NMP1L3150, Independent Spent Fuel Storage Installation, Submittal of 2016 Radioactive Effluent Release Report

Independent Spent Fuel Storage Installation, Submittal of 2016 Radioactive Effluent Release Report

ML17128A029
Person / Time
Site:	Nine Mile Point, 07201036
Issue date:	04/28/2017
From:	Orphanos P Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
Shared Package
ML17128A020	List: ML17128A030 NMP1L3150, Independent Spent Fuel Storage Installation, Submittal of 2016 Radioactive Effluent Release Report
References
NMP1L3150
Download: ML17128A029 (67)

Text

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~* Exelon Generation 10 CFR 50.36a 10 CFR 72.44(d)(3)

Technical Specifications NMP1L 3150 April 28, 2017 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 N RC Docket Nos. 50-220 and 50-410 Independent Spent Fuel Storage Installation (ISFSI)

ISFSI Docket No. 72-1036

Subject:

2016 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 2016. This letter also satisfies the annual effluent reporting requirements for the ISFSI required by 10 CFR 72.44(d}(3).

The format used for the effluent data is outlined in Appendix B of Regulatory Guide 1.21, Revision 1. During the reporting period, NMP1, NMP2, and the ISFSI did not exceed any 10 CFR 20, 10 CFR 50, 10 CFR 72, 40 CFR 190, Technical Specification, or ODCM limits for gaseous or liquid effluents.

Should you have questions regarding the information in this submittal, please contact Morgan Cazzolli, Acting Site Chemistry Environmental & Radwaste Manager, at (315) 349-4188.

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

_J

Document Control Desk April 28, 2017 Page 2

Enclosures:

(1) Nine Mile Point Nuclear Station, Unit 1 Radioactive Effluent Release Report, January - December 2016 (2) Nine Mile Point Nuclear Station, Unit 2 Radioactive Effluent Release Report, January - December 2016 (3) Errata/Correction to the 2015 Annua.1 Radioactive Effluent Release Report Cc: NRC Regional Administrator, Region 1 NRC Project Manager NRC Resident Inspector R. Rolph, NRC

NINE MILE POINT NUCLEAR STATION - UNIT 1 RADIOACTIVE EFFLUENT RELEASE REPORT January- December 2016

Page 1 of2 NINE MILE POINT NUCLEAR STATION - UNIT 1 RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2016 SUPPLEMENTAL INFORMATION 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&C) TRITIUM, IODINES 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 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.

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.

Page 2 of2

2. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY Described below are the methods used to measure or approximate the total radioactivity and radionuclide composition in effluents.

A) FISSION AND ACTIVATION GASES Noble gas effluent activity is determined by on-line gross activity monitoring (calibrated against gamma isotopic analysis of a 4.0L Marinelli grab sample) of an isokinetic stack sample stream.

B) IODINES Iodine effluent activity is determined by gamma spectroscopic analysis (at least weekly) of charcoal cartridges sampled from an isokinetic stack sample stream.

C) PARTICULATES Activity released from the main stack is determined by gamma spectroscopic analysis (at least weekly) of particulate filters sampled from an isokinetic sample stream and composite analysis of the filters for non-gamma emitters.

D) TRITIUM Tritium effluent activity is measured by liquid scintillation or gas proportional counting of monthly samples taken with an air sparging/water trap apparatus. Tritium effluent activity is measured during 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 offsite analysis results. The activity of fission and activation gases released due to tube leaks is based on reactor steam leak rates using offgas isotopic analyses.

F) LIQUID EFFLUENTS Isotopic contents of liquid effluents are 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 offsite 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 ofC-14 and the effluent dose consequences are estimates based on EPRI methodology provided in EPRI Report 1021106, Estimation ofCarbon-14 in Nuclear Power Plant Gaseous EjJluents, December 2010 and NUREG-0016, Calculation of Releases of Radioactive Materials in Gaseous and Liquid EjJluents 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 ofretaining this summary ofrequired meteorological data on site in a file that shall be provided to the NRC upon request.

ATTACHMENT 1 Page 1of2 Unit 1 x Unit 2 Re~orting Period: Janua!l'.- December 2016 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 2016.

Average MEG - µCi/ml (Qtr.1) = I NO RELEASES I Average MEG - µCi/ml (Qtr. ~ = I NO RELEASES I Average MEC - µCi/ml (Qtr..l) = I NO RELEASES Average MEC - µCi/ml (Qtr. .1) = I NO RELEASES I Average Energy (Fission and Activation gases - MeV):

Qrtr.1: ~v = N/A E13 = N/A Qrtr.2_: ~v = NIA E13 = N/A Qrtr. .9.: ~v = NIA E13 = N/A Qrtr.1: Ey = N/A E13 = N/A Liquid: Radwaste EC Vent Number of Batch Releases 0 0 Total Time Period for Batch Releases (hrs) 0 0.00 Maximum Time Period for a Batch Release (hrs) 0 0.00 Average Time Period for a Batch Release (hrs) 0 0.00 Minimum Time Period for a Batch Release (hrs) 0 0.00 Total volume of water used to dilute 1st 2nd 3rd 4th the liquid effluent during release period (L) Radwaste I N/A I N/A I N/A I N/A I Total volume of water available to 1st 2nd 3rd 4th dilute the liquid effluent during report period (L} Radwaste I 1.31 E+11 I 1.29E+11 I 1.37E+11 I 1.32E+11 I Gaseous(Emergency Condenser Vent):

Number of Batch Releases 0 Total Time Period for Batch Releases (hrs) 0.00 Maximum Time Period for a Batch Release (hrs) 0.00 Average Time Period for a Batch Release (hrs) 0.00 Minimum Time Period for a Batch Release (hrs) 0.00 Gaseous (Primary Containment Purge):

Number of Batch Releases 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

ATTACHMENT 1 Page 2 of 2 Unit 1 x Unit2 Reporting Period: January - December 2016 Abnormal Releases:

A. Liquids:

I Number of Releases I 0 I ITotal Activity Released I N/A ICi B. Gaseous:

INumber of Releases I 0 I

!Total Activity Released I 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 ODCM was revised (Revision 34) to require composite samples of discharges from the Reactor Building Perimeter Drain be collected and analyzed, and total curies reported in the RERR. Because this activity has been accounted for in previous RERRs, it is to be reported as a separate item, and not included in the liquid releases (Attachment 5).

Since 200.3, the Emergency Condensers have been actuated 7 times. These are identified in the 2003, 2004, 2009, 2010 and 2013 RERRs. The perimeter drain pumps were out of service between 2008 and 2012. Releases prior to that are assumed to have been dicharged to the storm drains while the pumps were functional. During the first quarter of 2016, Tritium was detected in the Perimeter Drain discharge at 1.79E-05 µCi/ml resulting in 0.19 Ci of tritium being released. No tritium was detected in the second, third or fourth quarters of 2016. No other isotopes were identified.

ATTACHMENT 2 Page 1of1 Unit 1 x Unit2 Re12orting Period: Janua~ - December 2016 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES, ELEVATED AND GROUND LEVEL 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter EST.TOTAL ERROR,%

A. i-1ss1on 1<. Ac11vat1on l.;ases 111 I .. I 1.

2.

Total Release Average Release Rate Ci

µCi/sec I ** I ** I 5.00E+01 B. Iodines (1)

1. Total Iodine - 131 Ci 3.06E-05 1.02E-04 2.30E-04 2.83E-04 I 3.00E+01

2. Average Release Rate for Period µCi/sec 3.62E-06 I 1.31E-05 2.90E-05 3.60E-05 C. Particulates (1)

1. Particulates with Half-lives>8 days Ci 4.31E-04 3.66E-04 1.0SE-03 1.76E-03 3.00E+01

2. Average Release Rate for Period

3. Gross Alpha Radioactivity

µCi/sec Ci ..

5.09E-05 4.71E-05 1.35E-04 2.24E-04

• • 2.50E+01 D. Tritium (1)

1. Total Release Ci 9.01E+01 6.50E+01 5.13E+01 4.33E+01 5.00E+01

2. Average Release Rate for Period µCi/sec 1.07E+01 8.33E+OO 6.45E+OO 5.49E+OO E. Percent of Tech. S11ec. Limits Fission and Activation Gases Percent of Quarterly Gamma Air Dose

% O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO Limit (5 mR)

Percent of Quarterly Beta Air Dose Limit

% O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO (10 mrad)

Percent of Annual Gamma Air Dose Limit

% O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO to Date (10 mR)

Percent of Annual Beta Air Dose Limit to

% O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Date (20 mrad)

Percent of Whole Body Dose Rate Limit

% O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO (500 mrem/yr)

Percent of Skin Dose Rate Limit (3000

% O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO mrem/yr)

Tritium, Iodines, and Particulates (with half-lives greater than 8 da~s)

Percent of Quarterly Dose Limit (7.5

% 6.23E-02 8.19E-02 1.45E-01 1.76E-01 mrem)

Percent of Annual Dose Limit to Date (15

% 3.11E-02 7.21E-02 1.45E-01 2.33E-01 mrem)

Percent of Organ Dose Limit (1500

% 1.26E-03 1.64E-03 2.88E-03 3.49E-03 mrem/yr (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.

ATTACHMENT 3 Page 1of2 Unit 1 x Unit2 Re1;1orting Period: Janua!Jl - December 2016 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 Krypton-85m Ci Ci .... .... .... ....

Krypton-87 Ci Krypton-88 Ci Xenon-127 Xenon-131m Ci Ci Xenon-133 Ci Xenon-133m Ci Xenon-135 Ci Xenon-135m Ci Xenon-137 Ci Xenon-138 Ci Iodines (1) lodine-131 Ci 3.06E-05 1.02E-04 2.30E-04 2.83E-04 lodine-133 lodine-135 Ci Ci ..

