PNP 2019-016, & Big Rock Point - 2018 Annual Radioactive Effluent Release and Waste Disposal Report

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& Big Rock Point - 2018 Annual Radioactive Effluent Release and Waste Disposal Report
ML19114A042
Person / Time
Site: Palisades, Big Rock Point  File:Consumers Energy icon.png
Issue date: 04/24/2019
From: Hardy J
Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
PNP 2019-016
Download: ML19114A042 (44)
v • d • e


Text

  • ~* Entergy _

Entergy Nuclear Operations, Inc.

Palisades Nuclear Plan 27780 Blue Star Memorial Hi hway Covert, MI 49043 2697642000 Jeffery A. Hardy Regulatory Assurance Manager PNP 2019-016 10 CFR 50.36(a)

April 24, 2019 ATIN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

201 8 Annual Radioactive Effluent Release and Waste Fisposal Report 1

Palisades Nuclear Plant Big Rock Point Docket Nos. 50-255 and 72-7 Docket Nos. 50-155 and 72-043 Renewed Facility Operating License No. DPR-6 License No. DPR-20

Dear Sir or Madam:

Attached are the Entergy Nuclear Operations, Inc. 2018 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).

Attachment 1 contains the report for PNP. Attachment 2 contains the report for the BRP ISFSI.

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 1,2018, through December 31, 2018.

If you have any questions regarding this submittal, please contact Mike Soja, Chemistry Manager, at 269-764-2536.

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

R n crtUI Y(fl, J~~~/

Attachment 1: Palisades Annual Radioactive Effluent Release Report Attachment 2: Big Rock Point ISFSI Annual Radioactive Effluent Release Report CC Administrator, Region III, USNRC Project Manager, Palisades, USNRC (wlo Attachments)

Resident Inspector, Palisades, USNRC (wlo Attachments)

NRC NMSS Project Manager, USNRC (wlo Attachments)

American Nuclear Insurers (ANI)

Attachment 1 Page 1 of 43 Plant: Palisades YEAR: 2018 Document Number: PNP 2019-016 Annual Radioactive Effluent Release Report L I I I

Plant: Palisades I Year: 2018 I Page 2 of 43 Annual Radioactive Effluent Release Report TABI:E-oF-CONTEN

1.0 INTRODUCTION

........................................................................................................................ 3 2.0 SUPPLEMENTAL INFORMATION ............................................................................................. 3 3.0 GASEOUS EFFLUENTS .......................................................................................................... 14 4.0 LIQUID EFFLUENTS ..................................................... ........................................................... 17 5.0 SOLID WASTE SUMMARy ...................................................................................................... 20 6.0 RADIOLOGICAL IMPACT TO MAN .......................................................................................... 23 7.0 METEOROLOGICAL DATA ...................................................................................................... 25 ATTACHMENTS I I - Palisades Annual Radioactive Effluent Release Report .................................................. 1 to Attachment 1 - Errata/Corrections to Previous ARERRs ............................................... 27 - Big Rock Point Independent Spent Fuel Storage Installation 2018 Radioactive Effluent Release Report ............................................................................................... 36

Plant: Palisades I Year: 2018 .1 Page 3 of 43 Annual Radioactive Effluent Release Report

1.0 INTRODUCTION

Palisades Nuclear Plant (Palisades) entered the reporting period online on January 1, 2018, at 100% full power. Palisades experienced no unexpected scrams during the 2018 calendar year. Palisades entered into a maintenance outage on March 27, 2018, and was synchronized to the grid on March 29, 2018. Palisades entered into a maintenance outage on October 13, 2018, and remained offline for a planned refueling outage. Palisades synchronized to the grid on December 28, 2018.

Palisades generated 5,455,944 MWh of net electrical energy during 2018.

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 ~ell below the limits defined in the ODCM. I 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. Noble gases dose rate due to radioactive materials released in gaseous effluents from the 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. Noble gas 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 mrads gamma
  • Less than or equal to 10 mrads beta
2) Yearly
  • Less than or equal to 10 mrads gamma
  • Less than or equal to 20 mrads beta

Plant: Palisades I Year: 2018 I Page 4 of 43 Annual Radioactive Effluent Release Report

2. lnaine-;-trilium, ana altra-aionucli-aes- in particulate-form witllh-alf-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/year 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 :
11) 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 10 mrem to any organ
4. Total Dose (40 CFR 190)
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.
  • Less than or equal to 75 mrem, Thyroid

Plant: Palisades I Year: 2018 I Page 5 of 43 Annual Radioactive Effluent Release Report

- - - -'2:" Ms-ximum- Permilrstbte- Co--nc-entrations

1. Fission & Activation Gases, lodines, and Particulates With Half Lives> Eight (8) Days 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 S, 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 S, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the total concentration r~leased 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 S, 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

1. 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 & 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 at least weekly in accordance with the ODCM.
b. lodines 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. Filters are analyzed on an HPGe system.
c. Particulates (half-lives> 8 days)

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

Plant: Palisades I Year: 2018 I Page 6 of 43 Annual Radioactive Effluent Release Report

-cr- - Tritium Tritium effluent is calculated monthly in accordance with the ODCM.

e. Carbon-14 Carbon-14 release values were estimated using the methodology included in the EPRI Technical Report 1021106, using the 2018 normalized Carbon-14 production rate of 3.9 Ci/GWtyr, a gaseous release fraction of 98%, a Carbon-14 carbon dioxide fraction of 30%, a reactor power rating of 2565.4 MWth , and equivalent full power operation of 282 days.
f. Liquid Effluents Each tank of liquid radwaste ~s sampled and analyzed for principal gamma emitters prior to release. Each sample tank is recirculated for a sufficient amount of time prior to sampling ensuring that a representative sample is obtained. Samples are then analyzed on an HPGe system and liquid release permits are generated based upon the isotopic analysis.
g. Estimated Total Error Present Estimates of measurement and analytical error for gaseous and liquid effluents are calculated as follows:

Where:

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

Plant: Palisades I Year: 2018 I Page 7 of 43 Annual Radioactive Effluent Release Report 2.5 Batch Releases:

2.5.1 Liquid

1. Number of batch releases: 16
2. Total time period for a batch release: 21,597 minutes
3. Maximum time period for a batch release: 5,732 minutes
4. Average time period for a batch release: 1350 minutes
5. Minimum time period for a batch release: 77 minutes 2.5.2 Gaseous
1. Number of batch releabes: 39
2. Total time period for a batch release: 1,846 hours0.00979 days <br />0.235 hours <br />0.0014 weeks <br />3.21903e-4 months <br />
3. Maximum time period for a batch release: 1,654 hours0.00757 days <br />0.182 hours <br />0.00108 weeks <br />2.48847e-4 months <br />
4. Average time period for a batch release: 47 hours5.439815e-4 days <br />0.0131 hours <br />7.771164e-5 weeks <br />1.78835e-5 months <br />
5. Minimum time period for a batch release: 56 minutes 2.6 Continuous Releases:

2.6.1 Liquid

1. Palisades continuously monitors one common continuous release discharge point (the mixing basin) using radiation monitors and sample analysis in accordance with Palisades ODeM. 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 ODeM. Palisades contracts an independent laboratory to perform redundant and specialized analysis.

