ML18122A177

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Annual Radioactive Effluent Release Report, and Annual Radiological Environmental Operating Report
ML18122A177
Person / Time
Site: Beaver Valley
Issue date: 04/21/2018
From: Seidel P
FirstEnergy Nuclear Operating Co
To:
Office of Nuclear Reactor Regulation
References
RTL# A9.690E
Download: ML18122A177 (171)


Text

{{#Wiki_filter:r I RTL# A9.690E ,,I FIRSTENERGY NUCLEAR OPERA TING COMPANY

 ,I         BEAVER VALLEY POWER STATION I

I I I I I I I I I 2017 I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (ARERR) I AND ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERA TING REPORT (AREOR) I UNITS NO. 1 AND 2

 ,I                  LICENSES DPR-66 AND NPF-73 I

I

I RTLA9.690E Enclosure 1 I BEAVER VALLEY POWER STATION I ENVIRONMENTAL & CHEMISTRY SECTION I Technical Report Approval: I 2017 I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (ARERR) I AND ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (AREOR) I UNITS NO. 1 AND 2 I LICENSES DPR-66 AND NPF-73 I Prepared by: Patrick C. Seidel ,? ~ Date: 5 //I'll 2~18 I

                                  ;(klwA--{_~. J~ ~                       /,o / 18 I  Reviewed by: Susan L. Vicinie                     ,*_J        Date:  1f I

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Subject:

Beaver Valley Power Station, Unit Nos. 1 and 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Radioactive Effluent Release Report for 2017, and Annual Radiological Environmental Operating Report for 2017 Distribution for Enclosures 1 - 3: Original Report to: U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Copies of Report to Other USNRC: I U.S. Nuclear Regulatory Commission NRR Project Manager I U. S. Nuclear Regulatory Commission NRC Senior Resident Inspector I U.S. Nuclear Regulatory Commission NRC Region I Administrator I U.S. Nuclear Regulatory Commission NRC Region I Health Physics Inspector I Copies o{Report to Other Agencies: I American Nuclear Insurers 95 Glastonbury Boulevard I Glastonbury, CT 06033 Department of Environmental Protection (5 copies) I Bureau of Radiation Protection & Toxicology P.O. Box 2063 Harrisburg, PA 17105-2063 I Department of Environmental Protection (2 copies) Southwest Regional Office I 400 Waterfront Drive Pittsburgh, PA 15222 I I I

Distribution for Enclosures 1 - 3: I Page 2

                                                ,I INPO 700 Galleria Parkway SE Suite 100 I

Atlanta, GA 30339-5957 11 Beaver County Cooperative Extension 156 Cowpath Road Aliquippa, PA 15001-5842 I Hancock County Office of Emergency Services PO Box 884 I New Cumberland, WV 26047 Ohio Department of Health I 246 North High Street Columbus, OH 43215-3363 I Ohio Emergency Management Agency 2855 West Dublin Granville Road I Columbus, OH 43235 East Liverpool Water Authority I 2220 Michigan Avenue East Liverpool, OH 43920 I ORSANCO 5735 Kellogg Avenue I Cincinnati, OH 45228 B. F. Jones Memorial Library I 663 Franklin Avenue Aliquippa, PA 15001 I Bureau of Radiation Protection HP3 Ohio Department of Health I Northeast District Office 161 South High Street, Suite 400 Akron, OH 44308-1612 11 11 I I

, Distribution for Enclosures 1 - 3:

Page 3 I Copies of Report for FENOC Addressees: I TE Migdal, BVPS; Manager, Site Chemistry (A-BV-A) SL Vicinie, BVPS; Supervisor, Nuclear Chemistry Services (A-BV-A) I RR Winters, BVPS; Supervisor, Nuclear Chemistry Services (A-BV-A) PC Seidel, BVPS; Chemistry Services, RETS (A-BV-A) 5 copies I PH Lashley, Akron; Fleet Licensing (A-WAC-Bl) 2 copies JB Bowden, BVPS; Operations Oversight (A-BV-NCD3) K Gillespie, BVPS, Radiation Monitor System Engineer (A-BV-SOSB6) I DJ Min1rns, BVPS, Radiation Monitor System Engineer (A-BV-SOSB6)

  • BVPS, Liquid Waste System Engineer (A-BV-SOSB6)

RG Garver, BVPS, BOP Systems Engineer Supervisor (A-BV-SOSB-6) I

  • Akron; Director, Environmental (A-G0-13)

DW Jenkins, Akron; Sr. Attorney II, Legal (A-G0-15)

  • Akron; Vice President, Energy Policy (A-G0-18)

I MJ Jirousek, Akron; Manager, Environmental Generation Services (A-G0-13) SA Wender, Akron; Manager, Fleet Chemistry/Environmental (A-WAC-A3) I MR Baker, Perry RETS & REMP Administrator (A-PY-CCB125) KA Filar, Davis-Besse RETS & REMP Administrator (A-DB-1041) A Banavali, Manager, Environmental, Inc. I RJ Dinello, Field Specialist, Environmental, Inc I BVPS Document Control, RTL A9.690E BVRC - Keywords: Radioactive Effluent Release Report, I Annual Radiological Environmental Operating Report I I I I I I I

I Form 1/2-ENV-01 .05.F01 (page 1 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTLA9.690E Enclosure 2, Page i I I 2017 Annual Radioactive Effluent Release Report I I I I FirstEnergy Nuclear Operating Company FENOC I Beaver Valley Power Station - Units 1 & 2 Unit 1 License No. DPR-66 Unit 2 License No. NPF-73 I I I I I I 11 ii I I I

Form 1/2-ENV-01.05.F01 (page 2 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page ii I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Index Title Page I Cover Index i ii I Executive Summary - Report Submittal Reauirements iii Executive Summary - Liquid and Gaseous Effluent Control (Part 1 of 2) Executive Summary - Liquid and Gaseous Effluent Control (Part 2 of 2) iv V I Executive Summary - Trends of Tota l Dose vi Executive Summary - Trends of Liquid Release Activity (Fission and Activation Products) Executive Summary - Trends of Liquid Release Activity (Tritium) vii viii I Executive Summary - Trends of Liquid Release Offsite Dose Projections ix Executive Summary - Trends of Gaseous Release Activity (Fission and Activation Gas) Executive Summary - Trends of Gaseous Release Activity (Particulates and Radioiodines) X xi I: Executive Summary - Trends of Gaseous Release Activity (Tritium) xii Executive Summary - Trends of Unit 1 Gaseous Release Offsite Dose Projections Executive Summary - Trends of Unit 2 Gaseous Re lease Offsite Dose Projections xiii xiv I Results of Abnormal Releases xv Results of Onsite Spills and Items Added to Decommissionina Files per 10CFR50.75(a) Results of Onsite Groundwater Monitorina Proaram xvi xvi i I Corrections to Previous Annual Radioactive Effluent Release Reports xviii Table 1A Supplemental Information Page Gaseous Effluents - Summation Of All Releases 1 2 I Table 1B-EB Gaseous Effluents - Elevated Batch Releases 3 Table 1B-EC Gaseous Effluents - Elevated Continuous Releases Table 1C-GB1 Gaseous Effluents - Ground Level Batch Releases (Unit 1) 4 5 I Table 1C-GC1 Gaseous Effluents - Ground Level Continuous Releases (Unit 1) 6 Table 1C-GB2 Gaseous Effluents - Ground Level Batch Releases (Unit 2) Table 1C-GC2 Gaseous Effluents - Ground Level Continuous Releases (Unit 2) 7 8 I Table 2A Liauid Effluents - Summation Of All Releases 9 Table 2B-B Table 2B-C Liau id Effluents - Batch Releases Liauid Effluents - Continuous Releases 10 11 I Table 3A Solid Waste And Irradiated Fuel Shipments (Part 1 of 3) 12 Table 38 Table 3C Solid Waste And Irradiated Fuel Shipments (Part 2 of 3) Solid Waste And Irradiated Fuel Shipments (Part 3 of 3) 13 14 I Table 4 Lower Limits Of Detectabilitv 15 Table 5A Table 58 Assessment Of Radiation Doses (Unit 1) Assessment Of Radiation Doses (Unit 2) 16 17 I Table 6 Effluent Monitoring Instrumentation Channels Not Returned To Operable Status Within 30 Days 18 Table 7 Table 8 Total Dose Commitments , Total Effective Dose Equivalents and Population Doses Offsite Dose Calculation Manual Surveillance Deficiencies 19 20 I Table 9 Unit 1 and 2 Offsite Dose Calculation Manual Cha naes (Description) 21 Attachment 1 Part 1: Joint Frequency Distribution Tables (35 ft) Part 2: Joint Frequency Distribution Tables (150 ft) I Part 3: Joint Freauency Distribution Tables (500 ft) Attachment 2 Un it 1 and 2 Offsite Dose Calculation Manual (Complete Copy) Note: The Total Error va lues(%) listed in this report are documented in Calculation Package No. ERS-ATL-04-002 I I

I Form 1/2-ENV-01 .05.F01 (page 3 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page iii I Annual Radioactive Effluent Release Report Calendar Year - 2017 Executive Summary - Report Submittal Requirements I Report Submittal and Requirements: The report was prepared and submitted in accordance with the I requirements contained in the following documents: BVPS Integrated Technical Specifications, Administrative Control 5.6.2 I Offsite Dose Calculation Manual (ODCM) procedure 1/2-0DC-3 .03, 'Controls for RETS and REMP Programs ", Attachment U, Control 6.9.3 I BVPS procedure l/2-ENV-01.05, "Compliance with Regulatory Guide 1.21 and Technical Specifications " I NUREG-1301 , " Offsite Dose Calculation Manual Guidance: Standard Radiological Ejjl.uent Controls for Pressurized Water Reactors, Generic Letter 89-01, Supplement No.I, April 1991 " I Regulatory Guide 1.21 , "Measuring Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Material in Liquid and Gaseous Ejjl.uents from Light-Water Cooled Nuclear Power Plants, Revision I , June 1974 " I BVPS Condition Report No. CR-2017-04211 , Lack of isokinetic sampling for ODCM requirements BVPS Condition Report No. CR-2017-04541 , RM-1MS-100C not returned to service within 30 days I BVPS Condition Report No. CR-2017-07282, U2 MSCV sump sample cannot be located, ODCM surveillance missed I BVPS Condition Report No. CR-2017-12446, RM-I LW-104 Not Returned to Service Within 30 days as Required by the ODCM I BVPS Condition Report No. CR-2018-00126, Annual Catch Basin samples were unable to be obtained I BVPS Condition Report No. CR-2018-02122, REMP Control Location TLD #48 exposure abnormally low BVPS SAP Order No. 601078879, 2017 RETS/REMP Tracking for ARERR/AREOR I I I I I I

