ML15118A534
| ML15118A534 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/20/2015 |
| From: | Lawrence D C Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 15-150 | |
| Download: ML15118A534 (110) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANYRICHMOND, VIRGINIA 23261April 20, 2015United States Nuclear Regulatory CommissionAttention: Document Control DeskWashington, DC 20555-0001Serial No.15-150SS&L/JSA RODocket Nos. 50-28050-281License Nos. DPR-32DPR-37Gentlemen:VIRGINIA ELECTRIC AND POWER COMPANYSURRY POWER STATION UNITS I AND 2ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTEnclosed is the Surry Power Station Annual Radioactive Effluent Release Report forJanuary 1, 2014 through December 31, 2014. The report, submitted pursuant to SurryPower Station Technical Specification 6.6.B.3, includes a summary of the quantities ofradioactive liquid and gaseous effluents and solid waste released during the 2014calendar year, as outlined in Regulatory Guide 1.21, Revision 1, June 1974.If you have any further questions, please contact Jason Eggart at 757-365-2010.Sinceraelv. AD6ugla(A. LawrenceDirector Safety & LicensingSurry Power StationAttachmentCommitments made in this letter: Nonecc: U. S. Nuclear Regulatory CommissionRegion IIMarquis One Tower245 Peachtree Center Ave., NE Suite 1200Atlanta, Georgia 30303-1257NRC Senior Resident InspectorSurry Power Station Serial No.15-150SPS Annual Rad Effluent ReportDocket Nos.: 50-280, 50-281ATTACHMENT 12014 Annual Radioactive Effluent Release ReportSURRY POWER STATION UNITS 1 AND 2VIRGINIA ELECTRIC AND POWER COMPANY Surry Power Station2014 Annual RadioactiveEffluent Release Reporti0Dominnon ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTSURRY POWER STATIONJanuary 1, 2014 through December 31, 2014Prepared By: 4P. F. BlountHealth PhysicistReviewed By: 2, A. /-P. R. HarrisSupervisor Radiological AnalysisReviewed By: K?Supervisor Health Physics Technical ServicesApproved By: _ )7Mna r J. W. Eggaro n dCManager Radiological Protection and Chemistry ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTFOR THESURRY POWER STATIONJanuary 1, 2014 through December 31, 2014IndexSection No.1234Subject PageExecutive Summary IPurpose and Scope 2Discussion 3Supplemental Information 4Attachment 1 Effluent Release DataAttachment 2 Annual and Quarterly DosesAttachment 3 Revisions to Offsite DoseCalculation Manual (ODCM)Attachment 4 Major Changes to RadioactiveLiquid, Gaseous and Solid WasteTreatment SystemsAttachment 5 Inoperability of Radioactive Liquidand Gaseous Effluent MonitoringInstrumentationAttachment 6 Unplanned ReleasesAttachment 7 Lower Limit of Detection (LLD)for Effluent Sample AnalysisAttachment 8 Industry Ground Water Protection Initiative FORWARDThis report is submitted as required by Appendix A to Operating License Nos. DPR-32 and DPR-37, Technical Specifications for Surry Power Station, Units 1 and 2, Virginia Electric and PowerCompany, Docket Nos. 50-280, 50-281, Section 6.6.B.3.
EXECUTIVE SUMMARYANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTThe Annual Radioactive Effluent Release Report describes the radiological effluent controlprogram conducted at Surry Power Station during the 2014 calendar year. This documentsummarizes the quantities of radioactive liquid and gaseous effluents and solid waste released fromSurry Power Station in accordance with Regulatory Guide 1.21, "Measuring, Evaluating, andReporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid andGaseous Effluents from Light-Water-Cooled Nuclear Power Plants", Revision 1, June 1974. Thereport also includes an assessment of radiation doses to the maximum exposed member of thepublic due to the radioactive liquid and gaseous effluents.During this reporting period, there were no unplanned liquid or gaseous effluent releases asclassified according to the criteria in the Offsite Dose Calculation Manual.Based on the 2014 effluent release data, 10CFR50 Appendix I dose calculations were performed inaccordance with the Offsite Dose Calculation Manual. The dose calculations are as follows:I. The total body dose due to liquid effluents was 2.04E-04 torem, which is3.40E-03% of the 6 mrem dose limit. The critical organ doses due to liquid effluents,GI-LLI and Liver respectively, were 3.22E-04 mrem and 1.99E-04 mrem. These dosesare 1.61E-03% and 9.95E-04% of the respective 20 mrem dose limit.2. The air dose due to noble gases in gaseous effluents was 2.OOE-06 mrad gamma, whichis 1.OOE-05% of the 20 mrad gamma dose limit, and 4.25E-06 mrad beta, which is1.06E-05% of the 40 mrad beta dose limit.3. The critical organ dose from gaseous effluents due to 1-131, 1-133, H-3, andparticulates with half-lives greater than 8 days is 1.19E-01 mrem, which is3.97E-01% of the 30 mrem dose limit.There were no major changes to the radioactive liquid, gaseous or solid waste treatment systemsduring this reporting period.There was one change made to VPAP-2103S, Offsite Dose Calculation Manual, during thisreporting period. Attachment 3 provides the changes to VPAP-2103S.In accordance with the Nuclear Energy Institute (NED Industry Ground Water Protection Initiative,analysis results of ground water monitoring locations not included in the RadiologicalEnvironmental Monitoring Program (REMP), will be included in this report. Ground watermonitoring well sample results are provided in Attachment 8.1 Based on the radioactivity measured and the dose calculations performed during this reportingperiod, the operation of Surry Power Station has resulted in negligible radiation dose consequencesto the maximum exposed member of the public in unrestricted areas.Purpose and ScopeAttachment 1 includes a summary of the quantities of radioactive liquid and gaseous effluents andsolid waste as outlined in Regulatory Guide 1.21, with data summarized on a quarterly or annualbasis following the format of Tables 1, 2 and 3 of Appendix B, thereof. Attachment 2 of this reportincludes an assessment of radiation doses to the maximum exposed member of the public due toradioactive liquid and gaseous effluents released from the site during 2014.As required by Technical Specification 6.8.B, changes to the Offsite Dose Calculation Manual(ODCM) for the time period covered by this report are included in Attachment 3. Major changes tothe radioactive liquid, gaseous and solid waste treatment systems are reported in Attachment 4, asrequired by the ODCM, Section 6.7.2. If changes are made to these systems, the report shallinclude information to support the reason for the change and a summary of the 1OCFR50.59evaluation. In lieu of reporting major changes in this report, major changes to the radioactive wastetreatment systems may be submitted as part of the annual FSAR update.As required by the ODCM, Sections 6.2.2 and 6.3.2, a list and explanation for the inoperability ofradioactive liquid and/or gaseous effluent monitoring instrumentation is provided in Attachment 5of this report. Additionally, a list of unplanned releases during the reporting period is included inAttachment 6.Attachment 7 provides the typical lower limit of detection (LLD) capabilities of the radioactiveeffluent analysis instrumentation.As required by the ODCM, Section 6.7.5, a summary of on-site radioactive spills or leaks that werecommunicated in accordance with the Industry Ground Water Protection Initiative reportingprotocol, and sample analyses from ground water wells that are not part of the RadiologicalEnvironmental Monitoring Program are provided in Attachment 8.2 DiscussionThe basis for the calculation of the percent of technical specification for the critical organ in Table1 A of Attachment 1 is the ODCM, Section 6.3.1, which requires that the dose rate for iodine- 131,iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8days shall be less than or equal to 1500 mrem/yr to the critical organ at or beyond the site boundary.The critical receptor was the child for the first two quarters, the teen for the last two quarters; bothvia the inhalation pathway.The basis for the calculation of the percent of technical specification for the total body and skin inTable 1A of Attachment 1 is the ODCM, Section 6.3.1, which requires that the dose rate for noblegases to areas at or beyond site boundary shall be less than or equal to 500 mrem/yr to the totalbody and less than or equal to 3000 mrem/yr to the skin.The basis for the calculation of the percent of technical specification in Table 2A of Attachment 1 isthe ODCM, Section 6.2.1, which states that the concentration of radioactive material releases inliquid effluents to unrestricted areas shall not exceed ten times the concentrations specified in10CFR20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrainednoble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.OOE-04microcuries/mL.Percent of technical specification calculations are based on the total gaseous or liquid effluentsreleased for the respective quarter.The annual and quarterly doses, as reported in Attachment 2, were calculated according to themethodology presented in the ODCM. The beta and gamma air doses due to noble gases releasedfrom the site were calculated at the site boundary. The maximum exposed member of the publicfrom the release of airborne iodine- 131, iodine-133, tritium and all radionuclides in particulate formwith half-lives greater than 8 days, was a child at 2.05 miles with the critical organ being the bonevia the ingestion pathway. The maximum exposed member of the public from radioactive materialsin liquid effluents in unrestricted areas was an adult, exposed by either the invertebrate or fishpathway, with the critical organ typically being the gastrointestinal-lower large intestine. The totalbody dose was also determined for this individual.Presented in Attachment 6 is a list of unplanned gaseous and liquid releases as required by theODCM, Section 6.7.2.The typical lower limit of detection (LLD) capabilities of the radioactive effluent analysisinstrumentation are presented in Attachment 7. These LLD values are based upon conservativeconditions (i.e., minimum sample volumes and maximum delay time prior to analysis). ActualLLD values may be lower. If a radioisotope was not detected when effluent samples were analyzed,then the activity of the radioisotope was reported as Not Detected (N/D) on Attachment 1 of thisreport. When all isotopes listed on Attachment 1 for a particular quarter and release mode are lessthan the lower limit of detection, then the totals for this period will be designated as Not Applicable(N/A).3 Supplemental InformationSection 6.6.1 of the ODCM requires the identification of the cause(s) for the unavailability of milk,or if required, leafy vegetation samples, and the identification for obtaining replacement samples.As milk was available for collection during this reporting period, leafy vegetation sampling was notrequired.As required by the ODCM, Section 6.6.2, evaluation of the Land Use Census is made to determineif new sample location(s) must be added to the Radiological Environmental Monitoring Program.Evaluation of the Land Use Census conducted for this reporting period identified no change insample locations for the Radiological Environmental Monitoring Program.4 EFFLUENT RELEASE DATAJanuary 1, 2014 through December 31, 2014This attachment includes a summary of the quantities of radioactive liquid and gaseous effluentsand solid waste as outlined in Regulatory Guide 1.21, Appendix B.
TABLE IAAttachment 1Page 1 of 12EFFLUENT AND WASTE DISPOSAL ANNUAL REPORTPERIOD: 1/1/14 TO 12/31/14GASEOUS EFFLUENT-SUMMATION OF ALL RELEASESSURRY POWER STATION UNITS 1 &2A. FISSION & ACTIVATION GASES1. TOTAL RELEASE2. AVE RELEASE RATE FOR PERIODB. IODINE1. TOTAL 1-1312. AVE RELEASE RATE FOR PERIODC. PARTICULATE1. HALF-LIFE >8 DAYS2. AVE RELEASE RATE FOR PERIOD3. GROSS ALPHA RADIOACTIVITYD. TRITIUM1. TOTAL RELEASE2. AVE RELEASE RATE FOR PERIODE. CARBON-141. TOTAL RELEASE2. AVE RELEASE RATE FOR PERIODPERCENTAGE OF T.S. LIMITSCRITICAL ORGAN DOSE RATETOTAL BODY DOSE RATESKIN DOSE RATEUNITCijiCi/secCiliCi/secCiliCi/secCiCitCi/secCi;iCi/secFIRSTQUARTER8.6 1E-021.11E-02N/DN/A1.79E-052.3 1E-06N/D6.35E+008.16E-017.08E+009.10E-011.20E-022.4 1E-079.47E-08SECONDQUARTER1.30E-011.66E-02N/DN/A3.2 1E-054.08E-06N/D6.OOE+007.63E-01% EST. ERROR1.80E+012.80E+012.80E+O13.1 OE+O 11.08E+011.37E+001.90E-021.26E-064.27E-07 TABLE 1AAttachment 1Page 2 of 12EFFLUENT AND WASTE DISPOSAL ANNUAL REPORTPERIOD: 1/1/14 TO 12/31/14GASEOUS EFFLUENT-SUMMATION OF ALL RELEASESSURRY POWER STATION UNITS 1&2A. FISSION & ACTIVATION GASES1. TOTAL RELEASE2. AVE RELEASE RATE FOR PERIODB. IODINE1. TOTAL 1-1312. AVE RELEASE RATE FOR PERIODC. PARTICULATE1. HALF-LIFE >8 DAYS2. AVE RELEASE RATE FOR PERIOD3. GROSS ALPHA RADIOACTIVITYD. TRITIUM1. TOTAL RELEASE2. AVE RELEASE RATE FOR PERIODE. CARBON-141. TOTAL RELEASE2. AVE RELEASE RATE FOR PERIODPERCENTAGE OF T.S. LIMITSCRITICAL ORGAN DOSE RATETOTAL BODY DOSE RATESKIN DOSE RATEUNITCigCi/secCiliCi/secCiliCi/secCiCi[tCi/secCiptCi/secTHIRDQUARTER6.59E-038.29E-04N/DN/AN/DN/AN/D5.3 1E+006.68E-015.42E-016.82E-02L.O1E-031.27E-084.98E-09FOURTHQUARTER2.12E-032.67E-04N/DN/AN/DN/AN/D5.86E+007.37E-011.74E-012.19E-021.11 E-024.07E-091.60E-09% EST. ERROR1.80E+012.80E+012.80E+013.1OE+O1 Page 3 of 12TABLE 1BEFFLUENT AND WASTE DISPOSAL ANNUAL REPORTPERIOD: 1/1/14 TO 12/31/14GASEOUS EFFLUENTS-MIXED MODE RELEASESCONTINUOUS MODEBATCH MODESURRY POWER STATION UNITS 1&21. FISSION & ACTIVATION GASESKr-85Kr-85mKr-87Kr-88Xe-133Xe-135Xe-135mXe-138Xe-131nmXe-133mAr-41UNIT FIRST SECONDQUARTER QUARTERFIRST SECONDQUARTER QUARTERCiCiCiCiCiCiCiCiCiCiCiN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DTOTAL FOR PERIODCi N/A2. IODINES1-1311-1331-135CiCiCiN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/AN/DN/DN/DN/AN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/D8.6 1E-02N/DN/DN/DN/DN/DN/D8.61E-02N/DN/DN/DN/AN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/D7.08E+00N/D3.4 1E-04N/DN/D1.1 OE-0 11.33E-02N/DN/DN/D1.19E-035.12E-031.30E-01N/DN/DN/DN/AN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/D1.07E+01TOTAL FOR PERIOD3. PARTICULATESSr-89Sr-90Cs-134Cs-137Ba-140La-140Co-58Co-60Mn-54Fe-59Zn-65Mo-99Ce-141Ce-144C-14TOTAL FOR PERIODCi N/ACiCiCiCiCiCiCiCiCiCiCiCiCiCiCiN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DCi N/A N/A7.08E+00 1.07E+01 Page 4 of 12TABLE 1BEFFLUENT AND WASTE DISPOSAL ANNUAL REPORTPERIOD: 1/1/14 TO 12/31/14GASEOUS EFFLUENTS-MIXED MODE RELEASESCONTINUOUS MODEBATCH MODESURRY POWER STATION UNITS 1 &21. FISSION & ACTIVATION GASESKr-85Kr-85mKr-87Kr-88Xe-133Xe-135Xe-135mXe-138Xe-131mXe-133mAr-41TOTAL FOR PERIODUNIT THIRD FOURTH THIRD FOURTHQUARTER QUARTER QUARTER QUARTERCiCiCiCiCiCiCiCiCiCiCiN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DNIDN/DN/DN/DN/DN/DN/DN/DN/DN/DN/AN/DN/DN/DN/D6.59E-03N/DN/DN/DN/DN/DN/D6.59E-03N/DN/DN/DN/D2.12E-03N/DN/DN/DN/DN/DN/D2.12E-03Ci N/A2. IODINES1-1311-1331-135Ci N/DCiCiN/DN/DTOTAL FOR PERIOD3. PARTICULATESSr-89Sr-90Cs-134Cs-137Ba-140La-140Co-58Co-60Mn-54Fe-59Zn-65Mo-99Ce-141Ce-144C-14TOTAL FOR PERIODCi N/ACiCiCiCiCiCiCiCiCiCiCiCiCiCiCiN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/AN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/AN/AN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/D5.42E-0 15.24E-01N/AN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/D1.74E-011.74E-01N/DN/DN/DN/DN/DN/DCi N/AJm TABLE ICAttachment IPage 5 of 12EFFLUENT AND WASTE DISPOSAL ANNUAL REPORTPERIOD: 1/1/14 TO 12/31/14GASEOUS EFFLUENTS-GROUND LEVEL RELEASESCONTINUOUS MODEBATCH MODESURRY POWER STATION UNITS 1 &21. FISSION & ACTIVATION GASESKr-85Kr-85mKr-87Kr-88Xe-133Xe-135Xe-135mXe-138Xe-131mXe-133mAr-41UNITFIRST SECOND FIRST SECONDQUARTER QUARTER QUARTER QUARTERCiCiCiCiCiCiCiCiCiCiCiCiN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/AN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/AN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/AN/DN/DN/DN/D6.57E-04N/DN/DN/DN/DN/DN/D6.57E-04TOTAL FOR PERIOD2. IODINES1-1311-1321-135TOTAL FOR PERIOD3. PARTICULATESSr-89Sr-90Cs-134Cs-137Ba-140La-140Co-58Co-60Mn-54Fe-59Zn-65Mo-99Ce-141Ce-144C-14TOTAL FOR PERIODCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiN/DN/DN/DN/AN/DN/DN/DN/DN/DN/D1.79E-05N/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/AN/DN/DN/DN/DN/DN/D3.21E-05N/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/AN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/AN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/D5.40E-02Ci 1.79E-05 3.21E-05N/A 5.40E-02 TABLE 1CAttachment IPage 6 of 12EFFLUENT AND WASTE DISPOSAL ANNUAL REPORTPERIOD: 1/1/14 TO 12/31/14GASEOUS EFFLUENTS-GROUND LEVEL RELEASESCONTINUOUS MODEBATCH MODESURRY POWER STATION UNITS 1 &21. FISSION & ACTIVATION GASESKr-85Kr-85mKr-87Kr-88Xe-133Xe- 135Xe-135mXe- 138Xe-131mXe-133mAr-41UNITTHIRD FOURTH THIRD FOURTHQUARTER QUARTER QUARTER QUARTERCiCiCiCiCiCiCiCiCiCiCiCiN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/AN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/AN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/AN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/ATOTAL FOR PERIOD2. IODINES1-1311-1331-135CiCiCiCiN/DN/DN/DN/AN/DN/DN/DN/AN/DN/DN/DN/AN/DN/DN/DN/ATOTAL FOR PERIOD3. PARTICULATESSr-89Sr-90Cs-134Cs-137Ba-140La-140Co-58Co-60Mn-54Fe-59Zn-65Mo-99Ce-141Ce-144C-14TOTAL FOR PERIODCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DCi N/A N/AN/A N/A TABLE 2A Page 7 of 12EFFLUENT AND WASTE DISPOSAL ANNUAL REPORTPERIOD: 1/1/14 TO 12/31/14LIQUID EFFLUENTS-SUMMATION OF ALL RELEASESSURRY POWER STATION UNITS 1 &2 UNIT FIRST SECOND % EST. ERRORQUARTER QUARTERA, FISSION AND ACTIVATION PRODUCTS1. TOTAL RELEASE (NOT INCLUDINGTRITIUM, GASES, ALPHA) Ci 