Text

Annual Radioactive Effluent Release Report
	ML17118A234
Person / Time
Site:	Harris
Issue date:	04/28/2017
From:	Bradley Jones; Duke Energy Carolinas
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	HNP-17-023
	Download: ML17118A234 (295)
	v • d • e

Bentley K. Jones

( -, DUKE Director, Organizational Effectiveness ENERGY. Harris Nuclear Plant 5413 Shearon Harris Rd New Hill, NC 27562-9300 919-362-2305 APR 2 8 ~017 seri~I : 'FIN"P-17-023 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400/Renewed License No. NPF-63

Subject:

Annual Radioactive Effluent Release Report Ladies and Gentlemen:

In accordance with Harris Nuclear Plant Technical Specification 6.9.1.4, Duke Energy Progress, LLC, is providing the enclosed Annual Radioactive Effluent Release Report for 2016.

This submittal contains no regulatory commitments. Should you have any questions regarding this submittal, please contact Jeff Robertson, Manager - Regulatory Affairs, at (919) 362-3137.

Sincerely, B~~

Enclosure cc: Mr. D. Retterer, NRC Sr. Resident Inspector, HNP Ms. M. Barillas, NRC Project Manager, HNP NRC Regional Administrator, Region II

Bentley K. Jones Director, Organizational Effectiveness Harris Nuclear Plant 5413 Shearon Harris Rd New Hill, NC 27562-9300 919-362-2305 Serial: HNP-17-023 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400/Renewed License No. NPF-63

Subject:

Annual Radioactive Effluent Release Report Ladies and Gentlemen:

In accordance with Harris Nuclear Plant Technical Specification 6.9.1.4, Duke Energy Progress, LLC, is providing the enclosed Annual Radioactive Effluent Release Report for 2016.

This submittal contains no regulatory commitments. Should you have any questions regarding this submittal, please contact Jeff Robertson, Manager - Regulatory Affairs, at (919) 362-3137.

Sincerely, Bentley K. Jones Enclosure cc: Mr. D. Retterer, NRC Sr. Resident Inspector, HNP Ms. M. Barillas, NRC Project Manager, HNP NRC Regional Administrator, Region II

Shearon Harris Nuclear Power Plant Unit 1 Annual Radioactive Effluent Release Report January 1, 2016 through December 31, 2016 Docket 50-400

Introduction The Annual Radioactive Effluent Release Report is pursuant to Shearon Harris Nuclear Power Plant Technical Specification 6.9.1.4 and ODCM Section F.2. The below listed attachments to this report provide the required information. In addition, the ODCM is included pursuant to Shearon Harris Nuclear Power Plant Technical Specification 6.14.

Attachment 1 Summary of Gaseous and Liquid Effluents Attachment 2 Supplemental Information Attachment 3 Solid Radioactive Waste Disposal Attachment 4 Meteorological Data Attachment 5 Unplanned Offsite Releases Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Attachment 7 Information to Support the NEI Ground Water Protection Initiative Attachment 8 Inoperable Equipment Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Attachment 10 Summary of Changes to the Process Control Program Attachment 11 Summary of Major Modifications to the Radioactive Waste Treatment Systems Attachment 12 Errata to a Previous Year's ARERR

Attachment 1 Summary of Gaseous and Liquid Effluents Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 ATTACHMENT 1 Summary of Gaseous and Liquid Effluents This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents as outlined in Regulatory Guide 1.21, Appendix B.

Page 1-1

Attachment 1 Summary of Gaseous and Liquid Effluents Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Gaseous Effluents - Summation of All Releases Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Fission and Activation Gases

1. Total Release Ci 1.16E-01 8.45E-03 2.11E-02 2.84E-03 1.48E-01

2. Avg. Release Rate µCi/sec 1.47E-02 1.08E-03 2.65E-03 3.57E-04 4.69E-03 B. Iodine-131

1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 1.27E-07 1.27E-07

2. Avg. Release Rate µCi/sec 0.00E+00 0.00E+00 0.00E+00 1.60E-08 4.02E-09 C. Particulates Half-Life 8 days

1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 2.58E-06 2.58E-06

2. Avg. Release Rate µCi/sec 0.00E+00 0.00E+00 0.00E+00 3.25E-07 8.16E-08 D. Tritium

1. Total Release Ci 2.36E+01 1.87E+01 1.81E+01 2.00E+01 8.04E+01

2. Avg. Release Rate µCi/sec 3.00E+00 2.38E+00 2.28E+00 2.52E+00 2.54E+00 E. Gross Alpha

1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2. Avg. Release Rate µCi/sec 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Page 1-2

Attachment 1 Summary of Gaseous and Liquid Effluents Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Gaseous Effluents - Elevated Releases - Continuous Mode

Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Fission and Activation Gases N/A Ci - - - - -

Total for Period Ci - - - - -

B. Iodines N/A Ci - - - - -

Total for Period Ci - - - - -

C. Particulates Half-Life 8 days N/A Ci - - - - -

Total for Period Ci - - - - -

D. Tritium N/A Ci - - - - -

E. Gross Alpha Total for Period Ci - - - - -

Shearon Harris Nuclear Power Plant Unit 1 does not have elevated releases.

Page 1-3

Attachment 1 Summary of Gaseous and Liquid Effluents Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Gaseous Effluents - Elevated Releases - Batch Mode

Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Fission and Activation Gases N/A Ci - - - - -

Total for Period Ci - - - - -

B. Iodines N/A Ci - - - - -

Total for Period Ci - - - - -

C. Particulates Half-Life 8 days N/A Ci - - - - -

Total for Period Ci - - - - -

D. Tritium N/A Ci - - - - -

E. Gross Alpha Total for Period Ci - - - - -

Shearon Harris Nuclear Power Plant Unit 1 does not have elevated releases.

Page 1-4

Attachment 1 Summary of Gaseous and Liquid Effluents Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Gaseous Effluents - Ground Releases - Continuous Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Fission and Activation Gases Xe-133 Ci 1.16E-01 6.16E-03 1.32E-03 2.84E-03 1.26E-01 Total for Period Ci 1.16E-01 6.16E-03 1.32E-03 2.84E-03 1.26E-01 B. Iodines None Ci - - - - -

Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C. Particulates Half-Life 8 days None Ci - - - - -

Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 D. Tritium H-3 Ci 2.36E+01 1.87E+01 1.81E+01 1.95E+01 7.99E+01 E. Gross Alpha Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Page 1-5

Attachment 1 Summary of Gaseous and Liquid Effluents Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Gaseous Effluents - Ground Releases - Batch Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Fission and Activation Gases Kr-85M Ci 0.00E+00 0.00E+00 2.26E-06 0.00E+00 2.26E-06 Xe-131M Ci 0.00E+00 4.20E-06 4.68E-04 0.00E+00 4.72E-04 Xe-133M Ci 0.00E+00 3.43E-05 5.11E-05 0.00E+00 8.54E-05 Xe-133 Ci 0.00E+00 2.17E-03 1.91E-02 0.00E+00 2.13E-02 Xe-135 Ci 0.00E+00 8.85E-05 9.72E-05 0.00E+00 1.86E-04 Total for Period Ci 0.00E+00 2.29E-03 1.97E-02 0.00E+00 2.20E-02 B. Iodines I-131 Ci 0.00E+00 0.00E+00 0.00E+00 1.27E-07 1.27E-07 Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 1.27E-07 1.27E-07 C. Particulates Half-Life 8 days Cr-51 Ci 0.00E+00 0.00E+00 0.00E+00 6.94E-07 6.94E-07 Mn-54 Ci 0.00E+00 0.00E+00 0.00E+00 1.23E-08 1.23E-08 Co-58 Ci 0.00E+00 0.00E+00 0.00E+00 5.51E-07 5.51E-07 Co-60 Ci 0.00E+00 0.00E+00 0.00E+00 5.25E-07 5.25E-07 Zr-95 Ci 0.00E+00 0.00E+00 0.00E+00 3.35E-07 3.35E-07 Nb-95 Ci 0.00E+00 0.00E+00 0.00E+00 4.29E-07 4.29E-07 Sb-125 Ci 0.00E+00 0.00E+00 0.00E+00 3.48E-08 3.48E-08 Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 2.58E-06 2.58E-06 D. Tritium H-3 Ci 0.00E+00 7.01E-05 7.79E-05 4.50E-01 4.50E-01 E. Gross Alpha Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Page 1-6

Attachment 1 Summary of Gaseous and Liquid Effluents Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Gaseous Effluents - Mixed-Mode Releases - Continuous Mode

Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Fission and Activation Gases N/A Ci - - - - -

Total for Period Ci - - - - -

B. Iodines N/A Ci - - - - -

Total for Period Ci - - - - -

C. Particulates Half-Life 8 days N/A Ci - - - - -

Total for Period Ci - - - - -

D. Tritium N/A Ci - - - - -

E. Gross Alpha Total for Period Ci - - - - -

Shearon Harris Nuclear Power Plant Unit 1 does not have mixed-mode releases.

Page 1-7

Attachment 1 Summary of Gaseous and Liquid Effluents Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Gaseous Effluents - Mixed-Mode Releases - Batch Mode

Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Fission and Activation Gases N/A Ci - - - - -

Total for Period Ci - - - - -

B. Iodines N/A Ci - - - - -

Total for Period Ci - - - - -

C. Particulates Half-Life 8 days N/A Ci - - - - -

Total for Period Ci - - - - -

D. Tritium N/A Ci - - - - -

E. Gross Alpha Total for Period Ci - - - - -

Shearon Harris Nuclear Power Plant Unit 1 does not have mixed-mode releases.

Page 1-8

Attachment 1 Summary of Gaseous and Liquid Effluents Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Liquid Effluents - Summation of All Releases Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Fission and Activation Products

1. Total Release Ci 4.84E-04 3.01E-04 1.66E-03 1.73E-02 1.97E-02

2. Avg. Diluted Conc. µCi/ml 1.03E-10 6.27E-11 3.36E-10 3.56E-09 1.02E-09 B. Tritium

1. Total Release Ci 1.17E+01 1.97E+02 4.09E+02 1.59E+02 7.77E+02

2. Avg. Diluted Conc. µCi/ml 2.49E-06 4.09E-05 8.28E-05 3.26E-05 4.02E-05 C. Dissolved & Entrained Gases

1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 2.08E-04 2.08E-04

2. Avg. Diluted Conc. µCi/ml 0.00E+00 0.00E+00 0.00E+00 4.28E-11 1.08E-11 D. Gross Alpha

1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

2. Avg. Diluted Conc. µCi/ml 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 E. Volume of Liquid Waste

1. Batch Releases liters 3.16E+05 6.53E+05 1.41E+06 2.33E+06 4.71E+06

2. Continuous Releases liters 8.33E+06 1.08E+07 1.18E+07 1.01E+07 4.09E+07 F. Volume of Dilution Water

1. Batch Releases liters 4.70E+09 4.81E+09 4.94E+09 4.86E+09 1.93E+10

2. Continuous Releases liters 4.10E+08 4.29E+08 7.06E+08 5.09E+08 2.05E+09 Excludes tritium, dissolved and entrained noble gases, and gross alpha.

Page 1-9

Attachment 1 Summary of Gaseous and Liquid Effluents Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Liquid Effluents - Continuous Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Fission and Activation Products None Ci - - - - -

Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 B. Tritium H-3 Ci 9.21E-02 9.91E-02 7.97E-02 8.39E-04 2.72E-01 C. Dissolved & Entrained Gases None Ci - - - - -

Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 D. Gross Alpha Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Page 1-10

Attachment 1 Summary of Gaseous and Liquid Effluents Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Liquid Effluents - Batch Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Fission and Activation Products Cr-51 Ci 0.00E+00 0.00E+00 5.31E-05 2.74E-03 2.79E-03 Mn-54 Ci 0.00E+00 0.00E+00 5.48E-05 3.70E-04 4.25E-04 Fe-55 Ci 0.00E+00 0.00E+00 0.00E+00 9.56E-04 9.56E-04 Fe-59 Ci 0.00E+00 0.00E+00 0.00E+00 1.12E-04 1.12E-04 Co-58 Ci 3.56E-05 0.00E+00 6.44E-05 6.16E-03 6.26E-03 Co-60 Ci 1.08E-04 1.07E-04 7.06E-04 2.52E-03 3.44E-03 Ni-63 Ci 2.69E-04 1.94E-04 5.17E-04 2.96E-03 3.94E-03 Zr-95 Ci 1.21E-05 0.00E+00 9.76E-06 4.33E-04 4.55E-04 Nb-95 Ci 1.17E-05 0.00E+00 4.45E-05 5.90E-04 6.46E-04 Sb-124 Ci 0.00E+00 0.00E+00 0.00E+00 1.06E-04 1.06E-04 Sb-125 Ci 4.15E-05 0.00E+00 2.00E-04 3.03E-04 5.45E-04 Cs-137 Ci 6.61E-06 0.00E+00 1.16E-05 3.73E-05 5.55E-05 Ce-143 Ci 0.00E+00 0.00E+00 0.00E+00 4.40E-06 4.40E-06 Total for Period Ci 4.84E-04 3.01E-04 1.66E-03 1.73E-02 1.97E-02 B. Tritium H-3 Ci 1.17E+01 1.97E+02 4.09E+02 1.59E+02 7.77E+02 C. Dissolved & Entrained Gases Xe-133 Ci 0.00E+00 0.00E+00 0.00E+00 2.08E-04 2.08E-04 Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 2.08E-04 2.08E-04 D. Gross Alpha Total for Period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Page 1-11

Attachment 2 Supplemental Information Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 ATTACHMENT 2 Supplemental Information This attachment includes supplemental information to the gaseous and liquid effluents report.

Page 2-1

Attachment 2 Supplemental Information Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 I. Regulatory Limits - Per Unit A. Noble Gases - Air Dose

1. Calendar Quarter Gamma Dose =5 mRAD

2. Calendar Quarter Beta Dose = 10 mRAD

3. Calendar Year Gamma Dose = 10 mRAD

4. Calendar Year Beta Dose = 20 mRAD B. Liquid Effluents - Dose

1. Calendar Quarter Total Body Dose = 1.5 mREM

2. Calendar Quarter Organ Dose =5 mREM

3. Calendar Year Total Body Dose =3 mREM

4. Calendar Year Organ Dose = 10 mREM C. Gaseous Effluents - Iodine-131 & 133, Tritium, and Particulates with Half-lives > 8 days

1. Calendar Quarter Organ Dose = 7.5 mREM

2. Calendar Year Organ Dose = 15 mREM II. Maximum Permissible Effluent Concentrations A. Gaseous Effluents

1. Information found in Offsite Dose Calculation Manual B. Liquid Effluents

1. Information found in 10 CFR Part 20, Appendix B, Table 2, Column 2 III. Average Energy (not applicable)

IV. Measurements and Approximations of Total Radioactivity Analyses of specific radionuclides in selected or composited samples as described in the ODCM are used to determine the radionuclide composition of the effluent. A summary description of the method used for estimating overall errors associated with radioactivity measurements is provided as part of this attachment.

V. Batch Releases A. Liquid Effluents Jan - Jun Jul - Dec

1. Total Number of Batch Releases = 1.30E+01 5.00E+01

2. Total Time (min) for Batch Releases = 1.01E+04 3.91E+04

3. Maximum Time (min) for a Batch Release = 8.79E+02 9.90E+02

4. Average Time (min) for Batch Releases = 7.75E+02 7.82E+02

5. Minimum Time (min) for a Batch Release = 5.64E+02 8.20E+01

6. Average Dilution Water Flow During = 9.48E+03 9.65E+03 Release (gpm)

B. Gaseous Effluents Jan - Jun Jul - Dec

1. Total Number of Batch Releases = 5.00E+00 2.00+01

2. Total Time (min) for Batch Releases = 3.85E+03 1.56E+04

3. Maximum Time (min) for a Batch Release = 2.03E+03 3.01E+03

4. Average Time (min) for Batch Releases = 7.69E+02 7.79E+02

5. Minimum Time (min) for a Batch Release = 2.03E+02 1.20E+02 VI. Abnormal Releases See Attachment 5, Unplanned Offsite Releases.

Page 2-2

Attachment 2 Supplemental Information Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Carbon-14 The Shearon Harris Nuclear Power Plant 2016 ARERR contains estimates of C-14 radioactivity released in 2016, and estimates of public dose resulting from the C-14 effluent. The concentration and offsite dose from C-14 has been estimated by using a calculation approach, assuming typical or maximum values for the various calculation parameters. Because the dose contribution of C-14 from liquid radioactive waste is much less than that contributed by gaseous radioactive waste, evaluation of C-14 in liquid radioactive waste is not required (Ref. Reg. Guide 1.21, Rev.

2).

The quantity of gaseous C-14 released to the environment can be estimated by use of a C-14 source term scaling factor based on power generation (Ref. Reg. Guide 1.21, Rev. 2). The Shearon Harris Nuclear Power Plant UFSAR states the expected C-14 generation to be 7.3 Curies assuming 292 effective full power days (EFPD) in a calendar year. For the Shearon Harris Nuclear Power Plant 2016 ARERR, a source term scaling factor using actual EFPD of 328.674 days is assumed. Using the source term scaling factor from Shearon Harris Nuclear Power Plant in 2016 results in a site total C-14 gaseous release estimate to the environment of 8.22 Curies. Due to the reducing environment of a Pressured Water Reactor, only 30% of the C-14 is assumed to be released in the Carbon Dioxide (CO 2 ) form. Dose is not expected from other forms (methane, etc). 70% of the C-14 gaseous effluent is assumed to be from batch releases (e.g. WGDTs), and the remaining 30% is assumed to be from continuous releases through the plant vent (ref. IAEA Technical Reports Series no. 421, "Management of Waste Containing Tritium and Carbon-14",

2004).

The resultant offsite doses were based upon this source term and the dose calculations described in NRC Regulatory Guide 1.109, revision 1, and the Shearon Harris Nuclear Power Plant ODCM. The estimated C-14 dose impact on the maximum organ dose from airborne effluents released from Shearon Harris Nuclear Power Plant in 2016 is well below the 10CFR50, Appendix I, ALARA design objective (i.e., 15 mrem/yr per unit).

Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Year

1. EFFD Days 90.366 90.607 91.596 56.105 328.674

2. C-14 Activity Released Ci 2.26E+00 2.27E+00 2.29E+00 1.40E+00 8.22E+00

3. C-14 Total Body Dose mREM 1.36E-02 1.54E-02 1.42E-02 8.46E-03 5.17E-02

4. C-14 Organ Dose mREM 6.85E-02 7.72E-02 7.11E-02 4.26E-02 2.59E-01 Receptor Location 3.07 km NNE Critical Age CHILD Critical Organ BONE Page 2-3

Attachment 2 Supplemental Information Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Dose from Returned/Re-used of Previously Discharge Plant Effluents Cooling Tower Plume Tritium in Cooling Tower plume creates an exposure pathway to a member of the public. Murray and Trettle, Inc. was contracted to perform an evaluation of the dose to a member of the public from exposure to tritium in the Cooling Tower plume. Results of the plume exposure are contained in report Impact of Tritium Release from the Cooling Tower at the Harris Nuclear Plant for 2016. Using the methodology described in ODCM 2.3.2, the following is a summary of tritium activity released through the Cooling Tower plume and resulting dose for 2016.

Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year

1. H-3 Activity Released Ci 2.55E+01 1.74E+01 2.52E+01 1.95E+01 8.75E+01

2. H-3 Dose mREM 1.12E-03 7.61E-04 1.10E-03 8.54E-04 3.84E-03 Receptor Location 3.07 km NNE Critical Age CHILD Critical Organ N/A

Harris Lake Evaporation Evaporation of water containing tritium in Harris Lake creates an exposure pathway to a member of the public.

Murray and Trettle, Inc. was contracted to perform an evaluation of the dose to a member of the public from evaporation of tritium in Harris Lake. Results of the evaluation are contained in report Impact of Tritium Release from the Water Reservoir (Lake Harris) at the Harris Nuclear Plant for 2016. Using the methodology described in ODCM 2.3.3, the following is a summary of tritium activity released through evaporation and resulting dose for 2016.

Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year

1. H-3 Activity Released Ci 1.58E+01 2.64E+01 4.37E+01 2.67E+01 1.13E+02

2. H-3 Dose mREM 1.23E-02 2.05E-02 3.38E-02 2.06E-02 8.72E-02 Receptor Location 6.70 km SSW Critical Age CHILD Critical Organ N/A

Drinking Water for Wake County Fire and HE&EC Training Centers Concentrations of radionuclides used in this specific drinking water pathway are determined by averaging the monthly concentrations detected in environmental location (REMP) DW-51. In 2016, no plant related gamma emitting radionuclides were detected. Tritium was detected each month, as expected. Using the methodology described in ODCM 2.3.1, the following is a summary of average concentration consumed and resulting dose for 2016.

Units Year

1. Avg. H-3 Concentration Ci/L 4.32E+03

2. H-3 Dose mREM 1.18E-01 Critical Age ADULT Critical Organ N/A *

The dose factor for H-3 is the same for all organs and Total Body (with the exception of Bone, which is 0.00E+00).

Page 2-4

Attachment 2 Supplemental Information Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 NOTE Tritium in Fish from Harris Lake Concentrations of radionuclides used in this specific fish consumption pathway are determined by averaging the monthly concentrations detected in environmental location (REMP) SW-26. In 2016, no plant related gamma emitting radionuclides were detected. Tritium was detected each month, as expected. Since tritium is consistently detected in Harris Lake REMP samples, tritium concentration in the fish is assumed to be in equilibrium with Harris Lake. Using the methodology and data described in NRC Regulatory Guide 1.109, Rev.1, October 1977, Equation A-1, Table E-5, and Table E-11, the following is a summary of average concentration consumed and resulting dose for 2016.

Units Year

1. Avg. H-3 Concentration Ci/L 5.76E+03

2. H-3 Dose mREM 1.14E-02 Critical Age ADULT Critical Organ N/A *

The dose factor for H-3 is the same for all organs and Total Body (with the exception of Bone, which is 0.00E+00).

NOTE: This information was previously included in the Shearon Harris Nuclear Power Plant AREOR. DRR 2008147 was written to include the fish dose calculation methodology in ODCM revision 26, and report in the ARERR.

Page 2-5

Attachment 2 Supplemental Information Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Overall Estimate of Error for Gaseous Effluent Radioactivity Release Reported The estimated percentage of overall error for Noble Gases in Gaseous effluent release data at Shearon Harris Nuclear Power Plant has been determined to be +/- 52.68%. This value was derived by taking the square root of the sum of the squares of the following discrete individual estimates of error:

1. Counting Standard (20000 counts/energy % error) = +/- 0.1%

2. Calibration Standard = +/- 5.0%

3. Acceptable Counting Statistic for Nuclide ID (R.E.) = +/- 25.0%

4. Sample Volume Variability = +/- 5.0%

5. Stack Flow Rates (Non-steady Release Rates) = +/- 10.0%

6. Rad Monitor Calibration = +/- 20.0%

7. Net Activity Determination from Rad Monitors = +/- 40.0%

The estimated percentage of overall error for Air Particulates in Gaseous effluent release data at Shearon Harris Nuclear Power Plant has been determined to be +/- 33.75%. This value was derived by taking the square root of the sum of the squares of the following discrete individual estimates of error:

1. Counting Standard (20000 counts/energy % error) = +/- 0.1%

2. Calibration Standard = +/- 5.0%

3. Acceptable Counting Statistic for Nuclide ID (R.E.) = +/- 25.0%

4. Sample Flow (Sample Volume) = +/- 10.0%

5. Potential Sample Line Losses = +/- 8.0%

6. Stack Flow Rates (Non-steady Release Rates) = +/- 10.0%

7. Chemical Yield Factors (Sr-89, 90) = +/- 15.0%

The estimated percentage of overall error for Iodine on Charcoal Filters in Gaseous effluent release data at Shearon Harris Nuclear Power Plant has been determined to be +/- 30.38%. This value was derived by taking the square root of the sum of the squares of the following discrete individual estimates of error:

1. Counting Standard (20000 counts/energy % error) = +/- 0.1%

2. Calibration Standard = +/- 5.0%

3. Acceptable Counting Statistic for Nuclide ID (R.E.) = +/- 25.0%

4. Sample Flow (Sample Volume) = +/- 10.0%

5. Potential Sample Line Losses = +/- 8.0%

6. Stack Flow Rates (Non-steady Release Rates) = +/- 10.0%

7. Collection Efficiency = +/- 3.0%

The estimated percentage of overall error for Tritium in Gaseous effluent release data at Shearon Harris Nuclear Power Plant has been determined to be +/- 52.20%. This value was derived by taking the square root of the sum of the squares of the following discrete individual estimates of error:

1. Counting Standard (20000 counts/energy % error) = +/- 0.1%

2. Calibration Standard = +/- 5.0%

3. Acceptable Counting Statistic for Nuclide ID (R.E.) = +/- 50.0%

4. Stack Flow Rates (Non-steady Release Rates) = +/- 10.0%

5. Collection Efficiency = +/- 10.0%

Page 2-6

Attachment 2 Supplemental Information Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Overall Estimate of Error for Liquid Effluent Radioactivity Release Reported The estimated percentage of overall error for Fission and Activation Products in Liquid effluent release data at Shearon Harris Nuclear Power Plant has been determined to be +/- 32.79%. This value was derived by taking the square root of the sum of the squares of the following discrete individual estimates of error:

1. Counting Standard (20000 counts/energy % error) = +/- 0.1%

2. Calibration Standard = +/- 5.0%

3. Acceptable Counting Statistic for Nuclide ID (R.E.) = +/- 25.0%

4. Sample (sample volume between techs) = +/- 5.0%

5. Volume Determinations (Tank Level) = +/- 20.0%

The estimated percentage of overall error for Tritium in Liquid effluent release data at Shearon Harris Nuclear Power Plant has been determined to be +/- 54.31%. This value was derived by taking the square root of the sum of the squares of the following discrete individual estimates of error:

1. Counting Standard (20000 counts/energy % error) = +/- 0.1%

2. Calibration Standard = +/- 5.0%

3. Acceptable Counting Statistic for Nuclide ID (R.E.) = +/- 50.0%

4. Sample (sample volume between techs) = +/- 5.0%

5. Volume Determinations (Tank Level) = +/- 20.0%

Page 2-7

Attachment 2 Supplemental Information Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Overall Estimate of Error for Solid Waste Radioactivity Reported The estimated percentage of overall error for Solid Waste data at Shearon Harris Nuclear Power Plant has been determined to be +/- 96%. This value was derived by taking the square root of the sum of the squares of the following discrete individual estimates of error:

1. Counting Standard (20000 counts/energy % error) = < +/- 0.1%

2. Calibration Standard = +/- 5.0%

3. Acceptable Counting Statistic for Nuclide ID (R.E.) = +/- 95.0%

4. Sample Volume Variability = +/- 0.001%

5. Instrument Errors = +/- 5.0%

6. Dose Rate Measurement = +/- 10.0%

7. Geometry = +/- 5.0%

8. Volume Determinations = +/- 5.0%

9. RADMAN Database (sample analysis variance) = +/- 0.96%

Page 2-8

Attachment 2 Supplemental Information Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Summary of Changes in Land Use Census Affecting Effluent Dose Calculations The 2016 Land Use Census was performed August 2-4, 2016, and the results were certified and made available for use on October 12, 2016. The following are changes to residences, gardens, and milk animals from the previous year.

Residences The residence in the E sector at 1.98 miles was replaced by a residence at 1.88 miles.

Gardens The garden in the NNE sector at 1.91 miles was replaced by a non-irrigated garden at 1.81 miles.

The garden in the NE sector at 3.22 miles was replaced by a non-irrigated garden at 2.92 miles.

The garden in the ESE sector at 4.76 miles was replaced by a non-irrigated garden at 2.75 miles.

The garden in the SSW sector at 4.20 miles was replaced by an irrigated (public utility) garden at 4.13 miles.

The garden in the W sector at 3.73 miles was replaced by an irrigated (well) garden at 2.75 miles.

The garden in the WNW sector at 3.39 miles was no longer present and replaced by an irrigated (well) garden at 4.33 miles.

NOTE: No gardens being irrigated from Harris Lake were identified. All irrigation sources identified were from wells, ponds, public utilities, etc.

Meat Animals The meat animal in the ESE sector at 2.74 miles was no longer present and replaced by a meat animal at 2.84 miles.

The meat animal in the SSE sector at 4.57 miles was replaced by a meat animal at 4.32 miles.

The meat animal in the W sector at 3.26 miles was replaced by a meat animal at 2.82 miles.

The meat animal in the WNW sector at 2.13 miles was no longer present and replaced by a meat animal at 3.39 miles.

Milk Animals A new milk animal (goat) was identified in the W sector at 2.82 miles. Owner may participate in REMP when able during breeding months in late-spring and late-fall seasons.

A new milk animal (goat) was identified in the NNW sector at 4.68 miles. Owner does not wish to participate in REMP.

Environmental Monitoring Locations No other changes to environmental monitoring locations in each sector.

Page 2-9

Attachment 3 Solid Radioactive Waste Disposal Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 ATTACHMENT 3 Solid Radioactive Waste Disposal This attachment includes a summary of the solid waste shipped off-site for burial and/or disposal, including:

Container volume

Total Curie content

Principal Radionuclides

Source/Type of waste

Solidification agent or absorbent

Type of shipping container

Number of shipments

Other relevant information as necessary Page 3-1

Attachment 3 Solid Radioactive Waste Disposal Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Burial Total Type of Number of Number of Waste Container Solidification Volume Activity Waste Shipped Shipments Containers Class Type Agent 3 (m ) (Curies)

1. Waste from Liquid Systems

a. Dewatered Spent Resins NRC 4 - A N/A 14.36 6.03E+01 (compacted) Approved

b. Evaporator Concentrates 0 - - - - - -

c. Dewatered Demineralizers 0 - - - - - -

d. Solidified (cement) Acids, 0 - - - - - -

Oils, Sludge

2. Dry Solid Waste

a. Dry Active Waste (dewatered, NRC 1 - B N/A 0.027 1.27E-01 compacted) Approved

b. Dry Active Waste (dewatered, NRC 7 - A N/A 343.22 8.10E-01 non-compacted) Approved

c. Dry Active Waste (brokered) 0 - - - - - -

d. Irradiated Components NRC 1 - A N/A 0.017 1.03E-01 (dewatered, non-compacted) Approved

e. Other (dewatered, non- NRC 8 - A N/A 195.95 1.26E-02 compacted) Approved

3. Total Solid Waste 21 - 553.57 6.14E+01 Page 3-2

Attachment 3 Solid Radioactive Waste Disposal Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Type of Waste Shipped Radionuclide % Abundance

1. Waste from Liquid Systems

a. Dewatered Spent Resins Be-7 5.57 C-14 0.36 Ce-144 0.06 Co-57 0.07 Co-58 1.85 Co-60 15.69 Cr-51 0.00 Cs-137 2.89 Fe-55 41.70 Fe-59 0.02 H-3 0.07 I-129 0.00 Mn-54 16.70 Nb-95 0.23 Ni-63 16.14 Sb-125 1.20 Sn-113 0.06 Sr-89 0.02 Sr-90 0.02 Tc-99 0.01 Zr-95 0.23

b. Evaporator Concentrates N/A N/A

c. Dewatered Demineralizers N/A N/A

d. Solidified (cement) Acids, Oils, Sludge N/A N/A

2. Dry Solid Waste

a. Dry Active Waste (dewatered, C-14 1.12 compacted) Ce-144 0.04 Co-57 0.02 Co-58 0.00 Co-60 24.40 Cs-137 0.07 Fe-55 50.80 H-3 3.99 Mn-54 0.94 Nb-95 0.00 Ni-63 17.60 Sb-125 1.03 Sr-90 0.02 Zr-95 0.00 I-129 0.01 Tc-99 0.03 Page 3-3

Attachment 3 Solid Radioactive Waste Disposal Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016

b. Dry Active Waste (dewatered, non- C-14 0.06 compacted) Ce-144 0.24 Co-57 0.00 Co-58 0.65 Co-60 11.30 Cr-51 1.31 Cs-137 0.14 Fe-55 6.22 Fe-59 0.00 H-3 5.67 I-129 0.01 Mn-54 0.38 Nb-95 17.29 Ni-63 6.32 Sb-125 1.28 Sn-113 0.00 Sr-90 0.07 Tc-99 0.08 Zr-95 13.47 Am-241 0.00 Cm-243 0.00 Pu-238 0.00 Pu-239 0.00 Pu-241 0.00 Cs-134 0.00

c. Dry Active Waste (brokered) N/A N/A

d. Irradiated Components (dewatered, C-14 0.03 non-compacted) Ce-144 0.00 Co-58 0.03 Co-60 68.90 Cr-51 10.49 Cs-137 0.00 Fe-55 10.59 Fe-59 0.21 H-3 0.00 I-129 0.00 Mn-54 0.04 Nb-95 0.00 Ni-63 0.31 Sb-125 0.00 Sr-90 0.00 Tc-99 0.00 Zr-95 0.00 Ni-59 0.00 Zn-65 9.40 Nb-94 0.00

e. Other (dewatered, non-compacted) C-14 8.26 Ce-144 0.04 Co-60 0.02 Cs-137 0.02 H-3 47.14 I-129 11.07 Tc-99 33.40 Page 3-4

Attachment 4 Meteorological Data Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 ATTACHMENT 4 Meteorological Data This attachment includes a summary of meteorological joint frequency distributions of wind speed, wind direction, and atmospheric stability (hours of occurrence).

Page 4-1

Attachment 4 Meteorological Data Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Wind Hours of Occurrence Stability Speed Sector Class (m/s) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.76-1.00 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 1.01-1.25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.26-1.50 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.51-2.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2.01-3.00 0 1 1 3 2 0 0 0 0 0 0 0 0 0 0 0 A

3.01-4.00 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 4.01-5.00 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 5.01-6.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 6.01-8.00 0 0 0 0 0 0 0 0 0 0 0 0 0 3 0 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 10.01-Max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.46-0.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.76-1.00 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 1.01-1.25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1.26-1.50 1 1 1 0 0 0 0 2 0 0 0 0 0 0 1 0 1.51-2.00 1 3 3 2 2 1 0 1 0 0 0 0 0 0 0 1 2.01-3.00 0 5 3 5 1 2 0 1 5 0 0 2 2 4 2 1 B

3.01-4.00 4 7 9 5 0 1 0 0 5 1 1 1 0 1 3 0 4.01-5.00 0 1 0 2 0 0 0 0 1 2 3 3 2 4 3 1 5.01-6.00 0 1 0 0 0 0 0 0 0 2 0 2 0 1 0 0 6.01-8.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 10.01-Max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 4-2

Attachment 4 Meteorological Data Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Wind Hours of Occurrence Stability Speed Sector Class (m/s) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW 0.46-0.75 0 0 0 1 0 0 0 0 1 0 1 0 0 1 0 0 0.76-1.00 3 1 3 1 0 2 0 1 1 0 1 0 0 0 0 1 1.01-1.25 2 1 2 2 2 2 2 1 1 1 3 0 2 2 1 1 1.26-1.50 1 3 5 3 3 5 3 4 1 4 1 3 3 1 2 1 1.51-2.00 3 11 13 6 8 6 6 7 8 6 8 5 6 4 3 3 2.01-3.00 8 14 14 17 3 4 5 10 29 8 5 19 3 8 19 20 C

3.01-4.00 13 16 15 4 2 1 2 1 12 9 6 17 7 12 18 11 4.01-5.00 0 1 0 0 0 0 0 0 1 5 14 5 4 6 9 6 5.01-6.00 0 0 0 0 0 0 0 0 0 6 3 2 0 4 3 2 6.01-8.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 10.01-Max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.46-0.75 10 10 17 17 9 6 11 5 6 5 10 9 9 13 6 15 0.76-1.00 11 10 25 14 14 20 12 6 8 16 10 17 16 14 10 16 1.01-1.25 13 21 21 17 14 14 8 11 12 12 16 20 16 10 12 14 1.26-1.50 24 22 35 11 16 14 12 17 24 17 17 23 12 15 21 17 1.51-2.00 64 70 61 55 29 37 22 24 42 59 62 69 38 29 34 44 2.01-3.00 123 188 79 54 23 24 20 33 76 102 96 137 71 39 62 96 D

3.01-4.00 74 76 23 7 0 3 3 15 48 56 52 39 36 31 37 41 4.01-5.00 15 7 0 0 0 0 0 2 13 26 34 19 7 15 19 20 5.01-6.00 6 5 0 0 0 0 0 3 4 16 7 7 5 5 5 3 6.01-8.00 2 7 0 0 0 0 0 0 2 0 2 2 2 1 0 0 8.01-10.00 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 10.01-Max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 4-3

Attachment 4 Meteorological Data Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Wind Hours of Occurrence Stability Speed Sector Class (m/s) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW 0.46-0.75 13 14 29 14 11 11 8 12 21 14 22 15 18 12 7 12 0.76-1.00 20 17 13 14 11 20 6 11 20 15 16 11 14 7 6 13 1.01-1.25 18 17 17 17 10 8 9 17 12 16 14 15 11 7 9 5 1.26-1.50 28 23 21 14 9 8 13 20 12 32 12 21 7 13 10 6 1.51-2.00 40 45 27 15 5 9 3 29 28 43 34 22 16 8 14 14 2.01-3.00 42 30 18 6 1 2 0 16 50 106 48 15 12 23 21 32 E

3.01-4.00 1 3 2 0 1 0 1 0 10 49 17 1 10 5 3 8 4.01-5.00 0 0 0 0 0 0 0 0 0 7 0 1 0 0 0 0 5.01-6.00 0 0 0 0 0 0 0 0 0 3 2 1 0 0 0 1 6.01-8.00 0 0 0 0 0 0 0 0 0 1 2 0 0 0 0 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 10.01-Max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.46-0.75 12 17 11 14 3 2 3 4 5 8 13 9 7 3 9 12 0.76-1.00 11 10 6 8 2 5 2 2 5 5 8 8 4 4 10 12 1.01-1.25 16 8 8 3 1 1 3 1 2 4 6 8 4 3 6 4 1.26-1.50 11 5 5 4 0 0 0 3 0 4 8 5 2 4 6 6 1.51-2.00 14 8 3 2 3 0 1 2 3 13 7 5 2 3 4 2 2.01-3.00 1 1 0 0 0 0 0 0 1 3 1 0 1 1 0 0 F

3.01-4.00 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 4.01-5.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 5.01-6.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6.01-8.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 10.01-Max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 4-4

Attachment 4 Meteorological Data Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Wind Hours of Occurrence Stability Speed Sector Class (m/s) N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW 0.46-0.75 18 8 12 10 3 5 2 4 3 2 6 8 5 7 2 14 0.76-1.00 6 3 4 2 1 0 2 0 4 2 4 3 5 8 5 4 1.01-1.25 4 1 1 0 0 0 0 0 1 3 1 1 0 0 2 2 1.26-1.50 3 1 0 0 0 0 0 1 0 1 3 0 1 0 0 0 1.51-2.00 1 2 0 0 0 0 0 0 1 0 1 0 0 0 0 0 2.01-3.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 G

3.01-4.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4.01-5.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 5.01-6.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6.01-8.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8.01-10.00 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 10.01-Max 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Page 4-5

Attachment 5 Unplanned Offsite Releases Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 ATTACHMENT 5 Unplanned Offsite Releases This attachment includes a summary of the unplanned offsite releases of gaseous and liquid radioactive effluents.

Page 5-1

Attachment 5 Unplanned Offsite Releases Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant had one (1) unplanned liquid release in 2016.

Shearon Harris Nuclear Power Plant had one (1) unplanned gaseous release in 2016.

Summaries in this attachment include:

Detailed description of event.

Total Curies released.

Anticipated dose consequences.

Page 5-2

Attachment 5 Unplanned Offsite Releases Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Gaseous Release- Waste Gas Decay Tank (WGDT) D 5/17/2016: Nuclear Condition Report (NCR) 2030195 After the transfer of "A" WGDT to "D" WGDT Operations noticed that the "D" WGDT had a lowering trend. Waste Gas 3

was secured and the inlet and outlet valves of the "D" WGDT were shut and the pressure stabilized. 347 ft of gas was released from the tank through the monitored released point.

Isotope Concentration Post Dilution Concentration Activity Released

(µCi/cc) (µCi/cc) (Ci)

H-3 3.621E-07 4.60E-12 3.56E-06 Xe-133M 3.907E-07 4.97E-12 3.84E-06 Xe-133 2.400E-05 3.05E-10 2.36E-04 Xe-135 1.008E-06 1.28E-11 9.91E-06 Total 2.53E-04 In order to determine the dose to a member of the public from the release of the D waste gas decay tank was calculated using the radiological effluent software (OpenEMS) and compared against 10 CFR Part 50 Appendix I limits. The maximum receptor dose for particulates, iodine, and tritium (PIT) from this release, including cow milk, ground plane, inhalation, meat, and vegetation pathways, was determined to be a child at the site boundary with a limiting organ of liver. The noble gas from all gamma and beta emitter in the air was computed, as well at the annual dose rate to the skin and total body. The result were documented in Gaseous Release Permit G-2016-0083 and listed in the table below.

Name Dose Limit % QTR % Annual 7.5 mrem/qtr Total Body (PIT) 1.81E-08 2.41E-07 1.21E-07 15 mrem/yr 7.5 mrem/qtr Organ (PIT) 1.81E-08 2.41E-07 1.21E-07 15 mrem/yr Skin Dose Rate (NG) 3.95E-04 3000 mrem/yr N/A 1.32E-05 Total Body Dose Rate (NG) 1.68E-04 500 mrem/yr N/A 3.35E-05 5 mrad/qtr Gamma Air Dose 7.55E-08 1.51E-06 7.55E-07 10 mrad/yr 10 mrad/qtr Beta Air Dose 2.03E-07 2.03E-06 1.01E-06 20 mrad/yr In each instance, the dose was < 0.01% of the dose limits and thus did not exceed any of the limits at or near the site boundary. Finally, the cumulative gaseous dose from all release (including all stacks and waste gas decay tank releases) is computed, the cumulative maximum individual organ dose from particulate, iodine, and tritium is 0.71% of the quarterly limits. Thus, the dose calculations from this release were well beneath any regulatory limits.

Page 5-3

Attachment 5 Unplanned Offsite Releases Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Liquid Release - Treated Laundry and Hot Shower (TLHS) "B": NCR 2069947 On October 12, 1400 Operations performed a planned, permitted radioactive discharge of the Treated Laundry Hot Shower Tank (TLHS) "B" in accordance to OP-120.10.04. The release was monitored by the TLHS radiation monitor REM-3540. After the release was completed on October 13, 03:23, Operations flushed the discharge, through the monitor, with 2,852 gallons of demin water per OP-120.10.04 Section 7.1. Like the radioactive tank discharge, the flush water flew unimpeded to Harris Lake via the Radwaste Discharge Pipe and Cooling Tower Blowdown Line.

After the contamination of the WPB demin water was identified, a sample of the remaining water in the pipe (3DW-169) associated with the flush was analyzed. Note: a sample of the actual flush water was impossible because the water had already entered and mixed with Harris Lake inventory. The sample contained 2.91E-06 uCi/ml tritium and 2.23E-07 uCi/ml Co58. The radiation monitor associated with this flush was reviewed (REM-3540) and no changes were identified during the period of the flush. Since the release was contained within the discharge piping to Harris Lake it did not impact groundwater. The contamination the demin water caused an unplanned radioactive discharge to the public.

Concentration Post Dilution Concentration Isotope Curies (uCi/mL) (uCi/mL)

H-3 2.91E-06 1.07E-08 3.14E-05 Co-58 2.23E-07 8.20E-10 2.41E-06 Total 3.38E-05 The dose and dose rate to a member of the public from the release of the contaminated flush water was calculated using the radiological effluent software (OpenEMS) and compared against 10 CFR Part 50 Appendix I limits. The maximum receptor was an adult and the dose factors where based upon site specific parameters as defined in the Off Site Dose Calculation Manual Section B. The result were documented in Liquid Release Permit L-2016-0048 and listed in the table below.

Name Dose Limit % QTR % Annual 1.5 mrem/qtr Total Body 2.45E-07 mrem 1.63E-05 8.17E-06 3 mrem/yr 5 mrem/qtr Organ (GILLI) 2.12E-06 mrem 4.23E-05 2.12E-05 10 mrem/yr In each instance, the dose was <0.01% of the dose limits and thus did not exceed any of the limits at or near the site boundary. Finally, the cumulative liquid dose from all release (including all liquid releases) is computed, the cumulative maximum total body dose is 8.80% of the annual limits. Thus, the dose calculations from this release were well beneath any regulatory limits.

Page 5-4

Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 ATTACHMENT 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public (includes fuel cycle dose calculation results)

This attachment includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site for each calendar quarter for the calendar year of the report as well as the total dose for the calendar year.

This attachment also includes an assessment of radiation doses to the maximum exposed member of the public from all uranium fuel cycle sources within 8 km of the site for the calendar year of this report to show conformance with 40 CFR Part 190.

Methods for calculating the dose contribution from liquid and gaseous effluents are given in the Offsite Dose Calculation Manual (ODCM).

Page 6-1

Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Gaseous Effluents Dose Summary Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Noble Gases

1. Maximum Gamma Air mRAD 2.97E-05 2.28E-06 5.47E-06 5.72E-07 3.81E-05 (a) Limit mRAD 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01 (b) % of Limit 5.95E-04 4.55E-05 1.09E-04 1.14E-05 3.81E-04

2. Maximum Beta Air mRAD 8.85E-05 6.58E-06 1.63E-05 1.70E-06 1.13E-04 (a) Limit mRAD 1.00E+01 1.00E+01 1.00E+01 1.00E+01 2.00E+01 (b) % of Limit 8.85E-04 6.58E-05 1.63E-04 1.70E-05 5.65E-04 Receptor Location 2.14 km SW B. Iodine, H-3, & Particulates

1. Maximum Organ Dose mREM 1.20E-01 9.52E-02 9.18E-02 7.96E-02 3.87E-01 (a) Limit mREM 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01 (b) % of Limit 1.60E+00 1.27E+00 1.22E+00 1.06E+00 2.58E+00 Receptor Location 2.14 km SW Critical Age CHILD Critical Organ THYROID Page 6-2

Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Liquid Effluents Dose Summary Units Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year A. Batch Mode

1. Maximum Organ Dose mREM 4.19E-04 3.91E-03 2.19E-02 9.27E-02 1.19E-01 (a) Limit mREM 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01 (b) % of Limit 8.39E-03 7.81E-02 4.38E-01 1.85E+00 1.19E+00

2. Maximum Total Body Dose mREM 1.38E-04 3.90E-03 1.87E-02 1.44E-02 3.71E-02 (a) Limit mREM 1.50E+00 1.50E+00 1.50E+00 1.50E+00 3.00E+00 (b) % of Limit 9.23E-03 2.60E-01 1.24E+00 9.59E-01 1.24E+00 Critical Age ADULT Critical Organ GILLI Page 6-3

Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 40 CFR Part 190 Uranium Fuel Cycle Dose Calculation Results In accordance with the requirements of 40 CFR Part 190, the annual dose commitment to any member of the general public shall be calculated to assure that doses are limited to 25 millirems to the total body or any organ with the exception of the thyroid which is limited to 75 millirems. The fuel cycle dose assessment for Shearon Harris Nuclear Power Plant includes liquid and gaseous effluent dose contributions from the plant. Direct and air-scatter dose from the reactor building and other onsite structures does not contribute measurable dose to the maximum exposed individual based on review of the 2016 environmental TLD data. No other uranium fuel cycle facility contributes significantly to the maximum exposed individual. Included below is an estimate of the dose contributed by Carbon-14 (Ref. Attachment 2, Supplemental Information, of this report for further information). Also included is dose from H-3 in the Shearon Harris Nuclear Power Plant Cooling Tower plume, evaporation of H-3 in Harris Lake, H-3 in on-site drinking water, and H-3 in fish from Harris Lake. The combined dose to a maximum exposed individual from effluent releases, combined with the additional dose pathways, is below 40 CFR Part 190 limits as shown by the following summary.

Note: The 40 CFR Part 190 effluent dose analysis to the maximum exposed individual from liquid and gas releases does not include the dose from noble gases (i.e., total body and skin) due to the low significance compared to other dose pathways.

40 CFR Part 190 Effluent Dose Summary A. Gaseous Effluent Dose E. Harris Lake Evaporation H-3 Dose

1. Location 2.14 km SW 1. Location 6.70 km SSW

2. Critical Age CHILD 2. Critical Age CHILD

3. Critical Organ THYROID 3. Critical Organ N/A

4. Organ Dose (mREM) 3.87E-01 4. Organ Dose (mREM) 8.72E-02

5. Total Body Dose (mREM) 3.87E-01 5. Total Body Dose (mREM) 8.72E-02 B. Liquid Effluent Dose F. Training Center Drinking Water H-3 Dose

1. Location 2.19 km S 1. Location OCA

2. Critical Age ADULT 2. Critical Age ADULT

3. Critical Organ GI-LLI 3. Critical Organ N/A

4. Organ Dose (mREM) 1.19E-01 4. Organ Dose (mREM) 1.18E-01

5. Total Body Dose (mREM) 3.71E-02 5. Total Body Dose (mREM) 1.18E-01 C. Carbon-14 Dose G. H-3 in Fish from Harris Lake

1. Location 3.07 km NNE 1. Location Lake

2. Critical Age CHILD 2. Critical Age ADULT

3. Critical Organ BONE 3. Critical Organ N/A

4. Organ Dose (mREM) 2.59E-01 4. Organ Dose (mREM) 1.14E-02

5. Total Body Dose (mREM) 5.17E-02 5. Total Body Dose (mREM) 1.14E-02 D. Cooling Tower Plume H-3 Dose

1. Location 3.07 km NNE

2. Critical Age CHILD

3. Critical Organ N/A

4. Organ Dose (mREM) 3.84E-03

5. Total Body Dose (mREM) 3.84E-03 Page 6-4

Attachment 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Dose contributions from Carbon-14 in gaseous effluents have been determined from ODCM 3.3.2, Carbon-14. The maximum dose rate to the nearest real individual from the release of Carbon-14 in batch and continuous gaseous effluents is conservatively calculated to be less than 2.59E-01 mrem/yr based on 8.22E+00 Curies released in 2016 (Ref. Attachment 2, Supplemental Information, of this report).

Dose contributions from Tritium in the Shearon Harris Nuclear Power Plant Cooling Tower plume have been determined from ODCM 2.3, Doses from Return/Re-use of Previously Discharged Radioactive Effluents. The maximum dose rate to the nearest real individual from the release of Tritium the plume is conservatively calculated to be less than 3.84E-03 mrem/yr based on 8.75E+01 Curies released in 2016 (Ref. Attachment 2, Supplemental Information, of this report).

Dose contributions from evaporation of Tritium Harris Lake have been determined from ODCM 2.3, Doses from Return/Re-use of Previously Discharged Radioactive Effluents. The maximum dose rate to the nearest real individual from evaporation of Tritium in Harris Lake is conservatively calculated to be less than 8.72E-02 mrem/yr based on 1.13E+02 Curies released in 2016 (Ref. Attachment 2, Supplemental Information, of this report).

Dose contributions from Tritium in drinking water at the Wake County Fire and HE&EC Training Centers have been determined from 2.3, Doses from Return/Re-use of Previously Discharged Radioactive Effluents. The maximum dose rate to the nearest real individual from consuming the drinking water is conservatively calculated to be less than 1.18E-01 mrem/yr based on an average concentration of 4.32E+03 Ci/L consumed in 2016 (Ref. Attachment 2, Supplemental Information, of this report).

Dose contributions from Tritium in fish in Harris Lake have been determined using NRC Regulatory Guide 1.109, Rev.1, October 1977, Equation A-1, and data from REMP location SW-26. This information was previously included in the Shearon Harris Nuclear Power Plant AREOR. DRR 2008147 was written to include the fish dose calculation methodology in ODCM revision 26, and report in the ARERR. The maximum dose rate to the nearest real individual from consuming the fish in Harris Lake is conservatively calculated to be less than 1.14E-02 mrem/yr based on an average concentration of 5.76E+03 Ci/L consumed in 2016 (Ref. Attachment 2, Supplemental Information, of this report).

Total dose from liquid and gaseous effluents from Shearon Harris Nuclear Power Plant and the additional pathways mentioned above is conservatively estimated to be less than 2 mrem/yr for total body and organ. It is recognized summing dose for different organs and age groups is not entirely accurate. However, the sum of the organ and age specific doses will always be less than the sum of the maximums of each. Therefore, summing the maximum values of each provides the most conservative value to ensure compliance with 40 CFR 190. The dose from all pathways related to operation of Shearon Harris Nuclear Power Plant meets the 40 CFR Part 190 requirements of an annual dose commitment to any member of the general public of less than 25 mrem total body or any organ and 75 mrem to the thyroid.

Page 6-5

Attachment 7 Information to Support the NEI Ground Water Protection Initiative Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 ATTACHMENT 7 Information to Support the NEI Ground Water Protection Initiative This attachment includes a summary of voluntary reports made in accordance with the NEI Ground Water Protection Initiative and a summary of ground water well sample data.

Page 7-1

Attachment 7 Information to Support the NEI Ground Water Protection Initiative Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Samples were taken at various locations throughout the plant in support of the Groundwater Protection Initiative.

Samples included Groundwater Monitoring Wells along the Cooling Tower Blowdown Line, Storm Drains, Vaults and Yard Drains that could potentially affect groundwater. None of the vaults, yard drains, or storm drains indicated plant related gamma emitters or tritium above the investigation limit. HNP Self Assessment (AR-0202000) determined Groundwater Monitoring location #76 did not meet the requirements for waterborne monitoring, so in September 2016 it was removed from the site's Radiological Environmental Monitoring Program (REMP). The well is located within the protected area and is not used as a source of drinking water or irrigation, thus is not a potential dose pathway. In addition, in June 2015 12 new groundwater monitoring wells were installed near the site's Waste Neutralization Basin.

These wells are not listed in the ODCM or part of the REMP. The data for these wells are located below. Per NEI 07-07 the results of the Groundwater Monitoring Wells were included in the REMP and are not listed in this report but included in the AREOR.

Results from sampling during 2016 are shown in the table below.

Tritium Concentration (Ci/L)

Well # 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr # Samples 1

GW76 <MDA 4.48E+02 4.29E+02 <MDA 4 HMW1 2.56E+02 2.67E+02 2.52E+02 2.81E+02 4 HMW2 <MDA <MDA <MDA <MDA 4 HMW3 <MDA <MDA <MDA <MDA 4 HMW4D <MDA <MDA <MDA <MDA 4 HMW4S <MDA <MDA <MDA <MDA 4 HMW5 <MDA <MDA <MDA <MDA 4 HMW6 <MDA <MDA 2.72E+02 2.63E+02 4 HMW7 <MDA <MDA <MDA <MDA 4 HMW8 <MDA <MDA <MDA <MDA 4 HMW9 <MDA <MDA <MDA <MDA 4 HMW10 <MDA <MDA <MDA <MDA 4 HMW11 <MDA <MDA <MDA <MDA 4 NOTE: MDA for monitoring wells 185 Ci/L 1

GW76 results from 1st to 3rd quarter 2016 are included in the Annual Radiological Environmental Operating Report Zero (0) events meeting the criteria for voluntary notification per NEI 07-07, Industry Ground Water Protection Initiative, occurred at Shearon Harris Nuclear Power Plant in 2016.

Page 7-2

Attachment 8 Inoperable Equipment Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 ATTACHMENT 8 Inoperable Equipment This attachment includes an explanation of inoperable instruments related to effluent monitoring in excess of allowed time defined by licensing bases and an explanation of temporary outside liquid storage tanks exceeding 10 Curies total activity (excluding tritium and dissolved or entrained noble gases).

Page 8-1

Attachment 8 Inoperable Equipment Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant did not experience inoperable equipment relevant to effluent monitoring in excess of ODCM limits during 2016.

Shearon Harris Nuclear Power Plant did not experience temporary outside liquid storage tanks exceeding 10 Curies total activity (excluding tritium and dissolved or entrained noble gases) during 2016.

Page 8-2

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 ATTACHMENT 9 Summary of Changes to the Offsite Dose Calculation Manual This attachment includes a summary of changes to the ODCM and Radiological Effluent Controls.

Page 9-1

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 ODCM Revision 26 There are two types of changes to the ODCM; 1) programmatic changes and 2) administrative corrections, changes, and clarifications. Programmatic Changes were as follows:

As part of fleet alignment, the fleet meteorology organization revised site's transportation and deposition model (XOQDOQ) increasing the number of wind classification from 7 to 13, concentrating more classes for the 0.75 - 3.50 mph wind speed. The increase the number of lower wind classifications improves the assessment of dose to show compliance with 10CFRPart20.1302 and 10CFRPart50 Appendix I.

The revision to the site's transportation and deposition model (XOQDOQ) changed the locations and value for the highest X/Q and D/Q. The site's Radiological Effluent Program and Emergency Plan have been revised to incorporate the update.

HNP Self Assessment (AR-0202000) evaluated the site's REMP against NUREG-1301 Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors requirements. The self assessment identified opportunities for improvements in the location of Special Interest (i.e. population center) TLD's. Due to the growth in the area the original location of population center TLD's no longer met the intent of ODCMOR 3/4.12.1. As a result, new TLD's were located near schools and neighborhoods.

HNP Self Assessment (AR-0202000) determined Groundwater Monitoring location #76 did not meet the requirements for waterborne monitoring. The well is located within the protected area and is not used as a source of drinking water or irrigation, thus is not a potential dose pathway. The well will continue to be sampled as part of the site's Groundwater Protection Program and the results published the Annual Radiological Effluent Release Report.

The owners of Food Crop #5 and Milk #96 no longer can provide food crop or milk samples. An alternative Food Crop location #96 (included in ODCM Revision 25) provides sufficient quantities of vegetation for Food Crop surveillance. Since, there are no active dairies in the area location #96 has been removed from the REMP. The annual Land Use Census will continue to monitor for new gardens or milk animals.

No changes to plant safety systems or components, FSAR-described evaluation methodologies, or tests/experiments outside the bounds of the FSAR are effected by Rev 26 to the ODCM.

Revision 26 was approved by the Plant Nuclear Safety Committee on 9-23-2016.

A complete list of the changes the ODCM in Revision 26 is below.

Page 9-2

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 DRRs 01998214, 01996625, 02008147, 02031405, 02031406 Section Page Description Table of Contents i Changed to ODCM REV. 26 CHANGE

SUMMARY

Entire Document The site's FSAR and the fleet now use a common revision number for the ODCM so the List of Effective Pages and revision headings were deleted. (DRR 2031406) The format and font of the entire document was adjusted for uniformity throughout.

ODCM REV 26 v Changed to reflect Rev. 26 revisions.

CHANGE

SUMMARY

2.3 2-16 Added "and the consumption of fish from Harris Lake". This is an additional return/reuse pathway.

2.3.4 2-20 Added dose calculation from the consumption of fish from Harris Lake. The dose assessment is based upon Reg Guide 1.109 (DRR 2008147) 3.0 3-1 Added "Minor release pathways, such as steam leaks, steam dumps, and open penetrations are evaluated for significant of release." (DRR 1998214) 3.1.1 3-2 Equation 3.1-1a and 3.1-1b incorrectly contain a summation sign.

The equations are for the individual release rates rather than the sum of all the releases. (DRR 2031405) 3.1.1, 3.1.2 3-2, 3-7, 3- Changed X/Q from 2.30E-05 to 1.8E-05 to update to highest X/Q 3.2.1, 3.3.1 12, 3-18 new value (AR 682873) 3.2.1 3-13 Changed X/Q period from 2003 - 2007 to 2010 - 2014 to reflect the new Appendix A update.

3.3.2 3-23 Changed D/Q from 1.00E-08 in SSW sector to 9.0E-09 in SW sector to update to highest D/Q new value (AR 682873) 3.3.2 3-24 Revised sentence "At SHNPP the SW sector has the highest X/Q v and the SSW sector has the highest annual average D/Q v values." to "At SHNPP the SW sector has the highest X/Q v and the SW and SSW sector have the highest annual average D/Q v values." because both the SW and SSW have the same D/Q =

9.0E-09 3.3.2 3-27 to 3-28 Revised Carbon-14 dose assessment to allow for dose to be calculated either quarterly or annually. Removed the word "annual" from descriptions and terms.

Changed the number of hours of photosynthesis per year from 4400 hours0.0509 days 1.222 hours 0.00728 weeks 0.00167 months to 4460 hour0.0516 days 1.239 hours 0.00737 weeks 0.0017 months s/yr and 1115 hour0.0129 days 0.31 hours 0.00184 weeks 4.242575e-4 months s/quarter. This result is based upon data from the US Naval Observatory for Raleigh, NC.

4.0 4-1 Deleted reference to figures 4.1-4, 4.1-5, and 4.1-6. Those figures were removed from the ODCM in earlier revision.

Table 4.1 - Direct 4-3 Added distance for location 5 at 13.3 mile (NCR 02047421)

Radiation Page 9-3

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Table 4.1 - Direct 4-5, 4-6 Deleted TLD locations 67, (HEEC), 34 (Apex), 35 (Holly Springs)

Radiation and replaced with TLD locations 98 (Holly Springs school complex) and 99 (Friendship High School). Due to the growth in the area, these locations are more centrally located to population.

Deleted TLD locations 36 (Sunset Lake) and 37 (Fuquay Varina).

These TLD locations are defined as special interest locations due to population centers per ODCMOR 3/4.12.1 and located approximately 10 miles from the plant. Since the inception of the Radiological Environmental Monitoring Program, the regional population has moved closer to the plant and these locations no longer meet the intent of ODCMOR 3/4.12.1 TLD locations #3 and #50 are new special interest locations. (AR 02020000)

Table 4.1 - Surface 4-6 Changed required analysis from Monthly Gross Beta and Water Quarterly Gamma Isotopic to the correct Monthly Gamma Isotopic and Quarterly Tritium per NUREG-1301 Table 3.12-1 Added note "H-3 analysis is normally performed monthly" Table 4.1 Groundwater 4-8 Removed Groundwater location 76 from the Radiological Monitoring Environmental Monitoring Program. The groundwater at this location does not meet the requirements for waterborne monitoring. Because this well is located within the protected area it is not used as a source of drinking water or irrigation.

This well will be sampled per plant procedures and the results published in the Annual Effluent Release Report per ODCM Section F.2. (AR 02020000)

Table 4.1 Ingestion -Milk 4-11 Removed location 96 from Milk. This location is no longer available because the homeowner no longer sells goat milk.

According to the homeowner's business website the goat milk is used for the production of soap. (AR 02020000)

Table 4.1 Ingestion - 4-12 Removed location 5 from Food Crop. This location is no longer Food Products available because the homeowner no longer gardens. Added reference to notes 10 and 16. (AR 02020000)

Notes for Table 4.1 4-14 Revised Note 1 to remove reference to figures 4.1-4, 4.1-5, and 4.1-6.

Revised Note 10, 11, 12, and 14 to include new information regarding Food Crop location 5 and groundwater monitoring well

76. Revised note 15 to clarify the description of broadleaf vegetation. Added new note 16 "Attention shall be paid to including samples of tuberous and root food products."

Table 4.2 Radiological 4-15 Deleted "M" for Site #5 under FP. Deleted Site #76 under GW Environmental and #96 under MK.

Monitoring Program Table 4.3 Radiological 4-16 Deleted Site # 34, 35, 36, 37, 67 and added # 98, 99. Identified Environmental locations #3 and #50 as special interest. Changed distance of Monitoring Program #5 from >12 m. to 13.3 mi. (NCR 02047421)

(TLD Sites)

Figure 4.1-2 4-18 Revised maps to reflect removal of location 76 Environmental Radiological Sampling Points Page 9-4

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Figure 4.1-3 4-19 Revised maps to reflect removal of location 34, 35, 36, 37, 96 Environmental and the addition of locations 98, 99 Radiological Sampling Points Appendix A A1 - A22 revised Appendix A to new XOQDOQ based upon 2010 - 2014 meteorology data. Increased the number of wind classifications from 7 to 13, concentrating more classes for the 0.75-3.50 mph wind speed. This class was split into 5 segments to get more accurate analysis of XOQDOQ. (AR 682873, DRR1996625)

Table 3.12-2 Food D-32 Added additional food product sample requirement from areas Products irrigated by water which liquid plant wastes have been discharged per NUREG-1301 Table 3.12-1. Note: there are currently no Food Products that are irrigated by plant discharges Note to Table 3.12-2 D-34 Added note 9 "If harvest occurs more than once per year, sampling shall be performed during each discrete harvest. If harvest occurs continuously, sampling shall be monthly." based upon NUREG-1301 Table 3.12-1 Table 4.12-1 D-36 Add the note "The specific LLD applies to the daughter nuclide of Detection Capabilities for an equilibrium mixture of the parent and daughter nuclides. Per Environmental Samples the Branch Technical Position, value of 60 pCi/L may be used for Ba-140 and 15 pCi/L may be used for La-140."

3 /4.12.3 Interlaboratory D-39 Deleted "The laboratory used for the Interlaboratory Comparison Comparison Program Program is to participate in the National Institute of Standard and Technology (NIST) program" This is not a recognized program.

Page 9-5

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 SHEARON HARRIS NUCLEAR POWER PLANT OFF-SITE DOSE CALCULATION MANUAL (ODCM)

Revision 26 Docket No. STN-50-400 DUKE ENERGY PROGRESS, Inc Formerly known as Carolina Power & Light Company Page 9-6

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE OF CONTENTS Section Title............................................................................................................................................. Page TABLE OF CONTENTS .................................................................................................................................................. i LIST OF TABLES ........................................................................................................................................................... ii LIST OF FIGURES........................................................................................................................................................ iv ODCM REV. 26 CHANGE

SUMMARY

.......................................................................................................................... v

1.0 INTRODUCTION

.......................................................................................................................................... 1-1 2.0 LIQUID EFFLUENTS .................................................................................................................................... 2-1 2.1 Compliance With 10 CFR 20 .......................................................................................................... 2-2 2.2 Compliance With 10 CFR 50 Appendix I ......................................................................................2-12 2.3 Doses from Return/Re-use of Previously Discharged Radioactive Effluents ................................ 2-16 3.0 GASEOUS EFFLUENTS .............................................................................................................................. 3-1 3.1 Monitor Alarm Setpoint Determination ............................................................................................ 3-1 3.2 Post-release Compliance With 10CFR20-Based ODCM Operational Requirement 3.11.2................................................................................................... 3-12 3.3 Compliance With 10 CFR 50 ........................................................................................................ 3-16 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ............................................................... 4-1 5.0 INTERLABORATORY COMPARISON STUDIES ......................................................................................... 5-1 6.0 TOTAL DOSE (COMPLIANCE WITH 40 CFR 190)for ODCM OR 3.11.4 .................................................... 6-1 6.1 Total Dose (COMPLIANCE WITH 40 CFR 190) for ODCM OR F.2 ............................................... 6-1 7.0 LICENSEE-INITIATED CHANGES TO THE ODCM ..................................................................................... 7-1 APPENDIX A - METEOROLOGICAL DISPERSION FACTOR COMPUTATIONS .................................................... A-1 APPENDIX B - DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM .............................................................................................................................. B-1 APPENDIX C - RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION NUMBERS ........................................................................ C-1 APPENDIX D - PROGRAMMATIC CONTROLS ........................................................................................................ D-1 APPENDIX E - PROGRAMMATIC CONTROL BASES ............................................................................................. E-1 APPENDIX F - ADMINISTRATIVE CONTROLS ........................................................................................................ F-1 APPENDIX G - DEFINITIONS ................................................................................................................................... G-1 i

Page 9-7

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 LIST OF TABLES No. Title Page 2.1-1a Liquid Effluent Release Tanks and Pumps Design Basis ........................................................... 2-21 2.1-1b Liquid Effluent Release Tanks and Pumps For Normal Operations............................................ 2-21 2.1-2 Setpoints for Cooling Tower Blowdown Dilution Flow Rates (Favail)................................................................................................................................ 2-22 2.1-3 Signal Processor Time Constants () for GA Technologies RD-53 Liquid Effluent Monitors ...... 2-22 2.1-4 Nuclide Parameters .................................................................................................................... 2-23 2.2-1 Ai Values for the Adult for the Shearon Harris Nuclear Power Plant ................................................................................................................................ 2-26 3.1-1 Gaseous Source Terms .............................................................................................................. 3-10 3.1-2 Dose Factors and Constants (Deleted) ...................................................................................... 3-11 3.1-3 Gaseous Monitor Parameters ..................................................................................................... 3-11 3.2-1 Releases from Shearon Harris Nuclear Power Plant Normal Operation (Curies/year).................................................................................................. 3-15 3.2-3 Dose Factors for Noble Gases ................................................................................................... 3-16 3.2-4 Pi Values (Inhalation) for a Child ............................................................................................... 3-17 I

3.3-1 through 3.3-19 R Values for the Shearon Harris Nuclear Power Plant ............................................................... 3-30 3.3-20 Recommended Values for Uap to be used for the Maximum Exposed Individual in Lieu of Site Specific Data ........................................................................................................ 3-60 3.3-21 Inhalation Dose Factors from Carbon-14 for organ to an individual from Tables E-7 to E-10 Regulatory Guide 1.109 Rev 1 ................................................................................................... 3-62 3.3-22 Ingestion Dose Factors from Carbon-14 for organ to an individual from Tables E-11 to E-14 Regulatory Guide 1.109 Rev 1 ................................................................................................... 3-62 4.1 Radiological Environmental Monitoring Program .......................................................................... 4-2 4.2 Radiological Environmental Monitoring Program Sampling Locations ........................................ 4-15 4.3 Radiological Environmental Monitoring Program Sampling Locations (TLD Sites)..................... 4-16 A-1 through A-4 X/Q and D/Q Values for Long-Term Ground-Level Releases at Special Locations ................................................................................................................... A-3 A-5 Undepleted, No Decay, X/Q Values For Long Term Ground Level Releases At Standard Distances 3

(sec/m ) ......................................................................................................................................... A-5 A-6 Undepleted, No Decay, X/Q Values For Long Term Ground Level Releases At Standard Distances 3

(sec/m ) ......................................................................................................................................... A-6 A-7 Undepleted, 2.26 Day Decay, X/Q Values For Long Term Ground Level Releases At Standard 3

Distances (sec/m ) ........................................................................................................................ A-7 ii Page 9-8

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 LIST OF TABLES (continued)

No. Title Page A-8 Undepleted, 2.26 Day Decay, X/Q Values For Long Term Ground Level Releases At Standard 3

Distances (sec/m ) ........................................................................................................................ A-8 A-9 Depleted, 8.0 Day Decay, X/Q Values For Long Term Ground Level Releases At Standard 3

Distances (sec/m ) ........................................................................................................................ A-9 A-10 Depleted, 8.0 Day Decay, X/Q Values For Long Term Ground Level Releases At Standard 3

Distances (sec/m ) ...................................................................................................................... A-10 A-11 Deposition Values (D/Q) For Long Term Releases At Standard Distances (m-2) ...................... A-11

-2 A-12 Deposition Values (D/Q) For Long Term Releases At Standard Distances (m ) ........................ A-12 A-13 Joint Wind Frequency Distribution By Pasquill Stability Classes At SHNPP ............................... A-13 A-14 Shearon Harris Plant Site Input Information for Continuous Ground-level Release Calculations With the NRC XOQDOQ Program ............................................................................................... A-17 B-1 Parameters for Cow and Goat Milk Pathways ............................................................................. B-10 B-2 Parameters for the Meat Pathway ............................................................................................... B-11 B-3 Parameters for the Vegetable Pathway ....................................................................................... B-12 NOTE: Tables in Appendix D are named after their respective Operational Requirement.

