RNP-RA/16-0029, 2015 Annual Radioactive Effluent Release Report
| ML16112A359 | |
| Person / Time | |
|---|---|
| Site: | Robinson |
| Issue date: | 04/21/2016 |
| From: | Hoffman D Duke Energy Progress |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RNP-RA/16-0029 | |
| Download: ML16112A359 (51) | |
Text
Serial: RNP-RA/16-0029 APR 21 2016 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEWED LICENSE NO. DPR-23 2015 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Ladies and Gentlemen:
David S. Hoffman H. B. Robinson Steam Electric Plant Unit 2 Director - Nuc Org Effectiveness Duke Energy Progress 3581 West Entrance Road Hartsville, SC 29550 0. 843 857 5239 F: 843 857 1319 10 CFR 50.36a(a)(2)
TS 5.6.3 Attached is the Annual Radioactive Effluent Release Report for H. 8. Robinson Steam Electric Plant (HBRSEP), Unit No. 2 for the period of January 1, 2015 through December 31, 2015. This report is submitted in accordance with 10 CFR 50.4, as required by 10 CFR 50.36a(a)(2) and HBRSEP, Unit No. 2, Technical Specifications (TS) Section 5.6.3.
This document contains no new Regulatory Commitments. If you have any questions regarding this submittal, please contact Mr. Scott Connelly, Manager (Acting) - Nuclear Regulatory Affairs, at (843) 857-1569.
Sincerely, -0 David S. Hoffm~ 71--
Director - Nuclear Organization Effectiveness DSH/am Attachment c:
NRC Regional Administrator, NRC, Region II D. Galvin, NRC Project Manager, NRR (w/o Attachment)
NRC Resident Inspector, HBRSEP
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/16-0029 50 Pages (including cover page)
DUKE ENERGY H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 RENEWED OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 RADIOACTIVE EFFLUENT RELEASE REPORT ANNUAL REPORT JANUARY 1, 2015-DECEMBER 31, 2015
(~ DUKE ENERGY.
H.B. Robinson Steam Electric Plant Unit 2 Annual Radioactive Effluent Release Report January 1, 2015 through December 31, 2015 Docket 50-261
Introduction The Annual Radioactive Effluent Release Report is pursuant to H.B. Robinson Steam Electric Plant Technical Specification 5.6.3 and ODCM 9.1. The below listed attachments to this report provide the required information. In addition, the ODCM is included pursuant to H.B. Robinson Steam Electric Plant Technical Specification 5.5.1.
Summary of Gaseous and Liquid Effluents Supplemental Information Solid Radioactive Waste Disposal Meteorological Data Unplanned Offsite Releases Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Information to Support the NEI Ground Water Protection Initiative Inoperable Equipment Summary of Changes to the Offsite Dose Calculation Manual 0 Summary of Changes to the Process Control Program 1 Summary of Major Modifications to the Radioactive Waste Treatment Systems 2 Errata to a Previous Year's ARERR Summary of Gaseous and Liquid Effluents H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 ATTACHMENT 1 Summary of Gaseous and Liquid Effluents This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents as outlined in Regulatory Guide 1.21, Appendix B.
Page 1-1 Summary of Gaseous and Liquid Effluents H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Gaseous Effluents - Summation of All Releases Units Qtr 1 Qtr 2 Qtr 3 A. Fission and Activation Gases
- 1. Total Release Ci 1.18E-01 3.05E+OO 3.99E-01
- 2. Avg. Release Rate
µCi/sec 1.51 E-02 3.88E-01 5.01 E-02 B. lodine-131
- 1. Total Release Ci O.OOE+OO O.OOE+OO O.OOE+OO
- 2. Avg. Release Rate
µCi/sec O.OOE+OO O.OOE+OO O.OOE+OO C. Particulates Half-Life ~ 8 days
- 1. Total Release Ci O.OOE+OO 4.14E-06 2.66E-08
- 2. Avg. Release Rate
µCi/sec O.OOE+OO 5.27E-07 3.35E-09 D. Tritium
- 1. Total Release Ci 3.14E+OO 7.37E+OO 6.25E+OO
- 2. Avg. Release Rate
µCi/sec 4.04E-01 9.37E-01 7.87E-01 E. Carbon-14
- 1. Total Release Ci 1.90E+OO 1.92E+OO 1.94E+OO
- 2. Avg. Release Rate
µCi/sec 2.44E-01 2.44E-01 2.44E-01 F. Gross Alpha
- 1. Total Release Ci O.OOE+OO O.OOE+OO O.OOE+OO
- 2. Avg. Release Rate
µCi/sec O.OOE+OO O.OOE+OO O.OOE+OO Qtr4 Year 2.69E+OO 6.26E+OO 3.38E-01 1.98E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.17E-06 O.OOE+OO 1.32E-07 6.11E+OO 2.29E+01 7.69E-01 7.25E-01 1.94E+OO 7.70E+OO 2.44E-01 2.44E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 1-2 Summary of Gaseous and Liquid Effluents H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Gaseous Effluents - Elevated Releases - Continuous Mode
- Units Qtr 1 Qtr 2 Qtr 3 A. Fission and Activation Gases N/A Ci Total for Period Ci B. Iodines NIA Ci Total for Period Ci C. Particulates Half-Life ~ 8 days N/A Ci Total for Period Ci D. Tritium N/A Ci E. Carbon-14 N/A Ci F. Gross Alpha Total for Period Ci
- H.B. Robinson Steam Electric Plant Unit 2 does not have elevated releases.
Page 1-3 Summary of Gaseous and Liquid Effluents H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Gaseous Effluents - Elevated Releases - Batch Mode
- Units Qtr 1 A. Fission and Activation Gases N/A Ci Total for Period Ci
- 8. Iodines N/A Ci Total for Period Ci C. Particulates Half-Life ;:: 8 days N/A Ci Total for Period Ci D. Tritium NIA Ci E. Carbon-14 N/A Ci F. Gross Alpha Total for Period Ci
- H.B. Robinson Steam Electric Plant Unit 2 does not have elevated releases.
Page 1-4 Summary of Gaseous and Liquid Effluents H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Gaseous Effluents - Ground & Mixed-Mode Releases - Continuous Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Gases Ar-41 Ci O.OOE+OO 2.55E+OO O.OOE+OO O.OOE+OO 2.55E+OO Xe-133 Ci 8.94E-03 2.53E-03 3.43E-01 2.63E+OO 2.98E+OO Total for Period Ci 8.94E-03 2.56E+OO 3.43E-01 2.63E+OO 5.54E+OO B. Iodines None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO C. Particulates Half-Life ~ 8 days Co-58 Ci O.OOE+OO 1.95E-06 O.OOE+OO O.OOE+OO 1.95E-06 Total for Period Ci O.OOE+OO 1.95E-06 O.OOE+OO O.OOE+OO 1.95E-06 D. Tritium H-3 Ci 3.09E+OO 7.22E+OO 6.16E+OO 6.03E+OO 2.25E+01 E. Carbon-14 C-14 Ci 1.39E+OO 7.06E-01 1.42E+OO 1.23E+OO 4.74E+OO F. Gross Alpha Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 1-5 Summary of Gaseous and Liquid Effluents H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Gaseous Effluents - Ground & Mixed Mode Releases - Batch Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Gases Ar-41 Ci 3.13E-02 4.91 E-01 5.52E-02 5.89E-02 6.36E-01 Kr-85m Ci 2.56E-05 O.OOE+OO O.OOE+OO 3.77E-06 2.94E-05 Xe-131m Ci 3.54E-04 O.OOE+OO O.OOE+OO O.OOE+OO 3.54E-04 Xe-133m Ci 1.52E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.52E-03 Xe-133 Ci 6.62E-02 2.37E-03 O.OOE+OO 2.30E-03 7.09E-02 Xe-135 Ci 9.33E-03 O.OOE+OO O.OOE+OO 5.92E-05 9.39E-03 Total for Period Ci 1.09E-01 4.93E-01 5.52E-02 6.13E-02 7.19E-01 B. Iodines None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO C. Particulates Half-Life ;:: 8 days Co-58 Ci O.OOE+OO 2.18E-06 O.OOE+OO O.OOE+OO 2.18E-06 Co-60 Ci O.OOE+OO 6.92E-09 2.66E-08 O.OOE+OO 3.35E-08 Cs-137 Ci O.OOE+OO 4.25E-09 O.OOE+OO O.OOE+OO 4.25E-09 Total for Period Ci O.OOE+OO 2.19E-06 2.66E-08 O.OOE+OO 2.22E-06 D. Tritium H-3 Ci 4.41E-02 1.48E-01 9.41E-02 7.67E-02 3.63E-01 E. Carbon-14 C-14 Ci 8.62E-01 4.39E-01 8.81 E-01 7.68E-01 2.95E+OO F. Gross Alpha Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 1-6 Summary of Gaseous and Liquid Effluents H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Liquid Effluents - Summation of All Releases Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Products
- 1. Total Release Ci 2.93E-03 1.98E-02 1.41 E-02 8.27E-04 3.77E-02
- 2. Avg. Diluted Cone.
µCi/ml 1.23E-11 1.22E-10 5.71E-11 3.39E-12 4.23E-11 B. Tritium
- 1. Total Release Ci 2.25E+02 1.73E+02 1.43E+01 9.82E+01 5.11 E+02
- 2. Avg. Diluted Cone.
µCi/ml 9.46E-07 1.07E-06 5.77E-08 4.02E-07 5.73E-07 C. Dissolved & Entrained Gases
- 1. Total Release Ci 1.15E-03 1.90E-02 O.OOE+OO 1.15E-04 2.03E-02
- 2. Avg. Diluted Cone.
µCi/ml 4.83E-12 1.17E-10 O.OOE+OO 4.72E-13 2.27E-11 D. Gross Alpha
- 1. Total Release Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 2. Avg. Diluted Cone.
µCi/ml O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO E. Volume of Liquid Waste
- 1. Continuous Releases liters 3.74E+06 O.OOE+OO O.OOE+OO 1.44E+06 5.18E+06
- 2. Batch Releases liters 4.39E+05 1.09E+06 3.66E+05 2.34E+05 2.13E+06 F. Volume of Dilution Water
- 1. Continuous Releases liters 2.28E+11 1.62E+11 2.47E+11 2.44E+11 8.91 E+11
- 2. Batch Releases liters 2.28E+11 1.62E+11 2.47E+11 2.44E+11 8.91 E+11 Excludes tritium, dissolved and entrained noble gases, and gross alpha.
Page 1-7 Summary of Gaseous and Liquid Effluents H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Liquid Effluents - Continuous Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Products F-18 Ci O.OOE+OO O.OOE+OO O.OOE+OO 1.16E-06 1.16E-06 Co-58 Ci 1.42E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.42E-05 Co-60 Ci 1.0SE-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.0SE-06 Total for Period Ci 1.52E-05 O.OOE+OO O.OOE+OO 1.16E-06 1.64E-05 B. Tritium H-3 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO C. Dissolved & Entrained Gases None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO D. Gross Alpha Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 1-8 Summary of Gaseous and Liquid Effluents H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Liquid Effluents - Batch Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Products Mn-54 Ci 1.23E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.23E-05 Fe-55 Ci 7.86E-05 9.28E-04 1.33E-04 7.50E-05 1.21 E-03 Co-57 Ci 4.68E-06 1.33E-05 3.45E-06 O.OOE+OO 2.14E-05 Co-58 Ci 6.47E-05 3.12E-03 3.28E-03 1.73E-04 6.64E-03 Co-60 Ci 2.37E-03 3.40E-03 3.42E-04 2.04E-05 6.13E-03 Ni-63 Ci 1.28E-04 2.30E-03 2.01 E-03 3.16E-04 4.75E-03 Sr-89 Ci O.OOE+OO O.OOE+OO O.OOE+OO 7.47E-06 7.47E-06 Sr-90 Ci O.OOE+OO O.OOE+OO O.OOE+OO 9.74E-07 9.74E-07 Nb-95 Ci O.OOE+OO 2.07E-06 1.21 E-06 O.OOE+OO 3.28E-06 Ag-110m Ci 1.47E-06 3.10E-06 8.72E-06 O.OOE+OO 1.33E-05 Sn-117m Ci 1.97E-06 4.97E-04 4.88E-05 O.OOE+OO 5.48E-04 Sb-122 Ci O.OOE+OO 1.40E-05 O.OOE+OO O.OOE+OO 1.40E-05 Sb-124 Ci O.OOE+OO 3.46E-04 1.02E-04 O.OOE+OO 4.48E-04 Sb-125 Ci 1.70E-04 8.54E-03 8.07E-03 2.32E-04 1.70E-02 Te-123m Ci 2.02E-06 5.10E-04 5.01E-05 O.OOE+OO 5.62E-04 Te-131m Ci 2.48E-05 3.94E-06 O.OOE+OO O.OOE+OO 2.87E-05 Te-132 Ci O.OOE+OO 4.29E-06 4.75E-06 O.OOE+OO 9.04E-06 1-134 Ci O.OOE+OO O.OOE+OO 4.03E-06 O.OOE+OO 4.03E-06 1-135 Ci O.OOE+OO O.OOE+OO 1.48E-06 O.OOE+OO 1.48E-06 Cs-137 Ci 3.95E-05 4.04E-05 5.21 E-05 O.OOE+OO 1.32E-04 Ba-133 Ci O.OOE+OO 7.46E-07 O.OOE+OO O.OOE+OO 7.46E-07 Ce-141 Ci 3.09E-07 O.OOE+OO O.OOE+OO O.OOE+OO 3.09E-07 Eu-152 Ci 1.41 E-05 4.01 E-05 1.04E-05 O.OOE+OO 6.46E-05 Total for Period Ci 2.91 E-03 1.98E-02 1.41 E-02 8.26E-04 3.76E-02 B. Tritium H-3 Ci 2.25E+02 1.73E+02 1.43E+01 9.82E+01 5.11E+02 C. Dissolved & Entrained Gases Kr-89 Ci O.OOE+OO 1.04E-02 O.OOE+OO O.OOE+OO 1.04E-02 Xe-131 m Ci O.OOE+OO 1.63E-05 O.OOE+OO O.OOE+OO 1.63E-05 Xe-133m Ci O.OOE+OO 5.08E-05 O.OOE+OO O.OOE+OO 5.08E-05 Xe-133 Ci 1.15E-03 8.51E-03 O.OOE+OO 1.15E-04 9.78E-03 Xe-135 Ci O.OOE+OO 3.04E-06 O.OOE+OO O.OOE+OO 3.04E-06 Total for Period Ci 1.15E-03 1.90E-02 O.OOE+OO 1.15E-04 2.03E-02 D. Gross Alpha Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 1-9 Supplemental Information H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015-12/31/2015 ATTACHMENT 2 Supplemental Information This attachment includes supplemental information to the gaseous and liquid effluents report.
