ML24058A122
ML24058A122 | |
Person / Time | |
---|---|
Site: | La Crosse File:Dairyland Power Cooperative icon.png |
Issue date: | 02/27/2024 |
From: | Moe M Dairyland Power Cooperative |
To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards |
References | |
LAC-14545 | |
Download: ML24058A122 (1) | |
Text
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Martin G. Moe ISFSI Manager DAIRYLAND POWER February 27, 2024 LAC-14545 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, De 20555 - 0001 COOPERATIVE 10 CFR 50.4 and 10 CFR 50.36a La Crosse Boiling Water Reactor Independent Spent Fuel Storage Installation Possession-Only License No. DPR-45 NRC Docket Nos. 50-409 and 72-046
Subject:
La Crosse Boiling Water Reactor (LACBWR) Independent Spent Fuel Storage Installation (ISFSI) Annual Radiological Environmental Operating Report. and Changes to the Off-Site Dose Calculation Manual for 2023 In accordance with the Quality Assurance Program Description (QAPD), Appendix C, Section 1.4.1, "Annual Radiological Environmental Monitoring Report," and Section 1.4.2, "Annual Radioactive Effluent Release Report," this letter submits the 2023 reports for LACBWR ISFSI Possession-Only License No. DPR-45. The reports are required to be submitted prior to March ist per the QAPD reporting requirements. The 2023 Annual Radiological Environmental Operating Report, which includes the Radiological Environmental Monitoring Report and the Radioactive Effluent Release Report, is provided as Attachment 1 to this letter. Also included as part of this report are Issues 00 and 01 of the LACBWR ISFSI Offsite Dose Calculation Manual which are provided as.
There are no new regulatory commitments in this submittal. If you have any questions about this submittal, please contact Don Allison at (608) 689-4275.
Respectfully,
~
Martin G. Moe ISFSI Manager MGM:DNA:tco
Martin G. Moe ISFSI Manager DAIRYLAND POWER COOPERATIVE Attachments:
- 2. RP-20.01 Offsite Dose Calculation Manual, Issues 00 and 01 cc:
Bernard White Tilda Liu Jack Giessner Jeremy Browning, CNO LACBWR ISFSI Service List (w/o attachments)
LACBWR ISFSI SERVICE LIST Yoira Diaz-Sanabria Chief, Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards John Henkelman, Licensing Engineer Dairyland Power Cooperative La Crosse Boiling Water Reactor Independent Spent Fuel Storage Installation S4601 State Highway 35 Genoa, WI 54632-8846 Mark Paulson, Manager Radiation Protection Section State of Wisconsin Po Box 2659 Madison, WI 53701-2659 Page 1 of 1
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
License No. DPR-45 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January - December 2023
EXECUTIVE
SUMMARY
Tables 1 and 2 summarize the quantity of radioactive gaseous and liquid effluents, respectively, for each quarter of 2023. There were no gaseous or liquid releases in 2023. Table 3 summarizes waste shipped offsite for disposal for 2023. There was no waste shipped for disposal in 2023.
Appendices A and B indicate the status of reportable items per the requirements of the Offsite Dose Calculation Manual (ODCM). There were no reportable items in 2023. Appendix C presents any changes in the ODCM. The ODCM was revised in its entirety during 2023.
LACBWR ISFSI 2023 Annual RER Report Page 1 of 13
Table 1 LACBWR ISFSI Effluent and Waste Disposal Annual Report 2023 Gaseous Effluents - Summation of All Releases Nuclides Released Units 1st 2nd 3rd 4th Quarter Quarter Quarter Quarter A. Fission and Activation Gases Total Release Ci N/A*
N/A*
N/A*
N/A*
Average release rate
µCi/s N/A*
N/A*
N/A*
N/A*
Percent of regulatory limit N/A*
N/A*
N/A*
N/A*
B. Iodines Total Iodines released Ci N/A*
N/A*
N/A*
N/A*
Average release rate
µCi/s N/A*
N/A*
N/A*
N/A*
Percent of regulatory limit N/A*
N/A*
N/A*
N/A*
C. Particulates Particulates Released Ci N/A*
N/A*
N/A*
N/A*
Average release rate
µCi/s N/A*
N/A*
N/A*
N/A*
Percent of regulatory limit N/A*
N/A*
N/A*
N/A*
Gross alpha radioactivity Ci N/A*
N/A*
N/A*
N/A*
D. Tritium Total release Ci N/A*
N/A*
N/A*
N/A*
Average release rate
µCi/s N/A*
N/A*
N/A*
N/A*
Percent of regulatory limit N/A*
N/A*
N/A*
N/A*
N/A*= Not Applicable Error N/A*
N/A*
N/A*
N/A*
There are no gaseous effluents associated with the LACBWR Independent Spent Fuel Storage Installation (ISFSI}
LACBWR ISFSI 2023 Annual RER Report Page 2 of 13
Table 1A LACBWR ISFSI Effluent and Waste Disposal Annual Report 2023 Gaseous Effluents - Ground Level Releases - Batch Mode Nuclides Released Unit 1st 2nd 3rd 4th Total Quarter Quarter Quarter Quarter
- 1. Fission Gases Krypton-85 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Krypton-85m Ci N/A*
N/A*
N/A*
N/A*
N/A*
Krypton-87 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Krypton-88 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Xenon-133 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Xenon-135 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Xenon-13Sm Ci N/A*
N/A*
N/A*
N/A*
N/A*
Xenon-138 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Unidentified Ci N/A*
N/A*
N/A*
N/A*
N/A*
Total for period Ci N/A*
N/A*
N/A*
N/A*
N/A*
- 2. Iodines lodine-131 Ci N/A*
N/A*
N/A*
N/A*
N/A*
lodine-133 Ci N/A*
N/A*
N/A*
N/A*
N/A*
lodine-135 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Total for period Ci N/A*
N/A*
N/A*
N/A*
N/A*
- 3. Particulates Strontium-89 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Strontium-90 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Cesium-134 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Cesium-137 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Cobalt-GO Ci N/A*
N/A*
N/A*
N/A*
N/A*
Barium-Lanthanum-140 Ci N/A*
N/A*
N/A*
N/A*
N/A*
- 4. Others-Ci N/A*
N/A*
N/A*
N/A*
N/A*
Plutonium-238 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Curium-243,244 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Uranium-234 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Uranium-238 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Thorium-232 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Radium-226 Ci N/A*
N/A*
N/A*
N/A*
N/A*
N/A*= Not Applicable There are no gaseous effluents associated with the LACBWR Independent Spent Fuel Storage Installation (ISFSI)
LACBWR ISFSI 2023 Annual RER Report Page 3 of 13
Table 1B LACBWR ISFSI Effluent and Waste Disposal Annual Report 2023 Gaseous Effluents - Ground Level Releases - Continuous Mode Nuclides Released Unit 1st 2nd 3rd 4th Total Quarter Quarter Quarter Quarter
- 1. Fission Gases Krypton-85 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Krypton-85m Ci N/A*
N/A*
N/A*
N/A*
N/A*
Krypton-87 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Krypton-88 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Xenon-133 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Xenon-135 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Xenon-135m Ci N/A*
N/A*
N/A*
N/A*
N/A*
Xenon-138 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Unidentified Ci N/A*
N/A*
N/A*
N/A*
N/A*
Total for period Ci N/A*
N/A*
N/A*
N/A*
N/A*
- 2. Iodines lodine-131 Ci N/A*
N/A*
N/A*
N/A*
N/A*
lodine-133 Ci N/A*
N/A*
N/A*
N/A*
N/A*
lodine-135 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Total for period Ci N/A*
N/A*
N/A*
N/A*
N/A*
