ML18127A216
| ML18127A216 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/01/2018 |
| From: | O'Connor M Dominion Energy Nuclear Connecticut |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18127A216 (70) | |
Text
Dominion Energy Nuclear Connecticut, Inc.
Rt 1¢6, Rope Ferry Road, Waterford, CT 06385 J Dominion Energy.com U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 MAY O 1 2018 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNITS 1, 2, AND 3 Serial No.
MPS Lic/GJC Docket Nos.
License Nos.
2017 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 18-176 RO 50-245 50-336 50-423 DPR-21 DPR-65 NPF-49 In accordance with 10 CFR 50.36a, this letter transmits the annual Radioactive Effluent Release Report (RERR) for the period January 2017 through December 2017. This report meets the provisions of Section 5. 7.3 of the Millstone Power Station Unit 1 Permanently Defueled Technical Specifications (POTS), and Sections 6.9.1.6b and 6.9.1.4 of the Millstone Power Station Units 2 and 3 Technical Specifications, respectively. transmits Volume 1 of the 2014 RERR, in accordance with Regulatory Guide 1.21. The RERR contains information regarding airborne, liquid, and solid radioactivity released from Millstone Power Station, including the off-site dose from airborne and liquid effluents. transmits Volume 2 of the report, which consists of a complete copy of the Radiological Effluent Monitoring and Off-Site Dose Calculation Manual (REMODCM) as of December 31, 2017. This satisfies the requirements of Sections 5.6.1 c of the Millstone Power Station Unit 1 POTS, and Sections 6.15c and 6.9.13c of the Millstone Power Station Units 2 and 3 Technical Specifications, respectively.
If you have any questions or require additional information, please contact Mr. Jeffry A. Langan at (860) 444-5544.
Sincerely, M. J. O'Connor Director, Nuclear Station Safety and Licensing
Attachments:
2 Commitments made in this letter:
- 1. None.
cc:
U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 S. J. Giebel Serial No.18-176 2017 Radioactive Effluent Release Report Page 2 of 4 NRC Project Manager Millstone Unit 1 U.S. Nuclear Regulatory Commission Two White Flint North, Mail Stop T-8 F5 11545 Rockville Pike Rockville, MD 20852-2738 L. A. Kauffman NRC Inspector U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 H. W Anagnostopoulos NRC Inspector U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 R. V. Guzman NRC Project Manager Millstone Units 2 and 3 U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 C2 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Director Bureau of Air Management Monitoring & Radiation Division Department of Energy and Environmental Protection 79 Elm Street Hartford, CT 06106-5127
A. Honnellio Regional Radiation Representative (EPA Region 1, Boston)
Serial No.18-176 2017 Radioactive Effluent Release Report Page 3 of 4 U. S. Environmental Protection Agency (Region 1) 5 Post Office Square Suite 100 Boston, MA 02109 G. Allen Jr.
Department of Health and Human Services U. S. Food and Drug Administration 140 Shrewsbury Street, Suite 1 Boylston, MA 01501 Mr. Robert Stein Chairman Connecticut Siting Council 10 Franklin Square New Britain, CT 06051 J.P. Kelley Waterford-East Lyme Shellfish Commission Waterford Town Hall Waterford, CT 06385 J. Foikwein American Nuclear Insurers 95 Glastonbury Blvd.
Glastonbury, CT 06033 D. Carey Connecticut Department of Agriculture Aquaculture Division P. 0. Box 97 Millford, CT 06460 Mr. Dan Steward First Selectman Town of Waterford Waterford Town Hall Waterford, CT 06385 M. C. Nickerson First Selectman Town of East Lyme PO Box 519 Niantic, CT 06357
University Of Connecticut Library Serials Department Storrs, CT 06268 Serial No.18-176 2017 Radioactive Effluent Release Report Page 4 of 4
ATTACHMENT 1 Serial No.18-176 Docket Nos. 50-245 50-336 50-423 License Nos. DPR-21 DPR-65 NPF-49 2017 RADIOACTIVE EFFLUENTS RELEASE REPORT VOLUME 1 MILLSTONE POWER STATION UNITS 1, 2, AND 3 DOMINION ENERGY NUCLEAR CONNECTICUT, INC. (DENC)
Millstone Power Station 2017 Radioactive Effluents Release Report Volume One Gaseous Effluents Dominion Energy Nuclear Connecticut, Inc.
Unit 1
2 3
License DPR-21 DPR-65 NPF-49 Docket 50-245 50-336 50-423 i l, EDominion
- iiiiiil' nergy
Contents List ofTables................................................................................................................................................................... 2 List of Acronyms............................................................................................................................................................. 3 Introduction..................................................................................................................................................................... 4 1.0 Off-Site Doses.......................................................................................................................................................... 4 1.1 Dose Calculations............................................................................................................................................. 4 1.1. I Gaseous Effluents................................................................................................................................... 5 1.1.2 Liquid Effluents...................................................................................................................................... 6 1.2 Dose Results...................................................................................................................................................... 6 1.2.1 Gaseous Effluents................................................................................................................................... 6 1.2.2 Liquid Effluents...................................................................................................................................... 6 1.2.3 Analysis of Results................................................................................................................................. 6 1.3 Other Sources of Radiation Dose to the Public (from Ref. 12)....................................................................... 11 2.0 Effluent Radioactivity............................................................................................................................................ 13
- 2. 1 Gaseous Effluents........................................................................................................................................... 13 2.1. 1 Measurement of Radioactivity in Gaseous Effluents........................................................................... 13 2.1.2 Estimate ofErrors................................................................................................................................. 14 2.1.3 Gaseous Batch Release Statistics......................................................................................................... 15 2.1.4 Abnormal Gaseous Releases................................................................................................................ 15 2.1.5 Gaseous Release Tables....................................................................................................................... 15 2.2 Liquid Effluents.............................................................................................................................................. 32 2.2. 1 Measurement of Radioactivity in Liquid Effluents.............................................................................. 32 2.2.1.1 Continuous Liquid Releases................................................................................................... 32 2.2.1.2 Batch Liquid Releases from Tanks and Sumps...................................................................... 32 2.2.2 Estimate of Errors................................................................................................................................. 33 2.2.3 Liquid Batch Release Statistics............................................................................................................ 33 2.2.4 Abnormal Liquid Releases................................................................................................................... 33 2.2.5 Liquid Release Tables.......................................................................................................................... 33 2.3 Solid Waste..................................................................................................................................................... 42 2.4 Groundwater Monitoring................................................................................................................................ 57 3.0 NONFUNCTIONAL Effluent Monitors................................................................................................................ 59
- 4. 0 Operating History................................................................................................................................................... 60 5.0 ERRATA................................................................................................................................................................ 63 6.0 REMO DCM Changes............................................................................................................................................ 63 7.0 References.............................................................................................................................................................. 64 1
List of Tables Table 1-1 2017 Off-Site Dose Commitments from Gaseous Effluents MPS - Units 1, 2, 3.................................................... 8 Table 1-2 2017 Off-Site Commitments from Liquid Effluents MPS - Units 1, 2, 3................................................................. 9 Table1-3 2017 Off-Site Dose Comparison to Limits MPS - Units 1, 2, 3.............................................................................. 10 Table 1-4 2017 Off-Site Dose Comparison Natural Background vs MPS Table 2.1-A1 MPSl Gaseous Effluents Release Summary......................................................................................................... 16 Table 2.1-A2 MPSl Gaseous Effluents - Continuous Ground - BOP Vent & SFPI Vent............................................................. 17 Table 2.1-L 1 MPSl Liquid Effluents - Release Summary.......................................................................................................... 34 Table 2.1-L2 MPSl Liq uid Effluents - Batch - Liquid Waste Processing.................................................................................. 35 Table 2.1-S MPSl Solid Waste & Irradiated Component Shipments...................................................................................... 43 Table 2.2-A1 MPS2 Gaseous Effluents - Release Summary...................................................................................................... 18 Table 2.2-A2 MPS 2 Gaseous Effluents - Ground Batch............................................................................................................ 19 Table 2.2-A3 M PS2 Gaseous Effluents - Ground Continuous - RWST Vent, Equipment Hatch............................................... 20 Table 2.2-A4 MPS2 Gaseous Effluents - Elevated Batch - MPS Stack...................................................................................... 21 Table 2.2-A5 MPS2 Gaseous Effluents - Elevated Continuous - MPS Stack............................................................................ 22 Table 2.2-A6 MPS2 Gaseous Effluents - Mixed Batch - MPS2 Main Exhaust Vent.................................................................. 23 Table 2.2-A7 MPS2 Gaseous Effluents - Mixed Continuous - MPS2 M ain Exhaust Vent........................................................ 24 Table 2.2-L 1 MPS2 Liquid Effluents - Release Summary.......................................................................................................... 36 Table 2.2-L2 MPS2 Liquid Effluents - Continuous - SGBD, SW, RBCCW, TB Sumps, Tendon Gallery....................................... 37 Table 2.2-L3 MPS2 Liquid Effluents - Batch - Liquid Radwaste System.................................................................................... 38 Table 2.2-S MPS2 Solid Waste & Irradiated Component Shipments...................................................................................... 47 Table 2.3-A1 MPS3 Gaseous Effluents - Release Summary...................................................................................................... 25 Table 2.3-A2 MPS3 Gaseous Effluents - Ground Batch - ESF Building Rooftop....................................................................... 26 Table 2.3-A3 Gaseous Effluents - Ground Continuous - ESF Building Vent, CTMT Equipment Hatch, RWST Vent, ABD TK-2 Vent...................................................................................................................................................................... 27 Table 2.3-A4 MPS3 Gaseous Effluents - Elevated Batch - MPS Stack....................................................................................... 28 Table 2.3-A5 MPS3 Gaseous Effluents - Elevated Continuous - MPS Stack............................................................................. 29 Table 2.3-A6 MPS3 Gaseous Effluents - Mixed Batch - MPS3 Ventilation Vent....................................................................... 30 2
Table 2.3-A7 MPS3 Gaseous Effl uents - Mixed Continuous - M PS3 Ventilation Vent............................................................. 31 Table 2.3-L 1 MPS3 Liquid Effluents - Release Summary.......................................................................................................... 39 Table 2.3-L2 MPS3 Liquid Effluents - Continuous - SGBD, SW, TB Sumps, SRW Sump 3, ABO TK-2......................................... 40 Table 2.3-L3 MPS3 Liquid Effluents - Batch - Liquid Radwaste System, CPF su mps, Hotwell, SG bu lk, wn Berm................. 41 Table 2.3-S MPS3 Solid Waste & Irradiated Component Shipments...................................................................................... 52 Table 2.4-GW Well Sample Results............................................................................................................................................. 57 List of Acronyms ABD-TK-2 Auxiliary Boiler Drains Tank 2 BOP - Balance of plant CFR - Code of Federal Regulations CPF - Condensate polishing facility DENC - Dominion Energy Nuclear Conncticut DOT - Department of Transportation DSN - Discharge serial number EBFS - Enclosure building filtration system EDAN-Environmental Data Acquisition Network ESF - Engineering safeguards facility GI - Gastrointestinal GWPP - Groundwater protection program HPGe - High purity germanium ISFSI - Independent spent fuel storage installation MPS - Millstone Power Station MPSl - Millstone Power Station Unit 1 MPS2 - Millstone Power Station Unit 2 MPS3 - Millstone Power Station Unit 3 MDA - Minimum Detectable Activity NCRP-National Council on Radiation Protection and Measurements NEI-Nuclear Energy Institute NPP - Nuclear power plant NRC - Nuclear Regulatory Commission RBCCW - Reactor building closed cooling water REMODCM - Radiological Effluent Monitoring and Offsite Dose Calculation Manual R WST - Reactor water storage tank SFPI - Spent Fuel Pool Island SG - Steam generator SGBD - Steam generator blowdown SLCRS - Secondary Leakage Collection and Recovery System SW - Service water TB - Turbine building WGDT - Waste gas decay tank WRGM - Wide range gas monitor WTT - Waste test tank 3
Introduction This report, for the period of January through December of 2017, is being submitted by DENC, Inc. for MPS 1, 2, and 3, in accordance with 10 CFR 50.36a, the Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM), the MPS! Permanently Defueled Technical Specifications, and the MPS2 and 3 Technical Specifications. This report contains radiological and volumetric information on gaseous and liquid effluents, doses to the public from these effluents, shipments of solid waste & irradiated components, onsite well water results, information on effluent instrumentation which was nonfunctional for more than 30 consecutive days and operating history.
Radioactive materials may be disposed of in solid waste shipments sent to licensed disposal sites or released in liquid or gas form in effluents to the local environment. The two basic characteristics used to describe radioactive effluents are radioactivity and radiation dose. The radioactivity of any given radionuclide increases in direct proportion to the amount of the radionuclide present. This report lists the amounts of various radionuclides present in radioactive effluents. For this report, activity can be thought of as the amount of radioactive material present in radioactive effluents. Section 2.0 of this report gives the activity released from MPS in 2017.
Although radioactivity is an important, inherent characteristic that helps to describe radioactive effluents, it is not-by itself-a good indicator of the potential health effects from exposure to radiation. Health effects are dependent on many factors, such as the radionuclide, the type ofradiation emitted by the radionuclide, the energy of the radiation, the uptake of the radionuclide into the human body, and the metabolism of the radionuclide by the human body. To properly describe the potential health effects from exposure to radioactive materials, a measure that accounts for all of these differences is needed. Dose is a measure of how much radiation energy is absorbed by organs or tissues of the body. Dose is a good indicator of the potential health effects from exposure to radiation. Section 1.0 of this report gives the dose from activity released from MPS in 2017.
1.0 Off-Site Doses This report provides a summary of the 2017 off-site radiation doses from releases of radioactive materials in gaseous and liquid effluents and from direct radiation from MPS 1, 2 and 3. This includes the annual maximum dose in millirem (mrem) to any real member of the public as well the maximum gamma and beta air doses. To provide perspective, these doses are compared to the regulatory limits (in Table 1-3) and to the annual average dose that a member of the public could receive from natural background and other sources (in Table 1-4). The doses from radioactive effluents were much less than the doses from other sources of natural radiation that are commonly considered safe. This indicates radioactive effluents from MPS in 2017 had no significant impact on the health and safety of the public or the environment.
1.1 Dose Calculations Dose from radioactive effluents are calculated to ensure compliance with NRC requirements in 10 CFR Part 50, Appendix I (Ref. 7). The dose calculations are based on the measurements and computer models listed below:
- measurements of the radioactive materials released to the environment,
- models of how radionuclides are dispersed and diluted in the environment,
- models of how radionuclides are incorporated into animals, plants, and soil, and
- models of the biokinetic of human uptake and metabolism of radioactive materials.
The models are designed to calculate the dose to a real ( or hypothetical) individual closest to MPS or to an individual who may be exposed to the highest concentrations of radioactive materials from radioactive effluents. This person is often referred to as the maximum exposed individual. The parameters and assumptions used in these dose calculations include conservative assumptions that tend to overestimate the calculated exposures. Although the location of the maximum individual may vary each quarterly period, the annual dose is the sum of these quarterly doses. This conservatively assumes that the individual is at the location of maximum dose each quarter. As a result, the actual doses received by real individuals are often much less than those calculated.
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The off-site dose to humans from radioactive material in liquid and gaseous effiuents have been calculated using measured radioactive effiuent data and the dose computation algorithm in OpenEMS, an effluent tracking program (Ref. 9). For liquid dose OpenEMS uses equations which yield the same result as the methodology given in NRC Regulatory Guide 1.109 (Ref. 3). For airborne dose OpenEMS uses an algorithm equivalent to the NRC code, GASP AR II (Ref. 1), which uses a semi-infinite cloud model to implement the NRC Regulatory Guide 1.109 (Ref. 3) dose models. The values of average relative effluent concentration (X/Q) and average relative deposition (D/Q) used in OpenEMS were generated using EDAN, a meteorological computer code.
The annual summary of hourly meteorological data (in 15-minute increments), which includes wind speed, direction, atmospheric stability, and joint frequency distribution, is not provided in the report but are available.
Doses are based upon exposure to radioactivity in gaseous and liquid effluents over a one-year period and an associated dose commitment over a 50-year period from initial exposure. The portion of the doses due to inhalation and ingestion take into account radioactive decay and biological elimination of the radioactive materials.
The dose calculations are based upon three types of input: radioactive source term, site-specific data, and generic factors. The radioactive source terms (Curies) are given in Section 2, Effiuent Radioactivity, of this report. The site-specific data includes: meteorological data ( e.g. wind speed, wind direction, atmospheric stability) to calculate the transport and dispersion of gaseous effluents, average annual milk consumption rates and dilution factors for liquid effluents. The generic factors include the average annual consumption rates (for ingestion of vegetables, produce, meat, fish, and shellfish), shielding factor for air submersion and ground irradiation and occupancy factors for shoreline activity, swimming and boating.
1.1.1 Gaseous Effluents The following release points are considered ground level:
MPSl SFPI Vent (73 foot)
MPSl BOP Vent (80 foot)
MPS2 and 3 Refueling Water Storage Tank (RWST) Vents MPS3 Engineered Safety Features Building (ESF) Ventilation Auxiliary Boiler Drains Tank 2 (ABD TK-2) Vent MPS2 & 3 Containment Equipment Hatch MPS3 Containment Drawdowns Doses for releases from these points were calculated using the 33 foot meteorology. For each unit, doses from their respective release points were summed to determine the total unit gaseous effiuent ground level dose.
The following release points are considered mixed mode (partially elevated and partially ground) releases:
MPS2 Auxiliary Building Ventilation (159 foot elevation)
MPS3 Auxiliary Building Ventilation (133 foot elevation)
The doses for mixed mode releases are calculated using 142 foot meteorology for which the Pasquill stability classes are determined based upon the temperature gradient between the 33 foot and 142 foot meteorological tower levels.
The MPS Stack release point at 374 foot elevation is considered an elevated release. Doses for elevated releases are calculated using Pasquill stability classes determined based upon the temperature gradient between the 33 foot and 374 foot meteorological tower levels. Only MPS2 and MPS3 discharge to the MPS Stack. In March 2001, MPS 1 was separated from the stack and two new release points were added to MPS 1, the Spent Fuel Pool Island (SFPI) Vent and the Balance of Plant (BOP) Vent. The following are sources of radioactivity for releases from the stack:
MPS2 Waste Gas Decay Tanks batch releases MPS2 Containment Vents batch releases MPS2 Containment Purge batch releases (only during outage in the second quarter)
MPS3 Containment Vents batch releases MPS3 Gaseous Waste System continuous releases MPS3 Containment Purge batch releases (only during outage in fourth quarter) 5
1.1.2 Liquid Effluents MPS discharges radioactivity in water through two release pathways - thru the MPS Quarry to the Long Island Sound and thru Discharge Point DSN-006 to Niantic Bay. Discharges to the MPS Quarry are from primary side water, primarily from liquid waste processing systems. Discharges to DSN-006 are from secondary side water, primarily turbine building sumps. MPSl discharges only to the MPS Quarry from sumps and leakage collection systems. Discharges to both release pathways are considered either continuous or batch discharges.
Sources of continuous and batch discharges are listed in Sections 2.2.1.1 and 2.2.1.2. Water containing radioactivity being discharged to the MPS Quarry is diluted mainly by circulating water and, to a minor extent, by service water. Water containing radioactivity being discharged to DSN-006 is diluted by storm drains runoff.
1.2 Dose Results The calculated maximum off-site doses are presented in Table 1-1 for gaseous effluents and Table 1-2 for liquid effluents. The units 'mrad' and 'mrem' used in this report are units of radiation dose. The letter 'm' is for 'milli', or one-thousandth ofa 'rad' or a 'rem.' The word 'rad' is an acronym for radiation absorbed dose. One rad is equal to the absorption of 100 ergs of energy per gram of tissue. The word 'rem' is an acronym for roentgen equivalent man. One rem is equal to a rad multiplied by factors to account for type of radiation and distribution within the body.
1.2.1 Gaseous Effluents For the dose to the maximum individual, OpenEMS calculates the dose to the whole body, gastrointestinal (GI), bone, liver, kidney, thyroid, lung, and skin from each of the following pathways: direct exposure from submersion in noble gases in the plume, direct exposure from ground deposition of radioactivity, inhalation, and ingestion of vegetation, produce, cow or goat milk, and meat. A cloud shine dose component for releases of noble gas radioactivity from the elevated MPS Stack is calculated using Reference 13. This cloud shine pathway accounts for dose to the maximum individual from the plume at the site boundary while the plume is still elevated. The values presented are a total from all pathways. Only the whole body, skin, thyroid and maximum organ ( other than thyroid) doses are presented.
For the plume and inhalation pathways, the maximum individual dose is calculated at the off-site location of the highest X/Q where a potential for dose exists.
For ground deposition and ingestion pathways (vegetation, meat and milk), the maximum individual dose is calculated at the location of the highest D/Q. For the milk pathways ( cow and goat), the calculated dose is included in the maximum individual's dose only at locations and times where these pathways actually exist.
To determine compliance with 10 CFR 50, Appendix I (Reference 7), the maximum individual whole body and organ doses include all applicable external pathways (i.e., plume and ground exposure) as well as the internal pathways (inhalation and ingestion).
1.2.2 Liquid Effluents Maximum individual doses from the release of radioactive liquid effluents were calculated using OpenEMS which gives dose results equal to dose results calculated using NRC Regulatory Guide 1.109. OpenEMS performs calculations for the following pathways: fish, shellfish, shoreline activity, swimming, and boating.
Doses are calculated for the whole body, skin, thyroid, and maximum organ (GI, bone, liver, kidney, and Jung).
1.2.3 Analysis of Results Table 1-3 provides a quantitative dose comparison with the limits specified in the REMODCM. Gaseous and liquid effluent doses are compared to limits required by technical specifications and contained in Appendix I of 10 CFR 50. Total offsite doses are compared to limits in 40 CFR 190 (Reference 8). The data indicates that the total whole body and organ doses to the maximum offsite individual from MPS including all sources of the 6
fuel cycle are well within the limits. On-site radioactive waste and spent fuel storage during this year was within storage criteria and the maximum dose to a member of the public from these sources was approximately 0.13 rnrem. The doses from gaseous and liquid effluents were added to the estimated dose from on-site radioactive waste storage to show compliance compared to 40 CFR 190.
The Offsite Dose Comparison, Table 1-4, provides a perspective on the maximum offsite individual dose received from MPS with the natural background radiation dose received by the average Connecticut resident (Reference 4). The total dose to the maximum individual received from MPS is small(< 0.3%) in comparison to the dose received from natural background radiation.
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Table 1-1 2017 Off-Site Dose Commitments from Gaseous Effluents MPS1, 2, 3 MPS1 Max Air Beta Gamma Max Individual Whole Body Skin Thyroid Max organ 1 MPS2 Max Air Beta Gamma Max Individual Whole Body Skin Thyroid Max organ 1 MPS3 Max Air Beta Gamma Max Individual Whole Body Skin Thyroid Max organ1 NOTES:
1st Quarter mrad O.OOE+OO O.OOE+OO mrem 9.28E-06 9.14E-06 9.14E-06 9.53E-06 1st Quarter mrad 5.66E-06 1.23E-05 mrem 2.42E-03 2.81 E-04 2.55E-03 1.17E-02 1st Quarter mrad 4.21 E-05 2.82E-06 mrem 4.81 E-03 2.35E-03 4.81 E-03 1.47E-02 2nd Quarter mrad O.OOE+OO O.OOE+OO mrem 3.60E-04 2.SOE-04 3.60E-04 3.60E-04 2nd Quarter mrad 3.18E-05 6.04E-05 mrem 1.79E-02 5.58E-04 1.80E-02 1.06E-01 2nd Quarter mrad 1.07E-06 1.93E-07 mrem 1.88E-02 1.79E-03 1.88E-02 9.83E-02 3rd Quarter 4th Quarter Annual Total mrad mrad mrad O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO mrem mrem mrem 1.12E-05 5.75E-04 9.55E-04 4.65E-06 4.61 E-04 7.25E-04 1.12E-05 5.75E-04 9.55E-04 1.12E-05 5.75E-04 9.56E-04 3rd Quarter 4th Quarter Annual Total mrad mrad mrad 5.77E-07 3.27E-06 4.13E-05 1.37E-06 8.15E-06 8.22E-05 mrem mrem mrem 1.18E-02 4.03E-02 7.24E-02 3.07E-04 1.04E-03 2.19E-03 1.18E-02 4.0SE-02 7.29E-02 6.98E-02 2.25E-01
- 4. 13E-01 3rd Quarter 4th Quarter Annual Total mrad mrad mrad 2.02E-06 2.38E-05 6.90E-05 3.34E-07 4.34E-05 4.67E-05 mrem mrem mrem 9.92E-03 5.88E-02 9.23E-02 3.79E-04 2.94E-03 7.46E-03 9.40E-03 5.71 E-02 9.01 E-02 5.76E-02 2.88E-01 4.59E-01 1-Maximum of the following organs (not including thyroid): Bone, GI-LL/, Kidney Liver Lung 8
Table 1-2 2017 Off-Site Commitments from Liquid Effluents MPS1, 2, 3 MPS1 Max Individual Whole Body Thyroid Max Or an 1 MPS2 Max Individual Whole Body Thyroid Max Ore an 1 MPS3 Max Individual Whole Body Thyroid Max Or an 1 NOTES:
1st Quarter (mrem) 1.37E-05 3.79E-06 2.19E-05 1st Quarter (mrem) 1.77E-04 1.12E-04 6.32E-04 1st Quarter (mrem) 6.19E-05 6.19E-05 6.19E-05 2nd Quarter (mrem) 3.00E-05 8.32E-06 4.58E-05 2nd Quarter (mrem) 1.96E-05 1.48E-05 1.49E-03 2nd Quarter (mrem) 7.56E-05 4.34E-05 2.80E-04 3rd Quarter (mrem)
O.OOE+OO O.OOE+OO O.OOE+OO 3rd Quarter (mrem) 2.38E-06 2.38E-06 2.38E-06 3rd Quarter (mrem) 2.09E-04 2.09E-04 2.09E-04 4th Quarter (mrem) 3.34E-06 9.69E-07 4.74E-06 4th Quarter (mrem) 3.03E-05 2.80E-05 3.79E-05 4th Quarter (mrem) 2.76E-04 2.75E-04 2.79E-04 Annual Total (mrem) 4.71 E-05 1.31E-05 7.25E-05 Annual Total (mrem) 2.29E-04 1.57E-04 2.16E-03 Annual Total (mrem) 6.22E-04 5.90E-04 8.31 E-04 1-Maximum of the following organs (not including thyroid): Bone, GI-LL/, Kidney Liver Lung 9
1, MPS1 MPS2 1,
MPS3 MPS Limits Table 1-3 2017 Off-Site Dose Comparison to Limits MPS1, 2, 3 Gaseous Effluents Dose Whole Body Thyroid Max Organ*
Skin Beta Air Gamma Air (mrem)
(mrem)
(mrem)
(mrem)
(mrad)
(mrad) 9.55E-04 9.55E-04 9.56E-04 7.25E-04 O.OOE+OO O.OOE+OO 7.24E-02 7.29E-02 4.13E-01 2.19E-03 4.13E-05 8.22E-05 9.23E-02 9.01 E-02 4.59E-01 7.46E-03 6.90E-05 4.67E-05 1.66E-01 1.64E-01 8.73E-01 1.04E-02 1.10E-04 1.29E-04 5
15 15 15 20 10 Liquid Effluents Dose Max Whole Body Thyroid Organ*
(mrem)
(mrem)
(mrem)
MPS1 4.71 E-05 1.31 E-05 7.25E-05 MPS2 2.29E-04 1.57E-04 2.16E-03 MPS3 6.22E-04 5.90E-04 8.31 E-04 MPS 8.98E-04 7.60E-04 3.06E-03 Limits 3
10 10 Total Off-Site Dose from MPS Max Organ Whole Body Thyroid (mrem)
(mrem)
(mrem)
Gaseous I
1.66E-01 1.64E-01 8.73E-01 Liquid 8.98E-04 1.57E-04 2.16E-03 Direct Shine**
1.40E-01 1.40E-01 1.40E-01 MPS 3.07E-01 3.04E-01 1.01 E+OO Limits 25 75 25 Maximum of the following organs (not including Thyroid): Bone, GI-LLI, Kidney, Liver, Lung
- Direct shine is radiation exposure from onsite storage of radwaste and spent fuel.