Page 2-1 Supplemental Information H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015-12/31/2015 I.
Regulatory Limits - Per Unit A. Noble Gases - Air Dose
- 1. Calendar Quarter Gamma Dose
- 2. Calendar Quarter Beta Dose
- 3. Calendar Year Gamma Dose
- 4. Calendar Year Beta Dose B. Liquid Effluents - Dose
- 1. Calendar Quarter Total Body Dose
- 2. Calendar Quarter Organ Dose
- 3. Calendar Year Total Body Dose
- 4. Calendar Year Organ Dose
=5
=10
=10
= 20
= 1.5
=5
=3
=10 mRAD mRAD mRAD mRAD mREM mREM mREM mREM C. Gaseous Effluents - lodine-131 & 133, Tritium, and Particulates with Half-lives> 8 days
- 1. Calendar Quarter Organ Dose
= 7.5 mREM
- 2. Calendar Year Organ Dose
= 15 mREM II.
Maximum Permissible Effluent Concentrations A. Gaseous Effluents
- 1. Information found in Offsite Dose Calculation Manual B. Liquid Effluents
- 1. Information found in 10 CFR Part 20, Appendix B, Table 2, Column 2 Ill.
Average Energy (not applicable)
IV.
Measurements and Approximations of Total Radioactivity Analyses of specific radionuclides in selected or composited samples as described in the ODCM are used to determine the radionuclide composition of the effluent. A summary description of the method used for estimating overall errors associated with radioactivity measurements is provided as part of this attachment.
- v.
Batch Releases A. Liquid Effluents Jan -Jun Jul - Dec
- 1. Total Number of Batch Releases
=
6.00E+01 2.20E+01
- 2. Total Time (min) for Batch Releases
=
1.12E+04 4.24E+03
- 3. Maximum Time (min) for a Batch Release
=
3.24E+02 2.44E+02
- 4. Average Time (min) for Batch Releases
=
1.87E+02 1.93E+02
- 5. Minimum Time (min) for a Batch Release
=
1.10E+01 1.30E+02
- 6. Average Dilution Water Flow During
=
3.25E+05 4.00E+05 Release (gpm)
B. Gaseous Effluents Jan -Jun Jul -Dec
- 1. Total Number of Batch Releases
=
4.90E+01 4.00E+01
- 2. Total Time (min) for Batch Releases
=
4.55E+04 2.61E+04
- 3. Maximum Time (min) for a Batch Release
=
1.84E+04 9.78E+03
- 4. Average Time (min) for Batch Releases
=
9.28E+02 6.53E+02
- 5. Minimum Time (min) for a Batch Release
=
1.70E+01 3.80E+01 VI.
Abnormal Releases See Attachment 5, Unplanned Offsite Releases.
Page 2-2 Supplemental Information H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Carbon-14 Carbon-14 (C-14), with a half-life of 5730 years, is a naturally occurring isotope of carbon produced by cosmic ray interactions in the atmosphere. Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. C-14 is also produced in commercial nuclear reactors, but the amounts produced are much less than those produced naturally or from weapons testing.
In Regulatory Guide 1.21, Revision 2, "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste", the NRC recommends U.S. nuclear power plants evaluate whether C-14 is a "principal radionuclide", and if so, report the amount of C-14 released.
Improvements over the years in effluent management practices and fuel performance have resulted in a decrease in gaseous radionuclide (non-C-14) concentrations, and a change in the distribution of gaseous radionuclides released to the environment. As a result, many sites show C-14 has become a "principal radionuclide" for the gaseous effluent pathway, as defined in Regulatory Guide 1.21, Rev. 2.
H.B. Robinson Steam Electric Plant 2015 ARERR contains estimates of C-14 radioactivity released in 2015, and estimates of public dose resulting from the C-14 effluent.
Because the dose contribution of C-14 from liquid radioactive waste is much less than that contributed by gaseous radioactive waste, evaluation of C-14 in liquid radioactive waste is not required (Ref. Reg. Guide 1.21, Rev. 2). The quantity of gaseous C-14 released to the environment can be estimated by use of a C-14 source term scaling factor based on power generation (Ref. Reg. Guide 1.21, Rev. 2}. Many documents provide information related to the magnitude of C-14 in typical effluents from commercial nuclear power plants. Those documents suggest that nominal annual releases of C-14 in gaseous effluents are approximately 5 to 7.3 curies from PWRs (Ref. Reg. Guide 1.21, Rev. 2}. A more recent study recommends a higher C-14 gaseous source term scaling factor of approximately 9.0 to 9.8 Ci/GWe-yr for a PWR (Westinghouse} (Ref. EPRI 1021106}. The H.B. Robinson Steam Electric Plant ODCM states the expected C-14 generation to be 7.3 Curies assuming 292 effective full power days (EFPD} in a calendar year. 2.8 of the 7.3 Curies are released in batch mode from the Containment building and Waste Gas Decay Tanks.
The remaining 4.5 Curies are released in continuous mode from the Auxiliary and Fuel Handling buildings. The total C-14 activity released compares favorably with more recent studies. For the H.B. Robinson Steam Electric Plant 2015 ARERR, a source term scaling factor using actual EFPD of 307.59 days is assumed. Using the source term scaling factor from H.B. Robinson Steam Electric Plant in 2015 results in a site total C-14 gaseous release estimate to the environment of 7.86 Curies, 2.95 Curies in batch mode and 4.74 Curies in continuous mode.
C-14 releases in PWRs occur primarily as a mix of organic carbon and carbon dioxide released from the waste gas system. Since the PWR operates with a reducing chemistry, most, if not all, of the C-14 species initially produced are organic (e.g., methane}. As a general rule, C-14 in the primary coolant is essentially all organic with a large fraction as a gaseous species. Any time the RCS liquid or gas is exposed to an oxidizing environment (e.g. during shutdown or refueling), a slow transformation from an organic to an inorganic chemical form can occur.
Various studies documenting measured C-14 releases from PWRs suggest a range of 70% to 95% organic with an average of 80%
organic with the remainder being C02 (Ref. EPRI TR-105715}. For the H.B. Robinson Steam Electric Plant 2015 ARERR a value of 70% organic C-14 is assumed.
Public dose estimates from airborne C-14 are performed using dose models in and Regulatory Guide 1.109. The dose models and assumptions used are documented in the H.B. Robinson Steam Electric Plant ODCM.
The estimated C-14 dose impact on the maximum organ dose from airborne effluents released from H.B. Robinson Steam Electric Plant in 2015 is well below the 10CFR50, Appendix I, ALARA design objective (i.e., 15 mrem/yr per unit}.
Page 2-3 Supplemental Information H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015-12/31/2015 Dose from Evaporation of Lake Robinson Evaporation of water containing tritium in Lake Robinson creates an exposure pathway to a member of the public.
Murray and Trettle, Inc. was contracted to perform an evaluation of the dose to a member of the public from evaporation of tritium in Lake Robinson. Results of the evaluation are contained in report "Impact of Tritium Release from Lake Robinson at the Robinson Nuclear Plant for 2015'. Using the methodology described in ODCM 2.5.3, the following is a summary of tritium activity released through evaporation and resulting dose for 2015.
- 1. H-3 Activity Released
- Year 4.83E+01 2.45E-01 Tritium in Fish from Lake Robinson NOTE Concentrations of radionuclides used in this specific fish consumption pathway are determined by averaging the monthly concentrations detected in environmental location (REMP) SW-40. In 2015, no plant related gamma emitting radionuclides were detected. Tritium was detected each month, as expected. Since tritium is consistently detected in Lake Robinson REMP samples, tritium concentration in the fish is assumed to be in equilibrium with Lake Robinson.
Using the methodology and data described in NRC Regulatory Guide 1.109, Rev.1, October 1977, Equation A-1, Table E-5, and Table E-11, the following is a summary of average concentration consumed and resulting dose for 2015.
- 1. Avg. H-3 Concentration
- Units pCi/L mREM Year 2.60E+03 5.73E-03
- The dose factor for H-3 is the same for all organs and Total Body (with the exception of Bone, which is 0. OOE+OO).
NOTE:
This information was previously included in the H.B. Robinson Steam Electric Plant AREOR. ORR 02012901 was written to include the fish dose calculation methodology in the next ODCM revision, and report in the ARERR.
Page 2-4 Supplemental Information H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Overall Estimate of Error for Effluent Radioactivity Release Reported The estimated percentage of overall error for both Liquid and Gaseous effluent release data at H.B. Robinson Steam Electric Plant has been determined to be +/- 30.3%. This value was derived by taking the square root of the sum of the squares of the following discrete individual estimates of error:
- 1.
Flow Rate Determining Devices =
+/-20%
- 2.
Counting Statistical Error
=
+/-20%
- 3.
Calibration Error
=
+/-10%
- 4.
Calibration Source Error
=
+/-2.5%
- 5.
Sample Preparation Error
=
+/-3%
Page 2-5 Supplemental Information H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015-12/31/2015 Summary of Changes in Land Use Census Affecting Effluent Dose Calculations The 2015 Land Use Census was performed July 30, 2015, and the results were certified and made available for use on February 29, 2016. The following are changes to residences, gardens, and milk animals from the previous year.
Residences No changes to nearest residence in each sector.
Gardens The garden in the WSW sector at 0.86 miles was removed and no other garden was identified within the 5 mile radius.
Meat Animals No changes to nearest meat animal in each sector.
Milk Animals No changes to nearest milk animal in each sector.
Environmental Monitoring Locations No changes to environmental monitoring locations in each sector.
Page 2-6 Solid Radioactive Waste Disposal H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 ATTACHMENT 3 Solid Radioactive Waste Disposal This attachment includes a summary of the solid waste shipped off-site for burial and/or disposal, including:
Container volume Total Curie content (specify whether determined by measurement or estimate)
Principal Radionuclides Source/Type of waste Solidification agent or absorbent Type of shipping container Number of shipments Other relevant information as necessary Page 3-1 Solid Radioactive Waste Disposal H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Type of Number of Number of Waste Container Solidification Burial Total Waste Shipped Shipments Containers Class Type Agent Volume Activity (mJ)
(Curies)*
- 1.
Waste from Liquid Svstems
- a. Dewatered Secondary Resins
- b. Dewatered Primary Resins 2
2 A-S 8-120 Poly NIA 6.814 8.95 HIC
- c. Evaporator Concentrates
- d. Dewatered Mechanical Filters
- e. Dewatered Demineralizers
- f.
Solidified (cement) Acids, Oils, Sludge
- 2.
Orv Solid Waste
- a. Dry Active Waste 7
9 A-U 20' Sealand NIA 283 0.491 (compacted)
- b. Dry Active Waste (non-A-U 14-195 NIA 5.874 0.751 compacted)
Steel Liner
- c.
Dry Active Waste (brokered)
- d. Irradiated Components
- 3.
Total Solid Waste 10 12 295.688 10.192
- Measurement Page 3-2 Solid Radioactive Waste Disposal H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Type of Waste Shipped Radionuclide
% Abundance
- 1.
Waste from Liquid Systems
- a. Dewatered Secondary Resins
- b. Dewatered Primary Resins
- c. Evaporator Concentrates
- d. Dewatered Mechanical Filters
- e. Dewatered Demineralizers
- f.