3.3-12 Radioactive Liquid Effluent Monitoring Instrumentation ................................................................. D-3 4.3-8 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements ..................... D-5 3.3-13 Radioactive Gaseous Effluent Monitoring Instrumentation ............................................................ D-8 4.3-9 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements .............. D-10 4.11-1 Radioactive Liquid Waste Sampling and Analysis Program ........................................................ D-13 4.11-2 Radioactive Gaseous Waste Sampling and Analysis Program.................................................... D-19 3.12-1 Radiological Environmental Monitoring Program ......................................................................... D-29 3.12-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples ............................ D-35 4.12-1 Detection Capabilities for Environmental Sample Analysis Lower Limit of Detection (LLD) ........ D-36 G-1 Frequency Notation ..................................................................................................................... G-5 G-2 Operational Mode ........................................................................................................................ G-5 iii Page 9-9

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 LIST OF FIGURES No. Title Page 2.1-1 Liquid Waste Processing Flow Diagram ..................................................................................... 2-29 2.1-2 Liquid Effluent Flow Stream Diagram ......................................................................................... 2-30 2.1-3 Normal Service Water Flow Diagram ......................................................................................... 2-31 2.1-4 Other Liquid Effluent Pathways .................................................................................................. 2-32 2.3-1 Map of Harris Lake for Evaporation Dose Calculation ................................................................ 2-33 3.1 SHNPP Gaseous Waste Streams .............................................................................................. 3-70 3.2 Schematic of Airborne Effluent Release Points .......................................................................... 3-71 3.3 SHNPP Condenser Off-Gas System .......................................................................................... 3-72 4.1-1 Map of the Site Boundary ........................................................................................................... 4-17 4.1-2 Environmental Radiological Sampling Points (1 mile Radius) .................................................... 4-18 4.1-3 Environmental Radiological Sampling Points (10 mile Radius) .................................................. 4-19 iv Page 9-10

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 ODCM REV. 26 CHANGE

SUMMARY

Revision 26 to the ODCM is as follows:

DRRs 1998214, 1996625, 2008147, 2031405, 2031406 Section Page Description Table of Contents i Changed to ODCM REV. 26 CHANGE

SUMMARY

Entire Document The site's FSAR and the fleet now use a common revision number for the ODCM so the List of Effective Pages and revision headings were deleted. (DRR 2031406) The format and font of the entire document was adjusted for uniformity throughout.

ODCM REV 26 CHANGE v Changed to reflect Rev. 26 revisions.

SUMMARY

2.3 2-16 Added "and the consumption of fish from Harris Lake". This is an additional return/reuse pathway.

2.3.4 2-20 Added dose calculation from the consumption of fish from Harris Lake.

The dose assessment is based upon Reg Guide 1.109 (DRR 2008147) 3.0 3-1 Added "Minor release pathways, such as steam leaks, steam dumps, and open penetrations are evaluated for significant of release." (DRR 1998214) 3.1.1 3-2 Equation 3.1-1a and 3.1-1b incorrectly contain a summation sign. The equations are for the individual release rates rather than the sum of all the releases. (DRR 2031405) 3.1.1, 3.1.2 3-2, 3-7, 3-12, Changed X/Q from 2.30E-05 to 1.8E-05 to update to highest X/Q new 3.2.1, 3.3.1 3-18 value (AR 682873) 3.2.1 3-13 Changed X/Q period from 2003 - 2007 to 2010 - 2014 to reflect the new Appendix A update.

3.3.2 3-23 Changed D/Q from 1.00E-08 in SSW sector to 9.0E-09 in SW sector to update to highest D/Q new value (AR 682873) 3.3.2 3-24 Revised sentence "At SHNPP the SW sector has the highest X/Qv and the SSW sector has the highest annual average D/Qv values." to "At SHNPP the SW sector has the highest X/Qv and the SW and SSW sector have the highest annual average D/Qv values." because both the SW and SSW have the same D/Q = 9.0E-09 3.3.2 3-27 to 3-28 Revised Carbon-14 dose assessment to allow for dose to be calculated either quarterly or annually. Removed the word "annual" from descriptions and terms.

Changed the number of hours of photosynthesis per year from 4400 hours0.0509 days 1.222 hours 0.00728 weeks 0.00167 months to 4460 hour0.0516 days 1.239 hours 0.00737 weeks 0.0017 months s/yr and 1115 hour0.0129 days 0.31 hours 0.00184 weeks 4.242575e-4 months s/quarter. This result is based upon data from the US Naval Observatory for Raleigh, NC.

4.0 4-1 Deleted reference to figures 4.1-4, 4.1-5, and 4.1-6. Those figures were removed from the ODCM in earlier revision.

Table 4.1 - Direct Radiation 4-3 Added distance for location 5 at 13.3 mile (NCR 02047421)

Table 4.1 - Direct Radiation 4-5, 4-6 Deleted TLD locations 67, (HEEC), 34 (Apex), 35 (Holly Springs) and replaced with TLD locations 98 (Holly Springs school complex) and 99 (Friendship High School). Due to the growth in the area, these locations are more centrally located to population.

Deleted TLD locations 36 (Sunset Lake) and 37 (Fuquay Varina). These TLD locations are defined as special interest locations due to population centers per ODCMOR 3/4.12.1 and located approximately 10 miles from the plant. Since the inception of the Radiological Environmental Monitoring Program, the regional population has moved closer to the plant and these locations no longer meet the intent of ODCMOR 3/4.12.1 TLD locations #3 and #50 are new special interest locations.

(AR 02020000) v Page 9-11

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 ODCM REV. 26 CHANGE

SUMMARY

(continue)

Table 4.1 - Surface Water 4-6 Changed required analysis from Monthly Gross Beta and Quarterly Gamma Isotopic to the correct Monthly Gamma Isotopic and Quarterly Tritium per NUREG-1301 Table 3.12-1 Added note "H-3 analysis is normally performed monthly" Table 4.1 Groundwater 4-8 Removed Groundwater location 76 from the Radiological Environmental Monitoring Monitoring Program. The groundwater at this location does not meet the requirements for waterborne monitoring. Because this well is located within the protected area it is not used as a source of drinking water or irrigation. This well will be sampled per plant procedures and the results published in the Annual Effluent Release Report per ODCM Section F.2.

(AR 02020000)

Table 4.1 Ingestion -Milk 4-11 Removed location 96 from Milk. This location is no longer available because the homeowner no longer sells goat milk. According to the homeowner's business website the goat milk is used for the production of soap. (AR 02020000)

Table 4.1 Ingestion - Food 4-12 Removed location 5 from Food Crop. This location is no longer Products available because the homeowner no longer gardens. Added reference to notes 10 and 16. (AR 02020000)

Notes for Table 4.1 4-14 Revised Note 1 to remove reference to figures 4.1-4, 4.1-5, and 4.1-6.

Revised Note 10, 11, 12, and 14 to include new information regarding Food Crop location 5 and groundwater monitoring well 76. Revised note 15 to clarify the description of broadleaf vegetation. Added new note 16 "Attention shall be paid to including samples of tuberous and root food products."

Table 4.2 Radiological 4-15 Deleted "M" for Site #5 under FP. Deleted Site #76 under GW and #96 Environmental Monitoring under MK.

Program Table 4.3 Radiological 4-16 Deleted Site # 34, 35, 36, 37, 67 and added # 98, 99. Identified Environmental Monitoring locations #3 and #50 as special interest. Changed distance of #5 from Program (TLD Sites) >12 m. to 13.3 mi. (NCR 02047421)

Figure 4.1-2 4-18 Revised maps to reflect removal of location 76 Environmental Radiological Sampling Points Figure 4.1-3 4-19 Revised maps to reflect removal of location 34, 35, 36, 37, 96 and the Environmental Radiological addition of locations 98, 99 Sampling Points Appendix A A1 - A22 revised Appendix A to new XOQDOQ based upon 2010 - 2014 meteorology data. Increased the number of wind classifications from 7 to 13, concentrating more classes for the 0.75-3.50 mph wind speed. This class was split into 5 segments to get more accurate analysis of XOQDOQ. (AR 682873, DRR1996625)

Table 3.12-2 Food Products D-32 Added additional food product sample requirement from areas irrigated by water which liquid plant wastes have been discharged per NUREG-1301 Table 3.12-1. Note: there are currently no Food Products that are irrigated by plant discharges Note to Table 3.12-2 D-34 Added note 9 "If harvest occurs more than once per year, sampling shall be performed during each discrete harvest. If harvest occurs continuously, sampling shall be monthly." based upon NUREG-1301 Table 3.12-1 Table 4.12-1 D-36 Add the note "The specific LLD applies to the daughter nuclide of an Detection Capabilities for equilibrium mixture of the parent and daughter nuclides. Per the Branch Environmental Samples Technical Position, value of 60 pCi/L may be used for Ba-140 and 15 pCi/L may be used for La-140."

3 /4.12.3 Interlaboratory D-39 Deleted "The laboratory used for the Interlaboratory Comparison Comparison Program Program is to participate in the National Institute of Standard and Technology (NIST) program" This is not a recognized program.

vi Page 9-12

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26

1.0 INTRODUCTION

The Off-Site Dose Calculation Manual (ODCM) provides the information and methodologies to be used by Shearon Harris Nuclear Power Plant (SHNPP) to ensure compliance with Operational Requirements 3.3.3.10, 3.3.3.11, 3/4.11.1, 3/4.11.2, 3/4.11.4, 4.12.1, 4.12.2, and 4.12.3 and reporting requirements in Appendix F of the ODCM. These operational requirements are those related to normal liquid and gaseous radiological effluents, environmental monitoring, and reporting. They are intended to show compliance with 10CFR20-based requirements, 10CFR50.36a, Appendix I of 10CFR50, and 40CFR190 in terms of appropriate monitoring instrumentation, setpoints, dose rate, and cumulative dose limitations. Off-site dose estimates from non-routine releases will be included in the cumulative dose estimates for the plant to comply with Appendix I of 10CFR50.

The ODCM is based on "Westinghouse Standard Technical Specifications" (NUREG 1301), "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants" (NUREG 0133), and guidance from the United States Nuclear Regulatory Commission (NRC). Specific plant and Nuclear Generation Group (NGG) procedures implement the ODCM program requirements.

The ODCM has been prepared as generically as possible in order to minimize the need for future revisions.

However, some changes to the ODCM are expected in the future. Any such changes will be properly reviewed and approved as indicated in Administrative Controls Section 6.14 of the SHNPP Technical Specifications.

The assessment of annual radiation doses to members of the public from radioactive liquid and gaseous effluents from the plant is estimated using the methodology in the ODCM for the report period. These off-site dose estimates for each calendar year are reported in the Annual Radioactive Effluent Release Report required by Appendix F of the ODCM.

1-1 Page 9-13

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 2.0 LIQUID EFFLUENTS Radioactive materials released in liquid effluents from SHNPP to unrestricted areas are required to demonstrate compliance with 10 CFR 50 Appendix I (ODCM Operational Requirement 3.11.1.2) and, on an annual average basis, be limited to the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column

2. For dissolved or entrained noble gases the concentration shall be limited to 2E-4 Ci/ml total activity. On an individual release basis, the release concentration for liquid effluents will be limited to ten times (10x) the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2, Effluent Concentration (ODCM Operational Requirement 3.11.1.1). The liquid effluent release point is at the point of discharge from the Cooling Tower Blowdown Line into Harris Lake (see Figure 2.1-3 and T/S Figure 5.1-3).

Figure 2.1-1, Liquid Waste Processing Flow Diagram, and Figure 2.1-2 Liquid Effluent Flow Stream Diagram, show how effluents are processed and where they are released.

Effluent monitor identification numbers are provided in Appendix C. Liquid effluent dilution prior to release to Harris Lake is provided by the Cooling Tower Blowdown Line. Concurrent batch releases shall not occur at SHNPP.

The Secondary Waste Sample Tank (SWST) and the Normal Service Water (NSW) system have a low potential for radioactive effluent releases. These releases are checked by effluent monitors on the SWST (Figure 2.1-2) and the NSW lines (Figure 2.1-3).

The Turbine Building floor drains and the outside tank area drains (Figure 2.1-4) are monitored effluent lines with low probability of radioactive contamination.

The radioactive liquid waste sampling and analysis required for batch and continuous releases are found in Table 4.11-1 of the ODCM Operational Requirements.

The SHNPP ODCM uses the Canberra, Inc, Effluent Management System (OpenEMS) software for automating the necessary calculations and recordkeeping.

2-1 Page 9-14

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 2.1 Compliance with 10 CFR 20 10 CFR 20.1301 requires that the total effective dose equivalent to individual members of the public will not exceed 0.1 rem (100 mrem) in a year.

10 CFR 20.1302 states that a licensee can show compliance with the annual dose limit of 20.1301 by demonstrating that the annual average concentration of radioactive material released in liquid effluents at the boundary of the unrestricted area does not exceed the values specified in 10 CFR 20, Appendix B, Table 2, Column 2.

ODCM Operational Requirement 3.11.1.1 states that, on an individual release basis, the concentration of radioactive material released in liquid effluents to unrestricted area shall be limited to 10 times the values specified in 10 CFR 20, Appendix B, Table 2, Column 2.

ODCM Operational Requirement 3.3.10 requires that radioactive effluent instrumentation have alarm/trip setpoints that will ensure that an alarm/trip will occur prior to exceeding 10 times the limits of ODCM Operational Requirement 3.11.1.1. for principal gamma emitters.

Liquid effluent monitors have two setpoints, the high alarm and the alert alarm. The high alarm setpoint, Smax, provides alarm and isolation if the radionuclide concentrations, when diluted, would approach the ODCM Operational Requirement limits for concentrations in unrestricted areas. Alert alarm setpoints, Salert, are set at a fraction of the Smax to provide an early warning of the approach to ODCM Operational Requirement limits.

2.1.1 Batch Releases Radioactive liquids are routinely released as batches from Treated Laundry and Hot Shower Tanks (TL&HST), Waste Evaporator Condensate Tank. Batch releases may also originate from the the Secondary Waste Sample Tank (SWST) and Waste Monitor Tanks (WMT). These tanks are shown in Figures 2.1-1 and 2.1-2. Based on analysis of the tank contents, the tank release rate is adjusted, based on the Cooling Tower Blowdown Line flow rate, to dilute the tank activities to 50 percent of the allowable concentrations at the release point to Harris Lake.

The ODCM software calculates a nuclide specific response setpoint which is based on the sum of responses for each nuclide. The nuclide specific response setpoint equates all gamma-emitting nuclides to Cs-137, to which the monitor is calibrated.

If analysis of the batch sample indicates all gamma-emitting nuclides are < LLD, (as defined in ODCM Operational Requirement Table 4.11-1), the tank gamma activity, Ci, may be assumed to consist only of Cs-134. This nuclide has the lowest Effluent Concentration Limit (ECL) of any to be found in liquid effluents and provides a conservative basis for a monitor setpoint.

2-2 Page 9-15

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 2.1.1 Batch Releases (continued)

1. Minimum Tank Mixing Time Footnote 2 to ODCM Operational Requirement Table 4.11-1 requires that the method used to mix an isolated effluent tank prior to sampling and analysis be described.

Equation 2.1-1 below provides an acceptable method for ensuring a well mixed tank so that a representative sample can be taken for radioactivity or other appropriate analyses.

(V) (E) (N)

R = (2.1-1)

(RR) (60) where:

R = Minimum allowable mixing time, hr V = Tank capacity, gal E = Eductor factor RR = Pump design recirculation flow rate, gpm n = Number of tank volumes for turnover; this will be a minimum of two 60 = 60 min/hr Table 2.1-1a lists the tank capacities, eductor factors, and pump design recirculation flow rates for individual liquid effluent release tanks.

Table 2.1-1b lists actual operational tank capacities, educator factors, and pump recirculation flows and pressures. These values are used by operations to ensure adequate mixing of two tank volumes The greater of the two minimum mixing times is used for determining time for obtaining a representative sample for release.

2-3 Page 9-16

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 2.1.1 Batch Releases (continued)

2. Required Dilution Factor ODCM Operational Requirement 3.11.1.1 requires that the sum of concentrations divided by ECL values must not exceed 10 for an individual release. Therefore:

Ci 10 (2.1-2) i ECLi where:

Ci = the concentration of nuclide i to be released ECLi = the Effluent Concentration Limit for nuclide i from 10CFR20, Appendix B, Table 2, Column 2.

If the summation is greater than 10, dilution is required. The total required dilution factor, Dreq, is the minimum acceptable dilution factor required to meet the limits of ODCM Operational Requirement 3.11.1.1, based on pre-release and composite analysis.

Dreq = Dreq,g + Dreq,ng (2.1-3) where:

Dreq,g = Required dilution factor for gamma-emitters Ci i = g ECLi

= (2.1-4) f

R max f = 0.5

= A safety factor to assure that the nuclide concentrations are 50% of the ODCM Operational Requirement limit at the point of discharge.

Rmax = The maximum ECL ratio for the release point (normally set to 10).

2-4 Page 9-17

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 2.1.1 Batch Releases (continued)

Dreq,ng = Required dilution factor for non-gamma-emitters Ci i = ng ECL i r

= + (2.1-5) f

R max f

R max and f = 0.5

= A safety factor to assure that the nuclide concentrations are 50% of the ODCM Operational Requirement limit at the point of discharge.

r = 1

= the ratio of the maximum tritium concentration to the H-3 ECL, to take into account that tritium is potentially being released via the settling basin discharge to the cooling tower discharge line. The maximum tritium value is set to 1.0E-03, which is the H-3 ECL.

NOTE: site has a target limit of 2.0E-04 µCi/ml.

Rmax = The maximum ECL ratio for the release point (normally set to 10).

The sums include gamma-emitters (g) and non-gamma-emitters (ng), respectively.

The measured concentration of each gamma-emitting nuclide, including noble gases, is reported in Ci/ml. If no gamma activity is detectable then an activity of 9E-07 Ci/ml of Cs-134 is assumed for setpoint calculations. The measured concentration of non-gamma emitters is determined by analysis of the liquid effluent or previous composite sample, and is reported in Ci/ml.

2-5 Page 9-18

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 2.1.1 Batch Releases (continued)

3. Maximum Waste Flow For liquid releases,the maximum permissible waste flow rate for this release, Wmax is the minimum of Rcwmax and Rwmax, where Favail

falloc R CWMAX = (2.1-6)

Dreq Rwmax = Liquid effluent tank maximum waste flow rate, as specified in Table 2.1-

1. This value is the same as Fwaste.

and Favail = The available dilution flow is the minimum dilution stream flow (Cooling Tower Blowdown) that can be ensured for the period of the release.

Since only one batch release occurs at a time out of a single discharge point, the flow is not corrected for other releases in progress, for any activity in the dilution stream, or reduced by a safety factor. The minimum dilution flow rate for each setting is shown in Table 2.1-2.

falloc = Fraction of the available dilution volume which may be assigned to a particular release to ensure discharge point limits are not exceeded by simultaneous radioactive liquid releases. The value of falloc is based on assumed operational considerations for simultaneous releases but normally will be 0.8 for a batch release and 0.2 for a continuous release.

4. Minimum Dilution Flow Rate The Minimum Dilution Flow Rate (min_dflow) is the minimum Cooling Tower discharge flow necessary to dilute the release to less than ODCM Operational Requirement Limits.

If Dreq 1, the minimum dilution flow rate is set to 0.0. If Dreq > 1, the minimum dilution flow rate is determined as follows:

Fwaste

D req min_dflow = (2.1-7) falloc where Fwaste = waste flow anticipated for this release 2-6 Page 9-19

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 2.1.1 Batch Releases (continued)

5. Setpoint Calculations The ODCM software calculates a nuclide specific response setpoint, which is based on the sum of responses for each nuclide. The setpoint equates all gamma-emitting nuclides to Cs-137, to which the monitor is calibrated. The setpoint is listed in terms of Cs-equiv and the units are Ci/ml.

If analysis of the batch sample indicates all gamma-emitting nuclides are < LLD, (as defined in ODCM Operational Requirement Table 4.11-1), the tank gamma activity, Ci, may be assumed to consist only of Cs-134. This nuclide has the lowest ECL of any to be found in liquid effluents and provides a conservative basis for a monitor setpoint.

(1) Maximum setpoint value, based on Nuclide Specific Response Smax (Cs-equiv) = (Sadj

Rmon) + B (2.1-8) where Sadj = Setpoint adjustment factor.

falloc

Favail Dreq, ng Fwaste

= (2.1-9)

Dreq, g Sadj should always be greater than 1 to ensure that adequate dilution flow is available for the release.

B = monitor background (Ci/ml) 2-7 Page 9-20

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 2.1.1 Batch Releases (continued)

Rmon = slopei

Ci where the sum extends over all nuclides which have response factors stored in the database for the monitor of interest and slopei = the Liquid Effluent Monitor Gamma Sensitivities (from Table 2.1-4) for nuclide i, relative to Cs-137. To make nuclide i relative to Cs-137, the nuclide sensitivity is divided by the Cs-137 sensitivity.

= Sensitivity (nuclide i)

Cs-137 Sensitivity (2) Monitor alert alarm setpoint, Salert (Cs-equiv)

An Alert Alarm setpoint is calculated to provide an operator with adequate warning that the high alarm setpoint is being approached. Salert is calculated from the nuclide specific response setpoint.

Salert = [(Smax - B)

Fx] + B (2.1-10) where:

Fx = A value <1.0 designed to provide an operator with adequate warning that the high alarm setpoint is being approached.

2-8 Page 9-21

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 2.1.1 Batch Releases (continued)

(3) Check for Excessive Monitor Background In order to differentiate between the Salert and the statistical fluctuations associated with a high monitor background, a check for excessive monitor background is made. As a check, verify that the minimum detectable concentration (MDC) for the monitor is less than 0.1 of the net Salert; therefore, background is acceptable if:

MDC 0.1[(Smax - B)

Fx] (2.1-11) where:

Bkg 2

2 MDC = (2.1-12)

Em where:

= Signal Processor Time constant, minutes. (Table 2.1-3)

Bkg = Background Count Rate, in cpm

= B / Em Em = Monitor efficiency for the Cs-137 gamma energy, cpm/Ci/ml determined by primary calibration.

If not, postpone the release and decontaminate or replace the sample chamber to reduce the background, then recalculate Smax and Salert using the new, lower background.

6. Post-Release Compliance After the release is made, actual concentrations are used to check 10 CFR 20 limits, and the actual dilution flow and waste flow are used instead of the anticipated dilution flow and waste flow.

For batch releases, the duration is determined from the start and end dates and times of the release. This is used with the actual release volume to calculate the release rate.

2-9 Page 9-22

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 2.1.2 Continuous Releases The continuous releases from the SWST and the NSW return lines are monitored as shown in Figures 2.1-2 and 2.1-3. The function of these monitors, in contrast to the isolation function of batch release tank monitors, is to provide an indication of low levels of radioactivity in the effluent. The continuous effluent monitor setpoint is based on an assumed FSAR nuclide mix for the SWST (from Table 11.2.1-5 of the FSAR).

The software does not calculate continuous release setpoints.

1. Monitor High Alarm Setpoint, Smax (Ci/ml).

0.1 (ECL eff

Senseff ) + Bkg S max = (2.1-13)

Em where:

ECLeff = Weighted Effluent Concentration Limit for the SWST nuclides listed in Table 11.2.1-5 of the FSAR.

Senseff = g (Sensi x % abundance) for the SWST nuclide mix, cpm/Ci/ml.

2. Monitor Alert Alarm Setpoint, Salert (Cs-equiv)

Salert = [(Smax - B)

Fx] + B (2.1-14)

When the monitor is operable and not in alarm, analysis of weekly composite samples is not required by ODCM Operational Requirement Table 4.11-1.

If the monitor is in alarm or the presence of non-naturally occurring radioactivity > effluent LLD is confirmed, the releases may continue provided the sampling and analysis required by ODCM Operational Requirement Table 4.11-1 are performed. The results of the sample analysis will be evaluated for compliance with ODCM Operational Requirement 3.11.1.1.

The monitor alarm setpoints may be recalculated using the methodology in Section 2.1.1 with the results of the gamma analysis and analyses of the composite sample.

3. Check for Excessive Monitor Background Monitor background is considered excessive when the minimum detectable concentration (MDC) for the monitor is >0.01 ECLeff. Therefore, background is acceptable if:

0.01(ECLeff

Senseff)

MDC (2.1-15)

Em 2-10 Page 9-23

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 2.1.3 Other Liquid Releases

1. Outdoor Tank Area Drain Effluent Line The outdoor tank area drain effluent line routes rain water collected in the outdoor tank area to the storm drain system and from there directly to the lake. The line is monitored for radioactivity by the Tank Area Drain Transfer Pump Monitor. Because no radioactivity is normally expected in this line, the monitor high alarm and alert alarm setpoints are determined using the methodology is Section 2.1.2. If the setpoint is exceeded, the discharge pump is automatically secured. Effluent can then be diverted to the floor drain system for processing and eventual release (see Figures 2.1-1 and 2.1-2).

2. Turbine Building Floor Drains Effluent Line Water collected in the turbine building floor drains is normally routed to the yard oil separator for release to the environment via the waste neutralization system and then to the cooling tower discharge line. Tritium is expected to be detected in this pathway from sources such as background from the lake. Because no other radioactivity is normally expected in this path, the setpoints for the turbine building drain monitor are determined using the methodology in Section 2.1.2. Should the setpoint be exceeded, the release is automatically terminated. Effluent can then be diverted to the secondary waste treatment system for processing and eventual release (see Figures 2.1-1 and 2.1-2).

2-11 Page 9-24

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 2.2 Compliance with 10 CFR 50 Appendix I 2.2.1 Cumulation of Doses The dose contribution from each release of liquid effluents will be calculated and a cumulative summation of the total body and each organ dose will be maintained for each 31 days (monthly), each calendar quarter, and the year.

The dose is the total over all pathways which apply to that receptor. A receptor is defined by receptor ID, age group (infant, child, teen, or adult), sector, and distance from the plant.

The dose contribution for batch releases and all defined periods of continuous release received by receptor "r" from a released nuclide "i" will be calculated using the following equation:

Dir = Air

ts Cis Frs (2.2-1) where:

Dir = the cumulative dose or dose commitment to the total body or an organ "" by nuclide "i" for receptor "r" from the liquid effluents for the total time period of the release, in mrem.

Air = site-related ingestion dose or dose commitment factor for receptor "r" to the total body or organ "" for nuclide "i", in mrem/hr per Ci/ml.

ts = length of time period 's', over which the concentration and F value are averaged, for all liquid releases, in hours.

Cis = the average concentration of nuclide "i" in undiluted liquid effluent during time period ts from any liquid release, in Ci/ml.

Frs = the near field average dilution factor for receptor "r" during any liquid effluent release Where:

Fwaste Frs =

R mix (2.2-2)

Fwaste + Favail and Rmix = mixing ratio

= fraction of the release that reaches the receptor. At the SHNPP, this value is set to 1.

Also, the sum extends over all time periods 's'.

In the case of a continuous secondary waste sample tank radioactive release, Ci = the concentration of nuclide "i" in the SWST composite sample. For the NSW, Ci = concentration of nuclide "i" in the cooling tower basin and Fwaste = discharge from the cooling tower basin while Favail = the flow from the makeup water cross-tie. For a release through the Turbine Building Floor Drain Line to the waste neutralization system, Ci = the Turbine Building floor drain sample activity, Fwaste = discharge from the Turbine Building floor drain line, and Favail = the average flow during the period of the total Cooling Tower discharge. The total Cooling Tower discharge is the sum of the Cooling Tower Blowdown flow and the Cooling Tower Bypass Line flow.

When there is a primary-to-secondary leak, the change in concentration of tritium in the steam generators times the secondary loses (balance of plant), will be used for effluent accountability. The secondary loss rate will also be used for volume accountability.

2-12 Page 9-25

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 The dose factor Ai (see NUREG-0133, Section 4.3.1) was calculated for an adult for each isotope "i" using the following equation:

t 730 i p A = 1.14E + 05 ( + 21BF ) DF

e (2.2-3) i D i i w

where:

Ai = The ingestion dose commitment factor to the whole body or any organ "" for an adult for each nuclide "i". Corresponding to fish consumption from the Harris Lake (dilution = 1) and drinking water from Lillington (dilution = 13.95).

= Values for the adult total body and organs in mrem/hr per Ci/ml are given in Table 2.2-1.

1.14E+05 = Unit Conversion Factor 6

10 pci 1000 ml 1 yr

= * * (2.2-4) 1 Ci 1 liter 8760 hrs 21 = Adult fish consumption rate (from Table E-5 of Regulatory Guide 1.109, Rev. 1), kg/yr; 730 = Adult water consumption rate (from Table E-5 of Regulatory Guide 1.109, Rev. 1), liters/yr.

Dw = Dilution factor for the drinking water pathway

= 13.95 BFi = Bioaccumulation factor for nuclide "i" in fish (from Table A-1 of Regulatory Guide 1.109, Rev. 1), pCi/kg per pCi/l DFi = Dose conversion factor for nuclide "i" for adults for a particular organ (from Table E-11 of Regulatory Guide 1.109, Rev. 1), mrem/pCi i = Radiological decay constant of nuclide "i," hr-1;

= 0.693 (t1/2)i (t1/2)i = Radiological half-life of nuclide "i," hr; tp = Average transport time to reach point of exposure, hr;

= 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The more limiting decay time for the drinking water and fish exposure pathways (Reg. Guide 1.109, Appendix A, Rev. 1).

-itp Table 2.2-1 presents the Ai values for an adult receptor. Values of e are presented in Table 2.1-4 for each nuclide i".

2-13 Page 9-26

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 2.2.2 Comparison Against Limits The sum of the cumulative dose from all batch and any continuous releases for a quarter is compared to one-half the design objectives for total body and any organ. The sum of the cumulative doses from all releases for a calendar year is compared to the design objective doses. The following relationships should hold for the SHNPP to show compliance with ODCM Operational Requirement 3.11.1.2.

For the calendar quarter:

Dir 1.5 mrem total body (2.2-5)

Dir 5 mrem any organ (2.2-6)

For the calendar year:

Dir 3 mrem total body (2.2-7)

Dir 10 mrem any organ (2.2-8) where:

Dir = Cumulative total dose to any organ t or the total body from all releases, mrem:

The quarterly limits given above represent one-half the annual design objective of 10 CFR 50, Appendix I, Section II.A. If any of the limits in equations (2.2-5) through (2.2-8) are exceeded, a special report pursuant to SHNPP Technical Specification 6.9.2 must be filed with the NRC. This report complies with Section IV.A of Appendix I, 10 CFR 50.

The calculations described in Section 2.2.1 will be used to ensure compliance with the limits in 10 CFR 50 Appendix I for each release. Summation of doses for all releases for the quarter and year are compared to the limits in 10CFR50 Appendix I to ensure compliance.

The SHNPP ODCM uses a "modified" NUREG 0133 equation with conservative assumptions. It calculates the dose to a single maximum (ALARA) individual. The ALARA individual is an individual that consumes fish caught in the Harris Lake (dilution of 1.0) and receives their drinking water from Lillington, North Carolina (dilution 13.95).

After the release is made, the doses are compared to the 10CFR50 limits. The actual dilution flow and waste flow are used instead of the anticipated dilution flow and waste flow.

For batch releases, the duration is determined from the actual start and end dates and times of the release.

This is used with the actual volume input to calculate the release rate. Each month the dilution volume is updated for times when no releases were being made in order to update the quarterly and yearly doses for comparison with the 10CFR50 Appendix I limits.

2-14 Page 9-27

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 2.2.3 Projection of Doses Dose projections for this section are required at least once per 31 days (monthly) in ODCM Operational Requirement 4.11.1.3.1 whenever the liquid radwaste treatment systems are not being fully utilized.

The doses will be calculated using Equation 2.2-1, and projected using the following expression:

Dp = (D

p) + Da (2.2-9) where:

Dp = the 31 Day Projected Dose by organ D = sum of all open and closed release points from the start of the quarter to the end of the current release in mrem per organ .

p = the Projection Factor which is the result of 31 divided by the number of days from start of the quarter to the end of the release.

Da = Additional Anticipated Dose for liquid releases by organ r and quarter of release.

NOTE: The 31 Day Projected Dose values appear on the Standard Permit Reports. The 31 day dose projections include any additional dose.

When possible, expected operational evolutions (i.e., outages, increased power levels, major planned liquid releases, etc.) should be accounted for in the dose projections. This may be accomplished by using the source-term data from similar historical operating experiences where practical, and adding the dose as Additional Anticipated Dose.

To show compliance with ODCM Operational Requirement 3.11.1.3, the projected 31 day dose should be compared to the following limits:

Dp 0.06 mrem for total body (2.2-10) and Dp 0.2 mrem for any organ (2.2-11)

If the projections exceed either Expressions 2.3-2 or 2.3-3, then the appropriate portions of the liquid radwaste treatment system shall be used to reduce releases of radioactivity.

2-15 Page 9-28

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 2.3 Doses from Return/Re-use of Previously Discharged Radioactive Effluents Known Potential Pathways from Return/Re-use of Previously Discharge Effluents The dose contribution from return/re-use of previously radioactive effluents (tritium from the lake) should be calculated at the end of each year. If the dose from the particular pathway is greater than 10 percent of the total dose from all pathways from plant releases (liquid, gaseous, iodines particulates > 8 day half lifes &

tritium from gaseous releases) the dose from the return of previously discharged effluents is to be reported in annual effluent report. The total body, each organ, and each age group if applicable the dose should be calculated at the end of year unless it is known to be less than 10 percent of all doses.

The current potential pathways are evaporation from the cooling tower, dose to the county fire training personnel & HE&EC Training center that is being used of offsite personnel, the dose to the nearest resident to the lake from lake evaporation, and the consumption of fish from Harris Lake.

2.3.1 The dose from drinking water to the worker at the Wake County Fire Training Center and/or HE&EC Training Center are to be calculated as follows:

Worker Drinking Water Pathway -

Rapj = Uap

Dapj

Cip (2.3-1)

Where; Rapj = Annual dose to organ j of individual of age group (adult in this case) from tritium in p pathway (ingestion), mrem/yr Uap = Usage term, 730 liters/year per Reg. 1.109 based on 50 weeks/year, this equals 14.6 liters/week or 2.085 liters/day. Half of the water is consumed at work 1.042 liters/day times 5 work days/week times 50 weeks /year equals 261 liters/year of drinking water from HNP.

Cip = Concentration (picoCurie/liter) of drinking water obtained from the annual average monthly composite from DW-51 Dapi = Dose factor specific to age group (adult in this case), for nuclide i (H-3 in this case) in units of mrem/picoCurie, 1.05E-07 mrem/pCi for total body & all organs with the exception of bone which has no dose Rapj = (261 liters/yr) * (1.05E-07 mrem/pCi) * (concentration pCi/L from DW-51) 2-16 Page 9-29

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 2.3.2 Tritium dose to the nearest resident from the Cooling Tower (CT)Plume.

The dose from inhalation to the nearest resident from the cooling tower plume is calculated by the following meteorology for the current year (using the elevated mode of release), the monthly composite tritium analysis from the cooling tower blowdown, and the evaporation rate from the top of the cooling tower.

The dose from Cooling Tower Plume can be calculated as follows:

DTr = (3.17E - 08) * (RTI) * (X/QElv) QVT (2.3-2) where:

DTr = the cumulative dose or dose commitment to the total body or an organ "" by Tritium for receptor "r" from the CT Plume for the total time period of the release, in mrem.

3.17 E-08 = The inverse of the number of seconds in a year (sec/year)-1 RTi = Dose factor for an organ "" for the tritium from the inhalation pathway in mrem/hr per Ci/ml.

X/QElv = The highest elevated calculated annual average relative concentration for the 3

nearest resident from the Cooling Tower (sec/m ).

QVT = Evr

ts

CTBD

qt The total tritium (µCi) released from the top of the Cooling Tower.

where:

Evr = the average evaporation rate from top of the Cooling Tower (CTBD)* (3785 ml/gal)

= ml/min.

CTBD = Average Cooling Tower Blowdown flow rate (gpm) ts = length of time period 's', over which the monthly tritium concentration value for Cooling Tower Tritium is used (number of days) * (1440 min/day) = minutes qt = Tritium concentration in Cooling Tower Blowdown for the time period (µCi/ml).

2-17 Page 9-30

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 2.3.3 Tritium dose to the nearest lake resident from lake evaporation.

The dose from inhalation to the nearest resident to the lake from lake evaporation is calculated by the meteorology for the current year (using the ground level mode of release), the monthly composite tritium analysis from Harris lake Spillway, and the evaporation rate from the lake.

1. Release Calculation from Evaporation:

Three methods are used to calculate monthly lake evaporation to the environment from the reservoir.

a. Analytical Method: Calculation of monthly evaporation using an empirical analytical formula developed by Meyer (1905) based on Daltons Law.

Ev = C * (Es - Ed) * (1 + U25/10) (2.3-3)

Where:

Ev = evaporation from a lake or pond in inches per month times 25.4 mm/inch times meter/1000mm equals meters of evaporation C = Coefficient that equals 11 for small lakes and reservoirs 15 for shallow ponds (for Harris Lake use 11)

Es = saturation vapor pressure (inches of Hg) of air at the water temperature (1 foot deep)

Ed = actual vapor pressure (inches of Hg) of air, equals to Es

Relative Humidity (RH) in fraction U = average wind velocity (miles/hr) at a height of 25 feet above the lake or surrounding areas

b. Derive the average evaporation rate from historical data.

Monthly historical evaporation data are available for the Chapel Hill station.

c. When available, use the monthly published evaporation rates by the State Climate Office of North Carolina.

Calculate the average evaporation rate from the above three methods (if data is obtainable from all three) for each month.

2. Yearly Calculation of Tritium Release from Lake (µCi)

QT = (Larea

EVave * (LTConc

1E-09)) (2.3-4)

Where:

QT = Yearly Tritium Release from Lake (Ci)

Larea = Lake area, 4169.61 acres which equals 1.687E+07 square meters EVave = evaporation from a lake or pond in inches per month times 25.4 mm/inch times meter/1000mm equals meters of evaporation LTConc = Monthly lake Tritium concentration from SW-26, pCi/l 3

1E-09 = Ci/1.0E12 pCi

liter/1000 cm

100 cm/meter

100 cm/meter

100 cm/meter =

3 Curies/meter 2-18 Page 9-31

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26

3. Lake Harris total surface area is 4169.61 acres. Being a large body of water the lake was divided into thirteen sections for analysis using Auto CAD Engineering Software. The area of each section and its centroid location were calculated (see Figure 2.3-1) and the following list for the respective section areas. The distances from the centroid to each nearest resident and its downwind sector are now established.

Lake Area Area 2

Sect. Acres m 1 316.40 1.280E+06 2 276.55 1.119E+06 3 156.32 6.326E+05 4 220.74 8.933E+05 5 230.05 9.310E+05 6 388.74 1.573E+06 7 392.03 1.587E+06 8 579.23 2.344E+06 9 426.97 1.728E+06 10 429.05 1.736E+06 11 316.52 1.281E+06 12 193.90 7.847E+05 13 243.10 9.838E+05 Total 4169.61 1.687E+07 The impact of each lake section are be calculated and then summed to determine the impact of the point of interest. The tritium concentration from each section of the lake to the point of interest for all points of interest is calculated as follows:

qTsect = (QT

X/Q

3.17E+04) (2.3-5)

Where:

qTsect = Total tritium concentration from the thirteen lake sections at point of interest (X,pCi/m3)

QT = Yearly Tritium Release from Lake Section, (Ci/yr)

X/Q = The relative concentration at the point of interest from lake section X, (sec/m3) 3.17E+04 = Conversion factor, (1.0E+12 pCi/Ci)/(8760 hr/yr)*(3600 sec/hr) 2-19 Page 9-32

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 The dose for each age group at each point of interest is to be calculated as follows:

Dosea,poi = (qTsect) * (DFA)a * (BR)a (2.3-6)

Where:

Dosea,poi = Total tritium dose for age group (a) at point of interest (mrem) for the year qTsect = Total tritium concentration from the thirteen lake sections at point of interest (pCi/m3)

(DFA)a = Organ inhalation factor for tritium at the point of interest of age group a (mrem/pCi), for tritium the dose factor is same for the liver, total body, thyroid, kidney, lung, and Gi-LLi (no bone dose). Infant = 4.62 E-07, Child = 3.04 E-07, Teen = 1.59 E-07, and Adult 1.58 E-07, mrem/pCi.

(BR)a = Breathing rate of age group a (m3/yr), Infant = 1400, Child = 3700, Teen =

8000, and Adult = 8000 m3/yr 2.3.4 The dose from the consumption of fish from Harris Lake. The concentration of tritium in fish is directly related to the concentration of tritium in the water. Equilibrium ratios between the concentration of tritium in the water and concentration of tritium in the flesh is based upon the bioaccumulation factor for tritium.

Because the adult age group will always have the maximum dose from fish consumption, adult is only age group considered.

Fish consumption Dose -

Rapj = Uap

Dapj

Cip

BFi (2.3-7)

Where; Rapj = Annual dose to organ j of individual of age group (adult in this case) from tritium in p pathway (ingestion), mrem/yr Uap = Usage term, 21 kg/yr per Reg. Guide 1.109 Table E-11 for an adult Cip = Concentration (pCi/L) of drinking water obtained from the annual average monthly composite from SW-26 Dapi = Dose factor specific to age group (adult in this case), for nuclide i (H-3 in this case) in units of mrem/pCi, 1.05E-07 mrem/pCi for total body & all organs with the exception of bone which is no dose BFi = Bioaccumulation factor for nuclide "i" in fish (from Table A-1 of Regulatory Guide 1.109, Rev.

1), pCi/kg per pCi/l, 0.90 pCi/kg per pCi/L 2-20 Page 9-33

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 2.1-1a LIQUID EFFLUENT RELEASE TANKS AND PUMPS DESIGN BASIS (1)

Tank Radiation No. of PUMP DESIGN CAPACITY (gpm) Eductor Capacity Effluent Tank (2) Tanks Discharge Recirculation Factor (gal) Monitor ID SWST 1 100 100 0.2 25,000 REM-3542 WECT 2 35 35 1.0 10,000 REM-3541 (3)

WMT 2 100 100 0.25 25,000 REM-3542 TL&HS 2 100 100 0.25 25,000 REM-3540 1

Reference SHNPP FSAR Tables 11.5.1-1 and 11.2.1-7 2

SWST: Secondary Waste Sample Tank WECT: Waste Evaporator Condensate Tank WMT: Waste Monitor Tank TL&HS: Treated Laundry and Hot Shower Tank 3

Waste Monitor Tanks are used to batch release secondary waste effluent when activity is suspected in this pathway.

TABLE 2.1-1b LIQUID EFFLUENT RELEASE TANKS AND PUMPS FOR NORMAL OPERATIONS (1)

PUMP CAPACITY Tank Capacity Radiation No. of Eductor @

Tank (2) Recirculation Pressure Effluent Tanks Factor Overflow (gpm) (psig) Monitor ID Line (gal)

SWST 1 80 71 0.2 23,922 REM-3542 WECT 2 35 110 1.0 9,447 REM-3541 (3)

WMT 2 80 101 0.25 23,945 REM-3542 TL&HS 2 80 91 0.25 25,000 REM-3540 1

Typical values used for normal operations.

The settling basin has two pumps. When one pump is running, the design flow rate is 500 gpm. When both pumps are running, the design flow rate is 800 gpm.

2-21 Page 9-34

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 2.1-2 Setpoints for Cooling Tower Blowdown Dilution Flow Rates (Favail)

Setting Trip Flow Rate (gpm) Minimum Dilution Flow Rate (gpm) 1 4,000 +/- 5% 3,800 2 7,000 +/- 5% 6,650 3 11,000 +/- 5% 10,450 4 15,000 +/- 5% 14,250 TABLE 2.1-3 Signal Processor Time Constants () for GA Technologies RD-53 Liquid Effluent Monitors Detector Background (cpm) (min) 101 - 102 10 2 3 3 10 - 10 10 /cpm bkg 3 4 10 - 10 103/cpm bkg 104 - 105 103/cpm bkg 105 - 106 0.01 6 7 10 - 10 0.01 2-22 Page 9-35

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Page 1 of 3 TABLE 2.1-4 Nuclide Parameters Half-Life Sensitivity Sensitivity

-t Nuclide (hr) (hr-1) e (cpm/Ci/ml) Slope TB Bldg.

Drain Only (cpm/Ci/ml)

H-3 1.08E+05 6.44E-06 1.00E+00 0.00E+00 0.00E+00 0.00E+00 C-14 5.02E+07 1.38E-08 1.00E+00 0.00E+00 0.00E+00 0.00E+00 F-18 1.83E+00 3.78E-01 1.07E-02 0.00E+00 0.00E+00 7.78E+07 Na-24 1.50E+01 4.62E-02 5.74E-01 9.36E+07 9.00E-01 9.11E+07 P-32 3.43E+02 2.02E-03 9.76E-01 0.00E+00 0.00E+00 0.00E+00 Cr-51 6.65E+02 1.04E-03 9.88E-01 1.61E+07 1.55E-01 2.79E+06 Mn-54 7.50E+03 9.24E-05 9.99E-01 1.03E+08 9.90E-01 4.45E+07 Mn-56 2.58E+00 2.68E-01 4.00E-02 1.01E+08 9.71E-01 6.41E+07 Fe-55 2.37E+04 2.93E-05 1.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 1.07E+03 6.47E-04 9.92E-01 1.26E+08 1.21E+00 4.58E+07 Co-57 6.50E+03 1.07E-04 9.99E-01 0.00E+00 0.00E+00 5.82E+06 Co-58 1.70E+03 4.08E-04 9.95E-01 1.46E+08 1.40E+00 5.68E+07 Co-60 4.62E+04 1.50E-05 1.00E+00 1.89E+08 1.82E+00 9.07E+07 Ni-63 8.78E+05 7.89E-07 1.00E+00 0.00E+00 0.00E+00 0.00E+00 Ni-65 2.52E+00 2.75E-01 3.67E-02 2.24E+07 2.15E-01 1.96E+07 Cu-64 1.27E+01 5.46E-02 5.19E-01 5.16E+07 4.96E-01 1.46E+07 Zn-65 5.87E+03 1.18E-04 9.99E-01 5.24E+07 5.04E-01 2.41E+07 Zn-69 9.27E-01 7.48E-01 1.26E-04 2.22E+03 2.13E-05 5.00E+02 Zn-69m 1.38E+01 5.03E-02 5.47E-01 0.00E+00 0.00E+00 3.52E+07 Br-82 3.53E+01 1.96E-02 7.90E-01 0.00E+00 0.00E+00 1.43E+08 Br-83 2.38E+00 2.91E-01 3.05E-02 1.95E+06 1.88E-02 5.74E+05 Br-84 5.30E-01 1.31E+00 1.53E-07 6.50E+07 6.25E-01 5.06E+07 Br-85 4.78E-02 1.45E+01 3.02E-76 6.76E+06 6.50E-02 3.21E+06 Rb-86 4.48E+02 1.55E-03 9.82E-01 8.39E+06 8.07E-02 3.96E+06 Rb-88 2.97E-01 2.34E+00 6.66E-13 1.45E+07 1.39E-01 1.83E+07 Rb-89 2.57E-01 2.70E+00 8.43E-15 1.22E+08 1.17E+00 7.00E+07 Sr-89 1.21E+03 5.71E-04 9.93E-01 1.46E+04 1.40E-04 6.72E+03 Sr-90 2.50E+05 2.77E-06 1.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-91 9.50E+00 7.30E-02 4.17E-01 8.16E+07 7.85E-01 3.48E+07 Sr-92 2.72E+00 2.55E-01 4.68E-02 1.01E+08 9.71E-01 4.61E+07 Y-90 6.42E+01 1.08E-02 8.78E-01 0.00E+00 0.00E+00 0.00E+00 Y-91 1.41E+03 4.93E-04 9.94E-01 2.83E+05 2.72E-03 1.36E+05 Y-91m 8.28E-01 8.37E-01 4.36E-05 1.28E+08 1.23E+00 3.96E+07 Y-92 3.53E+00 1.96E-01 9.50E-02 2.76E+07 2.65E-01 1.17E+07 Y-93 1.01E+01 6.86E-02 4.39E-01 1.37E+07 1.32E-01 3.96E+06 Zr-95 1.54E+03 4.51E-04 9.95E-01 1.07E+08 1.03E+00 4.35E+07 Zr-97 1.68E+01 4.12E-02 6.10E-1 2.68E+07 2.58E-01 9.16E+06 Nb-95 8.42E+02 8.24E-04 9.90E-01 1.06E+08 1.02E+00 4.41E+07 Nb-97 1.20E+00 5.771E-01 9.86E-04 0.00E+00 0.00E+00 4.33E+07 Mo-99 6.60E+01 1.05E-02 8.82E-01 3.47E+07 3.34E-01 9.38E+06 Tc-99m 6.02E+00 1.15E-01 2.51E-01 1.11E+08 1.07E+00 7.33E+06 2-23 Page 9-36

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Page 2 of 3 TABLE 2.1-4 Nuclide Parameters (continued)

Half-Life Sensitivity Sensitivity TB

-t Nuclide (hr) (hr-1) e (cpm/Ci/ml) Slope Bldg.

Drain Only (cpm/Ci/ml)

Tc-101 2.37E-01 2.93E+00 5.45E-16 1.66E+08 1.60E+00 2.92E+07 Ru-103 9.45E+02 7.33E-04 9.91E-01 1.38E+08 1.33E+00 3.83E+07 Ru-105 4.43E+00 1.56E-01 1.53E-01 1.71E+08 1.64E+00 5.21E+07 Ru-106 8.83E+03 7.85E-05 9.99E-01 4.52E+07 4.35E-01 1.43E+07 Ag-110m 6.00E+03 1.16E-04 9.99E-01 3.22E+08 3.10E+00 1.41E+08 Sn-113 2.76E+03 2.51E-04 9.97E-01 3.08E+06 2.96E-02 4.28E+05 Sb-124 1.45E+03 4.80E-04 9.94E-01 1.59E+08 1.53E+00 8.31E+07 Sb-125 2.43E+04 2.85E-05 1.00E+00 1.21E+08 1.16E+00 3.20E+07 Te-125m 1.39E+03 4.98E-04 9.94E-01 3.00E+05 2.88E-03 1.17E+04 Te-127m 2.62E+03 2.65E-04 9.97E-01 1.33E+04 1.28E-04 6.29E+03 Te-127 9.35E+00 7.41E-02 4.11E-01 1.97E+06 1.89E-02 4.14E+05 Te-129m 8.07E+02 8.59E-04 9.90E-01 5.17E+06 4.97E-02 1.95E+06 Te-129 1.16E+00 5.98E-01 7.69E-04 1.58E+07 1.52E-01 4.02E+06 Te-131m 3.00E+01 2.31E-02 7.58E-01 2.17E+08 2.09E+00 7.37E+07 Te-131 4.17E-01 1.66E+00 2.14E-09 1.50E+08 1.44E+00 2.58E+07 Te-132 7.82E+01 8.87E-03 8.99E-01 1.39E+08 1.34E+00 1.69E+07 I-130 1.24E+01 5.60E-02 5.10E-01 4.13E+08 3.97E+00 1.41E+08 I-131 1.93E+02 3.59E-03 9.58E-01 1.55E+08 1.49E+00 3.21E+07 I-132 2.30E+00 3.01E-01 2.69E-02 3.31E+08 3.18E+00 1.30E+08 I-133 2.08E+01 3.33E-02 6.71E-01 1.39E+08 1.34E+00 4.28E+07 I-134 8.77E-01 7.91E-01 7.58E-05 3.08E+08 2.96E+00 1.31E+08 I-135 6.62E+00 1.05E-01 2.84E-01 1.03E+08 9.90E-01 5.82E+07 Cs-134 1.80E+04 3.85E-05 1.00E+00 2.60E+08 2.50E+00 9.68E+07 Cs-136 3.17E+02 2.19E-03 9.74E-01 3.37E+08 3.24E+00 1.11E+08 Cs-137 2.65E+05 2.62E-06 1.00E+00 1.04E+08 1.00E+00 3.90E+07 Cs-138 5.37E-01 1.29E+00 1.86E-07 1.15E+08 1.11E+00 8.43E+07 Ba-139 1.39E+00 5.00E-01 2.46E-03 2.34E+07 2.25E-01 2.17E+06 Ba-140 3.07E+02 2.26E-03 9.73E-01 6.01E+07 5.78E-01 1.45E+07 Ba-141 3.05E-01 2.27E+00 1.43E-12 2.53E+08 2.43E+00 5.42E+07 Ba-142 1.78E-01 3.89E+00 5.54E-21 1.47E+08 1.41E+00 4.44E+07 La-140 4.02E+01 1.73E-02 8.13E-01 1.53E+08 1.47E+00 9.06E+07 La-142 1.59E+00 4.36E-01 5.35E-03 9.59E+07 9.22E-01 7.75E+07 Ce-141 7.80E+02 8.89E-04 9.89E-01 6.11E+07 5.88E-01 4.29E+06 Ce-143 3.30E+01 2.10E-02 7.77E-01 9.60E+07 9.23E-01 1.90E+07 Ce-144 6.82E+03 1.02E-04 9.99E-01 1.30E+07 1.25E-01 7.96E+05 Pr-143 3.25E+02 2.13E-03 9.75E-01 1.08E+02 1.04E-06 5.27E-01 Pr-144 2.88E-01 2.40E+00 2.96E-13 1.68E+06 1.62E-02 1.14E+06 Nd-147 2.63E+02 2.63E-03 9.69E-01 2.86E+07 2.75E-01 8.08E+06 Hf-181 1.02E+03 6.80E-04 9.92E-01 2.08E+08 2.00E+00 4.14E+07 W-187 2.38E+01 2.91E-02 7.05E-01 1.04E+08 1.00E+00 3.09E+07 Np-239 5.65E+01 1.23E-02 8.63E-01 1.13E+08 1.09E+00 1.01E+07 2-24 Page 9-37

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Page 3 of 3 TABLE 2.1-4 Nuclide Parameters (continued)

Half-Life Sensitivity Sensitivity TB

-t Nuclide (hr) (hr-1) e (cpm/Ci/ml) Slope Bldg.

Drain Only (cpm/Ci/ml)

Ar-41 1.83E+00 3.78E-01 1.07E-02 9.28E+07 8.92E-01 4.51E+07 Kr-83m 1.83E+00 3.78E-01 1.07E-02 0.00E+00 0.00E+00 0.00E+00 Kr-85 9.40E+04 7.37E-06 1.00E+00 6.20E+05 5.96E-03 1.75E+05 Kr-85m 4.48E+00 1.55E-01 1.56E-01 1.20E+08 1.15E+00 1.12E+07 Kr-87 1.27E+00 5.45E-01 1.44E-03 9.19E+07 8.84E-01 3.22E+07 Kr-88 2.83E+00 2.45E-01 5.31E-02 7.49E+07 7.20E-01 5.19E+07 Kr-89 5.27E-02 1.32E+01 2.58E-69 1.39E+08 1.34E+00 6.52E+07 Kr-90 8.95E-03 7.72E+01 0.00E+00 1.59E+08 1.53E+00 5.43E+07 Xe-131m 2.85E+02 2.45E-03 9.71E-01 2.62E+06 2.52E-02 2.21E+05 Xe-133 1.23E+02 5.51E-03 9.36E-01 9.90E+04 9.52E-04 9.33E+03 Xe-133m 5.25E+01 1.32E-02 8.53E-01 1.59E+07 1.53E-01 2.02E+06 Xe-135 9.12E+00 7.60E-02 4.02E-01 1.47E+08 1.41E+00 2.10E+07 Xe-135m 2.57E-01 2.70E+00 8.43E-15 1.14E+08 1.10E+00 3.30E+07 Xe-137 6.38E-02 1.09E+01 2.57E-57 4.85E+07 4.66E-01 1.32E+07 Xe-138 2.35E-01 2.95E+00 4.25E-16 1.20E+08 1.15E+00 4.25E+07 Notes to Table 2.1-4 Sensitivity = 80% of weighted response to 100 - 1400 keV gammas for offline and an adjacent to line monitor which are sodium iodide (NaI) detectors (reference GA Manual E-115-904, June 1980, and Figure 5, Expected Energy Response Normalized for one gamma per disintegration, Drawing 0360-8934 Rev A, page 14, respectively). Abundances for each gamma from "Radioactive Decay Tables" by David C. Kocher (Report DOE/TIC-11026, Washington, D.C., 1981)

Slope = The Liquid Effluent Monitor Gamma Sensitivities for nuclide i",

relative to Cs-137. To make nuclide i" relative to Cs-137, the nuclide sensitivity is divided by the Cs-137 sensitivity. This column does not apply to TB Drains monitor.

2-25 Page 9-38

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Sheet 1 of 3 TABLE 2.2-1 AiVALUES FOR THE ADULT FOR THE SHEARON HARRIS NUCLEAR POWER PLANT t

730 A =1.14E + 05 ( + 21BF ) DF *e i p i, r,p D i i w

(mrem/hr per Ci/ml)

Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi H-3 0.00E+00 8.54E-01 8.54E-01 8.54E-01 8.54E-01 8.54E-01 8.54E-01 C-14 3.13E+04 6.27E+03 6.27E+03 6.27E+03 6.27E+03 6.27E+03 6.27E+03 Na-24 2.40E+02 2.40E+02 2.40E+02 2.40E+02 2.40E+02 2.40E+02 2.40E+02 P-32 4.52E+07 2.81E+06 1.75E+06 0.00E+00 0.00E+00 0.00E+00 5.08E+06 Cr-51 0.00E+00 0.00E+00 1.28E+00 7.63E-01 2.81E-01 1.69E+00 3.21E+02 Mn-54 0.00E+00 4.41E+03 8.41E+02 0.00E+00 1.31E+03 0.00E+00 1.35E+04 Mn-56 0.00E+00 4.44E+00 7.87E-01 0.00E+00 5.63E+00 0.00E+00 1.42E+02 Fe-55 6.76E+02 4.67E+02 1.09E+02 0.00E+00 0.00E+00 2.60E+02 2.68E+02 Fe-59 1.06E+03 2.49E+03 9.54E+02 0.00E+00 0.00E+00 6.95E+02 8.29E+03 Co-57 0.00E+00 2.20E+01 3.66E+01 0.00E+00 0.00E+00 0.00E+00 5.58E+02 Co-58 0.00E+00 9.33E+01 2.09E+02 0.00E+00 0.00E+00 0.00E+00 1.89E+03 Co-60 0.00E+00 2.69E+02 5.94E+02 0.00E+00 0.00E+00 0.00E+00 5.06E+03 Ni-63 3.20E+04 2.21E+03 1.07E+03 0.00E+00 0.00E+00 0.00E+00 4.62E+02 Ni-65 4.76E+00 6.19E-01 2.82E-01 0.00E+00 0.00E+00 0.00E+00 1.57E+01 Cu-64 0.00E+00 5.45E+00 2.56E+00 0.00E+00 1.37E+01 0.00E+00 4.64E+02 Zn-65 2.32E+04 7.39E+04 3.34E+04 0.00E+00 4.94E+04 0.00E+00 4.65E+04 Zn-69M 4.46E+02 1.07E+03 9.79E+01 0.00E+00 6.48E+02 0.00E+00 6.54E+04 Zn-69 6.25E-03 1.20E-02 8.32E-04 0.00E+00 7.77E-03 0.00E+00 1.80E-03 Br-82 0.00E+00 0.00E+00 1.81E+03 0.00E+00 0.00E+00 0.00E+00 2.07E+03 Br-83 0.00E+00 0.00E+00 1.24E+00 0.00E+00 0.00E+00 0.00E+00 1.79E+00 Br-84 0.00E+00 0.00E+00 8.07E-06 0.00E+00 0.00E+00 0.00E+00 6.33E-11 Rb-86 0.00E+00 9.95E+04 4.63E+04 0.00E+00 0.00E+00 0.00E+00 1.96E+04 Rb-88 0.00E+00 1.94E-10 1.03E-10 0.00E+00 0.00E+00 0.00E+00 2.67E-21 Rb-89 0.00E+00 1.62E-12 1.14E-12 0.00E+00 0.00E+00 0.00E+00 9.43E-26 Sr-89 2.38E+04 0.00E+00 6.84E+02 0.00E+00 0.00E+00 0.00E+00 3.82E+03 Sr-90 5.91E+05 0.00E+00 1.45E+05 0.00E+00 0.00E+00 0.00E+00 1.71E+04 Sr-91 1.84E+02 0.00E+00 7.43E+00 0.00E+00 0.00E+00 0.00E+00 8.77E+02 Sr-92 7.84E+00 0.00E+00 3.39E-01 0.00E+00 0.00E+00 0.00E+00 1.55E+02 Y-90 5.57E-01 0.00E+00 1.49E-02 0.00E+00 0.00E+00 0.00E+00 5.91E+03 Y-91M 2.61E-07 0.00E+00 1.01E-08 0.00E+00 0.00E+00 0.00E+00 7.67E-07 Y-91 9.24E+00 0.00E+00 2.47E-01 0.00E+00 0.00E+00 0.00E+00 5.09E+03 Y-92 5.29E-03 0.00E+00 1.55E-04 0.00E+00 0.00E+00 0.00E+00 9.27E+01 Y-93 7.75E-02 0.00E+00 2.14E-03 0.00E+00 0.00E+00 0.00E+00 2.46E+03 Zr-95 4.20E-01 1.35E-01 9.12E-02 0.00E+00 2.11E-01 0.00E+00 4.27E+02 Zr-97 1.42E-02 2.87E-03 1.31E-03 0.00E+00 4.34E-03 0.00E+00 8.90E+02 Nb-95 4.43E+02 2.47E+02 1.33E+02 0.00E+00 2.44E+02 0.00E+00 1.50E+06 2-26 Page 9-39

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Sheet 2 of 3 TABLE 2.2-1 (Continued)

Ai VALUES FOR THE ADULT FOR THE SHEARON HARRIS NUCLEAR POWER PLANT (mrem/hr per Ci/ml)

Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi Nb-97 3.70E-03 9.36E-04 3.42E-04 0.00E+00 1.09E-03 0.00E+00 3.45E+00 Mo-99 0.00E+00 1.14E+02 2.17E+01 0.00E+00 2.58E+02 0.00E+00 2.64E+02 Tc-99M 2.60E-03 7.35E-03 9.36E-02 0.00E+00 1.12E-01 3.60E-03 4.35E+00 Tc-101 5.81E-18 8.37E-18 8.21E-17 0.00E+00 1.51E-16 4.28E-18 2.52E-29 Ru-103 5.49E+00 0.00E+00 2.37E+00 0.00E+00 2.10E+01 0.00E+00 6.41E+02 Ru-105 7.07E-02 0.00E+00 2.79E-02 0.00E+00 9.13E-01 0.00E+00 4.32E+01 Ru-106 8.23E+01 0.00E+00 1.04E+01 0.00E+00 1.59E+02 0.00E+00 5.33E+03 Ag-110M 1.84E+00 1.70E+00 1.01E+00 0.00E+00 3.34E+00 0.00E+00 6.93E+02 Sb-124 2.33E+01 4.40E-01 9.24E+00 5.65E-02 0.00E+00 1.82E+01 6.62E+02 Sb-125 1.50E+01 1.67E-01 3.57E+00 1.52E-02 0.00E+00 1.16E+01 1.65E+02 Te-125M 2.57E+03 9.32E+02 3.44E+02 7.73E+02 1.05E+04 0.00E+00 1.03E+04 Te-127m 6.51E+03 2.33E+03 7.94E+02 1.66E+03 2.65E+04 0.00E+00 2.18E+04 Te-127 4.36E+01 1.57E+01 9.44E+00 3.23E+01 1.78E+02 0.00E+00 3.44E+03 Te-129M 1.10E+04 4.10E+03 1.74E+03 3.77E+03 4.59E+04 0.00E+00 5.53E+04 Te-129 2.33E-02 8.76E-03 5.68E-03 1.79E-02 9.80E-02 0.00E+00 1.76E-02 Te-131M 1.27E+03 6.19E+02 5.16E+02 9.80E+02 6.27E+03 0.00E+00 6.14E+04 Te-131 4.07E-08 1.70E-08 1.28E-08 3.35E-08 1.78E-07 0.00E+00 5.76E-09 Te-132 2.19E+03 1.41E+03 1.33E+03 1.56E+03 1.36E+04 0.00E+00 6.69E+04 I-130 1.62E+01 4.77E+01 1.88E+01 4.05E+03 7.45E+01 0.00E+00 4.11E+01 I-131 1.67E+02 2.39E+02 1.37E+02 7.84E+04 4.10E+02 0.00E+00 6.31E+01 I-132 2.29E-01 6.12E-01 2.14E-01 2.14E+01 9.75E-01 0.00E+00 1.15E-01 I-133 4.00E+01 6.95E+01 2.12E+01 1.02E+04 1.21E+02 0.00E+00 6.25E+01 I-134 3.37E-04 9.15E-04 3.27E-04 1.59E-02 1.46E-03 0.00E+00 7.98E-07 I-135 5.29E+00 1.38E+01 5.11E+00 9.13E+02 2.22E+01 0.00E+00 1.56E+01 Cs-134 2.99E+05 7.10E+05 5.81E+05 0.00E+00 2.30E+05 7.63E+04 1.24E+04 Cs-136 3.05E+04 1.20E+05 8.65E+04 0.00E+00 6.69E+04 9.17E+03 1.37E+04 Cs-137 3.83E+05 5.23E+05 3.43E+05 0.00E+00 1.78E+05 5.91E+04 1.01E+04 Cs-138 4.92E-05 9.72E-05 4.82E-05 0.00E+00 7.14E-05 7.06E-06 4.15E-10 Ba-139 3.72E-03 2.65E-06 1.09E-04 0.00E+00 2.48E-06 1.50E-06 6.60E-03 Ba-140 3.08E+02 3.86E-01 2.02E+01 0.00E+00 1.31E-01 2.21E-01 6.33E+02 Ba-141 1.05E-12 7.94E-16 3.55E-14 0.00E+00 7.38E-16 4.51E-16 4.95E-22 Ba-142 1.84E-21 1.89E-24 1.16E-22 0.00E+00 1.60E-24 1.07E-24 2.59E-39 La-140 1.34E-01 6.75E-02 1.78E-02 0.00E+00 0.00E+00 0.00E+00 4.96E+03 La-142 4.51E-05 2.05E-05 5.11E-06 0.00E+00 0.00E+00 0.00E+00 1.50E-01 2-27 Page 9-40

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Sheet 3 of 3 TABLE 2.2-1 (Continued)

Ai VALUES FOR THE ADULT FOR THE SHEARON HARRIS NUCLEAR POWER PLANT (mrem/hr per Ci/ml)

Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi Ce-141 7.76E-02 5.24E-02 5.95E-03 0.00E+00 2.44E-02 0.00E+00 2.01E+02 Ce-143 1.07E-02 7.94E+00 8.79E-04 0.00E+00 3.50E-03 0.00E+00 2.97E+02 Ce-144 4.08E+00 1.71E+00 2.19E-01 0.00E+00 1.01E+00 0.00E+00 1.38E+03 Pr-143 5.91E-01 2.37E-01 2.93E-02 0.00E+00 1.37E-01 0.00E+00 2.59E+03 Pr-144 5.88E-16 2.44E-16 2.99E-17 0.00E+00 1.38E-16 0.00E+00 8.46E-23 Nd-147 4.02E-01 4.64E-01 2.78E-02 0.00E+00 2.71E-01 0.00E+00 2.23E+03 W-187 2.10E+02 1.75E+02 6.12E+01 0.00E+00 0.00E+00 0.00E+00 5.74E+04 Np-239 3.08E-02 3.03E-03 1.67E-03 0.00E+00 9.44E-03 0.00E+00 6.21E+02 2-28 Page 9-41

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Figure 2.1-1 Liquid Waste Processing Flow Diagram Low Conductivity Storage Tanks Secondary Waste Condensate Sample Tank Polisher Filtration Demin (SWST)

Demineralizer Regen High Conductivity Storage Tanks Bypass Waste Monitoring Tanks (WMT)

Chemistry Lab Drains & Laundry &

Detergent Hot Shower Drains Sump Tanks Treated Laundry &

Floor Drain Hot Shower Floor Drain Filtration Demin Tanks Sumps Tanks (TL&HST)

Equipment Waste Drains Holdup Sump Tank Waste Demin Evaporator Waste Evaporator Condensate Tank CVCS Recycle (WECT)

Letdown Demin Holdup Tanks Boron Recycle Demin Evaporator 2-29 Page 9-42

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Figure 2.1-2 Liquid Effluent Flow Stream Diagram Legend Tank or Basin Treated Laundry & Treated Laundry & C Hot Shower Tank Hot Shower Tank REM Radiation Effluent Monitor O O

Pump L I

REM N G

REM-1WL-3540 T

O Secondary Waste W Sample Tank E R

REM-21WS-3542 B

REM L O

W D

O Spectacle Flange W Waste Monitor Waste Monitor Waste Neutralization Tank Tank Basin

N Waste Evaporator Waste Evaporator Condensate Tank Setting Condensate Tank Basin

Liquids containing Radioactive materials other than tritium are not permitted by procedure to be sent to REM the Waste Neutralization Basin REM-21WL-3541 Harris Lake 2-30 Page 9-43

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Figure 2.1-3 Normal Service Water Flow Diagram Normal Service Water Reactor Auxiliary Building Heat Loads Heat Loads REM 3500 A

Waste Processing Heat Loads Building REM 3500 B

Main Condenser Turbine Building Normal Service Water Circulating Water Pumps Legend REM - Radiation Effluent Monitor NSW - Normal Service Water Cooling Tower Basin NSW Pumps CTMU CTMU Pumps Bypass Strainer Line Backwash Harris Lake NOTE: For detailed flow drawings of the Service Water System, refer to the FSAR 2-31 Page 9-44

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Figure 2.1-4 Other Liquid Effluent Pathways 2-32 Page 9-45

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Figure 2.3-1 Map of Harris Lake for Evaporation Dose Calculation 2-33 Page 9-46

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3.0 GASEOUS EFFLUENTS At SHNPP there are four gaseous effluent discharge points: Plant Vent Stack 1, Turbine Building Vent Stack 3A, and the Waste Processing Building Vent Stacks 5 and 5A. During refueling outages the Equipment Hatch is removed and has potential airborne particulate releases. These are shown in Figures 3.1, 3.2, and 3.3 along with their tributaries. Minor release pathways, such as steam leaks, steam dumps, and open penetrations are evaluated for significant of release. All gaseous effluent releases at the plant are considered ground releases.