5.29E-04 1.35E-03 2.92E-03 3.34E-03 Particulates (1 l Strontium-89 Ci .... ...... .... 4.39E-05 Strontium-90 Cesium-134 Ci Ci .. .. ..

Cesium-137 Ci 9.52E-06 5.08E-06 1.00E-05 Cobalt-60 Ci 2.72E-04 2.73E-04 6.63E-04 1.02E-03 Cobalt-58 Ci 1.63E-06 2.77E-05 2.98E-04 5.80E-04 Manganese-54 Ci 2.07E-06 2.73E-05 3.76E-05 Barium-140 Ci Lanthanum-140 Niobium-95 Ci Ci .... ...... ....

Cerium-141 Ci Cerium-144 Ci lron-59 Cesium-136 Ci Ci .... .... ..

Chromium-51 Zinc-65 Ci Ci 1.50E-06 .. ....

7.69E-05 3.26E-05 lron-55 Molybdenum-99 Ci Ci ....

1.44E-04 6.00E-05 4.80E-05 Neodymium-147 Ci Tritium {1} Ci I 8.33E+01 I 5.53E+01 I 3.99E+01 I 3.73E+01 I (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of 1.00E-04 µCi/ml for required noble gases, 1.00E-11 µCi/ml for required particulates, 1.00E-12 µCi/ml for required Iodines, and 1.00E-06 µCi/ml for Tritium as required by the ODCM, has been verified.

(2) Contributions from purges are included. There were no other batch releases during the reporting period.

ATTACHMENT 3 Page 2 of 2 Unit 1 x Unit2 Reizorting Period: Janua[Jl - December 2016 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 Krypton-85m Ci Ci Krypton-87 Ci Krypton-88 Xenon-127 Ci Ci .... ....

Xenon-131m Xenon-133 Ci Ci .... .... ...

Xenon-133m Xenon-135 Ci Ci Xenon-135m Xenon-137 Ci Ci Xenon-138 Ci Iodines (1) lodine-131 Ci .... .... .... ....

I .. I .. I .. I .. I lodine-133 Ci lodine-135 Ci Particulates !1 >

Strontium-89 Ci .... ..

Strontium-90 Cesium-134 Ci Ci .... .... .... ....

Cesium-137 Cobalt-60 Ci Ci .... ..

Cobalt-58 Manganese-54 Ci Ci .. .. .. ..

Barium-140 Lanthanum-140 Ci Ci Niobium-95 Cerium-141 Ci Ci .... ..

Cerium-144 lron-59 Ci Ci ....

Cesium-136 Chromium-51 Ci Ci .... .. .... ...

Zinc-65 lron-55 Ci Ci .... ..

Molybdenum-99 Neodymium-147 Ci Ci .. ..

Tritium (1l Ci I .. I .. I .. I .. I (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of 1.00E-04 µCi/ml for required noble gases, 1.00E-11 µCi/ml for required particulates, 1.00E-12 µCi/ml for required Iodines, and 1.00E-06 µCi/ml for Tritium as required by the ODCM, has been verified.

(2) Contributions from purges, if any, are included. There were no other batch releases during the reporting period.

ATTACHMENT 4 Page 1of2 Unit 1 x Unit2 Re12orting Period: Janua!:l£ - December 2016 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 Krypton-85 Ci Ci Krypton-85m Ci Krypton-87 Ci **

Krypton-88 Ci ** ** **

Xenon-127 Ci ** ** **

Xenon-131m Xenon-133 Ci Ci .... ..

Xenon-133m Xenon-135 Ci Ci Xenon-135m Ci **

Xenon-137 Xenon-138 Ci Ci ..

Iodines C1l lodine-131 Ci ** .. ** ..

I .. I .. I lodine-133 ** ** ** **

lodine-135 Ci Ci I ** ** I Particulates (1)

Strontium-89 Ci ** ** **

Strontium-90 Ci **

Cesium-134 Ci ** **

Cesium-137 Ci ** **

Cobalt-60 Cobalt-58 Ci Ci ..

Manganese-54 Ci **

Barium-140 Lanthanum-140 Ci Ci ..

Niobium-95 Cerium-141 Ci Ci Cerium-144 Ci ** ** **

lron-59 Ci **

Cesium-136 Ci ** **

Chromium-51 Ci **

Zinc-65 lron-55 Ci Ci ** ..

Molybdenum-99 Neodymium-147 Ci Ci Tritium (1} Ci I 6.78E+OO I 9.62E+OO I 1.14E+01 I 5.93E+OO I (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.

ATTACHMENT 4 Page 2 of 2 Unit 1 x Unit2 Re11orting Period: Januarl - December 2016 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)

Argonc41 Ci .... .... .... ....

Krypton-B5 Krypton-B5m Ci Ci .... .... .... ....

Krypton-B7 Ci Krypton-BB Xenon-127 Ci Ci Xenon-131m Ci Xenon-133 Ci Xenon-133m Xenon-135 Ci Ci .... .... .

Xenon-135m Xenon-137 Ci Ci .... .... .. ..

Xenon-13B Ci Iodines (1) lodine-131 Ci .... .... .... ....

lodine-133 lodine-135 Ci Ci I .. I .. I .. I I Particulates (1)

Strontium-B9 Ci Strontium-90 Cesium-134 Ci Ci Cesium-137 Ci **

Cobalt-60 Cobalt-5B Ci Ci .... .... ....

Manganese-54 Ci Barium-140 Ci Lanthanum-140 Ci Niobium-95 Ci Cerium-141 Cerium-144 Ci Ci .... .... ....

lron-59 Cesium-136 Ci Ci .... .... .... ....

Chromium-51 Zinc-65 Ci Ci lron-55 Molybdenum-99 Ci Ci Neodymium-147 Ci Tritium (1) Ci I .. I .. I .. I .. I (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.

ATTACHMENT 5 Page 1of2 Unit 1 x Unit2 Reeorting Period: Janua!:Jl - December 2016 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES (1) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Est. Total Error, %

A. t-1ss1on & Act1va11on 1-'roelucts

1. Total Release (not including Tritium, Ci No Releases No Releases No Releases No Releases 5.00E+01 gases, alpha)

2. Average diluted concentration during

µCi/ml No Releases No Releases No Releases No Releases reporting period B. Tritium

1. Total release Ci No Releases No Releases No Releases No Releases 5.00E+01

2. Average diluted concentration during

µCi/ml No Releases No Releases No Releases No Releases the reporting period C. Dissolved and Entrained Gases

1. Total release Ci No Releases No Releases No Releases No Releases 5.00E+01

2. Average diluted concentration during

µCi/ml No Releases No Releases No Releases No Releases the reporting period D. Gross Algha Radioactivity

1. Total release Ci No Releases No Releases No Releases No Releases 5.00E+01 E. Volumes

1. Prior to Dilution Liters No Releases No Releases No Releases No Releases 5.00E+01 *

2. Volume of dilution water used during Liters No Releases No Releases No Releases No Releases 5.00E+01 release period

3. Volume of dilution water available Liters 1.31 E+11 1.29E+11 1.37E+11 1.32E+11 5.00E+01 during reporting period - Cooling Water F. Percent of Tech. Sgec. 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 (5 mrem)

% No Releases No Releases No Releases No Releases 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 (2.00E-04 µCi/ml)

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

ATTACHMENT 5 Page 2 of2 Unit 1 x Unit2 Reeorting Period: Janua!:l£ - December 2016 LIQUID EFFLUENTS RELEASED Batch Mode (1),(2)

Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Nuclides Released Strontium-89 Ci No Releases No Releases No Releases No Releases Strontium-90 Ci No Releases No Releases No Releases No Releases Cesium-134 Ci No Releases No Releases No Releases No Releases Cesium-137 Ci No Releases No Releases No Releases No Releases lodine-131 Ci No Releases No Releases No Releases No Releases Cobalt-58 Ci No Releases No Releases No Releases No Releases Cobalt-60 Ci No Releases No Releases No Releases No Releases lron-59 Ci No Releases No Releases No Releases No Releases Zinc-65 Ci No Releases No Releases No Releases No Releases Manganese-54 Ci No Releases No Releases No Releases No Releases Chromium-51 Ci No Releases No Releases No Releases No Releases Zirconium-95 Ci No Releases No Releases No Releases No Releases Niobium-95 Ci No Releases No Releases No Releases No Releases Molybdenum-99 Ci No Releases No Releases No Releases No Releases Barium-140 Ci No Releases No Releases No Releases No Releases Lanthanum-140 Ci No Releases No Releases No Releases No Releases Cerium-141 Ci No Releases No Releases No Releases No Releases lodine-133 Ci No Releases No Releases No Releases No Releases lron-55 Ci No Releases No Releases No Releases No Releases Cerium-144 Ci No Releases No Releases No Releases No Releases Cesium-136 Ci No Releases No Releases No Releases No Releases Copper-64 Ci No Releases No Releases No Releases No Releases Manganese-56 Ci No Releases No Releases No Releases No Releases Nickel-65 Ci No Releases No Releases No Releases No Releases Sodium-24 Ci No Releases No Releases No Releases No Releases Dissolved or Entrained Gases Ci I No Releases I No Releases I No Releases I No Releases I Tritium Ci No Releases No Releases No Releases No Releases (1) No continuous mode release occurred during the report period as indicated by effluent sampling. There were no Radwaste Batch Releases.

(2) Concentrations less than the lower limit of detection of the counting system used have been verified for sampled effluents. A lower limit of detection of 5.00E-07 µCi/ml for required gamma emitting nuclides, 1.00E-05 µCi/ml for required dissolved and entrained noble gases and tritium, 5.00E-08 µCi/ml for Sr-89/90, 1.00E-06 µCi/ml for 1-131 and Fe-55, and 1.00E-07 µCi/ml for gross alpha radioactivity, as identified in the ODCM, has been verified. Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.

