PNP 2022-003, and Big Pock Point Plant - 2021 Annual Radioactive Effluent Release and Waste Disposal Report

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and Big Pock Point Plant - 2021 Annual Radioactive Effluent Release and Waste Disposal Report
ML22115A111
Person / Time
Site: Palisades, Big Rock Point  Entergy icon.png
Issue date: 04/25/2022
From: Dotson B
Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
PNP 2022-003
Download: ML22115A111 (43)
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Text

) entergy Barbara E. Dotson Manager, Regulatory Assurance Palisades Nuclear Plant 269-764-2265 PNP 2022-003 April 25, 2022 10 CFR 50.36a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

2021 Annual Radioactive Effluent Release and Waste Disposal Report Palisades Nuclear Plant Big Rock Point Docket 50-255 Dockets 50-155 and 72-043 Renewed Facility License No. DPR-20 License No. DPR-6 Attached are the Entergy Nuclear Operations, Inc. 2021 Annual Radioactive Effluent Release and Waste Disposal Reports for Palisades Nuclear Plant (PNP) and Big Rock Point (BRP) Independent Spent Fuel Storage Installation (ISFSI). These reports are submitted in accordance with 10 CFR 50.36a(a)(2). contains the report for PNP. Attachment 2 contains the report for the BRP ISFSI. Attachment 3 contains ERRATA to Palisades 2020 Annual Radioactive Effluent Release Report.

These reports provide a summary of the quantities of radioactive liquid and gaseous effluent releases and solid radioactive waste processed during the period of January 1, 2021 through December 31, 2021.

This letter contains no new commitments and no revisions to existing commitments.

Respectfully, BED/mrp Entergy Nuclear Operations, Inc., 27780 Blue Star Memorial Hwy, Covert, Ml 49043

) entergy Barbara E. Dotson Manager, Regulatory Assurance Palisades Nuclear Plant 269-764-2265 : Palisades Nuclear Plant 2019 Radioactive Effluent Release Report : Big Rock Point Independent Spent Fuel Storage Installation 2021 Radioactive Effluent Release Report : ERRATA to Palisades 2020 Annual Radioactive Effluent Release Report.

CC Administrator, Region Ill, USNRC Project Manager, Palisades, USNRC (w/o Attachments)

Resident Inspector, Palisades, USNRC (w/o Attachments)

NRC NMSS Project Manager, USNRC (w/o Attachments)

American Nuclear Insurers (ANI)

Entergy Nuclear Operations, Inc., 27780 Blue Star Memorial Hwy, Covert, Ml 49043

Page 1 of 31 Plant: Palisades YEAR: 2021 Document Number: PNP 2022-003 Annual Radioactive Effluent Release Report

Plant: Palisades I Year: 2021 I Page 2 of 31 Annual Radioactive Effluent Release Report TABLE OF CONTENTS

1.0 INTRODUCTION

........................................................................................................................ 3 2.0 SUPPLEMENTAL INFORMATION ............................................................................................. 3 3.0 GASEOUS EFFLUENTS .......................................................................................................... 15 4.0 LIQUID EFFLUENTS ................................................................................................................ 18 5.0 SOLID WASTE

SUMMARY

...................................................................................................... 22 6.0 RADIOLOGICAL IMPACT TO MAN .......................................................................................... 25 7.0 METEOROLOGICAL DATA ...................................................................................................... 27 ATTACHMENTS - Palisades Offsite Dose Calculation Manual (ODCM) .................................................... 29 - Big Rock Point Independent Spent Fuel Storage Installation 2021 Annual Radioactive Effluent Release Report ............................ ................................................ 30 - ERRATA to Palisades 2020 Annual Radioactive Effluent Release Report.. .................. 31

Plant: Palisades I Year: 2021 I Page 3 of 31 Annual Radioactive Effluent Release Report

1.0 INTRODUCTION

This report covers the 2021 calendar year for Palisades Nuclear Power Plant (license No. DPR-20} and the decommissioned nuclear facility Big Rock Point (license No.

DPR-6). Palisades is a Combustion Engineering Pressurized Water Reactor.

Palisades generated 7,014,805.56 MWh of net electrical energy during 2021.

This report is a summary of the effluent data in accordance with Technical Specification (TS) 5.6.3. Both liquid and gaseous effluents are released in accordance with the Offsite Dose Calculation Manual (ODCM). All releases in the reporting period were well below the limits defined in the ODCM.

2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits The ODCM contains the limits to which Palisades must adhere. Because of the "as low as reasonably achievable" (ALARA) philosophy at Palisades, actions are taken to reduce the amount of radiation released to the environment. Liquid and gaseous release data show that the dose from Palisades is considerably below the ODCM limits. This data reveals that the radioactive effluents have an overall minimal dose contribution to the surrounding environment. The following are the limits required by the ODCM:

1. Fission and activation gases:
a. Dose rates due to noble gas effluents released in gaseous form from the site to areas at and beyond the site boundary shall be limited to the following:
  • Less than or equal to 500 mrem/year to the total body
  • Less than or equal to 3000 mrem/year to the skin
b. Air dose due to noble gases released in gaseous effluents to areas at and beyond the site boundary shall be limited to the following:
1) Quarterly
  • Less than or equal to 5 mrad gamma
  • Less than or equal to 1O mrad beta
2) Yearly
  • Less than or equal to 10 mrad gamma I
  • Less than or equal to 20 mrad beta

Plant: Palisades I Year: 2021 I Page4of31 Annual Radioactive Effluent Release Report

2. Iodine, tritium, and all radionuclides in particulate form with half-lives greater than 8 days.
a. The dose rate for lodine-131, lodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:
  • Less than or equal to 1500 mrem/yr to any organ
b. 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 to areas at and beyond the site boundary shall be limited to the following:
1) Quarterly
  • Less than or equal to 7.5 mrem to any organ
2) Yearly
  • Less than or equal to 15 mrem to any organ
3. Liquid Effluents Dose
a. The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to unrestricted areas shall be limited to the following:
1) Quarterly
  • Less than or equal to 1.5 mrem total body
  • Less than or equal to 5 mrem to any organ
2) Yearly
  • Less than or equal to 3 mrem total body
  • Less than or equal to 1O mrem to any organ
4. Total Dose (40CFR190)
a. 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 the following:
  • Less than or equal to 25 mrem, Total Body or any Organ except Thyroid.