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Table 1-4 2017 Off-Site Dose Comparison Natural Background vs MPS Average Resident Cosmic Terrestrial (Atlantic and Gulf Coastal Plain)
Inhaled In the Body Courtesy UNSCEAR Report 2000 Maximum Off-Site Individual Gaseous Effluents Liquid Effluents Direct Shine Natural Background Radiation Dose 30 -100 mrem 30 - 60 mrem 20 - 1,000 mrem 20 - 80 mrem 100 -1,240 I mrem MPS Whole Body Dose 0.166 mrem 0.001 mrem 0.140 mrem 0.307 1 mrem 1.3 Other Sources of Radiation Dose to the Public (from Ref. 12)
This section discusses the doses that the average American typically receives each year from naturally occurring background radiation and all other sources of radiation. The reader can compare the doses received 11
from MPS effluents with the doses received from natural, medical, and other sources of radiation. This comparison provides some context to the concept of radiation dose effects. In March 2009, the National Council on Radiation Protection and Measurements (NCRP) published Report No. 160 as an update to the 1987 NCRP Report No. 93, Ionizing Radiation Exposure of the Population of the United States. Report No.
160 describes the doses to the U.S. population from all sources of ionizing radiation for 2006, the most recent data available at the time the NCRP report was written. The NCRP report also includes information on the variability of those doses from one individual to another. The NCRP estimated that the average person in the United States receives about 620 mrem of radiation dose each year. NCRP Report No. 160 describes each of the sources of radiation that contribute to this dose, including:
- Naturally occurring sources (natural background) such as cosmic radiation from space, terrestrial radiation from radioactive materials in the earth, and naturally occurring radioactive materials in the food people eat and in the air people breathe;
- medical sources from diagnosis and treatment of health disorders using radioactive pharmaceuticals and radiation-producing equipment;
- consumer products (such as household smoke detectors);
- industrial processes, security devices, educational tools, and research activities; and
- exposures of workers that result from their occupations.
Below is a pie chart showing the relative contributions of these sources of radiation to the dose received by the average American. Larger contributors to dose are represented by proportionally larger slices of the pie.
Doses to the public from nuclear power plants are included in the industrial category; doses to workers from nuclear power generation are included in the category of occupational dose. Doses to the public due to effluents from nuclear power plants are less than 0.1 % ( one-tenth of one percent) of what the average person receives each year from all sources of radiation. Doses to workers from occupational exposures, including those received from work at NPPs, also are less than 0.1 % of the average dose to a member of the public from all sources.
Sources of Radiation Exposure to the U.S. Population Industrial includes doses to the public from nuclear fX)wer generation
<0.1%
Occupational includes doses to work.ers from nuclear power generation
<0.1%
Conventional radiography /
fluoroscopy (medical) 5%
12 Space (background) 5%
lnterventional flouroscopy (medical) 7%
Internal (background) 5%
Computed tomography (medical) 24%
2.0 Effluent Radioactivity 2.1 Gaseous Effluents 2.1.1 Measurement of Radioactivity in Gaseous Effluents 2.1.1.1 Continuous Releases The following pathways have continuous radiation monitors which monitor gaseous radioactivity and collect radioactive particulates on filters and radioactive halogens (iodine's, etc.) on charcoal cartridges except where noted on the list.
MPSl SFPI Island (no charcoal cartridge)
MPSl BOP Vent (no charcoal cartridge)
MPS2 Ventilation Vent MPS2 Wide Range Gas Monitor (WRGM) to Site Stack MPS2 Equipment Hatch Opening (no gaseous monitoring)
MPS3 Ventilation Vent MPS3 SLCRS to Site Stack MPS3 ESF Building Vent MPS3 Containment Equipment Hatch Openings (no gaseous monitoring)
Most releases are based on results of sample analyses. Charcoal cartridges and particulate filters are replaced weekly (except every two weeks for MPSl) and analyzed for isotopic content using a gamma spectrometer. Particulate filters are also analyzed for Strontium-89 (Sr-89) ( except for MPS 1 ), Strontium-90 (Sr-90) and gross alpha. At least monthly, gaseous grab samples are taken and analyzed for noble gasses and H-3. The gas washing bottle (bubbler) method is utilized for H-3 collection. This sample is counted on a liquid scintillation detector. Isotopic concentrations at the release point are multiplied by the total flow to obtain the total activity released for each isotope.
Some releases are ba ed on calculation. These include tritium from spent fuel pools, Carbon 14 (C-14) and RWST vent releases.
Spent fuel pool tritium release is calculated using concentrations of tritium in the water and evaporation determined by change in pool levels. Grab samples from the MPS 1 SFPI Vent and the MPS2 and MPS3 Vents are compared to the measured evaporation technique and the higher amount from either the vent or the measured evaporation technique is used to determine the amount ofH-3 released.
C-14 releases are calculated using the methodology in Reference 11. Based on Reference 2, it was conservatively assumed that 30% of the C-14 exists as carbon dioxide (CO2) which may be deposited on surfaces. Thus only 30% of C-14 released yielded dose via ingestion pathways of milk, meat, produce and vegetation. C-14 has always been released from the plant but, previous to 2010, was not reported because it was not a significant release relative to other radioactive releases. Since the overall quantity of other radioactive releases has steadily decreased due to improvements in power plant operations, C-14 now qualifies as a principle radionuclide. For each Unit, it is assumed that half of the C-14 is released from the MPS and half from each unit's main ventilation vent.
When water is transferred to the RWST there is a potential for a release of radioactivity through the tank vent. Releases of particulates and H-3 from the MPS2 and MPS3 RWSTs were estimated using factors for release from water to air. For H-3 the release factor is based on the ratio of mass of water vapor to mass of dry air and adjusted for difference between water and air densities. For particulates the release factor is based on an assumed partitioning factor of 10,000. RWST vent releases are calculated using concentration of tritium in water, particulate radioactivity added to the RWST during outages and volumes of air exhaled based on observed changes in water level and on thermal fluctuations of the water. During 2017 MP-CHEM-17-07, "Reporting of Radioactivity Released from RWST Vents" was written to establish threshold values for determining releases. The threshold value eliminated the monthly tracking tritium released through the RWST vent, but ensures that major level changes resulting significant release are tracked.
13
Any releases from the spent fuel pool area in the reactor building at MPS 1 are released through the SFPI Vent.
Releases from other parts of the MPSI reactor building and other buildings are continuously discharged to the BOP Vent.
Samples of air near the containment equipment hatch openings are analyzed for particulates and iodines, during refueling outages for the period that the equipment hatch is open. An estimated flow out of the hatch and sample results are used to determine the radioactivity released. Containment equipment hatch and containment drawdown releases at MPS3 occurred only during the MPS3 outage during the second quarter.
2.1.1.2 Batch Releases The following sources of radioactivity releases are considered batch releases:
MPS2 Waste Gas Decay Tanks (WGDT) (via MPS2 WRGM to MPS Stack)
MPS3 Containment Purges (via Ventilation Vents)
MPS2 and MPS3 Containment Vents (via EBFS to MPS Stack for MPS2 and via SLCRS to MPS Stack for MPS3)
MPS3 Containment Drawdown (ground level release at containment)
Waste Gases from the MPS2 Gaseous Waste Processing System are held for decay in waste gas decay tanks prior to discharge through the MPS Site Stack. Each gas decay tank is analyzed prior to discharge for noble gas and H-3. Calculated volume discharged is multiplied by the isotopic concentrations (noble gas and H-
- 3) from the analysis of grab samples to determine the total activity released.
Containment air is sampled periodically for gamma and H-3 to determine the activity released from containment venting. The measured concentrations are multiplied by the containment vent volume to obtain the total activity released. MPS2 typically performs this process of discharging air from containment to maintain pressure approximately once per week and MPS3 vents containment about 15 times per month.
Any iodines and particulates discharged would be detected by the continuous monitoring discussed in Section 2.1. l. l.
Containment air is sampled prior to each purge for gamma and H-3 to determine the activity released from containment purging. Similar to containment venting, the measured concentrations are multiplied by the containment purge volume to obtain the total activity released. Any iodines and particulates discharged would be detected by the continuous monitoring discussed in section 2.1.1.1.
MPS3 containment is initially drawn down prior to startup. This is accomplished by using the containment vacuum steam jet ejector which releases through an unmonitored vent on the roof of the Auxiliary Building.
Grab samples are performed prior to drawdown to document the amount of radioactivity released during these evolutions.
2.1.2 Estimate of Errors Estimates of errors associated with radioactivity measurements were made using the following guidelines:
Radioactivity Measurement Calibration 10%
Calibration to NIST* standards Sampling/Data Collection Sample Line Loss Sample Counting Flow & Level Measurements 10%-20%
20%-40%
10%- 30%
10%-20%
14 Variation in sample collection Deposition of some nuclides Error for counting statistics Error for release volumes
- National Institute of Standards and Technology
2.1.3 Gaseous Batch Release Statistics MPS1 - None MPS2 CTMT Vents WGDT CTMTPurge Number of Batches 34 4
1 Total Time (min) 4780 714 1612 Maximum Time (min) 199 205 1612 Average Time (min) 141 179 1612 Minimum Time (min) 29 146 1612 MPS3 CTMT Vents CTMT Purge Number of Batches 168 1
Total Time (min) 48596 240 Maximum Time (min) 439 240 Average Time (min) 289 240 Minimum Time (min) 119 240 2.1.4 Abnormal Gaseous Releases An abnormal gaseous release of radioactivity is defined as radioactive material released in gaseous effluents to the environment that was unplanned or uncontrolled due to an unanticipated event. These do not include normal routine effluent releases from anticipated operational and maintenance occurrences such as power level changes, reactor trip, opening primary system loops, degassing, letdown of reactor coolant or transferring spent resin and do not include non-routine events such as minor leakages from piping, valves, pump seals, tank vents, etc.
2.1.4.1 MPS1 - None 2.1.4.2 MPS2 - None 2.1.4.3 MPS3 - None 2.1.5 Gaseous Release Tables The following tables provide the details of the gaseous radioactivity released from each of the MPS units.
They are categorized by type of release, source(s), and by release point of discharge to the environment.
15
Table 2.1-A1 MPS1 Gaseous Effluents - Release Summary Units A. Fission & Activation Gases
- 1.
Total Activity Ci Released
- 2.
Average Period uCi/sec Release Rate B I d"
/ H I 0 mes a O!=lens
- 1.
Total Activity Ci na na Released
- 2.
Average Period uCi/sec na na Release Rate C. Particulates
- 1.
Total Activity Ci 4.46E-07 9.85E-06 Released
- 2.
Average Period uCi/sec 5.73E-08 1.25E-06 Release Rate D. Gross Alpha
- 1.
Total Activity Ci Released E. Tritium
- 1.
Total Activity Ci 1.21 E-02 4.33E-01 Released
- 2.
Average Period uCi/sec 1.56E-03 5.51 E-02 Release Rate denotes less than Minimum Detectable Activity (MDA)
"na" denotes not required to be analyzed 16 na na 1.14E-02 1.44E-03 na na na na 1.03E-05 3.26E-07 6.11E-01 1.07E+OO 7.69E-02 3.39E-02
Table 2.1-A2 MPS1 Gaseous Effluents - Ground Continuous - BOP Vent & SFPI Vent Nuclides Released Units A. Fission & Activation Gases Kr-85 Ci Other v Emitters Ci Total Activity Ci B I d"
/ H I 0 mes a o~ ens 1-131 Ci na na Other v Emitters Ci Total Activity Ci C. Particulates Be-7 Ci 9.85E-06 Cs-1 37 Ci 4.46E-07 Other v Emitters Ci Sr-90 Ci Total Activity Ci 4.46E-07 9.85E-06 I Gross Alpha D. Gross Alpha Ci E. Tritium I H-3 Ci 1.21 E-02 4.33E-01 denotes less than Minimum Detectable Activity (MDA)
"na" denotes not required to be analyzed 17 na na 1.14E-02 6.11 E-01 na 9.85E-06 4.46E-07 1.03E-05 1.07E+OO
Table 2.2-A1 MPS2 Gaseous Effluents - Release Summary Units A. Fission & Activation Gases
- 1.
Total Activity Ci Released
- 2.
Average Period uCi/sec Release Rate B I d"
/ H I 0 mes a ogens
- 1.
Total Activity Released
- 2.
Average Period Release Rate C. Particulates
- 1.
Total Activity Released
- 2.
Average Period Release Rate D. Gross Alpha
- 1.
Total Activity Released E. Tritium
- 1.
Total Activity Released
- 2.
Average Period Release Rate F. C-14
- 1.
Total Activity Released**
- 2.
Average Period Release Rate Ci uCi/sec Ci uCi/sec Ci Ci uCi/sec Ci uCi/sec 8.72E-02 8.95E-02 1.12E-02 1.14E-02 8.12E-05 5.37E-05 1.04E-05 6.83E-06 3.45E-05 4.38E-06 9.39E-01 2.03E+OO 1.21 E-01 2.59E-01 2.26E+OO 2.26E+OO 2.91 E-01 2.87E-01 denotes less than Minimum Detectable Activity (MDA) 5.77E-02 7.26E-03 6.12E-07 7.70E-08 2.07E+OO 2.60E-01 2.26E+OO 2.84E-01 4.38E-02 2.78E-01 5.52E-03 8.82E-03 1.75E-06 1.37E-04 2.20E-07 4.35E-06 3.45E-05 1.09E-06 5.39E+OO 1.04E+01 6.78E-01 3.31 E-01 2.26E+OO 9.04E+OO 2.84E-01 2.87E-01 Calculated value per "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents" EPRI Final Report, 12/2010.
18
Table 2.2-A2 MPS2 Gaseous Effluents - Ground Level Release - Batch Mode Release Point - No Releases Nuclides Released Units A. Fission & Activation Gases I Total Activity I
Ci I
I Total Activity I
Ci B. Iodines / Halogens C. Particulates I Total Activity Ci
/ Gross Alpha Ci D. Gross Alpha E. Tritium I H-3 Ci No activity released 19
Table 2.2-A3 MPS2 Gaseous Effluents - Ground Level Release - Continuous Mode Release Point - Refuel Water Storage Tank Vent, Equipment Hatch Nuclides Released Units A. Fission & Activation Gases Xe-133 Ci 6.20E-04 Other v Emitters Ci Total Activity Ci B. Iodines / H alogens 1-131 Ci 5.94E-08 1-133 Ci Other v Emitters Ci Total Activity Ci 5.94E-08 C. Particulates Cr-51 Ci 7.07E-06 Mn-54 Ci 2.21 E-07 Fe-59 Ci 7.51 E-08 Co-58 Ci 1.57E-05 Co-60 Ci 2.27E-06 Zr-95 Ci 1.58E-06 Nb-95 Ci 2.25E-06 Aa-110m Ci 2.78E-06 Sn-113 Ci 2.03E-07 Sn-117m Ci 5.45E-08 Sb-124 Ci 3.98E-07 Sb-125 Ci 1.22E-06 Sb-126 Ci 6.92E-09 Cs-136 Ci 2.25E-08 Cs-137 Ci 5.77E-07 Ce-141 Ci 3.37E-09 Other v Emitters Ci Total Activity Ci 3.44E-05 I Gross Alpha D. Gross Alpha Ci na na na na E. Tritium Ci 1.42E-04 4.04E-03 "na" denotes Not Required to be Analyzed denotes less than Minimum Detectable Activity (MDA) 20 6.20E-04 6.20E-04 5.94E-08 5.94E-08 7.07E-06 2.21 E-07 7.51 E-08 1.57E-05 2.27E-06 1.58E-06 2.25E-06 2.78E-06 2.03E-07 5.45E-08 3.98E-07 1.22E-06 6.92E-09 2.25E-08 5.77E-07 3.37E-09 3.44E-05 na 4.18E-03
Table 2.2-A4 MPS2 Gaseous Effluents - Elevated Release - Batch Mode Release Point-MPS Stack Nuclides Released Units A. Fission & Activation Gases Ar-41 Ci 4.54E-02 2.01 E-02 Kr-85 Ci 6.79E-03 3.94E-03 Xe-133 Ci 3.43E-02 9.92E-03 Xe-135 Ci 6.93E-04 3.55E-04 Other y Emitters Ci Total Activity Ci 8.72E-02 3.43E-02 B I d"
/ H I 0 mes a o~ 1ens Ci Other v Emitters Ci Total Activity Ci C. Particulates I Othec y Emittecs i
Ci I
Ci Ci Total Activity D. Gross Alpha I Gross Alpha Ci na na E. Tritium I H-3 Ci 1.43E-01 2.90E-02 denotes less than Minimum Detectable Activity (MDA)
"na" denotes not required to be analyzed 21 3.47E-02 3.04E-02 1.19E-03 9.96E-04 2.11 E-02 1.19E-02 7.63E-04 5.63E-04 5.78E-02 4.39E-02 na na 1.39E-01 1.69E-01 1.31E-01 1.29E-02 7.73E-02 2.37E-03 2.23E-01 na 4.80E-01
Table 2.2-AS MPS2 Gaseous Effluents - Elevated Release - Continuous Mode Release Point - MPS Stack Nuclides Released Units A. Fission & Activation Gases I Olhec y Em;ttec, I ~: I Total Activity C
B I d"
/ H I 0 mes ao gens 1-131 Ci 1-133 Ci Other y Emitters Ci Total Activity Ci C. Particulates Sr-89 Ci Sr-90 Ci Other y Emitters Ci Total Activity Ci D. Gross Alpha I Gross Alpha I Ci E. Tritium I H-3 Ci 1.79E-01 1.27E-01 F. C-14 I C-14 Ci 1.13E+OO 1.13E+OO 1.13E+OO 1.13E+OO denotes less than Minimum Detectable Activity (MDA) 22 3.06E-01 4.52E+OO
Table 2.2-A6 MPS2 Gaseous Effluents - Mixed Mode Release - Batch Mode Release Point-MPS2 Main Exhaust Vent Nuclides Released Units A. Fission & Activation Gases Ar-41 Ci 1.98E-02 Xe-133 Ci 3.36E-02 Xe-135 Ci 1.19E-03 Other v Emitters Ci Total Activity Ci 5.46E-02 B I d.
/ H I 0 mes a ogens Br-82 Ci 1.30E-05 Other v Emitters Ci Total Activity Ci 1.30E-05 C. Particulates Ci Other v Emitters Ci Total Activity Ci I Gross Alpha D. Gross Alpha Ci na na na na E. Tritium I H-3 Ci 1.79E-01
- No activity released "na" denotes not required to be analyzed denotes less than Minimum Detectable Activity (MDA) 23 1.98E-02 3.36E-02 1.19E-03 5.46E-02 1.30E-05 1.30E-05 na 1.79E-01
Table 2.2-A7 MPS2 Gaseous Effluents - Mixed Mode Release - Continuous Mode Release Point - MPS 2 Main Exhaust Vent Nuclides Released Units A. Fission & Activation Gases I Olhec y Emitte~
I ;: I Total Activit B I d"
/ H 0 mes ao gens Br-85 Ci 5.41 E-06 1-131 Ci 1.82E-05 1.00E-06 6.12E-07 1.75E-06 1-133 Ci 5.75E-05 5.11 E-06 Other v Emitters Ci Total Activity Ci 8.1 1 E-05 6.11 E-06 6.12E-07 1.75E-06 C. Particulates Ci Other v Emitters Ci Sr-89 Ci Sr-90 Ci Total Activity Ci D. Gross Alpha I
I Gross Alpha Ci E. Tritium I H-3 Ci 7.96E-01 1.82E+OO 1.75E+OO 5.09E+OO F. C-14 I C-14 Ci 1.13E+OO 1.13E+OO 1.13E+OO 1.13E+OO denotes less than Minimum Detectable Activity (MDA) 24 5.41 E-06 2.16E-05 6.26E-05 8.96E-05 9.46E+OO 4.52E+OO
Table 2.3-A1 MPS3 Gaseous Effluents - Release Summary Units A. Fission & Activation Gases
- 1.
Total Activity Ci Released
- 2.
Average Period uCi/sec Release Rate B I d"
/ H I o mes a ogens
- 1.
Total Activity Released
- 2.
Average Period Release Rate C. Particulates
- 1.
Total Activity Released
- 2.
Average Period Release Rate D. Gross Alpha
- 1.
Total Activity Released E. Tritium
- 1.
Total Activity Released
- 2.
Average Period Release Rate F. C-14
- 1.
Total Activity Released**
- 2.
Average Period Release Rate Ci uCi/sec Ci uCi/sec Ci Ci uCi/sec Ci uCi/sec 2.23E-01 2.22E-01 2.87E-02 2.83E-02 2.75E-06 1.28E-05 3.53E-07 1.63E-06 5.89E-08 7.58E-09 1.34E+01 1.04E+01 1.73E+OO 1.32E+OO 2.88E+OO 2.88E+OO 3.70E-01 3.66E-01 denotes less than Minimum Detectable Activity (MDA) 2.46E-01 3.10E-02 1.81 E-06 2.27E-07 4.39E+OO 5.53E-01 2.88E+OO 3.62E-01 3.04E-01 9.96E-01 3.82E-02 3.16E-02 1.60E-06 1.90E-05 2.01 E-07 6.02E-07 1.42E-03 1.42E-03 1.79E-04 4.52E-05 1.35E+01 4.17E+01 1.70E+OO 1.32E+OO 2.88E+OO 1.15E+01 3.62E-01 3.65E-01 Calculated value per "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents" EPRI Final Report, 12/2010.