ATTACHMENT 6 Page 1 of4 Unit 1 x Unit2 Rei;iorting Period: Janua!Y - December 2016 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A1. TYPE Volume Activi~ {1}

(m3) (Ci)

Class Class A B c A B c a.1 Spent Resin (Dewatered) 2.00E+01 0.00E+OO 0.00E+OO 4.86E+01 O.OOE+OO O.OOE+OO a.2 Filter Sludge O.OOE+OO 8.13E+OO 0.00E+OO O.OOE+OO 1.17E+03 O.OOE+OO a.3 Concentrated Waste 0.00E+OO 0.00E+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO Totals 2.00E+01 8.13E+OO 0.00E+OO 4.86E+01 1.17E+03 O.OOE+OO b.1 Dry Compressible Waste 1.80E+02 O.OOE+OO 0.00E+OO 7.70E+OO O.OOE+OO O.OOE+OO b.2 Dry Non-Compressible Waste (Contaminated O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO Equipment)

Totals 1.80E+02 O.OOE+OO 0.00E+OO 7.70E+OO O.OOE+OO O.OOE+OO

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

d. Other (to vendor for processing) d.1 #13 Sump Liner 1.42E+OO O.OOE+OO 0.00E+OO 8.17E+OO O.OOE+OO O.OOE+OO (1) The estimated total error is 5.0E+01 %.

ATTACHMENT 6 Page 2 of 4 Unit 1 x Unit2 Reporting Period: January - December 2016 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A1. TYPE Container Package Solidification Agent a.1 Spent Resin Poly Liner General Design None a.2 Filter Sludge Poly Liner Type B None b.1 Dry Compressible Waste Sea van General Design None b.2 Dry Non-Compressible Waste (contaminated NIA NIA NIA equipment)

c. Irradiated Components, NIA NIA NIA Control Rods

d. Other (To vendor for processing) d.1 Sump Liner Poly Liner General Design None

ATTACHMENT 6 Page 3 of 4 Unit 1 x Unit2 Re[!orting Period: Janua[ll - December 2016 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 1.99% 2.41E+01 Fe-55 28.46% 3.46E+02 Co-60 58.03% 7.05E+02 Ni-63 1.09% 1.32E+01 Cs-137 9.31% 1.13E+02

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

Nuclide Percent Curies Mn-54 1.90% 1.47E-01 Fe-55 51.21 % 3.94E+OO Co-60 41.42% 3.19E+OO Ni-63 1.40% 1.08E-01 Cs-137 1.43% 1.10E-01

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

Nuclide Percent NIA NIA

d. Other: (To vendor for processing)

1. Sump Liner Nuclide Percent Curies H-3 16.75% 1.64E+OO Fe-55 31.07% 3.05E+OO Co-60 47.38% 4.65E+OO Cs-137 4.41% 4.32E-01

ATTACHMENT 6 Page4 of 4 Unit 1 x Unit2 Rei;iorting Period: Janua!Y - December 2016 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A3. SOLID WASTE DISPOSITION Number of ShiQments Mode of Trans12ortation Destination 17 Truck, highway Bear Creek 4 Truck, highway Clive B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shi12ments Mode of Trans12ortation 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 detectible quantities of plant-related nuclides from NMP to the treatment facility during the reporting period.

ATTACHMENT 7 Page 1of1 Unit 1 x Unit2 Rei;iorting Period: Janua[Jl - December 2016

SUMMARY

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

The following changes were made to the Unit 1 Off-Site Dose Calculation Manual (ODCM) during the reporting period.

REVISION 35 New/Amended Page# Description of Change Reason For Change Section#

Assigned procedure number CY-NM- Align with Fleet procedure specifications.

All All 170-301 per CY-AA-170-3100.

Cover Cover Replaced CENG logo with Exelon Align with Fleet procedure specifications.

2.1.5.4 Sampling Changed 2.1.5.4 paragraph 2 to allow Allow for on-site analysis.

1116 Frequency/Sample for performing tritium analyses on-site Analysis in addition to off-site.

Removed specific values for non- Current scaling factors are based on data gamma emitting nuclides to be used from the 1980's and are not indicative of when performing dose calculations recent performance. Inserted language from 2.1.5.6 Gaseous and actual values are not yet Unit 2 ODCM stating dose contributions would 1117 Radwaste Treatment available. be calculated using concentration estimates.

System Operation Actual values will be controlled by individual procedures to allow for changes due to plant conditions.

TABLE 3-23 Corrected Reg. Guide Reference for Digit was missing from the number.

PARAMETERS FOR Shoreline Pathway THE EVALUATION OF DOSES TO REAL 1167 MEMBERS OF THE PUBLIC FROM GASEOUS AND LIQUID EFFLUENTS C.2 Ground Plane Reformatted equation using equation Update to format 1184 Pathway editor.

C.3 Grass-(Cow or Reformatted equation using equation Update to format 1185 Goat)-Milk Pathway editor.

C.3 Grass-(Cow or Reformatted equation using equation Update to format 1186 Goat)-Milk Pathway editor.

C.4 Grass-Cow-Meat Reformatted equation using equation Update to format 1187 editor.

Pathway C.5 Vegetation Reformatted equation using equation Update to format 1188 editor.

Pathway

ATTACHMENT 8 Page 1 of 1 Unit 1 x Unit2 Reporting Perio,d: January - December 2016

SUMMARY

OF CHANGES TO THE PROCESS CONTROL PROGRAM (PCP)

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

ATTACHMENT 9 Page 1 of 1 Unit 1 x Unit 2 Re(!orting Period: Janua!JI: - December 2016

SUMMARY

OF NON-FUNCTIONAL MONITORS Dates Monitor was Monitor Cause and Corrective Actions Non-Functional Liquid Radwaste January 1, 2016 to These monitors were intentionally allowed to exceed their quarterly Discharge Monitors December 31, 2016 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 2016. This non-functionality is tracked in Equipment Status Log (ESL) 2006-0192.

ATTACHMENT 10 Page 1of4 Unit 1 _x_ Unit 2 Reporting Period: January - December 2016 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY Introduction An assessment of the radiation dose potentially received by a Member of the Public due to their activities inside the site boundary from Nine Mile Point Unit 1 (NMPl) liquid and gaseous effluents has been conducted for the period January through December 2016.

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 l, 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 2016, 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 NMPl 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 NMPl Stack and Emergency Condenser Vent.

• Direct radiation pathway; dose resulting from the operation ofNMPl, Nine Mile Point Unit 2 (NMP2) and the James A. Fitzpatrick Nuclear Power Plant (JAFNPP) Facilities.

Methodologies for Determining Dose for Applicable Pathways External Ground (Shoreline Sediment) Pathway Dose from the external ground (shoreline sediment) is based on the methodology in the NMPl Offsite Dose Calculation Manual (ODCM) as adapted from Regulatory Guide 1.109. For this evaluation it is assumed that the hypothetical maximum exposed individual fished from the shoreline at all times.

ATTACHMENT 10 Page 2 of4 Unit 1 _x_ Unit 2 Reporting Period: January - December 2016 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY The total dose received by the whole body and skin of the maximum exposed individual during 20 I 6 was calculated using the following input parameters:

• Usage Factor= 3 I2 hours (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 I. I 09, Table E-6.

• Fractional portion of the year= I (used average radionuclide concentration over total time period)

• Average Cs-137 concentration= l.ISE-OI 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 I, Exposure Pathway Annual Dose.

Inhalation Pathway The inhalation dose pathway is evaluated by utilizing the inhalation equation in the NMPI ODCM, as adapted from Regulatory Guide 1.109. The total whole body dose and organ dose received by the hypothetical maximum exposed fisherman during 20I6 calculated using the following input parameters for gaseous effluents released from both the NMPI Stack and Emergency Condenser Vent for the time period exposure is received:

NMP 1 Stack:

Variable Fisherman 1 3

XIQ (s/m ) 8.90E-06 Inhalation dose factor Table E-7, Regulatory Guide 1.109 3

Annual air intake (m /year) (adult) 8000 Fractional portion of the year 0.0356 H-3 (pCi/sec) 5.62E+06 Mn-54 (pCi.sec) 2.75E+OO C-14 (pCi/sec)2 2.80 E+05 Fe-55 (pCi/sec) 4.58E+OO Co-58 (pCi/sec) 3.84E+Ol Co-60 (pCi/sec) 8.28E+Ol Zn-65 (pCi/sec) 4 . 64E+OO Sr-89 (pCi/sec) l.86E+OO 1-131 (pCi/sec) 2.61E+Ol 1-133 (pCi/sec) 3.22E+02 Cs-137 (pCi/sec) 6.40E-01

ATTACHMENT 10 Page 3 of 4 Unit 1 _x_ Unit 2 Reporting Period: January - December 2016 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY NMP1 Emergency Condenser Vent:

Variable Fisherman 1 X/Q (s/m 3) 6.63£-06 Inhalation dose factor Table E-7, Regulatory Guide 1.109 3

Annual air intake (m /year) (adult) 8000 Fractional portion of the year 0.0356 H-3 (pCi/sec) l.13E+06 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 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 ofCarbon-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 NMPl ODCM. This pathway considers four components: direct radiation from the generating facilities, direct radiation from any possible overhead plume, direct radiation from ground deposition and direct radiation from plume submersion.

The direct radiation pathway is evaluated by the use of high sensitivity environmental Thermoluminescent Dosimeters (TLDs). Since fishing activities occur between April 1 and December 31, TLD data for the second, third, and fourth quarters of 2016 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) 1.18 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.