Plant: Palisades I Vear: 2021 I Page 5 of 31 Annual Radioactive Effluent Release Report

  • Less than or equal to 75 mrem, Thyroid 2.2 Maximum Permissible Concentrations
1. Fission & Activation Gases, Iodines, and Particulates With Half Lives > Eight (8)

Days The above limits (section 2.1.1 and 2.1.2) 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.

2. Liquid Effluents The concentration of radioactive material released shall be limited to ten times the concentration 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 total concentration released shall be limited to 2.0E-04 microCurie/ml.

2.3 Average Energy The average energy ( E) of the radionuclide 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.

2.4 Measurements & Approximations of Total Radioactivity Palisades' gamma spectroscopy system uses 0.25 keV per channel with a range of 0-2000 keV. All analyses are performed to achieve the required lower limit of detection as specified in Palisades' Offsite Dose Calculation Manual (ODCM).

a. Fission and Activation Gases Noble gas activity is continuously monitored via a beta scintillation detector on the main stack release point. Additional radiation monitors are located upstream for all likely radiological pathways. Data is reviewed and quantified weekly in accordance with the ODCM.
b. Airborne Iodine Iodine is continuously collected on a charcoal cartridge filter via an isokinetic sampling assembly from the main stack release point. Filters are analyzed once per week in accordance with the ODCM.

Plant: Palisades I Vear: 2021 I Page 6 of 31 Annual Radioactive Effluent Release Report

c. Airborne Particulates (half-lives > 8 days)

Particulates are continuously collected on a filter paper via an isokinetic sampling assembly on the main stack release point. Filters are analyzed once per week in accordance with the ODCM.

d. Airborne Tritium Gaseous tritium effluent is calculated monthly in accordance with the ODCM considering spent fuel pool evaporation rate. When the reactor head is removed and the reactor cavity is flooded, reactor cavity evaporation rate is also factored into this calculation.
e. Airborne Carbon-14 Carbon-14 release values were estimated using the methodology included in the EPRI Technical Report 1021106, using the normalized Carbon-14 production rate of 3.9 Ci/GW1yr (Curie per gigawatt-thermal-year), a gaseous release fraction of 98%, a Carbon-14 carbon dioxide fraction of 30%, a reactor power rating of 2565.4 MW,h, and equivalent full power operation of 310.29 days.
f. Airborne Sr-89 and Sr-90 A composite, made up of each weekly stack filter paper, is analyzed on a quarterly frequency for the radionuclide Sr-89 and Sr-90.
g. Airborne Gross Alpha A composite, made up of each weekly stack filter paper, is analyzed on a monthly frequency for gross alpha activity.
h. Liquid Gamma Emitters Continuous effluent pathways are sampled by a compositor approximately each hour. Weekly, the composite sample for each continuous release pathway is analyzed for gamma emitters. Additionally a monthly grab sample from each continuous effluent pathway is analyzed for gamma emitters. Each processed liquid radiological batch is analyzed for gamma emitters prior to release.

Plant: Palisades I Year: 2021 I Page 7 of 31 Annual Radioactive Effluent Release Report

i. Liquid Tritium, Gross Alpha Activity, and Gross Beta Activity Continuous effluent pathways are sampled by a compositor approximately each hour. Monthly, a composite sample for each continuous release pathway is analyzed for tritium and gross alpha activity. Service water effluent is also composited and analyzed monthly for gross beta activity. Each processed liquid radiological batch is analyzed for tritium prior to release. Each processed liquid radiological batch is analyzed as a monthly composite for tritium and gross alpha activity.
j. Liquid Sr-89, Sr-90, Ni-63, and Fe-55 Quarterly a composite from each continuous effluent pathway and a composite of processed liquid radiological batches are analyzed for Sr-89, Sr-90, Ni-63, and Fe-55.
k. Estimated Total Error Present Estimates of measurement and analytical error for gaseous and liquid effluents are calculated as follows:

Where:

Er = total percent error E1 ... En= percent error due to calibration standards, laboratory analysis, instruments, sample flow, etc.

2.5 Batch Releases:

1. Liquid
a. Number of batch releases: §
b. total time period for batch releases: 62.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
c. Maximum time period for a batch release: 26.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />
d. Average time period for a batch release: 12.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />
e. Minimum time period for a batch release: 7.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br />

Plant: Palisades I Year: 2021 I Page 8 of 31 Annual Radioactive Effluent Release Report

2. Gaseous
a. Number of batch releases: z
b. Total time period for batch releases: 11.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
c. Maximum time period for a batch release: 2.1 O hours
d. Average time period for a batch release: 1.66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br />
e. Minimum time period for a batch release: 1.17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> 2.6 Continuous Releases:
1. Liquid
a. Palisades continuously monitors one common continuous release discharge point (the mixing basin) using radiation monitors and sample analysis in accordance with Palisades ODCM. The major input pathways to the mixing basin include the service water effluent, turbine building sump effluent, processed liquid radiological effluent, and dilution water effluent. All major input pathways are also continuously monitored using radiation monitors and/or sample analysis in accordance with Palisades ODCM. Palisades contracts an independent laboratory to perform redundant and specialized analysis.
2. Gaseous
a. Palisades continuously monitors one common continuous release discharge point (the plant stack) using radiation monitors and sample analysis in accordance with Palisades ODCM. The major Input pathways to the plant stack include the auxiliary building, containment building, condenser off gas system, and waste gas decay tanks. All major input pathways are also continuously monitored using radiation monitors and/or sample analysis in accordance with Palisades ODCM. Palisades contracts an independent laboratory to perform redundant and specialized analysis.

Plant: Palisades I Year: 2021 I Page9of31 Annual Radioactive Effluent Release Report 2.7 Abnormal Releases

1. Gaseous
a. Number of releases: 1
b. Total Activity (Ci) released: 1.80E-02 Ci of H-3 and 1.15E-06 Ci of 1-133
c. On 7/28/2021, operations began a down-power to support maintenance for a condensate pump. Later on this date, a relief valve on the steam generator blowdown flash tank lifted, as designed, due to increased pressure in this system. This resulted in secondary plant steam being released to the environment. Secondary plant steam contains very low radiological activity. Sampling and analysis requirements were performed for this release in accordance with Palisades' offsite dose calculation manual (ODCM). The release was conservatively assumed to be from when the plant started the down-power until it was validated that the relief valve was no longer lifting (7/28/2021 08:45 through 7/31/2021 13:49).

The activity in the effluent was conservatively assumed to be the highest measured activity for each nuclide among all samples collected over the course of the release. This activity was 5.1 SE-05 uCi/ml of H-3 and 3.33E-09 uCi/ml of 1-133. The release rate was conservatively assumed to be the entire difference between flowrate going to the blowdown vent tank and flowrate downstream of the relief valve (demineralizer effluent).

