 03 7.72E 04 6.038 03 1.888 05 1.068 05 2.848 05 5.348 04 3.498 05 7.218 05 1.508 05 6.278 03 8.878 03 1.048 04 1.17E 04 2.568 03 1.53E 03 2.188 05 1.20E 05 4.27E 05 8.398 03 BONE 2.468 04 1.178 04.3.248 04 3.048 05 9.91E 07 1.078 05 2.528 04 8.638 03 3.728 05 3.908 04 4.788 05 3.908 04 1.998 04 LIVER 1.268 03 3.958 04 1.708 04 2.778 04 1.588 03 1.158 04 1.03E 05 3.44E 04 3.578 04 1.488 04 8.478 05 1.468 05 6.208 05 4.908 Ol 1.358 04 KIDNEY 1.268 03 2.288 01 9e838 03 6e898 04 5.418 04 6.12E 04 2.588 04 2e878 05 8.558 04 2.22E 05 1.678 Ol 6.25E 03 THYROID 1.26E 03 5.948 Ol 1.198 07 2.158 06 LUNG 1.268 03 1.448 04 1.408 7.218 1.018 06 pg c 06 9.758 04 1.208 04 7.518 04 1.278 06 3.618 05 9.278 05 5.968 06 8.638 05 1.408 06 9.59E 06 1.778 06 lpga TABLE 4-20 R VALUES-GROUND-ALL AGE GROUPS 2 M~modem/e>>Ci/sec NUCLIDE 1.BODY Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Zr 95 I.131 I 133~.Cs 134 Cs 136 Cs 137"Ba 140'Ce 141, I 135 Ba/La 140 Nb 95 Sb 125 4.66E 06 1.34E 09 2.75E 08 3.79E 08 2.15E 10 7.49E 08 2.23E 04 2.49E 08 1.72E 07 2.47E 06 6.82E 09 1.49E 08 1.03E 10 2.05E 07 1.36E 07 Later Later Later Later PYf 4 4 0 1 etr"'g'i,~

Nine Mile Point Nuclear Station Radiological Environmental Monitoring Program Sampling Locations Table 5.1 Type of Sample*Map Location (Env.Collection Site Pro am No.)Location Radioiodine and Paxticulates (air)Nine Mile Point Road North (R-1)1.8 mi 8 88'Radioiodine and Particulates (aix')Co.Rt.29&Lake Road (R-2)1.1 mi 8 104'SE Radioiodine and Particulates (air)Co.Rt.29 (R-3)1.5 mi 8 132'E Radioiodine and Particulates (air)Village of Lycoming, NY (R-4)1.8 mi 8 143'E"Radioiodine and Particulates (air)5.Montario Point Road (R-5)16.4 mi 8 42'E Direct Radiation (TLD)6 Direct Radiation (TLD)7 Direct Radiation (TLD)8 Direct Radiation (TLD)9 Direct Direct Radiation (TLD)10 Radiation (TLD)ll Direct Direct Radiation (TLD)15 Radiation (TLD)16 Direct Radiation (TLD)12.Direct Radiation (TLD)13.Direct Radiation (TLD)14 North Shoreline Area (75)North Shoreline Area (76)Noxth Shoreline Area (77)North Shoreline Area (23)JAP East Boundary (78)Rt.29 (79)Rt.29 (80)Miner Road (81)Miner Road (82)Lakeview Road (83)Lakeview Road (84)0.1 mi 8 5'0.1 mi 8 25'NE 0.2 mi 8 45'E 0.8 mi 8 70'NE 1.0 mi 8 90'1.1 mi 8 115'SE 1.4 mi 8 133'E 1.6 mi 8 159'SE 1.6 mi 8 181'1.2 mi 8 200'SW 1.1 mi 8 225'W Direct Radiation (TLD)17 Direct Radiation (TLD)18~p-See Figures 5.1-1 and 5.1-2 Site Meteorological Tower (7)0.7 mi 8 250'SW Energy Information Center (18)0.4 mi 8 265' I" Ill I'i~I r F J gA Qt+!8 W+'

Nine Mile Point Nuclear Station Radiological Environmental Monitoring Program Sampling Locations Table 5.1 (Continued)

Type of Sample*Map Location (Env.Collection Site Program No.)Location Surface Water 39 Direct Radiation (TLD)19'Direct Radiation (TLD)20 Direct Radiation (TLD)21 Direct Radiation (TLD)22 Direct Radiation (TLD)23 Direct Radiation (TLD)24 Direct'adiat'ion"(TLD) 25 Direct Radiation (TLD)26 Direct Radiation (TLD)27 Direct Radiation (TLD)28 Direct Radiation (TLD)29 Direct Radiation (TLD)30 Direct Radiation (TLD)31 Direct Radiation (TLD)32 Direct Radiation (TLD)33 Direct Radiation (TLD)34 Direct Radiation (TLD)35 Direct Radiation (TLD)36'irect Radiation (TLD)37 Surface Water 38 North Shoreline (85),North Shoreline (86)North Shoreline (87)Hickory Grove (88)Leavitt Road (89)Rt.104 (90)Rt.51A (91)Maiden Lane Road (92)Co.Rt.53 (93)Co.Rt.1 (94)Lake Shoreline (95)Phoenix, NY Control (49)S.W.Oswego, Control (14)Scribe, NY (96)Alcan Aluminum, Rt.1A (58)Lycoming, NY (97)New Haven, NY (56)W.Boundary, Bible Camp (15)Lake Road (98)OSS Inlet Canal (NA)JAFNPP Inlet Canal (NA)0.2 mi 8 294'NW 0.1 mi 8 315'W 0.1 mi 8.341'NW 4.5 mi 8 97'4.1 mi 8 ill'SE 4.2 mi 8 135'E 4-8 mi 8 156'SE 4 4 mi 8 183'6 4.4 mi 8 205'SW 4.7 mi 8 223'W 4.1 mi 8 237'SW 19.8 mi 8 170'12.6 mi 8 226'W 3.6 mi 8 199'SW 3.1 mi 8 220'W 1.8 mi 8 143'E 5.3 mi 8 123'SE 0.9 mi 8 237'SW 1 2 mi 8 101'7.6 mi 8 235'W 0 5 mi 8 70'NE (NA)~not applicable

  • Map~See'igures 5.1-1 and 5.1-2 J gv*l 1 1 I"~I I SI Nine Mile Point Nuclear Station Radiological Environmental Monitoring Program Sampling Locations Table 5.1'Continued)