Form 1/2-ENV-01 05.F01 (page 4 of 39), Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page iv I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Executive Summary - Liquid and Gaseous Effluent Control (Part 1 of 2) I Onsite Groundwater Monitoring: H-3 Summary: In 2017, twenty three (23) on-site monitoring wells were sampled in the spring and fall sampling periods. No new wells were installed, nor were any wells retired. MW-16 was sampled twelve (12) times throughout 2017, two (2) of which were included in the I yearly biannual sampling. These samples that were taken account for the highest concentrations. No adverse effect to the offsite environment has been detected at this time, because all offsite groundwater, drinking water and surface water samples were <440 pCi/L. See Enclosure 2, Page xvii for additional I details. Onsite Spills: There were no onsite spills > 100 gallons. I Decommissioning File Update: There were no items added to the site decommissioning files in accordance with 10CFR50.75(g). I Abnormal Liquid Releases: There were no abnormal liquid releases. Abnormal Gaseous Releases: There were two abnormal gaseous releases. I Liquid Radwaste Treatment System: The site operated via a shared Liquid Radwaste Treatment System, even though each Unit has its own ion-exchange vessels. Shared operation allowed either Unit to process I liquid waste at the Unit of origin, or at the other Unit. Typically, when Unit I or 2 high level liquid waste was processed (e.g., coolant recovery waste) it was performed at Unit 1, because it has a carbon pre-conditioning filter. I Gaseous Radwaste Treatment System: The site operated via a shared Gaseous Radwaste Treatment System, even though each Unit has its own charcoal delay beds and storage/decay tanks. Shared operation allowed either Unit to process gaseous waste at the Unit of origin, or at the other Unit. Typically, when Unit I I or 2 went to a shutdown condition, the gaseous waste was transferred for storage and decay at Unit 2, because Unit 2 has four (4) additional storage tanks. I I I I I I I I

I Form 1/2-ENV-01 .05 .F01 (page 5 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page v I Annual Radioactive Effluent Release Report Ca~ndarYear-2017 Executive Summary - Liquid and Gaseous Effluent Control (Part 1 of 2) I Lower Limits of Detectability (LLD): All a-priori calculated LLD met the minimum requirements I specified in the ODCM. Effluent Monitoring Channels Inoperable >30 Days:There were two (2) Effl uent Monitoring I Instrumentation Channels not returned to Operable status within 30 days. ODCM Surveillance Deficiencies: There were two (2) ODCM Surveillance Deficiencies. I ODCM Changes: There was one (1) changes made to the ODCM. Meteorological Data Recovery: The Meteorological Data Recovery met the minimum requirement of at-I least 90%, as specified in Section 5 of Revision 1 to Regulatory Guide 1.23, Meteorological Monitoring Programs for Nuclear Power Plants. I Population Dose vs. Natural

Background:

The 0-50 mile total and average population doses were calculated using liquid and gaseous release quantities and real time meteorology. The average population dose is based on four (4) million people within 0-50 miles of the BVPS site. The following comparison to I natural background radiation demonstrates that BVPS operations did not adversely affect the surround ing environment. I 99.96 man-mrem =BVPS Total Population Dose for the year 0.0000250 mrem = BVPS Average Individual Dose for the year I 296 mrem = Natural Background Individual Dose for the year. This dose value is documented as natural background radiation exposure for an individual in a year from the 1990 BElR V Report. I Carbon-14 Dose Assessment: Carbon-1 4 dose was calcu lated using EPRI & RG-1 .109 calculation methods and the default ODCM receptor. The highest organ doses were to the bone (child). Details of the I dose assessment due to releases of Carbon-14 in gaseous effluents are provided in Attachment 3 of this report. I I I I I I

Form 1/2-ENV-01 .05 F01 (page 6 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9 .690E Enclosure 2, Page vi I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Executive Summary -Trends of Total Dose I Trends of Total Dose: The following graph provides a comparison of the ODCM dose projections from all facility releases and direct radiation exposures to show compliance with Member of the Public dose limits from 10 CFR 20.1301 and 40 CFR Part 190. I 100.0% - - - - -- - - - -- - - - - - - - - - - - - - - - - - - - - - - -- ~ I I I I I 0.1% + - - l - - - + - - - - + - - + - - - - + - - + - - - - - + - - + - - - t - - - + - - - + - - + - - - + - - - - + - - - + - - - - + - - l

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unit 1&2, Percent of 40 CFR 190.10(a)Total Body Dose Limit o Unit 1&2 , Percent of 40 CFR190.10(a) Thyroid Dose Limit I

               - - - Unit 1&2, Percent of 10 CFR 20.1301(a)(1) TEDE Dose Limit I

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I Form 1/2-ENV-01 .05.F01 (page 7 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page vii I Annual Radioactive Effluent Release Report Calendar Year - 2017 Executive Summary - Trends of Liquid Release Activity (Fission and Activation Products) I Liquid Release Activity (Fission and Activation Products): The following graph provides a comparison I of total liquid mixed fission and activation product (particulate) radioactivity discharged from the site from 1976 to present. I 10.00 - - --* I 1.00 +-- - - - - - - - ---,1-- - - - - - - - - - - - - - - - - - - - - l I en Q)

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(.) I I 0.01 ;--t-+-t--+-+--t--+-+-+-t-+-+--+-+--t--+-+--+-t-+-+--+-+-+--+-+-+-,t-+-t-+-+--t--t--+-+-,t-+-t--t--i

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                                               -svPs Unit 1 -       svPs Unit 2 I

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Form 1/2-ENV-01 .05.F01 (page 8 of 39) , Rev 5 RTL# A9 .690E Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Page viii Annual Radioactive Effluent Release Report Calendar Year - 2017 I Executive Summary - Trends of Liquid Release Activity (Tritium) Liquid Release Activity (Tritium): The following graph provides a comparison of total liquid tritium radioactivity discharged from the site from 1976 to present. The latest increases were due to the increase power of the reactor, or power uprate, which lead to increased tritium. I 10000 I I

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  -~     100 +-'IF--- -----*- - - - - - - - - - - - -- -- - - - - - - - - - - - - - - <

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I Form 1/2-ENV-01 .05.F01 (page 9 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page ix I Annual Radioactive Effluent Release Report Calendar Year - 2017 II Executive Summary - Trends of Liquid Release Offsite Dose Projections Liquid Release Offsite Dose Projections: The following graph provides a comparison of liquid offsite I dose projections that were calculated to the maximum individual per 10 CFR 50, Appendix I and the ODCM. The projections use ODCM default flow rates for the receiving water (Ohio River), and were performed prior to release authorization. I 100.0% ~ - - - - - - - -- - -- - - - - - - -- - - - - -- - - -- -- ~ I I ~ E

J 10.0%

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I - u nit 1 or Unit 2, Percent of Maximum Organ Dose Limit o Unit 1 or Unit 2, Perce nt of Total Bod y Dose Limit I I I I I I I

Form 1/2-ENV-01 .05 .F01 (page 10 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page x I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Executive Summary - Trends of Gaseous Release Activity (Fission and Activation Gas) I Gaseous Release Activity (Fission and Activation Gas): The following graph provides a comparison of total gaseous fission and activation gas discharged from the site from 1976 to present. The steady decreases are due to extended hold-up periods of gas space prior to release. The differences between the units are I relative to the outages that occured that year. I 10000.00 1000.00 I 100.00 I

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(.) 10.00 I 1.00 0.10 I 0.01

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             ~     ~   ~        ~       ~  ~      ~    ~         ~        ~  ~      ~     ~        ~       ~     ~     ~    ~ ~ ~ ~

I -svPs Unit 1 - svPs Unit 2 I I I I I I I I 11 I

I I Form 1/2-ENV-01 .05 .F01 (page 11 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page xi I Annual Radioactive Effluent Release Report Calendar Year - 2017 Executive Summary - Trends of Gaseous Release Activity (Particulates and Radioiodines; I Gaseous Release Activity {Particulates and Radioiodines): The following graph provides a comparison I of total gaseous particulates and radioiodines discharged from the site from 1976 to present. The differences between the units are relative to the outages that occured that year. I 1.E-01 I 1.E-02 I Cl) (I) 1.E-03

      '§   1.E-04 I    0 1.E-05 I         1.E-06 I         1.E-07 I                                               -BVPS Unit 1   -    BVPS Unit 2 I

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Form 1/2-ENV-01 .05.F01 (page 12 of 39), Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page xii I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Executive Summary - Trends of Gaseous Release Activity (Tritium) Gaseous Release Activity (Tritium): The following graph provides a comparison of total gaseous tritium discharged from the site from 1976 to present. The recent decreases were due to efforts to reduce overall offsite dose. Specifically, discharging liquid radioactive inventory provided the benefit ofreduced total I offsite dose, due to reduction in evaporative losses from the fuel pools. The increase in Unit I tritium was due to the steam releases from the Forced Outage in November. I 11 I

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I Form 1/2-ENV-01.05.F01 (page 13 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Page xiii RTL# A9.690E I Annual Radioactive Effluent Release Report Calendar Year - 2017 Executive Summary - Trends of Unit 1 Gaseous Release Offsite Dose Projections I Unit 1 Gaseous Release Offsite Dose Projections: The following graph provides a comparison of Unit I I gaseous offsite dose projections that were calculated to the maximum individual per 10 CFR 50, Appendix I and the ODCM. The projections use ODCM default meteorological parameters for the atmospheric conditions surrounding the plant site, and were performed prior to release authorization. I 100.0000000% I 10.0000000% 1.0000000% I ~ E

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I 0 0.0000100% 0.0000010% I 0.0000001% 0.0000000% .L.....-f--+--+----+--+------i--+--+---+--+---+___..c...-+--+---+--+---+-~ - - t-L--+-- +="r

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I Unit 1, Percent of Gamma Air Dose limit ~ Unit 1, Percent of Beta Air Dose Limit . - - - Unit 1, Percent of Hig hest Organ Dose Limit I I I

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Form 1/2-ENV-01 .05 .F01 (page 14 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Page xiv RTL# A9.690E I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Executive Summary - Trends of Unit 1 Gaseous Release Offsite Dose Projections I Unit 2 Gaseous Release Offsite Dose Projections: The following graph provides a comparison of Unit 2 gaseous offsite dose projections that were calculated to the maximum individual per 10 CFR 50, Appendix I and the ODCM. The projections use ODCM default meteorological parameters for the atmospheric I conditions surrounding the plant site, and were performed prior to release authorization. I 100.0000000% 10.0000000% I 1.0000000%