This release rate was 19.8 gpm of water. It was therefore calculated that 1.S0E-02 Ci of H-3 and 1.15E-06 Ci of 1-133 was released. The release rate was significantly below regulatory limits listed in the ODCM. This release accounts for roughly 0.2% of the total gaseous H-3 and 1% of the total gaseous iodine (including all isotopes) released from Palisades in 2021. Similarly this release accounted for a small fraction of the total offsite dose due to gaseous effluents from Palisades. As shown in Table 11 and Table 12 of this report offsite dose is well below regulatory limits.

2. Liquid
a. Number of releases: 1
b. Total Activity (Ci) released: 2.90E-01 Ci of H-3 was released in 2020 and 1.11 E+00 Ci of H-3 was released in 2021.
c. On 03/19/2021 it was identified that the pathway by which a condensate receiver tank (T-927) was sending condensate to the mixing basin, was bypassing radiological monitoring equipment. This was immediately corrected upon discovery. A conservative calculation was performed to quantify the maximum amount of all radiological material which could have been discharged from this condition.

Plant: Palisades I Year: 2021 I Page 10 of 31 Annual Radioactive Effluent Release Report T-927 receives secondary system condensate which contains low level tritium. The duration of time T-927 was sending water to the mixing basin was conservatively assumed to be continuously from 11/17/2020 at 13:21 to 03/19/2021 at 16:44. The fraction of the release for 2020 is being added to this report under the ERRATA to show this impact of this release on 2020 reporting values. The flow rate of the release was calculated conservatively to be 98.0 gallons per minute based on the head pressure of an assumed full tank and physical restrictions to the downstream flow (such as piping length and diameter). The activity was conservatively assumed to be equal to the greatest measured activity for all nuclide from a secondary system condensate receiver tank over the duration of the release. This activity was 1.22E-05 uCi/ml of H-3 in 2020 and 2.68E-05 uCi/ml of H-3 in 2021. It was therefore calculated that 2.90E-01 Ci of H-3 was released in the 2020 and 1.11 E+00 Ci of H-3 was released in 2021. This accounts for 0.04% and 0.2% of the total liquid H-3 released from Palisades in 2020 and 2021 respectively. Similarly this release accounted for a small fraction of the total offsite dose due to liquid effluents from Palisades. As shown in Table 11 and Table 12 of this report offsite dose is well below regulatory limits.

2.8 Non-routine, Planned Discharges

1. Gaseous non*routine planned discharge of effluents accounted for a total of 4.92E-06 curies of activity associated with the category "Iodine, tritium, and all radionuclides in particulate form with half-lives greater than 8 days". This accounted for 0.000005% of the total activity of this category. These discharges are from radiological controlled areas which are not ventilated to the stack (such as Tool Decontamination Room and Hot Machine shop) . These areas are considered less-significant release points in accordance with Regulatory Guide 1.21 Revision 3.

2.9 Land Use Census Changes

1. The 2021 Land Use Census resulted in no changes to critical receptor locations (i.e. routes of exposure). The critical resident and garden are within 1 mile of the plant in the S and SSE sectors. The critical livestock are within 3 miles of the plant in the ESE sectors. The critical receptors are used in conjunction with meteorological data to model dose consequence of Palisades' effluent.

Plant: Palisades I Year: 2021 I Page 11 of 31 Annual Radioactive Effluent Release Report 2.10 Effluent Monitor Instrument lnoperability

1. During 2021 there was one instance of an effluent radiation monitor which exceeded 30 consecutive days being non-functional. This radiation monitor was the steam generator blowdown ventilation monitor (RIA-2320) which was non-functional from 11/05/2020 through 9/1/2021. The long duration for this monitor being non-functional is due to damage in the detector well which required a custom part to repair. During this period there was one release to the environment via this pathway during which time sampling and analysis was performed in accordance with the ODCM. This release was associated with relief valve cycling and was discussed in Section 2.7.1, Abnormal Releases.

2.11 Offsite Dose Calculation Manual (ODCM) Changes

1. Palisades ODCM was not revised in 2021.

2.12 Process Control Program (PCP) Changes

1. No major radwaste system modifications (as defined in the ODCM) were implemented in 2021.
2. There were no changes to the procedure (EN-RW-105) governing the PCP in 2021 and therefore no copy of EN-RW-105 is being provided in this report.

2.13 NON-REMP Groundwater Monitoring Results (NEI 07-07)

Groundwater is routinely sampled onsite in support of the Groundwater Protection Initiative (GPI). These samples are not part of the Radiological Environmental Monitoring Program. A summary of the sample results are listed in Table 2.13A. All groundwater monitoring wells in Table 2.13A are located within the owner controlled area to allow for prompt detection of leaks from plant systems. The minimum, maximum, and average concentration of tritium listed in Table 2.13A are for all samples which contained detectable concentrations of tritium.

Palisades has 23 groundwater monitoring wells (which have the prefix "MW").

Palisades also monitors 16 temporary wells (which have the prefix "TW") in addition to the 23 monitoring wells to provide additional monitoring in strategic locations. Table 2.13A indicates that temporary wells TW-2,TW-3, TW-4, TW-5, TW-6, TW-7, TW-9, TW-10, TW-13, TW-14, TW-16, TW-17 and monitoring wells MW-3, and MW-13 all contained detectable tritium in 2021. All of the monitoring wells and temporary wells which detected tritium in 2021 are located within an area approximately 140 feet wide (north to south) and 90 feet long (east to west).

Plant: Palisades I Year: 2021 I Page 12 of 31 Annual Radioactive Effluent Release Report Radiological effluents via groundwater are quantified in accordance with the methodology described in Regulatory Guide 4.25, "Assessment of Abnormal Radionuclide Discharges in Ground Water to the Unrestricted Area at Nuclear Power Plant Sites". The groundwater monitoring wells used for this analysis are those on the western perimeter of the site (between the site and Lake Michigan) and include MW1, MW1 A, MW2, MW3, MW3A, MW4, MWS, MW11, MW12, MW13, TW9, and TW10. The total tritium activity discharged via groundwater to Lake Michigan was 1.16E-01 Curies in 2021. This is a very small percentage (0.02%) of the total liquid tritium activity discharged from Palisades in 2021. Palisades total liquid effluents (including effluent via groundwater) is well below the limits specified in the ODCM.

Palisades made no NEI 07-07 voluntary notifications in 2021.