2.6.2 Gaseous

1. Palisades continuously monitors one common continuous release discharge point (the plant stack) using radiation monitors and sample analysis in accordance with Palisades ODeM. The major input pathways to the plant stack include the auxiliary building, containment building, condenser offgas 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 ODeM. Palisades contracts an independent laboratory to perform redundant and specialized analysis.

Plant: Palisades I Year: 2018 I Page 8 of 43 Annual Radioactive Effluent Release Report 2.7.1 During 2018 there was one abnormal release. The release was of low level tritium via the septic system which drains to a drain field just south of Palisades within the owner controlled area. The hydrological characteristics of this area indicate that the tritium would migrate to Lake Michigan. The depth to the water table in this area is estimated to be seven feet. The affected groundwater is not used for drinking water.

The one positive indication of tritium contained 1980 pCi/L. A follow-up sample was promptly obtained which contained no detectable tritium. The septic system is sampled once per calendar quarter and analyzed for tritium.

The release was conservatively assumed to be the duration between two samples which contained less than detectable concentrations of tritium. This date range was June 2, 2018 to September 18, 2018 (108 days). The volume was conservatively assumed to be ~~e total potable water used by the site over this period S6.82E+06 L}.

Therefore, the tqtal activity of tritium released was conservatively estimqted to be 1.3SE-02 Ci which is 1.S0E-03% of the total tritium activity released during 2018. For dose considerations, the same parameters (onsite dilution, offsite dilution, pathway, etc.) used for the normal discharge point were assumed for this release. The estimated dose from this release was negligible. This is because liquid tritium is a low dose consequence nuclide, this release is a small fraction of total annual release totals, and as demonstrated in Table 6.1 dose limits were not challenged in 2018. On site NRC staff was notified of this event upon detection of the positive tritium sample through the corrective action process and a face-to-face brief. Palisades continues to monitor this system.

This activity was included in the applicable tables of this report. The volume of this release was not included in the tables in section 4 to ensure that the calculated dose and release rates would be conservative and accurate.

2.7.2 Liquid

1. Number of releases: 1
2. Total Activity (Ci) released: 1.3SE-02 of tritium 2.7.3 Gaseous
1. Number of releases: 0
2. Total Activity (Ci) released: NA 2.8 Non-routine, Planned Discharges
1. Gaseous non-routine planned discharge of effluents accounted for a total of 1.14E-03 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 7.46E-03 % of the total activity of this category. These discharges are from radiologically controlled areas which are not ventilated to the stack. These areas are continuously monitored and are considered less significant release points in accordance with Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste," Revision 2.

Plant: Palisades I Year: 2018 I Page 9 of 43 Annual Radioactive Effluent Release Report

2. There was onetiqutcf non-routine--planned disch--arge in 20113. Tilts c-onsi-st"9"a-of a discharge of onsite groundwater which was collected in a 2,550 gallon holding tank. The tank was filled relatively quickly, independently sampled in accordance with site procedures, and discharged via the batch process to the approved discharge point (the mixing basin). This batch contained 6.53E-06 Ci of tritium which accounted for 7.24E-07

% of the total tritium released in 2018. After the completion of this release it was identified that the tank did not have the capability to recirculate the contents prior to sampling. The tank was promptly modified to include a recirculation pump and all available groundwater data was reviewed to assess if the independent sample could have been compromised. The data review supported the analysis results and therefore no modification to the release record was performed.

2.9 Land Use Census Changes

1. I The 2018 Land Use Census resulted in no changes 9ffecting the critical receptor location or routes of exposure. The critical r~sident and garden are within one mile of the plant in the S and SSE sectors. The critical livestock are within three miles of the plant in the ESE and NE sectors. The critical receptors are used in conjunction with meteorological data to model dose consequence of Palisades' effluent. Based on the results of the 2018 land use census, Palisades' has initiated goat milk sampling (in accordance with the aDCM) to be conducted during 2019 while the goat milk is being produced.

2.10 Effluent Monitor Instrument Inoperability

1. During 2018 there was one effluent radiation monitor that exceeded 30 consecutive days being non-functional. Radiation monitor RIA-0707, "Steam Generator Blowdown Effluent Radiation Monitor," was non-functional from December 7,2017, to January 12, 2018, due to communication problems between the sample stream flow element and control room alarms. Upon troubleshooting, it was identified that a relay socket base needed to be replaced and a probe was loose at the flowmeter. The delay in restoring functionality in a timelier manner was in part due to ordering and obtaining the relay socket base replacement. During the time frame when this radiation monitor was non-functional there was no release of radiological material via this pathway. It is typical for this pathway (steam generator blowdown effluent) to be unused as a pathway for release of radiological material.

2.11 Offsite Dose Calculation Manual (ODCM) Changes

1. Palisades aDCM was not revised during 2018. Therefore the aDCM is not included in this report.

2.12 Process Control Program (PCP) Changes

1. No major radwaste system modifications (as defined in the ODCM) were implemented in 2018.
2. There were no changes to the procedure (EN-RW-105) governing the PCP in 2018 and therefore no copy of EN-RW-105 is being provided in this report.

Plant: Palisades I Year: 2018 I Page 10 of 43 Annual Radioactive Effluent Release Report

  • Ground water samples were taken 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 below in Table 2.14A. All groundwater monitoring wells in Table 2.14A are located within the owner controlled area to allow for prompt detection of leaks from plant systems.

The minimum, maximum, and average values in Table 2.14A 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 for strategic locations where there have been historical leaks. Table 2.14A indicates that temporary wells TW-1, TW-5, TW-6, TW-7, TW-9, TW-10, TW-15, and TW-16 all contained detectable tritium in 2018. These wells traverse along an East-West transect (approximately 100 feet witie), are indicative of an inactive historic leak, and continue to be monitored. Tritium concentration typically parallels water table height in areas where there is historical contamination.

For example, when the water table rises, an increase in tritium concentration is observed, and when the water table decreases, the tritium concentration decreases (often to less than detectable values). Tritium spikes from washout of the vadose zone (due to changes in water table) have been trending downward over time. This is indicative of washout from a historical leak, rather than an indication of a new active leak.

  • 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, MW1A, MW2, MW3, MW3A, MW4, MW5, MW11, MW12, MW13, TW9, and TW10. The total tritium activity discharged via groundwater to Lake Michigan was 6.29E-02 Curies in 2018. This is 6.97E-03% of the total tritium activity discharged to Lake Michigan in 2018.
  • Palisades made no NEI 07-07 voluntary notifications in 2018.
  • Palisades had zero active leaks to groundwater during 2018.

