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{{#Wiki_filter:Exeto:n Generation | {{#Wiki_filter:Exeto:n Generation NMP1L3211 April 19, 2018 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Nine Mile Point Nuclear Station, Units 1 and 2 10 CFR 50.36a 1 O CFR 72.44(d)(3) | ||
Technical Specifications Renewed Facility Operating License Nos. DPR-63 and NPF-69 NRC Docket Nos. 50-220 and 50-410 | |||
==Subject:== | ==Subject:== | ||
2017 Radioactive Effluent Release Report for Nine Mile Point Units 1 and 2 In accordance with | Independent Spent Fuel Storage Installation (ISFSI) | ||
The format used for the effluent data is outlined in Appendix B of Regulatory Guide 1.21, Revision 1. During the reporting period, NMP1, NMP2, and the ISFSI did not exceed any | ISFSI Docket No. 72-1036 2017 Radioactive Effluent Release Report for Nine Mile Point Units 1 and 2 In accordance with 1 O CFR 50.36a, and the Nine Mile Point Unit 1 (NMP1) and Nine Mile Point Unit 2 (NMP2) Technical Specifications, enclosed are the Radioactive Effluent Release Reports for NMP1 and NMP2 for the period of January through December 2017. | ||
This letter also satisfies the annual effluent reporting requirements for the ISFSI required by 10 CFR 72.44(d)(3). | |||
The format used for the effluent data is outlined in Appendix B of Regulatory Guide 1.21, Revision 1. During the reporting period, NMP1, NMP2, and the ISFSI did not exceed any 1 O CFR 20, 1 O CFR 50, 1 O CFR 72, Technical Specification, or ODCM limits for gaseous or liquid effluents. | |||
Should you have questions regarding the information in this submittal, please contact Tom Tanguay, Site Chemistry Environmental & Radwaste Manager, at (315) 349-4264. | Should you have questions regarding the information in this submittal, please contact Tom Tanguay, Site Chemistry Environmental & Radwaste Manager, at (315) 349-4264. | ||
Sincerely, | Sincerely, Peter M. Orphanos Vice President, Nine Mile Point Nuclear Station Exelon Generation Company, LLC PMO/RSP z __ | ||
Peter M. Orphanos Vice President, Nine Mile Point Nuclear Station Exelon Generation Company, LLC PMO/RSP | |||
-----~-------------------------------------------- | -----~-------------------------------------------- | ||
Document Control Desk April 19, 2018 Page2 | Document Control Desk April 19, 2018 Page2 | ||
==Enclosures:== | ==Enclosures:== | ||
(1) | (1) | ||
Radioactive Effluent Release Report, January- December 2017 (2) | Nine Mile Point Nuclear Station, Unit 1. | ||
Radioactive Effluent Release Report, January-December 2017 (2) | |||
Nine Mile Point Nuclear Station, Unit 2 Radioactive Effluent Release Report, January - December 2017 Cc: | |||
NRG Regional Administrator, Region 1 NRG Project Manager NRG Resident Inspector R. Rolph, NRG | |||
NINE MILE POINT NUCLEAR STATION - UNIT 1 RADIOACTIVE EFFLUENT RELEASE REPORT January- December 2017 | NINE MILE POINT NUCLEAR STATION - UNIT 1 RADIOACTIVE EFFLUENT RELEASE REPORT January-December 2017 | ||
Page 1 of2 NINE MILE POINT NUCLEAR STATION - UNIT 1 RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY-DECEMBER2017 SUPPLEMENTAL INFORMATION Facilitv: Nine Mile Point Unit 1 | Page 1 of2 NINE MILE POINT NUCLEAR STATION - UNIT 1 RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY-DECEMBER2017 SUPPLEMENTAL INFORMATION Facilitv: Nine Mile Point Unit 1 Licensee: | ||
: 1. TECHNICAL SPECIFICATION LIMITS/ODCM Limits A) | Nine Mile Point Nuclear Station, LLC | ||
: 1. The dose rate limit of noble gases released in gaseous eftluents from the site to areas at and beyond the site boundary shall be less than or equal to 500 mrem/year to the total body and less than or equal to 3000 mrem/year to the skin. | : 1. | ||
: 2. The air dose due to noble gases released in gaseous effluents from Nine Mile Point Unit 1 to areas at and beyond the site boundary shall be limited during any calendar quarter to less than or equal to 5 milliroentgen for gamma radiation and less than or equal to 10 mrad for beta radiation, and during any calendar year to less than or equal to l O milliroentgen for gamma radiation and less than or equal to 20 1mad for beta radiation. | TECHNICAL SPECIFICATION LIMITS/ODCM Limits A) | ||
FISSION AND ACTIVATION GASES | |||
: 1. | |||
The dose rate limit of noble gases released in gaseous eftluents from the site to areas at and beyond the site boundary shall be less than or equal to 500 mrem/year to the total body and less than or equal to 3000 mrem/year to the skin. | |||
: 2. | |||
The air dose due to noble gases released in gaseous effluents from Nine Mile Point Unit 1 to areas at and beyond the site boundary shall be limited during any calendar quarter to less than or equal to 5 milliroentgen for gamma radiation and less than or equal to 10 mrad for beta radiation, and during any calendar year to less than or equal to l O milliroentgen for gamma radiation and less than or equal to 20 1mad for beta radiation. | |||
B&C) TRITIUM, IODINES AND PARTICULATES, HALF LIVES> 8 DAYS | B&C) TRITIUM, IODINES AND PARTICULATES, HALF LIVES> 8 DAYS | ||
: 1. The dose Tate limit of Iodine-131, Iodine-133, Tritium and all radionuclides in particulate form with half-lives greater than eight days, released in gaseous effluents from the site to areas at mid beyond the site boundary shall be less than or equal to 1500 rnrem/year to any organ. | : 1. | ||
: 2. The dose to a member of the public fro!I). Iodine-131, Iodine-133, Tritium and all radionuclides in particulate | The dose Tate limit of Iodine-131, Iodine-133, Tritium and all radionuclides in particulate form with half-lives greater than eight days, released in gaseous effluents from the site to areas at mid beyond the site boundary shall be less than or equal to 1500 rnrem/year to any organ. | ||
: 2. | |||
The dose to a member of the public fro!I). Iodine-131, Iodine-133, Tritium and all radionuclides in particulate | |||
* form with half-lives greater than eight days in gaseous effluents released from Nine Mile Point Unit 1 to. | * form with half-lives greater than eight days in gaseous effluents released from Nine Mile Point Unit 1 to. | ||
areas at and beyond the site boundmy shall be limited during any calendar quarter to less than or equal to 7.5 mrem to any organ, and during any calendar year to less than or equal to 15 mrem to any organ. | areas at and beyond the site boundmy shall be limited during any calendar quarter to less than or equal to 7.5 mrem to any organ, and during any calendar year to less than or equal to 15 mrem to any organ. | ||
D) | D) | ||
: 1. The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to ten times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-04 microcuries/ml total activity. | LIQUID EFFLUENTS | ||
: 2. The dose or dose conunitment to a member of the public from radioactive materials in liquid effluents released from Nine Mile Point Unit 1 to unrestricted areas shall be limited during any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 1mem to any organ, and during any calendar year to less than or equal to 3 rnrem to the total body and to less than or equal to 10 rnrem to any organ. | : 1. | ||
The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to ten times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-04 microcuries/ml total activity. | |||
: 2. | |||
The dose or dose conunitment to a member of the public from radioactive materials in liquid effluents released from Nine Mile Point Unit 1 to unrestricted areas shall be limited during any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 1mem to any organ, and during any calendar year to less than or equal to 3 rnrem to the total body and to less than or equal to 10 rnrem to any organ. | |||
Page 2 of2 | Page 2 of2 | ||
: 2. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY Described below are the methods used to measure or approximate the total radioactivity and radionuclide composition in effluents. | : 2. | ||
A) | MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY Described below are the methods used to measure or approximate the total radioactivity and radionuclide composition in effluents. | ||
B) | A) | ||
C) | FISSION AND ACTIVATION GASES Noble gas effluent activity is detem1ined by on-line gross activity monitoring (calibrated against gamma isotopic analysis of a 4.0L Marinelli grab sample) of an isokinetic stack sample stream. | ||
D) | B) | ||
E) | IODINES Iodine effluent activity is determined by gamma spectroscopic analysis (at least weekly) of charcoal cartridges sampled from an isokinetic stack sample stream. | ||
F) | C) | ||
G) | PARTICULATES Activity released from the main stack is determined by gamma spectroscopic analysis (at least weekly) of particulate filters sampled from an isokinetic sample stream and composite analysis of the filters for non-gamma emitters. | ||
H) | D) | ||
: 3. METEOROLOGICAL DATA An annual summary of hourly meteorological data collected over the previous year. This annual surnn1ary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distribution of wind speed, wind direction, and atmospheric stability. In lieu of submission with the Radiological Effluent Release Report, the licensee is exercising the option of retaining this summa1y of required meteorological data on site in a file that shall be provided to the NRC upon request. | TRITIUM Tritium effluent activity is measured by liquid scintillation or gas proportional counting of monthly samples taken with an air sparging/water trap apparatus. Tritium effluent activity is measured during pm-ge and weekly when foe! is offloaded until stable tritium release rates are demonstrated. | ||
E) | |||
EMERGENCY CONDENSER VENT EFFLUENTS The effluent curie quantities are estimated based on the isotopic distribution in the Condensate Storage Tank water and the Emergency Condenser shell water. | |||
Actual isotopic concentrations are found via gamma spectroscopy. Initial release rates of Sr-89, Sr-90 and Fe-55 are e*stimated by applying scaling factors to release rates of gamma emitters and actual release rates are determined from post offsite analysis results. The activity of fission and activation gases released due to tube leaks is based on reactor steam leak rates using offgas isotopic analyses. | |||
F) | |||
LIQUID EFFLUENTS Isotopic contents of liquid effluents are detennined by isotopic analysis of a representative sample of each batch and composite analysis of non-gamma emitters. Tritium activity is estimated on the most recent analysis of the Condensate Storage Tank water. Initial release rates ofSr-89, Sr-90, and Fe-55. are estimated by applying scaling factors to release rates of gamma emitters and achial release rates are determined from post offsite analysis results. | |||
G) | |||
SOLID EFFLUENTS Isotopic contents of waste shipments are deter1nined by gamma spectroscopy analysis of a representative* sample of each batch. Scaling factors established from primary composite sample analyses conducted off-site are applied, where appropriate, to find estimated concentration of non-gamma emitters. For low activity trash shipments, curie content is estimated by dose rate measurement and application of appropriate scaling factors. | |||
H) | |||
C-14 The production of C-14 and the effluent dose consequences are estimates based on EPRI methodology provided in EPRI Report 1021106, Estimation ofCarbon-14 in Nuclear Power Plant Gaseous Effluents, Dec;ember 2010 and NUREG-0016, Calculation of Releases of Radioactive Materials in Gaseous and Liquid Ejjl.uents for Boiling Water Reactors (BWR-GALE Code). | |||
: 3. | |||
METEOROLOGICAL DATA An annual summary of hourly meteorological data collected over the previous year. This annual surnn1ary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distribution of wind speed, wind direction, and atmospheric stability. In lieu of submission with the Radiological Effluent Release Report, the licensee is exercising the option of retaining this summa1y of required meteorological data on site in a file that shall be provided to the NRC upon request. | |||
ATTACHMENT 1 | ATTACHMENT 1 Page 1 of 2 Unit 1 X | ||
Unit2 Re12orting Period: Janua!J£ - December 2017 Liquid Effluents: | |||
ODCM Required Maximum Effluent Concentration (MEC) = 10 x 10CFR20, Appendix B, Table 2, Column 2 There were no batch discharges of liquid radwaste requiring use of MEC to determine allowable release rate. | ODCM Required Maximum Effluent Concentration (MEC) = 10 x 10CFR20, Appendix B, Table 2, Column 2 There were no batch discharges of liquid radwaste requiring use of MEC to determine allowable release rate. | ||
There were no Emergency Condenser Vent Liquid Discharges in 2017. | There were no Emergency Condenser Vent Liquid Discharges in 2017. | ||
Average MEC - µCi/ml (Qtr.1) = | Average MEC - µCi/ml (Qtr.1) = | ||
Qrtr.1: | I NO RELEASES Average MEC - µCi/ml (Qtr.1) = | ||
Number of Batch Releases | I NO RELEASES I Average MEC- µCi/ml (citr.2_) = | ||
Number of Batch Releases | I NO RELEASES Average MEC - µCi/ml (Qtr..4) = | ||
Total Time Period for Batch Releases (hrs) | I NO RELEASES I Average Energy (Fission and Activation gases - MeV): | ||
Qrtr.1: | |||
Ey = | |||
N/A E13 = | |||
N/A Qrtr.2_: | |||
§v = | |||
N/A | |||
§13 = | |||
N/A Qrtr. J.: | |||
~y = | |||
N/A E13 = | |||
N/A Qrtr.1: | |||
Ey = | |||
N/A E13 = | |||
N/A Liquid: | |||
Radwaste EC Vent Number of Batch Releases 0 | |||
0 Total Time Period for Batch Releases (hrs) 0 0.00 Maximum Time Period for a Batch Release (hrs) 0 0.00 Average Time Period for a Batch Release (hrs) 0 0.00 Minimum Time Period for a Batch Release (hrs) 0 0.00 Total volume of water used to dilute | |||
. 1st 2nd 3rd 4th the liquid effluent during release period (L) | |||
Radwaste I N/A I | |||
N/A I | |||
N/A I | |||
N/A I | |||
Total volume of water available to 1st 2nd 3rd 4th dilute the liquid effluent during report period (L) | |||
Radwaste I 1.11E+11 I 1.26E+11 I 1.31E+11 I 1.30E+11 I Gaseous(Emergency Condenser Vent): | |||
Number of Batch Releases 0 | |||
Total Time Period for Batch Releases (hrs) 0.00 Maximum Time Period for a Batch Release (hrs) 0.00 Average Time Period for a Batch Release (hrs) 0.00 Minimum Time Period for a Batch Release (hrs) | |||
- 0.00 Gaseous (Primary Containment Purge): | |||
Number of Batch Releases 2* | |||
Total Time Period for Batch Releases (hrs) 10.58 Maximum Time Period for a Batch Release (hrs) 5.73 Average Time Period for a Batch Release (hrs) 5.29 Minimum Time Period for a Batch Release (hrs) 4.85 | |||
ATTACHMENT .1 | ATTACHMENT.1 Page 2 of2 Unit 1 X | ||
Unit 2 Reporting Period: January - December 2017 Abnormal Releases: | |||
A. Liquids: | A. Liquids: | ||
I Number of Releases I | |||
0 I | |||
I Number of Releases | !Total Activity Released I | ||
NIA ICi B. Gaseous: | |||
I Number of Releases I | |||
0 I | |||
!Total Activity Released I | |||
N/A ICi Since 2003, the Emergency Condensers have been actuated 7 times. These are identified in the 2003, 2004, 2009, 2010 and 2013 RERRs. The perimeter drain pumps were out of service between 2008 and 2012. Releases prior to that are assumed to have been dicharged to the storm drains while the pumps were functional. | |||
In August 2012, tritium was identified in ground water outside Unit 1. Subsequent investigations determined the source of tritium was Emergency Condenser Vent discharges (during periodic testing, as well as past events). Per the ODCM, and through station procedures, the gaseous and liquid effluent releases to the environment via the Emergency Condenser pathway are analyzed and reported in the monthly effluent releases and reported annually in the Radioactive Effluent Release Report (RERR). As a result of this discovery, the Unit 1 ODCM was revised (Revision 34) to require composite samples of discharges from the Reactor Building Perimeter Drain be collected and analyzed, and total curies reported in the RERR Because this activity has been accounted for in previous RERRs, it is to be reported as a separate item, and not included in the liquid releases (Attachment 5). | In August 2012, tritium was identified in ground water outside Unit 1. Subsequent investigations determined the source of tritium was Emergency Condenser Vent discharges (during periodic testing, as well as past events). Per the ODCM, and through station procedures, the gaseous and liquid effluent releases to the environment via the Emergency Condenser pathway are analyzed and reported in the monthly effluent releases and reported annually in the Radioactive Effluent Release Report (RERR). As a result of this discovery, the Unit 1 ODCM was revised (Revision 34) to require composite samples of discharges from the Reactor Building Perimeter Drain be collected and analyzed, and total curies reported in the RERR Because this activity has been accounted for in previous RERRs, it is to be reported as a separate item, and not included in the liquid releases (Attachment 5). | ||
On September 6, 2017 from 11 :58 to 12:04, #11 Emergency Condenser String inlet and outlet isolation valves were opened. System parameters were monitored. Condenser temperatures never reached boiling as the temperature reached a maximum of 165°F for shell #111 and 182.°F for shell #112. For the remainder of the month, average shell temperature was between B6° and 100° F. The outside of the reactor building where the vents are located was visually inspected. Below and surrounding the vents showed no indication that ariy liquid discharge took place. For this reason, it is concluded that an emergency condenser liquid release did not take place and is not documented in this report. | On September 6, 2017 from 11 :58 to 12:04, #11 Emergency Condenser String inlet and outlet isolation valves were opened. System parameters were monitored. Condenser temperatures never reached boiling as the temperature reached a maximum of 165°F for shell #111 and 182.°F for shell #112. For the remainder of the month, average shell temperature was between B6° and 100° F. The outside of the reactor building where the vents are located was visually inspected. Below and surrounding the vents showed no indication that ariy liquid discharge took place. For this reason, it is concluded that an emergency condenser liquid release did not take place and is not documented in this report. | ||
ATTACHMENT 2 | ATTACHMENT 2 Page 1 of 1 Unit 1 X | ||
A. l-'1ss1on & Activation Gases 11-l | Unit2 Re(!orting Period: Januaot: - December 2017 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES, ELEVATED AND GROUND LEVEL 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter EST. TOTAL ERROR,% | ||
A. l-'1ss1on & Activation Gases 11-l | |||
. s:*:--*:,;..,.';_,J.)'J~i | |||
: 2. Average Release Rate | : 1. | ||
: 1. Total Iodine - 131 | *Total Release Ci I | ||
: 2. Average Release Rate for Period | I I | ||
:?":f'"'*I | |||
: 1. Particulates with Half-lives>8 days | .. I 5.00E+01 | ||
: 2. Average Release Rate for Period | : 2. | ||
Average Release Rate | |||
µCi/sec B. Iodines (1l | |||
2.31E-04 3.21E-05 | : 1. | ||
: 1. Total Release | Total Iodine - 131 Ci I | ||
: 2. Average Release Rate for Period | 1.03E-05 I | ||
.. I I | |||
Percent of Quarterly Beta Air Dose Limit | .. I 3.00E+01 | ||
: 2. | |||
Percent of Annual Gamma Air Dose Limit | Average Release Rate for Period | ||
µCi/sec 1.31E-06 C. Particulates (1l | |||
: 1. | |||
Percent of Whole Body Dose Rate Limit | Particulates with Half-lives>8 days Ci 1.82E-03 2.52E-04 1.93E-04 1.64E-04 3.00E+01 | ||
: 2. | |||
Percent of Skin Dose Rate Limit (3000 | Average Release Rate for Period | ||
µCi/sec 2.31E-04 3.21E-05 2.65E-05 2.09E-05 | |||
: 3. | |||
Gross Alpha Radioactivity Ci 2.50E+01 D. Tritium (1) | |||
: 1. | |||
Total Release Ci 1.94E+01 1.77E+01 1.79E+01 9.62E+OO 5.00E+01 | |||
: 2. | |||
Average Release Rate for Period | |||
µCi/sec 2.48E+OO 2.25E+OO 2.41E+OO 1.22E+OO E. Percent of Tech. S(!ec. Limits Fission and Activation Gases Percent of Quarterly Gamma Air Dose O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Limit (5 mR) | |||
Percent of Quarterly Beta Air Dose Limit O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO (19 mrad) | |||
Percent of Annual Gamma Air Dose Limit 0.00E+OO 0.00E+OO O.OOE+OO O.OOE+OO to Date (10 mR) | |||
Percent of Annual Beta Air Dose Limit to 0.00E+OO O.OOE+OO 0.00E+OO O.OOE+OO Date (20 mrad) | |||
Percent of Whole Body Dose Rate Limit O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO (500 mrem/yr) | |||
Percent of Skin Dose Rate Limit (3000 O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO mrem/yr) | |||
Tritium, Iodines, and Particulates (with half-lives greater than 8 days) | Tritium, Iodines, and Particulates (with half-lives greater than 8 days) | ||
Percent of Quarterly Dose Limit (7 .5 | Percent of Quarterly Dose Limit (7.5 7.68E-02 1.31E-02 1.55E-02 9.56E-03 mrem) | ||
Percent of Annual Dose Limit to Date (15 3.84E-02 4.49E-02 5.27E-02 5.74E-02 mrem) | |||
Percent of Annual Dose Limit to Date (15 | Percent of Organ Dose Limit (1500 1.56E-03 2.62E-04 3.07E-04 1.90E-04 mrem/yr (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. | ||
Percent of Organ Dose Limit (1500 | |||
ATTACHMENT 3 | ATTACHMENT 3 Page 1 of2 Unit 1 X | ||
Nuclides Released | Unit2 Reeorting Period: Janua!]£ - December 2017 GASEOUS EFFLUENTS-ELEVATED RELEASE Continuous Mode (2) | ||
Krypton-85m Krypton-87 Ci | Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Fission Gases {1l Argon-41 Ci Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-127 Ci Xenon-131m Ci Xenon-133 Ci Xenon-133m Ci Xenon-135 Ci Xenon-135m Ci Xen_on-137 Ci Xenon-138 Ci Iodines {1) lodine-131 Ci 1.03E-05 lodine-133 Ci lodine-135 Ci Particulates {1 l Strontium-89 Ci 7.21E-05 2.0?E-05 7.61E-05 7.65E-05 Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci Cobalt-60 Ci 1.26E-03 8.81E-05 1.17E-04 8.78E-05 Cobalt-58 Ci 9.21E-05 Manganese-54 Ci 6.04E-05 4.62E-06 Barium-140 Ci Ladthanum-140 Ci Niobium-95 Ci Cerium-141 Ci Cerium-144 Ci lron-59 Ci Cesium-136 Ci Chromium-51 Ci 1.91E-04 Zinc-65 Ci lron-55 Ci 1.38E-04 1.39E-04 Molybdenum-99 Ci Neodymium-14 7 Ci Tritium {1l Ci I 1.53E+01 I -1.45E+01 I 1.34E+01 I 7.58E+OO I (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower li_mit of detection of 1.00E-04 µCi/ml for required noble gases, 1.00E-11 µCi/ml for required particulates, 1.00E-12 µCi/ml for required Iodines, and 1.00E-06 µCi/ml for Tritium as required by the ODCM, has been verified. | ||
Krypton-88 Xenon-127 Ci | (2) Contributions from purges are included. There_were no other batch releases during the reporting period. | ||
Xenon-131m | |||
Xenon-133 Xenon-133m | |||
Ci | |||
Xenon-135m Xen_on-137 Xenon-138 | |||
lodine-133 lodine-135 Ci | |||
Particulates {1 l Strontium-89 | |||
7.21E-05 2.0?E-05 7.61E-05 7.65E-05 Cesium-134 Cesium-137 Ci | |||
Cobalt-60 | |||
Cerium-144 lron-59 Ci | |||
Cesium-136 Chromium-51 | |||
Zinc-65 | |||
lron-55 | |||
1.38E-04 1.39E-04 Neodymium- | |||
(2) Contributions from purges are included. There_were no other batch releases during the reporting period. | |||
ATTACHMENT 3 | ATTACHMENT 3 Page 2 of 2 Unit 1 X | ||
Nuclides Released | Unit2 Reeorting Period: JanuaO! - December 2017 GASEOUS EFFLUENTS-ELEVATED RELEASE Batch Mode (2) | ||
Krypton-87 | Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Fission Gases {1l Argon-41 Ci Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-127 Ci Xenon~131m Ci Xenon-133 Ci | ||
Krypton-88 | *~ | ||
Xenon-133 | Xenon-133m Ci Xenon-135 Ci Xenon-135m Ci Xenon-137 Ci Xenon-138 Ci Iodines (1) lodine-131 Ci I | ||
I I | |||
Xenon-133m | I | ||
Xenon-135 | ** I lodine-133 Ci lodine-135 Ci Particulates (1 l Strontium-89 Ci Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci Cobalt-60 Ci Cobalt-58 Ci Manganese-54 Ci 0 | ||
Iodines (1) lodine-131 | Barium-140 Ci Lanthanum-140 Ci Niobium-95 Ci Cerium-141 Ci Cerium-144 Ci lron-59 Ci Cesium-136 Ci Chromium-51 Ci Zinc-65 Ci lron-55 Ci Molybdenum-99 Ci Neodymium-14 7 Ci Tritium (1) | ||
lodine-133 lodine-135 Ci | Ci I.. | ||
Strontium-90 | I I | ||
I I | |||
Niobium-95 | (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of 1.00E-04 µCi/ml for required noble gases, 1.00E-11 µCi/ml for required particulates, 1.00E-12 µCi/ml for required Iodines, and 1.00E-06 µCi/ml for Tritium as required by the ODCM, has been verified. | ||
Cesium-136 | (2) Contributions from purges, if any, are included. There were no other batch releases during the reporting period. | ||
Tritium (1) | |||
(2) Contributions from purges, if any, are included. There were no other batch releases during the reporting period. | |||
ATTACHMENT 4 | ATTACHMENT 4 Page 1 of 2 Unit 1 X | ||
Continuous Mode Nuclides Released | Unit2 Re12orting Period: Januarl£ - December 2017 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Ground level releases are determined in accordance with the Off-Site Dose Calculation Manual and Chemistry procedures. | ||
Argon-41 | Continuous Mode Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Fission Gases (1) | ||
Krypton-85 | Argon-41 Ci Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-127 Ci Xenon-131m Ci Xenon-133 Ci Xenon-133m Ci Xenon-135 Ci* | ||
Krypton-85m Krypton-87 Ci | Xenon-135m Ci Xenon-137 Ci Xenon-138 Ci Iodines (1\\ | ||
Krypton-88 Xenon-127 Ci | lodine-131 Ci I | ||
Xenon-131m Xenon-133 Ci | I I | ||
Xenon-133m | I I | ||
Xenon-135m | lodine-133 Ci lodine-135 Ci Particulates {1 l Strontium-89 Ci Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci Cobalt-60 Ci 4.41E-08 Cobalt-58 Ci 2.85E-08 Manganese-54 Ci 7.91E-09 Barium-140 Ci Lanthanum-140 Ci Niobium-95 Ci Cerium-141 Ci Cerium-144 Ci lron-59 Ci Cesium-136 Ci Chromium-51 Ci Zinc-65 Ci lron-55 Ci Molybdenum-99 Ci Neodymium-147 Ci Tritium {11 Ci I 4.16E+OO I 3.19E+OO I 4.45E+OO I 2.03E+OO I (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. | ||
Iodines (1\ | |||
lodine-131 | |||
lodine-133 lodine-135 Ci | |||
Strontium-90 Cesium-134 Ci | |||
Cesium-137 | |||
Cesium-136 | |||
Chromium-51 Zinc-65 Ci | |||
lron-55 | |||
Molybdenum-99 Neodymium-147 Ci | |||
Tritium {11 | |||
ATTACHMENT 4 | ATTACHMENT 4 Page 2 of2 Unit 1 X | ||
Batch Mode Nuclides Released | Unit2 Rei;?orting Period: Janua~ - December 2017 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES Ground level releases are determined in accordance with the Off-Site Dose Calculation Manual and Chemistry procedures. | ||
Krypton-88 | Batch Mode Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Fission Gases (1 l Argon-41 Ci Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-127 Ci Xenon-131m Ci Xenon-133 Ci Xenon-133m Ci Xenon-135 Ci Xenon-135m Ci Xenon-137 Ci Xenon-138 Ci Iodines (1} | ||
Xenon-127 Xenon-131m | lodine-131 Ci I | ||
Xenon-137 | I I | ||
Xenon-138 | I I | ||
Iodines (1} | lodine-133 Ci lodine-135 Ci Particulates (1 l Strontium-89 Ci Strontium-9Q Ci Cesium-134 Ci Cesium-137 Ci Cobalt-60 Ci Cobalt-58 Ci Manganese-54 Ci Barium-140 Ci Lanthanum-140 Ci Niobium-95 Ci Cerium-141 Ci Cerium-144 Ci lron-59 Ci Cesium-136 Ci Chromium-51 Ci Zinc-65 Ci lron-55 Ci Molybdenum-99 Ci Neodymium-147 Ci Tritium (1} | ||
lodine-131 | Ci I | ||
I | I I | ||
lodine-135 | I I | ||
Strontium-9Q Cesium-134 Ci | (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. | ||
Cesium-137 Cobalt-60 Ci | |||
Cobalt-58 | |||
Manganese-54 Barium-140 Ci | |||
Lanthanum-140 | |||
Niobium-95 Cerium-141 Ci | |||
Cerium-144 lron-59 Ci | |||
Cesium-136 Chromium-51 Ci | |||
Zinc-65 lron-55 Ci | |||
Molybdenum-99 Neodymium-147 Ci | |||
Tritium (1} | |||
ATTACHMENT 5 | ATTACHMENT 5 Page 1 of 2 Unit 1 X | ||
Unit2 Reeorting Period: Januaot: - December 2017 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES (1) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Est. Total Error, % | |||
A. t-1ss1on & Act1vat1on Products | A. t-1ss1on & Act1vat1on Products | ||
: 1. Total Release (not including Tritium, Ci | : 1. Total Release (not including Tritium, Ci No Releases No Releases No Releases No Releases 5.00E+01 gases, alpha) | ||
: 2. Average diluted concentration during | : 2. Average diluted concentration during | ||
µCi/ml No Releases No Releases No Releases No Releases reporting period B. Tritium 1.Total release Ci No Releases No Releases No Releases No Releases 5.00E+01 | |||
: 2. Average diluted concentration during | : 2. Average diluted concentration during | ||
µCi/ml No Releases No Releases No Releases No Releases the reporting period C. Dissolved and Entrained Gases | |||
: 1. Total release | : 1. Total release Ci No Releases No Releases No Releases No Releases 5.00E+01 | ||
