Text

Radioactive Effluent Release Report for 2015
	ML16132A077
Person / Time
Site:	Nine Mile Point
Issue date:	05/02/2016
From:	Orphanos P; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NMP1L3082
	Download: ML16132A077 (67)
	v • d • e

/ Exelon Generatio*n NMP1L 3082 May 2, 2016 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Nine Mile Point Nuclear Station, Units 1 and 2 10 CFR 50.36a Technical Specifications Renewed Facility Operating License Nos. DPR-63 and NPF-69 NRG Docket Nos. 50-220 and 50-410

Subject:

2015 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 2015.

The format used for the effluent data is outlined in Appendix 8 of Regulatory Guide 1.21, Revision 1. During the reporting period, NMP1 and NMP2 did not exceed any 1 O CFR 20, 1 O CFR 50, Technical Specification, or ODCM limits for gaseous or liquid effluents.

Should you have questions regarding the information in this submittal, please contact Jeffrey W.

Gerber, Site Chemistry Environmental & Radwaste Manager, at (315) 349-4264.

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

Enclosures:

(1)

Nine Mile Point Nuclear Station, Unit 1 Radioactive Effluent Release Report, January - December 2015 (2)

Nine Mile Point Nuclear Station, Unit 2 Radioactive Effluent Release Report, January - December 2015

Document Control Desk May 2, 2016 Page 2 Cc:

NRG Regional Administrator, Region 1 NRG Project Manager NRG Resident Inspector C. Graves, NRG Nine Mile Point Nuclear Station, Unit 1 Radioactive Effluent Release Report, January - December 2015 Nine Mile Point Nuclear Station, Unit 2 Radioactive Effluent Release Report, January - December 2015

NINE MILE POINT NUCLEAR STATION - UNIT 2 RADIOACTIVE EFFLUENT RELEASE REPORT January-'December 2015

Page 1 of2 NINE MILE POINT NUCLEAR STATION - UNIT 2 RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECElVIBER 2015 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 TOT AL RADIOACTIVITY Described below are the methods used to measure or approximate the total radioactivity and radionuclide composition in effluents.

A)

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

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 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 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 of required meteorological data on site in a file that shall be provided to the NRC upon request.

Supplemental Information ATTACHMENT 1

SUMMARY

DATA Page 1 of2 Unit 1 Unit2 x

Re~orting Period: Janua!l'.- December 2015 Liquid Effluents:

ODCM Required Maximum Effluent Concentration (MEC) = 10x10CFR20.1001 - 20.2402, Appendix B, Table 2, Column 2 Average MEC - µCi/ml (Qtr. 1) =

I NO RELEASES Average MEC - µCi/ml (Qtr..ID =

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 =

3.43E-01 E~ =

1.83E-01 Qrtr. g:

~v =

NIA E~ =

N/A Qrtr. ;i:

~v =

N/A E~ =

N/A Qrtr. ~:

Ey =

N/A E~ =

N/A Liquid:

Number of Batch Releases 0

Total Time Period for Batch Releases (hrs) 0.0 Maximum Time Period for a Batch Release (hrs) 0.0 Average Time Period for a Batch Release (hrs) 0.0 Minimum Time Period for a Batch Release 0.0 Total volume of water used to dilute the liquid 1st 2nd 3rd 4th during the release period (L)

NIA N/A I

N/A I

Total volume of water available to dilute the liquid 1st 2nd 3rd 4th effluent during the report period (L) 1.16E+10 1.24E+10 I 1.31E+10 I 1.23E+10 I Gaseous (Emergency Condenser Vent) "Not applicable for Unit 2" Number of Batch Releases N/A Total Time Period for Batch Releases (hrs)

N/A Maximum Time Period for a Batch Release (hrs)

N/A Average Time Period for a Batch Release (hrs)

N/A Minimum Time Period for a Batch Release N/A Gaseous (Primary Containment Purge)

Number of Batch Releases 10 Total Time Period for Batch Releases (hrs) 523.1 Maximum Time Period for a Batch Release (hrs) 140.9 Average Time Period for a Batch Release (hrs) 52.3 Minimum Time Period for a Batch Release (hrs) 6.5

Supplemental Information Unit 1 Unit2 x

Abnormal Releases:

A. Liquids:

I Number of Releases

!Total Activity Released B. Gaseous:

I Number of Releases

!Total Activity Released I

I I

I ATTACHMENT 1

SUMMARY

DATA 0

I N/A ICL 0

I NIA I Ci Page 2 of 2 Re1;1orting Period: Janua[l,! - December 2015

Table 1A Gaseous Effluents -

Summation of All Releases -

Elevated and Ground Level Unit 1 Unit2 ATTACHMENT 2 Page 1of1 x

Re(!orting Period: Janua!'.l(- December 2015 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 1.63E+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.00E+01

2.

Average Release Rate

µCi/sec 2.09E-01 O.OOE+OO O.OOE+OO O.OOE+OO B. Iodines

1.

Total Iodine - 131 Ci 1.15E-04 8.17E-05 2.64E-04 1.72E-04 3.00E+01

2.

Average Release Rate for Period

µCi/sec 1.94E-05 1.04E-05 3.36E-05 2.18E-05 C. Particulates

1.

Particulates with Half-lives>8days Ci 5.02E-04 1.47E-04 1.64E-04 6.44E-04 3.00E+01

2.

Average Release Rate for Period

µCi/sec 7.05E-05 1.88E-05 2.09E-05 8.18E-05

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 7.71E+OO 1.37E+01 1.13E+01 1.08E+01 5.00E+01

2.

Average Release Rate for Period

µCi/sec 1.20E+OO 1.75E+OO 1.44E+OO 1.37E+OO E. Percent of Tech. S11ec. Limits Fission and Activation Gases Percent of Quarterly Gamma Air Dose Limit 1.17E-03 O.OOE+OO O.OOE+OO O.OOE+OO (5mR)

Percent of Quarterly Beta Air Dose Limit (10 3.29E-05 O.OOE+OO O.OOE+OO O.OOE+OO mrad)

Percent of Annual Gamma Air Dose Limit to 5.83E-04 5.83E-04 5.83E-04 5.83E-04 Date (10 mR)

Percent of Annual Beta Air Dose Limit to 1.65E-05 1.65E-05 1.65E-05 1.65E-05 Date (20 mrad)

Percent of Whole Body Dose Rate Limit (500 4.47E-05 O.OOE+OO O.OOE+OO O.OOE+OO mrem/yr)

Percent of Skin Dose Rate Limit (3000 9.11E-06 O.OOE+OO O.OOE+OO O.OOE+OO mrem/yr)

Tritium, Iodines, and Particulates (with half-lives greater than 8 dalls}

Percent of Quarterly Dose Limit (7.5 mrem) 5.47E-02 2.65E-02 7.28E-02 5.39E-02 Percent of Annual Dose Limit to Date (15 2.73E-02 4.06E-02 7.70E-02 1.04E-01 mrem)

Percent of Organ Dose Limit (1500 mrem/yr 1.11E-03 5.32E-04 1.44E-03 1.09E-03

Table 1 B Gaseous ATTACHMENT 3 Page 1 of2 Effluents - Elevated Releases Unit 1 Unit2 x

Re12orting Period: Janua[ll-December 2015 GASEOUS EFFLUENTS - ELEVATED RELEASE Continuous Mode (2)

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

Argon-41 Ci Krypton-85 Ci Krypton-85m.

