HNP-15-029, Annual Radioactive Effluent Release Report for 2014: Difference between revisions

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{{#Wiki_filter:Benjamin C. Waldrep
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*DUKE 4 ENERGY.                                                                                  Vice President Harris Nuclear Plant 5413 Shearon Harris Rd New Hill NC 27562-9300 919-362-2502 APR 1 6 2015 Serial: HNP-15-029 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, Inc., is providing the enclosed Annual Radioactive Effluent Release Report for 2014.
This submittal contains no regulatory commitments. Please refer any questions regarding this submittal to Dave Corlett, Manager - Regulatory Affairs, at (919) 362-3137.
Sincerely, Benjamin C. Waldtep Enclosure cc:      Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Ms. M. Barillas, NRC Project Manager, HNP Mr. V. M. McCree, NRC Regional Administrator, Region II p~-ooc1
 
Duke Energy Progress, Inc.
Shearon Harris Nuclear Power Plant Docket No. 50-400 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January 1, 2014, through December 31, 2014
                    -I-
 
Table of Contents Section                                                                  Page No.
Introduction                                                                    3 Discussion                                                                      3 Appendix 1. Supplemental Information                                            7 Appendix 2. Effluent and Waste Disposal Report
: 1.      Lower Limits of Detection (LLDs)                          11
: 2.      Effluents Released                                        13
: 3.      Solid Waste Disposal                                      22 Appendix 3. Changes to Offsite Dose Calculation Manual (ODCM)                  28 Appendix 4. Changes to the Environmental Monitoring Program
: 1.      Environmental Monitoring Program                          32
: 2.      Land Use Census                                          32 Appendix 5. Additional Operational Requirements
: 1.      Inoperability of Liquid Effluent Monitors                33
: 2.      Inoperability of Gaseous Effluent Monitors                33
: 3.      Unprotected Outdoor Tanks Exceeding Limits                33
: 4.      Gas Storage Tanks Exceeding Limits                        33
: 5.      Groundwater samples taken in Support of Groundwater Protection Initiative NEI 07-07                          34 Appendix 6. Major Modifications to Radwaste System                            34 Appendix 7. Meteorological Data                                                34 Appendix 8. Assessment of Radiation Doses                                      35 Appendix 9. Corrections to Previous Annual Report                              38 Appendix 10. ODCM Revision 25                                                  38
 
Introduction This Annual Radioactive Effluent Release Report is prepared in accordance with Shearon Harris Nuclear Power Plant's Operational Requirements - Offsite Dose Calculation Manual (ODCM), Appendix F Section F.2, and Technical Specification 6.9.1.4, Renewed Operating License No. NPF-63.
The Harris Nuclear Power Plant (HNP) achieved initial criticality on January 3, 1987. This Report covers the period from January 1, 2014, to December 31, 2014. During this period, the plant operated in Cycle 19.
Discussion I1. Protection Standards The main objective in the control of radiation is to ensure that any exposure is kept not only within regulatory limits, but As Low As Reasonably Achievable (ALARA). The ALARA concept applies to reducing radiation exposure both to workers at Harris Nuclear Plant and to the general public. "Reasonably Achievable" means that radiation exposure reduction is based on sound environmental practices, economic decisions, and operating practices. By practicing ALARA, Harris Nuclear Plant and Duke Energy Progress, Inc. minimize health risk, environmental detriment, and ensure that exposures are maintained well below regulatory limits.
: 2. Sources of Radioactivity Released During normal operations of a nuclear power station, most of the fission products are retained within the fuel and fuel cladding. However, small quantities of radioactive fission and activation products are present in the primary coolant water. The types of radioactive material released are noble gases, carbon-14, iodines and particulates, and tritium.
The noble gas fission products in the primary coolant are collected by a system designed for collection and storage for radioactive decay prior to release.
Small releases of radioactivity in liquids may occur from equipment associated with the primary coolant system. These liquids are collected and processed for radioactivity removal prior to release.
: 3. Noble Gas Some of the fission products released in airborne effluents are radioactive isotopes of noble gases, such as krypton and xenon. Noble gases are by nature inert and do not concentrate in humans or other organisms; therefore internal exposure is negligible. Their contribution to human radiation exposure is as an external exposure. Xenon-133 and Xenon-135, with half-lives of approximately 5 days and 9 hours respectively, are the major isotopes released. Half-life is defined as the time required for a radioactive isotope to lose 50 percent of its radioactivity by decay. Noble gases are readily dispersed in the atmosphere.
: 4. lodines and Particulates The annual release of iodines and particulates is small. Factors such as chemical reactivity and solubility in water, combined with high processing efficiencies, minimize their discharge. The main contribution of radioactive iodine to human exposure is to the thyroid gland, where the body concentrates iodine. The principal radioactive particulates are Cobalt-58, Cobalt-60, and Nickel-63 which contribute to internal exposure of tissues such as the muscle, liver, and intestines. These particulates can also be a source of exposure if deposited on the ground.
: 5. Tritium Tritium, a radioactive isotope of hydrogen, is the predominant radionuclide in liquid and gaseous effluents.
Tritium is produced in the reactor coolant as a result of neutron interaction with deuterium (also a hydrogen isotope) and boron, both of which are present in the primary coolant. Tritium contributes very little radiation exposure to the human body, and when it is inhaled or ingested, is dispersed throughout the body until eliminated.
: 6. Carbon-14 The concentration and offsite dose from carbon-14 has been estimated by using a calculation approach, assuming typical or maximum values for the various calculation parameters. The carbon-14 source term is based on measurements at 10 operational power plants and is documented in NUREG-0017 Rev 1. The 7.3 Curies carbon-14 source term in NUREG-0017 Rev I assumes an 80% capacity factor. The calculation normalizes the carbon-14 source term to actual electrical capacity for the entire year. Due to the reducing environment of a Pressured Water Reactor only 30% of the carbon-14 is assumed to be released in the Carbon Dioxide form, dose is not expected from other forms (methane, etc). The resultant offsite doses were based upon this source term and the dose calculations described in Reg. Guide 1.109.
: 7. Processing and Monitoring Effluents are strictly controlled and monitored to ensure that radioactivity released to the environment is minimal and within regulatory limits. Effluent control includes the operation of radiation monitoring systems, in-plant and environmental sampling and analyses, quality assurance programs for both in-plant and environmental sampling and analyses, and procedures that address effluent and environmental monitoring.
The plant radiation monitoring system has monitors that are designed to ensure that releases are below regulatory limits. Each instrument provides indication of the amount of radioactivity present and is equipped with alarms and indicators in the control room. The alarm setpoints are set lower than the ODCM Operational Requirements to ensure the limits are not exceeded. If a monitor alarms, a release from a tank is automatically suspended. Additionally, batch releases are sampled and analyzed in the laboratory prior to discharge. The sampling and analysis done in the laboratory provides a more sensitive and precise method of determining effluent composition than in-plant monitoring instruments.
The plant has a meteorological tower, which is linked to computers that record the meteorological data.
The meteorological data and the release data can be used to assess the dose to the public. The doses reported in this report use five-year average (2003 through 2007) data from the onsite meteorological program.
 
In addition to in-plant equipment the company maintains a Radiological Environmental Monitoring Program, which consists of devices used to constantly sample the air and water in the environment. The samples collected from the surrounding environment are analyzed to determine any presence of radioactive material in the environment.
: 8. Exposure Pathways Radiological exposure pathways are the methods by which people may become exposed to radioactive material. The major pathways of concern are those that could cause the highest calculated radiation dose.
The projected pathways are determined from the type and amount of radioactive material that may have been released, the environmental transport mechanism, and the use of the environment. Environmental transport mechanisms include, but are not limited to, local hydrology (water) and meteorology (weather).
The release of radioactive gaseous effluents can impact the public via pathways such as external whole body exposure, deposition on plants and soils, and human inhalation. The release of radioactive material in liquid effluents can impact the public via pathways such as drinking water, fish consumption, and direct exposure from the lake at the shoreline and submersion dose while swimming.
Even though radionuclides can reach humans by many different pathways, some radionuclides result in more exposure than others. The critical pathway is the exposure that will provide, for a specific radionuclide, the greatest exposure to a population, or a specific group of the population, called the critical group. The critical group may vary depending on the radionuclides involved, the age and diet of the group, and other cultural factors. The exposure may be received to the whole body or to a specific organ, with the organ receiving the largest fraction of the exposure called the critical organ.
: 9. Results The quantities of radioactive gaseous and liquid effluents and solid waste are reported using the format per Regulatory Guide 1.21 (Rev. 1) Appendix B.
The Radioactive Effluent Release Report is a detailed listing of the radioactivity released from the Harris Nuclear Plant during the period from January 1, 2014, through December 31, 2014. The assessment of annual radiation doses to members of the public from radioactive liquid and gaseous effluents from the plant are estimated using the methodology in the ODCM.
 
During the period of January 1, 2014, through December 31, 2014, the estimated maximum individual offsite dose due to radioactivity released in effluents was:
Liquid Effluents:                                                                    Limit 1.08 E-02 mrem, Total Body                                        3.0 E+00 mrem 1.68 E-02 mrem, Max Organ (GI-LLI)                                1.0 E+01 mrem Gaseous Effluents:                                                                  Limit Noble Gases 2.83 E-04 mrad, Beta                                              2.0 E+01 mrad 9.52 E-05 mrad, Gamma                                              1.0 E+01 mrad Tritium, Radioiodine 131, 133, and Particulates with greater than an 8 Day Half Life:
7.40 E-01 mrem, Critical Organ (Lung)                          1.5 E+01 mrem(*)
Carbon 14 5.32 E-01 mrem, Critical Organ (Bone)                          1.5 E+01 mrem(*)
(*) Limit applies to Tritium, Radioiodines, and Particulates with greater than an 8-Day Half Life:
These doses are in addition to what is received from natural background in the area surrounding the Harris Nuclear Plant (approximately 300 mrem per year).
 
Appendix 1: Supplemental Information Regulatory Limits A. Fission and Activation Gases:
ODCM Operational Requirements Maximum Instantaneous Concentration Total Body Dose <500 mrem/yr Skin Dose <3000 mrem/yr 10CFR20 Limits Annual Average Concentrations as specified in 10CFR20, Appendix B, Table 2, Column 1. This is based on 100 mrem/yr.
10CFR50, Appendix I For Calendar Quarter Gamma Dose <5 mrad (Used for calculating percent of applicable limit.)
Beta Dose <10 mrad (Used for calculating percent of applicable limit.)
For Calendar Year Gamma Dose <10 mrad Beta Dose <20 mrad B. Iodine - 131 and 133, Tritium, and Particulates >8 day half-lives:
ODCM Operational Requirements Maximum Instantaneous Release Rate is and inhalation dose (only) to a child to any organ
                <1500 mrem/yr 10CFR20 Limits Annual Average Concentrations as specified in 10CFR20, Appendix B, Table 2, Column
: 1. This is based on 50 mrem/yr.
10CFR50, Appendix I (Organ Doses)
For Calendar Quarter <7.5 mrnem (Used for calculating percent of applicable limit.)
For Calendar Year <15 mrem C. Liquids:
ODCM Operational Requirements Maximum Instantaneous Release Rate is ten times the concentrations specified in 10CFR20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases.
ODCM Operational Requirements For dissolved or entrained noble gases, the concentration shall be limited to 2.00E-04 RtCi/ml total activity.
10CFR20 Limits The annual average concentrations to be less than the concentrations specified in 10CFR20, Appendix B, Table 2, Column 2.(Used for calculating percent of applicable limit.) This is based on 50 mrem/yr.
10CFR50, Appendix I For Calendar Quarter Total Body Dose <1.5 mrem Any Organ Dose <5 mrem For Calendar Year Total Body Dose <3 mrem Any Organ Dose <10 mrem D. Average Energy (E):
None applicable at HNP. HNP determines dose and dose rate based on actual releases, not on an average energy value.
 
Appendix 1: Supplemental Information (Continued)
II. Measurements and Approximations of Total Radioactivity A. Continuous Gaseous Releases
: 1.      Fission and activation gases The total activity released is determined from the net activity of gaseous monitors times the total stack flow. The activity of each radionuclide is determined by the fraction of that radioactive gas in the isotopic analysis for that sampling period (typically weekly).
If no activity is detected for the sampling period, the mix is based on historical data.
: 2.      lodines The activity released as iodine-131 and 133 is based on isotopic analysis of the charcoal cartridge plus the particulate filter times the total vent flow for each sample period (typically weekly).
: 3.      Particulates The activity released as particulates with half-lives greater than eight days is determined by isotopic analysis of particulate filters times the total vent flow for each sample period.
The sample period is at a minimum weekly or more frequently if plant conditions require.
: 4.      Tritium The activity released as tritium is based on grab sample analysis using liquid scintillation times total stack flow. Grab sampling is typically performed weekly.
: 5.      Carbon- 14 The activity released as carbon-14 is calculated using Reg Guide 1.109 methodology and NUREG-0017 (GALE Code).
B. Batch Gaseous Releases
: 1.      Fission and activation gases The activity released is based on the volume released times the concentration of the individual nuclides obtained from an isotopic analysis of the grab sample taken prior to the release.
: 2.      Iodines The iodine activity released from Waste Gas Decay Tank (WGDT) batch releases is included in the iodine determination from the continuous releases.
: 3.      Particulates The particulate activity released from Waste Gas Decay Tank (WGDT) batch releases is included in the particulate determination from the continuous releases.
: 4.      Tritium The activity released as tritium is based on the grab sample analysis using liquid scintillation of each batch times the batch volume.
C.      Liquid Releases
: 1.      Fission and Activation Products The total activity released (excluding tritium, strontium, iron-55, alpha, and nickel-63) is comprised of the sum of the products of the individual radionuclide concentrations in each batch (identified using gamma spectroscopy) times the volume of the batch.
 
Appendix 1: Supplemental Information (Continued)
II. Measurements and Approximations of Total Radioactivity C.      Liquid Releases
: 2.      Alpha and Tritium The alpha activity released is the monthly composite alpha concentration times the volume released for the month.
The tritium activity released is the concentration of tritium in each batch release times the volume of the batch release.
The tritium activity released through the continuous pathways (turbine building drains and secondary waste) is the concentration from monthly composite samples (corrected for makeup water concentrations) times the volume released for the month. Makeup water is from the lake and has detectable tritium.
: 3.      Strontium-89, 90, Iron-55, and Nickel-63 Analyses are performed on quarterly composite samples times the volume released during the quarter to calculate the activity released.
D.      Estimated Total Errors
: 1.      Estimated total errors for gaseous effluents are based on uncertainties in counting equipment calibration, counting statistics, vent flow rates, vent sample flow rates, chemical yield factors, and sample losses for such items as charcoal cartridges.
: 2.      Estimated total errors for liquid effluents are based on uncertainties in counting equipment calibration, counting statistics, sampling, and volume determinations.
 
Appendix 1: Supplemental Information (Continued)
III. Batch Releases (2014)
A.        Liquid Batch Releases Jan - June 2014              July - Dec 2014 Number of batch releases                                          1.60 E+01                    1.80 E+01 Total time period for batch releases                        1.19 E+04 minutes            1.54 E+04 minutes Maximum time of a batch release                              8.84 E+02 minutes            1.04 E+03 minutes Average time for a batch release                            7.41 E+02 minutes            8.54 E+02 minutes Minimum Time for a batch release                            1.05 E+02 minutes            7.67 E+02 minutes Average stream flow during periods of release                  5.14 E+03 cf/s                1.03 E+03 cf/s B.        Gaseous Batch Releases Jan - June 2014              July - Dec 2014 Number of batch releases                                          9.00 E+00                    4.00 E+00 Total time period for batch releases                        9.48 E+03 minutes            1.38 E+03 minutes Maximum time of a batch release                              3.32 E+03 minutes            1.02 E+03 minutes Average time for a batch release                            1.05 E+03 minutes            3.44 E+02 minutes Minimum Time for a batch release                            5.90 E+01 minutes            3.00 E+00 minutes C.        Abnormal Releases
: a.        Liquid There were no abnormal effluent liquid releases in 2014.
: b.        Gaseous There was I unplanned release in 2014.
CR 718699 - Release from the "D" Waste Gas Decay Tank was due to a minor pressure loss from the hydrogen recombiner. The leak was stopped within 3 minutes by closing the manual drain isolation valve, as directed by plant procedures. A total of 7.23E-05 Curies of Noble Gas and
: 2. 1E-07 Curies of Tritium were released.
 
Appendix 2: Effluent and Waste Disposal Report Enclosure 1: Lower Limits of Detection (LLDs)
LLDs for Gaseous Effluents Nuclide                                            RtCi/cc Gross Alpha                                      1.20 E- 15 H-3                                              5.06 E-09 Ar-41                                            1.36 E-08 Kr-85                                            1.46 E-06 Kr-85m                                          4.76 E-09 Kr-87                                            1.89 E-08 Kr-88                                            9.16 E-09 Xe-131m                                          1.19 E-07 Xe-i133                                          1.01 E-08 Xe-133m                                          4.23 E-08 Xe-135                                          3.16 E-09 Xe-135m                                          3.99 E-09 Xe-138                                          3.61 E-07 1-131                                            2.78 E-14 1-133                                            3.65 E-13 Cr-51                                            1.00 E- 12 Mn-54                                            3.56 E-13 Co-58                                            2.47 E-13 Fe-59                                            6.08 E-13 Co-60                                            2.57 E-13 Zn-65                                            4.81 E-13 Sr-89                                            5.10 E-15 Sr-90                                            3.10 E-15 Nb-95                                            1.65 E-13 Zr-95                                            3.52 E- 13 Mo-99                                            1.47 E- 12 Cs- 134                                          1.29 E-13 Cs- 137                                          2.82 E-13 Ba- 140                                          8.07 E-13 La-140                                          4.31 E-13 Ce- 141                                          1.64 E-13 Ce- 144                                          7.90 E-13
 
Appendix 2: Effluent and Waste Disposal Report (Continued)
Enclosure 1: Lower Limits of Detection (LLDs)
: 2. LLDs for Liquid Effluents Nuclide                                            LLCi/ml Gross Alpha                                    5.56 E-08 H-3                                            1.59 E-06 Na-24                                          2.09 E-08 Cr-51                                          1.71 E-07 Mn-54                                          2.26 E-08 Fe-55                                          4.06 E-07 Co-57                                          1.19 E-08 Co-58                                          2.22 E-08 Fe-59                                          2.92 E-08 Co-60                                          1.74 E-08 Ni-63                                          1.46 E-07 Zn-65                                          3.29 E-08 Sr-89                                          3.14 E-08 Sr-90                                          2.16 E-08 Nb-95                                          1.22 E-08 Zr-95                                          2.18 E-08 Mo-99                                          9.31 E-08 Tc-99m                                          1.09 E-08 Ru- 106                                        1.04 E-07 Sb-124                                        2.49 E-08 Sb-125                                        2.55 E-08 Sb-126                                          1.09 E-08 1-131                                          1.82 E-08 1-133                                          1.08 E-08 Te- 132                                        1.19 E-08 Xe-133                                        3.88 E-08 Xe-133m                                        1.32 E-07 Xe- 135                                        1.34 E-08 Cs- 134                                        2.04 E-08 Cs-137                                          1.26 E-08 Ba-140                                        5.12 E-08 La- 140                                        4.17 E-08 Ce-141                                        2.37 E-08 Ce- 144                                        6.09 E-08
 
Appendix 2: Effluent and Waste Disposal Report (Continued)
Enclosure 2: Effluents Released Table IA: GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit            Quarter      Quarter        Est. Total 1            2            Error %
A. Fission and activation gases
: 1. Total release                                                Ci          2.29 E-02    3.26 E-02      5.27 E+01
: 2. Average release rate for period                            itCi/sec        2.95 E-03    4.14 E-03
: 3. Percent of ODCM Operational Requirement limit                  %          1.76 E-04    2.50 E-04 B. Iodines
: 1. Total iodine-131                                              Ci          0.00 E+00    0.00 E+00      3.04 E+01
: 2. Average release rate for period                            iiCi/sec      0.00 E+00    0.00 E+00
: 3. Percent of ODCM Operational Requirement limit*                %          2.45 E+00    2.60 E+00 C. Particulates
: 1. Particulates with half-lives >8 days                          Ci          0.00 E+00    0.00 E+00      3.38 E+01
: 2. Average release rate for period                            [iCi/sec      0.00 E+00    0.00 E+00
: 3. Percent of ODCM Operational Requirement limit*                %          2.45 E+00    2.60 E+00
: 4. Gross alpha radioactivity                                    Ci          0.00 E+00    0.00 E+00 D. Tritium
: 1. Total release                                                Ci          3.61 E+01    3.84 E+01      5.22 E+0  I
: 2. Average release rate for period                            gCi/sec        4.65 E+00    4.88 E+00
: 3. Percent of ODCM Operational Requirement limit*                %          2.45 E+00    2.60 E+00
* The Percent of ODCM Operational Requirement limits applies to lodines, Particulates and Tritium combined, and is calculated using ODCM methodology and parameters. The quarterly ODCM Operational Requirement limit is 7.5 millirem. The most critical organ for both quarters was the Thyroid.
 
Appendix 2: Effluent and Waste Disposal Report (Continued)
Enclosure 2: Effluents Released Table IA: GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit            Quarter    Quarter        Est. Total A. Fission and activation gases I. Total release                                                Ci          1.18 E-01    1.96 E-01      5.27 E+01
: 2. Average release rate for period                            [iCi/sec        1.49 E-02    2.46 E-02
: 3. Percent of ODCM Operational Requirement limit                  %          9.05 E-04    1.50 E-03 B. lodines
: 1. Total iodine-131                                              Ci          0.00 E+00    0.00 E+00        3.04 E+01I
: 2. Average release rate for period                            &#xfd;XCi/sec      0.00 E+00    0.00 E+00
: 3. Percent of ODCM Operational Requirement limit*                %          2.55 E+00  2.25 E+00 C. Particulates
: 1. Particulates with half-lives >8 days                          Ci          9.91 E-07  0.00 E+00        338 E+01
: 2. Average release rate for period                            [tCi/sec        1.25 E-07  0.00 E+00
: 3. Percent of ODCM Operational Requirement limit*                %          2.55 E+00  2.25 E+00
: 4. Gross alpha radioactivity                                    Ci          0.00 E+00  0.00 E+00 D. Tritium I. Total release                                                Ci          3.76 E+01  3.32 E+0l1      5.22 E+o  i
: 2. Average release rate for period                            [Ci/sec        4.73 E+00  4.18 E+00
: 3. Percent of ODCM Operational Requirement limit*                %          2.55 E+00  2.25 E+00
* The Percent of ODCM Operational Requirement limit applies to Iodines, Particulates and Tritium combined, and is calculated using ODCM methodology and parameters. The quarterly ODCM Operational Requirement limit is 7.5 millirem. The most critical organ for both quarters was the lung.
 
Appendix 2: Effluent and Waste Disposal Report (Continued)
Enclosure 2: Effluents Released Table IB: GASEOUS EFFLUENTS - ELEVATED RELEASES All releases at Harris Nuclear Power Plant are considered ground releases.
 
Appendix 2: Effluent and Waste Disposal Report (Continued)
Enclosure 2: Effluents Released Table IC: GASEOUS EFFLUENTS h
                                                      - GROUND LEVEL RELEASES II          Continuous Mode                  Batch Mode 11 Nuclides Released                Unit    J    Quarter 1          Quarter 2  Quarter I            Quarter 2 I. Fission Gases Xenon-131 m                      Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Xenon-133                        Ci          2.29 E-02          3.19 E-02  0.00 E+00          6.42 E-04 Xenon-133m                        Ci        0.00 E+00            0.00 E+00  0.00 E+00          7.09 E-06 Xenon- 135                        Ci        0.00 E+00            0.00 E+00  0.00 E+00            1.16 E-05 Xenon-135m                        Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Xenon-138                        Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Argon-41                          Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Krypton-85                        Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Krypton-85m                      Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Krypton-87                        Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Krypton-88                        Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Total for period                  Ci          2.29 E-02          3.19 E-02  0.00 E+00          6.61 E-04
: 2. Iodines Iodine-131                        Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Iodine-133                        Ci          0.00 E+00          0.00 E+00  0.00 E+00          0.00 E+00 Iodine-135                        Ci          0.00 E+00          0.00 E+00  0.00 E+00          0.00 E+00 Total for period                  Ci          0.00 E+00          0.00 E+00  0.00 E+00          0.00 E+00
: 3. Particulates Chromnium-51                      Ci          0.00 E+00          0.00 E+00  0.00 E+00          0.00 E+00 Manganese-54                      Ci          0.00 E+00          0.00 E+00  0.00 E+00          0.00 E+00 Cobalt-58                        Ci          0.00 E+00          0.00 E+00  0.00 E+00          0.00 E+00 Iron-59                          Ci          0.00 E+00          0.00 E+00  0.00 E+00          0.00 E+00 Cobalt-60                        Ci          0.00 E+00          0.00 E+00  0.00 E+00          0.00 E+00 Zinc-65                          Ci          0.00 E+00          0.00 E+00  0.00 E+00          0.00 E+00 Strontium-89                      Ci          0.00 E+00          0.00 E+00  0.00 E+00          0.00 E+00 Strontium-90                      Ci          0.00 E+00          0.00 E+00  0.00 E+00          0.00 E+00 Niobium-95                        Ci          0.00 E+00          0.00 E+00  0.00 E+00          0.00 E+00 Zirconium-95                      Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Molybdenum-99                    Ci          0.00 E+00          0.00 E+00  0.00 E+00          0.00 E+00 Cesium-134                        Ci          0.00 E+00          0.00 E+00  0.00 E+00          0.00 E+00 Cesium-137                        Ci          0.00 E+00          0.00 E+00  0.00 E+00          0.00 E+00 Barium-140                        Ci          0.00 E+00          0.00 E+00  0.00 E+00          0.00 E+00 Lanthanum-140                    Ci          0.00 E+00          0.00 E+00  0.00 E+00          0.00 E+00 Cerium-141                        Ci          0.00 E+00          0.00 E+00  0.00 E+00          0.00 E+00 Cerium-144                        Ci          0.00 E+00          0.00 E+00  0.00 E+00          0.00 E+00
[Total for period                  Ci          0.00 E+00          0.00 E+00  0.00 E+00          0.00 E+00
 
Appendix 2: Effluent and Waste Disposal Report (Continued)
Enclosure 2: Effluents Released Table IC: GASEOUS EFFLUENTS - GROUND LEVEL RELEASES II          Continuous Mode                  Batch Mode          ii NuclidesReleased                Unit          Quarter 3          Quarter 4  Quarter 3            Quarter 4 I. Fission Gases Xenon-131m                      Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Xenon-133                        Ci          1.14 E-01            1.96 E-01 3.70 E-03          4.97 E-05 Xenon-133mn                      Ci        0.00 E+00            0.00 E+00  0.00 E+00          9.80 E-07 Xenon-135                        Ci        0.00 E+00            0.00 E+00  0.00 E+00          1.78 E-05 Xenon-135m                      Ci        0.00 E+00            0.00 E+00  0.00 E+00          3.96 E-08 Xenon-138                        Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Argon-41                        Ci        0.00 E+00            0.00 E+00  0.00 E+00          1.48 E-06 Krypton-85                      Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Krypton-85m                      Ci        0.00 E+00            0.00 E+00  0.00 E+00          7.60 E-07 Krypton-87                      Ci        0.00 E+00            0.00 E+00  0.00 E+00          3.27 E-07 Krypton-88                      Ci        0.00 E+00            0.00 E+00  0.00 E+00          1.04 E-06 Total for penod                  Ci          1.14 E-01            1.96 E-01 3.70 E-03          7.21 E-05
: 2. lodines lodine-131                      Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Iodine-133                      Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Iodine-135                      Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Total for period                Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00
: 3. Particulates Chromium-51                      Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Manganese-54                    Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Cobalt-57                        Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Cobalt-58                        Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Iron-59                          Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Cobalt-60                        Ci          9.91 E-07          0.00 E+00  0.00 E+00          0.00 E+00 Zinc-65                          Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Strontium-89                    Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Strontium-90                    Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Niobiumn-95                      Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Zirconium-95                    Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Molybdenum-99                    Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Sn- 113                          Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Cesium-134                      Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Cesium-137                      Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Barium-140                      Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Lanthanum-140                    Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Cerium-141                      Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Cerium-144                      Ci        0.00 E+00            0.00 E+00  0.00 E+00          0.00 E+00 Total for period                Ci          9.91 E-07          0.00 E+00  0.00 E+00          0.00 E+00
 
Appendix 2: Effluent and Waste Disposal Report (Continued)
Enclosure 2: Effluents Released Table 2A: LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit I1 tQuarter
________12 Quarter  Est. Total Error %
A. Fission and Activation products Total release (not including tritium, I  gases, alpha)                              Ci            2.77 E-03  2.53 E-03 3.28 E+01 2    Average diluted concentration during period                                      RtCi/ml      5.57 E-10  5.16 E-10 Percent of applicable limit                  %            4.58 E-03  2.84 E-03 B. Tritium 1  Total release                              Ci              1.14 E+01 4.19 E+01 2    Average diluted concentration during period                                      [tCi/ml      2.29 E-06  8.53 E-06 Percent of applicable limit                  %            2.29 E-01  8.53 E-01 C. Dissolved and entrained gases 1  Total release                              Ci            0.00 E+00  0.00 E+00 3.28E+01 2    Average diluted concentration during period                                      [tCi/ml      0.00 E+00  0.00 E+00 Percent of applicable limit                  %            0.00 E+00  0.00 E+00 D. Gross alpha radioactivity 1  Total release                              Ci            0.00 E+00  0.00 E+00 3.28 E+01 E. Volume of waste released 1    Continuous Releases                        liters        7.54 E+06  1.07 E+07 2.00 E+01 2    Batch Releases                              liters        5.28 E+05  6.13 E+05 2.00 E+01 F. Volume of dilution water I  Continuous Releases                              liters        4.98 E+09  4.91 E+09 2.00 E+01 2  Batch Releases                                    liters        4.98 E+09  4.91 E+09 2.00 E+01
 
Appendix 2: Effluent and Waste Disposal Report (Continued)
Enclosure 2: Effluents Released Table 2A: LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES
[Unit          Quarter        Quarter    Est. Total 1            1 3___[______    4    J  Error%%
A. Fission and Activation products 1    Total release (not including tritium, gases,        Ci    2.59 E-03      1.38 E-03  3.28 E+01 alpha)                                                                                      II 2    Avera-e diluted concentration during            &#xfd;tCi/ml    5.49 E-10      2.87 E-10 periodZ 3    Percent of applicable limit                        %      4.77 E-03      1.53 E-03 B. Tritium 1    Total release                                      Ci    1.25 E+01      2.33 E+02  5.43 E+01 2    Average diluted concentration during            tiCi/ml    2.65 E-06      4.85 E-05 perio[
3    Percent of applicable limit                        %      2.65 E-01      4.85 E+00 C. Dissolved and entrained gases 1    Total release                                      Ci    0.00 E+00      0.00 E+00  3.28 E+01 2    Average diluted concentration during            [Ci/ml    0.00 E+00      0.00 E+00 period 3    Percent of applicable limit                        %      0.00 E+00      0.00 E+00 D. Gross alpha radioactivity 1    Total release                                      Ci    0.00 E+00      0.00 E+00  3.28 E+01 E. Volume of waste released 1    Continuous Releases                              liters  9.97 E+06      7.78 E+06  2.00 E+01 2    Batch Releases                                    liters  6.16 E+05      7.85 E+05  2.00 E+01 F. Volume of dilution water 1    CBntinuous Releases                                liters  4.73 E+09      4.80 E+09  2.00 E+01 2    BCtch Releases                                      liters  4.73 E+09      4.80 E+09  2.00 E+01
 
Appendix 2: Effluent and Waste Disposal Report (Continued)
Enclosure 2: Effluents Released Table 2B: LIQUID EFFLUENTS Continuous Mode                  Batch Mode Nuclides Released              Unit        Quarter 1      Quarter 2  f  Quarter 1        Quarter 2 Sodium-24                        Ci          0.00 E+00      0.00 E+00    0.00 E+00        0.00 E+00 Chromium-51                      Ci          0.00 E+00      0.00 E+00    5.95 E-05        0.00 E+00 Manganese-54                    Ci          0.00 E+00      0.00 E+00    1.69 E-05      5.89 E-05 Iron-55                          Ci          0.00 E+00      0.00 E+00    0.00 E+00        0.00 E+00 Cobalt-57                        Ci          0.00 E+00      0.00 E+00    0.00 E+00        0.00 E+00 Cobalt-58                        Ci          0.00 E+00      0.00 E+00    1.50 E-03      3.83 E-04 Iron-59                          Ci          0.00 E+00      0.00 E+00    0.00 E+00        0.00 E+00 Cobalt-60                        Ci          0.00 E+00      0.00 E+00    4.29 E-04        2.89 E-04 Nickel-63                        Ci          0.00 E+00      0.00 E+00    7.13 E-04        1.64 E-03 Strontium-89                    Ci          0.00 E+00      0.00 E+00    0.00 E+00        0.00 E+00 Strontium-90                    Ci          0.00 E+00      0.00 E+00    0.00 E+00        0.00 E+00 Zirconium-95                    Ci          0.00 E+00      0.00 E+00    1.48 E-05        1.39 E-05 Zirconium-97                    Ci          0.00 E+00      0.00 E+00    0.00 E+00        0.00 E+00 Niobium-95                      Ci          0.00 E+00      0.00 E+00    4.40 E-05        5.25 E-05 Niobium-97                      Ci          0.00 E+00      0.00 E+00    0.00 E+00        0.00 E+00 Technicium-99m                  Ci          0.00 E+00      0.00 E+00    0.00 E+00        0.00 E+00 Ruthenium-106                    Ci          0.00 E+00      0.00 E+00    0.00 E+00        0.00 E+00 Antimony-122                    Ci          0.00 E+00      0.00 E+00    0.00 E+00        0.00 E+00 Antimony-124                    Ci          0.00 E+00      0.00 E+00    0.00 E+00        0.00 E+00 Antimony-125                    Ci          0.00 E+00      0.00 E+00    0.00 E+00        9.09 E-05 Antimony-126                    Ci          0.00 E+00      0.00 E+00    0.00 E+00        0.00 E+00 Tellurium-132                    Ci          0.00 E+00      0.00 E+00    0.00 E+00        0.00 E+00 Iodine-131                      Ci          0.00 E+00      0.00 E+00    0.00 E+00        0.00 E+00 Iodine-132                      Ci          0.00 E+00      0.00 E+00    0.00 E+00        0.00 E+00 Iodine-133                      Ci          0.00 E+00      0.00 E+00    0.00 E+00        0.00 E+00 Cesium-134                      Ci          0.00 E+00      0.00 E+00    0.00 E+00        0.00 E+00 Cesium-137                      Ci          0.00 E+00      0.00 E+00    0.00 E+00        0.00 E+00 Barium-140                      Ci          0.00 E+00      0.00 E+00    0.00 E+00        0.00 E+00 Lanthanum- 140                  Ci          0.00 E+00      0.00 E+00    0.00 E+00        0.00 E+00 Cerium-141                      Ci          0.00 E+00      0.00 E+00    0.00 E+00        0.00 E+00 Cerium-144                      Ci          0.00 E+00      0.00 E+00    0.00 E+00        0.00 E+00 TOTAL                            Ci          0.00 E+00      0.00 E+00    2.77 E-03    ]  2.53 E-03 Xenon-133                        Ci          0.00 E+00      0.00 E+00    0.00 E+00        0.00 E+00 Xenon-133m                      Ci          0.00 E+00      0.00 E+00    0.00 E+00        0.00 E+00 Xenon-135                        Ci          0.00 E+00      0.00 E+00    0.00 E+00        0.00 E+00 TOTAL                            Ci          0.00 E+00      0.00 E+00    0.00 E+00        0.00 E+00 Tritium                          Ci          3.26 E-02        1.01 E-01  1.14 E+01        4.19 E+01
 
Appendix 2: Effluent and Waste Disposal Report (Continued)
Enclosure 2: Effluents Released Table 2B: LIQUID EFFLUENTS Continuous Mode              Batch Mode Nuclides Released              Unit          Quarter 3        Quarter 4  Quarter 3      Quarter 4 Sodium-24                        Ci          0.00 E+00        0.00 E+00  0.00 E+00      0.00 E+00 Chromium-51                      Ci          0.00 E+00        0.00 E+00  0.00 E+00      0.00 E+00 Manganese-54                    Ci          0.00 E+00        0.00 E+00  5.71 E-05      2.68 E-05 Iron-55                          Ci          0.00 E+00        0.00 E+00  9.12 E-04      8.32 E-04 Cobalt-57                        Ci          0.00 E+00        0.00 E+00  0.00 E+00      0.00 E+00 Cobalt-58                        Ci          0.00 E+00        0.00 E+00  3.05 E-04      2.78 E-05 Iron-59                          Ci          0.00 E+00        0.00 E+00  0.00 E+00      0.00 E+00 Cobalt-60                        Ci          0.00 E+00        0.00 E+00  5.61 E-04        1.78 E-04 Nickel-63                        Ci          0.00 E+00        0.00 E+00  6.47 E-04      2.90 E-04 Strontium- 8 9                  Ci          0.00 E+00        0.00 E+00  0.00 E+00      0.00 E+00 Strontium-90                    Ci          0.00 E+00        0.00 E+00  0.00 E+00      0.00 E+00 Zirconium-95                    Ci          0.00 E+00        0.00 E+00  0.00 E+00      0.00 E+00 Zirconium-97                    Ci          0.00 E+00        0.00 E+00  0.00 E+00      0.00 E+00 Niobium-95m                      Ci          0.00 E+00        0.00 E+00  0.00 E+00      0.00 E+00 Niobium-95                      Ci          0.00 E+00        0.00 E+00  4.36 E-05        1.92 E-05 Niobium-97                      Ci          0.00 E+00        0.00 E+00  0.00 E+00      0.00 E+00 Ruthenium-103                    Ci          0.00 E+00        0.00 E+00  0.00 E+00      0.00 E+00 Tin-1 13                        Ci          0.00 E+00        0.00 E+00  0.00 E+00        2.15 E-06 Ruthenium-106                    Ci          0.00 E+00        0.00 E+00  0.00 E+00      0.00 E+00 Antimony-122                    Ci          0.00 E+00        0.00 E+00  3.87 E-06      0.00 E+00 Antimony-124                    Ci          0.00 E+00        0.00 E+00  1.26 E-05      0.00 E+00 Antimony-125                    Ci          0.00 E+00        0.00 E+00  5.01 E-05      0.00 E+00 Antimony-126                    Ci          0.00 E+00        0.00 E+00  0.00 E+00      0.00 E+00 Iodine-131                      Ci          0.00 E+00        0.00 E+00  0.00 E+00      0.00 E+00 Iodine-132                      Ci          0.00 E+00        0.00 E+00  0.00 E+00      0.00 E+00 Iodine-133                      Ci          0.00 E+00        0.00 E+00  0.00 E+00      0.00 E+00 Cesium-134                      Ci          0.00 E+00        0.00 E+00  0.00 E+00      0.00 E+00 Cesium-137                      Ci          0.00 E+00        0.00 E+00  0.00 E+00      0.00 E+00 Barium-140                      Ci          0.00 E+00        0.00 E+00  0.00 E+00      0.00 E+00 Lanthanum-140                    Ci          0.00 E+00        0.00 E+00  0.00 E+00      0.00 E+00 Cerium- 141                      Ci          0.00 E+00        0.00 E+00  0.00 E+00      0.00 E+00 TOTAL                            Ci          0.00 E+00        0.00 E+00  2.59 E-03      1.38 E-03 Xenon-133                        Ci          0.00 E+00        0.00 E+00  0.00 E+00      0.00 E+00 Xenon-133m                      Ci          0.00 E+00        0.00 E+00  0.00 E+00      0.00 E+00 Xenon- 135                      Ci          0.00 E+00        0.00 E+00  0.00 E+00      0.00 E+00 TOTAL                            Ci          0.00 E+00        0.00 E+00  0.00 E+00      0.00 E+00 Tritium                          Ci            1.63 E-01        1.15 E-01  1.25 E+01      2.33 E+02
                                                -21  -
 
Appendix 2: Effluent and Waste Disposal Report (Continued)
Enclosure 3: Solid Waste Disposal Table 3: SOLID WASTE AND IRRADIATED FUEL SHIPMENTS
: 1.        Solid Waste Shipped for Burial or Disposal (WASTE CLASS A)
NOTE: Values reported in Table 3 section 1.A.a, b, & 1.B.a, b, refer to radioactive solid waste materials shipped in 2014 to a vendor for processing and subsequent burial.
A.        Type of Waste
: a.        Spent resins.
Note: Waste shipped in 2014 for processing and subsequent burial Number of Shipments                  5 Activity Shipped                    7.05 E+01 Curies Estimated Total Error                96%    3 Quantity Shipped                    12.38 m Solidification Agent                N/A Container Type                      NRC-Approved Package Shipment Form                        Dewatered, Compacted
: b.        Dry Active Waste (DAW), mechanical filters, contaminated equipment, etc.
Note: Waste shipped in 2014 for processing and subsequent burial.
Number of Shipments                  5 Activity Shipped                    1.08 E+01 Curies Estimated Total Error                96%          3 Quantity Shipped                    1.96 E+02 m Solidification Agent                N/A Container Type                      NRC-Approved Package Shipment Form                        Dewatered, Compacted
: c.        Irradiated components, control rods, etc.
No waste of this type was shipped during this Report Period.
: d.        Other (Radwaste Oil)
No waste of this type was shipped during this Report Period
                                                    -  22  -
 
Appendix 2: Effluent and Waste Disposal Report (Continued)
Enclosure 3: Solid Waste Disposal Table 3: SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Solid Waste Shipped for Burial or Disposal (WASTE CLASS A)
B.      Estimate of Major Nuclide Composition (by type of Waste)
: a.        Spent Radwaste Bead Resin Note: Waste shipped in 2014 for processing and subsequent burial.
Class A Resin Totals Nuclide    Total Activity (0)      % Abundance Be-7            1.28E+01              18.16%
C-14            1.53E-02              0.02%
Ce-144          6.42E-02              0.09%
Co-57            6.11E-02              0.09%
Co-58            2.20E+00              3.12%
Co-60            6.97E+00              9.88%
Cr-51          2.96E-02              0.04%
Cs-137          1.37E+00              1.95%
Fe-55          2.80E+01              39.69%
Fe-59          7.17E-02              0.10%
H-3            3.63E-02              0.05%
1-129          5.31E-04              0.00%
Mn-54            1.19E+01              16.91%
Nb-95            7.10E-02              0.10%
Ni-63          6.68E+00              9.47%
Sn-113          9.06E-02              0.13%
Sr-89          3.69E-02              0.05%
Sr-90          1.13E-02              0.02%
Tc-99            2.80E-03              0.00%
Zr-95          8.08E-02              0.11%
Total            7.05E+01              100.00%
                                    - 23  -
 
Appendix 2: Effluent and Waste Disposal Report (Continued)
Enclosure 3: Solid Waste Disposal Solid Waste Shipped for Burial or Disposal (WASTE CLASS A)
B.      Estimate of Major Nuclide Composition (by type of Waste)
: b.      Dry Active Waste (DAW), mechanical filters, contaminated equipment, etc.
Note: Waste shipped in 2014 for processing and subsequent burial.
Class A DAW Totals Total Activity Nuclide                  (0i)            % Abundance Am-241                4.60E-06                0.00%
C-14                4.96E-01                4.59%
Ce-144                1.05E-02                0.10%
Cm-243                2.45E-06                0.00%
Co-57                3.24E-03                0.03%
Co-58                1.13E-02                0.10%
Co-60              5.18E+00                47.87%
Cr-51                1.42E-02                0.13%
Cs-134                9.07E-04                0.01%
Cs-137                1.20E-01                1.11%
Fe-55                6.33E-01                5.85%
Fe-59                3.39E-08                0.00%
H-3                2.77E+00                25.64%
1-129                9.36E-02                0.87%
Mn-54                2.29E-01                2.12%
Nb-95                5.59E-02                0.52%
Ni-63                2.31E-01                2.14%
Pu-238                2.86E-06                0.00%
Pu-239                1.74E-06                0.00%
Pu-241                1.01E-04                0.00%
Sb-125                5.09E-01                4.71%
Sn-113                2.16E-03                0.02%
Tc-99                3.98E-01                3.68%
Zr-95                5.45E-02                0.50%
Total                1.08E+01              100.00%
                                    -  24 -
 
Appendix 2: Effluent and Waste Disposal Report (Continued)
Enclosure 3: Solid Waste Disposal Solid Waste Shipped for Burial or Disposal (WASTE CLASS A)
C.      Solid Waste Disposal Number of Shipments                  10 Mode of Transportation              Truck Destination                          Energy Solutions & Studsvik Note: Waste shipped in 2014 for processing and subsequent burial
                                  -  25 -
 
Appendix 2: Effluent and Waste Disposal Report (Continued)
Enclosure 3: Solid Waste Disposal Table 3: SOLID WASTE AND IRRADIATED FUEL SHIPMENTS
: 2. Solid Waste Shipped for Burial or Disposal (WASTE CLASS B)
A.      Type of Waste
: a.      Spent resins.
No waste of this type was shipped during this Report Period.
: b.      Dry Active Waste (DAW), mechanical filters, contaminated equipment, etc.
No waste of this type was shipped during this Report Period.
: c.      Irradiated components, control cods, etc.
No waste of this type was shipped during this Report Period.
: d.      Other (Describe)
No waste of this type was shipped during this Report Period.
B.      Estimate of Major Nuclide Composition (by type of Waste)
N/A C.      Solid Waste Disposal N/A
                                      - 26  -
 
Appendix 2: Effluent and Waste Disposal Report (Continued)
Enclosure 3: Solid Waste Disposal Table 3: SOLID WASTE AND IRRADIATED FUEL SHIPMENTS
: 3. Solid Waste Shipped for Burial or Disposal (WASTE CLASS C)
A.          Type of Waste
: a.      Spent Resins, Filter Sludges, Evaporator Bottoms, etc.
No waste of this type was shipped during this Report Period.
: b.      Dry Active Waste (DAW), Mechanical Filters, Contaminated Equipment, etc.
No waste of this type was shipped during this Report Period.
: c.      Irradiated Components, Control Rods, etc.
No waste of this type was shipped during this Report Period.
: d.      Other (Describe)
No waste of this type was shipped during this Report Period.
B.          Estimate of Major Nuclide Composition (by type of Waste)
N/A C.          Solid Waste Disposal N/A
                                  - 27  -
 
Appendix 3: Changes to the Offsite Dose Calculation Manual (ODCM)
Technical Specifications 6.14.c ODCM Revision 25 was issued November 17, 2014. There are two types of changes to the ODCM; 1) programmatic changes and 2) administrative corrections, changes, and clarifications.
Programmatic Changes were as follows:
    " Added Location 97 for Food Crop surveillance to the Radiological Environmental Monitoring Program (REMP).
* Revised the Harris Lake surface area based upon satellite map updates
* Updated figures to reflect system changes from EC 96109 "Settling Basin Discharge Piping and Behm Upgrade"
    " Revised equations to match OpenEMS calculating methodology for dose projection, dose rate to an individual child, and stack set points.
Administrative Changes were as follows:
    " Added complete list of dose factors that are in OpenEMS to the ODCM
* Corrected typographical errors that were identified in the OpenEMS CRTN
    " Inserted new EnRad REMP figures and deleted redundant figures A listing of the ODCM revision is on the next page.
                                                -  28 -
 
Appendix 3: Changes to the Offsite Dose Calculation Manual (ODCM)
Technical Specifications 6.14.c (Continued)
ODCM REV. 25 CHANGE
 
==SUMMARY==
 
Section          Page                                            Description Table of Contents            i        Changed to "ODCM REV. 25 CHANGE
 
==SUMMARY==
",
List of Table            ii        Table 3.1-2 Dose Factors and Constant table is identified as "Deleted" Changed page numbers for tables 3.3-1 through 3.3-19 to reflect the additional pages of dose factors Revised Titles for Tables 4.2 (Radiological Environmental Monitoring Program Sampling Locations) and 4.3 (Radiological Environmental Monitoring Program Sampling Locations - TLD Sites)
List of Figure          iv        Added Figures 4.1-2 Environmental Radiological Sampling Points (1 mile Radius) and Figure 4.1-3 Environmental Radiological Sampling Points (10 mile Radius)
ODCM REV 25              ix        Changed to reflect Rev. 25 revisions.
CHANGE
 
==SUMMARY==
 
2.0 Liquid            2-1        Added statement "The SHNPP ODCM uses the Canberra, Inc, Effluent Effluents                        Management System (OpenEMS) software for automating the necessary calculations and recordkeeping" in order to define the program used to calculate the release permits and Annual Reporting data.
2.2.3 Projection of      2-17        Changed dose to be used as an input for the dose projection equations as the Doses                          sum of all open and close permits for the current quarter up to the end of the current release. Previously the ODCM stated it only included the open release points. The use of both open and close permits yields a more realistic and conservative dose projection.
Revised Note - deleted "Special Reports" and on the "Approval/Results screen". These functions are no longer available.
2.3 Dose from          2-21        Revised the Harris Lake surface area from 4120.72 acres to 4169.61 acres.
Return/Reuse                      Murray and Truttle recalculated the area of the lake and new map created.
Table 2.2-1      2-28 to 2-30    Corrected the ODCM typographical errors that were identified in the OpenEMS CRTN (Agi 10m - all factors, Ba142 GiLLi 0.00 to 2.59E-39).
Updated Table 2.2-1 Liquid Dose factors Ai, (adult) to include the additional isotopes and dose factors to match OpenEMS. These factors were derived using equation 2.2-3.
Figure 2.1-4          2-34        EC 96109 Removed the Waste Neutralization/Settling Basin bypass line and capped the end of the pipe Figure 2.3-1          2-35        Updated Map of Harris Lake to reflect changes in calculated areas for each segment on page 2-21 3.3.1 Default          3-3        Deleted definition of L& 1.1Mi because table 3.1-2 is derived from Table 3.2-3 Continuous Release                    and includes rounding. All of the required information can be obtained using Monitor Setpoints                    Table 3.2-3.
3.1.2 Monitor          3-6        Deleted summation term for all vent stacks in equations 3.2-1 a and 3.2-1 b.
Setpoints                        Each monitor setpoint is determined individually and allocation fractions are being used to ensure that the total release rates do not exceed ODCM limits.
                                                    -  29  -
 
Appendix 3: Changes to the Offsite Dose Calculation Manual (ODCM)
Technical Specifications 6.14.c (Continued) 3.1.2 Monitor          3-8        Deleted summation term for all vent stacks in equations 3.2-2a and 3.2-2b.
Setpoints                        Each monitor setpoint is determined individually and allocation fractions are being used to ensure that the total release rates do not exceed ODCM limits.
Deleted definition of Li+l. IMi because table 3.1-2 is derived from Table 3.2-3 and includes rounding. All of the required information can be obtained using Table 3.2-3.
Table 3.1-2 Dose        3-13        Deleted Table 3.1-2 Li+l. 1Mi because this information is derived from Table Factors and                      3.2-3 and includes rounding. All of the required information can be obtained Constants                        using Table 3.2-3.
3.2.1 Noble Gases        3-16        Deleted the definition of factor Li+l.lMi because table 3.1-2 is derived from Table 3.2-3 and includes rounding.
3.2.2 Radioiodines        3-17        Deleted "The values of Pi reflect, for each radionuclide, the maximum Pi value and Particulates                    for any organ." Table 3.2-4 has been revised to include all Pi values for a nuclide. This change will more accurately reflect the dose rate to an individual and will align the ODCM with current practices at HNP.
Table 3.2-3 Dose        3-19        Updated Table 3.2-3 to include the additional isotopes and dose factors to Factors for Noble                    match OpenEMS Ki , Li, Mi, N, Gas Table 3.2-4 Pi        3-20        Table 3.2-4 revised to list all of the Pi values per organ for each nuclide.
values for Child                    Previously the ODCM only listed the maximum Pi value for a nuclide. This change will more accurately reflect the dose rate to an individual and will align the ODCM with current practices at HNP.
3.3.1.3 Projection      3-27        Changed dose to be used as an input for the dose projection equations as the of Doses            3-31        sum of all open and close permits for the current quarter up to the end of the 3.3.2.2 Projection                  current release. Previously the ODCM stated it only included the open release of Doses                        points. The use of both open and close permits yields a more realistic and conservative dose projection.
Revised Note - deleted "Special Reports" and on the "Approval/Results screen". These functions are no longer available.
Tables 3.3-1 to 3.3-  3-37 to 3-68    Revised Non Noble Gas Dose dose factors (R factors) to incorporate 13                          additional isotopes and dose factors to match OpenEMS.
Tables 3.3-15 to                    Note: Goat Milk Dose Factors (Table 3.3-12 to 3.3-15) are not included in 3.3-19                        OpenEMS because the pathway does not currently exist. The Goat Milk dose factors are being maintained in the ODCM in the event that the Goat Milk pathway is reintroduced. At that time OpenEMS could be revised to include these terms. (formatting of Table 3.3-14 was revised to match the other tables but the content was not changed)
Table 3.3-11          3-54        Corrected the ODCM typographical errors that were identified in the CRTN (Infant Cow Milk Y91 Total Body from 1.16E8 to 1.17E3)
Table 4.1 Ingestion      4-13        Added location 97 at Granite Springs Farm. This control location has a greater
  - Food Products                    diversity of food crops and provides an additional source of crops for the Food Products surveillance Figures 4.1-2 to    4-16 to 4-20    Revised Environmental Radiological Sampling Points figures. New figures 4.1-6                        were created showing each sample point in the appropriate sector and distance Table 4.2 to 4.3                    from the plant. Figures 4.1-4 and 4.1-5 were deleted because they were redundant. Replaced Figure 4.1-6 which was the legends for figures 4.1-2 to 4.1-5 with new tables 4.2 and 4.3. These tables identify the environmental monitoring location and the type of sample at each location. These tables are used in the Annual Environmental Operating Report 30  -
 