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0.1000000% I 0.0100000% I 111 Q)

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0 0.0000100% I 0.0000010% I Unit 2, Percent of Gamma Air Dose Limit - unit 2, Percent of Beta Air Dose Limit - - - Unit 2, Percent of Highest Organ Dose Limit I I I I I I I I I

Form 1/2-ENV-01 .05 .F01 (page 15 of 39) , Rev 5 RTL# A9 .690E Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Page xv Annual Radioactive Effluent Release Report Calendar Year - 2017 Results of Abnormal Releases I Description of Abnormal Release(s) I I Abnormal Liquid Releases : NONE 11 Abnormal Gaseous Releases : There were two abnormal discharges are from the Unit 1 Force Outage that was due to a reactor trip caused by generator overcurrent. One discharge is from the Auxiliary Feedwater Terry Turbine trip va lve and the other is for the Residual Heat Removal valves . These discharges were steam releases and are an expected response to a reactor trip . Tritium was the only radioactive isotope associated with them and no ODCM limits I were exceeded (reference CR-2017-11134). I I I I I I I I I I I I

Form 1/2-ENV-01 .05.F01 (page 16 of 39), Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page xvi I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Results of Onsite Spills and Items Added to Decommissioning Files per 10CFR50.75(g) Description of Spills or Items added to 10CFR50.75(g) I I Summary of Onsite Spills (>100 gallons): NONE I Summary of Items added to Decommissioning Files per 10CFR50.75(g) Files: NONE I 1: I I I I I I I I I I I I

i I Form 1/2-ENV-01 .05 .F01 (page 17 of 39), Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page xvii Annual Radioactive Effluent Release Report I Ca~ndarYear-2017 Results of Onsite Groundwater Monitoring Program I Summary of Onsite Groundwater Samples Are Any H-3 Analyses NEI and FENOC EPA 2017 2017 2017 Typical Required Pre Greater Than Communication Reporting I H-3 (pCi/Ll H-3 Maximum Minimum Average (pCi/L) H-3 (pCi/L) H-3 LLD (pCi/Ll H-3 LLD (pCi/L) Operational Mean For H-3 (pCi/Ll The Pre Operational Mean For H-3 ? Level For H-3 (pCi/Ll Level For H-3 (pCi/Ll I sering (02) I I I I <200 I <2000 I I I I I I I Fall (04) I 6517 14219 I 148 148 I 611 926 I <200 I <2000 I 440 440 I Yes Yes I 2000 2000 I 20000 20000 I I I I I I <200 I <2000 I I I I I I MW-16 15516 5916 8894 440 Yes 2000 20000 Tritium (H-3) Summary In 2017 , twenty three (23) on-site monitoring wells were sampled in the spring and fall sampling periods. No new wells were installed, nor were any wells retired . MW-16 was sampled twelve (12) times throughout 2017 , two (2) of which were included in I the yearly biannual sampling . These samples that were taken account for the highest concentrations . Sixteen (16) wells returned results of less than the pre-operational mean (440 pCi/L) during all sample periods in 2017. Seven (7) wells returned results >440 pCi/L, but <2000 pCi/l. One (1) well returned results >2000 pCi/L. No wells exceeded 20,000 pCi/L with the highest concentration recorded as 15,516 pCi/L. I The NEUFENOC communication level was reached for MW-12S & MW-12D during 2007. Notification to local, state & federal agencies was performed on 10/08/07. Additional communication for new well results was performed on 09/08/1 O for those new wells that exceeded 2000 pCi/L. The newly installed well MW-20D exceeded 2,000 pCi/L on its first sample, but this was expected since the well was installed to monitor the previously identified plume intercepting MW-16. No adverse effect to the I offsite environment has been detected at this time, because all offsite groundwater, drinking water and surface water samples were <440 pCi/l. Mitigation activities (catch basin sleeving) to prevent tritiated condensate water from reach ing the groundwater were completed 12/17/11 . Remediation well , EW-1, was installed and began operation in October 2013. This equipment captures the tritium plume and it I becomes a permitted discharge. Samples are taken monthly to provide the concentration of the discharge. Remediation will continue until the suspected plume is depleted and tritium levels stabilize. Principal Gamma Emmitter Summary I All onsite monitoring wells were sampled during the year, and analyzed for Principal Gamma Emitters. The results showed no positive indication of Licensed Radioactive Material (LRM) in any of the analyses. I 100000 Onsite Groundwater Monitoring Well Program H-3 Trends New Wells Installed Summer 2010 yes (2001 ~ 2011) _ _ _ __ I I I - - MW-10 (Upgradient Control Well) Avg . of all Samples Pre-Operational Mean H-3 (440 pCi/L)

                                                                           - - Maximum Tritium Sample
                                                                           -     H-3 LLD (typically <200 pCi/L)

Pre-Operational Max H-3

        -     NRC Required LLD (2,000 pCi/L) NEI Commun icati on Level     -     EPA Reporting Level (Non-Drinking Water) 30,000 pCi/L I

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Form 1/2-ENV-01 .05 .F01 (page 18 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page xviii I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Corrections to previous Annual Radioactive Effluent Release Reports I Description of Corrections Made to RERR(s) I Correction(s) to Previous Annual Radioactive Effluent Release Reports: NONI I I I I I I I I I I I I I I I

I Form 1/2-ENV-01 .05 .F01 (page 19 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9 .690E Enclosure 2, Page 1 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 Supplemental Information Page I I FACILITY: B.V.P.S. Units 1 and 2 I 1. Regulatory Limits

a. Fission and activation gases: Annual Unit 1 or 2 Dose : 10 mrad from Gamma , & 20 mrad from Beta
b. Iodines & particulates, half-lives > 8 days: Annual Unit 1 or 2 Dose: 15 mrem to Any Orqan I c. Liauid effluents: Annual Unit 1 or 2 Dose: 3 mrem to Total Body , & 10 mrem to Any Oman
2. Maximum Permissable Concentrations Used In Determining Allowable Release Rates Or Concentrations I a. Fission and activation gases:
b. Iodines & particulates, half-lives > 8 days:

Site Release Rate: 500 mrem/yr to Total Body, & 3000 mrem/yr to the Skin Site Release Rate : 1500 mrem/yr to Any Orqan I c. Liauid effluents: j 3. Average Energy (Not Applicable To The BVPS ODCM) Site Release Concentration : 10 times 10 CFR 20 Aooendix B, Table 2, EC's I 4. Measurements and Approximations of Total Radioactivity The methods used to measure or approximate the total radioactivity in effluents, and the methods used to determine I radionuclide composition are as follows:

a. Fission and activation gases: Ge Gamma Spectrometry , Liquid Scintillation Counter
b. Iodines: Ge Gamma Spectrometry I c. Particulates, half-lives > 8 days:
d. Liauid effluents:

Ge Gamma Spectrometry, Proportional Cou nter Ge Gamma Spectrometry , Proportional Counter, Liquid Scintillation Calendar

5. Batch & Abnormal Release Information unit Q1 Q2 Q3 Q4 Year
a. Liquid Batch Releases
1. Number of batch releases 18 21 37 17 93
2. Total time period for batch releases min 7466 13930 8741 7276 37413 I 3. Maximum time period for a batch release
4. Average time period for batch releases
5. Minimum time period for a batch release min min 3939 415 4135 663 4390 236 4445 428 4445 402 min 190 13 13 13 13 I 6. Average river flow during release periods
b. Gaseous Batch Releases cuft/sec 74911 64447 25186 34803 49837
1. Number of batch releases 6 12 2 5 25 I 2. Total time period for batch releases
3. Maximum time period for a batch release min min 4385 3595 11405 4972 282 176 7861 7210 23933 7210
4. Averaae time period for batch releases min 731 950 141 1572 957 I 5. Minimum time oeriod for a batch release
c. Abnormal Liquid Releases min 1 1 106 94 1
1. Number of releases NONE NONE NONE NONE NONE I 2. Total activity released
d. Abnormal Gaseous Releases Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO I 1. Number of releases
2. Total activity released Ci NONE O.OOE+OO NONE O.OOE+OO NONE O.OOE+OO 2

1.78E+06 1.78E+06 2 I

Form 1/2-ENV-01 .05.F01 (page 20 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page 2 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Table 1A Gaseous Effluents - Summation Of All Releases I Calendar Total unit Q1 Q2 Q3 Q4 Year Error% I A. Fission & Activation Gases

1. Site Total release 1a. Unit 1 Gases Cl Ci O.OOE+OO O.OOE+OO 1.48E-01 7.41E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.48E-01 7.41E-02 26.5%1 I 1b. Unit 2 Gases
2. Average release rate for period
3. Percent of applicable limit Cl uCi/sec O.OOE+OO O.OOE+OO N/A 7.41E-02 1.88E-02 N/A O.OOE+OO O.OOE+OO N/A O.OOE+OO O.OOE+OO N/A 7.41E-02 4.70E-03 N/A I

B. Iodines

1. Site Total iodine -131 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 28.3% 1 I

1a. Unit 1 iodine -131 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1b. Unit 2 iodine - 131

2. Average release rate for period
3. Percent of applicable limit Cl uCi/sec O.OOE+OO O.OOE+OO N/A O.OOE+OO O.OOE+OO N/A O.OOE+OO O.OOE+OO N/A O.OOE+OO O.OOE+OO N/A O.OOE+OO O.OOE+OO N/A I

C. Particulates

1. Particulates with half-lives > 8 days Ci O.OOE+OO 5.29E-04 5.17E-07 O.OOE+OO 5.30E-04 30.0%1 I

1a. Unit 1 Particulates 1b. Unit 2 Particulates

2. Average release rate for period Ci Ci uCl/sec O.OOE+OO O.OOE+OO O.OOE+OO 6.59E-07 5.29E-04 6.72E-05 2.59E-07 2.59E-07 6.57E-08 O.OOE+OO O.OOE+OO O.OOE+OO 9.18E-07 5.29E-04 1.68E-05 I
3. Percent of applicable limit  % N/A N/A N/A N/A N/A D. Gross Alpha I
1. Site Gross alpha radioactivity Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 30.0%1 1a. Unit 1 Gross alpha 1b. Unit 2 Gross alpha
2. Average release rate for period Ci Ci uCi/sec O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO I
3. Percent of applicable limit E. Tritium
                                                  %          N/A         N/A          N/A         N/A            N/A I
1. Site Total release 1a. Unit 1 Tritium 1b. Unit 2 Tritium Ci Ci Ci 5.82E-01 2.45E-01 3.38E-01 4.26E-01 3.52E-01 7.41E-02 8.10E-01 5.84E-01 2.26E-01 2.76E+OO 2.29E+OO 4.69E-01 4.58E+OO 3.47E+OO 1.11E+OO 32.9%

I

2. Average release rate for period uCi/sec 7.39E-02 5.41 E-02 1.03E-01 3.SOE-01 1.45E-01
3. Percent of applicable limit  % N/A N/A N/A N/A N/A I

F. Carbon-14

1. Site Total release 1a. Unit 1 Carbon-14 1b. Unit 2 Carbon-14 Ci Ci Ci 4.59E+OO 2.30E+OO 2.29E+OO 3.81E+OO 4.69E+OO 4.54E+OO 2.33E+OO 2.35E+OO 2.20E+OO 1.48E+OO 2.34E+OO 2.34E+OO 1.76E+01 9.18E+OO 8.45E+OO 41.1% 1 I
2. Average release rate for period
3. Percent of applicable limit uCi/sec 5.83E-01
                                                  %          N/A 4.83E-01 5.95E-01 5.76E-01 N/A          N/A          N/A 5.59E-01 N/A                 I NIA = Not Applicable The amount of time (in seconds) used to calcu late the release rates specified in A.2, B.2, C.2, D.2 and E.2 is the average amount of seconds per calendar quarter (7.88E+06 seconds) .