3.1 Monitor Alarm Setpoint Determination (ODCM Operational Requirement 3.3.3.11)

This section provides the methodology for stack effluent monitor setpoints to ensure that the dose rates from noble gases at the site boundary do not exceed the limits of 500 mrem/year to the whole body or 3000 mrem/year to the skin as specified in ODCM Operational Requirement 3.11.2.1. The 500 mrem/year to the whole body or 3000 mrem/year to the skin limits are more conservative than the 10 CFR 50.73 limits concerning airborne radioactivity release concentrations to unrestricted areas, and therefore the setpoint methodology set forth here is based on the limits of 500 mrem/year to the whole body or 3000 mrem/year to the skin.

The radioactivity effluent monitors for each stack and for specific effluent streams are shown in Figures 3.1 and 3.3 and are listed in Appendix C.

Gamma spectroscopy analysis of the gas sample should provide the nuclide identification and activity.

However, in the case where the noble gas activities are < LLD the relative nuclide composition can be assumed from the GALE code activities for projected normal operating releases (Table 3.1-1). The GALE code is used to establish a default setpoint for each vent stack. This setpoint will be used as a "fixed" setpoint until a more conservative setpoint is calculated, using either a different assumed mix or actual sample results.

3-1 Page 9-47

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3.1.1 Default Continuous Release Monitor Setpoints Using a Conservative mix (GALE code)

The following methodology is the default setpoint for the continuous release vent stacks based on conservative assumptions of mix (GALE code) and maximum stack flow rate.

1. Determine the noble gas radionuclide activity (Qi) in Ci, and the activity release rate Qi in Ci/sec for each nuclide i". Qi is the release rate of nuclide i" in gaseous effluent from discharge point v, in Ci/sec.

Qi = Ci

Fv

duration

28316.85 (3.1-1a) and Q i = Ci

Fv

28316.85 / 60 (3.1-1b) where:

v = index over all vent stacks Ci = concentration of nuclide, in Ci/cc

= the GALE code activities from Table 3.1-1.

Fv = effluent release rate or vent flow rate in cfm

= the maximum effluent design flow rate at the point of discharge (acfm) from Table 3.1-3.

duration = duration of release, in minutes 28316.85 = conversion factor for cc/ft3 60 = seconds per minute

2. Determine the maximum whole body and skin dose rate (mrem/year) during the release.

Qm-wb = (X / Q) [ i K i Q i ] (3.1-2a) and Qm-s = (X / Q) [ i (L i + 1.1M i ) Q i ] (3.1-2b) where:

i = index over all nuclides Ki = the total body dose factor due to gamma emissions for noble gas radionuclide i (in mrem/yr per µCi/m3), from Table 3.2-3.

Li = The skin dose factor due to beta emissions for noble gas radionuclide i (mrem/yr per Ci/m3), from Table 3.2-3 Mi = The air dose factor due to gamma emissions for noble gas radionuclide i (mrad/yr 3

per Ci/m ). A unit conversion constant of 1.1 mrad/mrem converts air dose to skin dose, from Table 3.2-3 X/Q = The highest calculated annual average relative concentration for any sector at or beyond the exclusion boundary (sec/m3) 3

= 1.8E-05 sec/m (Site Boundary SW) from Table A1 through A4, Appendix A 3-2 Page 9-48

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3.1.1 Default Continuous Release Monitor Setpoints Using a Conservative mix (GALE code) (continued)

3. Determine the ratio of dose rate limit to dose rate.

Whole Body ratio = 500 (3.1-3a)

Qm-wb and Skin ratio = 3000 (3.1-3b)

Qm-s where:

500 = site dose rate limit for whole body in mrem/year.

3000 = site dose rate limit for skin in mrem/year.

4. Determine Smax, the maximum concentration setpoint in Ci/cc, and RRmax the maximum release rate setpoint in Ci/sec for the monitor.

Smax = (fs

falloc

nratio

Ci ) + Bkg (3.1-4a) and RRmax = Smax

Fv

28316.852 / 60 (3.1-4b) where fs = safety factor for the discharge point

= 0.5 falloc = dose rate allocation factor for the discharge point

= fraction of the radioactivity from the site that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded by simultaneous releases. These values are based on current plant conditions and ideal values that can be procedurally controlled are in Table 3.1-3. The sum of the allocation factors must be 1.

nratio = lesser of the ratios Bkg = Monitor background, in Ci/cc

= 0 for calculation of default setpoint.

3-3 Page 9-49

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3.1.1 Default Continuous Release Monitor Setpoints Using a Conservative mix (GALE code) (continued)

Using the GALE code activities from Table 3.1-1 and the maximum effluent design flow rate, continuous release stack maximum setpoints in Ci/cc and Ci/sec are determined. These values will be used as default values for the stack monitors. Based on sampling and analysis, the setpoint will be recalculated. If the sample analysis setpoint is higher than the default setpoint, the setpoint will not be changed. If the sample analysis setpoint is lower than the default, the setpoint will be changed to reflect the more conservative setpoint. When the setpoint changes again, the more conservative setpoint, comparing the default (GALE code) and sample analysis, will be used.

5. Determine Salert, the gas channel alert alarm setpoint in Ci/cc, and RRalert the gas channel alert alarm release rate setpoint in Ci/sec.

Salert = [(Smax - Bkg) Af] + Bkg (3.1-5a) and RRalert = [(RRmax - Bkgrr) Af] + Bkgrr (3.1-5b) where:

Af = A value < 1.0 designed to alert the operator that the high alarm setpoint is being approached.

Bkgrr = Bkg

Fv

28316.85 / 60 3-4 Page 9-50

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3.1.2 Monitor Setpoints Using Sample Results In Stacks 1 and 5, the potential exists for batch releases concurrent with the normal continuous ventilation flow of effluents. The sources of batch releases for the Plant Vent Stack 1 include containment normal and pre-entry purge and pressure relief. Batch release sources for Vent Stack 5 include releases from the waste gas decay tanks (WGDT). In these cases, the monitor setpoint must reflect the contribution of both the continuous and batch sources.

The following methodology will calculate a setpoint for the continuous release vent stacks based on actual sample results and for batch releases occurring concurrently with continuous releases.

1. Determine the noble gas radionuclide activity (Qi) in Ci, and the activity release rate Qi in Ci/sec for each nuclide i". Qi is the average release rate of nuclide i" in gaseous effluent from discharge point v, in Ci/sec. Noble gases may be averaged over a period of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Qi = Ci

Fv

duration

28316.85 (3.2-1a) and Q i = Ci

Fv

28316.85 / 60 (3.2-1b) where:

Ci = concentration of nuclide, in Ci/cc

= the measured concentration from a stack effluent sample or pre-release sample.

If there is no activity in the sample, then the GALE code activities from Table 3.1-1 will be used.

WGDTs

= (µCi/cc from analysis of WGDT)(6.45 E-05) +

(µCi/cc from analysis/GALE Code of Vent Stack 5)(0.9999)

Containment Normal Purge (Batch)

= (µCi/cc from analysis of Containment)(3.60 E-03) +

(µCi/cc from analysis/GALE Code of PV Stack 1)(0.9964)

Containment Preentry Purge (Batch)

= (µCi/cc from analysis of Containment)(8.19 E-02) +

(µCi/cc from analysis/GALE Code of PV Stack 1)(0.9181) 6.45 E-05 = Dilution factor WGDT = (15 acfm)/(232,500 acfm + 15 acfm) 0.9999 = Dilution factor Vent Stack 5

= 232,500 acfm/(232,500 acfm + 15 acfm) 3.60 E-03 = Dilution factor Normal Purge

= 1500 acfm/(415,000 acfm + 1500 acfm) 0.9964 = Dilution factor PV-1 = 415,000 acfm/(415,000 acfm + 1500 acfm) 8.19 E-02 = Dilution factor Preentry Purge (Batch)

= 37,000 acfm/(415,000 acfm + 37,000 acfm) 0.9181 = Dilution factor PV-1

= 415,000 acfm/(415,000 acfm + 37,000 acfm) 3-5 Page 9-51

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3.1.2 Monitor Setpoints Using Sample Results (continued)

Fv = effluent release rate or vent flow rate in CFM

= for continuous releases, the measured effluent flow rate or the maximum effluent design flow rate at the point of release (acfm) from Table 3.1-3.

= for batch releases, the release flow rate, in acfm

= 1,500 acfm for containment normal purge + 415,000 acfm from Plant Vent Stack 1

= 37,000 acfm for containment preentry purge + 415,000 acfm from Plan Vent Stack 1

= 15 acfm for Waste Gas Decay Tank pre release permits + 232,500 acfm from Vent Stack 5 for posting Waste Gas Decay Tank and Containment Pressure releases the following is used for effluent accountability.

P 273 ° 2.26 E + 06 ( c ) ( )

14.7 Tc

=

t for a containment pressure release Pt 273° 600 ( )( )

14.7 Tt

=

t for a Waste Gas Decay Tank release where:

3 2.26E+06 and 600 are the volumes in ft of the containment and decay tank, respectively, and Tc, Tt, Pc, and Pt are the estimated, respective temperature and change in pressure (psig) following the release of the containment and decay tank; and, 14.7 psi = 1 atmosphere pressure t = Length of release, min Pc,Pt = change in pressure (psig) following the release of the containment or decay tank 273°K = 0°C T t, T c = 273°K + C° duration = duration of release, in minutes 3

28316.85 = conversion factor for cc/ft 3-6 Page 9-52

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3.1.2 Monitor Setpoints Using Sample Results (continued)

2. Determine the maximum whole body and skin dose rate (mrem/year) during the release by summing together the dose rates for this release with all concurrent releases for the time of the release.

Qm-wb = ( X / Q )[ i K i Q i ] (3.2-2a) and Qm-s = ( X / Q )[ i ( Li +1.1M i )Q i ] (3.2-2b) where:

i = index over all radionuclides Ki = the total body dose factor due to gamma emissions for noble gas radionuclide i (mrem/yr per Ci/m3), from Table 3.2-3.

Li = The skin dose factor due to beta emissions for noble gas radionuclide i (mrem/yr 3

per Ci/m ), from Table 3.2-3 Mi = The air dose factor due to gamma emissions for noble gas radionuclide i (mrad/yr per Ci/m3). A unit conversion constant of 1.1 mrad/mrem converts air dose to skin dose, from Table 3.2-3 X/Q = The highest calculated annual average relative concentration for any sector at or beyond the exclusion boundary (sec/m3)

= 1.8E-05 sec/m3 (Site Boundary SW) from Table A1 through A4, Appendix A 3-7 Page 9-53

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3.1.2 Monitor Setpoints Using Sample Results (continued)

3. Determine the ratio of dose rate limit to dose rate.

Whole Body ratio = 500 (3.2-3a)

Qm-wb and Skin ratio = 3000 (3.2-3b)

Qm-s where:

500 = site dose rate limit for whole body in mrem/year.

3000 = site dose rate limit for skin in mrem/year.

4. Determine Smax, the maximum concentration setpoint in Ci/cc, and RRmax the maximum release rate setpoint in Ci/sec for the monitor.

Smax = (fs

falloc

nratio

Ci ) + Bkg (3.2-4a) and RRmax = Smax

Fv

28316.85 / 60 (3.2-4b) where:

fs = safety factor for the discharge point

= 0.5 falloc = dose rate allocation factor for the discharge point

= fraction of the radioactivity from the site that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded by simultaneous releases. These values are based on current plant conditions and ideal values that can be procedurally controlled are in Table 3.1-3. The sum of the allocation factors must be 1.

nratio = lesser of the ratios Bkg = Monitor background, in Ci/cc

= measured background at time of release or 0.

3-8 Page 9-54

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3.1.2 Monitor Setpoints Using Sample Results (continued)

5. Determine Salert, the gas channel alert alarm setpoint in Ci/cc, and RRalert the gas channel alert alarm release rate setpoint in Ci/sec.

Salert = [(Smax - Bkg) Af] + Bkg (3.2-5a) and RRalert = [(RRmax - Bkgrr) Af] + Bkgrr (3.2-5b) where:

Af = A value < 1.0 designed to alert the operator that the high alarm setpoint is being approached.

Bkgrr = Bkg

Fv

28316.85 / 60 3.1.3 Effluent Monitoring During Hogging Operations If the reactor has been shut down for greater than 30 days, the condenser vacuum pump discharge during initial hogging operations at plant start-up and prior to turbine operation may be routed as dual exhaust to (1) the Turbine Vent Stack 3A and (2) the atmosphere directly. In this instance, the blind flange on the latter exhaust route will be removed (see Figure 3.3).

A conservative effluent channel setpoint has been established for Vent Stack 3A. The monitor setpoint should be reduced proportionately to the estimated fraction of the main condenser effluent flowing directly to the atmosphere.

3-9 Page 9-55

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Table 3.1-1 (a,b)

GASEOUS SOURCE TERMS Condenser Plant Vent Vacuum Pump WPB WPB Containment Ventilation Ventilation Ventilation Ventilation Purge or WGDT Flow Flow Flow Flow (c) Pressure Relief Release via via via via via via Stack 1 Stack 3A Stack 5 Stack 5A Stack 1 Stack 5 Ci % Rel. Ci % Rel. Ci % Rel. Ci % Rel. Ci % Rel. Ci % Rel.

Nuclide (Ci/cc) Mix (Ci/cc) Mix (Ci/cc) Mix (Ci/cc) Mix (Ci/cc) Mix (Ci/cc) Mix Kr-85m 4.86E-10 6.52 4.70E-9 9.52 0 0 1.96E-9 6.52 1.01E-7 3.79 0 0 Kr-85 0 0 0 0 1.60E-7 97.05 0 0 3.95E-8 1.49 2.22E-5 100.00 Kr-87 4.86E-10 6.52 4.70E-9 9.52 0 0 1.96E-9 6.52 3.59E-8 1.35 0 0 Kr-88 9.71E-10 13.04 7.04E-9 14.29 0 0 3.91E-9 13.04 1.29E-7 4.87 0 0 Xe-131m 3.24E-10 4.35 0 0 4.86E-9 2.95 1.30E-9 4.35 2.16E-7 8.12 0 0 Xe-133m 0 0 0 0 0 0 0 0 5.57E-8 2.10 0 0 Xe-133 1.78E-09 23.91 1.17E-8 23.81 0 0 7.17E-9 23.91 1.31E-6 49.39 0 0 Xe-135m 4.86E-10 6.52 2.35E-9 4.76 0 0 1.96E-9 6.52 7.19E-9 0.27 0 0 Xe-135 2.43E-9 32.61 1.64E-8 33.33 0 0 9.78E-9 32.61 7.55E-7 28.42 0 0 Xe-138 4.86E-10 6.52 2.35E-9 4.76 0 0 1.96E-9 6.52 5.39E-9 0.20 0 0 (a) Source terms are from SHNPP FSAR Table 11.3.3-1 and not actual releases.

Values apply only to routine releases and not emergency situations.

3 (b) (uCi/cc) = (Ci/yr )(yr/5.256E5min) (1E6Ci/Ci) (ft /28320cc) 3 (d)

(Flow Rate ft /min)

(c) Source term for this effluent stream not presented with FSAR. RAB mix assumed.

(d) Maximum Effluent Design Flow Rates:

Plant Vent Ventilation via Stack 1 = 415,000 acfm

Condenser Vacuum Pump Ventilation via Stack 3A = 28,620 acfm

WPB Ventilation via Stack 5 = 232,500 acfm

WPB Ventilation via Stack 5A = 103,050 acfm

Containment Purge or Pressure Relief via Stack 1 = 37,000 acfm

WGDT Release via Stack 5 = 15 acfm 3-10 Page 9-56

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.1-2 Deleted TABLE 3.1-3 GASEOUS MONITOR PARAMETERS PVS-1 TBVS-3A WPBVS-5 WPBVS-5A Maximum effluent design flow rate, 415,000 28,620 232,500 103,050 (acfm)

Flow Allocation Factor 0.532 0.037 0.298 0.132

[falloc]

3-11 Page 9-57

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3.2 Postrelease Compliance with 10CFR20-Based ODCM Operational Requirement 3.11.2 3.2.1 Noble Gases The gaseous effluent monitors setpoints are utilized to show prerelease compliance with ODCM Operational Requirement 3.11.2.1. However, because they may be based upon a conservative (GALE code) mix of radionuclides, when using Table 3.1-1, the possibility exists that the setpoints could be exceeded and yet 10CFR20-based limits may actually be met. Therefore, the following methodology has been provided in the event that if the high alarm setpoints are exceeded, a determination may be made as to whether the actual releases have exceeded the dose rate limits of ODCM Operational Requirement 3.11.2.1.

The dose rate in unrestricted areas resulting from noble gas effluents is limited to 500 mrem/year to the total body and 3000 mrem/year to the skin. Based upon NUREG-0133, the following equations are used to show compliance:

K i (X / Q)v Q i 500 mrem/yr (3.2-1) i v (Li + 1.1M i) (X / Q)v Q iv 3000 mrem/yr (3.2-2) i where:

(X/Q)v = The highest calculated annual average relative concentration for long-term vent stack releases for areas at or beyond the exclusion boundary sec/m3.

3

= 1.8E-05 sec/m (Site Boundary SW) from Table A1 through A4, Appendix A Ki = The total body dose factor due to gamma emissions for noble gas radionuclide 3

"i," mrem/year per Ci/m . Table 3.2-3.

Li = The skin dose factor due to beta emissions for noble gas radionuclide "i,"

3 mrem/year per Ci/m . Table 3.2-3.

Mi = The air dose factor due to gamma emissions for noble gas radionuclide "i,"

mrad/year per Ci/m3. Table 3.2-3 1.1 = The ratio of the tissue to air absorption coefficients over the energy range of the photon of interest. Converts mrad to mrem (Reference NUREG-0133).

Q iv = The release rate of radionuclide "i" in gaseous effluents from all plant vent stacks (Ci/sec).

The determination of the controlling location for implementation of dose rate limits for noble gas exposure is a function of the historical annual average meteorology.

The radionuclide mix is based on the sampling and analysis required by ODCM Operational Requirement 4.11.2.1.2. If the analysis is < LLD, then the GALE code, historical data for the mix, or a Xe-133 / Kr-85 LLD mix for that analysis will be used to demonstrate compliance.

The release rate is derived from either the actual flow rate or the default flow rate and the known or assumed mix.

3-12 Page 9-58

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3.2.1 Noble Gases (continued)

Release Rate (Ci/sec) = Flow (cc/sec)

Concentration (Ci/cc)

The noble gas radionuclide mix was based upon source terms calculated using the NRC GALE Code and presented in the SHNPP FSAR Table 11.3.3-1. They are reproduced in Table 3.2-1 as a function of release point.

The X/Q value utilized in the equations is the highest long-term annual average relative concentration(X/Q)v in the unrestricted area for the period 2010 - 2014. Long-term annual average (X/Q)v values at other special locations identified by the Land Use Census (see Operational Requirement 3.12.2) are presented in Appendix A. A description of their derivation is also provided in Appendix A.

To select the limiting location for ground-level releases, long-term annual average (X/Q)v values were calculated assuming no decay, undepleted transport to the exclusion boundary. These values are given in Table A1 through A4, Appendix A. The maximum exclusion boundary (X/Q)v for ground-level releases occurs in the SW sector. Therefore, the limiting location for implementation of the dose rate limits for noble gases is considered to be the exclusion boundary (1.33 miles) in the SW sector.

Values for Ki, Li, and Mi which are to be used by SHNPP in Equations 3.2-1 and 3.2-2 to show compliance with ODCM Operational Requirement 3.11.2 are presented in Table 3.2-3. These values were taken from Table B-1 of NRC Regulatory Guide 1.109, Revision 1. The values have been multiplied by 1.0E+06 to convert mrad/pCi to mrad/Ci for use in Equations 3.2-1 and 3.2-2.

3-13 Page 9-59

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3.2.2 Radioiodines and Particulates The basis for ODCM Operational Requirement 3/4.11.2.1 states that the dose rate to the thyroid of a child in an unrestricted area resulting from the inhalation of radioiodines, tritium, and particulates with half-lives 8 days is limited to 1500 mrem/yr to any organ. Based upon NUREG-0133, the following is used to show compliance:

P [(X / Q)v Q iv ] 1500 mrem / yr (3.2-3) i iI where:

Pi = The dose parameter for radionuclides other than noble gases for the inhalation pathway, I

mrem/yr per Ci/m3, from Table 3.2-4.

In the calculation to show compliance with ODCM Operational Requirement 3.11.2.1.b, only the inhalation pathway is considered.

The radionuclide mix is based on the sampling and analysis required by ODCM Operational Requirement 4.11.2.1.2. If the analysis is < LLD, then no activity is assumed to have been released during the sampling period. The release rate is derived from the flow (actual or default) and the mix.

Release Rate (Ci/sec) = Flow (cc/sec)

Concentration (Ci/cc)

The determination of the controlling exclusion boundary location was based upon the highest exclusion boundary (X/Q)v value. Values for Pi in Eq. 3.2-3 were calculated for a child for various radionuclides for I

the inhalation pathway using the methodology of NUREG-0133. The Pi values are presented in Table 3.2-I

4. A description of the methodology used in calculating the Pi values is presented in Appendix B.

The (X/Q)v value utilized in Equation 3.2-3 is obtained from the tables presented in Appendix A. A description of the derivation of the X/Q values is provided in Appendix A.

3-14 Page 9-60

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Table 3.2-1 Releases from the Shearon Harris Nuclear Power Plant (a)

Normal Operation (Curies/year)

Waste Processing Bldg Waste Processing Bldg Condenser Vacuum Pump Exhaust and/or Exhaust via VENT STACK 5A and Turbine Building Waste Gas Decay Tanks (b) RAB/FHB and Containment Exhaust via VENT STACK 5 Exhaust via VENT STACK 1 via VENT STACK 3A NOBLE NORMAL TOTAL GASES SHUTDOWN OPERATIONS CONTAINMENT RAB/FHB TURBINE STACK 3A Kr-85m 0 0 5.6E+01 3.E+00 0 2.0E+00 6.1E+01 Kr-85 5.0E+00 5.6E+02 2.2E+01 0 0 0 5.9E+02 Kr-87 0 0 2.0E+01 3.0E+00 0 2.0E+00 2.5E+01 Kr-88 0 0 7.2E+01 6.0E+00 0 3.0E+00 8.1E+01 Xe-131m 0 1.7E+01 1.2E+02 2.0E+00 0 0 1.4E+02 Xe-133m 0 0 3.1E+01 0 0 0 3.10E+01 Xe-133 0 0 7.3E+02 1.1E+01 0 5.0E+00 7.5E+02 Xe-135m 0 0 4.0E+00 3.0E+00 0 1.0E+00 8.0E+00 Xe-135 0 0 4.2E+02 1.5E+01 0 7.0E+00 4.4E+02 Xe-138 0 0 3.0E+00 3.0E+00 0 1.0E+00 7.0E+00 Ar-41 --- --- --- --- --- --- 3.4E+01 (a) Adapted from SHNPP FSAR Table 11.3.3-1 and do not reflect actual release data.

These values are only for routine releases and not for a complete inventory of gases in an emergency.

(b) Waste Gas Decay Tank releases assumed to be after a 90-day decay period.

3-15 Page 9-61

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.2-3 DOSE FACTORS FOR NOBLE GASES

Total Body Dose Skin Gamma Air Beta Air Factor Dose Factor Dose Factor Dose Factor Radionuclide Ki Li Mi Ni (mrem/yr per (mrem/yr per (mrad/yr per (mrad/yr per Ci/m3) Ci/m3) Ci/m3) Ci/m3)

Ar-41 8.840E+03 2.690E+03 9.300E+03 3.280E+03 Kr-83M 7.560E-02 0.000E+00 1.930E+01 2.880E+02 Kr-85M 1.170E+03 1.460E+03 1.230E+03 1.970E+03 Kr-85 1.610E+01 1.340E+03 1.720E+01 1.950E+03 Kr-87 5.920E+03 9.730E+03 6.170E+03 1.030E+04 Kr-88 1.470E+04 2.370E+03 1.520E+04 2.930E+03 Kr-89 1.660E+04 1.010E+04 1.730E+04 1.060E+04 Xe-127 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe-131M 9.150E+01 4.760E+02 1.560E+02 1.110E+03 Xe-133M 2.510E+02 9.940E+02 3.270E+02 1.480E+03 Xe-133 2.940E+02 3.060E+02 3.530E+02 1.050E+03 Xe-135M 3.120E+03 7.110E+02 3.360E+03 7.390E+02 Xe-135 1.810E+03 1.860E+03 1.920E+03 2.460E+03 Xe-137 1.420E+03 1.220E+04 1.510E+03 1.270E+04 Xe-138 8.830E+03 4.130E+03 9.210E+03 4.750E+03

The listed dose factors are for radionuclides that may be detected in gaseous effluents.

3-16 Page 9-62

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.2-4 Pi VALUES (INHALATION) FOR A CHILD I

Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi H-3 0.00E+00 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 P-32 2.60E+06 1.14E+05 9.86E+04 0.00E+00 0.00E+00 0.00E+00 4.21E+04 Cr-51 0.00E+00 0.00E+00 1.54E+02 8.53E+01 2.43E+01 1.70E+04 1.08E+03 Mn-54 0.00E+00 4.29E+04 9.50E+03 0.00E+00 1.00E+04 1.57E+06 2.29E+04 Fe-59 2.07E+04 3.34E+04 1.67E+04 0.00E+00 0.00E+00 1.27E+06 7.06E+04 Co-58 0.00E+00 1.77E+03 3.16E+03 0.00E+00 0.00E+00 1.10E+06 3.43E+04 Co-60 0.00E+00 1.31E+04 2.26E+04 0.00E+00 0.00E+00 7.06E+06 9.61E+04 Zn-65 4.25E+04 1.13E+05 7.02E+04 0.00E+00 7.13E+04 9.94E+05 1.63E+04 Rb-86 0.00E+00 1.98E+05 1.14E+05 0.00E+00 0.00E+00 0.00E+00 7.98E+03 Rb-88 0.00E+00 8.36E+02 5.45E+02 0.00E+00 0.00E+00 0.00E+00 2.56E+01 Rb-89 0.00E+00 5.13E+02 4.31E+02 0.00E+00 0.00E+00 0.00E+00 2.81E+00 Sr-89 5.99E+05 0.00E+00 1.72E+04 0.00E+00 0.00E+00 2.15E+06 1.67E+05 Sr-90 1.01E+08 0.00E+00 6.43E+06 0.00E+00 0.00E+00 1.47E+07 3.43E+05 Y-91 9.13E+05 0.00E+00 2.43E+04 0.00E+00 0.00E+00 2.62E+06 1.84E+05 Zr-95 1.90E+05 4.17E+04 3.69E+04 0.00E+00 5.95E+04 2.23E+06 6.10E+04 Zr-97 2.79E+02 4.04E+01 2.38E+01 0.00E+00 5.78E+01 1.68E+05 5.22E+05 Nb-95 2.35E+04 9.16E+03 6.54E+03 0.00E+00 8.61E+03 6.13E+05 3.69E+04 Nb-97 6.38E-01 1.14E-01 5.36E-02 0.00E+00 1.27E-01 5.08E+03 4.14E+04 Mo-99 0.00E+00 2.56E+02 6.33E+01 0.00E+00 5.83E+02 2.01E+05 1.88E+05 Tc-99M 2.65E-03 5.18E-03 8.58E-02 0.00E+00 7.54E-02 1.41E+03 7.15E+03 Ru-103 2.79E+03 0.00E+00 1.07E+03 0.00E+00 7.02E+03 6.61E+05 4.47E+04 Ru-106 1.36E+05 0.00E+00 1.69E+04 0.00E+00 1.84E+05 1.43E+07 4.29E+05 Ag-110M 1.68E+04 1.14E+04 9.13E+03 0.00E+00 2.12E+04 5.47E+06 1.00E+05 Sn-113 9.00E+03 2.91E+02 9.83E+03 1.19E+02 2.02E+02 3.40E+05 7.45E+03 Sb-124 5.73E+04 7.40E+02 2.00E+04 1.26E+02 0.00E+00 3.24E+06 1.64E+05 Sb-125 9.84E+04 7.59E+02 2.07E+04 9.10E+01 0.00E+00 2.32E+06 4.03E+04 Te-127m 2.48E+04 8.53E+03 3.01E+03 6.06E+03 6.35E+04 1.48E+06 7.13E+04 Te-127 4.12E+00 1.41E+00 9.08E-01 2.92E+00 1.05E+01 1.49E+04 8.36E+04 Te-129M 1.92E+04 6.84E+03 3.04E+03 6.32E+03 5.02E+04 1.76E+06 1.81E+05 Te-129 1.45E-01 5.20E-02 3.54E-02 1.06E-01 3.82E-01 4.36E+03 3.79E+04 Te-131M 2.00E+02 8.80E+01 7.54E+01 1.45E+02 5.94E+02 3.06E+05 4.58E+05 Te-131 3.23E-02 1.25E-02 9.79E-03 2.52E-02 8.75E-02 3.05E+03 1.98E+03 Te-132 7.15E+02 4.05E+02 3.92E+02 4.72E+02 2.63E+03 5.61E+05 2.05E+05 I-131 4.80E+04 4.80E+04 2.72E+04 1.62E+07 7.87E+04 0.00E+00 2.84E+03 I-132 2.11E+03 4.06E+03 1.87E+03 1.93E+05 6.24E+03 0.00E+00 3.20E+03 I-133 1.66E+04 2.03E+04 7.68E+03 3.84E+06 3.37E+04 0.00E+00 5.47E+03 I-134 1.74E+03 3.21E+03 1.48E+03 7.54E+04 4.91E+03 0.00E+00 1.42E+03 I-135 4.91E+03 8.72E+03 4.14E+03 7.91E+05 1.34E+04 0.00E+00 4.43E+03 Cs-134 6.50E+05 1.01E+06 2.24E+05 0.00E+00 3.30E+05 1.21E+05 3.84E+03 Cs-136 6.50E+04 1.71E+05 1.16E+05 0.00E+00 9.53E+04 1.45E+04 4.17E+03 Cs-137 9.05E+05 8.24E+05 1.28E+05 0.00E+00 2.82E+05 1.04E+05 3.61E+03 Ba-140 7.39E+04 6.47E+01 4.32E+03 0.00E+00 2.11E+01 1.74E+06 1.02E+05 Ce-141 3.92E+04 1.95E+04 2.89E+03 0.00E+00 8.53E+03 5.43E+05 5.65E+04 Ce-144 6.76E+06 2.11E+06 3.61E+05 0.00E+00 1.17E+06 1.19E+07 3.88E+05 Hf-181 8.44E+04 3.28E+02 8.50E+03 2.76E+02 2.64E+02 7.95E+05 5.31E+04 Np-239 6.93E+02 4.97E+01 3.49E+01 0.00E+00 1.45E+02 8.64E+04 9.52E+04 3-17 Page 9-63

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3.3 COMPLIANCE WITH 10CFR50 The calculations described in Section 3.2 will be used to ensure compliance with the limits in 10 CFR 50 Appendix I for each release. Summation of doses for all releases for the quarter and year are compared to the limits in 10CFR50 Appendix I to ensure compliance.

With the exception of Carbon-14, the SHNPP ODCM calculates the dose to a single maximum (ALARA) individual. The ALARA individual is an individual that "lives" at the site boundary in the sector that has the most limiting long-term average X/Q value. The Carbon-14 dose is based upon the dose to a child who resides at the location with the most limiting X/Q for a garden.

3.3.1 Noble Gases

1. Cumulation of Doses Based upon NUREG-0133, the air dose in the unrestricted area due to noble gases released in gaseous effluents can be determined by the following equations:

D = 3.17 E 08 M i [(X / Q)v Q ~

iv + (X / q)v q ~ ]

iv (3.3-1) i

~

D = 3.17 E 08 Ni [(X / Q)v Q i + (X / q)v q ~ ]

iv (3.3-2) i v where:

D = The air dose from gamma radiation, mrad.

D = The air dose from beta radiation, mrad.

3.17 E-08 = The inverse of the number of seconds in a year (sec/year)-1.

Mi = The air dose factor due to gamma emissions for each identified noble gas radionuclide (mrad/yr/Ci/m3). A unit conversion constant of 1.1 mrad/mrem converts air dose to skin dose. Table 3.2-3.

Ni = The air dose factor due to beta emissions for each identified noble gas radionuclide "i,"

mrad/year per Ci/m3. Table 3.2-3.

X/Qv = The relative concentration for areas at or beyond the exclusion boundary for long-term 3

ground-level vent stack releases ( 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year), sec/m . See Section 3.0 concerning ground-level releases at Shearon Harris Nuclear Plant or use 1.8E-05 sec/m3 from Table A1 through A4, Appendix A as the most limiting X/Qv.

X/qv = The relative concentration for areas at or beyond the exclusion boundary for short-term 3

ground-level vent stack releases ( 500 hour0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months s/year), sec/m . See Section 3.0 concerning ground-level releases at Shearon Harris Nuclear Plant or use 1.8E-05 sec/m3 from Table A1 through A4, Appendix A as the most limiting X/Qv.

~

Q = The total release of noble gas radionuclide "i" in gaseous effluents for long term releases i

v

(>500 hrs/yr) from all vent stacks (Ci).

~

q = The total release of radionuclide "i" in gaseous releases for short-term releases (500 i

v hours/year) from all vent stacks, (Ci).

3-18 Page 9-64

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3.3.1 Noble Gases (continued)

To show compliance with 10CFR50, Expressions 3.3-1 and 3.3-2 are evaluated at the controlling location where the air doses are at a maximum.

At SHNPP the limiting location is the exclusion boundary at 1.33 miles (~2.14 kilometers) in the SW sector based upon the tables presented in Appendix A (see Section 3.2.1 earlier). For this document, long-term annual average X/Qv values can be used in lieu of short-term values. See Section 3.0 concerning ground-level releases at Shearon Harris Nuclear Plant.

The determination of the limiting location for implementation of 10CFR50 is a function of parameters such as radionuclide mix and meteorology. To select the limiting location, the highest annual average X/Qv value for ground-level releases is controlling. The only source of short-term releases from the plant vent are containment purges, containment pressure relief, and waste gas decay tank release. Determination of source terms is described in 3.3.1.2.

Values for Mi and Ni, which are utilized in the calculation of the gamma air and beta air doses in Equation 3.3-1 to show compliance with 10CFR50, are presented in Table 3.2-3. These values originate from Table B-1 of the NRC Regulatory Guide 1.109, Revision 1. The values have been multiplied by 1.0E+06 to convert from mrad/pCi to mrad/Ci.

The following relationships should hold for SHNPP to show compliance with ODCM Operational Requirement 3.11.2.2.

For the calendar quarter:

D 5 mrad (3.3-3)

D 10 mrad (3.3-4)

For the calendar year:

D 10 mrad (3.3-5)

D 20 mrad (3.3-6)

The quarterly limits given above represent one-half of the annual design objectives of Section II.B.1 of Appendix I of 10CFR50. If any of the limits of Equations 3.3-3 through 3.3-6 are exceeded, a Special Report pursuant to Technical Specification 6.9.2 must be filed with the NRC. This report complies with Section IV.A of Appendix I of 10CFR50.

3-19 Page 9-65

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3.3.1 Noble Gases (continued)

2. Source Term Determination Containment Batch Purge A purge of containment may be started as a Batch purge and continued as a normal purge. The containment Batch Purge volume is considered to be two air containment volumes (RCB vol = 2.26E+06 ft3). The containment air is sampled and analyzed for noble gases and tritium prior to release. Stack 1 has a continuous particulate filter and iodine cartridge sampler that is analyzed weekly (minimum) and used for total particulate and iodine effluent accountability for continuous releases. The noble gases and tritium analysis are used for containment effluent accountability as follows; qi = Ci

vb (3.3-7)

Where; qi = Activity of nuclide "i" released (Ci).

Ci = Concentration of radionuclide "i" (Ci/cc) vb = Containment purge volume (cc).

Waste Gas Decay Tank Batch Releases Waste Gas Decay Tanks (WGDT) are sampled and analyzed for tritium and noble gases prior to each release. Stack 5 has a continuous particulate filter and iodine cartridge sampler that is analyzed weekly (minimum) and used for total particulate and iodine effluent accountability for continuous releases. The activity (Ci) for nuclide "i" for Waste Gas Decay Tank effluent accountability is calculated as follows; (C *P *600*28316.85*273) i t qi = (3.3-7a)

(14.7*283)

Where; qi = Activity of nuclide "i" released (Ci).

Ci = Concentration of nuclide "i" (Ci/cc).

Pt = Change in pressure (psia) of the WGDT (psia = psig + 14.7) 600 = WGDT volume, (ft3).

28316.85 = Conversion factor for converting from ft3 to cc.

0 273 = Standard Temperature for 0 C (°K).

14.7 = Sample pressure at time of measurement, (psia).

283 = WGDT Temperature, °k (see Note below)

NOTE: The FSAR assumes WGDT temperature to be in the 50-140 °F range.

Since there is no indicator for the actual WGDT temperature, 50°F (10°C) is conservatively assumed as an acceptable substitute.

3-20 Page 9-66

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3.3.1 Noble Gases (continued)

Containment Pressure Releases Containment Pressure Releases (ILRT) are calculated using the same methodology as Waste Gas Decay Tank Batch Releases. Containment Pressure Releases are released via Stack 1 and pressurization piping. The volume to use is 2.26E+06 ft3.

Continuous Releases Each of the four effluent stacks at the HNP have noble gas monitors. Using the net concentration (Ci/cc) from these monitors times the volume released (determined from the flow monitors) the total activity (Ci) of noble gases released are calculated as follows:

Qx = Cx

Vx (3.3-8)

Where; Qx = Total activity (Ci) released from Stack "x".

Cx = Net concentration (Ci/cc) from Stack "x" noble gas monitor.

Vx = Volume (cc) released from Stack "x" using the flow monitor and, if out of service use the compensatory measurements for volume determination.

The activity (Ci) released for radionuclide "i" equals the radionuclide "i" fraction of the radionuclide mix times the total activity released from Stack "x".

Qi = Qx

Si (3.3-8a)

Where; C

i Si = (3.3-8b)

C i

and; Si = The radionuclide "i" fraction of the radionuclide mix Ci = The concentration of nuclide "i" in the grab sample (Ci/cc).

Ci = Total activity in grab sample (Ci/cc).

The radionuclide mix is based on the sampling and analysis required by ODCM Operational Requirement 4.11.2.2.1. If the grab sample activity is < LLD, then a mix based on historical data or a mix based on the Xe-133 / Kr-85 LLD mix of that sample may be used.

When a monitor is out of service, the results of the compensatory sampling for each nuclide times the volume released for that time interval will be used for effluent accountability. During this situation if the sample shows no detectable activity then there is no activity released.

3-21 Page 9-67

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Corrections for Double Accounting For the two stacks that may have batch releases during the same time interval as continuous releases, the above calculations are corrected for double accounting as follows; Qic = Qi - qi (3.3-9)

Where; Qic = Total corrected activity of nuclide "i" (Ci) from Stack "x" when batch releases are being made during that time period.

For short term (batch) releases, the effluent stream is sampled and analyzed. The results of the sampling and analysis is used as the source term for the batch release. Release rate is derived from the source term and the release flow rate.

3. Projection of Doses Doses resulting from the release of gaseous effluents will be projected once every 31 days (monthly). The doses will be projected utilizing Equations 3.3-1 and 3.3-2, and projected using the following expression:

Dp = (D

p) + Da (3.3-10) where:

Dp = the 31 Day Projected Dose by organ D = sum of all open and closed release points from the start of the quarter to the end of the release in mrem per organ .

p = the Projection Factor which is the result of 31 divided by the number of days from start of the quarter to the end of the release.

Da = Additional Anticipated Dose for liquid releases by organ and quarter of release.

NOTE: The 31 Day Projected Dose values appear on the Standard Permit Reports. The 31 day dose projections include any additional dose.

Where possible, expected operational evolutions (i.e., outages, increased power levels, major planned batch gas releases, etc.) should be accounted for in the dose projections. This may be accomplished by using the source-term data from similar historical operating experiences where practical, and adding the dose as Additional Anticipated Dose.

To show compliance with ODCM Operational Requirement 3.11.2.4, the projected month's dose should be compared as in the following:

D 0.2 mrad to air for gamma radiation (3.3-11) and D 0.4 mrad to air for beta radiation (3.3-12)

If the projections exceed either Equations 3.3-11 or 3.3-12, then the appropriate portions of the gaseous radwaste treatment system shall be used to reduce releases of radioactivity.

3-22 Page 9-68

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3.3.2 Radioiodine and Particulates

1. Cumulation of DosesSection II.C of Appendix I of 10CFR50 limits the release of radioiodines and radioactive material in particulate form from a reactor such that the estimated dose or dose commitment to an individual in an unrestricted area from all pathways of exposure is not in excess of 15 mrem to any organ.

Based upon NUREG-0133, the dose to an organ of an individual from radioiodines and particulates with half-lives greater than 8 days in gaseous effluents released to unrestricted areas can be determined by the following equation:

~ ~ ] +

D = 3.17E 08 (Ri ) [(X/Q)v Qi + (X/q)v q iv i I v

~ ~ ]+

(Ri + Ri + Ri + Ri ) [(D/Q)v Qi + (D/q)v qiv M V G B v

~ ~

(RT + RT + RT + RT ) [(X/Q)V QT + (X/q)v qT ]

M I V B v v where:

D = Dose to any organ from tritium, radioiodines, and particulates, mrem.

(D/Q )v = The highest long-term (> 500 hr/yr) annual average relative deposition:

9.0E-09 m-2 for the food and ground plane pathways at the controlling location which is the exclusion boundary in the SW sector (from Table A1 through A4, Appendix A, for ground-level vent stack releases).

(D/q )v = The relative deposition factor for short term, ground-level vent releases

-2

( 500 hrs/yr), in m . See Section 3.0 concerning ground-level releases at Shearon Harris Nuclear Plant if using "real" meteorology or use 9.0E-09 m-2 from Table A1 through A4, Appendix A, for the food and ground plane pathways at the controlling location.

R = Dose factor for an organ for radionuclide "i" for either the cow milk or iM

-2 goat milk pathway, mrem/yr per Ci/sec per m .

R = Dose factor for an organ for radionuclide "i" for the ground plane iG exposure pathway, mrem/yr per Ci/sec per m-2.

R = Dose factor for an organ for radionuclide "i" for the inhalation pathway, iI mrem/yr per Ci/m3.

R iV = Dose factor for an organ for radionuclide "i" for the vegetable pathway, mrem/yr per Ci/sec per m-2.

R = Dose factor for an organ for radionuclide "i" for the meat pathway, iB

-2 mrem/yr per Ci/sec per m .

R = Dose factor for an organ for tritium for the milk pathway mrem/yr per TM Ci/m3.

R = Dose factor for an organ for tritium for the vegetable pathway, mrem/yr TV per Ci/m3.

R = Dose factor for an organ for tritium for the inhalation pathway, mrem/yr TI 3

per Ci/m .

3-23 Page 9-69

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3.3.2 Radioiodine and Particulates (continued)

R = Dose factor for an organ for tritium for the meat pathway, mrem/yr per TB 3

Ci/m .

~

Q = Release of tritium in gaseous effluents for long-term vent stack releases Tv

(> 500 hrs/yr), Ci.

~

q = Release of tritium in gaseous effluents for short-term vent stack Tv releases ( 500 hrs/yr), Ci.

To show compliance with 10CFR50, Equation 3.3-13 is evaluated for a hypothetical individual at the limiting location. At SHNPP the SW sector has the highest X/Qv and the SW and SSW sector have the highest annual average D/Qv values. This assures that the actual exposure of a member of the public will not be substantially underestimated. The critical receptor is a child.

Appropriate X/Qv and D/Qv values from tables in Appendix A are used. For this document, long-term annual average X/Qv and D/Qv values may be used in lieu of short-term values (see Section 3.0 concerning ground-level releases at Shearon Harris Nuclear Plant).

The determination of a limiting location for implementation of 10CFR50 for radioiodines and particulates is a function of:

1. Isotopic mix

2. Meteorology

3. Exposure pathway

4. Receptor's age In the determination of the limiting location, the radionuclide mix of radioiodines and particulates is based on the sampling and analysis required by ODCM Operational Requirement 4.11.2.1.2. If the analysis is < LLD, then no activity is assumed to have been released during the sampling period.

The release rate is derived from the flow (actual or default) and the isotopic mix.

In the determination of the limiting sector, all age groups and all of the exposure pathways are evaluated using the highest XOQDOQ values in Appendix A at the site boundary. These include beef and vegetable ingestion, inhalation, and ground plane exposure.

SHNPP ODCM Operational Requirement 3.12.2 requires that a land-use census survey be conducted on an annual basis. The age groupings at the various receptor locations are also determined during this survey. Thus, depending on the results of the survey, a new limiting location and receptor age group could result.

To avoid possible annual revisions to the ODCM software which evaluates effluent releases for compliance with 10CFR50, the limiting sector location has been fixed at the exclusion boundary in the SW sector. (Appendix A). With all of the exposure pathways identified in the Land Use Census (ODCM Operational Requirement 3.12.2). This approach avoids a substantial underestimate of the dose to a real member of the public.

Long-term X/Qv and D/Qv values for ground-level releases are provided in tables in Appendix A.

They may be utilized if an additional special location arises different from those presented in the special locations of the Land Use Census (ODCM Operational Requirement 3.12.2). A description of the derivation of the various X/Q and D/Q values is presented in Appendix A.

3-24 Page 9-70

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3.3.2 Radioiodine and Particulates (continued)

Tables 3.3-1 through 3.3-19 present Ri values for the total body, GI-tract, bone, liver, kidney, thyroid, and lung organs for the ground plane, inhalation, cow milk, goat milk, vegetable, and meat ingestion pathways for the infant, child, teen, and adult age groups as appropriate to the pathways.

These values were calculated using the methodology described in NUREG-0133 assuming a grazing period of eight months. A description of the methodology is presented in Appendix B.

The following relationship should hold for SHNPP to show compliance with SHNPP ODCM Operational Requirement 3.11.2.3.

For the calendar quarter:

D 7.5 mrem (3.3-14)

For the calendar year:

D 15 mrem (3.3-15)

The quarterly limits given above represent one-half the annual design objectives of Section II.C of Appendix I of 10CFR50. If any of the limits of Equations 3.3-14 or 3.3-15 are exceeded, a Special Report pursuant to Technical Specification 6.9.2 must be filed with the NRC. This report complies with Section IV.A of Appendix I of 10CFR50.

3-25 Page 9-71

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3.3.2 Radioiodine and Particulates (continued)

2. Projection of Doses Doses resulting from release of radioiodines and particulates will be projected once every 31 days (monthly). The doses will be projected utilizing Equation 3.3-13, and projected using the following expression:

Dp = (D

p) + Da (3.3-16) where:

Dp = the 31 Day Projected Dose by organ D = sum of all open and closed release points from the start of the quarter to the end of the release in mrem per organ .

p = the Projection Factor which is the result of 31 divided by the number of days from start of the quarter to the end of the release.

Da = Additional Anticipated Dose for gaseous releases by organ and quarter of release.

NOTE: The 31 Day Projected Dose values appear on the Standard Permit Reports. The 31 day dose projections include any additional dose.

When possible, expected operational evolutions (i.e., outages, increased power levels, major planned batch gas releases, etc.) should be accounted for in the dose projections. This may be accomplished by using the source-term data from similar historical operating experiences where practical, and adding the dose as Additional Anticipated Dose.

To show compliance with ODCM Operational Requirement 3.11.2.4, the projected month's dose should be compared as in the following:

D 0.3 mrem to any organ (3.3-17)

If the projections exceed Expression 3.3-14, then the appropriate portions of the gaseous radwaste treatment system shall be used to reduce releases of radioactivity.

3.3.2 Carbon 14 Carbon-14 may become a principal radionuclide for the gaseous effluent pathway. It is produced by several nuclear reactions. In a nuclear reactor the most dominate mechanism is the reaction of O-17 in the fuel or water with a neutron to produce C-14 and an alpha particle. C-14 releases in PWRs occur primarily as a mix of organic carbon and carbon dioxide released from the waste gas system. Because the dose contribution of C-14 from liquid radioactive waste is much less than that contributed by gaseous radioactive waste, evaluation of C-14 in liquid waste is not required. The dose rate and subsequent dose to an individual from C-14 intake depends upon the specific activity of the food from each source and the amount of the ingested C-14 which is retained over the period under consideration.

The quantity of C-14 discharged can be estimated by sample measurements or by use of a normalized C-14 source term and scaling factors based upon power generation. NUREG-0017 Rev 1 Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Reactors gives a C-14 source term based on measurements at 10 operating power plants. The C-14 source term recommended by NUREG-0017 (FSAR 11.1.5) is 7.3 curies/year for an 80% capacity factory or 292 Effective Full Power Days. It is not necessary to calculate uncertainties for C-14 or to include C-14 uncertainty in any calculation of overall uncertainty.

In the determination of the limiting sector, all age groups and all of the exposure pathways are evaluated using the highest XOQDOQ values in Appendix A at the site boundary. These include milk, meat and vegetable ingestion, and inhalation. Inorganic atmosphere Carbon Dioxide (CO2) 3-26 Page 9-72

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3.3.2 Carbon 14 (continue) and Methane (CO) is incorporated in cellular material by the photosynthetic actions of green plants.

Plants and grasses, from which most food stuff are derived, equilibrate with the C-14 CO2 of the air.

Due to the Primary Water System reducing environment, only 30% of the C-14 is released in the inorganic form.

Reg Guide 1.21, Rev 2 states that for PWR C-14 is released primarily through the waste gas system. IAEA Technical Reports Series No. 421 states that 70% of C-14 gaseous effluent from PWRs can be assumed to be from batch releases (WGDTs) and 30% from continuous stack releases. To address intermittent releases, a photosynthesis factor (p factor) is used as the ratio of the total release time (for C-14 atmospheric releases) to the total time which photosynthesis occurs (taken to be 4460 hour0.0516 days 1.239 hours 0.00737 weeks 0.0017 months s/year or 1115 hour0.0129 days 0.31 hours 0.00184 weeks 4.242575e-4 months s/quarter).

SHNPP ODCM Operational Requirement 3.12.2 requires that a land-use census survey be conducted on an annual basis. The age groupings at the various receptor locations are also determined during this survey. Thus, depending on the results of the survey, a new limiting location and receptor age group could result.

Regulatory Guide 1.109 provides the detailed implementation guidance to show compliance with Appendix I of 10 CFR 50 limits.

1. Dose from Inhalation of Carbon-14 in Air The average airborne concentration of C-14 at the location with respect to the release point may be determined as:

= 3.17 x 10 (3.3-18)

XC = the average ground-level concentration of C-14 in air, in pCi/m3 QC = is the release rate of C-14 to the atmosphere, in Ci/yr, this can be determined by:

(1) using actual sample data obtained during the reporting period (2) estimation by correcting the FSAR 11.1.5 annual C-14 curies released for actual capacity factor using the number of effective full power days (EFPD) for the reporting period Qc= 7.3 x EFPD (3.3-19) 292 X/Q = annual average atmosphere dispersion factor, in sec/m3 for ground level release with no decay, Table A1 through A4, Appendix A 3.17 X 104 = is the number of pCi/Ci divided by the number of sec/yr The dose associated with inhalation for C-14, to organ (j) to an age group (a), is then:

= ( ) (3.3-20)

= the dose from inhalation to an organ (j) of an age group (a) from C-14 in mrem Xc = the average ground-level concentration of C-14 in air, in pCi/m3

= Inhalation rate for age group (a), Table 3.3-20, in m3/yr

= Dose factor for an organ from carbon-14 for the inhalation pathway to an organ (j) of an age group (a), mrem/pCi Table 3.3-21 3-27 Page 9-73

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3.3.2 Carbon 14 (continue)

2. Concentration of Airborne Carbon-14 in vegetation The concentration of Carbon-14 in vegetation at location with respect to the release point may be determined as:

= (3.17 x 10 )( )( )

(3.3-21)

= The concentration of C-14 in vegetation in pCi/kg p = the fractional equilibrium fraction, dimensionless

= (0.70)(WGDT Release Hr)/(L) + (0.30)(Continuous Release Hrs)/(L)

L = hours photosynthesis occurs L = 1115 hour0.0129 days 0.31 hours 0.00184 weeks 4.242575e-4 months s/qtr or 4460 hour0.0516 days 1.239 hours 0.00737 weeks 0.0017 months s/yr Q14 = release rate of C-14 from a PWR, assume 30% of C-14 release rate in lieu of site specific data, in Ci

= 0.30 x QC 3

X/Q = annual average atmosphere dispersion factor, in sec/m for ground level release with no decay, Table A1 through A4, Appendix A 3.17 E7 = (1012 pCi/Ci)(103 g/kg) / (3.15E7 sec/yr) 0.11 = fraction of total plant mass that is natural carbon, dimensionless 0.16 = concentration of natural carbon in the atmosphere, in g/m3

3. Concentration of Airborne Carbon-14 in Milk The concentration of Carbon-14 in milk is dependent on the amount of contamination level of the feed consumed by the animal.

= ( )( )( ) (3.3-22)

= The concentration of C-14 in milk, pCi/L Fm = average fraction of the animals daily intake of C-14 that appears in each liter of milk, in days/liter

= Cow or cattle = 0.012 days/liter, goat = 0.10 days/liter

= The concentration of C-14 in animals feed, in pCi/kg Qf = amount of feed consumed by the animal per day, in kg/day

= Cow or cattle = 50 kg, goat = 6 kg 3-28 Page 9-74

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3.3.2 Carbon 14 (continue)

4. Concentration of Airborne Carbon-14 in Meat

= ( )( )( ) (3.3-23)

= The concentration of C-14 in meat, pCi/kg FF = average fraction of the animals daily intake of C-14 that appears in each kilogram of flesh, in days/kg

= 0.031

= The concentration of C-14 in animals feed, in pCi/kg Qf = amount of feed consumed by the animal per day, in kg/day

= Cow or cattle = 50 kg, goat = 6 kg

5. Dose from Atmospherically Released Carbon-14 in Foods

= [ + + + ] (3.3-24)

= the dose to organ (j) of an individual in age group (a) from the dietary intake of atmospherically released Carbon-14, in mrem

= the dose conversion factor for the ingestion of Carbon-14, organ (j), and age group (a), in mrem/pCi Table 3.3-22

= ingestion rate of produce (non-leafy vegetables, fruit, grains), in kg/yr, Table 3.3-20

= ingestion rate of milk, in l/yr, Table 3.3-20

= ingestion rate of meat and poultry in kg/yr, Table 3.3-20

= ingestion rate of leafy vegetables, in kg/yr, Table 3.3-20 fg = fraction of produce ingested grow in the garden of interest

= 0.76, in lieu of site specific data fl = fraction of leafy vegetables in the garden of interest

= 1.0 , in lieu of site specific data

= The concentration of C-14 in vegetation, in pCi/kg

= The concentration of C-14 in milk, pCi/kg

= The concentration of C-14 in meat, pCi/kg 3-29 Page 9-75

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-1 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Ground AGE GROUP = ALL Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi Na-24 1.71E+07 1.71E+07 1.71E+07 1.71E+07 1.71E+07 1.71E+07 1.71E+07 Cr-51 4.66E+06 4.66E+06 4.66E+06 4.66E+06 4.66E+06 4.66E+06 4.66E+06 Mn-54 1.34E+09 1.34E+09 1.34E+09 1.34E+09 1.34E+09 1.34E+09 1.34E+09 Mn-56 1.29E+06 1.29E+06 1.29E+06 1.29E+06 1.29E+06 1.29E+06 1.29E+06 Fe-59 2.75E+08 2.75E+08 2.75E+08 2.75E+08 2.75E+08 2.75E+08 2.75E+08 Co-57 1.88E+08 1.88E+08 1.88E+08 1.88E+08 1.88E+08 1.88E+08 1.88E+08 Co-58 3.79E+08 3.79E+08 3.79E+08 3.79E+08 3.79E+08 3.79E+08 3.79E+08 Co-60 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 Ni-65 4.24E+05 4.24E+05 4.24E+05 4.24E+05 4.24E+05 4.24E+05 4.24E+05 Cu-64 8.67E+05 8.67E+05 8.67E+05 8.67E+05 8.67E+05 8.67E+05 8.67E+05 Zn-65 7.49E+08 7.49E+08 7.49E+08 7.49E+08 7.49E+08 7.49E+08 7.49E+08 Zn-69M 3.44E+06 3.44E+06 3.44E+06 3.44E+06 3.44E+06 3.44E+06 3.44E+06 Br-82 5.11E+07 5.11E+07 5.11E+07 5.11E+07 5.11E+07 5.11E+07 5.11E+07 Br-83 6.94E+03 6.94E+03 6.94E+03 6.94E+03 6.94E+03 6.94E+03 6.94E+03 Br-84 2.89E+05 2.89E+05 2.89E+05 2.89E+05 2.89E+05 2.89E+05 2.89E+05 Rb-86 8.99E+06 8.99E+06 8.99E+06 8.99E+06 8.99E+06 8.99E+06 8.99E+06 Rb-88 4.72E+04 4.72E+04 4.72E+04 4.72E+04 4.72E+04 4.72E+04 4.72E+04 Rb-89 1.75E+05 1.75E+05 1.75E+05 1.75E+05 1.75E+05 1.75E+05 1.75E+05 Sr-89 2.23E+04 2.23E+04 2.23E+04 2.23E+04 2.23E+04 2.23E+04 2.23E+04 Sr-91 3.07E+06 3.07E+06 3.07E+06 3.07E+06 3.07E+06 3.07E+06 3.07E+06 Sr-92 1.11E+06 1.11E+06 1.11E+06 1.11E+06 1.11E+06 1.11E+06 1.11E+06 Y-90 6.42E+03 6.42E+03 6.42E+03 6.42E+03 6.42E+03 6.42E+03 6.42E+03 Y-91M 1.43E+05 1.43E+05 1.43E+05 1.43E+05 1.43E+05 1.43E+05 1.43E+05 Y-91 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.08E+06 1.08E+06 Y-92 2.57E+05 2.57E+05 2.57E+05 2.57E+05 2.57E+05 2.57E+05 2.57E+05 Y-93 2.62E+05 2.62E+05 2.62E+05 2.62E+05 2.62E+05 2.62E+05 2.62E+05 Zr-95 2.49E+08 2.49E+08 2.49E+08 2.49E+08 2.49E+08 2.49E+08 2.49E+08 Zr-97 4.21E+06 4.21E+06 4.21E+06 4.21E+06 4.21E+06 4.21E+06 4.21E+06 Nb-95 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1.36E+08 1.36E+08 Nb-97 4.43E+07 4.43E+07 4.43E+07 4.43E+07 4.43E+07 4.43E+07 4.43E+07 Mo-99 5.71E+06 5.71E+06 5.71E+06 5.71E+06 5.71E+06 5.71E+06 5.71E+06 Tc-99M 2.63E+05 2.63E+05 2.63E+05 2.63E+05 2.63E+05 2.63E+05 2.63E+05 3 -2

R Values in units of mrem/yr per Ci/m for inhalation and tritium and in units of mrem/yr per Ci/sec per m for all others.

3-30 Page 9-76

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-1 (Continue)

R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Ground AGE GROUP = ALL Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi Tc-101 2.91E+04 2.91E+04 2.91E+04 2.91E+04 2.91E+04 2.91E+04 2.91E+04 Ru-103 1.09E+08 1.09E+08 1.09E+08 1.09E+08 1.09E+08 1.09E+08 1.09E+08 Ru-105 9.08E+05 9.08E+05 9.08E+05 9.08E+05 9.08E+05 9.08E+05 9.08E+05 Ru-106 4.19E+08 4.19E+08 4.19E+08 4.19E+08 4.19E+08 4.19E+08 4.19E+08 Ag-110M 3.48E+09 3.48E+09 3.48E+09 3.48E+09 3.48E+09 3.48E+09 3.48E+09 Sn-113 1.22E+07 6.21E+06 1.44E+07 1.33E+07 1.00E+07 8.14E+06 6.28E+06 Sb-124 8.99E+08 7.76E+08 8.76E+08 1.01E+09 8.17E+08 8.23E+08 7.53E+08 Sb-125 2.34E+09 2.34E+09 2.34E+09 2.34E+09 2.34E+09 2.34E+09 2.34E+09 Te-125M 1.55E+06 1.55E+06 1.55E+06 1.55E+06 1.55E+06 1.55E+06 1.55E+06 Te-127m 9.15E+04 9.15E+04 9.15E+04 9.15E+04 9.15E+04 9.15E+04 9.15E+04 Te-127 4.25E+03 4.25E+03 4.25E+03 4.25E+03 4.25E+03 4.25E+03 4.25E+03 Te-129M 2.00E+07 2.00E+07 2.00E+07 2.00E+07 2.00E+07 2.00E+07 2.00E+07 Te-129 3.75E+04 3.75E+04 3.75E+04 3.75E+04 3.75E+04 3.75E+04 3.75E+04 Te-131M 1.15E+07 1.15E+07 1.15E+07 1.15E+07 1.15E+07 1.15E+07 1.15E+07 Te-131 4.17E+04 4.17E+04 4.17E+04 4.17E+04 4.17E+04 4.17E+04 4.17E+04 Te-132 6.05E+06 6.05E+06 6.05E+06 6.05E+06 6.05E+06 6.05E+06 6.05E+06 I-130 7.88E+06 7.88E+06 7.88E+06 7.88E+06 7.88E+06 7.88E+06 7.88E+06 I-131 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 I-132 1.24E+06 1.24E+06 1.24E+06 1.24E+06 1.24E+06 1.24E+06 1.24E+06 I-133 2.47E+06 2.47E+06 2.47E+06 2.47E+06 2.47E+06 2.47E+06 2.47E+06 I-134 6.38E+05 6.38E+05 6.38E+05 6.38E+05 6.38E+05 6.38E+05 6.38E+05 I-135 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 2.56E+06 Cs-134 6.82E+09 6.82E+09 6.82E+09 6.82E+09 6.82E+09 6.82E+09 6.82E+09 Cs-136 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 1.49E+08 Cs-137 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 Cs-138 5.13E+05 5.13E+05 5.13E+05 5.13E+05 5.13E+05 5.13E+05 5.13E+05 Ba-139 1.51E+05 1.51E+05 1.51E+05 1.51E+05 1.51E+05 1.51E+05 1.51E+05 Ba-140 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07 Ba-141 5.97E+04 5.97E+04 5.97E+04 5.97E+04 5.97E+04 5.97E+04 5.97E+04 Ba-142 6.41E+04 6.41E+04 6.41E+04 6.41E+04 6.41E+04 6.41E+04 6.41E+04 La-140 2.74E+07 2.74E+07 2.74E+07 2.74E+07 2.74E+07 2.74E+07 2.74E+07 La-142 1.09E+06 1.09E+06 1.09E+06 1.09E+06 1.09E+06 1.09E+06 1.09E+06 Ce-141 1.36E+07 1.36E+07 1.36E+07 1.36E+07 1.36E+07 1.36E+07 1.36E+07 Ce-143 3.30E+06 3.30E+06 3.30E+06 3.30E+06 3.30E+06 3.30E+06 3.30E+06 Ce-144 6.95E+07 6.95E+07 6.95E+07 6.95E+07 6.95E+07 6.95E+07 6.95E+07 Pr-144 2.62E+03 2.62E+03 2.62E+03 2.62E+03 2.62E+03 2.62E+03 2.62E+03 Nd-147 8.40E+06 8.40E+06 8.40E+06 8.40E+06 8.40E+06 8.40E+06 8.40E+06 Hf-181 2.30E+08 1.70E+08 1.97E+08 2.33E+08 1.77E+08 1.82E+08 1.63E+08 W-187 3.36E+06 3.36E+06 3.36E+06 3.36E+06 3.36E+06 3.36E+06 3.36E+06 Np-239 2.44E+06 2.44E+06 2.44E+06 2.44E+06 2.44E+06 2.44E+06 2.44E+06 3 -2

R Values in units of mrem/yr per Ci/m for inhalation and tritium and in units of mrem/yr per Ci/sec per m for all others.

