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| issue date = 04/16/2018
| issue date = 04/16/2018
| title = Independent Spent Fuel Storage Installation (ISFSI) Annual Radioactive Effluent Release Report
| title = Independent Spent Fuel Storage Installation (ISFSI) Annual Radioactive Effluent Release Report
| author name = Lane N L
| author name = Lane N
| author affiliation = Virginia Electric & Power Co (VEPCO)
| author affiliation = Virginia Electric & Power Co (VEPCO)
| addressee name =  
| addressee name =  
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:*.J:* ; VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 16,2018,2018 United States Nuclear Regulatory Commission Attention:
{{#Wiki_filter:*.J:*
Document Control Desk Washington, D. C. 20555 Serial No. 18-173 NAPS/DPM Docket Nos. 50-338/339 72-16 72-56 License Nos. NPF-4/7 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 16,2018,2018 United States Nuclear Regulatory Commission                 Serial No. 18-173 Attention: Document Control Desk                             NAPS/DPM Washington, D. C. 20555                                     Docket Nos. 50-338/339 72-16 72-56 License Nos. NPF-4/7 SNM-2507 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION  
NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION {ISFSI)
{ISFSI) ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SNM-2507 Enclosed is the 2017 Annual Radioactive Effluent Release Report. This report is provided pursuant to North Anna Units 1 and 2 Technical Specification 5.6.3 [10 CFR 50.36a] and North Anna Independent Spent Fuel Storage Installation Technical Specification 5.5.2c [10 CFR 72.44(d)(3)].
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Enclosed is the 2017 Annual Radioactive Effluent Release Report. This report is provided pursuant to North Anna Units 1 and 2 Technical Specification 5.6.3 [10 CFR 50.36a] and North Anna Independent Spent Fuel Storage Installation Technical Specification 5.5.2c [10 CFR 72.44(d)(3)].
If you have any questions or require additional information, please contact Mr. Donald R. Taylor at (540) 894-2100.
If you have any questions or require additional information, please contact Mr. Donald R. Taylor at (540) 894-2100.
Very truly yours, 0t~ N. Larry Lane Site Vice President Enclosure Commitments made inJhis letter: None cc: U. S. Nuclear Regulatory Commission (w/o Enclosure)
Very truly yours, 0t~
Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 Director, Division of Spent Fuel Management (w/o Enclosure)
N. Larry Lane Site Vice President Enclosure Commitments made inJhis letter: None cc:     U. S. Nuclear Regulatory Commission (w/o Enclosure)
Office of Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D. C. 20555 NRC Senior Resident Inspector (w/o Enclosure)
Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 Director, Division of Spent Fuel Management (w/o Enclosure) 7:&#xa3;4<?
North Anna Power Station 7:&#xa3;4<? t,JMS5z(p
Office of Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission t,JMS5z(p Washington, D. C. 20555
&#xb5;((f<-* f\) jllt, 5 s ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NORTH ANNA POWER STATION (JANUARY 01, 2017 TO DECEMBER 31, 2017) REVIEWED BY: Bradley T. Plea ants, Jr. Supervisor Radiological Analysis and Instrumentation  
                                                                                        &#xb5;((f<-*
------------
NRC Senior Resident Inspector (w/o Enclosure)                              f\) jllt, 5 s North Anna Power Station
Barb a r a J. Thompson Superintendent Health Physics Technical Services APPROVED BY: _ __.,_ w~ ___ .t._{2.,._,,.._'
 
_____ _ ~e R. Simmons Manager Radiological Protection and Chemistry
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NORTH ANNA POWER STATION (JANUARY 01, 2017 TO DECEMBER 31, 2017)
,, FORWARD This report is submitted in accordance with North Anna Unit 1 and 2 Technical Specification 5.6.3 and North Anna Independent Spent Fuel Storage Installation (ISFSI) Technical Specification 5.5.2.c and IOCFR72.44(d)(3).
Bradley T. Plea ants, Jr.
Section No. 2 3 4 Attachment 1 Attachment 2 Attachment 3 Attachment 4 Attachment 5 Attachment 6 Attachment 7 Attachment 8 Attachment 9 Miscellaneous ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE NORTH ANNA POWER STATION JANUARY 01, 2017 TO DECEMBER 31, 2017 INDEX Subject EXECUTIVE  
Supervisor Radiological Analysis and Instrumentation REVIEWED BY:- - - - - - - - - - - -
Barba r a J. Thompson Superintendent Health Physics Technical Services w~___
APPROVED BY: _ __.,_     .t._{2.,._,,.._'
                ~ e R. Simmons Manager Radiological Protection and Chemistry
 
FORWARD This report is submitted in accordance with North Anna Unit 1 and 2 Technical Specification 5.6.3 and North Anna Independent Spent Fuel Storage Installation (ISFSI) Technical Specification 5.5.2.c and IOCFR72.44(d)(3).
 
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE NORTH ANNA POWER STATION JANUARY 01, 2017 TO DECEMBER 31, 2017 INDEX Section No.                    Subject EXECUTIVE  


==SUMMARY==
==SUMMARY==
  .................................. . PURPOSE AND SCOPE .................................... . DISCUSSION  
  .................................. .           4 2            PURPOSE AND SCOPE .................................... .           5 3            DISCUSSION ................................................. . 5-6 4            SUPPLEMENTAL INFORMATION ...................... .                 6-7      Effluent Release Data ............................................. . 8      Annual and Quarterly Doses ..................................... . 9      Revisions to Offsite Dose Calculation Manual (ODCM) ....................................... .       10      Major Changes to Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems ................................................. . 11      Inoperability of Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation ....................................... . 12      Unplanned Releases ........................ *.................... . 13      Lower Limits of Detection (LLD) for Effluent Sample Analysis .......................... .       14-15      Results of Ground Water Protection Initiative Sample Analysis .................................... .     16-24      Carbon-14 Calculations ....................................... .     25 Miscellaneous    Annual Effluent Release Report Log ....................... .         26
................................................. . SUPPLEMENTAL INFORMATION  
 
...................... . Effluent Release Data ............................................. . Annual and Quarterly Doses ..................................... . Revisions to Offsite Dose Calculation Manual (ODCM) ....................................... . Major Changes to Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems ................................................. . Inoperability of Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation  
1.0c EXECUTIVE  
....................................... . Unplanned Releases ........................  
* .................... . Lower Limits of Detection (LLD) for Effluent Sample Analysis .......................... . Results of Ground Water Protection Initiative Sample Analysis .................................... . Carbon-14 Calculations  
....................................... . Annual Effluent Release Report Log ....................... . 4 5 5-6 6-7 8 9 10 11 12 13 14-15 16-24 25 26 1.0c EXECUTIVE  