I I

11 Form 1/2-ENV-01 .05.F01 (page 21 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page 3 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Table 18-EB Gaseous Effluents - Elevated Batch Releases (Unit 1 & 2) I Nuclides released unit Q1 Q2 Q3 Q4 Calendar Year I A. Fission gases argon-41 Ci LLD 8.53E-06 LLD LLD 8.53E-06 I krypton-85 krypton-85m krypton-87 Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I krypton-88 xenon-131m xenon-133 Ci Ci Ci LLD LLD LLD LLD LLD 1.93E-03 LLD LLD LLD LLD LLD LLD LLD LLD 1.93E-03 xenon-133m Ci LLD LLD LLD LLD LLD I xenon-135 xenon-135m Ci Ci LLD LLD 7.45E-04 8.16E-05 LLD LLD LLD LLD 7.45E-04 8.16E-05 xenon-138 Ci LLD LLD LLD LLD LLD I Total for period Ci ND 2.??E-03 ND ND 2.??E-03 B. Iodines I iodine-131 iodine-133 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD iodine-135 Ci LLD LLD LLD LLD LLD I Total for period Ci ND ND ND ND ND C. Particulates I chromium-51 manganese-54 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I cobalt-57 cobait-58 cobalt-60 Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD zinc-65 Ci LLD LLD LLD LLD LLD selenium-75 Ci LLD LLD LLD LLD LLD zirconium/niobium-95 Ci LLD LLD LLD LLD LLD zirconium/niobium-97 Ci LLD LLD LLD LLD LLD cesium-134 Ci LLD LLD LLD LLD LLD cesium-137 Ci LLD LLD LLD LLD LLD cerium-141 Ci LLD LLD LLD LLD LLD cerium-144 Ci LLD LLD LLD LLD LLD strontium-89 Ci LLD LLD LLD LLD LLD strontium-90 Ci LLD LLD LLD LLD LLD I Total for period Ci ND ND ND ND ND I NOTE: Unit 1/2 Process Vent LLD= Below the Lower Limit of Detectability, in uCi/cc (Table 4) . ND= None Detected I

Form 1/2-ENV-01 .05.F01 (page 22 of 39), Rev 5 RTL# A9.690E Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Page 4 of 21 Annual Radioactive Effluent Release Report Calendar Year - 2017 Table 18-EC Gaseous Effluents - Elevated Continuous Releases (Unit 1 & 2) Calendar Nuclides released unit Q1 Q2 Q3 Q4 Year A. Fission gases argon-41 Ci LLD LLD LLD LLD LLD I krypton-85 krypton-85m krypton-87 Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I krypton-88 xenon-131m xenon-133 Ci Ci Ci LLD LLD LLD LLD LLD 1.45E-01 LLD LLD LLD LLD LLD LLD LLD LLD 1.45E-01 I xenon-133m Ci LLD LLD LLD LLD LLD xenon-135 xenon-135m Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I xenon-138 Ci LLD LLD LLD LLD LLD Total for period Ci ND 1.45E-01 ND ND 1.45E-01 I B. Iodines iodine-131 iodine-133 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I iodine-135 Ci LLD LLD LLD LLD LLD Total for period Ci ND ND ND ND ND I C. Particulates chromium-51 manganese-54 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I cobalt-57 cobalt-58 cobalt-GO Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I zinc-65 Ci LLD LLD LLD LLD LLD selenium-75 zirconium/niobium-95 Ci Ci LLD LLD 1.32E-06 LLD 5.17E-07 LLD LLD LLD 1.84E-06 LLD I zirconium/niobium-97 Ci LLD LLD LLD LLD LLD cesium-134 cesium-137 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I cerium-141 Ci LLD LLD LLD LLD LLD cerium-144 strontium-89 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I strontium-90 Ci LLD LLD LLD LLD LLD Total for period Ci ND 1.32E-06 5.17E-07 ND 1.84E-06 I NOTE : Unit 1/2 Process Vent LLD= Below the Lower Limit of Detectability, in uCi/cc (Table 4). ND = None Detected I I

I Form 1/2-ENV-01.05.F01 (page 23 of 39) , Rev 5 Beaver Valley Power Station - Unit 1 RTL# A9.690E Enclosure 2, Page 5 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Table 1C-GB1 Gaseous Effluents - Ground Level Batch Releases (Unit 1) I Nuclides released unit Q1 Q2 Q3 Q4 Calendar Year I A. Fission gases argon-41 Ci LLD LLD LLD LLD LLD I krypton-BS krypton-BSm krypton-B7 Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I krypton-BB xenon-131m xenon-133 Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD xenon-133m Ci LLD LLD LLD LLD LLD I xenon-13S xenon-13Sm Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD xenon-13B Ci LLD LLD LLD LLD LLD I Total for period Ci ND ND ND ND ND B. Iodines I iodine-131 iodine-133 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD iodine-13S Ci LLD LLD LLD LLD LLD I Total for period Ci ND ND ND ND ND I C. Particulates chromium-S1 Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD manganese-54 Ci LLD I cobalt-S7 cobalt-SB cobalt-60 Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I zinc-6S Ci selenium-7S Ci LLD LLD LLD LLD LLD zirconiumfnioblum-9S Ci LLD LLD LLD LLD LLD zirconiumfniobium-97 Ci LLD LLD LLD LLD LLD I cesium-134 cesium-137 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD cerium-141 Ci LLD LLD LLD LLD LLD I cerium-144 strontium-B9 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD strontium-90 Ci LLD LLD LLD LLD LLD I Total for period Ci ND ND ND ND ND NOTE: Unit 1 Ventilation & Containment Vent I LLD= Below the Lower Limit of Detectability, in uCi/cc (Table 4). ND= None Detected I

Form 1/2-ENV-01 .05.F01 (page 24 of 39), Rev 5 Beaver Valley Power Station - Unit 1 RTL# A9.690E Enclosure 2, Page 6 of 21 I Annual Radioactive Effluent Release Report I Calendar Year - 2017 Table 1C-GC1 Gaseous Effluents - Ground Level Continuous Releases (Unit 1) I Nuclides released unit Q1 Q2 Q3 Q4 Calendar Year I A. Fission gases Ii argon-41 Ci LLD LLD LLD LLD LLD krypton-85 krypton-85m krypton-87 Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I krypton-88 xenon-131m xenon-133 Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I xenon-133m Ci LLD LLD LLD LLD LLD xenon-135 Ci LLD LLD LLD LLD LLD xenon-135m Ci LLD LLD LLD LLD LLD xenon-138 Ci LLD LLD LLD LLD LLD Total for period Ci ND ND ND ND ND B. Iodines iodine-131 iodine-133 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I iodine-135 Ci LLD LLD LLD LLD LLD Total for period Ci ND ND ND ND ND I C. Particulates chromium-51 manganese-54 Ci Ci LLD LLD LLD LLD LLD LLD LLD I LLD LLD LLD cobalt-57 cobalt-58 cobalt-60 Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 11I zinc-65 selenium-75 zirconium/niobium-95 Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I zirconium/niobium-97 Ci LLD LLD LLD LLD LLD cesium-134 cesium-137 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I cerium-141 Ci LLD LLD LLD LLD LLD cerium-144 strontium-89 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I strontium-90 Ci LLD LLD LLD LLD LLD Total for period Ci ND ND ND ND ND I NOTE: Unit 1 Ventilation & Containment Vent LLD= Below the Lower Limit of Detectability , in uCi/cc (Table 4) . ND = None Detected I I

Form 1/2-ENV-01 .05.F01 (page 25 of 39) , Rev 5 RTL# A9.690E Beaver Valley Power Station - Unit 2 Enclosure 2, Page 7 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Table 1C-GB2 Gaseous Effluents - Ground Level Batch Releases (Unit 2) I Nuclides released unit Q1 Q2 Q3 Q4 Calendar Year I A. Fission gases argon-41 Ci LLD LLD LLD LLD LLD I krypton-85 krypton-85m krypton-87 Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD krypton-88 Ci LLD LLD LLD LLD LLD I xenon-131m xenon-133 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD xenon-133m Ci LLD LLD LLD LLD LLD I xenon-135 xenon-135m Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD xenon-138 Ci LLD LLD LLD LLD LLD I Total for period Ci ND ND ND ND ND B. Iodines I iodine-131 iodine-133 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD iodine-135 Ci LLD LLD LLD LLD LLD I Total for period Ci ND ND ND ND ND C. Particulates I chromium-51 manganese-54 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I cobalt-57 cobalt-58 cobalt-60 Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD zinc-65 Ci LLD LLD LLD LLD LLD I selenium-75 zirconium/niobium-95 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD zirconium/niobium-97 Ci LLD LLD LLD LLD LLD I cesium-134 cesium-137 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD cerium-141 Ci LLD LLD LLD LLD LLD I cerium-144 strontium-89 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD strontium-90 Ci LLD LLD LLD LLD LLD I Total for period Ci ND ND ND ND ND NOTE: Unit 2 Ventilation , Containment, Decontamination Bldg , Waste Gas Vault, & Condensate Polishing Bldg . Vent I LLD= Below the Lower Limit of Detectability, in uCi/cc (Table 4) . ND = None Detected