25
Table 2.3-A2 MPS3 Gaseous Effluents - Ground Level Release - Batch Mode Release Point -ESF Building Rooftop Nuclides Released Units A. Fission & Activation Gases B. Iodines Halo~ens 1-131 Ci 1-133 Ci Other v Emitters Ci Total Activity Ci C. Particulates I y Emitters Ci Total Activity Ci D. Gross Alpha I Gross Alpha Ci na na na E. Tritium H-3 Ci
- No activity released II II denotes less than Minimum Detectable Activity (MDA)
"na" denotes Not Required to be Analyzed 26 na na
Table 2.3-A3 MPS3 Gaseous Effluents - Ground Level Release - Continuous Mode Release Point - ESF Building Vent, Containment Equipment Hatch, RWST Vent, ABD TK-2 Vent Nuclides Released Units A. Fission & Activation Gases I Othec y Emittern I ~: I Total Activity B I d"
/ H 0 mes a ogens 1-131 Ci 1-133 Ci Other y Emitters Ci Total Activity Ci C. Particulates Cr-51 Ci Mn-54 Ci Fe-59 Ci Co-57 Ci Co-58 Ci Co-60 Ci Zr-95 Ci Nb-95 Ci Sb-125 Ci Cs-137 Ci Total Activity Ci I Gross Alpha D. Gross Alpha Ci E. Tritium I H-3 Ci 4.81 E-02 1.13E-01 denotes less than Minimum Detectable Activity (MDA)
- No activity released 27 5.72E-04 5.72E-04
- 4. 16E-05 4.16E-05 1.62E-05 1.62E-05 2.84E-08 2.84E-08 4.31 E-04 4.31 E-04 1.1 0E-03 1.10E-03 4.32E-05 4.32E-05 6.97E-05 6.97E-05 4.76E-07 4.76E-07 6.01 E-06 6.01 E-06 2.28E-03 2.28E-03 3.89E-02 4.55E-02 2.45E-01
Table 2.3-A4 MPS3 Gaseous Effluents - Elevated Release - Batch Mode Release Point - MPS Stack Nuclides Released Units A. Fission & Activation Gases Ar-41 Ci 7.83E-03 Xe-133 Ci 5.61 E-04 Xe-135 Ci 2.60E-04 Other y Emitters Ci Total Activity Ci 8.65E-03 B I d"
/ H I 0 mes a ogens Ci Other v Emitters Ci I
Total Activity Ci I
C. Particulates I Othec y Emittern Ci Ci Total Activity Ci I Gross Alpha D. Gross Alpha Ci na E. Tritium I H-3 Ci 2.0SE-01 denotes less than Minimum Detectable Activity (MDA)
"na" denotes Not Required to be Analyzed 8.14E-03 8.20E-04 I 3.SSE-03 1.88E-04 8.40E-04 I 4.34E-05 1.19E-04 2.77E-04 I
8.45E-03 9.31 E-03 I 3.60E-03 I
I I
I na na na 6.36E-02 5.56E-02 2.56E-02 28 2.77E-02 1.63E-03 6.57E-04 3.00E-02 na 3.SOE-01
Table 2.3-AS MPS3 Gaseous Effluents - Elevated Release - Continuous Mode Release Point - MPS Stack Nuclides Released Units A. Fission & Activation Gases Ar-41 Ci 1.00E-04 1.40E-01 Kr-85 Ci 1.46E-01 2.14E-01 2.37E-01 1.26E-01 Kr-85m Ci 8.80E-05 1.68E-03 Kr-87 Ci 1.80E-04 2.00E-03 Kr-88 Ci 1.90E-04 2.50E-03 Xe-133 Ci 1.90E-04 3.20E-03 Xe-135 Ci 5.50E-04 3.20E-03 Xe-135m Ci 1.70E-04 1.01 E-02 Xe-138 Ci 7.00E-04 8.90E-03 Other v Emitters Ci Total Activity Ci 1.48E-01 2.14E-01 2.37E-01 2.98E-01 B I d'
/ H I 0 mes ao !1ens Br-82 Ci 2.75E-06 1.28E-05 1.81 E-06 1.60E-06 1-131 Ci 1-133 Ci Other v Emitters Ci Total Activity Ci 2.75E-06 1.28E-05 1.81 E-06 1.60E-06 C. Particulates Mn-54 Ci 3.08E-08 Co-58 Ci 4.42E-07 Co-60 Ci 1.96E-07 Sr-89 Ci Sr-90 Ci Ba-131 Ci 5.89E-08 Other v Emitters Ci Total Activity Ci 5.89E-08 6.69E-07 D. Gross Alpha I Gross Alpha I Ci E. Tritium J H-3 Ci 1.20E+OO 2.04E+OO 6.39E-01 2.15E-01 F. C-14 I C-14 Ci 1.44E+OO 1.44E+OO 1.44E+OO 1.44E+OO denotes less than Minimum Detectable Activity (MDA) 29 1.40E-01 7.23E-01 1.77E-03 2.18E-03 2.69E-03 3.39E-03 3.75E-03 1.03E-02 9.60E-03 8.97E-01 1.90E-05 1.90E-05 3.08E-08 4.42E-07 1.96E-07 5.89E-08 7.28E-07 4.09E+OO 5.76E+OO
Table 2.3-A6 MPS3 Gaseous Effluents - Mixed Mode Release - Batch Mode Release Point - MPS3 Ventilation Vent Nuclides Released Units A. Fission & Activation Gases Xe-133 Ci Xe-135 Ci Other y Emitters Ci Total Activity Ci B I d'
/ H 0 mes alogens Ci Other v Emitters Ci Total Activity Ci C. Particulates Ci Other v Emitters Ci Total Activity Ci I Gross Alpha D. Gross Alpha Ci E. Tritium 1.78E-03 6.26E-04 2.41 E-03 na na na na 1.78E-03 6.26E-04 2.41 E-03 na
! H-3 Ci
! 4.13E-02 ! 4.13E-02 !
- No activity released
"-" denotes less than Minimum Detectable Activity (MDA)
"na" denotes Not Required to be Analyzed 30
Table 2.3-A?
MPS3 Gaseous Effluents - Mixed Mode Release - Continuous Mode Release Point - MPS3 Ventilation Vent Nuclides Released Units A. Fission & Activation Gases Kr-85 Ci 6.60E-02 Other Emitters Ci Total Activit Ci 6.60E-02 B. Iodines/ Halo ens 1-131 Ci 1-133 Ci Other Emitters Ci Total Activit Ci C. Particulates Cr-51 Ci 3.53E-05 Co-58 Ci 7.80E-05 Co-60 Ci 1.39E-05 Nb-95 Ci 3.72E-06 Other Emitters Ci Sr-89 Ci Sr-90 Ci Total Activit Ci 1.31 E-04 D. Gross Alpha I Gross Alpha I Ci E. Tritium
/ H-3 Ci 1.20E+01 8.18E+OO 3.66E+OO 1.32E+OO F. C-14 I C-14 Ci 1.44E+OO 1.44E+OO 1.44E+OO 1.44E+OO denotes less than Minimum Detectable Activity (MDA) 31 6.60E-02 6.60E-02 3.53E-05 7.80E-05 1.39E-05 3.72E-06 1.31 E-04 3.70E+01 5.76E+OO
2.2 Liquid Effluents 2.2.1 Measurement of Radioactivity in Liquid Effluents 2.2.1.1 Continuous Liquid Releases Water containing radioactivity is continuously released through one of two pathways - the MPS Quarry or DSN006. DSN006 is next to the MPS3 intake structure (DSN is acronym for Discharge Serial Number.)
Grab samples are taken for continuous liquid release pathways and analyzed on the gamma spectrometer and liquid scintillation detector (for H-3) if required by the conditional action requirements of the REMODCM.
Total estimated volume is multiplied by the isotopic concentrations (if any) to determine the total activity released. A proportional aliquot of each discharge is retained for composite analysis for Sr-89, Sr-90, Fe-55 and gross alpha ifrequired by the conditional action requirements of the REMODCM. Sources for continuous liquid effluent releases via the MPS Quarry include Steam Generator Blowdown for MPS2 & MPS3, Service Water Effluent for MPS2 & MPS3 and Reactor Building Closed Cooling Water (RBCCW) Sump for MPS2.
Sources for continuous liquid effluent releases via DSN006 include Turbine Building Sump discharge from MPS2 & MPS3, CPF TK.2 from MPS3 and SRW Sump 3 from MPS3.
2.2.1.2 Batch Liquid Releases from Tanks and Sumps Batch liquid releases are made via both the MPS Quarry and DSN006. There are numerous sources from which batches of liquids containing radioactivity are discharged to the environs. Except for two sources from MPS3 to DSN006 they are discharged via the MPS Quarry. The sources are:
MPS1 Radwaste Processing System - Includes sources from:
- 1. Reactor Building Sumps
- 2. Underground Ventilation Duct
- 3. Site Stack Sump MPS2 Radwaste Processing System:
- 1. Clean Waste Monitor Tanks (2)
- 2. Aerated Waste Monitor Tanks Other Radwaste Sources:
- 1. CPF Waste Neutralization Sump
- 2. Steam Generator Bulk
- 3. Other Systems' Bulk Discharges MPS3 Radwaste Processing
- 1. Waste Test Tanks (2)
- 2. Low Level Waste Test Tanks (2)
- 3. Boron Test Tanks (2)
Other Radwaste Sources:
- 1. CPF Waste Neutralization Sump
- 2. Steam Generator Bulk
- 3. Other systems' Bulk Discharges (via Quarry or DSN006)
Prior to release, a tank is re-circulated for two equivalent tank volumes, a sample is drawn and then analyzed on the HPGe gamma spectrometer and liquid scintillation detector (H-3) for individual radionuclide composition.
Isotopic concentrations are multiplied by the volume released to obtain the total activity released.
For bulk releases, several samples are taken during the discharge to verify the amount of radioactivity released. A proportional aliquot of each discharge is retained for composite analysis for Sr-89, Sr-90, Fe-55, and gross alpha.
32
2.2.2 Estimate of Errors Estimates of errors associated with radioactivity measurements were made using the following guidelines:
Radioactivity Measurement Calibration 10%
Calibration to NIST* standards Sampling/Data Collection 10%-20%
Variation in sample collection Sample Counting 10%- 30%
Error for counting statistics Flow & Level Measurements 10%- 20%
Error for release volumes
- National Institute of Standards and Technology 2.2.3 Liquid Batch Release Statistics MPS1 MPS2 MPS3 Radwaste Processing System:
Number of Batches 6
24 82 Total Time (min) 260 3762 8372 Maximum Time (min) 60 281 123 Average Time (min) 43 157 201 Minimum Time (min) 34 60 48 MPS1 MPS2 MPS3 Other Radwaste Sources:
Number of Batches NA 5
167 Total Time (min)
NA 572 19800 Maximum Time (min)
NA 283 194 Average Time (min)
NA 58 125 Minimum Time ( min)
NA 17 30 2.2.4 Abnormal Liquid Releases An abnormal release of radioactivity is the discharge of a volume of liquid radioactive material to the environment that was unplanned or uncontrolled. In 2017, the following abnormal liquid releases occurred:
2.2.4.1 MPS1 - None 2.2.4.2 MPS2 - None 2.2.4.3 MPS3 - None 2.2.5 Liquid Release Tables The following tables provide the details of the liquid radioactivity released from each of the MPS units.
They are categorized by type of release, source(s), and by release point of discharge to the environment.
33
Table 2.1-L 1 MPS1 Liquid Effluents - Release Summary Units A. Fission and Activation Products
- 1.
Total Activity Ci 9.72E-04 Released
- 2.
Average Period uCi/ml 4.10E-12 Diluted Activity+
B. Tritium
- 1.
Total Activity Ci 1.53E-03 Released
- 2.
Average Period uCi/ml 6.44E-12 Diluted Activity+
C. Dissolved and Entrained Gases
- 1.
Total Activity Released
- 2.
Average Period Diluted Activity+
D. Gross Alpha
- 1.
Total Activity Released E. Volume
- 1.
Released Waste Volume
- 2.
Dilution Volume Durinq Releases
- 3.
Dilution Volume Durinq Period++
- No activity released Ci uCi/ml Ci Liters 6.11E+04 Liters 4.62E+08 Liters 2.37E+11 1.87E-03 1.10E-11 2.56E-03 1.51E-11 6.40E+04 3.24E+08 1.70E+11 denotes less than Minimum Detectable Activity (MDA) 1.79E-02 6.43E-11 6.26E+04 3.83E+08 2.78E+11
+
"Total Activity Released" 7 ("Released Waste Volume"+ "Dilution Volume During Period"}
++
MPS2 Dilution Volume During Period used because there is no MPS1 dilution 34 2.95E-03 4.30E-12 2.20E-02 3.21 E-11 1.88E+05 1.17E+09 6.85E+11
Table 2.1-L2 MPS1 Liquid Effluents - Batch Release to Quarry: Liquid Radwaste Processing System Nuclides Released Units A. Fission & Activation Products Cs-137 Ci 9.06E-04 1.78E-03 Other y Emitters Ci Sr-89 Ci 4.33E-06 Sr-90 Ci 3.90E-06 Fe-55 Ci 6.11 E-05 9.03E-05 Total Activity Ci 9.72E-04 1.87E-03 B. Tritium IH-3 Ci 1.53E-03 2.56E-03 C. Dissolved & Entrained Gases Kr-85 Ci Other y Emitters Ci Total Activity Ci D. Gross Alpha
!Gross Alpha I Ci
- No activity released denotes less than Minimum Detectable Activity (MDA)
"na" denotes not required to be analyzed 35 2.62E-04 2.95E-03 2.95E-03 1.79E-02 2.20E-02
Table 2.2-L 1 MPS2 Liquid Effluents - Release Summary Units A. Fission and Activation Products
- 1.
Total Activity Ci 1.06E-02 Released
- 2.
Average Period uCi/ml 4.47E-11 Diluted Activity*
B. Tritium
- 1.
Total Activity Ci 3.09E+02 Released
- 2.
Average Period uCi/ml 1.30E-06 Diluted Activity
- C. Dissolved and Entrained Gases
- 1.
Total Activity Released
- 2.
Average Period Diluted Activity
- D. Gross Alpha 1.
Total Activity Released E. Volume
- 1.
Released Waste Volume Primary Seconda Dilution Volume During
- 2.
Releases Primary Secondary (DSN006)
Ci uCi/ml Ci Liters Liters Liters Liters Liters
- 3.
Dilution Volume During Period Quarry Liters DSN006 Liters 1.74E-02 7.34E-11 8.62E+05 2.40E+06 9.80E+09 6.53E+07 2.41 E+09 2.37E+11 6.38E+07 6.36E-04 3.74E-1 2 3.17E+01 6.98E+OO 1.87E-07 2.50E-08 7.19E-04 4.23E-12 4.77E+05 8.66E+04 1.61 E+05 1.08E+04 1.13E+10 9.35E+08 2.42E+05 4.61E+05 3.16E+09 Note 1.70E+11 2.79E+11 4.76E+07 6.17E+07 9.39E-05 3.37E-13 3.28E+01 1.18E-07 1.59E+05 3.46E+05 3.46E+09 8.46E+06 8.88E+08 2.78E+11 5.72E+07
- "Total Activity Released".;- ("Released Waste Volume" + "Dilution Volume During Period")
1111 denotes less than Minimum Detectable Activity (MDA)
Note:
No secondary releases to DSN006 in 2nd and 3rd quarters.
36 1.13E-02 4.88E-11 3.80E+02 3.94E-07 1.81 E-02 7.76E-11 1.58E+06 2.92E+06 2.55E+10 7.45E+07 6.46E+09 9.64E+1 1 2.30E+08
Nuclides Table 2.2-L2 MPS2 Liquid Effluents - Continuous
- 1. Release to Quarry: Steam Generator Slowdown, Service Water and Reactor Building Closed Cooling Water
- 2. Release to DSN006: Turbine Building Sumps and Tendon Gallery Released Units A. Fission & Activation Products v Emitters Ci Sr-89 Ci Sr-90 Ci Ni-63 Ci Total Activity Ci B. Tritium
! H-3 Ci 2.02E+03 !
1.50E-03 !
8.30E-04 !
1.14E-03 I 2.02E+03 C. Dissolved & Entrained Gases D. Gross Alpha I Gross Alpha Ci denotes less than Minimum Detectable Activity (MDA)
- No activity released 37
Table 2.2-L3 MPS2 Liquid Effluents - Batch Release to Quarry: Liquid Radwaste Processing System Nuclides Released Units A. Fission & Activation Products Be-7 Ci Mn-54 Ci 3.89E-06 Co-58 Ci 7.00E-05 Co-60 Ci 1.55E-04 2.00E-04 Nb-97 Ci Aq-110m Ci 3.01 E-05 2.97E-04 Sb-125 Ci 1.83E-04 2.44E-05 1-131 Ci Cs-137 Ci 2.98E-05 Other y Emitters Ci Fe-55 Ci 6.03E-03 4.06E-05 9.39E-05 Ni-63 Ci 6.98E-04 Sr-89 Ci 3.50E-03 Sr-90 Ci Total Activity Ci 1.06E-02 6.36E-04 9.39E-05 B. Tritium 3.89E-06 7.00E-05 3.55E-04 3.27E-04 2.0?E-04 2.98E-05 6.16E-03 6.98E-04 3.50E-03 1.14E-02 I H-3
! Ci ! 3.09E+02 ! 3.17E+01 ! 6.98E+OO ! 3.28E+01 ! 3.80E+02 !
C. Dissolved & Entrained Gases Xe-133 Ci 1.?0E-02 7.19E-04 1.77E-02 Xe-133m Ci 1.29E-04 1.29E-04 Xe-135 Ci 2.93E-04 2.93E-04 Other v Emitters Ci Total Activity Ci 1.74E-02 7.19E-04 1.81 E-02 I Gross Alpha D. Gross Alpha Ci denotes less than Minimum Detectable Activity (MDA) 38
Table 2.3-L 1 MPS3 Liquid Effluents - Release Summary Units A. Fission and Activation Products
- 1.
Total Activity Ci 1.91 E-03 Released
- 2.
Average Period uCi/ml 4.77E-12 Diluted Activity
- B. Tritium
- 1.
Total Activity Ci 1.51 E+02 6.86E+01 6.26E+02 Released
- 2.
Average Period uCi/ml 3.49E-07 1.71 E-07 1.32E-06 Diluted Activity
- C. Dissolved and Entrained Gases
- 1.
Total Activity Ci Released
- 2.
Average Period uCi/ml Diluted Activity
- D. Gross Aleha
, 1.
Total Activity Ci Released E. Volume
- 1.
Released Waste Volume Primary Liters 5.35E+05 1.31 E+06 1.15E+06 Seconda Liters 2.60E+07 2.16E+07 1.84E+07
- 2.
Dilution Volume During Releases Primary Liters 4.51 E+09 1.19E+10 1.07E+10 Secondary (DSN006)
Liters 1.25E+08 4.71 E+07 1.20E+08 Seconda Liters 1.08E+12 9.00E+11 1.10E+12
- 3.
Dilution Volume During Period Quarry Liters 4.31 E+11 4.01 E+11 4.73E+11 DSN006 Liters 6.38E+07 4.76E+07 6.17E+07 denotes less than Minimum Detectable Activity (MDA) 3.02E-04 2.21 E-03 9.49E-13 1.36E-12 5.30E+02 1.38E+03 1.67E-06 8.47E-07 1.07E+06 4.07E+06 1.47E+07 8.07E+07 8.09E+09 3.52E+10 3.37E+04 2.92E+08 7.43E+11 3.82E+12 3.18E+11 1.62E+12 5.72E+07 2.30E+08
- "Total Activity Released" + (Primary "Released Waste Volume" + "Dilution Volume During Period")
39
Table 2.3-L2 MPS3 Liquid Effluents - Continuous
- 1. Release to Quarry: Steam Generator Slowdown, Service Water, ABD TK-2
- 2. Release to DSN006: Turbine Building Sump and SRW Sump 3 Nuclides Released Units A. Fission & Activation Products v Emitters Ci Sr-89 Ci Sr-90 Ci Fe-55 Ci Total Activity Ci B. Tritium
! H-3 Ci 6.51 E-01 5.06E-01 3.24E-01 8.60E-02 1.57E+OO C. Dissolved & Entrained Gases I Gross Alpha D. Gross Alpha Ci denotes less than Minimum Detectable Activity (MDA) 40
Table 2.3-L3 MPS3 Liquid Effluents - Batch
- 1. Release to Quarry: Liquid Radwaste Processing System, CPF Waste Neutralization Sumps, Hotwell and Steam Generator Bulk, ABD TK-2
- 2. Release to DSN006: Waste Test Tank Berm Nuclides Released Unit s
A. Fission & Activation Products Mn-54 Ci Co-58 Ci Co-60 Ci Zr-95 Ci Nb-95 Ci Sb-125 Ci Cs-134 Ci Cs-137 Ci Other y Emitters Ci Fe-55 Ci Ni-63 Ci Sr-89 Ci Sr-90 Ci Total Activity Ci B. Tritium 1.91 E-03 1.91 E-03 3.02E-04 3.02E-04 1.91 E-03 3.02E-04 2.21 E-03
! H-3 Ci 1.50E+02 6.81 E+01 I 6.26E+02 I 5.30E+02 1.37E+03 C. Dissolved & Entrained Gases I Gross Alpha D. Gross Alpha Ci denotes less than Minimum Detectable Activity (MDA) 41
2.3 Solid Waste Solid waste shipment summaries for each unit are given in the following tables:
Table 2.1-S MPSl Solid Waste and Irradiated Component Shipments Table 2.2-S MPS2 Solid Waste and Irradiated Component Shipments Table 2.3-S MPS3 Solid Waste and Irradiated Component Shipments The principal radionuclides in these tables were from shipping manifests.