- 3. Particulates Strontium-89 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Strontium-90 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Cesium-134 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Cesium-137 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Cobalt-GO Ci N/A*
N/A*
N/A*
N/A*
N/A*
Barium-Lanthanum-140 Ci N/A*
N/A*
N/A*
N/A*
N/A*
- 4. Others-Plutonium-238 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Curium-243,244 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Uranium-234 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Uranium-238 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Thorium-232 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Radium-226 Ci N/A*
N/A*
N/A*
N/A*
N/A*
N/A*= Not Applicable There are no gaseous effluents associated with LACBWR Independent Spent Fuel Storage Installation
{ISFSI)
LACBWR ISFSI 2023 Annual RER Report Page 4 of 13
Table lC LACBWR ISFSI Effluent and Waste Disposal Annual Report 2023 Gaseous Effluents - Elevated Releases - Batch Mode Nuclides Released Unit 1st 2nd 3rd 4th Quarter Quarter Quarter Quarter
- 1. Fission Gases Krypton-85 Ci N/A*
N/A*
N/A*
N/A*
Krypton -85m Ci N/A*
N/A*
N/A*
N/A*
Krypton -87 Ci N/A*
N/A*
N/A*
N/A*
Krypton -88 Ci N/A*
N/A*
N/A*
N/A*
Xenon-133 Ci N/A*
N/A*
N/A*
N/A*
Xenon-135 Ci N/A*
N/A*
N/A*
N/A*
Xenon-135m Ci N/A*
N/A*
N/A*
N/A*
Xenon-138 Ci N/A*
N/A*
N/A*
N/A*
Unidentified 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-133 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*
- 3. Particulates Strontium-89 Ci N/A*
N/A*
N/A*
N/A*
Strontium-90 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*
Cobalt-GO Ci N/A*
N/A*
N/A*
N/A*
Barium-Lanthanum-140 Ci N/A*
N/A*
N/A*
N/A*
- 4. Others-Plutonium-238 Ci N/A*
N/A*
N/A*
N/A*
Curium-243,244 Ci N/A*
N/A*
N/A*
N/A*
Uranium-234 Ci N/A*
N/A*
N/A*
N/A*
Uranium-238 Ci N/A*
N/A*
N/A*
N/A*
Thorium-232 Ci N/A*
N/A*
N/A*
N/A*
Radium-226 Ci N/A*
N/A*
N/A*
N/A*
N/A*= Not Applicable There are no gaseous effluents associated with LACBWR Independent Spent Fuel Storage Installation (ISFSI)
Total N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
LACBWR ISFSI 2023 Annual RER Report Page 5 of 13
Table 10 LACBWR ISFSI Effluent and Waste Disposal Annual Report 2023 Gaseous Effluents - Elevated Releases - Continuous Mode Nuclides Released Unit 1st 2nd 3rd 4th Total Quarter Quarter Quarter Quarter
- 1. Fission Gases Krypton-85 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Krypton-85m Ci N/A*
N/A*
N/A*
N/A*
N/A*
Krypton-87 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Krypton-88 Ci N/A*
N/A*
N/A*
N/A*
NIA*
Xenon-133 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Xenon-135 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Xenon-13Sm Ci N/A*
N/A*
N/A*
N/A*
N/A*
Xenon-138 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Unidentified Ci N/A*
N/A*
N/A*
N/A*
N/A*
Total for period Ci N/A*
N/A*
N/A*
N/A*
N/A*
- 2. Iodines lodine-131 Ci N/A*
N/A*
N/A*
N/A*
N/A*
lodine-133 Ci N/A*
N/A*
N/A*
N/A*
N/A*
lodine-135 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Total for period Ci N/A*
N/A*
N/A*
N/A*
N/A*
- 3. Particulates Strontium-89 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Strontium-90 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Cesium-134 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Cesium-137 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Cobalt-60 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Barium-Lanthanum-140 Ci N/A*
N/A*
N/A*
N/A*
N/A*
- 4. Others-Plutonium-238 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Curium-243,244 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Uranium-234 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Uranium-238 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Thorium-232 Ci N/A*
N/A*
N/A*
N/A*
N/A*
Radium-226 Ci N/A*
N/A*
N/A*
N/A*
N/A*
N/A*= Not Applicable There are no gaseous effluents associated with the LACBWR Independent Spent Fuel Storage Installation (ISFSI)
LACBWR ISFSI 2023 Annual RER Report Page 6 of 13
Table 2 LACBWR ISFSI Effluent and Waste Disposal Annual Report 2023 Liquid Effluents - Summation of All Releases Nuclides Released Units 1st 2nd 3rd Quarter Quarter Quarter A. Fission and Activation Products Total Release (not including Ci N/A*
N/A*
N/A*
tritium, gases, alpha}
Average diluted concentration
µCi/ml N/A*
N/A*
N/A*
during period Percent of applicable limit N/A*
N/A*
N/A*
B. Tritium Total Release Ci N/A*
N/A*
N/A*
Average diluted concentration
µCi/ml N/A*
N/A*
N/A*
during period Percent of applicable limit N/A*
N/A*
N/A*
C. Dissolved and Entrained Gases Total Release Ci N/A*
N/A*
N/A*
Average diluted concentration
µCi/ml N/A*
N/A*
N/A*
during period Percent of applicable limit N/A*
N/A*
N/A*
D. Gross Alpha Radioactivity Total Release Ci N/A*
N/A*
N/A*
Average diluted concentration
µCi/ml N/A*
N/A*
N/A*
during period E. Volume of Waste Released Liters N/A*
N/A*
N/A*
(prior to dilution)
F. Volume of Dilution Water Used Liters N/A*
N/A*
N/A*
During Period N/A*- Not Applicable 4th Quarter N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
There are no liquid effluents associated with the LACBWR Independent Spent Fuel Storage Installation (ISFSI}
LACBWR ISFSI 2023 Annual RER Report Page 7 of 13 Error N/A*
N/A*
N/A*
N/A*
Table 2A LACBWR ISFSI Effluent and Waste Disposal Annual Report 2023 Liquid Effluents -
Batch Mode Nuclides Released Units 1st 2nd 3rd Quarter Quarter Quarter Strontium-89 Ci N/A*
N/A*
N/A*
Strontium-90 Ci N/A*
N/A*
N/A*
Cesium-134 Ci N/A*
N/A*
N/A*
Cesium-137 Ci N/A*
N/A*
N/A*
lodine-131 Ci N/A*
N/A*
N/A*
Cobalt-58 Ci N/A*
N/A*
N/A*
Cobalt-GO Ci N/A*
N/A*
N/A*
lron-59 Ci N/A*
N/A*
N/A*
Zinc-GS Ci N/A*
N/A*
N/A*
Manganese-54 Ci N/A*
N/A*
N/A*
Chromium-51 Ci N/A*
N/A*
N/A*
Zirconium-Niobium-95 Ci N/A*
N/A*
N/A*
Molybdenum-99 Ci N/A*
N/A*
N/A*
Technetium-99m Ci N/A*
N/A*
N/A*
Barium-Lathanium-140 Ci N/A*
N/A*
N/A*
Cerium-141 Ci N/A*
N/A*
N/A*
Others-lron-55 Ci N/A*
N/A*
N/A*
Antimony-125 Ci N/A*
N/A*
N/A*
Unidentified Ci N/A*
N/A*
N/A*
Total for period (above)
Ci N/A*
N/A*
N/A*
Dissolved and Entrained Ci N/A*
N/A*
N/A*
Gasses Tritium Ci N/A*
N/A*
N/A*
Gross Alpha Ci N/A*
N/A*
N/A*
N/A*= Not Applicable 4th Quarter N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
There are no liquid effluents associated with the LACBWR Independent Spent Fuel Storage Installation {ISFSI)
Totals N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
LACBWR ISFSI 2023 Annual RER Report Page 8 of 13
Table 2B LACBWR ISFSI Effluent and Waste Disposal Annual Report 2023 Liquid Effluents -
Continuous Mode Nuclides Released Unit 1st 2nd 3rd Quarter Quarter Quarter Strontium-89 Ci N/A*
N/A*
N/A*
Strontium-90 Ci N/A*
N/A*
N/A*
Cesium-134 Ci N/A*
N/A*
N/A*
Cesium-137 Ci N/A*
N/A*
N/A*
lodine-131 Ci N/A*
N/A*
N/A*
Cobalt-58 Ci N/A*
N/A*
N/A*
Cobalt-GO Ci N/A*
N/A*
N/A*
lron-59 Ci N/A*
N/A*
N/A*
Zinc-GS Ci N/A*
N/A*
N/A*
Manganese-54 Ci N/A*
N/A*
N/A*
Chromium-51 Ci N/A*
N/A*
N/A*
Zirconium-Niobium-95 Ci N/A*
N/A*
N/A*
Molybdenum-99 Ci N/A*
N/A*
N/A*
Technetium-99m Ci N/A*
N/A*
N/A*
Barium-Lathanium-140 Ci N/A*
N/A*
N/A*
Cerium-141 Ci N/A*
N/A*
N/A*
Others-lron-55 Ci N/A*
N/A*
N/A*
Antimony -125 Ci N/A*
N/A*
N/A*