Form 1/2-ENV-01.05.F01 (page 26 of 39), Rev 5 Beaver Valley Power Station - Unit 2 RTL# A9.690E Enclosure 2, Page 8 of 21 I Annual Radioactive Effluent Release Report I Calendar Year - 2017 Table 1C-GC2 Gaseous Effluents - Ground Level Continuous Releases (Unit 2) I Nuclides released unit Q1 Q2 Q3 Q4 Calendar Year I A. Fission gases I argon-41 Ci LLD LLD LLD LLD LLD krypton-85 krypton-BSm krypton-B7 Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I krypton-BB xenon-131m xenon-133 Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I xenon-133m Ci LLD LLD LLD LLD LLD xenon-135 xenon-135m Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I xenon-138 Ci LLD LLD LLD LLD LLD Total for period Ci ND ND ND ND ND I B. Iodines iodine-131 iodine-133 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I iodine-135 Ci LLD LLD LLD LLD LLD Total for period Ci ND ND ND ND ND I C. Particulates chromium-51 manganese-54 Ci Ci LLD LLD 1.24E-04 2.58E-06 LLD LLD LLD LLD 1.24E-04 2.58E-06 I cobalt-57 cobalt-SB cobalt-GO Ci Ci Ci LLD LLD LLD LLD 2.83E-04 3.29E-05 LLD LLD LLD LLD LLD LLD LLD 2.83E-04 3.29E-05 I I zinc-65 Ci LLD LLD LLD LLD LLD selenium-75 Ci LLD LLD LLD LLD LLD zirconium/niobium-95 Ci LLD 8.56E-05 LLD LLD 8.56E-05 zirconium/niobium-97 Ci LLD LLD LLD LLD LLD cesium-134 cesium-137 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I cerium-141 Ci LLD LLD LLD LLD LLD cerium-144 strontium-89 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I strontium-90 Ci LLD LLD LLD LLD LLD Total for period Ci ND 5.28E-04 ND ND 5.28E-04 I NOTE : Unit 2 Ventilation , Containment, Decontamination Bldg , Waste Gas Vault, & Condensate Polishing Bldg . Vent LLD= Below the Lower Limit of Detectability , in uCi/cc (Table 4) . ND = None Detected I

I Form 1/2-ENV-01.05.F01 (page 27 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page 9 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 Table 2A I Liquid Effluents - Summation Of All Releases Calendar Total I unit Q1 Q2 Q3 Q4 Year Error % I A. Fission & activation products

1. Total release (excl. H-3, gas & alpha) Ci 1.10E-02 3.62E-02 1.93E-02 4 .39E-03 7.09E-02 26.1 % I
2. Average diluted concentration uCi/ml 2.65E-09 7.94E-09 4.37E-09 1.02E-09 4.06E-09 I 3. Percent of applicable limit  % 4.42E-01 1.45E+OO 7.72E-01 1.76E-01 7.09E-01
8. Tritium I 1. Total release Ci 2.20E+02 3.18E+02 2.03E+02 4.79E+02 1.22E+03 25.0% I
2. Average diluted concentration uCi/ml 5.28E-05 6.97E-05 4.59E-05 1.11 E-04 6.99E-05 I 3. Percent of applicable limit  % 5.28E-01 6.97E-01 4.59E-01 1.11E+OO 6.99E-01 C. Dissolved and entrained gases I 1. Total release
2. Average diluted concentration Ci uCi/mL ND 1.27E-04 2.78E-11 ND ND 1.27E-04 7.26E-12 27.0% I
3. Percent of applicable limit  % 1.39E-05 3.63E-06 I D. Gross alpha radioactivity Ci LLD LLD LLD LLD LLD 28 .9%

(total release) I E. Volume of waste released L 1.26E+07 1.34E+07 1.32E+07 1.27E+07 5.19E+07 11 .2% (prior to dilution) I F. Volume of dilution water used L 4.16E+09 4.54E+09 4.41 E+09 4.30E+09 1.74E+10 22 .9% I LLD= Below the Lower Limit of Detectability, in uCi/mL (Table 4) I A.3 is based on a historical PA-DEP guide of 10 Ci/yr 8 .3 is based on a ODCM limit of 1.00E-2 uCi/mL C.3 is based on a ODCM limit of 2.00E-04 uCi/mL I The values listed at F. are the volumes during actual liquid waste discharge periods. The total dilution volume for a continuous calendar quarter is approximately 1E+10 liters for BVPS-1 & 2 (ie.; - 22,800 gpm is the total dilution flow rate from the site) I I

Form 1/2-ENV-01 .05 .F01 (page 28 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page 10 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Table 28-B Liquid Effluents - Batch Releases I Calendar Nuclides released unit Q1 Q2 Q3 Q4 Year I A. Fission & Activation Products berylllum-7 sodium-24 chromlum-61 Cl Cl Cl LLD LLD LLD LLD LLD 2.SSE-03 LLD LLD 5.SOE-05 LLD LLD LLD LLD LLD 2.63E-03 I manganese-64 iron-69 cobalt-67 cobalt-58 Cl Cl Cl Cl 2.20E-04 LLD 3.73E-05 5.64E-04 3.23E-04 LLD 5.0SE-05 1.47E-02 3.47E-03 9.71E-06 4.30E-05 5.91E-03 1.07E-05 LLD 1.14E-05 1.11E-03 4.02E-03 9.71E-06 1.42E-04 2.23E-02 I cobalt-60 zlnc-66 zfrconium/nloblum-96 Cl Cl Cl 4.82E-03 2.19E-05 LLD 5.76E-03 LLD 9.21E-04 2.29E-03 LLD 2.04E-04 5.57E-04 LLD 3.70E-05 1.34E-02 2.19E-05 1.16E-03 I zfrconium/nlobfum-97 Ci 6.0?E-06 LLD 2.66E-05 3.0?E-05 6.33E-05 molybdenum-99/technetlum-99m ruthenfum-103 ruthenlum-106 Ci er Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I sllver-110m Cl 2.45 E-03 1.66E-03 3.SOE-04 7.SSE-05 4.53E-03 tln-113 tln-117m antlmony-122 Ci Cl Cl LLD LLD LLD 1.BSE-04 LLD 5.0BE-05 LLD LLD LLD LLD LLD LLD 1.BSE-04 LLD 5.0BE-05 I antrmony-124 Cl LLD 3.60E-04 1.79E-04 LLD 5.38E-04 antlmony-125 iodlne-131 lodlne-133 Cl Cl Cl 1.61E-03 LLD LLD 5.76E-03 LLD LLD 2.98E-03 LLD LLD 1.16E-03 LLD LLD

1. 15E-02 LLD LLD I

lodlne-136 Cl LLD LLD LLD LLD LLD ceslum-134 ceslum-137 barlum/lanthanum-140 Cl Cl Cl LLD 3.48E-05 LLD LLD 8.00E-05 LLD LLD 8.71E-07 LLD LLD 2.77E-06 LLD LLD 1.18E-04 LLD I cerfum-141 cerfum-144 iron-65 Cl Cl Ci LLD LLD 1.28E-03 LLD LLD 3.77E-03 LLD LLD 3.78E-03 LLD LLD 1.40E-03 LLD LLD 1.02E-02 I strontium-89 Cl LLD LLD LLD LLD LLD strontlum-90 Total for period Cl Cl LLD 1.10E-02 LLD 3.62E-02 LLD 1.93E-02 LLD 4.39E-03 LLD 7.09E-02 I B. Tritum hydrogen-3 Cl I 2.20E+02 I 3. 17E+02 I 2.02E+02 I 4.79E+02 I 1.22E+03 I I Total for period Cl I 2.20E+02 I 3. 17E+02 I 2.02E+02 I 4.79E+02 I 1.22E+03 I C. Dissolved & Entrained Gases I argon-41 Cl LLD LLD LLD LLD LLD krvpton-85 xenon-131m xenon-133 Ci Cl Cl LLD LLD LLD LLD LLD 1.27E-04 LLD LLD LLD LLD LLD LLD LLD LLD 1.27E-04 I' xenon-133m Cl LLD LLD LLD LLD LLD xenon-135 Ci LLD LLD LLD LLD LLD xenon-136m Ci LLD LLD LLD LLD LLD Total for period Cl ND 1.27E-04 ND ND 1.27E-04 LLD= Below the Lower Limit of Detectability , in uCi/mL (Table 4) ND= None Detected I I

I Form 1/2-ENV-01 .05.F01 (page 29 of 39), Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9 .690E Enclosure 2, Page 11 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 Table 2B-C I Liquid Effluents - Continuous Releases Calendar Nuclides released unit Q1 Q2 Q3 Q4 Year A. Fission & Activation Products I beryllium-7 sodlum-24 Ci Cl LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD chromlum-51 Cl LLD LLD LLD LLD LLD manganese-64 Cl LLD LLD LLD LLD LLD lron-69 Ci LLD LLD LLD LLD LLD cobalt-67 Ci LLD LLD LLD LLD LLD cobalt-68 Ci LLD LLD LLD LLD LLD cobalt-SO Cl LLD LLD LLD LLD LLD zinc-66 Ci LLD LLD LLD LLD LLD zlrconlum/nlobium-96 Cl LLD LLD LLD LLD LLD zirconlum/nloblum-97 Cl LLD LLD LLD LLD LLD I molybdenum-99/technetlum-99m ruthenlum-103 ruthenlum-106 Cl Cl Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD sllver-110m Cl LLD LLD LLD LLD LLD I tln-113 tln-117m antlmony-122 Cl Cl Cl LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD antlmony-124 Cl LLD LLD LLD LLD LLD I antlmony-125 iodlne-131 lodlne-133 Cl Cl Cl LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD lodlne-135 Cl LLD LLD LLD LLD LLD I ceslum-134 ceslum-137 barlum/lanthanum-140 Cl Ci Cl LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I cerlum-141 cerlum-144 iron-55 Ci Cl Cl LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD strontlum-89 Ci LLD LLD LLD LLD LLD I strontlum-90 Total for period Cl Ci LLD ND LLD ND LLD ND LLD ND LLD ND I B. Tritum hydrogen-3 Cl I 1.43E-01 I 1.82E-01 I 2.69E-01 I 2.33E-01 I 8.28E-01 I Total for period Ci I 1.43E-01 I 1.82E-01 I 2.69E-01 I 2.33E-01 I 8.28E-01 I I C. Dissolved & Entrained Gases ar11on-41 Cl LLD LLD LLD LLD LLD I krvpton-86 xenon-131m xenon-133 Cl Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD xenon-133m Cl LLD LLD LLD LLD LLD I xenon-135 xenon-135m Cl Cl LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD Total for period Ci ND ND ND ND ND I LLD= Below the Lower Limit of Detectability , in uCi/mL (Table 4) ND= None Detected II I