Ci Krypton-87 Ci Krypton-88 Ci Xenon-127 Ci Xenon-131m Ci Xenon-133 Ci 7.33E-02 Xenon-133m Ci Xenon-135 Ci 6.29E-01 Xenon-135m Ci 9.27E-01 Xenon-137 Ci Xenon-138 Ci Iodines (1) lodine-131 Ci 1.12E-04 8.17E-05 1.79E-04 1.59E-04 lodine-133 Ci 1.17E-03 9.92E-04 2.67E-03 2.59E-03 lodine-135 Ci Particulates (1 l Chromium-51 Ci Manganese-54 Ci 1.14E-06 1.97E-06 lron-55 Ci 2.86E-05 6.18E-05 lron-59 Ci Cobalt-58 Ci 5.34E-06 Cobalt-60 Ci 9.26E-05 1.20E-05 2.03E-05 1.34E-04 Neodymium-147 Ci Zinc-65 Ci 2.87E-05 Strontium-89 Ci Strontium-90 Ci Niobium-95 Ci Zirconium-95 Ci Molybdenum-99 Ci Ruthenium-103 Ci Cesium-134 Ci Cesium-136 Ci Cesium-137 Ci 3.55E-05 2.40E-06 Barium-140 Ci Lanthanum-140 Ci Cerium-141 Ci Cerium-144 Ci Tritium (1)

Ci I

5.23E+OO I 8.08E+OO I 8.77E+OO I 8.72E+OO 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 of2 Unit 1 Unit2 x

Regorting Period: Janua!Jl - December 2015 GASEOUS EFFLUENTS - ELEVATED RELEASE Batch Mode (2)

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

Argon-41 Ci Krypton-B5 Ci Krypton-B5m Ci Krypton-B7 Ci Krypton-BB Ci Xenon-127 Ci Xenon-131m Ci Xenon-133 Ci Xenon-133m Ci Xenon-135 Ci Xenon-135m Ci Xenon-137 Ci Xenon-13B Ci Iodines (1) lodine-131 Ci I

I I

lodine-133 Ci lodine-135 Ci Particulates (1}

Chromium-51 Ci Manganese-54 Ci lron-55 Ci lron-59 Ci Cobalt-5B Ci Cobalt-60 Ci Neodymium-147 Ci Zinc-65 Ci Strontium-B9 Ci Stronium-90 Ci Niobium-95 Ci Zirconium-95 Ci Molybdenum-99 Ci Ruthenium-103 Ci Cesium-134 Ci Cesium-136 Ci Cesium-137 Ci Barium-140 Ci Lanthanum-140 Ci Cerium-141 Ci Cerium-144 Ci Tritium (1}

Ci I

I I

(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

Re11orting Period: Janua!:Ji!- December 2015 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode (2)

Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Fission Gases (1l Argon-41 Ci Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-127 Ci Xenon-131m Ci Xenon-133 Ci Xenon-133m Ci Xendn-135 Ci Xenon-135m Ci Xenon-137 Ci Xenon-138 Ci Iodines (1l lodine-131 Ci 3.10E-06 8.45E-05 1.31E-05 lodine-133 Ci 2.52E-04 3.24E-06 4.33E-05 lodine-135 Ci Particulates (1l Chromium-51 Ci 1.95E-05 Manganese-54 Ci 6.69E-06 5.22E-06 6.33E-06 lron-55 Ci 4.73E-05 4.18E-05 2.18E-04 lron-59 Ci Cobalt-58 Ci 1.27E-06 4.15E-06 2.73E-06 Cobalt-60 Ci 2.88E-04 8.40E-05 9.40E-05 1.79E-04 Neodymium-147 Ci Zinc-65 Ci 8.36E-06 Strontium-89 Ci Strontium-90 Ci Niobium-95 Ci Zirconium-95 Ci Molybdenum-99 Ci Ruthenium-103 Ci Cesium-134 Ci Cesium-136 Ci Cesium-137 Ci 2.00E-05 6.00E-06 Barium-140 Ci Lanthanum-140 Ci Cerium-141 Ci Cerium-144 Ci Tritium (1)

Ci I 2.48E+OO I 5.66E+OO I 2.51E+OO I 2.10E+OO 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

Re(!orting Period: Janua[ll'.- December 2015 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Batch Mode Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Fission Gases C1l Ar-41 Ci Kr-85 Ci Kr-85m Ci Kr-87 Ci Kr-88 Ci Xe-127 Ci Xe-131m Ci Xe-133 Ci Xe-133m Ci Xe-135 Ci Xe-135m Ci Xe-137 Ci Xe-138 Ci Iodines (1) 1-131 Ci I I

I I

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

Cr-51 Ci Mn-54 Ci Fe-55 Ci Fe-59 Ci Co-58 Ci Co-60 Ci Nd-147 Ci Zn-65 Ci Sr-89 Ci Sr-90 Ci Nb-95 Ci Zr-95 Ci Mo-99 Ci Ru-103 Ci Cs-134 Ci Cs-136 Ci Cs-137 Ci Ba-140 Ci La-140 Ci Ce-141 Ci Ce-144 Ci Tritium (1)

Ci I

I I

(1) Concentrations less than the lower limit of detectior:i of the counting system used are indicated with a double**.

Table2A ATTACHMENT 5 Page 1of2 Unit 1 Unit2 x

ReE!orting Period: Janua!Jl - December 2015 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES (1) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Est. Total Error, %

A. Fission & Activation Products

1. Total Release (not including Tritium, Ci 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 Alr;iha 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 during Liters 1.16E+10 1.24E+10 1.31E+10 1.23E+10 5.00E+01 reporting period F. Percent of Tech. Sr;iec. 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 1 OCFR20 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 1 OCFR20 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.