: 2. Average diluted concentration during | : 2. Average diluted concentration during | ||
µCi/ml No Releases. No Releases No Releases No Releases the reporting period D. Gross Al12ha Radioactivit'.l | |||
: 1. Total release | : 1. Total release Ci No Releases No Releases No Releases No Releases 5.00E+01 | ||
-E. Volumes | |||
: 1. Prior to Dilution | : 1. Prior to Dilution Liters No Releases No Releases 1.89E+03 No Releases 5.00E+01 | ||
: 2. Volume of dilution water used during Liters | : 2. Volume of dilution water used during Liters No Releases No Releases O.OOE+OO No Releases 5.00E+01 release period | ||
: 3. Volume of dilution water available Liters | : 3. Volume of dilution water available Liters 1.11E+11 1.26E+11 1.31E+11 1.30E+11 5.00E+01 during reporting period - Cooling Water F. Percent of Tech. S12ec. Limits Percent of Quarterly Whole Body Dose No Releases No Releases No Releases No Releases Limit (1.5 mrem) | ||
Percent of Annual Whole Body Dose No Releases No Releases No Releases No Releases Limit to Date (3 mrem) | |||
Percent of Annual Whole Body Dose | Percent of Quarterly Organ Dose Limit No Releases No Releases No Releases No Releases (5 mrem) | ||
Percent of Annual Organ Dose Limit to No Releases No Releases No Releases No Releases Date (10 mrem) | |||
Percent of Quarterly Organ Dose Limit | Percent of 1 OCFR20 Concentration No Releases No Releases No Releases No Releases Limit Percent of Dissolved or Entrained Noble Gas Limit (2.00E-04 µCi/ml) | ||
No Releases No Releases No Releases No Releases (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. | |||
Percent of Annual Organ Dose Limit to | |||
Percent of | |||
(1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. | |||
ATTACHMENT 5 | ATTACHMENT 5 Page 2 of2 Unit 1 X | ||
Nuclides Released | Unit 2 Reeorting Period: Januarll: - December 2017 LIQUID EFFLUENTS RELEASED Batch Mode (1 ),(2) | ||
(2) Concentrations less than the lower limit of detection of the counting system used have been verified for sampled effluents. A lower limit of detection of 5.00E-07 µCi/ml for required gamma emitting nuclides, 1.00E-05 µCi/ml for required dissolved and entrained noble gases and tritium, 5.00E-08 µCi/ml for Sr-89/90, 1.00E-06 µCi/ml for 1-131 and Fe-55, and 1.00E-07 µCi/ml for gross alpha radioactivity, as identified in the ODCM, has been verified. Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. | Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Nuclides Released Strontium-89 Ci No Releases No Releases No Releases No Releases Strontium-90 Ci No Releases No Releases No Releases No Releases Cesium-134' Ci No Releases No Releases No Releases No Releases Cesium-137 Ci No Releases No Releases No Releases No Releases lodine-131 Ci No Releases No Releases No Releases No Releases Cobalt-58 Ci No Releases No Releases No Releases No Releases Cobalt-60 Ci No Releases No Releases No Releases No Releases lron-59 Ci No Releases No Releases No Releases No Releases Zinc-65 Ci No Releases No Releases No Releases No Releases Manganese-54 Ci No Releases No Releases No Releases No Releases Chromium-51 Ci No Releases No Releases No Releases No Releases Zirconium-95 Ci No Releases No Releases No Releases No Releases Niobium-95 Ci No Releases No Releases No Releases No Releases Molybdenum-99 Ci No Releases No Releases No Releases No Releases Barium-140 Ci No Releases No Releases No Releases No Releases Lanthanum-140 Ci No Releases No Releases No Releases No Releases Cerium-141 Ci No Releases No Releases No Releases No Releases lodine-133 Ci No Releases No Releas'es No Releases No Releases lron-55 Ci No Releases No Releases No Releases No Releases Cerium-144 Ci No Releases No Releases No Releases No Releases Cesium-136 Ci No Releases No Releases No Releases No Releases Copper-64 Ci No Releases No Releases No Releases No Releases Manganese-56 Ci No Releases No Releases No Releases No Releases Nickel-65 Ci No Releases No Releases No Releases No Releases Sodium-24 Ci No Releases No Releases No Releases No Releases Dissolved or Entrained Gases Ci No Releases No Releases No Releases No Releases Tritium Ci No Releases No Releases No Releases No Releases (1) No continuous mode release occurred during the report period as indicated by effluent sampling. There were no Radwaste Batch Releases. | ||
(2) Concentrations less than the lower limit of detection of the counting system used have been verified for sampled effluents. A lower limit of detection of 5.00E-07 µCi/ml for required gamma emitting nuclides, 1.00E-05 µCi/ml for required dissolved and entrained noble gases and tritium, 5.00E-08 µCi/ml for Sr-89/90, 1.00E-06 µCi/ml for 1-131 and Fe-55, and 1.00E-07 µCi/ml for gross alpha radioactivity, as identified in the ODCM, has been verified. Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. | |||
ATTACHMENT 6 | ATTACHMENT 6 Page 1 of4 Unit 1 X | ||
Unit2 Re12orting Period: Janua!Jl - December 2017 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A1. TYPE Volume Activi~ (1l (m3) | |||
A | (Ci) | ||
Totals | ~ | ||
: d. Other (to vendor for processing) d.1 Sewage Sludge | ~ | ||
A B | |||
C A | |||
B C | |||
a.1 Spent Resin (Dewatered) 2.02E+01 O.OOE+OO O.OOE+OO 1.66E+02 O.OOE+OO O.OOE+OO a.2 Filter Sludge O.OOE+OO 9.49E+OO O.OOE+OO O.OOE+OO 4.67E+02 O.OOE+OO a.3 Concentrated Waste O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Totals 2.02E+01 9.49E+OO O.OOE+OO 1.66E+02 4:67E+02 0.00E+OO b.1 Dry Compressible Waste* | |||
2.89E+02 O.OOE+OO O.OOE+OO 2.22E-01 O.OOE+OO O.OOE+OO b.2 Dry Non-Compressible Waste (Contaminated O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Equipment) | |||
Totals 2.89E+02 O.OOE+OO O.OOE+OO 2.22E-01 O.OOE+OO O.OOE+OO C. | |||
Irradiated Components, Control Rods, etc. | |||
O.OOE+OO O.OOE+OO O.OOE+oo* | |||
O.OOE+OO O.OOE+OO O.OOE+OO | |||
: d. Other (to vendor for processing) d.1 Sewage Sludge 3.53E+.01 O.OOE+OO O.OOE+OO 4.99E-03 O.OOE+OO O.OOE+OO (1) The estimated total error is 5.0E+01 %. | |||
ATTACHMENT 6 | ATTACHMENT 6 Page 2 of4 Unit 1 X | ||
: c. Irradiated Components, N/A | Unit2 Reporting Period: January - December 2017 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A1. TYPE Container Package Solidification Agent a.1 Spent Resin Poly Liner General Design None a.2 Filter Sludge Poly Liner Type B None b.1 Dry Compressible Waste Seavan General Design None b.2 Dry Non-Compressible Waste (contaminated N/A N/A N/A equipment) | ||
: d. Other (To vendor for processing) d.1 Sewage Sludge | : c. Irradiated Components, N/A N/A NIA Control Rods | ||
: d. Other (To vendor for processing) d.1 Sewage Sludge Bags General Design None | |||
ATTACHMENT 6 | ATTACHMENT 6 Page 3 of4 Unit 1 X | ||
: a. Spent Resins, Filter Sludges, Concentra.ted Waste Nuclide | Unit2 Re12orting Period: Janua!Jl - December 2017 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE) | ||
* Ni-63 | : a. Spent Resins, Filter Sludges, Concentra.ted Waste Nuclide Percent Curies Fe-55 16.03% | ||
1.02E+02 Co-60 73.69% | |||
4.70E+02 | |||
* Ni-63 1.08% | |||
6.91E+OO Cs-137 6.57% | |||
4.19E+01 | |||
: b. Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment) | : b. Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment) | ||
Nuclide | Nuclide Percent Curies Mn-54 1.90% | ||
4.22E-03 Fe-55 51.08% | |||
1.14E-01 Co-60 41.59% | |||
9.25E-02 Ni-63 1.40% | |||
3.12E-03 Cs-137 1.44% | |||
3.19E-03 I | |||
: c. Irradiated Components, Control Rods: There were no shipments. | : c. Irradiated Components, Control Rods: There were no shipments. | ||
Nuclide | Nuclide Percent NA NA | ||
: d. Other: (To vendor for processing) | : d. Other: (To vendor for processing) | ||
: 1. Sump Liner Nuclide | : 1. Sump Liner Nuclide Percent Curies Mn-54 2.03% | ||
9.88E-05 Co-60 94.70% | |||
4.62E-03 Cs-137 | |||
.3.27% | |||
1.59E-04 | |||
ATTACHMENT 6 | ATTACHMENT 6 Page 4 of4 Unit 1 X | ||
Number of Shi12ments | Unit2 Re12orting Period: Janua[ll - December 2017 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A3. SOLID WASTE DISPOSITION Number of Shi12ments Mode of Trans12ortation Destination 8 | ||
Truck, highway Bear Creek 1 | |||
Truck, highway Gallaher Road 5 | |||
Truck, highway Clive 3 | |||
Truck, highway wcs B. IRRADIATED FUEL SHIPMENTS (Disposition) | |||
Number of Shi12ments Mode of Trans12ortation Destination D. SEWAGE WASTES SHIPPED TO A TREATMENT FACILITY FOR PROCESSING AND BURIAL There were no shipments of sewage sludge with detectible quantities of plant-related nuclides from NMP to the treatment facility during the reporting period. | |||
ATTACHMENT 7 | ATTACHMENT 7 Page 1 of 1 Unit 1 X | ||
Unit2 Re[!orting Period: Janua(Y - December 2017 | |||
==SUMMARY== | ==SUMMARY== | ||
OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL (ODCM) | OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL (ODCM) | ||
The following changes were made to the Unit 1 Off-Site Dose Calculation Manual (ODCM) during the reporting period. | The following changes were made to the Unit 1 Off-Site Dose Calculation Manual (ODCM) during the reporting period. | ||
REVISION 36 New/Amended | REVISION 36 Page# | ||
13.1-10 | New/Amended Description of Change Reason For Change Section# | ||
13.1-10 NOTES FOR TABLED Removed phrasing in (g) action The basis for the change comes from 3.6.14-2 NER-NC-17-001-Yellow "Review of Offsite Dose Calculation Manual (ODCM) for Shutdown or Power Reduction Action Statements" 13.1-11 NOTES FOR TABLE D Added rewritten action (g) | |||
The basis for the change comes from 3.6.14-2 "Place the nonfunctional channel in the tripped NER-NC-17-001-Yellow condition within 12 hours OR (2) (a) Take grab samples within 12 hours and once per 12 hours thereafter AND (b) Analyze samples for gross activity within 24 hours of sampling completion. | |||
AND (3) Restore nonfunctional channel(s) to FUNCTIONAL status within 30 days. U)" | AND (3) Restore nonfunctional channel(s) to FUNCTIONAL status within 30 days. U)" | ||
13.1-11 | 13.1-11 NOTES FOR TABLE D Added action (j) | ||
IB3.1-1 | The basis for the change comes from 3.6.14-2 "If nonfunctional channel(s) not restored within NER-NC-17-001-Yellow specified time, explain why the inoperability was not corrected in a timely manner in the next Radioactive Effluent Release Report." | ||
EFFLUENT | IB3.1-1 BASES FOR DLCO BASES changed to align with notes from Table D The basis for the change comes from 3.6.14 and DSR 4.6.14 3.16.14-2 NER~NC-17-001-Yellow RADIOACTIVE EFFLUENT INSTRUMENTATION 183.1-1 BASES FOR DLCO Removed the line to align with BASES change: | ||
11-19 | The basis for the change comes from 3.6.14 and DSR 4.6.14 "When serving as backup NER-NC-17-001-Yellow RADIOACTIVE to the Offgas Monitors (Table D 3.6.14-2 Note g), | ||
II -19 | EFFLUENT this function may be satisfied by a single Low Range INSTRUMENTATION or High Range monitor because all Stack monitors function in the region of interest due to their design overlap." | ||
factor adding: | 11-19 2.2.1.1 Noble Gases Added missing 0;5 in the whole body dose rates | ||
~or whole body dose rates (mrem/sec) equation. | |||
was missing the release rate of isotope i from the stack factor (Qis)in the equation. | |||
II -19 2.2.1.1 Noble Gases Elaborated the definition of the structural shielding Definition was not comprehensive. | |||
factor adding: | |||
"(dimensionless). A shielding factor of 0.7 is discussed in Table E-15 of Regulatory Guide 1.109 Revision 1" | |||
ATTACHMENT 8 | ATTACHMENT 8 Page 1 of 1 Unit 1 X | ||
Unit2 Reporting Period: January - December 2017 | |||
==SUMMARY== | ==SUMMARY== | ||
OF CHANGES TO THE PROCESS CONTROL PROGRAM (PCP) | OF CHANGES TO THE PROCESS CONTROL PROGRAM (PCP) | ||
RW-AA-100, PROCESS CONTROL PROGRAM FOR RADIOACTIVE WASTES, was updated to remove Fort Calhoun from the procedure and include James A. Fitzpatrick Nuclear. | RW-AA-100, PROCESS CONTROL PROGRAM FOR RADIOACTIVE WASTES, was updated to remove Fort Calhoun from the procedure and include James A. Fitzpatrick Nuclear. | ||
ATTACHMENT 9 | ATTACHMENT 9 Page 1 of 1 Unit 1 X | ||
Unit2 Reporting Period: January - December 2017 | |||
==SUMMARY== | ==SUMMARY== | ||
OF NON-FUNCTIONAL MONITORS Dates Monitor was | OF NON-FUNCTIONAL MONITORS Monitor Dates Monitor was Cause and Corrective Actions Non-Functional Liquid Radwaste January 1, 2017 to These monitors were intentionally allolJ'.'.ed to exceed their quarterly Discharge Monitors Qecember 31, 2017 functional tests and annual calibration frequency, as no discharges 11 and 12 I | ||
I | are planned or expected. This condition is allowed as long as blank flanges are installed in the discharge line, precluding any unmonitored discharge. No liquid waste discharges were performed during 2017. This non-functionality is tracked in Equipment Status Log (ESL) 2006-0192. | ||
I I | |||
ATTACHMENT 10 | ATTACHMENT 10 Page 1 of 4 Unit 1 _x_ | ||
Unit 2 Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY Introduction An assessment of the radiation dose potentially received by a Member of the Public due to their activities inside the site boundary from Nine Mile Point Unit 1 (NMPl) liquid and gaseous effluents has been conducted for the perio~ January through December 2017. | |||
This assessment considers the maximum exposed individual and the various exposure pathways resulting from liquid and gaseous effluents to identify the maximum dose received by a Member of the Public during their activities within the site boundary. | This assessment considers the maximum exposed individual and the various exposure pathways resulting from liquid and gaseous effluents to identify the maximum dose received by a Member of the Public during their activities within the site boundary. | ||
Prior to September 11, 2001, the public had access to the Energy Information Center for purposes of observing the educational displays or for picnicking and associated activities. Fishing also occurred near the shoreline adjacent to the Nine Mile Point (NMP) site. Fishing near the shor~line adjacent to the NMP site. was the onsite activity that resulted in the potential maximum dose received by a Member of the Public. Following September *11, 2001 public access to the Energy Information Center has been restricted and fishing by Members of the Public at locations on site is also prohibited. Although fishing was not conducted during 2017, the annual dose to a hypothetical fisherman was still evaluated to provide contin\}ity of data for the location. | Prior to September 11, 2001, the public had access to the Energy Information Center for purposes of observing the educational displays or for picnicking and associated activities. Fishing also occurred near the shoreline adjacent to the Nine Mile Point (NMP) site. Fishing near the shor~line adjacent to the NMP site. was the onsite activity that resulted in the potential maximum dose received by a Member of the Public. Following September *11, 2001 public access to the Energy Information Center has been restricted and fishing by Members of the Public at locations on site is also prohibited. Although fishing was not conducted during 2017, the annual dose to a hypothetical fisherman was still evaluated to provide contin\\}ity of data for the location. | ||
Dose Pathways Dose pathways considered for this evaluation included direct radiation, inhalation and external ground (shoreline sediment or soil doses). Other pathways, such as ingestion pathways, are not considered because they are either not a~plicable, insignificant, or are considered as part of the evaluatipn of the total dose to a member of the public | Dose Pathways Dose pathways considered for this evaluation included direct radiation, inhalation and external ground (shoreline sediment or soil doses). Other pathways, such as ingestion pathways, are not considered because they are either not a~plicable, insignificant, or are considered as part of the evaluatipn of the total dose to a member of the public | ||
* locat~d off-site. In addition, only releases from the NMPl stack ,d emergency condenser vent were evaluated for the inhalation pathway. Dose due to aquatic pathways such as liquid effluents is not applicable since swimming is prohibited at the NMP site. | * locat~d off-site. In addition, only releases from the NMPl stack,d emergency condenser vent were evaluated for the inhalation pathway. Dose due to aquatic pathways such as liquid effluents is not applicable since swimming is prohibited at the NMP site. | ||
Dose to a hypothetical fisherman is received through the following pathways while standing on the shoreline fishing: | Dose to a hypothetical fisherman is received through the following pathways while standing on the shoreline fishing: | ||
External ground pathway; this dose is received from plant related radionuclides detected in the shoreline sediment. | |||
Inhalation pathway; this dose is received through inh~lation of gaseous effluents released from the NMPl Stack and Emergency Condenser Vent. | |||
Direct radiation pathway; dose resulting from the operation ofNMPl, Nine Mile Point Unit 2 (NMP2) and the James A. Fitzpatrick Nuclear Power Plant (JAFNPP) Facilities. | |||
Methodologies for Determining Dose for Applicable Pathways External Ground (Shoreline Sediment) Pathway Dose from the external ground (shoreline sediment) is based on the methodology in the NMPl Offsite Dose Calculation Manual (ODCM) as adapted from Regulatory Guide 1.109. For this evaluation it is assumed that the hypothetical maximum exposed individual fished from the shoreline at all times. | Methodologies for Determining Dose for Applicable Pathways External Ground (Shoreline Sediment) Pathway Dose from the external ground (shoreline sediment) is based on the methodology in the NMPl Offsite Dose Calculation Manual (ODCM) as adapted from Regulatory Guide 1.109. For this evaluation it is assumed that the hypothetical maximum exposed individual fished from the shoreline at all times. | ||
ATTACHMENT 10 | ATTACHMENT 10 Page 2 of 4 Unit 1 ~X-Unit 2 Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY The total dose received by the whole body and skin of the maximum exposed individual during 2017 was calculated using the following input parameters: | ||
Usage Factor= 312 hours (fishing 8 hours per week, 39 weeks per year) | |||
Density in grams per square 1meter = 40,000 Shore width factor= 0.3 1 | |||
Whole body and skin dose factor for each radionuclide= Regulatory Guide 1.109, Table E-6. | |||
Fractional portion of the year= 1 (used average radionuclide concentration over total time period) | |||
Average Cs-137 concentration= l.30E-01 pCi/g The total whole body and skin doses received by a hypothetical maximum exposed fisherman from the external ground pathway is presented in Table 1, Exposure Pathway Annual Dose. | |||
Inhalation Pathway The inhalation dose pathway is evaluated by utilizing the inhalation equation in the NMPl ODCM, as adapted from Regulatory Guide 1.109. The total whole body dose and organ dose received by the hypothetical maximum exposed fisherman during 2017 calculated using the following input parameters for gaseous effluents released from both the NMPl Stack and Emergency Condenser Vent for the time period exposure is received: | Inhalation Pathway The inhalation dose pathway is evaluated by utilizing the inhalation equation in the NMPl ODCM, as adapted from Regulatory Guide 1.109. The total whole body dose and organ dose received by the hypothetical maximum exposed fisherman during 2017 calculated using the following input parameters for gaseous effluents released from both the NMPl Stack and Emergency Condenser Vent for the time period exposure is received: | ||
NMP 1 Stack: | NMP 1 Stack: | ||
Variable | Variable Fisherman 1 X/Q (s/m3) 8.90E-06 Inhalation dose factor Table E-7, Regulatory Guide 1.109 Annual air intake (m3/year) (adult) 8000 Fractional portion of the year 0.0356 H-3 (pCi/sec) l.55E+06 Mn-54 (pCi.sec) 2.0lE-01 C-14 (pCi/sec)2 2.63E+05 Fe-55 (pCi/sec) 6.04E+OO Co-60 (pCi/sec) l.27E+Ol Sr-89 (pCi/sec) 6.64E+OO | ||
X/Q (s/ | |||
Annual air intake ( | |||
ATTACHMENT 10 | ATTACHMENT 10 Page 3 of 4 Unit 1 _X_ | ||
Unit 2 Reporting Period: January-December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY NMPJ Emergency Condenser Vent: | |||
Variable Fisherman 1 | |||
XIQ (s/m3) 6.63E-06 Inhalation dose factor Table E-7, Regulatory Guide 1.109 Annual air intake (ni3 /year) (adult) 8000 Fractional portion of the year 0.0356 H-3 (pCi/sec) 4.05E+05 Mn-54 (pCi/sec) 3.33E-04 Co-58 (pCi/sec) l.20E-03 Co-60 (pCi/sec) l.85E-03 The maximum exposed fisherman is assumed to be present on site during the period of April through December at a rate of 8 hours per week for 39 weeks per year equivalent to 312 hours for the year (fractional portion of_the year= 0.0356). Therefore, the Average Stack and Emergency Condenser Vent flow rates and radionuclide concentrations used to determine the dose are represented by second, third and fourth quarter gaseous effluent flow and concentration values. | |||
2 C-14 release rate detennined from NUREG-0016, "Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents for Boiling Water Reactors (BWR-GALE Code)," and EPRI Technical Report 1021106, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents." | 2 C-14 release rate detennined from NUREG-0016, "Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents for Boiling Water Reactors (BWR-GALE Code)," and EPRI Technical Report 1021106, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents." | ||
The total whole body dose and maximum organ dose received by the hypothetical maximum exposed fisherman is presented in Table 1, Exposure Pathway Annual Dose. | The total whole body dose and maximum organ dose received by the hypothetical maximum exposed fisherman is presented in Table 1, Exposure Pathway Annual Dose. | ||
Direct Radiation Pathwav The direct radiation pathway is evaluated in accordance with the methodology found in the NMPl ODCM. This pathway considers four components: direct radiation from the generating facilities, direct radiation from any possible overhead plume, direct radiation from ground deposition and direct radiation from plume submersion. | Direct Radiation Pathwav The direct radiation pathway is evaluated in accordance with the methodology found in the NMPl ODCM. This pathway considers four components: direct radiation from the generating facilities, direct radiation from any possible overhead plume, direct radiation from ground deposition and direct radiation from plume submersion. | ||
The direct radiation pathway is evaluated by the use of high sensitivity environmental Thermoluminescent Dosimeters (TLDs). Since fishing activities occur benveen April I and December 31, TLD data for the second, third, and fourth quarters of 2017 from TLDs placed in the general area where fishing once occurred were used to determine an average dose to the hypothetical maximum exposed fisherman from direct radiation. The following is a summary of the average dose rate and assumed time spent on site used to determine the total dose received: | The direct radiation pathway is evaluated by the use of high sensitivity environmental Thermoluminescent Dosimeters (TLDs). Since fishing activities occur benveen April I and December 31, TLD data for the second, third, and fourth quarters of 2017 from TLDs placed in the general area where fishing once occurred were used to determine an average dose to the hypothetical maximum exposed fisherman from direct radiation. The following is a summary of the average dose rate and assumed time spent on site used to determine the total dose received: | ||
Variable | Variable Fisherman Average Dose Rate (mRem/hr) l.04E-03 Exposure time (hours) 312 Total doses received by the hypothetical maximum exposed fishennan from direct radiation is presented in Table 1, Exposure Pathway Annual Dose. | ||
__J | __J | ||
ATTACHMENT 10 | L ATTACHMENT 10 Page 4 of4 Unit 1 _x_ | ||
TABLE 1 Exposure Pathway Annual Dose | Unit 2 Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY Dose Received By Hypothetical Maximum Exposed Member of the Public Inside the Site Boundary The following is a summary of the dose received by a hypothetical maximum exposed fisherman from liquid and gaseous effluents released from NMPl during 2017: | ||
Whole Body | TABLE 1 Exposure Pathway Annual Dose Exposure Pathway Dose Type Fisherman (mrem) | ||
TABLE2 Annual Dose Summary | External Ground Whole Body 2.04 E-03 Skin of Whole Body 2.38 E-03 Whole Body 1.02 E-03 Inhalation Maximum Organ Bone: 1.51 E-03 ThyToid 1.02 E-03 Direct Radiation Whole Body 0.32 Based on these values the total annual dose received by a hypothetical maximum exposed Member of the Public inside the site boundary is as follows: | ||
Total Whole Body | TABLE2 Annual Dose Summary Total Annual Dose for 2017 Fisherman (mrem) | ||
Total Whole Body 3.26 E-01 Skin of Whole Body | |||
_ 2.38 E-03 Maximum Organ Bone: 1.51 E-03 Thyroid 1.02 E -03 | |||
__J | |||
i | i | ||
( | ( | ||
ATTACHMENT 11 | ATTACHMENT 11 Page 1 of 5 Unit 1 _x_ | ||
Unit 2 Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Introduction An assessment of radiation doses potentially received by the likely most exposed Member of the Public located beyond the site boundary was conducted for the period January through December 2017 for comparison against the 40 CPR 190 annual dose limits. | |||
40 CPR 190 requires the annual radiation dose received by Members of the Public in the general environment, as a result of plant operations, be limited to: | I The intent of 40 CPR 190 requires that the effl~ents of Nine Mile Point Unit 1 (NMPl), as well as other nelrby uranium fuel cycle facilities, be considered. In this case, the effluents of NMPl, Nine Mile Point Unit 2 (NMP2) and the James A. FitzPatrick Nuclear Power Plant (JAFNPP) facilities must be considered. | ||
40 CPR 190 requires the annual radiation dose received by Members of the Public in the general environment, as a result of plant operations, be limited to: | |||
< 25 mRem whole body | |||
< 25 mRem any organ ( except thyroid) | |||
< 75 mRem thyroid This evaluation compares doses resulting from liquid and gaseous effluents and direct radiation originating from the site as a result of the operation of the NMPl, NMP2 and JAFNPP.nuclear facilities. | |||
Dose Pathways Dose pathways considered for this evaluation included doses resulting from liquid effluents, gaseous effluents and direct radiation from all nuclear operating facilities located on the Nine Mile Point site. | Dose Pathways Dose pathways considered for this evaluation included doses resulting from liquid effluents, gaseous effluents and direct radiation from all nuclear operating facilities located on the Nine Mile Point site. | ||
Dose to the likely most exposed Member of the l?Jublic, outside the site boundary, is received through the followJ*ng pathways: | Dose to the likely most exposed Member of the l?Jublic, outside the site boundary, is received through the followJ*ng pathways: | ||
Fish consumption pathway; this dose is rece ved from plant radionuclides that have concentrated in fish tha is consumed by a Member of the Public. | |||
Vegetation consumption pathway; this dose is received from plant radionuclides that have concentrated in vegetation that is consumed by a Member of the Public. | |||
Shoreline Sediment; this dose is received as a result of an individual's exposure to plant radionuclides in the shoreline sediment, which is used as a recreational area. | |||
Deposition, Inhalation and Ingestion pathways resulting from gaseous effluents; this dose is received through exposure to gaseous effluents released from NMPl, NMP2 and JAFNPP operating facilities. | |||
Direct Radiation pathway; radiation dose resulting from the operation ofNMPl, NMP2 and JAFNPP facilities (including the Independent Spent Fuel Storage Installations (ISFSI)). | |||
Methodologies for Determining Dose for Applicable Pathways Fish Consumption Dose received as a result of fish consumption is based on the methodology specified in the NMP 1 Off-Site Dose Calculation Manual (ODCM) as adapted from Regulatory Guide 1.109. The dose for 2017 is calculated from actual analysis results of environmental fish samples taken near the site discharge points. For this evaluation it is assumed that the most likely exposed Member of the Public consumes fish taken near the site discharge points. | Methodologies for Determining Dose for Applicable Pathways Fish Consumption Dose received as a result of fish consumption is based on the methodology specified in the NMP 1 Off-Site Dose Calculation Manual (ODCM) as adapted from Regulatory Guide 1.109. The dose for 2017 is calculated from actual analysis results of environmental fish samples taken near the site discharge points. For this evaluation it is assumed that the most likely exposed Member of the Public consumes fish taken near the site discharge points. | ||
