ML15105A080
| ML15105A080 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/10/2015 |
| From: | Bischof G T Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards |
| References | |
| 15-178 | |
| Download: ML15105A080 (137) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANYRICHMOND, VIRGINIA 23261April 10, 2015United States Nuclear Regulatory Commission Serial No. 15-178Attention:
Document Control Desk NAPS/JHLWashington, D. C. 20555 Docket Nos. 50-338/339 72-1672-56License Nos. NPF-4/7SNM-2507VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
NORTH ANNA POWER STATION UNIT NOS. 1 AND 2INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTEnclosed is the 2014 Annual Radioactive Effluent Release Report. This report isprovided pursuant to North Anna Units 1 and 2 Technical Specification 5.6.3 [10 CFR50.36a] 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 Page Kempat (540) 894-2295.
Very truly yours,Gerald T. BischofSite Vice President Enclosure Commitments made in this letter: Nonecc: U. S. Nuclear Regulatory Commission Region IIMarquis One Tower245 Peachtree Center Ave., NE Suite 1200Atlanta, Georgia 30303-1257
- Director, Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D. C. 20555NRC Senior Resident Inspector
---=North Anna Power Station k (H'ýSS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTNORTH ANNA POWER STATION(JANUARY 01, 2014 TO DECEMBER 31, 2014)PREPARED BY:_________________
Supe~rvisor Radiological Analysis and Instrumentation REVIEWED BY:_ _ _ _Supervisor Health PhysicsTechnical ServicesAPPROVED BY:___________
ManagerRadiological Protection and Chemistry FORWARDThis report is submitted in accordance with North Anna Unit 1 and 2 Technical Specification 5.6.3 andNorth Anna Independent Spent Fuel Storage Installation (ISFSI) Technical Specification 5.5.2.cand 10CFR72.44(d)(3).
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTFOR THENORTH ANNA POWER STATIONJANUARY 01, 2014 TO DECEMBER 31, 2014INDEXSubjectSection No.1234Attachment 1Attachment 2Attachment 3Attachment 4PageEXECUTIVE SUMMARY ...................................
PURPOSE AND SCOPE ...................................
D IS C U S S IO N ..................................................
SUPPLEMENTAL INFORMATION
.......................
-Effluent Release Data .................................
-Annual and Quarterly Doses .......................
-Revisions to Offsite Dose Calculation M anual (O D C M ) ........................................
-Major Changes to Radioactive Liquid,Gaseous, and Solid Waste Treatment S y s te m s ..................................................
-Inoperability of Radioactive Liquidand Gaseous Effluent Monitoring Instrum e ntation ........................................
-Unplanned Releases
.................................
-Lower Limits of Detection (LLD) forEffluent Sample Analysis
...........................
Results of Ground Water Protection Initiative S am ple A nalysis .....................................
Carbon-14 Calculations
.............................
Annual Effluent Release Report Log ............
1-223-44567891011 -1213 -2425 -2627Attachment 5Attachment 6Attachment 7Attachment 8Attachment 9Miscellaneous 1.0 EXECUTIVE SUMMARYThe Annual Radioactive Effluent Release Report describes the radioactive effluent control programconducted at the North Anna Power Station and Independent Spent Fuel Storage Installation (ISFSI) duringthe 2014 calendar year. This document summarizes the quantities of radioactive liquid and gaseouseffluents and solid waste released from the North Anna Power Station and ISFSI in accordance withRegulatory Guide 1.21 during the period January 1 through December 31, 2014, and includes anassessment of radiation doses to the maximum exposed member of the public due to radioactive liquid andgaseous effluents.
There were no releases from the ISFSI during 2014.There were no unplanned
- releases, meeting the reporting criteria of Section 6.7.2.a.3 of the Offsite DoseCalculation 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 2014 effluent release data in accordance with the Offsite Dose Calculation Manual. The results of these pathway dose calculations indicate thefollowing:
- a. The total body dose due to liquid effluents was 3.94E-1 mrem, which is 6.57% of the dose limit andthe critical organ dose due to liquid effluents was 3.95E-1 mrem, which is 1.98% of the dose limit.b. The air dose due to noble gases was 3.34E-3 mrad gamma, which is 1.67E-2%
of the annualgamma dose limit, and 2.04E-3 mrad beta, which is 5.10E-3%
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 daysincluding C-14 was 1.46 mrem, which is 4.87% of the annual dose limit. The bases of C-14calculations 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 notincluding C-14 was 6.87E-3 mrem, which is 2.29E-2%
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 two revisions to the Offsite Dose Calculation Manual during this reporting period.1 1.0 EXECUTIVE SUMMARY (cont.)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 resultedin negligible dose consequences to the maximum exposed member of the public in unrestricted areas.2.0 PURPOSE AND SCOPEThe Radioactive Effluent Release Report includes, in Attachment 1, a summary of the quantities ofradioactive 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 Liquidand Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants",
Revision 1, June 1974, with datasummarized on a quarterly basis for Table 1 and 2 and on an annual basis on Table 3. The reportsubmitted before May 1st of each year includes an assessment of radiation doses to the maximum exposedmember of the public due to radioactive liquid and gaseous effluents released from the site during theprevious calendar year. The report also includes a list of unplanned releases during the reporting period inAttachment 6.As required by Technical Specification, any changes to the Offsite Dose Calculation Manual (ODCM) for thetime 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) anda 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 thisreport.2
3.0 DISCUSSION
The basis for the calculation of the percent of Technical Specification for the critical organ in Table 1A ofAttachment 1 is the ODCM, section 6.3.1, which requires that the dose rate for iodine-1 31 and iodine-1 33,for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days shall be less than orequal to 1500 mrem/yr to the critical organ at or beyond the site boundary.
The critical organ is the child'sbone if C-14 is included and child's thyroid if C-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 1 A ofAttachment 1 is the ODCM, section 6.3.1, which requires that the dose rate for noble gases to areas at orbeyond the site boundary shall be less than or equal to 500 mrem/yr to the total body and less than or equalto 3000 mrem/yr to the skin.The basis for the calculation of the percent of Technical Specification in Table 2A in Attachment 1 is theODCM, section 6.2.1, which states that the concentrations of radioactive material released in liquid effluents to unrestricted 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 orentrained noble gases, the concentration shall be limited to 2.OE-4 piCi/ml.Percent of Technical Specification calculations are based on the total gaseous or liquid effluents releasedfor that respective quarter.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 werecalculated at site boundary.
The maximum exposed member of the public from the releases of airborneiodine-131 and iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8days, including carbon-14 is defined as a child, exposed through the vegetation
- pathway, with the criticalorgan being the bone. If carbon-14 is excluded from these calculations, the maximum exposed member ofthe public from the releases of airborne iodine-1 31 and iodine-1 33, tritium and all radionuclides in particulate form with half-lives greater than 8 days is defined as a child, exposed through the vegetation
- pathway, withthe critical organ being the thyroid gland. The maximum exposed member of the public for calculation oftotal body dose from radioactive materials in liquid effluents released to unrestricted areas is defined as achild, and also as a child for the calculation of critical organ dose, which was determined to be the liver. Theage group is exposed via the drinking water and fish ingestion pathways.
As shown in Attachment 6 there were no unplanned releases meeting the requirements of 6.7.2.a.3 of theODCM.3 3.0 DISCUSSION (cont.)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., minimumsample volume and maximum delay time prior to analysis).
Actual LLD values may be lower. If aradioisotope 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 notperformed, 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 newlocation(s) need be added for the radiological environmental monitoring program pursuant to the ODCM.There were no new sampling locations added. There were two (2) changes made to the land use census in2014. The nearest garden in the WSW sector changed from 2.36 miles to 2.22 miles. The nearestgarden in the WNW sector moved from 2.59 miles to 2.67 miles.Section 6.6.1 .b.4 of the ODCM requires identification of the cause(s) for the unavailability of milk or leafyvegetation
- samples, and the identification of new locations for obtaining replacement samples.
All milksamples were collected as required.
Vegetation samples were not collected from stations 14B, 15, 16, 23and 26 from January through April and from 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 water samples from various locations on the site.Attachment 9 contains an explanation of the bases for the carbon-14 calculations performed to assessdoses due to carbon-14.
Doses and %TS for gaseous releases are displayed with C-14 included andwithout for comparison of the values.4 ATTACHMENT IEFFLUENT RELEASE DATA(01/14 -12/14)This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste,as outlined in Regulatory Guide 1.21, Appendix B, except that in accordance with Step 6.7.2.a.1 of the ODCM liquidand gaseous data is summarized on a quarterly basis and solid waste is summarized on an annual basis.5 TABLE JANORTH ANNA POWER STATIONANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTSUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR (01/14 -12/14)Page 1 of 21 ST 2 ND ESTIMATED TOTALUNITS QUARTER QUARTER PERCENT ERROR (%)A. Fission and Activiation Gases1. Total Release Curies 1.18E+00 5.37E-01 1.80E+12. Average Release Rate For Period jiCi/sec 1.52E-01 6.83E-02B. Iodines:1. Total Iodine-131 Release Curies O.OOE+00 O.OOE+00 2.80E+12. Average Release Rate For Period gCi/sec O.OOE+00 O.OOE+00C. Particulate (T112 > 8 days):1. Total Particulate (T1/2> 8 days) Release Curies O.OOE+00 O.OOE+00 2.80E+12. Average Release Rate For Period piCi/sec O.OOE+00 O.OOE+003. Gross Alpha Radioactivity Release Curies 1.23E-07 3.55E-07D. Tritium:1. Total Release Curies 1.93E+00 1.56E+00 3.10E+12. Average Release Rate For Period jiCi/sec 2.48E-01 1.98E-01E. Carbon-14
- 1. Total Release Curies 5.10E+00 4.13E+002. Average Release Rate For Period piCi/sec 6.49E-01 5.25E-01F. Percentage Of Technical Specification Limits1. Total Body Dose Rate % 2.06E-03 1.98E-042. Skin Dose Rate % 5.00E-04 710E-053. Critical Organ Dose Rate (with C-14) % 1.25E-02 7,33E-03Critical Organ Dose Rate (without C-14) % 3.35E-05 1 00E-04 TABLE JANORTH ANNA POWER STATIONANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTSUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR (01114 -12/14)Page 2 of 23 RD 4TH ESTIMATED TOTALUNITS QUARTER QUARTER PERCENT ERROR (%)A. Fission and Activiation Gases1. Total Release Curies 4.OOE+00 9.67E-01 1.80E+12. Average Release Rate For Period pCi/sec 5.03E-01 1.22E-01B. Iodines:1. Total Iodine-131 Release Curies 1.12E-04 3.19E-07 2.80E+12. Average Release Rate For Period pCi/sec 1.41E-05 4.01E-08C. Particulate (T1l2 > 8 days):1. Total Particulate (T1/2 > 8 days) Release Curies 3.26E-05 4.42E-06 2.80E+12. Average Release Rate For Period pCi/sec 4.10E-06 5.56E-073. Gross Alpha Radioactivity Release Curies 3.91 E-07 1.54E-07D. Tritium:1. Total Release Curies 6.32E+00 2.11E+00 3.10E+12. Average Release Rate For Period pCi/sec 7.95E-01 2.65E-01F. Carbon-14
- 1. Total Release Curies 1.73E+01 4.19E+002. Average Release Rate For Period pCi/sec 2.18E+00 5.27E-01F. Percentage Of Technical Specification Limits1. Total Body Dose Rate % 8.55E-05 2.15E-042. Skin Dose Rate % 6.44E-05 5.80E-053. Critical Organ Dose Rate (with C-14) % 1.43E-02 2.97E-03Critical Organ Dose Rate (without C-14) % 5.98E-04 9.40E-05 TABLE 1BNORTH ANNA POWER STATIONANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTMIXED MODE GASEOUS EFFLUENT RELEASES FOR (01114 -12114)Page 1 of 4CONTINUOUS MODE BATCH MODE1ST 2ND 1ST 2NDNUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTERFission & Activation Gases:Krypton -85 Ci N/D N/D 1.93E-01 N/DKrypton -85m Ci N/D N/D NID N/DKrypton -87 Ci N/D N/D N/D N/DKrypton -88 Ci N/D N/D N/D N/DXenon -131m Ci N/D NID N/D N/DXenon -133 Ci N/D 4.17E-01 N/D N/DXenon -133m Ci NID NID N/D NIDXenon -135 Ci N/D N/D N/D N/DXenon -135m Ci N/D N/D N/D N/DXenon- 137 Ci N/D N/D N/D N/DXenon- 138 Ci N/D N/D N/D N/DOther (Specify)
NID NID N/D N/DArgon -41 Ci 5.53E-03 N/D N/D N/DTotal For Period Ci 5.53E-03 4.17E-01 1.93E-01 N/Dlodines:Iodine -131 Ci N/D N/D N/D N/DIodine -132 Ci N/D N/D NID N/DIodine -133 Ci NID N/D N/D N/DIodine -134 Ci N/D N/D N/D N/DIodine -135 Ci N/D N/D N/D N/DTotal For Period Ci N/D N/D N/D N/DParticulates:
-54 Ci N/D N/D N/D N/DCobalt -58 Ci N/D N/D N/D N/DIron -59 Ci N/D N/D N/D N/DCobalt -60 Ci N/D N/D N/D N/DZinc -65 Ci N/D N/D N/D N/DStrontium
-89 Ci N/D N/D N/D N/DStrontium
-90 Ci N/D N/D N/D N/DCesium- 134 Ci N/D N/D N/D N/DCesium -136 Ci N/D N/D N/D N/DCesium -137 Ci N/D N/D N/D N/D TABLE 1BNORTH ANNA POWER STATIONANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTMIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/14 -12/14)Page 2 of 4CONTINUOUS MODE BATCH MODE1ST 2ND 1ST 2NDNUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTERParticulates:
(cont.)Barium -Lanthanum
-140 Ci N/D N/D N/D N/DCerium- 141 Ci N/D N/D N/D N/DCerium- 144 Ci N/D N/D N/D N/DAg- 1i0m Ci N/D N/D N/D N/DTotal for Period (T1/2 > B days) Ci N/D N/D NID N/DTotal for Period (T11/2 < 8 days) Ci N/D N/D N/D N/DTotal For Period Ci N/D N/D N/D N/DGROSS ALPHA: Ci N/D N/D N/D N/DTRITIUM:
Ci 1 .79E+00 4.93E-01 8.38E-05 N/DCARBON-14 Ci 2.39E-02 1.80E+00 8.35E-01 0.OOE+00 TABLE lBNORTH ANNA POWER STATIONANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTMIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/14 -12/14)Page 3 of 4CONTINUOUS MODE BATCH MODE3RD 4TH 3RD 4THNUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTERFission & Activation Gases:Krypton -85 Ci N/D N/D 1.31E+00 5.81E-O1Krypton -85m Ci N/D N/D 1.85E-04 N/DKrypton -87 Ci N/D N/D N/D N/DKrypton -88 Ci N/D N/D N/D N/DXenon -131 m Ci N/D N/D N/D N/DXenon -133 Ci 2.53E-01 2.27E-02 1.67E+00 2.19E-01Xenon -133m Ci N/D N/D 2.28E-02 N/DXenon -135 Ci N/D N/D 2.77E-02 1.40E-02Xenon -135m Ci N/D N/D N/D N/DXenon -137 Ci N/D N/D N/D N/DXenon -138 Ci N/D N/D N/D N/DOther (Specify)
N/D N/D N/D N/DArgon -41 Ci N/D N/D N/D N/DTotal For Period Ci 2.53E-01 2.27E-02 3.03E+00 8.14E-01lodines:Iodine -131 Ci 7.66E-07 2.66E-08 N/D N/DIodine -132 N/D N/D N/D N/DIodine -133 Ci N/D N/D N/D N/DIodine -134 N/D N/D N/D N/DIodine- 135 Ci N/D N/D N/D N/DTotal For Period Ci 7.66E-07 2.66E-08 N/D N/DParticulates:
-54 Ci N/D N/D N/D N/DCobalt -58 Ci N/D N/D N/D N/DIron -59 Ci N/D N/D N/D N/DCobalt -60 Ci N/D N/D N/D N/DZinc -65 Ci N/D N/D N/D N/DStrontium
-85 Ci N/D N/D N/D N/DStrontium
-89 Ci N/D N/D N/D N/DStrontium
-90 Ci N/D N/D N/D N/DSilver-1 10m Ci 6.79E-09 1.19E-08 N/D N/DCesium -134 Ci N/D N/D N/D N/DCesium -137 Ci N/D N/D N/D N/D TABLE 1 BNORTH ANNA POWER STATIONANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTMIXED MODE GASEOUS EFFLUENT RELEASES FOR (01114 -12/14)Page 4 of 4CONTINUOUS MODE BATCH MODE3RD 4TH 3RD 4THNUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTERParticulates:
(cont.)Barium -Lanthanum
-140 Ci N/D N/D N/D N/DCerium- 141 Ci N/D N/D N/D N/DCerium- 144 Ci N/D N/D N/D N/DTotal for Pedod (T1/2 > 8 days) Ci 6.79E-09 1.19E-08 N/D N/DTotal for Period (T1/2 < 8 days) Ci N/D N/D N/D N/DTotal For Period Ci N/D N/D N/D N/DGROSS ALPHA: Ci N/D N/D N/D N/DTRITIUM:
Ci 1.64E+00 1.20E+00 4.53E-03 8.51E-04CARBON-14 Ci 1.09E+00 9.82E-02 1.31E+01 3.52E+00 TABLE ICNORTH ANNA POWER STATIONANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTGROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/14- 12/14)Page 1 of 4CONTINUOUS MODE BATCH MODE1ST 2ND 1ST 2NDNUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTERFission & Activation Gases:Krypton -85 Ci N/D N/D N/D 4.12E-01Krypton -85m Ci N/D N/D 8.17E-04 1.06E-03Krypton -87 Ci N/D NID N/D 8.76E-04Krypton -88 Ci N/D N/D 1.30E-03 1.66E-03Xenon -131m Ci N/D N/D N/D N/DXenon -133 Ci N/D N/D 7,40E-03 2.23E-02Xenon -133m Ci N/D N/D N/D 4.43E-04Xenon -135 Ci N/D N/D 8,01 E-03 1.09E-02Xenon -135m Ci N/D N/D N/D 2.86E-04Xenon -137 Ci N/D N/D N/D N/DXenon -138 Ci N/D N/D N/D 1.18E-03Other (Specify)
Argon -41 Ci N/D N/D 9.63E-01 8.62E-02Total For Period Ci N/D N/D 9.81E-01 5.37E-01Iodines:Iodine -131 Ci N/D N/D N/D N/DIodine -132 Ci N/D N/D N/D N/DIodine -133 Ci N/D Nil N/D N/DIodine -134 Ci N/D N/D N/D N/DIodine -135 Ci N/D N/D N/D N/DTotal For Period Ci N/D N/D N/D N/DParticulates:
-54 Ci N/D N/D N/D N/DCobalt -58 Ci N/D N/D N/D N/DIron -59 Ci N/D N/D N/D N/DCobalt -60 Ci N/D N/D N/D N/DZinc -65 Ci N/D N/D N/D N/DStrontium
-89 Ci N/D N/D N/D N/DStrontium
-90 Ci N/D N/D N/D N/DCesium -134 Ci N/D N/D N/D N/D TABLE 1CNORTH ANNA POWER STATIONANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTGROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/14 -12114)Page 2 of 4CONTINUOUS MODE BATCH MODE1ST 2ND 1ST 2NDNUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTERParticulates:
(cont.)Cesium -137 Ci N/D N/D N/D N/DBarium -Lanthanum
-140 Ci N/D N/D N/D N/DCerium- 141 Ci N/D N/D N/D N/DCerium -144 Ci N/D N/D N/D N/DNiobium-95 Ci N/D N/D N/D N/DZirconium-95 Ci N/D N/D N/D N/DRubidium-88 (T1/2 < 8 days) Ci N/D N/D N/D N/DCerium-143 (T1/2 < 8 days) Ci N/D N/D N/D N/DChromium-51 Ci N/D N/D N/D N/DTotal for Period (T1/2 > 8 days) Ci N/D N/D N/D N/DTotal for Period (T1/2 < 8 days) Ci N/D N/D N/D N/DTotal For Period Ci 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00GROSS ALPHA: Ci 1.23E-07 3.55E-07 N/D N/DTRITIUM:
Ci N/D 6.46E-01 1.42E-01 4.19E-01CARBON-14 Ci N/D N/D 4.24E +00 2.32E +00 TABLE 1CNORTH ANNA POWER STATIONANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTGROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01114 -12/14)Page 3 of 4CONTINUOUS MODE BATCH MODE3RD 4TH 3RD 4THNUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTERFission & Activation Gases:Krypton -85 Ci N/D N/D 5.72E-01 N/DKrypton -85m Ci N/D N/D 1.17E-04 1.35E-03Krypton -87 Ci N/D N/D 5.01 E-05 1.12E-03Krypton -88 Ci N/D N/D 1.02E-04 2.30E-03Xenon -131m Ci N/D N/D 1.60E-03 N/DXenon -133 Ci N/D N/D 9.86E-02 1.54E-02Xenon -133m Ci N/D N/D 2.06E-03 5.41E-04Xenon -135 Ci N/D N/D 9.84E-03 1.43E-02Xenon -135m Ci N/D N/D 8.16E-05 1.64E-03Xenon-537 Ci N/D N/D N/D N/DXenon -138 Ci N/D N/D N/D N/DOther (Specify)
CiArgon -41 Ci N/D N/D 2.61E-02 9.40E-02Total For Period Ci N/D N/D 7.11E-01 1.31 E-01Iodlines:
Iodine -131 Ci 1.05E-04 N/D 5.80E-06 2-92E-07Iodine -132 Ci 9.97E-05 N/D 4.24E-04 N/DIodine -133 Ci 8.81 E-05 N/D 1.16E-06 N/DIodine -134 Ci N/D N/D N/D N/DIodine -135 Ci N/D N/D N/D N/DTotal For Period Ci 2.93E-04 N/D 4.31 E-04 2.92E-07Particulates:
-54 Ci N/D N/D 3.34E-07 N/DCobalt -58 Ci N/D N/D 6.26E-06 N/DIron -59 Ci NID N/D N/D N/DCobalt -60 Ci N/D 3.28E-06 1.95E-05 N/DZinc -65 Ci N/D N/D N/D N/DStrontium
-89 Ci N/D N/D N/D N/DStrontium
-90 Ci N/D N/D N/D N/DICesium -134 Ci N/D N/D N/D N/D TABLE 1CNORTH ANNA POWER STATIONANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTGROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/14 -12/14)Page 4 of 4CONTINUOUS MODE BATCH MODE3RD 4TH 3RD 4THNUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTERParticulates:
(cont.)Cesium -137 Ci N/D 7.87E-07 6.59E-07 N/DBarium -Lanthanum
-140 Ci N/D N/D N/D N/DCerium- 141 Ci N/D N/D N/D N/DCerium- 144 Ci N/D N/D N/D N/DOther (Specify)
Chromium-51 (T1/2 > 8 days) Ci N/D N/D N/D N/DZirconium-95 (T1/2 > 8days) Ci N/D N/D 6.56E-07 N/DNiobium-95(T1/2
> 8days) Ci N/D N/D 1.87E-06 3.45E-07Ru-103 (Tl/2 > 8 days) Ci 3.33E-06 N/D N/D N/DTotal for Period (Tl/2 > 8 days) Ci 3.33E-06 4.07E-06 2.93E-05 3.45E-07Total for Period (Tl/2 < 8 days) Ci N/D N/D N/D N/DTotal For Period Ci 3.33E-06 4.07E-06 2.93E-05 3.45E-07GROSS ALPHA: Ci 3.91E-07 1.54E-07 N/D N/DTRITIUM:
Ci 2.62E+00 N/D 2.06E+00 9.09E-01CARBON-14 Ci N/D N/D 3.08E+00 5.67E-01 TABLE 2ANORTH ANNA POWER STATIONANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTLIQUID EFFLUENT
-SUMMATION OF ALL RELEASES FOR (01114 -12114)Page 1 of 21 ST 2 ND ESTIMATED TOTALUNITS QUARTER QUARTER PERCENT ERROR (%)A. Fission and Activiation Products:
- 1. Total Release (not including
- tritium, noble gas,and gross alpha). Curies 2.57E-03 6.04E-03 2.OOE+012. Average diluted concentration during theperiod. pCi/ml 4.OOE-12 7.OOE-123. Percent of applicable limit (.S.) % 5.55E-06 1.39E-05B. Tritium:1. Total release activity.
