ML15133A321

2014 Radioactive Effluent Release Report

ML15133A321
Person / Time
Site:	Nine Mile Point
Issue date:	05/01/2015
From:	Orphanos P Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NMP1L 3022
Download: ML15133A321 (67)

Text

I'b Exe!on Generation.

10 CFR 50.36a Technical Specifications NMP1L 3022 May 1, 2015 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Nine Mile Point Nuclear Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-63 and NPF-69 NRC Docket Nos. 50-220 and 50-410

Subject:

2014 Radioactive Effluent Release Report for Nine Mile Point Units 1 and 2 In accordance with 10 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 2014.

The format used for the effluent data is outlined in Appendix B of Regulatory Guide 1.21, Revision 1. During the reporting period, NMP1 and NMP2 did not exceed any 10 CFR 20, 10 CFR 50, Technical Specification, or ODCM limits for gaseous or liquid effluents.

Should you have questions regarding the information in this submittal, please contact Shane Howe, Site Chemistry Environmental & Radwaste Manager, at (315) 349-5210.

Sincerely, Peter M. Orphanos Vice President, Nine Mile Point Nuclear Station Exelon Generation Company, LLC PMO/BTV

Enclosures:

(1) Nine Mile Point Nuclear Station, Unit 1 Radioactive Effluent Release Report, January - December 2014 (2) Nine Mile Point Nuclear Station, Unit 2 Radioactive Effluent Release Report, January - December 2014

Document Control Desk May 1, 2015 Page 2 Cc: NRC Regional Administrator, Region 1 NRC Project Manager NRC Resident Inspector C. Graves, NRC

Enclosure I Nine Mile Point Nuclear Station, Unit 1 Radioactive Effluent Release Report, January - December 2014

x, .

NINE MILE POINT NUCLEAR STATION - UNIT 1 RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2014 SUPPLEMENTAL INFORM TION Facility: 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 effluents 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 10 milliroentgen for gamma radiation and less than or equal to 20 mrad for beta radiation.

B. IODINES

1. The dose rate 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 and 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 1 to areas at and 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.

C. TRITIUM AND PARTICULATES, HALF LIVES> 8 DAYS

1. The dose rate 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 and 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 I to areas at and 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.

Nine Mile Point Nuclear Station, LLC May 1, 2015

~Im 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 commitment 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 mrem to any organ, and during any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

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 determined by on-line gross activity monitoring (calibrated against gamma isotopic analysis of a 4.OL 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 purge and weekly when fuel 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 estimated by applying scaling factors to release rates of gamma emitters and actual release rates are determined from post off site 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.

Nine Mile Point Nuclear Station, LLC May 1, 2015

F. LIQUID EFFLUENTS Isotopic contents of liquid effluents are determined 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 of Sr-89, Sr-90, and Fe-55 are estimated by applying scaling factors to release rates of gamma emitters and actual release rates are determined from post off site analysis results.

G. SOLID EFFLUENTS Isotopic contents of waste shipments are determined 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 of Carbon-14 in Nuclear Power Plant Gaseous Effluents, December 2010 and NUREG-00 16, 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 of required meteorological data on site in a file that shall be provided to the NRC upon request.

Nine Mile Point Nuclear Station, LLC May 1, 2015

....I Supplemental Information ATTACHMENT 1 Page 1 of 2

SUMMARY

DATA Unit 1 X Unit 2 Reporting Period January -December 2014 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 2014.

Average MEC - pCi/ml (Qtr. 1)= NO RELEASES Average MEC - pCi/ml (Qtr. 3) = N LEASES Average MEC - pCi/mI (Qtr. i) NO RELEASES Average MEC - pCi/mI (Qtr. 4) =N EESS Average Energy (Fission and Activation gases - MeV):

Qrtr. 1: Ey = N/A EP = N/A Qrtr.2: Ev = N/A Ep = N/A Qrtr. 3: Ey = NIA EP = N/A Qrtr. 4: EV = N/A EP. = 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 N/A N/A N/A N/A Total volume of water available to 1st 2nd 3rd 4th dilute the liquid effluent during report period (L) Radwaste 1.29E+11 1'32E+11 I 1.36E+11 1.30E+11 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 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 Nine Mile Point Nuclear Station, LLC May 1, 2015

Supplemental Information ATTACHMENT I Page 2 of 2

SUMMARY

DATA Unit 1 X Unit 2 Reporting Period January - December 2014 Abnormal Releases:

A. Liquids:

Number of Releases 0 ITotal Activity Released I NA B. Gaseous:

I.Number of Releases 0 ITotal Activity Released N/A Ci 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 0DCM 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).

No tritium was detected in the Reactor Building Perimeter Drains during 2014.

Nine Mile Point Nuclear Station, LLC May 1, 2015

Table 1A Gaseous Effluents - ATTACHMENT 2 Page 1 of 1 Summation of All Releases -

Elevated and Ground Level Unit.1 X Unit 2 Reporting Period January - December 2014 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES, ELEVATED AND GROUND LEVEL 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter EST. TOTAL ERROR %

A. Fission & Activation Gases (11

1. Total Release Ci ** -- -5.OOE+01

• • ** ** ** 50E0

2. Average Release Rate pCi/sec B. lodines (1)

1. Total Iodine- 131 Ci 1.60E-05 1.40E-05 8.51E-05 4.81 E-05 3OOE+01

2. Average Release Rate for Period pCi/sec 2.03E-06 1.78E-06 1.01 E-05 6.11 E-06 C. Particulates (1)

1. Particulates with Half-lives>8 days Ci 1.31 E-04 1.96E-04 2.77E-04 2.40E-04 3.OOE+01

2. Average Release Rate for Period pCi/sec 1.67E-05 2.50E-05 3.31 E-05 3.05E-05

3. Gross Alpha Radioactivity Ci ** * - **2.50E+01 D. Tritium (1)

1. Total Release Ci 4.99E+00 5.50E+00 6.68E+00 9.82E+00 5.00E+01

2. Average Release Rate for Period pCi/sec 6.36E-01 6.99E-01 8.05E-01 1.25E+00 E. Percent of Tech. Spec. Limits Fission and Activation Gases Percent of Quarterly Gamma Air Dose Limit (5 mR) 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 Percent of Quarterly Beta Air Dose Limit (10 mrad) 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Percent of Annual Gamma Air Dose Limit to Date (10 mR) 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Percent of Annual Beta Air Dose Limit to Date (20 mrad) 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Percent of Whole Body Dose Rate Limit (500 mrem/yr) 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Percent of Skin Dose Rate Limit (3000 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 mrem/yr)

Tritium, lodines. and Particulates (with half-lives greater than 8 days)

Percent of Quartedy Dose Limit (7.5 1.53E-02 1.89E-02 4.68E-02 3.57E-02 mrem)

Percent of Annual Dose Limit to Date (15 mrem) 7.67E-03 1.71 E-02 4.05E-02 5.84E-02 Percent of Organ Dose Limit (1500 3.11E-04 3.80E-04 9.28E-04 7.09E-04 mrem/yr (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.

Nine Mile Point Nuclear Station, LLC May 1, 2015

Table 1B Gaseous ATTACHMENT 3 Page 1 of 2 Effluents - Elevated Releases

.Unit 1 X Unit 2 . Reporting Period January -December 2014 GASEOUS EFFLUENTS - ELEVATED RELEASE Continuous 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-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 lodines (1)

Iodine-131 Ci 1.60E-05 i.40E-05 8.51E-05 4.81E-05 Iodine-133 Ci 8.39E-04 1.03E-03 1.23E-03 1.56E-03 Iodine-135 Ci Particulates (1) ** I ** I ** I **

Strontium-89 Ci Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci 1.05E-05 2.OOE-06 1.51E-05 1.71 E-05 Cobalt-60 Ci 9.75E-05 1.75E-04 2.15E-04 2.06E-04 Cobalt-58 Ci ** 1.88E-05 1.87E-05 1.68E-05 Manganese-54 Ci Barum-140 Ci Lanthanum-140 Ci Niobium-95 Ci Cerium-141 Ci 2*3iE-O5** **

Cerium-144 Ci Iron-59 Ci Cesium-136 Ci Chromium-51 Ci 2.31 E-05 ...