1.69E-03 7.52E-03 2.OOE+012. AVE DIL. CONC. DURING PERIOD ýtCi/mL 2.71E-12 1.20E-1 13. PERCENT OF APPLICABLE LIMIT % 7.46E-06 1.62E-05B, TRITIUM1. TOTAL RELEASE Ci 1.93E+02 3.35E+02 2.OOE+012. AVE DIL. CONC. DURING PERIOD jiCi/mL 3.10E-07 5.37E-073. PERCENT OF APPLICABLE LIMIT % 3.1OE-03 5.37E-03C, DISSOLVED AND ENTRAINED GASES1. TOTAL RELEASE Ci 6.07E-05 4.81E-05 2.OOE+012. AVE DIL. CONC. DURING PERIOD ýtCi/mL 9.74E-14 7.71E-143. PERCENT OF APPLICABLE LIMIT % 4.87E-08 3.86E-08D. GROSS ALPHA RADIOACTIVITYI. TOTAL RELEASE Ci N/D N/D 2.00E+01E, VOLUME OF WASTE RELEASED(PRIOR TO DILUTION) LITERS 5.30E+07 5.47E+07 3.OOE+00F. VOLUME OF DILUTION WATERUSED DURING PERIOD LITERS 6.23E+ 11 6.24E+ 11 3.OOE+00 TABLE 2A Page 8 of 12EFFLUENT AND WASTE DISPOSAL ANNUAL REPORTPERIOD: 1/1/14 TO 12/31/14LIQUID EFFLUENTS-SUMMATION OF ALL RELEASESSURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH % EST. ERRORQUARTER QUARTERA. FISSION AND ACTIVATION PRODUCTS1. TOTAL RELEASE (NOT INCLUDINGTRITIUM, GASES, ALPHA) Ci 5.53E-03 3.09E-03 2.OOE+012. AVE DIL. CONC. DURING PERIOD ýtCi/mL 7.03E-12 4.62E-123. PERCENT OF APPLICABLE LIMIT % 8.13E-06 9.79E-06B. TRITIUM1. TOTAL RELEASE Ci 8.54E+01 3.42E+02 2.OOE+012. AVE DIL. CONC. DURING PERIOD ýtCi/mL 1.09E-07 5.13E-073. PERCENT OF APPLICABLE LIMIT % 1.09E-03 5.13E-03C. DISSOLVED AND ENTRAINED GASES1. TOTAL RELEASE Ci N/D 1.81E-05 2.OOE+012. AVE DIL. CONC. DURING PERIOD p.Ci/mL N/A 2.71E-143. PERCENT OF APPLICABLE LIMIT % N/A 1.36E-08D. GROSS ALPHA RADIOACTIVITY1. TOTAL RELEASE Ci N/D N/D 2.OOE+01E. VOLUME OF WASTE RELEASED(PRIOR TO DILUTION) LITERS 5.45E+07 5.49E+07 3.OOE+00F. VOLUME OF DILUTION WATERUSED DURING PERIOD LITERS 7.86E+11 6.67E+ 11 3.OOE+00 TABLE 2BAttachment 1Page 9 of 12EFFLUENT AND WASTE DISPOSAL ANNUAL REPORTPERIOD: -1/1/14 TO 12/31/14LIQUID EFFLUENTSSURRY POWER STATION UNITS 1 &2CONTINUOUS MODEUNIT FIRST SECONDQUARTER QUARTERBATCH MODEFIRST SECONDQUARTER QUARTERSr-89Sr-90Fe-55Cs-134Cs-1371-131Co-58Co-60Fe-59Zn-65Mn-54Cr-51Zr-95Nb-95Mo-99Tc-99mBa-140La-140Ce-141Ce- 144Sb-124Sb-125Co-57CiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiN/DN/DN/DN/D1.99E-04N/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/D3.68E-04N/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/D3.68E-04N/DN/DN/DN/DN/DN/DN/D9.01E-064.77E-062.68E-046.61 E-04N/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/D4.40E-065.42E-04N/D1.49E-036.07E-05NiDN/DN/DN/DN/DN/D2.67E-053.04E-052.83E-031.06E-03N/DN/DN/D1.16E-03N/DN/DN/DN/DN/DN/DN/DN/D1.64E-041.87E-03N/D7.14E-032.73E-05N/D2.07E-05TOTAL FOR PERIODCi 1.99E-04Xe-133Xe-135Ar-41CiCiCiN/DN/DN/DTOTAL FOR PERIODCi N/A N/A6.07E-05 4.81E-05 Page 10 of 12TABLE 2BEFFLUENT AND WASTE DISPOSAL ANNUAL REPORTPERIOD: 1/1/14 TO 12/31/14LIQUID EFFLUENTSSURRY POWER STATION UNITS 1&2CONTINUOUS MODEUNIT THIRD FOURTHQUARTER QUARTERBATCH MODETHIRD FOURTHQUARTER QUARTERSr-89Sr-90Fe-55Cs- 134Cs-1371-131Co-58Co-60Fe-59Zn-65Mn-54Cr-51Zr-95Nb-95Mo-99Tc-99mBa-140La-140Ce-141Ce-144Sb-124Sb-125Co-57CiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiCiN/DN/DN/DN/D2.01E-04N/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/D1.49E-04N/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/D1.49E-04N/DN/DN/DN/DN/DN/D3.89E-06N/D2.76E-037.02E-04N/DN/DN/D3.17E-04N/DN/DN/DN/DN/DN/DN/DN/D8.92E-051.45E-03N/D5.33E-03N/DN/DN/DN/DN/DN/D1.12E-055.3 1E-068.93E-041.25E-03N/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/DN/D7.75E-04N/D2.94E-031.81E-05N/DTOTAL FOR PERIODCi 2.01E-04Xe-133Xe-135CiCiN/DN/DTOTAL FOR PERIODCi N/A N/AN/A 1.81E-05 Page 11 of 12TABLE 3EFFLUENT AND WASTE DISPOSAL ANNUAL REPORTSOLID WASTE AND IRRADIATED FUEL SHIPMENTSPERIOD: 1/1/14 -12/31/14SURRY POWER STATIONA. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)1. Type of waste12 monthPeriodEst. TotalError, %a. Spent resins, filter sludges, evaporator m3 8.80E+00 Note 1 1.00E+01bottoms, etc. Ci 5.80E+02 3.OOE+O1b. Dry compressible waste, contaminated m3 3.33E+02 Note 2 1.00E+01equip., etc. Ci 1.03E+00 3.OOE+01c. Irradiated components, control m3 O.OOE+00 1.00E+01rods, etc. Ci O.OOE+00 3.OOE+01d. Other (Waste oil) m3 1.38E+00 Note 3 1.00E+01Ci 3.02E-03 3.OOE+012. Estimate of major nuclide composition (by type of waste)a. Co-60Ni-63Fe-55Sb-125Mn-54b. Cs-137Co-60Ni-63Fe-55Co-58Cr-514.95E+013.24E+011.24E+011.98E+001.24E+003.98E+013.58E+011.22E+014.61E+002.86E+001.73E+00C.d. C-14H-3Co-60Tc-991-1297.76E+018.51E+006.72E+003.94E+002.94E+00(based on MDA concentration)(based on MDA concentration)(based on MDA concentration)(based on MDA concentration)
TABLE 3EFFLUENT AND WASTE DISPOSAL ANNUAL REPORTSOLID WASTE AND IRRADIATED FUEL SHIPMENTSPERIOD: 1/1/14 -12/31/14CONTINUEDSURRY POWER STATIONA. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)3. Solid Waste DispositionNumber of Shipments Mode of Transportation10 TruckAttachment 1Page 12 of 12DestinationOak Ridge, TN (EnergySolutions)Erwin, TN (EnergySolutions)Bamwell, SC (EnergySolutions)21TruckTruckB. IRRADIATED FUEL SHIPMENT (Disposition)Number of Shipments0Mode of TransportationDestinationNOTE 1: Some of this waste was shipped to licensed waste processors for processing and/or volume reduction. Therefore,this volume is not representative of the actual volume buried. The total volume buried for this reporting period is 3.02E+00 m3.Burial volume by Erwin Resin Solutions is indeterminable due to mixing of Surry waste with other generators waste.NOTE 2: Some DAW was shipped to licensed waste processors for processing and/or volume reduction. Therefore,this volume is not representative of the actual volume buried. The total volume buried for this reporting period is 1.70E+02 m3.NOTE 3: This waste was shipped to a licensed waste processor for processing and/or volume reduction. The actualvolume buried is indeterminable. It is conservatively assumed that 2.80E-0 1 mm3was buried this reporting period. Page 1 of 1ANNUAL AND QUARTERLY DOSESAn assessment of radiation doses to the maximum exposed member of the public due toradioactive liquid and gaseous effluents released from the site for each calendar quarter for thecalendar year of this report, along with an annual total of each effluent pathway is madepursuant to the ODCM, Section 6.7.2, requirement.LIQUID GASEOUS2014 Total Body GI-LLI Liver Gamma Beta Bone(mrem) (mrem) (mrem) (mrad) (mrad) (mrem)1st Quarter 4.08E-05 5.56E-05 4.03E-05 3.56E-07 1.06E-06 4.44E-022nd Quarter 7.58E-05 1.18E-04 7.39E-05 1.62E-06 3.11 E-06 7.09E-023rd Quarter 1.82E-05 4.75E-05 1.66E-05 1.92E-08 5.70E-08 3.02E-034th Quarter 6.95E-05 1.OOE-04 6.77E-05 6.17E-09 1.84E-08 9.68E-04Annual 2.04E-04 3.22E-04 1.99E-04 2.OOE-06 4.25E-06 1.19E-01 Page 1 of IREVISIONS TO OFFSITE DOSE CALCULATION MANUAL (ODCM)As required by Technical Specification 6.8.B, revisions to the ODCM, effective for the time periodcovered by this report, are included with this attachment. There was one general revision to theODCM implemented during this reporting period.Revision 17:* Added Bases discussions to the liquid and gaseous radioactive waste effluent sections* Updated references and definitions* Clarified that liquid ingestion dose commitment factors are based on salt water bioaccumulation factors* Revised gaseous effluent dose rate and dose calculation equations by expanding the equations toclarify the use of dispersion and deposition factors* Added Attachment 7 which lists dispersion and deposition factors
)DonhinioWAdministrative Procedures Action Request(A-PAR) P4 jPaci I o I ..---.Requstrcin for Prcoduretn Monisictionm ar tocue comlee in ViRAeqUueso onepat(opeeboks1truh1.n1. Procedure NumberVPAP-2103S2. Revision173. Page1 of 14. Effective Date I1 -3 /LI5. Procedure Title .6. Expiration DateOffsite Dose Calculation Manual (Surry) N/A7. Tjype of RequestEI New Procedure [ Procedure Revision E3 Procedure Deletion El Emergency Change8. Brief description of the modificationSee Revsion Summary9. Location ZSPS E] NAPS F-- CORP Location [-]SPS ElNAPS [:CORP10. Requested by (Printed Name) 11. Date 12. Phone 13. Requested by (Printed Name) 14. Date 15. PhoneP. Blount -10/1/20141 2467 N/A N/A N/A16. Does procedure meet requirements of NOTE below? I]Yes ElNo17. Does this procedure require a 50.59 / 72.48 Evaluation (Form No. 730947)? El Yes [] No18. Are there any new sections or steps designated North Anna or Surry? LI Yes [] No19. Is the reason for the station-specific instructions due to differences in regulatory requirements? El Yes [E No j] N/A20. Is the reason for the station-specific instructions due to differences in construction? El Yes El No IZN/A21. Is the reason for the station-specific instructions due to station preferences? [E Yes [] No ZKN/AIf all answers are No or N/A, approval is required by PPOs as identified on the Procedure Cover Page. Check block 30.If block 16 or 17 is Yes, approval is required by PPOs, FSRCs, and/or Site Vice Presidents. Check blocks 30, 31, and 32, as appropriate.NOTE: VPAP-2103N, VPAP-2103S, and VPAP-2104 require Site Vice President(s) approval.SPIPs require FSRC(s) and Site Vice President(s) approval.Revisions to VPAP-0502, Attachment 26, require FSRC(s) approval.If block 18, 19, or 20 is Yes with block 21 No, approval is required by PPOs and Site Vice Presidents. Check blocks 30 and 32.If block 21 is Yes, approval is required by PPOs, Site Vice Presidents, and Vice President Corporate. Check blocks 30, 32, and 33.22. Did this procedure require the attachments in PI-AA-4000, Change Management, to be used? [] Yes j] No23. Location ISPS E--NAPS -CORP Location [:SPS ENAPS []CORP24. PPO (Printed Name) 25. Date 126. Phone 27. PPO (Printed Name) 28. Date 29. PhoneJ. Eggart 11/24/14 2010 N/A N/A N/ARqired A o Ato. -., -'- Deterinato. *n Abovi b i[ 30. PPO(s) [] 31. FSRCs [] 32. Site Vice Presidents El 33. Vice President (Corp)34. PPO (S nature) 35. Date 36. PPO (Signature) 37. Date10 .2b~ N/AI_ __38. FSRC C airman (Si~ature) j39. Date 40. FSRC Chairman (Signature) 41. DateN/A N/A N/A N/A42. Sit i! ent (Signature)43. DateI/ .-4lI44. Site Vice President (Signature)N/A45. DateN/A.Vice President Corporate (Signature)N/A47. DateN/AMR-Administrative Procedures Action Request; SPS-Surry Power Station;S-North Anna Power Station; CORP-Corporate; PPO(s)-Process/Program Owner(s);C-Facility Safety Review Committee; SPIPs-Security Plan Implementing ProceduresForm No. 720457(Feb 2010)
MStationrDominionW Administrative ProcedureTitle: Offsite Dose Calculation Manual (Surry)Process / Program Owner: Manager Radiological Protection and Chemistry(Surry)Procedure Number Revision Number Effective DateVPAP-2103S 17 On FileRevision SummaryThe following changes were made in response to SAR001749." Updated Reference 3.1.9 -changed "NUREG-0324, XOQDOQ" to "NUREG/CR-2919,XOQDOQ"" Deleted Reference 3.1.21 -Laboratory Quality Assurance Plan, Manual 100; FramatomeEnvironmental Laboratory." Updated 4.10, Members of the Public -changed "Individuals who, by virtue of their occupationalstatus, have no formal association with the Station" to "Any individual except when thatindividual is receiving an occupational dose."" Updated 6.2.1 .c -changed "Daily concentrations of radioactive materials" to "Concentrations ofradioactive materials."" Added 6.2.1.d, Bases -Liquid Effluent Concentration Limitations." Updated 6.2.2.d. 1, "C" definition -added "(ACW value)" and "for an isotopic mixture expectedin the effluent."" Added 6.2.2.e, Bases -Radioactive Liquid Effluent Monitoring Instrumentation." Updated 6.2.3.c, Dose Contribution Calculations, as follows:' "Ai" definition -changed "beta emitter in mrem-mL per hr-p.Ci. Values for Ai are provided inthe Canberra Source Code file" to "beta emitter in mrem/ hr per gCi/mL""Bli" and "BFi" definitions -added "salt water"* NOTE -deleted "NUREG/CR- 1276" and "TID-4500"" Added 6.2.3.e, Bases -Dose Due To Liquid Effluents." Added 6.2.4.d, Bases -Liquid Radwaste Treatment System." Deleted 6.3.1 .c. 1 NOTE -"The dose factors used in the Gaseous Effluent Dose Rate calculationsare included in the Canberra Source Code file. These dose factors, Ki, Li, Mi, and Pi forventilation vent and process vent releases, DO NOT include the applicable X/Q value. Equations(8), (9), and (10) must be multiplied by the appropriate X/Q value for Gaseous Effluent Dose Ratecalculations."* Updated 6.3.1.c. 1 & 2 formulas." Added 6.3.1.d, Bases -Dose Rate.(Revision Summary continued on Page 2)Approvals on File IDOMINION VPAP-2103SREVISION 17PAGE 2 OF 77Revision Summary continued" Updated 6.3.2.d.1, "D" definition -changed "implement 10 CFR 20" to "implement TechnicalSpecifications." I" Added 6.3.2.e, Bases -Radioactive Gaseous Effluent Monitoring Instrumentation." Deleted 6.3.3.a NOTE -"The dose factors used in the Noble Gas air dose calculations are includedin the Canberra Source Code file. These dose factors, Mi and Ni for ventilation vent and processvent releases, DO NOT include the applicable X/Q value. Equations (13) and (14) must bemultiplied by the appropriate X/Q value for gamma and beta air dose calculations."" Updated 6.3.3.c, Noble Gas Effluent Air Dose Calculation -updated formulas and definitions." Deleted 6.3.4.c. 1 NOTE -"The RMi and RI dose factors DO NOT include the applicable D/Q andX/Q values respectively for Surry Power Station. Equation (15) must be multiplied by theapplicable D/Q or X/Q, as appropriate, to calculate the critical organ dose."" Updated 6.3.4.c. 1 formulas and definitions. I" Updated 6.7.4.b.2 -added "Technical Specifications."" Updated 7.0, Records, to current format." Added Attachment 7, Dispersion and Deposition Factors." Updated renumbered Attachment 12, Meteorological, Liquid, and Gaseous Pathway Analysis, forconsistency with changes in the Instructions.IIIIIII DOMINION VPAP-2103SREVISION 17PAGE 3 OF 77TABLE OF CONTENTSSection Page1.0 PURPOSE 52.0 SCOPE
53.0 REFERENCES
/COMMITMENT DOCUMENTS 64.0 DEFINITIONS 75.0 RESPONSIBILITIES 116.0 INSTRUCTIONS 126.1 Sampling and Monitoring Criteria 126.2 Liquid Radioactive Waste Effluents 126.2.1 Liquid Effluent Concentration Limitations 126.2.2 Liquid Monitoring Instrumentation 146.2.3 Liquid Effluent Dose Limit 176.2.4 Liquid Radwaste Treatment 206.2.5 Liquid Sampling 226.3 Gaseous Radioactive Waste Effluents 226.3.1 Gaseous Effluent Dose Rate Limitations 226.3.2 Gaseous Monitoring Instrumentation 256.3.3 Noble Gas Effluent Air Dose Limit 286.3.4 1-131, 133, H-3 & Radionuclides in Particulate Form Effluent Dose Limit 296.3.5 Gaseous Radwaste Treatment 326.4 Radioactive Liquid and Gaseous Release Permits 336.4.1 Liquid Waste Batch Releases 336.4.2 Continuous Liquid Releases 336.4.3 Waste Gas Decay Tank (WGDT) Release Permit 346.4.4 Reactor Containment Release Permits 346.4.5 Miscellaneous Gaseous Release Permit 34 DOMINION VPAP-2103SREVISION 17PAGE 4 OF 77TABLE OF CONTENTS (continued) 1Section Page6.4.6 Radioactive Liquid and Gaseous Release Controls 346.5 Total Dose Limit to Public From Uranium Fuel Cycle Sources 356.6 Radiological Environmental Monitoring 366.6.1 Monitoring Program 366.6.2 Land Use Census 386.6.3 Interlaboratory Comparison Program 396.7 Reporting Requirements 406.7.1 Annual Radiological Environmental Operating Report 406.7.2 Annual Radioactive Effluent Release Report 426.7.3 Annual Meteorological Data 446.7.4 Changes to the ODCM 446.7.5 Industry Ground Water Protection Initiative 457.0 RECORDS 47ATTACHMENTS1 Radioactive Liquid Effluent Monitoring Instrumentation 48 32 Radioactive Liquid Effluent Monitoring Instrumentation 49Surveillance Requirements3 Radioactive Liquid Waste Sampling and Analysis Program 504 Radioactive Gaseous Waste Sampling and Analysis Program 535 Radioactive Gaseous Effluent Monitoring Instrumentation 576 Radioactive Gaseous Effluent Monitoring Instrumentation 59Surveillance Requirements7 Dispersion and Deposition Factors 618 Radiological Environmental Monitoring Program 629 Environmental Sampling Locations 6510 Detection Capabilities for Environmental Sample Analysis 6811 Reporting Levels for Radioactivity Concentrations in Environmental Samples 7012 Meteorological, Liquid, and Gaseous Pathway Analysis 71I DOMINION VPAP-2103SREVISION 17PAGE 5 OF 771.0 PURPOSEThe Offsite Dose Calculation Manual (ODCM) establishes requirements for the RadioactiveEffluent and Radiological Environmental Monitoring Programs. Methodology and parametersare 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 offsite doses due toradioactive liquid and gaseous effluents are performed to assure that:" Concentration of radioactive liquid effluents to the unrestricted area will be limited to tentimes the effluent concentration values of 10 CFR 20, Appendix B, Table 2, Column 2, forradionuclides other than dissolved or entrained noble gases and 2E-4 lCi/mL for dissolvedor entrained noble gases" Exposure to the maximum exposed member of the public in the unrestricted area fromradioactive liquid effluents will not result in doses greater than the liquid dose limitsof 10 CFR 50, Appendix I" Dose rate at and beyond the site boundary from radioactive gaseous effluents will be limitedto:Noble gases -less than or equal to a dose rate of 500 mremiyr to the total body and lessthan or equal to a dose rate of 3000 mrem/yr to the skin1131, 1133, and H3, and all radionuclides in particulate form with half-lives greater than 8days -less than or equal to a dose rate of 1500 mrem/yr to any organ-Exposure from radioactive gaseous effluents to the maximum exposed member of the publicin the unrestricted area will not result in doses greater than the gaseous dose limits of10 CFR 50, Appendix I, and" Exposure to a real individual will not exceed 40 CFR 190 dose limits2.0 SCOPEThis procedure applies to the Radioactive Effluent and Radiological EnvironmentalMonitoring Programs at Surry Power Station.