==SUMMARY==
==SUMMARY==
The Annual Radioactive Effluent Release Report describes the radioactive effluent control program conducted at the North Anna Power Station and the Independent Spent Fuel Storage Installation (ISFSI) during the 2017 calendar year. This document summarizes the quantities ofradioactive liquid and gaseous effluents and solid waste released from the North Anna Power Station and ISFSI in accordance with Regulatory Guide 1.21 during the period of January 1 through December 31, 2017, and includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents.
The Annual Radioactive Effluent Release Report describes the radioactive effluent control program conducted at the North Anna Power Station and the Independent Spent Fuel Storage Installation (ISFSI) during the 2017 calendar year. This document summarizes the quantities ofradioactive liquid and gaseous effluents and solid waste released from the North Anna Power Station and ISFSI in accordance with Regulatory Guide 1.21 during the period of January 1 through December 31, 2017, and includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents.
There were no releases from the ISFSI during 2017. There were no unplanned releases, meeting the reporting criteria of Section 6.7.2.a.3 of the Offsite Dose Calculation Manual during this reporting period. Also there were no spills or leaks meeting the voluntary communication criteria of the NEI Ground Water Protection Initiative.
There were no releases from the ISFSI during 2017.
There were no unplanned releases, meeting the reporting criteria of Section 6.7.2.a.3 of the Offsite Dose Calculation Manual during this reporting period. Also there were no spills or leaks meeting the voluntary communication criteria of the NEI Ground Water Protection Initiative. This will be discussed in Attachment 6.                                                *'
10 CFR 50, Appendix I dose calculations were performed on the 2017 effluent release data in accordance with the Offsite Dose Calculation Manual. The results of these pathway dose calculations indicate the following:
: a.     
... i
... i
* ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/17 -12/17) 4th Quarter 2017 Sample Date Sample H-3<1> Gamma -Emitting 1.131<1> Sr-89/90<1> Fe-ss<1> Ni-63<1> Alpha Pu-241<1> Media Particulates<
* ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/17 - 12/17) 4th Quarter 2017 Sample       Gamma -Emitting 1.131<1> Sr-89/90<1> Fe-ss<1> Ni-63<1> Alpha Sample            Date          H-3<1>                                                                  Pu-241<1>
1> TRU 11> PZ-3 10131117 WATER 2660 N/A NIA NIA NIA NIA NIA NIA PZ-3 11130117 WATER 2170 NIA NIA NIA NIA NIA NIA NIA PZ-3 12129117 WATER 1620 NIA NIA NIA NIA NIA NIA NIA GWP-3 12128117 WATER <1080 NIA NIA NIA NIA NIA NIA NIA GWP-4 12129117 WATER <918 NIA NIA NIA NIA NIA NIA NIA GWP-5A 12129117 WATER <918 NIA NIA NIA NIA NIA NIA NIA GWP-6 10131117 WATER 1540 NIA NIA NIA NIA NIA NIA NIA GWP-6 11130117 WATER 1080 NIA NIA NIA NIA NIA NIA NIA GWP-6 12129117 WATER 1150 NIA NIA NIA NIA NIA NIA NIA GWP-7 12129117 WATER 1490 NIA NIA NIA NIA NIA NIA NIA GWP-8 12129117 WATER <878 NIA NIA NIA NIA .NIA* NIA NIA GWP-9 12129117 WATER <882 NIA NIA NIA NIA NIA NIA NIA GWP-13 12129117 WATER <958 NIA NIA NIA NIA NIA NIA NIA GWP-14 01111118 WATER <769 NIA NIA NIA NIA NIA NIA NIA GWP-16 01111118 WATER <769 NIA NIA NIA NIA NIA NIA NIA GWP-17 01116118 WATER <896 NIA NIA NIA NIA NIA NIA NIA GWP-18 10130117 WATER 2190 NIA NIA NIA NIA NIA NIA NIA GWP-18 11130117 WATER 3638 NIA NIA NIA NIA NIA NIA NIA* GWP-18 12129117 WATER* 1070 NIA NIA NIA NIA NIA NIA NIA GWP-19 12129117 WATER <920 NIA NIA NIA NIA NIA NIA NIA GWP-20 12129117 WATER <915 NIA NIA NIA NIA NIA NIA NIA GWP-21 12129117 WATER 1200 NIA NIA NIA NIA NIA NIA NIA GWP-22 12129117 WATER 1600 NIA NIA NIA NIA NIA NIA NIA BTW-1 01103118 WATER <708 NIA NIA NIA NIA NIA NIA NIA BTW-2 01103118 WATER <743 NIA NIA NIA NIA NIA NIA NIA BTW-4 01104/18 WATER <695 NIA NIA NIA NIA NIA NIA NIA TTW-2 01103118 WATER <752 NIA NIA NIA NIA NIA NIA NIA TTW-3 01104118 WATER <745 NIA NIA NIA NIA NIA NIA NIA TTW-5 01104118 WATER <727 NIA NIA NIA NIA NIA NIA NIA Sub Surface Drains' 11114117 WATER <1661 NIA NIA NIA NIA NIA NIA NIA U-1 Intake Storm Drains 11127117 WATER <1640 NIA NIA NIA NIA NIA NIA NIA U-2 Intake Storm Drains 11127117 WATER <1640 NIA NIA NIA NIA NIA NIA NIA Disch Canal Storm Drains 11127117 WATER <1640 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump East 10125117 WATER <1520 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump East 01103118 WATER <1846 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 10125117 WATER <1526 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 01103118 WATER <1825 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 10125117 WATER <1518 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 01103118 WATER <1803 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 10125117 WATER <1516 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 01103118 WATER <1838 NIA NIA NIA NIA NIA NIA NIA 22 U-1 ABIFB GWMS 10125117 WATER <1529 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 01103118 WATER <1789 NIA* NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 10125117 WATER <1530 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 01103118 WATER <1824 NIA NIA NIA NIA NIA NIA NIA PZ-1 12129117 WATER Insufficient volume to sample PZ-2 12129117 WATER Insufficient volume to sample TTW-1 Well abandoned in place, pending decommissioning TTW-4 Well abandoned in place, pending decommissioning (1) pCi/L (2) Vendor Analysis 23 ATTACHMENT 9 CARBON-14 CALCULATIONS (01/17 -12/17) Carbon-I 4, C-14, is a naturally occurring isotope of carbon produced by cosmic ray interactions in the atmosphere.
Media         Particulates<1>                                       TRU 11 >
Nuclear weapons testing in the 1950s and 1960s significantly increased the amount ofC-14 in the atmosphere.
PZ-3         10131117 WATER 2660           N/A         NIA       NIA       NIA     NIA     NIA       NIA PZ-3         11130117 WATER 2170           NIA         NIA       NIA       NIA     NIA     NIA       NIA PZ-3         12129117 WATER 1620         NIA         NIA       NIA       NIA     NIA     NIA       NIA GWP-3           12128117 WATER <1080         NIA         NIA       NIA       NIA     NIA     NIA       NIA GWP-4           12129117 WATER <918           NIA         NIA       NIA       NIA     NIA     NIA       NIA GWP-5A           12129117 WATER <918           NIA         NIA       NIA       NIA     NIA     NIA       NIA GWP-6           10131117 WATER 1540         NIA         NIA       NIA       NIA     NIA     NIA       NIA GWP-6           11130117 WATER 1080         NIA         NIA       NIA       NIA     NIA     NIA       NIA GWP-6           12129117 WATER 1150         NIA         NIA       NIA       NIA     NIA     NIA       NIA GWP-7           12129117 WATER 1490         NIA         NIA       NIA       NIA     NIA     NIA       NIA GWP-8           12129117 WATER <878           NIA         NIA       NIA       NIA     .NIA*   NIA       NIA GWP-9           12129117 WATER <882           NIA         NIA       NIA       NIA     NIA     NIA       NIA GWP-13         12129117 WATER <958         NIA         NIA       NIA       NIA     NIA     NIA       NIA GWP-14         01111118 WATER <769         NIA         NIA       NIA       NIA     NIA     NIA       NIA GWP-16         01111118 WATER <769         NIA         NIA       NIA       NIA     NIA     NIA       NIA GWP-17         01116118 WATER <896           NIA         NIA       NIA       NIA     NIA     NIA       NIA GWP-18         10130117 WATER 2190           NIA         NIA       NIA       NIA     NIA     NIA       NIA GWP-18         11130117 WATER 3638           NIA         NIA       NIA       NIA     NIA     NIA       NIA*
Due to the long half-life ofC-14, 5730 years, a significant portion of the C-14 from this testing is still present in the environment.
GWP-18         12129117 WATER* 1070         NIA         NIA       NIA       NIA     NIA     NIA       NIA GWP-19         12129117 WATER <920           NIA         NIA       NIA       NIA     NIA     NIA       NIA GWP-20         12129117 WATER <915         NIA         NIA       NIA       NIA     NIA     NIA       NIA GWP-21         12129117 WATER 1200         NIA         NIA       NIA       NIA     NIA     NIA       NIA GWP-22         12129117 WATER 1600         NIA         NIA       NIA       NIA     NIA     NIA       NIA BTW-1         01103118 WATER <708         NIA         NIA       NIA       NIA     NIA     NIA       NIA BTW-2         01103118 WATER <743           NIA         NIA       NIA       NIA     NIA     NIA       NIA BTW-4         01104/18 WATER <695           NIA         NIA       NIA       NIA     NIA     NIA       NIA TTW-2         01103118 WATER <752           NIA         NIA       NIA       NIA     NIA     NIA       NIA TTW-3         01104118 WATER <745         NIA         NIA       NIA       NIA     NIA     NIA       NIA TTW-5         01104118 WATER <727         NIA         NIA       NIA       NIA     NIA     NIA       NIA Sub Surface Drains'   11114117 WATER <1661         NIA         NIA       NIA       NIA     NIA     NIA       NIA U-1 Intake Storm Drains 11127117 WATER <1640         NIA         NIA       NIA       NIA     NIA     NIA       NIA U-2 Intake Storm Drains 11127117 WATER <1640         NIA         NIA       NIA       NIA     NIA     NIA       NIA Disch Canal Storm Drains 11127117 WATER <1640         NIA         NIA       NIA       NIA     NIA     NIA       NIA U-1 Mat Sump East     10125117 WATER <1520         NIA         NIA       NIA       NIA     NIA     NIA       NIA U-1 Mat Sump East     01103118 WATER <1846         NIA         NIA       NIA       NIA     NIA     NIA       NIA U-1 Mat Sump South     10125117 WATER <1526         NIA         NIA       NIA       NIA     NIA     NIA       NIA U-1 Mat Sump South     01103118 WATER <1825         NIA         NIA       NIA       NIA     NIA     NIA       NIA U-2 Mat Sump Inside   10125117 WATER <1518         NIA         NIA       NIA       NIA     NIA     NIA       NIA U-2 Mat Sump Inside   01103118 WATER <1803         NIA         NIA       NIA       NIA     NIA     NIA       NIA U-2 Mat Sump Outside   10125117 WATER <1516         NIA         NIA       NIA       NIA     NIA     NIA       NIA U-2 Mat Sump Outside   01103118 WATER <1838         NIA         NIA       NIA       NIA     NIA     NIA       NIA 22
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 has recommended that U.S. nuclear power plants evaluate whether C-14 is a "principal radionuclide", and ifso, report the amount of C-14 released.
 
At North Anna, improvements over the years in fuel performance have resulted in a decrease in the amount and distribution of radionuclides released to the environment in gaseous effluents.
U-1 ABIFB GWMS 10125117 WATER     <1529         NIA           NIA         NIA     NIA NIA NIA NIA U-1 ABIFB GWMS 01103118 WATER     <1789         NIA*           NIA         NIA     NIA NIA NIA NIA U-2 ABIFB GWMS 10125117 WATER     <1530         NIA           NIA         NIA     NIA NIA NIA NIA U-2 ABIFB GWMS 01103118 WATER     <1824         NIA           NIA         NIA     NIA NIA NIA NIA PZ-1     12129117 WATER                               Insufficient volume to sample PZ-2     12129117 WATER                               Insufficient volume to sample TTW-1                             Well abandoned in place, pending decommissioning TTW-4                             Well abandoned in place, pending decommissioning (1) pCi/L     (2) Vendor Analysis 23
As a result, C-14 has become a "principal radionuclide" for the gaseous effluent pathway at North Anna, as defined in Regulatory Guide 1.21, Revision 2. Because the dose contribution of C-14 to liquid radioactive waste is a small fraction of the dose compared to other nuclides, evaluation of C-14 in liquid effluents is not required by Regulatory Guide 1.21, Revision 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.
 
North Anna utilized methodology in EPRl Report, Estimation ofC-14 in Nuclear Power Gaseous Effluents.
ATTACHMENT 9 CARBON-14 CALCULATIONS (01/17 - 12/17)
Based on this document, at full capacity, North Anna would generate and release about 32.8 Ci of C-14 per year. Since the units did not operate at full power for 100% of the year, this value was corrected for the capacity factor of each unit yielding an estimated 24.1 Ci ofC-14 produced and released.
Carbon- I 4, C-14, 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 ofC-14 in the atmosphere. Due to the long half-life ofC-14, 5730 years, a significant portion of the C-14 from this testing is still present in the environment. C-14 is also produced in commercial nuclear reactors, but the amounts produced are much less than those produced naturally or from weapons testing.
North Anna assumed that the fractional release of gaseous C-14 in any quarter and pathway could be approximated by the fraction of noble gasses released via that pathway in that quarter. Most C-14 species initially produced in a Pressurized Water Reactor are organic, e.g., methane. C-14 releases in PWRs occur primarily as a mix of organic carbon and carbon dioxide released from the waste gas system. 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, 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 of70% to 95% organic. North Anna used a value of70% organic and 30% CO 2 in its calculations.
In Regulatory Guide 1.21, Revision 2, "Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste", the NRC has recommended that U.S. nuclear power plants evaluate whether C-14 is a "principal radionuclide", and ifso, report the amount of C-14 released. At North Anna, improvements over the years in fuel performance have resulted in a decrease in the amount and distribution of radionuclides released to the environment in gaseous effluents. As a result, C-14 has become a "principal radionuclide" for the gaseous effluent pathway at North Anna, as defined in Regulatory Guide 1.21, Revision 2.             Because the dose contribution of C-14 to liquid radioactive waste is a small fraction of the dose compared to other nuclides, evaluation of C-14 in liquid effluents is not required by Regulatory Guide 1.21, Revision 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. North Anna utilized methodology in EPRl Report, Estimation ofC-14 in Nuclear Power Gaseous Effluents. Based on this document, at full capacity, North Anna would generate and release about 32.8 Ci of C-14 per year. Since the units did not operate at full power for 100% of the year, this value was corrected for the capacity factor of each unit yielding an estimated 24.1 Ci ofC-14 produced and released. North Anna assumed that the fractional release of gaseous C-14 in any quarter and pathway could be approximated by the fraction of noble gasses released via that pathway in that quarter.
Most C-14 species initially produced in a Pressurized Water Reactor are organic, e.g., methane. C-14 releases in PWRs occur primarily as a mix of organic carbon and carbon dioxide released from the waste gas system. 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, 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 of70%
to 95% organic. North Anna used a value of70% organic and 30% CO 2 in its calculations.
Public dose estimates from airborne C-14 were performed using dose models in NUREG-0133 and Regulatory Guide 1.109. The estimated C-14 dose impact on the maximum organ dose from airborne effluents released at North Anna is estimated to be 6.61E-02 mrem from the inhalation pathway, or 4.4 lE-03% TS of the 1500 mrem/yr dose rate limit and 6. l 9E-O 1 mrem from the ingestion pathway or 2.06E+00%
Public dose estimates from airborne C-14 were performed using dose models in NUREG-0133 and Regulatory Guide 1.109. The estimated C-14 dose impact on the maximum organ dose from airborne effluents released at North Anna is estimated to be 6.61E-02 mrem from the inhalation pathway, or 4.4 lE-03% TS of the 1500 mrem/yr dose rate limit and 6. l 9E-O 1 mrem from the ingestion pathway or 2.06E+00%
TS of the 10CFR50, Appendix I, ALARA design objective of 15 mrem/yrperunit.
TS of the 10CFR50, Appendix I, ALARA design objective of 15 mrem/yrperunit. In both cases the critical organ was determined to be the child's bone.
In both cases the critical organ was determined to be the child's bone. 24 Miscellaneous There were two entries on the Annual Effluent Release Report Log for 2017. The first entry was made to document that the Unit 2 High Capacity Blowdown Effluent radiation monitor was out of service for> 30 consecutive
24
 
Miscellaneous There were two entries on the Annual Effluent Release Report Log for 2017. The first entry was made to document that the Unit 2 High Capacity Blowdown Effluent radiation monitor was out of service for> 30 consecutive days. The second entry was made to document that a particulate patch was not installed in the Ventilation Vent A MGPI normal range iodine and particulate sampler for the sampling period beginning on 06/25/17 and ending on 07/01/17.
25
 
TABLE 1A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR (01/17 - 12/17)
Page 1

Latest revision as of 07:36, 23 February 2020

Independent Spent Fuel Storage Installation (ISFSI) Annual Radioactive Effluent Release Report
ML18116A455
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Site: North Anna  Dominion icon.png
Issue date: 04/16/2018
From: Lane N
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References
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 16,2018,2018 United States Nuclear Regulatory Commission Serial No.18-173 Attention: Document Control Desk NAPS/DPM Washington, D. C. 20555 Docket Nos. 50-338/339 72-16 72-56 License Nos. NPF-4/7 SNM-2507 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION {ISFSI)

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Enclosed is the 2017 Annual Radioactive Effluent Release Report. This report is provided pursuant to North Anna Units 1 and 2 Technical Specification 5.6.3 [10 CFR 50.36a] and North Anna Independent Spent Fuel Storage Installation Technical Specification 5.5.2c [10 CFR 72.44(d)(3)].