Plant: Palisades I Year: 2018 I Page 11 of 43 Annual Radioactive Effluent Release Report Table 2.14A, Non-REMP Groundwater Monitoring Results Summary (Palisades)

Well Total Samples With Minimum Tritium Maximum Tritium Average Tritium Number Samples Detectable Tritium (pC ilL) (pCilL) (pC ilL)

MW1 4 0 NA j\JA NA MW1A 4 0 NA j\J~ NA MW2 16 14 701 894~ 4086 MW3 5 Q NA NA NA MW3A 4 Q NA NA NA MW4 4 Q NA NA NA MW5 4 0 NA NA NA MW6 I 4 0 NA I NA NA MW7 I 4 0 NA I NA NA MW8 4 0 NA NA NA MW9 4 0 NA NA NA MW9A 4 0 NA NA NA MW10 4 0 NA NA NA MW11 8 3 861 4104 2991 MW-12 4 0 NA NA NA MW-13 5 1 703 703 703 MW14 4 0 NA NA NA MW15 4 0 NA NA NA MW16 4 0 NA NA NA MW17 4 0 NA NA NA MW18 4 0 NA NA NA MW19 4 0 NA NA NA MW20 4 0 NA NA NA TW1 11 1 1954 1954 1954 TW2 12 0 NA NA NA TW3 4 0 NA NA NA TW4 5 0 NA NA NA TW5 7 1 906 906 906 TW6 14 1 592 592 592 TW7 17 9 908 3654 2213 TW9 13 3 3411 4199 3870 TW10 17 10 768 7334 ~016 TW11 4 0 NA NA j\jA TW13 4 II NA NA NA TW14 10 II NA NA NA TW15 12 :i 1105 4601 2383 TW16 12 1 ~984 19a4 1984 TW17 6 0 NA NA NA TW18 5 0 NA NA NA

Plant: Palisades I Year: 2018 I Page 12 of 43 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) as listed in 10 CFR 20, Appendix S, Table 2, Column 2.

2.15 Errata/Corrections to Previous ARERRs

1. A less conservative analysis was used for the calculated effluents for one waste gas decay tank in 2017. This error resulted in no ODCM limits being exceeded. The difference between the analysis used and the more conservative analysis is considered a "small error" in accordance with Regulatory Guide 1.21, Revision 2, on the basis that the error accounted for less than 10% of the total annual activity reported. The corrected data table (page 1 of 1, Attachment 1 Table 1S~ has been included with revision bars noting the changes. All changes affected the 4th quarter column only.

Palisades has submitted this error to the corrective action process to ensure actions are created as necessary to prevent recurrence. One of the corrective actions included procedural enhancements, including a required checklist to be used when performing less frequent activities relating to the waste gas decay tank batch process.

2. It was identified that there was an error in the 2017 and 2016 Annual Radioactive Effluent Release Report (ARERR) for how C-14 activity, and consequentially, 40 CFR 190 dose values were calculated. The affected pages in the 2017 and 2016 ARERR are attached and include Section 15, Carbon-14, Table 1A, Table 1C, and Table 5. In accordance with Regulatory Guide 1.21 Revision 2, the error is dose-calculated and is considered a "small error," as the effect on the final value was less than 10% of the dose limit. The error in activity (curies) reported is considered a "large error," as the effect on the final value was greater than 10% of the value reported. The difference in the corrected activity and the activity reported was 15%. No limits of any type were challenged or exceeded as a result of this error. Palisades has submitted this error to the corrective action process to ensure actions are created, as necessary, to prevent recurrence.

Plant: Palisades 1 Year: 2018 1 Page 13 of 43 Annual Radioactive Effluent Release Report

3. In 2018 it was identified that the 1 Liter gas marinelli geometry used to perform some radiological analysis which feeds data into this report is in fact 1.24 L in volume. This error resulted in all noble gas effluents measured using this geometry to be over-reported (conservative) by 19.4% of the reported value.

All 2018 analyses were reviewed and corrected for this report. The cumulative effect on total noble gas activity for 2018 was that total noble gas activity was (at the most) over-reported by 1.28%. Similarly, the cumulative effect for 2017, 2016, and 2015 was that the total noble gas activity was (at the most) over-reported by 0.8%, 0.05%, and 0.1 % respectively. Data prior to 2015 was unaffected. The reason the total annual noble gas activity was only slightly affected by this error is because the marinelli geometry analysis contributes a relatively low fraction to the total noble gas activity when considering all analyses (continuous radiation monitoring and other geometries). The dose for all of the affected years was over-reported by less than percentages listed above because iodine ard particulates are larger dose contributors than noble I gases and these parameters were unaffected. This error is considered a "smal error" in accordance with Regulatory Guide 1.21, Revision 2, on the basis that the error accounted for less than 10% of the total annual activity reported.

Copies of the corrected pages from past reports for this error are not included in this report.

Plant: Palisades I Year: 2018 I Page 14 of 43 Annual Radioactive Effluent Release Report 3.0 GASEOUS EFFLUENTS 3.1 Gas Effluent and Waste Disposal Report Table 1, Gaseous Effluents-Summation of All Releases (Palisades)

A. Fission & Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Est.

Activation Gases Total Error

1. Total Release Ci 9.39E+00 6.95E+00 1.23E+00 1.07E+01 2.B2E+01 2.23%
2. Average release rate for IlCi/sec 1.21 E+OO B.B4E-01 1.55E-01 1.34E+0,0 B.95E-01 the period I

B. Iodine

1. Total Iodine Ci 3.92E-04 4.10E-04 NO 2.B3E-04 1.09E-03 1B.7%
2. Average release rate for IlCi/sec 5.05E-05 5.21 E-05 NA 3.56E-05 3.44E-05 the period C. Particulates
1. Particulates with half-lives Ci 25.2%

7.B2E-06 1.06E-07 NO 1.26E-04 1.34E-04

> B days

2. Average release rate for IlCi/sec 1.01 E-06 1.35E-OB NA 1.59E-05 4.26E-06 the period D. Tritium
1. Total Release Ci 3.16E+00 2.32E+00 1.BBE+00 7.92E+00 1.53E+01 5.77%
2. Average release rate for IlCi/sec 4.06E-01 2.95E-01 2.36E-01 9.97E-01 4.B4E-01 the period E. Gross Alpha
1. Total Release Ci NO NO NO NO NO NA I
2. Average release rate for IlCi/sec NA NA NA NA NA the period F. Carbon-14
1. Total Release Ci 2.2BE+00 2.44E+00 2.47E+00 3.B1 E-01 7.57E+00
2. Average release rate for IlCi/sec 2.93E-01 3.10E-01 3.11 E-01 4.79E-02 2.40E-01 the period

Plant: Palisades I Year: 2018 I Page 15 of 43 Annual Radioactive Effluent Release Report Table 2, Gaseous Effluents - Ground Level Release - Batch Mode (Palisades)