Zinc-65 Ci Iron-55 Ci ... 2.81E-05 *j Molybdenum-99 Ci Neodymium-147 Ci Tritium (1) Ci 4.12E+00 4.65E+00I 5.47E+00 8.99E+00 (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.OOE-04 pCi/ml for required noble gases, 1.OOE-1 1 pCi/ml for required particulates, 1.OOE-12 pCi/ml for required lodines, and 1.OOE-06 pCi/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.

Nine Mile Point Nuclear Station, LLC May 1, 2015

Table 1 B ATTACHMENT 3 Page 2 of 2 Unit 1 X Unit 2 Reporting Period January - December 2014 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-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 lodines (1)

I 3 ~3 ~3 ~3 Iodine-131 Ci Iodine-133 Ci Iodine-135 Ci Particulates (1)

Strontium-89 Ci Strontium-90 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 Iron-59 Ci Cesium-136 Ci Chromium-51 Ci Zinc-65 Ci Iron-55 Ci Molybdenum-99 Ci Neodymium-147 Ci Tritium (1) Ci (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.OOE-04 pCi/ml for required noble gases, 1.OOE-1i1 pCi/ml for required particulates, 1.OOE-12 pCi/ml for required lodines, and 1.OOE-06 pCi/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.

Nine Mile Point Nuclear Station, LLC May 1, 2015

Table 1C Gaseous ATTACHMENT 4 Page 1 of 2 Effluents - Ground Releases Unit 1 X Unit 2 Reporting Period January - December 2014 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 lodines (1)

Iodine-131 Ci Iodine-133 Ci Iodine-135 Ci Particulates (1)

Strontium-89 Ci Strontium-90 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 Iron-59 Ci Cesium-136 Ci Chromium-51 Ci Zinc-65 Ci Iron-55 Ci Molybdenum-99 Ci Neodymium-147 Ci Tritium (1) Ci 8.69E-0i 8.44E-0i i.21E+00 8.27E-0i (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.

Nine Mile Point Nuclear Station, LLC May 1, 2015

-3 Table 1C ATTACHMENT 4 Page 2 of 2 Unit 1 X Unit 2 Reporting Period January - December 2014 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)

Argon-41 Ci Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-127 Ci Xenon-1 31 m Ci Xenon-1 33 Ci Xenon-133m Ci Xenon-135 Ci Xenon-135m Ci Xenon-137 Ci Xenon-1 38 Ci lodines (1)

Iodine-131 Ci Iodine-133 Ci Iodine-135 Ci Particulates (1)

Strontium-89 Ci Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci Cobalt-60 Ci Cobalt-58 Ci Manganese-54 Ci Barium-140 Lanthanum-140 Ci Ci IT2 t 3" EEI 3"l

• Niobium-95 Ci Cerium-141 Ci Cerium-144 Ci Iron-59 Ci Cesium-136 Ci Chromium-51 Ci Zinc-65 Ci Iron-55 Ci Molybdenum-99 Ci Neodymium-147 Ci Tritium (1) Ci (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.

Nine Mile Point Nuclear Station, LLC May 1, 2015

Table 2A ATTACHMENT 5 Page 1 of 2 Unit 1 X Unit 2 Reporting Period January - December 2014 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES (1) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Est. Total Error, %

A. Fission & Activation Products

1. Total Release (not including Tritium, Ci 5.OOE+01 gases, alpha) No Releases No Releases No Releases No ReleasesI

2. Average diluted concentration during pCi/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.OOE+01

2. Average diluted concentration during pCi/ml No Releases No Releases No ReleasesjNoReleases the reporting period C. Dissolved and Entrained Gases

1. Total release Ci No Releases No Releases No Releases No Releases 5.OOE+01

2. Average diluted concentration during pCi/ml No Releases No Releases the reporting period No Releases No Releases D. Gross Alpha Radioactivity

1. Total release 5.OOE+01 Ci I No Releasesl No Releases No Releases I No Releases E. Volumes

1. Prior to Dilution Liters No Releases No Releases No Releases No Releases 5.OOE+01

2. Volume of dilution water used during release period Liters No Releases No Releases No Releases No Releases 5.OOE+01

3. Volume of dilution water available during reporting period - Cooling Water Liters 1.29E+11 1.32E+11 1.36E+11 1.30E+11 5.OOE+01 F. Percent of Tech. Spec. 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 10CFR20 Concentration No Releases No Releases No Releases No Releases Limit Percent of Dissolved or Entrained Noble No Releases No Releases No Releases No Releases Gas Limit (2.OOE-04 pCi/ml)

(1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.

Nine Mile Point Nuclear Station, LLC May 1, 2015

A Table 2B ATTACHMENT 5 Page 2 of 2 Unit I X Unit 2 Reporting Period January - December 2014 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 Iodine-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 Iron-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 Iodine-133 Ci No Releases No Releases No Releases No Releases Iron-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.OOE-07 pCi/ml for required gamma emitting nuclides, 1.OOE-05 pCi/ml for required dissolved and entrained noble gases and tritium, 5.OOE-08 pCi/ml for Sr-89/90, 1.OOE-06 pCi/ml for 1-131 and Fe-55, and 1.OOE-07 pCi/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.

Nine Mile Point Nuclear Station, LLC May 1, 2015

Table 3 ATTACHMENT 6 Page 1 of 4 Unit I X Unit 2 Reporting Period January - December 2014 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Al. TYPE Volume Activity (1)

(me) (Ci)

Class Class A B C A B C a.1 Spent Resin (Dewatered) 9.91 E+00 O.OOE+00 O.OOE+00 7.79E+00 0.00E+00 O.OOE+00 a.2 Filter Sludge O.OOE+O0 O.OOE+0O O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 a.3 Concentrated Waste O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Totals 9.91E+00 O.OOE+00 O.OOE+00 7.79E+00 O.OOE+00 O.OOE+00 b.1 Dry Compressible Waste 1.16E+02 O.OOE+00 O.OOE+00 5.02E-02 O.OOE+00 O.OOE+00 b.2 Dry Non-Compressible Waste (Contaminated O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Equipment) I I Totals 1.16E+02 O.OOE+00 O.OOE+00 5.02E-02 O.OOE+00 O.OOE+00 c to0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 Control Rods, etc.

d. Other (to vendor for processing) d.1 Sewage sludge 1.63E+01 O.OOE+00 O.OOE+00 2.08E-05 O.OOE+00 O.OOE+00 1(l)The estimated total error is 5.OE+01 %.

Nine Mile Point Nuclear Station, LLC May 1, 2015

• II Table 3 ATTACHMENT 6 Page 2 of 4 Unit I X Unit 2 Reporting Period January - December 2014 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Al. TYPE Container Package Solidification Agent a.1 Spent Resin (Dewatered) Poly Liner General Design None a.2 Filter Sludge N/A N/A N/A 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 N/A Control Rods

d. Other (To vendor for processing) d.1 Sewage sludge Flexible shipping bag General Design None

Table 3 ATTACHMENT 6 Page 3 of 4 Unit I X Unit 2 Reporting Period January - December 2014 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 H-3 1.66% 1.32E-01 C-14 2.05% 1.63E-01 Fe-55 4.12% 3.27E-01 Co-60 83.04% 6.59E+00 Cs-137 6.25% 4.96E-01

b. Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment)

Nuclide Percent Curies Cr-51 2.28% 1.14E-03 Mn-54 2.63% 1.32E-03 Fe-55 52.35% 2.63E-02 Co-60 38.61% 1.94E-02 Ni-63 1.33% 6.66E-04

c. Irradiated Components, Control Rods: There were no shipments.