Curies 1.95E+01 1.72E+01 2.O0E+012. Average diluted concentration during theperiod. p.Ci/ml 3.05E-08 1.99E-083. Percent of applicable limit (T.S.) % 3.05E-04 1.99E-04C. Dissolved and Entrained Gases:1. Total release activity.
Curies O.00E+00 O.0OE+00 2.OOE+012. Average diluted concentration during theperiod. ý,Ci/ml O.0OE+00 O.0OE+003. Percent of applicable limit (T.S.) % O.OOE+00 O.OOE+00D. Gross Alpha Radioactivity:
- 1. Total release activity.
Curies O.OOE+00 0.OOE+00 2.OOE+01E. Volume of waste released:
(prior todilution).
Liters 8.21E+07 1.12E+08 3.O0E+00F. Total volume of dilution water usedduring the period. Liters 6.41E+11 8.63E+11 3.OOE+0O TABLE 2ANORTH ANNA POWER STATIONANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTLIQUID EFFLUENT
-SUMMATION OF ALL RELEASES FOR (01114 -12/14)Page 2 of 23 RD 4 TH ESTIMATED TOTALUNITS QUARTER QUARTER PERCENT ERROR (%)A. Fission and Activiation Products:
- 1. Total Release (not including
- tritium, noble gas,and gross alpha). Curies 5.19E-04 5.49E-02 2.OOE+012. Average diluted concentration during theperiod. 1iCi/ml 6.59E-13 1.01E-103. Percent of applicable limit (T.S.) % 4.86E-07 7.18E-05B. Tritium:1. Total release activity.
Curies 8.94E+02 1.84E+02 2.OOE+012. Average diluted concentration during theperiod. ýICi/ml 1.14E-06 3.38E-073. Percent of applicable limit (T.S.) % 1.14E-02 3.38E-03C. Dissolved and Entrained Gases:1. Total release activity.
Curies O.OOE+00 O.OOE+00 2.00E+012. Average diluted concentration during theperiod. ýLCi/ml O.OOE+00 O.OOE+003. Percent of applicable limit (T.S.) % O.OOE+00 O.OOE+00D. Gross Alpha Radioactivity:
- 1. Total release activity.
Curies 0.OOE+00 O.OOE+00 2.OOE+01E. Volume of waste released:
(prior todilution).
Liters 1.13E+08 1.11E+08 3.O0E+00F. Total volume of dilution water usedduring the period. Liters 7.87E+1 1 5.44E+1 1 3.OOE+00 TABLE 2BNORTH ANNA POWER STATIONANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTLIQUID EFFLUENT RELEASES FOR (01114 -12114)Page 1 of 4CONTINUOUS MODE BATCH MODE1ST 2ND 1ST 2NDNUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTERFission & Activation Products:
-54 Ci N/D N/D N/A N/AIron -59 Ci 2.06E-05 N/D N/A N/ACobalt -58 Ci 1.71 E-03 3.82E-04 N/A N/ACobalt -60 Ci 7.86E-04 1.60E-03 N/A N/AStrontium
-89 Ci N/D N/D N/A N/AStrontium
-90 Ci N/D N/D N/A N/ANiobium -95 Ci 4.54E-05 N/D N/A N/ARuthenium-106 Ci N/D N/D N/A N/ASilver -11Om Ci N/D 3.53E-03 N/A N/AIodine -131 Ci N/D N/D N/A N/AIodine -133 Ci N/D N/D N/A N/ACesium -134 Ci N/D N/D N/A N/ACesium -137 Ci 4.97E-06 N/D N/A N/ABarium-Lathanum
-140 Ci N/D N/D N/A N/ACerium -141 Ci N/D N/D N/A N/AZirconium
-97 Ci N/D 5.35E-04 N/D N/ANiickel -63 (T1/2 > 8 days) Ci N/D N/ID N/A N/AAntimony-1 25 Ci N/D N/D N/A N/ATotal for Period Ci 2.57E-03 6.05E-03 N/A N/A TABLE 2BNORTH ANNA POWER STATIONANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTLIQUID EFFLUENT RELEASES FOR (01114 -12114)Page 2 of 4CONTINUOUS MODE BATCH MODE1ST 2ND 1ST 2NDNUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTERDissolved
& Entrained Noble Gases:Xenon -133 Ci N/D N/D N/A N/AXenon -133m Ci N/D N/D N/A N/AXenon -135 Ci N/D N/D N/A N/AXenon -135m Ci N/D N/D N/A N/AOther (Specify)
Ci N/D N/D N/A N/AKrypton-88
( T1/2 < 8 days) Ci N/D N/D N/A N/AKrypton-85 (TI/2 > 8 days) Ci N/D N/D N/A N/ATotal for Period Ci N/D N/D N/A N/ATitium Ci 1.95E+01 1.72E+01 N/A N/AGross Alpha Ci N/D N/D N/A N/A TABLE 2BNORTH ANNA POWER STATIONANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTLIQUID EFFLUENT RELEASES FOR (01/14- 12/14)Page 3 of 4CONTINUOUS MODE BATCH MODE3RD 4TH 3RD 4THNUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTERFission & Activation Products:
-54 Ci N/D 3.17E-04 N/A N/AIron -59 Ci N/D 1.17E-04 N/A N/ACobalt -58 Ci 4.72E-04 4.84E-02 N/A N/ACobalt -60 Ci 4.10E-05 4.20E-03 N/A N/AStrontium
-89 Ci N/D N/D N/A N/AStrontium
-90 Ci N/D N/D N/A N/ANiobium -95 Ci N/D 9.98E-05 N/A N/AZirconium
-95 Ci N/D 3.23E-05 N/A N/ASilver -110m Ci 5.88E-06 1.58E-04 N/A N/AIodine -131 Ci N/D N/D N/A N/AIodine -133 Ci N/D N/D N/A N/ACesium -134 Ci N/D N/D N/A N/ACesium -137 Ci N/D N/D N/A N/ABarium-Lathanum
-140 Ci N/D N/D N/A N/ACerium -141 Ci N/D N/D N/A N/AChromium-51 Ci N/D 1.41 E-03 N/A N/ANickel -63 (T1/2 > 8 days) Ci N/D 1.80E-04 N/A N/AAntimony-122 (TI/2 < 8 days) Ci N/D N/D N/A N/AAntimony-1 25 (T1/2 > 8 days) Ci N/D N/D N/A N/AAntimony-124 (T1/2 > 8 days) Ci N/D 2.09E-04 N/A N/ATellurium-125m (T1/2 > 8 days) Ci N/DTotal for Period Ci 5.19E-04 5.51E-02 N/A N/A TABLE 2BNORTH ANNA POWER STATIONANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTLIQUID EFFLUENT RELEASES FOR (01114 -12/14)Page 4 of 4CONTINUOUS MODE BATCH MODE3RD 4TH 3RD 4THNUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTERDissolved
& Entrained Noble Gases:Xenon -133 Ci N/D N/D N/A N/AXenon -133m Ci N/D N/D N/A N/AXenon -135 Ci N/D N/D N/A N/AXenon- 135m Ci N/D N/D N/A N/AOther (Specify)
Argon -41 (Tl/2 < 8 days) Ci N/D N/D N/A N/AKrypton -85 (Tl/2 > 8 days) Ci N/D N/D N/A N/ATotal for Period Ci N/D N/D N/A N/ATritium Ci 8.94E+02 1.84E+02 N/A N/AGross Alpha Ci N/D N/D N/A N/A TABLE 3NORTH ANNA POWER STATIONRADIOACTIVE EFFLUENT RELEASE REPORTSUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS FOR 01-01-14 THROUGH 12-31-14Page 1 of 2A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)12-Month Estimated Total1. Type of Waste Unit Period Percent Error (%)a. Spent resins, sludges, filters sludge, m3 1.27E+01
- 2.50E+01evaporator
- bottoms, etc., Ci 1.98E+02 2.50E+01b. Dry compressible waste, contaminated m3 2.59E+02
- 2.50E+01equipment, etc., Ci 3.28E+00 2.50E+01c. Irradiated components, control rods, m3 O.OOE+00 2.50E+01etc., Ci 0.OOE+00 2.50E+01d. Other (describe)
Used oil/Blast medialSewagelGravel m3 9.71E+01 2.50E+01Dessicant/Soil/Construction debris Ci 9.70E-02 2.50E+01Animal Carcasses
- 2. Estimate of major nuclide composition Estimated Total(by type of waste) (%) (Ci) Percent Error (%)a. Ni-63 3.62E+01 7.18E+01 2.60E+01Cs-1 37 2.50E+01 4.96E+01 2.50E+01Co-60 2.25E+01 4.46E+Oi 2.50E+01Fe-55 5.83E+00 1.16E+01 2.50E+01Cs-134 5.35E+00 1.06E+01 2.50E+01Mn-54 1.94E+00 3.85E+00 2.50E+01Co-58 8.48E-01 1.68E+00 2.50E+01C-14 4.67E-01 9.27E-01 2.50E+01Ni-59 4.45E-01 8.83E-01 2.50E+01Ag-110m 4.05E-01 8.04E-01 2.50E+01b. Co-60 2.61E+01 8.55E-01 2.50E+01Fe-55 2.06E+01 6.76E-01 2.50E+01Nb-95 1.15E+01 3.78E-01 2.50E+01Cs-1 37 1.1 5E+01 3.77E-01 2.50E+0iZr-95 1.06E+01 3.48E-01 2.60E+01Ni-63 8.03E+00 2.63E-01 2.50E+01Cr-51 7.89E+00 2.59E-01 2.50E+01Co-58 4.08E+00 1.34E-01 2.50E+01Mn-54 1.23E+00 4.04E-02 2.50E+01Sb-125 6.86E-01 2.25E-02 2.50E+01Zn-65 3.65E-01 1.20E-02 2.50E+01c. NONEd. Fe-55 2.54E+01 2.47E-02 2.50E+01NI-63 2.51 E+01 2.44E-02 2.50E+01Co-60 2.10E+01 2.03E-02 2.50E+01Co-58 31.8E+01 1.14E-02 2.50E+01Ag-110m 6.99E+00 6.78E-03 2.50E+01H-3 6.38E+00 6.19E-03 2.60E+01Nb-95 1.36E+00 1.32E-03 2.50E+01Zr-95 8.23E-01 7.99E-04 2.50E+01Cs-1 37 4.43E-01 4.30E-04 2.50E+01C-14 2.86E-01 2.77E-04 2.50E+01Cs-1 34 2.08E-01 2.02E-04 2.50E+01Tc-99 1.97E-01 1.91 E-04 2.50E+01Sb-125 1.95E-01 1.90E-04 2.50E+01Co-57 1.84E-01 1.79E-04 2.50E+01Mn-54 1.55E-01 1.50E-04 2.50E+01 TABLE 3NORTH ANNA POWER STATIONRADIOACTIVE EFFLUENT RELEASE REPORTSUMMATION OF SOLID RADIOACTIVE WASTEAND IRRADIATED FUEL SHIPMENTS 01-01-14 THROUGH 12-31-14Page 2 of 23. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 3 Truck Clive, UT2 Truck Erwin, TN12 Truck Oak Ridge, TN2 Truck Barnwell, SCB. Irradiated Fuel Shipments (Disposition)
Number of Shipments Mode of Transportation Destination 0 N/A N/A(2) shipments containing resins were shipped to a licensed waste processor for processing (2) shipments containing resins were shipped to a licensed waste processor for disposal(2) shipments containing mechanical filters were shipped to a licensed waste processor for processing (3) shipments containing mechanical filters were shipped to a licensed waste facility for disposal(6) shipments containing dry compactable waste were shipped to a licensed waste processor for processing (3) shipments containing dry compactable waste were shipped to a licensed waste facility for disposalNone(2) shipments containing biological material were shipped to a licensed waste processor for processing (1) shipment containing charcoal was shipped to a licensed waste facility for disposal(6) shipments containing construction debris were shipped to a licensed waste processor for processing (2) shipments containing charcoal were shipped to a licensed waste processor for disposal.
ATTACHMENT 2ANNUAL AND QUARTERLY DOSES(01114 -12114)An assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid andgaseous effluents released from the site for each calendar quarter for the calendar year of this report, along with anannual total of each effluent pathway will be made as required by ODCM Section 6.7.2.1st 2nd 3rdnl.nrt4r O~nmnrta nlh.rtar4thMinurtrAnnualTnfnlTotal BodyDose (mrem) 6.95E-3 6.15E-3 3.16E-1 6.52E-2 3.94E-1Critical OrganDose (mrem) 7.06E-3 6.31 E-3 3.16E-1 6.55E-2 3.95E-11st 2nd 3rd 4th AnnualQuarter Quarter Quarter Quarter Total-Noble GasGamma Dose (mrad) 2.67E-3 2.60E-4 1.20E-4 2.87E-4 3.34E-3Noble GasBeta Dose (mrad) 9.56E-4 3.42E-4 5.72E-4 1.67E-4 2.04E-3Critical Organ(Child bone)Dose for 1-131,r-P133, H-3,Particulates withT% > 8 days'including C-14) (mrem) 5.40E-1 3.40E-1 3.95E-1 1.88E-1 1.46E+0'ritical Organ'Child thyroid)Dose for 1-131,1-133, H-3,Particulates withT% > 8 days(excluding C-14) (mrem) 3.26E-4 5.68E-4 6.42E-3 5.62E-4 6.88E-3,ill6-A' ATTACHMENT 3REVISIONS TO OFFSITE DOSE CALCULATION MANUAL(ODCM)(01/14 -12/14)As required by Technical Specification 5.5.1 .c, revisions to the ODCM, effective for the time period covered by thisreport, are summarized in this attachment.
There were two revisions to the ODCM during this reporting period. Revision 22 was effective on 01/07/14 andwas made due to a change in Rated Thermal Power from 2893 MW to 2940 MW. Revision 23 was effective on07/10/14 and was made to document the change in location description for environmental sectorThermoluminescent Dosimeters at location WSW-23/55.
This change was in description only. Dosimeter locationremained unchanged.
7 ATTACHMENT 4MAJOR CHANGES TO RADIOACTIVE LIQUID. GASEOUS, AND SOLIDWASTE TREATMENT SYSTEMS(01114 -12114)As required by the ODCM, Section 6.7.2.a.4, major changes to radioactive liquid, gaseous and solid wastetreatment 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, asapplicable.
There were no major changes to the radioactive liquid, gaseous, and solid waste treatment systems for 2014.8 ATTACHMENT 5INOPERABILITY OF RADIOACTIVE LIQUID AND GASEOUSEFFLUENT MONITORING INSTRUMENTATION (01/14 -12114)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.
1-LW-RM-111, the Clarifier Effluent Radiation
- Monitor, was inoperable from 05/13/14 until 09/03/14.
Degradedcondition of this radiation monitor was discovered during annual calibration in September 2014. A subsequent review of available monitor data showed performance degraded over time to the point where it was considered tobe non functional on 05/13/14.
Other details as well as actions taken to preclude future loss of functionality forthis monitor are included in North Anna Condition Report, CR558708, and the follow up assessments generated from this Condition Report.9 ATTACHMENT 6UNPLANNED RELEASES(01/14 -12114)As required by the ODCM, Section 6.7.2.a.3, a list of unplanned
- releases, from the site to unrestricted areas, ofradioactive material in gaseous and liquid effluents occurring during the reporting period, is made in this attachment.
There were no unplanned releases during calendar year 2014 meeting the criteria of Section 6.7.2.a.3 of the ODCMfrom the site to unrestricted areas. Also, there were no spills or leaks that required voluntary communication underthe criteria of the NEI Ground Water Protection Initiative, NEI 07-07. Elevated results indicated in Attachment 8 arefrom the on-going investigation/
mitigation for the voluntary communication made in 2010. The hydrological modeling indicates the horizontal groundwater movement around well #6 is < 1 inch per day. However, RPSupervision decided to include one unplanned gaseous release under the requirement of Offsite Dose Calculation Manual, section 6.7.2.a.3 bullet number 4. This release is described below.On 03/02/14 a High Alarm was received on Vent Vent A (WA) radiation monitor ,1-VG-RM-179 and Vent Vent B(VVB) radiation
- monitor, 1-VG-RM-180 while Chemistry personnel were attempting to obtain a sample of the Unit 1Volume Control Tank (VCT) gas space. Per procedure CH-1 1.245 , when Chemistry obtains a VCT gas spacesample, they first purge the sample line to the Gas Strippers to obtain a representative sample. In this instance, thepurge header drain valve, 1-SS-56, was found to be in the open position versus it's normally closed position.
Thisopen valve position allowed gas being purged to go directly to the Chemistry Sample Sink hood which is ventilated byVVA instead of following the normal flowpath to the Gas Strippers, leading to an unplanned release.
The Chemistry Sample Sink release pathway is normally through WA exclusively.
- However, since Auxiliary Building CentralExhaust was aligned to pass through the Charcoal filter banks for this release, damper leaks within the iodinefiltration system caused a release to and subsequent alarm from both release pathways, WA and WB. Peak totalrelease rate was 3.19E-3 Ci/sec .Maximum Percent Technical Specification, based on total body limit of 500mrem/yr, was a fraction of the allowable limit and calculated to be 5.10%TS.
For further information, see North AnnaCondition Report, CR541149 and SAA035754.
10 ATTACHMENT 7LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS(01/14 -12/14)Gaseous Effluents:
Required L.L.D. Typical L.L.D.Radioisotope gCi/mL LLCi/mnLKrypton -87 1.OOE-4 2.50E-8 -7.50E-8Krypton -88 1.OOE-4 1.OOE-7 -4.50E-7Xenon -133 1.OOE-4 5.OOE-8 1.OOE-7Xenon -133m 1.OOE-4 2.OOE-7 -4.OOE-7Xenon -135 1.OOE-4 2.OOE-8 -5.OOE-8Xenon -135m 1.OOE-4 5.OOE-8 -2.OOE-7Xenon -138 1.OOE-4 1.OOE-7 -5.OOE-7Iodine -131 1.00E-12 6.OOE-14
-1.OOE-13Iodine -133 1.OOE-10 1.OOE-14
-7.OOE-13Manganese
-54 1.OOE-11 6.OOE-14
-8.OOE-14Cobalt -58 1.OOE-11 5.OOE-14
-8.OOE-14Iron -59 1.OOE-1 1 9.OOE-14
-2.OOE-13Cobalt -60 1.OOE-11 5.OOE-14
-2.OOE-13Zinc -65 1.OOE-11 9.OOE-14
-3.OOE-13Strontium
-89 1.OOE-11 3.OOE-14
-8.OOE-12Strontium
-90 1.OOE-11 3.OOE-15
-9.OOE-12Molybdenum
-99 1.OOE-11 7.OOE-14
-2.OOE-13Cesium -134 1.OOE-1 1 5.OOE-14
-1.OOE-13Cesium -137 1.OOE-11 5.OOE-14
-8.OOE-14Cerium -141 1.OOE-11 5.OOE-14
-2.OOE-13Cerium -144 1.OOE-11 2.OOE-13
-5.00E-13Gross Alpha 1.OOE-11 7.OOE-15
-2.OOE-14Tritium 1.OOE-6 4.OOE-09
-9.OOE-0911 ATTACHMENT 7LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS(01/14 -12/14)Liquid Effluents:
Required L.L.D. Typical L.L.D.Radioisotope uXCi/mL UCi/mLKrypton -87 1.OOE-5 4.OOE-8 -1.OOE-7Krypton -88 1.OOE-5 1.OOE-7 -1.OOE-6Xenon -133 1.OOE-5 7.00E-8 -1.50E-7Xenon -133m 1.OOE-5 9.OOE-8 -3.OOE-7Xenon -135 1.OOE-5 9.OOE-9 -5.OOE-8Xenon -135m 1.OOE-5 3.OOE-8 -2.OOE-7Xenon -138 1.OOE-5 1.OOE-7 -1.OOE-6Iodine -131 1.OOE-6 1.00E-8 -5.OOE-8Manganese
-54 5.OOE-7 2.00E-8 -5.OOE-8Iron -55 1.OOE-6 3.OOE-7 -8.OOE-7Cobalt -58 5.OOE-7 2.OOE-8 -6.OOE-8Iron -59 5.OOE-7 3.OOE-8 -7.OOE-8Cobalt -60 5.OOE-7 1.OOE-8 -5.50E-8Zinc -65 5.OOE-7 3.OOE-8 -6.OOE-8Strontium
-89 5.OOE-8 1.OOE-8 -4.OOE-8Strontium
-90 5.00E-8 5.OOE-9 -9.OOE-9Molybdenum
-99 5.OOE-7 2.00E-8 -6.OOE-8Cesium -134 5.OOE-7 2.OOE-8 -5.OOE-8Cesium -137 5.OOE-7 3.OOE-8 -6.OOE-8Cerium -141 5.OOE-7 3.OOE-8 -9.OOE-8Cerium -144 5.00E-7 1.OOE-7 -5.OOE-7Gross Alpha 1.OOE-7 2.OOE-8 -7.OOE-8Tritium 1.OOE-5 2.OOE-6 -5.00E-612 ATTACHMENT 8RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS(01/14 -12114)The Ground Water Protection Program was established to improve North Anna's management of and response toinstances 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 of NEI 07-07, INDUSTRYGROUND WATER PROTECTION INITIATIVE
-FINAL GUIDANCE DOCUMENT.
The industry initiative is intendedto improve public trust and confidence in the nuclear industry through sampling and analysis of ground water andtimely and effective communication with stakeholders, including the public and local, state, and federal officials.
Samples are obtained from monitoring wells installed outside the restricted area on a quarterly basis and analyzedby Teledyne Brown Engineering Laboratories.
Additional samples are obtained from wells located inside therestricted area and analyzed by Teledyne Brown. Samples are obtained from sumps and yard drains on a quarterly basis and analyzed onsite. Finally, samples may be obtained more frequently than normal, if required.
Thesesamples may be analyzed on-site or by a vendor such as Teledyne Brown. 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 forcalendar year 2014. 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 "ND" indicates an analysis wasperformed but the result was less than the Minimum Detectable
- Activity, MDA, and the required LLD. If a result isgreater than the MDA, but less than the LLD the result is listed. Some of these results may be false positives, dueto the analysis software or interferences from naturally occurring radioactivity.
In these cases, instead of the value,an explanatory footnote is provided.
