ML25092A076

Annual Radioactive Effluent Release Report

ML25092A076
Person / Time
Site:	Big Rock Point  File:Consumers Energy icon.png
Issue date:	04/02/2025
From:	Noval W Holtec Decommissioning International
To:	Office of Nuclear Material Safety and Safeguards, Document Control Desk
References
HDI BRP 2025-003
Download: ML25092A076 (1)

Text

HOLTEC DE CO MMI SSI O NI N G INTERN A TION A L Krishna P. Singh Technology Campus, 1 Holtec Blvd., Camden, NJ 08104 Telephone (856) 797-0900 Fax(856)797-0909 HDI BRP 2025-003 April 2, 2025 U.S. Nuclear Regulatory Commission ATTN : Document Control Desk Washington, DC 20555-0001

Subject:

Big Rock Point Docket No. 50-155 and 72-043 Facility Operating License No. DPR-6 Annual Radioactive Effluent Release Report 10 CFR 50.36a In accordance with the requirements of Title 10 of the Code of Federal Regulations Part 50 (10 CFR 50), Section 36a, Technical specifications on effluents from nuclear power reactors, subparagraph (a)(2), 10 CFR 50.36a(a)(2), Holtec Decommissioning International, LLC (HDI) on behalf of Holtec Palisades, LLC (Holtec Palisades) is submitting the 2024 Annual Radioactive Effluent Release Report (ARERR) for Big Rock Point (BRP) Independent Spent Fuel Storage Installation (ISFSI). The purpose of the report is to provide a summary of the quantities of radioactive liquid and gaseous effluent releases and solid radioactive waste processed during the period of January 1, 2024, through December 31, 2024. The 10 CFR 50.36a(a)(2) requirements are listed in BRP Defueled Technical Specifications Section 6.6.3. The letter enclosure contains the BRP ISFSI 2024 ARERR.

This letter contains no new and no revised regulatory commitments.

Should you have any questions or require additional information, please contact Amy Filbrandt, Acting Regulatory Assurance Manager at (269) 764-2520.

Respectfully, William Noval William Noval Digitally signed by William Naval ON: cn=William Naval, o=HDI,

ou=Regulatory Affairs, email=w.noval@holtec.com Date: 2025.04.02 08:05:36 -04'00' Director Regulatory Affairs Holtec Decommissioning International, LLC

Enclosure:

Annual Radioactive Effluent Release Report cc:

NRC Region Ill Regional Administrator NRC Decommissioning Inspector - Big Rock Point NRC NMSS Project Manager-Big Rock Point American Nuclear Insurers (ANI)

Enclosure to HDI BRP 2025-003 Annual Radioactive Effluent Release Report

Plant: Big Rock Point YEAR: 2024 Document Number: HDI BRP 2025-003 Annual Radioactive Effluent Release Report

2024 Annual Radioactive Effluent Release Re ort Plant: Bi Rock Point TABLE OF CONTENTS 1.0 Introduction 3

2.0 Supplemental Information 3

3.0 Gaseous Effluents 4

4.0 Liquid Effluents 4

5.0 Solid Waste 4

6.0 Summary of Radiological Impact on Man 4

7.0 Offsite Dose Calculation Manual 4

8.0 Process Control Program (PCP) 4 Page 2 of 11

2024 Annual Radioactive Effluent Release Re ort Plant: Bi Rock Point 1.0 Introduction This report provides information relating to radioactive effluent releases and solid radioactive waste disposal at Big Rock Point (BRP) for the calendar year of 2024. 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.

On January 8, 2007, the Nuclear Regulatory Commission (NRG) approved release of the former BRP Nuclear Plant property for unrestricted use in accordance with the BRP License Termination Plan 1. On June 28th, 2022, the license for BRP, DPR-06, was transferred to Holtec Decommissioning International.

During 2024, 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.

2.0 Supplemental Information A.

Batch Releases There were no batch releases of gaseous or liquid effluents during 2024. 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 2024.

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 3 of 11

2024 Annual Radioactive Effluent Release Re ort Plant: Bi Rock Point 3.0 Gaseous Effluents There were no gaseous effluents released during 2024. Table 2 lists and summarizes gaseous effluent releases in accordance with the ODCM.

4.0 Liquid Effluents There were no liquid effluent releases during 2024. Table 3 lists and summarizes liquid effluent releases in accordance with the ODCM.

5.0 Solid Waste There was no solid radioactive waste generated or shipped during 2024.

6.0 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 2024, there were no gaseous or liquid releases.