Solidified (cement) Acids, Oils, Sludge
- 2.
Orv Solid Waste
- a. Dry Active Waste (compacted)
NIA Ni-63 Fe-55 Co-60 Co-58 C-14 Cs-137 Mn-54 Sb-125 Cs-134 Co-57 Ag-110m H-3 Ni-59 Sr-90 Nb-95 Ce-144 Sb-124 Sn-113 Tc-99 1-129 NIA NIA NIA NIA Ni-63 Fe-55 Co-60 Co-58 H-3 Sb-125 Nb-95 C-14 Zr-95 Mn-54 Ag-110m Ce-144 Tc-99 Cs-137 Co-57 Cr-51 Sn-113 Sr-90 1-129 Te-123m Fe-59 NIA 30.4 24.8 20.8 9.08 6.23 2.84 2.58 1.02 0.673 0.611 0.279 0.265 0.167 0.067 0.046 0.035 0.028 0.023 0.022 0.002 NIA NIA NIA NIA 36.0 32.7 25.2 2.58 0.975 0.568 0.547 0.415 0.302 0.263 0.105 0.101 0.052 0.047 0.032 0.027 0.024 0.010 0.007 0.005 0.004 Page 3-3 Solid Radioactive Waste Disposal H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015
- b. Dry Active Waste (non-compacted)
Ni-63 Co-60 Fe-55 Co-58 Nb-95 C-14 Zr-95 Mn-54 Ce-144 H-3 Cs-137 Sr-90 Tc-99 1-129
- c.
Dry Active Waste (brokered)
N/A
- d. Irradiated Components N/A 49.2 23.7 21.7 3.21 0.857 0.492 0.365 0.141 0.121 0.093 0.045 0.018 0.017 0.004 N/A N/A Page 3-4 Meteorological Data H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 ATTACHMENT 4 Meteorological Data This attachment includes a summary of meteorological joint frequency distributions of wind speed, wind direction, and atmospheric stability (hours of occurrence).
Page 4-1
Wind Stability Speed Class (mph)
N NNE 0.75-3.50 0
0 3.51-7.50 3
12 7.51-12.50 10 5
A 12.51-18.50 1
0 18.51-25.00 0
0 25+
0 0
0.75-3.50 1
5 3.51-7.50 29 42 7.51-12.50 11 7
B 12.51-18.50 0
0 18.51-25.00 0
0 25+
0 0
0.75-3.50 3
7 3.51-7.50 54 64 7.51-12.50 22 10 c
12.51-18.50 4
0 18.51-25.00 0
0 25+
0 0
0.75-3.50 47 97 3.51-7.50 268 434 7.51-12.50 153 219 D
12.51-18.50 10 22 18.51-25.00 0
0 25+
0 0
Meteorological Data H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015-12/31/2015 Hours of Occurrence Sector NE ENE E
3 7
2 5
1 1
2 1
16 23 10 33 39 27 18 34 30 1
1 0
0 0
7 20 29 45 0
0 0
0 0
0 1
4 6
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
4 7
12 12 10 5
1 7
3 46 18 15 20 22 17 15 20 36 3
0 0
0 2
3 8
9 24 0
0 0
0 0
0 0
2 5
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
13 11 18 16 7
8 4
7 5
37 20 10 22 14 22 10 18 35 0
0 0
0 2
6 8
12 21 0
0 0
0 0
0 0
0 4
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
115 98 110 79 79 56 51 46 50 189 125 69 31 53 174 183 186 126 8
1 0
0 0
27 96 68 55 0
0 0
0 0
0 1
6 3
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
WSW w
WNW NW NNW 0
0 0
0 0
36 18 12 5
1 25 11 12 7
3 0
0 0
2 3
0 0
0 0
0 0
0 0
0 0
5 2
0 1
0 26 12 7
12 11 21 0
4 11 8
2 0
1 0
0 0
0 0
0 0
0 0
0 0
0 7
4 3
0 3
19 13 15 18 11 7
1 5
5 9
2 0
1 1
1 0
0 0
0 0
0 0
0 0
0 45 37 29 21 23 57 34 36 48 113 19 9
13 9
59 1
1 2
3 18 0
0 1
0 0
0 0
0 0
0 Page 4-2
Wind Stability Speed Class (mph)
N NNE 0.75-3.50 64 48 3.51-7.50 66 7
7.51-12.50 3
0 E
12.51-18.50 0
0 18.51-25.00 0
0 25+
0 0
0.75-3.50 34 7
3.51-7.50 9
0 7.51-12.50 0
0 F
12.51-18.50 0
0 18.51-25.00 0
0 25+
0 0
0.75-3.50 44 9
3.51-7.50 1
0 7.51-12.50 0
0 G
12.51-18.50 0
0 18.51-25.00 0
0 25+
0 0
Meteorological Data H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 -12/31/2015 Hours of Occurrence Sector NE ENE E
SSW SW 26 23 19 19 30 117 130 126 104 2
3 1
3 4
70 86 97 85 0
0 0
0 0
1 12 13 8
0 0
0 0
0 0
0 1
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 7
4 2
4 7
48 59 49 32 0
0 0
0 0
5 13 8
7 0
0 0
0 0
0 0
0 1
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
1 0
1 10 17 29 28 14 0
0 0
0 0
0 2
1 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
WSW w WNW NW NNW 70 50 27 62 52 33 22 23 47 141 3
2 3
4 15 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
23 29 46 34 68 7
3 7
19 65 0
0 1
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 26 27 20 62 111 1
0 0
6 10 1
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 Page 4-3 Unplanned Offsite Releases H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015-12/31/2015 ATTACHMENT 5 Unplanned Offsite Releases This attachment includes a summary of the unplanned offsite releases of gaseous and liquid radioactive effluents.
Page 5-1 Unplanned Offsite Releases H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 H.B. Robinson Steam Electric Plant did not experience any unplanned offsite effluent releases in 2015.
Page 5-2 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 ATTACHMENT 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public (includes fuel cycle dose calculation results)
This attachment includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site for each calendar quarter for the calendar year of the report as well as the total dose for the calendar year.
This attachment also includes an assessment of radiation doses to the maximum exposed member of the public from all uranium fuel cycle sources within 8 km of the site for the calendar year of this report to show conformance with 40 CFR Part 190.
Methods for calculating the dose contribution from liquid and gaseous effluents are given in the Offsite Dose Calculation Manual (ODCM).
Page 6-1 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Gaseous Effluents Dose Summary Units Q!r..1 Qtr2 Qtr 3 A. Noble Gases
- 1. Maximum Gamma Air mRAD 8.60E-04 7.26E-02 1.62E-03 (a)
Limit mRAD 5.00E+OO 5.00E+OO 5.00E+OO (b) % of Limit 1.72E-02 1.45E+OO 3.25E-02
- 2. Maximum Beta Air mRAD 5.31E-04 2.56E-02 1.39E-03 (a)
Limit mRAD 1.00E+01 1.00E+01 1.00E+01 (b) % of Limit 5.31 E-03 2.56E-01 1.39E-02 Receptor Location 0.42 km SSE B. Iodine, H-3, & Particulates
- 1. Maximum Organ Dose mREM 1.29E-01 1.31E-01 1.32E-01 (a) Limit mREM 7.50E+OO 7.50E+OO 7.50E+OO (b) % of Limit 1.72E+OO 1.74E+OO 1.76E+OO Receptor Location 0.42 km SSE Critical Age CHILD Critical Organ BONE
~
Year 3.78E-03 7.88E-02 5.00E+OO 1.00E+01 7.56E-02 7.88E-01 7.57E-03 3.51E-02 1.00E+01 2.00E+01 7.57E-02 1.75E-01 1.32E-01 5.24E-01 7.50E+OO 1.50E+01 1.76E+OO 3.49E+OO Page 6-2 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Liquid Effluents Dose Summary Units Q1l1 Q1r.l
~
A Batch & Continuous Mode
- 1. Maximum Organ Dose mREM 1.70E-04 4.88E-04 4.29E-06 (a) Limit mREM 5.00E+OO 5.00E+OO 5.00E+OO (b) % of Limit 3.41E-03 9.75E-03 8.58E-05
- 2. Maximum Total Body Dose mREM 1.66E-04 1.64E-04 4.32E-06 (a)
Limit mREM 1.50E+OO 1.50E+OO 1.50E+OO (b) % of Limit 1.11 E-02 1.10E-02 2.88E-04 Critical Age ADULT Critical Organ GI-LL/
Q!!:-4 Year 5.38E-05 7.16E-04 5.00E+OO 1.00E+01 1.08E-03 7.16E-03 5.39E-05 3.89E-04 1.50E+OO 3.00E+OO 3.59E-03 1.30E-02 Page 6-3 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 40 CFR Part 190 Uranium Fuel Cycle Dose Calculation Results In accordance with the requirements of 40 CFR Part 190, the annual dose commitment to any member of the general public shall be calculated to assure that doses are limited to 25 rnillirerns to the total body or any organ with the exception of the thyroid which is limited to 75 rnillirerns. The fuel cycle dose assessment for H.B. Robinson Stearn Electric Plant includes liquid and gaseous effluent dose contributions from H.B. Robinson Stearn Electric Plant and direct and air-scatter dose from the onsite ISFSI. No other direct or air-scatter source or uranium fuel cycle facility contributes significantly to the maximum exposed individual. Included om the gaseous effluent dose below is the estimated dose contributed by Carbon-14 (Ref. Attachment 2, Supplemental Information, of this report for further information). Also included is dose from evaporation of H-3 in Lake Robinson and H-3 in fish from Lake Robinson.
The combined dose to a maximum exposed individual from effluent releases, combined with the additional dose pathways, is below 40 CFR Part 190 limits as shown by the following summary.
Note: The 40 CFR Parl 190 effluent dose analysis to the maximum exposed individual from liquid and gas re/eases does not include the dose from noble gases (i.e., total body and skin) due to the low significance compared to other dose pathways.
40 CFR Part 190 Effluent Dose Summary A. Gaseous Effluent Dose
- 1. Location
- 2. Critical Age
- 3. Critical Organ
- 4. Organ Dose (rnREM)
- 5. Total Body Dose (rnREM)
B. Liquid Effluent Dose
- 1. Location
- 2. Critical Age
- 3. Critical Organ
- 4. Organ Dose (rnREM)
- 5. Total Body Dose (rnREM)
C. Lake Robinson Evaporation H-3 Dose
- 1. Location
- 2. Critical Age
- 3. Critical Organ
- 4. Organ Dose (rnREM)
- 5. Total Body Dose (rnREM)
D. H-3 in Fish from Lake Robinson
- 1. Location
- 2. Critical Age
- 3. Critical Organ
- 4. Organ Dose (rnREM)
- 5. Total Body Dose (mREM) 0.42 km SSE CHILD BONE 5.24E-01 4.19E-01 6.76 km NE ADULT Gl-LLI 7.16E-04 3.89E-04 6.38 km N CHILD N/A 2.45E-01 2.45E-01 Lake ADULT N/A 5.73E-03 5.73E-03 Page 6-4 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Dose contributions from Carbon-14 in gaseous effluents have been determined from ODCM 3.16, Methodology for Carbon-14 Dose. The maximum dose rate to the nearest real individual from the release of Carbon-14 in batch and continuous gaseous effluents is conservatively calculated to be less than 5.24E-01 mrem/yr based on 7.86 Curies released in 2015 (Ref. Attachment 2, Supplemental Information, of this report).
Dose contributions from evaporation of Tritium Lake Robinson have been determined from ODCM 2.5.3, Dose from Evaporation of Lake Robinson. The maximum dose rate to the nearest real individual from evaporation of Tritium in Lake Robinson is conservatively calculated to be less than 2.45E-01 mrem/yr based on 48.3 Curies released in 2015 (Ref. Attachment 2, Supplemental Information, of this report).
Dose contributions from Tritium in fish in Lake Robinson have been determined using NRC Regulatory Guide 1.109, Rev.1, October 1977, Equation A-1, and data from REMP location SW-40. This information was previously included in the H.B. Robinson Steam Electric Plant AREOR. DRR 02012901 was written to include the fish dose calculation methodology in the next ODCM revision, and report in the ARERR. The maximum dose rate to the nearest real individual from consuming the fish in Lake Robinson is conservatively calculated to be less than 5. 73E-03 mrem/yr based on an average concentration of 2.60E+03 pCi/L consumed in 2015 (Ref. Attachment 2, Supplemental Information, of this report).
Direct and air-scatter radiation dose contributions from the onsite ISFSI at H.B. Robinson Steam Electric Plant have been calculated and documented in the ISFSI Safety Analysis Report. The dose rate to the maximum exposed individual from the ISFSI is conservatively calculated to be less than 5 mrem/yr.
The below excerpt from the H.B. Robinson Steam Electric Plant ISFSI Safety Analysis Report is provided to document the conclusion that the H.B. Robinson Steam Electric Plant ISFSI contributes less than 6 mrem/year to the maximum exposed individual.