13 ATTACHMENT 8RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS(01114 -12114)s't Quarter 2014Sample Date Sample H-31' Gamma-Emitting 1-131" Sr-89I9O('
Fe-55(1) Ni-63" Alpha Pu-241Se Media Particulates' 11 TRU(1)IuGWP-6 01/09/14 WATER 47335 N/A N/A N/A N/A N/A N/A N/AGWP-6 01/16/14 WATER 29868 N/A N/A N/A N/A N/A N/A N/AGWP-6 01/23/14 WATER 37643 N/A N/A N/A N/A N/A N/A N/AGWP-6 01/30/14 WATER 57427 N/A N/A N/A N/A N/A N/A N/AGWP-6 02/06/14 WATER 24751 N/A N/A N/A N/A N/A N/A N/AGWP-6 02/14/14 WATER 33795 N/A N/A N/A N/A N/A N/A N/AGWP-6 02/20/14 WATER 39592 N/A N/A N/A N/A N/A N/A N/AU-1 Mat Sump South 04/09/14 WATER < 1352 N/A N/A N/A N/A N/A N/A N/AU-1 Mat Sump east 04/09/14 WATER < 1352 N/A N/A N/A N/A N/A N/A N/AU-1 AB/FB GWMS 04/09/14 WATER < 1352 N/A N/A N/A N/A N/A N/A N/AU-2 Inside Mat Sump 04/09/14 WATER < 1352 N/A N/A N/A N/A N/A N/A N/AU-2 Outside Mat Sump 04/09/14 WATER < 1352 N/A N/A N/A N/A N/A N/A N/AU-2 AB/FB GWMS 04/09/14 WATER < 1352 N/A N/A N/A N/A N/A N/A N/AU-1 Intake Yard Drains 02/05/14 WATER <1560 N/A N/A N/A N/A N/A N/A N/AU-2 Intake Yard drains 02/05/14 WATER <1560 N/A N/A N/A N/A N/A N/A N/ADischarge Canal Yard 02/05/14 WATER <1560 N/A N/A N/A N/A N/A N/A N/ADrainsSubsurface drains 02/05/14 WATER <1560 N/A N/A N/A N/A N/A N/A N/AGWP-6 02/27/14 WATER 60687 N/A N/A N/A N/A N/A N/A N/AGWP-6 03/06/14 WATER 66667 N/A N/A N/A N/A N/A N/A N/AGWP-6 03/11/14 WATER 69509 N/A N/A N/A N/A N/A N/A N/AGWP-6 (2) 03/11/14 WATER 61700 N/A N/A N/A N/A N/A N/A N/AGWP-6 03/20/14 WATER 56078 N/A N/A N/A N/A N/A N/A N/AGWP-62 03/27/14 WATER 46796 ND ND N/A N/A N/A N/A N/APZ-2 03/20/14 WATER Insufficient volume to samplePZ-1 03/20/14 WATER Insufficient volume to sampleGWP-3 04/03/14 WATER <1272 N/A N/A N/A N/A N/A N/A N/APZ-32 03/27/14 WATER 4130 ND ND N/A N/A N/A N/A N/AGWP-4 04/03/14 WATER <1272 N/A N/A N/A N/A N/A N/A N/AGWP-5A 04/03/14 WATER <1272 N/A N/A N/A N/A N/A N/A N/AGWP-7 04/03/14 WATER <1272 N/A N/A N/A N/A N/A N/A N/AGWP-8 04/03/14 WATER <1272 N/A N/A N/A N/A N/A N/A N/AGWP-9 04/03/14 WATER <1272 N/A N/A N/A N/A N/A N/A N/AGWP-13 04/03/14 WATER <1276 N/A N/A N/A N/A N/A N/A N/AGWP-14 04/03/14 WATER <1272 N/A N/A N/A N/A N/A N/A N/AGWP-15 04/03/14 WATER <1276 N/A N/A N/A N/A N/A N/A N/AGWP-16 04/03/14 WATER <1272 N/A N/A N/A N/A N/A N/A N/AGWP-17 04/03/14 WATER <1272 N/A N/A N/A N/A N/A N/A N/ABTW-1l2) 04/01/14 WATER <1520 N/A N/A N/A N/A N/A N/A N/ABTW-2(2) 04/01/14 WATER <1600 N/A N/A N/A N/A N/A N/A N/ABTW-4(2) 04/01/14 WATER <1530 N/A N/A N/A N/A N/A N/A N/ATrW-1 Well abandoned in place, pending decommissioning 14 ATTACHMENT 8RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS(01/14 -12114)Ist Quarter 2014Sampe Dte edi Patic~ate~
1~Fe-5~"Ni-3~"Alpha Pu.241(1)Sample H.31 Gamma -Emitting Sr-. TRUASample Date Media H31 Particulates(l) 1-131(11 89/90(,)
F-5)N-3' T U, u21lTTW-2(2) 04/01/14 WATER <1540 N/A N/A N/A N/A N/A N/A N/ATTW-3(2) 04/01/14 WATER <1510 N/A N/A N/A N/A N/A N/A N/ATTW-4 Well abandoned in place, pending decommissioning TTW5 (2) 04/01/14 WATER <1510 N/A I N/A IN/A I N/A IN/A N/A N/A(1) pCi/L(2) Vendor Analysis15
ATTACHMENT 8RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS(01/14 -12/14)2nd Quarter 2014Sample Date Sample H.31 Gamma -Emitting
.131(1) Sr.89/90'
- 1) Fe-55f1 Ni-63(11 Alpha Pu_241(1)
Media Particulates(
- 1) 1 TRU(1 -GWP-6 04/03/14 WATER 47652 N/A N/A N/A N/A N/A N/A N/AU-1 Mat Sump South 07/02/14 WATER < 1170 N/A N/A N/A N/A N/A N/A N/AU-1 Mat Sump east 07/02/14 WATER < 1170 N/A N/A N/A N/A N/A N/A N/AU-1 AB/F93 GWMS 07/02/14 WATER < 1170 N/A N/A N/A N/A N/A N/A N/AU-2 Inside Mat Sump 07/02/14 WATER < 1170 N/A N/A N/A N/A N/A N/A N/AU-2 Outside Mat Sump 07/02/14 WATER < 1170 N/A N/A N/A N/A N/A N/A N/AU-2 AB/F9 GWMS 07/02/14 WATER < 1170 N/A N/A N/A N/A N/A N/A N/AGWP-6 04/10/14 WATER 37491 N/A N/A N/A N/A N/A N/A N/AGWP-6 04/17/14 WATER 38835 N/A N/A N/A N/A N/A N/A N/AGWP-6 04/24/14 WATER 48965 N/A N/A N/A N/A N/A N/A N/AGWP-6 (2) 04/24/14 WATER 79559 N/A N/A N/A N/A N/A N/A N/AGWP-6 05/01/14 WATER 49413 N/A N/A N/A N/A N/A N/A N/AGWP-6 05/08/14 WATER 46174 N/A N/A N/A N/A N/A N/A N/AGWP-6 05/15/14 WATER 55165 N/A N/A N/A N/A N/A N/A N/AGWP-6 05/22/14 WATER 47491 ND N/A N/A N/A N/A N/A N/AGWP-6 05/29/14 WATER 34357 N/A N/A N/A N/A N/A N/A N/AGWP-6 06/03/14 WATER 33291 N/A N/A N/A N/A N/A N/A N/AGWP-6 06/12/14 WATER 38348 N/A N/A N/A N/A N/A N/A N/AGWP-6 06/16/14 WATER 42400 N/A N/A N/A N/A N/A N/A N/AGWP-6 (2) 06/16/14 WATER 51900 N/A N/A N/A N/A N/A N/A N/AGWP-6 06/26/14 WATER 48370 N/A N/A N/A N/A N/A N/A N/APZ-2 06/12/14 WATER Insufficient volume to samplePZ-1 06/12/14 WATER Insufficient volume to sampleGWP-3 06/16/14 WATER < 1260 N/A N/A N/A N/A N/A N/A N/AGWP-3(2) 06/16/14 WATER <868 N/A N/A N/A N/A N/A N/A N/APZ-3 06/19/14 WATER <1260 N/A N/A N/A N/A N/A N/A N/APZ-32 06/19/14 WATER 4800 ND ND N/A N/A N/A N/A N/AGWP-4 06/16/14 WATER 1835 N/A N/A N/A N/A N/A N/A N/AGWP-4(2) 06/16/14 WATER 2650 N/A N/A N/A N/A N/A N/A N/A(1) pCi/L(2) Vendor Analysis16 ATTACHMENT 8RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS(01114 -12/14)2nd Quarter 2014Sample H.3-1 Gamma -Emitting Sr- TRAp'Sample Date Media Particulates'")
89/901 Fe-55"' Ni.63 Alpha Pu.241m1GWP-5A 06/16/14 WATER < 1260 N/A N/A N/A N/A N/A N/A N/AGWP-5A 21 06/16/14 WATER <1950 N/A N/A N/A N/A N/A N/A N/AGWP-7 06/17/14 WATER <1260 N/A N/A N/A N/A N/A N/A N/AGWP-7(21 06/17/14 WATER <1950 N/A N/A N/A N/A N/A N/A N/AGWP-8 06/17/14 WATER <1260 N/A N/A N/A N/A N/A N/A N/AGWP-8(2' 06/17/14 WATER <1950 N/A N/A N/A N/A N/A N/A N/AGWP-9 06/16/14 WATER <1260 N/A N/A N/A N/A N/A N/A N/AGWP.9(2) 06/16/14 WATER <1940 N/A N/A N/A N/A N/A N/A N/AGWP-13 06/18/2014 WATER <1260 N/A N/A N/A N/A N/A N/A N/AGWP-13 (2) 06/18/2014 WATER <1950 N/A N/A N/A N/A N/A N/A N/AGWP-14 06/18/2014 WATER <1260 N/A N/A N/A N/A N/A N/A N/AGWP-14 (2) 06/18/2014 WATER <1950 N/A N/A N/A N/A N/A N/A N/AGWP-15 06/18/2014 WATER <1260 N/A N/A N/A N/A N/A N/A N/AGWP-15 (2) 06/18/2014 WATER <1970 N/A N/A N/A N/A N/A N/A N/AGWP-16 06/18/2014 WATER <1260 N/A N/A N/A N/A N/A N/A N/AGWP-16 (2) 06/18/2014 WATER <1940 N/A N/A N/A N/A N/A N/A N/AGWP-17 06/17/2014 WATER <1260 N/A N/A N/A N/A N/A N/A N/AGWP-17 (2) 06/17/2014 WATER <1950 N/A N/A N/A N/A N/A N/A N/AGWP-18 04/03/2014 WATER 3857 N/A N/A N/A N/A N/A N/A N/AGWP-18 (2) 04/03/2014 WATER 4820 N/A N/A N/A N/A N/A N/A N/AGWP-18 04/17/2014 WATER 4270 N/A N/A N/A N/A N/A N/A N/AGWP-18 04/24/2014 WATER <1345 N/A N/A N/A N/A N/A N/A N/AGWP-18 05/01/2014 WATER 6065 N/A N/A N/A N/A N/A N/A N/AGWP-18 (2) 05/01/2014 WATER 4230 N/A N/A N/A N/A N/A N/A N/AGWP-18 05/02/2014 WATER 6578 N/A N/A N/A N/A N/A N/A N/AGWP-18 (2) 05/02/2014 WATER 3680 N/A N/A N/A N/A N/A N/A N/AGWP-18 05/08/2014 WATER 3674 N/A N/A N/A N/A N/A N/A N/AGWP-18 05/15/2014 WATER 5000 N/A N/A N/A N/A N/A N/A N/AGWP-18 05/22/2014 WATER 3674 N/A N/A N/A N/A N/A N/A N/AGWP-18 05/29/2014 WATER 3957 N/A N/A N/A N/A N/A N/A N/AGWP-18 06/03/2014 WATER 3413 N/A N/A N/A N/A N/A N/A N/AGWP-18 06/12/2014 WATER 3543 N/A N/A N/A N/A N/A N/A N/AGWP-18 06/17/2014 WATER 1804 N/A N/A N/A N/A N/A N/A N/AGWP-18 (2) 06/17/2014 WATER 3790 N/A N/A N/A N/A N/A N/A N/AGWP-18 06/26/2014 WATER 4182 N/A N/A N/A N/A N/A N/A N/ABTW--1 2) 7/02/14 WATER <1670 ND ND N/A N/A N/A N/A N/ABTW-2(2) 7/03/14 WATER <1680 ND ND N/A N/A N/A N/A N/ABTW-4(2) 7/02/14 WATER <1710 ND ND N/A N/A N/A N/A N/ATTW-1 Well abandoned in place, pending decommissioning TTv-2(2) 7/02/14 WATER <1690 ND I ND I N/A I I /A N/A N/A(1) pCi/L(2) Vendor Analysis17 ATTACHMENT 8RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS(01/14 -12/14)I I I I I ITTW-3(2) 7/02/14 WATER 1 <1690 1 ND I ND I N/A I N/A I N/AI N/A I N/ATTVV-4 Well abandoned in place, pending decommissioning TTW .5(2)7/02/14 WATER 1 <1680 1ND I ND I N/A I N/A I N/A I N/A I N/A(1) pCi/L(2) Vendor Analysis18 ATTACHMENT 8RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS(01/14 -12/14)3rd Quarter 2014Sample H-3(1) Gamma -Emitting 1_1310) Sr- 1AlphaSample Date Media Particulates()1 89/90(1)
Fe'55R 1 AlU(p) Pu'241("GWP-3 09/21/14 WATER <1292 N/A N/A N/A N/A N/A N/A N/AGWP-4 09/21/14 WATER <1292 N/A N/A N/A N/A N/A N/A N/AGWP-5A 09/21/14 WATER < 1292 N/A N/A N/A N/A N/A N/A N/AGWP-7 09/21/14 WATER < 1292 N/A N/A N/A N/A N/A N/A N/AGWP-8 09/21/14 WATER < 1292 N/A N/A N/A N/A N/A N/A N/AGWP-9 09/21/14 WATER < 1292 N/A N/A N/A N/A N/A N/A N/AGWP-13 10/06/14 WATER <1313 N/A N/A N/A N/A N/A N/A N/AGWP-14 10/06/14 WATER <1313 N/A N/A N/A N/A N/A N/A N/AGWP-15 10/06/14 WATER <1313 N/A N/A N/A N/A N/A N/A N/AGWP-16 10/06/14 WATER <1313 N/A N/A N/A N/A N/A N/A N/AGWP-17 10/06/14 WATER <1313 N/A N/A N/A N/A N/A N/A N/AGWP-18 07/03/14 WATER 2870 N/A N/A N/A N/A N/A N/A N/AGWP-18 07/09/14 WATER 4174 N/A N/A N/A N/A N/A N/A N/AGWP-18 07/17/14 WATER 3730 N/A N/A N/A N/A N/A N/A N/AGWP-18 07/24/14 WATER 1704 N/A N/A N/A N/A N/A N/A N/AGWP-18 07/31/14 WATER 3274 N/A N/A N/A N/A N/A N/A N/AGWP-18 08/07/14 WATER <1201 N/A N/A N/A N/A N/A N/A N/AGWP-18 08/14/14 WATER 2060 N/A N/A N/A N/A N/A N/A N/AGWP-18 08/20/14 WATER 2140 N/A N/A N/A N/A N/A N/A N/ABTW-1(2) 09/24/14 WATER <1920 ND ND N/A N/A N/A N/A N/ABTW-2(2) 09/24/14 WATER <1920 ND ND N/A N/A N/A N/A N/ABTW-4(2) 09/24/14 WATER <1910 ND ND N/A N/A N/A N/A N/ATTW-1 Well abandoned in place, pending decommissioning TTW.2(2) 09/24/14 WATER <1920 NND D ]N/A N/A N/A J N/A N/ATTW_3(2) 09/24/14 WATER <1910 ND ND I N/A N/A N/A N/A N/ATTW-4 Well abandoned in place, pending decommissioning TTW-5(2) 09/24/14 WATER <1920 ND ND N/A N/A N/A N/A N/AGWP-6 06/20/14 WATER 50,833 N/A N/A N/A N/A N/A N/A N/AGWP-6 6/27/14 WATER 49,333 N/A N/A N/A N/A N/A N/A N/A(1) pCi/L(2) Vendor Analysis19 ATTACHMENT 8RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS(01/14 -12/14)3rd Quarter 2014Sampl 13li -EmittingAlpha Sample Date Sample H-3(1 Gamma-Emitting 1131( Sr.89/90(
- 1) Fe-55(1) 1 TRU(') Pu.2411)SapeMedia Particulates' 1 -TRl1GWP-6 07/03/14 WATER 75443 N/A N/A N/A N/A N/A N/A N/AGWP-6 07/09/14 WATER 46900 N/A N/A N/A N/A N/A N/A N/AGWP-6 07/17/14 WATER 57252 N/A N/A N/A N/A N/A N/A N/AGWP-6 07/24/14 WATER 51030 N/A N/A N/A N/A N/A N/A N/AGWP-6 07/31/14 WATER 43948 N/A N/A N/A N/A N/A N/A N/AGWP-6 08/07/14 WATER 41987 N/A N/A N/A N/A N/A N/A N/AGWP-6 08/14/14 WATER 41696 N/A N/A N/A N/A N/A N/A N/AGWP-6 08/20/14 WATER 33870 N/A N/A N/A N/A N/A N/A N/AGWP-6 08/27/14 WATER 38130 N/A N/A N/A N/A N/A N/A N/AGWP-6 09/03/14 WATER 25535 N/A N/A N/A N/A N/A N/A N/AGWP-6 09/11/14 WATER 52717 N/A N/A N/A N/A N/A N/A N/AGWP-6 09/18/14 WATER 29835 N/A N/A N/A N/A N/A N/A N/AGWP-6 09/20/14 WATER 19109 N/A N/A N/A N/A N/A N/A N/AGWP-6 (2) 09/20/14 WATER 18000 ND ND N/A N/A N/A N/A N/AU-1 Intake Yard Drains 08/06/14 WATER <1427 N/A N/A N/A N/A N/A N/A N/AU-2 Intake Yard drains 08/06/14 WATER <1427 N/A N/A N/A N/A N/A N/A N/ADischarge Canal Yard 08/06/14 WATER <1427 N/A N/A N/A N/A N/A N/A N/ADrainsSubsurface drains 08/06/14 WATER <1427 N/A N/A N/A N/A N/A N/A N/AU-1 Mat Sump South 08/28/14 WATER <1227 N/A N/A N/A N/A N/A N/A N/AU-1 Mat Sump east 08/28/14 WATER <1227 N/A N/A N/A N/A N/A N/A N/AU-1 AB/FB GWMS 08/28/14 WATER <1227 N/A N/A N/A N/A N/A N/A N/AU-1 AB/FB GWMS 09/15/14 WATER <1320 N/A N/A N/A N/A N/A N/A N/AU-1 AB/FB GWMS 09/18/14 WATER <1300 N/A N/A N/A N/A N/A N/A N/AU-1 AB/FB GWMS 09/19/14 WATER <1314 N/A N/A N/A N/A N/A N/A N/AU-2 Inside Mat Sump 08/28/14 WATER <1227 N/A N/A N/A N/A N/A N/A N/AU-2 Outside Mat Sump 08/28/14 WATER <1227 ND N/A N/A N/A N/A N/A N/AU-2 AB/FB GWMS 08/28/14 WATER <1227 N/A N/A N/A N/A N/A N/A N/AU-2 AB/FB GWMS 09/15/14 WATER <1320 N/A N/A N/A N/A N/A N/A N/AU-2 AB/FB GWMS 09/18/14 WATER <1300 N/A N/A N/A N/A N/A N/A N/AU-2 AB/FB GWMS 09/19/14 WATER <1314 N/A N/A N/A N/A N/A N/A N/APZ-1 09/21/14 WATER Insufficient volume to samplePZ-2 09/21/14 WATER Insufficient volume to samplePZ-3 08/27/14 WATER 4826 N/A N/A N/A N/A N/A N/A N/APZ-3 09/03/14 WATER 5252 N/A N/A N/A N/A N/A N/A N/APZ-3 09/11/14 WATER 6513 N/A N/A N/A N/A N/A N/A N/APZ-3 09/12/14 WATER 6230 N/A N/A N/A N/A N/A N/A N/APZ-3 09/18/14 WATER 6313 N/A N/A N/A N/A N/A N/A N/APZ-3 09/20/14 WATER 5891 ND ND N/A N/A N/A N/A N/APZ-3 (2) 09/20/14 WATER 5580 N/A N/A N/A N/A N/A N/A N/AGWP-5A 09/17/14 WATER <1331 N/A N/A N/A N/A N/A N/A N/A(1) pCi/L(2) Vendor Analysis20 ATTACHMENT 8RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS(01114 -12114)3rd Quarter 2014Sample Gamma -Emitting
'31(1 Sr- AlphaSample Date Media H-.( Particulates(
1-131 89,90(1)
Fe-55(1) Ni-631) TRUAlh Pu-241(lISFSI WELL #4c2) 07/17/14 WATER e1400 ND ND ND ND ND ND NDISFS1 WELL #4(2) 07/17/14 WATER e1390 ND ND ND ND ND ND ND(1) pCi/L(2) Vendor Analysis21 ATTACHMENT 8RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS(01/14 -12114)41h Quarter 2014Gamma -Sample Date Sample H-3V Emitting 1-131 Sr-89/90 Fe-55 Ni-63 TRU Pu-241Particulates GWP-3 12/18/14 WATER <1224 N/A N/A N/A N/A N/A N/A N/AGWP-4 12/18/14 WATER <1224 N/A N/A N/A N/A N/A N/A N/AGWP-5A 12/18/14 WATER <1224 N/A N/A N/A N/A N/A N/A N/AGWP-7 12/18/14 WATER <1224 N/A N/A N/A N/A N/A N/A N/AGWP-8 12/18/14 WATER <1224 N/A N/A N/A N/A N/A N/A N/AGWP-9 12/18/14 WATER <1224 N/A N/A N/A N/A N/A N/A N/AGWP-13 12/18/14 WATER <1224 N/A N/A N/A N/A N/A N/A N/AGWP-14 12/18/14 WATER < 1313 N/A N/A N/A N/A N/A N/A N/AGWP-15 01/07/15 WATER < 1290 N/A N/A N/A N/A N/A N/A N/AGWP-16 01/07/15 WATER < 1290 N/A N/A N/A N/A N/A N/A N/AGWP-17 01/07/15 WATER < 1290 N/A N/A N/A N/A N/A N/A N/AGWP-18 10/06/14 WATER <1313 N/A N/A N/A N/A N/A N/A N/AGWP-18 01/07/15 WATER <1290 N/A N/A N/A N/A N/A N/A N/AGWP-19 12/16/14 WATER 2610 N/A N/A N/A N/A N/A N/A N/AGWP-20 11/15/14 WATER 2610 N/A N/A N/A N/A N/A N/A N/ABTW-1 (2) 12/03/14 WATER <1260 IND ND N/A N/A N/A N/A N/ABTW-2 (2) 12/11/14 WATER <1270 ND ND N/A N/A N/A N/A N/ABTW-4 (2) 12/03/14 WATER <1280 ND ND N/A N/A N/A N/A N/ATTW-2 (2) 12/03/14 WATER <1280 ND ND N/A N/A N/A N/A N/ATTW-3 (2) 12/03/14 WATER <1270 ND ND N/A N/A N/A N/A N/ATTW-5 (2) 12/03/14 WATER <1270 ND ND N/A N/A N/A N/A N/ATTW-1 12/16/14 WATER Insufficient volume to sampleTTW-412/16/14 WATERInsufficient volume to sampleGWP-6 100214 WATER 16052 N/A N/A N/A N/A N/A N/A10/08/14 WATER 5565 N/A N/A N/A N/A N/A N/A10/15/14 WATER 2252 N/A N/A N/A N/A N/A N/A10/22/14 WATER 4196 N/A N/A N/A N/A N/A N/A10/29/14 WATER 4183 N/A N/A N/A N/A N/A N/AGW-6 11/05/14 WATER 4174 N/A N/A N/A N/A N/A N/A11/12/14 WATER 4065 N/A N/A N/A N/A N/A N/A11/19/14 WATER 2652 N/A N/A N/A N/A N/A N/AI(1) pCi/L(2) Vendor Analysis22 ATTACHMENT 8RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS(01114 -12114)4th Quarter 2014Gamma -AlphSample Date Sample H-3 (1) Emitting 1-131 Sr-89/90 Fe-55 Ni-63 a Pu-241Particulates TRUGWP-6 11/25/14 WATER 1557 N/A N/A N/A N/A N/A N/A N/AGWP-6 12/05/14 WATER 8000 N/A N/A N/A N/A N/A N/A N/AGWP-6 12/11/14 WATER 3478 N/A N/A N/A N/A N/A N/A N/AGWP-6 12/18/14 WATER 6370 N/A N/A N/A N/A N/A N/A N/AGWP-6 12/23/14 WATER 8361 N/A N/A N/A N/A N/A N/A N/AGWP-6 12/30/14 WATER 7457 N/A N/A N/A N/A N/A N/A N/AU-1 Intake Yard 10/28/14 WATER <1510 N/A N/A N/A N/A N/A N/A N/ADrains IU-2 Intake Yard 10/28/14 WATER <1510 N/A N/A N/A N/A N/A N/A N/ADrainsDischarge Canal Yard 10/28/14 WATER <1510 N/A N/A N/A N/A N/A N/A N/ADrainsSub SurfaceDrain 10/28/14 WATER <1510 N/A N/A N/A N/A N/A N/A N/ADrainsU-1 MatUmp Sat 10/16/14 WATER <1345 N/A N/A N/A N/A N/A N/A N/ASump SouthIU-1 MatU-1 Eat 10/16/14 WATER <1345 N/A N/A N/A N/A N/A N/A N/ASump EastU-2 MatU-2 nid 10/16/14 WATER <1345 ND <MDA <MDA <MDA <MDA N/A <MDASump InsideIU-2 Mat Sump 10/16/14 WATER <1345 N/A N/A N/A N/A N/A N/A N/AOutsideU-1 AB/FB 10/16/14 WATER <1345 N/A N/A N/A N/A N/A N/A N/AGWMS _______ _________
U-2GAB/B 10/16/14 WATER <1345 N/A N/A N/A N/A N/A N/A N/AGWMS I___ I__ I__PZ-1 12/18/14 WATER Insufficient volume to samplePZ-2 12/18/14 WATER Insufficient volume to samplePZ-3 10/02/14 WATER 6835 N/A N/A N/A N/A N/A N/A N/APz-3 10/08/14 WATER 5565 N/A N/A N/A N/A N/A N/A N/APz-3 10/15/14 WATER 3587 N/A N/A N/A N/A N/A N/A N/APZ-3 10/22114 WATER 4652 N/A N/A N/A N/A N/A N/A N/A(1) pCi/L(2) Vendor Analysis23 ATTACHMENT 8RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS(01/14 -12/14)4th Quarter 2014PZ-3 10/29/14 WATER 5248 N/A N/A N/A N/A N/A N/A N/APZ-3 11/05/14 WATER 6435 N/A N/A N/A N/A N/A N/A N/APZ-3 11/12/14 WATER 3478 N/A N/A N/A N/A N/A N/A N/APZ-3 11/19/14 WATER 3761 N/A N/A N/A N/A N/A N/A N/APZ-3 11/25/14 WATER 4448 N/A N/A N/A N/A N/A N/A N/APZ-3 12/05/14 WATER 5826 N/A N/A N/A N/A N/A N/A N/APZ-3 12/11/14 WATER 4796 N/A N/A N/A N/A N/A N/A N/APZ-3 12/18/14 WATER 5543 N/A N/A N/A N/A N/A N/A N/APZ-3 12/23/14 WATER 6065 N/A N/A N/A N/A N/A N/A N/APZ-3 12/30/14 WATER 5661 N/A N/A N/A N/A N/A N/A N/A24 ATTACHMENT 9CARBON-14 CALCULATIONS (01/14 -12114)Carbon-14, 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 of C-14 in the atmosphere.