Table28 ATTACHMENT 5 Page 2 of 2 Unit 1 Unit 2 x

Re[!orting Period: JanuaQ!- December 2015 LIQUID EFFLUENTS RELEASED Batch Mode (1),(2)

Nuclides Released 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Nuclldes 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 Release~ 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 Release_s 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

Rei;iorting Period: Janua!Jl - December 2015 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A1. TYPE Volume Activi~ (1}

(ma)

(Ci)

Class Class A

B c

A B

c a.1 Spent Resin (Dewatered) 4.90E+01 O.OOE+OO O.OOE+OO 7.96E+01 O.OOE+OO O.OOE+OO a.2 Filter Sludge O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO a.3 Concentrated Waste O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Totals 4.90E+01 O.OOE+OO 0.00E+OO 7.96E+01 O.OOE+OO O.OOE+OO b.1 Dry Compressible Waste 1.09E+02 O.OOE+OO O.OOE+OO 3.07E+01 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 1.09E+02 O.OOE+OO O.OOE+OO 3.07E+01 O.OOE+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 and Underwater 1.79E+01 O.OOE+OO O.OOE+OO 1.48E+01 O.OOE+OO O.OOE+OO Demineralizer (1) The estimated total error is 5.0E+01 %.

Table 3 ATTACHMENT 6 Page 2 of 4 Unit 1 Unit2 x

Reporting Period: January - December 2015 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 NIA NIA NIA 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)

Oily Waste Sea van General Design None Underwater Demineralizer Cask General Design None

Table 3 ATTACHMENT 6 Page 3 of 4 Unit 1 Unit2 x

Re1;1orting Period: Janua!Jl - December 2015 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE)

a. Spent Resins, Filter Sludges, Concentrated Waste Nuclide Percent Curies H-3 1.25%

1.01E+OO C-14 1.10%

8.91E-01 Mn-54 3.73%

3.01E+OO Fe-55 33.47%

2.70E+01 Co-60 56.08%

4.53E+01 Zn-65 3.23%

2.61E+OO

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

Nuclide Percent Curies Cr-51 2.52%

7.74E-01 Mn-54 3.42%

1.05E+OO Fe-55 65.94%

2.03E+01 Fe-59 1.03%

3.16E-01 Co-60 24.48%

7.52E+OO

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

Nuclide Percent N/A N/A

d. Other: (To vendor for processing)

1. Oily Waste

2. Underwater Demineralizer Nuclide Percent Curies Mn-54 1.81%

2.68E-01 Fe-55 74.92%

1.11E+01 Co-60 21.10%

3.13E+OO

Table 3 ATTACHMENT 6 Page 4 of 4 Unit 1 Unit2 x

Re12orting Period: Janua!'.ll - December 2015 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A3. SOLID WASTE DISPOSITION Number of ShiQments Mode of TransQortation Destination 10 Hittman Transport TN Energy Solutions Services INC (CVRF) 10 Hittman Transport TN Energy Solutions LLC (Clive)

B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of ShiQments Mode of TransQortation 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 detectible 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

Re(!orting Period: JanuaD£- December 2015

SUMMARY

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

The Unit 2 Off-Site Dose Calculation Manual (ODCM) was not revised during the reporting period.

REVISION XX Page#

New/Amended Description of Change Reason For Change Section#

REVISION XX Page#

New/Amended Description of Change Reason For Change Section#

ATTACHMENT 8 Page 1 of 1 Unit 1 Unit2 x

Reporting Period: January - December 2015

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 1of1 Unit 1 Unit2 x

Re12orting Period: Janua[Jl - December 2015

SUMMARY

OF NON-FUNCTIONAL MONITORS Monitor Dates Monitor was Cause and Corrective A~tions Non-Functional 2LWS-CA8206, January 1, 2015 to No liquid waste discharges were performed during 2015, and therefore, these 2LWS-FT330 &

December 31, 2015 monitors were not returned to service. The discharge manual isolation valves, 2LWS-FT331, 2LWS-V420 and 2LWS-V422, are locked closed during inoperable periods, Liquid Waste therefore, no inadvertent discharge can occur. Reference Equipment Status Discharge Monitor Log (ESL) 2010-0243.

ATTACHMENT 10 Page 1of5 Unit 1 Unit2_X_

Reporting Period: January-December 2015 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 2015.

This assessment considers the maximum exposed individual and the various exposure pathways resulting from liquid and gaseous effluents to identify the maximum dose received by a Member of the Public during their activities within the site boundary.

Prior to September 11, 2001, the public had access to the Energy Information Center for purposes of observing the educational displays or for picnicking and associated activities. Fishing also occurred near the shoreline adjacent to the Nine Mile Point (NMP) site. Fishing near the shoreline adjacent to the NMP site was the onsite activity that resulted in the potential maximum dose received by a Member of the Public. Following September 11, 2001 public access to the Energy Information Center has been restricted and fishing by Members of the Public at locations on site is also pro,hibited. Although fishing was not conducted during 2015 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 of Nine Mile Point Unit 1 (NMPl), NMP2 and the James A. Fitzpatrick Nuclear Power Plant (JAFNPP) Facilities.

Methodologies for Determining Dose for Applicable Pathways External Ground (Shoreline Sediment) Pathway Dose from the external ground (shoreline sediment) is based on the methodology in the NMP2 Offsite Dose Calculation Manual (ODCM) as adapted from Regulatory Guide 1.109. For this evaluation it is assumed that the hypothetical maximum exposed individual fished from the shoreline at all times.

ATTACHMENT 10 Page 2 of 5 Unit 1 Unit2_X_

Reporting Period: January-December 2015 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 2015 was calculated using the following input parameters:

Usage Factor= 312 hours0.00361 days 0.0867 hours 5.15873e-4 weeks 1.18716e-4 months (fishing 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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.SOE-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 Gt1ide 1.109. The total whole body dose and organ dose re".eived by the hypothetical maximum exposed fisherman during 2015 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:

Variable Fisherman 1 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) 1.09 E+06 C-14 (pCi/sec )2 5.97E+05 Mn-54 (pCi/sec) 8.36£-02 Fe-55 (pCi/sec) 2.62E+OO Co-58 (pCi/sec) 2.26£-01 Co-60 (pCl/sec) 7.06E+OO Zn-65 (pCi.sec) l.22E+OO I-131 (pCi/sec) l.78E+Ol 1-133 (pCi/sec) 2.65E+02 Cs-137 (pCi/sec) 1.02£-01

ATTACHMENT 10 Page 3 of 5 Unit 1 Unit2_X_

Reporting Period: January - December 2015 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY NMP2 Radwaste/Reactor Building Vent:

Variable Fisherman 1 XJQ (s/m3) 2.8 E-06 Inhalation dose factor Table E-7, Regulatory Guide 1.109 Annual air intake (m3/year) (adult) 8000 Fractional portion of the year 0.0356 H-3 (pCi/sec) 4.53E+05 Mn-54 (pCi/sec) 5.46E-OI Fe-55 (pCi/sec) 1.39E+Ol Co-58 (pCi/sec) 1.96E-01 Co-60 (pCi/sec) 1.55E+Ol 1-131 (pCi/sec) 4.61E+OO 1-133 (pCi/sec) 2.05E+OO Cs-137(pCi/sec) 2.84E-Ol 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per week for 39 weeks per year equivalent to 312 hours0.00361 days 0.0867 hours 5.15873e-4 weeks 1.18716e-4 months 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 2015 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 2015 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) 1.35E-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 During2015 The following is a summary of the dose received by a hypothetical maximum exposed fisherman from liquid and gaseous effluents released from NMP2 during 2015:

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

External Ground Whole Body 2.36E-03 Skin of Whole Body 2.75E-03 Whole Body 1.74E-04 Inhalation Maximum Organ Bone: 3.71 E-04 Thyroid 2.06E-04 Direct Radiation Whole Body 0.42

ATTACHMENT 10 Page 5 of 5 Unit 1 Unit2_X_

Reporting Period: January-December 2015 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.