No radionuclides were detected in fish samples collected and analyzed during 2017; therefore, no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2017. | No radionuclides were detected in fish samples collected and analyzed during 2017; therefore, no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2017. | ||
ATTACHMENT 11 | ATTACHMENT 11 Page 2 of 5 Unit 1 _x_ | ||
Unit 2 Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Vegetation Consumption Dose received as a result of vegetation consumption is based on the methodology specified in the NMPl ODCM as adapted from Regulatory Guide 1.109. The dose for 2017 is calculated from actual analysis results of environmental vegetation samples taken near the most exposed Member of the Public.. | |||
No radionuclides were detected in vegetation samples collected and analyzed during 2017; therefore, no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2017. | No radionuclides were detected in vegetation samples collected and analyzed during 2017; therefore, no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2017. | ||
For estimating C-14, dose received as a result of vegetation consumption is based on the methodology specified in the NMPl ODCM as adapted from Regulatory Guide 1.109. The estimated concentration of C-14 in vegetation is based on the estimated concentration of C-14 in plant gaseous effluents. | For estimating C-14, dose received as a result of vegetation consumption is based on the methodology specified in the NMPl ODCM as adapted from Regulatory Guide 1.109. The estimated concentration of C-14 in vegetation is based on the estimated concentration of C-14 in plant gaseous effluents. | ||
Shoreline Sediment . | Shoreline Sediment. | ||
Dose received from shoreline sediment is based on the methodology in the NMPl ODCM as adapted from Regulatory Guide 1.109. For this evaluation it is assumed that the most likely exposed Member of the Public spends 67 hours/year along the shoreline for recreational purposes. | Dose received from shoreline sediment is based on the methodology in the NMPl ODCM as adapted from Regulatory Guide 1.109. For this evaluation it is assumed that the most likely exposed Member of the Public spends 67 hours/year along the shoreline for recreational purposes. | ||
No radionuclides were detected in shoreline sediment samples collected and analyzed during 2017; therefore no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2017. | No radionuclides were detected in shoreline sediment samples collected and analyzed during 2017; therefore no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2017. | ||
| Line 341: | Line 411: | ||
Carbon-14 Dose Pathways Resulting from Gaseous Effluents The Cai'bon-14 (C-14) effluent source terms are used to estimate radiological doses from C-14 in site gaseous waste effluents. These estimates were generated in order to meet the NRC requirement to incorporate C-14 in nuclear power plant 2017 Annual Radiological Effluent Release Reports (ARERRs). The C-14 production and effluent source term estimates were based on EPRI methodology provided in EPRI Report 1021106, Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents, December 2010. The following methodology was used in estimating C-14 gaseous release activity and dose components for the 2017 ARERR. | Carbon-14 Dose Pathways Resulting from Gaseous Effluents The Cai'bon-14 (C-14) effluent source terms are used to estimate radiological doses from C-14 in site gaseous waste effluents. These estimates were generated in order to meet the NRC requirement to incorporate C-14 in nuclear power plant 2017 Annual Radiological Effluent Release Reports (ARERRs). The C-14 production and effluent source term estimates were based on EPRI methodology provided in EPRI Report 1021106, Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents, December 2010. The following methodology was used in estimating C-14 gaseous release activity and dose components for the 2017 ARERR. | ||
EPRI methodology for estimating C-14 production rates in Boiling Water Reactors (BWRs): | EPRI methodology for estimating C-14 production rates in Boiling Water Reactors (BWRs): | ||
For BWRs, EPRI Report 1021106 summarized the distribution of C-14 in release pathways as follows: gaseous 95% to 99%, liquid <0.5% and solid 1% to 5%. The report also states that -9 5% of C-14 in BWR gaseous waste. | For BWRs, EPRI Report 1021106 summarized the distribution of C-14 in release pathways as follows: gaseous 95% to 99%, liquid <0.5% and solid 1 % to 5%. The report also states that -9 5% of C-14 in BWR gaseous waste. | ||
effluents exists in the carbon dioxide form, which contributes to population dose via photosynthesis uptake in the food consumption cycle. | effluents exists in the carbon dioxide form, which contributes to population dose via photosynthesis uptake in the food consumption cycle. | ||
_ _J | |||
ATTACHMENT 11 | ATTACHMENT 11 Page 3 of 5 Unit 1 _x_ | ||
Unit 2 Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY For NMPl and NMP2, C-14 gaseous dose calculations in the site ARERR are made using the following assumptions for each unit: (1) continuous release of the estimated C-14 generated during power operation based on the number of Effective Full Power Days (EFPDs) for the period, (2) maximum G-14 activity from literature values cited in EPRI Report 1021106, and (3) typical fraction as carbon dioxide for gaseous releases from literature values also cited in EPRI Report 1021106. | |||
Equation 1 estimates the maximum annual production of C-14, PRMAX, for each BWR unit. | Equation 1 estimates the maximum annual production of C-14, PRMAX, for each BWR unit. | ||
PRMAX | PRMAX | ||
* MWT / 1000 | = | ||
5.1 | |||
* MWT / 1000 | |||
[Eq 1] | |||
Where: | |||
5.1 | |||
= | |||
BWR Normalized Production (Ci/GWt-yr) | |||
MWT | |||
= | |||
Mega Watts Thermal (MWt) 1000 | |||
= | |||
Conversion Factor (MWt to GWt) | |||
Equation 2 estimates the C-14 activity released, A c.14, into the gaseous pathway during the time period for each BWR unit. | |||
Where: | Where: | ||
A C-1./ | |||
PRMAX 0.99 EFPD 365 PR MAX | |||
A C-1./ | |||
* 0.9} | * 0.9} | ||
* EFPD I 365, Ci (for time period) | * EFPD I 365, Ci (for time period) | ||
[Eq2} | |||
maximum annual production rate ofC-14 fraction ofC-14 in BWR gaseous pathway releases (maximum literature value in EPRI Report 1021106; also Table 1) number of effective full power days for the unit during the time period; e.g., quarterly or yearly (Table 1) number of days in a typical year | |||
ATTACHMENT 11 Page 4 of 5 Unit 1 ~X-Unit 2 Reporting Period: January-December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Equation 3 estimates the C-14 activity released in carbon dioxide form, A c-l4, co2, into the gaseous pathway during the time period for each BWR unit. | |||
Where: | Where: | ||
A C-14, CO2 PRMAX 0.99 0.95 EFPD 365 | |||
EFPD | = | ||
= | |||
= | |||
= | |||
= | |||
= | |||
(R MAX o 0.99 | |||
* 0.95 | * 0.95 | ||
* EFPD I 365, Ci (for time period) I | * EFPD I 365, Ci (for time period) I maximum annual production rate of C-14 fraction of C-14 in BWR gaseous pathway releases (maximum literature value in EPRI Report 1021106; also Table 1) fraction of C-14 as carbon dioxide in BWR gaseous pathway | ||
[Eq3] | |||
releases (typical literature value in EPRI Report 1021106; also Table 1) number of effective full power days for the unit during the time period, e.g. quarterly or yearly (Table 1) conversion factor, 365 days in atypical average year For each BWR unit, the 2017 estimated C-14 activity releases (total and carbon dioxide chemical form) are summarized in Table 1. | |||
Table 1 2017 BWR Estimated C-14 Gaseous Releases Gaseous COiForm Max.Annual BWR Release Release EFPD Operation Fraction(a) | |||
Table 1 2017 BWR Estimated C-14 Gaseous Releases Gaseous | Fraction<hJ NMPl 0.99 0.95 331.2EFPD (90.7%) | ||
Fraction(a) | NMP2 0.99 0.95 359.85 EFPD (98.9%) | ||
JAFNPP 0.99 0.95 309.1 EFPD (84.7%) | |||
(a) Maximum literature values from EPRI Report 1021106. | (a) Maximum literature values from EPRI Report 1021106. | ||
(b) Typical value from EPRI Report 1021106. | (b) Typical value from EPRI Report 1021106. | ||
(c) NMP2 Reactor Power Rating increased to 3988 Megawatts thermal. | Prod. Rate (Eq 1) 9.44 Ci/yr 20.33 Ci/yr(c) 12.93 Ci/yr (c) NMP2 Reactor Power Rating increased to 3988 Megawatts thermal. | ||
As long as the core designs and power ratings are not significantly changed, the maximum annual production rates and annual total and carbon dioxide activity releases in Table 1 should be acceptable for use in estimating C-14 gaseous release activity and dose components for the ARERR. | 2017 Total Release (Eq2) 8.48 Ci 19.85 Ci 9.09 Ci 2017 CO2 Release (Eq3) 8.05 Ci 18.86 Ci 8.63 Ci As long as the core designs and power ratings are not significantly changed, the maximum annual production rates and annual total and carbon dioxide activity releases in Table 1 should be acceptable for use in estimating C-14 gaseous release activity and dose components for the ARERR. | ||
ATTACHMENT 11 | ATTACHMENT 11 Page 5 of 5 Unit 1 _X_ | ||
Table 2 Dose Potentially Received by the Likely Most Exposed Member of the Public Outside the Site Boundary During 2017 Exposure Pathway | Unit 2 Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Direct Radiation Pathwav Dose as a result of direct gamma radiation from the site, encompasses doses from direct "shine" from the generating facilities, direct radiation from any overhead gaseous plumes, plume submersion, and ground deposition. This total dose is measured by environmental TLDs. The critical location is based on the closest year-round residence from the generating facilities as well as the closest residence in the critical downwind sector in order to evaluate both direct radiation from the generating facilities and gaseous plumes as determined by the local meteorology. During 2017, the closest residence and the critical downwind residence are at the same location. | ||
Total Whole Body | Table 2 Dose Potentially Received by the Likely Most Exposed Member of the Public Outside the Site Boundary During 2017 Exposure Pathway Dose Type Dose (mrem) | ||
Maximum Organ | Total Whole Body No Dose Fish and Vegetation Consumption Total Maximum Organ No Dose Total Whole Body No Dose Shoreline Sediment Total Skin of Whole Body No Dose Total Whole Body 4.42 E-03 Gaseous Effluents Thyroid 1.02 E-02 (excluding C-14) | ||
Maximum Organ Thyroid: 1.02 E-02 Gaseous Eftluent Total Whole Body 3.52 E-01 (C-14) | |||
Maximum Organ Bone: 1.76 E+oO Direct Radiation Total Whole Body 0.91 Based on these values the maximum total annual dose potentially received by the likely most exposed Member of the Public during 2017 is as follows: | |||
Total Whole Body: | |||
Total Thyroid: | |||
Maximum Organ: | |||
40 CFR 190 Evaluation 1.27 E+OO mrem | |||
: 1. 02 E-02 mrem Bone: 1.76 E+OO mrem The ma.-x:imum total doses presented in this attachment are the result of operations at the NMPl, NMP2 and the JAFNPP facilities. The maximum organ dose (Bone: 1.76 mrem), maximum thyroid dose (0.010 mrem) and the maximum whole body dose (1.27 mrem) are below the 40 CFR 190 criteria of 25 mrem per calendar year to the maximum exposed organ or the whole body, and below 75 mrem per calendar year to the thyroid. | |||
ATTACHMENT 12 | ATTACHMENT 12 Page 1 of 1 Unit 1 _x_ | ||
Unit 2 -- | |||
GMX-MW1* | Re12orting Period: Janua!Jl - December 2017 Well Identification | ||
MW- | # Samples Minimum Maximum Number Collected | ||
* 4 | # Positive Samples Concentration (pCi/1) | ||
Concentration (pCi/1) | |||
GMX-MW1* | |||
4 0 | |||
<188 | |||
<194 MW-1 4 | |||
0 | |||
<188 | |||
<200 MW-5 4 | |||
0 | |||
<183 | |||
<193 MW-6 4 | |||
0 | |||
<186 | |||
<191 MW-7 4 | |||
0 | |||
<186 | |||
<194 MW-8 4 | |||
0 | |||
<187 | |||
<193 MW-91 4 | |||
0 | |||
<187 | |||
<192 MW-101 4 | |||
1 | |||
<186 240 MW-11 4 | |||
0 | |||
<186 | |||
<193 MW-12 4 | |||
0 | |||
<190 | |||
<193 MW-13 4 | |||
0 | |||
<184 | |||
<192 MW-14* | |||
4 1 | |||
<183 234 MW-15 4 | |||
1 | |||
<186 252 MW-16 4 | |||
0 | |||
<184 | |||
<192 MW-17 4 | |||
1 | |||
<183 222 MW-18 4 | |||
1 | |||
<190 270 MW-19 4 | |||
0 | |||
<186 | |||
<190 MW-20 4 | |||
0 | |||
<183 | |||
<192 MW-21 4 | |||
0 | |||
<183 | |||
<190 NMP2 MAT 2*3 4 | |||
1 | |||
<181 279 PZ-1 4 | |||
0 | |||
<190 | |||
<193 PZ-2 4 | |||
0 | |||
<191 | |||
<196 PZ-3 4 | |||
0 | |||
<187 | |||
<194 PZ-4 4 | |||
1 | |||
<189 214 PZ-5 4 | |||
0 | |||
<190 | |||
<191 PZ-6 4 | |||
0 | |||
<188 | |||
<192 PZ-7 4 | |||
4 291 435 PZ-8 4 | |||
0 | |||
<190 | |||
<198 PZ-9* | |||
4 0 | |||
<189 | |||
<194 Notes: | |||
* - Control Location 1 - Sentinel well location 2 - NMP2 Groundwater Depression Cone 3 | |||
- Samples collected from storm drain system which includes precipitation Nine Mile Point Nuclear Station, Unit 2 Radioactive Effluent Release Report, January-D,ecember 2017 | |||
NINE MILE POINT NUCLEAR STATION - UNIT 2 RADIOACTIVE EFFLUENT RELEASE REPORT January-December 2017 | |||
Page 1 of2 NINE MILE POINT NUCLEAR STATION - UNIT 2 RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2017 SUPPLEMENTAL INFORMATION Facility: Nine Mile Point Unit 2 Licensee: Nine Mile Point Nuclear Station, LLC | |||
: 1.. TECHNICAL SPECIFICATION/ODCM LIMITS A) | |||
Page 1 of2 NINE MILE POINT NUCLEAR STATION - UNIT 2 RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2017 SUPPLEMENTAL INFORMATION Facility: Nine Mile Point Unit 2 | FISSION AND ACTIVATION GASES | ||
: 1. . TECHNICAL SPECIFICATION/ODCM LIMITS A) | : 1. | ||
: 1. The dose rate limit of noble gases released in gaseous effluents from the site to areas at or beyond the site boundary shall be less than or equal to 500 mrem/year to the whole body and less than or equal to 3000 mrem/year to the skin. | The dose rate limit of noble gases released in gaseous effluents from the site to areas at or beyond the site boundary shall be less than or equal to 500 mrem/year to the whole body and less than or equal to 3000 mrem/year to the skin. | ||
: 2. The air dose from noble gases released in gaseous effluents from Nine Mile Point Unit 2 to areas at or beyond the site boundary shall be limited during any calendar quarter to less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and during any | : 2. | ||
The air dose from noble gases released in gaseous effluents from Nine Mile Point Unit 2 to areas at or beyond the site boundary shall be limited during any calendar quarter to less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and during any calendar year tA 1ess than or equal to 1 o mrad for gamma radiation and 1ess than or eqra1 to 20 mrad for beta radiatif. | |||
B&C) TRITIUM, IODINES AND PARTICULATES, HALF LIVES > 8 DAYS | B&C) TRITIUM, IODINES AND PARTICULATES, HALF LIVES > 8 DAYS | ||
: 1. The dose rate limit oflodine-131, Iodine-133, Tritium and all radionuclides in particulate form with half-lives greater than eight days, released in gaseous effluents from the site to areas at or beyond the site boundary shall be less than or equal to 1500 mrem/year to any organ. | : 1. | ||
: 2. The dose to a member of the public from Iodine-131, Iodine-133, Tritium and all radionuclides in particulate form with half-lives greater than eight days in gaseous effluents released from Nine Mile Point Unit 2 to areas at or beyond the site boundary shall be limited during any calendar quarter to less than or equal to 7.5 mrem to any organ, and during any calendar year to less than or equal to 15 mrem to any organ. | The dose rate limit oflodine-131, Iodine-133, Tritium and all radionuclides in particulate form with half-lives greater than eight days, released in gaseous effluents from the site to areas at or beyond the site boundary shall be less than or equal to 1500 mrem/year to any organ. | ||
D) | : 2. | ||
: 1. Improved Technical Specifications (ITS) limit the concentration of radioactive material released in the liquid effluents to unrestricted areas to ten times the concentrations specified in 10CFR20.1001-20.2402, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entraineq noble gases, the concentration shall be limited to 2E-04 microcuries/ml total activity. | The dose to a member of the public from Iodine-131, Iodine-133, Tritium and all radionuclides in particulate form with half-lives greater than eight days in gaseous effluents released from Nine Mile Point Unit 2 to areas at or beyond the site boundary shall be limited during any calendar quarter to less than or equal to 7.5 mrem to any organ, and during any calendar year to less than or equal to 15 mrem to any organ. | ||
: 2. . The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released from Nine Mile Point Unit 2 to unrestricted areas shall be limited during any calendar qu~rter to less than or equal to 1.5 mrem to the whole body and to less than or equal to 5 mrem to any organ, and -during any calendar year to less than or equal to 3 mrem to the whole body and to less than or equal to 10 mrem to any organ .. | D) | ||
LIQUID EFFLUENTS | |||
: 1. | |||
Improved Technical Specifications (ITS) limit the concentration of radioactive material released in the liquid effluents to unrestricted areas to ten times the concentrations specified in 10CFR20.1001-20.2402, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. | |||
For dissolved or entraineq noble gases, the concentration shall be limited to 2E-04 microcuries/ml total activity. | |||
: 2.. The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released from Nine Mile Point Unit 2 to unrestricted areas shall be limited during any calendar qu~rter to less than or equal to 1.5 mrem to the whole body and to less than or equal to 5 mrem to any organ, and -during any calendar year to less than or equal to 3 mrem to the whole body and to less than or equal to 10 mrem to any organ.. | |||
Page 2 of2 | Page 2 of2 | ||
: 2. MEASUREMENTS AND APPROXIMATIONS OF TOT AL RADIOACTIVITY Described below are the methods used to measure or approximate the total radioactivity and radionuclide composition in effluents. | : 2. | ||
A) | MEASUREMENTS AND APPROXIMATIONS OF TOT AL RADIOACTIVITY Described below are the methods used to measure or approximate the total radioactivity and radionuclide composition in effluents. | ||
I B) | A) | ||
C) | FISSION AND ACTIVATION GASES Noble gas effluent activity is determined by an on-line scintillation detector (calibrated against gamma isotopic analysis of a 4.0L Marinelli grab sample) of an isokinetic sample stream. | ||
D) | I B) | ||
E) | IODINES Iodine effluent activity is determined by gamma spectroscopic analysis (at least weekly) of charcoal cartridges sampled from an isokinetic sample stream. | ||
C) | |||
Isotop+ contents of waste shipments are determined by gamma spectroscopy analyses of a representative sample of each batch. Scaling factors established from primary composite sample analyses conducted off-site are applied, where appropriate, to find estimated concentration of non-gamma emitters. For low activity trash shipments, curie content is estimated by dose rate measurement and application of appropriate scaling factors. | PARTICULATES Activity released from the main stack and the combined Radwaste/Reactor Building vent is determined by gamma spectroscopic analysis (at least weekly) of particulate filters sampled from an isokinetic sample stream and composite analysis of the filters for non-gamma emitters. | ||
D) | |||
: 3. METEOROLOGICAL DATA An annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distribution of wind speed, wind direction, and atmospheric stability. In lieu of submission with the Radiological Effluent Release Report, the licensee is exercising the option of retaining this summary ofrequired meteorological data on site in a file that shall be provided to the NRC upon request. | TRITIUM Tritium effluent activity is measured by liquid scintillation or gas proportional counting of monthly samples taken with an air sparging/water trap apparatus. | ||
E) | |||
LIQUID EFFLUENTS F) | |||
G) | |||
Isotopic contents of liquid effluents are detennined by isotopic analysis of a representative sample of each batch and composite analysis of non-gamma emitters. | |||
souq EFFLUENTS | |||
) | |||
Isotop+ contents of waste shipments are determined by gamma spectroscopy analyses of a representative sample of each batch. Scaling factors established from primary composite sample analyses conducted off-site are applied, where appropriate, to find estimated concentration of non-gamma emitters. For low activity trash shipments, curie content is estimated by dose rate measurement and application of appropriate scaling factors. | |||
C-14 The production of C-14 and the effluent dose consequences are estimates based on EPRI methodology provided in EPRI Report 1021106, Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents, December 2010 and NUREG-0016, Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents for Boiling Water Reactors (BWR-GALE Code). | |||
: 3. | |||
METEOROLOGICAL DATA An annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distribution of wind speed, wind direction, and atmospheric stability. In lieu of submission with the Radiological Effluent Release Report, the licensee is exercising the option of retaining this summary ofrequired meteorological data on site in a file that shall be provided to the NRC upon request. | |||
Supplemental Information | Supplemental Information ATTACHMENT 1 | ||
==SUMMARY== | ==SUMMARY== | ||
DATA Unit 1 | DATA Unit 1 Unit2 X | ||
ODCM Required Maximum Effluent Concentration (MEC) | Re[!orting Period: | ||
Qrtr.1: | Liquid Effluents: | ||
Number of Batch Releases | ODCM Required Maximum Effluent Concentration (MEC) = 10 x 10CFR20.1001 - 20.2402, Appendix B, Table 2, Column 2 Average MEC - µCi/ml (Qtr.1) = | ||
Number of Batch Releases | I NO RELEASES Average MEC - µCi/ml (Qtr. m = | ||
Average MEC - µCi/ml (Qtr. £) = | |||
I NO RELEASES Average MEC - µCi/ml (Qtr.1) = | |||
Average Energy (Fission and Activation gases - MEV): | |||
Qrtr.1: | |||
Ey | |||
= | |||
N/A E13 | |||
= | |||
N/A Qrtr. l: | |||
~y | |||
= | |||
N/A E13 | |||
= | |||
N/A Qrtr. ~: | |||
~y | |||
= | |||
1.01E+OO Ef3 | |||
= | |||
5.69E-01 Qrtr.1: | |||
Ey | |||
= | |||
N/A Ef3 | |||
= | |||
N/A Liquid: | |||
Number of Batch Releases 0 | |||
Total Time Period for Batch Releases (hrs) 0.0 Maximum Time Period for a Batch Release (hrs) 0.0 Average Time Period for a Batch Release (hrs) 0.0 Minimum Time Period for a Batch Release 0.0 i | |||
To~~ volume of water used to dilute the liquid 1st 2nd 3rd 4th duri g the release period (L) | |||
N/A N/A 11 NIA I | |||
N/A I | |||
I Total volume of water available to dilute the liquid 1st 2nd 3rd 4th Page 1 of 2 Janua!)1-December 2017 I NO RELEASES I I NO RELEASES I I | |||
effluent durinq the report period (L) 1.08E+10 1.15E+10 I 1.31 E+10 I 1.16E+10 I Gaseous (Emergency Condenser Vent) "Not applicable for Unit 2" Number of Batch Releases N/A Total Time Period for Batch Releases (hrs) | |||
N/A Maximum Time Period for a Batch Release (hrs) | |||
N/A Average Time Period for a Batch Release (hrs) | |||
N/A Minimum Time Period for a Batch Release N/A Gaseous (Primary Containment Purge) | |||
Number of Batch Releases 7 | |||
Total Time Period for Batch Releases (hrs) 386.5 Maximum Time Period for a Batch Release (hrs) 133.2 Average Time Period for a Batch Release (hrs) 55.2 Minimum Time Period for a Batch Release (hrs) 3.3 | |||
Supplemental Information | Supplemental Information Unit 1 Unit 2 X | ||
Abnormal Releases: | |||
A. Liquids: | |||
I Number of Releases I | |||
I Total Activity Released I | |||
B. Gaseous: | |||
I Number of Releases I | |||
!Total Activity Released I | |||
ATTACHMENT 1 | |||
==SUMMARY== | ==SUMMARY== | ||
DATA | DATA 0 | ||
I N/A lei 0 | |||
I NIA ICi Page 2 of 2 Re);!orting Period: Janua!)! - December 2017 | |||
Table 1A Gaseous Effluents - | Table 1A Gaseous Effluents - | ||
Elevated and Ground Level Unit 1 | Summation of All Releases - | ||
Elevated and Ground Level Unit 1 Unit2 ATTACHMENT 2 Page 1 of 1 X | |||
Rer;!orting Period: Janua!:Ji! - December 2017 GASEOUS EFFLUENTS - SUMMATION OF All RELEASES, ELEVATED AND GROUND LEVEL 1st 2nd 3rd 4th Est. Total Quarter Quarter Quarter Quarter Error,% | |||
A. Fission & Activation Gases | A. Fission & Activation Gases | ||
: 1. Total Release | : 1. | ||
: 2. Average Release Rate | Total Release Ci O.OOE+OO O.OOE+OO 2.19E+OO O.OOE+OO 5.00E+01 I | ||
B. Iodines | : 2. | ||
: 1. Total Iodine - 131 | Average Release Rate | ||
: 2. Average Release Rate for Period | µCi/sec O.OOE+OO O.OOE+OO 3.91E-01 0.00E+OO I | ||
: 1. Particulates with Half-lives>Bdays | I B. Iodines | ||
: 2. Average Release Rate fqr Period | : 1. | ||
: 3. Gross Alpha Radioactivity | Total Iodine - 131 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.00E+01 | ||
: 1. Total Release | : 2. | ||
: 2. Average Release Rate for Period | Average Release Rate for Period | ||
µCi/sec O.OOE+OO 0.00E+OO 0.00E+OO 0.00E+OO C. Particulates | |||
Percent of Quarterly Beta Air Dose Limit (1 O | : 1. | ||
Particulates with Half-lives>Bdays Ci O.OOE+OO 0.00E+OO 3.29E-05 3.92E-06 3.00E+01 | |||
Percent of Annual Gamma Air Dose Limit to I | : 2. | ||
Average Release Rate fqr Period | |||
Percent of Annual Beta Air Dose Limit to "lo | µCi/sec 0.00E+OO O.OOE+OO 4.19E-06 4.99E-07 | ||
Percent of Whole Body Dose Rate Limit (500 | : 3. | ||
Gross Alpha Radioactivity Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.50E+01 D. Tritium | |||
Percent of Skin Dose Rate Limit (3000 | : 1. | ||
Total Release Ci 2.63E+01 4.38E+01 3.56E+01 4.14E+01 5.00E+01 | |||
: 2. | |||
Average Release Rate for Period | |||
µCi/sec 3.35E+OO 5.56E+OO 4.54E+OO 5.27E+OO E. Percent of Tech. Si;iec. Limits Fission and Activation Gases Percent of Quarterly Gamma Air Dose Limit O.OOE+OO O.OOE+OO 5.24E-03 O.OOE+OO (5 mR) | |||
Percent of Quarterly Beta Air Dose Limit (1 O | |||
~.OOE+OO O.OOE+OO 1.39E-04 O.OOE+OO I | |||
mrad) | |||
Percent of Annual Gamma Air Dose Limit to I | |||
Date (10 mR) | |||
O.OOE+OO O.OOE+OO 2.62E-03 2.62E-03 Percent of Annual Beta Air Dose Limit to "lo O.OOE+OO O.OOE+OO 6.95E-05 6.95E-05 Date (20 mrad) | |||
Percent of Whole Body Dose Rate Limit (500 O.OOE+OO O.OOE+OO 1.99E-04 O.OOE+OO mrem/yr) | |||
Percent of Skin Dose Rate Limit (3000 0.00E+OO O.OOE+OO 4.00E-05 O.OOE+OO mrem/yr) | |||
Tritium, Iodines, and Particulates (with half-lives greater than 8 daJls) | Tritium, Iodines, and Particulates (with half-lives greater than 8 daJls) | ||
Percent of Quarterly Dose Limit (7.5 mrem) | Percent of Quarterly Dose Limit (7.5 mrem) 5.71E-03 1.29E-02 1.07E-02 1.09E-02 Percent of Annual Dose Limit to Date (15 2.85E-03 9.28E-03 1.46E-02 1.99E-02 mrem) | ||
Percent of Organ Dose Limit (1500 mrem/yr 1.16E-04 2.57E-04 2.11 E-04 2.20E-04 | |||
Percent of Organ Dose Limit (1500 mrem/yr | |||
Table | Table 1 B Gaseous ATTACHMENT 3 Page 1 of 2 Effluents - Elevated Releases Unit 1 Unit2 X | ||
Nuclides Released | Reuorting Period: Januarz! - December 2017 GASEOUS EFFLUENTS-ELEVATED RELEASE Continuous Mode (2) | ||
I | Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter I | ||
Argon-41 | I I | ||
Krypton-BS Krypton-BSm | Fission Gases (1) | ||
3.43E-01 Xenon-13B | Argon-41 Ci Krypton-BS Ci Krypton-BSm Ci Krypton-B7 Ci 1.43E-01 Krypton-BB Ci Xenon-127 Ci Xenon-131m Ci Xenon-133 Ci Xenon-133m Ci Xenon-135 Ci 5.76E-02 Xenon-135m Ci 3.43E-01 Xenon-137 Ci Xenon-13B Ci 1.65E+OO Iodines (1) lodine-131 Ci I I | ||
lodine-133 | I I | ||
1.16E-04 | I lodine-133 Ci 1.16E-04 lodine-135 Ci Particulates (1) lei I | ||
Chromium-51 I | |||
lron-55 | Manganese-54 Ci lron-55 Ci lron-59 Ci Cobalt-SB Ci Cobalt-60 Ci Neodymium-14 7 Ci Zinc-65 Ci Strontium-B9 Ci Strontium-90 Ci Niobium-95 Ci Zirconium-95 Ci Molybdenum-99 Ci Ruthenium-103 Ci Cesium-134 Ci Cesium-136 Ci Cesium-137 Ci Barium-140 Ci Lanthanum-140 Ci Cerium-141 Ci Cerium-144 Ci Tritium (1) | ||
Neodymium- | Ci I | ||
Cesium-136 | 1.69E+01 I | ||
Tritium (1) | .1.63E+01 I | ||