Solidification Agent(s): No solidification on site Containers routinely used for radioactive waste shipment include:
55-gal Steel Drum DOT* 17-H container Steel Boxes Steel Container Steel "Sea Van" Polyethylene High Integrity Containers
- United States Department of Transportation 42 7.5 ft3 45 ft3 87 ft3 95 ft3 202. 1 ft3 1280 ft3 120.3 ft3 132.4 ft3 173.4 ft3 202. 1 ft3
Table 2.1-5 Solid Waste and Irradiated Component Shipments MPS1 January 1, 2017 through December 31, 2017 Resins, Filters, and Evaporator Bottoms Volume Curies Shipped Waste Class ft3 m3 Curies A
N/A N/A N/A B
N/A N/A N/A C
N/A N/A N/A ALL N/A N/A N/A Nuclides for the Above Table:
Radionuclide
% of Total Curies CURIES TOT AL 0
43
Table 2.1-S (continued)
Solid Waste and Irradiated Component Shipments MPS1 January 1, 2017 through December 31, 2017 Dry Active Waste Volume Curies Shipped Waste Class ft3 m3 Curies A
3.20E+02 9.05E+OO 2.73E-02 B
N/A N/A N/A C
N/A N/A N/A ALL 3.20E+02 9.05E+OO 2.73E-02 Nuclides for the Above Table:
Radionuclide
% of Total Curies C-14
< 0.01 %
1.06E-06 Fe-55 58.92%
1.61 E-02 Co-60 21.70%
5.93E-03 Ni-63 7.16%
1.96E-03 Sr-90 0.04%
1.1 OE-05 Cs-137 8.86%
2.42E-03 Pu-238
< 0.01 %
2.34E-07 Pu-239
< 0.01 %
2.15E-07 Pu-241 0.05%
1.44E-05 Am-241
< 0.01 %
8.10E-07 Cm-242
< 0.01 %
6.92E-09 Cm-244
< 0.01 %
3.51 E-07 CURIES (TOTAL) 2.73E-02 44
Table 2.1-5 (continued)
Solid Waste and Irradiated Component Shipments MPS1 January 1, 2017 through December 31, 2017 Irradiated Components Volume Curies Shipped Waste Class ft3 m3 Curies A
N/A N/A N/A B
N/A N/A N/A C
N/A N/A N/A ALL N/A N/A N/A Nuclides for the Above Table:
I Radionuclide I
% of Total Curies I
CURIES (TOT AL) 0 Other Waste Volume Curies Shipped Waste Class ft3 m3 Curies A
N/A N/A N/A B
N/A N/A N/A C
N/A N/A N/A ALL N/A N/A N/A Nuclides for the Above Table:
Radionuclide I
% of Total Curies CURIES (TOTAL) 0 45
Table 2.1-5 (continued)
Solid Waste and Irradiated Component Shipments MPS1 January 1, 2017 through December 31, 2017 Sum of All Low-Level Waste Shipped from Site Volume Curies Shipped Waste Class ft3 m3 Curies A
3.20E+02 9.05E+OO 2.73E-02 B
N/A N/A N/A C
N/A N/A N/A ALL 3.20E+02 9.05E+OO 2.73E-02 Nuclides for the Above Table:
Radionuclide
% of Total Curies C-14
< 0.01 %
1.06E-06 Fe-55 58.92%
1.61 E-02 Co-60 21.70%
5.93E-03 Ni-63 7.16%
1.96E-03 Sr-90 0.04%
1.10E-05 Cs-137 8.86%
2.42E-03 Pu-238
< 0.01 %
2.34E-07 Pu-239
< 0.01 %
2.15E-07 Pu-241 0.05%
1.44E-05 Am-241
< 0.01 %
8.10E-07 Cm-242
< 0.01%
6.92E-09 Cm-244
< 0.01 %
3.51 E-07 CURIES (TOTAL) 2.73E-02 46
Table 2.2-5 Solid Waste and Irradiated Component Shipments MPS2 January 1, 2017 through December 31, 201 7 Resins, Filters, and Evaporator Bottoms Volume Curies Shipped Waste Class ft3 m3 Curies A
8.87E+02 2.51 E+01 1.04E+01 B
NIA NIA NIA ALL 8.87E+02 2.51E+01 1.04E+01 Nuclides for the Above Table:
Radionuclide
% of Total Curies H-3 0.13%
1.41 E-02 C-14 2.41 %
2.51 E-01 Mn-54 10.70%
1.12E+OO Fe-55 28.58%
2.98E+OO Co-57 0.09%
9.36E-03 Co-58 0.73%
7.58E-02 Co-60 31.65%
3.30E+OO Ni-59 0.18%
1.92E-02 Ni-63 19.07%
1.99E+OO Sr-90 0.17%
1.78E-02 Tc-99 0.03%
3.26E-03 Ag-108m
< 0.01 %
1.92E-04 Aq-11 Om 0.43%
4.52E-02 Sn-113 0.32%
3.33E-02 Sb-125 3.70%
3.86E-01 Cs-137 1.11 %
1.16E-01 Ce-144
< 0.01 %
8.73E-05 Pu-238
< 0.01 %
2.24E-05 Pu-239
< 0.01 %
5.60E-06 Pu-241 0.02%
1.91 E-03 Am-241
< 0.01 %
1.02E-05 Cm-242
< 0.01 %
4.73E-06 Cm-244
< 0.01 %
1.23E-05 CURIES (TOTAL) 1.04E+01 47
Dry Active Waste Waste Class A
B C
ALL Table 2.2-S (continued)
Solid Waste and Irradiated Component Shipments MPS2 January 1, 2017 through December 31, 2017 Volume Curies Shipped ft3 mJ Curies 2.18E+04 6.16E+02 2.30E-01 NIA NIA NIA NIA NIA NIA 2.18E+04 6.16E+02 2.30E-01 Nuclides for the Above Table:
Radionuclide
% of Total Curies H-3 0.20%
4.67E-04 C-14 0.01 %
2.37E-05 Cr-51 3.43%
7.88E-03 Mn-54 0.96%
2.21 E-03 Fe-55 5.84%
1.34E-02 Co-57 0.03%
6.67E-05 Co-58 2.51 %
5.78E-03 Co-60 49.43%
1.14E-01 Ni-59 0.25%
5.64E-04 Ni-63 15.52%
3.57E-02 Sr-89
< 0.01 %
4.47E-06 Sr-90
< 0.01 %
8.59E-06 Zr-95 5.17%
1.19E-02 Nb-94 0.08%
1.78E-04 Nb-95 9.52%
2.19E-02 Tc-99 0.02%
5.15E-05 Aq-110m 1.06%
2.44E-03 Sn-113 0.34%
7.75E-04 Sb-125 3.95%
9.07E-03 Cs-137 0.66%
1.52E-03 Ce-144
< 0.01 %
8.34E-06 Pu-238
< 0.01 %
2.44E-06 Pu-239
< 0.01 %
2.06E-06 Pu-241 0.17%
3.84E-04 Am-241
< 0.01 %
1.04E-05 Cm-242
< 0.01 %
8.99E-07 Cm-244
< 0.01 %
3.86E-06 CURIES(TOTAL) 2.30E-01 48
Table 2.2-S (continued)
Solid Waste and Irradiated Component Shipments MPS2 January 1, 2017 through December 31, 2017 Irradiated Components Volume Curies Shipped Waste Class ft3 m3 Curies A
N/A N/A N/A B
N/A N/A N/A C
N/A N/A N/A ALL N/A N/A N/A Nuclides for the Above Table:
Radionuclide
% of Total Curies CURIES TOT AL 0
49
Other Waste Waste Class A
B C
ALL Table 2.2-S (continued)
Solid Waste and Irradiated Component Shipments MPS2 January 1, 2017 through December 31, 2017 Volume Curies Shipped ft3 mJ Curies 8.28E+02 2.34E+01 1.84E-02 N/A N/A N/A N/A N/A N/A 8.28E+02 2.34E+01 1.84E-02 Nuclides for the Above Table:
Radionuclide
% of Total Curies H-3 76.47%
1.41 E-02 C-14
< 0.01%
8.46E-09 Mn-54 0.01 %
2.63E-06 Fe-55 0.04%
6.86E-06 Co-57
< 0.01 %
1.93E-09 Co-58 0.14%
2.57E-05 Co-60 0.09%
1.69E-05 Ni-63 0.08%
1.39E-05 Zn-65
< 0.01 %
2.62E-09 Sr-89
< 0.01 %
4.61 E-08 Sr-90 3.13%
5.76E-04 Tc-99
< 0.01 %
7.81 E-07 Sb-125 0.05%
9.43E-06 Cs-137 19.94%
3.66E-03 Pu-238
< 0.01 %
1.83E-09 Pu-239
< 0.01 %
1.17E-09 Pu-241
< 0.01 %
4.55E-08 Am-241
< 0.01%
6.75E-09 Pu-240
< 0.01%
9.49E-10 Cm-242
< 0.01 %
1.14E-10 Cm-243
< 0.01 %
3.75E-09 Cm-244
< 0.01%
4.18E-09 CURIES (TOT AL) 1.84E-02 50
Table 2.2-S (continued)
Solid Waste and Irradiated Component Shipments MPS2 January 1, 2017 through December 31, 2017 Sum of All Low-Level Waste Shipped from Site Volume Curies Shipped Waste Class ft3 m3 Curies A
2.35E+04 6.65E+02 1.07E+01 B
N/A N/A N/A C
N/A N/A N/A ALL 2.35E+04 6.65E+02 1.07E+01 Nuclides for the Above Table:
Radionuclide
% of Total Curies H-3 0.27%
2.86E-02 C-14 2.35%
2.51 E-01 Cr-51 0.16%
1.68E-02 Mn-54 10.48%
1.12E+OO Fe-55 28.04%
2.99E+OO Co-57 0.09%
9.43E-03 Co-58 0.76%
8.16E-02 Co-60 31.97%
3.41 E+OO Ni-59 0.19%
1.98E-02 Ni-63 18.96%
2.03E+OO Zn-65 0.15%
1.55E-02 Sr-89 0.06%
6.13E-03 Sr-90 0.17%
1.83E-02 Zr-95 0.16%
1.70E-02 Nb-94
< 0.01 %
1.78E-04 Nb-95 0.31 %
3.26E-02 Tc-99 0.03%
3.31 E-03 Aq-108m
< 0.01 %
1.92E-04 Ag-11 Om 0.45%
4.77E-02 Sn-113 0.32%
3.41 E-02 Sb-125 3.70%
3.95E-01 Cs-137 1.13%
1.21 E-01 Ce-144
< 0.01 %
9.60E-05 Pu-238
< 0.01 %
2.48E-05 Pu-239
< 0.01 %
7.66E-06 Pu-241 0.02%
2.29E-03 Am-241
< 0.01%
2.06E-05 Pu-240
< 0.01%
9.49E-10 Cm-242
< 0.01 %
5.63E-06 Cm-243
< 0.01 %
3.75E-09 Cm-244
< 0.01 %
1.61 E-05 CURIES (TOTAL) 1.07E+01 51
Table 2.3-S Solid Waste and Irradiated Component Shipments MPS3 January 1, 2017 through December 31, 2017 Resins, Filters, and Evaporator Volume Curies Shipped Bottoms Waste Class ft" m"
Curies A
1.52E+02 4.31 E+OO 1.07E+01 B
N/A N/A N/A C
N/A N/A N/A ALL 1.52E+02 4.31 E+OO 1.07E+01 Nuclides for the Above Table:
Radionuclide
% of Total Curies H-3 1.06%
1.13E-01 C-14 1.96%
2.10E-01 Mn-54 0.83%
8.93E-02 Fe-55 3.24%
3.47E-01 Co-57 0.03%
3.16E-03 Co-58 0.23%
2.41 E-02 Co-60 2.61%
2.79E-01 Ni-59 0.43%
4.59E-02 Ni-63 37.91%
4.06E+OO Zn-65 0.01%
6.69E-04 Sr-90 0.01%
1.51 E-03 Nb-94
< 0.01%
1.94E-05 Tc-99 0.33%
3.57E-02 Ag-110m 0.02%
2.48E-03 Sb-125 50.45%
5.40E+OO Cs-134 0.10%
1.06E-02 Cs-137 0.78%
8.36E-02 Ce-144
< 0.01%
4.29E-06 Pu-238
< 0.01%
7.24E-06 Pu-239
< 0.01%
9.20E-08 Pu-241
< 0.01%
4.97E-04 Am-241
< 0.01%
1.75E-06 Cm-242
< 0.01%
3.06E-08 Cm-244
< 0.01%
5.04E-08 CURIES (TOTAL) 1.07E+01 52
Dry Active Waste Waste Class A
B C
ALL Table 2.3-S (continued)
Solid Waste and Irradiated Component Shipments MPS3 January 1, 2017 through December 31, 2017 Volume Curies Shipped ft3 m3 Curies 1.23E+04 3.49E+02 4.99E-01 NIA NIA NIA NIA NIA NIA 1.23E+04 3.49E+02 4.99E-01 Nuclides for the Above Table:
Radionuclide
% of Total Curies H-3 0.33%
1.62E-03 Cr-51 1.14%
5.67E-03 Mn-54 2.52%
1.26E-02 Fe-55 62.15%
3.1 OE-01 Fe-59 0.15%
7.24E-04 Co-57 0.06%
2.91 E-04 Co-58 2.58%
1.28E-02 Co-60 19.97%
9.96E-02 Ni-59 0.04%
2.23E-04 Ni-63 6.02%
3.00E-02 Sr-90
< 0.01 %
1.86E-05 Zr-95 1.20%
5.99E-03 Nb-94 0.03%
1.63E-04 Nb-95 2.19%
1.09E-02 Sn-113 0.06%
2.96E-04 Sb-125 0.58%
2.89E-03 Cs-137 0.95%
4.73E-03 Pu-241 0.04%
2.12E-04 Am-241
< 0.01 %
8.70E-07 Cm-242
< 0.01 %
2.31 E-07 Cm-244
< 0.01 %
6.85E-07 CURIES(TOTAL) 4.99E-01 53
Table 2.3-S (continued)
Solid Waste and Irradiated Component Shipments MPS3 January 1, 2017 through December 31, 2017 Irradiated Components Volume Curies Shipped Waste Class ft3 m3 Curies A
N/A N/A N/A B
N/A N/A N/A C
N/A N/A N/A ALL N/A N/A N/A Nuclides for the Above Table:
Radionuclide
% of Total Curies CURIES TOTAL) 0 54
Other Waste Table 2.3-5 (continued)
Solid Waste and Irradiated Component Shipments MPS3 January 1, 2017 through December 31, 2017 Volume Curies Shipped Waste Class ft3 m3 Curies A
4.50E+02 1.27E+01 8.91 E-03 B
NIA NIA NIA ALL 4.50E+02 1.27E+01 8.91E-03 Nuclides for the Above Table:
Radionuclide
% of Total Curies H-3 89.22%
7.95E-03 C-14
< 0.01 %
7.22E-09 Mn-54 0.02%
1.36E-06 Fe-55 0.03%
2.60E-06 Co-57
< 0.01 %
2.10E-09 Co-58 0.06%
5.64E-06 Co-60 0.06%
5.39E-06 Ni-63 0.04%
3.60E-06 Zn-65
< 0.01 %
2.85E-09 Sr-89
< 0.01 %
3.15E-08 Sr-90 1.42%
1.26E-04 Tc-99
< 0.01 %
3.47E-07 Sb-125 0.02%
2.07E-06 Cs-137 9.10%
8.11E-04 Pu-238
< 0.01 %
1.78E-09 Pu-239
< 0.01 %
1.11 E-09 Pu-241
< 0.01 %
1.48E-08 Am-241
< 0.01 %
6.47E-09 Pu-240
< 0.01 %
1.03E-09 Cm-242
< 0.01 %
3.73E-11 Cm-243
< 0.01 %
4.07E-09 Cm-244
< 0.01%
4.21 E-09 CURIES(TOTAL) 8.91E-03 55
Table 2.3-S (continued)
Solid Waste and Irradiated Component Shipments MPS3 January 1, 2017 through December 31, 2017 Sum of All Low-Level Waste Shipped from Site Volume Curies Shipped Waste Class ft3 m3 Curies A
1.29E+04 3.66E+02 1.12E+01 B
N/A N/A N/A C
N/A N/A N/A ALL 1.29E+04 3.66E+02 1.12E+01 Nuclides for the Above Table:
Radionuclide
% of Total Curies H-3 1.09%
1.23E-01 C-14 1.87%
2.1 OE-01 Cr-51 0.05%
5.67E-03 Mn-54 0.91 %
1.02E-01 Fe-55 5.86%
6.57E-01 Fe-59
< 0.01 %
7.24E-04 Co-57 0.03%
3.45E-03 Co-58 0.33%
3.69E-02 Co-60 3.38%
3.79E-01 Ni-59 0.41 %
4.62E-02 Ni-63 36.46%
4.09E+OO Zn-65
< 0.01 %
6.69E-04 Sr-89
< 0.01 %
3.61 E-08 Sr-90 0.01 %
1.66E-03 Zr-95 0.05%
5.99E-03 Nb-94
< 0.01 %
1.83E-04 Nb-95 0.10%
1.09E-02 Tc-99 0.32%
3.57E-02 Sn-113
< 0.01 %
2.96E-04 Sb-125 48.19%
5.41 E+OO Cs-137 0.79%
8.91 E-02 Pu-238
< 0.01 %
7.39E-06 Pu-239
< 0.01 %
2.33E-07 Pu-241
< 0.01 %
7.10E-04 Am-241
< 0.01%
2.62E-06 Pu-240
< 0.01 %
1.03E-09 Cm-242
< 0.01 %
2.61 E-07 Cm-243
< 0.01 %
4.07E-09 Cm-244
< 0.01 %
7.39E-07 CURIES(TOTAL) 1.12E+01 56
2.4 Groundwater Monitoring With the Groundwater Protection Program (GWPP) MPS implements the actions cited in the Nuclear Energy's Institute's (NEI) Groundwater Protection Initiative (Reference 9). The purpose of the GWPP is to establish a program to assure timely and effective management of situations involving potential releases of radioactive material to groundwater. A key element in the GWPP is on-site groundwater monitoring. The results of the GWPP are documented in tables below.
Another key element in the GWPP is site hydrological characterization. The general trend of groundwater flow at the station is toward the Long Island Sound. The underdrain system effectively captures groundwater in the area around MPS3 and channels this water via the storm drain system to Long Island Sound.
Table 2.4-GW (p. 1 of 3) e amp e esu s W ll S I R It H-31,2 Name Date (pCi/L)
Name MW-7C5 1/27/2017 4150 MW-7Dj 2/23/2017 7430
( cont.)
3/21/2017 4420 4/3/2017 2660 5/3/2017 3880 6/12/2017 4470 9/25/2017 4950 10/27/2017
<MDA 11/8/2017 4530 11/20/2017 3240 12/6/2017
<MDA MW-7D3 1/11/2017 8760 1/13/2017 9960 1/27/2017 8180 2/6/2017 7910 2/22/2017 6900 3/6/2017 5200 3/20/2017 4480 4/3/2017 4110 4/17/2017 2640 5/3/2017 2690 5/8/2017 2230 5/18/2017 2290 Notes: 1 -
There was no gamma radioactivity detected in these samples.
2 -
MDA is approximately 1,760 pCi/L.
H-31,i Date (pCi/L) 6/12/2017 4230 6/13/2017 3010 6/26/2017 3590 7/5/2017 4860 7/25/2017 4680 8/9/2017 6450 8/21/2017 5150 9/5/2017 7190 9/6/2017 7830 9/11/2017 7750 9/18/2017 7520 9/25/2017 8130 10/2/2017 6980 10/1 0/2017 9120 I 0/18/2017 8240 10/26/2017 6720 10/31/2017 5020 11/3/2017 4550 11/7/2017 3350 11/14/2017 3900 11/20/2017 7220 11/27/2017 5570 12/5/2017 6160 3 -
These wells are located near the MPS3 RWST which is downwind direction from the MPS3 Ventilation Vent. All or some of the H-3 detected in these wells is from releases out of the RWST vent and Ventilation Vent. Gaseous releases from the Ventilation Vent are reported in Table 2.3-A? and from the RWST vent in Table 2.3-A3. Any releases from RWST vent or Ventilation Vent which reach the groundwater are captured in sumps and underground vaults, and periodically monitored before release to the environment and reported in Table 2.3-L2. There has been no hydraulic communication with offsite groundwater.
57
Table 2.4-GW (p. 2 of 3) e amp e esu s W ll S I R It H-31,2 Name Date (pCi/L)
Name DP-102j 1/4/2017 2400 MW-GPI-08 4/11/2017 2960 8/10/2017 dry 9/5/2017 dry 11/28/2017 4130 MW-GPI-09q ME-2 7/19/2017
<MDA ME-5 7/26/2017
<MDA MW-6A 3/9/2017
<MDA 5/4/2017
<MDA 8/28/2017
<MDA 11/15/2017
<MDA MW-6B 3/8/2017
<MDA 5/4/2017
<MDA 8/25/2017
<MDA 11/15/2017
<MDA MW-GPI-02 2/2/2017
<MDA 5/10/2017
<MDA 7/17/2017
<MDA 12/1 1/2017
<MDA MW-GPI-03 7/26/2017
<MDA MW-GPI-04 4/27/2017
<MDA MW-GPI-06 1/4/2017
<MDA 4/13/2017
<MDA 8/10/2017 dry 9/5/2017 dry 11/28/2017
<MDA Notes: 1 -
There was no gamma radioactivity detected in these samples.
2 -
MDA is approximately l,760 pCi/L.
H-31,2 Date (pCi/L) 1/25/2017
<MDA 5/23/2017
<MDA 7/25/2017
<MDA 12/11/2017
<MDA 1/1 1/2017 2600 1/25/2017 4200 2/6/2017 3670 2/22/2017 3490 3/6/2017 4270 3/20/2017 2520 4/5/2017
<MDA 4/17/2017 2510 5/2/2017 2950 5/23/2017 2980 6/12/2017
<MDA 6/26/2017 2600 7/17/2017 2390 8/9/2017
<MDA 9/5/2017
<MDA 9/18/2017 2070 10/2/2017
<MDA 10/27/2017 2440 11/7/2017
<MDA 11/10/2017
<MDA 11/14/2017
<MDA 11/20/2017
<MDA 11/27/2017 2330 12/5/2017
<MDA 3 -
These wells are located near the MPS3 RWST which is downwind direction from the MPS3 Ventilation Vent. All or some of the H-3 detected in these wells is from releases out of the RWST vent and Ventilation Vent. Gaseous releases from the Ventilation Vent are reported in Table 2.3-A 7 and from the R WST vent in Table 2.3-A3. Any releases from R WST vent or Ventilation Vent which reach the groundwater are captured in sumps and underground vaults, and periodically monitored before release to the environment and reported in Table 2.3-L2. There has been no hydraulic communication with offsite groundwater.
4-Some results from MW-GPI-09 are positive. The source of tritium appears to be from the tritium being released via underground discharge tunnels. This tritium has been documented and the releases reported in another part of this report. No other leakage source has been identified.
58
Name Date MW-GPI-10 2/2/2017 5/8/2017 8/11/2017 10/10/2017 MW-GPI-1 1 1/13/2017 4/10/2017 7/31/2017 11/17/2017 Sl 1-MW-l 2/23/2017 1/30/2017 5/16/2017 8/14/2017 12/7/2017 Table 2.4-GW (p. 3 of 3)
Well Sample Results H-31,2 (pCi/L)
Name Date
<MDA Sl 2-MW-3 1/12/2017
<MDA 5/10/2017
<MDA 8/14/2017
<MDA 11/20/2017
<MDA Sl3-MW-l 2/8/2017
<MDA Sl-MW-1 1/19/2017
<MDA S3-MW-2 2/8/2017
<MDA T l 0-MW-5E 1/17/2017
<MDA T l 0-MW-6A 3/8/2017
<MDA Tl0-MW-6B 6/20/2017
<MDA Tl-MW-3 1/19/2017
<MDA
<MDA Notes: 1 -
There was no gamma radioactivity from licensed radioactive material detected in these samples.
2 -
MDA is approximately 1,760 pCi/L.
3.0 NONFUNCTIONAL Effluent Monitors H-31,2 (pCi/L)
<MDA
<MDA
<MDA
<MDA
<MDA
<MDA
<MDA
<MDA
<MDA
<MDA
<MDA During the period January 1 through December 31, 2017, the following effluent instrumentation were NONFUNCTIONAL for more than 30 consecutive days:
3.1.
MPS1 - None 3.2.
MPS2 - None 3.3.
MPS3 -
3HVR-19B - On 03/20/2017 3HVR19B, SLCRS Gas Low Range flow transmitter failed SP 3449B32, Supplemental Leak Collection and Release Operational Test and Calibration, surveillance.
Operations declared the radiation monitoring Non Functional based on the flow transmitter failing the surveillance.
As a result, condition report CR 1062683, HVR *FTl 9 unresponsive to M&TE mid-scale input signals and troubleshooting work order 53103060450 were initiated. The Maintenance Rule Functional Failure evaluation concluded that process flow indication is not required to support the gas channel indication. The troubleshooting work order required removal of the flow transmitter's circuit board, so that the vendor, FCI could repair the board. The time to develop a troubleshooting 59
work order coupled with the reliance on vendor repairs caused the 3HVR19B to be Non Functional for greater than 30 days.
The flow transmitter retested successfully on 05/11/2017 and Functionality was restored to HVR19B. All compensatory samples were taken once every seven days while the HVR19B was declared Non Functional.
4.0 Operating History The operating history of the MPS Units during this reporting period was as follows:
MPSl was shut down November 11, 1995 with a cessation of operation declared in July 1998.
MPS2 operated with a capacity factor of 89%
MPS3 operated with a capacity factor of91.7%
The power histograms for 2017 are on the following pages.
60
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MP3 - CYCLE 18/19 POWER HISTORY YEAR 2017 Note: Data at 3 Hour Interval
- 1. DOWN POWER TO 94% (1/29/17) TO FACILITATE TURBINE VALVE TESTING
- 2. DOWN POWER TO 93% (03/09/17) TO PERFORM LIFT ADJUSTMENT ON 'B' HDL PUMP
- 3. DOWN POWER TO 93% (03/20/17) FOR 'A' DSM REPAIRS
. DOWN POWER TO 88% (04/25/17) FOR ISOLATION OF "1A" FWH DUE TO STEAM LEAK
- 5. DOWN POWER TO 68% (05/15/17) FOR UNPLANNED OFF-SITE LINE OUTAGE AND TURBINE VALVE TESTING
- 6. DOWN POWER TO 93% (08/03/17) FOR TURBINE VALVE TESTING & 3HDL-LV21B1 REPAIR t--
t--
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5.0 ERRATA Not Applicable 6.0 REMODCM Changes The description and the bases of the change(s) for REMODCM Revision 29 (effective April 4, 2017) are included here in Volume II of the Radioactive Effluent Release Report. In addition, a complete copy of the REMODCM revision is provided to the Nuclear Regulatory Commission as Volume 2 of the R d" Effl R 1 R
a 10active uent e ease eport.
REMODCM Summary of Changes in Revision 29 Pg.I ILE changed from "MPS 1 Liquid Discharge" to "Liquid Discharge Flow Rates and Monitoring Setpoints" Table I.C.-1 Pg.8 MPS unit Radioactive Liquid Waste Sampling and Analysis Program Added Footnote C to obtain grab samples for alpha, Fe-55, and Sr-90.
Table I.C-2 Pg.12 MPS2 Radioactive Liquid Waste Sam p 1 in g and Analysis Program.
Added condensate as an alternate sample for steam generator m Footnotes H&I.
I.C-2 Liquid Radioactive Waste Treatment Pg.18 I) Added ALPS/AIM Processing to MPS2 processing equipment.
- 2) In MPS2 clean liquid waste processing equipment deleted "Aerated Liquid" which was with secondary or equivalent demineralizer.
Figure I.C.-2 Simplified Liquid Effluent Flow Diagram MPS2 Pg.21 Added ALPS processing Table I.D-1 MPS l Radioactive Gaseous Waste Sampling and Analysis Programs Pages 23-24
- 1)
Added new Footnote F to require monthly gas sample from BOP Vent when SFPI ventilation is shut down and ventilation of SFPI is exhausted to BOP vent.
- 2)
Added new Footnote G to allow an alternative to tritium analysis of vent sample.
Table I.D-1 MPS3 Radioactive Gaseous Waste Sampling and Analysis Program Pg.28
- 1)
In MPS3 table (I.D-3), deleted fuel building releases.
- 2)
In Footnote F of Table l.D-3 changed numbered conditions from 3 and 4 to and 2, respectively.
Table I.E-4 Maximum Values for Lower Limit of Detection (LLD)
Pg. 44 Continued...
I) Made food products LLDs applicable to vegetation LLD.
Added a LLD of 0.093 pCi/g for fish and shellfish for 1-131 analyses.
II.A Section II -Offsite Dose Calculation Manual (ODCM) - Introduction Deleted Pg. 51 5th and 6th paragraphs.
II.D.I Gaseous Dose Calculation -Site Release Rate Limit Pg. 55
("Instantaneous") revised wording in first paragraph as shown in attached markup.
Table 111.C-3 MPS 1 Radioactive Gaseous Effluent Monitoring Instrumentation Pg. 89 l) Changed 2°d Footnote 1 to Footnote 2.
- 2)
In ACTION B changed time requirement for analysis of filter collection from 24hrs to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
- 3)
In ACTION B added the word "duration" to "24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> sample' to clarify length of sample versus time of sample.
63
Table IV. C-1 &
MPS2 & MPS3 Radioactive liquid Effluent Monitoring Instrumentation V.C-1 Change required functionality of steam generator blowdown radiation Pages 104,122 monitors from Modes 1-4 to whenever the pathway is in use.
111.D, IV.D, V.D Radioactive Effluents Concentration and Dose Limitations Pages. 91,111,
In Surveillance Requirement changed reference to "Section 11" to "Section 131 ILE."
7.0 References
- 1.
NUREG-0597, User Guide to GASP AR Code, KF Eckerman, FJ Congel, AK Roecklien, WJ Pasciak, Division of Site Safety and Environmental Analysis, Office of Nuclear Reactor Regulation, US Nuclear Regulatory Commission, Washington, DC 20555, manuscript completed January 1980, published June 1980.
- 2.
EPRI Report 1021106, Estimation of Carbon-14 m Nuclear Power Plants Gaseous Effluents, December, 2010.
- 3.
NRC Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977.
- 4.
UNSCEAR 2000 Report Vol. I, Sources and Effects of Ionizing Radiation, United Nations Scientific Committee on the Effects of Atomic Radiation
- 5.
NRC Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Revision 1, July 1977.
- 6.
NUREG/CR-1276, ORNL/NUREG/TDMC-1, User's Manual for LADT AP II - A Computer Program for Calculating Radiation Exposure to Man from Routine Release of Nuclear Reactor Liquid Effluents, DB Simpson, BL McGill, prepared by Oak Ridge National Laboratory, Oak Ridge, TN 37830, for Office of Administration, US Nuclear Regulatory Commission, manuscript completed 17 March 1980.
- 7.
10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, Appendix I, Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion "As Low As Reasonably Achievable" for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents.
- 8.
40 CFR Part 190, Environmental Radiation Protection Standard for Nuclear Power Operation.
- 9.
NEI 07-07, Nuclear Energy Institute, Industry Ground Water Protection Initiative - Final Guidance Document, August 2007.
- 10. NRC Regulatory Guide 1.21, Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste, Revision 2, October 2008.
- 12. NUREG/CR-2907, Vol. 15, Radioactive Effluents from Nuclear Power Plants Annual Report 2009, R.
Conatser, US Nuclear Regulatory Commission and N. Daugherty, Oak Ridge Associated Universities, Aug., 2013.
- 13. Radiation Protection Calculation #16-18, "Isotopic Cloud Shine Doses For MPS Releases," Jan. 24, 2017.