IDOMINION VPAP-2103SREVISION 17PAGE 6 OF 7
73.0 REFERENCES
/COMMITMENT DOCUMENTS I3.1 References3.1.1 10 CFR 20, Standards for Protection Against Radiation3.1.2 10 CFR 50, Domestic Licensing of Production and Utilization Facilities3.1.3 40 CFR 190, Environmental Radiation Protection Standards for Nuclear PowerOperations3.1.4 TID-14844, Calculation of Distance Factors for Power and Test Reactor Sites3.1.5 Regulatory Guide 1.21, Measuring, Evaluating, and Reporting Radioactivity in SolidWastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents fromLight-Water-Cooled Nuclear Power Plants, Rev. 1, U.S. NRC, June 19743.1.6 Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releasesof Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50,Appendix I, Rev. 1, U.S. NRC, October 1977 I3.1.7 Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport andDispersion of Gaseous Effluents in Routine Releases from Light-Water-CooledReactors, Rev. 1, U.S. NRC, July 19773.1.8 Surry Technical Specifications (Units 1 and 2)3.1.9 NUREG/CR-2919, XOQDOQ, Computer Program for the Meteorological Evaluationof Routine Effluent Releases at Nuclear Power Stations, U.S. NRC, September 19823.1.10 NUREG/CR-1276, Users Manual for the LADTAP II Program, U.S. NRC,May, 19803.1.11 TID-4500, VCRL-50564, Rev. 1, Concentration Factors of Chemical Elements inEdible Aquatic Organisms, October, 19723.1.12 WASH 1258, Vol. 2, July 1973, Numerical Guides for Design Objectives and LimitingConditions for Operation to Meet the Criterion "As Low As Practicable" ForRadioactive Material in Light Water-Cooled Nuclear Power Reactor Effluents3.1.13 NUREG-0597, User's Guide to GASPAR Code, U.S. NRC, June, 19803.1.14 Radiological Assessment Branch Technical Position on Environmental Monitoring,November, 1979, Rev. 13.1.15 NUREG-0133, Preparation of Radiological Effluent Technical Specifications forNuclear Power Stations, October, 19783.1.16 NUREG-0543, February 1980, Methods for Demonstrating LWR Compliance Withthe EPA Uranium Fuel Cycle Standard (40 CFR Part 190)3.1.17 NUREG-0472, Standard Radiological Effluent Technical Specifications forPressurized Water Reactors, Draft, Rev. 3, March 1982 I3.1.18 Environmental Measurements Laboratory, DOE HASL 300 ManualI DOMINION VPAP-2103SREVISION 17PAGE 7 OF 773.1.19 NRC 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 Program3.1.20 Surry UFSAR3.1.21 VPAP-2802, Notifications and Reports3.1.22 HP-3010.021, Radioactive Liquid Waste Sampling and Analysis3.1.23 HP-3010.031, Radioactive Gaseous Waste Sampling and Analysis3.1.24 Design Change 01-022, Ventilation Radiation Monitoring (Kaman) SystemReplacement/Surry/Unit 1&23.1.25 NEI 07-07, Industry Ground Water Protection Initiative -Final Guidance Document3.1.26 CR022320 (Surry), Daily Channel Checks for 1-VG-RM-131-1 Flow Rate MeasuringDevice Not Performed3.1.27 RP-AA-502, Groundwater Protection Program3.2 Commitment Documents3.2.1 Quality Assurance Audit Report Number 92-03, Observation 04NS (Item 2)3.2.2 Deviation Report S-97-1281, Annual Radiological Effluent Release Report3.2.3 Deviation S-2000-0235, Continuous Vent Stack Sampling3.2.4 S-2005-0930, Response to the Verification of Back-up Effluent AccountabilitySampling4.0 DEFINITIONS4.1 Channel CalibrationAdjustment, as necessary, of the channel output so it responds with the necessary range andaccuracy to known values of the parameter the channel monitors. It encompasses the entirechannel, including the sensor and alarm and/or trip functions and the Channel Functional Test.The Channel Calibration can be performed by any series of sequential, overlapping, or totalchannel steps so the entire channel is calibrated.
IDOMINION VPAP-2103SREVISION 17PAGE 8 OF 774.2 Channel Check IA qualitative assessment, by observation, of channel behavior during operation. Thisassessment includes, where possible, comparison of the channel indication and/or status withother indications and/or status derived from independent instrumentation channels measuringthe same parameter.The Channel Check for the MGPI sampler flow rate measuring devices, as listed onAttachment 6 of this procedure, is the direct observation of the MGPI radiation monitor releaserate (i.e., microcuries per second) without the presence of a sampler flow fault display.4.3 Channel Functional TestThere are two types of Channel Functional Tests.4.3.1 Analog ChannelInjection of a simulated signal into a channel, as close to the sensor as practicable, toverify Operability, including alarm and/or trip functions.4.3.2 Bistable ChannelInjection of a simulated signal into a sensor to verify Operability, including alarmand/or trip functions.4.4 Critical Organ IThat organ, which has been determined to be the maximum exposed organ based on an effluentpathway analysis, thereby ensuring the dose and dose rate limitations to any organ will not beexceeded.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, 0132, 1133, 134, 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.I DOMINIONVPAP-2103SREVISION 17PAGE 9 OF 774.6 Frequency NotationsNOTE: Frequencies are allowed a maximum extension of 25 percent.NOTATION FREQUENCYD -DailyW -WeeklyM -MonthlyQ -QuarterlySA -Semi-annuallyR -RefuelingS/U -Start-upP -Prior to releaseN/A -Not applicableDR -During the releaseAt least once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />sAt least once per 7 daysAt least once per 31 daysAt least once per 92 daysAt least once per 184 daysAt least once per 18 monthsPrior to each reactor start-upCompleted prior to each releaseNot applicableAt least once during each release4.7 Gaseous Radwaste Treatment SystemA system that reduces radioactive gaseous effluents by collecting primary coolant systemoffgases from the primary system and providing delay or holdup to reduce total radioactivityprior to release to the environment. The system comprises the waste gas decay tanks,regenerative heat exchanger, waste gas charcoal filters, process vent blowers and waste gassurge tanks.4.8 General NomenclatureX = Chi: concentration at a point at a given instant (curies per cubic meter)D = Deposition: 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.
IDOMINION VPAP-2103SREVISION 17PAGE 10 OF 774.10 Members of the PublicAny individual except when that individual is receiving an occupational dose. This categoryincludes non-employees of Dominion who are permitted to use portions of the site forrecreational, occupational, or other purposes not associated with Station functions. Thiscategory does not include non-employees such as vending machine servicemen or postalworkers who, as part of their formal job function, occasionally enter an area that is controlledby Dominion to protect individuals from exposure to radiation and radioactive materials.4.11 Operable -OperabilityA system, subsystem, train, component, or device is operable or has operability when it iscapable of performing its specified functions and all necessary, attendant instrumentation,controls, normal and emergency electrical power sources, cooling or seal water, lubrication orother auxiliary equipment that are required for the system, subsystem, train, component, or 1device to perform its functions are also capable of performing their related support functions.4.12 Purge -Purging IControlled discharge of air or gas from a confinement to maintain temperature, pressure,humidity, concentration, or other operating condition, so that replacement air or gas is requiredto purify the confinement.4.13 Rated Thermal Power ITotal reactor core heat transfer rate to reactor coolant (i.e., 2587 Megawatts Thermal MWt).4.14 Site Boundary IThe line beyond which Dominion does not own, lease, or otherwise control the land.4.15 Source CheckFor Victoreen and Eberline monitors a source check is the qualitative assessment of channelresponse when a channel sensor is exposed to a radioactive source or a light emitting diode,LED.For MGPI monitors a source check is the verification of proper computer response tocontinuous operational checks on the detector and 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.II DOMINION VPAP-2103SREVISION 17PAGE 11 OF 774.17 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 radioactivematerials, or any area within the site boundary used for residential quarters or for industrial,commercial, institutional or recreational purposes.4.19 Ventilation Exhaust Treatment SystemA system that reduces gaseous radioiodine or radioactive material in particulate form ineffluents by passing ventilation or vent exhaust gases through charcoal adsorbers and HighEfficiency Particulate Air (HEPA) filters to remove iodines and particulates from a gaseousexhaust stream prior to release to the environment (such a system is not considered to have anyeffect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systemsare not Ventilation Exhaust Treatment System components.5.0 RESPONSIBILITIES5.1 Manager Radiological Protection and ChemistryThe Manager Radiological Protection and Chemistry is responsible for:5.1.1 Establishing and maintaining procedures for surveying, sampling, and monitoringradioactive effluents and the environment.5.1.2 Surveying, sampling, and analyzing plant effluents and environmental monitoring, anddocumenting these activities.5.1.3 Analyzing plant effluent trends and recommending actions to correct adverse trends.5.1.4 Preparing Effluent and Environmental Monitoring Program records.5.2 Manager Nuclear OperationsThe Manager Nuclear Operations is responsible for requesting samples, analyses, andauthorization to release effluents.
IDOMINION VPAP-2103SREVISION 17PAGE 12 OF 776.0 INSTRUCTIONS INOTE: Meteorological, liquid, and gaseous pathway analyses are presented inMeteorological, Liquid, and Gaseous Pathway Analysis (Attachment 12).6.1 Sampling and Monitoring Criteria6.1.1 Surveys, sampling, and analyses shall use instruments calibrated for the type and rangeof radiation monitored and the type of discharge monitored.6.1.2 Installed monitoring systems shall be calibrated for the type and range of radiation orparameter monitored.6.1.3 A sufficient number of survey points shall be used or samples taken to adequatelyassess the status of the discharge monitored.6.1.4 Samples shall be representative of the volume and type of discharge monitored.6.1.5 Surveys, sampling, analyses, and monitoring records shall be accurately and legiblydocumented, and sufficiently detailed that the meaning and intent of the records areclear.6.1.6 Surveys, analyses, and monitoring records shall be reviewed for trends, completeness,and accuracy.6.2 Liquid Radioactive Waste Effluents6.2.1 Liquid Effluent Concentration Limitationsa. Liquid waste concentrations discharged from the Station shall not exceed thefollowing limits:1. For radionuclides (other than dissolved or entrained noble gases), liquid effluentconcentrations 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 jtCi/mL.b. If the concentration of liquid effluent exceeds the limits in Step 6.2.1 .a., promptlyII DOMINIONVPAP-2103SREVISION 17PAGE 13 OF 77c. Concentrations of radioactive materials in liquid waste released to unrestrictedareas shall meet the following:Volume of Waste Discharged + Volume of Dilution Water > 1 (1)Volume of Waste Discharged xL ACW.i Iwhere:jtCi/mLi = the concentration of nuclide i in the liquid effluent dischargeACWi = ten times the effluent concentration value in unrestricted areas ofnuclide i, expressed as g.tCi/mL from 10 CFR 20, Appendix B, Table 2,Column 2 for radionuclides other than noble gases, and 2E-4 ltCi/mL fordissolved or entrained noble gasesd. Bases -Liquid Effluent Concentration LimitationsThis control is provided to ensure that the concentration of radioactive materialsreleased in liquid waste effluents to UNRESTRICTED AREAS will not exceed 10times the concentration values specified in Appendix B, Table 2, Column 2 of10 CFR 20. The specification provides operational flexibility for releasing liquideffluent in concentrations to follow the Section II.A and II.C design objectives ofAppendix I to 10 CFR Part 50. This limitation provides additional assurance thatthe levels of radioactive materials in bodies of water in UNRESTRICTED AREASwill result in exposures within: (1) the Section II.A design objectives of AppendixI, 10 CFR Part 50, to a MEMBER OF THE PUBLIC, and (2) restrictions authorizedby 10 CFR 20.1301(e). The concentration limit for dissolved or entrained noblegases is based upon the assumption that Xe-135 is the controlling radioisotope andits effluent concentration in air (submersion) was converted to an equivalentconcentration in water using the methods described in International Commission onRadiological Protection (ICRP) Publication 2. This specification does not affect therequirements to comply with the annual limitations of 10 CFR 20.1301(e).
IDOMINION VPAP-2103SREVISION 17PAGE 14 OF 776.2.2 Liquid Monitoring Instrumentationa. Radioactive Liquid Effluent Monitoring InstrumentationRadioactive liquid effluent monitoring instrumentation channels shown onRadioactive Liquid Effluent Monitoring Instrumentation (Attachment 1) shall beoperable with their alarm/trip setpoints set to ensure that Step 6.2.1 .a. limits are notexceeded.1. Alarm/trip setpoints of these channels shall be determined and adjusted inaccordance with Step 6.2.2.d., Setpoint Calculation.2. If a radioactive liquid effluent monitoring instrumentation channel alarm/tripsetpoint is less conservative than required by Step 6.2.2.a., perform one of thefollowing:" Promptly suspend release of radioactive liquid effluents monitored by theaffected channel" Declare the channel inoperable" Change the setpoint to an acceptable, conservative valueb. Radioactive Liquid Effluent Monitoring Instrumentation Operability IEach radioactive liquid effluent monitoring instrumentation channel shall bedemonstrated operable by performing a Channel Check, Source Check, ChannelCalibration, and Channel Functional Test at the frequencies shown in RadioactiveLiquid 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 Instrumentation (Attachment1) perform the action shown in those tables.2. Attempt to return the instruments to operable status within 30 days. Ifunsuccessful, explain in the next Annual Radioactive Effluent Release Reportwhy the inoperability was not corrected in a timely manner.IIII DOMINION VPAP-2103SREVISION 17PAGE 15 OF 77c. Applicable MonitorsLiquid effluent monitors for which alarm/trip setpoints shall be determined are:Release Point Instrument NumberService Water System Effluent Line I -SW-RM-107 A,B,C,DCondenser Circulating Water Line 1-SW-RM-1202-SW-RM-220Radwaste Facility Effluent Line RE- RRM-131d. Setpoint CalculationNOTE: 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 gtCi/mL, of the radioactivity monitor measuring theradioactivity concentration in the effluent line prior to dilutionC = the effluent concentration limit for the monitor used to implement10 CFR 20 for the Station (ACW in ptCi/mL) for an isotopic mixtureexpected in the effluentFE = maximum design pathway effluent flow rateFD = dilution water flow rate calculated as:FE + (200,000 gpm x number of circ. pumps in service)2. Each of the condenser circulating water channels (e.g., SW-120, SW-220)monitors the effluent (service water, including component cooling servicewater, circulating water, and liquid radwaste) in the circulating water dischargetunnel beyond the last point of possible radioactive material addition. Nodilution is assumed for this pathway. Therefore, Equation (2) becomes:S = C (3)The setpoint for Station monitors used to implement 10 CFR 20 for the sitebecomes the effluent concentration limit.
IDOMINION VPAP-2103SREVISION 17PAGE 16 OF 773. In addition, for added conservatism, setpoints shall be calculated for the service Iwater system effluent line (i.e., SW-107 A, B, C, D), and the Radwaste Facilityeffluent line (i.e., RRM- 131).4. For the service water system effluent line, Equation (2) becomes:IS CFDKsw(4S -FE (4)where:Ksw = Allocation fraction of the effluent concentration limit, used toimplement 10 CFR 20 for the Station, attributable to the servicewater effluent line pathway 15. For the Radwaste Facility effluent line, Equation (2) becomes:IS CFDKRW (5)FEwhere:KRW = Allocation fraction of the effluent concentration limit, used to Iimplement 10 CFR 20 attributable to the Radwaste Facility effluentline pathway6. The sum Ksw + KRW shall not be greater than 1.0.e. Bases -Radioactive Liquid Effluent Monitoring InstrumentationThe radioactive liquid effluent instrumentation is provided to monitor and control,as applicable, the releases of radioactive materials in liquid effluents during actualor potential releases of liquid effluents. The Alarm/Trip Setpoints for theseinstruments shall be calculated and adjusted in accordance with the methodologyand parameters in the ODCM to ensure that the alarm/trip will occur prior toexceeding 10 times the limits of 10 CFR Part 20. The OPERABILITY and use ofthis instrumentation is consistent with the requirements of General Design Criteria60, 63, and 64 of Appendix A to 10 CFR Part 50.I DOMINION VPAP-2103SREVISION 17PAGE 17 OF 776.2.3 Liquid Effluent Dose Limita. RequirementAt least once per 31 days, perform the dose calculations in Step 6.2.3.c. to ensurethe dose or dose commitment to the maximum exposed member of the public fromradioactive materials in liquid releases (from each reactor unit) to unrestricted areasis limited to:1. 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 organb. ActionIf the calculated dose from release of radioactive materials in liquid effluentsexceeds 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 subsequentreleases will be in compliance with the above limits.