Due to the long half-life of C-14, 5730 years, a significant portion of the C-14 from this testing is still present in theenvironment.
0-14 is also produced in commercial nuclear reactors, but the amounts produced are much less thanthose produced naturally or from weapons testing.In Regulatory Guide 1.21, Revision 2, "Measuring, Evaluating, and Reporting Radioactive Material in Liquid andGaseous Effluents and Solid Waste", the NRC has recommended that U.S. nuclear power plants evaluate whether0-14 is a "principal radionuclide",
and if so, report the amount of C-14 released.
At North Anna, improvements overthe years in fuel performance have resulted in a decrease in the amount and distribution radionuclides released tothe environment in gaseous effluents.
As a result, C-14 has become a "principal radionuclide" for the gaseouseffluent pathway at North Anna, as defined in Regulatory Guide 1.21, Revision
- 2. Because the dose contribution ofC-14 to liquid radioactive waste is a small fraction of the dose compared to other nuclides, evaluation of C-14 inliquid 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 scalingfactor based on power generation.
North Anna utilized methodology in EPRI Report, Estimation of C-14 in NuclearPower Gaseous Effluents.
Based on this document, at full capacity, North Anna would generate and release about32.8 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 30.7 Ci of C-14 produced and released.
North Annaassumed that the fractional release of gaseous C-14 in any quarter and pathway could be approximated by thefraction 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 inPWRs occur primarily as a mix of organic carbon and carbon dioxide released from the waste gas system. C-14 inthe primary coolant is essentially all organic with a large fraction as a gaseous species.
Any time the RCS liquid orgas is exposed to an oxidizing environment, a slow transformation from an organic to an inorganic chemical formcan occur. Various studies documenting measured C-14 releases from PWRs suggest a range of 70% to 95%organic.
North Anna used a value of 70% organic and 30% C02 in its calculations.
25 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 atNorth Anna is estimated to be 1.41 E-1 mrem from the inhalation
- pathway, or 9.39E-03%
TS of the 1500 mrem/yrdose rate limit and 1.32E+0 mrem from the ingestion pathway or 4.40E+00%
TS of the 10CFR50, Appendix I,ALARA design objective of 15 mrem/yr per unit. In both cases the critical organ was determined to be the child'sbone.26 Miscellaneous There was one entry,14-001 , on the Annual Effluent Release Report Log for 2014. Entry 14-001 was todocument that Clarifier Effluent Radiation
- Monitor, 1-LW-RM-1 11 was inoperable for greater than 31consecutive days.27 1&% StationWDominionw Administrative Procedure Title: Offsite Dose Calculation Manual (North Anna)Process / Program Owner: Manager Radiological Protection and Chemistry (North Anna)Procedure Number Revision Numb E ctive DateVPAP-2103N 23 /> On FileRevision SummaryLocation description changed for WSW-23/55
-Radio ,, as re ved.-Attachment 10, Page 2 of 5: Changed location to: 0/Ae, o SE of switchyard, entrance onRt. 700. N",%*,,VApprovals on File DOMINIONVPAP-2103N REVISION 23PAGE 2 OF 87TABLE OF CONTENTSSectionPage1.0 PURPOSE2.0 SCOPE5
53.0 REFERENCES
/COMMITMENT DOCUMENTS
4.0 DEFINITIONS
5.0 RESPONSIBILITIES
6.0 INSTRUCTIONS
6.1 Sampling and Monitoring Criteria6.2 Liquid Radioactive Waste Effluents 6.2.1 Liquid Effluent Concentra 6.2.2 Liquid Monitoring Insrw i6.2.3 Liquid Effluent D LLi t6.2.4 Liquid R-adw Tr t.ent6.2.5 Liquid San1/,,6812121212131618196.3 Gaseous R 6ac) ieWXe Effluents 6.3.1 G o>e uent Dose Rate Limitation 6.3. Gase nitoring Instrumentation
%8 as EEffluent Air Dose Limit31, 133, H-3 & Radionuclides In Particulate Form Effluent Dose Limit6 aseous Radwaste Treatment 6.4 Radioactive Liquid and Gaseous Release Permits6.4.1 Liquid Waste Batch Release Permits6.4.2 Continuous Release Permit6.4.3 Waste Gas Decay Tank (WGDT) Release Permit6.4.4 Reactor Containment Release Permits6.4.5 Miscellaneous Gaseous Release Permit191922252729313131323232 DOMINIONVPAP-2103N REVISION 23PAGE 3 OF 87TABLE OF CONTENTS (continued)
SectionPage6.4.6 Radioactive Liquid and Gaseous Release Controls6.5 Total Dose Limit to Public From Uranium Fuel Cycle Sources6.6 Radiological Environmental Monitoring 6.6.1 Monitoring Program6.6.2 Land Use Census6.6.3 Interlaboratory Comparison Program6.7 Reporting Requirements 6.7.1 Annual Radiological Environmental Operatin t6.7.2 Annual Radioactive Effluent Release R6.7.3 Annual Meteorological Data6.7.4 Changes to the ODCM6.7.5 Groundwater Protection In*i e e 3.1.35]RECORDS323434343637383839424243447.0 DOMINION VPAP-2103N REVISION 23PAGE 4 OF 87TABLE OF CONTENTS (continued)
Section PageATTACHMENTS 1 Radioactive Liquid Effluent Monitoring Instrumentation 452 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 473 Radioactive Liquid Waste Sampling and Analysis Program 494 Radioactive Gaseous Waste Sampling and Analysis Program 525 Gaseous Effluent Dose Factors 566 Radioactive Gaseous Effluent Monitoring Instrumenta 597 Radioactive Gaseous Effluent Monitoring Instrume 5Surveillance Requirements 628 Critical Organ Dose Factors 659 Radiological Environmental Monitoring r 6710 Environmental Sampling Locations 7211 Detection Capabilities for Enviro a pie Analysis 7712 Reporting Levels for Radioa it on ations in Environmental Samples 7913 Meteorological, Liqui d4 se Pathway Analysis 80 DOMINION VPAP-2103N REVISION 23PAGE 5 OF 871.0 PURPOSEThe Offsite Dose CalculationManual (ODCM) establishes requirements for the Radioactive Effluent and Radiological Environmental Monitoring Programs.
Methodology and parameters are provided to calculate offsite doses resulting from radioactive gaseous and liquid effluents, to calculate gaseous and liquid effluent monitoring alarm/trip setpoints, and to conduct theEnvironmental Monitoring Program.
Requirements are established for the AnnualRadiological Environmental Operating Report and the Annual Radioactive Effluent ReleaseReport required by Station Technical Specifications.
Calculation of o oses due toradioactive liquid and gaseous effluents are performed to assure tha." Concentration of radioactive liquid effluents to the unrestr/
we limited to tentimes the effluent concentration values of 10 CFR 20,1 B, B le 2, Column 2, forradionuclides other than dissolved or entrained nobt as 2,4 aCi/ml for dissolved orentrained noble gases.* Exposure to the maximum exposed member bl*ii the unrestricted area fromradioactive liquid effluents will not res dos er" than the liquid dose limitsof 10 CFR 50, Appendix I* Dose rate at and beyond the site ry radioactive gaseous effluents will be limitedto:Noble gases -less th or al t dose rate of 500 mremiyr to the total body and lessthan or equal to a f mrem/yr to the skin* 1131, 1133, and ar11 ra"onuclides in particulate form with half-lives greater than 8days -less th-- al to a dose rate of 1500 mrem/yr to any organ* Exposure yradlctive gaseous effluents to the maximum exposed member of the publicin th str ea will not result in doses greater than the gaseous dose limits of10 Ig ,)pendix I, and" Exposu real individual will not exceed 40 CFR 190 dose limits2.0 SCOPEThis procedure applies to the Radioactive Effluent and Environmental Monitoring Programs atNorth Anna Power Station.
DOMINION VPAP-2103N REVISION 23PAGE 6 OF 8
73.0 REFERENCES
/COMMITMENT DOCUMENTS 3.1 References
-3.1.1 10 CFR 20, Standards for Protection Against Radiation 3.1.2 10 CFR 50, Domestic Licensing of Production and Utilization Facilities 3.1.3 40 CFR 190, Environmental Radiation Protection Standards for Nuclear PowerOperations 3.1.4 TID-14844, Calculation of Distance Factors for Power and Test Reactor Sites3.1.5 Regulatory Guide 1.21, Measuring, Evaluating, and Reporti activity in SolidWastes and Releases of Radioactive Materials in Liquid a aseo ffluents fromLight-Water-Cooled Nuclear Power Plants, Rev. 1, U.iR ,n,1743.1.6 Regulatory Guide 1.109, Calculation of Annual Dos n F "Routine Releasesof Reactor Effluents for the Purpose of Evaluata ith 10 CFR 50,Appendix I, Rev. 1, U.S. NRC, October 197sp ercraspr3.1.7 Regulatory Guide 1.111, Methods for E atin pheric Transport andDispersion of Gaseous Effluents in R ne eas from Light-Water-Cooled
- Reactors, Rev. 1, U.S. NRC, July3.1.8 North Anna Technical Specifica i3.1.9 North Anna Technical Re e ual (TRM)3.1.10 NUREG-0324, XOQ or the Meteorological Evaluation of RoutineEffluent Releases uc a wer Stations, U.S. NRC, Septeimber 19773.1.11 NUREG/CR-1 s ual for the LADTAP II Program, U.S. NRC,May, 19803.1.12 TID-45 -50564, Rev. 1, Concentration Factors of Chemical Elements inEdible Aq anisms, October, 19723.1.13 8 ol. 2, July 1973, Numerical Guides for Design Objectives and Limitingr Operation to Meet the Criterion "As Low As Practicable" Forotive Material in Light Water-Cooled Nuclear Power Reactor Effluents 3.1.14 -0597, User's Guide to GASPAR Code, U.S. NRC, June, 19803.1.15 Radiological Assessment Branch Technical Position on Environmental Monitoring,
- November, 1979, Rev. 13.1.16 NUREG-0133, Preparation of Radiological Effluent Technical Specifications forNuclear Power Stations,
- October, 19783.1.17 NUREG-0543, February 1980, Methods for Demonstrating LWR Compliance Withthe EPA Uranium Fuel Cycle Standard (40 CFR Part 190)3.1.18 NUREG-0472, Standard Radiological Effluent Technical Specifications forPressurized Water Reactors, Proposed Rev. 3, March 1982 DOMINION3.1.193.1.203.1.213.1.22VPAP-2103N REVISION 23PAGE 7 OF 87Environmental Measurements Laboratory, DOE HASL 300 ManualNRC-,Generic Letter 89-01, Implementation of Programmatic Controls forRadiological Effluent Technical Specifications (RETS) in the Administrative ControlsSection of the Technical Specifications and the Relocation of Procedural Details ofRETS to the Offsite Dose Calculation Manual or to the Process Control ProgramNorth Anna UFSARNuclear Reactor Environmental Radiation Monitoring Quality Control Manual,IWL-0032-361 3.1.23 North Anna Circulating Water System Modifications
- a. DC-85-37-1 Unit 1b. DC-85-38-2 Unit 23.1.24 Plant Issue (Deviation)
N-1994-1137, Improp mergency TLDs3.1.25 ET N-05-0025, Justification for removin, S M- 8 from service when not inuse3.1.26 VPAP-2802, Notifications and Re3.1.27 0-PT-75.21, 1-SW-RM-108 Flo, 3.1.28 SAA001092, Non-SA SO) ect' s4 Review 93-1, Recommendation 33.1.29 NEI 07-07, Industry o
Initiative
-Final Guidance Document3.1.30 CA086406, Land C su suits3.1.31 Quality Assu it ort Number 91-03, Observation 08N3.1.32 Quality Asan u eport Number 92-03, Observation 02N3.1.33 Quality r Audit Report Number 92-03, Observation 04NS (Item 2)3.1.34 Plan -ue( viation)
N-1997-0926, Annual Radiological Effluent Release Report3.1.3 s icensing Commitment)
N-2006-4026-R15, Groundwater Monitoring 1 Ian3.1.36 S 93-1, Diagnosis and Mitigation of RCS Leakage including SGTR3.2 Commitment Documents None DOMINION VPAP-2103N REVISION 23PAGE 8 OF 874.0 DEFINITIONS 4.1 Channel Calibration A channel calibration shall be the adjustment, as necessary, of the channel output such that itresponds within the necessary range and accuracy to known values of the parameter that thechannel monitors.
The channel calibration shall encompass all devices in the channel requiredfor channel operability.
The channel calibration may be performed by means of any series ofsequential, overlapping, or total channel steps.4.2 Channel CheckA qualitative assessment, by observation, of channel behavior ng rat' .Thisassessment
- includes, where possible, comparison of the ch I i nd status withother indications or status derived from independent ins annels measuring thesame parameter.
4.3 Channel Operational Test < § 9A Channel Operational Test (COT) shall 1ýt-3,ti f a simulated or actual signal intothe channel as close to the sensor as h ik OPERABILITY of all devices in thechannel required for channel OPE IT ff COT shall include adjustments, asnecessary, of the required alar ,,,e trip setpoints required for channelOPERABILITY such that s in a ithin the necessary range and accuracy.
The COT maybe performed by means o r "e sequential, overlapping, or total channel steps.4.4 Critical Organ <,q, /ial,That organ, whic determined to be the maximum exposed organ based on an effluentpathway anad s, theby ensuring the dose and dose rate limitations to any organ will not beexcee To e ations to the critical organ will be evaluated in accordance withTechrn ec, ications 5.5.4 dose rate limits specified for any organ to check that these limitshave not exceeded.
4.5 Dose Equivalent 1-131That concentration of 1131 (gCi/cc) that alone would produce the same thyroid dose as thequantity and isotopic mixture of 1131, 1132, 1133, 1134, and 1135 actually present.
Thyroid doseconversion factors for this calculation are listed in Table III of TID- 14844, Calculation ofDistance Factors for Power and Test Reactor Sites. Thyroid dose conversion factors from NRCRegulatory Guide 1.109, Revision 1, may be used.
DOMINION VPAP-2103N REVISION 23PAGE 9 OF 874.6 Frequency Notations NOTE: Frequencies are allowed a maximum extension of 25 percent.NOTATION FREQUENCY D -Daily At least once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />sW -Weekly At least once per 7 daysM -Monthly At least once per 31 dayQ -Quarterly At least once per 92SA -Semi-annually At least once pe 4 ysR -Refueling At least oncS/U -Start-up Prior to h reahrt-up P- Prior to release Co rete o each releaseN.A. -Not applicable icaDR -During the release a ce during each release4.7 Gaseous Radwaste Treatment S ,A system that reduces
$/ySp uents by collecting primary coolant systemoffgases from the primary e an roviding delay or holdup to reduce total radioactivity prior to release to the envil 1tI system comprises the waste gas decay tanks,regenerative heat e ng as charcoal
- filters, process vent blowers, waste gas surgetanks, and waste s agm compressor.
4.8 General No nclaX= 951Z n at a point at a given instant (curies per cubic meter)D =6(o t : quantity of deposited radioactive material per unit area (curies per squaremeter)Q = Source strength (instantaneous; grams, curies)= Emission rate (continuous; grams per second, curies per second)= Emission rate (continuous line source; grams per second per meter)4.9 Lower Limit of Detection (LLD)The smallest concentration of radioactive material in a sample that will yield a net count (abovesystem background) that can be detected with 95 percent probability with only five percentprobability of falsely concluding that a blank observation represents a "real" signal.
DOMINION VPAP-2103N REVISION 23PAGE 10 OF 874.10 Members of the PublicIndividuals who, by virtue of their occupational status, have no formal association with theStation.
This category includes non-employees of Dominion who are permitted to use portionsof the site for recreational, occupational, or other purposes not associated with Stationfunctions.
This category does not include non-employees such as vending machine servicemen or postal workers who, as part of their formal job function, occasionally enter an area that iscontrolled by Dominion to protect individuals from exposure to radiation and radioactive materials.
4.11 Operable
-Operability A system, subsystem, train, component, or device is operabl ty when it iscapable of performing its specified functions and all nec en instrumentation,
- controls, normal and emergency electrical power sou coo seal water, lubrication orother auxiliary equipment that are required for th ste , u stem, train, component, ordevice to perform its functions are also capabl 0 their related support functions.
4.12 Purge -PurgingControlled discharge of air or gas f ent to maintain temperature,
- pressure, humidity, concentration, or other er ition, so that replacement air or gas is required.
to purify the confinement.
4.13 Rated Thermal PowTotal reactor core fer e to reactor coolant (i.e., North Anna -2940 MWt).4.14 Site BoundaryThe line o Dominion does not own, lease, or otherwise control the land.4.15 A qualitat sessment of channel response when a channel sensor is exposed to radiation.
This applies to installed radiation monitoring systems.
For MGPI monitors, a source check isthe verification of proper computer response to continuous operational checks on the detectorand the electronics.
4.16 Special ReportA report to NRC to comply with Subsections 6.2, 6.3, or 6.5 of this procedure.
Also refer toVPAP-2802, Notifications and Reports.
DOMINION VPAP-2103N REVISION 23PAGE 11 OF 874.17 Thermal PowerTotal reactor core heat transfer rate to the reactor coolant.4.18 Unrestricted AreaAny area at or beyond the site boundary, access to which is neither limited nor controlled byDominion for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the site boundary used for residential quarters or for industrial, commercial, institutional and/or recreational purposes.
4.19 Ventilation Exhaust Treatment SystemA system that reduces gaseous radioiodine or radioactive mat i , , form ineffluents by passing ventilation or vent exhaust gases throug _ oa sorbers and HighEfficiency Particulate Air (HEPA) filters to remove io ulates from a gaseousexhaust stream prior to release to the environment c yste is not considered to have anyeffect on noble gas effluents).
Engineered Safe e ýVe atmospheric cleanup systemsare not Ventilation Exhaust Treatment Sys c.5.0 RESPONSIBILITIES 5.1 Manager Radiological Protect*
a eft_.l stryThe Manager Radiological, ecti nd Chemistry is responsible for:5.1.1 Establishing a is rocedures for surveying,
- sampling, and monitoring radioactiv e s a e environment.
5.1.2 Surveyi g, and analyzing plant effluents and environmental monitoring, anddoc ntlng ese activities.
5.1." g plant effluent trends and recommending actions to correct adverse trends.5.1.4 P ig Effluent and Environmental Monitoring Program records.5.2 Manager Nuclear Operations The Manager Nuclear Operations is responsible for requesting
- samples, analyses, andauthorization to release effluents.
DOMINIONVPAP-2103N REVISION 23PAGE 12 OF 876.0 INSTRUCTIONS NOTE: Meteorological, liquid, and gaseous pathway analyses are presented inMeteorological, Liquid, and Gaseous Pathway Analysis (Attachment 13).6.1 Sampling and Monitoring Criteria6.1.1 Surveys,
- sampling, and analyses shall use instruments calibrated for the type andrange of radiation monitored and the type of discharge monitored.
6.1.2 Installed monitoring systems shall be calibrated for the typ nd ran of radiation orparameter monitored.
6.1.3 A sufficient number of survey points shall be use r le en to adequately assess the status of the discharge monitored.
6.1.4 Samples shall be representative of the v m a of discharge monitored.
6.1.5 Surveys,
- sampling, analyses, and to rtds shall be accurately and legiblydocumented, and sufficiently de meaning and intent of the records areclear.6.1.6 Surveys,
- analyses, a 0 ring records shall be reviewed for trends, completeness, and accuracy.
iquid Radioactiv as E ts6.2.1 Liquid Concentration Limitations
- a. I id e icentrations discharged from the Station shall not exceed the}nts:radionuclides (other than dissolved or entrained noble gases), liquid effluentoncentrations released to unrestricted areas shall not exceed ten times theeffluent concentration values specified in 10 CFR 20, Appendix B, Table 2,Column 2.2. For dissolved or entrained noble gases, concentrations shall not exceed2E-4 laCi/mld.
- b. If the concentration of liquid effluent exceeds the limits in Step 6.2.1 .a., promptlyreduce concentrations to within limits.6.2 1 DOMINION VPAP-2103N REVISION 23PAGE 13 OF 87c. Daily concentrations of radioactive materials in liquid waste released tounrestricted areas shall meet the following:
Volume of Waste Discharged
+ Volume of Dilution WaterVolume of Waste Discharged x , _.where:gCi/m-i = the concentration of nuclide i in the li ef e argeACWi = ten times the effluent concentratio u u tricted areas ofnuclide i, expressed as gCi/ml , Appendix B, Table 2,Column 2 for radionuclides an n e gases, and 2E-4 jCi/ml fordissolved or entrainedno gay e s6.2.2 Liquid Monitoring Instrumenta
\a. Radioactive Liquid Effiuen'o nstrumentation Radioactive liquid efflu .ori nstrumentation channels shown onRadioactive Liquid ue toring Instrumentation (Attachment
- 1) shall beoperable with the ar setpoints set to ensure that Step 6.2.1 .a. limits are notexceeded.
- 1. Ala rtrip-tpo' of these channels shall be determined and adjusted inai eri. with Step 6.2.2.d.,
Setpoint Calculation.
f ",a ra'active liquid effluent monitoring instrumentation channel alarm/trip s is less conservative than required by Step 6.2.2.a.,
perform one of thellowing:-Promptly suspend release of radioactive liquid effluents monitored by theaffected channel* Declare the channel inoperable
-Change the setpoint to an acceptable, conservative value DOMINION VPAP-2103N REVISION 23PAGE 14 OF 87b. Radioactive Liquid Effluent Monitoring Instrumentation Operability Each radioactive liquid effluent monitoring instrumentation channel shall bedemonstrated operable by performing a Channel Check, Source Check, ChannelCalibration, and Channel Operational Test at the frequencies shown in Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements (Attachment 2).1. If the number of operable channels is less than the minimum required by thetables in Radioactive Liquid Effluent Monitoring Inst on (Attachment
- 1) perform the action shown in those tables.2. Attempt to return the instruments to operable tuithi days. Ifunsuccessful and the channel is required t c ,en explain in the nextAnnual Radioactive Effluent Release th inoperability was notcorrected in a timely manner.c. Applicable MonitorsLiquid effluent monitors for iare:
DOMINION VPAP-2103N REVISION 23PAGE 15 OF 87d. Setpoint Calculation NOTE: This methodology does not preclude use of more conservative setpoints.
- 1. Maximum setpoint values shall be calculated by:CFDs -(2)FEwhere:S =the setpoint, in pCi/mi, of the radioaciiy i srn theradioactivity concentration in the efflu e r to dilutionFD = dhepiu t ,io n w ater/flow r the raiact"'
hC = the effluent concentration limit sed to implement 10 CFR 20 for the Station, inFE = maximum design pathwa u n ateFD = dilution water flow rate d, .D = FE + (218,000 n circ. pumps in service)2. Each of the condense
' ng ter channels (e.g., SW-130, SW-230)monitors the efflu (s ice er, including component cooling servicewater, circula, an quid radwaste) in the circulating water discharge tunnel bey r t ast nt of possible radioactive material addition.
Nodilutio s d this pathway.
Therefore,..Equation (2) becomes:S =C (3)The for Station monitors used to implement 10 CFR 20 for the sitethe effluent concentration limit.addition, for added conservatism, setpoints shall be calculated for the liquidradwaste effluent line LW- 111 and the Service Water System effluent lineSW-108.