Type of Sample*Map (Env.Location Collection Site Pro ram No.)Location Shoreline Sediment Fish Fish Fish Milk Milk Milk Food Product Food Product Food Product Food Product Food Product Food Product Food Product (CR)40 41 42: 43, 44 45 46 47 48 49 50 51 52 54 Sunset Bay Shoreline (NA)NMP Site Discharge Area (NA)NMP Site Discharge Area (NA)Oswego Harbor Area (NA)Milk Location 850 Milk Location 87 Milk Location 816 Milk Location 865 Produce Location 86**(Bergenstock)(NA)Produce Location 81**(J.Parkhurst)(NA)Produce Location 82<+(Vitullo)(NA)Produce Location 85*" (C.S.Parkhurst)(NA)Produce Location III3**(C.Narewski).Produce'Location 84**(S.Morris)(NA)Produce Location 87*" (Mc Millen)(NA)1.5mi 8 80 E 0.3 mi 8 315'W and/or 0.6 mi 8 55'E 6.2 mi 8 235'W 9.3 mi 8 93'5.5 mi 8 107'SE 5.9 mi 8 190'17.0 mi 8 220'W 1.9 mi 8 141'E 1.8 mi 8 96'1.9 mi 8 101'1.5 mi 8 114'SE 1.6 mi 8 84'2.0 mi 8-110'SE 15.0 mi 8 223'W 1 d w,l V CI'E4 J'F c>l I Nine Mile Point Nuclear Station Radiological Environmental Monitoring Program Sampling Locations Table 5.1 (Continued)

Type of Sample*Map (Env.Location" Collection Site"'-"Pro am No.)-.Location Food Product'(CR)55:.Produce.Location/$8"*(Denman)(NA)12.6 mi 8 225'W Food Product'ood Product Food Product Food Product 56 57 58 59 Produce Location/P9"*(O'onnor)(NA)..Produce Location 810**(C.L~on)(NA)Produce Location 811**(C.R.Parkhurst)(NA)Produce Location 812*" (Johnson)(NA)1.6 mi 6 171'2.2 mi 8 123'SE 2.0 mi 8 112'SE 1.9 mi 8 103 ESE 6 C I*Map-See Figures 5.1-1 and 5.1-2**Food Product Samples need not necessarily be col1ected from all listed locations.

Collected samples will be of the highest calculated site average D/Q.(N/A)~not applicable CR~Control Result (location)

  • =y" QPr.l Y<g~lk 14 1$I4<o~Ap (II FIGURE 5.(-I Hino Mlle Point On.Site Mep gf I Oweaewol SW lych'4W Jsh I>ca S%SW~I~NO%/ii 11 1$1$14 1$I 0 15'I t,"p*,"<~.(4,'e'E t*'>.~<(+t V'I I 1 rl Wt"qg'h~q~h*f

~t(lt It i~.llillNt I~~t pl 0 O 0 C Q Pl'll EP lO Pl

.r 4.JA$tt, sA W+t,O~" C'1+I l APPENDlX-A DOSE PARAMETERS FOR lODlNE 131 AND'l33 g PARil CULATES AND TBlTl 0 liras-88-'-

t t 4, HA h 0+49&TI iA w.jL<rW$sa'~'s't~T I 4 I Wl 44 , 1;)he s&2-"i i~r~w"y~~~" y 4'~M~'I~v I'Q DOSE PAiUMETERS FOR IODINE-131 AND-L33i PARTICULATES AND TRITIUM This appendix contains the methodology which was used to calculate the dose parameters for I-L31, I-L33, particulates, and tritium..The dose parameter, Ri, was-calculated using the methodology outlined in NUREG&L33 and'Regulatory"Guide L.L09,.Revision'L.-.

The-radioiodine and particulate Technical.-.;.Specification (Section 3.6.15)is applicable to the location in the unrestricted area where the combination of existing pathways and receptor age~i..groups indicates, the maximum potential exposure occurs, i.e., the critical receptor.The inhs1ation and ground plane exposure pathways are considered to exist at all locations but the critical location will be used for dose purposes.The grass-goat-misc, the grass-cow mQ3c, grass-caveat, and vegetation pathways are considered to exist at specific locations.

Ri values have been calculated for the adult, teen, child and infant age groups for all pathways.The methodology used to calculate these values foLlows: i,,:.',.,,'i,, A.L,Inhalation Pathwa R.~K(BR)(DFA)where~+~dose factor for each identified radionuclide i of the organ of interest (units-~mrem/hr per yCi/m);K'BR)(DFA),,'a'constant of unit conversion:

-10 pCi/qCi;6~Breathing rate of the receptor of age group a, (units M/yr);3 organ inhalation'dose.factor for radionuclide i for the receptor of age group a, (units~mrem/pCi).

89-mr~~t W:L~e4q1 t+,i A

~;The breathing rates (BR)for the various age groups, as given in Table a E-5 of Regulatory Guide 1.109 Revision 1, are tabulated below.A e Grou (a)Breathin Rate (m~/yr)Infant Child Teen-Adult 1rr00 3700 8000 8000 lnhalatron dose factors (DFA.)for the various age groups are given in i a"Tables E-7 through E-10 of Regulatory Guide 1.109 Revision 1.A.2 Ground Plane Pathwa I(R=K'K" (SF)DFG i XI t (Im)where: G Ri dose factor for the ground plane pathway for each Identified radionuclide i fOr the organ of interest (units=mrem/yr per uCI/sec per m)K'.a-constant of unit conversion:

10 pCI/uCi;6 K"=a constant of unit conver sion;8760 hr/year; g4 I l.l 0 the radiological decay constant for radionuclide i, (units=sec)t=the exposure ttme, sec;4 8 4.73 x 10 sec (IS years);DFC.,=the ground plane dose conversion factor for radionuclide i;(units=mr em/hr per pCi/m~)e'F=the shielding factor (dlmensionless);

I A shielding factor of 0.7 is discussed in Table E-15 of Regulatory Cuide 1.109 Revision 1.A tabulation of DFGi values is presented in Table E-6 of Regulatory Guide 1.109 Revision l.A.3 Grass-Cow or Coat-Milk Pathwa-Alt f Ri-K'QF U F (DFL)e Y I+B.(1-e.(I-f f)~p s, t r(tm'Y E i+Bi (lm th)e where: M R l=dose factor for the cow milk or goat milk pathway, for each""'"'identified radionuctide

for the organ of interest, (units mrem/yr per uCi/sec per m)..

0 l 5~"~4~-I~e'u e't@I E K'a constant of unit conversion:

10 pCi/uCi 6.QF=The cow's or goat's feed consumption rate, (units=Kg/day-wet weight)Uhe receptor's milk consumption rate'or-age group a, (units=liters/yr);

Y the agricultural product<vity by unit area of pasture feed grass, (units=kg/m~,);.Y I the agricultural productivity by unit area of stored feed, (units=kg/m~);the stable element transfer coefficients, (units=pCi/liter per pCi/day);r=fraction of deposited activity retained on cow's feed grass: (DFL)=the organ ingestion dose factor for radlonuclide i for the receptor in age group a, (units=mrem/pCi);

'he radiological decay-constant for.radionuclide-

-i, (units=sec);the decay constant for removal of activity on leaf and plant.surfaces by weathering

~7 5.73-x 10 sec.,(corresponding to a 10 day.half-life);,.

