Text

Offsite Dose Calculation Manual and Big Rock Point ISFSI - Attachment 2, 2017 Radioactive Effluent Release Report
	ML18113A248
Person / Time
Site:	Palisades, Big Rock Point File:Consumers Energy icon.png
Issue date:	12/18/2017
From:	Britting J; Entergy Nuclear Operations
To:	; Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
Shared Package
ML18113A244	List: ML18113A245; ML18113A246; ML18113A247; PNP 2018-020, Offsite Dose Calculation Manual and Big Rock Point ISFSI - Attachment 2, 2017 Radioactive Effluent Release Report;
References
	PNP 2018-020
	Download: ML18113A248 (181)
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ODCM Revision 29 Issued Date 12/18/17 PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL TITLE: OFFSITE DOSE CALCULATION MANUAL IProcess Applicability Exclusion D JCBritting 1 12/18/17 Procedure Sponsor Date CLJones 1 12/4/17 Technical Reviewer Date DWCorbin 1 12/14/17 General Manager Plant Operations Date

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Table of Contents Table of Contents I INTRODUCTION .........................................................................................................1-1 II DEFINITIONS ..............................................................................................................1-2 1.0 PROCEDURAL AND SURVEILLANCE REQUIREMENTS AND BASES .................. 1-8 1.1 GASEOUS EFFLUENT CONTROLS .......................................................... 1-8 1.1.1 Radioactive Gaseous Effluent Monitoring Instrumentation .................................................................... 1-8 1.1.2 Gaseous Effluents Dose Rate ........................................... 1-13 1.1.3 Noble Gases Dose .............................................................. 1-15 1.1.4 1-131, 1-133, Tritium, and Particulate Dose ....................... 1-17 1.1.5 Waste Gas System ............................................................. 1-21 1.2 LIQUID EFFLUENT CONTROLS .............................................................. 1-22 1.2.1 Radioactive Liquid Effluent Monitoring Instrumentation1-22 1.2.2 Liquid Effluents Concentration ......................................... 1-27 1.2.3 Liquid Effluent Dose .......................................................... 1-31 1.3 TOTAL DOSE ........................................................................................~ .. 1-33 1.4 RADIOLOGICAL ENVIRONMENTAL MONITORING .............................. 1-35 1.4.1 The Radiological Environmental Monitoring Program ... 1-35 1.5 SIRW OR TEMPORARY LIQUID STORAGE TANK ................................ 1-51 1.6 SURVEILLANCE REQUIREMENT TIME INTERVALS ............................ 1-53 1.7 SEALED SOURCE CONTAMINATION .................................................... 1-54 2.0 REPORTING REQUIREMENTS ................................................................................. 2-1 2.1 RADIOLOGICAL EFFLUENT RELEASE REPORT ................................... 2-1 2.2 RADIOLOGICAL ENVIRONMENTAL OPERATING REPORTING REQUiREMENTS ........................................................................................2-2 2.2.1 Annual Radiological Environmental Monitoring Report ... 2-2 2.2.2 Non-routine Reports ............................................................ 2-2 3.0 MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID AND WASTE GAS SYSTEMS ...................................................................................................................3-1 3.1 LICENSEE MODIFICATIONS .....................................................................3-1 3.2 DEFINITION OF MAJOR RADWASTE SYSTEM MODIFICATION ............ 3-1

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Table of Contents 3.2.1 Purpose .................................................................................3-1 3.2.2 Definition .............................................................................. 3-2 3.3 ONSITE GROUND WATER MONITORING ................................................ 3-2 4.0 GASEOUS EFFLUENTS ............................................................................................4-1 4.1 GASEOUS EFFLUENT CALCULATIONS .................................................. 4-1 4.1.1 Dose Rate Limits ..................................................................4-1 4.1.2 Dose Rate Calculations .......................................................4-1 4.2 ALARMITRIP SETPOINT METHODOLOGy .............................................. 4-4 4.2.1 Monitor Response ................................................................ 4-4 4.3 APPENDIX I DOSE CALCULATIONS ........................................................4-5 4.3.1 Unrestricted Area Noble Gas Air Dose ............................... 4-5 4.3.2 Radioiodine, Tritium and Particulate Organ Dose to a Member of the Public ........................................................... 4-7 4.4 WASTE GAS SYSTEM OPERATION ....................................................... 4*26 4.4.1 System Description ............................................................ 4-26 4.4.2 Determination of Satisfactory Operation ......................... 4-26 4.5 RELEASE RATE FOR OFFSITE EC ........................................................ 4-26 4.6 PARTICULATE AND IODINE SAMPLING ............................................... 4-27 4.7 NOBLE GAS SAMPLING ......................................................................... 4-27 5.0 LIQUID EFFLUENTS ..................................................................................................5-1 5.1 LIQUID EFFLUENT CALCULATIONS ....................................................... 5-1 5.1.1 Liquid Effluent Concentration Limits ................................. 5*1 5.1.2 Liquid Rad Monitor Setpoint Determination ...................... 5-4 5.1.3 Adjustments To Setpoints ................................................... 5-6 5.2 APPENDIX I DOSE CALCULATIONS ........................................................ 5-9 5.2.1 RETS Requirement ............................................................... 5-9 5.2.2 Liquid Effluent Organ Dose to a Member of the Public .... 5-9 5.2.3 Release Analysis ................................................................ 5-11 5.3 OPERABILITY OF LIQUID RADWASTE EQUIPMENT ........................... 5-11 5.4 RELEASE RATE FOR OFFSITE EC (50 MREMIYR) ............................... 5-11 6.0 URANIUM FUEL CYCLE DOSE ................................................................................. 6-1 ii

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Table of Contents 6.1 ASSUMPTIONS ..........................................................................................6-1 6.2 URANIUM FUEL CYCLE DOSE CALCULATIONS .................................... 6-1 6.2.1 Direct Radiation Dose to a Member of the Public ............. 6-2 6.2.2 Organ Dose to a Member of the Public From Noble Gases ....................................................................................6-2 6.2.3 Organ Dose to a Member of the Public Due to Radioiodines, Tritium and Particulates Released to the Atmos phere .......................................................................... 6-3 6.2.4 Total Uranium Fuel Cycle Dose .......................................... 6-4

7.0 REFERENCES

AND DATA ........................................................................................7-1 7.1 REFERENCE DOCUMENTS ...................................................................... 7-1 7.2 TRANSFER AND BIOACCUMULATION FACTORS ................................. 7-2 7.3 DOSE FACTORS ........................................................................................ 7-4 7.4 METEOROLOGICAL DATA ..................................................................... 7-37 iii

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Table of Contents Tables TABLE 1-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION .................................................................................... 1-9 TABLE 1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING .

INSTRUMENTATION SURVEILLANCE REQUiREMENTS ........................ 1-11 TABLE 1-3 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM .................................................*................................................. 1-19 TABLE 1-4 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION .................................................................................. 1-23 TABLE 1-5 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUiREMENTS ........................ 1-25 TABLE 1-6 -RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM .................................................................................................. 1-29 TABLE 1-7 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM .............. 1-39 TABLE 1-8 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES ................................................................... 1-43 TABLE 1-9 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANAL YSIS A................................................................................................. 1-44 TABLE 1-10 REMP PROGRAM LOCATIONS, TLD ........................................................ 1-49 TABLE 1-10 REMP PROGRAM LOCATIONS, TLD (CONTINUED) ............................... 1-50 TABLE 1-11 REMP PROGRAM LOCATIONS, AIR SAMPLE STATIONS ...................... 1-50 TABLE 1-12 REMP PROGRAM LOCATIONS, PALISADES PARK WELLS ................... 1-51 TABLE 2-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM SUMMARy .................................................................................................... 2-3 TABLE 4-1 X/Q AND D/Q AT LOCATIONS OF INTEREST .......................................... 4-19 TABLE 4-2 PARAMETERS USED IN GASEOUS EFFLUENT DOSE CALCULATIONS ......................................................................................... 4-20 TABLE 5-1 TYPICAL LIQUID RELEASE ALLOCATION FRACTIONS* .......................... 5-6 TABLE 5-2 PARAMETERS USED IN LIQUID EFFLUENT DOSE CALCULATIONS .... 5-11 TABLE 7-1 TRANSFER FACTORS ................................................................................. 7-2 TABLE 7-2 FRESHWATER BIOACCUMULATION FACTORS ....................................... 7-3 TABLE 7-3 NOBLE GAS IMMERSION DOSE FACTORS ............................................... 7-4 TABLE 7-4 ADULT - POTABLE WATER AND FISH INGESTION (Air) ........................... 7-5 TABLE 7-5 GROUND PLANE EXPOSURE - ALL AGE GROUPS (RAI(GP)J) .................... 7-7 TABLE 7-6 INHALATION EXPOSURE -INFANT AGE GROUP (RAI(IN)J) ........................ 7-9 TABLE 7-7 INHALATION EXPOSURE - CHILD AGE GROUP (RAI(IN)J) ........................ 7-11 TABLE 7-8 INHALATION EXPOSURE - TEEN AGE GROUP (RAI(IN)J) ......................... 7-13 TABLE 7-9 INHALATION EXPOSURE - ADULT AGE GROUP (RAI(IN)J) ....................... 7-15 TABLE 7-10 VEGETATION INGESTION - CHILD AGE GROUP (RAI(vG)J) ..................... 7-17 TABLE 7-11 VEGETATION INGESTION - TEEN AGE GROUP (RAI(vG)J) ....................... 7-19 TABLE 7-12 VEGETATION INGESTION - ADULT AGE GROUP (RAI(vG)J) .................... 7-21 TABLE 7-13 MILK INGESTION -INFANT AGE GROUP (RAI(MI)J) ................................... 7-23 TABLE 7-14 MILK INGESTION - CHILD AGE GROUP (RAI(MI)J) ..................................... 7-25 TABLE 7-15 MILK INGESTION - TEEN AGE GROUP (RAI(MI)J) ...................................... 7-27 iv

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Table of Contents TABLE 7-16 MILK INGESTION - ADULT AGE GROUP (RAI(MI)J) .................................... 7-29 TABLE 7-17 MEAT INGESTION - CHILD AGE GROUP (RA1(ME)J) .................................. 7-31 TABLE 7-18 MEAT INGESTION - TEEN AGE GROUP (RA1(ME)J) .................................... 7-33 TABLE 7-19 MEAT INGESTION - ADULT AGE GROUP (RA1(ME)J) ................................. 7-35 TABLE 7-20 PALISADES 10 YEAR X/Q - D/Q DATA ..................................................... 7-37 v

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Table of Contents Figures FIGURE 1.0-1 REMP SAMPLING LOCATIONS AT SEVEN MILES .................................. 1-47 FIGURE 1.0-2 REMP PROGRAM LOCATIONS AT FOUR MILES .................................... 1-48 FIGURE 4.0-1 GASEOUS EFFLUENT FLOW PATHS ....................................................... 4-28 FIGURE 5.0-1 PALISADES SITE BOUNDARy .................................................................. 5-12 FIGURE 5.0-2 LIQUID EFFLUENT FLOW PATHS ............................................................ 5-13 APPENDIXES APPENDIX B REQUEST TO RETAIN SOIL IN ACCORDANCE WITH 10CFR 20.302 REVISION O.

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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 INTRODUCTION The NRC, through 10 CFR Part 50.36a, requires implementation of Technical Specifications on effluents from nuclear power plants. NRC Generic Letter 89-01, dated January 31, 1989, allowed relocation of the existing procedural requirements from the Technical Specifications (implemented in Amendment 85, November 9, 1984). The relocated procedural requirements related to gaseous and liquid effluents, total dose, environmental monitoring program, and associated procedural reporting requirements follow below. Programmatic controls are retained in the Administrative Controls section of the Technical Specification to satisfy the regulatory requirements of 10 CFR Part 50.36a. The Technical Specifications programmatic controls include requirements for the establishment, implementation, maintenance, and changes to the Offsite Dose Calculation Manual (ODCM) as well as record retention and reporting requirements.

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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 II DEFINITIONS

.ABNORMAL DISCHARGE The unplanned or uncontrolled emission of an effluent (ie, containing plant-related, licensed radioactive material) into the UNRESTRICTED AREA.

ABNORMAL RELEASE The unplanned or uncontrolled emission of an effluent (ie, containing plant-related, licensed radioactive material).

ACTION ACTION shall be that part of a Control which prescribes measures required under designated conditions.

ANTICIPATED OPERATIONAL OCCURRENCES ANTICIPATED OPERATIONAL OCCURRENCES mean those conditions of normal operation which are expected to occur one or more times during the life of the nuclear power unit and include but are not limited to loss of power to all recirculation pumps, tripping of the turbine generator set, isolation of the main condenser, and loss of all offsite power.

BATCH RELEASE A BATCH RELEASE is the discharge of wastes of a discrete volume. Prior to sampling for analyses, each liquid batch shall be isolated and thoroughly mixed to ensure representative sampling.

CHANNEL CALIBRATION A Channel Calibration shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The Channel Calibration shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the Channel Function Test. The Channel Calibration may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.

CHANNEL CHECK A Channel Check shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrumentation channels measuring the same parameter.

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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 CHANNEL FUNCTIONAL TEST A Channel Functional Test shall be:

1. Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify operability including alarm and/or trip functions.

2. Bistable channels - the injection of a simulated signal into the sensor to verify operability including alarm and/or trip functions.

CONTINUOUS RELEASE An essentially uninterrupted release of gaseous or liquid effluent for extended periods during normal operation of the facility where the volume of radioactive waste is non-discrete and there is input flow during the release.

CONTROLLED DISCHARGE A radioactive discharge is considered to be "controlled" if (1) the discharge was conducted in accordance with methods, and without exceeding any of the limits, outlined in the ODCM, or (2) if one or more of the following three items are true:

1. The radioactive discharge had an associated, pre-planned method of radioactivity monitoring that ensured the discharge was properly accounted and was within the limits set by 10 CFR Part 20 and 10 CFR Part 50.

2. The radioactive discharge had an associated, pre-planned method of termination (and associated termination criteria) that ensured the discharge was properly accounted and was within the limits set by 10 CFR Part 20 and 10 CFR Part 50.

3. The radioactive discharge had an associated, pre-planned method of adjusting, modulating, or altering the flow rate (or the rate of release of radioactive material) that ensured the discharge was properly accounted and was within the limits set by 10 CFR Part 20 and 10 CFR Part 50.

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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 CONTROLLED RELEASE A radioactive release is considered to be "controlled" if (1) the release was conducted in accordance with methods, and without exceeding any of the limits, outlined in the ODCM, or (2) if one or more of the following three items are true:

1. The radioactive release had an associated, pre-planned method of radioactivity monitoring that ensured the release was properly accounted and was within the limits set by 10 CFR Part 20 and 10 CFR Part 50.

2. The radioactive release has an associated, pre-planned method of termination (and associated termination criteria) that ensured the release was properly accounted and was within the limits set by 10 CFR Part 20 and 10 CFR Part 50.

3. The radioactive release had an associated, pre-planned method of adjusting, modulating, or altering the flow rate (or the rate of release of radioactive material) that ensured the release was properly accounted and was within the limits set by 10 CFR Part 20 and 10 CFR Part 50.

CRITICAL ORGAN That organ, which has been determined to be the maximum exposed organ based on an effluent pathway analysis, thereby ensuring the dose and dose rate limitations to any other organ will not be exceeded.

CRITICAL RECEPTOR Represents that MEMBER OF THE PUBLIC in the UNRESTRICTED AREA who as a result of the combination of age group and existing local dose exposure pathways has the potential to receive the highest dose.

DOSE EQUIVALENT 1-131 The DOSE EQUIVALENT 1-131 is that concentration of 1131 (~9i/gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of 1131,1132,1133,1134, and 1135 actually present. The dose conversion factors used for this calculation are those listed in Table 2.1 of EPA Federal Guidance Report No 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion,"

EPA-520/1-88-020, September 1988. Alternately, dose conversion factors from Tables E-7 to E-14 of NRC Regulatory Guide 1.109, Revision 1, may be used.

EFFLUENT DISCHARGE The portion of an EFFLUENT RELEASE that reaches an UNRESTRICTED AREA.

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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 EFFLUENT RELEASE The emission of an effluent.

FREQUENCY NOTATIONS NOTATION FREQUENCY S-Once per shift At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D-Daily At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months W-Weekly At least once per 7 days M-Monthly At least once per 31 days Q-Quarterly At least once per 92 days SA-Semi-annually At least once per 184 days R-Refueling At least once per 18 months P-Prior to release Completed prior to each batch release NA-Not applicable Not applicable Note:

Frequencies are allowed a maximum extension of 25 percent.

Extension of 25 percent shall not be used to perform less surveillance tests over a period than defined by the frequency notation.

GASEOUS RADWASTE TREATMENT SYSTEM Any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system off gases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

GASPAR II An NRC computer code that calculates doses from releases to the atmosphere for the purpose~ of demonstrating compliance with 10 CFR Part 50, App I. GASPAR II implements the methodology of Regulatory Guide 1.109 and can be used as an alternate means of calculating App I doses.

GROUND WATER All water in the surface soil, the subsurface soil, or any other subsurface water. GROUND WATER is simply water in the ground regardless of its quality, including saline, brackish, or fresh water. GROUND WATER can be moisture in the ground that is above the regional water table in the unsaturated (or vadose) zone, or GROUND WATER can be at and below the water table in the saturated zone.

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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 ISFSI Independent Spent Fuel Storage Installation.

LADTAP" An NRC computer code that calculates doses from releases to the hydrosphere for the purposes of demonstrating compliance with 10 CFR Part 50, App I. LADTAP" implements the methodology of Regulatory Guide 1.109 and can be used as an alternate means of calculating App I doses.

LIQUID WASTE MANAGEMENT SYSTEM A LIQUID WASTE MANAGEMENT SYSTEM is any system designed and installed to reduce radioactive materials in liquid effluents by systematic collection, retention, and processing prior to release.

LOWER LIMIT OF DETECTION (LLO)

The smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with a 95% probability with only 5% 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.

MAXIMUM EXPOSED INDIVIDUAL Individuals characterized as maximum with regard to food consumption, occupancy, and other usage of the region in the vicinity of the plant site. As such, they represent individuals with habits that are considered to be reasonable deviations from the average for the population in general. Additionally, in physiological or metabolic respects, the maximum exposed individuals are assumed to have those characteristics that represent the averages for their corresponding age group in the general population.

MEMBER OF THE PUBLIC Any individual except when that individual is receiving an occupational dose. Also excluded from this category are persons who enter the site to service equipment or to make deliveries.

OPERABLE (OPERABILITY)

A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, SUbsystem, train, component or device to perform its function(s) are also capable of performing their related support function(s).

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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 OFFSITE DOSE CALCULATION MANUAL As defined by the Plant Technical Specifications, the Offsite Dose Calculation Manual (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm/trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain: 1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by the Technical Specifications, and 2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by the Technical Specifications.

PROCESS CONTROL PROGRAM Shall contain the current formula, sampling, analyses, tests, and determinations to be made to ensure that the processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Part 20, 10 CFR Part 71 and Federal and State regulations and other requirements governing the disposal of the radioactive waste.

SITE BOUNDARY That line beyond which the land is neither owned nor otherwise controlled by the licensee.

See FIGURE 5.0-1.

SOURCE CHECK A source check shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

UNRESTRICTED AREA Any area at or beyond the Site Boundary, access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or, any area within the Site Boundary used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

VENTILATION EXHAUST TREATMENT SYSTEM Any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents.

Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be ventilation exhaust treatment system components.

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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 1.0 PROCEDURAL AND SURVEILLANCE REQUIREMENTS AND BASES 1.1 GASEOUS EFFLUENT CONTROLS 1.1.1 Radioactive Gaseous Effluent Monitoring Instrumentation CONTROL 1.1 .1.1 The radioactive gaseous effluent,monitoring instrumentation channels shown in Table 1-1 shall be operable with their alarm/trip setpoints set to ensure that the limits of Control 1.1.2.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

Action

a. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above requirement, without delay, suspend the release of radioactive gaseous 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 gaseous effluent monitoring instrumentation channels operable, take the action shown in Table 1-1. Exert best efforts to return the instruments to operable status within 30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

Surveillance Requirements 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 1-2.

Bases The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of Control 1.1.2.1.

The operability and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 1-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum Instrument Operable Applicability Action Channels

1. WASTE GAS HOLDUP SYSTEM

a. Noble Gas Activity Monitor (RIA 1113) (1 ) At All Times 1 Providing Alarm and Automatic Termination of Release

2. CONDENSER EVACUATION SYSTEM (RIA 0631)

a. Noble Gas Activity Monitor (1 ) Above 210°F 3 Modes 1, 2, 3, 4

b. Evacuation Flow Indicator (FI-0631 or FI-0632) (1 )*** Above 210°F Modes 1, 2, 3, 4

3. STACK GAS EFFLUENT SYSTEM

a. Noble Gas Activity Monitor (RIA 2326)* (1 ) At All Times 3

b. lodine/Particulate/SampJer/Monitor (RIA 2325) (1 ) At All Times 6

c. Sampler Flow Rate Monitor (Fe-2346) (1 ) At All Times 2

d. Hi Range Noble Gas (RIA 2327)*

(1 ) Above 210°F 4 Modes 1,2,3,4

4. STEAM GENERATOR BLOWDOWN VENT SYSTEM

a. Noble Gas Activity Monitor (RIA 2320) (1 ) Above 210°F 3 Modes 1, 2, 3, 4

5. MAIN STEAM SAFETY AND DUMP VALVE DISCHARGE LINE

a. Gross Gamma Activity Monitor* 1 per Main Above 325°F 4 (RIA 2323 and 2324) Steam line Modes 1, 2, 3

6. ENGINEERED SAFEGUARDS PUMP ROOM VENTI LATION HIGH RADIATION SYSTEM

a. Noble Gas Activity Monitor ** 1 per Room Above 210°F 5 (RIA 1810 and 1811) Modes 1, 2, 3, 4

Setpoints for these instruments are exempt from 1.1.2.1 limits, but are governed by Emergency Implementing Procedures or Operating procedures.

- Setpoints for these instruments are exempt from 1.1.2.1 limits, but are governed by Technical Specifications SR 3.3.10.3.

- - Documentation of operability not required .

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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 1-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION (CONTINUED)

ACTION STATEMENTS ACTION 1 With the number of channels operable less than required by the Minimum Operable Channels requirements, the contents of the tank(s) may be released to the environment provided that prior to initiating the release:

a. At least two independent samples of the tank's contents are analyzed, and

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve line up; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 2 With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 3 With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 4 With the number of operable channels less than required by the Minimum Operable Channels requirements, initiate the preplanned alternate method of monitoring the appropriate parameter(s), within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

a. Either restore the inoperable channel(s) to operable status within 7 days of the event, or

b. Prepare and submit a Special Report to the NRC within 30 days following the event outlining the actions taken, the cause of the inoperability, and the plans and schedule for restoring the system to operable status.

ACTION 5 If either channel fails low or is otherwise inoperable, the ventilation dampers associated with that channel shall be closed immediately and action shall be taken to have the affected channel repaired. The dampers associated with the channel shall not be opened until the affected channel has been declared operable.

(Reference Technical Specifications LCO 3.3.10.)

ACTION 6 With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases via the affected pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Table 1-3.

1-10

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 1*2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Channel Modes in Which Channel Source Channel Instrument Functional Surveillance Check Check Calibration Test Required

1. WASTE GAS HOLDUP SYSTEM

a. Noble Gas Activity Monitor-Providing Alarm and 0(4) P R(3) 0(1)(2)

Automatic Termination of Release

2. CONDENSER EVACUATION SYSTEM

a. Noble Gas Activity Monitor 0 M R(3) 0(2) Above 210°F

b. Evacuation Flow Indicator (FI-0632) or Modes 1, 2, 3, 4

c. Evacuation Flow Indicator (FI-0631)

3. STACK GAS EFFLUENT SYSTEM

a. Noble Gas Activity Monitor 0 M R(3) 0(2)

b. Iodine Particulate Sampler/Monitor W M" R(3)*' NA

c. Sampler Flow Rate Monitor 0 NA R NA

d. Hi Range Noble Gas 0 M R(3) 0(2) . Above 210°F Modes 1, 2, 3, 4

4. STEAM GENERATOR BLOWDOWN VENT SYSTEM

a. Noble Gas Activity Monitor 0 M R(3) 0(2) Above 210°F Modes 1, 2, 3, 4

5. MAIN STEAM SAFETY AND DUMP VALVE DISCHARGE LINE

a. Gross Gamma Activity Monitor 0 M R(3) 0(2) Above 325°F Modes 1, 2, 3

6. ENGINEERED SAFEGUARDS PUMP ROOM VENTILATION HIGH RADIATION SYSTEM

a. Noble Gas Activity Monitor 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 31 days 18 months(3) 31 days(1 )(2) Above 210°F (Technical Specifications SR 3.3.10 and Modes 1, 2,3,4 SR 3.7.13.1) 1-11

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 1-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS (CONTINUED)

At all times other than when the line is valved out and locked.

Sampler not applicable This type of Flowmeter doesn't have any surveillance requirements.

TABLE NOTATIONS (1) The Channel Functional Test shall also demonstrate that automatic isolation of this pathway occurs if instrument indicates measured levels above the alarm/trip setpoin!.

(2) The Channel Functional Test shall also demonstrate that Control Room alarm annunciation occurs if either of the following conditions exists.

a. Instrument indicates measured levels above the alarm setpoint (not applicable for Item 3.d, Hi Range Noble Gas).

b. Circuit fa ilure.

(3) The Channel Calibration shall be performed using one or more of the reference standards traceable to the National Institute of Standards and Technology 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 range of energy and measurement range.

For subsequent Channel Calibration, sources that have been related to the primary calibration may be used.

(4) Cha~nel Check shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous or batch releases are made.

1-12

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 1.1.2 Gaseous Effluents Dose Rate CONTROL 1.1.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the Site Boundary (see FIGURE 5.0-1) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and

b. For lodine-131, for lodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.

Action With the dose rate(s) averaged over a period of one hour exceeding the above limits, without delay, restore the release rate to within the above limit(s).

Surveillance Requirements

a. 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 in the ODCM.

b. The dose rate due to lodine-131, lodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits of in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 1-3.

1-13

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Bases This specification provides 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 beyond the Site Boundary, excess of the design objectives of 10 CFR Part 50, Appendix I. This specification is provided to ensure that gaseous effluents from all units on the site will be appropriately controlled. It provides operational flexibility for releasing gaseous effluents to satisfy the Section II.B.1.A and II.C design objectives of 10 CFR Part 50. For Members of the Public who may at times be within the Site Boundary, the occupancy of the Member of the Public will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the Site Boundary. Equations for calculations for such Members of the Public, with the appropriate occupancy factors, shall be given in the ODeM. The specified release rate limits restrict, at all times, the corresponding dose rate above background to a Member of the Public at or beyond the Site Boundary to less than or equal to 500 mrems/yr to the total body or less than or equal to 3000 mrem/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem/yr. This specification does not affect the requirement to comply with the annual limitation of 10 CFR Part 20.1301 (a).

The required detection capabilities for radioactive materials in gaseous 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 HASL Procedures Manual, HASL-300, Currie, LA, "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal Chern 40,586-93 (1968), and Hartwell, JK, "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

1-14

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 1.1.3 Noble Gases Dose CONTROL 1.1.3.1 The air dose due to noble gases released in gaseous effluents to areas at and beyond the Site Boundary (see FIGURE 5.0-1) shall be limited to the following:

a. During any calendar 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 any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

Action With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC within 30 days a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

Surveillance Requirements Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

1-15

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Bases This requirement is provided to implement the requirements of Sections II.B, liLA, and IV.A of Appendix I, 10 CFR Part 50. The limiting Condition for Operation implements the guides set forth in Section II.B of Appendix I. The Action statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the 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 Section liLA of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a Member of the Public through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters 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 10 CFR Part 50, Appendix 1," 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 ODeM equations provided for determining the air doses at and beyond the Site Boundary are based upon the historical average atmospheric conditions.

1-16

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL

)

Revision 29 1.1.4 1-131,1-133, Tritium, and Particulate Dose CONTROL 1.1.4.1 The dose to a Member of the Public from lodine-131, lodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, to areas at and beyond the Site Boundary (see FIGURE 5.0-1) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ, and

b. During any calendar year: Less than or equal to 15 mrems to any organ.

Action With the calculated dose from the-release of lodine-131, lodine-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 NRC within 30 days a Special Report that identifies the cause(s) for exceeding the limit and define(s) the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

Surveillance Requirements Cumulative dose contributions for the current calendar quarter and current calendar year for lodine-131, lodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODeM at least once per 31 days.

1-17

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Bases This requirement is provided to implement the requirements of Sections II.C, liLA, and IV.A of Appendix I, 10 CFR Part 50. The requirements are the guides set forth in Section II.C of Appendix I. The Action statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents 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 Section liLA of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a Member of the Public through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters 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 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases From Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate requirements for lodine-131, lodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in areas at and beyond the Site Boundary. The pathways that were examined in the development 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.

1-18

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 1-3 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit Sampling Type of Gaseous Release Type Analysis Detection (LLD)"

Frequency Activity Analysis Frequency (IICi/ml)

A. Waste Gas Storage Tank P P Principal Gamma Emitters* 1 x 10*"

Each Tank Each Tank Grab Sample B. Containment PURGE P P Principal Gamma Emitters* 1 x 10*"

Each PURGE Each PURGE Grab Sample C. Stack Gas Effluent Continuous* W*,* 1.131,1-1339 1 x 10*'2 Charcoal Sample Continuous* W** Principal Gamma Emitters* 1 x 10.11 Particulate Sample Continuous* a Sr-89, Sr-90 1 x 10.11 Composite Particulate Sample Continuous M Gross Alpha 1 x 10.11 Composite Particulate Sample Continuous* Noble Gas Noble Gases 1 x 10**

Monitor Gross Beta or Gamma Grab Sample NA" Noble Gas 1 x 10-4 D. Condenser Evacuation System Continuous Noble Gas Monitor Noble Gases 1 x 10**

Grab Sample W' Principal Gamma Emitters* 1 x 10" 1-19

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 1*3 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM (CONTINUED)

TABLE NOTATIONS a . The LLD is defined in Table 1-9, note C.

b. 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, Cs-134, CS-137, Ce-141 , and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be considered . Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report.

c. The ratio of the sample flow rate to the sample stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Controls 1.1.2.1, 1.1.3.1, and 1.1.4.1.

d . Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing or after removal from sampler.

e. With channels operable on iodine monitor RIA 2325 less than required per Control 1.1.1 .1, sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, start-up or Thermal Power change exceeding 15 percent of Rated Thermal Power in one hour and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing . When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a factor of 10.

This requirement does not apply if:

1) analysis shows that the Dose Equivalent 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.

f. Obtain and analyze a gas sample weekly for noble gas quantification.

g. Sample analysis requirement includes 1-133 however; there is no required LLD for 1-133.

h. This sample refers to the compensatory noble gas grab sample under Action 3 in Table 1-1 Section 3.a.

1-20

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 1.1.5 Waste Gas System CONTROL 1.1.5.1 When gaseous waste exceeds a Xe-133 concentration of 1E-05 ~Ci/cc, the Waste Gas Decay Tank System shall be used to reduce radioactive gaseous effluents by holding gaseous waste collected by the system for a minimum of 15 days.

Action

a. If a waste gas decay tank is required to be released with less than 15 days holdup time, the system waste gas tank contents shall be evaluated and the waste gas decay tank with the lowest dose consequence shall be released.

b. Gaseous waste may be discharged directly from the waste gas surge tank through a high-efficiency filter or from a waste gas decay tank with less than 15 days of holdup directly to the stack for a period not to exceed 7 days if the holdup system equipment is not available and the release rates meet Controls 1.1.2.1,1.1.3.1 and 1.1.4.1.

Surveillance Requirements Not Applicable.

Bases The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable" by meeting the design objectives given in Section 11.0 of Appendix I to 10 CFR Part 50.lt is expected that releases of radioactive materials in effluents shall be kept at small fractions of the limits specified in 20.1302 of 10 CFR Part 20. At the same time the licensee is permitted the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided a dependable source of power even under unusual operating conditions which may temporarily result in releases higher than such small fractions, but still within the limits specified in Controls 1.1.2.1, 1.1.3.1 and 1.1.4.1.

1-21

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 1.2 LIQUID EFFLUENT CONTROLS 1.2.1 Radioactive Liquid Effluent Monitoring Instrumentation CONTROL 1.2.1.1 The radioactive liquid effluent monitoring instrumentation channels shown in Table 1-4 shall be operable with their alarm/trip setpoints set to ensure that the limits of 1.2.2.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the Offsite Dose Calculation Manual (ODCM).

Action

a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, without delay 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 1-4.

Exert best efforts to return the instruments to Operable status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

Surveillance Requirements 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 1-5.

Bases 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 and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding 10 times the limits of 10 CFR Part 20. The Operability and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

1-22

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 1-4 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Minimum Operable Applicability Action Instrument Channels

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE (1 ) For Effluent Releases 1

a. Liquid Radwaste Effluent Line (RIA 1049)

(1 ) For Effluent Releases 2

b. Steam Generator Blowdown Effluent Line (RIA 0707)

2. GROSS BETA OR GAMMA RADIOACTIVE MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE (1 ) For Effluent Releases 3

a. Service Water System Effluent Line (RIA 0833)

(1 ) For Effluent Releases 3

b. Turbine Building (Floor Drains) Sumps Effluent Line (RIA 5211)

3. FLOW RATE MEASUREMENT DEVICES (1 ) For Effluent Releases 4

a. Liquid Radwaste Effluent Line (Fie 1051 or 1050)

4. CONTINUOUS COMPOSITE SAMPLERS (AlarmlTrip Setpoints are not applicable)

(1 ) For Effluent Releases 3

a. Turbine Building Sumps Effluent Line (M-1051)

(1 ) For Effluent Releases 3

b. Service Water System Effluent (M-1052)

(1 ) For Effluent Releases 3

c. Steam Generator Blowdown Effluent 1-23

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 1-4 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION TABLE (CONTINUED)

TABLE NOTATIONS ACTION 1 With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases may continue provided that prior to initiating a release:

a. At least two independent samples are analyzed in accordance with requirements 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 2 With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases via this pathway may continue provided grab samples are analyzed for radioactivity at a lower limit of detection as specified in Table 1-9 Note c. for principle gamma emitters and 1-131 at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

NOTE: The Steam Generator blowdown monitor is normally used in a clean up closed loop system instead of as an effluent monitor. The action statement only applies when the monitor is used as an effluent monitor.

ACTION 3 With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases via this pathway may continue provided that, at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , grab samples are collected and analyzed for radioactivity at a lower limit of detection as specified in Table 1-6 for principle gamma emitters and 1-131.

ACTION 4 With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump performance curves or tank levels may be used to estimate flow.

1-24

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 1*5 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Channel Channel Source Channel Instrument Functional Check Check Calibration Test

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste Effluent Line (RIA 1049) P P R(3) Q(1)(2)

b. Steam Generator Blowdown Effluent Line (RIA 0707) 0 M R(3) Q(l )(2)

2. GROSS GAMMA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Service Water System Effluent Line (RIA 0833) 0 M R(3) Q(2)

b. Turbine Building (Floor Drains) Sumps Effluent Line (RIA 5211) D M R(3) Q(2)

3. FLOW RATE MEASUREMENT DEVICES (5)

a. Liquid Radwaste Effluent Line (Fie 1051 or 1050) 0(4) NA R NA

4. TURBINE SUMP EFFLUENT COMPOSITOR 0(4) NA NA NA

5. SERVICE WATER SYSTEM EFFLUENT COMPOSITE SAMPLER 0(4) NA NA NA

6. STEAM GENERATOR BLOWDOWN EFFLUENT COMPOSITOR D(4) NA NA NA

7. TURBINE SUMP TOTALIZER (FQ15210) NA NA R(5) NA 1-25

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 1-5 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS (CONTINUED)

TABLE NOTATIONS (1 ) The Channel Functional Test shall also demonstrate that automatic isolation of this pathway occurs if instrument indicates measured levels above the alarm/trip setpoint.

(2) The Channel Functional Test shall also demonstrate that Control Room alarm annunciation occurs if either of the following conditions exists:

a. Instrument indicates measured levels above the alarm setpoint.

b. Circuit failure.

(3) The Channel Calibration shall be performed using one or more of the reference standards traceable to the National Institute of Standards and Technology 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 range of energy and measurement range.

For subsequent Channel Calibration, sources that have been related to the primary calibration may be used.

(4) Channel Check shall consist of verifying indication of flow during periods of releases. Channel Check shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous or batch releases are made.

(5) Turbine Sump Totalizer is replaced at least once per 18 months. Calibration is performed by the factory.

1-26

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 1.2.2 Liquid Effluents Concentration CONTROL 1.2.2.1 The concentration of radioactive material released in liquid effluents to Unrestricted Areas shall be limited to 10 times the concentrations specified in 10 CFR Part 20, Appendix S, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10-4 microCuries/ml total activity.

Action With the concentration of radioactive material released in liquid effluents to Unrestricted Areas exceeding the above limits, without delay, restore the concentration to within the above limits.

Surveillance Requirements

a. Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 1-6.

b. 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 1.2.2.1 above.

1-27

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Bases This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to Unrestricted Areas will be less than 10 times the concentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. The specification provides operational flexibility for releasing liquid effluents in concentrations to follow the Section II.A and II.C design objectives of Appendix I to 10 CFR Part 50. This limitation provides reasonable 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 Appendix I, 10 CFR Part 50, to a Member of the Public and (2) restrictions authorized by 10 CFR Part 20.1301 (e). The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its 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.

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 HASL Procedures Manual, HASL-300, Currie, LA, "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal Chem 40,586-93 (1968), and Hartwell, JK, "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

1-28

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 1-6 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Sampling Minimum Analysis Liquid Release Type Type of Activity Analysis Detection (LLD)"

Frequency Frequency (IlCi/ml)

A. Batch Waste Release Tanks* P P Principal Gamma Emitters C 5 x 10-7 Each Batch Each Batch 1-131 1 x 10" P M Dissolved and Entrained Gases 1 x 10-'

One Batch/Month (Gamma Emitters)

P M H-3 1 x 10-'

Each Batch Composite d Gross Alpha 1 x 10-7 P a Sr-89, Sr-9O 5 x 10" Each Batch Composite d Fe-55, Ni-63 1 x 10" B. Continuous Releases' Continuous' W Principal Gamma EmittersC 5 x 10-7 (Turbine Sump, Steam Generator Composite' 1-131 1 x 10" Blowdown, and Service Water)

M M Dissolved and Entrained Gases 1 x 10-'

Grab Sample (Gamma Emitters)

Continuous' M H-3 1 x 10-'

Composite' Gross Alpha 1 x 10-7 Gross Beta (service water only) 1 x 10-7 Continuous' a Sr-89, Sr-90 5 x 10" Composite' Fe-55 Ni-63 1 x 10.6 1-29

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 1-6 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM (CONTINUED)

TABLE NOTATIONS

a. The LLD is defined in Table 9-1, note c.

b. 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.

c. The principal gamma emitters for which the LLD sJ)ecification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141. A LLD of 5 x 10'6 ~Ci/ml is acceptable for Ce-144 because of low gamma yields. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report.

d. 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 that is representative of the liquids released.

e. A continuous release is the discharge of liquid wastes of a nondiscrete volume; eg, from a volume of a system that has an input flow during the continuous release.

f. To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected in a series of aliquots of constant volume collected at regular time intervals and combined to form a single sample. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

1-30

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 1.2.3 Liquid Effluent Dose CONTROL 1.2.3.1 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 shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, and

b. During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.

Action With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the NRC within 30 days a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. This Special Report shall also include the results of radiological analyses of the drinking water source.

Surveillance Requirements Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once every 31 days.

1-31

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Bases This requirement is provided to implement the requirements of Sections II.A, liLA, and IV.A of Appendix 1,10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I. The Action statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to Unrestricted Areas will be kept "as low as is reasonably achievable." Also, for freshwater sites with drinking water supplies that can be potentially affected by Plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR Part 141. The dose calculation methodology and parameters in the ODCM implement the requirements in Section liLA of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of 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 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 1,"

Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents From Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix 1," April 1977.

1-32

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 1.3 TOTAL DOSE CONTROL 1.3.1.1 The annual (calendar year) dose or dose commitment to any Member of the Public due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

Action With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of 1.1.3.1 a, 1.1.3.1 b, 1.1.4.1 a, 1.1.4.1 b, 1.2.3.1 a, or 1.2.3.1 b, calculations should be made including C-14 and direct radiation contributions from the reactor units and from outside storage tanks to determine whether the above limits of Control 1.3.1.1 have been exceeded.

If such is the case, prepare and submit to the NRC within 30 days a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.2203, shall include an analysis that estimates the radiation exposure (dose) to a Member of the Public from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request and a variance is granted until staff action on the request is complete.

Surveillance Requirements Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Sections 4.3.1, 4.3.2, and 5.2.2. Alternately Section 6.2.2 may be used to calculate noble gas organ dose.

The doses from liquid and gaseous effluents may also be determined by the GASPAR II and LADTAP II codes as documented in NUREG 4013 (LADTAP II) and NUREG 4653 (GASPAR II).

Cumulative dose contributions from direct radiation from the reactor units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in the Action of Control 1.3.1.1 above.

1-33

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Bases This requirement is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. It also requires the preparation and submittal of a Special Report whenever the calculated doses from Plant generated radioactive effluents and direct radiation exceed 25 mrems to the total body or any organ, except for thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a Member of the Public will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose tb a Member of the Public to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the Member of the Public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered.

If the dose to any Member of the Public is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190 and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20. 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.

1-34

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 1.4 RADIOLOGICAL ENVIRONMENTAL MONITORING 1.4.1 The Radiological Environmental Monitoring Program CONTROL 1.4.1.1 The radiological environmental monitoring program shall be conducted as specified in Table 1-7.

Action

a. With the radiological environmental monitoring program not being conducted as specified in Table 1-7, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report 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 1-8 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days a Special Report that identifies the cause(s) for exceeding the calendar year limit(s) of Controls 1.1.3.1, 1.1.4.1 and 1.2.3.1 and defines the corrective actions to be taken to reduce radioactive effluents. When more than one of the radionuclides in Table 1-8 are detected in the sampling medium, this report shall be submitted if:

Concentration (1) + Concentration(2) + Concentration (i) >1 0 Reporting Level (1) Reporting Level (2) Reporting Level (i) - .

(1.0-1 )

When radionuclides other than those in Table 1-8 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 calendar year limits of Controls 1.1.3.1, 1.1.4.1, and 1.2.3.1. 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.

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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 1-7, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days. The specific locations from which samples were unavailable may then be deleted from the monitoring program.

Identify the cause of the unavailability of samples and identify the new location(s) for obtaining replacement samples in the next Annual Radiological Environmental Operating Report.

Surveillance Requirements

a. The radiological environmental monitoring samples shall be collected pursuant to Table 1-7 and shall be analyzed pursuant to the requirements of Table 1-7 and the detection capabilities required by Table 1-9.

b. A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 9 overland 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.

c. 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 and shall be included in a site procedure which maintains implementation of conducting the land use census. .

d. Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that has been approved by the NRC.

e. A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report.

f. The environmental air samplers shall be operationally checked monthly and airflow calibration process visually observed annually.

1-36

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Bases

a. Monitoring Program The radiological environmental monitoring program 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 station operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 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. The initially specified monitoring program will be effective for at least the first three 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 Table 1-9 are considered optimum for routine environmental measurements in industrial laboratories.

Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300, Currie, LA, "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry,"

Anal Chem 40, 586-92 (1968), and Hartwell, JK, "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-15 (June 1975).

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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29

b. Land Use Census:

This requirement 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 are made if required by results of this census. The best information from the door-to-door survey, from aerial surveyor from consulting with local agricultural authorities shall be used.

This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 50 m2 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 (16 kg/yr) 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 (ie, similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m 2 .

c. 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 Section IV.B.2 of Appendix I to 10 CFR Part 50.

1-38

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 1*7 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sampling and Exposure Pathway Number of Representative Type and Frequency Collection and/or Sample Samples and Sample Locations' of Analysis Frequency

1. DIRECT RADIATION" 23 routine monitoring stations either with tWo or more Quarterly Gamma dose quarterly dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:

One on site TLD in the vicinity of the Plant.

An inner ring of stations, one in each overland meteorological sector (9) in the general area ofthe Site Boundary and one additional location near the State Park camping area in the NE sector.

An outer ring of stations, one in each overland meteorological sector (9) within the 12 km range from the site.

The balance of the stations (3) to be placed to serve as control stations.

2. AIRBORNE Radioiodine and Samples from 5 locations. Continuous sample Radioiodine Canister:

Particulates operation with 1-131 analysis weekly for each 3 samples from within 6 km of the Site Boundary in sample collection filter"change.

different sectors (2.5 km-SSW, 5.8 km-ESE and weekly or more

.96 km-NE). frequently if required Particulate Samlller:

by dust loading. Gross beta radioactivity 1 sample from the vicinity of a community having the analysis following filter highest calculated annual average ground level DIQ changed. Gamma isotopic*

(Covert-6.2 km-SE). analysis on quarterly composite 1 sample from a control location in the least prevalent wind direction* (Grand Rapids 82 km-NEt.

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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Sampling and Exposure Pathway Number of Representative Type and Frequency Collection andlor Sample Samples and Sample Locations' of Analysis Frequency

3. WATERBORNE

a. Lake (surface) Plant lake water inlet. Composite sample Gamma isotopic* and tritium over 1-month analyses monthly.

periodf *

b. Lake (drinking) 1 sample of South Haven drinking water supply. Composite sample Gamma isotopic*, gross beta, over 1-month and tritium analyses monthly.

periodf

1 sample from a control location (Ludington Pumped Composite sample Gamma isotopic', gross beta, Storage 201 km N) over 1-month and tritium analyses monthly.

periodf *

c. Well (drinking) 1 grab sample per month when Palisades Park 1 grab sample per Gamma isotopic* and tritium community drinking water well is in operation (Park is month when analyses monthly when Park seasonal in operations and is only open for the summer operational is operational.

months)

d. Sediment from 1 sample from between north boundary and Van Buren Semiannually Gamma isotopic* analysis shoreline State Park beach, approximately Y. mile north of the Plant semiannually.

discharge.

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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Sampling and Exposure Pathway Number of Representative Type and Frequency Collection and/or Sample Samples and Sample Locations' of Analysis Frequency

4. INGESTION

a. Milk Samples from milking animals in 3 locations between Monthly Gamma isotopic* and 1-131 5-8 km distance. analyses monthly.

1 sample from milking animals at a control location. Monthly Gamma isotopic' and 1-131 15-30 km distance. analyses monthly.

b. Broad leaf vegetation Samples of 3 different kinds of broad leaf vegetation grown Monthly during Gamma isotopic* and 1-131 nearest each of two different offsite locations of highest growing season analyses predicted annual average ground level D/Q if milk sample is not performed. (SE or SSE sectors near site.)

1 sample of each of the similar broad leaf vegetation grown Monthly during Gamma isotopic' and 1-131 15-30 km distance in the least prevalent wind direction if growing season analyses milk sampling is not performed. (NNE or NE sectors.)

c. Fish Sample 2 species of commercially and/or recreationally Sample in season or Gamma isotopic* analysis important species in vicinity of Plant discharge area. semiannually if they 1 sample of same species in areas not influenced by Plant are not seasonal.

discharge.

d. Food Products 1 sample each of two principal fruit crops (blueberries and At time of harvestg Gamma isotopic* and 1-131 apples). analyses.

1-41

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 1*7 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (CONTINUED)

TABLE NOTATIONS

a. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report. 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 alternative media and locations may be chosen for the partic;:ular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program.

b. One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place, 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 or phosphor readout zones in a packet are considered as two or more dosimeters.

c. The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be substituted.

d. Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

e. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

f. A composite sample is one in which the quantity (aliquot) of liquid samples is proportional to the quantity of liquid discharged and in which the method of sampling employed results in a specimen that is representative of the liquid released (continuous composites or daily grab composites which meet these criteria are acceptable).

g. If harvest occurs more than once a year, sampling shall be performed during each discrete harvest.

h. The Control Air sample results from Cook Nuclear Plant, except Coloma, may be used as a backup of the Grand Rapids control.

1-42

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 1-8 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Water Airborne Particulates Fish Milk Food Products Analysis (pCill) or Gases (pCi/ml) (pCi/kg, Wet) (pCi/l) (pCi/kg, Wet)

H-3 20,000" Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 2"" 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 8a-La-140 200 300 For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCill may be used.

- If no drinking water pathway exists, a value of 15 pCill may be used .

1-43

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 1-9 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS 8 Lower Limit of Detection (LLD)bc Water Airborne Particulates Fish Milk Food Products Sediment Analysis (pCill) or Gases (pCi/m3) (pCi/kg, Wet) (pC ill) (pCi/kg, Wet) (pCi/kg, Dry)

Gross Beta 4 0.01 H-3 2,000' Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Zn-65 30 260 Zr-95 15 Nb-95 15 1-131 1** 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140e 60 60 La-140 15 15 If no drinking water pathway exists, a value of 3,000 pCill may be used.

- If no drinking water pathway exists, a value of 15 pCill may be used .

1-44

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 1*9 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS (CONTINUED)

TABLE NOTATIONS

a. 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.

b. Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.

c. The LLD is defined as the smallest concentration of radioactive material if! 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.

The LlD is defined as:

LLD = -=-::-=-2.=7=1-;+-;--4._6-;6_S=:b--:-:~

EV2.22 Yexp(-AiAt)

(1.0*2)

WHERE: LLD The "a priori" lower limit of detection as defined above (as pCi per unit mass or volume). Current literature defines the llD as the detection capability for the instrumentation only and the MOC, the minimum detectable concentration, as the detection capability for a given instrument procedure and type of sample.

4.66 = The Gaussian statistic based on 95% probability of detection.

2.71 Term that may be used to account for minor deviations of the Poisson distribution from the Gaussian.

The standard deviation of the background counting rate or the counting rate of a blank sample as appropriate sample time (in counts per minute).

E = The counting efficiency (in counts per disintegration).

V The sample size (in units of mass or volume).

2.22 The number of transformations per minute per picocurie.

Y The fractional radiochemical yield, when applicable.

= The radioactive decay constant for radionuclide "i".

= The elapsed time between midpoint of sample collection and time of counting.

1-45

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 1-9 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS (CONTINUED)

Typical values of E, V, y, and ll.t should be used in the calculation .

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. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.

d. The LLD for Ba-140 is based upon the Radiological Assessment Branch Technical Position Revision 1 of Regulatory Guide 4.8. Regulatory Guide 4.8, NUREG 1301, and Palisades' FSAR lists Ba-140 and La-140 as a single nuclide i.e. "BaLa140" or "Ba-La-140" and the corresponding LLD as 15 pCi/L. The two nuclei were listed together because historically analytical differentiation between the two nuclei was very difficult. The instruments used today can differentiate between the two nuclei, and therefore the Branch Technical Position of Regulatory Guide 4.8 stated that an LLD of 60 pCi/L for Ba-140 and 15 pCi/L for La-140 is acceptable.

1-46

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 FIGURE 1.0-1 REMP SAMPLING LOCATIONS AT SEVEN MILES NN~~ '"'-

I NW

/

I I

WNW i

W '

t ~

.~ i~ . "

\.

wsw \

_do. ...

ESE 5 I'-lILE r I

SW ** w. .... !

1-47

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 FIGURE 1.0-2 REMP PROGRAM LOCATIONS AT FOUR MILES

./

I t

1-48

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 1-10 REMP PROGRAM LOCATIONS, TLD Location Coordinates Distance (miles) Degrees Sector Stack N 421922.5 W 8618 50.8 1 N 421920.5 0.213 100.36 E W 861836.1 Inner Ring 13 N 421947.2 0.530 26.56 NNE W 861834.1 8 N 421946.8 0.602 39.19 NE W 861824.0 14 N 42 1941.1 0.551 49.64 NE W 861821.2 15 N 421941.7 0.834 63.76 ENE W 8617 58.1 16 N 421928.0 0.804 82.45 E W 861754.6 17 N 421910.5 0.572 113.74 ESE W 861813.9 18 N 42194.2 0.469 138.49 SE W 861828.9 19 N 421905 0.443 159.19 SSE W 861840 20 N 42191.1 0.412 176.05 S W 861848.8 21 N 42193.4 0.382 196.40 SSW W 86 1858.4 Outer Ring - Displayed on 7 mile map 7 N 422240.8 4.115 22.35 NNE W 8617 0.4 6 N 42 22 30.6 5.314 47.18 NE W 861415.9 23 N 42 2044.6 3.189 60.37 ENE W 86 1535.4 24 N 421959.5 6.021 83.19 E W 861149.4 5 N 421827.6 3.475 107.63 ESE W 8614 57.5 1-49

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 I

4 N 421710.8 3.668 133.54 SE W 861543.5 I

3 N 421437.9 5.684 163.92 SSE W 861600 I

2 N 421433.4 5.560 183.75 S W 86 19 16.4 I

9 N 42181.73 1.670 201.86 SSW W 861934.6 TABLE 1-10 REMP PROGRAM LOCATIONS, TLD (CONTINUED)

I Location Coordinates Distance (miles) Degrees Sector I Control TLDs I I

10 N 42 5316.7 50.746 39.49 NE W85 40 35.9 11 N 421524.5 W 853249.3 39.472 96.39 E I

12 N415654.3 W86 6 24.5 27.971 157.61 SSE I

TLD 10 is located within the Consumers Energy Grand Rapids service facility attached to a pole located adjacent to the south fence.

TLD 11 is located within Consumers Energy Kalamazoo service facility attached to a pole in the far NE corner of the facility, past the employee parking lot.

TLD 12 is located approximately 30 yards from the road, NE and next to a private residence located at 58399 Wilbur Road, Dowagiac, MI.

TABLE 1-11 REMP PROGRAM LOCATIONS, AIR SAMPLE STATIONS Location Coordinates Distance (miles) Degrees Sector A8 (State Park) N 421946.8 0.595 38.34 NE W 861824.8 A9 (Township Park) N 42184.6 1.525 191.38 SSW W 861912.0 A4 (Covert) N421712.1 3.882 130.12 SE W 861521.7 A5 (Rood) N 421830.5 3.590 106.12 ESE W 8614 47.8 A10 (Grand Rapids) N 42 5316.7 50.765 39.52 NE W 854033.8 A 19 (Walking Trail) N 42193.65 0.423 148.70 SSE W 861835.30 Air Sample Station 10 is located within Consumers Energy Grand Rapids service facility, south side, next to a small service building and due east of TLD 10.

1-50

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Control fish and water samples are normally obtained from the Consumers Energy Pump Storage Facility located in Ludington, MI or another location not influenced by Palisades plant discharges.

TABLE 1*12 REMP PROGRAM LOCATIONS, PALISADES PARK WELLS Location Coordinates Distance (miles) Degrees Sector Community Well N 421847.5 0.729 203.63 SSW W 861911.4 Commercial Well N 4218 48.5 .652 175.06 S W 861846.8 The Community Well services the community residents with well water to their homes; the Commercial Well services the community gardens and drinking fountains on the east side of the property.

1.5 SIRW OR TEMPORARY LIQUID STORAGE TANK CONTROL 1.5.1.1 The concentration of radioactive material (excluding tritium and noble gases) contained in the SIRW tank or any unprotected outside temporary tank* shall be limited such that the mixture radionuclides do not exceed 1,000 times the effluent concentration (EC) as listed in 10 CFR Part 20, Appendix B, Table 2, Column 2.

Concentration (1) Concentration (2) Concentration (i)

ECL (1) + ECL (2) ... + ECL (i) :5 1000 (1.0*8)

Action With the quantity of radioactive material in any of the above listed tanks exceeding the above concentration, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit, and describe the events leading to this condition in the next Radiological Effluent Release Report.

Surveillance Requirement The concentration of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

or A calculational methodology performed prior to the material being transferred may be used to show compliance with the requirement of this section if a representative sample cannot be obtained at least once per seven days. A representative sample 1-51

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 of the radioactive material to be added to the SIRW or Temporary Liquid Storage Tank shall be analyzed and a calculation performed to show compliance with the 1000 EC limit.

Bases This requirement will provide reasonable assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an Unrestricted Area. (The dilution between Palisades and the South Haven drinking water supply has been established as 1000.)

Tanks included in this specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.

NOTE: The limit for the SIRW Tank may be exceeded for operational flexibility if the conditions of this section are met.

1-52

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 1.6 SURVEILLANCE REQUIREMENT TIME INTERVALS CONTROL 1.6.1.1 Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.

Action Failure to perform a Surveillance Requirement within the allowed surveillance interval shall constitute noncompliance with the operability requirements. The time limits of the action requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The action requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveillance when the allowed outage time limits of the action requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Surveillance Requirements do not have to be performed on inoperable equipment.

Surveillance Requirements The applicable surveillance interval frequencies are specified in Table 1-2 and Table 1-5. The applicable sampling and/or analysis frequencies are specified in Table 1-2, Table 1-3, Table 1-5, Table 1-6 and Table 1-7. Extendable surveillance requirements are limited to Channel Checks, Source Checks, Channel Calibrations, Channel Functional Checks, sampling frequencies and/or analysis frequencies.

Bases The maximum allowable extension for a surveillance interval is consistent with the surveillance requirements specified in the Technical Specifications, Section 4.0.

Until relocated in the ODCM, all of the effluent surveillances were subject to these same requirements.

The 25% extension may not be used to extend time intervals specified in ACTION requirements.

1-53

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 1.7 SEALED SOURCE CONTAMINATION CONTROL 1.7.1.1 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of greater than or equal to 0.005 microcuries of removable contamination.

Action With a sealed source having removable contamination in excess of 0.005 microcuries, immediately withdraw the sealed source from use and either:

a. Decontaminate and repair the sealed source, or

b. Dispose of the sealed source in accordance with applicable regulations.

A report shall be prepared and submitted to the Commission on an annual basis if sealed source leakage tests reveal the presence of greater than or equal to 0.005 microcuries of removable contamination.

Surveillance Requirements

a. Each category of sealed sources as described in the requirement with a half-life greater than 30 days (excluding Hydrogen-3), and in any other form than gas, shall be tested for leakage and/or contamination at intervals not to exceed 6 months.

b. The test shall be performed by the licensee or by other persons specifically authorized by the Commission or an Agreement State. The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.

c. The test sample shall be taken from the sealed source or, in the case of permanently mounted sources, from the surfaces of the mounting device on which contamination would be expected to accumulate.

d. The periodic leak test does not apply to sealed sources that are stored and not being used. These sources shall be tested prior to use or transfer to another licensee, unless tested within the previous 6 months. Sealed sources which are continuously enclosed within a shielded mechanism (ie, sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.

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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29

e. Sealed sources transferred without a certificate indicating the last test date shall be tested prior to being placed in use.

Bases The requirement, actions, and surveillance requirements are the same as contained in the Technical Specifications 6.21 prior to relocation to the aDeM and will provide assurance that sealed sources are tested to demonstrate that source integrity is being maintained 1-55

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 2.0 REPORTING REQUIREMENTS 2.1 RADIOLOGICAL EFFLUENT RELEASE REPORT The Radioactive Effluent Release Report (RERR) shall be submitted in accordance with 10 CFR 50.36a prior to May 1 of each year. The report shall include a summary of the quantities of liquid and gaseous effluents and solid waste released as outlined in Regulatory Guide 1.21, Rev 1, Measuring, Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Material in Liquid and Gaseous Effluents from Light Water Cooled Nuclear Power Plants, with data summarized on a quarterly basis following the format of Appendix B, thereof.

The following information shall also be included in the RERR:

Assessment of the radiation doses due to the liquid and gaseous effluents released during the previous year

Inoperable effluent radiation monitors that exceeded 30 continuous days; explain causes of inoperability and actions taken to prevent reoccurrence

Evaluation to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation

Unplanned releases of radioactive materials in gaseous or liquid effluents to unrestricted areas on a quarterly basis

Any changes to this procedure made during the reporting period

Groundwater monitoring results taken in support of the Groundwater Protection Initiative, but are not part of the REMP Solid radioactive waste data shall be reported as follows:

Type of waste (example: spent resin, dry waste, irradiated components)

Volume in cubic meters, include estimated error

Curie quantity per type of waste, include estimated error

Principal radionuclides in each category

Disposition of waste shipments and irradiated fuel shipments (identify number of shipments, mode of transport and destination) 2-1

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 2.2 RADIOLOGICAL ENVIRONMENTAL OPERATING REPORTING REQUIREMENTS 2.2.1 Annual Radiological Environmental Monitoring Report The Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted prior to May 15 of each year.

The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in:

(1) the ODCM, and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

The Annual Radiological Environmental Operating Reports shall include summaries, interpretation and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the Plant operation on the environment. The reports shall also include the results of land use census pursuant to Control 1.4.1.1 Surveillance Requirement c.

The Annual Radiological Environmental Operating Reports shall include summarized and tabulated results in the format of Table 2-1 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following; a summary description of the radiological environmental monitoring program, including sampling methods for each sample type, a map of all sampling locations keyed to a table giving distances and directions from the reactor and the results of land use census required by Control 1.4.1.1 Surveillance Requirement c and results of the Interlaboratory Comparison Program required by Control 1.4.1.1 Surveillance Requirement e.

2.2.2 Non-routine Reports A report shall be submitted to the NRC in the event that: 1) the Radiological Environmental Monitoring Programs are not substantially conducted as described in 1.4.1 or 2) an unusual or important event occurs from Plant operation that causes a significant environmental impact or affects a potential environmental impact.

Reports shall be'submitted within 30 days.

2-2

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 2-1 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

Name of Facility Docket No Location of Facility Reporting Period (County. State TypefTotal Lower Limit All Indicator Control Medium or Pathway Number of Number of of Locations Name Mean (~b Locations Sampled REPORTABLE Analyses Detection" Mean (~b Distance & Direction Range Mean(ft (Unit of Measure) OCCURRENCES Performed (LLD) Range Range Air Particulates Gross B 416 0.003 0.08 Middletown 0.10 (5/52) 0.08 (8/104)- 1 (pCi/m') (200/312) 5 miles 340* (0.08-2.0) (0.05-1.40) v-Spec 32 (0 .05-2.0)

Cs-137 0.003 0.05 (4/24) Smithville 0.08 (2/4) < LLD 4 (0 .03-0.13) 2.5 miles 160* (0.03-0.13) 8a-140 0.003 0 .03 (2/24) Podunk 0.05 (2/4) 0.02 (1/8) 1 (0 .01-0.08) 4 miles 270* (0.01-0 .08)

Sr-89 40 0.002 < LLD -- -- < LLD 0 Sr-90 40 0.0003 < LLD -- -- < LLD 0 Fish v-Spec 8 pCi/kg (dry weight)

Cs-137 80 < LLD -- < LLD 90 (114) 0 Cs-134 80 <LLD -- <LLD < LLD 0 Co-60 80 120 (3/4) River Mile 35 See < LLD 0

. (90-200)

Nominal Lower Limit of Detection (LLD) as defined In table notation c of Table 1 9 .

Podunk River Column 4 Mean and range based upon detectable measurements only. Fraction of detectable measurements at specific locations is indicated in parentheses (I).

NOTE: The example data are provided for illustrative purposes only.

2-3

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 3.0 MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID AND WASTE GAS SYSTEMS 3.1 LICENSEE MODIFICATIONS Licensee initiated major modifications to the radioactive liquid and gaseous waste systems.

1. Shall be reported to the NRC pursuant to 10 CFR Part 50.59. The discussion of each modification shall contain:

a. A summary of the evaluation that led to the determination that the modification could be made in accordance with 10 CFR Part 50.59.

b. A description of the equipment, components and processes involved, and the interfaces with other Plant systems.

c. Documentation of the fact that the modification was reviewed and found acceptable by the OSRC.

2. Shall become effective upon review and acceptance by the General Manager Plant Operations.

3.2 DEFINITION-OF MAJOR RADWASTE SYSTEM MODIFICATION 3.2.1 Purpose The purpose of this definition is to assure that this requirement will be satisfied under clearly identifiable circumstances, and with the objective that current radwaste system capabilities are not jeopardized.

3-1

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 3.2.2 Definition A major radwaste system modification is a modification which would remove (either by bypassing for greater than 7 days or physical removal) or replace with less efficient equipment, any components of the radwaste system:

a. Letdown filters or demineralizers.

b. Vacuum degassifier (not applicable when the reactor is in cold shutdown and depressurized).

c. Miscellaneous or clean waste evaporators.

d. The present waste gas compressor/decay tank system.

e. Fuel Pool filters/demineralizers.

f. Radwaste polishing demineralizers.

g. Radwaste Solidification system.

Improvements or additions to improve efficiency will not be considered major modifications unless a complete substitution of equipment or systems is made with equipment of unrelated design. Examples would be: 1) replacement of mechanical degassifier with steam, jet degassifier, 2) replacement of waste gas system with cryogenic system, 3) replacement of asphalt solidification with cement system, and 4) change from deep bead resins to Powdex, etc.

3.3 ONSITE GROUND WATER MONITORING Palisades installed 5 ground water monitoring wells in 2007 and added an additional 9 wells in 2008. These wells were installed in response to NEI 07-07, Industry Ground Water Protection Initiative - Final Guidance Document. These wells are strategically placed within the Owner Controlled Area, both inside and outside the Protected Area to allow detection of radioactive contamination of ground water due to leaks or spills from plant systems. Palisades ground water monitoring wells are maintained by the ground water monitoring program.

3-2

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 4.0 GASEOUS EFFLUENTS 4.1 GASEOUS EFFLUENT CALCULATIONS 4.1.1 Dose Rate Limits Control 1.1.2.1 requires that the dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following: .

1. For noble gases: Less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin.

2. For lodine-131, lodine-133 and for all radioactive materials in particulate form and tritium with half-lives greater than 8 days: Less than or equal to 1500 mrem/yr to any organ Control 1.1.1.1 requires gaseous effluent monitors to have alarm/trip setpoints to ensure that offsite concentrations, when averaged over 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , will not be greater than control 1.1.2.1. This section of the ODCM describes the methodology that will be used to determine these setpoints.

The methodology for determining alarm/trip setpoints is divided into two major parts.

The first consists of calculating an allowable concentration for the nuclide mixture to be released. The second consists of determining monitor response to this mixture in order to establish the physical settings on the monitors.

4.1.2 Dose Rate Calculations Except where noted, Table 4-2 contains the numerical values for parameters used in the equations of this section.

4-1

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 4.1.2.1 Organ Dose Rate Due To Noble Gases The dose rate to the total body dose due to noble gases is given by:

Total Body Dose Rate(mrem/year) = X/Q M Li KiQl (4.0-1 )

The skin dose rate is given by:

Skin Dose Rate(mrem/year) = X/Q M L[L +

i i 1.1Mi ]Ql (4.0-2)

WHERE: X/Q M = The maximum or highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA in sec/m 3 . See Table 4-1.

Ql = The release rate of radionuclide "i," in !-ICi/sec.

Ki = The total body dose factor due to gamma emissions for noble gas radionuclide "i", from Column 4, Table B-1 of Regulatory Guide 1.109, in mrem/year per !-ICi/m3. (Note the values in Regulatory Guide 1.109 must be increased by a factor of 106 to match the units used in the NUREG 0133 equations.)

Li = The skin dose factor due to beta emissions for noble gas radionuclide "i," from Column 2, Table B-1 of Regulatory Guide 1.109, in mrem/year per !-ICi/m3. (Note the values in Regulatory Guide 1.109 must be increased by a factor of 106 to match the units used in this ODCM.)

1.1 = Conversion constant of 1.1 mrem/mrad.

Mi = The air dose factor due to gamma emissions for noble gas radionuclide "i," from Column 3, Table B-1 of Regulatory Guide 1.109, in mrad/year per !-ICi/m3. The unit conversion constant of 1.1 mrem/mrad is used to convert air dose to skin dose. (Note the values in Regulatory Guide 1.109 must be increased by a factor of 106 to match the units used in this ODCM.)

4-2

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 4.1.2.2 Organ Dose Rate Due To Radioiodines, Tritium , C-14 and Particulates Dose rate for lodine-131, lodine-133 and for all radioactive materials in particulate form and tritium (R-T -P) with half-lives greater than 8 days is given by:

R - T - P Dose Rate(mrem/year) = x/Q M It PtQl (4.0-3)

WHERE: X/Q M = The maximum or highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA in sec/m 3 . See Table 4-1.

= The dose conversion factor for radionuclide "i," in mrem/year per IJCi/m3 for the child-inhalation pathway (same as the Rai(IN)j of Table 7-7).

= The release rate of radionuclide "i," in IJCi/sec.

The dose conversion factor Pi is for the child inhalation pathway and is given by:

(4.0-4)

WHERE: K' = Unit conversion constant, 106 pCi/IJCi.

= The breathing rate of the child age group, in m3/year. The default value of 3700 m3 year is taken from Table E-5 of Regulatory Guide 1.109.

DFA[Cltj = The inhalation dose factor for the child age group for radionuclide "i," and organ "j" in mrem/pCi from Table E-9 of Regulatory Guide 1 .109.

The methodology of Equation (4.0-4) is identical to that of (4.0-11). As a result the Pi dose factor values for the child-inhalation exposure pathway are taken from Table 7-7.

4-3

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 4.2 ALARM/TRIP SETPOINT METHODOLOGY NOTE: If a batch release is made while a continuous release or another batch release is in progress, the sum of all values of Rk must be less than 10.0.The total EC-fraction (Rk) for each release point will be calculated by the relationship defined by Note 4 of Appendix B, 10 CFR 20:

Rk = X/Q x F x Li-! e*

Eei

5 10.0 (4.0-5)

WHERE:

X/Q = Most conservative sector site boundary dispersion (sec/m3)

(listed in site procedure CH 6.41, "Land Use Census")

Cj = Actual or measured concentration, at ambient temperature and pressure of nuclide i (,...Ci/cc)

ECi = The EC of nuclide i from 10 CFR 20, Appendix B, Table 2.

R(k) = The total EC-fraction for release point k F = Release flow rate (83,000 cfm =39.2 m3/sec) for stack monitor considerations; variable for other monitors 4.2.1 Monitor Response Normal radioactivity releases consist mainly of well-decayed fission gases.

Therefore, monitor response calibrations are performed to fission gas typical of normal releases (mainly Xe-133). Response of monitors used to define fission product release rates under accident conditions may vary from that of Xe-133, however. Monitor response for the two categories of monitor is determined as follows:

a. Normal Release (aged fission gases)

Total gas concentration (j.JCi/cc) at the monitor is calculated. The detector response to isotopic activities (cpm/j.JCi/cc) is applied to determine cpm expected. The setting for monitor alarms is established at some factor (b) greater than 1 but less than 1/Rk (Equation 1.1) times the measured concentration (c):

s = bxc (4.0-6) 4-4

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29

b. Accident Releases Monitors are preset to alarm at or before precalculated offsite dose rates would be achieved under hypothetical accident conditions. These setpoints are established in accordance with Emergency Plan requirements for defining Emergency Action Levels and associated actions. Emergency Implementing Procedures contain monitor-specific curves or calibration constants for conversion between cpm and jJCi/cc (or R/hr and jJCi/cc), depending on monitor type, for fission product mixtures as a function of mixture decay time.

When these monitors are utilized for other than accident conditions, either an appropriately*decayed "accident" conversion curve may be used, or a decayed fission gas calibration factor may be applied. In these cases, setpoints are established as shown above.

Setpoints of accident monitors (if set to monitor normal releases) are reset to the accident alarm settings at the end of normal release. Setpoints of other release monitors are maintained at the level used at the latest release (well below the level which would allow 10 times EC to be exceeded at the site boundary), or are reset to approximately three times background in order to detect leakage or inadvertent releases of low level gases.

4.3 APPENDIX I DOSE CALCULATIONS ODCM Controls 1.1.3 and 1.1.4 require doses to be calculated for (1) noble gases and (2) iodines, tritium and particulates. The doses as defined in this section are based on 10 CFR Part 50 Appendix I limits of mrem per quarter and millirem per year. All dose pathways of major importance in the Palisades environs are considered. An alternate to the dose calculation methodology presented in this section, the NRC computer code LADTAP II and GASPAR II as implemented by NRC Dose may be used.

4.3.1 Unrestricted Area Noble Gas Air Dose ODCM Control 1.1.3.1 restricts the noble gas air dose from each unit to the following:

a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation.

b. During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

4-5

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 4.3.1 .1 The noble gas gamma air dose in the unrestricted is given by:

Gamma Dose(mrad) = 3.17 X 10-8 x/Q M Ii MiQl (4.O-7) 4.3.1.2 The noble gas beta air dose in the UNRESTRICTED AREA due to noble gases is given by:

Beta Dose(mrad) = 3.17 X 10-8 x/Q M Ii NiQl WHERE: 3.17 x 10-8 = Conversion factor - years/sec.

x/Q M = The maximum or highest calculated annual average relative concentration for any area at or beyond the UNRESTRICTED AREA in sec/m 3 . See Table 4-1.

Ql = The total release of noble gas radionuclide "i," in l-lCi.

Mi = The air dose factor due to gamma emissions noble gas radionuclide "i," from Column 3, Table 8-1 of Regulatory Guide 1.109, in mrad/year per I-/Ci/m3 . (Note the values in Regulatory Guide 1.109 must be increased by a factor of 106 to match the units used in this ODCM.)

Ni = The air dose factor due to beta emissions for noble gas radionuclide "i," from Column 1, Table 8-1 of Regulatory Guide 1.109, in mrad/year per I-/Ci/m3 . (Note the values in Regulatory Guide 1.109 must be increased by a factor of 106 to match the units used in this ODCM.)

4-6

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 4 .3.2 Radioiodine. Tritium and Particulate Organ Dose to a Member of the Public The organ dose to MEMBER OF THE PUBLIC is given by:

CRDoseapj = 3.17 x 10- 8 W I i RaiP/11 (4.0-9)

WHERE: CRDoseapj = Is the CRITICAL RECEPTOR Dose for age group "a,"

exposure pathway "p" and organ "j" (mrem).

3.17 X 10- 8 = Conversion factor in years/sec.

W = Atmospheric dispersion or deposition term from Table 4-1 and is used as follows:

x/Q CR = Atmospheric dispersion value for immersion, inhalation, all tritium pathways and all C-14 pathways at the location of interest (typically the CRITICAL RECEPTOR) from Table 4-1 in sec/m 3 , or D / QCR =Atmospheric deposition value for ground plane and ingestion pathways at the location of interest from Table 4-1 in m-2 .

Raipj[W] = The site specific pathway dose factor for age group "a,"

radionuclide "i," pathway "p," and organ "j". These values are compiled in Table 7-5 through Table 7-19.

The [W] notation specifies the appropriate dispersion (x/Q) or deposition (D /Q) parameter to be used with the pathway dose factor.

The units of Raipj[x/Q] are m2 x mrem/year per \.lCi/sec for the ground plane and ingestion pathways with the exception of tritium and carbon-14.

The units of Raipj[x/Q] are mrem/year per \.lCi/m 3 for immersion, inhalation, and all tritium and carbon-14 pathways.

QI = The total release activity of radionuclide "i" in \.lCi.

4-7

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 4.3.2.1 Ground Plane Pathway Dose Factor Ground Plane - Radioiodines and Particulates 1 - e- Aitb ]

Rai(GP)j[D /QJ = K'K"(SF)DFGi [ Ai (4.0*10)

WHERE: Rai(GP)j [n / QJ = Is the dose factor for age group "a," nuclide "i," pathway "GP" (ground plane) and organ "j" in m2-mrem/yr per JJCi/sec. See Table 7-5.

K' = Unit conversion factor: 106 pCi/jJCi.

K" = Unit conversion factor: 8760 hr/yr.

SF = Dimensionless factor to account for residence time and structure shielding from Table E-15 of Regulatory Guide 1.109.

DFG i = Ground plane dose conversion factor for nuclide "i" from Table E-5 of Regulatory Guide 1.109 in mrem/hr per pCi/m 2 .

Ground plane dose factors for radionuclides listed in Table 7-5 and not found in Regulatory Guide 1.109 are taken from NUREG/CR-4013.

With the exception of skin, all other organs are assumed to receive the same dose as the total body. All age groups are assumed to receive the same ground plane exposure dose.

Ai = Decay constant for radionuclide "i" in sec-1 .

tb = The exposure time based on % of the plant operating lifetime in seconds.

4-8

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 4.3.2.2 Inhalation Pathway Dose Factor Inhalation - Radioiodines and Particulates Rai(IN)j[X/Q] = K'BRaDFAaij (4.0-11)

WHERE: Rai(IN)j[X/Q] = Dose commitment factor for age group "a," nuclide "i,"

pathway "IN" (inhalation) and organ "j" in mrem/year per

\JCi/m 3 . See Table 7-6 through Table 7-9.

K' = Unit conversion factor: 106 pCi/\JCi.

= Inhalation rate for age group, "a" in m3/yr.

DFAaij = Inhalation dose conversion factor for age group "a,"

nuclide "i.," and organ "j" in mrem/pCi. From Tables E-7 through E-10 of Regulatory Guide 1.109.

Inhalation dose factors for radionuclides listed in Table 7-6 through Table 7-9 and not found in Regulatory Guide 1.109 are taken from NUREG/CR-4013.

4-9

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 4.3.2.3 Vegetation Ingestion Pathway Dose Factors Vegetation Ingestion - Radioiodines and Particulates Rai(VG)j [D/Q] -- K' YV(Ai(r)

+ Aw) DFL aij X

[ULfi -A *tL a Le I

+ USaJGe F -A.tH]

I (4.0-12)

WHERE: Rai(vG)j[D/Q] = Dose commitment factor for age group "a," nuclide "i,"

pathway "VG" (vegetation ingestion) and organ "j" in m2 x mrem/year per ~Ci/sec. See Table 7-10 through Table 7-12.

K' = Unit conversion factor: 106 pCi/~Ci.

(r) = Dimensionless retention fraction for direct deposition onto leafy vegetation.

= 0.2 for particulates

= 1.0 for radioiodines YV = Agricultural productivity for garden vegetation in kg/m 2 .

= Decay constant for radionuclide "i" in sec- 1*

= Decay constant for weathering effects in sec-1 .

DFLaij = Ingestion dose conversion factor for age group "a,"

nuclide "i," and organ "j" in mrem/pCi. From Tables E-11 through E-14 of Regulatory Guide 1.109.

Ingestion dose factors for radionuclides listed in aDCM Table 7-10 through Table 7-12 and not found in Regulatory Guide 1.109 are taken from NUREG/CR-4013.

UaL = Consumption rate of fresh leafy vegetation for age group "a" in kg/yr.

fL = Fraction of annual intake of fresh leafy vegetation grown locally.

tL = Transport time from harvest of leafy vegetation to receptor in sec.

USa = Consumption rate of non-leafy vegetation for age group "a" in kg/yr.

fG = Fraction of annual intake of non-leafy (stored) vegetation grown locally.

4-10

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 tH = Transport time from harvest of non-leafy (stored) vegetation to receptor in sec.

Vegetation Ingestion - Tritium Ra(H-3)(VG)j[X/Q] = K' K"'(U~/L + U~/G)DFLa(H_3)j[0.75(0.5/H)]

(4.0-13)

WHERE: Ra(H-3)(VG)j[X/Q] = Dose commitment factor for age group "a," nuclide "H-3," pathway "VG" (vegetation ingestion) and organ "j" in mrem/year per

\JCi/m 3 . See Table 7-10 through Table 7-12.

K' = Unit conversion factor: 106 pCi/\JCi.

K'" = Unit conversion factor: 103 gm/kg.

U~ = Consumption rate of fresh leafy vegetation for age group "a" in kg/yr.

fL = Fraction of annual intake of fresh leafy vegetation grown locally.

U~ = Consumption rate of non-leafy vegetation for age group "a" in kg/yr.

IG = Fraction of annual intake of non-leafy vegetation grown locally.

DFL a(H-3)j = Ingestion dose conversion factor for age group "a,"

nuclide "H-3," and organ "j" in mrem/pCi. From Tables E-11 through E-14 of Regulatory Guide 1.109.

0.75 = Fraction of total vegetation that is water.

0.5 = Ratio of specific activity of vegetation water to atmospheric water.

H = Absolute atmospheric humidity in gm/m3 .

4-11

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Vegetation Ingestion - Carbon-14 Ra (C-14)(VG)j[X/Q] = K' Kill IC02 p(U~GLIL + ugGsIG)DFL a (C-14)j (G1. )

AIr (4.0-14)

WHERE: Ra (C-14)(VG)Ax/Q] = Dose commitment factor for age group "a," nuclide "C-14," pathway "VG" (vegetation ingestion) and organ "j" in mrem/year per

\JCi/m 3 . See Table 7-10 through Table 7-12.

K' = Unit conversion factor: 106 pCi/\JCi.

Kill = Unit conversion factor: 103 gm/kg.

IC02 = Fraction of carbon released as CO 2 .

p = Ratio of total release time to the annual time during which photosynthesis takes place.

UaL = Consumption rate of fresh leafy vegetation for age group "a" in kg/yr.

GL = Fraction of leafy vegetation mass that is natural carbon.

IL = Fraction of annual intake of fresh leafy vegetation grown locally.

USa = Consumption rate of non-leafy vegetation for age group "a" in kg/yr.

Gs = Fraction of non-leafy vegetation mass that is natural carbon.

IG = Fraction of annual intake of non-leafy vegetation grown locally.

DFL a (C-14)j = Ingestion dose conversion factor for age group "a,"

nuclide "C-14," and organ "j" in mrem/pCi. From Tables E-11 through E-14 of Regulatory Guide 1.109.

= Concentration of natural carbon in the atmosphere in gm-carbon/m 3-air.

4-12

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 4.3.2.4 Milk Ingestion Pathway Dose Factors Milk Ingestion - Radioiodines and Particulates R. .[D/Q]=K' QF U F a(Mf) (Mf)

(r) [fj f' DFL .. ...!:!.!..+

(1 - fj f' )e-A;tM ]

PlS -A;tp a,(MI)) O'i + AW) a,) Yp YS e (4.0-15)

WHERE: Rai(MI)j[D/Q] = Dose commitment factor for age group "a," nuclide "i," pathway "MI" (milk ingestion) and organ "j" in m 2

mrem/year per IJCi/sec.

See Table 7-13 through Table 7-16.

K' = Unit conversion factor: 106 pCi/IJCi.

= Feed consumption rate of milk producing animal in kg/da.

Ua(MI) = Consumption rate of milk for age group "a" in liters/yr.

= Stable element transfer coefficient from feed to milk in da/liter.

(r) = Dimensionless retention fraction for direct deposition onto leafy vegetation .

= 0.2 for particulates

= 1.0 for radioiodines

= Decay constant for radionuclide "i" in sec-1

= Decay constant for weathering effects in sec-1.

DFLaij = Ingestion dose conversion factor for age group "a," nuclide "i," and organ "j" in mrem/pCi. From Tables E-11 through E-14 of Regulatory Guide 1.109.

Ingestion dose factors for radionuclides listed in Table 7-13 through Table 7-16 and not found in Regulatory Guide 1.109 are taken from NUREG/CR-4013.

fp = Fraction of year that milk animal is on pasture.

fs = Fraction of feed that is pasture grass while milk animal is on pasture.

Yp = Agricultural productivity for pasture feed grass in kg/m2 .

Ys = Agricultural productivity for stored feed in kg/m2 .

tM = Transport time from consumption of pasture to milk to receptor in sec.

tH = Transport time from harvest of stored feed to milk or meat animal consumption in sec.

4-13

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Milk Ingestion - Tritium Ra(H-3)(MJ)j[X/Q] = K' Kill FMIQFUa(MI)DFLa(H_3)j[0.75(0.5/H)]

(4.0-16)

WHERE: Ra(H-3)(MI)j[X/Q] = Dose commitment factor for age group "a," nuclide "H-3," pathway "MI" (milk ingestion) and organ "j" in mrem/year per j.JCi/m 3 . See Table 7-13 through Table 7-16.

K' = Unit conversion factor: 106 pCi/j.JCi.

Kill = Unit conversion factor: 103 gm/kg.

= Stable element transfer coefficient from feed to milk in dalliter.

= Feed consumption rate of milk producing animal in kg/da .

Ua(MI) = Consumption rate of milk for age group "a" in liter/yr.

DFL a(H-3)j = Ingestion dose conversion factor for age group "a,"

nuclide "H-3," and organ "j," in mrem/pCi. From Tables E-11 through E-14 of Regulatory Guide 1.109.

0.75 = Fraction of total vegetation that is water.

0.5 = Ratio of specific activity of vegetation water to atmospheric water.

H = Absolute atmospheric humidity in gm/m3 .

4-14

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Milk Ingestion - Carbon-14 (4.0-17)

WHERE: Ra (C-14)(MI)j[X/Q]= Dose commitment factor for age group "a," nuclide "C-14," pathway "MI" (milk ingestion) and organ "j" in mrem/year per \JCi/m 3 . See Table 7-13 through Table 7-16.

K' = Unit conversion factor: 106 pCi/\JCi.

K'" = Unit conversion factor: 103 gm/kg.

tC02 = Fraction of carbon released as CO2 .

P = Ratio of total release time to the annual time during which photosynthesis takes place.

FM! = Stable element transfer coefficient from feed to milk in dalliter.

QF = Feed consumption rate of milk producing animal in kg/da.

Ua(M!) = Consumption rate of milk for age group "a" in liters/yr.

DFLa (C-14)j = Ingestion dose conversion factor for age group "a,"

nuclide "C-14," and organ "j" in mrem/pCi. From Tables E-11 through E-14 of Regulatory Guide 1.109.

G MiLk = Fraction of milk that is carbon.

GAiT = Concentration3 of natural carbon in the atmosphere in gm-carbon/m -air.

4-15

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 4.3.2.5 Meat Ingestion Pathway Dose Factor Meat Ingestion - Radioiodines and Particulates R. .[D/Q] = K' QFUa(ME) FME (r) DFL .. [I' I' + (1 - IPIS

!.!:!.!. I' I' )e-AitS] -AitP al(ME>>) (Ai + Aw) al) YP Ys e (4.0-18)

WHERE: Rai(ME)j[D/Q] = Dose commitment factor for age group "a," nuclide2 "i,"

pathway "ME" (meat ingestion) and organ "j" in m x mrem/year per !-ICi/sec. See Table 7-17 through Table 7-19.

K' = Unit conversion factor in 106 pCi/!-ICi.

QF = Feed consumption rate of meat producing animal in kg/da.

Ua(ME) = Consumption rate of meat for age group "a" in kg/yr.

FME = Stable element transfer coefficient for meat in da/kg.

(r) = Dimensionless retention fraction for direct deposition onto leafy vegetation.

= 0.2 for particulates

= 1.0 for radioiodines Ai = Decay constant for radionuclide "i" in sec- 1 .

