ML041610196
| ML041610196 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 04/09/2004 |
| From: | Doty M FirstEnergy Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| PY-CEI/NRR-2789L | |
| Download: ML041610196 (198) | |
Text
'NOP-iP003-01 Page ofi Rev.
I Initiating ActP* -RLP-3 R vev ODCM R.'e's Lee?(
Title:
Offsite Dose Calculation Manual Brief description of activity (what is being changed and why):
- 1. Revised to clarify that the wording in 4.0.2 of Appendix C so you can apply 1.25 times to actions in addition to surveillance items.
- 2. Corrected the frequency note for release path B on page 138 to (b) instead of (c) which was In error.
- 3. Added Ingestion and external dose factors for Cu-67 and Rr-87m.
- 4. Added reference to Federal Guidance Report 13 CD Supp;ement since this was the source for the dose factors for Cu-67 and Sr-87m.
- 5. Clarified that a batch release requires a review under 10 CFR 50.59.
- 1. EXEMPTIONS Is scope of the entire the activity exempt from the 10CFR50.59 process because It is limited to:
1.1 Managerial of administrative procedures.................-.-............. ... YES 0 NO 1.2 UFSAR changes (or equivalent Information) excluded from the requirement to perform a 10CFR50.59 Screen and Evaluation by NEI 98-03?. ................. .... . . ....... . D YES 0 NO 1.3 Maintenance activities, abandonment or non-reliance on a system to meet a requirement.
and temporary alterations planned for 90 days or less while at power. ............... ........[ _YES 0 NO 1.A Changes evaluated under another program that includes screening for 10CFR5059 appflcability.............................................Y.............E....... . ..... ___.... ......... __. IVS 0 NO
- 2. OTHER REGULATIONS 2.1 Does the activity require a license amendment?
2.1.1 Operating Ucense ..... ...................... . ..... ....... El YES NO 2.1.2 Technical Specifications . ... ......... _.. ._. .. ........... __ _ .. YES ED NO 2.1.3 Environmental Protection Plan.. ..... .......... .E _ YES ED NO 2.2 Does the activity deviate from the requirements of one or more of the following:
2.2.1 Quality Assurance Programr (ElCFR 5054(a)) .. __ YES 0 NO 2.2.2 SecurftyPlans (10CFR5O.54(p)) ...................... ... .......
- 0 NO
_EIYES 2.2.3 Emergency Plan 1CFR5O.54(q)).. . ........ _.... O YES 0 NO 2.2.4 IST Program Plan (.CFR5OS5(a)(f) ......................... _.... l YES ED NO 2.2.5 ISI Program Plan .10.__ .. ...__ YES _0 __NO 22.6 Fire Protection Program (10CFR5OA8) ......... ........ .... ........... ..E YES 0 NO 2.2.7 Independent Spent Fuel Storage Facility (IOCFR72.48) .................. ............ . YES 0 NO 2.2.8 Another regulation:
10 CFR 20 (including ODCM) . ........................ __ ........._. 0 ED YES El NO 10 CFR 50.12 ........ .............. ............ ._ _____.. _YES
.. __._.._ 0 NO iOCFR 50.46 .... ......................
. YES 0 NO Other - list the regulation(s): - .-.....
................. . ... . ....... . . .... ....... E YES 0l NO
- 3. CONCLUSION 3.1 DoesI0CFR50.59apply? . ..... ................. YES El NO 3.2 Does this activity require a change to the UFSAR? Change Request No: _ __.__ _.._...._. YES 0D NO 3.3 Summarize the bases for responses: Include Keywords used to search-documents, ODCM This Is a change to the ODCM and since the ODCM Is included in 2.2.8 next to 10 CFR 20 for another regualtion then IOCFR50.59 does apply.
Preparer (Print name) Sign atur_ Date Michael Doly I ///s/ 2-I Reviewer (Print name) Sign/tufe Date fi~J x~5 ///S
FL, Yne 10 CFR 50.59 SCREEN No. S02-01309 NOP-LP-4003-02 Page i of 1 Rev. t?-91o Initiating Actigl44p. Revy,9a J BVP 1I I EDBVPS2 lS DBNPS lPNPP
Title:
Offsite Dose Calculation Manual Scope of activity being screened.
- 1. Revised to clarify that the wording in 4.0.2 of Appendix C so you can apply 1.25 times to actions in addition to surveillance items.
- 2. Corrected the frequency note for release path B on page 138 to (b) instead of (c) which was in error.
- 3. Added ingestion and external dose factors for Cu-67 and sr-87m.
- 4. Added reference to Federa; Guidance Report 13 CD Supplement since this was the source for the dose factors for Cu-67 and Sr-87m.
- 5. Clarified that batch releases require a review for the requirements under 20 CFR 50.59.
List the UFSAR-described design functions potentially affected by the activity.
Degree of conformance with Reg. Guide 1.109.
Section 1.8-1 of the USAR describes the degree of conformance for Reg. Guide 1.109. The purpose of this Reg.
Guide to provide the methodology for the calculation of annual doses to man from routine releases of reactor effluents for the purpose of evaluating compliance with 10 CFR. Part 50 Appendix I. Reg. Guide 1.109 (revision 1 Issued In October 1977) does not contain dose factors for Cu-67 and Sr-87m however In the Introduction to the Reg. Guide it describes the guide as a general approach and that the use of site specific values by the applicant is encouraged If the assumptions and methods used to obtain these parameters is fully described and documented.
These Isotopes were detected In reactor coolant and since data could not be obtained In the Reg. Guide another source was researched. Federal Guidance Report Ho.13 - Cancer Risk Coefficients for Environmental Exposure to Radionuclides was issue by the EPA In September 1999. The CD Supplement Rev 1, which contains the specific tables for FGR 13 was issued in April of 2002. Use of the FGR dose conversion factors provides conservative factors from the most current guidance for the instances where RG 1.109 does not provide that information.
I OCFR 50.59 screening questions. Check the correct response.
- 1. Does the proposed activity Involve a change to an SSC that adversely affects an 0 YES 0 NO UFSAR-described design function?
The changes made to the ODCM will not change any system structure or component.
The changes being made will add dose conversion factors, clarify that the rule for the specified frequency of 125 times the specified time Interval can apply to an action requirement, and correct an error to a notation on a table for sampling requirements.
- 2. Does the proposed activity Involve a change to a procedure that adversely affects how a YES 0 NO UFSAR-described SSC design functions are performed or controlled?
The wording in section 4.0.2 of Appendix C Is being revised that will clarify that the rule for the specified frequency of 1.25 time the specified time interval can apply to action requirements is being changed since that was the intent of the change made when the ODCM was revised for Improved technical specifications. The wording in the original technical specifications for 4.0.2 was revised when Radiological Effluent Technical Specifications was relocated to the OffsIte Dose Calculation Manual. An effort was made to mimic the wording that was made as a part of Improved technical specifications however since improved technical specifications defines Completion Time which made it easier to define what the frequency extension applied to technical specifications. The wording used in the ODCM used time interval and It was not clear that this could be applied to an action. This was the Intent of this change and the wording is being revised to ensure this Isclear in the future.
- 3. Does the proposed activity involve revising or replacing an UFSAR-described O YES 3 NO evaluation methodology used In establishing the design bases or in the safety analyses?
The methods for performing dose calculations are not being revised. Using more specific dose factors is encouraged In Reg. Guide 1.109 and will not change the methodology used to perform these calculations.
- 4. Does the proposed activity involve a test or exoeriment not described In the UFSAR. a YES 0 NO where an SSC is utilized or controlled in a manner that Is outside the reference bounds of the design for that SSC or Is inconsistent with analyses or descriptions in the UFSAR?
The changes being made to the ODCM will add dose factors and clarify the application of the extension frequency for actions. These are not changes to test or experiments not described In the USAR.
List the documents reviewed where relevant Information was found, Including section numbers and key words searched:
UFSAR Sections: 1.8 Change Request No: N/A Technical Specifications: None Other regulatory documents: ODCM Keywords: Reg. Guide 1.109 D At least one question Is answered YES. Perform a IOCFR50.59 Evaluation.
l All questions are answered NO. A10CFR50.59 Evaluation Is not required. Justify the determination:
Technical Specifications allows for licensee initialed changes to the ODCM as long as the documentation contains the following:
- 1. sufficient information to support the changes together with the appropriate analyses or evaluations justifying the changes, and
- 2. a determination that the changes maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFRM0, Appendix I. and not adversely impact the accuracy or reliability of effluent, dose or setpoint calculations.
This screen pros des the documentation and evaluation of the changes. Reg. Guide 1.109 allows the use of more specific dosefactors. Use of the FGR dose conversion factors provides tdnservalive factors from the most current guidance for the Instances where RG 1.109 does not provide that inforirnation. These changes will not revise the dose calculation or setpoint calculation methodology and will maintain the level of radioactive control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a. and 10 CFR 50. Appendix I.
-M t
_ .ss, dri >B t*]{ iig t-
t~ --
No. 03-01131 NPage of I Rev. 0 Initiating Activity No. Rev.
CHI-ODCM 9 El BVPSI El BVPS 2 El DBNPS PNPP
Title:
Offsite Dose Calculation Manual Brief description of activity (what Is being changed and why)
- 1. <RECS-PCR-2003-0092> Added reference to Commitment 101117. The commitment text Is as follows:
"DURING PREPARATION OF THIS RESPONSE, THE DISTANCE REFERENCED FOR LOCATION 51 WAS REEXAMINED USING A USGS TOPOGRAPHIC MAP, AND BY REVIEWING PREVIOUS PNPP LAND USE SURVEY REPORTS. THIS DISTANCE WAS FOUND TO BE 9.6 MILES (15.4 KILOMETERS). THIS VALUE WILL BE INCORPORATED INTO THE ODCM AND FORWARDED TO YOU WITH THE NEXT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT."
This commitment had the ODCM listed as a closure document but was not listed In the ODCM. This change will Include this commitment In the ODCM.
- 2. <RECS-PCR-2003-0017> Removed reference to the low discharge volume throttle valves In Section 2.1.1.3.
The radwaste low discharge volume throttle valves were abandoned In place per DCN-05621 and evaluated per Safety Evaluation SE 96-0130.
- 3. <RECS-PCR-2003-0092> Removed reference to an Interlaboratory program approved by the commission from Control 3.12.3.
The NRC no longer approves any Interlaboratory check program.
- 4. <RECS-PCR-2003-0092> Updated the definition of MEMBER OF THE PUBLIC to reference the new IOCFR20 definition. Added the 10CFR20 definition of OCCUPATIONAL EXPOSURE since It Is used In the new definition of MEMBER OF THE PUBLIC.
- 1. EXEMPTIONS Is scope of the entire the activity exempt from the I OCFR50.59 process because It is limited to:
1.1 Managerial or administrative procedures......................................................................................... E] YES 0 NO 1.2 UFSAR changes (or equivalent Information) excluded from the requirement to perform a I OCFR50.59 Screen and Evaluation by NEI 98-03? ....................................................................... 0 YES 0 NO 1.3 Maintenance activities, abandonment or non-reliance on a system to meet a requirement, and temporary alterations planned for 90 days or less while at power . .C........................... E YES Z NO
.1.4 Changes evaluated under another program that includes screening for 10CFR50.59 applicability.......................................... ;YES C 0.. NO
- 2. OTHER REGULATIONS 2.1 Does the activity require a license amendment?
2.1.1 Operating License.C YES ONO 2.1.2 Technical Specifications .C YES 0 NO 2.1.3 Environmental Protection Plan.C YES 0 NO 2.2 Does the activity deviate from the requirements of one or more of the following:
2.2.1 Quality Assurance Program (10CFR50.54(a)) ........................................ C0 YES YES0 NO 2.2.2 Security Plans (10CFR50.54(p)) ........................................ C. Y3 YES 0] NO 2.2.3 Emergency Plan 10CFR50.54(q)) ........................................ C YES 0ES NO 2.2.4 IST Program Plan (10CFR50.55(a)(f)) ........................................ C0YES 0ES NO 2.2.5 ISI Program Plan (10CFR50.55(a)(g)) ........................................ .... . C YES 0.. NO 2.2.6 Fire Protection Program (10CFR50.48) ......................................... C. YES 0 NO 2.2.7 Independent Spent Fuel Storage Facility (10CFR72.48) ........................................ C. YES 0 NO 2.2.8 Another regulation:
10 CFR 20 (including ODCM) .......................................................... 0...YES C..NO 10 CFR 50.12 .......................................................... YES 0 NO 10 CFR 50.46 ........................................................... 0YES YE 0 NO Other - list the regulation(s): .. . ................ CO.........................
YES NO
- 3. CONCLUSION 3.1 Does IOCFR50.59 apply? .......................................................... YES 0 NO 3.2 Does this activity require a change to the UFSAR? Change Request No: ............ .............. D YES 0 NO 3.3 Summarize the bases for responses: Include Keywords used to search documents. The changes are to keep the document administratively current with commitments, definitions, and system design changes. Also incorporated in this change is the removal of the requirement to have the environmental monitoring Interlaboratory program approved by the NRC as the NRC no longer approves any programs. It does not
Fistneg REGULATORY APPLICABILITY DETERMINATION No. 03-01131 lNOP-LP4003-01 Page 2 of 2 Rev. 0 Initiating Activity No. Rev.
CHI-ODCM 9 Involve a change to a SSC, change to a procedure that affect activities or controls for a SSC design function or a change to an evaluation methodology used In estabiishing design basis. This Is not a test or experiment. UFSAR Sections: 13.5.2.2.8,1.08,11.05, 14.02 Keywords - Chemistry Instruction, Offsite Dose Calculation Manual, ODCM Preparer (Print name)' Signature Date Rodney E. States 8MO3 Reviewer (Print name) Signature Date
ODCM Page: i Rev.: 9 PERRY OPERATIONS MANUAL Offsite Dose Calculation Manual TITLE: OFFSITE DOSE CALCULATION MANUAL REVISION: 9 EFFECTIVE DATE: 9-9-03 PREPARED: P. H. Lashlev 7-31-03
/ Date
ODCM Page: ii Rev.: 9 Offsite Dose Calculation Manual Table of Contents Section Title Pae
1.0 INTRODUCTION
1 2.0 LIQUID EFFLUENTS 2 2.1 Batch Releases 2 2.1.1 Monitor Alarm Setpoint Determination 3 2.1.1.1 Minimum Acceptable Dilution Factor Determination 3 2.1.1.2 Maximum Allowable Radwaste Tank Discharge Flow Rate Determination 4 2.1.1.3 Liquid Radwaste Discharge Flow Monitor Alarm Setpoint 4 2.1.1.4 Liquid Radwaste Discharge Radiation Monitor Alarm/Trip Setpoint 5 2.1.2 10CFR20 Compliance - Liquid Effluent Concentration 6 2.1.2.1 Concentration of Radionuclides in Prerelease 7 2.1.2.2 Post Release 7 2.2 Continuous Releases 8 2.2.1 Monitor Alarm Setpoint Determination 9 2.2.1.1 Emergency Service Water Radiation Monitor Alarm Setpoint 9 2.2.1.2 Minimum Allowable Background of the Emergency Service Water Radiation Monitor 10 2.2.1.3 Determination of the Expected Monitor Response Based on the Reactor Water Source Term 10 2.2.1.4 Minimum Allowable Setpoint Based on Monitor Background 11 2.3 10CFR50, Appendix I Compliance - Liquid Effluent Dose 11 2.3.1 Dose Calculations 12 2.3.2 Cumulation of Doses 13 2.3.3 Projection of Doses 14 2.3.4 Population Dose 14 3.0 GASEOUS EFFLUENTS 32 3.0.1 Batch Releases 32 3.0.2 Continuous Releases 32 3.1 Monitor Alarm Setpoint Determination 34 3.1.1 Determination of the "Mix" (Noble Gas Radionuclide Composition) of the Gaseous Effluent 35 3.1.2 Determination of the Maximum Acceptable Total Activity Release Rate of Noble Gas Radionuclides in Gaseous Effluent Based on Whole Body Dose Rate Limit 35 3.1.3 Determination of the Maximum Acceptable Total Activity Release Rate of Noble Gas Radionuclides in Gaseous Effluent Based on Skin Dose Rate Limit 36 3.1.4 Determination of the Maximum Acceptable Total Radioactivity Concentration of all Noble Gas Radionuclides in Gaseous Effluent 37 3.1.5 Determination of the Maximum Acceptable Monitor Count Rate Above Background Attributed to Noble Gas Radionuclides 38
ODCM Page: iii Rev.: 9 Offsite Dose Calculation Manual Table of Contents (Cont.)
Section Title Page 3.1.5.1 Determination of the Monitor High Alarm Setpoint 38 3.1.5.2 Determination of the Monitor Alert Setpoint 39 3.2 Compliance with IOCFR20 - Gaseous Effluent Dose Rate 39 3.2.1 Noble Gases 39 3.2.2 Radionuclides, Particulates, and Other Radionuclides 40 3.2.3 Dose Rate Calculations 40 3.3 10CFR50, Appendix I Compliance - Gaseous Effluent Dose 67 3.3.1 Noble Gases 67 3.3.2 Radioiodines, Particulates, and Other Radionuclides 67 3.3.3 Dose Calculations 68 3.3.4 Cumulation of Doses 69 3.3.5 Projection of Doses 70 3.4 Population Dose 70 4.0 TOTAL DOSE 71 4.1 40CFRl90 Compliance - Uranium Fuel Cycle Dose 71 4.2 Direct Radiation Dose from PNPP 72 4.3 Dose to Members of the Public While Onsite 73 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 73 5.1 Monitoring Program 73 5.2 Land Use Census Program 74 5.3 Inter-Laboratory Comparison Program 75 APPENDIX A Atmospheric Dispersion and Deposition Parameters 86 APPENDIX B Lower Limit of Detection 100 APPENDIX C Controls 104 REFERENCES 185
ODCM Page: iv Rev.: 9 List of Tables Table Title Page 2.3-1 organs Used for Liquid Effluent Dose Calculations 15 2.3-2 Age Groups Used for Liquid Effluent Dose Calculations 15 2.3-3 Liquid Effluent Dose Pathways 15 2.3-4 Bio-Accumulation Factors (Bip) (pCi/kg per pCi/liter) 16 2.3-5 Ingestion Dose Factors for Adult (mrem/pCi ingested) 17 2.3-6 Ingestion Dose Factors for Teenager (mrem/pCi ingested) 19 2.3-7 Ingestion Dose Factors for Child (mrem/pCi ingested) 21 2.3-8 Ingestion Dose Factors for Infant (mrem/pCi ingested) 23 2.3-9 External Dose Factors for Standing on Contaminated Ground 25 2.3-10 Liquid Effluent Dilution Factors (MP) 27 2.3-11 Transit Times Required for Nuclides to Reach the Point of Exposure (tP) 27 2.3-12 Usage Factors (Uap) 28 2.3-13 Dilution Factors for Each of the Potable Water Intakes within 50 Miles of PNPP 29 2.3-14 Dilution Factors for the Fish Ingestion Pathway Individual Grid Locations 30 2.3-15 Dilution Factors for the Shore Exposure Pathway 31 3.1-1 Whole Body and Skin Dose Factors 37 3.2-1 Organs Used for Gaseous Effluent Dose Calculations 45 3.2-2 Age Groups Used for Gaseous Effluent Dose Calculations 45 3.2-3 Gaseous Effluent Dose Pathways 45 3.2-4 Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases 46 3.2-5 External Dose Factors for Standing on Contaminated Ground 47 3.2-6 Inhalation Dose Factors for Adult (mrem/pCi inhaled) 49
ODCM Page: v Rev.: 9 List of Tables (Cont.)
Table Title Page 3.2-7 Inhalation Dose Factors for Teenager (mrem/pCi inhaled) 51 3.2-8 Inhalation Dose Factors for Child (mrem/pCi inhaled) 53 3.2-9 Inhalation Dose Factors for Infant (mrem/pCi inhaled) 55 3.2-10 Ingestion Dose Factors for Adult (mrem/pCi ingested) 57 3.2-11 Ingestion Dose Factors for Teenager (mrem/pCi ingested) 59 3.2-12 Ingestion Dose Factors for Child (mrem/pCi ingested) 61 3.2-13 Ingestion Dose Factors for Infant (mrem/pCi ingested) 63 3.2-14 Annual Usage Factors for the Maximum Exposed Individual 65 3.2-15 Annual Usage Factors for the Average Individual 65 3.3-1 Gamma and Beta Air Dose Factors for Semi-Infinite Plume 70 5.1-1 Radiological Environmental Monitoring Program 76 5.1-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 81 5.1-3 Detection Capabilities for Environmental Sample Analysis and Lower Limit of Detection (LLD) 82 A-1 Atmospheric Depletion and Deposition Factors 88 A-2 Site Boundary Atmospheric Dispersion (X/Q) and Deposition Parameters (D/Q) for PNPP Unit 1 89 A-3 Atmospheric Dispersion (X/Q) as a Function of Distance (s/M3 ) 90 A-4 Atmospheric Dispersion (D/Q) as a Function of Distance (m-2 ) 95
ODCM Page: vi Rev.: 9 List of Figures Figures Title Page 2.1-1 Liquid Radioactive Waste (LRW) Discharge System 2 3.0-1 Gaseous Effluent System Flow Diagram 33 3.2-1 PNPP Site Boundary and Unrestricted Area 66 5.1-1 Technical Specification Required REMP Sampling Locations within Two Miles of the Plant Site 83 5.1-2 Technical Specification Required REMP Sampling Locations Between Two and Eight Miles from the Plant Site 84 5.1-3 Technical Specification Required REMP Sampling Locations Greater Than Eight Miles from the Plant Site 85
ODCM Page: vii Rev.: 9 SCOPE OF REVISION:
Rev. 9 - 1. <RECS-PCR-2003-0092> Added reference to Commitment L01117.
- 2. <RECS-PCR-2003-0017> Removed reference to the low discharge volume throttle valves in Section 2.1.1.3.
- 3. <RECS-PCR-2003-0092> Removed reference to an interlaboratory program approved by the commission from Control 3.12.3.
- 4. <RECS-PCR-2003-0092> Updated the definition of MEMBER OF THE PUBLIC to reference the new IOCFR20 definition. Added the IOCFR20 definition of OCCUPATIONAL EXPOSURE.
ODCM Page: 1 Rev.: 9
1.0 INTRODUCTION
This Offsite Dose Calculation Manual (ODCM) contains information and methodologies to be used by the Perry Nuclear Power Plant (PNPP), Unit 1, to ensure compliance with PNPP Radiological Effluent Technical Specifications. The Technical Specifications and this ODCM are written to satisfy 10CFR20, 10CFR50.36 and Appendix I, and 40CFR190 requirements.
Sections 2 and 3 of this manual deal with liquid and gaseous radiological effluents, respectively. Each of these sections contain alarm setpoint determination, radiation dose and dose rate calculation methodologies, as well as limits and requirements. Section 4 covers uranium fuel cycle related radiation dose limits including direct dose.
Also included in this manual, in Section 5, is information relating to the Radiological Environmental Monitoring Program (REMP). The figures and tables contained therein designate specific sample types and locations currently used to satisfy the Technical Specification requirements for the REMP as well as sampling reporting and detection capability limits. The sample types and locations are subject to change based on factors including the results of the annual Land Use Census.
The ODCM has been prepared, as generally as possible, in order to minimize future revisions. However, any such changes will be reviewed and approved as per the Administrative Control Section of the PNPP Technical Specifications.
Supplemental information needed to support calculations is contained in the appendices at the end of this manual. Appendix A contains atmospheric dispersion and deposition parameters and Appendix B presents the methodology for determining the lower limit of detection (LLD).
Appendix C of the ODCM was prepared based on guidance of NUREG-1302,
'Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors," Generic Letter 89-01, Supplement No. 1. This appendix along with plant procedures will be used by plant personnel to demonstrate compliance with Specification 5.5.4 (Radioactive Effluent Controls Program) of the PNPP Technical Specifications. <L02211>
ODCM Page: 2 Rev.: 9 2.0 LIQUID EFFLUENTS 2.1 Batch Releases A batch release is the discharge liquid radioactive waste of a discrete volume. Batch releases from the liquid radwaste system may occur from any of the following tanks: waste sample tank, floor drain sample tank, chemical waste distillate tank, and detergent drain tank (see Figure 2.1-1). The maximum release rate possible, due to pump capacity, is 200 gallons per minute from all release tanks except the detergent drain tanks, which have a maximum release rate of 50 gallons per minute.
All of the above liquid radwaste releases go to the Emergency Service Water discharge which is then released through the discharge tunnel after mixing with Service Water effluent and/or and blowdown from Circulating Water system, if present.
Figure 2.1-1 Liquid Radioactive Waste (LRW) Discharge System a 1 2 DttSit.
. ICl ~HIGH RAO.
DRINUN r.~~~~O Cr}
ISCH.
tt&W^stt. FO LANE
ODCM Page: 3 Rev.: 9 The type and frequency of sampling and analysis required by the ODCM is given in Appendix C, Table 4.11.1.1.1-1. Prior to sampling for analysis, each batch should be isolated, and thoroughly mixed to assure representative sampling. For mixing, the contents of the tank are recirculated by isolating the tank and turning on equipment that takes suction from and discharges back into the tank. Recycle lines are provided with one or more mixing eductors located near the bottom of the tanks to promote better mixing as well as reducing recirculation time.
This ensures that the water in the tank will be mixed and will be representative of the activity in the tank. The minimum recirculation performed is the equivalent of two volumes of the tank contents.
Monitor alarm setpoints will be determined in order to ensure compliance with 10CFR20. The radioactive content of each batch release will be determined prior to release in accordance with ODCM, Appendix C, Table 4.11.1.1.1-1. Concentrations for tritium and other non-gamma emitting isotopes will be those most recently determined (previous month/quarter).
2.1.1 Monitor Alarm Setpoint Determination The following methodology is used to calculate the setpoints for the Radwaste Discharge Radiation Monitor - ESW Discharge and Liquid Radwaste Adjustable High Flow Trip Unit to ensure that liquid radwaste effluent releases from the site to unrestricted areas are below the limiting effluent concentrations (EC) specified in 10CFR20, Appendix B, Table 2, Column 2 for radionuclides other than noble gases. An EC of 2.OE-4 pCi/ml has been established for dissolved and entrained noble gases. The Radwaste Discharge Radiation Monitor -
ESW Discharge provides alarm and automatic termination of releases prior to exceeding these limits.
NOTE: Liquid radwaste discharge flow rate shall be verified at least once per four hours, whenever the flow rate measuring device(s) is inoperable during actual releases.
2.1.1.1 Minimum Acceptable Dilution Factor Determination:
DF_ C. (2.1-1)
ECi Where:
DFo - the minimum acceptable dilution factor determined from analysis of the liquid effluent to be released; Ci = the concentration of radionuclide "i" in the batch to be released, pCi/ml. If the concentration of a radionuclide is below the lower limit of detection, the radionuclide shall not be included as a source term in the setpoint calculation.
= -
ODCM Page: 4 Rev.: 9 ECi = the limiting effluent concentration of radionuclide "i",
from IOCFR20, Appendix B, Table 2, Column 2, in pCi/ml and (2.OE-4 pCi/ml for noble gases).
DF = IODFO (2.1-2)
Where:
DF = the conservative dilution factor used by PNPP to calculate the maximum release rate prior to release in order to ensure compliance with 20CFR20; DFo = the minimum acceptable dilution factor, as per equation 2.1-1; 10 = a factor of ten less than 10CFR20, Appendix B, Table 2, Column 2, limits; which represents an order of magnitude of conservatism for liquid radwaste releases from PNPP.
2.1.1.2 Maximum Allowable Radwaste Tank Discharge Flow Rate Determination (0.64)(mdf) fmax = (2.1-3)
DF Where:
fmax 2 the maximum allowable radwaste tank discharge flow rate for the batch to be released, gpm; DF - the conservative dilution factor, per equation 2.1-2; mdf = the minimum dilution flow - supplied by the Service Water system, Emergency Service Water system, or Circulating Water system blowdown, gpm; 0.64 = an engineering factor to prevent spurious alarms.
2.1.1.3 Liquid Radwaste Discharge Flow Monitor Alarm Setpoint <L00434>
Monitor alarm setpoints are determined to ensure that the concentration of radionuclides in the liquid radwaste effluent released from PNPP to unrestricted areas does not exceed the limits specified in IOCFR20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved and entrained noble gases. A limiting effluent concentration of 2.OE-4 pCi/ml has been established for dissolved and entrained noble gases in liquid effluents.
ODCM Page: 5 Rev.: 9 SPf = (l.25)(fact) (2.1-4)
Where:
SPf = liquid radwaste adjustable high flow trip Unit (G50-K805A/B or GSO-K926/7) alarm setpoint, gpm; fact = actual allowable radwaste tank discharge flow rate for the batch to be released, not to exceed the maximum allowable radwaste discharge f low rate fmax as def ined in equation 2.1-3, gpm; 1.25 = engineering safety factor to prevent spurious alarms.
The liquid radwaste tank discharge flow should be maintained at or below this fact value by proper regulation of the high volume discharge throttle valves (G50-F153 or G50-F155).
2.1.1.4 Liquid Radwaste Discharge Radiation Monitor Alarm/Trip Setpoint Monitor alarm/trip setpoints are determined to ensure that the concentration of radionuclides in the liquid radwaste effluent released from PNPP to unrestricted areas does not exceed the limits specified in 10CFR20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. A limiting effluent concentration of 2.OE-4 gCi/ml has been established for dissolved and entrained noble gases in liquid effluents.
CRc = E (Ci)(EJ) (2.1-5)
Where:
CRC e the calculated monitor count rate above background, cpm; Ci = the concentration of radionuclide 'i" in the batch to be released, jICi/ml; Ei = the detector efficiency of the monitor for radionuclide "i", cpm/ (CICi/ml).
OR CRx = (Rs)(Fx)(ECi) (2.1-6)
Where:
CRX = the cross-calibrated monitor count rate above background, cpm;
ODCM Page: 6 Rev.: 9 Fx = the cross-calibration factor is used to ratio the liquid radwaste discharge radiation monitor actual response to the Cs-137 calibrated response; Rs = the response of the Liquid Radwaste Discharge Radiation Monitor to a Cs-137 calibrated standard, cpm/(pCi/ml).
SPr = (1.2 5)( fmaxj(CRn)+ BG (2.1-7) fact, Where:
SPr = the Radwaste Discharge Radiation Monitor - ESW Discharge alarm/trip setpoint, in cpm; BG = background count rate due to internal contamination and radiation levels in the area of the monitor, cpm; CRn = monitor net count rate, either CRc or CR,, as per equation 2.1-5 or 2.1-6, cpm; 1.25 = engineering safety factor to prevent spurious alarms; fmax/fact= an adjustment factor (to account for the difference between an actual radwaste discharge flow rate to be used for the discharge and maximum allowable radwaste discharge flow rate) to allow operational flexibility and to minimize spurious alarms; Where:
fact = the actual radwaste discharge flow rate, this value must always be less than or equal to fmax' gpm; fmax the maximum allowable radwaste discharge flow rate, per equation 2.1-3, gpm.
2.1.2 IOCFR20 Compliance - Liquid Effluent Concentration In order to show compliance with 10CFR20, the concentrations of radionuclides in liquid effluents will be determined and compared with the limiting effluent concentrations as defined in IOCFR20, Appendix B, Table 2, Column 2, (2.OE-4 pCi/ml for dissolved and entrained noble gases). Concentrations of radioactivity in effluents prior to dilution will be determined. Concentration in diluted effluent will be calculated using these results prior to each batch release, and following each batch release. PNPP has no continuous releases.
ODCM Page: 7 Rev.: 9 2.1.2.1 Concentration of Radionuclides in Prerelease The radioactivity content of each batch release will be determined prior to release. PNPP will show compliance with IOCFR20 in the following manner:
The concentration of the various radionuclides in batch releases prior to dilution is divided by the minimum dilution flow to obtain the concentration at the unrestricted area. This calculation is shown in the following equation:
Conci = (Ci)(f) mdf (2.1-8)
Where:
Conci = the concentration of radionuclide "i" at the unrestricted area, pCi/ml; Ci = the concentration of radionuclide "i" in the batch to be released, pCi/ml; f = the radwaste tank discharge flow rate for the batch to be released, gpm; mdf = the minimum dilution flow, per equation 2.1-3, gpm.
The projected radionuclide concentrations in the unrestricted area are compared to the limiting effluent concentrations in 10CFR20, Appendix B, Table 2, Column 2 (2.OE-4 pLCi/ml for dissolved and entrained noble gases) in order to give a final IOCFR20 compliance check, i.e., the following equation must be met:
EConci < 1 (2.1-9)
ECi Where:
Conci = the concentration of radionuclide "in at the unrestricted area, pCi/ml; ECi = the limiting effluent concentration of radionuclide "i",
from IOCFR20, Appendix B, Table 2, Column 2 (2.OE-4 pCi/ml for dissolved and entrained noble gases),
PCi/ml.
2.1.2.2 Post Release The actual radioactivity content of each batch release will be determined following release to show final compliance with IOCFR20.
ODCM Page: 8 Rev.: 9 The concentration of the various radionuclides in batch releases prior to dilution is divided by the actual dilution to obtain the concentration at the unrestricted area. This calculation is shown in the following equation:
Conci = (Ci)(Virt) (2.1-10)
Vdil Where:
Conci = the actual concentration of radionuclide "in at the unrestricted area for the release, pCi/ml; Ci = the concentration of radionuclide "in in the batch released, pCi/ml; Vdil = the actual volume of dilution water during the release (total plant discharge flow, including Service Water, Emergency Service Water, and cooling tower blowdown), in gallons; Vlrt = the actual volume of the liquid radwaste tank discharged for the batch, gal.
The concentrations in the unrestricted area are compared to the limiting effluent concentrations in 10CFR20, Appendix B, Table 2, Column 2 (2.OE-4 pCi/ml for dissolved and entrained noble gases). In order to demonstrate final compliance with IOCFR20, the following equation must be met:
Conci < 1 (2.1-11)
ECi Where:
Conci = concentration of radionuclide wi" at the unrestricted area, VCi/ml; ECi = limiting effluent concentration of radionuclide "i',
from 10CFR20, Appendix B, Table 2, Column 2, pCi/ml.
2.2 Continuous Releases A continuous release is the discharge of fluid wastes of a non-discrete volume, i.e., from a volume or system that has an input flow during the continuous release. The only potential for a continuous release at Perry is for RHR heat exchange leakage into the Emergency Service Water system and for tritium activity in the M35 Supply Plenum drain to storm drains.
ODCM Page: 9 Rev.: 9 Potentially contaminated discharges from the ESW are monitored by an installed radiation monitoring system. This system consists of two channels, one for monitoring downstream of equipment in Emergency Service Water System Loop A and the other for Emergency Service Water Loop B. If radiation is detected, the affected Emergency Service Water line can be manually isolated. The decision of whether to isolate or not is dependent upon other conditions. The PNPP staff will take appropriate action to limit release.
The Emergency Service Water discharged will be sampled and analyzed in accordance with ODCM Appendix C, Table 4.11.1.1.1-1. To show compliance with 10CFR20, the sum of the concentrations of radionuclide "i" in unrestricted areas due to both continuous and batch releases divided by that isotope's limiting effluent concentration must be less than 1.
During the summer months, the Turbine Building Supply Plenums (lM35BOOOlA,B,C) are used as a cooling source; condensation from the cooling coils is collected in the M35 plenum drain pans. The moisture from the outside air is condensed and flows into the drain pan. During hot, humid months with low wind speed, the potential exists for some of the gaseous effluent exhaust from the plant to be recycled back into the plant through the M35 Turbine Building Supply Plenums. Since the air from the plant gaseous effluents can contain tritium, then the water in the M35 Turbine Building Supply Plenums could also contain tritium if this exhaust was recycled back into the plant. The highest possible concentration of tritium in the M35 drains would be the condensed concentration in the effluent vent; however, this value is further diluted from humidity from outside air. The gaseous effluent vents radiation monitors will provide the monitoring to ensure compliance with IOCFR20. Grab samples will be performed in accordance with ODCM Appendix C Table 4.11.1.1.1-1 on the M35 drains.
2.2.1 Monitor Alarm Setpoint Determination The following methodology is used to calculate the setpoints for the Emergency Service Water loops A & B Radiation Monitors. This methodology ensures an alarm will be received prior to exceeding the limiting effluent concentration listed in 10CFR20, Appendix B, Table 2, Column 2.
- 1. Emergency Service Water Radiation Monitor Alarm Setpoint CRC =(BG + MR)(O.75)
Where:
CRC the calculated monitor count rate in cpm; BG = the background count rate due to internal contamination and radiation levels in the area of the monitor in cpm;
ODCM Page: 10 Rev.: 9 MR = expected monitor response due to 1.0 MPC of a typical reactor water isotopic mix; 0.75 engineering safety factor
- 2. Minimum Allowable Background of the Emergency Service Water Radiation Monitor BGmin = CRc - MR Where:
BGmin = minimum allowable background to ensure monitor will alarm prior to exceeding 1.0 EC; CRC = the calculated monitor count rate in cpm; MR = expected monitor response due to 1.0 EC of a typical reactor water isotopic mix; NOTE: If calculated value is negative, then 0 cpm will be used as the minimum allowable background.
- 3. Determination of the Expected Monitor Response Based on the Reactor Water Source Term MR = [ £ Idecayed decayed Effmon]
ECi Where:
MR = expected monitor response due to 1.0 MPC of a typical reactor water isotopic mix; Idecayed = activity of isotope (I) after decaying a given time; Effmon = radiation monitor detector efficiency for isotope (I);
ECi = Effluent concentration value for isotope (I),
Appendix B, Table 2, Column 2, IOCFR20
ODCM Page: 11 Rev.: 9
- 4. Minimum Allowable Setpoint Based on Monitor Background CRmin = BG + (BG /2T)
Where:
CRmin = Minimum allowable setpoint for a given monitor background (BG);
BG = the background count rate due to internal contamination and radiation levels in the area of the monitor in cpm; 2 = 95% confidence level; 2TC = two times the instrument time constant where
_ (Log1 oBG - LogloLocpm) (TChicpm - TClocpm) + TClocpm (LogJoHicpm - LogloLocpm)
Time Constants:
Hi/Lo cpm TC Hi/Lo cpm I 10 cpm 1.25 min 100 cpm 1.25 min 1,000 cpm 1.25 min 10,000 cpm 0.2 min 100,000 cpm 0.042 min 1,000,000 cpm 0.0033 min For Backgrounds less than 400 cpm, the following values will be used:
Locpm = 100 cpm TClocpm = 1.25 min Hicpm = 1000 cpm TCHicpm . 1.25 min For Backgrounds 2 400 cpm and less than 1,000 cpm, the following values will be used:
Locpm = 1,000 cpm TClocpm = 1.25 min Hicpm = 10,000 cpm TCHicpm = .2 min 2.3 10CFR50, Appendix I Compliance - Liquid Effluent Dose Doses resulting from liquid effluents will be calculated at least monthly to show compliance with 10CFR50, Appendix I. A cumulative summation of whole body and organ doses for the current quarter and current year will be maintained. Additionally, doses due to liquid releases are projected monthly.
ODCM Page: 12 Rev.: 9 2.3.1 Dose Calculations Radiation doses due to liquid radioactive effluents from PNPP are calculated based on three main dose pathways: potable water, aquatic foods (namely fresh water fish ingestion), and exposure to shoreline deposits. Irrigated food pathways, as discussed in Regulatory Guide 1.109, will not be of concern at PNPP as little or no water from Lake Erie is used for irrigation in the nearby Ohio counties of Lake, Ashtabula, Cuyahoga and Lorain. Nursery businesses and other agricultural activities that require supplemental water generally rely on water drawn from small ponds and streams.
Radiation dose to members of the public for liquid radioactive releases from PNPP will be calculated for the potable water, aquatic food, and shoreline deposit pathways using the following equations:
Potable Water Rajp 1100 Uap E(Qi)(Daipj)exp(-Xi tp) (2.3-1)
(Mp) (F)
Aquatic Foods Rajp 1100 Hap (Qi)(Bip)CDaipj)exp(-Xi tp) (2.3-2)
(Mp)(F)
Shoreline Deposits Rajp = 110,000 (ap) () (Qi) (Ti) (Daipj)[exp(- Xitj)] [ - exp(- Xitb)] (2.3-3)
(Mp) (F)
Where:
Rajp = the dose to individuals of age group "a" to organ "j" from all the radionuclides in pathway "p", in mrem; Bip = the equilibrium bioaccumulation factor for radionuclide "i" in pathway up", expressed as the ratio of the concentration in biota (pCi/kg) to the radionuclide concentration in water (pCi/l), from Table 2.3-4, 1/kg; Daipj= the dose factor, specific to a given age group "a",
radionuclide "i", pathway "p", and organ "j", which can be used to calculate the radiation dose from an intake of a radionuclide (mrem/pCi); or from exposure to a given concentration of a radionuclide in sediment, expressed as a ratio of the dose rate (mrem/h), and the areal radionuclide concentration, (pCi/m2 ), from Tables 2.3-5 through 2.3-9; F = the flow rate of the liquid effluent, ft3/sec;
p ODCM Page: 13 Rev.: 9 NOTE: The normal minimum dilution flow will be 30,000 gpm (USAR 11.2.3.2).