Appendix 3: Changes to the Offsite Dose Calculation Manual (ODCM)
Technical Specifications 6.14.c (Continued) 5.0 Interlaboratory      5-1      Deleted references to E&EC performing sample analysis. ODCM required Comparison                    radiochemical analysis are performed by a qualified laboratory (DRR 596293)
Studies Appendix B -          B-i      Deleted "The values for Pi presents the highest dose to any organ including the Bases            B-2      whole body resulting from inhalation of radionuclide "i" by a child." Table 3.2-4 revised to list all of the Pi values per organ for each nuclide. Previously the ODCM only listed the maximum Pi value for a nuclide. This change will more accurately reflect the dose rate to an individual and will align the ODCM with current practices at HNP.
                                                -  31    -
 
Appendix 4: Changes to the Environmental Monitoring Program Enclosure 1: Environmental Monitoring Program Offsite Dose Calculation Manual Operational Requirement 3.12.1 .c ODCM Revision 25 was issued November 17, 2014. A new control Food Crop location (97 - Granite Springs Farm) was added to the REMP. This control location has a greater diversity of food crops and provides an additional source of crops for the Food Products surveillance. Food Crops will continue to be sampled at location 5 for historical integrity.
Enclosure 2: Land Use Census Offsite Dose Calculation Manual Operational Requirements 3.12.2.a and 3.12.2.b A Land Use Census was conducted on August 26 and 27, 2014. The census was conducted by driving roads within the five mile radius of HNP and by visual inspections and/or verbal interview to determine the required data in each of the sixteen meteorological sectors. Global Positioning System (GPS) equipment was utilized to determine the distance and sector from the HNP centerline (350-38'-00" N by 780-57'-22" W) to the nearest resident, garden, meat animal, and milk animal in each of the sixteen meteorological sectors.
The changes observed in the 2014 Land Use Census from the previous year survey were as follows:
* The residence in the NNE sector (1.9 miles) was replaced with a new residence at 1.81 miles
* The residence in the S sector (5.3 miles) was not included in the 2014 survey data since the residence is outside the 5 mile radius.
* A new garden was found this year in the NNE and SE sectors. No gardens were found this year in the NE, ENE, E, S, and SSW sectors.
* There is a new meat animal in the NNE sector (1.81 miles) and the meat animal in the ESE sector (4.6 miles) was replaced by meat animal at 4.72 miles.
* Milk goats were located in the ESE sector, but according to the owner, the milk is not for consumption (milk, cheese, etc) but for soap production. No consumed milk animals were located within 5 miles of the site.
                                                - 32    -
 
Appendix 5: Additional Operational Requirements Enclosure 1: Inoperability of Liquid Effluent Monitors ODCM Operational Requirement 3.3.3. 1O.b Radioactivity Liquid Effluent Monitors Providing Alarms and Automatic Termination of Release were reviewed for operability during 2014 by the Condition Reporting Process pursuant to ODCM Operational Requirement 3.3.3.10.b. None were inoperable for greater than 30 continuous days during the reporting period.
Enclosure 2: Inoperability of Gaseous Effluent Monitors ODCM Operational Requirement 3.3.3.1 L.b Radioactivity Gaseous Effluent Monitors Providing Alarms and Automatic Termination of Release were reviewed for operability during 2014 by the Condition Reporting Process pursuant to ODCM Operational Requirement 3.3.3.1 Lb. None were inoperable for greater than 30 continuous days during the reporting period.
Enclosure 3: Unprotected Outdoor Tanks Exceeding Limits Technical Specification 3.11.1.4 No unprotected outdoor tank exceeded the Technical Specification limit of 10 Curies, excluding tritium or dissolved noble gases during this report period.
Enclosure 4: Gas Storage Tanks Exceeding Limits PLP- 114, Attachment 5, Operational Requirement 1.1 No gas storage tank exceeded the PLP-1 14, Attachment 5 Operational Requirement limit of 1.05 E+05 Curies during this report period.
                                                    -  33  -
 
Appendix 5: Additional Operational Requirements (continue)
Enclosure 5: Groundwater Samples taken in support of Groundwater Protection Initiative NEI 07-07 Industry Groundwater Protection Initiative -
Final Guidance Document, Objective 2.4 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. Per NEI 07-07 the results of the Groundwater Monitoring Wells were included in the REMP and are not listed in this report.
Appendix 6: Major Modifications to Radwaste System ODCM Operational Requirement F.3 No major modifications were made to the Radwaste System during this report period.
Appendix 7: Meteorological Data ODCM Operational Requirement F.2 As allowed by the Footnote to ODCM Operational Requirement F.2, the annual summary of meteorological data will be retained electronically on file. This data will be provided to the NRC upon request.
                                                        -  34  -
 
Appendix 8: Assessment of Radiation Doses ODCM Operational Requirement F.2 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 this report, along with an annual total of each effluent pathway is in pursuant to the Operational Requirement F.2. Since 10CFR50, Appendix I is more restrictive than 40CRF 190 for a single unit site, the assessment for 40CFR 190 is performed when any of the 10CFR50, Appendix I limits are exceeded by a factor of 2 using LADTAP, XOQDOQ, and GASPAR II (NRC computer codes). The ODCM software is more conservative and is used for annual effluent dose assessment for demonstration of compliance with 10CFR50, Appendix I and 40CFR190.
Gaseous The dose from the gaseous pathway is based on the highest calculated five-year average (2003 through 2007) relative concentration (X/Q) and deposition factor ((D/Q) for particulates) at the most restrictive location at the site boundary. The dose from the carbon-14 is based on the most restrictive garden.
3 rd              th              Annual lST                2 nd                                4 Quarter            Quarter            Quarter        Quarter                Total Noble Gas                    5.91 E-06          8.40 E-06            3.04 E-05      5.05 E-05            9.52 E-05 Gamma Dose (mrad) 10CFR50 Appendix I          5.00 E+00          5.00 E+00            5.00 E+00      5.00 E+00            1.00 E+01 Limit (mrad)
Noble Gas                    1.76 E-05          2.50 E-05            9.05 E-05      1.50 E-04            2.83 E-04 Beta Dose (mrad)
IOCFR50 Appendix 1          1.00 E+01          1.00 E+01            1.00 E+01      1.00 E+01          2.00 E+01 Limit (mrad)
Critical Organ Dose for 1-131, 1-133,        1.84 E-01          1.95 E-01            1.91 E-01      1.69 E-01          7.40 E-01 Particulates, & H3 With TI/2
> 8 days (mrem)
Critical Organ Dose          1.33 E-01          1.33 E-01          1.33 E-01        1.33 E-01          5.32 E-01 for C-14 Dose (mrem)
Total Critical Organ          3.17 E-01          3.28 E-01            3.24 E-01      3.02 E-01            1.27 E+00 Dose (mrem) 10CFR50 Appendix I Limit (mrem)                  7.5 E+00            7.5 E+00            7.5 E+00        7.5 E+00            1.50 E+01
                                                          -  35
 
Appendix 8: Assessment of Radiation Doses (Continued)
ODCM Operational Requirement F.2 Li-quid The dose from the liquid pathway is based on fish consumption from Harris Lake (parts of the lake are within the site boundary) plus drinking water from Lillington.
rd              th IST              2 nd            3                4                  Annual Quarter          Quarter          Quarter          Quarter                Total Total Body Dose (mrem)            2.52 E-04        8.61 E-04      3.06 E-04        9.39 E-03            1.08 E-02 10CFR50 Appendix I Limit (mrem)          1.50 E+00        1.50 E+00      1.50 E+00        1.50 E+00            3.00 E+00 Critical Organ Dose (mrem)            1.70 E-03        2.99 E-03        1.90 E-03        1.02 E-02            1.68 E-02 10CFR50 Appendix I Limit (mrem)          5.00 E+00        5.00 E+00      5.00 E+00        5.00 E+00            1.00 E+01 40CFR190 Uranium Fuel Cycle Dose Calculation Results The 40CFR 190 effluent dose analysis to the maximum exposed individual from liquid and gas releases includes the dose from noble gases (i.e. total body and skin)
Maximum Total Body Dose = 7.51 E-01 mrem Maximum Location: 1.33 Miles, South-SouthWest Sector Critical Age:      Child Liquid Effluent Dose = 1.08 E-02 mrem Gas Effluent Dose = 7.40 E-01 mrem 40CFR 190 Limit = 25 Maximum Organ Dose = 1.27 E+00 mrem Maximum Location: 1.33 Miles, South-SouthWest Sector Critical Age:      Child Critical Organ: GI-LLI Liquid Effluent Dose = 1.68 E-02 mrem Gas Effluent Dose = 1.27 E+00 mrem 40CFR190 Limit = 75 mrem (thyroid), 25 mrem (all other organs)
 
Appendix 8: Assessment of Radiation Doses (Continued)
ODCM Operational Requirement F.2 Doses Due to Direct Radiation from the Harris Nuclear Plant:
Ongoing Environmental TLD Dose measurements show that the offsite Direct Radiation Dose is negligible. Components considered include Radwaste storage onsite and the Old Steam Generator Storage Facility.
Doses from Return/Re-use of Previously Discharged Radioactive Effluents:
: 1. Tritium dose from drinking water to the worker at the Training Center for 2014 is equal to 1.34 E-01 mrem.
: 2. The highest annual tritium dose due to the cooling tower operation at HNP is received by a child residing at the 1.81 mile NNE location. This dose includes the inhalation pathway dose of 1.22E-03 mrem, the garden pathway dose of 4.38E-03 mrem, and the meat pathway dose of 2.54 E-04 mrem. The child would receive a total of 5.86 E-03 mrem dose in the calendar year 2014.
1StQuarter Dose =        2.03 E-03 mrem 2 nd Quarter Dose =        1.57 E-03 mrem 3 rd Quarter Dose =        1.13 E-03 mrem 4 th Quarter Dose =        1.13 E-03 mrem
: 3. Tritium dose to the nearest resident (child) from lake evaporation is equal to 9.69 E-02 mrem. This dose includes inhalation pathway dose of 2.01 E-02 mrem, the garden pathway dose of 7.25 E-02 mrem, and meat pathway dose of 4.24E-03 mrem. This resident is a child living in the SSW sector at a distance of 4 miles.
1st Quarter Dose =        2.32 E-02 mrem 2  nd Quarter Dose =      3.54 E-02 mrem 3  rd Quarter Dose =      2.54 E-02 mrem 4 th Quarter Dose =        1.28 E-02 mrem
                                                        -  37  -
 
Appendix 9: Corrections to Previous Annual Reports There are no corrections to be made to previous year's Annual Radioactive Effluent Release Reports.
Appendix 10: ODCM Revision 25
                                                      - 38  -
 
SHEARON HARRIS NUCLEAR POWER PLANT OFF-SITE DOSE CALCULATION MANUAL (ODCM)
Revision 25 Docket No. STN-50-400 DUKE ENERGY PROGRESS, Inc Formerly known as Carolina Power & Light Company Approval by PNSC Chairman Approval by General Manage*
rHarris Plant Prepared by Reviewed by            t14u%
Effective Date Uii4~
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                                                                                        Aug 2014 Offsite Dose Calculation Manual (ODCM)                                                                                                                                                Rev. 25 TABLE OF CONTENTS Se ctio n          Title .............................................................................................................................................                    Paag e TABLE OF CONTENTS ..................................................................................................................................................                            i LIS T O F T ABLES ...........................................................................................................................................................                  ii LIS T O F F IGUR E S ........................................................................................................................................................                  iv LIST OF EFFECTIVE PAGES ........................................................................................................................................                                v ODCM REV. 25 CHANGE SUM MARY .........................................................................................................................                                        ix 1 .0      INT R O DUC T ION ..........................................................................................................................................                      1-1 2.0      LIQUID EFFLUENTS ....................................................................................................................................                              2-1 2.1      Com pliance W ith 10 CFR 20 ..........................................................................................................                                    2-2 2.2      Com pliance W ith 10 CFR 50 Appendix I ......................................................................................                                            2-13 2.3      Doses from Return/Re-use of Previously Discharged Radioactive Effluents ................................                                                                2-19 3.0      GASEOUS EFFLUENTS ..............................................................................................................................                                  3-1 3.1      Monitor Alarm Setpoint Determ ination ............................................................................................                                        3-1 3.2      Post-release Compliance With 10CFR20-Based ODCM Operational Requirem ent 3.11.2 ...................................................................................................                                      3-15 3.3      Com pliance With 10 CFR 50 ........................................................................................................                                      3-21 4.0      RADIOLOGICAL ENVIRONM ENTAL MONITORING PROGRAM ...............................................................                                                                    4-1 5.0      INTERLABORATO RY COM PARISON STUDIES .........................................................................................                                                    5-1 6.0      TOTAL DOSE (COMPLIANCE WITH 40 CFR 190)for ODCM OR 3.11.4 ...............................................                                                                          6-1 6.1      Total Dose (COM PLIANCE W ITH 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, A ND TR ITIUM ..............................................................................................................................                            B-1 APPENDIX C - RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUM ENTATION NUM BERS ....................................................................                                                                C-1 APPENDIX D - PROGRAM MATIC CONTROLS ........................................................................................................                                                D-1 APPENDIX E - PROGRAM MATIC CONTROL BASES .........................................................................................                                                          E-1 APPENDIX F - ADM INISTRATIVE CONTROLS ........................................................................................................                                              F-1 APPENDIX G - DEFINITIONS ....................................................................................................                                ............................. G-1 i
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                                                                            August 2014 Offsite Dose Calculation Manual (ODCM)                                                                                                                                      Rev. 25 LIST OF TABLES No.                                                                            Title                                                                                          Paqe 2.1-1a            Liquid Effluent Release Tanks and Pumps Design Basis ...........................................................                                              2-23 2.1-1b            Liquid Effluent Release Tanks and Pumps For Normal Operations ............................................                                                    2-23 2.1-2            Setpoints for Cooling Tower Blowdown Dilution Flow R ate s (Favai)) ................................................................................................................................            2 -2 4 2.1-3            Signal Processor Time Constants (-) for GA Technologies RD-53 Liquid Effluent Monitors ...... 2-24 2 .1-4            Nuclide P a ra m ete rs ....................................................................................................................                  2-2 5 2.2-1            AI. Values for the Adult for the Shearon Harris Nuclear Po we r P la nt ...................    ............................................................................................................          2 -2 8 3 .1-1            G ase o us S o urce Te rm s ..............................................................................................................                    3-12 3.1-2            Dose Factors and Constants (Deleted) ..........................................                                                                              3-13 3.1-3            G aseous Monitor Param eters .....................................................................................................                            3-14 3.2-1            Releases from Shearon Harris Nuclear Power Plant Norm al O pe ration (C uries/year) ..................................................................................................                        3-18 3.2-3            D ose Factors for Noble Gases ...................................................................................................                            3-19 3.2-4            P il V alues (Inhalation) for a C hild ..............................................................................................                        3-20 3.3-1 through 3.3-19 R Values for the Shearon Harris Nuclear Power Plant ...............................................................                                          3-37 3.3-20            Recommended Values for Uap to be used for the Maximum Exposed Individual in Lie u of S ite S pecific D ata ........................................................................................................                    3-6 8 3.3-21            Inhalation Dose Factors from Carbon-14 for organ to an individual from Tables E-7 to E-10 R eg ulatory G uide 1.109 R ev 1 ..................................................................................................                          3-6 9 3.3-22            Ingestion Dose Factors from Carbon-14 for organ to an individual from Tables E-1 1 to E-14 R egulatory G uide 1.109 R ev 1 ...................................................................................................                          3-69 4.1              Radiological Environmental Monitoring Program ..........................................................................                                        4-2 4.2              Radiological Environmental Monitoring Program Sampling Locations ........................................                                                    4-16 4.3              Radiological Environmental Monitoring Program Sampling Locations (TLD Sites) ..................... 4-17 A-1 through A-4  X/Q and D/Q Values for Long-Term Ground-Level Releases a t S p ec ia l Lo ca tion s .....................................................................................................................              A -5 A-5              Undepleted, No Decay, X/Q Values For Long Term Ground Level Releases At Standard Distances (sec/m3) .............................................................              ........ _ .......      .    ......    .............          ...... A -7 A-6              Undepleted, No Decay, X/Q Values For Long Term Ground Level Releases At Standard Distances (sec /m3) .........................................................................................................................................              A-8 A-7                Undepleted, 2.26 Day Decay, X/Q Values For Long Term Ground Level Releases At Standard D ista nce s (sec /m 3) ........................................................................................................................                A-9 ii
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                                                                        May 2013 Offsite Dose Calculation Manual (ODCM)                                                                                                                            Rev. 24 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 Distances (sec/m 3) ..................................................................................................                              A -10 A-9              Depleted, 8.0 Day Decay, X/Q Values For Long Term Ground Level Releases At Standard Distances (sec/m 3) ..............................................................................................                                  A- 1 A-10              Depleted, 8.0 Day Decay, X/Q Values For Long Term Ground Level Releases At Standard D istances (sec/m 3) ..................................................................................................                            A-12 A-11              Deposition Values (D/Q) For Long Term Releases At Standard Distances                                                    (m2) ................ A-1 3 A-12              Deposition Values (D/Q) For Long Term Releases At Standard Distances                                                    (m-2) ..............      A-14 A-13              Joint Wind Frequency Distribution By Pasquill Stability Classes At SHNPP ..............................                                            A-15 A-14              Shearon Harris Plant Site Input Information for Continuous Ground-level Release Calculations W ith the NR C X O Q D O Q Program ..............................................................................................                  A -18 B-1              Parameters for Cow and Goat Milk Pathways ............................................................................                            B-16 B-2              Param eters for the Meat Pathway ........................................................................................                          B-17 B-3              Parameters for the Vegetable Pathway .................................................................................                              B-18 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              F re q ue n cy No tatio n .....................................................................................................................      G -5 G -2              O pe rationa l Mode ........................................................................................................................        G -6 iii
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                                                            August 2014 Offsite Dose Calculation Manual (ODCM)                                                                                                                    Rev. 25 LIST OF FIGURES No.                                                            Title                                                                                        Paoe 2.1-1            Liquid W aste Processing Flow Diagram .....................................................................................                2-31 2.1-2            Liquid Effluent Flow Stream Diagram .........................................................................................              2-32 2.1-3            Normal Service W ater Flow Diagram .........................................................................................                2-33 2.1-4            Other Liquid Effluent Pathways ..................................................................................................          2-34 2.3-1            Map of Harris Lake for Evaporation Dose Calculation ................................................................                        2-35 3.1              SHNPP Gaseous W aste 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 ...........................................................................................................        4-18 4.1-2            Environmental Radiological Sampling Points (1 mile Radius) ....................................................                            4-19 4.1-3            Environmental Radiological Sampling Points (10 mile Radius) ..................................................                              4-20 iv
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                                                                                                    August 2014 Offsite Dose Calculation Manual (ODCM)                                                                                                                                                              Rev. 25 List of Effective Pages Paqe                                                                                                                                                                                              Revision C o ve r P a g e ................................................................................................................................................................                          25 i ..................................................................................................................................................................................                        25 ii .................................................................................................................................................................................                        25 iii .................................................................................................................................................................................                      24 iv ................................................................................................................................................................................                        25 v-v iii ............................................................................................................................................................................                        25 ix -x i .............................................................................................................................................................................                      25 1-1 ..............................................................................................................................................................................                        24 2 -1 ..........................................        ...................................................................................................................................                25 2 -2 .........................................          .....................................................................................................................................                6 2 -3 ..........................................        .....................................................................................................................................                6 2 -4 ..............................................................................................................................................................................                        20 2 -5 ................................................................................................................................................................................                        6 2 -6 ..............................................................................................................................................................................                        24 2 -7 ...............................................................................................................................................................................                        6 2 -8 ................................................................................................................................................................................                        6 2 -9 ................................................................................................................................................................................                        4 2 - 10 ........................................          .....................................................................................................................................              6 2 - 1 1 ........................................        ...................................................................................................................................                24 2 - 12 ........................................          .....................................................................................................................................              7 2 - 13 ........................................          ...................................................................................................................................                24 2 - 14 ..............................................................................................................................................................................                        4 2 - 15 ..............................................................................................................................................................................                        6 2 - 16 ...........................................................................................................................................................................                          14 2 - 17 ........................................          ...................................................................................................................................                25 2 - 18 ............................................................................................................................................................................                        17 2 - 19 ........................................          ...................................................................................................................................                20 2 -2 0 ............................................................................................................................................................................                        20 2 -2 1 ............................................................................................................................................................................                        25 2 -2 2 ............................................................................................................................................................................                        20 2 -2 3 ..................................................................            .........................................................................................................            20 2 -2 4 ........................................          .....................................................................................................................................              4 2 -2 5 ............................................................................................................................................................................                        15 2 -2 6 ............................................................................................................................................................................                        15 2 -2 7 ............................................................................................................................................................................                        21 2 -2 8 ...........................................................................................................................................................................                          25 2 -2 9 ............................................................................................................................................................................                        25 2 -3 0 ............................................................................................................................................................................                        25 2 -3 1 ..............................................................................................................................................................................                        4 2 -3 2 ..............................................................................................................................................................................                        6 2 -3 3 ..................................................................................................................................................................                      ............ 4 2-3 4 ............................................................................................................................................................................                        25 2 -3 5 ............................................................................................................................................................................                        25 3- 1 ..............................................................................................................................................................................                        17 3-2 ...............................................................................................................................................................................                        5 3-3 ............................................................................................................................................................................                          25 3-4 ..............................................................................................................................................................................                        20 3-5 ................................................................................................................................................................................                        5 3-6 ..............................................................................................................................................................................                        25 3 -7 ..............................................................................................................................................................................                        23 3-8 ..............................................................................................................................................................................                        25 3 -9 ..............................................................................................................................................................................                        20 V
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                                                                                              August 2014 Offsite Dose Calculation Manual (ODCM)                                                                                                                                                        Rev. 25 List of Effective Pages Paqe                                                                                                                                                                                          Revision 3 - 10 .............................................................................................................................................................................                5 3 - 1 1 .............................................................        ................................................................................................................        5 3 - 12 ............................................................................................................................................................................                23 3 - 13 ...........................................................................................................................................................................                25 3- 14 ............................................................................................................................................................................                20 3- 15 ............................................................................................................................................................................                20 3- 16 ............................................................................................................................................................................                25 3- 17 ............................................................................................................................................................................                25 3- 18 ...........................................................................................................................................................................                  24 3- 19 ............................................................................................................................................................................                25 3-2 0 ...........................................................................................................................................................................                  25 3-2 1 ............................................................................................................................................................................                23 3-2 2 ............................................................................................................................................................................                24 3-2 3 ............................................................................................................................................................................                20 3 -2 4 ..........................................................................................................................................................................                  20 3 -2 5 ............................................................................................................................................................................                20 3 -2 6 ..............................................................................................................................................................................                6 3-2 7 ..........................................................................................................................................................................                  25 3-28 .........................................................................................                    .............................. .... ............. .... 20 3 -2 9 ...........................................................................................................................................................................                20 3 -3 0 ............................................................................................................................................................................                22 3 -3 1 ...........................................................................................................................................................................                25 3 -3 2 .............................................................................................................................................................................                6 3-33 ..................................................................................                                                                                                            24 3 -3 4 ............................................................................................................................................................................                23 3 -3 5 ..........................................................................................................................................................................                  24 3 -3 6 ............................................................................................................................................................................                25 3 -3 7 6 8 .................................................................................................................................................................                  25 3 -6 9 ............................................................................................................................................................................                23 3 -7 0 ............................................................................................................................................................................                23 3 -7 1 ............................................................................................................................................................................                17 3 -7 2 ............................................................................................................................................................................                13 3 -7 3 ..............................................................................................................................................................................                5 4 -1 ..............................................................................................................................................................................                19 4 -2 ..............................................................................................................................................................................                21 4 -3 .............................................................................................................................................................................                21 4 -4 ..............................................................................................................................................................................                21 4 -5 ..............................................................................................................................................................................                21 4 -6 ..............................................................................................................................................................................                21 4 -7 ..............................................................................................................................................................................                21 4 -8 ..............................................................................................................................................................................                23 4 -9 ..............................................................................................................................................................................                10 vi
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                                                                                                August 2014 Offsite Dose Calculation Manual (ODCM)                                                                                                                                                              Rev. 25 List of Effective Pages Paae                                                                                                                                                                                              Revision 4 -1 0 .............................................................................................................................................................................                        4 4 - 11 ..............................................................................................................................................................................                        4 4 -1 2 ............................................................................................................................................................................                        22 4 -1 3 ............................................................................................................................................................................                        25 4 -1 4 ............................................................................................................................................................................                        22 4 - 15 ............................................................................................................................................................................                        24 4 - 16 ............................................................................................................................................................................                        25 4 - 17 ............................................................................................................................................................................                        25 4 - 18 ............................................................................................................................................................................                        18 4 - 19 ..............................                ..............................................................................................................................................2 5 4 -2 0 ............................................................................................................................................................................                        25 5- 1 ..............................................................................................................................................................................                        25 6 - 1 ..............................................................................................................................................................................                        17 7 - 1 ..............................................................................................................................................................................                        17 A-1 ..........................................................................................................                                                                        ............. 20 A -2 .............................................................................................................................................................................                          20 A -3 ............................................................................................................................................................................                          20 A -4 .............................................................................................................................................................................                          24 A A- 1 7 ..................................................................................................................................................................                            20 A -1 8 - A-2 3 ..................................................................................................................................................................                            6 B- 1 .............................................................................................................................................................................                          25 B-2 .............................................................................................................................................................................                          25 B-3 ...............................................................................................................................................................................                          6 B-4 ...............................................................................................................................................................................                          5 B-5 ..............................................................................................................................................................................                            4 B-6 ...............................................................................................................................................................................                          4 B-7 .........................................................................              .....................................................................................................              4 B-8 ..................................................................            .....................................................      .....................................................        17 B-9 ...............................................................................................................................................................................                          4 B- 10 ...........................................................................................................................................................................                          17 B- 1 1 - B- 18 ...................................................................................................................................................................                            4 C -1 .............................................................................................................................................................................                          1 4 D- 1 ...............................................................................................................................................................................                          6 D-2 .............................................................................................................................................................................                          13 D -3 ...............................................................................................................................................................................                          9 D -4 ...............................................................................................................................................................................                          6 D-5 .........................................................................              ...................................................................................................              17 D-6 .......................................................................................................................................................................                          :..... 2 4 D-7 .............................................................................................................................................................................                          11 D -8 ..............................................................................................................................................................................                          6 D-9 ...............................................................................................................................................................................                          6 vii
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                                                                                                August 2014 Offsite Dose Calculation Manual (ODCM)                                                                                                                                                          Rev. 25 List of Effective Pages Page                                                                                                                                                                                            Revision D- 10 ...........................................................................................................................................................................                    17 D - 1 1 ...........................................................................................................................................................................                  24 D- 12 ..........................................................................................................................................................................                    17 D- 13 ...........................................................................................................................................................................                    17 D D-1 8 ..................................................................................................................................................................                      6 D- 19 ...........................................................................................................................................................................                    17 D-2 0 .............................................................................................................................................................................                    6 D-2 1 ..........................................................................................................................................................................                    19 D-2 2 ...........................................................................................................................................................................                    20 D-2 3 - D-2 6 .................................................................................................................................................................                        6 D-2 7 ...........................................................................................................................................................................                    19 D-2 8 ...........................................................................................................................................................................                    19 D -29 .............................................................................................................................................................................                    6 D-3 0 .............................................................................................................................................................................                    6 D-3 1 ...........................................................................................................................................................................                    19 D-3 2 ...........................................................................................................................................................................                    20 D-3 3 .............................................................................................................................................................................                    6 D-34 ...................................................................................................................                  ................... .................................... 20 D-3 5 .............................................................................................................................................................................                    6 D-3 6 - D-3 7 ...............................................................................................................................................................                        12 D-3 8 - D-3 9 .................................................................................................................................................................                        6 D -4 0 ...........................................................................................................................................................................                  15 E E-9 ......................................................................................................................................................................                    6 E- 10 ...........................................................................................................................................................................                    17 E - 1 1 ............................................................................................................................................................................                  6 E- 12 .............................................................................................................................................................................                    6 F -1 ................................................................................................................................................................................                  6 F -2 ................................................................................................................................................................................                  6 F -3 ...........................................................................................            I..................................................................................      20 F -4 ......................................................................................................................                ................... .................................... 19 F -5 ..............................................................................................................................................................................                  17 G -1 .............................................................................................................................................................................                  18 G-2 .............................................................................................................................................................................                    24 G-3 .............................................................................................................................................................................                    24 G -4 .............................................................................................................................................................................                  24 G -5 .................................................................          ...........................................................................................................          18 G -6 .............................................................................................................................................................................                    18 viii
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                August 2014 Offsite Dose Calculation Manual (ODCM)                                                                        Rev. 25 ODCM REV. 25 CHANGE
 
==SUMMARY==
 
Revision 25 to the ODCM is as follows:
DRR's 596293, 618980 Section                Page                                        Description Table of Contents              i        Changed to "ODCM REV. 25 CHANGE
 
==SUMMARY==
",
List of Table                ii      Table 3.1-2 Dose Factors and Constant table is identified as "Deleted" Changed page numbers for tables 3.3-1 through 3.3-19 to reflect the additional pages of dose factors Revised Titles for Tables 4.2 (Radiological Environmental Monitoring Program Sampling Locations) and 4.3 (Radiological Environmental Monitoring Program Sampling Locations - TLD Sites)
List of Figure              iv        Added Figures 4.1-2 Environmental Radiological Sampling Points (1 mile Radius) and Figure 4.1-3 Environmental Radiological Sampling Points (10 mile Radius)
ODCM REV 25 CHANGE                ix        Changed to reflect Rev. 25 revisions.
 
==SUMMARY==
 
2.0 Liquid Effluents          2-1        Added statement "The SHNPP ODCM uses the Canberra, Inc, Effluent Management System (OpenEMS) software for automating the necessary calculations and recordkeeping" in order to define the program used to calculate the release permits and Annual Reporting data.
2.2.3 Projection of Doses        2-17        Changed dose to be used as an input for the dose projection equations as the sum of all open and close permits for the current quarter up to the end of the current release. Previously the ODCM stated it only included the open release points. The use of both open and close permits yields a more realistic and conservative dose projection.
Revised Note - deleted "Special Reports" and on the "Approval/Results screen". These functions are no longer available.
2.3 Dose from              2-21        Revised the Lake Harris surface area from 4120.72 acres to 4169.61 Return/Reuse                          acres. Murray and Truttle recalculated the area of the lake and new map created.
Table 2.2-1          2-28 to 2-30    Corrected the ODCM typographical errors that were identified in the OpenEMS CRTN (Ag 1lOm - all factors, Ba142 GiLLi 0.00 to 2.59E-39).
Updated Table 2.2-1 Liquid Dose factors At (adult) to include the additional isotopes and dose factors to match OpenEMS. These factors were derived using equation 2.2-3.
Figure 2.1-4              2-34        EC 96109 Removed the Waste Neutralization/Settling Basin bypass line and capped the end of the pipe Figure 2.3-1              2-35        Updated Map of Harris Lake to reflect changes in calculated areas for each segment on page 2-21 3.3.1 Default Continuous          3-3        Deleted definition of Li+1.1Mi because table 3.1-2 is derived from Table Release Monitor Setpoints                    3.2-3 and includes rounding. All of the required information can be obtained using Table 3.2-3.
3.1.2 Monitor Setpoints          3-6        Deleted summation term for all vent stacks in equations 3.2-1a and 3.2-lb. Each monitor setpoint is determined individually and allocation fractions are being used to ensure that the total release rates do not exceed ODCM limits.
3.1.2 Monitor Setpoints          3-8        Deleted summation term for all vent stacks in equations 3.2-2a and 3.2-2b. Each monitor setpoint is determined individually and allocation fractions are being used to ensure that the total release rates do not exceed ODCM limits.
Deleted definition of Li+I. 1M because table 3.1-2 is derived from Table 3.2-3 and includes rounding. All of the required information can be obtained using Table 3.2-3.
.Table 3.1-2 Dose Factors        3-13        Deleted Table 3.1-2 L+1 .1Mi because this information is derived from and Constants                          Table 3.2-3 and includes rounding. All of the required information can be obtained using Table 3.2-3.
ix
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                  August 2014 Offsite Dose Calculation Manual (ODCM)                                                                          Rev. 25 ODCM REV. 25 CHANGE
 
==SUMMARY==
 
3.2.1 Noble Gases            3-16      Deleted the definition of factor Li+1. 1 M because table 3.1-2 is derived from Table 3.2-3 and includes rounding.
3.2.2 Radioiodines and        3-17      Deleted "The values of Pi reflect, for each radionuclide, the maximum Pi Particulates                        value for any organ." Table 3.2-4 has been revised to include all Pi values for a nuclide. This change will more accurately reflect the dose rate to an individual and will align the ODCM with current practices at HNP.
Table 3.2-3 Dose Factors        3-19      Updated Table 3.2-3 to include the additional isotopes and dose factors for Noble Gas                        to match OpenEMS K, Li, Mi, Ni Table 3.2-4 Pi values for        3-20      Table 3.2-4 revised to list all of the Pi values per organ for each nuclide.
Child                          Previously the ODCM only listed the maximum Pi value for a nuclide.
This change will more accurately reflect the dose rate to an individual and will align the ODCM with current practices at HNP.
3.3.1.3 Projection of Doses      3-27      Changed dose to be used as an input for the dose projection equations 3.3.2.2 Projection of Doses        3-31      as the sum of all open and close permits for the current quarter up to the end of the current release. Previously the ODCM stated it only included the open release points. The use of both open and close permits yields a more realistic and conservative dose projection.
Revised Note - deleted "Special Reports" and on the "Approval/Results screen". These functions are no longer available.
Tables 3.3-1 to 3.3-13    3-37 to 3-68  Revised Non Noble Gas Dose dose factors (R factors) to incorporate Tables 3.3-15 to 3.3-19                  additional isotopes and dose factors to match OpenEMS.
Note: Goat Milk Dose Factors (Table 3.3-12 to 3.3-15) are not included in OpenEMS because the pathway does not currently exist. The Goat Milk dose factors are being maintained in the ODCM in the event that the Goat Milk pathway is reintroduced. At that time OpenEMS could be revised to include these terms. (formatting of the Table 3.3-14 was revised to match the other tables but the content was not changed)
Table 3.3-11              3-54      Corrected the ODCM typographical errors that were identified in the CRTN (Infant Cow Milk Y91 Total Body from 1.16E8 to 1.17E3)
Table 4.1 Ingestion - Food        4-13      Added location 97 at Granite Springs Farm. This control location has a Products                          greater diversity of food crops and provides and addition source of crops for the Food Products surveillance Figures 4.1-2 to 4.1-6    4-16 to 4-20  Revised Environmental Radiological Sampling Points figures. New Table 4.2 to 4.3                      figures were created showing each sample point in the appropriate sector and distance from the plant. Figures 4.1-4 and 4.1-5 were deleted because they were redundant. Replaced Figured 4.1-6 which was the legends for figures 4.1-2 to 4.1-5 with new tables 4.2 and 4.3.
These tables identify the environmental monitoring location and the type of sample at each location. These tables are used in the Annual Environmental Operating Report 5.0 Interlaboratory          5-1      Deleted references to E&EC performing sample analysis. ODCM Comparison Studies                      required radiochemical analysis are performed by a qualified laboratory (DRR 596293)
Appendix B - Bases            B-1      Deleted "The values for Pi presents the highest dose to any organ B-2      including the whole body resulting from inhalation of radionuclide "i"by a child." Table 3.2-4 revised to list all of the Pi values per organ for each nuclide. Previously the ODCM only listed the maximum Pi value for a nuclide. This change will more accurately reflect the dose rate to an individual and will align the ODCM with current practices at HNP.
x
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                    May 2013 Offsite Dose Calculation Manual (ODCM)                                                                          Rev. 24
 
==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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                    August 2014 Offsite Dose Calculation Manual (ODCM)                                                                              Rev. 25 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 gCi/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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                    August 1995 Offsite Dose Calculation Manual (ODCM)                                                                              Rev. 6 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, Smx, 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, Saiert, are set at a fraction of the Smax to provide an early warning of the approach to ODCM Operational Requirement limits.
2-2
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                August 1995 Offsite Dose Calculation Manual (ODCM)                                                                            Rev. 6 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-1 37, 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.
2-3
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                  March 2009 Offsite Dose Calculation Manual (ODCM)                                                                          Rev. 20 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        V)                                                                                    (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.
2-4
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                  August 1995 Offsite Dose Calculation Manual (ODCM)                                                                              Rev. 6 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:
C.
1  < 10                                                                                (2.1-2)
ECLi where:
C          =      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                        Dreqg + Dreqng                                                        (2.1-3) where:
Dreq,g            =        Required dilution factor for gamma-emitters C.
ECL.
1-                                                        (2.1-4) f e  R...
2-5
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                        May 2013 Offsite Dose Calculation Manual (ODCM)                                                                                Rev. 24 2.1.1    Batch Releases (continued)
Dreq,ng            =          Required dilution factor for non-gamma-emitters C.
Y-i=ng      --
ZngECLi        r
                                                -      +
(2.1-5) feRmax        foRmax 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 dischjarge line. The maximum tritium value is set to 1.OE-03, which is the H-3 ECL.
NOTE: CRC-001 has a target limit of 2.OE-04 pCi/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 iiCi/ml. If no gamma activity is detectable then an activity of 9E-07 j.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 liCi/ml.
2-6
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                    August 1995 Offsite Dose Calculation Manual (ODCM)                                                                              Rev. 6 2.1.1    Batch Releases (continued)
: 3.      Maximum Waste Flow For liquid releasesthe maximum permissible waste flow rate for this release, Winax is the minimum of Rcwmax and Rwmax, where F~j,    *f.1, 0i (2.1-6)
Dr, Rwmax                      Liquid effluent tank maximum waste flow rate, as specified in Table 2.1-
: 1. This value is the same as Fwaste.
and 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.
fa, oc                      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 faroc 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  9D req min dflow                                                                                        (2.1-7) faiioc where Fwaste                                  waste flow anticipated for this release 2-7
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                  August 1995 Offsite Dose Calculation Manual (ODCM)                                                                            Rev. 6 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 ACi/ml.
Ifanalysis 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-1 34. 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.
Drq, ng Fuat
                                                      ....                  e                                    (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 (pCi/ml) 2-8
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                  June 1994 Offsite Dose Calculation Manual (ODCM)                                                                            Rev. 4 2.1.1    Batch Releases (continued)
Rmon    =        T  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-1 37, the nuclide sensitivity is divided by the Cs-1 37 sensitivity.
Sensitivity (nuclide i)
Cs-137 Sensitivity (2)    Monitor alert alarm setpoint,  SaIert (Cs-equiv)
An Alert Alarm setpoint is calculated to provide an operator with adequate warning that the high alarm setpoint is being approached. Saert is calculated from the nuclide specific response setpoint.
Salert    =        [(Smax - B)
* F.] + B                                              (2.1-10) where:
F,                A value <1.0 designed to provide an operator with adequate warning that the high alarm setpoint is being approached.
2-9
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                      August 1995 Offsite Dose Calculation Manual (ODCM)                                                                                  Rev. 6 2.1.1    Batch Releases (continued)
(3)        Check for Excessive Monitor Background In order to differentiate between the Sarert 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
MDC                  =                                                                  (2.1-12)
Em where:
T                              Signal Processor Time constant, minutes. (Table 2.1-3)
Bkg                  =          Background Count Rate, in cpm
                                                  =          B/rEm Em                    =        Monitor efficiency for the Cs-1 37 gamma energy, cpm/pCi/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.
2-10
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                        May 2013 Offsite Dose Calculation Manual (ODCM)                                                                              Rev. 24 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 (jiCi/ml).
Smax                            0.1 (ECLeff
* Senseff) +  Bkg
                                        =(2.1-13)
Em where:
ECLe,                          Weighted Effluent Concentration Limit for the SWST nuclides listed in Table 11.2.1-5 of the FSAR.
Sense,              =            ,g(Sensi x % abundance) for the SWST nuclide mix, cpm/liCi/ml.
: 2.      Monitor Alert Alarm Setpoint,      Saiert (Cs-equiv)
Saiert              =          [(Smax - B) e 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)                                        (2.1-15)
MDC_                                          Em 2-11
 