DOMINION VPAP-2103SREVISION 17PAGE 18 OF 77c. Dose Contribution CalculationsNOTE: All critical organ doses for each age group are calculated to determine which is thelimiting organ for the period being evaluated.Dose contributions shall be calculated for all radionuclides identified in liquideffluents released to unrestricted areas based on the equation:D =t F M CiAi (6)where:Subscripts = i, refers to individual radionuclideD = the cumulative dose commitment to the total body or critical organ from theliquid effluents for the period t, in mremt = the period for which Ci and F are averaged for all liquid releases, in hoursM = the mixing ratio (reciprocal of the dilution factor) at the point of exposure,dimensionless, 0.2 from Appendix 1 A, Surry UFSARF = the near field average dilution factor for Ci during any liquid effluentrelease; the ratio of the average undiluted liquid waste flow during releaseto the average flow from the site discharge structure to unrestricted areasCi = the average concentration of radionuclide, i, in undiluted liquid effluentduring the period t, from all liquid releases, in gCi/mLAi = the site-related ingestion dose commitment factor to the total body or criticalorgan for a particular age group for each identified principal gamma andbeta emitter in mrem/hr per pgCi/mLAi = 1.14 E+05 (21BFi + 5BIi) DFi (7)IIIIIIIIIIIIIIIIII DOMINION VPAP-2103SREVISION 17PAGE 19 OF 77For example:1.14 E+05 = 1 E+06 pCi/ltCi x 1 E+03 mL/L / (8760 hr/yr), units conversionfactor21 = adult fish consumption, kg/yr, from NUREG-0 1335 = adult invertebrate consumption, kg/yr, from NUREG-0133BIi = the salt water bioaccumulation factor for nuclide i, in invertebrates,pCi/kg per pCi/LBFi = the salt water bioaccumulation factor for nuclide i, in fish, pCi/kg perpCi/LDFi= the critical organ dose conversion factor for nuclide i, for adults, inrnrem/pCiNOTE: The above parameters were obtained from R.G. 1.109, Rev. 1, LADTAP II andVCRL-50564, Rev. 1.d. 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.
IDOMINION VPAP-2103SREVISION 17PAGE 20 OF 77e. Bases -Dose Due To Liquid EffluentsThis control is provided to implement the requirements of Sections II.A, III.A, andIV.A of Appendix I to 10 CFR Part 50. The control implements the guides set forthin Section II.A. The ACTION statement provides the required operating flexibilityand at the same time implements the guides set forth in Section IV.A of AppendixI to assure that the releases of radioactive material in liquid effluents toUNRESTRICTED AREAS will be kept "as low as is reasonably achievable." Thedose calculation methodology and parameters in the ODCM implement therequirements in Section III.A that conformance with the guides of Appendix I beshown by calculation procedures, such that the actual exposure of a MEMBER OFTHE PUBLIC is unlikely to be substantially underestimated. The equationsspecified in the ODCM for calculating the doses due to the actual release rates ofradioactive materials in liquid effluents are consistent with the methodologyprovided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man fromRoutine Releases of Reactor Effluents for the Purpose of Evaluating Compliancewith 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and RoutineReactor Releases for the Purpose of Implementing Appendix I," April 1977.6.2.4 Liquid Radwaste TreatmentHistorical data pertaining to the volumes and radioactivity of liquid effluents releasedin connection with specific station functions, such as maintenance or refuelingoutages, shall be used in projections as appropriate.a. Requirement1. The Surry Radwaste Facility Liquid Waste System shall be used to reduce theradioactive materials in liquid waste prior to discharge when projected dose dueto liquid effluent, from each reactor unit, to unrestricted areas would exceed0.06 mrem to total body or 0.2 mrem to the critical organ in a 31-day period.2. Doses due to liquid releases shall be projected at least once per 31 days.IIII DOMINION VPAP-2103SREVISION 17PAGE 21 OF 77b. ActionIf radioactive liquid waste is discharged without treatment and in excess of theabove limits, prepare and submit to the NRC, within 30 days, a special report inaccordance with VPAP-2802, Notifications and Reports, that includes thefollowing:1. An explanation of why liquid radwaste was being discharged without treatment,identification of any inoperable equipment or sub-system, and the reason for theinoperability.2. Actions taken to restore inoperable equipment to operable status.3. Summary description of actions taken to prevent recurrence.c. Projected Total Body and Critical Organ Dose Calculation1. Determine DL, the sum of all liquid open and closed release points, in mrem, bythe ith organ, for the quarter.2. Determine P, the Projection Factor, which is result of 31 divided by the numberof days from start of the quarter to the end of the release.3. Determine Da, additional anticipated dose for liquid releases by the ith organ forthe particular quarter of the release.4. Determine Dp, the 31 day projected dose by the ith organ:Dp = (DL x P) + Dad. Bases -Liquid Radwaste Treatment SystemThe OPERABILITY of the Liquid Radwaste Treatment System ensures that thissystem will be available for use whenever liquid effluents require treatment prior torelease to the environment. The requirement provides assurance that the releases ofradioactive materials in liquid effluents will be kept "as low as is reasonablyachievable." This control implements the requirements of 10 CFR 50.36a, GeneralDesign Criterion 60 of Appendix A to 10 CFR Part 50 and the design objectivegiven in Section II.D of Appendix I to 10 CFR Part 50. The specified limitsgoverning the use of appropriate portions of the Liquid Radwaste Treatment Systemwere specified as a suitable fraction of the dose design objectives set forth inSection II.A of Appendix I, 10 CFR Part 50 for liquid effluents.
iDOMINION VPAP-2103SREVISION 17PAGE 22 OF 776.2.5 Liquid Sampling IRadioactive liquid wastes shall be sampled and analyzed according to the samplingand analysis requirements in Radioactive Liquid Waste Sampling and AnalysisProgram (Attachment 3).6.3 Gaseous Radioactive Waste Effluents6.3.1 Gaseous Effluent Dose Rate Limitationsa. RequirementDose 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.2. The dose rate limit for 1131, 1133, for tritium, and for all radioactive materials inparticulate form with half-lives greater than 8 days shall be < 1500 mrem/yearto 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 be determined,continuously, to be within Step 6.3.1.a. limits.3. Dose rates due to 1131, 1133, tritium, and all radionuclides in particulate formwith half-lives greater than 8 days, in gaseous effluents shall be determined tobe within the above limits by obtaining representative samples and performinganalyses in accordance with the sampling and analysis program specified onRadioactive Gaseous Waste Sampling and Analysis Program (Attachment 4).IIII DOMINION VPAP-2103SREVISION 17PAGE 23 OF 77c. 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:[(Ki Q ivv _ i -+ (Ki Qipv ' t )] 500 mrem/yr to the total body (8)0 QipvORS1.1M)v ivv) +L +.lMi)Qipv Q )] 3000 mrem/yr to the skin (9)where:Subscripts = vv, refers to vent releases from the building ventilation vent,including Radwaste Facility Ventilation Vent;pv, refers to the vent releases from the process vent;i, refers to individual radionuclideKi = the total body dose factor due to gamma emissions for eachidentified noble gas radionuclide i, in mrem/yr per Curie/m3Li = the skin dose factor due to beta emissions for each identifiednoble gas radionuclide i, in mrem/yr per Curie/mr3Mi = the air dose factor due to gamma emissions for each identifiednoble gas radionuclide, i, in mrad/yr per Curie/m3Qipv = the release rate for ventilation vents or process vent of noblegas radionuclide i, in gaseous effluents in Curie/sec (per site)1.1 = the unit conversion factor that converts air dose to skin dose,in mrem/mradXlaiQ," X/Qip, = the gaseous dispersion factor, sec/m3(See Attachment 7)
DOMINIONVPAP-2103SREVISION 17PAGE 24 OF 772. The dose rate limit for 1131, 1133, tritium, and for all radionuclides in particulateform with half-lives greater than 8 days, shall be determined to be within thelimit by restricting the release rate to:Qv ivv + PiQipv ,pv] < 1500 mrem/yr to the critical organ (10)iIIIIIwhere:Pi= the critical organ dose factor for 1131, 1133, H3, and allradionuclides in particulate form with half-lives greater than 8days, for the child inhalation pathway, in mrem/yr perCurie/m3= the release rate for ventilation vents or process vent of 1131,!133, H3, and all radionuclides i, in particulate form withhalf-lives greater than 8 days, in gaseous effluents in Curie/sec(per site)X/Q,, X/Qit,, -- the gaseous dispersion factor, sec/mn(See Attachment 7)3. All gaseous releases, not through the process vent, are considered ground leveland shall be included in the determination of Q0i.d. Bases -Dose RateThis specification provides reasonable assurance radioactive materials dischargedin gaseous effluents will not result in the exposure of a MEMBER OF THEPUBLIC in an UNRESTRICTED AREA, either at or beyond the SITEBOUNDARY, in excess of the design objectives of Appendix I to 10 CFR Part 50.This specification is provided to ensure that gaseous effluents from all units on thesite will be appropriately controlled. It provides operational flexibility for releasinggaseous effluents to satisfy the Section II.A and II.C design objectives of AppendixI to 10 CFR Part 50. The specified release rate limits restrict, at all times, thecorresponding gamma and beta dose rates above background to a MEMBER OFTHE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500mrem/year to the whole body, less than or equal to 3000 mrem/year to the skin andthe corresponding thyroid dose rate above background to a child via the inhalationpathway to less than or equal to 1500 mrem/year. This specification does not affectthe requirements to comply with the annual limitation of 10 CFR 20.1301(a). Thiscontrol applies to the release of radioactive materials in gaseous effluents from allunits at the site.IIIIIIiIIIIIIIII DOMINION VPAP-2103SREVISION 17PAGE 25 OF 776.3.2 Gaseous Monitoring Instrumentationa. Requirement1. The radioactive gaseous effluent monitoring instrumentation channels shown inRadioactive Gaseous Effluent Monitoring Instrumentation (Attachment 5) shallbe operable with alarm/trip setpoints set to ensure that Step 6.3.1 .a. noble gaslimits are not exceeded. Alarm/trip setpoints of these channels shall bedetermined and adjusted in accordance with Step 6.3.2.d.2. Each radioactive gaseous effluent monitoring instrumentation channelshall be demonstrated operable by Channel Checks, Source Checks, ChannelCalibrations, and Channel Functional Tests at the frequencies shown inRadioactive Gaseous Effluent Monitoring Instrumentation SurveillanceRequirements (Attachment 6).b. Action1. If a radioactive gaseous effluent monitoring instrumentation channel alarm/tripsetpoint 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 inoperableor" Change the setpoint so it is acceptably conservative2. If the number of operable channels is less than the minimum required by tablesin Radioactive Gaseous Waste Sampling and Analysis Program (Attachment 4),take the action shown in those tables.3. Attempt to return instruments to operable status within 30 days. If unsuccessful,explain in the next Annual Radioactive Effluent Release Report why theinoperability was not corrected in a timely manner.
IIDOMINIONVPAP-2103SREVISION 17PAGE 26 OF 77c. Applicable Monitors IRadioactive gaseous effluent monitors for which alarm/trip setpoints shall bedetermined are: IRelease Point Instrument NumberProcess Vent 1-GW-RM-130BCondenser Air Ejector 1-SV-RM-1 112-SV-RM-211Ventilation Vent No. 1 1-VG-RM-104Ventilation Vent No. 2 1-VG-RM-131BRadwaste Facility Vent RRM-101d. Setpoint Calculations1. Setpoint calculations for each monitor listed in Step 6.3.2.c. shall maintain thisrelationship:D > Dpv + Dcae + Dvv(11)where:DDcae= Step 6.3. L.a. dose limits that implement Technical Specifications forthe Station, mrem/yr= the noble gas site boundary dose rate from process vent gaseouseffluent releases, mrem/yr= the noble gas site boundary dose rate from condenser air ejectorgaseous effluent releases, mrem/yr= the noble gas site boundary dose rate from summation of theVentilation Vents 1, 2, and the Radwaste Facility vent gaseouseffluent releases, mrem/yrUIIIIIIIIIIII DOMINION VPAP-2103SREVISION 17PAGE 27 OF 772. Setpoint values shall be determined by:Rm x 2.12 E-03Cm= Fm(12)m FMwhere:m = the release pathway, process vent (pv), ventilation vent (vv)condenser air ejector (cae), or Radwaste Facility (rv)Cm = the effluent concentration limit implementing Step 6.3.1 .a. forthe Station, gCi/mLRm = the release rate limit for pathway m determined frommethodology in Step 6.3.1.c., typically using Xe133 as nuclideto be released, pCi/sec2.12E-03 = CFM per mL/secFm = the maximum flow rate for pathway m, CFMNOTE: According to NUREG-0133, the radioactive effluent radiation monitor alarm/tripsetpoints 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.e. Bases -Radioactive Gaseous Effluent Monitoring InstrumentationThe radioactive gaseous effluent instrumentation is provided to monitor andcontrol, as applicable, the releases of radioactive materials in gaseous effluentsduring actual or potential releases of gaseous effluents. The Alarm/Trip Setpointsfor these instruments shall -be calculated and adjusted in accordance with themethodology and parameters in the ODCM to ensure that the alarm/trip will occurprior to exceeding the gaseous effluent dose rate limits of Section 6.3 of the ODCM.The OPERABILITY and use of this instrumentation is consistent with therequirements of General Design Criteria 60, 63, and 64 of Appendix Ato 10 CFR Part 50.
IDOMINION VPAP-2103SREVISION 17PAGE 28 OF 776.3.3 Noble Gas Effluent Air Dose Limit Ia. Requirement1. The air dose in unrestricted areas due to noble gases released in gaseouseffluents from each unit at or beyond the site boundary shall be limited to:" During any calendar quarter: < 5 mrads for gamma radiation and < 10 mradfor beta radiation" During any calendar year: < 10 mrads for gamma radiation and < 20 mrad forbeta radiation2. Cumulative dose contributions for noble gases for the current calendar quarterand current calendar year shall be determined in accordance with Step 6.3.3.c.at least once per 31 days.b. Action IIf the calculated air dose from radioactive noble gases in gaseous effluents exceedsany of the above limits, prepare and submit to the NRC, within 30 days, a special lreport in accordance with VPAP-2802, Notifications and Reports, that identifies thecauses for exceeding the limits and defines corrective actions that have been takento reduce releases and the proposed corrective actions to be taken to assure thatsubsequent releases will be in compliance with the limits in Step 6.3.3.a.c. Noble Gas Effluent Air Dose CalculationGaseous 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[(MiQivv ) + (MiQipv Q (13)iIII DOMINION VPAP-2103SREVISION 17PAGE 29 OF 77For beta radiation:D = 3.17E-08 [(NiQivv~i) + (NiQipv~ipv)] (14)Where:Subscripts vv, refers to vent releases from the building ventilation vents,including the Radwaste Facility Ventilation Vent and airejectorspv, refers to the vent releases from the process venti, refers to individual radionuclideDg = the air dose for gamma radiation, in mradDb = the air dose for beta radiation, in mradMi = the air dose factor due to garruna emissions for each identifiednoble gas radionuclide i, in mrad/yr per Curie/m3Ni= the air dose factor due to beta emissions for each identifiednoble gas radionuclide i, in mrad/yr per Curie/m3Qivv, 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 yearX/Qi, X/Qip = the gaseous dispersion factor, sec/m3 (See Attachment 7)6.3.4 1-131, 133, H-3 & Radionuclides in Particulate Form Effluent Dose Limita. Requirement1. 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 critical organ2. Cumulative dose contributions to a member of the public from 1"', 1133,tritium, and radionuclides in particulate form with half-lives greater than 8 days,in gaseous effluents released to unrestricted areas for the current calendarquarter and current calendar year shall be determined at least once per 31 daysin accordance with Step 6.3.4.c.
IDOMINION VPAP-2103SREVISION 17PAGE 30 OF 77b. ActionIf the calculated dose from the release of 1131, 1133, tritium, and radionuclides inparticulate form, with half-lives greater than 8 days, in gaseous effluents exceedsany of the above limits, prepare and submit to the NRC, within 30 days, a specialreport in accordance with VPAP-2802, Notifications and Reports, that contains the:1. Causes for exceeding limits.2. Corrective actions taken to reduce releases.3. Proposed corrective actions to be taken to assure that subsequent releases willbe in compliance with limits stated in Step 6.3.4.a.c. Dose CalculationsNOTE: All critical organ doses for each age group are calculated to determine which is thelimiting organ for the period being evaluated.Gaseous releases, not through the process vent, are considered ground level andshall be included in the determination of Q Historical data pertaining to thevolumes and radioactive concentrations of gaseous effluents released in connectionto specific Station functions, such as containment purges, shall be used in theestimates, as appropriate.IIIII DOMINION VPAP-2103SREVISION 17PAGE 31 OF 771. The dose to the maximum exposed member of the public, attributable togaseous effluents at and beyond the site boundary that contain 1131, 133, tritium,and particulate-form radionuclides with half-lives greater than 8 days, shall bedetermined by:Dr= 3.17E -08 [RM(Qiv'D/Qvv + Qpv D/Qpv)+RI(QiVV'X1QV'+QX1QPV) (15)+ RG (Qivv. D/Q,, ++/-,ý DIP") )+/-RH3 (Q1ý. X/IQ V+ Qi X/IQP)]For example:Subscripts = vv, refers to vent releases from the building ventilation vents,including the Radwaste Facility Ventilation Vent and airejectors;pv, refers to the vent releases from the process ventDr = the dose to the critical organ of the maximum exposed memberof the public in mremQiv, Qipv = the release for ventilation vents or process vent of 1131, 1133,tritium, and from all particulate-form radionuclides with half-lives greater than 8 days in Curies3.17 E-08 = the inverse of the number of seconds in a yearXYQIq, X/Qpv = the gaseous dispersion factor, sec/m3(See Attachment 7)D/Qw1, D/Qpv = the gaseous deposition factor, m-2 (See Attachment 7)RM = the cow-milk pathway dose factor due to 1131, 1133, tritium, andfrom all particulate-form radionuclides with half-lives greaterthan eight days, in m2.mrem/yr per Ci/secRI = the inhalation pathway dose factor due to 1131, 1133, tritium,and from all particulate-form radionuclides with half-livesgreater than eight days, in mrem/yr per Ci/m3RG = the ground plane pathway dose factor due to 1111, 1133, tritium,and from all particulate-form radionuclides with half-livesgreater than eight days, in m2-mrem/yr per Ci/secRH3= the tritium dose factor for milk in mrem/yr per Ci/m3 IDOMINION VPAP-2103SREVISION 17PAGE 32 OF 776.3.5 Gaseous Radwaste Treatment iHistorical data pertaining to the volumes and radioactive concentrations of gaseouseffluents released in connection with specific Station functions, such as containmentpurges, shall be used to calculate projected doses, as appropriate.a. Requirement1. Appropriate portions of the Gaseous Radwaste Treatment System shall be usedto reduce radioactive materials in gaseous waste before its discharge, when theprojected gaseous effluent air doses due to gaseous effluent releases, from eachunit to areas at and beyond the site boundary, would exceed 0.2 mrad for gammaradiation and 0.4 mrad for beta radiation, averaged over 31 days.2. The Ventilation Exhaust Treatment System shall be used to reduce radioactivematerials in gaseous waste before its discharge, when the projected doses due togaseous effluent releases, from each unit to areas at and beyond the siteboundary, would exceed 0.3 mrem to the critical organ, averaged over 31 days.3. Doses due to gaseous releases from the site shall be projected at least onceper 31 days, based on the calculations in Step 6.3.5.c.b. ActionIf gaseous waste that exceeds the limits in Step 6.3.5.a. is discharged without itreatment, prepare and submit to the NRC, within 30 days, a special report inaccordance with VPAP-2802, Notifications and Reports, that includes:1. An explanation why gaseous radwaste was being discharged without treatment,identification of any inoperable equipment or subsystems, and the reason for theinoperability.2. Actions taken to restore the inoperable equipment to operable status.3. Summary description of actions taken to prevent recurrence.c. Projected Dose Calculations i1. Determine Dg, the sum of all gaseous open and closed release points, in mrem,by the ith organ, for the quarter. I2. Determine P, the Projection Factor, which is result of 31 divided by the numberof days from start of the quarter to the end of the release.