MP = the dilution factor at the midpoint of exposure (or the point of withdrawal of drinking water, point of harvest of aquatic food or shoreline), from Table 2.3-10, dimensionless; Qi = the release of radionuclide "i", Ci; lb = the period of time for which the sediment or soil is exposed to the contaminated water, 1.75 x 105 hr (20 yrs);
Ti = the half-life of radionuclide "i", days; tp = the average transit time required for radionuclides to reach the point of exposure, from Table 2.3-11; for internal dose, tp is the total time elapsed between release of the radionuclides and the ingestion of food or water, hr; Uap = the usage factor that specifies the exposure time or intake rate for an individual of age group a associated with pathway "p", from Table 2.3-12, hr/yr, I/yr, or kg/yr; W = the shoreline width factor, 0.3 (from Regulatory Guide 1.109);
Xi = radioactive decay constant of radionuclide li", h-';
1100 = a factor to convert from (Ci/yr)/(ft3 /s) to pCi/l; 110,000= a factor to convert from (Ci/yr)/(ft3 /s) to pCi/l and to account for the proportionality constant used in the sediment radioactivity model.
2.3.2 Cumulation of Doses The dose contribution from liquid effluents will be calculated at least monthly. Calculations will be performed to determine the maximum whole body as well as the maximum organ dose to an individual. These dose calculations will be summed for comparison with quarterly and annual limits. These results will be summed with the doses cumulated from the other months in the quarter of interest and in the year of interest. To assure compliance with the dose limits of 10CFR5O, Appendix I the following relationships shall hold:
for the quarter:
Dose
- 1.5 mrems whole body; Dose
- 5 mrems any organ;
ODCM Page: 14 Rev.: 9 for the year:
Dose
- 3 mrems whole body; Dose
- 10 mrems any organ.
The quarterly limits given above represent one-half of the annual design objective. If these quarterly or annual limits are exceeded, a special report will be submitted to the NRC, in accordance with ODCM Appendix C controls, stating the reason and corrective action to be taken.
2.3.3 Projection of Doses Anticipated doses resulting from the release of liquid effluents will be projected monthly. The doses calculated for the present month will be used as the projected doses unless information exists indicating that actual releases could differ significantly in the next month.
If the projected dose, when averaged over 31 days, exceeds 0.06 mrem to the whole body or 0.2 mrem to any organ, the liquid radwaste system will be used to process waste. The values for the projected dose impact levels correspond to approximately one forty-eighth of the IOCFR5O, Appendix I design objective. If continued at this rate for one year, the projected impact would correspond to less than one-fourth of the 10CFR50, Appendix I limit. The projected doses will be calculated using equations 2.3-1, 2.3-2, and 2.3-3.
In this case, the source term will be adjusted to reflect this information and the justification for the adjustment noted. This adjustment should account for any radwaste equipment which was operated during the previous month that could be out of service in the coming month.
2.3.4 Population Dose PNPP's Annual Radioactive Effluent Release Reports, as required by Regulatory Guide 1.21, will include total population dose and average individual doses calculated for radioactive effluent releases. The total population dose and average individual doses will be calculated using average individual transit times and usage factors, Table 2.3-12, (as compared to maximum exposed individual factors used for individual doses). The total population dose will be calculated by dose pathway and organ, with pathway doses being corrected for the fraction of the population assumed to be in each age group (adult, teen, child and infant: 0.71, 0.11, 0.18, 0.0 respectively).
ODCM Page: 15 Rev.: 9 Table 2.3-1 Organs Used for Liquid Effluent Dose Calculations
- 1. Bone
- 2. GI Tract
- 3. Kidney
- 4. Liver
- 5. Lung
- 6. Thyroid
- 7. Whole Body
- 8. Skin Table 2.3-2 Age Groups Used for Liquid Effluent Dose Calculations
- 1. Adult (17 yrs. and older)
- 2. Teen (11 - 17 yrs)
- 3. Child (1 - 11 yrs)
- 4. Infant (0 - 1 yr)
Table 2.3-3 Liquid Effluent Dose Pathways
- 1. Water Ingestion
- 2. Shore Exposure
- 3. Fresh Water Fish Ingestion
ODCM Page: 16 Rev.: 9 Table 2.3-4 Bio-Accumulation Factors (B.-) (pCi/kg per pCi/liter)
Element Fish H 9.OE-Ol C 4. GE+03 Na 1.OE+02 P 1. OE+05 Cr 2.OE+02 Mn 4 . OE+02 Fe 1. OE+02 Co 5.OE+Ol Ni 1.OE+02 Cu 5.OE+Ol Zn 2.OE+03 Br 4 .2E+02 Rb 2.OE+03 Sr 3.OE+Ol y 2.5E+Ol Zr 3.3E+OO Nb 3. OE+04 Mo 1. OE+Ol Tc 1.5E+Ol Ru 1. OE+Ol Rh 1.OE+Ol Sb 1.OE+OO Te 4. OE+02 I 1.5E+Ol Cs 2.OE+03 Ba 4. OE+OO La 2.5E+Ol Ce 1.OE+Oo Pr 2.5E+Ol Nd 2.5E+Ol w 1.2E+03 Au l.OE+OO Np 1. OE+Ol
ODCM Page: 17 Rev. g Table 2.3-5 Ingestion Dose Factors for Adult (mrem/pCi ingested)
WHOLE ISOTOPE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI H3 0.00E+00 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C14 2.84E-06 5.6SE-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 NA24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P32 1.93E-04 1.20E-05 7.46E-06 0.00E+00 0.00E+00 0.00E+00 2.17E-05 CR51 0.00E+00 0.00E+00 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 MN54 0.00E+00 4.57E-06 8.72E-07 0.00E+00 1.36E-06 0.00E+00 1.40E-05 MN56 0.00E+00 1.15E-07 2.04E-08 0.00E+00 1.46E-07 0.00E+00 3.67E-06 FE55 2.75E-06 1.90E-06 4.43E-07 0.00E+00 0.00E+00 1.06E-06 1.09E-06 FE59 4.34E-06 1.02E-05 3.91E-06 0.00E+00 0.00E+00 2.85E-06 3.40E-05 C058 0.00E+00 7.45E-07 1.67E-06 0.00E+00 0.00E+00 0.00E+00 1.51E-05 C060 0.00E+00 2.14E-06 4.72E-06 0.00E+00 0.00E+00 0.00E+00 4.02E-05 NI63 1.30E-04 9.01E-06 4.36E-06 0.00E+00 0.00E+00 0.00E+00 1.88E-06 NI65 5.28E-07 6.86E-08 3.13E-08 0.00E+00 0.00E+00 0.00E+00 1.74E-06 CU64 0.00E+00 8.33E-08 3.91E-08 0.00E+00 2.10E-07 0.00E+00 7.10E-06 CU67 2.95E-07 8.41E-07 0.00E+00 2.24E-07 2.62E-07 2.27E-07 1.07E-05 ZN65 4.84E-06 1.54E-05 6.96E-06 0.00E+00 1.03E-05 0.00E+00 s.70E-06 ZN69 1.03E-08 1.97E-08 1.37E-09 0.00E+00 1.28E-08 0.00E+00 2.96E-09 BR83 0.00E+00 0.00E+00 4.02E-08 0.00E+00 0.00E+00 0.00E+00 5.79E-08 BR84 0.00E+00 0.00E+00 5.21E-08 0.00E+00 0.00E+00 0.00E+00 4.09E-13 BR85 0.00E+00 0.00E+00 2.14E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB86 0.00E+00 2.11E-05 9.83E-06 0.00E+00 0.00E+00 0.00E+00 4.16E-06 RB88 0.00E+00 6.05E-08 3.21E-08 0.00E+00 0.00E+00 0.00E+00 8.36E-19 RB89 0.00E+00 4.01E-08 2.82E-08 0.00E+00 0.00E+00 0.00E+00 2.33E-21 SR87M 1.52E-08 1.77E-08 0.00E+00 2.96E-09 2.58E-08 6.92E-09 2.15E-07 SR89 3.08E-04 0.00E+00 8.84E-06 0.00E+00 0.00E+00 0.00E+00 4.s4E-05 SR90 7.58E-03 0.00E+00 1.86E-03 0.00E+00 0.00E+00 0.00E+00 2.19E-04 SR91 5.67E-06 0.00E+00 2.29E-07 0.00E+00 0.00E+00 0.00E+00 2.70E-05 SR92 2.15E-06 0.00E+00 9.30E-08 0.00E+00 0.00E+00 0.00E+00 4.26E-05 Y90 9.62E-09 0.00E+00 2.58E-10 0.00E+00 0.00E+00 0.00E+00 1.02E-04 Y9lM 9.09E-11 0.00E+00 3.52E-12 0.00E+00 0.00E+00 0.00E+00 2.67E-10 Y91 1.41E-07 0.00E+00 3.77E-09 0.00E+00 0.00E+00 0.00E+00 7.67E-05 Y92 8.45E-10 0.00E+00 2.47E-11 0.00E+00 0.00E+00 0.00E+00 1.48E-05 Y93 2.68E-09 0.00E+00 7.40E-11 0.00E+00 0.00E+00 0.00E+00 8.50E-05 ZR95 3.04E-08 9.75E-09 6.60E-09 0.00E+00 1.53E-08 0.00E+00 3.09E-05 ZR97 1.68E-09 3.39E-10 1.55E-10 0.00E+00 5.12E-10 0.00E+00 1.05E-04 NB95 6.22E-09 3.46E-09 1.86E-09 0.00E+00 3.42E-os 0.00E+00 2.10E-05 MO99 0.00E+00 4.31E-06 8.20E-07 0.00E+00 9.76E-06 0.00E+00 9.99E-06 TC99M 2.47E-10 6.98E-10 8.89E-09 0.00E+00 1.06E-08 3.42E-10 4.13E-07
ODCM Page: 18 Rev.: 9 Table 2.3-5 (Cont.)
Ingestion Dose Factors for Adult (mrem/pCi ingested)
WHOLE ISOTOPE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI TC101 2.54E-10 3.66E-10 3.59E-09 0.OOE+00 6.59E-09 1.87E-10 1.10E-21 RU103 1.85E-07 0.OOE+00 7.97E-08 0.OOE+00 7.06E-07 0.OOE+00 2.16E-05 RUlos 1.54E-08 0.OOE+00 6.08E-09 O.OOE+00 1.99E-07 0.OOE+00 9.42E-06 RU106 2.75E-06 0.OOE+00 3.48E-07 0.OOE+00 5.31E-06 O.OOE+00 1.78E-04 AGllOM 1.60E-07 1.48E-07 8.79E-08 0.OOE+00 2.91E-07 0.OOE+00 6.04E-05 TE125M 2.68E-06 9.17E-07 3.59E-07 8.06E-07 1.09E-05 O.OOE+00 1.07E-05 TE127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-0S 0.OOE+00 2.27E-05 TE127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 0.O0E+00 8.68E-06 TE129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 O.OOE+00 5.79E-05 TE129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 0.OOE+00 2.37E-08 TE131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 O.OOE+00 8.40E-05 TE131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 O.OOE+00 2.79E-09 TE132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 O.OOE+00 7.71E-05 I130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 0.OOE+00 1.92E-06 I131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 O.OOE+00 1.57E-06 I132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 0.OOE+00 1.02E-07 I133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 0.OOE+00 2.22E-06 I134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 0.OOE+00 2.51E-10 I135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 O.OOE+00 1.31E-06 CS134 6.22E-05 1.48E-04 1.21E-04 0.OOE+00 4.79E-05 1.59E-05 2.59E-06 CS136 6.51E-06 2.57E-05 1.85E-05 0.OOE+00 1.43E-05 1.96E-06 2.92E-06 CS137 7.97E-05 1.09E-04 7.14E-05 0.OOE+00 3.70E-05 1.23E-05 2.11E-06 CS138 5.52E-08 1.09E-07 5.40E-08 0.OOE+00 8.01E-08 7.91E-09 4.65E-13 BA139 9.70E-08 6.91E-11 2.84E-09 0.OOE+00 6.46E-11 3.92E-11 1.72E-07 BA140 2.03E-05 2.55E-08 1.33E-06 0.00E+00 8.67E-09 1.46E-08 4.18E-05 BA141 4.71E-08 3.56E-11 1.59E-09 0.OOE+00 3.31E-11 2.02E-11 2.22E-17 BA142 2.13E-08 2.19E-11 1.34E-09 0.OOE+00 1.85E-11 1.24E-11 3.OOE-26 LA140 2.50E-09 1.26E-09 3.33E-10 0.OOE+00 O.OOE+00 0.OOE+00 9.25E-05 LA142 1.28E-10 5.82E-11 1.45E-11 O.OOE+00 0.OOE+00 0.OOE+00 4.25E-07 CE141 9.36E-09 6.33E-09 7.18E-10 0.OOE+00 2.94E-09 0.OOE+00 2.42E-05 CE143 1.65E-09 1.22E-06 1.35E-10 O.OOE+00 5.37E-10 0.OOE+00 4.56E-05 CE144 4.88E-07 2.04E-07 2.62E-08 0.OOE+00 1.21E-07 0.OOE+00 1.6SE-04 PR143 9.20E-09 3.69E-09 4.56E-10 0.OOE+00 2.13E-09 0.OOE+00 4.03E-05 PR144 3.01E-11 1.25E-11 1.53E-12 0.OOE+00 7.05E-12 0.00E+00 4.33E-18 ND147 6.29E-09 7.27E-09 4.35E-10 0.00E+00 4.25E-09 0.OOE+00 3.49E-05 W187 1.03E-07 8.61E-08 3.01E-08 0.OOE+00 0.OOE+00 0.OOE+00 2.82E-05 NP239 1.19E-09 1.17E-10 6.45E-11 0.OOE+00 3.65E-10 O.OOE+00 2.40E-05 AU199 0.OOE+00 7.OOE-08 5.89E-08 0.OOE+00 2.74E-07 O.OOE+00 1.13E-05 SB124 2.80E-06 5.29E-08 1.11E-06 6.79E-09 O.OOE+00 2.18E-06 7.95E-05 SB125 1.79E-06 2.OOE-08 4.26E-07 1.82E-09 O.OOE+00 1.38E-06 1.97E-05
ODCM Page: 19 Rev. : 9 Table 2.3-6 Ingestion Dose Factors for Teenager (mrem/pCi ingested)
WHOLE ISOTOPE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI H3 0.00E+00 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C14 4.06E-06 8.12E-07 8,12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 NA24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P32 2.76E-04 1.71E-05 1.07E-05 0.00E+00 0.00E+00 0.00E+00 2.32E-05 CR51 0.00E+00 0.00E+00 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 MN54 0.00E+00 5.90E-06 1.17E-06 0.00E+00 1.76E-06 0.00E+00 1.21E-05 MN56 0.00E+00 1.58E-07 2.81E-08 0.00E+00 2.00E-07 0.00E+00 1.04E-05 FE55 3.78E-06 2.68E-06 6.25E-07 0.00E+00 0.00E+00 1.70E-06 1.16E-06 FE59 5.87E-06 1.37E-05 5.29E-06 0.00E+00 0.00E+00 4.32E-06 3.24E-05 C058 0.00E+00 9.72E-07 2.24E-06 0.00E+00 0.00E+00 0.00E+00 1.34E-05 C060 0.00E+00 2.81E-06 6.33E-06 0.00E+00 0.00E+00 0.00E+00 3.66E-05 NI63 1.77E-04 1.25E-05 6.00E-06 0.00E+00 0.00E+00 0.00E+00 l.99E-06 NI65 7.49E-07 9.57E-08 4.36E-08 0.00E+00 0.00E+00 0.00E+00 5.19E-06 CU67 3.54E-07 1.07E-06 0.00E+00 2.74E-07 3.19E-7 2.81E-07 1.32E-05 CU64 0.00E+00 1.15E-07 5.41E-08 0.00E+00 2.91E-07 0.00E+00 8.92E-06 ZN65 5.76E-06 2.00E-05 9.33E-06 0.00E+00 1.28E-05 0.00E+00 8.47E-06 ZN69 1.47E-08 2.80E-08 1.96E-09 0.00E+00 1.83E-08 0.00E+00 5.16E-08 BR83 0.00E+00 0.00E+00 5.74E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR84 0.00E+00 0.00E+00 7.22E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR85 0.00E+00 0.00E+00 3.05E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB86 0.00E+00 2.98E-05 1.40E-05 0.00E+00 0.00E+00 0.00E+00 4.41E-06 RB88 0.00E+00 8.52E-08 4.54E-08 0.00E+00 0.00E+00 0.00E+00 7.30E-15 RB89 0.00E+00 5.50E-08 3.89E-08 0.00E+00 0.00E+00 0.00E+00 8.43E-17 SR87M 2.81E-8 2.18E-08 0.00E+00 4.40E-9 3.00E-08 9.91E-09 2.42E-07 SR89 4.40E-04 0.00E+00 1.26E-05 0.00E+00 0.00E+00 0.00E+00 5.24E-05 SR90 8.30E-03 0.00E+00 2.05E-03 0.00E+00 0.00E+00 0.00E+00 2.33E-04 SR91 8.07E-06 0.00E+00 3.21E-07 0.00E+00 0.00E+00 0.00E+00 3.66E-05 SR92 3.05E-06 0.00E+00 1.30E-07 0.00E+00 0.00E+00 0.00E+00 7.77E-05 Y90 1.37E-08 0.00E+00 3.69E-10 0.00E+00 0.00E+00 0.00E+00 1.13E-04 Y9lM 1.29E-10 0.00E+00 4.93E-12 0.00E+00 0.00E+00 0.00E+00 6.09E-09 Y91 2.01E-07 0.00E+00 5.39E-09 0.00E+00 0.00E+00 0.00E+00 8.24E-05 Y92 1.21E-09 0.00E+00 3.50E-11 0.00E+00 0.00E+00 0.00E+00 3.32E-05 Y93 3.83E-09 0.00E+00 1.05E-10 0.00E+00 0.00E+00 0.00E+00 1.17E-04 ZR95 4.12E-08 1.30E-08 8.94E-09 0.00E+00 l.91E-08 0.00E+00 3.00E-05 ZR97 2.37E-09 4.69E-10 2.16E-10 0.00E+00 7.11E-10 0.00E+00 1.27E-04 NB95 8.22E-09 4.56E-09 2.51E-09 0.00E+00 4.42E-09 0.00E+00 1.95E-05 MO99 0.00E+00 6.03E-06 1.15E-06 0.00E+00 1.38E-05 0.00E+00 1.08E-05 TC99M 3.32E-10 9.26E-10 1.20E-08 0.00E+00 1.38E-08 5.14E-10 6.08E-07
ODCM Page: 20 Rev.: 9 Table 2.3-6 (Cont.)
Ingestion Dose Factors for Teenager (mrem/pCi ingested)
WHOLE ISOTOPE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI TC101 3.60E-10 5.12E-10 5.03E-09 0.OOE+00 9.26E-09 3.12E-10 8.75E-17 RU103 2.55E-07 0.OOE+00 1.09E-07 0.O0E+00 8. 99E-07 0.OOE+00 2.13E-05 RU105 2.18E-08 0.OOE+00 8 .46E-09 0.OOE+00 2.75E-07 0.OOE+00 1.76E-05 RU106 3.92E-06 0.OOE+00 4.94E-07 0.00E+00 7.56E-06 0.OOE+00 1.88E-04 AGllOM 2.05E-07 1.94E-07 1.18E-07 0.00E+00 3.70E-07 0.OOE+00 5.45E-05 TE125M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 0.00E+00 0.OOE+00 1.13E-05 TE127M 9.67E-06 3.43E-06 1.15E-06 2.30QE-06 3.92E-05 0.OOE+00 2.41E-05 TE127 1.58E-07 5.60E-08 3 .40E-08 1.09E-07 6.40E-07 0.OOE+00 1.22E-05 TE129M 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 0.OOE+00 6.12E-05 TE129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 0.OOE+00 2.45E-07 TE131M 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 O.OOE+00 9.39E-05 TE131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 0.OOE+00 2.29E-09 TE132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 0.OOE+00 7.0OE-05 1130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 0.OOE+00 2.29E-06 I131 5.85E-06 8.19E-06 4 .40E-06 2.39E-03 1.41E-05 0.OOE+00 1.62E-06 I132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 0.OOE+00 3.18E-07 I133 2.01E-06 3.41E-06 1.04E-06 4 .76E-04 5.98E-06 0.0OE+00 2.58E-06 I134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 0.0OE+00 5.10E-09 I135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2 .48E-06 0.OOE+00 1.74E-06 CS134 8.37E-05 1.97E-04 9.14E-05 0.OOE+00 6.26E-05 2.39E-05 2.45E-06 CS136 8.59E-06 3.38E-05 2.27E-05 0.OOE+00 1.84E-05 2.90E-06 2.72E-06 CS137 1.12E-04 1.49E-04 5.19E-05 0. 00E+00 5.07E-05 1.97E-05 2.12E-06 CS138 7.76E-08 1.49E-07 7.45E-08 0.OOE+00 1.10E-07 1.28E-08 6.76E-11 BA139 1.39E-07 9.78E-11 4.05E-09 0.00E+00 9.22E-11 6.74E-11 1.24E-06 BA140 2.84E-05 3.48E-08 1.83E-06 0.00E+00 1.18E-08 2.34E-08 4. 38E-05 BA141 6.71E-08 5.01E-11 2.24E-09 0.OOE+00 4.65E-11 3.43E-11 1.43E-13 BA142 2.99E-08 2.99E-11 1.84E-09 0.00E+00 2.53E-11 1.99E-11 9.18E-20 LA140 3.48E-09 1.71E-09 4.55E-10 0.OOE+00 0.00E+00 0.OOE+00 9.82E-05 LA142 1.79E-10 7.95E-11 1.98E-ll 0.OOE+00 O.00E+00 0.OOE+00 2.42E-06 CE141 1.33E-08 8.88E-09 1.02E-09 0.OOE+00 4.18E-09 0.OOE+00 2.54E-05 CE143 2.35E-09 1.71E-06 1.91E-10 0.OOE+00 7.67E-10 0.OOE+00 5.14E-05 CE144 6.96E-07 2.88E-07 3.74E-08 0.00E+00 1.72E-07 0.OOE+00 1.75E-04 PR143 1.31E-08 5.23E-09 6.52E-10 0.OOE+00 3.04E-09 0.OOE+00 4.31E-05 PR144 4.30E-11 1.76E-11 2.18E-12 0.00E+00 1.01E-11 0.OOE+00 4.74E-14 ND147 9.38E-09 1.02E-08 6.11E-10 0.00E+00 5.99E-09 0.OOE+00 3.68E-05 W187 1.46E-07 1.19E-07 4.17E-08 0.OOE+O0 0.OOE+00 0.OOE+00 3.22E-05 NP239 1.76E-09 1.66E-10 9.22E-11 0.OOE+00 5.21E-10 0.OOE+00 2.67E-05 AUl99 0.OOE+00 9.92E-08 8.41E-08 0. 00E+00 3.92E-07 O.OOE+00 1.17E-05 SB124 3.87E-06 7.13E-08 1.51E-06 8.78E-09 0.00E+00 3.38E-06 7.80E-05 SB125 2.48E-06 2.71E-08 5.80E-07 2.37E-09 0.OOE+00 2.18E-06 1.93E-05
ODCM Page: 21 Rev.: 9 Table 2.3-7 Ingestion Dose Factors for Child (mrem/pCi ingested)
WHOLE ISOTOPE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI H3 O.OOE+00 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 NA24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P32 8.25E-04 3.86E-05 3.18E-05 O.00E+00 O.OOE+00 O.OOE+00 2.28E-05 CR51 O.OOE+00 O.OOE+00 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 MN54 O.OOE+00 1.07E-05 2.85E-06 O.OOE+00 3.OOE-06 O.OOE+00 8.98E-06 MN56 O.OOE+00 3.34E-07 7.54E-08 O.OOE+00 4.04E-07 O.OOE+00 4.84E-05 FES5 1.15E-05 6.10E-06 1.89E-06 O.OOE+00 O.OOE+00 3.45E-06 1.13E-06 FE59 1.65E-05 2.67E-05 1.33E-05 O.OOE+00 O.OOE+00 7.74E-06 2.78E-05 C058 O.OOE+00 1.80E-06 5.51E-06 O.OOE+00 O.OOE+00 O.OOE+00 1.05E-05 C060 O.OOE+00 5.29E-06 1.56E-05 O.OOE+00 O.OOE+00 O.OOE+00 2.93E-05 NI63 5.38E-04 2.88E-05 1.83E-05 O.OOE+00 O.OOE+00 O.OOE+00 1.94E-06 NI65 2.22E-06 2.09E-07 1.22E-07 O.OOE+00 O.OOE+00 O.OOE+00 2.56E-05 CU67 9.21E-07 2.52E-06 O.OOE+00 7.83E-07 8.74E-07 7.81E-07 3.89E-05 CU64 O.OOE+00 2.45E-07 1.48E-07 O.OOE+00 5.92E-07 O.OOE+00 1.15E-05 ZN65 1.37E-05 3.65E-05 2.27E-05 O.OOE+00 2.30E-05 O.OOE+00 6.41E-06 ZN69 4.38E-08 6.33E-08 5.85E-09 O.OOE+00 3.84E-08 O.OOE+00 3.99E-06 BR83 O.OOE+00 O.OOE+00 1.71E-07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 BR84 O.OOE+00 O.OOE+00 1.98E-07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 BR85 O.OOE+00 O.OOE+00 9.12E-09 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 RB86 O.OOE+00 6.70E-05 4.12E-05 O.OOE+00 O.OOE+00 O.OOE+00 4.31E-06 RB88 O.OOE+00 1.90E-07 1.32E-07 O.OOE+00 O.OOE+00 O.O0E+00 9.32E-09 RB89 O.OOE+00 1.17E-07 1.04E-07 O.OOE+00 O.OOE+00 O.OOE+00 1.02E-09 SR87M 5.47E-08 6.78E-08 O.OOE+00 1.34E-08 6.65E-08 2.57E-08 6.66E-07 SR89 1.32E-03 O.OOE+00 3.77E-05 O.OOE+00 O.OOE+00 O.OOE+00 5.11E-05 SR90 1.70E-02 O.OOE+00 4.31E-03 O.O0E+00 O.OOE+OO O.OOE+00 2.29E-04 SR91 2.40E-05 O.OOE+00 9.06E-07 O.O0E+00 0.00E+00 O.OOE+00 5.30E-05 SR92 9.03E-06 0.00E+00 3.62E-07 0.00E+00 0.00E+00 0.OOE+00 1.71E-04 Y90 4.11E-08 0.00E+00 1.10E-09 0.00E+00 0.00E+00 0.00E+00 1.17E-04 Y91M 3.82E-10 0.OOE+00 1.39E-11 0.00E+00 0.00E+00 0.00E+00 7.48E-07 Y91 6.02E-07 0.00E+00 1.61E-08 0.00E+00 0.00E+00 0.OOE+00 8.02E-05 Y92 3.60E-09 0.00E+00 1.03E-10 0.00E+00 0.00E+00 0.00E+00 1.04E-04 Y93 1.14E-08 0.OOE+00 3.13E-10 0.00E+00 0.OOE+00 0.00E+00 1.70E-04 ZR95 1.16E-07 2.55E-08 2.27E-08 0.00E+00 3.65E-08 0.00E+00 2.66E-05 ZR97 6.99E-09 1.01E-09 5.96E-10 0.00E+00 1.45E-09 0.00E+00 1.53E-04 NB95 2.25E-08 8.76E-09 6.26E-09 0.00E+00 8.23E-09 0.OOE+00 1.62E-05 M099 0.00E+00 1.33E-05 3.29E-06 0.00E+00 2.84E-05 0.00E+00 1.10E-05 TC99M 9.23E-10 1.81E-09 3.00E-08 0.00E+00 2.63E-08 9.19E-10 1.03E-06
ODCM Page: 22 Rev.: 9 Table 2.3-7 (Cont.)
Ingestion Dose Factors for Child (mrem/pCi ingested)
WHOLE ISOTOPE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI TC101 1.07E-09 1.12E-09 1.42E-08 0.00E+00 1.91E-08 5.92E-10 3.56E-09 RU103 7.31E-07 0.OOE+00 2.81E-07 0.00E+00 1.84E-06 0.OOE+00 1.89E-05 RU105 6.45E-08 0.00E+00 2.34E-08 0.00E+00 5.67E-07 0.OOE+00 4.21E-05 RU106 1.17E-05 0.00E+00 1.46E-06 0.OOE+00 1.58E-05 0.OOE+00 1.82E-04 AGllOM 5.39E-07 3.64E-07 2.91E-07 0.OOE+00 6.78E-07 0.OOE+00 4.33E-05 TE125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 0.OOE+00 0.00E+00 1.10E-05 TE127M 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 0.00E+00 2.34E-05 TE127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 0.OOE+00 1.84E-05 TE129M 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 0.00E+00 5.94E-05 TE129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 0.00E+00 8.34E-06 TE131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 0.00E+00 1.01E-04 TE131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 0.00E+00 4.36E-07 TE132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 0.00E+00 4.50E-05 I130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 0.00E+00 2.76E-06 I131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 0.00E+00 1.54E-06 1132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0.00E+00 1.73E-06 I133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 0.OOE+00 2.95E-06 I134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 0.00E+00 5.16E-07 I135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 0.00E+00 2.40E-06 CS134 2.34E-04 3.84E-04 8.10E-05 0.00E+00 1.19E-04 4.27E-05 2.07E-06 CS136 2.35E-05 6.46E-05 4.18E-05 0.00E+00 3.44E-05 5.13E-06 2.27E-06 CS137 3.27E-04 3.13E-04 4.62E-05 0.00E+00 1.02E-04 3.67E-05 1.96E-06 CS138 2.28E-07 3.17E-07 2.01E-07 0.00E+00 2.23E-07 2.40E-08 1.46E-07 BA139 4.14E-07 2.21E-10 1.20E-08 0.00E+00 1.93E-10 1.30E-10 2.39E-05 BA140 8.31E-05 7.28E-08 4.85E-06 0.OOE+00 2.37E-08 4.34E-08 4.21E-05 BA141 2.OOE-07 1.12E-10 6.51E-09 0.00E+00 9.69E-11 6.58E-10 1.14E-07 BA142 8.74E-08 6.29E-11 4.88E-09 0.00E+00 5.09E-11 3.70E-11 1.14E-09 LA140 1.01E-08 3.53E-09 1.19E-09 0.00E+00 0.OOE+00 0.00E+00 9.84E-05 LA142 5.24E-10 1.67E-10 5.23E-11 0.00E+00 0.OOE+00 0.00E+00 3.31E-05 CE141 3.97E-08 1.98E-08 2.94E-09 0.00E+00 8.68E-09 0.00E+00 2.47E-05 CE143 6.99E-09 3.79E-06 5.49E-10 0.00E+00 1.59E-09 0.00E+00 5.55E-05 CE144 2.08E-06 6.52E-07 1.11E-07 0.00E+00 3.61E-07 0.00E+00 1.70E-04 PR143 3.93E-08 1.18E-08 1.95E-09 0.00E+00 6.39E-09 0.00E+00 4.24E-05 PR144 1.29E-10 3.99E-11 6.49E-12 0.00E+00 2.11E-11 0.00E+00 8.59E-08 ND147 2.79E-08 2.26E-08 1.75E-09 0.00E+00 1.24E-08 0.00E+00 3.58E-05 W187 4.29E-07 2.54E-07 1.14E-07 0.00E+00 0.00E+00 0.00E+00 3.57E-05 NP239 5.25E-09 3.77E-10 2.65E-10 0.00E+00 1.09E-09 0.00E+00 2.79E-05 AU199 0.00E+00 2.25E-07 2.51E-07 0.00E+00 8.23E-07 0.00E+00 1.27E-05 SB124 1.11E-05 1.44E-07 3.89E-06 2.45E-08 0.00E+00 6.16E-06 6.94E-05 SB125 7.16E-06 5.52E-08 1.50E-06 6.63E-09 0.00E+00 3.99E-06 1.71E-05
ODCM Page: 23 Rev. : 9 Table 2.3-8 Ingestion Dose Factors for Infant (mrem/pCi ingested)
WHOLE ISOTOPE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI H3 0.00E+00 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 C14 2.37E-OS 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 NA24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 P32 1.70E-03 1.00E-04 6.59E-05 0.00E+00 0.00E+00 0.00E+00 2.30E-05 CR51 0.00E+00 0.00E+00 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4 .113E-07 MN54 0.00E+00 l.99E-05 4.51E-06 0.00E+00 4.41E-06 0.00E+00 7.31E-06 MN56 0.00E+00 8.18E-07 1.41E-07 0.00E+00 7.03E-07 0.00E+00 7.43E-05 FE55 1.39E-05 B.98E-06 2.40E-06 0.00E+00 0.00E+00 4.39E-06 1.14E-06 FE59 3.08E-05 5.38E-05 2.12E-05 0.00E+00 0.00E+00 1.59E-05 2.57E-05 C058 0.00E+00 3.60E-06 8.98E-06 0.00E+00 0.00E+00 0.00E+00 8.97E-06 C060 0.00E+00 1.08E-05 2.55E-05 0.00E+00 0.00E+00 0.00E+00 2.57E-05 NI63 6.34E-04 3.92E-05 2.20E-05 0.00E+00 0.00E+00 0.00E+00 1.95E-06 NI65 4.70E-06 5.32E-07 2.42E-07 0.00E+00 0.00E+00 0.00E+00 4.05E-05 CU67 5.26E-06 1.42E-05 0.00E+00 4.93E-06 4.98E-06 4.87E-06 1.36E-05 CU64 0.00E+00 6.09E-07 2.82E-07 0.00E+00 1.03E-06 0.00E+00 1.25E-05 zN65 1.84E-05 6.31E-05 2.91E-05 0.00E+00 3.06E-05 0.00E+00 5.33E-05 ZN69 9.33E-08 1.68E-07 1.25E-08 0.00E+00 6.98E-08 0.00E+00 1.37E-05 BR83 0.00E+00 0.00E+00 3.63E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR84 0.00E+00 0.00E+00 3.82E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR85 0.00E+00 0.00E+00 1.94E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB86 0.00E+00 1.70E-04 8.40E-05 0.00E+00 0.00E+00 0.00E+00 4.35E-06 RB88 0.00E+00 4.98E-07 2.73E-07 0.00E+00 0.00E+00 0.00E+00 4.85E-07 RB89 0.00E+00 2.86E-07 1.97E-07 0.00E+00 0.00E+00 0.00E+00 9.74E-08 SR87M 2.22E-07 1.56E-07 0.00E+00 4.70E-08 1.37E-07 7.71E-08 1.49E-06 SR89 2.51E-03 0.00E+00 7.20E-05 0.00E+00 0.00E+00 0.00E+00 5.16E-05 SR90 1.85E-02 0.00E+00 4.71E-03 0.00E+00 0.00E+00 0.00E+00 2.31E-04 SR91 5.00E-05 0.00E+00 1.81E-06 0.00E+00 0.00E+00 0.00E+00 5.92E-05 SR92 1.92E-05 0.00E+00 7.13E-07 0.00E+00 0.00E+00 0.00E+00 2.07E-04 Y90 8.69E-08 0.00E+00 2.33E-09 0.00E+00 0.00E+00 0.00E+00 1.20E-04 Y9lM 8.10E-10 0.00E+00 2.76E-11 0.00E+00 0.00E+00 0.00E+00 2.70E-06 Y91 1.13E-06 0.00E+00 3.01E-08 0.00E+00 0.00E+00 0.00E+00 8.10E-05 Y92 7.65E-09 0.00E+00 2.15E-10 0.00E+00 0.00E+00 0.00E+00 1.46E-04 Y93 2.43E-08 0.00E+00 6.62E-10 0.00E+00 0.00E+00 0.00E+00 1.92E-04 ZR95 2.06E-07 5.02E-08 3.56E-08 0.00E+00 5.41E-08 0.00E+00 2.50E-05 ZR97 1.48E-08 2.54E-09 1.16E-09 0.00E+00 2.56E-09 0.00E+00 1.62E-04 NB95 4.20E-08 1.73E-08 1.00E-08 0.00E+00 1.24E-08 0.00E+00 1.46E-05 MO99 0.00E+00 3.40E-05 6.63E-06 0.00E+00 5.08E-05 0.00E+00 1.12E-05 TC99M 1.92E-09 3.96E-09 5.10E-08 0.00E+00 4.26E-08 2.07E-09 1.15E-06
ODCM Page: 24 Rev.: 9 Table 2.3-8 (Cont.)
Ingestion Dose Factors for Infant (mrem/pCi ingested)
WHOLE ISOTOPE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI TC101 2.27E-09 2.86E-09 2.83E-08 O.OOE+O0 3.40E-08 1.56E-09 4.86E-07 RU103 1.48E-06 O.OOE+O0 4.95E-07 O.OOE+00 3.08E-06 O.OOE+00 1.80E-05 RU105 1.36E-07 O.OOE+00 4.58E-08 O.OOE+00 1.OOE-06 O.OOE+00 5.41E-05 RU106 2.41E-05 O.OOE+00 3.01E-06 O.OOE+00 2.85E-05 O.OOE+O0 1.83E-04 AGllOM 9.96E-07 7.27E-07 4.81E-07 O.OOE+00 1.04E-06 O.OOE+00 3.77E-05 TE125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 O.OOE+00 O.OOE+00 1.11E-05 TE127M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 O.OOE+00 2.36E-05 TE127 1.OOE-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 O.OOE+00 2.10E-05 TE129M 1.OOE-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 O.OOE+00 5.97E-O5 TE129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 O.OOE+00 2.27E-05 TE131M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 O.OOE+00 1.03E-04 TE131 1.76E-07 6.50E-08 4.94E-08 1.S7E-07 4.50E-07 o.OOE+00 7.11E-06 TE132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 O.OOE+00 3.81E-05 I130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 O.OOE+00 2.83E-06 I131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 O.OOE+00 1.51E-06 I132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 O.OOE+00 2.73E-06 I133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 O.OOE+00 3.08E-06 I134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 O.OOE+00 1.84E-06 I135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 O.OOE+00 2.62E-06 CS134 3.77E-04 7.03E-04 7.10E-05 O.OOE+00 1.81E-04 7.42E-05 1.91E-06 CS136 4.59E-05 1.35E-04 5.04E-05 O.OOE+00 5.38E-05 1.1OE-05 2.05E-06 CS137 5.22E-04 6.11E-04 4.33E-05 O.OOE+00 1.64E-04 6.64E-05 1.91E-06 CS138 4.81E-07 7.82E-07 3.79E-07 O.OOE+00 3.90E-07 6.09E-08 1.25E-06 BA139 8.81E-07 5.84E-10 2.55E-08 O.OOE+00 3.51E-10 3.54E-10 5.58E-05 BA140 1.71E-04 1.71E-07 8.81E-06 O.OOE+00 4.06E-08 1.05E-07 4.20E-05 BA141 4.25E-07 2.91E-10 1.34E-08 o.OOE+00 1.75E-10 1.77E-10 5.19E-06 BA142 1.84E-07 1.53E-10 9.06E-09 O.OOE+00 8.81E-11 9.26E-11 7.59E-07 LA140 2.11E-08 8.32E-09 2.14E-09 O.OOE+00 O.OOE+00 O.OOE+00 9.77E-05 LA142 1.10E-09 4.04E-10 9.67E-11 O.OOE+00 O.OOE+00 O.OOE+00 6.86E-05 CE141 7.87E-08 4.80E-08 5.65E-09 O.OOE+00 1.48E-08 O.OOE+00 2.48E-05 CE143 1.48E-08 9.82E-06 1.12E-09 O.OOE+00 2.86E-09 O.OOE+00 5.73E-05 CE144 2.98E-06 1.22E-06 1.67E-07 O.OOE+00 4.93E-07 O.OOE+00 1.71E-04 PR143 8.13E-08 3.04E-08 4.03E-09 O.OOE+00 1.13E-08 O.OOE+00 4.29E-05 PR144 2.74E-10 1.06E-10 1.38E-11 O.OOE+00 3.84E-11 O.OOE+00 4.93E-06 ND147 5.53E-08 5.68E-08 3.48E-09 O.OOE+00 2.19E-08 O.OOE+00 3.60E-05 W187 9.03E-07 6.28E-07 2.17E-07 O.OOE+00 O.OOE+00 O.OOE+00 3.69E-05 NP239 1.11E-08 9.93E-10 5.61E-10 O.OOE+00 1.98E-09 O.OOE+00 2.87E-05 AU199 O.OOE+00 5.91E-07 5.32E-07 O.OOE+00 1.49E-06 O.OOE+00 1.28E-05 SB124 2.14E-05 3.15E-07 6.63E-06 5.08E-08 O.OOE+00 1.34E-05 6.60E-05 SB12S 1.23E-05 1.19E-07 2.53E-06 1.54E-08 O.OOE+00 7.72E-06 1.64E-05
ODCM Page: 25 Rev.: 9 Table 2.3-9 External Dose Factors for Standing on Contaminated Ground (mrem/h per pCi/m 2 )
Element Whole Body Skin H-3 0.0 0.0 C-14 0.0 0.0 NA-24 2.50E-08 2.90E-08 P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 l.10E-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.OOE-09 9.40E-09 Co-58 7.0OE-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Ni-63 0.0 0 .0 Nr-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Cu-67 1.40E-09 2.14E-9 Zn-65 4.OOE-09 4.60E-09 Zn-69 0.0 0.0 Br-83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0 Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.OOE-09 Rb-89 1.50E-08 1.80E-08 Sr-87M 4.05E-09 5.36E-09 Sr-89 5.60E-13 6.50E-13 Sr-91 7.1OE-09 8.30E-09 Sr-92 9.00E-09 l.OOE-08 Y-90 2.20E-12 2.60E-12 Y-91M 3.80E-09 4 .40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.OOE-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Mo-95 5.10E-09 6.OOE-09 Mo-99 l.90E-09 2.20E-09 Tc-99M 9.60E-10 1.1OE-09 Tc-101 2.70E-09 3.00E-09 Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1.5OE-09 1.80E-09
ODCM Page: 26 Rev.: 9 Table 2.3-9 (Cont.)