If you have any questions or require additional information, please contact Mr. Donald R. Taylor at (540) 894-2100.

Very truly yours, 0t~

N. Larry Lane Site Vice President Enclosure Commitments made inJhis letter: None cc: U. S. Nuclear Regulatory Commission (w/o Enclosure)

Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 Director, Division of Spent Fuel Management (w/o Enclosure) 7:£4<?

Office of Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission t,JMS5z(p Washington, D. C. 20555

µ((f<-*

NRC Senior Resident Inspector (w/o Enclosure) f\) jllt, 5 s North Anna Power Station

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NORTH ANNA POWER STATION (JANUARY 01, 2017 TO DECEMBER 31, 2017)

Bradley T. Plea ants, Jr.

Supervisor Radiological Analysis and Instrumentation REVIEWED BY:- - - - - - - - - - - -

Barba r a J. Thompson Superintendent Health Physics Technical Services w~___

APPROVED BY: _ __.,_ .t._{2.,._,,.._'

~ e R. Simmons Manager Radiological Protection and Chemistry

FORWARD This report is submitted in accordance with North Anna Unit 1 and 2 Technical Specification 5.6.3 and North Anna Independent Spent Fuel Storage Installation (ISFSI) Technical Specification 5.5.2.c and IOCFR72.44(d)(3).

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE NORTH ANNA POWER STATION JANUARY 01, 2017 TO DECEMBER 31, 2017 INDEX Section No. Subject EXECUTIVE

SUMMARY

.................................. . 4 2 PURPOSE AND SCOPE .................................... . 5 3 DISCUSSION ................................................. . 5-6 4 SUPPLEMENTAL INFORMATION ...................... . 6-7 Effluent Release Data ............................................. . 8 Annual and Quarterly Doses ..................................... . 9 Revisions to Offsite Dose Calculation Manual (ODCM) ....................................... . 10 Major Changes to Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems ................................................. . 11 Inoperability of Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation ....................................... . 12 Unplanned Releases ........................ *.................... . 13 Lower Limits of Detection (LLD) for Effluent Sample Analysis .......................... . 14-15 Results of Ground Water Protection Initiative Sample Analysis .................................... . 16-24 Carbon-14 Calculations ....................................... . 25 Miscellaneous Annual Effluent Release Report Log ....................... . 26

1.0c EXECUTIVE

SUMMARY

The Annual Radioactive Effluent Release Report describes the radioactive effluent control program conducted at the North Anna Power Station and the Independent Spent Fuel Storage Installation (ISFSI) during the 2017 calendar year. This document summarizes the quantities ofradioactive liquid and gaseous effluents and solid waste released from the North Anna Power Station and ISFSI in accordance with Regulatory Guide 1.21 during the period of January 1 through December 31, 2017, and includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents.

There were no releases from the ISFSI during 2017.

There were no unplanned releases, meeting the reporting criteria of Section 6.7.2.a.3 of the Offsite Dose Calculation Manual during this reporting period. Also there were no spills or leaks meeting the voluntary communication criteria of the NEI Ground Water Protection Initiative. This will be discussed in Attachment 6. *'

10 CFR 50, Appendix I dose calculations were performed on the 2017 effluent release data in accordance with the Offsite Dose Calculation Manual. The results of these pathway dose calculations indicate the following:

a. The total body dose due to liquid effluents was 6.29E-01 mrem, which is 10.48% of the dose limit, and the critical organ dose due to liquid effluents was 6.3 lE-01 mrem, which is 3.16% of the dose limit.
b. The air dose due to noble gases was 3.57E-05 mrad gamma, which is l.78E-04% of the annual gamma dose limit, and 3.51E-05 mrad beta, which is 8.78E-05% of the annual beta dose limit.
c. The critical organ dose for 1-131, 1-133, H-3, and particulates with half-lives greater than 8 days including C-14 was 6.99 E-01 mrem, which is 2.33% of the annual dose limit. The bases ofC-14 calculations are described in Attachment 9.
d. The critical organ dose for 1-131, 1-133, H-3, and particulates with half-lives greater than 8 days not including C-14 was l.37E-02 mrem, which is 4.57E-02% of the annual dose limit.

There were no major changes to either the radioactive liquid waste treatment system, or to the gaseous, and solid waste treatment systems during this reporting period.

There were no revisions to the Offsite Dose Calculation Manual during this reporting period.

Based on the levels of radioactivity observed during this reporting period and the dose calculations performed, the operations of the North Anna Nuclear Power Station Units 1 and 2 and ISFSI have resulted in negligible dose consequences to the maximum exposed member of the public in unrestricted areas.

4

2.0t PURPOSE AND SCOPE The Radioactive Effluent Release Report includes, in Attachment 1, a summary of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants",

a Revision 1, June 1974, with data summarized on quarterly basis for Table 1 and 2 and on an annual basis on Table 3. The report submitted before May 1st of each year includes an assessment ofradiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site during the previous calendar year. The report also includes a list of unplanned releases during the reporting period in Attachment 6.

As required by Technical Specification, any changes to the Offsite Dose Calculation Manual (ODCM) for the time period covered by this report are included in Attachment 3.

Major changes to radioactive liquid, gaseous and solid waste treatment systems are reported in Attachment 4, as required by the ODCM, Section 6.7.2.a.4. Information to support the reason(s) for the change(s) and a summary of the 10 CFR 50.59 evaluation are included.

As required by the ODCM, Sections 6.2.2.b.2 and 6.3.2.b.3, a list and explanation for the inoperability ofradioactive liquid and/or gaseous effluent monitoring instrumentation is provided in Attachment 5 of this report.

3.0 DISCUSSION The basis for the calculation of percent of Technical Specification for the critical organ in Table lA of Attachment 1 is the ODCM, section 6.3.1, which requires that the dose rate for iodine-131 and iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days shall be less than or equal to 1500 mrem/yr to the critical organ at or beyond the site boundary. The critical organ is the child's bone ifC-14 is included and child's thyroid ifC-14 is not included both via the inhalation pathway.

The basis for the calculation of percent of Technical Specification for the total body and skin in Table lA of Attachment 1 is the ODCM, section 6.3.1, which requires that the dose rate for noble gases to areas at or beyond the site boundary shall be less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin.

The basis for the calculat.ion of the percent of Technical Specification in Table 2A in Attachment 1 is the ODCM, section 6.2.l, which states that the concentrations of radioactive material released in liquid effluents to umestricted areas shall be limited to 10 times the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-4 uCi/ml.

Percent of Technical Specification calculations are based on the total gaseous or liquid effluents released for that respective quarter.

5

'- The annual and quarterly doses, as reported in Attachment 2, were calculated according to the methodology presented in the ODCM. The beta and gamma air doses due to noble gases released from the site were calculated at site boundary. The maximum exposed member of the public from the releases ofairbome iodine-131 and iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days, including carbon-14 is defined as a child, exposed through the vegetation pathway, with the critical organ being the bone. If carbon-14 is excluded from these calculations, the maximum exposed member of the public from the releases of airborne iodine-131 and iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days is defined as a child, exposed through the vegetation pathway, with the critical organ being the thyroid gland. The maximum exposed member of the public for calculation of total body dose from radioactive materials in liquid effluents released to unrestricted areas is defined as a child, and also as a child for the calculation of critical organ dose, which was determined to be liver. The age group is exposed via the drinking water and fish ingestion pathways.

As shown in Attachment 6, there were no unplanned releases meeting the requirements of6.7.2.a.3 of the ODCM.

The typical Lower Limit of Detection (LLD) capabilities of the radioactive effluent analysis instrumentation are presented in Attachment 7. These LLD values are based upon conservative conditions (i.e., minimum sample volume and maximum delay time prior to analysis). Actual LLD values may be lower. If a radioisotope was not detected when effluent samples were analyzed, then the activity of that radioisotope was reported as Not Detectable (N/D) on Attachment 1 of this report. If an analysis for an isotope was not performed, then the activity was reported as Not Applicable (N/A).

4.0 SUPPLEMENTAL INFORMATION As required by the ODCM, section 6.6.2, evaluation of the Land Use Census is performed to identify if new location(s) need be added for the radiological environmental monitoring program pursuant to the ODCM. There were no new sampling locations added. There were seven (7) changes made to the land use census in 2017. The nearest garden location in the N sector changed from-1.56 miles to 2.75 miles. The nearest garden location in the NNE sector changed from 1.22 miles to 3.21 miles. The nearest garden location in the E sector changed from 2.04 miles to 1.75 miles. The nearest garden location in the SE sector changed from 1.54 miles to 1.4 miles. The nearest garden location in the SSW sector changed from 1.33 miles to 2.37 miles. The nearest garden location in the NW sector changed from 1.28 miles to 1.09 miles. Finally, the nearest garden location in the NNW sector changed from 2.54 miles to 1.33 miles.

Section 6.6.1.b.4 of the ODCM requires identification of the cause(s) for the unavailability of milk or leafy vegetation samples, and the identification of new locations for obtaining replacement samples. All milk samples were collected as required.

Vegetation samples were not collected from stations l 4B, 15, 16, 23 and 26 from January through March and November through December due to seasonal unavailability. All other vegetation samples were obtained.

Attachment 8 contains the results of samples associated with ground water protection sampling undertaken at North Anna to voluntarily comply with the Nuclear Energy Institute, NEI, Ground Water Protection Initiative. In addition to the well, river, and surface water samples included as part of the Radiological Environmental Monitoring Program, North Anna obtained subsurface 6

'* water samples from various locations on the site.

Attachment 9 contains an explanation of the bases for the carbon-14 calculations performed to assess doses due to carbon-14.

Doses and %TS for gaseous releases are displayed with C-14 included and without for comparison of the values.

7

ATTACHMENT 1 EFFLUENT RELEASE DATA (01/17 - 12/17)

This attachment includes a summary of the quantities ofradioactive liquid and gaseous effluents and solid waste, as outlined in Regulatory Guide 1.21, Appendix B, exceptthat in accordance with Step 6. 7.2.a. l of the ODCM liquid and gaseous data is summarized on a quarterly basis and solid waste is summarized on an annual basis.