ATTACHMENT 10 Page4 of4 Unit 1 _x_ Unit 2 Reporting Period: January - December 2016 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY Dose Received By Hypothetical Maximum Exposed Member of the Public Inside the Site Boundary The following is a summary of the dose received by a hypothetical maximum exposed fisherman from liquid and gaseous effluents released from NMPl during 2016:

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

Whole Body 1.80 E-03 External Ground Skin of Whole Body 2.10 E-03 Whole Body 2.89 E-03 Inhalation Maximum Organ Lung: 3 .06 E-03 Thyroid 2.89 E-03 Direct Radiation Whole Body 0.37 Based on these values the total annual dose received by a hypothetical maximum exposed Member of the . Public inside the site boundary is as follows:

TABLE2 Annual Dose Summary Fisherman Total Annual Dose for 2016 (mrem)

Total Whole Body 3.74 E-01 Skin of Whole Body 2.10 E-03 Maximum Organ Lung: 3.06 E-03 Thyroid 2.89 E-03

ATTACHMENT 11 Page 1of5 Unit 1 _x_ Unit 2 Reporting Period: January - December 2016 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 2016 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 (NMPl), as well as other nearby uranium fuel cycle facilities, be considered. In this case, the effluents of NMPl, Nine Mile Point Unit 2 (NMP2) and the James A. FitzPatrick Nuclear Power Plant (JAFNPP) facilities must be considered.

40 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:

• < 25 mRem whole body

• < 25 mRem any organ (except thyroid)

• < 75 mRem thyroid This evaluation compares doses resulting from liquid and gaseous effluents and direct radiation originating from the site as a result of the operation of the NMPl, NMP2 and JAFNPP nuclear facilities.

Dose Pathways Dose pathways considered for this evaluation included doses resulting from liquid effluents, gaseous effluents and direct radiation from all nuclear operating facilities located on the Nine Mile Point site.

Dose to the likely most exposed Member of the 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 NMPl, NMP2 and JAFNPP operating facilities.

• Direct Radiation pathway; radiation dose resulting from the operation ofNMPl, NMP2 and JAFNPP facilities (including the Independent Spent Fuel Storage Installations (ISFSI)).

Methodologies for Determining Dose for Applicable Pathways Fish Consumption Dose received as a result of fish consumption is based on the methodology specified in the NMPl Off-Site Dose Calculation Manual (ODCM) as adapted from Regulatory Guide 1.109. The dose for 2016 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 2016; therefore, no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2016.

ATTACHMENT 11 Page 2 of 5 Unit 1 _x_ Unit 2 Reporting Period: January - December 2016 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Vegetation Consumption Dose received as a result of vegetation consumption is based on the methodology specified in the NMPl ODCM as adapted from Regulatory Guide 1.109. The dose for 2016 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 2016; therefore, no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2016.

For estimating C-14, dose received as a result of vegetation consumption is based on the methodology specified in the NMP 1 0 DCM as adapted from Regulatory Guide 1.109. The estimated concentration of C-14 in vegetation is based on the estimated concentration of C-14 in plant gaseous effluents.

Shoreline Sediment Dose received from shoreline sediment is based on the methodology in the NMPl ODCM as adapted from Regulatory Guide 1.109. For this evaluation it is assumed that the most likely exposed Member of the Public spends 67 hour7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br />s/year along the shoreline for recreational purposes.

No radionuc!ides were detected in shoreline sediment samples collected and analyzed during 2016; therefore no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2016.

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 NMPl ODCM, NMP2 ODCM, and the JAFNPP ODCM. These calculations consider deposition, inhalation and ingestion pathways. Actual meteorological data was used to calculate doses to the likely most exposed Member of the Public. The total sum of doses resulting from gaseous effluents from NMPl, NMP2 and JAFNPP during 2016 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 2016 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 2016 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.

ATTACHMENT 11 Page 3 of 5 Unit 1 _x_ Unit 2 Reporting Period: January - December 2016 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY For NMPl and NMP2, C-14 gaseous dose calculations in the site ARERR are made using the following assumptions for each unit: (1) continuous release of the estimated C-14 generated during power operation based on the number of Effective Full Power Days (EFPDs) for the period, (2) maximum C-14 activity from literature values cited in EPRI Report 1021106, and (3) typical fraction as carbon dioxide for gaseous releases from literature values also cited in EPRI Report 1021106.

Equation 1 estimates the maximum annual production of C-14, PRMAX' for each BWR unit.

PRMAx 5.1

• MWT/ IUUU fHq lj Where:

5.1 BWR Normalized Production (Ci/GWt-yr)

MWT Mega Watts Thermal (MWt) 1000 Conversion Factor (MWt to GWt)

Equation 2 estimates the C-14 activity released, A c-l./, into the gaseous pathway during the time period for each BWR unit.

A C-1./ PR MAX

• 0.99

• EFPD I 365, Ci (for time period) [Eq2}

Where:

PR MAX 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

ATTACHMENT 11 Page 4 of 5 Unit 1 _x_ Unit 2 Reporting Period: January - December 2016 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-l-1, co2 , into the gaseous pathway during the time period for each BWR unit.

A C-1-1, C02 PRMAX

• 0.99

• 0.95

• EFPD I 365, Ci (for time period) [Eq3]

Where:

PR MAX maximum annual production rate of C-14 0.99 fraction of C-14 in BWR gaseous pathway releases (maximum literature value in EPRl Report 1021106; also Table 1) 0.95 fraction of C-14 as carbon dioxide in B WR gaseous pathway releases (typical literature value in EPRl 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 2016 estimated C-14 activity releases (total and carbon dioxide chemical form) are summarized in Table 1.

Table 1 2016 BWR Estimated C-14 Gaseous Releases Gaseous C0 2 Form Max.Annual 2016 Total Release 2016 C02 Release BWR Release Release EFPD Operation Prod. Rate (Eq 2) (Eq 3)

Fraction(a) Fraction(bl (Eq 1) 362.1 EFPD NMPl 0.99 0.95 9.44 Ci/yr 9.27 Ci 8.80 Ci (98.9%)

328.13 EFPD NMP2 0.99 0.95 20.34 Ci/yr<<> 18.1 Ci 17.2 Ci (89.7%)

296.4 EFPD JAFNPP 0.99 0.95 12.93 Ci/yr 10.4 Ci 9.88 Ci (81.0%)

(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.

ATTACHMENT 11 Page 5 of 5 Unit 1 _x_ Unit 2 Reporting Period: Januarv - December 2016 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Direct Radiation Pathway Dose as a result of direct gamma radiation from the site, encompasses doses from direct "shine" from the generating facilities, direct radiation from any overhead gaseous plumes, plume submersion, and ground deposition. This total dose is measured by 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 2016, the closest residence and the critical downwind residence are at the same location.

Table2 Dose Potentially Received by the Likely Most Exposed Member of the Public Outside the Site Boundary During 2016 Exposure Pathway Dose Type Dose (mrem)

Total Whole Body No Dose Fish and Vegetation Consumption Total Maximum Organ No Dose Total Whole Body No Dose Shoreline Sediment Total Skin of Whole Body No Dose Total Whole Body 5.86 E-03 Gaseous Effluents Thyroid 1.20 E-02 (excluding C-14)

Maximum Organ Thyroid: 1.20 E-02 Gaseous Effluent Total Whole Body 3.50 E-01 (C-14) Maximum Organ Bone: 1.75 E+OO Direct Radiation Total Whole Body 0.92 Based on these values the maximum total annual dose potentially received by the likely most exposed Member of the Public during 2016 is as follows:

• Total Whole Body: 1.28 E+OO mrem

• Total Thyroid: 1.20 E~02 mrem

• Maximum Organ: Bone: 1.75 E+OO mrem 40CFR190 Evaluation The maximum total doses presented in this attachment are the result of operations at the NMPl, NMP2 and the JAFNPP facilities. The maximum organ dose (Bone: 1.75 mrem), maximum thyroid dose (0.012 mrem) and the maximum whole body dose (1.28 mrem) are below the 40 CFR 190 criteria of 25 mrem per calendar year to the maximum exposed organ or the whole body, and below 75 mrem per calendar year to the thyroid.

l_

ATTACHMENT 12 Page 1 of 1 Unit 1 _x_ Unit2 - - Re12orting Period: Janua~ - December 2016 Well Identification #Samples Minimum Maximum

1. Positive Samples Number Collected Concentration (pCi/I) Concentration (pCi/I)

GMX-MW1* 4 0 <161 <198 MW-1 4 0 <157 <206 MW-5 4 0 <160 <213 MW-6 4 0 <156 <212 MW-7 4 0 <162 <209 MW-8 4 1 160 <195 1

MW-9 4 1 <175 220 1 <175 MW-10 4 0 <200 MW-11 4 0 <166 <198 MW-12 4 0 <108 <198 MW-13 4 0 <173 <200 MW-14* 4 0 <170 <199 MW-15 4 4 251 429 MW-16 4 0 <108 <199 '

MW-17 4 2 <108 261 MW-18 4 0 <172 <192 MW-19 4 0 <173 <203 MW-20 4 0 <109 <202 MW-21 4 1 <176 368 NMP2 MAT 2 '3 4 3 <147 201 PZ-1 4 0 <155 <205 PZ-2 4 0 <159 <197 PZ-3 4 0 <149 <212 PZ-4 4 4 199 233 PZ-5 '

4 4 213 323 PZ-6 4 3 232 292 PZ-7 4 4 496 749 PZ-8 4 0 <157 <204 PZ-9* 4 0 <154 <205 Notes: * - Control Location 1

- Sentinel well location .

2

- NMP2 Groundwater Depression Cone 3

- Samples collected from storm drain system which includes precipitation

NINE MILE POINT NUCLEAR STATION - UNIT 2 RADIOACTIVE EFFLUENT RELEASE REPORT January- December 2016

Page 1 of2 NINE MILK POINT NUCLEAR STATION - UNIT 2 RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2016 SUPPLEMENTAL INFORMATION Facility: Nine Mile Point Unit 2 Licensee: Nine Mile Point Nuclear Station, LLC

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

1. The dose rate limit of noble gases released in gaseous effluents from the site to areas at or beyond the site boundary shall be less than or equal to 500 mrem/year to the whole body and less than or equal to 3000 mrem/year to the skin.