DOMINIONVPAP-2103N REVISION 23PAGE 16 OF 874. For the liquid radwaste effluent line, Equation (2) becomes:S CFDKLWFEwhere:KLW = The fraction of the effluent concentration 10 CFR 20 for the site, attributable to theline pathway <5. For the Service Water System effluent line, E onCF S Wwhere:Ksw = The fraction oJ nt concentration 10 CFR theý n, attributable toline p I a6. The sum K, K 1i, 11 not be greater than 1.0.(4)to implement vaste effluentes:(5)limit, used to implement the service water effluent6.2.3 LiquidAtýr 31 days, perform the dose calculations in Step 6.2.3.c.
to ensurecommitment to the maximum exposed member of the public fromerials in liquid releases (from each reactor unit) to unrestricted areasI' During any calendar quarter:* Less than or equal to 1.5 mrem to the total body" Less than or equal to 5 mrem to the critical organ2. During any calendar year:" Less than or equal to 3 mrem to the total body" Less than or equal to 10 mrem to the critical organ DOMINIONVPAP-2103N REVISION 23PAGE 17 OF 87b. ActionIf the calculated dose from release of radioactive materials in liquid effluents exceeds any of the above limits, prepare and submit to the NRC, within 30 days, aspecial report in accordance with VPAP-2802, Notifications and Reports, thatidentifies causes for exceeding limits and defines corrective actions taken to reducereleases of radioactive materials in liquid effluents to ensure that subsequent releases will be in compliance with the above limits.c. Dose Contribution Calculations Dose contribution shall be calculated for all radionu(effluents released to unrestricted areas based on: <W ere:Subscripts
= i, refers to in vi utiuclide in liquid(6)D = thecuiliquidre'nt to the total body or critical organ from thet, in mremBi = DoseValutt'ictors (mrem/Ci) for each age group of interest.
ýovided in code file for North Anna Power Stationtical organ calculations Qi -'activity for the considered period and the ith nuclideQi = t x Ci x Waste Flow(7)= the period for which Ci and F are averaged for all liquid releases, inhoursCi = the average concentration of radionuclide, i, in undiluted liquid effluentduring the period, t, from any liquid releases, in laCi/ml DOMINION VPAP-2103N REVISION 23PAGE 18 OF 87d. Quarterly Composite AnalysesFor radionuclides not determined in each batch or weekly composite, dosecontribution to current monthly or calendar quarter cumulative summation may beapproximated by assuming an average monthly concentration based on previousmonthly or quarterly composite analyses.
- However, for reporting
- purposes, calculated dose contribution shall be based on the actual composite analyses.
6.2.4 Liquid Radwaste Treatment Historical data pertaining to the volumes and radioactivity ofluents releasedin connection with specific station functions, such as mai t \ce o efuelingoutages, shall be used in projections as appropriate.
- a. Requirement
- 1. The Liquid Radwaste Treatment Sy/p all b sed to reduce the radioactive materials in liquid waste prior t n projected dose due to liquideffluent, from each reactor it res ed areas would exceed 0.06 mremto total body or 0.2 mrem t t organ in a 31-day period.2. Doses due to liqu s projected at least once per 31 days.b. Action i"If radioactive l ste ldischarged without treatment and in excess of theabove 1i q to the NRC, within 30 days, a special report inaccor a VP -2802, Notifications and Reports, that includes thefollowne nation of why liquid radwaste was being discharged without treatment, entification of any inoperable equipment or sub-system, and the reason for theoperability.
- 2. Actions taken to restore inoperable equipment to operable status.3. Summary description of actions taken to prevent recurrence.
- c. Projected Total Body Dose Calculation
- 1. Determine DTB, the total body dose from liquid effluents in the previous 31-dayperiod, per Equation (6).
DOMINION VPAP-2103N REVISION 23PAGE 19 OF 872. Estimate R1, the ratio of the estimated volume of liquid effluent releases in thepresent 31-day period to the volume released in the previous 31-day period.3. Estimate F1, the ratio of the estimated liquid effluent radioactivity concentration in the present 31-day period to liquid effluent concentration in the previous 31-day period (jiCi/ml).
- 4. Determine PDTB, the projected total body dose in a 31-day period.PDTB = DTB(RlFl)
(8)d. Projected Critical Organ Dose Calculation
- 71. Determine DO, the critical organ dose from ue in theprevious 31-day period, per Equation (2. Estimate R1 as in Step 6.2.4.c.2.
- 3. Estimate F1 as in Step6.2.4.c.3
- 4. Determine PD, = project 'dose in a 31-day period.
FI1)(9)6.2.5 Liquid SamRadioactiv ast shall be sampled and analyzed according to the samplingand anal's) rements in Radioactive Liquid Waste Sampling and AnalysisPro (At hment 3).6.3 Gase s c'e Waste Effluents 6.3.1 sG Effluent Dose Rate Limitation
- a. Requirement Dose rate due to radioactive materials released in gaseous effluents from the site toareas at and beyond the site boundary shall be limited to:1. The dose rate limit for noble gases shall be < 500 mrem/year to the total bodyand < 3000 mrem/year to the skin.
DOMINION VPAP-2103N REVISION 23PAGE 20 OF 872. The dose rate limit for 131, 1133, for tritium, and for all radioactive materials in-particulate form with half-lives greater than 8 days shall be _< 1500 mrem/year to the critical organ.b. Action1. If dose rates exceed Step 6.3.1 .a. limits, promptly decrease the release rate towithin the above limits.2. Dose rates due to noble gases in gaseous effluents shall determined, continuously, to be within Step 6.3.1 .a. limits.3. Dose rates due to 1131, 1133, tritium, and all radi jclid ticulate formwith half-lives greater than 8 days, in gaseous ts alI be determined tobe within the above limits by mnples and performing analyses in accordance with the sa l1 and a lysis program specified onRadioactive Gaseous Waste Sang sis Program (Attachment 4).0" Kl "i DOMINION VPAP-2103N REVISION 23PAGE 21 OF 87c. Calculations of Gaseous Effluent Dose Rates1. .The dose rate limit for noble gases shall be determined to be within the limit bylimiting the release rate to the lesser of:Y [KivvQivv
+ KjpvQipv]
_ 500mnrem/yr to the total body (10)OR[(Livv + 1.1Mivv)Qivv
+ (Lipv + 1.1Mipv)Qipvj]
3000mrem/yr to thwhere:Subscripts
= vv, refers to vent rele ;sfrome uilding ventilation ventpv, refers to the re. i r, m the process vent;i, refers to ind u di l1'Ngcide Kivv, Kipv = The total o ac or ventilation vents or process ventrelease t missions for each identified noble gasradio , in em/yr per Curie/sec.
Factors are listed inG( ou)Ef ose Factors (Attachment 5)Liv, Lipv -i i factor for ventilation vents or process vente e d edue to beta emissions for each identified noble gasi in mrem/yr per Curie/sec.
Factors are listed inGa us Effluent Dose Factors (Attachment 5)Mi e air dose factor for ventilation vents or process vent releasedue to gamma emissions for each identified noble gasradionuclide, i, in mrad/yr per Curie/sec.
Factors are listed inGaseous Effluent Dose Factors (Attachment 5).The release rate for ventilation vents or process vent of noblegas radionuclide i, in gaseous effluents in Curie/sec (per site)I The unit conversion factor that converts air dose to skin dose,in mrem/mrad DOMINION VPAP-2103N REVISION 23PAGE 22 OF 872. The dose rate limit for 1131, 1133, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days, shall be determined to be within thelimit by restricting the release rate to:S[Pivv!Qivv
+ PipvQipv]
< 1500mrem/yr to the critical organ (12)where:Pivv, Pipv = The critical organ dose factor for ven vents or processvent for 1131, 1133, H3, and all radio ,ides i articulate formwith half-lives greater than 8 da , fo in ation pathway,in mrem/yr per Curie/sec.
F s lis> ,'n GaseousEffluent Dose Factors (Attach 5)Oi=vvipv The release rate for y ati r process vent of 1131,1133, H3, and all ra nd particulate form withhalf-lives an gaseous effluents in Curie/sec (per site)3. All gaseous releases, not tt ti ss vent, are considered ground leveland shall be included in t rn Lation of Qi,,,. *6.3.2 Gaseous Monitoring I u aa. Requirement
- 1. The radioa e fluent monitoring instrumentation channels shown inRadio 0i ffluent Monitoring Instrumentation (Attachment
- 6) shallbe o with arm/trip setpoints set to ensure that Step 6.3.1.a.
noble gasli n* "iot exceeded.
Alarm/trip setpoints of these channels shall beeter *ed and adjusted in accordance with Step 6.3.2.d.a adioactive gaseous effluent monitoring instrumentation channelall be demonstrated operable by Channel Checks, Source Checks, ChannelCalibrations, and Channel Operational Tests at the frequencies shown inRadioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements (Attachment 7).
DOMINION VPAP-2103N REVISION 23PAGE 23 OF 87b. Action1. If a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint is less conservative than required by Step 6.3.2.a.
1, promptly:
" Suspend the release of radioactive gaseous effluents monitored by the affectedchannel and declare the channel inoperable or" Change the setpoint so it is acceptably conservative
- 2. If the number of operable channels is less than the umr nired by tablesin Radioactive Gaseous Effluent Monitoring Instý tý onj ttachment 6)take the action shown in those tables. I3. Return instruments to operable status wit successful, explain inthe next Annual Radioactive Effluen a, e ort why the inoperability wasnot corrected in a timely mannerc. Applicable MonitorsRadioactive gaseous effluent o o hich alarm/trip setpoints shall bedetermined are:Releasef
-'Instrument NumberPro V t 1-GW-RM-178-1 r jector J-SV-RM-121 2--SV-RM-22 1tilation Vent A I-VG-RM-179-1 ilation Vent B 1 -VG-RM- 180-1 DOMINION VPAP-2103N REVISION 23PAGE 24 OF 87d. Setpoint Calculations
- 1. Setpoint calculations foreach monitor listed in Step 6.3.2.c.
shall maintain thisrelationship:
D > Dpv + Dcae + Dvv (13)where:D = Step 6.3.1.a.
dose limits that implement 10 CFR 20 for the Station,mrem/yrPV The noble gas site boundary dose rate fr roce ent gaseouseffluent
- releases, mrem/yrDcae = The noble gas site boundary dose f co nser air ejectorgaseous effluent
- releases, mreDVV = The noble gas site boundar se ro summation ofVentilation Vent A plusgg us e uent releases, mrem/yr2. Setpoint values shall be
,.2E-03m Fm (14)where:m he ease pathway, process vent (pv), ventilation vent (vv) air ejector (cae)S,, = e effluent concentration limit implementing Step 6.3.1.a.for the Station, paCi/mi\ = The release rate limit for pathway m determined frommethodology in Step 6.3.1.c.,
using Xe133 as nuclide to bereleased, gCi/sec12E-03 = CFM per ml/secm = The maximum flow rate for pathway m, CFM DOMINION VPAP-2103N REVISION 23PAGE 25 OF 87NOTE: According to NUREG-0133, the radioactive effluent radiation monitor alarm/trip setpoints should be based on the radioactive noble gases. It is not practicable to applyinstantaneous alarm/trip setpoints to integrating monitors sensitive to radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases.6.3.3 Noble Gas Effluent Air Dose Limita. Requirement
- 1. The air dose in unrestricted areas due to noble gases rele d in gaseouseffluents from each unit at or beyond the site boundw shal. limited to:* During any calendar quarter:
< 5 mrads for ga/a ra ti nd! <10 mradsfor beta radiation
- During any calendar year: < 10 mrads ation and < 20 mradsfor beta radiation
- 2. Cumulative dose contributions no ga or the current calendar quarterand current calendar year s e r\ d in accordance with Step 6.3.3.c.at least once per 31 days. (2b. ActionIf the calculated ai roactive noble gases in gaseous effluents exceedsany of the abo ' pr' " re and submit to the NRC, within 30 days, a specialreport in ac wit AP-2802, Notifications and Reports, that identifies thecaus d c in, e limits and defines corrective actions that have been takento re rses and the proposed corrective actions to be taken to assure thatse e ases will be in compliance with the limits in Step 6.3.3.a.
DOMINION VPAP-2103N REVISION 23PAGE 26 OF 87c. Noble Gas Effluent Air Dose Calculation Gaseous releases, not through the process vent, are considered ground-level andshall be included in the determination of Qivv.The air dose to areas at or beyond the site boundary due to noble gases shall bedetermined by the following:
For gamma radiation:
Dg = 3.17E-08Z[MivvQivv
+ Mi. (15)For beta radiation:
Db = 3.17E-08 I ipvQipv (16)Where:Subscripts
= vv, t leases from the building ventilation vents,i ci air
- torse vent releases from the process vent1, e to individual radionuclide D9 e ai ose for gamma radiation, in mradDb / r dose for beta radiation, in mrade air dose factors for ventilation vents or process vent releasedue to gamma emissions for each identified noble gasradionuclide i, in mrad/yr per Curie/sec.
Factors are listed inGaseous Effluent Dose Factors (Attachment 5)ipv =the air dose factor for ventilation vents or process vent releasedue to beta emissions for each identified noble gasradionuclide i, in mrad/yr per Curie/sec.
Factors are listed inGaseous Effluent Dose Factors (Attachment 5)Qivv, Qipv = the release for ventilation vents or process vent of noble gasradionuclide i, in gaseous effluents for 31 days, quarter, or yearas appropriate in Curies (per site)3.17 E-08 = the inverse of the number of seconds in a year DOMINION VPAP-2103N REVISION 23PAGE 27 OF 876.3.4 1-131, 133, H-3 & Radionuclides In Particulate Form Effluent Dose Limita. Requirement
- 1. Methods shall be implemented to ensure that the dose to any organ of a memberof the public from 1131, 1133; tritium, and all radionuclides in particulate formwith half-lives greater than 8 days, in gaseous effluents released from the site tounrestricted areas from each reactor unit shall be:" During any calendar quarter:
< 7.5 mrem to the critical organ" During any calendar year: < 15 mrem to the critical2. Cumulative dose contributions to a member of theu
- fro )131, 1133,tritium, and radionuclides in particulate form i haliveater than 8 days,in gaseous effluents released to unrestrict e r urrent calendarquarter and current calendar year shal dete t least once per 31 daysin accordance with Step 6.3.4.c.b. ActionIf the calculated dose from t e1133, tritium, and radionuclides inparticulate form, with haP reat than 8 days, in gaseous effluents exceedsany of the above limi re e a-ubmit to the NRC within 30 days, a specialreport in accorda wi PAP- 802, Notifications and Reports, that.contains the:1. C i ts.2. Co iv/tion aken to reduce releases.
- 3. Pro rrective actions to be taken to assure that subsequent releases willin c pliance with limits stated in Step 6.3.4.a.
DOMINION VPAP-2103N REVISION 23PAGE 28 OF 87c. Dose Calculations Gaseous releases, not through the process vent, are considered ground level andshall be included in the determination of Qw. Historical data pertaining to thevolumes and radioactive concentrations of gaseous effluents released in connection to specific Station functions, such as containment purges, shall be used in theestimates as appropriate.
- 1. The dose to the maximum exposed member of the public, attributable togaseous effluents at and beyond the site boundary, th .1131, 1133,tritium, and particulate-form radionuclides with h f gre rthan 8 days,shall be determined by:Dr = 3.7EO81[RMiv ivy pvQipv] (17)Where:Subscripts vv, refers t a rom the building ventilation vents;pv, refer o t eases from the process ventDr = the 0- c i al organ of the maximum exposed memberifc, nmremRMivv, RMip ~he fac r for ventilation venqts or process vent release due1 133, tritium, and from all particulate-form adi clides with half-lives greater than 8 days, in mrem/yr"~\4 urie/sec.
Factors are listed in' Critical Organ Dose Factors" ~ ttachment 8)= the release for ventilation vents or process vent of 1131, 1133,tritium, and from all particulate-form radionuclides withhalf-lives greater than 8 days, in Curies-08 the inverse of the number of seconds in a year DOMINION VPAP-2103N REVISION 23PAGE 29 OF 876.3.5 Gaseous Radwaste Treatment Historical data pertaining to the volumes and radioactive.,
concentrations of gaseouseffluents released in connection with specific Station functions, such as containment purges, shall be used to calculate projected doses, as appropriate.
- a. Requirement
- 1. The Gaseous Radwaste Treatment System and the Ventilation ExhaustTreatment System shall be used to reduce radioactive material in gaseous wastebefore its discharge, when projected gaseous effluent due to gaseouseffluent
- releases, from each unit to areas at and be site undary, would.exceed 0.2 mrad for gamma radiation and 0.4 be iation, averagedover 31 days.2. The Ventilation Exhaust Treatment Sy m sha se ed to reduce radioactive materials in gaseous waste before' isc e en the projected doses due togaseous effluent
- releases, from it t a eas at and beyond the siteboundary, would exceed 0 e, tical organ, averaged over 31 days.3. Doses due to gaseou a fro the site shall be projected at least onceper 31 days, base n t t ions in Step 6.3.5.c.b. ActionIf gaseous ex ds the limits in Step 6.3.5.a.
is discharged withouttreatme re a ubmit to the NRC within 30 days, a special report inacco c th VPAP-2802, Notifications and Reports, that includes:
n ex Ination why gaseous radwaste was being discharged without treatment,
" "cation of any inoperable equipment or subsystems, and the reason for theoperability.
Actions taken to restore the inoperable equipment to operable status.3. Summary description of actions taken to prevent recurrence.
- c. Projected Gamma Dose1. Determine Dg, the 31-day gamma air dose for the previous 31-day period,per Equation (15).2. Estimate Rg, the ratio of the estimated volume of gaseous effluent in the current31-day period to the volume released during the previous 31-day period.
DOMINION VPAP-2103N REVISION 23PAGE 30 OF 873. Estimate Fg, the ratio of the estimated noble gas effluent activity in the current31-day period to the noble gas effluent activity during the previous 31-dayperiod (jtCi/ml).
- 4. Determine PDg, the projected 31-day gamma air dose.PDg = Dg(R x Fg) (18)d. Projected Beta Dose1. Determine Db, the 31-day beta air dose in the ousldper Equation (16).2. Estimate Rg and Fg as in Steps 6.3.5.c.
.nd3. Determine PDb, the projected 31- be e.gD -) (19)e. Projected Maximu ember of the Public Dose1. Determine D x, the -day makimum exposed member of the public dose inthe previou y p d, per Equation (14), where Dr = Dmax.2.th o of the estimated activity from 1131, 1133, radioactive I particulate form with half-lives greater than 8 days, and tritium int~he c 1-day period to the activity of 1131, i133, radioactive materials inSltic te form with half-lives greater than 8 days, and tritium in the previous-ay period (pCi/ml).
etermine PDmax, the projected 31-day maximum exposed member of thepublic dose.PDmax = Dmax(Rg X Fi)(20)
DOMINIONVPAP-2103N REVISION 23PAGE 31 OF 876.4 Radioactive Liquid and Gaseous Release PermitsRP shall maintain procedures for Liquid and Gaseous Release Permits to ensure effluent doselimits are not exceeded when making releases.
6.4.1 Liquid Waste Batch Release PermitsOperations shall obtain RP authorization before initiating batch releases of radioactive liquids.
Examples of batch releases include:Batch ReleasesNOTE: If the clarifier is in service, releases from tanksconsidered continuous releases.
A Batch Release Permit is required for a reles(or potentially contain) radioactive liqui .anl,* BRTT* LLWDT" HLWDT" Turbine Buildin en secondary coc* CDT 2 /)wharifier arewhich contain6.4.2)rization befortlant activity exceeds 1.0 E-5 ltCi/mlinitiating continuous releases ofRelease Permit is required for:-Clarifier, unless being bypassed* Steam generator blowdown when clarifier is bypassed* Containment mat sumps and service water reservoir when clarifier is bypassed.
Sampling requirements and control and conditions for service water reservoir
- blowdown, when no radioactivity is detected, shall be specified on the permit.
DOMINION VPAP-2103N REVISION 23PAGE 32 OF 876.4.3 Waste Gas Decay Tank (WGDT) Release PermitOperations shall obtain-RP authorization before initiating WGDT releases.
6.4.4 Reactor Containment Release PermitsOperations shall obtain authorization from RP before initiating containment purges orcontainment hogging.
Reactor Containment Release Permits shall be valid from startof purge/hog until:" Routine termination
- Terminated for cause by RP" Receipt of Radiation Monitoring System (RMS) ai nt Monitor highalarm6.4.5 Miscellaneous Gaseous Release PermitOperations shall obtain RP authorizati e I ng releases of noble gases thatmay not be accounted for by routine 0,0oj y planned release not being routedthrough the Process Vent or Ve ati e g., steam driven auxiliary feedwater pump testing if primary to sea ge exists).6.4.6 Radioactive Liquid lease Controlsa. Operations shay$ tiR, pending releases and request RP to initiate theappropriate
/ n Operations shall provide the necessary information tocomplet e r uir lease permit.b. A rep .t e sample shall be obtained of the source to be released.
I etns shall provide RP with liquid samples and sample information(e.g.,
sample) for samples obtained outside the Primary Sample Room, exceptarifier Proportional Tank and Clarifier Grab Samples.2. Chemistry shall provide RP with liquid samples and sample information forsamples obtained from inside the Primary Sample Room.3. RP shall obtain gaseous samples.c. RP shall perform required sample analyses.
DOMINION VPAP-2103N REVISION 23PAGE 33 OF 87d. RP shall calculate and record the following information on a release permit:" Maximum authorized release rate I" Maximum authorized release rate in percentage of limits specified by the ODCM* Applicable conditions or controls pertaining to the releasee. RP shall notify the Shift Supervisor if it is determined that a release may not bewithin the effluent dose limits.f. Upon receipt of a release permit from RP, Operations shal1. Check that the correct source is authorized for rel s2. Note maximum authorized release rate.3. Note percent of Technical Specificatio se represents.
- 4. Note and ensure compliance with i a ntrols or conditions applicable to the release.g. When conmmencing
- release, 0vide RP with required information.
As appropriate, r nI include:" Date and time relea w t* Starting tank/s -le" Beginning p" Releas" Dil rflow rateh. n ter ating the release, Operations shall return the permit to RP and provide, aenfo necessary for completion of permit. As appropriate, required~ation shall include:~ate and time release was stopped* Tank/sump ending level* Release flow rate just prior to termination
" Ending pressure" Volume released DOMINION VPAP-2103N REVISION 23PAGE 34 OF 876.5 Total Dose Limit to Public From Uranium Fuel Cycle Sources6.5.1 Requirement The annual (calendar year) dose or dose commitment to a real individual due toreleases of radioactivity and radiation from uranium fuel cycle sources shall notexceed 25 mrem to the total body or the critical organ (except the thyroid, which shallnot exceed 75 mrem).6.5.2 Actiona. If the calculated doses from release of radioactive mated n id or gaseouseffluents exceed twice the limits in Steps 6.2.3.a.,
6.3 a.! 6.3. ., calculate (including direct radiation contribution from the s a fr tside storagetanks) whether limits in Step 6.5.1 have beenb. If the limits in Step 6.5.1 have been exce prep, ad submit to the NRCwithin 30 days, a special report in ac a c t PAP-2802, Notifications andReports, that defines the corrective b en to reduce subsequent releasesand to prevent recurrence, an c ule for achieving conformance withthe limits. Special reports 10 CFR 20.2203(a)(4),
shall include:1. An analysis that a raiation exposure (dose) to a real individual
--from uraniu el c sources, including all effluent pathways and directradiation, ale year that includes the releases.
covered by the report.2.A d ipti o levels of radiation and concentrations of radioactive rn o olved, and the cause of the exposure levels or concentrations.
f t ated dose exceeds the limits in Step 6.5.1, and if the releasen n that violates 40 CFR 190 has not already been corrected, the specialSport shall include a request for a variance in accordance with the provisions of0 CFR 190. Submittal of the report is considered a timely request, and avariance is granted until staff action on the request is complete.
6.6 Radiological Environmental Monitoring 6.6.1 Monitoring Programa. Requirement
- 1. The Radiological Environmental Monitoring Program shall be conducted asspecified in Radiological Environmental Monitoring Program (Attachment 9).
DOMINION VPAP-2103N REVISION 23PAGE 35 OF 872. Samples shall be collected from specific locations specified in Environmental
.-Sampling Locations (Attachment 10). [Reference 3.1.31].3. Samples shall be analyzed in accordance with:" Radiological Environmental Monitoring Program (Attachment 9)requirements
" Detection capabilities required by Detection Capabilities for Environmental Sample Analysis (Attachment 11)" Guidance of the Radiological Assessment Branch T Position onEnvironmental Monitoring dated November, 19 sio o. Ib. Action1. If the Radiological Environmental Moni
- is not being conducted as required in Step 6.6.1 .a., report the tion i cc"rdance with VPAP-2802, Notifications and Reports, by pre in a itting to the NRC, in theAnnual Radiological Environm
]er rng Report required by Technical Specifications 5.6.2, a des ti 'N for not conducting the programas required, and the pl ing recurrence.