Shearon Harris Nuclear Power Plant                                                                        November 1995 Offsite Dose Calculation Manual (ODCM)                                                                              Rev. 7 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. Ifthe 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).
2-12
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                          May 2013 Offsite Dose Calculation Manual (ODCM)                                                                                Rev. 24 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:
Di~r                =        Aitr - YX Ats Cis Frs                                                            (2.2-1) where:
Disr                        the cumulative dose or dose commitment to the total body or an organ "T"by nuclide "i" for receptor 'r' from the liquid effluents for the total time period of the release, in mrem.
Aitr                        site-related ingestion dose or dose commitment factor for receptor "r' to the total body or organ "T"for nuclide "i", in mrem/hr per iiCi/ml.
Ats                          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 Ats from any liquid release, in pCi/ml.
Frs                        the near field average dilution factor for receptor 'r' during any liquid effluent release.
2-13
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                        June 1994 Offsite Dose Calculation Manual (ODCM)                                                                                Rev. 4 2.2.1    Cumulation of Doses (continued)
Where:
F waste 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 Favaii = 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.
The dose factor A,, (see NUREG-0133, Section 4.3.1) was calculated for an adult for each isotope "i" using the following equation:
                                                                                  -A.t 730                            p A.                  =          1.14E + 05 (-          + 21BF.) DF.
* e                                      (2.2-3)
D                  IT where:
k                              The ingestion dose commitment factor to the whole body or any organ "I" 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 iiCi/ml are given in Table 2.2-1.
2-14
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                    August 1995 Offsite Dose Calculation Manual (ODCM)                                                                              Rev. 6 2.2.1    Cumulation of Doses (continued) 1.14E+05          =        Unit Conversion Factor 106  pci        1000 ml            1 yr
                                          -      -                                                                (2.2-4) 1 [ICi          1 liter        8760 hrs 21        =        Adult fish consumption rate (from Table E-5 of Regulatory Guide 1.109, Rev. 1), kglyr; 730        =      Adult water consumption rate (from Table E-5 of Regulatory Guide 1.109, Rev. 1), liters/yr.
D          =        Dilution factor for the drinking water pathway
                    =        13.95 BF        =        Bioaccumulation factor for nuclide "i" in fish (from Table A-1 of Regulatory Guide 1.109, Rev. 1), pCi/kg per pCi/I DF,      =        Dose conversion factor for nuclide "i' for adults for a particular organ T (from Table E-1 1 of Regulatory Guide 1.109, Rev. 1), mrem/pCi
                    =        Radiological decay constant of nuclide "i," hr';
                    =        0.693 (t1/2)i (t1/2)      =        Radiological half-life of nuclide "i," hr; tp        =        Average transport time to reach point of exposure, hr;
                    =        12 hours. The more limiting decay time for the drinking water and fish exposure pathways (Reg. Guide 1.109, Appendix A, Rev. 1).
Table 2.2-1 presents the Ai values for an adult receptor. Values of e-?,jtp are presented in Table 2.1-4 for each nuclide "i".
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.
2-15
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                November 2001 Offsite Dose Calculation Manual (ODCM)                                                                            Rev. 14 2.2.2    Comparison Against Limits (continued)
For the calendar quarter:
DiOr      <        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)
Di~r      -        10 mrem any organ                                                                      (2.2-8) where:
D        =        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 1, 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).
2-16
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                      Aug 2014 Offsite Dose Calculation Manual (ODCM)                                                                            Rev. 25 2.2.2    Post-release Compliance With 10 CFR 50 - Based ODCM Operational Requirement 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.
2.2.3    Proiection 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, &deg; p) + Dat                                                                                      (2.3-1) where:
Dp,      =      the 31 Day Projected Dose by organ      T DT        =        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 T.
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.
DaT      =      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.
2-17
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                              November 2004 Offsite Dose Calculation Manual (ODCM)                                                                            Rev. 17 2.2.3    Proiection of Doses (continued)
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                                                                            (2.3-2) and Dp, < 0.2 mrem for any organ                                                                              (2.3-3)
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.
2-18
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                        March 2009 Offsite Dose Calculation Manual (ODCM)                                                                                Rev. 20 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 life's &
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, and the dose to the nearest resident to the lake from lake evaporation.
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:
: 1) Worker Drinking Water Pathway        -
Rapj  = Uap
* Dapj
* Cip                                                                                      (2.3.1)
Where; Rapj =            is the 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 is no dose' Rapj =            (261 liters/yr) * (1.05E-07 mrem/pci) * (concentration pci/I from DW-51) 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:
DT~r                            (3.17E -08) * (RTIT)  * (X/QEIv) I Qvr                                          (2.3-2) where:
DTmr                            the cumulative dose or dose commitment to the total body or an organ "'" by Tritium for receptor Yr 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 2-19
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                      March 2009 Offsite Dose Calculation Manual (ODCM)                                                                            Rev. 20 RTi                          Dose factor for an organ "T" for the tritium from the inhalation pathway in mrem/hr per 4Ci/ml.
X/QEv                        The highest elevated calculated annual average relative concentration for the nearest resident from the Cooling Tower (sec/mr).
QVT                          Evr
* Ats
* CTBD
* qt The total tritium (pCi) 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)
Ats                =        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 (pCi/ml).
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 Dalton's Law.
Ev = C *(Es - Ed)      (1 + U25/10)                                                                        (3.3.1)
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.
2-20
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                      Aug 2014 Offsite Dose Calculation Manual (ODCM)                                                                              Rev. 25 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 (pCi)
QT = 7 (Larea
* EVave * (LTconc
* 1 E-09))                                                                (3.3.1)
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/I 3
1E-09                =        Ci/1.0E12 pCi
* liter/1000 cm
* 100 cm/meter
* 100 cm/meter
* 100 cm/meter=
Curies/meter 3
: 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 Sect. Acres            m2 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 2-21
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                        March 2009 Offsite Dose Calculation Manual (ODCM)                                                                                Rev. 20 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)
Where:
qTsect              =        Total tritium concentration from the thirteen lake sections at point of interest (X,pCilm 3)
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.OE+12 pCi/Ci)/(8760 hr/yr)*(3600 sec/hr)
The dose for each age group at each point of interest is to be calculated as follows:
Dosea~poi                      (qTsect) * (DFA)a * (BR)a Where:
Doseapoi            =          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/m 3 )
(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 m /yr 2-22
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                            March 2009 Offsite Dose Calculation Manual (ODCM)                                                                      Rev. 20 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 Reference SHNPP FSAR Tables 11.5.1-1 and 11.2.1-7 SWST: Secondary Waste Sample Tank WECT: Waste Evaporator Condensate Tank WMT: Waste Monitor Tank TL&HS: Treated Laundry and Hot Shower Tank 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 Eductor      Capacity @        Radiation Tank  (2)    No. of                                              Factor      Overflow          Effluent Tanks        Recirculation      Pressure (psig)
(gpm)                                            Line        Monitor ID (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 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.
2-23
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                              June 1994 Offsite Dose Calculation Manual (ODCM)                                                                      Rev. 4 TABLE 2.1-2 Setpoints for Cooling Tower Blowdown Dilution Flow Rates    (Favaii)
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 (T)for GA Technologies RD-53 Liquid Effluent Monitors Detector Background (cpm)                        T (min) 10 1- 1o2                                10 3
10 2 -10 3                          10 /cpm bkg 103-_ 104                            103/cpm bkg 10_4-_ 105                          103/cpm bkg 105._  106                              0.01 106. 107                                0.01 2-24
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                  July 2002 Offsite Dose Calculation Manual (ODCM)                                                                        Rev. 15 Page 1 of 3 TABLE 2.1-4 Nuclide Parameters Half-Life            .                          Sensitivity                            Sensitivity Nuclide            (hr)          (hr-1)            e-t        (cpm/jiCi/ml)          Slope              TB Bldg.
Drain Only (cpm/tiCi/ml)
H-3        1.08E+05        6 441::-06      1.0noE+On O0OE+0O                  n O0E+O0            O00E+O0 C-14        s  02E+n7        1.38F-08      100EOO            O.OE+0          0                    OOOE+0O F-18        1-83E+          3-78F-01                -        O.nOEnO0          O.OOE+O 0            7,78F+07 N-4          1 5+l1          469F-0.2E-2    5.74F-0          9 36F+07          A.9nE-01            9 11E+07 P-32        I4AE+02.        2.02.-0        qEOOE+On 760                                                  0o 0E+O0 Cr-51        6.5E+02.        1.04E-03      9. BE-01          1.61E+07          1255E-01            2.79E+06 Mn-54        7-50E+03        9-24E-05      999E-0            1 03E+08          A.9FO-E-l          4-45E+07 Mn-56        298E+/-+0l        2,68E-01      4.OOE-02          1.031E+08          9.71 E-01          6 41 E+07 Fe-55        2,37E+04        2.93F-05      1.00E+n00                +            O. +O0            O.OO+O Fe-59        1.n7E+/-+D        6-47F:-04      A 92D-01          1.26F+08          1 21F:+00          4 S8E+07 Co-57        8.50E+03        1-07E-04      999F-01            .0DOE+00        0 .OE+00            S.82E+_6 Co-58        1.70E+03        4.08E-04                -        I.46E+08          1.40E+O0            5.68F+07 c-0          4 62F+04        1 5-sn5-n    W10 ED+O            1. 89E+08          1.82E+00            9,_7E+_7 Ni-63      8.78E+05        7.89E-07      1 .00+0          nOOOE+O0          O_0F+00              n ODE +00 Ni-65      2.52E+00        295F-01.        3.67E-02          2,24E+07          9_15_-01            1.96E+07 (u-64        1297F+01        5467E-02                        5.16F+07          4 A6F-n    1          46F+07
__19E-01 7n-65        5 87E+03        1-18E-04      9_99E-01          5,24E+07          5.04_-01            2.41E+07 Zn-(9        A927F-01        7.48F-01      1.26E-04          2.22E+03                              5.00E+02    _213E-05 Zn-69m        1 381E+01        5 03FE-02      547E-01          OOOE+nO          n_0__+_o            3.59F+07 Br-82        3.53Ei+nl    W.OEQ+no 1.96E-02      7-90E-01          n.OOE+O0                              1,43E+08 Br-83        2.38E+00        2,91E-01      3.05E-0          1.95F+06          1-88F-02            5 74E+05 Sr-84        5. 3:          1.31 E+n0      1E53F-D7          6_50F+07                    _ __F-01_ 5    _E+_ 7 Br-85        4.78E-02        1.45E+01        3.02F-76          6.76E+06          6.50E-02            3.21E+06 Rb-86        4,48E+02        1.55E-03      9.892E-l          8 39E+O6          8.07E-02            3.96E+06 Rb-88-1                          4E9.+00 31-01        8 66E-13          I 45E+07          1.3E-1              1 83E+n7 Rb-89        9 57-1.        2.70E+00        8-43E-15          1.22E+08          1-17F+00            7 OOE+07 Sr-89        1.E91.+3        5.71E-04        -.93E-l        1.46E+04          1-40F-04            6 72E+03 St-A0        9 5F+o5        177E-6          1_00+00          0 .OE+O.F+0 000+00E+                              0 nOE +00 Sr-91        9-50E+00        7_30E-02      417E-0            8-16E+07          7.E-01              3-48E+07 Sr-92        2.72E+00        2.55F-01        4.68F-02          1.01E+08                              4.61E+07  0.71E-01 Y-90        6 49F.          109 E-02 12E+f0l1                        0 OE +0.OF+
D.7E-13                                0 OnE+D0 Y-91        1.41 F+03      4.93F-04        94F-01            283E+05              7E-03                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-81      9_5oE-02          2976E+07          2-65F-01            1.17E+07 Y-93        1.01 F+01      68E-02          4.39F-01          1_37E+07          1.39F-01            3 96E+06 Zr-95        1.54E+03        4.51E-04        9.95E-01          1.07E+08          1.03E+00            4-35E+07 r-7      1 682+01        4.1F-0          6-10F-1            68E+07          9 58E-01            9 16E+06 Nb-95        8-42E+02        8_24E-04      9,90E-01          106E+08            1.02E+00            4.41E+07 Nb-97          20+0        5.771E                E4                0 +000 OFE                      4 .33E+07 Mo-99          60F+01    1. 105E-02    18.82E-1              3.47F+07          3+ 4E-01            9 38E+06 Tc-99m    I602E+00        I1.15E-01          2.51lE-01I        1-11E+08          1.07E+00            7 33E+06 2-25
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                            July 2002 Offsite Dose Calculation Manual (ODCM)                                                                                    Rev. 15 Page 2 of 3 TABLE 2.1-4 Nuclide Parameters (continued)
Half-Life            ?ISensitivity                                                            Sensitivity TB Nuclide            (hr)          (hr-i)                e-k                (cpm/p~Ci/ml)          Slope              Bldg.
Drain Only
___________(cpmn4iCi/ml)
Tr-101        217E-01        2 w3E+nn              49F-16                  1 RR+0              n+o            9 A9+7 Rufla.    .. A E.1+/-D2._        TI-n              9AF-0                    1 319-+08          1,3E0            3-83E+07 Ru m.    . 4-43E+00        1-56F-0              1,53F-L                  1,71 E+08        1,64F0            5.21 E+07 flujfl6        s+/-DRs~n,        7,5-5                AAF                      4 r;2F+07          4-5E0            1 43F+07
.g-110m.        6 OO0    +/-.. 116-04              999-0                    3 29F+08          3.1E+0            1.41 E+08 iia.
13    9 7F+17.        2~i-51 F-0            Z97FL.                3 O8E+nR          2 RF0            4 98E+nr)
Shb124.      i4517+03            DE4.            q4E-L                    1 c59F+ns        1 F3F            8 311F+07
    ';- ,        2 43F+04..      2 85F1115              nn~o                  1 21 F+08          1-16FQn          .3 9nE+n7 TP-125m          1 9+0            98F04.            9.4F-01                  3 OOE+05          2 SF0            1.1 7E+04 Te-127m        2R2E+/-+0        2 RFnE2Fn 99F0                                13F0                                62Fn T-1m          3-SEFQ1.      2-31E-0.            7-58E-lL                2I7+              99q~                -7E+07
________
ITi22m 3    ~ 7,82EZ01  +/-2                                                  _          _9E0    1-1FnO          _1RF        _1F0 1-134t.      8-77F-01      7-9E-01              7.58E-05                  1 nS+0.929E0013E0 rJ-1 3        117.          9~lEDjEO.            9-74E-01                3 31Fn            3-4FOn            1 IF0 rq-133        2 65FD.L      9 6Q2F0              1 OOF~nn                  1 0E+n018170                          -9F0 Cs13          .9;E+/-~
                      'A7F-ni    1f                        ~
I 6F011E+08              29+0              111+0                684E+07 Ra13q        1JZE+/-2 39+0                  - I3,6F                                34F+07          945Fn            2171E+06 Ra1n inFnq          99Fnj                ATFl-01                  601E+07            c;7F-l~          3-45E+07 Ra-14      3-5F0                  +2EQ 1-.J.B-D                        2153E+08          2,43E0            8; 43E+n7 I a-49        59+0        4-3E-0              5..AfEL 3                    9+n7 A 4SF-E1          ..2.2?F-lL.        217-7E+07 Cet40..      7,80E20      8-9E0                q2aED.L                  6.11 E+07          5,8FQ1              4.2E+06 Ce14L          330+0          9 7.-o              7-773E012..              2 63E+n8          Q~iFn            5-90F+07 Ce14      682+            1-02E+/-04            95qqF-l.                  1-30E+07          1J49F-j~        7-46E+05 Nd-142.        9 6FL          2.63E-03.          22.8ZE-l.                2-86E+07          9.7ESF-0          I 90E+nB IN-29          5 6r+0      1  1    .Fn-I-0    I  A                        1 13F+nR      1    A8      I      1-01F+07 2-26
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                      July 2010 Offsite Dose Calculation Manual (ODCM)                                                                            Rev. 21 Page 3 of 3 TABLE 2.1-4 Nuclide Parameters (continued)
Half-Life          ?ISensitivity                                                        Sensitivity TB Nuclide          (hr)          (hr-i)            e-Xt        (cpm/VCi/ml)          Slope                Bldg.
Drain Only (cpm/ljCi/ml)
Ar-41      i 83E+nn        'I7sp-nj          i 7-              9 28E+07          sqF-i4                  51Fi-07 Kr-8      9.40E+04        ZIZ7F-n        JLD.E+/-OQ.            6-20E+05          S.87n*              1,75F+05 Kr85          4A48F+/-nO        15rr)-l.          1..J)F-lE&L.ng1.                      15F+0                19+0 JKr-8          9L.n        9 42ZE+/--n.        1 44AA.EA...      9.19E+07          8 84F-01            3 99F+07 Kr8        ')                4E-2*n            2Q74+07                            2.9F-QL            5; 19F+07 Kr8          5-27F0        1-2EF+01          2Ea.              I3+08            l.1Fn                6 59F+117 Kr2-..      8-9E-03        7Z2+/-L 79F+01D~                          1 5E08            1.V.,F0              5 43EF+07 Xe131m        9 8f;ED2.      2 45F-03          9.71E-01          2 62E+06          252F-02              2 21 F+05 Xe-3Fn93 - IS.5F-.,              936-0              A90E+n4          q.9?-4              q 33EI+n3 Xe-1 2E0    ~~    -6E0      ~ 35 4,2-108 9                                  1-41E+00            2.1OE+07 Xe1 5F-15          7F~n            4 F- S1            14E+08          1lp(n.                    F+n Xe13  3F-2        1EcF~l                7F5            4-85E+07          4E11-32E+07 Xe18 93Fn            .cFn            .9F1              1,20E+08EIJ&#xfd;+/-O                        42E0 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 (Nal) 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-1 1026, 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.
2-27
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                    Aug 2014 Offsite Dose Calculation Manual (ODCM)                                                          Rev. 25 Sheet 1  of    3 TABLE 2.2-1 AjVALUES FOR THE ADULT FOR THE SHEARON HARRIS NUCLEAR POWER PLANT t
730 + 21BF.) DF. *e-A 1 p A.        =1.14E + 05 (-
1T, r,p                D              IT w
(mrem/hr per gCi/ml)
Nuclide          Bone          Liver      Total Body      Thyroid      Kidney    Lung        Gi-LLi H-3              O.OOE+O0      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.OOE+00    0.OOE+00  0.OOE+00    5.08E+06 Cr-51            0.OOE+00      0.OOE+00      1.28E+00      7.63E-01    2.81E-01  1.69E+00    3.21E+02 Mn-54            0.OOE+00      4.41E+03      8.41E+02      0.OOE+00    1.31E+03  O.OOE+00    1.35E+04 Mn-56            0.OOE+00      4.44E+00      7.87E-01      0.OOE+00    5.63E+00  0.OOE+00    1.42E+02 Fe-55            6.76E+02      4.67E+02      1.09E+02      0.OOE+00    0.OOE+00  2.60E+02    2.68E+02 Fe-59            1.06E+03      2.49E+03      9.54E+02      0.OOE+00    0.OOE+00  6.95E+02    8.29E+03 Co-57            0.OOE+00      2.20E+01      3.66E+01      0.OOE+00    0.OOE+00  0.OOE+00    5.58E+02 Co-58            0.OOE+00      9.33E+01      2.09E+02      0.OOE+00    0.OOE+00  0.OOE+00    1.89E+03 Co-60            0.OOE+00      2.69E+02      5.94E+02      0.OOE+00    0.00E+00  0.OOE+00    5.06E+03 Ni-63            3.20E+04      2.21E+03      1.07E+03      0.OOE+00    O.OOE+00  0.OOE+00    4.62E+02 Ni-65            4.76E+00      6.19E-01      2.82E-01      0.OOE+00    0.OOE+00  0.OOE+00    1.57E+01 Cu-64            0.OOE+00      5.45E+00      2.56E+00      0.OOE+00    1.37E+01  0.OOE+00    4.64E+02 Zn-65            2.32E+04      7.39E+04      3.34E+04      0.OOE+00    4.94E+04  0.OOE+00    4.65E+04 Zn-69M          4.46E+02      1.07E+03      9.79E+01      0.OOE+00    6.48E+02  0.OOE+00    6.54E+04 Zn-69            6.25E-03      1.20E-02      8.32E-04      0.OOE+00    7.77E-03  0.OOE+00    1.80E-03 Br-82            0.OOE+00      0.OOE+00      1.81E+03      O.OOE+00    0.OOE+00  0.OOE+00    2.07E+03 Br-83            0.OOE+00      0.OOE+00      1.24E+00      0.OOE+00    0.OOE+00  0.OOE+00    1.79E+00 Br-84            0.00E+00      0.OOE+00      8.07E-06      0.OOE+00    0.OOE+00  0.OOE+00    6.33E-11 Rb-86            0.OOE+00      9.95E+04      4.63E+04      0.OOE+00    0.OOE+00  0.OOE+00    1.96E+04 Rb-88            0.OOE+00        1.94E-10    1.03E-10      O.OOE+00    0.OOE+00  0.0OE+00    2.67E-21 Rb-89            0.OOE+00        1.62E-12    1.14E-12      0.OOE+00    0.OOE+00  0.OOE+00    9.43E-26 Sr-89            2.38E+04      0.OOE+00      6.84E+02      0.OOE+00    0.OOE+00  0.OOE+00    3.82E+03 Sr-90            5.91E+05      0.OOE+00      1.45E+05      0.OOE+00    0.OOE+00  0.OOE+00    1.71E+04 Sr-91            1.84E+02      0.OOE+00      7.43E+00      0.OOE+00    0.OOE+00  O.OOE+00    8.77E+02 Sr-92            7.84E+00      0.OOE+00      3.39E-01      0.OOE+00    0.OOE+00  0.OOE+00    1.55E+02 Y-90              5.57E-01      0.OOE+00      1.49E-02      0.OOE+00    0.OOE+00  0.OOE+00    5.91E+03 Y-91M            2.61E-07      0.OOE+00      1.01E-08    0.OOE+00    0.OOE+00  0.OOE+00    7.67E-07 Y-91            9.24E+00      0.OOE+00      2.47E-01      0.OOE+00    0.OOE+00  0.OOE+00    5.09E+03 Y-92              5.29E-03      0.OOE+00      1.55E-04      0.OOE+00    0.OOE+00  0.00E+00    9.27E+01 Y-93              7.75E-02      0.OOE+00      2.14E-03      0.OOE+00    0.OOE+00  0.OOE+00    2.46E+03 Zr-95            4.20E-01        1.35E-01    9.12E-02      0.OOE+00      2.11E-01 0.0OE+00    4.27E+02 Zr-97            1.42E-02      2.87E-03      1.31E-03    0.OOE+00      4.34E-03 0.OOE+00    8.90E+02 Nb-95            4.43E+02      2.47E+02      1.33E+02      0.OOE+00    2.44E+02  0.OOE+00    1.50E+06 2-28
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                Aug 2014 Offsite Dose Calculation Manual (ODCM)                                                      Rev. 25 Sheet 2 of 3 TABLE 2.2-1 (Continued)
Ai, VALUES FOR THE ADULT FOR THE SHEARON HARRIS NUCLEAR POWER PLANT (mrem/hr per i.Ci/ml)
Nuclide          Bone          Liver  Total Body      Thyroid    Kidney    Lung          Gi-LLi Nb-97            3.70E-03      9.36E-04    3.42E-04      0.OOE+00  1.09E-03 0.OOE+00      3.45E+00 Mo-99            0.OOE+00      1.14E+02  2.17E+01      0.OOE+00  2.58E+02 0.OOE+00      2.64E+02 Tc-99M          2.60E-03      7.35E-03    9.36E-02      0.OOE+00  1.12E-01 3.60E-03      4.35E+00 Tc-101          5.81E-18      8.37E-18    8.21E-17      0.OOE+00  1.51E-16 4.28E-18      2.52E-29 Ru-103          5.49E+00      0.OOE+00  2.37E+00      0.OOE+00  2.10E+01 0.OOE+00      6.41E+02 Ru-105          7.07E-02      0.OOE+00    2.79E-02      0.OOE+00  9.13E-01 0.OOE+00      4.32E+01 Ru-106          8.23E+01      0.OOE+00    1.04E+01      0.OOE+00  1.59E+02 0.OOE+00      5.33E+03 Ag-110M          1.84E+00      1.70E+00    1.01E+00      0.OOE+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.OOE+00 1.82E+01      6.62E+02 Sb-125          1.50E+01      1.67E-01    3.57E+00        1.52E-02 0.OOE+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.OOE+00      1.03E+04 Te-127m          6.51E+03      2.33E+03  7.94E+02        1.66E+03  2.65E+04 0.OOE+00      2.18E+04 Te-127          4.36E+01      1.57E+01    9.44E+00      3.23E+01  1.78E+02 0.OOE+00      3.44E+03 Te-129M          1.10E+04      4.10E+03    1.74E+03      3.77E+03  4.59E+04 0.OOE+00      5.53E+04 Te-129          2.33E-02      8.76E-03    5.68E-03        1.79E-02 9.80E-02 0.OOE+00      1.76E-02 Te-131M          1.27E+03      6.19E+02    5.16E+02      9.80E+02  6.27E+03 0.OOE+00      6.14E+04 Te-131          4.07E-08      1.70E-08    1.28E-08        3.35E-08 1.78E-07 0.OOE+00      5.76E-09 Te-132          2.19E+03      1.41E+03    1.33E+03      1.56E+03  1.36E+04 0.OOE+00      6.69E+04 1-130            1.62E+01      4.77E+01    1.88E+01      4.05E+03  7.45E+01 0.OOE+00      4.11E+01 1-131            1.67E+02      2.39E+02    1.37E+02      7.84E+04  4.10E+02 0.OOE+00      6.31E+01 1-132            2.29E-01      6.12E-01    2.14E-01      2.14E+01  9.75E-01 0.OOE+00      1.15E-01 1-133            4.OOE+01      6.95E+01    2.12E+01      1.02E+04  1.21E+02 0.OOE+00      6.25E+01 1-134            3.37E-04      9.15E-04    3.27E-04        1.59E-02 1.46E-03 0.OOE+00      7.98E-07 1-135            5.29E+00      1.38E+01    5.11E+00      9.13E+02  2.22E+01 0.OOE+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.OOE+00  6.69E+04 9.17E+03      1.37E+04 Cs-137          3.83E+05      5.23E+05    3.43E+05      0.OOE+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.OOE+00  2.48E-06  1.50E-06      6.60E-03 Ba-140          3.08E+02      3.86E-01    2.02E+01      O.OOE+00  1.31E-01 2.21E-01      6.33E+02 Ba-141            1.05E-12      7.94E-16    3.55E-14      0.OOE+00  7.38E-16 4.51E-16      4.95E-22 Ba-142            1.84E-21      1.89E-24    1.16E-22      0.OOE+00  1.60E-24  1.07E-24      2.59E-39 La-140            1.34E-01      6.75E-02    1.78E-02      0.00E+00  O.OOE+00 O.OOE+0O      4.96E+03 La-142          4.51E-05      2.05E-05    5.11E-06      0.00E+00  0.OOE+00 0.OOE+00      1.50E-01 2-29
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                Aug 2014 Offsite Dose Calculation Manual (ODCM)                                                      Rev. 25 Sheet 3 of 3 TABLE 2.2-1 (Continued)
Aj, VALUES FOR THE ADULT FOR THE SHEARON HARRIS NUCLEAR POWER PLANT (mrem/hr per [LCilml)
Nuclide          Bone          Liver  Total Body        Thyroid  Kidney    Lung        Gi-LLi Ce-141          7.76E-02      5.24E-02    5.95E-03      O.OOE+00  2.44E-02 O.OOE+00    2.01E+02 Ce-143            1.07E-02      7.94E+00    8.79E-04      O.OOE+00  3.50E-03 O.OOE+00    2.97E+02 Ce-144          4.08E+00      1.71E+00    2.19E-01      O.OOE+00  1.01E+00 O.OOE+00      1.38E+03 Pr-143          5.91E-01      2.37E-01    2.93E-02      O.OOE+00  1.37E-01 O.OOE+00    2.59E+03 Pr-144          5.88E-16      2.44E-16    2.99E-17      O.OOE+00  1.38E-16 O.OOE+00      8.46E-23 Nd-147          4.02E-01      4.64E-01    2.78E-02      O.OOE+00  2.71E-01 O.OOE+00    2.23E+03 W-187            2.10E+02      1.75E+02  6.12E+01      O.OOE+00  O.OOE+00 O.OOE+00      5.74E+04 Np-239          3.08E-02      3.03E-03    1.67E-03      O.OOE+00  9.44E-03 O.OOE+00    6.21E+02 2-30
 
Shearon Harris Nuclear Power Plant (SHNPP)                                June 1994 Offsite Dose Calculation Manual (ODCM)                                        Rev. 4 Figure 2.1-1 Liquid Waste Processing Flow Diagram 2-31
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                            August 1995 Offsite Dose Calculation Manual (ODCM)                                                                      Rev. 6 Figure 2.1-2 Liquid Effluent Flow Stream Diagram Legend Tank or Basin R Radiation Effluent Monitor REM-1WL-3540 REM-21WS-3542 Waste Evaporator    Waste Evaporator Condenst Tank      Condensate Tank o Liquids containing Radioactive materials other than tritium are not permitted by procedure to be sent to the Waste Neutralization Basin REM-21WL-3541 2-32
 
Shearon Harris Nuclear Power Plant (SHNPP)                                            June 1994 Offsite Dose Calculation Manual (ODCM)                                                    Rev. 4 Figure 2.1-3 Normal Service Water Flow Diagram Normal Service Water Waste Processing Building Normal Service Water Legend REM - Radiation Effluent Monitor NSW - Normal Service Water NOTE: For detailed flow drawings of the Service Water System, refer to the FSAR 2-33
 
Shearon Harris Nuclear Power Plant (SHNPP)                                  August 2014 Offsite Dose Calculation Manual (ODCM)                                          Rev. 25 Figure 2.1-4 Other Liquid Effluent Pathways Turbine Building Floor Drains              Outside Tank Area Drains Effluent Line                            Effluent Line
* Turbine Building Floor Drains Effluent can be Diverted to the Secondary Waste Treatment System ii  Outside Tank Area Drains Effluent can be Diverted to the Liquid Radwaste Treatment System 2-34
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                            Aug 2014 Offsite Dose Calculation Manual (ODCM)                                                                  Rev. 25 Figure 2.3-1 Map of Harris    Lake for Evaporation        Dose Calculation Area 3 6.326E405 sq meters      Area 4 156.32 acres              8.933E+05 sq meters 220.74 acres              Area G Area I 1.573E+06 sq meters 1.280E+06 sq meters                                                          388.74 acres 316.40 acres Area S 9.310E+05 sq meters 230.09 acres Area 7 1.587E+06 sq meters 392.03 acres Area 9 1.72SE406 sq meters 426.97 acres Area 13 9.83SE-05 sq meters 243.10 acres 2-35
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                November 2004 Offsite Dose Calculation Manual (ODCM)                                                                            Rev. 17 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. 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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                  August 1994 Offsite Dose Calculation Manual (ODCM)                                                                            Rev. 5 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 (Q0)in pCi, and the activity release rate  Qi in pCi/sec for each nuclide 'T'. &#xfd;' is the release rate of nuclide i'Tin gaseous effluent from discharge point "v", in pCi/sec.
Q                  I v Ci
* Fv e duration 9 28316.85                                          (3.1-1a) and Tv Ci
* Fv e 28316.85 / 60                                                  (3.1-1b) where:
v                  =          index over all vent stacks Ci                =          concentration of nuclide, in pCi/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 3-2
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                Aug 2014 Offsite Dose Calculation Manual (ODCM)                                                                      Rev. 25 3.1.1    Default Continuous Release Monitor Setpoints Using a Conservative mix (GALE code) (continued)
: 2.      Determine the maximum whole body and skin dose rate (mrem/year) during the release.
Qm-wb    -        (X / Q) [Ii    Ki  0i]                                                (3.1-2a) and QM-s    =        (X / Q) [7i    (Li + l.iMi) Oil                                        (3.1-2b) where:
i      =        index over all nuclides K      =        the total body dose factor due to gamma emissions for noble gas radionuclide i (in mrem/yr per pCi/m3), from Table 3.2-3.
Li      The skin dose factor due to beta emissions for noble gas radionuclide i (mrem/yr per pCi/m 3), from Table 3.2-3 M      =        The air dose factor due to gamma emissions for noble gas radionuclide i (mrad/yr per pCi/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) 2.30E-05 sec/m3 (Site Boundary SW) from Table Al through A4, Appendix A 3-3
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                    March 2009 Offsite Dose Calculation Manual (ODCM)                                                                          Rev. 20 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 Sm., the maximum concentration setpoint in 1iCi/cc, and RRmax the maximum release rate setpoint in pCi/sec for the monitor.
Smax      =      (ft
* faiioc e nratio e YC ) + Bkg                                          (3.1-4a) and RRmax      =      Smrax    Fv  28316.852 /60                                                (3.1-4b) where fs        =      safety factor for the discharge point
                            =      0.5 faiioc    =      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 pCi/cc
                            =      0 for calculation of default setpoint.
3-4
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                  August 1994 Offsite Dose Calculation Manual (ODCM)                                                                              Rev. 5 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 liCi/cc and ptCi/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 Saiert, the gas channel alert alarm setpoint in p.Ci/cc, and RRaiert the gas channel alert alarm release rate setpoint in laCi/sec.
Saiert              =      [(Smax - Bkg) Af] + Bkg                                    (3.1-5a) and RRaiert            =      [(RRmnax - Bkgrr) Af] + Bkg,                              (3.1-5b) where:
Af                A value < 1.0 designed to alert the operator that the high alarm setpoint is being approached.
Bkgrr            Bkg e F,
* 28316.85 / 60 3-5
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                        Aug 2014 Offsite Dose Calculation Manual (ODCM)                                                                              Rev. 25 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 (Qj) in p.Ci, and the activity release rate &#xfd;i in tiCi/sec for each nuclide "i". &#xfd;i is the average release rate of nuclide "i"in gaseous effluent from discharge point "v", in piCi/sec. Noble gases may be averaged over a period of 1 hour.
Qi        =        Ci e Fv
* duration 9 28316.85                                              (3.2-1a) and
                              =        Ci Fv    28316.85 / 60                                                    (3.2-1b) where:
C          =        concentration of nuclide, in pCi/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 (IjCi/cc from analysis of WGDT)(6.45 E-05) +
(pCi/cc from analysis/GALE Code of Vent Stack 5)(0.9999)
Containment Normal Pur-ge (Batch)
(pCi/cc from analysis of Containment)(3.60 E-03) +
(pCi/cc from analysis/GALE Code of PV Stack 1)(0.9964)
Containment Preentry Purge (Batch)
(pCi/cc from analysis of Containment)(8.19 E-02) +
(pCi/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 acfrn + 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) 3-6
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                      May 2011 Offsite Dose Calculation Manual (ODCM)                                                                            Rev. 23 3.1.2    Monitor Setpoints Using Sample Results (continued)
F        =      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.
2.26E + 06 ( APc) (273')
14.7      Tc t
for a containment pressure release APt      2730 600 ( -            - )
14.7      Tt t
for a Waste Gas Decay Tank release where:
2.26E+06 and 600 are the volumes in ft3 of the containment and decay tank, respectively, and Tc, Tt, APc, and APt 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 APc,APt                        change in pressure (psig) following the release of the containment or decay tank 273'K              =          0oC
                                                      =          2731K + C&deg; duration          =      duration of release, in minutes 3
28316.85            =    conversion factor for cc/ft 3-7
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                  Aug 2014 Offsite Dose Calculation Manual (ODCM)                                                                          Rev. 25 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            (/.. Q)[I~iKi~1  I                                                          (3.2-2a) and QM-s        -    (XQ)[Yi(L1 +1.IM d)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 VCi/m3), from Table 3.2-3.
L        =      The skin dose factor due to beta emissions for noble gas radionuclide i (mrem/yr per ACi/m 3 ), from Table 3.2-3 M        =      The air dose factor due to gamma emissions for noble gas radionuclide i (mrad/yr per 1iCi/m 3). 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) 2.30E-05 sec/Im 3 (Site Boundary SW) from Table Al through A4, Appendix A 3-8
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                    March 2009 Offsite Dose Calculation Manual (ODCM)                                                                            Rev. 20 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 pCi/cc, and RRmax the maximum release rate setpoint in [tCi/sec for the monitor.
Smax      =        (fs 9 fa.,oc
* nratio e*.Ci  ) + Bkg                                      (3.2-4a) and RRmax              Smax e Fv      28316.85 / 60                                              (3.2-4b) where:
fs        =        safety factor for the discharge point
                            =        0.5 faiioc    =        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 pCi/cc
                            =        measured background at time of release or 0.
3-9
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                  August 1994 Offsite Dose Calculation Manual (ODCM)                                                                            Rev. 5 3.1.2    Monitor Setpoints Using Sample Results (continued)
: 5.      Determine Salert, the gas channel alert alarm setpoint in pCi/cc, and RRaiett the gas channel alert alarm release rate setpoint in pCi/sec.
Salert  -          [(Smax - Bkg) Af] + Bkg                                                    (3.2-5a) and RRaiert  =          [(RRmax - Bkg,) Af] + Bkgr                                                  (3.2-5b) where:
Af                  A value < 1.0 designed to alert the operator that the high alarm setpoint is being approached.
Bkgrr              Bkg
* F, e 28316.85 / 60 3-10
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                  August 1994 Offsite Dose Calculation Manual (ODCM)                                                                            Rev. 5 3.1.3    Effluent Monitoring During Hoggingq 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.
3-11
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                                                                                      May 2011 Offsite Dose Calculation'Manual (ODCM)                                                                                                                                          Rev. 23 Table 3.1-1 GASEOUS SOURCE TERMS(a'b)
Condenser Plant Vent                Vacuum Pump                    WPB                      WPB                  Containment Ventilation                  Ventilation              Ventilation              Ventilation                Purge or                WGDT Flow                        Flow                      Flow                  Flow W              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      (pCi/cc)          MiX      (uCi/c)          Miix    uCi/cc)        Mi.x    li/cc)          Miix    (Ci/cc)            Mix      (            mix MCi/cc)
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.
(b)      (uCi/cc) = (Ci/vr )(yr/5.256E5min) (1 E6uCi/Ci) (ft3/28320cc)
(Flow Rate __        ft3/min)' 5' (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 3-12
 
Shearon Harris Nuclear Power Plant (SHNPP)            August 2014 Offsite Dose Calculation Manual (ODCM)                    Rev. 25 TABLE 3.1-2 Deleted 3-13
 
Shearon Harris Nuclear Power Plant (SHNPP)                                  March 2009 Offsite Dose Calculation Manual (ODCM)                                          Rev. 20 TABLE 3.1-3 GASEOUS MONITOR PARAMETERS I__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
[fall..]
3-14
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                March 2009 Offsite Dose Calculation Manual (ODCM)                                                                          Rev. 20 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/yearto the skin. Based upon NUREG-0133, the following equations are used to show compliance:
          . Ki  (X / Qv                                *500 mrem/yr                                            (3.2-1) 1
          . (Li + l.liM)      (X /        Qi              3000mrem/yr                                          (3.2-2) 1 where:
(X/Q)"                      The highest calculated annual average relative concentration for Iong-term vent stack releases for areas at or beyond the exclusion boundary sec/min
                            =        2.30 E-05 sec/m 3 (Site Boundary SW) from Table Al through A4, Appendix A K          =        The total body dose factor due to gamma emissions for noble gas radionuclide "i," mrem/year per ipCi/m 3. Table 3.2-3.
Li                  The skin dose factor due to beta emissions for noble gas radionuclide I,"
mrem/year per &#xfd;.Ci/m 3 . Table 3.2-3.
M          =        The air dose factor due to gamma emissions for noble gas radionuclide "i,"
mrad/year per iPCi/m 3. Table 3.2-3.
3-15
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                    August 2014 Offsite Dose Calculation Manual (ODCM)                                                                              Rev. 25 3.2.1    Noble Gases (continued) 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).
Qv      =        The release rate of radionuclide 'T' in gaseous effluents from all plant vent stacks (gCi/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. Ifthe 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.
Release Rate (liCi/sec) = Flow (cc/sec)
* Concentration (gCi/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 2003 - 2007. 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 Al 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 K, 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.OE+06 to convert mrad/pCi to mrad/pCi for use in Equations 3.2-1 and 3.2-2.
3-16
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                    August 2014 Offsite Dose Calculation Manual (ODCM)                                                                              Rev. 25 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-01 33, the following is used to show compliance:
Pii  [(X / Q)v    Qiv]              1500 mrem / yr                                                  (3.2-3) where:
Pil      =        The dose parameter for radionuclides other than noble gases for the inhalation pathway, mrem/yr per pCi/m 3, 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 (pCi/sec) = Flow (cc/sec)
* Concentration (pCi/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 the inhalation pathway using the methodology of NUREG-0133. The Pi, values are presented in Table 3.2-
: 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.
3-17
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                May 2013 Offsite Dose Calculation Manual (ODCM)                                                                      Rev. 24 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.OE+01                3.OE+00                        0              2.OE+00  2.5E+01 Kr-88                0                0                        7.2E+01                6.OE+00                        0              3.OE+00  8.1E+01 Xe-1i31m                0            1.7E+01                      1.2E+02                2.OE+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.OE+00  7.5E+02 Xe-135m                0                0                        4.OE+00                3.OE+00                        0              1.OE+00  8.OE+00 Xe-135                0                0                        4.2E+02                  1.5E+01                        0              7.0E+00  4.4E+02 Xe-138                0                0                        3.OE+00                3.OE+00                        0              1.0E+00  7.OE+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.
3-18
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                            August 2014 Offsite Dose Calculation Manual (ODCM)                                                                      Rev. 25 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 laCi/m 3 )              pCi/m 3 )              PCi/m 3 )              pCi/m 3)
Ar-41                    8.840E+03                2.690E+03              9.300E+03              3.280E+03 Kr-83M                    7.560E-02              0.OOOE+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                    O.OOOE+O0                O.OOOE+O0              O.OOOE+00              O.OOOE+O0 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.
3-19
 
Shearon Harris Nuclear Power Plant (SHNPP)                                              August 2014 Offsite Dose Calculation Manual (ODCM)                                                      Rev. 25 TABLE 3.2-4 Pi, VALUES (INHALATION) FOR A CHILD Nuclide        Bone          Liver          Total Body    Thyroid  Kidney    Lung      Gi-LLi H-3            O.OOE+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.OOE+00  O.OOE+00  O.OOE+00  4.21E+04 Cr-51          0.OOE+00      0.OOE+00      1.54E+02      8.53E+01  2.43E+01  1.70E+04  1.08E+03 Mn-54          0.OOE+00      4.29E+04      9.50E+03      0.OOE+00  1.00E+04  1.57E+06  2.29E+04 Fe-59          2.07E+04      3.34E+04      1.67E+04      0.OOE+00  0,00E+00  1.27E+06  7.06E+04 Co-58          0.OOE+00      1.77E+03      3.16E+03      O.OOE+00  0.OOE+00  1.10E+06  3.43E+04 Co-60          0.OOE+00      1.31E+04      2.26E+04      0.OOE+00  0.OOE+00  7.06E+06  9.61E+04 Zn-65          4.25E+04      1.13E+05      7.02E+04      0.OOE+00  7.13E+04  9.94E+05  1.63E+04 Rb-86          0.OOE+00      1.98E+05      1.14E+05      O.OOE+00  0.OOE+00  0.OOE+00  7.98E+03 Rb-88          0.OOE+00      8.36E+02      5.45E+02      0.OOE+00  0.OOE+00  0.OOE+00  2.56E+01 Rb-89          0.OOE+00      5.13E+02      4.31E+02      0.OOE+00  O.OOE+00  0.OOE+00  2.81E+00 Sr-89          5.99E+05      0.OOE+00      1.72E+04      0.OOE+00  0.OOE+00  2.15E+06  1.67E+05 Sr-90          1.01E+08      0.OOE+00      6.43E+06      0.OOE+00  0.OOE+00  1.47E+07  3.43E+05 Y-91          9.13E+05      O.OOE+00      2.43E+04      0.OOE+00  0.OOE+00  2.62E+06  1.84E+05 Zr-95          1.90E+05      4.17E+04      3.69E+04      0.OOE+00  5.95E+04  2.23E+06  6.10E+04 Zr-97          2.79E+02      4.04E+01      2.38E+01      O.OOE+00  5.78E+01  1.68E+05  5.22E+05 Nb-95          2.35E+04      9.16E+03      6.54E+03      0.OOE+00  8.61E+03  6.13E+05  3.69E+04 Nb-97          6.38E-01      1.14E-01      5.36E-02      0.OOE+00  1.27E-01 5.08E+03  4.14E+04 Mo-99          0.OOE+00      2.56E+02      6.33E+01      0.OOE+00  5.83E+02  2.01E+05  1.88E+05 Tc-99M        2.65E-03      5.18E-03      8.58E-02      0.OOE+00  7.54E-02  1.41E+03  7.15E+03 Ru-103        2.79E+03      0.OOE+00      1.07E+03      0.OOE+00  7.02E+03  6.61E+05  4.47E+04 Ru-106        1.36E+05      0.OOE+00      1.69E+04      0.OOE+00  1.84E+05 1.43E+07  4.29E+05 Ag-110M        1.68E+04      1.14E+04      9.13E+03      0.OOE+00  2.12E+04  5.47E+06  1.OOE+05 Sn-113        9.OOE+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.OOE+04      1.26E+02  0.OOE+00  3.24E+06  1.64E+05 Sb-125        9.84E+04      7.59E+02      2.07E+04      9.10E+01  0.OOE+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.OOE+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 1-131          4.80E+04      4.80E+04      2.72E+04      1.62E+07  7.87E+04  0.OOE+00  2.84E+03 1-132          2.11E+03      4.06E+03      1.87E+03      1.93E+05  6.24E+03  0.OOE+00  3.20E+03 1-133          1.66E+04      2.03E+04      7.68E+03      3.84E+06  3.37E+04  0.OOE+00  5.47E+03 1-134          1.74E+03      3.21E+03      1.48E+03      7.54E+04  4.91E+03  0.00E+00  1.42E+03 1-135          4.91E+03      8.72E+03      4.14E+03      7.91E+05  1.34E+04 0.OOE+00  4.43E+03 Cs-134        6.50E+05      1.01E+06      2.24E+05      0.OOE+00  3.30E+05  1.21E+05  3.84E+03 Cs-136        6.S0E+04      1.71E+05      1.16E+05      O.OOE+00  9.53E+04  1.45E+04  4.17E+03 Cs-137        9.05E+05      8.24E+05      1.28E+05      O.OOE+00  2.82E+05 1.04E+05  3.61E+03 Ba-140        7.39E+04      6.47E+01      4.32E+03      0.OOE+00  2.11E+01 1.74E+06  1.02E+05 Ce-141        3.92E+04      1.95E+04      2189E+03      O0OOE+00  8.53E+03  5.43E+05  5.65E+04 Ce-144        6.76E+06      2.11E+06      3.61E+05      0.OOE+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.OOE+00  1.45E+02 8.64E+04  9.52E+04 3-20
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                      May 2011 Offsite Dose Calculation Manual (ODCM)                                                                            Rev. 23 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.
3-21
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                  May 2013 Offsite Dose Calculation Manual (ODCM)                                                                          Rev. 24 3.3.1    Noble Gases
: 1.      Cumulation of Doses Based upon NUREG-01 33, 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 1
Mi [(X / Q),      Qiv  + (X /q),    4j]                        (3.3-1)
Do                3.17 E -    08    Ni [ (X / Q)v    Qiv    + (X/ q)v      jv ]                      (3.3-2) where:
DY      =      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 .
i      =      The air dose factor due to gamma emissions for each identified noble gas radionuclide (mrad/yr/pCi/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,"
mradlyear per PCi/m 3 . Table 3.2-3.
X/Q"            The relative concentration for areas at or beyond the exclusion boundary for long-term ground-level vent stack releases (> 500 hours/year), sec/m 3. See Section 3.0 concerning ground-level releases at Shearon Harris Nuclear Plant or use 2.30E-05 sec/m3 from Table Al through A4, Appendix A as the most limiting X/Qv.
X/q,            The relative concentration for areas at or beyond the exclusion boundary for short-term ground-level vent stack releases (_<500 hours/year), sec/m 3 . See Section 3.0 concerning ground-level releases at Shearon Harris Nuclear Plant or use 2.30E-05 sec/m 3 from Table Al through A4, Appendix A as the most limiting X/Q,.
QQi            The total release of noble gas radionuclide "i" in gaseous effluents for long term releases v
(>500 hrs/yr) from all vent stacks (pCi).
q lv            The total release of radionuclide "i" in gaseous releases for short-term releases (s500 hours/year) from all vent stacks, (pCi).
3-22
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                  March 2009 Offsite Dose Calculation Manual (ODCM)                                                                          Rev. 20 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/4Ci.
The following relationships should hold for SHNPP to show compliance with ODCM Operational Requirement 3.11.2.2.
For the calendar quarter:
Dx < 5 mrad                                                                                              (3.3-3)
Dp:_ 10 mrad                                                                                            (3.3-4)
For the calendar year:
D,:<10 mrad                                                                                              (3.3-5)
D*:5 20 mrad                                                                                            (3.3-6)
The quarterly limits given above represent one-half of the annual design objectives of Section ll.B.1 of Appendix I of 1 OCFR50. 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.
3-23
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                  March 2009 Offsite Dose Calculation Manual (ODCM)                                                                            Rev. 20 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; q= Activity of nuclide "i' released (jiCi).
C= Concentration of radionuclide "i" (pCi/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 (vCi) for nuclide "i"for Waste Gas Decay Tank effluent accountability is calculated as follows; (C. AP .600.28316.85.273) qi        =                                                                          (3.3-7a)
(14.7o283)
Where; q        =        Activity of nuclide 'i" released (pCi).
C        =        Concentration of nuclide "i" (pCi/cc).
APt      =        Change in pressure (psia) of the WGDT (psia = psig + 14.7) 3-24
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                    March 2009 Offsite Dose Calculation Manual (ODCM)                                                                            Rev. 20 3.3.1    Noble Gases (continued) 600                WGDT volume, (ft 3).
28316.85      =        Conversion factor for converting from ft3 to cc.
273      =        Standard Temperature for 0&deg;C (oK).
14.7    =        Sample pressure at time of measurement, (psia).
283      =        WGDT Temperature, Ok (see Note below)
NOTE:              The FSAR assumes WGDT temperature to be in the 50-140 IF range.
Since there is no indicator for the actual WGDT temperature, 50&deg;F (10&deg;C) is conservatively assumed as an acceptable substitute.
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. The volume to use is 2.26E+06 ft 3 .
Continuous Releases Each of the four effluent stacks at the HNP have noble gas monitors. Using the net concentration (pCi/cc) from these monitors times the volume released (determined from the flow monitors) the total activity (p.Ci) of noble gases released are calculated as follows:
Q,      =        C,
* V)                                                              (3.3-8)
Where; Qx =    Total activity (gCi) released from Stack 'x'.
Cx =    Net concentration (pCi/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.
3-25
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                    August 1995 Offsite Dose Calculation Manual (ODCM)                                                                              Rev. 6 3.3.1    Noble Gases (continued)
The activity (ltCi) released for radionuclide "i" equals the radionuclide "i"fraction of the radionuclide mix times the total activity released from Stack 'x'.
Q = Q.
* Si                                                                            (3.3-8a)
Where; C1 Si                                                                                      (3.3-8b)
Zc and; Si =      The radionuclide "i" fraction of the radionuclide mix Ci =      The concentration of nuclide "i" in the grab sample (gCi/cc).
XCi =    Total activity in grab sample (&#xfd;tCi/cc).
The radionuclide mix is based on the sampling and analysis required by ODCM Operational Requirement 4.11.2.2.1. Ifthe grab sample activity is < LLD, then a mix based on historical data or a mix based on the Xe-1 33 / 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.
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; Q. = Q - qi                                                                              (3.3-9)
Where; Q=        Total corrected activity of nuclide "i"(gCi) 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.
3-26
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                  August 2014 Offsite Dose Calculation Manual (ODCM)                                                                          Rev. 25 3.3.1    Noble Gases (continued)
: 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&#xfd; = (Dr -S p) + Da,                                                                        (3.3-10) where:
Dp,      =        the 31 Day Projected Dose by organ r 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 r.
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.
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:
Dy < 0.2 mrad to air for gamma radiation                                            (3.3-11) and Dp _<0.4 mrad to air for beta radiation                                            (3.3-12)
Ifthe 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.
3-27
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                    March 2009 Offsite Dose Calculation Manual (ODCM)                                                                            Rev. 20 3.3.2    Radioiodine and Particulates
: 1.      Cumulation of Doses Section 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  '    (Rii) [(X/QX      Qiv+  (X/q)v qiv ] +
(RIM    +  R.V  +  RiG    +  RiB) [(D/Q)v    Q iv+  (D/q)v    qiv] +
(RTM +          + RT      + RTB)  [(X/Q)V    TV + (X/q)v      Tv]
where:
D                  -        Dose to any organ T from tritium, radioiodines, and particulates, mrem.
(D/Q                          The highest long-term (> 500 hr/yr) annual average relative deposition:
1.00 E-08 m2 for the food and ground plane pathways at the controlling location which is the exclusion boundary in the SSW sector (from Table Al through A4, Appendix A, for ground-level vent stack releases).
(D/q )v                      The relative deposition factor for short term, ground-level vent releases
(_<500 hrs/yr), m2 . See Section 3.0 concerning ground-level releases at Shearon Harris Nuclear Plant if using "real" meteorology or use 1.00 E-08 m,2 from Table Al through A4, Appendix A, for the food and ground plane pathways at the controlling location.
Ri                  =        Dose factor for an organ for radionuclide "i"for either the cow milk or goat milk pathway, mrem/yr per pCi/sec per m2.
3-28
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                    March 2009 Offsite Dose Calculation Manual (ODCM)                                                                            Rev. 20 3.3.2    Radioiodine and Particulates (continued)
R.                  =        Dose factor for an organ for radionuclide "i"for the ground plane exposure pathway, mrem/yr per [tCi/sec per M2.
R.II                          Dose factor for an organ for radionuclide "i"for the inhalation pathway, mrem/yr per P.Ci/m 3 .
R.iv Dose factor for an organ for radionuclide "i" for the vegetable pathway,
                                                                            -2 mrem/yr per iCi/sec per m2.
R.IB                =        Dose factor for an organ for radionuclide "i" for the meat pathway, mrem/yr per p.Ci/sec per  m2.
RTM                          Dose factor for an organ for tritium for the milk pathway mrem/yr per iCi/m3 .
RTv                          Dose factor for an organ for tritium for the vegetable pathway, mrem/yr per pCi/m 3.
RTi                          Dose factor for an organ for tritium for the inhalation pathway, mrem/yr per pCi/m 3 .
RTTB                          Dose factor for an organ for tritium for the meat pathway, mrem/yr per pCi/m 3.
Q Tv                        Release of tritium in gaseous effluents for long-term vent stack releases
(> 500 hrs/yr), p.Ci.
q Tv                        Release of tritium in gaseous effluents for short-term vent stack releases (_*500 hrs/yr), pCi.
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/Qvand the SSW sector has 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).
3-29
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                      Sept 2010 Offsite Dose Calculation Manual (ODCM)                                                                            Rev. 22 3.3.2    Radioiodine and Particulates (continued)
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.
3-30
 
Shearon    Harris Nuclear      Power Plant (SHNPP)                                                          Aug 2014 Offsite    Dose Calculation        Manual (ODCM)                                                              Rev. 25 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:
D0,*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.
: 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 = (Dr
* p) + Dar                                                                            (3.3-16) where:
O        =      the 31 Day Projected Dose by organ -r 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 Cand 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.
3-31
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                          August 1995 Offsite Dose Calculation Manual (ODCM)                                                                      Rev. 6 3.3.2  Radioiodine and Particulates (continued)
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.
3-32
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                  May 2013 Offsite Dose Calculation Manual (ODCM)                                                                      Rev. 24 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 0-17 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 (C02) 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 C02 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 annual release time (for C-14 atmospheric releases) to the total annual time which photosynthesis occurs (taken to be 4400 hours).
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, 3-33
 
Shearon  Harris Nuclear      Power Plant (SHNPP)                                                          May 2011 Offsite  Dose Calculation      Manual (ODCM)                                                                Rev. 23 3.3.2  Carbon 14 (continue)
: 1.      Annual Dose from Inhalation of Carbon-14 in Air The annual average airborne concentration of C-14 at the location with respect to the release point may be determined as:
X, = 3.17 x 104 Q, (Q)                                                                      (3.3-18) 3 Xc        =      the annual average ground-level concentration of C-14 in air, in pCi/m 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/m 3 for ground level release with no decay, Table Al through A4, Appendix A 3.17 X 104              is the number of pCilCi divided by the number of sec/yr The annual dose associated with inhalation for C-14, to organ () to an age group (a), is then:
DjA = (Uai)( DFAja)(Xc)                                                                      (3.3-20)
Dja      =      the annual dose from inhalation to an organ  U) of an age group (a) from C-14 in mrem/yr 3
X        =      the annual average ground-level concentration of C-14 in air, in pCi/m U.        =      Inhalation rate for age group (a), Table 3.3-20, in m 3/yr DFAja    =        Dose factor for an organ from carbon-14 for the inhalation pathway to an organ () of an age group (a), mrem/pCi Table 3.3-21 3-34
 
Shearon    Harris Nuclear    Power Plant (SHNPP)                                                          May 2013 Offsite    Dose Calculation    Manual (ODCM)                                                              Rev. 24 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:
Cr4 = (3.17 X 107 )(p)(Q14 )(      (0.1(                                                  (3.3-21)
CV 4      =      The concentration of C-14 in vegetation in pCi/kg p          =      the fractional equilibrium fraction, dimensionless
                            =      (0.70)(WGDT Release Hr per year/4400) + (0.30)(Continuous Release Hrs/4400)
Q14        =      annual release rate of C-14 from a PWR, assume 30% of annual C-14 release rate in lieu of site specific data, in Ci/yr
                            =      0. 3 0 x Qc X/Q        =      annual average atmosphere dispersion factor, in sec/m 3 for ground level release with no decay, Table Al 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 3
0.16      =      concentration of natural carbon in the atmosphere, in g/m
: 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.
CI = (Fm)(Cr4)(Qf)                                                                          (3.3-22)
CM        =      The concentration of C-14 in milk, pCi/L Fm        =      average fraction of the animal's 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 c          =      The concentration of C-14 in animal's 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 3-35
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                    May 2011 Offsite Dose Calculation Manual (ODCM)                                                                          Rev. 23 3.3.2  Carbon 14 (continue)
: 4.      Concentration of Airborne Carbon-14 in Meat CIN = (FF)(C1V)(Qf)                                                                              (3.3-23)
                          =        The concentration of C-14 in meat, pCi/kg FF        =        average fraction of the animal's daily intake of C-14 that appears in each kilogram of flesh, in days/kg
                          =        0.031 cv        =        The concentration of C-14 in animal's 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.      Annual Dose from Atmospherically Released Carbon-14 in Foods Dj.= DF/j [ Ua fg CY 4 + U.M CiN4 + UNBC 1B, + UcL  f, 'i4 ]                                (3.3-24)
D          =        the annual dose to organ (j) of an individual in age group (a) from the dietary intake of atmospherically released Carbon-14, in mrem/yr DFIja                the dose conversion factor for the ingestion of Carbon-14, organ (j), and age group (a), in mrem/pCi Table 3.3-22 Uv        =        ingestion rate of produce (non-leafy vegetables, fruit, grains), in kg/yr, Table 3.3-20
                          =        ingestion rate of milk, in I/yr, Table 3.3-20 U          =        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 f          =        fraction of produce ingested grow in the garden of interest
                          =        0.76, in lieu of site specific data f          =        fraction of leafy vegetables in the garden of interest
                          =          1.0, in lieu of site specific data Cv        =        The concentration of C-14 in vegetation, in pCi/kg C          =        The concentration of C-14 in milk, pCi/kg 4      =        The concentration of C-14 in meat, pCi/kg 3-36
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                              August 2014 Offsite Dose Calculation Manual (ODCM)                                                                        Rev. 25 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
*R Values in units of mrem/yr per pCi/m3 for inhalation and tritium and in units of mrem/yr per pCi/sec per m2 for all others.
3-37
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                August 2014 Offsite Dose Calculation Manual (ODCM)                                                                        Rev. 25 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-l01M        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.OOE+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.OOE+07      2.OOE+07        2.OOE+07        2.OOE+07        2.OOE+07      2.OOE+07      2.OOE+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 1-130          7.88E+06      7.88E+06        7.88E+06        7.88E+06        7.88E+06      7.88E+06      7.88E+06 1-131          1.72E+07      1.72E+07        1.72E+07        1.72E+07      1.72E+07      1.72E+07      1.72E+07 1-132          1.24E+06      1.24E+06        1.24E+06        1.24E+06      1.24E+06      1.24E+06      1.24E+06 1-133          2.47E+06      2.47E+06        2.47E+06        2.47E+06      2.47E+06      2.47E+06      2.47E+06 1-134          6.38E+05      6.38E+05        6.38E+05        6.38E+05      6.38E+05      6.38E+05      6.38E+05 1-135          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
*R Values in units of mrem/yr per pCi/mr3 for inhalation and tritium and in units of mrem/yr per pCi/sec per m2 for all others.
3-38
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                              August 2014 Offsite Dose Calculation Manual (ODCM)                                                                        Rev. 25 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            O.OOE+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        O.OOE+00        O.OOE+00      O.OOE+00        1.72E+08 Cr-51          O.OOE+00      O.OOE+00        4.60E+04        2.75E+04        1.01E+04      6.10E+04      1.16E+07 Mn-54          O.OOE+00      3.05E+08        5.83E+07        O.OOE+00        9.09E+07      O.OOE+00      9.36E+08 Mn-56          O.OOE+00      3.98E+01        7.06E+00        O.OOE+00        5.05E+01      O.OOE+00      1.27E+03 Fe-55          2.OOE+08      1.38E+08        3.22E+07        O.OOE+00        O.OOE+00      7.70E+07      7.91E+07 Fe-59          1.24E+08      2.93E+08        1.12E+08        O.OOE+00        O.OOE+00      8.17E+07      9.75E+08 Co-57          O.OOE+00      1.13E+07        1.88E+07        O.OOE+00        O.OOE+00      O.OOE+00      2.86E+08 Co-58          O.OOE+00      2.99E+07        6.71E+07        O.OOE+00        O.OOE+00      O.OOE+00      6.07E+08 Co-60          O.OOE+00      1.66E+08        3.67E+08        O.OOE+00        O.OOE+00      O.OOE+00      3.12E+09 Ni-63          1.20E+10      8.31E+08        4.02E+08        O.OOE+00        O.OOE+00      O.OOE+00      1.73E+08 Ni-65          1.50E+02      1.95E+01        8.90E+00        O.OOE+00        O.OOE+00      O.OOE+00      4.95E+02 Cu-64          O.OOE+00      2.34E+04        1.10E+04        O.OOE+00        5.89E+04      O.OOE+00      1.99E+06 Zn-65          4.01E+08      1.28E+09        5.77E+08        O.OOE+00        8.54E+08      O.OOE+00      8.04E+08 Zn-69M        5.73E+04      1.38E+05        1.26E+04        O.OOE+00        8.32E+04      0.00E+00      8.39E+06 Zn-69          1.29E-05      2.47E-05        1.72E-06        O.OOE+00        1.61E-05      O.OOE+00      3.72E-06 Br-82          O.OOE+00      O.OOE+00        3.90E+06        O.OOE+00        O.OOE+00      O.OOE+00      4.47E+06 Br-83          O.OOE+00      O.OOE+00        7.57E+00        O.OOE+00        O.OOE+00      O.OOE+00      1.09E+01 Br-84          O.OOE+00      O.OOE+00        5.51E-11        O.OOE+00        O.OOE+00      O.OOE+00      4.32E-16 Rb-86          O.OOE+00      2.21E+08        1.03E+08        O.OOE+00        O.OOE+00      O.OOE+00      4.36E+07 Rb-88          O.OOE+00      6.73E-22        3.57E-22        O.OOE+00      O.OOE+00      O.OOE+00      9.30E-33 Rb-89          O.OOE+00      6.19E-26        4.35E-26        O.OOE+00      O.OOE+00      O.OOE+00      3.59E-39 Sr-89          1.00E+10      O.OOE+00        2.87E+08        O.OOE+00      O.OOE+00      O.OOE+00      1.60E+09 Sr-90          6.70E+11      O.OOE+00        1.64E+11        O.OOE+00      O.OOE+00      O.OOE+00      1.93E+10 Sr-91          7.70E+05      O.OOE+00        3.11E+04        O.OOE+00      O.OOE+00      O.OOE+00      3.67E+06 Sr-92          1.07E+03      O.OOE+00        4.64E+01        O.OOE+00      O.OOE+00      O.OOE+00      2.13E+04 Y-90          3.43E+04      O.OOE+00        9.19E+02        O.OOE+00      O.OOE+00      O.OOE+00      3.63E+08 Y-91M          1.20E-08      O.OOE+00        4.66E-10        O.OOE+00      O.OOE+00      O.OOE+00      3.53E-08 Y-91          5.01E+06      O.OOE+00        1.34E+05        O.OOE+00      O.OOE+00      O.OOE+00      2.76E+09 Y-92          2.25E+00      O.OOE+00        6.59E-02        O.OOE+00        O.OOE+00      O.OOE+00      3.95E+04 Y-93          4.29E+02      O.O0E+00        1.18E+01        O.OGE+00      0.00E+00      O.OOE+00      1.36E+07 Zr-95          1.16E+06      3.71E+05        2.51E+05        O.OOE+00      5.82E+05      O.OOE+00      1.17E+09 Zr-97          8.50E+02      1.72E+02        7.84E+01        O.OOE+00      2.59E+02      O.OOE+00      5.31E+07 Nb-95          1.40E+05      7.79E+04        4.19E+04        O.OOE+00      7.70E+04      O.OOE+00      4.73E+08 Nb-97          5.13E-06      1.30E-06        4.74E-07        O.OOE+00      1.51E-06      O.OOE+00      4.79E-03 Mo-99          O.OOE+00      1.59E+07        3.02E+06        O.OOE+00      3.60E+07      O.OOE+00      3.68E+07 Tc-99M        7.81E+00      2.21E+01        2.81E+02        O.OOE+00      3.35E+02      1.08E+01      1.31E+04
*R Values in units of mrem/yr per pCi/m3 for inhalation and tritium and in units of mrem/yr per pCi/sec per m2  for all others.
3-39
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                August 2014 Offsite Dose Calculation Manual (ODCM)                                                                            Rev. 25 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        O.OOE+00 Ru-103        4.74E+06        0.OOE+00          2.04E+06        0.OOE+00        1.81E+07      0.OOE+00        5.53E+08 Ru-105        1.34E+02      0.OOE+00          5.28E+01        0.OOE+00        1.73E+03      0.OOE+00        8.18E+04 Ru-106        1.94E+08      0.OOE+00          2.46E+07        0.OOE+00        3.75E+08      0.OOE+00        1.26E+10 Ag-IIOM        1.13E+07      1.05E+07          6.23E+06        0.OOE+00        2.06E+07      0.OOE+00        4.28E+09 Sn-113        1.44E+07      5.66E+05          1.36E+07        1.96E+05      4.09E+05      0.OOE+00        2.52E+08 Sb-124        1.01E+08      1.92E+06          4.02E+07        2.46E+05        0.OOE+00      7.90E+07        2.88E+09 Sb-125        1.34E+08      1.50E+06          3.20E+07        1.37E+05      0.OOE+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.OOE+00        4.83E+08 Te-127m        5.02E+08      1.80E+08          6.12E+07        1.28E+08      2.04E+09      0.OOE+00        1.68E+09 Te-127        1.46E+04      5.25E+03          3.16E+03        1.08E+04      5.95E+04      O.OOE+00        1.15E+06 Te-129M        2.98E+08      1.11E+08          4.71E+07        1.02E+08      1.24E+09      0.OOE+00        1.50E+09 Te-129        1.85E-03      6.96E-04          4.51E-04        1.42E-03      7.78E-03      0.OOE+00        1.40E-03 Te-131M        2.38E+06      1.16E+06          9.71E+05        1.84E+06      1.18E+07      0.OOE+00        1.16E+08 Te-131        3.24E-15      1.35E-15          1.02E-15        2.66E-15        1.42E-14      0.OOE+00        4.58E-16 Te-132        1.14E+07      7.36E+06          6.91E+06        8.13E+06        7.09E+07      0.OOE+00        3.48E+08 1-130          1.96E+05      5.78E+05          2.28E+05        4.90E+07        9.02E+05      0.OOE+00        4.98E+05 1-131          8.07E+07      1.15E+08          6.61E+07        3.78E+10        1.98E+08      O.OOE+00        3.04E+07 1-132          5.57E+01      1.49E+02          5.21E+01        5.21E+03      2.37E+02      0.OOE+00        2.80E+01 1-133          2.11E+06      3.67E+06          1.12E+06        5.39E+08        6.40E+06      O.OOE+00        3.30E+06 1-134          4.49E-05      1.22E-04          4.36E-05        2.11E-03        1.94E-04      0.OOE+00        1.06E-07 1-135          4.05E+04      1.06E+05          3.91E+04        7.OOE+06      1.70E+05      0.OOE+00        1.20E+05 Cs-134        4.54E+09      1.08E+10          8.83E+09        0.OOE+00      3.49E+09      1.16E+09        1.89E+08 Cs-136        4.19E+07      1.66E+08          1.19E+08        0.OOE+00      9.21E+07      1.26E+07        1.88E+07 Cs-137        6.63E+09      9.07E+09          5.94E+09        0.OOE+00        3.08E+09      1.02E+09        1.76E+08 Cs-138        8.62E-11      1.70E-10          8.43E-11        0.OOE+00        1.25E-10      1.24E-11        7.26E-16 Ba-139        6.87E-02      4.89E-05          2.01E-03        O.OOE+00        4.57E-05      2.78E-05        1.22E-01 Ba-140        1.28E+08      1.61E+05          8.40E+06        0.OOE+00        5.47E+04      9.22E+04        2.64E+08 Ba-141        2.49E-21      1.88E-24          8.40E-23        0.OOE+00      1.75E-24      1.07E-24        1.17E-30 La-140        5.06E+03      2.55E+03          6.73E+02        0.OOE+00      0.OOE+00      0.OOE+00        1.87E+08 La-142        4.89E-04      2.22E-04          5.54E-05        0.OOE+00        0.OOE+00      O.OOE+00        1.62E+00 Ce-141        1.93E+05      1.31E+05          1.48E+04        0.QOE+00        6.07E+04      0.OOE+00        4.99E+08 Ce-143        2.55E+03      1.89E+06          2.09E+02        0.OOE+00      8.30E+02      0.OOE+00        7.05E+07 Ce-144        3.15E+07      1.32E+07          1.69E+06        0.OOE+00      7.80E+06      0.OOE+00        1.06E+10 Pr-143        6.23E+04      2.50E+04          3.09E+03        0.OOE+00      1.44E+04      0.OOE+00        2.73E+08 Pr-144        6.43E-26      2.67E-26          3.27E-27        0.OOE+00      1.50E-26      0.OOE+00        9.24E-33 Nd-147        3.33E+04      3.85E+04          2.30E+03        0.OOE+00      2.25E+04      0.OOE+00        1.85E+08 Hf-181        9.51E+06      5.36E+04          1.07E+06        3.41E+04      4.48E+04      0.OOE+00        7.06E+08 W-187          9.69E+04      8.10E+04          2.83E+04        0.OOE+00      0.OOE+00      O.OOE+00        2.65E+07 Np-239        3.67E+03      3.61E+02          1.99E+02        0.OOE+00      1.13E+03      0.OOE+00        7.40E+07
*R Values in units of mrem/yr per liCi/m 3 for inhalation and tritium and in units of mrem/yr per p.Ci/sec per m-2 for all others.
3-40
 