3-31 Page 9-77

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-2 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Vegetation AGE GROUP = Adult Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi H-3 0.00E+00 2.28E+03 2.28E+03 2.28E+03 2.28E+03 2.28E+03 2.28E+03 Na-24 6.83E+05 6.83E+05 6.83E+05 6.83E+05 6.83E+05 6.83E+05 6.83E+05 P-32 1.53E+09 9.51E+07 5.91E+07 0.00E+00 0.00E+00 0.00E+00 1.72E+08 Cr-51 0.00E+00 0.00E+00 4.60E+04 2.75E+04 1.01E+04 6.10E+04 1.16E+07 Mn-54 0.00E+00 3.05E+08 5.83E+07 0.00E+00 9.09E+07 0.00E+00 9.36E+08 Mn-56 0.00E+00 3.98E+01 7.06E+00 0.00E+00 5.05E+01 0.00E+00 1.27E+03 Fe-55 2.00E+08 1.38E+08 3.22E+07 0.00E+00 0.00E+00 7.70E+07 7.91E+07 Fe-59 1.24E+08 2.93E+08 1.12E+08 0.00E+00 0.00E+00 8.17E+07 9.75E+08 Co-57 0.00E+00 1.13E+07 1.88E+07 0.00E+00 0.00E+00 0.00E+00 2.86E+08 Co-58 0.00E+00 2.99E+07 6.71E+07 0.00E+00 0.00E+00 0.00E+00 6.07E+08 Co-60 0.00E+00 1.66E+08 3.67E+08 0.00E+00 0.00E+00 0.00E+00 3.12E+09 Ni-63 1.20E+10 8.31E+08 4.02E+08 0.00E+00 0.00E+00 0.00E+00 1.73E+08 Ni-65 1.50E+02 1.95E+01 8.90E+00 0.00E+00 0.00E+00 0.00E+00 4.95E+02 Cu-64 0.00E+00 2.34E+04 1.10E+04 0.00E+00 5.89E+04 0.00E+00 1.99E+06 Zn-65 4.01E+08 1.28E+09 5.77E+08 0.00E+00 8.54E+08 0.00E+00 8.04E+08 Zn-69M 5.73E+04 1.38E+05 1.26E+04 0.00E+00 8.32E+04 0.00E+00 8.39E+06 Zn-69 1.29E-05 2.47E-05 1.72E-06 0.00E+00 1.61E-05 0.00E+00 3.72E-06 Br-82 0.00E+00 0.00E+00 3.90E+06 0.00E+00 0.00E+00 0.00E+00 4.47E+06 Br-83 0.00E+00 0.00E+00 7.57E+00 0.00E+00 0.00E+00 0.00E+00 1.09E+01 Br-84 0.00E+00 0.00E+00 5.51E-11 0.00E+00 0.00E+00 0.00E+00 4.32E-16 Rb-86 0.00E+00 2.21E+08 1.03E+08 0.00E+00 0.00E+00 0.00E+00 4.36E+07 Rb-88 0.00E+00 6.73E-22 3.57E-22 0.00E+00 0.00E+00 0.00E+00 9.30E-33 Rb-89 0.00E+00 6.19E-26 4.35E-26 0.00E+00 0.00E+00 0.00E+00 3.59E-39 Sr-89 1.00E+10 0.00E+00 2.87E+08 0.00E+00 0.00E+00 0.00E+00 1.60E+09 Sr-90 6.70E+11 0.00E+00 1.64E+11 0.00E+00 0.00E+00 0.00E+00 1.93E+10 Sr-91 7.70E+05 0.00E+00 3.11E+04 0.00E+00 0.00E+00 0.00E+00 3.67E+06 Sr-92 1.07E+03 0.00E+00 4.64E+01 0.00E+00 0.00E+00 0.00E+00 2.13E+04 Y-90 3.43E+04 0.00E+00 9.19E+02 0.00E+00 0.00E+00 0.00E+00 3.63E+08 Y-91M 1.20E-08 0.00E+00 4.66E-10 0.00E+00 0.00E+00 0.00E+00 3.53E-08 Y-91 5.01E+06 0.00E+00 1.34E+05 0.00E+00 0.00E+00 0.00E+00 2.76E+09 Y-92 2.25E+00 0.00E+00 6.59E-02 0.00E+00 0.00E+00 0.00E+00 3.95E+04 Y-93 4.29E+02 0.00E+00 1.18E+01 0.00E+00 0.00E+00 0.00E+00 1.36E+07 Zr-95 1.16E+06 3.71E+05 2.51E+05 0.00E+00 5.82E+05 0.00E+00 1.17E+09 Zr-97 8.50E+02 1.72E+02 7.84E+01 0.00E+00 2.59E+02 0.00E+00 5.31E+07 Nb-95 1.40E+05 7.79E+04 4.19E+04 0.00E+00 7.70E+04 0.00E+00 4.73E+08 Nb-97 5.13E-06 1.30E-06 4.74E-07 0.00E+00 1.51E-06 0.00E+00 4.79E-03 Mo-99 0.00E+00 1.59E+07 3.02E+06 0.00E+00 3.60E+07 0.00E+00 3.68E+07 Tc-99M 7.81E+00 2.21E+01 2.81E+02 0.00E+00 3.35E+02 1.08E+01 1.31E+04 3 -2

R Values in units of mrem/yr per Ci/m for inhalation and tritium and in units of mrem/yr per Ci/sec per m for all others.

3-32 Page 9-78

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-2 (continue)

R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Vegetation AGE GROUP = Adult Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi Tc-101 1.51E-30 2.18E-30 2.14E-29 0.00E+00 3.93E-29 1.11E-30 0.00E+00 Ru-103 4.74E+06 0.00E+00 2.04E+06 0.00E+00 1.81E+07 0.00E+00 5.53E+08 Ru-105 1.34E+02 0.00E+00 5.28E+01 0.00E+00 1.73E+03 0.00E+00 8.18E+04 Ru-106 1.94E+08 0.00E+00 2.46E+07 0.00E+00 3.75E+08 0.00E+00 1.26E+10 Ag-110M 1.13E+07 1.05E+07 6.23E+06 0.00E+00 2.06E+07 0.00E+00 4.28E+09 Sn-113 1.44E+07 5.66E+05 1.36E+07 1.96E+05 4.09E+05 0.00E+00 2.52E+08 Sb-124 1.01E+08 1.92E+06 4.02E+07 2.46E+05 0.00E+00 7.90E+07 2.88E+09 Sb-125 1.34E+08 1.50E+06 3.20E+07 1.37E+05 0.00E+00 1.04E+08 1.48E+09 Te-125M 1.21E+08 4.38E+07 1.62E+07 3.64E+07 4.92E+08 0.00E+00 4.83E+08 Te-127m 5.02E+08 1.80E+08 6.12E+07 1.28E+08 2.04E+09 0.00E+00 1.68E+09 Te-127 1.46E+04 5.25E+03 3.16E+03 1.08E+04 5.95E+04 0.00E+00 1.15E+06 Te-129M 2.98E+08 1.11E+08 4.71E+07 1.02E+08 1.24E+09 0.00E+00 1.50E+09 Te-129 1.85E-03 6.96E-04 4.51E-04 1.42E-03 7.78E-03 0.00E+00 1.40E-03 Te-131M 2.38E+06 1.16E+06 9.71E+05 1.84E+06 1.18E+07 0.00E+00 1.16E+08 Te-131 3.24E-15 1.35E-15 1.02E-15 2.66E-15 1.42E-14 0.00E+00 4.58E-16 Te-132 1.14E+07 7.36E+06 6.91E+06 8.13E+06 7.09E+07 0.00E+00 3.48E+08 I-130 1.96E+05 5.78E+05 2.28E+05 4.90E+07 9.02E+05 0.00E+00 4.98E+05 I-131 8.07E+07 1.15E+08 6.61E+07 3.78E+10 1.98E+08 0.00E+00 3.04E+07 I-132 5.57E+01 1.49E+02 5.21E+01 5.21E+03 2.37E+02 0.00E+00 2.80E+01 I-133 2.11E+06 3.67E+06 1.12E+06 5.39E+08 6.40E+06 0.00E+00 3.30E+06 I-134 4.49E-05 1.22E-04 4.36E-05 2.11E-03 1.94E-04 0.00E+00 1.06E-07 I-135 4.05E+04 1.06E+05 3.91E+04 7.00E+06 1.70E+05 0.00E+00 1.20E+05 Cs-134 4.54E+09 1.08E+10 8.83E+09 0.00E+00 3.49E+09 1.16E+09 1.89E+08 Cs-136 4.19E+07 1.66E+08 1.19E+08 0.00E+00 9.21E+07 1.26E+07 1.88E+07 Cs-137 6.63E+09 9.07E+09 5.94E+09 0.00E+00 3.08E+09 1.02E+09 1.76E+08 Cs-138 8.62E-11 1.70E-10 8.43E-11 0.00E+00 1.25E-10 1.24E-11 7.26E-16 Ba-139 6.87E-02 4.89E-05 2.01E-03 0.00E+00 4.57E-05 2.78E-05 1.22E-01 Ba-140 1.28E+08 1.61E+05 8.40E+06 0.00E+00 5.47E+04 9.22E+04 2.64E+08 Ba-141 2.49E-21 1.88E-24 8.40E-23 0.00E+00 1.75E-24 1.07E-24 1.17E-30 La-140 5.06E+03 2.55E+03 6.73E+02 0.00E+00 0.00E+00 0.00E+00 1.87E+08 La-142 4.89E-04 2.22E-04 5.54E-05 0.00E+00 0.00E+00 0.00E+00 1.62E+00 Ce-141 1.93E+05 1.31E+05 1.48E+04 0.00E+00 6.07E+04 0.00E+00 4.99E+08 Ce-143 2.55E+03 1.89E+06 2.09E+02 0.00E+00 8.30E+02 0.00E+00 7.05E+07 Ce-144 3.15E+07 1.32E+07 1.69E+06 0.00E+00 7.80E+06 0.00E+00 1.06E+10 Pr-143 6.23E+04 2.50E+04 3.09E+03 0.00E+00 1.44E+04 0.00E+00 2.73E+08 Pr-144 6.43E-26 2.67E-26 3.27E-27 0.00E+00 1.50E-26 0.00E+00 9.24E-33 Nd-147 3.33E+04 3.85E+04 2.30E+03 0.00E+00 2.25E+04 0.00E+00 1.85E+08 Hf-181 9.51E+06 5.36E+04 1.07E+06 3.41E+04 4.48E+04 0.00E+00 7.06E+08 W-187 9.69E+04 8.10E+04 2.83E+04 0.00E+00 0.00E+00 0.00E+00 2.65E+07 Np-239 3.67E+03 3.61E+02 1.99E+02 0.00E+00 1.13E+03 0.00E+00 7.40E+07 3 -2

R Values in units of mrem/yr per Ci/m for inhalation and tritium and in units of mrem/yr per Ci/sec per m for all others.

3-33 Page 9-79

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-3 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Vegetation AGE GROUP = Teen Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi H-3 0.00E+00 2.61E+03 2.61E+03 2.61E+03 2.61E+03 2.61E+03 2.61E+03 Na-24 6.07E+05 6.07E+05 6.07E+05 6.07E+05 6.07E+05 6.07E+05 6.07E+05 P-32 1.75E+09 1.09E+08 6.80E+07 0.00E+00 0.00E+00 0.00E+00 1.47E+08 Cr-51 0.00E+00 0.00E+00 6.11E+04 3.39E+04 1.34E+04 8.72E+04 1.03E+07 Mn-54 0.00E+00 4.43E+08 8.79E+07 0.00E+00 1.32E+08 0.00E+00 9.09E+08 Mn-56 0.00E+00 3.59E+01 6.38E+00 0.00E+00 4.54E+01 0.00E+00 2.36E+03 Fe-55 3.10E+08 2.20E+08 5.13E+07 0.00E+00 0.00E+00 1.40E+08 9.53E+07 Fe-59 1.77E+08 4.14E+08 1.60E+08 0.00E+00 0.00E+00 1.30E+08 9.78E+08 Co-57 0.00E+00 1.72E+07 2.89E+07 0.00E+00 0.00E+00 0.00E+00 3.21E+08 Co-58 0.00E+00 4.25E+07 9.79E+07 0.00E+00 0.00E+00 0.00E+00 5.85E+08 Co-60 0.00E+00 2.47E+08 5.57E+08 0.00E+00 0.00E+00 0.00E+00 3.22E+09 Ni-63 1.85E+10 1.31E+09 6.28E+08 0.00E+00 0.00E+00 0.00E+00 2.08E+08 Ni-65 1.40E+02 1.79E+01 8.14E+00 0.00E+00 0.00E+00 0.00E+00 9.68E+02 Cu-64 0.00E+00 2.12E+04 9.95E+03 0.00E+00 5.35E+04 0.00E+00 1.64E+06 Zn-65 5.36E+08 1.86E+09 8.68E+08 0.00E+00 1.19E+09 0.00E+00 7.88E+08 Zn-69M 5.31E+04 1.25E+05 1.15E+04 0.00E+00 7.61E+04 0.00E+00 6.88E+06 Zn-69 1.21E-05 2.31E-05 1.61E-06 0.00E+00 1.51E-05 0.00E+00 4.25E-05 Br-82 0.00E+00 0.00E+00 3.44E+06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 7.10E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 5.01E-11 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.76E+08 1.30E+08 0.00E+00 0.00E+00 0.00E+00 4.09E+07 Rb-88 0.00E+00 6.22E-22 3.32E-22 0.00E+00 0.00E+00 0.00E+00 5.33E-29 Rb-89 0.00E+00 5.57E-26 3.94E-26 0.00E+00 0.00E+00 0.00E+00 8.54E-35 Sr-89 1.52E+10 0.00E+00 4.36E+08 0.00E+00 0.00E+00 0.00E+00 1.81E+09 Sr-90 8.32E+11 0.00E+00 2.05E+11 0.00E+00 0.00E+00 0.00E+00 2.33E+10 Sr-91 7.19E+05 0.00E+00 2.86E+04 0.00E+00 0.00E+00 0.00E+00 3.26E+06 Sr-92 9.99E+02 0.00E+00 4.26E+01 0.00E+00 0.00E+00 0.00E+00 2.54E+04 Y-90 3.20E+04 0.00E+00 8.63E+02 0.00E+00 0.00E+00 0.00E+00 2.64E+08 Y-91M 1.12E-08 0.00E+00 4.28E-10 0.00E+00 0.00E+00 0.00E+00 5.29E-07 Y-91 7.68E+06 0.00E+00 2.06E+05 0.00E+00 0.00E+00 0.00E+00 3.15E+09 Y-92 2.12E+00 0.00E+00 6.12E-02 0.00E+00 0.00E+00 0.00E+00 5.81E+04 Y-93 4.02E+02 0.00E+00 1.10E+01 0.00E+00 0.00E+00 0.00E+00 1.23E+07 Zr-95 1.69E+06 5.35E+05 3.68E+05 0.00E+00 7.86E+05 0.00E+00 1.23E+09 Zr-97 7.87E+02 1.56E+02 7.17E+01 0.00E+00 2.36E+02 0.00E+00 4.22E+07 Nb-95 1.89E+05 1.05E+05 5.77E+04 0.00E+00 1.02E+05 0.00E+00 4.48E+08 Nb-97 4.76E-06 1.18E-06 4.31E-07 0.00E+00 1.38E-06 0.00E+00 2.82E-02 Mo-99 0.00E+00 1.46E+07 2.78E+06 0.00E+00 3.34E+07 0.00E+00 2.61E+07 Tc-99M 6.89E+00 1.92E+01 2.49E+02 0.00E+00 2.86E+02 1.07E+01 1.26E+04 3 -2

R Values in units of mrem/yr per Ci/m for inhalation and tritium and in units of mrem/yr per Ci/sec per m for all others.

3-34 Page 9-80

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-3 (continue)

R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Vegetation AGE GROUP = Teen Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi Tc-101 1.41E-30 2.00E-30 1.97E-29 0.00E+00 3.62E-29 1.22E-30 3.42E-37 Ru-103 6.78E+06 0.00E+00 2.90E+06 0.00E+00 2.39E+07 0.00E+00 5.66E+08 Ru-105 1.24E+02 0.00E+00 4.82E+01 0.00E+00 1.57E+03 0.00E+00 1.00E+05 Ru-106 3.12E+08 0.00E+00 3.93E+07 0.00E+00 6.02E+08 0.00E+00 1.50E+10 Ag-110M 1.63E+07 1.54E+07 9.39E+06 0.00E+00 2.95E+07 0.00E+00 4.34E+09 Sn-113 1.91E+07 8.03E+05 2.02E+07 2.63E+05 5.65E+05 0.00E+00 2.29E+08 Sb-124 1.51E+08 2.78E+06 5.89E+07 3.43E+05 0.00E+00 1.32E+08 3.04E+09 Sb-125 2.11E+08 2.30E+06 4.92E+07 2.01E+05 0.00E+00 1.85E+08 1.64E+09 Te-125M 1.86E+08 6.69E+07 2.48E+07 5.19E+07 0.00E+00 0.00E+00 5.48E+08 Te-127m 7.93E+08 2.81E+08 9.44E+07 1.89E+08 3.22E+09 0.00E+00 1.98E+09 Te-127 1.38E+04 4.88E+03 2.96E+03 9.50E+03 5.58E+04 0.00E+00 1.06E+06 Te-129M 4.29E+08 1.59E+08 6.79E+07 1.38E+08 1.77E+09 0.00E+00 1.61E+09 Te-129 1.73E-03 6.46E-04 4.22E-04 1.24E-03 7.28E-03 0.00E+00 9.48E-03 Te-131M 2.20E+06 1.06E+06 8.82E+05 1.59E+06 1.10E+07 0.00E+00 8.48E+07 Te-131 3.01E-15 1.24E-15 9.40E-16 2.32E-15 1.32E-14 0.00E+00 2.47E-16 Te-132 1.03E+07 6.55E+06 6.17E+06 6.91E+06 6.29E+07 0.00E+00 2.08E+08 I-130 1.75E+05 5.07E+05 2.02E+05 4.13E+07 7.81E+05 0.00E+00 3.90E+05 I-131 7.68E+07 1.07E+08 5.77E+07 3.14E+10 1.85E+08 0.00E+00 2.13E+07 I-132 5.02E+01 1.31E+02 4.72E+01 4.43E+03 2.07E+02 0.00E+00 5.72E+01 I-133 1.96E+06 3.32E+06 1.01E+06 4.64E+08 5.83E+06 0.00E+00 2.51E+06 I-134 4.06E-05 1.08E-04 3.86E-05 1.79E-03 1.70E-04 0.00E+00 1.42E-06 I-135 3.66E+04 9.42E+04 3.49E+04 6.06E+06 1.49E+05 0.00E+00 1.04E+05 Cs-134 6.90E+09 1.62E+10 7.54E+09 0.00E+00 5.16E+09 1.97E+09 2.02E+08 Cs-136 4.28E+07 1.68E+08 1.13E+08 0.00E+00 9.16E+07 1.44E+07 1.35E+07 Cs-137 1.06E+10 1.41E+10 4.90E+09 0.00E+00 4.78E+09 1.86E+09 2.00E+08 Cs-138 7.95E-11 1.53E-10 7.63E-11 0.00E+00 1.13E-10 1.31E-11 6.93E-14 Ba-139 6.46E-02 4.54E-05 1.88E-03 0.00E+00 4.28E-05 3.13E-05 5.76E-01 Ba-140 1.38E+08 1.69E+05 8.88E+06 0.00E+00 5.72E+04 1.14E+05 2.12E+08 Ba-141 2.33E-21 1.74E-24 7.77E-23 0.00E+00 1.61E-24 1.19E-24 4.96E-27 La-140 4.62E+03 2.27E+03 6.04E+02 0.00E+00 0.00E+00 0.00E+00 1.30E+08 La-142 4.49E-04 1.99E-04 4.97E-05 0.00E+00 0.00E+00 0.00E+00 6.07E+00 Ce-141 2.77E+05 1.85E+05 2.12E+04 0.00E+00 8.70E+04 0.00E+00 5.29E+08 Ce-143 2.38E+03 1.73E+06 1.94E+02 0.00E+00 7.78E+02 0.00E+00 5.21E+07 Ce-144 5.04E+07 2.09E+07 2.71E+06 0.00E+00 1.25E+07 0.00E+00 1.27E+10 Pr-143 6.97E+04 2.78E+04 3.47E+03 0.00E+00 1.62E+04 0.00E+00 2.29E+08 Pr-144 6.02E-26 2.47E-26 3.05E-27 0.00E+00 1.41E-26 0.00E+00 6.64E-29 Nd-147 3.62E+04 3.94E+04 2.36E+03 0.00E+00 2.31E+04 0.00E+00 1.42E+08 Hf-181 1.38E+07 7.58E+04 1.54E+06 4.63E+04 6.32E+04 0.00E+00 6.90E+08 W-187 9.02E+04 7.35E+04 2.58E+04 0.00E+00 0.00E+00 0.00E+00 1.99E+07 Np-239 3.56E+03 3.36E+02 1.87E+02 0.00E+00 1.05E+03 0.00E+00 5.40E+07 3 -2

R Values in units of mrem/yr per Ci/m for inhalation and tritium and in units of mrem/yr per Ci/sec per m for all others.

3-35 Page 9-81

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-4 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Vegetation AGE GROUP = Child Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi H-3 0.00E+00 4.04E+03 4.04E+03 4.04E+03 4.04E+03 4.04E+03 4.04E+03 Na-24 9.47E+05 9.47E+05 9.47E+05 9.47E+05 9.47E+05 9.47E+05 9.47E+05 P-32 3.67E+09 1.72E+08 1.42E+08 0.00E+00 0.00E+00 0.00E+00 1.01E+08 Cr-51 0.00E+00 0.00E+00 1.16E+05 6.44E+04 1.76E+04 1.18E+05 6.15E+06 Mn-54 0.00E+00 6.49E+08 1.73E+08 0.00E+00 1.82E+08 0.00E+00 5.44E+08 Mn-56 0.00E+00 4.70E+01 1.06E+01 0.00E+00 5.68E+01 0.00E+00 6.81E+03 Fe-55 7.63E+08 4.05E+08 1.25E+08 0.00E+00 0.00E+00 2.29E+08 7.50E+07 Fe-59 3.93E+08 6.36E+08 3.17E+08 0.00E+00 0.00E+00 1.84E+08 6.62E+08 Co-57 0.00E+00 2.88E+07 5.83E+07 0.00E+00 0.00E+00 0.00E+00 2.36E+08 Co-58 0.00E+00 6.27E+07 1.92E+08 0.00E+00 0.00E+00 0.00E+00 3.66E+08 Co-60 0.00E+00 3.76E+08 1.11E+09 0.00E+00 0.00E+00 0.00E+00 2.08E+09 Ni-63 4.55E+10 2.44E+09 1.55E+09 0.00E+00 0.00E+00 0.00E+00 1.64E+08 Ni-65 2.56E+02 2.41E+01 1.41E+01 0.00E+00 0.00E+00 0.00E+00 2.96E+03 Cu-64 0.00E+00 2.79E+04 1.69E+04 0.00E+00 6.74E+04 0.00E+00 1.31E+06 Zn-65 1.03E+09 2.74E+09 1.70E+09 0.00E+00 1.73E+09 0.00E+00 4.81E+08 Zn-69M 9.72E+04 1.66E+05 1.96E+04 0.00E+00 9.63E+04 0.00E+00 5.39E+06 Zn-69 2.23E-05 3.23E-05 2.98E-06 0.00E+00 1.96E-05 0.00E+00 2.04E-03 Br-82 0.00E+00 0.00E+00 5.29E+06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 1.31E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 8.50E-11 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 4.56E+08 2.81E+08 0.00E+00 0.00E+00 0.00E+00 2.94E+07 Rb-88 0.00E+00 8.59E-22 5.97E-22 0.00E+00 0.00E+00 0.00E+00 4.21E-23 Rb-89 0.00E+00 7.33E-26 6.52E-26 0.00E+00 0.00E+00 0.00E+00 6.39E-28 Sr-89 3.62E+10 0.00E+00 1.03E+09 0.00E+00 0.00E+00 0.00E+00 1.40E+09 Sr-90 1.38E+12 0.00E+00 3.49E+11 0.00E+00 0.00E+00 0.00E+00 1.86E+10 Sr-91 1.32E+06 0.00E+00 5.00E+04 0.00E+00 0.00E+00 0.00E+00 2.92E+06 Sr-92 1.83E+03 0.00E+00 7.34E+01 0.00E+00 0.00E+00 0.00E+00 3.47E+04 Y-90 5.95E+04 0.00E+00 1.59E+03 0.00E+00 0.00E+00 0.00E+00 1.69E+08 Y-91M 2.05E-08 0.00E+00 7.48E-10 0.00E+00 0.00E+00 0.00E+00 4.02E-05 Y-91 1.83E+07 0.00E+00 4.89E+05 0.00E+00 0.00E+00 0.00E+00 2.44E+09 Y-92 3.90E+00 0.00E+00 1.12E-01 0.00E+00 0.00E+00 0.00E+00 1.13E+05 Y-93 7.41E+02 0.00E+00 2.03E+01 0.00E+00 0.00E+00 0.00E+00 1.10E+07 Zr-95 3.80E+06 8.35E+05 7.44E+05 0.00E+00 1.20E+06 0.00E+00 8.71E+08 Zr-97 1.44E+03 2.08E+02 1.23E+02 0.00E+00 2.98E+02 0.00E+00 3.15E+07 Nb-95 4.04E+05 1.57E+05 1.12E+05 0.00E+00 1.48E+05 0.00E+00 2.91E+08 Nb-97 8.67E-06 1.57E-06 7.31E-07 0.00E+00 1.74E-06 0.00E+00 4.83E-01 Mo-99 0.00E+00 1.99E+07 4.92E+06 0.00E+00 4.25E+07 0.00E+00 1.65E+07 Tc-99M 1.19E+01 2.32E+01 3.85E+02 0.00E+00 3.38E+02 1.18E+01 1.32E+04 3 -2

R Values in units of mrem/yr per Ci/m for inhalation and tritium and in units of mrem/yr per Ci/sec per m for all others.

3-36 Page 9-82

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-4 (continue)

R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Vegetation AGE GROUP = Child Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi Tc-101 2.59E-30 2.71E-30 3.44E-29 0.00E+00 4.62E-29 1.43E-30 8.62E-30 Ru-103 1.52E+07 0.00E+00 5.86E+06 0.00E+00 3.84E+07 0.00E+00 3.94E+08 Ru-105 2.28E+02 0.00E+00 8.26E+01 0.00E+00 2.00E+03 0.00E+00 1.49E+05 Ru-106 7.52E+08 0.00E+00 9.38E+07 0.00E+00 1.02E+09 0.00E+00 1.17E+10 Ag-110M 3.46E+07 2.34E+07 1.87E+07 0.00E+00 4.35E+07 0.00E+00 2.78E+09 Sn-113 3.64E+07 1.18E+06 3.97E+07 4.82E+05 8.09E+05 0.00E+00 1.45E+08 Sb-124 3.44E+08 4.47E+06 1.21E+08 7.61E+05 0.00E+00 1.91E+08 2.16E+09 Sb-125 4.91E+08 3.79E+06 1.03E+08 4.55E+05 0.00E+00 2.74E+08 1.17E+09 Te-125M 4.39E+08 1.19E+08 5.85E+07 1.23E+08 0.00E+00 0.00E+00 4.24E+08 Te-127m 1.90E+09 5.12E+08 2.26E+08 4.55E+08 5.42E+09 0.00E+00 1.54E+09 Te-127 2.54E+04 6.85E+03 5.45E+03 1.76E+04 7.23E+04 0.00E+00 9.93E+05 Te-129M 9.98E+08 2.79E+08 1.55E+08 3.22E+08 2.93E+09 0.00E+00 1.22E+09 Te-129 3.21E-03 8.96E-04 7.62E-04 2.29E-03 9.39E-03 0.00E+00 2.00E-01 Te-131M 4.03E+06 1.39E+06 1.48E+06 2.86E+06 1.35E+07 0.00E+00 5.65E+07 Te-131 5.54E-15 1.69E-15 1.65E-15 4.24E-15 1.68E-14 0.00E+00 2.91E-14 Te-132 1.85E+07 8.20E+06 9.91E+06 1.19E+07 7.62E+07 0.00E+00 8.26E+07 I-130 3.08E+05 6.21E+05 3.20E+05 6.85E+07 9.29E+05 0.00E+00 2.91E+05 I-131 1.43E+08 1.44E+08 8.16E+07 4.75E+10 2.36E+08 0.00E+00 1.23E+07 I-132 8.91E+01 1.64E+02 7.53E+01 7.60E+03 2.51E+02 0.00E+00 1.93E+02 I-133 3.57E+06 4.42E+06 1.67E+06 8.21E+08 7.36E+06 0.00E+00 1.78E+06 I-134 7.21E-05 1.34E-04 6.16E-05 3.08E-03 2.05E-04 0.00E+00 8.88E-05 I-135 6.50E+04 1.17E+05 5.54E+04 1.04E+07 1.79E+05 0.00E+00 8.92E+04 Cs-134 1.56E+10 2.56E+10 5.40E+09 0.00E+00 7.93E+09 2.84E+09 1.38E+08 Cs-136 8.04E+07 2.21E+08 1.43E+08 0.00E+00 1.18E+08 1.76E+07 7.77E+06 Cs-137 2.49E+10 2.39E+10 3.52E+09 0.00E+00 7.78E+09 2.80E+09 1.50E+08 Cs-138 1.45E-10 2.01E-10 1.27E-10 0.00E+00 1.41E-10 1.52E-11 9.26E-11 Ba-139 1.19E-01 6.36E-05 3.45E-03 0.00E+00 5.55E-05 3.74E-05 6.87E+00 Ba-140 2.76E+08 2.42E+05 1.61E+07 0.00E+00 7.87E+04 1.44E+05 1.40E+08 Ba-141 4.29E-21 2.40E-24 1.40E-22 0.00E+00 2.08E-24 1.41E-23 2.45E-21 La-140 8.30E+03 2.90E+03 9.78E+02 0.00E+00 0.00E+00 0.00E+00 8.08E+07 La-142 8.14E-04 2.59E-04 8.12E-05 0.00E+00 0.00E+00 0.00E+00 5.14E+01 Ce-141 6.42E+05 3.20E+05 4.75E+04 0.00E+00 1.40E+05 0.00E+00 3.99E+08 Ce-143 4.39E+03 2.38E+06 3.45E+02 0.00E+00 9.98E+02 0.00E+00 3.48E+07 Ce-144 1.22E+08 3.81E+07 6.49E+06 0.00E+00 2.11E+07 0.00E+00 9.94E+09 Pr-143 1.45E+05 4.35E+04 7.18E+03 0.00E+00 2.35E+04 0.00E+00 1.56E+08 Pr-144 1.12E-25 3.46E-26 5.63E-27 0.00E+00 1.83E-26 0.00E+00 7.45E-23 Nd-147 7.15E+04 5.79E+04 4.48E+03 0.00E+00 3.18E+04 0.00E+00 9.17E+07 Hf-181 3.13E+07 1.22E+05 3.15E+06 1.03E+05 9.78E+04 0.00E+00 5.17E+08 W-187 1.64E+05 9.71E+04 4.36E+04 0.00E+00 0.00E+00 0.00E+00 1.36E+07 Np-239 6.58E+03 4.72E+02 3.32E+02 0.00E+00 1.37E+03 0.00E+00 3.49E+07

R Values in units of mrem/yr per Ci/m3 for inhalation and tritium and in units of mrem/yr per Ci/sec per m-2 for all others.

3-37 Page 9-83

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-5 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Meat AGE GROUP = Adult Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi H-3 0.00E+00 3.27E+02 3.27E+02 3.27E+02 3.27E+02 3.27E+02 3.27E+02 P-32 3.05E+09 1.89E+08 1.18E+08 0.00E+00 0.00E+00 0.00E+00 3.43E+08 Cr-51 0.00E+00 0.00E+00 4.27E+03 2.56E+03 9.42E+02 5.67E+03 1.08E+06 Mn-54 0.00E+00 5.57E+06 1.06E+06 0.00E+00 1.66E+06 0.00E+00 1.71E+07 Fe-55 1.83E+08 1.26E+08 2.95E+07 0.00E+00 0.00E+00 7.05E+07 7.25E+07 Fe-59 1.59E+08 3.74E+08 1.43E+08 0.00E+00 0.00E+00 1.04E+08 1.25E+09 Co-57 0.00E+00 3.48E+06 5.79E+06 0.00E+00 0.00E+00 0.00E+00 8.84E+07 Co-58 0.00E+00 1.08E+07 2.43E+07 0.00E+00 0.00E+00 0.00E+00 2.20E+08 Co-60 0.00E+00 4.66E+07 1.03E+08 0.00E+00 0.00E+00 0.00E+00 8.76E+08 Ni-63 1.32E+10 9.13E+08 4.42E+08 0.00E+00 0.00E+00 0.00E+00 1.91E+08 Zn-65 2.49E+08 7.91E+08 3.58E+08 0.00E+00 5.29E+08 0.00E+00 4.98E+08 Br-82 0.00E+00 0.00E+00 1.38E-32 0.00E+00 0.00E+00 0.00E+00 1.58E-32 Rb-86 0.00E+00 3.04E+08 1.42E+08 0.00E+00 0.00E+00 0.00E+00 6.00E+07 Sr-89 1.82E+08 0.00E+00 5.23E+06 0.00E+00 0.00E+00 0.00E+00 2.92E+07 Sr-90 8.22E+09 0.00E+00 2.02E+09 0.00E+00 0.00E+00 0.00E+00 2.38E+08 Y-90 1.06E-17 0.00E+00 2.83E-19 0.00E+00 0.00E+00 0.00E+00 1.12E-13 Y-91 6.75E+05 0.00E+00 1.80E+04 0.00E+00 0.00E+00 0.00E+00 3.71E+08 Zr-95 1.12E+06 3.59E+05 2.43E+05 0.00E+00 5.64E+05 0.00E+00 1.14E+09 Nb-95 1.38E+06 7.66E+05 4.12E+05 0.00E+00 7.58E+05 0.00E+00 4.65E+09 Nb-97 8.25E-08 2.09E-08 7.62E-09 0.00E+00 2.43E-08 0.00E+00 7.70E-05 Mo-99 0.00E+00 4.67E-15 8.89E-16 0.00E+00 1.06E-14 0.00E+00 1.08E-14 Ru-103 6.32E+07 0.00E+00 2.72E+07 0.00E+00 2.41E+08 0.00E+00 7.38E+09 Ru-106 1.73E+09 0.00E+00 2.19E+08 0.00E+00 3.35E+09 0.00E+00 1.12E+11 Ag-110M 4.27E+06 3.95E+06 2.34E+06 0.00E+00 7.76E+06 0.00E+00 1.61E+09 Sn-113 2.97E+07 1.15E+06 2.80E+07 4.03E+05 8.40E+05 0.00E+00 5.19E+08 Sb-124 1.19E+07 2.25E+05 4.72E+06 2.88E+04 0.00E+00 9.27E+06 3.38E+08 Te-125M 2.43E+08 8.79E+07 3.25E+07 7.30E+07 9.87E+08 0.00E+00 9.69E+08 Te-127m 8.22E+08 2.94E+08 1.00E+08 2.10E+08 3.34E+09 0.00E+00 2.76E+09 Te-129M 7.40E+08 2.76E+08 1.17E+08 2.54E+08 3.09E+09 0.00E+00 3.73E+09 Te-132 4.41E-10 2.85E-10 2.68E-10 3.15E-10 2.75E-09 0.00E+00 1.35E-08 I-131 7.04E+06 1.01E+07 5.77E+06 3.30E+09 1.73E+07 0.00E+00 2.66E+06 I-133 2.85E-01 4.96E-01 1.51E-01 7.29E+01 8.66E-01 0.00E+00 4.46E-01 I-135 6.28E-17 1.64E-16 6.07E-17 1.08E-14 2.64E-16 0.00E+00 1.86E-16 Cs-134 4.01E+08 9.55E+08 7.81E+08 0.00E+00 3.09E+08 1.03E+08 1.67E+07 Cs-136 7.53E+06 2.97E+07 2.14E+07 0.00E+00 1.65E+07 2.27E+06 3.33E+06 Cs-137 5.57E+08 7.61E+08 4.99E+08 0.00E+00 2.58E+08 8.59E+07 1.47E+07 Ba-140 1.83E+07 2.30E+04 1.20E+06 0.00E+00 7.82E+03 1.32E+04 3.77E+07 La-140 7.57E-33 3.82E-33 1.01E-33 0.00E+00 0.00E+00 0.00E+00 2.80E-28 Ce-141 8.42E+03 5.69E+03 6.46E+02 0.00E+00 2.65E+03 0.00E+00 2.18E+07 Ce-144 8.75E+05 3.66E+05 4.70E+04 0.00E+00 2.17E+05 0.00E+00 2.96E+08 Pr-143 1.33E+04 5.34E+03 6.60E+02 0.00E+00 3.08E+03 0.00E+00 5.83E+07 Nd-147 4.57E+03 5.29E+03 3.16E+02 0.00E+00 3.09E+03 0.00E+00 2.54E+07 Hf-181 1.34E+07 7.57E+04 1.52E+06 4.81E+04 6.33E+04 0.00E+00 9.97E+08 Np-239 5.63E-23 5.53E-24 3.05E-24 0.00E+00 1.73E-23 0.00E+00 1.14E-18 3 -2

R Values in units of mrem/yr per Ci/m for inhalation and tritium and in units of mrem/yr per Ci/sec per m for all others.

3-38 Page 9-84

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-6 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Meat AGE GROUP = Teen Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi H-3 0.00E+00 1.95E+02 1.95E+02 1.95E+02 1.95E+02 1.95E+02 1.95E+02 P-32 2.58E+09 1.60E+08 9.98E+07 0.00E+00 0.00E+00 0.00E+00 2.16E+08 Cr-51 0.00E+00 0.00E+00 3.42E+03 1.90E+03 7.49E+02 4.88E+03 5.75E+05 Mn-54 0.00E+00 4.25E+06 8.43E+05 0.00E+00 1.27E+06 0.00E+00 8.72E+06 Fe-55 1.49E+08 1.05E+08 2.46E+07 0.00E+00 0.00E+00 6.68E+07 4.56E+07 Fe-59 1.27E+08 2.97E+08 1.15E+08 0.00E+00 0.00E+00 9.36E+07 7.02E+08 Co-57 0.00E+00 2.80E+06 4.69E+06 0.00E+00 0.00E+00 0.00E+00 5.22E+07 Co-58 0.00E+00 8.36E+06 1.93E+07 0.00E+00 0.00E+00 0.00E+00 1.15E+08 Co-60 0.00E+00 3.62E+07 8.15E+07 0.00E+00 0.00E+00 0.00E+00 4.71E+08 Ni-63 1.06E+10 7.49E+08 3.59E+08 0.00E+00 0.00E+00 0.00E+00 1.19E+08 Zn-65 1.75E+08 6.07E+08 2.83E+08 0.00E+00 3.89E+08 0.00E+00 2.57E+08 Br-82 0.00E+00 0.00E+00 1.10E-32 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.54E+08 1.19E+08 0.00E+00 0.00E+00 0.00E+00 3.76E+07 Sr-89 1.54E+08 0.00E+00 4.40E+06 0.00E+00 0.00E+00 0.00E+00 1.83E+07 Sr-90 5.32E+09 0.00E+00 1.31E+09 0.00E+00 0.00E+00 0.00E+00 1.49E+08 Y-90 8.89E-18 0.00E+00 2.39E-19 0.00E+00 0.00E+00 0.00E+00 7.33E-14 Y-91 5.68E+05 0.00E+00 1.52E+04 0.00E+00 0.00E+00 0.00E+00 2.33E+08 Zr-95 8.97E+05 2.83E+05 1.95E+05 0.00E+00 4.16E+05 0.00E+00 6.53E+08 Nb-95 1.08E+06 5.97E+05 3.29E+05 0.00E+00 5.79E+05 0.00E+00 2.55E+09 Nb-97 6.83E-08 1.71E-08 6.24E-09 0.00E+00 2.00E-08 0.00E+00 4.08E-04 Mo-99 0.00E+00 3.86E-15 7.37E-16 0.00E+00 8.84E-15 0.00E+00 6.92E-15 Ru-103 5.15E+07 0.00E+00 2.20E+07 0.00E+00 1.82E+08 0.00E+00 4.30E+09 Ru-106 1.46E+09 0.00E+00 1.84E+08 0.00E+00 2.81E+09 0.00E+00 7.00E+10 Ag-110M 3.23E+06 3.06E+06 1.86E+06 0.00E+00 5.83E+06 0.00E+00 8.59E+08 Sn-113 2.09E+07 8.80E+05 2.22E+07 2.88E+05 6.19E+05 0.00E+00 2.51E+08 Sb-124 9.73E+06 1.79E+05 3.80E+06 2.21E+04 0.00E+00 8.50E+06 1.96E+08 Te-125M 2.05E+08 7.39E+07 2.74E+07 5.73E+07 0.00E+00 0.00E+00 6.05E+08 Te-127m 6.94E+08 2.46E+08 8.25E+07 1.65E+08 2.81E+09 0.00E+00 1.73E+09 Te-129M 6.20E+08 2.30E+08 9.81E+07 2.00E+08 2.59E+09 0.00E+00 2.33E+09 Te-132 3.61E-10 2.28E-10 2.15E-10 2.41E-10 2.19E-09 0.00E+00 7.23E-09 I-131 5.85E+06 8.20E+06 4.40E+06 2.39E+09 1.41E+07 0.00E+00 1.62E+06 I-133 2.39E-01 4.05E-01 1.23E-01 5.65E+01 7.10E-01 0.00E+00 3.06E-01 I-135 5.11E-17 1.32E-16 4.88E-17 8.46E-15 2.08E-16 0.00E+00 1.46E-16 Cs-134 3.19E+08 7.51E+08 3.48E+08 0.00E+00 2.39E+08 9.11E+07 9.34E+06 Cs-136 5.87E+06 2.31E+07 1.55E+07 0.00E+00 1.26E+07 1.98E+06 1.86E+06 Cs-137 4.62E+08 6.15E+08 2.14E+08 0.00E+00 2.09E+08 8.13E+07 8.75E+06 Ba-140 1.51E+07 1.86E+04 9.76E+05 0.00E+00 6.29E+03 1.25E+04 2.34E+07 La-140 6.23E-33 3.06E-33 8.14E-34 0.00E+00 0.00E+00 0.00E+00 1.76E-28 Ce-141 7.07E+03 4.72E+03 5.42E+02 0.00E+00 2.22E+03 0.00E+00 1.35E+07 Ce-144 7.37E+05 3.05E+05 3.96E+04 0.00E+00 1.82E+05 0.00E+00 1.85E+08 Pr-143 1.12E+04 4.47E+03 5.58E+02 0.00E+00 2.60E+03 0.00E+00 3.69E+07 Nd-147 4.03E+03 4.38E+03 2.63E+02 0.00E+00 2.57E+03 0.00E+00 1.58E+07 Hf-181 1.10E+07 6.05E+04 1.22E+06 3.69E+04 5.04E+04 0.00E+00 5.50E+08 Np-239 4.92E-23 4.64E-24 2.58E-24 0.00E+00 1.46E-23 0.00E+00 7.46E-19 3 -2

R Values in units of mrem/yr per Ci/m for inhalation and tritium and in units of mrem/yr per Ci/sec per m for all others.

3-39 Page 9-85

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-7 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Meat AGE GROUP = Child Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi H-3 0.00E+00 2.36E+02 2.36E+02 2.36E+02 2.36E+02 2.36E+02 2.36E+02 P-32 4.86E+09 2.27E+08 1.87E+08 0.00E+00 0.00E+00 0.00E+00 1.34E+08 Cr-51 0.00E+00 0.00E+00 5.33E+03 2.96E+03 8.09E+02 5.40E+03 2.83E+05 Mn-54 0.00E+00 4.86E+06 1.30E+06 0.00E+00 1.36E+06 0.00E+00 4.08E+06 Fe-55 2.85E+08 1.51E+08 4.69E+07 0.00E+00 0.00E+00 8.56E+07 2.80E+07 Fe-59 2.25E+08 3.65E+08 1.82E+08 0.00E+00 0.00E+00 1.06E+08 3.80E+08 Co-57 0.00E+00 3.66E+06 7.41E+06 0.00E+00 0.00E+00 0.00E+00 3.00E+07 Co-58 0.00E+00 9.76E+06 2.99E+07 0.00E+00 0.00E+00 0.00E+00 5.70E+07 Co-60 0.00E+00 4.30E+07 1.27E+08 0.00E+00 0.00E+00 0.00E+00 2.38E+08 Ni-63 2.03E+10 1.09E+09 6.91E+08 0.00E+00 0.00E+00 0.00E+00 7.33E+07 Zn-65 2.62E+08 6.99E+08 4.35E+08 0.00E+00 4.40E+08 0.00E+00 1.23E+08 Br-82 0.00E+00 0.00E+00 1.72E-32 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 3.60E+08 2.21E+08 0.00E+00 0.00E+00 0.00E+00 2.32E+07 Sr-89 2.91E+08 0.00E+00 8.31E+06 0.00E+00 0.00E+00 0.00E+00 1.13E+07 Sr-90 6.87E+09 0.00E+00 1.74E+09 0.00E+00 0.00E+00 0.00E+00 9.26E+07 Y-90 1.68E-17 0.00E+00 4.50E-19 0.00E+00 0.00E+00 0.00E+00 4.79E-14 Y-91 1.07E+06 0.00E+00 2.87E+04 0.00E+00 0.00E+00 0.00E+00 1.43E+08 Zr-95 1.59E+06 3.50E+05 3.12E+05 0.00E+00 5.01E+05 0.00E+00 3.65E+08 Nb-95 1.86E+06 7.23E+05 5.17E+05 0.00E+00 6.80E+05 0.00E+00 1.34E+09 Nb-97 1.28E-07 2.31E-08 1.08E-08 0.00E+00 2.56E-08 0.00E+00 7.13E-03 Mo-99 0.00E+00 5.38E-15 1.33E-15 0.00E+00 1.15E-14 0.00E+00 4.45E-15 Ru-103 9.31E+07 0.00E+00 3.58E+07 0.00E+00 2.34E+08 0.00E+00 2.41E+09 Ru-106 2.75E+09 0.00E+00 3.43E+08 0.00E+00 3.71E+09 0.00E+00 4.27E+10 Ag-110M 5.36E+06 3.62E+06 2.89E+06 0.00E+00 6.74E+06 0.00E+00 4.30E+08 Sn-113 3.14E+07 1.01E+06 3.42E+07 4.15E+05 6.97E+05 0.00E+00 1.25E+08 Sb-124 1.76E+07 2.28E+05 6.17E+06 3.88E+04 0.00E+00 9.77E+06 1.10E+08 Te-125M 3.85E+08 1.04E+08 5.13E+07 1.08E+08 0.00E+00 0.00E+00 3.71E+08 Te-127m 1.31E+09 3.52E+08 1.55E+08 3.13E+08 3.73E+09 0.00E+00 1.06E+09 Te-129M 1.17E+09 3.26E+08 1.81E+08 3.77E+08 3.43E+09 0.00E+00 1.42E+09 Te-132 6.58E-10 2.91E-10 3.52E-10 4.24E-10 2.70E-09 0.00E+00 2.93E-09 I-131 1.09E+07 1.09E+07 6.20E+06 3.61E+09 1.79E+07 0.00E+00 9.72E+05 I-133 4.43E-01 5.48E-01 2.07E-01 1.02E+02 9.13E-01 0.00E+00 2.21E-01 I-135 9.25E-17 1.66E-16 7.87E-17 1.47E-14 2.55E-16 0.00E+00 1.27E-16 Cs-134 5.63E+08 9.23E+08 1.95E+08 0.00E+00 2.86E+08 1.03E+08 4.93E+06 Cs-136 1.01E+07 2.78E+07 1.80E+07 0.00E+00 1.48E+07 2.21E+06 9.78E+05 Cs-137 8.51E+08 8.15E+08 1.20E+08 0.00E+00 2.65E+08 9.55E+07 5.10E+06 Ba-140 2.80E+07 2.45E+04 1.63E+06 0.00E+00 7.97E+03 1.46E+04 1.42E+07 La-140 1.14E-32 3.98E-33 1.34E-33 0.00E+00 0.00E+00 0.00E+00 1.11E-28 Ce-141 1.33E+04 6.64E+03 9.86E+02 0.00E+00 2.91E+03 0.00E+00 8.28E+06 Ce-144 1.39E+06 4.36E+05 7.42E+04 0.00E+00 2.41E+05 0.00E+00 1.14E+08 Pr-143 2.12E+04 6.37E+03 1.05E+03 0.00E+00 3.45E+03 0.00E+00 2.29E+07 Nd-147 7.56E+03 6.12E+03 4.74E+02 0.00E+00 3.36E+03 0.00E+00 9.70E+06 Hf-181 2.00E+07 7.79E+04 2.02E+06 6.56E+04 6.26E+04 0.00E+00 3.31E+08 Np-239 9.26E-23 6.65E-24 4.67E-24 0.00E+00 1.92E-23 0.00E+00 4.92E-19 3 -2

R Values in units of mrem/yr per Ci/m for inhalation and tritium and in units of mrem/yr per Ci/sec per m for all others.

3-40 Page 9-86

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-8 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Cow Milk AGE GROUP = Adult Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi H-3 0.00E+00 7.69E+02 7.69E+02 7.69E+02 7.69E+02 7.69E+02 7.69E+02 P-32 1.12E+10 6.95E+08 4.32E+08 0.00E+00 0.00E+00 0.00E+00 1.26E+09 Cr-51 0.00E+00 0.00E+00 1.73E+04 1.04E+04 3.82E+03 2.30E+04 4.36E+06 Mn-54 0.00E+00 5.11E+06 9.76E+05 0.00E+00 1.52E+06 0.00E+00 1.57E+07 Fe-55 1.57E+07 1.08E+07 2.52E+06 0.00E+00 0.00E+00 6.04E+06 6.21E+06 Fe-59 1.77E+07 4.17E+07 1.60E+07 0.00E+00 0.00E+00 1.17E+07 1.39E+08 Co-57 0.00E+00 7.91E+05 1.32E+06 0.00E+00 0.00E+00 0.00E+00 2.01E+07 Co-58 0.00E+00 2.80E+06 6.28E+06 0.00E+00 0.00E+00 0.00E+00 5.68E+07 Co-60 0.00E+00 1.02E+07 2.24E+07 0.00E+00 0.00E+00 0.00E+00 1.91E+08 Ni-63 4.70E+09 3.25E+08 1.57E+08 0.00E+00 0.00E+00 0.00E+00 6.79E+07 Zn-65 9.59E+08 3.05E+09 1.38E+09 0.00E+00 2.04E+09 0.00E+00 1.92E+09 Br-82 0.00E+00 0.00E+00 2.09E-29 0.00E+00 0.00E+00 0.00E+00 2.39E-29 Rb-86 0.00E+00 1.62E+09 7.54E+08 0.00E+00 0.00E+00 0.00E+00 3.19E+08 Sr-89 8.70E+08 0.00E+00 2.50E+07 0.00E+00 0.00E+00 0.00E+00 1.40E+08 Sr-90 3.09E+10 0.00E+00 7.59E+09 0.00E+00 0.00E+00 0.00E+00 8.94E+08 Y-90 1.44E-18 0.00E+00 3.86E-20 0.00E+00 0.00E+00 0.00E+00 1.53E-14 Y-91 5.11E+03 0.00E+00 1.37E+02 0.00E+00 0.00E+00 0.00E+00 2.81E+06 Zr-95 5.62E+02 1.80E+02 1.22E+02 0.00E+00 2.83E+02 0.00E+00 5.71E+05 Nb-95 4.95E+04 2.75E+04 1.48E+04 0.00E+00 2.72E+04 0.00E+00 1.67E+08 Nb-97 1.09E-08 2.75E-09 1.00E-09 0.00E+00 3.21E-09 0.00E+00 1.01E-05 Mo-99 0.00E+00 1.83E-12 3.49E-13 0.00E+00 4.15E-12 0.00E+00 4.25E-12 Ru-103 6.11E+02 0.00E+00 2.63E+02 0.00E+00 2.33E+03 0.00E+00 7.14E+04 Ru-106 1.26E+04 0.00E+00 1.60E+03 0.00E+00 2.44E+04 0.00E+00 8.17E+05 Ag-110M 3.71E+07 3.44E+07 2.04E+07 0.00E+00 6.76E+07 0.00E+00 1.40E+10 Sn-113 1.40E+06 5.41E+04 1.32E+06 1.90E+04 3.95E+04 0.00E+00 2.44E+07 Sb-124 1.55E+07 2.92E+05 6.14E+06 3.75E+04 0.00E+00 1.20E+07 4.39E+08 Sb-125 1.30E+07 1.45E+05 3.09E+06 1.32E+04 0.00E+00 1.00E+07 1.43E+08 Te-125M 1.10E+07 3.99E+06 1.48E+06 3.31E+06 4.48E+07 0.00E+00 4.40E+07 Te-127m 3.37E+07 1.21E+07 4.11E+06 8.62E+06 1.37E+08 0.00E+00 1.13E+08 Te-129M 3.91E+07 1.46E+07 6.19E+06 1.34E+07 1.63E+08 0.00E+00 1.97E+08 Te-132 2.06E-10 1.33E-10 1.25E-10 1.47E-10 1.28E-09 0.00E+00 6.29E-09 I-131 1.94E+08 2.77E+08 1.59E+08 9.09E+10 4.76E+08 0.00E+00 7.32E+07 I-132 1.10E+01 2.93E+01 1.03E+01 1.03E+01 4.67E+01 0.00E+00 5.51E-02 I-133 2.64E+06 4.59E+06 1.40E+06 6.75E+08 8.01E+06 0.00E+00 4.13E+06 I-135 9.34E+03 2.45E+04 9.03E+03 1.61E+06 3.92E+04 0.00E+00 2.76E+04 3 -2

R Values in units of mrem/yr per Ci/m for inhalation and tritium and in units of mrem/yr per Ci/sec per m for all others.

3-41 Page 9-87

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-8 (continue)

R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Cow Milk AGE GROUP = Adult Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi Cs-134 3.45E+09 3.21E+09 6.71E+09 0.00E+00 2.66E+09 8.82E+08 1.44E+08 Cs-136 1.66E+08 6.57E+08 4.73E+08 0.00E+00 3.65E+08 5.01E+07 7.46E+07 Cs-137 4.71E+09 6.44E+09 4.22E+09 0.00E+00 2.19E+09 7.27E+08 1.25E+08 Ba-140 1.71E+07 2.15E+04 1.12E+06 0.00E+00 7.32E+03 1.23E+04 3.53E+07 La-140 7.56E-32 3.81E-32 1.01E-32 0.00E+00 0.00E+00 0.00E+00 2.80E-27 Ce-141 2.91E+03 1.97E+03 2.23E+02 0.00E+00 9.14E+02 0.00E+00 7.52E+06 Ce-144 2.15E+05 8.97E+04 1.15E+04 0.00E+00 5.32E+04 0.00E+00 7.26E+07 Pr-143 1.00E+02 4.02E+01 4.97E+00 0.00E+00 2.32E+01 0.00E+00 4.39E+05 Nd-147 6.08E+01 7.02E+01 4.20E+00 0.00E+00 4.10E+01 0.00E+00 3.37E+05 Hf-181 5.91E+03 3.33E+01 6.68E+02 2.12E+01 2.79E+01 0.00E+00 4.38E+05 Np-239 1.34E-22 1.32E-23 7.28E-24 0.00E+00 4.12E-23 0.00E+00 2.71E-18

R Values in units of mrem/yr per Ci/m3 for inhalation and tritium and in units of mrem/yr per Ci/sec per m-2 for all others.

3-42 Page 9-88

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-9 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Cow Milk AGE GROUP = Teen Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi H-3 0.00E+00 1.00E+03 1.00E+03 1.00E+03 1.00E+03 1.00E+03 1.00E+03 P-32 2.06E+10 1.28E+09 8.00E+08 0.00E+00 0.00E+00 0.00E+00 1.73E+09 Cr-51 0.00E+00 0.00E+00 3.02E+04 1.68E+04 6.63E+03 4.32E+04 5.08E+06 Mn-54 0.00E+00 8.52E+06 1.69E+06 0.00E+00 2.54E+06 0.00E+00 1.75E+07 Fe-55 2.78E+07 1.97E+07 4.59E+06 0.00E+00 0.00E+00 1.25E+07 8.53E+06 Fe-59 3.10E+07 7.23E+07 2.79E+07 0.00E+00 0.00E+00 2.28E+07 1.71E+08 Co-57 0.00E+00 1.39E+06 2.33E+06 0.00E+00 0.00E+00 0.00E+00 2.59E+07 Co-58 0.00E+00 4.72E+06 1.09E+07 0.00E+00 0.00E+00 0.00E+00 6.50E+07 Co-60 0.00E+00 1.72E+07 3.88E+07 0.00E+00 0.00E+00 0.00E+00 2.25E+08 Ni-63 8.25E+09 5.83E+08 2.80E+08 0.00E+00 0.00E+00 0.00E+00 9.27E+07 Zn-65 1.47E+09 5.11E+09 2.38E+09 0.00E+00 3.27E+09 0.00E+00 2.16E+09 Br-82 0.00E+00 0.00E+00 3.62E-29 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 2.95E+09 1.39E+09 0.00E+00 0.00E+00 0.00E+00 4.37E+08 Sr-89 1.60E+09 0.00E+00 4.59E+07 0.00E+00 0.00E+00 0.00E+00 1.91E+08 Sr-90 4.37E+10 0.00E+00 1.08E+10 0.00E+00 0.00E+00 0.00E+00 1.23E+09 Y-90 2.64E-18 0.00E+00 7.12E-20 0.00E+00 0.00E+00 0.00E+00 2.18E-14 Y-91 9.40E+03 0.00E+00 2.52E+02 0.00E+00 0.00E+00 0.00E+00 3.85E+06 Zr-95 9.83E+02 3.10E+02 2.13E+02 0.00E+00 4.56E+02 0.00E+00 7.16E+05 Nb-95 8.45E+04 4.68E+04 2.58E+04 0.00E+00 4.54E+04 0.00E+00 2.00E+08 Nb-97 1.97E-08 4.92E-09 1.80E-09 0.00E+00 5.75E-09 0.00E+00 1.17E-04 Mo-99 0.00E+00 3.31E-12 6.31E-13 0.00E+00 7.57E-12 0.00E+00 5.92E-12 Ru-103 1.09E+03 0.00E+00 4.65E+02 0.00E+00 3.83E+03 0.00E+00 9.08E+04 Ru-106 2.32E+04 0.00E+00 2.93E+03 0.00E+00 4.48E+04 0.00E+00 1.11E+06 Ag-110M 6.14E+07 5.81E+07 3.53E+07 0.00E+00 1.11E+08 0.00E+00 1.63E+10 Sn-113 2.15E+06 9.06E+04 2.28E+06 2.97E+04 6.37E+04 0.00E+00 2.58E+07 Sb-124 2.76E+07 5.08E+05 1.08E+07 6.26E+04 0.00E+00 2.41E+07 5.56E+08 Sb-125 2.32E+07 2.53E+05 5.42E+06 2.22E+04 0.00E+00 2.04E+07 1.80E+08 Te-125M 2.03E+07 7.32E+06 2.72E+06 5.68E+06 0.00E+00 0.00E+00 5.99E+07 Te-127m 6.22E+07 2.21E+07 7.39E+06 1.48E+07 2.52E+08 0.00E+00 1.55E+08 Te-129M 7.15E+07 2.65E+07 1.13E+07 2.31E+07 2.99E+08 0.00E+00 2.69E+08 Te-132 3.68E-10 2.33E-10 2.19E-10 2.45E-10 2.23E-09 0.00E+00 7.37E-09 I-131 3.52E+08 4.93E+08 2.65E+08 1.44E+11 8.48E+08 0.00E+00 9.75E+07 I-132 1.94E+01 5.09E+01 1.83E+01 1.71E+01 8.02E+01 0.00E+00 2.22E+01 I-133 4.82E+06 8.18E+06 2.49E+06 1.14E+09 1.43E+07 0.00E+00 6.19E+06 I-135 1.66E+04 4.27E+04 1.58E+04 2.75E+06 6.75E+04 0.00E+00 4.74E+04

R Values in units of mrem/yr per Ci/m3 for inhalation and tritium and in units of mrem/yr per Ci/sec per m-2 for all others.

3-43 Page 9-89

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-9 (continue)

R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Cow Milk AGE GROUP = Teen Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi Cs-134 5.99E+09 1.41E+10 6.54E+09 0.00E+00 4.48E+09 1.71E+09 1.75E+08 Cs-136 2.83E+08 1.11E+09 7.48E+08 0.00E+00 6.07E+08 9.56E+07 8.97E+07 Cs-137 8.54E+09 1.14E+10 3.96E+09 0.00E+00 3.87E+09 1.50E+09 1.62E+08 Ba-140 3.09E+07 3.79E+04 1.99E+06 0.00E+00 1.28E+04 2.55E+04 4.77E+07 La-140 1.36E-31 6.68E-32 1.78E-32 0.00E+00 0.00E+00 0.00E+00 3.83E-27 Ce-141 5.33E+03 3.56E+03 4.09E+02 0.00E+00 1.68E+03 0.00E+00 1.02E+07 Ce-144 3.95E+05 1.63E+05 2.12E+04 0.00E+00 9.76E+04 0.00E+00 9.93E+07 Pr-143 1.84E+02 7.36E+01 9.17E+00 0.00E+00 4.28E+01 0.00E+00 6.06E+05 Nd-147 1.17E+02 1.27E+02 7.61E+00 0.00E+00 7.47E+01 0.00E+00 4.59E+05 Hf-181 1.06E+04 5.82E+01 1.18E+03 3.55E+01 4.84E+01 0.00E+00 5.28E+05 Np-239 2.56E-22 2.42E-23 1.34E-23 0.00E+00 7.59E-23 0.00E+00 3.89E-18

R Values in units of mrem/yr per Ci/m3 for inhalation and tritium and in units of mrem/yr per Ci/sec per m-2 for all others.

3-44 Page 9-90

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-10 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Cow Milk AGE GROUP = Child Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi H-3 0.00E+00 1.58E+03 1.58E+03 1.58E+03 1.58E+03 1.58E+03 1.58E+03 P-32 5.09E+10 2.38E+09 1.96E+09 0.00E+00 0.00E+00 0.00E+00 1.41E+09 Cr-51 0.00E+00 0.00E+00 6.17E+04 3.42E+04 9.36E+03 6.25E+04 3.27E+06 Mn-54 0.00E+00 1.27E+07 3.39E+06 0.00E+00 3.57E+06 0.00E+00 1.07E+07 Fe-55 6.97E+07 3.70E+07 1.15E+07 0.00E+00 0.00E+00 2.09E+07 6.85E+06 Fe-59 7.18E+07 1.16E+08 5.79E+07 0.00E+00 0.00E+00 3.37E+07 1.21E+08 Co-57 0.00E+00 2.37E+06 4.80E+06 0.00E+00 0.00E+00 0.00E+00 1.94E+07 Co-58 0.00E+00 7.21E+06 2.21E+07 0.00E+00 0.00E+00 0.00E+00 4.20E+07 Co-60 0.00E+00 2.68E+07 7.90E+07 0.00E+00 0.00E+00 0.00E+00 1.48E+08 Ni-63 2.07E+10 1.11E+09 7.04E+08 0.00E+00 0.00E+00 0.00E+00 7.46E+07 Zn-65 2.89E+09 7.70E+09 4.79E+09 0.00E+00 4.85E+09 0.00E+00 1.35E+09 Br-82 0.00E+00 0.00E+00 7.42E-29 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 5.47E+09 3.36E+09 0.00E+00 0.00E+00 0.00E+00 3.52E+08 Sr-89 3.97E+09 0.00E+00 1.13E+08 0.00E+00 0.00E+00 0.00E+00 1.54E+08 Sr-90 7.38E+10 0.00E+00 1.87E+10 0.00E+00 0.00E+00 0.00E+00 9.95E+08 Y-90 6.54E-18 0.00E+00 1.75E-19 0.00E+00 0.00E+00 0.00E+00 1.86E-14 Y-91 2.32E+04 0.00E+00 6.21E+02 0.00E+00 0.00E+00 0.00E+00 3.09E+06 Zr-95 2.28E+03 5.02E+02 4.47E+02 0.00E+00 7.18E+02 0.00E+00 5.23E+05 Nb-95 1.91E+05 7.42E+04 5.31E+04 0.00E+00 6.98E+04 0.00E+00 1.37E+08 Nb-97 4.81E-08 8.70E-09 4.06E-09 0.00E+00 9.65E-09 0.00E+00 2.68E-03 Mo-99 0.00E+00 6.02E-12 1.49E-12 0.00E+00 1.29E-11 0.00E+00 4.98E-12 Ru-103 2.57E+03 0.00E+00 9.88E+02 0.00E+00 6.47E+03 0.00E+00 6.65E+04 Ru-106 5.72E+04 0.00E+00 7.14E+03 0.00E+00 7.72E+04 0.00E+00 8.90E+05 Ag-110M 1.33E+08 9.00E+07 7.19E+07 0.00E+00 1.68E+08 0.00E+00 1.07E+10 Sn-113 4.22E+05 1.36E+04 4.61E+05 5.58E+03 9.37E+03 0.00E+00 1.69E+06 Sb-124 6.53E+07 8.47E+05 2.29E+07 1.44E+05 0.00E+00 3.62E+07 4.09E+08 Sb-125 5.52E+07 4.26E+05 1.16E+07 5.11E+04 0.00E+00 3.08E+07 1.32E+08 Te-125M 4.99E+07 1.35E+07 6.65E+06 1.40E+07 0.00E+00 0.00E+00 4.81E+07 Te-127m 1.53E+08 4.13E+07 1.82E+07 3.66E+07 4.37E+08 0.00E+00 1.24E+08 Te-129M 1.76E+08 4.92E+07 2.74E+07 5.68E+07 5.18E+08 0.00E+00 2.15E+08 Te-132 8.78E-10 3.88E-10 4.69E-10 5.66E-10 3.61E-09 0.00E+00 3.91E-09 I-131 8.54E+08 8.59E+08 4.88E+08 2.84E+11 1.41E+09 0.00E+00 7.64E+07 I-132 4.60E+01 8.45E+01 3.89E+01 3.92E+01 1.29E+00 0.00E+00 9.95E+01 I-133 1.17E+07 1.45E+07 5.48E+06 2.69E+09 2.41E+07 0.00E+00 5.84E+06 I-135 3.93E+04 7.07E+04 3.35E+04 6.26E+06 1.08E+05 0.00E+00 5.39E+04

R Values in units of mrem/yr per Ci/m3 for inhalation and tritium and in units of mrem/yr per Ci/sec per m-2 for all others.

3-45 Page 9-91

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-10 (continue)

R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Cow Milk AGE GROUP = Child Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi Cs-134 1.38E+10 2.27E+10 4.78E+09 0.00E+00 7.03E+09 2.52E+09 1.22E+08 Cs-136 6.39E+08 1.76E+09 1.14E+09 0.00E+00 9.36E+08 1.40E+08 6.17E+07 Cs-137 2.06E+10 1.97E+10 2.91E+09 0.00E+00 6.42E+09 2.31E+09 1.23E+08 Ba-140 7.47E+07 6.54E+04 4.36E+06 0.00E+00 2.13E+04 3.90E+04 3.78E+07 La-140 3.25E-31 1.14E-31 3.83E-32 0.00E+00 0.00E+00 0.00E+00 3.17E-27 Ce-141 1.31E+04 6.55E+03 9.73E+02 0.00E+00 2.87E+03 0.00E+00 8.17E+06 Ce-144 9.74E+05 3.05E+05 5.20E+04 0.00E+00 1.69E+05 0.00E+00 7.96E+07 Pr-143 4.56E+02 1.37E+02 2.26E+01 0.00E+00 7.42E+01 0.00E+00 4.92E+05 Nd-147 2.87E+02 2.32E+02 1.80E+01 0.00E+00 1.27E+02 0.00E+00 3.68E+05 Hf-181 2.51E+04 9.79E+01 2.53E+03 8.24E+01 7.86E+01 0.00E+00 4.16E+05 Np-239 6.31E-22 4.53E-23 3.18E-23 0.00E+00 1.31E-22 0.00E+00 3.35E-18 3 -2

R Values in units of mrem/yr per Ci/m for inhalation and tritium and in units of mrem/yr per Ci/sec per m for all others.