External Dose Factors for Standing on Contaminated Ground 2
(mrem/h per pCi/m )
Element Whole Body Skin Ag-llOM 1.80E-08 2.10E-08 Te-125M 3.50E-11 4.80E-l1 Te-127M 1.lOE-12 1.30E-12 Te-127 l.OOE-11 l.1OE-ll Te-129M 7.70E-10 9.OOE-10 Te-129 7.10E-10 8.40E-10 Te-131M 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.OOE-09 Sb-124 2.28E-08 6.93E-08 Sb-125 5.67E-09 7.96E-09 1-130 1.40E-08 1.70E-08 I-131 2.80E-09 3.40E-09 I-132 1.70E-08 2.OOE-08 I-133 3.70E-09 4.50E-09 I-134 1.60E-08 1.90E-08 I-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.OOE-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 Nd-147 l.OOE-09 1.20E-09 W-187 3.10E-09 3.60E-09 Au-199 1.13E-9 1.39E-09 Np-239 9.50E-10 l.lOE-09
ODCM Page: 27 Rev.: 9 Table 2.3-10 Liquid Effluent Dilution Factors (MD)
Maximum Individual Dilution Factors Pathwa!y Location Mp Potable Water Ingestion 3.9 mile WSW of site 32.2 Fresh Water Fish Ingestion Near Discharge Structure 10.9 Shoreline Exposure 0.7 mile ENE of Site 14 .5 Population Dose Dilution Factors Pathway Location MP Potable Water Ingestion Population Weighted Average 314 Fresh Water Fish Ingestion Catch Weighted Average 77.4 Shoreline Exposure 7.7 mile WSW of site 162 Table 2.3-11 Transit Times Required for Nuclides to Reach the Point of Exposure (tD)
Maximum Average Exposed Exposed Individual Individual*
Eventual transit time for water ingestion 12 h 24 h Eventual transit time for fish ingestion 24 h 168 h Eventual transit time for shore exposure 0 h 0 h
- for total population and average individual dose calculations
ODCM Page: 28 Rev.: 9 Table 2.3-12 Usage Factors (Uap)
Maximum Average Exposed Exposed Individual Individual*
Water ingestion (L/yr) Adult 730 370 Water ingestion (L/yr) Teen 510 260 Water ingestion (L/yr) Child 510 260 Water ingestion (L/yr) Infant 330 Fresh water fish ingestion (kg/yr) Adult 21 6.9 Fresh water fish ingestion (kg/yr) Teen 16 5.2 Fresh water fish ingestion (kg/yr) Child 6.9 2.2 Fresh water fish ingestion (kg/yr) Infant --
Shore exposure (h/yr) Adult 12 8.3 Shore exposure (h/yr) Teen 67 47 Shore exposure (h/yr) Child 14 9.5 Shore exposure (h/yr) Infant --
- for total population and average individual dose calculations
ODCM Page: 29 Rev.: 9 Table 2.3-13 Dilution Factors for Each of the Potable Water Intakes within 50 Miles of PNPP The total population dilution factor of 314 is population weighted using dilution factors for each of the potable water intakes within 50 miles of PNPP.
Weighted Dist. Fraction of Dilution Dilution Intake (Mi) Dir Population Population Factor Factor Ohio American Water Serv. Co. 20 ENE 38,500 2.12E-2 187.7 3.98E+00 Conneaut 33 ENE 13,500 7.43E-03 238.2 1.77E+00 Avon Lake 50 WSW 99, 500 5.48E-02 388.5 2.13E+01 Cleveland 35 SW 1,437,000 7.92E-01 326.7 2.59E+02 Fairport Harbor 7 WSW 3,200 1.76E-03 154.2 2.71E-01 Lake County East 3.5 WSW 10,258 5.65E-03 107.4 6.07E-01 Lake County West 15 WSW 85,000 4.68E-02 220.0 1.03E+01 Ohio Water Serv. 10 WSW 60,000 3.30E-02 181.9 6.OOE+00 Painesville 7.5 WSW 27,000 1.49E-02 159.3 2.37E+00 Kent County Water Supply 50 NW 42,000 2.31E-2102 388.5 8.97E+00 TOTALS 1,815,958 1.00E+0 TOTAL DF 3.14E+02 Dist, Dir Population = distance, direction, and population values obtained from the 1989 Engineering Report "Lake Erie Potable Water Facilities and Intakes within 50 Miles of PNPP" (Ref. SO-11552 "E").
Fraction of Population = The ratio of the population receiving drinking water from that intake to the total population number for all drinking water intakes located within 50 miles of PNPP.
Dilution Factor = Values obtained from the Perry Environmental Report -
Operating License Stage, Table 5.1-10 "Annual Average Dilution Factors for Lake Water Intakes within 50 Miles of PNPP" and Q&R Page 2.1-2. Lake County West dilution factor per interpolation. Kent County Water Supply dilution factor was estimated.
The Weighted Dilution Factor = (Fraction of Population) x (Dilution Factor),
based on the population for each drinking water intake; the sum of which is to be used as the potable water total population dilution factor for radioactive liquid effluent releases from PNPP.
ODCM Page: 30 Rev.: 9 Table 2.3-14 Dilution Factors for the Fish Ingestion Pathway Individual Grid Locations The total population dilution factor of 77.4 is catch distance and volume weighted using dilution factors at those locations. Fish harvest is based on Ohio Department of Natural Resources the total angler catch (1987 annual) values for Lake Erie within 50 mile of PNPP.
Grid No. of Fraction Distance Dilution (Frac Fish)x Fish of Fish (mi) Factor (Dil Factor) 617 52823 3.91E-02 29 92 3.60E+00 618 76004 5.63E-02 36 100 5.63E+00 714 102522 7.59E-02 9 52 3.96E+00 715 10743 7.95E-03 9 52 4.13E-01 716 19817 1.47E-02 11 56 8.21E-01 717 73401 5.43E-02 24 83 4.51E+00 718 118676 8.78E-02 33 95 8.34E+00 809 0 0.OOE+00 48 115 0.OOE+00 810 3953 2.93E-03 39 105 3.07E-01 811 13648 1.01E-02 30 92 9.29E-01 812 33923 2.51E-02 22 78 1.96E+00 813 182663 1.35E-01 13 61 8.25E+00 814 164369 1.22E-01 4 34 4.14E+00 909 80753 5.98E-02 50 116 6.93E+00 910 43800 3.24E-02 42 110 3.57E+00 911 117430 8.69E-02 33 95 8.26E+00 912 256529 1.90E-01 24 83 1.58E+0l TOTAL 1351054 1.00E+00 TOTAL D.F. 7.74E+01 Grid No. and No. of Fish = Total angler catch (1987 annual) for each grid location; per letter from Michael R. Rawson, Fairport Fisheries Research Station, Ohio Department of Natural Resources to Richard Cochnar (6/20/88).
Commercial harvest data were not used as they were differentiated by harbor location only, not by geographical grid location.
Fraction of Fish = The ratio of the fish caught in that grid to the total number of fish caught in all grids located within 50 miles of PNPP.
Distance = Distance to the center of that grid from PNPP, in miles.
Dilution Factor = Derived, for the appropriate distance (center of each grid),
from annual average dilution factor data (non-adjusted), per Perry Environmental Report - Operating License Stage, Table 5.1-10 "Annual Average Dilution Factors for Lake Water Intakes within 50 Miles of PNPP.2 (Fraction of Fish) x (Dilution Factor) = The weighted dilution factor, based on catch, for each grid; the sum of which is to be used as the fish ingestion total population dilution factor for radioactive liquid effluent releases from PNPP.
ODCM Page: 31 Rev.: 9 Table 2.3-15 Dilution Factors for the Shore Exposure Pathway MAXIMUM EXPOSED INDIVIDUAL DILUTION FACTOR The point of exposure assumed for this pathway is the shoreline at the PNPP site boundary 0.7 miles down shore from the plant discharge structure.
Interpolation of the data presented in the Perry Environmental Report -
Operating License Stage, Table 5.1-10, "Annual Average Dilution Factors for Lake Water Intakes within 50 Miles of PNPP" yields a maximum individual dose dilution factor of 14.5 (dilution factor unadjusted for current frequency).
TOTAL POPULATION DILUTION FACTOR The total population dilution factor of 162 is that of the Headlands Beach State Park, 7.7 miles WSW of PNPP (interpolated, adjusted WSW dilution factor). This location was selected because of its lake site location and it has, by far, the highest attendance of any park located in vicinity of PNPP (Perry Environmental Report - Operating License State, Table 2.1-2 "Major Camps and Parks within 10 Miles of the PNPP").
ODCM Page: 32 Rev.: 9 3.0 GASEOUS EFFLUENTS 3.0.1 Batch Releases A batch release is the discontinuous discharge of gaseous radioactive effluents of known radionuclide concentration(s) and flowrate taking place over a finite period of time, usually hours or days. A batch release to the environment may occur as a result of an effluent flowpath that bypasses treatment or monitoring. Since radioactive releases approaching 10CFR20.106 limits are not anticipated, an ODCM Control is not entered for batch releases. Every reasonable effort will be made to maintain the levels of radioactive material in the gaseous effluents ALARA.
The radioactive gaseous effluent release flowpath is monitored for principal gamma emitters (noble gases, particulates, and halogens) as if the inoperable radioactive effluent monitor requirements of Table 3.3.7.10-1 had been entered. This action ensures the dose to a member of the general public is within the limits of Controls 3.11.2.2 and 3.11.2.3. If radioactivity is detected, the radionuclide concentration(s) is added to the dose calculations for the appropriate radioactive gaseous effluent continuous release point. Administrative instructions are employed to establish minimum monitoring requirements for these batch releases to ensure compliance with all regulatory requirements. The administrative instructions shall also ensure that the specific activity that will cause a batch release has been reviewed for the requirements of 10 CFR 50.59.
3.0.2 Continuous Releases There are four environmental release points for gaseous effluents used for Unit 1 operation of the Perry Nuclear Power Plant: Turbine Bldg/Heater Bay Vent, Off-Gas Vent, Unit 1 Vent, and Unit 2 Vent (see Figure 3.0-1). The Unit 1 and Unit 2 Vents are located on the top of the Intermediate Building, Elevation 753'9". The Turbine Bldg/Heater Bay Vent is located on the top of the Heater Bay Building, Elevation 722'0". The Off-Gas Vent is located on the top of the Off-Gas Building, Elevation 723'0". Site ground level elevation is 620'0'.
Radiological releases from each vent are monitored by a noble gas radiation monitor.
All gaseous effluent releases from PNPP via these vents will be continuous releases, and are considered to be long-term (i.e.,
greater than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per year) and ground level.
Containment/drywell purges and vents will be considered periods of increased radiological release as they are vented through the Unit 1 Vent, concurrent with normal, continuous releases.
ODCM Rev.: 9 Page: 33 Figure 3.0-1 Gaseous Effluent System Flow Diagram M w.
N_. Aff
_*-W yso_ IAm
_na _
r ~-. b=-"9-
-aL ,= L ; H[ _ -aa0
-. 0
, l, I) 3
ODCM Page: 34 Rev.: 9 3.1 Monitor Alarm Setpoint Determination The following calculation methods provide a means of determining the High Alarm Setpoint (HSP) and the Alert Setpoint (ASP) to ensure compliance with the regulatory dose rate limit to areas at or beyond the site boundary of 500 mrem/yr for the following noble gas monitors:
- 1. Unit 1 Vent radiation monitor (1D17K0786)
- 2. Unit 2 Vent radiation monitor (2D17K0786)
- 3. Off-Gas Vent radiation monitor (ID17K0836)
- 4. Turbine Building/Heater Bay Vent radiation monitor (ID17K0856)
The Unit 2 Vent radiation monitor is included for the operation of Unit 1 of the Perry Nuclear Power Plant because the second train of the Unit 1 Annulus Exhaust and the Control Complex and Intermediate Building ventilations are exhausted through the Unit 2 Vent.
The High Alarm Setpoint (HSP) for each release point radiation monitor will be set at 70% of the annual dose rate limit (350 mrem/yr) and the Alert Setpoint (ASP) will be at 10% of the annual dose rate limit (50 mrem/yr).
NOTE: These values are set as a small fraction of the total activity that may be released via the monitored pathways to ensure that the site boundary dose rate limits are not exceeded. Any single ASP can be exceeded without exceeding the 500 mrem/yr dose rate limit.
- a. Upon receipt of an alert alarm, a sample from the alarming effluent path will be obtained and analyzed. If two or more effluent monitors exceed the ASP, or if any one effluent monitor exceeds the HSP, the potential exists that the 500 mrem/yr dose rate limit may be exceeded. In this case, all four effluent paths will be sampled and analyzed, with the appropriate actions initiated to limit gaseous releases to below the annual dose rate limit.
- b. If a single HSP, or two or more ASPs continue to be exceeded, verification shall be made at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, via the gaseous effluent radiation monitors, that plant releases are below the ODCM Appendix C 3.11.2.1 dose rate limits. Sampling and analysis shall be performed on the four gaseous effluent release points at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
This procedure determines the monitor alarm setpoints that indicate if the dose rate beyond the site boundary due to noble gas radionuclides in gaseous effluent released from the site exceeds 500 mrem/year to the whole body, or 3000 mrem/year to the skin.
ODCM Page: 35 Rev.: 9 3.1.1 Determination of the "Mix" (Noble Gas Radionuclide Composition) of the Gaseous Effluent
- a. The gaseous source terms that are representative of the "mix" of the gaseous effluent are determined. Gaseous source terms are the concentrations of the noble gas radionuclides in the effluent as determined by analysis of the various sources of gaseous effluents. During the early period of plant operation, before a sufficient operational effluent source term data base has been obtained, source terms will be those generated by the GALE code, Revision 0 for PNPP (FSAR Tables 11.3-9 and 11.3-10).
- b. Determination of the fraction of the total radioactivity in the gaseous effluent for each noble gas radionuclide in the gaseous effluent.
Si = Ai (3.1-1)
X Ai Where:
Si = the fraction of the total for radionuclide "ia in the effluent; Ai = the activity of radionuclide "i" in the gaseous effluent.
NOTE: If the activity of a noble gas radionuclide is below the lower limit of detection the noble gas radionuclide is not included as a source term in this setpoint calculation.
3.1.2 Determination of the Maximum Acceptable Total Activity Release Rate of Noble Gas Radionuclides in Gaseous Effluent Based on Whole Body Dose Rate Limit 500
( x) 7 (Ki) (Si)
Where:
Qb = the maximum acceptable total activity release rate of all noble gas radionuclides in the effluent (for whole body exposure), pCi/s; Ki = the whole body dose factor for a semi-infinite cloud of radionuclide Ii" (includes 5g/cm2 tissue attenuation) from Table 3.1-1, (mrem/yr)/(pCi/m3 );
ODCM Page: 36 Rev.: 9 Si = the fraction of the total for radionuclide "i", as per equation 3.1.1; X/Q = the annual average dispersion factor in s/m3 (see Appendix A);
NOTE: The dispersion parameters (X/Q) used in these calculations are the highest calculated site boundary values for any of the land-based sectors only. At PNPP the site boundary locations in the following sectors are totally over water: N, NNE, NNW, NW, W, WNW.
500 = the whole body dose rate limit, in mrem/yr.
3.1.3 Determination of the Maximum Acceptable Total Activity Release Rate of Noble Gas Radionuclides in Gaseous Effluent Based on Skin Dose Rate Limit QS = 3000 (3.1-3)
(X/) (Li + 1.11iMi) (Si)(31)
Where:
Qs the maximum acceptable total activity release rate of all noble gas radionuclides in the effluent (for skin exposure), in pCi/s; Li = the beta skin dose factor for a semi-infinite cloud of radionuclide "i" (includes attenuation by the outer "dead, layer of skin), in (mrem/yr)/(ptCi/m3 );
Mi = the gamma air dose factor for a uniform semi-infinite cloud of radionuclide "it, in (mrad/yr)/(jtCi/m3 );
Si = the fraction of the total for radionuclide "ii", per equation 3.1.1; x/Q = the annual average dispersion factor in s/M3 (see Appendix A);
1.11= the air dose to tissue dose equivalent conversion factor, in mrem/mrad; 3000= the skin dose rate limit, in mrem/yr.
(Li + 1.11 Mi) values are shown in Table 3.1-1.
ODCM Page: 37 Rev.: 9 Table 3.1-1 Whole Body and Skin Dose Factors Whole Body Dose Factor Skin Dose Factor (K 1) (Lj+1.11 M 1)
Radionuclide 3 (mrem/yr/pCi/m ) mrem/yr/pCi/m3 )
Kr-83m 7.56E-02 2.14E+01 Kr-85m 1.17E+03 2.83E+03 Kr-85 1.61E+Ol 1.36E+03 Kr-87 5.92E+03 1.66E+04 Kr-88 1.47E+04 1.92E+04 Kr-89 1.66E+04 2.93E+04 Xe-131m 9.15E+Ol 6.49E+02 Xe-133m 2.51E+02 1.36E+03 Xe-133 2.94E+02 6.97E+02 Xe-135 l.81E+03 3.99E+03 Xe-135m 3.12E+03 4.44E+03 Xe-137 1.42E+03 1.39E+04 Xe-138 8.83E+03 1.44E+04 Ar-41 8.84E+03 1.30E+04 3.1.4 Determination of the Maximum Acceptable Total Radioactivity Concentration of all Noble Gas Radionuclides in the Gaseous Effluent
- (2.12 xlO-3)(Qt) (3.1-4)
Ctf Where:
Ct = the maximum acceptable total radioactivity concentration of all noble gas radionuclides in the effluent, in pcCi/cc; f = the flow rate for the release point from the respective flow rate recorders, in ft3 /min; NOTE: Design flow rates, which incorporate a 10%
flow rate inaccuracy correction, may be used in lieu of actual flow rates.
ODCM Page: 38 Rev.: 9 Effluent Release Path Flow Rate (cfm)
Unit 1 Vent 140,000 Unit 2 Vent 60,000 Off-Gas Vent 19,000 Turbine Building/Heater Bay Vent 400,000 (summer) 220,000 (winter)
Qt = the smaller of Qb and Q5 , calculated in equations 3.1-2 and 3.1-3, respectively, pCi/s; 2.12E-12 = the conversion factor to convert (pCi/s) (ft3 /min),
pCi/cc.
3.1.5 Determination of the Maximum Acceptable Monitor Count Rate Above Background Attributed to Noble Gas Radionuclides CRC = (0.8)(Ct)(Em) (3.1-5)
Where:
CRC = the calculated monitor count rate above background attributed to noble gas radionuclides, in cpm; Ct = the maximum acceptable radioactivity concentration, per equation 3.1-4, pCi/cc; Em = the detector efficiency of the monitor for the "mix" of noble gas radionuclides in the effluent, in cpm/(pCi/cc);
= the total pCi/cc concentration divided into the net monitor count rate taken at the time the sample was taken; during the early period of operation, before a sufficient operational effluent source term data base has been obtained, the value will be calculated using monitor calibration data; 0.8 = an engineering safety factor.
3.1.5.1 Determination of the Monitor High Alarm Setpoint HSP = (0.70) (CRc) + BG (3.1-6)
Where:
HSP = the high alarm setpoint (including background), in cpm;
ODCM Page: 39 Rev.: 9 BG the background count rate due to internal contamination and radiation levels in the area in which the monitor is installed when the monitor chamber is filled with uncontaminated air, in cpm; CRC = the calculated monitor net count rate, per equation 3.1-5, in cpm; 0.70 = the fraction of the maximum acceptable activity that may be released from the vent to ensure that the site boundary dose rate limits are not exceeded during concurrent releases from several pathways.
3.1.5.2 Determination of the Monitor Alert Setpoint ASP = (0.10) (CRc) + BG (3.1-7)
Where:
ASP = the alert setpoint (including background), in cpm; BG = the background count rate due to internal contamination and radiation levels in the area in which the monitor is installed when-the monitor chamber is filled with uncontaminated air, in cpm; CRc = the calculated monitor net count rate, per equation 3.1-5, cpm; 0.10 = the fraction of the maximum acceptable activity that may be released from the vent to ensure that the site boundary dose rate limits are not exceeded during concurrent releases from several pathways.
3.2 IOCFR20 Compliance - Gaseous Effluent Dose Rate Dose rates resulting from the release of noble gases, radioiodines, tritium, and radionuclides in particulate form must be calculated to show compliance with IOCFR20. The limits of IOCFR20 are conservatively applied for the release period at the controlling location.
3.2.1 Noble Gases The dose rate in unrestricted areas resulting from noble gas effluents is limited, by ODCM Appendix C controls, to 500 mrem/yr to the whole body and 3000 mrem/yr to the skin. Only the external dose pathway will be considered for noble gases. Because all gaseous effluent releases from PNPP are considered ground level, the controlling location for these dose rate limits is the site boundary location (see Figure 3.2-1) with the highest relative dispersion factor (X/Q). (See Appendix A for elaboration on atmospheric dispersion.)
ODCM Page: 40 Rev.: 9 The alarm setpoint determinations discussed in the previous section should ensure compliance with these dose rate limits. However, if any one high alarm or two or more alert alarms occur, the dose rates in unrestricted areas resulting from the release of noble gas radionuclides from all vents will be calculated. The calculations will be based on the results of analyses obtained pursuant to the ODCM, Appendix C, CONTROLS.
3.2.2 Radioiodines, Particulates, and Other Radionuclides The dose rate in unrestricted areas resulting from the release of iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than eight days is limited, by ODCM Appendix C controls, to 1500 mrem/yr to any organ. The calculation of dose rate from these radionuclides will be performed based on results of analyses obtained pursuant to those Appendix C controls.
The controlling location for this limit is the location of the highest relative deposition (D/Q) for the period of release as well as the actual receptor pathway. The receptor pathway locations will be reviewed once per year following the performance of the Land Use Census to include consideration of nearest residences, garden, and farm animal locations in each sector.
3.2.3 Dose Rate Calculations The following is the equation used to calculate the dose rate resultant from the release of radioactive materials in gaseous effluents to areas at or beyond the site boundary for the purpose of showing compliance with ODCM Appendix C controls as related to 10CFR20.
Dajp = (33.15xlO) )( or % ) Faijp) (Qi) (3.2-1)
Where:
Dajp = the organ "j" dose rate as a function of age group "a" and pathway "p", mrem/yr; DFaijp = the dose factor for organ type "j", age group "a",
pathway upl for isotope "ift (see Tables 3.2-1 through 3.2-3); units and equations used (equations 3.2-2 through 3.2-6) are provided later in this section; (X/Q or D/Q) = the normal or depleted relative dispersion factor (x/Q) in s/M3, or relative deposition (D/Q) in m-2, at the receptor distance (see Appendix A);
1 3.15x10 =conversion factor to convert (mrem*pCi)/(Ci*s) to mrem/yr;
ODCM Page: 41 Rev.: 9 0i = release rate of isotope 'i" (annualized) , pCi/s
= (472)(Ci)(f)
Where:
Ci = the concentration of radionuclide "i" in the gaseous effluent, in pCi/cc; f = the gaseous effluent flow rate during the release, ft3 /min; 472 = conversion factor, (cc/f t3 )/(s/min).
The following relationships are used to derive the dose factors (Dfaijp) for noble gases, tritium, radioiodines and particulates used in equation 3.2-1.
- a. Whole Body Dose Factors from Exposure to a Semi-Infinite Plume DF i =(SF) i)yjFBi) (3.2-2)
Where:
T DFi = the whole body factor due to immersion in a semi-infinite cloud of radionuclide "i",
(mrem
- m 3 )/(Ci
- s);
DFBi = the whole body gamma dose factor for a semi-infinite cloud of radionuclide "i" which includes the attenuation of Sg/cm 2 of tissue from Table 3.2-4, mrem/yr per pCi/m 3 ;
SF = the attenuation factor that accounts for the dose reduction due to the shielding provided by residential structures, optional, dimensionless:
maximum exposed individual = 0.7, population dose 0.5 (Regulatory Guide 1.109);
Xi = the annual average concentration of radionuclide wi" 3
in air (pCi/mr ), for a unit release rate (Ci/yr) and a unit X/Q (s/m3 ), (pCi/M 3) / (Ci/yr) (s/m3).
- b. Skin Dose Factors for Exposure to a Semi-Infinite Plume DFi = (xi)[( 1ll)(SF)(DFZ) + FSi)] (3.2-3)
ODCM Page: 42 Rev.: 9 Where:
S DFi = the skin dose factor due to immersion in a semi-infinite cloud of radionuclide "i",
(mrem
- m3 )/(Ci
- s);
DFiYI = the gamma air dose factor for a uniform semi-infinite cloud of radionuclide "i", from Table 3.2-4, mrad/yr per pci/m 3; DSFi = the beta skin dose factor for a semi-infinite cloud of radionuclide "in (includes attenuation by the outer "dead" layer of skin), from Table 3.2-4, mrem/yr per pCi/m 3 ;
SF = the attenuation factor that accounts for the dose reduction due to the shielding provided by residential structures,-optional, dimensionless:
= maximum exposed individual = 0.7, population dose = 0.5 (Regulatory Guide 1.109);
Xi = the annual average concentration of radionuclide "i" in air (pCi/M 3), for a unit release rate (Ci/yr) and a unit X/Q (s/m3), (pCi/M 3 )/(Ci/yr) (s/M3);
1.11 = the air dose to tissue dose equivalent conversion factor, mrem/mrad.
- c. Dose Factors from External Irradiation from Radionuclides Deposited onto the Ground Surface DF it= (8760) LCi) kFGij) (SF) (3.2-4)
Where:
DF = the dose factor for radionuclide "i" to organ "j" resulting from exposure to radionuclides deposited onto the ground surface, (mrem
- i 2)/Ci; C = the ground plane concentration (pCi/M2 ) of radionuclide li" for a unit release rate (Ci/yr) and a unit D/Q, relative ground deposition (m-2),
2 (pCi/ 2 )/ (Ci/yr) (Mr );
DFGij = the open field ground plane dose conversion factor for organ "j" from radionuclide "i", from Table 3.2-5, mrem/yr per pCi/m 2 ;
ODCM Page: 43 Rev.: 9 SF = the attenuation factor that accounts for the dose reduction due to the shielding provided by residential structures, optional, dimensionless:
maximum exposed individual = 0.7, population dose = 0.5 (Regulatory Guide 1.109);
8760 = the number of hours per year.
- d. Dose Factors from Inhalation of Radionuclides in Air DF A= FAaij) (Ra) ii) (3.2-5) aij Where:
DFaij = the dose factor for radionuclide "i" to organ "j" of an individual in age group "a" due to inhalation, (mrem m3 )/(Ci s) [equivalent to (mrem/yr) (yr/Ci) (m3 /s)];
DFAaij = the inhalation dose factor for radionuclide "i",
organ "j", and age group "a" (the value for skin is assumed to be 0), from Tables 3.2-6 through 3.2-9, mrem/pCi; Ra = the annual air intake for individuals in age group "a", from Table 3.2-14, m3 /yr; Xi = the annual average concentration of radionuclide "i" in air (pCi/lm 3 ), for a unit release rate (Ci/yr) and a unit X/Q (s/M3),
(pCi/m3 )/(Ci/yr) (s/m3).
- e. Dose Factors from the Ingestion of Atmospherically Released Radionuclides in Food aij([
DF ?DFIaij aij A( i ( )(f L) i)( a)( i) +(U Va)(f V)( i)] (3.2A 326 Where:
DFaij = the dose factor for radionuclide "iN to organ "j" of an individual in age group "a" from the ingestion of meat, leafy vegetables, milk, and produce (non-leafy vegetables, fruits, and grains) in (mrem
in (mrem
- rm )/(Ci
- s);
ODCM Page: 44 Rev.: 9 Ci Ci CM CYi the concentrations of radionuclide "il in meat, leafy vegetables, milk, and produce, respectively (pCi/kg or pCi/L) for a unit release rate (Ci/yr) and a unit D/Q, relative ground deposition (m-2),
or in cases of H-3 and C.' 4
, a unit X/Q, relative ground-level concentration (s/r3 ), in (pCi/kg) (Ci/yr)(m') or (pCi/kg)/(Ci/yr) (s/r3 ) or (pCi/L)/(Ci/yr)(m') or (pCi/L) (yr/Ci) (s/r3 );
DFIaij = the ingestion dose factor for radionuclide "i",
organ "j", and age group "a", from Tables 3.2-10 through 3.2-13, mrem/pCi; fL fV = the respective fractions of the ingestion rates of leafy vegetables and produce that are produced in the garden of interest, 1.0 and 0.76 respectively (Regulatory Guide 1.109);
F L M V Ua a U a = the annual intake (usage) of meat, leafy vegetables, milk, and produce respectively, for individuals in age group "a", from Table 3.2-14, kg/yr or 1/yr.
- f. Dose rate example problem:
- 1) For the purpose of this sample problem, the following assumptions are utilized: a release of Xel33 at l.OE-5uCi/cc, a flow rate of l.0E5ft'/min, and a whole body dose factor of 2.94E-4 mrem/yr per pCi/mr. A dose rate and 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> cumulative dose are calculated.
- 2) Whole Body Dose Factor Dose factor per ODCM equation 3.2-2.
T mrem/yr IE + 12 pCi/rn 3 m1r_____3 DFT (0.7)(2.94E - 04 YI C/ 3i 6.52 mrem m pCi/rn3 L(Ci/yr)(3.15E + 07sec/m3JJ Cisec
- 3) Dose Rate per ODCM equation 3.2-1.
(3.25E)( BE - 6152 6
sc mrem m m472 ccmn Pci 1.05E lES-ft 3 "
m Cisec 3 ft sec -cc min mrem
= 0.562 yr (0.562 _E_ ( 87hr)[1 J6.42E-smrem
ODCM Page: 45 Rev.: 9 Table 3.2-1 Organ Used for Gaseous Effluent Dose Calculations
- 1. Bone
- 2. GI Tract
- 3. Kidney
- 4. Liver
- 5. Lung
- 6. Thyroid
- 7. Whole Body
- 8. Skin Table 3.2-2 Age Groups Used for Gaseous Effluent Dose Calculations
- 1. Adult (17 yr and older)
- 2. Teen (11-17 yr)
- 3. Child (1-11 yr)
- 4. Infant (0-1 yr)
Table 3.2-3 Gaseous Effluent Dose Pathways
- 1. Plume
- 2. Ground Shine
- 3. Vegetables
- 4. Meat
- 5. Cow Milk
- 6. Goat Milk
- 7. Inhalation
ODCM Page: 46 Rev.: 9 Table 3.2-4 Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases Gamma Air**
Whole Body* Beta Skin* Dose Factor Gamma Dose Dose Factor Nuclide Factor (DFBi) (DFS ) (DF )
Kr-83m 7.56E-08 1.93E-05 Kr-85m 1.17E-03 1.46E-03 1.23E-03 Kr-85 1.61E-05 1.34E-03 1.72E-05 Kr-87 5.92E-03 9.73E-03 6.17E-03 Kr-88 1.47E-02 2.37E-03 1.52E-02 Kr-89 1.66E-02 1.OlE-02 1.73E-02 Kr-90 1.56E-02 7.29E-03 1.63E-02 Xe-131m 9.15E-05 4.76E-04 1.56E-04 Xe-133m 2.51E-04 9.94E-04 3.27E-04 Xe-133 2.94E-04 3.06E-04 3.53E-04 Xe-135m 3.12E-03 7.11E-04 3.36E-03 Xe-135 1.81E-03 1.86E-03 1.92E-03 Xe-137 1.42E-03 1.22E-02 1.51E-03 Xe-138 8.83E-03 4.13E-03 9.21E-03 Ar-41 8.84E-03 2.69E-03 9.3OE-03
- mrem/yr per pCi/m3
- mrad/yr per pCi/m3
ODCM Page: 47 Rev.: 9 Table 3.2-5 External Dose Factors for Standing on Contaminated Ground (mrem/h per pCi/m 2 )
Element Whole BodY Skin H-3 0.0 0.0 C-14 0.0 0.0 NA-24 2.50E-08 2.90E-08 P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 l.lOE-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.OOE-09 9.40E-09 Co-58 7.OOE-09 8.20E-09 Co-60 1.70E-08 2.OOE-08 Ni-63 0.0 0.0 Nr-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.OOE-09 4.60E-09 Zn-69 0.0 0.0 Br-83 6.40E-11 9.30E-ll Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0 Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.OOE-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9.OOE-09 1.OOE-08 Y-90 2.20E-12 2.60E-12 Y-91M 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-ll Y-92 1.60E-09 l.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.OOE-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Mo-95 5.10E-09 6.OOE-09 Mo-99 l.90E-09 2.20E-09 Tc-99M 9.60E-10 l.lOE-09 Tc-101 2.70E-09 3.OOE-09 Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09 Ag-llON 1.80E-08 2.10E-08
ODCM Page: 48 Rev.: 9 Table 3.2-5 (Cont.)
External Dose Factors for Standing on Contaminated Ground 2
(mrem/h per pCi/m )
Element Whole Body Skin Te-125M 3.50E-11 4.80E-1l Te-127M l.1OE-12 1.30E-12 Te-127 1.OOE-11 1.lOE-11 Te-129M 7.70E-10 9.OOE-10 Te-129 7.10E-10 8.40E-10 Te-131M 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.OOE-09 1-130 1.40E-08 1.70E-08 I-131 2.80E-09 3.40E-09 I-132 1.70E-08 2.OOE-08 I-133 3.70E-09 4.50E-09 I-134 1.60E-08 l.90E-08 I-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.OOE-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 Nd-147 l.OOE-09 1.20E-09 W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1.10E-09
ODCM Page: 49 Rev.: 9 Table 3.2-6 Inhalation Dose Factors for Adult (mrem/pCi inhaled)
WHOLE NUCLIDE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 C 14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 NA 24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 p 32 1.65E-04 9.64E-06 6.26E-06 NO DATA NO DATA NO DATA 1.08E-05 CR 51 NO DATA NO DATA 1.25E-08 7.44E-09 2. 85E-09 1.80E-06 4.15E-07 MN 54 NO DATA 4.95E-06 7.87E-07 NO DATA 1.23E-06 1.75E-04 9.67E-06 MN 56 NO DATA 1.55E-10 2.29E-11 NO DATA 1.63E-10 1.18E-06 2.53E-06 FE 55 3.07E-06 2.12E-06 4.23E-07 NO DATA NO DATA 9.01E-06 7.54E-07 FE 59 1.47E-06 3.47E-06 1.32E-06 NO DATA NO DATA 1.27E-04 2.35E-05 CO 58 NO DATA 1.98E-07 2.59E-07 NO DATA NO DATA 1.16E-04 1.33E-05 CO 60 NO DATA 1.44E-06 1.85E-06 NO DATA NO DATA 7.46E-o5 3.56E-05 NI 63 5.40E-05 3.93E-06 1.81E-06 NO DATA NO DATA 2.23E-05 1.67E-06 NI 65 1.92E-10 2.62E-11 1.14E-11 NO DATA NO DATA 7.0OE-07 1.54E-06 CU 64 NO DATA 1.83E-10 7.69E-11 NO DATA 5.78E-10 8.48E-07 6.12E-06 ZN 65 4.05E-06 1.29E-05 5.82E-06 NO DATA 8.62E-06 1.08E-04 6.68E-06 ZN 69 4.23E-12 8.14E-12 5.65E-13 NO DATA 5.27E-12 1.15E-07 2.04E-09 BR 83 NO DATA NO DATA 3.01E-08 NO DATA NO DATA NO DATA 2. 90E-08 BR 84 NO DATA NO DATA 3.91E-08 NO DATA NO DATA NO DATA 2.05E-13 BR 85 NO DATA NO DATA 1.60E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 1.69E-05 7.37E-06 NO DATA NO DATA NO DATA 2.08E-06 RB 88 NO DATA 4.84E-08 2.41E-08 NO DATA NO DATA NO DATA 4.18E-19 RB 89 NO DATA 3.20E-08 2.12E-08 NO DATA NO DATA NO DATA 1.16E-21 SR 89 3. 80E-05 NO DATA 1.09E-06 NO DATA NO DATA 1.75E-04 4.37E-05 SR 90 1.24E-02 NO DATA 7.62E-04 NO DATA NO DATA 1.20E-03 9.02E-05 SR 91 7.74E-09 NO DATA 3.13E-10 NO DATA NO DATA 4.56E-06 2.39E-05 SR 92 8.43E-10 NO DATA 3.64E-11 NO DATA NO DATA 2.06E-06 5.38E-06 Y 90 2.61E-07 NO DATA 7.01E-09 NO DATA NO DATA 2.12E-05 6.32E-05 Y 91M 3.26E-11 NO DATA 1.27E-12 NO DATA NO DATA 2.40E-07 1.66E-10 Y 91 5.78E-05 NO DATA 1.55E-06 NO DATA NO DATA 2.13E-04 4.81E-05 Y 92 1.29E-09 NO DATA 3.77E-11 NO DATA NO DATA 1.96E-06 9.19E-06 Y 93 1.18E-08 NO DATA 3.26E-10 NO DATA NO DATA 6.06E-06 5.27E-05 ZR 95 1.34E-05 4.30E-06 2.91E-06 NO DATA 6.77E-06 2.21E-04 1.88E-05 ZR 97 1.21E-08 2.45E-09 1.13E-09 NO DATA 3.71E-09 9.84E-06 6.54E-05 NB 95 1.76E-06 9.77E-07 5.26E-07 NO DATA 9.67E-07 6.31E-05 1.30E-05 MO 99 NO DATA 1.51E-08 2.87E-09 NO DATA 3.64E-08 1.14E-05 3.10E-05 TC 99M 1.2 9E-13 3.64E-13 4.63E-12 NO DATA 5.52E-12 9.55E-08 5.20E-07
ODCM Page: 50 Rev.: 9 Table 3.2-6 (Cont.)