- 14. MP-CHEM-17-07, "Reporting of Radioactivity Released from RWST Vents," May 26, 2016.
64
Dominion Energy Nuclear Connecticut, Inc.
Rt 1¢6, Rope Ferry Road, Waterford, CT 06385 J Dominion Energy.com U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 MAY O 1 2018 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNITS 1, 2, AND 3 Serial No.
MPS Lic/GJC Docket Nos.
License Nos.
2017 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 18-176 RO 50-245 50-336 50-423 DPR-21 DPR-65 NPF-49 In accordance with 10 CFR 50.36a, this letter transmits the annual Radioactive Effluent Release Report (RERR) for the period January 2017 through December 2017. This report meets the provisions of Section 5. 7.3 of the Millstone Power Station Unit 1 Permanently Defueled Technical Specifications (POTS), and Sections 6.9.1.6b and 6.9.1.4 of the Millstone Power Station Units 2 and 3 Technical Specifications, respectively. transmits Volume 1 of the 2014 RERR, in accordance with Regulatory Guide 1.21. The RERR contains information regarding airborne, liquid, and solid radioactivity released from Millstone Power Station, including the off-site dose from airborne and liquid effluents. transmits Volume 2 of the report, which consists of a complete copy of the Radiological Effluent Monitoring and Off-Site Dose Calculation Manual (REMODCM) as of December 31, 2017. This satisfies the requirements of Sections 5.6.1 c of the Millstone Power Station Unit 1 POTS, and Sections 6.15c and 6.9.13c of the Millstone Power Station Units 2 and 3 Technical Specifications, respectively.
If you have any questions or require additional information, please contact Mr. Jeffry A. Langan at (860) 444-5544.
Sincerely, M. J. O'Connor Director, Nuclear Station Safety and Licensing
Attachments:
2 Commitments made in this letter:
- 1. None.
cc:
U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 S. J. Giebel Serial No.18-176 2017 Radioactive Effluent Release Report Page 2 of 4 NRC Project Manager Millstone Unit 1 U.S. Nuclear Regulatory Commission Two White Flint North, Mail Stop T-8 F5 11545 Rockville Pike Rockville, MD 20852-2738 L. A. Kauffman NRC Inspector U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 H. W Anagnostopoulos NRC Inspector U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 R. V. Guzman NRC Project Manager Millstone Units 2 and 3 U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 C2 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Director Bureau of Air Management Monitoring & Radiation Division Department of Energy and Environmental Protection 79 Elm Street Hartford, CT 06106-5127
A. Honnellio Regional Radiation Representative (EPA Region 1, Boston)
Serial No.18-176 2017 Radioactive Effluent Release Report Page 3 of 4 U. S. Environmental Protection Agency (Region 1) 5 Post Office Square Suite 100 Boston, MA 02109 G. Allen Jr.
Department of Health and Human Services U. S. Food and Drug Administration 140 Shrewsbury Street, Suite 1 Boylston, MA 01501 Mr. Robert Stein Chairman Connecticut Siting Council 10 Franklin Square New Britain, CT 06051 J.P. Kelley Waterford-East Lyme Shellfish Commission Waterford Town Hall Waterford, CT 06385 J. Foikwein American Nuclear Insurers 95 Glastonbury Blvd.
Glastonbury, CT 06033 D. Carey Connecticut Department of Agriculture Aquaculture Division P. 0. Box 97 Millford, CT 06460 Mr. Dan Steward First Selectman Town of Waterford Waterford Town Hall Waterford, CT 06385 M. C. Nickerson First Selectman Town of East Lyme PO Box 519 Niantic, CT 06357
University Of Connecticut Library Serials Department Storrs, CT 06268 Serial No.18-176 2017 Radioactive Effluent Release Report Page 4 of 4
ATTACHMENT 1 Serial No.18-176 Docket Nos. 50-245 50-336 50-423 License Nos. DPR-21 DPR-65 NPF-49 2017 RADIOACTIVE EFFLUENTS RELEASE REPORT VOLUME 1 MILLSTONE POWER STATION UNITS 1, 2, AND 3 DOMINION ENERGY NUCLEAR CONNECTICUT, INC. (DENC)
Millstone Power Station 2017 Radioactive Effluents Release Report Volume One Gaseous Effluents Dominion Energy Nuclear Connecticut, Inc.
Unit 1
2 3
License DPR-21 DPR-65 NPF-49 Docket 50-245 50-336 50-423 i l, EDominion
- iiiiiil' nergy
Contents List ofTables................................................................................................................................................................... 2 List of Acronyms............................................................................................................................................................. 3 Introduction..................................................................................................................................................................... 4 1.0 Off-Site Doses.......................................................................................................................................................... 4 1.1 Dose Calculations............................................................................................................................................. 4 1.1. I Gaseous Effluents................................................................................................................................... 5 1.1.2 Liquid Effluents...................................................................................................................................... 6 1.2 Dose Results...................................................................................................................................................... 6 1.2.1 Gaseous Effluents................................................................................................................................... 6 1.2.2 Liquid Effluents...................................................................................................................................... 6 1.2.3 Analysis of Results................................................................................................................................. 6 1.3 Other Sources of Radiation Dose to the Public (from Ref. 12)....................................................................... 11 2.0 Effluent Radioactivity............................................................................................................................................ 13
- 2. 1 Gaseous Effluents........................................................................................................................................... 13 2.1. 1 Measurement of Radioactivity in Gaseous Effluents........................................................................... 13 2.1.2 Estimate ofErrors................................................................................................................................. 14 2.1.3 Gaseous Batch Release Statistics......................................................................................................... 15 2.1.4 Abnormal Gaseous Releases................................................................................................................ 15 2.1.5 Gaseous Release Tables....................................................................................................................... 15 2.2 Liquid Effluents.............................................................................................................................................. 32 2.2. 1 Measurement of Radioactivity in Liquid Effluents.............................................................................. 32 2.2.1.1 Continuous Liquid Releases................................................................................................... 32 2.2.1.2 Batch Liquid Releases from Tanks and Sumps...................................................................... 32 2.2.2 Estimate of Errors................................................................................................................................. 33 2.2.3 Liquid Batch Release Statistics............................................................................................................ 33 2.2.4 Abnormal Liquid Releases................................................................................................................... 33 2.2.5 Liquid Release Tables.......................................................................................................................... 33 2.3 Solid Waste..................................................................................................................................................... 42 2.4 Groundwater Monitoring................................................................................................................................ 57 3.0 NONFUNCTIONAL Effluent Monitors................................................................................................................ 59
- 4. 0 Operating History................................................................................................................................................... 60 5.0 ERRATA................................................................................................................................................................ 63 6.0 REMO DCM Changes............................................................................................................................................ 63 7.0 References.............................................................................................................................................................. 64 1
List of Tables Table 1-1 2017 Off-Site Dose Commitments from Gaseous Effluents MPS - Units 1, 2, 3.................................................... 8 Table 1-2 2017 Off-Site Commitments from Liquid Effluents MPS - Units 1, 2, 3................................................................. 9 Table1-3 2017 Off-Site Dose Comparison to Limits MPS - Units 1, 2, 3.............................................................................. 10 Table 1-4 2017 Off-Site Dose Comparison Natural Background vs MPS Table 2.1-A1 MPSl Gaseous Effluents Release Summary......................................................................................................... 16 Table 2.1-A2 MPSl Gaseous Effluents - Continuous Ground - BOP Vent & SFPI Vent............................................................. 17 Table 2.1-L 1 MPSl Liquid Effluents - Release Summary.......................................................................................................... 34 Table 2.1-L2 MPSl Liq uid Effluents - Batch - Liquid Waste Processing.................................................................................. 35 Table 2.1-S MPSl Solid Waste & Irradiated Component Shipments...................................................................................... 43 Table 2.2-A1 MPS2 Gaseous Effluents - Release Summary...................................................................................................... 18 Table 2.2-A2 MPS 2 Gaseous Effluents - Ground Batch............................................................................................................ 19 Table 2.2-A3 M PS2 Gaseous Effluents - Ground Continuous - RWST Vent, Equipment Hatch............................................... 20 Table 2.2-A4 MPS2 Gaseous Effluents - Elevated Batch - MPS Stack...................................................................................... 21 Table 2.2-A5 MPS2 Gaseous Effluents - Elevated Continuous - MPS Stack............................................................................ 22 Table 2.2-A6 MPS2 Gaseous Effluents - Mixed Batch - MPS2 Main Exhaust Vent.................................................................. 23 Table 2.2-A7 MPS2 Gaseous Effluents - Mixed Continuous - MPS2 M ain Exhaust Vent........................................................ 24 Table 2.2-L 1 MPS2 Liquid Effluents - Release Summary.......................................................................................................... 36 Table 2.2-L2 MPS2 Liquid Effluents - Continuous - SGBD, SW, RBCCW, TB Sumps, Tendon Gallery....................................... 37 Table 2.2-L3 MPS2 Liquid Effluents - Batch - Liquid Radwaste System.................................................................................... 38 Table 2.2-S MPS2 Solid Waste & Irradiated Component Shipments...................................................................................... 47 Table 2.3-A1 MPS3 Gaseous Effluents - Release Summary...................................................................................................... 25 Table 2.3-A2 MPS3 Gaseous Effluents - Ground Batch - ESF Building Rooftop....................................................................... 26 Table 2.3-A3 Gaseous Effluents - Ground Continuous - ESF Building Vent, CTMT Equipment Hatch, RWST Vent, ABD TK-2 Vent...................................................................................................................................................................... 27 Table 2.3-A4 MPS3 Gaseous Effluents - Elevated Batch - MPS Stack....................................................................................... 28 Table 2.3-A5 MPS3 Gaseous Effluents - Elevated Continuous - MPS Stack............................................................................. 29 Table 2.3-A6 MPS3 Gaseous Effluents - Mixed Batch - MPS3 Ventilation Vent....................................................................... 30 2
Table 2.3-A7 MPS3 Gaseous Effl uents - Mixed Continuous - M PS3 Ventilation Vent............................................................. 31 Table 2.3-L 1 MPS3 Liquid Effluents - Release Summary.......................................................................................................... 39 Table 2.3-L2 MPS3 Liquid Effluents - Continuous - SGBD, SW, TB Sumps, SRW Sump 3, ABO TK-2......................................... 40 Table 2.3-L3 MPS3 Liquid Effluents - Batch - Liquid Radwaste System, CPF su mps, Hotwell, SG bu lk, wn Berm................. 41 Table 2.3-S MPS3 Solid Waste & Irradiated Component Shipments...................................................................................... 52 Table 2.4-GW Well Sample Results............................................................................................................................................. 57 List of Acronyms ABD-TK-2 Auxiliary Boiler Drains Tank 2 BOP - Balance of plant CFR - Code of Federal Regulations CPF - Condensate polishing facility DENC - Dominion Energy Nuclear Conncticut DOT - Department of Transportation DSN - Discharge serial number EBFS - Enclosure building filtration system EDAN-Environmental Data Acquisition Network ESF - Engineering safeguards facility GI - Gastrointestinal GWPP - Groundwater protection program HPGe - High purity germanium ISFSI - Independent spent fuel storage installation MPS - Millstone Power Station MPSl - Millstone Power Station Unit 1 MPS2 - Millstone Power Station Unit 2 MPS3 - Millstone Power Station Unit 3 MDA - Minimum Detectable Activity NCRP-National Council on Radiation Protection and Measurements NEI-Nuclear Energy Institute NPP - Nuclear power plant NRC - Nuclear Regulatory Commission RBCCW - Reactor building closed cooling water REMODCM - Radiological Effluent Monitoring and Offsite Dose Calculation Manual R WST - Reactor water storage tank SFPI - Spent Fuel Pool Island SG - Steam generator SGBD - Steam generator blowdown SLCRS - Secondary Leakage Collection and Recovery System SW - Service water TB - Turbine building WGDT - Waste gas decay tank WRGM - Wide range gas monitor WTT - Waste test tank 3
Introduction This report, for the period of January through December of 2017, is being submitted by DENC, Inc. for MPS 1, 2, and 3, in accordance with 10 CFR 50.36a, the Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM), the MPS! Permanently Defueled Technical Specifications, and the MPS2 and 3 Technical Specifications. This report contains radiological and volumetric information on gaseous and liquid effluents, doses to the public from these effluents, shipments of solid waste & irradiated components, onsite well water results, information on effluent instrumentation which was nonfunctional for more than 30 consecutive days and operating history.
Radioactive materials may be disposed of in solid waste shipments sent to licensed disposal sites or released in liquid or gas form in effluents to the local environment. The two basic characteristics used to describe radioactive effluents are radioactivity and radiation dose. The radioactivity of any given radionuclide increases in direct proportion to the amount of the radionuclide present. This report lists the amounts of various radionuclides present in radioactive effluents. For this report, activity can be thought of as the amount of radioactive material present in radioactive effluents. Section 2.0 of this report gives the activity released from MPS in 2017.
Although radioactivity is an important, inherent characteristic that helps to describe radioactive effluents, it is not-by itself-a good indicator of the potential health effects from exposure to radiation. Health effects are dependent on many factors, such as the radionuclide, the type ofradiation emitted by the radionuclide, the energy of the radiation, the uptake of the radionuclide into the human body, and the metabolism of the radionuclide by the human body. To properly describe the potential health effects from exposure to radioactive materials, a measure that accounts for all of these differences is needed. Dose is a measure of how much radiation energy is absorbed by organs or tissues of the body. Dose is a good indicator of the potential health effects from exposure to radiation. Section 1.0 of this report gives the dose from activity released from MPS in 2017.
1.0 Off-Site Doses This report provides a summary of the 2017 off-site radiation doses from releases of radioactive materials in gaseous and liquid effluents and from direct radiation from MPS 1, 2 and 3. This includes the annual maximum dose in millirem (mrem) to any real member of the public as well the maximum gamma and beta air doses. To provide perspective, these doses are compared to the regulatory limits (in Table 1-3) and to the annual average dose that a member of the public could receive from natural background and other sources (in Table 1-4). The doses from radioactive effluents were much less than the doses from other sources of natural radiation that are commonly considered safe. This indicates radioactive effluents from MPS in 2017 had no significant impact on the health and safety of the public or the environment.
1.1 Dose Calculations Dose from radioactive effluents are calculated to ensure compliance with NRC requirements in 10 CFR Part 50, Appendix I (Ref. 7). The dose calculations are based on the measurements and computer models listed below:
- measurements of the radioactive materials released to the environment,
- models of how radionuclides are dispersed and diluted in the environment,
- models of how radionuclides are incorporated into animals, plants, and soil, and
- models of the biokinetic of human uptake and metabolism of radioactive materials.
The models are designed to calculate the dose to a real ( or hypothetical) individual closest to MPS or to an individual who may be exposed to the highest concentrations of radioactive materials from radioactive effluents. This person is often referred to as the maximum exposed individual. The parameters and assumptions used in these dose calculations include conservative assumptions that tend to overestimate the calculated exposures. Although the location of the maximum individual may vary each quarterly period, the annual dose is the sum of these quarterly doses. This conservatively assumes that the individual is at the location of maximum dose each quarter. As a result, the actual doses received by real individuals are often much less than those calculated.
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The off-site dose to humans from radioactive material in liquid and gaseous effiuents have been calculated using measured radioactive effiuent data and the dose computation algorithm in OpenEMS, an effluent tracking program (Ref. 9). For liquid dose OpenEMS uses equations which yield the same result as the methodology given in NRC Regulatory Guide 1.109 (Ref. 3). For airborne dose OpenEMS uses an algorithm equivalent to the NRC code, GASP AR II (Ref. 1), which uses a semi-infinite cloud model to implement the NRC Regulatory Guide 1.109 (Ref. 3) dose models. The values of average relative effluent concentration (X/Q) and average relative deposition (D/Q) used in OpenEMS were generated using EDAN, a meteorological computer code.
The annual summary of hourly meteorological data (in 15-minute increments), which includes wind speed, direction, atmospheric stability, and joint frequency distribution, is not provided in the report but are available.
Doses are based upon exposure to radioactivity in gaseous and liquid effluents over a one-year period and an associated dose commitment over a 50-year period from initial exposure. The portion of the doses due to inhalation and ingestion take into account radioactive decay and biological elimination of the radioactive materials.
The dose calculations are based upon three types of input: radioactive source term, site-specific data, and generic factors. The radioactive source terms (Curies) are given in Section 2, Effiuent Radioactivity, of this report. The site-specific data includes: meteorological data ( e.g. wind speed, wind direction, atmospheric stability) to calculate the transport and dispersion of gaseous effluents, average annual milk consumption rates and dilution factors for liquid effluents. The generic factors include the average annual consumption rates (for ingestion of vegetables, produce, meat, fish, and shellfish), shielding factor for air submersion and ground irradiation and occupancy factors for shoreline activity, swimming and boating.
1.1.1 Gaseous Effluents The following release points are considered ground level:
MPSl SFPI Vent (73 foot)
MPSl BOP Vent (80 foot)
MPS2 and 3 Refueling Water Storage Tank (RWST) Vents MPS3 Engineered Safety Features Building (ESF) Ventilation Auxiliary Boiler Drains Tank 2 (ABD TK-2) Vent MPS2 & 3 Containment Equipment Hatch MPS3 Containment Drawdowns Doses for releases from these points were calculated using the 33 foot meteorology. For each unit, doses from their respective release points were summed to determine the total unit gaseous effiuent ground level dose.
The following release points are considered mixed mode (partially elevated and partially ground) releases:
MPS2 Auxiliary Building Ventilation (159 foot elevation)
MPS3 Auxiliary Building Ventilation (133 foot elevation)
The doses for mixed mode releases are calculated using 142 foot meteorology for which the Pasquill stability classes are determined based upon the temperature gradient between the 33 foot and 142 foot meteorological tower levels.
The MPS Stack release point at 374 foot elevation is considered an elevated release. Doses for elevated releases are calculated using Pasquill stability classes determined based upon the temperature gradient between the 33 foot and 374 foot meteorological tower levels. Only MPS2 and MPS3 discharge to the MPS Stack. In March 2001, MPS 1 was separated from the stack and two new release points were added to MPS 1, the Spent Fuel Pool Island (SFPI) Vent and the Balance of Plant (BOP) Vent. The following are sources of radioactivity for releases from the stack:
MPS2 Waste Gas Decay Tanks batch releases MPS2 Containment Vents batch releases MPS2 Containment Purge batch releases (only during outage in the second quarter)
MPS3 Containment Vents batch releases MPS3 Gaseous Waste System continuous releases MPS3 Containment Purge batch releases (only during outage in fourth quarter) 5
1.1.2 Liquid Effluents MPS discharges radioactivity in water through two release pathways - thru the MPS Quarry to the Long Island Sound and thru Discharge Point DSN-006 to Niantic Bay. Discharges to the MPS Quarry are from primary side water, primarily from liquid waste processing systems. Discharges to DSN-006 are from secondary side water, primarily turbine building sumps. MPSl discharges only to the MPS Quarry from sumps and leakage collection systems. Discharges to both release pathways are considered either continuous or batch discharges.
Sources of continuous and batch discharges are listed in Sections 2.2.1.1 and 2.2.1.2. Water containing radioactivity being discharged to the MPS Quarry is diluted mainly by circulating water and, to a minor extent, by service water. Water containing radioactivity being discharged to DSN-006 is diluted by storm drains runoff.
1.2 Dose Results The calculated maximum off-site doses are presented in Table 1-1 for gaseous effluents and Table 1-2 for liquid effluents. The units 'mrad' and 'mrem' used in this report are units of radiation dose. The letter 'm' is for 'milli', or one-thousandth ofa 'rad' or a 'rem.' The word 'rad' is an acronym for radiation absorbed dose. One rad is equal to the absorption of 100 ergs of energy per gram of tissue. The word 'rem' is an acronym for roentgen equivalent man. One rem is equal to a rad multiplied by factors to account for type of radiation and distribution within the body.
1.2.1 Gaseous Effluents For the dose to the maximum individual, OpenEMS calculates the dose to the whole body, gastrointestinal (GI), bone, liver, kidney, thyroid, lung, and skin from each of the following pathways: direct exposure from submersion in noble gases in the plume, direct exposure from ground deposition of radioactivity, inhalation, and ingestion of vegetation, produce, cow or goat milk, and meat. A cloud shine dose component for releases of noble gas radioactivity from the elevated MPS Stack is calculated using Reference 13. This cloud shine pathway accounts for dose to the maximum individual from the plume at the site boundary while the plume is still elevated. The values presented are a total from all pathways. Only the whole body, skin, thyroid and maximum organ ( other than thyroid) doses are presented.
For the plume and inhalation pathways, the maximum individual dose is calculated at the off-site location of the highest X/Q where a potential for dose exists.
For ground deposition and ingestion pathways (vegetation, meat and milk), the maximum individual dose is calculated at the location of the highest D/Q. For the milk pathways ( cow and goat), the calculated dose is included in the maximum individual's dose only at locations and times where these pathways actually exist.
To determine compliance with 10 CFR 50, Appendix I (Reference 7), the maximum individual whole body and organ doses include all applicable external pathways (i.e., plume and ground exposure) as well as the internal pathways (inhalation and ingestion).
1.2.2 Liquid Effluents Maximum individual doses from the release of radioactive liquid effluents were calculated using OpenEMS which gives dose results equal to dose results calculated using NRC Regulatory Guide 1.109. OpenEMS performs calculations for the following pathways: fish, shellfish, shoreline activity, swimming, and boating.
Doses are calculated for the whole body, skin, thyroid, and maximum organ (GI, bone, liver, kidney, and Jung).
1.2.3 Analysis of Results Table 1-3 provides a quantitative dose comparison with the limits specified in the REMODCM. Gaseous and liquid effluent doses are compared to limits required by technical specifications and contained in Appendix I of 10 CFR 50. Total offsite doses are compared to limits in 40 CFR 190 (Reference 8). The data indicates that the total whole body and organ doses to the maximum offsite individual from MPS including all sources of the 6
fuel cycle are well within the limits. On-site radioactive waste and spent fuel storage during this year was within storage criteria and the maximum dose to a member of the public from these sources was approximately 0.13 rnrem. The doses from gaseous and liquid effluents were added to the estimated dose from on-site radioactive waste storage to show compliance compared to 40 CFR 190.
The Offsite Dose Comparison, Table 1-4, provides a perspective on the maximum offsite individual dose received from MPS with the natural background radiation dose received by the average Connecticut resident (Reference 4). The total dose to the maximum individual received from MPS is small(< 0.3%) in comparison to the dose received from natural background radiation.
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Table 1-1 2017 Off-Site Dose Commitments from Gaseous Effluents MPS1, 2, 3 MPS1 Max Air Beta Gamma Max Individual Whole Body Skin Thyroid Max organ 1 MPS2 Max Air Beta Gamma Max Individual Whole Body Skin Thyroid Max organ 1 MPS3 Max Air Beta Gamma Max Individual Whole Body Skin Thyroid Max organ1 NOTES:
1st Quarter mrad O.OOE+OO O.OOE+OO mrem 9.28E-06 9.14E-06 9.14E-06 9.53E-06 1st Quarter mrad 5.66E-06 1.23E-05 mrem 2.42E-03 2.81 E-04 2.55E-03 1.17E-02 1st Quarter mrad 4.21 E-05 2.82E-06 mrem 4.81 E-03 2.35E-03 4.81 E-03 1.47E-02 2nd Quarter mrad O.OOE+OO O.OOE+OO mrem 3.60E-04 2.SOE-04 3.60E-04 3.60E-04 2nd Quarter mrad 3.18E-05 6.04E-05 mrem 1.79E-02 5.58E-04 1.80E-02 1.06E-01 2nd Quarter mrad 1.07E-06 1.93E-07 mrem 1.88E-02 1.79E-03 1.88E-02 9.83E-02 3rd Quarter 4th Quarter Annual Total mrad mrad mrad O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO mrem mrem mrem 1.12E-05 5.75E-04 9.55E-04 4.65E-06 4.61 E-04 7.25E-04 1.12E-05 5.75E-04 9.55E-04 1.12E-05 5.75E-04 9.56E-04 3rd Quarter 4th Quarter Annual Total mrad mrad mrad 5.77E-07 3.27E-06 4.13E-05 1.37E-06 8.15E-06 8.22E-05 mrem mrem mrem 1.18E-02 4.03E-02 7.24E-02 3.07E-04 1.04E-03 2.19E-03 1.18E-02 4.0SE-02 7.29E-02 6.98E-02 2.25E-01
- 4. 13E-01 3rd Quarter 4th Quarter Annual Total mrad mrad mrad 2.02E-06 2.38E-05 6.90E-05 3.34E-07 4.34E-05 4.67E-05 mrem mrem mrem 9.92E-03 5.88E-02 9.23E-02 3.79E-04 2.94E-03 7.46E-03 9.40E-03 5.71 E-02 9.01 E-02 5.76E-02 2.88E-01 4.59E-01 1-Maximum of the following organs (not including thyroid): Bone, GI-LL/, Kidney Liver Lung 8
Table 1-2 2017 Off-Site Commitments from Liquid Effluents MPS1, 2, 3 MPS1 Max Individual Whole Body Thyroid Max Or an 1 MPS2 Max Individual Whole Body Thyroid Max Ore an 1 MPS3 Max Individual Whole Body Thyroid Max Or an 1 NOTES:
1st Quarter (mrem) 1.37E-05 3.79E-06 2.19E-05 1st Quarter (mrem) 1.77E-04 1.12E-04 6.32E-04 1st Quarter (mrem) 6.19E-05 6.19E-05 6.19E-05 2nd Quarter (mrem) 3.00E-05 8.32E-06 4.58E-05 2nd Quarter (mrem) 1.96E-05 1.48E-05 1.49E-03 2nd Quarter (mrem) 7.56E-05 4.34E-05 2.80E-04 3rd Quarter (mrem)
O.OOE+OO O.OOE+OO O.OOE+OO 3rd Quarter (mrem) 2.38E-06 2.38E-06 2.38E-06 3rd Quarter (mrem) 2.09E-04 2.09E-04 2.09E-04 4th Quarter (mrem) 3.34E-06 9.69E-07 4.74E-06 4th Quarter (mrem) 3.03E-05 2.80E-05 3.79E-05 4th Quarter (mrem) 2.76E-04 2.75E-04 2.79E-04 Annual Total (mrem) 4.71 E-05 1.31E-05 7.25E-05 Annual Total (mrem) 2.29E-04 1.57E-04 2.16E-03 Annual Total (mrem) 6.22E-04 5.90E-04 8.31 E-04 1-Maximum of the following organs (not including thyroid): Bone, GI-LL/, Kidney Liver Lung 9
1, MPS1 MPS2 1,
MPS3 MPS Limits Table 1-3 2017 Off-Site Dose Comparison to Limits MPS1, 2, 3 Gaseous Effluents Dose Whole Body Thyroid Max Organ*
Skin Beta Air Gamma Air (mrem)
(mrem)
(mrem)
(mrem)
(mrad)
(mrad) 9.55E-04 9.55E-04 9.56E-04 7.25E-04 O.OOE+OO O.OOE+OO 7.24E-02 7.29E-02 4.13E-01 2.19E-03 4.13E-05 8.22E-05 9.23E-02 9.01 E-02 4.59E-01 7.46E-03 6.90E-05 4.67E-05 1.66E-01 1.64E-01 8.73E-01 1.04E-02 1.10E-04 1.29E-04 5
15 15 15 20 10 Liquid Effluents Dose Max Whole Body Thyroid Organ*
(mrem)
(mrem)
(mrem)
MPS1 4.71 E-05 1.31 E-05 7.25E-05 MPS2 2.29E-04 1.57E-04 2.16E-03 MPS3 6.22E-04 5.90E-04 8.31 E-04 MPS 8.98E-04 7.60E-04 3.06E-03 Limits 3
10 10 Total Off-Site Dose from MPS Max Organ Whole Body Thyroid (mrem)
(mrem)
(mrem)
Gaseous I
1.66E-01 1.64E-01 8.73E-01 Liquid 8.98E-04 1.57E-04 2.16E-03 Direct Shine**
1.40E-01 1.40E-01 1.40E-01 MPS 3.07E-01 3.04E-01 1.01 E+OO Limits 25 75 25 Maximum of the following organs (not including Thyroid): Bone, GI-LLI, Kidney, Liver, Lung
- Direct shine is radiation exposure from onsite storage of radwaste and spent fuel.