Unidentified Ci N/A*
N/A*
N/A*
Total for period (above)
Ci N/A*
N/A*
N/A*
Dissolved and Entrained Ci N/A*
N/A*
N/A*
Gasses Tritium Ci N/A*
N/A*
N/A*
Gross Alpha Ci N/A*
N/A*
N/A*
N/A*= Not Applicable 4th Quarter N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
There are no liquid effluents associated with the LACBWR Independent Spent Fuel Storage Installation {ISFSI)
Totals N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
N/A*
LACBWR ISFSI 2023 Annual RER Report Page 9 of 13
Table 3 LACBWR ISFSI Effluent and Waste Disposal Annual Report 2023 Low Level Waste Shipments Resins, Filters and Evaporator Bottoms Volume Waste Class Solidifying Agent ft3 m3 A
0 0
B 0
0 C
0 0
All 0
0 Major radionuclides for above data:
Dry Active Waste Volume Waste Class Solidifying Agent ft3 m3 A
0 0
B 0
0 C
0 0
All 0
0 Major radionuclides for above data:
Irradiated Components Volume Waste Class Solidifying Agent ft3 m3 A
0 0
B 0
0 C
0 0
All 0
0 Major radionuclides for above data:
Other Waste Volume Waste Class Solidifying Agent ft3 m3 A
0 0
B 0
0 C
0 0
All 0
0 Major radionuclides for above data:
LACBWR ISFSI 2023 Annual RER Report Curies Shipped Curies 0
0 0
0 Curies Shipped Curies 0
0 0
0 Curies Shipped Curies 0
0 0
0 Curies Shipped Curies 0
0 0
0 Page 10 of 13
Appendix A Radiation Dose Assessment There were no gaseous or liquid effluent releases in 2023 at the LACBWR ISFSI, therefore, no calculations were required to show compliance with 40 CFR 190. An assessment of radiation doses to the most likely exposed member(s) of the public for direct radiation was conducted to show compliance with 10 CFR 72.104.
LACBWR ISFSI 2023 Annual RER Report Page 11 of 13
Appendix B Unplanned Releases There were no unplanned releases of radioactive materials from the LACBWR ISFSI in 2023.
LACBWR ISFSI 2023 Annual RER Report Page 12 of 13
Appendix C Offsite Dose Calculation Manual (ODCM) Changes LACBWR ISFSI procedure RP-20.01, Offsite Dose Calculation Manual (ODCM), was revised in its entirety during 2023 due to transfer of the NRC Possession-Only License (DPR-45) from LaCrosseSolutions back to Dairyland Power Cooperative. Later, section 8.1 Radioactive Effluent Control Program, was revised to incorporate into the program, the Radioactive Effluent Control Program (RECP) and added sections for liquid, gaseous and tritium effluents. A reference was added to the ODCM to reference the NAC International, Inc. Final Safety Analysis (FSAR) for the NAC Multi-Purposed Canister (NAC-MPC) System.
The second revision in 2023 was made to fully align the ODCM with the Quality Assurance Program Description (QAPD). There was no reduction in effectiveness from the ODCM changes in 2023.
LACBWR ISFSI 2023 Annual RER Report Page 13 of 13
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
License No. DPR-45 ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT January - December 2023
EXECUTIVE
SUMMARY
The La Crosse Boiling Water Reactor (LACBWR) Independent Spent Fuel Storage Installation
{ISFSI) has been in operation since 2012. All fuel has been transferred into dry storage casks and placed at the Independent Spent Fuel Storage Installation. The Radiological Environmental Monitoring Program (REMP) for the LACBWR ISFSI located in Genoa, Wisconsin was continued for the period January through December 2023 in compliance with the LACBWR ISFSI Offsite Dose Calculation Manual {ODCM).
By design, there are no liquid or gaseous effluents associated with the operation of the ISFSI.
Therefore, the ODCM only requires monitoring of direct exposure from the installation. There were changes made to the Offsite Dose Calculation Manual in 2023, however, there was no reduction in effectiveness of the ODCM from the changes.
Thermoluminescent Dosimeter {TLDs) were used to measure direct gamma exposure at ten locations in the vicinity of the ISFSI and Owner Controlled Area fence. Two Environmental Background TLDs are located approximately 0. 72 kilometers away from the ISFSI pad. The results of these measurements showed no significant change in exposure rates and potential doses to members of the public during the monitoring period. The results of the monitoring performed in 2023 showed that operating the LACBWR ISFSI results in only a small fraction of the 40 CFR Part 190 and 10 CFR Part 72.104 direct radiation dose limit of 25 mrem/year to members of the public.
LACBWR ISFSI 2023 Annual REO Report Page 1 of 24
TABLE OF CONTENTS Section Title Page
1.0 INTRODUCTION
5 2.0 GENERAL ISFSI AND SITE INFORMATION 5
3.0 PROGRAM DESIGN 6
3.1 MONITORING ZONES 6
3.2 PATHWAYS MONITORED 6
3.3 DESCRIPTION
OF MONITORING PROGRAM 6
4.0 RADIOLOGICAL DATA
SUMMARY
TABLES 11 5.0 ANALYSIS OF ENVIRONMENTAL RESULTS 22 5.1 SAMPLING PROGRAM DEVIATIONS 22 5.2 DIRECT RADIATION PATHWAY 22
6.0 REFERENCES
23 7.0 ERRATA DATA 23 LACBWR ISFSI 2023 Annual REO Report Page 2 of 24
LIST OF TABLES Table Title Page 3.1 Radiological Environmental Monitoring Program........................................................... 8 3.2 Radiological Environmental Monitoring Locations......................................................... 9 4.1 TLD Measurements by Quarter.................................................................................... 12 4.2 TLD Data Summary....................................................................................................... 13 4.3 Direct Dose from ISFSI Operations................................................................................ 14 4.4 Errata Data.................................................................................................................. 24 LACBWR ISFSI 2023 Annual REO Report Page 3 of 24
Figure LIST OF FIGURES Title Page 3.1 Radiological Environmental Monitoring Locations.................................................. 10 4.1 Annual Dose Trend at Environmental 1 Location..................................................... 16 4.2 Annual Dose Trend at Environmental 6 Location..................................................... 17 4.3 Annual Dose Trend at Environmental 7 Location..................................................... 18 4.4 Annual Dose Trend at Environmental 8 Location..................................................... 19 4.5 Annual Dose Trend at Environmental 9 Location..................................................... 20 4.6 Annual Dose Trend at Environmental 10 Location................................................... 21 LACBWR ISFSI 2023 Annual REO Report Page 4 of 24
1.0 INTRODUCTION
This report summarizes the findings of the Radiological Environmental Monitoring Program (REMP) conducted by Dairyland Power Cooperation (DPC) LACBWR Independent Spent Fuel Storage Installation in Genoa, Wisconsin during the calendar year 2023. It is submitted annually in compliance with the Offsite Dose Calculation Manual {ODCM).
2.0 GENERAL ISFSI AND SITE INFORMATION The La Crosse Boiling Water Reactor (LACBWR) Independent Spent Fuel Storage Installation {ISFSI) The LACBWR ISFSI is located one mile south of the village of Genoa, Wisconsin, on the east bank of the Mississippi River. Also located on the 163.5-acre site is the coal-fired generating plant Genoa 3 {G-3). The G-3 plant is in the process of being decommissioned.