In 2021 Palisades implemented several plant enhancements to mitigate and correct the potential release of tritium to groundwater. These enhancements included the lining of below-grade pipes and sumps which contain secondary plant water and the installation of a "flap" (or one-way valve) on the discharge of below grade piping going to the mixing basin.

Palisades continues to implement the GPI in accordance with NEI 07-07 with the goal of prompt identification and correction of leaks from plant systems.

Plant: Palisades I Year: 2021 I Page 13 of 31 Annual Radioactive Effluent Release Report Table 2.13A, Non-REMP Groundwater Monitoring Results Summary Well Total Samples with Minimum Maximum Average Number Samples Detectable Tritium Tritium (pCi/L) Tritium (pCi/L) Tritium (pCi/L)

MW1 ll n .. IA .. IA 1\1.ll

.. IA .. IA MW1A 4 n 1\1.ll MW? 4 0 N.ll 1\1.ll

~AW'l. 11 ll R?'l. -:i-:ic;n 1A<-A

~AIA/'l..ll

" n N.ll I\IA 1\1.ll MWll ll n N.ll

"'" N.ll

.. ,.,c ll n .. IA N.ll I\IA ll n I\IA N.ll I\IA MW7 ll n I\IA N.ll 1\1.ll

..,.,o c; n I\IA

"'" 1\1.ll lAIA/n ll n .. IA

~A\/1/Q.ll ll n

"'" "'" I\IA

~Aw1n ll n

"'" "'" 1\1.ll

~AW11 A n I\IA

"'" 1\1.ll

~AW.1? 'l. n "IA

"'" 1\1.ll MW-13 Q c; '1C'l'l 1ncc'l 11-:ic;n U\Ali,l ll n "IA "IA 1\1.ll

~AW1<- ll n I\IA 1\111 MW1A 4 n "IA t,.IA 1\111 MW17 ll n

"'" "IA NII MW1R ll n t,.IA

"'" 1\111 MW1Q ll n t,.IA

"'" 1\111

~AW?n ll n I\IA

"'" 1\111 TW1 ll n 1\111 .. ,A I\IA TW? 11 7 7?ll '-IAR7n 1770A TW'-1 1n Q 1ll 17 .d.0107 ?7<-R1 TWll 1 'l. 11 ll77<1 ACOCO 1n<>o1 Twc; 11 A 1nRR '-17?4 17.tA T\AIC 1n A 1,t7c; r.ic;no ?n.to TW7 7 c; C'lO '>',R7 1nr,c TWO 11 R

""'" A<>An 1"""'

Tw1n R 7 7'l.l- 9073 ?7R7 TW11 ll n NII 1\1.ll 1\111 TW1<1 1<1 Q i:;71 470"i4 <inOAQ TW1ll Q R 1C'l0C: -t-:inn7 ?9f;?7 TW1<; c; n N.ll 1\111 1\111 TW1A A 1 7<:\ll 734 734 TW17 1<1 11 con 410RR ?1074 TW1R '-I n 1\111 "l.ll 1\111

Plant: Palisades I Year: 2021 I Page 14 of 31 Annual Radioactive Effluent Release Report 2.14 Outside Tanks

1. All outdoor tanks as described in the ODCM were maintained within the ODCM limit of less than 1,000 times the effluent concentration (EC), excluding tritium and noble gases, as listed in 10 CFR Part 20, Appendix B, Table 2, Column 2.

2.15 Errata/Corrections to Previous ARERRs

1. Due to the discovery of the abnormal release described in Section 2.7.2 the activity from the faction of the release which occurred in 2020 is being added to the ERRATA section (Attachment 3) of this report.
2. The errors in the 2020 ARERR resulted in an underestimate of the total liquid tritium effluent by approximately 0.04% for that reporting year. This resulted in an underestimate of the annual offsite dose consequence by approximately 0.01% for organ dose via liquid effluents. There was no change to the reported whole body dose via liquid effluents in 2020. As shown in the revised Table 11 in Attachment 3 of this report, liquid dose is a very small fraction of the most restrictive regulatory limits (10 CFR Part 50 Appendix I design objective).
3. The affected pages of the 2020 AREA A include page 17, 19, and 23. These pages contain Table 4, Table 6, and Table 11. The changed pages are in Attachment 3 of this report.

2.16 Table Notes for Tables 1 through Table 14-

1. The "annual total" column for all Tables in this report may not be equal to exactly the sum of the four quarters due to rounding differences and the three significant figure format for reporting.
2. The annual dose values may not be equal to the sum of the four quarters due to different critical receptors and critical age groups between different quarters.
3. Table notation "ND" means "not detected"
4. Table notation "NA" means "not applicable"

Plant: Palisades I Year: 2021 I Page 15 of 31 Annual Radioactive Effluent Release Report 3.0 GASEOUS EFFLUENTS 3.1 Gaseous Effluent and Waste Disposal Report Table 1, Gaseous Effluents-Summation of All Releases - Palisades A. Fission and Activation Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Est. Total Gases Error%

1. Total Release Ci 3.44E-01 1.85E+O0 5.81 E-01 1.27E+00 4.05E+00 1.11 E+01
2. Average release rate for µCi/sec 4.43E-02 2.35E-01 7.30E-02 1.60E-01 1.28E-01 the period
8. Iodine
1. Total 1-131 Ci 1.19E-05 1.44E-05 3.17E-05 2.27E-05 8.0BE-05 3.09E+01
2. Average release rate for µCi/sec the period 1.53E-06 1.84E-06 3.99E-06 2.86E-06 2.56E-06 C. Particulates
1. Particulates with half- Ci 3.95E-08 1.28E-07 3.70E-07 3.45E-11 5.38E-07 2.83E+01 lives> 8 days
2. Average release rate for µCi/sec 5.0BE-09 1.63E-08 4.66E-08 4.34E-12 1.71 E-08 the period D. Tritium
1. Total Release Ci 2.90E+OO 3.21E+O0 2.43E+OO 2.41 E+00 1.09E+01 8.75E+O0
2. Average release rate µCi/sec 3.73E-01 4.0BE-01 3.05E-01 3.03E-01 3.47E-01 for the period E. Gross Alpha
1. Total Release Ci ND ND ND ND ND NA
2. Average release rate µCi/sec NA NA NA NA NA for the period F. Carbon-14
1. Total Release Ci 2.41 E+00 2.44E+O0 2.43E+00 2.47E+00 9.75E+00
2. Average release rate µCi/sec 3.11 E-01 3.11 E-01 3.05E-01 3.11 E-01 3.09E-01 for the period