1.57E+01 I | |||
2.01E+01 I | |||
(1) | (1) | ||
* Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of 1.00E-04 µCi/ml for required noble gases, 1.00E-11 µCi/ml for required particulates and gross alpha, 1.00E-12 µCi/ml for required Iodine~, 1.00E-11 | * Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of 1.00E-04 µCi/ml for required noble gases, 1.00E-11 µCi/ml for required particulates and gross alpha, 1.00E-12 µCi/ml for required Iodine~, 1.00E-11 | ||
µCi/ml for Sr-B9/90 and 1.00E-06 µCi/ml for Tritium, as required by the ODCM, has. been verified. | |||
(2) Contributions from purges are included. There were no other batch releases during the reporting period. | (2) Contributions from purges are included. There were no other batch releases during the reporting period. | ||
ATTACHMENT 3 | ATTACHMENT 3 Page 2 of 2 Unit 1 Unit2 X | ||
Nuclides Released | Re12orting Period: Janua!Jl - December 2017 GASEOUS EFFLUENTS - ELEVATED RELEASE Batch Mode (2) | ||
Argon-41 | Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Fission Gases (1) | ||
Xenon-127 | Argon-41 Ci Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-BB Ci Xenon-127 Ci Xenon-131m Ci Xenon-133 Ci Xenon-133m Ci Xenon-135 Ci Xenon-135m Ci Xenon-137 Ci Xenon-138 Ci Iodines (1) lodine-131 Ci lodine-133 Ci lodine-135 I | ||
Xenon-131m | Ci Particulates (11 Chromium-51 Ci Manganese-54 Ci lron-55 Ci lron-59 Ci Cobalt-58 Ci Cobalt-60 Ci Neodymium-147 Ci Zinc-65 Ci Strontium-89 Ci Stronium-90 Ci Niobium-95 Ci Zirconium-95 Ci Molybdenum-99 Ci Ruthenium-103 Ci Cesium-134 Ci Cesium-136 Ci Cesium-137 Ci Barium-140 Ci Lanthanum-140 Ci Cerium-141 Ci Cerium-144 Ci Tritium (1) | ||
Xenon-133 | Ci I | ||
Xenon-133m | I I | ||
Xenon-135 | I I | ||
Xenon-135m | (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of 1.00E-04 µCi/ml for required noble gases, 1.00E-11 µCi/ml for required particulates and gross alpha, 1.00E-12 µCi/ml for required Iodines, 1.00E-~ 1 | ||
Xenon-137 | µCi/ml for Sr-89/90 and 1.00E-06 µCi/ml for Tritium, as required by the ODCM, has been verified. | ||
Xenon-138 | (2) Contributions from purges are included. There were no other batch releases during the reporting period. | ||
Iodines (1) lodine-131 | |||
lodine-133 | |||
lodine-135 | |||
Particulates (11 | |||
Chromium-51 | |||
Manganese-54 | |||
lron-55 | |||
lron-59 | |||
Cobalt-58 | |||
Cobalt-60 | |||
Neodymium-147 | |||
Zinc-65 | |||
Strontium-89 Stronium-90 | |||
Zirconium-95 | |||
Molybdenum-99 | |||
Ruthenium-103 | |||
Cesium-134 | |||
Cesium-136 | |||
Cesium-137 | |||
Barium-140 | |||
Lanthanum-140 | |||
Cerium-141 | |||
Cerium-144 | |||
Tritium (1) | |||
I | |||
I | |||
I | |||
(2) Contributions from purges are included. There were no other batch releases during the reporting period. | |||
Table 1C | Table 1C ATTACHMENT 4 Page 1 of 2 Unit 1 Unit2 X | ||
Nuclides Released | ReRorting Period: Janua01 - December 2017 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode (2) | ||
I I | Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter I | ||
Argon-41 | I I | ||
Krypton-BS Krypton-B5m Ci | I Fission Gases {1) | ||
Krypton-B7 Krypton-BB Ci | Argon-41 Ci Krypton-BS Ci Krypton-B5m Ci Krypton-B7 Ci Krypton-BB Ci Xenon-127 Ci Xenon-131m Ci Xenon-133 Ci Xenon-133m Ci Xenon-135 Ci Xenon-135m Ci Xenon-137 Ci Xenon-138 Ci Iodines {1) lodine-131 Ci I | ||
Xenon-127 Xenon-131m Ci | I I | ||
Xenon-133 Xenon-133m Ci | I I | ||
Xenon-135 Xenon-135m Ci | lodine-133 Ci lodine-135 Ci Pkrticulates m I | ||
Xenon-137 Xenon-138 Ci | lromium-51 Ci I.. | ||
Iodines {1) lodine-131 | anganese-54 Ci I.. | ||
Ci | lron-55 Ci lron-59 Ci Cobalt-58 Ci Cobalt-60 Ci 3.29E-05 Neodymium-14 7 Ci Zinc-65 Ci Strontium-B9 Ci Strontium-90 Ci Niobium-95 Ci Zirconium-95 Ci Molybdenum-99 Ci Ruthenium-103 Ci Cesium-134 Ci Cesium-136 Ci Cesium-137 Ci 3.92E-06 Barium-140 Ci Lanthanum-140 Ci Cerium-141 Ci Cerium-144 Ci Tritium {1) | ||
Ci I 9.44E+OO I 2.75E+01 I 1.99E+01 I 2.13E+01 I (1) Concentrations less than the lower limit of detection of the counting system used* are indicated with a double asterisk. A lower limit of detection of 1.00E-04 µCi/ml for required noble gases, 1.00E~11 µCi/ml for required particulates and gross alpha, 1.00E-12 µCi/ml for required iodines, 1.00E - | |||
Cobalt-60 | |||
3.29E-05 Zinc-65 Strontium-B9 Ci | |||
Strontium-90 Niobium-95 | |||
Tritium {1) | |||
11 µCi/ml for Sr-B9/90 and 1.00E-06 µCi/ml for Tritium, as required by the ODCM, has been verified. | 11 µCi/ml for Sr-B9/90 and 1.00E-06 µCi/ml for Tritium, as required by the ODCM, has been verified. | ||
(2) There were no batch releases from this path during the reporting period. | (2) There were no batch releases from this path during the reporting period. | ||
Table 1C | Table 1C ATTACHMENT 4 Page2 of2 Unit 1 Unit2 X | ||
Re1;1orting Period: Janua!Y - December 2017 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Batch Mode Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter I | |||
Fission Gases {1} | Fission Gases {1} | ||
Ar-41 | Ar-41 Ci Kr-85 Ci Kr-85m Ci Kr-87 Ci Kr-88 Ci Xe-127 Ci Xe-131m Ci Xe-133 Ci Xe-133m Ci Xe-135 Ci Xe-135m Ci Xe-137 Ci Xe-138 Ci Iodines {11 1-131 Ci I | ||
Kr-85 | ** I I | ||
Kr-85m | I | ||
Kr-87 | ** I 1-132 Ci 1-133 Ci I | ||
Kr-88 | Particulates {1} | ||
Xe-127 | I Cr-51 Ci I | ||
Xe-131m | Mn-54 Ci Fe-55 Ci Fe-59 Ci Co-58 Ci Co-60 Ci Nd-147 Ci Zn-65 Ci Sr-89 Ci Sr-90 Ci Nb-95 Ci Zr-95 Ci Mo-99 Ci Ru-103 Ci Cs-134 Ci Cs-136 Ci Cs-137 Ci Ba-140 Ci La-140 Ci Ce-141 Ci Ce-144 Ci Tritium {1} | ||
Xe-133 | Ci I | ||
Xe-133m | I I | ||
Xe-135 | I I | ||
Xe-135m | (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double **. | ||
Xe-137 | |||
Xe-138 | |||
Iodines {11 1-131 | |||
1-132 1-133 Ci | |||
Fe-55 | |||
Fe-59 | |||
Co-58 | |||
Co-60 | |||
Nd-147 | |||
Zn-65 | |||
Sr-89 | |||
Sr-90 | |||
Nb-95 | |||
Zr-95 | |||
Mo-99 | |||
Ru-103 | |||
Cs-134 | |||
Cs-136 | |||
Cs-137 | |||
Ba-140 | |||
La-140 | |||
Ce-141 | |||
Ce-144 | |||
Tritium {1} | |||
I | |||
I | |||
I | |||
Table 2A | Table 2A ATTACHMENT 5 Page 1 of 2 Unit 1 Unit2 X | ||
Re12orting Period: Janua!:)l - December 2017 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES (1) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Est. Total Error, % | |||
A. 1-1ss1on & Act1vat1on t-'roaucts | A. 1-1ss1on & Act1vat1on t-'roaucts | ||
: 1. Total Release (not including Tritium, | : 1. Total Release (not including Tritium, Ci No Releases No Releases No Releases No Releases 5.00E+01 gases, alpha) | ||
: 2. Average diluted concentration during | : 2. Average diluted concentration during i | ||
reporting period | |||
: 2. Average diluted concentration during the | µCi/ml No Releases No Releases No Releases No Releases B. Tritium 1.Total release Ci No Releases No Releases No Releases No Releases 5.00E+01 | ||
: 2. Average diluted concentration during the | |||
: 1. Total release | µCi/ml No Releases No Releases No Releases No Releases reporting period C. Dissolved and Entrained Gases | ||
: 2. Average diluted concentration during the | : 1. Total release Ci No Releases No Releases No Releases No Releases 5.00E+01 | ||
: 2. Average diluted concentration during the | |||
: 1. Total release | µCi/ml No Releases No Releases No Releases No Releases reporting period D. Gross Al11ha Radioactivit~ | ||
: 1. Prior to Dilution | : 1. Total release Ci No Releases No Releases No Releases No Releases 5.00E+01 E. Volumes | ||
: 2. Volume of dilution water used during | : 1. Prior to Dilution Liters No 1 | ||
: 3. Volume of dilution water available during Liters | Releases No Releases No Releases No Releases 5.00E+01 I | ||
: 2. Volume of dilution water used during Liters N~ Releases No Releases No Releases No Releases 5.00E+01 release period | |||
Percent of Annual Whole Body Dose Limit to | : 3. Volume of dilution water available during Liters 1.08E+10 1.15E+10 1.31E+10 1.16E+10 5.00E+01 reporting period F. Percent of Tech. S11ec. Limits Percent of Quarterly Whole Body Dose Limit 0.00E+OO O.OOE+OO 0.00E+OO O.OOE+OO (1.5 mrem) | ||
Percent of Annual Whole Body Dose Limit to O.OOE+OO O.OOE+OO 0.00E+OO 0.00E+OO Date (3 mrem) | |||
Percent of Quarterly Organ Dose Limit (5 | Percent of Quarterly Organ Dose Limit (5 O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO mrem) | ||
Percent of Annual Organ Dose Limit to Date O.OOE+OO O.OOE+OO 0.00E+OO 0.00E+OO (10 mrem) | |||
Percent of Annual Organ Dose Limit to Date | |||
Percent of 10CFR20 Concentration Limit (2), | Percent of 10CFR20 Concentration Limit (2), | ||
O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO (3) | |||
Percent of Dissolved or Entrained Noble Gas | Percent of Dissolved or Entrained Noble Gas O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Limit (2.00E-04 µCi/ml) | ||
(1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of 5.00E-07 µCi/ml for required gamma emitting nuclides, 1.00E-05 µCi/ml for required dissolved and entrained noble gases and tritium, 5.00E-08 | |||
(1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of 5.00E-07 µCi/ml for required gamma emitting nuclides, 1.00E-05 µCi/ml for required dissolved and entrained noble gases and tritium, 5.00E-08 | µCi/ml for Sr-8~/90, 1.00E-06 µCi/ml for 1-131 and Fe-55, and 1.00E-07 µCi/ml for gross alpha radioactivity, as required by the Off-Site Dose Calculation Manual (ODCM), has been verified. | ||
(2) The percent of 1_0CFR20 concentration limit is based on the average concentration during the quarter. | (2) The percent of 1_0CFR20 concentration limit is based on the average concentration during the quarter. | ||
(3) Improved Technicai ~pecifications limit the concentration of radioactive material released in the liquid effluents to unrestricted areas to ten times the concentrations specified in 10CFR20.1001 - 20.2402, Appendix B, Table 2, Column 2. Maximum Effluent Concentrations (MEC) numerically equal | (3) Improved Technicai ~pecifications limit the concentration of radioactive material released in the liquid effluents to unrestricted areas to ten times the concentrations specified in 10CFR20.1001 - 20.2402, Appendix B, Table 2, Column 2. Maximum Effluent Concentrations (MEC) numerically equal | ||
.to ten times ihe 10CF_R20.1001 - 20.2402 concentrations were adopted to evaluate liquid effluents. | |||
Table2B | Table2B ATTACHMENT 5 Page 2 of 2 Unit 1 Unit2 X | ||
Nuclides Released | Rei;iorting Period: Janua!Y - December 2017 LIQUID EFFLUENTS RELEASED Batch Mode (1),(2) | ||
Nuclides Released I | Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Nuclides Released I | ||
Strontium-89 | I Strontium-89 Ci No Releases No Releases No Releases No Releases Strontium-90 Ci No Releases No Releases No Releases No Releases Cesium-134 Ci No Releases No Releases No Releases No Releases Cesium-137 Ci No Releases No Releases No Releases No Releases lodine-131 Ci No Releases No Releases No Releases No Releases Cobalt-58 Ci No Releases No Releases No Releases No Releases Cobalt-60 Ci No Releases No Releases No Releases No Releases lron-59 Ci No Releases No Releases No Releases No Releases Zinc-65 Ci No Releases No Releases No Releases No Releases Manganese-54 Ci No Releases No Releases No Releases No Releases Chromium-51 Ci No Releases No Releases No Releases No Releases Zirconium-95 Ci No Releases No Releases No Releases No Releases Niobium-95 Ci No Releases No Releases No Releases No Releases Molybderm-99 Ci No Releases No Releases No Releasf!S No Releases Techneti m-99m Ci No Releases No Releases No Releas~s No Releases Barium-1ii0 Ci No Releases No Releases No Releases No Releases Lanthanum-140 Ci No Releases No Releases No Releases No Releases Cerium-141 Ci No Releases No Releases No Releases No Releases Tungsten-187 Ci No Releases No Releases No Releases No Releases Arsenic-76 Ci No Releases No Releases No Releases No Releases lodine-133 Ci No Releases No Releases No Releases No Releases lron-55 Ci No Releases No Releases No Releases No Releases Neptunium-239 Ci No Releases No Releases No Releases No Releases Si1ver-110m Ci No Releases No Releases No Releases No Releases Gold-199 Ci No Releases No Releases No Releases No Releases Cerium-144 Ci No Releases No Releases No Releases No Releases Cesium-136 Ci No Releases No Releases No Releases No Releases Copper-64 Ci No Releases No Releases No Releases No Releases Dissolved or Entrained Gases Ci I No Releases I No Releases I No Releases I No Releases I Tritium Ci I No Releases I No Releases I No Releases I No Releases I (1) No contin*uous mode release occurred during the report period as indicated by effluent sampling. | ||
(2) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of 5.00E-07 µCi/ml for required gamma-emitting nucfides, 1.00E-05 µCi/ml for required dissolved and entrained noble gases and tritium, 5.00E-08 | (2) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of 5.00E-07 µCi/ml for required gamma-emitting nucfides, 1.00E-05 µCi/ml for required dissolved and entrained noble gases and tritium, 5.00E-08 | ||
µCi/ml for Sr-89/90, 1.00E-06 µCi/ml for 1-131 and Fe-55,- and 1.00E-07 µCi/ml for gross alpha radioactivity, as identified in the ODCM, has been verified. | |||
Table 3 | Table 3 ATTACHMENT 6 Page 1 of 4 Unit 1 Unit2 X | ||
(ma) | Re!;!Orting Period: Janua!Jl - December 2017 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A1. TYPE Volume Activitll {1} | ||
Totals | (ma) | ||
(Ci) | |||
' i i | |||
Class Class A | |||
B C | |||
A B | |||
C a.1 Spent Resin (Dewatered) 2.70E+01 O.OOE+OO O.OOE+OO 5.17E+01 O.OOE+OO O.OOE+OO a.2 Filter Sludge O.OOE+OO 5.38E+OO O.OOE+OO 0.00E+OO 1, 11 E+03 0.00E+OO a.3 Concentrated Waste 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O,OOE+OO O.OOE+OO Totals 2.70E+01 5.38E+OO O.OOE+OO 5.17E+01 1,11E+03 O.OOE+OO b.1 Dry Compressible Waste 3.75E+02 O.OOE+OO O.OOE+OO 2.69E-01 O.OOE+OO O.OOE+OO b.2 Dry Non-Compressible Waste (Contaminated O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Equipment) | |||
Totals 3.75E+02 O.OOE+OO 0.00E+OO 2.69E-01 O.OOE+OO O.OOE+OO I | |||
I I | |||
I I | I I | ||
: c. Irradiated Components, O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0,00E+OO O.OOE+OO Control Rods, etc. | |||
: c. Irradiated Components, O.OOE+OO | : d. Other (to vendor for processing) d.1 Oilywaste 3.67E+01 O.OOE+OO O.OOE+OO 2.95E+02 0.00E+OO O.OOE+OO (1) The estimated total error is 5.0E+01 %. | ||
: d. Other (to vendor for processing) d.1 Oilywaste | |||
Table 3 | Table 3 ATTACHMENT 6 Page 2 of 4 Unit 1 Unit 2 X | ||
: c. Irradiated Components, NIA | Reporting Period: January - December 2017 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A1. TYPE Container Package Solidification Agent a.1 Spent Resin (Dewatered) | ||
Poly Liner General Design None a.2 Filter Sludge Poly Liner Type B None b.1 Dry Compressible Waste Seavan General Design None b.2 Dry Non-Compressible Waste (contaminated NIA NIA Nia equipment) | |||
: c. Irradiated Components, NIA NIA NIA Control Rods | |||
: d. Other (To vendor for processing) | : d. Other (To vendor for processing) | ||
Oil/Aqueous Liquid | Oil/Aqueous Liquid 55 gallon drums General Design None I | ||
I | I | ||
Table 3 | Table 3 ATTACHMENT 6 Page 3 of 4 Unit 1 Unit 2 X | ||
: a. Spent Resins, Filter Sludges, Concentrated Waste Nuclide | Re[!orting Period: Janua!Y - December 2017 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE) | ||
37.00% | : a. Spent Resins, Filter Sludges, Concentrated Waste Nuclide Percent Curies Fe-55 59.09% | ||
Mn-54 | 6.89E+02 4.31E+02 Co-60 37.00% | ||
Mn-54 1.51% | |||
1.76E+01 Zn-65 1.39% | |||
1.62E+01 | |||
: b. Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment) | : b. Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment) | ||
Nuclide | Nuclide Percent Curies Fe-55 67.14% | ||
1.80E-01 Co-60 28.91% | |||
7.76E-02 Mn-54 1.56% | |||
4.20E-03 | |||
: c. Irradiated Components, Control Rods: There were no shipments. | : c. Irradiated Components, Control Rods: There were no shipments. | ||
Nuclide | Nuclide I | ||
Percent I | |||
N/A N/A | |||
: d. Other: (To vendor for processing) | : d. Other: (To vendor for processing) | ||
Nuclide | Nuclide Percent Curies Fe-55 79.67% | ||
2.35E+02 Co-60 18.61% | |||
5.50E+01 Mn-54 1.21% | |||
3.57E+OO | |||
Table 3 | Table 3 ATTACHMENT 6 Page 4 of 4 Unit 1 Unit2 X | ||
Number of Shi12ments | Re(!orting Period: Janua!}! - December 2017 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A3. SOLID WASTE DISPOSITION Number of Shi12ments Mode of Trans12ortation Destination 14 Truck.highway Bear Creek 6 | ||
I | Truck.highway Clive 2 | ||
Truck,highway wcs B. IRRADIATED FUEL SHIPMENTS (Disposition) | |||
Number of Shi12ments Mode of Trans(!ortation Destination 0 | |||
NIA N/A D. SEWAGE WASTES SHIPPED TO A TREATMENT FACILITY FOR PROCESSING AND BURIAL There are no shipments of sewage sludge with detectible quantities of plant-related nuclides from NMP to the treatment facility during the reporting period. | |||
I I | |||
ATTACHMENT 7 | ATTACHMENT 7 Page 1 of 1 Unit 1 Unit2 X | ||
Re~orting Period: Janua!Jl - December 2017 | |||
==SUMMARY== | ==SUMMARY== | ||
OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL (ODCM) | OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL (ODCM) | ||
The Unit 2 Off-Site Dose Calculation Manual (ODCM) was not revised during the reporting period. | The Unit 2 Off-Site Dose Calculation Manual (ODCM) was not revised during the reporting period. | ||
REVISION XX New/Amended | REVISION XX Page# | ||
I | New/Amended Description of Change Reason For Change Section# | ||
I I | |||
REVISION XX Page# | |||
New/Amended Description of Change Reason For Change Section# | |||
ATTACHMENT 8 | ATTACHMENT 8 Page 1 of 1 Unit 1 Unit 2 X | ||
Reporting Period: January - December 2017 | |||
==SUMMARY== | ==SUMMARY== | ||
OF CHANGES TO THE PROCESS CONTROL PROGRAM (PCP) | OF CHANGES TO THE PROCESS CONTROL PROGRAM (PCP) | ||
RW-AA-100, PROCESS CONTROL PROGRAM FOR RADIOACTIVE WASTES, was updated to remove Fort Calhoun from the procedure and include James A. Fitzpatrick Nuclear. | RW-AA-100, PROCESS CONTROL PROGRAM FOR RADIOACTIVE WASTES, was updated to remove Fort Calhoun from the procedure and include James A. Fitzpatrick Nuclear. | ||
ATTACHMENT 9 | ATTACHMENT 9 Page 1 of 1 Unit 1 Unit2 X | ||
Rei;iorting Period: Janua!Jl - December 2017 | |||
==SUMMARY== | ==SUMMARY== | ||
OF NON-FUNCTIONAL MONITORS Dates Monitor was | OF NON-FUNCTIONAL MONITORS Monitor Dates Monitor was Cause and Corrective Actions Non-Functional 2LWS-CAB206, January 1, 2017 to No liquid waste dis,charges were performed during 2017, and therefore, these 2LWS-FT330 & | ||
I | December 31, 2017 monitors were not returned to seNice. The discharge manual isolation 2LWS-FT331, valves, 2LWS-V420 and 2LWS-V422, are locked closed during inoperable Liquid Waste periods, therefore, no inadvertent discharge can occur. Reference Equipment Discharge Monitor Status Log (ESL) 2010-0243. | ||
I I | |||
ATTACHMENT 10 | ATTACHMENT 10 Page 1 of 4 Unit 1 Unit2_X_ | ||
Reporting Period: January - Decembe~ 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY Introduction An assessment of the radiation dose potentially received by a Member of the Public due to their activities inside the site boundary from Nine Mile Point Unit 2 (NMP2).liquid and gaseous effluents has been conducted for the period January through December 2017. | |||
This assessment considers the maximum exposed individual and the various exposure pathways resulting from liquid and gaseous effluents to identify the maximum dose received by a Member of the Public during their activities within the site boundary. | This assessment considers the maximum exposed individual and the various exposure pathways resulting from liquid and gaseous effluents to identify the maximum dose received by a Member of the Public during their activities within the site boundary. | ||
Prior to September 11, 2001, the public had access to the Energy Information Center for purposes of observing the educational displays or for picnicking and associated activities. Fishing also occurred near the shoreline adjacent to the Nine Mile Point (NMP) site. Fishing near the shoreline adjacent to the NMP site was the onsite activity that resulted in the potential maximum dose received by a Member of the Public. Following September 11, 2001 public access to the Energy Information Center has been restricted and fishing by Members of the Public at locations on site is also prohibited. Although fishing was not conducted during 2017 the annual dose to a hypothetical fisherman was still evaluated to provide continuity of data for the location. | Prior to September 11, 2001, the public had access to the Energy Information Center for purposes of observing the educational displays or for picnicking and associated activities. Fishing also occurred near the shoreline adjacent to the Nine Mile Point (NMP) site. Fishing near the shoreline adjacent to the NMP site was the onsite activity that resulted in the potential maximum dose received by a Member of the Public. Following September 11, 2001 public access to the Energy Information Center has been restricted and fishing by Members of the Public at locations on site is also prohibited. Although fishing was not conducted during 2017 the annual dose to a hypothetical fisherman was still evaluated to provide continuity of data for the location. | ||
Dose Pathways Dose pathways considered for this evaluation included direct radiation, inhalation and external grou~d (shoreline sediment or soil doses). Other pa+ways, such as ingestion pathways, are not considered becau e they are either not applicable, insignificant, or are considered as part of the evaluation of the total dose to a member of the public located off-site. In addition, only releases from the NMP2 Stack and Radwaste/Reactor Building Vent were evaluated for the inhalation pathway. Dose due to aquatic pathways such as liquid effluents is not applicable since swimming is prohibited at the NMP site. | Dose Pathways Dose pathways considered for this evaluation included direct radiation, inhalation and external grou~d (shoreline sediment or soil doses). Other pa+ways, such as ingestion pathways, are not considered becau e they are either not applicable, insignificant, or are considered as part of the evaluation of the total dose to a member of the public located off-site. In addition, only releases from the NMP2 Stack and Radwaste/Reactor Building Vent were evaluated for the inhalation pathway. Dose due to aquatic pathways such as liquid effluents is not applicable since swimming is prohibited at the NMP site. | ||
Dose to a hypothetical fisherman is received through the following pathways while standing on the shoreline fishing: | Dose to a hypothetical fisherman is received through the following pathways while standing on the shoreline fishing: | ||
External ground pathway; this dose is received from plant related radionuclides detected in the ~horeline sediment. | |||
Inhalation pathway; this dose is received through inhalation of gaseous effluents released from the NMP2 Stack and Radwaste/Reactor Building Vent. | |||
Direct radiation pathway; dose resulting from the operation of Nine Mile Point Unit 1 (NMPl), NMP2 and the James A. Fitzpatrick Nuclear Power Plant (JAFNPP) Facilities. | |||
Methodologies for Determining Dose for Applicable Pathways External Ground (Shoreline Sediment) Pathway Dose from the external ground (shoreline sediment) is based on the methodology in the NMP2 Offsite Dose Calculation Manual (ODCM) as adapted from Regulatory Guide 1.109. For this evaluation it is assumed that the hypothetical maximum exposed individual fished from the shoreline at all times. | Methodologies for Determining Dose for Applicable Pathways External Ground (Shoreline Sediment) Pathway Dose from the external ground (shoreline sediment) is based on the methodology in the NMP2 Offsite Dose Calculation Manual (ODCM) as adapted from Regulatory Guide 1.109. For this evaluation it is assumed that the hypothetical maximum exposed individual fished from the shoreline at all times. | ||
ATTACHMENT 10 | ATTACHMENT 10 Page 2 of 4 Unit 1 Unit2_X_ | ||
Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY The total dose received by the whole body and skin of the maximum exposed individual during 2017 was calculated using the following input parameters: | |||
Usage Factor= 312 hours (fishing 8 hours per week, 39 weeks per year) | |||
Density in grams per square meter= 40,000 Shore width factor= 0.3 Whole body and skin dose factor for each radionuclide = Regulatory Guide 1.109, Table E-6. | |||
Fractional portion of the year= 1 (used average radionuclide concentration over total time period) | |||
Average Cs-137 concentration= 1.30E-01 pCi/g The total whole body and skin doses received by a hypothetical maximum exposed fisherman from the external ground pathway is presented in Table 1, Exposure Pathway Annual Dose. | |||
Inhalation Pathway The inhalation dose pathway is evaluated by utilizing the inhalation equation in the NMP2 ODCM, as adapted from Regulatory Guide 1.109. The total whole body dose and organ dose received by the hypothetical maximum exposed fisherman during 2017 calculated using the following input parameters for gaseous effluents released from both the NMP2 Stack and Radwaste/Reactor Building Vent for the time period exposure is received: | Inhalation Pathway The inhalation dose pathway is evaluated by utilizing the inhalation equation in the NMP2 ODCM, as adapted from Regulatory Guide 1.109. The total whole body dose and organ dose received by the hypothetical maximum exposed fisherman during 2017 calculated using the following input parameters for gaseous effluents released from both the NMP2 Stack and Radwaste/Reactor Building Vent for the time period exposure is received: | ||
NMP2Stack* | NMP2Stack* | ||
I Vari hie | I Vari hie Fisherman 1 I | ||
Variable | X/Q (s/m3) 9.6 E-07 Inhalation dose factor Table E-7, Regulatory Guide 1.109 Annual air intake (m3/year) (adult) 8000 Fractional portion of the year 0.0356 H-3 (pCi/sec) 2.21 E+06 C-14 (pCi/sec/ | ||
X/0 (slm ) | 6.00 E+05 NMP2 Radwaste/Reactor Building Vent: | ||
Cs-137(pCi/sec) | Variable Fisherman 1 X/0 (slm 3 | ||
) | |||
2.8 E-06 Inhalation dose factor Table E-7, Regulatory Guide 1.109 Annual air intake (m 3/year) (adult) 8000 Fractional portion of the year 0.0356 H-3 (pCi/sec) 2.91E+06 Co-60 (pCi/sec) 1.40E+oo* | |||
Cs-137(pCi/sec) l.66E-Ol | |||
ATTACHMENT 10 | Unit 1 ATTACHMENT 10 Page 3 of4 Unit2_X_ | ||
Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY | |||
: 1. The maximum exposed fisherman is assumed to be present on site during the period of April through December at a rate of 8 hours per week for 39 weeks per year equivalent to 312 hours for the year (fractional portion of the year = 0.0356). Therefore, the Average Stack and Radwaste/Reactor Building Vent flow rates and radionuclide concentrations used to determine the dose are represented by second, third and fourth quarter gaseous effluent flow and concentration values. | : 1. The maximum exposed fisherman is assumed to be present on site during the period of April through December at a rate of 8 hours per week for 39 weeks per year equivalent to 312 hours for the year (fractional portion of the year = 0.0356). Therefore, the Average Stack and Radwaste/Reactor Building Vent flow rates and radionuclide concentrations used to determine the dose are represented by second, third and fourth quarter gaseous effluent flow and concentration values. | ||
: 2. C-14 release rate determined from NUREG-0016, "Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents for Boiling Water Reactors (BWR-GALE Code)," | : 2. C-14 release rate determined from NUREG-0016, "Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents for Boiling Water Reactors (BWR-GALE Code)," | ||
| Line 710: | Line 920: | ||
The total whole body dose and maximum organ dose received by the hypothetical maximum exposed fisherman is presented in Table 1, Exposure Pathway Annual Dose. | The total whole body dose and maximum organ dose received by the hypothetical maximum exposed fisherman is presented in Table 1, Exposure Pathway Annual Dose. | ||
Direct Radiation Pathway The direct radiation pathway is evaluated in accordance with the methodology found in the NMP2 ODCM. | Direct Radiation Pathway The direct radiation pathway is evaluated in accordance with the methodology found in the NMP2 ODCM. | ||