~rtl~q n a tf the transport time from feed to cow or goat to milk, to receptor, (units=sec);th=the transport time from harvest, to cow or goat, to consumption, (units=sec);tb=period of time that soil is exposed.to gaseous effluents, (units=sec);8.concentration factor for uptake of radionuclide i from the soil by the edible parts of crops, (units=pCi/Kg (wet weight)per pCi/Kg (dry soil);P=effective surface density for soil, (units=Kg (dry soil)/m~);

f=fraction of the year that the cow or goat is on pasture*;f=" fraction of the cow feed that is pasture grass while the cow is on pasture;t=period of pasture grass and crop exposure during the growing season, (units"-sec);<<Milk cattle and goats are considered to be fed from two potential sources, pasture grass and stored feeds.Following the development in Regulatory Cuide 1;109 Revision 1, the value of f was considered unity in lieu of s ,p'site-specifi.information.

The value of f was.0.667.based upon, an 8-month grazing period.Table A-1 contains the appropriate values and their source in Regulatory Cuide 1.109 Revision 1.The concentration of>>tritium in milk is based on the airborne concentration rather than the deposition.

Therefore, the Ri is based on X/Q: R=KsKts'F Q U (DFL)0 75(0 5/H)

'l 4 Aw vv ml'ls k%k

}cher.e: M RT dose factor for the cow or goat milk pathway for tritium for the organ of interest, (units=mrem/yr per uCi/m');K'"=a constant of unit conversion; l0~gm/kg;H=absolute humidity of the atmosphere, (units"-gm/m~);0.75=the fraction of total feed that is water;0-5=the ratio of the specific activity of the feed grass water to the atmospheric water.,.OC Other values are given above.A value of H of 8 grams/meter3, was used in lieu of site-specific information.

A.O Crass-Cow-Meat Pathwa-Xitf Ri K'~F ap" Y XE i+B.(1m (l-f f)r(lm e tb+8 (l e iv)Kith e s E i R~=l dose factor for the meat ingestion pathway for radlonuclide i for.-any organ:ofinterest, (units."-mrem/yr per uCi/sec per m):-2.F<=the stable element transfer coefficients, (units=days/Kg):

=S>>I\1 1 l f,~4 l~g)AVIPA I I Q f 4 t g}e V~~@Ok>t ap the receptor's meat consumption rate for age group a.(units=kg/year;t=the transport time from slaughter to consumption, (units=,sec);the, transport time-.from.,harvest..

to, animal" consumpt>on.

-(units=sec): t=period of pasture grass and crop exposure during the growing season, (units=sec)""'"'"All'other"<terms-remain'the.same as defined for the milk pathway.Table A-2 contains the values which were used in calculating R..i The concentration of tritium in meat is based on airborne concentration rather than deposition.

Therefore, the Ri is based on X/Q.R T=K'K"'FfQ U (DFLi)(0.75(0.5/H)

J where: dose factor for the meat ingestion pathway for tritium for any organ of interest.(units=mrem/yr per uCl/m~).,.All terms are defined above.A.S V etation Pathwa The integrated concentration in vegetation consumed by man follows the expression developed for.milk.Man is considered to consume two types of vegetation (fresh and stored)that differ only in the time period between harvest and consumption, therefore:

(I f i h.%'4g Ale 4.

R.,"-K'(DFL)XitL U f e a L t lm+Y I E l PX1-X.tb where: S'ith Ua fge t r(l-e)Y A hi-A t B (le ib), R,=dose factor.for vegetable pathway for radionucllde i for the organ of interest, (units=mrem/yr per uCi/sec per m);K'a constant of unit conversion; l0 pCi/uCi: 6 L Ua=the consumption rate of fresh leafy vegetation by the recepCor in age group a, (units=kg/yr);fL=the fraction of the annual intake of fresh leafy vegetation grown locally;fg the fraction o f the annual intake of sto red vegetation grown locally~..tL...=., Che.,average

.time between, harvest--of leafy vegetation and its consumption,.(units=sec);the average time between harvest of stored vegetation and its consumption, (units=sec);Y-the vegetation area density, (units=kg/m~);t=period of leafy vegetable exposure during growing season (units=sec);

~7I All other factors are defined above.Table A-3 presents the appropriate parameter values and their source in Regulatory Guide 1.109 Revision 1.In lieu of site-specific data, values for fL.and;f of, 1.0'nd'.76,'respectively, were used in the calculation.

These values were obtained from Table E-15 of Regulatory Guide 1.109 Revision 1.The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition.

Therefore, the R.is based'on I.X/Q: R=K'K" T U f+U f a L ag (DFL)0.75(0.5/H) where: V RT dose factor for the vegetable pathway for tritium for any organ of interest, (units=mrem/yr per uCI/m~).Atl other terms are defined in preceeding sections.

Jl R~~i'o 4~1 Ik 4[5 I TABLE A-1 Parameters for Cow and Goat Milk Pathways Parameter QF (kg/day)Y (kg/m~)tf (seconds)Value 50 (cow)6 (goat)0.7 1.73 x 10 (2 days)1.0 (radioiodines) 0.2 (particulates)

  • Reference (R., Guide 1.109 Rev.1)Table E-3 Table E-3 Table E-15 Table E-15 Table E-15 Table E-15 (DFL)(mrem/pCi)

F (pCl/day per pCi/liter) t (seconds)Y (kg/m~)Y (kg/m~)t(seconds).

U" (liters/yr) t (seconds)Each radionuclide Each stable element 0.73 x 10 (15 yr)2.0 0.7 7.78 x 10 (90 days)330 infant 330 child 000 teen 310 adult 2.59 x 106 (pasture)6 5.'18 x 10 (stored feed)Tables E-11 to E-14 Table E-1 (cow)Table E-2 (goat)Table E-15 Table E-15 Table E-15 Table E-15 Table'-5 Table E-5 Table E-5 Table E-5 Table E-15 Bl(pCl/Kg (wet weight)Each-stable element per pCi/Kg (dry soil))Table E-I P (Kg dry soil/m~)200 Table E-15 II g+~a~A'.4 it@'P C PV TABLE A-2 a Parameters for the Meat.Pathway Parameter Ff (pCi/Kg per pCi/day)U (Kg/yr)ap Value',1.0 (radioiodines) 0.2 (particulates)

Each stable element 0 infant 01 child.65 teen 110 adult Reference (R.Cuide 1.109 Rev.1)Table E-15 Table E-15 Table E-1 Table E-5 Table E-5 Table E-5 Table E-5, a (DFL)(mrem/pCi)

Y (kg/m~)Y (kg/mi)tb (seconds)t (seconds).t (seconds)t.-(seconds) 1 QF (kg/day)B., (pCi/Kg (wet weight per pCi/Kg (dry soil))P (Kg (dry=soil)/m~)Each radionuclide 0.7 2.0 1.73 7.78 2.59 5.18 50 x 10 x 10 x 10 x 106 6 x 10 (15 yr)(20 days)(90 days)(pasture)(stored feed)200 Each stable element Tables E-11 to E-14 Table E-15 Table E-'lS Table E-15 Table E-15 Table E-15 Table E-15 Table E-3 Table E-1 Table E-15-99-I 4)e"'C/'i TABLE A-3 Parameters for the Vegetable Pathway Parameter r'(dimensionless)(DFL)(mrem/Ci)U (kg/yr)-infant-child*-teen-adult U (kg/yr)-infant S~-child-teen-adult t<.(seconds)t(seconds)