8

ATTACHMENT 2 ANNUAL AND QUARTERLY DOSES (01/17 - 12/17)

An assessment ofradiation doses to the maximum exposed member of the public du.e to radioactive liquid and gaseous effluents released from the site for each calendar quarter for the calendar year of this report, along with an annual total of each effluent pathway will be made as required by ODCM Section 6.7.2.

1st 2nd 3rd 4th Annual Quarter Quarter Quarter Quarter Total Total Body Dose (mrem) 6.736E-2 1.661E-1 3.354E-1 5.955E-2 6.284E-1 Critical Organ Dose (mrem) 6.988E-2 1.663E-1 3.354E-1 5.962E-2 6.312E-1 1st 2nd 3rd 4th Annual Quarter Quarter Quarter Quarter Total Noble Gas Gamma Dose (mrad) 5.279E-6 6.795E-6 9.318E-6 1.426E-5 3.565E-5 Noble Gas Beta Dose (mrad) 1.270E-5 2.775E-6 l.434E-5 5.285E-6 3.512E-5 Critical Organ (Child bone)

Dose for 1-131, 1-133, H-3, Particulates with TYz > 8 days (including C-14) (mrem) 3.588E-1 7.044E-2 1.552E-l 1.143E-1 6.987E-1 Critical Organ (Child thyroid)

Dose for 1-131, 1-133, H-3, Particulates with TYz > 8 days (excluding C-14) (mrem) 7.363E-3 1.700E-3 2.039E-3 2.579E-3 l.368E-2 9

ATTACHMENT 3 REVISIONS TO OFFSITE DOSE CALCULATION MANUAL (ODCM)

(01/17 - 12/17)

As required by Technical Specification 5.5.1.c, revisions to the ODCM, effective for the time period covered by this report, are summarized in this attachment.

There were no revisions to the ODCM during this reporting period.

10

J C ATTACHMENT 4 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS (01/17 - 12/17)

As required by the ODCM, Section 6. 7.2.a.4, major changes to radioactive liquid, gaseous and solid waste treatment systems for the time period covered by this report are synopsized in this attachment. Supporting information as to the reason(s) for the change(s) and a summary of the 10 CFR 50.59 evaluations are included, as applicable.

There were no major changes to the radioactive liquid, gaseous, and solid waste treatment systems for 2017.

11

1 "

ATTACHMENT 5 INOPERABILITY OF RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION (01/17 - 12/17)

As required by the ODCM, Sections 6.2.2.b.2 and 6.3.2.b.3, a list and explanation for extended inoperability ofradioactive liquid and/or gaseous effluent monitoring instrumentation is provided in this attachment.

The Unit 2 High Capacity Blowdown effluent radiation monitor, 2-SS-RM-225, was out of service for greater than 30 days during the calendar year 2017. The radiation monitor was declared out of service on 02/10/2017 during calibration. The monitor was adjusted during calibration however still experienced moderate output signal spiking below the alarm setpoint. The monitor remained out of service pending evaluation of the output signal spiking issue. Evaluations by the manufacturer and Station Engineering determined that the signal spiking issue did not compromise the functionality or operability of the radiation monitor. The radiation monitor was declared fully operational and returned to service on 03/30/2017.

A system update for 2-SS-RM-225 is planned for June 2018 and will be implemented with DCP NA-17-00173. This will improve the overall equipment health for the radiation monitoring system.

12

) .

ATTACHMENT 6 UNPLANNED RELEASES (01/17 - 12/17)

As required by the ODCM, Section 6.7.2.a.3, a list of unplanned releases, from the site to unrestricted areas, of radioactive material in gaseous and liquid effluents occurring during the reporting period, is made in this attachment.

There were no unplanned releases during calendar year 2017 meeting the criteria of Section 6.7.2.a.3 of the ODCM from the site to unrestricted areas. Also, there were no spills or leaks that required voluntary communication under the criteria of the NEI Ground Water Protection Initiative, NEI 07-07. Elevated results indicated in Attachment 8 are from the on-going investigation/ mitigation for the voluntary communication made in 2010. The hydrological modeling indicates the horizontal groundwater movement around well

  1. 6 is< 1 inch per day.

13

ATTACHMENT 7 LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS (01/17 - 12/17)

Gaseous Effluents:

Required L.L.D. Typical L.L.D.

Radioisotope µCi/mL µCi/mL Krypton - 87 1.00E-4 2.50E-8 7.50E-8 Krypton - 88 1.00E-4 4.00E-8 2.50E-7 Xenon -133* 1.00E-4 2.00E-8 1.00E-7 Xenon-133m 1.00E-4 1.00E-7 4.00E-7 Xenon -135 1.00E-4 1.00E-8 5.00E-8 Xenon -135m 1.00E-4 5.00E-8 2.00E-7 Xenon -138 1.00E-4 9.00E-8 4.00E-7 Iodine -131 1.00E-12 3.00E-14 1.00E-13 Iodine - 133 1.00E-10 1.00E-14 7.00E-13 Manganese - 54 1.00E-11 2.00E-14 6.00E-14 Cobalt- 58 1.00E-11 2.00E-14 6.00E-14 Iron - 59 1.00E~ll 6.00E-14 1.00E-13 Cobalt- 60 1.00E-11 3.00E-14 1.00E-13 Zinc- 65 1.00E-11 6.00E-14 2.00E-13 Strontium - 89 1.00E-11 3.00E-14 8.00E-12 Strontium - 90 1.00E-11 3.00E-15 9.00E-12 Molybdenum - 99 1.00E-11 2.00E-14 1.00E-13 Cesium - 134 1.00E-11 2.00E-14 8.00E-14 Cesium -137 1.00E-11 3.00E-14 8.00E-14 Cerium -141 1.00E-11 3.00E-14 1.00E-13 Cerium -144 1.00E-11 1.50E-13 4.00E-13 Gross Alpha l.OOE-11 7.00E-15 2.00E-14 Tritium 1.00E-6 4.00E-09 9.00E-09 14

~

ATTACHMENT 7 LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS (01/17 - 12/17)

Liguid Effluents:

Required L.L.D. Typical L.L.D.

Radioisotope µCi/mL µCi/mL Krypton-87 1.00E-5 3.00E-8 1.00E-7 Krypton-88 1.00E-5 5.00E-8 5.00E-7 Xenon-133 1.00E-5 3.00E-8 1.00E-7 Xenon-133m 1.00E-5 9.00E-8 3.00E-7 Xenon-135 1.00E-5 1.00E-8 5.00E-8 Xenon-135m 1.00E-5 3.00E-8 2.00E-7 Xenon-138 1.00E-5 1.00E-7 1.00E-6 Iodine- 131 1.00E-6 1.00E-8 5.00E-8 Manganese - 54 5.00E-7 1.00E-8 5.00E-8 Iron - 55 1.00E-6 3.00E-7 8.00E-7 Cobalt-58 5.00E-7 1.50E-8 6.00E-8 Iron - 59 5.00E-7 3.00E-8 7.00E-8 Cobalt-60 5.00E-7 1.00E-8 5.50E-8 Zinc- 65 5.00E-7 3.00E-8 6.00E-8 Strontium - 89 5.00E-8 1.00E-8 4.00E-8 Strontium - 90 5.00E-8 5.00E-9 9.00E-9 Molybdenum - 99 5.00E-7 2.00E-8 6.00E-8 Cesium-134 5.00E-7 l.50E-8 5.00E-8 Cesium-137 5.00E-7 1.SOE-8 6.00E-8 Cerium-141 5.00E-7 3.00E-8 9.00E-8 Cerium-144 5.00E-7 1.00E-7 . 5.00E-7 Gross Alpha 1.00E-7 2.00E-8 7.00E-8 Tritium 1.00E-5 2.00E-6 5.00E-6 15

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/17 - 12/17)

The Ground Water Protection Program was established to improve North Anna's management of and response to instances where the inadvertent release of radioactive substances may result in low but detectible levels of plant-related materials in subsurface soils and water.

It complies with the requirements ofNEI 07-07, INDUSTRY GROUND WATER PROTECTION INITIATIVE - FINAL GUIDANCE DOCUMENT. The industry initiative is intended to improve public trust and confidence in the nuclear industry through sampling and analysis of ground water and timely and effective communication with stakeholders, including the public and local, state, and federal officials.

Samples are obtained from monitoring wells installed both inside and outside the restricted area on a quarterly basis and analyzed onsite.

Annually, during the second quarter, these samples are analyzed by an Independent Lab. Samples are also obtained from sumps and yard drains on a quarterly basis and analyzed onsite. Samples may be obtained more frequently than normal, if required and may be analyzed on-site or by an Independent Lab. The required Lower Limits of Detection, LLDs, and reporting limits for the ground water detection program are those associated with the radiological environmental program as listed in Attachments 11 and 12 to VPAP-2103N.

On the following pages is a summary of the samples and results of the ground water protection program taken for calendar year 2017. All liquid results are reported in pCi/L, while soil results for tritium are reported in pCi/g of soil, wet. An "N/A" indicates a sample analysis was not performed for that sample. An "N/D" indicates an analysis was performed but the result was less than the Minimum Detectable Activity, MDA, and the required LLD. If a result is greater than the MDA, but less than the LLD the result is listed. Some of these results may be false positives, due to the analysis software or interferences from naturally occurring radioactivity. In these cases, instead of the value, an explanatory footnote is provided.

Ground water well GWP-15 was decommissioned during calendar year 2017 due to construction activities required for plant operations. It will be replaced by well GWP-15R at a later date. Therefore, no data is available for well GWP-15 in the following data tables after the second quarter of 2017.

16

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/17 - 12/17) 1st Quarter 2017 Sample Gamma -Emitting Alpha Sample Date H-3<11 1-131<11 Sr-89/90< 11 Fe-ss<1J Ni-63<11 Pu-241< 11 Media Particulates<1J TRU<11 PZ-3 01118117 WATER 2488 NIA NIA NIA NIA NIA NIA NIA PZ-3 02123117 WATER 3793 NIA NIA NIA NIA NIA NIA NIA PZ-3 03122117 WATER 1290 NIA NIA NIA NIA NIA NIA NIA GWP-3 03121117 WATER <817 NIA NIA NIA NIA NIA NIA NIA GWP-4 03121117 WATER <817 NIA NIA NIA NIA NIA NIA NIA GWP-5A 03121117 WATER <817 NIA NIA NIA NIA NIA NIA NIA GWP-6 01118117 WATER <882 NIA NIA NIA NIA NIA NIA NIA GWP-6 02123117 WATER <871 NIA NIA NIA NIA NIA NIA NIA GWP-6 03123117 WATER 1720 NIA NIA NIA NIA NIA NIA NIA GWP-7 03129117 WATER <901 NIA NIA NIA NIA NIA NIA NIA GWP-8 03129117 WATER <901 NIA NIA NIA NIA NIA NIA NIA GWP-9 03129117 WATER <901 . NIA NIA NIA NIA NIA NIA NIA GWP-13 03129117 WATER <901 NIA NIA NIA NIA NIA NIA NIA GWP-14 03129117 <901 NIA NIA NIA NIA NIA WATER NIA NIA GWP-15 03129117 WATER <901 NIA NIA NIA NIA NIA NIA NIA GWP-16 03129117 WATER <893 NIA NIA NIA NIA NIA NIA NIA GWP-17 03129117 WATER <893 NIA NIA NIA NIA NIA NIA NIA GWP-18 01118117 WATER 1678 NIA NIA NIA NIA NIA NIA NIA GWP18 02123117 WATER 3811 NIA NIA NIA NIA NIA NIA NIA GWP18 03123117 WATER 3850 NIA NIA NIA NIA NIA NIA NIA GWP-19 03121117 WATER <817 NIA NIA NIA NIA NIA NIA NIA GWP-20 03127117 WATER <820 NIA NIA NIA NIA NIA NIA NIA GWP-21 03129117 WATER <901 NIA NIA NIA NIA NIA NIA NIA.