This pathway considers four components: direct radiation from the generating facilities, direct radiation from any possible overhead plume, direct radiation from ground deposition and direct radiation from plume Strmersion. The direct radiation pathway is evaluated by \the use of high sensitivity environmental Tl ermoluminescent Dosimeters (TLDs). Since fishing activiti1s occur between April 1 and December 31, T D data for the second, third, and fourth quarters of 2017 from TLDs placed in the general area where fishing once occurred were used to determine an average dose to the hypothetical maximum exposed fisherman from direct radiation. The following is a summary of the average dose rate and assumed time spent on site used to determine the total dose received: | This pathway considers four components: direct radiation from the generating facilities, direct radiation from any possible overhead plume, direct radiation from ground deposition and direct radiation from plume Strmersion. The direct radiation pathway is evaluated by \\the use of high sensitivity environmental Tl ermoluminescent Dosimeters (TLDs). Since fishing activiti1s occur between April 1 and December 31, T D data for the second, third, and fourth quarters of 2017 from TLDs placed in the general area where fishing once occurred were used to determine an average dose to the hypothetical maximum exposed fisherman from direct radiation. The following is a summary of the average dose rate and assumed time spent on site used to determine the total dose received: | ||
Variable | Variable Fisherman Average Dose Rate (mRem/hr) l.04E-03 Exposure time (hours) 312 Total Doses received by the hypothetical maximum exposed fisherman from direct radiation is presented in Table 1, Exposure Pathway Annual Dose. | ||
ATTACHMENT 10 | ATTACHMENT 10 Page4 of 4 Unit 1 Unit2_X_ | ||
Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY Dose Received By A Hypothetical Maximum Exposed Member o.f the Public Inside the Site Boundary During 2017 I | |||
The following is a summary of the dose received by a hypothetical maximum exposed fisherman from liquid | |||
* and gaseous effluents released from NMP2 during 2017: | * and gaseous effluents released from NMP2 during 2017: | ||
TABLE 1 Exposure Pathway Annual Dose Fisherman Exposure Pathway | TABLE 1 Exposure Pathway Annual Dose Fisherman Exposure Pathway Dose Type (mreni) | ||
Whole Body | Whole Body 2.04E-03 External Ground Skin of Whole Body 2.38E-03 Whole Body 5.32E-04 Inhalation Maximum Organ Lung: 5.33E-04 Thyroid 5.32E-04 Direct Radiation Whole Body 0.32 Based on these values, the total annual dose receivfd by a hypothetical maximum exposed Member of the Public inside the site boundary is as follows: | ||
Total Whole Body | I TABLE2 Annual Dose Summary Fisherman Total Annual Dose for 2017 (mrem) | ||
Total Whole Body 3.26E-01 Skin of Whole Body 2.38E-03 Maximum Organ Lung: 5.33E-04 Thyroid 5.32E-04 | |||
ATTACHMENT 11 | ATTACHMENT 11 Page 1 of 5 Unit 1 Unit2_X __ | ||
40 CPR 190 requires the annual radiation dose received by Members of the Public in the general environment, as a result of plant operations, be limited to: | Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Introduction An assessment of radiation doses potentially received by the l~kely most exposed Meinber of the Public located beyond the site boundary was conducted for the period January through December 2017 for comparison against the 40 CPR 190 annual dose limits. | ||
/ | |||
I The intent of 40 CPR 190 requires that the effluents of Nine Mile Point Unit 2 (NMP2), as well as other nearby uranium fuel cycle facilities, be considered. In this case, the effluents of Nine Mile Point Unit 1 (NMPl), NMP2 and the James A. FitzPatrick Nuclear Power Plant (JAFNPP) facilities must be considered. | |||
40 CPR 190 requires the annual radiation dose received by Members of the Public in the general environment, as a result of plant operations, be limited to: | |||
< 25 mRem whole body | |||
< 25 mRem any organ ( except thyroid) | |||
< 75 mRem thyroid This evaluation compares doses resulting from liquid and gaseous effluents and direct radiation originating from the site as a result of the operation of the NMPl, NMP2 and JAFNPP nuclear facilities. | |||
Dose Pathways Dose pathways considered for this evaluation included doses resulting from liquid effluents, gaseous effluents and direct radiation from all nuclear operating facilities located on the Nine Mile Point site. | Dose Pathways Dose pathways considered for this evaluation included doses resulting from liquid effluents, gaseous effluents and direct radiation from all nuclear operating facilities located on the Nine Mile Point site. | ||
D9se to the likely most exposed Member otthe Public, outside the site boundary, is received through the | D9se to the likely most exposed Member otthe Public, outside the site boundary, is received through the Ji 1 | ||
ollowing pathways: | |||
r Fish consumption pathway; this dose is received from plant radionuclides that have concentrated in fish that is consumed by a Member of the Public. | |||
Vegetation consumption pathway; this dose is received from plant radionuclides that have concentrated in vegetation that is consumed by a Member of the Public. | |||
Shoreline Sediment; this dose is received as a result of an individual's exposure to plant radionuclides in the shoreline sediment, which is used as a recreational area. | |||
Deposition, Inhalation and Ingestion pathways resulting from gaseous effluents; this dose is received through exposure to gaseous effluents released from NMPl, NMP2 and JAFNPP operating facilities. | |||
Direct Radiation pathway; radiation dose resulting from the operation ofNMPl, NMP2 and JAFNPP facilities (including the Independent Spent Fuel Storage Installations (ISFSI)). | |||
Methodologies for Determining Dose for Applicable Pathways Fish Consumption D9se received as a result of fish consumption is based on the methodology specified in the NMP2 Off-Site Dose Calculation Manual (ODCM) as adapted from Regulatory Guide 1.109. The dose for 2017 is calculated from | Methodologies for Determining Dose for Applicable Pathways Fish Consumption D9se received as a result of fish consumption is based on the methodology specified in the NMP2 Off-Site Dose Calculation Manual (ODCM) as adapted from Regulatory Guide 1.109. The dose for 2017 is calculated from | ||
_actuaLanalysis results of environmental fish samples taken near the site discharge points. For this evaluation it is | _actuaLanalysis results of environmental fish samples taken near the site discharge points. For this evaluation it is | ||
** asimme_d that the most likely exposed Member of the Public consumes fish taken near the site discharge points. | ** asimme_d that the most likely exposed Member of the Public consumes fish taken near the site discharge points. | ||
N9 radionuclides were detected in fish samples collected *and analyzed during 2017; therefore, no dose was repeived by the whole body and organs of the likely most exposed Member of the Public during 2017. | N9 radionuclides were detected in fish samples collected *and analyzed during 2017; therefore, no dose was repeived by the whole body and organs of the likely most exposed Member of the Public during 2017. | ||
ATTACHMENT 11 | ATTACHMENT 11 Page 2 of 5 Unit 1 Unit2_X __ | ||
Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Vegetation Consumption Dose received as a result of vegetation cons4mption is based on the methodology specified in the NMP2 ODCM as adapted from Regulatory Guide 1.109. The dose for 2017 is calculated from actual analysis results of environmental vegetation samples taken near the most exposed Member of the Public. | |||
i No radionuclides were detected in vegetation samples collected and analyzed during 2017; therefore, no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2017. | |||
For estimating C-14, dose received as a res4lt of vegetation consumption is based on the methodology specified in the NMP2 ODCM as adapted from Regulatory Guide 1.109. The estimated concentration of C-14 in vegetation is based on the estimated concentration of C-14 in plant gaseous effluents. | For estimating C-14, dose received as a res4lt of vegetation consumption is based on the methodology specified in the NMP2 ODCM as adapted from Regulatory Guide 1.109. The estimated concentration of C-14 in vegetation is based on the estimated concentration of C-14 in plant gaseous effluents. | ||
Shor"eline Sediment Dose received from shoreline sediment is based on the methodology in the NMP2 ODCM as adapted from Regulatory Guide 1.109. For this evaluation it is assumed that the most likely exposed Member of the Public spends 67 hours/year along the shoreline for recreational purposes. | Shor"eline Sediment Dose received from shoreline sediment is based on the methodology in the NMP2 ODCM as adapted from Regulatory Guide 1.109. For this evaluation it is assumed that the most likely exposed Member of the Public spends 67 hours/year along the shoreline for recreational purposes. | ||
No radionuclides were detected in shorelin~ sediment samples collected and analyzed during 2017; therefore no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2017. | No radionuclides were detected in shorelin~ sediment samples collected and analyzed during 2017; therefore no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2017. | ||
Dose Pathwa s Resultin Fro.m Gaseous Effluents | Dose Pathwa s Resultin Fro.m Gaseous Effluents I | ||
Dose received by the likely ost exposeq Member of the Public due to gaseous efflu~nts is calculated in accordance with the methodology provided in the NMPl ODCM, NMP2 ODCM, and the JAFNPP ODCM. These calculations consider deposition, inhalatioµ and ingestion pathways. Actual meteorological data was used to calculate doses to the likely most exposed Member of the Public. The total sum of doses resulting from gaseous effluents from NMPl, NMP2 and JAFNPP during 2017 provides a total dose to the whole body and maximum organ dose for this pathway. | |||
Carbon-14 Dose Pathways Resulting from Gaseous Effluents The Carbon-14 (C-14) effluent source terms are used to estimate radiological doses from C-14 in site gaseous waste effluents. These estimates were generated in order to meet the NRC requirement to incorporate C-14 in nuclear power plant 2017 Annual Radiological Effluent Release Reports (ARERRs). The C-14 production and effluent source term estimates were based on EPRI methodology provided in EPRI Report 1021106, Estimation of Carbon-14 in Nuclear Power Plant Gaseou~ Effluents, December 2010. The following methodology was used in estimating C-14 gaseous release activity and dose components for the 2017 ARERR. | Carbon-14 Dose Pathways Resulting from Gaseous Effluents The Carbon-14 (C-14) effluent source terms are used to estimate radiological doses from C-14 in site gaseous waste effluents. These estimates were generated in order to meet the NRC requirement to incorporate C-14 in nuclear power plant 2017 Annual Radiological Effluent Release Reports (ARERRs). The C-14 production and effluent source term estimates were based on EPRI methodology provided in EPRI Report 1021106, Estimation of Carbon-14 in Nuclear Power Plant Gaseou~ Effluents, December 2010. The following methodology was used in estimating C-14 gaseous release activity and dose components for the 2017 ARERR. | ||
EPRI methodology for estimating C-14 proquction rates in.Boiling Water Reactors (BWRs): | EPRI methodology for estimating C-14 proquction rates in.Boiling Water Reactors (BWRs): | ||
ForBWRs, EPRI R.ep~rt 1021106 summarized the .distribution of C-14 in releas*e pathways as follows: gaseous 95% to 99%, liquid <0.5% and | ForBWRs, EPRI R.ep~rt 1021106 summarized the.distribution of C-14 in releas*e pathways as follows: gaseous 95% to 99%, liquid <0.5% and solid 1 % to 5%. The report also states that -95% of C., 14 in BWR gaseous waste effluents exists in the carbon dioxide form, which contributes to population dose via photosynthesis uptake in the food consumption cycle. | ||
ATTACHMENT 11 | ATTACHMENT 11 Page 3 of 5 Unit 1 Unit2_X __ | ||
Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDA~Y For NMPl and NMP2, C-14 gaseous dose calculations in the site ARERR are made using the following assumptions for each unit: (1) continuous release of the estimated C-14 generated during power operation based on the number of Effective Full Power Days (EFPDs) for the period, (2) maximum C-14 activity from literature values cited in EPRI Report 1021106, and (3) typical fraction as carbon dioxide for'. gaseous releases from literature values also cited in EPRI Report 1021106. | |||
Equation 1 estimates the maximum annual production of C-14, PRMAX, for each BWR unit. | Equation 1 estimates the maximum annual production of C-14, PRMAX, for each BWR unit. | ||
PRMAX | PRMAX | ||
* MWT / 1000 | = | ||
5.1 | |||
* MWT / 1000 | |||
[Eq 1} | |||
Where: | Where: | ||
5.1 | 5.1 | ||
MWT | = | ||
Equation 2 estimates the C-14 activity released, A c.14 , into the gaseous pathway during the time peripd for each BWR unit. | BWR Normalized Production (Ci/GWt-yr) | ||
A C-14 | MWT | ||
= | |||
Mega Watts Thermal (MWt) 1000 | |||
= | |||
Conversion Factor (MWt to GWt) | |||
Equation 2 estimates the C-14 activity released, A c.14, into the gaseous pathway during the time peripd for each BWR unit. | |||
A C-14 Where: | |||
PRMAX 0.99 EFPD 365 | |||
~ | |||
PR MAX | |||
* 0.99 | * 0.99 | ||
* EFPD I 365, Ci (for time period) | * EFPD I 365, Ci (for time period) | ||
[Eq2] | |||
= | |||
maximum annual production rate ofC-14 | |||
= | |||
fraction ofC-14 in BWR gaseous pathway releases (maximum literature value in EPRI Report 1021106; also Table 1) number of effective full power days for the unit during the time period; e.g., quarterly or yearly (Table 1) | |||
= | |||
number of days in a typical year | |||
ATTACHMENT 11 | ATTACHMENT 11 Page 4 of 5 Unit 1 Unit2_X __ | ||
A C-14, CO2 | Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Equation 3 estimates the C-14 activity released in carbon dioxide form, A C-l4, co2, into the gaseous pathway during the time period for each BWR unit. | ||
A C-14, CO2 Where: | |||
PRMAX | |||
= | |||
0.99 | |||
= | |||
0.95 | |||
= | |||
EFPD | |||
= | |||
365 PR MAX | |||
* 0.99 | * 0.99 | ||
* 0.95 | * 0.95 | ||
* EFPD I 365, Ci (for time period) | * EFPD I 365, Ci (for time period) maximum annual production rate of C-14 fraction of C-14 in BWR gaseous pathway releases (maximum literatur~ value in EPRI Report 1021106; also Table 1) fraction of C-14 as carbon dioxide in BWR gaseous pathway | ||
[Eq3} | |||
releases (typical literature value in EPRI Report 1021106; also Table 1) number of effective full power days for the unit during the time period, e.g. quarterly or yearly (Table 1) conversion factor, 365 days in a typical average year For each BWR unit, the 2017 estimated C-14 activity releases (total and carbon dioxide chemical form) are summarized in Table 1. | |||
Table 1 I | |||
Table 1 | 2017 BWR Estimated C-14 Gaseous Releases Gaseous CO2 Form Max.Annual BWR Release Release EFPD Operation Fraction(a) | ||
Fraction(a) | Fraction(b) | ||
NMPl 0.99 0.95 331.2 EFPD (90.7%) | |||
NMP2 0.99 0.95 359.85 EFPD (98.6%) | |||
JAFNPP 0.99 0.95 309.1 EFPD (84.7%) | |||
(a) Maximum literature values from EPRI Report 1021106. | (a) Maximum literature values from EPRI Report 1021106. | ||
(b) Typical value from EPRI Report 1021106. | (b) Typical value from EPRI Report 1021106. | ||
Prod. Rate (Eq 1) 9.44 Ci/yr 20.34 Ci/yr(c) 12.93 Ci/yr | |||
As long as the core designs and power ratings are not significantly changed, the maximum annual production rates and annual total and carbon dioxide activity releases in Table 1 should be acceptable for use in estimating C-14 gaseous release activity and dose components for the ARERR. | * (c) NMP2 Reactor Power Rating increased to 3988 Megawatts thermal. | ||
2017 Total Release (Eq 2) 8.48 Ci 19.85 Ci 9.09 Ci 2017 CO2 Release (Eq3) 8.05 Ci 18.86 Ci 8.63 Ci As long as the core designs and power ratings are not significantly changed, the maximum annual production rates and annual total and carbon dioxide activity releases in Table 1 should be acceptable for use in estimating C-14 gaseous release activity and dose components for the ARERR. | |||
ATTACHMENT 11 | ATTACHMENT 11 Page 5 of 5 Unit 1 Unit 2 X | ||
Table 2 Dose Potentially Received by the Likely Most Exposed M~mber of the Public Outside the Site Boundary During 2017 Exposure Pathway | Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Direct Radiation Pathway Dose as a result of direct gamma radiation from the site, encompasses doses from direct "shine" from the generating facilities, direct radiation from any overhead gaseous plumes, plume submersion, and ground deposition. This total dose is measured by environmentai TLDs. The critical location is based on the closest year-round residence from the generating facilities as well as the closest residence in the critical downwind sector in order to evaluate both direct radiation from the generating facilities and gaseous plumes as determined by the local meteorology. During 2017, the closest residence and the critical downwind residence are at the same location. | ||
Total Whole Body | Table 2 Dose Potentially Received by the Likely Most Exposed M~mber of the Public Outside the Site Boundary During 2017 Exposure Pathway Dose Type Dose (mrem) | ||
Maximum Organ | Total Whole Body No Dose Fish and Vegetation Consumption Total Maximum Organ No Dose Total Whole Body No Dose Shoreline Sediment Total Skin of Whole Body No Dose Total Whole ~ody 4.42 E-03 Gaseous Effluents Thyroid I 1.02 E-02 (excluding C-14) | ||
Maximum Organ Thyroid: 1.02 E-02 Gaseous Effluent Total Whole Body 3.52 E-01 (C-14) | |||
Maximum Organ Bone: 1.76 E+OO Direct Radiation Total Whole Body 0.91 Based on these values the maximum total annual dose potentially received by the likely most exposed Member of the Public during 2017 is as follows: | |||
\\ | |||
Total Whole Body: | |||
1.27 E+OO mrem Total Thyroid: | |||
1.02 E-02 Maximum Organ: | |||
Bone: 1.76 E+OO mrem 40 CFR 190 Evaluation The maximum total doses presented in this attachment are the result of operations at the NMPl, NMP2 and the JAFNPP facilities. The maximum organ dose (Bone: 1.76 mrem), maximum thyroid dose (0.010 mrem) and the maximum whole body dose (1.27 mrem) are below the 40 CFR 190 criteria of 25 mrem per calendar year to the maximum exposed organ or the whole body, and below 75 mrem per calendar year to the thyroid. | |||
l ATTACHMENT 12 | l ATTACHMENT 12 Page 1 of 1 Unit 1 -- | ||
Unit2 _x_ | |||
GMX-MW1* | Regorting Period: Janua!)(- December 2017 Well Identification | ||
MW-5 | #Samples | ||
MW- | # Positive Minimum Maximum Number Collected Samples Concentration (pCiil) | ||
MW- | Concentration (pCi/1) | ||
GMX-MW1* | |||
4 0 | |||
<188 | |||
<194 MW-1 4 | |||
0 | |||
<188 | |||
<200 MW-5 4 | |||
I 0 | |||
<183 | |||
<193 MW-6 4 | |||
0 | |||
<186 | |||
<191 MW-7 4 | |||
0 | |||
<186 | |||
<194 MW-8 4 | |||
0 | |||
<187 | |||
<193 MW-91 4 | |||
0 | |||
<187 | |||
<192 MW-101 4 | |||
1 | |||
<186 240 MW-11 4 | |||
0 | |||
<186 | |||
<193 MW-12 4 | |||
0 | |||
<190 | |||
<193 MW-13 4 | |||
0 | |||
<184 | |||
<192 fvlW-14* | |||
4 1 | |||
<183 234 MW-15 4 | |||
1 | |||
<186 252 MW-16 4 | |||
0 | |||
<184 | |||
<192 MW-17 4 | |||
1 | |||
<183 222 fvlW-18 4 | |||
1 | |||
<190 270 MW-19 4 | |||
I 0 | |||
<186 | |||
<190 I | |||
MW-20 4 | |||
I 0 | |||
<183 | |||
<192 I | |||
MW-21 4 | |||
0 | |||
<183 | |||
<190 NMP2 MAT 2'3 4 | |||
1 | |||
<181 279 PZ-1 4 | |||
0 | |||
<190 | |||
<193 PZ-2 4 | |||
0 | |||
<191 | |||
<196 PZ-3 4 | |||
0 | |||
<187 | |||
<194 PZ-4 4 | |||
1 | |||
<189 214 PZ-5 4 | |||
0 | |||
<190 | |||
<191 PZ-6 4 | |||
0 | |||
<188 | |||
<192 PZ-7 4 | |||
4 291 435 PZ-8 4 | |||
0 | |||
<190 | |||
<198 PZ-9* | |||
4 0 | |||
<189 | |||
<194 Notes: | |||
* - Control Location 1 - Sentinel well location 2 - NMP2 Groundwater Depression Cone 3 | |||
- Samples collected from storm drain system which includes precipitation *}} | |||
Latest revision as of 23:27, 5 January 2025
| ML18115A103 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 04/19/2018 |
| From: | Orphanos P Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18115A92 | List: |
| References | |
| NMP1L3211 | |
| Download: ML18115A103 (61) | |
Text
Exeto:n Generation NMP1L3211 April 19, 2018 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Nine Mile Point Nuclear Station, Units 1 and 2 10 CFR 50.36a 1 O CFR 72.44(d)(3)
Technical Specifications Renewed Facility Operating License Nos. DPR-63 and NPF-69 NRC Docket Nos. 50-220 and 50-410
Subject:
Independent Spent Fuel Storage Installation (ISFSI)
ISFSI Docket No. 72-1036 2017 Radioactive Effluent Release Report for Nine Mile Point Units 1 and 2 In accordance with 1 O CFR 50.36a, and the Nine Mile Point Unit 1 (NMP1) and Nine Mile Point Unit 2 (NMP2) Technical Specifications, enclosed are the Radioactive Effluent Release Reports for NMP1 and NMP2 for the period of January through December 2017.
This letter also satisfies the annual effluent reporting requirements for the ISFSI required by 10 CFR 72.44(d)(3).
The format used for the effluent data is outlined in Appendix B of Regulatory Guide 1.21, Revision 1. During the reporting period, NMP1, NMP2, and the ISFSI did not exceed any 1 O CFR 20, 1 O CFR 50, 1 O CFR 72, Technical Specification, or ODCM limits for gaseous or liquid effluents.
Should you have questions regarding the information in this submittal, please contact Tom Tanguay, Site Chemistry Environmental & Radwaste Manager, at (315) 349-4264.
Sincerely, Peter M. Orphanos Vice President, Nine Mile Point Nuclear Station Exelon Generation Company, LLC PMO/RSP z __
~--------------------------------------------
Document Control Desk April 19, 2018 Page2
Enclosures:
(1)
Nine Mile Point Nuclear Station, Unit 1.
Radioactive Effluent Release Report, January-December 2017 (2)
Nine Mile Point Nuclear Station, Unit 2 Radioactive Effluent Release Report, January - December 2017 Cc:
NRG Regional Administrator, Region 1 NRG Project Manager NRG Resident Inspector R. Rolph, NRG
NINE MILE POINT NUCLEAR STATION - UNIT 1 RADIOACTIVE EFFLUENT RELEASE REPORT January-December 2017
Page 1 of2 NINE MILE POINT NUCLEAR STATION - UNIT 1 RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY-DECEMBER2017 SUPPLEMENTAL INFORMATION Facilitv: Nine Mile Point Unit 1 Licensee:
Nine Mile Point Nuclear Station, LLC
- 1.
TECHNICAL SPECIFICATION LIMITS/ODCM Limits A)
FISSION AND ACTIVATION GASES
- 1.
The dose rate limit of noble gases released in gaseous eftluents from the site to areas at and beyond the site boundary shall be less than or equal to 500 mrem/year to the total body and less than or equal to 3000 mrem/year to the skin.
- 2.
The air dose due to noble gases released in gaseous effluents from Nine Mile Point Unit 1 to areas at and beyond the site boundary shall be limited during any calendar quarter to less than or equal to 5 milliroentgen for gamma radiation and less than or equal to 10 mrad for beta radiation, and during any calendar year to less than or equal to l O milliroentgen for gamma radiation and less than or equal to 20 1mad for beta radiation.
B&C) TRITIUM, IODINES AND PARTICULATES, HALF LIVES> 8 DAYS
- 1.
The dose Tate limit of Iodine-131, Iodine-133, Tritium and all radionuclides in particulate form with half-lives greater than eight days, released in gaseous effluents from the site to areas at mid beyond the site boundary shall be less than or equal to 1500 rnrem/year to any organ.
- 2.
The dose to a member of the public fro!I). Iodine-131, Iodine-133, Tritium and all radionuclides in particulate
- form with half-lives greater than eight days in gaseous effluents released from Nine Mile Point Unit 1 to.
areas at and beyond the site boundmy shall be limited during any calendar quarter to less than or equal to 7.5 mrem to any organ, and during any calendar year to less than or equal to 15 mrem to any organ.
D)
LIQUID EFFLUENTS
- 1.
The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to ten times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-04 microcuries/ml total activity.
- 2.
The dose or dose conunitment to a member of the public from radioactive materials in liquid effluents released from Nine Mile Point Unit 1 to unrestricted areas shall be limited during any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 1mem to any organ, and during any calendar year to less than or equal to 3 rnrem to the total body and to less than or equal to 10 rnrem to any organ.
Page 2 of2
- 2.
MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY Described below are the methods used to measure or approximate the total radioactivity and radionuclide composition in effluents.
A)
FISSION AND ACTIVATION GASES Noble gas effluent activity is detem1ined by on-line gross activity monitoring (calibrated against gamma isotopic analysis of a 4.0L Marinelli grab sample) of an isokinetic stack sample stream.
B)
IODINES Iodine effluent activity is determined by gamma spectroscopic analysis (at least weekly) of charcoal cartridges sampled from an isokinetic stack sample stream.
C)
PARTICULATES Activity released from the main stack is determined by gamma spectroscopic analysis (at least weekly) of particulate filters sampled from an isokinetic sample stream and composite analysis of the filters for non-gamma emitters.
D)
TRITIUM Tritium effluent activity is measured by liquid scintillation or gas proportional counting of monthly samples taken with an air sparging/water trap apparatus. Tritium effluent activity is measured during pm-ge and weekly when foe! is offloaded until stable tritium release rates are demonstrated.
E)
EMERGENCY CONDENSER VENT EFFLUENTS The effluent curie quantities are estimated based on the isotopic distribution in the Condensate Storage Tank water and the Emergency Condenser shell water.
Actual isotopic concentrations are found via gamma spectroscopy. Initial release rates of Sr-89, Sr-90 and Fe-55 are e*stimated by applying scaling factors to release rates of gamma emitters and actual release rates are determined from post offsite analysis results. The activity of fission and activation gases released due to tube leaks is based on reactor steam leak rates using offgas isotopic analyses.
F)
LIQUID EFFLUENTS Isotopic contents of liquid effluents are detennined by isotopic analysis of a representative sample of each batch and composite analysis of non-gamma emitters. Tritium activity is estimated on the most recent analysis of the Condensate Storage Tank water. Initial release rates ofSr-89, Sr-90, and Fe-55. are estimated by applying scaling factors to release rates of gamma emitters and achial release rates are determined from post offsite analysis results.
G)
SOLID EFFLUENTS Isotopic contents of waste shipments are deter1nined by gamma spectroscopy analysis of a representative* sample of each batch. Scaling factors established from primary composite sample analyses conducted off-site are applied, where appropriate, to find estimated concentration of non-gamma emitters. For low activity trash shipments, curie content is estimated by dose rate measurement and application of appropriate scaling factors.
H)
C-14 The production of C-14 and the effluent dose consequences are estimates based on EPRI methodology provided in EPRI Report 1021106, Estimation ofCarbon-14 in Nuclear Power Plant Gaseous Effluents, Dec;ember 2010 and NUREG-0016, Calculation of Releases of Radioactive Materials in Gaseous and Liquid Ejjl.uents for Boiling Water Reactors (BWR-GALE Code).
- 3.
METEOROLOGICAL DATA An annual summary of hourly meteorological data collected over the previous year. This annual surnn1ary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distribution of wind speed, wind direction, and atmospheric stability. In lieu of submission with the Radiological Effluent Release Report, the licensee is exercising the option of retaining this summa1y of required meteorological data on site in a file that shall be provided to the NRC upon request.
ATTACHMENT 1 Page 1 of 2 Unit 1 X
Unit2 Re12orting Period: Janua!J£ - December 2017 Liquid Effluents:
ODCM Required Maximum Effluent Concentration (MEC) = 10 x 10CFR20, Appendix B, Table 2, Column 2 There were no batch discharges of liquid radwaste requiring use of MEC to determine allowable release rate.
There were no Emergency Condenser Vent Liquid Discharges in 2017.