Publidnside the site boundary is as follows:

TABLE2 Annual Dose Summary Total Annual Dose for 2015 Fisherman (mrem)

Total Whole Body 4.23E-Ol Skin of Whole Body 2.75E-03 Maximum Organ Bone: 3.71 E-04 Thyroid 2.06E-04

ATTACHMENT 11 Page 1of5 Unit 1 Unit2 X

Reporting Period: Januarv-December 2015 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 2015 for comparison against the 40 CPR 190 annual dose limits.

The intent of 40 CPR 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 ofNMPl, Nine Mile Point Unit 2 (NMP2) and the James A. FitzPatrick Nuclear Power Plant (JAFNPP) facilities must be considered.

40 CPR 190 requires the annual radiation dose received by Members of the Public in the general environment, as a result of plant operations, be limited to:

< 25 mRem whole body

< 25 mRem any organ (except thyroid)

< 75 mRem thyroid This evaluation compares doses resulting from liquid and gaseous effluents and direct radiation originating from the site as a result of the operation of~he 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 NMPI, 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 2015 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 2015; therefore, no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2015.

ATTACHMENT 11 Page 2 of 5 Unit 1 Unit2_X __

Reporting Period: Januarv-December 2015 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 2015 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 2015; therefore, no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2015.

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

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

No radionuclides were detected in shoreline sediment samples collected and a~alyzed dilring 2015; therefore no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2015.

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. The total sum of doses resulting from gaseous effluents from NMPl, NMP2 and JAFNPP during 2015 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 2015 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 2015 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 Unit2_X __

Reporting Period: January - December 2015 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY For NMP 1 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.

Where:

5.1 MWT 1000 5.1

MWT I 1000 BWR Normalized Production (Ci/GWt-yr)

Mega Watts Thermal (MWt)

Conversion Factor (MWt to GWt)

[Eq I]

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

Where:

A C-14 PR MAX 0.99 EFPD 365 PR MAX

0.99

EFPD I 365, Ci (for time period)

[Eq2]

maximum annual production rate of C-14 fraction ofC-14 in BWR gaseous pathway releases (maximum literature value in EPRI Report 1021106; also Table 1) number of effective full power days for the unit during the time period; e.g., quarterly or yearly (Table 1) number of days in a typical year

ATTACHMENT 11 Page 4 of 5 Unit 1 Unit2_X __

Reporting Period: January-December 2015 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Equation 3 estimates the C-14 activity released in carbon dioxide_ form, A c.14* co2, into the gaseous pathway during the time period for each BWR unit.

Where:

Ac.u. co2 PR MAX 0.99 0.95 EFPD 365 PR MAX

0.99

0.95

EFPD I 365, Ci (for time period) maximum annual production rate of C-14 fraction of C-14 in BWR gaseous pathway releases (maximum literature value in EPRI Report 1021106; also Table 1) fraction of C-14 as carbon dioxide in BWR gaseous pathway

[Eq3]

releases (typical literature value in EPRI Report 1021106; also Table 1) number of effective full power days for the unit during the time period, e.g. quarterly or yearly (Table 1) conversion factor, 365 days in. a typical average year For each BWR unit, the 2015 estimated C-14 activity releases (total and carbon dioxide chemical form) are summarized in Table 1.

Table 1 2015 BWR Estimated C-14 Gaseous Releases Gaseous C02 Form Max.Annual BWR Release Release EFPD Operation Fraction(a)

Fraction<hl NMPl 0.99 0.95 330EFPD (90.5%)

NMP2 0.99 0.95 358.l EFPD (98.1%)

JAFNPP 0.99 0.95 364.3 EFPD (99.8%)

(a) Maximum literature values from EPRI Report 1021106.

(b) Typical value from EPRI Report 1021106.

Prod. Rate (Eq 1).

9.44 Ci/yr 20.34 Ci/yr(cl 12.93 Ci/yr (c) NMP2 Reactor Power Rating increased to 3988 Megawatts thermal.

2015 Total Release (Eq2) 8.45 Ci 19.75 Ci 10.73 Ci 2015 C02 Release (Eq3) 8.03 Ci 18.77 Ci 10.20 Ci As long as the core designs and power ratings are not significantly changed, the maximum annual production rates and annual total and carbon dioxide activity releases in Table 1 should be acceptable for use in estimating C-14 gaseous release activity and dose components for the ARERR.

ATTACHMENT 11 Page 5 of 5 Unit 1 Unit 2 X

Reporting Period: January - December 2015 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 2015, 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 2015 Exposure Pathway Dose Type Dose (mrem)

Fish and Vegetation Total Whole Body No Dose Consumption Total Maximum Organ No Dose Total Whole Body No Dose Shoreline Sediment Total Skin of Whole Body No Dose Total Whole Body 1.93 E-03 Gaseous Effluents Thyroid 7.80 E-03 (excluding C-14)

Maximum Organ Thyroid: 7.80 E-03 Gaseous Effluent Total Whole Body 4.28 E-02 (C-14)

Maximum Organ Bone: 2.14 E-01 Direct Radiation Total Whole Body 2.05 Based on these values the maximum total annual dose potentially received by the likely most exposed Member of the Public during 2015 is as follows:

Total Whole Body:

2.09 E+OO mrem Total Thyroid:

7.80 E-03 mrem Maximum Organ:

Bone: 2.14 E-01 mrem 40 CFR 190 Evaluation The maximum total doses presented in this attachment are the result of operations at the NMPl, NMP2 and the JAFNPP facilities. The maximum organ dose (Bone: 0.214 mrem), maximum thyroid dose (0.008 mrem) and the maximum whole body dose (2.09 mrem) are below the 40 CFR 190 criteria of 25 mrem per calendar year to the maximum exposed organ.or the whole body, and below 75 mrem per calendar year to the thyroid.