Shearon Harris Nuclear        Power Plant (SHNPP)                                                        August 2014 offsite  Dose Calculation        Manual (ODCM)                                                                  Rev. 25 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          O.OOE+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        O.OOE+00      O.OOE+00      O.OOE+00        1.47E+08 Cr-51          O.OOE+00      O.OOE+00          6.11E+04        3.39E+04      1.34E+04      8.72E+04        1.03E+07 Mn-54        O.OOE+00      4.43E+08          8.79E+07        O.OOE+00      1.32E+08      O.OOE+00      9.09E+08 Mn-56        O.OOE+00      3.59E+01          6.38E+00        O.OOE+00      4.54E+01      O.OOE+00        2.36E+03 Fe-55        3.10E+08      2.20E+08          5.13E+07        O.OOE+00      O.OOE+00      1.40E+08      9.53E+07 Fe-59        1.77E+08      4.14E+08          1.60E+08        O.OOE+00      O.OOE+00      1.30E+08      9.78E+08 Co-57          O.OOE+00      1.72E+07          2.89E+07        O.OOE+00      O.OOE+00      O.OOE+00        3.21E+08 Co-58          O.OOE+00      4.25E+07          9.79E+07        O.OOE+00      O.OOE+00      O.OOE+00        5.85E+08 Co-60        O.OOE+00      2.47E+08          5.57E+08        O.OOE+00      O.OOE+00      O.OOE+00        3.22E+09 Ni-63        1.85E+10      1.31E+09          6.28E+08        O.OOE+00      O.OOE+00      O.OOE+00        2.08E+08 Ni-65        1.40E+02      1.79E+01          8.14E+00        O.OOE+00      O.OOE+00      O.OOE+00        9.68E+02 Cu-64        O.OOE+00      2.12E+04          9.95E+03        O.OOE+00      5.35E+04      O.OOE+00        1.64E+06 Zn-65        5.36E+08      1.86E+09          8.68E+08        O.OOE+00      1.19E+09      O.OOE+00        7.88E+08 Zn-69M        5.31E+04      1.25E+05          1.15E+04        O.OOE+00      7.61E+04      O.OOE+00        6.88E+06 Zn-69        1.21E-05      2.31E-05          1.61E-06        O.OOE+00      1.51E-05      O.OOE+00      4.25E-05 Br-82        O.OOE+00      O.OOE+00          3.44E+06        O.OOE+00      O.OOE+00      O.OOE+00        O.OOE+00 Br-83        O.OOE+00      O.OOE+00          7.10E+00        O.OOE+00      O.OOE+00      O.OOE+00        O.OOE+00 Br-84        O.OOE+00      O.OOE+00          5.01E-11        O.OOE+00      O.OOE+00      O.OOE+00        O.OOE+00 Rb-86        O.OOE+00      2.76E+08          1.30E+08        O.OOE+00      O.OOE+00      O.OOE+00        4.09E+07 Rb-88        O.OOE+00      6.22E-22          3.32E-22        O.OOE+00      O.OOE+00      O.OOE+00        5.33E-29 Rb-89        O.OOE+00      5.57E-26          3.94E-26        O.OOE+00      O.OOE+00      O.OOE+00        8.54E-35 Sr-89        1.52E+10      O.OOE+00          4.36E+08        O.OOE+00      O.OOE+00      O.OOE+00        1.81E+09 Sr-90        8.32E+11      O.OOE+00          2.05E+11        O.OOE+00      O.OOE+00      O.OOE+00        2.33E+10 Sr-91        7.19E+05      O.OOE+00          2.86E+04        O.OOE+00      O.OOE+00      O.OOE+00        3.26E+06 Sr-92        9.99E+02      O.OOE+00          4.26E+01        O.OOE+00      O.OOE+00      O.OOE+00        2.54E+04 Y-90          3.20E+04      O.OOE+00          8.63E+02        O.OOE+00      O.OOE+00      O.OOE+00        2.64E+08 Y-91M          1.12E-08      O.OOE+00          4.28E-10        O.OOE+00      O.OOE+00      O.OOE+00        5.29E-07 Y-91          7.68E+06      O.OOE+00          2.06E+05        O.OOE+00      O.OOE+00      O.OOE+00        3.15E+09 Y-92          2.12E+00      O.OOE+00          6.12E-02        O.OOE+00      O.OOE+00      O.OOE+00        5.81E+04 Y-93          4.02E+02      O.OOE+00          1.10E+01        O.OOE+00      O.OOE+00      O.OOE+00        1.23E+07 Zr-95          1.69E+06      5.35E+05          3.68E+05        O.OOE+00      7.86E+05      O.OOE+00        1.23E+09 Zr-97        7.87E+02      1.56E+02          7.17E+01        O.OOE+00      2.36E+02      O.OOE+00        4.22E+07 Nb-95          1.89E+05      1.05E+05          5.77E+04        O.OOE+00      1.02E+05      O.OOE+00        4.48E+08 Nb-97        4.76E-06      1.18E-06          4.31E-07        O.OOE+00      1.38E-06      O.OOE+00        2.82E-02 Mo-99        O.OOE+00      1.46E+07          2.78E+06        O.OOE+00      3.34E+07      O.OOE+00        2.61E+07 Tc-99M        6.89E+00      1.92E+01          2.49E+02        O.OOE+00      2.86E+02      1.07E+01        1.26E+04
*R Values in units of mrem/yr per iiCi/m 3 for inhalation and tritium and in units of mrem/yr per piCi/sec per m-2 for all others.
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Shearon Harris Nuclear        Power Plant (SHNPP)                                                      August 2014 Offsite  Dose Calculation        Manual (ODCM)                                                                Rev. 25 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.OOE-30        1.97E-29        0.OOE+00      3.62E-29      1.22E-30      3.42E-37 Ru-103        6.78E+06      0.OOE+00        2.90E+06        0.OOE+00      2.39E+07      0.OOE+00      5.66E+08 Ru-105        1.24E+02      0.OOE+00        4.82E+01        0.OOE+00      1.57E+03      0.OOE+00      1.00E+05 Ru-106        3.12E+08      O.OOE+00        3.93E+07        0.OOE+00      6.02E+08      0.OOE+00      1.50E+10 Ag-110M        1.63E+07      1.54E+07        9.39E+06        0.OOE+00      2.95E+07      0.OOE+00      4.34E+09 Sn-113        1.91E+07      8.03E+05        2.02E+07        2.63E+05      5.65E+05      O.OOE+00      2.29E+08 Sb-124        1.51E+08      2.78E+06        5.89E+07        3.43E+05      O.OOE+00      1.32E+08      3.04E+09 Sb-125        2.11E+08      2.30E+06        4.92E+07        2.01E+05      O.OOE+00      1.85E+08      1.64E+09 Te-125M        1.86E+08      6.69E+07        2.48E+07        5.19E+07      O.OOE+00      O.OOE+00      5.48E+08 Te-127m        7.93E+08      2.81E+08        9.44E+07        1.89E+08      3.22E+09      0.OOE+00      1.98E+09 Te-127        1.38E+04      4.88E+03        2.96E+03        9.50E+03      5.58E+04      O.OOE+00      1.06E+06 Te-129M        4.29E+08      1.59E+08        6.79E+07        1.38E+08      1.77E+09      O.OOE+00      1.61E+09 Te-129        1.73E-03      6.46E-04        4.22E-04        1.24E-03      7.28E-03      O.OOE+00      9.48E-03 Te-131M        2.20E+06      1.06E+06        8.82E+05        1.59E+06      1.10E+07      0.OOE+00      8.48E+07 Te-131        3.01E-15      1.24E-15        9.40E-16        2.32E-15      1.32E-14      0.OOE+00      2.47E-16 Te-132        1.03E+07      6.55E+06        6.17E+06        6.91E+06      6.29E+07      O.OOE+00      2.08E+08 1-130          1.75E+05      5.07E+05        2.02E+05        4.13E+07      7.81E+05      O.OOE+00      3.90E+05 1-131          7.68E+07        1.07E+08        5.77E+07        3.14E+10      1.85E+08      0.OOE+00      2.13E+07 1-132          5.02E+01      1.31E+02        4.72E+01        4.43E+03      2.07E+02      0.OOE+00      5.72E+01 1-133          1.96E+06      3.32E+06        1.01E+06        4.64E+08      5.83E+06      0.OOE+00      2.51E+06 1-134          4.06E-05        1.08E-04        3.86E-05        1.79E-03      1.70E-04      O.OOE+00      1.42E-06 1-135          3.66E+04      9.42E+04        3.49E+04        6.06E+06      1.49E+05      0.OOE+00      1.04E+05 Cs-134        6.90E+09      1.62E+10        7.54E+09        0.OOE+00      5.16E+09      1.97E+09      2.02E+08 Cs-136        4.28E+07      1.68E+08        1.13E+08        0.OOE+00      9.16E+07      1.44E+07      1.35E+07 Cs-137          1.06E+10      1.41E+10        4.90E+09        0.OOE+00      4.78E+09      1.86E+09      2.OOE+08 Cs-138        7.95E-11        1.53E-10        7.63E-11        0.OOE+00      1.13E-10      1.31E-11      6.93E-14 Ba-139        6.46E-02      4.54E-05        1.88E-03        0.OOE+00      4.28E-05      3.13E-05      5.76E-01 Ba-140          1.38E+08      1.69E+05        8.88E+06        0.OOE+00      5.72E+04      1.14E+05      2.12E+08 Ba-141        2.33E-21      1.74E-24        7.77E-23        0.OOE+00      1.61E-24      1.19E-24      4.96E-27 La-140        4.62E+03      2.27E+03        6.04E+02        0.OOE+00      0.OOE+00      0.OOE+00      1.30E+08 La-142        4.49E-04      1.99E-04        4.97E-05        0.OOE+00      0.OOE+00      0.OOE+00      6.07E+00 Ce-141        2.77E+05      1.85E+05        2.12E+04        O.OOE+00      8.70E+04      0.OOE+00      5.29E+08 Ce-143        2.38E+03      1.73E+06        1.94E+02        0.OOE+00      7.78E+02      0.OOE+00      5.21E+07 Ce-144        5.04E+07      2.09E+07        2.71E+06        0.OOE+00      1.25E+07      0.OOE+00      1.27E+10 Pr-143        6.97E+04      2.78E+04        3.47E+03        O.OOE+00      1.62E+04      0.OOE+00      2.29E+08 Pr-144        6.02E-26      2.47E-26        3.05E-27        O.OOE+00      1.41E-26      O.OOE+00      6.64E-29 Nd-147        3.62E+04      3.94E+04        2.36E+03        O.OOE+00      2.31E+04      O.OOE+00      1.42E+08 Hf-181          1.38E+07      7.58E+04        1.54E+06        4.63E+04      6.32E+04      0.OOE+00      6.90E+08 W-187          9.02E+04      7.35E+04        2.58E+04        0.OOE+00      0.OOE+00      0.OOE+00      1.99E+07 Np-239        3.56E+03      3.36E+02        1.87E+02        0.OOE+00      1.05E+03      0.OOE+00      5.40E+07
*R Values in units of mrem/yr per gCi/m 3 for inhalation and tritium and in units of mrem/yr per pCi/sec per m2 for all others.
3-42
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                August 2014 Offsite Dose Calculation Manual (ODCM)                                                                          Rev. 25 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            O.OOE+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        O.OOE+00        O.OOE+00      O.OOE+00        1.01E+08 Cr-51          O.OOE+00      O.OOE+00        1.16E+05        6.44E+04        1.76E+04      1.18E+05        6.15E+06 Mn-54          O.OOE+00      6.49E+08        1.73E+08        O.OOE+00        1.82E+08      O.OOE+00        5.44E+08 Mn-56          O.OOE+00      4.70E+01        1.06E+01        O.OOE+00        5.68E+01      O.OOE+00        6.81E+03 Fe-55          7.63E+08      4.05E+08        1.25E+08        O.OOE+00        O.OOE+00      2.29E+08        7.50E+07 Fe-59          3.93E+08      6.36E+08        3.17E+08        O.OOE+00        O.OOE+00      1.84E+08        6.62E+08 Co-57          O.OOE+00      2.88E+07        5.83E+07        O.OOE+00        O.OOE+00      O.OOE+00        2.36E+08 Co-58          O.OOE+00      6.27E+07        1.92E+08        O.OOE+00        O.OOE+00      O.OOE+00        3.66E+08 Co-60          O.OOE+00      3.76E+08        1.11E+09        O.OOE+00        O.OOE+00      O.OOE+00        2.08E+09 Ni-63          4.55E+10      2.44E+09        1.55E+09        O.OOE+00        O.OOE+00      0.00E+00        1.64E+08 Ni-65          2.56E+02      2.41E+01        1.41E+01        O.OOE+00        O.OOE+00      O.OOE+00        2.96E+03 Cu-64          O.OOE+00      2.79E+04        1.69E+04        O.OOE+00        6.74E+04      O.OOE+00        1.31E+06 Zn-65          1.03E+09      2.74E+09        1.70E+09        O.OOE+00        1.73E+09      O.OOE+00        4.81E+08 Zn-69M        9.72E+04      1.66E+05        1.96E+04        O.OOE+00        9.63E+04      O.OOE+00        5.39E+06 Zn-69          2.23E-05      3.23E-05        2.98E-06        O.OOE+00        1.96E-05      O.OOE+00        2.04E-03 Br-82          O.OOE+00      O.OOE+00        5.29E+06        O.OOE+00        O.OOE+00      O.OOE+00        O.OOE+00 Br-83          O.OOE+00      O.OOE+00        1.31E+01        O.OOE+00        O.OOE+00      O.OOE+00        O.OOE+00 Br-84          O.OOE+00      O.OOE+00        8.50E-11        O.OOE+00        O.OOE+00      O.OOE+00        O.OOE+00 Rb-86          O.OOE+00      4.56E+08        2.81E+08        O.OOE+00        O.OOE+00      O.OOE+00        2.94E+07 Rb-88          0.00E+00      8.59E-22        5.97E-22        O.OOE+00        O.OOE+00      O.OOE+00        4.21E-23 Rb-89          0.00E+00      7.33E-26        6.52E-26        O.OOE+00        O.OOE+00      O.OOE+00        6.39E-28 Sr-89          3.62E+10      O.OOE+00        1.03E+09        O.OOE+00        O.OOE+00      O.OOE+00        1.40E+09 Sr-90          1.38E+12      O.OOE+00        3.49E+11        O.OOE+00        O.OOE+00      O.OOE+00        1.86E+10 Sr-91          1.32E+06      O.OOE+00        5.OOE+04        O.OOE+00        O.OOE+00      O.OOE+00        2.92E+06 Sr-92          1.83E+03      O.OOE+00        7.34E+01        O.OOE+00        O.OOE+00      O.OOE+00        3.47E+04 Y-90          5.95E+04      O.OOE+00        1.59E+03        O.OOE+00        O.OOE+00      O.OOE+00        1.69E+08 Y-91M          2.05E-08      O.OOE+00        7.48E-10        O.OOE+00        O.OOE+00      O.OOE+00        4.02E-05 Y-91          1.83E+07      0.00E+00        4.89E+05        O.OOE+00        O.OOE+00      O.OOE+00        2.44E+09 Y-92          3.90E+00      O.OOE+00        1.12E-01        O.OOE+00        O.OOE+00      O.OOE+00        1.13E+05 Y-93          7.41E+02      O.OOE+00        2.03E+01        O.OOE+00        O.OOE+00      O.OOE+00        1.10E+07 Zr-95          3.80E+06      8.35E+05        7.44E+05        O.OOE+00      1.20E+06      O.OOE+00        8.71E+08 Zr-97          1.44E+03      2.08E+02        1.23E+02        O.OOE+00      2.98E+02      O.OOE+00        3.15E+07 Nb-95          4.04E+05      1.57E+05        1.12E+05        O.OOE+00        1.48E+05      O.OOE+00        2,91E+08 Nb-97          8.67E-06      1.57E-06        7.31E-07        O.OOE+00      1.74E-06      O.OOE+00        4.83E-01 Mo-99          O.OOE+00      1.99E+07        4.92E+06        O.OOE+00        4.25E+07      O.OOE+00        1.65E+07 Tc-99M          1.19E+01      2.32E+01        3.85E+02        O.OOE+00      3.38E+02      1.18E+01        1.32E+04
*R Values in units of mrem/yr per 4iCi/m3 for inhalation and tritium and in units of mrem/yr per piCi/sec per m2  for all others.
3-43
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                              August 2014 Offsite Dose Calculation Manual (ODCM)                                                                          Rev. 25 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        O.OOE+00      4.62E-29      1.43E-30      8.62E-30 Ru-103        1.52E+07      0.OOE+00        5.86E+06        O.OOE+00      3.84E+07      O.OOE+00      3.94E+08 Ru-105        2.28E+02      O.OOE+00        8.26E+01        0.OOE+00      2.OOE+03      O.OOE+00      1.49E+05 Ru-106        7.52E+08      O.OOE+00        9.38E+07        O.OOE+00      1.02E+09      O.OOE+00      1.17E+10 Ag-lO0M        3.46E+07      2.34E+07        1.87E+07        0.OOE+00      4.35E+07      O.OOE+00      2.78E+09 Sn-113        3.64E+07      1.18E+06        3.97E+07        4.82E+05      8.09E+05      O.OOE+00      1.45E+08 Sb-124        3.44E+08      4.47E+06        1.21E+08        7.61E+05      O.OOE+00      1.91E+08      2.16E+09 Sb-125        4.91E+08      3.79E+06        1.03E+08        4.55E+05      O.OOE+00      2.74E+08      1.17E+09 Te-125M        4.39E+08      1.19E+08        5.85E+07        1.23E+08      O.OOE+00      O.OOE+00      4.24E+08 Te-127m        1.90E+09      5.12E+08        2.26E+08        4.55E+08      5.42E+09      O.OOE+00      1.54E+09 Te-127        2.54E+04      6.85E+03        5.45E+03        1.76E+04      7.23E+04      O.OOE+00      9.93E+05 Te-129M        9.98E+08      2.79E+08        1.55E+08        3.22E+08      2.93E+09      O.OOE+00      1.22E+09 Te-129        3.21E-03      8.96E-04        7.62E-04        2.29E-03      9.39E-03      O.OOE+00      2.OOE-01 Te-131M        4.03E+06      1.39E+06        1.48E+06        2.86E+06      1.35E+07      O.OOE+00      5.65E+07 Te-131        5.54E-15      1.69E-15        1.65E-15        4.24E-15      1.68E-14      O.OOE+00      2.91E-14 Te-132        1.85E+07      8.20E+06        9.91E+06        1.19E+07      7.62E+07      O.OOE+00      8.26E+07 1-130          3.08E+05      6.21E+05        3.20E+05        6.85E+07      9.29E+05      O.OOE+00      2.91E+05 1-131          1.43E+08      1.44E+08        8.16E+07        4.75E+10      2.36E+08      O.OOE+00      1.23E+07 1-132          8.91E+01      1.64E+02        7.53E+01        7.60E+03      2.51E+02      O.OOE+00      1.93E+02 1-133          3.57E+06      4.42E+06        1.67E+06        8.21E+08      7.36E+06      O.OOE+00      1.78E+06 1-134          7.21E-05      1.34E-04        6.16E-05        3.08E-03      2.05E-04      O.OOE+00      8.88E-05 1-135          6.50E+04      1.17E+05        5.54E+04        1.04E+07      1.79E+05      0.OOE+00      8.92E+04 Cs-134        1.56E+10      2.56E+10        5.40E+09        O.OOE+00      7.93E+09      2.84E+09      1.38E+08 Cs-136        8.04E+07      2.21E+08        1.43E+08        0.OOE+00      1.18E+08      1.76E+07      7.77E+06 Cs-137        2.49E+10      2.39E+10        3.52E+09        0.OOE+00      7.78E+09      2.80E+09      1.50E+08 Cs-138        1.45E-10      2.01E-10        1.27E-10        0.OOE+00      1.41E-10      1.52E-11      9.26E-11 Ba-139        1.19E-01      6.36E-05        3.45E-03        0.OOE+00      5.55E-05      3.74E-05      6.87E+00 Ba-140        2.76E+08      2.42E+05        1.61E+07        0.OOE+00      7.87E+04      1.44E+05      1.40E+08 Ba-141        4.29E-21      2.40E-24        1.40E-22        0.OOE+00      2.08E-24      1.41E-23      2.45E-21 La-140        8.30E+03      2.90E+03        9.78E+02        0.OOE+00      0.OOE+00      0.OOE+00      8.08E+07 La-142        8.14E-04      2.59E-04        8.12E-05        0.OOE+00      0.OOE+00      0.OOE+00      5.14E+01 Ce-141        6.42E+05      3.20E+05        4.75E+04        0.OOE+00      1.40E+05      0.OOE+00      3.99E+08 Ce-143        4.39E+03      2.38E+06        3.45E+02        0.OOE+00      9.98E+02      0.OOE+00      3.48E+07 Ce-144        1.22E+08      3.81E+07        6.49E+06        0.OOE+00      2.11E+07      0.OOE+00      9.94E+09 Pr-143        1.45E+05      4.35E+04        7.18E+03        0.OOE+00      2.35E+04      0.OOE+00      1.56E+08 Pr-144        1.12E-25      3.46E-26        5.63E-27        0.OOE+00      1.83E-26      0.OOE+00      7.45E-23 Nd-147        7.15E+04      5.79E+04        4.48E+03        0.OOE+00      3.18E+04      0.OOE+00      9.17E+07 Hf-181        3.13E+07      1.22E+05        3.15E+06        1.03E+05      9.78E+04      O.OOE+00      5.17E+08 W-187          1.64E+05      9.71E+04        4.36E+04        0.OOE+00      0.OOE+00      0.OOE+00      1.36E+07 Np-239        6.58E+03      4.72E+02        3.32E+02        0.OOE+00      1.37E+03      O.OOE+00      3.49E+07
*R Values in units of mrem/yr per pCi/m 3 for inhalation and tritium and in units of mrem/yr per pCi/sec per m-2 for all others.
3-44
 
Shearon Harris Nuclear        Power Plant (SHNPP)                                                        August 2014 Offsite  Dose Calculation        Manual (ODCM)                                                                Rev. 25 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            O.OOE+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        O.OOE+00      O.OOE+00      O.OOE+00        3.43E+08 Cr-51          O.OOE+00      O.OOE+00        4.27E+03        2.56E+03      9,42E+02      5.67E+03        1.08E+06 Mn-54          O.OOE+00      5.57E+06        1.06E+06        O.OOE+00      1.66E+06      O.OOE+00        1.71E+07 Fe-55          1.83E+08      1.26E+08        2.95E+07        O.OOE+00      O.OOE+00      7.05E+07        7.25E+07 Fe-59          1.59E+08      3.74E+08        1.43E+08        O.OOE+00      O.OOE+00      1.04E+08        1.25E+09 Co-57          O.OOE+00      3.48E+06        5.79E+06        O.OOE+00      O.OOE+00      O.OOE+00        8.84E+07 Co-58          O.OOE+00      1.08E+07        2.43E+07        O.OOE+00      O.OOE+00      O.OOE+00        2.20E+08 Co-60          O.OOE+00      4.66E+07        1.03E+08        O.OOE+00      O.OOE+00      O.OOE+00        8.76E+08 Ni-63          1.32E+10      9.13E+08        4.42E+08        O.OOE+00      O.OOE+00      O.OOE+00        1.91E+08 Zn-65          2.49E+08      7.91E+08        3.58E+08        O.OOE+00      5.29E+08      O.OOE+00        4.98E+08 Br-82          O.OOE+00      O.OOE+00        1.38E-32        O.OOE+00      O.OOE+00      O.OOE+00        1.58E-32 Rb-86          O.OOE+00      3.04E+08        1.42E+08        O.OOE+00      O.OOE+00      O.OOE+00        6.OOE+07 Sr-89          1.82E+08      O.OOE+00        5.23E+06        O.OOE+00      O.OOE+00      O.OOE+00        2.92E+07 Sr-90          8.22E+09      O.OOE+00        2.02E+09        O.OOE+00      O.OOE+00      O.OOE+00        2.38E+08 Y-90          1.06E-17      O.OOE+00        2.83E-19        O.OOE+00      O.OOE+00      O.OOE+00        1.12E-13 Y-91          6.75E+05      O.OOE+00        1.80E+04        O.OOE+00      O.OOE+00      O.OOE+00        3.71E+08 Zr-95          1.12E+06      3.59E+05        2.43E+05        O.OOE+00      5.64E+05      O.OOE+00        1.14E+09 Nb-95          1.38E+06      7.66E+05        4.12E+05        O.OOE+00      7.58E+05      O.OOE+00        4.65E+09 Nb-97          8.25E-08      2.09E-08        7.62E-09        O.OOE+00      2.43E-08      O.OOE+00        7.70E-05 Mo-99          O.OOE+00      4.67E-15        8.89E-16        O.OOE+00      1.06E-14      O.OOE+00        1.08E-14 Ru-103        6.32E+07      O.OOE+00        2.72E+07        O.OOE+00      2.41E+08      O.OOE+00        7.38E+09 Ru-106        1.73E+09      O.OOE+00        2.19E+08        O.OOE+00      3.35E+09      O.OOE+00        1.12E+11 Ag-110M        4.27E+06      3.95E+06        2.34E+06        O.OOE+00      7.76E+06      O.OOE+00        1.61E+09 Sn-113        2.97E+07      1.15E+06        2.80E+07        4.03E+05      8.40E+05      O.OOE+00        5.19E+08 Sb-124        1.19E+07      2.25E+05        4.72E+06        2.88E+04      O.OOE+00      9.27E+06        3.38E+08 Te-125M        2.43E+08      8.79E+07        3.25E+07        7.30E+07      9.87E+08      O.OOE+00        9.69E+08 Te-127m        8.22E+08      2.94E+08        1.OOE+08        2.10E+08      3.34E+09      O.OOE+00        2.76E+09 Te-129M        7.40E+08      2.76E+08        1.17E+08        2.54E+08      3.09E+09      O.OOE+00        3.73E+09 Te-132        4.41E-10      2.85E-10        2.68E-10        3.15E-10      2.75E-09      O.OOE+00        1.35E-08 1-131          7.04E+06      1.01E+07        5.77E+06        3.30E+09      1.73E+07      O.OOE+00        2.66E+06 1-133          2.85E-01      4.96E-01        1.51E-01        7.29E+01      8.66E-01      O.OOE+00        4.46E-01 1-135          6.28E-17      1.64E-16        6.07E-17        1.08E-14      2.64E-16      O.OOE+00        1.86E-16 Cs-134        4.01E+08      9.55E+08        7.81E+08        O.OOE+00      3.09E+08      1.03E+08        1.67E+07 Cs-136        7.53E+06      2.97E+07        2.14E+07        O.OOE+00      1.65E+07      2.27E+06        3.33E+06 Cs-137        5.57E+08      7.61E+08        4.99E+08        O.OOE+00      2.58E+08      8.59E+07        1.47E+07 Ba-140        1.83E+07      2.30E+04        1.20E+06        O.OOE+00      7.82E+03      1.32E+04        3.77E+07 La-140        7.57E-33      3.82E-33        1.01E-33        O.OOE+00      O.OOE+00      O.OOE+00        2.80E-28 Ce-141        8.42E+03      5.69E+03        6.46E+02        O.OOE+00      2.65E+03      O.OOE+00        2.18E+07 Ce-144        8.75E+05      3.66E+05        4.70E+04.        O.OOE+00      2.17E+05      O.OOE+00        2.96E+08 Pr-143        1.33E+04      5.34E+03        6.60E+02        O.OOE+00      3.08E+03      O.OOE+00        5.83E+07 Nd-147        4.57E+03      5.29E+03        3.16E+02        O.OOE+00      3.09E+03      O.OOE+00        2.54E+07 Hf-181        1.34E+07      7.57E+04        1.52E+06        4.81E+04      6.33E+04      O.OOE+00        9.97E+08 Np-239        5.63E-23      5.53E-24        3.05E-24        O.OOE+00      1.73E-23      O.OOE+00        1.14E-18
*R Values in units of mrem/yr per iCi/m 3 for inhalation and tritium and in units of mrem/yr per iiCi/sec per m 2 for all others.
3-45
 
Shearon  Harris Nuclear      Power Plant (SHNPP)                                                    August 2014 Offsite  Dose Calculation        Manual (ODCM)                                                              Rev. 25 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            O.OOE+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        O.OOE+00      O.OOE+00      O.OOE+00        2.16E+08 Cr-51          O.OOE+00      O.OOE+00      3.42E+03        1.90E+03      7.49E+02      4.88E+03        5.75E+05 Mn-54          O.OOE+00      4.25E+06      8.43E+05        O.OOE+00      1.27E+06      O.OOE+00        8.72E+06 Fe-55          1.49E+08      1.05E+08      2.46E+07        O.OOE+00      O.OOE+00      6.68E+07      4.56E+07 Fe-59          1.27E+08      2.97E+08      1.15E+08        O.OOE+00      O.OOE+00      9.36E+07        7.02E+08 Co-57          O.OOE+00      2.80E+06      4.69E+06        O.OOE+00      O.OOE+00      O.OOE+00      5.22E+07 Co-58          O.OOE+00      8.36E+06      1.93E+07        O.OOE+00      O.OOE+00      O.OOE+00      1.15E+08 Co-60          O.OOE+00      3.62E+07      8.15E+07        O.OOE+00      O.OOE+00      O.OOE+00      4.71E+08 Ni-63          1.06E+10      7.49E+08      3.59E+08        O.OOE+00      O.OOE+00      O.OOE+00      1.19E+08 Zn-65          1.75E+08      6.07E+08      2.83E+08        O.OOE+00      3.89E+08      O.OOE+00      2.57E+08 Br-82          O.OOE+00      O.OOE+00      1.10E-32        O.OOE+00      O.OOE+00      O.OOE+00      O.OOE+00 Rb-86          O.OOE+00      2.54E+08      1.19E+08        O.OOE+00      O.OOE+00      O.OOE+00      3.76E+07 Sr-89          1.54E+08      O.OOE+00      4.40E+06        O.OOE+00      O.OOE+00      O.OOE+00      1.83E+07 Sr-90          5.32E+09      O.OOE+00      1.31E+09        O.OOE+00      O.OOE+00      O.OOE+00      1.49E+08 Y-90          8.89E-18      O.OOE+00      2.39E-19        O.OOE+00      O.OOE+00      O.OOE+00      7.33E-14 Y-91          5.68E+05      O.OOE+00      1.52E+04        O.OOE+00      O.OOE+00      O.OOE+00      2.33E+08 Zr-95          8.97E+05      2.83E+05      1.95E+05        O.OOE+00      4.16E+05      O.OOE+00      6.53E+08 Nb-95          1.08E+06      5.97E+05      3.29E+05        O.OOE+00      5.79E+05      O.OOE+00      2.55E+09 Nb-97          6.83E-08      1.71E-08      6.24E-09        O.OOE+00      2.OOE-08      O.OOE+00      4.08E-04 Mo-99          O.OOE+00      3.86E-15      7.37E-16        O.OOE+00      8.84E-15      O.OOE+00      6.92E-15 Ru-103        5.15E+07      O.OOE+00      2.20E+07        O.OOE+00      1.82E+08      O.OOE+00      4.30E+09 Ru-106        1.46E+09      O.OOE+00      1.84E+08        O.OOE+00      2.81E+09      O.OOE+00      7.OOE+10 Ag-iOrM        3.23E+06      3.06E+06      1.86E+06        O.OOE+00      5.83E+06      O.OOE+00      8.59E+08 Sn-113        2.09E+07      8.80E+05      2.22E+07        2.88E+05      6.19E+05      O.OOE+00      2.51E+08 Sb-124        9.73E+06      1.79E+05      3.80E+06        2.21E+04      O.OOE+00      8.50E+06      1.96E+08 Te-125M        2.05E+08      7.39E+07      2.74E+07        5.73E+07      O.OOE+00      O.OOE+00      6.05E+08 Te-127m        6.94E+08      2.46E+08      8.25E+07        1.65E+08      2.81E+09      O.OOE+00      1.73E+09 Te-129M        6.20E+08      2.30E+08      9.81E+07        2.OOE+08      2.59E+09      O.OOE+00      2.33E+09 Te-132        3.61E-10      2.28E-10      2.15E-10        2.41E-10      2.19E-09      O.OOE+00      7.23E-09 1-131          5.85E+06      8.20E+06      4.40E+06        2.39E+09      1.41E+07      O.OOE+00      1.62E+06 1-133          2.39E-01      4.05E-01      1.23E-01        5.65E+01      7.10E-01      O.OOE+00      3.06E-01 1-135          5.11E-17      1.32E-16      4.88E-17        8.46E-15      2.08E-16      O.OOE+00      1.46E-16 Cs-134        3.19E+08      7.51E+08      3.48E+08        O.OOE+00      2.39E+08      9.11E+07      9.34E+06 Cs-136        5.87E+06      2.31E+07      1.55E+07        O.OOE+00      1.26E+07      1.98E+06      1.86E+06 Cs-137        4.62E+08      6.15E+08      2.14E+08        O.OOE+00      2.09E+08      8.13E+07      8.75E+06 Ba-140        1.51E+07      1.86E+04      9.76E+05        O.OOE+00      6.29E+03      1.25E+04      2.34E+07 La-140        6.23E-33      3.06E-33      8.14E-34        O.OOE+00      O.OOE+00      O.OOE+00      1.76E-28 Ce-141        7.07E+03      4.72E+03      5.42E+02        O.OOE+00      2.22E+03      O.OOE+00      1.35E+07 Ce-144        7.37E+05      3.05E+05      3.96E+04        O.OOE+00      1.82E+05      O.OOE+00      1.85E+08 Pr-143        1.12E+04      4.47E+03      5.58E+02        O.OOE+00      2.60E+03      O.OOE+00      3.69E+07 Nd-147        4.03E+03      4.38E+03      2.63E+02        O.OOE+00      2.57E+03      O.OOE+00      1.58E+07 Hf-181        1.10E+07      6.05E+04      1.22E+06        3.69E+04      5.04E+04      O.OOE+00      5.50E+08 Np-239        4.92E-23      4.64E-24      2.58E-24        O.00E+00      1.46E-23      O.OOE+00      7.46E-19
*R Values in units of mrem/yr per PCi/m 1    for inhalation and-tritium and in units of mrem/yr per pCi/sec per'm forall others.
3-46
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                              August 2014 Offsite Dose Calculation Manual (ODCM)                                                                        Rev. 25 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            O.OOE+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        O.OOE+00        O.OOE+00      O.OOE+00        1.34E+08 Cr-51          O.OOE+00      O.OOE+00      5.33E+03        2.96E+03        8.09E+02      5.40E+03      2.83E+05 Mn-54          O.OOE+00      4.86E+06      1.30E+06        O.OOE+00        1.36E+06      O.OOE+00      4.08E+06 Fe-55          2.85E+08      1.51E+08      4.69E+07        O.OOE+00        O.OOE+00      8.56E+07      2.80E+07 Fe-59          2.25E+08      3.65E+08      1.82E+08        O.OOE+00        O.OOE+00      1.06E+08      3.80E+08 Co-57          O0OOE+00      3.66E+06      7.41E+06        O.GQE+00        OOOE+00        O.OOE+00      3.OOE+07 Co-58          O.OOE+00      9.76E+06      2.99E+07        O.OOE+00        O.OOE+00      O.OOE+00      5.70E+07 Co-60          O.OOE+00      4.30E+07      1.27E+08        O.OOE+00        O.OOE+00      O.OOE+00      2.38E+08 Ni-63          2.03E+10      1.09E+09      6.91E+08        O.OOE+00        O.OOE+00      O.OOE+00      7.33E+07 Zn-65          2.62E+08      6.99E+08      4.35E+08        O.OOE+00        4.40E+08      O.OOE+00        1,23E+08 Br-82          O.OOE+00      O.OOE+00      1.72E-32        O.OOE+00        O.OOE+00      O.OOE+00      O.OOE+00 Rb-86          O.OOE+00      3.60E+08      2.21E+08        O.OOE+00        O.OOE+00      O.OOE+00      2.32E+07 Sr-89          2.91E+08      O.OOE+00      8.31E+06        O.OOE+00      O.OOE+00      O.OOE+00        1.13E+07 Sr-90          6.87E+09      O.OOE+00      1.74E+09        O.OOE+00      O.OOE+00      O.OOE+00      9.26E+07 Y-90          1.68E-17      O.OOE+00      4.50E-19        O.OOE+00      O.OOE+00      O.OOE+00      4.79E-14 Y-91          1.07E+06      O.OOE+00      2.87E+04        O.OOE+00      O.OOE+00      O.OOE+00        1.43E+08 Zr-95          1.59E+06      3.50E+05      3.12E+05        O.OOE+00      5.01E+05      O.OOE+00      3.65E+08 Nb-95          1.86E+06      7.23E+05      5.17E+05        O.OOE+00      6.80E+05      O.OOE+00        1.34E+09 Nb-97          1.28E-07      2.31E-08      1.08E-08        O.OOE+00      2.56E-08      O.OOE+00      7.13E-03 Mo-99          O.OOE+00      5.38E-15      1.33E-15        O.OOE+00      1.15E-14      O.OOE+00      4.45E-15 Ru-103        9.31E+07      O.OOE+00      3.58E+07        O.OOE+00      2.34E+08      O.OOE+00        2.41E+09 Ru-106        2.75E+09      O.OOE+00      3.43E+08        O.OOE+00      3.71E+09      O.OOE+00      4.27E+10 Ag-i1OM        5.36E+06      3.62E+06      2.89E+06        O.OOE+00      6.74E+06      O.OOE+00      4.30E+08 Sn-113        3.14E+07      1.01E+06      3.42E+07        4.15E+05      6.97E+05      O.OOE+00        1.25E+08 Sb-124        1.76E+07      2.28E+05      6.17E+06        3.88E+04      O.OOE+00      9.77E+06        1.10E+08 Te-125M        3.85E+08      1.04E+08      5.13E+07        1.08E+08      O.OOE+00      O.OOE+00      3.71E+08 Te-127m        1.31E+09      3.52E+08      1.55E+08        3.13E+08      3.73E+09      O.OOE+00        1.06E+09 Te-129M        1.17E+09      3.26E+08      1.81E+08        3.77E+08      3.43E+09      O.OOE+00        1.42E+09 Te-132        6.58E-10      2.91E-10      3.52E-10        4.24E-10      2.70E-09      O.OOE+00        2.93E-09 1-131          1.09E+07      1.09E+07      6.20E+06        3.61E+09      1.79E+07      O.OOE+00      9.72E+05 1-133          4.43E-01      5.48E-01      2.07E-01        1.02E+02      9.13E-01      0,00E+00        2.21E-01 1-135          9.25E-17      1.66E-16      7.87E-17        1.47E-14      2.55E-16      O.OOE+00        1.27E-16 Cs-134        5.63E+08      9.23E+08      1.95E+08        O.OOE+00      2.86E+08      1.03E+08      4.93E+06 Cs-136        1.01E+07      2.78E+07      1.80E+07        O.OOE+00      1.48E+07      2.21E+06        9.78E+05 Cs-137        8.51E+08      8.15E+08      1.20E+08        O.OOE+00      2.65E+08      9.55E+07        5.10E+06 Ba-140        2.80E+07      2.45E+04      1.63E+06        O.OOE+00      7.97E+03      1.46E+04        1.42E+07 La-140        1.14E-32      3.98E-33      1.34E-33        O.OOE+00      O.OOE+00      O.OOE+00        1.11E-28 Ce-141        1.33E+04      6.64E+03      9.86E+02        O.OOE+00      2.91E+03      O.OOE+00        8.28E+06 Ce-144        1.39E+06      4.36E+05      7.42E+04        O.OOE+00      2.41E+05      O.OOE+00        1.14E+08 Pr-143        2.12E+04      6.37E+03      1.05E+03        O.OOE+00      3.45E+03      O.OOE+00        2.29E+07 Nd-147        7.56E+03      6.12E+03      4.74E+02        O.OOE+00      3.36E+03      O.OOE+00        9.70E+06 Hf-181        2.OOE+07      7.79E+04      2.02E+06        6.56E+04      6.26E+04      O.OOE+00        3.31E+08 N -239        9.26E-23      6.65E-24      4.67E-24        O.OOE+00      1.92E-23      O.OOE+00        4.92E-19
*R Values in units of mrem/yr per TCi/m for inhalation and tritium and in units of mrem/yr per VLCi/sec per m- for all others.
3-47
 