GWP-22 03129117 WATER <901 NIA NIA NIA NIA NIA NIA NIA BTW-1 03130117 WATER <888 NIA NIA NIA NIA NIA NIA NIA BTW-2 03130117 WATER <893 NIA NIA NIA NIA NIA NIA NIA BTW-4 03130117 WATER <890 NIA NIA NIA NIA NIA NIA NIA TTW-2 03130117 WATER <895 NIA NIA NIA NIA NIA NIA NIA TTW-3 03130117 WATER <897 NIA NIA NIA NIA NIA NIA NIA TTW-5 03130117 WATER <890 NIA NIA NIA NIA NIA NIA NIA Sub Surface Drains 02121117 WATER <1727 NIA NIA NIA NIA NIA NIA NIA U-1 Intake Storm Drains 02108117 WATER <1600 NIA NIA NIA NIA NIA NIA NIA U-2 Intake Storm Drains 02108117 WATER <1600 NIA NIA NIA NIA NIA NIA NIA Disch Canal Storm Drains 02108117 WATER <1590 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump East 02123117 WATER <1578 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 02123117 WATER <1557 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 02123117 WATER <1553 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 02123117 WATER <1546 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 02123117 WATER <1545 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 02123117 WATER <1550 NIA NIA NIA NIA NIA NIA NIA.

PZ-1 03129117 WATER Insufficient Volume to Sample PZ-2 03129117 WATER Insufficient Volume to Sample TTW-1 Well abandoned in place, pending decommissioning.

TTW-4 Well abandoned in place, pending decommissioning 17

t (1) pCi/L ATTACHMENT* 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/17 - 12/17) 2"d Quarter 2017 Sample H-3<1> Gamma -Emitting Alpha

! Sample Date 1.131<11 Sr-89/90<1> Fe-ss<1> Ni-63<1> Pu-241<1>

Media Particulates<1> TRU<1>

PZ-3 04120117 WATER 2519 NIA NIA NIA NIA NIA NIA NIA PZ-3 05118117 WATER 3130 NIA NIA NIA NIA NIA NIA NIA PZ-3 06114117 WATER 3670 NIA NIA NIA NIA NIA N/A NIA PZ-3 (2) 06114117 WATER 2280 NIA NIA NIA NIA NIA N/A NIA GWP-3 06114117 WATER 2030 NIA NIA NIA NIA NIA NIA NIA GWP-3 (2) 06114117 WATER <855 NIA NIA NIA NIA NIA NIA N/A GWP-4 06114117 WATER 2260 NIA N/A NIA NIA NIA NIA NIA GWP-4 (2) 06114117 WATER <870 NIA N/A NIA NIA NIA NIA N/A GWP-5A 06114117 WATER <853 NIA NIA NIA NIA NIA NIA NIA GWP-5A(2) 06114117 WATER <853 NIA NIA NIA NIA NIA NIA N/A I GWP-6 04126/17 WATER 1059. NIA NIA NIA NIA NIA NIA NIA I GWP-6 05118117 WATER 1150 NIA NIA N/A N/A NIA NIA N/A GWP-6 06114117 WATER 2800 NIA N/A NIA NIA NIA NIA NIA

.j GWP-6 (2) 06114117 WATER 1300 NIA NIA NIA NIA NIA NIA N/A GWP-7 06115117 WATER 1330 NIA NIA NIA NIA NIA NIA NIA GWP-7 (2) 06115117 WATER <845 NIA NIA NIA NIA NIA NIA NIA GWP-8 06114117 WATER 1650 N/A NIA NIA NIA NIA NIA NIA

! GWP-8 (2) 06114117 WATER <859 NIA NIA NIA NIA NIA NIA NIA I

GWP-9 06115117 WATER <867 N/A NIA NIA NIA NIA NIA N/A GWP-9 (2) 06115117 WATER <853 NIA NIA NIA NIA N/A N/A NIA GWP-13 06114117 WATER <878 NIA NIA NIA NIA NIA NIA NIA I

GWP-13 (2) 06114117 WATER <850 NIA NIA NIA NIA N/A NIA NIA

GWP-14 06115117 WATER <865 NIA N/A NIA NIA NIA NIA NIA GWP-14 (2) 06115117 WATER <851 NIA NIA NIA NIA NIA NIA NIA

' GWP-15 06114117 WATER <846 NIA NIA NIA NIA NIA NIA N/A GWP-15 (2) 06114117 WATER <848 NIA NIA NIA NIA NIA NIA NIA GWP-16 06115117 WATER <859 NIA NIA NIA NIA NIA NIA NIA GWP-16 (2) 06115117 WATER <861 NIA NIA NIA NIA NIA NIA NIA GWP-17 06114117 WATER <869 NIA NIA NIA NIA NIA NIA NIA i GWP-17 (2) 06114117 WATER <850 NIA NIA NIA NIA NIA NIA NIA GWP-18 04127117 WATER 2980 NIA NIA NIA NIA NIA NIA NIA i GWP-18 05118117 WATER 3550 NIA NIA NIA NIA NIA NIA NIA

GWP-18 06115117 WATER 3280 NIA NIA NIA NIA NIA NIA NIA GWP-18 (2) 06115117 WATER 2330 NIA NIA NIA NIA NIA NIA NIA GWP-19 06115117 WATER 1960 NIA N/A NIA NIA NIA NIA NIA GWP-19 (2) 06115117 WATER <863 NIA NIA NIA NIA NIA NIA NIA GWP-20 06115117 WATER <881 NIA NIA NIA N/A NIA NIA NIA GWP-20 (2) 06115IJ7 WATER <852 NIA NIA N/A N/A NIA NIA NIA GWP-21 06115117 WATER <871 NIA NIA NIA NIA NIA NIA NIA GWP-21 (2) 06115117 WATER <852 NIA NIA NIA NIA N/A NIA NIA

' GWP-22 06115117 WATER <879 NIA NIA N/A NIA NIA NIA NIA GWP-22 (2) 06115117 WATER <843 NIA NIA NIA NIA NIA NIA NIA l BTW-1 06/26117 WATER <879 NIA NIA NIA NIA NIA NIA NIA BTW-1 (2) 06126117 WATER <841 NIA NIA NIA NIA NIA NIA NIA 18

I BTW-2 06126117 WATER <869 NIA NIA NIA NIA NIA NIA NIA BTW-2 (2) 06126117 WATER <845 NIA NIA NIA NIA NIA NIA NIA BTW-4 06128117 WATER <884 NIA NIA NIA NIA NIA NIA NIA BTW-4 (2) 06128117 WATER <835 NIA NIA NIA NIA NIA NIA NIA TTW-2 06128117 WATER <869 NIA NIA NIA NIA NIA NIA NIA TTW-2 (2) 06128117 WATER <832 NIA NIA NIA NIA NIA NIA NIA TTW-3 06127117 WATER <881 NIA NIA NIA NIA NIA NIA NIA TTW-3 (2) 06127117 WATER <861 NIA NIA NIA NIA NIA NIA NIA TTW-5 06128117 WATER <899 NIA NIA NIA NIA NIA NIA NIA TTW-5 (2) 06128117 WATER <844 NIA NIA NIA NIA NIA NIA NIA Sub Surface Drains 05111117 WATER <1550 NIA NIA NIA NIA NIA NIA NIA U-1 Intake Storm Drains 05116117 WATER <1531 NIA NIA NIA NIA NIA NIA NIA U-2 Intake Storm Drains 05116117 WATER <1531 NIA NIA NIA NIA NIA NIA NIA Disch Canal Storm Drains 05116117 WATER <1531 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump East 06114117 WATER <1772 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 06114117 WATER <1798 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 06114117 WATER <1796 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 06114117 WATER <1818 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 06114117 WATER <1795 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 06114117 WATER <1799 NIA NIA NIA NIA NIA NIA NIA PZ-1 06126117 WATER Insufficient Volume to Sample PZ-2 06126117 WATER Insufficient Volume to Sample TTW-1. Well abandoned in place, pending decommissioning TTW-4 Well abandoned in place, pending decommissioning (1) pCi/L (2) Vendor Analysis 19

)_ ,*

ATTACHMENT 8 RES ULTS* OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/17 - 12/17) 3rd Quarter 2017 Sample Gamma -Emitting Sr- Alpha Sample Date H-311 > 1-131 11 > Fe-55 111 Ni-63111 Pu-2411 11 Media Particulates 111 89/90 111 TRU 111 PZ-3 07120117 WATER 3640 NIA NIA NIA NIA NIA NIA NIA PZ-3 08128117 WATER 3330 NIA NIA NIA NIA N/A N/A N/A PZ-3 09/20/17 WATER 3050 N/A NIA NIA NIA NIA N/A NIA GWP-3 09120117 WATER 977 N/A N/A N/A NIA NIA N/A NIA GWP-3 10106117 WATER 1220 N/A NIA NIA NIA NIA NIA NIA GWP-4 09120117 WATER 1520 NIA NIA NIA NIA NIA N/A N/A GWP-4 10106117 WATER 1150 NIA NIA NIA NIA NIA N/A NIA GWP-5A 09122117 WATER <801 NIA N/A NIA NIA NIA N/A NIA GWP-6 07/20117 WATER 2610 NIA NIA NIA NIA NIA NIA N/A GWP-6 08128117 WATER 1830 NIA NIA NIA NIA NIA NIA N/A GWP-6 09122117 WATER 1810 NIA NIA NIA NIA NIA NIA NIA GWP-7 09122117 WATER 873 NIA NIA NIA NIA NIA NIA NIA GWP-7 10106117 WATER <877 NIA NIA NIA NIA NIA NIA NIA GWP-8 09122117 WATER <803 NIA NIA NIA NIA N/A NIA NIA GWP-9 09120117 WATER <842 NIA NIA NIA NIA NIA NIA NIA GWP-13 09120117 WATER <966 NIA NIA NIA N/A NIA NIA NIA GWP-14 09130117 WATER <880 NIA NIA NIA NIA NIA NIA NIA GWP-16 09130117 WATER <874 NIA NIA NIA NIA NIA NIA NIA GWP-17 09130117 WATER <876 NIA NIA NIA NIA NIA NIA NIA GWP-18 07120117 WATER 2900 NIA N/A NIA NIA NIA NIA NIA GWP-18 08128117 WATER <899 NIA NIA NIA NIA N/A N/A N/A GWP-18 09130117 WATER 3120 NIA NIA NIA NIA NIA NIA NIA GWP-19 09120117 WATER <881 NIA NIA NIA NIA NIA N/A NIA GWP-20 09122117 WATER <793 NIA NIA NIA NIA NIA NIA NIA GWP-21 09126117 WATER <940 NIA NIA NIA NIA NIA NIA NIA GWP-22 09126117 WATER <948 NIA NIA NIA NIA NIA NIA NIA BTW-1 09130117 WATER <912 NIA NIA NIA NIA NIA NIA N/A BTW-2 09130117 WATER <904 NIA NIA NIA NIA NIA NIA NIA BTW-4 09130117 WATER <1039 NIA NIA NIA NIA NIA NIA NIA TTW-2 09/30117 WATER <908 NIA NIA NIA NIA NIA NIA NIA TTW-3 09130117 WATER <912 NIA NIA NIA NIA NIA NIA NIA TTW-5 09/30117 WATER <910 NIA NIA N/A NIA NIA NIA NIA Sub Surface Drains 08/14117 WATER <1594 N/A NIA N/A NIA N/A NIA NIA U-1 Intake Storm Drains 08117117 WATER <1718 NIA NIA NIA NIA NIA NIA NIA U-2 Intake Storm Drains 08117117 WATER <1746 N/A NIA NIA NIA NIA NIA NIA Disch Canal Storm Drains 08117117 WATER <1693 N/A NIA NIA NIA NIA NIA NIA U-1 Mat Sump East 08131117 WATER <1827 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump East 09120117 WATER <1798 NIA N/A NIA N/A NIA NIA NIA U-1 Mat Sump South 08131117 WATER <1798 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 09120117 WATER <1820 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 08131117 WATER <1773 NIA NIA NIA NIA N/A N/A NIA 20