ATTACHMENT 12 Page 1of1 Unit 1 --

Unit2 _x_

Regorting Period: Janua!:l£ *December 2015 Well Identification

Samples

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

Concentration (pCi/I)

GMX-MW1*

4 1

<155 215 MW-1 4

0

<106

<171 MW-4 3

1 132

<163 MW-5 1

0

<168

<168 MW-6 4

1 120

<169 MW-7 4

1

<157 250 MW-8 4

1 119

<166 MW-91 4

1

<114 174 MW-101 4

0

<114

<167 MW-11 4

0

<149

<167 MW-12 4

0

<135

<168 MW-13 4

0

<129

<166 MW-14*

4 0

<122

<154 MW-15 4

4 212 460 MW-16 4

0

<133

<169 MW-17 4

2 147 255 MW-18 4

3

<124 215 MW-19 4

0

<121

<161 MW-20 4

0

<122

<153 MW-21 4

0

<113

<158 NMP2 MAT 2'3 4

0

<167

<512 PZ-1 4

1 129

<159 PZ-2 4

0

<123

<161 PZ-3 4

1 147

<159 PZ-4 4

4 147 323 PZ-5 4

4 222 440 PZ-6 4

4 192 329 PZ-7 4

4 644 947 PZ-8 4

0

<108

<162 PZ-9*

4 0

<108

<164.

Notes:

- Control Location 1 - Sentinel well location 2 - NMP2 Groundwater Depression Cone 3 - Samples collected from storm drain system which includes precipitation

ATTACHMENT13 Page 1of1 Unit 1 Unit2 x

Reporting Period: January - December 2015 Off-Site Dose Calculation Manual (QDCM)

There was no revision to the Off-Site Dose Calculation Manual for 2015.

ATTACHMENT 14 Page 1 of 1 Unit 1 Unit2 x

Reporting Period: January - December 2015 Process Control Program CPCP)

There were no changes to the Process Control Program in 2015.

NINE MILE POINT NUCLEAR STATION.. UNIT 1 RADIOACTIVE EFFLUENT RELEASE REPORT January-December 2015

Page 1 of2 NINE MILE POINT NUCLEAR STATION - UNIT 1 RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2015 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 1J1illiroentgen 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 IO 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 I.

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 a:ny 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 IO 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 IO 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 proportionar' counting of monthly samples taken with an air sparging/water trap apparatus. Tritium effluent activicy 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 ;:inalysis of a representative sample of each batch. Scaling factors established from primary composite sample analyses conducted off-site are applied, where appropriate, to find estimated concentration of non-gamma emitters. For low activity trash shipments, curie content is estimated by dose rate measurement and application of appropriate scaling factors.

H)

C-14 The production of C-14 and the effluent dose consequences are estimates based on EPRI methodology provided in EPRI Report 1021106, Estimation ofCarbon-14 in Nuclear Power Plant Gaseous Effluents, 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 of required meteorological data on site in a file that shall be provided to the NRC upon request.

ATTACHMENT 1 Page 1 of2 Unit 1 x

Unit2 Re(!orting Period: Janua[ll - December 2015 Liquid Effluents:

ODCM Required Maximum Effluent Concentration (MEC) = 10x10CFR20, 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 2015.

Average MEC - µCi/ml (Qtr. 1) =

I NO RELEASES Average MEC - µCi/ml (Qtr. ID =

I NO RELEASES I Average MEC - µCi/ml (Qtr..1.) =

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 E~ =

NIA Qrtr.-2_:

~v

=

N/A E~ =

NIA Qrtr. ~:

~v

=

N/A E~ =

NIA Qrtr.1_:

Ey

=

N/A E~ =

NIA 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 perio9 (L)

Radwaste 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 1.07E+11 I 1.18E+11 I 1.35E+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 2

Total Time Period for Batch Releases (hrs) 21.75 Maximum Time Period for a Batch Release (hrs) 12.12 Average Time Period for a Batch Release (hrs) 10.88 r

Minimum Time Period for a Batch Release (hrs) 9.63

ATTACHMENT 1 Page 2 of2 Unit 1 x

Unit2 Reporting Period: Januarv - December 2015 Abnormal Releases:

A. Liquids:

!Number of Releases I

0 I

!Total Activity Released I

N/A.

I Ci B. Gaseous:

I Number of Releases I

0 I

!Total Activity Released I

N/A I 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 2003, the Emergency Condensers have been actuated 7 times. These are identified in the 2003, 2004, 2009, 201 O 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 2015, Tritium was detected in the Perimeter Drain discharge at 2.53E-06 µCi/ml resulting in 0.023 Ci of tritium being release. No tritium was detected in the second, third or fourth quarters of 2015. No other isotopes were identified.

ATTACHMENT 2 Page 1of1 Unit 1 x

Unit2 Reeorting Period: Janua!Y - December 2015 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES, ELEVATED AND GROUND LEVEL 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter EST. TOTAL ERROR,%

A. Fission & Activation Gases (1}

1.

Total Release Ci I

- I

- I

- I

.. I 5.00E+01

2.

Average Release Rate

µCi/sec B. Iodines (1}

1.

Total Iodine - 131 Ci 1.0SE-04 3.49E-06 2.31E-05 1.00E-04 3.00E+01

2.

Average Release Rate for Period

µCi/sec 1.48E-05 4.44E-07 2.94E-06 1.27E-05 C. Particulates (1}

1.

Particulates with Half-lives>8 days Ci 9.22E-04 6.25E-04 3.30E-04 3.26E-04 3.00E+01

2.

Average Release Rate for Period

µCVsec 1.26E-04 7.95E-05 4.20E-05 4.15E-05

3.

Gross Alpha Radioactivity Ci 2.50E+01 D. Tritium (1}

1.

Total Release Ci 1.45E+01 2.22E+01 4.34E+01 7.85E+01 5.00E+01

2.

Average Release Rate for Period

µCi/sec 1.97E+OO 2.83E+OO 5.51E+OO 9.97E+OO E. Percent of Tech. Si;iec. Limits Fission and Activation Gases Percent of Quarterly Gamma Air Dose O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Limit (5 mR)

Percent of Quarterly Beta Air Dose Limit O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO (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 days)

Percent of Quarterly Dose Limit (7.5 6.49E-02 2.11E-02 3.64E-02 7.45E-02 mrem)

Percent of Annual Dose Limit to Date (15 3.25E-02 4.30E-02 6.12E-02 9.85E-02 mrem)

Percent of Organ Dose Limit (1500 1.32E-03 4.22E-04 7.22E-04 1.48E-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 1 of2 Unit 1 x

Unit2 Re12orting Period: Janua!:ll:- December 2015 GASEOUS EFFLUENTS - ELEVATED RELEASE Continuous Mode (2)

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

Argon-41 Ci Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-127 Ci Xenon-131m Ci Xenon-133 Ci Xenon-133m Ci Xenon-135 Ci Xenon-135m Ci Xenon-137 Ci Xenon-138 Ci Iodines (1) lodine-131 Ci 1.08E-04 3.49E-06 2.31E-05 1.00E-04 lodine-133 Ci 1.26E-03 5.49E-05 2.41E-04 8.43E-05 lodine-135 Ci Particulates (1)