3-46 Page 9-92

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-11 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Cow Milk AGE GROUP = Infant Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi H-3 0.00E+00 2.40E+03 2.40E+03 2.40E+03 2.40E+03 2.40E+03 2.40E+03 P-32 1.05E+11 6.17E+09 4.06E+09 0.00E+00 0.00E+00 0.00E+00 1.42E+09 Cr-51 0.00E+00 0.00E+00 9.77E+04 6.38E+04 1.39E+04 1.24E+05 2.85E+06 Mn-54 0.00E+00 2.37E+07 5.37E+06 0.00E+00 5.25E+06 0.00E+00 8.71E+06 Fe-55 8.43E+07 5.45E+07 1.46E+07 0.00E+00 0.00E+00 2.66E+07 6.91E+06 Fe-59 1.34E+08 2.34E+08 9.23E+07 0.00E+00 0.00E+00 6.92E+07 1.12E+08 Co-57 0.00E+00 5.53E+06 9.00E+06 0.00E+00 0.00E+00 0.00E+00 1.89E+07 Co-58 0.00E+00 1.44E+07 3.60E+07 0.00E+00 0.00E+00 0.00E+00 3.59E+07 Co-60 0.00E+00 5.47E+07 1.29E+08 0.00E+00 0.00E+00 0.00E+00 1.30E+08 Ni-63 2.44E+10 1.51E+09 8.46E+08 0.00E+00 0.00E+00 0.00E+00 7.50E+07 Zn-65 3.88E+09 1.33E+10 6.14E+09 0.00E+00 6.45E+09 0.00E+00 1.12E+10 Br-82 0.00E+00 0.00E+00 1.25E-28 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.39E+10 6.86E+09 0.00E+00 0.00E+00 0.00E+00 3.55E+08 Sr-89 7.55E+09 0.00E+00 2.17E+08 0.00E+00 0.00E+00 0.00E+00 1.55E+08 Sr-90 8.04E+10 0.00E+00 2.05E+10 0.00E+00 0.00E+00 0.00E+00 1.00E+09 Y-90 1.38E-17 0.00E+00 3.71E-19 0.00E+00 0.00E+00 0.00E+00 1.91E-14 Y-91 4.36E+04 0.00E+00 1.17E+03 0.00E+00 0.00E+00 0.00E+00 3.12E+06 Zr-95 4.05E+03 9.88E+02 7.01E+02 0.00E+00 1.06E+03 0.00E+00 4.92E+05 Nb-95 3.56E+05 1.47E+05 8.48E+04 0.00E+00 1.05E+05 0.00E+00 1.24E+08 Nb-97 1.02E-07 2.17E-08 7.83E-09 0.00E+00 1.70E-08 0.00E+00 6.85E-03 Mo-99 0.00E+00 1.54E-11 3.00E-12 0.00E+00 2.30E-11 0.00E+00 5.07E-12 Ru-103 5.21E+03 0.00E+00 1.74E+03 0.00E+00 1.08E+04 0.00E+00 6.33E+04 Ru-106 1.18E+05 0.00E+00 1.47E+04 0.00E+00 1.39E+05 0.00E+00 8.95E+05 Ag-110M 2.46E+08 1.80E+08 1.19E+08 0.00E+00 2.57E+08 0.00E+00 9.32E+09 Sn-113 6.45E+06 2.45E+05 6.65E+06 9.34E+04 1.31E+05 0.00E+00 1.37E+07 Sb-124 1.26E+08 1.85E+06 3.90E+07 3.34E+05 0.00E+00 7.88E+07 3.88E+08 Sb-125 9.49E+07 9.18E+05 1.95E+07 1.19E+05 0.00E+00 5.95E+07 1.26E+08 Te-125M 1.02E+08 3.41E+07 1.38E+07 3.43E+07 0.00E+00 0.00E+00 4.86E+07 Te-127m 3.10E+08 1.03E+08 3.75E+07 8.96E+07 7.64E+08 0.00E+00 1.25E+08 Te-129M 3.62E+08 1.24E+08 5.57E+07 1.39E+08 9.05E+08 0.00E+00 2.16E+08 Te-132 1.81E-09 8.95E-10 8.35E-10 1.32E-09 5.60E-09 0.00E+00 3.31E-09 I-131 1.78E+09 2.10E+09 9.23E+08 6.90E+11 2.45E+09 0.00E+00 7.49E+07 I-132 9.55E+01 1.94E+00 6.90E+01 9.09E+01 2.16E+00 0.00E+00 1.57E+00 I-133 2.47E+07 3.60E+07 1.05E+07 6.55E+09 4.23E+07 0.00E+00 6.09E+06 I-135 8.17E+04 1.63E+05 5.93E+04 1.46E+07 1.81E+05 0.00E+00 5.88E+04 3 -2

R Values in units of mrem/yr per Ci/m for inhalation and tritium and in units of mrem/yr per Ci/sec per m for all others.

3-47 Page 9-93

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-11 (continue)

R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Cow Milk AGE GROUP = Infant Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi Cs-134 2.23E+10 4.15E+10 4.19E+09 0.00E+00 1.07E+10 4.38E+09 1.13E+08 Cs-136 1.25E+09 3.67E+09 1.37E+09 0.00E+00 1.46E+09 2.99E+08 5.58E+07 Cs-137 3.28E+10 3.84E+10 2.72E+09 0.00E+00 1.03E+10 4.18E+09 1.20E+08 Ba-140 1.54E+08 1.54E+05 7.91E+06 0.00E+00 3.65E+04 9.43E+04 3.77E+07 La-140 6.80E-31 2.68E-31 6.89E-32 0.00E+00 0.00E+00 0.00E+00 3.15E-27 Ce-141 2.60E+04 1.59E+04 1.87E+03 0.00E+00 4.90E+03 0.00E+00 8.21E+06 Ce-144 1.40E+06 5.71E+05 7.82E+04 0.00E+00 2.31E+05 0.00E+00 8.01E+07 Pr-143 9.44E+02 3.53E+02 4.68E+01 0.00E+00 1.31E+02 0.00E+00 4.98E+05 Nd-147 5.69E+02 5.84E+02 3.58E+01 0.00E+00 2.25E+02 0.00E+00 3.70E+05 Hf-181 4.78E+04 2.26E+02 4.23E+03 1.91E+02 1.32E+02 0.00E+00 3.93E+05 Np-239 1.33E-21 1.19E-22 6.74E-23 0.00E+00 2.38E-22 0.00E+00 3.45E-18

R Values in units of mrem/yr per Ci/m3 for inhalation and tritium and in units of mrem/yr per Ci/sec per m-2 for all others.

3-48 Page 9-94

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-12 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Goat Milk AGE GROUP = Adult Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 1.57E+03 1.57E+03 0.00E+01 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 P-32 5.19E+08 1.51E+09 1.34E+10 8.34E+08 0.00E+01 0.00E+01 0.00E+01 0.00E+01 Cr-51 2.08E+03 5.23E+05 0.00E+01 0.00E+01 4.58E+02 1.24E+03 2.76E+03 0.00E+01 Mn-54 1.17E+05 1.88E+06 0.00E+01 6.14E+05 1.83E+05 0.00E+01 0.00E+01 0.00E+01 Fe-59 2.08E+05 1.81E+06 2.31E+05 5.42E+05 0.00E+01 0.00E+01 1.51E+05 0.00E+01 Co-58 7.54E+05 6.82E+06 0.00E+01 3.36E+05 0.00E+01 0.00E+01 0.00E+01 0.00E+01 Co-60 2.69E+06 2.29E+07 0.00E+01 1.22E+06 0.00E+01 0.00E+01 0.00E+01 0.00E+01 Zn-65 1.65E+08 2.31E+08 1.15E+08 3.66E+08 2.45E+08 0.00E+01 0.00E+01 0.00E+01 Rb-86 9.05E+07 3.83E+07 0.00E+01 1.94E+08 0.00E+01 0.00E+01 0.00E+01 0.00E+01 Sr-89 5.24E+07 2.93E+08 1.83E+09 0.00E+01 0.00E+01 0.00E+01 0.00E+01 0.00E+01 Sr-90 1.59E+10 1.88E+09 6.49E+10 0.00E+01 0.00E+01 0.00E+01 0.00E+01 0.00E+01 Y-91 1.64E+01 3.37E+05 6.13E+02 0.00E+01 0.00E+01 0.00E+01 0.00E+01 0.00E+01 Zr-95 1.46E+01 6.85E+04 6.74E+01 2.16E+01 3.39E+01 0.00E+01 0.00E+01 0.00E+01 Nb-95 1.78E+03 2.01E+07 5.94E+03 3.31E+03 3.27E+03 0.00E+01 0.00E+01 0.00E+01 Ru-103 3.16E+01 8.56E+03 7.33E+01 0.00E+01 2.80E+02 0.00E+01 0.00E+01 0.00E+01 Ru-106 1.92E+02 9.81E+04 1.52E+03 0.00E+01 2.93E+03 0.00E+01 0.00E+01 0.00E+01 Ag-11OM 2.45E+06 1.68E+09 4.46E+06 4.12E+06 8.11E+06 0.00E+01 0.00E+01 0.00E+01 Sn-113 1.32E+05 2.44E+06 1.40E+05 5.41E+03 3.96E+03 1.90E+03 0.00E+01 0.00E+01 Sb-124 7.36E+05 5.27E+07 1.86E+06 3.51E+04 0.00E+01 4.50E+03 1.44E+06 0.00E+01 Te-127M 4.93E+05 1.36E+07 4.05E+06 1.45E+06 1.64E+07 1.03E+06 0.00E+01 0.00E+01 Te-129M 7.43E+05 2.36E+07 4.69E+06 1.75E+06 1.96E+07 1.61E+06 0.00E+01 0.00E+01 I-131 1.91E+08 8.78E+07 2.33E+08 3.33E+08 5.71E+08 1.09E+11 0.00E+01 0.00E+01 I-132 1.23E+01 6.61E-02 1.32E+01 3.52E+01 5.61E+01 1.23E+01 0.00E+01 0.00E+01 I-133 1.68E+06 4.95E+06 3.17E+06 5.51E+06 9.61E+06 8.10E+08 0.00E+01 0.00E+01 I-135 1.08E+04 3.32E+04 1.12E+04 2.94E+04 4.71E+04 1.94E+06 0.00E+01 0.00E+01 Cs-134 2.01E+10 4.31E+08 1.03E+10 2.46E+10 7.97E+09 0.00E+01 2.65E+09 0.00E+01 Cs-136 1.42E+09 2.24E+08 4.99E+08 1.97E+09 1.10E+09 0.00E+01 1.50E+08 0.00E+01 Cs-137 1.27E+10 3.74E+08 1.41E+10 1.93E+10 6.56E+09 0.00E+01 2.18E+09 0.00E+01 Ba-140 1.35E+05 4.23E+06 2.06E+06 2.58E+03 8.78E+02 0.00E+01 1.48E+03 0.00E+01 Ce-141 2.68E+01 9.03E+05 3.49E+02 2.36E+02 1.10E+02 0.00E+01 0.00E+01 0.00E+01 Ce-144 1.38E+03 8.71E+06 2.58E+04 1.08E+04 6.39E+03 0.00E+01 0.00E+01 0.00E+01 Hf-181 8.02E+01 5.26E+04 7.09E+02 3.99E+00 3.34E+00 2.54E+00 0.00E+01 0.00E+01 R Values in units of mrem/yr per Ci/m3 for inhalation and tritium and in units of mrem/yr per Ci/sec per m-2 for all others.

3-49 Page 9-95

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-13 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Goat Milk AGE GROUP = Teen Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 2.04E+03 2.04E+03 0.00E+01 2.04E+03 2.04E+03 2.04E+03 2.04E+03 2.04E+03 P-32 9.60E+08 2.08E+09 2.48E+10 1.53E+09 0.00E+01 0.00E+01 0.00E+01 0.00E+01 Cr-51 3.63E+03 6.10E+05 0.00E+01 0.00E+01 7.95E+02 2.02E+03 5.18E+03 0.00E+01 Mn-54 2.03E+05 2.10E+06 0.00E+01 1.02E+06 3.05E+05 0.00E+01 0.00E+01 0.00E+01 Fe-59 3.63E+05 2.22E+06 4.03E+05 9.40E+05 0.00E+01 0.00E+01 2.96E+05 0.00E+01 Co-58 1.30E+06 7.80E+06 0.00E+01 5.66E+05 0.00E+01 0.00E+01 0.00E+01 0.00E+01 Co-60 4.66E+06 2.69E+07 0.00E+01 2.07E+06 0.00E+01 0.00E+01 0.00E+01 0.00E+01 Zn-65 2.86E+08 2.60E+08 1.77E+08 6.13E+08 3.93E+08 0.00E+01 0.00E+01 0.00E+01 Rb-86 1.66E+08 5.24E+07 0.00E+01 3.54E+08 0.00E+01 0.00E+01 0.00E+01 0.00E+01 Sr-89 9.65E+07 4.01E+08 3.37E+09 0.00E+01 0.00E+01 0.00E+01 0.00E+01 0.00E+01 Sr-90 2.27E+10 2.58E+09 9.18E+10 0.00E+01 0.00E+01 0.00E+01 0.00E+01 0.00E+01 Y-91 3.02E+01 4.62E+05 1.13E+03 0.00E+01 0.00E+01 0.00E+01 0.00E+01 0.00E+01 Zr-95 2.56E+01 8.59E+04 1.18E+02 3.72E+01 5.47E+01 0.00E+01 0.00E+01 0.00E+01 Nb-95 3.09E+03 2.40E+07 1.01E+04 5.62E+03 5.45E+03 0.00E+01 0.00E+01 0.00E+01 Ru-103 5.58E+01 1.09E+04 1.30E+02 0.00E+01 4.60E+02 0.00E+01 0.00E+01 0.00E+01 Ru-106 3.51E+02 1.34E+05 2.79E+03 0.00E+01 5.38E+03 0.00E+01 0.00E+01 0.00E+01 Ag-11OM 4.24E+06 1.96E+09 7.37E+06 6.97E+06 1.33E+07 0.00E+01 0.00E+01 0.00E+01 Sn-113 2.28E+05 2.58E+06 2.15E+05 9.06E+03 6.37E+03 2.97E+03 0.00E+01 0.00E+01 Sb-124 1.29E+06 6.67E+07 3.31E+06 6.10E+04 0.00E+01 7.51E+03 2.89E+06 0.00E+01 Te-127M 8.87E+05 1.86E+07 7.46E+06 2.65E+06 3.02E+07 1.77E+06 0.00E+01 0.00E+01 Te-129M 1.36E+06 3.22E+07 8.58E+06 3.19E+06 3.59E+07 2.77E+06 0.00E+01 0.00E+01 I-131 3.18E+08 1.17E+08 4.22E+08 5.91E+08 1.02E+09 1.73E+11 0.00E+01 0.00E+01 I-132 2.19E+01 2.66E+01 2.33E+01 6.11E+01 9.62E+01 2.06E+01 0.00E+01 0.00E+01 I-133 2.99E+06 7.43E+06 5.79E+06 9.81E+06 1.72E+07 1.37E+09 0.00E+01 0.00E+01 I-135 1.90E+04 5.63E+04 1.99E+04 5.13E+04 8.10E+04 3.30E+06 0.00E+01 0.00E+01 Cs-134 1.96E+10 5.26E+08 1.80E+10 4.23E+10 1.34E+10 0.00E+01 5.13E+09 0.00E+01 Cs-136 2.25E+09 2.69E+07 8.50E+08 3.34E+09 1.82E+09 0.00E+01 2.87E+08 0.00E+01 Cs-137 1.19E+10 4.85E+08 2.56E+10 3.41E+10 1.16E+10 0.00E+01 4.51E+09 0.00E+01 Ba-140 2.39E+05 5.72E+06 3.71E+06 4.55E+03 1.54E+03 0.00E+01 3.06E+03 0.00E+01 Ce-141 4.91E+01 1.22E+06 6.40E+02 4.27E+02 2.01E+02 0.00E+01 0.00E+01 0.00E+01 Ce-144 2.55E+03 1.19E+07 4.74E+04 1.96E+04 1.17E+04 0.00E+01 0.00E+01 0.00E+01 Hf-181 1.41E+02 6.34E+04 1.27E+03 6.97E+00 5.80E+00 4.26E+00 0.00E+01 0.00E+01

R Values in units of mrem/yr per Ci/m3 for inhalation and tritium and in units of mrem/yr per Ci/sec per m-2 for all others.

3-50 Page 9-96

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-14 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Goat Milk AGE GROUP = Child Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 3.23E+03 3.23E+03 0.00E+01 3.23E+03 3.23E+03 3.23E+03 3.23E+03 3.23E+03 P-32 2.35E+09 1.69E+09 6.11E+10 2.86E+09 0.00E+01 0.00E+01 0.00E+01 0.00E+01 Cr-51 7.40E+03 3.93E+05 0.00E+01 0.00E+01 1.12E+03 4.11E+03 7.50E+03 0.00E+01 Mn-54 4.07E+05 1.28E+06 0.00E+01 1.53E+06 4.29E+05 0.00E+01 0.00E+01 0.00E+01 Fe-59 7.52E+05 1.57E+06 9.34E+05 1.51E+06 0.00E+01 0.00E+01 4.38E+05 0.00E+01 Co-58 2.65E+06 5.05E+06 0.00E+01 8.65E+05 0.00E+01 0.00E+01 0.00E+01 0.00E+01 Co-60 9.48E+06 1.78E+07 0.00E+01 3.21E+06 0.00E+01 0.00E+01 0.00E+01 0.00E+01 Zn-65 5.74E+08 1.62E+08 3.47E+08 9.24E+08 5.82E+08 0.00E+01 0.00E+01 0.00E+01 Rb-86 4.04E+08 4.22E+07 0.00E+01 6.57E+08 0.00E+01 0.00E+01 0.00E+01 0.00E+01 Sr-89 2.38E+08 3.23E+08 8.34E+09 0.00E+01 0.00E+01 0.00E+01 0.00E+01 0.00E+01 Sr-90 3.93E+10 2.09E+09 1.55E+11 0.00E+01 0.00E+01 0.00E+01 0.00E+01 0.00E+01 Y-91 7.45E+01 3.71E+05 2.79E+03 0.00E+01 0.00E+01 0.00E+01 0.00E+01 0.00E+01 Zr-95 5.36E+01 6.28E+04 2.74E+02 6.02E+01 8.62E+01 0.00E+01 0.00E+01 0.00E+01 Nb-95 6.37E+03 1.65E+07 2.29E+04 8.91E+03 8.37E+03 0.00E+01 0.00E+01 0.00E+01 Ru-103 1.19E+02 7.98E+03 3.09E+02 0.00E+01 7.77E+02 0.00E+01 0.00E+01 0.00E+01 Ru-106 8.56E+02 1.07E+05 6.86E+03 0.00E+01 9.27E+03 0.00E+01 0.00E+01 0.00E+01 Ag-11OM 8.63E+06 1.28E+09 1.60E+07 1.08E+07 2.01E+07 0.00E+01 0.00E+01 0.00E+01 Sn-113 4.61E+05 1.69E+06 4.22E+05 1.36E+04 9.38E+03 5.59E+03 0.00E+01 0.00E+01 Sb-124 2.75E+06 4.91E+07 7.84E+06 1.02E+05 0.00E+01 1.73E+04 4.35E+06 0.00E+01 Te-127M 2.18E+06 1.49E+07 1.84E+07 4.95E+06 5.24E+07 4.40E+06 0.00E+01 0.00E+01 Te-129M 3.28E+06 2.58E+07 2.12E+07 5.91E+06 6.21E+07 6.82E+06 0.00E+01 0.00E+01 I-131 5.85E+08 9.17E+07 1.02E+09 1.03E+09 1.69E+09 3.41E+11 0.00E+01 0.00E+01 I-132 4.67E+01 1.19E+00 5.52E+01 1.01E+00 1.55E+00 4.71E+01 0.00E+01 0.00E+01 I-133 6.58E+06 7.00E+06 1.41E+07 1.74E+07 2.90E+07 3.23E+09 0.00E+01 0.00E+01 I-135 4.01E+04 6.47E+04 4.72E+04 8.49E+04 1.30E+05 7.52E+06 0.00E+01 0.00E+01 Cs-134 1.43E+10 3.67E+08 4.14E+10 6.80E+10 2.11E+10 0.00E+01 7.56E+09 0.00E+01 Cs-136 3.41E+09 1.85E+08 1.92E+09 5.27E+09 2.81E+09 0.00E+01 4.19E+08 0.00E+01 Cs-137 8.72E+09 3.70E+08 6.17E+10 5.91E+10 1.93E+10 0.00E+01 6.93E+09 0.00E+01 Ba-140 5.23E+05 4.54E+05 8.96E+06 7.85E+03 2.56E+03 0.00E+01 4.68E+03 0.00E+01 Ce-141 1.17E+02 9.81E+05 1.53E+03 7.36E+02 3.45E+02 0.00E+01 0.00E+01 0.00E+01 Ce-144 6.24E+03 9.55E+06 1.17E+05 3.66E+04 2.03E+04 0.00E+01 0.00E+01 0.00E+01 Hf-181 3.04E+02 4.99E+04 3.02E+03 1.17E+01 9.43E+00 9.88E+00 0.00E+01 0.00E+01

R Values in units of mrem/yr per Ci/m3 for inhalation and tritium and in units of mrem/yr per Ci/sec per m-2 for all others.

3-51 Page 9-97

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-15 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Goat Milk AGE GROUP = Infant Nuclide T. Body GI-Tract Bone Liver Kidney Thyroid Lung Skin H-3 4.90E+03 4.90E+03 0.00E+01 4.90E+03 4.90E+03 4.90E+03 4.90E+03 4.90E+03 P-32 4.88E+09 1.70E+09 1.26E+11 7.40E+09 0.00E+01 0.00E+01 0.00E+01 0.00E+01 Cr-51 1.17E+04 3.42E+05 0.00E+01 0.00E+01 1.67E+03 7.65E+03 1.49E+04 0.00E+01 Mn-54 6.45E+05 1.04E+06 0.00E+01 2.84E+06 6.30E+05 0.00E+01 0.00E+01 0.00E+01 Fe-59 1.20E+06 1.45E+06 1.74E+06 3.04E+06 0.00E+01 0.00E+01 9.00E+05 0.00E+01 Co-58 4.31E+06 4.31E+06 0.00E+01 1.73E+06 0.00E+01 0.00E+01 0.00E+01 0.00E+01 Co-60 1.55E+07 1.56E+07 0.00E+01 6.56E+06 0.00E+01 0.00E+01 0.00E+01 0.00E+01 Zn-65 7.36E+08 1.35E+09 4.66E+08 1.60E+09 7.74E+08 0.00E+01 0.00E+01 0.00E+01 Rb-86 8.23E+08 4.26E+07 0.00E+01 1.67E+09 0.00E+01 0.00E+01 0.00E+01 0.00E+01 Sr-89 4.55E+08 3.26E+08 1.59E+10 0.00E+01 0.00E+01 0.00E+01 0.00E+01 0.00E+01 Sr-90 4.30E+10 2.11E+09 1.69E+11 0.00E+01 0.00E+01 0.00E+01 0.00E+01 0.00E+01 Y-91 1.39E+02 3.75E+05 5.23E+03 0.00E+01 0.00E+01 0.00E+01 0.00E+01 0.00E+01 Zr-95 8.41E+01 5.90E+04 4.85E+02 1.19E+02 1.28E+02 0.00E+01 0.00E+01 0.00E+01 Nb-95 1.02E+04 1.48E+07 4.27E+04 1.76E+04 1.26E+04 0.00E+01 0.00E+01 0.00E+01 Ru-103 2.09E+02 7.60E+03 6.25E+02 0.00E+01 1.30E+03 0.00E+01 0.00E+01 0.00E+01 Ru-106 1.77E+03 1.07E+05 1.41E+04 0.00E+01 1.67E+04 0.00E+01 0.00E+01 0.00E+01 Ag-11OM 1.43E+07 1.12E+09 2.95E+07 2.16E+07 3.08E+07 0.00E+01 0.00E+01 0.00E+01 Sn-113 6.66E+05 1.37E+06 6.46E+05 2.45E+04 1.32E+04 9.34E+03 0.00E+01 0.00E+01 Sb-124 4.68E+06 4.66E+07 1.51E+07 2.22E+05 0.00E+01 4.01E+04 9.46E+06 0.00E+01 Te-127M 4.51E+06 1.50E+07 3.72E+07 1.23E+07 9.16E+07 1.08E+07 0.00E+01 0.00E+01 Te-129M 6.69E+06 2.59E+07 4.34E+07 1.49E+07 1.09E+08 1.67E+07 0.00E+01 0.00E+01 I-131 1.11E+09 8.99E+07 2.14E+09 2.52E+09 2.94E+09 8.28E+11 0.00E+01 0.00E+01 I-132 8.28E+01 1.88E+00 1.15E+00 2.33E+00 2.59E+00 1.09E+02 0.00E+01 0.00E+01 I-133 1.27E+07 7.31E+06 2.97E+07 4.32E+07 5.08E+07 7.86E+09 0.00E+01 0.00E+01 I-135 7.11E+04 7.06E+04 9.81E+04 1.95E+05 2.17E+05 1.75E+07 0.00E+01 0.00E+01 Cs-134 1.26E+10 3.38E+08 6.68E+10 1.25E+11 3.21E+10 0.00E+01 1.31E+10 0.00E+01 Cs-136 4.11E+09 1.67E+08 3.75E+09 1.10E+10 4.39E+09 0.00E+01 8.98E+08 0.00E+01 Cs-137 8.17E+09 3.61E+08 9.85E+10 1.15E+11 3.10E+10 0.00E+01 1.25E+10 0.00E+01 Ba-140 9.50E+05 4.53E+06 1.84E+07 1.84E+04 4.38E+03 0.00E+01 1.13E+04 0.00E+01 Ce-141 2.24E+02 9.85E+05 3.13E+03 1.91E+03 5.88E+02 0.00E+01 0.00E+01 0.00E+01 Ce-144 9.39E+03 9.61E+06 1.67E+05 6.86E+04 2.77E+04 0.00E+01 0.00E+01 0.00E+01 Hf-181 5.08E+02 4.72E+04 5.74E+03 2.71E+01 1.58E+01 2.30E+01 0.00E+01 0.00E+01

R Values in units of mrem/yr per Ci/m3 for inhalation and tritium and in units of mrem/yr per Ci/sec per m-2 for all others.

3-52 Page 9-98

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-16 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Inhalation AGE GROUP = Adult Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi H-3 0.00E+00 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 C-14 1.82E+04 3.41E+03 3.41E+03 3.41E+03 3.41E+03 3.41E+03 3.41E+03 Na-24 1.04E+04 1.04E+04 1.04E+04 1.04E+04 1.04E+04 1.04E+04 1.04E+04 P-32 1.32E+06 7.70E+04 5.00E+04 0.00E+00 0.00E+00 0.00E+00 8.63E+04 Cr-51 0.00E+00 0.00E+00 9.99E+01 5.94E+01 2.28E+01 1.44E+04 3.32E+03 Mn-54 0.00E+00 3.95E+04 6.29E+03 0.00E+00 9.83E+03 1.40E+06 7.72E+04 Mn-56 0.00E+00 1.26E+00 1.85E-01 0.00E+00 1.32E+00 9.56E+03 2.05E+04 Fe-55 2.49E+04 1.72E+04 3.99E+03 0.00E+00 0.00E+00 7.30E+04 6.11E+03 Fe-59 1.17E+04 2.77E+04 1.05E+04 0.00E+00 0.00E+00 1.01E+06 1.88E+05 Co-57 0.00E+00 7.01E+02 6.80E+02 0.00E+00 0.00E+00 3.74E+05 3.18E+04 Co-58 0.00E+00 1.58E+03 2.07E+03 0.00E+00 0.00E+00 9.27E+05 1.06E+05 Co-60 0.00E+00 1.15E+04 1.48E+04 0.00E+00 0.00E+00 5.96E+06 2.84E+05 Ni-63 4.37E+05 3.18E+04 1.47E+04 0.00E+00 0.00E+00 1.81E+05 1.35E+04 Ni-65 1.56E+00 2.12E-01 9.23E-02 0.00E+00 0.00E+00 5.67E+03 1.25E+04 Cu-64 0.00E+00 1.48E+00 6.23E-01 0.00E+00 4.68E+00 6.87E+03 4.96E+04 Zn-65 3.24E+04 1.03E+05 4.65E+04 0.00E+00 6.89E+04 8.63E+05 5.34E+04 Zn-69M 8.26E+00 1.98E+01 1.81E+00 0.00E+00 1.20E+01 1.93E+04 1.39E+05 Zn-69 3.43E-02 6.59E-02 4.58E-03 0.00E+00 4.27E-02 9.32E+02 1.65E+01 Br-82 0.00E+00 0.00E+00 1.37E+04 0.00E+00 0.00E+00 0.00E+00 1.05E+04 Br-83 0.00E+00 0.00E+00 2.44E+02 0.00E+00 0.00E+00 0.00E+00 2.35E+02 Br-84 0.00E+00 0.00E+00 3.17E+02 0.00E+00 0.00E+00 0.00E+00 1.66E-03 Br-85 0.00E+00 0.00E+00 1.30E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.35E+05 5.89E+04 0.00E+00 0.00E+00 0.00E+00 1.66E+04 Rb-88 0.00E+00 3.92E+02 1.95E+02 0.00E+00 0.00E+00 0.00E+00 3.39E-09 Rb-89 0.00E+00 2.59E+02 1.72E+02 0.00E+00 0.00E+00 0.00E+00 9.40E-12 Sr-89 3.04E+05 0.00E+00 8.71E+03 0.00E+00 0.00E+00 1.40E+06 3.49E+05 Sr-90 9.91E+07 0.00E+00 6.09E+06 0.00E+00 0.00E+00 9.59E+06 7.21E+05 Sr-91 6.27E+01 0.00E+00 2.54E+00 0.00E+00 0.00E+00 3.69E+04 1.94E+05 Sr-92 6.83E+00 0.00E+00 2.95E-01 0.00E+00 0.00E+00 1.67E+04 4.36E+04 Y-90 2.11E+03 0.00E+00 5.68E+01 0.00E+00 0.00E+00 1.72E+05 5.12E+05 Y-91M 2.64E-01 0.00E+00 1.03E-02 0.00E+00 0.00E+00 1.94E+03 1.34E+00 Y-91 4.62E+05 0.00E+00 1.24E+04 0.00E+00 0.00E+00 1.70E+06 3.84E+05 Y-92 1.04E+01 0.00E+00 3.05E-01 0.00E+00 0.00E+00 1.59E+04 7.44E+04 Y-93 9.56E+01 0.00E+00 2.64E+00 0.00E+00 0.00E+00 4.91E+04 4.27E+05 Zr-95 1.07E+05 3.44E+04 2.32E+04 0.00E+00 5.41E+04 1.77E+06 1.50E+05 Zr-97 9.80E+01 1.98E+01 9.15E+00 0.00E+00 3.01E+01 7.97E+04 5.30E+05 Nb-95 1.41E+04 7.80E+03 4.20E+03 0.00E+00 7.72E+03 5.04E+05 1.04E+05 Nb-97 2.25E-01 5.69E-02 2.07E-02 0.00E+00 6.63E-02 2.43E+03 2.45E+02 Mo-99 0.00E+00 1.22E+02 2.32E+01 0.00E+00 2.95E+02 9.23E+04 2.51E+05 Tc-99M 1.04E-03 2.95E-03 3.75E-02 0.00E+00 4.47E-02 7.74E+02 4.21E+03 3 -2

R Values in units of mrem/yr per Ci/m for inhalation and tritium and in units of mrem/yr per Ci/sec per m for all others.

3-53 Page 9-99

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-16 (continue)

R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Inhalation AGE GROUP = Adult Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi Tc-101 4.23E-05 6.09E-05 5.98E-04 0.00E+00 1.09E-03 4.04E+02 1.10E-11 Ru-103 1.53E+03 0.00E+00 6.57E+02 0.00E+00 5.82E+03 5.04E+05 1.10E+05 Ru-105 8.00E-01 0.00E+00 3.15E-01 0.00E+00 1.03E+00 1.11E+04 4.88E+04 Ru-106 6.90E+04 0.00E+00 8.71E+03 0.00E+00 1.33E+05 9.35E+06 9.11E+05 Ag-110M 1.08E+04 9.99E+03 5.94E+03 0.00E+00 1.97E+04 4.63E+06 3.02E+05 Sn-113 6.86E+03 2.69E+02 6.48E+03 9.33E+01 1.97E+02 2.99E+05 2.48E+04 Sb-124 3.12E+04 5.88E+02 1.24E+04 7.55E+01 0.00E+00 2.48E+06 4.06E+05 Sb-125 5.40E+04 6.03E+02 1.28E+04 5.47E+01 0.00E+00 1.77E+06 1.02E+05 Te-125M 3.46E+03 1.60E+03 4.73E+02 1.06E+03 1.26E+04 3.18E+05 7.15E+04 Te-127m 1.26E+04 5.76E+03 1.57E+03 3.28E+03 4.57E+04 9.59E+05 1.49E+05 Te-127 1.42E+00 6.50E-01 3.13E-01 1.07E+00 5.16E+00 6.59E+03 5.81E+04 Te-129M 9.75E+03 4.67E+03 1.58E+03 3.44E+03 3.65E+04 1.16E+06 3.83E+05 Te-129 5.04E-02 2.42E-02 1.26E-02 3.94E-02 1.90E-01 1.96E+03 1.59E+02 Te-131M 7.08E+01 4.41E+01 2.94E+01 5.57E+01 3.13E+02 1.47E+05 5.63E+05 Te-131 1.13E-02 6.03E-03 3.64E-03 9.48E-03 4.42E-02 1.41E+03 1.86E+01 Te-132 2.63E+02 2.18E+02 1.64E+02 1.92E+02 1.47E+03 2.92E+05 5.16E+05 I-130 4.63E+03 1.36E+04 5.35E+03 1.15E+06 2.11E+04 0.00E+00 7.78E+03 I-131 2.52E+04 3.57E+04 2.05E+04 1.19E+07 6.12E+04 0.00E+00 6.27E+03 I-132 1.16E+03 3.25E+03 1.16E+03 1.14E+05 5.18E+03 0.00E+00 4.06E+02 I-133 8.63E+03 1.48E+04 4.51E+03 2.15E+06 2.58E+04 0.00E+00 8.87E+03 I-134 6.52E+02 1.75E+03 6.23E+02 3.02E+04 2.79E+03 0.00E+00 1.02E+00 I-135 2.68E+03 6.97E+03 2.56E+03 4.47E+05 1.11E+04 0.00E+00 5.24E+03 Cs-134 3.72E+05 8.47E+05 7.27E+05 0.00E+00 2.87E+05 9.75E+04 1.04E+04 Cs-136 3.90E+04 1.46E+05 1.10E+05 0.00E+00 8.55E+04 1.20E+04 1.17E+04 Cs-137 4.78E+05 6.20E+05 4.27E+05 0.00E+00 2.22E+05 7.51E+04 8.39E+03 Cs-138 3.35E+02 6.29E+02 3.28E+02 0.00E+00 4.86E+02 4.92E+01 1.89E-03 Ba-139 9.48E-01 6.74E-04 2.77E-02 0.00E+00 6.30E-04 3.81E+03 9.07E+02 Ba-140 3.90E+04 4.90E+01 2.56E+03 0.00E+00 1.67E+01 1.27E+06 2.18E+05 Ba-141 1.01E-01 7.62E-05 3.40E-03 0.00E+00 7.09E-05 1.96E+03 1.17E-07 Ba-142 2.66E-02 2.74E-05 1.68E-03 0.00E+00 2.32E-05 1.21E+03 1.59E-16 La-140 3.48E+02 1.76E+02 4.64E+01 0.00E+00 0.00E+00 1.38E+05 4.64E+05 La-142 6.92E-01 3.14E-01 7.82E-02 0.00E+00 0.00E+00 6.41E+03 2.14E+03 Ce-141 1.99E+04 1.35E+04 1.53E+03 0.00E+00 6.25E+03 3.61E+05 1.20E+05 Ce-143 1.89E+02 1.39E+02 1.55E+01 0.00E+00 6.16E+01 8.08E+04 2.29E+05 Ce-144 3.43E+06 1.43E+06 1.84E+05 0.00E+00 8.47E+05 7.76E+06 8.15E+05 Pr-143 9.48E+03 3.80E+03 4.70E+02 0.00E+00 2.19E+03 2.84E+05 2.03E+05 Pr-144 3.05E-02 1.26E-02 1.55E-03 0.00E+00 7.14E-03 1.03E+03 2.18E-08 Nd-147 5.34E+03 6.17E+03 3.69E+02 0.00E+00 3.60E+03 2.24E+05 1.75E+05 Hf-181 4.56E+04 2.57E+02 5.16E+03 1.63E+02 2.15E+02 5.99E+05 1.29E+05 W-187 8.59E+00 7.17E+00 2.51E+00 0.00E+00 0.00E+00 2.94E+04 1.57E+05 Np-239 2.32E+02 2.28E+01 1.26E+01 0.00E+00 7.09E+01 3.81E+04 1.21E+05

R Values in units of mrem/yr per Ci/m3 for inhalation and tritium and in units of mrem/yr per Ci/sec per m-2 for all others.

3-54 Page 9-100

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-17 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Inhalation AGE GROUP = Teen Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi H-3 0.00E+00 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 C-14 2.60E+04 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 Na-24 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 P-32 1.89E+06 1.09E+05 7.15E+04 0.00E+00 0.00E+00 0.00E+00 9.27E+04 Cr-51 0.00E+00 0.00E+00 1.35E+02 7.49E+01 3.07E+01 2.09E+04 3.00E+03 Mn-54 0.00E+00 5.10E+04 8.39E+03 0.00E+00 1.27E+04 1.98E+06 6.67E+04 Mn-56 0.00E+00 1.70E+00 2.52E-01 0.00E+00 1.79E+00 1.52E+04 5.74E+04 Fe-55 3.34E+04 2.38E+04 5.54E+03 0.00E+00 0.00E+00 1.24E+05 6.39E+03 Fe-59 1.59E+04 3.69E+04 1.43E+04 0.00E+00 0.00E+00 1.53E+06 1.78E+05 Co-57 0.00E+00 9.44E+02 9.20E+02 0.00E+00 0.00E+00 5.86E+05 3.14E+04 Co-58 0.00E+00 2.07E+03 2.77E+03 0.00E+00 0.00E+00 1.34E+06 9.51E+04 Co-60 0.00E+00 1.51E+04 1.98E+04 0.00E+00 0.00E+00 8.71E+06 2.59E+05 Ni-63 5.80E+05 4.34E+04 1.98E+04 0.00E+00 0.00E+00 3.07E+05 1.42E+04 Ni-65 2.18E+00 2.93E-01 1.27E-01 0.00E+00 0.00E+00 9.36E+03 3.67E+04 Cu-64 0.00E+00 2.03E+00 8.48E-01 0.00E+00 6.41E+00 1.11E+04 6.14E+04 Zn-65 3.85E+04 1.33E+05 6.23E+04 0.00E+00 8.63E+04 1.24E+06 4.66E+04 Zn-69M 1.15E+01 2.71E+01 2.49E+00 0.00E+00 1.65E+01 3.14E+04 1.71E+05 Zn-69 4.83E-02 9.20E-02 6.46E-03 0.00E+00 6.02E-02 1.58E+03 2.85E+02 Br-82 0.00E+00 0.00E+00 1.82E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 3.44E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 4.33E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 1.83E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.90E+05 8.39E+04 0.00E+00 0.00E+00 0.00E+00 1.77E+04 Rb-88 0.00E+00 5.46E+02 2.72E+02 0.00E+00 0.00E+00 0.00E+00 2.92E-05 Rb-89 0.00E+00 3.52E+02 2.33E+02 0.00E+00 0.00E+00 0.00E+00 3.38E-07 Sr-89 4.34E+05 0.00E+00 1.25E+04 0.00E+00 0.00E+00 2.41E+06 3.71E+05 Sr-90 1.08E+08 0.00E+00 6.67E+06 0.00E+00 0.00E+00 1.65E+07 7.64E+05 Sr-91 8.80E+01 0.00E+00 3.51E+00 0.00E+00 0.00E+00 6.07E+04 2.59E+05 Sr-92 9.52E+00 0.00E+00 4.06E-01 0.00E+00 0.00E+00 2.74E+04 1.19E+05 Y-90 2.98E+03 0.00E+00 8.00E+01 0.00E+00 0.00E+00 2.93E+05 5.59E+05 Y-91M 3.70E-01 0.00E+00 1.42E-02 0.00E+00 0.00E+00 3.20E+03 3.02E+01 Y-91 6.60E+05 0.00E+00 1.77E+04 0.00E+00 0.00E+00 2.93E+06 4.08E+05 Y-92 1.47E+01 0.00E+00 4.29E-01 0.00E+00 0.00E+00 2.68E+04 1.65E+05 Y-93 1.35E+02 0.00E+00 3.72E+00 0.00E+00 0.00E+00 8.32E+04 5.79E+05 Zr-95 1.45E+05 4.58E+04 3.15E+04 0.00E+00 6.73E+04 2.68E+06 1.49E+05 Zr-97 1.38E+02 2.72E+01 1.26E+01 0.00E+00 4.12E+01 1.30E+05 6.30E+05 Nb-95 1.85E+04 1.03E+04 5.66E+03 0.00E+00 9.99E+03 7.50E+05 9.67E+04 Nb-97 3.14E-01 7.78E-02 2.84E-02 0.00E+00 9.12E-02 3.93E+03 2.17E+03 Mo-99 0.00E+00 1.69E+02 3.22E+01 0.00E+00 4.11E+02 1.54E+05 2.69E+05 Tc-99M 1.38E-03 3.86E-03 4.99E-02 0.00E+00 5.76E-02 1.15E+03 6.13E+03 3 -2

R Values in units of mrem/yr per Ci/m for inhalation and tritium and in units of mrem/yr per Ci/sec per m for all others.

3-55 Page 9-101

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-17 (continue)

R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Inhalation AGE GROUP = Teen Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi Tc-101 5.92E-05 8.40E-05 8.24E-04 0.00E+00 1.52E-03 6.67E+02 8.72E-07 Ru-103 2.10E+03 0.00E+00 8.95E+02 0.00E+00 7.42E+03 7.82E+05 1.09E+05 Ru-105 1.12E+00 0.00E+00 4.34E-01 0.00E+00 1.41E+00 1.82E+04 9.04E+04 Ru-106 9.83E+04 0.00E+00 1.24E+04 0.00E+00 1.90E+05 1.61E+07 9.59E+05 Ag-110M 1.38E+04 1.31E+04 7.98E+03 0.00E+00 2.50E+04 6.74E+06 2.72E+05 Sn-113 8.19E+03 3.44E+02 8.68E+03 1.13E+02 2.45E+02 4.27E+05 2.03E+04 Sb-124 4.30E+04 7.94E+02 1.68E+04 9.76E+01 0.00E+00 3.85E+06 3.98E+05 Sb-125 7.38E+04 8.08E+02 1.72E+04 7.04E+01 0.00E+00 2.74E+06 9.92E+04 Te-125M 4.88E+03 2.24E+03 6.67E+02 1.40E+03 0.00E+00 5.36E+05 7.50E+04 Te-127m 1.80E+04 8.15E+03 2.18E+03 4.38E+03 6.53E+04 1.65E+06 1.59E+05 Te-127 2.01E+00 9.12E-01 4.42E-01 1.42E+00 7.28E+00 1.12E+04 8.08E+04 Te-129M 1.39E+04 6.57E+03 2.24E+03 4.57E+03 5.18E+04 1.97E+06 4.04E+05 Te-129 7.10E-02 3.38E-02 1.76E-02 5.18E-02 2.66E-01 3.30E+03 1.62E+03 Te-131M 9.84E+01 6.01E+01 4.02E+01 7.25E+01 4.39E+02 2.38E+05 6.21E+05 Te-131 1.58E-02 8.32E-03 5.04E-03 1.24E-02 6.18E-02 2.34E+03 1.51E+01 Te-132 3.60E+02 2.90E+02 2.19E+02 2.46E+02 1.95E+03 4.49E+05 4.63E+05 I-130 6.24E+03 1.79E+04 7.17E+03 1.49E+06 2.75E+04 0.00E+00 9.12E+03 I-131 3.54E+04 4.90E+04 2.64E+04 1.46E+07 8.39E+04 0.00E+00 6.48E+03 I-132 1.59E+03 4.37E+03 1.57E+03 1.51E+05 6.91E+03 0.00E+00 1.27E+03 I-133 1.21E+04 2.05E+04 6.21E+03 2.92E+06 3.59E+04 0.00E+00 1.03E+04 I-134 8.88E+02 2.32E+03 8.40E+02 3.95E+04 3.66E+03 0.00E+00 2.04E+01 I-135 3.69E+03 9.43E+03 3.48E+03 6.20E+05 1.49E+04 0.00E+00 6.94E+03 Cs-134 5.02E+05 1.13E+06 5.48E+05 0.00E+00 3.75E+05 1.46E+05 9.75E+03 Cs-136 5.14E+04 1.93E+05 1.37E+05 0.00E+00 1.10E+05 1.77E+04 1.09E+04 Cs-137 6.69E+05 8.47E+05 3.11E+05 0.00E+00 3.04E+05 1.21E+05 8.48E+03 Cs-138 4.66E+02 8.56E+02 4.46E+02 0.00E+00 6.62E+02 7.87E+01 2.70E-01 Ba-139 1.34E+00 9.44E-04 3.90E-02 0.00E+00 8.88E-04 6.46E+03 6.45E+03 Ba-140 5.46E+04 6.69E+01 3.51E+03 0.00E+00 2.28E+01 2.03E+06 2.28E+05 Ba-141 1.42E-01 1.06E-04 4.74E-03 0.00E+00 9.84E-05 3.29E+03 7.46E-04 Ba-142 3.70E-02 3.70E-05 2.27E-03 0.00E+00 3.14E-05 1.91E+03 4.79E-10 La-140 4.79E+02 2.36E+02 6.26E+01 0.00E+00 0.00E+00 2.14E+05 4.87E+05 La-142 9.60E-01 4.25E-01 1.06E-01 0.00E+00 0.00E+00 1.02E+04 1.20E+04 Ce-141 2.84E+04 1.89E+04 2.16E+03 0.00E+00 8.87E+03 6.13E+05 1.26E+05 Ce-143 2.66E+02 1.94E+02 2.16E+01 0.00E+00 8.64E+01 1.30E+05 2.55E+05 Ce-144 4.88E+06 2.02E+06 2.62E+05 0.00E+00 1.21E+06 1.33E+07 8.63E+05 Pr-143 1.34E+04 5.31E+03 6.62E+02 0.00E+00 3.09E+03 4.83E+05 2.14E+05 Pr-144 4.30E-02 1.76E-02 2.18E-03 0.00E+00 1.01E-02 1.75E+03 2.35E-04 Nd-147 7.86E+03 8.56E+03 5.13E+02 0.00E+00 5.02E+03 3.72E+05 1.82E+05 Hf-181 6.32E+04 3.48E+02 7.04E+03 2.12E+02 2.90E+02 9.39E+05 1.20E+05 W-187 1.20E+01 9.76E+00 3.43E+00 0.00E+00 0.00E+00 4.74E+04 1.77E+05 Np-239 3.38E+02 3.19E+01 1.77E+01 0.00E+00 1.00E+02 6.49E+04 1.32E+05

R Values in units of mrem/yr per Ci/m3 for inhalation and tritium and in units of mrem/yr per Ci/sec per m-2 for all others.

3-56 Page 9-102

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-18 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Inhalation AGE GROUP = Child Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi H-3 0.00E+00 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 C-14 3.59E+04 6.73E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03 Na-24 2.39E+04 2.39E+04 2.39E+04 2.39E+04 2.39E+04 2.39E+04 2.39E+04 P-32 2.60E+06 1.14E+05 9.86E+04 0.00E+00 0.00E+00 0.00E+00 4.21E+04 Cr-51 0.00E+00 0.00E+00 1.54E+02 8.53E+01 2.43E+01 1.70E+04 1.08E+03 Mn-54 0.00E+00 4.29E+04 9.50E+03 0.00E+00 1.00E+04 1.57E+06 2.29E+04 Mn-56 0.00E+00 2.46E+00 4.64E-01 0.00E+00 2.49E+00 1.95E+04 1.83E+05 Fe-55 4.74E+04 2.52E+04 7.77E+03 0.00E+00 0.00E+00 1.11E+05 2.87E+03 Fe-59 2.07E+04 3.34E+04 1.67E+04 0.00E+00 0.00E+00 1.27E+06 7.06E+04 Co-57 0.00E+00 9.03E+02 1.07E+03 0.00E+00 0.00E+00 5.07E+05 1.32E+04 Co-58 0.00E+00 1.77E+03 3.16E+03 0.00E+00 0.00E+00 1.10E+06 3.43E+04 Co-60 0.00E+00 1.31E+04 2.26E+04 0.00E+00 0.00E+00 7.06E+06 9.61E+04 Ni-63 8.21E+05 4.63E+04 2.80E+04 0.00E+00 0.00E+00 2.75E+05 6.33E+03 Ni-65 4.44E+00 4.39E-01 2.44E-01 0.00E+00 0.00E+00 1.22E+04 1.25E+05 Cu-64 0.00E+00 2.96E+00 1.60E+00 0.00E+00 8.97E+00 1.42E+04 5.46E+04 Zn-65 4.25E+04 1.13E+05 7.02E+04 0.00E+00 7.13E+04 9.94E+05 1.63E+04 Zn-69M 2.34E+01 4.00E+01 4.72E+00 0.00E+00 2.32E+01 4.05E+04 1.49E+05 Zn-69 9.96E-02 1.44E-01 1.33E-02 0.00E+00 8.69E-02 2.11E+03 1.51E+04 Br-82 0.00E+00 0.00E+00 3.11E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 7.04E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 8.14E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 3.76E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.98E+05 1.14E+05 0.00E+00 0.00E+00 0.00E+00 7.98E+03 Rb-88 0.00E+00 8.36E+02 5.45E+02 0.00E+00 0.00E+00 0.00E+00 2.56E+01 Rb-89 0.00E+00 5.13E+02 4.31E+02 0.00E+00 0.00E+00 0.00E+00 2.81E+00 Sr-89 5.99E+05 0.00E+00 1.72E+04 0.00E+00 0.00E+00 2.15E+06 1.67E+05 Sr-90 1.01E+08 0.00E+00 6.43E+06 0.00E+00 0.00E+00 1.47E+07 3.43E+05 Sr-91 1.80E+02 0.00E+00 6.82E+00 0.00E+00 0.00E+00 7.92E+04 2.59E+05 Sr-92 1.95E+01 0.00E+00 7.81E-01 0.00E+00 0.00E+00 3.57E+04 3.60E+05 Y-90 6.11E+03 0.00E+00 1.64E+02 0.00E+00 0.00E+00 3.89E+05 3.98E+05 Y-91M 7.54E-01 0.00E+00 2.74E-02 0.00E+00 0.00E+00 4.18E+03 2.55E+03 Y-91 9.13E+05 0.00E+00 2.43E+04 0.00E+00 0.00E+00 2.62E+06 1.84E+05 Y-92 3.03E+01 0.00E+00 8.64E-01 0.00E+00 0.00E+00 3.55E+04 3.55E+05 Y-93 2.77E+02 0.00E+00 7.59E+00 0.00E+00 0.00E+00 1.11E+05 5.78E+05 Zr-95 1.90E+05 4.17E+04 3.69E+04 0.00E+00 5.95E+04 2.23E+06 6.10E+04 Zr-97 2.79E+02 4.04E+01 2.38E+01 0.00E+00 5.78E+01 1.68E+05 5.22E+05 Nb-95 2.35E+04 9.16E+03 6.54E+03 0.00E+00 8.61E+03 6.13E+05 3.69E+04 Nb-97 6.38E-01 1.14E-01 5.36E-02 0.00E+00 1.27E-01 5.08E+03 4.14E+04 Mo-99 0.00E+00 2.56E+02 6.33E+01 0.00E+00 5.83E+02 2.01E+05 1.88E+05 Tc-99M 2.65E-03 5.18E-03 8.58E-02 0.00E+00 7.54E-02 1.41E+03 7.15E+03 3 -2

R Values in units of mrem/yr per Ci/m for inhalation and tritium and in units of mrem/yr per Ci/sec per m for all others.

3-57 Page 9-103

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-18 (continue)

R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Inhalation AGE GROUP = Child Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi Tc-101 1.20E-04 1.27E-04 1.60E-03 0.00E+00 2.16E-03 8.69E+02 2.43E+01 Ru-103 2.79E+03 0.00E+00 1.07E+03 0.00E+00 7.02E+03 6.61E+05 4.47E+04 Ru-105 2.27E+00 0.00E+00 8.25E-01 0.00E+00 2.00E+00 2.37E+04 1.48E+05 Ru-106 1.36E+05 0.00E+00 1.69E+04 0.00E+00 1.84E+05 1.43E+07 4.29E+05 Ag-110M 1.68E+04 1.14E+04 9.13E+03 0.00E+00 2.12E+04 5.47E+06 1.00E+05 Sn-113 9.00E+03 2.91E+02 9.83E+03 1.19E+02 2.02E+02 3.40E+05 7.45E+03 Sb-124 5.73E+04 7.40E+02 2.00E+04 1.26E+02 0.00E+00 3.24E+06 1.64E+05 Sb-125 9.84E+04 7.59E+02 2.07E+04 9.10E+01 0.00E+00 2.32E+06 4.03E+04 Te-125M 6.73E+03 2.33E+03 9.14E+02 1.92E+03 0.00E+00 4.77E+05 3.38E+04 Te-127m 2.48E+04 8.53E+03 3.01E+03 6.06E+03 6.35E+04 1.48E+06 7.13E+04 Te-127 4.12E+00 1.41E+00 9.08E-01 2.92E+00 1.05E+01 1.49E+04 8.36E+04 Te-129M 1.92E+04 6.84E+03 3.04E+03 6.32E+03 5.02E+04 1.76E+06 1.81E+05 Te-129 1.45E-01 5.20E-02 3.54E-02 1.06E-01 3.82E-01 4.36E+03 3.79E+04 Te-131M 2.00E+02 8.80E+01 7.54E+01 1.45E+02 5.94E+02 3.06E+05 4.58E+05 Te-131 3.23E-02 1.25E-02 9.79E-03 2.52E-02 8.75E-02 3.05E+03 1.98E+03 Te-132 7.15E+02 4.05E+02 3.92E+02 4.72E+02 2.63E+03 5.61E+05 2.05E+05 I-130 1.22E+04 2.44E+04 1.25E+04 2.74E+06 3.64E+04 0.00E+00 7.59E+03 I-131 4.80E+04 4.80E+04 2.72E+04 1.62E+07 7.87E+04 0.00E+00 2.84E+03 I-132 2.11E+03 4.06E+03 1.87E+03 1.93E+05 6.24E+03 0.00E+00 3.20E+03 I-133 1.66E+04 2.03E+04 7.68E+03 3.84E+06 3.37E+04 0.00E+00 5.47E+03 I-134 1.74E+03 3.21E+03 1.48E+03 7.54E+04 4.91E+03 0.00E+00 1.42E+03 I-135 4.91E+03 8.72E+03 4.14E+03 7.91E+05 1.34E+04 0.00E+00 4.43E+03 Cs-134 6.50E+05 1.01E+06 2.24E+05 0.00E+00 3.30E+05 1.21E+05 3.84E+03 Cs-136 6.50E+04 1.71E+05 1.16E+05 0.00E+00 9.53E+04 1.45E+04 4.17E+03 Cs-137 9.05E+05 8.24E+05 1.28E+05 0.00E+00 2.82E+05 1.04E+05 3.61E+03 Cs-138 9.41E+02 1.25E+03 8.25E+02 0.00E+00 9.24E+02 1.01E+02 4.01E+02 Ba-139 2.74E+00 1.46E-03 7.98E-02 0.00E+00 1.28E-03 8.58E+03 8.58E+04 Ba-140 7.39E+04 6.47E+01 4.32E+03 0.00E+00 2.11E+01 1.74E+06 1.02E+05 Ba-141 2.91E-01 1.62E-04 9.46E-03 0.00E+00 1.41E-04 4.34E+03 4.09E+02 Ba-142 7.43E-02 5.35E-05 4.15E-03 0.00E+00 4.33E-05 2.44E+03 4.08E+00 La-140 9.57E+02 3.34E+02 1.12E+02 0.00E+00 0.00E+00 2.72E+05 3.36E+05 La-142 1.93E+00 6.11E-01 1.92E-01 0.00E+00 0.00E+00 1.29E+04 1.13E+05 Ce-141 3.92E+04 1.95E+04 2.89E+03 0.00E+00 8.53E+03 5.43E+05 5.65E+04 Ce-143 5.44E+02 2.95E+02 4.27E+01 0.00E+00 1.24E+02 1.72E+05 1.89E+05 Ce-144 6.76E+06 2.11E+06 3.61E+05 0.00E+00 1.17E+06 1.19E+07 3.88E+05 Pr-143 1.85E+04 5.55E+03 9.14E+02 0.00E+00 3.00E+03 4.33E+05 9.73E+04 Pr-144 8.86E-02 2.74E-02 4.46E-03 0.00E+00 1.45E-02 2.33E+03 2.93E+02 Nd-147 1.08E+04 8.73E+03 6.81E+02 0.00E+00 4.81E+03 3.28E+05 8.21E+04 Hf-181 8.44E+04 3.28E+02 8.50E+03 2.76E+02 2.64E+02 7.95E+05 5.31E+04 W-187 2.43E+01 1.44E+01 6.44E+00 0.00E+00 0.00E+00 6.11E+04 1.35E+05 Np-239 6.93E+02 4.97E+01 3.49E+01 0.00E+00 1.45E+02 8.64E+04 9.52E+04

R Values in units of mrem/yr per Ci/m3 for inhalation and tritium and in units of mrem/yr per Ci/sec per m-2 for all others.

3-58 Page 9-104

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-19 R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Inhalation AGE GROUP = Infant Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi H-3 0.00E+00 6.46E+02 6.46E+02 6.46E+02 6.46E+02 6.46E+02 6.46E+02 C-14 2.65E+04 5.31E+03 5.31E+03 5.31E+03 5.31E+03 5.31E+03 5.31E+03 Na-24 1.06E+04 1.06E+04 1.06E+04 1.06E+04 1.06E+04 1.06E+04 1.06E+04 P-32 2.03E+06 1.12E+05 7.73E+04 0.00E+00 0.00E+00 0.00E+00 1.61E+04 Cr-51 0.00E+00 0.00E+00 8.93E+01 5.75E+01 1.32E+01 1.28E+04 3.56E+02 Mn-54 0.00E+00 2.53E+04 4.98E+03 0.00E+00 4.98E+03 9.98E+05 7.05E+03 Mn-56 0.00E+00 1.54E+00 2.21E-01 0.00E+00 1.10E+00 1.25E+04 7.17E+04 Fe-55 1.97E+04 1.17E+04 3.33E+03 0.00E+00 0.00E+00 8.69E+04 1.09E+03 Fe-59 1.35E+04 2.35E+04 9.46E+03 0.00E+00 0.00E+00 1.01E+06 2.47E+04 Co-57 0.00E+00 6.51E+02 6.41E+02 0.00E+00 0.00E+00 3.79E+05 4.86E+03 Co-58 0.00E+00 1.22E+03 1.82E+03 0.00E+00 0.00E+00 7.76E+05 1.11E+04 Co-60 0.00E+00 8.01E+03 1.18E+04 0.00E+00 0.00E+00 4.50E+06 3.19E+04 Ni-63 3.39E+05 2.04E+04 1.16E+04 0.00E+00 0.00E+00 2.09E+05 2.42E+03 Ni-65 2.39E+00 2.84E-01 1.23E-01 0.00E+00 0.00E+00 8.12E+03 5.01E+04 Cu-64 0.00E+00 1.88E+00 7.74E-01 0.00E+00 3.98E+00 9.30E+03 1.50E+04 Zn-65 1.93E+04 6.25E+04 3.10E+04 0.00E+00 3.24E+04 6.46E+05 5.13E+04 Zn-69M 1.26E+01 2.58E+01 2.34E+00 0.00E+00 1.04E+01 2.67E+04 4.09E+04 Zn-69 5.39E-02 9.67E-02 7.18E-03 0.00E+00 4.02E-02 1.47E+03 1.32E+04 Br-82 0.00E+00 0.00E+00 1.33E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 3.81E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 4.00E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-85 0.00E+00 0.00E+00 2.04E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 1.90E+05 8.81E+04 0.00E+00 0.00E+00 0.00E+00 3.03E+03 Rb-88 0.00E+00 5.57E+02 2.87E+02 0.00E+00 0.00E+00 0.00E+00 3.39E+02 Rb-89 0.00E+00 3.21E+02 2.06E+02 0.00E+00 0.00E+00 0.00E+00 6.82E+01 Sr-89 3.97E+05 0.00E+00 1.14E+04 0.00E+00 0.00E+00 2.03E+06 6.39E+04 Sr-90 4.08E+07 0.00E+00 2.59E+06 0.00E+00 0.00E+00 1.12E+07 1.31E+05 Sr-91 9.56E+01 0.00E+00 3.46E+00 0.00E+00 0.00E+00 5.26E+04 7.34E+04 Sr-92 1.05E+01 0.00E+00 3.91E-01 0.00E+00 0.00E+00 2.38E+04 1.40E+05 Y-90 3.29E+03 0.00E+00 8.82E+01 0.00E+00 0.00E+00 2.69E+05 1.04E+05 Y-91M 4.07E-01 0.00E+00 1.39E-02 0.00E+00 0.00E+00 2.79E+03 2.35E+03 Y-91 5.87E+05 0.00E+00 1.57E+04 0.00E+00 0.00E+00 2.45E+06 7.02E+04 Y-92 1.64E+01 0.00E+00 4.61E-01 0.00E+00 0.00E+00 2.45E+04 1.27E+05 Y-93 1.50E+02 0.00E+00 4.07E+00 0.00E+00 0.00E+00 7.64E+04 1.67E+05 Zr-95 1.15E+05 2.78E+04 2.03E+04 0.00E+00 3.10E+04 1.75E+06 2.17E+04 Zr-97 1.50E+02 2.56E+01 1.17E+01 0.00E+00 2.59E+01 1.10E+05 1.40E+05 Nb-95 1.57E+04 6.42E+03 3.77E+03 0.00E+00 4.71E+03 4.78E+05 1.27E+04 Nb-97 3.42E-01 7.29E-02 2.63E-02 0.00E+00 5.70E-02 3.32E+03 2.69E+04 Mo-99 0.00E+00 1.65E+02 3.23E+01 0.00E+00 2.65E+02 1.35E+05 4.87E+04 Tc-99M 1.40E-03 2.88E-03 3.72E-02 0.00E+00 3.11E-02 8.11E+02 2.03E+03 3 -2

R Values in units of mrem/yr per Ci/m for inhalation and tritium and in units of mrem/yr per Ci/sec per m for all others.

3-59 Page 9-105

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-19 (continue)

R VALUES FOR THE SHEARON HARRIS NUCLEAR POWER PLANT*

PATHWAY = Inhal AGE GROUP = Infant Nuclide Bone Liver Total Body Thyroid Kidney Lung Gi-LLi Tc-101 6.51E-05 8.23E-05 8.12E-04 0.00E+00 9.79E-04 5.84E+02 8.44E+02 Ru-103 2.01E+03 0.00E+00 6.78E+02 0.00E+00 4.24E+03 5.51E+05 1.61E+04 Ru-105 1.22E+00 0.00E+00 4.10E-01 0.00E+00 8.99E-01 1.57E+04 4.84E+04 Ru-106 8.67E+04 0.00E+00 1.09E+04 0.00E+00 1.06E+05 1.15E+07 1.64E+05 Ag-110M 9.97E+03 7.21E+03 4.99E+03 0.00E+00 1.09E+04 3.66E+06 3.30E+04 Sn-113 4.67E+03 1.74E+02 4.89E+03 6.73E+01 9.94E+01 2.30E+05 2.29E+03 Sb-124 3.79E+04 5.56E+02 1.20E+04 1.00E+02 0.00E+00 2.64E+06 5.91E+04 Sb-125 5.17E+04 4.77E+02 1.09E+04 6.23E+01 0.00E+00 1.64E+06 1.47E+04 Te-125M 4.76E+03 1.99E+03 6.58E+02 1.62E+03 0.00E+00 4.47E+05 1.29E+04 Te-127m 1.66E+04 6.89E+03 2.07E+03 4.86E+03 3.75E+04 1.31E+06 2.73E+04 Te-127 2.23E+00 9.53E-01 4.89E-01 1.85E+00 4.86E+00 1.03E+04 2.44E+04 Te-129M 1.41E+04 6.08E+03 2.22E+03 5.47E+03 3.17E+04 1.68E+06 6.89E+04 Te-129 7.88E-02 3.47E-02 1.88E-02 6.75E-02 1.75E-01 3.00E+03 2.63E+04 Te-131M 1.07E+02 5.50E+01 3.63E+01 8.93E+01 2.65E+02 1.99E+05 1.19E+05 Te-131 1.74E-02 8.22E-03 5.00E-03 1.58E-02 3.99E-02 2.06E+03 8.22E+03 Te-132 3.72E+02 2.37E+02 1.76E+02 2.79E+02 1.03E+03 3.40E+05 4.41E+04 I-130 6.36E+03 1.39E+04 5.57E+03 1.60E+06 1.53E+04 0.00E+00 1.99E+03 I-131 3.79E+04 4.43E+04 1.96E+04 1.48E+07 5.17E+04 0.00E+00 1.06E+03 I-132 1.69E+03 3.54E+03 1.26E+03 1.69E+05 3.94E+03 0.00E+00 1.90E+03 I-133 1.32E+04 1.92E+04 5.59E+03 3.55E+06 2.24E+04 0.00E+00 2.15E+03 I-134 9.21E+02 1.88E+03 6.65E+02 4.45E+04 2.09E+03 0.00E+00 1.29E+03 I-135 3.86E+03 7.59E+03 2.77E+03 6.95E+05 8.46E+03 0.00E+00 1.83E+03 Cs-134 3.96E+05 7.02E+05 7.44E+04 0.00E+00 1.90E+05 7.95E+04 1.33E+03 Cs-136 4.82E+04 1.34E+05 5.28E+04 0.00E+00 5.63E+04 1.17E+04 1.43E+03 Cs-137 5.48E+05 6.11E+05 4.54E+04 0.00E+00 1.72E+05 7.12E+04 1.33E+03 Cs-138 5.05E+02 7.81E+02 3.98E+02 0.00E+00 4.10E+02 6.54E+01 8.76E+02 Ba-139 1.48E+00 9.84E-04 4.30E-02 0.00E+00 5.92E-04 5.95E+03 5.10E+04 Ba-140 5.59E+04 5.59E+01 2.89E+03 0.00E+00 1.34E+01 1.59E+06 3.83E+04 Ba-141 1.57E-01 1.08E-04 4.97E-03 0.00E+00 6.50E-05 2.97E+03 4.75E+03 Ba-142 3.98E-02 3.30E-05 1.96E-03 0.00E+00 1.90E-05 1.55E+03 6.93E+02 La-140 5.05E+02 2.00E+02 5.15E+01 0.00E+00 0.00E+00 1.68E+05 8.48E+04 La-142 1.03E+00 3.77E-01 9.04E-02 0.00E+00 0.00E+00 8.22E+03 5.95E+04 Ce-141 2.77E+04 1.66E+04 1.99E+03 0.00E+00 5.24E+03 5.16E+05 2.15E+04 Ce-143 2.93E+02 1.93E+02 2.21E+01 0.00E+00 5.64E+01 1.16E+05 4.97E+04 Ce-144 3.19E+06 1.21E+06 1.76E+05 0.00E+00 5.37E+05 9.83E+06 1.48E+05 Pr-143 1.40E+04 5.24E+03 6.99E+02 0.00E+00 1.97E+03 4.33E+05 3.72E+04 Pr-144 4.79E-02 1.85E-02 2.41E-03 0.00E+00 6.72E-03 1.61E+03 4.28E+03 Nd-147 7.94E+03 8.13E+03 5.00E+02 0.00E+00 3.15E+03 3.22E+05 3.12E+04 Hf-181 5.65E+04 2.66E+02 5.05E+03 2.25E+02 1.59E+02 6.73E+05 1.90E+04 W-187 1.30E+01 9.02E+00 3.12E+00 0.00E+00 0.00E+00 3.96E+04 3.56E+04 Np-239 3.71E+02 3.32E+01 1.88E+01 0.00E+00 6.62E+01 5.95E+04 2.49E+04

R Values in units of mrem/yr per Ci/m3 for inhalation and tritium and in units of mrem/yr per Ci/sec per m-2 for all others.