Shearon Harris Nuclear        Power Plant (SHNPP)                                                      August 2014 Offsite  Dose Calculation      Manual (ODCM)                                                                Rev. 25 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              O.OOE+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        O.OOE+00      O.OOE+00      O.OOE+00      1.26E+09 Cr-51            O.OOE+00      O.OOE+00        1.73E+04          1.04E+04      3.82E+03      2.30E+04      4.36E+06 Mn-54            O.OOE+00      5.11E+06        9.76E+05          O.OOE+00      1.52E+06      O.OOE+00      1.57E+07 Fe-55            1.57E+07      1.08E+07        2.52E+06          O.OOE+00      O.OOE+00      6.04E+06      6.21E+06 Fe-59            1.77E+07      4.17E+07        1.60E+07        0.00E+00      O.OOE+00      1.17E+07      1.39E+08 Co-57            O.OOE+00      7.91E+05        1.32E+06          O.OOE+00      O.OOE+00      O.OOE+00      2.01E+07 Co-58            O.OOE+00      2.80E+06        6.28E+06          O.OOE+00      O.OOE+00      O.OOE+00      5.68E+07 Co-60            O.OOE+00      1.02E+07        2.24E+07          O.OOE+00      O.OOE+00      O.OOE+00      1.91E+08 Ni-63            4.70E+09      3.25E+08        1.57E+08          O.OOE+00      O.OOE+00      O.OOE+00      6.79E+07 Zn-65            9.59E+08      3.05E+09        1.38E+09          O.OOE+00      2.04E+09      O.OOE+00      1.92E+09 Br-82            O.OOE+00      O.OOE+00          2.09E-29        O.OOE+00      O.OOE+00      O.OOE+00      2.39E-29 Rb-86            O.OOE+00      1.62E+09        7.54E+08          O.OOE+00      O.OOE+00      O.OOE+00      3.19E+08 Sr-89            8.70E+08      O.OOE+00        2.50E+07          O.OOE+00      O.OOE+00      O.OOE+00      1.40E+08 Sr-90            3.09E+10      O.OOE+00        7.59E+09          O.OOE+00      O.OOE+00      O.OOE+00      8.94E+08 Y-90              1.44E-18    O.OOE+00          3.86E-20        O.00E+00      0.00E+00      0.OOE+00      1.53E-14 Y-91            5.11E+03      O.OOE+00        1.37E+02          O.OOE+00      O.OOE+00      O.OOE+00      2.81E+06 Zr-95            5.62E+02      1.80E+02        1.22E+02          O.OOE+00      2.83E+02      O.OOE+00      5.71E+05 Nb-95            4.95E+04      2.75E+04        1.48E+04          O.OOE+00      2.72E+04      O.OOE+00      1.67E+08 Nb-97            1.09E-08      2.75E-09        1.00E-09        O.OOE+00      3.21E-09      O.OOE+00      1.01E-05 Mo-99            O.OOE+00      1.83E-12        3.49E-13        O.OOE+00      4.15E-12      O.OOE+00      4.25E-12 Ru-103          6.11E+02      O.OOE+00        2.63E+02          O.OOE+00      2.33E+03      O.OOE+00      7.14E+04 Ru-106          1.26E+04      O.OOE+00        1.60E+03          O.OOE+00      2.44E+04      O.OOE+00      8.17E+05 Ag-110M          3.71E+07      3.44E+07        2.04E+07          O.OOE+00      6.76E+07      O.OOE+00      1.40E+10 5n-113          1.40E+06      5.41E+04        1.32E+06          1.90E+04      3.95E+04      O.OOE+00      2.44E+07 Sb-124          1.55E+07      2.92E+05        6.14E+06          3.75E+04      O.OOE+OO      1.20E+07      4.39E+08 Sb-125          1.30E+07      1.45E+05        3.09E+06          1.32E+04      O.OOE+O0      1.00E+07      1.43E+08 Te-125M          1.10E+07      3.99E+06        1.48E+06          3.31E+06      4.48E+07      O.OOE+O0      4.40E+07 Te-127m          3.37E+07      1.21E+07        4.11E+06          8.62E+06      1.37E+08      O.OOE+O0      1.13E+08 Te-129M          3.91E+07      1.46E+07        6.19E+06          1.34E+07      1.63E+08      O.OOE+O0      1.97E+08 Te-132            2.06E-10      1.33E-10        1.25E-10          1.47E-10      1.28E-09      O.OOE+O0      6.29E-09 1-131            1.94E+08      2.77E+08        1.59E+08          9.09E+10      4.76E+08      O.OOE+O0      7.32E+07 1-132            1.10E+01      2.93E+01        1.03E+01          1.03E+01      4.67E+01      O.OOE+O0      5.51E-02 1-133            2.64E+06      4.59E+06        1.40E+06          6.75E+08      8.01E+06      O.OOE+O0      4.13E+06 1-135            9.34E+03      2.45E+04        9.03E+03          1.61E+06      3.92E+04      O.OOE+O0      2.76E+04
*R Values in units of mrem/yr per pCi/m 3 for inhalation and tritium and in units of mrem/yr per pCi/sec per m2 for all others.
3-4R
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                  August 2014 Offsite Dose Calculation Manual (ODCM)                                                                          Rev. 25 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        O.OOE+00      2.66E+09      8.82E+08        1.44E+08 Cs-136          1.66E+08      6.57E+08          4.73E+08        O.OOE+00      3.65E+08      5.01E+07      7.46E+07 Cs-137          4.71E+09      6.44E+09          4.22E+09        O.OOE+00      2.19E+09      7.27E+08        1.25E+08 Ba-140          1.71E+07      2.15E+04          1.12E+06        O.OOE+00      7.32E+03      1.23E+04        3.53E+07 La-140          7.56E-32      3.81E-32          1.01E-32        O.OOE+00      O.OOE+00      O.OOE+00        2.80E-27 Ce-141          2.91E+03      1.97E+03          2.23E+02        O.OOE+00      9.14E+02      O.OOE+00        7.52E+06 Ce-144          2.15E+05      8.97E+04          1.15E+04        0.00E+00      5.32E+04      O.OOE+00        7.26E+07 Pr-143          1.OOE+02      4.02E+01          4.97E+00        O.OOE+00      2.32E+01      O.OOE+00      4.39E+05 Nd-147          6.08E+01      7.02E+01          4.20E+00        O.OOE+00      4.10E+01      O.OOE+00        3.37E+05 Hf-181          5.91E+03      3.33E+01          6.68E+02        2.12E+01      2.79E+01      O.OOE+00      4.38E+05 Np-239          1.34E-22        1.32E-23        7.28E-24        O.OOE+00        4.12E-23      O.OOE+00        2.71E-18 3
*R Values in units of mrem/yr per  giCi/m  for inhalation and tritium and in units of mrem/yr per [ICi/sec per m 2 for all others.
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                August 2014 Offsite Dose Calculation Manual (ODCM)                                                                        Rev. 25 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              O.OOE+00      1.OOE+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.OOE+08          O.OOE+00      O.OOE+00      O.OE+00        1.73E+09 Cr-51            O.OOE+00      O.OOE+00        3.02E+04          1.68E+04      6.63E+03      4.32E+04      5.08E+06 Mn-54            O.OOE+00      8.52E+06          1.69E+06          O.OOE+00      2.54E+06      O.OOE+00      1.75E+07 Fe-55            2.78E+07      1.97E+07        4.59E+06          O.OOE+00      O.OOE+00      1.25E+07      8.53E+06 Fe-59            3.10E+07      7.23E+07          2.79E+07          O.OOE+00      O.OOE+00      2.28E+07      1.71E+08 Co-57            O.OOE+00      1.39E+06        2.33E+06          O.OOE+00      O.OOE+00      O.OOE+00      2.59E+07 Co-58            O.OOE+00      4.72E+06          1.09E+07          O.OOE+00      G.OOE+00      O.OOE+00      6.50E+07 Co-60            O.OOE+00      1.72E+07        3.88E+07          O.OOE+00      O.OOE+00      O.OOE+00      2.25E+08 Ni-63            8.25E+09      5.83E+08        2.80E+08          O.OOE+00      O.OOE+00      O.OOE+00      9.27E+07 Zn-65            1.47E+09      5.11E+09        2.38E+09          O.OOE+00      3.27E+09      O.OOE+00      2.16E+09 Br-82            O.OOE+00      O.OOE+00          3.62E-29        O.OOE+00      O.OOE+00      O.OOE+00      O.OOE+00 Rb-86            O.OOE+00      2.95E+09        1.39E+09          O.OOE+00      O.OOE+00      O.OOE+00      4.37E+08 Sr-89            1.60E+09      O.OOE+00        4.59E+07          O.OOE+00      O.OOE+00      O.OOE+00      1.91E+08 Sr-90            4.37E+10      O.OOE+00        1.08E+10          O.OOE+00      O.OOE+00      O.OOE+00      1.23E+09 Y-90              2.64E-18      O.OOE+00          7.12E-20        O.OOE+00      O.OOE+00      O.OOE+00      2.18E-14 Y-91            9.40E+03      O.OOE+00        2.52E+02          O.OOE+00      O.OOE+00      O.OOE+00      3.85E+06 Zr-95            9.83E+02      3.10E+02        2.13E+02          O.OOE+00      4.56E+02      O.OOE+00      7.16E+05 Nb-95            8.45E+04      4.68E+04          2.58E+04          O.OOE+00      4.54E+04      O.OOE+00      2.OOE+08 Nb-97            1.97E-08      4.92E-09          1.80E-09        O.OOE+00      5.75E-09      O.OOE+00      1.17E-04 Mo-99            O.OOE+00      3.31E-12          6.31E-13        O.OOE+00      7.57E-12      O.OOE+00      5.92E-12 Ru-103          1.09E+03      O.OOE+00        4.65E+02          O.OOE+00      3.83E+03      O.OOE+00      9.08E+04 Ru-106          2.32E+04      O.OOE+00        2.93E+03          O.OOE+00      4.48E+04      O.OOE+00      1.11E+06 Ag-110M          6.14E+07      5.81E+07        3.53E+07          O.OOE+00      1.11E+08      O.OOE+00      1.63E+10 Sn-113          2.15E+06      9.06E+04        2.28E+06          2.97E+04      6.37E+04      O.OOE+00      2.58E+07 Sb-124          2.76E+07      5.08E+05          1.08E+07        6.26E+04      O.OOE+00      2.41E+07      5.56E+08 Sb-125          2.32E+07      2.53E+05        5.42E+06          2.22E+04      O.OOE+00      2.04E+07      1.80E+08 Te-125M          2.03E+07      7.32E+06        2.72E+06          5.68E+06      O.OOE+00      O.OOE+00      5.99E+07 Te-127m          6.22E+07      2.21E+07        7.39E+06          1.48E+07      2.52E+08      O.OOE+00      1.55E+08 Te-129M          7.15E+07      2.65E+07          1.13E+07        2.31E+07      2.99E+08      O.OOE+00      2.69E+08 Te-132            3.68E-10      2.33E-10          2.19E-10        2.45E-10      2.23E-09      O.OOE+00      7.37E-09 1-131            3.52E+08      4.93E+08        2.65E+08          1.44E+11      8.48E+08      O.OOE+00      9.75E+07 1-132            1.94E+01      5.09E+01          1.83E+01        1.71E+01      8.02E+01      O.OOE+00      2.22E+01 1-133            4.82E+06      8.18E+06        2.49E+06          1.14E+09      1.43E+07      O.OOE+00      6.19E+06 1-135            1.66E+04      4.27E+04          1.58E+04        2.75E+06      6.75E+04      O.OOE+00      4.74E+04
*R Values in units of mrem/yr per piCi/m 3 for inhalation and tritium and in units of mrem/yr per pCi/sec per m2 for all others.
3-50
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                              August 2014 Offsite Dose Calculation Manual (ODCM)                                                                        Rev. 25 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.OOE+00      4.48E+09      1.71E+09        1.75E+08 Cs-136          2.83E+08      1.11E+09      7.48E+08          0.OOE+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          O.OOE+00      1.68E+03      O.OOE+00        1.02E+07 Ce-144          3.95E+05      1.63E+05      2.12E+04          0.OOE+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.OOE+00      6.06E+05 Nd-147          1.17E+02      1.27E+02      7.61E+00          0.00E+00      7.47E+01      0.OOE+00      4.59E+05 Hf-181          1.06E+04      5.82E+01      1.18E+03          3.55E+01      4.84E+01      0.OOE+00        5.28E+05 Np-239          2.56E-22      2.42E-23        1.34E-23        0.OOE+00      7.59E-23      0.OOE+00        3.89E-18 2
*R Values in units of mrem/yr per pCi/m3 for inhalation and tritium and in units of mrem/yr per pCi/sec per m    for all others.
3-51
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                              August 2014 Offsite Dose Calculation Manual (ODCM)                                                                        Rev. 25 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              O.OOE+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.OOE+00      0.OOE+00      1.41E+09 Cr-51            0.OOE+00      0.OOE+00        6.17E+04          3.42E+04      9.36E+03      6.25E+04      3.27E+06 Mn-54            0.OOE+00      1.27E+07        3.39E+06          0.OOE+00      3.57E+06      0.OOE+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.OOE+00      3.37E+07      1.21E+08 Co-57            0.OOE+00      2.37E+06        4.80E+06          0.OOE+00      0.00E+00      0.00E+00      1,94E+07 Co-58            0.OOE+00      7.21E+06        2.21E+07          0.OOE+00      0.00E+00      0.00E+00      4.20E+07 Co-60            0.OOE+00      2.68E+07        7.90E+07          0.00E+00      0.OOE+00      0.OOE+00      1,48E+08 Ni-63            2.07E+10      1.11E+09        7.04E+08          0.OOE+00      0.OOE+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.OOE+00      0.OOE+00        7.42E-29        0.OOE+00      0.OOE+00      0.00E+00      0.OOE+00 Rb-86            0.OOE+00      5.47E+09        3.36E+09          0.00E+00      0.00E+00      0.OOE+00      3,52E+08 Sr-89            3.97E+09      0.00E+00        1.13E+08          0.00E+00      0.00E+00      0.OOE+00      1,54E+08 Sr-90            7.38E+10      0.00E+00        1.87E+10          0.OOE+00      0.OOE+00      0.OOE+00      9.95E+08 Y-90            6.54E-18      0.00E+00        1.75E-19        0.OOE+00      0.OOE+00      0.00E+00      1.86E-14 Y-91            2.32E+04      0.OOE+00        6.21E+02          0.00E+00      0.OOE+00      0.OOE+00      3.09E+06 Zr-95            2.28E+03      5.02E+02        4.47E+02          0.00E+00      7.18E+02      0.OOE+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.OOE+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.OOE+00      6.47E+03      0.00E+00      6.65E+04 Ru-106          5.72E+04      0.00E+00        7.14E+03          0.OOE+00      7.72E+04      0.OOE+00      8.90E+05 Ag-110M          1.33E+08      9.00E+07        7.19E+07          0.OOE+00      1.68E+08      0.OOE+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.OOE+00      3.62E+07      4.09E+08 Sb-125          5.52E+07      4.26E+05        1.16E+07          5.11E+04      0.OOE+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 1-131            8.54E+08      8.59E+08        4.88E+08          2.84E+11      1.41E+09      0.00E+00      7.64E+07 1-132            4.60E+01      8.45E+01        3.89E+01          3.92E+01      1.29E+00      0.00E+00      9.95E+01 1-133            1.17E+07      1.45E+07        5.48E+06          2.69E+09      2.41E+07      0.00E+00      5.84E+06 1-135            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 mremlyr per 4Ci/m 3 for inhalation and tritium and in units of mrem/yr per pCi/sec per m2 for all others.
3-52
 
Shearon Harris Nuclear        Power Plant (SHNPP)                                                        August 2014 Offsite  Dose Calculation        Manual (ODCM)                                                                Rev. 25 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.OOE+00      7.03E+09      2.52E+09      1.22E+08 Cs-136          6.39E+08      1.76E+09          1.14E+09          0.OOE+00      9.36E+08      1.40E+08      6.17E+07 Cs-137          2.06E+10      1.97E+10          2.91E+09          0.OOE+00      6.42E+09      2.31E+09      1.23E+08 Ba-140          7.47E+07      6.54E+04          4.36E+06          O.OOE+00      2.13E+04      3.90E+04      3.78E+07 La-140          3.25E-31      1.14E-31          3.83E-32        0.OOE+00      0.OOE+00      0.OOE+00      3.17E-27 Ce-141          1.31E+04      6,55E+03          9.73E+02          0.OOE+00      2.87E+03        .OOE+00      8&17E+06 Ce-144          9.74E+05      3.05E+05          5.20E+04          O.OOE+00        1.69E+05      0.OOE+00      7.96E+07 Pr-143          4.56E+02      1.37E+02          2.26E+01          0.OOE+00      7.42E+01      O.OOE+00      4.92E+05 Nd-147          2.87E+02      2.32E+02          1.80E+01          0.OOE+00        1.27E+02      0.OOE+00      3.68E+05 Hf-181          2.51E+04      9.79E+01          2.53E+03          8.24E+01      7.86E+01      O.OOE+00      4.16E+05 Np-239          6.31E-22      4.53E-23          3.18E-23        0.OOE+00        1.31E-22      O.OOE+00      3.35E-18
*R Values in units of mrem/yr per 1iCi/m 3 for inhalation and 32 tritium and in units of mrem/yr per gCi/sec per m2 for all others.
3-53
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                August 2014 Offsite Dose Calculation Manual (ODCM)                                                                        Rev. 25 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        O.OOE+00      O.OOE+00      O.OOE+00      1.42E+09 Cr-51            O.OOE+00      O.OOE+00          9.77E+04        6.38E+04        1.39E+04      1.24E+05      2.85E+06 Mn-54            O.OOE+00      2.37E+07          5.37E+06        0.00E+00      5.25E+06      O.OE+00      8.71E+06 Fe-55            8.43E+07      5.45E+07          1.46E+07        O.OOE+00      O.OOE+00      2.66E+07      6.91E+06 Fe-59            1.34E+08      2.34E+08          9.23E+07        O.OOE+00      O.OOE+00      6.92E+07      1.12E+08 Co-57            O.OOE+00      5.53E+06          9.OOE+06        O.OOE+00      O.OOE+00      O.OOE+00      1.89E+07 Co-58            O.OOE+00      1.44E+07        3.60E+07          O.OOE+00      O.OOE+00      O.OOE+00      3.59E+07 Co-60            O.OOE+00      5.47E+07          1.29E+08          O.OOE+00      O.OOE+00      O.OOE+00      1.30E+08 Ni-63            2.44E+10      1.51E+09        8.46E+08          O.OOE+00      O.OOE+00      O.OOE+00      7.50E+07 Zn-65            3.88E+09      1.33E+10        6.14E+09          O.OOE+00      6.45E+09      O.OOE+00      1.12E+10 Br-82            O.OOE+00      O.OOE+00          1.25E-28        O.OOE+00      O.OOE+00      O.OOE+00      O.OOE+00 Rb-86            O.OOE+00      1.39E+10        6.86E+09          O.OOE+00      O.OOE+00      O.OOE+00      3.55E+08 Sr-89            7.55E+09      O.OOE+00          2.17E+08          O.OOE+00      O.OOE+00      O.OOE+00      1.55E+08 Sr-90            8.04E+10      O.OOE+00          2.05E+10          O.OOE+00      O.OOE+00      O.OOE+00      1.OOE+09 Y-90              1.38E-17    O.OOE+00          3.71E-19        O.OOE+00      O.OOE+00      O.OOE+00      1.91E-14 Y-91            4.36E+04      O.OOE+00        1.17E+03          O.OOE+00      O.OOE+00      O.OOE+00      3.12E+06 Zr-95            4.05E+03      9.88E+02          7.01E+02          O.OOE+00      1.06E+03      O.OOE+00      4.92E+05 Nb-95            3.56E+05      1.47E+05        8.48E+04          O.OOE+00      1.05E+05      O.OOE+00      1.24E+08 Nb-97            1.02E-07      2.17E-08          7.83E-09        O.OOE+00      1.70E-08      0.00E+00      6.85E-03 Mo-99            O.OOE+00      1.54E-11          3.OOE-12        O.OOE+00      2.30E-11      O.OOE+00      5.07E-12 Ru-103          5.21E+03      O.OOE+00        1.74E+03          O.OOE+00      1.08E+04      O.OOE+00      6.33E+04 Ru-106          1.18E+05      O.OOE+00        1.47E+04          O.OOE+00      1.39E+05      O.OOE+00      8.95E+05 Ag-110M          2.46E+08      1.80E+08        1.19E+08          O.OOE+00      2.57E+08      O.OOE+00      9.32E+09 Sn-113          6.45E+06      2.45E+05        6.65E+06          9.34E+04      1.31E+05      O.OOE+00      1.37E+07 Sb-124          1.26E+08      1.85E+06        3.90E+07          3.34E+05      O.OOE+00      7.88E+07      3.88E+08 Sb-125          9.49E+07      9.18E+05        1.95E+07          1.19E+05      O.OOE+00      5.95E+07      1.26E+08 Te-125M          1.02E+08      3.41E+07        1.38E+07          3.43E+07      O.OOE+00      O.OOE+00      4.86E+07 Te-127m          3.10E+08      1.03E+08        3.75E+07          8.96E+07      7.64E+08      O.OOE+00      1.25E+08 Te-129M          3.62E+08      1.24E+08        5.57E+07          1.39E+08      9.05E+08      O.OOE+00      2.16E+08 Te-132            1.81E-09      8.95E-10          8.35E-10        1.32E-09      5.60E-09      O.OOE+00      3.31E-09 1-131            1.78E+09      2.10E+09        9.23E+08          6.90E+11      2.45E+09      O.OOE+00      7.49E+07 1-132            9.55E+01      1.94E+00        6.90E+01          9.09E+01      2.16E+00      O.OOE+00      1.57E+00 1-133            2.47E+07      3.60E+07        1.05E+07          6.55E+09      4.23E+07      O.OOE+00      6.09E+06 1-135            8.17E+04      1.63E+05        5.93E+04          1.46E+07      1.81E+05      O.OOE+00      5.88E+04
*R Values in units of mrem/yr per jiCi/m 3 for inhalation and tritium and in units of mrem/yr per pCi/sec per m2 for all others.
3-54
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                August 2014 Offsite Dose Calculation Manual (ODCM)                                                                          Rev. 25 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        O.OOE+00        1.07E+10      4.38E+09        1.13E+08 Cs-136          1.25E+09      3.67E+09          1.37E+09        O.OOE+00        1.46E+09      2.99E+08        5.58E+07 Cs-137          3.28E+10      3.84E+10          2.72E+09        O.OOE+00        1.03E+10      4.18E+09        1.20E+08 Ba-140          1.54E+08      1.54E+05        7.91E+06        O.OOE+00      3.65E+04      9.43E+04        3.77E+07 La-140          6.80E-31      2.68E-31          6.89E-32        O.OOE+00        O.OOE+00      O.OOE+00        3.15E-27 Ce-141          2.60E+04      1.59E+04        1.87E+03        O.OOE+00      4.90E+03      O.OOE+00        8.21E+06 Ce-144          1.40E+06      5.71E+05          7.82E+04        O.OOE+00        2.31E+05      O.OOE+00        8.01E+07 Pr-143          9.44E+02      3.53E+02          4.68E+01        O.OOE+00        1.31E+02      O.OOE+00        4.98E+05 Nd-147          5.69E+02      5.84E+02          3.58E+01        O.OOE+00        2.25E+02      O.OOE+00        3.70E+05 Hf-181          4.78E+04      2.26E+02          4.23E+03        1.91E+02        1.32E+02      O.OOE+00        3.93E+05 Np-239        1.33E-21      1.19E-22          6.74E-23        0.00E+00      2.38E-22      O.OOE+00        3.45E-18 3
*R Values in units of mrem/yr per [LCi/m  for inhalation and tritium and in units of mrem/yr per IiCi/sec per m2 for all others.
3-55
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                              August 1994 Offsite Dose Calculation Manual (ODCM)                                                                        Rev. 5 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    O.OOE+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    O.OOE+01      O.OOE+01    O.OOE+01    O.OOE+01 Cr-51        2.08E+03    5.23E+05    O.OOE+01      O.OOE+01    4.58E+02      1.24E+03    2.76E+03    O.OOE+01 Mn-54        1.17E+05    1.88E+06    O.OOE+01      6.14E+05    1.83E+05      O.OOE+01    O.OOE+01    O.OOE+01 Fe-59        2.08E+05    1.81E+06    2.31E+05      5.42E+05    O.OOE+01      O.OOE+01    1.51E+05    O.OOE+01 Co-58        7.54E+05    6.82E+06    O.OOE+01      3.36E+05    O.OOE+01      O.OOE+01    O.OOE+01    O.OOE+01 Co-60        2.69E+06    2.29E+07    O.OOE+01      1.22E+06    O.OOE+01      O.OOE+01    O.OOE+01    O.OOE+01 Zn-65        1.65E+08    2.31E+08    1.15E+08      3.66E+08    2.45E+08      O.OOE+01    O.OOE+01    O.OOE+01 Rb-86        9.05E+07    3.83E+07    O.OOE+01      1.94E+08    O.OOE+01      O.OOE+01    O.OOE+01    O.OOE+01 Sr-89        5.24E+07    2.93E+08    1.83E+09      O.OOE+01    O.OOE+01      O.OOE+01    O.OOE+01    O.OOE+01 Sr-90        1.59E+10    1.88E+09    6.49E+10      O.OOE+01      O.OOE+01      O.OOE+01    O.OOE+01    O.OOE+01 Y-91          1.64E+01    3.37E+05    6.13E+02      O.OOE+01    O.OOE+01      O.OOE+01    O.OOE+01    O.OOE+01 Zr-95        1.46E+01    6.85E+04    6.74E+01      2.16E+01    3.39E+01      O.OOE+01    O.OOE+01    O.OOE+01 Nb-95        1.78E+03    2.01E+07    5.94E+03      3.31E+03    3.27E+03      O.OOE+01    O.OOE+01    O.OOE+01 Ru-103        3.16E+01    8.56E+03    7.33E+01      O.OOE+01    2.80E+02      O.OOE+01    O.OOE+01    O.OOE+01 Ru-106        1.92E+02    9.81E+04    1.52E+03      0.00E+01      2.93E+03      O.OOE+01    O.OOE+01    O.OOE+01 Ag-llOM      2.45E+06    1.68E+09    4.46E+06      4.12E+06      8.11E+06      O.OOE+01    O.OOE+01    O.OOE+01 Sn-113        1.32E+05    2.44E+06      1.40E+05      5.41E+03    3.96E+03      1.90E+03    O.OOE+01    O.OOE+01 Sb-124        7.36E+05    5.27E+07    1.86E+06      3.51E+04      O.OOE+01      4.50E+03    1.44E+06    O.OOE+01 Te-127M      4.93E+05    1.36E+07    4.05E+06      1.45E+06      1.64E+07      1.03E+06    O.OOE+01    O.OOE+01 Te-129M      7.43E+05    2.36E+07    4.69E+06      1.75E+06      1.96E+07      1.61E+06    O.OOE+01    O.OOE+01 1-131        1.91E+08    8.78E+07    2.33E+08      3.33E+08      5.71E+08      1.09E+11    O.OOE+01    O.OOE+01 1-132        1.23E+01      6.61E-02    1.32E+01      3.52E+01      5.61E+01      1.23E+01    O.OOE+01    O.OOE+01 1-133        1.68E+06    4.95E+06    3.17E+06      5.51E+06    9.61E+06      8,10E+08    O.OOE+01    O.OOE+01 1-135        1.08E+04    3.32E+04      1.12E+04      2.94E+04    4.71E+04      1.94E+06    O.OOE+01    O.OOE+01 Cs-134        2.01E+10    4.31E+08      1.03E+10      2.46E+10      7.97E+09      O.OOE+01    2.65E+09    O.OOE+01 Cs-136        1.42E+09    2.24E+08    4.99E+08      1.97E+09      1.10E+09      O.OOE+01    1.50E+08    O.OOE+01 Cs-137        1.27E+10    3.74E+08      1.41E+10      1.93E+10      6.56E+09      O.OOE+01    2.18E+09    O.OOE+01 Ba-140        1.35E+05    4.23E+06    2,06E+06      2.58E+03      8.78E+02      O.O0E+01    1.48E+03    O.OOE+01 Ce-141      2.68E+01    9.03E+05    3.49E+02      2.36E+02      1.10E+02      O.OOE+01    O.OOE+01    O.OOE+01 Ce-144        1.38E+03    8.71E+06    2.58E+04      1.08E+04      6.39E+03      O.OOE+01    O.OOE+01    O.OOE+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 ltCi/m for inhalation and tritium and in units of mrem/yr per VtCi/sec per'mfrall others.
3-56
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                              August 1994 Offsite Dose Calculation Manual (ODCM)                                                                        Rev. 5 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      O.OOE+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    O.OOE+01      O.OOE+01    O.OOE+01    O.OOE+01 Cr-51        3.63E+03    6.10E+05      O.OOE+01      O.OOE+01    7.95E+02      2,02E+03    5.18E+03    O.OOE+01 Mn-54        2.03E+05    2.10E+06      O.OOE+01      1.02E+06    3.05E+05      O.OOE+01    O.OOE+01    O.OOE+01 Fe-59        3.63E+05    2.22E+06      4.03E+05      9.40E+05    O.OOE+01      O.OOE+01    2.96E+05    O.OOE+01 Co-58        1.30E+06    7.80E+06      O.OOE+01      5.66E+05    O.OOE+01      O.OOE+01    O.OOE+01    O.OOE+01 Co-60        4.66E+06    2.69E+07      O.OOE+01      2.07E+06    O.0OE+01      O.OOE+01    O.OOE+01    G.OOE+01 Zn-65        2.86E+08    2.60E+08      1.77E+08      6.13E+08    3.93E+08      O.OOE+01    O.OOE+01    O.OOE+01 Rb-86        1.66E+08    5.24E+07      O.OOE+01      3.54E+08    O.OOE+01      O.0OE+01    O.OOE+01    O.OOE+01 Sr-89        9.65E+07    4.01E+08      3.37E+09      O.OOE+01    O.OOE+01      O.OOE+01    O.OOE+01    O.OOE+01 Sr-90        2.27E+10    2.58E+09      9.18E+10      O.OOE+01    O.OOE+01      O.OOE+01    O.OOE+01    O.OOE+01 Y-91          3.02E+01    4.62E+05      1.13E+03      O.OOE+01    O.OOE+01      O.OOE+01    O.OOE+01    O.OOE+01 Zr-95        2.56E+01    8.59E+04      1.18E+02      3.72E+01    5.47E+01      O.OOE+01    O.OOE+01    O.OOE+01 Nb-95        3.09E+03      2.40E+07    1.01E+04      5.62E+03    5.45E+03      O.OOE+01    O.OOE+01    O.OOE+01 Ru-103        5.58E+01      1.09E+04    1.30E+02      O.OOE+01    4.60E+02      O.OOE+01    O.OOE+01    O.OOE+01 Ru-106        3.51E+02      1.34E+05    2.79E+03      O.OOE+01    5.38E+03      O.OOE+01    O.OOE+01    O.OOE+01 Ag-11OM      4.24E+06      1.96E+09    7.37E+06      6.97E+06      1.33E+07      O.OOE+01    O.OOE+01    O.OOE+01 Sn-113        2.28E+05    2.58E+06      2.15E+05      9.06E+03    6.37E+03      2.97E+03    O.OOE+01    O.OOE+01 Sb-124        1.29E+06    6.67E+07      3.31E+06      6.10E+04    O.OOE+01      7.51E+03    2.89E+06    O.OOE+01 Te-127M      8.87E+05      1.86E+07    7.46E+06      2.65E+06    3.02E+07      1.77E+06    O.OOE+01    O.OOE+01 Te-129M      1.36E+06    3.22E+07      8.58E+06      3.19E+06    3.59E+07      2.77E+06    O.OOE+01    O.OOE+01 1-131        3.18E+08      1.17E+08    4.22E+08      5.91E+08      1.02E+09      1.73E+11    O.OOE+01    O.OOE+01 1-132        2.19E+01      2.66E+01    2.33E+01      6.11E+01    9.62E+01      2.06E+01    O.OOE+01    O.OOE+01 1-133        2.99E+06    7.43E+06      5.79E+06      9.81E+06      1.72E+07      1.37E+09    O.OOE+01    O.OOE+01 1-135        1.90E+04      5.63E+04    1.99E+04      5.13E+04      8.10E+04      3.30E+06    O.OOE+01    O.OOE+01 Cs-134        1.96E+10      5.26E+08    1.80E+10      4.23E+10      1.34E+10      O.OOE+01    5.13E+09    O.OOE+01 Cs-136        2.25E+09      2.69E+07    8.50E+08      3.34E+09      1.82E+09      O.OOE+01    2.87E+08    OOOE+01 Cs-137        1.19E+10    4.85E+08      2.56E+10      3.41E+10      1.16E+10      O.OOE+01    4.51E+09    O.OOE+01 Ba-140        2.39E+05      5.72E+06    3.71E+06      4.55E+03      1.54E+03      O.OOE+01    3.06E+03    OOOE+01 Ce-141        4.91E+01      1.22E+06    6.40E+02      4.27E+02      2.01E+02      O.OOE+01    O.OOE+01    O.OOE+01 Ce-144        2.55E+03      1.19E+07    4.74E+04      1.96E+04      1.17E+04      O.OOE+01    O.OOE+01    O.OOE+01 Hf-181        1.41E+02      6.34E+04    1,27E+03      6.97E+00      5.80E+00 4.26E+00        O.OOE+01    O.OOE+01
*R Values in units of mrem/yr per laCi/m for inhalation and tritium and in units of mrem/yr per pCi/sec per m2for all others.
3-57
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                August 1994 Offsite Dose Calculation Manual (ODCM)                                                                            Rev. 5 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      O.OOE+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      O.OOE+01    O.OOE+01    O.OOE+01      O.OOE+01 Cr-51        7.40E+03    3.93E+05      0.00E+01      O.OOE+01      1.12E+03    4.11E+03    7.50E+03      O.OOE+01 Mn-54        4.07E+05    1.28E+06      0.00E+01      1.53E+06    4.29E+05      O.OOE+01    O.OOE+01      O.OOE+01 Fe-59        7.52E+05    1.57E+06      9.34E+05      1.51E+06      O.OOE+01      O.OOE+01    4.38E+05      O.OOE+01 Co-58        2.65E+06    5.05E+06      O.OOE+01      8.65E+05      O.OOE+01      O.OOE+01    O.OOE+01      O.OOE+01 Co-60        9.48E+06    1.78E+07      O.OOE+01      3.21E+06      O.OOE+01      O.OOE+01    O.OOE+01      O.OOE+01 Zn-65        5.74E+08    1.62E+08      3.47E+08      9.24E+08      5.82E+08      O.OOE+01    O.OOE+01      O.OOE+01 Rb-86        4.04E+08    4.22E+07      O.OOE+01      6.57E+08      O.OOE+01      0,00E+01    O.OOE+01      O.OOE+01 Sr-89        2.38E+08    3.23E+08      8.34E+09      O.OOE+01      O.OOE+01      O.OOE+01    O.OOE+01      O.OOE+01 Sr-90        3.93E+10    2.09E+09      1.55E+11      O.OOE+01      O.OOE+01      O.OOE+01    O.OOE+01      O.OOE+01 Y-91          7.45E+01    3.71E+05      2.79E+03      O.OOE+01      O.OOE+01      O.OOE+01    O.OOE+01      O.OOE+01 Zr-95        5.36E+01    6.28E+04      2.74E+02      6.02E+01      8.62E+01      O.OOE+01    O.OOE+01      O.OOE+01 Nb-95        6.37E+03      1.65E+07    2.29E+04      8.91E+03      8.37E+03      O.OOE+01    O.OOE+01      O.OOE+01 Ru-103        1.19E+02    7.98E+03      3.09E+02      O.OOE+01      7.77E+02      O.OOE+01    O.OOE+01      O.OOE+01 Ru-106        8.56E+02      1.07E+05    6.86E+03      O.OOE+01      9.27E+03      O.OOE+01    O.OOE+01      O.OGE+01 Ag-IIOM      8.63E+06      1.28E+09      1.60E+07      1.08E+07      2.01E+07      O.OOE+01    O.OOE+01      O.OOE+01 Sn-113        4.61E+05      1.69E+06    4.22E+05      1.36E+04      9.38E+03      5.59E+03    O.OOE+01      O.OOE+01 Sb-124        2.75E+06    4.91E+07      7.84E+06      1.02E+05      O.OOE+01      1.73E+04    4.35E+06      O.OOE+01 Te-127M      2.18E+06      1.49E+07      1.84E+07      4.95E+06      5.24E+07      4.40E+06    O.OOE+01      O.OOE+01 Te-129M      3.28E+06    2.58E+07      2.12E+07      5.91E+06      6.21E+07      6.82E+06    O.OOE+01      O.OOE+01 1-131        5.85E+08    9.17E+07      1.02E+09      1.03E+09      1.69E+09      3.41E+11    O.OOE+01      O.OOE+01 1-132        4.67E+01      1.19E+00    5.52E+01      1.01E+00      1.55E+00      4.71E+01    O.OOE+01      O.OOE+01 1-133        6.58E+06    7.OOE+06      1.41E+07      1.74E+07      2.90E+07      3.23E+09    O.OOE+01      O.OOE+01 1-135        4.01E+04    6.47E+04      4.72E+04      8.49E+04      1.30E+05      7.52E+06    O.OOE+01      O.OOE+01 Cs-134        1.43E+10    3.67E+08      4.14E+10      6.80E+10      2.11E+10      O.OOE+01    7.56E+09      O.OOE+01 Cs-136        3.41E+09      1.85E+08      1.92E+09      5.27E+09      2.81E+09      O.OOE+01    4.19E+08      O.OOE+01 Cs-137        8.72E+09    3.70E+08      6.17E+10      5.91E+10      1.93E+10      O.OOE+01    6.93E+09      O.OOE+01 Ba-140        5.23E+05    4.54E+05      8.96E+06      7.85E+03      2.56E+03      O.OOE+01    4.68E+03      O.OOE+01 Ce-141        1.17E+02    9.81E+05      1.53E+03      7.36E+02      3.45E+02      O.OOE+01    O.OOE+01      O.OOE+01 Ce-144        6.24E+03    9.55E+06      1.17E+05      3.66E+04      2.03E+04      O.OOE+01    O.OOE+01      O.OOE+01 Hf-181        3.04E+02    4.99E+04      3.02E+03      1.17E+01      9.43E+00      9.88E+00    O.OOE+01      O.OOE+01
*R Values in units of mrem/yr per ptCi/m3 for inhalation and tritium and in units of mrem/yr per [tCi/sec per m 2 for all others.
3-58
 
Shearon  Harris Nuclear      Power Plant (SHNPP)                                                    August 1994 Offsite  Dose Calculation      Manual (ODCM)                                                                Rev. 5 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    O.OOE+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      O.OOE+01    O.OOE+01    O.OOE+01 Cr-51        1.17E+04    3.42E+05    O.OOE+01      O.OOE+01      1.67E+03    7.65E+03    1.49E+04    O.OOE+01 Mn-54        6.45E+05      1.04E+06    O.OOE+01      2.84E+06    6.30E+05      O.OOE+01    O.OOE+01    O.OOE+01 Fe-59        1.20E+06      1.45E+06    1.74E+06      3.04E+06    O.OOE+01      O.OOE+01    9.OOE+05    O.OOE+01 Co-58        4.31E+06    4.31E+06    O.OOE+01      1.73E+06    O.OOE+01      O.OOE+01    O.OOE+01    O.OOE+01 Co-60        1.55E+07      1.56E+07    O.OOE+01      6.56E+06    O.OOE+01      O.OOE+01    O.OOE+01    O.OOE+01 Zn-65        7.36E+08      1.35E+09    4.66E+08      1.60E+09    7.74E+08      O.OOE+01    O.OOE+01    O.OOE+01 Rb-86        8.23E+08    4.26E+07    O.OOE+01      1.67E+09    0.00E+01      O.OOE+01    O.OOE+01    O.OOE+01 Sr-89        4.55E+08    3.26E+08    1.59E+10      O.OOE+01    0,00E+01      O.OOE+01    O.OOE+01    O.OOE+01 Sr-90        4.30E+10    2.11E+09    1.69E+11      O.OOE+01    0,00E+01      O.OOE+01    O.OOE+01    O.OOE+01 Y-91          1.39E+02    3.75E+05    5.23E+03      O.OOE+01    0,00E+01      O.OOE+01    O.OOE+01    O.OOE+01 Zr-95        8.41E+01      5.90E+04    4.85E+02      1.19E+02      1.28E+02      O.OOE+01    O.OOE+01    O.OOE+01 Nb-95        1.02E+04      1.48E+07    4.27E+04      1.76E+04      1.26E+04      O.OOE+01    O.OOE+01    O.OOE+01 Ru-103        2.09E+02    7.60E+03    6.25E+02      O.OOE+01      1.30E+03      O.OOE+01    O.OOE+01    O.OOE+01 Ru-106        1.77E+03      1.07E+05    1.41E+04      O.OOE+01      1,67E+04      O.OOE+01    O.OOE+01    O.OOE+01 Ag-IOM        1.43E+07      1.12E+09    2.95E+07      2.16E+07      3,08E+07      O.OOE+01    O.OOE+01    O.OOE+01 Sn-113        6.66E+05      1.37E+06    6.46E+05      2.45E+04      1.32E+04      9.34E+03    O.OOE+01    O.OOE+01 Sb-124        4.68E+06    4.66E+07    1.51E+07      2.22E+05      O.OOE+01      4.01E+04    9.46E+06    O.OOE+01
-e-127M      4.51E+06      1.50E+07    3.72E+07      1.23E+07    9.16E+07      1.08E+07    O.OOE+01    O.OOE+01 Te-129M      6.69E+06      2.59E+07    4.34E+07      1.49E+07      1.09E+08      1.67E+07    O.OOE+01    O.OOE+01 1-131        1.11E+09    8.99E+07    2.14E+09      2.52E+09      2.94E+09      8.28E+11    O.OOE+01    OOOE+01 1-132        8.28E+01      1.88E+00    1.15E+00      2.33E+00      2.59E+00      1.09E+02    O.OOE+01    O.OOE+01 1-133        1.27E+07      7.31E+06    2.97E+07      4.32E+07      5.08E+07      7.86E+09    O.OOE+01    O.OOE+01 1-135        7.11E+04      7.06E+04    9.81E+04      1.95E+05      2.17E+05      1.75E+07    O.OOE+01    O.OOE+01 Cs-134        1.26E+10      3.38E+08    6.68E+10      1.25E+11      3.21E+10      O.OOE+01    1.31E+10    O.OOE+01 Cs-136        4.11E+09      1.67E+08    3.75E+09      1.10E+10      4.39E+09      O.OOE+01    8.98E+08    O.OOE+01 Cs-137        8.17E+09      3.61E+08    9.85E+10      1.15E+11      3.10E+10      O.OOE+01    1.25E+10    O.OOE+01 Ba-140        9.50E+05      4.53E+06    1.84E+07      1.84E+04      4.38E+03      O.OOE+01    1.13E+04    0.00E+01 Ce-141        2.24E+02      9.85E+05    3.13E+03      1.91E+03      5.88E+02      O.OOE+01    O.OOE+01    O.OOE+01 Ce-144        9.39E+03      9.61E+06    1.67E+05      6.86E+04      2.77E+04      O.OOE+01    O.OOE+01    O.OOE+01 Hf-181        5.08E+02      4.72E+04 5.74E+03        2.71E+01      1.58E+01      2.30E+01    O.OOE+01    O.OOE+01
*R Values in units of mrem/yr per pCi/m for inhalation and tritium and in units of mrem/yr per pCi/sec per m2 for all others.
3-59
 
Shearon      Harris Nuclear    Power Plant (SHNPP)                                                      August 2014 Offsite      Dose Calculation    Manual (ODCM)                                                              Rev. 25 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        O.OOE+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.OOE+04        O.OOE+00      O.OOE+00      O.OOE+00      8.63E+04 Cr-51        O.OOE+00      O.OOE+00        9.99E+01        5.94E+01        2.28E+01      1.44E+04      3.32E+03 Mn-54        O.OOE+00      3.95E+04        6.29E+03        O.OOE+00      9.83E+03        1.40E+06      7.72E+04 Mn-56        O.OOE+00      1.26E+00        1.85E-01        O.OOE+00        1.32E+00      9.56E+03      2.05E+04 Fe-55        2.49E+04      1.72E+04        3.99E+03        O.OOE+00      O.OOE+00      7.30E+04      6.11E+03 Fe-59        1.17E+04      2.77E+04        1.05E+04        O.OOE+00      O.OOE+00        1.01E+06      1.88E+05 Co-57        O.OOE+00      7.01E+02        6.80E+02        O.OOE+00        O.O0E+00      3.74E+05      3.18E+04 Co-58        O.OOE+00      1.58E+03        2.07E+03        O.OOE+00        O.OOE+00      9.27E+05      1.06E+05 Co-60        O.OOE+00      1.15E+04        1.48E+04        O.OOE+00        O.OOE+00      5.96E+06      2.84E+05 Ni-63      4.37E+05      3.18E+04        1.47E+04        O.OOE+00        O.OOE+00      1.81E+05      1.35E+04 Ni-65      1.56E+00      2.12E-01        9.23E-02        O.OOE+00        O.OOE+00      5.67E+03      1.25E+04 Cu-64        O.OOE+00      1.48E+00        6.23E-01        O.OOE+00        4.68E+00      6.87E+03      4.96E+04 Zn-65        3.24E+04      1.03E+05        4.65E+04        O.OOE+00        6.89E+04      8.63E+05      5.34E+04 Zn-69M        8.26E+00      1.98E+01        1.81E+00        O.OOE+00        1.20E+01      1.93E+04      1.39E+05 Zn-69        3.43E-02      6.59E-02        4.58E-03        O.OOE+00        4.27E-02      9.32E+02      1.65E+01 Br-82      O.OOE+00      O.OOE+00        1.37E+04        O.OOE+00        O.OOE+00      O.OOE+00      1.05E+04 Br-83      O.OOE+00      O.OOE+00        2.44E+02        O.OOE+00        O.OOE+00      O.OOE+00      2.35E+02 Br-84      O.OOE+00      O.OOE+00        3.17E+02        O.OOE+00        O.OOE+00      O.OOE+00      1.66E-03 Br-85      O.OOE+00      O.OOE+00        1.30E+01        O.OOE+00        O.OOE+00      O.OOE+00      O.OOE+00 Rb-86        O.OOE+00      1.35E+05        5.89E+04        O.OOE+00        O.OOE+00      O.OOE+00      1.66E+04 Rb-88        O.OOE+00      3.92E+02        1.95E+02        O.OOE+00        O.OOE+00      O.OOE+00      3.39E-09 Rb-89        O.OOE+00      2.59E+02        1.72E+02        O.OOE+00        O.OOE+00      O.OOE+00      9.40E-12 Sr-89      3.04E+05      O.OOE+O0        8.71E+03        O.OOE+O0        O.OOE+O0      1.40E+06      3.49E+05 Sr-90      9.91E+07      O.OOE+O0        6.09E+06        O.OOE+O0        O.OOE+O0      9.59E+06      7.21E+05 Sr-91      6.27E+01      O.OOE+O0        2.54E+00        O.OOE+O0        O.OOE+O0      3.69E+04      1.94E+05 Sr-92      6.83E+00      O.OOE+O0        2.95E-01        O.OOE+O0        O.OOE+O0      1.67E+04      4.36E+04 Y-90        2.11E+03      O.OOE+O0        5.68E+01        O.OOE+O0        O.OOE+O0      1.72E+05      5.12E+05 Y-91M        2.64E-01    O.OOE+O0        1.03E-02        O.OOE+O0        O.OOE+O0      1.94E+03      1.34E+00 Y-91        4.62E+05      O.OOE+O0        1.24E+04        O.OOE+O0        O.OOE+O0      1.70E+06      3.84E+05 Y-92        1.04E+O1      O.OOE+O0        3.05E-01        O.OOE+O0        O.OOE+O0      1.59E+04      7.44E+04 Y-93        9.56E+01      O.OOE+O0        2.64E+00        O.OOE+O0        O.OOE+O0      4.91E+04      4.27E+05 Zr-95      1.07E+05      3.44E+04        2.32E+04        O.OOE+O0        5.41E+04      1.77E+06      1.50E+05 Zr-97      9.80E+01      1.98E+01        9.15E+00        O.OOE+O0        3.01E+O1      7.97E+04      5.30E+05 Nb-95        1.41E+04      7.80E+03        4.20E+03        O.OOE+O0        7.72E+03      5.04E+05      1.04E+05 Nb-97        2.25E-01    5.69E-02        2.07E-02        O.OOE+O0        6.63E-02      2.43E+03      2.45E+02 Mo-99        O.OOE+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        O.OOE+00        4.47E-02      7.74E+02      4.21E+03
*R Values in units of mrem/yr per 1iCi/m3 for inhalation and tritium and in units of mrem/yr per iCi/sec per m2 for all others.
3-60
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                              August 2014 Offsite Dose Calculation Manual (ODCM)                                                                      Rev. 25 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.OOE+00        1.09E-03      4.04E+02        1.10E-11 Ru-103        1.53E+03      0.OOE+00        6.57E+02        0.OOE+00        5.82E+03      5.04E+05      1.10E+05 Ru-105        8.OOE-01      0.OOE+00        3.15E-01        O.OOE+00        1.03E+00      1.11E+04      4.88E+04 Ru-106        6.90E+04      0.OOE+00        8.71E+03        0.OOE+00        1.33E+05      9.35E+06      9.11E+05 Ag-110M        1.08E+04      9.99E+03        5.94E+03        0.OOE+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        O.OOE+00      2.48E+06      4.06E+05 Sb-125        5.40E+04      6.03E+02        1.28E+04        5.47E+01        0.OOE+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 1-130        4.63E+03      1.36E+04        5.35E+03          1.15E+06      2.11E+04      0.OOE+00      7.78E+03 1-131        2.52E+04      3.57E+04        2.05E+04          1.19E+07      6.12E+04      0.OOE+00      6.27E+03 1-132        1.16E+03      3.25E+03        1.16E+03          1.14E+05      5.18E+03      0.OOE+00      4.06E+02 1-133        8.63E+03      1.48E+04        4.51E+03          2.15E+06      2.58E+04      0.OOE+00      8.87E+03 1-134        6.52E+02      1.75E+03        6.23E+02        3.02E+04        2.79E+03      0.OOE+00      1.02E+00 1-135        2.68E+03      6.97E+03        2.56E+03        4.47E+05        1.11E+04      0.OOE+00      5.24E+03 Cs-134        3.72E+05      8.47E+05        7.27E+05          0.OOE+00      2.87E+05      9.75E+04      1.04E+04 Cs-136        3.90E+04      1.46E+05        1.10E+05          O.OOE+00      8.55E+04      1.20E+04      1.17E+04 Cs-137        4.78E+05      6.20E+05        4.27E+05          0.OOE+00      2.22E+05      7.51E+04      8.39E+03 Cs-138        3.35E+02      6.29E+02        3.28E+02        0.OOE+00        4.86E+02      4.92E+01        1.89E-03 Ba-139        9.48E-01      6.74E-04        2.77E-02        0.OOE+00        6.30E-04      3.81E+03      9.07E+02 Ba-140        3.90E+04      4.90E+01        2.56E+03          0.OOE+00      1.67E+01      1.27E+06      2.18E+05 Ba-141        1.01E-01      7.62E-05        3.40E-03        O.OOE+00      7.09E-05      1.96E+03      1.17E-07 Ba-142        2.66E-02      2.74E-05        1.68E-03        0.OOE+00      2.32E-05      1.21E+03      1.59E-16 La-140        3.48E+02      1.76E+02        4.64E+01          0.OOE+00      0.OOE+00      1.38E+05      4.64E+05 La-142        6.92E-01      3.14E-01        7.82E-02        0.OOE+00      0.OOE+00      6.41E+03      2.14E+03 Ce-141        1.99E+04      1.35E+04        1.53E+03          0.OOE+00      6.25E+03      3.61E+05      1.20E+05 Ce-143        1.89E+02      1.39E+02        1.55E+01          0.OOE+00      6.16E+01      8.08E+04      2.29E+05 Ce-144        3.43E+06      1.43E+06        1.84E+05          0.OOE+00      8.47E+05      7.76E+06      8.15E+05 Pr-143        9.48E+03      3.80E+03        4.70E+02          0.OOE+00      2.19E+03      2.84E+05      2.03E+05 Pr-144        3.05E-02      1.26E-02        1.55E-03        0.OOE+00      7.14E-03      1.03E+03      2.18E-08 Nd-147        5.34E+03      6.17E+03        3.69E+02          0.OOE+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          O.OOE+00      0.00E+00      2.94E+04      1.57E+05 Np-239        2.32E+02      2.28E+01        1.26E+01          0.OOE+00      7.09E+01      3.81E+04      1.21E+05
*R Values in units of mrem/yr per pCi/m3 for inhalation and tritium and in units of mrem/yr per pCi/sec per m2 for all others.
3-61
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                              August 2014 Offsite Dose Calculation Manual (ODCM)                                                                      Rev. 25 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        O.OOE+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        O.OOE+00        O.OOE+00      O.OOE+00      9.27E+04 Cr-51        O.OOE+00      O.OOE+00        1.35E+02        7.49E+01        3.07E+01      2.09E+04      3.OOE+03 Mn-54        O.OOE+00      5.10E+04        8.39E+03        O.OOE+00        1.27E+04      1.98E+06      6.67E+04 Mn-56        O.OOE+00      1.70E+00        2.52E-01        O.OOE+00        1.79E+00      1.52E+04      5.74E+04 Fe-55        3.34E+04      2.38E+04        5.54E+03        O.OOE+00        O.OOE+00      1.24E+05      6.39E+03 Fe-59        1.59E+04      3.69E+04        1.43E+04        O.OOE+00        O.OOE+00      1.53E+06      1.78E+05 Co-57        O.OOE+00      9.44E+02        9.20E+02        O.OOE+00        O.OOE+00      5.86E+05      3.14E+04 Co-58        O.OOE+00      2.07E+03        2.77E+03        O.OOE+00        O.OOE+00      1.34E+06      9.51E+04 Co-60        O.OOE+00      1.51E+04        1.98E+04        O.OOE+00        O.OOE+00      8.71E+06      2.59E+05 Ni-63        5.80E+05      4.34E+04        1.98E+04        O.OOE+00        O.OOE+00      3.07E+05      1.42E+04 Ni-65        2.18E+00        2.93E-01      1.27E-01        O.OOE+00        O.OOE+00      9.36E+03      3.67E+04 Cu-64        O.OOE+00      2.03E+00        8.48E-01        O.OOE+00        6.41E+00      1.11E+04      6.14E+04 Zn-65        3.85E+04        1.33E+05      6.23E+04        O.OOE+00        8.63E+04      1.24E+06      4.66E+04 Zn-69M        1.15E+01      2.71E+01        2.49E+00        O.OOE+00        1.65E+01      3.14E+04      1.71E+05 Zn-69        4.83E-02      9.20E-02      6.46E-03        O.OOE+00        6.02E-02      1.58E+03      2.85E+02 Br-82        O.OOE+00      O.OOE+00        1.82E+04        O.OOE+00        O.OOE+00      O.OOE+00      O.OOE+00 Br-83        O.OOE+00      O.OOE+00        3.44E+02        O.OOE+00        O.OOE+00      O.OOE+00      O.OOE+00 Br-84        O.OOE+00      O.OOE+00        4.33E+02        O.OOE+00        O.OOE+00      O.OOE+00      O.OOE+00 Br-85        O.OOE+00      O.OOE+00        1.83E+01        O.OOE+00        O.OOE+00      O.OOE+00      O.OOE+00 Rb-86        O.OOE+00        1.90E+05      8.39E+04        O.OOE+00        O.OOE+00      O.OOE+00      1.77E+04 Rb-88        O.OOE+00      5.46E+02        2.72E+02        O.OOE+00        O.OOE+00      O.OOE+00        2.92E-05 Rb-89        O.OOE+00      3.52E+02        2.33E+02        O.OOE+00        O.OOE+00      O.OOE+00        3.38E-07 Sr-89        4.34E+05      O.OOE+00        1.25E+04        O.OOE+00        O.OOE+00      2.41E+06      3.71E+05 Sr-90        1.08E+08      O.OOE+00        6.67E+06        O.OOE+00        O.OOE+00      1.65E+07      7.64E+05 Sr-91        8.80E+01      O.OOE+00        3.51E+00        O.OOE+00        O.OOE+00      6.07E+04      2.59E+05 Sr-92        9.52E+00      O.OOE+00        4.06E-01        O.OOE+00        O.OOE+00      2.74E+04      1.19E+05 Y-90        2.98E+03      O.OOE+00        8.OOE+01        O.OOE+00        O.OOE+00      2.93E+05      5.59E+05 Y-91M          3.70E-01      O.OOE+00        1.42E-02        O.OOE+00        O.OOE+00      3.20E+03      3.02E+01 Y-91        6.60E+05      O.OOE+00        1.77E+04        O.OOE+00        O.OOE+00      2.93E+06      4.08E+05 Y-92        1.47E+01      O.OOE+00        4.29E-01        O.OOE+00        O.OOE+00      2.68E+04      1.65E+05 Y-93        1.35E+02      O.OOE+00        3.72E+00        O.OOE+00        O.OOE+00      8.32E+04      5.79E+05 Zr-95        1.45E+05      4.58E+04        3.15E+04        O.OOE+00        6.73E+04      2.68E+06      1.49E+05 Zr-97        1.38E+02      2.72E+01        1.26E+01        O.OOE+00        4.12E+01      1.30E+05      6.30E+05 Nb-95        1.85E+04        1.03E+04      5.66E+03        O.OOE+00        9.99E+03      7.50E+05      9.67E+04 Nb-97        3.14E-01      7.78E-02        2.84E-02        O.OOE+00        9.12E-02      3.93E+03      2.17E+03 Mo-99        O.OOE+00        1.69E+02      3.22E+01        O.OOE+00        4.11E+02      1.54E+05      2.69E+05 Tc-99M        1.38E-03      3.86E-03      4.99E-02        O.OOE+00        5.76E-02      1.15E+03      6.13E+03
*R Values in units of mrem/yr per pCi/m3 for inhalation and tritium and in units of mrem/yr per pCi/sec per m 2 for all others.
3-62
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                August 2014 Offsite Dose Calculation Manual (ODCM)                                                                          Rev. 25 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.OOE+00        1.52E-03      6.67E+02      8.72E-07 Ru-103        2.10E+03      0.OOE+00          8.95E+02        0.OOE+00        7.42E+03      7.82E+05      1.09E+05 Ru-105        1.12E+00        0.OOE+00        4.34E-01        0.OOE+00        1.41E+00      1.82E+04      9.04E+04 Ru-106        9.83E+04        0.OOE+00        1.24E+04        O.OOE+00        1.90E+05      1.61E+07      9.59E+05 Ag-110M        1.38E+04        1.31E+04        7.98E+03        O.OOE+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.OOE+00      3.85E+06      3,98E+05 Sb-125        7.38E+04        8.08E+02        1.72E+04        7.04E+01        0.OOE+00      2.74E+06      9.92E+04 Te-125M        4.88E+03        2.24E+03        6.67E+02        1.40E+03        0.OOE+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 1-130        6.24E+03        1.79E+04        7.17E+03        1.49E+06        2.75E+04      0.OOE+00      9.12E+03 1-131        3.54E+04        4.90E+04        2.64E+04        1.46E+07        8.39E+04      0.OOE+00      6.48E+03 1-132        1.59E+03      4.37E+03        1.57E+03        1.51E+05        6.91E+03      0.OOE+00      1.27E+03 1-133        1.21E+04      2.05E+04        6.21E+03        2.92E+06        3.59E+04      0.OOE+00      1.03E+04 1-134        8.88E+02        2.32E+03        8.40E+02        3.95E+04        3.66E+03      0.OOE+00      2.04E+01 1-135        3.69E+03        9.43E+03        3.48E+03        6.20E+05        1.49E+04      0.OOE+00      6.94E+03 Cs-134        5.02E+05        1.13E+06        5.48E+05        O.OOE+00        3.75E+05      1.46E+05      9.75E+03 Cs-136        5.14E+04        1.93E+05        1.37E+05        0.OOE+00        1.10E+05      1.77E+04      1.09E+04 Cs-137        6.69E+05        8.47E+05        3.11E+05        0.OQE+00        3.04E+05      1.21E+05      8.48E+03 Cs-138        4.66E+02        8.56E+02        4.46E+02        0.OOE+00        6.62E+02      7.87E+01        2.70E-01 Ba-139        1.34E+00      9.44E-04        3.90E-02        0.OOE+00        8.88E-04      6.46E+03      6.45E+03 Ba-140        5.46E+04        6.69E+01        3.51E+03        0.OOE+00        2.28E+01      2.03E+06      2.28E+05 Ba-141        1.42E-01      1.06E-04        4.74E-03        0.OOE+00        9.84E-05      3.29E+03        7.46E-04 Ba-142        3.70E-02      3.70E-05          2.27E-03        0.OOE+00        3.14E-05      1.91E+03        4.79E-10 La-140        4.79E+02        2.36E+02        6.26E+01        O.OOE+00        O.OOE+00      2.14E+05      4.87E+05 La-142        9.60E-01      4.25E-01          1.06E-01        0.OOE+00        0.OOE+00      1.02E+04      1.20E+04 Ce-141        2.84E+04      1.89E+04        2.16E+03        0.OOE+00        8.87E+03      6.13E+05      1.26E+05 Ce-143        2.66E+02      1.94E+02        2.16E+01        0.OOE+00        8.64E+01      1.30E+05      2.55E+05 Ce-144        4.88E+06        2.02E+06        2.62E+05        0.OOE+00        1.21E+06      1.33E+07      8.63E+05 Pr-143        1.34E+04      5.31E+03        6.62E+02        0.OOE+00        3.09E+03      4.83E+05      2.14E+05 Pr-144        4.30E-02      1.76E-02          2.18E-03        0.OOE+00        1.01E-02      1.75E+03        2.35E-04 Nd-147        7.86E+03        8.56E+03        5.13E+02        0.OOE+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.OOE+00        0.OOE+00      4.74E+04      1.77E+05 Np-239        3.38E+02      3.19E+01        1.77E+01        0.OOE+00        1.00E+02      6.49E+04      1.32E+05 3
*R Values in units of mrem/yr per  PCi/m  for inhalation and tritium and in units of mrem/yr per PCi/sec per m-2 for all others.
3-63
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                              August 2014 Offsite Dose Calculation Manual (ODCM)                                                                        Rev. 25 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        O.OOE+O0      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        O.OOE+O0      O.OOE+O0      O.OOE+O0      4.21E+04 Cr-51        O.OOE+O0      O.OOE+O0        1.54E+02        8.53E+01        2.43E+01      1.70E+04      1.08E+03 Mn-54        O.OOE+00      4.29E+04        9.50E+03        O.OOE+00        1.00E+04      1.57E+06      2.29E+04 Mn-56        O.OOE+00      2.46E+00        4.64E-01        O.OOE+00        2.49E+00      1.95E+04      1.83E+05 Fe-55        4.74E+04      2.52E+04        7.77E+03        O.OOE+00      O.OOE+00        1.11E+05      2.87E+03 Fe-59        2.07E+04      3.34E+04        1.67E+04        O.OOE+00      O.OOE+00        1.27E+06      7.06E+04 Co-57        O.OOE+00      9.03E+02        1.07E+03        O.OOE+00      O.OOE+00      5.07E+05      1.32E+04 Co-58        O.OOE+00      1.77E+03        3.16E+03        O.OOE+00        O.OOE+00      1.10E+06      3.43E+04 Co-60        O.OOE+00      1.31E+04        2.26E+04        O.OOE+00        O.OOE+00      7.06E+06      9.61E+04 Ni-63        8.21E+05      4.63E+04        2.80E+04        O.OOE+00        O.OOE+00      2.75E+05      6.33E+03 Ni-65        4.44E+00        4,39E-01        2.44E-01        0.00E+00      O.OOE+00        1.22E+04      1.25E+05 Cu-64        O.OOE+00      2.96E+00        1.60E+00        O.OOE+00        8.97E+00      1.42E+04      5.46E+04 Zn-65        4.25E+04      1.13E+05        7.02E+04        O.OOE+00        7.13E+04      9.94E+05      1.63E+04 Zn-69M        2.34E+01      4.OOE+01        4.72E+00        O.O0E+00        2.32E+01      4.05E+04      1.49E+05 Zn-69        9.96E-02      1.44E-01        1.33E-02        O.OOE+00        8.69E-02      2.11E+03      1.51E+04 Br-82        O.OOE+00      O.OOE+00        3.11E+04        O.OOE+00        O.OOE+00      O.OOE+00      O.OOE+00 Br-83        O.OOE+00      O.OOE+00        7.04E+02        O.OOE+00        O.OOE+00      O.OOE+00      O.OOE+00 Br-84        O.OOE+00      O.OOE+00        8.14E+02        O.OOE+00        O.OOE+00      O.OOE+00      O.OOE+00 Br-85        O.OOE+00      O.OOE+00        3.76E+01        O.OOE+00        O.OOE+00      O.OOE+00      O.OOE+00 Rb-86        O.OOE+00      1.98E+05        1.14E+05        O.OOE+00        O.OOE+00      O.OOE+00      7.98E+03 Rb-88        O.OOE+00      8.36E+02        5.45E+02        O.OOE+00        O.OOE+00      O.OOE+00      2.56E+01 Rb-89        O.OOE+00      5.13E+02        4.31E+02        O.OOE+00        O.OOE+00      O.OE+00        2.81E+00 Sr-89        5,99E+05      O.OOE+00        1.72E+04        O.OOE+00      O.OOE+00        2.15E+06      1.67E+05 Sr-90        1.01E+08      O.OOE+00        6.43E+06        O.OOE+00        O.OOE+00      1.47E+07      3.43E+05 Sr-91        1.80E+02      O.OOE+00        6.82E+00        0.00E+00        O.OOE+00      7.92E+04      2.59E+05 Sr-92        1.95E+01      O.OOE+00          7.81E-01        O.OOE+00        O.OOE+00      3.57E+04      3.60E+05 Y-90        6.11E+03      O.OOE+00        1.64E+02        O.OOE+00        O.OOE+00      3.89E+05      3.98E+05 Y-91M          7.54E-01      O.OOE+00          2.74E-02        O.OOE+00        O.OOE+00      4.18E+03      2.55E+03 Y-91        9.13E+05      O.OOE+00        2.43E+04        O.OOE+00        O.OOE+00      2.62E+06      1.84E+05 Y-92        3.03E+01      O.OOE+00          8.64E-01        O.OOE+00        O.OOE+00      3.55E+04      3.55E+05 Y-93        2.77E+02      O.OOE+00        7.59E+00        O.OOE+00        O.OOE+00      1.11E+05      5.78E+05 Zr-95        1.90E+05      4.17E+04        3.69E+04        O.OOE+00        5.95E+04      2.23E+06      6.10E+04 Zr-97        2.79E+02      4.04E+01        2.38E+01        O.OOE+00        5.78E+01      1.68E+05      5.22E+05 Nb-95        2.35E+04      9.16E+03        6.54E+03        O.OOE+00        8.61E+03      6.13E+05      3.69E+04 Nb-97          6.38E-01      1.14E-01        5.36E-02        O.OOE+00        1.27E-01      5.08E+03      4.14E+04 Mo-99        O.OOE+00      2.56E+02        6.33E+01        O.OOE+00        5.83E+02      2.01E+05      1.88E+05 Tc-99M          2.65E-03      5.18E-03        8.58E-02        O.OOE+00        7.54E-02      1.41E+03      7.15E+03
*R Values in units of mrem/yr per pCi/mr3 for inhalation and tritium and in units of mrem/yr per pCi/sec per m2 for all others.
3-64
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                              August 2014 Offsite Dose Calculation Manual (ODCM)                                                                      Rev. 25 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        O.OOE+00        2.16E-03      8.69E+02      2.43E+01 Ru-103      2.79E+03      0.OOE+00        1.07E+03        0.OOE+00        7.02E+03      6.61E+05      4.47E+04 Ru-105      2.27E+00      0.OOE+00          8.25E-01        0.OOE+00        2.OOE+00      2.37E+04      1.48E+05 Ru-106      1.36E+05      0.OOE+00        1.69E+04        O.OOE+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.OOE+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.OOE+04        1.26E+02        0.OOE+00      3.24E+06      1.64E+05 Sb-125      9.84E+04      7.59E+02        2.07E+04        9.10E+01        0.OOE+00      2.32E+06      4.03E+04 Te-125M      6.73E+03      2.33E+03        9.14E+02        1.92E+03        0.OOE+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.OOE+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 1-130        1.22E+04      2.44E+04        1.25E+04        2.74E+06        3.64E+04      0.OOE+00      7.59E+03 1-131      4.80E+04      4.80E+04        2.72E+04        1.62E+07        7.87E+04      0.OOE+00      2.84E+03 1-132      2.11E+03      4.06E+03        1.87E+03        1.93E+05        6.24E+03      0.OOE+00      3.20E+03 1-133        1.66E+04      2.03E+04        7.68E+03        3.84E+06        3.37E+04      O.OOE+00      5.47E+03 1-134        1.74E+03      3.21E+03        1.48E+03        7.54E+04        4.91E+03      0.OOE+00      1.42E+03 1-135      4.91E+03      8.72E+03        4.14E+03        7.91E+05        1.34E+04      O.OOE+00      4.43E+03 Cs-134      6.50E+05        1.01E+06        2.24E+05        0.OOE+00        3.30E+05      1.21E+05      3.84E+03 Cs-136      6.50E+04        1.71E+05        1.16E+05        0.OOE+00        9.53E+04      1.45E+04      4.17E+03 Cs-137      9.05E+05      8.24E+05        1.28E+05        0.OOE+00        2.82E+05      1.04E+05      3.61E+03 Cs-138      9.41E+02      1.25E+03        8.25E+02        0.OOE+00        9.24E+02      1.01E+02      4.01E+02 Ba-139      2.74E+00        1.46E-03        7.98E-02        0.OOE+00        1.28E-03      8.58E+03      8.58E+04 Ba-140      7.39E+04      6.47E+01        4.32E+03        0.OOE+00        2.11E+01      1.74E+06      1.02E+05 Ba-141        2.91E-01      1.62E-04        9.46E-03        0.OOE+00        1.41E-04      4.34E+03      4.09E+02 Ba-142        7.43E-02      5.35E-05        4.15E-03        0.OOE+00        4.33E-05      2.44E+03      4.08E+00 La-140      9.57E+02      3.34E+02        1.12E+02        0.OOE+00        0.OOE+00      2.72E+05      3.36E+05 La-142        1.93E+00      6.11E-01        1.92E-01        0.OOE+00        0.OOE+00      1.29E+04      1.13E+05 Ce-141      3.92E+04      1.95E+04        2.89E+03        O.OOE+00        8.53E+03      5.43E+05      5.65E+04 Ce-143      5.44E+02      2.95E+02        4.27E+01        O.OOE+00        1.24E+02      1.72E+05      1.89E+05 Ce-144      6.76E+06      2.11E+06        3.61E+05        0.OOE+00        1.17E+06      1.19E+07      3.88E+05 Pr-143        1.85E+04      5.55E+03        9.14E+02        0.OOE+00        3.OOE+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.OOE+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        O.OOE+00        0.OOE+00      6.11E+04      1.35E+05 Np-239      6.93E+02      4.97E+01        3.49E+01        0.O0E+00        1.45E+02      8.64E+04      9.52E+04
*R Valuesin units of mrem/yr per pCi/mr3 for inhalation and tritium and in units of mrem/yr per pCi/sec per m2 for all others.
3-65
 