Y (kg/m~)t (seconds)'"t"'(seconds)

~P(Kg(dry soil)/m~)81~(pCl/Kg (wet weight)per pCi/kg (dry soll))Value 1.0 (radioiodines) 0.2 (particulates)

Each radionuclide 0 26 A%2 64 0 520 630'20 8.6 x 10 (1 day)5.18 x 10 (60 days).2.0 5.18 x 10 (60 days).."Oe73 x 10.(15 yr)8 2ao Each stable element Reference (R.Guide 1.109 Rev.1)Table E-1 Table E-1 Tables E-11 to E-10 Table E-5 Table E-5 Table E-5 Table E-5 Table E-5 Table E-5 Table E-5 Table E-5 Table E-15 Table E-15 Table E-15 Table E-15 Table E-15 Table E-15 Table E-1;.-.100-I V~" PE P 4 pi h APPENKNX-B";-'NGRAMS OP LNUlD AND GASEOUS RNDNASTE TREATMENT SYSTEMS.10.1 PO'I 4~r td p eP 4 ygCg~,<c y q0+>~>a I+'g if yl\'I (c, 4%

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NOTES TO FIGURE B 1 (a)NHP1 Stack (height is 350')(b)NMP2 Stack (height is 430')(c)JAFNPP Stack (height is 385')(d)NMPl Radioactive Liquid Discharge (Lake Ontario, bottom)(e)NHP2 Radioactive Liquid Discharge (Lake Ontario, bottom)(f)JAFNPP Radioactive Liquid Discharge (Lake Ontario, bottom)(g)Site Boundary~(h)Lake Ontario Shoreline (i)Meteorological Tower (j)Training Center (k)Energy Information Center Additional Information:

-NMP2 Reactor Building Vent is located 187 feet above ground level-.JAFNPP Reactor and Turbine Building Vents are located 173 feet above ground level-JAFNPP Radwaste Building Vent is 112 feet above ground level-The Energy Information Center and adjoining picnic area are UNRESTRICTED

.'-4.AREAS"within;,the, SITE~BOUNDARY.that are accessible to HEHBERS OF THE PUBLIC-Lake Road, a private road, is an UNRESTRICTED AREA within the SITE BOUNDARY accessible to MEMBERS OF THE PUBLIC 5-6 I~I I)>>$I'~ll h'.AP>>h)">>" h>>P h~I I I,>>, I h II III PRINTER GRT PARTICULATE 00 INPU j/DILUTION STATION IODINE DETEGTORS (3)INSTRUMENTATION CABINET MAIN FRAME FIGURE B 8-111-Simplified View of Hodel 400 Stack Honitor NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT-UNIT t OFFSITE DOSE CALC.MANUAL t e I IV I f" 4~I gr., t a