Radionuclide Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Released Fission Gases Ar-41 Ci 3.68E-03 7.12E-04 NO 7.60E-03 1.20E-02 Kr-8S Ci 1.7SE-01 9.29E-02 1.33E-01 1.S1E-01 S.S3E-01 Kr-8Sm Ci 1.79E-07 1.69E-02 NO 4.70E-03 2.16E-02 Kr-88 Ci NO S.29E-03 NO 6.11 E-03 1.14E-02 Xe-131m Ci 7.3SE-02 1.77E-02 2.76E-03 S.49E-02 1.49E-01 Xe-133 Ci 7.07E+OO 2.S9E-01 1.62E-03 4.14E+OO 1.1SE+01 Xe-133m Ci 6.98E-02 6.16E-OS NO 4.33E-02 1.13E-01 I I Xe-13S I Ci 7.26E-03 7 .S8E-01 NO I 7.81E-02 8.43E-01 Total Ci 7.40E+OO 1.1SE+OO 1.37E-01 4.48E+OO 1.32E+01 lodines 1-131 Ci 2.66E-OS 1.2SE-06 NO 2.96E-06 3.08E-OS 1-132 Ci 4.02E-08 S.60E-07 NO 1.28E-06 1.88E-06 1-133 Ci 3.10E-OS 6.23E-OS NO 2.67E-06 9.60E-OS 1-13S Ci 2.36E-09 1.99E-OS NO NO 1.99E-OS Total Ci S.76E-OS 8.41E-OS NO 6.90E-06 1.49E-04 Particulates Na-24 Ci S.23E-09 NO NO NO S.23E-09 Co-S8 Ci NO NO NO 2.87E-06 2.87E-06 Rb-88 Ci NO 3.1SE-OS NO 1.13E-03 1.17E-03 Y-88 Ci 7.19E-06 NO NO 3.S4E-OS 4.26E-OS Nb-97 Ci NO NO NO 3.S2E-09 3.S2E-09 Total Ci 7.19E-06 3.1SE-OS NO 1.17E-03 1.21E-03 Tritium H-3 Ci 2.30E-01 NA NA 6.29E-02 2.93E-01

Plant: Palisades I Year: 2018 I Page 16 of 43 Annual Radioactive Effluent Release Report Table 3, Gaseous Effluents - Ground Level Release - Continuous Mode (Palisades)

Radionuclide Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Released Fission Gases Ar-41 Ci 1.12E-01 1.26E+OO 1.76E-01 S.SSE-01 2.14E+OO Kr-SSm Ci 3.19E-02 1.92E-01 2.42E-02 4.32E-02 2.91 E-01 Kr-S7 Ci 6.1SE-02 3 .03E-01 4.3SE-02 9.02E-02 4.98E-01 Kr-8S Ci S.74E-02 4.2SE-01 6.77E-02 1.12E-01 6.9SE-01 Xe-133 Ci 1.12E+OO 1.2SE+OO 2.30E-01 3.71E+OO 6.31E+OO Xe-13S Ci 2.S4E-01 1.2SE+OO 1.S0E-01 S.99E-01 2.61E+OO XJ-13sm Ci 7.76E-03 1.4SE-01 I 3.6SE-03 S.11 E-04 1.S7E-01 Xe-137 Ci S.3SE-02 1.S0E-02 1.8SE-01 3.94E-01 6.S4E-01 Xe-138 Ci 2.33E-01 9.S3E-01 1.82E-01 3.S1 E-01 1.72E+OO Total Ci 1.99E+OO S.SOE+OO 1.10E+OO 6.1SE+OO 1.S1 E+01 lodines 1-131 Ci 1.S1 E-04 2.67E-04 NO 1.91 E-04 6.09E-04 1-13S Ci 1.S4E-04 S.91 E-OS NO S.S1 E-OS 3.2SE-04 Total Ci 3.3SE-04 3.26E-04 NO 2.76E-04 9.37E-04 Particulates Cr-S1 Ci NO NO NO 3.1SE-06 3.1SE-06 Mn-S4 Ci NO NO NO S.44E-07 S.44E-07 Ni-S7 Ci NO NO NO 2.46E-10 2.46E-10 Co-SS Ci 1.23E-07 NO NO 2.36E-OS 2.3SE-OS Co-60 Ci 4.12E-07 1.06E-07 NO 4.32E-06 4.S3E-06 Sr-92 Ci NO NO NO 2.SSE-06 2.SSE-06 Nb-9S Ci NO NO NO 1.6SE-OS 1.6SE-OS Zr-9S Ci NO NO NO 1.12E-OS 1.12E-OS Ag-108m Ci NO NO NO 3.3SE-OS 3.3SE-OS Ag-110m Ci NO NO NO 2.S7E-OS 2.S7E-OS Cs-137 Ci 9.S6E-OS NO NO NO 9.S6E-OS Total Ci 6.30E-07 1.06E-07 NO 9.09E-OS 9.17E-OS Tritium H-3 Ci 2.93E+OO 2.32E+OO 1.SSE+OO 7.S6E+OO 1.S0E+01 Gross Alpha Alpha Ci NO NO NO NO NO Carbon-14 C-14 Ci 2.2SE+OO 2.44E+OO 2.47E+OO 3.81 E-01 7.SSE+OO

Plant: Palisades I Year: 2018 1 Page 17 of 43 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 & Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Est.

Activation Products Total Error

1. Total Release (not Ci including tritium, 3.48E-03 1.59E-03 8.28E-03 1.84E-03 1.52E-02 25.7%

gases or alpha)

I I I I 2 Average diluted IlCi/mL concentration 9.03E-11 4.01 E-11 2.09E-10 1.13E-10 1.13E-10 during period B. Tritium

1. Total Release Ci 9.61 E+01 3.82E+02 2.41 E+02 1.83E+02 9.02E+02 5.83% I
2. Average diluted IlCi/mL concentration 2.49E-06 9.65E-06 6.09E-06 1.12E-05 6.73E-06 during period
c. Dissolved &

Entrained Gases

1. Total Release Ci O.OOE+OO 1.89E-03 5.29E-05 3.87E-03 5.82E-03 18.0%

I

2. Average diluted IlCi/mL concentration O.OOE+OO 4.78E-11 1.33E-12 2.38E-10 4.34E-11 during period D. Gross Alpha Activity
1. Total Release Ci I

E. Volume Of Waste Liters Released (prior 4.29E+06 4.96E+06 5.72E+06 9.42E+06 2.44E+07 to dilution)

F. Volume Of Dilution Liters Water Used During 3.86E+10 3.96E+10 3.97E+10 1.63E+10 1.34E+11 Period

Plant: Palisades I Year: 2018 1 Page 18 of 43 Annual Radioactive Effluent Release Report Table 5, Batch Mode Liquid Effluents (Palisades)