Inhalation Dose Factors for Adult (mrem/pCi inhaled)
WHOLE NUCLIDE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI TC101 5.22E-15 7.52E-15 7.38E-14 NO DATA 1.35E-13 4.99E-08 1.36E-21 RU103 1.91E-07 NO DATA 8.23E-08 NO DATA 7.29E-07 6.31E-05 1.38E-05 RU105 9.88E-ll NO DATA 3.89E-11 NO DATA 1.27E-10 1.37E-06 6.02E-06 RU106 8.64E-06 NO DATA 1.OOE-06 NO DATA 1.67E-05 1.17E-03 1.14E-04 AGllOM 1.35E-06 1.25E-06 7.43E-07 NO DATA 2.46E-06 5.79E-04 3.78E-05 TE125M 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-05 TE127M 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05 TE127 1.75E-10 8.00E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 TE129M 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 TE129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-l1 2.42E-07 1.96E-08 TE131M 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3. 86E-08 1.82E-05 6.95E-05 TE131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 TE132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 I 130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 NO DATA 9.61E-07 I 131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 NO DATA 7.85E-07 I 132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 NO DATA 5.08E-08 I 133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 NO DATA 1.11E-06 I 134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3 .44E-07 NO DATA 1.26E-10 I 135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 NO DATA 6.56E-07 CS134 4.66E-05 1.06E-04 9.1OE-05 NO DATA 3.59E-05 1.22E-05 1.30E-06 CS136 4.88E-06 1.83E-05 1.38E-05 NO DATA 1.07E-05 1.50E-06 1.46E-06 CS137 5.98E-05 7.76E-05 5.35E-05 NO DATA 2.78E-05 9.40E-06 1.05E-06 CS138 4.14E-08 7.76E-08 4.05E-08 NO DATA 6.O0E-08 6.07E-09 2.33E-13 BA139 1.17E-10 8.32E-14 3.42E-12 NO DATA 7.78E-14 4.70E-07 1.12E-07 BA140 4.88E-06 6.13E-09 3.21E-07 NO DATA 2.09E-09 1.59E-04 2.73E-05 BA141 1.25E-11 9.41E-15 4.20E-13 NO DATA 8.75E-15 2.42E-07 1.45E-17 BA142 3.29E-12 3.38E-15 2.07E-13 NO DATA 2.86E-15 1.49E-07 1.96E-26 LA140 4 .30E-08 2.17E-08 5.73E-09 NO DATA NO DATA 1.70E-05 5.73E-05 LA142 8.54E-11 3.88E-11 9.65E-12 NO DATA NO DATA 7.91E-07 2.64E-07 CE141 2.49E-06 1.69E-06 l.91E-07 NO DATA 7.83E-07 4.52E-05 1.50E-05 CE143 2.33E-08 1.72E-08 1.91E-09 NO DATA 7.60E-09 9.97E-06 2.83E-05 CE144 4.29E-04 1.79E-04 2.30E-05 NO DATA 1.06E-04 9.72E-04 1.02E-04 PR143 1.17E-06 4.69E-07 5.80E-08 NO DATA 2.70E-07 3.51E-05 2.50E-05 PR144 3.76E-12 1.56E-12 1.91E-13 NO DATA 8.81E-13 1.27E-07 2.69E-18 ND147 6.59E-07 7.62E-07 4.56E-08 NO DATA 4.45E-07 2.76E-05 2.16E-05 W 187 1.06E-09 8.85E-10 3.10E-10 NO DATA NO DATA 3.63E-06 1.94E-05 NP239 2.37E-08 2.82E-09 1.55E-09 NO DATA 8.75E-09 4.70E-06 1.49E-05
ODCM Page: 51 Rev.: 9 Table 3.2-7 Inhalation Dose Factors for Teenaqer (mrem/pCi inhaled)
WHOLE NUCLIDE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 C 14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 NA 24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P 32 2.36E-04 1.37E-05 8.95E-06 NO DATA NO DATA NO DATA 1.16E-05 CR 51 NO DATA NO DATA 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 MN 54 NO DATA 6.32E-06 1.05E-06 NO DATA 1.59E-06 2.48E-04 8.35E-06 MN 56 NO DATA 2.12E-10 3.15E-11 NO DATA 2.24E-10 1.90E-06 7.18E-06 FE 55 4.18E-06 2.98E-06 6.93E-07 NO DATA NO DATA 1.55E-05 7.99E-07 FE 59 1.29E-06 4.62E-06 1.79E-06 NO DATA NO DATA 1.91E-04 2.23E-05 CO 58 NO DATA 2.59E-07 3.47E-07 NO DATA NO DATA 1.68E-04 1. 19E-05 CO 60 NO DATA 1.89E-06 2.48E-06 NO DATA NO DATA 1.09E-03 3.24E-05 NI 63 7.25E-05 5.43E-06 2.47E-06 NO DATA NO DATA 3.84E-05 1.77E-06 NI 65 2.73E-10 3.66E-11 1.59E-11 NO DATA NO DATA 1.17E-06 4. 59E-06 CU 64 NO DATA 2.54E-10 1.06E-10 NO DATA 8. 01E-10 1.39E-06 7.68E-06 ZN 65 4.82E-06 1.67E-05 7.80E-06 NO DATA 1.08E-05 1.55E-04 5.83E-06 ZN 69 6.04E-12 1.15E-11 8.07E-13 NO DATA 7.53E-12 1.98E-07 3.56E-08 BR 83 NO DATA NO DATA 4.30E-08 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 5.41E-08 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 2.29E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.38E-05 1.05E-05 NO DATA NO DATA NO DATA 2.21E-06 RB 88 NO DATA 6.82E-08 3.40E-08 NO DATA NO DATA NO DATA 3.65E-15 RB 89 NO DATA 4.40E-08 2.91E-08 NO DATA NO DATA NO DATA 4.22E-17 SR 89 5.43E-05 NO DATA 1.56E-06 NO DATA NO DATA 3.02E-04 4.64E-05 SR 90 1.35E-02 NO DATA 8.35E-04 NO DATA NO DATA 2.06E-03 9.56E-05 SR 91 1.10E-08 NO DATA 4.39E-10 NO DATA NO DATA 7.59E-06 3.24E-05 SR 92 1.19E-09 NO DATA 5.08E-11 NO DATA NO DATA 3.43E-06 1.49E-05 Y 90 3.73E-07 NO DATA 1.OOE-08 NO DATA NO DATA 3.66E-05 6.99E-05 Y 91M 4.63E-11 NO DATA 1.77E-12 NO DATA NO DATA 4.OOE-07 3.77E-09 Y 91 8.26E-05 NO DATA 2.21E-06 NO DATA NO DATA 3.67E-04 5.11E-05 Y 92 1.84E-09 NO DATA 5.36E-11 NO DATA NO DATA 3.35E-06 2.06E-05 Y 93 1.69E-08 NO DATA 4.65E-10 NO DATA NO DATA 1.04E-05 7.24E-05 ZR 95 1.82E-05 5.73E-06 3.94E-06 NO DATA 8.42E-06 3.36E-04 1.86E-05 ZR 97 1.72E-08 3.40E-09 1.57E-09 NO DATA 5.15E-09 1.62E-05 7.88E-05 NB 95 2.32E-06 1.29E-06 7.08E-07 NO DATA 1.25E-06 8.39E-05 1.21E-05 MO 99 NO DATA 2.11E-08 4.03E-09 NO DATA 5.14E-08 1.92E-05 3.36E-05 TC 99M 1.73E-13 4.83E-13 6.24E-12 NO DATA 7.20E-12 1.44E-07 7.66E-07
ODCM Page: 52 Rev.: 9 Table 3.2-7 (Cont.)
Inhalation Dose Factors for Teenager (mrem/pCi inhaled)
WHOLE NUCLIDE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI TC101 7.40E-1S 1.05E-14 1.03E-13 NO DATA 1.90E-13 8.34E-08 1.09E-16 RU103 2.63E-07 NO DATA 1.12E-07 NO DATA 9.29E-07 9.79E-05 1.36E-05 RU105 1.40E-10 NO DATA 5.42E-11 NO DATA 1.76E-10 2.27E-06 1.13E-05 RU106 1.23E-05 NO DATA 1.55E-06 NO DATA 2.38E-05 2.01E-03 1.20E-04 AGlIOM 1.73E-06 1.64E-06 9.99E-07 NO DATA 3.13E-06 8.44E-04 3.41E-05 TE125M 6.10E-07 2.80E-07 8.34E-08 1.75E-07 NO DATA 6.70E-05 9.38E-06 TE127M 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 TE127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 TE129M 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 TE129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 TE131M 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 TEI31 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.97E-07 1.89E-09 TE132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 I 130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 NO DATA 1.14E-06 I 131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 NO DATA 8.11E-07 I 132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 NO DATA 1.59E-07 I 133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 NO DATA 1.29E-06 I 134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 NO DATA 2.55E-09 I 135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 NO DATA 8.69E-07 CS134 6.28E-05 1.41E-04 6.86E-05 NO DATA 4.69E-05 1.83E-05 1.22E-06 CS136 6.44E-06 2.42E-05 1.71E-05 NO DATA 1.38E-05 2.22E-06 1.36E-06 CS137 8.38E-05 1.06E-04 3.89E-05 NO DATA 3.80E-05 1.51E-05 1.06E-06 CS138 5.82E-08 1.07E-07 5.58E-08 NO DATA 8.28E-08 9.84E-09 3.38E-11 BA139 1.67E-10 1.18E-13 4.87E-12 NO DATA 1.11E-13 8.08E-07 8.06E-07 BA140 6.84E-06 8.38E-09 4.40E-07 NO DATA 2.85E-09 2.54E-04 2.86E-05 BA141 1.78E-11 1.32E-14 5.93E-13 NO DATA 1.23E-14 4.11E-07 9.33E-14 BA142 4.62E-12 4.63E-15 2.84E-13 NO DATA 3.92E-15 2.39E-07 5.99E-20 LA140 5.99E-08 2.95E-08 7.82E-09 NO DATA NO DATA 2.68E-05 6.09E-05 LA142 1.20E-10 5.31E-11 1.32E-11 NO DATA NO DATA 1.27E-06 1.50E-06 CE141 3.55E-06 2.37E-06 2.71E-07 NO DATA 1.11E-06 7.67E-05 1.58E-05 CE143 3.32E-08 2.42E-08 2.70E-09 NO DATA 1.08E-08 1.63E-05 3.19E-05 CE144 6.11E-04 2.53E-04 3.28E-05 NO DATA 1.51E-04 1.67E-03 1.08E-04 PR143 1.67E-06 6.64E-07 8.28E-08 NO DATA 3.86E-07 6.04E-05 2.67E-05 PR144 5.37E-12 2.20E-12 2.72E-13 NO DATA 1.26E-12 2.19E-07 2.94E-14 ND147 9.83E-07 1.07E-06 6.41E-08 NO DATA 6.28E-07 4.65E-05 2.28E-05 W 187 1.50E-09 1.22E-09 4.29E-10 NO DATA NO DATA 5.92E-06 2.21E-05 NP239 4.23E-08 3.99E-09 2.21E-09 NO DATA 1.75E-08 8.11E-06 1.65E-05
ODCM Page: 53 Rev.: 9 Table 3.2-8 Inhalation Dose Factors for Child (mrem/pCi inhaled)
WHOLE NUCLIDE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 C 14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 NA 24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P 32 7.04E-04 3.09E-05 2.67E-05 NO DATA NO DATA NO DATA 1.14E-05 CR 51 NO DATA NO DATA 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 MN 54 NO DATA 1.16E-05 2.57E-06 NO DATA 2.71E-06 4.26E-04 6.19E-06 MN 56 NO DATA 4.48E-10 8.43E-11 NO DATA 4.52E-10 3.55E-06 3.33E-05 FE 55 1.28E-05 6.80E-06 2.10E-06 NO DATA NO DATA 3.OOE-05 7.75E-07 FE 59 5.59E-06 9.04E-06 4.51E-06 NO DATA NO DATA 3.43E-04 1.91E-05 CO 58 NO DATA 4.70E-07 8.55E-07 NO DATA NO DATA 2.99E-04 9.29E-06 CO 60 NO DATA 3.55E-06 6.12E-06 NO DATA NO DATA 1.91E-03 2.60E-05 NI 63 2.22E-04 1.25E-05 7.56E-06 NO DATA NO DATA 7.43E-05 1.71E-06 NI 65 8.08E-10 7.99E-11 4.44E-11 NO DATA NO DATA 2.21E-06 2.27E-05 CU 64 NO DATA 5.39E-10 2.90E-10 NO DATA 1.63E-09 2.59E-06 9.92E-06 ZN 65 1.15E-05 3.06E-05 1.90E-05 NO DATA 1.93E-05 2.69E-04 4.41E-06 ZN 69 1.81E-11 2.61E-11 2.41E-12 NO DATA 1.58E-11 3.84E-07 2.75E-06 BR 83 NO DATA NO DATA 1.28E-07 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 1.48E-07 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 6.84E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 5.36E-05 3.09E-05 NO DATA NO DATA NO DATA 2.16E-06 RB 88 NO DATA 1.52E-07 9.90E-08 NO DATA NO DATA NO DATA 4.66E-09 RB 89 NO DATA 9.33E-08 7.83E-08 NO DATA NO DATA NO DATA 5.11E-10 SR 89 1.62E-04 NO DATA 4.66E-06 NO DATA NO DATA 5.83E-04 4.52E-05 SR 90 2.73E-02 NO DATA 1.74E-03 NO DATA NO DATA 3.99E-03 9.28E-05 SR 91 3.28E-08 NO DATA 1.24E-09 NO DATA NO DATA 1.44E-05 4.70E-05 SR 92 3.54E-09 NO DATA 1.42E-10 NO DATA NO DATA 6.49E-06 6.55E-05 Y 90 l.llE-06 NO DATA 2.99E-08 NO DATA NO DATA 7.07E-05 7.24E-05 Y 91M 1.37E-10 NO DATA 4.98E-12 NO DATA NO DATA 7.60E-07 4.64E-07 Y 91 2.47E-04 NO DATA 6.59E-06 NO DATA NO DATA 7.10E-04 4.97E-05 Y 92 5.50E-09 NO DATA 1.57E-10 NO DATA NO DATA 6.46E-06 6.46E-05 Y 93 5.04E-08 NO DATA 1.38E-09 NO DATA NO DATA 2.01E-05 1.05E-04 ZR 95 5.13E-05 1.13E-05 1.00E-05 NO DATA 1.61E-05 6.03E-04 1.65E-05 ZR 97 5.07E-08 7.34E-09 4.32E-09 NO DATA 1.05E-08 3.06E-05 9.49E-05 NB 95 6.35E-06 2.48E-06 1.77E-06 NO DATA 2.33E-06 1.66E-04 1.OOE-05 MO 99 NO DATA 4.66E-08 1.15E-08 NO DATA 1.06E-07 3.66E-05 3.42E-05 TC 99M 4.81E-13 9.41E-13 1.56E-11 NO DATA 1.37E-11 2.57E-07 1.30E-06
ODCM Page: 54 Rev.: 9 Table 3.2-8 (Cont.)
Inhalation Dose Factors for Child (mrem/pCi inhaled)
WHOLE NUCLIDE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI TC101 2.19E-14 2.30E-14 2.91E-13 NO DATA 3.92E-13 1.58E-07 4.41E-09 RU103 7.55E-07 NO DATA 2.90E-07 NO DATA 1.90E-06 1.79E-04 1.21E-05 RU105 4.13E-10 NO DATA 1.50E-10 NO DATA 3.63E-10 4.30E-06 2.69E-05 RU106 3.68E-05 NO DATA 4.57E-06 NO DATA 4.97E-05 3.87E-03 1.16E-04 AGllOM 4.56E-06 3.08E-06 2.47E-06 NO DATA 5.74E-06 1.48E-03 2.71E-05 TE125M 1.82E-06 6.29E-07 2.47E-07 5.20E-07 NO DATA 1.29E-04 9.13E-06 TE127M 6.72E-06 2.31E-06 8.18E-07 1.64E-06 1.72E-05 4.OOE-04 1.93E-05 TE127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 TE129M 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 TE129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 TE131M 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.S6E-05 8.32E-05 TE131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 TE132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 I 130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 NO DATA 1.38E-06 I 131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 NO DATA 7.68E-07 I 132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 NO DATA 8.65E-07 I 133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 NO DATA 1.48E-06 I 134 3.17E-07 5.84E-07 2.09E-07 1.37E-05 8.92E-07 NO DATA 2.58E-07 I 135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 NO DATA 1.20E-06 CS134 1.76E-04 2.74E-04 6.07E-05 NO DATA 8.93E-05 3.27E-05 1.04E-06 CS136 1.76E-05 4.62E-05 3.14E-05 NO DATA 2.58E-05 3.93E-06 1.13E-06 CS137 2.45E-04 2.23E-04 3.47E-05 NO DATA 7.63E-05 2.81E-05 9.78E-07 CS138 1.71E-07 2.27E-07 1.50E-07 NO DATA 1.68E-07 1.84E-08 7.29E-08 BA139 4.98E-10 2.66E-13 1.45E-11 NO DATA 2.33E-13 1.56E-06 1.56E-05 BA140 2.OOE-05 1.75E-08 1.17E-06 NO DATA 5.71E-09 4.71E-04 2.75E-05 BA141 5.29E-11 2.95E-14 1.72E-12 NO DATA 2.56E-14 7.89E-07 7.44E-08 BA142 1.35E-11 2.73E-15 7.54E-13 NO DATA 7.87E-15 4.44E-07 7.41E-10 LA140 1.74E-07 6.08E-08 2.04E-08 NO DATA NO DATA 4.94E-05 6.10E-05 LA142 3.50E-10 1.11E-10 3.49E-11 NO DATA NO DATA 2.35E-06 2.OSE-05 CE141 1.06E-05 5.28E-06 7.83E-07 NO DATA 2.31E-06 1.47E-05 1.53E-05 CE143 9.89E-08 5.37E-08 7.77E-09 NO DATA 2.26E-08 3.12E-05 3.44E-05 CE144 1.83E-03 5.72E-04 9.77E-05 NO DATA 3.17E-04 3.23E-03 1.05E-04 PR143 4.99E-06 1.50E-06 2.47E-07 NO DATA 8.11E-07 1.17E-04 2.63E-05 PR144 1.61E-11 4.99E-12 8.10E-13 NO DATA 2.64E-12 4.23E-07 5.32E-08 ND147 2.92E-06 2.36E-06 1.84E-07 NO DATA 1.30E-06 8.87E-05 2.22E-05 W 187 4.41E-09 2.61E-09 1.17E-09 NO DATA NO DATA 1.11E-05 2.46E-05 NP239 1.26E-07 9.04E-09 6.35E-09 NO DATA 2.63E-08 1.57E-05 1.73E-05
ODCM Page: 55 Rev.: 9 Table 3.2-9 Inhalation Dose Factors for Infant (mrem/pCi inhaled)
WHOLE NUCLIDE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 C 14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 NA 24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P 32 1.45E-03 8.03E-05 5.53E-05 NO DATA NO DATA NO DATA 1.15E-05 CR 51 NO DATA NO DATA 6.37E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07 MN 54 NO DATA 1.81E-05 3.56E-06 NO DATA 3.56E-06 7.14E-04 5.04E-06 MN 56 NO DATA 1.10E-09 1.58E-10 NO DATA 7.86E-10 8.95E-06 5.12E-05 FE 55 1.41E-05 8.39E-06 2.38E-06 NO DATA NO DATA 6.21E-05 7.82E-07 FE 59 9.69E-06 1.68E-05 6.77E-06 NO DATA NO DATA 7.25E-04 1.77E-05 CO 58 NO DATA 8.71E-07 1.30E-06 NO DATA NO DATA 5.55E-04 7.95E-06 CO 60 NO DATA 5.73E-06 8.41E-06 NO DATA NO DATA 3.22E-03 2.28E-05 NI 63 2.42E-04 1.46E-05 8.29E-06 NO DATA NO DATA 1.49E-04 1.73E-06 NI 65 1.71E-09 2.03E-10 8.79E-11 NO DATA NO DATA 5.80E-06 3.58E-05 CU 64 NO DATA 1.34E-09 5.53E-10 NO DATA 2.84E-09 6.64E-06 1.07E-05 ZN 65 1.38E-05 4.47E-05 2.22E-05 NO DATA 2.32E-05 4.62E-04 3.67E-05 ZN 69 3.85E-11 6.91E-11 5.13E-12 NO DATA 2.87E-11 1.05E-06 9.44E-06 BR 83 NO DATA NO DATA 2.72E-07 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 2.86E-07 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 1.46E-08 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 1.36E-04 6.30E-05 NO DATA NO DATA NO DATA 2.17E-06 RB 88 NO DATA 3.98E-07 2.03E-07 NO DATA NO DATA NO DATA 2.42E-07 RB 89 NO DATA 2.29E-07 1.47E-07 NO DATA NO DATA NO DATA 4.87E-08 SR 89 2.84E-04 NO DATA 8.15E-06 NO DATA NO DATA 1.45E-03 4.57E-05 SR 90 2.92E-02 NO DATA 1.85E-03 NO DATA NO DATA 8.03E-03 9.36E-05 SR 91 6.83E-08 NO DATA 2.47E-09 NO DATA NO DATA 3.76E-05 5.24E-05 SR 92 7.50E-09 NO DATA 2.79E-10 NO DATA NO DATA 1.70E-05 1.OOE-04 Y 90 2.35E-06 NO DATA 6.30E-08 NO DATA NO DATA 1.92E-04 7.43E-05 Y 91M 2.91E-10 NO DATA 9.90E-12 NO DATA NO DATA 1.99E-06 1.68E-06 Y 91 4.20E-04 NO DATA 1.12E-05 NO DATA NO DATA 1.75E-03 5.02E-05 Y 92 1.17E-08 NO DATA 3.29E-10 NO DATA NO DATA 1.75E-05 9.04E-05 Y 93 1.07E-07 NO DATA 2.91E-09 NO DATA NO DATA 5.46E-05 1.19E-04 ZR 95 8.24E-05 1.99E-05 1.45E-06 NO DATA 2.22E-OS 1.25E-03 1.55E-05 ZR 97 1.07E-07 1.83E-08 8.36E-09 NO DATA 1.85E-08 7.88E-05 1.00E-04 NB 95 1.12E-05 4.59E-06 2.70E-06 NO DATA 3.37E-06 3.42E-04 9.05E-06 MO 99 NO DATA 1.18E-07 2.31E-08 NO DATA 1.89E-07 9.63E-05 3.48E-05 TC 99M 9.98E-13 2.06E-12 2.66E-11 NO DATA 2.22E-11 5.79E-07 1.45E-06
ODCM Page: 56 Rev.: 9 Table 3.2-9 (Cont.)
Inhalation Dose Factors for Infant (mrem/pCi inhaled)
WHOLE NUCLIDE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI TC101 4.65E-14 5.58E-14 5.80E-13 NO DATA 6.99E-13 4.17E-07 6.03E-07 RU103 1.44E-06 NO DATA 4.85E-07 NO DATA 3.03E-06 3.94E-04 1.15E-05 RU105 8.74E-10 NO DATA 2.93E-10 NO DATA 6.42E-10 1.12E-05 3.46E-05 RU106 6.20E-05 NO DATA 7.77E-06 NO DATA 7.61E-05 8.26E-03 1.17E-04 AGllOM 7.13E-06 5.16E-06 3.57E-06 NO DATA 7.80E-06 2.62E-03 2.36E-05 TE125M 3.40E-06 1.42E-06 4.70E-07 1.16E-06 NO DATA 3.19E-04 9.22E-06 TE127M 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 TE127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 TE129M 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 TE129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 TE131M 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 TE131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 TE132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 I 130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 NO DATA 1.42E-06 I 131 1.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 NO DATA 7.56E-07 I 132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 NO DATA 1.36E-06 I 133 9.46E-06 1.37E-05 4.OOE-06 2.54E-03 1.60E-05 NO DATA 1.54E-06 I 134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 NO DATA 9.21E-07 I 135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 NO DATA 1.31E-06 CS134 2.83E-04 5.02E-04 5.32E-05 NO DATA 1.36E-04 5.69E-05 9.53E-07 CS136 3.45E-05 9.61E-05 3.78E-05 NO DATA 4.03E-05 8.40E-06 1.02E-06 CS137 3.92E-04 4.37E-04 3.25E-05 NO DATA 1.23E-04 5.09E-05 9.53E-07 CS138 3.61E-07 5.58E-07 2.84E-07 NO DATA 2.93E-07 4.67E-08 6.26E-07 BA139 1.06E-09 7.03E-13 3.07E-11 NO DATA 4.23E-13 4.25E-06 3.64E-05 BA140 4.OOE-05 4.OOE-08 2.07E-06 NO DATA 9.59E-09 1.14E-03 2.74E-05 BA141 1.12E-10 7.70E-14 3.55E-12 NO DATA 4.64E-14 2.12E-06 3.39E-06 BA142 2.84E-11 2.36E-14 1.40E-12 NO DATA 1.36E-14 1.11E-06 4.95E-07 LA140 3.61E-07 1.43E-07 3.68E-08 NO DATA NO DATA 1.20E-04 6.06E-05 LA142 7.36E-10 2.69E-10 3.46E-1 NO DATA NO DATA 5.87E-06 4.25E-05 CE141 1.98E-05 1.19E-05 1.42E-06 NO DATA 3.75E-06 3.69E-04 1.54E-05 CE143 2.09E-07 1.38E-07 1.58E-08 NO DATA 4.03E-08 8.30E-05 3.55E-05 CE144 2.28E-03 8.65E-04 1.26E-04 NO DATA 3.84E-04 7.03E-03 1.06E-04 PR143 1.00E-05 3.74E-06 4.99E-07 NO DATA 1.41E-06 3.09E-04 2.66E-05 PR144 3.42E-11 1.32E-11 1.72E-12 NO DATA 4.80E-12 1.15E-06 3.06E-06 ND147 5.67E-06 5.81E-06 3.57E-07 NO DATA 2.25E-06 2.30E-04 2.23E-05 W 187 9.26E-09 6.44E-09 2.23E-09 NO DATA NO DATA 2.83E-05 2.54E-05 NP239 2.65E-07 2.37E-08 1.34E-08 NO DATA 4.73E-08 4.25E-05 1.78E-05
ODCM Page: 57 Rev. : 9 Table 3.2-10 Ingestion Dose Factors for Adult (mrem/pCi ingested)
WHOLE ISOTOPE B3ONE LIVER BODY THYROID KIDNEY LUNG GI-LLI H3 0.00E+00 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 NA24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P32 1.93E-04 1.20E-05 7.46E-06 0.00E+00 0.00E+00 0.00E+00 2.17E-05 CR51 0.00E+00 0.00E+00 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 W 54 0.00E+00 4.57E-06 8.72E-07 0.00E+00 1.36E-06 0.00E+00 1.40E-05 WN56 0.00E+00 1.15E-07 2.04E-08 0.00E+00 1.46E-07 0.00E+00 3.67E-06 FE55 2.75E-06 1.90E-06 4.43E-07 0.00E+00 0.00E+00 1.06E-06 1.09E-06 FE59 4.34E-06 1.02E-05 3.91E-06 0.00E+00 0.00E+00 2.85E-06 3.40E-05 C058 0.00E+00 7.45E-07 1.67E-06 0.00E+00 0.00E+00 0.00E+00 1.51E-05 C060 0.00E+00 2.14E-06 4.72E-06 0.00E+00 0.00E+00 0.00E+00 4.02E-05 NI63 1.30E-04 9.01E-06 4.36E-06 0.00E+00 0.00E+00 0.00E+00 1.88E-06 NI65 5.28E-07 6.86E-08 3.13E-08 0.00E+00 0.00E+00 0.00E+00 1.74E-06 CU64 0.00E+00 8.33E-08 3.91E-08 0.00E+00 2.10E-07 0.00E+00 7.10E-06 ZN65 4.84E-06 1.54E-05 6.96E-06 0.00E+00 1.03E-05 0.00E+00 9.70E-06 ZN69 1.03E-08 1.97E-08 1.37E-09 0.00E+00 1.28E-08 0.00E+00 2.96E-09 BR83 0.00E+00 0.00E+00 4.02E-08 0.00E+00 0.00E+00 0.00E+00 5.79E-08 BR84 0.00E+00 0.00E+00 5.21E-08 0.00E+00 0.00E+00 0.00E+00 4.09E-13 BR85 0.00E+00 0.00E+00 2.14E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB86 0.00E+00 2.11E-05 9.83E-06 0.00E+00 0.00E+00 0.00E+00 4.16E-06 RB88 0.00E+00 6.05E-08 3.21E-08 0.00E+00 0.00E+00 0.00E+00 8.36E-19 RB89 0.00E+00 4.01E-08 2.82E-08 0.00E+00 0.00E+00 0.00E+00 2.33E-21 SR89 3.08E-04 0.00E+00 8.84E-06 0.00E+00 0.00E+00 0.00E+00 4.94E-05 SR90 7.58E-03 0.00E+00 1.86E-03 0.00E+00 0.00E+00 0.00E+00 2.19E-04 SR91 5.67E-06 0.00E+00 2.29E-07 0.00E+00 0.00E+00 0.00E+00 2.70E-05 SR92 2.15E-06 0.00E+00 9.30E-08 0.00E+00 0.00E+00 0.00E+00 4.26E-05 Y90 9.62E-09 0.00E+00 2.58E-10 0.00E+00 0.00E+00 0.00E+00 1.02E-04 Y9lM 9.09E-11 0.00E+00 3.52E-12 0.00E+00 0.00E+00 0.00E+00 2.67E-10 Y91 1.41E-07 0.00E+00 3.77E-09 0.00E+00 0.00E+00 0.00E+00 7.67E-05 Y92 8.45E-10 0.00E+00 2.47E-11 0.00E+00 0.00E+00 0.00E+00 1.48E-05 Y93 2.68E-09 0.00E+00 7.40E-11 0.00E+00 0.00E+00 0.00E+00 8.50E-05 ZR95 3.04E-08 9.75E-09 6.60E-09 0.00E+00 1.53E-08 0.00E+00 3.09E-05 ZR97 1.68E-09 3.39E-10 1.55E-10 0.00E+00 5.12E-10 0.00E+00 1.05E-04 NB95 6.22E-09 3.46E-09 1.86E-09 0.00E+00 3.42E-09 0.00E+00 2.10E-05 MO99 0.00E+00 4.31E-06 8.20E-07 0.00E+00 9.76E-06 0.00E+00 9.99E3-06 TC99M 2.47E-10 6.98E-10 8.89E-09 0.00E+00 1.06E-08 3.42E-10 4.13E-07
ODCM Page: 58 Rev.: 9 Table 3.2-10 (Cont.)
Ingestion Dose Factors for Adult (mrem/pCi ingested)
WHOLE ISOTOPE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI TC101 2.54E-10 3.66E-10 3.59E-09 0.OOE+00 6.59E-09 1.87E-10 1.10E-21 RU103 1.85E-07 0.OOE+00 7.97E-08 0.OOE+00 7.06E-07 O.OOE+00 2.16E-05 RU105 1.54E-08 0.OOE+00 6.08E-09 0.OOE+00 1.99E-07 0.OOE+00 9.42E-06 RU106 2.75E-06 0.OOE+00 3.48E-07 0.OOE+00 5.31E-06 0.OOE+00 1.78E-04 AGllOM 1.60E-07 1.48E-07 8.79E-08 0.OOE+00 2.91E-07 0.OOE+00 6.04E-05 TE125M 2.68E-06 9.17E-07 3.59E-07 8.06E-07 1.09E-05 O.OOE+00 1.07E-05 TE127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 0.OOE+00 2.27E-05 TE127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 0.OOE+00 8.68E-06 TE129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 0.OOE+00 5.79E-05 TE129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 0.OOE+00 2.37E-08 TE131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 0.OOE+00 8.40E-05 TE131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 0.OOE+00 2.79E-09 TE132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 0.OOE+00 7.71E-05 I130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 O.OOE+00 1.92E-06 I131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 0.OOE+00 1.57E-06 I132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 O.OOE+00 1.02E-07 I133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 O.OOE+00 2.22E-06 1134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 O.OOE+00 2.51E-10 I135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 O.OOE+00 1.31E-06 CS134 6.22E-05 1.48E-04 1.21E-04 0.OOE+00 4.79E-05 1.59E-05 2.59E-06 CS136 6.51E-06 2.57E-05 1.85E-05 O.OOE+00 1.43E-05 1.96E-06 2.92E-06 CS137 7.97E-05 1.09E-04 7.14E-05 0.OOE+00 3.70E-05 1.23E-05 2.11E-06 CS138 5.52E-08 1.09E-07 5.40E-08 0.OOE+00 8.01E-08 7.91E-09 4.65E-13 BA139 9.70E-08 6.91E-11 2.84E-09 0.OOE+00 6.46E-11 3.92E-11 1.72E-07 BA140 2.03E-05 2.55E-08 1.33E-06 0.OOE+00 8.67E-09 1.46E-08 4.18E-05 BA141 4.71E-08 3.56E-11 1.59E-09 0.OOE+00 3.31E-11 2.02E-11 2.22E-17 BA142 2.13E-08 2.19E-11 1.34E-09 0.OOE+00 1.85E-11 1.24E-11 3.OOE-26 LA140 2.50E-09 1.26E-09 3.33E-10 0.OOE+00 O.OOE+00 0.OOE+00 9.25E-05 LA142 1.28E-10 5.82E-11 1.45E-11 O.OOE+00 0.OOE+00 O.OOE+00 4.25E-07 CE141 9.36E-09 6.33E-09 7.18E-10 0.OOE+00 2.94E-09 0.OOE+00 2.42E-05 CE143 1.65E-09 1.22E-06 1.35E-10 O.OOE+00 5.37E-10 O.OOE+00 4.56E-05 CE144 4.88E-07 2.04E-07 2.62E-08 0.OOE+00 1.21E-07 O.OOE+00 1.65E-04 PR143 9.20E-09 3.69E-09 4.56E-10 0.OOE+00 2.13E-09 O.OOE+00 4.03E-05 PR144 3.01E-11 1.25E-11 1.53E-12 0.OOE+00 7.05E-12 O.OOE+00 4.33E-18 ND147 6.29E-09 7.27E-09 4.35E-10 O.OOE+00 4.25E-09 O.OOE+00 3.49E-05 W187 1.03E-07 8.61E-08 3.01E-08 0.OOE+00 O.OOE+00 0.OOE+00 2.82E-05 NP239 1.19E-09 1.17E-10 6.45E-11 0.OOE+00 3.65E-10 O.OOE+00 2.40E-05
ODCM Page: 59 Rev.: 9 Table 3.2-11 Inqestion Dose Factors for Teenager (mrem/pCi ingested)
WHOLE ISOTOPE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI H3 0.0OE+00 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 NA24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P32 2.76E-04 1.71E-05 1.07E-05 0.00E+00 0.00E+00 0.00E+00 2.32E-05 CR51 0.00E+00 0.00E+00 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 MN54 0.00E+00 5.90E-06 1.17E-06 0.00E+00 1.76E-06 0.00E+00 1.21E-05 MN56 0.00E+00 1.58E-07 2.81E-08 0.00E+00 2.00E-07 0.00E+00 1.04E-05 FE55 3.78E-06 2.68E-06 6.25E-07 0.00E+00 0.00E+00 1.70E-06 1.16E-06 FE59 5.87E-06 1.37E-05 5.29E-06 0.00E+00 0.00E+00 4.32E-06 3.24E-05 C058 0.00E+00 9.72E-07 2.24E-06 0.00E+00 0.00E+00 0.00E+00 1.34E-05 C060 0.00E+00 2.81E-06 6.33E-06 0.00E+00 0.00E+00 0.00E+00 3.66E-05 NI63 1.77E-04 1.25E-05 6.00E-06 0.00E+00 0.00E+00 0.00E+00 1.99E-06 NI65 7.49E-07 9.57E-08 4.36E-08 0.00E+00 0.00E+00 0.00E+00 5.19E-06 CU64 0.00E+00 1.15E-07 5.41E-08 0.00E+00 2.91E-07 0.00E+00 8.92E-06 ZN65 5.76E-06 2.00E-05 9.33E-06 0.00E+00 1.28E-05 0.00E+00 8.47E-06 ZN69 1.47E-08 2.80E-08 1.96E-09 0.00E+00 1.83E-08 0.00E+00 5.16E-08 BR83 0.OOE+00 0.00E+00 5.74E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR84 0.00E+00 0.00E+00 7.22E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR85 0.00E+00 0.OOE+00 3.05E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB86 0.00E+00 2.98E-05 1.40E-05 0.00E+00 0.00E+00 0.00E+00 4.41E-06 RB88 0.00E+00 8.52E-08 4.54E-08 0.00E+00 0.00E+00 0.00E+00 7.3OE-15 RB89 0.00E+00 5.50E-08 3.89E-08 0.00E+00 0.00E+00 0.00E+00 8.43E-17 SR89 4.40E-04 0.00E+00 1.26E-05 0. 00E+00 0.00E+00 0.00E+00 5.24E-05 SR90 8.30E-03 0.OOE+00 2.05E-03 0.00E+00 0.00E+00 0.00E+00 2.33E-04 SR91 8.07E-06 0.00E+00 3.21E-07 0.00E+00 0.00E+00 0.00E+00 3.66E-05 SR92 3.05E-06 0.00E+00 1.30E-07 0.00E+00 0.00E+00 0.00E+00 7.77E-05 Y90 1.37E-08 0.00E+00 3.69E-10 0.00E+00 0.00E+00 0.00E+00 1.13E-04 Y9lM 1.29E-10 0.00E+00 4.93E-12 0.00E+00 0.00E+00 0.00E+00 6.09E-09 Y91 2.01E-07 0.00E+00 5.39E-09 0.00E+00 0.00E+00 0.00E+00 8.24E-05 Y92 1.21E-09 0.0OE+00 3.50E-11 0.00E+00 0.00E+00 0.00E+00 3.32E-05 Y93 3.83E-09 0.00E+00 1.05E-10 0.00E+00 0.00E+00 0.00E+00 1.17E-04 ZR95 4.12E-08 1.30E-08 8.94E-09 0.00E+00 1.91E-08 0.00E+00 3.00E-05 ZR97 2.37E-09 4.69E-10 2.16E-10 0.00E+00 7.11E-10 0.00E+00 1.27E-04 NB95 8.22E-09 4.56E-09 2.51E-09 0.00E+00 4.42E-09 0.00E+00 1.95E-05 MO99 0.OOE+00 6.03E-06 1.15E-06 0.00E+00 1.38E-05 0.00E+00 1.08E-05 TC99M 3.32E-10 9.26E-10 1.20E-08 0.00E+00 1.38E-08 5.14E-10 6.08E-07
ODCM Page: 60 Rev.: 9 Table 3.2-11 (Cont.)
Ingestion Dose Factor for Teenager (mrem/pCi ingested)
WHOLE ISOTOPE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI TC101 3.60E-10 5.12E-10 5.03E-09 0.OOE+00 9.26E-09 3.12E-10 8.75E-17 RU103 2.55E-07 0.OOE+00 1.09E-07 0.OOE+00 8.99E-07 0.OOE+00 2.13E-05 RU105 2.18E-08 0.OOE+00 8.46E-09 0.OOE+00 2.75E-07 0.OOE+00 1.76E-05 RU106 3.92E-06 0.OOE+00 4.94E-07 0.OOE+00 7.56E-06 O.OOE+00 1.88E-04 AGllOM 2.05E-07 1.94E-07 1.18E-07 0.OOE+00 3.70E-07 O.OOE+00 5.45E-05 TE125M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 O.OOE+00 O.OOE+00 1.13E-05 TE127M 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 0.OOE+00 2.41E-05 TE127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 0.OOE+00 1.22E-05 TE129M 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 0.OOE+00 6.12E-05 TE129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 0.OOE+00 2.45E-07 TE131M 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 0.OOE+00 9.39E-05 TE131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 0.OOE+00 2.29E-09 TE132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 0.OOE+00 7.OOE-05 1130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 O.OOE+00 2.29E-06 I131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 0.OOE+00 1.62E-06 1132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 0.OOE+00 3.18E-07 I133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 0.OOE+00 2.58E-06 I134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 O.OOE+00 5.10E-09 I135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 O.OOE+00 1.74E-06 CS134 8.37E-05 1.97E-04 9.14E-05 O.OOE+00 6.26E-05 2.39E-05 2.45E-06 CS136 8.59E-06 3.38E-05 2.27E-05 0.OOE+00 1.84E-05 2.90E-06 2.72E-06 CS137 1.12E-04 1.49E-04 5.19E-05 0.00E+00 5.07E-05 1.97E-05 2.12E-06 CS138 7.76E-08 1.49E-07 7.45E-08 0.OOE+00 1.10E-07 1.28E-08 6.76E-11 BA139 1.39E-07 9.78E-11 4.05E-09 0.OOE+00 9.22E-11 6.74E-11 1.24E-06 BA140 2.84E-05 3.48E-08 1.83E-06 0.OOE+00 1.18E-08 2.34E-08 4.38E-05 BA141 6.71E-08 5.01E-11 2.24E-09 0.OOE+00 4.65E-11 3.43E-11 1.43E-13 BA142 2.99E-08 2.99E-11 1.84E-09 0.OOE+00 2.53E-11 1.99E-11 9.18E-20 LA140 3.48E-09 1.71E-09 4.55E-10 O.OOE+00 0.OOE+00 0.OOE+00 9.82E-05 LA142 1.79E-10 7.95E-11 1.98E-11 0.OOE+00 0.OOE+00 0.OOE+00 2.42E-06 CE141 1.33E-08 8.88E-09 1.02E-09 0.OOE+00 4.18E-09 0.OOE+00 2.54E-05 CE143 2.35E-09 1.71E-06 1.91E-10 0.OOE+00 7.67E-10 O.OOE+00 5.14E-05 CE144 6.96E-07 2.88E-07 3.74E-08 O.OOE+00 1.72E-07 O.OOE+00 1.75E-04 PR143 1.31E-08 5.23E-09 6.52E-10 O.OOE+00 3.04E-09 O.OOE+00 4.31E-05 PR144 4.30E-11 1.76E-11 2.18E-12 0.OOE+00 1.01E-11 0.OOE+00 4.74E-14 ND147 9.38E-09 1.02E-08 6.11E-10 O.OOE+00 5.99E-09 0.OOE+00 3.68E-05 W187 1.46E-07 1.19E-07 4.17E-08 0.OOE+00 O.OOE+00 0.OOE+00 3.22E-05 NP239 1.76E-09 1.66E-10 9.22E-11 O.OOE+00 5.21E-10 0.OOE+00 2.67E-05
ODCM Page: 61 Rev.: 9 Table 3.2-12 Ingestion Dose Factors for Child (mrem/pCi ingested)
WHOLE ISOTOPE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI H3 0.OOE+00 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 NA24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P32 8.25E-04 3.86E-05 3.18E-05 0.OOE+00 0. OOE+00 0.OOE+00 2.28E-05 CR51 0.00E+00 0.OOE+00 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 MN54 0.OOE+00 1.07E-05 2.85E-06 0.OOE+00 3.OOE-06 0.OOE+00 8.98E-06 MN56 0.00E+00 3.34E-07 7.54E-08 0.OOE+00 4.04E-07 0.OOE+00 4.84E-05 FE55 1.15E-05 6. 10E-06 1.89E-06 0.OOE+00 0. OOE+00 3.45E-06 1.13E-06 FE59 1.65E-05 2.67E-05 1.33E-05 0.OOE+00 0.OOE+00 7.74E-06 2.78E-05 C058 o.00E+00 1.80E-06 5.51E-06 0.OOE+00 0.OOE+00 0.OOE+00 1.05E-05 C060 0.00E+00 5.29E-06 1.56E-05 0.OOE+00 0.OOE+00 0.OOE+00 2.93E-05 NI63 5.38E-04 2.88E-05 1.83E-05 0.OOE+00 0.OOE+00 0.OOE+00 1.94E-06 NI65 2.22E-06 2.09E-07 1.22E-07 0.OOE+00 0. OOE+00 0.OOE+00 2.56E-05 CU64 o.OOE+00 2.45E-07 1.48E-07 0.OOE+00 5.92E-07 0.OOE+00 1.15E-05 ZN6S 1.37E-05 3.65E-05 2.27E-05 0.OOE+00 2.30E-05 0.OOE+00 6.41E-06 ZN69 4.38E-08 6.33E-08 5.85E-09 0.OOE+00 3.84E-08 0.OOE+00 3.99E-06 BR83 0.OOE+00 0.OOE+00 1.71E-07 0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 BR84 0.00E+00 0.OOE+00 1.98E-07 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 BR85 O.OOE+00 0.00E+00 9.12E-09 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 RB86 0.OOE+00 6.70E-05 4.12E-05 0.OOE+00 0.OOE+00 0.OOE+00 4.31E-06 RB88 0.0OE+00 1.90E-07 1.32E-07 0.OOE+00 0.OOE+00 0.OOE+00 9.32E-09 RB89 0.OOE+00 1.17E-07 1.04E-07 0.OOE+00 0.OOE+00 0.OOE+00 1.02E-09 SR89 1.32E-03 0.OOE+00 3.77E-05 0.OOE+00 0.OOE+00 0.OOE+00 5.11E-05 SR90 1.70E-02 0.OOE+00 4.31E-03 0.OOE+00 0.OOE+00 0.OOE+00 2.29E-04 SR91 2.4OE-05 0.00E+00 9.06E-07 0.OOE+00 0.OOE+00 0.OOE+00 5.30E-05 SR92 9.03E-06 0.00E+00 3.62E-07 0.OOE+00 0.OOE+00 0.OOE+00 1.71E-04 Y90 4.11E-08 0.OOE+00 1.10E-09 0.OOE+00 0.OOE+00 0.OOE+00 1.17E-04 Y9lM 3.82E-10 0.00E+00 1.39E-11 0.OOE+00 0.OOE+00 0.OOE+00 7.48E-07 Y91 6.02E-07 0.OOE+00 1.61E-08 0.OOE+00 0.OOE+00 0.OOE+00 8.02E-05 Y92 3.60E-09 0.OOE+00 1.03E-10 0.OOE+00 0.OOE+00 0.OOE+00 1.04E-04 Y93 1.14E-08 0.OOE+00 3.13E-10 0.OOE+00 0.OOE+00 0.OOE+00 1.70E-04 ZR95 1.16E-07 2.55E-08 2.27E-08 0.OOE+00 3.65E-08 0.OOE+00 2.66E-05 ZR97 6.99E-09 1.01E-09 5.96E-10 0.OOE+00 1.45E-09 0.OOE+00 1.53E-04 NB95 2.25E-08 8.76E-09 6.26E-09 0.OOE+00 8.23E-09 0.OOE+00 1.62E-05 M099 0.00E+00 1.33E-05 3.29E-06 0.OOE+00 2.84E-05 0.OOE+00 1.10E-05 TC99M 9.23E-10 1.81E-09 3.O0E-08 0.OOE+00 2.63E-08 9.19E-10 1.03E-06
ODCM Page: 62 Rev.: 9 Table 3.2-12 (Cont.)