Form 1/2-ENV-01.05.F01 (page 30 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9 .690E Enclosure 2, Page 12 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Table 3A Solid Waste And Irradiated Fuel Shipments (Part 1 of 3) I A. Solid Waste Shipped Offsite For Burial Or Disposal (Not irradiated fuel)

1. Type of Waste (Spent resins, Filter Sludges, Evaporator Bottoms, Oil)

Jan -Jun Jul - Dec Estimated Total Error I

a. Volume Shipped 12.40 m 3 11 .52 m 3 0.0% (1)
b. Volume Buried
c. Total Activity 2.80 m 3 43 .10 Ci 8.80 m 3 36.36 Ci 0.0% (1) 30.0%

I

2. Estimate of Major Nuclide Composition by Tvoe of Waste On This TablE ( >

H-3 2 Percent(%) 1.08 % Percent(%) 1.64 % I C-14 4.41 % 2.48 % Mn-54 Fe-55 0.416 % 9.68 % 0.88 % 7.72 % I Co-58 6.98 % 2.01 % Co-60 Ni-59 13.22 % 0.694 % 19 04 % 0.34 % I Ni-63 58 .80 % 60.84 % Zn-65 Zr-95 0.327 % 0.38 % 0.48 % 0.11 % I Nb-95 0.786 % 0.24 % Sb-125 Cs-137 1.61 % 0.38 % 3.03 % 0.64 % I

3. Number of Shipments 7 4
a. Type of LSA Type A 7

0 4 0 I Container Used

b. Solidification Type B Large Quantity Cement 0

0 0 0 0 0 I Agent UreaFormaldehyde 0 0 Used

c. Mode of None Truck 7

7 4 4 I Transport Rail 0 0

d. Final Other Oak Ridge, TN 0

6 0 3 I Destination Erwin, TN 1 1

e. Waste Class Class A Class B 2

1 4 0 I per Class C 4 0 10 CFR Part 61 > Class C 0 0 I (1) Since container volumes are provided by the burial site, a calcu lational error of zero is assumed . (2) Percent va lues for any nuclide that are <0.01 % are not shown on this table . Data is available upon request. I I I

I Form 1/2-ENV-01.05.F01 (page 31 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page 13 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 Table 38 I Solid Waste And Irradiated Fuel Shipments (Part 2 of 3) A. Solid Waste Shipped Offsite For Burial Or Disposal (Not irradiated fuel) I 1. Type of Waste (Dry Compressible Waste, Contaminated Equipment, etc.) Jan -Jun Jul - Dec Estimated Total Error

a. Volume Shipped 275.00 m 3 366 .13 m 3 0.0% (1)

I b. Volume Buried

c. Total Activity 28.82 m 0.63 Ci 3

27 .20 m 3 1.73 Ci 0.0% (1) 30.0%

2. Estimate of Major Nuclide Composition I by Type of Waste On This Table <2>

H-3 Percent(%) 4.34 % Percent(%) 0.10 % C-14 1.19 % 1.48 % I Cr-51 Mn-54 0.41 % 0.57 % 0.085 % 0.36 % Fe-55 28.1 % 21 .30 % I Co-58 Co-60 15.54 % 18.6 % 4.57 % 14.62 % Ni-59 0.07 % 0.0 % I Ni-63 Zn-65 26.9 % 0.03 % 0.2 % 0.0 % Zr-95 0.61 % 0.2 % I Nb-95 Ag-110m 1.0 % 0.08 % 0.39 % 0.13 % Sn-113 0.0 % 0.002 % I Sb-125 Cs-134 1.37 % 0.0 % 2.17 % 0.5 % Cs-137 8.0 % 7.0 % I 3. Number of Shipments

a. Type LSA 6

6 5 5 of Type A 0 0 I Container Used Type B Large Quantity 0 0 0 0

b. Solidification Cement 0 0 I Agent Used UreaFormaldehyde None 0

6 0 5

c. Mode of Truck 6 5 I Transport Rail Other 0

0 0 0

d. Final Oak Ridge, TN 6 5 I Destination
e. Waste Wampum, PA Class A 0

6 0 5 Class Class B 0 0 I per 10 CFR Part 61 Class C

                                            > Class C 0

0 0 0 I (1) Since container volumes are provided by the burial site , a calculational error of zero is assumed . (2) Percent values for any nuclide that are <0.01 % are not shown on this table . Data is available upon request. I

Form 1/2-ENV-01 .05.F01 (page 32 of 39), Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL # A9 .690E Enclosure 2, Page 14 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Table 3C Solid Waste And Irradiated Fuel Shipments (Part 3 of 3) I A. Solid Waste Shipped Offsite For Burial Or Disposal (Not irradiated fuel)

1. Type of Waste (Irradiated components, Control Rods, etc)

Jan -Jun Jul - Dec Estimated Total Error I

a. Volume Shipped m3 m3
b. Volume Buried m3 m3
c. Total Activity Ci Ci 0.0%
2. Estimate of Major Nuclide Composition Percent(%) Percent(%)

by Tvoe of Waste On This TablEl 2> I I I

3. Number of Shipments a.Type of LSA Type A I

Container Type B Used

b. Solidification Large Quantity Cement I

Agent Urea Formaldehyde Used

c. Mode of None Truck I

Transport Rail

d. Final Other Oak Ridge, TN I

Destination Barnwell, SC

e. Waste Class Class A Class B I

per Class C 10 CFR Part 61 > Class C I B. No Irradiated Fuel Shipments I (1) Since container volumes are provided by the burial site, a calculational error of zero is assumed . (2) Percent values for any nuclide that are <0.01 % are not shown on this table. Data is available upon request. I I I

I Form 1/2-ENV-01 .05.F01 (page 33 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page 15 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 Table 4 I Lower Limits Of Detectability (LLD) RWDA-G RWDA-L Filter Paper/ Charcoal I 1000 cc Gas Grab Sample Calculated (3) ODCM Required 1000 ml Liauid Grab Samole Calculated (3) ODCM Required Continuous Effluent Sam le Calculated (3) ODCM Required Nuclide LLD LLD LLD LLD (2) LLD LLD I H-3 Na-24 (4) (uCi/ccl 1.00E-06 7.33 E-08 (uCi/cc) 1E-06 1E-04 (uCi/mL) 1.00E-06 1.63E-08 (uCi/mL) 1E-06 SE-07 uCi/cc uCi/cc 1E-11 Ar-41 1.09E-07 1E-04 2.42E-08 SE-07 I Cr-51 Mn-54 Fe-55 3.29E-07 5.35E-08 1E-04 1E-04 (1) 7.98E-08 1.22E-08 1.00E-06 SE-07 SE-07 1E-06 1E-11 1E-11 Fe-59 1.15E-07 1E-04 2.59E-08 SE-07 2.91E-13 1E-11 I Co-57 Co-58 Co-60 4.61 E-08 4.71 E-08 5.29E-08 1E-04 1E-04 1E-04 1.25E-08 1.07E-08 1.18E-08 SE-07 5E-07 SE-07 7.44E-14 1.99E-13 2.99E-13 1E-11 1E-11 1E-11 Zn-65 1.77E-07 1E-04 3.96E-08 SE-07 5.74E-13 1E-11 I Se-75 Kr-85 Kr-85m 1.21 E-05

6. 17E-08 1E-04 1E-04 2.86E-06 1.60E-08 1E-05 1E-05 9.33 E-14 1E-11 Kr-87 1.22E-07 1E-04 2.93E-08 1E-05 I Kr-88 Sr-89 Sr-90 1.78E-07 1E-04 (1)

(1) 4.48E-08 5.00E-08 5.00E-08 1E-05 SE-08 SE-08 Sr-92 1.22 E-07 1E-04 2.71E-08 SE-07 2.26E-13 1E-11 I Nb-95 Nb-97 Zr-95 6.75 E-08 7.44E-08 1.00E-07 1E-04 1E-04 1E-04 1.55E-08 1.72E-08 2.30E-08 SE-07 SE-07 SE-07 1.43E- 13 1.47E-13 2.76 E-13 1E-11 1E-1 1 1E-11 Mo-99 5.37E-07 1E-04 1.23E-07 SE-07 1.70E-12 1E-1 1 I Tc-99m Aci-11 0m Sb-124 4.BOE-08 6.64E-08 5.43E-08 1E-04 1E-04 1E-04 1.27E-08 1.54E-08 1.27 E-08 SE-07 5E-07 SE-07 8.92E-14 1.40E-13 1.BOE-13 1E-11 1E-11 1E-11 Sb-125 1.62E-07 1E-04 3.87E-08 SE-07 2.97 E-13 1E-11 I 1-131 1-133 1-135 6.27E-08 4.42E-08 3.45E-07 1E-04 1E-04 1E-04 1.51E-08 1.04E-08 7.68E-08 1E-06 5E-07 SE-07 1.25E-13 1.98E-13 1E-12 1E-10 Xe-131m 1.89E-06 1E-04 4.85E-07 1E-05 Xe-133 1.29 E-07 1E-04 4.32E-08 1E-05 Xe-133m 3.99E-07 1E-04 9.87E-08 1E-05 Xe-135 4.24E-08 1E-04 1.04E-08 1E-05 Xe-135m 7.71 E-08 1E-04 1.81E-08 1E-05 Xe-137 7.07E-07 1E-04 1.68E-07 1E-05 Xe-138 2.16E-07 1E-04 5.30E-08 1E-05 Cs-134 4.73 E-08 1E-04 1.10E-08 SE-07 1.28E-13 1E-11 Cs-137 7.11 E-08 1E-04 1.64E-08 SE-07 1.49E-13 1E-11 I Ba-139 Ba-140 La-140 1.90E-07 1.58E-07 6.94E-08 1E-04 1E-04 1E-04 4.87E-08 3.71 E-08 1.55E-08 SE-07 SE-07 SE-07 2.67E-1 3 3.79 E-13 2.82E-13 1E-11 1E-11 1E-11 Ce-141 8.32E-08 1E-04 2.18E-08 5E-07 1.66E-13 1E-11 I Ce-144 Gross Alpha 3.19E-07 (1) Sample analyses perform ed by a contractor laboratory. 1E-04 (1) 8.52E-08 1.00E-07 5E-07 1E-07 8.47E-13 3.51E-1 5 1E-1 1 1E-1 1 I (2) These LLD calculations contain a default weekly continuous sample volu me of 2.85 E+8 cc. Therefore, grab sample LLD val ues reflect a different volume (ie; 10 cuft or 2.83E+5 cc) . (3) T he calculated LLD's are for Unit 2 Detector 2, except those denoted by (1) , are from a counter/detector cal ibration on 11 /16/17. I These values are typical for other counter/d etectors used for effluent counti ng at BVPS. (4) Based on counting 50 ml of the water that was bubbled through a 20 liter air sampl e. I