The LACBWR ISFSI is located south of the G-3 plant, about midway between the Mississippi River on the west and Highway 35 on the east and is between the two closed ash landfills of the Genoa site.
In the vicinity of the site, the river valley is deeply cut into highly dissected uplands. From La Crosse 19 miles north to Prairie du Chien approximately 40 miles south, the valley varies between 2 % and 4% miles in width. The valley walls rise sharply 500 to 600 feet from river level. There is little or no agricultural use of the river valley floor which consists primarily of marshy land, islands between river channels and extensions of low-lying flood plain cut by ponds, sloughs, and meandering stream channels. Numerous short, steep-sided valleys that have been cut into the uplands by tributary streams intercept the main river valley. Both walls of the main channel are wooded.
The flat upland areas and some of the tributary valleys are cultivated and grazed. The prevailing winds are subjected to the channeling effects of the river valley. This channeling directs almost all of the regional scale cross-valley winds into the north-south orientation of the valley. Wind speeds are also lower as a result of vertical decoupling caused by the river valley. In summer, low wind speeds cause air stagnation in the valley during periods of hot humid weather, and in winter some deepening of inversion conditions can cause a stagnant layer of cold air on the valley floor.
There are no major industrial or military facilities of any type in this area; it is principally used for agriculture. There are no facilities or airports using large commercial or military aircraft in the nearby area. There are no industrial facilities of any significant size in the surrounding area. Transportation routes include the twin-track Burlington Northern Sante Fe Railroad line which is west of and parallel to Highway 35. The Mississippi River main channel to the west of the site is used for barge transportation.
LACBWR ISFSI 2023 Annual REO Report Page 5 of 24
3.0 PROGRAM DESIGN The REMP for the LACBWR ISFSI was designed to provide assurance to regulatory agencies and the public that the station's environmental impact is known and within anticipated limits. The direct dose limit for members of the public from operation of the ISFSI is less than 25 mrem per year (References 3 and 4).
The detailed sampling requirements of the REMP are given in the ODCM. The sampling requirements specified in the ODCM are summarized in Table 3.1 of this report. Details of the monitored locations are shown in Table 3.2, as well as Figures 3.1 of this report.
3.1 Monitoring Zones The REMP is designed to allow comparison of levels of radioactivity in samples from the area possibly influenced by the ISFSI to levels found in areas not influenced by the ISFSI. The first area is called "Environmental TLDs". The second area is called "Environmental Background TLDs". The distinction between the two is based on relative direction from the installation and distance. Analysis of survey data from the two zones aids in determining if there is a significant difference between the two areas. It can also help in differentiating between radioactivity or radiation due to releases and that due to other fluctuations in the environment, such as seasonal variations in the natural background.
Environmental TLD locations 1, 6, 7, 8, 9 and 10 are used to assess ambient dose conditions to the public and are located on the Owner Controlled Area (OCA) fence. Environmental TLD locations 2 through 5 are located on the Protected Area (PA) fence in order to monitor and trend dose for information only from the ISFSI Pad.
3.2 Pathways Monitored Based on the design of the ISFSI, the only exposure pathway is direct radiation exposure, monitored by the REMP. This pathway is monitored by the collective placement of thermoluminescent dosimeters (TLDs) which are described in more detail in the following section.
3.3 Description of Monitoring Program 3.3.1 Direct Radiation Direct gamma radiation exposure was continuously monitored during 2023 with the use of thermoluminescent dosimeters (TLDs). At each monitoring location, these TLDs are sealed in plastic bags and attached to an object such as a fence. The TLDs are posted and retrieved on a quarterly basis.
LACBWR ISFSI 2023 Annual REO Report Page 6 of 24
All TLDs are provided and processed by a National Voluntary Laboratory Accreditation Program (NVLAP) certified vendor. The TLDs are placed at various locations around the ISFSI. Table 3.2 lists the Environmental TLD location numbers, distances, and direction of the TLDs from the ISFSI.
3.3.2 Special Monitoring Special samples can be taken that are not required in the ODCM. No special samples were collected in 2023.
LACBWR ISFSI 2023 Annual REO Report Page 7 of 24
Table 3.1 Radiological Environmental Monitoring Program Exposure Collection Analysis Pathway Analysis Analysis and/or Number of Sample Routine Collection Sample Media Locations Sampling Mode Frequency Type Frequency Direct Total Locations: 12 (6 Continuous Quarterly Gamma Quarterly Radiation around perimeter of dose (TLD) the OCA, 4 around the perimeter of the PA fence and 2 offsite control locations)
LACBWR ISFSI 2023 Annual REO Report Page 8 of 24
Table 3.2 Radiological Environmental Monitoring Locations Environmental Station Description Distance Direction TLD Location #
From ISFSI (feet)
From ISFSI 1
ISFSI Administrative Building 373 w
2*
ISFSI Protected Area 25 NE 3*
ISFSI Protected Area so NW 4*
ISFSI Owner Control Fence 573 N
7 ISFSI Owner Control Fence 361 w
8 ISFSI Owner Control Fence 516 E
9 ISFSI Owner Control Fence 483 NE 10 ISFSI Owner Control Fence 798 w
11 Background Dosimeter #1 2360 NE 12 Background Dosimeter #2 2365 NE
¥ Figure 3.1 Radiological Environmental Monitoring Locations
-M*
-"'-------~
--c~r~--'-= =~-'}:
..... c
(,
)1
-~--
,~,~ /
~
1
- ---- _S?_
/ "-...,, ~c.; ~" -~- - '--'L.:10
"(,,)~
!!!!!!I tJ;ao..
LACBWR ISFSI 2023 Annual REO Report
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-..;<ll'f.--.----.
- -e;:**1~
h 1J Page 10 of 24
4.0 RADIOLOGICAL DATA
SUMMARY
TABLES This section summarizes the analytical results of the environmental samples, which were collected during the monitoring period.
Data from direct radiation measurements made by TLDs are presented in Table 4.1.
The summarized TLD measurements, shown in Table 4.2, are presented in a format similar to that prescribed in the NRCs Radiological Assessment Branch Technical Position on Environmental Monitoring (Reference 1).
Table 4.3 presents the estimated direct dose from ISFSI operations as determined by TLD data shown in Table 4.1.
Table 4.4 contains Errata Data to correct an error made in the 2022 report.
LACBWR ISFSI 2023 Annual REO Report Page 11 of 24
Table 4.1 TLD Measurements by Quarter (mrem)
Location Direction 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Number 1
w 1
1 1
0 2
NE 23 20 20 24 3
NW 76 67 78 77 4
SW 10 15 15 18 5
SE 23 25 27 28 6
N 1
1 1
0 7
w 1
1 1
0 8
E 1
3 3
2 9
NE 1
2 2
1 10 w
3 4
4 3
11 NE 18 15 17 21 12 NE 18 15 17 21 LACBWR ISFSI 2023 Annual REO Report Page 12 of 24
Table 4.2 TLD Data Summary (mrem)
- OCA Fence TLDs Env BkgTLDs OCA Fence TLD with Highest Mean Mean Range Mean Range Location Mean Range No. Measurements+
No. Measurements +
Number No. Measurements+
1.6 17.8 10 3.5 1-4 15-21 3-4 24 8
4
+Each "measurement" is based on quarterly readings.
LACBWR ISFSI 2023 Annual REO Report Page 13 of 24
Table 4.3 Direct Dose from ISFSI Operation (mrem) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Net Net Net Location TLD Calculated TLD Calculated TLD Calculated NetTLD Calculated Annual Number Results Dose Results Dose Results Dose Results Dose Dose 1
1 0.01 1
0.01 1
0.01 0
0.00 0.03 6
1 0.01 1
0.01 1
0.01 0
0.00 0.03 7
1 0.01 1
0.01 1
0.01 0
0.00 0.03 8
1 0.01 3
0.02 3
0.02 2
0.02 0.07 9
1 0.01 2
0.02 2
0.02 1
0.01 0.06 10 3
0.02 4
0.03 4
0.03 3
0.02 0.10 Maximum Dose=>
0.10 Note:
Doses based on a 67-hour occupancy in unrestricted area for the year.