Ingestion Dose Factors for Child (mrem/pCi ingested)
WHOLE ISOTOPE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI TC101 1.07E-09 1.12E-09 1.42E-08 0.OOE+00 1.91E-08 5.92E-10 3.56E-09 RU103 7.31E-07 0.00E+00 2.81E-07 O.OOE+00 1.84E-06 0.OOE+00 1.89E-05 RU105 6.45E-08 0.OOE+00 2.34E-08 O.OOE+00 5.67E-07 0.00E+00 4.21E-05 RU106 1.17E-05 0.OOE+00 1.46E-06 0.OOE+00 1.58E-05 0.OOE+00 1.82E-04 AGllOM 5.39E-07 3.64E-07 2.91E-07 O.OOE+00 6.78E-07 0.OOE+00 4.33E-05 TE125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 0.OOE+00 0.OOE+00 1.10E-05 TE127M 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 0.OOE+00 2.34E-05 TE127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 O.OOE+00 1.84E-05 TE129M 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 O.OOE+00 5.94E-05 TE129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 O.OOE+00 8.34E-06 TE131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 O.OOE+00 1.01E-04 TE131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 O.OOE+00 4.36E-07 TE132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 O.OOE+00 4.50E-05 I130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 O.OOE+00 2.76E-06 I131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 0.OOE+00 1.54E-06 I132 8.OOE-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0.OOE+00 1.73E-06 I133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 0.OOE+00 2.95E-06 I134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 l.19E-06 0.00E+00 5.16E-07 I135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 0.OOE+00 2.40E-06 CS134 2.34E-04 3.84E-04 8.10E-05 0.OOE+00 1.19E-04 4.27E-05 2.07E-06 CS136 2.35E-05 6.46E-05 4.18E-05 0.OOE+00 3.44E-05 5.13E-06 2.27E-06 CS137 3.27E-04 3.13E-04 4.62E-05 0.OOE+00 1.02E-04 3.67E-05 1.96E-06 CS138 2.28E-07 3.17E-07 2.01E-07 O.OOE+00 2.23E-07 2.40E-08 1.46E-07 BA139 4.14E-07 2.21E-10 1.20E-08 0.00E+00 1.93E-10 1.30E-10 2.39E-05 BA140 8.31E-05 7.28E-08 4.85E-06 0.OOE+00 2.37E-08 4.34E-08 4.21E-05 BA141 2.OOE-07 1.12E-10 6.51E-09 0.OOE+00 9.69E-11 6.58E-10 1.14E-07 BA142 8.74E-08 6.29E-11 4.88E-09 0.OOE+00 5.09E-11 3.70E-11 1.14E-09 LA140 1.01E-08 3.53E-09 1.19E-09 0.OOE+00 0.OOE+00 0.OOE+00 9.84E-05 LA142 5.24E-10 1.67E-10 5.23E-11 0.OOE+00 0.OOE+00 O.OOE+00 3.31E-05 CE141 3.97E-08 1.98E-08 2.94E-09 0.OOE+00 8.68E-09 0.OOE+00 2.47E-05 CE143 6.99E-09 3.79E-06 5.49E-10 0.OOE+00 1.59E-09 0.OOE+00 5.55E-05 CE144 2.08E-06 6.52E-07 1.11E-07 0.OOE+00 3.61E-07 0.OOE+00 1.70E-04 PR143 3.93E-08 1.18E-08 1.95E-09 0.OOE+00 6.39E-09 O.0OE+00 4.24E-05 PR144 1.29E-10 3.99E-11 6.49E-12 0.OOE+00 2.11E-11 0.OOE+00 8.59E-08 ND147 2.79E-08 2.26E-08 1.75E-09 0.OOE+00 1.24E-08 O.OOE+00 3.58E-05 W187 4.29E-07 2.54E-07 1.14E-07 0.OOE+00 0.OOE+00 0.OOE+00 3.57E-05 NP239 5.25E-09 3.77E-10 2.65E-10 O.OOE+00 1.09E-09 O.OOE+00 2.79E-05
ODCM Page: 63 Rev.: 9 Table 3.2-13 Ingestion Dose Factors for Infant (mrem/pCi ingested)
WHOLE ISOTOPE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI H3 O.OOE+00 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 C14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 NA24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 P32 1.70E-03 1.00E-04 6.59E-05 O.OOE+00 O.OOE+00 O.OOE+00 2.30E-05 CR51 O.OOE+00 O.OOE+00 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 MN54 O.OOE+00 1.99E-05 4.51E-06 O.OOE+00 4.41E-06 O.OOE+00 7.31E-06 MN56 O.OOE+00 8.18E-07 1.41E-07 O.OE+00 7.03E-07 O.OOE+00 7.43E-05 FE55 1.39E-05 8.98E-06 2.40E-06 O.OOE+00 O.OOE+00 4.39E-06 1.14E-06 FE59 3.08E-05 5.38E-05 2.12E-05 O.OOE+00 O.OOE+00 1.59E-05 2.57E-05 C058 O.OOE+00 3.60E-06 8.98E-06 O.OOE+00 O.OOE+00 O.OOE+00 8.97E-06 C060 O.OOE+00 1.08E-05 2.55E-05 O.OOE+00 O.OOE+00 O.OOE+00 2.57E-05 NI63 6.34E-04 3.92E-05 2.20E-05 O.OOE+00 O.OOE+00 O.OOE+00 1.95E-06 NI65 4.70E-06 5.32E-07 2.42E-07 O.OOE+00 O.OOE+00 O.OOE+00 4.05E-05 CU64 O.OOE+00 6.09E-07 2.82E-07 O.OOE+00 1.03E-06 O.OOE+00 1.25E-05 ZN65 1.84E-05 6.31E-05 2.91E-05 O.OOE+00 3.06E-05 O.OOE+00 5.33E-05 ZN69 9.33E-08 1.68E-07 1.25E-08 O.OOE+00 6.98E-08 O.OOE+00 1.37E-05 BR83 O.OOE+00 O.OOE+00 3.63E-07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 BR84 O.OOE+00 O.O0E+00 3.82E-07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 BR85 O.OOE+00 O.OOE+00 1.94E-08 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 RB86 O.OOE+00 1.70E-04 8.40E-05 O.OOE+00 O.OOE+00 O.OOE+00 4.35E-06 RB88 O.OOE+00 4.98E-07 2.73E-07 O.OOE+00 O.OOE+00 O.OOE+00 4.85E-07 RB89 O.OOE+00 2.86E-07 1.97E-07 O.OOE+00 O.OOE+00 O.OOE+00 9.74E-08 SR89 2.51E-03 O.OOE+00 7.20E-05 O.OOE+00 O.OOE+00 0.OOE+00 5.16E-05 SR90 1.85E-02 O.OOE+00 4.71E-03 O.OOE+00 O.OOE+00 0.OOE+00 2.31E-04 SR91 5.OOE-05 O.OOE+00 1.81E-06 O.OOE+00 O.OOE+00 0.OOE+00 5.92E-05 SR92 1.92E-05 O.OOE+00 7.13E-07 O.OOE+00 O.OOE+00 O.OOE+00 2.07E-04 Y90 8.69E-08 0.00E+00 2.33E-09 0.00E+00 0.00E+00 0.OOE+00 1.20E-04 Y91M 8.10E-10 0.00E+00 2.76E-11 0.00E+00 0.00E+00 0.00E+00 2.70E-06 Y91 1.13E-06 0.00E+00 3.01E-08 0.00E+00 0.00E+00 0.00E+00 8.10E-05 Y92 7.65E-09 0.OOE+00 2.15E-10 0.OOE+00 0.OOE+00 0.00E+00 1.46E-04 Y93 2.43E-08 0.OOE+00 6.62E-10 0.OOE+00 0.00E+00 0.00E+00 1.92E-04 ZR95 2.06E-07 5.02E-08 3.56E-08 0.00E+00 5.41E-08 0.00E+00 2.50E-05 ZR97 1.48E-08 2.54E-09 1.16E-09 0.00E+00 2.56E-09 0.OOE+00 1.62E-04 NB95 4.20E-08 1.73E-08 1.OOE-08 0.OOE+00 1.24E-08 0.OOE+00 1.46E-05 M099 0.OOE+00 3.40E-05 6.63E-06 0.00E+00 5.08E-05 0.00E+00 1.12E-05 TC99M 1.92E-09 3.96E-09 5.10E-08 0.OOE+00 4.26E-08 2.07E-09 1.15E-06
ODCM Page: 64 Rev.: 9 Table 3.2-13 (Cont.)
Ingestion Dose Factors for Infant WHOLE ISOTOPE BONE LIVER BODY THYROID KIDNEY LUNG GI-LLI TC101 2.27E-09 2.86E-09 2.83E-08 0.OOE+00 3.40E-08 1.56E-09 4.86E-07 RU103 1.48E-06 O.OOE+00 4.95E-07 0.OOE+00 3.08E-06 0.OOE+00 1.80E-05 RU105 1.36E-07 0.OOE+00 4.58E-08 0.OOE+00 1.OOE-06 O.OOE+00 5.41E-05 RU106 2.41E-05 0.OOE+00 3.01E-06 O.OOE+00 2.85E-05 0.OOE+00 1.83E-04 AGllOM 9.96E-07 7.27E-07 4.81E-07 0.OOE+00 1.04E-06 O.OOE+00 3.77E-05 TE125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 0.OOE+00 0.OOE+00 1.11E-05 TE127M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 0.OOE+00 2.36E-05 TE127 1.OOE-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 0.OOE+00 2.10E-05 TE129M 1.OOE-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 0.OOE+00 5.97E-05 TE129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 0.OOE+00 2.27E-05 TE131M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 0.OOE+00 1.03E-04 TE131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 0.OOE+00 7.11E-06 TE132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 O.OOE+00 3.81E-05 I130 6.OOE-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 0.OOE+00 2.83E-06 I131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 0.OOE+00 1.51E-06 I132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 0.OOE+00 2.73E-06 1133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 0.OOE+00 3.08E-06 I134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 0.OOE+00 1.84E-06 I135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 O.OOE+00 2.62E-06 CS134 3.77E-04 7.03E-04 7.10E-05 0.OOE+00 1.81E-04 7.42E-05 1.91E-06 CS136 4.59E-05 1.35E-04 5.04E-05 O.OOE+00 5.38E-05 1.10E-05 2.05E-06 CS137 5.22E-04 6.11E-04 4.33E-05 0.00E+00 1.64E-04 6.64E-05 1.91E-06 CS138 4.81E-07 7.82E-07 3.79E-07 0.00E+00 3.90E-07 6.09E-08 1.25E-06 BA139 8.81E-07 5.84E-10 2.55E-08 0.00E+00 3.51E-10 3.54E-10 5.58E-05 BA140 1.71E-04 1.71E-07 8.81E-06 0.00E+00 4.06E-08 1.05E-07 4.20E-05 BA141 4.25E-07 2.91E-10 1.34E-08 0.OOE+00 1.75E-10 1.77E-10 5.19E-06 BA142 1.84E-07 1.53E-10 9.06E-09 0.00E+00 8.81E-11 9.26E-11 7.59E-07 LA140 2.11E-08 8.32E-09 2.14E-09 0.OOE+00 0.00E+00 0.00E+00 9.77E-05 LA142 1.10E-09 4.04E-10 9.67E-11 0.00E+00 0.00E+00 0.00E+00 6.86E-05 CE141 7.87E-08 4.80E-08 5.65E-09 0.00E+00 1.48E-08 0.00E+00 2.48E-05 CE143 1.48E-08 9.82E-06 1.12E-09 0.00E+00 2.86E-09 0.00E+00 5.73E-05 CE144 2.98E-06 1.22E-06 1.67E-07 0.00E+00 4.93E-07 0.00E+00 1.71E-04 PR143 8.13E-08 3.04E-08 4.03E-09 0.00E+00 1.13E-08 0.00E+00 4.29E-05 PR144 2.74E-10 1.06E-10 1.38E-11 0.00E+00 3.84E-11 0.00E+00 4.93E-06 ND147 5.53E-08 5.68E-08 3.48E-09 0.00E+00 2.19E-08 0.00E+00 3.60E-05 W187 9.03E-07 6.28E-07 2.17E-07 0.00E+00 0.00E+00 0.00E+00 3.69E-05 NP239 1.11E-08 9.93E-10 5.61E-10 0.00E+00 1.98E-09 0.00E+00 2.87E-05
ODCM Page: 65 Rev.: 9 Table 3.2-14 Annual Usage Factors for the Maximum Exposed Individual Pathway Infant Child Teen - Adult Fruits, vegetables & -- 520 630 520 grain (kg/yr)*
Leafy -- 26 42 64 vegetables(kg/yr)
Milk (L/yr) 330 330 400 310 Meat & poultry -- 41 65 110 (kg/yr)
Inhalation (m3/yr) 1400 3700 8000 8000
- Consists of the following (on a mass basis): 22% fruit, 54% vegetables (including leafy vegetables), and 24% grain.
Table 3.2-15 Annual Usage Factors for the Average Individual**
Pathway Infant Child Teen Adult Fruits, vegetables & -- 200 240 190 grain (kg/yr)*
Milk (L/yr) -- 170 200 110 Meat & poultry -- 37 59 95 (kg/yr)
Inhalation (m3/yr) -- 3700 8000 8000
- Consists of the following (on a mass basis): 22% fruit, 54% vegetables (including leafy vegetables), and 24% grain.
- For total population and average individual dose calculations.
ODCM Rev.: 9 Page: 66 Figure 3.2-1 PNPP Site Boundary and Unrestricted Area AUEMMCTKD ANNA i ! S- FR LZQVID FMr wok MttsI BYINOMRS FMR GALSMS UFFLUUTS AD M\ =l=USIOU AREA LEGEND POW a WrT I YW tS4-a uTb OWAS4 VWm i2ar OF VWMg 7W4'
£ UQU iAsm Q9cHANGE l.Zmlfl ama~8h j~ ____NM#E 7he boundary line alon th lae sareapplies
__ only to liquid effluents unrestricted area boundary.
UNRESTRICTED AREA
.9
ODCM Page: 67 Rev.: 9 3.3 10CFR50, Appendix I Compliance - Gaseous Effluent Dose Doses resulting from the release of noble gases, radioiodines, tritium and radionuclides in particulate form must be calculated to show compliance with 10CFR50, Appendix I. The calculations will be performed at least monthly for all gaseous effluents.
3.3.1 Noble Gases 10CFR50, Appendix I, Section II.B.1, limits the releases of gaseous effluents from each reactor to unrestricted areas such that the estimated annual gamma air dose is limited to 10 millirads and the beta air dose is limited to 20 millirads. The external dose pathway only will be considered for noble gases. The controlling location for the above stated dose limits is the nearest site boundary location for the period of release.
ODCM Appendix C controls limit the dose resulting from the release of noble gas radionuclides in gaseous effluents to the following:
- a. For gamma radiation, during the current quarter:
Dair
- 5 mrads,
- b. For beta radiation, during the current quarter:
D .
air S 10 mrads,
- c. For gamma radiation, during the current year:
Dair 5 10 mrads,
- d. For beta radiation, during the current year:
Dair 5 20 mrads.
3.3.2 Radioiodines, Particulates, and Other Radionuclides 10CFR50, Appendix I, Section II.C, limits the annual release of radioiodines and radioactive materials in particulate form from each reactor such that estimated dose or dose commitment to an individual in an unrestricted area from all pathways of exposure is not in excess of 15 mrem to any organ. The controlling location for this organ dose limit is the nearest site boundary, the deposition (D/Q) for the period of release, and the receptor pathway. Receptor pathway locations will be reviewed once per year following the performance of the Land Use Census to include consideration of nearest residences, garden, and farm animal locations in each sector.
ODCM Page: 68 Rev.: 9 ODCM, Appendix C, CONTROLS limit the dose resultant from the release of iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than eight days to the following:
- a. During the current quarter:
Dose to Any Organ S 7.5 mrems
- b. During the current year:
Dose to Any Organ
- 15 mrems.
3.3.3 Dose Calculations The following calculations are used to determine gamma and beta air doses resultant from noble gas release to areas at or beyond the site boundary for purpose of showing compliance with 10CFR50, Appendix I.
The equations used to calculate organ doses resultant from the release of iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than eight days are those found in Section 3.2.3.
Dose values are obtained by applying the dose rates over the appropriate surveillance or sampling time period.
- a. Gamma Air Dose from Noble Gas Releases Dair = (3.15xlO)(X)Z (Qi)(DFY)
Where:
Da the annual gamma air dose due to noble gas air radionuclides, mrad/yr; DF = the gamma air dose factor for a uniform semi-infinite cloud of radionuclide "i", from Table 3.3-1, (mrad m3 )/(s Ci);
Qi = the release rate of radionuclide "i", ttCi/s; X/Q = the annual average dispersion factor (see Appendix A), s/M3; 3.15x10I = the conversion factor to convert (mrad*gCi)/(Ci*s) to mrad/yr.
ODCM Page: 69 Rev.: 9
- b. Beta Air dose from Noble Gas Releases Dir = (3.15xl10)(YJ) x (Qi)(DFP)
Where:
D air = the annual beta air dose due to noble gas radionuclides, mrad/yr; DF9 = the beta air dose factor for a uniform semi-infinite cloud of radionuclide "il, from Table 3.3-1, (mrad m3 )/(Ci 5);
Qi = the release rate of radionuclide "i", pCi/s; x/Q = the annual average dispersion factor (see Appendix A), s/m3; 3.15x10 1 = the conversion factor to convert (mrad*JCi)/(Ci*s) to mrad/yr.
3.3.4 Cumulation of Doses The dose contribution from gaseous effluents will be calculated at least monthly. Calculations will be performed to determine the maximum air dose as well as the maximum organ dose to an individual.
These dose calculations will be summed for comparison with quarterly and annual limits. To assure compliance with 10CFR50, Appendix I, the dose limits for air dose and organ dose are those found in Sections 3.3.1 and 3.3.2, respectively. The quarterly limits specified in those sections represent one half of the annual design objectives. If these limits are exceeded, a special report will be submitted to the NRC in accordance with ODCM Appendix C controls.
ODCM Page: 70 Rev.: 9 Table 3.3-1 Gamma and Beta Air Dose Factors for Semi-Infinite Plume (mrad/s per Ci/m3 )
Gamma Air Beta Air Dose Factor Dose Factor (DFXJ) (DF J Ar-41 2.95+02 1.04+02 Kr-83m 6.12-01 9.13+00 Kr-85m 3.90+01 6.24+01 Kr-85 5.45-01 6.18+01 Kr-87 1.96+02 3.27+02 Kr-88 4 .82+02 9.29+01 Kr-89 5.48+02 3.36+02 Kr-90 5.14+02 2.48+02 Xe-131m 4.95+00 3.53+01 Xe-133m 1.04+01 4.69+01 Xe-133 1.12+01 3.33+01 Xe-135m 1.07+02 2.34+01 Xe-135 6.09+01 7.80+01 Xe-137 4 .79+01 4.03+02 Xe-138 2.92+02 1.51+02 3.3.5 Projection of Doses Anticipated doses resulting from the release of gaseous effluents will be projected monthly. The doses calculated for the present month will be used as the projected doses unless information exists indicating that actual releases could differ significantly in the next month. In this case the source term will be adjusted to reflect this information and the justification for the adjustment noted.
If the sum of the projected doses for the 31-day period exceeds 0.3 mrem to any organ, appropriate portions of the ventilation exhaust treatment system will be operated to reduce releases. The values for the projected dose impact levels correspond to about one forty-eighth of the IOCFR50, Appendix I dose limits. If continued for a year, these values would correspond to less than one-fourth of the 10CFR50, Appendix I dose limits.
3.4 Population Dose PNPP's Annual Radioactive Effluent Release Reports, as required by Regulatory Guide 1.21, will include total population dose and average individual doses calculated for all radioactive gaseous effluent releases. The total population dose and average individual dose will be computed, taking into account geographical population distribution and pathway(s) using the equations in Section 3.2. However, the dose factors, DFaijp, differ; total population and average individual doses are
ODCM Page: 71 Rev.: 9 calculated in a manner similar to that used for maximum individuals except that Regulatory Guide 1.109, Revision 1, assumptions for average individuals are used rather than for maximum exposed individuals and they are averaged over all age groups after weighting by the fraction of population in each age group.
4.0 TOTAL DOSE 4.1 40CFRl90 Compliance - Uranium Fuel Cycle Dose Annual dose contributions from liquid and gaseous effluent releases, as discussed in Sections 2.3.2 and 3.3.4, are summed to evaluate compliance with the 40CFR190 annual limit of 25 mrem whole body or any organ (except the thyroid, which is 75 mrem).
PNPP does not intend to exceed 40CFR190 limits during normal operation.
However, if such a situation should occur, violations would be handled as per ODCM Appendix C Control 3/4.11.4a. which requires the following:
With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Control 3.11.1.2a., 3.11.1.2b., 3.11.2.2a., 3.11.2.2b., 3.11.2.3a. or 3.11.2.3b., calculations shall be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the above limits of Control 3.11.4 have been exceeded.
If such is the case, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10CFR20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40CFR190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40CFRl90. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
This Special Report shall contain:
- 1. A determination of which fuel cycle facilities or operations, in addition to the nuclear power reactor unit(s) at the site, contribute to the annual dose to the maximum exposed individual. Nuclear fuel facilities over five miles from PNPP need not be considered in this determination.
ODCM Page: 72 Rev.: 9
- 2. A determination of the maximum exposed individual.
- 3. A determination of the total annual dose to this person from all existing pathways and sources of radioactive effluents and direct radiation using the methodologies described in this ODCM. Where additional information on pathways and nuclides is needed, the best available information will be used and documented.
- 4. A determination of the dose resulting from direct radiation from the plant and storage facilities.
The whole body and organ doses resulting from liquid effluents from the PNPP will be summed with the doses resulting from gaseous releases of noble gases, radioiodines, tritium, and particulates with half-lines greater than eight days when any of the dose limits outlined in Sections 2.3.2, 3.3.1 or 3.3.2 are exceeded by a factor of two. The doses from the PNPP will be summed with the dose to the maximum exposed individual contributed from other operations of the uranium fuel cycle.
4.2 Direct Radiation Dose from PNPP Potential direct radiation dose to individuals outside PNPP will arise from (a) skyshine and direct dose from the turbines, (b) direct dose from the external surfaces of buildings, and (c) direct dose from stored radwaste.
Coolant activation by high energy neutrons, the 016(n,p)N"6 reaction, is of interest in boiling water reactors, like PNPP, because it can result in turbine skyshine and direct dose. The N-16 present in the steam of a direct cycle BWR is carried with the steam into the turbine moisture separators, and associated equipment. Although N-16 has a half-life of 7.13 seconds, its gamma emission can present a radiation dose problem to the site boundary as a result of the high energy gamma scatter from structures and the atmosphere.
All external walls of buildings at PNPP have been designed to attenuate radiation sources from within the plant to maximum of 0.5 mrem/h outside, with an expected radiation dose not to exceed 0.25 mrem/h.
Projected direct radiation dose assessment for normal operations was performed, based on 80% load factor and 100% occupancy, for the closest site boundary location (WSW sector). Direct dose from turbine skyshine was calculated to be 1.3 mrem/yr and direct dose from the surface of buildings was calculated to be 2.2 E-3 mrem/yr.
Direct radiation doses at PNPP will be measured by self-contained dosimeters encircling the site located in the general area of the site boundary. These self-contained dosimeters will be of the thermoluminescent variety (TLDs) with analyses performed quarterly and annually.
ODCM Page: 73 Rev.: 9 4.3 Dose to Members of the Public While Onsite ODCM Appendix C Control 6.9.1.7 requires "assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the site boundary." This assessment is included in Annual Radioactive Effluent Release Reporting.
A member of the public is defined in ODCM Appendix C to include anyone who is not occupationally associated with the plant, i.e., not a utility employee, contractor or vendor. Also excluded from this category is any person who enters the site to service equipment or make deliveries.
Maximum dose to member of the public while onsite is conservatively assessed relative to offsite dose values. The assessment methodology incorporates use of appropriate dilution, dispersion, and occupancy factors for onsite activities.
The only liquid effluent dose pathway affecting members of the public while onsite is shore exposure, which is assumed to be fishing on the Lake Erie shoreline. Onsite dose assessment is made via ratio to the maximum calculated offsite shore exposure dose, using adjustments for occupancy factor and liquid effluent dilution.
Several cases are considered for gaseous effluent dose assessment to member of the public while onsite including: traversing a public road within the site boundary, lakeshore fishing, non-PNPP related training sessions at the Training and Education Center, car pooling to the Primary Access Control Point (PACP) parking lot, and job applicant interviews.
This evaluation is made using "relative X/Q" (atmospheric dispersion) values. "Relative X/Q" values are the product of the highest annual average X/Q for the point of concern, and occupancy factor for the case.
The ratio of the highest onsite "relative X/Q" to the highest site boundary "relative X/Q" is used as an adjustment factor. (A unity occupancy factor is used in the determination of the highest site boundary "relative X/Q"). A conservative onsite dose determination is made by applying the "relative X/Q" adjustment factor for the highest potential onsite dose activity to the highest calculated gaseous effluent offsite dose.
5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 5.1 Monitoring Program Environmental samples shall be collected and analyzed according to Table 5.1-1 at locations shown in Figures 5.1-1, 5.1-2 and 5.1-3. The Radiological Environmental Monitoring Program (REMP) sample locations are controlled by RMP-0013. A list and figures of the specific locations are contained in the Master List of Sampling Locations in the REMP file.
Analytical techniques used shall ensure that the detection capabilities in Table 5.1-3 are achieved.
ODCM Page: 74 Rev.: 9 Ground water sampling will not be conducted as part of PNPP's REMP because this source is not tapped for drinking or irrigation purposes in the area of the plant. The position of the plant and the underdrain system with respect to the hydraulic gradient is such that any leakage or overflow from the underdrain system will flow north towards Lake Erie.
Local domestic wells outside the exclusion area boundary are up-gradient from the plant. As part of the REMP, samples will be routinely collected from the closest potable water intakes on Lake Erie.
The results of the radiological environmental monitoring program are intended to supplement the results of the radiological effluent monitoring by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. Thus, the specified environmental monitoring program provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation. The initial radiological environmental monitoring program was conducted for the first three years of commercial operation; program changes may now be proposed based on operational experience.
5.2 Land Use Census Program A Land Use Census shall be conducted annually to identify, within a distance of 8 km (5 miles), the location in each of the meteorological sectors of the nearest residence, the nearest garden' greater than 50m 2 (500 ft2 ) and the nearest milk-producing animal.
If a Land Use Census identifies a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at the location from which samples are currently being obtained the new location(s) will be added to the radiological environmental monitoring program within 30 days. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted.
The Land Use Census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, general observations, or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report.
- Broad leaf vegetation sampling of at least three different types of vegetation may be performed at the site boundary in each of two different sectors with the highest predicted D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 5.1-1 shall be followed, including analysis of control samples.
ODCM Page: 75 Rev.: 9 5.3 Inter-Laboratory Comparison Program The laboratories of the licensee and/or licensee's contractors which perform analyses shall participate in an Interlaboratory Comparison Program which has been approved by the Commission. This participation shall include all of the determinations (sample medium-radionuclide combinations) that are included in the monitoring program. The results of analysis of these comparison samples shall be included in the Annual Radiological Environmental Operating Report.
If the results of a determination in the comparison crosscheck program are outside the specified control limits, the laboratory shall investigate the cause of the problem and take steps to correct it. The results of this investigation and corrective action shall be included in the Annual Radiological Environmental Operating Report.
ODCM Rev.: 9 Page: 76 Table 5.1-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Sample Sample Locational' Collection Frequency of Analysis
- 1. Direct Radiation (2)
Twenty eight routine monitoring Quarterly Gamma dose quarterly stations either with two or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:
An inner ring of stations, one in each meteorological sector, other than those sectors entirely over water (N, NE, NNE, NNW, NW, W, WNW), in the general area of the SITE BOUNDARY; An outer ring of stations, one in each meteorological sector, other than those sectors entirely over water (N, NNE, NNW, NW, W, WNW), in the 6- to 8- km range from the site; and The balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and in one or two areas to serve as control stations.
) 9)
ODCM Rev. : 9 Page: 77 Table 5.1-1 (Cont.)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Sample Sample Locational Collection Frequency of Analysis
- 2. Airborne Radio-iodine and Samples from five locations: Continuous sampler Radio-Iodine Canister:
Particulate operation with sample Three samples from close to the collection weekly, or I-131 analysis weekly three SITE BOUNDARY locations, in more frequently, if Particulate Sampler:
different sectors, of the highest required by dust calculated annual average loading. Gross beta radioactivity ground-level D/Q; analysis following filter change(3);
One sample from the vicinity of a community having the highest Gamma isotopic analysis (4) calculated annual average ground of composite (by location) level D/Q; and quarterly.
One sample from a control location, as for example 15 to 30 km distant and in the least prevalent wind direction.
- 1) I)
ODCM Rev.: 9 Page: 78 Table 5.1-1 (Cont.)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Sample Sample Location(1) Collection Frequency of Analysis
- 3. Waterborne
- a. Surface Two samples Composite sample over Gamma isotopic analysis (4) 1-month period(5S) monthly.
Composite for tritium analysis quarterly.
- b. Drinking One sample of each of one to three of Composite sample over I-131 analysis on each the nearest water supplies that could 2-week period 5) when composite when the dose be affected by its discharge. I-131 analysis is calculated from the performed; monthly consumption of the water One sample from a control location. composite otherwise. is greater than 1 mrem per year. (6)
Composite for gross beta and gamma isotopic analysis (4) monthly.
Composite for tritium analysis quarterly.
- c. Sediment from One sample from area with existing or Semi-annually Gamma isotopic analysis (4)
Shoreline potential recreational value. semi-annually.
D
ODCM Rev. : 9 Page: 79 Table 5.1-1 (Cont.)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Samples and Sampling and Type and Frequency and/or Sample Sample Location l) Collection Frequency of Analysis
- 4. Ingestion
- a. Milk Samples from milking animals in three Semi-monthly when Gamma isotopic analysis (4) locations within 5 km distance having animals are on and 1-131 analysis the highest dose potential. If there pasture; semi-monthly when animals are none, then one sample from are on pasture; monthly at milking animals in each of three Monthly at other other times.
areas between 5 to 8 km distant where times.
doses are calculated to be greater than 1 mrem per yr . One sample from milking animals at a control location 15 to 30 km distant and in the least prevalent wind direction.
- b. Fish and One sample of one commercially and/or One sample in season. Gamma isotopic analysis (4)
Invertebrates recreationally important species in on edible portions.
vicinity of plant discharge area.
One sample of same species in areas not influenced by plant discharge.
- c. Food Samples of three different kinds of Monthly during growing Gamma isotopic analysis (4)
Products broad leaf vegetation grown nearest season. and I-131 analysis.
to each of two different offsite locations of highest predicted annual average ground level D/Q, if milk sampling is not performed.
One sample of each of the similar Monthly during growing Gamma isotopic analysis(4) broad leaf vegetation grown 15 to season. and I-131 analysis.
30 km distant in the least prevalent wind direction, if milk sampling is not performed.
ODCM Page: 80 Rev.: 9 Table 5.1-1 (Cont.)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Table Notations (1) Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, and malfunction of automatic sampling equipment.
If specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to <ODCM Appendix C Control 6.9.1.6>. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable specific alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made with in the thirty days.
(2) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters.
(3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.
(4) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.
(5) A composite sample is one in which the quantity (aliquot) of liquid sampled is proportional to the quantity of flowing liquid and in which the method of sampling employed results in a specimen that is representative of the liquid flow. In this program composite sample aliquots shall be collected at time intervals that are very short (e.g.,
hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.
(6) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters within this manual.
ODCM Rev.: 9 Page: 81 Table 5.1-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples Water AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS ANALYSIS (pCi/l) OR GASES (pCi/m 3 ) (pCi/kg, wet) (pCi/l) (pCi/kg, wet)
H-3 2 x 104 (a)
Mn-54 1 x 103 3 x 104 Fe-59 4 x 102 1 X 104 Co-58 1 x 103 3 x 104 Co-60 3 x 102 1 X 104 Zn-65 3 x 102 2 X 104 Zr-Nb-95 4 x 102 I-131 2 x 100 9 x 10-' 3 x 100 1 X 102 Cs-134 3 x 101 1 x 101 1 x l03 6 x 101 1 X 103 Cs-137 5 x 101 2 x 101 2 x 103 7 x 101 2 x 103 Ba-La-140 2 x 102 3 x 102 (a) For drinking water samples. The value given is the 40CFR141 value.
)
ODCM Rev. : 9 Page: 82 Table 5.1-3 Detection Capabilities for Environmental Sample Analysis and (a)(b)
Lower Limit of Detection (LLD)
AIRBORNE Water PARTICULATE FISH MILK FOOD PRODUCTS SEDIMENT ANALYSIS(C) (pCi/l) OR GASES (pCi/M3) (pCi/kg, wet) (pCi/l) (pCi/kg, wet) (pCi/kg, dry)
Gross Beta 4 x 100 1 x 10.2 H-3 2 x 1 03 (d)
Mn-54 1.5 x 101 1.3 x 102 Fe-59 3 x 101 2.6 x 102 Co-58, 60 1.5 x 101 1.3 x 102 Zn-65 3 x 101 2.6 x 102 Nb-95 1.5 x 101 Zr-95 3 x 101 1-131 1 x 100(e) 7 x 10-2 1 x 100 6 x 101 Cs-134 1.5 x 10' 5 x 10.2 1.3 x 102 1.5 x 101 6 x 101 1.5 x 102 Cs-137 1.8 x 101 6 x 10.2 1.5 x 102 1.8 x 10' 8 x 101 1.8 x 102 Ba-140 6 x 10 6 x 101 La-140 1.5 x 10' 1.5 x 101 a Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13, except for specification regarding energy dependence. Correction factors shall be provided for energy ranges not meeting the energy dependence specification.
The methodology for determining the LLD is contained in Appendix B.
C This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.1.6. For these radionuclides in ODCM Appendix C Table 4.12-1 which are not detected, the typical LLDs for the measurement system will be separately reported in the annual report.
d If no drinking water pathway exists, a value of 3 x 103 pCi/L may be used.
e If no drinking water pathway exists, a value of 1.5 x 101 pCi/L may be used.
)
ODCM Rev.: 9 Page: 83 Figure 5.1-1 TECHNICAL SPECIFICATION REQUIRED REMP SAMPLING LOCATIONS WITHIN TWO MILES OF THE PLANT SITE NNW N NNE NW NE LEGEND:
STATION NO. MEDIA DIRECTION 2 FP NNE 3 TLD SE 4 AIR, TLD S S TLD SW NW EN 7 AIR, TLD NE 8 TLD E 9 TLD ESE W 10 TLD SSE ES 11 TLD WSW 12 TLD WSW 25 SED, FSH NNW 34 WTR NW SW ES 35 AIR, TLD E 37 FP ENE 53 TLD ENE 58 TLD ENE SW SE SSW S SSE
)
ODCM Rev.: 9 Page: 84 Figure 5.1-2 TECHNICAL SPECIFICATION REQUIRED REMP SAMPLING LOCATIONS BETWEEN TWO AND EIGHT MILES FROM THE PLANT SITE Il dv NNW N NNE NE LEGEND:
STATION NO. MEDIA DIRECTION 1 AIR, TLD ENE 13 TLD ENE 14 TLD E 15 TLD ESE WNW ENE 21. TLD WSW 23 TLD WSW 29 TLD SSE 30 TLD SSW 31 TLD SE 33 TLD S 36 WATER, TLD WSW W E 54 TLD SW 55 TLD S
.)
ODCM Rev.: 9 Page: 85 Figure 5.1-3 TECHNICAL SPECIFICATION REQUIRED REMP SAMPLING LOCATIONS GREATER THAN EIGHT MILES FROM THE PLANT SITE WNW ENE W E WSW ESE 0 5 10 15 20MILES LEGEND:
STATION NO. MEDIA DIRECTION V8" - 1 MILE 6 AIR, TLD SSW 24 TIL SW 25 WATER ENE 32 FISH WSW 70 FP 8SW
)
ODCM Page: 86 Rev.: 9 Appendix A Atmospheric Dispersion and Deposition Parameters
ODCM Page: 87 Rev.: 9 The atmospheric dispersion and deposition parameters used to calculate gaseous effluent doses will be calculated using the following equations. Dose calculations will be performed using meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents or using historical average atmospheric conditions. All atmospheric releases at PNPP are considered to be ground-level releases.
- a. Constant Mean Wind Direction Relative Dispersion Factor
= (2.32)(Tf) (A-1)
/Q (U) (x) (a)
Where:
X/Q = the annual average dispersion factor, s/m3; Tf = the terrain correction factor, from FSAR Table 2.3-26, dimensionless; U = the wind speed (measured at lin), in m/s; X = the distance of calculation, in m; 2.032 = (2/it)A divided by the width in radians of a 22.5 0 sector
( 2 /2 a = the lesser of z + .cJ or (CZ)(31/2)
Where:
Hc ' the building height (44.8m);
CTZ - the vertical dispersion coefficient, per Regulatory Guide 1.111, in m.
- b. Depleted Relative Dispersion Factor X/Qd = (X/Q) DPIj) (A-2)
Where:
X/Qd = the depleted relative dispersion factor (for airborne halogens and particulates), in s/m3; DPLj = the ground depletion factor for the ajuth distance, interpolated from Table A-1, dimensionless; X/Q = the annual average dispersion factor per equation A-1, s/m3.
ODCM Page: 88 Rev.: 9
- c. Ground Deposition D/ EPj) (Tf)
(A-3)
(0.3927) (x)
Where:
D/Q = the relative deposition per unit area (for halogens and particulates), m2 ;
DEPj . the ground deposition factor for the 'nj"thdistance, interpolated from Table A-1, m-l; Tf - terrain correction factor, from FSAR Table 2.3-26, dimensionless; x = the "jMth distance, m; 0.3927 = radians per 22.50 sector Table A-1 Atmospheric Depletion and Deposition Factors Depletion Deposition Factors Factors (DPLj) (DEPj, mn1)
Pasquill Stability Class All All Distance (meters) 200 0.970 1.25E-04 500 0.936 8.OE-05 1, 000 0.900 5.4E-05 2,000 0.860 3.2E-05 3,000 0.832 2. 6E-05 6,000 0.770 1.5E-05 10, 000 0.714 9.9E-06 30, 000 0.590 4.5E-06 SO, 000 0.517 3.OE-06 80,000 0.440 2 .OE-06 The following tables contain annual average atmospheric dispersion and deposition parameters for long-term releases at PNPP. Long-term releases are those that occur greater than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per year. The highest annual average relative concentration (X/Q) value at the site boundary for sectors over land shall be used for radioactive gaseous effluent monitor setpoint calculations.