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Table 1-4 2017 Off-Site Dose Comparison Natural Background vs MPS Average Resident Cosmic Terrestrial (Atlantic and Gulf Coastal Plain)
Inhaled In the Body Courtesy UNSCEAR Report 2000 Maximum Off-Site Individual Gaseous Effluents Liquid Effluents Direct Shine Natural Background Radiation Dose 30 -100 mrem 30 - 60 mrem 20 - 1,000 mrem 20 - 80 mrem 100 -1,240 I mrem MPS Whole Body Dose 0.166 mrem 0.001 mrem 0.140 mrem 0.307 1 mrem 1.3 Other Sources of Radiation Dose to the Public (from Ref. 12)
This section discusses the doses that the average American typically receives each year from naturally occurring background radiation and all other sources of radiation. The reader can compare the doses received 11
from MPS effluents with the doses received from natural, medical, and other sources of radiation. This comparison provides some context to the concept of radiation dose effects. In March 2009, the National Council on Radiation Protection and Measurements (NCRP) published Report No. 160 as an update to the 1987 NCRP Report No. 93, Ionizing Radiation Exposure of the Population of the United States. Report No.
160 describes the doses to the U.S. population from all sources of ionizing radiation for 2006, the most recent data available at the time the NCRP report was written. The NCRP report also includes information on the variability of those doses from one individual to another. The NCRP estimated that the average person in the United States receives about 620 mrem of radiation dose each year. NCRP Report No. 160 describes each of the sources of radiation that contribute to this dose, including:
- Naturally occurring sources (natural background) such as cosmic radiation from space, terrestrial radiation from radioactive materials in the earth, and naturally occurring radioactive materials in the food people eat and in the air people breathe;
- medical sources from diagnosis and treatment of health disorders using radioactive pharmaceuticals and radiation-producing equipment;
- consumer products (such as household smoke detectors);
- industrial processes, security devices, educational tools, and research activities; and
- exposures of workers that result from their occupations.
Below is a pie chart showing the relative contributions of these sources of radiation to the dose received by the average American. Larger contributors to dose are represented by proportionally larger slices of the pie.
Doses to the public from nuclear power plants are included in the industrial category; doses to workers from nuclear power generation are included in the category of occupational dose. Doses to the public due to effluents from nuclear power plants are less than 0.1 % ( one-tenth of one percent) of what the average person receives each year from all sources of radiation. Doses to workers from occupational exposures, including those received from work at NPPs, also are less than 0.1 % of the average dose to a member of the public from all sources.
Sources of Radiation Exposure to the U.S. Population Industrial includes doses to the public from nuclear fX)wer generation
<0.1%
Occupational includes doses to work.ers from nuclear power generation
<0.1%
Conventional radiography /
fluoroscopy (medical) 5%
12 Space (background) 5%
lnterventional flouroscopy (medical) 7%
Internal (background) 5%
Computed tomography (medical) 24%
2.0 Effluent Radioactivity 2.1 Gaseous Effluents 2.1.1 Measurement of Radioactivity in Gaseous Effluents 2.1.1.1 Continuous Releases The following pathways have continuous radiation monitors which monitor gaseous radioactivity and collect radioactive particulates on filters and radioactive halogens (iodine's, etc.) on charcoal cartridges except where noted on the list.
MPSl SFPI Island (no charcoal cartridge)
MPSl BOP Vent (no charcoal cartridge)
MPS2 Ventilation Vent MPS2 Wide Range Gas Monitor (WRGM) to Site Stack MPS2 Equipment Hatch Opening (no gaseous monitoring)
MPS3 Ventilation Vent MPS3 SLCRS to Site Stack MPS3 ESF Building Vent MPS3 Containment Equipment Hatch Openings (no gaseous monitoring)
Most releases are based on results of sample analyses. Charcoal cartridges and particulate filters are replaced weekly (except every two weeks for MPSl) and analyzed for isotopic content using a gamma spectrometer. Particulate filters are also analyzed for Strontium-89 (Sr-89) ( except for MPS 1 ), Strontium-90 (Sr-90) and gross alpha. At least monthly, gaseous grab samples are taken and analyzed for noble gasses and H-3. The gas washing bottle (bubbler) method is utilized for H-3 collection. This sample is counted on a liquid scintillation detector. Isotopic concentrations at the release point are multiplied by the total flow to obtain the total activity released for each isotope.
Some releases are ba ed on calculation. These include tritium from spent fuel pools, Carbon 14 (C-14) and RWST vent releases.
Spent fuel pool tritium release is calculated using concentrations of tritium in the water and evaporation determined by change in pool levels. Grab samples from the MPS 1 SFPI Vent and the MPS2 and MPS3 Vents are compared to the measured evaporation technique and the higher amount from either the vent or the measured evaporation technique is used to determine the amount ofH-3 released.
C-14 releases are calculated using the methodology in Reference 11. Based on Reference 2, it was conservatively assumed that 30% of the C-14 exists as carbon dioxide (CO2) which may be deposited on surfaces. Thus only 30% of C-14 released yielded dose via ingestion pathways of milk, meat, produce and vegetation. C-14 has always been released from the plant but, previous to 2010, was not reported because it was not a significant release relative to other radioactive releases. Since the overall quantity of other radioactive releases has steadily decreased due to improvements in power plant operations, C-14 now qualifies as a principle radionuclide. For each Unit, it is assumed that half of the C-14 is released from the MPS and half from each unit's main ventilation vent.
When water is transferred to the RWST there is a potential for a release of radioactivity through the tank vent. Releases of particulates and H-3 from the MPS2 and MPS3 RWSTs were estimated using factors for release from water to air. For H-3 the release factor is based on the ratio of mass of water vapor to mass of dry air and adjusted for difference between water and air densities. For particulates the release factor is based on an assumed partitioning factor of 10,000. RWST vent releases are calculated using concentration of tritium in water, particulate radioactivity added to the RWST during outages and volumes of air exhaled based on observed changes in water level and on thermal fluctuations of the water. During 2017 MP-CHEM-17-07, "Reporting of Radioactivity Released from RWST Vents" was written to establish threshold values for determining releases. The threshold value eliminated the monthly tracking tritium released through the RWST vent, but ensures that major level changes resulting significant release are tracked.
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Any releases from the spent fuel pool area in the reactor building at MPS 1 are released through the SFPI Vent.
Releases from other parts of the MPSI reactor building and other buildings are continuously discharged to the BOP Vent.
Samples of air near the containment equipment hatch openings are analyzed for particulates and iodines, during refueling outages for the period that the equipment hatch is open. An estimated flow out of the hatch and sample results are used to determine the radioactivity released. Containment equipment hatch and containment drawdown releases at MPS3 occurred only during the MPS3 outage during the second quarter.
2.1.1.2 Batch Releases The following sources of radioactivity releases are considered batch releases:
MPS2 Waste Gas Decay Tanks (WGDT) (via MPS2 WRGM to MPS Stack)
MPS3 Containment Purges (via Ventilation Vents)
MPS2 and MPS3 Containment Vents (via EBFS to MPS Stack for MPS2 and via SLCRS to MPS Stack for MPS3)
MPS3 Containment Drawdown (ground level release at containment)
Waste Gases from the MPS2 Gaseous Waste Processing System are held for decay in waste gas decay tanks prior to discharge through the MPS Site Stack. Each gas decay tank is analyzed prior to discharge for noble gas and H-3. Calculated volume discharged is multiplied by the isotopic concentrations (noble gas and H-
- 3) from the analysis of grab samples to determine the total activity released.
Containment air is sampled periodically for gamma and H-3 to determine the activity released from containment venting. The measured concentrations are multiplied by the containment vent volume to obtain the total activity released. MPS2 typically performs this process of discharging air from containment to maintain pressure approximately once per week and MPS3 vents containment about 15 times per month.
Any iodines and particulates discharged would be detected by the continuous monitoring discussed in Section 2.1. l. l.
Containment air is sampled prior to each purge for gamma and H-3 to determine the activity released from containment purging. Similar to containment venting, the measured concentrations are multiplied by the containment purge volume to obtain the total activity released. Any iodines and particulates discharged would be detected by the continuous monitoring discussed in section 2.1.1.1.
MPS3 containment is initially drawn down prior to startup. This is accomplished by using the containment vacuum steam jet ejector which releases through an unmonitored vent on the roof of the Auxiliary Building.
Grab samples are performed prior to drawdown to document the amount of radioactivity released during these evolutions.
2.1.2 Estimate of Errors Estimates of errors associated with radioactivity measurements were made using the following guidelines:
Radioactivity Measurement Calibration 10%
Calibration to NIST* standards Sampling/Data Collection Sample Line Loss Sample Counting Flow & Level Measurements 10%-20%
20%-40%
10%- 30%
10%-20%
14 Variation in sample collection Deposition of some nuclides Error for counting statistics Error for release volumes
- National Institute of Standards and Technology
2.1.3 Gaseous Batch Release Statistics MPS1 - None MPS2 CTMT Vents WGDT CTMTPurge Number of Batches 34 4
1 Total Time (min) 4780 714 1612 Maximum Time (min) 199 205 1612 Average Time (min) 141 179 1612 Minimum Time (min) 29 146 1612 MPS3 CTMT Vents CTMT Purge Number of Batches 168 1
Total Time (min) 48596 240 Maximum Time (min) 439 240 Average Time (min) 289 240 Minimum Time (min) 119 240 2.1.4 Abnormal Gaseous Releases An abnormal gaseous release of radioactivity is defined as radioactive material released in gaseous effluents to the environment that was unplanned or uncontrolled due to an unanticipated event. These do not include normal routine effluent releases from anticipated operational and maintenance occurrences such as power level changes, reactor trip, opening primary system loops, degassing, letdown of reactor coolant or transferring spent resin and do not include non-routine events such as minor leakages from piping, valves, pump seals, tank vents, etc.
2.1.4.1 MPS1 - None 2.1.4.2 MPS2 - None 2.1.4.3 MPS3 - None 2.1.5 Gaseous Release Tables The following tables provide the details of the gaseous radioactivity released from each of the MPS units.
They are categorized by type of release, source(s), and by release point of discharge to the environment.
15
Table 2.1-A1 MPS1 Gaseous Effluents - Release Summary Units A. Fission & Activation Gases
- 1.
Total Activity Ci Released
- 2.
Average Period uCi/sec Release Rate B I d"
/ H I 0 mes a O!=lens
- 1.
Total Activity Ci na na Released
- 2.
Average Period uCi/sec na na Release Rate C. Particulates
- 1.
Total Activity Ci 4.46E-07 9.85E-06 Released
- 2.
Average Period uCi/sec 5.73E-08 1.25E-06 Release Rate D. Gross Alpha
- 1.
Total Activity Ci Released E. Tritium
- 1.
Total Activity Ci 1.21 E-02 4.33E-01 Released
- 2.
Average Period uCi/sec 1.56E-03 5.51 E-02 Release Rate denotes less than Minimum Detectable Activity (MDA)
"na" denotes not required to be analyzed 16 na na 1.14E-02 1.44E-03 na na na na 1.03E-05 3.26E-07 6.11E-01 1.07E+OO 7.69E-02 3.39E-02
Table 2.1-A2 MPS1 Gaseous Effluents - Ground Continuous - BOP Vent & SFPI Vent Nuclides Released Units A. Fission & Activation Gases Kr-85 Ci Other v Emitters Ci Total Activity Ci B I d"
/ H I 0 mes a o~ ens 1-131 Ci na na Other v Emitters Ci Total Activity Ci C. Particulates Be-7 Ci 9.85E-06 Cs-1 37 Ci 4.46E-07 Other v Emitters Ci Sr-90 Ci Total Activity Ci 4.46E-07 9.85E-06 I Gross Alpha D. Gross Alpha Ci E. Tritium I H-3 Ci 1.21 E-02 4.33E-01 denotes less than Minimum Detectable Activity (MDA)
"na" denotes not required to be analyzed 17 na na 1.14E-02 6.11 E-01 na 9.85E-06 4.46E-07 1.03E-05 1.07E+OO
Table 2.2-A1 MPS2 Gaseous Effluents - Release Summary Units A. Fission & Activation Gases
- 1.
Total Activity Ci Released
- 2.
Average Period uCi/sec Release Rate B I d"
/ H I 0 mes a ogens
- 1.
Total Activity Released
- 2.
Average Period Release Rate C. Particulates
- 1.
Total Activity Released
- 2.
Average Period Release Rate D. Gross Alpha
- 1.
Total Activity Released E. Tritium
- 1.
Total Activity Released
- 2.
Average Period Release Rate F. C-14
- 1.
Total Activity Released**
- 2.
Average Period Release Rate Ci uCi/sec Ci uCi/sec Ci Ci uCi/sec Ci uCi/sec 8.72E-02 8.95E-02 1.12E-02 1.14E-02 8.12E-05 5.37E-05 1.04E-05 6.83E-06 3.45E-05 4.38E-06 9.39E-01 2.03E+OO 1.21 E-01 2.59E-01 2.26E+OO 2.26E+OO 2.91 E-01 2.87E-01 denotes less than Minimum Detectable Activity (MDA) 5.77E-02 7.26E-03 6.12E-07 7.70E-08 2.07E+OO 2.60E-01 2.26E+OO 2.84E-01 4.38E-02 2.78E-01 5.52E-03 8.82E-03 1.75E-06 1.37E-04 2.20E-07 4.35E-06 3.45E-05 1.09E-06 5.39E+OO 1.04E+01 6.78E-01 3.31 E-01 2.26E+OO 9.04E+OO 2.84E-01 2.87E-01 Calculated value per "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents" EPRI Final Report, 12/2010.
18
Table 2.2-A2 MPS2 Gaseous Effluents - Ground Level Release - Batch Mode Release Point - No Releases Nuclides Released Units A. Fission & Activation Gases I Total Activity I
Ci I
I Total Activity I
Ci B. Iodines / Halogens C. Particulates I Total Activity Ci
/ Gross Alpha Ci D. Gross Alpha E. Tritium I H-3 Ci No activity released 19
Table 2.2-A3 MPS2 Gaseous Effluents - Ground Level Release - Continuous Mode Release Point - Refuel Water Storage Tank Vent, Equipment Hatch Nuclides Released Units A. Fission & Activation Gases Xe-133 Ci 6.20E-04 Other v Emitters Ci Total Activity Ci B. Iodines / H alogens 1-131 Ci 5.94E-08 1-133 Ci Other v Emitters Ci Total Activity Ci 5.94E-08 C. Particulates Cr-51 Ci 7.07E-06 Mn-54 Ci 2.21 E-07 Fe-59 Ci 7.51 E-08 Co-58 Ci 1.57E-05 Co-60 Ci 2.27E-06 Zr-95 Ci 1.58E-06 Nb-95 Ci 2.25E-06 Aa-110m Ci 2.78E-06 Sn-113 Ci 2.03E-07 Sn-117m Ci 5.45E-08 Sb-124 Ci 3.98E-07 Sb-125 Ci 1.22E-06 Sb-126 Ci 6.92E-09 Cs-136 Ci 2.25E-08 Cs-137 Ci 5.77E-07 Ce-141 Ci 3.37E-09 Other v Emitters Ci Total Activity Ci 3.44E-05 I Gross Alpha D. Gross Alpha Ci na na na na E. Tritium Ci 1.42E-04 4.04E-03 "na" denotes Not Required to be Analyzed denotes less than Minimum Detectable Activity (MDA) 20 6.20E-04 6.20E-04 5.94E-08 5.94E-08 7.07E-06 2.21 E-07 7.51 E-08 1.57E-05 2.27E-06 1.58E-06 2.25E-06 2.78E-06 2.03E-07 5.45E-08 3.98E-07 1.22E-06 6.92E-09 2.25E-08 5.77E-07 3.37E-09 3.44E-05 na 4.18E-03
Table 2.2-A4 MPS2 Gaseous Effluents - Elevated Release - Batch Mode Release Point-MPS Stack Nuclides Released Units A. Fission & Activation Gases Ar-41 Ci 4.54E-02 2.01 E-02 Kr-85 Ci 6.79E-03 3.94E-03 Xe-133 Ci 3.43E-02 9.92E-03 Xe-135 Ci 6.93E-04 3.55E-04 Other y Emitters Ci Total Activity Ci 8.72E-02 3.43E-02 B I d"
/ H I 0 mes a o~ 1ens Ci Other v Emitters Ci Total Activity Ci C. Particulates I Othec y Emittecs i
Ci I
Ci Ci Total Activity D. Gross Alpha I Gross Alpha Ci na na E. Tritium I H-3 Ci 1.43E-01 2.90E-02 denotes less than Minimum Detectable Activity (MDA)
"na" denotes not required to be analyzed 21 3.47E-02 3.04E-02 1.19E-03 9.96E-04 2.11 E-02 1.19E-02 7.63E-04 5.63E-04 5.78E-02 4.39E-02 na na 1.39E-01 1.69E-01 1.31E-01 1.29E-02 7.73E-02 2.37E-03 2.23E-01 na 4.80E-01
Table 2.2-AS MPS2 Gaseous Effluents - Elevated Release - Continuous Mode Release Point - MPS Stack Nuclides Released Units A. Fission & Activation Gases I Olhec y Em;ttec, I ~: I Total Activity C
B I d"
/ H I 0 mes ao gens 1-131 Ci 1-133 Ci Other y Emitters Ci Total Activity Ci C. Particulates Sr-89 Ci Sr-90 Ci Other y Emitters Ci Total Activity Ci D. Gross Alpha I Gross Alpha I Ci E. Tritium I H-3 Ci 1.79E-01 1.27E-01 F. C-14 I C-14 Ci 1.13E+OO 1.13E+OO 1.13E+OO 1.13E+OO denotes less than Minimum Detectable Activity (MDA) 22 3.06E-01 4.52E+OO
Table 2.2-A6 MPS2 Gaseous Effluents - Mixed Mode Release - Batch Mode Release Point-MPS2 Main Exhaust Vent Nuclides Released Units A. Fission & Activation Gases Ar-41 Ci 1.98E-02 Xe-133 Ci 3.36E-02 Xe-135 Ci 1.19E-03 Other v Emitters Ci Total Activity Ci 5.46E-02 B I d.
/ H I 0 mes a ogens Br-82 Ci 1.30E-05 Other v Emitters Ci Total Activity Ci 1.30E-05 C. Particulates Ci Other v Emitters Ci Total Activity Ci I Gross Alpha D. Gross Alpha Ci na na na na E. Tritium I H-3 Ci 1.79E-01
- No activity released "na" denotes not required to be analyzed denotes less than Minimum Detectable Activity (MDA) 23 1.98E-02 3.36E-02 1.19E-03 5.46E-02 1.30E-05 1.30E-05 na 1.79E-01
Table 2.2-A7 MPS2 Gaseous Effluents - Mixed Mode Release - Continuous Mode Release Point - MPS 2 Main Exhaust Vent Nuclides Released Units A. Fission & Activation Gases I Olhec y Emitte~
I ;: I Total Activit B I d"
/ H 0 mes ao gens Br-85 Ci 5.41 E-06 1-131 Ci 1.82E-05 1.00E-06 6.12E-07 1.75E-06 1-133 Ci 5.75E-05 5.11 E-06 Other v Emitters Ci Total Activity Ci 8.1 1 E-05 6.11 E-06 6.12E-07 1.75E-06 C. Particulates Ci Other v Emitters Ci Sr-89 Ci Sr-90 Ci Total Activity Ci D. Gross Alpha I
I Gross Alpha Ci E. Tritium I H-3 Ci 7.96E-01 1.82E+OO 1.75E+OO 5.09E+OO F. C-14 I C-14 Ci 1.13E+OO 1.13E+OO 1.13E+OO 1.13E+OO denotes less than Minimum Detectable Activity (MDA) 24 5.41 E-06 2.16E-05 6.26E-05 8.96E-05 9.46E+OO 4.52E+OO
Table 2.3-A1 MPS3 Gaseous Effluents - Release Summary Units A. Fission & Activation Gases
- 1.
Total Activity Ci Released
- 2.
Average Period uCi/sec Release Rate B I d"
/ H I o mes a ogens
- 1.
Total Activity Released
- 2.
Average Period Release Rate C. Particulates
- 1.
Total Activity Released
- 2.
Average Period Release Rate D. Gross Alpha
- 1.
Total Activity Released E. Tritium
- 1.
Total Activity Released
- 2.
Average Period Release Rate F. C-14
- 1.
Total Activity Released**
- 2.
Average Period Release Rate Ci uCi/sec Ci uCi/sec Ci Ci uCi/sec Ci uCi/sec 2.23E-01 2.22E-01 2.87E-02 2.83E-02 2.75E-06 1.28E-05 3.53E-07 1.63E-06 5.89E-08 7.58E-09 1.34E+01 1.04E+01 1.73E+OO 1.32E+OO 2.88E+OO 2.88E+OO 3.70E-01 3.66E-01 denotes less than Minimum Detectable Activity (MDA) 2.46E-01 3.10E-02 1.81 E-06 2.27E-07 4.39E+OO 5.53E-01 2.88E+OO 3.62E-01 3.04E-01 9.96E-01 3.82E-02 3.16E-02 1.60E-06 1.90E-05 2.01 E-07 6.02E-07 1.42E-03 1.42E-03 1.79E-04 4.52E-05 1.35E+01 4.17E+01 1.70E+OO 1.32E+OO 2.88E+OO 1.15E+01 3.62E-01 3.65E-01 Calculated value per "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents" EPRI Final Report, 12/2010.