Nuclides Released Batch Mode Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Fission Products Mn-54 Ci 2.76E-05 NO 7.10E-05 NO 9.87E-05 Fe-55 Ci 6.85E-04 4.34E-04 3.05E-03 NO 4.17E-03 Co-57 Ci 1.29E-05 NO NO NO 1.29E-05 Co-58 Ci 5.25E-04 5.17E-04 3.67E-04 6.41 E-05 1.47E-03 Co-60 Ci 9.27E-04 2.78E-04 2.98E-03 8.64E-04 5.05E-03 Ni-63 Ci 3.21 E-04 NO NO NO 3.21E-04 Sr-92 Ci I NO NO 1.06E-05 1.47E-06 I 1.21 E-05 I

Ag-108m Ci bOE-05 NO 1.53E-04 7.17E-05 2.48E-04 Ag-110m Ci 9.59E-04 3.02E-04 1.65E-03 8.36E-04 3.75E-03 Total Ci 3.48E-03 1.53E-03 8.28E-03 1.84E-03 1.51 E-02 Dissolved and Entrained Gases Xe-133 Ci NO 1.89E-03 5.29E-05 3.84E-03 5.79E-03 Xe-135 Ci NO NO NO 2.95E-05 2.95E-05 Total Ci NO 1.89E-03 5.29E-05 3.87E-03 5.82E-03 Tritium H-3 Ci 9.60E+01 3.82E+02 2.41E+02 1.83E+02 9.02E+02 Gross Alpha Alpha Ci NO NO NO NO NO

Plant: Palisades I Year: 2018 I Page 19 of 43 Annual Radioactive Effluent Release Report Table 6, Continuous Mode Liquid Effluents (Palisades)

Nuclides Released Continuous Mode Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Fission Products Cs-137 Ci NO S.67E-OS NO NO S.67E-OS Total Ci NO S.67E-OS NO NO S.67E-OS Tritium H-3 Ci 1.33E-01 S.93E-02 7.34E-02 1.70E-02 2.83E-01

Plant: Palisades I Year: 2018 I Page 20 of 43 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 (Palisades)

Types of Waste Total Quantity Total Activity Est. Total (m3 ) (Ci) Error (%)

a. Spent resins, filter sludges, evaporator bottoms, etc. 2.06E+01 5.49E+OO 25
b. Dry cfmpressible waste, contaminated equip, etc. 3.52E402 2.47E+OO 25
c. Irradiated components, control rods, etc. 1.36E-01 6.74E+03 25
d. Other (sludge, used oil, water, etc.) 2.02E+01 6.84E-04 25 5.1.2 Estimate of major nuclide composition (by waste type) only> 1% [Note 1) are reported.

Table 8, Major Nuclides (Palisades)

Major Nuclide Composition  % Curies

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

H-3 98.69% 5.41 E+OO

b. Dry compressible waste, contaminated equip, etc.

H-3 1.82% 4.46E-02 Cr-51 2.23% 5.45E-02 Fe-55 6.63% 1.62E-01 Co-58 42.13% 1.03E+OO Co-60 12.97% 3.18E-01 Ni-63 13.25% 3.24E-01 Zr-95 2.91% 7.12E-02 Nb-95 4.62% 1.13E-01 Ag-110m 8.12% 1.99E-01 Cs-137 2.58% 6.31 E-02

c. Irradiated components, control rods, etc.

Plant: Palisades I Year: 2018 I Page 21 of 43 Annual Radioactive Effluent Release R~port Table 8, Major Nuclides (Palisades)

Mn-54 2.15% 1.44E+02 Fe-55 41.52% 2.80E+03 Co-60 48.5% 3.27E+03 Ni-63 7.39% 4.98E+02

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

H-3 9.54% 5.59E-05 C-14 2.03% 1.19E-05 F-55 I 6.04% 3.55E-05 Co-58 15.22% 8.93E-05 Co-60 20.53% 1.20E-04 Ni-63 16.05% 9.42E-05 Sr-90 1.11% 6.50E-06 Nb-95 1.81% 1.06E-05 Tc-99 2.61% 1.53E-05 Ag-110m 3.15% 1.85E-05 Cs-137 17.55% 1.03E-04 Cs-144 1.96% 1.15E-05

[Note 1] - "Major" radlonuchde IS equivalent to a "principle" radlonuchde, I.e. greater than 1 percent of total activity.

Plant: Palisades I Year: 2018 I Page 22 of 43 Annual Radioactive Effluent Release Report 5.1.3 Solid Waste Disposition Table 9, Solid Waste Disposition (Palisades)

Number of Mode of Transportation Destination Shipments 14 Hittman Transport Energy Solutions Bear Creek Facility 1560 Bear Creek Road 2 Hittman Transport Waste Control Specialist LLC Compact Waste Disposal Facility 1 Tri-State Motor Transit Co Energy Solutions Bear Creek 1acility 1560 Bear Creek Road Table 10, Irradiated Fuel Shipments Disposition (Palisades)

Number of Mode of Transportation Destination Shipments 0 NA NA

Plant: Palisades I Year: 2018 I Page 23 of 43 Annual Radioactive Effluent Release Report 6.0 RADIOLOGICAL IMPACT TO MAN 6.1 10 CFR 50, Appendix I Evaluation Table 11, Dose Assessment (Palisades)

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.B5E-04 3.94E-04 1.42E-03 1.21 E-03 3.51 E-03

% of Limit 3.23E-02 2.63E-02 9.47E-02 B.07Ei 02 1.17E-01 I

Liquid Effluent Dose Limit, 5 mrem 5 mrem 5 mrem 5 mrem 10 mrem Any Organ Maximum Organ Dose 4.9BE-04 4.6BE-04 1.4BE-03 1.23E-03 3.6BE-03 (mrem)

% of Limit 9.96E-03 9.36E-03 2.96E-02 2.46E-02 3.6BE-02 Gaseous Effluent Dose 5 mrad 5 mrad 5 mrad 5 mrad 10 mrad Limit, Gamma Air Gamma Air Dose (mrad) 3.12E-04 1.77E-03 2.69E-04 9.37E-04 3.29E-03

% of Limit 6.24E-03 3.54E-02 5.3BE-03 1.B7E-02 3.29E-02 Gaseous Effluent Dose 10 mrad 10 mrad 10 mrad 10 mrad 20 mrad Limit, Beta Air Beta Air Dose (mrad) 2.B9E-04 1.02E-03 1.77E-04 1.07E-03 2.56E-03

% of Limit 2.B9E-03 1.02E-02 1.77E-03 1.07E-02 1.2BE-02 Gaseous Effluent Organ Dose Limit (Iodine, 7.5 mrem 7.5 mrem 7.5 mrem 7.5 mrem 15 mrem Tritium, Particulates with>

B day half-life)

Gaseous Effluent Organ Dose (Iodine, Tritium, 1.09E-02 1.65E-02 2.94E-03 1.57E-02 4.61 E-02 Particulates with> B day half-life) (mrem)

% of Limit 1.46E-01 2.20E-01 3.92E-02 2.09E-01 3.07E-01

Plant: Palisades I Year: 2018 I Page 24 of 43 Annual Radioactive Effluent Release Report 6.2 40 CFR 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) 9.35E-02 1.27E-01 4.05E-01

% of Limit 3.74E-01 1.70E-01 1.62E+OO 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 190.1 1

Plant: Palisades I Year: 2018 I Page 25 of 43 Annual Radioactive Effluent Release Report 7.0 METEOROLOGICAL DATA 7.1 Joint Frequency Distributions

1. Period of Record: 01/01/2018 - 12/31/2018
2. Elevation: 10 meter Table 13, Hours of Each Wind Speed and Direction Wind Speed (m/s)

Wind Direction 0.1 -1.0 1.1 - 2.0 2.1 - 3.0 3.