The dispersion model used was XOQDOQ, with PNPP FSAR site-specific terrain adjustment factors included. Dispersion values are based on seven years of meteorological data (May 1, 1972 through April 30, 1974 and September 1, 1977 through August 31, 1982), ground-level releases, sector spread for purge calculations, and twelve wind speed classes.
ODCM Page: 89 Rev.: 9 Table A-2 Site Boundary Atmospheric Dispersion (X/Q) and Deposition Parameters (D/Q) for PNPP Unit 1 SECTOR DISTANCE x/Q D/Q (MILES) (SEC./CUB. METER) (PER SQ. METER)
N 0.18 5.7E-05* 1.6E-07 NNE 0.25 1.8E-05* 7.9E-08 NE 0.42 5.8E-06* 3.1E-08 ENE 0.67 2.1E-06* 1.6E-08 E 0.67 2.2E-06 1.8E-08 ESE 0.67 1.6E-06 1.3E-08 SE 0.79 1.4E-06 1.lE-08 SSE 0.82 2.2E-06 1.4E-08 S 0.81 2.7E-06 1.6E-08 SSW 0.80 1.3E-06 6.8E-09 SW 0.65 2.3E-06* l.lE-08 WSW 0.56 4.2E-06* 1.SE-08 W 0.27 2.5E-05* 4.6E-08 WNW 0.18 5.9E-05* 8.4E-08 NW 0.17 6.6E-05* 1.lE-07 NNW 0.17 S.9E-05* 1.2E-07 NOTE: All X/Q values are taken from the Updated Safety Analysis Report (USAR) Table 2.3-27. All marked values (*) are from Unit 1 USAR values, and the balance are Unit 2 values. In each case, the most conservative X/Q value is utilized.
ODCM Page: 90 Rev.: 9 Table A-3 3
Atmospheric Dispersion (0/Q) as a Function of Distance (s/m )
SECTOR 0.2 0.3 0.4 0.5 0.6 (MILES) (MILES) (MILES) (MILES) (MILES)
N 4.904E-05 2.453E-05 1.525E-05 1.057E-05 7.918E-06 NNE 2.656E-05 1.360E-05 8.64OE-06 6.082E-06 4.612E-06 NE 1.859E-05 9.760E-06 6.293E-06 4.460E-06 3.383E-06 ENE 1.327E-05 7.129E-06 4.636E-06 3.293E-06 2.490E-06 E 1.363E-05 7.362E-06 4.760E-06 3.367E-06 2.538E-06 ESE 1.025E-05 5.566E-06 3.602E-06 2.547E-06 1.916E-06 SE 1.113E-05 6. 061E-06 3.935E-06 2.788E-06 2.100E-06 SSE 1.894E-05 1.022E-05 6.647E-06 4.718E-06 3.560E-06 S 2.283E-05 1.227E-05 7.932E-06 5.615E-05 4 .238E-06 SSW 1.142E-05 6. 079E-06 3.925E-06 2.777E-06 2. 097E-06 SW 1.449E-05 7.663E-06 4 .928E-06 3.479E-06 2.622E-06 WSW 2.151E-05 1.111E-05 7.031E-06 4.934E-06 3.733E-06 W 4 .184E-05 2. OBE-05 1.281E-05 8.833E-06 6.606E-06 WNW 4.669E-05 2.298E-05 1.401E-05 9.573E-06 7.093E-06 NW 4.908E-05 2.423E-05 1.482E-05 1.015E-05 7.521E-06 NNW 4.580E-05 2.266E-05 1.390E-05 9.541E-06 7.083E-06 SECTOR 0.7 0.8 0.9 1.0 1.1 (MILES) (MILES) (MILES) (MILES) (MILES)
N 6.138E-06 4.968E-06 4 .203E-06 3 .636E-06 1.949E-06 NNE 3.622E-06 2.947E-06 2.481E-06 2.132E-06 1.278E-06 NE 2.662E-06 2.165E-06 1.815E-06 1.552E-06 9.269E-07 ENE 1.957E-06 1.588E-06 1.325E-06 1.129E-06 6.710E-07 E 1.991E-06 1.613E-06 1.343E-06 1.141E-06 6.768E-07 ESE 1.501E-06 1.215E-06 1.OlOE-06 8.571E-07 5.080E-07 SE 1.647E-06 1.334E-06 1.108E-06 9.402E-07 4 .456E-07 SSE 2.796E-06 2.266E-06 1.885E-06 1.601E-06 5.524E-07 S 3 .327E-06 2.697E-06 2.247E-06 1.911E-06 7.340E-07 SSW 1.646E-06 1.335E-06 1.114E-06 9.486E-07 5.223E-07 SW 2.053E-06 1.664E-06 1.391E-06 1.188E-06 5.667E-07 WSW 2.927E-06 2.380E-06 2.002E-06 1.719E-06 8.671E-07 W 5.110E-06 4.135E-06 3.504E-06 3.036E-06 1.630E-06 WNW 5.434E-06 4.37SE-06 3.719E-06 3.235E-06 1.845E-06 NW 5.764E-06 4 .643E-06 3.941E-06 3.425E-06 1.952E-06 NNW 5.439E-06 4 .385E-06 3 .720E-06 3 .230E-06 1.839E-06
ODCM Page: 91 Rev.: 9 Table A-3 (Cont.)
3 Atmospheric Dispersion (X/Q) as a Function of Distance (s/m )
SECTOR 1.2 1.3 1.4 1.5 1.6 (MILES) (MILES) (MILES) (MILES) (MILES)
N 1.729E-06 1.549E-06 1.399E-06 1.273E-06 1.166E-06 NNE 1.128E-06 1.006E-06 9.050E-07 8.202E-07 7.485E-07 NE 8.150E-07 7.243E-07 6.494E-07 5. 867E-07 5.34OE-07 ENE 5.878E-07 5.205E-07 4.652E-07 4.190E-07 3.803E-07 E 5.917E-07 5.230E-07 4.667E-07 4.197E-07 3.804E-07 ESE 4.437E-07 3.919E-07 3.494E-07 3.140E-07 2.843E-07 SE 3.891E-07 3 .436E-07 3.062E-07 2.751E-07 2.491E-07 SSE 4.829E-07 4.267E-07 3.807E-07 3.423E-07 3.102E-07 S 6.424E-07 5.684E-07 5.076E-07 4.569E-07 4.145E-07 SSW 4.576E-07 4.054E-07 3.624E-07 3 .266E-07 2.965E-07 SW 4.976E-07 4 .417E-07 3.955E-07 3.570E-07 3.246E-07 WSW 7.648E-07 6.814E-07 6.125E-07 5.547E-07 5.060E-07 W 1.448E-06 1.299E-06 1.175E-06 1.070E-06 9.809E-07 WNW 1.644E-06 1.479E-06 1.341E-06 1.224E-06 1.124E-06 NW 1.733E-06 1.563E-06 1.416E-06 1.292E-06 1.186E-06 NNW 1.637E-06 1.471E-06 1.332E-06 1.214E-06 1.115E-06 SECTOR 1.7 1.8 1.9 2.0 2.1 (MILES) (MILES) (MILES) (MILES) (MILES)
N 1.074E-06 9.931E-07 9.226E-07 8.604E-07 8.052E-07 NNE 6.867E-07 6.331E-07 5.864E-07 5.453E-07 5.090E-07 NE 4 .886E-07 4.494E-07 4.153E-07 3.854E-07 3 .263E-07 ENE 3.471E-07 3.184E-07 2. 936E-07 2.718E-07 2.526E-07 E 3.467E-07 3.177E-07 2.925E-07 2.705E-07 2.283E-07 ESE 2.590E-07 2.371E-07 2.182E-07 2.017E-07 1.871E-07 SE 2.268E-07 2.076E-07 1.910E-07 1.765E-07 1.637E-07 SSE 2.827E-07 2.590E-07 2.384E-07 2.205E-07 1.407E-07 S 3.780E-07 3.466E-07 3.194E-07 2.955E-07 1.373E-07 SSW 2.706E-07 2.484E-07 2.290E-07 2.121E-07 1.409E-07 SW 2.968E-07 2.727E-07 2.518E-07 2.335E-07 2.173E-07 WSW 4 .639E-07 4.275E-07 3.957E-07 3.678E-07 5.303E-07 W 9.037E-07 8.365E-07 7.777E-07 7.258E-07 1.050E-06 WNW 1.038E-06 9.622E-07 8.960E-07 8.375E-07 1.142E-06 NW 1.095E-06 1.015E-06 9.445E-07 8.826E-07 8.275E-07 NNW 1.028E-06 9.527E-07 8.865E-07 8.281E-07 7.761E-07
ODCM Page: 92 Rev.: 9 Table A-3 (Cont.)
Atmospheric Dispersion (X/Q) as a Function of Distance (s/mr)
SECTOR 2.2 2.3 2.4 2.5 2.6 (MILES) (MILES) (MILES) (MILES) (MILES)
N 7.560E-07 7.118E-07 6.720E-07 6.359E-07 6.033E-07 NNE 4.766E-07 4 .477E-07 4.217E-07 3.982E-07 3.770E-07 NE 3.050E-07 2.859E-07 2.688E-07 2.534E-07 2.395E-07 ENE 2.356E-07 2.205E-07 2.069E-07 1.947E-07 1.837E-07 E 2.127E-07 1.988E-07 1.864E-07 1.752E-07 1.652E-07 ESE 1.743E-07 1.628E-07 1.525E-07 1.433E-07 1.351E-07 SE 1.524E-07 1.424E-07 1.334E-07 1.253E-07 1.181E-07 SSE 1.311E-07 1.225E-07 1.149E-07 1.080E-07 1.018E-07 S 1.280E-07 1.197E-07 1.123E-07 1.056E-07 9.963E-08 SSW 1.314E-07 1.23OE-07 1.154E-07 1.087E-07 1.025E-07 SW 2.030E-07 1.902E-07 1.787E-07 1.683E-07 1.590E-07 WSW 4.964E-07 4.661E-07 4.388E-07 4.142E-07 3 .920E-07 W 9.867E-07 9.296E-07 8.780E-07 8.313E-07 7.891E-07 WNW 1.075E-06 1.014E-06 9.587E-07 9.088E-07 8.636E-07 NW 7.782E-07 7.339E-07 6.939E-07 6.576E-07 6.247E-07 NNW 7.297E-07 6.879E-07 6.502E-07 6.161E-07 5.852E-07 SECTOR 2.7 2.8 2.9 3.0 3.1 (MILES) (MILES) (MILES) (MILES) (MILES)
N 5.734E-07 5.460E-07 5.208E-07 4.976E-07 4.762E-07 NNE 3.576E-07 3.398E-07 3.235E-07 3.086E-07 2.948E-07 NE 2.268E-07 2.152E-07 2.046E-07 1.949E-07 1.859E-07 ENE 1.737E-07 1.645E-07 1.562E-07 1.485E-07 1.415E-07 E 1.560E-07 1.477E-07 1.401E-07 1.331E-07 1.267E-07 ESE 1.275E-07 1.207E-07 1.144E-07 1.087E-07 9.399E-08 SE 1.115E-07 1.054E-07 9.996E-08 9.493E-08 9.031E-08 SSE 9.613E-08 9.099E-08 8.630E-08 8.200E-08 7.805E-08 S 9.415E-08 8.917E-08 8.462E-08 8.044E-08 7.661E-08 SSW 9.697E-08 9. 189E-08 8.725E-08 8.299E-08 7.907E-08 SW 1.505E-07 1.428E-07 1.357E-07 1.291E-07 1.231E-07 WSW 3.716E-07 3.531E-07 3.360E-07 3.204E-07 2.520E-07 W 7.503E-07 7.147E-07 6.820E-07 6.519E-07 5.874E-07 NNW WNW 8.220E-07 7.838E-07 7.487E-07 7.164E-07 7.722E-07 NW 5.945E-07 5.668E-07 5.413E-07 5.178E-07 5.412E-07 5.567E-07 5.307E-07 5.067E-07 4.846E-07 4.642E-07
ODCM Page: 93 Rev.: 9 Table A-3 (Cont.)
Atmospheric Dispersion (y/Q) as a Function of Distance (s/mr)
SECTOR 3.2 3.3 3.4 3.5 3.6 (MILES) (MILES) (MILES) (MILES) (MILES)
N 4 .563E-07 4.379E-07 4.208E-07 4.047E-07 3.899E-07 NNE 2.820E-07 2.702E-07 2.592E-07 2.489E-07 2.395E-07 NE 1.777E-07 1.700E-07 1.629E-07 1.562E-07 1.501E-07 ENE 1.350E-07 1.290E-07 1.234E-07 1.182E-07 1.135E-07 E 1.208E-07 1.154E-07 1.103E-07 1.056E-07 1.013E-07 ESE 8.958E-08 8.550E-08 8.173E-08 7.821E-08 7.499E-08 SE 8.606E-08 8.213E-08 7.849E-08 7.510E-08 7.200E-08 SSE 7.441E-08 7.105E-08 6.794E-08 6.503E-08 6.237E-08 S 7.307E-08 6.980E-08 6.678E-08 6.395E-08 6.136E-08 SSW 7.546E-08 7.212E-08 6.902E-08 6.613E-08 6.348E-08 SW 1.176E-07 1.125E-07 1.077E-07 1.033E-07 9.922E-08 WSW 2.410E-07 2.308E-07 2.214E-07 2.125E-07 2.044E-07 W 5.631E-07 5.406E-07 5.196E-07 4.999E-07 4.818E-07 WNW 7.409E-07 7.118E-07 6.848E-07 6.593E-07 6.359E-07 NW 5.192E-07 4. 987E-07 4.797E-07 4.618E-07 4.454E-07 NNW 4.452E-07 4 .276E-07 4.112E-07 3.958E-07 3.817E-07 SECTOR 3.7 3.8 3.9 4.0 4.1 (MILES) (MILES) (MILES) (MILES) (MILES)
N 3 .759E-07 3 .628E-07 3 .504E-07 3.388E-07 2.981E-07 NNE 2.306E-07 2.222E-07 2.144E-07 2.070E-07 1.819E-07 NE 1.444E-07 1.390E-07 1.339E-07 1.292E-07 1.247E-07 ENE 1.090E-07 1.048E-07 1.009E-07 9.718E-08 9.373E-08 E 9.722E-08 9.342E-08 8. 987E-08 8.653E-08 8.341E-08 ESE 7.196E-08 6.912E-08 6.647E-08 6.399E-08 6.166E-08 SE 6. 908E-08 6.635E-08 6.38OE-08 6.140E-08 5.378E-08 SSE 5.987E-08 5.753E-08 5.533E-08 5.328E-08 5.13SE-08 S 5.892E-08 5.664E-08 5.451E-08 5.251E-08 5.063E-08 SSW 6.098E-08 5.86SE-08 5.646E-08 5.441E-08 5.248E-08 SW 9.537E-08 9.178E-08 8.841E-08 8.525E-08 8.228E-08 WSW 1.967E-07 1.896E-07 1.828E-07 1.765E-07 1.462E-07 W 4.646E-07 4 .485E-07 4.334E-07 4.191E-07 3.043E-07 WNW 6.137E-07 6.929E-07 5.733E-07 5.548E-07 4.18OE-07 NW 4.298E-07 4 .151E-07 4.013E-07 3 .883E-07 3.761E-07 NNW 3.682E-07 3.556E-07 3 .438E-07 3.326E-07 2. 928E-07
ODCM Page: 94 Rev.: 9 Table A-3 (Cont.)
Atmospheric Dispersion (X/Q) as a Function of Distance (s/m3)
SECTOR 4.2 4.3 4.4 4.5 4.6 (MILES) (MILES) (MILES) (MILES) (MILES)
N 2.887E-07 2.798E-07 2.714E-07 2.634E-07 2.559E-07 NNE 1.759E-07 1.703E-07 1.650E-07 1.599E-07 1.552E-07 NE 1.205E-07 1.166E-07 1.128E-07 1.093E-07 1.059E-07 ENE 9.047E-08 8.740E-08 8.451E-08 8.176E-08 7. 921E-08 E 8.046E-08 7.769E-08 7.508E-08 7.260E-08 7.03OE-08 ESE 5.946E-08 5.740E-08 5.545E-08 5.361E-08 5.189E-08 SE 5.186E-08 5.005E-08 4.835E-08 4.673E-08 4 .523E-08 SSE 4. 954E-08 4.783E-08 4 .622E-08 4 .469E-08 4.327E-08 S 4.886E-08 4.719E-08 4 .562E-08 4 .413E-08 4.274E-08 SSW 5.067E-08 4.896E-08 4 .735E-08 4.581E-08 4 .439E-08 SW 7.948E-08 7.684E-08 7.435E-08 7.198E-08 6.978E-08 WSW 1.413E-07 1.368E-07 1.325E-07 1.284E-07 1.246E-07 W 2.948E-07 2.858E-07 2.773E-07 2.691E-07 2.616E-07 WNW 4.051E-07 3. 930E-07 3.815E-07 3.706E-07 3.603E-07 NW 3 .645E-07 3.536E-07 3.432E-07 3.333E-07 3.241E-07 NNW 2.837E-07 2.752E-07 2.671E-07 2.593E-07 2.521E-07 SECTOR 4.7 4.8 4.9 5.0 (MILES) (MILES) (MILES) (MILES)
N 2 .487E-07 2.419E-07 2.354E-07 2.292E-07 NNE 1.507E-07 1.464E-07 1.423E-07 1.384E-07 NE 1.028E-07 9.975E-08 9. 689E-08 9.416E-08 ENE 7.676E-08 7.443E-08 7.223E-08 7.014E-08 E 6.809E-08 6.600E-08 6.402E-08 6.214E-08 ESE 5.025E-08 4.869E-08 4.722E-08 4.582E-08 SE 4.379E-08 4 .244E-08 4 .115E-08 3.992E-08 SSE 4 .191E-08 4. 063E-08 3 .941E-08 3.825E-08 S 4 .141E-08 4. 01SE-08 3 .896E-08 3 .782E-08 SSW 4 .302E-08 4.173E-08 4.050E-08 3.934E-08 WSW 6.767E-08 6.567E-08 6.377E-08 6.196E-08 WSW 1.210E-07 1.175E-07 1.142E-07 1.llOE-07 W 2.543E-07 2.474E-07 2.408E-07 2.345E-07 WNW 3.505E-07 3.411E-07 3.322E-07 3.237E-07 NW 3.152E-07 3.068E-07 2. 987E-07 2. 910E-07 NNW 2.452E-07 2.336E-07 2.323E-07 2.263E-07
ODCM Page: 95 Rev.: 9 Table A-4 Atmospheric Dispersion (D/Q) as a Function of Distance (m 2)
SECTOR 0.2 0.3 0.4 0.5 0.6 (MILES) (MILES) (MILES) (MILES) (MILES)
N 1.396E-07 7.578E-08 4 .836E-08 3 .383E-08 2.516E-08 NNE 1.107E-07 6. 008E-08 3 .834E-08 2.682E-08 1.99SE-08 NE 9.733E-08 5.284E-08 3.372E-08 2.359E-08 1.755E-08 ENE 1.067E-07 5.795E-08 3.698E-08 2.587E-08 1.924E-08 E 1.184E-07 6.429E-08 4 .103E-08 2.870E-08 2.135E-08 ESE 8.865E-08 4.813E-08 3.071E-08 2.149E-08 1.598E-08 SE 9.402E-08 5.105E-08 3.258E-08 2.279E-08 1.695E-08 SSE 1.338E-07 7.266E-08 4.637E-08 3.244E-08 2.413E-08 S 1.429E-07 7.757E-08 4.951E-08 3.463E-08 2.576E-08 SSW 6.094E-08 3.309E-08 2.111E-08 1.477E-08 1.099E-08 SW 7.267E-08 3 .945E-08 2.518E-08 1.761E-08 1.310E-08 WSW 7.117E-08 3.864E-08 2.466E-08 1.725E-08 1.283E-08 W 7.129E-08 3.870E-08 2.470E-08 1.728E-08 1.28SE-08 WNW 6.970E-08 3.784E-08 2.415E-08 1.689E-08 1.256E-08 NW 8.904E-08 4 .834E-08 3.085E-08 2.158E-08 1.605E-08 NNW 9.623E-08 5.225E-08 3.334E-08 2.332E-08 1.735E-08 SECTOR 0.7 0.8 0.9 1.0 1.1 (MILES) (MILES) (MILES) (MILES) (MILES)
N 1.954E-08 1.560E-08 1.277E-08 1.068E-08 5.545E-09 NNE 1.549E-08 1.237E-08 1.013E-08 8.465E-09 4.94SE-09 NE 1.362E-08 1.088E-08 8.907E-09 7.445E-09 4 .350E-09 ENE 1.494E-08 1.193E-08 9.768E-09 8.164E-09 4.770E-09 E 1.658E-08 1.323E-08 1.084E-08 9.058E-09 5.292E-09 ESE 1.241E-08 9.905E-09 8.112E-09 6.781E-09 3.961E-09 SE 1.316E-08 1.051E-08 8.605E-09 7.192E-09 3.361E-09 SSE 1.874E-08 1.496E-08 1.225E-08 1.024E-08 3.480E-09 S 2.OOOE-08 1.597E-08 1.308E-08 1.093E-08 4.128E-09 SSW 8.531E-09 6.810E-09 5.577E-09 4.662E-09 2.521E-09 SW 1.017E-08 8.120E-09 6.651E-09 5.559E-09 2.598E-09 WSW 9.963E-09 7.953E-09 6 .513E-09 5.444E-09 2.678E-09 W 9.980E-09 7.966E-09 6.524E-09 5.453E-09 2.832E-09 WNW 9.757E-09 7.788E-09 6.379E-09 5.332E-09 2 .932E-09 NW 1.246E-08 9.949E-09 8.148E-09 6.811E-09 3.745E-09 NNW 1.347E-08 1. 075E-08 8.807E-09 7.361E-09 4 .047E-09
ODCM Page: 96 Rev.: 9 Table A-4 (Cont.)
Atmospheric Deposition (D/Q) as a Function of Distance (m2)
SECTOR 1.2 1.3 1.4 1.5 1.6 (MILES) (MILES) (MILES) (MILES) (MILES)
N 4.777E-09 4.163E-09 3.664E-09 3.252E-09 2.910E-09 NNE 4 .260E-09 3 .713E-09 3.268E-09 2.900E-09 2.595E-09 NE 3.747E-09 3.265E-09 2.874E-09 2.551E-09 2.283E-09 ENE 4.109E-09 3.581E-09 3.151E-09 2.797E-09 2.503E-09 E 4.559E-09 3.973E-09 3.497E-09 3.104E-09 2.777E-09 ESE 3.413E-09 2.974E-09 2.617E-09 2.323E-09 2. 079E-09 SE 2.896E-09 2.524E-09 2.221E-09 1.971E-09 1.764E-09 SSE 2. 998E-09 2.612E-09 2.299E-09 2.041E-09 1.826E-09 S 3.556E-09 3 .099E-09 2.727E-09 2.421E-09 2.166E-09 SSW 2. 172E-09 1.892E-09 1.666E-09 1.478E-09 1.323E-09 SW 2.238E-09 1.950E-09 1.717E-09 1.524E-09 1.363E-09 WSW 2.307E-09 2.011E-09 1.770E-09 1.571E-09 1.406E-09 W 2.440E-09 2.126E-09 1.871E-09 1.661E-09 1.486E-09 WNW 2 .525E-09 2.201E-09 1.937E-09 1.719E-09 1.538E-09 NW 3 .226E-09 2.811E-09 2.474E-09 2.196E-09 1.965E-09 NNW 3 .487E-09 3. 039E-09 2.674E-09 2.374E-09 2.124E-09 SECTOR 1.7 1.8 1.9 2.0 2.1 (MILES) (MILES) (MILES) (MILES) (MILES)
N 2 .619E-09 2.371E-09 2.158E-09 1.973E-09 1.812E-09 NNE 2.336E-09 2.115E-09 1.925E-09 1.760E-09 1.616E-09 NE 2.055E-09 1.860E-09 1.693E-09 1.548E-09 1.292E-09 ENE 2.253E-09 2. 040E-09 1.856E-09 1.697E-09 1.558E-09 E 2.500E-09 2.263E-09 2.059E-09 1.883E-09 1.572E-09 ESE 1.871E-09 1.694E-09 1.542E-09 1.410E-09 1.294E-09 SE 1.583E-09 1.437E-09 1.308E-09 1.196E-09 1.098E-09 SSE 1.644E-09 1.488E-09 1.354E-09 1.238E-09 7. 816E-10 S 1.950E-09 1.765E-09 1.606E-09 1.469E-09 6.743E-10 SSW 1.191E-09 1.078E-09 9.810E-10 8.969E-10 5.883E-10 SW 1.227E-09 1.111E-09 1.011E-09 9.244E-10 8 .488E-10 WSW 1.265E-09 1.145E-09 1.042E-09 9.530E-10 1.352E-09 W 1.338E-09 1.211E-09 1.102E-09 1.008E-09 1.43OE-09 WNW 1.385E-09 1.254E-09 1.141E-09 1.043E-09 1.393E-09 NW 1.769E-09 1.601E-09 1.457E-09 1.333E-09 1.223E-09 NNW 1.912E-09 1.731E-09 1.575E-09 1.44OE-09 1.322E-09
ODCM Page: 97 Rev.: 9 Table A-4 (Cont.)
Atmospheric Deposition (D/Q) as a Function of Distance (m 2)
SECTOR 2.2 2.3 2.4 2.5 2.6 (MILES) (MILES) (MILES) (MILES) (MILES)
N 1.670E-09 1.544E-09 1.433E-09 1.334E-09 1.245E-09 NNE 1.489E-09 1.377E-09 1.278E-09 1.189E-09 1.110E-09 NE 1.191E-09 1.101E-09 1.022E-09 9.511E-10 8.879E-10 ENE 1.436E-09 1.328E-09 1.233E-09 1.147E-09 1.071E-09 E 1.449E-09 1.340E-09 1.243E-09 1.157E-09 1.080E-09 ESE 1.193E-09 1.103E-09 1.024E-09 9.528E-10 8.895E-10 SE 1.012E-09 9.362E-10 8.687E-10 8.085E-10 7.548E-10 SSE 7.204E-10 6.663E-10 6.183E-10 5.754E-10 5.372E-10 S 6.215E-10 5.749E-10 5.334E-10 4.964E-10 4.634E-10 SSW 5.422E-10 5.015E-10 4.653E-10 4.331E-10 4.043E-10 SW 7.823E-10 7.236E-10 6.714E-10 6.249E-10 5.834E-10 WSW 1.246E-09 1.153E-09 1.070E-09 9.956E-10 9.294E-10 W 1.318E-09 1.219E-09 1.131E-09 1.053E-09 9.827E-10 WNW 1.284E-09 1.188E-09 1.102E-09 1.026E-09 9.575E-10 NW 1.128E-09 1.043E-09 9.678E-10 9.007E-10 8.409E-10 NNW 1.219E-09 1.127E-09 1.046E-09 9.735E-10 9.089E-10 SECTOR 2.7 2.8 2.9 3.0 3.1 (MILES) (MILES) (MILES) (MILES) (MILES)
N 1.165E-09 1.092E-09 1.026E-09 9.666E-10 9.120E-10 NNE 1.039E-09 9.742E-10 9.155E-10 8.621E-10 8.134E-10 NE 8.307E-10 7.789E-10 7.320E-10 6.893E-10 6.504E-10 ENE 1.002E-09 9.396E-10 8.830E-10 8.315E-10 7.845E-lo E 1.011E-09 9.477E-10 8.906E-10 8.387E-10 7.913E-10 ESE 8.322E-10 7.804E-10 7.334E-10 6.906E-10 5.923E-10 SE 7.061E-10 6.622E-10 6.223E-10 5.860E-10 5.529E-10 SSE 5.026E-10 4.713E-10 4.429E-10 4.171E-10 3.935E-10 S 4.336E-10 4.066E-10 3.821E-10 3.598E-10 3.395E-10 SSW 3.782E-10 3.547E-10 3 .333E-10 3 .139E-10 2.961E-10 SW 5.458E-10 5.118E-10 4 .810E-10 4 .529E-10 4.273E-10 WSW 8.695E-10 8.154E-10 7.663E-10 7.216E-10 5.607E-10 W 9.194E-10 8.621E-10 8.102E-10 7.630E-10 6.775E-10 WNW 8.958E-10 8.400E-10 7.894E-10 7.434E-10 7.890E-10 NW 7.867E-10 7.377E-10 6.933E-10 6.528E-10 6.719E-10 NNW 8.503E-10 7.973E-10 7.493E-10 7.056E-10 6.657E-10
ODCM Page: 98 Rev.: 9 Table A-4 (Cont.)
2 Atmospheric Deposition (D/Q) as a Function of Distance (m )
SECTOR 3.2 3.3 3.4 3.5 3.6 (MILES) (MILES) (MILES) (MILES) (MILES)
N 8.620E-10 8.161E-10 7.739E-10 7.347E-10 6.991E-10 NNE 7.688E-10 7.279E-10 6.902E-10 6.552E-10 6.235E-10 NE 6.147E-10 5.820E-10 5.518E-10 5.239E-10 4.985E-10 ENE 7.415E-10 7.020E-10 6.657E-10 6.320E-10 6.014E-10 E 7.479E-10 7.081E-10 6.714E-10 6.374E-10 6.066E-10 ESE 5.598E-10 5.300E-10 5.026E-10 4.771E-10 4.541E-10 SE 5.225E-10 4.947E-10 4.691E-10 4.454E-10 4.238E-10 SSE 3.719E-10 3.521E-10 3.339E-10 3.170E-10 3.016E-10 S 3 .209E-10 3 .038E-10 2.880E-10 2.735E-10 2.602E-10 SSW 2.799E-10 2.650E-10 2.513E-10 2.386E-10 2.270E-10 SW 4 .039E-10 3.824E-10 3 .626E-10 3 .442E-10 3.276E-10 WSW 5.299E-10 5. 017E-10 4.757E-10 4.516E-10 4.298E-10 W 6.403E-10 6.062E-10 5.749E-10 5.458E-20 5.193E-10 WNW 7.457E-10 7.060E-10 6.695E-10 6.356E-10 6.048E-10 NW 6.351E-10 6.013E-10 5.702E-10 5.413E-10 5.151E-10 NNW 6.292E-10 5. 957E-10 5.649E-10 5.363E-10 5.103E-10 SECTOR 3.7 3.8 3.9 4.0 4.1 (MILES) (MILES) (MILES) (MILES) (MILES)
N 6.657E-10 6.34 7E-10 6.059E-10 5.791E-10 5.036E-10 NNE 5.937E-10 5.661E-10 5.404E-10 5.165E-10 4.492E-10 NE 4.747E-10 4.526E-10 4.321E-10 4 .129E-10 3.951E-10 ENE 5.727E-10 5.460E-10 5.212E-10 4.981E-10 4 .766E-10 E 5.776E-10 5.507E-10 5.257E-10 5.024E-10 4.807E-10 ESE 4 .324E-10 4.122E-10 3.935E-10 3.761E-10 3 .598E-10 SE 4.036E-10 3.848E-10 3.673E-10 3.510E-10 3.053E-10 SSE 2.872E-10 2.739E-10 2.614E-10 2.498E-10 2.390E-10 S 2.478E-10 2.363E-10 2.255E-10 2.155E-10 2.062E-10 SSW 2.162E-10 2.061E-10 1.968E-10 1.880E-10 1.799E-10 SW 3.119E-10 2.974E-10 2.839E-10 2.713E-10 2.596E-10 WSW 4.093E-10 3.902E-10 3.725E-10 3.560E-10 2.919E-10 W 4. 945E-10 4.715E-10 4.501E-10 4 .302E-10 3.087E-10 WNW 5.759E-10 5.491E-10 5.242E-10 5.010E-10 3.728E-10 NW 4. 905E-10 4.677E-10 4.464E-10 4 .266E-10 4 .082E-10 NNW 4.895E-10 4.633E-10 4.423E-10 4 .227E-10 3.676E-10
ODCM Page: 99 Rev.: 9 Table A-4 (Cont.)
2 Atmospheric Deposition (D/Q) as a Function of Distance (m )
SECTOR 4.2 4.3 4.4 4.5 4.6 (MILES) (MILES) (MILES) (MILES) (MILES)
N 4.823E-10 4 .624E-10 4 .437E-10 4 .260E-10 4.097E-10 NNE 4 .302E-10 4.124E-10 3.957E-10 3.800E-10 3.654E-10 NE 3.784E-10 3.627E-10 3.480E-10 3.342E-10 3.214E-10 ENE 4.564E-10 4.375E-10 4.198E-10 4.031E-10 3.877E-10 E 4.603E-10 4.413E-10 4.234E-10 4.066E-10 3.910E-10 ESE 3.446E-10 3.303E-10 3.170E-10 3.044E-10 2.927E-10 SE 2.924E-10 2.803E-10 2.690E-10 2.583E-10 2.484E-10 SSE 2.289E-10 2.195E-10 2.106E-10 2. 022E-10 1. 944E-10 S 1.975E-10 1.893E-10 1.817E-10 1.744E-10 1.677E-10 SSW 1.723E-10 1.652E-10 1.585E-10 1.522E-10 1.463E-10 SW 2.486E-10 2.383E-10 2.287E-10 2.196E-10 2.112E-10 WSW 2.796E-10 2.680E-10 2.572E-10 2.469E-10 2.375E-10 W 2.956E-10 2.834E-10 2.719E-l0 2.611E-10 2.511E-10 WNW 3.570E-10 3 .422E-10 3.284E-10 3.153E-10 3. 032E-10 NW 3. 909E-10 3.747E-10 3 .596E-10 3 .453E-10 3 .320E-10 NNW 3.521E-10 3.375E-10 3.239E-l0 3. 1OE-10 2.991E-10 SECTOR 4.7 4.8 4.9 5.0 (MILES) (MILES) (MILES) (MILES)
N 3.941E-10 3.795E-10 3.656E-10 3.525E-10 NNE 3 .515E-10 3.384E-10 3.261E-10 3.144E-10 NE 3.092E-10 2.977E-10 2.868E-10 2.765E-10 ENE 3.729E-10 3.591E-10 3.460E-10 3.336E-10 E 3.762E-10 3 .622E-10 3 .489E-10 3.364E-10 ESE 2.816E-10 2.711E-10 2.612E-10 2.519E-10 SE 2.389E-10 2.300E-10 2.216E-10 2.137E-10 SSE 1.871E-10 1.801E-10 1.73SE-10 1.673E-10 S 1.614E-10 1.554E-10 1.497E-10 1.443E-10 SSW 1.408E-10 1.355E-10 1.306E-10 1.259E-10 SW 2.031E-10 1.956E-10 1.884E-10 1.817E-10 WSW 2.285E-10 2.199E-10 2.119E-10 2.043E-lO W 2.415E-10 2.326E-10 2.241E-10 2.160E-10 WNW 2.917E-10 2. 809E-10 2.706E-10 2.609E-10 NW 3.194E-10 3.075E-10 2.963E-10 2.857E-10 NNW 2.877E-10 2.770E-10 2.669E-10 2.573E-10
ODCM Page: 1oo Rev.: 9 Appendix B LOWER LIMIT OF DETECTION
ODCM Page: 101 Rev.: 9 The lower limit of detection (LLD) is the smallest concentration of radioactive material in a sample that will be detected with a 95 percent probability with a 5 percent probability of falsely concluding that a blank observation represents a "real" signal.
The LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement.
For a measurement system (which may include radiochemical separation) based on gross beta, gross alpha, liquid scintillation, or other analyses where a background count determined by a separate measurement with no sample (or blank sample) is subtracted from the gross sample count to obtain a net count due to sample activity:
1/2 3.3 rb + rb LLD = ts tb (B-1)
(C)(E)(V)(Yc)exp(- XAt)
Where:
LLD = the "a priori" lower limit of detection, as defined above; C = the conversion factor of transformations per unit time per uCi or pCi; E = the detector efficiency; rb = the background count rate in units of transformations per unit time; tb = the counting time of background; ts = the counting time of the sample; V = the sample size, in units of mass or volume; Yc = the fractional radiochemical sample collection or concentration yield (when applicable);
At = for plant effluents, the elapsed time between the midpoint of sample collection and time of counting; for environmental samples, the elapsed time between sample collection (or end of the sample collection period) and time of counting;
= the radioactive decay constant for the radionuclide in question.
ODCM Page: 102 Rev.: 9 For the purpose of routine analyses, count times for both the sample(s) and background(s) are equal. This satisfies the given ODCM Appendix C control for lower limit of detection definition, as the numerator of equation B-1 simplifies to 4.66 Sb, where Sb is the standard deviation of the background count rate or the count rate of a blank sample, as appropriate.
For gamma ray spectroscopy analyses:
At LD exp°0693 1/2 )
LLD = (B-2)
(C)(E) (t) (v) (Yc) (YY)
Where:
LLD = the lower limit of detection, in pCi or pCi per unit mass or volume; C = the conversion factor of transformations per unit time per pCi or pCi; E = the detector efficiency for the energy in question; t = the data collection (counting) time of sample; t1/2 = the half-life of the radionuclide in question; V = the sample size, in units of mass or volume; Yc = the fractional radiochemical, sample collection, or concentration yield (when applicable);
= the yield of the gamma ray in question; At = for plant effluents the elapsed time between midpoint of sample collection and time of counting; for environmental samples, the elapsed time between sample collection (or end of the sample collection period) and the time of counting; Ld = the detection limit k2+2k(N
+ (1+ N)(Bl+B2)+I+o2 f (B-3)
Where:
B1 the number of counts in "nn background channels below the peak due to Compton scattering, etc., determined at the same time a photopeak is measured;
ODCM Page: 103 Rev.: 9 B2 = the number of counts in the "n, background channels above the peak; k = an abscissa of the normal distribution corresponding to confidence level,
= 1.645 at a confidence level of 95%;
I = the measured value of interference in the photopeak of interest due to environmental background, detector contamination, etc.,
determined by a separate measurement with no sample; N = the number of channels in the photopeak of interest; n e the number of background channels on each side of the photopeak of interest; aI = the standard deviation of I.
Typical values of E, V, Y, and At shall be used in the calculation.
In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples).
Analyses shall be performed in such a manner that the LLD's listed in Tables 4.11.1.1.1-1, 4.11.2.1.2-1, and 4.12.1-1 of the ODCM Appendix C controls for the Perry Nuclear Power Plant will be achieved under routine conditions. Occasionally, background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.