Shearon  Harris Nuclear      Power Plant (SHNPP)                                                      August 2014 Offsite  Dose Calculation        Manual (ODCM)                                                              Rev. 25 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              O.OOE+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          O.OOE+00      O.OOE+00      O.OOE+00      1.61E+04 Cr-51            O.OOE+00      O.OOE+00      8.93E+01          5.75E+01      1.32E+01      1.28E+04      3.56E+02 Mn-54            O.OOE+00      2.53E+04        4.98E+03          O.OOE+00      4.98E+03      9.98E+05      7.05E+03 Mn-56            O.OOE+00      1.54E+00        2.21E-01        O.OOE+00      1.10E+00      1.25E+04      7.17E+04 Fe-55            1.97E+04      1.17E+04      3.33E+03          O.OOE+00      O.OOE+00      8.69E+04      1.09E+03 Fe-59            1.35E+04      2.35E+04      9.46E+03          O.OOE+00      O.OOE+00      1.01E+06      2.47E+04 Co-57            O.OOE+00      6.51E+02        6.41E+02          O.OOE+00      O.OOE+00      3.79E+05      4.86E+03 Co-58            O.OOE+00      1.22E+03      1.82E+03          O.OOE+00      O.OOE+00      7.76E+05      1.11E+04 Co-60            O.OOE+00      8.01E+03      1.18E+04          O.OOE+00      O.OOE+00      4.50E+06      3.19E+04 Ni-63            3.39E+05      2.04E+04      1.16E+04          O.OOE+00      O.OOE+00      2.09E+05      2.42E+03 Ni-65            2.39E+00      2.84E-01        1.23E-01        O.OOE+00      O.OOE+00      8.12E+03      5.01E+04 Cu-64            O.OOE+00      1.88E+00        7.74E-01        O.OOE+00      3.98E+00      9.30E+03      1.50E+04 Zn-65            1.93E+04      6.25E+04      3.10E+04          O.OOE+00      3.24E+04      6.46E+05      5.13E+04 Zn-69M          1.26E+01      2.58E+01      2.34E+00          O.OOE+00      1.04E+01      2.67E+04      4.09E+04 Zn-69            5.39E-02      9.67E-02        7.18E-03        O.OOE+00      4.02E-02      1.47E+03    1.32E+04 Br-82            O.OOE+00      O.OOE+00      1.33E+04          O.OOE+00      O.OOE+00      O.OOE+00      O.OOE+00 Br-83            O.OOE+00      O.OOE+00      3.81E+02          O.OOE+00      O.OOE+00      O.OOE+00      O.OOE+00 Br-84          O.OOE+00      G.O0E+00      4.OOE+02          O.OOE+00      O.OOE+00      O.OOE+00      O.OOE+00 Br-85          O.OOE+00      O.OOE+00      2.04E+01          O.OOE+00      O.OOE+00      O.OOE+00      O.OOE+00 Rb-86          O.OOE+00      1.90E+05      8.81E+04          O.OOE+00      O.OOE+00      O.OOE+00      3.03E+03 Rb-88          O.OOE+00      5.57E+02      2.87E+02          O.OOE+00      O.OOE+00      O.OOE+00      3.39E+02 Rb-89          O.OOE+00      3.21E+02      2.06E+02          O.OOE+00      O.OOE+00      O.OOE+00      6.82E+01 Sr-89            3.97E+05      O.OOE+00      1.14E+04          O.OOE+00      O.OOE+00      2.03E+06      6.39E+04 Sr-90            4.08E+07      O.OOE+00      2.59E+06          O.OOE+00      O.OOE+00      1.12E+07      1.31E+05 Sr-91            9.56E+01      O.OOE+00      3.46E+00          O.OOE+00      O.OOE+00      5.26E+04      7.34E+04 Sr-92            1.05E+01      O.OOE+00        3.91E-01        O.OOE+00      O.OOE+00      2.38E+04      1.40E+05 Y-90            3.29E+03      O.OOE+00      8.82E+01          O.OOE+00      O.OOE+00      2.69E+05      1.04E+05 Y-91M            4.07E-01      O.OOE+00        1.39E-02        O.OOE+00      O.OOE+00      2.79E+03      2.35E+03 Y-91            5.87E+05      O.OOE+00      1.57E+04          O.OOE+00      O.OOE+00      2.45E+06      7.02E+04 Y-92            1.64E+01      O.OOE+00        4.61E-01        O.OOE+00      O.OOE+00      2.45E+04      1.27E+05 Y-93            1.SOE+02      O.OOE+00      4.07E+00          O.OOE+00      O.OOE+00      7.64E+04      1.67E+05 Zr-95            1.15E+05      2.78E+04      2.03E+04          O.OOE+00      3.10E+04      1.75E+06    2.17E+04 Zr-97            1.50E+02      2.56E+01        1.17E+01        O.OOE+00      2.59E+01      1.10E+05      1.40E+05 Nb-95            1.57E+04      6.42E+03      3.77E+03          O.OOE+00      4.71E+03      4.78E+05      1.27E+04 Nb-97            3.42E-01      7.29E-02        2.63E-02        O.OOE+00      5.70E-02      3.32E+03      2.69E+04 Mo-99          O.OOE+00      1.65E+02      3.23E+01          O.OOE+00      2.65E+02      1.35E+05    4.87E+04 Tc-99M            1.40E-03      2.88E-03        3.72E-02        O.OOE+00      3.11E-02      8.11E+02      2.03E+03
*R Values in units of mrem/yr per pCi/m3 for inhalation and tritium and in units of mrem/yr per gCi/sec per m2 for all others.
3-66
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                              August 2014 Offsite Dose Calculation Manual (ODCM)                                                                        Rev. 25 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.OOE+00        9.79E-04      5.84E+02      8.44E+02 Ru-103          2.01E+03      0.OOE+00        6.78E+02        0.OOE+00      4.24E+03      5.51E+05      1.61E+04 Ru-105          1,22E+00      0.OOE+00        4.10E-01        0.OOE+00        8.99E-01      1.57E+04      4.84E+04 Ru-106          8.67E+04      O.OOE+00        1.09E+04        0.OOE+00        1.06E+05      1.15E+07      1.64E+05 Ag-ll0M          9.97E+03      7.21E+03        4.99E+03        O.OOE+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.OOE+02      0.OOE+00      2.64E+06      5.91E+04 Sb-125          5,17E+04      4.77E+02        1.09E+04        6.23E+01      O.OOE+00      1.64E+06      1.47E+04 Te-125M          4.76E+03      1.99E+03        6.58E+02          1.62E+03      O.OOE+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.OOE+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.OOE-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 1-130            6,36E+03      1.39E+04        5.57E+03          1.60E+06      1.53E+04      O.OOE+00      1.99E+03 1-131            3.79E+04      4.43E+04        1.96E+04          1.48E+07      5.17E+04      O.OOE+00      1.06E+03 1-132            1,69E+03      3.54E+03        1.26E+03          1.69E+05      3.94E+03      O.OOE+00      1.90E+03 1-133            1.32E+04      1.92E+04        5.59E+03          3.55E+06      2.24E+04      O.OOE+00      2.15E+03 1-134            9.21E+02      1.88E+03        6.65E+02          4.45E+04      2.09E+03      O.OOE+00      1.29E+03 1-135            3.86E+03      7.59E+03        2.77E+03          6.95E+05      8.46E+03      0.OOE+00      1.83E+03 Cs-134          3.96E+05      7.02E+05        7.44E+04          O.OOE+00      1.90E+05      7.95E+04      1.33E+03 Cs-136          4.82E+04      1.34E+05        5.28E+04          0.OOE+00      5.63E+04      1.17E+04      1.43E+03 Cs-137          5,48E+05      6.11E+05        4.54E+04          0.OOE+00      1.72E+05      7.12E+04      1.33E+03 Cs-138          5.05E+02      7.81E+02        3.98E+02          0.OOE+00      4.10E+02      6.54E+01      8.76E+02 Ba-139          1.48E+00      9.84E-04        4.30E-02        0.OOE+00      5.92E-04      5.95E+03      5.10E+04 Ba-140          5.59E+04      5.59E+01        2.89E+03          O.OOE+00      1.34E+01      1.59E+06      3.83E+04 Ba-141            1.57E-01      1.08E-04        4.97E-03          0.OOE+00      6.50E-05      2.97E+03      4.75E+03 Ba-142          3.98E-02      3.30E-05        1.96E-03        0.OOE+00      1.90E-05      1.55E+03      6.93E+02 La-140          5,05E+02      2.OOE+02        5.15E+01          0.OOE+00      0.OOE+00      1.68E+05      8.48E+04 La-142          1.03E+00      3.77E-01        9.04E-02        0.OOE+00      O.OOE+00      8.22E+03      5.95E+04 Ce-141          2.77E+04      1.66E+04        1.99E+03          O.OOE+00      5.24E+03      5.16E+05      2.15E+04 Ce-143          2.93E+02      1.93E+02        2.21E+01          0.OOE+00      5.64E+01      1.16E+05      4.97E+04 Ce-144          3.19E+06      1.21E+06        1.76E+05          0.OOE+00      5.37E+05      9.83E+06      1.48E+05 Pr-143          1.40E+04      5.24E+03        6.99E+02          0.OOE+00      1.97E+03      4.33E+05      3.72E+04 Pr-144          4.79E-02      1.85E-02        2.41E-03        0.OOE+00      6.72E-03      1.61E+03      4.28E+03 Nd-147          7.94E+03      8.13E+03        5.OOE+02          O.OOE+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.OOE+00      0.OOE+00      3.96E+04      3.56E+04 Np-239          3.71E+02      3.32E+01        1.88E+01          0.OOE+00      6.62E+01      5.95E+04      2.49E+04
*R Values in units of mrem/yr per PCi/m 3 for inhalation and tritium and in units of mrem/yr per pCi/sec per m2 for all others.
3-67
 
Shearon Harris Nuclear          Power Plant (SHNPP)                                                      May 2011 Offsite  Dose Calculation          Manual (ODCM)                                                            Rev. 23 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                      520      630          520 (kg/yr) 1 Leafy Vegetables (kg/yr)            -          26        42            64 Milk (L/yr)              330          330      400          310 Meat & poultry (kg/yr)            -          41        65          110 Inhalation (m3/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 3-68
 
Shearon      Harris Nuclear      Power Plant (SHNPP)                                                  May 2011 Offsite      Dose Calculation        Manual (ODCM)                                                      Rev. 23 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        1.21 E-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 3-69
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                                        November 2004 Offsite Dose Calculation Manual (ODCM)                                                                                                      Rev. 17 Figure 3.1 SHNPP Gaseous Waste Streams urbine Bldg Vent Stack 3A REM -  Radiation        Effluent        Monitor
                                                        -WPB                              - Waste Processing              Bldg RAB - Reactor Auxiliary Bldg Condenser V--                              -                                FHB - Fuel Handling Bldg Condenser    Polishe  Aet-          _        _    _  _                    WRGM -  Wide Range          Gas Monitor andee      oStem                                                          RM - Radiation Monitor Glend  Steam WPB Vent Stack 5 FRs-lWV-3S46-1  (WHg4)    0RO                        R1-WV34 Hot & Cold Laundry BPs                                                          I.-___________--______-__-__  WEBOffice    rea. Exhaust WEECold Laundry Dryers                                                  _  _4_          _    WE Control Roo      Smuk. Eh.ust WEE Office Areas                                                        __                    WEB General  Area  Exhaust WE Chiller    Room Exhaust                                    "                                Waste Gas Decay Tanks Waste Processing Area Filtered      Exhaust WPB Vent Stack 5A P5-lWV-35d7-l1      e~E WEE Ssitohgeer RoOMExahust-WE HVAt Equip.- Room Exhaust We  Personnel    Handling Facility  Exhaut-0 WEE Hot &Los    Activity  Lahe Exhaust We Lab    Areas ExhaustL IPlant      Vent Stak La    Detection NormaL EKhaust(Ope-. FL) South Noml    Exhaust(Oper. F1) North 3-70
 
Shearon Harris Nuclear Power Plant (SHNPP)                        May 2001 Offsite Dose Calculation Manual (ODCM)                              Rev. 13 Figure 3.2 Schematic of Airborne Effluent Release Points 3-71
 
Shearon Harris Nuclear  Power Plant (SHNPP)                        August 1994 Offsite Dose Calculation  Manual (ODCM)                                Rev. 5 Figure 3.3 SHNPP Condenser Off-Gas System Turbine Building Vent Stack  - 3A Blind Flange 3-72
 
Shearon Harris Nuclear        Power Plant (SHNPP)                                                            March 2007 Offsite Dose Calculation        Manual (ODCM)                                                                    Rev. 19 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, 4.1-3, 4.1-4, and 4.1-5 show the locations                        of the various sampling points            and TLD locations.        Figure 4.1-6 provides a legend for Figures 4.1-2 through 4.1-5.
4-1
 
Shearon    Harris Nuclear      Power Plant (SHNPP)                                                July 2010 Offsite    Dose Calculation      Manual (ODCM)                                                      Rev. 21 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.
2 Analysis Frequency and                                        Weekly Gross Beta Required Analysis:                                            Weekly    1-131 (charcoal canisters) 45 Quarterly Gamma Isotopic ,
(Composited by location)
Sample Point 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.
4            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.      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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                    July 2010 Offsite Dose Calculation Manual (ODCM)                                                          Rev. 21 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 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 ENE sector,      1.9  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 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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                July 2010 Offsite Dose Calculation Manual (ODCM)                                                      Rev. 21 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 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
 
Shearon Harris Nuclear          Power Plant (SHNPP)                                            July 2010 Offsite    Dose Calculation      Manual (ODCM)                                                  Rev. 21 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 ID No.                  Sample Point,    Description1 ,  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            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            Apex (Population Center).
NE sector, 8.7 mi. from site.
35            Holly Springs (Population Center).
E sector, 6.9 mi. from site.
36            SR 1393 at intersection of SR 1421.
E sector, 10.9 mi. from site.
37            US 401 at old CP&L office, Fuquay-Varina            (Pop. Center).
ESE sector, 9.2 mi. from site.
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            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          HE&EC,  Sewage Treatment Facility
_ENE  Sector,  1.2 mi. from site.
4-5
 
Shearon Harris Nuclear          Power Plant (SHNPP)                                          July 2010 Offsite    Dose Calculation      Manual (ODCM)                                                Rev. 21 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 Exposure Pathway and/or Sample:                        Waterborne,  Surface Water Sampling and Collection Frequency:                    Composite sample 5 collected over a monthly period.
Analysis Frequency and Required Analysis:                                    Monthly Gross Beta 4 and Quarterly Gamma Isotopic 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.
 
Shearon Harris Nuclear Power Plant (SHNPP)                                              July 2010 Offsite Dose Calculation Manual (ODCM)                                                    Rev. 21 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 Required Analysis:                                  Each Sample Gamma Isotopic'  and Tritium Sample Point ID No.                  Sample Point,    Descriptioni, 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 68        SHNPP Site (LP-6)
N. of old Steam Generator Storage Building W sector, 0.2 mi. from site SHNPP Site (LP-7)
S. side of Warehouse        9.
NNE sector,    0.2 mi. from site 70        SHNPP Site (LP-9)
N. side of Plant Entrance Road.
E sector, 0.4 mi. from site 71        SHNPP Site (LP-16)
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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                          May 2011 Offsite Dose Calculation Manual (ODCM)                                              Rev. 23 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 Required Analysis:                              Each Sample Gamma Isotopic 4 and Tritium Sample Point ID No.              Sample Point,  Description',  Distance, and Direction SHNPP Site 75        W. of Security Building Entrance ESE sector, 0.1 mi. from site 76      SHNPP Site Inside Owner Controlled Area between Waste Processing Building and Service Building S sector, 0.1 mi. from site SHNPP Site (BD-MWI) 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-MWI6) 83      Along the Cooling Tower Blowdown Line SSW sector, 1.6 mi. from site 4-8
 
Shearon Harris Nuclear            Power Plant (SHNPP)                                            December 1997 Offsite    Dose Calculation        Manual (ODCM)                                                      Rev. 10 TABLE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway and/or Sample:                        Waterborne,  Drinking Water Sampling and Collection Frequency:                    Composite sample 5 collected over a two-week period if 1-131 analysis is performed; monthly composite otherwise.
Analysis Frequency and Required Analysis:                                    1-131 on each composite when the dose 6 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
 
Shearon Harris Nuclear          Power Plant (SHNPP)                                        June, 1994 Offsite    Dose Calculation      Manual (ODCM)                                                Rev. 4 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                                                          4 Required Analysis:                                    Each Sample Gamma Isotopic Sample Point 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.
4-10
 
Shearon Harris Nuclear Power Plant (SHNPP)                                            June, 1994 Offsite Dose Calculation Manual (ODCM)                                                    Rev. 4 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 Required Analysis:                                  Each Sample Gamma Isotopic 4 Sample Point ID No.                Sample Point,  Description',  Distance,  and Direction 52        Harris Lake in the vicinity of the mixing zone of the cooling tower S  sector,    3.8 miles  from site.
4-11
 
Shearon Harris Nuclear          Power Plant (SHNPP)                                          Sept 2010 Offsite    Dose Calculation      Manual (ODCM)                                                Rev. 22 TABLE  4.1 RADIOLOGICAL ENVIRONMENTAL      MONITORING  PROGRAM Exposure Pathway and/or Sample:                        Ingestion - Milk 8 Sampling and Collection Frequency:                    Grab samples semi-monthly when animals are 9on pasture; monthly at other times.
Analysis Frequency and Required Analysis:                                Each Sample 1-131          4 Each Sample Gamma Isotopic Sample Point ID No.                  Sample Point,  Description',    Distance,  and Direction 3
5            Manco's Dairy, Pittsboro      (Control Station)
WNW sector from site, > 12 mi. from site 96            Humbug Farm on SR 1127 ESE sector, 4.6 mi. from site 4-12
 
Shearon Harris Nuclear          Power Plant (SHNPP)                                        August 2014 Offsite    Dose Calculation      Manual (ODCM)                                                Rev. 25 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)
Analysis Frequency                                    Each sample - Gamma Isotopic4 on and Required Analysis:                                edible portion for each Sample Point ID No.                  Sample Point,  Description',    Distance,  and Direction 44            Site varies within the Harris Lake.
45            Site varies above Buckhorn Dam on Cape Fear River (Control Station)
Exposure Pathway and/or Sample:                      Ingestion -  Food Products 7 Sampling and Collection Frequency:                    Samples of 3 different kinds of broadleaf vegetation monthly during the growing season Analysis Frequency                                    Each sample - Gamma Isotopic4 on and Required Analysis:                                edible portion for each Sample Point ID No.                  Sample Point,  Description',    Distance,  and Direction 3
5            Pittsboro    (Control Station)
NNW sector from site,  > 12 mi. from site 97            Granite Springs Farm (Control Station)'
NW sector,  19.1 miles  from site 4-13
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                  Sept 2010 Offsite Dose Calculation Manual (ODCM)                                                        Rev. 22 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 Sampling and Collection Frequency:                    Monthly,  during growing season '5 Analysis Frequency                                                                  4 and Required Analysis:                              Each sample - Gamma Isotopic 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 4-14
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                May 2013 Offsite Dose Calculation Manual (ODCM)                                                      Rev. 24 NOTES TO TABLE 4.1 SHNPP Radiological Environmental  Monitoring Program
: 1.      Sample locations are shown on Figures 4.1-2, 4.1-3, 4.1-4,      and 4.1-5. Figure 4.1-6 provides a legend for Figures 4.1-2 through 4.1-5.
: 2.      Particulate samples will be analyzed for gross beta radioactivity 24        hours 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 hours) 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 crop 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 58 was deleted from groundwater monitoring in Revision 18 since being shown to have direct communication with lake/surface water.
: 11. Sample Locations 68 through 72 were added to the groundwater monitoring in Revision 19 based on evaluation of data from bedrock wells. Location 57 was removed in Revision 19 based on the same evaluation of groundwater data.
: 12. Sample 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 site's  hydrology.
: 15. Broadleaf vegetation refers to deciduous plants, shrubs and trees that have wide, flat  leaves. Typically leaves are only present during the growing season May through October.
4-15
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                      August 2014 Offsite Dose Calculation Manual (ODCM)                                                                                Rev. 25 TABLE 4.2 RADIOLOGICAL      ENVIRONMENTAL        MONITORING    PROGRAM SAMPLING          LOCATIONS Site#      Type      Location Description*          Ac &      I  1W oSW  SS      JSBAV IvFP"'        Fish    Milk  BLV"aI I[I)Mik                                  I    AP 1        I    2.6 miles N                        W/Q W/Q 2        I    1.4 miles NNE 4        I    3.1 miles NNE                      W/Q
                  >12 miles WNW -                    W/Q                    -                                SM/M    M (b) 5        C Pittsboro
                  >12 Miles NNW -
Pittsboro (BLV) 12        I    0.9 miles SSW                                                                                      M-b-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 --                        BW/M    BW/M Lillington 41        1    3.8 miles S                                              SA          A 44        I    Site varies in Harris                                                                SA Lake 45        C    Site varies in Cape                                                                  SA Fear River above Buckhorn Dam 47        1    3.4 miles SSW                      W/Q 51        I    Water Treatment                                    BW/M Building (On Site) 52        1    3.8 miles S                                                    SA 57        1    0.4 miles SSW                                                                                              Q 59        1    0.5 miles NNE                                                                                              Q 60        1    0.5 miles ESE                                                                                              Q 61        C    2.5 miles EA 63        1    0.6 miles SW                      W/Q                                                            M(b) 68        1    0.2 miles W                                                                                                Q 69        1    0.2 miles NNE                                                                                              Q 70        1    0.4 miles E                                                                                                Q 71        1    0.3 miles SE                                                                                                Q 72        1    0.2 miles SE                                                                                                Q 73        1    0.2 miles S                                                                                                Q 74        1    0.2 miles SSE                                                                                              Q 75        1    0.1 miles ESE                                                                                              Q 76        1    0.1 miles S                                                                                                Q 77        1    0.4 miles S                                                                                                Q 78        1    0.5 miles S                                                                                                Q 79        1    0.5 miles S                                                                                                Q 80        1    0.6 miles S                                                                                                Q 81        1    0.6 miles S                                                                                                Q 82        1    0.6 miles S                                                                                                Q 83        1    1.6 miles SSW                                                                                              Q 90        1    0.5 miles SSW                      W/Q 91        1    1.6 miles ENE                      W/Q 96        1    4.6 miles ESE Humbug                                                                      SM/M Farm (not sampled in 2013) 97        C    19.1 miles NW Granite                                                      M ia)
ISprings    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.      CPS 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 4-16
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                    August 2014 Offsite Dose Calculation Manual (ODCM)                                                                            Rev. 25 TABLE  4.3 RADIOLOGICAL    ENVIRONMENTAL          MONITORING PROGRAM        SAMPLING    LOCATIONS (TLD Sites)
SieMeasure ILcto*                  Distance        Sco    [ieMeasure-            Location*      Distance TSector1 Type              i          (miles)                    #        Type                        (miles) 1        IR                              2.6            N      26        OR                          4.7          S 2        IR                              1.4          NNE      27        OR                          4.8        SSW 3        IR                              1.9          ENE      28        OR                          4.8          SW 4        SI          New Hill          3.1          NNE      29        OR                          5.7        WSW (Population Center) 5        C          Pittsboro          >12          WNW      30        OR                          5.6          W 6        IR                              0.8          ENE      31        OR                            4.7        WNW 7        IR                              0.7            E      32        SI      Jordan Lake          6.4        NNW (Population Center) 8        IR                              0.6          ESE      33        OR                            4.5        NNW 9        IR                              2.2            SE      34        SI          Apex            8.7        NE (Population Center) 10        IR                              2.2          SSE      35        SI      Holly Springs        6.9          E (Population Center) 11        IR                              0.6            S      36        SI      Sunset Lake        10.9          E (Population Center) 12        IR                              0.9          SSW      37        SI      Fuquay-Varina        9.2        ESE (Population Center) 13        IR                              0.7          WSW      48        OR                            4.5          N 14        IR                              1.5            W      49          IR                          2.5        NE 15        IR                              2.0            W      50          IR                          2.6        ESE 19        OR                              5.0          NNE      53        OR                            5.8        NW 20        OR                              4.5          NE      56          IR                          3.0        WSW 21        OR                              4.8          ENE      63        IR                          0.6        SW 22        OR                              4.3            E      67        IR                            1.2        ENE 23        OR                              4.8          ESE      93        IR                            2.2        WNW 24        OR                              4.0          SE      94        IR                            2.0        NW 25        OR                              4.7          SSE      95        IR                            2.0        NNW
* 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 4-17
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                        July 2006 Offsite Dose Calculation Manual (ODCM)                                                                Rev. 18 Figure 4.1-1 Ifvp of the Site Boundary 10 SR 101 10 10 Approximate Scale 0          1          2 Kilometers 0          1                2 I  I        I        I Miles 1 - Main Reservoir 2 - Auxiliary Reservoir 3 - Main Dam 4 - Auxiliary Dam Spillway 5 - Plant 6 - Cooling Tower Blowdown Line 7 - Cooling Tower 8 - Site Boundary for Radioactive Liquid Effluents 9 - Site Boundary for Radioactive Gaseous Effluents 10 - Unrestrcted Area B - Boat Ramp W - Wake County - Harris Lake Park 4-18
 
Shearon Harris Nuclear Power Plant (SHNPP)                        August 2014 Offsite Dose Calculation Manual (ODCM)                                Rev. 25 Figure 4.1-2 Environmental Radiological Sampling Points (One Mile Radius) 4-19
 
H(D P. "-
(tO 0ODi cJ t-I H'-
H    HD W (D rt" w H0 10 0
01 (D
:jJ 10 HH H      F W.F--
Hl-  0 0 H-H 10
    '0 H'-
En 0
t-n  Nz~
 
Shearon Harris Nuclear Power Plant (SHNPP)                                      August 2014 Offsite Dose Calculation Manual (ODCM)                                                Rev. 25 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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                      November 2004 Offsite Dose Calculation Manual (ODCM)                                                Rev. 17 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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                    November 2004 Offsite Dose Calculation Manual (ODCM)                                              Rev. 17 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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                        March 2009 Offsite Dose Calculation Manual (ODCM)                                              Rev. 20 Sheet 1 of 4 APPENDIX A Updated by:            Murray and Trettel, Inc.
600 N. First Bank Drive, Suite A Palatine, IL 60067 847-963-9000 x146 Contact Person:        Hasmukh (Hirsh) Shah P.E.      219-322-3456 and 219-742-4447 A-1
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                March 2009 Offsite Dose Calculation Manual (ODCM)                                                        Rev. 20 Sheet 2 of 4 APPENDIX A METEROLOGICAL DISPERSION FACTOR COMPUTATIONS Carolina Power & Light Company (CP&L) now conducting business as Progress Energy Carolinas 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 (USNRC, 1977).
The results of the assessment were to provide the relative depositions 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-advectation 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 Meterological Evaluationof Routine Effluent Releases at Nuclear Power Stations, NUREG/CRG-2919 (USNRC, September 1982) would be used for generating the required analyses of Appendix I. to provide a more realistic accounting of the variability of wind around the plant site, standard terrain /
recirculation correction factors (TCF) were used.
A-2
 
Shearon Harris Nuclear Power Plant (SHNPP)                                            March 2009 Offsite Dose Calculation Manual (ODCM)                                                    Rev. 20 Sheet 3 of 4 APPENDIX A METEROLOGICAL DISPERSION FACTOR COMPUTATIONS A five-year record of meterological data was used from the on-site meterological program at the Shearon Harris Nuclear Power Plant. These data consisted of all collected parameters from the normal 10.0 meter level for all years 2003-2007. The description of the model used and computations are presented in NUREG/CRC-2919. The following tables provide the meterological dilution factors (i.e.; the X/Q and D/Q values) utilized to show compliance with ODCM Operational Requirements 3/4.11.2 for noble gases and radioiodines and particulates.
Tables A-1 through A-4 Relative undepleted concentration, relative depleted concentration, and relative deposition flux estimates for the ground level releases for special locations 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 2003-2007.
A-3
 
Shearon Harris Nuclear Power Plant (SHNPP)                                              May 2013 Offsite Dose Calculation Manual (ODCM)                                                      Rev. 24 Sheet 4 of 4 APPENDIX A METEROLOGICAL DISPERSION FACTOR COMPUTATIONS The NRC XOQDOQ Program was obtained and installed on Murray and Trettle, Inc.'s (M/T) computer system. The Program was run with appropriate physical plant data, appropriate meterological information of the standard distances, and special locations of interest with terrain / recirculation factor. The input to XOQDOQ for the ground level releases are presented in Table A-14. The resulting computations have the TCFs applied to produce a final atmospheric diffusion estimate for the site.
A-4
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                            March 2009 Offsite Dose Calculation Manual (ODCM)                                                                    Rev. 20 Table A-1 through A-4 X/Q and DIQ Values for Long Term Ground Level Releases at Specific Locations XOQDOQ - - SHNPP GROUND LEVEL METEOROLOGICAL DATA, 2003-2007 EXIT ONE - - GROUND LEVEL HISTORICAL DATA, 2003-2007 CORRECTED USING STANDARD OPEN TERRAIN FACTORS SPECIFIC POINTS OF INTEREST RELEASE          TYPE OF    DIRECTION        DISTANCE        TABLE A-  TABLE A-2  TABLE A-3 TABLE A-4 ID        LOCATION      FROM SITE                              I MILES    METERS        X/Q        X/Q        X/Q      DIQ SEC/MA3    SEC/MA3    SECIMA3  PER  MA2 NO      2.3 D      8.0 D DECAY      DECAY      DECAY DEPLETED  DEPLETED Site Boundary      S        1.36      2189      1.1 OE-05  1.1 OE-05  9.30E-06  7.20E-09 Site Boundary    SSW        1.33      2140      1.60E-05  1.60E-05  1.40E-05  1.OOE-08 Site Boundary      SW        1.33      2140      2.30E-05    2.30E-05  2.OOE-05  9.80E-09 Site Boundary    WSW        1.33      2140      1.1 OE-05  1.1 OE-05  9.70E-06  5.50E-09 Site Boundary      W        1.33      2140      4.80E-06    4.60E-06  4.1OE-06  3.OOE-09 Site Boundary    WNW        1.33      2140      3.20E-06    3.OOE-06  2.70E-06  2.30E-09 Site Boundary      NW        1.26      2028      4.OOE-06    3.90E-06  3.40E-06  3.10E-09 Site Boundary    NNW        1.26      2028      4.60E-06    4.50E-06  4.OOE-06  4.20E-09 Site Boundary      N        1.32      2124      6.1OE-06    5.90E-06  5.20E-06  6.10E-09 Site Boundary    NNE        1.33      2140      7.70E-06    7.50E-06  6.60E-06  6.80E-09 Site Boundary      NE        1.33      2140      8.OOE-06    7.70E-06  6.80E-06  7.70E-09 Site Boundary    ENE        1.33      2140      8.70E-06    8.40E-06  7.40E-06  8.60E-09 Site Boundary      E        1.33      2140      6.20E-06    6.OOE-06  5.20E-06  4.70E-09 Site Boundary      ESE      1.33      2140      4.50E-06    4.30E-06  3.80E-06  4.OOE-09 Site Boundary      SE        1.33      2140      5.20E-06  5.OOE-06  4.40E-06  4.80E-09 Site Boundary      SSE      1.33      2140      7.80E-06  7.50E-06  6.60E-06  5.30E-09 Garden          S        5.3      8530      9.1OE-07  7.80E-07  6.40E-07  3.10E-10 Garden        SSW        3.8      6116      2.30E-06  2.OOE-06  1.70E-06  8.40E-10 Garden        SW        2.9      4667      5.30E-06  4.90E-06  4.20E-06  1.50E-09 Garden        WSW        4.5      7242      1.20E-06  1.1OE-06  8.80E-07  3.10E-10 Garden          W        3.1      4989      9.20E-07  8.40E-07  7.10E-07  3.90E-10 Garden        WNW          5      8046      2.60E-07  2.30E-07  1.90E-07  1.OOE-10 Garden        NW        2.4      3862      1.10E-06  1.OOE-06  8.60E-07  6.40E-10 Garden        NNW          2      3219      1.80E-06  1.70E-06  1.40E-06  1.40E-09 Garden          N        2.2      3541      2.1 OE-06  2.OOE-06  1.70E-06  1.70E-09 Garden        NNE        1.9      3058      3.70E-06  3.50E-06  3.OOE-06  2.80E-09 Garden        NE          5      8046      6.30E-07  5.60E-07  4.60E-07  3.50E-10 Garden        ENE        1.8      2897      4.60E-06  4.40E-06  3.80E-06  4.10E-09 Garden          E        1.7      2735      3.70E-06  3.50E-06  3.1OE-06  2.50E-09 Garden        ESE        4.6      7402      4.30E-07  3.80E-07  3.1OE-07  2.20E-10 Garden          SE        2.6      4184      1.40E-06  1.30E-06  1.1OE-06  9.60E-10 Garden        SSE        4.2      6759      9.OOE-07  7.90E-07  6.60E-07  3.50E-10 A-5
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                      Sept 2010 Offsite Dose Calculation Manual (ODCM)                                                              Rev. 22 Table A-1 through A-4 X/Q and DIQ Values for Long Term Ground Level Releases at Specific Locations XOQDOQ - - SHNPP GROUND LEVEL METEOROLOGICAL DATA, 2003-2007 EXIT ONE - - GROUND LEVEL HISTORICAL DATA, 2003-2007 CORRECTED USING STANDARD OPEN TERRAIN FACTORS SPECIFIC POINTS OF INTEREST RELEASE        TYPE OF      DIRECTION      DISTANCE        TABLE A- TABLE A-2  TABLE A-3 TABLE A-ID        LOCATION      FROM SITE                            I                              4 MILES    METERS        XIQ      X/Q        X/Q      DIQ SECIMA3  SEC/MA3    SECIMA3  PER  MA2 NO      2.3 D      8.0 D DECAY    DECAY      DECAY DEPLETED    DEPLETED Meat &Poultry      S        5        8047      1.OOE-06  8.60E-07    7.1OE-07 3.50E-10 Meat &Poultry    SSW        5        8047      1.40E-06  1.20E-06    1.OOE-06 4.60E-10 Meat &Poultry      SW      2.9      4667      5.30E-06  4.90E-06    4.20E-06 1.50E-09 Meat &Poultry    WSW      4.5      7242      1.20E-06  1.1OE-06    8.80E-07 3.10E-10 Meat &Poultry      W      3.1      4989      9.20E-07  8.40E-07    7.10E-07 3.90E-10 Meat &Poultry    WNW        5        8047      2.60E-07  2.30E-07    1.90E-07 1.OOE-10 Meat &Poultry      NW        5        8047      2.90E-07  2.50E-07    2.1OE-07 1.20E-10 Meat &Poultry    NNW        2        3219      1.80E-06  1.70E-06    1.40E-06 1.40E-09 Meat &Poultry      N      2.2      3541      2.1OE-06  2.OOE-06    1.70E-06 1.70E-09 Meat &Poultry    NNE      1.9      3058      3.70E-06  3.50E-06    3.OOE-06 2.80E-09 Meat &Poultry      NE        5        8047      6.30E-07  5.60E-07    4.60E-07 3.50E-10 Meat &Poultry    ENE      1.8      2897      4.60E-06  4.40E-06    3.80E-06 4.1OE-09 Meat &Poultry      E      1.7      2735      3.70E-06  3.50E-06    3.1OE-06 2.50E-09 Meat &Poultry      ESE      4.6      7402      4.30E-07  3.80E-07    3.1OE-07 2.20E-10 Meat &Poultry      SE      2.6      4184      1.40E-06  1.30E-06    1.1OE-06 9.60E-10 Meat &Poultry      SSE      4.2      6759      9.OOE-07  7.90E-07    6.60E-07 3.50E-10 Resident          S      5.3      8530      9.1OE-07  7.80E-07    6.40E-07 3.10E-10 Resident        SSW      3.8      6116      2.30E-06  2.OOE-06    1.70E-06 8.40E-10 Resident        SW      2.9      4667      5.30E-06  4.90E-06    4.20E-06 1.50E-09 Resident        WSW      4.5      7242      1.20E-06  1.10E-06    8.80E-07 3.10E-10 Resident          W        3        4828      9.80E-07  9.OOE-07    7.60E-07 4.20E-10 Resident        WNW      2.5      4023      8.90E-07  8.30E-07    7.10E-07 5,O0E-10 Resident        NW      2.4      3862      1.1OE-06  1.OOE-06    8.60E-07 6.40E-10 Resident        NNW      1.6      2575      2.80E-06  2.70E-06    2.30E-06 2.30E-09 Resident          N      2.2      3541      2.1OE-06  2.OOE-06    1.70E-06 1.70E-09 Resident        NNE      1.9      3058      3.70E-06  3.50E-06    3.OOE-06 2.80E-09 Resident        NE      2.3      3701      2.60E-06  2.40E-06    2.1OE-06 2.OOE-09 Resident        ENE      1.6      2574      5.90E-06  5.70E-06    4.90E-06 5.40E-09 Resident          E      1.7      2735      3.70E-06  3.50E-06    3.10E-06 2.50E-09 Resident        ESE      2.6      4184      1.20E-06  1.1OE-06    9.30E-07 7.80E-10 Resident        SE      2.6      4184      1.40E-06  1.30E-06    1.1OE-06 9.60E-10 Resident        SSE      4.2      6759      9.OOE-07  7.90E-07    6.60E-07 3.50E-10 Cow Milk          N      2.2      3540      2.1OE-06  2.OOE-06    1.70E-06 1.70E-09 Goat Milk        ESE      4.6      7402      4.30E-07  3.80E-07    3.10E-07 2.20E-10
 