1- 4.0 4.1 - 5.0 5.1 and greater Total N 33 109 108 70 26 37 383 NNE 26 2.6 198.4 30 9 6 272 NE 28 170 113 23 12 10 356 ENE 25 105 117 88 39 32 406 E 25 55 50 69 55 91 345 ESE 30 62 28 16 36 41 213 SE 22 95 120 177 152 346 912 SSE 36 263 385 214 100 105 1103 S 40 274 231 60 18 4 627 SSW 34 102 118 60 19 0 333 SW 37 107 157 129 91 31 552 WSW 34 121 118 74 62 31 440 W 50 115 105 91 65 29 455 WNW 36 157 145 134 54 27 553 NWN 58 295 220 134 131 100 938 NNW 36 193 209 144 114 142 838

3. Variable
a. There were 31 calm hours in 2018.

Plant: Palisades I Year: 2018 I Page 26 of 43 Annual Radioactive Effluent Release Report

b. From January 1 through July 1, 2018, data recovery was 100.0% for all parameters except the 1O-meter temperature and 10-60 meter delta-T.

For these two parameters there was 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> of missing data.

Sigma-theta was used as a surrogate for the stability class derived from delta-T and therefore the joint control room availability was 100.0%.

From July 1 through December 31, 2018, data recovery was 99.9% for all parameters except the 60 meter sigma-theta which was 99.7%. The joint control room availability from July 1 through December 31,2018, was 99.9%.

7.2 Stability Class Table 14, Classification of Atmospheric Stability Stability Condition Pasquill Categories Hours {Percentage L Extremely Unstable I A 826 (9.46%)

Moderately Stable I

B 264 (3.02%)

Slightly Unstable C 409 (4.68%)

Neutral D 3865 (44.3%)

Slightly Stable E 2204 (25.2%)

Moderately Stable F 656 (7.51%)

Extremely Stable G 507 (5.81%)

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

Plant: Palisades I Year: 2018 I Page 27 of 43 Annual Radioactive Effluent Release Report Enclosure 1 to Attachment 1 Errata/Corrections to Previous ARERRs

15. Carbon-14 In 2010, PNP and other facilities participated in an EPRI task force to build a model to accurately estimate gaseous C-14 releases, given some key site-specific plant parameters (mass of the primary coolant, average thermal neutron cross section, rated MW, etc.). This work was completed in November 2010. The estimates for C-14 were constructed using the aforementioned EPRI methodology contained within EPR11021106, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents." Using the C-14 curie estimates, the annual dose to man was derived from guidance contained within Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactpr Effluents for the Purpose of Evaluating Compliance vyith 10 CFR Part SO, Appendix I." The dose contribution of C-14 from liquid radioactive waste is much less than that contributed by gaseous radioactive waste and therefore the evaluation of C-14 in liquid radioactive waste is not required. Gaseous C-14 is reported as CO2 Curies because the major pathway by which C-14 contributes to the dose to man is by entering vegetables in the form of CO2 and then being ingested. The "total body" and the "bone" dose reported below is the maximum among the four age groups; Adult, Teenage, Child, Infant.

Annual C-14 release for PNP and subsequent doses for 2017:

Total Gaseous C-14 Released = 8.SSE+00 Curies Gaseous C-14 as CO 2 = 2.S6E+00 Curies Effective Total Body Dose, C-14 = 1.32E-01 mrem Effective Bone Dose, C-14 = 6.60E-01 mrem The quarterly curies released are provided in Table 1A, 1B, and 1C. Airborne doses due to C-14 are contained in Table 1A.

Page 18 of 20

Plant: Palisades I Year: 2018 I Page 28 of 43 Annual Radioactive Effluent Release Report ATTACHMENT 1 Palisades - Table 1A 2017 Gaseous Effluents - Summation of All Releases Summation of Uncertainty All Releases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total (%)

Fission and Activation Gases Ci 7.17E+00 6.76E+00 2.32E+00 6.40E+00 2.27E+01 Average Release Rate

% of Limit = Percentage of one EC (Effluent Concentration) defined per 10 CFR Part 20 Appendix B Table 2 Column 1 ND = Measurement performed and no activity detected NA = Not applicable Ci = Curies IJCi/s = microCurie per second Page 1 of 1

Plant: Palisades I Year: 2018 I Page 29 of 43 Annual Radioactive Effluent Release Report 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-B5 Ci 1.36E-03 2.02E-03 7.75E-04 9.B2E-04 4.92E-03 Kr-B5m Ci 1.93E-OB NO NO 2.93E-170 1.93E-OB Kr-BB Ci 3.32E-10 3.51 E-OB NO NO 3.54E-OB Xe-131m Ci 7.53E-03 1.03E-02 B.5BE-04 1.91 E-06 1.B7E-02 Xe-133 Ci 1.B3E+OO 3.90E-01 B.6BE-02 6.0BE-06 2.31E+OO Xe-133m Ci 3.53E-02 9.B3E-05 1.1BE-03 3.03E-17 3.66E-02 Xe-135 Ci 6.51 E-02 5.24E-02 2.19E-04 1.2BE-B4 1.1BE-01 Totali Ci 1.94E+OO 4.55E-01 $.9BE-02 9.90E-04 2.49E+OO 10dines/Halogens Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual 1-131 Ci 1.B1 E-06 2.77E-06 9.12E-10 7.53E-13 4.5BE-06 1-132 Ci B.5BE-11 NO NO 2.73E-45 B.5BE-11 1-133 Ci 2.23E-06 3.15E-14 NO NO 2.23E-06 1-135 Ci 1.26E-06 NO NO NO 1.26E-06 Total Ci 5.29E-06 2.77E-06 9.12E-10 7.53E-13 B.06E-06 Particulates Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Cr-51 Ci 1.42E-07 NO NO NO 1.42E-07 Mn-54 Ci B.6BE-09 NO NO NO B.6BE-09 Co-57 Ci 3.14E-09 NO NO NO 3.14E-09 Co-5B Ci 1.61 E-06 2.32E-07 5.4BE-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 1.11 E-06 Nb-95 Ci 6.50E-OB 7.37E-OB 1.37E-09 NO 1.40E-07 Zr-95 Ci 6.57E-OB 5.34E-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-105 Ci NO NO 1.37E-OB NO 1.37E-OB Total Ci 3.3BE-06 3.59E-07 6.99E-OB NO 3.B1 E-06 Other radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Tritium Ci 1.54E-02 5.41 E-03 NO NO 2.0BE-02 NO = Measurement performed and no activity detected Ci = Curies

  • = Very small values are due to a long decay correct of a Waste Gas Oecay Tank and are conservative values.