~. 09120117 Ll-2 Mat Sump Inside WATER <1798 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 08131117 WATER <1754 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 09120117 WATER <1792 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 08131117 WATER <1766 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 09120117 WATER <1803 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 08131117 WATER <1756 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 09120117 WATER <1779 NIA NIA NIA NIA NIA NIA NIA PZ-1 09120117 WATER Insufficient volume to sample PZ-2 09120117 WATER Insufficient volume to sample TTW-1 Well abandoned in place, pending decommissioning TTW-4 Well abandoned in place, pending decommissioning (1) pCi/L (2) Vendor Analysis 21

... i

  • ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/17 - 12/17) 4th Quarter 2017 Sample Gamma -Emitting 1.131<1> Sr-89/90<1> Fe-ss<1> Ni-63<1> Alpha Sample Date H-3<1> Pu-241<1>

Media Particulates<1> TRU 11 >

PZ-3 10131117 WATER 2660 N/A NIA NIA NIA NIA NIA NIA PZ-3 11130117 WATER 2170 NIA NIA NIA NIA NIA NIA NIA PZ-3 12129117 WATER 1620 NIA NIA NIA NIA NIA NIA NIA GWP-3 12128117 WATER <1080 NIA NIA NIA NIA NIA NIA NIA GWP-4 12129117 WATER <918 NIA NIA NIA NIA NIA NIA NIA GWP-5A 12129117 WATER <918 NIA NIA NIA NIA NIA NIA NIA GWP-6 10131117 WATER 1540 NIA NIA NIA NIA NIA NIA NIA GWP-6 11130117 WATER 1080 NIA NIA NIA NIA NIA NIA NIA GWP-6 12129117 WATER 1150 NIA NIA NIA NIA NIA NIA NIA GWP-7 12129117 WATER 1490 NIA NIA NIA NIA NIA NIA NIA GWP-8 12129117 WATER <878 NIA NIA NIA NIA .NIA* NIA NIA GWP-9 12129117 WATER <882 NIA NIA NIA NIA NIA NIA NIA GWP-13 12129117 WATER <958 NIA NIA NIA NIA NIA NIA NIA GWP-14 01111118 WATER <769 NIA NIA NIA NIA NIA NIA NIA GWP-16 01111118 WATER <769 NIA NIA NIA NIA NIA NIA NIA GWP-17 01116118 WATER <896 NIA NIA NIA NIA NIA NIA NIA GWP-18 10130117 WATER 2190 NIA NIA NIA NIA NIA NIA NIA GWP-18 11130117 WATER 3638 NIA NIA NIA NIA NIA NIA NIA*

GWP-18 12129117 WATER* 1070 NIA NIA NIA NIA NIA NIA NIA GWP-19 12129117 WATER <920 NIA NIA NIA NIA NIA NIA NIA GWP-20 12129117 WATER <915 NIA NIA NIA NIA NIA NIA NIA GWP-21 12129117 WATER 1200 NIA NIA NIA NIA NIA NIA NIA GWP-22 12129117 WATER 1600 NIA NIA NIA NIA NIA NIA NIA BTW-1 01103118 WATER <708 NIA NIA NIA NIA NIA NIA NIA BTW-2 01103118 WATER <743 NIA NIA NIA NIA NIA NIA NIA BTW-4 01104/18 WATER <695 NIA NIA NIA NIA NIA NIA NIA TTW-2 01103118 WATER <752 NIA NIA NIA NIA NIA NIA NIA TTW-3 01104118 WATER <745 NIA NIA NIA NIA NIA NIA NIA TTW-5 01104118 WATER <727 NIA NIA NIA NIA NIA NIA NIA Sub Surface Drains' 11114117 WATER <1661 NIA NIA NIA NIA NIA NIA NIA U-1 Intake Storm Drains 11127117 WATER <1640 NIA NIA NIA NIA NIA NIA NIA U-2 Intake Storm Drains 11127117 WATER <1640 NIA NIA NIA NIA NIA NIA NIA Disch Canal Storm Drains 11127117 WATER <1640 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump East 10125117 WATER <1520 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump East 01103118 WATER <1846 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 10125117 WATER <1526 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 01103118 WATER <1825 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 10125117 WATER <1518 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 01103118 WATER <1803 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 10125117 WATER <1516 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 01103118 WATER <1838 NIA NIA NIA NIA NIA NIA NIA 22

U-1 ABIFB GWMS 10125117 WATER <1529 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 01103118 WATER <1789 NIA* NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 10125117 WATER <1530 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 01103118 WATER <1824 NIA NIA NIA NIA NIA NIA NIA PZ-1 12129117 WATER Insufficient volume to sample PZ-2 12129117 WATER Insufficient volume to sample TTW-1 Well abandoned in place, pending decommissioning TTW-4 Well abandoned in place, pending decommissioning (1) pCi/L (2) Vendor Analysis 23

ATTACHMENT 9 CARBON-14 CALCULATIONS (01/17 - 12/17)

Carbon- I 4, C-14, 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 ofC-14 in the atmosphere. Due to the long half-life ofC-14, 5730 years, a significant portion of the C-14 from this testing is still present in the environment. 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 has recommended that U.S. nuclear power plants evaluate whether C-14 is a "principal radionuclide", and ifso, report the amount of C-14 released. At North Anna, improvements over the years in fuel performance have resulted in a decrease in the amount and distribution of radionuclides released to the environment in gaseous effluents. As a result, C-14 has become a "principal radionuclide" for the gaseous effluent pathway at North Anna, as defined in Regulatory Guide 1.21, Revision 2. Because the dose contribution of C-14 to liquid radioactive waste is a small fraction of the dose compared to other nuclides, evaluation of C-14 in liquid effluents is not required by Regulatory Guide 1.21, Revision 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. North Anna utilized methodology in EPRl Report, Estimation ofC-14 in Nuclear Power Gaseous Effluents. Based on this document, at full capacity, North Anna would generate and release about 32.8 Ci of C-14 per year. Since the units did not operate at full power for 100% of the year, this value was corrected for the capacity factor of each unit yielding an estimated 24.1 Ci ofC-14 produced and released. North Anna assumed that the fractional release of gaseous C-14 in any quarter and pathway could be approximated by the fraction of noble gasses released via that pathway in that quarter.

Most C-14 species initially produced in a Pressurized Water Reactor are organic, e.g., methane. C-14 releases in PWRs occur primarily as a mix of organic carbon and carbon dioxide released from the waste gas system. 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, 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 of70%

to 95% organic. North Anna used a value of70% organic and 30% CO 2 in its calculations.

Public dose estimates from airborne C-14 were performed using dose models in NUREG-0133 and Regulatory Guide 1.109. The estimated C-14 dose impact on the maximum organ dose from airborne effluents released at North Anna is estimated to be 6.61E-02 mrem from the inhalation pathway, or 4.4 lE-03% TS of the 1500 mrem/yr dose rate limit and 6. l 9E-O 1 mrem from the ingestion pathway or 2.06E+00%

TS of the 10CFR50, Appendix I, ALARA design objective of 15 mrem/yrperunit. In both cases the critical organ was determined to be the child's bone.

24

Miscellaneous There were two entries on the Annual Effluent Release Report Log for 2017. The first entry was made to document that the Unit 2 High Capacity Blowdown Effluent radiation monitor was out of service for> 30 consecutive days. The second entry was made to document that a particulate patch was not installed in the Ventilation Vent A MGPI normal range iodine and particulate sampler for the sampling period beginning on 06/25/17 and ending on 07/01/17.

25

TABLE 1A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR (01/17 - 12/17)

Page 1 of 2 1 ST 2ND ESTIMATED TOTAL UNITS QUARTER QUARTER PERCENT ERROR (%)

A. Fission and Activiation Gases:

1. Total Release Curies 5.65E-02 2.88E-02 1.80E+1
2. Average Release Rate For Period µCi/sec 7.27E-03 3.66E-03
8. Iodines:
1. Total lodine-131 Release Curies O.OOE+OO O.OOE+OO 2.80E+1
2. Average Release Rate For Period µCi/sec O.OOE+OO O.OOE+OO C. Particulate (T112 > 8 days):
1. Total Particulate (T112 > 8 days) Release Curies O.OOE+OO O.OOE+OO 2.80E+1
2. Average Release Rate For Period µCi/sec O.OOE+OO O.OOE+OO
3. Gross Alpha Radioactivity Release Curies 1.99E-07 1.83E-07 D. Tritium:
1. Total Release Curies 1.46E+01 4.52E+OO 3.10E+1
2. Average Release Rate For Period µCi/sec 1.88E+OO 5.75E-01 E. Carbon-14
1. Total Release Curies 4.08E+OO 2.08E+OO
2. Average Release Rate For Period µCi/sec 5.19E-01 2.65E-01 F. Percentage Of Technical Specification Limits
1. Total Body Dose Rate  % 3.71E-06 8.46E-08
2. Skin Dose Rate  % 1.42E-06 1.28E-06
3. Critical Organ Dose Rate (with C-14)  % 1.50E-02
  • 2.46E-03 Critical Organ Dose Rate (without C-14)  % 7.36E-03 1.70E-03

TABLE 1A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR (01/17 - 12/17)

Page 2 of 2 3RD 4TH ESTIMATED TOTAL UNITS QUARTER QUARTER PERCENT ERROR (%)

A. Fission and Activiation Gases:

1. Total Release Curies 2.02E-01 4.68E-02 1.80E+1
2. Average Release Rate For Period µCi/sec 2.54E-02 5.89E-03 B. Iodines:
1. Total lodine-131 Release Curies O.OOE+OO O.OOE+OO 2.80E+1
2. Average Release Rate For Period µCi/sec O.OOE+OO O.OOE+OO C. Particulate CT112 > 8 days}:
1. Total Particulate (T112 > 8 days) Release Curies 5.24E-06 3.59E-07 2.80E+1
2. Average Release Rate For Period µCi/sec 6.59E-07 4.51E-08
3. Gross Alpha Radioactivity Release Curies 2.50E-07 O.OOE+OO D. Tritium:
1. Total Release Curies 5.21E+OO 7.58E+OO 3.10E+1
2. Average Release Rate For Period µCi/sec 6.55E-01 9.53E-01 F. Carbon-14
1. Total Release Curies 1.46E+01 3.38E+OO
2. Average Release Rate For Period µCi/sec 1.84E+OO 4.25E-01 F. Percentage Of Technical Specification Limits
1. Total Body Dose Rate  % 4.39E-06 6.48E-08
2. Skin Dose Rate  % 2.13E-06 2.63E-06
3. Critical Organ Dose Rate (with C-14)  % 1.00E-02 3.83E-03 Critical Organ Dose Rate (without C-14)  % 2.04E-03 2.58E-03

TABLE 18 NORTH ANNA POWER STATION

~1 y.,

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/17 - 12/17)

Page 1 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission & Activation Gases:

Krypton - 85 . Ci N/D N/D N/D N/D Krypton - 85m Ci N/D N/D N/D N/D Krypton - 87 Ci N/D N/D N/D N/D Krypton - 88 Ci N/D N/D N/D N/D Xenon - 131m Ci N/D N/D N/D N/D Xenon -133 Ci 2.22E-02 9.41E-03 N/D N/D Xenon -133m Ci N/D N/D N/D N/D Xenon - 135 Ci N/D N/D N/D 7.01E-04 Xenon-135m Ci N/0. N/D N/D N/D Xenon -137 Ci N/D N/D N/D N/D Xenon - 138 Ci N/D N/D N/D N/D Other (Specify) N/D N/D N/D N/D Argon -41 Ci N/D 1.63E-02 N/D 2.45E-03 Total For Period Ci 2.22E-02 2.57E-02 N/D 3.15E-03 Iodines:

Iodine -130 Ci N/D N/D N/D N/D Iodine -131 Ci N/D N/D N/D N/D Iodine -132 Ci N/D N/D N/D N/D Iodine -133 Ci N/D N/D N/D N/D Iodine -134 Ci N/D N/D N/D N/D Iodine -135 Ci N/D N/D N/D N/D Total For Period Ci N/D N/D N/D N/D Particulates:

Manganese - 54 Ci N/D N/D N/D N/D Cobalt - 58 Ci N/D N/D N/D N/D Iron - 59 Ci N/D N/D N/D N/D Cobalt-60 Ci N/D N/D N/D N/D Zinc-65 Ci N/D N/D N/D N/D Strontium - 89 Ci N/D N/D N/D N/D Strontium - 90 Ci N/D N/D N/D N/D Cesium-134 Ci N/D N/D N/D N/D Cesium -136 Ci N/D N/D N/0 N/D Cesium-137 Ci N/D N/D N/D N/D

TABLE 18 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/17 - 12/17)

Page 2 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Particulates: (cont.)

Barium - Lanthanum - 140 Ci N/D. N/D N/D N/D Cerium - 141 Ci N/D N/D N/D N/D Cerium - 144 Ci N/D N/D N/D N/D Ag-110m Ci N/D N/D N/D N/D Total for Period (T1/2 > 8 days) Ci N/D N/D N/D N/D Total for Period (T1/2 < 8 days) Ci N/D N/D N/D N/D Total For Period Ci N/D N/D N/D N/D GROSS ALPHA: Ci N/D N/D N/D N/D TRITIUM: Ci 1.26E+OO 7.08E-01 4.17E-04 N/D CARBON-14 Ci 1.60E+OO 1.85E+OO N/D 2.27E-01

TABLE 18 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/17 - 12/17)

Page 3 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER "

QUARTER Fission & Activation Gases:

Krypton - 85 Ci N/D N/D N/D N/D Krypton - 85m Ci N/D N/D N/D N/D Krypton - 87 Ci N/D N/D N/D N/D Krypton - 88 Ci N/D N/D N/D N/D Xenon -131m Ci N/D N/D N/D N/D Xenon - 133 Ci 3.60E-02 N/D 1.40E-01 6.71E-03 Xenon-133m Ci N/D N/D 5.50E-04 N/D Xenon -135 Ci N/D N/D 1.02E-03 N/D Xenon-135m Ci N/D N/D N/D N/D Xenon -137 Ci N/D N/D N/D N/D Xenon -138 Ci N/D N/D N/D N/D Other (Specify) N/D N/D N/D N/D Argon - 41 Ci 8.32E-03 4.00E-02 N/D N/D Total For Period Ci 4.43E-02 4.00E-02 1.42E-01 6.71E-03 Iodines:

Iodine -130 Ci N/D N/D N/D N/D Iodine -131 Ci N/D N/D N/D N/D Iodine -132 Ci N/D N/D N/D N/D Iodine - 133 Ci N/D N/D N/D N/D Iodine - 134 Ci N/D N/D N/D N/D Iodine - 135 Ci N/D N/D N/D N/D Total For Period Ci N/D N/D N/D N/D Particulates:

Manganese - 54 Ci N/D N/D N/D N/D Cobalt- 58 Ci N/D N/D N/D N/D Iron - 59 Ci N/D N/D N/D N/D Cobalt- 60 Ci N/D 2.76E-08 N/D N/D Zinc-65 Ci N/D N/D N/D N/D Strontium - 85 Ci N/D N/D N/D N/D Strontium - 89 Ci N/D N/D N/D N/D Strontium - 90 Ci N/D N/D N/D N/D Silver-110m Ci N/D N/D N/D N/D Cesium -134 Ci N/D N/D N/D N/D Cesium -137 Ci N/D N/D N/D N/D

r TABLE 18 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/17 - 12/17)

Page 4 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Particulates: (cont.)

Barium - Lanthanum -140 Ci N/D N/D N/D N/D Cerium -141 Ci N/D N/D N/D N/D Cerium -144 Ci N/D N/D N/D N/D Total for Period (T1/2 > 8 days) Ci N/D 2.76E-08 N/D N/D Total for Period (T1/2 < 8 days) Ci N/D N/D N/D N/D Total For Period Ci N/D 2.76E-08 N/D N/D GROSS ALPHA: Ci N/D N/D N/D N/D TRITIUM: Ci 4.65E-01 2.00E+OO 5.50E-02 1.51E-04 CARBON-14 Ci 3.20E+OO 2.89E+OO 1.02E+01 4.84E-01

TABLE 1C --

(

NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/17 - 12/17)

Page 1 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission & Activation Gases:

Krypton - 85 Ci N/D N/D N/D N/D Krypton - 85m Ci N/D N/D 3.76E-05 N/D Krypton - 87 Ci N/D N/D N/D N/D Krypton - 88 Ci N/D N/D N/D N/D Xenon - 131m Ci N/D N/D 3.06E-04 N/D Xenon - 133 Ci N/D N/D 3.08E-02 N/D Xenon -133m Ci N/D N/D 6.38E-04 N/D Xenon - 135 Ci N/D N/D 2.42E-03 N/D Xenon - 135m Ci N/D N/D N/D N/D Xenon -137 Ci N/D N/D N/D N/D Xenon - 138 Ci N/D N/D N/D N/D Other (Specify)

Argon - 41 Ci N/D N/D 1.13E-04 N/D Total For Period Ci N/D N/D 3.43E-02 N/D Iodines:

Iodine - 130 Ci N/D N/D N/D N/D Iodine - 131 Ci N/D N/D N/D N/D Iodine - 132 Ci N/D N/D N/D N/D Iodine - 133 Ci N/D N/D N/D N/D Iodine - 134 Ci N/D N/D N/D N/D Iodine - 135 Ci N/D N/D N/D N/D Total For Period Ci N/D N/D N/D N/D Particulates:

Manganese - 54 Ci N/D N/D N/D N/D Cobalt - 58 Ci N/D N/D N/D N/D Iron - 59 Ci N/D N/D N/D N/D Cobalt- 60 Ci N/D N/D N/D N/D Zinc- 65 Ci N/D N/D N/D N/D Strontium - 89 Ci N/D N/D N/D N/D Strontium - 90 Ci N/D N/D N/D N/D Cesium -134 Ci N/D N/D N/D N/D

TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/17 - 12/17)

Page 2 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Particulates: (cont.)

Cesium -137 Ci N/D N/D N/D N/D Barium - Lanthanum - 140 Ci N/D N/D N/D N/D Ruthenium-103 (T1/2 > 8 days) Ci N/D N/D N/D N/D Cerium -144 Ci N/D N/D N/D N/D Niobium-95 Ci N/D N/D N/D N/D Zirconium-95 Ci N/D N/D N/D N/D Tellurium-131m (T1/2 < 8 days) Ci N/D N/D N/D N/D Yttrium-91m (T1/2 < 8 days) Ci N/D N/D N/D N/D Chromium-51 Ci N/D N/D N/D N/D Total for Period (T1/2 > 8 days) Ci N/D N/D N/D N/D Total for Period (T1/2 < 8 days) Ci N/D N/D N/D N/D Total For Period Ci N/D N/D N/D N/D GROSS ALPHA: Ci 1.99E-07 1.83E-07 N/D N/D TRITIUM: Ci 1.34E+01 3.81E+OO 9.29E-04 1.02E-04 CARBON-14 Ci N/D N/D 2.48E+OO N/D

TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/17 - 12/17)

Page 3 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission & Activation Gases:

Krypton - 85 Ci N/D N/D N/D N/D Krypton - 85m Ci N/D N/D 2.21E-05 N/D Krypton - 87 Ci N/D N/D 1.96E-06 N/D Krypton - 88 Ci N/D N/D 1.44E-05 '

N/D Xenon - 131m Ci N/D N/D 2.81E-05 N/D Xenon -133 Ci N/D N/D 1.24E-02 7.61E-05 Xenon -133m Ci N/D N/D 2.67E-04 N/D Xenon -135 Ci N/D N/D 2.36E-03 N/D Xenon -135m Ci N/D N/D 2.66E-05 N/D Xenon-137 Ci N/D N/D N/D N/D Xenon -138 Ci N/D N/D N/D N/D Other (Specify) Ci Argon - 41 Ci N/D N/D 4.25E-04 N/D Total For Period Ci N/D N/D 1.55E-02 7.61E-05 Iodines:

Iodine - 130 Ci N/D N/D N/D N/D Iodine - 131 Ci N/D N/D N/D N/D Iodine -132 Ci N/D N/D 1.13E-05 N/D Iodine - 133 Ci N/D N/D 6.56E-08 N/D Iodine - 134 Ci N/D N/D N/D N/D Iodine - 135 Ci N/D N/D N/D N/D Total For Period Ci N/D N/D 1.14E-05 N/D Particulates:

Manganese - 54 Ci N/D N/D N/D N/D Cobalt - 58 Ci 1.51E-06 N/D 3.37E-07 N/D Iron - 59 Ci N/D N/D N/D N/D Cobalt-60 Ci N/D N/D 2.23E-06 3.31E-07 Zinc- 65 Ci N/D N/D N/D N/D Strontium - 89 Ci N/D N/D N/D N/D Strontium - 90 Ci N/D N/D N/D N/D Cesium -134 Ci N/D N/D N/D N/D

If TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/17 - 12/17}

Page 4 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Particulates: {cont.)