7.6.2 ANALYSIS OF MULTIPLE CONTRIBUTION The maximally exposed member of the public would receive approximately 1. 6 mrem per year from an ISFSI made up of a three-unit HSM (reference Figure 7.6.1). An ISFSI consisting of an eight-unit HSM would contribute approximately 4.3 mrem per year. This is a result of external radiation only; there are no gaseous, particulate, or liquid effluents associated with the nonnal operation of the ISFSI. It can be concluded that the actual exposure contribution from the ISFSI along with the total of all other uranium fuel cycle activities is within the regulatory limits set forth in 40CFR190.
Assessment of the actual dose from direct radiation is performed as part of the H.B. Robinson Steam Electric Plant REMP and reported in the AREOR. During 2015, the assessment of dose from direct radiation, performed as part of the REMP, demonstrated no measurable contribution above background attributable to H.B. Robinson Steam Electric Plant operations.
Total dose from liquid and gaseous effluents from H.B. Robinson Steam Electric Plant and the additional pathways mentioned above is conservatively estimated to be less than 6 mrem/yr for total body and organ. It is recognized summing dose for different organs and age groups is not entirely accurate. However, the sum of the organ and age specific doses will always be less than the sum of the maximums of each. Therefore, summing the maximum values of each provides the most conservative value to ensure compliance with 40 CFR 190. The dose from all pathways related to operation of H.B. Robinson Steam Electric Plant meets the 40 CFR Part 190 requirements of an annual dose commitment to any member of the general public of less than 25 mrem total body or any organ and 75 mrem to the thyroid.
Page 6-5 Information to Support the NEI Ground Water Protection Initiative H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 ATTACHMENT 7 Information to Support the NEI Ground Water Protection Initiative This attachment includes a summary of voluntary reports made in accordance with the NEI Ground Water Protection Initiative and a summary of ground water well sample data.
Page 7-1 Information to Support the NEI Ground Water Protection Initiative H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 H.B. Robinson Steam Electric Plant has implemented a Ground Water Protection program in accordance with NEI 07-
- 07. This initiative was developed to ensure timely and effective management of situations involving inadvertent releases of licensed material to ground water. As part of this program, H.B. Robinson Steam Electric Plant monitored 28 wells in 2015. 11 wells not sampled as part of the ODCM REMP are reported below. The remaining 17 wells are sampled in accordance with the ODCM REMP and reported in the AREOR.
Wells are sampled quarterly. Ground water samples are analyzed for tritium and gamma emitters. No gamma, other than naturally occurring radionuclides, were identified in well samples during 2015. There were no anomalous results identified in 2015.
Results from sampling during 2015 are shown in the table below.
No events meeting the criteria for voluntary notification per NEI 07-07, Industry Ground Water Protection Initiative, occurred at H.B. Robinson Steam Electric Plant in 2015. No special dose calculations were performed as part of the Ground Water Protection program.
Key to below table.
NS pCi/I
<MDA 20,000 pCi/I 1,000,000 pCi/I Not scheduled to be sampled, not sampled due to insufficient volume in well, or well inaccessible during outage.
picocuries per liter.
less than minimum detectable activity, typically 250 pCi/I.
the Environmental Protection Agency drinking water standard for tritium. This standard applies only to water used for drinking.
the 10 CFR Part 20, Appendix B, Table 2, Column 2, Effluent Concentration Limit for tritium.
Well Location I Description Tritium Concentration (pCill)
- of Name 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Samples MW-1R NPDESAsh
<MDA
<MDA
<MDA
<MDA 4
MW-2R NPDESAsh
<MDA
<MDA
<MDA
<MDA 4
MW-3R NPDESAsh 1.28E+03 1.27E+03 1.15E+03 1.12E+03 4
MW-4R NPDES Ash 2.61E+02
<MDA
<MDA
<MDA 4
MW-5 NPDESAsh 7.33E+02 4.80E+02 4.91E+02 5.83E+02 4
MW-6 NPDESAsh 1.11E+03 9.37E+02 8.72E+02 8.06E+02 4
MW-7 NPDESAsh 4.75E+02 4.17E+02 2.59E+02 2.37E+02 4
P-1 North of Discharge Canal 1.51E+03 6.77E+02 4.80E+02 1.13E+03 4
P-2 South of Discharge Canal
<MDA
<MDA
<MDA 2.20E+02 4
PSW-04 West of Plant Site
<MDA
<MDA
<MDA
<MDA 4
PSW-05 SW Plant, Background Well
<MDA
<MDA
<MDA 1.82E+02 4
Page 7-2 Inoperable Equipment H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 ATTACHMENT 8 Inoperable Equipment This attachment includes an explanation of inoperable instruments related to effluent monitoring in excess of allowed time defined by licensing bases and an explanation of permanent or temporary outside liquid storage tanks exceeding 10 Curies total activity (excluding tritium and dissolved or entrained noble gases).
Page 8-1 Inoperable Equipment H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015-12/31/2015 H.B. Robinson Steam Electric Plant did not experience inoperable equipment relevant to effluent monitoring in excess of ODCM limits during 2015.
H.B. Robinson Steam Electric Plant did not experience permanent or temporary outside liquid storage tanks not surrounded by liners, dikes, or walls, capable of holding the tank's contents and that does not have tank overflows and surrounding area drains connected to the Liquid Waste Disposal System exceeding 10 Curies total activity (excluding tritium and dissolved or entrained noble gases) during 2015.
Page 8-2 Summary of Changes to the Offsite Dose Calculation Manual H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 ATTACHMENT 9 Summary of Changes to the Offsite Dose Calculation Manual Example This attachment includes a summary of changes to the ODCM and Radiological Effluent Controls.
Page 9-1 Summary of Changes to the Offsite Dose Calculation Manual ODCM Revision 33 H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 -12/31/2015 The H.B. Robinson Steam Electric Plant ODCM did not warrant revision during the period 1/1/2015 - 12/31/2015.
Therefore, it was not revised in 2015. Revision 33, which was submitted along with the 2011 ARERR, continues to remain the most recent revision.
Page 9-2 0
Summary of Changes to the Process Control Program H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 -12/31/2015 ATTACHMENT 10 Summary of Changes to the Process Control Program This attachment includes a summary of changes to the PCP.
Page 10-1 0
Summary of Changes to the Process Control Program H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 The H.B. Robinson Steam Electric Plant PCP was not revised in 2015. The most recent revision is 6 and is provided on the following pages.
Page 10-2 0
Summary of Changes to the Process Control Program H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 PROGRESS ENERGY H. B. ROBINSON - UNIT 2 PROCESS CONTROL PROGRAM (PCP)
REVISIONS DOCKET NO, S0-261 EFFECTIVe DATE: 0 I- 0 7 - I 0 REVIEWED AND ACCEPTED BY PNSC: ~h4 DATE". 01-CJi-lO PNSC CHAIRMAN PCP RC\\lision 6 Pagel of 6 Page 10-3 0
Summary of Changes to the Process Control Program H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015-12/31/2015 LIST OF EFFECTIVE PAGES EFFECTIVE PAGES REVISION Cover Sheet LEP 3 through 6 6
6 6
SUMMARY
OF CHANGES Revised Section 2.0 to specify dewatering and solidification may be performed by qualified vendor or qualified Progress Energy personnel in accordance with a qualified PCP or a program approved by the NRC or burial site facility.
Revised Section 3.1.2 to include review of both vendor and RNP operating procedures, retention of both vendor and RNP completed records, and monitoring of both vendor and RNP operations for compliance with TRMS 3.22 requirements.
Revised Section 3.1.3 to include RC Supervisor (with accountability for radioactive waste processing) responsibility for advising the RC Superintendent on the adequacy of both vendor and RNP operating procedures.
Revised Section 3.2 to clarify that specified vendor requirements apply to vendors who supply both solidification and dewatering services to RNP.
PCP Revision 6 Page 2of6 Page 10-4
1.0 SCOPE 0 Summary of Changes to the Process Control Program H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 H.B. ROBINSON PROCESS CONTROL PROGRAM This program established the management systems and controls that the Robinson Nuclear Plant (RNP) uses to ensure safe and effective solidification and dewatering of various low-level radioactive waste liquids and slurries for offsite disposal.
2.0 OBJECTIVE It is the objective of this program that solidification and/or dewatering of various low-level radioactive waste liquids and slurries (including oily wastes) for offsite disposal will be performed by either qualified vendors or qualified Progress Energy personnel, in accordance with a qualified PCP or a program approved by the NRC or burial site facility. The quality of the solidified and/or dewatered product shall meet or exceed regulatory requirements and the disposal site criteria prior to release from the RNP site for shallow disposal.
3.0 MANAGEMENT PROGRAM 3.1 Responsibilities 3.1.1 The Plant General Manager is responsible for ensuring that waste is shipped in accordance with the appropriate state and federal regulations.
3.1.2 The Superintendent - Radiation Control (RC) or designee is responsible for:
PCP Revision 6
- a. Advising the Plant General Manager on the appropriate technical standards, regulations and requirements as related to solidification, dewatering and shipping.
- b. Ensuring changes to the vendor's Process Control Program (PCP),
vendor and RNP operating procedures, and proposed contractual agreements are reviewed and advising the Plant General Manager as to their adequacy.
- c. Retaining vendor - supplied documentation and completed RNP records for NRC inspection and review.
Page 3of6 Page 10-5 0
Summary of Changes to the Process Control Program H.B. Robinson Steam Electric Plant Unit 2 Period 1 /1 /2015 - 12/3112015 3.1 Responsibilities (continued)
PCP Revision 6
- d. Ensuring vendor and RNP operations are monitored for compliance with:
- 1.
Section 3.22 Technical Requirements Manual (TRMS). The Solid Radwaste System shall be used in accordance with a PCP to process wet radioactive waste to meet shipping and burial ground requirements.
- 2.
Section 3.22.A TRMS. With the provisions of the PCP not satisfied, immediately suspend shipments of defectively processed or defectively packaged solid radioactive waste from the site.
- 3.
Section 3.22.B TRMS. If any test specimen, as required by the PCP, fails to verify solidification, the solidification of the batch under test shall be immediately suspended until such time as additional test specimens can be obtained, alternative solidification parameters can be determined in accordance with Section 5.5.17 of the TRMS. Solidification of the batch may then be resumed using alternative solidification parameters as determined by the PCP.
- 4.
Section 3.22.1 TRMS. The PCP shall be used to verify the solidification of one representative test specimen from every tenth batch of wet radioactive waste.
Page 4of6 Page 10-6 0
Summary of Changes to the Process Control Program H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015-12/31/2015 3.1 Responsibilities (continued)
Note: The following step is only required to be met if the initial test specimen from a batch of waste fails to verify solidification and continues until at least three consecutive initial test specimens demonstrate solidification.
- 5.
Section 3.22.2 TRMS. Collect and test representative test specimens of every consecutive batch of the same type of wet radioactive waste to verify solidification in accordance with the PCP.
3.1.3 The RC Supervisor with accountability for radioactive waste processing is responsible for advising the Superintendent-RC on:
- a.
The appropriate technical standards, regulations and requirements as related to solidification, dewatering and shipping.
- b.
The adequacy of the vendor's PCP, vendor and RNP operating procedures, and proposed contractual agreements.
3.2 Specification of Vendors The qualified solidification and/or dewatering vendor will:
3.2.1 Provide a qualified PCP or a program approved by:
- a.
NRC
- b.
Disposal site licensee 3.2.2 The vendor will perform the tests described in the PCP.
3.2.3 The vendor will supply the Superintendent - RC with all documentation required to demonstrate compliance with dewatering and/or solidification requirements.
3.2.4 The Superintendent-RC will retain documentation required to demonstrate compliance with solidification requirements and standards.
PCP Revision 6 Page 5of6 Page 10-7 0
Summary of Changes to the Process Control Program H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015-12/31/2015 4.0 MANAGEMENT/CONTRACTOR INTERACTIONS 4.1 The vendor is accountable to the Superintendent - RC for the solidification and/or dewatering of liquid wastes.
4.2 The RC Supervisor with accountability for radioactive waste processing handles the shipping of solidified and dewatering wastes and maintains required documentation. The vendor and the RC Supervisor may communicate on the matters as necessary.
5.0 ATTACHMENTS 5.1 None Applicable PCP Revision 6 Page 6of6 Page 10-8 1
Summary of Major Modifications to the Radioactive Waste Treatment Systems H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 ATTACHMENT 11 Summary of Major Modifications to the Radioactive Waste Treatment Systems This attachment includes a description of major modifications to the radioactive waste treatment systems that are anticipated to affect effluent releases.
Page 11-1 1
Summary of Major Modifications to the Radioactive Waste Treatment Systems H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 No major modifications to liquid, gaseous, solid, or mobile radioactive waste treatment systems occurred at H.B.
Robinson Steam Electric Plant in 2015.
Page 11-2 2
Errata to a Previous Year's ARERR Example H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 ATTACHMENT 12 Errata to a Previous Year's ARERR This attachment includes any amended pages from a previous year's ARERR.
Page 12-1 2
Errata to a Previous Year's ARERR Example H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 There are no changes to a previous year's ARERR.