Average MEC - µCi/ml (Qtr.1) =
I NO RELEASES Average MEC - µCi/ml (Qtr.1) =
I NO RELEASES I Average MEC- µCi/ml (citr.2_) =
I NO RELEASES Average MEC - µCi/ml (Qtr..4) =
I NO RELEASES I Average Energy (Fission and Activation gases - MeV):
Qrtr.1:
Ey =
N/A E13 =
N/A Qrtr.2_:
§v =
N/A
§13 =
N/A Qrtr. J.:
~y =
N/A E13 =
N/A Qrtr.1:
Ey =
N/A E13 =
N/A Liquid:
Radwaste EC Vent Number of Batch Releases 0
0 Total Time Period for Batch Releases (hrs) 0 0.00 Maximum Time Period for a Batch Release (hrs) 0 0.00 Average Time Period for a Batch Release (hrs) 0 0.00 Minimum Time Period for a Batch Release (hrs) 0 0.00 Total volume of water used to dilute
. 1st 2nd 3rd 4th the liquid effluent during release period (L)
Radwaste I N/A I
N/A I
N/A I
N/A I
Total volume of water available to 1st 2nd 3rd 4th dilute the liquid effluent during report period (L)
Radwaste I 1.11E+11 I 1.26E+11 I 1.31E+11 I 1.30E+11 I Gaseous(Emergency Condenser Vent):
Number of Batch Releases 0
Total Time Period for Batch Releases (hrs) 0.00 Maximum Time Period for a Batch Release (hrs) 0.00 Average Time Period for a Batch Release (hrs) 0.00 Minimum Time Period for a Batch Release (hrs)
- 0.00 Gaseous (Primary Containment Purge):
Number of Batch Releases 2*
Total Time Period for Batch Releases (hrs) 10.58 Maximum Time Period for a Batch Release (hrs) 5.73 Average Time Period for a Batch Release (hrs) 5.29 Minimum Time Period for a Batch Release (hrs) 4.85
ATTACHMENT.1 Page 2 of2 Unit 1 X
Unit 2 Reporting Period: January - December 2017 Abnormal Releases:
A. Liquids:
I Number of Releases I
0 I
!Total Activity Released I
NIA ICi B. Gaseous:
I Number of Releases I
0 I
!Total Activity Released I
N/A ICi Since 2003, the Emergency Condensers have been actuated 7 times. These are identified in the 2003, 2004, 2009, 2010 and 2013 RERRs. The perimeter drain pumps were out of service between 2008 and 2012. Releases prior to that are assumed to have been dicharged to the storm drains while the pumps were functional.
In August 2012, tritium was identified in ground water outside Unit 1. Subsequent investigations determined the source of tritium was Emergency Condenser Vent discharges (during periodic testing, as well as past events). Per the ODCM, and through station procedures, the gaseous and liquid effluent releases to the environment via the Emergency Condenser pathway are analyzed and reported in the monthly effluent releases and reported annually in the Radioactive Effluent Release Report (RERR). As a result of this discovery, the Unit 1 ODCM was revised (Revision 34) to require composite samples of discharges from the Reactor Building Perimeter Drain be collected and analyzed, and total curies reported in the RERR Because this activity has been accounted for in previous RERRs, it is to be reported as a separate item, and not included in the liquid releases (Attachment 5).
On September 6, 2017 from 11 :58 to 12:04, #11 Emergency Condenser String inlet and outlet isolation valves were opened. System parameters were monitored. Condenser temperatures never reached boiling as the temperature reached a maximum of 165°F for shell #111 and 182.°F for shell #112. For the remainder of the month, average shell temperature was between B6° and 100° F. The outside of the reactor building where the vents are located was visually inspected. Below and surrounding the vents showed no indication that ariy liquid discharge took place. For this reason, it is concluded that an emergency condenser liquid release did not take place and is not documented in this report.
ATTACHMENT 2 Page 1 of 1 Unit 1 X
Unit2 Re(!orting Period: Januaot: - December 2017 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES, ELEVATED AND GROUND LEVEL 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter EST. TOTAL ERROR,%
A. l-'1ss1on & Activation Gases 11-l
. s:*:--*:,;..,.';_,J.)'J~i
- 1.
- Total Release Ci I
I I
- ?":f'"'*I
.. I 5.00E+01
- 2.
Average Release Rate
µCi/sec B. Iodines (1l
- 1.
Total Iodine - 131 Ci I
1.03E-05 I
.. I I
.. I 3.00E+01
- 2.
Average Release Rate for Period
µCi/sec 1.31E-06 C. Particulates (1l
- 1.
Particulates with Half-lives>8 days Ci 1.82E-03 2.52E-04 1.93E-04 1.64E-04 3.00E+01
- 2.
Average Release Rate for Period
µCi/sec 2.31E-04 3.21E-05 2.65E-05 2.09E-05
- 3.
Gross Alpha Radioactivity Ci 2.50E+01 D. Tritium (1)
- 1.
Total Release Ci 1.94E+01 1.77E+01 1.79E+01 9.62E+OO 5.00E+01
- 2.
Average Release Rate for Period
µCi/sec 2.48E+OO 2.25E+OO 2.41E+OO 1.22E+OO E. Percent of Tech. S(!ec. Limits Fission and Activation Gases Percent of Quarterly Gamma Air Dose O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Limit (5 mR)
Percent of Quarterly Beta Air Dose Limit O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO (19 mrad)
Percent of Annual Gamma Air Dose Limit 0.00E+OO 0.00E+OO O.OOE+OO O.OOE+OO to Date (10 mR)
Percent of Annual Beta Air Dose Limit to 0.00E+OO O.OOE+OO 0.00E+OO O.OOE+OO Date (20 mrad)
Percent of Whole Body Dose Rate Limit O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO (500 mrem/yr)
Percent of Skin Dose Rate Limit (3000 O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO mrem/yr)
Tritium, Iodines, and Particulates (with half-lives greater than 8 days)
Percent of Quarterly Dose Limit (7.5 7.68E-02 1.31E-02 1.55E-02 9.56E-03 mrem)
Percent of Annual Dose Limit to Date (15 3.84E-02 4.49E-02 5.27E-02 5.74E-02 mrem)
Percent of Organ Dose Limit (1500 1.56E-03 2.62E-04 3.07E-04 1.90E-04 mrem/yr (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.
ATTACHMENT 3 Page 1 of2 Unit 1 X
Unit2 Reeorting Period: Janua!]£ - December 2017 GASEOUS EFFLUENTS-ELEVATED RELEASE Continuous Mode (2)
Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Fission Gases {1l Argon-41 Ci Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-127 Ci Xenon-131m Ci Xenon-133 Ci Xenon-133m Ci Xenon-135 Ci Xenon-135m Ci Xen_on-137 Ci Xenon-138 Ci Iodines {1) lodine-131 Ci 1.03E-05 lodine-133 Ci lodine-135 Ci Particulates {1 l Strontium-89 Ci 7.21E-05 2.0?E-05 7.61E-05 7.65E-05 Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci Cobalt-60 Ci 1.26E-03 8.81E-05 1.17E-04 8.78E-05 Cobalt-58 Ci 9.21E-05 Manganese-54 Ci 6.04E-05 4.62E-06 Barium-140 Ci Ladthanum-140 Ci Niobium-95 Ci Cerium-141 Ci Cerium-144 Ci lron-59 Ci Cesium-136 Ci Chromium-51 Ci 1.91E-04 Zinc-65 Ci lron-55 Ci 1.38E-04 1.39E-04 Molybdenum-99 Ci Neodymium-14 7 Ci Tritium {1l Ci I 1.53E+01 I -1.45E+01 I 1.34E+01 I 7.58E+OO I (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower li_mit of detection of 1.00E-04 µCi/ml for required noble gases, 1.00E-11 µCi/ml for required particulates, 1.00E-12 µCi/ml for required Iodines, and 1.00E-06 µCi/ml for Tritium as required by the ODCM, has been verified.
(2) Contributions from purges are included. There_were no other batch releases during the reporting period.
ATTACHMENT 3 Page 2 of 2 Unit 1 X
Unit2 Reeorting Period: JanuaO! - December 2017 GASEOUS EFFLUENTS-ELEVATED RELEASE Batch Mode (2)
Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Fission Gases {1l Argon-41 Ci Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-127 Ci Xenon~131m Ci Xenon-133 Ci
- ~
Xenon-133m Ci Xenon-135 Ci Xenon-135m Ci Xenon-137 Ci Xenon-138 Ci Iodines (1) lodine-131 Ci I
I I
I
- I lodine-133 Ci lodine-135 Ci Particulates (1 l Strontium-89 Ci Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci Cobalt-60 Ci Cobalt-58 Ci Manganese-54 Ci 0
Barium-140 Ci Lanthanum-140 Ci Niobium-95 Ci Cerium-141 Ci Cerium-144 Ci lron-59 Ci Cesium-136 Ci Chromium-51 Ci Zinc-65 Ci lron-55 Ci Molybdenum-99 Ci Neodymium-14 7 Ci Tritium (1)
Ci I..
I I
I I
(1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of 1.00E-04 µCi/ml for required noble gases, 1.00E-11 µCi/ml for required particulates, 1.00E-12 µCi/ml for required Iodines, and 1.00E-06 µCi/ml for Tritium as required by the ODCM, has been verified.
(2) Contributions from purges, if any, are included. There were no other batch releases during the reporting period.
ATTACHMENT 4 Page 1 of 2 Unit 1 X
Unit2 Re12orting Period: Januarl£ - December 2017 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Ground level releases are determined in accordance with the Off-Site Dose Calculation Manual and Chemistry procedures.
Continuous Mode Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Fission Gases (1)
Argon-41 Ci Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-127 Ci Xenon-131m Ci Xenon-133 Ci Xenon-133m Ci Xenon-135 Ci*
Xenon-135m Ci Xenon-137 Ci Xenon-138 Ci Iodines (1\\
lodine-131 Ci I
I I
I I
lodine-133 Ci lodine-135 Ci Particulates {1 l Strontium-89 Ci Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci Cobalt-60 Ci 4.41E-08 Cobalt-58 Ci 2.85E-08 Manganese-54 Ci 7.91E-09 Barium-140 Ci Lanthanum-140 Ci Niobium-95 Ci Cerium-141 Ci Cerium-144 Ci lron-59 Ci Cesium-136 Ci Chromium-51 Ci Zinc-65 Ci lron-55 Ci Molybdenum-99 Ci Neodymium-147 Ci Tritium {11 Ci I 4.16E+OO I 3.19E+OO I 4.45E+OO I 2.03E+OO I (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.
ATTACHMENT 4 Page 2 of2 Unit 1 X
Unit2 Rei;?orting Period: Janua~ - December 2017 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES Ground level releases are determined in accordance with the Off-Site Dose Calculation Manual and Chemistry procedures.
Batch Mode Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Fission Gases (1 l Argon-41 Ci Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-127 Ci Xenon-131m Ci Xenon-133 Ci Xenon-133m Ci Xenon-135 Ci Xenon-135m Ci Xenon-137 Ci Xenon-138 Ci Iodines (1}
lodine-131 Ci I
I I
I I
lodine-133 Ci lodine-135 Ci Particulates (1 l Strontium-89 Ci Strontium-9Q Ci Cesium-134 Ci Cesium-137 Ci Cobalt-60 Ci Cobalt-58 Ci Manganese-54 Ci Barium-140 Ci Lanthanum-140 Ci Niobium-95 Ci Cerium-141 Ci Cerium-144 Ci lron-59 Ci Cesium-136 Ci Chromium-51 Ci Zinc-65 Ci lron-55 Ci Molybdenum-99 Ci Neodymium-147 Ci Tritium (1}
Ci I
I I
I I
(1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.
ATTACHMENT 5 Page 1 of 2 Unit 1 X
Unit2 Reeorting Period: Januaot: - December 2017 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES (1) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Est. Total Error, %
A. t-1ss1on & Act1vat1on Products
- 1. Total Release (not including Tritium, Ci No Releases No Releases No Releases No Releases 5.00E+01 gases, alpha)
- 2. Average diluted concentration during
µCi/ml No Releases No Releases No Releases No Releases reporting period B. Tritium 1.Total release Ci No Releases No Releases No Releases No Releases 5.00E+01
- 2. Average diluted concentration during
µCi/ml No Releases No Releases No Releases No Releases the reporting period C. Dissolved and Entrained Gases
- 1. Total release Ci No Releases No Releases No Releases No Releases 5.00E+01
- 2. Average diluted concentration during
µCi/ml No Releases. No Releases No Releases No Releases the reporting period D. Gross Al12ha Radioactivit'.l
- 1. Total release Ci No Releases No Releases No Releases No Releases 5.00E+01
-E. Volumes
- 1. Prior to Dilution Liters No Releases No Releases 1.89E+03 No Releases 5.00E+01
- 2. Volume of dilution water used during Liters No Releases No Releases O.OOE+OO No Releases 5.00E+01 release period
- 3. Volume of dilution water available Liters 1.11E+11 1.26E+11 1.31E+11 1.30E+11 5.00E+01 during reporting period - Cooling Water F. Percent of Tech. S12ec. Limits Percent of Quarterly Whole Body Dose No Releases No Releases No Releases No Releases Limit (1.5 mrem)
Percent of Annual Whole Body Dose No Releases No Releases No Releases No Releases Limit to Date (3 mrem)
Percent of Quarterly Organ Dose Limit No Releases No Releases No Releases No Releases (5 mrem)
Percent of Annual Organ Dose Limit to No Releases No Releases No Releases No Releases Date (10 mrem)
Percent of 1 OCFR20 Concentration No Releases No Releases No Releases No Releases Limit Percent of Dissolved or Entrained Noble Gas Limit (2.00E-04 µCi/ml)
No Releases No Releases No Releases No Releases (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.
ATTACHMENT 5 Page 2 of2 Unit 1 X
Unit 2 Reeorting Period: Januarll: - December 2017 LIQUID EFFLUENTS RELEASED Batch Mode (1 ),(2)
Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Nuclides Released Strontium-89 Ci No Releases No Releases No Releases No Releases Strontium-90 Ci No Releases No Releases No Releases No Releases Cesium-134' Ci No Releases No Releases No Releases No Releases Cesium-137 Ci No Releases No Releases No Releases No Releases lodine-131 Ci No Releases No Releases No Releases No Releases Cobalt-58 Ci No Releases No Releases No Releases No Releases Cobalt-60 Ci No Releases No Releases No Releases No Releases lron-59 Ci No Releases No Releases No Releases No Releases Zinc-65 Ci No Releases No Releases No Releases No Releases Manganese-54 Ci No Releases No Releases No Releases No Releases Chromium-51 Ci No Releases No Releases No Releases No Releases Zirconium-95 Ci No Releases No Releases No Releases No Releases Niobium-95 Ci No Releases No Releases No Releases No Releases Molybdenum-99 Ci No Releases No Releases No Releases No Releases Barium-140 Ci No Releases No Releases No Releases No Releases Lanthanum-140 Ci No Releases No Releases No Releases No Releases Cerium-141 Ci No Releases No Releases No Releases No Releases lodine-133 Ci No Releases No Releas'es No Releases No Releases lron-55 Ci No Releases No Releases No Releases No Releases Cerium-144 Ci No Releases No Releases No Releases No Releases Cesium-136 Ci No Releases No Releases No Releases No Releases Copper-64 Ci No Releases No Releases No Releases No Releases Manganese-56 Ci No Releases No Releases No Releases No Releases Nickel-65 Ci No Releases No Releases No Releases No Releases Sodium-24 Ci No Releases No Releases No Releases No Releases Dissolved or Entrained Gases Ci No Releases No Releases No Releases No Releases Tritium Ci No Releases No Releases No Releases No Releases (1) No continuous mode release occurred during the report period as indicated by effluent sampling. There were no Radwaste Batch Releases.
(2) Concentrations less than the lower limit of detection of the counting system used have been verified for sampled effluents. A lower limit of detection of 5.00E-07 µCi/ml for required gamma emitting nuclides, 1.00E-05 µCi/ml for required dissolved and entrained noble gases and tritium, 5.00E-08 µCi/ml for Sr-89/90, 1.00E-06 µCi/ml for 1-131 and Fe-55, and 1.00E-07 µCi/ml for gross alpha radioactivity, as identified in the ODCM, has been verified. Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.
ATTACHMENT 6 Page 1 of4 Unit 1 X
Unit2 Re12orting Period: Janua!Jl - December 2017 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A1. TYPE Volume Activi~ (1l (m3)
(Ci)
~
~
A B
C A
B C
a.1 Spent Resin (Dewatered) 2.02E+01 O.OOE+OO O.OOE+OO 1.66E+02 O.OOE+OO O.OOE+OO a.2 Filter Sludge O.OOE+OO 9.49E+OO O.OOE+OO O.OOE+OO 4.67E+02 O.OOE+OO a.3 Concentrated Waste O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Totals 2.02E+01 9.49E+OO O.OOE+OO 1.66E+02 4:67E+02 0.00E+OO b.1 Dry Compressible Waste*
2.89E+02 O.OOE+OO O.OOE+OO 2.22E-01 O.OOE+OO O.OOE+OO b.2 Dry Non-Compressible Waste (Contaminated O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Equipment)
Totals 2.89E+02 O.OOE+OO O.OOE+OO 2.22E-01 O.OOE+OO O.OOE+OO C.
Irradiated Components, Control Rods, etc.
O.OOE+OO O.OOE+OO O.OOE+oo*
O.OOE+OO O.OOE+OO O.OOE+OO
- d. Other (to vendor for processing) d.1 Sewage Sludge 3.53E+.01 O.OOE+OO O.OOE+OO 4.99E-03 O.OOE+OO O.OOE+OO (1) The estimated total error is 5.0E+01 %.
ATTACHMENT 6 Page 2 of4 Unit 1 X
Unit2 Reporting Period: January - December 2017 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A1. TYPE Container Package Solidification Agent a.1 Spent Resin Poly Liner General Design None a.2 Filter Sludge Poly Liner Type B None b.1 Dry Compressible Waste Seavan General Design None b.2 Dry Non-Compressible Waste (contaminated N/A N/A N/A equipment)
- c. Irradiated Components, N/A N/A NIA Control Rods
- d. Other (To vendor for processing) d.1 Sewage Sludge Bags General Design None
ATTACHMENT 6 Page 3 of4 Unit 1 X
Unit2 Re12orting Period: Janua!Jl - December 2017 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE)
- a. Spent Resins, Filter Sludges, Concentra.ted Waste Nuclide Percent Curies Fe-55 16.03%
1.02E+02 Co-60 73.69%
4.70E+02
- Ni-63 1.08%
6.91E+OO Cs-137 6.57%
4.19E+01
- b. Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment)
Nuclide Percent Curies Mn-54 1.90%
4.22E-03 Fe-55 51.08%
1.14E-01 Co-60 41.59%
9.25E-02 Ni-63 1.40%
3.12E-03 Cs-137 1.44%
3.19E-03 I
- c. Irradiated Components, Control Rods: There were no shipments.
Nuclide Percent NA NA
- d. Other: (To vendor for processing)
9.88E-05 Co-60 94.70%
4.62E-03 Cs-137
.3.27%
1.59E-04
ATTACHMENT 6 Page 4 of4 Unit 1 X
Unit2 Re12orting Period: Janua[ll - December 2017 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A3. SOLID WASTE DISPOSITION Number of Shi12ments Mode of Trans12ortation Destination 8
Truck, highway Bear Creek 1
Truck, highway Gallaher Road 5
Truck, highway Clive 3
Truck, highway wcs B. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shi12ments Mode of Trans12ortation Destination D. SEWAGE WASTES SHIPPED TO A TREATMENT FACILITY FOR PROCESSING AND BURIAL There were no shipments of sewage sludge with detectible quantities of plant-related nuclides from NMP to the treatment facility during the reporting period.
ATTACHMENT 7 Page 1 of 1 Unit 1 X
Unit2 Re[!orting Period: Janua(Y - December 2017
SUMMARY
OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL (ODCM)
The following changes were made to the Unit 1 Off-Site Dose Calculation Manual (ODCM) during the reporting period.
REVISION 36 Page#
New/Amended Description of Change Reason For Change Section#
13.1-10 NOTES FOR TABLED Removed phrasing in (g) action The basis for the change comes from 3.6.14-2 NER-NC-17-001-Yellow "Review of Offsite Dose Calculation Manual (ODCM) for Shutdown or Power Reduction Action Statements" 13.1-11 NOTES FOR TABLE D Added rewritten action (g)
The basis for the change comes from 3.6.14-2 "Place the nonfunctional channel in the tripped NER-NC-17-001-Yellow condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OR (2) (a) Take grab samples within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter AND (b) Analyze samples for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of sampling completion.
AND (3) Restore nonfunctional channel(s) to FUNCTIONAL status within 30 days. U)"
13.1-11 NOTES FOR TABLE D Added action (j)
The basis for the change comes from 3.6.14-2 "If nonfunctional channel(s) not restored within NER-NC-17-001-Yellow specified time, explain why the inoperability was not corrected in a timely manner in the next Radioactive Effluent Release Report."
IB3.1-1 BASES FOR DLCO BASES changed to align with notes from Table D The basis for the change comes from 3.6.14 and DSR 4.6.14 3.16.14-2 NER~NC-17-001-Yellow RADIOACTIVE EFFLUENT INSTRUMENTATION 183.1-1 BASES FOR DLCO Removed the line to align with BASES change:
The basis for the change comes from 3.6.14 and DSR 4.6.14 "When serving as backup NER-NC-17-001-Yellow RADIOACTIVE to the Offgas Monitors (Table D 3.6.14-2 Note g),
EFFLUENT this function may be satisfied by a single Low Range INSTRUMENTATION or High Range monitor because all Stack monitors function in the region of interest due to their design overlap."
11-19 2.2.1.1 Noble Gases Added missing 0;5 in the whole body dose rates
~or whole body dose rates (mrem/sec) equation.
was missing the release rate of isotope i from the stack factor (Qis)in the equation.
II -19 2.2.1.1 Noble Gases Elaborated the definition of the structural shielding Definition was not comprehensive.
factor adding:
"(dimensionless). A shielding factor of 0.7 is discussed in Table E-15 of Regulatory Guide 1.109 Revision 1"
ATTACHMENT 8 Page 1 of 1 Unit 1 X
Unit2 Reporting Period: January - December 2017
SUMMARY
OF CHANGES TO THE PROCESS CONTROL PROGRAM (PCP)
RW-AA-100, PROCESS CONTROL PROGRAM FOR RADIOACTIVE WASTES, was updated to remove Fort Calhoun from the procedure and include James A. Fitzpatrick Nuclear.
ATTACHMENT 9 Page 1 of 1 Unit 1 X
Unit2 Reporting Period: January - December 2017
SUMMARY
OF NON-FUNCTIONAL MONITORS Monitor Dates Monitor was Cause and Corrective Actions Non-Functional Liquid Radwaste January 1, 2017 to These monitors were intentionally allolJ'.'.ed to exceed their quarterly Discharge Monitors Qecember 31, 2017 functional tests and annual calibration frequency, as no discharges 11 and 12 I
are planned or expected. This condition is allowed as long as blank flanges are installed in the discharge line, precluding any unmonitored discharge. No liquid waste discharges were performed during 2017. This non-functionality is tracked in Equipment Status Log (ESL) 2006-0192.
I I
ATTACHMENT 10 Page 1 of 4 Unit 1 _x_
Unit 2 Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY Introduction An assessment of the radiation dose potentially received by a Member of the Public due to their activities inside the site boundary from Nine Mile Point Unit 1 (NMPl) liquid and gaseous effluents has been conducted for the perio~ January through December 2017.
This assessment considers the maximum exposed individual and the various exposure pathways resulting from liquid and gaseous effluents to identify the maximum dose received by a Member of the Public during their activities within the site boundary.
Prior to September 11, 2001, the public had access to the Energy Information Center for purposes of observing the educational displays or for picnicking and associated activities. Fishing also occurred near the shoreline adjacent to the Nine Mile Point (NMP) site. Fishing near the shor~line adjacent to the NMP site. was the onsite activity that resulted in the potential maximum dose received by a Member of the Public. Following September *11, 2001 public access to the Energy Information Center has been restricted and fishing by Members of the Public at locations on site is also prohibited. Although fishing was not conducted during 2017, the annual dose to a hypothetical fisherman was still evaluated to provide contin\\}ity of data for the location.
Dose Pathways Dose pathways considered for this evaluation included direct radiation, inhalation and external ground (shoreline sediment or soil doses). Other pathways, such as ingestion pathways, are not considered because they are either not a~plicable, insignificant, or are considered as part of the evaluatipn of the total dose to a member of the public
- locat~d off-site. In addition, only releases from the NMPl stack,d emergency condenser vent were evaluated for the inhalation pathway. Dose due to aquatic pathways such as liquid effluents is not applicable since swimming is prohibited at the NMP site.
Dose to a hypothetical fisherman is received through the following pathways while standing on the shoreline fishing:
External ground pathway; this dose is received from plant related radionuclides detected in the shoreline sediment.
Inhalation pathway; this dose is received through inh~lation of gaseous effluents released from the NMPl Stack and Emergency Condenser Vent.
Direct radiation pathway; dose resulting from the operation ofNMPl, Nine Mile Point Unit 2 (NMP2) and the James A. Fitzpatrick Nuclear Power Plant (JAFNPP) Facilities.
Methodologies for Determining Dose for Applicable Pathways External Ground (Shoreline Sediment) Pathway Dose from the external ground (shoreline sediment) is based on the methodology in the NMPl Offsite Dose Calculation Manual (ODCM) as adapted from Regulatory Guide 1.109. For this evaluation it is assumed that the hypothetical maximum exposed individual fished from the shoreline at all times.
ATTACHMENT 10 Page 2 of 4 Unit 1 ~X-Unit 2 Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY The total dose received by the whole body and skin of the maximum exposed individual during 2017 was calculated using the following input parameters:
Usage Factor= 312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br /> (fishing 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per week, 39 weeks per year)
Density in grams per square 1meter = 40,000 Shore width factor= 0.3 1
Whole body and skin dose factor for each radionuclide= Regulatory Guide 1.109, Table E-6.
Fractional portion of the year= 1 (used average radionuclide concentration over total time period)
Average Cs-137 concentration= l.30E-01 pCi/g The total whole body and skin doses received by a hypothetical maximum exposed fisherman from the external ground pathway is presented in Table 1, Exposure Pathway Annual Dose.
Inhalation Pathway The inhalation dose pathway is evaluated by utilizing the inhalation equation in the NMPl ODCM, as adapted from Regulatory Guide 1.109. The total whole body dose and organ dose received by the hypothetical maximum exposed fisherman during 2017 calculated using the following input parameters for gaseous effluents released from both the NMPl Stack and Emergency Condenser Vent for the time period exposure is received:
NMP 1 Stack:
Variable Fisherman 1 X/Q (s/m3) 8.90E-06 Inhalation dose factor Table E-7, Regulatory Guide 1.109 Annual air intake (m3/year) (adult) 8000 Fractional portion of the year 0.0356 H-3 (pCi/sec) l.55E+06 Mn-54 (pCi.sec) 2.0lE-01 C-14 (pCi/sec)2 2.63E+05 Fe-55 (pCi/sec) 6.04E+OO Co-60 (pCi/sec) l.27E+Ol Sr-89 (pCi/sec) 6.64E+OO
ATTACHMENT 10 Page 3 of 4 Unit 1 _X_
Unit 2 Reporting Period: January-December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY NMPJ Emergency Condenser Vent:
Variable Fisherman 1
XIQ (s/m3) 6.63E-06 Inhalation dose factor Table E-7, Regulatory Guide 1.109 Annual air intake (ni3 /year) (adult) 8000 Fractional portion of the year 0.0356 H-3 (pCi/sec) 4.05E+05 Mn-54 (pCi/sec) 3.33E-04 Co-58 (pCi/sec) l.20E-03 Co-60 (pCi/sec) l.85E-03 The maximum exposed fisherman is assumed to be present on site during the period of April through December at a rate of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per week for 39 weeks per year equivalent to 312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br /> for the year (fractional portion of_the year= 0.0356). Therefore, the Average Stack and Emergency Condenser Vent flow rates and radionuclide concentrations used to determine the dose are represented by second, third and fourth quarter gaseous effluent flow and concentration values.
2 C-14 release rate detennined from NUREG-0016, "Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents for Boiling Water Reactors (BWR-GALE Code)," and EPRI Technical Report 1021106, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents."
The total whole body dose and maximum organ dose received by the hypothetical maximum exposed fisherman is presented in Table 1, Exposure Pathway Annual Dose.
Direct Radiation Pathwav The direct radiation pathway is evaluated in accordance with the methodology found in the NMPl ODCM. This pathway considers four components: direct radiation from the generating facilities, direct radiation from any possible overhead plume, direct radiation from ground deposition and direct radiation from plume submersion.
The direct radiation pathway is evaluated by the use of high sensitivity environmental Thermoluminescent Dosimeters (TLDs). Since fishing activities occur benveen April I and December 31, TLD data for the second, third, and fourth quarters of 2017 from TLDs placed in the general area where fishing once occurred were used to determine an average dose to the hypothetical maximum exposed fisherman from direct radiation. The following is a summary of the average dose rate and assumed time spent on site used to determine the total dose received:
Variable Fisherman Average Dose Rate (mRem/hr) l.04E-03 Exposure time (hours) 312 Total doses received by the hypothetical maximum exposed fishennan from direct radiation is presented in Table 1, Exposure Pathway Annual Dose.