Aw = Decay constant for weathering effects in sec- 1 .

DFLaij = Ingestion dose conversion factor for age group "a,"

nuclide "i," and organ "j" mrem/pCi. From Tables E-11 through E-14 of Regulatory Guide 1.109.

Ingestion dose factors for radionuclides listed in aDCM Table 7-17 through Table 7-19 and not found in Regulatory Guide 1.109 are taken from NUREG/CR-4013.

fp = Fraction of year that meat animal is on pasture.

fs = Fraction of feed that is pasture grass while meat animal is on pasture.

Yp = Agricultural productivity for pasture feed grass in kg/m 2 .

Ys = Agricultural productivity for stored feed in kg/m 2 .

tp = Transport time from consumption of pasture to meat to receptor in sec.

4-16

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 ts = Transport time from harvest of stored feed to meat animal consumption in sec.

Meat Ingestion - Tritium Ra(H-3)(ME)j[X/Q] = K' K"' FMEQFUa(ME)DFLa(H-3)j[O.75(O.5/H)]

(4.0-19)

WHERE: Ra(H-3)(ME)j[X/Q]= Dose commitment factor for age group "a," nuclide "H-3," pathway "ME" ~meat ingestion) and organ "j" in mrem/year per IJCi/m . See Table 7-17 through Table 7-19.

K' = Unit conversion factor: 106 pCi/IJCi.

K"' = Unit conversion factor: 103 gm/kg.

= Stable element transfer coefficient from feed to meat in da/kg.

= Feed consumption rate of meat producing animal in kg/da .

Ua(ME) = Consumption rate of meat for age group "a" in kg/yr.

DFL a(H-3)j = Ingestion dose conversion factor for age group "a,"

nuclide "H-3," and organ "j" in mrem/pCi. From Tables E-11 through E-14 of Regulatory Guide 1.109.

0.75 = Fraction of total vegetation that is water.

0.5 = Ratio of specific activity of vegetation water to atmospheric water.

H = Absolute atmospheric humidity in gm/m 3 .

4-17

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Meat Ingestion - Carbon-14 Ra (C-14)(ME)j[X/Q] = K' K"'Ic02 P FMEQFUa(ME)DFLa(C-14)j(GMeat/GAiT)

(4.0-20)

WHERE: Ra (C-14)(ME)Ax/Q] = Dose commitment factor for age group "a," nuclide "C-14," pathway "ME" (meat ingestion) and organ "j" in m2 . mrem/year per \-ICi/sec. See Table 7-17 through Table 7-19.

K' = Unit conversion factor: 106 pCi/\-ICi.

Kill = Unit conversion factor: 103 gm/kg.

Ic02 = Fraction of carbon released as C02 .

p = Ratio of total release time to the annual time during which photosynthesis takes place

= Stable element transfer coefficient from feed to meat in da/kg .

QF = Feed consumption rate of meat producing animal in kg/da.

Ua(ME) = Consumption rate of meat for age group "a" in liters/yr.

DFLa (C-14)j = Ingestion dose conversion factor for age group "a,"

nuclide "C-14," and organ "j" in mrem/pCi. From Tables E-11 through E-14 of Regulatory Guide 1.109.

G Meat = Fraction of meat that is carbon.

GAiT = Concentration of natural carbon in the atmosphere in gm-carbon/m 3 -air.

4-18

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 4-1 XlQ AND D/Q AT LOCATIONS OF INTEREST Atmospheric Dispersion Direction

Distance

Location Type XlQ (sec/m3)

From Site (miles)

Site Boundary1 SSE 0.48 2.30E-06 Residence 2 S 0.51 1.47E-06 Garden 1 SSE 0.70 1.29E-06 Beef Cattle2 ESE 2.04 2.09E-07 Goaf NE 2.45 1.88E-07 Atmospheric Deposition Direction Distance Location Type D/Q (11m2)

From Site (miles)

Site Boundary 1 SSE 0.48 1.97E-08 Residence 1 SSE 0.80 8.47E-09 Garden 1 SSE 0.70 1.06E-08 Beef Cattle2 ESE 2.04 1.29E-09 Goaf NE 2.45 9.33E-10 Calculated by XOQOOQ. The results are listed in Table 7-20.

1 Values from 2016 Land Use Census using Meteorological data from 1/1/2006 to 12131/2015.

2 Values from 2017 Land Use Census using Meteorological data from 1/1/2007 to 12131/2016.

4-19

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 4-2 PARAMETERS USED IN GASEOUS EFFLUENT DOSE CALCULATIONS Parameter Description Equation(s) Reference Atmospheric Dispersion and Deposition x/Q M = The maximum or highest calculated (4.0-1 ) Site Specific.

annual average relative (4.0-2) Values are listed in Table concentration for any area at or (4.0-3) 4-1.

beyond the UNRESTRICTED AREA (4.0-7) in units of sec/m 3 * (4.0-8)

W= Atmospheric dispersion or (4.0-9) Site Specific.

deposition term. See ODCM Values are listed in Table Section 1.1.4.1. 4-1.

x/Q CR = The dispersion value in units of (4.0-9) Site Specific.

sec/m 3 at the location of the (6.0-1 ) Values are listed in Table CRITICAL RECEPTOR. (6.0-2) 4-1.

D/Q CR = The deposition value in units of m-2 (4.0-9) Site Specific.

at the location of the CRITICAL Values are listed in Table RECEPTOR. 4-1.

Noble Gas Dose Factors Ki= The total body dose factor due to (4.0-1 ) From Column 4, Table 8-1 of gamma emissions for noble gas (6.0-1 ) Regulatory Guide 1.109, in radionuclide "i". mrem/year per IJCi/m3 .

Li= The skin dose factor due to beta (4.0-2) From Column 2, Table 8-1 of emissions for noble gas radionuclide (6.0-2) Regulatory Guide 1.109, in "i". mrem/year per IJCi/m3 .

Mi= The air dose factor due to gamma (4.0-2) From Column 3, Table 8-1 of emissions for noble gas radionuclide (4.0-7) Regulatory Guide 1.109, in "i". (6.0-2) mrad/year per IJCi/m3 .

Ni = The air dose factor due to beta (4.0-8) From Column 1, Table 8-1 of emissions for noble gas radionuclide Regulatory Guide 1.109, in "i". mrad/year per IJCi/m3 .

4-20

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Parameter Description I Equation(s) Reference Ground Plane, Inhalation and Ingestion Dose Factors DFG i = Ground dose factor in mrem/hr per (4.0-10) From Table E-6 of Regulatory

~Ci/m2. Guide 1.109.

DFAaij = Inhalation dose factor for age group, (4.0-11 ) From Tables E-7 through "a," radionuclide "i," and organ "j" in E-10 of Regulatory Guide mrem/pCi. 1.109.

DFA[cjij = The inhalation dose factor for the (4.0-4) From Table E-9 of Regulatory child age group for radionuclide "i," in Guide 1.109.

mrem/pCi.

DFLaij = Ingestion dose factor for age group, (4.0-10) From Tables E-11 through "a," radionuclide "i," and organ "j" in through E-14 of Regulatory Guide mrem/pCi. (4.0-20) 1.109.

Site Specific Dose Factors Pi = The child inhalation dose conversion From Table 7-7 factor for radionuclide "i," in units of (4.0-3) mrem/year per ~Ci/m3.

Raipj = Site specific dose factor for age group (4.0-9) From Table 7-6 through Table "a," radionuclide "i," pathway "p" and through 7-19.

organ "j". (4.0-20)

Usage Factors tb = The exposure time based on ~ of the (4.0-10) Site specific.

plant operating lifetime (60 years),

9.46x10 8 seconds.

BR[C) = The child inhalation rate: 3700 m3 per (4.0-4) Value from Table E-5 of year. Regulatory Guide 1.109.

BRa= Inhalation rate for age group, "a" in (4.0-11 ) From Table E-5 of Regulatory m3/yr. Guide 1.109.

UaL = Consumption rate of fresh leafy (4.0-12) Site Specific.

vegetation for age group "a" in kg/yr. (4.0-13) Default values are from Table (4.0-14) E-5 of Regulatory Guide 1.109.

USa = Consumption rate of non-leafy (4.0-12) Site Specific.

vegetation for age group "a" in kg/yr. (4.0-13) Default values are from Table (4.0-14) E-5 of Regulatory Guide 1.109.

4-21

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Parameter I Description I Equation(s) Reference Ua(Ml) = Consumption rate of milk for age (4.0-15) Values are from Table E-5 of group "a" in Ityr. (4.0-16) Regulatory Guide 1.109.

(4.0-17)

Ua(ME) = Consumption rate of meat for age (4.0-18) Values are from Table E-5 of group "a" in Ityr. (4.0-19) Regulatory Guide 1.109.

(4.0-20)

Agricultural Parameters F(MI) = Stable element transfer coefficient (4.0-15) Values are from Tables E-1 from feed to milk in datI. (4.0-16) and E-2 of Regulatory Guide (4.0-17) 1.109 as appropriate.

F(ME) = Stable element transfer coefficient (4.0-18) Values are from Tables E-1 from feed to meat in datkg. (4.0-19) and E-2 of Regulatory Guide (4.0-20) 1.109 as appropriate.

fe = Fraction of annual intake of non-leafy (4.0-12) Site Specific.

(stored) vegetation grown locally, 0.76 (4.0-13) Default value is from Section (default). (4.0-14) 5.3.1.5 of NUREG 0133.

fL = Fraction of annual intake of fresh (4.0-12) Site Specific.

leafy vegetation grown locally, 1.0 (4.0-13) Default value is from Section (default). (4.0-14 ) 5.3.1.5 of NUREG 0133.

fp = Fraction of year that milk or meat (4.0-15) Site Specific.

animal is on pasture, 1.0 (default). (4.0-18) Default value is from Section 5.3.1.3 of NUREG 0133.

fs = Fraction of feed that is pasture grass (4.0-15) Site Specific.

while milk or meat animal is on (4.0-18) Default value is from Section pasture, 1.0 (default). 5.3.1.3 of NUREG 0133.

(r) = Dimensionless retention fraction for (4.0-12) From Table E-15 of direct deposition onto leafy (4.0-15) Regulatory Guide 1.109.

vegetation. (4.0-18) 0.2 for particulates 1.0 for radioiodines tL = Transport time from harvest of leafy (4.0-12) Site Specific.

vegetation to receptor (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ), Default values are from Table B.64x104 sec (default). E-15 of Regulatory Guide 1.109.

tH = Transport time from harvest of non- (4.0-12) Site Specific leafy (stored) vegetation to receptor Default values are from Table (60 days) 5x106 sec (default). E-15 of Regulatory Guide 1.109.

4-22

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Parameter Description I Equation(s) Reference tM = Transport time from consumption of (4.0-15) Site Specific.

pasture to milk to receptor (2 days) Default values are from Table 1.73x105 sec (default). E-15 of Regulatory Guide 1.109.

tp = Transport time from consumption of (4.0-18) Site Specific.

pasture to meat to receptor (20 days) Default values are from Table 1.73x106 sec (default). E-15 of Regulatory Guide 1.109.

ts = Transport time from harvest of stored (4.0-15) Site Specific.

feed to milk or meat animal (4.0-18) Default values are from Table consumption (90 days) 7.78x106 sec E-15 of Regulatory Guide (default). 1.109.

QF = Milk or meat animal consumption rate, (4.0-15) Site Specific.

50 in kg/da (default). through Default values is from Table (4.0-20) E-3 of Regulatory Guide 1.109.

Agricultural Parameters Yv= Agricultural productivity for garden (4.0-12) Site Specific.

vegetation, 2.0 kg-vegetation/m 2 Default value from Table E-15 (default). of Regulatory Guide 1.109.

Yp= Agricultural vegetation productivity for (4.0-15) Site Specific.

pasture feed prass, 0.7 kg- (4.0-18) Default value from Table E-15 vegetation/m (default). of Regulatory Guide 1 .109.

Ys= Agricultural vegetation productivity for (4.0-15) Site Specific.

stored feed, 2.0 kg-vegetation/m 2 (4.0-18) Default value from Table E-15 (default). of Regulatory Guide 1.109.

, Tritium Parameters H= Absolute atmospheric humidity, 8.84 (4.0-13) Site Specific.

in gm-H20/m3. (4.0-16)

(4.0-19) 0.75 = Fraction of total vegetation that is (4.0-13) Default value from Table E-15 water. (4.0-16) of Regulatory Guide 1.109.

(4.0-19) 0.5 = Ratio of specific activity of vegetation (4.0-13) Default value from Table E-15 water to atmospheric water. (4.0-16) of Regulatory Guide 1.109.

(4.0-19) 4-23

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Parameter Description I Equation(s) I Reference Carbon-14 Parameters

[C02 = Fraction of carbon released as CO2 , (4.0-14) Site Specific. From EPRI 0.20. (4.0-17) Report 1023023, "Impact of (4.0-20) Nuclear Power Plant Operations on Carbon-14 Generation, Chemical Forms, and Releases" p= Ratio of total release time to the (4.0-14) Site Specific.

annual time during which (4.0-17) photosynthesis takes place, 1 (4.0-20)

(default).

GA1R = Concentration of natural carbon in the (4.0-14) EPA value as of 2014.

atmosphere, 0.19 grams-carbon per (4.0-17) m3-air. (4.0-20)

GL = Leafy vegetation carbon fraction, 0.11 (4.0-14) Default value from Appendix (default). C.3 of Regulatory Guide 1.109.

Gs = Stored vegetation carbon fraction, (4.0-14) Default value from Appendix 0.11 (default). C.3 of Regulatory Guide 1.109.

GMi1k = Fraction of animal feed mass that is (4.0-17) Default value from Appendix natural carbon, 0.11 (default). C.3 of Regulatory Guide 1.109.

GMeat = Fraction of animal feed mass that is (4.0-20) Default value from Appendix natural carbon, 0.11 (default). C.3 of Regulatory Guide 1.109.

4-24

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Parameter Description Equation(s) Reference Constants 1.1 = Constant to convert gamma air dose (4.0-2)

(mrad) to gamma skin dose (mrem). (6.0-2) 3.17x10- B Conversion constant: seconds to (4.0-7) years. (4.0-8)

(4.0-9)

(6.0-1 )

(6.0-2)

K'= Conversion constant: 106 pCi/J..lCi. (4.0-4)

(4.0-10) through (4.0-20)

K"= Conversion constant: 8760 hr/yr. (4.0-10)

K"'= Conversion constant: 103 gm/kg. (4.0-13)

(4.0-14)

(4.0-16)

(4.0-17)

(4.0-19)

(4.0-20)

Miscellaneous Parameters Qi= The release rate of radionuclide "i," (4.0-1 )

in units of J..lCi/sec. (4.0-2)

(4.0-3)

Q! = The total release of radionuclide "i" (4.0-7) in J..lCi. (4.0-8)

(4.0-9)

(6.0-1 )

(6.0-2)

SF= Shielding factor to account for (4.0-10) From Table E-15 of residence and structure shielding, (6.0-1 ) Regulatory Guide 1.109.

0.7. (6.0-2)

Ai= Decay constant for radionuclide "i" in (4.0-10) sec- 1 * (4.0-12)

(4.0-15)

(4.0-18)

Aw= Decay constant account for removal (4.0-12) From Table E-15 of of activity due to weathering effects (4.0-15) Regulatory Guide 1.109.

(14 days), 5. 73E-07 sec-1 . (4.0-18) 4-25

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 4.4 WASTE GAS SYSTEM OPERATION The waste gas system (WGS) described below shall be maintained and operated to keep releases ALARA.

4.4.1 System Description A flow diagram for the WGS is given in Figure 4.0-1. The system consists of three waste-gas compressor packages, six gas decay tanks, and the associated piping, valves, and instrumentation. Gaseous wastes are received from the following:

degassing of the reactor coolant and purging of the volume control tank prior to a cold shutdown and displacing of cover gases caused by liquid accumulation in the tanks connected to the vent header.

Design of the system precludes hydrogen explosion by means of ignition source elimination (diaphragm valves, low flow diaphragm compressors and system electrical grounding), and minimization of leakage outside the system. Explosive mixtures of hydrogen and oxygen have been demonstrated compatible with the system by operational experience.

4.4.2 Determination of Satisfactory Operation Doses will be calculated for batch and continuous releases as described in Section 4.3. These calculations will be used to ensure that the WGS is operating as designed. Because the Plant was designed to collect and hold for decay a vast majority of the high level gases generated within the primary system, and because the operating history of the Plant has demonstrated the system's consistent performance well below Appendix I limits, no additional operability requirements are specified.

4.5 RELEASE RATE FOR OFFSITE EC 10 CFR Part 20.1302 requires radioactive effluent releases to unrestricted areas be in concentrations less than the limits specified in Appendix B, Table 2 when averaged over a period not to exceed one year. (Note: there are no unrestricted areas anywhere within the site boundary as defined by Figure 5.0-1.)

Concentrations at this level if inhaled or ingested continuously for one year will result in a dose of 50 mrem whole body except for submersion dose isotopes (noble gases) which will results in a dose of 100 mrem whole body.

10 CFR Part 50.36a requires that the release of radioactive materials be kept as low as reasonably achievable. However, the section further states that the licensee is permitted the flexibility of operation, to assure a dependable source of power even under unusual operating conditions, to release quantities of material higher than a small percentage of 10 CFR Part 20.1302 limits but still within those limits.

Appendix I to 10 CFR Part 50 provides the numerical guidelines on limiting conditions for operations to meet the as low as reasonably achievable requirement.

4-26

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Demonstration of compliance with the lower dose limits of Appendix I to 10 CFR Part 50 provides reasonable assurance that the limits of 10 CFR Part 20.1302 are not exceeded.

X/Q and D/Q values are evaluated periodically (every 3 to 5 years) considering 5 (or more) years of meteorological data. If the evaluation indicates the long-term, annual average X/Q and D/Q are non-conservative by 10 percent or more, affected values are revised or the reason why such changes are not necessary is documented.

4.6 PARTICULATE AND IODINE SAMPLING Particulate and iodine samples are obtained from the continuous sample stream pulled from the Plant stack. Samples typically are obtained to represent an integrated release from a gas batch (waste gas decay tank or Containment purge, for example), or a series of samples are obtained to follow the course of a release.

In any event, sample intervals are weekly, at a minimum.

Because HEPA filters are present between most source inputs to the stack and the sample point, releases of particulates normally are significantly less than pre-release calculations indicate. This provides for conservatism in establishing setpoints and in estimation of pre-release dose calculations. However, for the sake of maintaining accurate release totals, monitor results (for gases) and sample results (for particulates and iodines) utilized rather than the pre-release estimates, for cumulative records.

Gamma analytical results for particulate and halogen filters are combined for determination of total activity of particulates and halogens released. Sampling and analysis will be performed per Table 1-3 requirements.

4.7 NOBLE GAS SAMPLING Noble gases will be sampled from Waste Gas Decay Tanks prior to release and the Containment prior to purging. Analysis of these samples will be used for accountability of noble gases. Off gas will be sampled at least weekly and used to calculate monthly noble gas releases. Non-routine releases will be quantified from the stack noble gas monitor (RE 2326) which has a LLD of 1E-06 !-ICi/cc. Sampling and analysis will be performed per Table 1-3 requirements.

4.8 TRITIUM SAMPLING Tritium has a low dose consequence to the public because of low energy decay.

The major contributors to tritium effluents are evaporation from the fuel pool and reactor cavity (when flooded). Because of the low dose impact, gaseous tritium sampling will not be required. Tritium effluents will be estimated using conservative evaporation rate calculations from the fuel pool and reactor cavity.

4-27

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 FIGURE 4.0-1 GASEOUS EFFLUENT FLOW PATHS CllliJEt.A Of

teA IMJIIIAlJ CDlfAlft.

IlDG lit ..'

I-IJ......_ 1lIi.'L" SUPft,v-...,....

Mil'

"III ' * . 17" . . , ml11l1PlUfft.Y Nfl) 0lIl( OJ r..\) ~

. _______ ._ _____ ._______._ _ __ ____ __! lCM "NOT thIIIIMn:O _________ _ ______ ________ __ _

4-28

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 5.0 LIQUID EFFLUENTS 5.1 LIQUID EFFLUENT CALCULATIONS 5.1.1 liquid Effluent Concentration limits Control 1.2.1.1 requires liquid effluent monitors to have alarm/trip setpoints to ensure that the instantaneous concentration at the site boundary does not exceed 10 times the concentration limits specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. The liquid concentration limit must meet the restriction of equation (5.0-1) as required by Control 1.2.1.1. The Liquid Radwaste Effluent Line Monitor must provide alarm and automatic termination of a release prior to exceeding the concentration limits of Control 1.2.1.1. To meet this requirement, the alarm/trip setpoints for the appropriate liquid effluent monitors and flow measurement devices are set to ensure that equation (5.0-1) is satisfied at the discharge point into the environment.

~c.

LEC~. ~ 10 i !

(5.0-1)

WHERE: Ci = The concentration of radionuclide, "i" in IJCilml.

= Effluent Concentration Limit (ECL) for radionuclide, "i" in IJCi/ml from 10 CFR Part 20, Appendix B, Table 2, Column 2.

The dilution to waste ratio required to meet the constraints of equation (5.0-1) for a specific radionuclide mix is defined as the Required Dilution Factor (RDF) and is given by:

~ C.

RDF = Li 10 x ~CL.!

(5.0-2)

WHERE: RDF = The Required Dilution Factor. This is also referred to as the Total ECL Fraction.

L i lOXECLi Ci = Defined as the Total ECL Fraction.

Ci = The effluent concentration of radionuclide, "i" in IJCi/ml.

HCL i = The 10 CFR Part 20 Effluent Concentration limit (ECL) for radionuclide, "i" in IJCi/ml.

The Actual Dilution Factor (ADF) is defined as the ratio of the dilution flow to the waste flow as shown in equation (5.0-3).

5-1

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Dilution Flow (F)

ADF=-----

Waste Flow (f)

(5.0-3)

To meet the requirements of equation (5.0-1) the actual dilution factor (ADF) must be greater than the required dilution factor (RDF) or:

Dilution Flow (F) '\' Ci Waste Flow (f) > 410, X ECL; (5.0-4)

The concentration limits of ODCM Section 5.1.1 can be met by establishing the following operational constraints.

Minimum Dilution Flow

Maximum Waste Flow

Maximum Effluent Concentration To ensure that monitor alarm takes place prior to exceeding the concentration limits an Administrative Safety Factor (ASF) is used to establish more conservative release parameters. It may be adjusted as desired provided the value does not exceed 0.9.

The concentration limits of ODCM Section 1.2.2 are site limits and therefore it is necessary to account for discharges from all liquid release points. A Release Allocation Fraction (RAF) is used to account for simultaneous discharges from the site. The values listed in Table 5-1, are typical and may be adjusted according to operational needs provided the sum of the RAFs for all release points from the site does not exceed 0.9.

Operational limits for these parameters are established using the following methodologies:

5-2

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 5.1.1.1 Minimum Dilution Flow Rate Limit The Minimum acceptable operational dilution flow (Fmin) is:

fXRDF f " Ci Fmin = ASF x RAF = ASF x RAF x 410 X ECL i t

(5.0-5)

WHERE: Fmin = Minimum acceptable dilution flow from the unit in gpm.

f = The expected waste flow rate in gpm.

RDF = The required dilution factor as defined by equation (5.0-2).

ASF = An Administrative Safety Factor to ensure that alarm/trip occurs prior to exceeding the limits, defined as ~ 0.9.

RAF = A Release Allocation Fraction to ensure that the concentration limits of Control 1.2.2.1 will be met during simultaneous discharges from the site. See Table 5-1.

5.1.1.2 Maximum Effluent Discharge Flow Rate Limit The maximum allowable operational effluent flow rate (fmax) is:

F x ASF x RAF F xASF x RAF fmax = RDF 10 XLi CJECL i (5.0-6)

WHERE: fmax = Maximum allowable operational effluent flow rate in gpm.

F = Expected dilution from for the unit in gpm.

ASF = The Administrative Safety Factor defined as ~ 0.9.

RAF = A Release Allocation Fraction to ensure that the concentration limits of Control 1.2.2.1 will be met during simultaneous discharges from the site. See Table 5-1.

5-3

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 5.1.1.3 Maximum Liquid Effluent Concentration The maximum allowable effluent concentration is given by:

C = ~ C. Fminlfmax x ASF x RAF max L t RDF i

(5.0-7)

WHERE: Cmax = Maximum allowable liquid effluent concentration in ~Ci/ml.

Ci = Concentration of radionuclide, "i" in uC/ml.

Fmin = Guaranteed maximum waste flow throughout the period of release in gpm. The maximum waste flow may be determined by pump curves or other means.

fmax = Maximum allowable operational effluent flow rate in gpm.

RDF = The Required Dilution Factor as defined by equation (5.0-2).

ASF = The Administrative Safety Factor defined as :5 0.9.

RAF = A Release Allocation Fraction to ensure that the concentration limits of Control 1.2.2.1 will be met during simultaneous discharges from the site. See Table 5-1.

5.1.2 Liquid Rad Monitor Setpoint Determination The liquid rad monitor setpoint methodology makes use of the Administrative Safety Factor and the Release Allocation Fraction to ensure liquid rad effluent alarm and/or trip occurs prior to exceeding the limits of ODCM Section 1.2.2 during periods of simultaneous releases .

The actual operational setpoint may be set more conservative than specified by equation (5.0-8) or (5.0-12), provided the restrictions of equation (5.0-1) are met.

5-4

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 5.1.2.1 Liquid Rad Monitor Setpoint Methodology The liquid rad monitor setpoint is given by:

SP =L"C9 9

x [Fminlfmax] x ASF x RAF x MR + Bk RDF 9 (S.O-B)

WHERE: SP = Liquid rad monitor setpoint in IJCi/ml.

= Total gamma emitter concentration in IJCi/ml.

= Concentration of gamma emitter "g" in IJCi/ml.

= Minimum acceptable dilution flow from the unit as defined by equation (5.0-5) in gpm.

fmax = Maximum allowable operational effluent flow rate as defined by equation (5.0-6) in gpm.

RDF = The Required Dilution Factor as defined by equation (5.0-2).

ASF = The Administrative Safety Factor defined as ~ 0.9 to ensure that alarm/trip occurs prior to exceeding the limits of Control 1.2.2.1. The factor may be adjusted downward as desired.

RAF = A Release Allocation Fraction to ensure that the concentration limits of Control 1.2.2.1 will be met during simultaneous discharges from the site. See Table 5-1 .

MR = Monitor Response in cpm per uCi/ml Bkg = Adjustment for rad monitor background.

5-5

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 5-1 TYPICAL LIQUID RELEASE ALLOCATION FRACTIONS*

Instrument Monitor Unit Release Allocation Monitor Number Function Fraction Liquid Radwaste Alarm and RIA-1049 0.7 Discharge Terminate Alarm and 0.1 Waste Water Discharge RIA-5211 Terminate Service Water Slowdown RIA-0833 Alarm Only 0.1

The sum of the Release Allocation Fractions for the site shall not exceed 0.9. The rad mOnitor Release Allocation Fractions may be adjusted based on operational requirements.

5.1.3 Adjustments To Setpoints 5.1.3.1 Contaminated Dilution Stream Normally the dilution flow stream is expected to be uncontaminated. However, in the '

event that activity is present in the dilution flow stream the minimum acceptable dilution flow, Fmin , may be adjusted as shown:

FI min = Fmin X ( ~

1 - L..i-Cli)

ECLi (5.0-9)

WHERE: F' min = Minimum acceptable contaminated dilution flow from the unit in gpm.

= Minimum acceptable dilution flow from the unit as defined by equation (5.0-5) in gpm.

e'*t = Concentration of radionuclide "i" in the dilution stream.

= Effluent Concentration Limit (ECl) for radionuclide, "i" in I-ICilml from 10 CFR Part 20, Appendix B, Table 2, Column 2.

5-6

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 5.1.3.2 High Effluent Tritium Concentrations For low gamma activity releases with relatively high tritium concentrations an alternate setpoint methodology may be applied.

A Tritium Correction Factor (TCF) is defined as:

rCF = [ 1- ( CH-3/( lOXECLH_3))]

O.9xF* If*

(5.0-10)

WHERE: TCF = The dimensionless Tritium Correction Factor.

CH- 3 = An assumed conservative (maximum) concentration of Tritium (H-3) in the effluent stream in I-ICilml.

ECL H _ 3 = Effluent concentration limit for H-3 in I-ICi/ml.

F* = An assumed conservative (minimum) dilution flow rate in gpm.

r = An assumed conservative (maximum) waste flow rate in gpm.

0.9 = Administrative factor to provide a conservative value for the Tritium Correction Factor.

Values for CH- 3

F* and r should be chosen such that it is unnecessary to recalculate the Tritium Correction Factor for normal releases.

The Corrected Required Dilution Factor (RDF*) is defined as:

RDF* =~ . Ci (5.0-11)

L.1~B-3 lOXECLi WHERE: RDF* = The Corrected Required Tritium Correction Factor which excludes H-3.

~ Ci_

L.i*H-310XECLi -

The Total ECl Fraction excluding H-3.

ECL i = Effluent concentration limit for radionuclide "i" in I-ICi/ml.

5-7

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 The corrected Set Point (SP*) is given by:

SP* = L o C0 X [Fminlfmax] X rCF RDF' x ASF x RAF x MR + Bkg (5.0-12)

WHERE: Co = Concentration of gamma emitter "g" in !-,Ci/ml.

LoCo = Total gamma emitter concentration in !-,Ci/ml.

Fmin = Minimum acceptable dilution flow rate from the unit as defined by equation (5.0-5) as appropriate, in gpm.

{max = Maximum allowable operational effluent flow rate as defined by equation (5.0-6) in gpm.

RDF* = The Required Dilution Factor adjusted for the omission of H-3 as defined by equation (5.0-11).

rCF = The Tritium Correction Factor as defined by equation (5.0-10).

ASF = The Administrative Safety Factor defined as :5 0.9.

The factor may be adjusted downward as desired.

RAF = A Release Allocation Fraction to ensure that the concentration limits of Control 1.2.2.1 will be met during simultaneous discharges from the site. See Table 5-1.

MR = Monitor Response in cpm per uCi/ml (or appropriate units)

Bkg = Adjustment for rad monitor background.

5.1 .3.3 Setpoints during periods of no effluent discharge.

When no liquid discharges are taking place, the rad effluent monitor setpoint shall be set at a sufficient level above background to prevent spurious alarms due to fluctuation in the background.

5-8

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 5.2 APPENDIX I DOSE CALCULATIONS 5.2.1 RETS Requirement Control 1.2.3.1 requires that the quantity of radionuclides released be limited such that the dose or dose commitment to an individual from radioactive materials in liquid effluents release to unrestricted areas from the reactor (see Figure 5.0-1) will not exceed:

a. During any calendar quarter, 1.5 mrem to the total body and 5 mrem to any organ, and

b. During any calendar year, 3 mrem to the total body and 10 mrem to any organ.

To ensure compliance, quantities of activity of each radionuclide released will be summed for each release and accumulated for each quarter as follows in Section 5.2.2.

5.2.2 Liquid Effluent Organ Dose to a Member of the Public 5.2.2.1 Critical Receptor Dose The organ dose for the adult age group is given by:

Dr = Ft::.t Ii AirCi (5.0-13)

WHERE: Dr = Dose to adult organ "T" in mrem.

= Is the site specific ingestion dose factor for radionuclide "i" and organ "T," in units of mrem/hr per ~Cilml. Site specific values are listed in Table 7-4.

= Duration of release in hours.

= Waste stream concentration of radionuclide "i" in ~Ci/ml.

F = The near field dilution average dilution factor as defined in equation (5.0-15).

5-9

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 The site specific ingestion dose factors, Ail are listed in Table 7-4 and are given by:

(5.0-14)

WHERE: Ko = Unit conversion factor: 1.14x1 05 in pCi/IJCi x year/hr.

Uwa = The potable water consumption for the age adult group in liters/yr.

Dw = The far field dilution factor which describes the dilution from the near field area within one-quarter mile of the release point(s) to the potable water intake for water consumption.

UFa = The fish consumption for the adult age group in kg/yr.

BFi = The bioaccumulation factor for fresh water fish for nuclide "i" .

in pCi/kg per pCi/1. From Table 7-2.

DFaiT = The ingestion dose factor for the adult age group, radionuclide "i" and organ "r". In mrem per pCi from Regulatory Guide 1.109, Table E-11. Ingestion dose factors for radionuclides listed in Table 7-4 and not found in Regulatory Guide 1.109 are taken from NUREG/CR-4013.

The near field average dilution factor is given by:

(average undiluted liquid waste flow)

FIe =----------------~--------------------~------------~-----------

(average flow from the discharge structure) x Z (5.0-15)

WHERE: Z = The factor that describes the mixing effect of the discharge structure into the near field.

5-10

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 5-2 PARAMETERS USED IN LIQUID EFFLUENT DOSE CALCULATIONS Paramete Equation(

Description Reference r s)

Dw= The far field dilution factor which (5.0-14) Based upon USFAR 11.2.3.1 describes the dilution from the and 11.2.5.

near field area within one-quarter mile of the release point(s) to the potable water intake for water consumption.

The value used is 66.7.

Uwa = The potable water consumption (5.0-14) Site Specific.

for the age adult group, 720 Default value is from Table liters/yr. E-5 of Regulatory Guide 1.109.

UFa = The fish consumption for the (5.0-14) Site Specific.

adult age group, 21 kg/yr. Default value is from Table E-5 of Regulatory Guide 1.109.

Z= The factor that describes the (5.0-15) Taken from UFSAR 11.2.5.

mixing effect of the discharge structure into the near field, 15.

5.2.3 Release Analysis Dose calculations shall be performed for each batch release, and weekly for continuous releases.

5.3 OPERABILITY OF LIQUID RADWASTE EQUIPMENT The Palisades liquid radwaste system is designed to reduce the radioactive materials in liquid wastes prior to their discharge (through deep bed filtration and ion exchange) so that radioactivity in liquid effluent releases to unrestricted areas (see FIGURE 5.0-1) will not exceed the limits of Control 1.2.2.1.

5.4 RELEASE RATE FOR OFFSITE EC (50 MREMIYR) 10 CFR Part 20.1302 requires radioactive effluent releases to unrestricted areas be less than the limits specified in Appendix B, Table 2 when averaged over a period not to exceed one year. Concentrations at this Effluent Concentration (EC) level, if ingested for one year, will result in a dose of 50 millirem to the total body. In addition, 10 CFR Part 50.36a requires that the release of radioactive materials be kept as low as is reasonably achievable. Appendix I to 10 CFR Part 50 provides the numerical guidelines on limiting conditions for operations to meet the as low as is reasonably achievable requirement.

5-11

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 FIGURE 5.0-1 PALISADES SITE BOUNDARY

\

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/ .2;,:;

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5-12

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 FIGURE 5.0-2 LIQUID EFFLUENT FLOW PATHS n 1J\N WI\' ,I\

.Y ~, 1( ""

PR tMAR Y SYST(M StORAGE IIINIe

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SERVICE WAIER _ _ _--JI.-----_-,;;.\A;,;,!(.;.;E;.;Ilt;.:.:.

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5-13

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 6.0 URANIUM FUEL CYCLE DOSE SPECIFICATION In accordance with Control 1.3.1.1, if either liquid or gaseous quarterly releases exceed the quantity which would cause offsite doses more than twice the limit of Controls 1.1.3.1, 1.1.4.1, or 1.2.3.1, then the cumulative dose contributions from combined release plus direct radiation sources (from the reactor unit and radwaste storage tanks) shall be calculated. The dose is to be determined for the member of the public protected to be the most highly exposed to these combined sources.

6.1 ASSUMPTIONS

1. The full time resident determined to be maximally exposed individual (excluding infant) is assumed also to be a fisherman. This individual is assumed to drink water and ingest local fish at the rates specified in Table 5-2.

2. Amount of shore line fishing (at accessible shoreline adjacent to site security fence) is conservatively assumed as 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months per quarter (average of approximately 1/2 hour per day each day of the quarter) for the second and third quarters of the year, 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months for the fourth quarter and 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months for the first quarter.

6.2 URANIUM FUEL CYCLE DOSE CALCULATIONS Maximum doses to the total body and internal organs of an individual shall be determined by use of LADTAP II and GASPAR II computer codes, and doses to like organs and total body summed. Added to this sum will be a mean dose rate, calculated or measured for the shoreline due to Plant present curing the quarter in question, times the assumed fishing time.

Radiological Effluent Control 1.3.1.1 limits the dose to any MEMBER OF THE PUBLIC, due to releases of radioactivity and radiation, from uranium fuel cycle sources to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consecutive months. The dose limits of this control differ from those of 1.2.3.1, 1.1.3.1 and 1.1.4.1 in that dose to an individual from all units and all pathways, including direct radiation must be considered.

It is highly unlikely that an individual receiving the highest dose via the liquid pathway will simultaneously be receiving the highest dose due to direct radiation, noble gases and radioiodines, H-3, C-14 and particulates. Therefore only the doses resulting from direct radiation and radiological EFFLUENT RELEASES to the atmosphere need be addressed.

6-1

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 6.2.1 Direct Radiation Dose to a Member of the Public 6.2.1.1 The dose contribution to a MEMBER OF THE PUBLIC as a result of direct radiation shall be determined by direct field measurements (SITE BOUNDARY or AREA TLDs, micro R meter readings, etc.), calculation or shielding code or an appropriate combination thereof.

6.2.2 Organ Dose to a Member of the Public From Noble Gases Calculation of noble gas organ dose to a MEMBER OF THE PUBLIC, is not required to demonstrate compliance with 10 CFR Part 50, App I. However the noble gas organ dose should be used to demonstrate compliance with the Total Fuel Cycle dose limits of Control 1.3.1.1.

Dose due to immersion in noble gases is an external dose pathway and therefore results in a total body dose due to gammas and a skin dose due to gamma and beta.

Doses to all other organs are presumed to be equal to the total body dose. Organ dose and skin dose are assumed to be the same for all age groups.

6.2.2.1 Organ Dose to the Total Body to a Member of the Public Due to Immersion in Noble Gases Total Body Dose (mrem) = 3.17 x 1O- 8 (SF) X/Q CR Li KJJ! (6.0*1 )

6-2

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 6.2.2.2 Organ Dose to the Skin to a Member of the Public Due to Immersion in Noble Gases Skin(mrem) = 3.17 x 10-8 X/Q CR Li(L i + (SF)1.1Maiil (6.0-2)

WHERE: Total Body Dose= The total body and organ dose for all age groups in mrem.

Skin = The skin dose for all age groups in mrem.

3.17 x 10- 8 = Conversion factor in years/sec.

x/Q CR = Atmospheric dispersion value for immersion at the location of interest (typically the CRITICAL RECEPTOR) in sec/m 3 . See Table 4-1.

SF = Dimensionless factor to account for residence and structure shielding from Table E-15 of Regulatory Guide 1.109.

Ki = The total body dose factor due to gamma emissions for noble gas radionuclide "i," from Table 7-3.

Li = The skin dose factor due to beta emissions for noble gas radionuclide "i," from Table 7-3.

1.1 = Conversion constant of 1.1 mrem/mrad.

Mi = The air dose factor due to gamma emissions noble gas radionuclide "i," from Table 7-3.

iiI = The total release of noble gas radionuclide "i" in jJCi.

6.2.3 Organ Dose to a Member of the Public Due to Radioiodines. Tritium and Particulates Released to the Atmosphere 6.2.3.1 The organ dose to a MEMBER OF THE PUBLIC due to Radioiodines, Tritium, Carbon-14 and Particulates released to the atmosphere shall be determined by the methodology of ODCM Section 4.3.2.

6-3

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 6.2.4 Total Uranium Fuel Cycle Dose 6.2.4.1 The dose due to the Total Uranium Fuel Cycle is determined by:

DoseUFC = DI + DD + DNG + DRP (6.0-3)

WHERE: DoseUFC = The Total Uranium Fuel Cycle dose for the site (mrem).

DI = Direct radiation dose from the ISFSI as determined by aDCM Section 6.2.1 (mrem).

DD = Direct radiation dose from the site as determined by aDCM Section 6.2.1 (mrem).

DNG = The reactor unit organ dose (mrem) due to noble gases released to the atmosphere units calculated in accordance with aDCM Section 6.2.2.

The noble gas air dose as calculated in aDCM Section 4.3.1 may be used as a conservative approximation for noble gas organ dose.

DRP = The reactor unit organ dose (mrem) due to radioiodines, tritium, carbon-14 and particulates released to the atmosphere calculated in accordance with aDCM Section 4.3.2. '

The Total Uranium Fuel Cycle dose should be assessed at that location in the UNRESTRICTED AREA where the combination of existing pathways and receptor age groups indicate the maximum potential exposure to an individual.

6-4

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29

7.0 REFERENCES

AND DATA 7.1 REFERENCE DOCUMENTS

1. CH 6.61, Revising the ODCM.

2. EPRI Report 1023023, "Impact of Nuclear Power Plant Operations on Carbon-14 Generation, Chemical Forms, and Releases," (December 2011).

3. ODCM Appendix B DOCKET 50-255 - LICENSE DPR PALISADES PLANT REQUEST TO RETAIN SOIL IN ACCORDANCE WITH 10 CFR 20.302 Revision 0 August 1, 1991

4. Slade, DH, (editor), "Meteorology and Atomic Energy," US Atomic Energy Commission, AEC TID-24190, (1968).

5. US NRC NUREG-0133, Boegli, TS, RR Bellamy, WL Britz, and RL Waterfield, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants" (October 1978).