Form 1/2-ENV-01 .05.F01 (page 34 of 39) , Rev 5 Beaver Valley Power Station - Unit 1 RTL# A9 .690E Enclosure 2, Page 16 of 21 I Annual Radioactive Effluent Release Report I Calendar Year - 2017 Table 5A Assessment Of Radiation Doses I Unit 1 Liquid Effluents I 1st Quarter

                                        % of 2nd Quarter
                                                                   % of 3rd Quarter
                                                                                            % of 4th Quarter
                                                                                                                           % of Calendar Year
                                                                                                                                             % of    I Batch              Dose         ODCM          Dose ODCM                 Dose ODCM                   Dose          ODCM       Dose ODCM Releases Bone              5.94E-04 Limit 0.0119     2.13E-03 Limit 0.0426     4.27E-05 Limit 0.0009        7.78E-05 Limit 0.0016  2.85E-03 Limit 0.0285 I

0 Liver 6 .96E-03 0.1392 1.55E-02 0.3110 6.17E-03 0.1235 6.05E-03 0.1209 3.47E-02 0.3473 R G Total Body Thyroid 6.70E-03 6.10E-03 0.4469 0.1220 1.48E-02 1.31 E-02 0.9880 0.2619 6.18E-03 6.08E-03 0.4123 0.1217 6.01E-03 5.96E-03 0.4007 0.1192 3.37E-02 3.12E-02 1.1239 0.3124 I A N (1) Kidney Lung GI-LLI 6.39E-03 6.18E-03 7.15E-03 0.1278 0.1237 0.1430 1.38E-02 1.34E-02 1.84E-02 0.2758 0.2680 0.3681 6.09E-03 6.10E-03 6.93E-03 0.1219 0.1219 0.1386 5.98E-03 5.98E-03 6.14E-03 0.1195 0.1197 0.1228 3.23E-02 3.17E-02 3.86E-02 0.3225 0.3166 0.3863 I I Unit 1 Gaseous Effluents 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Calendar Year I

                                        % of                        % of                    % of                           % of Batch &

Continuous Releases Dose ODCM Limit Dose ODCM Limit Dose ODCM Limit Dose ODCM Limit Dose ODCM

                                                                                                                                             %of Limit I

(2) Gamma Air (2) Beta Air O.OOE+OO O.OOE+OO 0.0000 0.0000 5.59E-07 2.65E-09 0.0000 0.0000 O.OOE+OO O.OOE+OO 0.0000 0.0000 O.OOE+OO O.OOE+OO 0.0000 0.0000 5.59E-07 2.65E-09 0.0000 0.0000 I Bone O.OOE+OO 0.0000 3.65E-09 0.0000 1.38E-08 0.0000 O.OOE+OO 0.0000 1.74E-08 0.0000 0 Liver R Total Body 2.82E-03 2.82E-03 0.0376 0.0376 3.72E-03 3.72E-03 0.0496 0.0496 5.31 E-03 5.31E-03 0.0708 0.0708 1.03E-02 1.03E-02 0.1374 0.1374 2.22E-02 2.22E-02 0.1477 0.1477 I G Thyroid 2.82E-03 0.0376 3.72E-03 0.0496 5.31E-03 0.0708 1.03E-02 0.1374 2.22E-02 0.1477 A Kidney N Lung 2.82E-03 2.82E-03 0.0376 0.0376 3.72E-03 3.72E-03 0.0496 0.0496 5.31E-03 5.31E-03 0.0708 0.0708 1.03E-02 1.03E-02 0.1374 0.1374 2.22E-02 2.22E-02 0.1477 0.1477 I (3) GI-LLI 2.82E-03 0.0376 3.72E-03 0.0496 5.31 E-03 0.0708 1.03E-02 0.1374 2.22E-02 0.1477 (1) These doses are listed in mrem ; they are calculated for the maximum individual for all batch liquid effluents I (2) These doses are listed in mrad ; they are calculated at the site boundary for batch & continuous gaseous effluents (0.4 miles NW) (3) These doses are listed in mrem ; they are calculated for the most likely exposed real individual (ch ild) via all real pathways at 0.89 miles NW. I Limits used for calculation of percent(%) are from ODCM procedure 1/2-0DC-3.03, Attachment H Control 3.11.1.2, Attachment L Control 3.11.2.2, and Attachment M Control 3.11.2.3 (considered to be the design objectives). I I I

I Form 1/2-ENV-01 .05.F01 (page 35 of 39), Rev 5 Beaver Valley Power Station - Unit 2 RTL# A9.690E Enclosure 2, Page 17 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Table 58 Assessment Of Radiation Doses I Unit 2 Liquid Effluents I 1st Quarter

                                          % of 2nd Quarter
                                                                     % of 3rd Quarter
                                                                                              % of 4th Quarter
                                                                                                                            % of Calendar Year
                                                                                                                                              % of Batch              Dose ODCM                  Dose ODCM                 Dose ODCM                  Dose ODCM                Dose ODCM I        Releases Bone              5.94E-04 Limit 0.01 19    2.13E-03 Limit 0.0426     4.27E-05 Limit 0.0009       7.78E-05 Limit 0.0016  2.85E-03 Limit 0.0285 0     Liver             6.96E-03        0.1392     1.55E-02        0.31 10    6.17E-03      0.1235       6 .05E-03        0.1209  3.47E-02  0.3473 I  R G

Total Body Thyroid 6.70E-03 6.10E-03 0.4469 0.1220 1.48E-02 1.31 E-02 0.9880 0.2619 6.18E-03 6.08E-03 0.4123 0.1217 6.01E-03 5.96E-03 0.4007 0.1192 3.37E-02 3.12E-02 1.1239 0.3124 I A N Kidney Lung 6.39E-03 6.18E-03 0.1278 0.1237 1.38E-02 1.34E-02 0.2758 0.2680 6.09E-03 6.10E-03 0.1219 0.1219 5.98E-03 5.98E-03 0.1195 0.1197 3.23E-02 3.17E-02 0.3225 0.3166 (1) GI-LLI 7.15E-03 0.1430 1.84E-02 0.3681 6.93E-03 0.1386 6.14E-03 0.1228 3.86E-02 0.3863 I I 1st Quarter 2nd Quarter Unit 2 Gaseous Effluents 3rd Quarter 4th Quarter Calendar Year I Batch & Continuous Releases Dose ODCM

                                          % of Limit Dose ODCM
                                                                     % of Limit Dose ODCM
                                                                                              % of Limit Dose ODCM
                                                                                                                            % of Limit Dose ODCM
                                                                                                                                              % of Limit I (2) Gamma Air O.OOE+OO (2) Beta Air             O.OOE+OO 0.0000 0.0000 5.59E-07 2.65E-09 0.0000 0.0000 O.OOE+OO O.OOE+OO 0.0000 0.0000 O.OOE+OO O.OOE+OO 0.0000 0.0000 5.59E-07 2.65E-09 0.0000 0.0000 Bone              O.OOE+OO        0.0000      3.67E-04        0.0049    1.38E-08       0.0000     O.OOE+OO          0.0000  3.67E-04  0.0024 I  0 Liver R Total Body 8.84E-04 8.84E-04        0.0118 0.0118 9.35E-04 9.62E-04 0.01 25 0.0128 7.60E-04 7.60E-04 0.0101 0.0101 8.60E-04 8.60E-04 0.0115 0.0115 3.44E-03 3.47E-03 0.0229 0.0231 G Thyroid                8.84E-04       0.0118      9.20E-04        0.01 23   7.60E-04       0.0101      8.60E-04         0.0115  3.42E-03   0.0228 I  A Kidney N Lung 8.84E-04 8.84E-04 0.0118 0.0118 9.22E-04 1.42E-03 0.0123 0.0190 7.60E-04 7.60E-04 0.0101 0.0101 8.60E-04 8.60E-04 0.0115 0.0115 3.43E-03 3.93E-03 0.0228 0.0262 (3) GI-LLI I                           8.84E-04       0.0118      1.03E-03        0.0137    7.60E-04       0.0101      8.60E-04 (1) These doses are listed in mrem ; they are calculated for the maximum individual for all batch liquid effluents 0.0115  3.53E-03   0.0236 I (2) These doses are listed in mrad ; they are calculated at the site boundary for batch & continuous gaseous effluents (0.4 miles NW)

(3) These doses are listed in mrem ; they are calculated for the most likely exposed real individual (child) via all real pathways at 0.89 miles NW I Limits used for calculation of percent(%) are from ODCM procedure 1/2-0DC-3.03, Attachment H Control 3.11 .1.2, Attachment L Control 3.11.2.2, and Attachment M Control 3. 11.2.3 (considered to be the design objectives). I I

Form 1/2-ENV-01 .05 .F01 (page 36 of 39), Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page 18 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Table 6 I Effluent Monitoring Instrumentation Channels Not Returned To Operable Status Within 30 Days I There were two Effluent Monitoring Instrumentation Channels that were not returned to operable status within 30 days.