ODCM Page: 104 Rev.: 9 Appendix C Controls
ODCM Page: 105 Rev.: 9 INDEX DEFINITIONS SECTION 1.0 DEFINITIONS PAGE ACTIONS........................................................... 1-1 CHANNEL CALIBRATION............................................... 1-1 CHANNEL CHECK ................................................... 1-1 CHANNEL FUNCTIONAL TEST ........................................... 1-1 DOSE EQUIVALENT 1-131 ............................................. 1-1 FREQUENCY NOTATION ................................................ 1-2 GASEOUS RADWASTE TREATMENT (OFF-GAS) SYSTEM ....................... 1-2 LIQUID RADWASTE TREATMENT SYSTEM .................................. 1-2 MEMBER(S) OF THE PUBLIC ........................................... 1-2 MODE ................................................... 1-2 OFFSITE DOSE CALCULATION MANUAL ................................... 1-2 OPERABLE - OPERABILITY ............................................ 1-3 PURGE - PURGING ................................................... 1-3 RATED THERMAL POWER ............................................... 1-3 REPORTABLE EVENT .................................................. 1-3 SITE BOUNDARY .................................................... 1-3 SOURCE CHECK ................................................... 1-3 THERMAL POWER ................................................... 1-3 UNRESTRICTED AREA ................................................. 1-3 VENTILATION EXHAUST TREATMENT SYSTEMS ............................. 1-4 VENTING........................................................... 1-4 Table 1.1, Surveillance Frequency Notation ........................ 1-5 Table 1.2, MODES .................................................. 1-6 PERRY - UNIT 1 i
ODCM Page: 106 Rev.: 9 CONTROLSAND SURVEILLANCEREQUIREMENTS SECTION PAGE 3/4.0 APPLICABILITY .............................................. 3/4 0-1 3/4.3 INSTRUMENTATION Radioactive Liquid Effluent Monitoring Instrumen-tation ..... 3/4 1-1 Table 3.3.7.9-1 Radioactive Liquid Effluent Monitoring Instrumentation .3/4 1-2 Table 4.3.7.9-1 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements .3/4 1-4 Radioactive Gaseous Effluent Monitoring Instrumen-tation ............. 3/4 1-6 Table 3.3.7.10-1 Radioactive Gaseous Effluent Monitoring Instrumentation .3/4 1-7 Table 4.3.7.10-1 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements .3/4 1-10 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration ............................................ 3/4 2-1 Table 4.11.1.1.1-1 Radioactive Liquid Waste Sampling and Analysis Program .3/4 2-2 Dose .. 3/4 2-5 Liquid Radwaste Treatment System ......................... 3/4 2-6 3/4.11.2 GASEOUS EFFLUENTS Dose Rate ................................................ 3/4 2-7 Table 4.11.2.1.2-1 Radioactive Gaseous Waste Sampling and Analysis Program ....................... 3/4 2-8 Dose - Noble Gases ........................................ 3/4 2-11 Dose - Iodine-131, Iodine-133, Tritium and Radionuclides in Particulate Form ...................... 3/4 2-12 PERRY - UNIT 1 ii
ODCM Page: 107 Rev.: 9 CONTROLS AND SURVEILLANCE REQUIREMENTS SECTION PAGE RADIOACTIVE EFFLUENTS (Continued)
Gaseous Radwaste (Off-Gas) Treatment ..................... 3/4 2-13 Ventilation Exhaust Treatment Systems .................... 3/4 2-14 3/4.11.4 TOTAL DOSE ............................................... 3/4 2-15 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM ....................................... 3/4 3-1 Table 3.12.1-1 Radiological Environmental Monitoring Program ................ 3/4 3-3 Table 3.12.1-2 Reporting Levels for Radioactivity Concentrations In Environmental Samples ............................ 3/4 3-9 Table 4.12.1-1 Maximum Values for the Lower Limits of Detection (LLD) In Environmental Samples ............................ 3/4 3-10 3/4.12.2 LAND USE CENSUS .......................................... 3/4 3-13 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM ....................... 3/4 3-14 BASES SECTION PAGE 3/4.0 APPLICABILITY .............................................. B 3/4 0-1 3/4.3 INSTRUMENTATION Radioactive Liquid Effluent Monitoring Instrumentation .......................................... B 3/4 1-1 Radioactive Gaseous Effluent Monitoring Instrumentation .......................................... B 3/4 1-1 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration ............................................ B 3/4 2-1 Dose .............................................. B 3/4 2-1 Liquid Radwaste Treatment System ......................... B 3/4 2-2 PERRY - UNIT 1 iii
ODCM Page: 108 Rev.: 9 BASES SECTION PAGE 3/4.11 RADIOACTIVE EFFLUENTS (Continued) 3/4.11.2 GASEOUS EFFLUENTS Dose Rate ................................................ B 3/4 2-3 Dose - Noble Gases ....................................... B 3/4 2-3 Dose - Iodine-131, Iodine-133, Tritium and Radionuclides in Particulate Form........................ B 3/4 2-4 Gaseous Radwaste Treatment (Offgas) System and Ventilation Exhaust Treatment Systems .................... B 3/4 2-5 3/4.11.4 TOTAL DOSE ............................................... B 3/4 2-6 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM ....................................... B 3/4 3-1 3/4.12.2 LAND USE CENSUS .......................................... B 3/4 3-1 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM ....................... B 3/4 3-2 ADMINISTRATIVE CONTROLS SECTION PAGE 6.9 REPORTING REQUIREMENTS 6.9.1.6 Annual Radiological Environmental Operating Report ....... 4-1 6.9.1.7 Annual Radioactive Effluent Release Report ............... 4-2 6.9.2 SPECIAL REPORTS .......................................... 4-3 6.10 RECORD RETENTION ............................................ 4-3 6.15 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS ........ 4-3 PERRY - UNIT 1 iv
ODCM Page: 109 Rev.: 9 SECTION 1.0 DEFINITIONS
ODCM Page: 110 Rev.: 9 1.0 DEFINITIONS The following terms are defined so that uniform interpretation of these Controls may be achieved. The defined terms appear in capitalized type and shall be applicable throughout these Controls.
ACTIONS ACTIONS shall be that part of a Control that prescribes remedial measures to be taken under designated conditions.
CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, display and trip functions, and shall include the CHANNEL FUNCTIONAL TEST.
The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping or total channel steps so that the entire channel is calibrated.
CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.
CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY, including required alarm, interlock, display, and trip functions and channel failure trips. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is tested.
DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries per gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present.
The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, AEC, 1962, "Calculation of Distance Factors for Power and Test Reactor Sites."
PERRY - UNIT 1 1-1I
ODCM Page: 111 Rev.: 9 DEFINITIONS FREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.
GASEOUS RADWASTE TREATMENT (OFF-GAS) SYSTEM THE GASEOUS RADWASTE TREATMENT (OFF-GAS) SYSTEM is the system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system off-gasses from the main condenser evacuation system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
LIQUID RADWASTE TREATMENT SYSTEM The LIQUID RADWASTE TREATMENT SYSTEM is any process or control equipment used to reduce the amount or concentration of liquid radioactive materials prior to their discharge to UNRESTRICTED AREAS. It involves all the installed and available liquid radwaste management system equipment, as well as their controls, power instrumentation, and services that make the system functional.
MEMBER OF THE PUBLIC MEMBER OF THE PUBLIC means any individual except when that individual is receiving an OCCUPATIONAL DOSE.
MODE A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.2 with fuel in the reactor vessel.
OCCUPATIONAL DOSE OCCUPATIONAL DOSE means the dose received by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation or to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person.
Occupational dose does not include doses received from background radiation, from any medical administration the individual has received, from exposure to individuals administered radioactive material and released under § 35.75, from voluntary participation in medical research programs, or as a member of the public.
PERRY - UNIT 1 1-2
ODCM Page: 112 Rev.: 9 DEFINITIONS OFFSITE DOSE CALCULATION MANUAL (ODCM)
The OFFSITE DOSE CALCULATION MANUAL shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm/trip setpoints, and in the conduct of the radiological environmental monitoring program. The ODCM shall also contain the Radioactive Effluent Controls Program required by Technical Specification 5.5.4, the Radiological Environmental Monitoring Programs and descriptions of the information that should be included in the Annual Radioactive Effluent Release Report required by Technical Specifications 5.6.2 and 5.6.3.
OPERABLE - OPERABILITY A system, subsystem, division, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified functions and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication and other auxiliary equipment that are required for the system, subsystem, division, component or device to perform its specified safety function(s) are also capable of performing their related support functions.
PURGE - PURGING PURGE OR PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
RATED THERMAL POWER -
RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3758 MWT.
REPORTABLE EVENT A REPORTABLE EVENT shall be any of those conditions specified in 10CFR50.73.
SITE BOUNDARY The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.
SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.
THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
PERRY - UNIT 1 1-3
ODCM Page: 113 Rev.: 9 DEFINITIONS UNRESTRICTED AREA An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of MEMBERS OF THE PUBLIC from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.
VENTILATION EXHAUST TREATMENT SYSTEMS A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components provided the ESF system is not utilized to treat normal releases.
VENTING VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.
PERRY - UNIT 1 1-4
ODCM Page: 114 Rev.: 9 TABLE 1.1 SURVEILLANCE FREQUENCY NOTATION NOTATION FREQUENCY S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
W At least once per 7 days.
M At least once per 31 days.
Q At least once per 92 days.
SA At least once per 184 days.
A At least once per 366 days.
R At least once per 24 months.
S/U Prior to each reactor startup.
P Completed prior to each release.
4H Every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when required.
N.A. Not applicable.
PERRY - UNIT 1 1-5
ODCM Page: 115 Rev.: 9 TABLE 1.2 MODES REACTOR MODE AVERAGE REACTOR MODE TITLE SWITCH POSITION COOLANT TEMPERATURE 2 POWER OPERATION Run NA 2 STARTUP Refuel(a) or Startup/Hot NA Standby 3 HOT SHUTDOWN(a) Shutdown > 200 0F 4 COLD SHUTDOWN(a) Shutdown
- 200 0F 5 REFUELING(b) Shutdown or Refuel NA (a) All reactor vessel head closure bolts fully tensioned.
(b) One or more reactor vessel head closure bolts less than fully tensioned.
PERRY - UNIT 1 1-6
ODCM Page: 116 Rev.: 9 SECTIONS 3.0 and 4.0 CONTROLS AND SURVEILLANCE REQUIREMENTS
ODCM Page: 117 Rev.: 9 3/4.0 APPLICABILITY CONTROLS 3.0.1 Controls shall be met during the MODES or other conditions specified in the Applicability except as provided in Control 3.0.2.
3.0.2 Upon discovery of a failure to meet a Control, the requirements of the Actions shall be met except as provided in Control 3.0.5. If the Control is met or is no longer applicable prior to expiration of the specified time interval(s), completion of the Action(s) is not required, unless otherwise stated.
3.0.3 When a Control is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, the unit shall be placed in a MODE or other specified condition in which the Control is not applicable. Action shall be initiated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to place the unit, as applicable, in:
- a. MODE 2 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />;
- b. MODE 3 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />; and
- c. MODE 4 within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />.
Exceptions to this Control are stated in the individual Controls.
Where corrective measures are completed that permit operation in accordance with the Control or ACTIONS, completion of the actions required by Control 3.0.3 is not required.
Control 3.0.3 is only applicable in MODES 1, 2, and 3.
3.0.4 When a Control is not met, entry into a MODE or other specified condition in the Applicability shall not be made except when the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time.
This Control shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS, or that are part of a shutdown of the unit.
Exceptions to this Control are stated in the individual Controls. These exceptions allow entry into MODES or other specified conditions in the Applicability when the associated ACTIONS to be entered allow unit operation in the MODE or other specified condition in the Applicability only for a limited period of time.
Control 3.0.4 is only applicable for entry into a MODE or other specified condition in the Applicability in MODES 1, 2, and 3.
3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to Control 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.
PERRY - UNIT 1 3/4 0-1
ODCM Page: 118 Rev.: 9 3/4.0 APPLICABILITY SURVEILLANCE REQUIREMENT (SRI 4.0.1 SRs shall be met during the MODES or other specified conditions in the Applicability for individual Controls, unless otherwise stated in the SR.
Failure to meet a Surveillance, whether such failure is experienced during the performance of the surveillance or between performances of the Surveillance, shall be failure to meet the Control. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the Control except as provided in SR 4.0.3. Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.
4.0.2 The specified frequency for-each SR is met if the Surveillance is performed within 1.25 times the interval specified in the frequency, as measured from the previous performance or as measured from the time a specified condition of the frequency is met.
If a completion time for an action requires periodic performance on a "once per ... " basis, the above frequency extension applies to each performance after the initial performance.
Exceptions to this SR are stated in the individual SR's.
4.0.3 If it is discovered that a Surveillance was not performed within its specified frequency, then compliance with the requirement to declare the Control not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified frequency, whichever is less. This delay period is permitted to allow performance of the Surveillance.
If the Surveillance is not performed within the delay period, the Control must immediately be declared not met, and the applicable ACTION(s) must be entered.
When the Surveillance is performed within the delay period and the Surveillance is not met, the Control must immediately be declared not met, and the applicable ACTION(s) must be entered.
4.0.4 Entry into a MODE or other specified condition in the Applicability of a Control shall not be made unless the Control's Surveillances have been met within their specified frequency. This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.
SR 4.0.4 is only applicable for entry into a MODE or other specified condition in the Applicability in MODES 1, 2, and 3.
PERRY - UNIT 1 3/4 0-2
ODCM Page: 119 Rev.: 9 3/4.3 INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.7.9 In accordance with Perry Nuclear Power Plant Unit 1 TS 5.5.4.a, the radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3.7.9-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Control 3.11.1.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).
APPLICABILITY: At all times.
ACTION:
- a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above Control, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable, or change the setpoint so it is acceptably conservative.
- b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.9-1. Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain why this inoperability was not corrected in a timely manner in the next Annual Radioactive Effluent Release Report.
- c. The provisions of Control 3.0.3 are not applicable.
SURVEILLANCE REOUIREMENTS 4.3.7.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7.9-1.
PERRY - UNIT 1 3/4 1-1
ODCM Rev. : 9 Page: 120 TABLE 3.3.7.9-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION
- 1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
- a. Liquid Radwaste Discharge Radiation Monitor - 1 110 ESW Discharge
- 2. GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE
- a. Emergency Service Water Loop A Radiation Monitor 1 111
- b. Emergency Service Water Loop B Radiation Monitor 1 111
- 3. FLOW RATE MEASUREMENT DEVICES
- a. Radwaste High-Flow Discharge Header Flow 1 112
- b. Service Water Discharge Header Flow Monitor 1 113
- c. Unit 1 Emergency Service Water Header Flow Monitor or 1 113 individual ESW HX Monitors
- 1) Emergency Service Water Flow Monitor, or
PERRY - UNIT 1 3/4 1-2 D D
ODCM Page: 121 Rev.: 9 TABLE 3.3.7.9-1 (Continued)
RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION ACTION STATEMENTS ACTION 110 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases from this pathway may continue provided that prior to initiating a release:
- a. At least two independent samples are analyzed in accordance with Control 4.11.1.1.1, and
- b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 111 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 107- microcuries/ml.
ACTION 112 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the discharge valve position is verified to be consistent with the flow rate provisions of the release permit at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Prior to initiating another release, at least two technically qualified members of the Facility Staff shall independently verify the discharge line valving and that the discharge valve position corresponds to the desired flow rate.
Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 113 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump performance curves generated in place as well as other curves generated using pump performance may be used to estimate flow.
PERRY - UNIT 1 3/4 1-3
ODCM Rev.: 9 Page: 122 TABLE 4.3.7.9-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL FLOW SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CHECK CALIBRATION TEST
- 1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
- a. Liquid Radwaste Discharge Radiation D N/A P R (3) Q (1)
Monitor - ESW Discharge
- 2. GROSS BETA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE
- a. Emergency Service Water Loop A Radiation D N/A M R (3) Q (2)
Monitor
- b. Emergency Service Water Loop B Radiation D N/A M R (3) Q (2)
Monitor
- 3. FLOW RATE MEASUREMENT DEVICES
- a. Radwaste High-Flow Discharge Header Flow D(4) N/A N/A R Q
- b. Service Water Discharge Header Flow D(4) N/A N/A R Q
- c. Unit 1 Emergency Service Water Header Flow
- 1) Emergency Service Water Flow, or D (4) N/A N/A R Q
)
ODCM Page: 123 Rev.: 9 TABLE 4.3.7.9-1 (Continued)
RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATION (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm/trip setpoint.
- 2. Instrument indicates a downscale failure.
- 3. Instrument controls not set in operate mode except in high voltage position.
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm setpoint.
- 2. Instrument indicates a downscale failure.
- 3. Instrument controls not set in operate mode, except in high voltage position.
(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.
(4) CHANNEL CHECK shall consist of verifying indication of flow. A CHANNEL CHECK shall be made initially and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days when continuous, periodic or batch releases occurs. Pump performance curves may be used to verify the indication of flow from flow instrumentation.
(5) FLOW CHECK shall consist of verifying indication of flow by summing the individual RHR, ECC and DG heat exchanger flows. A FLOW CHECK shall be made initially, prior to securing ESW pumps, at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during a Liquid Radwaste discharge, and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during operation of ESW pumps.
PERRY - UNIT 1 3/4 1-5
ODCM Page: 124 Rev.: 9 INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.7.10 In accordance with Perry Nuclear Power Plant Unit 1 TS 5.5.4.a, the radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3.7.10-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Control 3.11.2.1 are not exceeded. The alarm/trip setpoints of applicable channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.
APPLICABILITY: As shown in Table 3.3.7.10-1 ACTION:
- a. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, declare the channel inoperable, or change the setpoint so it is acceptably conservative.
- b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.10-1. Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain why this inoperability was not corrected in a timely manner in the next Annual Radioactive Effluent Release Report.
- c. The provisions of Control 3.0.3 are not applicable.
SURVEILLANCE REOUIREMENTS 4.3.7.10 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7.10-1.
PERRY - UNIT 1 3/4 1-6
ODCM Rev.: 9 Page: 125 TABLE 3.3.7.10-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION
- 1. OFF-GAS VENT RADIATION MONITOR
- a. Noble Gas Activity Monitor 1
- 121
- b. Iodine Sampler (1) 1
- 122
- c. Particulate Sampler (a) a 122
- d. Effluent System Flow Rate Monitor 1 123
- e. Sampler Flow Rate Monitor (Victoreen 1 123 Flow Monitor)
- 2. UNIT 1 VENT RADIATION MONITOR
- a. Noble Gas Activity Monitor <L02211> 1 1, 2, 3 121, 125 4, 5 121
- b. Iodine Sampler (1) 1 122
- c. Particulate Sampler (1) 1 122
- d. Effluent System Flow Rate Monitor 1 123
- e. Sampler Flow Rate 1 123 Monitor (Victoreen Flow Monitor)
(1) This encompasses the isokinetic and Victoreen photohelics.
PERRY - UNIT 1 3/4 1-7
ODCM Rev.: 9 Page: 126 TABLE 3.3.7.10-1 (Continued)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION
- 3. UNIT 2 VENT RADIATION MONITOR
- a. Noble Gas Activity Monitor 1
- 121
- b. Iodine Sampler (1) 1 122
- c. Particulate Sampler (1) 1 122
- d. Effluent System Flow Rate Monitor 1
- 123
- e. Sampler Flow Rate Monitor (Victoreen 1
- 123 Flow Monitor)
- 4. TURBINE BUILDING/HEATER BAY VENT RADIATION MONITOR
- a. Noble Gas Activity Monitor <L02211> 1
- 121
- b. Iodine Sampler (1) 1 122
- c. Particulate Sampler (1) 1 122
- d. Effluent System Flow Rate Monitor 1 123
- e. Sampler Flow Rate Monitor (Victoreen 1 123 Flow Monitor)
(1) This encompasses the isokinetic and Victoreen photohelics.
PERRY - UNIT 1 3/4 1-8
) 9
ODCM Page: 127 Rev.: 9 TABLE 3.3.7.10-1 (Continued)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TABLE NOTATION
- At all times.
- During main condenser offgas treatment system operation.
ACTION 121 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for principal gamma emitters as required by Table 4.11.2.1.2-1.
ACTION 122 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided samples are continuously collected within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> with auxiliary sampling equipment as required by Table 4.11.2.1.2-1. If the inoperability is due to failure of the AMC skid, the Victoreen skid alone can be used as the auxiliary sampling equipment for a maximum of 30 consecutive days. <L02211> Loss of the isokinetic flow monitor constitutes inoperability of particulate and iodine channels (b, c).
ACTION 123 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent release via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. This action applies to both the effluent system flow and victoreen sample flow (d, e).
ACTION 124 - NOT USED ACTION 125 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, except as a result of a non-conservative setpoint, immediately suspend operation of the Containment Vessel and Drywell Purge (M14) system. Prior to resuming M14 System operation, ensure compliance with Control 3.11.2.1 requirements. If Control 3.11.2.1 compliance is met, operation of the M14 System may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and analyzed for principal gamma emitters, as required by Table 4.11.2.1.2-1.
PERRY - UNIT 1 3/4 1-9
ODCM Rev.: 9 Page: 128 TABLE 4.3.7.10-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED
- 1. OFFGAS VENT RADIATION MONITOR
- a. Noble Gas Activity Monitor D M R (2) Q (1)
- b. Iodine Sampler W(4) N.A. N.A. N.A.
- c. Particulate Sampler W(4) N.A. N.A. N.A.
- d. Effluent System Flow Rate Monitor D N.A. R Q
- e. Sampler Flow Rate Monitor D N.A. R Q
- 2. UNIT 1 VENT RADIATION MONITOR
- a. Noble Gas Activity Monitor D M R(2) Q (1)
- b. Iodine Sampler W (4) N.A. N.A. N.A.
- c. Particulate Sampler W (4) N.A. N.A. N.A.
- d. Effluent System Flow Rate Monitor D N.A. R Q
- e. Sampler Flow Rate Monitor D N.A. R Q PERRY - UNIT 1 3/4 1-10 j)
01DCM Rev.: 9 Page: 129 TABLE 4.3.7.10-1 (Continued)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED
- 3. UNIT 2 VENT RADIATION MONITOR
- a. Noble Gas Activity Monitor D M R (2) Q (1)
- b. Iodine Sampler W(4) N.A. N.A. N.A.
- c. Particulate Sampler W (4) N.A. N.A. N.A.
- d. Effluent System Flow Rate Monitor D N.A. R Q
- e. Sampler Flow Rate Monitor D N.A. R Q
- 4. TURBINE BUILDING/HEATER BAY VENT RADIATION MONITOR
- a. Noble Gas Activity Monitor D M R (2) Q (1) *
- b. Iodine Sampler W(4) N.A. N.A. N.A. *
- c. Particulate Sampler W(4) N.A. N.A. N.A. *
- d. Effluent System Flow Rate Monitor D N.A. R Q *
- e. Sampler Flow Rate Monitor D N.A. R Q
- PERRY - UNIT 1 3/4 1-11
.9 J
ODCM Page: 130 Rev.: 9 TABLE 4.3.7.10-1 (Continued)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATION
- At all times.
- During main condenser offgas treatment system operation.
(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm setpoint.
- 2. Instrument indicates a downscale failure.
- 3. Instrument controls not set in operate mode.
(2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST.
These standards shall permit calibrating the system over its intended energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.
(3) NOT USED (4) The iodine cartridges and particulate filters will be changed at least once per 7 days. Performance of this CHANNEL CHECK does not render the system inoperable, and the applicable ACTION statements need not be entered.
PERRY - UNIT 1 3/4 1-12
ODCM Page: 131 Rev.: 9 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION CONTROLS 3.11.1.1 In accordance with Perry Nuclear Power Plant TS 5.5.4.b and c, the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure 3.2-1) shall be limited to the concentrations specified in 10CFR20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved and entrained noble gases, the concentration shall be limited to 2 x 10-4 microcuries/ml total activity.
APPLICABILITY: At all times.
ACTION:
With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits.
SURVEILLANCE REOUIREMENTS 4.11.1.1.1 The radioactivity content of each batch of radioactive liquid waste shall be determined prior to release by sampling and analysis in accordance with Table 4.11.1.1.1-1. The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 3.11.1.1.
4.11.1.1.2 Post-release analyses of samples composited from batch releases shall be performed in accordance with Table 4.11.1.1.1-1. The results of the radioactivity analysis shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Control 3.11.1.1.
4.11.1.1.3 Continuous releases of radioactive liquid effluents shall be sampled and analyzed in accordance with Table 4.11.1.1.1-1. The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Control 3.11.1.1.
PERRY - UNIT 1 3/4 2-1
ODCM Page: 132 Rev.: 9 TABLE 4.11.1.1.1-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Type of Lower Limit Liquid Release Sampling Analysis Activity of Detection Type Frequency Frequency Analysis (LLD)
(PCi/ml) a A. Batch Waste p P Principal Gamma 5x10 7 Release Each batch Each batch Emittersd Tanks' 1-131 1x10'-
P M Dissolved and 1x10-5 One Batch/M Entrained Gases (Gamma emitters)
P M H-3 1x10-5 Each Batch Compositeb Gross Alpha 3x10-7 P Q Sr-89, Sr-90 5x10-8 Each Batch Compositeb Fe-55 1x10-6 B. Continuous D W Principal Gamma 5x10-7 Releases' Grab Compo- Emittersd RHR Heat Sampled, sites b__9 Exchanger ESW Outlet 1-131 1x10-6 or M35 Drains 9 mg M Dissolved and lx10'5 Grab Sample Entrained Gases (Gamma emitters)
D M H-3 1x10X5 9
Grab Sample Compositeb_9 Gross Alpha 1x10-7 8
9 Grab Sample Compositeb.9
<R00449>
Fe-55 lXi O-6 PERRY - UNIT 1 3/4 2-2
ODCM Page: 133 Rev.: 9 TABLE 4.11.1.1.1-1 (Continued)
RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION
- a. The LLD is the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an la posteriori" (after the fact) limit for a particular measurement.
For a particular measurement system (which may include radiochemical separation):
LLD = 4.66Sb (E)(V)(2. 22xl 0') (Y)exp(- ,Apt) where LLD is the "a priori" lower limit of detection as defined above (as pCi per unit mass or volume).
Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)
E is the counting efficiency (as counts per disintegration)
V is the sample size (in units of mass or volume) 2.22 x 106 is the number of disintegrations per minute per microcurie Y is the fractional radiochemical yield (when applicable)
A is the radioactive decay constant for the particular radionuclide (sec-1)
At is the elapsed time between sample collection (or end of the sample collection period) and time of counting (sec)
Typical values of E, V, Y and At should be used in the calculation.
PERRY - UNIT 1 3/4 2-3
ODCM Page: 134 Rev.: 9 TABLE 4.11.1.1.1-1 (Continued)
RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION (Continued)
- b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.
- c. A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.
- d. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141. Ce-144 shall also be measured, but with an LLD of 5x10-6 . This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported in the Annual Radioactive Effluent Release Report pursuant to Control 6.9.1.7 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.
- e. A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release. Sampling/Analysis of RHR Heat Exchanger is only applicable when there is ESW flow thru the RHR Heat Exchanger.
- f. Sampling and analysis is required of the RHR heat exchanger ESW outlet every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the samples indicate levels greater than LLD.
- g. Sampling is only required for M35 drains, when the M35 drains have been lined up to storm drains. If activity other than tritium or naturally occurring isotopes is detected in the M35 drains, then these drains shall be lined up to radwaste.
PERRY - UNIT 1 3/4 2-4
ODCM Page: 135 Rev.: 9 RADIOACTIVE EFFLUENTS DOSE CONTROLS 3.11.1.2 In accordance with Perry Nuclear Power Plant Unit 1 TS 5.5.4.d and e, the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS (see Figure 3.2-1) shall be limited:
- a. During the current quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ; and
- b. During the current year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.
APPLICABILITY: At all times.
ACTION:
- a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the corrective actions to be taken to ensure that future releases will be in compliance with the above limits.
- b. The provisions of Control 3.0.3 are not applicable.
SURVEILLANCE REOUIREMENTS 4.11.1.2 Dose Calculations. Cumulative dose contributions from liquid effluents for the current quarter and the current year shall be determined in accordance with the methodology and parameters of the ODCM at least once per 31 days.
PERRY - UNIT 1 3/4 2-5
ODCM Page: 136 Rev.: 9 RADIOACTIVE EFFLUENTS LIQUID RADWASTE TREATMENT SYSTEM CONTROLS 3.11.1.3 In accordance with Perry Nuclear Power Plant Unit 1 TS 5.5.4.f, the LIQUID RADWASTE TREATMENT SYSTEM shall be OPERABLE and appropriate portions of the system shall be used to reduce the release of radioactivity when the projected doses due to the liquid effluent from each reactor unit to UNRESTRICTED AREAS (see Figure 3.2-1) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ, in a 31-day period.
APPLICABILITY: At all times.
ACTION:
- a. With radioactive liquid waste being discharged without treatment and in excess of the above limits, and any portion of the liquid radwaste treatment system not in operation, prepare and submit to the Commission, within 30 days pursuant to Control 6.9.2, a Special Report which includes the following information:
- 1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability, and
- 2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. Summary description of action(s) taken to prevent a recurrence.
- b. The provisions of Control 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases from each reactor unit to UNRESTRICTED AREAS shall be projected at least once per 31 days, in accordance with methodology and parameters in the ODCM.
4.11.1.3.2 The installed LIQUID RADWASTE TREATMENT SYSTEM shall be demonstrated OPERABLE by meeting Controls 3.11.1.1 and 3.11.1.2.
PERRY - UNIT 1 3/4 2-6
ODCM Page: 137 Rev.: 9 RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE CONTROLS 3.11.2.1 In accordance with Perry Nuclear Power Plant Unit 1 TS 5.5.4.c and g, the dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 3.2-1) shall be limited to the following:
- a. For noble gases: Less than or equal to 500 mrems/yr to the whole.
body and less than or equal to 3000 mrems/yr to the skin, and
- b. For all iodine-131, iodine-133, tritium and all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.
APPLICABILITY: At all times.
ACTION:
With the dose rate(s) exceeding the above limits, immediately decrease the release rate(s) to within the above limit(s).
SURVEILLANCE REOUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters of the ODCM.
4.11.2.1.2 The dose rate due to iodine-131, iodine-133, tritium and to radionuclides in particulate form with half lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11.2.1.2-1.
PERRY - UNIT 3/4 2-7
ODCM Rev. : 9 Page: 138 TABLE 4.11.2.1.2-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM LOWER LIMIT OF SAMPLING ANALYSIS TYPE OF DETECTION (LLD) (a)
GASEOUS RELEASE PATH FREQUENCY FREQUENCY ACTIVITY ANALYSIS (gCi/mL)
A. Containment Vessel Each PURGE (b) Each PURGElb) Principal Gamma lx10 and Drywell Purge and VENT and VENT Emitters (e)
(M14) System, and Grab Sample Combustible Gas Control (M15) System 6
M M H-3 1x10 Grab Sample B. Offgas Vent, Unit 1 MMb) M(b) Principal Gamma 1x10-4 Vent, Unit 2 Vent, Grab Sample Emitters(be) and Turbine Bldg/Heater H-3 -6 Bay Vent lx10 12 C. All Release Paths as Continuous 'd) w(C) I-131 -x10 listed in B above Charcoal Sample I-133 lxlO -10 Continuous 'd) W(c) Principal Gamma lxlO-11 Particulate Emitters (
Sample Continuous WdI M Gross Alpha lx11 Composite Par-ticulate Filter Continuous (d) Q Sr-89, Sr-90 lxlO 11 Composite Par-ticulate Filter Continuous (d) Noble Gas Noble Gases lxl6 Monitor(f) Gross Beta or Gamma (Xe-133 equivalent)
PERRY - UNIT 1 3/4 2-8
ODCM Page: 139 Rev.: 9 TABLE 4.11.2.1.2-1 (Continued)
RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION
- a. The LLD'is the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95t probability with only 5t probability of falsely concluding that a blank observation represents a "real" signal.
It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement.
For a particular measurement system (which may include radiochemical separation):
LLD = 4.66 Sb (E ) (V) (2.22x106) (y)exp(- XAt) where LLD is the "a priori" lower limit of detection as defined above (as pCi per unit mass or volume).
Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)
E is the counting efficiency (as counts per disintegration)
V is the sample size (in units of mass or volume) 2.22 x 106 is the number of disintegrations per minute per microcurie Y is the fractional radiochemical yield (when applicable)
X is the radioactive decay constant for the particular radionuclide (sec-2)
At is the elapsed time between sample collection (or end of the sample collection period) and time of counting (sec)
Typical values of E, V, Y and At should be used in the calculation.
PERRY - UNIT 1 3/4 2 -9
ODCM Page: 140 Rev.: 9 TABLE 4.11.2.1.2-1 (Continued)
RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION (Continued)
- b. Analyses shall also be performed following startup, shutdown, or a THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER within a one hour period. This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.
- c. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing or after removal from sampler.
Sampling and analyses shall also be performed at least daily (2 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in one hour. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLD's may be increased by a factor of 10. This requirement does not apply if:
(1) Analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) The noble gas monitor shows that effluent activity has not increased more than a factor of 3. If the noble gas monitor is not operable, then a grab sample may be used to demonstrate that activity has not increased by a factor of 3.
- d. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Control 3.11.2.1, 3.11.2.2 and 3.11.2.3.
- e. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported in the Annual Radioactive Effluent Release Report pursuant to Control 6.9.1.7 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.
- f. Sampling and analysis of gaseous release points shall be performed initially whenever a high alarm setpoint is exceeded or whenever two or more of the alert setpoints are exceeded. If the high alarm setpoint or two or more of the alert setpoints continue to be exceeded, verify at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> via the radiation monitors that plant releases are below the Control 3.11.2.1 dose rate limits and sampling and analysis shall be performed at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
PERRY - UNIT 3/4 2-10
ODCM Page: 141 Rev.: 9 RADIOACTIVE EFFLUENTS DOSE - NOBLE GASES CONTROLS 3.11.2.2 In accordance with Perry Nuclear Power Plant Unit 1 TS 5.5.4.e and h, the air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site to areas at and beyond the SITE BOUNDARY (see Figure 3.2-1) shall be limited to the following:
- a. During the current quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation; and
- b. During the current year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
APPLICABILITY: At all times.
ACTION:
- a. With the calculated air dose from the radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to ensure that future releases will be in compliance with Control 3.11.2.2.
- b. The provisions of Control 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.2 Dose Calculations. Cumulative dose contributions for noble gases for the current quarter and current year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
PERRY - UNIT 1 3/4 2 -11
ODCM Page: 142 Rev.: 9 RADIOACTIVE EFFLUENTS DOSE - IODINE-131, IODINE-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM CONTROLS 3.11.2.3 In accordance with Perry Nuclear Power Plant Unit 1 TS 5.5.4.e and i, the dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium and radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, from the site to areas at and beyond the SITE BOUNDARY (see Figure 3.2-1) shall be limited to the following:
- a. During the current quarter: Less than or equal to 7.5 mrem to any organ; and
- b. During the current year: Less than or equal to 15 mrem to any organ.
APPLICABILITY: At all times.
ACTION:
- a. With the calculated dose from the release of iodine-131, iodine-133, tritium and radionuclides in particulate form, with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce releases and the proposed corrective actions to be taken to ensure that future releases will be in compliance with Control 3.11.2.3.
- b. The provisions of Control 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.3 Dose Calculations. Cumulative dose contributions from iodine-131, iodine-133, tritium and radionuclides in particulate form with half-lives greater than 8 days for the current quarter and current year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
PERRY - UNIT 1 3/4 2-12
ODCM Page: 143 Rev.: 9 RADIOACTIVE EFFLUENTS GASEOUS RADWASTE (OFF-GAS) TREATMENT CONTROLS 3.11.2.4 The GASEOUS RADWASTE TREATMENT (OFFGAS) SYSTEM shall be in operation*. <L02211> The Charcoal bypass mode shall not be used unless the off-gas post-treatment radiation monitor is OPERABLE.
APPLICABILITY: Whenever the main condenser air ejector evacuation system is in operation.
ACTION:
- a. With gaseous radwaste from the main condenser air ejector system being discharged without treatment for more than 7 consecutive days, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report which includes the following information:
- 1. Explanation of why gaseous radwaste was being discharged without treatment, identification of the inoperable equipment or subsystems which resulted in gaseous radwaste being discharged without treatment, and the reason for inoperability.
- 2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. Summary description of action(s) taken to prevent a recurrence.
- b. The provisions of Control 3.0.3 are not applicable.
SURVEILLANCE REOUIREMENTS 4.11.2.4 The readings of relevant instrumentation shall be checked at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the main condenser air ejector is in use to ensure that the gaseous radwaste treatment system is functioning.
- - Flow directed through the adsorber beds. <L02211>
PERRY - UNIT 1 3/4 2-13
ODCM Page: 144 Rev.: 9 RADIOACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEMS CONTROLS 3.11.2.5 The VENTILATION EXHAUST TREATMENT SYSTEMS shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected dose due to gaseous effluent releases from each reactor unit to areas at and beyond the SITE BOUNDARY (see Figure 3.2-1) in a 31 day period would exceed 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.
APPLICABILITY: At all times.
ACTION:
- a. With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report which includes the following information:
- 1. Explanation of why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems which resulted in gaseous radwaste being discharged without treatment, and the reason for the inoperability,
- 2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. Summary description of action(s) taken to prevent a recurrence.
- b. The provisions of Control 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.5.1 Doses due to gaseous releases from each reactor unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM.
4.11.2.5.2 The installed VENTILATION EXHAUST TREATMENT SYSTEMS shall be demonstrated OPERABLE by meeting Controls 3.11.2.1 and 3.11.2.3.
PERRY - UNIT 1 3/4 2-14
ODCM Page: 145 Rev.: 9 RADIOACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE CONTROLS 3.11.4 In accordance with Perry Nuclear Power Plant Unit 1 TS 5.5.4.j, the current year dose or dose commitment to any MEMBER of THE PUBLIC, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.
APPLICABILITY: At all times.
ACTION:
- a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Control 3.11.1.2a., 3.11.1.2b., 3.11.2.2a., 3.11.2.2b., 3.11.2.3a, or 3.11.2.3b., calculations shall be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the above limits of Control 3.11.4 have been exceeded.
- 1. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Control 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits.
- 2. This Special Report, as defined in 10CFR20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the current year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.
- 3. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40CFRl90 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40CFRl90. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
- b. The provisions of Control 3.0.3 are not applicable.
PERRY - UNIT 3/4 2 -15
ODCM Page: 146 Rev.: 9 SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Controls 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the ODCM.
4.11.4.2 If the cumulative dose contributions exceed the limits defined in 3.11.4, ACTION a, cumulative dose contributions from direct radiation from unit operation including outside storage tanks shall be determined in accordance with the methodology and parameters in the ODCM.
PERRY - UNIT 1 3/4 2-16
ODCM Page: 147 Rev.: 9 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM CONTROLS 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12.1-1.
APPLICABILITY: At all times.
ACTION:
- a. With the radiological environmental monitoring program not being conducted as specified in Table 3.12.1-1, prepare and submit to the Commission, in the Annual Environmental and Effluent Release Report per Control 6.9.1.6, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
- b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12.1-2 when averaged over the current quarter, prepare and submit to the Commission within 30 days pursuant to Control 6.9.2 a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the current year limits of Control 3.11.1.2, 3.11.2.2 and 3.11.2.3. When more than one of the radionuclides in Table 3.12.1-2 are detected in the sampling medium, this report shall be submitted if:
concentration(l) + concentration(2) + 1.0 reporting level (1) reportinglevel(2)
When radionuclides other than those in Table 3.12.1-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose* to a MEMBER OF THE PUBLIC is equal to or greater than the current year limits of Control 3.11.1.2, 3.11.2.2 and 3.11.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the annual Radiological Environmental Operating Report required by Control 6.9.1.6.
- The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.
PERRY - UNIT 1 3/4 3-l
ODCM Page: 148 Rev.: 9 RADIOLOGICAL ENVIRONMENTAL MONITORING CONTROLS
- c. With milk or broad leaf vegetation samples unavailable from one or more of the sample locations required by Table 3.12.1-1, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The specific locations from which samples were unavailable may then be deleted from the monitoring program.
Pursuant to Control 6.9.1.7, submit in the next Annual Radiological Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table for the ODCM reflecting the new location~s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new locationfs) for obtaining samples.
- d. The provisions of Control 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12.1-1 from the specific locations given in the table and figures in the ODCM and shall be analyzed pursuant to the requirements of Table 3.12.1-1 and the detection capabilities required by Table 4.12.1-1.
PERRY - UNIT 1 3/4 3 -2
ODCM Rev. : 9 Page: 149 TABLE 3.12.1-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM*
Number of Samples Exposure Pathway and (1) Sampling and Type and Frequency and/or Sample Sample Locations Collection Frequency of Analysis
- 1. Direction Twenty-eight routine monitoring Quarterly. Gamma dose quarterly.
Radiation(2) stations either with two or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:
An inner ring of stations, one in each meteorological sector, other than those sectors entirely over water (N, NNE, NNW, NW, W, WNW), in the general area of the SITE BOUNDARY; An outer ring of stations, one in each meteorological sector, other than those sectors entirely over water (N, NE, NNE, NNW, NW, W, WNW), in the 6- to 8-km range from the site; and The balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and in one or two areas to serve as control stations.
PERRY - UNIT 1 3/4 3-3 I)
ODCM Rev. : 9 Page: 150 TABLE 3.12.1-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Number of Samples Exposure Pathway and (1) Sampling and Type and Frequency and/or Sample Sample Locations Collection Frequency of Analysis
- 2. Airborne Radioiodine Samples from five locations: Continuous sampler Radioiodine Canister:
and operation with sample 1-131 analysis weekly.
Particulate Three samples from close to the collection weekly, or three SITE BOUNDARY locations, more frequently if in different sectors, of the required by dust Particulate Sampler:
highest calculated annual loading. Gross beta radioactivity average ground-level D/Q. analysis following filter change; (3) and One sample from the vicinity of gamma isotopic a community having the highest analysis(4) of composite calculated annual average (by location) quarterly.
ground-level D/Q; and One sample from a control location, as for example 15 to 30 km distant and in the least prevalent wind direction.
- 3. Waterborne
- a. Surface Two samples Composite sample over a Gamma isotopic 1-month period.15) analysis(4) monthly.
Composite for tritium analysis quarterly.
PERRY - UNIT 1 3/4 3 -4
ODCM Rev. : 9 Page: 151 TABLE 3.12.1-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Number of Samples Exposure Pathway and (1) Sampling and Type and Frequency and/or Sample Sample Locations Collection Frequency of Analysis
- 3. Waterborne (Continued)
- b. Drinking One sample of each of one to Composite sample over I-131 analysis on each three of the nearest water 2-week period"5 ) when composite when the dose supplies that could be affected I-131 analysis is calculated from the by its discharge. performed; monthly consumption of the water composite otherwise. is greater than 1 mrem One sample from a control per year.(6G Composite location. for gross beta and gamma isotopic analyses (4) monthly. Composite for tritium analysis quarterly.
- c. Sediment One sample from area with Semi-annually. Gamma isotopic from existing or potential analysis (4) shoreline recreational value. semi-annually.
- 4. Ingestion
- a. Milk Samples from milking animals in Semi-monthly when Gamma isotopic three locations within 5km animals are on pasture; analysis(') and 1-131 distance having the highest dose monthly at other times. analysis semi-monthly, potential. If there are none, when animals are on then one sample from milking pasture; monthly at animals in each of between 5 to other times.
8 km distant where doses are three areas calculated to be greater than 1 mrem per yr. (6)
One sample from milking animals at a control location 15 to 30 km distant and in the least prevalent wind direction.