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APPENDlX.-C Df SPERSt ON CALCULATION TAB t.ES @~i'O'I~k lfgj fg'I lp'J L f ge l 4i IC TABLE C-1 D/q TABLE (ANHVAL METEOROLOGICAL DATA)NNP UN I T+I S I AC K CORREC'IKD FOR OPEN TERRAIN RECIRCULATION tooeeryoooooottooo ~to RELATIVE DKPDST jlDH PER UNlT DIRECT IDH FRON SITE.So.I.oo 1.50 e.oo.8>1.040E-0$3.2608-09 I.RC<E-I9 6.78)E-IO SSl)1.806E-OB'3.78TE-09 I.<CRE-O'9 T.STIE-IO SD 7.14 I E-09 R.4038-09 9.852E-I~5.413K-I I LJSD 2.169K-09 V.C32E" I I 3.843K-I I I.835E-I I , w R.<56E-09 8.59)f lo 3.CSIE-IO R.OBSE-IO DND 5.076E-09 1.74<E-09 7.<3bK"I~4.ROSE-IO NM 1.666E-OS<.947E-09 1.9CIK-IO 1.057E-09 MNM 1.582E-OS 1.66RE-O9 1.814K-II O.CC9E 10 H 1.5IVE-OS 4.701E-09 1.883K-09 I.OR<K-09 NHE 6.572K-09 R.)30E-09 8.$04E-IO 1.96<E-IO NE 8.968K-09 R.CSIE-O9 I.IT&K-I9 5.856K 10 EWE 3.003E-OS 8.677E-09 3.400E-09 I.BISE-09 E 4.315E-OS I.RI3E-IS 4.C94E 09 R.<BIE-09 ESE 2.837E-OS 7.97)K-09 3.878K-~9 1.68IE-OO SE R.122K-OS C.R5RE-O'9 R.43OE-~I).895K-09 SSE 1.073E-OS 3.302E-09 I.RTSE I9 C.83RE-IO AREA INt~-2)AT FIXE DISTANCES IH NILES 2.50 3.00 4.2R9K-IO 2.$9)E-IO 4.9RIE-IO 3.367E-IO 3.459E-IO 2.390E-IO I.IS<E-IO 8.260E-II 1.3<9E-IO 9.<ROE-II 8.71)K-IO 1.890E-IO 6.605E" Io 4.51<E-IO 6.003E-IO 4.086E-IO 6.146E-IO 4.<RVE-IO 3.172E-IO 2.198E-IO 3.681K-lo 8.527E-IO I.IRBE-09 7.671K-IO 1.53'IE-09 1.037E-09 9'982K-IO 6.755E-IO 8.035E-IO 5.169E-IO<.R5IE lo R.90IE-IO 4.00 4.50 I 594E-Io 1.25IE-IO 1.856E-IO).45<E-)0 1.328E-IO 1.042K-IO 4.638E-II 3.645E-II S.ROBE-II<.)55E-II 1.059E-IO 8.3ISE-II R.<TTE-IO 1.936E-IO 2.236E-IO 1.747K-lo 2.145E-IO 1.91<E-IO 1.22<F.-IO '9.592E-I'I 1.389E-IO 1.084E-IO 1.191E-IO 3.87)E-IO 5.630E lo 4.387E-IO 3.667E-IO R.S5TE-IO 2.9'92E Io 8.338E-IO 1.596E-IO 1.25)E-IO 3.50 2.I 0 I E-10 R.<<TE-I 0 1.747E-IO 6.07<E-I I 6.927K-II 1.389E-IO 3.27<E-IO 2.957E-IO 3.822E-)0 1.609E-IO 1.835E-)0 5.519E-10 7.172E-I 0 4.867E-10 3.957E-I0 R.105K" 10 D POINTS SY DOLINWIND SECTORS 5.00 I.OOTE-IO I.I CSE-I I 8.366K-II 8.932E-)l 3.339K-l I 6.682E-II 1.55RE-IO I.<0 1f-l 0 1.537E-I~7.696E-II S.CTSE-I'I R.619E-10 3.51 OE-I 0 R.ROTE-I I I.875E-I I I.OOCE Io 5.50 8.878E-II 9.5S6E-II C.SSIE-II e.<oef-ll 2.731K-I I S.469E-)l I.R69E-IO 1.1<BE-10 I.R59E-I I 6.29<E-I I 7.083E-II R.I<IE-10 R.SCSE-IO 1.869E-I~1.536E-IO 8.861E-I I I~~0~0~~IOOI~01~~il~lIt DIRK CT)OH FROtl SITE 8 SSH Sl)ll SD D DHIJ Nl)NNll N NNE NE KNE f ESE Sf SSE 6.006.9)TE-II S.OOIE"II 5.704E-II 8.000E-II 2.27<F.-II 1.5<VE-I I 1.056E-'10 9.565E-II I.0<BE-I I 5.23)E-II 5.879E-II I.78 IK-I I R.385 E-10 1.555E-I I I.RBOE-10 6.903E-II 6.50 5.999E-II 6.93<E-II 4.963E-II I.749f"'I I 1.988E-II 3.973E-II 9.127E-II 8.256E-II 9.092E-I)<.SSSE-II 5.083E-II 1.535E-IO 8.050E-IO 1.336E"10 I.I OSE" 10 5.979E-II 7.00 5.RISE-II C.I 8 I E" I I 4.379K-II I.514E-I I 1.754E-I)3.505E-I)B.I52E-I I 7.886E-)I S.IR3E-I I 4~~Ibf II 4.<seE-)i 1.35<E-I~I.BOSE-I~I.179K-)O 9.75 I E-I I 5.e79E-I)7.50<.VISE-I I S.119E-I I 3.896E"II 1.373K-II 1.56 IE-I I 3.)ISE-II 7.)63E-I I C.<83E" I I 7.139E-I I 3.573E-II 3.985E-)l I.ROSE-IO 1.60BE-IO I.0<BE"10 8.677K-II<.TOIE-I I DISTANCES 8.00 4.832E-II<.SBCE-II 3.<92E-II I.23)E-I I 1.39SE" I I R.794E-II 6.<I VE-I I 5.81OE-I I 6.39SE-II 3.80 IE-I I 3.568E-II 1.079K-IO I.<<Of-l 0 9.390E-II 7.776K-II 4.R)6E-I I)N tl)LES 8.50 3.BRIE-II 1.109E-I I 3.149E-I I I.I I OE-I I I.26 I K-I I R.5 I'9E-I I S.VSSE-II 5.240E-)l 5.770E-II R.BS6E-II 3.el<E-11 9.788E-II 1.298E-IO 8.16<E-I I 7.01<E-II 3.80&E-II 9.00 3.<TOE-I I<.OOIE-II R.BS&E-II I.OOTE"11 I.I<<E" 11 2.28<E-I I 5.2<5E-II 1.753K-ll 5.834E-II 2.616E-I I e.912K-I I 8.8 I BE-I I I.176E-I I 7.678E"II 6.3&RE-)l 3.455E-)1 9.50 3.167K-ll 3.650E"II 2.604K-I I 9.183K-IR 1.0<RE-I I R.OSRE-II 4.779E II 4.333E-II 1.77 I E-I I 2.38<E-II e.