DOMINION VPAP-2103SREVISION 17PAGE 33 OF 773. Determine Da, additional anticipated dose for gaseous releases by the ith organfor the particular quarter of the release.4. Determine Dp, the 31 day projected dose by the ith organ.Dp = (Dg x P) + Da6.4 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. As indicated on Attachment 3, RadioactiveLiquid Waste Sampling and Analysis Program, prerelease assessments/permits are required forbatch releases. Depending on the affected plant system, continuous releases may or may notallow for a prerelease assessment and are evaluated on a case by case basis.6.4.1 Liquid Waste Batch Releasesa. Operations shall obtain RP authorization before initiating batch releases ofradioactive liquids.b. Release of contents from the following tanks/sumps other than transfers to theRadwaste Facility shall have a release permit before the discharge. Examples ofbatch releases include:" Turbine Building Sumps when RP determines that source activity requiresplacing pumps in manual mode* Condensate Polishing Building Sumps and Steam Generator secondary waterwhen RP determines the presence of contamination from primary-to-secondaryleakage" Radwaste Facility release tanks (LWMT, LDMT)6.4.2 Continuous Liquid Releasesa. Operations shall obtain RP authorization before initiating continuous releases ofradioactive liquids.b. Examples of continuous releases include:" Steam generator blowdown* Component Cooling Water (CCW) heat exchanger to service water leakage, ifapplicable" Turbine building sumps and subsurface drains when pumps are in automaticmode or storm drains IDOMINION VPAP-2103SREVISION 17PAGE 34 OF 776.4.3 Waste Gas Decay Tank (WGDT) Release Permit IOperations shall obtain RP authorization before initiating WGDT releases.6.4.4 Reactor Containment Release Permits iOperations 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 I* Terminated for cause by RP* Receipt of Radiation Monitoring System (RMS) Containment Gas Monitor highalarm6.4.5 Miscellaneous Gaseous Release PermitOperations shall obtain RP authorization before initiating releases of noble gases thatmay not be accounted for by routine sampling, or any planned release not being routedthrough the Process Vent or Ventilation Vents.6.4.6 Radioactive Liquid and Gaseous Release Controls Ia. Operations shall notify RP of pending releases and request RP to initiate theappropriate release permit. Operations shall provide the necessary information to Icomplete the required release permit.b. A representative sample shall be obtained of the source to be released. I1. Operations shall provide RP with liquid samples and sample information (e.g.,time of sample) for samples obtained outside the Primary Sample Room. i2. Chemistry shall provide RP with liquid samples and sample information forsamples obtained from inside the Primary Sample Room. i3. RP shall obtain gaseous samples.c. RP shall perform required sample analyses.d. RP shall calculate and record the following information on a release permit:" Maximum authorized release rate* Applicable conditions or controls pertaining to the release DOMINION VPAP-2103SREVISION 17PAGE 35 OF 77e. RP shall notify the Operations Shift Supervision if it is determined that a releasemay not be within the effluent dose limits.f. Upon receipt of a release permit from RP, Operations shall:1. Verify the correct source is authorized for release.2. Note maximum authorized release rate.3. Note and ensure compliance with any indicated controls or conditionsapplicable to the release.g. When commencing release, Operations shall provide RP with required information.As appropriate, required information shall include:" Date and time release was started" Starting tank/sump level" Beginning pressure" Release flow rate" Dilution water flow rateh. Upon terminating the release, Operations shall return the permit to RP and provideinformation necessary for completion of permit. As appropriate, requiredinformation shall include:" Date and time release was stopped* Tank/sump ending level" Release flow rate just prior to termination" Ending pressure" Volume released6.5 Total Dose Limit to Public From Uranium Fuel Cycle Sources6.5.1 RequirementThe 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).
IDOMINION VPAP-2103SREVISION 17PAGE 36 OF 776.5.2 Action Ua. If the calculated doses from release of radioactive materials in liquid or gaseouseffluents exceed twice the limits in Steps 6.2.3.a., 6.3.3.a., or 6.3.4.a., calculate(including direct radiation contribution from the units and from outside storagetanks) whether limits in Step 6.5.1 have been exceeded.b. If the limits in Step 6.5.1 have been exceeded, prepare and submit to the NRC,within 30 days, a special report in accordance with VPAP-2802, Notifications andReports, that defines the corrective action to be taken to reduce subsequent releasesand to prevent recurrence, and includes a schedule for achieving conformance withthe limits. Special reports, as defined in 10 CFR 20.2203(a)(4), shall include:1. An analysis that estimates the radiation exposure (dose) to a real individualfrom uranium fuel cycle sources, including all effluent pathways and direct Iradiation, for the calendar year that includes the releases covered by the report.2. A description of the levels of radiation and concentrations of radioactive Imaterial involved, and the cause of the exposure levels or concentrations.3. If the estimated dose exceeds the limits in Step 6.5.1, and if the release Icondition that violates 40 CFR 190 has not already been corrected, the specialreport shall include a request for a variance in accordance with the provisions of40 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 Monitoring6.6.1 Monitoring Programa. Requirement1. The Radiological Environmental Monitoring Program shall be conducted asspecified in Radiological Environmental Monitoring Program (Attachment 8).2. Samples shall be collected from specific locations specified in EnvironmentalSampling Locations (Attachment 9).II DOMINION VPAP-2103SREVISION 17PAGE 37 OF 773. Samples shall be analyzed in accordance with:* Radiological Environmental Monitoring Program (Attachment 8)requirements" Detection capabilities required by Detection Capabilities for EnvironmentalSample Analysis (Attachment 10)" Guidance of the Radiological Assessment Branch Technical Position onEnvironmental Monitoring dated November, 1979, Revision No. 1b. Action1. If the Radiological Environmental Monitoring Program is not being conductedas required in Step 6.6.1 .a., report the situation in accordance with VPAP-2802,Notifications and Reports, by preparing and submitting to the NRC, in theAnnual Radiological Environmental Operating Report required by TechnicalSpecification (Surry Technical Specification 6.6.B.2), a description of thereasons for not conducting the program as required, and the plan for precludingrecurrence.2. If, when averaged over any calendar quarter, radioactivity exceeds the reportinglevels of Reporting Levels for Radioactivity Concentrations in EnvironmentalSamples (Attachment 11), prepare and submit to the NRC, within 30 days, aspecial report in accordance with VPAP-2802, Notifications and Reports, that:" Identifies the causes for exceeding the limits, and" Defines the corrective actions to be taken to reduce radioactive effluents sothat the potential annual dose to a member of the public is less than thecalendar 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 11) aredetected in the sampling medium, the report shall be submitted if:concentration (1) + concentration (2) + .1.0 (15)reporting level (1) reporting level (2)
IDOMINION VPAP-2103SREVISION 17PAGE 38 OF 773. When radionuclides other than those listed in Reporting Levels for mRadioactivity Concentrations in Environmental Samples (Attachment 11) 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 accordance with VPAP-2802, INotifications and Reports.4. If milk or fresh leafy vegetable samples are unavailable from one or more of the 1sample locations required by Radiological Environmental Monitoring Program(Attachment 8), identify locations for obtaining replacement samples and addthem to the radiological environmental monitoring program within 30 days. Thespecific locations from which samples were unavailable may then be deletedfrom the monitoring program. Identify the cause of the unavailability ofsamples and identify the new locations for obtaining replacement samples in thenext Annual Radioactive Effluent Release Report in accordance with *VPAP-2802, Notifications and Reports.6.6.2 Land Use Census Ia. RequirementA land use census shall be conducted and shall identify, within a distance of 8 kmr(5 miles), the location in each of the 16 meteorological sectors of the following:* Nearest milk animal-Nearest residence-Nearest garden greater than 50 m2 (500 ft2) that produces broad leaf vegetation1. 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 usecensus results shall be included in the Annual Radiological EnvironmentalOperating Report in accordance with VPAP-2802, Notifications and Reports.I DOMINION VPAP-2103SREVISION 17PAGE 39 OF 772. 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 RadiologicalEnvironmental Monitoring Program (Attachment 8) shall be followed,including analysis of control samples.b. Action1. If a land use census identifies locations that yield a calculated dose or dosecommitment greater than the values currently being calculated in Step 6.3.4.a.,identify the new locations in the next Annual Radioactive Effluent ReleaseReport in accordance with VPAP-2802, Notifications and Reports.2. If a land use census identifies locations that yield a calculated dose or dosecommitment (via the same exposure pathway) 20 percent greater than at alocation from which samples are currently being obtained, add the newlocations to the Radiological Environmental Monitoring Program within 30days. Sampling locations, excluding the control station location, that have thelowest calculated dose or dose commitments (via the same exposure pathway)may be deleted from the monitoring program. Identify new locations in the nextAnnual Radioactive Effluent Release Report and include in the report revisedfigures and tables reflecting the new locations in accordance with VPAP-2802,Notifications and Reports. [Commitment 3.2.1]6.6.3 Interlaboratory Comparison Programa. RequirementRadioactive materials (which contain nuclides produced at the Station), supplied aspart of an Interlaboratory Comparison Program, shall be analyzed.
IDOMINION VPAP-2103SREVISION 17PAGE 40 OF 77b. Action1. Analyses shall be performed at least semi-annually as follows:Program Cross-Check of IMilk 1131, Gamma, Sr89 and Sr90Water Gross Beta, Gamma, 1131, H3 (Tritium), Sr89and Sr90 (blind-any combinations of aboveradionuclides)Air Filter Gross Beta, Gamma, Sr902. If analyses are not performed as required by Step 6.6.3.b., report in the AnnualRadiological Environmental Operating Report in accordance with VPAP-2802,Notifications and Reports, the corrective actions taken to prevent recurrence.c. ResultsResults shall be reported in the Annual Radiological Environmental MonitoringReport in accordance with VPAP-2802, Notifications and Reports.6.7 Reporting Requirements6.7.1 Annual Radiological Environmental Operating ReportRoutine Radiological Environmental Operating Reports covering the operation of theunits during the previous calendar year shall be submitted prior to May 1 of each year.A single submittal may be made for the Station. Radiological Environmental IOperating Reports shall include:a. Summaries, interpretations, and analysis of trends of results of radiological Ienvironmental surveillance activities for the report period, including:" A comparison (as appropriate) with preoperational studies, operational controls, Iand previous environmental surveillance reports" An assessment of the observed impacts of the plant operation on the environment* Results of land use census per Step 6.6.2I DOMINION VPAP-2103 SREVISION 17PAGE 41 OF 77b. Results of analysis of radiological environmental samples and of environmentalradiation measurements taken per Step 6.6.1, Monitoring Program. Results shall besummarized and tabulated in the format of the table in the Radiological AssessmentBranch 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 environmental monitoring program.d. At least two legible maps covering sampling locations, keyed to a table givingdistances and directions from the centerline of one reactor. One map shall coverstations near the site boundary; a second shall include more distant stations.e. Results of Station participation in the Interlaboratory Comparison Program,per Step 6.6.3.f. Discussion of deviations from the Station's environmental sampling schedule perRadiological Environmental Monitoring Program (Attachment 8).g. Discussion of analyses in which the lower limit of detection (LLD) required byDetection Capabilities for Environmental Sample Analysis (Attachment 10) wasnot achievable.h. Results of analysis of ground water wells described in the environmentalmonitoring program, whether required by the program or not.
IDOMINION VPAP-2103SREVISION 17PAGE 42 OF 77NOTE: NUREG-0543 states: "There is reasonable assurance that sites with up to four Ioperating reactors that have releases within Appendix I design objective values arealso in conformance with the EPA Uranium Fuel Cycle Standard, 40 CFR Part 190."6.7.2 Annual Radioactive Effluent Release Reporta. Requirement -Station IRadioactive Effluent Release Reports covering operation of the units during theprevious 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.[Commitment 3.2.2]2. 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 in Iaccordance 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 Report and involve thedischarge of contents of the wrong Waste Gas Decay Tank or the wrong liquidradwaste release tank" Unplanned releases from large leaks due to unexpected valve or pipefailures that result in a quantity of release such that a 10 CFR 50.72, 1Immediate Notification Requirements for Operating Nuclear Power Reactorsor 10 CFR 50.73, Licensee Event Report System, report is required" Unplanned releases as determined by Radiation Protection Supervision,which may or may not require a Condition Report DOMINION VPAP-2103SREVISION 17PAGE 43 OF 774. Major changes to radioactive liquid, gaseous, and solid waste treatment systemsduring the reporting period.5. Changes to VPAP-2103S, Offsite Dose Calculation Manual (Surry) (SeeStep 6.7.4).6. A listing of new locations for dose calculations or environmental monitoringidentified by the land use census (See Step 6.6.2).7. A 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.8. Groundwater sample results from locations not part of the RadiologicalEnvironmental Monitoring Program.b. Dose Assessment -Station1. Radiation dose to individuals due to radioactive liquid and gaseous effluentsfrom 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 public due to radioactiveliquid and gaseous effluents from the Station and from the ISFSI shall beincorporated with the dose assessment performed above. If the dose to themaximum exposed member of the public exceeds twice the limits of 6.2.3.a. 1,6.2.3.a.2, 6.3.3.a. 1, or 6.3.4.a. 1, the dose assessment shall include thecontribution from direct radiation.3. Meteorological conditions during the previous calendar year or historicalannual average atmospheric dispersion conditions shall be used to determinegaseous pathway doses.
IDOMINION VPAP-2103SREVISION 17PAGE 44 OF 77NOTE: The Annual Radioactive Effluent Release Reports for Surry Station and Surry ISFSI Iare separate and not submitted as a combined report.c. Requirement -ISFSI 11. Radioactive Effluent Release Report covering operation of the ISFSI during theprevious 12 months of operation shall be submitted within 60 days afterJanuary 1.2. The ISFSI Radioactive Effluent Release Report shall specify the quantities of Ieach of the principal radionuclides released to the environment in liquid and ingaseous effluents.3. Dose Assessment -ISFSIProvide such information as may be required by the Commission to estimate Ipotential radiation dose commitment to the public resulting from effluentreleases from the ISFSI.6.7.3 Annual Meteorological Dataa. Meteorological data collected during the previous year shall be in the form of jointfrequency distributions of wind speed, wind direction, and atmospheric stability.b. Meteorological data shall be retained in a file on site and shall be made available toNRC upon request.6.7.4 Changes to the ODCMChanges to the ODCM shall be:a. Approved by the 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.III DOMINION VPAP-2103SREVISION 17PAGE 45 OF 772. 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 I* Technical Specificationsc. Submitted to NRC in the form of a complete, legible copy of the entire ODCM as apart of, or concurrent with the Annual Radioactive Effluent Release Report for theperiod of the report in which any change was made. Each change shall be identifiedby markings in the margin of the affected pages, clearly indicating the area of thepage that was changed, and shall indicate the date (e.g., month/year) the change wasimplemented.d. Submitted to NRC in accordance with VPAP-2802, Notifications and Reports.6.7.5 Industry Ground Water Protection Initiativea. ProgramThe Ground Water Protection Program is established in Administrative ProcedureRP-AA-502, Groundwater Protection Program.NOTE: RP-AA-502 Attachment 1, Voluntary Communication Protocol, contains a flow chartto assist with determining if an event should be communicated to State and Localofficials and to the NRC.b. Communications1. Informal communication shall be made to the State, Local and NRC officials bythe end of the next business day for any spill or leak meeting the requirementsof 6.7.2.a.7.
UDOMINION VPAP-2103SREVISION 17PAGE 46 OF 772. Informal communication shall be made to the State, Local and NRC officials by Ithe end of the next business day for a water sample result that meets thefollowing criteria:* An off-site ground water or surface water sample result that exceeds thereporting criteria listed in Reporting Levels for Radioactivity Concentrationsin Environmental Samples (Attachment 11)." An on-site surface water sample result, that is hydrologically connected toground water, or ground water that is or could be used as a source of drinking Iwater, that exceeds the reporting criteria listed in Reporting Levels forRadioactivity Concentrations in Environmental Samples (Attachment 11).c. 30-Day Reports1. Submit a written 30-day report to the NRC for a water sample result for on-siteor off-site ground water that is or could be used as a source of drinking waterthat exceeds the reporting criteria listed in Reporting Levels for RadioactivityConcentrations in Environmental Samples (Attachment 11). A 30-day report isonly required on the initial discovery of a contaminated ground water plume.2. Concurrently submit a copy of the written 30-day NRC report to the appropriateState and Local officials.d. Annual Reports1. Report sample results communicated per 6.7.5.b. 1 in the Annual RadiologicalEffluent Release Report.2. Report ground water sample results that are not included in the RadiologicalEnvironmental Monitoring Program in the Annual Radiological EffluentRelease Report.3. Report sample results communicated per 6.7.5.b.2 in the Annual RadiologicalEffluent Release Report or the Annual Radiological Environmental OperatingReport.4. Report ground water sample results that are included in the RadiologicalEnvironmental Monitoring Program in the Annual Radiological EnvironmentalOperating Report.II DOMINION VPAP-2103SREVISION 17PAGE 47 OF 777.0 RECORDS7.1 The following record(s) completed as a result of this procedure are required to be transmittedto Nuclear Document Management (NDM). The records have been identified and retentionrequirements established for the Nuclear Records Retention Schedule (NRRS) perRM-AA-101, Record Creation, Transmittal, and Retrieval.7.1.1 Quality Assurance Records" Records of changes to the ODCM in accordance with Step 6.7.4" Records of meteorological data in accordance with Step 6.7.3" Records of sampling and analyses" Records of radioactive materials and other effluents released to the environment" Records of preventive maintenance, surveillances, and calibrations7.1.2 Non-Quality Assurance RecordsNone7.2 The following record(s) completed as a result of this procedure are NOT required to betransmitted to Nuclear Document Management (NDM), but are required to be retained asindicated below. The NRRS has been updated and Alternate Storage approved per RM-AA-101 for Quality Assurance Records.7.2.1 Quality Assurance RecordsNone7.2.2 Non-Quality Assurance RecordsNone7.3 The following item(s) completed as a result of this procedure are NOT records and are NOTrequired to be transmitted to Nuclear Document Management (NDM).None ItDOMINIONVPAP-2103SREVISION 17PAGE 48 OF 77ATTACHMENT 1(Page 1 of 1)Radioactive Liquid Effluent Monitoring Instrumentation IInstrument Minimum ActionOperableChannelsI. GROSS RADIOACTIVITY MONITORS PROVIDING ALARMAND AUTOMATIC TERMINATION OF RELEASE(a) Radwaste Facility Liquid Effluent Line,RE-RRM-13 12. GROSS BETA OR GAMMA RADIOACTIVITY MONITORSPROVIDING ALARM BUT NOT PROVIDING AUTOMATICTERMINATION OF RELEASE(a) Circulating Water Discharge Lines,Unit 1: I-SW-RM-120 1 2Unit 2: 2-SW-RM-220 1 2(b) Component Cooling Service Water Effluent Lines,I-SW-RM- 107A 1 2I-SW-RM- 107B 1 2I-SW-RM- 107C 1 2I-SW-RM- 107D 1 23. FLOW RATE MEASUREMENT DEVICES(a) Radwaste Facility Liquid Effluent Line,Instrument Loop RLW-153 1IIIIIIIIIIIIIIIIIACTION 1:ACTION 2:If the number of operable channels is less than required, effluent releases via thispathway shall be suspended.If the number of operable channels is less than required, effluent releases via thispathway may continue provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples arecollected and analyzed for principal gamma emitters, as defined in Radioactive LiquidWaste Sampling and Analysis Program (Attachment 3). When the effluent release viathis pathway continues, then initiate the "Loss of Radioactive Liquid EffluentMonitoring Instrumentation Sampling Schedule" attachment in HP-3010.021,Radioactive Liquid Waste Sampling and Analysis.