Plant: Palisades I Year: 2021 I Page 16 of 31 Annual Radioactive Effluent Release Report Table 2, Gaseous Effluents - Ground Level Release - Batch Mode Radionuclide Unit Quarter 1 Quarter 2 [Note 11Quarter 3 Quarter 4 Total Released Fission Gases Kr-85 Ci ND 6.46E*04 1.71 E-04 8.14E-04 1.63E*03 Xe-133 Ci 6.25E-06 4.17E-06 ND ND 1.04E-05 Total Ci 6.25E-06 6.S0E-04 1.71E-04 8.14E-04 1.64E-03 Iodines Total CJ NO ND ND NO ND Particulates Total Cl ND Nb ND ND ND Tritium H-3 Ci NA lilA NA 111A NA

Plant: Palisades I Year: 2021 I Page 17 of 31 Annual Radioactive Effluent Release Report Table 3, Gaseous Effluents - Ground Level Release - Continuous Mode Radionuclide Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Released Fission Gases Ar-41 Ci 9.20E*02 5.32E*01 1.78E-01 4.91E*01 1.29E+00 Kr-85m Ci ND 1.29E*02 3.34E*03 1.81E*02 3.42E*02 Kr-87 Ci 2.14E*03 7.38E-02 3.05E*02 4.44E-02 1.51E*01 Kr-88 Ci 4.94E*04 6.36E*02 1.00E-02 2.24E*02 9.65E-02 Xe-133 Ci 1.83E-03 3.79E-02 1.89E-02 5.94E-02 1.18E*01 Xe-135 Ci 6.43E-02 3.91 E-01 1.05E*01 2.31E-01 7.90E-01 Xe*135m Ci 4.33E-03 5.65E-03 6.68E-03 5.71E*03 2.24E-02 Xe-137 Ci 9.20E*02 2.15E*01 9.15E*02 9.44E*02 4.93E-01 Xe-138 Ci 8.71E*02 5.18E-01 1.37E*01 3.03E*01 1.05E+O0 Total Ci 3.44E-01 1.85E+00 5.B0E-01 1.27E+00 4.04E+00 Iodines 1-131 Ci 1.19E-05 1.44E*05 3.17E*05 2.27E-05 8.08E*05 1-133 Ci 5.63E*06 1.11E*05 4.66E-05 1.00E-05 7.33E-05 Total Ci 1.75E*05 2.55E*05 7.83E*05 3.28E*05 1.54E*04 Particulates Co-60 Ci 3.95E-08 1.28E-07 2.86E*07 3.45E*11 4.54E*07 Ag*110m Ci ND ND 8.43E-08 ND 8.43E-08 Total Ci 3.95E-08 1.28E-07 3.70E*07 3.45E*11 5.38E-07 Tritium H-3 2.90E+00 3.21E+00 2.43E+00 2.41E+00 1.09E+01 Cl Gross Alpha Alpha bi ND ND ND ND ND Carbon-14 C-14 Cl 2.41E+00 2.44E+00 2.43E+00 2.47E+00 9.75E+OO

Plant: Palisades I Year: 2021 I Page 18 of 31 Annual Radioactive Effluent Release Report 4.0 LIQUID EFFLUENTS 4.1 Liquid Effluent and Waste Disposal Report Table 4, Liquid Effluents-Summation of All Releases - Palisades A. Fission and Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Est. Total Activation Products Error%

1. Total Release (not Ci including tritium, ND 1.07E-04 1.0BE-04 1.25E-05 2.27E-04 3.53E+01 gases or alpha) 2 Average diluted µCi/ml concentration NA 2.73E-12 2.69E-12 3.14E-13 1.44E-12 during period B. Tritium
1. Total Release Ci 1.25E+00 9.00E+01 2.78E+02 1.19E+02 4.88E+02 6.37E+00
2. Average diluted µCi/ml concentration 3.19E-08 2.29E-06 6.95E-06 2.99E-06 3.0BE-06 during period C. Dissolved and Entrained Gases
1. Total Release Ci ND ND 1.82E-05 ND 1.82E-05 5.56E+01
2. Average diluted µCi/ml concentration NA NA 4.54E-13 NA USE-13 during period D. Gross Alpha Activity
1. Total Release Ci ND ND ND ND ND NA
2. Average diluted µCi/ml concentration NA NA NA NA NA during period E. Volume of Waste Released (prior Liters 5.19E+07 7.29E+06 7.78E+06 8.17E+06 7.51 E+07 to dilution)

Plant: Palisades I Vear: 2021 I Page 19 of 31 Annual Radioactive Effluent Release Report Table 4, Liquid Effluents-Summation of All Releases - Palisades Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total F. Volume of Liters Dilution Water 3.92E+10 3.92E+10 4.00E+10 3.97E+10 1.58E+11 Used During Period

Plant: Palisades I Year: 2021 I Page 20 of 31 Annual Radioactive Effluent Release Report Table 5, Batch Mode Liquid Effluents Nuclides Released .. Batch Mode Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Fission Products Co-60 Ci NA 1.51E-05 4.11E-05 ND 5.61E-05 Ag-108m Ci NA 7.52E*06 ND ND 7.52E-06 Ag-110m Ci NA 8.45E-05 5.76E*05 1.25E-05 1.SSE-04 Total Ci NA 1.07E-04 9.87E-05 1.25E-05 2.18E-04 Dissolved and Entrained Gases Xe-133 Ci NA ND 1.82E-05 ND 1.82E-05 Total Ci NA ND 1.82E-05 ND 1.82E-05 Tritium H-3 Ci NA 8.98E+01 2.78E+02 1.18E+02 4.86E+02 Gross Alpha Alpha Ci NA ND ND ND ND

Plant: Palisades I Year: 2021 I Page 21 of 31 Annual Radioactive Effluent Release Report Table 6, Continuous Mode Liquid Effluents Nuclides Released Continuous Mode Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Fission and Activation Products Co-58 Ci ND ND 9.02E-06 ND 9.02E-06 Cs-137 Ci ND ND 1.19E-04 ND 1.19E-04 Total Ci ND ND 9.02E-06 ND 9.02E-06 Dissolved and Entrained Gases Total Ci ND NO ND ND ND Tritium H-3 Ci 1.25E+00 1.81 E-01 1.78E*01 2.16E-01 1.83E+00 Gross Alpha Alpha Ci ND ND ND ND ND

Plant: Palisades I Year: 2021 I Page 22 of 31 Annual Radioactive Effluent Release Report 5.0 SOLID WASTE

SUMMARY

5.1 Solid Waste Shipped Offsite for Burial or Disposal (Not Irradiated Fuel) 5.1.1 Types of Waste Table 7, Types of Solid Waste Summary Types of Waste Total Quantity Total Activity Est. Total (m3) (Ci) Error(%)

a. Spent resins, filter sludges, evaporator bottoms, etc. 1.94E+01 1.63E+02 25
b. Dry compressible waste, contaminated equip, etc. 1.65E+02 1.01E+00 25
c. Irradiated components, control rods, etc. 0.00E+00 0.00E+00 NA
d. Other (sludge, used oil, water, etc.) 0.00E+00 0.00E+00 NA 5.1.2 Estimate of major nuclide composition (by waste type) only >1% !Note 1> are reported.