Page 1 of 1

Plant: Palisades I Year: 2018 I Page 30 of 43 Annual Radioactive Effluent Release Report ATTACHMENT 1 Palisades - Table 1 C 2017 Gaseous Effluents - Ground-Level Release - Continuous Mode Fission and Activation Gases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Ar-41 Ci NO 2.06E+00 S.10E-01 S.S4E-01 3.13E+00 Kr-BS Ci NO 3.32E-03 NO NO 3.32E-03 Kr-BSm Ci NO 3.47E-03 3.79E-02 1.S0E-01 1.92E-01 Kr-B7 Ci NO B.36E-02 1.0SE-01 2.SSE-01 4.43E-01 Kr-BB Ci 4.60E-01 B.70E-03 1.01 E-01 3.7BE-01 9.4BE-01 Xe-131m Ci NO 1.06E-01 NO NO 1.06E-01 Xe-133 Ci 3.14fF+00 2.S1E+00 S.34E-01 2.BOE+00 B.9BE+00 Xe-133m Ci NO 6.64E-04 6.43E-04 B.04E-04 2.11 E-03 Xe-13S Ci 1.63E+00 7.70E-01 4.63E-01 1.04E+00 3.90E+00 Xe-13Sm Ci 2.06E-03 2.S1 E-03 1.47E-02 2.37E-02 4.30E-02 Xe-137 Ci NO NO S.01 E-02 2.17E-01 2.67E-01 Xe-13B Ci NO 7.S4E-01 4.16E-01 9.B1 E-01 2.1SE+00 Total Ci S.23E+00 6.31E+00 2.23E+00 6.40E+00 2.02E+01 lodines/Halogens Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual 1-131 Ci 4.SBE-OS 3.67E-OS 7.42E-06 1.36E-OS 1.04E-04 1-133 Ci 1.02E-04 S.71 E-OS NO 2.S0E-OS 1.B4E-04 Total Ci 1.4BE-04 9.3BE-OS 7.42E-06 3.B6E-OS 2.BBE-04 Particulates Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Cr-S1 Ci 2.23E-OB 1.71 E-09 NO NO 2.40E-OB Mn-S4 Ci NO NO NO S.2BE-07 S.2BE-07 Co-S7 Ci NO NO NO 1.S9E-07 1.S9E-07 Co-SB Ci NO 3.46E-OS NO 1.27E-OS 4.74E-OS Co-60 Ci 3.76E-09 2.BSE-OB 3.BBE-OB 7.42E-06 7.49E-06 Nb-9S Ci NO 3.2SE-OB S.09E-11 1.2BE-06 1.31 E-06 Zr-9S Ci NO 2.66E-OB S.14E-07 6.3SE-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-OS 1.1SE-OS Cs-137 Ci NO NO NO 1.14E-11 1.14E-11 Total Ci 4.B4E-OB 3.4BE-OS S.S3E-07 3.43E-OS 6.9BE-OS Other radionuclide Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual Tritium Ci 2.04E+00 2.7BE+00 2.S9E+00 3.10E+00 1.0SE+01 C-14 Ci 2.17E+00 1.44E+00 2.47E+00 2.47E+00 B.SSE+OO NO = Measurement performed and no activity detected Ci = Curies Page 1 of 1

Plant: Palisades I Year: 2018 I Page 31 of 43 Annual Radioactive Effluent Release Report 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) 1.43E-01 1.49E-01 6.74E-01

% of Limit 0.57% 0.20% 2.70%

Page 1 of 1

Plant: Palisades I Year: 2018 I Page 32 of 43 Annual Radioactive Effluent Release Report

15. Carbon-14 In 2010, PNP and other facilities participated in an EPRI task force to build a model to accurately estimate gaseous C-14 releases, given some key site-specific plant parameters (mass of the primary coolant, average thermal neutron cross section, rated MW, etc). This work was completed in November 2010. The estimates for C-14 were constructed using the aforementioned EPRI methodology contained within EPRI 1021106, Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents. Using the C-14 curie estimates, the annual dose to man was derived from guidance contained within 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." Because the dose contribution of C-14 from liquid radioactive waste is much less than that contributed by gaseous radioactive waste, evaluation of C-14 in liquid radioactive waste is not required. Gaseous C-14 is reported as CO2 Curies because the major pathway by which C-14 contributes to the dose to man is by entering vegetables in the form of CO 2 and then being ingested. I I Annual C-14 release for PNP and subsequent doses for 2016:

Total Gaseous C-14 Released Curies = 9.82 Gaseous C-14 as CO 2 Curies = 2.95 Effective Child TB Dose, C-14 mrem = 0.0784 Effective Child Bone Dose, C-14 mrem = 0.393 The quarterly curies released are provided in Table 1A, Table 1B, and Table 1C.

Airborne doses due to C-14 are contained in Table 1A.

Page 12 of 13

Plant: Palisades I Year: 2018 I Page 33 of 43 Annual Radioactive Effluent Release Report ATTACHMENT 1 Palisades - Table 1A 2016 Gaseous Effluents - Sum of All Releases Summation Uncertainty of All Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total (%)

Releases Fission and Activation Gases Ci 4.12E+OO 2.37E+OO 3.6SE-01 1.81 E+OO 8.66E+OO 23.18 Average Release Rate S.24E-01 3.02E-01 4.60E-02 2.28E-01 2.74E-01 S.29E-03 9.78E-04 S.02E-04 2.42E-03 2.29E-03 3.96E-OS 2.97E-OS 9.69E-OS 2.88 1.9SE-04 S.04E-06 3.78E-06 1.22E-OS 3.62E-06 6.17E-06

% of Limit  % 2.1SE-06 1.60E-06 4.90E-06 2.11 E-06 Particulates Ci 1.S8E-08 o. 1.68E-07 7.86E-11 1.83 Average Release Rate Ci/s 2.00E-09 O.OOE+OO 2.11 E-08 9.89E-12 S.80E-09

% of Limit 0/0 9.18E-09 O.OOE+OO 1.S0E-08 2.26E-11 6.06E-09 Tritium Ci 3.S7E+OO 3.S4E+OO 3.6SE+OO 2.91E+OO 1.37E+01 Average Release Rate Ci/s 4.S4E-01 4.S0E-01 4.S9E-01 3.66E-01 4.32E-01

% of Limit  % 1.04E-03 1.03E-03 1.0SE-03 8.38E-04 9.89E-04 Gross Alpha Ci NO NO NO NO NO C-14 Ci 2.44E+OO 2.44E+OO 2.47 Average Release Rate 3.10E-01 3.10E-01 3.11 E-01 3.11 E-01 3.11E-01

% of Limit 0/0 2.37E-06 2.37E-06 2.37E-06 2.37E-06 2.37E-06 Page 1 of 1

Plant: Palisades I Year: 2018 I Page 34 of 43 Annual Radioactive Effluent Release Report ATTACHMENT 1 Palisades - Table 1C 2016 Gaseous Effluents - Ground Level Release, Continuous Mode Tritium Ci 3.S7E+OO 3.S4E+OO 3.6SE+OO 2.89E+OO 1.36E+01 Gross Alpha Ci NO NO NO ND*** NO I C-14 Ci 2.44E+OO 2.44E+OO 2.47E+OO 2.47E+OO 9.82E+OO NO = Measurement performed but no activity detected NR = Analysis not required and not performed NA = Not applicable

      • = Analysis does not include December data, see section 14 for explanation.