2. The air dose from noble gases released in gaseous effluents from Nine Mile Point Unit 2 to areas at or beyond the site boundary shall be limited during any calendar quarter to less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and during any calendar year to less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

B&C) TRITIUM, IODINES 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 or beyond the site boundary shall be less than or equal to 1500 mrem/year to any organ.

2. The dose to a member of the public from Iodine-131, Iodine-133, Tritium and all radionuclides in particulate form with half-lives greater than eight days in gaseous effluents released from Nine Mile Point Unit 2 to areas at or beyond the site boundary shall be limited during any calendar quarter to less than or equal to 7.5 mrem to any organ, and during any calendar year to less than or equal to 15 mrem to any organ.

D) LIQUID EFFLUENTS

1. Improved Technical Specifications (ITS) limit the concentration of radioactive material released in the liquid effluents to unrestricted areas to ten times the concentrations specified in 10CFR20.1001-20.2402, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or 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 2 to unrestricted areas shall be limited during any calendar quarter to less than or equal to 1.5 mrem to the whole body and to less than or equal to 5 mrem to any organ, and during any calendar year to less than or equal to 3 mrem to the whole body and to less than or equal to 10 mrem to any organ.

Page 2 of2

2. MEASUREMENTS AND APPROXIMATIONS OF 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 an on-line scintillation detector (calibrated against gamma isotopic analysis of a 4.0L Marinelli grab sample) of an isokinetic sample stream.

B) IODINES Iodine effluent activity is determined by gamma spectroscopic analysis (at least weekly) of charcoal cartridges sampled from an isokinetic sample stream.

C) PARTICULATES Activity released from the main stack and the combined Radwaste/Reactor Building vent is determined by gamma spectroscopic analysis (at least weekly) of particulate filters sampled from an isokinetic sample stream and composite analysis of the filters for non-gamma emitters.

D) TRITIUM Tritium effluent activity is measured by liquid scintillation or gas proportional counting of monthly samples taken with an air sparging/water trap apparatus.

E) LIQUID EFFLUENTS Isotopic contents of liquid effluents are determined by isotopic analysis of a representative sample of each batch and composite analysis of non-gamma emitters.

F) SOLID EFFLUENTS Isotopic contents of waste shipments are determined by gamma spectroscopy analyses of a representative sample of each batch. Scaling factors established from primary composite sample analyses conducted off-site are applied, where appropriate, to find estimated concentration of non-gamma emitters. For low activity trash shipments, curie content is estimated by dose rate measurement and application of appropriate scaling factors.

G) C-14 The production of C-14 and the effluent dose consequences are estimates based on EPRI methodology provided in EPRI Report 1021106, Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents, December 2010 and NUREG-0016, Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents for Boiling Water Reactors (BWR-GALE Code).

3. METEOROLOGICAL DATA An annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distribution of wind speed, wind direction, and atmospheric stability. In lieu of submission with the Radiological Effluent Release Report, the licensee is exercising the option of retaining this summary ofrequired meteorological data on site in a file that shall be provided to the NRC upon request.

Supplemental Information ATTACHMENT 1 Page 1of2

SUMMARY

DATA Unit 1 Unit 2 x Re~orting Period: Janua[ll- December 2016 Liquid Effluents:

ODCM Required Maximum Effluent Concentration (MEC) =10x10CFR20.1001 - 20.2402, Appendix B, Table 2, Column 2 Average MEC - µCi/ml (Qtr. j) = I NO RELEASES Average MEC - µCi/ml (Qtr. ;D = I NO RELEASES I Average MEC - µCi/ml (Qtr. ~ = I NO RELEASES Average MEC - µCi/ml (Qtr. ~ = I NO RELEASES I Average Energy (Fission and Activation gases - MEV):

Qrtr.1: ~v = 1.59E-01 E~ = 2.53E-01 Qrtr. 6_: ~v = NIA E~ = NIA Qrtr. ~:

~v = NIA E~ = NIA Qrtr. ~: Ey = NIA E~ = NIA Liquid:

Number of Batch Releases 0 Total Time Period for Batch Releases (hrs) 0.0 Maximum Time Period for a Batch Release (hrs) 0.0 Average Time Period for a Batch Release (hrs) 0.0 Minimum Time Period for a Batch Release 0.0 Total volume of water used to dilute the liquid 1st 2nd 3rd 4th durina the release period (L) NIA NIA I NIA I NIA I Total volume of water available.to dilute the liquid 1st 2nd 3rd 4th effluent durina the report period (L) 1.18E+10 1.21E+10 I 1.23E+10 I 1.22E+10 I Gaseous (Emergency Condenser Vent) "Not applicable for Unit 2" Number of Batch Releases NIA Total Time Period for Batch Releases (hrs) NIA Maximum Time Period for a Batch Release (hrs) NIA Average Time Period for a Batch Release (hrs) NIA Minimum Time Period for a Batch Release NIA Gaseous (Primary Containment Purge)

Number of Batch Releases 15 Total Time Period for Batch Releases (hrs) 443.0 Maximum Time Period for a Batch Release (hrs) 157.1 Average Time Period for a Batch Release (hrs) 29.5 Minimum Time Period for a Batch Release (hrs) 4.4

Supplemental Information ATTACHMENT 1 Page 2 of 2

SUMMARY

DATA Unit 1 Unit 2 x Rej!orting Period: Janua!Jl - December 2016 Abnormal Releases:

A. Liquids:

INumber of Releases I 0 I

!Total Activity Released I NIA ICi B. Gaseous:

INumber of Releases I 0 I

!Total Activity Released I NIA ICi

Table 1A Gaseous Effluents - ATTACHMENT 2 Page 1of1 Summation of All Releases -

Elevated and Ground Level Unit 1 Unit2 x Rei;zorting Period: Janua!:lr'. - December 2016 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES, ELEVATED AND GROUND LEVEL 1st 2nd 3rd 4th Est. Total quarter quarter quarter quarter Error,%

A. Fission & Activation Gases

1. Total Release Ci 7.18E-02 O.OOE+OO O.OOE+OO O.OOE+OO 5.00E+01

2. Average Release Rate µCi/sec 9.13E-03 I O.OOE+OO . O.OOE+OO O.OOE+OO B. Iodines

1. Total Iodine - 131 Ci 2.31E-04 7.49E-05 6.37E-06 1.74E-05 3.00E+01

2. Average Release Rate for Period µCi/sec 2.94E-05 9.53E-06 8.11E-07 2.21E-06 C. Particulates

1. Particulates with Half-lives>8days Ci 3.70E-04 6.05E-04 5.54E-05 3.66E-05 3.00E+01

2. Average Release Rate for Period µCi/sec 4.71E-05 7.70E-05 7.04E-06 4.66E-06

3. Gross Alpha Radioactivity Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.50E+01 D. Tritium

1. Total Release Ci 1.32E+01 1.46E+01 2.16E+01 3.41 E+01 5.00E+01

2. Average Release Rate for Period µCi/sec 1.68E+OO 1.86E+OO 2.75E+OO 4.34E+OO E. Percent of Tech. S11ec. Limits Fission and Activation Gases Percent of Quarterly Gamma Air Dose Limit

% 2.30E-05 O.OOE+OO O.OOE+OO O.OOE+OO (5mR)

Percent of Quarterly Beta Air Dose Limit (1 O

% 2.02E-06 O.OOE+OO O.OOE+OO O.OOE+OO mrad)

Percent of Annual Gamma Air Dose Limit to

% 1.15E-05 1.15E-05 1.15E-05 1.15E-05 Date (10 mR)

Percent of Annual Beta Air Dose Limit to

% 1.01 E-06 1.01E-06 1.01E-06 1.01E-06 Date (20 mrad)

Percent of Whole Body Dose Rate Limit (500

% 8.97E-07 O.OOE+OO O.OOE+OO O.OOE+OO mrem/yr)

Percent of Skin Dose Rate Limit (3000

% 1.92E-07 O.OOE+OO 0.00E+OO O.OOE+OO mrem/yr)

Tritium, Iodines, and Particulates (with half-lives greater than 8 da~s)

Percent of Quarterly Dose Limit (7.5 mrem)  % 6.57E-02 2.93E-02 7.47E-03 1.39E-02 Percent of Annual Dose Limit to Date (15

% 3.29E-02 4.75E-02 5.13E-02 5.82E-02 mrem)

Percent of Organ Dose Limit (1500 mrem/yr  % 1.32E-03 5.88E-04 1.48E-04 2.78E-04

Table 1B Gaseous ATTACHMENT 3 Page 1 of2 Effluents - Elevated Releases Unit 1 Unit2 x Re12orting Period: Janua!Jl - December 2016 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 Krypton-87 Ci Ci ....

7.18E-02 Krypton-88 Xenon-127 Ci Ci .... .... .... ....

Xenon-131m Xenon-133 Ci Ci .... ...... ...... ....

Xenon-133m Ci Xenon-135 Xenon-135m Ci Ci .... ...... ....

Xenon-137 Xenon-138 Ci Ci .. .. ..

Iodines (1) lodine-131 Ci 2.31E-04 7.49E-05 6.37E-06 1.74E-05 lodine-133 lodine-135 Ci Ci ..

3.65E-03 7.16E-04 1.91 E-04 Particulates (1}

Chromium-51 Ci .. .... .. ..

Manganese-54 Ci 7.19E-06 1.47E-06 1.04E-05 lron-55 lron-59 Ci Ci ..

7.30E-05 Cobalt-58 Ci 2.86E-06 Cobalt-60 Neodymium-147 Ci Ci ..

1.58E-04 3.88E-05 1.80E-05 1.09E-05 Zinc-65 Strontium-89 Ci Ci ....

1.89E-05 6.53E-06 Strontium-90 Ci Niobium-95 Zirconium-95 Ci Ci .... ....

Molybdenum-99 Ruthenium-103 Ci Ci .... .... ...... ....