Table 8, Major Nuclides Major Nuclide Composition  % Curies

a. Spent resins, filter sludges, evaporator bottoms, etc.

Fe-55 20.83 3.40E+01 Co-58 9.51 1.55E+01 Co-60 47.49 7.75E+01 Ni-63 13.39 2.19E+01 Zn-65 1.30 2.12E+00 Nb-95 1.22 1.99E+0O

b. Dry compressible waste, contaminated equip, etc.

C-14 2.40 2.43E-02 C-51 1.32 1.34E-02 Co-58 18.01 1.82E-01 Co-60 25.23 2.55E-01

Plant: Palisades I Year: 2021 I Page 23 of 31 Annual Radioactive Effluent Release Report Table 8, Major Nuclides Ni-63 25.00 2.53E-01 Zr-95 1.56 1.57E-02 Nb-95 2.99 3.02E-02 Ag-110m 5.73 5.B0E-02

c. Irradiated components, control rods, etc.

NA NA NA

d. Other (sludge, used oil, water, etc.)

NA NA NA

[Note 1] - "Major" radionuclide is equivalent to a "principle" radionuclide, i.e. greater than 1 percent of total activity.

Plant: Palisades I Year: 2021 I Page 24 of 31 Annual Radioactive Effluent Release Report 5.1.3 Solid Waste Disposition Table 9, Solid Waste Disposition Number of Mode of Transportation Destination Shipments 11 Hittman Transport Energy Solutions Bear Creek Facility 1560 Bear Creek Road 1 Hittman Transport Erwin ResinSolutions, LLC 151 T.C.

Runion Road Table 10, Irradiated Fuel Shipments Disposition Number of Mode of Transportation Destination Shipments 0 NA NA

Plant: Palisades I Year: 2021 I Page 25 of 31 Annual Radioactive Effluent Release Report 6.0 RADIOLOGICAL IMPACT TO MAN 6.1 10CFR Part50, Appendix I Evaluation Table 11, Dose Assessment Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Liquid Effluent Dose Limit, 1.5 mrem 1.5 mrem 1.5 mrem 1.5 mrem 3mrem Total Body Total Body Dose (mrem) 9.37E-07 7.03E-05 3.66E-04 9.03E-05 5.29E-04

% of Limit 6.25E-05 4.69E-03 2.44E-02 6.02E-03 1.76E-02 Liquid Effluent Dose Limit, 5mrem 5 mrem 5 mrem 5 mrem 10 mrem Any Organ Maximum Organ Dose 9.37E-07 7.07E-05 4.45E-04 9.03E-05 6.08E-04 (mrem)

% of Limit 1.87E-05 1.41 E-03 8.90E-03 1.81 E-03 6.08E-03 Gaseous Effluent Dose 5mrad 5 mrad 5 mrad 5 mrad 10 mrad Limit, Gamma Air Gamma Air Dose (mrad) 1.46E-04 9.14E-04 2.71 E-04 6.42E-04 1.97E-03

% of Limit 2.92E-03 1.83E-02 5.42E-03 1.28E-02 1.97E-02 Gaseous Effluent Dose 10 mrad 10 mrad 10 mrad 10 mrad 20 mrad Limit, Beta Air Beta Air Dose (mrad) 1.54E-04 6.65E-04 2.26E-04 4.06E-04 1.45E-03

% of Limit 1.54E-03 6.65E-03 2.26E-03 4.06E-03 7.25E-03 Gaseous Effluent Organ Dose Limit (Iodine, 7.5 mrem 7.5 mrem 7.5 mrem 7.5 mrem 15 mrem Tritium, Particulates with>

8 day half-life)

Gaseous Effluent Organ Dose (Iodine, Tritium, 2.73E-03 3.59E-03 3.63E-03 3.34E-03 1.33E-02 Particulates with > 8 day half-life) (mrem)

% of Limit 3.63E-02 4.79E-02 4.84E-02 4.45E-02 8.87E-02

Plant: Palisades I Year: 2021 I Page 26 of 31 Annual Radioactive Effluent Release Report 6.2 40CFR Part 190 Evaluation for an Individual in the Unrestricted Area Table 12, EPA 40 CFR PART 190 Evaluation Whole Body Thyroid Any Other Organ Dose Limit 25 mrem 75 mrem 25 mrem Dose (mrem) 1.12E-01 1.17E-01 5.22E-01

% of Limit 4.49E-01 1.56E-01 2.09E+00 Liquid dose, gaseous dose including C14, direct shine from each unit, ISFSI and any other nuclear power related facility within 5 miles of the station are considered when calculating dose compliance with 40 CFR 190.

Plant: Palisades I Year: 2021 I Page 27 of 31 Annual Radioactive Effluent Release Report 7.0 METEOROLOGICAL DATA 7.1 Joint Frequency Distributions

1. Period of Record: 01/01/2021 - 1.2/31/2021
2. Elevation: 10 meter Table 13, Hours of Each Wind Speed and Direction Wind Speed (m/s)

Wind 0.1 - 1.0 1.1 - 2.0 2.1 - 3.0 3.1 - 4.0 4.1 - 5.0 5.1 and Speed not Direction greater available Total N 19 139 132 75 29 8 3 405 NNE 20 107 74 29 8 0 0 238 NE 24 118 127 35 10 2 0 316 ENE 23 74 125 83 39 24 0 368 E 28 44 30 43 16 43 0 204 ESE 21 56 29 19 11 10 0 146 SE 29 77 149 151 112 208 0 726 SSE 50 351 434 275 127 105 0 1342 s 67 406 180 40 19 1 0 713 SSW 42 124 122 37 11 6 0 342 SW 42 137 224 221 88 27 0 739 WSW 45 147 150 88 46 27 0 503 w 48 138 89 75 48 59 0 457 WNW 61 154 159 121 52 40 0 587 NW 51 209 218 171 96 49 0 794 NNW 30 158 274 192 87 73 0 814

Plant: Palisades I Year: 2021 I Page 28 of 31 Annual Radioactive Effluent Release Report

3. Variables
a. There were 65 calm hours in 2021.
b. From January 1 through July 1 of 2021 data recovery was 97.4% for all parameters. The missing data was the 10 meter temperature data and the cause for the loss of data was a connection issue between the sensor and the computer which has been fixed. The joint control room availability of at least one wind speed, one wind direction, and one stability parameter, from January 1 through July 1 of 2021 was 4344/4344 or 100.0%.
c. From July 1 through December 31 of 2021 data recovery was 99.8% for all parameters. The missing data was the 10 meter temperature data and the cause for the loss of data is unknown. Most of the missing data was recoverable and therefore the joint control room availability of at least one wind speed, one wind direction, and one stability parameter, from July 1 through December 31 of 2021 was 4415/4416 or 99.98%.