25
Table 2.3-A2 MPS3 Gaseous Effluents - Ground Level Release - Batch Mode Release Point -ESF Building Rooftop Nuclides Released Units A. Fission & Activation Gases B. Iodines Halo~ens 1-131 Ci 1-133 Ci Other v Emitters Ci Total Activity Ci C. Particulates I y Emitters Ci Total Activity Ci D. Gross Alpha I Gross Alpha Ci na na na E. Tritium H-3 Ci
- No activity released II II denotes less than Minimum Detectable Activity (MDA)
"na" denotes Not Required to be Analyzed 26 na na
Table 2.3-A3 MPS3 Gaseous Effluents - Ground Level Release - Continuous Mode Release Point - ESF Building Vent, Containment Equipment Hatch, RWST Vent, ABD TK-2 Vent Nuclides Released Units A. Fission & Activation Gases I Othec y Emittern I ~: I Total Activity B I d"
/ H 0 mes a ogens 1-131 Ci 1-133 Ci Other y Emitters Ci Total Activity Ci C. Particulates Cr-51 Ci Mn-54 Ci Fe-59 Ci Co-57 Ci Co-58 Ci Co-60 Ci Zr-95 Ci Nb-95 Ci Sb-125 Ci Cs-137 Ci Total Activity Ci I Gross Alpha D. Gross Alpha Ci E. Tritium I H-3 Ci 4.81 E-02 1.13E-01 denotes less than Minimum Detectable Activity (MDA)
- No activity released 27 5.72E-04 5.72E-04
- 4. 16E-05 4.16E-05 1.62E-05 1.62E-05 2.84E-08 2.84E-08 4.31 E-04 4.31 E-04 1.1 0E-03 1.10E-03 4.32E-05 4.32E-05 6.97E-05 6.97E-05 4.76E-07 4.76E-07 6.01 E-06 6.01 E-06 2.28E-03 2.28E-03 3.89E-02 4.55E-02 2.45E-01
Table 2.3-A4 MPS3 Gaseous Effluents - Elevated Release - Batch Mode Release Point - MPS Stack Nuclides Released Units A. Fission & Activation Gases Ar-41 Ci 7.83E-03 Xe-133 Ci 5.61 E-04 Xe-135 Ci 2.60E-04 Other y Emitters Ci Total Activity Ci 8.65E-03 B I d"
/ H I 0 mes a ogens Ci Other v Emitters Ci I
Total Activity Ci I
C. Particulates I Othec y Emittern Ci Ci Total Activity Ci I Gross Alpha D. Gross Alpha Ci na E. Tritium I H-3 Ci 2.0SE-01 denotes less than Minimum Detectable Activity (MDA)
"na" denotes Not Required to be Analyzed 8.14E-03 8.20E-04 I 3.SSE-03 1.88E-04 8.40E-04 I 4.34E-05 1.19E-04 2.77E-04 I
8.45E-03 9.31 E-03 I 3.60E-03 I
I I
I na na na 6.36E-02 5.56E-02 2.56E-02 28 2.77E-02 1.63E-03 6.57E-04 3.00E-02 na 3.SOE-01
Table 2.3-AS MPS3 Gaseous Effluents - Elevated Release - Continuous Mode Release Point - MPS Stack Nuclides Released Units A. Fission & Activation Gases Ar-41 Ci 1.00E-04 1.40E-01 Kr-85 Ci 1.46E-01 2.14E-01 2.37E-01 1.26E-01 Kr-85m Ci 8.80E-05 1.68E-03 Kr-87 Ci 1.80E-04 2.00E-03 Kr-88 Ci 1.90E-04 2.50E-03 Xe-133 Ci 1.90E-04 3.20E-03 Xe-135 Ci 5.50E-04 3.20E-03 Xe-135m Ci 1.70E-04 1.01 E-02 Xe-138 Ci 7.00E-04 8.90E-03 Other v Emitters Ci Total Activity Ci 1.48E-01 2.14E-01 2.37E-01 2.98E-01 B I d'
/ H I 0 mes ao !1ens Br-82 Ci 2.75E-06 1.28E-05 1.81 E-06 1.60E-06 1-131 Ci 1-133 Ci Other v Emitters Ci Total Activity Ci 2.75E-06 1.28E-05 1.81 E-06 1.60E-06 C. Particulates Mn-54 Ci 3.08E-08 Co-58 Ci 4.42E-07 Co-60 Ci 1.96E-07 Sr-89 Ci Sr-90 Ci Ba-131 Ci 5.89E-08 Other v Emitters Ci Total Activity Ci 5.89E-08 6.69E-07 D. Gross Alpha I Gross Alpha I Ci E. Tritium J H-3 Ci 1.20E+OO 2.04E+OO 6.39E-01 2.15E-01 F. C-14 I C-14 Ci 1.44E+OO 1.44E+OO 1.44E+OO 1.44E+OO denotes less than Minimum Detectable Activity (MDA) 29 1.40E-01 7.23E-01 1.77E-03 2.18E-03 2.69E-03 3.39E-03 3.75E-03 1.03E-02 9.60E-03 8.97E-01 1.90E-05 1.90E-05 3.08E-08 4.42E-07 1.96E-07 5.89E-08 7.28E-07 4.09E+OO 5.76E+OO
Table 2.3-A6 MPS3 Gaseous Effluents - Mixed Mode Release - Batch Mode Release Point - MPS3 Ventilation Vent Nuclides Released Units A. Fission & Activation Gases Xe-133 Ci Xe-135 Ci Other y Emitters Ci Total Activity Ci B I d'
/ H 0 mes alogens Ci Other v Emitters Ci Total Activity Ci C. Particulates Ci Other v Emitters Ci Total Activity Ci I Gross Alpha D. Gross Alpha Ci E. Tritium 1.78E-03 6.26E-04 2.41 E-03 na na na na 1.78E-03 6.26E-04 2.41 E-03 na
! H-3 Ci
! 4.13E-02 ! 4.13E-02 !
- No activity released
"-" denotes less than Minimum Detectable Activity (MDA)
"na" denotes Not Required to be Analyzed 30
Table 2.3-A?
MPS3 Gaseous Effluents - Mixed Mode Release - Continuous Mode Release Point - MPS3 Ventilation Vent Nuclides Released Units A. Fission & Activation Gases Kr-85 Ci 6.60E-02 Other Emitters Ci Total Activit Ci 6.60E-02 B. Iodines/ Halo ens 1-131 Ci 1-133 Ci Other Emitters Ci Total Activit Ci C. Particulates Cr-51 Ci 3.53E-05 Co-58 Ci 7.80E-05 Co-60 Ci 1.39E-05 Nb-95 Ci 3.72E-06 Other Emitters Ci Sr-89 Ci Sr-90 Ci Total Activit Ci 1.31 E-04 D. Gross Alpha I Gross Alpha I Ci E. Tritium
/ H-3 Ci 1.20E+01 8.18E+OO 3.66E+OO 1.32E+OO F. C-14 I C-14 Ci 1.44E+OO 1.44E+OO 1.44E+OO 1.44E+OO denotes less than Minimum Detectable Activity (MDA) 31 6.60E-02 6.60E-02 3.53E-05 7.80E-05 1.39E-05 3.72E-06 1.31 E-04 3.70E+01 5.76E+OO
2.2 Liquid Effluents 2.2.1 Measurement of Radioactivity in Liquid Effluents 2.2.1.1 Continuous Liquid Releases Water containing radioactivity is continuously released through one of two pathways - the MPS Quarry or DSN006. DSN006 is next to the MPS3 intake structure (DSN is acronym for Discharge Serial Number.)
Grab samples are taken for continuous liquid release pathways and analyzed on the gamma spectrometer and liquid scintillation detector (for H-3) if required by the conditional action requirements of the REMODCM.
Total estimated volume is multiplied by the isotopic concentrations (if any) to determine the total activity released. A proportional aliquot of each discharge is retained for composite analysis for Sr-89, Sr-90, Fe-55 and gross alpha ifrequired by the conditional action requirements of the REMODCM. Sources for continuous liquid effluent releases via the MPS Quarry include Steam Generator Blowdown for MPS2 & MPS3, Service Water Effluent for MPS2 & MPS3 and Reactor Building Closed Cooling Water (RBCCW) Sump for MPS2.
Sources for continuous liquid effluent releases via DSN006 include Turbine Building Sump discharge from MPS2 & MPS3, CPF TK.2 from MPS3 and SRW Sump 3 from MPS3.
2.2.1.2 Batch Liquid Releases from Tanks and Sumps Batch liquid releases are made via both the MPS Quarry and DSN006. There are numerous sources from which batches of liquids containing radioactivity are discharged to the environs. Except for two sources from MPS3 to DSN006 they are discharged via the MPS Quarry. The sources are:
MPS1 Radwaste Processing System - Includes sources from:
- 1. Reactor Building Sumps
- 2. Underground Ventilation Duct
- 3. Site Stack Sump MPS2 Radwaste Processing System:
- 1. Clean Waste Monitor Tanks (2)
- 2. Aerated Waste Monitor Tanks Other Radwaste Sources:
- 1. CPF Waste Neutralization Sump
- 2. Steam Generator Bulk
- 3. Other Systems' Bulk Discharges MPS3 Radwaste Processing
- 1. Waste Test Tanks (2)
- 2. Low Level Waste Test Tanks (2)
- 3. Boron Test Tanks (2)
Other Radwaste Sources:
- 1. CPF Waste Neutralization Sump
- 2. Steam Generator Bulk
- 3. Other systems' Bulk Discharges (via Quarry or DSN006)
Prior to release, a tank is re-circulated for two equivalent tank volumes, a sample is drawn and then analyzed on the HPGe gamma spectrometer and liquid scintillation detector (H-3) for individual radionuclide composition.
Isotopic concentrations are multiplied by the volume released to obtain the total activity released.
For bulk releases, several samples are taken during the discharge to verify the amount of radioactivity released. A proportional aliquot of each discharge is retained for composite analysis for Sr-89, Sr-90, Fe-55, and gross alpha.
32
2.2.2 Estimate of Errors Estimates of errors associated with radioactivity measurements were made using the following guidelines:
Radioactivity Measurement Calibration 10%
Calibration to NIST* standards Sampling/Data Collection 10%-20%
Variation in sample collection Sample Counting 10%- 30%
Error for counting statistics Flow & Level Measurements 10%- 20%
Error for release volumes
- National Institute of Standards and Technology 2.2.3 Liquid Batch Release Statistics MPS1 MPS2 MPS3 Radwaste Processing System:
Number of Batches 6
24 82 Total Time (min) 260 3762 8372 Maximum Time (min) 60 281 123 Average Time (min) 43 157 201 Minimum Time (min) 34 60 48 MPS1 MPS2 MPS3 Other Radwaste Sources:
Number of Batches NA 5
167 Total Time (min)
NA 572 19800 Maximum Time (min)
NA 283 194 Average Time (min)
NA 58 125 Minimum Time ( min)
NA 17 30 2.2.4 Abnormal Liquid Releases An abnormal release of radioactivity is the discharge of a volume of liquid radioactive material to the environment that was unplanned or uncontrolled. In 2017, the following abnormal liquid releases occurred:
2.2.4.1 MPS1 - None 2.2.4.2 MPS2 - None 2.2.4.3 MPS3 - None 2.2.5 Liquid Release Tables The following tables provide the details of the liquid radioactivity released from each of the MPS units.
They are categorized by type of release, source(s), and by release point of discharge to the environment.
33
Table 2.1-L 1 MPS1 Liquid Effluents - Release Summary Units A. Fission and Activation Products
- 1.
Total Activity Ci 9.72E-04 Released
- 2.
Average Period uCi/ml 4.10E-12 Diluted Activity+
B. Tritium
- 1.
Total Activity Ci 1.53E-03 Released
- 2.
Average Period uCi/ml 6.44E-12 Diluted Activity+
C. Dissolved and Entrained Gases
- 1.
Total Activity Released
- 2.
Average Period Diluted Activity+
D. Gross Alpha
- 1.
Total Activity Released E. Volume
- 1.
Released Waste Volume
- 2.
Dilution Volume Durinq Releases
- 3.
Dilution Volume Durinq Period++
- No activity released Ci uCi/ml Ci Liters 6.11E+04 Liters 4.62E+08 Liters 2.37E+11 1.87E-03 1.10E-11 2.56E-03 1.51E-11 6.40E+04 3.24E+08 1.70E+11 denotes less than Minimum Detectable Activity (MDA) 1.79E-02 6.43E-11 6.26E+04 3.83E+08 2.78E+11
+
"Total Activity Released" 7 ("Released Waste Volume"+ "Dilution Volume During Period"}
++
MPS2 Dilution Volume During Period used because there is no MPS1 dilution 34 2.95E-03 4.30E-12 2.20E-02 3.21 E-11 1.88E+05 1.17E+09 6.85E+11
Table 2.1-L2 MPS1 Liquid Effluents - Batch Release to Quarry: Liquid Radwaste Processing System Nuclides Released Units A. Fission & Activation Products Cs-137 Ci 9.06E-04 1.78E-03 Other y Emitters Ci Sr-89 Ci 4.33E-06 Sr-90 Ci 3.90E-06 Fe-55 Ci 6.11 E-05 9.03E-05 Total Activity Ci 9.72E-04 1.87E-03 B. Tritium IH-3 Ci 1.53E-03 2.56E-03 C. Dissolved & Entrained Gases Kr-85 Ci Other y Emitters Ci Total Activity Ci D. Gross Alpha
!Gross Alpha I Ci
- No activity released denotes less than Minimum Detectable Activity (MDA)
"na" denotes not required to be analyzed 35 2.62E-04 2.95E-03 2.95E-03 1.79E-02 2.20E-02
Table 2.2-L 1 MPS2 Liquid Effluents - Release Summary Units A. Fission and Activation Products
- 1.
Total Activity Ci 1.06E-02 Released
- 2.
Average Period uCi/ml 4.47E-11 Diluted Activity*
B. Tritium
- 1.
Total Activity Ci 3.09E+02 Released
- 2.
Average Period uCi/ml 1.30E-06 Diluted Activity
- C. Dissolved and Entrained Gases
- 1.
Total Activity Released
- 2.
Average Period Diluted Activity
- D. Gross Alpha 1.
Total Activity Released E. Volume
- 1.
Released Waste Volume Primary Seconda Dilution Volume During
- 2.
Releases Primary Secondary (DSN006)
Ci uCi/ml Ci Liters Liters Liters Liters Liters
- 3.
Dilution Volume During Period Quarry Liters DSN006 Liters 1.74E-02 7.34E-11 8.62E+05 2.40E+06 9.80E+09 6.53E+07 2.41 E+09 2.37E+11 6.38E+07 6.36E-04 3.74E-1 2 3.17E+01 6.98E+OO 1.87E-07 2.50E-08 7.19E-04 4.23E-12 4.77E+05 8.66E+04 1.61 E+05 1.08E+04 1.13E+10 9.35E+08 2.42E+05 4.61E+05 3.16E+09 Note 1.70E+11 2.79E+11 4.76E+07 6.17E+07 9.39E-05 3.37E-13 3.28E+01 1.18E-07 1.59E+05 3.46E+05 3.46E+09 8.46E+06 8.88E+08 2.78E+11 5.72E+07
- "Total Activity Released".;- ("Released Waste Volume" + "Dilution Volume During Period")
1111 denotes less than Minimum Detectable Activity (MDA)
Note:
No secondary releases to DSN006 in 2nd and 3rd quarters.
36 1.13E-02 4.88E-11 3.80E+02 3.94E-07 1.81 E-02 7.76E-11 1.58E+06 2.92E+06 2.55E+10 7.45E+07 6.46E+09 9.64E+1 1 2.30E+08
Nuclides Table 2.2-L2 MPS2 Liquid Effluents - Continuous
- 1. Release to Quarry: Steam Generator Slowdown, Service Water and Reactor Building Closed Cooling Water
- 2. Release to DSN006: Turbine Building Sumps and Tendon Gallery Released Units A. Fission & Activation Products v Emitters Ci Sr-89 Ci Sr-90 Ci Ni-63 Ci Total Activity Ci B. Tritium
! H-3 Ci 2.02E+03 !
1.50E-03 !
8.30E-04 !
1.14E-03 I 2.02E+03 C. Dissolved & Entrained Gases D. Gross Alpha I Gross Alpha Ci denotes less than Minimum Detectable Activity (MDA)
- No activity released 37
Table 2.2-L3 MPS2 Liquid Effluents - Batch Release to Quarry: Liquid Radwaste Processing System Nuclides Released Units A. Fission & Activation Products Be-7 Ci Mn-54 Ci 3.89E-06 Co-58 Ci 7.00E-05 Co-60 Ci 1.55E-04 2.00E-04 Nb-97 Ci Aq-110m Ci 3.01 E-05 2.97E-04 Sb-125 Ci 1.83E-04 2.44E-05 1-131 Ci Cs-137 Ci 2.98E-05 Other y Emitters Ci Fe-55 Ci 6.03E-03 4.06E-05 9.39E-05 Ni-63 Ci 6.98E-04 Sr-89 Ci 3.50E-03 Sr-90 Ci Total Activity Ci 1.06E-02 6.36E-04 9.39E-05 B. Tritium 3.89E-06 7.00E-05 3.55E-04 3.27E-04 2.0?E-04 2.98E-05 6.16E-03 6.98E-04 3.50E-03 1.14E-02 I H-3
! Ci ! 3.09E+02 ! 3.17E+01 ! 6.98E+OO ! 3.28E+01 ! 3.80E+02 !
C. Dissolved & Entrained Gases Xe-133 Ci 1.?0E-02 7.19E-04 1.77E-02 Xe-133m Ci 1.29E-04 1.29E-04 Xe-135 Ci 2.93E-04 2.93E-04 Other v Emitters Ci Total Activity Ci 1.74E-02 7.19E-04 1.81 E-02 I Gross Alpha D. Gross Alpha Ci denotes less than Minimum Detectable Activity (MDA) 38
Table 2.3-L 1 MPS3 Liquid Effluents - Release Summary Units A. Fission and Activation Products
- 1.
Total Activity Ci 1.91 E-03 Released
- 2.
Average Period uCi/ml 4.77E-12 Diluted Activity
- B. Tritium
- 1.
Total Activity Ci 1.51 E+02 6.86E+01 6.26E+02 Released
- 2.
Average Period uCi/ml 3.49E-07 1.71 E-07 1.32E-06 Diluted Activity
- C. Dissolved and Entrained Gases
- 1.
Total Activity Ci Released
- 2.
Average Period uCi/ml Diluted Activity
- D. Gross Aleha
, 1.
Total Activity Ci Released E. Volume
- 1.
Released Waste Volume Primary Liters 5.35E+05 1.31 E+06 1.15E+06 Seconda Liters 2.60E+07 2.16E+07 1.84E+07
- 2.
Dilution Volume During Releases Primary Liters 4.51 E+09 1.19E+10 1.07E+10 Secondary (DSN006)
Liters 1.25E+08 4.71 E+07 1.20E+08 Seconda Liters 1.08E+12 9.00E+11 1.10E+12
- 3.
Dilution Volume During Period Quarry Liters 4.31 E+11 4.01 E+11 4.73E+11 DSN006 Liters 6.38E+07 4.76E+07 6.17E+07 denotes less than Minimum Detectable Activity (MDA) 3.02E-04 2.21 E-03 9.49E-13 1.36E-12 5.30E+02 1.38E+03 1.67E-06 8.47E-07 1.07E+06 4.07E+06 1.47E+07 8.07E+07 8.09E+09 3.52E+10 3.37E+04 2.92E+08 7.43E+11 3.82E+12 3.18E+11 1.62E+12 5.72E+07 2.30E+08
- "Total Activity Released" + (Primary "Released Waste Volume" + "Dilution Volume During Period")
39
Table 2.3-L2 MPS3 Liquid Effluents - Continuous
- 1. Release to Quarry: Steam Generator Slowdown, Service Water, ABD TK-2
- 2. Release to DSN006: Turbine Building Sump and SRW Sump 3 Nuclides Released Units A. Fission & Activation Products v Emitters Ci Sr-89 Ci Sr-90 Ci Fe-55 Ci Total Activity Ci B. Tritium
! H-3 Ci 6.51 E-01 5.06E-01 3.24E-01 8.60E-02 1.57E+OO C. Dissolved & Entrained Gases I Gross Alpha D. Gross Alpha Ci denotes less than Minimum Detectable Activity (MDA) 40
Table 2.3-L3 MPS3 Liquid Effluents - Batch
- 1. Release to Quarry: Liquid Radwaste Processing System, CPF Waste Neutralization Sumps, Hotwell and Steam Generator Bulk, ABD TK-2
- 2. Release to DSN006: Waste Test Tank Berm Nuclides Released Unit s
A. Fission & Activation Products Mn-54 Ci Co-58 Ci Co-60 Ci Zr-95 Ci Nb-95 Ci Sb-125 Ci Cs-134 Ci Cs-137 Ci Other y Emitters Ci Fe-55 Ci Ni-63 Ci Sr-89 Ci Sr-90 Ci Total Activity Ci B. Tritium 1.91 E-03 1.91 E-03 3.02E-04 3.02E-04 1.91 E-03 3.02E-04 2.21 E-03
! H-3 Ci 1.50E+02 6.81 E+01 I 6.26E+02 I 5.30E+02 1.37E+03 C. Dissolved & Entrained Gases I Gross Alpha D. Gross Alpha Ci denotes less than Minimum Detectable Activity (MDA) 41
2.3 Solid Waste Solid waste shipment summaries for each unit are given in the following tables:
Table 2.1-S MPSl Solid Waste and Irradiated Component Shipments Table 2.2-S MPS2 Solid Waste and Irradiated Component Shipments Table 2.3-S MPS3 Solid Waste and Irradiated Component Shipments The principal radionuclides in these tables were from shipping manifests.