Cesium-134 Cesium-136 Ci Ci .... ...... .... ....

Cesium-137 Barium-140 Ci Ci Lanthanum-140 Ci Cerium-141 Cerium-144 Ci Ci .. .. ..

Tritium (1} Ci I 1.02E+01 I 8.41E+OO I 1.37E+01 I 1.52E+01 I (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of 1.00E-04 µCi/ml for required noble gases, 1.00E-11 µCi/ml for required particulates and gross alpha, 1.00E-12 µCi/ml for required Iodines, 1.00E-11

µCi/ml for Sr-89/90 and 1.00E-06 µCi/ml for Tritium, as required by the ODCM, has been verified.

(2) Contributions from purges are included. There were no other batch releases during the reporting period.

ATTACHMENT 3 Page 2 of 2 Unit 1 Unit2 x Rei;iorting Period: Janua!Jl- December 2016 GASEOUS EFFLUENTS - ELEVATED RELEASE Batch Mode (2)

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

Argon-41 Ci Krypton-BS Ci Krypton-BSm Ci Krypton-B7 Ci Krypton-BB Xenon-127 Ci Ci .. .. .. **

Xenon-131m Xenon-133 Ci Ci ..

Xenon-133m Ci ** ** ** **

Xenon-13S Ci ** ** ** **

Xenon-13Sm Ci ** ** ** **

Xenon-137 Ci ** ** ** **

Xenon-13B Ci ** ** ** **

Iodines (1) lodine-131 Ci **

lodine-133 lodine-13S Ci Ci I

• • I .. I .. I **

I Particulates {1)

Chromium-S1 Ci .... .... ..

Manganese-S4 Ci Iron-SS Ci lron-S9 Ci Cobalt-SB Cobalt-60 Ci Ci Neodymium-147 Ci Zinc-6S Strontium-B9 Ci Ci ..

Stronium-90 Ci Niobium-9S Zirconium-9S Ci Ci ** .... ..

Molybdenum-99 Ci ** **

Ruthenium-103 Cesium-134 Ci Ci Cesium-136 Cesium-137 Ci Ci ..

Barium-140 Ci Lanthanum-140 Cerium-141 Ci Ci ** ..

Cerium-144 Ci ** **

Tritium {1) Ci I .. I **

I **

I ** I (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of 1.00E-04 µCi/ml for required noble gases, 1.00E-11 µCi/ml for required particulates and gross alpha, 1.00E-12 µCi/ml for required Iodines, 1.00E-11

µCi/ml for Sr-B9/90 and 1.00E-06 µCi/ml for Tritium, as required by the ODCM, has been verified.

(2) Contributions from purges are included. There were no other batch releases during the reporting period.

Table 1C ATTACHMENT 4 Page 1of2 Unit 1 Unit2 x ReE!orting Period: Janua!J£ - December 2016 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-133m Ci ** ** ** **

Xenon-135 Ci ** ** ** **

Xenon-135m Ci ** ** ** **

Xenon-137 . Ci ** ** ** **

Xenon-138 Ci ** ** ** **

Iodines (1) lodirie-131 Ci **

lodine-133 Ci ** ** **

lodine-135 Ci I ** I I ** I ** I Particulates (1 l Chromium-51 Ci .... ..

5.47E-05 ** ..

Manganese-54 Ci 4.02E-06 **

lron-55 lron-59 Ci Ci 8.74E-05 2.45E-04 **

Cobalt-58 Ci 7.86E-06 Cobalt-60 Ci 2.26E-05 2.52E-04 2.78E-05 1.54E-05 Neodymium-147 Zinc-65 Ci Ci ..

Strontium-89 Ci ** ** **

Strontium-90 Niobium-95 Ci Ci Zirconium-95 Molybdenum-99 Ci Ci

• • 2.55E-06 ..

Ruthenium-103 Cesium-134 Ci Ci ..

Cesium-136 Cesium-137 Ci Ci ..

4.09E-06 Barium-140 Ci Lanthanum-140 Ci **

Cerium-141 Ci ** **

Cerium-144 Ci ** ** **

Tritium (1} Ci I 3.01E+OO I 6.23E+OO I 7.93E+OO I 1.89E+01 I (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of 1.00E-04 µCi/ml for required noble gases, 1.00E-11 µCi/ml for required particulates and gross alpha, 1.00E-12 µCi/ml for required iodines, 1.00E -

11 µCi/ml for Sr-89/90 and 1.00E-06 µCi/ml for Tritium, as required by the ODCM, has been verified.

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

Table 1C ATTACHMENT 4 Page 2 of 2 Unit 1 Unit2 x Rei;iorting Period: Janua~ - December 2016 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Batch Mode Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Fission Gases 111 Ar-41 Ci Kr-85 Ci Kr-85m Kr-87 Ci Ci Kr-88 Xe-127 Ci Ci Xe-131m Xe-133 Ci Ci Xe-133m Ci Xe-135 Xe-135m Ci Ci .... ....

Xe-137 Xe-138 Ci Ci .. .. .. ..

Iodines (1) 1-131 Ci .... .... .... ......

I .. I .. I .. I 1-132 Ci 1-133 Ci I Particulates (1)

Cr-51 Ci Mn-54 Ci Fe-55 Fe-59 Ci Ci .... ....

Co-58 Ci Co-60 Ci Nd-147 Ci Zn-65 Sr-89 Ci Ci .... ....

Sr-90 Ci Nb-95 Ci Zr-95 Mo-99 Ci Ci Ru-103 Ci Cs-134 Cs-136 Ci Ci .... .... ....

Cs-137 Ba-140 Ci Ci .... .... .... ....

La-140 Ce-141 Ci Ci .... .... .. ..

Ce-144 Ci Tritium {1l Ci I .. I .. I .. I .. I (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double **.

Table2A ATTACHMENT 5 Page 1of2 Unit 1 Unit2 x ReQorting Period: Janua!Y - December 2016 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES (1) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Est. Total Error, %

A. 1-1ss1on & Act1vat1on t-'roaucts

1. Total Release (not including Tritium, Ci No Releases No Releases No Releases No Releases 5.00E+01 gases, alpha)

2. Average diluted concentration during

µCi/ml No Releases No Releases No Releases No Releases reporting period B. Tritium 1.Total release Ci No Releases No Releases No Releases No Releases 5.00E+01

2. Average diluted concentration during the

µCi/ml No Releases No Releases No Releases No Releases reporting period C. Dissolved and Entrained Gases

1. Total release Ci No Releases No Releases No Releases No Releases 5.00E+01

2. Average diluted concentration during the

µCi/ml No Releases No Releases No Releases No Releases reporting period D. Gross Al11ha Radioactivitll

1. Total release Ci No Releases No Releases No Releases No Releases 5.00E+01 E. Volumes

1. Prior to Dilution Liters No Releases No Releases No Releases No Releases 5.00E+01

2. Volume of dilution water used during Liters No Releases No Releases No Releases No Releases 5.00E+01 release period

3. Volume of dilution water available during Liters 1.18E+10 1.21E+10 1.23E+10 1.22E+10 5.00E+01 reporting period F. Percent of Tech. S11ec. Limits Percent of Quarterly Whole Body Dose Limit

% O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO (1.5 mrem)

Percent of Annual Whole Body Dose Limit to

% O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Date (3 mrem)

Percent of Quarterly Organ Dose Limit (5

% O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO mrem)

Percent of Annual Organ Dose Limit to Date

% O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO (10 mrem)

Percent of 10CFR20 Concentration Limit (2),

% O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO (3)

Percent of Dissolved or Entrained Noble Gas

% O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Limit (2.00E-04 µCi/ml)

(1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of 5.00E-07 µCi/ml for required gamma emitting nuclides, 1.00E-05 µCi/ml for required dissolved and entrained noble gases and tritium, 5.00E-08

µCi/ml for Sr-89/90, 1.00E-06 µCi/ml for 1-131 and Fe-55, and 1.00E-07 µCi/ml for gross alpha radioactivity, as required by the Off-Site Dose Calculation Manual (ODCM), has been verified.

(2) The percent of 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 (MEG) numerically equal to ten times the 10CFR20.1001 - 20.2402 concentrations were adopted to evaluate liquid effluents.

Table 28 ATTACHMENT 5 Page 2 of2 Unit 1 Unit2 x Re(!orting Period: Janua!Jl - December 2016 LIQUID EFFLUENTS RELEASED Batch Mode (1),(2)

Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Nuclides Released Strontium-89 Ci No Releases No Releases No Releases No Releases Strontium-90 Ci No Releases No Releases No Releases No Releases Cesium-134 Ci No Releases No Releases No Releases No Releases Cesium-137 Ci No Releases No Releases No Releases No Releases lodine-131 Ci No Releases No Releases No Releases No Releases Cobalt-58 Ci No Releases No Releases No Releases No Releases Cobalt-60 Ci No Releases No Releases No Releases No Releases lron-59 Ci No Releases No Releases No Releases No Releases Zinc-65 Ci No Releases No Releases No Releases No Releases Manganese-54 Ci No Releases No Releases No Releases No Releases Chromium-51 Ci No Releases No Releases No Releases No Releases Zirconium-95 Ci No Releases No Releases No Releases No Releases Niobium-95 Ci No Releases No Releases No Releases No Releases Molybdenum-99 Ci No Releases No Releases No Releases No Releases Technetium-99m 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 Tungsten-187 Ci No Releases No Releases No Releases No Releases Arsenic-76 Ci No Releases No Releases No Releases No Releases lodine-133 Ci No Releases No Releases No Releases No Releases lron-55 Ci No Releases No Releases No Releases No Releases Neptunium-239 Ci. No Releases No Releases No Releases No Releases Silver-110m Ci No Releases No Releases No Releases No Releases Gold-199 Ci No Releases No Releases No Releases No Releases Cerium-144 Ci No Releases No Releases No Releases No Releases Cesium-136 Ci No Releases No Releases No Releases No Releases Copper-64 Ci No Releases No Releases No Releases No Releases Dissolved or Entrained Gases Ci I No Releases I No Releases I No Releases I No Releases I Tritium Ci I No Releases I No Releases I No Releases I No Releases I (1) No 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 5.00E-07 µCi/ml for required gamma emitting nuclides, 1.00E-05 µCi/ml for required dissolved and entrained noble gases and tritium, 5.00E-08

µCi/ml for Sr-89/90, 1.00E-06 µCi/ml for 1-131 and Fe-55, and 1.00E-07 µCi/ml for gross alpha radioactivity, as identified in the ODCM, has been verified.