Strontium-89 Ci Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci 7.27E-06 3.39E-06 6.89E-06 2.74E-06 Cobalt-60 Ci 3.66E-04 2.16E-04 1.72E-04

. 1.47E-04 Cobalt-58 Ci 4.89E-05 2.99E-05 6.85E-06 6.75E-06 Manganese-54 Ci 1.94E-05 1.60E-05 7.85E-06 3.80E-06 Barium-140 Ci Lanthanum-140 Ci Niobium-95 Ci Cerium-141 Ci Cerium-144 Ci lron-59 Ci Cesium-136 Ci Chromium-51 Ci 1.61E-04 9.16E-05 Ziric-65 Ci 4.20E-06 lron-55 Ci 3.15E-04 2.68E-04 1.37E-04 1.66E-04 Molybdenum-99 Ci Neodymium-14 7 Ci Tritium (1}

Ci I 1.35E+01 I 2.01E+01 I 3.77E+01 I 7.15E+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 of2 Unit 1 x

Unit2 Re(!orting Period: Janua[l(- December 2015 GASEOUS EFFLUENTS-ELEVATED RELEASE Batch Mode (2)

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

Argon-41 Ci Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-127 Ci Xenon-131m Ci Xenon-133 Ci Xenon-133m Ci Xenon-135 Ci Xenon-135m Ci Xenon-137 Ci Xenon-138 Ci Iodines C1l lodine-131 Ci I

I I

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

Strontium-89 Ci Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci Cobalt-60 Ci Cobalt-58 Ci Manganese-54 Ci Barium-140 Ci Lanthanum-140 Ci Niobium-95 Ci Cerium-141 Ci Cerium-144 Ci lron-59

-Ci Cesium-136 Ci Chromium-51 Ci Zinc-65 Ci lron-55 Ci Molybdenum-99 Ci Neodymium-14 7 Ci Tritium (1)

Ci I

I I

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

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

ATTACHMENT 4 Page 1 of2 Unit 1 x

Unit2 Re11orting Period: Janua!l'. - December 2015 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Ground level releases are determined in accordance with the Off-Site Dose Calculation Manual and Chemistry procedures.

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

Argon-41 Ci Krypton-B5 Ci Krypton-B5m Ci Krypton-B7 Ci Krypton-BB Ci Xenon-127 Ci Xenon-131m Ci Xenon-133 Ci Xenon-133m Ci Xenon-135 Ci Xenon-135m Ci Xenon-137 Ci Xenon-13B Ci Iodines (1) lodine-131 Ci I

I I

lodine-133 Ci lodine-135 Ci Particulates C1l Strontium-B9 Ci Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci Cobalt-60 Ci Cobalt-5B Ci Manganese-54 Ci Barium-140 Ci Lanthanum-140 Ci Niobium-95 Ci Cerium-141 Ci Cerium-144 Ci lron-59 Ci Cesium-136 Ci Chromium-51 Ci Zinc-65 Ci lron-55 Ci Molybdenum-99 Ci Neodymium-14 7 Ci Tritium {1)

Ci I 1.09E+OO I 2.12E+OO I 5.77E+OO I 7.00E+OO I (1) Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.

ATTACHMENT 4 Page 2 of2 Unit 1 x

Unit2 Re11orting Period: Janua!)£- December 2015 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Ground level releases are determined in accordance with the Off-Site Dose Calculation Manual and Chemistry procedures.

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

Argon-41 Ci Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-127 Ci Xenon-131m Ci Xenon-133 Ci Xenon-133m Ci Xenon-135 Ci Xenon-135m Ci Xenon-137 Ci Xenon-138 Ci Iodines (1) lodine-131 Ci I

I I

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

Strontium-89 Ci Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci Cobalt-60 Ci Cobalt-58 Ci Manganese-54 Ci Barium-140 Ci Lanthanum-140 Ci Niobium-95 Ci Cerium-141 Ci Cerium-144 Ci lron-59 Ci Cesium-136 Ci Chromium-51 Ci Zinc-65 Ci lron-55 Ci Molybdenum-99 Ci Neodymium-147 Ci Tritium {11 Ci I

I I

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

ATTACHMENT 5 Page 1 of2 Unit 1 x

Unit2 Rei;iorting Period: Janua!Y-December 2015 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES (1) 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Est. Total Error, %

A. Fission & Activation Products

1. Total Release (not including Tritium, Ci 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 Al1:1ha Radioactivi~

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 1.07E+11 1.18E+11 1.35E.+11 1.32E+11 5.00E+01 during reporting period - Cooling Water F. Percent of Tech. S1:1ec. 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 Nd Releases Limit to Date (3 mrem)

Percent of Quarterly Organ Dose Limit No Releases No Releases No Releases No Releases (5 mrem)

Percent of Annual Organ Dose Limit to No Releases No Releases No Releases No Releases Date (10 mrem)

Percent of 1 OCFR20 Concentration No Releases No Releases No Releases No Releases Limit Percent of Dissolved or Entrained Noble 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 of 2 Unit 1 x

Unit2 Re12orting Period: Janua!Y - December 2015 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 Nci 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 Nci 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 of 4 Unit 1 x

Unit2 Rei;iorting Period: Janua!:l£- December 2015 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A1. TYPE Volume Activi~ {1}

(m3)

(Ci)

~

Class A

B c

A B

c a.1 Spent Resin (Dewatered) 3.74E+01 O.OOE+OO 0.00E+OO 2.64E+01 O.OOE+OO O.OOE+OO a.2 Filter Sludge 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO a.3 Concentrated Waste 0.00E+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO Totals 3.74E+01 O.OOE+OO O.OOE+OO 2.64E+01 O.OOE+OO O.OOE+OO b.1 Dry Compressible Waste 8.97E+02 O.OOE+OO O.OOE+OO 8.59E+OO O.OOE+OO O.OOE+OO b.2 Dry Non-Compressible Waste (Contaminated 0.00E+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO Equipment)

Totals 8.97E+02 O.OOE+OO 0.00E+OO 8.59E+OO O.OOE+OO O.OOE+OO

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

O.OOE+OO O.OOE+OO

d. Other (to vendor for processing) d.1 Iron Prefilter Septa (4) 1.53E+01 O.OOE+OO 0.00E+OO 4.84E+01 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 2015 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 NIA NIA NIA 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 Iron Prefilter Septa Cask General Design None

ATTACHMENT 6 Page 3 of 4 Unit 1 x

Unit2 Rei;iorting Period: Janua!'.ll-December 2015 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A2.. ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE)

a. Spent Resins, Filter Sludges, Concentrated Waste Nuclide Percent Curies H-3 1.66%