Shearon Haris Nuclear Power Plant (SHNPP)                                                                                                                      March 2009 OffsMte Dose Calculation manual (ODCM)                                                                                                                            Rev. 20 TABLE A-6 UNDEPLETED, NO DECAY, X1Q Values for Long Term Ground Level Release at Standard Distances in seclmA3 XOQDOQ - - SHNPP GROUND LEVEL METEOROLOGOCAL DATA, 2003-2007 EXIT ONE - - GROUND-LEVEL HISTORICAL DATA 2003-2007 CORRECTED USING STANDARD OPEN TERRAIN FACTORS Annual Average ChI/Q sec/meter cubed                                              Distance in miles from site sector          0.250          0.500        0.760      1.000          1.600          2.000            2.500          3.000      3.00      4,OO          4500 S          3.010E-04      9.024E-05      4.499E-05  2.236E-05      8.939E-08      5.072E-06        3.328E-08      2.388E-06  1.817E-08  1.444E-06    1.185E-06 SSW          4.444E-04      1.317E-04    6.467E-05  3.172E-05      1.257E-05      7.194E-06        4.749E-06      3.423E-06  2.6172-08  2.087E-06    1.717E-06 SW          6.665E-04      1.949E-04    9.454E-05  4.601E-0S        1.817E-05      1.048E-05        8.959E-06      5.037E-06  3.865E-08  3.091E-06    2.550E-06 WSW          3.145E-04      9.282E-06      4.551E-05  2.235E-05      8.879E-06      5.087E-06        3.361E-08      2.424E-06  1.854E-06  1.479E-08    1.218E-06 W          1.239E-04      3.737E-05      1.870E-05  9.264E-08      3.687E-06      2.088E-06        1.368E-06      9.805E-07  7.460E-07  5.925E-07    4.859E-07 WNW          7.825E-05      2.396E-05      1.217E-05  6.088E-06      2.435E-06      1.368E-08        8.909E-07      6.362E-07  4.813E-07    3.809E-07    3.1115E-07 NW          8.594E-05      2.653E-05      1.358E-05  6.826E-00      2.737E-08      1.631 E-00      9.940E-07      7.068E-07  5.344E-07  4.222E-07    3.447E-07 NNW          9.843E-05      3.012E-05      1.683E-05  7.885E-06      3.165E-06      1.761E-06        1.138E-00      8.065E-07  6.081E-07  4.793E-07    3.904E-07 N          1.406E-04      4.387E-05    2.277E-05  1.154E-05      4.64SE-06      2.582E-06        1.667E-08      1.181E-08  8.897E-07  7.008E-07    6.707E-07 NNE          1.802E-04      5.616E-05    2.919E-05  1.479E-06      6.956E-08      3.313E-06        2.141E-06      1.517E-06  1.144E-06  9.013E-07    7.341E-07 NE          1.885E-04      &798E-05      3.004E-05  1.522E-05      6.134E-06      "$.415E-06        2.209E-00      1.566E-06  1.181E-08  9.309E-07    7.585E-07 ENE          2.120E-04      6.487E-05    3.307E-05  1.671E-05      6.736E-06      3.772E-06        2.449E-08      1.742E-06  1.316E-.0  1.041E-06    8.502E-07 E          1.575E-04      4.754E-05    2.386E-06  1.192E-05      4.780E-06      2.701E-06        1.768E-06      1.283E-06  9.594E-07  7.610E-07    6.234E-07 ESE          1.115E-04      3.399E-05    1.721E-05  8.626E-08      3.459E-06      1.945E-08        1.267E-06      9.039E-07  6.861E-07  5.424E-07    4.436E-07 SE          1.327E-04      4.029E-05    2.016E-05  1.000E-05      3.981E-08      2.248E-0M        l.470E-06      1.051E-06  7.987E-07  6.336E-07    5.191E-07 SSE          2.046E-04      6.142E-05    3.055E-05  1.515E-05      6.043E-08      3.429E-06        2.250E-08      1.614E-06  1.229E-06  9.763E-07    8.012E-07 Annual Average Chi/Q sedmeter cubed                                                Distance in miles from site sector          6.000          7.600        10.000      16.000          20.000          26.000          30.000          35.000    40.000      4,.000        50.000 S          9.963E-07      5.434E-07    3.866E-07  2.221E-07      1.5680E-07      1.188E-07        9.520E-08      7.898E-08  6.721E-08  5.832E-08    5.138E-08 SSW          1.448E-06      7.976E-07      5.417E-07  3.311E-07      2.340E-07        1.790E-07        1.439E-07      1.197E-07  1.021E-07  8.882E-08    7.840E-08 SW          2.155E-08      1.196E-08      8.168E-07  5.025E-07      3.587E-07      2.737E-07        2.208E-07      1.840E-07  1.572E-07  1.369E-07    1.210E-07 WSW          1.027E-06      5.681E-07    3.847E-07  2.353E-07        1.683E-07      1.273E-07        1.023E-07      8.516E-08  7.288E-08  6.319E-08    5.578E-08 W          4.086E-07      2.226E-07      1.501E-07  9.085E-08      6.380E-08      4.858E-08        3.891E-08      3.228E-08  2.747E-08  2.383E-08    2.099E-08 WNW          2.612E-07      1.409E-07    9.437E-08  5.661E-08      3.951E-08      2.995E-08        2.390E-08      1.977E-08  1.678E-08  1.452E-08    1.277E-08 NW          2.886E-07      1.548E-07      1.033E-07  6.167E-08      4.290E-08      3.243E-08        2.683E-08      -1322E-08  1.807E-08  1.562E-08    1.372E-08 NNW          3.264E-07      1.739E-07    1.156E-07  6.851E-08      4.745E-08      3.575E-08        2.840E-08      2.339E-08    1.978E-08  1.708E-08    1.497E-08 N          4.768E-07      2.538E-07    1.683E-07  9.965E-08      6.894E-08      5.190E-08        4.119E-08      3.391E-08  2.887E-08  2.473E-08    2.168E-08 NNE          6.135E-07      3.287E-07    2.169E-07  1.285E-07      8.897E-08      6.699E-08        5.319E-08      4.379E-08  3.703E-08  3.195E-08    2.800E-08 NE        6.341E-07      3.380E-07    2.246E-07  1.332E-07      9.226E-08      6.950E-08        5.520E-08      4.547E-08  3.646E-08  3.319E-08    2.910E-08 ENE          7.121E-07      3.822E-07    2.552E-07  1.524E-07      1.061E-07      8.019E-08        6.388E-08      5.274E-08  4.470E-08  3.865E-08    3.394E-08 E          5.238E-07      2.841E-07    1.911E-07  1.152E-07      8.071E-08      6.133E-08        4.9065E-08    4.063E-08  3.453E-08  2.993E-08    2.634E-08 ESE          3.721E-07      2.008E-07    1.346E-07  8.077E-08      5.641E-08      4.276E-08        3.413E-08      2.823E-08  2.397E-08  2.075E-08    1.824E-08 SE        4.361E-07      2.368E-07    1.593E-07  9.618E-08      6.744E-08      5.129E-08        4.105E-08      3.402E-08  2.893E-08  2.509E-08    2.209E-08 SSE          6.739E-07      3.877E-07    2.482E-07  1.504E-07      1.057E-07      8.0552-08        6.455E-08      5.357E-08  4.580E-08  3.957E-08    3.487E-08 A-7
 
Shearon Haris Nuclear Power Plant (SHNPP)                                                                                                      Novembe March 2009 Offsite Dose Calculation manual (ODCM)                                                                                                            Rev.
Rev. 20 TABLE A-UNDEPLETED, NO DECAY, XIQ Values for Long Term Ground Level Release at Standard Distances in eeclmA3 XOQDOQ -- SHNPP GROUND LEVEL METEOROLOGOCAL DATA, 2003-2007 EXIT ONE- - GROUND-LEVEL HISTORICAL DATA 2003-2007 CORRECTED USING STANDARD OPEN TERRAIN FACTORS Annual Average ChI/Q sec/meter cubed                      NO DECAY, UNDEPLETED Annual Average Chl/Q sec/meter cubed                                                      Distance Inmiles from sIte SEGMENT BOUNDARIES INMILES FROM THE SITE 0.5-1.0            1,0-2.0        2.0-3.0    3.04.0        4.0-5.0      5.0-10.0          10.0-20.0  20.0-30.0 30.0-40.0      40.0-50.0 sector S          4.499E-06        I .020E-06      3.416E-06  1.837E-06      1.192E-06    5.655E-07        2.249E-07  1.193E-07  7.913E-08      5.838E-08 SSW          6.492E-05        1.444E-05      4.871 E-06  2.645E-06      1.727E-06    8.285E-07          3.347E-07  1.798E-07  1.199E-07      8.891E-08 SW          9.628E-05        2.094E-05      7.130E-06  3.905E-06      2.564E-06    1.241E-06        5.076E-07  2.746E-07  1.843E-07      1.370E-07 WSW            4.573E-05        1.019E-05      3.447E-06  1.874E-06      1.224E-06    5.879E-07          2.378E-07  1.277E-07  8.531 E-08    6.325E-08 W            1.866E-05        4.216E-08      1.405E-06  7.545E-07      4.888E-07    2.317E-07          9.199E-08  4.877E-08  3.234E-08      2.386E-08 WNW            1.209E-05        2,773E-06      9.158E-07  4.870E-07      3.134E-07    1.469E-07        5.740E-08  3.008E-08  1.981E-08      1.454E-08 NW            1.346E-05        3.11IOE-06      1.022E.06  5.409E-07      3.469E-07    1.617E-07          6.258E-08  3.258E-08  2.137E-08      1.564E-08 NNW            1.541E-05        3.590E-06      1.171E-06  6.157E-07      3.930E-07    1.818E-07          6.959E-08  3.593E-08  2.345E-08      1.710E-08 N            2.246E-05        5.260E-06      1.717E-06  9.009E-07      5.745E-07    2.653E-07          1.013E-07  5.216E-08  3.399E-08      2.477E-08 NNE          2.878E-05        6.744E-08      2.204E-06  1.158E-06      7.390E-07    3.417E-07          1.306E-07  6.733E-08  4.390E-08      3.199E-08 NE          2.966E-05        6.945E-06      2.273E-06  1.19BE-06      7.635E-07    3.534E-07          1.353E-07  6.985E-08  4.558E-08      3.323E-08 ENE          3.286E-05        7.635E-06      2.519E-06  1.334E-06      8.556E-07    3.991E-07          1.546E-07  8.056E-08  5.286E-08      3.870E-08 E          2.382E-05        5.443E-06      1.814E-06  9.705E-07      6.272E-07    2.960E-07          1.167E-07  6.158E-08  4.071E-08      2.997E-08 ESE          1.713E-05        3.934E-06      1.303E-06  6.933E-07      4.464E-07    2.094E-07          8.190E-08  4.295E-08  2.829E-08      2.077E-08 SE          2.012E-05        4.549E-06      1.510E-06  8.080E-07      5.223E-07    2.466E-07          9.744E-08  5.150E-08  3.409E-08      2.512E-08 SSE          3.056E-05        6.906E-06      2.310E-06  1.242E-06      8.059E-07    3.826E-07          1.523E-07  8.088E-08  5.367E-08      3.962E-08 A-8
 
Shearon Harris Nuclear Power Plant (SHNPP)
March 2009 Offaite Dose Calculation manual (ODCM)
Rev. 20 TABLE A-7 UNDEPLETED, 2.26 Day Decay, X/Q Values for Long Term Ground Level Release at Standard Distances In sechnA3 XOQDOQ - - SHNPP GROUND LEVEL METEOROLOGOCAL DATA, 2003-2007 EXIT ONE - - GROUND-LEVEL HISTORICAL DATA 2003-2007 CORRECTED USING STANDARD OPEN TERRAIN FACTORS Annual Average ChIl/Q aecmeter cubed                                        Distance In miles from site sector          0.250            0.100        0.780      1.000          1.800      2.000              2.600      3.000      &.600      4.000        4.600 s              2.99E-04          8.89E-05    4.40E-05    2.17E-05      8.56E-06    4.79E-06            3.10E-06  2.19E-06    1.64E-06  1.28E-06    1.04E-06 SSW              4.41 E-04        1.30E-04    6.32E-05    3.08E-05        1.20E-05    6.78E-06          4.40E-06  3.13E-06    2.35E-06    1.85E-06    1.50E-06 Sw              6.61 E-04        1.92E-04    9.23E-05    4.46E-05        1.73E-05    9.84E-06          6.43E-06  4.58E-06    3.46E-06    2.72E-06    2.21E-06 wSw              3.12E-04          9.14E-05    4.45E-05    2.17E-05      8.48E-06    4.79E-06            3.11E-06  2.21E-06    1.66E-06  1.31E-06    1.06E-08 w              1.23E-04          3.68E-05    1.83E-05    9.OOE-06      3.53E-06    1.97E-06            1.27E-06  8.99E-07    6.74E-07    5.27E-07    4.26E-07 WNW              7.77E-05          2.36E-05    1.19E-05    5.93E-06      2.34E-06    1.30E-06          8.32E-07  5.85E-07    4.37E-07  3.41E-07    2.75E-07 NW              8.54E-05          2.62E-05    1.33E-05  6.65E-06        2.63E-06    1.45E-06          9.30E-07  6.52E-07    4.86E-07  3.79E-07    3.05E-07 NNW              9.58E-05        2.97E-05      1.53E-05    7.69E-06      3.05E-06    1.67E-06            1.07E-06  7.47E-07    5.56E-07  4.32E-07    3.47E-07 N              1.40E-04        4.33E-05    2.24E-05    1.13E-05      4.48E-06    2.46E-06            1.57E-06  1.09E-06    8.14E-07  6.33E-07    5.09E-07 NNE              1.79E-04        5.54E-05    2.87E-05    1.44E-05      5.74E-06    3.15E-06            2.01E-06  1.41E-06    1.05E-08  8.13E-07    6.53E-07 NE              1.85E-04        5.73E-05    2.95E-05    1.48E-05      5.91E-06    3.25E-06            2.07E-08  1.45E-06    1.08E-06  8.40E-07    6.75E-07 ENE              2.11 E-04        6.40E-05    3.24E-05    1.63E-05      6.48E-06    3.58E-06            2.29E-06  1.61E-06    1.20E-06  9.35E-07    7.53E-07 E              1.56E-04        4.69E-05    2.34E-05    1.16E-05      4.59E-06    2.55E-06            1.65E-06  1.162-06    8.68E-07  6.79E-07    5.48E-07 ESE              1.11E-04        3.35E-05    1,69E-05    8.40E-06        3.32E-06    1.84E-06            1.18E-06  8.32E-07    6.22E-07  4.86E-07    3.922-07 SE              1.32E-04        3.97E-05    1.98E-05    9.74E-06        3.82E-06    2.13E-06            1.37E-06  9.67E-07    7.24E-07  5.66E-07    4.57E-07 SSE              2.03E-04        6.05E-05    2.99E-05    1.47E-05        5.79E-06    3.24E-06            2.09E-06  1.48E-06    1.11E-06  8.68E-07    7.02E-07 Annual Average ChlQ saec/meter cubed                                        Distance Inmiles from site sector            11000            7.600        10.000      16.000        20.0m        2.000 50.000                        28A0        40.000    46.000      80.000 S              8.60E-07        4.36E-07    2.73E-07    1.43E-07        8.68E-08    5.74E-08            4.01E-08  2.91E-08    2.17E-08  1.66E-08    1.29E-08 SSW              1.24E-06        6.34E-07    3.99E-07    2.09E-07        1.27E-07    8.38E-08            5.83E-08  4.20E-08    3.12E-08  2.37E-08    1.842-08 SW              1.84E-06        9.41E-07    5.93E-07    3.11E-07        1.89E-07    1.24E-07            8.59E-08  6.16E-08    4.55E-08  3.43E-08    2.63E-08 WSW              8.79E-07          4.48E-07    2.82E-07    1.48E-07        8.96E-08    5.90E-08            4.09E-08  2.95E-08    2.18E-08  1.652-08    1.281-08 W              3.53E-07          1.79E-07    1.12E-07    5.84E-08        3.55E-08    2.35E-08            1.64E-08  1.19E-08    8.85E-09  6.76E-09    5.27E-09 WNW              2.27E-07          1.14E-07    7.12E-08    3.71E-08        2.26E-08    1.50E-08            1.05E-08  7.64E-09    5.74E-09  4.41E-09    3.46E-09 NW              2.52E-07          1.26E-07    7.85E-08    4.08E-08        2.48E-08    1.65E-08            1.16E-08  8.44E-09    6.35E-09  4.90E-09    3.86E-09 NNW              2.87E-07          1.43E-07    8.88E-08    4.62E-08        2.82E-08    1.88E-08            1.32E-08  9.71E-09    7.35E-09  5.71E-09    4.52E-09 N              4.19E-07          2.09E-07    1.30E-07    6.77E-08        4.13E-08    2.76E-08            1;95E-08  1.43E-08    1.09E-08  8.48E-09    6.74E-09 NNE              5,39E-07        2.69E-07      1.67E-07    8.69E-08        5.30E-08    3.53E-08            2.49E-08  1.83E-08    1.39E-08  1.08E-08    8.57E-09 NE              5.572-07          2.78E-07    1.73E-07    9.01E-08        5.50E-08    3.67E-08            2.59E-08  1.90E-08    1.45E-08  1.12E-08    8.92E-;09 ENE              6.22E-07          3.12E-07    1.95E-07    1.02E-07        6.20E-08    4.13E-08            2.91E-08  2.13E-08    1.61E-08  1.25E-08    9.88E-09 E              4.54E-07          2.29E-07    1.43E-07    7.47E-08        4.55E-08    3.01E-08            2.11E-08  1.53E-08    1.15E-08  8.80E-09    6.89E-09 ESE              3.24E-07          1.63E-07    1.02E-07    5.31E-08        3.23E-08    2.15E-08            1.51E-08  1.10E-08    8.286-09  6.361-09    5.00E-09 SE              3.78E-07          1.91E-07    1.20E-07    6.25E-08        3.81E-08    2.53E-08            1.77E-08  1.29E-08    9.63E-09  7.40E-09    5.79E-09 SSE              5.82E-07        2.94E-07      1.84E-07    9.64E-08        5.86E-08    3.87E-08            2.70E-08  1.98E-08    1.46E-08  1.11E-08    8.67E-09 A-9
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                                                      March 2009 Offsite Dose Calculation manual (ODCM)                                                                                                              Rev. 20 TABLE A- 8 UNDEPLETED, 2.26 DAY DECAY, XIQ Values for Long Term Ground Level Release at Standard Distances In seclmA3 XOQDOO -- SHNPP GROUND LEVEL METEOROLOGOCAL DATA, 2003-2007 EXIT ONE - - GROUND-LEVEL HISTORICAL DATA 2003-2007 CORRECTED USING STANDARD OPEN TERRAIN FACTORS Annual Average Chi/O sac/meter cubed                    2.26 DAY DECAY, UNDEPLETED Annual Average Chi/M sac/meter cubed                                                        Distance inmiles from site SEGMENT BOUNDARIES IN MILES FROM THE SITE 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 sector S            4.410E-05        9.813E-06      3.184E-06  1.661E-06        1.045E-06    4.577E-07          1.468E-07  5.831E-08  2.940E-08      1.676E-08 SSW          6.358E-05        1.386E-05      4.525E-06  2.381 E-06      1.507E-06    6.646E-07          2.147E-07  8.510E-08  4.255E-08      2.396E-08 SW            9.322E-05        2.006E-05      8.598E-06  3.497E-06        2.223E-06    9.856E-07        3.195E-07  1.261E-07  8.238E-08      3.464E-08 wSw            4.477E-05        9.773E-06      3.197E-06  1.684E-06        1.066E-06    4.701E-07          1.516E-07  5.991 E-08 2.983E-08      1.671 E-08 w            1.829E-05        4.055E-06      1.310E-06  6.823E-07        4.289E-07    1.876E-07        8.007E-08  2.383E-08  1.200E-08      6.827E-09 WNW            1.186E-05        2.672E-06      8.567E-07  4.425E-07        2.767E-07    1.202E-07        3.824E-08  1.521 E-08 7.727E-09      4.452E-09 NW            1.321E-05        3.OOOE-06      9.579E-07  4.926E-07        3.071E-07    1.328E-07        4.209E-08  1.674E-08  8.538E-09      4.945E-09 NNW            1.514E-05        3.469E-06      I.101E-06  5.631E-07        3.499E-07    1.507E-07        4.767E-08  1.907E-08  9.818E-09      5.755E-09 N            2.208E-05        5.085E-06      1.614E-06  8.250E-07        5.123E-07    2.206E-07        6.979E-08  2.801E-08  1.450E-08      8.549E-09 NNE          2.828E-05        6.516E-06      2.071E-06  1.059E-06        6.580E-07    2.834E-07        8.965E-08  3.590E-08  I.853E-08      1.089E-08 NE            2.915E-05        8.711E-06      2.137E-06  1.094E-06        8.800E-07    2.932E-07        9.291E-08  3.72SE-08  1.925E-08      1.133E-08 ENE          3.227E-05        7.368E-06      2.362E-06  1.216E-06        7.587E-07    3.287E-07        1.046E-07  4.190E-08  2.154E-08      1.259E-08 E            2.336E-05        5.240E-06      1.693E-06  8.793E-07        5.51 7E-07    2.407E-07        7.692E-08  3.058E-08  1.549E-08      8.883E-09 ESE          1.681E-05        3.793E-06      1.219E-06  6.302E-07        3.943E-07    1.714E-07        5.468E-08  2.179E-08  1.110E-08      6.420E-09 SE            1.974E-05        4.383E-06      1.411 E-06  7.332E-07        4.602E-07    2.009E-07        6.435E-08  2.564E-08  1.300E-08      7.464E-09 SSE          2.996E-05        6.640E-06      2.152E-06  1.123E-06        7.066E-07    3.093E-07        9.916E-08  3.932E-08  1.978E-08      1.124E-08 A-10
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                                                                March 2009 Offsite Dose Calculation manual (ODCM)                                                                                                                          Rev. 20 TABLE A - 9 DEPLETED, 8.0 Day Decay, X/Q Values for Long Term Ground Level Release at Standard Distances In sechnA3 XOQDOQ - - SHNPP GROUND LEVEL METEOROLOGOCAL DATA, 2003-2007 EXIT ONE - - GROUND-LEVEL HISTORICAL DATA 200342007 CORRECTED USING STANDARD OPEN TERRAIN FACTORS Annual Average ChI/0 seotmeter cubed                                                Distance In miles from site sector          0.250            0.600          0.760      1.0oo          1.600            2.000              2.600      3.000    3.600      4.,00          4.600 s          2.842E-04        8.207E-05        3.985E-05  1.942E-05      7.5002-06        4.132E-06          2.641E-06  1.849E-06  1.377E-06  1.072E-06      8.627E-07 ssw          4.197E-04        1.197E-04      5.726E-05  2.753E-05      1.0542-05        5.856E-06          3.766E-06  2.650E-06  1.981E-06 1.547E-06        1.249E-06 sw          6.294E-04          1.772E-04      8.368E-05  3.992E-05      1.523E-05        8.525E-08          5.512E-06  3.895E-06 2.922E-06  2.288E-06        1.851E-06 wSw          2.970E-04        8.439E-05      4.029E-05  1.940E-05      7.444E-06        4.140E-06          2.664E-06  1.876E-06  1.403E-06 1.096E.06      8.848E-07 w          1.171E-04        3.399E-05        1.657E-05 8.044E-06      3.0932-06        1.701E-06          1.086E-08  7.598E-07 5.655E-07  4.400E-07      3.539E-07 WNW          7.391E-05        2.179E-05        1.079E-05 5.289E-06      2.04412-1016      1.115E-06          7.077E-07  4.928E-07 3.653E-07  2.833E-07      2.272E-07 NW          8.118E-05        2.414E-05        1.203E-05 5.931E-06      2.299E-06        1.249E-06          7.900E-07  5.487E-07 4.059E-07  3.142E-07      2.516E-07 NNW        9.11OE-05        2.741EE-05      1.385E-05 6.854E-06      2.659E-06        1.437E-06          9.052E-07  6.267E-07 4.624E-07  3.572E-07      2.855E-07 N          1.328E-04        3.992E-05      2.018E-05  1.003E-05      3.904E-06        2.108E-06          1.327E-06  9.178E-07 6.768E-07  5.225E-07      4.175E-07 NNE        1.702E-04        5.110E-05      2.588E-05  1.285E-05      5.004E-06        2.704E-06          1.703E-06  1,179E-06 8.698E-07  6.717E-07      5.368E-07 NE        1.762E-04        5.276E-05      2.663E-05  1.323E-05      5.154E-06        2.788E-06          1.757E-06  1.217E-06 8.981E-07  6.939E-07      5.547E-07 ENE        2.002E-04        5.902E-05      2.931E-05  1.452E-05      5.658E-06        3.077E-06          1.947E-06  1.353E-06 1.001E-06  7.752E-07      6.210E-07 E          1.488E-04        4.324E-05      2.113E-05  1.036E-05      4.012E-06        2.201E-06          1.402E-06  9.791E-07 7.277E-07  5.655E-07      4.543E-07 ESE        1.053E-04        3.092E-05      1.525E-05  7.494E-06      2.904E-06        1.588E-06          1.007E-06  7.013E-07 5.201E-07  4.035E-07      3.237E-07 SE          1.254E-04        3.665E-05      1.786E-05  8.689E-06      3.342E-06        1.833E-06          1.167E-06  8.154E-07 6.061E-07  4.710E-07      3.785E-07 SSE        1.933E-04        5.585E-05      2.708E-05  1.315E-05      5.070E-06        2.793E-06          1.785E-06  1.250E-06 9.311E-07  7.249E-07      5.833E-07 Annual Average Chil/ seclmeter cubed                                                Distance In miles from site sector            6.000            7.500          10.000    1.000          20.000          26.000              30.000    35.00    40.00      48.000=        5.000 S          7.123E-07        3.596E-07      2.263E-07  1.215E-07      7.6812E-08        5.309E-08          3.884E-08  2.955E-08 2.315E-08  1.853E-06      1.510E-08 SSW          1.034E-06        5.266E-07      3.333E-07  1.803E-07      1.145E-07        7.937E-08          5.818E-08  4.434E-08 3.476E-08  2.785E-08      2.270E-08 Sw          1.535E-06        7.878E-07      5.010E-07  2.725E-07      1.7352-07        1.205E-07          8.845E-08  6.745E-08 5.290E-08  4.240E-08      3.456E-08 wsw          7.326E-07        3.734E-07      2.365E-07  1.280E-07      8.124E-08        5.631E-08          4.127E-08  3.144E-06 2.465E-08  1.974E-08      1.609E-08 w          2.921E-07        1.473E-07      9.265E-08  4,972E-08      3.1412E-08        2.170E-08          1.587E-08  1.208E-08 9.457E-09  7.571E-09      6.169E-09 WNW          1.871E-07        9.350E-08      5.846E-08  3.114E-08      1.9592-08        1.349E-08          9.848E-09  7.482E-09 5.853E-09  4.684E-09      3.815E-09 NW          2.069E-07        1.029E-07      6.412E-05  3.401E-08      2.1332-08        1.487E-08          1.070E-08  8.118E-09 6.347E-09  5.076E-09      4.134E-09 NNW          2.344E-07        1.158E-07      7.192E-08  3.797E-08      2.375E-08        1.630E-06          1.187E-08  9.006E-09 7.040E-09  5.630E-09      4.586E-09 N          3.426E-07        1.691E-07      1.049E-07  5.532E-08      3.459E-08        2.374E-08          1.729E-08  1.311E-08 1.025E-08  8.202E-09      6.682E-09 NNE          4.406E-07        2.177E-07      1.351E-07  7.128E-08      4.457E-08        3.059E-08          2.227E-08  1.689E-08 1.320E-08  1.056E-08      8.603E-09 NE          4.554E-07        2.252E-07      1.399E-07  7.387E-08      4,622E-08        3.174E-08          2.312E-08  1.754E-08 1.371E-08  1.097E-08      8.939E-09 ENE          5.107E-07        2.542E-07      1.585E-07  8.416E-08      5.285E-08        3.638E-08          2.654E-08  2.016E-08 1.578E-08  1.263E-08      1.029E-08 E          3.747E-07        1.883E-07      1.181E-07  6.320E-08      3.986E-08        2.751E-08          2.010E-08  1.529E-08 1.197E-08  9.580E-09      7.805E-09 ESE          2.666E-07        1.333E-07      8.339E-08  4.445E-08      2.797E-08        1.928E-08          1.408E-08  1.070E-08 8.373E-09  6.702E-09      5.460E-09 SE          3.122E-07        1.570E-07      9.856E-08  5.279E-08      3.332E-08        2.301E-08          1.683E-08  1.280E-08 1.003E-08  8,031E-09      6.545E-09 SSE          4.817E-07        2.432E-07      1.531E-07  8.225E-08      5.200E-08        3.594E-08          2.630E-08  2.001E-08 1.567E-08  1.255E-08      1.022E-08 A-Il
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                                                      March 2009 Rev. 20 Offsite Dose Calculation manual (ODCM)
TABLE A - 10 DEPLETED, 8.000 DAY DECAY, X/Q Values for Long Term Ground Level Release at Standard Distances In secdmA3 XOQDOQ -- SHNPP GROUND LEVEL METEOROLOGOCAL DATA, 2003-2007 EXIT ONE -- GROUND-LEVEL HISTORICAL DATA 2003-2007 CORRECTED USING STANDARD OPEN TERRAIN FACTORS Annual Average Chi/Q sec/meter cubed                      8.000 DAY DECAY, DEPLETED Annual Average ChI/Q sechneter cubed                                                        Distance In miles frm site SEGMENT BOUNDARIES IN MILES FROM THE SITE 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 sector S          4.015E-05        8.651E-06      2.722E-06  1.396E-06        8.690E-07      3.787E-07          1.249E-07  5.372E-08 2.976E-08    1.863E-08 SSW          5.793E-05        1.223E-05      3.877E-06  2.007E-06        1.258E-06      5.534E-07          1.851E-07  8.026E-08 4.464E-08    2.799E-08 SW          8.501E-05        1.774E-05      5.668E-06  2.959E-06        1.864E-06      8.265E-07          2.793E-07  1.218E-07 6.791E-08    4.261E-08 WSW          4.081E-05        8.633E-06      2.742E-06  1.421E-06        8.910E-07      3.924E-07          1.313E-07  5.694E-08 3.168E-08    1.984E-08 W            1.685E-05        3.575E-06      1.120E-06  5.732E-07        3.565E-07      1.552E-07          5.112E-08  2.196E-08 1.216E-08    7.611E-09 WNW          1.D79E-05        2.352E-06      7.305E-07  3.705E-07        2:290E-07      9.873E-08          3.208E-08  1.366E-08 7.538E-09    4.708E-09 NW          1.201E-05        2.639E-06      8.159E-07  4.118E-07        2.536E-07      1.088E-07          3.507E-08  1.486E-08 8.179E-09    5.104E-09 NNW          1.375E-05        3.048E-06      9.356E-07  4.693E-07        2.878E-07      1.227E-07          3.919E-08  1.652E-08 9.076E-09    5.661E-09 N          2.006E-05        4.467E-06      1.371E-06  6.869E-07        4.209E-07      1.791E-07          5.712E-08  2.405E-08 1.322E-08    8.246E-09 NNE          2.569E-05        5.726E-06      1.760E-06  8.827E-07        5.412E-07      2.305E-07          7.359E-08  3.099E-08 1.703E-08    1.062E-08 NE          2.648E-05        5.897E-06      1.816E-06  9.114E-07        5.592E-07      2.384E-07          7.625E-08  3.215E-08 1.768E-08    1.103E-08 ENE          2.934E-05        6.480E-06      2.011E-08  1.016E-06        6.258E-07      2.687E-07          8.677E-08  3.684E-08 2.032E-08    1.270E-08 E          2.126E-05        4.617E-06      1.446E-06  7.377E-07        4.578E-07      1.985E-07          6.503E-08  2.784E-08 1.540E-08    9.630E-09 ESE          1.529E-05        3.338E-06      1.039E-06  5.275E-07        3.262E-07      1.407E-07          4.578E-08  1.952E-08 1.078E-08    6.737E-09 SE          1.796E-05        3.859E-06      1.204E-08  6.144E-07        3.813E-07      1.655E-07          5.431E-08  2.329E-08 1.290E-08    8.072E-09 SSE          2.728E-05        5.855E-06      1.840E-06  9.437E-07        5.876E-07      2.562E-07          8.455E-08  3.637E-08 2.015E-08    1.261E-08 A- 12
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                                                                      March 2009 Offsite Dose Calculation manual (ODCM)                                                                                                                              Rev. 20 TABLE A - 11 Deposition Values (DIQ) for Long Term Ground Level Release at Standard Distances In I1mA2 XOQDOQ - - SHNPP GROUND LEVEL METEOROLOGOCAL DATA, 2003-2007 EXIT ONE - - GROUND-LEVEL HISTORICAL DATA 2003-2007 CORRECTED USING STANDARD OPEN TERRAIN FACTORS
                              .      RELATIVE DEPOSITION PER UNIT AREA (MA -2) AT FIXED POINTS BY DOWNWIND SECTORS Annual Average D/0 1 / mA 2                                                        Distance In miles from site sector          0.250            0.600          0.760          1.000            1.800          2.000              2.600      3.000      3.600      4.000        4.600 S        1.915E-07        6.476E-08      3.325E-08      1.581E-08      5.678E-09      2.816E-09          1.658E-09    1.086E-09  7.639E-10  5.661E-10    4.363E-10 SSW        2.548E-07        8.616E-08      4.424E-08      2.103E-08      7.555E-09      3.747E-09          2.206E-09    1.445E-09  1.016E-09  7.533E-10    5.805E-10 SW        2.452E-07        8.292E-08      4.258E-08      2.024E-08      7.271E-09      3.606E-09          2.123E-09    1.390E-09  9.782E-10 7.250E-10    5.587E-10 WSW          1.378E-07        4.660E-08      2.393E-08      1.137E-08      4.086E-09      2.026E-09          1.193E-09  7.812E-10  5.497E-10 4.074E-10    3.139E-10 W          7.486E-08        2.531 E-08      1.300E-08      6.179E-09      2.219E-09      1.101E-09          6.481E-10  4.244E-10  2.986E-10  2.213E-10    1.705E-10 WNW          5.750E-08        1.945E-08      9.984E-09      4.747E-09        1.705E-09      8.455E-10          4.979E-10  3.260E-10  2.294E-10  1.700E-10'  1.310E-10 NW        6.729E-08        2.275E-08      1.168E-08      5.554E-09      1.995E-09      9.894E-10          5.826E-10  3.815E-10  2.684E-10  1.989E-10    1.533E-10 NNW        9.252E-08        3.129E-08      1.606E-08      7.637E-09      2.743E-09      1.360E-09          8.011E-10  5.245E-10  3.691E-10  2.735E-10    2.1082-10 N        1.487E-07        5.028E-08      2.582E-08      1.227E-08      4.409E-09      2.186E-09          1.287E-09  8.430E-10  5.932E-10  4.396E-10    3.388E-10 NNE        1.702E-07        5.755E-08      2.955E-08      1.405E-08      5.046E-09      2.502E-09          1.473E-09  9.648E-10  6.789E-10  5.031E-10    3.877E-10 NE        1.91 3E-07      6.468E-08      3.321E-08      1.579E-08      5.672E-09      2.813E-09          1.656E-09  1.084E-09  7.631E-10  5.655E-10    4.358E-10 ENE        2.148E-07        7.265E-08      3.730E-08      1.773E-08      6.370E-09      3.159E-09          1.860E-09  1.218E-09  8.570E-10  6.351E-10    4.894E-10 E        1.165E-07        3.939E-08      2.022E-08      9.615E-09      3.454E-09      1.713E-09          1.009E-09  6.604E-10  4.647E-10  3.444E-10    2.654E-10 ESE        9.932E-08        3.35BE-08      1.724E-08      8.198E-09      2.945E-09      1.460E-09          8.599E-10  5.630E-10  3.962E-10  2.938E-10    2.263E-10 SE        1.209E-07        4.089E-08      2.100r-08      9.981E-09      3.585E-09      1.778E-09          1.047E-09  6.855E-10  4.824E-10  3.575E-10    2.755E-10 SSE        1.328E-07        4.491E-08      2.306E-08      1.096E-08      3.938E-09      1.953E-09          1.150E-09  7.530E-10  5.298E-10  3.926E-10    3.026E-10 Annual Average D/0 I I m 112                                                        Distance In miles from site.
sector          G.000            7.500          10.000        15.000          20.000          25.000              30.000      36.000    40.000    48.000        60.000 S        3.466E-10        1.540E-10      9.327E-11      4.714E-11        2.853E-11      1.913E-11          1.371E-11  1.029E-11  8.003E-12  6.393E-12    5.218E-12 SSW        4.612E-10        2.049E-10      1.241E-10      6.273E-11        3.797E-11      2.545E-11          1.824E-11  1.370E-11  1.065E-11  8.506E-12    6.943E-12 SW        4.438E-10        1.972E-10      1.194E-10      6.037E-11        3.654E-11      2.450E-11          1.755E-11  1.318E-11  1.025E-11  8.187E-12    6.682E-12 WSW        2.494E-10        1.108E-10      6.711E-11      3.392E-11        2.053E-11      1,377E-11          9.864E-12  7.407E-12  5.759E-12  4.600E-12    3.755E-12 W        1.355E-10        6.019E-1 1      3.646E-1 1      1.843E-11      1.115E-11      7.478E-12          5.358E-12  4.024E-12  3.128E-12  2.499E-12    2.040E-12 WNW          1.041E-10        4.623E-1 1    2.801E-11        1.416E-1 1      8.568E-12      5.745E-12          4.116E-12    3.091E-12  2.403E-12  1.920E-12    1.567E-12 NW        1.218E-10        5.410E-11      3.277E-11      1.656E-11      1.003E-11      6.722E-12          4.817E-12    3.617E-12  2.812E-12  2.246E-12    1.833E-12 NNW        1.675E-10        7.439E-1 1    4.506E-11      2.278E-11        1.379E-11      9,243E-12          6.623E-12    4.973E-12  3.867E-12  3.089E-12    2.521E-12 N        2.691E-10        1.196E-10      7.242E-11      3.661E-11        2.216E-11      1.485E-11          1.064E-11  7.993E-12  6.214E-12  4.964E-12    4.052E-12 NNE        3.080E-10        1.368E-10      8.288E-11      4.189E-11        2.536E-11      1.700E-11          1.218E-11  9.147E-12  7.112E-12  5.681E-12    4.637E-12 NE        3.462E-10        1.538E-10      9.316E-11      4.709E-11        2.850E-11      1.911E-11          1.369E-11    1,028E-11  7.994E-12  6.386E-12    5.212E-12 ENE        3.888E-10        1.727E-10      1.046E-10      5.289E-11        3.201E-11      2.146E-11          1.538E-11    1.155E-11  8.979E-12  7.172E-12    5.854E-12 E        2.108E-10        9.365E-1 I    5.673E-11      2.868E-11        1.736E-11      1.164E-11          8.338E-12    6.261E-12  4.868E-12  3.889E-12    3.174E-12 ESE        1.797E-10        7.985E-11      4.837E-11      2.445E-11        1.480E-11      9.921E-12          7.109E-12    5.338E-12  4.151E-12  3.316E-12    2.706E-12 SE        2.189E-10        9.722E-11      5.889E-11      2.977E-11        1.802E-11      1.208E-11          8.656E-12    6.500E-12  5.054E-12  4.037E-12    3.295E-12 SSE        2.404E-10        1.068E-10      6.469E-11      3.270E- 11      1.979E-11      1.327E-11          9.507E-12    7.139E-12  5.551E-12  4.434E-12    3.619E-12 A-13
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                                                        March 2009 Offsite Dose Calculation manual (ODCM)                                                                                                                Rev. 20 TABLE A - 12 Deposition Values (DIQ) for Long Term Ground Level Release at Standard Distances In 11mA2 XOQDOQ -- SHNPP GROUND LEVEL METEOROLOGOCAL DATA, 2003-2007 EXIT ONE - - GROUND-LEVEL HISTORICAL DATA 2003-2007 CORRECTED USING STANDARD OPEN TERRAIN FACTORS
                  .....        "... RELATIVE DEPOSITION PER UNIT AREA (M A -2) AT FIXED POINTS BY DOWNWIND SECTORS *      *.*
* SEGMENT BOUNDARIES IN MILES FROM THE SITE 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 sector S          3.250E-08      6.657E-09      1.738E-09      7.805E-10        4.415E-10      1.698E-10  4.912E-11    1  9.470E-12  1.040E-11      6.435E-12 SW            4.324E-08      8.857E-09    2.312E-09        1.039E-09        5.875E-10      2.259E-10  6.536E-11    2  5.900E-12  1.383E-11      8.562E-12 SW          4.162E-08      8.524E-09    2.225E-09        9.995E-10        5.654E-10      2.174E-10  6.290E-11    2  4.930E-12  1.331E-11      8.240E-12 wSW            2.339E-08      4.790E-09      1.250E-09      5.616E-10        3.177E-10      1.222E-10  3.535E-11    1  4.010E-12  7.481E-12      4.630E-12 w            1.270E-08      2.602E-09    6.793E-10        3.051E-10        1.726E-10      6.637E-11  1.920E-11  7  6.100E-13  4.064E-12      2.515E-12 WNW            9.759E-09      1.999E-09    5.218E-10        2.344E-10        1.326E-10      5.099E-11  1.475E-11  5  8.460E-13  3.122E-12      1.932E-12 NW            1.142E-08      2.339E-09    6.106E-10        2.742E-10        1.551E-10      5.966E-11  1.726E-11    6  8.410E-13  3.653E-12      2.261E-12 NNW          1.570E-08      3.216E-09    8.396E-10        3.771E-10        2.133E-10      8.204E-11  2.373E-11    9  4.060E-13  5.023E-12      3.109E-12 N          2.524E-08        5.169E-09      1.349E-09      6.061E-10        3.429E-10      1.318E-10  3.814E-11    1  5.120E-12  8.073E-12      4.997E-12 NNE          2.888E-08        5.916E-09    1.544E-09      6.936E-10        3.924E-10      1.509E-10  4.365E-11    1  7.300E-12  9.239E-12      5.719E-12 NE          3.248E-08        6.649E-09    1.736E-09      7.796E-10        4.410E-10      1.696E-10  4.907E-11    1  9.450E-12  1.038E-11      6.428E-12 ENE          3.646E-08        7.468E-09    1.950E-09      8.756E-10        4.954E-10      1.905E-10  5.511E-11    2  1.840E-12  1.166E-1I      7.219E-12 E            1.977E-08      4.049E-09    1.057E-09      4.748E-10        2.686E-10      1.033E-10  2.988E-11    1  1.840E-12  6.324E-12      3.914E-12 ESE          1.685E-08      3.452E-09    9.013E-10      4.048E-10        2.290E-10      8.806E-11  2.548E-11    1  1.000E-13  5.392E-12      3.337E-12 SE          2.052E-08        4.203E-09    1.097E-09      4.928E-10        2.788E-10      1.072E-10  3.102E-11    1  2,290E-12  6.565E-12      4.063E-12 SSE          2.254E-08        4.617E-09    1.205E-09      5.413E-10        3.062E-10      1.178E-10  3.407E-11    1  3.500E-12  7.211E-12      4.463E-12 A-14
 
March 2009 Shearon Harris Nuclear Power Plant (SHNPP)
Rev. 20 Offaite Dose Calculation manual (ODCM)
TABLE A-13 Joint Wind Frequency Distribution by Pasquill Stability Classes at SHNPP XOODOQ -- SHNPP GROUND LEVEL METEOROLOGOCAL DATA. 2003-2007 Joint Wind Frequency Distribution of Wind Speed and Wind Direction. Wind Speeds In meters per Second.
Atmospheric Stability Class A UMAX          N        NNE        NE      ENE        E        ESE        SE      SSE          S      SSW        SW      WSW      W    WNW    NW    NNW      TOTAL 0.36    0.000      0.000      0.000    0.000  0.000      0.000    0.000    0.000      0.000    0.000      0.000    0.000  0.000  0.000  0.000  0.000    0.000 1.56    0.002      0.000      0.000    0.000    0.000      0.000    0.000    0.002      0.002    0.002      0.000    0.002  0.000  0.000  0.000  0.000    0.012 3.35    0.007      0.019      0.063    0.061    0.030      0.016    0.007    0.012      0.035    0.033      0.021    0.047  0.030  0.000  0.009  0.009    0.398 5.59    0.000      0.028      0.051    0.002    0.002      0.000    0.000    0.000      0.002    0.007      0.014    0.023  0.007  0.000  0.000  0.000    0.137 8.27      0.000      0.007      0.000    0.000    0.000      0.000    0.000    0.000      0.000    0.000      0.000    0.000  0.000  0.000  0.000  0.000    0.007 10.95    0.000      0.000      0.000    0.000    0.000      0.000    0.000    0.000      0.000    0.000      0.000    0.000  0.000  0.000  0.000  0.000    0.000 15.65      0.000      0.000    0.000    0.000    0.000      0.000    0.000    0.000      0.000    0.000      0.000    0.000  0.000  0.000  0.000  0.000    0.000 TOTAL      0.010      0.060    0.110    0.060    0.030      0.020    0.010    0.010      0.040    0.040      0,030    0.070  0.040  0.000  0.010  0.010    0.550 Atmospheric Stability Class B UMAX        N        NNE        NE      ENE        E        ESE      SE        SSE        S      SSW          SW      WSW      W    WNW    NW    NNW    TOTAL 0.35      0.000      0.000    0.000    0.000    0.000      0.000    0.000    0.000      0.000    0.000      0.000    0.000  0.000  0.000  0.000  0.000    0.000 1.56    0.014      0.009    0.000    0.005    0.014      0.005    0.002    0.007      0.005    0.015      0.012    0.007  0.002  0.007  0.007  0.005    0.116 3.35      0.049      0.137    0.161    0.102    0.095      0.033    0.021    0.049      0.137    0.098      0.112    0.249  0.082  0.023  0.051  0.044    1.444 5.59      0.009      0.079    0.058    0.002    0.000      0.000    0.000    0.002    0.005    0.014      0.042    0.063  0.054  0.033  0.009  0.005    0.375 8.27      0.000      0.002    0.005    0.000    0.000      0.000    0.000    0.000    0.000    0.000      0.000    0.000  0.000  0.000  0.000  0.000    0.007 10.95      0.000      0.000    0.000    0.000    0.000      0.000    0.000    0.000    0.000    0.000      0.000    0.000  0.000  0.000 0.000  0.000    0.000 15.65      0.000      0.000    0.000    0.000    0.000      0.000    0.000    0.000    0.000    0.000      0.000    0.000  0.000  0.000 0.000  0.000    0.000 TOTAL      0.070      0.230    0.220    0.110    0.110      0.040    0.020    0.080    0.150    0.130      0.170    0.320  0.140  0.060 0.070  0.050    1.940 Atmospheric Stability Class C UMAX        N        NNE        NE      ENE      E        ESE      SE        SSE        S      SSW        SW      WSW      W    WNW      NW    NNW    TOTAL 0.36      0.000    0.000      0.000    0.000    0.000      0.000    0.000    0.000      0.000    0.000      0.000      0.001 0.000  0.000  0.000  0.000    0.005 1.56    0.065      0.040      0.047    0.040    0.035    0.030    0.049    0.047    '0.086    0.061      0.040    0.100  0.033  0.047 0.063  0.065    0.845 3.35    0.195      0.312      0.340    0.233    0.105    0.070    0.086    0.126      0.324    0.235      0.333    0.741  0.265  0.154  0.277  0.298    4.094 5.59    0.044      0.114      0.075    0.012    0.002    0.002    0.002    0.000      0.007    0.026      0.049    0.1568 0.070  0.072  0.077  0.049    0.759 8.27    0.000      0.007      0.000    0.000    0.000    0.000    0.000    0.000      0.000    0.000      0.000    0.000  0,000  0.009  0.000  0.000    0.016 10.95    0.000      0.000      0.000    0.000    0.000    0.000    0.000    0.000      0.000    0.000      0.000    0.000  0.000  0.000  0.000  0.000    0.000 15.65    0.000      0.000      0.000    0.000    0.000    0.000    0.000    0.000      0.000    0.000      0.000    0.000  0.000  0.000  0.000  0.000    0.000 TOTAL      0.310      0.470      0.460    0.280    0.140      0.100    0.140    0.170      0.420    0.320      0.420    1.000  0.370  0.280  0.420  0.410    5.720 Atmospheric Stability Class D UMAX          N        NNE        NE      ENE        E        ESE        SE      SSE        S      SSW          SW      WSW      W    WNW    NW    NNW      TOTAL 0.36      0.085      0.062    0.060    0.047    0.042      0.034    0.044    0.049      0.088    0.083      0.077    0.063  0.044  0.036  0.044  0.055    0.873 1.56    1.109      1.057      1.027    0.806    0.710      0.575    0.755    0.838      1.120    1.409      1.313    1.074  0.752  0.619  0.750  0.934    14.847 3.35      1.994      2.972      1.740    0.962    0.440      0.424    0.442    0.782      1.225    1.118      1.581    1.912  0.932  0.769  1.395  1.302    19.966 5.59      0.263      0.708    0.419    0.100    0.007      0.007    0.023    0.118    0.170    0.121      0.305    0.452  0.245  0.522  0.624  0.261    4.343 8.27      0.012      0.072    0.007    0.000    0.000      0.000    0.000    0.002    0.002    0.000      0.016    0.012  0.007  0.044  0.028  0.000    0.203 10.95    0.000      0.000    0.000    0.000    0.000      0.000    0.000    0.000    0.000    0.000      0.000    0.000  0.000  0.000  0.000  0.000    0.000 15.65    0.000      0.000    0.000    0.000    0.000      0.000    0.000    0.000    0.000    0.000      0,000    0.000  0.000  0.000  0.000  0.000    0.000 TOTAL      3.440      4.870    3.250    1.920    1.200      1.040    1.260    1.770    2.680    2,730      3.290    3.510  1.980  1.990  2.840  2.550    40.230 A-IS
 
March 2009 Shearon Haeis Nuclear Power Plant (SHNPP)
Offsite Dose Calculation manual (ODCM)                                                                                                                      Rev. 20 TABLE A- 13 Joint Wind Frequency Distribution by Pasqulfl Stability Classes at SHNPP XOQDOQ -- SHNPP GROUND LEVEL METEOROLOGOCAL DATA 2003-2007 Joint Wind Frequency Distribution of Wind Speed and Wind Direction. Wind Speeds In meter per Second.
Atmospheric Stability Class E UMAX        N        NNE        NE      ENE        E        ESE      SE      SSE          S      SSW        SW      WSW      W  WNW    NW    NNW      TOTAL 0.38 0.239        0.212      0.196    0.157  0.123      0.104    0.128    0.186      0.256    0.361      0.331    0.257  0.141 0.124  0.093  0.143    3.051 1.56 1.109        0.983      0.913    0.731  0.571      0.484    0.594    0.888      1.188    1.679    1.539    1.195  0.654 0.575  0.431  0.664    14.176 3.35 0.610        0.769      0.373    0.233  0.165      0.126    0.109    0.265      0.694    0.727    0.973      0.966  0.384 0.331 0.331  0.282    7.338 5.59 0.026        0.061      0.081    0.009  0.000      0.002    0.007    0.005      0.047    0.058    0.102      0.095  0.033 0.047 0.028  0.005    0.585 8.27 0.000        0.000      0.009    0.000    0.000      0.000    0.000    0.000      0.000    0.000    0.000      0.007  0.005 0.002 0.009  0.005    0.037 10.95 0.000        0.000    0.000    0.000    0.00D      0.000    0.000    0.000      0.000    0.000    0.000      0.000  0.000 0.000 0.000  0.000    0.000 15.65 0.000        0.000    0,000    0.000    0.000      0.000    0.000    0.000      0.000    0.000    0.000      0.000 0.000  0.000 0.000  0.000    0.000 TOTAL        1.980      2.020      1.550    1.130  0.810      0.720    0.840    1.320      2.180    2.830    2.950      2.520  1.220 1.080 0.890  1.100  25.190 Atmospheric Stability Class F UMAX        N        NNE        NE      ENE      E          ESE      SE      SSE        S      SSW        SW      WSW      W  WNW    NW    NNW    TOTAL 0.36 0.422      0.330      0.313    0.283    0.127      0.112    0.146    0.161      0.285    0.345    0.382    0.478  0.270  0.191 0.165  0.270    4.278 1.56 0.524      0.410      0.389    0.352    0.158      0.140    0.182    0.200      0.354    0.429    0.475    0.592  0.335  0.238 0.205  0.335    5.317 3.35 0.077      0.040      0.007    0.012    0.000      0.005    0.005    0.007      0.030    0.026    0.012    0.100  0.012  0.009 0.007  0.009    0.358 5.59 0.000      0.000      0.000    0.000    0.000      0.000    0.000    0.000      0.000    0.000    0.000    0.000  0.000  0.000 0.000  0.000    0.000 8.27 0.000      0.000      0.000    0.000    0.000      0.000    0.000    0.000      0.000    0.000    0.000    0.000  0.000  0.000 0.000  0.000    0.000 10.95 0.000        0.000      0.000    0.000    0.000      0.000    0.000    0.000      0.000    0.000    0.000    0.000  0.000  0.000 0.000  0.000    0.000 15.65 0.000        0.000      0.000    0.000    0.000      0.000    0.000    0.000      0.000    0.000    0.000    0.000  0.000  0.000 0.000  0.000    0.000 TOTAL        1.020    0.780      0.710    0.650    0.290      0.260    0.330    0.370      0.670    0.800    0.870    1.170  0.620  0.440 0.380  0.810    9.950 Atmospheric Stability Class 0 UMAX        N        NNE        NE      ENE      E        ESE      SE      SSE          S      SSW        SW      WSW      W    WNW    NW    NNW      TOTAL 0.36 1.134        2.028      3.383    1.426    0.478      0.248    0.239    0.230      0.301    0.399      0.416    0.540  0.631  0.345 0.487  0.788    12.974 1.58 0.298      0.533      0.890    0.376    0.126      0.065    0.063    0.061      0.079    0.105      0.109    0.142  0.140  0.091 0.128  0.207    3.412 3.35 0.002        0.012      0.002    0.000    0.000      0.000    0.000    0.002      0.000    0.000      0.002    0.002  0.002  0.000 0.002  0.000    0.028 5.69 0.000        0.000      0.000    0.000    0.000      0.000    0.000    0.000      0.000    0.000      0.000    0,000  0.000  0.000 0.000  0.000    0.000 8.27 0.000        0.000      0.000    0.000    0.000      0,000    0.000    0.000      0.000    0.000      0.000    0.000  0.000  0.000 0.000  0.000    0.000 10.95 0.000        0.000      0.000    0.000    0.000      0.000    0.000    0.000      0.000    0.000      0.000    0.000  0.000  0.000 0.000  0.000    0.000 15.85 0.000        0.000      0.000    0.000    0.000      0.000    0.000    0.000      0.000    0.000      0.000    0,000  0.000  0.000 0.000  0.000    0.000 TOTAL        1.430      2.570    4.280      1.800  0.600      0.310    0.300    0.290      0.380    0.500      0.530    0.680  0,670  0.440 0.620  1.000    16.410 OVERALL WIND DIRECTION FREQUENCY N        NNE          NE . ENE        E        ESE      SE      SSE          S    SSW        SW      WSW      W    WNW    NW    NNW      TOTAL 8.30      11.00      10.60    5.90    3.20        2.50    2.90    4.00        6.40    7.30      8.30      9.30  5.00  4.30  5.20    5.70    100.00 A- 16
 