6. US NRC NUREG-0472, "Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors," Revision 3 (January 1983).

7. US NRC NUREG-1301, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors, (April 1991).

8. US NRC NUREG/CR-4013, LADTAP 11- Technical Reference and User Guide, Apri11986.

9. US NRC NUREG/CR-4653, GASPAR II - Technical Reference and User Guide, March 1987.

10. US NRC 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).

11. US NRC 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, (March 1976).

12. US NRC Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light - Water - Cooled Reactors," (March 1976).

13. US NRC 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).

7-1

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 7.2 TRANSFER AND SIOACCUMULATION FACTORS TABLE 7-1 TRANSFER FACTORS Fm - Milk (COW) Fm - MILK (GOAT) Ff - MEAT Biv Element (DAYS/L) (DAYS/L) (DAYS/KG) (VEG/SOIL)

H 1.00E-02 1.70E-01 1.20E-02 4.BOE+OO C 1.20E-02 1.00E-01 3.10E-02 5.50E+OO Na 4.00E-02 4.00E-02 3.00E-02 5.20E-02 P 2.50E-02 2.50E-01 4.60E-02 1.10E+OO Cr 2.20E-03 2.20E-03 2.40E-03 2.50E-04 Mn 2.50E-04 2.50E-04 B.OOE-04 2.90E-02 Fe 1.20E-03 1.30E-04 4.00E-02 6.60E-04 Co 1.00E-03 1.00E-03 1.30E-02 9.40E-03 Ni 6.70E-03 6.70E-03 5.30E-02 1.90E-02 Cu 1.40E-02 1.30E-02 B.OOE-03 1.20E-01 Zn 3.90E-02 3.90E-02 3.00E-02 4.00E-01 Rb 3.00E-02 3.00E-02 3.10E-02 1.30E-01 Sr B.OOE-04 1.40E-02 6.00E-04 1.70E-02 Y 1.00E-05 1.00E-05 4.60E-03 2.60E-03 Zr 5.00E-06 5.00E-06 3.40E-02 1.70E-04 Nb 2.50E-03 2.50E-03 2.BOE-01 9.40E-03 Mo 7.50E-03 7.50E-03 B.OOE-03 1.20E-01 Tc 2.50E-02 2.50E-02 4 .00E-01 2.50E-01 Ru 1.00E-06 1.00E-06 4.00E-01 5.00E-02 Rh 1.00E-02 1.00E-02 1.50E-03 1.30E+01 Ag 5.00E-02 5.00E-02 1.70E-02 1.50E-01 Te 1.00E-03 1.00E-03 7.70E-02 1.30E+OO I 6.00E-03 6.00E-02 2.90E-03 2.00E-02 Cs ' 1.20E-02 3.00E-01 4.00E-03 1.00E-02 Sa 4.00E-04 4.00E-04 3.20E-03 5.00E-03 La 5.00E-06 5.00E-06 2.00E-04 2.50E-03 Ce 1.00E-04 1.00E-04 1.20E-03 2.50E-03 Pr 5.00E-06 5.00E-06 4.70E-03 2.50E-03 Nd 5.00E,.06 5.00E-06 3.30E-03 2.40E-03 W 5.00E-04 5.00E-04 1.30E-03 1.BOE-02 Np 5.00E-06 5.00E-06 2.00E-04 2.50E-03 7-2

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 7-2 FRESHWATER BIOACCUMULATION FACTORS (pCi/kg per pCi/liter)

Fresh Water

Fresh Water

Element Fish Invertebrate H 9.00E-01 9.00E-01 C 4.60E+03 9.10E+03 F 1.00E+01 1.00E+02 Na 1.00E+02 2.00E+02 P 1.00E+OS 2.00E+04 Cr 2.00E+02 2.00E+03 Mn 4.OOE+02 9.00E+04 Fe 1.00E+02 3.20E+03 Co S.OOE+01 2.00E+02 Ni 1.00E+02 1.00E+02 Cu S.OOE+01 4.OOE+02 Zn 2.00E+03 1.00E+04 Br 4.20E+02 3.30E+02 Rb 2.00E+03 1.00E+03 Sr 3.00E+01 1.00E+02 y 2.S0E+01 1.00E+03 Zr 3.30E+OO 6.70E+OO Nb 3.00E+04 1.00E+02 Mo 1.00E+01 1.00E+01 Tc 1.S0E+01 S.OOE+OO Ru 1.00E+01 3.00E+02 Rh 1.00E+01 3.00E+02 Sb 1.00E+OO 1.00E+01 Te 4.OOE+02 6.10E+03 I 1.S0E+01 S.OOE+OO Cs 2.00E+03 1.00E+03 Ba 4.OOE+OO 2.00E+02 La 2.S0E+01 1.00E+03 Ce 1.00E+OO 1.00E+03 Pr 2.S0E+01 1.00E+03 Nd 2.S0E+01 1.00E+03 W 1.20E+03 1.00E+01

From Table A-1 of Regulatory Guide 1.109 7-3

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 7.3 DOSE FACTORS TABLE 7-3 NOBLE GAS IMMERSION DOSE FACTORS Gamma body Beta Skin Gamma Air Beta Air Nuclide Dose1 Dose1 Dose2 Dose2 JKil (ll) (Mi) {Nit Kr-85m 1.17E3 1.46E3 1.23E3 1.97E3 Kr-85 1.61 E1 1.34E3 1.72E1 1.95E3 Kr-87 5.92E3 9.73E3 6.17E3 1.03E4 Kr-88 1.47E4 2.37E3 1.52E4 2.93E3 Kr-89 1.66E4 1.01 E4 1.73E4 1.06E4 Xe-131m 9.15E1 4.76E2 1.56E2 1.11 E3 Xe-133m 2.51E2 9.94E2 3.27E2 1.48E3 Xe-133 2.94E2 3.06E2 3.53E2 1.05E3 Xe-135m 3.12E3 7.11 E2 3.36E3 7.39E2 Xe-135 1.81E3 1.86E3 1.92E3 2.46E3 Xe-137 1.42E3 1.22E4 1.51 E3 1.27E4 Xe-138 8.83E3 4.13E3 9.21E3 4.75E3 Ar-41 8.84E3 2.69E3 9.30E3 3.28E3

1. mrem/y per flC1/m-"

2. mrad/y per flCi/m3

Dose factors for exposure to a semi-infinite cloud of noble gases. Values were obtained from USNRC Regulatory Guide 1.109, Revision 1 (October 1977).

7-4

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 7-4 ADULT - POTABLE WATER AND FISH INGESTION (A1T)

Age Group: Adult Pathway: Potable Water and Fish Ingestion Units: mrem/yr per ~Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gi-LLi TBody H-3 O.OOE+OO 3.57E-01 3.57E-01 3.57E-01 3.57E-01 3.57E-01 3.57E-01 C-14 3.13E+04 6.26E+03 6.26E+03 6.26E+03 6.26E+03 6.26E+03 6.26E+03 F-18 1.57E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.66E-01 1.74E+00 P-32 4.62E+07 2.87E+06 O.OOE+OO O.OOE+OO O.OOE+OO 5.20E+06 1.79E+06 CR-51 O.OOE+OO O.OOE+OO 7.63E-01 2.81E-01 1.69E+00 3.21E+02 1.28E+00 MN-54 O.OOE+OO 4.38E+03 O.OOE+OO 1.30E+03 O.OOE+OO 1.34E+04 8.36E+02 MN-56 O.OOE+OO 1.10E+02 O.OOE+OO 1.40E+02 O.OOE+OO 3.52E+03 1.96E+01 FE-55 6.62E+02 4.57E+02 O.OOE+OO O.OOE+OO 2.55E+02 2.62E+02 1.07E+02 FE-59 1.04E+03 2.45E+03 O.OOE+OO O.OOE+OO 6.86E+02 8.18E+03 9.41E+02 CO-57 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CO-58 O.OOE+OO 9.01E+01 O.OOE+OO O.OOE+OO O.OOE+OO 1.83E+03 2.02E+02 CO-60 O.OOE+OO 2.59E+02 O.OOE+OO O.OOE+OO O.OOE+OO 4.86E+03 5.71E+02 NI-63 3.13E+04 2.17E+03 O.OOE+OO O.OOE+OO O.OOE+OO 4.52E+02 1.05E+03 NI-65 1.27E+02 1.65E+01 O.OOE+OO O.OOE+OO O.OOE+OO 4.19E+02 7.53E+00 CU-64 O.OOE+OO 1.01 E+01 O.OOE+OO 2.54E+01 O.OOE+OO 8.59E+02 4.73E+00 ZN-65 2.32E+04 7.38E+04 O.OOE+OO 4.93E+04 O.OOE+OO 4.65E+04 3.33E+04 ZN-69 4.93E+01 9.43E+01 O.OOE+OO 6.13E+01 O.OOE+OO 1.42E+01 6.56E+00 ZN-69M 8.14E+02 1.95E+03 O.OOE+OO 1.18E+03 O.OOE+OO 1.19E+05 1.79E+02 BR-82 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.61E+03 2.28E+03 BR-83 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.83E+01 4.05E+01 BR-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.12E-04 5.25E+01 BR-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.15E+00 RB-86 O.OOE+OO 1.01E+OS O.OOE+OO O.OOE+OO O.OOE+OO 1.99E+04 4.71E+04 RB-88 O.OOE+OO 2.90E+02 O.OOE+OO O.OOE+OO O.OOE+OO 4.00E-09 1.54E+02 RB-89 O.OOE+OO 1.92E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.12E-11 1.35E+02 SR-89 2.2SE+04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.61E+03 6.46E+02 SR-90 5.54E+05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.60E+04 1.36E+05 SR-91 4.14E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.97E+03 1.67E+01 SR-92 1.57E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.11E+03 6.80E+00 Y-90 5.88E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.23E+03 1.58E-02 Y-91M 5.55E-03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.63E-02 2.15E-04 Y-91 8.61 E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.74E+03 2.30E-01 Y-92 5.16E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.04E+02 1.51 E-03 Y-93 1.64E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.19E+03 4.52E-03 ZR-95 2.78E-01 8.92E-02 O.OOE+OO 1.40E-01 O.OOE+OO 2.83E+02 6.04E-02 ZR-97 1.54E-02 3.lOE-03 O.OOE+OO 4.68E-03 O.OOE+OO 9.61E+02 1.42E-03 NB-95 4.47E+02 2.49E+02 O.OOE+OO 2.46E+02 O.OOE+OO 1.51E+06 1.34E+02 NB-97 3.75E+00 9.48E-01 O.OOE+OO 1.11E+00 O.OOE+OO 3.50E+03 3.46E-01 MO-99 O.OOE+OO 1.09E+02 O.OOE+OO 2.46E+02 O.OOE+OO 2.52E+02 2.07E+01 TC-99M 9.18E-03 2.59E-02 O.OOE+OO 3.94E-01 1.27E-02 1.53E+01 3.30E-01 TC-101 9.44E-03 1.36E-02 O.OOE+OO 2.45E-01 6.95E-03 4.09E-14 1.33E-01 7-5

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Age Group: Adult Pathway: Potable Water and Fish Ingestion Units: mrem/yr per ~Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gi*LLi TBody RU*103 4.66E+00 O.OOE+OO O.OOE+OO 1.78E+01 O.OOE+OO 5.44E+02 2.01E+00 RU-105 3.88E-01 O.OOE+OO O.OOE+OO 5.01E+00 O.OOE+OO 2.37E+02 1.53E-01 RU-106 6.93E+01 O.OOE+OO O:OOE+OO 1.34E+02 O.OOE+OO 4.48E+03 8.77E+00 AG-110M 1.08E+00 1.00E+00 O.OOE+OO 1.97E+00 O.OOE+OO 4.08E+02 5.94E-01 SB-124 1.02E+01 1.93E-01 2.47E-02 O.OOE+OO 7.94E+00 2.90E+02 4.04E+00 SB-125 6.52E+00 7.28E-02 6.63E-03 O.OOE+OO 5.03E+00 7.17E+01 1.55E+00 SB-126 4.19E+00 8.52E-02 2.56E-02 O.OOE+OO 2.57E+00 3.42E+02 1.51E+00 SB-127 9.40E-01 2.06E-02 1.13E-02 O.OOE+OO 5.57E-01 2.15E+02 3.61 E-01 TE-125M 2.57E+03 9.31E+02 7.73E+02 1.05E+04 O.OOE+OO 1.03E+04 3.44E+02 TE-127M 6.49E+03 2.32E+03 1.66E+03 2.64E+04 O.OOE+OO 2.18E+04 7.91 E+02 TE-127 1.05E+02 3.79E+01 7.81E+01 4.30E+02 O.OOE+OO 8.32E+03 2.28E+01 TE-129M 1.10E+04 4.11E+03 3.79E+03 4.60E+04 O.OOE+OO 5.55E+04 1.75E+03 TE-129 3.01E+01 1.13E+01 2.31E+01 1.27E+02 O.OOE+OO 2.27E+01 7.34E+00 TE-131M 1.66E+03 8.11E+02 1.28E+03 8.22E+03 O.OOE+OO 8.05E+04 6.76E+02 TE-131 1.89E+01 7.89E+00 1.55E+01 8.27E+01 O.OOE+OO 2.68E+00 5.96E+00 TE-132 2.42E+03 1.56E+03 1.73E+03 1.51E+04 O.OOE+OO 7.39E+04 1.47E+03 1-130 2.81E+01 8.29E+01 7.02E+03 1.29E+02 O.OOE+OO 7.13E+01 3.27E+01 1-131 1.55E+02 2.21E+02 7.25E+04 3.79E+02 O.OOE+OO 5.83E+01 1.27E+02 1-132 7.54E+00 2.02E+01 7.06E+02 3.21E+01 O.OOE+OO 3.79E+00 7.06E+00 1-133 5.28E+01 9.18E+01 1.35E+04 1.60E+02 O.OOE+OO 8.25E+01 2.80E+01 1-134 3.94E+00 1.07E+01 1.85E+02 1.70E+01 O.OOE+OO 9.33E-03 3.83E+00 1-135 1.65E+01 4.31E+01 2.84E+03 6.91E+01 O.OOE+OO 4.87E+01 1.59E+01 CS-134 2.98E+05 7.09E+05 O.OOE+OO 2.29E+05 7.61E+04 1.24E+04 5.79E+05 CS-136 3.12E+04 1.23E+05 O.OOE+OO 6.85E+04 9.39E+03 1.40E+04 8.86E+04 CS-137 3.82E+05 5.22E+05 O.OOE+OO 1.77E+05 5.89E+04 1.01E+04 3.42E+05 CS-138 2.64E+02 5.22E+02 O.OOE+OO 3.84E+02 3.79E+01 2.23E-03 2.59E+02 BA-139 1.05E+00 7.48E-04 O.OOE+OO 6.99E-04 4.24E-04 1.86E+00 3.07E-02 BA-140 2.20E+02 2.76E-01 O.OOE+OO 9.38E-02 1.58E-01 4.52E+02 1.44E+01 BA-141 5.10E-01 3.85E-04 O.OOE+OO 3.58E-04 2.19E-04 2.40E-10 1.72E-02 BA-142 2.31 E-01 2.37E-04 O.OOE+OO 2.00E-04 1.34E-04 3.25E-19 1.45E-02 LA-140 1.53E-01 7.70E-02 O.OOE+OO O.OOE+OO O.OOE+OO 5.65E+03 2.03E-02 LA-142 7.82E-03 3.56E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.60E+01 8.86E-04 CE-141 3.41 E-02 2.31E-02 O.OOE+OO 1.07E-02 O.OOE+OO 8.81E+01 2.61 E-03 CE-143 6.01E-03 4.44E+00 O.OOE+OO 1.96E-03 O.OOE+OO 1.66E+02 4.92E-04 CE-144 1.78E+00 7.43E-01 O.OOE+OO 4.41E-01 O.OOE+OO 6.01E+02 9.54E-02 PR-143 5.62E-01 2.25E-01 O.OOE+OO 1.30E-01 O.OOE+OO 2.46E+03 2.79E-02 PR-144 1.84E-03 7.64E-04 O.OOE+OO 4.31E-04 O.OOE+OO 2.65E-10 9.35E-05 NO-147 3.84E-01 4.44E-01 O.OOE+OO 2.60E-01 O.OOE+OO 2.13E+03 2.66E-02 W-187 2.96E+02 2.47E+02 O.OOE+OO O.OOE+OO O.OOE+OO 8.10E+04 8.65E+01 NP-239 3.00E-02 2.95E-03 O.OOE+OO 9.19E-03 O.OOE+OO 6.05E+02 1.62E-03 7-6

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 7-5 GROUND PLANE EXPOSURE - ALL AGE GROUPS (RA1(GP)J)

Age Grou p: All Pathway: Ground Plane Units: m 2 x mrem/yr 3er J,lCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gi-LLi TBody Skin H-3 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO C-14 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NA-24 1.20E+07 1.20E+07 1.20E+07 1.20E+07 1.20E+07 1.20E+07 1.20E+07 1.39E+07 P-32 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CR-S1 4.6SE+06 4.6SE+06 4.6SE+06 4.6SE+06 4.6SE+06 4.6SE+06 4.6SE+06 S.SOE+06 MN-S4 1.3BE+09 1.3BE+09 1.3BE+09 1.3BE+09 1.3BE+09 1.3BE+09 1.3BE+09 1.62E+09 MN-S6 B.99E+OS B.99E+OS B.99E+OS B.99E+OS B.99E+OS B.99E+OS B.99E+OS 1.06E+06 FE-55 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO FE-59 2.73E+OB 2.73E+OB 2.73E+OB 2.73E+OB 2.73E+OB 2.73E+OB 2.73E+OB 3.20E+OB CO-SB 3.BOE+OB 3.BOE+OB 3.BOE+OB 3.BOE+OB 3.BOE+OB 3.BOE+OB 3.BOE+OB 4.4SE+OB CO-60 2.1SE+10 2.1SE+10 2.1SE+10 2.1SE+10 2.1SE+10 2.1SE+10 2.1SE+10 2.S3E+10 NI-63 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NI-6S 2.97E+OS 2.97E+OS 2.97E+OS 2.97E+OS 2.97E+OS 2.97E+OS 2.97E+OS 3.4SE+OS CU-64 6.0SE+OS 6.0SE+OS 6.0SE+OS 6.0SE+OS 6.0SE+OS 6.0SE+OS 6.0SE+OS 6.B6E+OS ZN-6S 7.46E+OB 7.46E+OB 7.46E+OB 7.46E+OB 7.46E+OB 7.46E+OB 7.46E+OB B.S7E+OB ZN-69 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-B3 4.BBE+03 4.BBE+03 4.BBE+03 4.BBE+03 4.BBE+03 4.BBE+03 4.BBE+03 7.0BE+03 BR-B4 2.03E+OS 2.03E+OS 2.03E+OS 2.03E+OS 2.03E+OS 2.03E+OS 2.03E+OS 2.36E+OS BR-BS O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-B6 9.01E+06 9.01E+06 9.01E+06 9.01E+06 9.01E+06 9.01E+06 9.01E+06 1.03E+07 RB-BB 3.32E+04 3.32E+04 3.32E+04 3.32E+04 3.32E+04 3.32E+04 3.32E+04 3.79E+04 RB-B9 1.22E+OS 1.22E+OS 1.22E+OS 1.22E+OS 1.22E+OS 1.22E+OS 1.22E+OS 1.46E+OS SR-B9 2.16E+04 2.16E+04 2.16E+04 2.16E+04 2.16E+04 2.16E+04 2.16E+04 2.S1E+04 SR-90 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO SR-91 2.14E+06 2.14E+06 2.14E+06 2.14E+06 2.14E+06 2.14E+06 2.14E+06 2.S1E+06 SR-92 7.77E+OS 7.77E+OS 7.77E+OS 7.77E+OS 7.77E+OS 7.77E+OS 7.77E+OS B.64E+OS Y-90 4.S0E+03 4.S0E+03 4.S0E+03 4.S0E+03 4.S0E+03 4.S0E+03 4.S0E+03 S.31E+03 Y-91M 1.00E+OS 1.00E+OS 1.00E+OS 1.00E+OS 1.00E+OS 1.00E+OS 1.00E+OS 1.16E+OS Y-91 1.07E+06 1.07E+06 1.07E+06 1.07E+06 1.07E+06 1.07E+06 1.07E+06 1.21E+06 Y-92 1.B1E+OS 1.B1E+OS 1.B1E+OS 1.B1E+OS 1.B1E+OS 1.B1E+OS 1.B1E+OS 2.1SE+OS Y-93 1.B3E+OS 1.B3E+OS 1.B3E+OS 1.B3E+OS 1.B3E+OS 1.B3E+OS 1.B3E+OS 2.S0E+OS ZR-9S 2.4SE+OB 2.4SE+OB 2.4SE+OB 2.4SE+OB 2.4SE+OB 2.4SE+OB 2.4SE+OB 2.BSE+OB ZR-97 2.96E+06 2.96E+06 2.96E+06 2.96E+06 2.96E+06 2.96E+06 2.96E+06 3.44E+06 NB-9S 1.37E+OB 1.37E+OB 1.37E+OB 1.37E+OB 1.37E+OB 1.37E+OB 1.37E+OB 1.61E+OB MO-99 3.99E+06 3.99E+06 3.99E+06 3.99E+06 3.99E+06 3.99E+06 3.99E+06 4.62E+06 TC-99M 1.B4E+OS 1.B4E+OS 1.B4E+OS 1.B4E+OS 1.B4E+OS 1.B4E+OS 1.B4E+OS 2.11 E+OS TC-101 2.03E+04 2.03E+04 2.03E+04 2.03E+04 2.03E+04 2.03E+04 2.03E+04 2.26E+04 RU-103 1.0BE+OB 1.0BE+OB 1.0BE+OB 1.0BE+OB 1.0BE+OB 1.0BE+OB 1.0BE+OB 1.26E+OB RU-10S 6.36E+OS 6.36E+OS 6.36E+OS 6.36E+OS 6.36E+OS 6.36E+OS 6.36E+OS 7.21E+OS RU-106 4.22E+OB 4.22E+OB 4.22E+OB 4.22E+OB 4.22E+OB 4.22E+OB 4.22E+OB S.06E+OB AG-110M 3.4SE+09 3.4SE+09 3.4SE+09 3.4SE+09 3.4SE+09 3.4SE+09 3.4SE+09 4.02E+09 7-7

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Age Grou J: All Pathway: Ground Plane Units: m 2 x mrem/yr per IJCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gi-LLi TBody Skin TE-12SM 1.S6E+06 1.S6E+06 1.S6E+06 1.S6E+06 1.S6E+06 1.S6E+06 1.S6E+06 2.13E+06 TE-127M 9.16E+04 9.16E+04 9.16E+04 9.16E+04 9.16E+04 9.16E+04 9.16E+04 1.0BE+05 TE-127 2.9BE+03 2.9BE+03 2.9BE+03 2.9BE+03 2.9BE+03 2.9BE+03 2.9BE+03 3.27E+03 TE-129M 1.9BE+07 1.9BE+07 1.9BE+07 1.9BE+07 1.9BE+07 1.9BE+07 1.9BE+07 2.31E+07 TE-129 2.62E+04 2.62E+04 2.62E+04 2.62E+04 2.62E+04 2.62E+04 2.62E+04 3.10E+04 TE-131M 8.02E+06 B.02E+06 B.02E+06 8.02E+06 B.02E+06 B.02E+06 8.02E+06 9.46E+06 TE-131 2.93E+04 2.93E+04 2.93E+04 2.93E+04 2.93E+04 2.93E+04 2.93E+04 3.46E+07 TE-132 4.24E+06 4.24E+06 4.24E+06 4.24E+06 4.24E+06 4.24E+06 4.24E+06 4.99E+06 1-130 S.50E+06 5.S0E+06 S.50E+06 5.50E+06 5.50E+06 5.S0E+06 S.50E+06 6.6BE+06 1-131 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 2.09E+07 1-132 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.47E+06 1-133 2.45E+06 2.45E+06 2.45E+06 2.4SE+06 2.4SE+06 2.45E+06 2.45E+06 2.9BE+06 1-134 4.46E+OS 4.46E+05 4.46E+OS 4.46E+OS 4.46E+05 4.46E+OS 4.46E+OS S.30E+05 1-135 2.52E+06 2.52E+06 2.S2E+06 2.52E+06 2.52E+06 2.52E+06 2.52E+06 2.94E+06 CS-134 6.B3E+09 6.B3E+09 6.83E+09 6.B3E+09 6.B3E+09 6.B3E+09 6.B3E+09 7.97E+09 CS-136 1.50E+08 1.50E+OB 1.50E+08 1.50E+OB 1.50E+OB 1.50E+OB 1.50E+OB 1.70E+OB CS-137 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.20E+10 CS-138 3.60E+OS 3.60E+05 3.60E+OS 3.60E+05 3.60E+05 3.60E+OS 3.60E+05 4.11E+05 BA-139 1.05E+OS 1.05E+05 1.05E+05 1.05E+05 1.0SE+05 1.05E+OS 1.05E+05 1.1BE+05 BA-140 2.05E+07 2.05E+07 2.05E+07 2.0SE+07 2.0SE+07 2.05E+07 2.05E+07 2.35E+07 BA-141 4.17E+04 4.17E+04 4.17E+04 4.17E+04 4.17E+04 4.17E+04 4.17E+04 4.75E+04 BA-142 4.49E+04 4.49E+04 4.49E+04 4.49E+04 4.49E+04 4.49E+04 4.49E+04 5.11E+04 LA-140 1.92E+07 1.92E+07 1.92E+07 1.92E+07 1.92E+07 1.92E+07 1.92E+07 2.1BE+07 LA-142 7.36E+OS 7.36E+05 7.36E+OS 7.36E+05 7.36E+05 7.36E+OS 7.36E+05 B.B3E+05 CE-141 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.S4E+07 CE-143 2.32E+06 2.32E+06 2.32E+06 2.32E+06 2.32E+06 2.32E+06 2.32E+06 2.64E+06 CE-144 6.96E+07 6.96E+07 6.96E+07 6.96E+07 6.96E+07 6.96E+07 6.96E+07 B.05E+07 PR-143 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO PR-144 1.B3E+03 1.B3E+03 1.B3E+03 1.B3E+03 1.B3E+03 1.B3E+03 1.B3E+03 2.11E+03 ND-147 B.4BE+06 B.48E+06 B.4BE+06 B.4BE+06 B.4BE+06 B.4BE+06 B.4BE+06 1.02E+07 W-1B7 2.36E+06 2.36E+06 2.36E+06 2.36E+06 2.36E+06 2.36E+06 2.36E+06 2.74E+06 NP-239 1.71E+06 1.71E+06 1.71E+06 1.71E+06 1.71E+06 1.71E+06 1.71E+06 1.9BE+06 7-B

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 7-6 INHALATION EXPOSURE -INFANT AGE GROUP (RAI(IN)J)

Age Group: Infant Pathway: Inhalation Units: mrem/yr per J,lCi/m3 Nuclide Bone Liver Thyroid Kidney Lung Gi-LLi TBody Skin H-3 O.OOE+OO 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 O.OOE+OO C-14 2.6SE+04 S.31E+03 S.31E+03 S.31E+03 S.31E+03 S.31E+03 S.31E+03 O.OOE+OO NA-24 1.06E+04 1.06E+04 1.06E+04 1.06E+04 1.06E+04 1.06E+04 1.06E+04 O.OOE+OO P-32 2.03E+06 1.12E+OS O.OOE+OO O.OOE+OO O.OOE+OO 1.61E+04 7.74E+04 O.OOE+OO CR-S1 O.OOE+OO O.OOE+OO S.7SE+01 1.32E+01 1.28E+04 3.S7E+02 8.9SE+01 O.OOE+OO MN-S4 O.OOE+OO 2.S3E+04 O.OOE+OO 4.98E+03 1.00E+06 7.06E+03 4.98E+03 O.OOE+OO MN-S6 O.OOE+OO 1.S4E+OO O.OOE+OO 1.10E+OO 1.2SE+04 7.17E+04 2.21 E-01 O.OOE+OO FE-SS 1.97E+04 1.17E+04 O.OOE+OO O.OOE+OO 8.69E+04 1.09E+03 3.33E+03 O.OOE+OO FE-S9 1.36E+04 2.3SE+04 O.OOE+OO O.OOE+OO 1.02E+06 2.48E+04 9.48E+03 O.OOE+OO CO-S8 O.OOE+OO 1.22E+03 O.OOE+OO O.OOE+OO 7.77E+OS 1.11E+04 1.82E+03 O.OOE+OO CO-60 O.OOE+OO 8.02E+03 O.OOE+OO O.OOE+OO 4.S1E+06 3.19E+04 1.18E+04 O.OOE+OO NI-63 3.39E+OS 2.04E+04 O.OOE+OO O.OOE+OO 2.09E+OS 2.42E+03 1.16E+04 O.OOE+OO NI-6S 2.39E+OO 2.84E-01 O.OOE+OO O.OOE+OO 8.12E+03 S.01E+04 1.23E-01 O.OOE+OO CU-64 O.OOE+OO 1.88E+OO O.OOE+OO 3.98E+OO 9.30E+03 1.S0E+04 7.74E-01 O.OOE+OO ZN-6S 1.93E+04 6.26E+04 O.OOE+OO 3.2SE+04 6.47E+OS S.14E+04 3.11E+04 O.OOE+OO ZN-69 S.39E-02 9.67E-02 O.OOE+OO 4.02E-02 1.47E+03 1.32E+04 7.18E-03 O.OOE+OO BR-83 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.81E+02 O.OOE+OO BR-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.00E+02 O.OOE+OO BR-8S O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.04E+01 O.OOE+OO RB-86 O.OOE+OO 1.90E+OS O.OOE+OO O.OOE+OO O.OOE+OO 3.04E+03 8.82E+04 O.OOE+OO RB-88 O.OOE+OO S.S7E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.39E+02 2.87E+02 O.OOE+OO RB-89 O.OOE+OO 3.21E+02 O.OOE+OO O.OOE+OO O.OOE+OO 6.82E+01 2.06E+02 O.OOE+OO SR-89 3.98E+OS O.OOE+OO O.OOE+OO O.OOE+OO 2.03E+06 6.40E+04 1.14E+04 O.OOE+OO SR-90 4.09E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.12E+07 1.31E+OS 2.S9E+06 O.OOE+OO SR-91 9.S6E+01 O.OOE+OO O.OOE+OO O.OOE+OO S.26E+04 7.34E+04 3.46E+OO O.OOE+OO SR-92 1.0SE+01 O.OOE+OO O.OOE+OO O.OOE+OO 2.38E+04 1.40E+OS 3.91 E-01 O.OOE+OO Y-90 3.29E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.69E+OS 1.04E+OS 8.82E+01 O.OOE+OO Y-91M 4.07E-01 O.OOE+OO O.OOE+OO O.OOE+OO 2.79E+03 2.3SE+03 1.39E-02 O.OOE+OO Y-91 S.88E+OS O.OOE+OO O.OOE+OO O.OOE+OO 2.4SE+06 7.03E+04 1.S7E+04 O.OOE+OO Y-92 1.64E+01 O.OOE+OO O.OOE+OO O.OOE+OO 2.4SE+04 1.27E+OS 4.61E-01 O.OOE+OO Y-93 1.S0E+02 O.OOE+OO O.OOE+OO O.OOE+OO 7.64E+04 1.67E+OS 4.07E+OO O.OOE+OO ZR-9S 1.1SE+OS 2.79E+04 O.OOE+OO 3.11E+04 1.7SE+06 2.17E+04 2.03E+04 O.OOE+OO ZR-97 1.S0E+02 2.56E+01 O.OOE+OO 2.S9E+01 1.10E+OS 1.40E+OS 1.17E+01 O.OOE+OO NB-9S 1.S7E+04 6.43E+03 O.OOE+OO 4.72E+03 4.79E+OS 1.27E+04 3.78E+03 O.OOE+OO MO-99 O.OOE+OO 1.6SE+02 O.OOE+OO 2.6SE+02 1.3SE+OS 4.87E+04 3.23E+01 O.OOE+OO TC-99M 1.40E-03 2.88E-03 O.OOE+OO 3.11E-02 8.11E+02 2.03E+03 3.72E-02 O.OOE+OO TC-101 6.S1E-OS 8.23E-OS O.OOE+OO 9.79E-04 S.84E+02 8.44E+02 8.12E-04 O.OOE+OO RU-103 2.02E+03 O.OOE+OO O.OOE+OO 4.24E+03 S.S2E+OS 1.61 E+04 6.79E+02 O.OOE+OO RU-10S 1.22E+OO O.OOE+OO O.OOE+OO 8.99E-01 1.S7E+04 4.84E+04 4.10E-01 O.OOE+OO RU-106 8.68E+04 O.OOE+OO O.OOE+OO 1.07E+OS 1.16E+07 1.64E+OS 1.09E+04 O.OOE+OO AG-110M 9.98E+03 7.22E+03 O.OOE+OO 1.09E+04 3.67E+06 3.30E+04 S.OOE+03 O.OOE+OO 7-9

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29

~ge Group: Infant Pathway: Inhalation Units: mrem/yr per uCi/m3 Nuclide Bone Liver Thyroid Kidney Lung Gi-LLi TBody Skin TE-12SM 4.76E+03 1.99E+03 1.62E+03 O.OOE+OO 4.47E+OS 1.29E+04 6.S8E+02 O.OOE+OO TE-127M 1.67E+04 6.90E+03 4.87E+03 3.7SE+04 1.31E+06 2.73E+04 2.07E+03 O.OOE+OO TE-127 2.23E+00 9.S3E-01 1.8SE+00 4.86E+00 1.03E+04 2.44E+04 4.89E-01 O.OOE+OO TE-129M 1.41E+04 6.09E+03 S.47E+03 3.18E+04 1.68E+06 6.90E+04 2.23E+03 O.OOE+OO TE-129 7.88E-02 3.47E-02 6.7SE-02 1.7SE-01 3.00E+03 2.63E+04 1.88E-02 O.OOE+OO TE-131M 1.07E+02 S.SOE+01 8.93E+01 2.6SE+02 1.99E+OS 1.19E+OS 3.63E+01 O.OOE+OO TE-131 1.74E-02 8.22E-03 1.S8E-02 3.99E-02 2.06E+03 8.22E+03 S.00E-03 O.OOE+OO TE-132 3.72E+02 2.37E+02 2.79E+02 1.03E+03 3.40E+OS 4.41E+04 1.76E+02 O.OOE+OO 1-130 6.36E+03 1.39E+04 1.60E+06 1.S3E+04 O.OOE+OO 1.99E+03 S.S7E+03 O.OOE+OO 1-131 3.79E+04 4.44E+04 1.48E+07 S.18E+04 O.OOE+OO 1.06E+03 1.96E+04 O.OOE+OO 1-132 1.69E+03 3.S4E+03 1.69E+OS 3.9SE+03 O.OOE+OO 1.90E+03 1.26E+03 O.OOE+OO 1-133 1.32E+04 1.92E+04 3.S6E+06 2.24E+04 O.OOE+OO 2.16E+03 S.60E+03 O.OOE+OO 1-134 9.21E+02 1.88E+03 4.4SE+04 2.09E+03 O.OOE+OO 1.29E+03 6.6SE+02 O.OOE+OO 1-13S 3.86E+03 7.60E+03 6.96E+OS 8.47E+03 O.OOE+OO 1.83E+03 2.77E+03 O.OOE+OO CS-134 3.96E+OS 7.03E+OS O.OOE+OO 1.90E+OS 7.97E+04 1.33E+03 7.4SE+04 O.OOE+OO CS-136 4.83E+04 1.3SE+OS O.OOE+OO S.64E+04 1.18E+04 1.43E+03 S.29E+04 O.OOE+OO CS-137 5.49E+OS 6.12E+OS O.OOE+OO 1.72E+OS 7.13E+04 1.33E+03 4.SSE+04 O.OOE+OO CS-138 5.0SE+02 7.81E+02 O.OOE+OO 4.10E+02 6.S4E+01 8.76E+02 3.98E+02 O.OOE+OO BA-139 1.48E+00 9.84E-04 O.OOE+OO S.92E-04 S.9SE+03 S.10E+04 4.30E-02 O.OOE+OO BA-140 S.60E+04 S.60E+01 O.OOE+OO 1.34E+01 1.60E+06 3.84E+04 2.90E+03 O.OOE+OO BA-141 1.S7E-01 1.08E-04 O.OOE+OO 6.S0E-OS 2.97E+03 4.7SE+03 4.97E-03 O.OOE+OO BA-142 3.98E-02 3.30E-OS O.OOE+OO 1.90E-OS 1.SSE+03 6.93E+02 1.96E-03 O.OOE+OO LA-140 S.OSE+02 2.00E+02 O.OOE+OO O.OOE+OO 1.68E+OS 8.48E+04 S.1SE+01 O.OOE+OO LA-142 1.03E+00 3.77E-01 O.OOE+OO O.OOE+OO 8.22E+03 S.9SE+04 9.04E-02 O.OOE+OO CE-141 2.77E+04 1.67E+04 O.OOE+OO S.2SE+03 S.17E+OS 2.16E+04 1.99E+03 O.OOE+OO CE-143 2.93E+02 1.93E+02 O.OOE+OO S.64E+01 1.16E+OS 4.97E+04 2.21E+01 O.OOE+OO CE-144 3.19E+06 1.21E+06 O.OOE+OO S.38E+OS 9.84E+06 1.48E+OS 1.76E+OS O.OOE+OO PR-143 1.40E+04 S.24E+03 O.OOE+OO 1.97E+03 4.33E+OS 3.72E+04 6.99E+02 O.OOE+OO PR-144 4.79E-02 1.8SE-02 O.OOE+OO 6.72E-03 1.61E+03 4.28E+03 2.41 E-03 O.OOE+OO NO-147 7.94E+03 8.13E+03 O.OOE+OO 3.1SE+03 3.22E+OS 3.12E+04 S.00E+02 O.OOE+OO W-187 1.30E+01 9.02E+00 O.OOE+OO O.OOE+OO 3.96E+04 3.S6E+04 3.12E+00 O.OOE+OO NP-239 3.71E+02 2.98E+02 O.OOE+OO 6.62E+01 S.9SE+04 2.49E+04 1.88E+01 O.OOE+OO 7-10

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 7-7 INHALATION EXPOSURE - CHILD AGE GROUP (RAI(IN)J)

Age Group: Child Pathway: Inhalation Units: mrem/yr per IJCi/m 3 Nuclide Bone Liver Thyroid Kidney Lung Gi-LLi TBody Skin H-3 O.OOE+OO 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 O.OOE+OO C-14 3.S9E+04 6.73E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03 O.OOE+OO NA-24 1.61E+04 1.61E+04 1.61E+04 1.61E+04 1.61E+04 1.61 E+04 1.61 E+04 O.OOE+OO P-32 2.60E+06 1.14E+OS O.OOE+OO O.OOE+OO O.OOE+OO 4.22E+04 9.8BE+04 O.OOE+OO CR-S1 O.OOE+OO O.OOE+OO 8.SSE+01 2.43E+01 1.70E+04 1.0BE+03 1.S4E+02 O.OOE+OO MN-S4 O.OOE+OO 4.29E+04 O.OOE+OO 1.00E+04 1.S8E+06 2.29E+04 9.S1E+03 O.OOE+OO MN-S6 O.OOE+OO 1.66E+00 O.OOE+OO 1.67E+00 1.31E+04 1.23E+OS 3.12E-01 O.OOE+OO FE-55 4.74E+04 2.S2E+04 O.OOE+OO O.OOE+OO 1.11E+OS 2.B7E+03 7.77E+03 O.OOE+OO FE-59 2.07E+04 3.34E+04 O.OOE+OO O.OOE+OO 1.27E+06 7.07E+04 1.67E+04 O.OOE+OO CO-SB O.OOE+OO 1.77E+03 O.OOE+OO O.OOE+OO 1.11E+06 3.44E+04 3.16E+03 O.OOE+OO CO-60 O.OOE+OO 1.31E+04 O.OOE+OO O.OOE+OO 7.07E+06 9.62E+04 2.26E+04 O.OOE+OO NI-63 B.21E+OS 4.63E+04 O.OOE+OO O.OOE+OO 2.7SE+OS 6.33E+03 2.80E+04 O.OOE+OO NI-6S 2.99E+00 2.96E-01 O.OOE+OO O.OOE+OO 8.1BE+03 B.40E+04 1.64E-01 O.OOE+OO CU-64 O.OOE+OO 1.99E+00 O.OOE+OO 6.03E+00 9.SBE+03 3.67E+04 1.07E+00 O.OOE+OO ZN-6S 4.26E+04 1.13E+OS O.OOE+OO 7.14E+04 9.9SE+OS 1.63E+04 7.03E+04 O.OOE+OO ZN-69 6.70E-02 9.66E-02 O.OOE+OO S.BSE-02 1.42E+03 1.02E+04 B.92E-03 O.OOE+OO BR-83 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.74E+02 O.OOE+OO BR-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO S.4BE+02 O.OOE+OO BR-8S O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.S3E+01 O.OOE+OO RB-86 O.OOE+OO 1.9BE+OS O.OOE+OO O.OOE+OO O.OOE+OO 7.99E+03 1.14E+OS O.OOE+OO RB-88 O.OOE+OO S.62E+02 O.OOE+OO O.OOE+OO . O.OOE+OO 1.72E+01 3.66E+02 O.OOE+OO RB-B9 O.OOE+OO 3.4SE+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.B9E+00 2.90E+02 O.OOE+OO SR-B9 S.99E+OS O.OOE+OO O.OOE+OO O.OOE+OO 2.16E+06 1.67E+OS 1.72E+04 O.OOE+OO SR-90 1.01 E+OB O.OOE+OO O.OOE+OO O.OOE+OO 1.48E+07 3.43E+OS 6.44E+06 O.OOE+OO SR-91 1.21E+02 O.OOE+OO O.OOE+OO O.OOE+OO S.33E+04 1.74E+OS 4.S9E+00 O.OOE+OO SR-92 1.31E+01 O.OOE+OO O.OOE+OO O.OOE+OO 2.40E+04 2.42E+OS S.2SE-01 O.OOE+OO Y-90 4.11E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.62E+OS 2.68E+OS 1.11E+02 O.OOE+OO Y-91M S.07E-01 O.OOE+OO O.OOE+OO O.OOE+OO 2.81E+03 1.72E+03 1.84E-02 O.OOE+OO Y-91 9.14E+OS O.OOE+OO O.OOE+OO O.OOE+OO 2.63E+06 1.84E+OS 2.44E+04 O.OOE+OO Y-92 2.04E+01 O.OOE+OO O.OOE+OO O.OOE+OO 2.39E+04 2.39E+OS S.81E-01 O.OOE+OO Y-93 1.86E+02 O.OOE+OO O.OOE+OO O.OOE+OO 7.44E+04 3.89E+OS S.11E+00 O.OOE+OO ZR-9S 1.90E+OS 4.18E+04 O.OOE+OO S.96E+04 2.23E+06 6.11E+04 3.70E+04 O.OOE+OO ZR-97 1.88E+02 2.72E+01 O.OOE+OO 3.89E+01 1.13E+OS 3.S1E+OS 1.60E+01 O.OOE+OO NB-9S 2.3SE+04 9.18E+03 O.OOE+OO 8.62E+03 6.14E+OS 3.70E+04 6.SSE+03 O.OOE+OO MO-99 O.OOE+OO 1.72E+02 O.OOE+OO 3.92E+02 1.3SE+OS 1.27E+OS 4.26E+01 O.OOE+OO TC-99M 1.78E-03 3.48E-03 O.OOE+OO S.07E-02 9.S1E+02 4.81E+03 S.77E-02 O.OOE+OO TC-101 B.10E-OS 8.S1E-OS O.OOE+OO 1.4SE-03 S.8SE+02 1.63E+01 1.0BE-03 O.OOE+OO RU-103 2.79E+03 O.OOE+OO O.OOE+OO 7.03E+03 6.62E+OS 4.48E+04 1.07E+03 O.OOE+OO RU-10S 1.S3E+00 O.OOE+OO O.OOE+OO 1.34E+00 1.S9E+04 9.9SE+04 S.SSE-01 O.OOE+OO RU-106 1.36E+OS O.OOE+OO O.OOE+OO 1.B4E+OS 1.43E+07 4.29E+OS 1.69E+04 O.OOE+OO AG-110M 1.69E+04 1.14E+04 O.OOE+OO 2.12E+04 S.4BE+06 1.00E+OS 9.14E+03 O.OOE+OO 7-11