LACBWR ISFSI 2023 Annual REO Report Page 14 of 24
Radiological Environmental Monitoring Program Trending A series of graphs of REMP TLD data have been developed and are provided for trending purposes.
The trending is developed for each of the Environmental TLD locations based on the annual historical doses. The trending is provided for the "real members of the public" based on the guidance provided in the ODCM. The analysis of the trends and associated data shows very small annual doses with minor fluctuations in the data. In this report, the Environmental TLD results have been summarized and the annual doses, calculated for "real members of the public" based upon guidance in the ODCM, have been plotted for trending.
LACBWR ISFSI 2023 Annual REO Report Page 15 of 24
Figure 4.1 Annual Dose Trend at Environmental 1 Location Environmental 1 30.00 25.00
.._ 20.00
~ 15.00 E 10.00 5.00 0.03 0.03 0.13 0.03 0.08 0.02 0.00 2018 2019 2020 2021 2022 2023 Year
~
Environmental 1
~
Reg limit Annual Doses (mrem/yr)
Location 2018 2019 2020 2021 2022 2023 Environmental 1 0.03 0.13 0.03 0.08 0.02 0.03 LACBWR ISFSI 2023 Annual REO Report Page 16 of 24
Figure 4.2 Annual Dose Trend at Environmental 6 Location Environmental 6 30.00 25.00... ____.,. ____.... ____..,. __________ _
,._ 20.00
~ 15.00 E 10.00 5.00 0.04 0.11 0.01 0.05 0.08 0.03 0.00 ______.,. ____.... ____..,. ____.,.. ____...
2018 2019 2020 2021 2022 2023 Year
~
Environmental 6
~
Reg Limit Annual Doses (mrem/yr)
Location 2018 2019 2020 2021 2022 2023 Environmental 6 0.04 0.11 0.01 0.05 0.08 0.03 LACBWR ISFSI 2023 Annual REO Report Page 17 of 24
Figure 4.3 Annual Dose Trend at Environmental 7 Location Environmental 7 30.00 25.00.,_ ___.,_ ___.,_ ___,._ ___,._ ___
.._ 20.00
~ 15.00 E 10.00 5.00 0.06 0.13 0.03 0.08 0.04 0.03 0.00 _____.,_ ___..., ___..., ___,._ ___
2018 Location Environmental 7 2019 2020 Year 2021
--Environmental 7 --Reg Limit Annual Doses (mrem/yr) 2018 2019 2020 2021 0.06 0.13 0.03 0.08 LACBWR ISFSI 2023 Annual REO Report 2022 2023 2022 2023 0.04 0.03 Page 18 of 24
Figure 4.4 Annual Dose Trend at Environmental 8 Location Environmental 8 30.00 25.00.,_ ____,._ ____..., ____... ____..., ____.,.
.... 20.00
~ 15.00 L.
E 10.00 5.00 0.08 0.15 0.06 0.10 0.06 0.07 0.00.,_ ____..., ____,._ ____... ____..., ____.,.
2018 2019 2020 2021 2022 2023 Year
~
Environmental 8
~
Reg Limit Annual Doses (mrem/yr)
Location 2018 2019 2020 2021 2022 2023 Environmental 8 0.08 0.15 0.06 0.10 0.06 0.07 LACBWR ISFSI 2023 Annual REO Report Page 19 of 24
Figure 4.5 Annual Dose Trend at Environmental 9 Location Environmental 9 30.00 25.00 ---------------~
...... ------~----41------e
'-- 20.00
~ 15.00 E 10.00 5.00 0.02 0.15 0.03 0.03 0.06 0.06 0.00 _______________....,j...... ------~-----e-----o 2018 2019 2020 2021 2022 2023 Year
~
Environmental 9
~
Reg Limit Annual Doses (mrem/yr)
Location 2018 2019 2020 2021 2022 2023 Environmental 9 0.02 0.15 0.03 0.03 0.06 0.06 LACBWR ISFSI 2023 Annual REO Report Page 20 of 24
Figure 4.6 Annual Dose Trend at Environmental 10 Location Environmental 10 30.00 25.00 ______,._ ____... ____... ____..., ____ __
,.._ 20.00
-2:
~ 15.00 E 10.00 5.00 0.13 0.17 0.10 0.17 0.10 0.10 0.00 _____,._ ____,.. ____..,. ____.., ____ __
2018 2019 2020 2021 2022 2023 Year
~
Environmental 10
~
Reg Limit Annual Doses (mrem/yr)
Location 2018 2019 2020 2021 2022 2023 Environmental 10 0.13 0.17 0.10 0.17 0.10 0.10 LACBWR ISFSI 2023 Annual REO Report Page 21 of 24
5.0 ANALYSIS OF ENVIRONMENTAL RESULTS 5.1 Sampling Program Deviations A sampling program deviation is defined as samples that are unobtainable due to hazardous conditions or to malfunction of sampling equipment. Such deviations do not compromise the program's effectiveness and in fact are considered.
insignificant with respect to what is normally anticipated for this Radiological Environmental Monitoring Program.
There were no deviations during the monitoring year 2023.
5.2 Direct Radiation Pathway 5.2.1 Annual Dose Trends Direct radiation is continuously measured at 10 Environmental locations surrounding the LACBWR ISFSI, 6 are located on the Owner Controlled Area (OCA) fence, monitoring dose to the public and 4 located on the Protected Area (PA) are used for trending purposes only. There are also, 2 Environmental Background locations using thermoluminescent dosimeters (TLDs). These dosimeters are collected on a quarterly basis for readout at the NVLAP certified dosimetry services vendor.
Review of the data in Figures 4.1 through 4.6 shows no significant difference in annual doses over time at the indicator locations and their relation to the 25 mrem/yr limit.
5.2.2 Direct Doses from ISFSI Operations A dose estimate is the potential dose to any real member of the public that could use portions of the site or be present adjacent to the site for recreational activities throughout the year. Direct exposure above background can be estimated by subtracting the average TLD value of the Environmental Background TLDs from the Environmental TLD location measurements. The 2023 dose estimate assumes a total of 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> maximum occupancy for the dose calculation. The most likely location for exposure to a member of the public from the ISFSI at the Public Boat Launch at approximately 840 feet from ISFSI pad, near Environmental 10 TLD location.
Table 4.3 presents the results of the dose calculations. The highest calculated dose is at the Environmental 10 TLD location. The maximum calculated annual dose at those locations is 0.10 mrem. This value is only 0.4 percent of the 25 mrem per year limit.
LACBWR ISFSI 2023 Annual REO Report Page 22 of 24
6.0 REFERENCES
- 1. USN RC Radiological Assessment Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program," Revision 1, November 1979.
- 2. LACBWR ISFSI Radiation Protection Procedure, RP-20.01, Offsite Dose Calculation Manual, Issue 01.
- 3. 40 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operation".
- 4. 10 CFR Part 72.104, "Criteria for Radioactive Materials in Effluents and Direct Radiation from an ISFSI or MRS".
7.0 ERRATA DATA A typographical error was noted in the 2022 LACBWR AREOR, Table 3, "Quarterly Environmental TLD Results for ISFSI Area." For the fourth quarter of 2022, Station Location No. 1 was recorded as 2 mrem for the period when the completed TLD form and raw data provided a dose of 1 mrem. The decrease of Station Location No. 1 from 2 mrem to 1 mrem does not result in a change in the maximum Whole-Body Dose for 2022.
Table 4.4 shows the corrected Table 3 from the 2022 LACBWR AREOR.
LACBWR ISFSI 2023 Annual REO Report Page 23 of 24
Table 4.4 Errata Data QUARTERLY ENVIRONMENTAL TLD RESULTS FOR ISFSI AREA February 09, 2022 - January 01,2023 STATION NO.