Dose due to all sources of the uranium fuel cycle (40CFR190) includes direct dose from tanks and ISFSI pads as well as gaseous and liquid effluents. Direct dose is measured using dosimeters placed on the fence around the ISFSI pad and in various places around the site. The nearest dosimeter reading to the spent fuel casks yielded values just above background. Other dosimeters further out but within site boundaries yielded background results. As such, the dose contribution from the dry cask storage to the nearest resident located approximately 2400 ft away (Figure 1) is not measurable.

7.0 Offsite Dose Calculation Manual The ODCM describes the radiological release requirements for the BRP site.

There were no revisions to the ODCM in 2024.

8.0 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 2024.

Page 4 of 11

2024 Annual Radioactive Effluent Release Re ort Plant: Bi Rock Point TABLE 1: Batch Releases A. GASEOUS Units 1ST QTR 2ND QTR 3RD QTR 4TH QTR Number of Releases N/A N/A N/A N/A Total Release Time Minutes N/A N/A N/A N/A Maximum Release Time Minutes N/A N/A N/A N/A Averaqe Release Time Minutes N/A N/A N/A N/A Minimum Release Time Minutes N/A N/A N/A N/A B. LIQUID 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 Averaqe Release Time Minutes N/A N/A N/A N/A Minimum Release Time Minutes N/A N/A N/A N/A Page 5 of 11

2024 Annual Radioactive Effluent Release Re ort Plant: Bi Rock Point TABLE 2: Gaseous Effluent Releases 1ST 2ND 3RD 4TH Est Total A. FISSION AND ACTIVATION GASES Units QTR QTR QTR QTR Error%

1. Total release Ci N/A N/A N/A N/A

2. Averaqe release rate for period uCi/sec N/A N/A N/A N/A N/A

3. Percent of annual avq EC N/A N/A N/A N/A B. IODINES

1. Total iodine Ci N/A N/A N/A N/A

2. Averaqe release rate for period uCi/sec N/A N/A N/A N/A N/A

3. Percent of annual avg EC N/A N/A N/A N/A C. PARTICULATES

1. Particulates with half-life >8 day Ci N/A N/A N/A N/A

2. Averaqe release rate for period uCi/sec N/A N/A N/A N/A N/A

3. Percent of annual avq 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 uCi/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) (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 public 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 Page 6 of 11

2024 Annual Radioactive Effluent Release Re ort Plant: Bi Rock Point TABLE 3: Gaseous Batch and Continuous Effluent Releases

1. NUCLIDES RELEASED Units 1ST QTR 2ND QTR 3RD QTR 4TH QTR Fission & Activation Gases Ci N/A N/A N/A N/A Iodines Ci N/A N/A N/A N/A Particulates*

Ci N/A N/A N/A N/A

• Particulates with half-life >8 days Page 7 of 11

2024 Annual Radioactive Effluent Release Re ort Plant: Bi Rock Point TABLE 4: Liquid Effluent Releases Est Total A. FISSION AND ACTIVATION PRODUCTS Units 1ST QTR 2ND QTR 3RD QTR 4TH QTR Error %

1. Total release (not including tritium, gases, alpha)

Ci N/A N/A N/A N/A N/A

2. Averaae diluted concentration durina period uCi/ml N/A N/A N/A N/A

3. Percent of EC N/A N/A N/A N/A B. TRITIUM

1. Total release Ci N/A N/A N/A N/A N/A

2. Average diluted concentration during period

µCi/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

µCi/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 Ci N/A N/A N/A N/A E. VOLUME OF WASTE RELEASED (Prior to dilution)

Liters N/A N/A N/A N/A F. VOLUME OF DILUTION WATER USED DURING PERIOD Liters N/A N/A N/A N/A G. MAXIMUM DOSE COMMITMENT 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 Page 8 of 11

2024 Annual Radioactive Effluent Release Re ort Plant: Bi Rock Point TABLE 5: Liquid Batch and Continuous Effluent Releases

1. NUCLIDES RELEASED Units 1ST QTR 2ND QTR 3RD QTR 4TH QTR Fission & Activation Product Total Ci N/A N/A N/A N/A Dissolved and Entrained Qases Ci N/A N/A N/A N/A Tritium Ci N/A N/A N/A N/A Page 9of 11

2024 Annual Radioactive Effluent Release Re ort Plant: Bi Rock Point Figure 1 Nearest Resident Measure distance Click on tile map to add to your path Total d stance* 2.385 74 fl (:,27 17 m)

Page 10of 11

2024 Annual Radioactive Effluent Release Re ort Plant: Bi Rock Point Figure 2 Dosimeter Locations Page 11of 11