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Age Group: Child Pathway: Inhalation Units: mrem/yr per IJCi/m3 Nuclide Bone Liver Thyroid Kidney Lung Gi-LLi TBody Skin TE-12SM 6.73E+03 2.33E+03 1.92E+03 O.OOE+OO 4.77E+OS 3.38E+04 9.14E+02 O.OOE+OO TE-127M 2.49E+04 8.SSE+03 6.07E+03 6.36E+04 1.48E+06 7.14E+04 3.02E+03 O.OOE+OO TE-127 2.77E+00 9.S1E-01 1.96E+00 7.07E+00 1.00E+04 S.62E+04 6.11E-01 O.OOE+OO TE-129M 1.92E+04 6.8SE+03 6.33E+03 S.03E+04 1.76E+06 1.82E+OS 3.04E+03 O.OOE+OO TE-129 9.77E-02 3.S0E-02 7.14E-02 2.S7E-01 2.93E+03 2.SSE+04 2.38E-02 O.OOE+OO TE-131M 1.34E+02 S.92E+01 9.77E+01 4.00E+02 2.06E+OS 3.08E+OS S.07E+01 O.OOE+OO TE-131 2.17E-02 8.44E-03 1.70E-02 S.88E-02 2.0SE+03 1.33E+03 6.S9E-03 O.OOE+OO TE-132 4.81E+02 2.72E+02 3.17E+02 1.77E+03 3.77E+OS 1.38E+OS 2.63E+02 O.OOE+OO 1-130 8.18E+03 1.64E+04 1.8SE+06 2.4SE+04 O.OOE+OO S.11E+03 8.44E+03 O.OOE+OO 1-131 4.81E+04 4.81E+04 1.62E+07 7.88E+04 O.OOE+OO 2.84E+03 2.73E+04 O.OOE+OO 1-132 2.12E+03 4.07E+03 1.94E+OS 6.2SE+03 O.OOE+OO 3.20E+03 1.88E+03 O.OOE+OO 1-133 1.66E+04 2.03E+04 3.8SE+06 3.38E+04 O.OOE+OO S.48E+03 7.70E+03 O.OOE+OO 1-134 1.17E+03 2.16E+03 S.07E+04 3.30E+03 O.OOE+OO 9.SSE+02 9.9SE+02 O.OOE+OO 1-13S 4.92E+03 8.73E+03 7.92E+OS 1.34E+04 O.OOE+OO 4.44E+03 4.14E+03 O.OOE+OO CS-134 6.S1E+OS 1.01E+06 O.OOE+OO 3.30E+OS 1.21 E+OS 3.8SE+03 2.2SE+OS O.OOE+OO CS-136 6.S1E+04 1.71E+OS O.OOE+OO 9.SSE+04 1.4SE+04 4.18E+03 1.16E+OS O.OOE+OO CS-137 9.07E+OS 8.2SE+OS O.OOE+OO 2.82E+OS 1.04E+OS 3.62E+03 1.28E+OS O.OOE+OO CS-138 6.33E+02 8.40E+02 O.OOE+OO 6.22E+02 6.81E+01 2.70E+02 S.SSE+02 O.OOE+OO BA-139 1.84E+00 9.84E-04 O.OOE+OO 8.62E-04 S.77E+03 S.77E+04 S.37E-02 O.OOE+OO BA-140 7.40E+04 6.48E+01 O.OOE+OO 2.11E+01 1.74E+06 1.02E+OS 4.33E+03 O.OOE+OO BA-141 1.96E-01 1.09E-04 O.OOE+OO 9.47E-OS 2.92E+03 2.7SE+02 6.36E-03 O.OOE+OO BA-142 S.OOE-02 3.60E-OS O.OOE+OO 2.91E-OS 1.64E+03 2.74E+OO 2.79E-03 O.OOE+OO LA-140 6.44E+02 2.2SE+02 O.OOE+OO O.OOE+OO 1.83E+OS 2.26E+OS 7.SSE+01 O.OOE+OO LA-142 1.30E+OO 4.11 E-01 O.OOE+OO O.OOE+OO 8.70E+03 7.S9E+04 1.29E-01 O.OOE+OO CE-141 3.92E+04 1.9SE+04 O.OOE+OO 8.SSE+03 S.44E+OS S.66E+04 2.90E+03 O.OOE+OO CE-143 3.66E+02 1.99E+02 O.OOE+OO 8.36E+01 1.1SE+OS 1.27E+OS 2.87E+01 O.OOE+OO CE-144 6.77E+06 2.12E+06 O.OOE+OO 1.17E+06 1.20E+07 3.89E+OS 3.61E+OS O.OOE+OO PR-143 1.8SE+04 S.SSE+03 O.OOE+OO 3.00E+03 4.33E+OS 9.73E+04 9.14E+02 O.OOE+OO PR-144 S.96E-02 1.8SE-02 O.OOE+OO 9.77E-03 1.S7E+03 1.97E+02 3.00E-03 O.OOE+OO ND-147 1.08E+04 8.73E+03 O.OOE+OO 4.81E+03 3.28E+OS 8.21E+04 6.81E+02 O.OOE+OO W-187 1.63E+01 9.66E+OO O.OOE+OO O.OOE+OO 4.11E+04 9.10E+04 4.33E+OO O.OOE+OO NP-239 4.66E+02 3.01E+02 O.OOE+OO 9.73E+01 S.81E+04 6.40E+04 2.3SE+01 O.OOE+OO 7-12

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 7-8 INHALATION EXPOSURE - TEEN AGE GROUP (RA1(IN)J)

Age Group: Teen Pathway: Inhalation Units: mrem/yr per ~Ci/m3 Nuclide Bone Liver Thyroid Kidney Lung Gi-LLi TBody Skin H-3 O.OOE+OO 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 O.OOE+OO C-14 2.60E+04 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 O.OOE+OO NA-24 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 O.OOE+OO P-32 1.89E+06 1.10E+OS O.OOE+OO O.OOE+OO O.OOE+OO 9.28E+04 7.16E+04 O.OOE+OO CR-S1 O.OOE+OO O.OOE+OO 7.S0E+01 3.07E+01 2.10E+04 3.00E+03 1.3SE+02 O.OOE+OO MN-S4 O.OOE+OO S.11 E+04 O.OOE+OO 1.27E+04 1.98E+06 6.68E+04 8.40E+03 O.OOE+OO MN-S6 O.OOE+OO 1.70E+OO O.OOE+OO 1.79E+OO 1.S2E+04 S.74E+04 2.S2E-01 O.OOE+OO FE-SS 3.34E+04 2.38E+04 O.OOE+OO O.OOE+OO 1.24E+OS 6.39E+03 S.S4E+03 O.OOE+OO FE-S9 1.S9E+04 3.70E+04 O.OOE+OO O.OOE+OO 1.S3E+06 1.78E+OS 1.43E+04 O.OOE+OO CO-S8 O.OOE+OO 2.07E+03 O.OOE+OO O.OOE+OO 1.34E+06 9.S2E+04 2.78E+03 O.OOE+OO CO-60 O.OOE+OO 1.S1E+04 O.OOE+OO O.OOE+OO 8.72E+06 2.S9E+OS 1.98E+04 O.OOE+OO NI-63 S.80E+OS 4.34E+04 O.OOE+OO O.OOE+OO 3.07E+OS 1.42E+04 1.98E+04 O.OOE+OO NI-6S 2.18E+OO 2.93E-01 O.OOE+OO O.OOE+OO 9.36E+03 3.67E+04 1.27E-01 O.OOE+OO CU-64 O.OOE+OO 2.03E+OO O.OOE+OO 6.41E+OO 1.11E+04 6.14E+04 8.48E-01 O.OOE+OO ZN-6S 3.86E+04 1.34E+OS O.OOE+OO 8.64E+04 1.24E+06 4.66E+04 6.24E+04 O.OOE+OO ZN-69 4.83E-02 9.20E-02 O.OOE+OO 6.02E-02 1.S8E+03 2.8SE+02 6.46E-03 O.OOE+OO BR-83 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.44E+02 O.OOE+OO BR-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.33E+02 O.OOE+OO BR-8S O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.83E+01 O.OOE+OO RB-86 O.OOE+OO 1.90E+OS O.OOE+OO O.OOE+OO O.OOE+OO 1.77E+04 8.40E+04 O.OOE+OO RB-88 O.OOE+OO S.46E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.92E-OS 2.72E+02 O.OOE+OO RB-89 O.OOE+OO 3.S2E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.38E-07 2.33E+02 O.OOE+OO SR-89 4.34E+OS O.OOE+OO O.OOE+OO O.OOE+OO 2.42E+06 3.71E+OS 1.2SE+04 O.OOE+OO SR-90 1.08E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.6SE+07 7.6SE+OS 6.68E+06 O.OOE+OO SR-91 8.80E+01 O.OOE+OO O.OOE+OO O.OOE+OO ' 6.07E+04 2.S9E+OS 3.S1E+OO O.OOE+OO SR-92 9.S2E+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.74E+04 1.19E+OS 4.06E-01 O.OOE+OO Y-90 2.98E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.93E+OS S.S9E+OS 8.00E+01 O.OOE+OO Y-91M 3.70E-01 O.OOE+OO O.OOE+OO O.OOE+OO 3.20E+03 3.02E+01 1.42E-02 O.OOE+OO Y-91 6.61E+OS O.OOE+OO O.OOE+OO O.OOE+OO 2.94E+06 4.09E+OS 1.77E+04 O.OOE+OO Y-92 1.47E+01 O.OOE+OO O.OOE+OO O.OOE+OO 2.68E+04 1.6SE+OS 4.29E-01 O.OOE+OO Y-93 1.3SE+02 O.OOE+OO O.OOE+OO O.OOE+OO 8.32E+04 S.79E+OS 3.72E+OO O.OOE+OO ZR-9S 1.46E+OS 4.S8E+04 O.OOE+OO 6.74E+04 2.69E+06 1.49E+OS 3.1SE+04 O.OOE+OO ZR-97 1.38E+02 2.72E+01 O.OOE+OO 4.12E+01 1.30E+OS 6.30E+OS 1.26E+01 O.OOE+OO NB-9S 1.86E+04 1.03E+04 O.OOE+OO 1.00E+04 7.S1E+OS 9.68E+04 S.66E+03 O.OOE+OO MO-99 O.OOE+OO 1.69E+02 O.OOE+OO 4.11 E+02 1.S4E+OS 2.69E+OS 3.22E+01 O.OOE+OO TC-99M 1.38E-03 3.86E-03 O.OOE+OO S.76E-02 1.1SE+03 6.13E+03 4.99E-02 O.OOE+OO TC-101 S.92E-OS 8.40E-OS O.OOE+OO 1.S2E-03 6.67E+02 8.72E-07 8.24E-04 O.OOE+OO RU-103 2.10E+03 O.OOE+OO O.OOE+OO 7.43E+03 7.83E+OS 1.09E+OS 8.96E+02 O.OOE+OO RU-10S 1.12E+OO O.OOE+OO O.OOE+OO 1.41E+OO 1.82E+04 9.04E+04 4.34E-01 O.OOE+OO RU-106 9.84E+04 O.OOE+OO O.OOE+OO 1.90E+OS 1.61E+07 9.60E+OS 1.24E+04 O.OOE+OO AG-110M 1.38E+04 1.31E+04 O.OOE+OO 2.S0E+04 6.7SE+06 2.73E+OS 7.99E+03 O.OOE+OO 7-13

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Age Group: Teen Pathway: Inhalation Units: mrem/yr per J,lCi/m3 Nuclide Bone Liver Thyroid Kidney Lung Gi-LLi TBody Skin TE-12SM 4.88E+03 2.24E+03 1.40E+03 O.OOE+OO S.36E+OS 7.S0E+04 6.67E+02 O.OOE+OO TE-127M 1.80E+04 8.16E+03 4.38E+03 6.S4E+04 1.66E+06 1.S9E+OS 2.18E+03 O.OOE+OO TE-127 2.01E+00 9.12E-01 1.42E+00 7.28E+00 1.12E+04 8.08E+04 4.42E-01 O.OOE+OO TE-129M 1.39E+04 6.S8E+03 4.S8E+03 S.19E+04 1.98E+06 4.0SE+OS 2.2SE+03 O.OOE+OO TE-129 7.10E-02 3.38E-02 S.18E-02 2.66E-01 3.30E+03 1.62E+03 1.76E-02 O.OOE+OO TE-131M 9.84E+01 6.01E+01 7.2SE+01 4.39E+02 2.38E+OS 6.21E+OS 4.02E+01 O.OOE+OO TE-131 1.S8E-02 8.32E-03 1.24E-02 6.18E-02 2.34E+03 1.S1E+01 S.04E-03 O.OOE+OO TE-132 3.60E+02 2.90E+02 2.46E+02 1.9SE+03 4.49E+OS 4.63E+OS 2.19E+02 O.OOE+OO 1-130 6.24E+03 1.79E+04 1.49E+06 2.7SE+04 O.OOE+OO 9.12E+03 7.17E+03 O.OOE+OO 1-131 3.S4E+04 4.91E+04 1.46E+07 8.40E+04 O.OOE+OO 6.49E+03 2.64E+04 O.OOE+OO 1-132 1.S9E+03 4.38E+03 1.S1E+OS 6.92E+03 O.OOE+OO 1.27E+03 1.S8E+03 O.OOE+OO 1-133 1.22E+04 2.0SE+04 2.92E+06 3.S9E+04 O.OOE+OO 1.03E+04 6.22E+03 O.OOE+OO 1-134 8.88E+02 2.32E+03 3.9SE+04 3.66E+03 O.OOE+OO 2.04E+01 8.40E+02 O.OOE+OO 1-13S 3.70E+03 9.44E+03 6.21E+OS 1.49E+04 O.OOE+OO 6.9SE+03 3.49E+03 O.OOE+OO CS-134 S.02E+OS 1.13E+06 O.OOE+OO 3.7SE+OS 1.46E+OS 9.76E+03 S.49E+OS O.OOE+OO CS-136 S.1SE+04 1.94E+OS O.OOE+OO 1.10E+OS 1.78E+04 1.09E+04 1.37E+OS O.OOE+OO CS-137 6.70E+OS 8.48E+OS O.OOE+OO 3.04E+OS 1.21E+OS 8.48E+03 3.11E+OS O.OOE+OO CS-138 4.66E+02 8.S6E+02 O.OOE+OO 6.62E+02 7.87E+01 2.70E-01 4.46E+02 O.OOE+OO BA-139 1.34E+00 9.44E-04 O.OOE+OO 8.88E-04 6.46E+03 6.4SE+03 3.90E-02 O.OOE+OO BA-140 S.47E+04 6.70E+01 O.OOE+OO 2.28E+01 2.03E+06 2.29E+OS 3.S2E+03 O.OOE+OO BA-141 1.42E-01 1.06E-04 O.OOE+OO 9.84E-OS 3.29E+03 7.46E-04 4.74E-03 O.OOE+OO BA-142 3.70E-02 3.70E-OS O.OOE+OO 3.14E-OS 1.91E+03 4.79E-10 2.27E-03 O.OOE+OO LA-140 4.79E+02 2.36E+02 O.OOE+OO O.OOE+OO 2.14E+OS 4.87E+OS 6.26E+01 O.OOE+OO LA-142 9.60E-01 4.2SE-01 O.OOE+OO O.OOE+OO 1.02E+04 1.20E+04 1.06E-01 O.OOE+OO CE-141 2.84E+04 1.90E+04 O.OOE+OO 8.88E+03 6.14E+OS 1.26E+OS 2.17E+03 O.OOE+OO CE-143 2.66E+02 1.94E+02 O.OOE+OO 8.64E+01 1.30E+OS 2.SSE+OS 2.16E+01 O.OOE+OO CE-144 4.89E+06 2.02E+06 O.OOE+OO 1.21E+06 1.34E+07 8.64E+OS 2.62E+OS O.OOE+OO PR-143 1.34E+04 S.31E+03 O.OOE+OO 3.09E+03 4.83E+OS 2.14E+OS 6.62E+02 O.OOE+OO PR-144 4.30E-02 1.76E-02 O.OOE+OO 1.01E-02 1.7SE+03 2.3SE-04 2.18E-03 O.OOE+OO ND-147 7.86E+03 8.S6E+03 O.OOE+OO S.02E+03 3.72E+OS 1.82E+OS S.13E+02 O.OOE+OO W-187 1.20E+01 9.76E+00 O.OOE+OO O.OOE+OO 4.74E+04 1.77E+OS 3.43E+OO O.OOE+OO NP-239 3.38E+02 2.88E+02 O.OOE+OO 1.00E+02 6.49E+04 1.32E+OS 1.77E+01 O.OOE+OO 7-14

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 7-9 INHALATION EXPOSURE - ADULT AGE GROUP (RA1(IN)J)

Age Group: Adult Pathway: Inhalation Units: mrem/yr per ~Ci/m3 Nuclide Bone Liver Thyroid Kidney Lung Gi-LLi TBody Skin H-3 O.OOE+OO 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 O.OOE+OO C-14 1.82E+04 3.41E+03 3.41E+03 3.41E+03 3.41E+03 3.41E+03 3.41E+03 O.OOE+OO NA-24 1.02E+04 1.02E+04 1.02E+04 1.02E+04 1.02E+04 1.02E+04 1.02E+04 O.OOE+OO P-32 1.32E+06 7.71E+04 O.OOE+OO O.OOE+OO O.OOE+OO 8.64E+04 S.01E+04 O.OOE+OO CR-S1 O.OOE+OO O.OOE+OO S.9SE+01 2.28E+01 1.44E+04 3.32E+03 1.00E+02 O.OOE+OO MN-S4 O.OOE+OO 3.96E+04 O.OOE+OO 9.84E+03 1.40E+06 7.74E+04 6.30E+03 O.OOE+OO MN-S6 O.OOE+OO 1.24E+OO O.OOE+OO 1.30E+OO 9.44E+03 2.02E+04 1.83E-01 O.OOE+OO FE-SS 2.46E+04 1.70E+04 O.OOE+OO O.OOE+OO 7.21E+04 6.03E+03 3.94E+03 O.OOE+OO FE-S9 1.18E+04 2.78E+04 O.OOE+OO O.OOE+OO 1.02E+06 1.88E+OS 1.06E+04 O.OOE+OO CO-S8 O.OOE+OO 1.S8E+03 O.OOE+OO O.OOE+OO 9.28E+OS 1.06E+OS 2.07E+03 O.OOE+OO CO-60 O.OOE+OO 1.1SE+04 O.OOE+OO O.OOE+OO S.97E+06 2.8SE+OS 1.48E+04 O.OOE+OO NI-63 4.32E+OS 3.14E+04 O.OOE+OO O.OOE+OO 1.78E+OS 1.34E+04 1.4SE+04 O.OOE+OO NI-6S 1.S4E+OO 2.10E-01 O.OOE+OO O.OOE+OO S.60E+03 1.23E+04 9.12E-02 O.OOE+OO CU-64 O.OOE+OO 1.46E+OO O.OOE+OO 4.62E+OO 6.78E+03 4.90E+04 6.1SE-01 O.OOE+OO ZN-6S 3.24E+04 1.03E+OS O.OOE+OO 6.90E+04 8.64E+OS S.34E+04 4.66E+04 O.OOE+OO ZN-69 3.38E-02 6.S1E-02 O.OOE+OO 4.22E-02 9.20E+02 1.63E+01 4.S2E-03 O.OOE+OO BR-83 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.32E+02 2.41E+02 O.OOE+OO BR-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.64E-03 3.13E+02 O.OOE+OO BR-8S O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.28E+01 O.OOE+OO RB-86 O.OOE+OO 1.3SE+OS O.OOE+OO O.OOE+OO O.OOE+OO 1.66E+04 S.90E+04 O.OOE+OO RB-88 O.OOE+OO 3.87E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.34E-09 1.93E+02 O.OOE+OO RB-89 O.OOE+OO 2.S6E+02 O.OOE+OO O.OOE+OO O.OOE+OO 9.28E-12 1.70E+02 O.OOE+OO SR-89 3.04E+OS O.OOE+OO O.OOE+OO O.OOE+OO 1.40E+06 3.S0E+OS 8.72E+03 O.OOE+OO SR-90 9.92E+07 O.OOE+OO O.OOE+OO O.OOE+OO 9.60E+06 7.22E+OS 6.10E+06 O.OOE+OO SR-91 6.19E+01 O.OOE+OO O.OOE+OO O.OOE+OO 3.6SE+04 1.91E+OS 2.S0E+OO O.OOE+OO SR-92 6.74E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.6SE+04 4.30E+04 2.91 E-01 O.OOE+OO Y-90 2.09E+03 O.OOE+OO O.OOE+OO O.OOE+OO 1.70E+OS S.06E+OS S.61E+01 O.OOE+OO Y-91M 2.61E-01 O.OOE+OO O.OOE+OO O.OOE+OO 1.92E+03 1.33E+OO 1.02E-02 O.OOE+OO Y-91 4.62E+OS O.OOE+OO O.OOE+OO O.OOE+OO 1.70E+06 3.8SE+OS 1.24E+04 O.OOE+OO Y-92 1.03E+01 O.OOE+OO O.OOE+OO O.OOE+OO 1.S7E+04 7.3SE+04 3.02E-01 O.OOE+OO Y-93 9.44E+01 O.OOE+OO O.OOE+OO O.OOE+OO 4.8SE+04 4.22E+OS 2.61E+OO O.OOE+OO ZR-9S 1.07E+OS 3.44E+04 O.OOE+OO S.42E+04 1.77E+06 1.S0E+OS 2.33E+04 O.OOE+OO ZR-97 9.68E+01 1.96E+01 O.OOE+OO 2.97E+01 7.87E+04 S.23E+OS 9.04E+OO O.OOE+OO NB-9S 1.41E+04 7.82E+03 O.OOE+OO 7.74E+03 S.OSE+OS 1.04E+OS 4.21E+03 O.OOE+OO MO-99 O.OOE+OO 1.21 E+02 O.OOE+OO 2.91E+02 9.12E+04 2.48E+OS 2.30E+01 O.OOE+OO TC-99M 1.03E-03 2.91E-03 O.OOE+OO 4.42E-02 7.64E+02 4.16E+03 3.70E-02 O.OOE+OO TC-101 4.18E-OS 6.02E-OS O.OOE+OO 1.08E-03 3.99E+02 1.09E-11 S.90E-04 O.OOE+OO RU-103 1.S3E+03 O.OOE+OO O.OOE+OO S.83E+03 S.OSE+OS 1.10E+OS 6.S8E+02 O.OOE+OO RU-10S 7.90E-01 O.OOE+OO O.OOE+OO 1.02E+OO 1.10E+04 4.82E+04 3.11E-01 O.OOE+OO RU-106 6.91E+04 O.OOE+OO O.OOE+OO 1.34E+OS 9.36E+06 9.12E+OS 8.72E+03 O.OOE+OO AG-110M 1.08E+04 1.00E+04 O.OOE+OO 1.97E+04 4.63E+06 3.02E+OS S.94E+03 O.OOE+OO 7-15

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Age Group: Adult Pathway: Inhalation Units: rnrern/yr per !-ICi/rn3 Nuclide Bone Liver Thyroid Kidney LUll9 Gi-LLi TBody_ Skin TE-12SM 3.42E+03 1.S8E+03 1.0SE+03 1.24E+04 3.14E+OS 7.06E+04 4.67E+02 O.OOE+OO TE-127M 1.26E+04 S.77E+03 3.29E+03 4.S8E+04 9.60E+OS 1.S0E+OS 1.S7E+03 O.OOE+OO TE-127 1.40E+00 6.42E-01 1.06E+00 S.10E+00 6.S1E+03 S.74E+04 3.10E-01 O.OOE+OO TE-129M 9.76E+03 4.67E+03 3.44E+03 3.66E+04 1.16E+06 3.83E+OS 1.S8E+03 O.OOE+OO TE-129 4.98E-02 2.39E-02 3.90E-02 1.87E-01 1.94E+03 1.S7E+02 1.24E-02 O.OOE+OO TE-131M 6.99E+01 4.36E+01 S.SOE+01 3.09E+02 1.46E+OS S.S6E+OS 2.90E+01 O.OOE+OO TE-131 1.11 E-02 S.9SE-03 9.36E-03 4.37E-02 1.39E+03 1.84E+01 3.S9E-03 O.OOE+OO TE-132 2.60E+02 2.1SE+02 1.90E+02 1.46E+03 2.88E+OS S.10E+OS 1.62E+02 O.OOE+OO 1-130 4.S8E+03 1.34E+04 1.14E+06 2.09E+04 O.OOE+OO 7.69E+03 S.28E+03 O.OOE+OO 1-131 2.S2E+04 3.S8E+04 1.19E+07 6.13E+04 O.OOE+OO 6.28E+03 2.0SE+04 O.OOE+OO 1-132 1.16E+03 3.26E+03 1.14E+OS S.18E+03 O.OOE+OO 4.06E+02 1.16E+03 O.OOE+OO 1-133 8.64E+03 1.48E+04 2.1SE+06 2.S8E+04 O.OOE+OO 8.88E+03 4.S2E+03 O.OOE+OO 1-134 6.44E+02 1.73E+03 2.98E+04 2.7SE+03 O.OOE+OO 1.01E+00 6.1SE+02 O.OOE+OO 1":135 2.68E+03 6.98E+03 4.48E+OS 1.11E+04 O.OOE+OO S.2SE+03 2.S7E+03 O.OOE+OO CS-134 3.73E+OS B.4BE+OS O.OOE+OO 2.87E+OS 9.76E+04 1.04E+04 7.28E+OS O.OOE+OO CS-136 3.90E+04 1.46E+OS O.OOE+OO B.S6E+04 1.20E+04 1.17E+04 1.10E+OS O.OOE+OO CS-137 4.7BE+OS 6.21E+OS O.OOE+OO 2.22E+OS 7.S2E+04 8.40E+03 4.2BE+OS O.OOE+OO CS-138 3.31E+02 6.21E+02 O.OOE+OO 4.BOE+02 4.86E+01 1.86E-03 3.24E+02 O.OOE+OO BA-139 9.36E-01 6.66E-04 O.OOE+OO 6.22E-04 3.76E+03 B.96E+02 2.74E-02 O.OOE+OO BA-140 3.90E+04 4.90E+01 O.OOE+OO 1.67E+01 1.27E+06 2.1BE+OS 2.S7E+03 O.OOE+OO BA-141 1.00E-01 7.S3E-OS O.OOE+OO 7.00E-OS 1.94E+03 1.16E-07 3.36E-03 O.OOE+OO BA-142 2.63E-02 2.70E-OS O.OOE+OO 2.29E-OS 1.19E+03 1.S7E-16 1.66E-03 O.OOE+OO LA-140 3.44E+02 1.74E+02 O.OOE+OO O.OOE+OO 1.36E+OS 4.SBE+OS 4.SBE+01 O.OOE+OO LA-142 6.B3E-01 3.10E-01 O.OOE+OO O.OOE+OO 6.33E+03 2.11E+03 7.72E-02 O.OOE+OO CE-141 1.99E+04 1.3SE+04 O.OOE+OO 6.26E+03 3.62E+OS 1.20E+OS 1.S3E+03 O.OOE+OO CE-143 1.B6E+02 1.3BE+02 O.OOE+OO 6.0BE+01 7.9BE+04 2.26E+OS 1.S3E+01 O.OOE+OO CE-144 3.43E+06 1.43E+06 O.OOE+OO 8.48E+OS 7.7BE+06 8.16E+OS 1.B4E+OS O.OOE+OO PR-143 9.36E+03 3.7SE+03 O.OOE+OO 2.16E+03 2.B1E+OS 2.00E+OS 4.64E+02 O.OOE+OO PR-144 3.01E-02 1.2SE-02 O.OOE+OO 7.0SE-03 1.02E+03 2.1SE-OB 1.S3E-03 O.OOE+OO ND-147 5.27E+03 6.10E+03 O.OOE+OO 3.S6E+03 2.21E+OS 1.73E+OS 3.6SE+02 O.OOE+OO W-1B7 B.48E+OO 7.08E+00 O.OOE+OO O.OOE+OO 2.90E+04 1.SSE+OS 2.4BE+00 O.OOE+OO NP-239 2.30E+02 2.03E+02 O.OOE+OO 7.00E+01 3.76E+04 1.19E+OS 1.24E+01 O.OOE+OO 7-16

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 7-10 VEGETATION INGESTION - CHILD AGE GROUP (RA1(vG)J)

Age Group: Child Pathway: Vegetation Units: m2 x mrem/yr per lI_Ci/sec Nuclide Bone Liver Thyroid Kidney Lung Gi-LLi TBody Skin H-3

O.OOE+OO 3.63E+03 3.63E+03 3.63E+03 3.63E+03 3.63E+03 3.63E+03 O.OOE+OO C-14

7.6SE+OS 1.S3E+OS 1.S3E+OS 1.S3E+OS 1.S3E+OS 1.S3E+OS 1.S3E+OS O.OOE+OO NA-24 3.73E+OS 3.73E+OS 3.73E+OS 3.73E+OS 3.73E+OS 3.73E+OS 3.73E+OS O.OOE+OO P-32 3.37E+09 1.SBE+OB O.OOE+OO O.OOE+OO O.OOE+OO 9.32E+07 1.30E+OB O.OOE+OO CR-S1 O.OOE+OO O.OOE+OO 6.4BE+04 1.77E+04 1.1BE+OS 6.19E+06 1.17E+OS O.OOE+OO MN-S4 O.OOE+OO 6.6SE+OB O.OOE+OO 1.B6E+OB O.OOE+OO S.SBE+OB 1.77E+OB O.OOE+OO MN-S6 O.OOE+OO 1.76E+01 O.OOE+OO 2.13E+01 O.OOE+OO 2.SSE+03 3.9BE+OO O.OOE+OO FE-SS B.01E+OB 4.2SE+OB O.OOE+OO O.OOE+OO 2.40E+OB 7.B7E+07 1.32E+OB O.OOE+OO FE-S9 3.97E+OB 6.42E+OB O.OOE+OO O.OOE+OO 1.B6E+OB 6.6BE+OB 3.20E+OB O.OOE+OO CO-SB O.OOE+OO 6.4SE+07 O.OOE+OO O.OOE+OO O.OOE+OO 3.76E+OB 1.97E+OB O.OOE+OO CO-60 O.OOE+OO 3.7BE+OB O.OOE+OO O.OOE+OO O.OOE+OO 2.10E+09 1.12E+09 O.OOE+OO NI-63 3.9SE+10 2.11E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.42E+OB 1.34E+09 O.OOE+OO NI-6S 1.02E+02 9.S9E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.1BE+03 S.60E+OO O.OOE+OO CU-64 O.OOE+OO 1.09E+04 O.OOE+OO 2.62E+04 O.OOE+OO S.10E+OS 6.S6E+03 O.OOE+OO ZN-6S B.12E+OB 2.16E+09 O.OOE+OO 1.36E+09 O.OOE+OO 3.BOE+OB 1.3SE+09 O.OOE+OO ZN-69 1.3SE-OS 1.9SE-OS O.OOE+OO 1.1BE-OS O.OOE+OO 1.23E-03 1.BOE-06 O.OOE+OO BR-B3 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO S.23E+OO O.OOE+OO BR-B4 O.OOE+OO O.OOE+OO *O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.39E-11 O.OOE+OO BR-BS O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-B6 O.OOE+OO 4.S3E+OB O.OOE+OO O.OOE+OO O.OOE+OO 2.92E+07 2.79E+OB O.OOE+OO RB-BB O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-B9 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO SR-B9 3.S9E+10 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.39E+09 1.02E+09 O.OOE+OO SR-90 1.24E+12 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.67E+10 3.1SE+11 O.OOE+OO SR-91 S.17E+OS O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.14E+06 1.9SE+04 O.OOE+OO SR-92 7.11E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.3SE+04 2.BSE+01 O.OOE+OO Y-90 2.31E+04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.S7E+07 6.1BE+02 O.OOE+OO Y-91M 7.69E-09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.S1E-OS 2.BOE-10 O.OOE+OO Y-91 1.B6E+07 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.4BE+09 4.99E+OS O.OOE+OO Y-92 1.SBE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.S7E+04 4.S2E-02 O.OOE+OO Y-93 2.B9E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.31E+06 7.94E+OO O.OOE+OO ZR-9S 3.B6E+06 B.49E+OS O.OOE+OO 1.22E+06 O.OOE+OO B.B6E+OB 7.S6E+OS O.OOE+OO ZR-97 S.67E+02 B.19E+01 O.OOE+OO 1.1BE+02 O.OOE+OO 1.24E+07 4.B3E+01 O.OOE+OO NB-9S 4.12E+OS 1.60E+OS O.OOE+OO 1.S1E+OS O.OOE+OO 2.97E+OB 1.1SE+OS O.OOE+OO MO-99 O.OOE+OO 7.69E+06 O.OOE+OO 1.64E+07 O.OOE+OO 6.36E+06 1.90E+06 O.OOE+OO TC-99M 4.64E+OO 9.10E+OO O.OOE+OO 1.32E+02 4.62E+OO S.1BE+03 1.S1E+02 O.OOE+OO TC-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RU-103 1.S3E+07 O.OOE+OO O.OOE+OO 3.B6E+07 O.OOE+OO 3.96E+OB S.B9E+06 O.OOE+OO RU-10S B.97E+01 O.OOE+OO O.OOE+OO 7.B9E+02 O.OOE+OO S.B6E+04 3.2SE+01 O.OOE+OO

Units for H-3 and C-14 are: mrem/yr per uCi/m 3 7-17

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Age Grou~ Child Pathway: Vegetation Units: m2 x mrem/yr per J,lCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gi-LLi TBody Skin RU-106 7.4SE+OB O.OOE+OO O.OOE+OO 1.01E+09 O.OOE+OO 1.16E+10 9.30E+07 O.OOE+OO AG-110M 3.21E+07 2.17E+07 O.OOE+OO 4.04E+07 O.OOE+OO 2.SBE+09 1.74E+07 O.OOE+OO TE-12SM 3.S1E+OB 9.S2E+07 9.BSE+07 O.OOE+OO O.OOE+OO 3.39E+OB 4.6BE+07 O.OOE+OO TE-127M 1.32E+09 3.S6E+OB 3.16E+OB 3.77E+09 O.OOE+OO 1.07E+09 1.S7E+OB O.OOE+OO TE-127 9.76E+03 2.63E+03 6.7SE+03 2.7BE+04 O.OOE+OO 3.B1E+OS 2.09E+03 O.OOE+OO TE-129M B.39E+OB 2.34E+OB 2.71E+OB 2.46E+09 O.OOE+OO 1.02E+09 1.30E+OB O.OOE+OO TE-129 1.23E-03 3.4SE-04 B.B1E-04 3.61E-03 O.OOE+OO 7.69E-02 2.93E-04 O.OOE+OO TE-131M 1.S4E+06 S.32E+OS 1.09E+06 S.1SE+06 O.OOE+OO 2.16E+07 S.66E+OS O.OOE+OO TE-131 2.3SE-1S 7.17E-16 1.BOE-1S 7.12E-1S O.OOE+OO 1.24E-14 7.00E-16 O.OOE+OO TE-132 7.00E+06 3.10E+06 4.S1E+06 2.BBE+07 O.OOE+OO 3.12E+07 3.74E+06 O.OOE+OO 1-130 6.10E+OS 1.23E+06 1.36E+OB 1.B4E+06 O.OOE+OO S.76E+OS 6.3SE+OS O.OOE+OO 1-131 1.43E+OB 1.44E+OB 4.7SE+10 2.36E+OB O.OOE+OO 1.2BE+07 B.16E+07 O.OOE+OO 1-132 8.93E+01 1.64E+02 7.61E+03 2.S1E+02 O.OOE+OO 1.93E+02 7.S4E+01 O.OOE+OO 1-133 3.S2E+06 4.36E+06 B.09E+OB 7.26E+06 O.OOE+OO 1.76E+06 1.6SE+06 O.OOE+OO 1-134 1.37E-04 2.SSE-04 S.B6E-03 3.90E-04 O.OOE+OO 1.69E-04 1.17E-04 O.OOE+OO 1-135 6.13E+04 1.10E+OS 9.77E+06 1.69E+OS O.OOE+OO B.41E+04 S.22E+04 O.OOE+OO CS-134 1.60E+10 2.63E+10 O.OOE+OO B.1SE+09 2.93E+09 1.42E+08 S.SSE+09 O.OOE+OO CS-136 B.17E+07 2.2SE+OB O.OOE+OO 1.20E+OB 1.78E+07 7.90E+06 1.4SE+OB O.OOE+OO CS-137 2.39E+10 2.29E+10 O.OOE+OO 7.46E+09 2.68E+09 1.43E+OB 3.3BE+09 O.OOE+OO CS-138 6.10E-11 B.4BE-11 O.OOE+OO S.96E-11 6.42E-12 3.90E-11 S.37E-11 O.OOE+OO BA-139 4.27E-02 2.2BE-OS O.OOE+OO 1.99E-OS 1.34E-OS 2.47E+00 1.24E-03 O.OOE+OO BA-140 2.77E+OB 2.42E+OS O.OOE+OO 7.89E+04 1.44E+OS 1.40E+08 1.61E+07 O.OOE+OO BA-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BA-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO LA-140 3.2SE+03 1.13E+03 O.OOE+OO O.OOE+OO O.OOE+OO 3.16E+07 3.B2E+02 O.OOE+OO LA-142 2.21E-04 7.0SE-OS O.OOE+OO O.OOE+OO O.OOE+OO 1.40E+01 2.21E-OS O.OOE+OO CE-141 6.SSE+OS 3.27E+OS O.OOE+OO 1.43E+OS O.OOE+OO 4.07E+OB 4.BSE+04 O.OOE+OO CE-143 1.72E+03 9.34E+OS O.OOE+OO 3.92E+02 O.OOE+OO 1.37E+07 1.3SE+02 O.OOE+OO CE-144 1.27E+OB 3.98E+07 O.OOE+OO 2.21E+07 O.OOE+OO 1.04E+10 6.7BE+06 O.OOE+OO PR-143 1.46E+OS 4.39E+04 O.OOE+OO 2.3BE+04 O.OOE+OO 1.SBE+OB 7.2SE+03 O.OOE+OO PR-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NO-147 7.26E+04 S.88E+04 O.OOE+OO 3.23E+04 O.OOE+OO 9.32E+07 4.S6E+03 O.OOE+OO W-1B7 6.4SE+04 3.B2E+04 O.OOE+OO O.OOE+OO O.OOE+OO S.37E+06 1.71E+04 O.OOE+OO NP-239 2.S6E+03 1.B4E+02 O.OOE+OO S.32E+02 O.OOE+OO 1.36E+07 1.29E+02 O.OOE+OO

Units for H-3 and C-14 are: mrem/yr per uCilm3 7-18

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 7-11 VEGETATION INGESTION - TEEN AGE GROUP (RA1(vG)J)

Age Group: Teen Pathway: Vegetation Units: m2 x mrem/yr per ~Ci/sec Nuclide Bone Liver Thyroid Kidney Lung Gi-LLi TBody Skin H-3

O.OOE+OO 2.34E+03 2.34E+03 2.34E+03 2.34E+03 2.34E+03 2.34E+03 2.34E+03 C-14

3.16E+05 6.32E+04 6.32E+04 6.32E+04 6.32E+04 6.32E+04 6.32E+04 O.OOE+OO NA-24 2.39E+05 2.39E+OS 2.39E+OS 2.39E+OS 2.39E+OS 2.39E+OS 2.39E+OS O.OOE+OO P-32 1.61E+09 9.97E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.35E+OS 6.24E+07 O.OOE+OO CR-S1 O.OOE+OO O.OOE+OO 3.42E+04 1.3SE+04 S.7SE+04 1.03E+07 6.1SE+04 O.OOE+OO MN-S4 O.OOE+OO 4.S4E+OS O.OOE+OO 1.36E+OS O.OOE+OO 9.32E+OS 9.01E+07 O.OOE+OO MN-S6 O.OOE+OO 1.3SE+01 O.OOE+OO 1.70E+01 O.OOE+OO S.S7E+02 2.40E+OO O.OOE+OO FE-55 3.26E+OS 2.31E+OS O.OOE+OO O.OOE+OO 1.47E+OS 1.00E+OS S.39E+07 O.OOE+OO FE-59 1.79E+OS 4.1SE+OS O.OOE+OO O.OOE+OO 1.32E+OS 9.SSE+OS 1.61E+OS O.OOE+OO CO-SS O.OOE+OO 4.37E+07 O.OOE+OO O.OOE+OO O.OOE+OO 6.02E+OS 1.01E+OS O.OOE+OO CO-60 O.OOE+OO 2.49E+OS O.OOE+OO O.OOE+OO O.OOE+OO 3.24E+09 5.60E+OS O.OOE+OO NI-63 1.61E+10 1.13E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.S1E+OS S.4SE+OS O.OOE+OO NI-65 S.55E+01 7.10E+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.S5E+02 3.23E+OO O.OOE+OO CU-64 O.OOE+OO S.24E+03 O.OOE+OO 2.0SE+04 O.OOE+OO 6.39E+05 3.S7E+03 O.OOE+OO ZN-65 4.24E+OS 1.47E+09 O.OOE+OO 9.41E+OS O.OOE+OO 6.23E+OS 6.S6E+OS O.OOE+OO ZN-69 7.32E-06 1.39E-OS O.OOE+OO 9.12E-06 O.OOE+OO 2.57E-05 9.76E-07 O.OOE+OO BR-S3 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.S4E+OO O.OOE+OO BR-S4 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.00E-11 O.OOE+OO BR-SS O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-S6 O.OOE+OO 2.74E+OS O.OOE+OO O.OOE+OO O.OOE+OO 4.06E+07 1.29E+OS O.OOE+OO RB-SS O.OOE+OO O.OOE+OO

O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-S9 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO SR-S9 1.S1E+10 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.S0E+09 4.33E+OS O.OOE+OO SR-90 7.S1E+11 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.11E+10 1.SSE+11 O.OOE+OO SR-91 2.S1E+05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.27E+06 1.12E+04 O.OOE+OO SR-92 3.SSE+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.SSE+03 1.6SE+01 O.OOE+OO Y-90 1.24E+04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.03E+OS 3.3SE+02 O.OOE+OO Y-91M 4.19E-09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.9SE-07 1.60E-10 O.OOE+OO Y-91 7.S4E+06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.21E+09 2.10E+OS O.OOE+OO Y-92 S.SSE-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.36E+04 2.4SE-02 O.OOE+OO Y-93 1.S7E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.S0E+06 4.30E+OO O.OOE+OO ZR-9S 1.72E+06 S.44E+OS O.OOE+OO 7.99E+OS O.OOE+OO 1.26E+09 3.74E+05 O.OOE+OO ZR-97 3.10E+02 6.14E+01 O.OOE+OO 9.31E+01 O.OOE+OO 1.66E+07 2.S3E+01 O.OOE+OO NB-9S 1.93E+OS 1.07E+OS O.OOE+OO 1.04E+05 O.OOE+OO 4.SSE+OS S.S9E+04 O.OOE+OO MO-99 O.OOE+OO S.63E+06 O.OOE+OO 1.29E+07 O.OOE+OO 1.01E+07 1.07E+06 O.OOE+OO TC-99M 2.70E+OO 7.S2E+OO O.OOE+OO 1.12E+02 4.17E+OO 4.94E+03 9.7SE+01 O.OOE+OO TC-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RU-103 6.S1E+06 O.OOE+OO O.OOE+OO 2.40E+07 O.OOE+OO S.69E+OS 2.91E+06 O.OOE+OO RU-10S 4.90E+01 O.OOE+OO O.OOE+OO 6.1SE+02 O.OOE+OO 3.95E+04 1.90E+01 O.OOE+OO RU-106 3.09E+OS O.OOE+OO O.OOE+OO S.97E+OS O.OOE+OO 1.4SE+10 3.90E+07 O.OOE+OO AG-110M 1.52E+07 1.43E+07 O.OOE+OO 2.74E+07 O.OOE+OO 4.03E+09 S.73E+06 O.OOE+OO