1st QUARTER 2nd QUARTER 3rd QUARTER 4THQuarter mRem mRem mRem mRem 1
</=BKG
</=BKG 1.0 1.0 2
13.0 20.0 22.0 20.0 3
41.0 64.0 75.0 61.0 4
9.0 15.0 15.0 15.0 5
17.0 23.0 25.0 24.0 6 (*)
</=BKG 0.02 0.05 0.02 7 (*)
</=BKG 0.02 0.01 0.02 8 (*)
0.01 0.01 0.02 0.03 9 (*)
0.01 0.02 0.02 0.02 10 (*)
0.02 0.02 0.03 0.03 All background corrected and those on Owner Controlled Area fence line identified with (*) had occupancy factor correction applied if> background TLD results.
LACBWR ISFSI 2023 Annual REO Report Page 24 of 24
ATTACHMENT 2 DAIRYLAND POWER COOPERATIVE LACBWR ISFSI OFFSITE DOSE CALCULATION MANUAL CHANGES JANUARY - DECEMBER 2023
ILACBWR ISFSI RP-20.01 Issue 00 RADIATION PROTECTION PROCEDURE RP-20.01 OFFS/TE DOSE CALCULATION MANUAL PREPARER: k ~
DATE: /6.~-a
-:)bL I
QUALIFIED TECHNICAL RFENIEWEecf)L._. DATE:#2.3
ISSUE NOTICE LACBWR ISFSI RADIATION PROTECTION PROCEDURE OFFS/TE DOSE CALCULATION MANUAL (ODCM)
INSTRUCTIONS Description of and Reason for Change REMOVE AND INSERT ALL PAGES.
New Procedure Changes to this procedure do not require a 72.48 screening Training Requirements: Presentation_ Read-Study _x_ NIA_
RP-20.01 Issue 00 This issue shall not become effective unless signed off following Qualified Technical Review and required approval.
1.0 PURPOSE LACBWR ISFSI RADIATION PROTECTION PROCEDURE OFFSITE DOSE CALCULATION MANUAL (ODCMJ RP-20.01 Issue 00 The Offsite Dose Calculation Manual (ODCM) contains the methodology, parameters, and descriptions for the calculation of offslte doses resulting from ambient direct exposures from radiation released during La Crosse Boiling Water Reactor (LACBWR)
ISFSI operation activities. Reporting requirements in the ODCM, and the Radiological Environmental Monitoring Program are described. This procedure describes routine and special reports that must be submitted to the Nuclear Regulatory Commission (NRC).
2.0 SCOPE This procedure applies to those personnel responsible for performing any of the actions related to the ODCM, including radiological environmental monitoring and those personnel who prepare any reports in this procedure. The ISFSI under normal operations of day-to-day surveillance of the Vertical Concrete Casks or bounded off-normal conditions, which are described in the NAC-MPC system in the Certificate of Compliance No. 1205, do not create any radioactive effluents or radioactive waste:
therefore, specific operating procedures for the control of radioactive effluents are not required.
3.0 RESPONSIBILITIES 3.1 The ISFSI Radiation Protection Manager (RPM) is responsible for:
3.2.1 Ensuring the requirements in this document are implemented.
3.2.2 Developing the Annual Radioactive Environmental Operating Report (AREOR).
3.2.3 Calculating dose commitments from direct radiation sources to the total body.
3.2.4 Upon verification that any of the limits given in Sections 8.1.2 have been exceeded or there has been a REMP Non-Conformance per Section 8.3.2, promptly reporting the results to the ISFSI Manager and/or Licensing Engineer (LE).
3.2.5 Ensuring the requirements for monitoring, and surveillance, specified in this document are completed 3.2 The ISFSI Manager is responsible for:
Page 1 of 6
RP-20.01 Issue 00 3.2.1 Approving and transmitting reports to the NRC if the total dose to a member of the public exceeds the limits provided In Section 8.1.2 or if or there has been a REMP Non-Conformance per Section 8.3.2.
3.2.2 Approving and submitting the routine, special and non-conformance reports to the NRC as required In Section 8.1.2 and 8.3.2.
3.2.3 Reporting any other circumstances that are required to be reported to the NRC per this ODCM.
4.0 REFERENCES
s.o 4.1 NRC, Title 10, Pert 20, Standards for Protection Against Radiation, Appendix B, Table 2, Columns 1 and 2 4.2 NRC, Regulatory Guide 1.109, Rev. 1, 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 4.3 NRC, Title 10, Part 50.36a, Technical Specifications on Effluents from Nuclear Power Reactors 4.4 NRC, Title 10, Part 50, Domestic Licensing of Production and UtiHzation Facilities, Appendix I 4.5 Environmental Protection Agency (EPA), Trtle 40, Part 190, Environmental Radiation Protection Standards for Nuclear Power Operations 4.6 NRC, NUREG-0473, Rev. 2, Draft Radiological Effluent Technical Specifications 4.7 NRC, Regulatory Guide 1.21, Rev. 1, Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste 4.8 NRC, NUREG 1302, Offsite Dose Calculation Manual Guidance: Radiological Effluent Controls for Boiling Water Reactors 4.9 DPC ISFSI Procedure RP-20.03, LACBWR Environmental Monitoring Program 4.10 Environmental Protection Agency (EPA), EPA-520/1-88-020, Federal Guidance Report 11 4.11 Regulatory Guide 4.15, Quality Assurance for Radiological Monitoring Programs-Effluent Streams and the Environment.
4.12 La Crosse Boiling Water Reactor ISFSI QAPD Appendix C 4.13 Environmental TLD Location, Drawing No. ISFSI-C-001 DEFINITIONS 5.1 Effluent Release Boundary - The owner Controlled Area fence around the LACBWR ISFSI.
5.2 Member of the Public - Any individual, except when he or she is receiving an occupational dose. The definition includes any individual who can receive a Page 2 of6
RP-20.01 Issue 00 radiation dose in the general environment, independent of whether the individual may also be exposed to radiation in an occupation associated with the nuclear fuel cycle.
6.0 PREREQUISITIES Not applicable.
7.0 PRECAUTIONS 7.1 If any of the assumptions cited in the ODCM change in a non-conservative manner (e.g., would result in higher doses to a member of the public), the RPM must be notified.
7.2 Ensure that upon verification that any of the limits given in Sections 8.1.2 have been exceeded or there has been a REMP Non-Conformance per Section 8.3.2, the results are promptly reported to the appropriate individual or organization.
8.0 PROCEDURE 8.1 Radioactive Effluent Control Program NOTE:
The NAC-MPC System at LACBWR ISFSI by design and evaluation does not create any radioactive effluents nor contain any radioactive waste systems.
8.1.1 Program requirements 8.1.1.1 In accordance with provisions of 40 CFR 190 (Reference 4.5),
the restrictions and surveillance requirements for total dose to any member of the public from all LACBWR ISFSI related ambient radiation exposure are evaluated on a quarterly and an annual basis.
8.1.2 Total Dose to a Member of the Public Limits and Reporting Requirements 8.1.2.1 The total dose equivalent to any member of the public due to release of radioactivity from LACBWR ISFSI direct radiation sources shall be limited to < 25 mrem to the total body over a period of one calendar year and <2 mrem/hr. in any one hour.
8.1.2.2 If the annual dose limits to a member of the public from direct radiation sources have been exceeded, notify the RPM.
8.1.2.3 The RPM will prepare a Special Report (including the analysis, which estimates the radiation dose to a member of the public for the calendar year) and submit it to the ISFSI Manager. The ISFSI Manager will review, approve and submit the Special Report to the Director, Nuclear Reactor Regulation, U.S.
Nuclear Regulatory Commission, Washington, DC 20555, within 30 days, which includes the estimated total body doses and defines the corrective actions to be taken to reduce Page 3 of6
RP-20.01 Issue 00 subsequent releases to prevent recurrence of exceeding these limits. If the release condition resulting in the limits being exceeded has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190. Submittal of the Special Report is considered a timely request, and a variance is granted until staff action on the request is complete.