Page 12-2
Serial: RNP-RA/16-0029 APR 21 2016 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEWED LICENSE NO. DPR-23 2015 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Ladies and Gentlemen:
David S. Hoffman H. B. Robinson Steam Electric Plant Unit 2 Director - Nuc Org Effectiveness Duke Energy Progress 3581 West Entrance Road Hartsville, SC 29550 0. 843 857 5239 F: 843 857 1319 10 CFR 50.36a(a)(2)
TS 5.6.3 Attached is the Annual Radioactive Effluent Release Report for H. 8. Robinson Steam Electric Plant (HBRSEP), Unit No. 2 for the period of January 1, 2015 through December 31, 2015. This report is submitted in accordance with 10 CFR 50.4, as required by 10 CFR 50.36a(a)(2) and HBRSEP, Unit No. 2, Technical Specifications (TS) Section 5.6.3.
This document contains no new Regulatory Commitments. If you have any questions regarding this submittal, please contact Mr. Scott Connelly, Manager (Acting) - Nuclear Regulatory Affairs, at (843) 857-1569.
Sincerely, -0 David S. Hoffm~ 71--
Director - Nuclear Organization Effectiveness DSH/am Attachment c:
NRC Regional Administrator, NRC, Region II D. Galvin, NRC Project Manager, NRR (w/o Attachment)
NRC Resident Inspector, HBRSEP
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/16-0029 50 Pages (including cover page)
DUKE ENERGY H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 RENEWED OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 RADIOACTIVE EFFLUENT RELEASE REPORT ANNUAL REPORT JANUARY 1, 2015-DECEMBER 31, 2015
(~ DUKE ENERGY.
H.B. Robinson Steam Electric Plant Unit 2 Annual Radioactive Effluent Release Report January 1, 2015 through December 31, 2015 Docket 50-261
Introduction The Annual Radioactive Effluent Release Report is pursuant to H.B. Robinson Steam Electric Plant Technical Specification 5.6.3 and ODCM 9.1. The below listed attachments to this report provide the required information. In addition, the ODCM is included pursuant to H.B. Robinson Steam Electric Plant Technical Specification 5.5.1.
Summary of Gaseous and Liquid Effluents Supplemental Information Solid Radioactive Waste Disposal Meteorological Data Unplanned Offsite Releases Assessment of Radiation Dose from Radioactive Effluents to Members of the Public Information to Support the NEI Ground Water Protection Initiative Inoperable Equipment Summary of Changes to the Offsite Dose Calculation Manual 0 Summary of Changes to the Process Control Program 1 Summary of Major Modifications to the Radioactive Waste Treatment Systems 2 Errata to a Previous Year's ARERR Summary of Gaseous and Liquid Effluents H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 ATTACHMENT 1 Summary of Gaseous and Liquid Effluents This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents as outlined in Regulatory Guide 1.21, Appendix B.
Page 1-1 Summary of Gaseous and Liquid Effluents H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Gaseous Effluents - Summation of All Releases Units Qtr 1 Qtr 2 Qtr 3 A. Fission and Activation Gases
- 1. Total Release Ci 1.18E-01 3.05E+OO 3.99E-01
- 2. Avg. Release Rate
µCi/sec 1.51 E-02 3.88E-01 5.01 E-02 B. lodine-131
- 1. Total Release Ci O.OOE+OO O.OOE+OO O.OOE+OO
- 2. Avg. Release Rate
µCi/sec O.OOE+OO O.OOE+OO O.OOE+OO C. Particulates Half-Life ~ 8 days
- 1. Total Release Ci O.OOE+OO 4.14E-06 2.66E-08
- 2. Avg. Release Rate
µCi/sec O.OOE+OO 5.27E-07 3.35E-09 D. Tritium
- 1. Total Release Ci 3.14E+OO 7.37E+OO 6.25E+OO
- 2. Avg. Release Rate
µCi/sec 4.04E-01 9.37E-01 7.87E-01 E. Carbon-14
- 1. Total Release Ci 1.90E+OO 1.92E+OO 1.94E+OO
- 2. Avg. Release Rate
µCi/sec 2.44E-01 2.44E-01 2.44E-01 F. Gross Alpha
- 1. Total Release Ci O.OOE+OO O.OOE+OO O.OOE+OO
- 2. Avg. Release Rate
µCi/sec O.OOE+OO O.OOE+OO O.OOE+OO Qtr4 Year 2.69E+OO 6.26E+OO 3.38E-01 1.98E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.17E-06 O.OOE+OO 1.32E-07 6.11E+OO 2.29E+01 7.69E-01 7.25E-01 1.94E+OO 7.70E+OO 2.44E-01 2.44E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 1-2 Summary of Gaseous and Liquid Effluents H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Gaseous Effluents - Elevated Releases - Continuous Mode
- Units Qtr 1 Qtr 2 Qtr 3 A. Fission and Activation Gases N/A Ci Total for Period Ci B. Iodines NIA Ci Total for Period Ci C. Particulates Half-Life ~ 8 days N/A Ci Total for Period Ci D. Tritium N/A Ci E. Carbon-14 N/A Ci F. Gross Alpha Total for Period Ci
- H.B. Robinson Steam Electric Plant Unit 2 does not have elevated releases.
Page 1-3 Summary of Gaseous and Liquid Effluents H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Gaseous Effluents - Elevated Releases - Batch Mode
- Units Qtr 1 A. Fission and Activation Gases N/A Ci Total for Period Ci
- 8. Iodines N/A Ci Total for Period Ci C. Particulates Half-Life ;:: 8 days N/A Ci Total for Period Ci D. Tritium NIA Ci E. Carbon-14 N/A Ci F. Gross Alpha Total for Period Ci
- H.B. Robinson Steam Electric Plant Unit 2 does not have elevated releases.
Page 1-4 Summary of Gaseous and Liquid Effluents H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Gaseous Effluents - Ground & Mixed-Mode Releases - Continuous Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Gases Ar-41 Ci O.OOE+OO 2.55E+OO O.OOE+OO O.OOE+OO 2.55E+OO Xe-133 Ci 8.94E-03 2.53E-03 3.43E-01 2.63E+OO 2.98E+OO Total for Period Ci 8.94E-03 2.56E+OO 3.43E-01 2.63E+OO 5.54E+OO B. Iodines None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO C. Particulates Half-Life ~ 8 days Co-58 Ci O.OOE+OO 1.95E-06 O.OOE+OO O.OOE+OO 1.95E-06 Total for Period Ci O.OOE+OO 1.95E-06 O.OOE+OO O.OOE+OO 1.95E-06 D. Tritium H-3 Ci 3.09E+OO 7.22E+OO 6.16E+OO 6.03E+OO 2.25E+01 E. Carbon-14 C-14 Ci 1.39E+OO 7.06E-01 1.42E+OO 1.23E+OO 4.74E+OO F. Gross Alpha Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 1-5 Summary of Gaseous and Liquid Effluents H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Gaseous Effluents - Ground & Mixed Mode Releases - Batch Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Gases Ar-41 Ci 3.13E-02 4.91 E-01 5.52E-02 5.89E-02 6.36E-01 Kr-85m Ci 2.56E-05 O.OOE+OO O.OOE+OO 3.77E-06 2.94E-05 Xe-131m Ci 3.54E-04 O.OOE+OO O.OOE+OO O.OOE+OO 3.54E-04 Xe-133m Ci 1.52E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.52E-03 Xe-133 Ci 6.62E-02 2.37E-03 O.OOE+OO 2.30E-03 7.09E-02 Xe-135 Ci 9.33E-03 O.OOE+OO O.OOE+OO 5.92E-05 9.39E-03 Total for Period Ci 1.09E-01 4.93E-01 5.52E-02 6.13E-02 7.19E-01 B. Iodines None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO C. Particulates Half-Life ;:: 8 days Co-58 Ci O.OOE+OO 2.18E-06 O.OOE+OO O.OOE+OO 2.18E-06 Co-60 Ci O.OOE+OO 6.92E-09 2.66E-08 O.OOE+OO 3.35E-08 Cs-137 Ci O.OOE+OO 4.25E-09 O.OOE+OO O.OOE+OO 4.25E-09 Total for Period Ci O.OOE+OO 2.19E-06 2.66E-08 O.OOE+OO 2.22E-06 D. Tritium H-3 Ci 4.41E-02 1.48E-01 9.41E-02 7.67E-02 3.63E-01 E. Carbon-14 C-14 Ci 8.62E-01 4.39E-01 8.81 E-01 7.68E-01 2.95E+OO F. Gross Alpha Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 1-6 Summary of Gaseous and Liquid Effluents H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Liquid Effluents - Summation of All Releases Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Products
- 1. Total Release Ci 2.93E-03 1.98E-02 1.41 E-02 8.27E-04 3.77E-02
- 2. Avg. Diluted Cone.
µCi/ml 1.23E-11 1.22E-10 5.71E-11 3.39E-12 4.23E-11 B. Tritium
- 1. Total Release Ci 2.25E+02 1.73E+02 1.43E+01 9.82E+01 5.11 E+02
- 2. Avg. Diluted Cone.
µCi/ml 9.46E-07 1.07E-06 5.77E-08 4.02E-07 5.73E-07 C. Dissolved & Entrained Gases
- 1. Total Release Ci 1.15E-03 1.90E-02 O.OOE+OO 1.15E-04 2.03E-02
- 2. Avg. Diluted Cone.
µCi/ml 4.83E-12 1.17E-10 O.OOE+OO 4.72E-13 2.27E-11 D. Gross Alpha
- 1. Total Release Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO
- 2. Avg. Diluted Cone.
µCi/ml O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO E. Volume of Liquid Waste
- 1. Continuous Releases liters 3.74E+06 O.OOE+OO O.OOE+OO 1.44E+06 5.18E+06
- 2. Batch Releases liters 4.39E+05 1.09E+06 3.66E+05 2.34E+05 2.13E+06 F. Volume of Dilution Water
- 1. Continuous Releases liters 2.28E+11 1.62E+11 2.47E+11 2.44E+11 8.91 E+11
- 2. Batch Releases liters 2.28E+11 1.62E+11 2.47E+11 2.44E+11 8.91 E+11 Excludes tritium, dissolved and entrained noble gases, and gross alpha.
Page 1-7 Summary of Gaseous and Liquid Effluents H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Liquid Effluents - Continuous Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Products F-18 Ci O.OOE+OO O.OOE+OO O.OOE+OO 1.16E-06 1.16E-06 Co-58 Ci 1.42E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.42E-05 Co-60 Ci 1.0SE-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.0SE-06 Total for Period Ci 1.52E-05 O.OOE+OO O.OOE+OO 1.16E-06 1.64E-05 B. Tritium H-3 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO C. Dissolved & Entrained Gases None Ci Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO D. Gross Alpha Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 1-8 Summary of Gaseous and Liquid Effluents H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Liquid Effluents - Batch Mode Units Qtr 1 Qtr 2 Qtr 3 Qtr4 Year A. Fission and Activation Products Mn-54 Ci 1.23E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.23E-05 Fe-55 Ci 7.86E-05 9.28E-04 1.33E-04 7.50E-05 1.21 E-03 Co-57 Ci 4.68E-06 1.33E-05 3.45E-06 O.OOE+OO 2.14E-05 Co-58 Ci 6.47E-05 3.12E-03 3.28E-03 1.73E-04 6.64E-03 Co-60 Ci 2.37E-03 3.40E-03 3.42E-04 2.04E-05 6.13E-03 Ni-63 Ci 1.28E-04 2.30E-03 2.01 E-03 3.16E-04 4.75E-03 Sr-89 Ci O.OOE+OO O.OOE+OO O.OOE+OO 7.47E-06 7.47E-06 Sr-90 Ci O.OOE+OO O.OOE+OO O.OOE+OO 9.74E-07 9.74E-07 Nb-95 Ci O.OOE+OO 2.07E-06 1.21 E-06 O.OOE+OO 3.28E-06 Ag-110m Ci 1.47E-06 3.10E-06 8.72E-06 O.OOE+OO 1.33E-05 Sn-117m Ci 1.97E-06 4.97E-04 4.88E-05 O.OOE+OO 5.48E-04 Sb-122 Ci O.OOE+OO 1.40E-05 O.OOE+OO O.OOE+OO 1.40E-05 Sb-124 Ci O.OOE+OO 3.46E-04 1.02E-04 O.OOE+OO 4.48E-04 Sb-125 Ci 1.70E-04 8.54E-03 8.07E-03 2.32E-04 1.70E-02 Te-123m Ci 2.02E-06 5.10E-04 5.01E-05 O.OOE+OO 5.62E-04 Te-131m Ci 2.48E-05 3.94E-06 O.OOE+OO O.OOE+OO 2.87E-05 Te-132 Ci O.OOE+OO 4.29E-06 4.75E-06 O.OOE+OO 9.04E-06 1-134 Ci O.OOE+OO O.OOE+OO 4.03E-06 O.OOE+OO 4.03E-06 1-135 Ci O.OOE+OO O.OOE+OO 1.48E-06 O.OOE+OO 1.48E-06 Cs-137 Ci 3.95E-05 4.04E-05 5.21 E-05 O.OOE+OO 1.32E-04 Ba-133 Ci O.OOE+OO 7.46E-07 O.OOE+OO O.OOE+OO 7.46E-07 Ce-141 Ci 3.09E-07 O.OOE+OO O.OOE+OO O.OOE+OO 3.09E-07 Eu-152 Ci 1.41 E-05 4.01 E-05 1.04E-05 O.OOE+OO 6.46E-05 Total for Period Ci 2.91 E-03 1.98E-02 1.41 E-02 8.26E-04 3.76E-02 B. Tritium H-3 Ci 2.25E+02 1.73E+02 1.43E+01 9.82E+01 5.11E+02 C. Dissolved & Entrained Gases Kr-89 Ci O.OOE+OO 1.04E-02 O.OOE+OO O.OOE+OO 1.04E-02 Xe-131 m Ci O.OOE+OO 1.63E-05 O.OOE+OO O.OOE+OO 1.63E-05 Xe-133m Ci O.OOE+OO 5.08E-05 O.OOE+OO O.OOE+OO 5.08E-05 Xe-133 Ci 1.15E-03 8.51E-03 O.OOE+OO 1.15E-04 9.78E-03 Xe-135 Ci O.OOE+OO 3.04E-06 O.OOE+OO O.OOE+OO 3.04E-06 Total for Period Ci 1.15E-03 1.90E-02 O.OOE+OO 1.15E-04 2.03E-02 D. Gross Alpha Total for Period Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Page 1-9 Supplemental Information H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015-12/31/2015 ATTACHMENT 2 Supplemental Information This attachment includes supplemental information to the gaseous and liquid effluents report.