Page 1 of 1

Plant: Palisades I Year: 2018 J Page 35 of 43 Annual Radioactive Effluent Release Report ATTACHMENT 1 Palisades - Table 5 2016 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) 8.51 E-02 1.54E-01 4.03E-01

% of Limit 0.34% 0.21% 1.61%

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Page 36 of 43 Plant: Big Rock Point ISFSI YEAR: 2018 Document Number: PNP 2019-016 Annual Radio~ctive Effluent Release Repo ~t This report provides information relating to radioactive effluent releases and solid radioactive waste disposal at Big Rock Point (BRP) for the year 2018. 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.

2018 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 2018, 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 2018. 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 2018.

1 Letter from the USNRC dated January 8, 2007, "Release of Land from Part 50 License for Unrestricted Use"

Plant: Big Rock Point ISFSI I Year: 2018 I Page 37 of 43 Annual Radioactive Effluent Release Report C. Radioactive Effluent Monitoring Instrumentation SRP ODCM currently specifies required actions when less than the minimum numbers of radioactive effluent monitoring instrument channels are operable.

The aDCM 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.

2. Gaseous Effluents Although there were no gaseous effluents released during 2018, Table 2 provides a sutnmary of all gaseous radioactive effluent monitoring copducted during the reporting period as required by the aDCM.
3. Liquid Effluents There were no liquid effluent batch releases during 2018. Table 3 lists and summarizes liquid effluent releases in accordance with the aDCM.
4. Solid Waste There was no solid radioactive waste generated or shipped during 2018.
5. Summary of Radiological Impact on Man The aDCM 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 2018, there were no releases.

Therefore, no calculations were required.

6. Offsite Dose Calculation Manual The aDCM describes the radiological release requirements for the SRP site. No aDCM changes in 2018 had any effect on the Radiological Effluent Program at SRP.
7. Process Control Program (PCP)

The Process Control Program (PCP) describes solid waste processing and disposal methods utilized at the SRP site. Changes to the fleet procedure governing the PCP have no effect on the SRP site in 2018.

Plant: Big Rock Point ISFSI I Year: 2018 I Page 38 of 43 Annual Radioactive Effluent Release Report TABLE 1 Batch Releases January 1, 2018 to December 31, 2018 A. GASEOUS Units 1ST QTR 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 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. LlaUIQ Units 1STQTR 2NDQTR I 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 Average Release Time Minutes N/A N/A N/A N/A Minimum Release Time Minutes N/A N/A N/A N/A

Plant: Big Rock Point ISFSI I Year: 2018 I Page 39 of 43 Annual Radioactive Effluent Release Report TABLE 2 Gaseous Effluent Releases January 1, 2018 to December 31 , 2018 1ST 2ND 3RD 4TH EstTotal 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 ~Ci/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 J.lCi/sec t-J/A N/A N/A N/A N/A I
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. Average release rate for period ~Ci/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
4. Gross alpha radioactivity Ci N/A N/A N/A N/A D TRITIUM
1. Total Release Ci N/A N/A N/A N/A
2. Average release rate for period ~Ci/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 (ODCM Section 1, 1.3.2 a (1) (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 (ODCM Section 1, 1.3.2 a (1 i (2)) mrads N/A N/A N/A N/A
4. Percent limit  % N/A N/A N/A N/A F. ORGAN DOSE (ODCM Section 1, 1.3.2b (1) (2))
1. Maximum organ dose to pubic based on Critical Receptors (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

Plant: Big Rock Point ISFSI I Year: 2018 I Page 40 of 43 Annual Radioactive Effluent Release Report TABLE 2 Gaseous Effluent Releases January 1, 2018 to December 31, 2018

1. FISSION GASES Units 1STQTR 2NOQTR 3ROQTR 4TH QTR Krypton-85m Ci N/A N/A N/A N/A Krypton-8? 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 IN/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

Plant: Big Rock Point ISFSI I Year: 2018 I Page 41 of 43 Annual Radioactive Effluent Release Report TABLE 2 Gaseous Effluent Releases January 1, 2018 to December 31, 2018

3. PARTICULATES* Units 1STOTR 2NDOTR 3RD OTR 4TH OTR Chromium-51 Ci N/A N/A N/A N/A ManQanese-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 ICi N/A N/A N/A N/~

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-hfe >8 days

Plant: Big Rock Point ISFSI I Year: 2018 I Page 42 of 43 Annual Radioactive Effluent Release Report TABLE 3 Liquid Effluent Releases January 1, 2018 to December 31, 2018 Est Total A. FISSION AND ACTIVATION PRODUCTS Units 1STQTR 2ND QTR 3RDQTR 4TH QTR Error %

1. Total release (not includinQ tritium, Qases, alpha) Ci N/A N/A N/A N/A N/A
2. Aver~e diluted concentration during period IlCilml 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 I Ci N/A N/A I N/A N/A N/A
2. Average diluted concentration durinQ period IlCi/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 during period IlCi/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 jPrior 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 WHOLEBODY mrem N/A N/A N/A N/A Percent of ODCM 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 ODCM Section 1, 2.3.2 b (3.0 mrem)  % N/A N/A N/A N/A

Plant: Big Rock Point I Year: 2018 I Page 43 of 43 Annual Radioactive Effluent Release Report TABLE 3 Liquid Effluent Releases January 1,2018 to December 31,2018

1. NUCLIDES RELEASED Units 1STOTR 2ND OTR 3RD OTR 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 COQalt-60 Ci N/A N/A I N/A N/A I I Zinc-65 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 Molybdenum-99 Ci N/A N/A N/A N/A Silver-110m Ci N/A N/A N/A N/A lodine-131 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 Antimony-125 Ci N/A N/A N/A N/A Tin-113 Ci N/A N/A N/A N/A Net Unidentified Beta Ci N/A N/A N/A N/A Fission & Activation Product Total Ci N/A N/A N/A N/A Xenon-133 Ci N/A N/A N/A N/A Tritium Ci N/A N/A N/A N/A Total Ci N/A N/A N/A N/A
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