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L ATTACHMENT 10 Page 4 of4 Unit 1 _x_
Unit 2 Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY Dose Received By Hypothetical Maximum Exposed Member of the Public Inside the Site Boundary The following is a summary of the dose received by a hypothetical maximum exposed fisherman from liquid and gaseous effluents released from NMPl during 2017:
TABLE 1 Exposure Pathway Annual Dose Exposure Pathway Dose Type Fisherman (mrem)
External Ground Whole Body 2.04 E-03 Skin of Whole Body 2.38 E-03 Whole Body 1.02 E-03 Inhalation Maximum Organ Bone: 1.51 E-03 ThyToid 1.02 E-03 Direct Radiation Whole Body 0.32 Based on these values the total annual dose received by a hypothetical maximum exposed Member of the Public inside the site boundary is as follows:
TABLE2 Annual Dose Summary Total Annual Dose for 2017 Fisherman (mrem)
Total Whole Body 3.26 E-01 Skin of Whole Body
_ 2.38 E-03 Maximum Organ Bone: 1.51 E-03 Thyroid 1.02 E -03
__J
i
(
ATTACHMENT 11 Page 1 of 5 Unit 1 _x_
Unit 2 Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Introduction An assessment of radiation doses potentially received by the likely most exposed Member of the Public located beyond the site boundary was conducted for the period January through December 2017 for comparison against the 40 CPR 190 annual dose limits.
I The intent of 40 CPR 190 requires that the effl~ents of Nine Mile Point Unit 1 (NMPl), as well as other nelrby uranium fuel cycle facilities, be considered. In this case, the effluents of NMPl, Nine Mile Point Unit 2 (NMP2) and the James A. FitzPatrick Nuclear Power Plant (JAFNPP) facilities must be considered.
40 CPR 190 requires the annual radiation dose received by Members of the Public in the general environment, as a result of plant operations, be limited to:
< 25 mRem whole body
< 25 mRem any organ ( except thyroid)
< 75 mRem thyroid This evaluation compares doses resulting from liquid and gaseous effluents and direct radiation originating from the site as a result of the operation of the NMPl, NMP2 and JAFNPP.nuclear facilities.
Dose Pathways Dose pathways considered for this evaluation included doses resulting from liquid effluents, gaseous effluents and direct radiation from all nuclear operating facilities located on the Nine Mile Point site.
Dose to the likely most exposed Member of the l?Jublic, outside the site boundary, is received through the followJ*ng pathways:
Fish consumption pathway; this dose is rece ved from plant radionuclides that have concentrated in fish tha is consumed by a Member of the Public.
Vegetation consumption pathway; this dose is received from plant radionuclides that have concentrated in vegetation that is consumed by a Member of the Public.
Shoreline Sediment; this dose is received as a result of an individual's exposure to plant radionuclides in the shoreline sediment, which is used as a recreational area.
Deposition, Inhalation and Ingestion pathways resulting from gaseous effluents; this dose is received through exposure to gaseous effluents released from NMPl, NMP2 and JAFNPP operating facilities.
Direct Radiation pathway; radiation dose resulting from the operation ofNMPl, NMP2 and JAFNPP facilities (including the Independent Spent Fuel Storage Installations (ISFSI)).
Methodologies for Determining Dose for Applicable Pathways Fish Consumption Dose received as a result of fish consumption is based on the methodology specified in the NMP 1 Off-Site Dose Calculation Manual (ODCM) as adapted from Regulatory Guide 1.109. The dose for 2017 is calculated from actual analysis results of environmental fish samples taken near the site discharge points. For this evaluation it is assumed that the most likely exposed Member of the Public consumes fish taken near the site discharge points.
No radionuclides were detected in fish samples collected and analyzed during 2017; therefore, no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2017.
ATTACHMENT 11 Page 2 of 5 Unit 1 _x_
Unit 2 Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Vegetation Consumption Dose received as a result of vegetation consumption is based on the methodology specified in the NMPl ODCM as adapted from Regulatory Guide 1.109. The dose for 2017 is calculated from actual analysis results of environmental vegetation samples taken near the most exposed Member of the Public..
No radionuclides were detected in vegetation samples collected and analyzed during 2017; therefore, no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2017.
For estimating C-14, dose received as a result of vegetation consumption is based on the methodology specified in the NMPl ODCM as adapted from Regulatory Guide 1.109. The estimated concentration of C-14 in vegetation is based on the estimated concentration of C-14 in plant gaseous effluents.
Shoreline Sediment.
Dose received from shoreline sediment is based on the methodology in the NMPl ODCM as adapted from Regulatory Guide 1.109. For this evaluation it is assumed that the most likely exposed Member of the Public spends 67 hour7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br />s/year along the shoreline for recreational purposes.
No radionuclides were detected in shoreline sediment samples collected and analyzed during 2017; therefore no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2017.
Dose Pathwavs Resulting From Gaseous Effluents Dose received by the likely most exposed Member of the Public due to gaseous effluents is calculated in accordance with the methodology provided in the NMPl ODCM, NMP2 ODCM, and the JAFNPP ODCM. These calculations consider deposition, inhalation and ingestion pathways. Actual meteorological data was used to calculate doses to the likely most exposed Member of the Public. The total sum of doses resulting from gaseous effluents from NMP 1, NMP2 and JAFNPP during 2017 provides a total dose to the whole body and maximum organ dose for this pathway.
Carbon-14 Dose Pathways Resulting from Gaseous Effluents The Cai'bon-14 (C-14) effluent source terms are used to estimate radiological doses from C-14 in site gaseous waste effluents. These estimates were generated in order to meet the NRC requirement to incorporate C-14 in nuclear power plant 2017 Annual Radiological Effluent Release Reports (ARERRs). The C-14 production and effluent source term estimates were based on EPRI methodology provided in EPRI Report 1021106, Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents, December 2010. The following methodology was used in estimating C-14 gaseous release activity and dose components for the 2017 ARERR.
EPRI methodology for estimating C-14 production rates in Boiling Water Reactors (BWRs):
For BWRs, EPRI Report 1021106 summarized the distribution of C-14 in release pathways as follows: gaseous 95% to 99%, liquid <0.5% and solid 1 % to 5%. The report also states that -9 5% of C-14 in BWR gaseous waste.
effluents exists in the carbon dioxide form, which contributes to population dose via photosynthesis uptake in the food consumption cycle.
_ _J
ATTACHMENT 11 Page 3 of 5 Unit 1 _x_
Unit 2 Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY For NMPl and NMP2, C-14 gaseous dose calculations in the site ARERR are made using the following assumptions for each unit: (1) continuous release of the estimated C-14 generated during power operation based on the number of Effective Full Power Days (EFPDs) for the period, (2) maximum G-14 activity from literature values cited in EPRI Report 1021106, and (3) typical fraction as carbon dioxide for gaseous releases from literature values also cited in EPRI Report 1021106.
Equation 1 estimates the maximum annual production of C-14, PRMAX, for each BWR unit.
PRMAX
=
5.1
- MWT / 1000
[Eq 1]
Where:
5.1
=
BWR Normalized Production (Ci/GWt-yr)
MWT
=
Mega Watts Thermal (MWt) 1000
=
Conversion Factor (MWt to GWt)
Equation 2 estimates the C-14 activity released, A c.14, into the gaseous pathway during the time period for each BWR unit.
Where:
A C-1./
PRMAX 0.99 EFPD 365 PR MAX
- 0.9}
- EFPD I 365, Ci (for time period)
[Eq2}
maximum annual production rate ofC-14 fraction ofC-14 in BWR gaseous pathway releases (maximum literature value in EPRI Report 1021106; also Table 1) number of effective full power days for the unit during the time period; e.g., quarterly or yearly (Table 1) number of days in a typical year
ATTACHMENT 11 Page 4 of 5 Unit 1 ~X-Unit 2 Reporting Period: January-December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Equation 3 estimates the C-14 activity released in carbon dioxide form, A c-l4, co2, into the gaseous pathway during the time period for each BWR unit.
Where:
A C-14, CO2 PRMAX 0.99 0.95 EFPD 365
=
=
=
=
=
=
(R MAX o 0.99
- 0.95
- EFPD I 365, Ci (for time period) I maximum annual production rate of C-14 fraction of C-14 in BWR gaseous pathway releases (maximum literature value in EPRI Report 1021106; also Table 1) fraction of C-14 as carbon dioxide in BWR gaseous pathway
[Eq3]
releases (typical literature value in EPRI Report 1021106; also Table 1) number of effective full power days for the unit during the time period, e.g. quarterly or yearly (Table 1) conversion factor, 365 days in atypical average year For each BWR unit, the 2017 estimated C-14 activity releases (total and carbon dioxide chemical form) are summarized in Table 1.
Table 1 2017 BWR Estimated C-14 Gaseous Releases Gaseous COiForm Max.Annual BWR Release Release EFPD Operation Fraction(a)
Fraction<hJ NMPl 0.99 0.95 331.2EFPD (90.7%)
NMP2 0.99 0.95 359.85 EFPD (98.9%)
JAFNPP 0.99 0.95 309.1 EFPD (84.7%)
(a) Maximum literature values from EPRI Report 1021106.
(b) Typical value from EPRI Report 1021106.
Prod. Rate (Eq 1) 9.44 Ci/yr 20.33 Ci/yr(c) 12.93 Ci/yr (c) NMP2 Reactor Power Rating increased to 3988 Megawatts thermal.
2017 Total Release (Eq2) 8.48 Ci 19.85 Ci 9.09 Ci 2017 CO2 Release (Eq3) 8.05 Ci 18.86 Ci 8.63 Ci As long as the core designs and power ratings are not significantly changed, the maximum annual production rates and annual total and carbon dioxide activity releases in Table 1 should be acceptable for use in estimating C-14 gaseous release activity and dose components for the ARERR.
ATTACHMENT 11 Page 5 of 5 Unit 1 _X_
Unit 2 Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Direct Radiation Pathwav Dose as a result of direct gamma radiation from the site, encompasses doses from direct "shine" from the generating facilities, direct radiation from any overhead gaseous plumes, plume submersion, and ground deposition. This total dose is measured by environmental TLDs. The critical location is based on the closest year-round residence from the generating facilities as well as the closest residence in the critical downwind sector in order to evaluate both direct radiation from the generating facilities and gaseous plumes as determined by the local meteorology. During 2017, the closest residence and the critical downwind residence are at the same location.
Table 2 Dose Potentially Received by the Likely Most Exposed Member of the Public Outside the Site Boundary During 2017 Exposure Pathway Dose Type Dose (mrem)
Total Whole Body No Dose Fish and Vegetation Consumption Total Maximum Organ No Dose Total Whole Body No Dose Shoreline Sediment Total Skin of Whole Body No Dose Total Whole Body 4.42 E-03 Gaseous Effluents Thyroid 1.02 E-02 (excluding C-14)
Maximum Organ Thyroid: 1.02 E-02 Gaseous Eftluent Total Whole Body 3.52 E-01 (C-14)
Maximum Organ Bone: 1.76 E+oO Direct Radiation Total Whole Body 0.91 Based on these values the maximum total annual dose potentially received by the likely most exposed Member of the Public during 2017 is as follows:
Total Whole Body:
Total Thyroid:
Maximum Organ:
40 CFR 190 Evaluation 1.27 E+OO mrem
- 1. 02 E-02 mrem Bone: 1.76 E+OO mrem The ma.-x:imum total doses presented in this attachment are the result of operations at the NMPl, NMP2 and the JAFNPP facilities. The maximum organ dose (Bone: 1.76 mrem), maximum thyroid dose (0.010 mrem) and the maximum whole body dose (1.27 mrem) are below the 40 CFR 190 criteria of 25 mrem per calendar year to the maximum exposed organ or the whole body, and below 75 mrem per calendar year to the thyroid.
ATTACHMENT 12 Page 1 of 1 Unit 1 _x_
Unit 2 --
Re12orting Period: Janua!Jl - December 2017 Well Identification
- Samples Minimum Maximum Number Collected
- Positive Samples Concentration (pCi/1)
Concentration (pCi/1)
GMX-MW1*
4 0
<188
<194 MW-1 4
0
<188
<200 MW-5 4
0
<183
<193 MW-6 4
0
<186
<191 MW-7 4
0
<186
<194 MW-8 4
0
<187
<193 MW-91 4
0
<187
<192 MW-101 4
1
<186 240 MW-11 4
0
<186
<193 MW-12 4
0
<190
<193 MW-13 4
0
<184
<192 MW-14*
4 1
<183 234 MW-15 4
1
<186 252 MW-16 4
0
<184
<192 MW-17 4
1
<183 222 MW-18 4
1
<190 270 MW-19 4
0
<186
<190 MW-20 4
0
<183
<192 MW-21 4
0
<183
<190 NMP2 MAT 2*3 4
1
<181 279 PZ-1 4
0
<190
<193 PZ-2 4
0
<191
<196 PZ-3 4
0
<187
<194 PZ-4 4
1
<189 214 PZ-5 4
0
<190
<191 PZ-6 4
0
<188
<192 PZ-7 4
4 291 435 PZ-8 4
0
<190
<198 PZ-9*
4 0
<189
<194 Notes:
- - Control Location 1 - Sentinel well location 2 - NMP2 Groundwater Depression Cone 3
- Samples collected from storm drain system which includes precipitation Nine Mile Point Nuclear Station, Unit 2 Radioactive Effluent Release Report, January-D,ecember 2017
NINE MILE POINT NUCLEAR STATION - UNIT 2 RADIOACTIVE EFFLUENT RELEASE REPORT January-December 2017
Page 1 of2 NINE MILE POINT NUCLEAR STATION - UNIT 2 RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2017 SUPPLEMENTAL INFORMATION Facility: Nine Mile Point Unit 2 Licensee: Nine Mile Point Nuclear Station, LLC
- 1.. TECHNICAL SPECIFICATION/ODCM LIMITS A)
FISSION AND ACTIVATION GASES
- 1.
The dose rate limit of noble gases released in gaseous effluents from the site to areas at or beyond the site boundary shall be less than or equal to 500 mrem/year to the whole body and less than or equal to 3000 mrem/year to the skin.
- 2.
The air dose from noble gases released in gaseous effluents from Nine Mile Point Unit 2 to areas at or beyond the site boundary shall be limited during any calendar quarter to less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and during any calendar year tA 1ess than or equal to 1 o mrad for gamma radiation and 1ess than or eqra1 to 20 mrad for beta radiatif.
B&C) TRITIUM, IODINES AND PARTICULATES, HALF LIVES > 8 DAYS
- 1.
The dose rate limit oflodine-131, Iodine-133, Tritium and all radionuclides in particulate form with half-lives greater than eight days, released in gaseous effluents from the site to areas at or beyond the site boundary shall be less than or equal to 1500 mrem/year to any organ.
- 2.
The dose to a member of the public from Iodine-131, Iodine-133, Tritium and all radionuclides in particulate form with half-lives greater than eight days in gaseous effluents released from Nine Mile Point Unit 2 to areas at or beyond the site boundary shall be limited during any calendar quarter to less than or equal to 7.5 mrem to any organ, and during any calendar year to less than or equal to 15 mrem to any organ.
D)
LIQUID EFFLUENTS
- 1.
Improved Technical Specifications (ITS) limit the concentration of radioactive material released in the liquid effluents to unrestricted areas to ten times the concentrations specified in 10CFR20.1001-20.2402, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases.
For dissolved or entraineq noble gases, the concentration shall be limited to 2E-04 microcuries/ml total activity.
- 2.. The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released from Nine Mile Point Unit 2 to unrestricted areas shall be limited during any calendar qu~rter to less than or equal to 1.5 mrem to the whole body and to less than or equal to 5 mrem to any organ, and -during any calendar year to less than or equal to 3 mrem to the whole body and to less than or equal to 10 mrem to any organ..
Page 2 of2
- 2.
MEASUREMENTS AND APPROXIMATIONS OF TOT AL RADIOACTIVITY Described below are the methods used to measure or approximate the total radioactivity and radionuclide composition in effluents.
A)
FISSION AND ACTIVATION GASES Noble gas effluent activity is determined by an on-line scintillation detector (calibrated against gamma isotopic analysis of a 4.0L Marinelli grab sample) of an isokinetic sample stream.
I B)
IODINES Iodine effluent activity is determined by gamma spectroscopic analysis (at least weekly) of charcoal cartridges sampled from an isokinetic sample stream.
C)
PARTICULATES Activity released from the main stack and the combined Radwaste/Reactor Building vent is determined by gamma spectroscopic analysis (at least weekly) of particulate filters sampled from an isokinetic sample stream and composite analysis of the filters for non-gamma emitters.
D)
TRITIUM Tritium effluent activity is measured by liquid scintillation or gas proportional counting of monthly samples taken with an air sparging/water trap apparatus.
E)
LIQUID EFFLUENTS F)
G)
Isotopic contents of liquid effluents are detennined by isotopic analysis of a representative sample of each batch and composite analysis of non-gamma emitters.
souq EFFLUENTS
)
Isotop+ contents of waste shipments are determined by gamma spectroscopy analyses of a representative sample of each batch. Scaling factors established from primary composite sample analyses conducted off-site are applied, where appropriate, to find estimated concentration of non-gamma emitters. For low activity trash shipments, curie content is estimated by dose rate measurement and application of appropriate scaling factors.
C-14 The production of C-14 and the effluent dose consequences are estimates based on EPRI methodology provided in EPRI Report 1021106, Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents, December 2010 and NUREG-0016, Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents for Boiling Water Reactors (BWR-GALE Code).
- 3.
METEOROLOGICAL DATA An annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distribution of wind speed, wind direction, and atmospheric stability. In lieu of submission with the Radiological Effluent Release Report, the licensee is exercising the option of retaining this summary ofrequired meteorological data on site in a file that shall be provided to the NRC upon request.
Supplemental Information ATTACHMENT 1
SUMMARY
DATA Unit 1 Unit2 X
Re[!orting Period:
Liquid Effluents:
ODCM Required Maximum Effluent Concentration (MEC) = 10 x 10CFR20.1001 - 20.2402, Appendix B, Table 2, Column 2 Average MEC - µCi/ml (Qtr.1) =
I NO RELEASES Average MEC - µCi/ml (Qtr. m =
Average MEC - µCi/ml (Qtr. £) =
I NO RELEASES Average MEC - µCi/ml (Qtr.1) =
Average Energy (Fission and Activation gases - MEV):
Qrtr.1:
Ey
=
N/A E13
=
N/A Qrtr. l:
~y
=
N/A E13
=
N/A Qrtr. ~:
~y
=
1.01E+OO Ef3
=
5.69E-01 Qrtr.1:
Ey
=
N/A Ef3
=
N/A Liquid:
Number of Batch Releases 0
Total Time Period for Batch Releases (hrs) 0.0 Maximum Time Period for a Batch Release (hrs) 0.0 Average Time Period for a Batch Release (hrs) 0.0 Minimum Time Period for a Batch Release 0.0 i
To~~ volume of water used to dilute the liquid 1st 2nd 3rd 4th duri g the release period (L)
N/A N/A 11 NIA I
N/A I
I Total volume of water available to dilute the liquid 1st 2nd 3rd 4th Page 1 of 2 Janua!)1-December 2017 I NO RELEASES I I NO RELEASES I I
effluent durinq the report period (L) 1.08E+10 1.15E+10 I 1.31 E+10 I 1.16E+10 I Gaseous (Emergency Condenser Vent) "Not applicable for Unit 2" Number of Batch Releases N/A Total Time Period for Batch Releases (hrs)
N/A Maximum Time Period for a Batch Release (hrs)
N/A Average Time Period for a Batch Release (hrs)
N/A Minimum Time Period for a Batch Release N/A Gaseous (Primary Containment Purge)
Number of Batch Releases 7
Total Time Period for Batch Releases (hrs) 386.5 Maximum Time Period for a Batch Release (hrs) 133.2 Average Time Period for a Batch Release (hrs) 55.2 Minimum Time Period for a Batch Release (hrs) 3.3
Supplemental Information Unit 1 Unit 2 X
Abnormal Releases:
A. Liquids:
I Number of Releases I
I Total Activity Released I
B. Gaseous:
I Number of Releases I
!Total Activity Released I
ATTACHMENT 1
SUMMARY
DATA 0
I N/A lei 0
I NIA ICi Page 2 of 2 Re);!orting Period: Janua!)! - December 2017
Table 1A Gaseous Effluents -
Summation of All Releases -
Elevated and Ground Level Unit 1 Unit2 ATTACHMENT 2 Page 1 of 1 X
Rer;!orting Period: Janua!:Ji! - December 2017 GASEOUS EFFLUENTS - SUMMATION OF All RELEASES, ELEVATED AND GROUND LEVEL 1st 2nd 3rd 4th Est. Total Quarter Quarter Quarter Quarter Error,%
A. Fission & Activation Gases
- 1.
Total Release Ci O.OOE+OO O.OOE+OO 2.19E+OO O.OOE+OO 5.00E+01 I
- 2.
Average Release Rate
µCi/sec O.OOE+OO O.OOE+OO 3.91E-01 0.00E+OO I
I B. Iodines
- 1.
Total Iodine - 131 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.00E+01
- 2.
Average Release Rate for Period
µCi/sec O.OOE+OO 0.00E+OO 0.00E+OO 0.00E+OO C. Particulates
- 1.
Particulates with Half-lives>Bdays Ci O.OOE+OO 0.00E+OO 3.29E-05 3.92E-06 3.00E+01
- 2.
Average Release Rate fqr Period
µCi/sec 0.00E+OO O.OOE+OO 4.19E-06 4.99E-07
- 3.
Gross Alpha Radioactivity Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.50E+01 D. Tritium
- 1.
Total Release Ci 2.63E+01 4.38E+01 3.56E+01 4.14E+01 5.00E+01
- 2.
Average Release Rate for Period
µCi/sec 3.35E+OO 5.56E+OO 4.54E+OO 5.27E+OO E. Percent of Tech. Si;iec. Limits Fission and Activation Gases Percent of Quarterly Gamma Air Dose Limit O.OOE+OO O.OOE+OO 5.24E-03 O.OOE+OO (5 mR)
Percent of Quarterly Beta Air Dose Limit (1 O
~.OOE+OO O.OOE+OO 1.39E-04 O.OOE+OO I
mrad)
Percent of Annual Gamma Air Dose Limit to I
Date (10 mR)
O.OOE+OO O.OOE+OO 2.62E-03 2.62E-03 Percent of Annual Beta Air Dose Limit to "lo O.OOE+OO O.OOE+OO 6.95E-05 6.95E-05 Date (20 mrad)
Percent of Whole Body Dose Rate Limit (500 O.OOE+OO O.OOE+OO 1.99E-04 O.OOE+OO mrem/yr)
Percent of Skin Dose Rate Limit (3000 0.00E+OO O.OOE+OO 4.00E-05 O.OOE+OO mrem/yr)
Tritium, Iodines, and Particulates (with half-lives greater than 8 daJls)
Percent of Quarterly Dose Limit (7.5 mrem) 5.71E-03 1.29E-02 1.07E-02 1.09E-02 Percent of Annual Dose Limit to Date (15 2.85E-03 9.28E-03 1.46E-02 1.99E-02 mrem)
Percent of Organ Dose Limit (1500 mrem/yr 1.16E-04 2.57E-04 2.11 E-04 2.20E-04
Table 1 B Gaseous ATTACHMENT 3 Page 1 of 2 Effluents - Elevated Releases Unit 1 Unit2 X
Reuorting Period: Januarz! - December 2017 GASEOUS EFFLUENTS-ELEVATED RELEASE Continuous Mode (2)
Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter I
I I
Fission Gases (1)
Argon-41 Ci Krypton-BS Ci Krypton-BSm Ci Krypton-B7 Ci 1.43E-01 Krypton-BB Ci Xenon-127 Ci Xenon-131m Ci Xenon-133 Ci Xenon-133m Ci Xenon-135 Ci 5.76E-02 Xenon-135m Ci 3.43E-01 Xenon-137 Ci Xenon-13B Ci 1.65E+OO Iodines (1) lodine-131 Ci I I
I I
I lodine-133 Ci 1.16E-04 lodine-135 Ci Particulates (1) lei I
Chromium-51 I
Manganese-54 Ci lron-55 Ci lron-59 Ci Cobalt-SB Ci Cobalt-60 Ci Neodymium-14 7 Ci Zinc-65 Ci Strontium-B9 Ci Strontium-90 Ci Niobium-95 Ci Zirconium-95 Ci Molybdenum-99 Ci Ruthenium-103 Ci Cesium-134 Ci Cesium-136 Ci Cesium-137 Ci Barium-140 Ci Lanthanum-140 Ci Cerium-141 Ci Cerium-144 Ci Tritium (1)
Ci I
1.69E+01 I
.1.63E+01 I
1.57E+01 I
2.01E+01 I
(1)
- Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of 1.00E-04 µCi/ml for required noble gases, 1.00E-11 µCi/ml for required particulates and gross alpha, 1.00E-12 µCi/ml for required Iodine~, 1.00E-11
µCi/ml for Sr-B9/90 and 1.00E-06 µCi/ml for Tritium, as required by the ODCM, has. been verified.
(2) Contributions from purges are included. There were no other batch releases during the reporting period.
ATTACHMENT 3 Page 2 of 2 Unit 1 Unit2 X
Re12orting Period: Janua!Jl - December 2017 GASEOUS EFFLUENTS - ELEVATED RELEASE Batch Mode (2)
Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Fission Gases (1)
Argon-41 Ci Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-BB Ci Xenon-127 Ci Xenon-131m Ci Xenon-133 Ci Xenon-133m Ci Xenon-135 Ci Xenon-135m Ci Xenon-137 Ci Xenon-138 Ci Iodines (1) lodine-131 Ci lodine-133 Ci lodine-135 I
Ci Particulates (11 Chromium-51 Ci Manganese-54 Ci lron-55 Ci lron-59 Ci Cobalt-58 Ci Cobalt-60 Ci Neodymium-147 Ci Zinc-65 Ci Strontium-89 Ci Stronium-90 Ci Niobium-95 Ci Zirconium-95 Ci Molybdenum-99 Ci Ruthenium-103 Ci Cesium-134 Ci Cesium-136 Ci Cesium-137 Ci Barium-140 Ci Lanthanum-140 Ci Cerium-141 Ci Cerium-144 Ci Tritium (1)
Ci I
I I
I I
(1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of 1.00E-04 µCi/ml for required noble gases, 1.00E-11 µCi/ml for required particulates and gross alpha, 1.00E-12 µCi/ml for required Iodines, 1.00E-~ 1
µCi/ml for Sr-89/90 and 1.00E-06 µCi/ml for Tritium, as required by the ODCM, has been verified.
(2) Contributions from purges are included. There were no other batch releases during the reporting period.
Table 1C ATTACHMENT 4 Page 1 of 2 Unit 1 Unit2 X
ReRorting Period: Janua01 - December 2017 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode (2)
Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter I
I I
I Fission Gases {1)
Argon-41 Ci Krypton-BS Ci Krypton-B5m Ci Krypton-B7 Ci Krypton-BB Ci Xenon-127 Ci Xenon-131m Ci Xenon-133 Ci Xenon-133m Ci Xenon-135 Ci Xenon-135m Ci Xenon-137 Ci Xenon-138 Ci Iodines {1) lodine-131 Ci I
I I
I I
lodine-133 Ci lodine-135 Ci Pkrticulates m I
lromium-51 Ci I..
anganese-54 Ci I..
lron-55 Ci lron-59 Ci Cobalt-58 Ci Cobalt-60 Ci 3.29E-05 Neodymium-14 7 Ci Zinc-65 Ci Strontium-B9 Ci Strontium-90 Ci Niobium-95 Ci Zirconium-95 Ci Molybdenum-99 Ci Ruthenium-103 Ci Cesium-134 Ci Cesium-136 Ci Cesium-137 Ci 3.92E-06 Barium-140 Ci Lanthanum-140 Ci Cerium-141 Ci Cerium-144 Ci Tritium {1)
Ci I 9.44E+OO I 2.75E+01 I 1.99E+01 I 2.13E+01 I (1) Concentrations less than the lower limit of detection of the counting system used* are indicated with a double asterisk. A lower limit of detection of 1.00E-04 µCi/ml for required noble gases, 1.00E~11 µCi/ml for required particulates and gross alpha, 1.00E-12 µCi/ml for required iodines, 1.00E -
11 µCi/ml for Sr-B9/90 and 1.00E-06 µCi/ml for Tritium, as required by the ODCM, has been verified.
(2) There were no batch releases from this path during the reporting period.
Table 1C ATTACHMENT 4 Page2 of2 Unit 1 Unit2 X
Re1;1orting Period: Janua!Y - December 2017 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Batch Mode Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter I
Fission Gases {1}
Ar-41 Ci Kr-85 Ci Kr-85m Ci Kr-87 Ci Kr-88 Ci Xe-127 Ci Xe-131m Ci Xe-133 Ci Xe-133m Ci Xe-135 Ci Xe-135m Ci Xe-137 Ci Xe-138 Ci Iodines {11 1-131 Ci I
- I I
I
- I 1-132 Ci 1-133 Ci I
Particulates {1}
I Cr-51 Ci I
Mn-54 Ci Fe-55 Ci Fe-59 Ci Co-58 Ci Co-60 Ci Nd-147 Ci Zn-65 Ci Sr-89 Ci Sr-90 Ci Nb-95 Ci Zr-95 Ci Mo-99 Ci Ru-103 Ci Cs-134 Ci Cs-136 Ci Cs-137 Ci Ba-140 Ci La-140 Ci Ce-141 Ci Ce-144 Ci Tritium {1}
Ci I
I I
I I
(1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double **.