Table 3 ATTACHMENT 6 Page 1 of 4 Unit 1 Unit2 x Re~orting Period: Janua!Jl - December 2016 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A1. TYPE Volume Activi~ (1)

(m3) (Ci)

Class Class A B c A B c a.1 Spent Resin (Dewatered) 4.90E+01 O.OOE+OO 0.00E+OO 1.06E+02 O.OOE+OO O.OOE+OO a.2 Filter Sludge O.OOE+OO 9.91E-01 O.OOE+OO O.OOE+OO 5.93E+01 O.OOE+OO a.3 Concentrated Waste O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO Totals 4.90E+01 9.91E-01 O.OOE+OO 1.06E+02 5.93E+01 O.OOE+OO b.1 Dry Compressible Waste 1.13E+03 O.OOE+OO O.OOE+OO 1.39E+01 O.OOE+OO O.OOE+OO b.2 Dry Non-Compressible Waste (Contaminated O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Equipment)

Totals 1.13E+03 O.OOE+OO O.OOE+OO 1.39E+01 0.00E+OO O.OOE+OO

c. Irradiated Components, O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Control Rods, etc.

d. Other (to vendor for processing)

Oily Waste 1.43E+01 O.OOE+OO O.OOE+OO 2.00E-02 O.OOE+OO O.OOE+OO (1) The estimated total error is 5.0E+01%.

Table 3 ATTACHMENT 6 Page 2 of 4 Unit 1 Unit 2 x Reporting Period: January - December 2016 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A1. TYPE Container Package Solidification Agent a.1 Spent Resin (Dewatered) Poly Liner General Design None a.2 Filter Sludge Poly Liner Type B None b.1 Dry Compressible Waste Seavan General Design None b.2 Dry Non-Compressible Waste (contaminated N/A N/A N/A equipment)

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

d. Other (To vendor for processing)

Oil/Aqueous Liquid 20' Pan Van (Metal box) General Design None

Table 3 ATTACHMENT 6 Page 3 of 4 Unit 1 Unit 2 x Re12orting Period: Janua!l! - December 2016 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 1.72% 2.85E+OO Fe-55 29.26% 4.85E+01 Co-60 62.79% 1.04E+02 Ni-63 2.07% 3.43E+OO Zn-65 2.43% 4.04E+OO

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

Nuclide Percent Curies Mn-54 1.25% 1.73E-01 Fe-55 70.66% 9.81E+OO Co-60 26.93% 3.74E+OO

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

Nuclide Percent N/A N/A

d. Other: (To vendor for processing)

1. Oil

2. Aqueous Liquid Nuclide Percent Curies Mn-54 1.20% 2.40E-04 Fe-55 70.28% 1.40E-02 Co-60 27.43% 5.48E-03

Table 3 ATTACHMENT 6 Page 4 of 4 Unit 1 Unit2 x Re12orting Period: Janua!Y - December 2016 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A3. SOLID WASTE DISPOSITION Number of Shi1:1ments Mode of Trans1:1ortation Destination 28 Truck.highway Bear Creek 10 Truck, highway Clive B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shi1:1ments Mode of Trans1:1ortation Destination 0 N/A N/A D. SEWAGE WASTES SHIPPED TO A TREATMENT FACILITY FOR PROCESSING AND BURIAL There are no shipments of sewage sludge with deteclible quantities of plant-related nuclides from NMP to the treatment facility during the reporting period.

ATTACHMENT 7 Page 1 of 1 Unit 1 Unit2 x Re1;1orting Period: Janua!)!- December 2016

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 New/Amended Page# Description of Change Reason For Change Section#

REVISION XX New/Amended Page# Description of Change Reason For Change Section#

ATTACHMENT 8 Page 1 of 1 Unit 1 Unit2 x Reporting Period: January - December 2016

SUMMARY

OF CHANGES TO THE PROCESS CONTROL PROGRAM (PCP)

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

ATTACHMENT 9 Page 1 of 1 Unit 1 Unit2 x ReE!orting Period: JanuaQ'. - December 2016

SUMMARY

OF NON-FUNCTIONAL MONITORS Dates Monitor was Monitor Cause and Corrective Actions Non-Functional 2LWS-CAB206, January 1, 2016 to No liquid waste discharges were performed during 2016, and therefore, these 2LWS-FT330 & December 31, 2016 monitors were not returned to service. The discharge manual isolation 2LWS-FT331, valves, 2LWS-V420 and 2LWS-V422, are locked closed during inoperable Liquid Waste periods, therefore, no inadvertent discharge can occur. Reference Equipment Discharge Monitor Status Log (ESL) 2010-0243.

20FG-AT168 Offgas August18, 2016to On August 18, 2016, Off Gas Hydrogen Analyzer 20FG-AT16B was found Hydrogen Monitor November 18, 2016 failed during rounds. Trouble shooting determined the analyzer cell failed.

Due to obsolescence, a useable replacement cell had a long lead time. The cell was replaced and tested satisfactorily on November 11, 2016. Reference Equipment Status Log (ESL) 2016-0171.

ATTACHMENT 10 Page 1of5 Unit 1 Unit2_X_ Reporting Period: Januarv - December 2016 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 2016.

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 I, 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, 200 I 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 2016 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 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 NMP2 Stack and Radwaste/Reactor Building Vent.

• Direct radiation pathway; dose resulting from the operation ofNine Mile Point Unit 1 (NMPl), NMP2 and the James A. Fitzpatrick Nuclear Power Plant (JAFNPP) Facilities.

Methodologies for Determining Dose for Applicable Pathways External Ground (Shoreline Sediment) Pathway Dose from the external ground (shoreline sediment) is based on the methodology in the NMP2 Offsite Dose Calculation Manual (ODCM) as adapted from Regulatory Guide I. I 09. For this evaluation it is assumed that the hypothetical maximum exposed individual fished from the shoreline at all times.

ATTACHMENT 10 Page 2 of 5 Unit 1 Unit2_X_ Reporting Period: Januarv- December 2016 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY The total dose received by the whole body and skin of the maximum exposed individual during 2016 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.lSE-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 L 109. The total whole body dose and organ dose received by the hypothetical maximum exposed fisherman during 2016 calculated using the following input parameters for gaseous effluents released from both the NMP2 Stack and Radwaste/Reactor Building Vent for the time period exposure is received:

NMP2Stack:

I Variable Fisherman XIQ (s/m3 ) 9.6 E-07 Inhalation dose factor Table E-7, Regulatory Guide 1.109 Annual air intake (m3/year) (adult) 8000 Fractional portion of the year 0.0356 H-3 (pCi/sec) 1.58 E+06 C-14 (pCi/sec) 2 5.47E+05 Mn-54 (pCi/sec) 5.03E-01 Co-60 (pCI/sec) 2.87E+OO Zn-65 (pCi.sec) 2.77E-01 1-131 (pCi/sec) 4.18E+OO 1-133.(pCi/sec) 3.85E+Ol

ATTACHMENT 10 Page 3 of 5 Unit 1 Unit2_X_ Reporting Period: Januarv- December 2016 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY NMP2 Radwaste/Reactor Building Vent:

Variable Fisherman 1 3 2.8 E-06 X/Q (s/m )

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) l.40E+06 Cr-51 (pCi/sec) 2.32E+OO Mn-54 (pCi/sec) l.70E-OI Fe-55 (pCi/sec) l.04E+OI Co-58 (pCi/sec) 3.33E-OI Co-60 (pCi/sec) l.25E+OI Mo-99 (pCi/sec) l.08E-OI Cs-137(pCi/sec) l.73E-OI

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.

ATTACHMENT 10 Page 4 of 5 Unit 1 Unit2_X_ Reporting Period: January - December 2016 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY 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 Thermo luminescent Dosimeters (TLDs). Since fishing activities occur between April 1 and December 31, TLD data for the second, third, and fourth quarters of 2016 from TLDs placed in the general area where fishing once occurred were used to determine an average dose to the hypothetical maximum exposed fisherman from direct radiation. The following is a summary of the average dose rate and assumed time spent on site used to determine the total dose received:

Variable Fisherman Average Dose Rate (mRem/hr) l.ISE-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 During 2016 The following is a summary of the dose received by a hypothetical maximum exposed fisherman from liquid and gaseous effluents released from NMP2 during 2016:

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

Whole Body l.SOE-03 External Ground Skin of Whole Body 2.IOE-03 Whole Body 3.09E-04 Inhalation Maximum Organ Bone: 3.40 E-04 Thyroid 3.13E-04 Direct Radiation Whole Body 0.37

ATTACHMENT 10 Page 5 of 5 Unit 1 Unit2_X_ Reporting Period: Januarv- December 2016 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:

TABLE2 Annual Dose Summary Fisherman Total Annual Dose for 2016 (mrem)

Total Whole Body 3.72E-01 Skin of Whole Body 2.lOE-03 Maximum Organ Bone: 3.40 E-04 Thyroid 3.13E-04

ATTACHMENT 11 Page 1of5 Unit 1 Unit2_X__ Reporting Period: January - December 2016 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 2016 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 ofNMPl, 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:

• < 25 mRem whole body

• < 25 mRem any organ (except thyroid)

• < 75 mRem thyroid This evaluation compares doses resulting from liquid and gaseous effluents and direct radiation originating from the site as a result of the operation of the NMPl, NMP2 and JAFNPP nuclear facilities.