Nuclide Percent N/A N/A

d. Other: (To vendor for processing)

1. Dried Sewage Sludge shipped in "Flexible Shipping Bag" Nuclide Percent Curies Mn-54 3.76% 7.80E-07 Co-60 90.56% 1.88E-05 Cs-137 5.68% 1.18E-06 Nine Mile Point Nuclear Station, LLC May 1, 2015

b Table 3 ATTACHMENT 6 Page 4 of 4 Unit I X Unit 2 Reporting Period January - December 2014 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A3. SOLID WASTE DISPOSITION Number of Shipments Mode of Transportation Destination 1 Hittman Transport Barnwell Processing Facility 1 Hittman Transport Durateck Services, Inc (GRF) 2 Hittman Transport Energy Solutions Services (CVRF) 1 Hittman Transport Energy Solutions (Clive)

B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination 0 N/A N/A D. SEWAGE WASTES SHIPPED TO A TREATMENT FACILITY FOR PROCESSING AND BURIAL Sewage sludge with detectable quantities of plant-related nuclides was shipped from NMP to the treatment facility during 2014.

Nine Mile Point Nuclear Station, LLC May 1, 2015

ATTACHMENT 7 Page 1 of 1 Unit 1 X Unit 2 Reporting Period January - December 2014

SUMMARY

OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL (ODCM)

The Unit 1 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 #

REVISION XX NewlAmended Page # Section #d Description of Change Reason For Change

__ I____ I______ I_______

Nine Mile Point Nuclear Station, LLC May 1, 2015

-h ATTACHMENT 8 Page 1 of 1 Unit 1 X Unit 2 Reporting Period January - December 2014

SUMMARY

OF CHANGES TO THE PROCESS CONTROL PROGRAM (PCP)

There were no changes to the NMP1 Process Control Program (PCP) during the reporting period.

Nine Mile Point Nuclear Station, LLC May 1, 2015

ji ATTACHMENT 9 Page 1 of 1 Unit 1 X Unit 2 Reporting Period January - December 2014

SUMMARY

OF NON-FUNCTIONAL MONITORS Monitor Dates Monitor was Cause and Corrective Actions Non-Functional Liquid Radwaste January 1, 2014 to These monitors were intentionally allowed to exceed their quarterly Discharge Monitors December 31, 2014 functional test and annual calibration frequency, as no discharges 11 and 12 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 2014. This non-functionality is tracked in Equipment Status Log (ESL) 2006-0192.

)

ATTACHMENT 10 Page 1 of 4 Unit I X Unit 2 _ Reporting Period: January -December 2014 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 (NMPI) liquid and gaseous effluents has been conducted for the period January through December 2014.

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 2014, 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 ground (shoreline sediment or soil doses). Other pathways, such as ingestion pathways, are not considered because 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 NMP1 stack and 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 inhalation of gaseous effluents released from the NMP1 Stack and Emergency Condenser Vent.

" Direct radiation pathway; dose resulting from the operation of NMP1, 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 NMP1 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.

Nine Mile Point Nuclear Station, LLC May 1, 2015

-l ATTACHMENT 10 Page 2 of 4 1

Unit 1 X Unit 2 Reporting Period: January - December 2014 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY I The total dose received by the whole body and skin of the maximum exposed individual during 2014 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 = I (used average radionuclide concentration over total time period)

" Average Cs-137 concentration = 1.05E-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 NMP1 ODCM, as adapted from Regulatory Guide 1.109. The total whole body dose and organ dose received by the hypothetical maximum exposed fisherman during 2014 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 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) 7.92 E+05 2

C-14 (pCi/sec) 2.75 E+05 Fe-55 (pCi/sec) 1.17 E+00 Co-58 (pCi/sec) 2.25 E+00 Co-60 (pCI/sec) 2.47 E+01 1-131 (pCi/sec) 6.10 E+00 1-133 (pCi/sec) 1.58 E+02 Cs- 137 (pCi/sec) 1.42 E+00 Nine Mile Point Nuclear Station, LLC May 1, 2015

ATTACHMENT 10 Page 3 of 4 Unit 1 X Unit 2 __ Reporting Period: January - December 2014 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY_

NMPI Emergency Condenser Vent:

Variable Fisherman X/Q (s/rn3) 6.63E-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) 1.21 E+05 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 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 NMPI 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 between April 1 and December 31, TLD data for the second, third, and fourth quarters of 2014 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) 5.47 E-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.

Nine Mile Point Nuclear Station, LLC May 1, 2015

ATTACHMENT 10 Page 4 of 4 Unit 1 X DOSESUnitTO 2 MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE Reporting Period:THE SITE BOUNDARY January - December 2014 I Dose Received By A Hypothetical Maximum Exposed Member of the Public Inside the Site Boundary During 2014 The following is a summary of the dose received by a hypothetical maximum exposed fisherman from liquid and gaseous effluents released from NMP1 during 2014:

TABLE 1 Exposure Pathway Annual Dose Exposure Pathway Dose Type Fmrma (mrem)

External Ground Whole Body 1.65 E-03 Skin of Whole Body 1.92 E-03 Whole Body 6.51 E-04 Inhalation Maximum Organ Bone: 1.58 E-03 Thyroid 6.50 E-04 Direct Radiation Whole Body 0.47 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:

TABLE 2 Annual Dose Summary Total Annual Dose for 2014 Fisherman (mrem)

Total Whole Body 4.75 E-01 Skin of Whole Body 1.92 E-03 Maximum Organ Bone: 1.58 E-03 Thyroid 6.50 E-04 Nine Mile Point Nuclear Station, LLC May 1, 2015

6 ATTACHMENT 11 Page 1 of 5 Unit 1 X Unit 2 Reporting Period: January - December 2014 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 2014 for comparison against the 40 CFR 190 annual dose limits.

The intent of 40 CFR 190 requires that the effluents of Nine Mile Point Unit 1 (NMP1), as well as other nearby uranium fuel cycle facilities, be considered. In this case, the effluents of NMP1, Nine Mile Point Unit 2 (NMP2) and the James A. FitzPatrick Nuclear Power Plant (JAFNPP) facilities must be considered.

40 CFR 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:

S< 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 NMP 1, 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 Public, outside the site boundary, is received through the following pathways:

• 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 NMP1, NMP2 and JAFNPP operating facilities.

• Direct Radiation pathway; radiation dose resulting from the operation ofNMPI, 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 NMP1 Off-Site Dose Calculation Manual (ODCM) as adapted from Regulatory Guide 1.109. The dose for 2014 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 2014; therefore, no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2014.

Nine Mile Point Nuclear Station, LLC May 1, 2015

ATTACHMENT 11 Page 2 of 5 Unit 1 X Unit 2 Reporting Period: January - December 2014 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 NMP I ODCM as adapted from Regulatory Guide 1.109. The dose for 2014 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 2014; therefore, no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2014.

For estimating C-14, dose received as a result of vegetation consumption is based on the methodology specified in the NMP 1 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 NMPI 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 2014; therefore no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2014.

Dose Pathways 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 NMP1 ODCM, NMP2 ODCM, and the JAFNPP ODCM. These calculations consider deposition, inhalation and ingestion pathways. The total sum of doses resulting from gaseous effluents from NMP1, NMP2 and JAFNPP during 2014 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 2014 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 2014 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 -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.

Nine Mile Point Nuclear Station, LLC May 1, 2015

ATTACHMENT 11 Page 3 of 5 Unit I X Unit 2 __Reporting Period: January - December 2014 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY For NMPI 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 a MWT/ 1000 [Eq 1]

Where:

5.1 = BWR Normalized Production (Ci/GWt-yr)

MWT MegaWatts 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.

A c-14 PRq4,y

• 0.99

• EFPD / 365, Ci (for timeperiod) [Eq 2]

Where:

PR " = maximum annual production rate of C-14 0.99 = fraction of C-14 in BWR gaseous pathway releases (maximum literature value in EPRI Report 1021106; also Table 1)

EFPD number of effective full power days for the unit during the time period; e.g., quarterly or yearly (Table 1) 365 number of days in a typical year Nine Mile Point Nuclear Station, LLC May 1, 2015

ATTACHMENT 11 Page 4 of 5 IUnit 1 X DOSES UnitTO 2 MEMBERS

__ Reporting Period: January - December 2014 I

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-14, Co2, into the gaseous pathway during the time period for each BWR unit.