&52E-II 8.03<E-I I 1.072E-10 6.989E-II 5.799E-II 3.153E-I I 10.00 2.904K-ll 3.31<E" I I 2.384E-II 8.412E-IR 9.5<6E-I2 1.906E-II 4.375E-II 3.968E-II 4.369E"II 8.)822-11 R.125E-I I 7.352E-II 9.805E-II 6.395E-II 5.31)E-II 2.890E-II IS.00 1.533E-)l 1.754K-II I.2<RE-I I 4.393E-IR 4.9&SE-IR 9.907E-)2 2.866E-II R.OCCE-II 8.8'16E-II 1.130E II I.R45E-)l 3.799E 11 S.054K-I I 3.30 I E-I I 8.765E-II 1.522E-II eo.oo 9.66<E-I R 1.099E-II 7.742E-IR e.V<6E-le 3.097E"le 6.168K-le I.105K" I I).286K"ll I.4 I BE-I I T.OIRE IR 7.663E-IR 8.35')E-II 3.119E-I I 8.040E-II I.TRRK-II 9.569E-IR-114-0'$I qt k~'C I~1 tgz t'-" JQ', TABLE C-2 D/g TABLE (GRAZING SEASON METEOROLOGICAL DATA)HHP UNIT<4 I STACK CORRECTED FOR OPEH TERRAIN RECIRCUL RELAT)VE~tttt1~10~00~I~10ttrO~AT)ON DEPO817)ON PER UN)T AREA)Nil-Rf AT FIXED POINTS BY DOUIIUIHD SECTORS 0~~00~~11I~t~~1~OtttO D)RECT)ON FRON 81'TE 8 SSll SU USU UNU Nil Hkli N NNE NE EHK E ESE SE SSE.50'1.00 1.079E-OS 3.3e<E-09).030K-OS 3.R<RE-O'9 5.999E-09 1.97<K-ot 1.658E-09 5;t39K-10 I.sVRE-09 6.736E-IO<.629E-09 1.579E-~9).586E-OS<.VBRE-~'9 1.556E-OB<.658E-09 1.63)K-OS 5.076E-09 6.522E-09 2.113E-49 7.276E-09 R.Reef-ot 2.9SSE-OS 8.799K-O'9 3.971E-OB I.1<3E-08 2.30SE-OS C.595E-09 1.880E-OB 5.557E-49 1.120E-OB 3.3&IE"09 1.54 I.RTOE-09 I.RTOE-~9 S.47<E-I 4 R.SRCE-I~R.918E-I~C.CTTE-I~1.90&E"09 I.8 I SE-09 R.03)f-ot S.BORE-I~9.I<IK-14 3.<89E-09<<.CIE-at 8,553E-at R.l<3E-09 I.RTTE-49 2.00 6.7<BE-IO C.B<9E 10<<.C<E-IO I.<3RE-I~I.C6RE-I 0 3.7&OE-I4).032E-09 9.78SE-IO I.105E-09<.899E-14 5.028E-14 I.BBOK-09 8.375K-ot 1.3538-09 I.138E-09 C.7<3E-I~DISTANCES 1N I)ILES R.50 3.00 3.50<.)82K-IO R.8<BE-IO 2.06<E-IO<.RSTE-Io 2.93&E-IO R.)36E-)O 2.839E-IO 1.96<E-)0 I.<36E-IO 9.253E-)l 6.<63E-II<.757E-II I.OVSE-'Io 7.5<BE-I'I 5.5&OE-II 2.<ISE-IO 1.683K-IO 1.236K-IO 6.<68E 10<<.30E"lo 3.217K-IO 6.055E-IO<.129E-Io 2.993E"10 C.953E-IO<.776E-10 3.<TVE-IO 3.IRTE-!0 R.l&VE-IO 1.585E-IO 3.18SE-IO 2.)9<E-IO 1.598E-)0 I.176E-09 8.036E-)0 5.829E-IO I.<73E-09 I.OOIE-09 7.236E Io$.361K-IO 5.672E-IO<.09<K-IO 7.0<5E-IO<.789E-IO 3.<6<E-IO<.16)E-Io 2.82<K-IO 2.0<RE-IO<.00 1.565E-IO).622E-IO 1.093K-I~3.63SE-II<.2<9E-II 9.<23E-II 2.<37E-10 R.265E-IO e.&39E-lo l.eo&f-lo I.Rlef I 0<<.IRE-)4 5.<63E Io 3.089E Io R.&I tf-10 1.5<SE-)0<.50 I.RRTE-IO I.eVef-lo 8.580E-II 2.859E-II 3.3<OE-II 7.39SE-II 1.906E-IO I.77ef-I o 2.067E-IO 9.<5)K" I I 9.<TBE-II 3.<<SE-IO<.263E-IO e.<I of-I o 2.0<BE-IO I.RIOE-IO 5.00 9.876E-II 1.023E-IO 6.898E-II 8.300E-)l R.&86K-II 5.9<5E-II 1.5RSE-IO 1.<eeE-IO 1.659E-14 7.585E II 7.59IE-I I 2.76<E"lo 3.<I<E IO I.930E-10 I.6<<E-10 t.TRSE-II 5.50 S.)ROE-II 8.<OIE-II 5.65SE-II 1.88&E-II R.ROOE-II<.867E-II I.RSIE-I0 I.I&5E-10 1.360E-IO 6.205E-II 6.1')9E-Il 2.26)K-I 0 8.798E-IO 1.579K-)4 1.3<TE-IO 7.'993E-II DIRECT)OH FROH SITK 8 SSll SII I)SU U UHU NU NHll.H Hkf NE ENE E ESK SE SSE 6.00 6.796E-)l 7.0)SE-II<.7)RE-I I I.57 I E-I I 1.830E-II<.0<9E-II I.0<IE" I 0 9.71<E-I I 1.133K 10 5.158E-II 5.I<6E-I I 1.882E"10 8.323E-)0 1.31<E-I 0 I.IR<E-10 6.68<K-II 6.50 5.88<E II 6.090E-II<.IOSE-I I 1.375E-II 1.603E"II 3.536E-II 9.007E-II 8.397K-II 9.828K-II<<.9)K-11<<.CRE-II 1.627E-IO R.OOIE-IO I.13)E-I~9.702E-II 5.77<K-II 7.0~5.197E-II 5.377K-II 3.CR3E-I I I.RI<E-'I I I.<I<E II 3.)ROE-II 7.9<TE-II 7.<IIE-II 8.673E-II 3.tCRE-II 3.935E-II I.@35E-I4 I.TCSE-I~'t.tSRK-II 8.56<E-II S.ottf-ll 7.50<.Ceif-Ii<.78TE-I I 3.22<K)1 1.080E-II 1.858E-II 8.77&E-II 7.069E-II C.595E-II 7.717E-II 3.52<E-II 3.<99E-II I.eTTE-io I.STOE-14 8.879K-II 7.622E-II<.5<OE-II D)STANCES 8.00<.153E If<.29<E-II 8.890E-I)9.682K-le I.IRTE"II'.<BVE-)l 6.33<E"II 5.91)E-II C.t)TK-II 3.157K"II 3.133E-I I I.I<<E-I 0 1.<OTE-10 7.95SE-I)C.833E-II<.473E-ll IH H)LES 8.50 3.750E-II 3.876E-II 8.60TE-)l S.73<K-IR I.0 I TK-I I 2.2<3E-II 5.71)E-fl 5.332K-ll 6.239E-I)R.B<6E-)l 2.823K-ll 1.03IE-10 I.R&SE-IO 7.ITRE-I I 6.I&5E-I I 3.677K-ll 9.00 3.<06f-ll 3.518E-I I 8.366E-II T.tesf-ie 9.220E-IR 2.03<K-II 5.)TSE-II<.837E-II 5.659E"II 2.580K-II e.ssBE-)l 9.350E-II I.150K-I 0 6.542E-II 5.593K-ll 3.338K-ll 9.50 3.149E-1 I 3.210E-II 2.157E II 7.2RTE-)8 8.<05E-IR 1.85<E-II<.7)9K-II<<.IIE"II 5.164K-ll 2.35)E-II R.370E-II B.seof-ll 1.0<VE-IO 5.985K-II 5.)0 I E-I I 3.0<7K-II 10.00 2.85)E-)l 8.9<3E-II 1.976E-)f 6.62)E-IR 7.698E-)8 I.698E-I I<.320E-ll<.0<OE-II<.726E-If R.152E"ll 8.13)E-II 7.799E-II 9.58TE-II 5.<2<E-II<.673E-)1 R.793E"II)5.00 1.508E-II 1.5<9E-)l 1.03<K-II 3.<65E-IR<.~IRK-)2 8.838E-I 2 R.2<IE-11 R.IOSE-f I R.<65f-ll I.I)6E-I)1.097E-II<.0<2E-II<.957E-ll 2.808K-ll e.<<ef-l I I.<73E-I I 20.00 9.52)f-I 2 9.7<IE-12 6.