- 2. If, when average endar quarter, radioactivity due to station"-.effluents exc s th orting levels of Reporting Levels.for Radioactivity Concentra s nvi mental Samples (Attachment
- 12) prepare and submit-..to the I days, a special report in accordance with VPAP-2802, Nand ors, that:1 Id~f he causes for exceeding the limits, and,Defi)s the corrective actions to be taken to reduce radioactive effluents sothe potential annual dose to a member of the public is less than theSc calendar year limits of Steps 6.2.3, 6.3.3, and 6.3.4When more than one of the radionuclides listed in Reporting Levels forRadioactivity Concentrations in Environmental Samples (Attachment
- 12) aredetected in the sampling medium, the report shall be submitted if:concentration (1) + concentration (2) + ... 1.0 (21)reporting level (1) reporting level (2)
DOMINION VPAP-2103N REVISION 23PAGE 36 OF 873. When radionuclides other than those listed in Reporting Levels forRadioactivity Concentrations in Environmental Samples (Attachment
- 12) aredetected and are the result of plant effluents, the report shall be submitted if thepotential annual dose to a member of the public is equal to or greater than thecalendar year limits of Steps 6.2.3, 6.3.3, and 6.3.4. The report is not required ifthe measured level of radioactivity was not the result of plant effluents;
- however, in such an event, report and describe the condition in the AnnualRadiological Environmental Operating Report in accord with VPAP-2802, Notifications and Reports.
<KN\4. If milk or fresh leafy vegetable samples are una b e or more of thesample locations required by Environmental
.gppcations (Attachment ic10), identify locations for obtaining re e s es and add them to theradiological environmental monitorig
,ranithin 30 days. The specificlocations from which samples u aimay then be deleted from themonitoring program.
Identi ej- ee e unavailability of samples andidentify the new locations r.n'eplacement samples in the next AnnualRadioactive Effluen a ee t in accordance with VPAP-2802, Notifications and eode in the report a revised figure and table for theODCM to re t the locations.
6.6.2 Land Ua. Req )tAla , sus shall be conducted and shall identify, within a distance of 8 kmes ation in each of the 16 meteorological sectors of the following:
ilk animalrest residence wrest garden greater than 50 m2 (500 ft2) that produces broad leaf vegetation
- 1. The land use census shall be conducted during the growing season, at least onceper 12 months, using methods that will provide the best results (e.g., door-to-door survey, aerial survey, local agriculture authorities).
Land use census resultsshall be included in the Annual Radiological Environmental Operating Reportin accordance with VPAP-2802, Notifications and Reports.
DOMINION VPAP-2103N REVISION 23PAGE 37 OF 872. In lieu of the garden census, broad leaf vegetation sampling of at least threedifferent kinds of vegetation may be performed at the site boundary in each oftwo different direction sectors with the highest predicted ground deposition (D/Qs). Specifications for broad leaf vegetation sampling in Radiological Environmental Monitoring Program (Attachment
- 9) shall be followed, including analysis of control samples.b. Action1. If a land use census identifies locations that yield a c dose or dosecommitment greater than the values currently bei gJ,,ulate
)n 6.3.4.a.2, identify the new locations in the next Annual io iv uent ReleaseReport in accordance with VPAP-2802, No s Reports.2. If a land use census identifies locatio t a culated dose or dosecommitment (via the same expos path ) percent greater than at alocation from which samples ar, tly] ng obtained, add the newlocations to the Radiologii Ivir al Monitoring Program within 30days. Sampling locations, i the control station location, that have thelowest calculated os mitments (via the same exposure pathway)may be deleted o _ ring program.
Identify new locations in the nextAnnual Rai ,,t' E' ~ent Release Report and include in the report revisedfigures s'xk < re ting the new locations in accordance with VPAP-2802, Not'iti an eports. [Reference 3.1.33]6.6.3 Interlabo o~ow"'omparison Programa.re te materials (which contain nuclides produced at the Station),
supplied asan Interlaboratory Comparison
- Program, shall be analyzed.
DOMINION VPAP-2103N REVISION 23PAGE 38 OF 87b. Action1. Analyses shall be performed at least semiannually as follows:Program Cross-Check ofMilk 1131, Gamma, Sr89 and Sr90Water Gross Beta, Gamma, 1131, H3 (Tritium),
Sr89and Sr9° (blind -any combinations of aboveradionuclides)
Air Filter Gross Beta, Gamma, Sr902. If analyses are not performed as required by 3.b , rport in the AnnualRadiological Environmental Operating ance with VPAP-2802, Notifications and Reports, the corre i tic aken to prevent recurrence.
- c. ResultsResults shall be reported in the ua" d*gical Environmental Monitoring Report in accordance with ' kifications and Reports.6.7 Reporting Requirements 6.7.1 Annual Radiologicln men al Operating ReportRoutine Radiolog
'-I iron ntal Operating Reports covering the operation of theunits during )i syv P dar year shall be submitted prior to May 1 of each year.A singlee i may made for the Station.
Radiological Environmental Operatinr
, shall include:' ari interpretations, and analysis of trends of results of radiological
( o nmental surveillance activities for the report period, including:
~ omparison (as appropriate) with preoperational
- studies, operational
- controls, and previous environmental surveillance reports* An assessment of the observed impacts of the plant operation on the environment
- Results of land use census per Step 6.6.2 DOMINION VPAP-2103N REVISION 23PAGE 39 OF 87b. Results of analysis of radiological environmental samples and of environmental radiation measurements taken per Step 6.6.1, Monitoring Program.
Results shall besummarized and tabulated in the format of the table in the Radiological Assessment Branch Technical Position on Environmental Monitoring.
- 1. If some individual results are not available for inclusion with the report, thereport shall be submitted, noting and explaining reasons for missing results.2. Missing data shall be submitted in a supplementary report as soon as possible.
- c. A summary description of the radiological environment onit tg, pgd. At least two legible maps covering sampling locat' table givingdistances and directions from the centerline of on or. e map shall coverstations near the site boundary; a second s in e distant stations.
- e. Results of Station participation in the rla Comparison Program,per Step 6.6.3.f. Discussion of deviations fro e4 a.ronmental sampling schedule perRadiological Environme iori Program (Attachment 9).g. Discussion of analys nAee lower limit of detection (LLD) required byDetection Capabi es nvironmental Sample Analysis (Attachment
- 11) wasnot achievable.
- h. Any reIt any groundwater wells described in the environmental prog \(K er the results were required by the environmental program or not.6.7.2 An I Ra "cve Effluent Release Reportae ¢ nt t- Stationa active Effluent Release Reports covering operation of the units during theious 12 months of operation shall be submitted before May 1 of each year. Asingle submittal may be made for the Station and should combine those sections thatare common to both units. Radioactive Effluent Release Reports shall include:1. A summary of quantities of radioactive liquid and gaseous effluents and solidwaste released.
Data shall be summarized on a quarterly basis following theformat of Regulatory Guide 1.21, Appendix B, for liquid and gaseous effluents.
Data shall be summarized on an annual basis following the format ofRegulatory Guide 1.21, Appendix B, for solid waste. [Reference 3.1.34]
DOMINION VPAP-2103N REVISION 23PAGE 40 OF 872. An assessment of radiation doses to the maximum exposed members of thepublic due to the radioactive liquid and gaseous effluents released from theStation during the previous calendar year. This assessment shall be inaccordance with Step 6.7.2.b.3. A list and description of unplanned releases from the site to unrestricted areas,during the reporting period, which meet the following criteria:
- Unplanned releases that exceeded the limits in Steps 6.2.1 and 6.3.1" Unplanned releases which require a Condition Re and ' olve thedischarge of contents of the wrong Waste Gas ay k e wrong liquidradwaste release tank" Unplanned releases from large leaks t d valve or pipe failuresthat result in a quantity of release t a CFR 50.72, Immediate Notification Requirements fo er g ear Power Reactors or 10 CFR50.73, Licensee Event R -S m .rt is required* Unplanned releases d n by Radiation Protection Supervision, which may or m qun Condition Report4. Major than or tive liquid, gaseous, and solid waste treatri.
nt systemsduring the iod.5. Cha PA 103N, Offsite Dose Calculation Manual (North Anna)S .7.4).isi new locations for dose calculations or environmental monitoring
>i i*d by the land use census (See Step 6.6.2).summary of radioactive leaks or spills meeting the following criteria:
- An unintended spill or leak with the potential to reach groundwater, as definedin NEI 07-07, and" The spill or leak must be greater than 100 gallons in volume or the volumecannot be quantified but is estimated to be greater than 100 gallons; or* Any spill or leak, regardless of volume or activity deemed by the licensee tobe reportable.
DOMINION VPAP-2103N REVISION 23PAGE 41 OF 878. Any groundwater sample results from locations not part of the Radiological Environmental Monitoring Program.b. Dose Assessment
- 1. Radiation dose to individuals due to radioactive liquid and gaseous effluents from the Station during the previous calendar year shall either be calculated inaccordance with this procedure or in accordance with Regulatory Guide 1.109.Population doses shall not be included in dose assessments.
- 2. The dose to the maximum exposed member of the p *c radioactive liquid and gaseous effluents from the Station shall or d with the doseassessment performed above. If the dose to th a i u osed member ofthe public exceeds twice the limits of .3.3.a. 1, or 6.3.4.a.
1,the dose assessment shall include the tribUtt direct radiation.
NOTE: NUREG-0543 states: "There is reasoneKran tat sites with up to fouroperating reactors that have releaý it dix I design objective values arealso in conformance with the a fuel Cycle Standard, 40 CFR Part 190."3. Meteorological c i ng the previous calendar year or historical annualaver at o ric dispersion conditions shall be used todetermine gaseous a os DOMINION VPAP-2103N REVISION 23PAGE 42 OF 87NOTE: The Annual Radioactive Effluent Report for the North Anna ISFSI is included as partof the North Anna Station Annual Radioactive Effluent Release Report.c. ISFSIDose Assessment
" Radiation dose to individuals due to radioactive liquid and gaseous effluents during the previous calendar year shall either be calculated in accordance withthis procedure or in accordance with Regulatory Guide opulation dosesshall not be included in dose assessments.
" The dose to the maximum exposed member of th ldo liquidand gaseous effluents from the Station shall b 11 or with the doseassessment performed above. If the dose. eexposed member of thepublic exceeds twice the limits of 6.. .a. 23 2, 6.3.3.a.
1, or 6.3.4.a.
1, thedose assessment shall include thentrj tio m direct radiation.
- Meteorological conditions th e i s calendar year or historical annualaverage atmospheric disper4_:l i ios shall be used to determine gaseouspathway doses.6.7.3. Annual Meteorolo "i$la. Meteorologica ta lect during the previous year shall be in the form of jointfrequency wind speed, wind direction, and atmospheric stability.
- b. data shall be retained in a file on site and shall be made available toCup r e st.6.7.4 n 0 ODCMto the ODCM shall be:a."-viewed and approved by Site Vice President before implementation.
- b. Documented.
Records of reviews shall be retained as Station records.Documentation shall include:1. Sufficient information to support changes, together with appropriate analyses orevaluations justifying changes.
DOMINIONVPAP-2103N REVISION 23PAGE 43 OF 872. A determination that a change will not adversely impact the accuracy orreliability of effluent doses or setpoint calculations, and will maintain the levelof radioactive effluent control required by:* 10 CFR 20 Subpart D* 40 CFR 190* 10 CFR 50.36a* 10 CFR 50, Appendix Ic. Submitted to NRC in the form of a complete, legiblepart of, or concurrent with the Annual Radioactive Eperiod of the report in which any change was mad//by markings in the margin of the affected pa- c,page that was changed, and shall indicate tiateimplemented.
- etiNiltire ODCM as atelea)l Report for thehah- be identified
ýjating the area of theith/year) the change wasd. Submitted to NRC in accordance 6.7.5 Groundwater Protection Initit,a. Notifications and 1. Informal cornmu frtiof the next b iess for:P- J2, Notifications and Reports.ce 3.1.35]made to state/local/NRC officials by the end-* Any spillNm titng the requirements of Step 6.7.2.a.7.
ample result exceeding the retporting levels of Reporting Radioactivity Concentrations in Environmental Samplesnt 12).1 30- report shall be submitted to the NRC and a copy concurrentlyrwarded to state and local officials for any groundwater sampling result,,hether on site or off site, exceeding the reporting levels of Reporting Levelsfor Radioactivity Concentrations in Environmental Samples (Attachment 12)and having the potential to reach groundwater that is or could be used as asource of drinking water. A 30-day report is only required on the initialdiscovery of a contaminated groundwater plume.b. Any spill or leak for which an informal notification is made in accordance withStep 6.7.5.a.
shall be summarized in the Annual Radioactive Effluent Report.
DOMINION VPAP-2103N REVISION 23PAGE 44 OF 87c. Any groundwater sample result from a groundwater source that is not part of theradiological environmental monitoring program shall be included in theAnnual Radioactive Effluent Report.d. Any groundwater sample result from any groundwater well described in theradiological environmental monitoring program shall be included in theAnnual Radiological Environmental Operating Report.7.0 RECORDS7.1 The following record(s) completed as a result of this procedure are uired be transmitted to Nuclear Document Management (DNM). The records have n id >i.jt and retention requirements established for the Nuclear Records Retention e ( S) per RM-AA-100, Record Creation, Transmittal and Retrieval.
Quality Assurance Records* Records of changes to the ODCM in accorda,/
h, .p 6.7.4* Records of meteorological data in acc a.n .pj2)ik 6.7.3* Records of sampling and analyses" Records of radioactive materi n u1fflents released to the environment
" Records of preventive m n c .,rveillances, and calibrations 7.2 The following item(s) a esult of this procedure are NOT records and are NOTrequired to be tran tte N ar Document Management (DNM).None DOMINIONVPAP-2103N REVISION 23PAGE 45 OF 87ATTACHMENT 1(Page 1 of 2)Radioactive Liquid Effluent Monitoring Instrumentation Instrument
- 1. Liquid Radwaste Effluent(a) 1-LW-RM-1 11, Liquid Radwaste Effluent Monitor(b) 1-LW-FT-104, Liquid Radwaste Effluent Total Flow Measuring Device(c) 1-LW-TK-20, Liquid Waste Effluent Sample Vessel(d) I-LW-i 130, Liquid Waste Effluent Proportional I(e) 1-SW-RM-108, Service Water Effluent1(f) 1-SW-RM-130, Unit 1Monitor1* .. (g) 2-SW-RM-230, Unit 2.I Monitor12.(a)11(b)ýr High Capacity Blowdown Flash Tank OutletRateUnit 1 I-BD-FT-105 Unit 2 2-BD-FT-205 11(c) Steam Generator High Capacity Blowdown Proportional SampliniSystem Collection TankUnit 1 1-BD-TK-4 Unit 2 2-BD-TK-4 11 DOMINION VPAP-2103N REVISION 23PAGE 46 OF 87ATTACHMENT 1(Page 2 of 2)Radioactive Liquid Effluent Monitoring Instrumentation ACTION 1: If the number of operable channels is less than required, effluent releases via thispathway may continue if, at least once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected andanalyzed for gross radioactivity (beta and gamma) at an LLD of at least lx10-7 lgCi/gor an isotopic radioactivity at an LLD of at least 5x 10-7 lCi/g.ACTION 2: If the number of operable channels is less than required, e re es via thispathway may continue if the flow rate is estimated at le nours duringactual releases.
Design capacity performance curves d errd^in may be used toestimate flow.ACTION 3: If the number of operable channels is less tn uire ake repairs as soon aspossible.
Effluent releases via this path ym c e provided that, at least onceper 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples from the c/y are collected and analyzed forprincipal gamma emitters as defid i 'I ve Liquid Waste Sampling andAnalysis Program (Attachm
.NOTE 1: The capability for obtaining t least every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> must exist. Grab samplesshall conimence if ther in c of radioactivity in the Service Water System or a*nindication from other r n itors in the Service Water System of an increase inradioactivity.
NOTE 2: To utilize I- -08 as the effluent radiation monitor for the associated loop,0-PT-75 (1- R"- 108 Flow Verification) must be performed prior to placing the loopin s, re." ut.'monitoring is not required when discharge flowpath is not in service.
DOMINIONVPAP-2103N REVISION 23PAGE 47 OF 87ATTACHMENT 2(Page 1 of 2)Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements Channel Description Channel Source Channel ChannelCheck Check Calibration Operational Test1. Liquid Radwaste Effluent(a) I-LW-RM-1J N, Liquid Radwaste Effluent Monitor D D Q (NOTE 1)(b) I-LW-FT-104, Liquid Radwaste Effluent Total Flow D (NOTE 3) ) R QMeasuring Device >(c) 1-LW-TK-20, Liquid Waste Effluent Sample Vessel D TE 4) N N/A N/A(d) 1-LW-1 130, Liquid Waste Effluent Proportional Sam< OT 4 N/A N/A N/AValve(e) I-SW-RM-108, SW Effluent Monitor (NOTE D M R Q (NOTE 2)(f) 1-SW-RM-130, Unit I Circul i n Ka2 em D M R Q(NOTE2)Effluent Line Monitor QN)E2(g) 2-SW-RM-230, Unit 2 i L 9 ter System D M R Q (NOTE 2)Efflutent Line Monit°/orAV X /-2. Steam Generator (S ~g' : pacity Blowdown(a) SGwn Radiation MonitorUnit -125 Q (NOTE 6)Unit 2 -225 D (NOTE 7) D (NOTE 8) R (NOTE 5)(b) SG High Capacity Blowdown Flash Tank OutletFlow RateUnit 1 1-BD-FT-105 D (NOTE 8) N/A N/AUnit 2 2-BD-FT-205 (c) SG High Capacity Blowdown Proportional SamplingSystem Collection TankUnit 1 1-BD-TK-4 Unit 2 2-BD-TK-4 D (NOTE4) N/A N/A N/A DOMINION VPAP-2103N REVISION 23PAGE 48 OF 87ATTACHMENT 2(Page 2 of 2)Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements NOTE 1: The Channel Operational Test shall demonstrate:
- a. Automatic isolation of this pathway and Control Room alarm annunciation occur if theinstrument indicates measured levels above alarm/trip setpoint.
- b. Alarm annunciation occurs if the instrument controls are not se "operate" mode.NOTE 2: The Channel Operational Test shall demonstrate that Control alarnnnunciation occurs if any of the following conditions exists:-\/
- a. Instrument indicates measured levels above the at t.b. Instrument controls not set in "operate" mode.<,,,
))NOTE 3: Channel Check shall consist of checking in aio during periods of release.Channel Check shall be made at least o p h on days on which continuous,
- periodic, or batch releases are made.NOTE 4: Channel Check shall consist of in roportional flow exceeds 0.5 mls/gallon.
NOTE 5: Channel Operational that system isolation odcurs on a.radiation monitor High-High AlNOTE 6: Channel Operatio all onstrate:
- a. Trip sign s. erate at the required setpoints.
Isolation is not required.
- b. Loc radiat'f kmitor indication occurs if instrument controls are not set in "Operate" t i strument indicates measured levels are above the alarm/trip setpoint.
NOTE 7: T monitor automatically performs periodic source checks. The Source Checkand Cl Check are satisfied as long as the green light is lit.NOTE 8: This is confirmed by indicated effluent flow less than or equal to 190 gpm.NOTE 9: To utilize I-SW-RM-108 as the effluent radiation monitor for the associated loop,0-PT-75.21, (1-SW-RM-108 Flow Verification) must be performed prior to placing the loopin service.
Effluent monitoring is not required when discharge flowpath is not in service.
DOMINIONVPAP-2103N REVISION 23PAGE 49 OF 87ATTACHMENT 3(Page 1 of 3)Radioactive Liquid Waste Sampling and Analysis ProgramBatch Releases(Notes 2 and 7)Continuous Releases(Note DOMINIONVPAP-2103N REVISION 23PAGE 50 OF 87ATTACHMENT 3(Page 2 of 3)Radioactive Liquid Waste Sampling and Analysis ProgramNOTE 1: For a particular measurement system (which may include radiochemical separation):
4.66 SbLLD =(9-1)Where:LLD = the "a priori" (before the fact) Lower(as microcuries per unit mass orSb = the standard deviation of the krate of a blank sample as teqti'n as defined abovesection 4.8)inting rate or of the countingints per minute, cpm)EV =2.22E+06Ythe counting efficieJ (a u er disintegration) the sample si nit S or volume)the num 0 1"ntegratlons per minute (dpm) per microcurie r chemical yield (when applicable) eKioact e decay constant for the particular radionuclide
, time between the midpoint of sample collection and time ofntingof E, V, Y and At should be used in the calculation.
AtThe LED'-is an "a priori" (before the fact) limit representing the capability of a measurement system and not a "posteriori" (after the fact) limit for a particular measurement.
NOTE 2: A batch release is the discharge of liquid wastes of a discrete volume. Before sampling foranalyses, each batch shall be isolated, and then thoroughly mixed as the situation permits,to assure representative sampling.
DOMINION VPAP-2103N REVISION 23PAGE 51 OF 87ATTACHMENT 3(Page 3 of 3)Radioactive Liquid Waste Sampling and Analysis ProgramNOTE 3: The principal gamma emitters for which the LLD specification applies exclusively are thefollowing radionuclides:
Mn54, Fe59, Co58, Co60, Zn65, Mo99, Cs134, Cs137, Ce141, andCe144.This list does not mean that only these nuclides are to be detected and reported.
Other peaks that are measurable and identifiable, at levels exceeding the LLD, togetherwith the above nuclides, shall also be identified and reported.
NOTE 4: A composite sample is one in which the quantity of liquid saI, pr 1brtional to thequantity of liquid waste discharged and for which the met of p e'g{ mployed resultsin a specimen that is representative of the liquids releNOTE 5: A continuous release is the discharge of liquid wa of a i-lscrete volume, e.g., froma volume of a system that has an input flow n th uous release.NOTE 6: To be representative of the quantities an o trat's of radioactive materials in liquideffluents, samples shall be collected nti proportion to the rate of flow of theeffluent stream. Prior to analyse e ken for the composite shall be thoroughly mixed in order for the comp e e representative of the effluent releases.
NOTE-7: Whenever the secondar ol n tivity exceeds 10-5-jCi/ml, the turbine building sumppumps shall be placed ual/eration and samples shall be taken and analyzed priorto release.
Seco 0 vity samples shall be collected and analyzed on aweekly basis mples are analyzed for gross activity or gamma isotopic activitywithin 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> .NOTE 8: The it for which the LLD specification applies exclusively are the following ra :"r-87, Kr-88, Xe-133, Xe-133m, Xe-135, Xe-135m and Xe-138. This listdoes n t .n that only these nuclides are to be detected and reported.
Other peaks that aremeasurable and identifiable, at levels exceeding the LLD, together with the above nuclidesshall also be identified and reported.
DOMINIONVPAP-2103N REVISION 23PAGE 52 OF 87ATTACHMENT 4(Page 1 of 4)Radioactive Gaseous Waste Sampling and Analysis ProgramGaseous Release Sampling Minimum Analysis Type of Activity Detection (LLD)Type Frequency Frequency Analysis (tCi/ml),
(Note 1)Prior to Release Prncpa 6am 1X 10-4Pi toste Release TPrior to Release Emitters (NotA. Waste Gas (Each Tank (Each Tank)Storage Tank Grab Sample) H3 I X 10-6B. Containment Prior to Release Prior to Release Erin 1 X 10-4Purge (Each PURGE (Each PURGE) I x 10-6Grab Sample) (cP GC. Ventilation Monthly ri/ 7_ri 1 X 10-4(1) Process Vent (Grab Sample) <tE ' ters (Note 2)(2) Vent Vent A (Notes 3 and 5) (!jte H3 x 10-6(3) Vent Vent BContinuous ee e IV31 1 x 10-12(Note 4 and 5 -mple) 1 xAll Release C t \,Weekly Principal Gamma 1 x 10-11(Note 4-q culate Sample Emitter (Note 2)'/ MonthlyTypes as listed t Composite Gross Alpha Ix 10-11Particulate SampleCo *N,, Co~tuous Quarterly and 5) Composite Sr89 and Sr90 1 x 10-11n AParticulate C(Nontinuou Noble Gas Monitor Noble Gases Gross 1 x 10-6(Note 4 and 5) Beta or GammaCondenser Air Weekly Weekly Principle Gamma I x 10-4Ejector/Steam Emitters (Note 7)Generator Grab Sample H3 1 x 10-6Blowdown Vent / (Note 6)BRT VentContainment Prior to Release Prior to each Principle Gamma I X 10-4Vacuum Steam Emitters (Note 2)(Grab Sample) Release H3 1 x 10-6Ejector (Hogger)
(Note 8)
DOMINIONVPAP-2103N REVISION 23PAGE 53 OF 87ATTACHMENT 4(Page 2 of 4)Radioactive Gaseous Waste Sampling and Analysis ProgramNOTE 1: For a particular measurement system (which may include radiochemical separation):
4.66 SbLLD =Where:LLD = the "a priori" (before the fact) Lower Lii(as microcuries per unit mass or vSb = the standard deviation of the k nrate of a blank sample as o t,E = the counting efficie (ba5 u er d(V = the sample sie nit ss or voltn as defined abovesection 4.9)inting rate or of the countingnts per minute, cpm)isintegration) 2.22E+06
=per minute (dpm) per microcurie Ydecay constant for the particular radionuclide Attime between the midpoint of sample collection and time ofintingof E, V, Y and At should be used in the calculation.