4.42E-01 C-14 1.13%

3.00E-01 Fe-55 3.16%

8.40E-01 Co-60 83.94%

2.23E+01 Zn-65 4.22%

1.12E+OO Cs-137 3.72%

9.BBE-01

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

Nuclide Percent Curies Cr-51 1.15%

9.93E-02 Mn-54 2.13%

1.83E-01 Fe-55 49.27%

4.24E+OO Co-60 42.65%

3.67E+OO Cs-137 1.24%

1.07E-01

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

Nuclide Percent NIA NIA

d. Other: (To vendor for processing)

1. Iron Prefilter Septa Nuclide Percent Curies H-3 44.56%

2.21E+01 C-14 1.51%

7.51E-01 Cr-51 1.76%

8.71E-01 Mn-54 2.55%

1.26E+OO Fe-55 30.76%

1.53E+01 Co-60 15.27%

7.58E+OO Zn-65 1.66%

8.22E-01

ATTACHMENT 6 Page4 of 4 Unit 1 x

Unit2 Regorting Period: Janua!)l-December 2015 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A3. SOLID WASTE DISPOSITION Number of Shi[!ments Mode of Trans[!ortation Destination 26 Hittman Transport TN Energy Solutions Services INC (CVRF) 7 Hittman Transport TN Energy Solutions LLC (Clive) 1 Landstar Energy Solutions Services INC (CVRF)

B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shi[!ments Mode of Trans[!ortation 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 Re11orting Period: Janua!)l-December 2015

SUMMARY

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

The Unit 1 Off-Site Dose Calculation Manual (ODCM) was not revised during the reporting period.

REVISION XX Page#

New/Amended Description of Change Reason For Change Section#

REVISION XX Page#

New/Amended Description of Change Reason For Change Section#

ATTACHMENT 8' Page 1 of 1 Unit 1 x

Unit2 Reporting Period: Januarv-December 2015

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

Unit2 ReE!orting Period: Janua!:Jl - December 2015

SUMMARY

OF NON-FUNCTIONAL MONITORS Monitor Dates Monitor was Cause and Corrective Actions Non-Functional Liquid Radwaste January 1, 2015 to These monitors were intentionally allowed to exceed their quarterly Discharge Monitors December 31, 2015 functional test and annual calibration frequency, as no discharges 11and12 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 2015. This non-functionality is tracked in Equipment Status Log (ESL) 2006-0192.

ATTACHMENT 10 Page 1 of 4 Unit 1 _x_

Unit 2 Reporting Period: January - December 2015 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 I (NMPI) liquid and gaseous effluents has been conducted for the period January through December 2015.

This assessment considers the maximum exposed individual and the various exposure pathways resulting from liquid and gaseous effluents to identify the maximum dose received by a Member of the Public during their activities within the site boundary.

Prior to September 11, 2001, the public had access to the Energy Information Center for purposes of observing the educational displays or for picnicking and associated activities. Fishing also occurred near the shoreline adjacent to the Nine Mile Point (NMP) site. Fishing near the shoreline adjacent to the NMP site was the onsite activity that resulted in the potential maximum dose received by a Member of the Public. Following September 11, 2001 public access to the Energy Information Center has been restricted and fishing by Members of the Public at locations on site is also prohibited. Although fishing was not conducted during 2015, 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 NMPI 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 NMPI 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.

ATTACHMENT10 Page 2 of 4 Unit 1 _x_

Unit 2 Reporting Period: January-December 2015 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 2015 was calculated using the following input parameters:

Usage Factor= 312 hours0.00361 days 0.0867 hours 5.15873e-4 weeks 1.18716e-4 months (fishing 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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= l.50E-01 pCi/g The total whole body and skin doses received by a hypothetical maximum exposed fisherman from the external ground pathway is presented in Table 1, Exposure Pathway Annual Dose.

Inhalation Pathway The inhalation dose pathway is evaluated by utilizing the inhalation equation in the NMPl ODCM, as adapted from Regulatory Guide 1.109. The total whole body dose and organ dose received by the hypotheticalcmaximum exposed fisherman during 2015 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:

NMPJ Stack:

Variable Fisherman 1 X!Q (s/m3) 8.90£-06 Inhalation dose factor Table E-7, Regulatory Guide 1.109 Annual air intake (m3/year) (adult) 8000 Fractional portion of the year 0.0356 H-3 (pCi/sec) 5.48E+06 Cr-51 (pCi.sec) 3.88E+OO Mn-54 (pCi.sec) l.17E+OO C-14 (pCi/sec)2 2.55 E+05 Fe-55 (pCi/sec) 2.42E+Ol Co-58 (pCi/sec) 1.84 E+OO Co-60 (pCl/sec) 2.26 E+Ol 1-131 (pCi/sec) 5.36 E+OO 1-133 (pCi/sec) l.61E+Ol Cs-137 (pCi/sec) 5.52£-01

ATTACHMENT 10 Page 3 of 4 Unit 1 _x_

Unit 2 Reporting Period: Januarv-December 2015 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY NMPJ Emergency Condenser Vent:

1 Variable Fisherman 1 XIQ (s/m3) 6.63E-06 Inhalation dose factor Table E-7, Regulatory Guide 1.109 Annual air intake (m3/year) (adult) 8000 Fractional portion of the year 0.0356 H-3 (pCi/sec) 6.26 E+05 The maximum exposed fisherman is assumed to be present on site during the period of April through December at a rate of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months per week for 39 weeks per year equivalent to 312 hours0.00361 days 0.0867 hours 5.15873e-4 weeks 1.18716e-4 months 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 EPRl Technical Report 1021106, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents."

The total whole body dose and maximum organ dose received by the hypothetical maximum exposed fisherman is presented in Table 1, Exposure Pathway Annual Dose.

Direct Radiation Pathway The direct radiation pathway is evaluated in accordance with the methodology found in the 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 2015 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) 1.35 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 Page 4 of 4 Unit 1 _x_

Unit 2 Reporting Period: January - December 2015 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 2015:

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

Whole Body 2.36 E-03 External Ground Skin of Whole Body 2.75 E-03 Whole Body 2.66 E-03 Inhalation Maximum Organ Lung: 2.70 E-03 Thyroid 2.66 E-03 Direct Radiation Whole Body 0.42 Based on these values the total annual dose received by a hypothetical maximum exposed Member of the Public inside the site boundary is as follows:

TABLE2 Annual Dose Summary Total Annual Dose for 2015 Fisherman (mrem)

Total Whole Body 4.25 E-01

. Skin of Whole Body 2.75 E-03 Maximum Organ Lung: 2.70 E-03 Thyroid 2.66 E-3

ATTACHMENT 11 Page 1of5 Unit 1 _x_

Unit 2 Reporting Period: January-December 2015 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 2015 for comparison against the 40 CPR 190 annual dose limits.