A C-14, c02 = PR .fAv # 0.99 v 0.95

• EFPD / 365, Ci (for time period) [Eq 3]

Where:

PR ftX = maximum annual production rate of C-14 0.99 = fraction of C-14 in BWR gaseous pathway releases (maximum literature value in EPRI Report 1021106; also Table 1) 0.95 fraction of C-14 as carbon dioxide in BWR gaseous pathway releases (typical literature value in EPRI Report 1021106; also Table 1)

EFPD = number of effective full power days for the unit during the time period, e.g. quarterly or yearly (Table 1) 365 = conversion factor, 365 days in a typical average year For each BWR unit, the 2014 estimated C-14 activity releases (total and carbon dioxide chemical form) are summarized in Table 1.

Table 1 2014 BWR Estimated C-14 Gaseous Releases Gaseous CO 2 Form Max. Annual 2014 Total Release 2014 CO 2 Release BWR Release Release EFPD Operation Prod. Rate Fraction(b) (Eq 1)

Fraction(s) 363 EFPD NMP1 0.99 0.95 (99.4%) 9.44 Ci/yr 9.29 Ci 8.82 Ci 318 EFPD NMP2 0.99 0.95 (87.1%) 20.34 Ci/yr(c) 17.54 Ci 16.67 Ci JAFNPP 0.99 0.95 282 EFPD 10.84 Ci/yr 8.29 Ci 7.87 Ci (77.3%)

(a) Maximum literature values from EPRI Report 1021106.

(b) Typical value from EPRI Report 1021106.

(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.

Nine Mile Point Nuclear Station, LLC May 1, 2015

ATTACHMENT 11 Page 5 of 5 Unit 1 X DOSESUnitTO 2 MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES Reporting Period: THE OUTSIDE January SITE- BOUNDARY December 2014 I 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 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 2014, 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 2014 Exposure Pathway Dose Type Dose (mrem)

Fish and Vegetation Total Whole Body No Dose Consumption Total Maximum Organ No Dose Shoreline Sediment Total Whole Body No Dose Total Skin of Whole Body No Dose Total Whole Body 9.90 E-04 Gaseous Effluents Thyroid 6.21 E-03 (excluding C- 14)

Maximum Organ Thyroid: 6.21 E-03 Gaseous Effluent Total Whole Body 4.41 E-02 (C-14) Maximum Organ Bone: 2.20 E-01 Direct Radiation Total Whole Body 2.05 Based on these values the maximum total annual dose potentially received by the likely most exposed Member of the Public during 2014 is as follows:

• Total Whole Body: 2.09 E+00 mrem

" Total Thyroid: 6.21 E-03 mrem

" Maximum Organ: Bone: 2.21 E-01 mrem 40 CFR 190 Evaluation The maximum total doses presented in this attachment are the result of operations at the NMPI, NMP2 and the JAFNPP facilities. The maximum organ dose (Bone: 0.221 mrem), maximum thyroid dose (0.006 mrem) and the maximum whole body dose (2.09 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.

Nine Mile Point Nuclear Station, LLC May 1, 2015

ATTACHMENT 12 Page 1 of 1 1

Unit 1 X Unit 2 __ Reporting Period: January- December 2014 GROUNDWATER PROTECTION PROGRAM TRITIUM RESULTS

SUMMARY

I Well Identification # Samples Minimum Maximum Number Collected Concentration (pCi/I) Concentration (pCi/I)

GMX-MW1* 4 0 <404 <493 MW-B119* 4 0 <404 <493 MW-1 4 0 <404 <493 MW-4 4 0 <404 <493 MW-6 4 0 <404 <493 MW-7 4 0 <404 <493 MW-8 4 0 <404 <493 1

MW-9 4 0 <404 <493 MW-101 4 0 <404 <493 MW-11 4 0 <404 <493 MW-12 4 0 <404 <493 MW-13 4 0 <404 <493 MW-14* 4 0 <404 <493 MW-15 4 0 <404 <493 MW-16 4 0 <404 <493 MW-17 4 0 <376 <493 MW-18 4 0 <404 <493 MW-19 4 0 <404 <493 MW-20 4 0 <404 <493 MW-21 4 0 <404 <493 NMP2 MAT 23 4 0 <368 <488 Notes: *- Control Location 1 _Sentinel well location 2_ NMP2 Groundwater Depression Cone

- Samples collected from storm drain system which includes precipitation Nine Mile Point Nuclear Station, LLC May 1, 2015

ATTACHMENT 13 Page 1 of 1 Unit I X Unit 2 Reporting Period January - December 2014 Off-Site Dose Calculation Manual (ODCM)

There was no revision to the Off-Site Dose Calculation Manual for 2014.

Nine Mile Point Nuclear Station, LLC May 1, 2015

ATTACHMENT 14 Page 1 of 1 Unit 1 X Unit 2 Reporting Period January - December 2014 Process Control Program (PCP)

There were no changes to the Process Control Program in 2014.

Nine Mile Point Nuclear Station, LLC May 1, 2015

Enclosure 2 Nine Mile Point Nuclear Station, Unit 2 Radioactive Effluent Release Report, January - December 2014

NINE MILE POINT NUCLEAR STATION - UNIT 2 RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2014 SUPPLEMENTAL INFORMATION Facijiy: Nine Mile Point Unit 2 LL t-.Nine Mile Point Nuclear Station, LLC

1. TECHNICAL SPECIFICATION LIMITS/ODCM lTimits A. FISSION AND ACTIVATION GASES

1. The dose rate limit of noble gases released in gaseous effluents 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 I 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 10 milliroentgen for gamma radiation and less than or equal to 20 mrad for beta radiation.

B. IODINES

1. The dose rate 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 and 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 1 to areas at and 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.

C. TRITIUM AND PARTICULATES, HALF LIVES> 8 DAYS

1. The dose rate limit of Iodine-13 1, 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 and beyond the site boundary shall be less than or equal to 1500 mremryear 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 1 to areas at and 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.

Nine Mile Point Nuclear Station, LLC May 1, 2015

D. LIQUID EFFLUENTS I. 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 commitment 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 mrem to any organ, and during any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

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 determined by on-line gross activity monitoring (calibrated against gamma isotopic analysis of a 4.OL 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 purge and weekly when fuel 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 estimated by applying scaling factors to release rates of gamma emitters and actual release rates are determined from post off site 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.

Nine Mile Point Nuclear Station, LLC May 1, 2015

F. LIQUID EFFLUENTS Isotopic contents of liquid effluents are determined 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 of Sr-89, Sr-90, and Fe-55 are estimated by applying scaling factors to. release rates of gamma emitters and actual release rates are determined from post off site analysis results.

G. SOLID EFFLUENTS Isotopic contents of waste shipments are determined 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 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 ofjoint 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 of required meteorological data on site in a file that shall be provided to the NRC upon request.

Nine Mile Point Nuclear Station, LLC May 1, 2015

Supplemental Information ATTACHMENT 1 Page 1 of 2

SUMMARY

DATA Unit I Unit 2 X Reporting Period January - December 2014 Liquid Effluents:

ODCM Required Maximum Effluent Concentration (MEC) = 10 x 10CFR20.1001 - 20.2402, Appendix B, Table 2, Column 2 Average MEC - pCi/ml (Qtr. 1)= NO RELEASE Average MEC - pCi/ml (Qtr. 3) = NO RELEASES Average MEC - pCi/mI (Qtr.. 2) = [ .OO-oLJ Average MEC - pCi/mI (Qtr. 4) = NO REEASES Average Energy (Fission and Activation gases - MEV):

Qrtr. 1: Ey = 7.57E-01 EP = 2.94E-01 Qrtr. 2: Ey = 1.59E-01 E3 = 2.53E-01 Qrtr._3: Ey = N/A Ep = N/A Qrtr. 4: Ey = N/A Ep = N/A Liquid:

Number of Batch Releases 1 Total Time Period for Batch Releases (hrs) 888.0 Maximum Time Period for a Batch Release (hrs) 888.0 Average Time Perod for a Batch Release (hrs) 888.0 Minimum Time Period for a Batch Release 888.0 Total volume of water used to dilute the liquid I 1st 2nd 3rd 4th during the release period (L) N/A 4.73E+09 N/A N/A lTotal volume of water available to dilute the liquid ist 2nd 3rd 4th effluent during the report period (L) 1.24E+10 1.27E+10 1.36E+10 1.23E+1 0 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 13 Total Time Period for Batch Releases (hrs) 72.4 Maximum Time Period for a Batch Release (hrs) 6.0 Average Time Period for a Batch Release (hrs) 5.6 Minimum Time Period for a Batch Release (hrs) 2.8 Nine Mile Point Nuclear Station, LLC May 1, 2015

Supplemental Information ATTACHMENT 1 Page 2 of 2

SUMMARY

DATA Unit 1 Unit 2 X Reporting Period January - December 2014 Abnormal Releases:

A. Liquids:

Number of Releases 1 ITotal Activity Released 2.24E-04 Ci B. Gaseous:

INumber of Releases 0 Total Activity Released N/A Ci Nine Mile Point Nuclear Station, LLC May 1, 2015

Table 1A Gaseous Effluents - ATTACHMENT 2 Page 1 of 1 Summation of All Releases -

Elevated and Ground Level Unit I Unit 2 X Reporting Period January - December 2014 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 I. Total Release Ci 8.88E+00 4.89E-01 0.OOE+00 0.OOE+00 5.OOE+01

2. Average Release Rate pCi/sec 1.14E+00 6.22E-02 0.OOE+00 0.OOE+00 B. lodines

1. Total Iodine - 131 Ci 5.33E-04 5.27E-05 3.22E-05 1.57E-04 3.OOE+01

2. Average Release Rate for Period pCi/sec 6.78E-05 6.70E-06 4.10E-06 2.OOE-05 C. Particulates

1. Particulates with Half-lives>8days Ci 5.49E-04 6.24E-04 2.60E-04 2.06E-04 3.OOE+01

2. Average Release Rate for Period pCi/sec 6.98E-05 7.94E-05 3.31 E-05 2.62E-05

3. Gross Alpha Radioactivity Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.50E+01 D. Tritium

1. Total Release Ci 9.87E+00 5.75E+00 1-29-E-+01 -T9*91E+001 5.OOE+01

2. Average Release Rate for Period pCi/sec 1.26E+00 7.32E-01 1.64E+00 1.26E+00 E. Percent of Tech. Spec. Limits Fission and Activation Gases Percent of Quarterly Gamma Air Dose Limit 1.54E-02 1.58E-04 0.OOE+00 0.OOE+00 (5 mR)

Percent of Quarterly Beta Air Dose Limit (10 2.90E-04 1.37E-05 0.OOE+00 0.OOE+00 mrad)

Percent of Annual Gamma Air Dose Limit to 7.72E-03 7.80E-03 7.80E-03 7.80E-03 Date (10 mR)

Percent of Annual Beta Air Dose Limit to 1.45E-04 1.52E-04 1.52E-04 1.52E-04 Date (20 mrad)

Percent of Whole Body Dose Rate Limit (500 6.12E-04 9.76E-06 0.OOE+00 0.OOE+00 mrem/yr)

Percent of Skin Dose Rate Limit (3000 1.19E-04 1.30E-06 0.OOE+00 0.OOE+00 mrem/yr)

Tritium, lodines. and Particulates (with half-lives qreater than 8 days)

Percent of Quarterly Dose Limit (7.5 mrem) 1.53E-01 2.35E-02 1.80E-02 2.97E-02 Percent of Annual Dose Limit to Date (15 7.67E-02 8.84E-02 9.74E-02 1.12E-01 mrem)

Percent of Organ Dose Limit (1500 mrem/yr 3.11E-03 4.70E-04 3.57E-04 6.02E-04 Nine Mile Point Nuclear Station, LLC May 1, 2015

Table 1B Gaseous ATTACHMENT 3 Page 1 of 2 Effluents - Elevated Releases unit I Unit 2 X Reporting Period January - December 2014 GASEOUS EFFLUENTS - ELEVATED RELEASE Continuous Mode (2)

Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Fission Gases (1)

Argon-41 Ci Krypton-85 Ci Krypton-85m Ci 5.92E+00 4.89E-01 ....

Krypton-87 Ci Krypton-88 Ci 2.96E+00 ..

Xenon-127 Ci Xenon-131m Ci Xenon-1 33 Ci Xenon-133m Ci Xenon-135 Ci Xenon-1 35m Xenon-137 Ci Ci

• • I ** I ** i **

Xenon-I38 Ci lodines (1)

Iodine-131 Ci 4.96E-04 5.02E-05 [ 2.36E-05 j 9.26E-05 Iodine-133 Ci 9.11E-03 3.15E-04 4.51E-04 1.06E-03 Iodine-135 Ci Particulates (1)

Chromium-51 Ci Manganese-54 Ci 1.18E-04 1.75E-05 4.29E-06 1.17E-06 1i.02E-05 **

Iron-55 Ci Iron-59 Ci Cobalt-58 Ci Cobalt-60 Ci i1.27E-05 8.77E-05 3.90E-05 4.06E-05 Neodymium-147 Ci Zinc-65 Ci Strontium-89 Ci Strontium-90 Ci Niobium-95 Ci Zirconium-95 Ci Molybdenum-99 Ci S.04E-06** ** **

Ruthenium-1 03 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 8.03E00 3.89E+00 5.12E+00 8.15E+00::]

(i) 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 pCi/ml for required noble gases, 1.OOE-1 1 pCi/ml for required particulates and gross alpha, 1.OOE-12 pCi/ml for required lodines, 1.OOE-1 1 pCi/ml for Sr-89/90 and 1.OOE-06 pCi/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.

Nine Mile Point Nuclear Station, LLC May 1, 2015

ATTACHMENT 3 Page 2 of 2 Unit I Unit 2 X Reporting Period January - December 2014 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-88 Ci Xenon-1 27 Ci Xenon-1 31 m Ci Xenon-1 33 Ci Xenon-133m Ci Xenon-135 Ci Xenon-135m Ci Xenon-1 37 Ci Xenon-1 38 Ci lodines (1)

T Iodine-131 Iodine-133 Iodine-135 Ci Ci Ci

_________________ I 1

Particulates (1)

Chromium-51 Manganese-54 Iron-55 Iron-59 Cobalt-58 Cobalt-60 Neodymium-147 Zinc-65 Strontium-89 Stronium-90 Niobium-95 Zirconium-95 Molybdenum-99 Ruthenium-103 Cesium-134 Cesium-136 Cesium-137 Barium-140 Lanthanum-140 Cerium-141 Cerium-144 Tritium (11 Ci (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.OOE-04 pCi/ml for required noble gases, 1.OOE-1 1 pCi/ml for required particulates and gross alpha, 1.OOE-12 pCi/ml for required lodines, 1.00E-11 pCi/ml for Sr-89/90 and 1.OOE-06 pCi/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.

Nine Mile Point Nuclear Station, LLC May 1, 2015

Table 1C ATTACHMENT 4 Page 1 of 2 Unit I Unit 2 X Reporting Period January - December 2014 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous 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-88 Ci Xenon-127 Ci Xenon-131m Ci Xenon-133 Ci Xenon-1 33m Xenon-135 Ci Ci

• • ** I ** I **

Xenon-135m Ci Xenon-137 Ci Xenon-1 38 Ci lodines (1)

Iodine-131 Ci 3.65E-05 2.48E-06 f8.62E-06 6.45E-05 Iodine-133 Ci 5.39E-04 3.45E-05 I _____I4.91iE-05 Iodine-135 Ci Particulates (11 Chromium-51 Ci Manganese-54 Ci .65E-05 3.87E-0 .60E-05 **

Iron-55 Ci 1.87E-04 1.35E-04 5.90E-05 Iron-59 Ci Cobalt-58 Ci i1.3i1E-06 i1.40E-06 i1.26E-06 7.6E0 2.70E-06 I*77E00 Cobalt-60 Ci i1.72E-04 3.1i0E-04 2.00E-04 i1.03E-04 Neodymium-147 Ci Zinc-65 Ci 7.85E-06 2.34E-0 ** **

Strontium-89 Ci Strontium-90 Ci Niobium-95 Ci S.46E-06** **

Zirconium-95 Ci Molybdenum-99 Ci Ruthenium-103 Ci Cesium-134 Ci 3.7E-0 ** **

Cesium-136 Ci Cesium-137 Ci Barium-140 Ci Lanthanum-140 Ci Cerium-141 Ci Cerium-144 Ci Tritium (1) Ci 1.84E+00 I.86E+00 i77E+00 I.6E0 (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.OOE-04 pCi/ml for required noble gases, 1.OOE-11 pCi/ml for required particulates and gross alpha, 1.OOE-12 pCi/ml for required iodines, 1.00E -

11 pCi/ml for Sr-89/90 and 1.OOE-06 pCi/ml for Tritium, as required by the ODCM, has been verified.