Page 2-1 Supplemental Information H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015-12/31/2015 I.
Regulatory Limits - Per Unit A. Noble Gases - Air Dose
- 1. Calendar Quarter Gamma Dose
- 2. Calendar Quarter Beta Dose
- 3. Calendar Year Gamma Dose
- 4. Calendar Year Beta Dose B. Liquid Effluents - Dose
- 1. Calendar Quarter Total Body Dose
- 2. Calendar Quarter Organ Dose
- 3. Calendar Year Total Body Dose
- 4. Calendar Year Organ Dose
=5
=10
=10
= 20
= 1.5
=5
=3
=10 mRAD mRAD mRAD mRAD mREM mREM mREM mREM C. Gaseous Effluents - lodine-131 & 133, Tritium, and Particulates with Half-lives> 8 days
- 1. Calendar Quarter Organ Dose
= 7.5 mREM
- 2. Calendar Year Organ Dose
= 15 mREM II.
Maximum Permissible Effluent Concentrations A. Gaseous Effluents
- 1. Information found in Offsite Dose Calculation Manual B. Liquid Effluents
- 1. Information found in 10 CFR Part 20, Appendix B, Table 2, Column 2 Ill.
Average Energy (not applicable)
IV.
Measurements and Approximations of Total Radioactivity Analyses of specific radionuclides in selected or composited samples as described in the ODCM are used to determine the radionuclide composition of the effluent. A summary description of the method used for estimating overall errors associated with radioactivity measurements is provided as part of this attachment.
- v.
Batch Releases A. Liquid Effluents Jan -Jun Jul - Dec
- 1. Total Number of Batch Releases
=
6.00E+01 2.20E+01
- 2. Total Time (min) for Batch Releases
=
1.12E+04 4.24E+03
- 3. Maximum Time (min) for a Batch Release
=
3.24E+02 2.44E+02
- 4. Average Time (min) for Batch Releases
=
1.87E+02 1.93E+02
- 5. Minimum Time (min) for a Batch Release
=
1.10E+01 1.30E+02
- 6. Average Dilution Water Flow During
=
3.25E+05 4.00E+05 Release (gpm)
B. Gaseous Effluents Jan -Jun Jul -Dec
- 1. Total Number of Batch Releases
=
4.90E+01 4.00E+01
- 2. Total Time (min) for Batch Releases
=
4.55E+04 2.61E+04
- 3. Maximum Time (min) for a Batch Release
=
1.84E+04 9.78E+03
- 4. Average Time (min) for Batch Releases
=
9.28E+02 6.53E+02
- 5. Minimum Time (min) for a Batch Release
=
1.70E+01 3.80E+01 VI.
Abnormal Releases See Attachment 5, Unplanned Offsite Releases.
Page 2-2 Supplemental Information H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Carbon-14 Carbon-14 (C-14), with a half-life of 5730 years, is a naturally occurring isotope of carbon produced by cosmic ray interactions in the atmosphere. Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. C-14 is also produced in commercial nuclear reactors, but the amounts produced are much less than those produced naturally or from weapons testing.
In Regulatory Guide 1.21, Revision 2, "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste", the NRC recommends U.S. nuclear power plants evaluate whether C-14 is a "principal radionuclide", and if so, report the amount of C-14 released.
Improvements over the years in effluent management practices and fuel performance have resulted in a decrease in gaseous radionuclide (non-C-14) concentrations, and a change in the distribution of gaseous radionuclides released to the environment. As a result, many sites show C-14 has become a "principal radionuclide" for the gaseous effluent pathway, as defined in Regulatory Guide 1.21, Rev. 2.
H.B. Robinson Steam Electric Plant 2015 ARERR contains estimates of C-14 radioactivity released in 2015, and estimates of public dose resulting from the C-14 effluent.
Because the dose contribution of C-14 from liquid radioactive waste is much less than that contributed by gaseous radioactive waste, evaluation of C-14 in liquid radioactive waste is not required (Ref. Reg. Guide 1.21, Rev. 2). The quantity of gaseous C-14 released to the environment can be estimated by use of a C-14 source term scaling factor based on power generation (Ref. Reg. Guide 1.21, Rev. 2}. Many documents provide information related to the magnitude of C-14 in typical effluents from commercial nuclear power plants. Those documents suggest that nominal annual releases of C-14 in gaseous effluents are approximately 5 to 7.3 curies from PWRs (Ref. Reg. Guide 1.21, Rev. 2}. A more recent study recommends a higher C-14 gaseous source term scaling factor of approximately 9.0 to 9.8 Ci/GWe-yr for a PWR (Westinghouse} (Ref. EPRI 1021106}. The H.B. Robinson Steam Electric Plant ODCM states the expected C-14 generation to be 7.3 Curies assuming 292 effective full power days (EFPD} in a calendar year. 2.8 of the 7.3 Curies are released in batch mode from the Containment building and Waste Gas Decay Tanks.
The remaining 4.5 Curies are released in continuous mode from the Auxiliary and Fuel Handling buildings. The total C-14 activity released compares favorably with more recent studies. For the H.B. Robinson Steam Electric Plant 2015 ARERR, a source term scaling factor using actual EFPD of 307.59 days is assumed. Using the source term scaling factor from H.B. Robinson Steam Electric Plant in 2015 results in a site total C-14 gaseous release estimate to the environment of 7.86 Curies, 2.95 Curies in batch mode and 4.74 Curies in continuous mode.
C-14 releases in PWRs occur primarily as a mix of organic carbon and carbon dioxide released from the waste gas system. Since the PWR operates with a reducing chemistry, most, if not all, of the C-14 species initially produced are organic (e.g., methane}. As a general rule, C-14 in the primary coolant is essentially all organic with a large fraction as a gaseous species. Any time the RCS liquid or gas is exposed to an oxidizing environment (e.g. during shutdown or refueling), a slow transformation from an organic to an inorganic chemical form can occur.
Various studies documenting measured C-14 releases from PWRs suggest a range of 70% to 95% organic with an average of 80%
organic with the remainder being C02 (Ref. EPRI TR-105715}. For the H.B. Robinson Steam Electric Plant 2015 ARERR a value of 70% organic C-14 is assumed.
Public dose estimates from airborne C-14 are performed using dose models in and Regulatory Guide 1.109. The dose models and assumptions used are documented in the H.B. Robinson Steam Electric Plant ODCM.
The estimated C-14 dose impact on the maximum organ dose from airborne effluents released from H.B. Robinson Steam Electric Plant in 2015 is well below the 10CFR50, Appendix I, ALARA design objective (i.e., 15 mrem/yr per unit}.
Page 2-3 Supplemental Information H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015-12/31/2015 Dose from Evaporation of Lake Robinson Evaporation of water containing tritium in Lake Robinson creates an exposure pathway to a member of the public.
Murray and Trettle, Inc. was contracted to perform an evaluation of the dose to a member of the public from evaporation of tritium in Lake Robinson. Results of the evaluation are contained in report "Impact of Tritium Release from Lake Robinson at the Robinson Nuclear Plant for 2015'. Using the methodology described in ODCM 2.5.3, the following is a summary of tritium activity released through evaporation and resulting dose for 2015.
- 1. H-3 Activity Released
- Year 4.83E+01 2.45E-01 Tritium in Fish from Lake Robinson NOTE Concentrations of radionuclides used in this specific fish consumption pathway are determined by averaging the monthly concentrations detected in environmental location (REMP) SW-40. In 2015, no plant related gamma emitting radionuclides were detected. Tritium was detected each month, as expected. Since tritium is consistently detected in Lake Robinson REMP samples, tritium concentration in the fish is assumed to be in equilibrium with Lake Robinson.
Using the methodology and data described in NRC Regulatory Guide 1.109, Rev.1, October 1977, Equation A-1, Table E-5, and Table E-11, the following is a summary of average concentration consumed and resulting dose for 2015.
- 1. Avg. H-3 Concentration
- Units pCi/L mREM Year 2.60E+03 5.73E-03
- The dose factor for H-3 is the same for all organs and Total Body (with the exception of Bone, which is 0. OOE+OO).
NOTE:
This information was previously included in the H.B. Robinson Steam Electric Plant AREOR. ORR 02012901 was written to include the fish dose calculation methodology in the next ODCM revision, and report in the ARERR.
Page 2-4 Supplemental Information H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Overall Estimate of Error for Effluent Radioactivity Release Reported The estimated percentage of overall error for both Liquid and Gaseous effluent release data at H.B. Robinson Steam Electric Plant has been determined to be +/- 30.3%. This value was derived by taking the square root of the sum of the squares of the following discrete individual estimates of error:
- 1.
Flow Rate Determining Devices =
+/-20%
- 2.
Counting Statistical Error
=
+/-20%
- 3.
Calibration Error
=
+/-10%
- 4.
Calibration Source Error
=
+/-2.5%
- 5.
Sample Preparation Error
=
+/-3%
Page 2-5 Supplemental Information H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015-12/31/2015 Summary of Changes in Land Use Census Affecting Effluent Dose Calculations The 2015 Land Use Census was performed July 30, 2015, and the results were certified and made available for use on February 29, 2016. The following are changes to residences, gardens, and milk animals from the previous year.
Residences No changes to nearest residence in each sector.
Gardens The garden in the WSW sector at 0.86 miles was removed and no other garden was identified within the 5 mile radius.
Meat Animals No changes to nearest meat animal in each sector.
Milk Animals No changes to nearest milk animal in each sector.
Environmental Monitoring Locations No changes to environmental monitoring locations in each sector.
Page 2-6 Solid Radioactive Waste Disposal H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 ATTACHMENT 3 Solid Radioactive Waste Disposal This attachment includes a summary of the solid waste shipped off-site for burial and/or disposal, including:
Container volume Total Curie content (specify whether determined by measurement or estimate)
Principal Radionuclides Source/Type of waste Solidification agent or absorbent Type of shipping container Number of shipments Other relevant information as necessary Page 3-1 Solid Radioactive Waste Disposal H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Type of Number of Number of Waste Container Solidification Burial Total Waste Shipped Shipments Containers Class Type Agent Volume Activity (mJ)
(Curies)*
- 1.
Waste from Liquid Svstems
- a. Dewatered Secondary Resins
- b. Dewatered Primary Resins 2
2 A-S 8-120 Poly NIA 6.814 8.95 HIC
- c. Evaporator Concentrates
- d. Dewatered Mechanical Filters
- e. Dewatered Demineralizers
- f.
Solidified (cement) Acids, Oils, Sludge
- 2.
Orv Solid Waste
- a. Dry Active Waste 7
9 A-U 20' Sealand NIA 283 0.491 (compacted)
- b. Dry Active Waste (non-A-U 14-195 NIA 5.874 0.751 compacted)
Steel Liner
- c.
Dry Active Waste (brokered)
- d. Irradiated Components
- 3.
Total Solid Waste 10 12 295.688 10.192
- Measurement Page 3-2 Solid Radioactive Waste Disposal H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Type of Waste Shipped Radionuclide
% Abundance
- 1.
Waste from Liquid Systems
- a. Dewatered Secondary Resins
- b. Dewatered Primary Resins
- c. Evaporator Concentrates
- d. Dewatered Mechanical Filters
- e. Dewatered Demineralizers
- f.
Solidified (cement) Acids, Oils, Sludge
- 2.