Dose Pathways Dose pathways considered for this evaluation included doses resulting from liquid effluents, gaseous effluents and direct radiation from all nuclear operating facilities located on the Nine Mile Point site.

Dose to the likely most exposed Member of the 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 NMPl, NMP2 and JAFNPP operating facilities.

• Direct Radiation pathway; radiation dose resulting from the operation ofNMPl, Nl\1P2 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 NMPl Off-Site Dose Calculation Manual (ODCM) as adapted from Regulatory Guide 1.109. The dose for 2016 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 2016; therefore, no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2016.

ATTACHMENT 11 Page 2 of 5 Unit 1 Unit2_X__ Reporting Period: Januarv - December 2016 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Vegetation Consumption Dose received as a result of vegetation consumption is based on the methodology specified in the NMPl ODCM as adapted from Regulatory Guide 1.109. The dose for 2016 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 2016; therefore, no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2016.

For estimating C-14, dose received as a result of vegetation consumption is based on the methodology specified in the NMPl ODCM as adapted from Regulatory Guide 1.109. The estimated concentration ofC-14 in vegetation is based on the estimated concentration of C-14 in plant gaseous effluents.

Shoreline Sediment Dose received from shoreline sediment is based on the methodology in the NMPl ODCM as adapted from Regulatory Guide 1.109. For this evaluation it is assumed that the most likely exposed Member of the Public spends 67 hour7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br />s/year along the shoreline for recreational purposes.

No radionuclides were detected in shoreline sediment samples collected and analyzed during 2016; therefore no dose was received by the whole body and organs of the likely most exposed Member of the Publlc during 2016.

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 NMPl ODCM, NMP2 ODCM, and the JAFNPP ODCM. These calculations consider deposition, inhalation and ingestion pathways. Actual meteorological data was used to calculate doses to the likely most exposed Member of the Public. The total sum of doses resulting from gaseous effluents from NMPl, NMP2 and JAFNPP during 2016 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 2016 Annual Radiological Effluent Release Reports (ARERRs). The C-14 production and effluent source term estimates were based on EPRl methodology provided in EPRl 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 2016 ARERR.

EPRI methodology for estimating C-14 production rates in Boiling Water Reactors (BWRs):

For BWRs, EPRl 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.

ATTACHMENT 11 Page 3 of 5 Unit 1 Unit2_X__ Reporting Period: January - December 2016 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY For NMPl and NMP2, C-14 gaseous dose calculations in the site ARERR are made using the following assumptions for each unit: (1) continuous release of the estimated C-14 generated during power operation based on the number of Effective Full Power Days (EFPDs) for the period, (2) maximum 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 ofC-14, PRMAX* for each BWR unit.

PRMAX 5.1

• MWT I lUUU {./!,'q lj 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-J-1, into the gaseous pathway during the time period for each BWR unit.

A C-1./ PR MAX

• 0.99

• EFPD I 365, Ci (for time period) [Eq2]

Where:

PR MAX maximum annual production rate of C-14 0.99 fraction ofC-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

ATTACHMENT 11 Page 4 of 5 Unit 1 Unit2_X__ Reporting Period: Januarv - December 2016 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-l./, co2 , into the gaseous pathway during the time period for each BWR unit.

A C-1./, C02 PR MAX

• 0.99

• 0.95

• EFPD I 365, Ci (for time period) [Eq3}

Where:

PR MAX 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 2016 estimated C-14 activity releases (total and carbon dioxide chemical form) are summarized in Table 1.

Table 1 2016 BWR Estimated C-14 Gaseous Releases Gaseous C0 2 Form Max.Annual 2016 Total Release 2016 C02 Release BWR Release Release EFPD Operation Prod. Rate (Eq 2) (Eq 3)

Fraction<*> Fraction(b) (Eq 1) 362.l EFPD NMPl 0.99 0.95 9.44 Ci/yr 9.27 Ci 8.80 Ci (98:9%)

328.1 EFPD NMP2 0.99 0.95 20.34 Ci/yr<<l 18.1 Ci 17.2 Ci (89.7%)

296.4 EFPD JAFNPP 0.99 0.95 12.93 Ci/yr 10.4 Ci 9.88 Ci (81.0%)

(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.

ATTACHMENT 11 Page 5 of 5 Unit 1 Unit 2 X Reporting Period: January - December 2016 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Direct Radiation Pathway Dose as a result of* direct gamma radiation from the site, encompasses doses from direct "shine" from the generating facilities, direct radiation from any overhead gaseous plumes, plume submersion, and ground deposition. This total dose is measured by 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 2016, the closest residence and the critical downwind residence are at the same location.

Table2 Dose Potentially Received by the Likely Most Exposed Member of the Public Outside the Site Boundary During 2016 Exposure Pathway Dose Type Dose (mrem)

Total Whole Body No Dose Fish and Vegetation Consumption Total Maximum Organ No Dose Total Whole Body No Dose Shoreline Sediment Total Skin of Whole Body No Dose Total Whole Body 5.86 E-03 Gaseous Effluents Thyroid 1.20 E-02 (excluding C-14)

Maximum Organ Thyroid: 1.20 E-02 Gaseous Effluent Total Whole Body 3.50 E-01 (C-14) Maximum Organ Bone: 1.75 E+OO Direct Radiation Total Whole Body 0.92 Based on these values the maximum total annual dose potentially received by the likely most exposed Member of the Public during 2016 is as follows:

• Total Whole Body: 1.28 E+OO mrem

• Total Thyroid: 1.20 E-02

• Maximum Organ: Bone: 1.75 E+OO mrem 40 CFR 190 Evaluation The maximum total doses presented in this attachment are the result of operations at the NMP 1, NMP2 and the JAFNPP facilities. The maximum organ dose (Bone: 1.75 mrem), maximum thyroid dose (0.012 mrem) and the maximum whole body dose (1.28 mrem) are below the 40 CFR 190 criteria of 25 mrem per calendar year to the maximum exposed organ or the whole body, and below 75 mrem per calendar year to the thyroid.

ATTACHMENT 12 Page 1of1 Unit2 _x_

Unit 1

-- Re11orting Period: Janua!:JI:

• December 2016

\/\(ell Identification #Samples Minimum Maximum

1. Positive Samples Number Collected Concentration (pCi/I) Concentration (pCi/I)

GMX-MW1* 4 0 <161 <198 MW-1 4 0 <157 <206 MW-5 4 0 <160 <213 MW-6 4 0 <156 <212 MW-7 4 0 <162 <209 MW-8 4 1' 160 <195 1

MW-9 4 1 <175 220 1

MW-10 4 0 <175 <200 MW-11 4 0 <166 <198 MW-12 4 0 <108 <198 MW-13 4 0 <173 <200 MW-14* 4 0 <170 <199 MW-15 4 4 251 429 MW-16 4 0 <108 <199 MW-17 4 2 <108 261 MW-18 4 0 <172 <192 MW-19 4 0 <173 <203 MW-20 4 0 <109 <202 MW-21 4 1 <176 368 23 NMP2 MAT ' 4 3 <147 201 PZ-1 4 0 <155 <205 PZ-2 4 0 <159 <197 PZ-3

• 4 0 <149 <212 PZ-4 4 4 199 233 PZ-5 4 4 213 323 PZ-6 4 3 232 292 PZ-7 4 4 496 749 PZ-8 4 0 <157 <204 PZ-9* 4 0 <154 . <205 Notes: * - Control Location 1

- Sentinel well location 2

- NMP2 Groundwater Depression Cone 3

- Samples collected from storm drain system which includes precipitation

ATTACHMENT 13 Page 1 of 1 Unit 1 Unit2 x Reporting Period: January - December 2016 Off-Site Dose Calculation Manual (QDCM)

There was no revision to the Off-Site Dose Calculation Manual for 2016.

ATTACHMENT 14 Page 1 of 1 Unit 1 Unit2 x Reporting Period: January- December 2016 Process Control Program <PCP)

There were no changes to the Process Control Program in 2016.

Enclosure 3 Errata/Correction to the 2015 Annual Radioactive Effluent Release Report Errata/Correction to the 2015 ARERR The following identifies each piece of errata data that has been identified within the previous year. The following pages reflect the affected original submitted pag~ and the edited page. The edited page contains revision bars to track the changes. At the top of each page, the year of the appropriate report is outlined. The errors in the report are inconsequential. The Station Corrective Action Program was utilized to capture these errors and to provide a tracking mechanism to correct the data from the 2015 Radiological Effluent Release Report.

Changes are made to Attachment 14 Process Control Program (PCP). Procedure RW-AA-101 was revised to clarify the definitions of Blending, Classification Controlling Nuclides, Concentration Averaging, Homogeneous Waste, Mixable Waste, and Nuclides of Concern. The revision also updates the references to NRC-2011-0022 and adds station specific UFSAR references.

ATTACHMENT 14 Page 1of1 Unit 1 x Unit2 Reporting Period: January - December 2015 Process Control Program (PCP)

Changes to the Process Control Program in 2015 are as follows:

Procedure RW-AA-101 was revised to clarify the definitions of Blending, Classification Controlling Nuclides, Concentration Averaging, Homogeneous Waste, Mixable Waste, and Nuclides of Concern. The revision also

, updates the references to NRC-2011-0022 and adds station specific UFSAR references.

ATTACHMENT 14 Page 1of1 Unit 1 Unit2 x Reporting Period: January - December 2015 Process Control Program (PCP)

Changes to the Process Control Program in 2015 are as follows:

Procedure RW-M-101 was revised to clarify the definitions of Blending, Classification Controlling Nuclides, Concentration Averaging, Homogeneous Waste, Mixable Waste, and Nuclides of Concern. The revision also updates the references to NRC-2011-0022 and ;:idds station specific UFSAR references.