3-60 Page 9-106

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Table 3.3-20 Recommended Values for Uap to be used for the Maximum Exposed Individual in Lieu of Site Specific Data (Table E-5 Regulatory Guide 1.109 Rev 1)

Pathway Infant Child Teen Adult Fruits, vegetables & grain 1 - 520 630 520 (kg/yr)

Leafy Vegetables (kg/yr) - 26 42 64 Milk (L/yr) 330 330 400 310 Meat & poultry (kg/yr) - 41 65 110 3

Inhalation (m /yr) 1400 3700 8000 8000 Note 1 - Consists of the following (on a mass basis): 22% fruit, 54% vegetables (including leafy vegetables), and 24% grain 3-61 Page 9-107

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Table 3.3-21 Inhalation Dose Factors from Carbon-14 for organ to an individual from Tables E-7 to E-10 Regulatory Guide 1.109 Rev 1 (mrem/pCi inhaled)

Individual Bone Liver T.Body Thyroid Kidney Lung GI-LLI Infant 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Child 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Teen 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 Adult 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Table 3.3-22 Ingestion Dose Factors from Carbon-14 for organ to an individual from Tables E-11 to E-14 Regulatory Guide 1.109 Rev 1 (mrem/pCi ingested)

Individual Bone Liver T.Body Thyroid Kidney Lung GI-LLI Infant 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Child 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 Teen 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 Adult 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 3-62 Page 9-108

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Figure 3.1 SHNPP Gaseous Waste Streams Turbine Bldg Vent Stack 3A REM - Radiation Effluent Monitor RM-1TV3536-1(WRGM) RM WPB - Waste Processing Bldg RAB - Reactor Auxiliary Bldg REM-1TV-3534 Condenser Vacuum Pump REM FHB - Fuel Handling Bldg WRGM - Wide Range Gas Monitor Condenser Polisher Area RM - Radiation Monitor Gland Steam WPB Vent Stack 5 RM-1WV-3546-1 (WRGM) RM REM REM-1WV-3546 WPB Hot & Cold Laundry WPB Office Area Exhaust WPB Cold Laundry Dryers WPB Control Room Smoke Exhaust WPB Office Areas WPB General Area Exhaust WPB Chiller Room Exhaust Waste Gas Decay Tanks Waste Processing Area Filtered Exhaust WPB Vent Stack 5A RM-1WV-3547-1 (WRGM) RM WPB Switchgear Room Exhaust WPB HVAC Equip. Room Exhaust WPB Personnel Handling Facility Exhaust WPB Hot & Low Activity Labs Exhaust WPB Lab Areas Exhaust Plant Vent Stack 1 RM-21AV-3509-1SA (WRGM)

REM REM-1LT-3502A REM-1LT-3502B RM Containment Leak Detection REM Containment Pre-Entry Purge FHB Normal Exhaust North REM-1AV-3531 REM RAB Normal Exhaust FHB Normal Exhaust South REM REM-1AV-3532A REM REM-1FL-3506 RAB Emergency Exhaust REM-1AV-3532B FHB Normal Exhaust(Oper. Fl) South REM REM REM-1FL-3507 RAB Ventilation System FHB Normal Exhaust(Oper. Fl) North Hydrogen Purge REM REM-1FL-3508-SA RAB Smoke Purge FHB Emergency Exhaust REM REM-1FL-3508-SB RAB Purge 3-63 Page 9-109

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Figure 3.2 Schematic of Airborne Effluent Release Points 3-64 Page 9-110

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Figure 3.3 SHNPP Condenser Off-Gas System Turbine Building Vent Stack - 3A Wide Range Gas Monitor (WRGM)

RM RM-TV- 3536-1 Gland Steam Condenser CVPETS Main REM Condenser REM-1TV- 3534 Hogging Valve Atmosphere Blind Flange 3-65 Page 9-111

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The purpose of the radiological monitoring program is to measure radioactivity in the environment, to determine whether measured radioactivity is the result of operation of the Shearon Harris Nuclear Power Plant, and to assess the potential dose to the offsite population based on the cumulative measurements of radioactivity of plant origin. The program provides representative measurements of radioactivity in the highest potential exposure pathways and verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways (i.e. air, surface water, groundwater.)

Table 4.1 contains the sample point description, sampling and collection frequency, analysis type, and frequency for various exposure pathways in the vicinity of the SHNPP for the radiological monitoring program.

Figure 4.1-1 shows the exclusion boundary surrounding SHNPP. Figures 4.1-2 and 4.1-3 show the locations of the various sampling points and TLD locations.

4-1 Page 9-112

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sample: Airborne Particulates and Radioiodine Sampling and Collection Frequency: Continuous operating sampler with sample collection as required by dust loading but at least once per 7 days.

Analysis Frequency and Weekly Gross Beta2 Required Analysis: Weekly I-131 (charcoal canisters) 4,5 Quarterly Gamma Isotopic (Composited by location)

Sample Point ID No. Sample Point, Description1, Distance, and Direction 1 0.1 mi. S on SR 1134 from SR 1011 intersection.

N sector, 2.6 mi. from site.

2 1.4 mi. S on SR 1134 from SR 1011 intersection.

NNE sector, 1.4 mi. from site.

4 0.7 mi. N on SR 1127 from intersection with US 1.

NNE sector, 3.1 mi. from site.

5 Pittsboro (Control Station)3 WNW sector from site, > 12 mi. from site 26 Harris Lake Spillway S sector, 4.7 mi. from site 47 1.3 mi. N on SR 1912 from intersection of NC 42 SSW sector, 3.4 miles from site 63 SHNPP site.

SW sector, 0.6 mi. from site.

90 SHNPP site.

SSW sector, 0.5 mi. from site.

91 HE&EC, Sewage Treatment Facility ENE Sector, 1.6 mi. from site.

4-2 Page 9-113

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sample: Direct Radiation (TLD)

Sampling and Collection Frequency: Continuous measurement with an integrated readout at least once per quarter.

Analysis Frequency and Required Analysis: Quarterly Gamma Dose Sample Point 1

ID No. Sample Point, Description , Distance, and Direction 1 0.1 mi. S on SR 1134 from SR 1011 intersection.

N sector, 2.6 mi. from site.

2 1.4 mi. S on SR 1134 from SR 1011 intersection.

NNE sector, 1.4 mi. from site.

3 HE&EC Visitor Center (Population Center)

ENE sector, 1.9 mi. from site.

4 New Hill (Population Center) 0.7 mi. N on SR 1127 from intersection with US 1 NNE sector, 3.1 mi. from site.

3 5 Pittsboro (Control Station)

WNW sector from site, >12 mi. (13.3 mi.) from site 6 Intersection of SR 1134 & SR 1135.

ENE sector, 0.8 mi. from site.

7 Extension of SR 1134.

E sector 0.7 mi. from site.

8 Dead end of road. Extension of SR 1134.

ESE sector, 0.6 mi. from site.

9 1 mi. S on SR 1130 from intersection of SR 1127, 1115, and 1130.

SE sector, 2.2 mi. from site.

10 SR 1130 S of intersection of SR 1127, 1115, and 1130.

SSE sector, 2.2 mi. from site.

11 SHNPP site.

S sector, 0.6 mi. from site 12 SHNPP site.

SSW sector, 0.9 mi. from site.

13 SHNPP site.

WSW sector 0.7 mi. from site.

14 SHNPP site. Access road to aux. reservoir.

W sector, 1.5 mi. from site.

4-3 Page 9-114

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sample: Direct Radiation (TLD)

Sampling and Collection Frequency: Continuous measurement with an integrated readout at least once per quarter.

Analysis Frequency and Required Analysis: Quarterly Gamma Dose Sample Point 1

ID No. Sample Point, Description , Distance, and Direction 15 SR 1911.

W sector, 2.0 mi. from site.

19 0.6 mi. E on SR 1142 from intersection of SR 1141.

NNE sector 5.0 mi. from site.

20 US 1 at intersection SR 1149.

NE sector 4.5 mi. from site.

21 1.2 mi. W on SR 1152 from intersection SR 1153.

ENE sector, 4.8 mi. from site.

22 Formerly Ragan's Dairy on SR 1115.

E sector, 4.3 mi. from site.

23 Intersection of SR 1127 and SR 1116.

ESE sector, 4.8 mi. from site.

24 Sweet Springs Church on SR 1116.

SE sector 4.0 mi. from site.

25 0.2 mi. W on SR 1402 from intersection of SR 1400 SSE sector, 4.7 mi. from site 26 Harris Lake Spillway S sector, 4.7 mi. from site 27 NC 42 @ Buckhorn United Methodist Church SSW sector, 4.8 mi. from site.

28 0.6 mi. on SR 1924 from intersection of SR 1916.

SW sector, 4.8 mi. from site.

29 Parking lot of Arclin, Inc. on SR 1916.

WSW sector, 5.7 mi. from site.

`

4-4 Page 9-115

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sample: Direct Radiation (TLD)

Sampling and Collection Frequency: Continuous measurement with an integrated readout at least once per quarter.

Analysis Frequency and Required Analysis: Quarterly Gamma Dose Sample Point 1

ID No. Sample Point, Description , Distance, and Direction 30 Exit intersection of SR 1972 and US 1.

W sector, 5.6 mi. from site.

31 At intersection of SR 1908, 1909, 1910.

WNW sector, 4.7 mi. from site.

32 Jordan Lake (Population Center)

SR 1008.

NNW sector 6.4 mi. from site.

33 SR 1142. 1.7 mi.from intersection of SR 1141.

NNW sector, 4.5 mi. from site.

34 Deleted 35 Deleted 36 Deleted 37 Deleted 48 SR 1142. 1.5 mi. from intersection of SR 1141.

N sector, 4.5 mi. from site.

49 SR 1127. 0.3 mi. S from intersection with US 1.

NE sector, 2.5 mi. from site.

50 Holleman Crossroad (Population Center)

SR 1127 W from intersection SR 1115 and 1130.

ESE sector, 2.6 mi. from site.

53 SR 1972 N from intersection of SR 1910 and SR 1972.

NW sector, 5.8 mi. from site.

56 SR 1912 at intersection of SR 1912 and SR 1924.

WSW sector, 3.0 mi. from site.

63 SHNPP Site.

SW sector, 0.6 mi. from site.

67 Deleted 4-5 Page 9-116

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sample: Direct Radiation (TLD)

Sampling and Collection Frequency: Continuous measurement with an integrated readout at least once per quarter.

Analysis Frequency and Required Analysis: Quarterly Gamma Dose 93 SR 1911.

WNW sector, 2.2 mi. from site.

94 Old US HWY 1 NW sector, 2.0 mi. from site 95 Bonsal Rd NNW sector, 2.0 mi. from site 98 Holly Springs School Complex (Population Center)

E sector, 5.9 mi. from site 99 Friendship High School (Population Center)

NNE sector, 5.5 mi. from site Exposure Pathway and/or Sample: Waterborne, Surface Water 5

Sampling and Collection Frequency: Composite sample collected over a monthly period.

Analysis Frequency and Required Analysis: Monthly Gamma Isotopic4 Quarterly Tritium Sample Point ID No. Sample Point, Description1, Distance, and Direction 26 Harris Lake Spillway S sector, 4.7 mi. from site 38 Cape Fear Steam Electric Plant Intake Structure (Control Station)3 WSW sector, 6.2 miles from site 40 NE Harnett Metro Water Treatment Plant Intake Building Duncan Street, Lillington, N.C.

SSE sector, ~17 mi. from site.

NOTE: H-3 analysis is normally performed monthly.

4-6 Page 9-117

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sample: Waterborne, Groundwater Sampling and Collection Frequency: Grab sample collected quarterly Analysis Frequency and Quarterly Gamma Isotopic4 Required Analysis: Quarterly Tritium Sample Point 1

ID No. Sample Point, Description , Distance, and Direction SHNPP Site (LP-13) 57 N. side of Aux Res Intake canal SSW sector, 0.4 mi. from site.

SHNPP Site (W-13) 59 N. side of Old Construction Road.

NNE sector, 0.5 mi. from site SHNPP Site (W-9A) 60 W. bank of Harris Lake SE of Cooling Tower.

ESE sector, 0.5 mi. from site SHNPP Site (LP-6) 68 N. of old Steam Generator Storage Building W sector, 0.2 mi. from site SHNPP Site (LP-7) 69 S. side of Warehouse 9.

NNE sector, 0.2 mi. from site SHNPP Site (LP-9) 70 N. side of Plant Entrance Road.

E sector, 0.4 mi. from site SHNPP Site (LP-16) 71 S. of Switch Yard SE sector, 0.3 mi. from site SHNPP Site (MWA-12) 72 N. of Cooling Tower Makeup Water Intake Structures.

SE sector, 0.2 mi. from site SHNPP Site 73 N. of Emergency Service Water Screening Structure.

S sector, 0.2 mi. from site SHNPP Site 74 N. of helicopter landing pad.

SSE sector, 0.2 mi. from site 4-7 Page 9-118

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sample: Waterborne, Groundwater Sampling and Collection Frequency: Grab sample collected quarterly Analysis Frequency and Quarterly Gamma Isotopic4 Required Analysis: Quarterly Tritium Sample Point 1

ID No. Sample Point, Description , Distance, and Direction SHNPP Site 75 W. of Security Building Entrance ESE sector, 0.1 mi. from site 76 Deleted SHNPP Site (BD-MW1) 77 Along the Cooling Tower Blowdown Line S sector, 0.4 mi. from site SHNPP Site (BD-MW2) 78 Along the Cooling Tower Blowdown Line S sector, 0.5 mi. from site SHNPP Site (BD-MW3) 79 Along the Cooling Tower Blowdown Line S sector, 0.5 mi. from site SHNPP Site (BD-MW5) 80 Along the Cooling Tower Blowdown Line S sector, 0.6 mi. from site SHNPP Site (BD-MW7) 81 Along the Cooling Tower Blowdown Line S sector, 0.6 mi. from site SHNPP Site (BD-MW8) 82 Along the Cooling Tower Blowdown Line S sector, 0.6 mi. from site SHNPP Site (BD-MW16) 83 Along the Cooling Tower Blowdown Line SSW sector, 1.6 mi. from site 4-8 Page 9-119

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sample: Waterborne, Drinking Water 5

Sampling and Collection Frequency: Composite sample collected over a two-week period if I-131 analysis is performed; monthly composite otherwise.

Analysis Frequency and 6

Required Analysis: I-131 on each composite when the dose calculated for the consumption of the water is greater than 1 mrem per yr.

Monthly Gross Beta Monthly Gamma Isotopic4 Quarterly Tritium Sample Point ID No. Sample Point, Description1, Distance, and Direction 38 Cape Fear Steam Electric Plant Intake Structure (Control Station)3 WSW sector, 6.2 miles from site 40 NE Harnett Metro Water Treatment Plant Intake Building Duncan Street, Lillington, N.C.

SSE sector, ~17 mi. from site.

51 SHNPP Water Treatment Building On Site NOTE: H-3 analysis is normally performed monthly.

4-9 Page 9-120

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sample: Waterborne, Sediment from Shoreline Sampling and Collection Frequency: Shoreline Sediment sample collected semiannually.

Analysis Frequency and Required Analysis: Each Sample Gamma Isotopic4 Sample Point 1

ID No. Sample Point, Description , Distance, and Direction 26 Harris Lake Spillway S sector, 4.6 mi. from site 41 Shoreline of Mixing Zone of Cooling Tower Blowdown Line S sector, 3.8 miles from site.

TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sample: Waterborne, Bottom Sediment Sampling and Collection Frequency: Bottom Sediment sample collected semiannually.

Analysis Frequency and 4

Required Analysis: Each Sample Gamma Isotopic Sample Point ID No. Sample Point, Description1, Distance, and Direction 52 Harris Lake in the vicinity of the mixing zone of the cooling tower S sector, 3.8 miles from site.

4-10 Page 9-121

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sample: Ingestion - Milk8 Sampling and Collection Frequency: Grab samples semi-monthly when animals are on pasture; monthly at other times.9 Analysis Frequency and Required Analysis: Each Sample I-131 4

Each Sample Gamma Isotopic Sample Point ID No. Sample Point, Description1, Distance, and Direction 3

5 Manco's Dairy, Pittsboro (Control Station)

WNW sector from site, > 12 mi. from site 96 Deleted TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sample: Ingestion - Fish Sampling and Collection Frequency: One sample of each of the following semiannually:

1. Catfish (bottom feeders)

2. Sunfish & Largemouth Bass (free swimmers) 4 Analysis Frequency Each sample - Gamma Isotopic on and Required Analysis: edible portion for each Sample Point ID No. Sample Point, Description1, Distance, and Direction 44 Site varies within the Harris Lake.

45 Site varies above Buckhorn Dam on Cape Fear River (Control Station)3 4-11 Page 9-122

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 7,10 Exposure Pathway and/or Sample: Ingestion - Food Products Sampling and Collection Frequency: Samples of 3 different kinds of broadleaf 16 vegetation monthly during the growing season Analysis Frequency Each sample - Gamma Isotopic4 on and Required Analysis: edible portion for each Sample Point 1

ID No. Sample Point, Description , Distance, and Direction 5 Deleted 3

97 Granite Springs Farm (Control Station)

NW sector, 19.1 miles from site 4-12 Page 9-123

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sample: Aquatic Vegetation Sampling and Collection Frequency: Annually Analysis Frequency and Required Analysis: Each sample - Gamma Isotopic4 Sample Point Sample Point, Description1, Distance, and Direction ID No.

26 Harris Lake Spillway S sector, 4.7 mi. from site 41 Shoreline of Mixing Zone of Cooling Tower Blowdown Line S sector, 3.8 miles from site.

61 Harris Lake East of New Hill- Holleman Rd (Control Location)

E sector, 2.5 mi. from site Exposure Pathway and/or Sample: Broadleaf Vegetation 8 Sampling and Collection Frequency: Monthly, during growing season 15 Analysis Frequency 4

and Required Analysis: Each sample - Gamma Isotopic 1

Sample Point Sample Point, Description , Distance, and Direction ID No.

5 Pittsboro (Control Station)3 NNW sector, > 12 mi. from site 12 SHNPP Site SSW sector, 0.9 mi. from site 63 SHNPP Site SW sector, 0.6 mi from site 4-13 Page 9-124

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 NOTES TO TABLE 4.1 SHNPP Radiological Environmental Monitoring Program

1. Sample locations are shown on Figures 4.1-2 and 4.1-3. Tables 4.2 and 4.3 lists the sample locations and frequencies.

2. Particulate samples will be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more following filter change to allow for radon and thorium daughter decay. If gross beta activity is greater than ten times the yearly mean of the control sample station activity, a gamma isotopic analysis will be performed on the individual samples.

3. Control sample stations (or background stations) are located in areas that are unaffected by plant operations.

All other sample stations that have the potential to be affected by radioactive emissions from plant operations are considered indicator stations.

4. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to effluents from plant operations.

5. Composite samples will be collected with equipment which is capable of collecting an aliquot at time intervals which are very short (e.g., every 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) relative to the compositing period (e.g., monthly).

6. The dose will be calculated for the maximum organ and age group, using the methodology contained in ODCM Equation 2.2-1.

7. Based on historical meteorology (1976-1987), food product Locations 54 and 55 were added in the summer of 1988 as the off-site locations with the highest predicted D/Q values. Food product locations 43 and 46 were deleted after the 1988 growing season.

8. If milk animals are not present or unavailable for sampling at indicator locations per page 4-11, sampling of Broadleaf Vegetation per page 4-14 can be substituted.

9. When no milk animals are available at indicator locations, milk sampling of the control location can be reduced to once per month to maintain historical data.

10. Sample Locations 54, 55, 62, 64 were deleted from food product sampling in Revision 18 as crops are not irrigated with water in which plant wastes have been discharged or crops are no longer being grown at a location. Sample Location 5 was deleted in Revision 26. The owner of this control location no longer gardens in sufficient quantity provide three different kinds of broadleaf vegetation. The new control location 97 is a commercial operation and satisfies the food crop requirement. Currently there are no food product locations irrigated by water containing plant discharges.

11. Sample Location 58 was deleted from groundwater monitoring in Revision 18 since being shown to have direct communication with lake/surface water. Sample Locations 68 through 72 were added to the groundwater monitoring in Revision 19 based on evaluation of data from bedrock wells.

12. Location 57 was removed from the groundwater monitoring in Revision 19 and Locations 39 deleted the groundwater monitoring in Revision 20 based on evaluation of data from bedrock wells.

13. Sample Locations 65 & 66 deleted Broad Leaf vegetation samples and added Broad Leaf vegetation to Sample Locations 12 and 63 in Revision 20 based on new meteorology data.

14. In Revision 21, Sample Locations 57, 73 through 76 were added to the groundwater monitoring in Revision 21 in order to provide a more complete picture of the sites hydrology. Sample Location 76 was removed from the groundwater monitoring in Revision 26 because within the protected area it is not used as a source of drinking water or irrigation.

15. Broadleaf vegetation refers to any natural vegetation, plants, shrubs or trees that have wide, flat leaves or leaves with veins which branch from a main vein. Typically leaves are only present during the growing season May through October.

16. Attention shall be paid to including samples of tuberous and root food products.

4-14 Page 9-125

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 4.2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS (a) (b)

Site# Type Location Description* AC & SW DW SS SB AV FP Fish Milk BLV GW AP (FI) (Mk) 1 I 2.6 miles N W/Q 2 I 1.4 miles NNE W/Q 4 I 3.1 miles NNE W/Q (b) 5 C >12 miles WNW - Pittsboro W/Q SM/M M

>12 Miles NNW - Pittsboro (BLV)

(b) 12 I 0.9 miles SSW M 26 I 4.7 miles S W/Q BW/M SA A 38 C 6.2 miles WSW BW/M BW/M 40 I 17.2 miles SSE -- Lillington BW/M BW/M 41 I 3.8 miles S SA A 44 I Site varies in Harris Lake SA 45 C Site varies in Cape Fear River SA above Buckhorn Dam 47 I 3.4 miles SSW W/Q 51 I Water Treatment Building (On BW/M Site) 52 I 3.8 miles S SA 57 I 0.4 miles SSW Q 59 I 0.5 miles NNE Q 60 I 0.5 miles ESE Q 61 C 2.5 miles E A (b) 63 I 0.6 miles SW W/Q M 68 I 0.2 miles W Q 69 I 0.2 miles NNE Q 70 I 0.4 miles E Q 71 I 0.3 miles SE Q 72 I 0.2 miles SE Q 73 I 0.2 miles S Q 74 I 0.2 miles SSE Q 75 I 0.1 miles ESE Q 77 I 0.4 miles S Q 78 I 0.5 miles S Q 79 I 0.5 miles S Q 80 I 0.6 miles S Q 81 I 0.6 miles S Q 82 I 0.6 miles S Q 83 I 1.6 miles SSW Q 90 I 0.5 miles SSW W/Q 91 I 1.6 miles ENE W/Q (a) 97 C 19.1 miles NW Granite M Springs Farm (a) When Available, during Harvest/Growing Season (b) During Growing Season per ODCM - May through October

GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as close as possible to the item of interest.

W Weekly SM Semimonthly AC Air Cartridge SB Sediment Bottom FI Fish BW BiWeekly Q Quarterly AP Air Particulate AV Aquatic Vegetation MK Milk M Monthly SA Semiannually SW Surface Water FP Food Product A Annual DW Drinking Water BLV Broadleaf Vegetation C Control I Indicator SS Sediment Shoreline GW Ground Water 4-15 Page 9-126

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 4.3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS (TLD Sites)

Site Measure Location* Distance Sector Site Measure Location* Distance Sector

Type (miles) # Type (miles) 1 IR 2.6 N 26 OR 4.7 S 2 IR 1.4 NNE 27 OR 4.8 SSW HE&EC Visitor Center 3 SI 1.9 ENE 28 OR 4.8 SW (Population Center)

New Hill 4 SI 3.1 NNE 29 OR 5.7 WSW (Population Center)

Pittsboro 5 C 13.3 WNW 30 OR 5.6 W (Control Station) 6 IR 0.8 ENE 31 OR 4.7 WNW Jordan Lake 7 IR 0.7 E 32 SI 6.4 NNW (Population Center) 8 IR 0.6 ESE 33 OR 4.5 NNW 9 IR 2.2 SE 48 OR 4.5 N 10 IR 2.2 SSE 49 IR 2.5 NE Holleman Crossroads 11 IR 0.6 S 50 SI 2.6 ESE (Population Center) 12 IR 0.9 SSW 53 OR 5.8 NW 13 IR 0.7 WSW 56 IR 3.0 WSW 14 IR 1.5 W 63 IR 0.6 SW 15 IR 2.0 W 93 IR 2.2 WNW 19 OR 5.0 NNE 94 IR 2.0 NW 20 OR 4.5 NE 95 IR 2.0 NNW Holly Springs School 21 OR 4.8 ENE 98 SI Complex 5.9 E (Population Center)

Friendship School 22 OR 4.3 E 99 SI 5.5 NNE (Population Center) 23 OR 4.8 ESE 24 OR 4.0 SE 25 OR 4.7 SSE

GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as close as possible to the item of interest.

IR Inner Ring OR Outer Ring C Control SI Special Interest/

Population Center 4-16 Page 9-127

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 4-17 Page 9-128

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Figure 4.1-2 Environmental Radiological Sampling Points (One Mile Radius) 4-18 Page 9-129

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Figure 4.1-3 Environmental Radiological Sampling Points (10 mile Radius) 4-19 Page 9-130

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 5.0 INTERLABORATORY COMPARISON STUDIES The objective of this program is to evaluate the total laboratory analysis process by comparing results for an equivalent sample with those obtained by an independent laboratory or laboratories.

Environmental samples from the SHNPP environs are to be analyzed by a qualified laboratory.

These laboratories will participate at least annually in a nationally recognized interlaboratory comparison study. The results of the laboratories' performances in the study will be included in the Annual Radiological Environmental Operating Report (see SHNPP ODCM Operational Requirement 4.12.3).

Radiochemical analyses of composite samples required by ODCM Operational Requirements Tables 4.11-1 and 4.11-2 will be performed by a qualified laboratory. The qualified radiochemistry laboratory will participate annually in a corporate interlaboratory comparison study or an equivalent study.

The qualified laboratory results shall be compared to the criteria established in the NRC Inspection Manual (Procedure 84750) for Radioactive Waste Treatment, Effluent, and Environmental Monitoring. The referenced criteria is as follows:

a) Divide each standard result by its associated uncertainty to obtain resolution (the uncertainty is defined as the relative standard deviation, one sigma, of the standard result as calculated from counting statistics).

b) Divide each laboratory result by the corresponding standard result to obtain the ratio (laboratory result/standard).

c) The laboratory measurement is in agreement if the value of the ratio falls within the limits shown below for the corresponding resolution:

Resolution Ratio

<4 0.4 - 2.5 4-7 0.5 - 2.0 8 - 15 0.6 - 1.66 16 - 50 0.75 - 1.33 51 -200 0.80 - 1.25

>200 0.85 - 1.28 If the qualified laboratory results lay outside the ratio criteria, an evaluation will be performed to identify any recommended remedial actions to reduce anomalous errors. Complete documentation of the evaluation will be available to HNP and will be provided to the NRC upon request.

5-1 Page 9-131

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 6.0 TOTAL DOSE (COMPLIANCE WITH 40 CFR 190) for ODCM OR 3.11.4 Compliance with 40 CFR 190 as prescribed in ODCM Operational Requirement 3.11.4 must be demonstrated only when one or more of ODCM Operational Requirements 3.11.1.2a, 3.11.1.2b, 3.11.2.2a, 3.11.2.2b, 3.11.2.3a, or 3.11.2.3b is exceeded by a factor of two. Once this occurs, the company has 30 days to submit this report in accordance with Technical Specification 6.9.2.

ODCM Operational Requirement 3.11.4 requires that the annual dose or dose commitment to a member of the public from uranium fuel cycle sources be limited to 25 mrem for the whole body and any organ except the thyroid which is limited to 75 mrem. In addition, assessment of radiation doses to the likely most exposed member of the public from primary effluent pathways, direct radiation, and any other nearby uranium fuel cycle sources are to be included.

The dose estimates from the gas and liquid effluent pathways to the likely most exposed member of the public can be obtained by using the Regulatory Guide 1.109 and WASH 1258-based NRC codes LADTAP II and GASPAR. This will allow the use of current annual average meteorology X/Q and D/Q values derived from the NRC XOQDOQ (NUREG/CR-2919) Code that is appropriate for the specific location of the receptor and the applicable exposure pathways.

Radiation exposures of members of the public from direct radiation sources (the reactor unit and other primary system components, radwaste, radioactivity in auxiliary systems such as storage tanks, transportation of radioactive material, etc.) will be determined from TLD measurements.

Quarterly TLD measurements at locations within three miles of the plant center (inner ring) will be compared with the four-year, pre-operational TLD measurements using methods contained in NBS Handbook 91, "Experimental Statistics," to determine any significant contribution from direct radiation associated with plant operation.

If there is a significant direct radiation component at the TLD location in the sector containing the likely most exposed member of the public then this dose will be added to the doses from effluent pathways derived from LADTAP II and GASPAR.

6.1 Total Dose (COMPLIANCE WITH 40 CFR 190)for ODCM OR F.2 To demonstrate compliance with ODCM Operational Requirement F.2, the ODCM dose equations for noble gases, iodines, particulates, and tritium are used. They provide conservative dose estimates. The X/Q and D/Q valves are based on historical data for the exclusion boundary distances. The liquid dose estimates also use the ODCM equations for dose determination which are added together for demonstration of compliance with 40 CFR 190.

6-1 Page 9-132

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 7.0 LICENSEE-INITIATED CHANGES TO THE ODCM Changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained as required by Technical Specification 6.14. This documentation shall contain:

1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and

2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b. Shall become effective after review and acceptance by the PNSC and the approval of the Plant General Manager.

c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the areas of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.

7-1 Page 9-133

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 A.0 Appendix A Duke Energy has performed the assessment of the transport and dispersion of the effluent in the atmosphere as outlined in Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, NUREG 0133 (USNRC,1978). The methodology for this assessment was based on guidelines presented in Regulatory Guide 1.111. Revision 1 (USRNC,1977). The results of the assessment were to provide the relative deposition flux and relative concentrations (undepleted and depleted) based on numerical models acceptable for use in Appendix I evaluations.

Regulatory Guide 1.111 presented three acceptable diffusion models for use in estimating deposition flux and concentrations. These are:

1. Particle-in-cell model (a variable trajectory model based on the gradient-transport theory),

2. Puff-advection model (a variable trajectory model based on the statistical approach to diffusion),

and

3. The constant mean wind direction model referred to here as the straight-line trajectory Gaussian diffusion model (the most widely used model based on a statistical approach). It was resolved that for operational efficiency, the straight-line method described in XOQDOQ Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations, NUREG/CRG-2919 (USNRC, September 1982) would be used for generating the required analysis of Appendix I to provide a more realistic accounting of the variability of wind around the plant site, standard open-terrain recirculation factors were used.

A five-year record of meteorological data was used from the on-site meteorological program at the Shearon Harris Nuclear Power Plant. This data consisted of all collected parameters from the 12.5 meter level for years 2010-2014. The description of the model used and computations are presented in NUREG/CRC-2919. The following tables provide the meteorological dispersion factors (i.e. concentration (X/Q) and deposition (D/Q) values) utilized to show compliance with ODCM Operational Requirement 3/4.11.2 for noble gases, radioiodines and particulates.

A-1 Page 9-134

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 A.1 Changes to X/Q and D/Q modeling Along with updating the ODCM with X/Q and D/Q values using 2010-2014 meteorological data, there were some changes to the XOQDOQ modeling setup based on interpretations of Regulatory Guide 1.111 and NUREG/CRC-2919. The most notable of these changes was to increase the number of wind speed classes from 7 to 13, concentrating more classes for lower wind speeds.

Wind speed classes:

Previous: Current:

1) Calm 1) Calm

2) 0.45-0.75 mph 2) 0.45-0.75 m/s

3) 0.75-3.50 mph 3) 0.75-1.00 m/s

4) 3.50-7.50 mph 4) 1.00-1.25 m/s

5) 7.50-12.50 mph 5) 1.25-1.50 m/s

6) 12.50-18.50 mph 6) 1.50-2.00 m/s

7) 18.50-25.00 mph 7) 2.00-3.00 m/s

8) 25.00 + mph 8) 3.00-4.00 m/s

9) 4.00-5.00 m/s 10 5.00-6.00 m/s

11) 6.00-8.00 m/s

12) 8.00-10.00 m/s

13) 10.00+ m/s Tables A-1 through A-4 Relative undepleted concentration, relative depleted concentration, and relative deposition flux estimates for the ground level releases for special receptors for long-term releases.

Tables A-5 through A-12 Relative undepleted concentration, relative depleted concentration, and relative deposition flux estimates for the ground level releases for standard and segmented distance locations for long-term releases.

Table A-13 SHNPP on-site Joint Wind Frequency Distributions for years 2010-2014.

Table A-14 The NRC XOQDOQ program input is presented. XOQDOQ was obtained and installed on Duke Energys computer system. This model is part of the NRCs NRCDose program, version 2.3.20. The program was run with appropriate physical plant data and included special receptor locations noted by the annual landuse census. The open-terrain recirculation factors were applied within the model.

A-2 Page 9-135

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Tables A-1 through A-4 X/Q and D/Q Values for Routine Ground Level Releases (Special Receptor Locations)

Model: XOQDOQ - SHNP 10 meter Meteorological Data, 2010-2014 Corrected using Standard Open-Terrain factors TABLE A-1 TABLE A-2 TABLE A-3 TABLE A-4 Type of Receptor Direction Distance X/Q X/Q X/Q D/Q From Site (miles) sec m-3 sec m-3 sec m-3 1/m2 No Decay 2.3 Day Decay 8 Day Decay Undepleted Undepleted Depleted SITE BOUNDARY S 1.36 9.4E-06 9.1E-06 8.0E-06 7.7E-09 SITE BOUNDARY SSW 1.33 1.0E-05 1.0E-05 8.7E-06 9.0E-09 SITE BOUNDARY SW 1.33 1.8E-05 1.7E-05 1.5E-05 9.0E-09 SITE BOUNDARY WSW 1.33 1.1E-05 1.1E-05 9.5E-06 6.1E-09 SITE BOUNDARY W 1.33 5.3E-06 5.1E-06 4.5E-06 3.2E-09 SITE BOUNDARY WNW 1.33 2.6E-06 2.6E-06 2.3E-06 2.4E-09 SITE BOUNDARY NW 1.26 3.6E-06 3.5E-06 3.1E-06 3.3E-09 SITE BOUNDARY NNW 1.26 3.5E-06 3.4E-06 3.0E-06 4.2E-09 SITE BOUNDARY N 1.32 3.8E-06 3.7E-06 3.3E-06 5.9E-09 SITE BOUNDARY NNE 1.33 5.1E-06 5.0E-06 4.3E-06 8.3E-09 SITE BOUNDARY NE 1.33 5.6E-06 5.4E-06 4.7E-06 7.5E-09 SITE BOUNDARY ENE 1.33 5.4E-06 5.3E-06 4.6E-06 7.2E-09 SITE BOUNDARY E 1.33 4.5E-06 4.4E-06 3.9E-06 4.6E-09 SITE BOUNDARY ESE 1.33 3.4E-06 3.3E-06 2.9E-06 4.3E-09 SITE BOUNDARY SE 1.33 4.0E-06 3.9E-06 3.4E-06 4.9E-09 SITE BOUNDARY SSE 1.33 5.8E-06 5.7E-06 5.0E-06 5.7E-09 RESIDENT SSW 3.82 1.4E-06 1.3E-06 1.0E-06 7.3E-10 RESIDENT SW 2.76 4.4E-06 4.1E-06 3.4E-06 1.5E-09 RESIDENT WSW 4.29 1.3E-06 1.1E-06 9.4E-07 3.8E-10 RESIDENT W 2.75 1.3E-06 1.2E-06 1.0E-06 5.6E-10 RESIDENT WNW 2.13 1.0E-06 9.7E-07 8.2E-07 7.5E-10 RESIDENT NW 2.24 1.1E-06 1.0E-06 8.8E-07 8.0E-10 RESIDENT NNW 1.55 2.2E-06 2.2E-06 1.9E-06 2.5E-09 RESIDENT N 2.21 1.3E-06 1.3E-06 1.1E-06 1.7E-09 RESIDENT NNE 1.81 2.6E-06 2.6E-06 2.2E-06 3.9E-09 RESIDENT NE 2.43 1.6E-06 1.6E-06 1.3E-06 1.7E-09 RESIDENT ENE 1.78 3.0E-06 2.9E-06 2.5E-06 3.5E-09 RESIDENT E 1.98 2.0E-06 1.9E-06 1.6E-06 1.7E-09 RESIDENT ESE 2.73 8.1E-07 7.7E-07 6.4E-07 7.6E-10 RESIDENT SE 4.11 4.6E-07 4.2E-07 3.4E-07 3.4E-10 RESIDENT SSE 4.26 6.4E-07 5.9E-07 4.8E-07 3.6E-10 A-3 Page 9-136

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Tables A-1 through A-4 X/Q and D/Q Values for Routine Ground Level Releases (Special Receptor Locations)

Model: XOQDOQ - SHNP 10 meter Meteorological Data, 2010-2014 Corrected using Standard Open-Terrain factors TABLE A-1 TABLE A-2 TABLE A-3 TABLE A-4 Type of Receptor Direction Distance X/Q X/Q X/Q D/Q From Site (miles) sec m-3 sec m-3 sec m-3 1/m2 No Decay 2.3 Day Decay 8 Day Decay Undepleted Undepleted Depleted GARDEN SSW 4.20 1.2E-06 1.1E-06 8.8E-07 5.9E-10 GARDEN SW 2.80 4.2E-06 4.0E-06 3.3E-06 1.5E-09 GARDEN WSW 4.29 1.3E-06 1.1E-06 9.4E-07 3.8E-10 GARDEN W 3.73 7.4E-07 6.8E-07 5.6E-07 2.8E-10 GARDEN WNW 3.39 4.2E-07 3.9E-07 3.2E-07 2.5E-10 GARDEN NW 3.17 5.7E-07 5.3E-07 4.4E-07 3.6E-10 GARDEN NNW 1.82 1.6E-06 1.5E-06 1.3E-06 1.7E-09 GARDEN N 2.21 1.3E-06 1.3E-06 1.1E-06 1.7E-09 GARDEN NNE 1.91 2.4E-06 2.3E-06 2.0E-06 3.4E-09 GARDEN NE 3.22 9.7E-07 9.1E-07 7.5E-07 9.0E-10 GARDEN ENE 2.06 2.2E-06 2.1E-06 1.8E-06 2.5E-09 GARDEN ESE 4.76 3.0E-07 2.8E-07 2.2E-07 2.2E-10 GARDEN SE 4.11 4.6E-07 4.2E-07 3.4E-07 3.4E-10 GARDEN SSE 4.26 6.4E-07 5.9E-07 4.8E-07 3.6E-10 MEAT ANIMAL SSW 3.93 1.3E-06 1.2E-06 9.9E-07 6.9E-10 MEAT ANIMAL SW 2.80 4.2E-06 4.0E-06 3.3E-06 1.5E-09 MEAT ANIMAL WSW 4.29 1.3E-06 1.1E-06 9.4E-07 3.8E-10 MEAT ANIMAL W 3.26 9.4E-07 8.7E-07 7.2E-07 3.8E-10 MEAT ANIMAL WNW 2.13 1.0E-06 9.7E-07 8.2E-07 7.5E-10 MEAT ANIMAL NW 2.24 1.1E-06 1.0E-06 8.8E-07 8.0E-10 MEAT ANIMAL NNW 1.82 1.6E-06 1.5E-06 1.3E-06 1.7E-09 MEAT ANIMAL N 2.21 1.3E-06 1.3E-06 1.1E-06 1.7E-09 MEAT ANIMAL NNE 1.91 2.4E-06 2.3E-06 2.0E-06 3.4E-09 MEAT ANIMAL NE 3.22 9.7E-07 9.1E-07 7.5E-07 9.0E-10 MEAT ANIMAL ENE 2.01 2.3E-06 2.2E-06 1.9E-06 2.6E-09 MEAT ANIMAL ESE 2.74 8.1E-07 7.7E-07 6.4E-07 7.6E-10 MEAT ANIMAL SE 4.11 4.6E-07 4.2E-07 3.4E-07 3.4E-10 MEAT ANIMAL SSE 4.57 5.7E-07 5.2E-07 4.2E-07 3.1E-10 A-4 Page 9-137

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Table A-5 Undepleted, no decay, X/Q values for Ground Level Routine Release at standard distances in sec m-3 Annual Average X/Q Distance in miles from the site Sector 0.25 0.5 0.75 1 1.5 2 2.5 3 3.5 4 4.5 S 2.611E-04 7.818E-05 3.882E-05 1.920E-05 7.644E-06 4.346E-06 2.856E-06 2.050E-06 1.563E-06 1.243E-06 1.021E-06 SSW 2.698E-04 8.112E-05 4.041E-05 1.998E-05 7.945E-06 4.509E-06 2.959E-06 2.122E-06 1.616E-06 1.284E-06 1.054E-06 SW 4.894E-04 1.442E-04 7.057E-05 3.460E-05 1.372E-05 7.874E-06 5.207E-06 3.758E-06 2.876E-06 2.295E-06 1.890E-06 WSW 3.013E-04 8.921E-05 4.401E-05 2.172E-05 8.656E-06 4.945E-06 3.260E-06 2.347E-06 1.792E-06 1.428E-06 1.174E-06 W 1.375E-04 4.124E-05 2.060E-05 1.021E-05 4.072E-06 2.311E-06 1.517E-06 1.088E-06 8.284E-07 6.584E-07 5.403E-07 WNW 6.379E-05 1.967E-05 1.009E-05 5.083E-06 2.043E-06 1.142E-06 7.407E-07 5.265E-07 3.979E-07 3.142E-07 2.564E-07 NW 7.673E-05 2.375E-05 1.221E-05 6.115E-06 2.443E-06 1.366E-06 8.861E-07 6.299E-07 4.762E-07 3.761E-07 3.070E-07 NNW 7.313E-05 2.287E-05 1.182E-05 5.951E-06 2.383E-06 1.326E-06 8.572E-07 6.076E-07 4.581E-07 3.611E-07 2.942E-07 N 8.759E-05 2.771E-05 1.446E-05 7.266E-06 2.897E-06 1.604E-06 1.033E-06 7.301E-07 5.493E-07 4.322E-07 3.515E-07 NNE 1.163E-04 3.682E-05 1.924E-05 9.723E-06 3.897E-06 2.156E-06 1.388E-06 9.805E-07 7.373E-07 5.797E-07 4.713E-07 NE 1.350E-04 4.174E-05 2.136E-05 1.073E-05 4.295E-06 2.402E-06 1.558E-06 1.108E-06 8.374E-07 6.614E-07 5.399E-07 ENE 1.342E-04 4.128E-05 2.100E-05 1.050E-05 4.189E-06 2.346E-06 1.524E-06 1.085E-06 8.210E-07 6.490E-07 5.302E-07 E 1.133E-04 3.465E-05 1.757E-05 8.770E-06 3.502E-06 1.969E-06 1.282E-06 9.145E-07 6.932E-07 5.488E-07 4.488E-07 ESE 8.409E-05 2.601E-05 1.329E-05 6.638E-06 2.646E-06 1.480E-06 9.609E-07 6.834E-07 5.168E-07 4.084E-07 3.334E-07 SE 9.933E-05 3.054E-05 1.549E-05 7.730E-06 3.082E-06 1.729E-06 1.124E-06 8.009E-07 6.064E-07 4.797E-07 3.921E-07 SSE 1.492E-04 4.526E-05 2.272E-05 1.130E-05 4.507E-06 2.545E-06 1.664E-06 1.190E-06 9.038E-07 7.168E-07 5.872E-07 Annual Average X/Q Distance in miles from the site Sector 5 7.5 10 15 20 25 30 35 40 45 50 S 8.590E-07 4.697E-07 3.175E-07 1.928E-07 1.357E-07 1.035E-07 8.298E-08 6.890E-08 5.868E-08 5.095E-08 4.491E-08 SSW 8.867E-07 4.840E-07 3.268E-07 1.982E-07 1.394E-07 1.062E-07 8.514E-08 7.067E-08 6.016E-08 5.222E-08 4.602E-08 SW 1.595E-06 8.806E-07 5.990E-07 3.667E-07 2.595E-07 1.987E-07 1.598E-07 1.331E-07 1.136E-07 9.879E-08 8.722E-08 WSW 9.896E-07 5.437E-07 3.686E-07 2.247E-07 1.586E-07 1.211E-07 9.731E-08 8.089E-08 6.896E-08 5.993E-08 5.286E-08 W 4.546E-07 2.481E-07 1.675E-07 1.015E-07 7.135E-08 5.436E-08 4.357E-08 3.615E-08 3.077E-08 2.671E-08 2.353E-08 WNW 2.146E-07 1.150E-07 7.670E-08 4.573E-08 3.179E-08 2.402E-08 1.912E-08 1.578E-08 1.337E-08 1.155E-08 1.014E-08 NW 2.571E-07 1.379E-07 9.202E-08 5.493E-08 3.822E-08 2.889E-08 2.302E-08 1.900E-08 1.611E-08 1.393E-08 1.223E-08 NNW 2.459E-07 1.311E-07 8.712E-08 5.170E-08 3.583E-08 2.701E-08 2.146E-08 1.768E-08 1.496E-08 1.292E-08 1.133E-08 N 2.934E-07 1.556E-07 1.031E-07 6.090E-08 4.209E-08 3.166E-08 2.512E-08 2.067E-08 1.747E-08 1.507E-08 1.321E-08 NNE 3.932E-07 2.082E-07 1.376E-07 8.114E-08 5.598E-08 4.204E-08 3.332E-08 2.739E-08 2.313E-08 1.993E-08 1.745E-08 NE 4.520E-07 2.424E-07 1.617E-07 9.652E-08 6.714E-08 5.075E-08 4.042E-08 3.337E-08 2.828E-08 2.445E-08 2.147E-08 ENE 4.443E-07 2.389E-07 1.598E-07 9.564E-08 6.669E-08 5.051E-08 4.029E-08 3.330E-08 2.825E-08 2.445E-08 2.149E-08 E 3.764E-07 2.032E-07 1.362E-07 8.178E-08 5.713E-08 4.333E-08 3.460E-08 2.863E-08 2.430E-08 2.105E-08 1.851E-08 ESE 2.793E-07 1.500E-07 1.002E-07 5.987E-08 4.170E-08 3.156E-08 2.516E-08 2.078E-08 1.762E-08 1.525E-08 1.340E-08 SE 3.286E-07 1.770E-07 1.185E-07 7.102E-08 4.957E-08 3.756E-08 2.998E-08 2.479E-08 2.104E-08 1.821E-08 1.601E-08 SSE 4.932E-07 2.676E-07 1.800E-07 1.086E-07 7.609E-08 5.783E-08 4.627E-08 3.834E-08 3.259E-08 2.825E-08 2.487E-08 A-5 Page 9-138

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Table A-6 Undepleted, no decay, X/Q values for Ground Level Routine Release at standard distances in sec m-3 Annual Average X/Q Segment Boundaries (miles from site)

Sector 0.5-1.0 1.0-2.0 2.0-3.0 3.0-4.0 4.0-5.0 5.0-10.0 10.0-20.0 20.0-30.0 30.0-40.0 40.0-50.0 S 3.884E-05 8.746E-06 2.931E-06 1.580E-06 1.027E-06 4.885E-07 1.951E-07 1.039E-07 6.903E-08 5.100E-08 SSW 4.038E-05 9.092E-06 3.037E-06 1.634E-06 1.060E-06 5.036E-07 2.006E-07 1.066E-07 7.080E-08 5.228E-08 SW 7.093E-05 1.576E-05 5.339E-06 2.907E-06 1.901E-06 9.143E-07 3.707E-07 1.994E-07 1.333E-07 9.888E-08 WSW 4.415E-05 9.911E-06 3.344E-06 1.812E-06 1.181E-06 5.650E-07 2.273E-07 1.216E-07 8.104E-08 5.999E-08 W 2.057E-05 4.654E-06 1.557E-06 8.378E-07 5.436E-07 2.581E-07 1.028E-07 5.457E-08 3.622E-08 2.673E-08 WNW 9.993E-06 2.318E-06 7.620E-07 4.027E-07 2.581E-07 1.201E-07 4.642E-08 2.413E-08 1.582E-08 1.157E-08 NW 1.207E-05 2.780E-06 9.115E-07 4.820E-07 3.090E-07 1.440E-07 5.575E-08 2.903E-08 1.905E-08 1.395E-08 NNW 1.167E-05 2.706E-06 8.824E-07 4.639E-07 2.962E-07 1.371E-07 5.252E-08 2.714E-08 1.773E-08 1.294E-08 N 1.421E-05 3.293E-06 1.064E-06 5.563E-07 3.539E-07 1.629E-07 6.191E-08 3.182E-08 2.072E-08 1.509E-08 NNE 1.892E-05 4.418E-06 1.430E-06 7.467E-07 4.745E-07 2.179E-07 8.251E-08 4.227E-08 2.746E-08 1.996E-08 NE 2.116E-05 4.883E-06 1.603E-06 8.476E-07 5.433E-07 2.531E-07 9.796E-08 5.099E-08 3.345E-08 2.448E-08 ENE 2.084E-05 4.772E-06 1.568E-06 8.309E-07 5.336E-07 2.494E-07 9.703E-08 5.074E-08 3.338E-08 2.448E-08 E 1.745E-05 3.991E-06 1.318E-06 7.014E-07 4.516E-07 2.119E-07 8.292E-08 4.352E-08 2.869E-08 2.107E-08 ESE 1.316E-05 3.015E-06 9.884E-07 5.231E-07 3.356E-07 1.566E-07 6.075E-08 3.170E-08 2.083E-08 1.527E-08 SE 1.539E-05 3.513E-06 1.156E-06 6.137E-07 3.945E-07 1.847E-07 7.203E-08 3.773E-08 2.484E-08 1.824E-08 SSE 2.265E-05 5.145E-06 1.709E-06 9.143E-07 5.908E-07 2.788E-07 1.100E-07 5.807E-08 3.841E-08 2.829E-08 A-6 Page 9-139

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Table A-7 Undepleted, 2.26 Day Decay, X/Q values for Ground Level Routine Release at standard distances in sec m-3 Annual Average X/Q Distance in miles from the site Sector 0.25 0.5 0.75 1 1.5 2 2.5 3 3.5 4 4.5 S 2.596E-04 7.730E-05 3.818E-05 1.878E-05 7.397E-06 4.158E-06 2.701E-06 1.917E-06 1.444E-06 1.136E-06 9.217E-07 SSW 2.683E-04 8.021E-05 3.975E-05 1.954E-05 7.687E-06 4.312E-06 2.797E-06 1.983E-06 1.493E-06 1.173E-06 9.512E-07 SW 4.863E-04 1.424E-04 6.927E-05 3.375E-05 1.323E-05 7.493E-06 4.893E-06 3.487E-06 2.635E-06 2.077E-06 1.689E-06 WSW 2.994E-04 8.813E-05 4.322E-05 2.121E-05 8.351E-06 4.712E-06 3.069E-06 2.182E-06 1.646E-06 1.295E-06 1.052E-06 W 1.367E-04 4.075E-05 2.025E-05 9.980E-06 3.933E-06 2.206E-06 1.430E-06 1.014E-06 7.628E-07 5.990E-07 4.857E-07 WNW 6.345E-05 1.947E-05 9.932E-06 4.981E-06 1.981E-06 1.096E-06 7.033E-07 4.945E-07 3.697E-07 2.888E-07 2.332E-07 NW 7.631E-05 2.351E-05 1.202E-05 5.991E-06 2.369E-06 1.310E-06 8.412E-07 5.916E-07 4.424E-07 3.457E-07 2.791E-07 NNW 7.276E-05 2.265E-05 1.165E-05 5.840E-06 2.317E-06 1.276E-06 8.167E-07 5.731E-07 4.277E-07 3.337E-07 2.691E-07 N 8.719E-05 2.747E-05 1.428E-05 7.142E-06 2.823E-06 1.548E-06 9.882E-07 6.920E-07 5.157E-07 4.019E-07 3.239E-07 NNE 1.158E-04 3.651E-05 1.900E-05 9.562E-06 3.800E-06 2.084E-06 1.330E-06 9.307E-07 6.935E-07 5.403E-07 4.353E-07 NE 1.343E-04 4.133E-05 2.106E-05 1.053E-05 4.175E-06 2.311E-06 1.485E-06 1.045E-06 7.817E-07 6.112E-07 4.938E-07 ENE 1.335E-04 4.087E-05 2.070E-05 1.030E-05 4.069E-06 2.256E-06 1.450E-06 1.022E-06 7.650E-07 5.985E-07 4.838E-07 E 1.127E-04 3.429E-05 1.730E-05 8.590E-06 3.395E-06 1.888E-06 1.216E-06 8.581E-07 6.433E-07 5.037E-07 4.074E-07 ESE 8.366E-05 2.576E-05 1.309E-05 6.510E-06 2.570E-06 1.423E-06 9.143E-07 6.435E-07 4.816E-07 3.766E-07 3.043E-07 SE 9.880E-05 3.022E-05 1.526E-05 7.576E-06 2.990E-06 1.659E-06 1.068E-06 7.525E-07 5.636E-07 4.410E-07 3.566E-07 SSE 1.483E-04 4.477E-05 2.236E-05 1.106E-05 4.367E-06 2.439E-06 1.577E-06 1.115E-06 8.375E-07 6.568E-07 5.320E-07 Annual Average X/Q Distance in miles from the site Sector 5 7.5 10 15 20 25 30 35 40 45 50 S 7.669E-07 3.957E-07 2.525E-07 1.367E-07 8.591E-08 5.860E-08 4.213E-08 3.142E-08 2.409E-08 1.887E-08 1.505E-08 SSW 7.909E-07 4.072E-07 2.593E-07 1.400E-07 8.780E-08 5.976E-08 4.287E-08 3.190E-08 2.441E-08 1.908E-08 1.518E-08 SW 1.407E-06 7.292E-07 4.657E-07 2.514E-07 1.571E-07 1.063E-07 7.569E-08 5.585E-08 4.232E-08 3.274E-08 2.575E-08 WSW 8.760E-07 4.525E-07 2.885E-07 1.557E-07 9.735E-08 6.600E-08 4.712E-08 3.487E-08 2.652E-08 2.059E-08 1.627E-08 W 4.037E-07 2.074E-07 1.319E-07 7.092E-08 4.429E-08 3.002E-08 2.145E-08 1.589E-08 1.210E-08 9.412E-09 7.449E-09 WNW 1.931E-07 9.804E-08 6.195E-08 3.319E-08 2.077E-08 1.416E-08 1.019E-08 7.616E-09 5.860E-09 4.611E-09 3.694E-09 NW 2.312E-07 1.175E-07 7.425E-08 3.980E-08 2.491E-08 1.697E-08 1.220E-08 9.119E-09 7.011E-09 5.512E-09 4.414E-09 NNW 2.227E-07 1.128E-07 7.119E-08 3.816E-08 2.393E-08 1.635E-08 1.180E-08 8.859E-09 6.844E-09 5.408E-09 4.353E-09 N 2.678E-07 1.355E-07 8.556E-08 4.604E-08 2.903E-08 1.997E-08 1.452E-08 1.099E-08 8.556E-09 6.819E-09 5.537E-09 NNE 3.599E-07 1.820E-07 1.149E-07 6.190E-08 3.909E-08 2.694E-08 1.964E-08 1.489E-08 1.163E-08 9.296E-09 7.571E-09 NE 4.093E-07 2.085E-07 1.322E-07 7.131E-08 4.491E-08 3.081E-08 2.232E-08 1.681E-08 1.302E-08 1.032E-08 8.336E-09 ENE 4.011E-07 2.046E-07 1.298E-07 6.998E-08 4.403E-08 3.015E-08 2.180E-08 1.637E-08 1.265E-08 9.996E-09 8.045E-09 E 3.380E-07 1.726E-07 1.095E-07 5.893E-08 3.696E-08 2.521E-08 1.815E-08 1.356E-08 1.043E-08 8.198E-09 6.562E-09 ESE 2.522E-07 1.285E-07 8.141E-08 4.384E-08 2.756E-08 1.886E-08 1.362E-08 1.023E-08 7.898E-09 6.238E-09 5.018E-09 SE 2.956E-07 1.508E-07 9.558E-08 5.142E-08 3.226E-08 2.201E-08 1.586E-08 1.186E-08 9.130E-09 7.185E-09 5.758E-09 SSE 4.419E-07 2.266E-07 1.441E-07 7.774E-08 4.879E-08 3.328E-08 2.394E-08 1.788E-08 1.373E-08 1.078E-08 8.614E-09 A-7 Page 9-140

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Table A-8 Undepleted, 2.26 Day Decay, X/Q values for Ground Level Routine Release at standard distances in sec m-3 Segment Boundaries (miles from site)

Sector 0.5-1.0 1.0-2.0 2.0-3.0 3.0-4.0 4.0-5.0 5.0-10.0 10.0-20.0 20.0-30.0 30.0-40.0 40.0-50.0 S 3.825E-05 8.487E-06 2.776E-06 1.462E-06 9.277E-07 4.145E-07 1.399E-07 5.930E-08 3.169E-08 1.900E-08 SSW 3.976E-05 8.822E-06 2.876E-06 1.511E-06 9.574E-07 4.267E-07 1.433E-07 6.048E-08 3.218E-08 1.921E-08 SW 6.973E-05 1.524E-05 5.024E-06 2.666E-06 1.699E-06 7.627E-07 2.571E-07 1.076E-07 5.637E-08 3.299E-08 WSW 4.342E-05 9.591E-06 3.152E-06 1.666E-06 1.059E-06 4.737E-07 1.593E-07 6.680E-08 3.519E-08 2.075E-08 W 2.024E-05 4.509E-06 1.471E-06 7.721E-07 4.889E-07 2.174E-07 7.263E-08 3.040E-08 1.603E-08 9.481E-09 WNW 9.851E-06 2.254E-06 7.244E-07 3.745E-07 2.348E-07 1.031E-07 3.406E-08 1.433E-08 7.682E-09 4.641E-09 NW 1.189E-05 2.704E-06 8.665E-07 4.482E-07 2.811E-07 1.235E-07 4.083E-08 1.718E-08 9.197E-09 5.550E-09 NNW 1.151E-05 2.637E-06 8.418E-07 4.334E-07 2.711E-07 1.187E-07 3.918E-08 1.655E-08 8.933E-09 5.443E-09 N 1.404E-05 3.216E-06 1.019E-06 5.227E-07 3.262E-07 1.427E-07 4.726E-08 2.021E-08 1.107E-08 6.859E-09 NNE 1.869E-05 4.318E-06 1.371E-06 7.029E-07 4.385E-07 1.917E-07 6.355E-08 2.726E-08 1.501E-08 9.349E-09 NE 2.088E-05 4.758E-06 1.529E-06 7.919E-07 4.973E-07 2.192E-07 7.311E-08 3.117E-08 1.694E-08 1.039E-08 ENE 2.056E-05 4.647E-06 1.494E-06 7.749E-07 4.871E-07 2.150E-07 7.174E-08 3.051E-08 1.650E-08 1.006E-08 E 1.720E-05 3.880E-06 1.252E-06 6.515E-07 4.102E-07 1.813E-07 6.041E-08 2.552E-08 1.368E-08 8.253E-09 ESE 1.298E-05 2.936E-06 9.416E-07 4.878E-07 3.064E-07 1.350E-07 4.496E-08 1.909E-08 1.031E-08 6.278E-09 SE 1.517E-05 3.418E-06 1.099E-06 5.709E-07 3.590E-07 1.584E-07 5.271E-08 2.228E-08 1.196E-08 7.233E-09 SSE 2.232E-05 4.998E-06 1.622E-06 8.479E-07 5.356E-07 2.378E-07 7.962E-08 3.368E-08 1.803E-08 1.085E-08 A-8 Page 9-141

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Table A-9 Depleted, 8 Day Decay, X/Q values for Ground Level Routine Release at standard distances in sec m-3 Annual Average X/Q Distance in miles from the site Sector 0.25 0.5 0.75 1 1.5 2 2.5 3 3.5 4 4.5 S 2.467E-04 7.116E-05 3.443E-05 1.670E-05 6.431E-06 3.554E-06 2.277E-06 1.598E-06 1.192E-06 9.299E-07 7.496E-07 SSW 2.550E-04 7.384E-05 3.584E-05 1.738E-05 6.685E-06 3.687E-06 2.359E-06 1.653E-06 1.233E-06 9.608E-07 7.740E-07 SW 4.624E-04 1.312E-04 6.256E-05 3.007E-05 1.153E-05 6.429E-06 4.144E-06 2.922E-06 2.189E-06 1.713E-06 1.384E-06 WSW 2.847E-04 8.119E-05 3.902E-05 1.889E-05 7.277E-06 4.039E-06 2.596E-06 1.826E-06 1.365E-06 1.066E-06 8.606E-07 W 1.299E-04 3.753E-05 1.827E-05 8.882E-06 3.425E-06 1.889E-06 1.208E-06 8.470E-07 6.315E-07 4.921E-07 3.964E-07 WNW 6.028E-05 1.791E-05 8.949E-06 4.424E-06 1.720E-06 9.346E-07 5.913E-07 4.108E-07 3.040E-07 2.355E-07 1.887E-07 NW 7.250E-05 2.163E-05 1.083E-05 5.322E-06 2.057E-06 1.118E-06 7.072E-07 4.915E-07 3.639E-07 2.819E-07 2.259E-07 NNW 6.911E-05 2.083E-05 1.049E-05 5.182E-06 2.008E-06 1.086E-06 6.849E-07 4.746E-07 3.506E-07 2.710E-07 2.169E-07 N 8.279E-05 2.524E-05 1.284E-05 6.329E-06 2.442E-06 1.315E-06 8.263E-07 5.712E-07 4.210E-07 3.249E-07 2.596E-07 NNE 1.099E-04 3.354E-05 1.708E-05 8.471E-06 3.286E-06 1.768E-06 1.111E-06 7.673E-07 5.653E-07 4.362E-07 3.483E-07 NE 1.276E-04 3.801E-05 1.896E-05 9.339E-06 3.619E-06 1.967E-06 1.245E-06 8.654E-07 6.407E-07 4.964E-07 3.979E-07 ENE 1.268E-04 3.759E-05 1.864E-05 9.138E-06 3.528E-06 1.921E-06 1.217E-06 8.472E-07 6.279E-07 4.869E-07 3.905E-07 E 1.071E-04 3.155E-05 1.559E-05 7.632E-06 2.948E-06 1.611E-06 1.023E-06 7.134E-07 5.295E-07 4.111E-07 3.301E-07 ESE 7.947E-05 2.369E-05 1.179E-05 5.778E-06 2.229E-06 1.212E-06 7.674E-07 5.336E-07 3.952E-07 3.063E-07 2.456E-07 SE 9.387E-05 2.780E-05 1.375E-05 6.728E-06 2.595E-06 1.415E-06 8.975E-07 6.250E-07 4.635E-07 3.595E-07 2.885E-07 SSE 1.410E-04 4.120E-05 2.016E-05 9.832E-06 3.794E-06 2.082E-06 1.327E-06 9.278E-07 6.901E-07 5.368E-07 4.317E-07 Annual Average X/Q Distance in miles from the site Sector 5 7.5 10 15 20 25 30 35 40 45 50 S 6.200E-07 3.153E-07 1.998E-07 1.086E-07 6.939E-08 4.848E-08 3.584E-08 2.755E-08 2.180E-08 1.763E-08 1.451E-08 SSW 6.398E-07 3.248E-07 2.055E-07 1.115E-07 7.118E-08 4.968E-08 3.670E-08 2.819E-08 2.229E-08 1.801E-08 1.481E-08 SW 1.148E-06 5.884E-07 3.746E-07 2.047E-07 1.312E-07 9.180E-08 6.790E-08 5.220E-08 4.128E-08 3.336E-08 2.742E-08 WSW 7.126E-07 3.638E-07 2.309E-07 1.258E-07 8.047E-08 5.623E-08 4.156E-08 3.193E-08 2.525E-08 2.040E-08 1.677E-08 W 3.276E-07 1.662E-07 1.051E-07 5.695E-08 3.631E-08 2.532E-08 1.868E-08 1.434E-08 1.132E-08 9.143E-09 7.511E-09 WNW 1.552E-07 7.746E-08 4.846E-08 2.592E-08 1.640E-08 1.137E-08 8.364E-09 6.404E-09 5.051E-09 4.075E-09 3.347E-09 NW 1.859E-07 9.285E-08 5.813E-08 3.112E-08 1.970E-08 1.367E-08 1.005E-08 7.700E-09 6.073E-09 4.900E-09 4.025E-09 NNW 1.782E-07 8.852E-08 5.522E-08 2.943E-08 1.858E-08 1.288E-08 9.462E-09 7.241E-09 5.710E-09 4.606E-09 3.784E-09 N 2.131E-07 1.054E-07 6.561E-08 3.489E-08 2.202E-08 1.526E-08 1.122E-08 8.594E-09 6.784E-09 5.480E-09 4.508E-09 NNE 2.858E-07 1.412E-07 8.776E-08 4.660E-08 2.938E-08 2.035E-08 1.495E-08 1.145E-08 9.040E-09 7.303E-09 6.008E-09 NE 3.275E-07 1.637E-07 1.025E-07 5.495E-08 3.483E-08 2.421E-08 1.783E-08 1.368E-08 1.080E-08 8.731E-09 7.183E-09 ENE 3.216E-07 1.611E-07 1.011E-07 5.431E-08 3.448E-08 2.399E-08 1.768E-08 1.357E-08 1.072E-08 8.662E-09 7.125E-09 E 2.721E-07 1.367E-07 8.595E-08 4.625E-08 2.939E-08 2.045E-08 1.507E-08 1.156E-08 9.128E-09 7.372E-09 6.061E-09 ESE 2.022E-07 1.011E-07 6.340E-08 3.401E-08 2.157E-08 1.499E-08 1.105E-08 8.470E-09 6.690E-09 5.405E-09 4.445E-09 SE 2.377E-07 1.192E-07 7.483E-08 4.022E-08 2.553E-08 1.775E-08 1.308E-08 1.003E-08 7.921E-09 6.397E-09 5.259E-09 SSE 3.563E-07 1.799E-07 1.135E-07 6.131E-08 3.904E-08 2.721E-08 2.008E-08 1.541E-08 1.218E-08 9.844E-09 8.096E-09 A-9 Page 9-142

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Table A-10 Depleted, 8 Day Decay, X/Q values for Ground Level Routine Release at standard distances in sec m-3 Segment Boundaries (miles from site)

Sector 0.5-1.0 1.0-2.0 2.0-3.0 3.0-4.0 4.0-5.0 5.0-10.0 10.0-20.0 20.0-30.0 30.0-40.0 40.0-50.0 S 3.471E-05 7.435E-06 2.346E-06 1.208E-06 7.550E-07 3.316E-07 1.114E-07 4.900E-08 2.773E-08 1.771E-08 SSW 3.608E-05 7.729E-06 2.431E-06 1.249E-06 7.796E-07 3.418E-07 1.145E-07 5.022E-08 2.837E-08 1.809E-08 SW 6.337E-05 1.339E-05 4.265E-06 2.217E-06 1.394E-06 6.176E-07 2.098E-07 9.276E-08 5.253E-08 3.351E-08 WSW 3.944E-05 8.418E-06 2.673E-06 1.383E-06 8.667E-07 3.822E-07 1.290E-07 5.683E-08 3.214E-08 2.049E-08 W 1.838E-05 3.955E-06 1.245E-06 6.399E-07 3.992E-07 1.749E-07 5.847E-08 2.560E-08 1.443E-08 9.185E-09 WNW 8.930E-06 1.972E-06 6.106E-07 3.084E-07 1.902E-07 8.186E-08 2.670E-08 1.151E-08 6.448E-09 4.094E-09 NW 1.078E-05 2.365E-06 7.304E-07 3.691E-07 2.277E-07 9.810E-08 3.204E-08 1.383E-08 7.753E-09 4.923E-09 NNW 1.043E-05 2.304E-06 7.078E-07 3.557E-07 2.186E-07 9.365E-08 3.034E-08 1.303E-08 7.292E-09 4.628E-09 N 1.270E-05 2.805E-06 8.545E-07 4.273E-07 2.617E-07 1.116E-07 3.600E-08 1.545E-08 8.654E-09 5.506E-09 NNE 1.691E-05 3.764E-06 1.149E-06 5.738E-07 3.512E-07 1.496E-07 4.810E-08 2.060E-08 1.153E-08 7.338E-09 NE 1.892E-05 4.156E-06 1.286E-06 6.499E-07 4.010E-07 1.729E-07 5.658E-08 2.449E-08 1.377E-08 8.772E-09 ENE 1.863E-05 4.061E-06 1.257E-06 6.368E-07 3.936E-07 1.701E-07 5.590E-08 2.426E-08 1.366E-08 8.702E-09 E 1.560E-05 3.395E-06 1.056E-06 5.369E-07 3.326E-07 1.442E-07 4.758E-08 2.068E-08 1.164E-08 7.407E-09 ESE 1.176E-05 2.566E-06 7.925E-07 4.009E-07 2.475E-07 1.068E-07 3.501E-08 1.517E-08 8.528E-09 5.430E-09 SE 1.375E-05 2.989E-06 9.265E-07 4.700E-07 2.907E-07 1.258E-07 4.138E-08 1.796E-08 1.010E-08 6.427E-09 SSE 2.024E-05 4.375E-06 1.369E-06 6.996E-07 4.349E-07 1.896E-07 6.300E-08 2.751E-08 1.552E-08 9.890E-09 A-10 Page 9-143