DOMINIONVPAP-2103SREVISION 17PAGE 49 OF 77ATTACHMENT 2(Page 1 of 1)Radioactive Liquid Effluent Monitoring Instrumentation Surveillance RequirementsChannel Description Channel Source Channel ChannelCheck Check Calibration Functional Test1. GROSS RADIOACTIVITY MONITORSPROVIDING ALARM AND AUTOMATICTERMINATION OF RELEASE(a) Radwaste Facility Liquid Effluent Line,RE-RRM-131 D P R Q2. GROSS BETA OR GAMMA RADIOACTIVI-TY MONITORS PROVIDING ALARM BUTNOT PROVIDING AUTOMATIC TERMI-NATION OF RELEASE(a) Circulating Water Discharge Lines,Unit 1: 1-SW-RM-120Unit 2: 2-SW-RM-220(b) Component Cooling Service WaterEffluent Lines,I-SW-RM-107A1-SW-RM- 107B1-SW-RM-107C D M Q1-SW-RM-107D3. FLOW RATE MEASUREMENT DEVICES(a) Radwaste Facility Liquid Effluent Line,Instrument Loop RLW-153 DR N/A R N/A IIDOMINIONVPAP-2103SREVISION 17PAGE 50 OF 77ATTACHMENT 3(Page 1 of 3)Radioactive Liquid Waste Sampling and Analysis Program *Actiity Lower Limit ofLiquid Release Sampling Minimum Analysis Type of Activi Detection (LLD)Type Frequency Frequency Analysis (ptCi/mL), (Note 1)P P Principal Gamma 5 x 10-7Emitters (Note 3)(Each Batch) (Each Batch) 1131 1 x 10-6Dissolved andBatch Releases P M Entrained Gases 1 x 10-(Gamma Emitters)(Note 2) P M Composite H3 1 x 10-5(Each Batch) (Note 4) Gross Alpha 1 x 10-7P Q Composite Sr89 and Sr90 5 x 10-8(Each Batch) (Note 4) Fe55 1 x 10-6Continuous W Composite Principal Gamma 5 x 10-7Emitters (Note 6)(Note 6) (Note 6) 1131 1 x 10-6Continuous M Dissolved andContnuos G M Entrained Gases 1 x I05Releases Grab Sample (Gamma Emitters)(Note 5) Continuous M Composite H3 1 x 10-5(Note 6) (Note 6) Gross Alpha 1 x 10-7Continuous Q Composite Sr89 and Sr90 5 x 10-8(Note 6) (Note 6) Fe551 x 10-6IIIIIIIIIIIIIIIII DOMINION VPAP-2103SREVISION 17PAGE 51 OF 77ATTACHMENT 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 = b(8-1)E
- V e 2.22E+06
- Y
- e-(X(At)Where:LLD = the "a priori" (before the fact) Lower Limit of Detection (as microcuriesper unit mass or volume) (See Subsection 4.9)Sb = the standard deviation of the background counting rate or of the countingrate of a blank sample as appropriate (as counts per minute, cpm)E = the counting efficiency (as counts per disintegration)V = the sample size (in units of mass or volume)2.22E+06 = the number of disintegrations per minute (dpm) per microcurieY = the fractional radiochemical yield (when applicable)k = the radioactive decay constant for the particular radionuclideAt = the elapsed time between the midpoint of sample collection and time ofcountingTypical 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 measurementsystem 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 appropriate methods will be used to obtain arepresentative sample for analysis.
IDOMINION VPAP-2103SREVISION 17PAGE 52 OF 77ATTACHMENT 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 sampled is proportional to thequantity of liquid waste discharged and for which the method of sampling employed resultsin a specimen that is representative of the liquids released.NOTE 5: A continuous release is the discharge of liquid wastes of a non-discrete volume, e.g., froma volume of a system that has an input flow during the continuous release.NOTE 6: To be representative of the quantities and concentrations of radioactive materials in liquideffluents, composite sampling shall employ appropriate methods which will result in aspecimen representative of the effluent release.IIIIIII DOMINIONVPAP-2103SREVISION 17PAGE 53 OF 77ATTACHMENT 4(Page 1 of 4)Radioactive Gaseous Waste Sampling and Analysis ProgramGaseous Release Sampling Minimum Analysis Type of Activity Lower Limit ofType Frequency Frequency Analysis Detection (LLD)(lRCi/mL), (Note 1)A. Waste Gas Prior to Release Prior to Release Principal Gamma 10-Storage Tank (Each Tank) (Each Tank) Emitters (Note 2)(Grab Sample)Prior to Release Prior to Release Principal Gamma I X 10-4B. Containment Emitters (Note 2)Purge (Each PURGE) (Each PURGE) H3 1 x 10-6(Grab Sample)C. Ventilation Weekly Weekly Principal Gamma 1 x 10-4(1)Process Vent (Grab Sample) Emitters (Note 2)(2)Vent Vent #1(3)Vent Vent #2 (Note 3) (Note 3) H3 1 x 10-6(4)SRF VentContinuous Weekly (Note 5) 1 1 x(Note 4) (Charcoal Sample) 1133 1 x 10-10Continuous Weekly (Note 5) Principal Gamma 1 x 10-11All Release (Note 4) Particulate Sample Emitter (Note 2)Continuous WeeklyTypes as listed (Note 4) Composite Gross Alpha l x 10-11Particulate Samplein A, B, and C Continuous QuarterlyComposite Sr89 and Sr9° 1 x 10-11(Note 4) ParticulateContinuous Noble Gas Monitor Noble Gases Gross 1 x 10-6(Note 4) Beta and GammaWeekly Weekly Principal Gamma 1 x 10-Condenser Air Emitters (Note 2)Ejector Grab Sample (Note 3) H3 1 x 10-6(Note 3)
IIDOMINIONVPAP-2103SREVISION 17PAGE 54 OF 77ATTACHMENT 4(Page 2 of 4)Radioactive Gaseous Waste Sampling and Analysis Program 1Gaseous Release Sampling Minimum Analysis Type of Activity Lower Limit ofType Frequency Frequency Analysis Detection (LLD)(tCi/mL), (Note 1)Prior to Release Prior to Release Principal Gamma 1 X 10-4Emitters(Grab Sample) (Each Release) H3 1 x 10-6Continuous Charcoal Sample 1131 1 x 1011(Note 4) (Note 6) 0133 1 x 10-10ContainmentContinuous Particulate Sample Principal Gamma IHog Depres- (Note 4) (Note 6) Emitter (Note 2)surization Continuous Composite Particu-Cotinuus late Sample Gross Alpha 1 x 10-10(Note 6)Continuous Composite Particu- 89late Sample Sr and Sr90 1 x 10-10(Note 4)(Note 6)UIIIIIIIIIIIIII DOMINION VPAP-2103SREVISION 17PAGE 55 OF 77ATTACHMENT 4(Page 3 of 4)Radioactive Gaseous Waste Sampling and Analysis ProgramNOTE 1: For a particular measurement system (which may include radiochemical separation):4.66 sbLLD = b(10-1)E
- V e 2.22E+06 9 Y e -(XAt)Where:LLD = the "a priori" (before the fact) Lower Limit of Detection as defined above(as microcuries per unit mass or volume) (See Subsection 4.9).Sb = the standard deviation of the background counting rate or of the countingrate of a blank sample as appropriate (as counts per minute, cpm).E = the counting efficiency (as counts per disintegration).V = the sample size (in units of mass or volume).2.22E+06 = the number of disintegrations per minute (dpm) per microcurie.Y = the fractional radiochemical yield (when applicable).x = the radioactive decay constant for the particular radionuclide.At = the elapsed time between the midpoint of sample collection and time ofcounting.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 measurementsystem and not a "posteriori" (after the fact) limit for a particular measurement.
IDOMINION VPAP-2103SREVISION 17PAGE 56 OF 77ATTACHMENT 4(Page 4 of 4)Radioactive Gaseous Waste Sampling and Analysis ProgramNOTE 2: The principal gamma emitters for which the LLD specification applies exclusively are thefollowing radionuclides: Kr87, Kr88 Xe133, Xe133m, Xe135, 135m 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 nuclides with half lives greater than 8 days, that are measurable andidentifiable at levels exceeding the LLD, together with the above nuclides, shall also beidentified and reported.NOTE 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, when:a.. Analysis shows that the dose equivalent 1131 concentration in the primary coolant hasincreased more than a factor of 3; andb. The noble gas activity monitor shows that effluent activity has increased by more thana factor of 3.NOTE 4: The ratio of the sample flow rate to the sampled stream flow rate shall be known for theperiod covered by each dose or dose rate calculation made in accordance withSteps 6.3.1, 6.3.3, and 6.3.4.NOTE 5: Samples shall be changed at least once per seven days and analyses shall be completed Iwithin 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from sampler). Sampling shall also beperformed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least seven days following each shutdown, start-up, or thermal power change exceeding 15 percent of rated thermal power in one hour, andanalyses shall be completed within 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 24hours are analyzed, the corresponding LLDs may be increased by a factor of 10. Thisrequirement applies if:a. Analysis shows that the dose equivalent 1131 concentration in the primary coolant has Iincreased by a factor of 3; andb. Noble gas monitor shows that effluent activity has increased more than a factor of 3. INOTE 6: To be representative of the quantities and concentrations of radioactive materials in gaseouseffluents, composite sampling shall employ appropriate methods that will result in a Ispecimen representative of the effluent release.II DOMINIONVPAP-2103SREVISION 17PAGE 57 OF 77ATTACHMENT 5(Page 1 of 2)Radioactive Gaseous Effluent Monitoring InstrumentationMINIMUMINSTRUMENT OPERABLE ACTIONCHANNELS1. PROCESS VENT SYSTEM(a) Noble Gas Activity Monitor -Providing Alarm andAutomatic Termination of Release:I-GW-RM- 130B 1 1(b) Iodine Sampler:Continuous HP Sampler, or1-GW-RM-130-1 (NOTE 1) 1 2In-Line Particulate / Iodine Sampler(c) Particulate Sampler:Continuous HP Sampler, orl-GW-RM-130-1 (NOTE 1) 1 2In-Line Particulate / Iodine Sampler(d) Process Vent Flow Rate Monitor:1-GW-FT- 100 1 3(e) Sampler Flow Rate Measuring Device:HP Sampler Rotometer or MGPI Flow Rate Measuring 1 3Device2. CONDENSER AIR EJECTOR SYSTEM(a) Gross Activity Monitor:l-SV-RM- 111 1 12-SV-RM-211 1 1(b) Air Ejector Flow Rate Measuring Device:Unit 1: 1-VP-FI-lA 1 31-VP-Fl-lB 1 3Unit 2: 2-VP-FI-lA 1 32-VP-FI- 1B 1 33. VENTILATION VENT SYSTEM(a) Noble Gas Activity Monitor:SRF: RRM-101 1 1SPS: Vent #1, 1-VG-RM-104 1 1Vent #2, 1 -VG-RM- 131B 1 1(b) Iodine Sampler:SRF: RRM-101 1 2SPS: Vent #1, 1-VG-RM-104 (NOTE 2) 1 2Vent #2, Continuous HP Sampler, or1-VG-RM-131-1 (NOTE 1) 1 2In-Line Particulate / Iodine Sampler IIDOMINIONVPAP-2103SREVISION 17PAGE 58 OF 77ATTACHMENT 5(Page 2 of 2)Radioactive Gaseous Effluent Monitoring Instrumentation 1MINIMUMINSTRUMENT OPERABLE ACTIONCHANNELS(c) Particulate Sampler:SRF: RRM-101 1 2SPS: Vent #1, VG-RM-104 (NOTE 2) 1 2Vent #2, HP Continuous Sampler, orl-VG-RM-131-1 (NOTE 1) 1 2In-Line Particulate / Iodine Sampler(d) Ventilation Vent Flow Rate Monitor:SRF: 01-RHV-FT-156 1 3SPS: Vent#1, 1-VS-FT-119 1 3Vent #2, 1-VS-FT- 116 1 3(e) Sampler Flow Rate Measuring Device:SRF: RRM-101 1 3SPS: Vent #1, l-VG-RM-104 (NOTE 2) 1 3Vent #2, HP Sampler Rotometer or 1 3MGPI Flow Rate Measuring DeviceNOTE 1: The mark number listed refers to the entire radiation monitor skid which includes particulate, iodine,and noble gas components.NOTE 2: Vent # 1, 1-VG-RM-104, HP continuous sampler pump automatically maintains isokinetic sampleflow when changes in stack flow are detected. Isokinetic sample flow adjustment can take15 -20 minutes. [Commitment 3.2.3]ACTION 1: If the number of operable channels is less than required, effluent releases via this path may continueprovided that the best efforts are made to repair the channel and that grab samples are taken at least onceper 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 for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. When the effluent releasevia this pathway continues, then initiate the "Loss of Radioactive Gaseous Effluent MonitoringInstrumentation Sampling Schedule" attachment in HP-3010.031, Radioactive Gaseous Waste Samplingand Analysis. [Commitment 3.2.4]ACTION 2: If the number of operable channels is less than required, effluent releases via this pathway may continueprovided that the best efforts are made to repair the channel and that the samples are continuouslycollected with auxiliary sampling equipment within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the initiation of this ACTIONstatement as required in Radioactive Gaseous Waste Sampling and Analysis Program (Attachment 4).[Commitment 3.2.4]ACTION 3: If the number of operable channels is less than required, effluent releases via this pathway may continueprovided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.UIIIIIIIIIIIII DOMINIONVPAP-2103SREVISION 17PAGE 59 OF 77ATTACHMENT 6(Page 1 of 2)Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance RequirementsCHANNEL CHANNEL SOURCE CHANNEL CHANNELDESCRIPTION CHECK CHECK CALIBRATION FUNCTIONALTEST1. PROCESS VENT SYSTEM(a) Noble Gas Activity Monitor -Providing Alarm and AutomaticTermination of Releasel-GW-RM-130B D M R Q(b) Iodine Sampler (NOTE 1)Process Vent Continuous HPSampler, or 1-GW-RM-130-l W N/A N/A N/AIn-Line Particulate / Iodine Sampler(c) Particulate Sampler (NOTE 1)Process Vent Continuous HPSampler, or I-GW-RM-130-1 W N/A N/A N/AIn-Line Particulate / Iodine Sampler(d) Process Vent Flow Rate MonitorI-GW-FT-100 D N/A R N/A(e) Sampler Flow Rate MeasuringDeviceHP Sampler Rotometer, or D N/A SA N/AMGPI Flow Rate Measuring Device D N/A R N/A2. CONDENSER AIR EJECTOR SYSTEM(a) Gross Activity MonitorUnit 1: 1-SV-RM- l11Unit 2:2-SV-RM-211(b) Air Ejector Flow Rate MeasuringDeviceUnit 1: 1-VP-FI-lA1-VP-Fl- 1BI-PF-IBD N/A R N/AUnit 2: 2-VP-Fl-IA2-VP-FI-I B3. VENTILATION VENT SYSTEM(a) Noble Gas Activity MonitorSRF: RRM-101SPS: 1-VG-RM-131B D M R Q1-VG-RM-104 DOMINIONVPAP-2103SREVISION 17PAGE 60 OF 77ATTACHMENT 6(Page 2 of 2)Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance RequirementsCHANNELCHANNEL CHANNEL SOURCE CHANNEL FUN NALDESCRIPTION CHECK CHECK CALIBRATION FUNCTIONALTEST(b) Iodine Sampler (NOTE 1)SRF: RRM-101SPS: Vent #1, I-VG-RM-104Vent #2, Continuous HPSampler or 1 -VG-RM- 131-1In-Line Particulate / IodineSampler(c) Particulate Sampler (NOTE 1)SRF: RRM-101SPS: Vent #1, 1-VG-RM-104Vent #2, Continuous HPSampler or 1-VG-RM- 131-1In-Line Particulate / IodineSampler(d) Ventilation Vent Flow Rate MonitorSRF:01-RHV-FT- 156SPS: Vent#l1, I-VS-FT-119 D N/A R N/AVent #2, I-VS-FT-116(e) Sampler Flow Rate MeasuringDevice (NOTE 1)SRF: RRM-101 D N/A R N/ASPS: Vent #1, I-VG-RM-104 D N/A R N/AVent #2, HP Sampler Rotometer D N/A R N/Aor MGPI Flow Rate Measuring D N/A SA N/ADeviceNOTE 1:The mark numbers listed above in 1(b), 1(c), 3(b), 3(c), and 3(e) refer to the gaseouseffluent radiation monitor or monitor skid with which the iodine and particulatesamplers and the flow rate measuring devices are associated. The listed mark numbersdo not refer to the particulate radiation monitor.IIIIIIIIIIIIIIII DOMINIONVPAP-2103SREVISION 17PAGE 61 OF 77ATTACHMENT 7(Page 1 of 1)Dispersion and Deposition FactorsDescription Sector Distance, Ventilation Vent Process Vent_ meters X/Q D/Q X/Q D/QN 500 1.4E-05 1.6E-08 4.2E-08 3.9E-10NNE 532 1.8E-05 3.3E-08 1.2E-07 1.2E-09NE 629 1.3E-05 3.OE-08 1.8E-07 1.6E-09ENE 806 7.1E-06 1.3E-08 1.8E-07 1.8E-09E 1210 2.7E-06 7.2E-09 2.6E-07 1.8E-09ESE 1984 9.7E-07 3.2E-09 2.4E-07 1.7E-09SE 1371 2.3E-06 6.9E-09 2.6E-07 2.1E-09SSE 919 4.6E-06 9.5E-09 2.3E-07 1.2E-09Site Boundary S 645 6.OE-06 1.1E-08 1.7E-07 1.3E-09SSW 565 6.4E-06 1.2E-08 1.3E-07 1.4E-09SW 548 9.8E-06 1.8E-08 1.3E-07 1.3E-09WSW 656 8.3E-06 1.6E-08 1.4E-07 1.3E-09W 565 1.1E-05 2.8E-08 1.2E-07 1.OE-09WNW 565 1.4E-05 2.6E-08 8.7E-08 5.8E-10NW 581 1.3E-05 1.7E-08 1.2E-07 8.9E-10NNW 581 9.5E-06 1.1E-08 5.1E-08 3.IE-10N 6534 2.4E-07 2.1E-10 6.7E-08 8.8E-11NNE 3122 1.OE-06 1.7E-09 1.9E-07 3.7E-10NE 7564 2.8E-07 4.2E-10 6.7E-08 1.8E-10SE 4554 3.5E-07 8.7E-10 8.7E-08 2.7E-10SSE 4265 3.8E-07 6.9E-09 9.5E-08 2.5E-10S 2736 5.5E-07 9.7E-10 1.9E-07 5.7E-10Resident SSW 2977 4.2E-07 7.6E-10 1.4E-07 4.5E-10SW 3637 4.5E-07 7.7E-10 1.2E-07 3.4E-10WSW 660 6.4E-06 1.2E-08 1.8E-07 1.3E-09W 5053 3.4E-07 6.9E-10 8.1E-08 2.IE-10WNW 7886 2.2E-07 2.9E-10 4.9E-08 9.4E-11NW 7467 2.2E-07 2.1E-10 5.8E-08 1.3E-10NNW 6035 2.3E-07 2.OE-10 6.2E-08 7.1E-11Milk Cow SSW 7693 1.OE-07 1.4E-10 5.OE-08 1.2E-10NNW 5938 2.4E-07 2.1E-10 6.3E-08 7.1E-11S 3235 4.3E-07 7.2E-10 1.6E-07 4.3E-10SSW 3122 3.9E-07 7.OE-10 1.3E-07 4.1E-10Garden SW 7596 1.5E-07 2.1E-10 5.3E-08 1.2E-10WSW 5713 2.OE-07 3.1E-10 7.5E-08 1.8E-10W 5536 2.9E-07 5.8E-10 7.5E-08 1.8E-10NNW 7017 1.9E-07 1.6E-10 5.3E-08 7.4E-11 IIDOMINIONVPAP-2103SREVISION 17PAGE 62 OF 77ATTACHMENT 8(Page 1 of 3)Radiological Environmental Monitoring Program 1Exposure Pathway Number of Sample and Collection Type and Frequency ofand/or Sample Sample Location Frequency Analysis1. DIRECTRADIATIONAbout 40 Routine Monitor-ing Stations to be placed asfollows:1) Inner Ring in generalarea of site boundary GAMMA DOSEwith station in eachsector2) Outer Ring 6 to 8 kmfrom the site with a Quarterly Quarterlystation in each sector3) The balance of the 8dosimeters should beplaced in special interestareas such as populationcenters, nearbyresidents, schools, andin 2 or 3 areas to serve ascontrols2. AIRBORNESamples from 7 locations:a) 1 sample from close tothe site boundarylocation of the highest Radioiodine Canistercalculated annual 1131 Analysis Weeklyaverage ground level ContinuousRadioiodines and D/Q SamplerParticulates b) 5 sample locations 6-8 operation with Particulate Samplerkm distance located in a sample collection Gross beta radioactivityconcentric ring around weekly analysis following filterthe Station change;c) 1 sample from a control Gamma isotopic analysislocation 15-30 km of composite (bydistant, providing valid location) quarterlybackground dataUIIIIIIIIIIIIII DOMINIONVPAP-2103SREVISION 17PAGE 63 OF 77ATTACHMENT 8(Page 2 of 3)Radiological Environmental Monitoring ProgramExposure Pathway Number of Sample and Collection Type and Frequency ofand/or Sample Sample Location Frequency Analysis3. WATERBORNEGamma isotopic analysisa) Surface Monthly Sample monthly;b) 1 sample downstream Composite for tritium analysisquarterlyb) Ground Sample from I or 2 sources Quarterly Gamma isotopic and tritiumanalysis quarterlyc) Sediment from a) 1 sample upstream Semi-Annually Gamma isotopic analysisshoreline b) 1 sample downstream semi-annuallya) 1 sample upstream Gamma isotopic analysisb) 1 sample downstream semi-annually4. INGESTIONa) Milk a) 2 samples from milkinganimals in the vicinity ofthe Station. (NOTE 1) Gamma isotopic and I131b) I sample from milking Monthlyanimals at a control analysis monthlylocation (-15-30 kmdistant). (NOTE 2)a) 6 samples of filter feeders(clams, oysters) in the Semi-Annuallyb) Fish and vicinity of the StationInvertebrates c) 1 sampling of crabs from Gamma isotopic on ediblethe vicinity of the Station Annually portionsd) 1 sampling of 2 differentspecies from the discharge Semi-Annuallycanal (catfish, white perch,eel)NOTE 1: If milk sampling cannot be performed, use item 4.c. Food Products -d. Milk sampling cannot be performedwhen there are no milk sampling locations in the vicinity of the Station.NOTE 2: If milk sampling from a control location cannot be performed, use item 4.c) e).Milk sampling cannot be performed when there is no milk sampling location 30 km distant.