<67E-12 2.)TOE IR R.so<f-le 5.509K-IR 1.392K-I)1.3)5E-I I 1.538E-I I 6.930E-IR 6.766E-IR 2.508E-II 3.069K-lf 1.7<OE-II 1.585E-II t.ecSE-IR-115-F~IF f<<'t<<'FI It C<<<<I TABLE C-3 x/q (hHNUAL HETEOROLOGICM. DATA)NNP UIIIT O'I STACK ND DECAY, UNDEPLETEQ CDRREC1EO f QR QPEII 1fRRhlN RECIRCULATION 4 hlttIUAL AVERACK Ctlt/0 IBKC/NETER CUSEOl.500 I.ooo I.50'.I07E 07'9.910K-DS 4.R64K-OS 4.880K-OT I.209E-OT 5.I33E-OS 3.851K-or 9.486K-os 4.o46f-os R.o<<f-or 4.984K-os e.092E-os 2.802K-or 6.13IE-DS R.TSTK-OS 4.206E"Dl I.028E-OY 4.3RCE-DS I.I I tf-06 2.695K-OY 1.DBTE-OT l.062E-DC R.555K-OT I.ORYE"01 I.I I3E-06 2.705K-OT I.IOIE-07 6.664E-DT I.6llf-or 6.5COE-OS 7.774E-DY I.855E-OY 7.430K-OB I.390E-DC 3.316E-~7 l.3CTK-DT l.550E-06 3.789K-O7 I.54lf-~7 8.385E-OT 2.044K-OT 8.386K-OS 5:921E-or I.459K-or 6.lace-oa 3.641E-07 S.'l98f-08 3.7CRK-OS BEC10R 8 SSM BM MSM M MNM NM IttIM II ttttE NE Etlf E ESE Sf 5SE e.ooo 2.558E-OS 3.052K-OS R.463E-OS I.R73E-OS I.678E-OS 2.6lrf-os C.292E-OS 5.89SE-OB C.422E-OB 3.859E-OS 4.275E-OS 7.817E-08 8.87DE-DS 4.86RE 08 3.Cl 9f-08 e.eoof-oa I.BDRE-OB 2.I32E-08 I.766E-OS 9.289K-ot l.e<<f-oo l.s'YDK-DB 4.340K-OS 4.04IE-OB 4.459K-DB R.7IIE-OS 2.939K-OB 5.38IE-OB 6.036K-OB 3.323K-OS R.559K-DB I.593E-OS l.386E-DB I.626K-DB l.317E-DB 7.436E-09 9.590K-09 1.45fE-OS 3.292E-DB 3.052K-OB 3.403E"08 2.092E-DB R.RRBE-OB 4.036E-OS 4.501E" 08 2.486K-os I.936K-OB I.225E-OS DISTANCE IN NILES e.5oo 3.ooo 3.500 I.I24E-OB I.309E-OB I.IRBE-OS 6.265K-09 B.DOBE-09 I.I92E-OB 2.643K-OO 2.445E-OB 2.747E-DB l.706K-OB I.Y92E-OB 3.ROSE"08 3.564E-OS'I.961K-OS I.544E-OB 9.926E-09 4.000'9.449K 09 I'92E-08 9.545E-09 5 444E-09 6.908E-09 I~OOBK-OS 2.203E-OS 2.03'IE-08 e.3olE-oa I.44IE-OS I.498E-OB R.644E-DB 2.930E"08 I.CITE-OS I.R75E-08 8.333K-ot 4.500 5.'000 S.I44E-09 T.ISBE-D'9 9.34BE-O9 S.I66E-09 8.260K-ot 7.276K-ot 4.829E-D9 4.349K"09 6.09IE-09 5.451E-09 B.1I9E"09 1.611E-09 I.885E-DB l.644K-OB I.743K-OB I.SRRE"08 I.9 7TE-08 I.732E-08 I.247E-OS I.099E-OB I.RBYE-oa I.leaf-os R.e42f-oa I.942K-os R.477E-OB R.140K-OS I.366K"08 I.I79E-DS I.OSIE-OS'9.365f-ot Y.I73E-09 6.300E-09 5.500 C.3885-09 7.244E-09 6.4t Yf-09 3.96 IE-09 4.94SE-09 6.85IE-09 I.457K-08 I.35 IE-08 I.540E-OB 9.8ICE-09 l.004E-OS I.1 I OE-08 I.SSOE-OS I.035K"08 8.24 I E-09 5.6 I TE" 09 hlttlUAL AVERACK SEAR INC BSM CM UOM It MtlM IIM tMIM tl tttlf NE Ettf E EBE SE.SOE Cttl/0 IBEC/METER CUBKQl 6.000 6.500 7~Oo~5.765K-09 5.27TK-O'9 4.89'TE-Ot 6.503E-09 5.'923E-09 5.413K-ot 5.863E-09 5.363K-09 4.975K-ot 3.640E-09 3.384E-ot 3.I84K-09 4.5R9E-09 4.l'trf-09 3.939K-09 6.IBIE-09 5.653E-~9 5.242K-O'9 I.306E-DB I.189E-OS I.DOTE-OS I.RI3K-OS I.I05E-OB I.ORRE-DS l.386E-DS I.265K-.OS I.ITIK-08 8.86tf-09 S.IRRE-09 7.542K-09 9.039E-09 S.R63E-09 T.CC4K-09 I.525K-OB l.38IE-DB I.RTDK OS 1.673E-OS I.5IRE-OS l.38SK-OS 9 l99f-09 8.308E-Ot T.CISE-~9 7.3442-09 6.644K-ot C.'IDRK Ot 5.065E-09 4.633E"09 4.Rtlf-ot 7.500 4.568E-D9 5.080E-09 4.633K-09 3.005K-O'9 3.708K-D9 4.88IE-09 I.OIBE-DS 9.496E-O'9 I.089K-DS 1.0'33E-0'9 7.I4IE-09 l.l74E-OB l.28IE-OS 7.023E-09 S.C33f-o'9 4.004E-09 4.275K-09 4.735K-09 4.330E"09 2.842K-ot 3.500K-O'9 4.562E-D9 9.417K-09 8.859E-09 I.OITE-OB 6.'582K-09 6.68IK-09 l.090K-OS l.lsrf-oa 6.505E-09 5.223K-09 3.744E-09 4.0I4E-09 4.429E-09 4.060E-09 2.695K"09 3.3I2K-09 4.277E-09 8.858E-09 S.R94f-ot 9.526E-09 6.I 79E-09 6.273E-09 I.DICE-08 I.ID5E-08 6.050E-09 4.863K-09 3.5I3E-09 Q!STANCE Itl tllLES S.DDD 8.500 9.00D 3.780E-09 4.I55E"09 3.BISE-09 2.560K-09 3.I4IE-09 4.022E-09 8.307K-09 7.7'tOE-09 8.953E-09 5.BISE-09 5.908K-09 9.5075-0'I I.O'33E"08 5.648E-09 4.544E-09 3.306E-09 9.500 3.570E 09 3.9IOE"09 3 CDOE-09 2.436E"09 2.985E-09'3.792K-09 Y.BI3E"09 7.338E 0'9 8.437E Dt 5.493E-09 5.580E-09 8.924E-09 9.CYBE-09 5.R90E"09 4.P59K 09 3.I I 9E-09 I0.000 I5.000 3.380E-09 2.269K-O'9 3.C90E-09 R.414E-09 3.403K-09 2.254K 09 2.323E-09 I.C35E 09 2.842E-09 I.983E 09 3.585E-09 2.375E-09 7.368E-D'9 4.SORE 09 6.93IK"09 4.573E-09 7.972E-09 5.210E-09 S.I98E-09 3.474E"09 5.2$4f-ot 3.5&6E-09 8.40RE-09 5.4Rtf-09 9.099E-09 5.SIDE"09 4.970E"09 3.I59E-09 4.004E-09 R.S60E-09 R.95IE-09 I.OCOK 09 eo.ooo l.689E-09 l.764K-09 1.659K-09 l.e47E-09 I.506E-09 1.748E-09 3.498E-09 3.362E-09 3.876E-09 2.570E-09 2.666E-09 3.950E-09 4.I 91E-09 R.ersf-ot I.852K-09 I 4h7F 44 ~~K xl%t I 