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Table A-11 2

Deposition values (D/Q) for Ground Level Routine Release at standard distances in per m Distance in miles from the site Sector 0.25 0.5 0.75 1 1.5 2 2.5 3 3.5 4 4.5 S 2.043E-07 6.909E-08 3.547E-08 1.687E-08 6.058E-09 3.004E-09 1.769E-09 1.158E-09 8.150E-10 6.040E-10 4.655E-10 SSW 2.243E-07 7.584E-08 3.894E-08 1.851E-08 6.649E-09 3.298E-09 1.942E-09 1.271E-09 8.946E-10 6.630E-10 5.109E-10 SW 2.249E-07 7.606E-08 3.905E-08 1.857E-08 6.669E-09 3.307E-09 1.947E-09 1.275E-09 8.973E-10 6.650E-10 5.124E-10 WSW 1.520E-07 5.141E-08 2.640E-08 1.255E-08 4.508E-09 2.235E-09 1.316E-09 8.619E-10 6.065E-10 4.494E-10 3.464E-10 W 8.074E-08 2.730E-08 1.402E-08 6.665E-09 2.394E-09 1.187E-09 6.990E-10 4.577E-10 3.221E-10 2.387E-10 1.839E-10 WNW 5.925E-08 2.003E-08 1.029E-08 4.890E-09 1.757E-09 8.712E-10 5.130E-10 3.359E-10 2.363E-10 1.752E-10 1.350E-10 NW 7.104E-08 2.402E-08 1.233E-08 5.864E-09 2.106E-09 1.045E-09 6.151E-10 4.027E-10 2.834E-10 2.100E-10 1.618E-10 NNW 9.208E-08 3.114E-08 1.599E-08 7.601E-09 2.730E-09 1.354E-09 7.973E-10 5.220E-10 3.673E-10 2.722E-10 2.098E-10 N 1.450E-07 4.905E-08 2.518E-08 1.197E-08 4.300E-09 2.133E-09 1.256E-09 8.223E-10 5.786E-10 4.288E-10 3.304E-10 NNE 2.084E-07 7.048E-08 3.619E-08 1.720E-08 6.180E-09 3.065E-09 1.805E-09 1.182E-09 8.315E-10 6.162E-10 4.749E-10 NE 1.864E-07 6.302E-08 3.236E-08 1.538E-08 5.526E-09 2.740E-09 1.614E-09 1.057E-09 7.434E-10 5.509E-10 4.246E-10 ENE 1.809E-07 6.118E-08 3.141E-08 1.493E-08 5.364E-09 2.660E-09 1.566E-09 1.026E-09 7.217E-10 5.348E-10 4.121E-10 E 1.151E-07 3.892E-08 1.999E-08 9.501E-09 3.413E-09 1.693E-09 9.966E-10 6.526E-10 4.592E-10 3.403E-10 2.622E-10 ESE 1.081E-07 3.655E-08 1.877E-08 8.922E-09 3.205E-09 1.589E-09 9.358E-10 6.128E-10 4.312E-10 3.195E-10 2.462E-10 SE 1.221E-07 4.129E-08 2.120E-08 1.008E-08 3.620E-09 1.795E-09 1.057E-09 6.922E-10 4.871E-10 3.610E-10 2.782E-10 SSE 1.413E-07 4.778E-08 2.453E-08 1.166E-08 4.189E-09 2.078E-09 1.223E-09 8.010E-10 5.636E-10 4.177E-10 3.219E-10 Distance in miles from the site Sector 5 7.5 10 15 20 25 30 35 40 45 50 S 3.698E-10 1.643E-10 9.951E-11 5.030E-11 3.044E-11 2.041E-11 1.463E-11 1.098E-11 8.539E-12 6.821E-12 5.567E-12 SSW 4.059E-10 1.803E-10 1.092E-10 5.521E-11 3.341E-11 2.240E-11 1.605E-11 1.205E-11 9.373E-12 7.487E-12 6.111E-12 SW 4.071E-10 1.809E-10 1.096E-10 5.537E-11 3.351E-11 2.247E-11 1.610E-11 1.209E-11 9.401E-12 7.509E-12 6.129E-12 WSW 2.752E-10 1.222E-10 7.404E-11 3.743E-11 2.265E-11 1.519E-11 1.088E-11 8.172E-12 6.354E-12 5.075E-12 4.143E-12 W 1.461E-10 6.492E-11 3.932E-11 1.988E-11 1.203E-11 8.066E-12 5.779E-12 4.340E-12 3.374E-12 2.695E-12 2.200E-12 WNW 1.072E-10 4.763E-11 2.886E-11 1.458E-11 8.827E-12 5.919E-12 4.241E-12 3.185E-12 2.476E-12 1.978E-12 1.614E-12 NW 1.286E-10 5.712E-11 3.460E-11 1.749E-11 1.058E-11 7.097E-12 5.085E-12 3.818E-12 2.969E-12 2.372E-12 1.936E-12 NNW 1.667E-10 7.404E-11 4.485E-11 2.267E-11 1.372E-11 9.199E-12 6.592E-12 4.950E-12 3.848E-12 3.074E-12 2.509E-12 N 2.625E-10 1.166E-10 7.064E-11 3.570E-11 2.161E-11 1.449E-11 1.038E-11 7.796E-12 6.062E-12 4.842E-12 3.952E-12 NNE 3.772E-10 1.676E-10 1.015E-10 5.131E-11 3.106E-11 2.082E-11 1.492E-11 1.120E-11 8.711E-12 6.958E-12 5.680E-12 NE 3.373E-10 1.498E-10 9.076E-11 4.588E-11 2.777E-11 1.862E-11 1.334E-11 1.002E-11 7.788E-12 6.221E-12 5.078E-12 ENE 3.274E-10 1.455E-10 8.811E-11 4.453E-11 2.695E-11 1.807E-11 1.295E-11 9.724E-12 7.561E-12 6.039E-12 4.930E-12 E 2.083E-10 9.255E-11 5.606E-11 2.834E-11 1.715E-11 1.150E-11 8.240E-12 6.187E-12 4.811E-12 3.843E-12 3.137E-12 ESE 1.956E-10 8.691E-11 5.264E-11 2.661E-11 1.610E-11 1.080E-11 7.737E-12 5.810E-12 4.517E-12 3.608E-12 2.945E-12 SE 2.210E-10 9.817E-11 5.947E-11 3.006E-11 1.819E-11 1.220E-11 8.740E-12 6.563E-12 5.103E-12 4.076E-12 3.327E-12 SSE 2.557E-10 1.136E-10 6.882E-11 3.478E-11 2.105E-11 1.412E-11 1.011E-11 7.595E-12 5.905E-12 4.717E-12 3.850E-12 A-11 Page 9-144

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Table A-12 2

Deposition values (D/Q) for Ground Level Routine Release at standard distances in per m Segment Boundaries (miles from site)

Sector 0.5-1.0 1.0-2.0 2.0-3.0 3.0-4.0 4.0-5.0 5.0-10.0 10.0-20.0 20.0-30.0 30.0-40.0 40.0-50.0 S 3.467E-08 7.102E-09 1.854E-09 8.327E-10 4.711E-10 1.812E-10 5.241E-11 2.077E-11 1.109E-11 6.866E-12 SSW 3.806E-08 7.796E-09 2.035E-09 9.140E-10 5.171E-10 1.988E-10 5.753E-11 2.280E-11 1.218E-11 7.536E-12 SW 3.817E-08 7.819E-09 2.041E-09 9.168E-10 5.186E-10 1.994E-10 5.770E-11 2.287E-11 1.221E-11 7.559E-12 WSW 2.580E-08 5.285E-09 1.380E-09 6.196E-10 3.505E-10 1.348E-10 3.900E-11 1.546E-11 8.254E-12 5.109E-12 W 1.370E-08 2.807E-09 7.327E-10 3.291E-10 1.862E-10 7.159E-11 2.071E-11 8.208E-12 4.383E-12 2.713E-12 WNW 1.005E-08 2.059E-09 5.376E-10 2.415E-10 1.366E-10 5.253E-11 1.520E-11 6.023E-12 3.216E-12 1.991E-12 NW 1.206E-08 2.469E-09 6.447E-10 2.895E-10 1.638E-10 6.299E-11 1.822E-11 7.222E-12 3.857E-12 2.387E-12 NNW 1.563E-08 3.201E-09 8.356E-10 3.753E-10 2.123E-10 8.165E-11 2.362E-11 9.362E-12 4.999E-12 3.094E-12 N 2.461E-08 5.042E-09 1.316E-09 5.911E-10 3.344E-10 1.286E-10 3.720E-11 1.475E-11 7.874E-12 4.874E-12 NNE 3.537E-08 7.245E-09 1.891E-09 8.495E-10 4.806E-10 1.848E-10 5.346E-11 2.119E-11 1.132E-11 7.004E-12 NE 3.163E-08 6.478E-09 1.691E-09 7.595E-10 4.297E-10 1.652E-10 4.780E-11 1.895E-11 1.012E-11 6.262E-12 ENE 3.070E-08 6.289E-09 1.642E-09 7.373E-10 4.171E-10 1.604E-10 4.640E-11 1.839E-11 9.822E-12 6.079E-12 E 1.953E-08 4.001E-09 1.045E-09 4.691E-10 2.654E-10 1.021E-10 2.953E-11 1.170E-11 6.249E-12 3.868E-12 ESE 1.834E-08 3.757E-09 9.809E-10 4.405E-10 2.492E-10 9.584E-11 2.773E-11 1.099E-11 5.868E-12 3.632E-12 SE 2.072E-08 4.244E-09 1.108E-09 4.976E-10 2.815E-10 1.083E-10 3.132E-11 1.241E-11 6.629E-12 4.103E-12 SSE 2.398E-08 4.912E-09 1.282E-09 5.759E-10 3.258E-10 1.253E-10 3.624E-11 1.436E-11 7.671E-12 4.748E-12 A-12 Page 9-145

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Table A-13 Joint Wind Frequency Distribution by Pasquill Stability Classes at SHNP (2010-2014 meteorological data, 12.5 meter level)

Stability Class A Umax N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 0.45 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.75 0 0 0 0 0 0 0 0 0 0 0 0 0 0.002 0 0 0.002 1 0 0 0 0.002 0.005 0 0 0 0 0 0 0 0 0 0 0 0.007 1.25 0.002 0 0.005 0.002 0 0.002 0 0 0 0.002 0.002 0 0 0.002 0 0 0.018 1.5 0 0 0.005 0.002 0 0 0.005 0.002 0 0.002 0.002 0 0.005 0 0.005 0 0.028 2 0.002 0 0 0.009 0 0.002 0 0.007 0.002 0 0.005 0.009 0.005 0.002 0.002 0.002 0.048 3 0 0.014 0.028 0.035 0.012 0.002 0 0.007 0.007 0.012 0.012 0.025 0.012 0.005 0.005 0.002 0.175 4 0.005 0.018 0.023 0.018 0.002 0 0.002 0.012 0.023 0.009 0.007 0.037 0.016 0.002 0.009 0.002 0.186 5 0.002 0.014 0.007 0.002 0.005 0 0 0 0.007 0.007 0.012 0.007 0.002 0.002 0.005 0.002 0.074 6 0 0.002 0 0 0 0 0 0 0 0 0.005 0.007 0.002 0 0.002 0.002 0.021 8 0 0 0 0 0 0 0 0 0 0 0.002 0.002 0 0 0 0 0.005 10 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.9 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 0.01 0.05 0.07 0.07 0.02 0.01 0.01 0.03 0.04 0.03 0.05 0.09 0.04 0.02 0.03 0.01 0.56 Stability Class B Umax N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 0.45 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.75 0 0 0 0.002 0.002 0.002 0.002 0 0 0 0 0 0 0 0 0 0.009 1 0 0 0 0 0 0 0 0 0 0.002 0.002 0.002 0 0.002 0 0.005 0.014 1.25 0.002 0 0.002 0.002 0.002 0 0 0 0 0 0.002 0.005 0 0 0.005 0.005 0.025 1.5 0.002 0.005 0.009 0.009 0.005 0.002 0.002 0.005 0 0 0.002 0.005 0.005 0.005 0.002 0.002 0.06 2 0.007 0.012 0.023 0.03 0.021 0.018 0.005 0.012 0.018 0.014 0.007 0.016 0.012 0.007 0.009 0.007 0.216 3 0.044 0.071 0.134 0.076 0.025 0.007 0.018 0.032 0.046 0.044 0.035 0.076 0.028 0.028 0.028 0.016 0.707 4 0.005 0.067 0.041 0.032 0.005 0.009 0.005 0.009 0.085 0.067 0.062 0.104 0.023 0.021 0.023 0.016 0.573 5 0.009 0.018 0.012 0.009 0 0.002 0 0 0.021 0.016 0.032 0.032 0.016 0.007 0.012 0.012 0.198 6 0.009 0.002 0.002 0.002 0 0 0 0 0.005 0.005 0.023 0.007 0.005 0.016 0.005 0.005 0.085 8 0 0 0.002 0 0 0 0 0 0 0 0.002 0.002 0.002 0.002 0.002 0 0.014 10 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.9 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 0.08 0.17 0.23 0.16 0.06 0.04 0.03 0.06 0.17 0.15 0.17 0.25 0.09 0.09 0.09 0.07 1.9 A-13 Page 9-146

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Table A-13 (continue)

Joint Wind Frequency Distribution by Pasquill Stability Classes at SHNP (2010-2014 meteorological data, 12.5 meter level)

Stability Class C Umax N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 0.45 0.003 0.001 0 0 0 0.001 0.002 0 0.001 0.001 0.001 0.001 0.002 0 0.004 0 0.016 0.75 0.007 0.002 0 0 0 0.002 0.005 0 0.002 0.002 0.002 0.002 0.005 0 0.009 0 0.039 1 0.007 0.005 0.007 0.002 0.007 0.007 0.005 0.009 0.005 0.007 0.005 0.007 0.005 0.014 0.005 0.002 0.097 1.25 0.012 0.012 0.014 0.007 0.012 0.018 0.009 0.007 0.016 0.009 0.007 0.014 0.014 0.005 0.002 0 0.157 1.5 0.023 0.018 0.037 0.032 0.012 0.018 0.018 0.005 0.03 0.016 0.009 0.023 0.016 0.03 0.016 0.023 0.327 2 0.046 0.051 0.064 0.099 0.039 0.032 0.039 0.037 0.048 0.046 0.055 0.069 0.062 0.037 0.067 0.053 0.845 3 0.087 0.26 0.191 0.157 0.074 0.053 0.048 0.113 0.219 0.175 0.11 0.322 0.129 0.099 0.145 0.127 2.309 4 0.085 0.127 0.087 0.03 0.005 0.012 0.009 0.023 0.124 0.131 0.127 0.292 0.099 0.11 0.124 0.09 1.476 5 0.028 0.039 0.014 0 0 0 0 0.002 0.023 0.062 0.046 0.062 0.023 0.032 0.046 0.039 0.417 6 0.002 0.014 0.005 0 0 0 0 0.002 0 0.012 0.018 0.005 0.007 0.012 0.009 0.002 0.087 8 0 0 0 0 0 0 0 0 0 0 0.002 0 0.002 0.007 0.005 0 0.016 10 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.9 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 0.3 0.53 0.42 0.33 0.15 0.14 0.14 0.2 0.47 0.46 0.38 0.8 0.36 0.35 0.43 0.34 5.78 Stability Class D Umax N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 0.45 0.038 0.063 0.082 0.058 0.042 0.034 0.047 0.041 0.047 0.08 0.055 0.041 0.054 0.051 0.042 0.055 0.831 0.75 0.067 0.11 0.143 0.101 0.074 0.06 0.083 0.071 0.083 0.14 0.097 0.071 0.094 0.09 0.074 0.097 1.455 1 0.207 0.226 0.237 0.198 0.152 0.11 0.129 0.12 0.117 0.161 0.122 0.129 0.127 0.12 0.099 0.154 2.408 1.25 0.23 0.216 0.207 0.138 0.122 0.092 0.115 0.163 0.173 0.157 0.163 0.159 0.108 0.122 0.127 0.163 2.456 1.5 0.311 0.279 0.272 0.193 0.122 0.157 0.143 0.182 0.209 0.292 0.274 0.244 0.189 0.175 0.182 0.258 3.481 2 0.693 0.799 0.571 0.405 0.251 0.244 0.304 0.389 0.504 0.661 0.573 0.615 0.329 0.237 0.352 0.456 7.382 3 1.462 1.563 0.882 0.433 0.26 0.209 0.343 0.64 1.091 1.16 1.128 1.186 0.61 0.453 0.829 0.937 13.186 4 0.605 0.734 0.401 0.166 0.023 0.078 0.076 0.189 0.467 0.737 0.757 0.702 0.371 0.465 0.603 0.506 6.881 5 0.163 0.209 0.087 0.018 0.012 0.007 0.005 0.044 0.115 0.421 0.357 0.299 0.15 0.336 0.311 0.134 2.668 6 0.028 0.067 0.021 0.002 0 0.002 0 0.023 0.048 0.182 0.152 0.113 0.055 0.147 0.076 0.023 0.939 8 0.005 0.009 0 0 0 0 0 0.009 0.03 0.06 0.064 0.035 0.018 0.064 0.021 0.012 0.327 10 0 0 0 0 0 0 0 0 0 0 0 0.002 0 0.012 0 0 0.014 13.9 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 3.81 4.28 2.9 1.71 1.06 0.99 1.24 1.87 2.89 4.05 3.74 3.6 2.1 2.27 2.71 2.79 42.03 A-14 Page 9-147

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Table A-13 (continue)

Joint Wind Frequency Distribution by Pasquill Stability Classes at SHNP (2010-2014 meteorological data, 12.5 meter level)

Stability Class E Umax N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 0.45 0.164 0.207 0.302 0.249 0.169 0.103 0.149 0.106 0.169 0.166 0.156 0.156 0.136 0.108 0.116 0.128 2.585 0.75 0.15 0.189 0.276 0.228 0.154 0.094 0.136 0.097 0.154 0.152 0.143 0.143 0.124 0.099 0.106 0.117 2.362 1 0.205 0.239 0.244 0.209 0.145 0.129 0.161 0.184 0.198 0.182 0.182 0.166 0.198 0.161 0.122 0.134 2.859 1.25 0.221 0.258 0.18 0.173 0.136 0.099 0.113 0.154 0.12 0.228 0.154 0.198 0.177 0.124 0.106 0.127 2.567 1.5 0.32 0.304 0.203 0.237 0.136 0.11 0.203 0.182 0.2 0.306 0.256 0.256 0.138 0.124 0.12 0.173 3.266 2 0.472 0.467 0.237 0.163 0.15 0.157 0.168 0.315 0.479 0.559 0.474 0.387 0.239 0.196 0.219 0.279 4.961 3 0.336 0.419 0.244 0.145 0.076 0.076 0.048 0.161 0.472 1.054 0.741 0.35 0.228 0.246 0.232 0.348 5.177 4 0.046 0.053 0.046 0.021 0.007 0.009 0.012 0.009 0.134 0.447 0.193 0.078 0.046 0.081 0.062 0.11 1.354 5 0.005 0.014 0.002 0 0 0.002 0.002 0 0.016 0.081 0.069 0.023 0.021 0.016 0.012 0.007 0.269 6 0.005 0.005 0 0 0 0 0 0 0.005 0.028 0.009 0.012 0 0.002 0.005 0 0.069 8 0.007 0 0 0 0 0 0 0 0 0.007 0.005 0 0 0 0 0.002 0.021 10 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.9 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 1.93 2.15 1.73 1.43 0.97 0.78 0.99 1.21 1.95 3.21 2.38 1.77 1.31 1.16 1.1 1.42 25.49 Stability Class F Umax N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 0.45 0.281 0.286 0.44 0.367 0.168 0.132 0.095 0.127 0.091 0.195 0.227 0.181 0.159 0.095 0.136 0.2 3.179 0.75 0.143 0.145 0.223 0.186 0.085 0.067 0.048 0.064 0.046 0.099 0.115 0.092 0.081 0.048 0.069 0.101 1.614 1 0.173 0.122 0.152 0.152 0.062 0.074 0.058 0.039 0.083 0.076 0.099 0.11 0.074 0.092 0.071 0.11 1.547 1.25 0.11 0.087 0.048 0.101 0.053 0.023 0.046 0.03 0.051 0.081 0.06 0.078 0.064 0.055 0.053 0.081 1.022 1.5 0.154 0.094 0.03 0.048 0.025 0.014 0.039 0.044 0.055 0.069 0.078 0.101 0.058 0.058 0.062 0.058 0.988 2 0.12 0.074 0.039 0.03 0.014 0.009 0.012 0.025 0.051 0.131 0.069 0.074 0.032 0.023 0.025 0.051 0.778 3 0.018 0.021 0.005 0.007 0.005 0 0.005 0.002 0.018 0.037 0.025 0.028 0.012 0.009 0.002 0.007 0.2 4 0 0.002 0 0 0 0 0 0 0 0 0 0.002 0.002 0.005 0 0.005 0.016 5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 10 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.9 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 1 0.83 0.94 0.89 0.41 0.32 0.3 0.33 0.39 0.69 0.67 0.67 0.48 0.39 0.42 0.61 9.34 A-15 Page 9-148

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Table A-13 (continue)

Joint Wind Frequency Distribution by Pasquill Stability Classes at SHNP (2010-2014 meteorological data, 12.5 meter level)

Stability Class G Umax N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 0.45 1.23 1.266 2.698 1.504 0.633 0.191 0.263 0.215 0.239 0.275 0.43 0.478 0.43 0.298 0.37 0.621 11.139 0.75 0.237 0.244 0.52 0.29 0.122 0.037 0.051 0.041 0.046 0.053 0.083 0.092 0.083 0.058 0.071 0.12 2.148 1 0.092 0.085 0.136 0.134 0.037 0.037 0.016 0.012 0.028 0.046 0.058 0.041 0.035 0.032 0.035 0.048 0.87 1.25 0.041 0.039 0.048 0.03 0.009 0.007 0.016 0.007 0.018 0.018 0.044 0.018 0.021 0.009 0.007 0.03 0.364 1.5 0.044 0.016 0.016 0.009 0.007 0 0.005 0.005 0.009 0.009 0.025 0.016 0.009 0.005 0.007 0.025 0.207 2 0.048 0.018 0.009 0.002 0.007 0.002 0.005 0.002 0.009 0.007 0.012 0.002 0.005 0 0.005 0.012 0.145 3 0.002 0.002 0 0.002 0 0 0 0 0.005 0.002 0 0 0 0 0 0 0.014 4 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 5 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 6 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 10 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13.9 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 TOTAL 1.69 1.67 3.43 1.97 0.81 0.27 0.35 0.28 0.35 0.41 0.65 0.65 0.58 0.4 0.49 0.86 14.89 TOTAL HOURS CONSIDERED: 43441 hours from January 2010 to December 2014 WIND MEASURED AT 12.5 METERS OVERALL WIND DIRECTION FREQUENCY DIRECTION: N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW FREQUENCY(%): 8.8 9.7 9.7 6.6 3.5 2.6 3.1 4.0 6.3 9.0 8.0 7.8 5.0 4.7 5.3 6.1 WIND SPEED CLASS DETAILS MAX WIND SPEED (UMAX) (M/S): .450 .750 1.000 1.250 1.500 2.000 3.000 4.000 5.000 6.000 8.000 10.000 13.900 AVE WIND SPEED (M/S): .225 .600 .875 1.125 1.375 1.750 2.500 3.500 4.500 5.500 7.000 9.000 11.950 WIND SPEED FREQUENCY %): 17.75 7.63 7.80 6.61 8.36 14.38 21.77 10.49 3.63 1.20 .38 .01 .00 A-16 Page 9-149

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Table A-14 Shearon Harris Plant Site XOQDOQ Model Input Information for Continuous Ground Level Releases Card Type Columns Variable Name Format Description Value used in XOQDOQ Card Type 1 is an array (KOPT) of options, such that 1 = DO, 0 = BYPASS.

These options remain in effect for all release points run. Thus, all release points must have the same assumptions.

1 1 KOPT(1) I1 Option to distribute calms as the first wind-speed class (if calms are already 1 distributed by direction in Card Type 6, KOPT(1) = 0, and Card Type 5 is blank). If KOPT(1) = 1, the calm values of Card Type 5 are distributed by direction in the same proportion as the direction frequency of wind-speed class two.

1 2 KOPT(2) I1 Option to input joint frequency distribution data as percent frequency. 0 1 3 KOPT(3) I1 Option to compute a sector spread for comparison with centerline value in 0 purge calculation (Normally = 1).

1 4 KOPT(4) I1 Option to plot short-term X/Q values versus probability of occurrence 0 (Normally = 0).

1 5 KOPT(5) I1 Option to use cubic spline in lieu of least square function for fitting 0 intermittent release distribution (Normally = 1).

1 6 KOPT(6) I1 Option to punch radial segment X/Q and D/Q values (Normally = 1). 1 1 7 KOPT(7) I1 Option to punch output of X/Q and D/Q values of the points of interest 1 (Normally = 1).

1 8 KOPT(8) I1 Option to correct X/Q and D/Q values for open terrain recirculation. 1 1 9 KOPT(9) I1 Option to correct X/Q and D/Q values using site specific terrain recirculation 0 data.

A-17 Page 9-150

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Table A-14 Shearon Harris Plant Site XOQDOQ Model Input Information for Continuous Ground Level Releases Card Type Columns Variable Name Format Description Value used in XOQDOQ 1 10 KOPT(10) I1 Option to use desert sigma curves (Normally = 0) 0 1 11 KOPT(11) I1 Option to calculate annual X/Q with 30 degree sectors for North, East, 0 South and West and 20 degree sectors for all others. (Normally = 0, and the code will use 22-1/2 degree sectors) 2 1 - 80 TITLM 20A4 The main title printed at the beginning of the output. N/A 3 1-5 NVEL I5 The number of velocity categories (maximum of 14). 13 3 6 - 10 NSTA I5 The number of stability categories (maximum of 7) (1 always equals 7 Pasquill stability class A, 2 = B, ..., 7 = G).

3 11 - 15 NDIS I5 The number of distances with terrain data for each sector. The number 0 of distances must be the same for each sector (Card Type 10) (maximum of 10).

3 16 - 20 INC I5 The increment in percent for which plotted results are printed out 15 (Normally = 15).

3 21 - 25 NPTYPE I5 The number of titles of receptor types (cow, garden, etc.) (Card Type 13) 4 (maximum of eight) 3 26 - 30 NEXIT I5 The number of release exit points (maximum of five). 1 3 31 - 35 NCOR I5 The number of distances of site specific correction factors for 0 recirculation (maximum of 10).

4 1-5 PLEV F5.0 The height (in meters, above ground level) of the measured wind 12.5 presented in the joint frequency data (Card Type 7). (For elevated/ground-level mixed release, use the lower level winds).

A-18 Page 9-151

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Table A-14 Shearon Harris Plant Site XOQDOQ Model Input Information for Continuous Ground Level Releases Card Type Columns Variable Name Format Description Value used in XOQDOQ 4 6 - 20 DECAYS(I) 3F5.0 For each I: The half-life (days) used in the X/Q calculations: if DECAYS > 101.00 I = 1,3 100, no decay will occur; if DECAYS < 0, depletion factor will be used in 2.26 the X/Q calculations; if DECAYS = 0, X/Q will not be calculated. (Normally, -8.00 DECAYS(1) = 101, (2) = 2.26, (3) = -8.00.)

4 21 - 25 PLGRAD F5.0 Plant grade elevation (feet above sea level). If PLGRAD = 0.0, DIST and 0 HT data Card Type 10 and 11 must be in meters. If PLGRAD < 0.0, DIST in miles and HT data in feet above plant grade. If PLGRAD > 0.0 above DIST in miles and HT data in feet above sea level.

5 1 - 35 CALM(I) 7F5.0 The number of hours, or percent, of calm for each stability category; if Determined by onsite I = 1,NSTA KOPT(1) = 0, insert blank card. (Note: I = 1 is stability class A, 2 = B, ..., 7 MET Data

= G).

6 1 - 80 FREQ(K,I,J) The joint frequency distribution in hours (or percent). The values for 16 (K) JFD K = 1,16 sectors are read on each card for each combination of wind-speed class (I)

I = 1,NVEL (if and stability class (J). The loop to read these value cycles first on direction KOPT(1)=0) continuing in a clockwise fashion), then on wind class and finally on stability I = 2,NVEL (if class.

KOPT(1)=1)

J = 1,NSTA 7 1-5 UCOR F5.0 A correction factor applied to wind-speed classes. If UCOR < 0: no -1 corrections will be made. If UCOR > 100: the wind-speed classes will be converted from miles/hour to meters/second.

A-19 Page 9-152

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Table A-14 Shearon Harris Plant Site Input Information for Continuous Ground Level Releases Card Type Columns Variable Name Format Description Value used in XOQDOQ 7 6 - 75 UMAX(I) 14F5.0 The maximum wind speed in each wind-speed class, in either See Table A-13 (UMAX) miles/hour or meters/second. (If given in miles/hour, set UCOR >

100.)

Card Types 8 and 9 are read in for each correction factor and distance given, I = 1,NCOR 8 1 - 80 VRDIST(K,I) 16F5.0 The distance in meters at which correction factors are given. These SKIP K = 1,16 values are read in beginning with south and proceeding in a clockwise direction (maximum of 10).

9 1 - 80 VRCD(K,I) 16F5.0 Correction factor to be applied to X/Q and D/Q values corresponds SKIP K = 1,16 to distances specified in VRDIST.

Card Types 8 and 9 are repeated for the remaining distances and correction factors.

Card Types 10 and 11 are read in for each terrain distance and height given, I = 1,NDIS 10 1 - 80 DIST(K,I) 16F5.0 The distance in meters at which terrain heights are given. These SKIP K = 1,16 values are read in beginning with south and proceeding in a clockwise direction (maximum of ten distances).

11 1 - 80 HT(K,I) 16F5.0 The terrain heights (in meters, above plant grade level) SKIP K = 1,16 corresponding to the distances specified in the DIST array (Card Type 10). These values are read in the same order as the DIST array. For a given direction and distance, the terrain height should be the highest elevation between the source and that distance anywhere within the direction sector.

Card Types 10 and 11 are repeated for the remaining distances and heights.

A-20 Page 9-153

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Table A-14 Shearon Harris Plant Site Input Information for Continuous Ground Level Releases Card Type Columns Variable Name Format Description Value used in XOQDOQ 12 1 - 25 NPOINT(I) 5I5 The number (maximum of 30) of receptor locations for a particular receptor 16,15,14,14 I = 1,NPTYPE type (such as the number of cows, gardens, or site boundaries).

Card Types 13 and 14 are read in for each receptor type, thus I = 1,NPTYPE 13 1 - 16 TITLPT(I,J) 4A4 The title (cows, gardens, etc.) of the receptor type for the receptor Site Boundary = 16 locations (Card Type 14) (a maximum of 16 spaces). Nearest Resident = 15 Garden = 14 Meat Animal = 14 14 1 - 80 KDIR(I,N) 8(I5,F5.0) The receptor direction and distance. KDIR is the direction of interest, such See Table A-1 PTDIST(I,N) that 1 = South, 2 = SSW......, 16 = SSE, PTDIST is the distance, in meters, N = 1,NPOINT(I) to the receptor location.

Card Types 13 and 14 are repeated for the remaining receptor types (See annual Land Use Census).

Card Types 15, 16 and 17 are read in for each plant release point, thus I = 1,NEXIT.

15 1 - 80 TITLE(I,J) 20A4 The title for the release point whose characteristics are described on Card Turbine Building Types 16 and 17.

16 1-5 EXIT(I) F5.0 The vent average velocity (meters/second). (Note: if a 100% ground-level 0 release is assumed, set EXIT = 0, DIAMTR = 0, and SLEV = 10 meters).

16 6 - 10 DIAMTR F5.0 The vent inside diameter (meters). 0 16 11 - 15 HSTACK(I) F5.0 The height of the vent release point (meters, plant grade level). If release 0.0 is 100% elevated, input negative of height.

16 16 - 20 HBLDG(I) F5.0 The height of the vents building (meters, above plant grade level). 55.0 A-21 Page 9-154

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 Table A-14 Card Type Columns Variable Name Format Description Value used in XOQDOQ 16 21 - 25 CRSEC(I) F5.0 The minimum cross-sectional area for the vents building (square meters). 2161.0 16 26 - 30 SLEV(I) F5.0 The wind height used for the vent elevated release (meters, above plant 12.5 grade level).

16 31 - 35 HEATR(I) F5.0 The vent heat emission rate (cal/sec) (Normally = 0). 0.0 17 1 RLSID(I) A1 A one letter identification for the release point. G 17 2-5 IPURGE(I) I4 IPURGE = 1, 2 or 3 if the vent has intermittent releases. The 1, 2, or 3 0 corresponds to DECAYS(1), DECAYS(2), or DECAYS(3) (Card Type 4),

respectively, whichever is used as the base for intermittent release calculations (normally no decay/no deplete X/Q, such that IPURGE(I) = 1; if a vent has no intermittent releases, IPURGE = 0.

17 6 - 10 NPURGE(I) I5 The number of intermittent releases per year for this release point. 0 17 11 - 15 NPRGHR(I) I5 The average number of hours per intermittent release. 0 Card Types 15, 16, and 17 are repeated for the remaining release points.

Card Types 1 - 17 may be repeated for the next case.

A-22 Page 9-155

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 B.0 APPENDIX B DOSE PARAMETERS FOR RADIOIODINES, PARTICULATES, AND TRITIUM This appendix contains the methodology which was used to calculate the dose parameters for radioiodines, particulates, and tritium to show compliance with ODCM Operational Requirement 3.11.2.1.b and Appendix I of 10CFR50 for gaseous effluents. These dose parameters, Pi and Ri, were calculated using the methodology outlined in NUREG 0133 along with Regulatory Guide 1.109, Revision 1. The following sections provide the specific methodology which was utilized in calculating the Pi and Ri values for the various exposure pathways (Tables 3.2-4 and 3.3-1 through 3.3-19, respectively).

B.1 Calculation of Pi The dose parameter, Pi, contained in the radioiodine and particulates portion of Section 3.2 includes only the inhalation pathway transport parameter of the "i" radionuclide, the receptor's usage of the pathway media, and the dosimetry of the exposure. Inhalation rates and the internal dosimetry are functions of the receptor's age; however, under the exposure conditions for ODCM Operational Requirement 3.11.2.1b, the child is considered to receive the highest dose. The following sections provide in detail the methodology which was used in calculating the Pi values for inclusion into this ODCM.

The age group considered is the child because the bases for the ODCM Operational Requirement 3.11.2.1.b is to restrict the dose to the child's thyroid via inhalation to 1500 mrem/yr. The child's breathing rate is taken as 3700 3

m /yr from Table E-5 of Regulatory Guide 1.109, Revision 1. The inhalation dose factors for the child, DFAi, are presented in Table E-9 of Regulatory Guide 1.109 in units of mrem/pCi.

The dose factor from the inhalation pathway is calculated by P = K'(BR) DFAi (B.1-1) iI where:

P = Dose factor for radionuclide "i" for the inhalation pathway, mrem/yr per Ci/m3, per organ of iI interest K' = A constant of unit conversion; 6

= 10 pCi/Ci; BR = The breathing rate of the children's age group, m3/yr; DFAi = The organ inhalation dose factor for the children's age group for radionuclide "i," mrem/pCi.

3 The incorporation of breathing rate of a child (3700 m /yr) and the unit conversion factor results in the following equation:

P = 3.7 E+09 DFAi (B.1-2) iI B-1 Page 9-156

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 B.2 Calculation of Ri The basis for ODCM Operational Requirement 3.11.2.3 states that conformance with the guidance in Appendix I should be shown by calculational procedures based on models and data such that the actual exposure of a member of the public through appropriate pathways is unlikely to be substantially underestimated. Underestimation of the dose can be avoided by assigning a theoretical individual to the exclusion boundary in the sector with the highest X/Q and D/Q values and employing all of the likely exposure pathways, e.g., inhalation, cow milk, meat, vegetation, and ground plane. Ri values have been calculated for the adult, teen, child, and infant age groups for the inhalation, ground plane, cow milk, goat milk, vegetable, and beef ingestion pathways. The methodology which was utilized to calculate these values is presented below.

B.2.1 Inhalation Pathway The dose factor from the inhalation pathway is calculated by:

R = K' (BR)a (DFAi)a (B.2-1) iI where:

R = Dose factor for each identified radionuclide "i" of the organ of interest, mrem/yr per Ci/m3; iI K' = A constant of unit conversion;

= 106 pCi/Ci; (BR)a = Breathing rate of the receptor of age group "a," m3/yr; (DFAi)a = Organ inhalation dose factor for radionuclide "i" for the receptor of age group "a", mrem/pCi.

The breathing rates (BR)a for the various age groups are tabulated below, as given in Table E-5 of Regulatory Guide 1.109, Revision 1.

3 Age Group (a) Breathing Rate (m /yr)

Infant 1400 Child 3700 Teen 8000 Adult 8000 Inhalation dose factors (DFAi)a for the various age groups are given in Tables E-7 through E-10 of Regulatory Guide 1.109, Revision 1.

B-2 Page 9-157

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 B.2.2 Ground Plane Pathway The ground plane pathway dose factor is calculated by:

it Ri = I K'K"(SF)DFG (1 e ) / i (B.2-2)

G i i where:

R = Dose factor for the ground plane pathway for each identified radionuclide "i" for the organ of iG

-2 interest, mrem/yr per Ci/sec per m ;

K' = A constant of unit conversion;

= 106 pCi/Ci; K" = A constant of unit conversion;

= 8760 hr/year; SF = The shielding factor (dimensionless);

(A shielding factor of 0.7 is suggested in Table E-15 of Regulatory Guide 1.109, Revision 1.)

2 DFGi = The ground plane dose conversion factor for radionuclide "i," mrem/hr per pCi/m ;

(A tabulation of DFGi values is presented in Table E-6 of Regulatory Guide 1.109, Revision 1.)

i = The radiological decay constant for radionuclide "i," sec-1; t = The exposure time, sec;

= 4.73 E+08 sec (15 years);

Ii = Factor to account for fractional deposition of radionuclide "i."

For radionuclides other than iodine, the factor Ii is equal to one. For radioiodines, the value of Ii may vary. However, a value of 1.0 was used in calculating the R values in Table 3.3-2. (Reference NUREG 0133)

B-3 Page 9-158

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 B.2.3 Grass Cow or Goat Milk Pathway The dose factor for the cow milk or goat milk pathway for each radionuclide for each organ is calculated by:

t t E e (1 e i b) t r(1 e i ) B iv Ri = I K Q U F (DFL ) e i f(f f ( + ) +

M i F ap m ia ps Y P p E i i

t t E e) B (1 e i b) r(1 e i iv t (1 f f ) ( + )e i h) ps Y P s E i i

(B.2-3) where:

R = Dose factor for the cow milk or goat milk pathway, for each identified radionuclide "i" for the organ of iM interest, mrem/yr per Ci/sec per m-2; K' = A constant of unit conversion;

= 106 pCi/Ci; QF = The cow's or goat's feed consumption rate, kg/day (wet weight);

U = The receptor's milk consumption rate for age group "a," liters/yr; ap Yp = The agricultural productivity by unit area of pasture feed grass, kg/m2; Ys = The agricultural productivity by unit area of stored feed, kg/m2; Fm = The stable element transfer coefficients, pCi/liter per pCi/day; r = Fraction of deposited activity retained on cow's feed grass; (DFLi)a = The organ ingestion dose for radionuclide "i" for the receptor in age group "a," mrem/pCi; B-4 Page 9-159

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 B.2.3 Grass Cow or Goat Milk Pathway (continued)

E = i + w; I

= The radiological decay constant for radionuclide "i," sec-1; i

= The decay constant for removal of activity on leaf and plant surfaces by weathering, sec-1; w

= 5.73 E-07 sec-1 (14 day half-life);

t = Period of pasture grass and crop exposure during the growing season, sec; e

t = The transport time from feed, to cow or goat, to milk, to receptor, sec; f

t = The transport time from pasture, to cow or goat, to milk to receptor, sec; h

t = Period of time that sediment is exposed to gaseous effluents, sec; b

B = Concentration factor for uptake of radionuclide "i" from the soil by the edible parts of crops, pCi/Kg iv (wet weight) per pCi/Kg (dry soil)

P = Effective surface density for soil, Kg (dry soil)/m2; f = Fraction of the year that the cow or goat is on pasture; (dimensionless).

p f = Fraction of the cow feed that is pasture grass while the cow is on pasture; s

(dimensionless).

t = Period of pasture grass and crop exposure during the growing season, sec; e

I = Factor to account for fractional deposition of radionuclide "i."

i For radionuclides other than iodine, the factor I is equal to one. For radioiodines, the value of I may i i vary. However, a value of 1.0 was used in calculating the R values in Tables 3.3-8 through 3.3-15.

(Reference NUREG 0133)

Milk cattle and goats are considered to be fed from two potential sources, pasture grass and stored feeds.

Following the development in Regulatory Guide 1.109, Revision 1, the value of fs was considered unity in lieu of site-specific information. The value of fp was 0.667 based upon an 8-month grazing period.

Table B-1 contains the appropriate parameter values and their source in Regulatory Guide 1.109, Revision B-5 Page 9-160

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 B.2.3 Grass Cow or Goat Milk Pathway (continued)

The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the Ri is based on X/Q:

R = K'KFmQFU (DFLi)a 0.75(0.5/H) (B.2-4)

TM ap where:

R = Dose factor for the cow or goat milk pathway for tritium for the organ of interest, mrem/yr per TM Ci/m3; K = A constant of unit conversion;

= 103 gm/kg; H = Absolute humidity of the atmosphere, gm/m3; A value of H = 8 grams/ meter3, was used in lieu of site-specific information.

0.75 = The fraction of total feed that is water; 0.5 = The ratio of the specific activity of the feed grass water to the atmospheric water.

and other parameters and values as previously defined.

B-6 Page 9-161

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 B.2.4 Grass-Cow-Meat Pathway The integrated concentration in meat follows in a similar manner to the development for the milk pathway; therefore:

t t E e (1 e i b) t r(1 e i ) B iv Ri = I K Q U F (DFL ) e i s(f f ( + ) +

B i F ap f ia p s Y P p E i i

t t E e) B (1 e i b) r(1 e i iv t (1 f f ) ( + ) e i h) p s Y P s E i i

(B.2.5) where:

R = Dose factor for the meat ingestion pathway for radionuclide "i" for any organ of interest, mrem/yr iB per Ci/sec per m-2; Ff = The stable element transfer coefficients, pCi/Kg per pCi/day; U = The receptor's meat consumption rate for age group "a," kg/yr; ap t = Transport time from slaughter to consumption, sec; s

t = Transport time from harvest to animal consumption, sec; h

t = Period of pasture grass and crop exposure during the growing season, sec; e

I = Factor to account for fractional deposition of radionuclide "i."

i For radionuclides other than iodine, Ii is equal to one. For radioiodines, the value of Ii may vary. However, a value of 1.0 was used in calculating the R values in Tables 3.3-5 through 3.3-7.

All other terms remain the same as defined in Equation B.2-3. Table B-2 contains the values which were used in calculating Ri for the meat pathway.

The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore, the Ri is based on X/Q.

R = K'KFf QF Uap (DFLi)a 0.75 (0.5/H) (B.2-6)

TB where:

R = Dose factor for the meat ingestion pathway for tritium for any organ of interest, mrem/yr per Ci/m3.

TB All other terms are defined in Equations B.2-4 and B.2-5.

B-7 Page 9-162

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 B.2.5 Vegetation Pathway The integrated concentration in vegetation consumed by man follows the expression developed in the derivation of the milk factor. Man is considered to consume two types of vegetation (fresh and stored) that differ only in the time period between harvest and consumption; therefore:

t t E t i L r(1 e i e) B (1 e i b)

L iv R iv = I K (DFL ) (U f e ( + ) +

i ia a L Y P v E i i

t t E e B (1 e i b)

S t r(1 e i ) iv U f e i h ( + ) )

a g Y P v E i i

(B.2-7) where:

R = Dose factor for vegetable pathway for radionuclide "i" for the organ of interest, mrem/yr per Ci/sec iV per m-2; K' = A constant of unit conversion; 6

= 10 pCi/Ci; UL = The consumption rate of fresh leafy vegetation by the receptor in age group "a," kg/yr; a

US = The consumption rate of stored vegetation by the receptor in age group "a," kg/yr; a

fL = The fraction of the annual intake of fresh leafy vegetation grown locally;

= 1.0 fg = The fraction of annual intake of stored vegetation grown locally;

= 0.76 tL = The average time between harvest of leafy vegetation and its consumption, sec; th = The average time between harvest of stored vegetation and its consumption, sec; 2

Yv = The vegetation a real density, kg/m ;

te = Period of leafy vegetable exposure during growing season, sec; Ii = Factor to account for fractional deposition of radionuclide "i."

All other factors as previously defined.

B-8 Page 9-163

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 B.2.5 Vegetation Pathway (continued)

For radionuclides other than iodine, the factor Ii is equal to one. For radioiodines, the value of Ii may vary.

However, a value of 1.0 was used in Tables 3.3-2 through 3.3-4.

Table B-3 presents the appropriate parameter values and their source in Regulatory Guide 1.109, Revision 1.

In lieu of site-specific data default values for fL and fg, 1.0 and 0.76, respectively, were used in the calculations on Ri. These values were obtained from Table E-15 of Regulatory Guide 1.109, Revision 1.

The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, the Ri is based on X/Q:

S RT = K K ULaf + U f (DFLi)a 0.75 (0.5 / H) (B.2.8)

V L a g where:

R = Dose factor for the vegetable pathway for tritium for any organ of interest, mrem/yr per TV Ci/m3.

All other terms remain the same as those in Equations B.2-4 and B.2-7.

B-9 Page 9-164

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE B-1 Parameters For Cow and Goat Milk Pathways Parameter Value Reference (Reg. Guide 1.109, Rev. 1)

Q (kg/day) 50 (cow) Table E-3 F 6 (goat Table E-3 Y (kg/M2) 0.7 Table E-15 p

t (seconds) 1.73 E+05 (2 days) Table E-15 f

r 1.0 (radioiodines) Table E-15 0.2 (particulates) Table E-15 (DFL ) (mrem/pCi) Each radionuclide Table E-11 to E-14 ia F (pCi/liter per pCi/day) Each stable element Table E-1 (cow) m Table E-2 (goat)

T (seconds) 4.75 E+08 (15 yr) Table E-15 b

Y (kr/m2) 2.0 Table E-15 s

t (seconds) 7.78 E+06 (90 days) Table E-15 h

U (liters/yr) 330 infant Table E-5 ap 330 child Table E-5 400 teen Table E-5 310 adult Table E-5 t (seconds) 2.59 E+06 (pasture) Table E-15 e 5.18 E+06 (stored feed)

B (pCi/kg [wet weight] Each stable element Table E-1 iv per pCi/kg [dry soil])

P (kg dry soil/m2) 240 Table E-15 B-10 Page 9-165

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE B-2 Parameters For The Meat Pathway Reference Parameter Value (Reg. Guide 1.109, Rev. 1) r 1.0 (radioiodines) Table E-15 0.2 (particulates) Table E-15 F (pCi/ke per (pCi/Day) Each stable element Table E-1 f

U (kg/yr) 0 infant Table E-5 ap 41 child Table E-5 65 teen Table E-5 110 adult Table E-5 (DFL ) (mrem/pCi) Each radionuclide Tables E-11 to E-14 ia 2

Y (kg/m ) 0.7 Table E-15 p

2 Y (kr/m ) 2.0 Table E-15 s

T (seconds) 4.73 E+08 (15 yr) Table E-15 b

T (seconds) 1.73 E+06 (20 days) Table E-15 s

t (seconds) 7.78 E+06 (90 days) Table E-15 h

t (seconds) 2.59 E+06 (pasture) Table E-15 e 5.18 E+06 (stored feed)

Q (kg/day) 50 Table E-3 F

B (pCi/kg [wet weight] Each stable element Table E-1 iv per pCi/kg [dry soil])

2 P (kg dry soil/m 240 Table E-15 B-11 Page 9-166

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE B-3 Parameters for The Vegetable Pathway Reference Parameter Value (Reg. Guide 1.109, Rev. 1) r (dimensionless) 1.0 (radioiodines) Table E-1 0.2 (particulates) Table E-1 (DFL ) (mrem/pCi) Each radionuclide Tables E-11 to E-14 ia Q (kg/day) 50 (cow) Table E-3 F 6 (goat) Table E-3 UL (kg/yr) - Infant 0 Table E-5 a 26 Table E-5

- Child 42 Table E-5

- Teen 64 Table E-5

- Adult US (kr/hr) - Infant 0 Table E-5 a 520 Table E-5

- Child 630 Table E-5

- Teen 520 Table E-5

- Adult T (seconds) 8.6 E+04 (1 day) Table E-15 L

t (seconds) 5.18 E+06 (60 day) Table E-15 h

Y (kg/m2) 2.0 Table E-15 v

t (seconds) 5.18 E+06 (60 day) Table E-15 e

t (seconds) 4.73 E+08 (15 yr) Table E-15 b

P (kg dry soil/m2) 240 Table E-15 B (pCi/kg [wet weight] Each stable element Table E-1 iv per pCi/kg [dry soil])

B-12 Page 9-167

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 C.0 APPENDIX C RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION NUMBERS Monitor Identification I. Liquid Effluent Monitoring Instruments A. Treated Laundry and Hot Shower Tank.................................................................... REM-1WL-3540 B. Waste Monitor Tank ............................................................................................... REM-21WL-3541 C. Waste Evaporator Condensate Tank...................................................................... REM-21WL-3541 D. Secondary Waste Sample Tank ............................................................................ REM-21WS-3542 E. NSW Returns to Circulating Water System from Waste Processing Building ............................................................. REM-1SW-3500A from Reactor Auxiliary Building ............................................................... REM-1SW-3500B F. Outdoor Tank Area Drain Transfer Pump Monitor ....................................................REM-1MD-3530 G. Turbine Building Floor Drains Effluent ......................................................................REM-1MD-3528 II. Gaseous Effluent Monitoring Instruments A. Plant Vent Stack 1 .........................................................................................

RM-21AV-3509-1SA B. Turbine Building Vent Stack 3A ............................................................................

RM-1TV-3536-1 C. Waste Processing Building Vent Stack 5 ............................................ REM-1WV-3546

........................................

RM-1WV-3546-1 D. Waste Processing Building Vent Stack 5A ..........................................................

RM-1WV-3547-1

Wide-Range Gas Monitor (WRGM)

C-1 Page 9-168

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 D.0 APPENDIX D PROGRAMMATIC CONTROLS The surveillance and operational requirements pertaining to the ODCM Operational Requirements are detailed in Sections:

D.1 - Instrumentation D.2 - Radioactive Effluents D.3 - Radiological Environmental Monitoring D-1 Page 9-169

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 D.1 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.10 Radioactive Liquid Effluent Monitoring Instrumentation OPERATIONAL REQUIREMENT 3.3.3.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of Operational Requirement 3.11.1.1 are not exceeded. The Alarm/Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY: At all times.

ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel Alarm/Trip Setpoint less conservative than required by the above Operational Requirement, immediately (1) suspend the release of radioactive liquid effluents monitored by the affected channel or (2) declare the channel inoperable and take ACTION as directed by b. below.

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12. Exert best effort to restore to the minimum number of radioactive liquid effluent channels within 30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report pursuant to ODCM, Appendix F, Section F.2 why this inoperability was not corrected in a timely manner.

SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and DIGITAL CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-8.

Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

D-2 Page 9-170

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-12 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM INSTRUMENT CHANNELS ACTION OPERABLE

1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release

a. Liquid Radwaste Effluent Lines

1) Treated Laundry and Hot Shower Tanks 1 35 Discharge Monitor

2) Waste Monitor Tanks and Waste Evaporator 1 35 Condensate Tanks Discharge Monitor

3) Secondary Waste Sample Tank Discharge 1 35, 36*

Monitor

b. Turbine Building Floor Drains Effluent Line 1 36

2. Radioactivity Monitor Providing Alarm and Automatic Stop Signal to Discharge Pump

a. Outdoor Tank Area Drain Transfer Pump Monitor 1 37

3. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release

a. Normal Service Water System Return From Waste 1 39 Processing Building to the Circulating Water System

b. Normal Service Water System Return From the Reactor 1 39 Auxiliary Building to the Circulating Water System

4. Flow Rate Measurement Devices

a. Liquid Radwaste Effluent Lines

1) Treated Laundry and Hot Shower Tanks 1 38 Discharge

2) Waste Monitor Tanks and Waste Evaporator 1 38 Condensate Tanks Discharge

3) Secondary Waste Sample Tank 1 38

b. Cooling Tower Blowdown 1 38

When the Secondary Waste System is in the continuous release mode and releases are occurring, Action 36 shall be taken when the monitor is inoperable. In the batch release mode, Action 35 is applicable.

D-3 Page 9-171

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-12 (Continued)

ACTION STATEMENTS ACTION 35 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that prior to initiating a release:

a. At least two independent samples are analyzed in accordance with Operational Requirement 4.11.1.1.1, and

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 36 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for radioactivity at a lower limit of detection of no more than 1E-07 µCi/ml:

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the secondary coolant is greater than 0.01 µCi/gram DOSE EQUIVALENT I-131 or,

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is less than or equal to 0.01 µCi/gram DOSE EQUIVALENT I-131.

ACTION 37 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and analyzed for radioactivity at a lower limit of detection of no more than 1E-07 µCi/ml.

ACTION 38 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump performance curves generated in place may be used to estimate flow.

ACTION 39 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the weekly Cooling Tower Blowdown weir surveillance is performed as required by Operational Requirement 4.11.1.1.1. Otherwise, follow the ACTION specified in ACTION 37 above.

D-4 Page 9-172

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 4.3-8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS DIGITAL CHANNEL CHANNEL SOURCE CHANNEL INSTRUMENT CALIBRATIO CHECK CHECK OPERATIONAL N

TEST

1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release

a. Liquid Radwaste Effluent Lines

1) Treated Laundry and Hot Shower D P R(3) Q(1)

Tanks Discharge Monitor

2) Waste Monitor Tanks and Waste Evaporator Condensate Tanks D P R(3) Q(1)

Discharge Monitor

3) Secondary Waste Sample Tank D P, M(5) R(3) Q(1)

Discharge Monitor

b. Turbine Building Floor Drains Effluent Line D M R(3) Q(1)

2. Radioactivity Monitor Providing Alarm and Automatic Stop Signal to Discharge Pump

a. Outdoor Tank Area Drain Transfer Pump D M R(3) Q(1)

Monitor

3. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release

a. Normal Service Water System Return From Waste Processing Building to the D M R(3) Q(2)

Circulating Water System

b. Normal Service Water System Return From the Reactor Auxiliary Building to the D M R(3) Q(2)

Circulating Water System

4. Flow Rate Measurement Devices

a. Liquid Radwaste Effluent Lines

1) Treated Laundry and Hot Shower D(4) N.A. R N.A.

Tanks Discharge

2) Waste Monitor Tanks and Waste Evaporator Condensate Tanks D(4) N.A. R N.A.

Discharge

3) Secondary Waste Sample Tank Pump D(4) N.A. R N.A.

Monitor

b. Cooling Tower Blowdown D(4) N.A. R N.A.

See Table G-1 for explanation of frequency notation D-5 Page 9-173

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 4.3-8 (Continued)

TABLE NOTATIONS (1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate automatic isolation of this pathway (or, for the Outdoor Tank Area Drains Monitor, automatic stop signal to the discharge pump) and control room alarm annunciation* occur if any of the following conditions exists (liquid activity channel only):

a. Instrument indicates measured levels above the Alarm/Trip Setpoint,

b. Circuit failure (monitor loss of communications (alarm only), detector loss of counts (Alarm only) and monitor loss of power),

c. Detector check source test failure (alarm only),

d. Detector channel out of service (alarm only),

e. Monitor loss of sample flow (alarm only). (Not applicable for Turbine Building Drain Rad Monitor)

(2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation* occurs if any of the following conditions exists (liquid activity channel only):

a. Instrument indicates measured levels above the Alarm Setpoint,

b. Circuit failure (monitor loss of communications, detector loss of counts, and monitor loss of power),

c. Detector check source test failure,

d. Detector channel out of service,

e. Monitor loss of sample flow.

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous, periodic, or batch releases are made.

(5) When the Secondary Waste System is being used in the batch release mode, the source check shall be prior to release. When the system is being used in the continuous release mode, the source check shall be monthly.

Control Room Alarm Annunciation shall consist of a change in state of the tested channel on the RM-11 terminal (i.e., a change in color) or a highlighted message on the DICSP Workstation Channel.

D-6 Page 9-174

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.11 Radioactive Gaseous Effluent Monitoring Instrumentation OPERATIONAL REQUIREMENT 3.3.3.11 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of Operational Requirements 3.11.2.1 are not exceeded. The Alarm/Trip Setpoints of these channels meeting Operational Requirement 3.11.2.1 shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

APPLICABILITY: As shown in Table 3.3-13 ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel Alarm/Trip Setpoint less conservative than required by the above Operational Requirement, immediately (1) suspend the release of radioactive gaseous effluents monitored by the affected channel or (2) declare the channel inoperable and take ACTION as directed by b. below.

b. With the number of OPERABLE radioactive gaseous effluent monitoring instrumentation channels less than the Minimum Channels OPERABLE, take the ACTION shown in Table 3.3-13. Exert best efforts to return the instrument to OPERABLE status within 30 days. If unsuccessful, explain in the next Annual Radioactive Effluent Release Report pursuant to ODCM, Appendix F, Section F.2 why this inoperability was not corrected in a timely manner.

SURVEILLANCE REQUIREMENTS 4.3.3.11 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and a DIGITAL CHANNEL OPERATIONAL TEST or an ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-9.

Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

D-7 Page 9-175

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-13 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MIN.

INSTRUMENT CHANNELS APPLICABILITY ACTION OPERABLE

1. GASEOUS WASTE PROCESSING SYSTEM - HYDROGEN AND OXYGEN ANALYZERS Specification is not used in ODCM

2. TURBINE BUILDING VENT STACK

a. Noble Gas Activity Monitor 1

47

b. Iodine Sampler 1

49

c. Particulate Sampler 1

49

d. Flow Rate Monitor 1

46

e. Sampler Flow Rate Monitor 1

46

3. PLANT VENT STACK

a. Noble Gas Activity Monitor 1

47

b. Iodine Sampler 1

49

c. Particulate Sampler 1

49

d. Flow Rate Monitor 1

46

e. Sampler Flow Rate Monitor 1

46

4. WASTE PROCESSING BUILDING VENT STACK 5 a.1 Noble Gas Activity Monitor (PIG) 1

45, 51 a.2 Noble Gas Activity Monitor (WRGM) 1 MODES 1, 2, 3 52

b. Iodine Sampler 1

49

c. Particulate Sampler 1

49

d. Flow Rate Monitor 1

46

e. Sampler Flow Rate Monitor 1

46

5. WASTE PROCESSING BUILDING STACK 5A

a. Noble Gas Activity Monitor 1

47

b. Iodine Sampler 1

49

c. Particulate Sampler 1

49

d. Flow Rate Monitor 1

46

e. Sampler Flow Rate Monitor 1

46 TABLE NOTATIONS

At all times.

D-8 Page 9-176

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.3-13 (Continued)

ACTION STATEMENTS ACTION 45 - With the number channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the waste gas decay tank(s) may be released to the environment provided that prior to initiating the release:

a. At least two independent samples of the tank's contents are analyzed, and

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 46 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 47 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 48 - Not Used in the ODCM.

ACTION 49 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Table 4.11-2.

ACTION 50 - Not used in the ODCM.

ACTION 51 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement for both the PIG and WRGM, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 52 - With the number of OPERABLE accident monitoring instrumentation channels for the radiation monitor(s) less than the Minimum Channels OPERABLE requirements of Technical Specification Table 3.3-10, initiate the preplanned alternate method of monitoring the appropriate parameter(s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and either restore the inoperable channel(s) to OPERABLE status within 14 days or prepare and submit a Special Report to the Commission, pursuant to Technical Specification 6.9.2, within the next 14 days that provides actions taken, cause of the inoperability, and the plans and schedule for restoring the channel(s) to OPERABLE status.

D-9 Page 9-177

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 4.3-9 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS**

DIGITAL MODES FOR CHANNEL SOURCE CHANNEL CHANNEL WHICH INSTRUMENT CHECK CHECK CALIBRATION OPERATIONAL SURVEILLANCE TEST IS REQUIRED

1. GASEOUS WASTE PROCESSING SYSTEM - HYDROGEN AND OXYGEN ANALYZERS Not Used in the ODCM.

2. TURBINE BUILDING VENT STACK

a. Noble Gas Activity D M R(3) Q(2) *

b. Iodine Sampler N.A. N.A. N.A. N.A. *

c. Particulate Sampler N.A. N.A. N.A. N.A. *

d. Flow Rate Monitor D N.A. R Q *

e. Sampler Flow Rate Monitor D N.A. R Q *

3. PLANT VENT STACK

a. Noble Gas Activity Monitor D M R(3) Q(2) *

b. Iodine Sampler N.A. N.A. N.A. N.A. *

c. Particulate Sampler N.A. N.A. N.A. N.A. *

d. Flow Rate Monitor D N.A. R Q *

e. Sampler Flow Rate Monitor D N.A. R Q *

4. WASTE PROCESSING BUILDING VENT STACK 5 a.1 Noble Gas Activity Monitor D M R(3) Q(1) *

(PIG) a.2 Noble Gas Activity Monitor D M R(3) Q(2) *

(WRGM)

b. Iodine Sampler N.A. N.A. N.A. N.A. *

c. Particulate Sampler N.A. N.A. N.A. N.A. *

d. Flow Rate Monitor D N.A. R Q *

e. Sampler Flow Rate Monitor D N.A. R Q *

5. WASTE PROCESSING BUILDING VENT STACK 5A

a. Noble Gas Activity Monitor D M R(3) Q(2) *

b. Iodine Sampler N.A. N.A. N.A. N.A. *

c. Particulate Sampler N.A. N.A. N.A. N.A. *

d. Flow Rate Monitor D N.A. R Q *

e. Sampler Flow Rate Monitor D N.A. R Q *

At all times.

- See Table G-1 for explanation of frequency notation D-10 Page 9-178

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 ABLE 4.3-9 (Continued)

TABLE NOTATIONS (1) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room annunciation* occur if any of the following conditions exists (gas activity and gas effluent channels only):

a. Instrument indicates measured levels above the Alarm/Trip Setpoint,

b. Circuit failure (monitor loss of communications - (alarm only), detector loss of counts (alarm only) and monitor loss of power),

c. Detector check source test failure (gas activity channel only), (alarm only),

d. Detector channel out of service (alarm only),

e. Monitor loss of sample flow (alarm only).

(2) The DIGITAL CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation* occurs if any of the following conditions exists (gas activity and gas effluent channels only):

a. Instrument indicates measured levels above the Alarm Setpoint,

b. Circuit failure (monitor loss of communications (alarm only), detector loss of counts, and monitor loss of power),

c. Detector check source test failure (gas activity channel only),

d. Detector channel out of service,

e. Monitor loss of sample flow.

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

(4) Not used in the ODCM.

(5) Not used in the ODCM.

Control Room Alarm Annunciation shall consist of a change in state of the tested channel on the RM-11 terminal (i.e., a change in color) or a highlighted message on the DICSP Workstation Channel.

D-11 Page 9-179

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 D.2 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 Concentration OPERATIONAL REQUIREMENT 3.11.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Technical Specification Figure 5.1-3) shall be limited to 10 times the concentrations specified in 10 CFR Part 20.1001 - 20.2401, 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 µCi/ml total activity.

APPLICABILITY: At all times.

ACTION:

a. With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits.

SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11-1.

4.11.1.1.2 The results of the radioactivity analyses shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Operational Requirement 3.11.1.1.

Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

D-12 Page 9-180

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 4.11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM*

LOWER LIMIT MINIMUM OF DETECTION SAMPLING ANALYSIS TYPES OF ACTIVITY (LLD)(1)

LIQUID RELEASE TYPE FREQUENCY FREQUENCY ANALYSIS (Ci/ml)

(2)

1. Batch Waste Release Tanks

a. Waste Monitor P P Principal Gamma 5E-07 Tanks Each Batch Each Batch Emitters(3)

I-131 1E-06

b. Waste P M Dissolved and Evaporator One Batch/M Entrained Gases 1E-05 Condensate (Gamma Emitters)

Tanks

c. Secondary Waste P M (8) (4) H-3 1E-05 Sample Tank Each Batch Composite Gross Alpha 1E-07

d. Treated Laundry and P Q (4) Sr-89, Sr-90 5E-08 Hot Shower Tanks Each Batch Composite Fe-55 1E-06 (5)(7)

2. Continuous Releases

a. Cooling Tower Weir Continuous(6) W Composite(6)(7) Principal Gamma (3) 5E-07 Emitters

b. Secondary Waste M(7) M(7) Dissolved and Sample Tank(8) Grab Sample Entrained Gases 1E-05 (Gamma Emitters)

I-131 1E-06 (6)

Continuous M (6)(7) H-3 1E-05 Composite Gross Alpha 1E-07 (6)

Continuous Q Sr-89, Sr-90 5E-08 Composite(6)(7)

Fe-55 1E-06

See Table G-1 for explanation of frequency notation D-13 Page 9-181

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 4.11-1 (Continued)

TABLE NOTATIONS (1) The LLD is defined, for purposes of these Operational Requirements, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

4.66

s LLD = b E

V * (2.22E + 06)

Y

e t Where:

LLD = the "a priori" lower limit of detection (µCi per unit mass or volume),

sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

E = the counting efficiency (counts per disintegration),

V = the sample size (units of mass or volume),

2.22E+06 = the number of disintegrations per minute per µCi, Y = the fractional radiochemical yield, when applicable,

-1

= the radioactive decay constant for the particular radionuclide (sec ), and t = the elapsed time between the midpoint of sample collection and the time of counting (sec).

Typical values of E, V, Y, and t should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

(2) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in the ODCM to assure representative sampling.

D-14 Page 9-182

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 4.11-1 (Continued)

TABLE NOTATIONS (Continued)

(3) The principal gamma emitters for which the LLD Operational Requirement applies include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141. Ce-144 shall also be measured but with a LLD of 5E-06. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to ODCM, Appendix F, Section F.2 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

(4) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.

(5) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.

(6) To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

(7) These points monitor potential release pathways only and not actual release pathways. The potential contamination points are in the Normal Service Water (NSW) and Secondary Waste (SW) Systems. Action under this Operational Requirement is as follows:

a) If the applicable (NSW or SW) monitors in Table 3.3-12 are OPERABLE and not in alarm, then no analysis under this Operational Requirement is required but weekly composites will be collected.

b) If the applicable monitor is out of service, then the weekly analysis for principal gamma emitters will be performed.

c) If the applicable monitor is in alarm or if the principal gamma emitter analysis indicates the presence of radioactivity as defined in the ODCM, then all other analyses of this Operational Requirement shall be performed at the indicated frequency as long as the initiating conditions exist.

(8) The Secondary Waste System releases can be either batch or continuous. The type of sample required is determined by the mode of operation being used.

D-15 Page 9-183

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.2 Dose OPERATIONAL REQUIREMENT 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS (see Technical Specification Figure 5.1-3) shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and

b. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

D-16 Page 9-184

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.3 Liquid Radwaste Treatment System OPERATIONAL REQUIREMENT 3.11.1.3 The Liquid Radwaste Treatment System shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses, due to the liquid effluent, to UNRESTRICTED AREAS (see Technical Specification Figure 5.1-3) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period.