Cesium -137 Ci N/D N/D N/D N/D Barium - Lanthanum - 140 Ci N/D N/D N/D N/D Cerium -141 Ci N/D N/D N/D N/D Cerium -144 Ci N/D N/D N/D N/D Other {Specify)

Strontium-91 {T1/2 < 8 days) Ci N/D N/D 8.40E-09 N/D Rubidium-BB {T1/2 < 8 days) Ci N/D N/D 1.99E-06 N/D Niobium-95 {T1/2 > 8 days) Ci N/D N/D 7.31E-07 N/D Ru-103 {T1/2 > 8 days) Ci N/D N/D 4.26E-07 N/D Rhodium-105 {T1/2 < 8 days) Ci N/D N/D N/D N/0 Ruthenium-105 {T1/2 < 8 days) Ci N/D N/D N/D N/D Total for Period {T1/2 > 8 days) Ci N/D N/D 3.73E-06 3.31 E-07 Total for Period {T1/2 < 8 days) Ci N/D N/D 1.99E-06 N/D Total For Period Ci N/0 N/D 5.72E-06 3.31E-07 GROSS ALPHA: Ci 2.SOE-07 N/0 N/D N/0 TRITIUM: Ci 3.39E+OO 5.53E+OO 1.32E+OO 4.56E-02 CARBON-14 Ci N/D N/D 1.12E+OO 5.49E-03

TABLE 2A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT -SUMMATION OF ALL RELEASES FOR (01/17 12/17}

Page 1 of 2 1 ST 2 ND ESTIMATED TOTAL UNITS QUARTER QUARTER PERCENT ERROR (%)

A. Fission and Activiation Products:

1. Total Release (not ineluding tritium, noble gas, and gross alpha). Curies 4.SOE-03 1.15E-04 2.00E+01
2. Average diluted concentration during the period. µCi/ml 1.02E-11 1.48E-13
3. Percent of applicable limit (T.S.)  % 2.26E-05 3.0SE-07 B. Tritium:
1. Total release activity. Curies 1.90E+02 4.71E+02 2.00E+01
2. Average diluted concentration during the period. µCi/ml 4.29E-07 6.07E-07
3. Percent of applicable limit (T.S.)  % 4.29E-03 6.07E-03 C. Dissolved and Entrained Gases:
1. Total release activity. Curies O.OOE+OO O.OOE+OO 2.00E+01
2. Average diluted concentration during the period. µCi/ml O.OOE+OO O.OOE+OO
3. Percent of applicable limit (T.S.)  % O.OOE+OO O.OOE+OO D. Gross Alpha Radioactivity:
1. Total release activity. Curies O.OOE+OO O.OOE+OO 2.00E+01 E. Volume of waste released: (prior to dilution). Liters 1.01E+08 1.10E+08 3.00E+OO F. Total volume of dilution water used during the period. Liters 4.42E+11 7.76E+11 3.00E+OO

TABLE 2A

Page 2 of2 3 RD 4 TH ESTIMATED TOTAL

  • UNITS QUARTER QUARTER PERCENT ERROR (%)

A. Fission and Activiation Products:

1. Total Release (not including tritium, noble gas, and gross alpha). Curies 2.78E-03 7.37E-03 2.00E+01
2. Average diluted concentration during the period. µCi/ml 3.51E-12 1.0?E-11
3. Percent of applicable limit (T.S.)  % 3.0?E-06 1.02E-05 B. Tritium:
1. Total release activity. Curies 9.51E+02 1.69E+02 2.00E+01
2. Average diluted concentration during the period. µCi/ml 1.20E-06 2.46E-07
3. Percent of applicable limit (T.S.)  % 1.20E-02 2.46E-03 C. Dissolved and Entrained Gases:
1. Total release activity. Curies O.OOE+OO O.OOE+OO 2.00E+01
2. Average diluted concentration during the period. µCi/ml O.OOE+OO O.OOE+OO
3. Percent of applicable limit (T.S.)  % O.OOE+OO O.OOE+OO D. Gross Alpha Radioactivity:
1. Total release activity. Curies O.OOE+OO O.OOE+OO 2.00E+01 E. Volume of waste released: (prior to dilution). Liters 8.52E+07 8.81E+07 3.00E+OO F. Total volume of dilution water used during the period. Liters 7.92E+11 6.87E+11 3.00E+OO

/J

/*i TABLE 28 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/17 - 12/17)

Page 1 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission & Activation Products:

Manganese - 54 Ci 9.20E-05 NID NIA NID Iron - 59 Ci 8.54E-05 NID NIA NID Cobalt-58 Ci 1.19E-03 4.84E-05 NIA NID Cobalt- 60 Ci 2.28E-03 3.BBE-05 NIA NID Strontium - 89 Ci NID NID NIA NID Strontium - 90 Ci NID NID NIA NID Niobium - 95 Ci 3.10E-04 NID NIA NID Antimony-124 Ci 1.70E-05 NID NIA NID Silver- 110m Ci 6.BBE-05 NID NIA NID Iodine -131 Ci NID N/D NIA NID Iodine - 133 Ci NID N/D NIA NID Cesium -134 Ci NID NID NIA NID Cesium -137 Ci 1.31 E-04 NID NIA 7.56E-06 Zirconium - 95 Ci 8.14E-05 NID NIA NID Cerium -141 Ci NID NID NIA NID Tellurium-125m Ci 4.57E-05 NID NIA 3.82E-06 Niickel - 63 (T112 > 8 days) Ci NID NID NIA NID Antimony-125 Ci 1.98E-04 NID NIA 1.65E-05 Total for Period Ci 4.50E-03 8.72E-05' NIA 2.79E-05

J.;

TABLE 28 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/17 - 12/17)

Page 2 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Dissolved & Entrained Noble Gases:

Xenon -133 Ci N/D N/D N/A N/D Xenon -133m Ci N/D N/D N/A N/D Xenon -135 Ci N/D N/D N/A N/D Xenon -135m Ci N/D N/D N/A N/D Other (Specify) Ci N/D N/D N/A N/D Krypton-BB ( T1/2 < B days) Ci N/D N/D N/A N/D Krypton-B5 (T1/2 > B days) Ci N/D N/D N/A N/D Total for Period Ci N/D N/D N/A N/D Tritium Ci 1.B9E+02 4.71E+02 N/A 1.6BE-02 Gross Alpha Ci N/D N/D N/A N/D

TABLE 28 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/17 - 12/17)

Page 3 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission & Activation Products:

Manganese - 54 Ci 1.71E-04 1.24E-04 NIA NIA Iron - 59 Ci NID NID NIA NIA Cobalt-58 Ci 2.23E-03 6.05E-03 NIA NIA Cobalt-60 Ci 3.79E-04 1.19E-03 NIA NIA Strontium - 89 Ci NID NID NIA NIA Strontium - 90 Ci NID NID NIA NIA Niobium-95 Ci NID NID NIA NIA Zirconium - 95 Ci NID NID NIA NIA Silver-110m Ci NID N/D NIA NIA Iodine - 131 Ci NID NID NIA NIA Iodine - 133 Ci NID NID NIA NIA Cesium -134 Ci NID NID NIA NIA Cesium - 137 Ci NID NID NIA NIA Barium-Lathanum - 140 Ci NID NID NIA NIA Cerium -141 Ci NID NID NIA NIA Chromium-51 Ci NID NID NIA NIA Nickel - 63 (T112 > 8 days) Ci NID NID NIA NIA Antimony-122 (T112 < 8 days) Ci NID NID NIA NIA Antimony-125 (T112 > 8 days) Ci NID NIA NIA Antimony-124 (T112 > 8 days) Ci NID NID NIA NIA Tellurium-125m (T112 > 8 days) Ci NID NIA NIA Total for Period Ci 2.78E-03 7.36E-03 NIA NIA

TABLE 28 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/17 - 12/17) .

Page 4 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Dissolved & Entrained Noble Gases:

Xenon -133 Ci NID N/D NIA NIA Xenon -133m Ci NID NID NIA NIA Xenon -135 Ci NID NID NIA NIA Xenon -135m Ci NID NID NIA NIA Other (Specify)

Argon - 41 (T112 < 8 days) Ci NID NID NIA NIA Krypton - 85 (T112 > 8 days) Ci NID NID NIA NIA Total for Period Ci NID NID NIA NIA Tritium Ci 9.51E+02 1.69E+02 NIA NIA Gross Alpha Ci NID NID NIA NIA

TABLE 3 NORTH ANNA POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS FOR 01-01-17 THROUGH 12-31-17 Page 1 of 2 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 12-Month Estimated Total

1. Type of Waste Unit Period Percent Error (%)
a. Spent resins, sludges, filters sludge, mJ 2.10E+01
  • 2.50E+01 evaporator bottoms, etc., Ci 1.54E+02 2.50E+01
b. Dry compressible waste, contaminated mJ 2.63E+02 ** 2.50E+01 equipment, etc., Ci 2.10E+OO 2.50E+01
c. Irradiated components, control rods, mJ O.OOE+OO 2.50E+01 etc., Ci O.OOE+OO 2.50E+01
d. Other (describe)

Used oil/Blast media/Sewage/Gravel mJ 9.20E-02 **** 2.50E+01 Dessicant/Soil/Construction debris Ci 1.61E-04 2.50E+01 Animal Carcasses

2. Estimate of major nuclide composition Estimated Total (by type of waste) (%) (Ci) Percent Error (%)
a. Co-60 5.08E+01 7.82E+01 2.50E+01 Ni-63 2.03E+01 3.13E+01 2.50E+01 Cs-137 1.02E+01 1.57E+01 2.50E+01 Fe-55 5.58E+OO 8.SOE+OO 2.50E+01 Cs-134 3.47E+OO 5.35E+OO 2.50E+01 Mn-54 2.44E+OO 3.76E+OO 2.50E+01 Co-58 1.99E+OO 3.07E+OO 2.50E+01 Sb-125 1.53E+OO 2.36E+OO 2.50E+01 Be-7 7.90E-01 1.22E+OO 2.50E+01 C-14 5.30E-01 8.16E-01 2.50E+01 Ni-59 1.SOE-01 2.36E-01 2.50E+01 H-3 1.10E-01 1.66E*01 2.50E+01 Cr-51 9.00E-02 1.38E-01 2.50E+01 Nb-95 6.00E-02 9.95E-02 2.50E+01 Zn-65 6.00E-02 9.72E-02 2.50E+01
b. Co-60 4.59E+01 9.63E-01 2.50E+01 Nb-95 1.73E+01 3.64E*01 2.50E+01 Zr-95 9.74E+OO 2.0SE-01 2.50E+01 Cr-51 8.96E+OO 1.88E-01 2.50E+01 Cs-137 8.30E+OO 1.74E-01 2.50E+01 Co-58 6.23E+OO 1.31E-01 2.50E+01 Fe-55 4.57E+OO 9.SOE-02 2.50E+01 Ni-63 3.09E+OO 6.49E-02 2.50E+01 Mn-54 1.14E+OO 2.39E-02 2.50E+01 Fe-59 8.90E-01 1.87E-02 2.50E+01 Sb-125 6.90E-01 1.45E-02 2.50E+01 Cs-134 5.90E-01 1.25E*02 2.50E+01 Zn-65 5.SOE-01 1.15E-02 2.50E+01 Sn-113 3.20E-01 6.77E-03 2.50E+01 Sb-124 3.00E-01 6.22E-03 2.50E+01 H-3 1.SOE-01 3.25E-03 2.50E+01
c. NONE
d. Co-60 6.94E+01 1.12E-04 2.50E+01 H-3 1.59E+01 2.57E-05 2.50E+01 Cs-137 4.BOE+OO 7.73E-06 2.50E+01 Fe-55 2.75E+OO 4.43E-06 Ni-63 2.SOE+OO 4.03E*06 Co-58 1.15E+OO 1.86E-06 Nb-95 1.09E+OO 1.76E-06 Zr-95 5.SOE-01 8.82E-07 Mn-54 5.30E-01 8.57E-07 Sb-125 4.30E-01 6.94E-07 2.50E+01

TABLE 3 NORTH ANNA POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS.

01-01-17 THROUGH 12-31-17 Page 2 of 2

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 1 Truck Clive, UT 9 Truck Oak Ridge, TN B. Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination 0 NIA N/A (4) shipments containing resins were shipped to a licensed waste processor for final dewatering and disposal (1) shipment containing mechanical filters was shipped to a licensed waste facility for disposal (2) shipments containing mechanical filters were shipped to a licensed waste processor for processing (1) shipment containing resins was shipped to a licensed waste processor for processing (1) shipment containing sludge was shipped to a licensed waste processor for processing (6) shipments containing dry compactable waste were shipped to a licensed waste processor for processing (1) shipment containing dry compactable waste was shipped to a licensed waste facility for disposal None (1) shipment containing dried bird droppings and animal carcases was shipped to a licensed waste disposal facility for processing

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