Solidification Agent(s): No solidification on site Containers routinely used for radioactive waste shipment include:
55-gal Steel Drum DOT* 17-H container Steel Boxes Steel Container Steel "Sea Van" Polyethylene High Integrity Containers
- United States Department of Transportation 42 7.5 ft3 45 ft3 87 ft3 95 ft3 202. 1 ft3 1280 ft3 120.3 ft3 132.4 ft3 173.4 ft3 202. 1 ft3
Table 2.1-5 Solid Waste and Irradiated Component Shipments MPS1 January 1, 2017 through December 31, 2017 Resins, Filters, and Evaporator Bottoms Volume Curies Shipped Waste Class ft3 m3 Curies A
N/A N/A N/A B
N/A N/A N/A C
N/A N/A N/A ALL N/A N/A N/A Nuclides for the Above Table:
Radionuclide
% of Total Curies CURIES TOT AL 0
43
Table 2.1-S (continued)
Solid Waste and Irradiated Component Shipments MPS1 January 1, 2017 through December 31, 2017 Dry Active Waste Volume Curies Shipped Waste Class ft3 m3 Curies A
3.20E+02 9.05E+OO 2.73E-02 B
N/A N/A N/A C
N/A N/A N/A ALL 3.20E+02 9.05E+OO 2.73E-02 Nuclides for the Above Table:
Radionuclide
% of Total Curies C-14
< 0.01 %
1.06E-06 Fe-55 58.92%
1.61 E-02 Co-60 21.70%
5.93E-03 Ni-63 7.16%
1.96E-03 Sr-90 0.04%
1.1 OE-05 Cs-137 8.86%
2.42E-03 Pu-238
< 0.01 %
2.34E-07 Pu-239
< 0.01 %
2.15E-07 Pu-241 0.05%
1.44E-05 Am-241
< 0.01 %
8.10E-07 Cm-242
< 0.01 %
6.92E-09 Cm-244
< 0.01 %
3.51 E-07 CURIES (TOTAL) 2.73E-02 44
Table 2.1-5 (continued)
Solid Waste and Irradiated Component Shipments MPS1 January 1, 2017 through December 31, 2017 Irradiated Components Volume Curies Shipped Waste Class ft3 m3 Curies A
N/A N/A N/A B
N/A N/A N/A C
N/A N/A N/A ALL N/A N/A N/A Nuclides for the Above Table:
I Radionuclide I
% of Total Curies I
CURIES (TOT AL) 0 Other Waste Volume Curies Shipped Waste Class ft3 m3 Curies A
N/A N/A N/A B
N/A N/A N/A C
N/A N/A N/A ALL N/A N/A N/A Nuclides for the Above Table:
Radionuclide I
% of Total Curies CURIES (TOTAL) 0 45
Table 2.1-5 (continued)
Solid Waste and Irradiated Component Shipments MPS1 January 1, 2017 through December 31, 2017 Sum of All Low-Level Waste Shipped from Site Volume Curies Shipped Waste Class ft3 m3 Curies A
3.20E+02 9.05E+OO 2.73E-02 B
N/A N/A N/A C
N/A N/A N/A ALL 3.20E+02 9.05E+OO 2.73E-02 Nuclides for the Above Table:
Radionuclide
% of Total Curies C-14
< 0.01 %
1.06E-06 Fe-55 58.92%
1.61 E-02 Co-60 21.70%
5.93E-03 Ni-63 7.16%
1.96E-03 Sr-90 0.04%
1.10E-05 Cs-137 8.86%
2.42E-03 Pu-238
< 0.01 %
2.34E-07 Pu-239
< 0.01 %
2.15E-07 Pu-241 0.05%
1.44E-05 Am-241
< 0.01 %
8.10E-07 Cm-242
< 0.01%
6.92E-09 Cm-244
< 0.01 %
3.51 E-07 CURIES (TOTAL) 2.73E-02 46
Table 2.2-5 Solid Waste and Irradiated Component Shipments MPS2 January 1, 2017 through December 31, 201 7 Resins, Filters, and Evaporator Bottoms Volume Curies Shipped Waste Class ft3 m3 Curies A
8.87E+02 2.51 E+01 1.04E+01 B
NIA NIA NIA ALL 8.87E+02 2.51E+01 1.04E+01 Nuclides for the Above Table:
Radionuclide
% of Total Curies H-3 0.13%
1.41 E-02 C-14 2.41 %
2.51 E-01 Mn-54 10.70%
1.12E+OO Fe-55 28.58%
2.98E+OO Co-57 0.09%
9.36E-03 Co-58 0.73%
7.58E-02 Co-60 31.65%
3.30E+OO Ni-59 0.18%
1.92E-02 Ni-63 19.07%
1.99E+OO Sr-90 0.17%
1.78E-02 Tc-99 0.03%
3.26E-03 Ag-108m
< 0.01 %
1.92E-04 Aq-11 Om 0.43%
4.52E-02 Sn-113 0.32%
3.33E-02 Sb-125 3.70%
3.86E-01 Cs-137 1.11 %
1.16E-01 Ce-144
< 0.01 %
8.73E-05 Pu-238
< 0.01 %
2.24E-05 Pu-239
< 0.01 %
5.60E-06 Pu-241 0.02%
1.91 E-03 Am-241
< 0.01 %
1.02E-05 Cm-242
< 0.01 %
4.73E-06 Cm-244
< 0.01 %
1.23E-05 CURIES (TOTAL) 1.04E+01 47
Dry Active Waste Waste Class A
B C
ALL Table 2.2-S (continued)
Solid Waste and Irradiated Component Shipments MPS2 January 1, 2017 through December 31, 2017 Volume Curies Shipped ft3 mJ Curies 2.18E+04 6.16E+02 2.30E-01 NIA NIA NIA NIA NIA NIA 2.18E+04 6.16E+02 2.30E-01 Nuclides for the Above Table:
Radionuclide
% of Total Curies H-3 0.20%
4.67E-04 C-14 0.01 %
2.37E-05 Cr-51 3.43%
7.88E-03 Mn-54 0.96%
2.21 E-03 Fe-55 5.84%
1.34E-02 Co-57 0.03%
6.67E-05 Co-58 2.51 %
5.78E-03 Co-60 49.43%
1.14E-01 Ni-59 0.25%
5.64E-04 Ni-63 15.52%
3.57E-02 Sr-89
< 0.01 %
4.47E-06 Sr-90
< 0.01 %
8.59E-06 Zr-95 5.17%
1.19E-02 Nb-94 0.08%
1.78E-04 Nb-95 9.52%
2.19E-02 Tc-99 0.02%
5.15E-05 Aq-110m 1.06%
2.44E-03 Sn-113 0.34%
7.75E-04 Sb-125 3.95%
9.07E-03 Cs-137 0.66%
1.52E-03 Ce-144
< 0.01 %
8.34E-06 Pu-238
< 0.01 %
2.44E-06 Pu-239
< 0.01 %
2.06E-06 Pu-241 0.17%
3.84E-04 Am-241
< 0.01 %
1.04E-05 Cm-242
< 0.01 %
8.99E-07 Cm-244
< 0.01 %
3.86E-06 CURIES(TOTAL) 2.30E-01 48
Table 2.2-S (continued)
Solid Waste and Irradiated Component Shipments MPS2 January 1, 2017 through December 31, 2017 Irradiated Components Volume Curies Shipped Waste Class ft3 m3 Curies A
N/A N/A N/A B
N/A N/A N/A C
N/A N/A N/A ALL N/A N/A N/A Nuclides for the Above Table:
Radionuclide
% of Total Curies CURIES TOT AL 0
49
Other Waste Waste Class A
B C
ALL Table 2.2-S (continued)
Solid Waste and Irradiated Component Shipments MPS2 January 1, 2017 through December 31, 2017 Volume Curies Shipped ft3 mJ Curies 8.28E+02 2.34E+01 1.84E-02 N/A N/A N/A N/A N/A N/A 8.28E+02 2.34E+01 1.84E-02 Nuclides for the Above Table:
Radionuclide
% of Total Curies H-3 76.47%
1.41 E-02 C-14
< 0.01%
8.46E-09 Mn-54 0.01 %
2.63E-06 Fe-55 0.04%
6.86E-06 Co-57
< 0.01 %
1.93E-09 Co-58 0.14%
2.57E-05 Co-60 0.09%
1.69E-05 Ni-63 0.08%
1.39E-05 Zn-65
< 0.01 %
2.62E-09 Sr-89
< 0.01 %
4.61 E-08 Sr-90 3.13%
5.76E-04 Tc-99
< 0.01 %
7.81 E-07 Sb-125 0.05%
9.43E-06 Cs-137 19.94%
3.66E-03 Pu-238
< 0.01 %
1.83E-09 Pu-239
< 0.01 %
1.17E-09 Pu-241
< 0.01 %
4.55E-08 Am-241
< 0.01%
6.75E-09 Pu-240
< 0.01%
9.49E-10 Cm-242
< 0.01 %
1.14E-10 Cm-243
< 0.01 %
3.75E-09 Cm-244
< 0.01%
4.18E-09 CURIES (TOT AL) 1.84E-02 50
Table 2.2-S (continued)
Solid Waste and Irradiated Component Shipments MPS2 January 1, 2017 through December 31, 2017 Sum of All Low-Level Waste Shipped from Site Volume Curies Shipped Waste Class ft3 m3 Curies A
2.35E+04 6.65E+02 1.07E+01 B
N/A N/A N/A C
N/A N/A N/A ALL 2.35E+04 6.65E+02 1.07E+01 Nuclides for the Above Table:
Radionuclide
% of Total Curies H-3 0.27%
2.86E-02 C-14 2.35%
2.51 E-01 Cr-51 0.16%
1.68E-02 Mn-54 10.48%
1.12E+OO Fe-55 28.04%
2.99E+OO Co-57 0.09%
9.43E-03 Co-58 0.76%
8.16E-02 Co-60 31.97%
3.41 E+OO Ni-59 0.19%
1.98E-02 Ni-63 18.96%
2.03E+OO Zn-65 0.15%
1.55E-02 Sr-89 0.06%
6.13E-03 Sr-90 0.17%
1.83E-02 Zr-95 0.16%
1.70E-02 Nb-94
< 0.01 %
1.78E-04 Nb-95 0.31 %
3.26E-02 Tc-99 0.03%
3.31 E-03 Aq-108m
< 0.01 %
1.92E-04 Ag-11 Om 0.45%
4.77E-02 Sn-113 0.32%
3.41 E-02 Sb-125 3.70%
3.95E-01 Cs-137 1.13%
1.21 E-01 Ce-144
< 0.01 %
9.60E-05 Pu-238
< 0.01 %
2.48E-05 Pu-239
< 0.01 %
7.66E-06 Pu-241 0.02%
2.29E-03 Am-241
< 0.01%
2.06E-05 Pu-240
< 0.01%
9.49E-10 Cm-242
< 0.01 %
5.63E-06 Cm-243
< 0.01 %
3.75E-09 Cm-244
< 0.01 %
1.61 E-05 CURIES (TOTAL) 1.07E+01 51
Table 2.3-S Solid Waste and Irradiated Component Shipments MPS3 January 1, 2017 through December 31, 2017 Resins, Filters, and Evaporator Volume Curies Shipped Bottoms Waste Class ft" m"
Curies A
1.52E+02 4.31 E+OO 1.07E+01 B
N/A N/A N/A C
N/A N/A N/A ALL 1.52E+02 4.31 E+OO 1.07E+01 Nuclides for the Above Table:
Radionuclide
% of Total Curies H-3 1.06%
1.13E-01 C-14 1.96%
2.10E-01 Mn-54 0.83%
8.93E-02 Fe-55 3.24%
3.47E-01 Co-57 0.03%
3.16E-03 Co-58 0.23%
2.41 E-02 Co-60 2.61%
2.79E-01 Ni-59 0.43%
4.59E-02 Ni-63 37.91%
4.06E+OO Zn-65 0.01%
6.69E-04 Sr-90 0.01%
1.51 E-03 Nb-94
< 0.01%
1.94E-05 Tc-99 0.33%
3.57E-02 Ag-110m 0.02%
2.48E-03 Sb-125 50.45%
5.40E+OO Cs-134 0.10%
1.06E-02 Cs-137 0.78%
8.36E-02 Ce-144
< 0.01%
4.29E-06 Pu-238
< 0.01%
7.24E-06 Pu-239
< 0.01%
9.20E-08 Pu-241
< 0.01%
4.97E-04 Am-241
< 0.01%
1.75E-06 Cm-242
< 0.01%
3.06E-08 Cm-244
< 0.01%
5.04E-08 CURIES (TOTAL) 1.07E+01 52
Dry Active Waste Waste Class A
B C
ALL Table 2.3-S (continued)
Solid Waste and Irradiated Component Shipments MPS3 January 1, 2017 through December 31, 2017 Volume Curies Shipped ft3 m3 Curies 1.23E+04 3.49E+02 4.99E-01 NIA NIA NIA NIA NIA NIA 1.23E+04 3.49E+02 4.99E-01 Nuclides for the Above Table:
Radionuclide
% of Total Curies H-3 0.33%
1.62E-03 Cr-51 1.14%
5.67E-03 Mn-54 2.52%
1.26E-02 Fe-55 62.15%
3.1 OE-01 Fe-59 0.15%
7.24E-04 Co-57 0.06%
2.91 E-04 Co-58 2.58%
1.28E-02 Co-60 19.97%
9.96E-02 Ni-59 0.04%
2.23E-04 Ni-63 6.02%
3.00E-02 Sr-90
< 0.01 %
1.86E-05 Zr-95 1.20%
5.99E-03 Nb-94 0.03%
1.63E-04 Nb-95 2.19%
1.09E-02 Sn-113 0.06%
2.96E-04 Sb-125 0.58%
2.89E-03 Cs-137 0.95%
4.73E-03 Pu-241 0.04%
2.12E-04 Am-241
< 0.01 %
8.70E-07 Cm-242
< 0.01 %
2.31 E-07 Cm-244
< 0.01 %
6.85E-07 CURIES(TOTAL) 4.99E-01 53
Table 2.3-S (continued)
Solid Waste and Irradiated Component Shipments MPS3 January 1, 2017 through December 31, 2017 Irradiated Components Volume Curies Shipped Waste Class ft3 m3 Curies A
N/A N/A N/A B
N/A N/A N/A C
N/A N/A N/A ALL N/A N/A N/A Nuclides for the Above Table:
Radionuclide
% of Total Curies CURIES TOTAL) 0 54
Other Waste Table 2.3-5 (continued)
Solid Waste and Irradiated Component Shipments MPS3 January 1, 2017 through December 31, 2017 Volume Curies Shipped Waste Class ft3 m3 Curies A
4.50E+02 1.27E+01 8.91 E-03 B
NIA NIA NIA ALL 4.50E+02 1.27E+01 8.91E-03 Nuclides for the Above Table:
Radionuclide
% of Total Curies H-3 89.22%
7.95E-03 C-14
< 0.01 %
7.22E-09 Mn-54 0.02%
1.36E-06 Fe-55 0.03%
2.60E-06 Co-57
< 0.01 %
2.10E-09 Co-58 0.06%
5.64E-06 Co-60 0.06%
5.39E-06 Ni-63 0.04%
3.60E-06 Zn-65
< 0.01 %
2.85E-09 Sr-89
< 0.01 %
3.15E-08 Sr-90 1.42%
1.26E-04 Tc-99
< 0.01 %
3.47E-07 Sb-125 0.02%
2.07E-06 Cs-137 9.10%
8.11E-04 Pu-238
< 0.01 %
1.78E-09 Pu-239
< 0.01 %
1.11 E-09 Pu-241
< 0.01 %
1.48E-08 Am-241
< 0.01 %
6.47E-09 Pu-240
< 0.01 %
1.03E-09 Cm-242
< 0.01 %
3.73E-11 Cm-243
< 0.01 %
4.07E-09 Cm-244
< 0.01%
4.21 E-09 CURIES(TOTAL) 8.91E-03 55
Table 2.3-S (continued)
Solid Waste and Irradiated Component Shipments MPS3 January 1, 2017 through December 31, 2017 Sum of All Low-Level Waste Shipped from Site Volume Curies Shipped Waste Class ft3 m3 Curies A
1.29E+04 3.66E+02 1.12E+01 B
N/A N/A N/A C
N/A N/A N/A ALL 1.29E+04 3.66E+02 1.12E+01 Nuclides for the Above Table:
Radionuclide
% of Total Curies H-3 1.09%
1.23E-01 C-14 1.87%
2.1 OE-01 Cr-51 0.05%
5.67E-03 Mn-54 0.91 %
1.02E-01 Fe-55 5.86%
6.57E-01 Fe-59
< 0.01 %
7.24E-04 Co-57 0.03%
3.45E-03 Co-58 0.33%
3.69E-02 Co-60 3.38%
3.79E-01 Ni-59 0.41 %
4.62E-02 Ni-63 36.46%
4.09E+OO Zn-65
< 0.01 %
6.69E-04 Sr-89
< 0.01 %
3.61 E-08 Sr-90 0.01 %
1.66E-03 Zr-95 0.05%
5.99E-03 Nb-94
< 0.01 %
1.83E-04 Nb-95 0.10%
1.09E-02 Tc-99 0.32%
3.57E-02 Sn-113
< 0.01 %
2.96E-04 Sb-125 48.19%
5.41 E+OO Cs-137 0.79%
8.91 E-02 Pu-238
< 0.01 %
7.39E-06 Pu-239
< 0.01 %
2.33E-07 Pu-241
< 0.01 %
7.10E-04 Am-241
< 0.01%
2.62E-06 Pu-240
< 0.01 %
1.03E-09 Cm-242
< 0.01 %
2.61 E-07 Cm-243
< 0.01 %
4.07E-09 Cm-244
< 0.01 %
7.39E-07 CURIES(TOTAL) 1.12E+01 56
2.4 Groundwater Monitoring With the Groundwater Protection Program (GWPP) MPS implements the actions cited in the Nuclear Energy's Institute's (NEI) Groundwater Protection Initiative (Reference 9). The purpose of the GWPP is to establish a program to assure timely and effective management of situations involving potential releases of radioactive material to groundwater. A key element in the GWPP is on-site groundwater monitoring. The results of the GWPP are documented in tables below.
Another key element in the GWPP is site hydrological characterization. The general trend of groundwater flow at the station is toward the Long Island Sound. The underdrain system effectively captures groundwater in the area around MPS3 and channels this water via the storm drain system to Long Island Sound.
Table 2.4-GW (p. 1 of 3) e amp e esu s W ll S I R It H-31,2 Name Date (pCi/L)
Name MW-7C5 1/27/2017 4150 MW-7Dj 2/23/2017 7430
( cont.)
3/21/2017 4420 4/3/2017 2660 5/3/2017 3880 6/12/2017 4470 9/25/2017 4950 10/27/2017
<MDA 11/8/2017 4530 11/20/2017 3240 12/6/2017
<MDA MW-7D3 1/11/2017 8760 1/13/2017 9960 1/27/2017 8180 2/6/2017 7910 2/22/2017 6900 3/6/2017 5200 3/20/2017 4480 4/3/2017 4110 4/17/2017 2640 5/3/2017 2690 5/8/2017 2230 5/18/2017 2290 Notes: 1 -
There was no gamma radioactivity detected in these samples.
2 -
MDA is approximately 1,760 pCi/L.
H-31,i Date (pCi/L) 6/12/2017 4230 6/13/2017 3010 6/26/2017 3590 7/5/2017 4860 7/25/2017 4680 8/9/2017 6450 8/21/2017 5150 9/5/2017 7190 9/6/2017 7830 9/11/2017 7750 9/18/2017 7520 9/25/2017 8130 10/2/2017 6980 10/1 0/2017 9120 I 0/18/2017 8240 10/26/2017 6720 10/31/2017 5020 11/3/2017 4550 11/7/2017 3350 11/14/2017 3900 11/20/2017 7220 11/27/2017 5570 12/5/2017 6160 3 -
These wells are located near the MPS3 RWST which is downwind direction from the MPS3 Ventilation Vent. All or some of the H-3 detected in these wells is from releases out of the RWST vent and Ventilation Vent. Gaseous releases from the Ventilation Vent are reported in Table 2.3-A? and from the RWST vent in Table 2.3-A3. Any releases from RWST vent or Ventilation Vent which reach the groundwater are captured in sumps and underground vaults, and periodically monitored before release to the environment and reported in Table 2.3-L2. There has been no hydraulic communication with offsite groundwater.
57
Table 2.4-GW (p. 2 of 3) e amp e esu s W ll S I R It H-31,2 Name Date (pCi/L)
Name DP-102j 1/4/2017 2400 MW-GPI-08 4/11/2017 2960 8/10/2017 dry 9/5/2017 dry 11/28/2017 4130 MW-GPI-09q ME-2 7/19/2017
<MDA ME-5 7/26/2017
<MDA MW-6A 3/9/2017
<MDA 5/4/2017
<MDA 8/28/2017
<MDA 11/15/2017
<MDA MW-6B 3/8/2017
<MDA 5/4/2017
<MDA 8/25/2017
<MDA 11/15/2017
<MDA MW-GPI-02 2/2/2017
<MDA 5/10/2017
<MDA 7/17/2017
<MDA 12/1 1/2017
<MDA MW-GPI-03 7/26/2017
<MDA MW-GPI-04 4/27/2017
<MDA MW-GPI-06 1/4/2017
<MDA 4/13/2017
<MDA 8/10/2017 dry 9/5/2017 dry 11/28/2017
<MDA Notes: 1 -
There was no gamma radioactivity detected in these samples.
2 -
MDA is approximately l,760 pCi/L.
H-31,2 Date (pCi/L) 1/25/2017
<MDA 5/23/2017
<MDA 7/25/2017
<MDA 12/11/2017
<MDA 1/1 1/2017 2600 1/25/2017 4200 2/6/2017 3670 2/22/2017 3490 3/6/2017 4270 3/20/2017 2520 4/5/2017
<MDA 4/17/2017 2510 5/2/2017 2950 5/23/2017 2980 6/12/2017
<MDA 6/26/2017 2600 7/17/2017 2390 8/9/2017
<MDA 9/5/2017
<MDA 9/18/2017 2070 10/2/2017
<MDA 10/27/2017 2440 11/7/2017
<MDA 11/10/2017
<MDA 11/14/2017
<MDA 11/20/2017
<MDA 11/27/2017 2330 12/5/2017
<MDA 3 -
These wells are located near the MPS3 RWST which is downwind direction from the MPS3 Ventilation Vent. All or some of the H-3 detected in these wells is from releases out of the RWST vent and Ventilation Vent. Gaseous releases from the Ventilation Vent are reported in Table 2.3-A 7 and from the R WST vent in Table 2.3-A3. Any releases from R WST vent or Ventilation Vent which reach the groundwater are captured in sumps and underground vaults, and periodically monitored before release to the environment and reported in Table 2.3-L2. There has been no hydraulic communication with offsite groundwater.
4-Some results from MW-GPI-09 are positive. The source of tritium appears to be from the tritium being released via underground discharge tunnels. This tritium has been documented and the releases reported in another part of this report. No other leakage source has been identified.
58
Name Date MW-GPI-10 2/2/2017 5/8/2017 8/11/2017 10/10/2017 MW-GPI-1 1 1/13/2017 4/10/2017 7/31/2017 11/17/2017 Sl 1-MW-l 2/23/2017 1/30/2017 5/16/2017 8/14/2017 12/7/2017 Table 2.4-GW (p. 3 of 3)
Well Sample Results H-31,2 (pCi/L)
Name Date
<MDA Sl 2-MW-3 1/12/2017
<MDA 5/10/2017
<MDA 8/14/2017
<MDA 11/20/2017
<MDA Sl3-MW-l 2/8/2017
<MDA Sl-MW-1 1/19/2017
<MDA S3-MW-2 2/8/2017
<MDA T l 0-MW-5E 1/17/2017
<MDA T l 0-MW-6A 3/8/2017
<MDA Tl0-MW-6B 6/20/2017
<MDA Tl-MW-3 1/19/2017
<MDA
<MDA Notes: 1 -
There was no gamma radioactivity from licensed radioactive material detected in these samples.
2 -
MDA is approximately 1,760 pCi/L.
3.0 NONFUNCTIONAL Effluent Monitors H-31,2 (pCi/L)
<MDA
<MDA
<MDA
<MDA
<MDA
<MDA
<MDA
<MDA
<MDA
<MDA
<MDA During the period January 1 through December 31, 2017, the following effluent instrumentation were NONFUNCTIONAL for more than 30 consecutive days:
3.1.
MPS1 - None 3.2.
MPS2 - None 3.3.
MPS3 -
3HVR-19B - On 03/20/2017 3HVR19B, SLCRS Gas Low Range flow transmitter failed SP 3449B32, Supplemental Leak Collection and Release Operational Test and Calibration, surveillance.
Operations declared the radiation monitoring Non Functional based on the flow transmitter failing the surveillance.
As a result, condition report CR 1062683, HVR *FTl 9 unresponsive to M&TE mid-scale input signals and troubleshooting work order 53103060450 were initiated. The Maintenance Rule Functional Failure evaluation concluded that process flow indication is not required to support the gas channel indication. The troubleshooting work order required removal of the flow transmitter's circuit board, so that the vendor, FCI could repair the board. The time to develop a troubleshooting 59
work order coupled with the reliance on vendor repairs caused the 3HVR19B to be Non Functional for greater than 30 days.
The flow transmitter retested successfully on 05/11/2017 and Functionality was restored to HVR19B. All compensatory samples were taken once every seven days while the HVR19B was declared Non Functional.
4.0 Operating History The operating history of the MPS Units during this reporting period was as follows:
MPSl was shut down November 11, 1995 with a cessation of operation declared in July 1998.
MPS2 operated with a capacity factor of 89%
MPS3 operated with a capacity factor of91.7%
The power histograms for 2017 are on the following pages.
60
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MP3 - CYCLE 18/19 POWER HISTORY YEAR 2017 Note: Data at 3 Hour Interval
- 1. DOWN POWER TO 94% (1/29/17) TO FACILITATE TURBINE VALVE TESTING
- 2. DOWN POWER TO 93% (03/09/17) TO PERFORM LIFT ADJUSTMENT ON 'B' HDL PUMP
- 3. DOWN POWER TO 93% (03/20/17) FOR 'A' DSM REPAIRS
. DOWN POWER TO 88% (04/25/17) FOR ISOLATION OF "1A" FWH DUE TO STEAM LEAK
- 5. DOWN POWER TO 68% (05/15/17) FOR UNPLANNED OFF-SITE LINE OUTAGE AND TURBINE VALVE TESTING
- 6. DOWN POWER TO 93% (08/03/17) FOR TURBINE VALVE TESTING & 3HDL-LV21B1 REPAIR t--
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5.0 ERRATA Not Applicable 6.0 REMODCM Changes The description and the bases of the change(s) for REMODCM Revision 29 (effective April 4, 2017) are included here in Volume II of the Radioactive Effluent Release Report. In addition, a complete copy of the REMODCM revision is provided to the Nuclear Regulatory Commission as Volume 2 of the R d" Effl R 1 R
a 10active uent e ease eport.
REMODCM Summary of Changes in Revision 29 Pg.I ILE changed from "MPS 1 Liquid Discharge" to "Liquid Discharge Flow Rates and Monitoring Setpoints" Table I.C.-1 Pg.8 MPS unit Radioactive Liquid Waste Sampling and Analysis Program Added Footnote C to obtain grab samples for alpha, Fe-55, and Sr-90.
Table I.C-2 Pg.12 MPS2 Radioactive Liquid Waste Sam p 1 in g and Analysis Program.
Added condensate as an alternate sample for steam generator m Footnotes H&I.
I.C-2 Liquid Radioactive Waste Treatment Pg.18 I) Added ALPS/AIM Processing to MPS2 processing equipment.
- 2) In MPS2 clean liquid waste processing equipment deleted "Aerated Liquid" which was with secondary or equivalent demineralizer.
Figure I.C.-2 Simplified Liquid Effluent Flow Diagram MPS2 Pg.21 Added ALPS processing Table I.D-1 MPS l Radioactive Gaseous Waste Sampling and Analysis Programs Pages 23-24
- 1)
Added new Footnote F to require monthly gas sample from BOP Vent when SFPI ventilation is shut down and ventilation of SFPI is exhausted to BOP vent.
- 2)
Added new Footnote G to allow an alternative to tritium analysis of vent sample.
Table I.D-1 MPS3 Radioactive Gaseous Waste Sampling and Analysis Program Pg.28
- 1)
In MPS3 table (I.D-3), deleted fuel building releases.
- 2)
In Footnote F of Table l.D-3 changed numbered conditions from 3 and 4 to and 2, respectively.
Table I.E-4 Maximum Values for Lower Limit of Detection (LLD)
Pg. 44 Continued...
I) Made food products LLDs applicable to vegetation LLD.
Added a LLD of 0.093 pCi/g for fish and shellfish for 1-131 analyses.
II.A Section II -Offsite Dose Calculation Manual (ODCM) - Introduction Deleted Pg. 51 5th and 6th paragraphs.
II.D.I Gaseous Dose Calculation -Site Release Rate Limit Pg. 55
("Instantaneous") revised wording in first paragraph as shown in attached markup.
Table 111.C-3 MPS 1 Radioactive Gaseous Effluent Monitoring Instrumentation Pg. 89 l) Changed 2°d Footnote 1 to Footnote 2.
- 2)
In ACTION B changed time requirement for analysis of filter collection from 24hrs to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
- 3)
In ACTION B added the word "duration" to "24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> sample' to clarify length of sample versus time of sample.
63
Table IV. C-1 &
MPS2 & MPS3 Radioactive liquid Effluent Monitoring Instrumentation V.C-1 Change required functionality of steam generator blowdown radiation Pages 104,122 monitors from Modes 1-4 to whenever the pathway is in use.
111.D, IV.D, V.D Radioactive Effluents Concentration and Dose Limitations Pages. 91,111,
In Surveillance Requirement changed reference to "Section 11" to "Section 131 ILE."
7.0 References
- 1.
NUREG-0597, User Guide to GASP AR Code, KF Eckerman, FJ Congel, AK Roecklien, WJ Pasciak, Division of Site Safety and Environmental Analysis, Office of Nuclear Reactor Regulation, US Nuclear Regulatory Commission, Washington, DC 20555, manuscript completed January 1980, published June 1980.
- 2.
EPRI Report 1021106, Estimation of Carbon-14 m Nuclear Power Plants Gaseous Effluents, December, 2010.
- 3.
NRC Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977.
- 4.
UNSCEAR 2000 Report Vol. I, Sources and Effects of Ionizing Radiation, United Nations Scientific Committee on the Effects of Atomic Radiation
- 5.
NRC Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Revision 1, July 1977.
- 6.
NUREG/CR-1276, ORNL/NUREG/TDMC-1, User's Manual for LADT AP II - A Computer Program for Calculating Radiation Exposure to Man from Routine Release of Nuclear Reactor Liquid Effluents, DB Simpson, BL McGill, prepared by Oak Ridge National Laboratory, Oak Ridge, TN 37830, for Office of Administration, US Nuclear Regulatory Commission, manuscript completed 17 March 1980.
- 7.
10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, Appendix I, Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion "As Low As Reasonably Achievable" for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents.
- 8.
40 CFR Part 190, Environmental Radiation Protection Standard for Nuclear Power Operation.
- 9.
NEI 07-07, Nuclear Energy Institute, Industry Ground Water Protection Initiative - Final Guidance Document, August 2007.
- 10. NRC Regulatory Guide 1.21, Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste, Revision 2, October 2008.
- 12. NUREG/CR-2907, Vol. 15, Radioactive Effluents from Nuclear Power Plants Annual Report 2009, R.
Conatser, US Nuclear Regulatory Commission and N. Daugherty, Oak Ridge Associated Universities, Aug., 2013.
- 13. Radiation Protection Calculation #16-18, "Isotopic Cloud Shine Doses For MPS Releases," Jan. 24, 2017.
- 14. MP-CHEM-17-07, "Reporting of Radioactivity Released from RWST Vents," May 26, 2016.
64