PERRY - UNIT 1 3/4 3-5
ODCM Rev. : 9 Page: 152 TABLE 3.12.1-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Number of Samples Exposure Pathway and (1) Sampling and Type and Frequency and/or Sample Sample Locations Collection Frequency of Analysis
- 4. Ingestion (Continued)
- b. Fish and One sample of one commercially One sample in season. Gamma isotopic Inverte- and/or recreationally-important analysis"4) on edible brates species in vicinity of plant portions.
discharge area.
One sample of same species in areas not influenced by plant discharge.
- c. Food Sample of three different kinds of Monthly during growing Gamma isotopic Products broad leaf vegetation grown nearest season. analysis(4) and 1-131 each of two different offsite analysis.
locations of highest predicted annual average ground level D/Q if milk sampling is not performed.
One sample of each of the similar Monthly during growing Gamma isotopic broad leaf vegetation grown 15 to season. analysis(4) and I-131 30 km distant in the least prevalent analysis.
wind direction if milk sampling is not performed.
PERRY - UNIT 1 3/4 3-6
ODCM Page: 153 Rev.: 9 TABLE 3.12.1-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATIONS
- Sample locations are given on the figure and the table in the ODCM.
(1) Specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, shall be provided for each and every sample location in Table 3.12-1 in a table and figure(s) in the ODCM. Refer to NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,"
October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, and malfunction of automatic sampling equipment. If specimen's are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the annual Radiological Environmental Operating Report pursuant to Control 6.9.1.6.
It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable specific alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made with 30 days in the Radiological Environmental Monitoring Program given in the ODCM. Pursuant to Control 6.9.1.7, submit in the next annual Radioactive Effluent Release Report documentation for a change in the ODCM, including a revised figure(s) and table for the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples for that pathway and justifying the selection of the new location(s) for obtaining samples.
(2) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters.
Film badges shall not be used as dosimeters for measuring direct radiation. (The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.)
(3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.
PERRY - UNIT 1 3/4 3-7
ODCM Page: 154 Rev.: 9 TABLE 3.12.1-1 (Continued)
TABLE NOTATIONS (Continued (4) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.
(5) A composite sample is one in which the quantity (aliquot) of liquid sampled is proportional to the quantity of flowing liquid and in which the method of sampling employed results in a specimen that is representative of the liquid flow. In this program composite sample aliquots shall be collected at time intervals that are very short (e.g.,
hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.
(6) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.
PERRY - UNIT 1 3/4 3-8
ODCM Rev.: 9 Page: 155 TABLE 3.12.1-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels Water Airborne Particulate Fish Milk Food Products Analysis (pCi/L) or Gases (pCi/m 3 ) (pCi/Kg, wet) (pCi/L) (pCi/kg, wet) a H-3 2 x 10 NA NA NA NA Mn-54 1 x 103 NA 3 x 104 NA NA Fe-59 4 x 102 NA 1 x 10 NA NA Co-58 1 x 103 NA 3 x 104 NA NA Co-60 3 x 102 NA 1 x 10 NA NA Zn-65 3 x 102 NA 2 x 104 NA NA Zr-Nb-95 4 x 102 NA NA NA NA I-131 2 0.9 NA 3 1 x 1o2 Cs-134 30 10 1 x 103 60 1 x 103 Cs-137 50 20 2 x 103 70 2 x 103 Ba-La-140 2 x 102 NA NA 3 x 102 NA For drinking water samples. This is a 40CFR141 value.
PERRY - UNIT 1 3/4 3-9
..2y I)
ODCM Rev.: 9 Page: 156 TABLE 4.12.1-1 (a), (b), (c)
MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)
IN ENVIRONMENTAL SAMPLES Airborne Particulate Broad Leaf Analysis Water or Gases Fish Milk Vegetation Sediment (pci/i) (pCi/m3 ) (pCi/Kg, wet) (pCi/l) (pCi/kg,wet) (pCi/kg,wet)
Gross beta 4 1 x 102 NA NA NA NA H-3 2000* NA NA NA NA NA Mn-54 15 NA 130 NA NA NA Fe-59 30 NA 260 NA NA NA Co-58,60 15 NA 130 NA NA NA Zn-65 30 NA 260 NA NA NA Zr-95 30 NA NA NA NA NA Nb-95 15 NA NA NA NA NA 1-131 7 x 102 NA 1 60 NA Cs-134 15 5 x 10 130 15 60 150 2
Cs-137 18 6 x 10 150 18 80 180 Ba-140 60 NA NA 60 NA NA La-140 15 NA NA 15 NA NA
- If no drinking water pathway exists, a value of 3000 pCi/l may be used.
- If no drinking water pathway exists, a value of 15 pCi/l may be used.
PERRY - UNIT 1 3/4 3-10 9)
ODCM Page: 157 Rev.: 9 TABLE 4.12.1-1 (Continued)
MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)
TABLE NOTATION aAcceptable detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.
Table 4.12-1 indicates acceptable detection capabilities for radioactive materials in environmental samples. These detection capabilities are tabulated in terms of the lower limits of detection (LLDs). The LLD is defined, for purposes of this guide, as the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability with only 5%
probability of falsely concluding that a blank observation represents a
,real, signal.
For a particular measurement system (which may include radiochemical separation):
LLD =4.66 Sb LD (E) (V (2-22 x 106) (Y) exp (- A At) where LLD is the "a priori" lower limit of detection as defined above (as PCi per unit mass or volume).
Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)
E is the counting efficiency (as counts per disintegration)
V is the sample size (in units of mass or volume) 2.22 106 is the number of disintegrations per minute per microcurie Y is the fractional radiochemical yield (when applicable)
A is the radioactive decay constant for the particular radionuclide (sec-1)
At is the elapsed time between sample collection (or end of the sample collection period) and time of counting (sec)
Typical values of E, V, Y and At should be used in the calculation.
PERRY - UNIT 1 3/4 3 -11
ODCM Page: 158 Rev.: 9 TABLE 4.12.1-1 (Continued)
MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)
TABLE NOTATION (continued)
It should be recognized that the LLD is defined as an "a priori, (before the fact) limit representing the capability of a measurement system and not as an "a posteriori, (after the fact) limit for a particular measurement.
Occasionally background fluctuations, unavoidable small sample size, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors should be identified and described in the annual Radiological Environmental Operating Report pursuant to Control 6.9.1.6.
The value of Sb used in the calculation of the LLD for a particular measurement system should be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicated variance.
cThis list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Control 6.9.16.
PERRY - UNIT 1 3/4 3 -12
ODCM Page: 159 Rev.: 9 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS CONTROLS 3.12.2 A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden* of greater than 50 m2 (500 ft2) producing broad leaf vegetation.
APPLICABILITY: At all times.
ACTION:
- a. With a land use census identifying a location(s) which yields a calculated dose or dose commitment greater than the values currently being calculated in Control 4.11.2.3, identify the new location(s)* in the next Annual Radioactive Effluent Release Report, pursuant to Control 6.9.1.7.
- b. With a land use census identifying a location(s) which yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which milk and/or broad leaf vegetation samples are currently being obtained in accordance with Control 3.12.1, add the new location(s) to the radiological environmental monitoring program within 30 days. If no milk and/or broad leaf vegetation samples are identified in the new sector with the highest D/Q value, then the next sector with the highest D/Q value will be considered and so on until a sampling location can be established. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.* Identify the new location(s) in the next annual Radioactive Effluent Release Report and also include in the report a revised figure(s) and table(s) for the ODCM reflecting the new location(s).
- c. The provisions of Control 3.0.3 are not applicable.
SURVEILLANCE REOUIREMENTS 4.12.2 The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the annual Radiological Environmental Operating Report pursuant to Control 6.9.1.6.
- Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Controls for broad leaf vegetation sampling in Table 3.12.1-1 shall be followed, including analysis of control samples.
PERRY - UNIT 1 3/4 3 -13
ODCM Page: 160 Rev.: 9 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM CONTROLS 3.12.3 Analyses shall be performed on radioactive materials that correspond to samples required by Table 3.12.1-1. These materials are supplied as part of an Inter-laboratory Comparison Program.
APPLICABILITY: At all times.
ACTION:
- a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Environmental and Effluent Release Report pursuant to Control 6.9.1.6.
- b. The provisions of Control 3.0.3 are not applicable.
SURVEILLANCE REOUIREMENTS 4.12.3 A summary of the results obtained as part of the above required Inter-Laboratory Comparison Program shall be included in the annual Radiological Environmental Operating Report pursuant to Control 6.9.1.6.
PERRY - UNIT 1 3/4 3-14
ODCM Page: 161 Rev.: 9 BASES FOR SECTIONS 3.0 AND 4.0 CONTROLS AND SURVEILLANCE REQUIREMENTS NOTE The BASES contained in succeeding pages summarize the reasons for the Controls in Section 3.0 and 4.0, but are not part of these Controls.
ODCM Page: 162 Rev.: 9 3/4 CONTROLS AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY BASES Controls 3.0.1 through 3.0.5 establish the general requirements applicable to Appendix C Controls and apply at all times, unless otherwise stated.
Control 3.0.1 establishes the Applicability statement within each individual control as the requirement for when the Control is required to be met (i.e.,
when the unit is in the MODES or other specified conditions of the Applicability statement of each Control).
Control 3.0.2 establishes that upon discovery of a failure to meet a Control, the associated ACTIONS shall be met. The Completion Time of each ACTION condition is applicable from the point in time that an ACTIONS condition is entered. The ACTIONS establish those remedial measures that must be taken within specified times when the requirements of a Control are not met. This Control establishes that:
- a. Completion of the ACTIONS within the specified times constitutes compliance with a Control; and
- b. Completion of the ACTIONS is not required when a Control is met within the specified time, unless otherwise specified.
There are two basic types of ACTION requirements. The first type of ACTIONS specifies a time limit in which the Control must be met. This time limit is the time to restore an inoperable system or component to OPERABLE status or to restore variables to within specified limits. If this type of ACTION is not completed within the specified completion time, a shutdown may be required to place the unit in a MODE or condition in which the Control is not applicable.
(Whether stated as an ACTION or not, correction of the entered condition is an action that may always be considered upon entering ACTIONS.) The second type of ACTION specifies the remedial measures that permit continued operation of the unit that is not further restricted by the completion time. In this case, compliance with the ACTIONS provides an acceptable level of safety for continued operation.
Completing the ACTIONS is not required when a Control is met or is no longer applicable, unless otherwise stated in the individual Control.
The nature of some ACTIONS of some conditions necessitates that, once the condition is entered, the ACTIONS must be completed even though the associated condition no longer exists. The individual Control's ACTIONS specify where this is the case.
PERRY - UNIT 1 B 3/4 0-1
ODCM Page: 163 Rev.: 9 3/4.0 APPLICABILITY BASES (Continued)
The completion times of the ACTIONS are also applicable when a system or component is removed from service intentionally. The reasons for intentionally relying on the ACTIONS include, but are not limited to, performance of Surveillances, preventive maintenance, corrective maintenance, or investigation of operational problems. Entering ACTIONS for these reasons must be done in a manner that does not compromise safety. Intentional entry into ACTIONS should not be made for operational convenience. Alternatives that would not result in redundant equipment being inoperable should be used instead. Doing so limits the time both subsystems/divisions of a safety function are inoperable and limits the time other conditions exist which result in Control 3.0.3 being entered. Individual Controls may specify a time limit for performing an SR when equipment is removed from service or bypassed for testing. In this case, the completion times of ACTIONS are applicable when this time limit expires, if the equipment remains removed from service or bypassed.
When a change in MODE or other specified condition is required to comply with an ACTION, the unit may enter a MODE or other specified condition in which another Control becomes applicable. In this case, the completion times of the associated ACTIONS would apply from the point in time that the new Control becomes applicable and the ACTIONS condition(s) are entered.
Control 3.0.3 establishes the actions that must be implemented when a Control is not met and:
- a. An associated ACTION and completion time is not met and no other condition applies; or
- b. The condition of the unit is not specifically addressed by the associated ACTIONS. This means that no combination of conditions stated in the ACTIONS can be made that exactly corresponds to the actual condition of the unit. Sometimes, possible combinations of conditions are such that entering Control 3.0.3 is warranted; in such cases, the ACTIONS specifically state a condition corresponding to such combinations and also that Control 3.0.3 be entered immediately.
This Control delineates the time limits for placing the unit in a safe MODE or other specified condition when operation cannot be maintained within the limits for safe operation as defined by the Control and its ACTIONS. It is not intended to be used as an operational convenience that permits routine voluntary removal of redundant systems or components from service in lieu of other alternatives that would not result in redundant systems or components being inoperable.
PERRY - UNIT 1 B 3/4 0-2
ODCM Page: 164 Rev.: 9 3/4.0 APPLICABILITY BASES (Continued)
Upon entering Control 3.0.3, 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is allowed to prepare for an orderly shutdown before initiating a change in unit operation. This includes time to permit the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid. The time limits specified to reach lower MODES of operation permit the shutdown to proceed in a controlled and orderly manner that is well within the specified maximum cooldown rate and within the capabilities of the unit, assuming that only the minimum required equipment is OPERABLE. This reduces thermal stresses on components of the Reactor Coolant System and the potential for a plant upset that could challenge safety systems under conditions to which this Control applies.
A unit shutdown required in accordance with Control 3.0.3 may be terminated and Control 3.0.3 exited if any of the following occurs:
- a. The Control is met.
- b. A condition exists for which the ACTIONS have now been performed.
- c. ACTIONS exist that do not have expired completion times. These completion times are applicable from the point in time that the condition is initially entered and not from the time Control 3.0.3 is exited.
The time limits of Control 3.0.3 allow 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> for the unit to be in MODE 4 when a shutdown is required during MODE 1 operation. If the unit is in a lower MODE of operation when a shutdown is required, the time limit for reaching the next lower MODE applies. If a lower MODE of operation is reached in less time than allowed, however, the total allowable time to reach MODE 4, or other applicable MODE, is not reduced. For example, if MODE 2 is reached in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, then the time allowed for reaching MODE 3 is the next 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />, because the total time for reaching MODE 3 is not reduced from the allowable limit of 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />. Therefore, if remedial measures are completed that would permit a return to MODE 1, a penalty is not incurred by having to reach a lower MODE of operation in less than the total time allowed.
In MODES 1, 2, and 3, Control 3.0.3 provides actions for conditions not covered in other Controls. The requirements of Control 3.0.3 do not apply in MODES 4 and 5 because the unit is already in the most restrictive condition required by Control 3.0.3. The requirements of Control 3.0.3 do not apply in other specified conditions of the Applicability (unless in MODE 1, 2, or 3) because the ACTIONS of individual Controls sufficiently define the remedial measures to be taken.
Exceptions to Control 3.0.3 are provided in instances where requiring a unit shutdown, in accordance with Control 3.0.3, would not provide appropriate remedial measures for the associated condition of the unit. These exceptions are addressed in the individual Controls.
PERRY - UNIT 1 B 3/4 0-3
ODCM Page: 165 Rev.: 9 3/4.0 APPLICABILITY BASES (Continued)
Control 3.0.4 establishes limitations on changes in MODES or other specified conditions in the Applicability when a Control is not met. It precludes placing the Unit in a MODE or other specified condition stated in that Applicability (e.g., Applicability desired to be entered) when the following exist:
- a. Unit conditions are such that the requirements of the Control would not be met in the Applicability desired to be entered; and
- b. Continued noncompliance with the Control requirements, if the Applicability were entered, would result in the unit being required to exit the Applicability desired to be entered to comply with the ACTIONS.
Compliance with ACTION requirements that permit continued operation of the facility for an unlimited period of time in a MODE or other specified condition provides an acceptable level of safety for continued operation.
This is without regard to the status of the plant before or after the MODE change. Therefore, in such cases, entry into a MODE or other specified condition in the Applicability may be made in accordance with the provisions of the ACTION requirements. The provisions of this control should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before Unit startup.
The provisions of Control 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS. In addition, the provisions of Control 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown.
Exceptions to Control 3.0.4 are stated in the individual Controls. Exceptions may apply to all the ACTIONS or to a specific ACTION of a Control.
Surveillances do not have to be performed on the associated inoperable equipment (or on variables outside the specified limits), as permitted by SR 3.0.1. Therefore, changing MODES or other specified conditions while in an ACTIONS condition, either compliance with Control 3.0.4, or where an exception to Control 3.0.4 is stated, is not a violation of SR 4.0.1 or SR 4.0.4 for those Surveillances that do not have to be performed due to the associated inoperable equipment. However, SRs must be met to ensure OPERABILITY prior to declaring the associated equipment OPERABLE (or variable within limits) and restoring compliance with the affected Control.
Control 3.0.4 is only applicable when entering MODE 3 from MODE 4, MODE 2 from MODE 3 or 4, or MODE 1 from MODE 2. Furthermore, Control 3.0.4 is applicable when entering any other specified condition in the Applicability only while operating in MODE 1, 2, or 3. The requirements of Control 3.0.4 do not apply in MODES 4 and 5, or in the other specified conditions of the Applicability (unless in MODE 1, 2, or 3) because the ACTIONS of individual Controls sufficiently define the remedial measures to be taken.
PERRY - UNIT 1 B 3/4 0-4
ODCM Page: 166 Rev.: 9 3/4.0 APPLICABILITY BASES (Continued)
Control 3.0.5 establishes the allowance for restoring equipment to service under administrative controls when it has been removed from service or declared inoperable to comply with ACTIONS. The sole purpose of this Control is to provide an exception to Control 3.0.2 (e.g., to not comply with the applicable ACTION(s)) to allow the performance of SRs to demonstrate:
- a. The OPERABILITY of the equipment being returned to service; or
- b. The OPERABILITY of other equipment.
The administrative controls ensure the time the equipment is returned to service in conflict with the requirements of the ACTIONS is limited to the time absolutely necessary to perform the allows SRs. This Control does not provide time to perform any other preventative or corrective maintenance.
SR 4.0.1 through 4.0.5 establish the general requirements applicable to all Controls and apply at all times, unless otherwise stated.
SR 4.0.1 establishes the requirement that SRs must be met during the MODES or other specified conditions in the Applicability for which the requirements of the Control apply, unless otherwise specified in the individual SRs. This Control is to ensure that Surveillances are performed to verify the OPERABILITY of systems and components, and that variables are within specified limits. Failure to meet a Surveillance within the specified frequency, in accordance with SR 4.0.2, constitutes a failure to meet a Control.
Systems and components are assumed to be OPERABLE when the associated SRs have been met. Nothing in this Control, however, is to be construed as implying that systems or components are OPERABLE when:
- a. The systems or components are known to be inoperable, although still meeting the SRs; or
- b. The requirements of the Surveillance(s) are known to be not met between required Surveillance performances.
Surveillances do not have to be performed when the unit is in a MODE or other specified condition for which the requirements of the associated Control are not applicable, unless otherwise specified. The SRs associated with a Special Operations Control are only applicable when the Special Operations Control is used as an allowable exception to the requirements of a Control.
Surveillances, including Surveillances invoked by ACTIONS, do not have to be performed on inoperable equipment because the ACTIONS define the remedial measures that apply. Surveillances have to be met and performed in accordance with SR 4.0.2, prior to returning equipment to OPERABLE status.
PERRY - UNIT 1 B 3/4 0-5
ODCM Page: 167 Rev.: 9 3/4.0 APPLICABILITY BASES (Continued)
Upon completion of maintenance, appropriate post maintenance testing is required to declare equipment OPERABLE. This includes ensuring applicable Surveillances are not failed and their most recent performance is in accordance with SR 4.0.2. Post maintenance testing may not be possible in the current MODE or other specified conditions in the Applicability due to the necessary unit parameters not having been established. In these situations, the equipment may be considered OPERABLE provided testing has been satisfactorily completed to the extent possible and the equipment is not otherwise believed to be incapable of performing its function. This will allow operation to proceed to a MODE or other specified condition where other necessary post maintenance tests can be completed.
SR 4.0.2 establishes the requirements for meeting the specified frequency for Surveillances and any ACTIONS with a completion time that requires the periodic performance of the ACTION on a "once per ... " interval.
SR 4.0.2 permits a 25% extension of the interval specified in the frequency.
This extension facilitates Surveillance scheduling and considers plant operating conditions that may not be suitable for conducting the Surveillance (e.g., transient conditions or other ongoing Surveillance or maintenance activities).
The 25t extension does not significantly degrade the reliability that results from performing the Surveillance at its specified frequency. This is based on the recognition that the most probable result of any particular Surveillance being performed is the verification of conformance with the SRs. The exceptions to SR 4.0.2 are those Surveillances for which the 25% extension of the interval specified in the frequency does not apply. These exceptions are stated in the individual Controls.
As stated in SR 4.0.2, the 25% extension also does not apply to the initial portion of a periodic completion time that requires performance on a "once per ... " basis. The 25% extension applies to each performance after the initial performance. The initial performance of the ACTION, whether it is a particular Surveillance or some other remedial action, is considered a single action with a single completion time. One reason for not allowing the 25%
extension to this completion time is that such an action usually verifies that no loss of function has occurred by checking the status of redundant or diverse components or accomplishes the function of the inoperable equipment in an alternative manner.
The provisions of SR 4.0.2 are not intended to be used repeatedly merely as an operational convenience to extend Surveillance intervals (other than those consistent with refueling intervals) or periodic completion time intervals beyond those specified.
PERRY - UNIT 1 B 3/4 0-6
ODCM Page: 168 Rev.: 9 3/4.0 APPLICABILITY BASES (Continued)
SR 4.0.3 establishes the flexibility to defer declaring affected equipment inoperable or an affected variable outside the specified limits when a Surveillance has not been completed within the specified frequency. A delay period of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified frequency, whichever is less, applies from the point in time that it is discovered that the Surveillance has not been performed in accordance with SR 4.0.2, and not at the time that the specified frequency was not met. This delay period provides adequate time to complete Surveillances that have been missed. This delay period permits the completion of a Surveillance before complying with ACTIONS or other remedial measures that might preclude completion of the Surveillance.
The basis for this delay period includes consideration of unit conditions, adequate planning, availability of personnel, the time required to perform the Surveillance, the safety significance of the delay in completing the required Surveillance, and the recognition that the most probable result of any particular Surveillance being performed is the verification of conformance with the requirements.
When a Surveillance with a frequency based not on time intervals, but upon specified unit conditions or operational situations, is discovered not to have been performed when specified, SR 4.0.3 allows the full delay period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to perform the Surveillance.
SR 4.0.3 also provides a time limit for completion of Surveillances that become applicable as a consequence of MODE changes imposed by ACTIONS.
Failure to comply with specified frequencies for Surveillance Requirements is expected to be an infrequent occurrence. Use of the delay period established by SR 4.0.3 is a flexibility which is not intended to be used as an operational convenience to extend Surveillance intervals.
If a Surveillance is not completed within the allowed delay period, then the equipment is considered inoperable or the variable then is considered outside the specified limits and the completion times of the ACTIONS for the applicable Control conditions begin immediately upon expiration of the delay period. If a Surveillance is failed within the delay period, then the equipment is inoperable, or the variable is outside the specified limits and the completion times of the required ACTIONS for the applicable Control conditions begin immediately upon failure of the Surveillance.
Completion of the Surveillance within the delay period allowed by this Control, or within the completion time of the ACTIONS, restores compliance with SR 4.0.1.
SR 4.0.4 establishes the requirement that all applicable SRs must be met before entry into a MODE or other specified condition in the Applicability.
PERRY - UNIT 1 B 3/4 0-7
ODCM Page: 169 Rev.: 9 3/4.0 APPLICABILITY BASES (Continued)
This Control ensures that system and component OPERABILITY requirements and variable limits are met before entry into MODES or other specified conditions in the Applicability for which these systems and components ensure safe operation of the unit.
However, in certain circumstances failing to meet an SR will not result in SR 4.0.4 restricting a MODE change or other specified condition change. When a system, subsystem, division, component, device, or variable is inoperable or outside its specified limits, the associated SR(s) are not required to be performed per SR 4.0.1 which states that surveillances do not have to be performed on inoperable equipment or variables outside specified limits. When equipment is inoperable, or variables are outside their specified limits, SR 4.0.4 does not apply to the associated SR(s) since the requirement for the SR(s) to be performed is removed. Therefore, failing to perform the Surveillance(s) within the specified frequency, on equipment that is inoperable, or on variables that are outside specified limits, does not result in an SR 4.0.4 restriction to changing MODES or other specified conditions in the Applicability. However, since the Control is not met in this instance, Control 3.0.4 will govern any restrictions that may (or may not) apply to MODE or other specified condition changes. The provisions of this Control should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before entering an associated MODE or other specified condition in the Applicability.
The provisions of SR 4.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS. In addition, the provisions of SR 4.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown.
The precise requirements for performance of SRs are specified such that exceptions to SR 4.0.4 are not necessary. The specific time frames and conditions necessary for meeting the SRs are specified in the frequency, in the Surveillance, or both. This allows performance of Surveillances when the prerequisite condition(s) specified in a Surveillance procedure require entry into the MODE or other specified condition in the Applicability of the associated Control prior to the performance or completion of a Surveillance.
A Surveillance that could not be performed until after entering the Control Applicability would have its frequency specified such that it is not "due" until the specific conditions needed are met. Alternately, the Surveillance may be stated in the form of a note as not required (to be met or performed) until a particular event, condition, or time has been reached.
SR 4.0.4 is only applicable when entering MODE 3 from MODE 4, MODE 2 from MODE 3 or 4, or MODE 1 from MODE 2. Furthermore, SR 4.0.4 is applicable when entering any other specified condition in the Applicability only while operating in MODE 1, 2, or 3. The requirements of SR 4.0.4 do not apply in MODES 4 and 5, or in the other specified conditions of the Applicability (unless in MODE 1, 2, or 3) because the ACTIONS of individual Controls sufficiently define the remedial measures to be taken.
PERRY - UNIT 1 B 3/4 0-8
ODCM Page: 170 Rev.: 9 3/4.3 INSTRUMENTATION BASES 3/4.3.7 MONITORING INSTRUMENTATION 3/4.3.7.9 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10CFR20. The OPERABILITY and use of this instrumentation is consistent with the requirements of 10CFR50, Appendix A, General Design Criteria 60, 63, and 64.
3/4.3.7.10 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm will occur prior to exceeding the limits of 10CFR20. The OPERABILITY and use of this instrumentation is consistent with the requirements of 10CFR50, Appendix A, General Design Criteria 60, 63, and 64.
PERRY - UNIT 1 B 3/4 1-1
ODCM Page: 171 Rev.: 9 3/4.11 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This Control is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10CFR20, Appendix B, Table 2, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II.A. design objectives of 10CFR50, Appendix I, to a MEMBER OF THE PUBLIC, and (2) the limits of IOCFR20.106(e) to the population. The concentration limit for dissolved and entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its limiting effluent concentration in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.
This Control applies to the release of radioactive materials in liquid effluents from all units at the site.
The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs).
Detailed discussion of the LLD, and other detection limits, can be found in:
(1) Currie, L. A.., "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," NUREG/CR-4007 (September, 1984).
(2) HASL Procedures Manual, HASL-300 (revised annually).
3/4.11.1.2 DOSE This Control is provided to implement the requirements of 10CFR50, Appendix I, Sections II.A, III.A and IV.A. The Control implements the guides set forth in of 10CFRS0, Appendix I,Section II.A. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in of 10CFR50, Appendix I, Section IV.A which assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable.' Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40CFR141. The dose calculations in the ODCM implement the requirements in 10CFR50, Appendix I, Section III.A that conformance with the guides of 10CFR50, Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents PERRY - UNIT 1 B 3/4 2-1
ODCM Page: 172 Rev.: 9 RADIOACTIVE EFFLUENTS BASES 3/4.11.1.2 DOSE (Continued) are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977, and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluent from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.
This Control applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.
3/4.11.1.3 LIQUID RADWASTE TREATMENT SYSTEM The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment.
The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This Control implements the requirements of 10CFR50.36a; 10CFR50, Appendix A, General Design Criterion 60; and the design objective given in 10CFR50, Appendix I, Section II.D. The specified limit governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in 10CFR50, Appendix I, Section II.A, for liquid effluents.
This Control applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing the system.
PERRY - UNIT 1 B 3/4 2-2
ODCM Page: 173 Rev.: 9 RADIOACTIVE EFFLUENTS BASES 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This Control is provided to ensure that the dose any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of IOCFR20 for UNRESTRICTED AREAS. The annual dose rate limits are those associated with the concentrations of those limiting effluent concentrations, as described in Regulatory Guide 1.109.
These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in 10CFR20.106(b),
Appendix B, Table II. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/year to the whole body or to less than or equal to 3000 mrems/year to the skin.
These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/year.
This Control applies to the release of radioactive materials in gaseous effluents from all reactors at the site. The required detection capabilities for radioactive material in gaseous waste samples are tabulated in terms of the lower limit of detection (LLDs). Detailed discussion of the LLD and other detection limits can be found in:
(1) Currie, L. A., "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," NUREG/CR-4007 (September 1984).
(2) HASL Procedures Manual, HASL-300 (revised annually).
3/4.11.2.2 DOSE - NOBLE GASES This Control is provided to implement the requirements of 10CFR50, Appendix I, Sections II.B, III.A and IV.A. The Control implements the guides set forth in 10CFR50, Appendix I, Section II.B. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in 10CFR50, Appendix I, Section IV.A to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in 10CFR50, Appendix I, Section III.A that conformance with the guides of 10CFR50, Appendix I, be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC PERRY - UNIT 1 B 3/4 2-3
ODCM Page: 174 Rev.: 9 RADIOACTIVE EFFLUENTS BASES 3/4.11.2.2 DOSE - NOBLE GASES (Continued) through appropriate pathways is unlikely to be substantially underestimated.
The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I, Revision 1", October 1977, and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are made using meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents or are based upon the historical average atmospheric conditions.
This Control applies to the release of radioactive materials in gaseous effluents from each reactor at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.
3/4.11.2.3 DOSE - IODINE-131, IODINE-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM This Control is provided to implement the requirements of 10CFR50, Appendix I, Sections II.C, III.A and IV.A. The Controls are the guides set forth in 10CFR50, Appendix I, Section II.C. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in 10CFR50, Appendix I, Section IV.A, to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in 10CFR50, Appendix I, Section III.A, that conformance with the guides of 10CFR50, Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I," Revision 1, October 1977, and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses using meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents or are based upon the historical average atmospheric conditions. The release rate specifications for iodine-131, iodine-133, tritium and radionuclides in particulate form are dependent on the existing radionuclide pathway to man in the areas at and beyond the SITE BOUNDARY. The pathways which were examined in the development PERRY - UNIT 1 B 3/4 2-4
ODCM Page: 175 Rev.: 9 RADIOACTIVE EFFLUENTS BASES 3/4.11.2.3 DOSE - IODINE-131, IODINE-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM (Continued) of these calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat-producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man.
This Control applies to the release of radioactive materials in gaseous effluents from each reactor at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units sharing that system.
3/4.11.2.4 AND 3/4.11.2.5 GASEOUS RADWASTE TREATMENT (OFFGAS) SYSTEM AND VENTILATION EXHAUST TREATMENT SYSTEMS The OPERABILITY of the GASEOUS RADWASTE TREATMENT (OFFGAS) SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEMS ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of the systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This Control implements the requirements of 10CFR50.36a; 10CFR50, Appendix A, General Design Criterion; and the design objectives given in 10CFR50, Appendix I, Section II.D. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in 10CFR50, Appendix I, Sections II.B and II.C, for gaseous effluents.
This Control applies to the release of radioactive materials in gaseous effluents from each reactor at the site. For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportional among the units sharing that system.
PERRY - UNIT 1 B 3/4 2-5
ODCM Page: 176 Rev.: 9 RADIOACTIVE EFFLUENTS BASES 3/4.11.4 TOTAL DOSE This Control is provided to meet the dose limitations of 40CFRl90 that have been incorporated into IOCFR20 by 46 FR 18525. The Control requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40CFR190, if the individual reactors remain within twice the dose design objectives of 10CFR50, Appendix I, and if direct radiation doses from the units including outside storage tanks, etc. are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40CFR190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40CFR190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40CFR190 have not already been corrected), in accordance with the provisions of 40CFR190.11 and 10CFR20.405c, is considered to be a timely request and fulfills the requirements of 40CFRl90 until NRC staff action is completed. The variance only relates to the limits of 40CFRl90, and does not apply in any way to the other requirements for dose limitation of IOCFR20, as addressed in ODCM Controls 3.11.1.1 and 3.11.2.1.
An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.
PERRY - UNIT 1 B 3/4 2-6
ODCM Page: 177 Rev.: 9 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM The Radiological Environmental Monitoring Program required by this Control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the plant operation. This monitoring program implements 10CFR50, Appendix I, Section IV.B.2, and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979. The initially specified monitoring program will be effective for at least the first 3 years of commercial operation. Following this period, program changes may be initiated based on operational experience.
The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by ODCM Table 4.12-1 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
Detailed discussion of the LLD, and other detection limits, can be found in:
(1) Currie, L. A. "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements," NUREG/CR-4007 (September 1984).
(2) HASL Procedure Manual, HASL-300 (revised annually).
3/4.12.2 LAND USE CENSUS This Control is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program given in the ODCM are made if required by the results of the census. The best information from door-to-door survey, visual or aerial survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of 10CFR50, Appendix I, Section IV.B.3. Restricting the census to gardens of greater than So m 2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/M 2.
PERRY - UNIT 1 B 3/4 3-1
ODCM Page: 178 Rev.: 9 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of 10CFR50, Appendix I, Section IV.B.2.
PERRY - UNIT 1 B 3/4 3-2
ODCM Page: 179 Rev.: 9 6.0 ADMINISTRATIVE CONTROLS
ODCM Page: 180 Rev.: 9 ADMINISTRATIVE CONTROLS ANNUAL REPORTS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.6 Routine radiological environmental operating reports covering the operation of the unit during the previous year shall be submitted prior to May 1 of each year.
The annual Radiological Environmental Operating Report shall include:
- a. Summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with pre-operational studies, operational controls (as appropriate). and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment;
- b. The results of land use censuses required by Control 3.12.2;
- c. The results of analysis of all radiological environmental samples and of all locations specified in the table and figures in the Offsite Dose Calculation Manual, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report;
- d. A summary description of the Radiological Environmental Monitoring Program; at least two legible maps* covering all sampling locations keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Inter-laboratory Comparison Program and the corrective action taken if the specified program is not being performed as required by Control 3.12.3; reasons for not conducting the Radiological Environmental Monitoring Program as required by Control 3.12.1, and discussion of all deviations from the sampling schedule of Table 3.12.1-1; discussion of environmental sample measurements that exceed the reporting levels of Table 3.12.1-2 but are not the result of plant effluents, pursuant to ACTION b of Control 3.12.1; and discussion of all analyses in which the LLD required by Table 4.12.1-1 was not achievable.
- One map shall cover stations near the SITE BOUNDARY; a second shall include the more distant stations.
PERRY - UNIT 1 4 -1
ODCM Page: 181 Rev.: 9 ADMINISTRATIVE CONTROLS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT <L01117>
6.9.1.7 Routine radioactive release reports covering the operation of the unit during the previous year shall be submitted annually. The report must be submitted as specified in 10CFR50.4 and the time between submission of reports must be no longer than 12 months.
The annual Radioactive Effluent Release Report shall include:
- a. A summary of the quantities of radioactive liquid and gaseous effluents released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.
- b. A summary of hourly meteorological data collected over the previous year.
This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.*
This report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous year. This report shall also 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 (see Figure 3.2-1) during the report period. All assumptions used in making these assessments, i.e., specific activity, exposure time, and location, shall be included in these reports. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).
- c. An assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40CFRl90, "Environmental Radiation Protection Standards for Nuclear Power Operation." Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.
- In lieu of submission with the annual Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.
PERRY - UNIT 1 4-2
ODCM Page: 182 Rev.: 9 ADMINISTRATIVE CONTROLS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (Continued)
- d. A list and description of unplanned releases from the site to UNRESTRICTED AREAS (see Figure 3.2-1) of radioactive materials in gaseous and liquid effluents made during the reporting period.
- e. Any changes made during the reporting period to the OFFSITE DOSE CALCULATION MANUAL (ODCM), pursuant to PNPP Technical Specification 5.5.1 as well as any major change to Liquid or Gaseous Treatment Systems pursuant to Control 6.15. It shall also include a listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use Census pursuant to Control 3.12.2.
- f. The report shall also include the following: an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in Control 3.3.7.9 or 3.3.7.10, respectively; and description of the events leading to liquid holdup tanks exceeding total curie limits.
SPECIAL REPORTS 6.9.2 Special reports shall be submitted in accordance with 10CFR50.4 within the time period specified for each report.
6.10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of Title 10 Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.
6.10.2 Records of surveillance activities, inspections, and calibrations required by these Controls shall be retained for at least 5 years:
6.15 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS*
6.15.1 Licensee initiated major changes to the radioactive waste systems, liquid, gaseous and solid:
- Licensee may choose to submit the information called for in this Control as part of the annual USAR update.
PERRY - UNIT 1 4-3
ODCM Page: 183 Rev.: 9 ADMINISTRATIVE CONTROLS
- 1. Shall be reported to the Commission in the annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the PORC. The discussion of each change shall contain:
- a. A summary of the evaluation that led to the determination that the change could be made in accordance with 10CFR50.59;
- b. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;
- c. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems
- d. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto;
- e. An evaluation of the change which shows the expected maximum exposures to MEMBERS OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and amendments thereto;
- f. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made;
- g. An estimate of the exposure to plant operating personnel as a result of the change; and
- 2. Shall become effective upon review and approval by the Plant Manager.
- Licensee may choose to submit the information called for in this Control as part of the annual USAR update.
PERRY - UNIT 1 4-4
ODCM Page: 184 Rev.: 9 Records The following records are generated by this document:
Quality Assurance Records Annual Radioactive Effluent Release Report Non-Quality Records None PERRY - UNIT 1 4 -5
ODCM Page: 185 Rev.: 9 REFERENCES
- 1. Title 10, "Energy," Chapter 1, Code of Federal Regulations; Part 20, U.S.
Government Printing Office, Washington, D.C. 20402, May 21, 1991.
- 2. Title 10, "Energy," Chapter 1, Code of Federal Regulations; Part 50; U.S.
Government Printing Office, Washington, D.C. 20402, January 1, 1984.
- 3. Title 40, "Protection of Environment," Chapter 1, Code of Federal Regulations, Part 190, Federal Register, Vol. 42, Washington, D.C.
20402, January 13, 1977.
- 4. U.S. Nuclear Regulatory Commission, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," USNRC NUREG-0133, Washington, D.C. 20555, October, 1981.
- 5. U.S. Nuclear Regulatory Commission, "Draft Radiological Effluent Technical Specifications for PWR's," USNRC NUREG-0473, Revision 2, Washington, D.C. 20555, February, 1980.
- 6. Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants,' Revision 1, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, June 1974.
- 7. Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR 50, Appendix I," Revision 0, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, March 1976.
- 8. Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I," Revision 1, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, October 1977.
- 9. Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, July 1977.
- 10. Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing.
Appendix I," Revision 1, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, April 1977.
ODCM Page: 186 - LAST Rev.: 9 REFERENCES (Cont.)
- 11. Regulatory Guide 4.15, "Quality Assurance for Radiological Monitoring Programs (Normal Operation) - Effluent Streams and the Environment," U.S.
Nuclear Regulatory Commission, Washington, D.C. 20555, February 1979.
- 12. U.S. Nuclear Regulatory Commission, "Branch Technical Position,"
Revision 1, Washington, D.C. 20555, November 1979.
- 13. Perry Nuclear Power Plant, Unit 1 and 2, "Final Safety Analysis Report,"
Amendment 14, The Cleveland Electric Illuminating Company, Perry, Ohio 44081, August 1984.
- 14. Perry Nuclear Power Plant, Units 1 and 2, "Environmental Report, Operating License Stage," Supplement 3, The Cleveland Electric Illuminating Company, Perry, Ohio 44081, November 1981.
- 15. Perry Nuclear Power Plant, Units 1 and 2, "Radiological Environmental Monitoring Program Manual," The Cleveland Electric Illuminating Company, Perry, Ohio 44081, February 1985.
- 16. "Midas User's Manual, for the Cleveland Electric Illuminating Company, Perry Nuclear Power Plant," Pickard, Lowe and Garrick, Washington, D.C.
20036, July 1983.
- 17. Kocher, D.C., "Radioactive Decay Data Tables," Technical Information Center, U.S. Department of Energy, Springfield, Virginia 22161, September 1985.
- 18. 1989 Engineering Report "Lake Erie Potable Water Facilities and Intakes within 50 Miles of PNPP, (Ref. SO-11552 "E").
- 19. Perry Environmental Report Operating License Stage, Table 5.1-10 "Annual Average Dilution Factors for Lake Water Intakes within 50 Miles of PNPP and Q&R Page 2.1-2.
- 20. PNPP Ohio Power Siting Commission application of August 1974, Appendix 1304-C-2, Table IV-A-2.
- 21. Total Angler Catch (1987 annual) for Each Grid Location; per letter from Michael R. Rawson, Fairport Fisheries Research Station, Ohio Department of Natural Resources (6-20-88).
- 22. Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors; Generic Letter 89-01, Supplement No. 1.
- 23. Federal Guidance Report 13 CD Supplement: Cancer Risk Coefficients for Environmental Exposure to Radionuclides.
- 24. Commitment L01117: Radioactive Effluent Release Report. I