APPLICABILITY: At all times.

ACTION:

a. With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Radwaste Treatment System not in operation, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that includes the following information:

1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action(s) taken to prevent a recurrence.

SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when Liquid Radwaste Treatment Systems are not being fully utilized.

4.11.1.3.2 The installed Liquid Radwaste Treatment System shall be considered OPERABLE by meeting Operational Requirements 3.11.1.1 and 3.11.1.2.

Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

D-17 Page 9-185

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 Dose Rate OPERATIONAL REQUIREMENT 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Technical Specification Figure 5.1-1) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrems/yr to the skin, and

b. For Iodine-131, for Iodine-133, for tritium, and for all radionuclides in particular form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the dose rate(s) exceeding the above limits, immediately restore the release rate to within the above limit(s).

SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM.

4.11.2.1.2 The dose rate due to Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11-2.

Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

D-18 Page 9-186

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM LOWER LIMIT OF (1)

SAMPLING ANALYSIS DETECTION (LLD)

GASEOUS RELEASE TYPE FREQUENCY FREQUENCY TYPE OF ACTIVITY ANALYSIS (Ci/ml)

(2a)

1. Waste Gas Storage P P Principal Gamma Emitters 1E-04 Tank Each Tank Each Tank Grab Sample (2a)

2. Containment Purge P P Principal Gamma Emitters 1E-04 (10) (3) or Vent Each PURGE (3) Each PURGE Grab Sample M H-3 (oxide) 1E-06 (3),(4),(5) (2a)

3. a. Plant Vent Stack M M Principal Gamma Emitters 1E-04 Grab Sample H-3 (oxide) 1E-06 (2a)

M M Principal Gamma Emitters 1E-04

b. Turbine Bldg Vent Stack, Waste Proc. Grab Sample Bldg. Vent Stacks 5 & 5A (6) (7) (2b)

4. All Release Types as Continuous W I-131 1E-12 listed in 1.,2., and Charcoal (2b)

3. above (8), (9), (10)

Sample I-133 1E-10 (6) (7,12) (2c)

Continuous W Principal Gamma Emitters 1E-11 Particulate Sample (6)

Continuous M Gross Alpha 1E-11 Composite Particulate Sample (6)

Continuous Q Sr-89, Sr-90 1E-11 Composite Particulate Sample (2b)

5. Equipment Hatch Continuous D I-131 1E-11 during Refueling Charcoal (2b)

Sample I-133 1E-09 (11)

Continuous D Principal Gamma Emitters 1E-10 Particulate Sample

See Table G-1 for explanation of frequency notation D-19 Page 9-187

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 4.11-2 (Continued)

TABLE NOTATIONS (1) The LLD is defined, for purposes of these Operational Requirements, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

4.66

s LLD = b E

V * (2.22E + 06)

Y

e t Where:

LLD = the "a priori" lower limit of detection (µCi per unit mass or volume),

sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

E = the counting efficiency (counts per disintegration),

V = the sample size (units of mass or volume),

2.22E+06 = the number of disintegrations per minute per µCi, Y = the fractional radiochemical yield, when applicable,

= the radioactive decay constant for the particular radionuclide (sec-1), and t = the elapsed time between the midpoint of sample collection and the time of counting (sec).

Typical values of E, V, Y, and t should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

D-20 Page 9-188

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 4.11-2 (Continued)

TABLE NOTATIONS (Continued)

(2a) The principal gamma emitters for which the LLD Operational Requirement applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases. This list does not mean that only these nuclides are to be considered. Other noble gas gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to ODCM, Appendix F, Section F.2 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

(2b) The principal gamma emitters for which the LLD Operational Requirement applies include I-131 and I-133 in Iodine (charcoal cartridge) samples. This list does not mean that only these nuclides are to be considered.

Other iodine gamma peaks that are identifiable, together with I-131 and I-133 nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to ODCM, Appendix F, Section F.2 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

(2c) The principal gamma emitters for which the LLD Operational Requirement applies include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141, and Ce-144 in particulate releases. This list does not mean that only these nuclides are to be considered. Other particulate gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to ODCM, Appendix F, Section F.2 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

(3) Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period.

(4) Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded.

(5) Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.

(6) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Operational Requirements 3.11.2.1, 3.11.2.2, and 3.11.2.3.

(7) Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing, or after removal from sampler. Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, startup, or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing.

When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a factor of

10. This requirement does not apply if: (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

(8) Continuous sampling of Waste Gas Decay Tank (WGDT) releases can be met using the continuous samplers on Wide Range Gas Monitor RM-*1WV-3546-1 on Waste Processing Building Vent Stack 5.

(9) Continuous sampling of containment atmosphere for (1) Venting, (2) Normal Purge, and (3) Pre-entry purge operations, required by Operational Requirement 4.11.2.1.2, can be met using the continuous samplers on Wide Range Gas Monitor RM-01AV-3509-1SA on Plant Vent Stack 1 D-21 Page 9-189

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 4.11-2 (Continued)

TABLE NOTATIONS (Continued)

(10) The requirement to sample the containment atmosphere prior to release for normal and pre-entry containment purge operations (that is, to "permit" the release per the ODCM) is required on initial system startup, and prior to system restart following any system shutdown due to radiological changes in the containment (e.g. valid high alarms on leak detection or containment area monitors). System shutdown occurring on changes in containment pressure, equipment malfunctions, operational convenience, sampling, and so forth, do not require new samples or release permits.

(11) The composite of all filters collected when releases were being made through the equipment hatch are to be analyzed for gross alpha, strontium-89, and strontium 90 at the end of the outage.

(12) If isokinetic skid for Plant Vent Stack 1 is INOPERABLE particulate sampling for effluent accountability is to be installed on 286 of the fuel handling building. ANSI 13.1, 1969 defines the conditions for obtaining a representative particulate sample.

D-22 Page 9-190

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.2 Dose - Noble Gases OPERATIONAL REQUIREMENT 3.11.2.2 The air dose due to noble gases released in gaseous effluents to areas at and beyond the SITE BOUNDARY (see Technical Specification Figure 5.1-3) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and

b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

APPLICABILITY: At all times.

ACTION:

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

D-23 Page 9-191

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.3 Dose - Iodine-131, Iodine-133, Tritium, and Radioactive Material in Particulate Form OPERATIONAL REQUIREMENT 3.11.2.3 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 8 days in gaseous effluents released to areas at and beyond the SITE BOUNDARY (see Technical Specification Figure 5.1-3) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ, and

b. During any calendar year: Less than or equal to 15 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose, from the release of Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

D-24 Page 9-192

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.4 Gaseous Radwaste Treatment System OPERATIONAL REQUIREMENT 3.11.2.4 The VENTILATION EXHAUST TREATMENT SYSTEM and the GASEOUS RADWASTE TREATMENT SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases to areas at and beyond the SITE BOUNDARY (see Technical Specification Figure 5.1-3) would exceed:

a. 0.2 mrad to air from gamma radiation, or

b. 0.4 mrad to air from beta radiation, or

c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

APPLICABILITY: At all times.

ACTION:

a. With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that includes the following information:

1. Identification of any inoperable equipment or subsystems, and the reason for the inoperability,

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action(s) taken to prevent a recurrence.

SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when the GASEOUS RADWASTE TREATMENT SYSTEM is not being fully utilized.

4.11.2.4.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM and GASEOUS RADWASTE TREATMENT SYSTEM shall be considered OPERABLE by meeting Operational Requirements 3.11.2.1 and 3.11.2.2 or 3.11.2.3.

Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

D-25 Page 9-193

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3/4.11.4 TOTAL DOSE OPERATIONAL REQUIREMENT 3.11.4 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

APPLICABILITY: At all times.

ACTION:

a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Operational Requirement 3.11.1.2a., 3.11.1.2b., 3.11.2.2a., 3.11.2.2b.,

3.11.2.3a., or 3.11.2.3b., calculations shall be made including direct radiation contributions from the units and from outside storage tanks to determine whether the above limits of Operational Requirement 3.11.4 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.405(c), shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Operational Requirements 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the ODCM.

4.11.4.2 Cumulative dose contributions from direct radiation from the units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in ACTION a. of Operational Requirement 3.11.4.

Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

D-26 Page 9-194

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 D.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM OPERATIONAL REQUIREMENT 3.12.1 The Radiological Environment Monitoring Program shall be conducted as specified in Table 3.12-1.

APPLICABILITY: At all times.

ACTION:

a. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by ODCM, Appendix F, Section F.1, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose* to a MEMBER OF THE PUBLIC is less than the calendar year limits of Operational Requirements 3.11.1.2. 3.11.2.2, or 3.11.2.3. When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:

concentrat ion(1) concentrat ion(2)

+ +...1.0 reporting level(1) reporting level(2)

When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose* to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of Operational Requirement 3.11.1.2, 3.11.2.2, or 3.11.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report required by ODCM, Appendix F, Section F.1.

The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

D-27 Page 9-195

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3/4.12.1 MONITORING PROGRAM OPERATIONAL REQUIREMENT ACTION (Continued):

c. With milk or fresh leafy vegetation samples unavailable from one or more of the sample locations required by Table 3.12-1, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM.

The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to ODCM, Appendix F, Section F.2, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table for the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location(s) for obtaining samples.

d. If any sample result for onsite groundwater, that is or may be used as a source of drinking water, exceeds the reporting criteria of ODCM Table 3.12-2, then submit a special 30 day written report to the NRC. Additionally, a copy of this report shall be forwarded to designated state/local offices listed below in Action e.

e. If any offsite groundwater, offsite surface water, onsite groundwater monitoring well, or onsite surface water that is hydrologically connected to groundwater exceed the reporting criteria of ODCM Table 3.12-2, then make informal notification to the designated state/local offices listed below by the end of the next business day. Special Ground Water Protection Reports listed in this section are not required for subsequent sample results that are from the same plume and have already been reported in accordance with this section. The Designated State offices for notification are as follows: 1) North Carolina Department of Environmental and Natural Resources, Radiation Protection Section and 2) North Carolina Department of Environmental and Natural Resources, Division of Water Quality.

SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the specific locations given in the table and figure(s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 3.12-1 and the detection capabilities required by Table 4.12-1.

Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

D-28 Page 9-196

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE LOCATIONS(1) COLLECTION FREQUENCY OF ANALYSIS

1. Direct Radiation(2) Forty routine monitoring stations Quarterly. Gamma dose quarterly.

either with two or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:

An inner ring of stations, one in each meteorological sector in the general area of the SITE BOUNDARY; An outer ring of stations, one in each meteorological sector in the 6 to 8 km range from the site; and The balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and in one or two areas to serve as control stations.

D-29 Page 9-197

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.12-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE LOCATIONS(1) COLLECTION FREQUENCY OF ANALYSIS

2. Airborne Samples from five locations: Continuous sampler Radioiodine Cannister:

Radioiodine and operation with sample I-131 analysis weekly.

Particulates Three samples from close to collection weekly, or the three SITE BOUNDARY more frequently if locations, in different sectors, of the highest required by dust calculated annual average loading. Particulate Sampler:

ground-level D/Q; Gross beta radioactivity analysis following One sample from the vicinity filter change;(3) and of a community having the gamma isotopic analysis(4) highest calculated annual of composite (by location) average ground-level D/Q; and quarterly.

One sample from a control location, as for example 15 to 30 km distant and in the least prevalent wind direction.

3. Waterborne (4)

One sample upstream. Composite sample over Gamma isotopic analysis

a. Surface(5) 1-month period.

(6) monthly. Composite for One sample downstream. tritium analysis quarterly.

(4)

b. Ground Samples from one or two sources only if likely Quarterly. Gamma isotopic and to be affected(7). tritium analysis quarterly.

D-30 Page 9-198

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.12-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE LOCATIONS(1) COLLECTION FREQUENCY OF ANALYSIS

3. Waterborne I-131 analysis on each (Continued) One sample in the vicinity of the nearest Composite sample over composite when the dose (6) downstream municipal water supply intake 2-week period when calculated for the consumption of

c. Drinking from the Cape Fear River. I-131 analysis is the water is greater than 1 mrem performed; monthly per year.(8)

One sample from a control composite otherwise.

location. Composite for gross beta and gamma isotopic analyses(4) monthly.

Composite for tritium analysis quarterly.

(4)

d. Sediment One sample in the vicinity of the cooling tower Semiannually. Gamma isotopic analysis from blowdown discharge in an area with existing or semiannually.

Shoreline potential recreational value.

4. Ingestion Samples from milking animals in (4)

a. Milk three locations within 5 km distance having the Semimonthly when Gamma isotopic and highest dose potential. If there are none, animals are on pasture; I-131 analysis then one sample from milking animals in each of monthly at other times. When semimonthly when three areas between 5 to 8 km distant where no milk animals are available at animals are on pasture; doses are calculated to be greater than 1 mrem indicator locations, milk monthly at other times.

(8) per yr. sampling of the control location can be reduced to once per One sample from milking animals month to maintain historical at a control location 15 to 30 km data.

distant and in the least prevalent wind direction.

D-31 Page 9-199

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.12-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE LOCATIONS(1) COLLECTION FREQUENCY OF ANALYSIS

4. Ingestion (Continued)

One sample of Sunfish, Catfish, and Sample in season, or Gamma isotopic

b. Fish and Large-Mouth Bass species in vicinity semiannually if they analysis(4) on Invertebrates of plant discharge area. are not seasonal. edible portions.

One sample of same species in areas not influenced by plant discharge.

c. Food Products One sample of each principle class of food products At time of harvest (9) Gamma isotopic analysis(4) from any area that is irrigated by water which liquid on edible portions.

plant wastes have been discharged Samples of three different kinds of broad leaf Monthly during growing Gamma isotopic(4) and vegetation grown nearest each of two different season. I-131 analysis.

locations of highest predicted annual average ground level D/Q if milk sampling is not performed.

One sample of each of the similar broad leaf vegetation grown 15 to 30 km distant in the least prevalent wind direction if milk sampling is not performed.

D-32 Page 9-200

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.12-1 (Continued)

TABLE NOTATIONS (1) Specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, shall be provided for each and every sample location in Table 3.12-1 in a table and figure(s) in the ODCM. Refer to NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances such as hazardous conditions, seasonal unavailability, and malfunction of automatic sampling equipment. If specimens are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.3. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Environmental Monitoring Program. Pursuant to ODCM, Appendix F, Section F.2, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table for the ODCM reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples for that pathway and justifying the selection of the new location(s) for obtaining samples.

(2) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. (The 40 stations are not an absolute number. The number of direct radiation monitoring stations may be reduced according to geographical limitations; e.g., at an ocean site, some sectors will be over water so that the number of dosimeters may be reduced accordingly. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information within minimal fading.)

(3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

(4) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

(5) The "upstream sample" shall be taken at a distance beyond significant influence of the discharge. The "downstream" sample shall be taken in an area beyond but near the mixing zone. "Upstream" samples in an estuary must be taken far enough upstream to be beyond the plant influence. Salt water shall be sampled only when the receiving water is utilized for recreational activities.

(6) A composite sample is one in which the quantity (aliquot) of liquid sampled is proportional to the quantity of flowing liquid and in which the method of sampling employed results in a specimen that is representative of the liquid flow. In this program composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.

(7) Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination. None of the previously identified locations have been used for drinking water since pre-operational days of Harris Nuclear Project nor have these wells ever been used for irrigation purposes. These wells were abandoned for drinking water purposes prior to plant operations. Since that time, these wells have been used to monitor the hydraulic gradient or gradient properties for the Harris Site and for the operational Radiological Environmental Monitoring program.

D-33 Page 9-201

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.12-1 (Continued)

TABLE NOTATIONS (Continued)

(8) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.

(9) If harvest occurs more than once per year, sampling shall be performed during each discrete harvest. If harvest occurs continuously, sampling shall be monthly.

D-34 Page 9-202

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 3.12-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES AIRBORNE WATER FISH MILK FOOD PRODUCTS ANALYSIS PARTICULATE (pCi/l) (pCi/kg, wet) (pCi/l) (pCi/kg, wet)

OR GASES (pCi/m3)

H-3 20,000*

Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 I-131 2** 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300

For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/l may be used.

- If no drinking water pathway exists, a value of 20 pCi/l may be used.

D-35 Page 9-203

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 4.12-1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS(1)

LOWER LIMIT OF DETECTION (LLD)(2)

AIRBORNE FOOD WATER FISH MILK SEDIMENT ANALYSIS PARTICULATE PRODUCTS (pCi/l) (pCi/kg, wet) (pCi/l) (pCi/kg, dry)

OR GASES (pCi/m3) (pCi/kg, wet)

Gross Beta 4 0.01 H-3 2000*

Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-Nb-95 15 I-131 1** 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15*** 15***

If no drinking water pathway exists, a value of 3000 pCi/l may be used.

- If no drinking water pathway exists, a value of 15 pCi/l may be used.

- - The specific LLD applies to the daughter nuclide of an equilibrium mixture of the parent and daughter nuclides. Per the Branch Technical Position, value of 60 pCi/L may be used for Ba-140 and 15 pCi/L may be used for La-140.

D-36 Page 9-204

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE 4.12-1 (Continued)

TABLE NOTATIONS (1) This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to ODCM, Appendix F, Section F.1.

(2) The LLD is defined, for purposes of these Operational Requirements, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

4.66

s LLD = b E

V * (2.22E + 06)

Y

e t Where:

LLD = the "a priori" lower limit of detection (µCi per unit mass or volume),

sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

E = the counting efficiency (counts per disintegration),

V = the sample size (units of mass or volume),

2.22E+06 = the number of disintegrations per minute per µCi, Y = the fractional radiochemical yield, when applicable,

= the radioactive decay constant for the particular radionuclide (sec-1), and t = the elapsed time between the midpoint of sample collection and the time of counting (sec).

Typical values of E, V, Y, and t should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report pursuant to ODCM, Appendix F, Section F.1.

D-37 Page 9-205

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3/4.12.2 LAND USE CENSUS OPERATIONAL REQUIREMENT 3.12.2 A Land Use Census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden* of greater than 50 m2 (500 ft2) producing broad leaf vegetation.

APPLICABILITY: At all times.

ACTION:

a. With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Operational Requirement 4.11.2.3, pursuant to ODCM, Appendix F, Section F.2, identify the new location(s) in the next Annual Radioactive Effluent Release Report.

b. With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Operational Requirement 3.12.1, add the new location(s) within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Pursuant to ODCM, Appendix F, Section F.2, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure(s) and table(s) for the ODCM reflecting the new location(s) with information supporting the change in sampling locations.

SURVEILLANCE REQUIREMENTS 4.12.2 The Land Use Census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to ODCM, Appendix F, Section F.1.

Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census.

Operational Requirements for broad leaf vegetation sampling in Table 3.12-1, Part 4.c., shall be followed, including analysis of control samples.

D-38 Page 9-206

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM OPERATIONAL REQUIREMENT 3.12.3 Analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory Comparison Program, that correspond to samples required by Table 3.12-1.

APPLICABILITY: At all times.

ACTION:

a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to ODCM, Appendix F, Section F.1.

SURVEILLANCE REQUIREMENTS 4.12.3 The Interlaboratory Comparison Program shall be described in the ODCM. A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to ODCM, Appendix F, Section F.1.

Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

D-39 Page 9-207

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 E.0 APPENDIX E PROGRAMMATIC CONTROL BASES The Bases for the ODCM Operational Requirements are detailed in Sections:

E.1 - Instrumentation E.2 - Radioactive Effluents E.3 - Radiological Environmental Monitoring E-1 Page 9-208

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 E.1 INSTRUMENTATION BASES 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.10 Radioactive Liquid Effluent Monitoring Instrumentation The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The Alarm/Trip Set Points for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

3/4.3.3.11 Radioactive Gaseous Effluent Monitoring Instrumentation The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The Alarm/Trip Set Points for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. The sensitivity of any noble gas activity monitors used to show compliance with the gaseous effluent release requirements of Operational Requirement 3.11.2.2 shall be such that concentrations as low as 1E-06 Ci/ml are measurable.

E-2 Page 9-209

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 E.2 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 Concentration This Operational Requirement is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table 2, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within: (1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR Part 20.106(e) to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L. A.,

"Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry,"

Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

3/4.11.1.2 Dose This Operational Requirement is provided to implement the requirements of Sections II.A, III.A, and IV.A of Appendix I, 10 CFR Part 50. The Operational Requirement implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable". The dose calculation methodology and parameters in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.

3/4.11.1.3 Liquid Radwaste Treatment System The OPERABILITY of the Liquid Radwaste Treatment System ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment.

The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This Operational Requirement implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50 for liquid effluents.

E-3 Page 9-210

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 E.2 RADIOACTIVE EFFLUENTS BASES (continue) 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 Dose Rate This Operational Requirement is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column I. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 [10 CFR Part 20.106(b)]. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM.

The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/year to the whole body or to less than or equal to 3000 mrems/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/year.

The required detection capabilities for radioactive material in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300, Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

3/4.11.2.2 Dose - Noble Gases This Operational Requirement is provided to implement the requirements of Section II.B, III.A, and IV.A of Appendix I, 10 CFR Part 50. The Operational Requirement implements the guides set forth in Section I.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Dose to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision I, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions.

E-4 Page 9-211

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 E.2 RADIOACTIVE EFFLUENTS BASES (continue) 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.3 Dose - Iodine-131, Iodine-133, Tritium, and Radioactive Material in Particulate Form This Operational Requirement is provided to implement the requirements of Sections II.C, III.A, and IV.A of Appendix I, 10 CFR Part 50. The Operational Requirements are the guides set forth in Section II.C of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonable achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate Operational Requirements for Iodine-131, Iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of the calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and (4) deposition of the ground with subsequent exposure of man.

3/4.11.2.4 Gaseous Radwaste Treatment System The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensure that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This Operational Requirement implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

3/4.11.3 SOLID RADIOACTIVE WASTES This specification implements the requirements of 10 CFR 50.36a, 10 CFR 61, and General Design Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters included in establishing the PROCESS CONTROL PROGRAM may include, but are not limited to, waste type, waste pH, waste/liquid/SOLIDIFICATION agent/catalyst ratios, waste oil content, waste principal chemical constituents, and mixing and curing times.

E-5 Page 9-212

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 E.2 RADIOACTIVE EFFLUENTS BASES (continued) 3/4.11.4 TOTAL DOSE This Operational Requirement is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The Operational Requirement requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the units and from outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.2203, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Operational Requirements 3.11.1.1 and 3.11.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

E-6 Page 9-213

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 E.3 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM The Radiological Environmental Monitoring Program required by this Operational Requirement provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of MEMBERS OF THE PUBLIC resulting from the plant operation. This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways.

Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979. The initially specified monitoring program will be effective for at least the first 3 years of commercial operation. Following this period, program changes may be initiated based on operational experience.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 4.12-1 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300, Currie, L. A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K., "Detection Limits for Radioanalytical Counting Techniques" Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

3/4.12.2 LAND USE CENSUS This Operational Requirement is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program are made, if required, by the results of this census. The best information from the door-to-door survey, from aerial survey, or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m2.

3/4.12.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50.

E-7 Page 9-214

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 F.0 APPENDIX F ADMINISTRATIVE CONTROLS The Reporting Requirements pertaining to the ODCM Operational Requirements are detailed in Sections:

F.1 - Annual Radiological Environmental Operating Report F.2 - Annual Radioactive Effluent Release Report F.3 - Major changes to the Radwaste Treatment System (liquid and gaseous)

F-1 Page 9-215

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 F.1 Annual Radiological Environmental Operating Report (Formerly part of Specification 6.9.1.3)

Routine Annual Radiological Environmental Operating Reports, covering the operation of the unit during the previous calendar year, shall be submitted prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality.

The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, with operational controls, as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of the Land Use Census required by Operational Requirement 3.12.2.

The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the OFFSITE DOSE CALCULATION MANUAL, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. The reports shall also include the following: a summary description of the Radiological Environmental Monitoring Program; at least two legible maps* covering all sampling locations keyed to a table giving distances and directions from the centerline of the reactor; the results of licensee participation in the Interlaboratory Comparison Program and the corrective action taken if the specified program is not being performed as required by Operational Requirement 3.12.3; reasons for not conducting the Radiological Environmental Monitoring Program as required by Operational Requirement 3.12.1, and discussion of all deviations from the sampling schedule of Table 3.12-1; discussion of environmental sample measurements that exceed the reporting levels of Table 3.12-2 but are not the result of plant effluents, pursuant to ACTION b. of Operational Requirement 3.12.1; and discussion of all analyses in which the LLD required by Table 4.12-1 was not achievable.

One map shall cover stations near the EXCLUSION AREA BOUNDARY; a second shall include the more distant station.

F-2 Page 9-216

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 F.2 Annual Radioactive Effluent Release Report (Formerly part of Specification 6.9.1.4)

Routine Annual Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be submitted by May 1 of each year. The period of the first report shall begin with the date of initial criticality.

The Annual Radioactive Effluent Release Report shall include a summary of the quantities of radioactive liquid and gaseous effluents released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.

The Annual Radioactive Effluent Release Report shall include 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 distributions of wind speed, wind direction, and atmospheric stability.** This report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. For the assessment of radiation doses, approximate and conservative methods are acceptable. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the Offsite Dose Calculation Manual (ODCM).

The Annual Radioactive Effluent Release Report shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operation."

The Annual Radioactive Effluent Release Report shall also include the dose contribution from return/re-use of previously radioactive effluents (tritium from the lake) at the end of each year. If the dose from the particular pathway is greater than 10 percent of the total dose from all pathways from plant releases (liquid, gaseous, iodines particulates > 8 day half lifes & tritium from gaseous releases) the dose from the return of previously discharged effluents is to be reported. The total body, each organ, and each age group if applicable the dose should be calculated at the end of year unless it is known to be less than 10 percent of all doses.

The Annual Radioactive Effluent Release Report shall include a list and description of unplanned releases, from the site to UNRESTRICTED AREAS, of radioactive materials in gaseous and liquid effluents made during the reporting period.

The Annual Radioactive Effluent Release Report shall include any changes made during the reporting period to the ODCM, pursuant to Technical Specification 6.14, as well as any major change to Liquid and Gaseous Radwaste Treatment Systems pursuant to ODCM, Appendix F, Section F.3. It shall also include a listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use Census pursuant to Operational Requirement 3.12.2.

The Annual Radioactive Effluent Release Report shall also include the following: an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in Operational Requirement 3.3.3.10 or 3.3.3.11, respectively; and a description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Technical Specification 3.11.1.4 or PLP-114, Attachment 5, respectively.

The Annual Radioactive Effluent Release Report shall include any dose calculations that were performed as a result of a spill or leak from the site that occurred during the reporting period. The Annual Radioactive Effluent Release Report shall include a summary of any on-site spills and leaks that occurred during the reporting period that are communicated IAW the NEI Voluntary Groundwater Initiative.

- In lieu of submission with the Annual Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

F-3 Page 9-217

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 F.3 Major Changes to Liquid and Gaseous Radwaste Treatment Systems*

(Formerly part of Specification 6.15)

Licensee-initiated major changes to the Radwaste Treatment Systems (liquid and gaseous):

a. Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the PNSC. The discussion of each change shall contain:

1. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59.

2. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information.

3. A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems.

4. An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from those previously predicted in the License application and amendments thereto.

5. An evaluation of the change, which shows the expected maximum exposures, to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population, that differ from those previously estimated in the License application and amendments thereto.

6. A comparison of the predicted releases of radioactive materials in liquid and gaseous effluents to the actual releases for the period prior to when the change is to be made.

7. An estimate of the exposure to plant operating personnel as a result of the change.

8. Documentation of the fact that the change was reviewed and found acceptable by the PNSC.

b. Shall become effective upon review and acceptance by the PNSC.

Licensees may choose to submit the information called for in the Operational Requirement as part of the annual FSAR update F-4 Page 9-218

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 G.0 APPENDIX G DEFINITIONS The defined terms of this section appear in capitalized type and are applicable throughout the ODCM Operational Requirements.

ACTION ACTION shall be that part of an ODCM Operational Requirement which prescribes remedial measures required under designated conditions.

ANALOG CHANNEL OPERATIONAL TEST An ANALOG CHANNEL OPERATIONAL TEST shall be the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY of alarm, interlock and/or trip functions. The ANALOG CHANNEL OPERATIONAL TEST shall include adjustments, as necessary, of the alarm, interlock and/or Trip Setpoints such that the Setpoints are within the required range and accuracy.

CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel such that it responds within the required range and accuracy to known values of input. The CHANNEL CALIBRATION shall encompass the entire channel including the sensors and alarm, interlock and/or trip functions and may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.

CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

DIGITAL CHANNEL OPERATIONAL TEST A DIGITAL CHANNEL OPERATIONAL TEST shall consist of exercising the digital computer hardware using data base manipulation to verify OPERABILITY of alarm and/or trip functions.

DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (µCi/gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in ICRP-30, "Limits for Intakes of Radionuclides by Workers."

EXCLUSION AREA BOUNDARY The EXCLUSION AREA BOUNDARY shall be that line beyond which the land is not controlled by the licensee to limit access.

FREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of Operational Requirements shall correspond to the intervals defined in Table G-1.

GASEOUS RADWASTE TREATMENT SYSTEM A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system off-gases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

G-1 Page 9-219

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 DEFINITIONS (continued)

LIQUID WASTE PROCESSING SYSTEM A LIQUID WASTE PROCESSING SYSTEM provides for the collection, storing, processing, and controlled release of radioactive and potentially radioactive liquids. The system is considered fully utilized when the Modular Fluidized Transfer Demineralization System (MFTDS) is used for the purpose of reducing the total radioactivity prior to release to the environment. Some of the original processing equipment and evaporators have been removed from service but descriptions are still maintained to allow for future reactivation.

MEMBER(S) OF THE PUBLIC MEMBER(S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the licensee, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

OFFSITE DOSE CALCULATION MANUAL The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program.

OPERABLE - OPERABILITY A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s),and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related support function(s).

OPERATIONAL MODE - MODE An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table G-2.

PROCESS CONTROL PROGRAM The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71 and Federal and State regulations, burial ground requirements, and other requirements governing the disposal of radioactive waste.

PURGE - PURGING PURGE or PURGING shall be any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

G-2 Page 9-220

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 DEFINITIONS (continued)

RELEASE A RELEASE shall be the discharge of radioactive effluent from the facility in gaseous, particulate or liquid media. Releases can be further categorized for evaluation purposes:

ABNORMAL/UNPLANNED DISCHARGE - Unplanned or uncontrolled emission of licensed radioactive effluent to the unrestricted area. Release may be batch or continuous discharges.

Examples: unintentional discharge of a waste gas decay tank, failure of radiation monitor to terminate a release.

ABNORMAL/UNPLANNED RELEASE - Unplanned or uncontrolled release of licensed radioactive material from the plant within the site boundary.

CONTROLLED RELEASE/DISCHARGE - A pre-planned release which can be controlled through component manipulation to assure the discharge was properly accounted, within ODCM limits, and had a pre-planned method of termination or altering the flow rate.

ELEVATED RELEASE - A gaseous effluent release made from a height that is more than twice the height of adjacent solid structures GROUND-LEVEL RELEASE - A gaseous release made from a height that is at, or less than, the height of adjacent solid structures.

MONITORED RELEASE - A RELEASE which is monitored through installed or portable samplers.

NON-ROUTINE, PLANNED RELEASE/DISCHARGE - An effluent release from a release point that is not defined in the ODCM but that has been planned, monitored, and discharged in accordance with 10 CFR 20.2001.

UNCONTROLLED RELEASE/DISCHARGE - An effluent release that does not meet the definition of a controlled release SITE BOUNDARY For these Operational Requirements, the SITE BOUNDARY shall be identical to the EXCLUSION AREA BOUNDARY defined above.

SOLIDIFICATION SOLIDIFICATION shall be the conversion of wet wastes into a form that meets shipping and burial ground requirements.

SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

UNRESTRICTED AREA An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

G-3 Page 9-221

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 DEFINITIONS (continued)

VENTILATION EXHAUST TREATMENT SYSTEM A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Features Atmospheric Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

VENTING VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.

G-4 Page 9-222

Attachment 9 Summary of Changes to the Offsite Dose Calculation Manual Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant Offsite Dose Calculation Manual (ODCM) Revision 26 TABLE G-1 FREQUENCY NOTATION NOTATION FREQUENCY*

S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

W At least once per 7 days.

M At least once per 31 days.

Q At least once per 92 days.

SA At least once per 184 days.

R At least once per 18 months.

S/U Prior to each reactor startup.

N.A. Not applicable.

P Completed prior to each release.

Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

TABLE G-2 OPERATIONAL MODES Mode Reactivity Keff % RATED AVERAGE COOLANT Condition THERMAL POWER* TEMPERATURE 1 Power Operations 0.99 > 5% 350°F 2 Startup 0.99 5% 350°F 3 Hot Standby < 0.99 0 350°F 4 Hot Shutdown < 0.99 0 350°F > Tavg > 200°F 5 Cold Shutdown < 0.99 0 200°F 6 Refueling ** < 0.95 0 140°F

Excluding decay heat.

- Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.

G-5 Page 9-223

Attachment 10 Summary of Changes to the Process Control Program Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 ATTACHMENT 10 Summary of Changes to the Process Control Program This attachment includes a summary of changes to the PCP.

Page 10-1

Attachment 10 Summary of Changes to the Process Control Program Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 The Shearon Harris Nuclear Power Plant PCP Revision 12 was implemented in 2016 and provided in entirety in this section.

PLP-300 (HNP Process Control Program) directs HNP to follow specific vendor procedures to perform dewatering activities. The procedures that are referenced have become obsolete since EnergySolutions buyout of Studsvik.

EnergySolutions has developed a dewatering system that is offered in place of the Studsvik system. References to the Studsvik system and its procedures (FP-001, FP-003, & FP-004) will be replaced by the EnergySolutions system and corresponding procedures (CS-OP-PR-008 & CS-OP-PR-010). The purpose, applicability, applicable industrial &

radiological requirements, and acceptance criteria remain unchanged. Differences in the two sets of procedures are limited to step by step operating instructions.

No changes to plant safety systems or components, FSAR-described evaluation methodologies, or tests/experiments outside the bounds of the FSAR are effected by Rev 12 to the PCP.

The following is a summary of changes.

Updated to PAS (procedure automation system) format (format upgrade only) which included the following:

o Reordered sections o Moved old Section 5.1, Management Responsibilities, to new Section 4.0, Responsibilities.

o Removed abbreviations for "PCP" and "FSAR" previously located in the old Definitions/Abbreviations section.

Replaced "CP&L" with "Duke Energy" in Section 5.6 Step 1.

Replaced reference to "FP-003" with "CS-OP-PR-008" and "CS-OP-PR-010" in [7.3.3] and [7.3.4].

Replaced "Superintendent - RP" with "Manager - RP" in Section 4.2.

Page 10-2

Attachment 10 Summary of Changes to the Process Control Program Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Information Use HARRIS UNIT 1 PLANT PROGRAM PLP-300 PROCESS CONTROL PROGRAM REVISION 12 Page 10-3

Attachment 10 Summary of Changes to the Process Control Program Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 PROCESS CONTROL PROGRAM PLP-300 Rev. 12 Page 2 of 18 REVISION

SUMMARY

PRR 1979753 DESCRIPTION The following changes were implemented in this revision to support implementation of the Process Control Program:

Updated to PAS format (format upgrade only) which included the following:

Reordered sections Moved old Section 5.1, Management Responsibilities, to new Section 4.0, Responsibilities.

Removed abbreviations for "PCP" and "FSAR" previously located in the old Definitions/Abbreviations section.

Replaced "CP&L" with "Duke Energy" in Section 5.6 Step 1.

Replaced reference to "FP-003" with "CS-OP-PR-008" and "CS-OP-PR-010" in [7.3.3] and

[7.3.4].

Replaced "Superintendent - RP" with "Manager - RP" in Section 4.2.

Revised by Theresa Tripp.

Page 10-4

Attachment 10 Summary of Changes to the Process Control Program Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 PROCESS CONTROL PROGRAM PLP-300 Rev. 12 Page 3 of 18 TABLE OF CONTENTS SECTION .......................................................................................................................... PAGE 1.0 PURPOSE ..................................................................................................................... 4 2.0 SCOPE .......................................................................................................................... 4 3.0 DEFINITIONS ................................................................................................................ 4 4.0 RESPONSIBILITIES ...................................................................................................... 5 5.0 INSTRUCTIONS ............................................................................................................ 6 5.1 Background Information................................................................................................. 6 5.2 Review, Approval, And Changes ................................................................................... 6 5.3 General Requirements................................................................................................... 7 5.4 Implementation .............................................................................................................. 7 5.5 Waste Streams .............................................................................................................. 8 5.6 Vendor Solidification/Dewatering Requirements............................................................ 8 5.7 High Integrity Containers ............................................................................................. 10 5.8 Reporting Of Mishaps .................................................................................................. 11 5.9 10CFR61 Implementation ............................................................................................ 12 5.9.1 Waste Classification 10CFR61.55 .................................................................. 12 5.9.2 Radioactive Waste Characteristics 10CFR61.56 ........................................... 13 5.9.3 Labeling 10CFR61.57 .................................................................................... 13 5.10 10CFR20.2006 Implementation ................................................................................... 14 5.10.1 Shipment Manifest ......................................................................................... 14 5.10.2 Quality Control Program ................................................................................. 14 6.0 RECORDS................................................................................................................... 14

7.0 REFERENCES

............................................................................................................ 14 ATTACHMENTS 1 Solid Radwaste Programmatic Controls ...................................................................... 16 Page 10-5

Attachment 10 Summary of Changes to the Process Control Program Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 PROCESS CONTROL PROGRAM PLP-300 Rev. 12 Page 4 of 18 1.0 PURPOSE

1. The purpose of the Process Control Program (PCP) is to establish the management responsibilities and controls used at Harris Nuclear Power Plant (HNP) to provide reasonable assurance of complete dewatering and solidification of various radioactive waste.

2.0 SCOPE

1. This procedure demonstrates compliance with 10CFR20, 10CFR61, Plant Technical Specifications, Federal and State regulation, burial site requirements and other requirements governing the disposal of radioactive waste.

3.0 DEFINITIONS

1. Batch - For the purpose of the HNP PCP, a batch is a specific quantity of a particular waste stream which can be isolated from further inputs. This may be the volume in a tank or in a liner.

2. Dewatering - The process of removing water from a bed of solid waste.

Dewatering processes can also be used to prepare solid waste for shipment without solidification using cement or other chemical agents. Dewatered waste must meet NRC and burial site conditions on maximum drainable liquid content.

3. High Integrity Containers (HICs) - Containers certified by the burial state to meet the stability requirements for wastes requiring stability for disposal.

4. Liner - A container into which radioactive waste is placed for shipment to the burial site.

5. Qualified Process Control Program - A PCP which the testing to meet 10CFR61 requirements is underway or test results have been transmitted to the NRC, or agreement state, for approval.

6. Scaling Factor - The ratio of a hard to measure isotope to an isotope that is easily measured through techniques such as gamma-spectral analysis.

7. Solidification - The process of converting wet wastes, pretreatment chemicals, cement and the appropriate additives together to produce a free standing solidified form that meets shipping and burial ground requirements.

8. Solidification Formulation - The quantities of waste, pretreatment chemicals, cement and additives required to affect solidification. Also referred to as the recipe.

Page 10-6

Attachment 10 Summary of Changes to the Process Control Program Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 PROCESS CONTROL PROGRAM PLP-300 Rev. 12 Page 5 of 18 3.0 DEFINITIONS (continued)

9. Stable Waste - Wastes that, by virtue of their radionuclide content, have been dewatered in high integrity containers or solidified using a solidification formulation that results in a solidified product that meets the performance requirements of 10CFR61.56, Waste Characteristics.

10. Unstable Waste - Wastes that, by virtue of their radionuclide content, have been dewatered in steel liners or solidified to meet the minimum requirements of 10CFR61.56(a).

11. Waste Classification - The determination of a waste class as outlined in 10CFR61 by radionuclide isotopic analysis and/or correlation with other measured nuclides.

12. Waste Streams - Radioactive wastes are divided into separate waste streams categories based on scaling factors and characteristics of the waste.

4.0 RESPONSIBILITIES 4.1 General Manager - Harris Plant

1. Ensures that radioactive waste is processed and shipped per the appropriate state and federal regulations.

4.2 Manager - RP

1. Assures spent resin, radwaste filters, radwaste sludge, and radwaste evaporator concentrates and other radioactive wastes are processed and packaged per Attachment 1, Solid Radwaste Programmatic Controls, HPP-830, the PCP, and plant procedures.

2. Ensures that radioactive wastes are stored and shipped per plant procedures; and the state, burial site, and federal regulations.

3. Ensures radioactive wastes are sampled and classified per 10CFR61.

4.3 PCP Coordinator

1. Advises plant management on the appropriate technical standards, regulations, and requirements related to solidification and dewatering of radioactive waste.

2. Ensures the vendor's PCP and solidification/dewatering procedures are reviewed and approved as required.

Page 10-7

Attachment 10 Summary of Changes to the Process Control Program Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 PROCESS CONTROL PROGRAM PLP-300 Rev. 12 Page 6 of 18 4.3 PCP Coordinator (continued)

3. Retains vendor supplied documentation for NRC inspection and review.

4. Advises plant management on the appropriate technical standards, regulations, and requirements related to storage and shipment of radioactive waste.

5.0 INSTRUCTIONS 5.1 Background Information

1. The installed plant solidification system at HNP failed to meet the requirements of 10CFR61 and has been abandoned. Vendor processes and equipment are used for solidification and dewatering of radioactive waste. Attachment 1, Solid Radwaste Programmatic Controls, requires the Solid Radwaste System to be used per a vendor PCP to meet shipping and transportation requirements and disposal site criteria. It is the objective of the HNP PCP to provide reasonable assurance of meeting the applicable shipping, transportation, and disposal site requirements by:

Requiring solidification, dewatering, packaging, waste classification, and transportation to be done per the HNP PCP and approved plant procedures.

Defining the various solid radwaste waste streams at HNP.

Providing management programmatic controls for vendor solidification and dewatering of these waste streams.

Implementing the burial site disposal criteria.

Implementing a sampling and waste classification system per 10CFR61.55 and 10CFR20.2006 Appendix F to 20.1001-20.2402.

Providing a quality control program required by 10CFR20.2006 Appendix F to 20.1001-20.2402.

5.2 Review, Approval, And Changes

1. The HNP PCP shall be reviewed by the PNSC and approved by the NRC before implementation. Revision 0 of the HNP PCP was submitted to the NRC in September 1985 and approved in the Shearon Harris Safety Evaluation Report, (NUREG-1038) Supplement #3.

Page 10-8

Attachment 10 Summary of Changes to the Process Control Program Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 PROCESS CONTROL PROGRAM PLP-300 Rev. 12 Page 7 of 18 5.2 Review, Approval, And Changes (continued)

2. Changes to the PCP shall be reviewed by the PNSC per Technical Specification 6.13. Certain Vendor PCP procedures (referenced in HPP-830) shall be included in the HNP PCP and are subject to the same review by the PNSC as changes to this Program.

5.3 General Requirements

1. All radioactive waste shall be processed, packaged, classified, and shipped to the burial site per the requirements of the HNP PCP.

2. Class A Unstable waste products need only demonstrate that the product is a free standing monolith with NO more than 0.5 percent of the waste volume as free liquid. Qualified Individuals shall ensure that Class A Stable, Class B and Class C wastes meet stability requirements of 10CFR61 or be packaged in a High Integrity Container approved by the burial site.

3. Solidification and/or dewatering shall be done by qualified individuals who have completed a solidification and/or dewatering training and qualification program.

4. If solidification does NOT meet disposal site and shipping/transportation requirements, the PCP Coordinator/designee shall immediately suspend shipment of inadequately processed waste and correct the PCP, the implementing procedures, and/or the Solid Waste Processing System to prevent recurrence.

5. If solidification is NOT performed per the HNP PCP, the PCP Coordinator/designee shall ensure the processed waste in each container is tested to ensure it meets burial site and shipping requirements and take appropriate actions to prevent recurrence.

6. With the installed Solid Waste Processing equipment incapable of meeting requirements of Attachment 1, Solid Radwaste Programmatic Controls, or declared inoperable, the PCP Coordinator/designee shall ensure the equipment is returned to operable status or provide for contract capability to process waste as necessary to satisfy applicable transportation and disposal requirements.

5.4 Implementation

1. The HNP PCP shall be implemented by use of approved plant procedures.

These procedures shall provide step-by-step direction for the operation of solidification and dewatering systems and for transportation/disposal of waste at a licensed burial facility. All plant procedures which implement the PCP shall be reviewed and approved per Technical Specification 6.13.

Page 10-9

Attachment 10 Summary of Changes to the Process Control Program Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 PROCESS CONTROL PROGRAM PLP-300 Rev. 12 Page 8 of 18 5.5 Waste Streams

1. Radioactive wastes are divided into separate waste stream categories based on scaling factors and characteristics of the waste and/or batch. Waste streams at HNP include, but are NOT limited to:

Dry Active Waste (DAW)

Radwaste Filters

Radwaste Resin/Charcoal

CVCS Resin/BTRS Resin/Spent Fuel Pool Resin

Sludge

Evaporator Concentrates

Spent Fuel Pool Charcoal

Spent Fuel Pool Filters

Decontamination Waste

Oil 5.6 Vendor Solidification/Dewatering Requirements

1. Before performing solidification/dewatering services at HNP, the vendor shall provide documentation on the following for Duke Energy review, evaluation, and retention:

a. A qualified PCP or a program approved by the NRC, or agreement state.

For each low-level radioactive waste formulation, the PCP (reference HPP-830 for current vendor PCP) should address the boundary conditions for processing the waste to provide reasonable assurance that the final waste form will meet 10CFR61 stability requirements.

b. Topical Report for Solidification/Dewatering including review and acceptance letter from the NRC, or agreement state.

c. Copy of the 10CFR61 Testing Program to meet stability requirements including submittal letter or NRC approval letter. This is NOT required if the vendor only performs dewatering service or solidification of waste NOT requiring stability.

d. Sketch or drawing of the solidification/dewatering process system.

Page 10-10

Attachment 10 Summary of Changes to the Process Control Program Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 PROCESS CONTROL PROGRAM PLP-300 Rev. 12 Page 9 of 18 5.6 Vendor Solidification/Dewatering Requirements (continued)

e. Detailed procedures for operation of the solidification/dewatering equipment and inspection and use of containers.

f. Documentation that the operator has been qualified per the vendor's solidification/dewatering training and qualification program.

g. Identification of solidification agent(s) and formulation used by the process.

h. Copies of the Technical Specification(s) and Material Safety Data Sheets for all chemicals that will be used by the vendor.

i. Certificate of Compliance for any High Integrity Containers and a list of incompatible waste.

2. The vendor is accountable to the PCP Coordinator/designee for the solidification and/or dewatering of liquid waste. The RP unit is responsible for shipping of solidified and dewatered wastes.

3. Solidification and/or dewatering shall be done by qualified individuals who have completed a solidification and/or dewatering training and qualification program.

Certification shall be provided by the vendor for vendor operators and shall be on file prior to any solidification/dewatering work performed by the individual.

4. Solidification and/or dewatering shall be done per approved procedures described in HPP-830.

5. As required by Attachment 1, Solid Radwaste Programmatic Controls, a test solidification of at least every tenth batch of each type of wet radioactive waste shall be performed. Test solidification of every batch may be performed if desired.

6. If any test specimen fails to verify solidification, the solidification of the batch under test shall NOT be performed until such time as additional test specimens can be obtained, alternative solidification parameters can be determined, and a subsequent test verifies solidification. Solidification of the batch may then be resumed using the alternative solidification parameters.

7. If the initial test specimen from a batch of waste fails to verify solidification, then representative test samples shall be collected from each consecutive batch of the same type of wet waste until at least three consecutive initial test specimens demonstrate solidification.

Page 10-11

Attachment 10 Summary of Changes to the Process Control Program Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 PROCESS CONTROL PROGRAM PLP-300 Rev. 12 Page 10 of 18 5.6 Vendor Solidification/Dewatering Requirements (continued)

8. For high activity waste, where handling samples could result in personnel radiation exposures which are inconsistent with ALARA principles, representative non-radioactive samples may be test solidified. These samples shall be as close to the actual waste and chemical properties as possible. For resins, the resin beads shall be depleted prior to test solidification.

9. The quality of the solidified and/or dewatered product shall meet or exceed regulatory requirements and the disposal site criteria prior to release from the HNP site. Copies of the site disposal criteria shall be maintained by the PCP Coordinator/designee. The site disposal criteria requirements are implemented as requirements by reference from this PCP.

5.7 High Integrity Containers

1. With the approval from the land disposal facility, wastes may be disposed of in approved high integrity containers (HICs). Certificate of Compliance from the disposal facility shall be on file prior to use of any high integrity containers.

2. The maximum allowable free liquid in a high integrity container shall be less than one percent of the waste volume.

3. Corrosion and chemical tests should be performed to confirm the suitability of the proposed container. List of prohibited contents should be available. If it is suspected that the waste may contain any of the prohibited chemicals, chemical tests shall be run to verify the absence of the chemical. As a minimum, the waste pH shall be determined to be within the acceptable range for the HIC.

4. Written procedures or documentation for use, inspection and storage of a HIC shall be provided by the manufacturer/supplier.

5. The length of on-site storage of HICs may vary depending on the type of container. Procedures for use and storage of HICs should contain maximum storage times. Photosensitive containers shall be kept out of direct sunlight and away from any other sources of ultraviolet radiation.

6. HICs shall be inspected prior to use.

Page 10-12

Attachment 10 Summary of Changes to the Process Control Program Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 PROCESS CONTROL PROGRAM PLP-300 Rev. 12 Page 11 of 18 5.8 Reporting Of Mishaps

1. Any knowledge of misuse or failure of waste forms and containers shall be reported to the NRC's Director of the Division of Low Level Waste Management and Decommissioning and the designated State disposal site regulatory authority within 30 days of the knowledge of the incident. An Condition Report shall be completed and sent to Regulatory Compliance Unit. For any such waste form mishap occurrence, the affected waste form should NOT be shipped off-site until approval is obtained from the disposal site regulatory authority. Such mishaps include, but are NOT necessarily limited to:

a. The failure of high integrity containers used to ensure structural stability.

Such failure may be evidenced by changed container dimensions, cracking, or injury from mishandling.

b. The misuse of high integrity containers, as evidenced by a quantity of free liquid greater than or equal to one percent of the waste volume, or an excessive void space within the container.

c. The production of solidified Class A Stable, Class B, or Class C waste form that has any of the following characteristics:

(1) Greater than 0.5 percent volume of free liquid.

(2) Concentrations of radionuclides greater than the concentrations demonstrated to be stable in the waste form in qualification testing accepted by the regulatory agency.

(3) Greater or lesser amounts of solidification media than were used in qualification testing accepted by the regulatory agency.

(4) Contains chemical ingredients NOT present or accounted for in qualification testing accepted by the regulatory agency.

(5) Shows instability evidenced by crumbling, cracking, spalling, voids, softening, disintegration, non homogeneity, or change in dimensions.

(6) Evidences processing phenomena that exceed the limiting processing conditions identified in applicable topical reports or PCPs, such as foaming, excessive temperature, premature or slow hardening, production of volatile material.

Page 10-13

Attachment 10 Summary of Changes to the Process Control Program Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 PROCESS CONTROL PROGRAM PLP-300 Rev. 12 Page 12 of 18 5.9 10CFR61 Implementation Solidified radioactive waste packaged for disposal at a licensed burial facility shall meet the requirements of 10CFR61.

5.9.1 Waste Classification 10CFR61.55

1. Waste is determined to be generally unacceptable for near-surface disposal if it contains any of the radionuclides listed in Table 1 and 2 of 10CFR61.55 in concentrations exceeding the limits established for the radionuclides.

Compliance with these limits shall be determined prior to shipment.

2. Waste transported for disposal must be classified as Class A, Class B, or Class C for the purpose of segregation at the disposal site. The waste class is based on the concentration of certain radionuclides in the waste form as given in 10CFR61.55.

3. Waste shall be classified based on isotopic analysis and the use of scaling factors for hard to measure isotopes. Initially, generic scaling factors will be used for waste classification. Each waste stream shall then be sampled after the first three months of commercial operation or prior to the first shipment if generated after the first three months of commercial operation.

4. Confirmatory sampling for Class A waste shall be performed on a bi-annual basis. Class B and Class C wastes shall be sampled for confirmation of scaling factors at least on an annual basis. These frequencies may be extended based on fuel performance factors influencing the affected waste stream. Samples shall NOT be required if the waste stream is NOT generated during the sampling frequency. These infrequently generated waste stream shall be sampled and the scaling factors updated prior to shipment. In addition, a waste stream shall be sampled if it is determined that a factor of 10 shift in any scaling factor has occurred in that waste stream.

5. If the plant is in an outage period at the same time the sampling period is due, the sampling period may be delayed until after the outage period. Resampling should NOT be completed until after two months at full power operation to allow the reactor water chemistry and waste stream characteristics to stabilize.

6. A computerized waste classification and shipping program is normally used to determine waste classification from isotopic analysis and the scaling factors.

Manual methods may be used if the computer system is NOT available. Waste Classification is controlled by HPS-NGGC-0001.

Page 10-14

Attachment 10 Summary of Changes to the Process Control Program Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 PROCESS CONTROL PROGRAM PLP-300 Rev. 12 Page 13 of 18 5.9.2 Radioactive Waste Characteristics 10CFR61.56

1. The eight minimum waste characteristics identified in 10CFR61.56(a) and listed below shall apply to any waste solidified or dewatered at HNP.

a. Waste must NOT be packaged for disposal in cardboard or fiberboard boxes.

b. Liquid waste must be solidified or packaged in sufficient absorbent material to absorb twice the volume of the liquid.

c. Solid waste containing liquid shall contain as little free standing and noncorrosive liquid as is reasonably achievable, but in NO case shall the liquid exceed 1% of the volume.

d. Waste must NOT be readily capable of detonation or of explosive decomposition or reaction at normal pressures and temperatures, or of explosive reaction with water.

e. Waste must NOT contain, or be capable of generating, quantities of toxic gases, vapors, or fumes harmful to persons transporting, handling, or disposing of the waste.

f. Waste must NOT be pyrophoric. Pyrophoric materials contained in waste shall be treated, prepared, and packaged to be nonflammable.

g. Waste in a gaseous form must be packaged at a pressure that does NOT exceed 1.5 atmospheres at 20°C. Total Activity must NOT exceed 100 curies per container.

h. Waste containing hazardous, biological, pathogenic, or infectious material must be treated to reduce to the maximum extent practicable the potential hazard from the non-radiological materials.

2. Waste stability requirements are assured by the requirement in Section 5.3 for the vendor to provide a copy of the 10CFR61 Testing Program for Waste Stability.

5.9.3 Labeling 10CFR61.57

1. Each package of waste shall be clearly labeled to identify the appropriate waste classification per Section 5.6.1.

Page 10-15

Attachment 10 Summary of Changes to the Process Control Program Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 PROCESS CONTROL PROGRAM PLP-300 Rev. 12 Page 14 of 18 5.10 10CFR20.2006 Implementation Radioactive waste transferred for disposal by Harris Nuclear Plant shall meet the requirements of 10CFR20.2006 and Appendix F to 20.1001-20.2402.

5.10.1 Shipment Manifest The requirements of 10CFR20.2006 and Appendix F to 20.1001-20.2402 for shipment manifest and record keeping shall be included in HPS-NGGC-0001.

5.10.2 Quality Control Program

1. The quality control program consists of required use of plant procedures which implement the PCP and audits by personnel independent of the activities.

2. The PCP and implementing procedures for processing and packaging radioactive wastes are audited once per 24 months by Nuclear Oversight (NOS) per plant FSAR Section 17.3. These audits shall be reviewed by the Superintendent - RP.

6.0 RECORDS

1. No QA records are generated by this procedure.

7.0 REFERENCES

7.1 Commitments None 7.2 Procedures

1. HPS-NGGC-0001, Radioactive Material Shipping Procedure

2. HPP-830, Process Control Program Implementation 7.3 Miscellaneous Documents

1. 10CFR20.2006, Transfer for Disposal and Manifests

2. 10CFR61, Licensing Requirements for Land Disposal of Radioactive Waste

3. CS-OP-PR-008, Setup and Operation of EnergySolutions Self-Engaging Dewatering Systems Fillhead Page 10-16

Attachment 10 Summary of Changes to the Process Control Program Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 PROCESS CONTROL PROGRAM PLP-300 Rev. 12 Page 15 of 18 7.3 Miscellaneous Documents (continued)

4. CS-OP-PR-010, Bead Resin/Activated Carbon Dewatering Procedure For EnergySolutions14-215 Or Smaller Liners, Utilizing EnergySolutions Self-Engaging Dewatering System

5. FO-AD-002, Operating Guidelines For Use Of Polyethylene High Integrity Containers

6. HNP Technical Specification 6.13, Process Control Program

7. Issuance of Final Branch Technical Position on Concentration Averaging and Encapsulation, Revision in Part to Waste Classification Technical Position -

January 1995

8. NUREG-0133, Preparation of Radiological Effluent Technical Specification for Nuclear Power Plants

9. NUREG-0472, Radiological Effluent Technical Specification for PWR, July 1979

10. NUREG-1038, Supplement #3, Safety Evaluation Report

11. Technical Position on Waste Form - January 1991

12. USNRC Generic Letter 89-01, Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program Page 10-17

Attachment 10 Summary of Changes to the Process Control Program Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 PROCESS CONTROL PROGRAM PLP-300 Rev. 12 Page 16 of 18 ATTACHMENT 1 Page 1 of 3

<< Solid Radwaste Programmatic Controls >>

3/4.11.3 SOLID RADIOACTIVE WASTES (historical information removed from Technical Specifications)

OPERATIONAL REQUIREMENT 3.11.3 Radioactive wastes shall be solidified or dewatered per the PROCESS CONTROL PROGRAM to meet shipping and transportation requirements during transit, and disposal site requirements when received at the disposal site.

APPLICABILITY: At all times.

ACTION:

a. With SOLIDIFICATION or dewatering NOT meeting disposal site and shipping and transportation requirements, suspend shipment of the inadequately processed wastes and correct the PROCESS CONTROL PROGRAM, the procedures, and/or the Solid Waste System as necessary to prevent recurrence.

b. With SOLIDIFICATION or dewatering NOT performed per the PROCESS CONTROL PROGRAM, test the improperly processed waste in each container to ensure that it meets burial ground and shipping requirements and take appropriate administrative action to prevent recurrence.

SURVEILLANCE REQUIREMENTS 4.11.3 SOLIDIFICATION of at least one representative test specimen from at least every tenth batch of each type of wet radioactive wastes (for example, filter sludges, spent resins, evaporator bottoms, boric acid solutions, and sodium sulfate solutions) shall be verified per the PROCESS CONTROL PROGRAM:

a. If any test specimen fails to verify SOLIDIFICATION, the SOLIDIFICATION of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative SOLIDIFICATION parameters can be determined per the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION. SOLIDIFICATION of the batch may then be resumed using the alternative SOLIDIFICATION parameters determined by the PROCESS CONTROL PROGRAM; Page 10-18

Attachment 10 Summary of Changes to the Process Control Program Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 PROCESS CONTROL PROGRAM PLP-300 Rev. 12 Page 17 of 18 ATTACHMENT 1 Page 2 of 3

<< Solid Radwaste Programmatic Controls >>

b. If the initial test specimen from a batch of waste fails to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall provide for the collection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least three consecutive initial test specimens demonstrate SOLIDIFICATION. The PROCESS CONTROL PROGRAM shall be modified as required, as provided in Technical Specification 6.13, to assure SOLIDIFICATION of subsequent batches of waste; and

c. With the installed equipment incapable of meeting Effluent Specification 3.11.3 or declared inoperable, restore the equipment to OPERABLE status or provide for contract capability to process wastes as necessary to satisfy all applicable transportation and disposal requirements.

3/4.11.3 SOLID RADIOACTIVE WASTES BASES This specification implements the requirements of 10CFR50.36a, 10CFR61, and General Design Criterion 60 of Appendix A to 10CFR50. The process parameters included in establishing the PROCESS CONTROL PROGRAM may include, but are NOT limited to, waste type, waste pH, waste/liquid/SOLIDIFICATION agent/catalyst ratios, waste oil content, waste principal chemical constituents, and mixing and curing times.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6.9.1.4 Routine Annual Radioactive Effluent Release Reports covering the operation of the unit during the previous year of operation shall be submitted by May 1 of each year. The period of the first report shall begin with the date of initial criticality.

The Annual Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof. For solid wastes, the format for Table 3 in Appendix B shall be supplemented with three additional categories: class of solid wastes (as defined by 10CFR61), type of container (for example, Type A, Type B) and SOLIDIFICATION agent or absorbent (for example, cement).

Page 10-19

Attachment 10 Summary of Changes to the Process Control Program Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 PROCESS CONTROL PROGRAM PLP-300 Rev. 12 Page 18 of 18 ATTACHMENT 1 Page 3 of 3

<< Solid Radwaste Programmatic Controls >>

6.15 MAJOR CHANGES TO SOLID RADWASTE TREATMENT SYSTEMS* (Operational Requirement)

Licensee-initiated major changes to the Solid Radwaste Treatment Systems:

a. Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed per Technical Specification 6.9. The discussion of each change shall contain:

1. A summary of the evaluation that led to the determination that the change could be made per 10CFR50.59;

2. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;

3. A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems;

4. An evaluation of the change, which shows the predicted quantity of solid waste that differ from those previously predicted in the License application and amendments thereto;

5. A comparison of the predicted releases of radioactive materials, in solid waste, to the actual releases for the period prior to when the change is to be made;

6. An estimate of the exposure to plant operating personnel as a result of the change; and

7. Documentation of the fact that the change was reviewed and found acceptable per Technical Specification 6.13.

b. Shall become effective upon review and acceptance per Technical Specification 6.13.

Licensees may choose to submit the information called for in this Operational Requirement as part of the annual FSAR update.

Page 10-20

Attachment 11 Summary of Major Modifications to the Radioactive Waste Treatment Systems Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 ATTACHMENT 11 Summary of Major Modifications to the Radioactive Waste Treatment Systems This attachment includes a description of major modifications to the radioactive waste treatment systems that are anticipated to affect effluent releases.

Page 11-1

Attachment 11 Summary of Major Modifications to the Radioactive Waste Treatment Systems Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 One major modification to Shearon Harris Nuclear Power Plant liquid, gaseous, solid, or mobile radioactive waste treatment systems occurred in 2016.

The Modular Fluidized Transfer Demineralizer System (MFTDS) is a radwaste processing set of equipment on Waste Processing Building Elev 236' that the plant uses to reduce floor drain, equipment drain and laundry/hot shower liquid waste to levels low enough to discharge to the environment. The water may be processed through the MFTDS as many times as necessary to reduce nuclide concentration.

EC 400448 modified the MFTDS equipment by adding a prefilter (F-40) and replacing two existing bag filters (F-50 &

F-60) with deep bed granular activated carbon (GAC) filters. Each GAC filter is be mobile and has hose quick-connect fittings compatible with the existing MFTDS hose fittings. Each mobile GAC filter has a mobile shield package to facilitate radwaste shipping for offsite disposal of the spent carbon and recharging with fresh carbon.

Stationary radiation shielding was provided to minimize general area dose rates in the MFTDS room. The new prefilter (F-40) was added upstream of the GAC filters due to the sludge heels in the Floor Drain Tanks. The prefilter contains the same type and size bag elements contained in the existing bag filter (F-4) currently used to prefilter the influent to the MFTDS.

Many plants have already switched their radwaste processing systems to use activated carbon. Activated carbon offers the benefit of retaining and stripping several high energy nuclides of electrons which predisposes them for efficient removal in the MFTDS demineralizers. GAC filters have proven to be reliable for removal of dirt, turbidity, oil, color, organics and colloidal particulate (including Co-58, Co-60, Ag-110, and Mn-54) in significantly larger volumes than cartridge filters. This deep bed filtration method increases the life of the downstream media, thus reducing secondary radioactive waste generation and personnel exposure resulting from media replacement.

The change was reviewed and approved by the Plant Nuclear Safety Committee on May 19, 2016.

Page 11-2

Attachment 12 Errata to a Previous Year's ARERR Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 ATTACHMENT 12 Errata to a Previous Year's ARERR This attachment includes any amended pages from a previous year's ARERR.

Page 12-1

Attachment 12 Errata to a Previous Year's ARERR Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 The following contains amended pages to the Shearon Harris Nuclear Power Plant 2015 ARERR. Amended pages are identified with "Amendment #" on page. Specific changes are identified with change bars in right margin.

The Shearon Harris Nuclear Power Plant 2015 ARERR Amendment #1 requires the following change from Page 3-2:

Shearon Harris Nuclear Power Plant 2015 ARERR as submitted:

Burial Total Type of Number of Number of Waste Container Solidification Volume Activity Waste Shipped Shipments Containers Class Type Agent 3 (m ) (Curies)

1. Waste from Liquid Systems

a. Dewatered Spent Resins NRC 2 2 A N/A 8.04 2.92E-01 (compacted) Approved

b. Evaporator Concentrates 0 - - - - - -

c. Dewatered Demineralizers 0 - - - - - -

d. Solidified (cement) Acids, 0 - - - - - -

Oils, Sludge

2. Dry Solid Waste

a. Dry Active Waste 0 - - - - - -

(compacted)

b. Dry Active Waste (dewatered, NRC 5 5 A N/A 294 6.45E-01 non-compacted) Approved

c. Dry Active Waste (brokered) 0 - - - - - -

d. Irradiated Components NRC 1 1 A N/A 294 1.39E-01 (dewatered, non-compacted) Approved

3. Total Solid Waste 8 8 596.04 1.08E+00 Page 12-2

Attachment 12 Errata to a Previous Year's ARERR Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Shearon Harris Nuclear Power Plant 2015 ARERR Amendment #1 as revised:

Burial Total Type of Number of Number of Waste Container Solidification Volume Activity Waste Shipped Shipments Containers Class Type Agent 3 (m ) (Curies)

1. Waste from Liquid Systems

a. Dewatered Spent Resins NRC 2 2 A N/A 8.0 2.92E-01 (compacted) Approved

b. Evaporator Concentrates 0 - - - - - -

c. Dewatered Demineralizers 0 - - - - - -

d. Solidified (cement) Acids, 0 - - - - - -

Oils, Sludge

2. Dry Solid Waste

a. Dry Active Waste 0 - - - - - -

(compacted)

b. Dry Active Waste (dewatered, NRC 5 5 A N/A 59.2 6.45E-01 non-compacted) Approved

c. Dry Active Waste (brokered) 0 - - - - - -

d. Irradiated Components NRC 1 1 A N/A 3.2 1.39E-01 (dewatered, non-compacted) Approved

3. Total Solid Waste 8 8 70.5 1.08E+00 Page 12-3

Attachment 12 Errata to a Previous Year's ARERR Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2016 - 12/31/2016 Attachment 3 Solid Radioactive Waste Disposal Shearon Harris Nuclear Power Plant Unit 1 Period 1/1/2015 - 12/31/2015 Burial Total Type of Number of Number of Waste Container Solidification Volume Activity Waste Shipped Shipments Containers Class Type Agent 3 (m ) (Curies)

1. Waste from Liquid Systems

a. Dewatered Spent Resins NRC 2 2 A N/A 8.0 2.92E-01 (compacted) Approved

b. Evaporator Concentrates 0 - - - - - -

c. Dewatered Demineralizers 0 - - - - - -

d. Solidified (cement) Acids, 0 - - - - - -

Oils, Sludge

2. Dry Solid Waste

a. Dry Active Waste 0 - - - - - -

(compacted)

b. Dry Active Waste (dewatered, NRC 5 5 A N/A 59.2 6.45E-01 non-compacted) Approved

c. Dry Active Waste (brokered) 0 - - - - - -

d. Irradiated Components NRC 1 1 A N/A 3.2 1.39E-01 (dewatered, non-compacted) Approved

3. Total Solid Waste 8 8 70.5 1.08E+00 Page 3-2 Shearon Harris Nuclear Plant 2015 ARERR Amendment #1 Page 12-4

HNP-17-023, Annual Radioactive Effluent Release Report

Contents

Text

Subject:

Subject:

SUMMARY

SUMMARY

SUMMARY

1.0 INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

SUMMARY

1.0 INTRODUCTION

SUMMARY

7.0 REFERENCES

7.0 REFERENCES

Navigation menu

HNP-17-023, Annual Radioactive Effluent Release Report

Text

Subject:

Subject:

SUMMARY

SUMMARY

SUMMARY

1.0 INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

SUMMARY

1.0 INTRODUCTION

SUMMARY

7.0 REFERENCES

7.0 REFERENCES

Navigation menu

Search