(2) There were no batch releases from this path during the reporting period.

Nine Mile Point Nuclear Station, LLC May 1, 2015

Table 1C ATTACHMENT 4 Page 2 of 2 Unit I Unit 2 X Reporting Period January - December 2014 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Batch Mode Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 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 3** 3* **31

• Xe-138 Ci lodines (1) 1-131 Ci 1-132 Ci 1-133 Ci Particulates (1)

Cr-51 Ci 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 (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double **.

Nine Mile Point Nuclear Station, LLC May 1, 2015

Table 2A ATTACHMENT 5 Page 1 of 2 Unit I Unit 2 X Reporting Period January - December 2014 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES (1) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Est. Total Error, %

A. Fission & Activation Products

1. Total Release (not including Tritium, gases, alpha)

Ci No Releases 2.24E-04 No Releases No Releases 5.00E+011

2. Average diluted concentration during pCi/ml No Releases 1.77E-1 1 No Releases No Releases reporting period B. Tritium 1.Total release Ci No Releases

• No Releases No Releases 5.O0E+01

2. Average diluted concentration during the pCi/ml No Releases ** No Releases No Releases reporting period C. Dissolved and Entrained Gases

1. Total release Ci No Releases ** No Releases No Releases 5.OOE+01

2. Average diluted concentration during the pCi/mI No Releases ** No Releases No Releases reporting period D. Gross Alpha Radioactivity

1. Total release Ci ENo Releases _ No ReleasesjNo eleases] 5.00E+01 E. Volumes

1. Prior to Dilution Liters No Releases 5.10E+06 No Releases No Releases 5.OOE+01

2. Volume of dilution water used during release period Liters No Releases 4.73E+09 No Releases No Releases 5.OOE+01

3. Volume of dilution water available during Liters 1.24E+10 1.27E+10 1.36E+10 1.23E+10 5.00E+01 reporting period F. Percent of Tech. Spec. Limits Percent of Quarterly Whole Body Dose Limit 0.00E+00 4.65E-04 0.00E+00 0.00E+00 (1.5 mrem)

Percent of Annual Whole Body Dose Limit to 0.00E+00 2.32E-04 0.OOE+00 0.00E+00 Date (3 mrem)

Percent of Quarterly Organ Dose Limit (5 0.00E+00 7.28E-04 0.00E+00 0.00E+00 mrem)

Percent of Annual Organ Dose Limit to Date 0.00E+00 3.64E-04 0.00E+00 0.00E+00 (10 mrem)

Percent of 10CFR20 Concentration Limit (2),

0.00E+00 5.89E-05 0.OOE+00 0.OOE+00 (3)

Percent of Dissolved or Entrained Noble Gas 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 Limit (2.OOE-04 pCi/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 pCi/mI for required gamma emitting nuclides, 1.OOE-05 pCi/mI for required dissolved and entrained noble gases and tritium, 5.00E-08 pCi/mI for Sr-89/90, 1.00E-06 pCi/ml for 1-131 and Fe-55, and 1.00E-07 pCi/ml for gross alpha radioactivity, as required by the Off-Site Dose Calculation Manual (ODCM), has been verified.

(2) The percent of 10CFR20 concentration limit is based on the average concentration during the quarter.

(3) Improved Technical Specifications 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 the 10CFR20.1001 - 20.2402 concentrations were adopted to evaluate liquid effluents.

Nine Mile Point Nuclear Station, LLC May 1, 2015

Table 2B ATTACHMENT 5 Page 2 of 2 Unit 1 Unit 2 X Reporting Period January - December 2014 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 Strontium-90 Ci No Releases ** No Releases No Releases Cesium-134 Ci No Releases No Releases No Releases Cesium-137 Ci No Releases No Releases No Releases Iodine-131 Ci No Releases No Releases No Releases Cobalt-58 Ci No Releases No Releases No Releases Cobalt-60 Ci No Releases 2.24E-04 No Releases No Releases Iron-59 Ci No Releases ** No Releases No Releases Zinc-65 Ci No Releases ** No Releases No Releases Manganese-54 Ci No Releases ** No Releases No Releases Chromium-51 Ci No Releases ** No Releases No Releases Zirconium-95 Ci No Releases ** No Releases No Releases Niobium-95 Ci No Releases ** No Releases No Releases Molybdenum-99 Ci No Releases No Releases No Releases Technetium-99m Ci No Releases ** No Releases No Releases Barium-140 Ci No Releases No Releases No Releases Lanthanum-140 Ci No Releases ** No Releases No Releases No Releases ** No Releases No Releases Cerium-141 Ci No Releases ** No Releases No Releases Tungsten-187 Ci No Releases No Releases No Releases Arsenic-76 Ci No Releases No Releases No Releases Iodine-133 Ci No Releases No Releases No Releases Iron-55 Ci No Releases No Releases No Releases Neptunium-239 Ci No Releases No Releases No Releases Silver-11 Om Ci No Releases ** No Releases No Releases Gold-199 Ci No Releases ** No Releases No Releases Cerium-144 Ci No Releases No Releases No Releases Cesium-136 Ci No Releases ** No Releases No Releases Copper-64 Ci No Releases No Releases No Releases Dissolved or Entrained Gases Ci Tritium Ci No Releases ** NO Releases I No Releases (1) No continuous 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.OOE-07 pCi/ml for required gamma emitting nuclides, 1.OOE-05 pCi/ml for required dissolved and entrained noble gases and tritium, 5.OOE-08 pCi/ml for Sr-89/90, 1.OOE-06 pCi/ml for 1-131 and Fe-55, and 1.OOE-07 pCi/ml for gross alpha radioactivity, as identified in the ODCM, has been verified.

Nine Mile Point Nuclear Station, LLC May 1, 2015

Table 3 ATTACHMENT 6 Page 1 of 4 Unit I Unit 2 X Reporting Period January - December 2014 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Ai. TYPE Volume Activity 01)

(mi) (Ci)

Class Class A B C A B C a.1 Spent Resins 7.51E+01 O.0OE+00 O.OOE+00 2.64E+02 O.OOE+00 O.OOE+00 (Dewatered) a.2 Filter Sludge O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 a.3 Concentrated Waste O.OOE+0O O.OOE+00 O.OOE+00 O.O0E+00 O.OOE+00 O.OOE+00 Totals 7.51 E+01 O.OOE+00 O.OOE+00 2.64E+02 O.OOE+00 O.OOE+00 b.1 Dry, compressible waste 8.66E+02 O.OOE+00 O.OOE+00 1.72E+00 O.OOE+00 O.OOE+00 b.2 Dry, non-compressible O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 waste (contaminated equipment)

Totals 8.66E+02 O.OOE+00 O.OOE+00 1.72E+00 O.OOE+00 O.OOE+00

c. Irradiated Components, O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Control Rods

d. Other (to vendor for processing) d.1 Oilywaste 1.42E+01 O.0OE+00 O.OOE+00 1.62E-02 O.OOE+00 O.OOE+00 (1) The estimated total error is 5.OOE+01%.