Table 2A ATTACHMENT 5 Page 1 of 2 Unit 1 Unit2 X
Re12orting Period: Janua!:)l - December 2017 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES (1) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Est. Total Error, %
A. 1-1ss1on & Act1vat1on t-'roaucts
- 1. Total Release (not including Tritium, Ci No Releases No Releases No Releases No Releases 5.00E+01 gases, alpha)
- 2. Average diluted concentration during i
reporting period
µCi/ml No Releases No Releases No Releases No Releases B. Tritium 1.Total release Ci No Releases No Releases No Releases No Releases 5.00E+01
- 2. Average diluted concentration during the
µCi/ml No Releases No Releases No Releases No Releases reporting period C. Dissolved and Entrained Gases
- 1. Total release Ci No Releases No Releases No Releases No Releases 5.00E+01
- 2. Average diluted concentration during the
µCi/ml No Releases No Releases No Releases No Releases reporting period D. Gross Al11ha Radioactivit~
- 1. Total release Ci No Releases No Releases No Releases No Releases 5.00E+01 E. Volumes
- 1. Prior to Dilution Liters No 1
Releases No Releases No Releases No Releases 5.00E+01 I
- 2. Volume of dilution water used during Liters N~ Releases No Releases No Releases No Releases 5.00E+01 release period
- 3. Volume of dilution water available during Liters 1.08E+10 1.15E+10 1.31E+10 1.16E+10 5.00E+01 reporting period F. Percent of Tech. S11ec. Limits Percent of Quarterly Whole Body Dose Limit 0.00E+OO O.OOE+OO 0.00E+OO O.OOE+OO (1.5 mrem)
Percent of Annual Whole Body Dose Limit to O.OOE+OO O.OOE+OO 0.00E+OO 0.00E+OO Date (3 mrem)
Percent of Quarterly Organ Dose Limit (5 O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO mrem)
Percent of Annual Organ Dose Limit to Date O.OOE+OO O.OOE+OO 0.00E+OO 0.00E+OO (10 mrem)
Percent of 10CFR20 Concentration Limit (2),
O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO (3)
Percent of Dissolved or Entrained Noble Gas O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Limit (2.00E-04 µCi/ml)
(1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of 5.00E-07 µCi/ml for required gamma emitting nuclides, 1.00E-05 µCi/ml for required dissolved and entrained noble gases and tritium, 5.00E-08
µCi/ml for Sr-8~/90, 1.00E-06 µCi/ml for 1-131 and Fe-55, and 1.00E-07 µCi/ml for gross alpha radioactivity, as required by the Off-Site Dose Calculation Manual (ODCM), has been verified.
(2) The percent of 1_0CFR20 concentration limit is based on the average concentration during the quarter.
(3) Improved Technicai ~pecifications limit the concentration of radioactive material released in the liquid effluents to unrestricted areas to ten times the concentrations specified in 10CFR20.1001 - 20.2402, Appendix B, Table 2, Column 2. Maximum Effluent Concentrations (MEC) numerically equal
.to ten times ihe 10CF_R20.1001 - 20.2402 concentrations were adopted to evaluate liquid effluents.
Table2B ATTACHMENT 5 Page 2 of 2 Unit 1 Unit2 X
Rei;iorting Period: Janua!Y - December 2017 LIQUID EFFLUENTS RELEASED Batch Mode (1),(2)
Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Nuclides Released I
I Strontium-89 Ci No Releases No Releases No Releases No Releases Strontium-90 Ci No Releases No Releases No Releases No Releases Cesium-134 Ci No Releases No Releases No Releases No Releases Cesium-137 Ci No Releases No Releases No Releases No Releases lodine-131 Ci No Releases No Releases No Releases No Releases Cobalt-58 Ci No Releases No Releases No Releases No Releases Cobalt-60 Ci No Releases No Releases No Releases No Releases lron-59 Ci No Releases No Releases No Releases No Releases Zinc-65 Ci No Releases No Releases No Releases No Releases Manganese-54 Ci No Releases No Releases No Releases No Releases Chromium-51 Ci No Releases No Releases No Releases No Releases Zirconium-95 Ci No Releases No Releases No Releases No Releases Niobium-95 Ci No Releases No Releases No Releases No Releases Molybderm-99 Ci No Releases No Releases No Releasf!S No Releases Techneti m-99m Ci No Releases No Releases No Releas~s No Releases Barium-1ii0 Ci No Releases No Releases No Releases No Releases Lanthanum-140 Ci No Releases No Releases No Releases No Releases Cerium-141 Ci No Releases No Releases No Releases No Releases Tungsten-187 Ci No Releases No Releases No Releases No Releases Arsenic-76 Ci No Releases No Releases No Releases No Releases lodine-133 Ci No Releases No Releases No Releases No Releases lron-55 Ci No Releases No Releases No Releases No Releases Neptunium-239 Ci No Releases No Releases No Releases No Releases Si1ver-110m Ci No Releases No Releases No Releases No Releases Gold-199 Ci No Releases No Releases No Releases No Releases Cerium-144 Ci No Releases No Releases No Releases No Releases Cesium-136 Ci No Releases No Releases No Releases No Releases Copper-64 Ci No Releases No Releases No Releases No Releases Dissolved or Entrained Gases Ci I No Releases I No Releases I No Releases I No Releases I Tritium Ci I No Releases I No Releases I No Releases I No Releases I (1) No contin*uous mode release occurred during the report period as indicated by effluent sampling.
(2) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of 5.00E-07 µCi/ml for required gamma-emitting nucfides, 1.00E-05 µCi/ml for required dissolved and entrained noble gases and tritium, 5.00E-08
µCi/ml for Sr-89/90, 1.00E-06 µCi/ml for 1-131 and Fe-55,- and 1.00E-07 µCi/ml for gross alpha radioactivity, as identified in the ODCM, has been verified.
Table 3 ATTACHMENT 6 Page 1 of 4 Unit 1 Unit2 X
Re!;!Orting Period: Janua!Jl - December 2017 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A1. TYPE Volume Activitll {1}
(ma)
(Ci)
' i i
Class Class A
B C
A B
C a.1 Spent Resin (Dewatered) 2.70E+01 O.OOE+OO O.OOE+OO 5.17E+01 O.OOE+OO O.OOE+OO a.2 Filter Sludge O.OOE+OO 5.38E+OO O.OOE+OO 0.00E+OO 1, 11 E+03 0.00E+OO a.3 Concentrated Waste 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O,OOE+OO O.OOE+OO Totals 2.70E+01 5.38E+OO O.OOE+OO 5.17E+01 1,11E+03 O.OOE+OO b.1 Dry Compressible Waste 3.75E+02 O.OOE+OO O.OOE+OO 2.69E-01 O.OOE+OO O.OOE+OO b.2 Dry Non-Compressible Waste (Contaminated O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Equipment)
Totals 3.75E+02 O.OOE+OO 0.00E+OO 2.69E-01 O.OOE+OO O.OOE+OO I
I I
I I
- c. Irradiated Components, O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0,00E+OO O.OOE+OO Control Rods, etc.
- d. Other (to vendor for processing) d.1 Oilywaste 3.67E+01 O.OOE+OO O.OOE+OO 2.95E+02 0.00E+OO O.OOE+OO (1) The estimated total error is 5.0E+01 %.
Table 3 ATTACHMENT 6 Page 2 of 4 Unit 1 Unit 2 X
Reporting Period: January - December 2017 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A1. TYPE Container Package Solidification Agent a.1 Spent Resin (Dewatered)
Poly Liner General Design None a.2 Filter Sludge Poly Liner Type B None b.1 Dry Compressible Waste Seavan General Design None b.2 Dry Non-Compressible Waste (contaminated NIA NIA Nia equipment)
- c. Irradiated Components, NIA NIA NIA Control Rods
- d. Other (To vendor for processing)
Oil/Aqueous Liquid 55 gallon drums General Design None I
I
Table 3 ATTACHMENT 6 Page 3 of 4 Unit 1 Unit 2 X
Re[!orting Period: Janua!Y - December 2017 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE)
- a. Spent Resins, Filter Sludges, Concentrated Waste Nuclide Percent Curies Fe-55 59.09%
6.89E+02 4.31E+02 Co-60 37.00%
Mn-54 1.51%
1.76E+01 Zn-65 1.39%
1.62E+01
- b. Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment)
Nuclide Percent Curies Fe-55 67.14%
1.80E-01 Co-60 28.91%
7.76E-02 Mn-54 1.56%
4.20E-03
- c. Irradiated Components, Control Rods: There were no shipments.
Nuclide I
Percent I
N/A N/A
- d. Other: (To vendor for processing)
Nuclide Percent Curies Fe-55 79.67%
2.35E+02 Co-60 18.61%
5.50E+01 Mn-54 1.21%
3.57E+OO
Table 3 ATTACHMENT 6 Page 4 of 4 Unit 1 Unit2 X
Re(!orting Period: Janua!}! - December 2017 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A3. SOLID WASTE DISPOSITION Number of Shi12ments Mode of Trans12ortation Destination 14 Truck.highway Bear Creek 6
Truck.highway Clive 2
Truck,highway wcs B. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shi12ments Mode of Trans(!ortation Destination 0
NIA N/A D. SEWAGE WASTES SHIPPED TO A TREATMENT FACILITY FOR PROCESSING AND BURIAL There are no shipments of sewage sludge with detectible quantities of plant-related nuclides from NMP to the treatment facility during the reporting period.
I I
ATTACHMENT 7 Page 1 of 1 Unit 1 Unit2 X
Re~orting Period: Janua!Jl - December 2017
SUMMARY
OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL (ODCM)
The Unit 2 Off-Site Dose Calculation Manual (ODCM) was not revised during the reporting period.
REVISION XX Page#
New/Amended Description of Change Reason For Change Section#
I I
REVISION XX Page#
New/Amended Description of Change Reason For Change Section#
ATTACHMENT 8 Page 1 of 1 Unit 1 Unit 2 X
Reporting Period: January - December 2017
SUMMARY
OF CHANGES TO THE PROCESS CONTROL PROGRAM (PCP)
RW-AA-100, PROCESS CONTROL PROGRAM FOR RADIOACTIVE WASTES, was updated to remove Fort Calhoun from the procedure and include James A. Fitzpatrick Nuclear.
ATTACHMENT 9 Page 1 of 1 Unit 1 Unit2 X
Rei;iorting Period: Janua!Jl - December 2017
SUMMARY
OF NON-FUNCTIONAL MONITORS Monitor Dates Monitor was Cause and Corrective Actions Non-Functional 2LWS-CAB206, January 1, 2017 to No liquid waste dis,charges were performed during 2017, and therefore, these 2LWS-FT330 &
December 31, 2017 monitors were not returned to seNice. The discharge manual isolation 2LWS-FT331, valves, 2LWS-V420 and 2LWS-V422, are locked closed during inoperable Liquid Waste periods, therefore, no inadvertent discharge can occur. Reference Equipment Discharge Monitor Status Log (ESL) 2010-0243.
I I
ATTACHMENT 10 Page 1 of 4 Unit 1 Unit2_X_
Reporting Period: January - Decembe~ 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY Introduction An assessment of the radiation dose potentially received by a Member of the Public due to their activities inside the site boundary from Nine Mile Point Unit 2 (NMP2).liquid and gaseous effluents has been conducted for the period January through December 2017.
This assessment considers the maximum exposed individual and the various exposure pathways resulting from liquid and gaseous effluents to identify the maximum dose received by a Member of the Public during their activities within the site boundary.
Prior to September 11, 2001, the public had access to the Energy Information Center for purposes of observing the educational displays or for picnicking and associated activities. Fishing also occurred near the shoreline adjacent to the Nine Mile Point (NMP) site. Fishing near the shoreline adjacent to the NMP site was the onsite activity that resulted in the potential maximum dose received by a Member of the Public. Following September 11, 2001 public access to the Energy Information Center has been restricted and fishing by Members of the Public at locations on site is also prohibited. Although fishing was not conducted during 2017 the annual dose to a hypothetical fisherman was still evaluated to provide continuity of data for the location.
Dose Pathways Dose pathways considered for this evaluation included direct radiation, inhalation and external grou~d (shoreline sediment or soil doses). Other pa+ways, such as ingestion pathways, are not considered becau e they are either not applicable, insignificant, or are considered as part of the evaluation of the total dose to a member of the public located off-site. In addition, only releases from the NMP2 Stack and Radwaste/Reactor Building Vent were evaluated for the inhalation pathway. Dose due to aquatic pathways such as liquid effluents is not applicable since swimming is prohibited at the NMP site.
Dose to a hypothetical fisherman is received through the following pathways while standing on the shoreline fishing:
External ground pathway; this dose is received from plant related radionuclides detected in the ~horeline sediment.
Inhalation pathway; this dose is received through inhalation of gaseous effluents released from the NMP2 Stack and Radwaste/Reactor Building Vent.
Direct radiation pathway; dose resulting from the operation of Nine Mile Point Unit 1 (NMPl), NMP2 and the James A. Fitzpatrick Nuclear Power Plant (JAFNPP) Facilities.
Methodologies for Determining Dose for Applicable Pathways External Ground (Shoreline Sediment) Pathway Dose from the external ground (shoreline sediment) is based on the methodology in the NMP2 Offsite Dose Calculation Manual (ODCM) as adapted from Regulatory Guide 1.109. For this evaluation it is assumed that the hypothetical maximum exposed individual fished from the shoreline at all times.
ATTACHMENT 10 Page 2 of 4 Unit 1 Unit2_X_
Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY The total dose received by the whole body and skin of the maximum exposed individual during 2017 was calculated using the following input parameters:
Usage Factor= 312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br /> (fishing 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per week, 39 weeks per year)
Density in grams per square meter= 40,000 Shore width factor= 0.3 Whole body and skin dose factor for each radionuclide = Regulatory Guide 1.109, Table E-6.
Fractional portion of the year= 1 (used average radionuclide concentration over total time period)
Average Cs-137 concentration= 1.30E-01 pCi/g The total whole body and skin doses received by a hypothetical maximum exposed fisherman from the external ground pathway is presented in Table 1, Exposure Pathway Annual Dose.
Inhalation Pathway The inhalation dose pathway is evaluated by utilizing the inhalation equation in the NMP2 ODCM, as adapted from Regulatory Guide 1.109. The total whole body dose and organ dose received by the hypothetical maximum exposed fisherman during 2017 calculated using the following input parameters for gaseous effluents released from both the NMP2 Stack and Radwaste/Reactor Building Vent for the time period exposure is received:
NMP2Stack*
I Vari hie Fisherman 1 I
X/Q (s/m3) 9.6 E-07 Inhalation dose factor Table E-7, Regulatory Guide 1.109 Annual air intake (m3/year) (adult) 8000 Fractional portion of the year 0.0356 H-3 (pCi/sec) 2.21 E+06 C-14 (pCi/sec/
6.00 E+05 NMP2 Radwaste/Reactor Building Vent:
Variable Fisherman 1 X/0 (slm 3
)
2.8 E-06 Inhalation dose factor Table E-7, Regulatory Guide 1.109 Annual air intake (m 3/year) (adult) 8000 Fractional portion of the year 0.0356 H-3 (pCi/sec) 2.91E+06 Co-60 (pCi/sec) 1.40E+oo*
Cs-137(pCi/sec) l.66E-Ol
Unit 1 ATTACHMENT 10 Page 3 of4 Unit2_X_
Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY
- 1. The maximum exposed fisherman is assumed to be present on site during the period of April through December at a rate of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per week for 39 weeks per year equivalent to 312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br /> for the year (fractional portion of the year = 0.0356). Therefore, the Average Stack and Radwaste/Reactor Building Vent flow rates and radionuclide concentrations used to determine the dose are represented by second, third and fourth quarter gaseous effluent flow and concentration values.
- 2. C-14 release rate determined from NUREG-0016, "Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents for Boiling Water Reactors (BWR-GALE Code),"
and EPRI Technical Report 1021106, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents."
The total whole body dose and maximum organ dose received by the hypothetical maximum exposed fisherman is presented in Table 1, Exposure Pathway Annual Dose.
Direct Radiation Pathway The direct radiation pathway is evaluated in accordance with the methodology found in the NMP2 ODCM.
This pathway considers four components: direct radiation from the generating facilities, direct radiation from any possible overhead plume, direct radiation from ground deposition and direct radiation from plume Strmersion. The direct radiation pathway is evaluated by \\the use of high sensitivity environmental Tl ermoluminescent Dosimeters (TLDs). Since fishing activiti1s occur between April 1 and December 31, T D data for the second, third, and fourth quarters of 2017 from TLDs placed in the general area where fishing once occurred were used to determine an average dose to the hypothetical maximum exposed fisherman from direct radiation. The following is a summary of the average dose rate and assumed time spent on site used to determine the total dose received:
Variable Fisherman Average Dose Rate (mRem/hr) l.04E-03 Exposure time (hours) 312 Total Doses received by the hypothetical maximum exposed fisherman from direct radiation is presented in Table 1, Exposure Pathway Annual Dose.
ATTACHMENT 10 Page4 of 4 Unit 1 Unit2_X_
Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY Dose Received By A Hypothetical Maximum Exposed Member o.f the Public Inside the Site Boundary During 2017 I
The following is a summary of the dose received by a hypothetical maximum exposed fisherman from liquid
- and gaseous effluents released from NMP2 during 2017:
TABLE 1 Exposure Pathway Annual Dose Fisherman Exposure Pathway Dose Type (mreni)
Whole Body 2.04E-03 External Ground Skin of Whole Body 2.38E-03 Whole Body 5.32E-04 Inhalation Maximum Organ Lung: 5.33E-04 Thyroid 5.32E-04 Direct Radiation Whole Body 0.32 Based on these values, the total annual dose receivfd by a hypothetical maximum exposed Member of the Public inside the site boundary is as follows:
I TABLE2 Annual Dose Summary Fisherman Total Annual Dose for 2017 (mrem)
Total Whole Body 3.26E-01 Skin of Whole Body 2.38E-03 Maximum Organ Lung: 5.33E-04 Thyroid 5.32E-04
ATTACHMENT 11 Page 1 of 5 Unit 1 Unit2_X __
Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Introduction An assessment of radiation doses potentially received by the l~kely most exposed Meinber of the Public located beyond the site boundary was conducted for the period January through December 2017 for comparison against the 40 CPR 190 annual dose limits.
/
I The intent of 40 CPR 190 requires that the effluents of Nine Mile Point Unit 2 (NMP2), as well as other nearby uranium fuel cycle facilities, be considered. In this case, the effluents of Nine Mile Point Unit 1 (NMPl), NMP2 and the James A. FitzPatrick Nuclear Power Plant (JAFNPP) facilities must be considered.
40 CPR 190 requires the annual radiation dose received by Members of the Public in the general environment, as a result of plant operations, be limited to:
< 25 mRem whole body
< 25 mRem any organ ( except thyroid)
< 75 mRem thyroid This evaluation compares doses resulting from liquid and gaseous effluents and direct radiation originating from the site as a result of the operation of the NMPl, NMP2 and JAFNPP nuclear facilities.
Dose Pathways Dose pathways considered for this evaluation included doses resulting from liquid effluents, gaseous effluents and direct radiation from all nuclear operating facilities located on the Nine Mile Point site.
D9se to the likely most exposed Member otthe Public, outside the site boundary, is received through the Ji 1
ollowing pathways:
r Fish consumption pathway; this dose is received from plant radionuclides that have concentrated in fish that is consumed by a Member of the Public.
Vegetation consumption pathway; this dose is received from plant radionuclides that have concentrated in vegetation that is consumed by a Member of the Public.
Shoreline Sediment; this dose is received as a result of an individual's exposure to plant radionuclides in the shoreline sediment, which is used as a recreational area.
Deposition, Inhalation and Ingestion pathways resulting from gaseous effluents; this dose is received through exposure to gaseous effluents released from NMPl, NMP2 and JAFNPP operating facilities.
Direct Radiation pathway; radiation dose resulting from the operation ofNMPl, NMP2 and JAFNPP facilities (including the Independent Spent Fuel Storage Installations (ISFSI)).
Methodologies for Determining Dose for Applicable Pathways Fish Consumption D9se received as a result of fish consumption is based on the methodology specified in the NMP2 Off-Site Dose Calculation Manual (ODCM) as adapted from Regulatory Guide 1.109. The dose for 2017 is calculated from
_actuaLanalysis results of environmental fish samples taken near the site discharge points. For this evaluation it is
- asimme_d that the most likely exposed Member of the Public consumes fish taken near the site discharge points.
N9 radionuclides were detected in fish samples collected *and analyzed during 2017; therefore, no dose was repeived by the whole body and organs of the likely most exposed Member of the Public during 2017.
ATTACHMENT 11 Page 2 of 5 Unit 1 Unit2_X __
Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Vegetation Consumption Dose received as a result of vegetation cons4mption is based on the methodology specified in the NMP2 ODCM as adapted from Regulatory Guide 1.109. The dose for 2017 is calculated from actual analysis results of environmental vegetation samples taken near the most exposed Member of the Public.
i No radionuclides were detected in vegetation samples collected and analyzed during 2017; therefore, no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2017.
For estimating C-14, dose received as a res4lt of vegetation consumption is based on the methodology specified in the NMP2 ODCM as adapted from Regulatory Guide 1.109. The estimated concentration of C-14 in vegetation is based on the estimated concentration of C-14 in plant gaseous effluents.
Shor"eline Sediment Dose received from shoreline sediment is based on the methodology in the NMP2 ODCM as adapted from Regulatory Guide 1.109. For this evaluation it is assumed that the most likely exposed Member of the Public spends 67 hour7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br />s/year along the shoreline for recreational purposes.
No radionuclides were detected in shorelin~ sediment samples collected and analyzed during 2017; therefore no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2017.
Dose Pathwa s Resultin Fro.m Gaseous Effluents I
Dose received by the likely ost exposeq Member of the Public due to gaseous efflu~nts is calculated in accordance with the methodology provided in the NMPl ODCM, NMP2 ODCM, and the JAFNPP ODCM. These calculations consider deposition, inhalatioµ and ingestion pathways. Actual meteorological data was used to calculate doses to the likely most exposed Member of the Public. The total sum of doses resulting from gaseous effluents from NMPl, NMP2 and JAFNPP during 2017 provides a total dose to the whole body and maximum organ dose for this pathway.
Carbon-14 Dose Pathways Resulting from Gaseous Effluents The Carbon-14 (C-14) effluent source terms are used to estimate radiological doses from C-14 in site gaseous waste effluents. These estimates were generated in order to meet the NRC requirement to incorporate C-14 in nuclear power plant 2017 Annual Radiological Effluent Release Reports (ARERRs). The C-14 production and effluent source term estimates were based on EPRI methodology provided in EPRI Report 1021106, Estimation of Carbon-14 in Nuclear Power Plant Gaseou~ Effluents, December 2010. The following methodology was used in estimating C-14 gaseous release activity and dose components for the 2017 ARERR.
EPRI methodology for estimating C-14 proquction rates in.Boiling Water Reactors (BWRs):
ForBWRs, EPRI R.ep~rt 1021106 summarized the.distribution of C-14 in releas*e pathways as follows: gaseous 95% to 99%, liquid <0.5% and solid 1 % to 5%. The report also states that -95% of C., 14 in BWR gaseous waste effluents exists in the carbon dioxide form, which contributes to population dose via photosynthesis uptake in the food consumption cycle.
ATTACHMENT 11 Page 3 of 5 Unit 1 Unit2_X __
Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDA~Y For NMPl and NMP2, C-14 gaseous dose calculations in the site ARERR are made using the following assumptions for each unit: (1) continuous release of the estimated C-14 generated during power operation based on the number of Effective Full Power Days (EFPDs) for the period, (2) maximum C-14 activity from literature values cited in EPRI Report 1021106, and (3) typical fraction as carbon dioxide for'. gaseous releases from literature values also cited in EPRI Report 1021106.
Equation 1 estimates the maximum annual production of C-14, PRMAX, for each BWR unit.
PRMAX
=
5.1
- MWT / 1000
[Eq 1}
Where:
5.1
=
BWR Normalized Production (Ci/GWt-yr)
MWT
=
Mega Watts Thermal (MWt) 1000
=
Conversion Factor (MWt to GWt)
Equation 2 estimates the C-14 activity released, A c.14, into the gaseous pathway during the time peripd for each BWR unit.
A C-14 Where:
PRMAX 0.99 EFPD 365
~
PR MAX
- 0.99
- EFPD I 365, Ci (for time period)
[Eq2]
=
maximum annual production rate ofC-14
=
fraction ofC-14 in BWR gaseous pathway releases (maximum literature value in EPRI Report 1021106; also Table 1) number of effective full power days for the unit during the time period; e.g., quarterly or yearly (Table 1)
=
number of days in a typical year
ATTACHMENT 11 Page 4 of 5 Unit 1 Unit2_X __
Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Equation 3 estimates the C-14 activity released in carbon dioxide form, A C-l4, co2, into the gaseous pathway during the time period for each BWR unit.
PRMAX
=
0.99
=
0.95
=
=
365 PR MAX
- 0.99
- 0.95
- EFPD I 365, Ci (for time period) maximum annual production rate of C-14 fraction of C-14 in BWR gaseous pathway releases (maximum literatur~ value in EPRI Report 1021106; also Table 1) fraction of C-14 as carbon dioxide in BWR gaseous pathway
[Eq3}
releases (typical literature value in EPRI Report 1021106; also Table 1) number of effective full power days for the unit during the time period, e.g. quarterly or yearly (Table 1) conversion factor, 365 days in a typical average year For each BWR unit, the 2017 estimated C-14 activity releases (total and carbon dioxide chemical form) are summarized in Table 1.
Table 1 I
2017 BWR Estimated C-14 Gaseous Releases Gaseous CO2 Form Max.Annual BWR Release Release EFPD Operation Fraction(a)
Fraction(b)
NMPl 0.99 0.95 331.2 EFPD (90.7%)
NMP2 0.99 0.95 359.85 EFPD (98.6%)
JAFNPP 0.99 0.95 309.1 EFPD (84.7%)
(a) Maximum literature values from EPRI Report 1021106.
(b) Typical value from EPRI Report 1021106.
Prod. Rate (Eq 1) 9.44 Ci/yr 20.34 Ci/yr(c) 12.93 Ci/yr
- (c) NMP2 Reactor Power Rating increased to 3988 Megawatts thermal.
2017 Total Release (Eq 2) 8.48 Ci 19.85 Ci 9.09 Ci 2017 CO2 Release (Eq3) 8.05 Ci 18.86 Ci 8.63 Ci As long as the core designs and power ratings are not significantly changed, the maximum annual production rates and annual total and carbon dioxide activity releases in Table 1 should be acceptable for use in estimating C-14 gaseous release activity and dose components for the ARERR.
ATTACHMENT 11 Page 5 of 5 Unit 1 Unit 2 X
Reporting Period: January - December 2017 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Direct Radiation Pathway Dose as a result of direct gamma radiation from the site, encompasses doses from direct "shine" from the generating facilities, direct radiation from any overhead gaseous plumes, plume submersion, and ground deposition. This total dose is measured by environmentai TLDs. The critical location is based on the closest year-round residence from the generating facilities as well as the closest residence in the critical downwind sector in order to evaluate both direct radiation from the generating facilities and gaseous plumes as determined by the local meteorology. During 2017, the closest residence and the critical downwind residence are at the same location.
Table 2 Dose Potentially Received by the Likely Most Exposed M~mber of the Public Outside the Site Boundary During 2017 Exposure Pathway Dose Type Dose (mrem)
Total Whole Body No Dose Fish and Vegetation Consumption Total Maximum Organ No Dose Total Whole Body No Dose Shoreline Sediment Total Skin of Whole Body No Dose Total Whole ~ody 4.42 E-03 Gaseous Effluents Thyroid I 1.02 E-02 (excluding C-14)
Maximum Organ Thyroid: 1.02 E-02 Gaseous Effluent Total Whole Body 3.52 E-01 (C-14)
Maximum Organ Bone: 1.76 E+OO Direct Radiation Total Whole Body 0.91 Based on these values the maximum total annual dose potentially received by the likely most exposed Member of the Public during 2017 is as follows:
\\
Total Whole Body:
1.27 E+OO mrem Total Thyroid:
1.02 E-02 Maximum Organ:
Bone: 1.76 E+OO mrem 40 CFR 190 Evaluation The maximum total doses presented in this attachment are the result of operations at the NMPl, NMP2 and the JAFNPP facilities. The maximum organ dose (Bone: 1.76 mrem), maximum thyroid dose (0.010 mrem) and the maximum whole body dose (1.27 mrem) are below the 40 CFR 190 criteria of 25 mrem per calendar year to the maximum exposed organ or the whole body, and below 75 mrem per calendar year to the thyroid.
l ATTACHMENT 12 Page 1 of 1 Unit 1 --
Unit2 _x_
Regorting Period: Janua!)(- December 2017 Well Identification
- Samples
- Positive Minimum Maximum Number Collected Samples Concentration (pCiil)
Concentration (pCi/1)
GMX-MW1*
4 0
<188
<194 MW-1 4
0
<188
<200 MW-5 4
I 0
<183
<193 MW-6 4
0
<186
<191 MW-7 4
0
<186
<194 MW-8 4
0
<187
<193 MW-91 4
0
<187
<192 MW-101 4
1
<186 240 MW-11 4
0
<186
<193 MW-12 4
0
<190
<193 MW-13 4
0
<184
<192 fvlW-14*
4 1
<183 234 MW-15 4
1
<186 252 MW-16 4
0
<184
<192 MW-17 4
1
<183 222 fvlW-18 4
1
<190 270 MW-19 4
I 0
<186
<190 I
MW-20 4
I 0
<183
<192 I
MW-21 4
0
<183
<190 NMP2 MAT 2'3 4
1
<181 279 PZ-1 4
0
<190
<193 PZ-2 4
0
<191
<196 PZ-3 4
0
<187
<194 PZ-4 4
1
<189 214 PZ-5 4
0
<190
<191 PZ-6 4
0
<188
<192 PZ-7 4
4 291 435 PZ-8 4
0
<190
<198 PZ-9*
4 0
<189
<194 Notes:
- - Control Location 1 - Sentinel well location 2 - NMP2 Groundwater Depression Cone 3
- Samples collected from storm drain system which includes precipitation *