7.2 Stability Class Table 14, Classification of Atmospheric Stability Stability Condition Pasquill Categories Hours (Percentage)

Extremely Unstable A 21.4 Moderately Stable B 4.5 Sliahtly Unstable C 5.7 Neutral D 34.7 Sliahtly Stable E 19.5 Moderately Stable F 7.8 Extremely Stable G 4.9 Data not available N/A 1.4 t .

Palisades' meteorological data is maintained on-site and available for review upon request

Plant: Palisades I Year: 2021 I Page 29 of 31 Annual Radioactive Effluent Release Report Attachment 1 Palisades Offsite Dose Calculation Manual (ODCM)

Not applicable, there was no ODCM revision in the reporting year

Plant: Palisades I Year: 2021 I Page 30 of 31 Annual Radioactive Effluent Release Report Attachment 2 Big Rock Point Independent Spent Fuel Storage Installation 2021 Annual Radioactive Effluent Release Report 7 pages to follow

ATTACHMENT 2 BIG ROCK POINT INDEPENDENT SPENT FUEL STORAGE INSTALLATION 2021 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 2021. 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.

2021 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 2021, 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 iodines 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 2021. All batch releases of radioactive liquids as described in the ODCM ceased in 2004. Reference Table 1.

B. Abnormal Releases There were no abnormal releases from BRP during 2021.

C. Radioactive Effluent Monitoring Instrumentation 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 There were no gaseous effluents released during 2021. Table 2 lists and summarizes gaseous effluent releases in accordance with the ODCM.
3. Liquid Effluents There were no liquid effluent batch releases during 2021. Table 3 lists and summarizes liquid effluent releases in accordance with the ODCM.
4. Solid Waste There was no solid radioactive waste generated or shipped during 2021.
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 2021, 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.

There were no revisions to the ODCM in 2021.

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 2021.

Page 2 of 2

TABLE 1 Big Rock Point Batch Releases January 1, 2021 to December 31, 2021 A. GASEOUS Units 1STQTR 2NDQTR 3RDQTR 4TH QTR Number of Releases NIA NIA NIA NIA Total Release Time Minutes NIA NIA NIA NIA Maximum Release Time Minutes NIA NIA NIA NIA Average Release Time Minutes NIA NIA NIA NIA Minimum Release Time Minutes NIA NIA NIA NIA B. LIQUID Units 1STQTR 2NDQTR 3RDQTR 4TH OTR Number of Releases NIA NIA NIA NIA Total Release Time Minutes NIA NIA NIA NIA Maximum Release Time Minutes NIA NIA NIA NIA Averaae Release Time Minutes NIA NIA NIA NIA Minimum Release Time Minutes NIA NIA NIA NIA Page 1 of 1

TABLE 2 Big Rock Point Gaseous Effluent Releases January 1, 2021 to December 31, 2021 1ST 2ND 3RD 4TH Est Total A. FISSION AND ACTIVATION GASES Units OTA OTA OTA OTA Error%

1. Total release Ci N/A NIA NIA N/A
2. Averaae release rate for period uCi/sec N/A N/A NIA N/A NIA
3. Percent ol annual avg EC  % NIA NIA NIA N/A B. IODINES
1. Total iodine Ci NIA NIA NIA NIA
2. Average release rate for period µCi/sec N/A NIA NIA N/A N/A
3. Percent of annual avQ EC  % NIA NIA N/A N/A C. PARTICULATES
1. Particulates with hall-life >8 dav Ci NIA N/A NIA N/A
2. AveraQe release rate for period µCi/sec N/A NIA NIA NIA N/A
3. Percent of annual avQ EC  % NIA NIA N/A NIA
4. Gross alpha radioactivity Ci NIA NIA N/A N/A D. TRITIUM
1. Total Release Ci NIA N/A N/A N/A
2. Average release rate for period µCi/sec N/A N/A NIA N/A
3. Percent of annual avQ EC  % NIA NIA N/A NIA E. WHOLE BODY DOSE
1. Beta Air dose at Site Boundary due to Noble Gases (ODCM Section 1, 1.3.2 a (1) (2)) mrads N/A NIA N/A NIA
2. Percent limit  % NIA NIA N/A NIA
3. Gamma Air dose at Site Boundary due to Noble Gas (ODCM Section 1, 1.3.2 a (1) (2)) mrads NIA NIA N/A N/A
4. Percent limit  % N/A N{A N/A NIA F. ORGAN DOSE (ODCM Section 1, 1.3.2b (1) (2))
1. Maximum organ dose to public based on Critical Receptors (child bone) mrem N/A NIA NIA NfA
2. Percent of limit (7.5 mrem/auarter)  % N/A N/A NIA NIA Page 1 of 2

TABLE 2 Big Rock Point Gaseous Effluent Releases January 1, 2021 to December 31, 2021

1. NUCLIDES RELEASED Units 1ST OTR 2NDQTR 3RDOTR 4TH OTR Fission & Activation Gases Ci NIA NIA NIA NIA Iodines Ci NIA NIA NIA NIA Particulates* Ci NIA NIA NIA NIA
  • Particulates with half-life >8 days Page 2 of 2

TABLE 3 Big Rock Point Liquid Effluent Releases January 1, 2021 to December 31, 2021 Est Total A. FISSION AND ACTIVATION PRODUCTS Units 1STQTR 2NDQTR 3RDQTR 4TH QTR Error%