March 2009 Shearon Harris Nuclear Power Plant (SHNPP)                                                                                                          Rev. 20 Offaite Dose Calculation manual (ODCM)
TAeLE A - 13 Joint Wind Frequency Distribution by Pasquill Stability Classes at SHNPP XOQDOQ -- SHNPP GROUND LEM METEOROLOGOCAL DATA.200-2007 Period of Record:        01/01/2003 to 12/31/2007 Total hours considered are:        42939    hours Overall Wind Speed Frequency Max Wind Speed, MIS                0.368    1.665    3.353      5.588    8.270 10.952    15.646 Average Wind Speed, M/S            0.179    0.961    2.459        4.470    6.929  9.611    13.299 Wind Speed Frequency              21.180    38.720    33.620      6.200    0.270  0.000      0.000 Conversion Factor applied to the Wind Speed is        0.447 Distances and Terrain Heights in Meters as Function of Direction from the Site.
Direction      S        SSW        SW      WSW        W        WNW        NW    NNW          N      NNE        NE      ENE  E  ESE  SE  SSE Distance      2189      2140      2140      2140    2140        2140      2028  2124      2140      2140      2140      2140 2140 2140 2140  2140 Vent and Building Parameters:
Release Height                      0.0  Meters Diameter                            0.0  Meters Exit Velocity                      0.0  Meters Rep. Wind Height                  10.0  Meters Building Height                    55.0  Meters Bldg. Min. Cre. Sec. Area        2141.0 Sq. meters Heat Emission Rate                  0.0  Cal/Sec All Ground Level Releases Wind Measured at 12.0 Meters.
A-17
 
Shearon Harris Nuclear Power Plant (SHNPP)                                          August 1995 Offsite Dose Calculation Manual (ODCM)                                                  Rev. 6 TABLE A-14 Shearon Harris Plant Site Input Information for Continuous Ground Level Releases Calculations with the NRC XOQDOQ Program Card Type  [ Columns  Variable Name      Format                                Description                          Value used in L                I      [XOQDOQ      I                                                              I 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(l)          Ii        Option to distribute calms as the first wind-speed class              0 (if calms are already distributed by direction in Card Type 6, KOPT(l) = 0, and Card Type 5 is blank). If KOPT(l) = 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)          Ii          Option to input joint frequency distribution data as                0 percent frequency.
1          3      KOPT(3)          II          Option to compute a sector spread for comparison with                1 centerline value in purge calculation (Normally = 1).
1          4      KOPT(4)          II        Option to plot short-term X/Q values versus probability                0 of occurrence  (Normally = 0).
1          5      KOPT(5)          II            Option to use cubic spline in lieu of least square                0 function for fitting intermittent release distribution (Normally = 1).
1            6      KOPT(6)          Ii            Option to punch radial segment X/Q and D/Q values                1 (Normally = 1).
1            7      NOPT(7)          Il            Option to punch output of X/Q and D/Q values of the                1 points of interest (Normally = 1).
1          8      KOPT(8)          Ti          Option to correct X/Q and D/Q values for open terrain                1 recirculation.
1          9      KOPT(9)          II        Option to correct X/Q and D/Q values using site specific              0 terrain recirculation data.
A-18
 
Shearon Harris Nuclear Power Plant (SHNPP)                                            August 1995 offsite  Dose Calculation Manual (ODCM)                                                    Rev. 6 TABLE A-14 Shearon  Harris Plant Site Input Information for Continuous Ground Level Releases Calculations with the NRC XOQDOQ Program Card Type    Columns    Variable Name      Format                              Description                      Value used in XOQDOQ 1        I0        KOPT(10)          Ii    Option to use desert sigma curves      (Normally = 0)                0 1        11        KOPT(11)          Ii    Option to calculate annual X/Q with 30 degree sectors                0 for North, East, 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).              7 3      6 -  10      NSTA            I5    The number of stability      categories (maximum of 7)  (1          7 always equals Pasquill stability      class A, 2 = B.
7 = G).
3    11 -    15      NDIS            15    The number of distances with terrain data for each                    1 sector. The number of distances must be the same for each sector (Card Type 10) (maximum of 10).
3    16 -    20      INC            T5    The increment in percent for which plotted results are              15 printed out (Normally = 15).
3    21 -    25    NPTYPE            15    The number of titles    of receptor types (cow,  garden,            5 etc.)  (Card Type 13)  (maximum of eight) 3    26 -    30    NEXIT            15    The number  of release exit points    (maximum of five).            1 3    31  -  35      NCOR            15    The number of distances of site      specific correction              1 factors for recirculation (maximum of 10).
4      1 -  5      PLEV          F5.0    The height (in meters, above ground level) of the                  12.0 measured wind presented in the joint frequency data (Card Type 7).    (For elevated/ground-level mixed release, use the 10-meter level winds).
A-19
 
Shearon Harris Nuclear Power Plant (SHNPP)                                          August 1995 Offsite Dose Calculation Manual (ODCM)                                                    Rev. 6 TABLE A-14 Shearon  Harris Plant Site Input Information for Continuous Ground        Level Releases Calculations with the NRC XOQDOQ Program 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              101.00 I = 1,3                    calculations: if DECAYS > 100, no decay will        occur; if            2.30 DECAYS < 0, depletion factor will be used in        the X/Q            -8.00 calculations; if DECAYS = 0, X/Q will not be calculated.      (Normally, DECAYS(l) = 101, (2)    = 2.26, (3) = -8.00.)
4      21 -  25        PLGPAD          F5.0    Plant grade elevation (feet above sea level).          If                0.00 PLGRAD = 0.0, DIST and 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 PLGPAD > 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                      BLANK I = 1,NSTA                  stability    category; if KOPT(l) = 0, insert      blank card.
(Note: I = 1 is stability      class A, 2 = B ....      7 = G).
6        1 -  80  FREQ(K,I,J)                    The joint frequency distribution in hours (or percent).                  (1)
K = 1,16                        The values for 16 (K) sectors are read on each card for I = 1,NVEL (if                  each combination of wind-speed class (I) and stability KOPT(1)=0)                      class (J).      The loop to read these value cycles first I = 2,NVEL (if                  on direction continuing in a clockwise fashion), then KOPT(1)=l)                      on wind class and finally on stability      class.
J = 1,NSTA 7        1 -  5          UCOR            F5.0    A correction factor applied to wind-speed classes.            If          200.
UCOR < 0: nocorrections will be made.        If UCOR > 100:
the wind-speed classes will be converted from miles/hour to meters/second.
A-20
 
Shearon Harris Nuclear Power Plant (SHNPP)                                      August 1995 Offsite Dose Calculation Manual (ODCM)                                                Rev. 6 TABLE A-14 Shearon Harris  Plant Site Input Information for Continuous Ground Level Releases Calculations with the NRC XOQDOQ Program Description                      [  Value used in XOQDOQ 14F5.0    The maximum wind speed in each wind-speed class,        0.75, 3.50, 7.50, 12.50, in either miles/hour or meters/second,      (If  given      16.50, 25.00, 26.00 in miles/hour, set UCOR > 100.)
Card Types 8 and 9 are read    in for each  correction factor and distance given,    I = l,NCOR 8      1 - 80      VRDIST(K,I)      16F5.0    The distance in meters at which correction factors          All Distances = 1.0 K = 1,16                    are given. These 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              All Factors = 1.000 K = 1,16                    values corresponds 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 = l,NDIS 10      1 - 80        DIST(K,I)        16F5.0    The distance in meters at which terrain heights          Distance = Site Boundary K = 1,16                    are given. These values are read in beginning                  Distance 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            All Heights = 0.0 K = 1,16                    level) 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-21
 
Shearon Harris Nuclear Power Plant (SHNPP)                                              August 1995 Offsite Dose Calculation Manual (ODCM)                                                        Rev. 6 TABLE A-14 Shearon Harris  Plant Site Input Information for Continuous Ground            Level Releases Calculations with the NRC XOQDOQ Program Card Type  Columns      Variable Name    j    Format  ]                              Description                          Value used in    XOQDOQ 12      1 - 25          NPOINT(I)            S'S      The number (maximum of 30) of receptor locations for a                16, 15, 13,2,0, 11 I    I,NPTYPE 1                          particular receptor type (such as the number of cows, d T                                              gardens, or site        boundaries).
Card Types 13 and 14 are read in    for each receptor type, thus I b,NPTYPE =
13      1 - 16        TITLPT&#xfd;I,2)            4A4      The title      (cows, gardens, etc.) of the receptor type          Site Boundary = 16 for the receptor locations (Card Type 14) (a maximum of            Nearest Resident = 15 16 spaces).                                                            Garden = 13 Cow Milkl      2 Goat Milk = 0 Meat & Poultry = 11 14      1 - 80          KDIR(I,N)        8(I5,F5.0)  The receptor direction and distance.            KDIR is the            See  Table A-i PTDIST(I,N)                    direction of interest,        such that 1 = South, 2-N = l,NPOINT(T)                    SSW ......        16 = SSE, PTDIST is the distance, in meters, to the receptor location.
Card Types  13 and 14 are repeated    for the  remaining receptor types.
plant    release point,    thus I = 1,NEXIT.
The title      for the release point whose characteristics                  (1) are described on Card Types 16 and 17.
The vent average velocity (meters/second).            (Note: if a              0 100% ground-level release is assumed, set EXIT = 0, DIAMTR = 0, and SLEV = 10 meters).
The vent inside diameter          (meters).                                    0 The height of the vent release point (meters, plant                          0.0 grade level).        If release is 100% elevated, input negative of height.
The height of the vent's          building  (meters, above plant            55.0 grade level).
A-22
 
Shearon Harris Nuclear Power Plant (SHNPP)                                            August 1995 Offsite Dose Calculation Manual (ODCM)                                                      Rev. 6 TABLE A-14 Shearon Harris  Plant Site Input Information for Continuous Ground        Level Releases Calculations with the NRC XOQDOQ Program Card Type    Columns 2
Variable  Name 1FFormat                              Description                          Value used in XOQDOQ 16      21 -    25            CRSEC(I)          F5.0    The minimum cross-sectional      area for  the vent's            2161.0 building (square meters).
16      26 -    30            SLEV(I)            F5.0    The wind height used for the vent elevated        release          10.0 (meters, above plant grade level).
16      31 -    35            HEATR(I)          F5.0      The vent heat emission rate      (cal/sec)  (Normally = 0).      0.0 17          1                RLSID(I)            Al      A one letter  identification    for the  release point.              A 17        2 -    5            IPURGE(I)            24      IPURGE = 1, 2 or 3 if    the vent has intermittent                    0 releases. The 1, 2, or 3 corresponds to DECAYS(l(,
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)            15    The number of intermittent      releases per year for this            0 release point.
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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                      August 2014 Offsite Dose Calcilation Manual (ODCM)                                              Rev. 25 APPENDIX B                        Sheet  1  of  15 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 10CFR5O 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 P.--
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 m3 /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.
B-1
 
Shearon Harris Nuclear Power Plant (SHNPP)                                          August 2014 Offsite Dose Calculation Manual (ODCM)                                                  Rev. 25 APPENDIX B                          Sheet  2  of  15 DOSE PARAMETERS FOR RADIOIODINES,    PARTICULATES,    AND TRITIUM B.1    Calculation of Pi    (continued)
The dose factor  from the inhalation pathway is    calculated by P      =      K'(BR)  DFA1                                                              (B.1-1) where:
P      =      Dose factor for radionuclide    "i" for the inhalation pathway,    mrem/yr per ii 3
gCi/m ,  per organ of interest K'    =      A constant of unit conversion;
      =      106 pCi/&#xfd;ICi; BR    =      The breathing  rate of the children's age group,    m3/yr; DFA1  =      The organ inhalation dose factor    for the children's age group for radionuclide "i,"  mrem/pCi.
The incorporation of breathing rate of a child    (3700 m3 /yr)  and the unit conversion factor results in the following equation:
P      =      3.7 E+09 DFA1                                                            (B.1-2) 1I B-2
 
Shearon Harris Nuclear                Power Plant (SHNPP)                                                        August 1995 Offsite      Dose Calculation            Manual (ODCM)                                                                  Rev. 6 APPENDIX B                                      Sheet    3  of  15 DOSE PARAMETERS      FOR RADIOIODINES,              PARTICULATES,      AND TRITIUM 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-3
 
Shearon Harris Nuclear Power Plant (SHNPP)                                              August 1994 Offsite Dose Calculation Manual (ODCM)                                                        Rev. 5 APPENDIX B                            Sheet  4  of  15 DOSE PARAMETERS FOR RADIOIODINES,        PARTICULATES,    AND TRITIUM 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.1I    =      Dose factor for each identified radionuclide        "i"    of the organ of 3
interest,    mrem/yr per gCi/m ;
K'      =      A constant of unit conversion;
        =    106 pCi/gCi; (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.
Age Group      (a)                      Breathing Rate    (m3/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-4
 
Shearon Harris Nuclear Power Plant (SHNPP)                                              June 1994 Offsite Dose Calculation Manual (ODCM)                                                      Rev. 4 APPENDIX B                          Sheet  5  of  15 DOSE PARAMETERS    FOR RADIOIODINES,    PARTICULATES,  AND TRITIUM B.2.2  Ground Plane Pathway The ground plane pathway dose factor is        calculated by:
t
      =      I. K'K"(SF)DFG    (1 - e -X i)/    i                                      (B.2-2) where:
R.iG  =      Dose factor for the ground plane pathway for each identified radionuclide "i"  for the organ of interest,      mrem/yr per pCi/sec per m K'    =      A constant of unit conversion;
      =      1 0 6 pCi/ACi; 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.)
DFGi  =      The ground plane dose conversion factor for radionuclide "i,"          mrem/hr per pCi/m';
(A tabulation of DFGj values is presented in Table E-6 of Regulatory Guide 1.109, Revision 1.)
k      =      The radiological decay constant for radionuclide          "i," sec-1; t      =      The exposure time,    sec;
      -      4.73 E+08 sec    (15 years);
B-5
 
Shearon Harris Nuclear          Power Plant (SHNPP)                                                      June 1994 Offsite    Dose Calculation        Manual (ODCM)                                                              Rev. 4 APPENDIX B                                Sheet      6    of  15 DOSE PARAMETERS      FOR RADIOIODINES,      PARTICULATES,    AND TRITIUM B.2.2      Ground Plane        Pathway  (continued)
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-6
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                      June 1994 Offsite Dose Calculation Manual (ODCM)                                                                                Rev. 4 APPENDIX H                                Sheet    7    of  15 DOSE PARAMETERS FOR RADIOIODINES,                  PARTICULATES,  AND TRITIUM 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:
B    (  -  e      ib)
RM=      I K'Q      U      F    (DFL)  e - kitf i(f      f( r(l - e            +    v p s      Yp          +          PE              +
i    F    ap      m        i a                        p    E.                  i 1
                          -    x  it                    -    ib (il-f    f )( fr(  -      e        e  + B.lv (1 -  e            )e  _ kiith 1    )
p s            Yk                          Pk sE.i 1
(B.2-3) where:
R.                  Dose factor for the cow milk or goat milk pathway,                      for each identified 1M radionuclide        "i"  for the organ of interest,          mrem/yr per pCi/sec per m-            ;
K'        =        A constant of unit conversion;
          -        I06 pCi/Ici; 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 Y          =        The  agricultural productivity by unit area of pasture feed grass,                            kg/m; Ys  =        The agricultural productivity by unit area of stored feed,                          kg/mZ; B-7
 
Shearon    Harris Nuclear      Power Plant (SHNPP)                                                        November 2004 Offsite    Dose Calculation      Manual (ODCM)                                                                      Rev. 17 APPENDIX B                                        Sheet    8  of    15 DOSE    PARAMETERS  FOR RADIOIODINES,              PARTICULATES,      AND TRITIUM B.2.3  Grass Cow or Goat Milk Pathway                (continued)
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;
?EI      =      Xi + kw; K1      =        The radiological        decay constant for radionuclide                  "i,"    sec-;
K      =        The decay constant for removal of activity on leaf and plant surfaces                                    by w
weathering,      sec-1 5.73 E-07 sec-'      (14  day half-life);
t                Period of pasture grass and crop exposure during the growing season,                                    sec; e
tff              The transport time from feed,                to cow or goat,          to milk,      to receptor,      sec; thh              The transport      time from pasture,            to cow or goat,        to milk to receptor, sec; tbb              Period of time that sediment is                  exposed to gaseous effluents,                sec; B.              Concentration      factor for uptake of radionuclide                  "i"    from the soil by the iv edible parts of crops,            pCi/Kg      (wet weight)      per pCi/Kg        (dry soil);
B-8
 
Shearon Harris Nuclear    Power Plant (SHNPP)                                            June 1994 Offsite  Dose Calculation    Manual (ODCM)                                                    Rev. 4 APPENDIX B                            Sheet    9  of  155 DOSE PARAMETERS    FOR RADIOIODINES,  PARTICULATES,  AND TRITIUM B.2.3  Grass Cow or Goat Milk Pathway      (continued)
P      -      Effective    surface density for soil,    Kg (dry soil)/m 2 ;
f              Fraction of the year that the cow or goat is      on pasture;    (dimensionless).
p fs              Fraction of the cow feed that is      pasture grass while the cow is      on s
pasture;    (dimensionless).
t e            Period of pasture grass and crop exposure during the growing season,            sec; e
I.              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 I. may vary. However, a value of 1.0 was used in    calculating the R 1
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 1.
B-9
 
Shearon Harris Nuclear Power Plant (SHNPP)                                          November 2004 Offsite Dose Calculation Manual (ODCM)                                                    Rev. 17 APPENDIX B                        Sheet  10  of  15 DOSE PARAMETERS      FOR RADIOIODINES,    PARTICULATES,  AND TRITIUM 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'K'''FmQFU    (DFLi)a  0.75(0.5/H)                                        (B.2-4)
TM                      ap where:
RTTM          Dose factor for the cow or goat milk pathway for tritium for the organ of interest,  mrem/yr per gCi/m 3 ;
K'''  =      A constant    of unit    conversion; 103 gm/kg; H            Absolute humidity of the atmosphere, gm/m 3 ;        A value of H  = 8 grams/
meter 3 , 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-10
 
Shearon        Harris Nuclear              Power Plant (SHNPP)                                                                    June 1994 Offsite        Dose Calculation              Manual (ODCM)                                                                          Rev. 4 APPENDIX B                                    Sheet    11    of  15 DOSE PARAMETERS            FOR RADIOIODINES,                PARTICULATES,    AND TRITIUM 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:
                                                                                      - E. te                    -Xtb
                                                      -    kit            r(l -    e      '        B.    (1 -  e      itD)
R iB R.=      I i K'Q F    U ap  Ff    (DFL,)i ae              s(fp fs ))    Yp-  X        +            PX.              +
p    S.l 1
r(l  -    e      i  e)      B.    (i    -  ea        b      _ kit (1-ftf            (Cr(l -ff      _            +    iv e                      )
                                                                              )  e      i )
p s              Ys                                  Pk j.
(B.2.5) where:
R.                      Dose factor for the meat ingestion pathway for radionuclide                                        "i"  for any iB organ of interest,                mrem/yr per gCi/sec per m Fr          =          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; 5
B-11
 
Shearon Harris Nuclear Power Plant (SHNPP)                                              June 1994 Offsite Dose Calculation Manual (ODCM)                                                      Rev. 4 APPENDIX B                        Sheet    12  of  15 DOSE PARAMETERS    FOR RADIOIODINES,  PARTICULATES,  AND TRITIUM B.2.4  Grass-Cow-Meat Pathway      (continued) t h          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."
1 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 R1 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 TB  =      K'K'  ''FfQFU ap (DFLi)a 0.75(0.5/H)                                          (B.2-6) where:
R TB  =      Dose factor    for the meat ingestion pathway for tritium for any organ of interest,    mrem/yr per pCi/m 3 .
All other terms are defined in      Equations B.2-4 and B.2-5.
B-12
 
Shearon Harris Nuclear              Power Plant (SHNPP)                                                              June 1994 Offsite    Dose Calculation          Manual (ODCM)                                                                      Rev. 4 APPENDIX          B                            Sheet  13  of  15 DOSE    PARAMETERS          FOR RADIOIODINES,                PARTICULATES,    AND TRITIUM 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:
                                                              - X B,  (il-e-      itb) itL      r(l -  e          i      e)      iv
        =  I K'(DFL )      (ULf e                                                +                        )++/-
1      i a      a L                      Y      k 1
v      E.
1
                              - X SE t e                        -    X..t
        - Xith    r(l -e                        B. (1 - e            i b)
                                            +    iv      P                    )
u ag fe      ih          Y y E                                1 1
(B.2-7) where:
R.                  Dose factor for vegetable pathway for radionuclide                                  "i"  for the organ of iv interest,        mrem/yr per pCi/sec per m-;
K,        =        A constant of unit conversion; 6
          =          0l pCi/pCi; B-13
 
Shearon Harris Nuclear            Power Plant (SHNPP)                                                                          June 1994 Offsite    Dose Calculation          Manual (ODCM)                                                                                  Rev. 4 APPENDIX B                                              Sheet      14    of  15 DOSE PARAMETERS          FOR RADIOIODINES,                PARTICULATES,          AND TRITIUM B.2.5  Vegetation        Pathway    (continued)
U      =      The consumption          rate    of  fresh      leafy      vegetation        by the      receptor      in  age a
group        "a,"  kg/yr; U      =      The consumption          rate    of stored          vegetation          by the receptor            in  age group a
                "a,"      kg/yr; fL              The fraction          of the annual          intake      of fresh        leafy    vegetation        grown locally;
        =      1.0 fi      =      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; YV      =      The vegetation          a real density,              kg/m2; 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-14
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                      June 1994 Offsite Dose Calculation Manual (ODCM)                                                                Rev. 4 APPENDIX B                            Sheet    15      of  15 DOSE PARAMETERS FOR RADIOIODINES,        PARTICULATES,  AND TRITIUM 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 f.,  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:
R Tv=      KFK"'[UJf      + Ufg]  (DFLi)a  0.75 (0.5 / H)]                                        (.2.8) where:
R                  Dose factor for the vegetable pathway for tritium for any organ of interest,  mrem/yr per gCi/m 3 .
All other terms remain the same as those in            Equations B.2-4 and B.2-7.
B-15
 
a        rCr      F<        13          13              hi        C        l<                          O--)
(D P-          (D                pi      0-)      U)      0-          Cl                                ~  '        InI1 H- 0 0      -0          (D                  H    (D        fl      (D          n)                        U)      LC      )
C- H-    n)          C (D                  '      &#xfd;          H                          C:          1.
h  aa                            Fl- Cl                    a                                      CD :
L<      -
(D-                                                                  (D  (D                                                U) u    x 0    '        0                                                                  hi          ~                              El          En- F1-hD                                  nU(                                                          HZ 0    H Fl    (DU                                                                            -C                        -d(D rt D H*- hi 0
0 (D
U) hi U)
(D N)          [    (jnC-Ili    U.    , Li          -              NJ              N  N      C)H              H-      C)  m cn U)U)
OF-nUo  H Hf C)                h--r C*    0    D    C) 0        -j      C)        -j        C)  0)    C-iC            -2        -
0    0                    ti 0-              mw                              Vn        En                        t-            w    0 Zn rt    + +          - *D H- I-h        +                  +          C-  U      UU              +                              C-'&#xfd; U)    C)O          HD      H0          0                  C) co        U)  H, a      rt P.
tiCa            L&#xfd; CD                                0hi U)  0      P- 0                                            rC (D        0      *-
P H 0 I                      c F-*
w3                                                                                                        -      '
H              (D    rt w                            CD                    U'      -U C)-      H
                                                                          'H          U)  H-          0-          U)                      U)<
HD hi      C  a      ()D (D        l (D  (D    U)U            U)
I                                0I C:
rt    &#xfd;-h                                                            C-C                                                            CH (D
a U)<
LC (D~
0 H3 U) HH33      3&#xfd;        H        H3      H      H        (D      -3            H3        H-  HH F3 C-3                                                              D0H-C"                            w- 7Cjw 0              -      0        0'              N-I--                                                                                                          0-        0    0-0        C-h HF        HH            H        H        H          L-1  I      HH            H            H          (D-(D          (D U)
H hi Hr                                                                                                                                    HD IL N
II                I      I F-.            H  "                  H"      H.&#xfd;      H              0C        I'                                    (D U''UIJ              Ln        U'      U'    0~ 0nO                          U'        U'Ln (D)                  C-4 (D
 
Shearon Harris Nuclear Power Plant (SHNPP)                                          June 1994 Offsite Dose Calculation Manual (ODCM)                                                Rev. 4 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 Ff    (pCi/ke per    (pCi/Day)  Each stable element                      Table E-1 Uap    (kg/yr)                0 infant                                Table  E-5 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 1 a Y (kg/M 2 )                    0.7                                      Table E-15 P
Y      (kr/M2 )                2.0                                      Table E-15 s
Tb    (seconds)                4.73 E+08  (15 yr)                      Table E-15 T    (seconds)                1.73 E+06  (20 days)                    Table E-15 s
th    (seconds)                7.78 E+06  (90  days)                  Table E-15 t    (seconds)                2.59 E+06  (pasture)                    Table E-15 e                            5.18 E+06  (stored feed)
QF (kg/day)                    50                                      Table E-3 B.      (pCi/kg  [wet weight]  Each stable element                      Table E-1 lv per pCi/kg      [dry soil])
2 P    (kg dry soil/mr            240                                      Table E-15 B-17
 
Shearon Harris Nuclear Power Plant (SHNPP)                                              June 19 94 Offsite Dose Calculation Manual (ODCM)                                                    Rev. 4 TABLE B-3 Parameters for The Vegetable  Pathway Reference Parameter                        Value              (Rea. 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 la QF (kg/day)                                  50 (cow)                      Table E-3 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 L (seconds)                            8.6 E+04  (1 day)                Table E-15 th  (seconds)                          5.18 E+06 (60    day)              Table E-15 2
Yv  (kg/m )                                    2.0                        Table E-15 t    (seconds)                          5.18 E+06 (60    day)              Table E-15 e
tb  (seconds)                          4.73 E+08    (15 yr)                Table E-15 2
P  (kg  dry soil/mr      )                      240                        Table E-15 Biv    (pCi/kg    [wet weight]        Each stable element                  Table E-1 per pCi/kg    [dry soil])
B-18
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                            November 2001 Offsite Dose Calculation Manual (ODCM)                                                                        Rev. 14 Sheet  1  of  1 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-lWL-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-lSW-3500A from Reactor Auxiliary Building ......................                          REM-ISW-3500B F. Outdoor Tank Area Drain Transfer Pump Monitor ................                          REM-lMD-3530 G. Turbine Building Floor Drains Effluent ......................                            REM-IMD-3528 II. Gaseous Effluent Monitoring Instruments A. Plant Vent Stack 1 ...................................
* RM-21AV-3509-lSA B. Turbine Building Vent Stack 3A ..........................
* RM-lTV-3536-1 C. Waste Processing Building Vent Stack 5                      .....................        REM-lWV-3546
                                                                          . .................
* RM-lWV-3546-1 D. Waste Processing Building Vent Stack 5A ..................
* RM-1WV-3547-1
* Wide-Range Gas Monitor          (WRGM)
C-1
 
Shearon    Harris Nuclear          Power Plant (SHNPP)                                  August 1995 Offsite    Dose Calculation          Manual (ODCM)                                            Rev. 6 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
 
Shearon Harris Nuclear              Power Plant (SHNPP)                                                                              May 2001 Offsite      Dose Calculation        Manual (ODCM)                                                                                  Rev. 13 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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                August 1996 Offsite Dose Calculation Manual (ODCM)                                              Rev. 9 TABLE 3.3-12 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT                          OPERABLE    ACTION
: 1.      Radioactivity Monitors Providing Alarm and Automatic Termination of Release
: a.      Liquid Radwaste Effluent Lines
: 1)        Treated Laundry and Hot Shower          1          35 Tanks Discharge Monitor
: 2)        Waste Monitor Tanks and Waste          1          35 Evaporator Condensate Tanks Discharge Monitor
: 3)        Secondary Waste Sample Tank            1      35,    36*
Discharge Monitor
: b.      Turbine Building Floor Drains Effluent            1          36 Line
: 2.      Radioactivity Monitor Providing Alarm and Automatic Stop Signal to Discharge Pump
: a.      Outdoor Tank Area Drain Transfer Pump            1          37 Monitor
: 3.      Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release
: a.      Normal Service Water System Return From          1          39 Waste Processing Building to the Circulating Water System
: b.        Normal Service Water System Return From          1          39 the Reactor Auxiliary Building to the Circulating Water System
: 4. Flow Rate Measurement    Devices
: a.      Liquid Radwaste Effluent Lines
: 1)        Treated Laundry and Hot Shower          1          38 Tanks Discharge
: 2)        Waste Monitor Tanks and Waste          1          38 Evaporator 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
 
Shearon Harris Nuclear      Power Plant (SHNPP)                                    August 1995 Offsite Dose Calculation      Manual (ODCM)                                              Rev. 6 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 pCi/ml:
: a.        At least once per 12 hours when the specific activity of the secondary coolant is greater than 0.01 pCi/gram DOSE EQUIVALENT      I-131 or,
: b.        At least once per 24 hours when the specific activity of the secondary coolant is less than or equal to 0.01 pCi/gram DOSE EQUIVALENT 1-131.
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 hours, grab samples are collected and analyzed for radioactivity at a lower limit of detection of no more than 1E-07 pCi/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 hours 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
 
Shearon Harris Nuclear          Power Plant (SHNPP)                                      November 2004 Offsite    Dose Calculation      Manual (ODCM)                                                  Rev. 17 TABLE  4.3-8 RADIOACTIVE      LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS DIGITAL CHANNEL INSTRUMENT                        CHANNEL        SOURCE  CHANNEL    OPERATIONAL CHECK        CHECK CALIBRATION      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(l)
Tanks Discharge Monitor
: 2)  Waste Monitor Tanks and Waste              D            P      R(3)          Q(l)
Evaporator Condensate Tanks Discharge Monitor
: 3)  Secondary Waste Sample Tank                D          P,      R(3)          Q(l)
Discharge Monitor                                      M(5)
: b. Turbine Building Floor Drains                    D            N      R(3)          Q(l)
Effluent Line
: 2. Radioactivity Monitor Providing Alarm and Automatic Stop Signal to Discharge Pump
: a. Outdoor Tank Area Drain Transfer Pump Monitor                                    D            N      R(3)          Q(1)
: 3. Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination of Release
: a. Normal Service Water System Return              D            N      R(3)          Q(2)
From Waste Processing Building to the Circulating Water System
: b. Normal Service Water System Return              D            N      R(3)          Q(2)
From the Reactor Auxiliary Building to the 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            D(4)          N.A.      R          N.A.
Evaporator Condensate Tanks Discharge
: 3)  Secondary Waste Sample Tank              D(4)          N.A.      R          N.A.
Pump Monitor
: b. Cooling Tower Blowdown                          D(4)          N.A.      R          N.A.
See Table G-1    for  explanation  of frequency    notation D-5
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                May 2013 Offsite Dose Calculation Manual (ODCM)                                                    Rev. 24 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 hours 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-r
 
Shearon      Harris Nuclear        Power Plant (SHNPP)                                                            December 1998 Offsite      Dose Calculation        Manual (ODCM)                                                                          Rev. 11 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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                    August 1995 Offsite Dose Calculation Manual (ODCM)                                              Rev. 6 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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                          August 1995 Offsite Dose Calculation Manual (ODCM)                                                    Rev. 6 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 hours.
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 hours and these samples are analyzed for radioactivity within 24 hours.
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 hours and these samples are analyzed for radioactivity within 24 hours.
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 hours, 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
 
Shearon      Harris Nuclear      Power Plant (SHNPP)                                            November 2004 Offsite      Dose Calculation      Manual (ODCM)                                                      Rev. 17 TABLE 4.3-9 RADIOACTIVE GASEOUS EFFLUENT MONITORING            INSTRUMENTATION SURVEILLANCE REQUIREMENTS DIGITAL      MODES FOR CHANNEL        WHICH CHANNEL    SOURCE      C HANNEL      0OPERATIONAL  SURVEILLANCE INSTRUMENT                CHECK      CHECK    CAL IBRATION          TEST      IS REQUIRED
: 1.        GASEOUS WASTE PROCESSING SYSTEM - HYDROGEN AND OXYCGEN 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              D        N.A.          R                Q Monitor
: 3.        PLANT VENT STACK
: a. Noble Gas Activity              D          M          R(3)            Q(2)
Monitor
: 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            D        N.A.            R                Q Monitor
: 4. WASTE PROCESSING BUILDING VENT STACK 5 a.l    Noble Gas Activity              D          M          R(3)            Q(1)
Monitor (PIG) a.2 Noble Gas Activity                D          M          R(3)            Q(2)
Monitor (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              D        N.A.            R                Q Monitor
: 5. WASTE PROCESSING BUILDING VENT STACK 5A
: a. Noble Gas Activity              D          M          R(3)            Q(2)
Monitor
: 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              D        N.A.            R                Q Monitor
* At all    times.
**          See Table G-1 for explanation    of frequency notation D-10
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                  May 2013 Offsite Dose Calculation Manual (ODCM)                                                      Rev. 24 TABLE 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-1I
 
Shearon Harris Nuclear Power Plant (SHNPP)                                  November 2004 Offsite Dose Calculation Manual (ODCM)                                            Rev. 17 D.2    RADIOACTIVE EFFLUENTS 3/4.11.1      LIQUID EFFLUENTS 3/4.11.1.1    Concentration DPERATIONAL 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 pCi/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.
n- 12
 
Shearon Harris Nuclear Power Plant (SHNPP)                                            November 2004 Offsite Dose Calculation Manual (ODCM)                                                      Rev. 17 TABLE 4.11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT MINIMUM                                OF DETECTION SAMPLING            ANALYSIS        TYPES OF ACTIVITY          (LLD)(')
LIQUID RELEASE TYPE        FREQUENCY          FREQUENCY            ANALYSIS              (pCi/ml) 2
: 1. Batch Waste Release Tanks(    )
: a.        Waste Monitor            P                  P            Principal Gamma            5E-07 Tanks              Each Batch          Each Batch            Emitters (3) 1-131                1E-06
: b.      Waste                      P                  M              Dissolved and            1E-05 Evaporator          One Batch/M                            Entrained Gases Condensate                                                  (Gamma Emitters)
Tanks
: c.      Secondary Waste            P                  M                  H-3                  1E-05 Sample Tank(8)      Each Batch          Composite(4)
Gross Alpha              1E-07
: d.      Treated Laundry            P                  Q    4        Sr-89,  Sr-90            5E-08 and Hot Shower      Each Batch          Composite1 )
Tanks Fe-55                1E-06
: 2.        Continuous Releases(5)(7)
: a.      Cooling Tower      Continuous  (6)            W            Principal Gamma            5E-07 Weir                                    Composite(6)(7)        Emitters (3)
: b.      Secondary Waste          M(7)                M(7 )          Dissolved and            1E-05 Sample Tank18)      Grab Sample                            Entrained Gases (Gamma Emitters) 1-131                1E-06 Continuous  6)            M                  H-3                  1E-05 (7)
Composite(6)
Gross Alpha              1E-07 Continuous  (6)            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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                              August 1995 Offsite Dose Calculation Manual (ODCM)                                                          Rev. 6 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:
LLD =              4.66    Sb
                                    &
E
* V *  (2.22E + 06) . Y
* e-"
Where:
LLD    =        the "a priori" lower limit of detection          (pCi 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 pCi, Y      =        the fractional radiochemical          yield, when applicable, X      =        the radioactive decay constant for the particular radionuclide (sec- 1 ), and At      =        the elapsed time between the midpoint of sample collection and the time of counting (sec).
Typical values of E,        V,  Y, and At 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
 
Shearon Harris Nuclear                  Power Plant (SHNPP)                                                                    August 1995 Offsite    Dose Calculation                Manual (ODCM)                                                                              Rev. 6 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.
0-15
 
Shearon Harris Nuclear Power Plant (SHNPP)                                    August 1995 Offsite Dose Calculation Manual (ODCM)                                            Rev. 6 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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                    August 1995 Offsite Dose Calculation Manual (ODCM)                                              Rev. 6 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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                      August 1995 Offsite Dose Calculation Manual (ODCM)                                                Rev. 6 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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                                              Nov. 2004 Offsite Dose Calculation Manual (ODCM)                                                                                                    Rev. 17 TABLE 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM" MINIMUM                                              LOWERLIMIT UO SAMPLING                  ANALYSIS                                            DETECTION (LLD)
GASEOUS RELEASE TYPE                    FREQUENCY                FREQUENCY              TYPE OF ACTIVITY ANALYSI S        (tCi/ml)
: 1. Waste Gas Storage                    P                                P                Principal Gamma Emitters            IE-04 Tank                                Each Tank                Each Tank Grab Sampl le Containment Purge                    P                                P    3 Principal  Gamma Emitters        IE-04 0
or Vent"" '                          Each PURGE(3j            Each PURGE"'
Grab Sampl e              M                      H-3  (oxide)                        IE-06
: 3. a. Plant Vent Stack                                        M                      Principal Gamma Emitters            1E-04 Grab Sampl le                                    H-3  (oxide)                        IE-06 M                      Principal Gamma Emitters            IE-04
: b. Turbine Bldg Vent Stack, Waste              Grab Sampl le Proc. Bldg. Vent Stacks 5 & 5A
: 4. All Release Types as                Continuous'6'            W1"'                    1-1315"'                            1E-12 listed in 1.2.,          and                                  Charcoal
: 3. above  (9), '9)' 115)                                    Sample 1-13312b)                          IE-IO Continuous'6)            W"7,-                  Principal Gamma Emitters'2c)        1E-S1 Particulate Sample Continuous"'              M                      Gross Alpha                        1E-St Composite Particulate Sample Continuous"'              Q                      Sr-89,  Sr-90                      1E-I1 Composite Particulate Sample
: 5. Equ ipment    Hatch                  Continuous                D                      1-131,&                            IE-11 dur ing Refueling                                              Charcoal                1-133                              IE-09
                                                                    'ample Continuous                D'11                    Principal Gamma Emitters            IE-10 Particulate Sample See Table G-1          for explanation of frequency notation D-19
 
Shearon Harris Nuclear Power Plant (SHNPP)                                            August 1995 Offsite Dose Calculation Manual (ODCM)                                                      Rev. 6 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 . Sb LLD E
* V - (2.22E + 06)
* Y
* e-'\
Where:
LLD    =      the "a priori" lower limit of detection        (pCi 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 pCi, Y      =      the fractional radiochemical        yield, when applicable, X      =      the radioactive decay constant for the particular          radionuclide (sec- 1 ), and At    =      the elapsed time between the midpoint of sample collection and the time of counting (sec).
Typical values of E, V,        Y, and At 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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                              March 2007 Offsite Dose Calculation Manual (ODCM)                                                        Rev. 19 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 1-131 and 1-133 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 1-131 and 1-133 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, 1-131, 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 hours 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 hours after changing, or after removal from sampler.
Sampling shall also be performed at least once per 24 hours 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 hours of changing.          When samples collected for 24 hours 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 1-131 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-*lWV-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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                            March 2009 Offsite Dose Calculation Manual (ODCM)                                                    Rev. 20 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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                    August 1995 Offsite Dose Calculation Manual (ODCM)                                              Rev. 6 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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                      August 1995 Offsite Dose Calculation Manual (ODCM)                                                Rev. 6 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
 
Shearon    Harris Nuclear      Power Plant (SHNPP)                                    August 1995 Offsite    Dose Calculation      Manual (ODCM)                                            Rev. 6 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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                      August 1995 Offsite Dose Calculation Manual (ODCM)                                                Rev. 6 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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                      March 2007 Offsite Dose Calculation Manual (ODCM)                                            Rev. 19 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:
concentration(l) + concentration(2)  +. .. .
reporting level(l) 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.I.
*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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                      March 2007 Offsite Dose Calculation Manual (ODCM)                                              Rev. 19 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.
0-28
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                                    August 1995 Offsite Dose Calculation Manual (ODCM)                                                                                              Rev.6 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")            COLLECTION FREQUENCY        OF ANALYSIS
: 1. Direct Radiation")          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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                                          August 1995 Offsite Dose Calculation Manual (ODCM)                                                                                                    Rev.6 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"'            COLLECTION FREQUENCY                OF ANALYSIS Airborne                  Samples from five locations:            Continuous sampler      Radioiodine Cannister:
Radioiodine and                                                    operation with sample      1-131 analysis weekly.
Particulates                                                      collection weekly, or Three samples from close to              more frequently if the three SITE BOUNDARY                  required by dust locations, in different sectors,        loading.                Particulate Sampler:
of the highest                                                      Gross beta radioactivity calculated annual average                                            analysis following 3
ground-level D/Q;                                                    filter  change; " and    41 gamma isotopic analysis One sample from the vicinity                                        of composite (by location) of a community having the                                            quarterly.
highest calculated annual average ground-level D/Q;    and One sample    from a control location, as for example 15 to 30 km distant and in the least prevalent wind direction.
: 3. Waterborne 5                                                                                                      41
: a. Surface" )          One sample upstream.                    Composite sample over    Gamma isotopic analysis" 1-month period. (6)      monthly. Composite for One sample downstream.                                            tritium analysis quarterly.
4
: b. Ground              Samples from one or two sources          Quarterly.              Gamma isotopic" ) and only if likely                                                    tritium analysis quarterly.
1 to be affected" .
D-30
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                                        March 2007 Offsite Dose Calculation Manual (ODCM)                                                                                                Rev. 19 TABLE 3.12-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING      PROGRAM EXPOSURE PATHWAY                  NUMBER OF REPRESENTATIVE                      SAMPLING AND        TYPE AND FREQUENCY ANO/OR SAMPLE              SAMPLES AND SAMPLE LOCATIONS"'            COLLECTION FREQUENCY            OF A1ALYSIS
: 3. Waterborne (Continued)
: c. Drinking              One sample in the vicinity                Composite sample over      1-131 analysis on each 6
of the nearest downstream                2-week period"        when composite when the dose municipal water supply intake            1-131 analysis is          calculated for the from the Cape Fear River.                performed; monthly        consumption of the water composite otherwise.      is greater than 8
One sample  from a control                                          1 mrem per year. '
location.                                                            Composite for gross beta and gamma isotopic 4
analyses" ) monthly.
Composite for tritium analysis quarterly.
4
: d. Sediment              One sample in the vicinity of the        Semiannually.              Gamma isotopic analysis' )
from                  cooling tower blowdown discharge                                    semiannually.
Shoreline            in an area with existing or potential recreational value.
: 4. Ingestion
: a. Milk                  Samples from milking animals in          Semimonthly when          Gamma isotopic"'4 and three locations within 5 km distance      animals are on pasture;    1-131 analysis having the highest dose                  monthly at other times. semimonthly when potential. If there are none,          When no milk animals are  animals are on pasture; then one sample from milking              available at indicator    monthly at other times.
animals in each of three areas            locations, milk sampling between 5 to 8 km distant where          of the control location doses are calculated to be greater        can be reduced to once than I mrem per yr."'                    per month to maintain One sample from milking animals          historical      data.
at a control location 15 to 30 km distant and in the least    prevalent wind direction.
D-31
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                                                        March 2009 Offsite Dose Calculation Manual (ODCM)                                                                                                                Rev.20 TABLE 3.12-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY                        NUMBER OF REPRESENTATIVE 1                            SAMPLING AND              TYPE AND FREQUENCY AND/OR SAMPLE                    SAMPLES AND SAMPLE LOCATIONS( "                    COLLECTION FREQUENCY                OF ANALYSIS
: 4. Ingestion (Continued)
: b. Fish and                    One sample of Sunfish, Catfish, and                      Sample in season, or          Gamma isotopic 4
Invertebrates              Large-Mouth Bass species in vicinity                      semiannually if they          analysis( ) on of plant discharge area.                                  are not seasonal.              edible portions.
One sample of same species in areas not influenced by plant discharge.
4
: c. Food Products              Samples of three different kinds of broad leaf            Monthly during growing season. Gamma isotopic" ) and vegetation grown nearest each of two different                                          1-131 analysis.
locations of highest predicted annual average ground level D/Q if milk sampling is not performed.
4 One sample of each of the similar                        Monthly during                Gamma isotopic1 1 and broad leaf vegetation grown 15 to                        growing season                1-131 analysis.
30 km distant in the least prevalent wind direction if milk sampling is not performed.
D-32
 
Shearon    Harris Nuclear              Power Plant (SHNPP)                                                                                August 1995 Offsite    Dose Calculation                Manual (ODCM)                                                                                          Rev. 6 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 hours 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.
D-33
 
Shearon Harris Nuclear                  Power Plant (SHNPP)                                                                          March 2009 Offsite    Dose Calculation                Manual (ODCM)                                                                                    Rev. 20 TABLE 3.12-1            (Continued)
TABLE NOTATIONS                (Continued)
(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.
(8)    The dose shall              be calculated          for      the maximum organ              and age group,            using the methodology and parameters                      in  the ODCM.
D-34
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                                    August 1995 Offsite Dose Calculation Manual (ODCM)                                                                                            Rev. 6 TABLE 3.12-2 REPORTING LEVELS  FOR RADIOACTIVITY CONCENTRATIONS    IN ENVIRONMENTAL SAMPLES WATER            AIRBORNE PARTICULATE      FISH              MILK            FOOD PRODUCTS ANALYSIS            (pCi/l)          OR GASES (pCi/m')          (pCi/kg,  wet)    (pCi/I)        (pCi/kg, wet)
H-3                20,000O 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 1-131                    2-          0.9                                          3                  D00 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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                                                          December 1999 Offsite Dose Calculation Manual (ODCM)                                                                                    Rev. 12 TABLE 4.12-1 DETECTION CAPABILITIES    FOR ENVIRONMENTAL SAMPLE ANALYSIS(')
LOWER LIMIT OF DETECTION    (LLD)121 WATER      AIRBORNE PARTICULATE      FISH              MILK          FOOD PRODUCTS SEDIMENT ANALYSIS        (pCi/I)    OR GASES (pCi/m')          (pCi/kg,  wet)    (pCi/l)        (pCi/kg, wet) (pCi/kg, dry)
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 1-131                1'. 0.07                                        1              60 Cs-134              15    0.05                        130              15            60            150 Cs-137              18    0.06                        150              1i            80            180 4
Ba-La-1  0        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.
D-36
 
Shearon Harris Nuclear            Power Plant (SHNPP)                                                      December 1999 Offsite    Dose Calculation            Manual (ODCM)                                                                  Rev. 12 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 repdrted in                  the Annual Radiological Environmental Operating Report pursuant to ODCM, Appendix F, Section F.l.
(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
* Sb LLD =
E e V      (2. 2 2 E + 06)    Y
* e-Where:
LLD        =          the "a priori" lower limit of detection                      (pCi 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 pCi, Y          =          the fractional radiochemical                  yield,  when applicable, X          =          the radioactive decay constant for the particular radionuclide (sec-'), and At                    the elapsed time between the midpoint of sample collection                              and the time of counting (sec).
Typical values of E,              V,    Y, and At should be used in            the calculation.
D-37
 
Shearon    Harris Nuclear              Power Plant (SHNPP)                                                        August 1995 Offsite    Dose Calculation              Manual (ODCM)                                                                Rev. 6 TABLE    4.12-1  (Continued)
TABLE    NOTATIONS      (Continued)
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.l.
D-3R
 
Shearon Harris Nuclear Power Plant (SHNPP)                                    August 1995 Offsite Dose Calculation Manual (ODCM)                                                Rev. 6 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.l.
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-39
 
Shearon Harris Nuclear Power Plant (SHNPP)                                      July 2002 Offsite Dose Calculation Manual (ODCM)                                            Rev. 15 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. The laboratory used for the Interlaboratory Comparison Program is to participate in the National Institute of Standard and Technology (NIST) program 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.l.
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-40
 
Shearon  Harris Nuclear      Power Plant (SHNPP)                                    August 1995 Offsite  Dose Calculation      Manual (ODCM)                                            Rev. 6 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 F.-i
 
Shearon Harris Nuclear                Power Plant (SHNPP)                                                                            August 1995 Offsite  Dose Calculation              Manual (ODCM)                                                                                          Rev. 6 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        /uCi/ml  are      measurable.
                                                                                .- 2
 
Shearon Harris Nuclear Power Plant (SHNPP)                                        August 1995 Offsite Dose Calculation Manual (ODCM)                                                  Rev. 6 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.
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Shearon Harris Nuclear Power Plant (SHNPP)                                    August 1995 Offsite Dose Calculation Manual (ODCM)                                              Rev. 6 E.2    RADIOACTIVE EFFLUENTS BASES 3/4.11.1      LIQUID EFFLUENTS 3/4.11.1.2    Dose  (continued)
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.
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Shearon Harris Nuclear                Power Plant (SHNPP)                                                                      August 1995 Offsite    Dose Calculation              Manual (ODCM)                                                                                    Rev. 6 E.2      RADIOACTIVE EFFLUENTS BASES 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).
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Shearon Harris    Nuclear Power Plant      (SHNPP)                                August 1995 Offsite  Dose Calculation      Manual  (ODCM)                                          Rev. 6 E.2    RADIOACTIVE EFFLUENTS BASES 3/4.11.2      GASEOUS EFFLUENTS 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.
 
Shearon Harris Nuclear Power Plant (SHNPP)                                          August 1995 Offsite Dose Calculation Manual (ODCM)                                                    Rev. 6 E.2    RADIOACTIVE EFFLUENTS BASES 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.
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Shearon Harris Nuclear Power Plant (SHNPP)                                      August 1995 Offsite Dose Calculation Manual (ODCM)                                              Rev. 6 E.2    RADIOACTIVE EFFLUENTS BASES  (continued) 3/4.11.2      GASEOUS EFFLUENTS 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.
E-8
 
Shearon Harris Nuclear          Power Plant (SHNPP)                                        August 1995 Offsite    Dose Calculation          Manual (ODCM)                                                Rev. 6 E.2      RADIOACTIVE EFFLUENTS BASES                (continued) 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-9
 
Shearon Harris Nuclear Power Plant (SHNPP)                                    November 2004 Offsite Dose Calculation Manual (ODCM)                                              Rev. 17 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-10
 
Shearon Harris Nuclear Power Plant (SHNPP)                                            August 1995 Offsite Dose Calculation Manual (ODCM)                                                    Rev. 6 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 implements Section 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/m 2 .
P,-I1
 
Shearon Harris Nuclear Power Plant (SHNPP)                                  August 1995 Offsite Dose Calculation Manual (ODCM)                                            Rev. 6 E.3    RADIOLOGICAL ENVIRONMENTAL MONITORING BASES  (continued) 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-12
 
Shearon  Harris Nuclear  Power Plant (SHNPP)                                  August 1995 Offsite  Dose Calculation  Manual (ODCM)                                          Rev. 6 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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                            August 1995 Offsite Dose Calculation Manual (ODCM)                                                      Rev. 6 F.l    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
 
Shearon    Harris Nuclear              Power Plant (SHNPP)                                                                              March 2009 Offsite    Dose Calculation              Manual (ODCM)                                                                                      Rev. 20 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              life's    & 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.
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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                        March 2007 Offsite Dose Calculation Manual (ODCM)                                                Rev. 19 F.2    Annual Radioactive Effluent Release Report    (continued)
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.
F-4
 
Shearon Harris Nuclear Power Plant (SHNPP)                                    November 2004 Offsite Dose Calculation Manual (ODCM)                                              Rev. 17 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-5
 
Shearon Harris Nuclear            Power Plant (SHNPP)                                                                            July 2006 Offsite    Dose Calculation          Manual (ODCM)                                                                                Rev. 18 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 1-131 DOSE EQUIVALENT 1-131 shall                      be that      concentration            of 1-131 (pCi/gram)            which alone would produce the same thyroid                              dose as the quantity                and isotopic        mixture of 1-131, 1-132, 1-133,                  1-134, and 1-135 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-I.
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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                          May 2013 Offsite Dose Calculation Manual (ODCM)                                                Rev. 24 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
 
Shearon Harris Nuclear Power Plant (SHNPP)                                          May 2013 Offsite Dose Calculation Manual (ODCM)                                              Rev. 24 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.
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.
 
Shearon Harris Nuclear Power Plant (SHNPP)                                      May 2013 Offsite Dose Calculation Manual (ODCM)                                          Rev. 24 DEFINITIONS  (continued)
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.
 
Shearon Harris Nuclear Power Plant (SHNPP)                                    July 2006 Offsite Dose Calculation Manual (ODCM)                                          Rev. 18 TABLE G-1 FREQUENCY NOTATION NOTATION              FREQUEN S              At least once per 12 hours.
D              At least once per 24 hours.
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.
 
Shearon    Harris Nuclear      Power Plant (SHNPP)                                  July 2006 Offsite    Dose Calculation      Manual (ODCM)                                        Rev. 18 TABLE G-2 OPERATIONAL    MODES Mode          Reactivity              Keff            % RATED    AVERAGE COOLANT Condition                          THERMAL POWER*      TEMPERATURE 1        Power Operations            > 0.99            > 5%            > 350OF 2        Startup                      &#x17d; 0.99
* 5%          &#x17d; 350OF 3        Hot Standby                  < 0.99              0            > 350OF 4        Hot Shutdown                < 0.99              0      350'F > Tavg > 200'F 5        Cold Shutdown                < 0.99              0            < 200OF 6        Refueling      **          < 0.95              0                140OF
* Excluding decay heat.
**        Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.}}

Latest revision as of 13:11, 10 January 2025

Annual Radioactive Effluent Release Report for 2014
ML15112A529
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 04/16/2015
From: Waldrep B
Duke Energy Progress
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
HNP-15-029
Download: ML15112A529 (286)
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