The intent of 40 CPR 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 CPR 190 requires the annual radiation dose received by Members of the Public in the general environment, as a result of plant operations, be limited to:

< 25 mRem whole body

< 25 mRem any organ (except thyroid)

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

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

Dose to the likely most exposed Member of the 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 2015 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 2015; therefore, no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2015.

ATTACHMENT 11 Page 2 of 5 Unit 1 _x_

Unit 2 Reporting Period: January - December 2015 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 2015 is calculated from actual analysis results of environlliental vegetation samples taken near the most exposed Member of the Public.

No radionuclides were detected in vegetation samples collected and analyzed during 2015; therefore, no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2015.

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

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

No radionuclides were detected in shoreline sediment samples collected and analyzed during 2015; therefore no dose was received by the whole body and organs of the likely most exposed Member of the Public during 2015.

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. The total sum of doses resulting from gaseous effluents from NMPl, NMP2 and JAFNPP during 2015 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 2015 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 Piant Gaseous Effluents, December 2010. The following metho.dology was used in estimating C-14 gaseous release activity and dose components for the 2015 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 2015 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.

Where:

5.1 MWT 1000 5.1

MWT I 1000 BWR Normalized Production (Ci/GWt-yr)

Mega Watts Thermal (MWt)

Conversion Factor (MWt to GWt)

[Eq 1]

Equation 2 estimates the C-14 activity released, A C-l4, into the gaseous pathway during the time period for each BWRunit.

Where:

Ac-14 PR MAX 0.99 EFPD 365 PR MAX

0.99

EFPD I 365, Ci (for time period)

[Eq2]

maximum annual production rate of C-14 fraction of C-14 in BWR gaseous pathway releases (maximum literature value in EPRI Report 1021106; also Table 1) number of effective full power days for the unit during the time period; e.g., quarterly or yearly (Table 1) number of days in a typical year

ATTACHMENT 11 Page4 of 5 Unit 1 _x_

Unit 2 Reporting Period: January - December 2015 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY Equation 3 estimates the C-14 activity released in carbon dioxide form, A C-l4. co2, into the gaseous pathway during the time period for each BWR unit.

Where:

A C-14. C02 PR MAX 0.99 0.95 EFPD 365 PR MAX

0.99

0.95

EFPD I 365, Ci (for time period) maximum annual production rate of C-14 fraction of C-14 in BWR gaseous pathway releases (maximum literature value in EPRI Report 1021106; also Table 1) fraction of C-14 as carbon dioxide in BWR gaseous pathway

[Eq3}

releases (typical literature value in EPRI Report 1021106; also Table 1) number of effective full power days for the unit during the time period, e.g. quarterly or yearly (Table 1) conversion factor, 365 days in a typical average year For each BWR unit, the 2015 estimated C-14 activity releases (total and carbon dioxide chemical form) are summarized in Table 1.

Table 1 2015 BWR Estimated C-14 Gaseous Releases Gaseous C02 Form Max.Annual BWR Release Release EFPD Operation Fraction<*)

Fraction(b)

NMPl 0.99 0.95 330 EFPD (90.5%)

NMP2 0.99 0.95 358.l EFPD (98.1%)

JAFNPP 0.99 0.95 364.3 EFPD (99.8%)

(a) Maximum literature values from EPRI Report 1021106.

(b) Typical value from EPRI Report 1021106.

Prod. Rate (Eq 1) 9.44 Ci/yr 20.34 Ci/yrCcl 12.93 Ci/yr (c) NMP2 Reactor Power Rating increased to 3988 Megawatts thermal.

2015 Total Release (Eq 2) 8.45 Ci 19.75 Ci 10.73 Ci 2015 C02 Release (Eq 3) 8.03 Ci 18.77 Ci 10.20 Ci As long as the core designs and power ratings are not significantly changed, the maximum annual production rates and annual total and carbon dioxide activity releases in Table 1 should be acceptable for use in estimating C-14 gaseous release activity and dose components for the ARERR.

ATTACHMENT 11 Page 5 of 5 Unit 1 _x_

Unit 2 Reporting Period: January - December 2015 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 2015, 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 2015 Exposure Pathway Dose Type Dose (mrem)

Fish and Vegetation Total Whole Body No Dose Consumption Total Maximum Organ No Dose Total Whole Body No Dose Shoreline Sediment Total Skin of Whole Body No Dose Total Whole Body 1.93 E-03 Gaseous Effluents Thyroid 7.80 E-03 (excluding C-14)

Maximum Organ Thyroid: 7.80 E-03 Gaseous Effluent Total Whole Body 4.28 E-02 (C-14)

Maximum Organ Bone: 2.14 E-Of Direct Radiation Total Whole Body 2.05 Based on these values the maximum total annual dose potentially received by the likely most exposed Member of the Public during 2015 is as follows:

Total Whole Body:

Total Thyroid:

Maximum Organ:

40 CFR 190 Evaluation 2.09 E+OO mrem 7.80 E-03 mrem Bone: 2.14 E-01 mrem 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: 0.214 mrem), maximum thyroid dose (0.008 mrem) and the maximum whole body dose (2.09 mrem) are below the 40 CPR 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 Unit 1 _x_

Unit2 --

Re(!orting Period: Janua!Jl - December 2015 Well Identification

Samples

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

Concentration (pCi/I)

GMX-MW1*

4 1

<155 215 MW-1 4

0

<106

<171 MW-4 3

1 132

<163 MW-5 1

0

<168

<168 MW-6 4

1 120

<169 MW-7 4

1

<157 250 MW-8 4

1 119

<166 MW-91 4

1

<114 174 MW-101 4

0

<114

<167 MW-11 4

0

<149

<167 MW-12 4

0

<135

<168 MW-13 4

0

<129

<166 MW-14*

4 0

<122

<154 MW-15 4

4 212 460 MW-16 4

0

<133

<169 MW-17 4

2 147 255 MW-18 4

3

<124 215 MW-19 4

0

<121

<161 MW-20 4

0

<122

<153 MW-21 4

0

<113

<158 NMP2 MAT 2'3 4

0

<167

<512 PZ-1 4

1 129

<159 PZ-2 4

0

<123

<161 PZ-3 4

1 147

<159 PZ-4 4

4 147 323 PZ-5 4

4 222 440 PZ-6 4

4 192 329 PZ-7 4

4 644 947 PZ-8 4

0

<108

<162 PZ-9*

4 0

<108

<164 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 1of1 Unit 1 x

Unit2 Reporting Period: January - December 2015 Off-Site Dose Calculation Manual CODCM)

There was no revision to the Off-Site Dose Calculation Manual for 2015.

ATTACHMENT14 Page 1of1 Unit 1 x

Unit2 Reporting Period: January - December 2015 Process Control Program CPCP)