1. Total release (not includina tritium, gases, alpha) Ci N/A NIA NIA N/A N/A
2. Averaae diluted concentration durina oeriod uCi/ml NIA NIA N/A N/A
3. Percent of EC  % NIA NIA N/A N/A B TRITIUM
1. Total release Ci NIA NIA N/A N/A N/A
2. Average diluted concentration durina oeriod uCi/ml N/A NIA NIA NIA
3. Percent of EC  % NIA NIA N/A N/A C. DISSOLVED AND ENTRAINED GASES
1. Total release Ci NIA NIA NIA N/A N/A
2. Average diluted concentration during period µCi/ml NIA NIA N/A N/A
3. Percent of EC  % NIA NIA N/A NIA D. GROSS ALPHA RADIOACTIVITY Ci NIA NIA NIA NIA E. VOLUME OF WASTE RELEASED (Prior to dilution) Liters N/A NIA NIA NIA F. VOLUME OF DILUTION WATER USED DURING PERIOD Liters N/A NIA NIA NIA G. MAXIMUM DOSE COMMITMENT WHOLEBODY mrem NIA NIA NIA NIA Percent of ODCM Section 1, 2.3.2 a (1.5 mreml  % NIA NIA NIA NTA H. MAXIMUM DOSE COMMITMENT - ORGAN Mrem NIA NIA NIA NIA Percent of ODCM Section 1, 2.3.2 b 13.0 mrem)  % NIA NIA N/A NIA Page 1 of 2

TABLE 3 Big Rock Point Liquid Effluent Releases January 1, 2021 to December 31, 2021

1. NUCLIDES RELEASED Units 1STQTR 2NDQTR 3RDQTR 4THQTR Fission & Activation Product Total Ci NIA NIA NIA NIA Dissolved and Entrained aases Ci NIA NIA NIA NIA Tritium Ci NIA NIA NIA NIA Page 2 of 2

Plant: Palisades I Year: 2021 I Page 31 of 31 Annual Radioactive Effluent Release Report Attachment 3 ERRATA to Palisades 2020 Annual Radioactive Effluent Release Report 3 pages to follow

Plant: Palisades I Year: 2020 I Page 17 of 28 Annual Radioactive Effluent Release Report 4.0 LIQUID EFFLUENTS 4.1 Liquid Effluent and Waste Disposal Report Table 4, Liquid Effluents-Summation of All Releases - Palisades A. Fission and Unit Quarter Quarter 2 Quarter 3 Quarter4 Total Est. Total Activation Products 1 Error%

1. Total Release (not Ci including tritium, 5.57E-03 7.46E-04 3.32E-03 2.45E-03 1.~1E-02 1.91E+01%

gases or alpha) 2 Average diluted pCi/ml concentration 1.40E-10 1.89E-11 1.21E-10 6.96E-11 8.53E-11 during period B. Tritium tf.SS~tbl

1. Total Release Ci 2.07E+02 2.50E+02 3.16E+02 -4.eze, e1 8.21E+02 5.05E+00%
2. Average diluted !LCi/ml concentration 5.22E-06 6.33E-06 1. 15E-05 1.31E e& 5.79E-06 during period 1,3~f-o6 C. Dissolved and Entrained Gases
1. Total Release Ci ND ND 6.02E-04 ND 6.02E-04 1.97E+01%
2. Average diluted pCi/ml concentration NA NA 2,20E-11 NA 4.25E-12 during period D. Gross Alpha Activity
1. Total Release Ci ND ND 4.77E-04 3.91 E-05 5.16E-04 2.00E+00%

E. Volume of Waste Liters Released (prior "S.28*o1 ;,l.f5f+07 to dilution) 6.78E+06 8.33E+06 6.52E+06 ..g.esE,e& .,

F. Volume of Liters DIiution Water 3.97E+10 3.95E+10 2.74E+10 3.52E+10 1.42E+11 Used During Period

Plant: Palisades I Year: 2020 I Page 23 of 28 Annual Radioactive Effluent Release Report 6.0 RADIOLOGICAL IMPACT TO MAN 6.1 10CFR Part50, Appendix I Evaluation Table 11, Dose Assessment Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Liquid Effluent Dose Limit, 1.5 mrem 1.5 mrem 1.5 mrem 1.5 mrem 3mrem Total Body Total Body Dose (mrem) 4.25E-04 3.89E-04 8.44E-04 2.09E-04 1.73E-03

% of Limit 2.83E-02 2.59E-02 5.63E-02 1.39E-02 5.77E-02 Liquid Effluent Dose Limit, 5mrem 5mrern 5mrem 5 mrern 10 mrern Any Organ Maximum Organ Dose 8.98E-03 5.42E-04 9.32E-04 4..42E 84 1.0SE-02 (mrem) 1.vn, E-o'f

% of Limit 1.80E-01 1.0SE-02 1.86E-02

-~*8f~IJ 1.06E-01 Gaseous Effluent Dose 5 mrad 5 mrad 5 mrad 5 mrad 10 mrad Limit, Gamma Air Gamma Air Dose (mrad) 5.33E-04 2.38E-04 1.51E-03 3.87E-04 2.67E-03

% of Limit 1.07E-02 4.76E-03 3.02E-02 7.74E-03 2.67E-02 Gaseous Effluent Dose 10 mrad 10 mrad 10 mrad 10 mrad 20 mrad Limit, Beta Air Beta Air Dose (mrad) 5.21E-04 1.75E-04 9.82E-04 2.10E-04 1.89E-03

% of Limit 5.21E-03 1.75E-03 9.82E-03 2.10E-03 9.45E-03 Gaseous Effluent Organ Dose Limit (Iodine, 7.5 mrem 7.5 mrem 7.5 mrem 7.5 mrem 15 mrem Tritium, Particulates with >

8 day half-life)

Gaseous Effluent Organ Dose (Iodine, Tritium, 4.35E-03 3.94E-03 6.SBE-03 3.00E-03 1.78E-02 Particulates with > 8 day half-life) (mrem)

% of Limit 5.80E-02 5.25E-02 8.78E..Q2 4.00E-02 1.19E-01

Plant: Palisades I Year: 2020 I Page 19 of 28 Annual Radioactive Effluent Release Report Table 6, Continuous Mode Liquid Effluents Nuclides Released Continuous Mode Unit Quarter1 Quarter 2 Quarter3 Quarter4 Total Fission and Activation Producti Cs-137 Ci 6.19E-05 1.17E-04 4.72E-05 ND 2,26E-04 Total Ci 6.19E-05 1.17E-04 4.72E-05 ND 2.26E-04 Tritium H-3 Ci 1.40E-01 1.93E-01 2.72E-01 ' ~-iHIEIH

  • il.48E 81 Lf.1.'f[-01 1.03 +-00 \
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