Orv Solid Waste
- a. Dry Active Waste (compacted)
NIA Ni-63 Fe-55 Co-60 Co-58 C-14 Cs-137 Mn-54 Sb-125 Cs-134 Co-57 Ag-110m H-3 Ni-59 Sr-90 Nb-95 Ce-144 Sb-124 Sn-113 Tc-99 1-129 NIA NIA NIA NIA Ni-63 Fe-55 Co-60 Co-58 H-3 Sb-125 Nb-95 C-14 Zr-95 Mn-54 Ag-110m Ce-144 Tc-99 Cs-137 Co-57 Cr-51 Sn-113 Sr-90 1-129 Te-123m Fe-59 NIA 30.4 24.8 20.8 9.08 6.23 2.84 2.58 1.02 0.673 0.611 0.279 0.265 0.167 0.067 0.046 0.035 0.028 0.023 0.022 0.002 NIA NIA NIA NIA 36.0 32.7 25.2 2.58 0.975 0.568 0.547 0.415 0.302 0.263 0.105 0.101 0.052 0.047 0.032 0.027 0.024 0.010 0.007 0.005 0.004 Page 3-3 Solid Radioactive Waste Disposal H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015
- b. Dry Active Waste (non-compacted)
Ni-63 Co-60 Fe-55 Co-58 Nb-95 C-14 Zr-95 Mn-54 Ce-144 H-3 Cs-137 Sr-90 Tc-99 1-129
- c.
Dry Active Waste (brokered)
N/A
- d. Irradiated Components N/A 49.2 23.7 21.7 3.21 0.857 0.492 0.365 0.141 0.121 0.093 0.045 0.018 0.017 0.004 N/A N/A Page 3-4 Meteorological Data H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 ATTACHMENT 4 Meteorological Data This attachment includes a summary of meteorological joint frequency distributions of wind speed, wind direction, and atmospheric stability (hours of occurrence).
Page 4-1
Wind Stability Speed Class (mph)
N NNE 0.75-3.50 0
0 3.51-7.50 3
12 7.51-12.50 10 5
A 12.51-18.50 1
0 18.51-25.00 0
0 25+
0 0
0.75-3.50 1
5 3.51-7.50 29 42 7.51-12.50 11 7
B 12.51-18.50 0
0 18.51-25.00 0
0 25+
0 0
0.75-3.50 3
7 3.51-7.50 54 64 7.51-12.50 22 10 c
12.51-18.50 4
0 18.51-25.00 0
0 25+
0 0
0.75-3.50 47 97 3.51-7.50 268 434 7.51-12.50 153 219 D
12.51-18.50 10 22 18.51-25.00 0
0 25+
0 0
Meteorological Data H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015-12/31/2015 Hours of Occurrence Sector NE ENE E
3 7
2 5
1 1
2 1
16 23 10 33 39 27 18 34 30 1
1 0
0 0
7 20 29 45 0
0 0
0 0
0 1
4 6
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
4 7
12 12 10 5
1 7
3 46 18 15 20 22 17 15 20 36 3
0 0
0 2
3 8
9 24 0
0 0
0 0
0 0
2 5
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
13 11 18 16 7
8 4
7 5
37 20 10 22 14 22 10 18 35 0
0 0
0 2
6 8
12 21 0
0 0
0 0
0 0
0 4
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
115 98 110 79 79 56 51 46 50 189 125 69 31 53 174 183 186 126 8
1 0
0 0
27 96 68 55 0
0 0
0 0
0 1
6 3
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
WSW w
WNW NW NNW 0
0 0
0 0
36 18 12 5
1 25 11 12 7
3 0
0 0
2 3
0 0
0 0
0 0
0 0
0 0
5 2
0 1
0 26 12 7
12 11 21 0
4 11 8
2 0
1 0
0 0
0 0
0 0
0 0
0 0
0 7
4 3
0 3
19 13 15 18 11 7
1 5
5 9
2 0
1 1
1 0
0 0
0 0
0 0
0 0
0 45 37 29 21 23 57 34 36 48 113 19 9
13 9
59 1
1 2
3 18 0
0 1
0 0
0 0
0 0
0 Page 4-2
Wind Stability Speed Class (mph)
N NNE 0.75-3.50 64 48 3.51-7.50 66 7
7.51-12.50 3
0 E
12.51-18.50 0
0 18.51-25.00 0
0 25+
0 0
0.75-3.50 34 7
3.51-7.50 9
0 7.51-12.50 0
0 F
12.51-18.50 0
0 18.51-25.00 0
0 25+
0 0
0.75-3.50 44 9
3.51-7.50 1
0 7.51-12.50 0
0 G
12.51-18.50 0
0 18.51-25.00 0
0 25+
0 0
Meteorological Data H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 -12/31/2015 Hours of Occurrence Sector NE ENE E
SSW SW 26 23 19 19 30 117 130 126 104 2
3 1
3 4
70 86 97 85 0
0 0
0 0
1 12 13 8
0 0
0 0
0 0
0 1
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 7
4 2
4 7
48 59 49 32 0
0 0
0 0
5 13 8
7 0
0 0
0 0
0 0
0 1
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
1 0
1 10 17 29 28 14 0
0 0
0 0
0 2
1 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
WSW w WNW NW NNW 70 50 27 62 52 33 22 23 47 141 3
2 3
4 15 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
23 29 46 34 68 7
3 7
19 65 0
0 1
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 26 27 20 62 111 1
0 0
6 10 1
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 Page 4-3 Unplanned Offsite Releases H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015-12/31/2015 ATTACHMENT 5 Unplanned Offsite Releases This attachment includes a summary of the unplanned offsite releases of gaseous and liquid radioactive effluents.
Page 5-1 Unplanned Offsite Releases H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 H.B. Robinson Steam Electric Plant did not experience any unplanned offsite effluent releases in 2015.
Page 5-2 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 ATTACHMENT 6 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public (includes fuel cycle dose calculation results)
This attachment includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site for each calendar quarter for the calendar year of the report as well as the total dose for the calendar year.
This attachment also includes an assessment of radiation doses to the maximum exposed member of the public from all uranium fuel cycle sources within 8 km of the site for the calendar year of this report to show conformance with 40 CFR Part 190.
Methods for calculating the dose contribution from liquid and gaseous effluents are given in the Offsite Dose Calculation Manual (ODCM).
Page 6-1 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Gaseous Effluents Dose Summary Units Q!r..1 Qtr2 Qtr 3 A. Noble Gases
- 1. Maximum Gamma Air mRAD 8.60E-04 7.26E-02 1.62E-03 (a)
Limit mRAD 5.00E+OO 5.00E+OO 5.00E+OO (b) % of Limit 1.72E-02 1.45E+OO 3.25E-02
- 2. Maximum Beta Air mRAD 5.31E-04 2.56E-02 1.39E-03 (a)
Limit mRAD 1.00E+01 1.00E+01 1.00E+01 (b) % of Limit 5.31 E-03 2.56E-01 1.39E-02 Receptor Location 0.42 km SSE B. Iodine, H-3, & Particulates
- 1. Maximum Organ Dose mREM 1.29E-01 1.31E-01 1.32E-01 (a) Limit mREM 7.50E+OO 7.50E+OO 7.50E+OO (b) % of Limit 1.72E+OO 1.74E+OO 1.76E+OO Receptor Location 0.42 km SSE Critical Age CHILD Critical Organ BONE
~
Year 3.78E-03 7.88E-02 5.00E+OO 1.00E+01 7.56E-02 7.88E-01 7.57E-03 3.51E-02 1.00E+01 2.00E+01 7.57E-02 1.75E-01 1.32E-01 5.24E-01 7.50E+OO 1.50E+01 1.76E+OO 3.49E+OO Page 6-2 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Liquid Effluents Dose Summary Units Q1l1 Q1r.l
~
A Batch & Continuous Mode
- 1. Maximum Organ Dose mREM 1.70E-04 4.88E-04 4.29E-06 (a) Limit mREM 5.00E+OO 5.00E+OO 5.00E+OO (b) % of Limit 3.41E-03 9.75E-03 8.58E-05
- 2. Maximum Total Body Dose mREM 1.66E-04 1.64E-04 4.32E-06 (a)
Limit mREM 1.50E+OO 1.50E+OO 1.50E+OO (b) % of Limit 1.11 E-02 1.10E-02 2.88E-04 Critical Age ADULT Critical Organ GI-LL/
Q!!:-4 Year 5.38E-05 7.16E-04 5.00E+OO 1.00E+01 1.08E-03 7.16E-03 5.39E-05 3.89E-04 1.50E+OO 3.00E+OO 3.59E-03 1.30E-02 Page 6-3 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 40 CFR Part 190 Uranium Fuel Cycle Dose Calculation Results In accordance with the requirements of 40 CFR Part 190, the annual dose commitment to any member of the general public shall be calculated to assure that doses are limited to 25 rnillirerns to the total body or any organ with the exception of the thyroid which is limited to 75 rnillirerns. The fuel cycle dose assessment for H.B. Robinson Stearn Electric Plant includes liquid and gaseous effluent dose contributions from H.B. Robinson Stearn Electric Plant and direct and air-scatter dose from the onsite ISFSI. No other direct or air-scatter source or uranium fuel cycle facility contributes significantly to the maximum exposed individual. Included om the gaseous effluent dose below is the estimated dose contributed by Carbon-14 (Ref. Attachment 2, Supplemental Information, of this report for further information). Also included is dose from evaporation of H-3 in Lake Robinson and H-3 in fish from Lake Robinson.
The combined dose to a maximum exposed individual from effluent releases, combined with the additional dose pathways, is below 40 CFR Part 190 limits as shown by the following summary.
Note: The 40 CFR Parl 190 effluent dose analysis to the maximum exposed individual from liquid and gas re/eases does not include the dose from noble gases (i.e., total body and skin) due to the low significance compared to other dose pathways.
40 CFR Part 190 Effluent Dose Summary A. Gaseous Effluent Dose
- 1. Location
- 2. Critical Age
- 3. Critical Organ
- 4. Organ Dose (rnREM)
- 5. Total Body Dose (rnREM)
B. Liquid Effluent Dose
- 1. Location
- 2. Critical Age
- 3. Critical Organ
- 4. Organ Dose (rnREM)
- 5. Total Body Dose (rnREM)
C. Lake Robinson Evaporation H-3 Dose
- 1. Location
- 2. Critical Age
- 3. Critical Organ
- 4. Organ Dose (rnREM)
- 5. Total Body Dose (rnREM)
D. H-3 in Fish from Lake Robinson
- 1. Location
- 2. Critical Age
- 3. Critical Organ
- 4. Organ Dose (rnREM)
- 5. Total Body Dose (mREM) 0.42 km SSE CHILD BONE 5.24E-01 4.19E-01 6.76 km NE ADULT Gl-LLI 7.16E-04 3.89E-04 6.38 km N CHILD N/A 2.45E-01 2.45E-01 Lake ADULT N/A 5.73E-03 5.73E-03 Page 6-4 Assessment of Radiation Dose from Radioactive Effluents to Members of the Public H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 Dose contributions from Carbon-14 in gaseous effluents have been determined from ODCM 3.16, Methodology for Carbon-14 Dose. The maximum dose rate to the nearest real individual from the release of Carbon-14 in batch and continuous gaseous effluents is conservatively calculated to be less than 5.24E-01 mrem/yr based on 7.86 Curies released in 2015 (Ref. Attachment 2, Supplemental Information, of this report).
Dose contributions from evaporation of Tritium Lake Robinson have been determined from ODCM 2.5.3, Dose from Evaporation of Lake Robinson. The maximum dose rate to the nearest real individual from evaporation of Tritium in Lake Robinson is conservatively calculated to be less than 2.45E-01 mrem/yr based on 48.3 Curies released in 2015 (Ref. Attachment 2, Supplemental Information, of this report).
Dose contributions from Tritium in fish in Lake Robinson have been determined using NRC Regulatory Guide 1.109, Rev.1, October 1977, Equation A-1, and data from REMP location SW-40. This information was previously included in the H.B. Robinson Steam Electric Plant AREOR. DRR 02012901 was written to include the fish dose calculation methodology in the next ODCM revision, and report in the ARERR. The maximum dose rate to the nearest real individual from consuming the fish in Lake Robinson is conservatively calculated to be less than 5. 73E-03 mrem/yr based on an average concentration of 2.60E+03 pCi/L consumed in 2015 (Ref. Attachment 2, Supplemental Information, of this report).
Direct and air-scatter radiation dose contributions from the onsite ISFSI at H.B. Robinson Steam Electric Plant have been calculated and documented in the ISFSI Safety Analysis Report. The dose rate to the maximum exposed individual from the ISFSI is conservatively calculated to be less than 5 mrem/yr.
The below excerpt from the H.B. Robinson Steam Electric Plant ISFSI Safety Analysis Report is provided to document the conclusion that the H.B. Robinson Steam Electric Plant ISFSI contributes less than 6 mrem/year to the maximum exposed individual.