Units for H-3 and C-14 are: mrem/yr per uCi/m 3 7-19

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Age Group: Teen Pathway: Vegetation Units: m2 x mrem/yr per J.lCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gi-LLi TBody Skin TE-12SM 1.4BE+OB S.3SE+07 4.1SE+07 O.OOE+OO O.OOE+OO 4.3BE+OB 1.9BE+07 O.OOE+OO TE-127M S.S1E+OB 1.96E+OB 1.31E+OB 2.24E+09 O.OOE+OO 1.37E+09 6.S6E+07 O.OOE+OO TE-127 S.29E+03 1.B7E+03 3.6SE+03 2.14E+04 O.OOE+OO 4.0BE+OS 1.14E+03 O.OOE+OO TE-129M 3.61E+OB 1.34E+OB 1.16E+OB 1.S1E+09 O.OOE+OO 1.36E+09 S.71E+07 O.OOE+OO TE-129 6.67E-04 2.49E-04 4.76E-04 2.BOE-03 O.OOE+OO 3.6SE-03 1.62E-04 O.OOE+OO TE-131M B.42E+OS 4.04E+OS 6.07E+OS 4.21E+06 O.OOE+OO 3.24E+07 3.37E+OS O.OOE+OO TE-131 1.2BE-1S S.27E-16 9.BSE-16 S.S9E-1S O.OOE+OO 1.0SE-16 3.99E-16 O.OOE+OO TE-132 3.91E+06 2.47E+06 2.61E+06 2.37E+07 O.OOE+OO 7.B4E+07 2.33E+06 O.OOE+OO 1-130 3.47E+OS 1.01E+06 B.20E+07 1.SSE+06 O.OOE+OO 7.73E+OS 4.01E+OS O.OOE+OO 1-131 7.6BE+07 1.0BE+OB 3.14E+10 1.BSE+OB O.OOE+OO 2.13E+07 S.7BE+07 O.OOE+OO 1-132 S.03E+01 1.32E+02 4.43E+03 . 2.07E+02 O.OOE+OO S.73E+01 4.72E+01 O.OOE+OO 1-133 1.93E+06 3.2BE+06 4.SBE+OB S.7SE+06 O.OOE+OO 2.4BE+06 1.00E+06 O.OOE+OO 1-134 7.73E-OS 2.OSE-04 3.41 E-03 3.23E-04 O.OOE+OO 2.70E-06 7.36E-OS O.OOE+OO 1-13S 3.4SE+04 B.BBE+04 S.72E+06 1.40E+OS O.OOE+OO 9.BSE+04 3.29E+04 O.OOE+OO CS-134 7.10E+09 1.67E+10 O.OOE+OO S.31E+09 2.03E+09 2.OBE+OB 7.7SE+09 O.OOE+OO CS-136 4.34E+07 1.71E+OB O.OOE+OO 9.30E+07 1.47E+07 1.37E+07 1.1SE+OB O.OOE+OO CS-137 1.01E+10 1.3SE+10 O.OOE+OO 4.S9E+09 1.7BE+09 1.92E+OB 4.69E+09 O.OOE+OO CS-13B 3.3SE-11 6.44E-11 O.OOE+OO 4.7SE-11 S.S3E-12 2.92E-14 3.22E-11 O.OOE+OO BA-139 2.32E-02 1.63E-OS O.OOE+OO 1.S4E-OS 1.12E-OS 2.07E-01 6.7SE-04 O.OOE+OO BA-140 1.3BE+OB 1.69E+OS O.OOE+OO S.74E+04 1.14E+OS 2.13E+OB B.90E+06 O.OOE+OO BA-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BA-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO LA-140 1.B1E+03 B.BBE+02 O.OOE+OO O.OOE+OO O.OOE+OO S.10E+07 2.36E+02 O.OOE+OO LA-142 1.22E-04 S.42E-OS O.OOE+OO O.OOE+OO O.OOE+OO 1.6SE+00 1.3SE-OS O.OOE+OO CE-141 2.B3E+OS 1.B9E+OS O.OOE+OO B.BBE+04 O.OOE+OO S.40E+OB 2.17E+04 O.OOE+OO CE-143 9.36E+02 6.B1E+OS O.OOE+OO 3.0SE+02 O.OOE+OO 2.OSE+07 7.61E+01 O.OOE+OO CE-144 S.27E+07 2.1BE+07 O.OOE+OO 1.30E+07 O.OOE+OO 1.33E+10 2.B3E+06 O.OOE+OO PR-143 7.03E+04 2.B1E+04 O.OOE+OO 1.63E+04 O.OOE+OO 2.31 E+OB 3.S0E+03 O.OOE+OO PR-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NO-147 3.67E+04 3.99E+04 O.OOE+OO 2.3SE+04 O.OOE+OO 1.44E+OB 2.39E+03 O.OOE+OO W-1B7 3.SSE+04 2.B9E+04 O.OOE+OO O.OOE+OO O.OOE+OO 7.B2E+06 1.01E+04 O.OOE+OO NP-239 1.39E+03 1.31 E+02 O.OOE+OO 4.11E+02 O.OOE+OO 2.10E+07 7.27E+01 O.OOE+OO

Units for H-3 and C-14 are: mrem/yr per uCi/m 3 7-20

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 7-12 VEGETATION INGESTION - ADULT AGE GROUP (RAI(vG)J)

Age Group: Adult Pathway: Vegetation Units: m 2 x mrem/yr per IJCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gi-LLi TBody Skin H-3 '* O.OOE+OO 2.0SE+03 2.0SE+03 2.0SE+03 2.0SE+03 2.0SE+03 2.0SE+03 O.OOE+OO C-14

1.92E+OS 3.S4E+04 3.S4E+04 3.S4E+04 3.S4E+04 3.S4E+04 3.S4E+04 O.OOE+OO NA-24 2.69E+OS 2.69E+OS 2.69E+OS 2.69E+OS 2.69E+OS 2.69E+OS 2.69E+OS O.OOE+OO P-32 1.40E+09 S.73E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.SSE+OS S.43E+07 O.OOE+OO CR-S1 O.OOE+OO O.OOE+OO 2.77E+04 1.02E+04 6.1SE+04 1.17E+07 4.63E+04 O.OOE+OO MN-S4 O.OOE+OO 3.13E+OS O.OOE+OO 9.31E+07 O.OOE+OO 9.SSE+OS S.97E+07 O.OOE+OO MN-S6 O.OOE+OO 1.49E+01 O.OOE+OO 1.90E+01 O.OOE+OO 4.77E+02 2.6SE+OO O.OOE+OO FE-55 2.10E+OS 1.4SE+OS O.OOE+OO O.OOE+OO 8.0SE+07 8.31E+07 3.3SE+07 O.OOE+OO FE-59 1.26E+OS 2.96E+OS O.OOE+OO O.OOE+OO S.27E+07 9.S6E+OS 1.13E+OS O.OOE+OO CO-SS O.OOE+OO 3.0SE+07 O.OOE+OO O.OOE+OO O.OOE+OO 6.24E+OS 6.90E+07 O.OOE+OO CO-60 O.OOE+OO 1.67E+OS O.OOE+OO O.OOE+OO O.OOE+OO 3.14E+09 3.69E+OS O.OOE+OO NI-63 1.04E+10 7.21E+OS O.OOE+OO O.OOE+OO O.OOE+OO 1.S0E+OS 3.49E+OS O.OOE+OO NI-6S S.97E+01 7.7SE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.97E+02 3.S4E+OO O.OOE+OO CU-64 O.OOE+OO 9.09E+03 O.OOE+OO 2.29E+04 O.OOE+OO 7.7SE+OS 4.27E+03 O.OOE+OO ZN-6S 3.17E+OS 1.01E+09 O.OOE+OO 6.7SE+OS O.OOE+OO 6.36E+OS 4.S6E+08 O.OOE+OO ZN-69 7.S2E-06 1.S0E-OS O.OOE+OO 9.72E-06 O.OOE+OO 2.2SE-06 1.04E-06 O.OOE+OO BR-S3 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4 .36E+OO 3.03E+OO O.OOE+OO BR-S4 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.72E-16 2.20E-11 O.OOE+OO BR-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-S6 O.OOE+OO 2.20E+OS O.OOE+OO O.OOE+OO O.OOE+OO 4.34E+07 1.02E+OS O.OOE+OO RB-SS O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO SR-S9 9.9SE+09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.60E+09 2.S6E+OS O.OOE+OO SR-90 6.0SE+11 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.7SE+10 1.4SE+11 O.OOE+OO SR-91 3.01E+OS O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.43E+06 1.22E+04 O.OOE+OO SR-92 4.17E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO S.2SE+03 1.S0E+01 O.OOE+OO Y-90 1.33E+04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.41E+OS 3.S7E+02 O.OOE+OO Y-91M 4.S0E-09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.32E-OS 1.74E-10 O.OOE+OO Y-91 S.11E+06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.S1E+09 1.37E+OS O.OOE+OO Y-92 9.14E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.60E+04 2.67E-02 O.OOE+OO Y-93 1.67E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO S.31E+06 4.62E+OO O.OOE+OO ZR-9S 1.1SE+06 3.77E+OS O.OOE+OO S.92E+OS O.OOE+OO 1.20E+09 2.SSE+OS O.OOE+OO ZR-97 3.3SE+02 6.77E+01 O.OOE+OO 1.02E+02 O.OOE+OO 2.10E+07 3.09E+01 O.OOE+OO NB-9S 1.43E+OS 7.9SE+04 O.OOE+OO 7.SSE+04 O.OOE+OO 4.S2E+OS 4.27E+04 O.OOE+OO MO-99 O.OOE+OO 6.14E+06 O.OOE+OO 1.39E+07 O.OOE+OO 1.42E+07 1.17E+06 O.OOE+OO TC-99M 3.06E+OO S.64E+OO O.OOE+OO 1.31E+02 4.23E+OO S.11E+03 1.10E+02 O.OOE+OO TC-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RU-103 4.77E+06 O.OOE+OO O.OOE+OO 1.S2E+07 O.OOE+OO S.S6E+OS 2.0SE+06 O.OOE+OO

Units for H-3 and C-14 are: mrem/yr per uCi/m 3 7-21

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Age Group: Adult Pathway: Vegetation Units: m2 x mrem/yr per ~Ci/sec Nuclide Bone Liver Thyroid Kidney Lung Gi-LLi TBody Skin RU-10S S.27E+01 O.OOE+OO O.OOE+OO 6.B1E+02 O.OOE+OO 3.23E+04 2.0BE+01 O.OOE+OO RU-106 1.93E+OB O.OOE+OO O.OOE+OO 3.72E+OB O.OOE+OO 1.2SE+10 2.44E+07 O.OOE+OO AG-110M 1.0SE+07 9.7SE+06 O.OOE+OO 1.92E+07 O.OOE+OO 3.9BE+09 S.79E+06 O.OOE+OO TE-12SM 9.67E+07 3.S0E+07 2.91E+07 3.93E+OB O.OOE+OO 3.B6E+OB 1.30E+07 O.OOE+OO TE-127M 3.49E+OB 1.2SE+OB B.92E+07 1.42E+09 O.OOE+OO 1.17E+09 4.2SE+07 O.OOE+OO TE-127 S.61E+03 2.01E+03 4.16E+03 2.2BE+04 O.OOE+OO 4.43E+OS 1.21E+03 O.OOE+OO TE-129M 2.51E+OB 9.36E+07 B.62E+07 1.0SE+09 O.OOE+OO 1.26E+09 3.97E+07 O.OOE+OO TE-129 7.12E-04 2.6BE-04 S.47E-04 2.99E-03 O.OOE+OO S.3BE-04 1.74E-04 O.OOE+OO TE-131M 9.09E+05 4.4SE+OS 7.04E+OS 4.S0E+06 O.OOE+OO 4.41E+07 3.71E+OS O.OOE+OO TE-131 1.37E-1S S.74E-16 1.13E-1S 6.02E-1S O.OOE+OO 1.9SE-16 4.34E-16 O.OOE+OO TE-132 4.30E+06 2.7BE+06 3.07E+06 2.6BE+07 O.OOE+OO 1.32E+OB 2.61E+06 O.OOE+OO

'-130 3.B9E+OS 1.1SE+06 9.72E+07 1.79E+06 O.OOE+OO 9.B7E+OS 4.S2E+OS O.OOE+OO 1-131 B.07E+07 1.1SE+OB 3.7BE+10 1.9BE+OB O.OOE+OO 3.0SE+07 6.61E+07 O.OOE+OO

'-132 S.5BE+01 1.49E+02 S.22E+03 2.3BE+02 O.OOE+OO 2.BOE+01 S.22E+01 O.OOE+OO

'-133 2.0BE+06 3.62E+06 S.32E+OB 6.31E+06 O.OOE+OO 3.2SE+06 1.10E+06 O.OOE+OO

'-134 B.SSE-OS 2.32E-04 4.02E-03 3.69E-04 O.OOE+OO 2.02E-07 8.31 E-OS O.OOE+OO

'-13S 3.B2E+04 1.00E+OS 6.60E+06 1.60E+OS O.OOE+OO 1.13E+OS 3.69E+04 O.OOE+OO CS-134 4.67E+09 1.11E+10 O.OOE+OO 3.S9E+09 1.19E+09 1.94E+OB 9.0BE+09 O.OOE+OO CS-136 4.24E+07 1.6BE+OB O.OOE+OO 9.32E+07 1.2BE+07 1.90E+07 1.21E+OB O.OOE+OO CS-137 6.36E+09 B.70E+09 O.OOE+OO 2.9SE+09 9.B1E+OB 1.6BE+OB S.70E+09 O.OOE+OO CS-13B 3.63E-11 7.17E-11 O.OOE+OO S.27E-11 S.21E-12 3.06E-16 3.SSE-11 O.OOE+OO BA-139 2.47E-02 1.76E-OS O.OOE+OO 1.64E-OS 9.96E-06 4.37E-02 7.22E-04 O.OOE+OO BA-140 1.2BE+OB 1.61E+OS O.OOE+OO S.49E+04 9.24E+04 2.6SE+OB B.42E+06 O.OOE+OO BA-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BA-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO LA-140 1.9BE+03 9.97E+02 O.OOE+OO O.OOE+OO O.OOE+OO 7.32E+07 2.63E+02 O.OOE+OO LA-142 1.33E-04 6.0SE-OS O.OOE+OO O.OOE+OO O.OOE+OO 4.42E-01 1.S1E-OS O.OOE+OO CE-141 1.97E+OS 1.33E+OS O.OOE+OO 6.1BE+04 O.OOE+OO S.09E+OB 1.S1E+04 O.OOE+OO CE-143 1.00E+03 7.40E+OS O.OOE+OO 3.26E+02 O.OOE+OO 2.77E+07 B.19E+01 O.OOE+OO CE-144 3.29E+07 1.3BE+07 O.OOE+OO B.16E+06 O.OOE+OO 1.11E+10 1.77E+06 O.OOE+OO PR-143 6.2BE+04 2.S2E+04 O.OOE+OO 1.4SE+04 O.OOE+OO 2.7SE+OB 3.11E+03 O.OOE+OO PR-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NO-147 3.37E+04 3.90E+04 O.OOE+OO 2.2BE+04 O.OOE+OO 1.B7E+OB 2.33E+03 O.OOE+OO W-187 3.B1E+04 3.19E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.04E+07 1.11E+04 O.OOE+OO NP-239 1.43E+03 1.40E+02 O.OOE+OO 4.3BE+02 O.OOE+OO 2.BBE+07 7.7SE+01 O.OOE+OO

Units for H-3 and C-14 are: mrem/yr per uCi/m3 7-22

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 7-13 MILK INGESTION -INFANT AGE GROUP (RAI(MI)J)

Age Group: Infant Pathway: Milk Units: m 2 x mrem/yr per ~Ci/sec Nuclide Bone Liver Thyroid Kidney Lung Gi-LLi TBody Skin H-3

O.OOE+OO 2.16E+03 2.16E+03 2.16E+03 2.16E+03 2.16E+03 2.16E+03 O.OOE+OO C-14

9.06E+OS 1.93E+OS 1.93E+OS 1.93E+OS 1.93E+OS 1.93E+OS 1.93E+OS O.OOE+OO NA-24 1.S6E+07 1.S6E+07 1.S6E+07 1.S6E+07 1.S6E+07 1.S6E+07 1.S6E+07 O.OOE+OO P-32 1.60E+11 9.43E+09 O.OOE+OO O.OOE+OO O.OOE+OO 2.17E+09 6.22E+09 O.OOE+OO CR-S1 O.OOE+OO O.OOE+OO 1.0SE+OS 2.30E+04 2.0SE+OS 4.70E+06 1.61E+OS O.OOE+OO MN-S4 O.OOE+OO 3.90E+07 O.OOE+OO B.64E+06 O.OOE+OO 1.43E+07 B.B4E+06 O.OOE+OO MN-S6 O.OOE+OO 3.00E-02 O.OOE+OO 2.SBE-02 O.OOE+OO 2.73E+OO S.17E-03 O.OOE+OO FE-SS 1.3SE+OB B.73E+07 O.OOE+OO O.OOE+OO 4.27E+07 1.11E+07 2.33E+07 O.OOE+OO FE-S9 2.24E+OB 3.92E+OB O.OOE+OO O.OOE+OO 1.16E+OB 1.B7E+OB 1.S4E+OB O.OOE+OO CO-SB O.OOE+OO 2.43E+07 O.OOE+OO O.OOE+OO O.OOE+OO 6.0SE+07 6.0SE+07 O.OOE+OO CO-60 O.OOE+OO B.B1E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.10E+OB 2.0BE+OB O.OOE+OO NI-63 3.49E+10 2.16E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.07E+OB 1.21E+09 O.OOE+OO NI-6S 3.S6E+OO 4.03E-01 O.OOE+OO O.OOE+OO O.OOE+OO 3.07E+01 1.B3E-01 O.OOE+OO CU-64 O.OOE+OO 1.B4E+OS O.OOE+OO 3.12E+OS O.OOE+OO 3.7BE+06 B.S3E+04 O.OOE+OO ZN-6S S.SSE+09 1.90E+10 O.OOE+OO 9.23E+09 O.OOE+OO 1.61E+10 B.7BE+09 O.OOE+OO ZN-69 4.91 E-11 B.BSE-11 O.OOE+OO 3.6BE-11 O.OOE+OO 7.21E-09 6.SBE-12 O.OOE+OO BR-B3 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.60E-01 O.OOE+OO BR-B4 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-BS O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-B6 O.OOE+OO 2.23E+10 O.OOE+OO O.OOE+OO O.OOE+OO S.70E+OB 1.10E+10 O.OOE+OO RB-BB O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-B9 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO SR-B9 1.26E+10 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.S9E+OB 3.61E+OB O.OOE+OO SR-90 1.22E+11 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.S2E+09 3.10E+10 O.OOE+OO SR-91 2.71E+OS O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.20E+OS 9.BOE+03 O.OOE+OO SR-92 4.7SE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO S.12E+01 1.76E-01 O.OOE+OO Y-90 6.B3E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.43E+OS 1.B3E+01 O.OOE+OO Y-91M S.34E-19 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.7BE-1S 1.B2E-20 O.OOE+OO Y-91 7.33E+04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO S.2SE+06 1.9SE+03 O.OOE+OO Y-92 S.64E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.0BE+01 1.S8E-OS O.OOE+OO Y-93 2.1SE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.70E+04 S.BSE-02 O.OOE+OO ZR-9S 6.B1E+03 1.66E+03 O.OOE+OO 1.79E+03 O.OOE+OO B.26E+OS 1.1BE+03 O.OOE+OO ZR-97 4 .06E+OO 6.97E-01 O.OOE+OO 7.03E-01 O.OOE+OO 4.4SE+04 3.19E-01 O.OOE+OO NB-9S S.94E+OS 2.4SE+OS O.OOE+OO 1.7SE+OS O.OOE+OO 2.07E+OB 1.41E+OS O.OOE+OO MO-99 O.OOE+OO 2.0BE+OB O.OOE+OO 3.10E+OB O.OOE+OO 6.B4E+07 4.0SE+07 O.OOE+OO TC-99M 2.76E+01 S.6BE+01 O.OOE+OO 6.12E+02 2.97E+01 1.6SE+04 7.32E+02 O.OOE+OO TC-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RU-103 B.67E+03 O.OOE+OO O.OOE+OO 1.BOE+04 O.OOE+OO 1.0SE+OS 2.90E+03 O.OOE+OO RU-10S B.07E-03 O.OOE+OO O.OOE+OO S.93E-02 O.OOE+OO 3.21E+OO 2.72E-03 O.OOE+OO RU-106 1.90E+OS O.OOE+OO O.OOE+OO 2.2SE+OS O.OOE+OO 1.44E+06 2.3BE+04 O.OOE+OO AG-110M 3.B6E+OB 2.82E+OB O.OOE+OO 4.03E+OB O.OOE+OO 1.46E+10 1.B6E+OB O.OOE+OO

Units for H-3 and C-14 are: mrem/yr per uCi/m 3 7-23

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Age Group: Infant Pathway: Milk Units: m2 x mrem/yr per ~Ci/sec Nuclide Bone Liver Thyroid Kidney Lung Gi-LLi TBody Skin TE-12SM 1.S1E+OB S.04E+07 S.OBE+07 O.OOE+OO O.OOE+OO 7.19E+07 2.04E+07 O.OOE+OO TE-127M 4.21E+OB 1.40E+OB 1.22E+OB 1.04E+09 O.OOE+OO 1.70E+OB S.10E+07 O.OOE+OO TE-127 6.33E+03 2.12E+03 S.16E+03 1.SSE+04 O.OOE+OO 1.33E+OS 1.36E+03 O.OOE+OO TE-129M S.S7E+OB 1.91 E+OB 2.14E+OB 1.39E+09 O.OOE+OO 3.33E+OB B.SBE+07 O.OOE+OO TE-129 2.BOE-09 9.66E-10 2.3SE-09 6.9BE-09 O.OOE+OO 2.24E-07 6.S4E-10 O.OOE+OO TE-131M 3.3BE+06 1.36E+06 2.76E+06 9.36E+06 O.OOE+OO 2.29E+07 1.12E+06 O.OOE+OO TE-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TE-132 2.11 E+07 1.0SE+07 1.S4E+07 6.S4E+07 O.OOE+OO 3.B7E+07 9.76E+06 O.OOE+OO 1-130 3.S4E+06 7.79E+06 B.74E+OB B.S6E+06 O.OOE+OO 1.67E+06 3.13E+06 O.OOE+OO 1-131 2.72E+09 3.20E+09 1.0SE+12 3.74E+09 O.OOE+OO 1.14E+OB 1.41 E+09 O.OOE+OO 1-132 1.46E+00 2.96E+00 1.39E+02 3.30E+00 O.OOE+OO 2.40E+00 1.0SE+00 O.OOE+OO 1-133 3.64E+07 S.30E+07 9.64E+09 6.23E+07 O.OOE+OO B.97E+06 1.SSE+07 O.OOE+OO 1-134 1.72E-11 3.S3E-11 B.22E-10 3.94E-11 O.OOE+OO 3.64E-11 1.2SE-11 O.OOE+OO 1-13S 1.11E+OS 2.21E+OS 1.9BE+07 2.47E+OS O.OOE+OO B.01E+04 B.07E+04 O.OOE+OO CS-134 3.6SE+10 6.BOE+10 O.OOE+OO 1.7SE+10 7.1BE+09 1.BSE+OB 6.B7E+09 O.OOE+OO CS-136 1.97E+09 S.BOE+09 O.OOE+OO 2.31E+09 4.72E+OB B.BOE+07 2.16E+09 O.OOE+OO CS-137 S.1SE+10 6.02E+10 O.OOE+OO 1.62E+10 6.SSE+09 1.BBE+OB 4.27E+09 O.OOE+OO CS-13B O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BA-139 3.6BE-07 2.44E-10 O.OOE+OO 1.47E-10 1.4BE-10 2.33E-OS 1.07E-OB O.OOE+OO BA-140 2.41E+OB 2.41E+OS O.OOE+OO S.72E+04 1.4BE+OS S.92E+07 1.24E+07 O.OOE+OO BA-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BA-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO LA-140 4.07E+01 1.60E+01 O.OOE+OO O.OOE+OO O.OOE+OO 1.BBE+OS 4.13E+OO O.OOE+OO LA-142 B.S9E-11 3.16E-11 O.OOE+OO O.OOE+OO O.OOE+OO S.36E-06 7.SSE-12 O.OOE+OO CE-141 4.34E+04 2.64E+04 O.OOE+OO B.1SE+03 O.OOE+OO 1.37E+07 3.11E+03 O.OOE+OO CE-143 4.01E+02 2.66E+OS O.OOE+OO 7.74E+01 O.OOE+OO 1.SSE+06 3.03E+01 O.OOE+OO CE-144 2.33E+06 9.S2E+OS O.OOE+OO 3.BSE+OS O.OOE+OO 1.33E+OB 1.30E+OS O.OOE+OO PR-143 1.49E+03 S.S6E+02 O.OOE+OO 2.07E+02 O.OOE+OO 7.BSE+OS 7.3BE+01 O.OOE+OO PR-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NO-147 B.BBE+02 9.12E+02 O.OOE+OO 3.S2E+02 O.OOE+OO S.7BE+OS S.S9E+01 O.OOE+OO W-1B7 6.14E+04 4.27E+04 O.OOE+OO O.OOE+OO O.OOE+OO 2.S1E+06 1.4BE+04 O.OOE+OO NP-239 3.66E+01 3.27E+OO O.OOE+OO 6.S3E+OO O.OOE+OO 9.46E+04 1.BSE+00 O.OOE+OO

Units for H-3 and C-14 are: mrem/yr per uCi/m3 7-24

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 7-14 MILK INGESTION - CHILD AGE GROUP (RA1(MI)J)

Age Group: Child Pathway: Milk Units: m2 x mrem/yr per ",Ci/sec Nuclide Bone Liver Thyroid Kidney Lung Gi-LLi TBody Skin H-3

O.OOE+OO 1.42E+03 1.42E+03 1.42E+03 1.42E+03 1.42E+03 1.42E+03 O.OOE+OO C-14

4.62E+05 9.25E+04 9.25E+04 9.25E+04 9.25E+04 9.25E+04 9.25E+04 O.OOE+OO NA-24 B.96E+06 B.96E+06 B.96E+06 B.96E+06 B.96E+06 B.96E+06 B.96E+06 O.OOE+OO P-32 7.7BE+10 3.64E+09 O.OOE+OO O.OOE+OO O.OOE+OO 2.15E+09 3.00E+09 O.OOE+OO CR-51 O.OOE+OO O.OOE+OO 5.65E+04 1.54E+04 1.03E+05 5.40E+06 1.02E+05 O.OOE+OO MN-54 O.OOE+OO 2.10E+07 O.OOE+OO 5.BBE+06 O.OOE+OO 1.76E+07 5.59E+06 O.OOE+OO MN-56 O.OOE+OO 1.23E-02 O.OOE+OO 1.4BE-02 O.OOE+OO 1.7BE+OO 2.77E-03 O.OOE+OO FE-55 1.12E+OB 5.93E+07 O.OOE+OO O.OOE+OO 3.35E+07 1.10E+07 1.B4E+07 O.OOE+OO FE-59 1.20E+OB 1.94E+OB O.OOE+OO O.OOE+OO 5.64E+07 2.02E+08 9.69E+07 O.OOE+OO CO-5B O.OOE+OO 1.21 E+07 O.OOE+OO O.OOE+OO O.OOE+OO 7.0BE+07 3.71E+07 O.OOE+OO CO-60 O.OOE+OO 4.32E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.39E+OB 1.27E+OB O.OOE+OO NI-63 2.9,6E+10 1.59E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.07E+OB 1.01E+09 O.OOE+OO NI-65 1.6BE+OO 1.5BE-01 O.OOE+OO O.OOE+OO O.OOE+OO 1.94E+01 9.25E-02 O.OOE+OO CU-64 O.OOE+OO 7.41E+04 O.OOE+OO 1.79E+05 O.OOE+OO 3.4BE+06 4.4BE+04 O.OOE+OO ZN-65 4.13E+09 1.10E+10 O.OOE+OO 6.94E+09 O.OOE+OO 1.93E+09 6.B5E+09 O.OOE+OO ZN-69 2.31 E-11 3.33E-11 O.OOE+OO 2.02E-11 O.OOE+OO 2.10E-09 3.0BE-12 O.OOE+OO BR-B3 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.52E-01 O.OOE+OO BR-B4 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-B5 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-B6 O.OOE+OO B.7BE+09 O.OOE+OO O.OOE+OO O.OOE+OO 5.65E+OB 5.40E+09 O.OOE+OO RB-BB O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-B9 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO SR-B9 6.62E+09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.56E+OB 1.B9E+OB O.OOE+OO SR-90 1.12E+11 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.51 E+09 2.B3E+10 O.OOE+OO SR-91 1.30E+05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.B7E+05 4.90E+03 O.OOE+OO SR-92 2.23E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.23E+01 B.96E-02 O.OOE+OO Y-90 3.23E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.19E+05 B.64E+OO O.OOE+OO Y-91M 2.52E-19 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.93E-16 O.OOE+OO O.OOE+OO Y-91 3.90E+04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.20E+06 1.04E+03 O.OOE+OO Y-92 2.65E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 7.66E+OO 7.59E-06 O.OOE+OO Y-93 1.01 E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.50E+04 2.77E-02 O.OOE+OO ZR-95 3.B3E+03 B.43E+02 O.OOE+OO 1.21 E+03 O.OOE+OO B.79E+05 7.50E+02 O.OOE+OO ZR-97 1.92E+OO 2.77E-01 O.OOE+OO 3.9BE-01 O.OOE+OO 4.20E+04 1.64E-01 O.OOE+OO NB-95 3.1BE+05 1.24E+05 O.OOE+OO 1.16E+05 O.OOE+OO 2.29E+OB B.B5E+04 O.OOE+OO MO-99 O.OOE+OO B.13E+07 O.OOE+OO 1.74E+OB O.OOE+OO 6.72E+07 2.01E+07 O.OOE+OO TC-99M 1.33E+01 2.60E+01 O.OOE+OO 3.7BE+02 1.32E+01 1.4BE+04 4.31E+02 O.OOE+OO TC-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RU-103 4.2BE+03 O.OOE+OO O.OOE+OO 1.0BE+04 O.OOE+OO 1.11E+05 1.65E+03 O.OOE+OO RU-105 3.83E-03 O.OOE+OO O.OOE+OO 3.36E-02 O.OOE+OO 2.S0E+00 1.39E-03 O.OOE+OO RU-106 9.24E+04 O.OOE+OO O.OOE+OO 1.2SE+OS O.OOE+OO 1.44E+06 1.1SE+04 O.OOE+OO AG-110M 2.09E+OB 1.41E+08 O.OOE+OO 2.63E+OB O.OOE+OO 1.68E+10 1.13E+OB O.OOE+OO

Units for H-3 and C-14 are: mrem/yr per uCilm 3 7-25

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Age Group: Child Pathway: Milk Units: m 2 x mrem/Yfper ~Ci/sec Nuclide Bone Liver Thyroid Kidney Lung Gi-LLi TBody Skin

TE-12SM 7.3BE+07 2.00E+07 2.07E+07 O.OOE+OO O.OOE+OO 7.12E+07 9.B4E+06 O.OOE+OO TE-127M 2.0BE+OB S.60E+07 4.97E+07 S.93E+OB O.OOE+OO 1.6BE+OB 2.47E+07 O.OOE+OO TE-127 2.9BE+03 B.04E+02 2.06E+03 B.49E+03 O.OOE+OO 1.17E+OS 6.40E+02 O.OOE+OO TE-129M 2.71E+OB 7.SBE+07 B.7SE+07 7.97E+OB O.OOE+OO 3.31 E+OB 4.21E+07 O.OOE+OO TE-129 1.32E-09 3.69E-10 9.43E-10 3.B7E-09 O.OOE+OO B.23E-OB 3.14E-10 O.OOE+OO TE-131M 1.60E+06 S.S4E+OS 1.14E+06 S.36E+06 O.OOE+OO 2.2SE+07 S.B9E+OS O.OOE+OO TE-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TE-132 1.03E+07 4.S4E+06 6.61E+06 4.22E+07 O.OOE+OO 4.S7E+07 S.49E+06 O.OOE+OO 1-130 1.72E+06 3.4BE+06 3.B4E+OB S.21E+06 O.OOE+OO 1.63E+06 1.79E+06 O.OOE+OO 1-131 1.30E+09 1.31E+09 4.33E+11 2.1SE+09 O.OOE+OO 1.17E+OB 7.4SE+OB O.OOE+OO 1-132 7.02E-01 1.29E+OO S.99E+01 1.9BE+OO O.OOE+OO 1.S2E+OO S.94E-01 O.OOE+OO 1-133 1.72E+07 2.13E+07 3.96E+09 3.SSE+07 O.OOE+OO B.S9E+06 B.06E+06 O.OOE+OO 1-134 B.30E-12 1.S4E-11 3.SSE-10 2.36E-11 O.OOE+OO 1.02E-11 7.09E-12 O.OOE+OO 1-13S S.3SE+04 9.63E+04 B.S3E+06 1.4BE+OS O.OOE+OO 7.34E+04 4.S6E+04 O.OOE+OO CS-134 2.26E+10 3.71E+10 O.OOE+OO 1.1SE+10 4.13E+09 2.00E+OB 7.B4E+09 O.OOE+OO CS-136 1.01E+09 2.77E+09 O.OOE+OO 1.4BE+09 2.20E+OB 9.7SE+07 1.BOE+09 O.OOE+OO CS-137 3.22E+10 3.09E+10 O.OOE+OO 1.01E+10 3.62E+09 1.93E+OB 4.SSE+09 O.OOE+OO CS-13B O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BA-139 1.73E-07 9.24E-11 O.OOE+OO B.07E-11 S.43E-11 9.99E-06 S.02E-09 O.OOE+OO BA-140 1.17E+OB 1.03E+OS O.OOE+OO 3.34E+04 6.12E+04 S.94E+07 6.B4E+06 O.OOE+OO BA-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BA-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO LA-140 1.95E+01 6.B1E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.90E+OS 2.29E+OO O.OOE+OO LA-142 4.09E-11 1.30E-11 O.OOE+OO O.OOE+OO O.OOE+OO 2.S9E-06 4.09E-12 O.OOE+OO CE-141 2.19E+04 1.09E+04 O.OOE+OO 4.7BE+03 O.OOE+OO 1.36E+07 1.62E+03 O.OOE+OO CE-143 1.B9E+02 1.03E+OS O.OOE+OO 4.30E+01 O.OOE+OO 1.S0E+06 1.49E+01 O.OOE+OO CE-144 1.62E+06 S.09E+OS O.OOE+OO 2.B2E+OS O.OOE+OO 1.33E+OB B.66E+04 O.OOE+OO PR-143 7.19E+02 2.16E+02 O.OOE+OO 1.17E+02 O.OOE+OO 7.76E+OS 3.S7E+01 O.OOE+OO PR-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO ND-147 4.4BE+02 3.63E+02 O.OOE+OO 1.99E+02 O.OOE+OO S.7SE+OS 2.B1 E+01 O.OOE+OO W-1B7 2.92E+04 1.73E+04 O.OOE+OO O.OOE+OO O.OOE+OO 2.43E+06 7.7SE+03 O.OOE+OO NP-239 1.73E+01 1.24E+OO O.OOE+OO 3.S9E+OO O.OOE+OO 9.20E+04 B.74E-01 O.OOE+OO

Units for H-3 and C-14 are: mrem/yr per uCi/m3 7-26

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 7-15 MILK INGESTION - TEEN AGE GROUP (RA1(MI}J)

Age Group: Teen Pathway: Milk Units: m2 x mrem/yr per !-ICi/sec Nuclide Bone Liver Thyroid Kidney Lung Gi-LLi TBody Skin H-3

O.OOE+OO B.99E+02 B.99E+02 B.99E+02 B.99E+02 B.99E+02 B.99E+02 O.OOE+OO C-14

1.BBE+05 3.76E+04 3.76E+04 3.76E+04 3.76E+04 3.76E+04 3.76E+04 1.BBE+05 NA-24 4.30E+06 4.30E+06 4.30E+06 4.30E+06 4.30E+06 4.30E+06 4.30E+06 O.OOE+OO P-32 3.16E+10 1.96E+09 O.OOE+OO O.OOE+OO O.OOE+OO 2.65E+09 1.22E+09 O.OOE+OO CR-51 O.OOE+OO O.OOE+OO 2.77E+04 1.09E+04 7.12E+04 B.3BE+06 4.99E+04 O.OOE+OO MN-54 O.OOE+OO 1.40E+07 O.OOE+OO 4.1BE+06 O.OOE+OO 2.B7E+07 2.7BE+06

O.OOE+OO MN-56 O.OOE+OO 7.03E-03 O.OOE+OO B.B9E-03 O.OOE+OO 4.63E-01 1.25E-03 O.OOE+OO FE-55 4.45E+07 3.16E+07 O.OOE+OO O.OOE+OO 2.00E+07 1.37E+07 7.36E+06 O.OOE+OO FE-59 5.1BE+07 1.21 E+OB O.OOE+OO O.OOE+OO 3.B1E+07 2.B6E+OB 4.67E+07 O.OOE+OO CO-5B O.OOE+OO 7.94E+06 O.OOE+OO O.OOE+OO O.OOE+OO 1.09E+OB 1.B3E+07 O.OOE+OO CO-60 O.OOE+OO 2.7BE+07 O.OOE+OO O.OOE+OO O.OOE+OO 3.62E+OB 6.26E+07 O.OOE+OO NI-63 1.1BE+10 B.35E+OB O.OOE+OO O.OOE+OO O.OOE+OO 1.33E+OB 4.01E+OB O.OOE+OO NI-65 6.BBE-01 B.79E-02 O.OOE+OO O.OOE+OO O.OOE+OO 4.77E+00 4.01E-02 O.OOE+OO CU-64 O.OOE+OO 4.22E+04 O.OOE+OO 1.07E+05 O.OOE+OO 3.27E+06 1.9BE+04 O.OOE+OO ZN-65 2.11E+09 7.31E+09 O.OOE+OO 4.6BE+09 O.OOE+OO 3.10E+09 3.41 E+09 O.OOE+OO ZN-69 9.3BE-12 1.79E-11 O.OOE+OO 1.17E-11 O.OOE+OO 3.29E-11 1.25E-12 O.OOE+OO BR-B3 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.B4E-01 O.OOE+OO BR-B4 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-B5 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-B6 O.OOE+OO 4.73E+09 O.OOE+OO O.OOE+OO O.OOE+OO 7.01 E+OB 2.22E+09 O.OOE+OO RB-BB O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-B9 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO SR-B9 2.67E+09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.1BE+OB 7.66E+07 O.OOE+OO SR-90 6.61E+10 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.B6E+09 1.63E+10 O.OOE+OO SR-91 5.30E+04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.40E+05 2.11 E+03 O.OOE+OO SR-92 9.15E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.33E+01 3.90E-02 O.OOE+OO Y-90 1.30E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.0BE+06 3.51E+00 O.OOE+OO Y-91M 1.03E-19 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.B7E-1B O.OOE+OO O.OOE+OO Y-91 1.5BE+04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.4BE+06 4.24E+02 O.OOE+OO Y-92 1.0BE-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.97E+OO 3.13E-06 O.OOE+OO Y-93 4.10E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.25E+04 1.12E-02 O.OOE+OO ZR-95 1.65E+03 5.21E+02 O.OOE+OO 7.65E+02 O.OOE+OO 1.20E+06 3.5BE+02 O.OOE+OO ZR-97 7.B9E-01 1.56E-01 O.OOE+OO 2.37E-01 O.OOE+OO 4.23E+04 7.19E-02 O.OOE+OO NB-95 1.41E+05 7.B2E+04 O.OOE+OO 7.5BE+04 O.OOE+OO 3.34E+OB 4.30E+04 O.OOE+OO MO-99 O.OOE+OO 4.47E+07 O.OOE+OO 1.02E+OB O.OOE+OO B.OOE+07 B.52E+06 O.OOE+OO TC-99M 5.7BE+OO 1.61E+01 O.OOE+OO 2.40E+02 B.94E+00 1.06E+04 2.09E+02 O.OOE+OO TC-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RU-103 1.B1E+03 O.OOE+OO O.OOE+OO 6.3BE+03 O.OOE+OO 1.51 E+05 7.74E+02 O.OOE+OO RU-105 1.57E-03 O.OOE+OO O.OOE+OO 1.9BE-02 O.OOE+OO 1.27E+OO 6.0BE-04 O.OOE+OO

Units for H-3 and C-14 are: mrem/yr per uCi/m 3 7-27

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Age Group: Teen Pathway: Milk Units: m2 x mrem/yr per JjCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gi-LLi TBody Skin RU-106 3.7SE+04 O.OOE+OO O.OOE+OO 7.24E+04 O.OOE+OO 1.BOE+06 4.73E+03 O.OOE+OO AG-110M 9.63E+07 9.11E+07 O.OOE+OO 1.74E+OB O.OOE+OO 2.S6E+10 S.S4E+07 O.OOE+OO TE-12SM 3.01E+07 1.0BE+07 B.40E+06 O.OOE+OO O.OOE+OO B.B7E+07 4.02E+06 O.OOE+OO TE-127M B.44E+07 2.99E+07 2.01E+07 3.42E+OB O.OOE+OO 2.10E+OB 1.00E+07 O.OOE+OO TE-127 1.21 E+03 4.30E+02 B.37E+02 4.91E+03 O.OOE+OO 9.37E+04 2.61E+02 O.OOE+OO TE-129M 1.10E+OB 4.09E+07 3.SSE+07 4.61E+OB O.OOE+OO 4.13E+OB 1.74E+07 O.OOE+OO TE-129 S.36E-10 2.00E-10 3.B3E-10 2.2SE-09 O.OOE+OO 2.93E-09 1.30E-10 O.OOE+OO TE-131M 6.S7E+OS 3.1SE+OS 4.74E+OS 3.29E+06 O.OOE+OO 2.S3E+07 2.63E+OS O.OOE+OO TE-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TE-132 4.30E+06 2.72E+06 2.B7E+06 2.61E+07 O.OOE+OO B.62E+07 2.S6E+06 O.OOE+OO 1-130 7.37E+OS 2.13E+06 1.74E+OB 3.2BE+06 O.OOE+OO 1.64E+06 B.S1E+OS O.OOE+OO 1-131 S.37E+OB 7.S2E+OB 2.19E+11 1.29E+09 O.OOE+OO 1.49E+OB 4.04E+OB O.OOE+OO 1-132 2.97E-01 7.77E-01 2.62E+01 1.22E+00 O.OOE+OO 3.3BE-01 2.79E-01 O.OOE+OO 1-133 7.09E+06 1.20E+07 1.6BE+09 2.11E+07 O.OOE+OO 9.11E+06 3.67E+06 O.OOE+OO 1-134 3.S1E-12 9.29E-12 1.SSE-10 1.46E-11 O.OOE+OO 1.22E-13 3.34E-12 O.OOE+OO 1-13S 2.26E+04 S.B2E+04 3.74E+06 9.19E+04 O.OOE+OO 6.4SE+04 2.16E+04 O.OOE+OO CS-134 9.B1E+09 2.31E+10 O.OOE+OO 7.34E+09 2.BOE+09 2.B7E+OB 1.07E+10 O.OOE+OO CS-136 4.47E+OB 1.76E+09 O.OOE+OO 9.SBE+OB 1.S1E+OB 1.42E+OB 1.1BE+09 O.OOE+OO CS-137 1.34E+10 1.7BE+10 O.OOE+OO 6.06E+09 2.35E+09 2.S3E+OB 6.20E+09 O.OOE+OO CS-13B O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BA-139 7.04E-OB 4.9SE-11 O.OOE+OO 4.67E-11 3.41E-11 6.2BE-07 2.0SE-09 O.OOE+OO BA-140 4.8SE+07 S.9SE+04 O.OOE+OO 2.02E+04 4.00E+04 7.49E+07 3.13E+06 O.OOE+OO BA-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BA-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO LA-140 B.13E+00 4.00E+00 O.OOE+OO O.OOE+OO O.OOE+OO 2.29E+OS 1.06E+00 O.OOE+OO LA-142 1.69E-11 7.S3E-12 O.OOE+OO O.OOE+OO O.OOE+OO 2.29E-07 1.B7E-12 O.OOE+OO CE-141 B.BBE+03 S.93E+03 O.OOE+OO 2.79E+03 O.OOE+OO 1.70E+07 6.B1E+02 O.OOE+OO CE-143 7.71E+01 S.61E+04 O.OOE+OO 2.S2E+01 O.OOE+OO 1.69E+06 6.27E+00 O.OOE+OO CE-144 6.SBE+OS 2.72E+OS O.OOE+OO 1.63E+OS O.OOE+OO 1.66E+OB 3.S4E+04 O.OOE+OO PR-143 2.91E+02 1.16E+02 O.OOE+OO 6.74E+01 O.OOE+OO 9.S6E+OS 1.4SE+01 O.OOE+OO PR-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NO-147 1.83E+02 1.9BE+02 O.OOE+OO 1.17E+02 O.OOE+OO 7.16E+OS 1.19E+01 O.OOE+OO W-1B7 1.20E+04 9.B1E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.6SE+06 3.44E+03 O.OOE+OO NP-239 7.03E+OO 6.63E-01 O.OOE+OO 2.0BE+00 O.OOE+OO 1.07E+OS 3.6BE-01 O.OOE+OO