The L-DLis an "a priori" (before the fact) limit representing the capability of a measurement system and not as "posteriori" (after the fact) limit for a particular measurement.
NOTE 2: The principal gamma emitters for which the LLD specification applies exclusively are thefollowing radionuclides:
Kr87, Kr88, Xe133, Xe133m, Xe135, Xe135m, and Xe138 for gaseousemissions and Mn54, Fe59, Co58, Co60, Zn65, Mo99, Cs134, Cs137, Ce141 and Ce144 forparticulate emissions.
This list does not mean that only these nuclides are to be detected andreported.
Other peaks that are measurable and identifiable, at levels exceeding the LLD,together with the above nuclides, shall also be identified and reported.
DOMINION VPAP-2103N REVISION 23PAGE 54 OF 87ATTACHMENT 4(Page 3 of 4)Radioactive Gaseous Waste Sampling and Analysis ProgramNOTE 3: Sampling and analysis shall also be performed following
- shutdown, start-up, and whenevera thermal power change exceeding 15 percent of the rated thermal power occurs within anyone-hour period, if:a. Analysis shows that the dose equivalent 1131 concentration in the rimary coolant isgreater than 1.0 laCi/gm; andb. The noble gas activity monitor shows that effluent activ' as d by more thana factor of 3.NOTE 4: The ratio of the sample flow rate to the sampled st all be known for theperiod covered by each dose or dose rate calcu io de) accordance withSteps 6.3.1, 6.3.3, and 6.3.4.NOTE 5: Samples shall be changed at least onc i e d and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or a, Iom sampler).
Sampling shall also beperformed at least once per 24 or o, t seven days following each shutdown, start-up or thermal power c a 15 percent of rated thermal power in one hourand analyses shall be c le d in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing.
When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are ana oc sponding LLDs may be increased by a factor of 10. Thisrequirement ap )ifa. Analysis
, 'at the dose equivalent 1131 concentration in the primary coolant isgrea han g i/gm and;b. tor shows that effluent activity has increased more than a factor of 3.NOTE 6: Wheneve e secondary coolant activity exceeds 10-5 pCi/ml, Condenser Air Ejector andSteam enerator Blowdown Vent samples shall be obtained and analyzed weekly.Secondary coolant activity samples shall be collected and analyzed on a weekly basis.These samples are analyzed for gross activity or gamma isotopic activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.NOTE 7: The principal gamma emitters for which the LLD specification applies exclusively are thefollowing radionuclides:
Kr87, Kr88, Xe133, Xe133m, Xe135, Xe135m, and Xe138 for gaseousemissions.
This list does not mean that only these nuclides are to be detected and reported.
Other peaks that are measurable and identifiable, at levels exceeding the LLD together withthe above nuclides, shall also be identified and reported.
DOMINION VPAP-2103N REVISION 23PAGE 55 OF 87ATTACHMENT 4(Page 4 of 4)Radioactive Gaseous Waste Sampling and Analysis ProgramNOTE 8: If the secondary coolant activity level in any Steam Generator supplying steam to theHogger exceeds 1.OE-5 ptCi/ml, Steam Generator samples shall be obtained and analyzedprior to release.
DOMINION VPAP-2103N REVISION 23PAGE 56 OF 87ATTACHMENT 5(Page 1 of 3)Gaseous Effluent Dose Factors(Gamma and Beta Dose Factors)X/Q = 9.3E-06 sec/m3 at 1416 meters SE Direction Dose Factors for Ventilation Vent DOMINION VPAP-2103N REVISION 23PAGE 57 OF 87ATTACHMENT 5(Page 2 of 3)Gaseous Effluent Dose Factors(Gamma and Beta Dose Factors)X/Q = 1.2E-06 sec/m3 at 1513 meters S Direction Dose Factors for Process Vent DOMINIONVPAP-2103N REVISION 23PAGE 58 OF 87ATTACHMENT 5(Page 3 of 3)Gaseous Effluent Dose Factors(Inhalation Pathway Dose Factors)Ventilation Vent x/Q = 9.3E-06 sec/mr3 at 1416 meters SE Direction Process Vent x/Q = 1.2E-06 sec/mr3 at 1513 meters S Direction Pivv IipvRadionuclide mrem/yr_Curie/sec
ýCu sercH-3 1.05E+04 03Cr-51 7.95E+02 E+02Mn-54 ND NDFe-59 ND NDCo-58 ND NDCo-60 ND NDZn-65 NDRb-86 NDSr-90 NDY-91 NDZr-95 ND NDNb-95 ND NDRu- 103 ND NDRu- 106 ND NDAg-"O ND NDTe- 5.64E+04 7.28E+03Te 5.88E+04 7.59E+03Cs-13 ND NDCs-136 ND NDCs-137 ND NDBa-140 ND NDCe-141 ND NDCe-144 ND ND1-131 1.51E+08 1.95E+071-133 3.58E+07 4.62E+06ND -No data for dose factor according to Regulatory Guide 1.109, Revision 1
DOMINION VPAP-2103N REVISION 23PAGE 59 OF 87ATTACHMENT 6(Page 1 of 3)Radioactive Gaseous Effluent Monitoring Instrumentation INSTRUMENT MINIMUM OPERABLE ACTIONCHANNELS1. PROCESS VENT SYSTEM(a) Noble Gas Activity MonitorI-GW-RM-178-1 (NO1 2,4(b) Iodine SamplerI-GW-RM-178-1 2,5Process Vent Continuous HP Sampler(c) Particulate SamplerI-GW-RM-178-1 1Process Vent Continuous HP Sampler < (NOTE 3) 2,5(d) Total Flow Monitor1 -GW-FT- 10811(e) Sampler Flow Rate MeasuriMGPI Flow Rate Measu e ic "HP Sampler Rotameter (NOTE 3)2. CONDENSER AIR E IM(a) Gro ss Acti vil,,xqg9
-Unit I3-SV-R3Unit 2 .-RM- (b) Flo e ng Device I- -FI-101A 1(NOTE 1) 14*7SV-FI-100B31-SV-FI-1011B Unit 2 2-SV-FI-200A 2-SV-FI-20 1 A) Q17 .)AnnJ I(NOTE 2) 12-SV-FI-20 1 B DOMINION VPAP-2103N REVISION 23PAGE 60 OF 87ATTACHMENT 6(Page 2 of 3)Radioactive Gaseous Effluent Monitoring Instrumentation INSTRUMENT MINIMUM OPERABLE ACTIONCHANNELS3. VENTILATION VENT A(a) Noble Gas Activity Monitor1-VG-RM-179-1O(NO 1 2(b) Iodine SamplerI-VG-RM-179-1 Vent Vent A Continuous HP Sampler(c) Particulate SamplerI -VG-RM- 179-1 2Vent Vent A Continuous HP Sampler (NOTE 3)"2(d) Total Flow MonitorI -HV-FT- 121 2A11(e) Sampler Flow Rate Measuri IMGPI Flow Rate Measui e ic1HP Sampler Rotameter (NOTE 3) 14. VENTILATION VEN, " '/(a) Noble Gas i nitor"V(NOTE 3)2Vent Continuous HP Sampler (NOTE 3)(c) Particulate Sampler1 -VG-RM- 180-1 1Vent Vent B Continuous HP Sampler (NOTE 3)(d) Total Flow Monitor1-HV-FT-1212B 1 I(e) Sampler Flow Rate Measuring DeviceMGPI Flow Rate Measuring Device 1HP Sampler Rotameter (NOTE 3)
DOMINION VPAP-2103N REVISION 23PAGE 61 OF 87ATTACHMENT 6(Page 3 of 3)Radioactive Gaseous Effluent Monitoring Instrumentation ACTION 1: If the number of operable channels is less than required, effluent
- releases, via this path, maycontinue if the flow rate is estimated at least once per four hours.ACTION 2: If the number of operable channels is less than required, effluent
- releases, via this path, maycontinue if grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed forgross activity or gamma isotopic activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.ACTION 3: If the number of operable channels is less than required, effluent r e ithis path maycontinue if grab samples are taken at least once per twelve (12) h and t e e samples areanalyzed for gross activity or gamma isotopic activity within t ("ur.,his requirement is for effluent accountability and is distinct and separate f an qu'h ,ent for primary-to-secondary leak rate determination.
The need to determine th", nar y--secondary leak rate,e.g., the performance of 1/2-PT-46.3B, shall be deter with the requirements of TRM TR 3.4.5. However, the same sample ma used tulffll both the requirements ofthis action and primary-to-secondary leak rate er) tio./ACTION 4: If the number of operable channels is less n r red, contents of the Waste Gas DecayTanks may be released to the environm 4' ed t prior to initiation of the release:a. At least two independent sampl s of t ontents are analyzed, and:b. At least two technically qu d mbeof the Station staff independently check therelease rate calculation di har ve lineup.ACTION 5: If the number of operablh' I than required, effluent releases from the Waste GasDecay Tank may con e p vi'lamples are continuously collected with auxiliary samplingequipment as re e adi ive Gaseous Waste Sampling and Analysis Program(Attachment NOTE 1: A channel s C t of:a. The ninstren nstalled in the ejector through which the discharge is routed; either Trainý4.S -10 , 10lA), or Train B (1-SV-FI-LOOB, l01B) or both.b.
nts 101A and 101B provide low range measurement.
Flow instruments 100A andp ide high range measurement.
NOTE 2: A cha shall consist of:a. The flow instrument installed in the ejector through which the discharge is routed; either TrainA (2-SV-FI-200A, 201A), or Train B (2-SV-FI-200B, 201B) or both.b. Flow instruments 201A and 201B provide low range measurement.
Flow instruments 200A and200B provide high range measurement.
NOTE 3: A channel shall consist of a MGPI monitor; and a MGPI or HP particulate and iodinesampler, and its associated sampler flow rate measuring device or rotameter.
DOMINION VPAP-2103N REVISION 23PAGE 62 OF 87ATTACHMENT 7(Page 1 of 3)Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL DESCRIPTION CHANNEL SOURCE CHANNEL ChannelCHECK CHECK CALIBRATION Operational Test1. PROCESS VENT SYSTEM(a) Noble Gas Activity Monitor1-GW-RM-178-1 D M (NOTE5) Q (NOTE 1)(b) Iodine Sampler1-GW-RM-178-1 W N/A A N/AProcess Vent Continuous HPSampler D (NOTE 3) N/ N/A(c) Particulate Sampler1 -GW-RM- 178-1 W N/A N/AProcess Vent Continuous HP <Sampler D (NO N/A N/A(d) Total Flow Monitor "7I-GW-FT-108 N/A R Q(e) Sampler Flow Rate Measurin<
DeviceMGPI Flow Rate Meas D (_ TE 3) N/A R N/ADeviceHP Sampler Rot 5ter) (NOTE 3) N/A Every 18 months N/A2. CONDENSER JECTORSYSTEM(a) Noble Ga ctivity onitor-221 D M R Q, R (NOTE 6)(b) Flow easuring DeviceUnit 1 1-SV-FI-100A I-SV-FI-IO1A D N/A R N/A1-SV-FI-100GB 1-SV-FI-1O1B Unit 2 2-SV-FI-200A 2-SV-FI-201 A2-SV-FI-200B D N/A R N/A2-SV-FL-201 B
DOMINIONVPAP-2103N REVISION 23PAGE 63 OF 87ATTACHMENT 7(Page 2 of 3)Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL DESCRIPTION CHANNEL SOURCE CHANNEL ChannelCHECK CHECK CALIBRATION Operational Test3. VENTILATION VENT A(a) Noble Gas Activity Monitor1-VG-RM-179-1 D M (NOTE 5) R Q (NOTE 2)(b) Iodine Sampler1-VG-RM-179-1 W N/A A N/AVent Vent A Continuous HPSampler D (NOTE 3) N/A < / N/A(c) Particulate Sampler1 -VG-RM- 179-1 N/Vent Vent A Continuous HP D A N/Sampler D (NOTE 3) N/A N/A(d) Total Flow Monitor <1-HV-FT-1212A D N/ R Q(e) Sampler Flow Rate Measuring DeviceMGPI Flow Rate Measuring TEO3 N/A R N/ADevice ., = 0HP Sampler Rotameter 0, -N/A Every 18 months N/A4. VENTILATION VENT B / '(a) Noble Gas.Activity 1-VG-RM-180-1 D M (NOTE 5) R Q (NOTE 2)(b) Iodine S ample rNVI-VG-RM-180-W N/A N/A N/AVent VeB Cont u PSap1r D (NOTE 3) N/A N/A N/A(c ) P ' u l A ha T -II 1- W N/A N/A N/AVent V ontinuous HPSamp elr D (NOTE 3) N/A N/A N/A(d) Total Flow Monitor1-HV-FT-1212B D N/A R Q(e) Sampler Flow Rate Measuring DeviceMGPI Flow Rate Measuring D (NOTE 3) N/A R N/ADeviceHP Sampler Rotameter D (NOTE 3) N/A R N/A DOMINIONVPAP-2103N REVISION 23PAGE 64 OF 87ATTACHMENT 7(Page 3 of 3)Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements NOTE 1: The Channel Operational Test shall demonstrate:
- a. Automatic actuation of the valves in this pathway and Control Room alarmannunciation occur if the instrument indicates measured levels above thealarm/trip setpoint.
- b. Alarm annunciation occurs if the instrument controls not sele" mode.NOTE 2: The Channel Operational Test shall demonstrate:
- a. Control Room alarm annunciation occurs if the iilevels are above the alarm/trip setpoint.
- b. Alarm annunciation occurs if the instrun conNOTE 3: Channel Checks shall consist of checkin i .onChannel Checks shall be made at lea pi rperiodic, or batch releases are m .cat neeof one train, either MGPI or SaNOTE 4: The Channel Operation st demonstrate thata. Control Room alarb .ion occurs if the-iare above ale e seb. The Intode selection control automatic htes measuredset in "operate" mode.flow during periods of release.ours on days on which continuous, d only to be done to check operability nstrument indicates measured levelsally resets to "operate" mode whenNOTE 5: M lt-) [ -178-1, l-VG-RM-179-1, and l-VG-RM-180-1 perform periodicso e s automatically.
NOTE 6: The q -ly, Q, Channel Operational Test shall demonstrate that Control Room Alarmannuciation occurs if the instrument indicates measured levels above the alarm/trip setpointand alarm annunciation occurs if the instrument controls are not set in the "operate" mode.The refueling, R, Channel Operational Test shall demonstrate:
- a. Automatic actuation of the valves in this pathway and Control Room Alarmannunciation occur if the instrument indicates above the alarm/trip setpoint.
- b. Alarm annunciation occurs if the instrument controls are not set in the "operate" mode.
DOMINIONVPAP-2103N REVISION 23PAGE 65 OF 87ATTACHMENT 8(Page 1 of 2)Critical Organ Dose Factors(Critical Pathway Dose Factors)Ventilation Vent X/Q = 3.3E-6 at 1593 meters SSE Direction Process Vent X/Q = 9.5E-7 at 1593 meters SSE Direction Ventilation Vent D/Q = 1.7E-8 at 1593 meters SSE Direction Process Vent D/Q = 1.1E-8 at 1593 meters SSE DirectioRmivvRadionuclide mrem/yr < re rCurie/sec
//u /secH-3 1.32E+4 1E+3Mn-54 ND NDFe-59 ND NDCr-Si 1.11E+3/
7.16E+2Co-58 ND NDCo-60 NDZn-65 NDRb-86 N NDSr-89 NDSr-90 ND NDY-91 ND NDZr-95 NDNDNb-95 ND NDu-10_3 ,ND NDRu/ ND ND1ND NDTe-12 5.37E+6 3.48E+6Te- 129m 4.61E+6 2.98E+61-131 8.08E+8 5.23E+81-133 1.38E+7 8.93E+6Cs- 134 ND NDCs-136 ND NDCs-137 ND NDBa-140 ND NDCe-141 ND ND DOMINIONVPAP-2103N REVISION 23PAGE 66 OF 87ATTACHMENT 8(Page 2 of 2)Critical Organ Dose Factors DOMINIONVPAP-2103N REVISION 23PAGE 67 OF 87ATTACHMENT 9(Page 1 of 5)Radiological Environmental Monitoring ProgramExposure Pathway Number of Sample and Collection Type and Frequency o[and/or Sample Sample Location (NOTE 2) Frequency Analysis1. DIRECTRADIATION (NOTE 3)36 routine monitoring
- stations, either with two ormore dosimeters or withone instrument formeasuring and recording dose rate continuously, tobe placed as follows:1) An inner ring ofstations, one in eachenvironmental GAMMA DOSEmeteorological s twithin the sit ary2) An outer ri fi ---stations e i chenvirq1rhep~l "e tor Quarterly Quarterly thi8 ge fromalance of thetio s to be placed incial interest areassuch as population
- centers, nearbyresidences,
- schools, andin I or 2 areas to serve ascontrol stationsAdditional TFL~s are n aced in anoronriate emer~encv nian sectors.
These are not nart of the environmental
?rogram.
Collect and report with environmental TLDs.
DOMINIONVPAP-2103N REVISION 23PAGE 68 OF 87ATTACHMENT 9(Page 2 of 5)Radiological Environmental Monitoring ProgramExposure Pathway Number of Sample and Collection Type and Frequency ofand/or Sample Sample Location (NOTE 2) Frequency Analysis2. AIRBORNESamples from 5 locations:
a) 3 samples from close tothe 3 site boundarylocations (in different ioI e Canistersectors) of the highest 1 Analysis, weeklycalculated historical annual average ground Conti iRadioiodines and level D/Q sa erParticulates b) 1 sample from the ra. wivicinity of a communi,:a eco tion Particulate Samplerhaving the highest Gross beta radioactivity calculated annu analysis following filteraverage grou e < change; (NOTE 4)D/Q c) 1 samp om ntrol Gamma isotopic analy-locat 5 kI sis of composite (byi "tanqin east location) quarterlyut direction (NOTE 5)J. WAYERBURNE S I om 3 locations:
) ample upstream Gamma isotopic analysisa) Surfa b1 sample downstream Grab Monthly mo steyfor tritiumc) 1 sample from cooling analysis quarterly lagoonl oamma isotopic and tritiumb) Ground Sample from 1 or 2 sources Grab Quarterly analysis quarterly (NOTEonly if likely to be affected 5)1 sample from downstream Gamma isotopic analysisc) Sediment area with existing or Semi-Annually potential recreational value DOMINIONVPAP-2103N REVISION 23PAGE 69 OF 87ATTACHMENT 9(Page 3 of 5)Radiological Environmental Monitoring ProgramExposure Pathway Number of Sample and Collection Type and Frequency ofand/or Sample Sample Location (NOTE 2) Frequency Analysis4.
a) Samples from milkinganimals in 3 locations within5 km that have the highestpotential.
If there are none,then I sample from milkinganimals in each of 3 areasa) Milk between 5 to 8 km where M I mma isotopic (NOTE 5)(NOTE 7) doses are calculated to be and 1131 analysis monthlygreater than 1 mrem per yr(NOTE 6)b) I sample from milkinanimals at a control I(15-30 km in theprevalent win irea) I sampleo n ia ndrecreati lyi p ntspecies unh, catfish)b) Fish and in I discharge Gamma isotopic
.on edibleInvertebrates Seinulyportions s le of same species ininfluenced by plantis.N.discharge of an edible broadleaf vegetation grown nearesteach of two different offsitelocations of highest predicted historical annual average Monthly ifgroud lvel /Q f n-ilkGamma isotopic (NOTE 5)c) Food Products ground level D/Q if milk available, or and 1131 analysissampling is not performed at harvestb) 1 sample of broad leafvegetation grown 15-30 km inthe least prevalent winddirection if milk sampling isnot performed DOMINION VPAP-2103N REVISION 23PAGE 70 OF 87ATTACHMENT 9(Page 4 of 5)Radiological Environmental Monitoring ProgramNOTE 1: The number, media, frequency, and location of samples may vary from site to site. Thistable presents an acceptable minimum program for a site at which each entry is applicable.
Local site characteristics must be examined to determine if pathways not covered by thistable may significantly contribute to an individual's dose and be included in the samplingprogram.NOTE 2: For each and every sample location in Environmental Sampli ons ttachment 10),specific parameters of distance and direction sector fronml c rli the reactor, andadditional description where pertinent, shall be provio i n ac nt 10. Refer toRadiological Assessment Branch Technical Positi and t G-0 133, Preparation ofRadiological Effluent Technical Specificatio r ea ower Plant. Deviations arepermitted from the required sampling sche e , eci ns are unattainable due tohazardous conditions, seasonal unava ty, ction of automatic samplingequipment and other legitimate reaso, p mens are unattainable due to samplingequipment malfunction, every aal de to complete corrective action before theend of the next samplingp i o ions from the sampling schedule shall bedocumented in the An R io'l cal Environmental Operating Report pursuant toStep 6.7.1. It is rec at imes, it may not be possible or practicable to continueto obtain samp of t me of choice at the most desired location or time. In theseinstances, su--le rl' native media and locations may be chosen for the particular pathwayin questi and roiate substitutions made within 30 days in the radiologicale'- toring program.
In lieu of a Licensee Event Report and pursuant toSt entify the cause of the unavailability of samples for that pathway and identifythe rie," tions for obtaining replacement samples in the next Annual Radioactive Effluent Release Report, and include revised figures and tables from the ODCM reflecting the new locations in the report.
DOMINION VPAP-2103N REVISION 23PAGE 71 OF 87ATTACHMENT 9(Page 5 of 5)Radiological Environmental Monitoring ProgramNOTE 3: One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters.
For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to beone phosphor; two or more phosphors in a packet are considered as two or more dosimeters.
Film badges shall not be used as dosimeters for measuring direct The 36 stationsare not an absolute number. The number of direct radiation ni st ions may bereduced according to geographical limitations, e.g., at anan*te, sectors will beover water so that the number of dosimeters may be red cecor ly. The frequency ofanalysis or readout for TLD systems will depend n t eristics of the specificsystem used and should be selected to obtainom dos nformation with minimalfading.NOTE 4: Airborne particulate sample filters sh an or gross beta radioactivity 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />sor more after sampling to allow for r oron daughter decay. If gross beta activityin air particulate samples is gr an es the yearly mean of control samples,gamma isotopic analysis s l',i.d on the individual samples.NOTE 5: Gamma isotopic anal is idlification and quantification of gamma-emitting radionuclides that triI ble to effluents from the facility.
It %X'7NOTE 6: The dose shal"' ated r the maximum organ and age group, using the methodology and parameter tN DCM.NOTE 7: If mi a not be performed, use item 4.c (Page 3 of 5, Radiological E *ro t-onitoring Program (Attachment 9)).NOTE: ally, the following TLDs are placed in the indicated locations for Emergency Plan requirements.
This is due to the fact that Emergency Plan and Environmental Plangrid centers are in different locations.
These TLDs are collected quarterly inconjunction with Environmental Sector TLDs.EP Sector TLD Designator LocationA EPSAI/2 On fence, U-2 side, Intake Structure F EPSF 3/4 On power pole on island (across from FPPH)R EPSR 5/6 On door of Substation "M"P EPSP 9/10 On/near Switchyard gateJ EPSJ 7/8 NW corner of the Generator Rewind Bldg.