7.6.2 ANALYSIS OF MULTIPLE CONTRIBUTION The maximally exposed member of the public would receive approximately 1. 6 mrem per year from an ISFSI made up of a three-unit HSM (reference Figure 7.6.1). An ISFSI consisting of an eight-unit HSM would contribute approximately 4.3 mrem per year. This is a result of external radiation only; there are no gaseous, particulate, or liquid effluents associated with the nonnal operation of the ISFSI. It can be concluded that the actual exposure contribution from the ISFSI along with the total of all other uranium fuel cycle activities is within the regulatory limits set forth in 40CFR190.
Assessment of the actual dose from direct radiation is performed as part of the H.B. Robinson Steam Electric Plant REMP and reported in the AREOR. During 2015, the assessment of dose from direct radiation, performed as part of the REMP, demonstrated no measurable contribution above background attributable to H.B. Robinson Steam Electric Plant operations.
Total dose from liquid and gaseous effluents from H.B. Robinson Steam Electric Plant and the additional pathways mentioned above is conservatively estimated to be less than 6 mrem/yr for total body and organ. It is recognized summing dose for different organs and age groups is not entirely accurate. However, the sum of the organ and age specific doses will always be less than the sum of the maximums of each. Therefore, summing the maximum values of each provides the most conservative value to ensure compliance with 40 CFR 190. The dose from all pathways related to operation of H.B. Robinson Steam Electric Plant meets the 40 CFR Part 190 requirements of an annual dose commitment to any member of the general public of less than 25 mrem total body or any organ and 75 mrem to the thyroid.
Page 6-5 Information to Support the NEI Ground Water Protection Initiative H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 ATTACHMENT 7 Information to Support the NEI Ground Water Protection Initiative This attachment includes a summary of voluntary reports made in accordance with the NEI Ground Water Protection Initiative and a summary of ground water well sample data.
Page 7-1 Information to Support the NEI Ground Water Protection Initiative H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 H.B. Robinson Steam Electric Plant has implemented a Ground Water Protection program in accordance with NEI 07-
- 07. This initiative was developed to ensure timely and effective management of situations involving inadvertent releases of licensed material to ground water. As part of this program, H.B. Robinson Steam Electric Plant monitored 28 wells in 2015. 11 wells not sampled as part of the ODCM REMP are reported below. The remaining 17 wells are sampled in accordance with the ODCM REMP and reported in the AREOR.
Wells are sampled quarterly. Ground water samples are analyzed for tritium and gamma emitters. No gamma, other than naturally occurring radionuclides, were identified in well samples during 2015. There were no anomalous results identified in 2015.
Results from sampling during 2015 are shown in the table below.
No events meeting the criteria for voluntary notification per NEI 07-07, Industry Ground Water Protection Initiative, occurred at H.B. Robinson Steam Electric Plant in 2015. No special dose calculations were performed as part of the Ground Water Protection program.
Key to below table.
NS pCi/I
<MDA 20,000 pCi/I 1,000,000 pCi/I Not scheduled to be sampled, not sampled due to insufficient volume in well, or well inaccessible during outage.
picocuries per liter.
less than minimum detectable activity, typically 250 pCi/I.
the Environmental Protection Agency drinking water standard for tritium. This standard applies only to water used for drinking.
the 10 CFR Part 20, Appendix B, Table 2, Column 2, Effluent Concentration Limit for tritium.
Well Location I Description Tritium Concentration (pCill)
- of Name 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Samples MW-1R NPDESAsh
<MDA
<MDA
<MDA
<MDA 4
MW-2R NPDESAsh
<MDA
<MDA
<MDA
<MDA 4
MW-3R NPDESAsh 1.28E+03 1.27E+03 1.15E+03 1.12E+03 4
MW-4R NPDES Ash 2.61E+02
<MDA
<MDA
<MDA 4
MW-5 NPDESAsh 7.33E+02 4.80E+02 4.91E+02 5.83E+02 4
MW-6 NPDESAsh 1.11E+03 9.37E+02 8.72E+02 8.06E+02 4
MW-7 NPDESAsh 4.75E+02 4.17E+02 2.59E+02 2.37E+02 4
P-1 North of Discharge Canal 1.51E+03 6.77E+02 4.80E+02 1.13E+03 4
P-2 South of Discharge Canal
<MDA
<MDA
<MDA 2.20E+02 4
PSW-04 West of Plant Site
<MDA
<MDA
<MDA
<MDA 4
PSW-05 SW Plant, Background Well
<MDA
<MDA
<MDA 1.82E+02 4
Page 7-2 Inoperable Equipment H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 ATTACHMENT 8 Inoperable Equipment This attachment includes an explanation of inoperable instruments related to effluent monitoring in excess of allowed time defined by licensing bases and an explanation of permanent or temporary outside liquid storage tanks exceeding 10 Curies total activity (excluding tritium and dissolved or entrained noble gases).
Page 8-1 Inoperable Equipment H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015-12/31/2015 H.B. Robinson Steam Electric Plant did not experience inoperable equipment relevant to effluent monitoring in excess of ODCM limits during 2015.
H.B. Robinson Steam Electric Plant did not experience permanent or temporary outside liquid storage tanks not surrounded by liners, dikes, or walls, capable of holding the tank's contents and that does not have tank overflows and surrounding area drains connected to the Liquid Waste Disposal System exceeding 10 Curies total activity (excluding tritium and dissolved or entrained noble gases) during 2015.
Page 8-2 Summary of Changes to the Offsite Dose Calculation Manual H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 ATTACHMENT 9 Summary of Changes to the Offsite Dose Calculation Manual Example This attachment includes a summary of changes to the ODCM and Radiological Effluent Controls.
Page 9-1 Summary of Changes to the Offsite Dose Calculation Manual ODCM Revision 33 H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 -12/31/2015 The H.B. Robinson Steam Electric Plant ODCM did not warrant revision during the period 1/1/2015 - 12/31/2015.
Therefore, it was not revised in 2015. Revision 33, which was submitted along with the 2011 ARERR, continues to remain the most recent revision.
Page 9-2 0
Summary of Changes to the Process Control Program H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 -12/31/2015 ATTACHMENT 10 Summary of Changes to the Process Control Program This attachment includes a summary of changes to the PCP.
Page 10-1 0
Summary of Changes to the Process Control Program H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 The H.B. Robinson Steam Electric Plant PCP was not revised in 2015. The most recent revision is 6 and is provided on the following pages.
Page 10-2 0
Summary of Changes to the Process Control Program H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 PROGRESS ENERGY H. B. ROBINSON - UNIT 2 PROCESS CONTROL PROGRAM (PCP)
REVISIONS DOCKET NO, S0-261 EFFECTIVe DATE: 0 I- 0 7 - I 0 REVIEWED AND ACCEPTED BY PNSC: ~h4 DATE". 01-CJi-lO PNSC CHAIRMAN PCP RC\\lision 6 Pagel of 6 Page 10-3 0
Summary of Changes to the Process Control Program H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015-12/31/2015 LIST OF EFFECTIVE PAGES EFFECTIVE PAGES REVISION Cover Sheet LEP 3 through 6 6
6 6
SUMMARY
OF CHANGES Revised Section 2.0 to specify dewatering and solidification may be performed by qualified vendor or qualified Progress Energy personnel in accordance with a qualified PCP or a program approved by the NRC or burial site facility.
Revised Section 3.1.2 to include review of both vendor and RNP operating procedures, retention of both vendor and RNP completed records, and monitoring of both vendor and RNP operations for compliance with TRMS 3.22 requirements.
Revised Section 3.1.3 to include RC Supervisor (with accountability for radioactive waste processing) responsibility for advising the RC Superintendent on the adequacy of both vendor and RNP operating procedures.
Revised Section 3.2 to clarify that specified vendor requirements apply to vendors who supply both solidification and dewatering services to RNP.
PCP Revision 6 Page 2of6 Page 10-4
1.0 SCOPE 0 Summary of Changes to the Process Control Program H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 H.B. ROBINSON PROCESS CONTROL PROGRAM This program established the management systems and controls that the Robinson Nuclear Plant (RNP) uses to ensure safe and effective solidification and dewatering of various low-level radioactive waste liquids and slurries for offsite disposal.
2.0 OBJECTIVE It is the objective of this program that solidification and/or dewatering of various low-level radioactive waste liquids and slurries (including oily wastes) for offsite disposal will be performed by either qualified vendors or qualified Progress Energy personnel, in accordance with a qualified PCP or a program approved by the NRC or burial site facility. The quality of the solidified and/or dewatered product shall meet or exceed regulatory requirements and the disposal site criteria prior to release from the RNP site for shallow disposal.
3.0 MANAGEMENT PROGRAM 3.1 Responsibilities 3.1.1 The Plant General Manager is responsible for ensuring that waste is shipped in accordance with the appropriate state and federal regulations.
3.1.2 The Superintendent - Radiation Control (RC) or designee is responsible for:
PCP Revision 6
- a. Advising the Plant General Manager on the appropriate technical standards, regulations and requirements as related to solidification, dewatering and shipping.
- b. Ensuring changes to the vendor's Process Control Program (PCP),
vendor and RNP operating procedures, and proposed contractual agreements are reviewed and advising the Plant General Manager as to their adequacy.
- c. Retaining vendor - supplied documentation and completed RNP records for NRC inspection and review.
Page 3of6 Page 10-5 0
Summary of Changes to the Process Control Program H.B. Robinson Steam Electric Plant Unit 2 Period 1 /1 /2015 - 12/3112015 3.1 Responsibilities (continued)
PCP Revision 6
- d. Ensuring vendor and RNP operations are monitored for compliance with:
- 1.
Section 3.22 Technical Requirements Manual (TRMS). The Solid Radwaste System shall be used in accordance with a PCP to process wet radioactive waste to meet shipping and burial ground requirements.
- 2.
Section 3.22.A TRMS. With the provisions of the PCP not satisfied, immediately suspend shipments of defectively processed or defectively packaged solid radioactive waste from the site.
- 3.
Section 3.22.B TRMS. If any test specimen, as required by the PCP, fails to verify solidification, the solidification of the batch under test shall be immediately suspended until such time as additional test specimens can be obtained, alternative solidification parameters can be determined in accordance with Section 5.5.17 of the TRMS. Solidification of the batch may then be resumed using alternative solidification parameters as determined by the PCP.
- 4.
Section 3.22.1 TRMS. The PCP shall be used to verify the solidification of one representative test specimen from every tenth batch of wet radioactive waste.
Page 4of6 Page 10-6 0
Summary of Changes to the Process Control Program H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015-12/31/2015 3.1 Responsibilities (continued)
Note: The following step is only required to be met if the initial test specimen from a batch of waste fails to verify solidification and continues until at least three consecutive initial test specimens demonstrate solidification.
- 5.
Section 3.22.2 TRMS. Collect and test representative test specimens of every consecutive batch of the same type of wet radioactive waste to verify solidification in accordance with the PCP.
3.1.3 The RC Supervisor with accountability for radioactive waste processing is responsible for advising the Superintendent-RC on:
- a.
The appropriate technical standards, regulations and requirements as related to solidification, dewatering and shipping.
- b.
The adequacy of the vendor's PCP, vendor and RNP operating procedures, and proposed contractual agreements.
3.2 Specification of Vendors The qualified solidification and/or dewatering vendor will:
3.2.1 Provide a qualified PCP or a program approved by:
- a.
NRC
- b.
Disposal site licensee 3.2.2 The vendor will perform the tests described in the PCP.
3.2.3 The vendor will supply the Superintendent - RC with all documentation required to demonstrate compliance with dewatering and/or solidification requirements.
3.2.4 The Superintendent-RC will retain documentation required to demonstrate compliance with solidification requirements and standards.
PCP Revision 6 Page 5of6 Page 10-7 0
Summary of Changes to the Process Control Program H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015-12/31/2015 4.0 MANAGEMENT/CONTRACTOR INTERACTIONS 4.1 The vendor is accountable to the Superintendent - RC for the solidification and/or dewatering of liquid wastes.
4.2 The RC Supervisor with accountability for radioactive waste processing handles the shipping of solidified and dewatering wastes and maintains required documentation. The vendor and the RC Supervisor may communicate on the matters as necessary.
5.0 ATTACHMENTS 5.1 None Applicable PCP Revision 6 Page 6of6 Page 10-8 1
Summary of Major Modifications to the Radioactive Waste Treatment Systems H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 ATTACHMENT 11 Summary of Major Modifications to the Radioactive Waste Treatment Systems This attachment includes a description of major modifications to the radioactive waste treatment systems that are anticipated to affect effluent releases.
Page 11-1 1
Summary of Major Modifications to the Radioactive Waste Treatment Systems H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 No major modifications to liquid, gaseous, solid, or mobile radioactive waste treatment systems occurred at H.B.
Robinson Steam Electric Plant in 2015.
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Errata to a Previous Year's ARERR Example H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 ATTACHMENT 12 Errata to a Previous Year's ARERR This attachment includes any amended pages from a previous year's ARERR.
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Errata to a Previous Year's ARERR Example H.B. Robinson Steam Electric Plant Unit 2 Period 1/1/2015 - 12/31/2015 There are no changes to a previous year's ARERR.
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