Units for H-3 and C-14 are: mrem/yr per uCi/m 3 7-2B

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 7-16 MILK INGESTION - ADULT AGE GROUP (RAI(MI)J)

Age Group: Adult Pathway: Milk Units: m 2 x mrem/yr per J,lCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gi-LLi TBody Skin H-3

O.OOE+OO 6.90E+02 6.90E+02 6.90E+02 6.90E+02 6.90E+02 6.90E+02 O.OOE+OO C-14

1.02E+OS 2.04E+04 2.04E+04 2.04E+04 2.04E+04 2.04E+04 2.04E+04 O.OOE+OO NA-24 2.47E+06 2.47E+06 2.47E+06 2.47E+06 2.47E+06 2.47E+06 2.47E+06 O.OOE+OO P-32 1.71E+10 1.06E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.92E+09 6.61E+08 O.OOE+OO CR-S1 O.OOE+OO O.OOE+OO 1.71E+04 6.29E+03 3.79E+04 7.18E+06 2.86E+04 O.OOE+OO MN-S4 O.OOE+OO 8.41E+06 O.OOE+OO 2.S0E+06 O.OOE+OO 2.S8E+07 1.61E+06 O.OOE+OO MN-S6 O.OOE+OO 3.96E-03 O.OOE+OO S.03E-03 O.OOE+OO 1.26E-01 7.03E-04 O.OOE+OO FE-SS 2.S1E+07 1.74E+07 O.OOE+OO O.OOE+OO 9.68E+06 9.9SE+06 4.0SE+06 O.OOE+OO FE-S9 2.97E+07 6.98E+07 O.OOE+OO O.OOE+OO 1.9SE+07 2.33E+08 2.67E+07 O.OOE+OO CO-S8 O.OOE+OO 4.72E+06 O.OOE+OO O.OOE+OO O.OOE+OO 9.S6E+07 1.06E+07 O.OOE+OO CO-60 O.OOE+OO 1.64E+07 O.OOE+OO O.OOE+OO O.OOE+OO 3.08E+08 3.62E+07 O.OOE+OO NI-63 6.73E+09 4 .66E+08 O.OOE+OO O.OOE+OO O.OOE+OO 9.73E+07 2.26E+08 O.OOE+OO NI-6S 3.76E-01 4.88E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.24E+OO 2.23E-02 O.OOE+OO CU-64 O.OOE+OO 2.37E+04 O.OOE+OO S.97E+04 O.OOE+OO 2.02E+06 1.11E+04 O.OOE+OO ZN-6S 1.37E+09 4.36E+09 O.OOE+OO 2.92E+09 O.OOE+OO 2.7SE+09 1.97E+09 O.OOE+OO ZN-69 S.09E-12 9.74E-12 O.OOE+OO 6.33E-12 O.OOE+OO 1.46E-12 6.78E-13 O.OOE+OO BR-83 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.44E-01 9.99E-02 O.OOE+OO BR-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-8S O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-86 O.OOE+OO 2.60E+09 O.OOE+OO O.OOE+OO O.OOE+OO S.12E+08 1.21E+09 O.OOE+OO RB-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO SR-89 1.4SE+09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.33E+08 4.16E+07 O.OOE+OO SR-90 4.68E+10 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.3SE+09 1.1SE+10 O.OOE+OO SR-91 2.88E+04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.37E+OS 1.16E+03 O.OOE+OO SR-92 S.OOE-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.90E+OO 2.16E-02 O.OOE+OO Y-90 7.10E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 7.S3E+OS 1.90E+OO O.OOE+OO Y-91M S.63E-20 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.6SE-19 O.OOE+OO O.OOE+OO Y-91 8.S9E+03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4 .73E+06 2.30E+02 O.OOE+OO Y-92 S.8SE-OS O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.02E+OO 1.71E-06 O.OOE+OO Y-93 2.22E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 7.0SE+03 6.14E-03 O.OOE+OO ZR-9S 9.44E+02 3.03E+02 O.OOE+OO 4.7SE+02 O.OOE+OO 9.S9E+OS 2.0SE+02 O.OOE+OO ZR-97 4.33E-01 8.74E-02 O.OOE+OO 1.32E-01 O.OOE+OO 2.71E+04 4.00E-02 O.OOE+OO NB-9S 8.27E+04 4.60E+04 O.OOE+OO 4.S4E+04 O.OOE+OO 2.79E+08 2.47E+04 O.OOE+OO MO-99 O.OOE+OO 2.47E+07 O.OOE+OO S.60E+07 O.OOE+OO S.74E+07 4.71E+06 O.OOE+OO TC-99M 3.33E+OO 9.41E+OO O.OOE+OO 1.43E+02 4.61E+OO S.S7E+03 1.20E+02 O.OOE+OO TC-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RU-103 1.02E+03 O.OOE+OO O.OOE+OO 3.88E+03 O.OOE+OO 1.19E+OS 4.39E+02 O.OOE+OO RU-10S 8.S8E-04 O.OOE+OO O.OOE+OO 1.11E-02 O.OOE+OO S.2SE-01 3.39E-04 O.OOE+OO

Units for H-3 and C-14 are: mrem/yr per uCi/m 3 7-29

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Age Group: Adult Pathway: Milk Units: m 2 x mrem/yr per !-ICi/sec Nuclide Bone Liver Thyroid Kidney Lung Gi-LLi TBody Skin RU-106 2.04E+04 O.OOE+OO O.OOE+OO 3.94E+04 O.OOE+OO 1.32E+06 2.SBE+03 O.OOE+OO AG-110M S.B2E+07 S.39E+07 O.OOE+OO 1.06E+OB O.OOE+OO 2.20E+10 3.20E+07 O.OOE+OO TE-12SM 1.63E+07 S.91E+06 4.90E+06 6.63E+07 O.OOE+OO 6.S1E+07 2.1BE+06 O.OOE+OO TE-127M 4.SBE+07 1.64E+07 1.17E+07 1.B6E+OB O.OOE+OO 1.S4E+OB S.SBE+06 O.OOE+OO TE-127 6.SSE+02 2.3SE+02 4.BSE+02 2.67E+03 O.OOE+OO S.16E+04 1.42E+02 O.OOE+OO TE-129M 6.02E+07 2.2SE+07 2.07E+07 2.S1E+OB O.OOE+OO 3.03E+OB 9.S2E+06 O.OOE+OO TE-129 2.91E-10 1.09E-10 2.23E-10 1.22E-09 O.OOE+OO 2.20E-10 7.09E-11 O.OOE+OO TE-131M 3.61E+OS 1.77E+OS 2.BOE+OS 1.79E+06 O.OOE+OO 1.7SE+07 1.47E+OS O.OOE+OO TE-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TE-132 2.41E+06 1.S6E+06 1.72E+06 1.S0E+07 O.OOE+OO 7.36E+07 1.46E+06 O.OOE+OO 1-130 4.19E+OS 1.24E+06 1.0SE+OB 1.93E+06 O.OOE+OO 1.06E+06 4.BBE+OS O.OOE+OO 1-131 2.96E+OB 4.23E+OB 1.39E+11 7.26E+OB O.OOE+OO 1.12E+OB 2.43E+OB O.OOE+OO 1-132 1.67E-01 4.4BE-01 1.S7E+01 7.13E-01 O.OOE+OO B.41E-02 1.S7E-01 O.OOE+OO 1-133 3.BBE+06 6.76E+06 9.93E+OB 1.1BE+07 O.OOE+OO 6.07E+06 2.06E+06 O.OOE+OO 1-134 1.97E-12 S.36E-12 9.29E-11 B.S2E-12 O.OOE+OO 4.67E-1S 1.92E-12 O.OOE+OO 1-13S 1.27E+04 3.33E+04 2.20E+06 S.34E+04 O.OOE+OO 3.76E+04 1.23E+04 O.OOE+OO CS-134 S.6SE+09 1.34E+10 O.OOE+OO 4.3SE+09 1.44E+09 2.3SE+OB 1.10E+10 O.OOE+OO CS-136 2.63E+OB 1.04E+09 O.OOE+OO S.77E+OB 7.91E+07 1.1BE+OB 7.46E+OB O.OOE+OO CS-137 7.3BE+09 1.01E+10 O.OOE+OO 3.43E+09 1.14E+09 1.9SE+OB 6.61E+09 O.OOE+OO CS-13B O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BA-139 3.B1E-OB 2.71 E-11 O.OOE+OO 2.S4E-11 1.S4E-11 6.7SE-OB 1.12E-09 O.OOE+OO BA-140 2.69E+07 3.3BE+04 O.OOE+OO 1.1SE+04 1.93E+04 S.S4E+07 1.76E+06 O.OOE+OO BA-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BA-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO LA-140 4.S3E+00 2.2BE+00 O.OOE+OO O.OOE+OO O.OOE+OO 1.6BE+OS 6.03E-01 O.OOE+OO LA-142 9.39E-12 4.27E-12 O.OOE+OO O.OOE+OO O.OOE+OO 3.12E-OB 1.06E-12 O.OOE+OO CE-141 4.B4E+03 3.2BE+03 O.OOE+OO 1.S2E+03 O.OOE+OO 1.2SE+07 3.72E+02 O.OOE+OO CE-143 4.19E+01 3.10E+04 O.OOE+OO *1.37E+01 O.OOE+OO 1.16E+06 3.43E+00 O.OOE+OO CE-144 3.SBE+OS 1.S0E+OS O.OOE+OO B.B7E+04 O.OOE+OO 1.21E+OB 1.92E+04 O.OOE+OO PR-143 1.SBE+02 6.34E+01 O.OOE+OO 3.66E+01 O.OOE+OO 6.93E+OS 7.B4E+OO O.OOE+OO PR-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NO-147 9.4BE+01 1.10E+02 O.OOE+OO 6.41E+01 O.OOE+OO S.26E+OS 6.S6E+00 O.OOE+OO W-1B7 6.SBE+03 S.SOE+03 O.OOE+OO O.OOE+OO O.OOE+OO 1.BOE+06 1.92E+03 O.OOE+OO NP-239 3.69E+00 3.62E-01 O.OOE+OO 1.13E+00 O.OOE+OO 7.43E+04 2.00E-01 O.OOE+OO

Units for H-3 and C-14 are: mrem/yr per uCi/m3 7-30

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 7-17 MEAT INGESTION - CHILD AGE GROUP (RA1(ME)J)

Age Group: Child Pathway: Meat Units: m 2 x mrem/yr per ... Ci/sec Nuclide Bone Liver Thyroid Kidney Lung Gi-LLi TBody Skin H-3

O.OOE+OO 2.12E+02 2.12E+02 2.12E+02 2.12E+02 2.12E+02 2.12E+02 O.OOE+OO C-14

S.74E+04 1.1SE+04 1.1SE+04 1.1SE+04 1.1SE+04 1.1SE+04 1.1SE+04 O.OOE+OO NA-24 1.B9E-03 1.B9E-03 1.B9E-03 1.B9E-03 1.B9E-03 1.89E-03 1.B9E-03 O.OOE+OO P-32 7.43E+09 3.4BE+OB O.OOE+OO O.OOE+OO O.OOE+OO 2.0SE+08 2.B7E+OB O.OOE+OO CR-S1 O.OOE+OO O.OOE+OO 4.BBE+03 1.33E+03 B.90E+03 4.66E+OS 8.7BE+03 O.OOE+OO MN-S4 O.OOE+OO B.01E+06 O.OOE+OO 2.2SE+06 O.OOE+OO 6.72E+06 2.13E+06 O.OOE+OO MN-S6 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO FE-SS 4.S7E+OB 2.42E+OB O.OOE+OO O.OOE+OO 1.37E+OB 4.49E+07 7.S1E+07 O.OOE+OO FE-S9 3.76E+OB 6.09E+OB O.OOE+OO O.OOE+OO 1.76E+OB 6.34E+OB 3.03E+OB O.OOE+OO CO-SB O.OOE+OO 1.64E+07 O.OOE+OO O.OOE+OO O.OOE+OO 9.S9E+07 S.03E+07 O.OOE+OO CO-60 O.OOE+OO 6.93E+07 O.OOE+OO O.OOE+OO O.OOE+OO 3.84E+OB 2.04E+OB O.OOE+OO NI-63 2.91E+10 1.S6E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.0SE+OB 9.91E+OB O.OOE+OO NI-6S O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CU-64 O.OOE+OO 2.BSE-07 O.OOE+OO 6.B9E-07 O.OOE+OO 1.34E-OS 1.72E-07 O.OOE+OO ZN-6S 3.7SE+OB 1.00E+09 O.OOE+OO 6.30E+OB O.OOE+OO 1.76E+OB 6.22E+OB O.OOE+OO ZN-69 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-B3 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-B4 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-BS O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-86 O.OOE+OO S.79E+OB O.OOE+OO O.OOE+OO O.OOE+OO 3.72E+07 3.S6E+OB O.OOE+OO RB-B8 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-B9 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO SR-B9 4.B1E+OB O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.86E+07 1.3BE+07 O.OOE+OO SR-90 1.04E+10 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.40E+OB 2.64E+09 O.OOE+OO SR-91 2.36E-10 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO S.20E-10 B.B9E-12 O.OOE+OO SR-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-90 1.74E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.9SE+OS 4 .6SE+OO O.OOE+OO Y-91M O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-91 1.BOE+06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.40E+OB 4.B2E+04 O.OOE+OO Y-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-93 7.24E-12 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.0BE-07 1.99E-13 O.OOE+OO ZR-9S 2.67E+06 S.86E+OS O.OOE+OO B.39E+OS O.OOE+OO 6.11E+OB S.22E+OS O.OOE+OO ZR-97 3.24E-OS 4.68E-06 O.OOE+OO 6.72E-06 O.OOE+OO 7.09E-01 2.76E-06 O.OOE+OO NB-9S 3.11E+06 1.21 E+06 O.OOE+OO 1.14E+06 O.OOE+OO 2.24E+09 8.64E+OS O.OOE+OO MO-99 O.OOE+OO 1.1SE+OS O.OOE+OO 2.4SE+OS O.OOE+OO 9.S0E+04 2.B4E+04 O.OOE+OO TC-99M O.OOE+OO 1.26E-20 O.OOE+OO 1.B3E-19 O.OOE+OO 7.16E-1B 2.09E-19 O.OOE+OO TC-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RU-103 1.SSE+OB O.OOE+OO O.OOE+OO 3.90E+OB O.OOE+OO 4.01E+09 S.96E+07 O.OOE+OO RU-10S O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

Units for H-3 and C-14 are: mrem/yr per uCi/m 3 7-31

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Age Group: Child Pathway: Meat Units: m 2 x mrem/yr per &.ICi/sec Nuclide Bone Liver Thyroid Kidney Lung Gi-LLi TBody Skin RU-106 4.44E+09 O.OOE+OO O.OOE+OO 5.99E+09 O.OOE+OO 6.90E+10 5.54E+OB O.OOE+OO AG-110M B.39E+06 5.67E+06 O.OOE+OO 1.06E+07 O.OOE+OO 6.74E+OB 4.53E+06 O.OOE+OO TE-125M 5.70E+OB 1.54E+OB 1.60E+OB O.OOE+OO O.OOE+OO 5.50E+OB 7.60E+07 O.OOE+OO TE-127M 1.7BE+09 4.7BE+OB 4.24E+OB 5.06E+09 O.OOE+OO 1.44E+09 2.11E+OB O.OOE+OO TE-127 3.4BE-10 9.39E-11 2.41E-10 9.91E-10 O.OOE+OO 1.36E-OB 7.47E-11 O.OOE+OO TE-129M 1.79E+09 5.00E+OB 5.77E+OB 5.26E+09 O.OOE+OO 2.1BE+09 2.7BE+OB O.OOE+OO TE-129 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TE-131M 7.06E+02 2.44E+02 5.02E+02 2.36E+03 O.OOE+OO 9.91E+03 2.60E+02 O.OOE+OO TE-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TE-132 2.14E+06 9.47E+05 1.3BE+06 B.79E+06 O.OOE+OO 9.54E+06 1.14E+06 O.OOE+OO 1-130 3.01E-06 6.0BE-06 6.70E-04 9.09E-06 O.OOE+OO 2.B4E-06 3.13E-06 O.OOE+OO 1-131 1.66E+07 1.67E+07 5.51E+09 2.74E+07 O.OOE+OO 1.4BE+06 9.47E+06 O.OOE+OO 1-132 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1-133 5.B5E-01 7.24E-01 1.34E+02 1.21 E+OO O.OOE+OO 2.92E-01 2.74E-01 O.OOE+OO 1-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1-135 6.09E-17 1.10E-16 9.71E-15 1.6BE-16 O.OOE+OO B.36E-17 5.19E-17 O.OOE+OO CS-134 9.22E+OB 1.51 E+09 O.OOE+OO 4.69E+OB 1.6BE+OB B.16E+06 3.19E+OB O.OOE+OO CS-136 1.61E+07 4.44E+07 O.OOE+OO 2.36E+07 3.52E+06 1.56E+06 2.B7E+07 O.OOE+OO CS-137 1.33E+09 1.28E+09 O.OOE+OO 4.16E+OB 1.50E+OB 7.99E+06 1.BBE+OB O.OOE+OO CS-13B O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BA-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BA-140 4.39E+07 3.B5E+04 O.OOE+OO 1.25E+04 2.29E+04 2.23E+07 2.56E+06 O.OOE+OO BA-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BA-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO LA-140 5.72E-02 2.00E-02 O.OOE+OO O.OOE+OO O.OOE+OO 5.57E+02 6.74E-03 O.OOE+OO LA-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CE-141 2.22E+04 1.11E+04 O.OOE+OO 4.B6E+03 O.OOE+OO 1.3BE+07 1.64E+03 O.OOE+OO CE-143 3.36E-02 1.B2E+01 O.OOE+OO 7.64E-03 O.OOE+OO 2.67E+02 2.64E-03 O.OOE+OO CE-144 2.32E+06 7.26E+05 O.OOE+OO 4.02E+05 O.OOE+OO 1.B9E+OB 1.24E+05 O.OOE+OO PR-143 3.36E+04 1.01E+04 O.OOE+OO 5.46E+03 O.OOE+OO 3.62E+07 1.67E+03 O.OOE+OO PR-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NO-147 1.19E+04 9.66E+03 O.OOE+OO 5.30E+03 O.OOE+OO 1.53E+07 7.4BE+02 O.OOE+OO W-1B7 3.45E-02 2.04E-02 O.OOE+OO O.OOE+OO O.OOE+OO 2.B7E+OO 9.16E-03 O.OOE+OO NP-239 4.35E-01 3.12E-02 O.OOE+OO 9.03E-02 O.OOE+OO 2.31E+03 2.19E-02 O.OOE+OO

Units for H-3 and C-14 are: mrem/yr per uCi/m3 7-32

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 7-18 MEAT INGESTION - TEEN AGE GROUP (RAI(ME)J)

Age Group: Teen Pathway: Meat Units: m 2 x mrem/yr per !-ICi/sec Nuclide Bone Liver Th~oid Kidney Lung Gi-LLi TBody Skin H-3

O.OOE+OO 1.7SE+02 1.7SE+02 1.7SE+02 1.7SE+02 1.7SE+02 1.7SE+02 O.OOE+OO C-14

3.06E+04 6.11 E+03 6.11E+03 6.11E+03 6.11E+03 6.11E+03 6.11E+03 O.OOE+OO NA-24 1.19E-03 1.19E-03 1.19E-03 1.19E-03 1.19E-03 1.19E-03 1.19E-03 O.OOE+OO P-32 3.94E+09 2.44E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.31E+08 1.S3E+08 O.OOE+OO CR-S1 O.OOE+OO O.OOE+OO 3.13E+03 1.23E+03 8.04E+03 9.47E+OS S.63E+03 O.OOE+OO MN-S4 O.OOE+OO 7.00E+06 O.OOE+OO 2.09E+06 O.OOE+OO 1.44E+07 1.39E+06 O.OOE+OO MN-S6 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO FE-SS 2.38E+08 1.69E+08 O.OOE+OO O.OOE+OO 1.07E+08 7.31E+07 3.94E+07 O.OOE+OO FE-S9 2.12E+08 4.9SE+08 O.OOE+OO O.OOE+OO 1.S6E+08 1.17E+09 1.91 E+08 O.OOE+OO CO-S8 O.OOE+OO 1.41E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.94E+08 3.24E+07 O.OOE+OO CO-60 O.OOE+OO S.83E+07 O.OOE+OO O.OOE+OO O.OOE+OO 7.60E+08 1.31 E+08 O.OOE+OO NI-63 1.S2E+10 1.07E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.71E+08 S.1SE+08 O.OOE+OO NI-6S O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CU-64 O.OOE+OO 2.12E-07 O.OOE+OO S.37E-07 O.OOE+OO 1.6SE-OS 9.98E-08 O.OOE+OO ZN-6S 2.S0E+08 8.69E+08 O.OOE+OO S.S6E+08 O.OOE+OO 3.68E+08 4.0SE+08 O.OOE+OO ZN-69 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-83 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-8S O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-86 O.OOE+OO 4.08E+08 O.OOE+OO O.OOE+OO O.OOE+OO 6.04E+07 1.92E+08 O.OOE+OO RB-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO SR-89 2.S4E+08 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.03E+07 7.29E+06 O.OOE+OO SR-90 8.0SE+09 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.26E+08 1.99E+09 O.OOE+OO SR-91 1.26E-10 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO S.70E-10 4.99E-12 O.OOE+OO SR-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-90 9.18E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 7.S7E+OS 2.47E+OO O.OOE+OO Y-91M O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-91 9.S4E+OS O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.91E+08 2.S6E+04 O.OOE+OO Y-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-93 3.86E-12 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.18E-07 1.06E-13 O.OOE+OO ZR-9S 1.S0E+06 4.74E+OS O.OOE+OO 6.96E+OS O.OOE+OO 1.09E+09 3.26E+OS O.OOE+OO ZR-97 1.74E-OS 3.44E-06 O.OOE+OO S.22E-06 O.OOE+OO 9.32E-01 1.S9E-06 O.OOE+OO NB-9S 1.80E+06 9.98E+OS O.OOE+OO 9.68E+OS O.OOE+OO 4.27E+09 S.49E+OS O.OOE+OO MO-99 O.OOE+OO 8.2SE+04 O.OOE+OO 1.89E+OS O.OOE+OO 1.48E+OS 1.S7E+04 O.OOE+OO TC-99M O.OOE+OO 1.02E-20 O.OOE+OO 1.S2E-19 O.OOE+OO 6.70E-18 1.32E-19 O.OOE+OO TC-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RU-103 8.S7E+07 O.OOE+OO O.OOE+OO 3.02E+08 O.OOE+OO 7.16E+09 3.66E+07 O.OOE+OO RU-10S O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

Units for H-3 and C-14 are: mrem/yr per uCi/m 3 7-33

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Age Group: Teen Pathway: Meat Units: m 2 x mrem/yr per J.lCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gi-LLi TBody Skin RU-106 2.36E+09 O.OOE+OO O.OOE+OO 4.SSE+09 O.OOE+OO 1.13E+11 2.97E+OB O.OOE+OO AG-110M S.06E+OS 4.79E+06 O.OOE+OO 9.13E+06 O.OOE+OO 1.3SE+09* 2.91E+06 O.OOE+OO TE-12SM 3.03E+OB 1.09E+OB B.4BE+07 O.OOE+OO O.OOE+OO B.9SE+OB 4.06E+07 O.OOE+OO TE-127M 9.42E+OB 3.34E+OB 2.24E+OB 3.B2E+09 O.OOE+OO 2.3SE+09 1.12E+OB O.OOE+OO TE-127 1.BSE-10 S.S6E-11 1.2BE-10 7.S0E-10 O.OOE+OO 1.43E-OB 3.99E-11 O.OOE+OO TE-129M 9.S0E+OB 3.S2E+OB 3.06E+OB 3.97E+09 O.OOE+OO 3.S7E+09 1.S0E+OB O.OOE+OO TE-129 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TE-131M 3.79E+02 1.B2E+02 2.74E+02 1.90E+03 O.OOE+OO 1.46E+04 1.S2E+02 O.OOE+OO TE-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TE-132 1.17E+OS 7.42E+OS 7.B3E+OS 7.12E+OS O.OOE+OO 2.3SE+07 6.99E+OS O.OOE+OO 1-130 1.6BE-06 4.B7E-06 3.97E-04 7.S0E-06 O.OOE+OO 3.74E-06 1.94E-06 O.OOE+OO 1-131 B.94E+06 1.2SE+07 3.6SE+09 2.1SE+07 O.OOE+OO 2.47E+OS 6.72E+06 O.OOE+OO 1-132 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1-133 3.1SE-01 S.34E-01 7.46E+01 9.37E-01 O.OOE+OO 4.04E-01 1.63E-01 O.OOE+OO 1-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1-13S 3.37E-17 B.67E-17 S.S7E-1S 1.37E-16 O.OOE+OO 9.60E-17 3.21E-17 O.OOE+OO CS-134 S.23E+OB 1.23E+09 O.OOE+OO 3.91E+OB 1.49E+OB 1.S3E+07 S.71E+OB O.OOE+OO CS-136 9.3SE+06 3.SBE+07 O.OOE+OO 2.00E+07 3.16E+OS 2.96E+06 2.47E+07 O.OOE+OO CS-137 7.24E+OB 9.S3E+OB O.OOE+OO 3.2BE+OB 1.27E+OB 1.37E+07 3.3SE+OB O.OOE+OO CS-13B O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BA-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BA-140 2.3BE+07 2.92E+04 O.OOE+OO 9.B9E+03 1.96E+04 3.67E+07 1.S3E+06 O.OOE+OO BA-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BA-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO LA-140 3.12E-02 1.S3E-02 O.OOE+OO O.OOE+OO O.OOE+OO B.B1E+02 4.0BE-03 O.OOE+OO LA-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CE-141 1.1BE+04 7.B7E+03 O.OOE+OO 3.71E+03 O.OOE+OO 2.2SE+07 9.05E+02 O.OOE+OO CE-143 1.79E-02 1.30E+01 O.OOE+OO S.B4E-03 O.OOE+OO 3.92E+02 1.4SE-03 O.OOE+OO CE-144 1.23E+OS S.OBE+OS O.OOE+OO 3.04E+OS O.OOE+OO 3.09E+OB 6.60E+04 O.OOE+OO PR-143 1.77E+04 7.0BE+03 O.OOE+OO 4.12E+03 O.OOE+OO S.B3E+07 B.B3E+02 O.OOE+OO PR-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO ND-147 6.3SE+03 6.91E+03 O.OOE+OO 4 .06E+03 O.OOE+OO 2.49E+07 4.14E+02 O.OOE+OO W-1B7 1.BSE-02 1.S2E-02 O.OOE+OO O.OOE+OO O.OOE+OO 4.10E+OO S.31E-03 O.OOE+OO NP-239 2.31 E-01 2.1BE-02 O.OOE+OO 6.B4E-02 O.OOE+OO 3.S0E+03 1.21 E-02 O.OOE+OO

Units for H-3 and C-14 are: mrem/yr per uCilm 3 7-34

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 TABLE 7-19 MEAT INGESTION - ADULT AGE GROUP (RAI(ME)J)

Age Group: Adult Pathway: Meat Units: m2 x mrem/yr per !-ICi/sec Nuclide Bone Liver Thyroid Kidney Lung Gi-LLi TBody Skin H-3 .. O.OOE+OO 2.94E+02 2.94E+02 2.94E+02 2.94E+02 2.94E+02 2.94E+02 O.OOE+OO C-14 .. 3.62E+04 7.23E+03 7.23E+03 7.23E+03 7.23E+03 7.23E+03 7.23E+03 O.OOE+OO NA-24 1.49E-03 1.49E-03 1.49E-03 1.49E-03 1.49E-03 1.49E-03 1.49E-03 O.OOE+OO P-32 4.67E+09 2.90E+OB O.OOE+OO O.OOE+OO O.OOE+OO S.2SE+OB 1.BOE+OB O.OOE+OO CR-S1 O.OOE+OO O.OOE+OO 4.21E+03 1.SSE+03 9.3SE+03 1.77E+06 7.04E+03 O.OOE+OO MN-S4 O.OOE+OO 9.1BE+06 O.OOE+OO 2.73E+06 O.OOE+OO 2.B1E+07 1.7SE+06 O.OOE+OO MN-S6 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO FE-SS 2.93E+OB 2.03E+OB O.OOE+OO O.OOE+OO 1.13E+OB 1.16E+OB 4.72E+07 O.OOE+OO FE-S9 2.6SE+OB 6.24E+OB O.OOE+OO O.OOE+OO 1.74E+OB 2.0BE+09 2.39E+OB O.OOE+OO CO-SB O.OOE+OO 1.B3E+07 O.OOE+OO O.OOE+OO O.OOE+OO 3.70E+OB 4.09E+07 O.OOE+OO CO-60 O.OOE+OO 7.S2E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.41E+09 1.66E+OB O.OOE+OO NI-63 1.B9E+10 1.31E+09 O.OOE+OO O.OOE+OO O.OOE+OO 2.73E+OB 6.33E+OB O.OOE+OO NI-6S O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CU-64 O.OOE+OO 2.60E-07 O.OOE+OO 6.S6E-07 O.OOE+OO 2.22E-OS 1.22E-07 O.OOE+OO ZN-6S 3.S6E+OB 1.13E+09 O.OOE+OO 7.S7E+OB O.OOE+OO 7.13E+OB S.12E+OB O.OOE+OO ZN-69 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-B3 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-B4 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BR-BS O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-B6 O.OOE+OO 4.B9E+OB O.OOE+OO O.OOE+OO O.OOE+OO 9.64E+07 2.2BE+OB O.OOE+OO RB-BB O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RB-B9 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO SR-B9 3.01E+OB O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.B3E+07 B.6SE+06 O.OOE+OO SR-90 1.24E+10 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.S9E+OB 3.0SE+09 O.OOE+OO SR-91 1.49E-10 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 7.11E-10 6.03E-12 O.OOE+OO SR-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO V-90 1.09E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.16E+06 2.93E+OO O.OOE+OO V-91M O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO V-91 1.13E+06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.24E+OB 3.03E+04 O.OOE+OO V-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO V-93 4.S7E-12 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.4SE-07 1.26E-13 O.OOE+OO ZR-9S 1.B7E+06 6.01E+OS O.OOE+OO 9.44E+OS O.OOE+OO 1.91E+09 4.07E+OS O.OOE+OO ZR-97 2.09E-OS 4.21E-06 O.OOE+OO 6.36E-06 O.OOE+OO 1.30E+OO 1.93E-06 O.OOE+OO NB-9S 2.30E+06 1.2BE+06 O.OOE+OO 1.27E+06 O.OOE+OO 7.7BE+09 6.B9E+OS O.OOE+OO MO-99 O.OOE+OO 9.9BE+04 O.OOE+OO 2.26E+OS O.OOE+OO 2.31E+OS 1.90E+04 O.OOE+OO TC-99M O.OOE+OO 1.30E-20 O.OOE+OO 1.9BE-19 O.OOE+OO 7.70E-1B 1.66E-19 O.OOE+OO TC-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO RU-103 1.0SE+OB O.OOE+OO O.OOE+OO 4 .01E+OB O.OOE+OO 1.23E+10 4.S3E+07 O.OOE+OO RU-10S O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

.. Units for H-3 and C-14 are: mrem/yr per uCi/m 3 7-35

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 Age Group: Adult Pathway: Meat Units: m2 x mrem/yr per ",Ci/sec Nuclide Bone Liver Thyroid Kidney Lung Gi-LLi TBody Skin RU-106 2.BOE+09 O.OOE+OO O.OOE+OO 5.40E+09 O.OOE+OO 1.B1E+11 3.54E+OB O.OOE+OO AG-110M 6.6BE+06 6.1BE+06 O.OOE+OO 1.22E+07 O.OOE+OO 2.52E+09 3.67E+06 O.OOE+OO TE-125M 3.59E+OB 1.30E+OB 1.0BE+OB 1.46E+09 O.OOE+OO 1.43E+09 4.B1E+07 O.OOE+OO TE-127M 1.12E+09 3.99E+OB 2.B5E+OB 4.53E+09 O.OOE+OO 3.74E+09 1.36E+OB O.OOE+OO TE-127 2.1BE-10 7.B4E-11 1.62E-10 B.B9E-10 O.OOE+OO 1.72E-OB 4.72E-11 O.OOE+OO TE-129M 1.13E+09 4.23E+OB 3.B9E+OB 4.73E+09 O.OOE+OO 5.71E+09 1.79E+OB O.OOE+OO TE-129 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TE-131M 4.55E+02 2.23E+02 3.53E+02 2.25E+03 O.OOE+OO 2.21E+04 1.B6E+02 O.OOE+OO TE-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TE-132 1.43E+06 9.27E+05 1.02E+06 B.93E+06 O.OOE+OO 4.3BE+07 B.70E+05 O.OOE+OO 1-130 2.09E-06 6.17E-06 5.23E-04 9.62E-06 O.OOE+OO 5.31 E-06 2.43E-06 O.OOE+OO 1-131 1.0BE+07 1.54E+07 5.04E+09 2.64E+07 O.OOE+OO 4.06E+06 B.B2E+06 O.OOE+OO 1-132 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1-133 3.77E-01 6.55E-01 9.63E+01 1.14E+OO O.OOE+OO 5.B9E-01 2.00E-01 O.OOE+OO 1-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1-135 4.14E-17 1.0BE-16 7.15E-15 1.74E-16 O.OOE+OO 1.22E-16 4.00E-17 O.OOE+OO CS-134 6.5BE+OB 1.56E+09 O.OOE+OO 5.06E+OB 1.6BE+OB 2.74E+07 1.2BE+09 O.OOE+OO CS-136 1.20E+07 4.73E+07 O.OOE+OO 2.63E+07 3.61E+06 5.3BE+06 3.41E+07 O.OOE+OO CS-137 B.72E+OB 1.19E+09 O.OOE+OO 4.05E+OB 1.35E+OB 2.31E+07 7.B1E+OB O.OOE+OO CS-13B O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BA-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BA-140 2.BBE+07 3.62E+04 O.OOE+OO 1.23E+04 2.07E+04 5.93E+07 1.B9E+06 O.OOE+OO BA-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO BA-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO LA-140 3.BOE-02 1.91E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.40E+03 5.06E-03 O.OOE+OO LA-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CE-141 1.40E+04 9.50E+03 O.OOE+OO 4.41E+03 O.OOE+OO 3.63E+07 1.0BE+03 O.OOE+OO CE-143 2.13E-02 1.57E+01 O.OOE+OO 6.92E-03 O.OOE+OO 5.BBE+02 1.74E-03 O.OOE+OO CE-144 1.46E+06 6.09E+05 O.OOE+OO 3.61E+05 O.OOE+OO 4.93E+OB 7.B3E+04 O.OOE+OO PR-143 2.11 E+04 B.45E+03 O.OOE+OO 4.BBE+03 O.OOE+OO 9.23E+07 1.04E+03 O.OOE+OO PR-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO NO-147 7.22E+03 B.34E+03 O.OOE+OO 4.BBE+03 O.OOE+OO 4.00E+07 4.99E+02 O.OOE+OO W-1B7 2.22E-02 1.B6E-02 O.OOE+OO O.OOE+OO O.OOE+OO 6.0BE+OO 6.49E-03 O.OOE+OO NP-239 2.64E-01 2.60E-02 O.OOE+OO B.11E-02 O.OOE+OO 5.33E+03 1.43E-02 O.OOE+OO

Units for H-3 and C-14 are: mrem/yr per uCi/m3 7-36

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 7.4 METEOROLOGICAL DATA TABLE 7-20 PALISADES 10 YEAR XlQ - D/Q DATA USNRC COMPUTER CODE - XOQDOQ. VERSION 2 .0 RUN DATE: 2BNOV16

- - - - PALISADES XOQDOQB2 *** ** USING 01/01/2006 - 12131/2015 MET DATA *****

GROUND LEVEL RELEASE - TOP OF CONTAINMENT BUILDING SPECIFIC POINTS OF INTEREST X/Q (SEC/CUB.METER) X/Q (SEC/CUB.METER) X/Q (SEC/CUB. METER) D/Q RELEASE TYPE OF DIRECTION DISTANCE NO DECAY 2.260 DAY DECAY 8.000 DAY DECAY (PER 10 LOCATION FROM SITE (MILES) (METERS)

UNDEPLETED UNDEPLETED DEPLETED SQ.METER)

A SITE BOUNDARY NNE 0.50 B05 1.71E-06 1.70E-06 1.56E-06 7.96E-09 A SITE BOUNDARY NE 0.65 1046 1.30E-06 1.30E-06 1.17-06 9.00E-09 A SITE BOUNDARY ENE 0.B7 1400 6.45E-07 6.42E-07 5.69E-07 4.52E-09 A SITE BOUNDARY E 0.B2 1320 7.47E-07 7.44E-07 6.62E-07 5.53E-09 A SITE BOUNDARY ESE 0.76 1223 9.06E-07 9.02E-07 B.06E-07 7.01E-09 A SITE BOUNDARY SE 0.63 1014 1.47E-06 1.47E-06 1.32E-06 1.23E-OB A SITE BOUNDARY SSE 0.4B 772 2.30E-06 2.29E-06 2.10E-06 1.97E-OB A SITE BOUNDARY S 0.42 676 1.B7E-06 1.B6E-06 1.72E-06 1.0BE-OB A SITE BOUNDARY SSW O.4B 772 1.20E-06 1.20E-06 1.10E-06 5.97E-09 A RESIDENCE NNE 1.67 26BB 2.B2E-07 2.BOE-07 2.37E-07 1.04E-09 A RESIDENCE NE 1.14 1B35 5.63E-07 5.60E-07 4 .B7E-07 3.47E-09 A RESIDENCE ENE 1.19 1915 4.05E-07 4 .03E-07 3.50E-07 2 .65E-09 A RESIDENCE E 1.67 26BB 2.59E-07 2.57E-07 2.1BE-07 1.64E-09 A RESIDENCE ESE 1.35 2173 3.B3E-07 3.BOE-07 3.27E-07 2.63E-09 A RESIDENCE SE 0.B7 1400 B.95E-07 B.92E-07 7.90E-07 7.16E-09 A RESIDENCE SSE O.BO 12B7 1.06E-06 1.05E-06 9.36E-07 B.47E-09 A RESIDENCE S 0.51 B21 1.40E-06 1.40E-06 1.2BE-06 7.91E-09 A RESIDENCE SSW 0.4B 772 1.20E-06 1.20E-06 1.10E-06 5.97E-09 A GARDEN NNE 1.71 2752 2.73E-07 2.71E-07 2.29E-07 9.9BE-10 A GARDEN NE 2.09 3364 2.31E-07 2.29E-07 1.90E-07 1.22E-09 A GARDEN E 2.46 3959 1.46E-07 12.45E-07 1.1BE-07 8 .31E-10 A GARDEN ESE 1.66 2672 2.B1E-07 2.79E-07 2.36E-07 1.B4E-09 A GARDEN SE 1.51 2430 3.92E-07 3.90E-07 3.332E-07 2.7BE-09 A GARDEN SSE 0.70 1127 1.29E-06 1.29E-06 1.15E-06 1.06E-OB A GARDEN S 3.70 5955 7.92E-OB 7.79E-OB 6.11E-OB 2.63E-10 A GARDEN SSW 4.B5 7B05 4.27E-OB 4.17E-OB 3.17E-OB 1. 11E-10 A BEEF CATTLE ENE 3.3B 5440 B.77E-OB B.62E-OB 6.B4E-OB 4.2BE-10 A BEEF CATTLE SE 3.BB 6244 9.76E-OB 9 .5BE-OB 7.4BE-OB 5.29E-10 A GOAT NE 2.45 3943 1.B3E-07 1.B1E-07 1.4BE-07 9.20E-10 A GOAT E 3.49 5617 B.74E-OB B.60E-OB 6.79E-OB 4 .4BE-10 7-37

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 29 USNRC COMPUTER CODE - XOODOO. VERSION 2.0 RUN DATE: 03NOV17 I

- - - - PALISADES XOODOQ82 ***** USING 01/01/2007 - 12131/2016 MET DATA ***** I GROUND LEVEL RELEASE - TOP OF CONTAINMENT BUILDING SPECIFIC POINTS OF INTEREST I X/Q (SEC/CUB.METER) X/Q (SEC/CUB.METER) X/Q (SEC/CUB.METER) D/Q II RELEASE TYPE OF DIRECTION DISTANCE NO DECAY 2.260 DAY DECAY 8.000 DAY DECAY (PER 10 LOCATION FROM SITE (MILES) (METERS)

UN DEPLETED UNDEPLETED DEPLETED SQ.METER)

A SITE BOUNDARY NNE 0.50 805 1.78E-06 1.77E-06 1.62E-06 8.05E-09 A SITE BOUNDARY NE 0.65 1046 1.34E-06 1.33E-06 1.20E-06 9.13E-09 A SITE BOUNDARY ENE 0.87 1400 6.59E-07 6.57E-07 5.B2E-07 4.54E-09 A SITE BOUNDARY E 0.B2 1320 7.76E-07 7.73E-07 6.B7E-07 5.62E-09 I A SITE BOUNDARY ESE 0.76 1223 9.16E-07 9.13E-07 B.15E-07 7.02E-09 A SITE BOUNDARY SE 0.63 1014 1.45E-06 1.44E-06 1.30E-06 1.20E-OB I A SITE BOUNDARY SSE 0.4B 772 2.30E-06 2.29E-06 2.10E-06 1 .94E-OB I A SITE BOUNDARY S 0.42 676 1.96E-06 1.96E-06 1.B1E-06 1.10E-OB A SITE BOUNDARY SSW 0.4B 772 1.22E-06 1.21E-06 1.11E-06 5.93E-09 I A RESIDENCE NNE 1.67 26BB 2.93E-07 2.91E-07 2.46E-07 1.05E-09 I A RESIDENCE NE 1.14 1B35 5.7BE-07 5.75E-07 5.01E-07 3.52E-09 I A RESIDENCE ENE 1.19 1915 4.15E-07 4.12E-07 3.5BE-07 2.66E-09 I A RESIDENCE E 1.67 26BB 2.69E-07 2.67E-07 2.26E-07 1.66E-09 A RESIDENCE ESE 1.35 2173 3.B7E-07 3.B4E-07 3.31E-07 2.63E-09 A RESIDENCE SE 0.B7 1400 B.B1E-07 B.7BE-07 7.7BE-07 6.97E-09 A RESIDENCE SSE O.BO 12B7 1.05E-06 1.05E-06 9.35E-07 B.36E-09 A RESIDENCE S 0.51 B21 1.47E-06 1.47E-06 1.34E-06 8 .06E-09 I A RESIDENCE SSW 0.4B 772 1.22E-06 1.21E-06 1.11E-06 5.93E-09 I A GARDEN NNE 1.7B 2B65 2.69E-07 2.66E-07 2.24E-07 9.41E-10 I A GARDEN NE 1.90 3058 2.73E-07 2.70E-07 2.26E-07 1.46E-09 A GARDEN ENE 2.58 4152 1.33E-07 1.31E-07 1.07E-07 6.93E-10 A GARDEN E 2.46 3959 1.52E-07 1.51E-07 1.23E-07 8.44E-10 I A GARDEN ESE 2.04 3283 2.09E-07 2.07E-07 1.72E-07 1.29E-09 I A GARDEN SE 2.55 4104 1.78E-07 1.76E-07 1.43E-07 1.09E-09 I A GARDEN SSE 0.70 1127 1.29E-06 1.29E-06 1.15E-06 1.05E-08 I A BEEF CATTLE ENE 3.38 5440 8.9BE-OB B.B3E-OB 7.00E-OB 4 .29E-10 A BEEF CATTLE ESE 2.04 32B3 2.09E-07 2.07E-07 1.72E-07 1 .29E-09 A BEEF CATTLE SE 3.BB 6244 9.61E-OB 9.42E-OB 7.36E-OB 5.15E-10 A GOAT NE 2.45 3943 1.BBE-07 . 1.B6E-07 1.52E-07 9.33E-10 I A GOAT E 3.49 5617 9.11E-OB B.96E-OB 7.0BE-OB 4 .54E-10 I 7-38

ENCLOSURE 2 ERRATA/CORRECTIONS TO THE 2016 ARERR 11 Pages Follow

14. Other Groundwater Monitoring:

PNP has 23 groundwater monitoring wells (MW) strategically placed within the owner controlled area to allow for detection of radioactive contamination of ground water due to leaks or spills from plant systems. Two additional wells were installed in 2016 to increase the ability for PNP to monitor groundwater. Since installation, neither of the two new wells have detected measureable tritium levels. PNP also monitors 16 temporary wells.