8.2 Radiological Environmental Monitoring Program (REMP) 8.2.1 The REMP conforms to the guidance of Appendix I to 10 CFR Part 50 (Reference 4.4). The REMP provides the requirements for monitoring, and reporting radiation exposure in the environment resulting from ambient air radiation emanating from the LACBWR ISFSI facility. These requirements have been established to ensure measurements of direct radiation in potential exposure pathways to members of the public are performed.
8.2.2 The radiological monitoring program provides measurements of ambient direct radiation, which lead to the potential radiation exposures to individual members of the public resulting from site operations.
8.2.3 REMP Description 8.2.3.1 Environmental TLDs that are used to assess ambient dose conditions to the public are discussed and locations are described in Ref. 4.9.
NOTE:
Locations 1,6,7, 8, 9, and 10 are used to assess ambient dose conditions to the public, which are depicted on the Environmental TLD Drawing (Reference 4.13).
8.3 Radiological Environmental Monitoring Report Requirements 8.3.1 Radiological Environmental Monitoring Report 8.3.1.1 The Radiological Environmental Monitoring Report is prepared annually. This report includes summarized and tabulated monitoring results, including interpretations and analysis of data trends, for environmental TLDs processed during the previous calendar year.
8.3.1.2 In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.
8.3.1.3 The report also includes the following: a summary description of the Radiological Environmental Monitoring Program, a map of all sampling locations keyed to a table.
Page4of6
RP-20.01 lssueO0 8.3.1.4 The RPM will prepare the Radiological Environmental Monitoring Report and submit it to the ISFSI Manager.
8.3.1.5 The ISFSI Manager will review, approve and submit the report to the Director, Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555, by March 1 for the previous calendar year.
8.3.2 REMP Non-Conformance Reporting 8.3.2. 1 If the Radiological Environmental Monitoring Program is not being conducted as specified in Reference 4.9 or if there are unexpected results, notify the RPM.
8.3.2.2 The RPM will investigate the non-conformance and include in the Radiological Environmental Monitoring Report a description of the reasons for not conducting the program as required, analysis of the cause of unexpected results and the plans for preventing a recurrence.
8.3.2.3 The RPM will review and approve the report and submit the report to the ISFSI Manager or Licensing Engineer.
8.3.2.4 The ISFSI Manager or Licensing Engineer will review, approve and submit the report to the U.S. Nuclear Regulatory Commission, Washington, DC 20555.
8.4 Program Changes 8.4.1 Changes to the ODCM 8.4.1.1 Shall be documented and records of reviews performed shall be retained as required by the Quality Assurance Program Description (QAPD). This documentation shall contain:
a)
Sufficient Information to support the change together with the appropriate analyses or evaluations justifying the change(s); and b) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302 and 40 CFR Part 190.
c) Documentation of the fact that the change has been reviewed and found acceptable by a Qualified Technical Review.
d) Shall become effective after the approval of the ISFSI Manager on the date specified by the Qualified Technical Review.
Page 5 of 6
RP-20.01 Issue 00 e) Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Environmental Operating Report for the period of the report in which any change to the OOCM was made effective. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was Implemented.
9.0 ATTACHMENTS/RECORDS RECORD ATTACHMENT DOCUMENT TITLE Location Retention 1
Environmental TLD Locations N/A LT Annual Radiological Environmental NIA Operating Report (AREOR) /
RP-20.01 LT Radiological Environmental file Monitoring Program (REMP) Report Pages of6
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RP-20.01 Issue 01 LACBWR ISFSI RADIATION PROTECTION RADIATION PROTECTION PROCEDURE RP-20.01 OFFS/TE DOSE CALCULATION MANUAL PREPARER:
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DATE: 11/21/2023 QUALIFIED TECHNICAL REVIEWER: B,4,'h1~l c DATE: 11/21/2023 APPROVER: __ -P-~~.,.._.~f'+------ DATE ~
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ISSUE NOTICE LACBWR ISFSI RADIATION PROTECTION PROCEDURE OFFS/TE DOSE CALCULATION MANUAL (ODCMJ INSTRUCTIONS Description of and Reason for Change RP-20.01 Issue 01 REMOVE ANO INSERT ALL PAGES.
Revised Section 8.1, Radioactive Effluent Control Program by incorporating into the program liquid gaseous and tritium effluents.
CAR 2023-032 Added NAC-MPS System FSAR to Reference Section.
Changes to this procedure do not require a 72.48 screening Training Requirements: Presentation _Read-Study __ N/A_X_
This issue shall not become effective unless signed off following Qualified Technical Review and required approval.
1.0 PURPOSE LACBWR ISFSI RADIATION PROTECTION PROCEDURE OFFS/TE DOSE CALCULATION MANUAL {ODCMJ RP-20.01 Issue 01 The Offsite Dose Calculation Manual (ODCM) contains the methodology, parameters, and descriptions for the calculation of offsite doses resulting from ambient direct exposures from radiation released during La Crosse Boiling Water Reactor (LACBWR)
ISFSI operation activities. Reporting requirements in the ODCM, and the Radiological Environmental Monitoring Program are described. This procedure describes routine and special reports that must be submitted to the Nuclear Regulatory Commission (NRC).
2.0 SCOPE This procedure applies to those personnel responsible for performing any of the actions related to the ODCM, including radiological environmental monitoring and those personnel who prepare any reports in this procedure. The ISFSI under normal operations of day-to-day surveillance of the Vertical Concrete Casks or bounded off-normal conditions, which are described in the NAC-MPC system in the Certificate of Compliance No. 1205, do not create any radioactive effluents or radioactive waste; therefore, specific operating procedures for the control of radioactive effluents are not required.
3.0 RESPONSIBILITIES 3.1 The ISFSI Radiation Protection Manager (RPM) is responsible for:
3.2.1 Ensuring the requirements in this document are implemented.
3.2.2 Developing the Annual Radioactive Environmental Operating Report (AREOR).
3.2.3 Calculating dose commitments from direct radiation sources to the total body.
3.2.4 Upon verification that any of the limits given in Sections 8.1.2 have been exceeded or there has been a REMP Non-Conformance per Section 8.3.2, promptly reporting the results to the ISFSI Manager and/or Licensing Engineer (LE).
3.2.5 Ensuring the requirements for monitoring, and surveillance, specified in this document are completed Page 1 of 7
4.0 3.2 The ISFSI Manager is responsible for:
RP-20.01 Issue 01 3.2.1 Approving and transmitting reports to the NRC if the total dose to a member of the public exceeds the limits provided in Section 8.1.2 or if or there has been a REMP Non-Conformance per Section 8.3.2.
3.2.2 Approving and submitting the routine, special and non-conformance reports to the NRC as required in Section 8.1.2 and 8.3.2.
3.2.3 Reporting any other circumstances that are required to be reported to the NRC per this ODCM.
REFERENCES 4.1 NRC, Title 10, Part 20, Standards for Protection Against Radiation, Appendix B, Table 2, Columns 1 and 2 4.2 NRC, Regulatory Guide 1.109, Rev. 1, 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 4.3 NRC, Title 10, Part 50.36a, Technical Specifications on Effluents from Nuclear Power Reactors 4.4 NRC, Title 10, Part 50, Domestic Licensing of Production and Utilization Facilities, Appendix I 4.5 Environmental Protection Agency (EPA), Title 40, Part 190, Environmental Radiation Protection Standards for Nuclear Power Operations 4.6 NRC, NUREG-0473, Rev. 2, Draft Radiological Effluent Technical Specifications 4.7 NRC, Regulatory Guide 1.21, Rev. 1, Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste 4.8 NRC, NUREG 1302, Offsite Dose Calculation Manual Guidance: Radiological Effluent Controls for Boiling Water Reactors 4.9 DPC ISFSI Procedure RP-20.03, LACBWR Environmental Monitoring Program 4.10 Environmental Protection Agency (EPA), EPA-520/1-88-020, Federal Guidance Report 11 4.11 Regulatory Guide 4.15, Quality Assurance for Radiological Monitoring Programs-Effluent Streams and the Environment.