DOMINIONVPAP-2103N REVISION 23PAGE 72 OF 87ATTACHMENT 10(Page 1 of 5)Environmental Sampling Locations Distance and Direction From Unit No. 1Sample Location Station Distance Direction Collection RemarksMedia No. (Miles) Frequency Environmental NAPS Sewage 01 0.20 NE Quarterly
& On-SiteTLDs Treatment Plant A n nualyFrederick's Hall025.30SSWualyMineral,VA 03 7.10 WS Q ri)nWares Crossroads 04 5.10 FrlyallyRoute 752 05 4.20 NNE uarterly
&AnnuallySturgeon's Creek05AMarina AnnuallyLevy, VA 06 Quarterly
&SE_ AnnuallyBumpass, VA SSE Quarterly
&AnnuallyEnd of Route 685 1.00 WNW Quarterly
& Site Boundary// AnnuallyRoute 700 < 1.00 WSW Quarterly
& Site BoundaryAnnually0.93 SSE Quarterly
& Site BoundaryAnnually"A sp en H i Q u arterlynuall Orange, << 24 22.00 NW Quarterly
&ControlBea Co^ g Towe 0.06 N uartery On-Sitexe N-2/34 2.04 N Quarterly P iLot "C" NNE-3/35 0.24 NNE Quarterly On-SiteGood Hope Church NNE-4/36 3.77 NNE Quarterly Parking Lot "B" NE-5/37 0.20 NE Quarterly On-SiteBogg's Drive NE-6/38 1.46 NE Quarterly Weather Tower Fence ENE-7/39 0.36 ENE Quarterly On-SiteRoute 689 ENE-8/40 2.43 ENE Quarterly Near Training Facility E-9/41 0.30 E Quarterly On-Site"Morning Glory Hill" E-10/42 2.85 E Quarterly Island Dike ESE- 11/43 0.12 ESE Quarterly On-Site(toute 622t,5 L- 1 Z1444. /UL11SLQuarterly DOMINIONVPAP-2103N REVISION 23PAGE 73 OF 87ATTACHMENT 10(Page 2 of 5)Environmental Sampling Locations Distance and Direction From Unit No. 1Sample Location Station Distance Direction Collection RemarksMedia No. (Miles) _ _ciFrequencyR EnvironmentalI TLDs Biology Lab SE-13/45 0.64 SE Quarterly On-SiteRoute 701(Dam Entrance)
SE- 14/465.88SE,
- GaN"Aspen Hills" SSE-15/47 0.93 5o Btoundary Elk Creek SSE-16/48 2.33 NAPS Access Road S-17/49 0.36 // ýuarterly On-SiteElk Creek Church S-18/50 "_ " Quarterly NAPS Access Road SSW-19/51
.2 Quarterly On-SiteRoute 618 SSW-20/5 \.< SSW Quarterly 500KV Tower SW-2 53 SW Quarterly On-SiteRoute 700 -.96 SW Quarterly At NAPS, on pole, SE ofswitchyard, entrance o , 0.38 WSW Quarterly On-SiteRoute 700 -24/56 1.00 WSW Quarterly SiteBoundaryS W-25/57 0.32 W Quarterly On-SiteS witchyoý,))/
Route 68 W-26/58 1.55 W Quarterly F out 85 WNW-27/59 1.00 WNW Quarterly BndrBoundaryWNW-28/60 1.40 WNW Quarterly d n Area North NW-29/61 0.52 NW Quarterly On-SiteLake Anna Campground NW-30/62 2.54 NW Quarterly
- 1/#2 Intake NNW-31/63 0.07 NNW Quarterly On-SiteRoute 208 NNW-32/64 2.21 NNW Quarterly Bumpass Post Office C-1/2 7.30 SSE Quarterly Orange, VA C-3/4 22.00 NW Quarterly ControlMineral, VA C-5/6 7.10 WSW Quarterly Louisa, VAC-7/811.54WSWQuarterly Control DOMINIONVPAP-2103N REVISION 23PAGE 74 OF 87ATTACHMENT 10(Page 3 of 5)Environmental Sampling Locations Distance and Direction From Unit No. 1Sample Location Station Distance Direction Collection RemarksMedia No. (Miles) Frequency Airborne NAPS Sewage 01 0.20 NE Weekly On-SiteTreatment PlantParticulate Biology Lab 01-A 0.64 SE Wee On-Siteand Frederick's Hall 02 5.30 SSW yefd \Radioiodine
- Mineral, VA 03 7.10 WSW e )Wares Crossroads 04 5.10 WNW kRoute 752 05 4.20 NNE eeeSturgeon's Creek 05A 2.04 ZW:IMarinaLevy, VA .06 4.70/Bumpass, VA 07 7. / WeeklyEnd of Route 685 21 e"0. 0V Weekly Site BoundaryRoute 700 22 1 , \WSW Weekly Site Boundary"Aspen Hills" ;3-\ ..SSE Weekly Site BoundaryOrange, VA 4 NW Weekly ControlSurtace Water Waste Heat Treatme[Reference Facility (Second 3.37 SSE Monthly3.1.311 Cooling Lagoon)(up. stream /09A 12.9 WNW Monthly ControlBridge) ____No Lnna eY 11 5.80 SE MonthlyaGiroundwater/
_(well wate Lab 01A 0.64 SE Quarterly (well water)\Aquatic M eat Treatment Semi-Sediment Faci-ity (Second 08 3.37 SSE AnnuallySedient Cooling Lagoon) AnalNorth Anna River(upstream)
Rt 669 09A 12.9 WNW Semi- ControlBridge (Brook's AnnuallyBridge)North Anna River 11 5.80 SE Semi-(downstream)
AnnuallyShoreline Soil Lake Anna 08 3.37 SSE Semi-Annually Soil NAPS Sewage 01 0.20 NE Once per 3 yrs On-SiteTreatment Plant DOMINIONVPAP-2103N REVISION 23PAGE 75 OF 87ATTACHMENT 10(Page 4 of 5)Environmental Sampling Locations Distance and Direction From Unit No. 1Sample Location Station Distance Direction Collection RemarksMedia No. (Miles) Frequency Soil Fredericks Hall 02 -5.30 SSW Once per 3 yrs(continued)
- Mineral, VA 03 7.10 WSW Once per 3rsWares Crossroads 04 5.10 WNW OnceRoute 752 05 4.20 NNE One 3 yrs)Sturgeon's Creek2.04 N /ncp erMarinaLevy, VA 06 4.70 EE--yrBumpass, VA 07 7.30 c er3 yrsEnd of Route 685 21 1.00 ,S ce per 3 yrs Site BoundaryRoute 700 22 ,,0ý1.0 / /Sn Once per 3 yrs Site Boundary"Aspen Hills" 23 3.SS Once per 3 yrs Site BoundaryOrange, VA 24 2. Once per 3 yrs ControlMilk Lakeside Dairy 1 .50 NW Monthly(Charles Harris)Waste Heat Treatment Fish Facility (Second 3.37 SSE Semi-Annually Cooling Lagoon)w,,Z Lake Orange,,
16.50 NW Semi-Annually ControlFood Products Stagecoac oad)) 4B varies NNE Monthly(Edible if available, broadleaf Route 61 15 varies SE or at harvestvegetation')
<\!1 varies NWControl n 26 varies S__._sp ills" Area 23 varies SSEa. If edible broa eaf vegetation is unavailable, non-edible vegetation of similar leafcharacteristics may be substituted.
DOMINION VPAP-2103N REVISION 23PAGE 76 OF 87ATTACHMENT 10(Page 5 of 5)Environmental Sampling Locations NOTE: Additionally, the following TLDs are placed in the indicated locations for Emergency Plan requirements.
This is due to the fact that Emergency Plan and Environmental Plangrid centers are in different locations.
These TLDs are collected quarterly inconjunction with Environmental Sector TLDs.EP Sector TLD Designator Location
" NA EPSAI/2 On fence, U-2 side, Intake Stru reF EPSF 3/4 On power pole on island (acrd frV 1WR EPSR 5/6 On door of Substation "M"P EPSP 9/10 On/near Switchyard gJ EPSJ 7/8 NW corner of the G ator i Bldg.NOTE: ISFSI well water samples are obtaine on 'onal Use Permit issued by theCounty of Louisa.'K,?'0 DOMINIONVPAP-2103N REVISION 23PAGE 77 OF 87ATTACHMENT 11(Page 1 of 2)Detection Capabilities for Environmental Sample Analysis*
LOWER LIMIT OF DETECTION (LLD)NOTE 1: Requ dNNecti kapabilities for thermoluminescent dosimeters used for environmental ma r given in Regulatory Guide 4.13.NOTE 2: This i t not mean that only these nuclides are to be detected and reported.
Other peaksthat are measurable and identifiable, together with the above nuclides, shall also beidentified and reported.
NOTE 3: LLD for the drinking water samples.
Drinking water includes samples from Lake Anna andwell samples analyzed as part of the REMP. The LLD for the non-drinking water samplesis 10 pCi/1.NOTE 4: No LLD for precipitation water due to short-half lives of these nuclides.
DOMINION VPAP-2103N REVISION 23PAGE 78 OF 87ATTACHMENT 11(Page 2 of 2)Detection Capabilities for Environmental Sample AnalysisLOWER LIMIT OF DETECTION (LLD) (NOTE 3)NOTE 1: For a particular measurement system (which may include radiochemical separation):
4.66 sbLLD=
E e V
- 2.22E+06
- Y
- e-(2-(Where:LLD the "a priori" (before the fact) Lowe e ion as defined above(as microcuries per unit mass or,,e) ee, ubsection 4.9)Sb= the standard deviation of the b gr d ing rate or of the counting rateof a blank sample as a (a unt per minute, cpm)E = the counting efficie c nts per disintegration)
V = the sample o mass or volume)2.22E+06
= the n er di egrations per minute (dpm) per microcurie Y = iochemical yield (when applicable)
, dt ioactive decay constant for the particular radionuclide At t elapsed time between sample collection (or end of the sample period) and time of counting (for environmental
- samples, notplant effluent samples)Typical values of E, V, Y and At should be used in the calculation.
The LLD is an "a priori" (before the fact) limit representing the capability of a measurement system and not a "posteriori" (after the fact) limit for a particular measurement.
DOMINIONVPAP-2103N REVISION 23PAGE 79 OF 87ATTACHMENT 12(Page 1 of 1)Reporting Levels for Radioactivity Concentrations in Environmental SamplesWater Airborne Fish Milk Food ProductsAnalysisParticulate orAnalysis (pCi/l) Gases (pCicm3) (pCi/kg, wet) (pCi/I) (pCi/kg, wet)(NOTE 1)H-3* 20,000Mn-54 1,000 30,000Fe-59 400 10,000Co-58 1,000 30,000Co-60 300Zn-65 300 0Zr-Nb-95 4001-131 2111120.9 3 100Cs- 134 30 60 1,000Cs- 137 50 70 2,000Ba-La-140 200 300NOTE 1: For drinking water DOMINION VPAP-2103N REVISION 23PAGE 80 OF 87ATTACHMENT 13(Page 1 of 8)Meteorological, Liquid, and Gaseous Pathway Analysis1.0 METEOROLOGICAL ANALYSIS1.1 PurposeThe purpose of the meteorological analysis was to determine the annual average X/Q and D/Qvalues at critical locations around the Station for ventilation vent (ground level) and processvent (mixed mode) releases.
The annual average X/Q and D/Q valu ere d to perform adose pathway analysis to determine both the maximum exposed i vi at boundary andmember of the public. The X/Q and D/Q values resulting in m u posures wereincorporated into the dose factors in Gaseous Effluent D achment 5) andCritical Organ Dose Factors (Attachment 8).1.2 Meteorological Data, Parameters, and Met loOnsite meteorological data for the period J r 9, through December 31, 1981, wereused in calculations.
These data include I ind direction, and differential temperature for the purpose of dete ig-- in quency distributions for those releasescharacterized as ground level (e.( .,ve vent), and those characterized as mixed mode(i.e., process vent). The por " s ase characterized as ground level were based onAT158.9ft_28.2ft and 28.2 fo , and the portions characterized as mixed mode werebased on AT158,9ft-, t wind data.Z/Q's and D/Q's e culated using the NRC computer code "XOQDOQ -Program forthe Meteor ical lu'ion of Routine Effluent Releases at Nuclear Power Stations,"9 code is based upon a straight line airflow model implementing theassumnt ined in Section C (excluding C1a and Clb) of Regulatory Guide 1.111,"Method s'timating Atmospheric Transport and Dispersion of Gaseous Effluents inRoutine Releases from Light-Water-Cooled Reactors."
The open terrain adjustment factors were applied to the Z/Q values as recommended inRegulatory Guide 1.111. The site region is characterized by gently rolling terrain so openterrain correction factors were considered appropriate.
The ground level ventilation ventrelease calculations included a building wake correction based on a 1516 m2 containment minimum cross-sectional area.
DOMINION VPAP-2103N REVISION 23PAGE 81 OF 87ATTACHMENT 13(Page 2 of 8)Meteorological, Liquid, and Gaseous Pathway AnalysisThe effective release height used in mixed mode release calculations was based on a processvent release height of 157.5 ft, and plume rise due to momentum for a vent diameter of 3 in.with plume exit velocity of 100 ft/sec. Ventilation vent, and vent releases other than from theprocess vent, are considered ground level as specified in Regulatory Guide 1.111 for releasepoints less than the height of adjacent solid structures.
Terrain elevae obtained fromNorth Anna Power Station Units 1 and 2, Virginia Electric and Py Final SafetyAnalysis Report Table 11C.2-8.X/Q and D/Q values were calculated for the nearest site ent, milk cow, andvegetable garden by sector for process vent and yen i n ven leases at distances specified from North Anna Power Station Annual Environ ta S ata for 1981. X/Q values werealso calculated for the nearest lake shoreline b bor e process vent and ventilation ventreleases.
According to the definition for sho in G-0133, "Preparation of Radiological Effluent Technical Specification r Power Stations,"
- October, 1978, some gaseousreleases may fit this catego4riri waste gas decay tank releases and containment purges.However, these releases i de " ong term for dose calculations as past releases wereboth random in tim an tion as evidenced by reviewing past release reports.Therefore, the u al average concentrations is appropriate according to NUREG-0133.
The X/Q an Q Nalculated from 1981 meteorological data are comparable to thevalues nte North Anna Power Station IJFSAR.1.3 Results--@
/The X/Q value that resulted in the maximum total body, skin and inhalation exposure forventilation vent releases was 9.3E-06 sec/m3 at a site boundary location 1416 metersSE sector. For process vent releases, the site boundary X/Q value was 1.2E-06 sec/m3 at alocation 1513 meters S sector. The shoreline X/Q value that resulted in the maximum inhalation exposure for ventilation vent releases was 1.OE-04 sec/m3 at a location 274 meters NNE sector.The shoreline X/Q value for process vent was 2.7E-06 sec/m3 at a location 274 meters NNEsector.
DOMINION VPAP-2103N REVISION 23PAGE 82 OF 87ATTACHMENT 13(Page 3 of 8)Meteorological, Liquid, and Gaseous Pathway AnalysisThe original pathway analysis indicated that the maximum exposure from 1131, 1133, and fromall radionuclides in particulate form with half-lives greater than 8 days was through thegrass-cow-milk pathway.
The D/Q value from ventilation vent releases resulting in themaximum exposure was 2.4E-09 per m2 at a location 3250 meters N sector. For process ventreleases, the D/Q value was 1.1 E-09 per m2 at a location 3250 meters For tritium, theZ/Q value from ventilation vent releases resulting in the maximt sure I rthe milkpathway was 7.2E-07 sec/m3, and 3.9E-07 sec/m3 for proces n e a location 3250meters N sector.Analysis using 2007 release data indicates that the m ,limiti Cal organ is the child'sthyroid.
The location is 1593 meters SSE sector r o t releases, the D/Q is 1.IE-8.For tritium releases, the X/Q values at this loca" e --7 for the process vent and3.3E-6 for the ventilation vents.2.0 LIQUID PATHWAY ANALYS2.1 Purpose 'rmThe purpose of the liquid an is was to determine the maximum exposed memberof the public in unrest a ai esult of radioactive liquid effluent releases.
The analysisincludes a determi on/mos estrictive liquid pathway, most restrictive age group, andcritical organ. T h- is is required for Subsection 6.2.2.2 Data, Psa Mthodology
- Initial, i e liquid effluent release data for the years 1979, 1980, and 1981 werecompile o e North Anna Power Station semi-annual effluent release reports.
The data foreach year, a ong with appropriate site specific parameters and default selected parameters, wereentered into the NRC computer code LADTAP as described in NUREG-0133.
DOMINION VPAP-2103N REVISION 23PAGE 83 OF 87ATTACHMENT 13(Page 4 of 8)Meteorological, Liquid, and Gaseous Pathway AnalysisRe-concentration of effluents using the small lake connected to larger water body model wasselected with the appropriate parameters determined from Table 3.5.3.5, Design Data forReservoir and Waste Heat Treatment Facility from Virginia Electric and Power Company,Applicant's Environmental Report Supplement, North Anna Power Station, Units 1 and 2,March 15, 1972. Dilution factors for aquatic foods, shoreline, and dater were set toone. Transit time calculations were based on average flow rates. pa meters weredefaults selected by the LADTAP computer code.Beginning in 1997, the activity by nuclide released in ti s entered into theNorth Anna Power Station liquid pathway critical alcu ons spreadsheet, whichcalculates the most limiting age group total bod I an. This Process is repeatedannually.
2.3 ResultsInitially, the fish pathway resulted' rg e. The critical organ each year was the liver,and the adult and teenage age ~ the same organ dose. However, since the adulttotal body dose was great n et total body dose for each year, the adult was selectedas the most restrictive, a B ning in 1997, the most limiting age group for both totalbody and critical or is lcu , from .the spreadsheet for North Anna Power Station liquidpathway critical a culations.
DOMINION VPAP-2103N REVISION 23PAGE 84 OF 87ATTACHMENT 13(Page 5 of 8)Meteorological, Liquid, and Gaseous Pathway Analysis3.0 GASEOUS PATHWAY ANALYSIS3.1 PurposeA gaseous effluent pathway analysis was performed to determine the location that would resultin the maximum doses due to noble gases for use in demonstrating cor liance withSteps 6.3.l.a.
and 6.3.3.a.
The analysis also included a determinatio<fdi h tical pathway,location of maximum exposed member of the public, and the c ' al" an the maximumdose due to 1131, 1133, tritium, and for all radionuclides in pa ul for ith half-lives greater than 8 days for use in demonstrating compliance e s in Step 6.3.4.a.
- 1. Inaddition, the analysis included a determination of thc itic y, maximum age group,and sector location of an exposed individual thro th i a 'on pathway from 1131, 1133,tritium, and particulates with half-lives greateK a demonstrate compliance withStep 6.3.1.a.3.2 Data, Parameters, and MethodohAnnual average X/Q values were ,s described in Section 1 of this attachment, forthe nearest site boundary in h i/'onal sector and at other critical locations beyond thesite boundary.
The largest uea determined to be 9.3E-06 sec/m3 at site boundary forventilation vent rele s a 1416 meters SE direction, a'nd 1.2E-06 sec/m3 at siteboundary for .pr releases at a location 1513 meters S direction.
The maximum dosesto total body and s i a ir doses for gamma and beta radiation due to noble gases, wouldbe at t es & .und locations.
The doses from both release points are summed incalcul on a ate total maximum dose.Step 6.3.1@ se limits apply specifically to the inhalation pathway.
Therefore, the locations and X/Q values determined for maximum noble gas doses can be used to determine themaximum dose from 1131, 1133, tritium, and for all radionuclides in particulate form withhalf-lives greater than 8 days for the inhalation pathway.
DOMINION VPAP-2103N REVISION 23PAGE 85 OF 87ATTACHMENT 13(Page 6 of 8)Meteorological, Liquid, and Gaseous Pathway AnalysisThe NRC computer code GASPAR, "Evaluation of Atmospheric Releases,"
Revised 8/19/77,was run using 1979, 1980 and 1981 North Anna Power Station Gaseous Effluent ReleaseReport data. Doses from 1131, 1133, tritium, and particulates for the inhalation pathway werecalculated using the 9.3E-06 sec/m3 site boundary X/Q. Except for the source term data and theX/Q value, computer code default parameters were used. Results for indicated thatthe critical age group was the child and the critical organ was th d for e inhalation pathway.The gamma and beta dose factors Kivv, Livv, Mivv, an I us Effluent DoseFactors (Attachment
- 5) were obtained by performing its co rsion of the appropriate dosefactors from Table B-1, Regulatory Guide 1.109 ev. , yr per Ci/m3 or mrad/yr perCi/m3, and multiplying by the ventilation vent s nd ',/Q value of 9.3E-06 sec/m3.Thesame approach was used in calculating t a eta dose factors Kipv, Lipv, Mipv, andNipv in Gaseous Effluent Dose Facto MA'irt 5) using the process vent site boundaryX/Q value of 1.2E-06 sec/m3.The inhalation pathway do act rs and Pipv in Gaseous Effluent Dose Factors(Attachment
- 5) were calcu sin he following equation:
'(B ) DFAi(x/Q)
(mrem/yr per Curie/sec)
(29-1)where:K' o f unit conversion, 1E+12 pCi/CiBR the eathing rate of the child age group, 3700 m3/yr, from Table E-5, Regulatory
- i lel.109, Rev.1DFAi the thyroid organ inhalation dose factor for child age group for the ith radionuclide, in mrem/pCi, from Table E-9, Regulatory Guide 1.109, Rev. 1X/Q the ventilation vent site boundary X/Q, 9.3E-06 sec/m3, or the process vent siteboundary X/Q, 1.2E-06 sec/m3, as appropriate DOMINION VPAP-2103N REVISION 23PAGE 86 OF 87ATTACHMENT 13(Page 7 of 8)Meteorological, Liquid, and Gaseous Pathway AnalysisStep 6.3.4.a.,
requires that the dose to the maximum exposed member of the public from 1131,1133, tritium, and from all radionuclides in particulate form with half-lives greater than 8 daysbe less than or equal to the specified limits. Dose calculations were performed for an exposedmember of the public within site boundary unrestricted areas, and to an exposed member of thepublic beyond site boundary at locations identified in the North Ann tation AnnualEnvironmental Survey Data for 1981.It was determined that the member of the public within site n1d be using LakeAnna for recreational purposes a maximum of 2232 ho assumed that thismember of the public would be located the entire 22. ours a h ke shoreline with thelargest annual X/Q of a.OE-04 at a location 274 er, tor. The NRC computer codeGASPAR was run to calculate the inhalation do is ii vidual. The GASPAR results werecorrected for the fractional year the me r " .c would be using the lake.Using the NRC computer code G an al average X/Q and D/Q values obtained asdescribed in Section 1 of this a t, ember of the public receiving the largest dosebeyond site boundary was mj e be located'1432 meters N sector. The critical pathwaywas vegetation, the maxim pos age group was the child, and the critical organ was thethyroid.
QPathway analysis u dicate that existing
- pathways, including ground and inhalation, within five tis of Nth nna Power Station, yield Ri dose factors less than those determined for the ati .erence 3.1.32]The R I, a Mipv dose factors, except for tritium, in Critical Organ Dose Factors(Attachment
- 8) were calculated by multiplying the appropriate D/Q value with the following equation:
K ' _' A +_ ) -U StL iSt, h -)]= L[Yv(Xri
+ w)](DFLi)[UclFLe C+ Ufge j (29-2)where:K' = a constant of unit conversion, 1E+12 pCi/CiYv = vegetable areal density in Kg/mi2 DOMINION VPAP-2103N REVISION 23PAGE 87 OF 87ATTACHMENT 13(Page 8 of 8)Meteorological, Liquid, and Gaseous Pathway AnalysisUcd = child leafy vegetable consumption rate, 26 Kg/yrUc= child stored vegetable consumption rate, 520 Kg/yrr = fraction of deposited activity retained on vegetation, 1.0 for radioiodine, and0.2 for particulates DFLi = thyroid ingestion dose factor for the ith radionuclide for the em/pCi,-from Table E-13, Regulatory Guide 1.109, Rev. 1Xi = decay constant for the ith radionuclide, in sec-1, fro ocrXw = decay constant for removal of activity of leaf an fa by weathering, 5.73E-07 sec-1 (corresponding to a 14 day htf = time between harvest of leafy vegetation est 8.60E+4, in secondsth = time between harvest of stored eget n n on, 5.18E+6, in secondsfL fraction of annual intake of leaf tI locally, 1.0 (dimensionless) fg = fraction of annual intake of stol" I. grown locally, 0.76 (dimensionless)
Parameters used in the above equ re ed from NUREG-0133 and Regulatory Guide 1.109, Revision 1Since the concentration oti in 'etation is based on the airborne concentration ratherthan the deposition, t -Dose Factors (Attachment 8)for tritium were calculated by multiplying t by the appropriate X/Q:by multplyinequation
.K K U fL+ U f](DFLj)a[O.75(O.5/H)]
(29-3)where:K"' = a constant of unit conversion 1 E+03 gm/kgH = absolute humidity of the atmosphere, 8.0, gm/rm30.75 = the fraction of total feed that is water0.5 = the ratio of the specific activity of the feed grass to the atmospheric waterOther parameters have been previously defined.