Monitoring Well 11 identified a tritium leak from T-91 (Utility Water Storage Tank).

Details of this event are summarized in section 6, "Abnormal Discharges."

TW-15, TW-9, and TW-1 traverse along an East-West transect that is indicative of a historic leak that continues to be monitored. In 2016 tritium levels in TW-15 peaked in January at 31,779 pCill. Tritium levels have spiked in TW-15 when the water table rises from a large rainfall or spring melt. The high tritium levels in this area are residual of a leak which was reported to the NRC on December 10,2007.

Monitoring of the residual groundwater tritium plume continues to assess repair effectiveness and follow the site hydrology data. Well locations are depicted in Figure 1.

Table 1 below contains a summary and all raw data of all groundwater monitoring well results over the monitoring period. The average tritium concentration considers only those which had a detectable concentration of tritium. If no value is included in a cell then no measurement was performed for that location on that date. If the value in a cell is "less than" (Le. "<") a number, <MDA, <LLD, NO, or

<mda, then the analysis was performed but no analyte (Le. tritium or gamma emitters) were detected .

Depth to Local Water Table - The depth range for 2016 was approximately 7 to 8.5 feet.

Classification of Subsurface Aquifers - Not used for drinking water.

Expected Movement/Mobility of Groundwater Plume - Westerly direction down-gradient (West) toward Lake Michigan at approximately 2.2 feet per day.

Land Use Characteristics - PNP site property, water not used for drinking or irrigation.

Page 10 of 13

Table 1 2016 Groundwater Monitoring Well Results Monitoring Wells Gamma Activity (pCi/L) ,

Monitoring Well Number Sample Date and Time MW1 MW1A MW2 MW3 MW3A MW4 MW5 MW6 MW7 MW8 MW9 MW9A 2/17/201612:00 <mda <mda 3/23/201612:00 <MDA <MDA <MDA <MDA <MDA <mda <MDA <MDA 3/24/201612:00 <mda <mda <mda <mda 4/12/2016 12:00 <mda <mda 5/11/201612:00 <mda <mda 6/7/201612:00 <MDA <MDA <MDA <MDA <MDA <MDA <MDA <MDA 6/8/201612:00 <MDA <MDA <MDA <MDA 7/12/201612:00 <MDA <MDA 8/10/201612:00 <MDA <MDA 9/7/201612:00 <mda <mda <mda <mda <mda <mda <mda <mda 9/8/201610:10 <mda <mda <mda <mda 10/5/201611:50 <MDA 11/2/201612:00 <mda <mda <mda <mda <mda <mda <mda <mda 11/3/2016 12:00 <mda <MDA <MDA <MDA 11/15/201612:00 <MDA 11/22/201611:15 <MDA 11/29/201610:47 <LLD 12/1/201610:50 <mda 12/13/201611:20 <mda 12/15/201611:58 <MDA 12/20/20169:38 <MDA 12/27/201612:00 <MDA

Table 1 2016G roun dwater Mom°tonng We II Resu It5 Monitoring Wells Gamma Activity (pCi/L) Monitoring Well Number Sample Date and Time MW10 MWH MW-1l MW-13 MWI4 MW15 MW16 TW15 TWIG MW17 MW18 MW19 MW20 3/23/201612:00 <MDA <MDA 3/24/201612:00 <mda <mda <mda <mda <mda <mda <mda 6/7/2016 12:00 <MDA <MDA 6/8/201612:00 <MDA <MDA <MDA <MDA <MDA <MDA <MDA 9/7/2016 12:00 <mda <mda <mda <mda 9/8/2016 10:10 <mda <mda <mda <mda <mda <mda <mda 10/5/2016 11:50 11/2/2016 12:00 <MDA <mda <mda <MDA 11/3/2016 12:00 <MDA <mda <MDA <MDA <MDA <MDA <MDA 11/10/201610:30 <MDA 11/15/201612:00 <MDA 11/22/2016 11:15 <mda 11/29/201612:00 <MDA 12/1/201611:00 <mda 12/8/20169:01 <mda 12/13/201610:35 <mda 12/15/201610:37 <MDA 12/20/2016 8:51 <MDA

Table 1 2016 G roun d wa t er Mom"tormg W e II Resu ts Monitoring Well Temporary TRITIUM (pCi/L) Temporary Well Number Sample Date and Time TWI TW2 TW3 TW4 TW5 TW6 TW7 TlN-7C TW9 TWI0 TW11 TW13 TW14 TW15 TW16 TlN17 lVI/lS 1/20/2016 12:CO 9C06 <549 <549 11441 <549 7410 <549 <549 2/17/201612:CO 960 <578 589 777 <578 834 <578 7450 <578 <578 < 592 < 592 5360 673 <592 <592 3/23/201612:00 1670 <609 <609 7977 <609 <609 14728 1068 <609 <609 4/12/201612:00 9572 <581 <581 <581 <581 <581 <581 <581 < 581 <581 < 596 <596 31779 <596 <596 < 596 4/25/201612:00 25957 <580 1559 25766 1579 5/11/201612:00 8623 <574 < 574 768 <574 20409 1005 <574 6/7/201612:00 < 570 <570 <570 <570 < 570 <570 11095 <570 <570 <570 7/12/201612:00 <565 <548 <548 <565 <565 < 565 <565 <565 <570 <570 <570 <570 9438 < 570 <570 <570 8/10/2016 12:00 <569 <566 < 566 < 566 <566 11374 <569 <566 9/7/201612:00 <587 <587 < 587 3510 < 587 <587 13CCO 4510 <587 < 587 10/5/201612:00 <594 <594 <568 <568 <568 <568 <568 8908 <594 <568 < 594 <594 2250 <594 <594 <594 11/2/201612:00 <534 < 534 12897 <534 11/3/2016 12:00 <540 < 540 <557 5882 < 557 < 557 11/10/201612:CO < 552 10946 803 11/15/201612:00 <543 < 543 <543 11335 620 11/22/201612:00 <554 < 554 <554 <554 11/29/201612:00 <554 <554 < 554 944 12/1/201612:00 <562 < 562 <562 < 562 12/5/201612:00 < 553 3284 721 716 12/8/2016 12:00 <554 <554 <554 <554 759 12/13/201612:00 < 542 < 542 < 557 <557 . <557 10210 < 557 10136 625 12/15/201612:00 < 535 < 572 < 553 744 12/20/201612:00 < 543 < 525 < 525 < 577 12/27/201612:00 <585 < 585 <585 < 585

Table 1 2016 G roun dwa t er MOnl"tormg We II Resu Its Monitoring Wells Tritium (pCi/t.:) MonitoringWell Number Sample Date and Time MWlA MWI MW2 MW3 MW3A MW4 MW5 MW6 MW7 MW8 MV'I9 MW9A MWI0 1/20/201612:00 4248 <549 2/17/201612:00 2040 <592 3/23/201612:00 902 <646 <646 <646 <646 <646 <646 <646 3/24/201612:00 <643 <643 <643 <643 < 643 4/12/201612:00 < 596 <596 4/25/201612:00 5/11/201612:00 <574 <574 617/201612:00 1046 <576 <576 <576 <576 <576 <576 <576 6/8/201612:00 <589 <589 <589 <589 < 589 7/12/201612:00 <565 <548 8/10/201612:00 <566 <566 9/7/201612:00 <595 <595 <595 <595 < 595 < 595 <595 < 595 9/8/2016 12:00 <579 <579 <579 <579 < 579 10/5/201612:00 < 568 11/2/2016 12:00 <534 <534 <534 < 534 11/2/201612:01 11/3/2016 12:00 <544 <544 <557 < 557 <540 < 557 < 544 <544 < 544 11/15/201612:00 <543 11/22/201612:00 <554 n/29/2016 12:00 <554 12/1/201612:01 <562 12/5/201612:00 <553 12/8/201612:00 <554 12/13/201612:00 <551 12{15/201612:oo < 535 12/20/201612:00 < 525 12/21/201612:00 < 585

Table 1 2016 Groundwater Monitoring Well Results Monitoring Wells Tritium (pCilL) Monitoring Well Number Sample Date andTime MW11 MW-12 MW-13 MW14 MW15 MW16 MW17 MW18 MW19 MW20 3/23/201612:00 867 <646 3/24/201612:00 <643 <643 <643 < 643 <643 <630 6/7/201612:00 <576 < 595 6/8/2016 12:00 <589 <589 <589 < 589 <589 <600 9/7/2016 12:00 < 595 <595 < 579 < 598 9/8/201612:00 < 619 < 595 < 595 < 579 <579 <556 11/2/2016 12:00 9730 <534 < 534 <603 11/2/2016 12:01 10400 11/3/201612:00 < 582 <549 <568 < 544 <544 <532 11/10/2016 12:00 7301 11/15/201612:00 2487 11/22/2016 12:00 46327 11/29/2016 12:00 59902 11/29/2016 12:01 59000 12/1/201612:00 105341 12/1/2016 12:01 99022 12/5/2016 12:00 112818 12/8/2016 12:00 77751 12/13/201612:00 30523 12/15/2016 12:00 27557 12/20/2016 12:00 9852 12/27/201612:00 < 593

The above limits are provided to ensure that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area to annual average concentrations exceeding the limits of 10 CFR 20, Appendix B, Table 2, Column 1.

b. Liquid Effluents The concentration of radioactive material released at any time from the site to l' unrestricted areas shall be limited to 10 times the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 ~Cilml total activity.

3. Average Energy The average energy ( E ) of the radio nuclide mixture in releases of fission and activation gases as defined in Regulatory Guide 1.21, Appendix B, Section A.3 is not applicable because the limits used for gaseous releases are based on calculated dose to members of the public.

4. Measurements and Approximations of Total Radioactivity PNP uses 0.25 KeV per channel with a range of 0-2000 KeV.

a. Fission and activation gases are sampled and then analyzed on an 8192 channel analyzer with a high purity germanium (HpGe) detector.

b. lodines are sampled and then analyzed on an 8192 channel analyzer with an HpGe detector.

c. Particulates are sampled and then analyzed on an 8192 channel analyzer with an HpGe detector.

d. Liquid effluents are sampled and then analyzed on an 8192 channel analyzer with an HpGe detector. Tritium analysis is performed using liquid scintillation.

Gross Alpha, gross beta, Fe-55, Ni-63, Sr-8g, and Sr-90 analyses are performed by an offsite vendor.

Page 3 of 17

1st Quarter 2nd Quarter 3rd Quarter 4th Quarter o o o o

8. Radioactive Waste Treatment System Changes None.

9. Annual Land Use Census Changes The garden critical receptor is located in the SSE sector at 0.48 miles. The residence critical receptor is unchanged and remains in the SSW sector at 0.49 miles. The goat critical receptor is unchanged and remains in the NE sector at 2.45 miles. There are no dairy cows located within five miles of the plant.

10. Effluent Monitoring System Inoperability One of the Radiological Effluent Monitors described in the Offsite Dose Calculation Manual (ODCM) were inoperable for greater than 30 consecutive days. This monitor was RIA-5211, "Turbine Building Sump Discharge Monitor". The monitor was declared inoperable when the continuous sampler was unable to maintain sufficient flow from the turbine building sump. Upon investigation it was discovered that silUdebris had clogged the piping sufficiently to restrict flow to the sampler.

The piping was replaced and the RIA-5211 was returned to service upon successful calibration/functional check. RIA-5211 was inoperable for 37 days during which time compensatory actions defined in the ODCM were implemented.

One non-ODCM radiological monitor (RIA-1323, "Circulating Water Discharge Monitor") was inoperable for more than 30 consecutive days during the reporting period. RIA-1323 required a replacement of an electrical component when the connection between the detector and the plant process computer failed. RIA-1323 was inoperable for 40 consecutive days.

11. Offsite Dose Calculation Manual (ODeM) Changes The Offsite Dose Calculation Manual (ODCM), ODCM Appendix A. and ODeM Appendix B were revised in 2016. The General Manager Plant Operations .

approved changes to the ODCM. The ODCM was re-written with the assistance of an industry subject matter expert to align the ODCM with industry standard in terms of methodology, content, and format. The ODCM Appendix A has been relocated to the beginning of the ODCM.

A copy of the ODCM and ODCM Appendix 8 are attached in Enclosure 1.

Page 6 of 17

ATTACHMENT 1 Palisades* Table 1A 2016 Gaseous Effluents - Sum of All Releases Summation of Uncertainty All Releases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total

(%)

Fission and Activation Gases Ci 4.12E+OO 2.37E+OO 3.6SE-01 1.81E+OO 8.66E+OO 23.18 Average Release Rate 4.60E-02 S.02E-04 2.97E-OS 9.69E-OS 2.88E-OS 1.9SE-04 3.78E-06 1.22E-OS 3.62E-06 I

2.71E-01 2.4SE-01

% of Limit 2.07E-04 1.87E-04 Page 1 of 1

ATTACHMENT 1 Palisades - Table 2B 2016 Liquid Effluents - Batch Mode Fission and Activation Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Products Cr-51 Ci NO NO NO NO NO Mn-S4 Ci 1.26E-04 NO 6.08E-06 NO 1.33E-04 Fe-5S Ci NO NO NO NO NO Fe-59 Ci NO NO NO NO NO Co-S7 Ci NO NO NO NO NO Co-S8 Ci 1.43E-03 3.S2E-OS 2.84E-05 1.42E-OS 1.51E-03 Co-60 Ci 4.34E-04 4.S2E-OS 3.86E-OS 2.S9E-06 S.21E-04 Ni-63 Ci 4.69E-04 NO NO NO 4.69E-04 Sr-89 Ci 4.40E-OS NO NO NO 4.40E-OS Sr-90 Ci 2.98E-OS NO 1.07E-06 NO 3.09E-OS Nb-9S Ci NO NO NO NO NO Nb-97 Ci NO NO NO NO NO Ag-110m I Ci 8.3SE-OS NO NO NO 8.3SE-OS Sn-113 Ci NO NO NO NO NO Sb-124 Ci NO NO NO NO NO Sb-12S Ci NO NO NO NO NO ._-

1-131 Ci NO NO NO NO NO

-- I-:--:=- - -

1-133 Ci NO NO NO NO NO

-- -- r-c-------- -

1-13S Ci NO NO NO NO NO Cs-134 Ci NO NO NO NO NO Cs-137 Ci 8.S2E-OS NO f-NO NO 8.S2E-OS Zn-6S Ci NO NO NO , NO NO f - = - - -.. -- - - -- - -

Zr-9S Ci NO NO NO NO NO Mo-99 Ci NO NO NO NO NO Ru-10S Ci NO NO NO NO NO La-140 Ci NO NO NO NO NO Ce-141 Ci NO NO NO NO NO Ce-144 Ci NO NO NO NO NO

\

Tc-99m Ci NO NO NO NO NO Totals Ci 2.70E-03 8.0SE-OS 7.41E-OS 1.68E-OS 2.87E-03 Oissolved and Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Entrained Gases Kr-8S Ci NO NO NO NO NO Kr-8Sm Ci INO NO NO NO NO Kr-88 Ci NO NO NO NO NO Xe-131m Ci NO NO NO NO NO Xe-133 Ci NO NO NO NO NO Xe-133m Ci NO NO NO NO NO Xe-13S Ci NO NO NO NO NO Xe-13Sm Ci NO NO NO NO NO Page 1 of 2

ATTACHMENT 1 Palisades - Table 2C 2016 liquid Effluents - Continuous Mode Totals CI NO NO NO NO NO Tritium Ci 5.64E-02 1.06E-01 9.15E-02 9.59E-02 3.50E-01 Gross Alpha Ci NO NO NO NO NO

=

NO Measurement performed but no activity detected NR = Analysis not required and not performed

=

NA Not applicable

=

Nuclide is suspected to originate from a medical diagnostic procedure Page 2 of 2

ATTACHMENT 1 Palisades - Table 1A 2017 Gaseous Effluents - Summation of All Releases Summation of Uncertainty Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total All Releases %)

Fission and Activation Gases Ci 7.17E+OO 6.76E+OO 2.32E+OO 6.40E+OO 2.27E+01 4.04E+OO 8.60E-01 2.92E-01 8.0SE-01 7.19E-01 7.81E-03 2.88E-03 S.S7E-03 1.S3E-04 9.66E-OS 7.42E-06 3.86E-OS 1.97E-OS 1.63E-01 2.77E-01 2.77E-01 2.41E-01 1.2SE-04 2.12E-04 2.12E-04

% of Limit =Percentage of one EC (Effluent Concentration) defined per 10 CFR Part 20 Appendix 8 Table 2 Column 1 NO = Measurement performed and no activity detected NA = Not applicable Ci = Curies I-lCils =microCurie per second Page 1 of 1

ATTACHMENT 1 Palisades - Table 1B 2017 Gaseous Effluents - Ground Level Release - Batch Mode Fission and Activation Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Gases Kr-BS Ci 1.36E-03 2.02E-03 7.7SE-04 7.76E-04 4.92E-03 Kr-BSm Ci 1.93E-OB NO NO NO 1.93E-OB Kr-BB Ci 3.32E-10 3.S1E-OB NO NO 3.S4E-OB Xe-131m Ci 7.S3E-03 1.03E-02 B.SBE-04 NO 1.B7E-02 Xe-133 Ci 1.B3E+OO 3.90E-01 B.6BE-02 9.S3E-06 2.31E+OO Xe-133m Ci 3.S3E-02 9.B3E-OS 1.1BE-03 NO 3.66E-02 Xe-13S Ci 6.S1E-02 S.24E-02 2.19E-04 NO 1.1BE-01 Total Ci 1.94E+OO 4.SSE-01 B.9BE-02 7.B6E-04 2.49E+OO lodines/Halogens Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual 1-131 Ci 1.B1 E-06 2.77E-06 9.12E-10 NO 4.SBE-06 1-132 Ci B.SBE-11 NO NO NO B.SBE-11 1-133 Ci 2.23E-06 3.1SE-14 NO NO 2.23E-06 1-13S Ci 1.26E-06 NO NO NO 1.26E-06 Total Ci S.29E-06 2.77E-06 9.12E-10 NO B.06E-06 Particulates Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Cr-S1 Ci 1.42E-07 NO NO NO 1.42E-07 Mn-S4 Ci B.6BE-09 NO NO NO B.6BE-09 Co-S7 Ci 3.14E-09 NO NO NO 3.14E-09 Co-SB Ci 1.61 E-06 2.32E-07 S.4BE-OB NO 1.90E-06 Co-60 Ci 3.40E-07 NO NO NO 3.40E-07 Rb-BB Ci 1.11 E-06 NO NO NO 1.11E-06 Nb-9S Ci 6.S0E-OB 7.37E-OB 1.37E-09 NO 1.40E-07 Zr-9S Ci 6.S7E-OB S.34E-OB NO NO 1.19E-07 Nb-97 Ci 2.00E-11 NO NO NO 2.00E-11 Ag-110m Ci 2.67E-OB NO NO NO 2.67E-OB Ru-10S Ci NO NO 1.37E-OB NO 1.37E-OB Total Ci 3.3BE-06 3.S9E-07 6.99E-OB NO 3.B1E-06 Other radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Tritium Ci 1.S4E-02 S.41 E-03 NO NO 2.0BE-02 NO =Measurement performed and no activity detected Ci =Curies Page 1 of 1

ATTACHMENT 1 Palisades - Table 1C 2017 Gaseous Effluents - Ground-Level Release - Continuous Mode Fission and Activation Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Gases Ar~41 Ci NO 2.06E+OO 5.10E-01 5.54E-01 3.13E+OO Kr-B5 Ci NO 3.32E-03 NO NO 3.32E-03 Kr-B5m Ci NO 3.47E-03 3.79E-02 1.50E-01 1.92E-01 Kr-B7 Ci NO B.36E-02 1.05E-01 2.55E-01 4.43E-01 Kr-BB Ci 4.60E-01 B.70E-03 1.01E-01 3.7BE-01 9.4BE-01 Xe-131m Ci NO 1.06E-01 NO NO 1.06E-01 Xe-133 Ci 3.14E+OO 2.51E+OO 5.34E-01 2.BOE+OO B.9BE+OO Xe-133m Ci NO 6.64E-04 6.43E-04 B.04E-04 2.11 E-03 Xe-135 Ci 1.63E+OO 7.70E-01 4.63E-01 1.04E+OO 3.90E+OO Xe-135m Ci 2.06E-03 2.51E-03 1.47E-02 2.37E-02 4.30E-02 Xe-137 Ci NO NO 5.01E-02 2.17E-01 2.67E-01 Xe-13B Ci NO 7.54E-01 4.16E-01 9.B1 E-01 2.15E+OO Total Ci 5.23E+OO 6.31E+OO 2.23E+OO 6.40E+OO 2.02E+01 lodines/Halogens Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual 1-131 Ci 4.5BE-05 3.67E-05 7.42E-06 1.36E-05 1.04E-04 1-133 Ci 1.02E-04 5.71E-05 NO 2.50E-05 1.B4E-04 Total Ci 1.4BE-04 9.3BE-05 7.42E-06 3.B6E-05 2.BBE-04 Particulates Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Cr-51 Ci 2.23E-OB 1.71 E-09 NO NO 2.40E-OB Mn-54 Ci NO NO NO 5.2BE-07 5.2BE-07 Co-57 Ci NO NO NO 1.59E-07 1.59E-07 Co-5B Ci NO 3.46E-05 NO 1.27E-05 4.74E-05 Co-60 Ci 3.76E-09 2.B5E-OB 3.BBE-OB 7.42E-06 7.49E-06 Nb-95 Ci NO 3.25E-OB 5.09E-11 1.2BE-06 1.31 E-06 Zr-95 Ci NO 2.66E-OB 5.14E-07 6.35E-07 1.1BE-06 Mo-99 Ci 2.23E-OB NO NO NO 2.23E-OB Ag-10Bm Ci NO NO NO 2.02E-07 2.02E-07 Ag-110m Ci NO 7.04E-OB NO 1.14E-05 1.15E-05 Cs-137 Ci NO NO NO 1.14E-11 1.14E-11 Total Ci 4.B4E-OB 3.4BE-05 5.53E-07 3.43E-05 6.9BE-05 Other radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Tritium Ci 2.04E+OO 2.7BE+OO 2.59E+OO 3.10E+OO 1.05E+01 C-14 Ci 1.93E+OO 1.2BE+OO 2.20E+OO 2.20E+OO 7.61E+OO NO = Measurement performed and no activity detected Ci = Curies Page 1 of 1

ATTACHMENT 1 Palisades - Table 2A 2017 Liquid Effluents - Summation of All Releases Summation of All Uncertainty Liquid Releases Units rter1 Quarter 2 Quarter 3 Quarter 4 Total Fission and Activation Products (excluding tritium, gases, and gross al Ci 6.S2E-03 4.76E-03 1.S2E-04 1.17E-03 1.26E-02 6.9BE+OO Average Concentration B.72E-11 Tritium 7.11E+OO Average Concentration 1.29E-OS 2.0BE-06

% of Limit 1.29E+OO 2.0BE-01 Dissolved and Entrained Gases Ci 3.66E-03 3.0SE-04 ND ND Average Concentration ilml 9.42E-11 1.17E-11 NA 2.7SE-11

% Of Limit 4.71E-OS S.B3E-06 Gross Alpha ND ND Average Concentration ilml NA NA NA NA Volume of Batch Liquid Effluent (Before Dilution) Liters 1.3BE+06 1.29E+06 7.66E+04 1.2SE+OS Dilution Water Used for Above Liters 3.B9E+10 2.61E+10 3.93E+10 4.01E+10 1.44E+11 Volume of Continuous or Balance-of-Plant Liquid Effluent (e.g.,

low-activity or unprocessed)

Before Dilu Liters 7.B4E+09 B.42E+09 9.7SE+09 B.01E+09 Average Stream Flow m3/s S.OOE+OO 3.32E+OO 4.94E+OO S.OSE+OO ND = Measurement performed and no activity detected NA = Not applicable Ci = Curies

~Cils = microCurie per second

~Cilml = microCurie per milliliter Page 1 of 1

ATTACHMENT 1 Palisades - Table 2B 2017 Liquid Effluents - Batch Mode Fission and Activation Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Products Mn-S4 Ci 7.88E-OS NO NO NO 7.88E-OS Fe-SS Ci 1.84E-03 1.42E-03 NO S.4SE-04 3.81E-03 Co-S7 Ci NO 1.64E-06 NO NO 1.64E-06 Co-S8 Ci 4.3SE-04 2.71E-03 1.04E-04 2.0SE-04 3.46E-03 Co-60 Ci 1.S7E-03 S.07E-04 3.63E-OS 1.2SE-04 2.23E-03 Sr-92 Ci NO 4.03E-06 NO NO 4.03E-06 Nb-9S Ci 2.27E-OS NO NO NO 2.27E-OS Nb-97 Ci 1.86E-06 1.S6E-OS NO NO 1.7SE-OS Ag-110m Ci 2.48E-03 1.03E-04 1.14E-OS 2.94E-04 2.89E-03 1-131 Ci 9.40E-06 NO NO NO 9.40E-06 La-140 Ci 2.S2E-OS NO NO NO 2.S2E-OS Ag-108m Ci 4.82E-OS NO NO 1.68E-OS 6.S0E-OS Totals Ci 6.S1E-03 4.76E-03 1.S2E-04 1.18E-03 1.26E-02 Dissolved and Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Entrained Gases Xe-133 Ci 3.66E-03 3.0SE-04 NO NO 3.97E-03 Xe-13S Ci 6.20E-07 NO NO NO 6.20E-07 Totals Ci 3.66E-03 3.0SE-04 NO NO 3.97E-03 Other Radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Tritium Ci S.02E+02 S.43E+01 3.24E+OO 7.00E+OO S.66E+02 Gross Alpha Ci NO NO NO NO* NO NO := Measurement performed but no activity detected

:= The decay time for October's composite was longer than typical (see section 14 for description)

Ci:= Curies Page 1 of 1

ATTACHMENT 1 Palisades - Table 2C 2017 Liquid Effluents - Continuous Mode Fission and Activation Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Products Cs-137 Ci 5.06E-05 NO NO NO 5.06E-05 Totals Ci 5.06E-05 NO NO NO 5.06E-05 Other radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Tritium Ci 6.B1E-02 5.14E-03 6.50E-02 1.11 E-01 2.45E-01 NO =Measurement performed but no activity detected Ci = Curies No Dissolved and Entrained Gases were detected in continuous liquid effluents for 2017 Page 1 of 1

ATTACHMENT 1 Palisades - Table 3 2017 Solid Waste and Irradiated Fuel Shipments

1. Solid waste shipped offsite for burial or disposal (not irradiated fuel)

1. Type of waste Unit Estimated amount Est Total Error, %

a. Spent resin, filters, m3 1.56E+01 evaporator bottoms, etc. 25 Ci 2.25E+02

b. Dry compressible waste, m3 2.95E+02 dry active waste Ci 25 contaminated equipment, 1.19E+01 etc.

c. Irradiated components, m3 O.OOE+OO control rods, etc.

Ci NA O.OOE+OO

d. Other (metal waste, and m3 1.89E+01 used oil) 25 Ci 4.63E-05

e. sum of all waste m3 3.29E+02 25 Ci 2.37E+02 NA = Not Applicable Ci = curies m3 = cubic meter Page 1 of 3

ATTACHMENT 1 Palisades - Table 3 2017 Solid Waste and Irradiated Fuel Shipments

2. Estimate of Major Nuclide composition (by type of waste), list nuclides as needed

a. Co-60 37.43% Cs-137 1.47%

Fe-55 8.75% Ag-110m 1.27%

Ni-63 34.46% Co-58 5.57%

Sr-90 3.60% Mn-54 1.88%

C-14 2.09%

b. Co-60 9.22% Cs-137 5.28%

Fe-55 7.96% Cr-51 1.99%

Ni-63 38.19% Co-58 5.35%

Sr-90 26.24% Pu-241 1.61%

c. INA NA

d. I H-3 100%

e. Co-60 36.01% Cs-137 1.66%

Fe-55 8.71% Ag-110m 1.23%

Ni-63 34.64% Co-58 5.55%

Sr-90 4.75% Mn-54 1.80%

C-14 1.99%

NA = Not Applicable Page 2 of 3

ATTACHMENT 1 Palisades - Table 3 2017 Solid Waste and Irradiated Fuel Shipments

3. Solid Waste Disposition .

Number of shipments Mode of transportation Destination

\ Entergy Solutions Bear Creek Facility 17 HiUman Transport 1560 Bear Creek Road Erwin ResinSolutions, LLC 1 Hittman Transport 151 T.C. Runnion Road Entergy Solutions Bear Creek Facility 1 Interstate Ventures Inc. 1560 Bear Creek Road Irradiated fuel shipments (disposition)

Number of shipments Mode of transportation Destination 0 NA NA NA = Not Applicable Page 30f3

ATTACHMENT 1 Palisades - Table 4 2017 Dose Assessments, 10 CFR Part 50, Appendix I Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Liquid Effluent Dose Limit, Total Body 1.5 mrem 1.5 mrem 1.5 mrem 1.5 mrem 3mrem Total Body Dose (mrem) 1.10E-03 3.87E-04 1.77E-05 7.25E-05 1.57E-03

% Of Limit 0.073% 0.026% 0.001% 0.005% 0.052%

Liquid Effluent Dose Limit, Any Organ 5 mrem 5mrem 5 mrem 5 mrem 10 mrem Liquid Effluent Organ Dose (mrem) 1.17E-03 4.11E-04 1.85E-05 7.51E-05 1.68E-03

% of Limit 0.0234% 0.0082% 0.0004% 0.0015% 0.0168%

Gaseous Effluent Dose Limit, 5 mrad 5 mrad 5 mrad 5 mrad 10 mrad Gamma Air Gamma Air Dose (mrad) 8.29E-04 1.63E-03 6.31E-04 1.28E-03 4.37E-03

% of Limit 0.02% 0.03% 0.01% 0.03% 0.04%

Gaseous Effluent Dose Limit, Beta 10 mrad 10 mrad 10 mrad 10 mrad 20 mrad Air Beta Air Dose (mrad) 7.71E-04 9.20E-04 3.74E-04 B.97E-04 2.96E-03

% of Limit 0.008% 0.009% 0.004% 0.009% 0.015%

Gaseous Effluent Dose Limit, Any 7.5 mrem 7.5 mrem 7.5 mrem 7.5 mrem 15 mrem Organ (Iodine, Tritium, Particulates)

Gaseous Effluent Organ Dose 4.33E-03 4.76E-03 2.46E-03 3.78E-03 1.52E-02 (mrem) (Iodine, Tritium, Particulates)

% of Limit 0.06% 0.06% 0.03% 0.05% 0.10%

Page 1 of 1

ATTACHMENT 1 Palisades - Table 5 2017 Dose Assessments, EPA 40 CFR Part 190, Individual in the Unrestricted Area Whole Body Thyroid Any Other Organ Dose Limit (mrem) 25 75 25 Dose (mrem) 1.26E-01 1.32E-01 5.89E-01

% of Limit 0.51% 0.18% 2.36%

Page 1 of 1

ATTACHMENT 2 BIG ROCK POINT INDEPENDENT SPENT FUEL STORAGE INSTALLATION 2017 RADIOACTIVE EFFLUENT RELEASE REPORT This report provides information relating to radioactive effluent releases and solid radioactive waste disposal at Big Rock Point (BRP) for the year 2017. The report format is detailed in the BRP Offsite Dose Calculation Manual (ODCM). Effluent releases from BRP are controlled by the Defueled Technical Specifications and the ODCM requirements.

2017 Operating History On January 8,2007, the Nuclear Regulatory Commission (NRC) approved release of the former BRP nuclear plant property for unrestricted use in accordance with the BRP License Termination Plan 1 . On April 11, 2007, the license for BRP, DPR-06, was transferred to Entergy Nuclear Operations, Inc.

During 2017, normal independent spent fuel storage installation (ISFSI) operations continued. There were no operational activities that generated any solid radioactive waste.

Liquid and gaseous effluent monitoring is no longer conducted as the former BRP nuclear plant property has been released from the license. Short-lived radionuclides, including iodine and noble gas, are neither expected nor reported.

1. Supplemental Information A. Batch Releases There were no batch releases of gaseous or liquid effluents during 2017. All batch releases of radioactive liquids as described in the ODCM ceased in 2004. Reference Table 6.

B. Abnormal Releases There were no abnormal releases from BRP during 2017.

C. Radioactive Effluent Monitoring Instrumentation BRP ODCM currently specifies required actions when less than the minimum numbers of radioactive effluent monitoring instrument channels are operable. The ODCM also specifies these actions be taken when installed effluent monitoring systems are removed from service for decommissioning.

All plant-installed liquid and gaseous radioactive effluent monitoring instrument channels have been permanently removed and dismantled.

1 Letter from the USNRC dated January 8, 2007, "Release of Land from Part 50 License for Unrestricted Use" Page 1 of 2

2. Gaseous Effluents Although there were no gaseous effluents released during 2017, Table 7 provides a summary of all gaseous radioactive effluent monitoring conducted during the reporting period as required by the ODCM.

3. Liquid Effluents There were no liquid effluent batch releases during 2017. Table 8 lists and summarizes liquid effluent releases in accordance with the ODCM.

4. Solid Waste There was no solid radioactive waste generated or shipped during 2017.

5. Summary of Radiological Impact on Man The ODCM specifies that the annual effluent release report provide potential dose calculations based on measured effluent to liquid and gaseous pathways, if estimates of dose exceed one millirem to an organ or total body of any individual or more than one person-rem to the population within 50 miles. During 2017, there were no releases. Therefore, no calculations were required.

6. Offsite Dose Calculation Manual The ODCM describes the radiological release requirements for the BRP site. No ODCM changes in 2017 had any effect on the Radiological Effluent Program at BRP.

7. Process Control Program (PCP)

The Process Control Program (PCP) describes solid waste processing and disposal methods utilized at the BRP site. Changes to the fleet procedure governing the PCP have no effect on the BRP site in 2017.

Page 2 of 2

TABLE 6 Big Rock Point Batch Releases January 1, 2017 to December 31, 2017 A.GASEOUS Units 1ST QTR 2NDQTR 3RDQTR 4TH QTR Number of Releases N/A N/A N/A N/A Total Release Time Minutes N/A N/A N/A N/A Maximum Release Time Minutes N/A N/A N/A N/A Average Release Time Minutes N/A N/A N/A N/A Minimum Release Time Minutes N/A N/A N/A N/A B. LIQUID Units 1STQTR 2NDQTR 3RD QTR 4TH QTR Number of Releases N/A N/A N/A N/A Total Release Time Minutes N/A N/A N/A N/A Maximum Release Time Minutes N/A N/A N/A N/A AveraQe Release Time Minutes N/A N/A N/A N/A Minimum Release Time Minutes N/A N/A N/A N/A Page 1 of 1

TABLE 7 Big Rock Point Gaseous Effluent Releases January 1, 2017 to December 31, 2017 1ST 2ND 3RD 4TH Est Total A. FISSION AND ACTIVATION GASES Units OTR OTR OTR OTR Error %

1. Total release Ci N/A N/A N/A N/A

2. Average release rate for period IJCi/sec N/A N/A N/A N/A N/A

3. Percent of annual avg EC % N/A N/A N/A N/A B IODINES

1. Total iodine Ci N/A N/A N/A N/A

2. Average release rate for period IJCi/sec N/A N/A N/A N/A N/A

3. Percent of annual avg EC % N/A N/A N/A N/A C PARTICULATES

1. Particulates with half-life >8 day Ci N/A N/A N/A N/A

2. AveraQe release rate for period IJCilsec N/A N/A N/A N/A N/A

3. Percent of annual avg EC % N/A N/A N/A N/A

4. Gross alpha radioactivity Ci N/A N/A N/A N/A o TRITIUM

1. Total Release Ci N/A N/A N/A N/A

2. AveraQe release rate for period IJCi/sec N/A N/A N/A N/A

3. Percent of annual avg EC % N/A N/A N/A N/A E. WHOLE BODY DOSE

1. Beta Air dose at Site Boundary due to Noble Gases (aDCM Section 1, 1.3.2 a (1l(2)} mrads N/A N/A N/A N/A

2. Percent limit % N/A N/A N/A N/A

3. Gamma Air dose at Site Boundary due to Noble Gas (aDCM Section 1,1.3.2 a (1) (2)) mrads N/A N/A N/A N/A

4. Percent limit % N/A N/A N/A N/A F. ORGAN DOSE (aDCM Section 1, 1.3.2b (1) (2))

1. Maximum organ dose to pubic based on Critical RecepJors (child bone) mrem N/A N/A N/A N/A

2. Percent of limit (7.5 mrem/Quarter) % N/A N/A N/A N/A Page 1 of 3

TABLE 7 Big Rock Point Gaseous Effluent Releases January 1, 2017 to December 31, 2017

1. FISSION GASES Units 1STOTR 2NDOTR 3RD OTR 4TH OTR Krypton-85m Ci N/A N/A N/A N/A Krypton-87 Ci N/A N/A N/A N/A Krypton-88 Ci N/A N/A N/A N/A Xenon-133 Ci N/A N/A N/A N/A Xenon-133m Ci N/A N/A N/A N/A Xenon-135 Ci N/A N/A N/A N/A Xenon-135m Ci N/A N/A N/A N/A Xenon-138 Ci N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A

2. IODINES lodine-131 Ci N/A N/A N/A N/A lodine-132 Ci N/A N/A N/A N/A lodine-133 Ci N/A N/A N/A N/A lodine-134 Ci N/A N/A N/A N/A lodine-135 Ci N/A N/A N/A N/A Total for Period Ci N/A N/A N/A N/A Page 2 of 3

TABLE 7 Big Rock Point Gaseous Effluent Releases January 1, 2017 to December 31 , 2017

3. PARTICULATES* Units 1STOTR 2ND OTR 3RDOTR 4TH OTR Chromium-51 Ci N/A N/A N/A N/A Manganese-54 Ci N/A N/A N/A N/A Cobalt-58 Ci N/A N/A N/A N/A Iron-59 Ci N/A N/A N/A N/A Cobalt-60 Ci N/A N/A N/A N/A Zinc-65 Ci N/A N/A N/A N/A Silver-110m Ci N/A N/A N/A N/A Cesium-134 Ci N/A N/A N/A N/A Cesium-137 Ci N/A N/A N/A N/A Barium-140 Ci N/A N/A N/A N/A Europium-152 Ci N/A N/A N/A N/A Strontium-89 Ci N/A N/A N/A N/A Strontium-90 Ci N/A N/A N/A N/A Net unidentified beta Ci N/A N/A N/A N/A Total Ci N/A N/A N/A N/A

Particulates with half-life >8 days Page 3 of 3

TABLE 8 Big Rock Point Liquid Effluent Releases January 1, 2017 to December 31, 2017 Est Total A. FISSION AND ACTIVATION PRODUCTS Units 1STOTR 2NDOTR 3ROOTR 4TH OTR Error %

1. Total release (not including tritium, gases, alpha) Ci N/A N/A N/A N/A N/A

2. Average diluted concentration during period jJCi/ml N/A N/A N/A N/A

3. Percent of EC % N/A N/A N/A N/A B TRITIUM

1. Total release Ci N/A N/A N/A N/A N/A

2. Average diluted concentration during period I-ICi/ml N/A N/A N/A N/A

3. Percent of EC % N/A N/A N/A N/A C DISSOLVED AND ENTRAINED GASES

1. Total release Ci N/A N/A N/A N/A N/A

2. Average diluted concentration duringjleriod blCi/ml N/A N/A N/A N/A

3. Percent of EC % N/A N/A N/A N/A D. GROSS ALPHA RADIOACTIVITY E. VOLUME OF WASTE RELEASED (Prior to dilution) Liters N/A N/A N/A N/A F. VOLUME OF DILUTION WATER USED DURING PERIOD Liters N/A N/A N/A N/A G. MAXIMUM DOSE COMMITMENT WHOLE BODY mrem N/A N/A N/A N/A Percent of aDCM Section 1,2.3.2 a (1.5 mrem) % N/A N/A N/A N/A H. MAXIMUM DOSE COMMITMENT - ORGAN Mrem N/A N/A N/A N/A Percent of aDCM Section 1, 2.3.2 b (3.0 mrem) % N/A N/A N/A N/A Page 1 of 2

TABLE 8 Big Rock Point Liquid Effluent Releases January 1, 2017 to December 31, 2017

1. NUCLIDES RELEASED Units 1ST OTR 2ND OTR 3RDOTR 4TH aTR Chromium-51 Ci - -- - --

Manganese 54 Ci - -- - --

Cobalt-58 Ci - - - -

Iron-59 Ci -- -- -- -

Cobalt-60 Ci - - - -

Zinc-65 Ci - -- - -

Strontium-89 Ci -- - -- -

Strontium-gO Ci -- -- -- -

Molybdenum-99 Ci - -- - -

Silver-110m Ci -- - -- -

lodine-131 Ci - -- -- --

Cesium-134 Ci - -- - -

Cesium-137 Ci -- -- - -

Antimony-125 Ci - -- - --

Tin-113 Ci -- -- -- --

Net Unidentified Beta Ci - - - -

Fission & Activation Product Total Ci -- -- -- --

Xenon-133 Ci -- - - --

Tritium Ci -- -- -- -

Grand Total Ci -- -- - -

Page 2 of 2

PNP 2018-020, Offsite Dose Calculation Manual and Big Rock Point ISFSI - Attachment 2, 2017 Radioactive Effluent Release Report

Text

7.0 REFERENCES

SUMMARY

7.0 REFERENCES

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