IIDOMINIONVPAP-2103SREVISION 17PAGE 64 OF 77ATTACHMENT 8(Page 3 of 3)Radiological Environmental Monitoring ProgramExposure Pathway Number of Sample and Collection Type and Frequency ofand/or Sample Sample Location Frequency Analysis4. INGESTION(Continued)a) 1 sample corn Gamma isotopic on edibleb) 1 sample soybeans Annually portionsc) 1 sample peanutsd) 1 sample of a broadleafvegetation grownnearest in each of twodifferent availableoffsite locations(sectors) with thec) Food Products highest annual averageground level D/Qs, if Monthly, if Gamma isotopic and 1131milk sampling is not available, or at analysisperformed. harveste) I sample of a broadleafvegetation grown 15 -30 km distant in theavailable least prevalentwind direction, if milksampling is notperformed.UIIIIIIIIIII DOMINIONVPAP-2103SREVISION 17PAGE 65 OF 77ATTACHMENT 9(Page 1 of 3)Environmental Sampling LocationsSAMPLE LOCATION DISTANCE DIRECTION REMARKSMEDIA (MILES)Air Charcoal and Surry Station (SS) 0.3 NNEParticulate Hog Island Reserve (HIR) 2.0 NNEBacon's Castle (BC) 4.5 SSWAlliance (ALL) 5.1 WSWColonial Parkway (CP) 3.8 NNWBASF (BASF) 5.1 ENEFort Eustis (FE) 4.9 ESENewport News (NN) 19.3 SE Control LocationEnvironmental Control (00) Onsite *TLDs West North West (02) 0.2 WNW Site BoundarySurry Station Discharge 0.4 NW Site Boundary(03)North North West (04) 0.2 NNW Site BoundaryNorth (05) 0.3 N Site BoundaryNorth North East (06) 0.3 NNE Site BoundaryNorth East (07) 0.3 NE Site BoundaryEast North East (08) 0.4 ENE Site BoundaryEast (09) 0.3 E Site BoundaryWest (10) 0.1 W Site BoundaryWest South West (11) 0.4 WSW Site BoundarySouth West (12) 0.3 SW Site BoundarySouth South West (13) 0.3 SSW Site BoundarySouth (14) 0.4 S Site BoundarySouth South East (15) 0.6 SSE Site BoundarySouth East (16) 0.9 SE Site BoundaryStation Intake (18) 1.6 ESE Site BoundaryHog Island Reserve (19) 2.0 NNE Near Resident DOMINIONVPAP-2103SREVISION 17PAGE 66 OF 77ATTACHMENT 9(Page 2 of 3)Environmental Sampling LocationsSAMPLE LOCATION DISTANCE DIRECTION REMARKSMEDIA I (MILES) IEnvironmentalTLDsBacon's Castle(20)4.5SSWApprox. 5 milesRoute 633 (21) 4.9 SW Approx. 5 milesAlliance (22) 5.1 WSW Approx. 5 milesSurry (23) 7.7 WSW Population CenterRoute 636 and 637 (24) 4.0 W Approx. 5 milesScotland Wharf (25) 5.0 WNW Approx. 5 milesJamestown (26) 6.3 NW Approx. 5 milesColonial Parkway (27) 3.8 NNW Approx. 5 milesRoute 617 and 618 (28) 4.9 NNW Approx. 5 milesKingsmill (29) 4.6 N Approx. 5 milesWilliamsburg (30) 7.8 N Population CenterKingsmill North (31) 5.5 NNE Approx. 5 milesBudweiser (32) 5.8 NNE Population CenterWater Plant (33) 5.0 NE Approx. 5 milesBASF (34) 5.1 ENE Approx. 5 milesLee Hall (35) 7.1 ENE Population CenterGoose Island (36) 5.1 E Approx. 5 milesFort Eustis (37) 4.9 ESE Approx. 5 milesNewport News (38) 19.3 SE Population CenterJames River Bridge (39) 17.1 SE ControlBenn's Church (40) 17.0 SSE ControlSmithfield (41) 13.4 SSE ControlRushmere (42) 5.3 SSE Approx. 5 milesRoute 628 (43) 5.1 S Approx. 5 milesEpps 4.8 SSWColonial Parkway 3.7 NNWWilliams 27.5 S Control LocationIIIIIIIIIIIIIIIIII DOMINIONVPAP-2103SREVISION 17PAGE 67 OF 77ATTACHMENT 9(Page 3 of 3)Environmental Sampling LocationsSAMPLE LOCATION DISTANCE DIRECTION REMARKSMEDIA (MILES)Well Water Surry Station Onsite**Hog Island Reserve 2.0 NNEConstruction Site 0.3 E Onsite***Crops (Corn, Slade's Farm 3.2 SPeanuts,Soybeans) Brock's Farm 3.8 SRiver Water Surry Discharge 0.4 NW(Monthly) Scotland Wharf 4.9 WNW Control LocationSediment Chickahominy River 11.2 WNW Control Location(Silt) Surry Station Discharge 1.3 NNWClams Chickahominy River 11.2 WNW Control LocationSurry Station Discharge 1.3 NNWJamestown Island 3.9 NWOysters Point of Shoals 6.4 SSEMulberry Point 4.9 ESELawne's Creek 2.4 SECrabs Surry Station Discharge 1.3 NNWFish Surry Station Discharge 1.3 NNWShoreline Hog Island Reserve 0.6 NSedimentChickahominy River 11.2 WNW Control Location* Onsite Location -in Lead Shield** Onsite sample of Well Water taken from tap-water at Surry Environmental BuildingOnsite sample of Well Water taken from tap-water at Surry Training Center DOMINIONVPAP-2103SREVISION 17PAGE 68 OF 77ATTACHMENT 10(Page 1 of 2)Detection Capabilities for Environmental Sample AnalysisLOWER LIMIT OF DETECTION (LLD)Analysis Water Airborne Fish Milk Food Sediment(NOTE 2) (pCi/L) Particulate (pCi/kg) (pCi/L) Products (pCi/kg)or Gases (wet) (pCi/kg) (dry)(pCi/m3) (wet)Gross beta 4 0.01H-3 2,000Mn-54 15 130Fe-59 30 260Co-58, 60 15 130Zn-65 30 260Zr-95 30Nb-95 151-131 (NOTE 3) 1 0.07 1 60Cs- 134 15 0.05 130 15 60 150Cs-137 18 0.06 150 18 80 180Ba-140 60 60La-140 15 15NOTE 1: Required detection capabilities for thermoluminescent dosimeters used for environmentalmeasurements are given in Regulatory Guide 4.13.NOTE 2: This list does 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 ground (drinking) water samples. The LLD for the surface (non-drinking)water samples is 10 pCi/L.IIIIIIIIIIIIIIII DOMINION VPAP-2103SREVISION 17PAGE 69 OF 77ATTACHMENT 10(Page 2 of 2)Detection Capabilities for Environmental Sample AnalysisLOWER LIMIT OF DETECTION (LLD)NOTE 1: For a particular measurement system (which may include radiochemical separation):4.66 sbLLD = b(24-1)E
- V
- 2.22E+06 e Y
- e-(X(At)Where:LLD = the "a priori" (before the fact) Lower Limit of Detection as defined above(as microcuries per unit mass or volume) (See Subsection 4.9)Sb = the standard deviation of the background counting rate or of the countingrate of a blank sample as appropriate (as counts per minute, cpm)E = the counting efficiency (as counts per disintegration)V = the sample size (in units of mass or volume)2.22E+06 = the number of disintegrations per minute (dpm) per microcurieY = the fractional radiochemical yield (when applicable)x = the radioactive decay constant for the particular radionuclideAt = the elapsed time between sample collection (or end of the samplecollection 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 measurementsystem and not a "posteriori" (after the fact) limit for a particular measurement.
DOMINIONVPAP-2103SREVISION 17PAGE 70 OF 77ATTACHMENT 11(Page 1 of 1)Reporting Levels for Radioactivity Concentrations in Environmental SamplesAnalysis Water Airborne Fish Milk Food Products(pCi/L) Particulate or (pCi/kg, wet) (pCi/L) (pCi/kg, wet)Gases (pCi/m3)H-3 20,000*Mn-54 1,000 30,000Fe-59 400 10,000Co-58 1,000 30,000Co-60 300 10,000Zn-65 300 20,000Zr-Nb-95 4001-131 2* 0.9 3 100Cs-134 30 10 1,000 60 1,000Cs- 137 50 20 2,000 70 2,000Ba-La-140 200 300*Reporting level for the ground (drinking) water samples required by RadiologicalEnvironmental Monitoring Program (Attachment 8). The reporting level for the surface (non-drinking) water samples required by Attachment 8 is 30,000 pCi/L for H-3 and20 pCi/L for 1- 131.IIIIIIIIIIIIIIII DOMINION VPAP-2103SREVISION 17PAGE 71 OF 77ATTACHMENT 12(Page 1 of 7)Meteorological, Liquid, and Gaseous Pathway Analysis1.0 METEORLOGICAL ANALYSIS1.1 PurposeThe purpose of the meteorological analysis was to determine the five (5) year average X/Q andD/Q values at critical locations around the Station for ventilation vent (ground level) andprocess vent (mixed mode) releases. The five year average X/Q and D/Q values are used in thedose pathway analysis to determine dose and dose rate at site boundary and dose to the memberof the public.1.2 Meteorological Data, Parameters, and MethodologyA five (5) year average of representative onsite meteorological data for the period January 1,2007 through December 31, 2011, is used in the gaseous effluent dose pathway calculations.This data includes wind speed, wind direction, and differential temperature for the purpose ofdetermining joint frequency distributions for those releases characterized as ground level (i.e.,ventilation vent), and those characterized as mixed mode (i.e., process vent).X/Qs and D/Qs were calculated using the PC version of NRC computer code "XOQDOQ -Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear PowerStations", Version 2.0, provided in NUREG-0324.The open terrain adjustment factors were applied to the X/Q values as recommended inRegulatory Guide 1.111. The site region is characterized as flat terrain such that open terraincorrection factors are considered appropriate. The ground level ventilation vent releasecalculations included a building wake correction based on a 1516 m2 containment minimumcross-sectional area. The effective release height used in mixed mode release calculations wasbased on a process vent release height of 131 ft, and plume rise due to momentum for a ventdiameter of 1.5 in. with plume exit velocity of 100 ft/sec.Ventilation vent, and vent releases other than from the process vent, are considered groundlevel as specified in Regulatory Guide 1.111 for release points less than the height of adjacentsolid structures. Terrain elevations were obtained from Surry Power Station Units 1 and 2Virginia Electric and Power Company Updated Final Safety Analysis Report Table 1 1A-8.X/Q and D/Q values were calculated for the nearest site boundary, residence, milk-cow,discharge bank, and vegetable garden by sector for process vent and ventilation vent releases.
IDOMINION VPAP-2103SREVISION 17PAGE 72 OF 77ATTACHMENT 12(Page 2 of 7)Meteorological, Liquid, and Gaseous Pathway AnalysisAccording to the definition for short term in NUREG-0133, "Preparation of RadiologicalEffluent Technical Specifications for Nuclear Power Stations," October, 1978, some gaseousreleases may fit this category, primarily waste gas decay tank releases and containment purges.However, these releases are considered long term for dose calculations as past releases wereboth random in time of day and duration as evidenced by reviewing past release reports.Therefore, the use of annual average concentrations is appropriate according to NUREG-0133.1.3 ResultsThe X/Q and D/Q values used in the dose pathway analysis for ventilation vent releases andprocess vent releases can be found in Attachment 7.2.0 LIQUID PATHWAY ANALYSIS2.1 PurposeThe purpose of the liquid pathway analysis was to determine the maximum exposed memberof the public in unrestricted areas as a result of radioactive liquid effluent releases. The analysisincluded a determination of most restrictive liquid pathway, most restrictive age group, andcritical organ. This analysis is required for Subsection 6.2, Liquid Radioactive WasteEffluents.2.2 Data, Parameters, and Methodology IRadioactive liquid effluent release data for the years 1976, 1977, 1978, 1979, 1980, and 1981were compiled from the Surry Power Station effluent release reports. The data for each year,along with appropriate site specific parameters and default selected parameters, were enteredinto the NRC computer code LADTAP as described in NUREG- 1276. ILiquid radioactive effluents from both units are released to the James River via the dischargecanal. Possible pathways of exposure for release from the Station include ingestion of fishand invertebrates and shoreline activities. The irrigated food pathway and potable waterpathway do not exist at this location. Access to the discharge canal by the general public isgained two ways: bank fishing, controlled by the Station and limited to Dominion employeesor guests of employees, and by boat as far upstream as the inshore end of the discharge canalgroin. It has been estimated that boat sport fishing would be performed a maximum of 800 1hours per year, and that bank fishing would be performed a maximum of 160 hours0.00185 days <br />0.0444 hours <br />2.645503e-4 weeks <br />6.088e-5 months <br /> per year.I.. .I DOMINION VPAP-2103SREVISION 17PAGE 73 OF 77ATTACHMENT 12(Page 3 of 7)Meteorological, Liquid, and Gaseous Pathway AnalysisFor an individual fishing in the discharge canal, no river dilution was assumed for the fishpathway. For an individual located beyond the discharge canal groins, a river dilution factor of5 (i.e., a mixing ratio of 0.2) was assumed as appropriate according to Regulatory Guide 1.109,Rev. 1, and the fish, invertebrate, and shoreline pathways were considered to exist. Dosefactors, bioaccumulation factors, shore width factors and usage terms for shoreline activitiesand -ingestion of fish and invertebrates are included in the Source Code file. Dose to anindividual fishing on the discharge bank was determined by multiplying the annual dosecalculated with LADTAP by the fractional year the individual spent fishing in the canal.2.3 ResultsFor the years 1976, 1977, 1979, 1980, and 1981, the invertebrate pathway resulted in the largestdose. In 1978 the fish pathway resulted in the largest dose. The maximum exposed member ofthe public was determined to utilize the James River. The critical age group was the adult andthe critical organ was either the thyroid or GI-LLI. The ingestion dose factors,.which includethe fish and invertebrate pathways, are calculated for total body and various critical organs.Validation of the limiting age group and critical organ is performed by the liquid effluent dosecalculation program using the data, parameters, and methodology provided in the Source Codefile.3.0 GASEOUS PATHWAY ANALYSIS3.1 PurposeGaseous effluent pathway analyses are performed to determine the location that would resultin the maximum doses due to noble gases, for use in demonstrating compliance withSteps 6.3.I.a. and 6.3.3.a. The analyses includes a determination of the location, pathway, andcritical organ, of the maximum exposed member of the public, as a result of the release of 1131,1133, tritium, and for all radionuclides in particulate form with half-lives greater than eight daysfor use in demonstrating compliance with Step 6.3.4.a. In addition, the analyses includes adetermination of the critical organ, maximum age group, and sector location of an exposedindividual through the inhalation pathway from 1131, 1133, tritium, and particulates todemonstrate compliance with Step 6.3.1.a.