Nine Mile Point Nuclear Station, LLC May 1, 2015

Table 3 ATTACHMENT 6 Page 2 of 4 Unit 1 Unit 2 X Reporting Period January - December 2014 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Al. TYPE Container Packaae Solidification Aaent a.1 Spent Resin (Dewatered) Poly Liner General Design None a.2 Filter Sludge N/A N/A N/A b.1 Dry Compressible Waste Seavan General Design None b.2 Dry, Non-Compressible N/A N/A N/A Waste

c. Irradiated Components, N/A N/A N/A Control Rods

d. Other (to vendor for processing) d.1 Oily waste

_ 55 gallon drums General Design None Nine Mile Point Nuclear Station, LLC May 1, 2015

Table 3 ATTACHMENT 6 Page 3 of 4 Unit I Unit 2 X Reporting Period January - December 2014 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 Mn-54 5.59% 1.48E+01 Fe-55 57.36% 1.52E+02 Co-60 33.20% 8.78E+01 Zn-65 2.60% 6.88E+00

b. Dry, compressible waste, dry, non-compressible waste (contaminated equipment)

Nuclide Percent Curies Cr_51 2.22% 3.82E-02 Mn-54 4.87% 8.37E-02 Fe-55 63.23% 1.09E+00 Fe-59 1.03% 1.78E-02 Co-60 24.61% 4.23E-01 Zn-65 1.35% 2.33E-02

c. Irradiated Components, Control Rods: There were no shipments.

Nuclide Percent N/A N/A

d. Other (To Vendor for Processing) 1, Oily Drums shipped in Pan Seavan Nuclide Percent Curies Cr-51 2.23% 3.67E-04 Mn-54 4.90% 8.05E-04 Fe-55 63.22% 1.04E-04 Fe-59 1.03% 1.70E-04 Co-60 24.51% 4.03E-03 Zn-65  !.37% 2.25E-04 Nine Mile Point Nuclear Station, LLC May 1, 2015

Table 3 ATTACHMENT 6 Page 4 of 4 Unit 1 Unit 2 X Reporting Period January - December 2014 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A3. SOLID WASTE DISPOSITION Number of Shipments Mode of Transportation Destination 6 Hittman Transport Bamwell Processing Facility 19 Hittman Transport Energy Solutions Services (CVRF) 3 Hittman Transport Energy Solutions LLC (Clive) 1 Hittman Transport Toxco, Inc 2 Hittman Transport Bamwell Processing Facility 5 Hittman Transport Energy Solutions Services (CVRF)

B. IRRADIATED FUEL SHIPMENTS (Disposition): There were no shipments.

Number of Shipments Mode of Transportation Destination 0 N/A N/A D. SEWAGE WASTES SHIPPED TO A TREATMENT FACILITY FOR PROCESSING AND BURIAL There were no shipments of sewage sludge with detectable quantities of plant-related nuclides from NMP to the treatment facility during the reporting period.

Nine Mile Point Nuclear Station, LLC May 1, 2015

ATTACHMENT 7 Page 1 of 1 Unit I Unit 2 X Reporting Period January - December 2014

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 1* I I 1* I I 1~ I I 1* I I Nine Mile Point Nuclear Station, LLC May 1, 2015

ATTACHMENT 8 Page 1 of 1 Unit 1 Unit 2 X Reporting Period January - December 2014

SUMMARY

OF CHANGES TO THE PROCESS CONTROL PROGRAM (PCP)

There were no changes to the NMP2 Process Control Program (PCP) during the reporting period.

Nine Mile Point Nuclear Station, LLC May 1, 2015

ATTACHMENT 9 Page 1 of 1 Unit 1 Unit 2 X Reporting Period January - December 2014

SUMMARY

OF NON-FUNCTIONAL MONITORS Monitor Dates Monitor was Cause and Corrective Actions Non-Functional 2LWS-CAB206, January 1, 2014 to No liquid waste discharges were performed during 2014, and therefore, these 2LWS-FT330 & December 31, 2014 monitors were not returned to service. The discharge manual isolation valves, 2LWS-FT331, 2LWS-V420 and 2LWS-V422, are locked closed during inoperable periods, Liquid Waste therefore, no inadvertent discharge can occur. Reference Equipment Status Discharge Monitor Log (ESL) 2010-0243.

2OFG-AT115, Offgas 2/22/14 - 5/2/14 Monitor failed downscale, no cause was identified. Instrument passed next Common Hydrogen surveillance test.

Monitor No action required with 2OFG-AT16A, Offgas Train A Hydrogen Monitor &

2OFG-AT16B, Offgas Train B Hydrogen Monitor FUNCTIONAL.

ATTACHMENT 10 Page 1 of 5 IUnit 1 Unit 2 X Reporting Period: January - December 2014 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 2014.

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, 200 1, 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 2014 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 ground (shoreline sediment or soil doses). Other pathways, such as ingestion pathways, are not considered because 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 NMIP 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 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 I (NMP 1), 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.

Nine Mile Point Nuclear Station, LLC May 1, 2015

ATTACHMENT 10 Page 2 of 5 IUnit 1 DOSES TO2 MEMBERS Unit X OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE Reporting THEJanuary Period: SITE BOUNDARY

- December 2014 The total dose received by the whole body and skin of the maximum exposed individual during 2014 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 = 1.05E-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 2014 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:

NMP2 Stack:

Variable Fisherman X/Q (s/m3) 9.6 E-07 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) 7.07 E+05 C-14 (pCi/sec) 2 5.90 E+05 Mn-54 (pCi/sec) 9.96 E-01 Fe-55 (pCi/sec) 4.82 E-01 Co-60 (pCI/sec) 6.93 E+00 1-131 (pCi/sec) 7.76 E+00 1-133 (pCi/sec) 8.62 E+0l Nine Mile Point Nuclear Station, LLC May 1, 2015

ATTACHMENT 10 Page 3 of 5 Unit 1 -DOSES TO2 MEMBERS Unit X OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE Reporting Period:THE SITE BOUNDARY January - December 2014 I NMP2 Radwaste/ReactorBuilding Vent:

Variable Fisherman X/Q (s/m3) 2.8 E-06 Inhalation dose factor Table E-7, Regulatory Guide 1.109 3 8000 Annual air intake (m /year) (adult)

Fractional portion of the year 0.0356 H-3 (pCi/sec) 4.83 E+05 Mn-54 (pCi/sec) 2.32 E+00 Fe-55 (pCi/sec) 8.22 E+00 Co-58 (pCi/sec) 2.27 E-01 Co-60 (pCi/sec) 2.60 E+01 Zn-65 (pCi/sec) 9.91 E-01 1-131 (pCi/sec) 6.38 E-01 1-133 (pCi/sec) 6.11 E+00

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.

Nine Mile Point Nuclear Station, LLC May 1, 2015

ATTACHMENT 10 Page 4 of 5 IUnit 1 Unit 2 X Reporting Period: January - December 2014 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY I 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 submersion. The direct radiation pathway is evaluated by the use of high sensitivity environmental Thermoluminescent Dosimeters (TLDs). Since fishing activities occur between April 1 and December 31, TLD data for the second, third, and fourth quarters of 2014 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) 5.47 E-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.

Dose Received By A Hypothetical Maximum Exposed Member of the Public Inside the Site Boundary Durin2 2014 The following is a summary of the dose received by a hypothetical maximum exposed fisherman from liquid and gaseous effluents released from NMP2 during 2014:

TABLE 1 Exposure Pathway Annual Dose Fisherman Exposure Pathway Dose Type (mrem)

External Ground Whole Body 1.65 E-03 Skin of Whole Body 1.92 E-03 Whole Body 1.60 E-04 Inhalation Maximum Organ Bone: 3.66 E-04 Thyroid 1.72 E-04 Direct Radiation Whole Body 0.47 Nine Mile Point Nuclear Station, LLC May 1, 2015

ATTACHMENT 10 Page 5 of 5 Unit 1 Unit 2 X Reporting Period: January - December 2014 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY 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:

TABLE 2 Annual Dose Summary Fisherman Total Annual Dose for 2014 (mrem)

Total Whole Body 4.75 E-01 Skin of Whole Body 1.92 E-03 Maximum Organ Bone: 3.66 E-04 Thyroid 1.72 E-04 Nine Mile Point Nuclear Station, LLC May 1, 2015

ATTACHMENT 11 Page 1 of 5 Unit 1 Unit 2 X Reporting Period: January - December 2014 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 2014 for comparison against the 40 CFR 190 annual dose limits.