4~~~a<<g I~~4-lk E JJ p II 'j.'ABLE C" 3 (ANNUAL HETEIJROLOGICAL DATA)NNP UIIIT Dl STACK NO DECAYS UNDKPLETED CORRECIED FOR OPEII'IERRAIN IIECIRCULATTON AIIHUAL AVERACK SECTOR 8 SSM SM IJSM M MNM JJM IRIIJ tl ttttE ttE Etta E ESE SE SBF.Ctll/0 I SEC/NETER CUBED I.500 I-tt 00 I~500 4.I OTE-07'S.'914E-08 4.264K-OS 4.OBOE-DT I.R09E-DT 5.133E-OB 3.851K'-OT 9.4S6E-OS 4.046E-DS 2.014K-DT 4.9s4a-os e.otea-os 2.802E-OF C.73IE-OS R.TSTE-OS 4.20&E-07 1.028K"07 4.3RLE-OS I.119E-06 R.69SE-OF I.DBTE"07 1.062K-O&2.555E-OF 1.027K-OT 1.113E-06 2.705E-OT I.IDIE-OT 6.664E-DT 1.61IE-DT IL.5COE-OB 7,774E-OT I.SSSE-OT 7.430E 08 1.394K~06 3.376K-DT I.'3CTE-07 1.55OE-DC 3.78$E-OT 1.54IE-DT 8.385K-OT 2.044E-07 8.38CE-DS 5.921E-OT 1.459E-DT 6.ISRE-08 3.647E-ol$.798K-DB 3.1C2E-DB e.ooo R.558E"08 3.052E-OS 2.463E"08 I.R73K-OS 1.678E-OS R.LITE-OS C.R92E-OB 5.898E-DS 6.422E-OB 3.859E-OB 4.275K-OS 7.8TTE-08 S.STDK-DB 4.862K-OS 3.67$E"08 e.e64E-oe 1.842E-OB P..I32E-DB 1.76&E-OS 9.289K"49 I.Rl IE" OO I.STDE-OS 4.340E-DB 4.041E-OS 4.459E-DB 2.71IE-OB 2.939E-DB 5.3SIK-OS 6.036K-DB 3.323E-OS 2.559K-OS 1.593E-OB 1.386K"48 I.L26E-DB t.311K-os 7.436E-09 9.590E-09 1.45&E-OB 3.292E-OB 3.452E-DB 3.403E-DS 2.092E-OB e.RRSE-oe 4.036E-OB 4.SOTE-DS 2.486K-os 1.936E-DB 1.225E-DB Dl slhttCK lH tl1 LES R.540 3.040 3.540 1.124K-OS I 309K-os t.IRDE-OS L.P&SE-49 B.oosa-ot I 192K-08 2.643E-DS 2.445K-DS P..741K-08 1.706K-OB 1.192K-OB 3.245E-DS 3.564E 00 1.96JE-DS I.s44a-os 9.926K-09 4.000 9.44'JK-49 t.o'JRE-08 9.54SE-Dt 5.444E-OS 6.948K-OS I.DOBE-DB 2.203E-OB 2.031E-08 2.341K-OS 1.441K-oe 1.498E-OS 2.&44E-48 2.93OE-OS 1.611E-DS I.RTSE-08 8.333E-DS 5.'040 4.500 8.144K-09 7.158K-09 9.348K-09 S.I&6E-09 S.e&oa-ot 7.216K-ot 4.829E-09 4.349E-09 6.09IE"09 5.457E-09 8.119E-09 7.671E-09 I.BSSE-OB 1.644E-OS 1.743E"08 1.522K-DB 1.911E-DS 1.732K-DB 1.247E-OS 1.09'lE-08 I.RSTE-OS I.Ieea-08 2.242K-OB 1.942K-OS 2.477K-DS 2.14oa-os 1.366E-DB I.179E-0$I.OBIK-OB 9.365E-09 7.173E-O'I 6.300E-09 5.500 6.388E-09 7.244E-09 6.4tTE-09 3.9&IE-09 4.948E-09 6.851K-OS 1.457E-OB 1.35IE-DB 1.540E-OB 9.816E"09 1.004K-OB I.TIDE-OS I.BSOE-DS'1.435E-DB 8.24IE-DS 5.611E"O'9 AtttlUAL AVEIJACK Cttl/0 I SEC/tIE IER CUBEDI SEAR I JIC 6.400 6.500 1.000 7.5DO DISTAIICK IN tIILES.8.000$.500 94DO 9.500 14.000 15.000 RO.OOO SSM SM IJSIJ M IJIIM ttM lt IIM tl NJIE ttE EHE E KBE SE SSE 5.7&5E-09 5.217E-09 4.899E-09 6.503E 09 5.923E-09 5.473E-09 5.863E"09 5.363K-09 4.STSE 09 3.640E-09 3.384E-09 3.184E-09 4.529E-09 4.191E"09 3.939E-09 6.18IE-O'I 5.653K-OS 5.24RE 0$t.306K-o'8 l.Ieta-oe 1.091E-oe 1.213K-OS I.tosa-oe I~DRRE"08 1.386K-OB I.R&5E-.OS I.ITIK OS 8.8&la-ot 8.122E"09 7.542E-09 9.039K"09 S.R63E-09 7.6C4E-O'9 1.525E-os 1.3sta-os I.eloa-os 1.673E-OS I.stea-os 1.388E-DB 9 I'SSE-09 8.34BE-09'1.618K 09 7.344E-OS 6.644E"Ot C.142E 0'9 5.065K-09 4.63]E-OS 4.291E 0$4.568K-09 5.OBOE-09 4.633E-09 3'.045E-0'9 3.TOBE-09 4.88IE-49 I.OIBE-OB$.496E-09 1.089E-OS 7.033E-O'9 7.14IE-09 I.174E-08 I.RBIE-OB 7.023K-09 5.633E-09 4.004E-09 4.275E-09 4.414E-09 3.TBOE-09 3.510E-0'9 4.735E-DS 4.429E-09 4.155E-OS 3.9IDE-OS 4.330K-09 4.060E-49 3.8IBK-O9 3 LODE-0$2.842K-09 2.695E-49 2.560E-09 2.436E-DS'3.504E-O'9 3.312E-49 3.141K"09 2.9$5E-DS 4.5&2E"49 4'77E-O'J 4 022K-Ot 3.192E-09 9.417K-09 8.858K" 09 B.301E-D9 7.813E-O'9 8.859E-09 S.R94E-09 1 790E-09 7.338K-09 1.011K-OB 9.526K-09 8.953E-09 8.437E-OS 6.582E-49 6.119E-49 S.BISE-09 5.493K-09 6.6BIE-09 6.R13E-O'J S.tosa-49 5.580E-OS I.D90K-OS 1.416K-OB 9.507K-09 8.$24E-OS I.IBTE-OS 1.105K-DB 1.033E-OB 9.67OE"0$6.505K-09 6.450K-09 5 64SE-09 5.290E"0$5.223E-49 4.863E-OS 4.544K-09 4.25$E-OS 3.744E-09 3.513E-09 3.30&E-DS 3.119E"09 3.380E-49 R.269K-09 3.690E-09 2.414E-09 3.403K-09 2.254E-09 2.323E-09 1.635K-OS 2.842E-09 1.983K-09 3.585E-OS 2.375E-OS 7.3&BE-09 4.802K-09 6.9'3 IE-09 4.513K-09 7.912a-ot s.eloa-ot 5.198E-09 3.414E-09 S,RD4E-09 3.566E-OS 8.402E-09 5.429K-09 9.099E-09 S.BIDE"09 4.974E"09 3.159E-09 4.004E-09 2.560K-09 2.95IE-09 1.969K-09 1.689E-09 1.764K-09 1.659K-09 1.247E-09 1.506K"0'9 1.74BE-09 3.498E"09 3.36RE-09 3.876E-O'9 2.570E-09 R.6L6E 0'9 3.950E-DS 4.191K-O'9 R.215E-09 1.852E-DS 4avc-nn /'I l a I F d}}

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