4.12 La Crosse Boiling Water Reactor ISFSI QAPD Appendix C 4.13 Environmental TLD Location, Drawing No. ISFSI-C-001 4.14 NAC International, Inc., Final Safety Analysis Report (FSAR) for the NAC Multi-Purposed Canister (NAC-MPC) System Page 2 of 7
5.0 DEFINITIONS RP-20.01 Issue 01 5.1 Effluent Release Boundary - The Owner Controlled Area fence around the LACBWR ISFSI.
5.2 Member of the Public - Any individual, except when he or she is receiving an occupational dose. The definition includes any individual who can receive a radiation dose in the general environment, independent of whether the individual may also be exposed to radiation in an occupation associated with the nuclear fuel cycle.
6.0 PREREQUISITIES 7.0 8.0 Not applicable.
PRECAUTIONS 7.1 If any of the assumptions cited in the ODCM change in a non-conservative manner (e.g., would result in higher doses to a member of the public), the RPM must be notified.
7.2 Ensure that upon verification that any of the limits given in Sections 8.1.2 have been exceeded or there has been a REMP Non-Conformance per Section 8.3.2, the results are promptly reported to the appropriate individual or organization.
PROCEDURE 8.1 Radioactive Effluent Control Program NOTE:
The NAC-MPC System at LACBWR ISFSI by design and evaluation does not create any radioactive effluents nor contain any radioactive waste systems.
8.1.1 Program requirements 8.1.2.1 The Radioactive Effluent Control Program (RECP) shall conform to the guidance of 1 O CFR 50.53a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. This program shall establish the requirements for monitoring, sampling, and analysis of radioactive liquid effluents released from LACBWR ISFSI to ensure the concentration in effluents release to areas beyond the EFFLUENT RELEASE BOUNDARY conform to 10 CFR Part 20, Appendix B, Table 2, Columns 1 and 2. It shall provide limitations on the annual and quarterly dose commitment to a MEMBER OF THE PUBLIC from radioactive effluents in conformance with Appendix I of 10 CFR Part 50.
In accordance with provisions of 40 CFR 190 (Reference 4.5),
the restrictions and surveillance requirements for total dose to any member of the public from all LACBWR ISFSI related ambient radiation exposure are evaluated on a quarterly and an annual basis.
Page 3 of 7
RP-20.01 Issue 01 8.1.2 Liquid Effluents 8.1.2.1 By design, the NAC-MPC System does not create any radioactive liquid effluent (Reference 4.14, NAC FSAR for the NAC-MPC System). Therefore, no radioactive liquid effluent controls, instrumentation, equipment, monitoring, sampling, or analysis are required.
8.1.3 Gaseous Effluents 8.1.3.1 By design, the NAC-MPC System does not create any radioactive gaseous effluent (Reference 4.14, NAC FSAR for the NAC-MPC System}. Therefore, no radioactive liquid effluent controls, instrumentation, equipment, monitoring, sampling, or analysis are required.
8.1.4 Tritium Effluents 8.1.4.1 By design, the NAC-MPC System does not create any tritium effluent (Reference 4.14, NAC FSAR for the NAC-MPC System). Therefore, no tritium effluent controls, instrumentation, equipment, monitoring, sampling, or analysis are required.
8.1.5 Total Dose to a Member of the Public Limits and Reporting Requirements 8.1.5.1 The total dose equivalent to any member of the public due to release of radioactivity from LACBWR ISFSI direct radiation sources shall be limited to < 25 mrem to the total body over a period of one calendar year and <2 mrem/hr. in any one hour.
8.1.5.2 If the annual dose limits to a member of the public from direct radiation sources have been exceeded, notify the RPM.
8.1.5.3 The RPM will prepare a Special Report (including the analysis, which estimates the radiation dose to a member of the public for the calendar year) and submit it to the ISFSI Manager. The ISFSI Manager will review, approve and submit the Special Report to the Director, Nuclear Reactor Regulation, U.S.
Nuclear Regulatory Commission, Washington, DC 20555, within 30 days, which includes the estimated total body doses and defines the corrective actions to be taken to reduce subsequent releases to prevent recurrence of exceeding these limits. If the release condition resulting in the limits being exceeded has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190. Submittal of the Special Report is considered a timely request, and a variance is granted until staff action on the request is complete.
8.1.5.4 In the unlikely event at the LACBWR ISFSI that would create Page 4 of 7
RP-20.01 Issue 01 an effluent path (liquid, gaseous), procedures for monitoring, sampling, and analysis of the effluents released from LACBWR ISFSI shall be generated to ensure the concentrations in effluents released to areas beyond the EFFLUENT RELEASE BOUNDARY conform to 10 CFR Part 20, Appendix B, Table 2, Columns 1 and 2.
8.2 Radiological Environmental Monitoring Program (REMP) 8.2.1 The REMP conforms to the guidance of Appendix I to 10 CFR Part 50 (Reference 4.4). The REMP provides the requirements for monitoring, and reporting radiation exposure in the environment resulting from ambient air radiation emanating from the LACBWR ISFSI facility. These requirements have been established to ensure measurements of direct radiation in potential exposure pathways to members of the public are performed.
8.2.2 The radiological monitoring program provides measurements of ambient direct radiation, which lead to the potential radiation exposures to individual members of the public resulting from site operations.
8.2.3 REMP Description 8.2.3.1 Environmental TLDs that are used to assess ambient dose conditions to the public are discussed and locations are described in Ref. 4.9.
NOTE:
Locations 1,6,7, 8, 9, and 10 are used to assess ambient dose conditions to the public, which are depicted on the Environmental TLD Drawing
{Reference 4.13).
8.3 Radiological Environmental Monitoring Report Requirements 8.3.1 Radiological Environmental Monitoring Report 8.3.1.1 The Radiological Environmental Monitoring Report is prepared annually. This report includes summarized and tabulated monitoring results, including interpretations and analysis of data trends, for environmental TLDs processed during the previous calendar year.
8.3.1.2 In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.
8.3.1.3 The report also includes the following: a summary description of the Radiological Environmental Monitoring Program, a map of all sampling locations keyed to a table.
Page 5 of 7
RP-20.01 Issue 01 8.3.1.4 The RPM will prepare the Radiological Environmental Monitoring Report and submit it to the ISFSI Manager.
8.3.1.5 The ISFSI Manager will review, approve and submit the report to the Director, Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555, by March 1 for the previous calendar year.
8.3.2 REMP Non-Conformance Reporting 8.3.2.1 If the Radiological Environmental Monitoring Program is not being conducted as specified in Reference 4.9 or if there are unexpected results, notify the RPM.
8.3.2.2 The RPM will investigate the non-conformance and include in the Radiological Environmental Monitoring Report a description of the reasons for not conducting the program as required, analysis of the cause of unexpected results and the plans for preventing a recurrence.
8.3.2.3 The RPM will review and approve the report and submit the report to the ISFSI Manager or Licensing Engineer.
8.3.2.4 The ISFSI Manager or Licensing Engineer will review, approve and submit the report to the U.S. Nuclear Regulatory Commission, Washington, DC 20555.
8.4 Program Changes 8.4.1 Changes to the OOCM 8.4.1.1 Shall be documented and records of reviews performed shall be retained as required by the Quality Assurance Program Description (QAPD). This documentation shall contain:
a)
Sufficient Information to support the change together with the appropriate analyses or evaluations justifying the change(s); and b) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302 and 40 CFR Part 190.
c) Documentation of the fact that the change has been reviewed and found acceptable by a Qualified Technical Review.
d) Shall become effective after the approval of the ISFSI Manager on the date specified by the Qualified Technical Review.
Page 6 of 7
RP-20.01 Issue 01 e) Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Environmental Operating Report for the period of the report in which any change to the ODCM was made effective. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.
9.0 ATTACHMENTS/RECORDS RECORD ATTACHMENT DOCUMENT TITLE Location Retention 1
Environmental TLD Locations NIA LT Annual Radiological Environmental NIA Operating Report (AREOR) I RP-20.01 LT Radiological Environmental file Monitoring Program (REMP) Report Page 7 of 7
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