The intent of 40 CFR 190 requires that the effluents of Nine Mile Point Unit 1 (NMP 1), as well as other nearby uranium fuel cycle facilities, be considered. In this case, the effluents of NMP1, Nine Mile Point Unit 2 (NMP2) and the James A. FitzPatrick Nuclear Power Plant (JAFNPP) facilities must be considered.

40 CFR 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:

0 < 25 mRem whole body

• < 25 mRem any organ (except thyroid)

S< 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 NMP 1, 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 Public, outside the site boundary, is received through the following pathways:

• 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 NMP1, NMP2 and JAFNPP operating facilities.

" Direct Radiation pathway; radiation dose resulting from the operation of NMP I, 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 2014 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 2014; therefore, no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2014.

Nine Mile Point Nuclear Station, LLC May 1, 2015

ATTACHMENT 11 Page 2 of 5 Unit 1 Unit 2 X Reporting Period: January- December 2014 DOSES TO MEMBE RS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY I Vegetation Consumption Dose received as a result of vegetation consumption is based on the methodology specified in the NMPI ODCM as adapted from Regulatory Guide 1.109. The dose for 2014 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 2014; therefore, no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2014.

For estimating C-14, dose received as a result of vegetation consumption is based on the methodology specified in the NMP1 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 NMP1 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 2014; therefore no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2014.

Dose Pathways 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 NMP 1 ODCM, NMP2 ODCM, and the JAFNPP ODCM. These calculations consider deposition, inhalation and ingestion pathways. The total sum of doses resulting from gaseous effluents from NMP1, NMP2 and JAFNPP during 2014 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 2014 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 2014 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 -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.

Nine Mile Point Nuclear Station, LLC May 1, 2015

ATTACHMENT 11 Page 3 of 5 Unit 1 Unit 2 X Reporting Period: January - December 2014 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY I

For NMP1 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 I estimates the maximum annual production of C-14, PRMAx, for each BWR unit.

PRMAx = 5.1 v MWT / 1000 [Eq 1]

Where:

5.1 = BWR Normalized Production (Ci/GWt-yr)

MWT = MegaWatts 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.

A c-14 PR lf4v o 0.99 a EFPD / 365, Ci (for time period) [Eq 2]

Where:

PR MAt = maximum annual production rate of C-14 0.99 = fraction of C-14 in BWR gaseous pathway releases (maximum literature value in EPRI Report 1021106; also Table 1)

EFPD number of effective full power days for the unit during the time period; e.g., quarterly or yearly (Table 1) 365 number of days in a typical year Nine Mile Point Nuclear Station, LLC May 1, 2015

ATTACHMENT 11 Page 4 of 5 Unit 1 Unit 2 X Reporting Period: January- December 2014 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.14. Co2, into the gaseous pathway during the time period for each BWR unit.

A C-14, C02 = PR m{Y

• 0.99

• 0.95 v EFPD / 365, Ci (for time period) [Eq 3]

Where:

PR MfA = maximum annual production rate of C-14 0.99 fraction of C-14 in BWR gaseous pathway releases (maximum literature value in EPRI Report 1021106; also Table 1) 0.95 fraction of C-14 as carbon dioxide in BWR gaseous pathway releases (typical literature value in EPRI Report 1021106; also Table 1)

EFPD number of effective full power days for the unit during the time period, e.g. quarterly or yearly (Table 1) 365 conversion factor, 365 days in a typical average year For each BWR unit, the 2014 estimated C-14 activity releases (total and carbon dioxide chemical form) are summarized in Table 1.

Table 1 2014 BWR Estimated C-14 Gaseous Releases Gaseous C0 2 Form Max. Annual 2014 Total Release 2014 CO 2 Release BWR Release Release EFPD Operation Prod. Rate Fraction(a) Fraction(b) (Eq I) 363 EFPD NMP1 0.99 0.95 (99.4%) 9.44 Ci/yr 9.29 Ci 8.82 Ci 318 EFPD NMP2 0.99 0.95 (87.1%) 20.34 Ci/yr(c) 17.54 Ci 16.67 Ci JAFNPP 0.99 0.95 282 EFPD 10.84 Ci/yr 8.29 Ci 7.87 Ci (77.3%)

(a) Maximum literature values from EPRI Report 1021106.

(b) Typical value from EPRI Report 1021106.

(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.

Nine Mile Point Nuclear Station, LLC May 1, 2015

ATTACHMENT 11 Page 5 of 5 Unit 1 Unit 2 X Reporting Period: January - December 2014 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY I 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 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 2014, 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 2014 Exposure Pathway Dose Type Dose (mrem)

Fish and Vegetation Total Whole Body No Dose Consumption Total Maximum Organ No Dose Shoreline Sediment Total Whole Body No Dose Total Skin of Whole Body No Dose Total Whole Body 9.90 E-04 Gaseous Effluents Thyroid 6.21 E-03 (excluding C- 14)

Maximum Organ Thyroid: 6.21 E-03 Gaseous Effluent Total Whole Body 4.41 E-02 (C-14) Maximum Organ Bone: 2.20 E-01 Direct Radiation Total Whole Body 2.05 Based on these values the maximum total annual dose potentially received by the likely most exposed Member of the Public during 2014 is as follows:

" Total Whole Body: 2.09 E+00 mrem

" Total Thyroid: 6.21 E-03 mrem

• Maximum Organ: Bone: 2.21 E-01 mrem 40 CFR 190 Evaluation The maximum total doses presented in this attachment are the result of operations at the NMP1, NMP2 and the JAFNPP facilities. The maximum organ dose (Bone: 0.221 mrem), maximum thyroid dose (0.006 mrem) and the maximum whole body dose (2.09 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.

Nine Mile Point Nuclear Station, LLC May 1, 2015

ATTACHMENT 12 Page 1 of I 1

Unit 1 Unit 2 X Reporting Period: January - December 2014 GROUNDWATER PROTECTION PROGRAM TRITIUM RESULTS

SUMMARY

I Well Identification # Samples # Positive Samples Minimum Maximum Number Collected Concentration (pCi/I) Concentration (pCi/I)

GMX-MWl* 4 0 <404 <493 MW-B119* 4 0 <404 <493 MW-1 4 0 <404 <493 MW-4 4 0 <404 <493 MW-6 4 0 <404 <493 MW-7 4 0 <404 <493 MW-8 4 0 <404 <493 MW-9' 4 0 <404 <493 MW-101 4 0 <404 <493 MW-11 4 0 <404 <493 MW-12 4 0 <404 <493 MW-13 4 0 <404 <493 MW-14* 4 0 <404 <493 MW-15 4 0 <404 <493 MW-16 4 0 <404 <493 MW-17 4 0 <376 <493 MW-18 4 0 <404 <493 MW-19 4 0 <404 <493 MW-20 4 0 <404 <493 MW-21 4 0 <404 <493 NMP2 MAT 23 4 0 <368 <488 Notes: *- Control Location

- Sentinel well location 2 _ NMP2 Groundwater Depression Cone 3 _ Samples collected from storm drain system which includes precipitation Nine Mile Point Nuclear Station, LLC May 1, 2015

ATTACHMENT 13 Page 1 of 1 Unit 1 Unit 2 X Reporting Period January - December 2014 Off-Site Dose Calculation Manual (ODCM)

There was no revision to the Off-Site Dose Calculation Manual for 2014.

Nine Mile Point Nuclear Station, LLC May 1, 2015

ATTACHMENT 14 Page 1 of 1 Unit 1 Unit 2 X Reporting Period January - December 2014 Process Control Proaram (PCP)

There were no changes to the Process Control Program in 2014.

Nine Mile Point Nuclear Station, LLC May 1, 2015