IDOMINION VPAP-2103SREVISION 17PAGE 74 OF 77ATTACHMENT 12(Page 4 of 7)Meteorological, Liquid, and Gaseous Pathway Analysis3.2 Data, Parameters, and MethodologyFive year average X/Q values were calculated, as described in Section 1 of this attachment. The Imaximum doses to total body and skin, and air doses for gamma and beta radiation due to noblegases would be at these site boundary locations. The doses from both the ventilation vent andprocess vent release points are summed to calculate total maximum dose.6.3.1.a.2 dose limits apply specifically to the inhalation pathway. Therefore, the locations andX/Q values determined for maximum noble gas doses can be used to determine the maximumdose from 1131, 1133, tritium, and for all radionuclides in particulate form with half-lives greaterthan 8 days for the inhalation pathway.The maximum exposed individual for 10 CFR 50, Appendix I, compliance could be at any ofthe following locations: site boundary, nearest resident, nearest milk-cow, or nearest vegetablegarden, using the Land Use Census data which is assessed annually. Therefore, ventilation ventand process vent X/Q and D/Q values for these selected receptors are included in the gaseouseffluent dose pathway analyses. Ground plane, inhalation, cow-milk, and vegetable gardenpathways are active with the exception of the infant age group, which is not active for thevegetable garden pathway. Otherwise, all age groups are evaluated at these locations. The data,parameters, and methodology of R. G. 1.109, Rev. 1, and NUREG-0133 are used in the gaseouseffluent dose pathway analyses.The ganuna and beta dose factors Kivv, Livv, Mivv, and Nivv for ground level releases and thegamma and beta dose factors Kipv, Lipv, Mipv, and Nipv for mixed mode releases are includedin the Source Code file.Inhalation pathway dose factors Pivv and Pipv are calculated using the following equation:Pi = K' (BR) DFAi mrem/yr per Ci/m3 (28-1)where:K' = a constant of unit conversion, 1 E+ 12 pCi/Ci IBR = the breathing rate of the particular age group, m3/yr, from Table E-5, Regulatory Guide1.109, Rev.1DFAi = the critical organ inhalation dose factor for particular age group for the ithradionuclide, in mrem/pCiI DOMINION VPAP-2103SREVISION 17PAGE 75 OF 77ATTACHMENT 12(Page 5 of 7)Meteorological, Liquid, and Gaseous Pathway AnalysisParameters used above were obtained from NUREG-0133 and R.G. 1.109, Rev. 1.It was determined that the member of the public within site boundary would be using thedischarge canal bank for fishing a maximum of 160 hours0.00185 days <br />0.0444 hours <br />2.645503e-4 weeks <br />6.088e-5 months <br /> per year. Active pathways are groundplane and inhalation, and all age groups are evaluated for this pathway analysis.The RMivv and RMipv dose factors, except for tritium, are calculated using the followingequation:R =K'QF a Fm (r) (DFLi) + (1- fpf,)eklth e tf (28-2)+w kYp Y swhere:K' = a constant of unit conversion, 1E+12 pCi/CiQF = cow's consumption rate, 50, in kg/day (wet weight)Uap= infant milk consumption rate, 330, in liters/yrYp = agricultural productivity by unit area of pasture feed grass, 0.7 in kg/m2Ys = agricultural productivity by unit area of stored feed, 2.0, in kg/m2Fm = stable element transfer coefficients, in days/literr = fraction of deposited activity retained on cow's feed grass, 1.0 for radioiodine, and 0.2for particulatesDFLi=critical organ ingestion dose factor for the ith radionuclide for the particular age group,in mrem/pCi= decay constant for the ith radionuclide, in sec-1Xw = decay constant for removal of activity of leaf and plant surfaces by weathering, 5.73E-07sec-1 (corresponding to a 14 day half-life)tf = transport time from pasture to cow, to milk, to receptor, 1.73+05, in secondsth = transport time from pasture, to harvest, to cow, to milk, to receptor, 7.78E+06, in secondsfp = fraction of year that cow is on pasture, 1.0 (dimensionless)
IDOMINION VPAP-2103SREVISION 17PAGE 76 OF 77ATTACHMENT 12(Page 6 of 7)Meteorological, Liquid, and Gaseous Pathway Analysisfs = fraction of cow feed that is pasture grass while cow is on pasture, 0.8 (dimensionless)Parameters used above were obtained from NUREG-0133 and Regulatory Guide 1.109, Rev.1. ISince the concentration of tritium in milk is based on the airborne concentration rather than thedeposition, the following equation is used:RH3 = K'K'"Fm QFUap(DFLH3) [0.75(0.5/H)] (28-3)where:K"'= a constant of unit conversion 1E+03 gm/kgH = absolute humidity of the atmosphere, 8.0, in gm/m30.75 = 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.The inhalation pathway dose factors RIvv and Rlipv were calculated using the following Iequation:IRIi = K' (BR) DFAi mrem/yr per Ci/m3 (28-4)where:K' = a constant of unit conversion, 1E+12 pCi/CiBR = breathing rate of the particular age group, m3/yrDFAi=critical organ inhalation dose factor for particular age group for the ith radionuclide, inmrem/pCiIII DOMINIONVPAP-2103SREVISION 17PAGE 77 OF 77ATTACHMENT 12(Page 7 of 7)Meteorological, Liquid, and Gaseous Pathway AnalysisParameters used above were obtained from NUREG-0133 and R. G. 1.109, Rev. 1.Breathing RateInfant = 1400 m3/yrChild = 3700 m3/yrTeen = 8000 m3/yrAdult = 8000 mi3/yrThe RG dose factors are calculated using the following equation:[1-?e-itb 2, mirem lyrRG = K'K" (SF)DFGi L Ci / secwhere:K' = A constant of unit conversion, IE+ 12 pCi/CiK" = A constant of unit conversion, 8760 hr/year.= The decay constant for nuclide i, sec-1.tb The exposure time, 4.73x 108 sec (15 years), from Table E-15 of RegGuide 1.109.DFGi =The ground plane dose conversion factor for nuclide i, from Table E-6of Reg. Guide 1. 109 (mrem/hr per pCi/mi2).SF = The shielding factor 0.7 (dimensionless), from Table E-15 of RegGuide 1.109.(28 -5) Page 1 of 1MAJOR CHANGES TO RADIOACTIVE LIQUID.GASEOUS AND SOLID WASTE TREATMENT SYSTEMSThere were no major changes to the radioactive liquid, gaseous or solid waste treatmentsystems for this reporting period. Page 1 of 1INOPERABILITY OF RADIOACTIVE LIQUID AND GASEOUSEFFLUENT MONITORING INSTRUMENTATIONThe Annual Radioactive Effluent Release Report shall explain why monitoring instrumentationrequired by the ODCM Attachments I and 5, which were determined to be inoperable, were notreturned to operable status within 30 days. None of the above referenced instrumentationwere inoperable greater than 30 days during this reporting period. Page 1 of 1UNPLANNED RELEASESThere were no unplanned liquid or unplanned gaseous releases during this reporting period. Page I of ILOWER LIMIT OF DETECTION (LLD) FOR EFFLUENT SAMPLE ANALYSISGASEOUS:LIQUID:IsotopeKr-87Kr-88Xe-133Xe-133mXe-135Xe-135mXe-1381-1311-133Sr-89Sr-90Cs-134Cs-137Mn-54Fe-59Co-58Co-60Zn-65Mo-99Ce-141Ce-144AlphaTritiumSr-89Sr-90Cs-134Cs-1371-131Co-58Co-60Fe-59Zn-65Mn-54Mo-99Ce-141Ce-144Fe-55AlphaTritiumXe-133Xe-135Xe-133mXe-135mXe-138Kr-87Kr-88Required LLD1.OOE-041.OOE-041.OOE-041.OOE-041.OOE-041.OOE-041.OOE-041.OOE-121.OOE-101.OOE-111.OOE-111.OOE-111.OOE-111.OOE-111.OOE-111.OOE-111.OOE- 111.OOE- 111.OOE-111.OOE-111.OOE-111.OOE- 111.OOE-065.OOE-085.OOE-085.OOE-075.OOE-071.OOE-065.OOE-075.OOE-075.OOE-075.OOE-075.OOE-075.OOE-075.OOE-075.OOE-071.OOE-061.OOE-071.OOE-051.OOE-051.OOE-051.OOE-051.OOE-051.OOE-051.OOE-051.OOE-05Typical LLD2.15E-06 -1.77E-051.56E-06 -1.94E-051.28E-06 -1.55E-053.68E-06 -4.06E-053.66E-07 -5.24E-061.31E-05 -6.26E-052.68E-05 -9.90E-054.06E-13 -4.06E-134.06E- 11 -4.06E- 119.13E-15 -1.82E-121.23E-15 -1.06E-121.63E-13 -2.45E-131.54E-13 -3.21E-139.68E-14 -3.49E-133.50E-13 -7.03E-139.62E-14 -3.12E-132.49E-13 -4.97E-134.98E-14 -6.80E-134.06E-12 -4.06E-121.96E-13 -2.57E-135.97E-13 -1.03E-121.68E-14 -1.69E-146.35E-08 -6.35E-081.40E-084.82E-091.96E-081.58E-082.81E-081.24E-081.97E-083.58E-085.09E-091.23E-082.9 1E-072.93E-081.07E-072.86E-072.76E-081.58E-068.32E-082.07E-082.1OE-071.47E-063.32E-061.15E-077.70E-084.38E-083.21E-085.73E-087.85E-085.63E-086.54E-081.1OE-071.46E-071.37E-077.45E-084.95E-079.27E-083.47E-079.04E-072.78E-081.58E-062.95E-075.62E-085.66E-073.50E-068.78E-062.53E-072.85E-07 Page 1 of 3INDUSTRY GROUND WATER PROTECTION INITIATIVEThe following is a summary of 2014 sample analyses of ground water monitoring wells that are not a partof the Radiological Environmental Monitoring Program (REMP). Analyses are performed by anindependent laboratory.Well Sample Tritium Gamma Fe-55 Ni-63 Sr-90 TRUDesignation Date pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter1-PL-Piez-29 1/21/14 9,870 NA NA NA NA NA1-PL-Piez-04 2/4/14 <760 ND NA NA NA NA1-PL-Piez-05 2/4/14 5,720 ND <141 <2.58 <0.722 ND1-PL-Piez-06 2/4/14 2,610 ND <88.7 <2.58 <0.876 ND1-PL-Piez-29 2/4/14 6,700 ND <157 <2.58 <0.774 ND1-PL-Piez-33 2/4/14 <755 ND NA NA NA NAl-PL-Piez-34 2/4/14 <768 ND NA NA NA NAI -PL-Piez-41 2/4/14 <767 ND NA NA NA NA1-PL-Piez-42 2/4/14 <769 ND NA NA NA NA1-PL-Piez-07 2/5/14 <756 ND NA NA NA NA1 -PL-Piez-24 2/5/14 <756 ND NA NA NA NA1-PL-Piez-27 2/5/14 <765 ND NA NA NA NA1-PL-Piez-05 3/13/14 6,690 NA NA NA NA NA1-PL-Piez-06 3/13/14 2,170 NA NA NA NA NA1-PL-Piez-29 3/13/14 11,200 NA NA NA NA NA1-PL-Piez-05 4/9/14 7,040 NA NA NA NA NA1-PL-Piez-06 4/9/14 2,490 NA NA NA NA NA1-PL-Piez-29 4/9/14 7,890 NA NA NA NA NA1-PL-Piez-05 5/1/14 6,960 NA NA NA NA NA1-PL-Piez-06 5/1/14 2,200 NA NA NA NA NAl-PL-Piez-29 5/1/14 9,150 NA NA NA NA NA1-PL-Piez-05 5/8/14 5,400 NA NA NA NA NA1-PL-Piez-06 5/8/14 2,220 NA NA NA NA NA1-PL-Piez-29 5/8/14 8,770 NA NA NA NA NA1-PL-Piez-05 5/15/14 5,950 NA NA NA NA NA1-PL-Piez-06 5/15/14 2,730 NA NA NA NA NA1 -PL-Piez-29 5/15/14 8,410 NA NA NA NA NA1-PL-Piez-05 5/22/14 8,200 NA NA NA NA NA1-PL-Piez-29 5/22/14 10,100 NA NA NA NA NAl-PL-Piez-05 5/29/14 6,570 NA NA NA NA NA1-PL-Piez-29 5/29/14 9,480 NA NA NA NA NA1-PL-Piez-03 6/9/14 <1,210 NA NA NA NA NA1 -PL-Piez-04 6/9/14 <1,210 ND NA NA NA NA1 -PL-Piez-07 6/9/14 <1,200 ND NA NA NA NA1-PL-Piez-08 6/9/14 <1,220 ND NA NA NA NA Page 2 of 3INDUSTRY GROUND WATER PROTECTION INITIATIVEWell Sample Tritium Ganma Fe-55 Ni-63 Sr-90 TRUDesignation Date pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter1 -PL-Piez-09 6/9/14 <1,230 NA NA NA NA NA1-PL-Piez-20 6/9/14 <1,220 ND NA NA NA NA1-PL-Piez-22 6/9/14 <1,210 ND NA NA NA NA1 -PL-Piez-24 6/9/14 <1,210 ND NA NA NA NA1-PL-Piez-25 6/9/14 <1,210 ND NA NA NA NA1-PL-Piez-27 6/9/14 <1,230 ND NA NA NA NA1-PL-Piez-28 6/9/14 <1,220 ND NA NA NA NA1-PL-Piez-33 6/9/14 <1,210 ND NA NA NA NA1 -PL-Piez-34 6/9/14 <1,220 ND NA NA NA NA1-PL-Piez-35 6/9/14 <1,210 NA NA NA NA NA1-PL-Piez-36 6/9/14 <1,210 NA NA NA NA NA1-PL-Piez-40 6/9/14 <1,210 ND NA NA NA NA1-PL-Piez-05 6/10/14 7,520 ND NA NA NA NA1-PL-Piez-06 6/10/14 2,180 ND NA NA NA NA1-PL-Piez-23 6/10/14 <1,220 ND NA NA NA NA1-PL-Piez-29 6/10/14 9,660 ND NA NA NA NA1-PL-Piez-37 6/10/14 <1,220 NA NA NA NA NA1-PL-Piez-38 6/10/14 <1,360 NA NA NA NA NA1-PL-Piez-39 6/10/14 <1,240 NA NA NA NA NA1-PL-Piez-41 6/10/14 <1,210 ND NA NA NA NA1-PL-Piez-42 6/10/14 <1,220 ND NA NA NA NA1-PL-Piez-05 6/26/14 6,150 NA NA NA NA NA1-PL-Piez-29 6/26/14 9,070 NA NA NA NA NA1-PL-Piez-05 7/7/14 8,610 NA NA NA NA NA1-PL-Piez-29 7/7/14 10,200 NA NA NA NA NA1-PL-Piez-05 7/25/14 6,380 NA NA NA NA NA1-PL-Piez-29 7/25/14 9,930 NA NA NA NA NA1-PL-Piez-05 9/18/14 7,950 NA NA NA NA NA1 -PL-Piez-29 9/18/14 6,690 NA NA NA NA NA1-PL-Piez-04 8/25/14 <1,380 ND NA NA NA NA1-PL-Piez-05 8/25/14 6,030 ND NA NA NA NA1-PL-Piez-06 8/25/14 3,480 ND NA NA NA NA1-PL-Piez-07 8/25/14 <1,380 ND NA NA NA NA1-PL-Piez-24 8/25/14 <1,380 ND NA NA NA NA1-PL-Piez-27 8/25/14 <1,380 ND NA NA NA NA1 -PL-Piez-29 8/25/14 7,450 ND NA NA NA NA1-PL-Piez-33 8/25/14 <1,370 ND NA NA NA NA Page 3 of 3INDUSTRY GROUND WATER PROTECTION INITIATIVEWell Sample Tritium Gamma Fe-55 Ni-63 Sr-90 TRUDesignation Date pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter1-PL-Piez-34 8/25/14 <1,380 ND NA NA NA NA1-PL-Piez-41 8/25/14 <1,380 ND NA NA NA NA1-PL-Piez-42 8/25/14 <1,380 ND NA NA NA NA1-PL-Piez-04 11/24/14 <1,320 ND NA NA NA NA1-PL-Piez-05 11/24/14 7,010 ND NA NA NA NA1-PL-Piez-06 11/24/14 2,660 ND NA NA NA NA1-PL-Piez-07 11/24/14 <1,320 ND NA NA NA NA1-PL-Piez-08 11/24/14 <1,330 ND NA NA NA NA1-PL-Piez-24 11/24/14 <1,320 ND NA NA NA NA1-PL-Piez-25 11/24/14 <1,310 ND NA NA NA NA1-PL-Piez-27 11/24/14 <1,300 ND NA NA NA NA1-PL-Piez-29 11/24/14 9,030 ND NA NA NA NA1-PL-Piez-33 11/24/14 <1,320 ND NA NA NA NA1-PL-Piez-34 11/24/14 <1,300 ND NA NA NA NA1-PL-Piez-40 11/24/14 <1,290 ND NA NA NA NA1-PL-Piez-41 11/24/14 <1,320 ND NA NA NA NA1-PL-Piez-42 11/24/14 <1,300 ND NA NA NA NANA = Analysis not required.ND =.No non-natural gamma emitting nuclides detected when analyzed to REMP LLDs.TRU = Transuranics (Am-241, Cm-242, Cm-243/244, Pu-238 ,Pu-239/240 and Pu-241)