1) Unit 1 Main Steam Effluent Monitor, RM-1 MS-1 OOC On 03/25/17 the monitor was taken out of service to inspect and repair with regards to spiking . It was determined that the detector and preamp were to be replaced . Due to the location of the detector, it must be replaced during an outage . The monitor is currently out of service and is schedu led to be replaced during 1R25. (reference CR-2017-04541 ).
2) Unit 1 Liquid Waste Effluent Monitor, RM-1LW-104 On 11/26/17 the monitor was taken out of service in support of ECP 16-0113-001 that would replace and install new digital rate meters. Due to Engineering and vendor issues with parts, the replacement was delayed. The monitor was returned to I

service on 02/01/2018 (reference CR-2017-12446). I I I I I I I I I

I Form 1/2-ENV-01 .05.F01 (page 37 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9 .690E Enclosure 2, Page 19 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Table 7 Total Dose Commitments, Total Effective Dose Equivalents and Population Doses I Total Dose Commitment From All Facility Releases To Members of the Public 40 CFR 190.10(a) Environmental Doses Effluent Dose 11 l Direct Radiation Dose 121 Total Dose  % ofODCM or ,I Organ Bone (mrem) 6 .06E-03 (mrem) O.OOE+OO (mrem) 6.06E-03 40 CFR 190 Limit 0.02% 'I Liver Total Body 9 .50E-02 9.30E-02 O.OOE+OO O.OOE+OO 9.50E-02 9.30E-02 0.38% 0 .37% Thyroid 8 .80E-02 O.OOE+OO 8.80E-02 0.12% I Kidney Lung 9 .01E-02 8.94E-02 O.OOE+OO O.OOE+OO 9.01E-02 8.94E-02 0.36% 0.36% GI-LLI 1.03E-01 O.OOE+OO 1.03E-01 0.41% I (1) The cumulative dose contributions from liquid and gaseous effluents were determined in accordance with the applicable CONTROLS & SURVEILLANCE REQUIREMENTS listed in ODCM procedure 1/2-0DC-3.03. I The dose commitment limits for 40 CFR 190 MEMBERS OF THE PUBLIC (ODCM 1/2-0DC-3.03 Control 3.11.4.1) are as follows : a) <or= 25 mrem / calendar year (for the total body, or any organ except the thyroid) I b) < or= 75 mrem / calendar year (for the thyroid) (2) The dose contribution listed for the total body is for Direct Radiation . This was calculated by comparing offsite TLD exposure at the ODCM controlling location (0 .8 miles NW; Midland, PA) to TLD exposure at the I REMP control location (16 .5 miles SSW; Weirton , WV) . Compliance to 100 mrem Limit of 10 CFR 20.1301 For Total Effective Dose Equivalent I Pursuant to 10 CFR 20.1301(a)(1), the Tota l Effective Dose Equivalent from licensed operation to the maximum individual during the report period , is 5.06 mrem. This is a summation of Direct Radiation Exposure (calculated by comparing the maximum of all perimeter TLD exposures to TLD exposure at the REMP control location) plus Effluent Doses (calcu lated per the ODCM). I Members of the Public Doses Due To Their Activities Inside The Site Boundary I The radiation doses for MEMBER(S) OF THE PUBLIC due to their activities inside the site boundary are not greater than the doses listed in this table to show compliance with 40 CFR Part 190 or 10 CFR 20.1301 . Evaluations have shown that exposure time for individuals not occupationally associated with the plant site is minimal in comparison to the exposure time considered I for the dose calculation at or beyond the site boundary. Therefore , a separate assessment of radiation doses from radioactive effluents to MEMBER(S) OF THE PUBLIC , due to their activities inside the site boundary , is not necessary for this report period. I 0-50 Mile Population Doses From Liquid and Gaseous Effluents 0-50 mile Total Population Dose from liquid and gaseous effluents= 99.96 man-mrem (Total Body) 0-50 mile Average Population Dose from liquid and gaseous effluents = 0.0000250 man-mrem (Total Body) I I I

Form 1/2-ENV-01 .05.F01 (page 38 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page 20 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Table 8 I Offsite Dose Calculation Manual Surveillance Deficiencies I There were three Offsite Dose Calculation Manual Surveillance Deficiencies during this report period .

1) Main Steam Cable Vault (Fire Sump) sample On 5/22/17 the main steam cable vault was discharged. Two independent samples were obtained by Radiation I

Protection and no isotopes were identified. However, the samples were discarded before Chemistry could analyze them for tritium . The discharge was documented and based on the tritium from the most recent sump discharge (reference CR-2017-07282) . I

2) Catch Basin (Yard Drain) Sample Catch Basin 17A, 1CB-17A, is sampled annually. During Q4 2017 , there was no flow observed at this location and no sample could be obtained. Th is location is the first sample point of the yard drains around Unit 1 and samples I

were obtained downstream of 1CB-17A and had no LRM detected . (reference CR-2018-00126)

3) Beaver Valley Representative Sampling I

It was determined that, due to incorrectly sized nozzles and variations the ventilation stack flows , the effluent monitor sampling skid does not provide representative sampling of particulate isotopes (especially of larger particle sizes) under all normally occurring ventilation conditions at all of Unit 1 pathways and Unit 2 Ventilation Vent and Condensate Polishing Building Vent pathways. This condition was identified and questioned during a Unit 1 sample I pump replacement in April 2017. Due to the limited amount of particu late that is released from the site, it does not significantly affect dose or dose rates to the pub lic, nor challenge any regulatory limits (reference CR-2017-04211 ). I I I I I I I I I I

Form 1/2-ENV-01 .05.F01 (page 39 of 39), Rev 5 RTL# A9 .690E Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Page 21 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 Table 9 I Offsite Dose Calculation Manual Changes (Description) I There was one (1) change made to the ODCM during the report period. See ODCM procedure 1/2-0DC-1 .01 , I "ODCM : Index, Matrix and History ODCM Changes" for a complete description of the change and the change justification. A brief description of the change is as follows :

1) Change (41) to the ODCM (Effective January 2017)

I <> Procedure 1/2-0DC-1.01 , "ODCM : Index, Matrix and History of ODCM Changes" (Rev 24) Updated the History of ODCM changes to include this change I <> Procedure 1/2-0DC-2.03, "ODCM : Radiological Environmental Monitoring Program" (Rev 8) Updated for the relocation of waterbourne surface sample location from #2 .1 to #5 and added milk sample location #114 . Maps for all sample locations were updated . I I I I I I I I I I I I

I I I I I I I I I ENCL0SURE2,ATTACHMENT1 I I I I I I I I I I

I Beaver Valley Power Station - Units 1 & 2 RTL # A9.690E Enclosure 2, Attachment 1 I Annual Radioactive Effluent Release Report Calendar Year - 2017 Attachment 1 Joint Frequency Distribution Tables Attachment 1 I As specified in the ODCM , an annual summary of hourly meteorological data (in the form of joint frequency distribution) is provided for the calendar year. In summary , the joint frequency distribution data is similar to previous years and close to long-term normals. I Meteorological Data Recovery I The Meteorological Data Recovery for the calendar year met the minimum requirement of at-least 90% (as specified in Section 5 of Revision 1 to Regulatory Guide 1.23, Meteorological Monitoring Programs for Nuclear Power Plants) . The actual Meteorological Data Recovery is shown in the following table : I PERCENT RECOVERY OF INDIVIDUAL METEOROLOGICAL PARAMETERS 99.5% =Wind Speed 35' 98 .1% =Wind Speed 150' 99.9% =Wind Speed 500' I 99.9% =Wind Direction 35' 99.9% =Wind Direction 150' 99.8% =Wind Direction 500' I 99.8% =Delta Temperature (150' - 35') 1P 99.8% =Delta Temperature (500' - 35' ) 2P 99.8% =Temperature 35' 99 .9% =Precipitation I 99.6% =Average Recovery of Individual Meteorological Parameters PERCENT RECOVERY OF COMPOSITE VARIABLES I 99.7% =Wind Speed 35', Wind Direction 35', Delta Temperature 1P 98.1% =Wind Speed 150', Wind Direction 150', Delta Temperature 1P 99.7% =Wind Speed 500', Wind Direction 500', Delta Temperature 2P

                                          =Average Recovery of Composite Variables I                                 99.5%

Attachment 1 Clarification Hourly meteorological data is not provided for specific periods of Abnormal Gaseous Release during the calendar I quarters (as indicated in Regulatory Guide 1.21 ), for the following reasons :

1) All routine Gaseous Releases for the calendar year were determined to be within design objectives, where as, the I ODCM Dose Limits and the ODCM Dose Rate Limits are considered to be the design objectives.
2) There were two Abnormal Gaseous Releases during the calendar year, neither exceeded design objectives.

I For a copy of the hourly meteorological data during the calendar quarters, contact Radiological Effluents Administrator at 724-682-4255. I I I I

RTL A9.690E Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Attachment 1 (Part 1 of 3) Annual Radioactive Effluent Release Report Calendar Year - 2017 I Part 1: Joint Frequency Distribution Tables (35ft) Page 1 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period All Hours I Period of Record Elevation:

                        =

Speed: SP35P 01/01 /2017 0 I :00 - 12/31 /2017 23 :00 Direction: DI35P Lapse: DT150-35 I Stability Class: A Delta Temperature Extremely Unstable Ii Wind Speed (mph) Wind Direction 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total Ii N 43 42 0 0 0 0 85 NNE NE ENE 34 41 59 28 7 18 0 0 0 0 0 0 0 0 0 0 0 0 62 48 77 I E 25 24 0 0 0 0 49 ESE SE SSE 30 31 11 7 9 6 0 0 0 0 0 0 0 0 0 0 0 0 37 40 17 I s 21 24 1 0 0 0 46 SSW SW 19 26 49 66 24 9 0 0 0 0 0 0 77 116 I WSW 32 104 17 0 0 0 153 w 39 143 17 0 0 0 199 WNW 47 98 6 0 0 0 151 NW 52 50 2 0 0 0 104 NNW 35 44 0 0 0 0 79 Total 545 719 76 0 0 0 1340 Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 240 0 I' Invalid Hours for: Total Period All Hours 26 Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 1340 8759 I I I I

I Beaver Valley Power Station - Units 1 & 2 RTLA9.690E Enclosure 2, Attachment 1 (Part 1 of 3) Annual Radioactive Effluent Release Report I Calendar Year - 20 17 Attachment 1 I Part I : Joint Frequency Distribution Tables (35ft) Page 2 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period All Hours I Period of Record Elevation:

                           =

Speed: SP35P 01/01 /2017 01:00- 12/31 /2017 23:00 Direction: DI35P Lapse: DT150-35 I Stability Class: B Delta Temperature Moderately Unstable Wind Speed (mph) I Wind Direction N 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total 9 4 0 0 0 0 13 I NNE NE ENE 2 7 10 5 0 4 0 0 0 0 0 0 0 0 0 0 0 0 7 7 14 E 4 1 0 0 0 0 5 I ESE SE SSE 2 4 5 0 2 1 0 0 0 0 0 0 0 0 0 0 0 0 2 5 7 s I SSW SW 2 2 2 3 9 9 0 7 13 0 0 3 0 0 0 0 0 0 5 18 27 WSW 7 24 8 I 0 0 40 I WNW w NW 8 5 9 20 8 6 1 0 0 0 0 0 0 34 14 6 I 0 0 0 16 NNW I Total 80 2 4 100 36 0 0 4 0 0 0 0 220 6 I Calm Hours not Included above for: Variable Direction Hours for: Invalid Hours for: Total Total Period Period All All Hours Hours 240 0 Total Period All Hours 26 I Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 220 8759 I I I I

RTL A9.690E Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Attachment 1 (Part 1 of 3) I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Part 1: Joint Frequency Distribution Tables (35ft) Page 3 of 8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period I All Hours Period of Record Elevation:

                        =

Speed: SP35P 01 /01/2017 0 I :00 - 12/31 /2017 23 :00 Direction: Dl35P Lapse: DT150-35 I Stability Class: C Delta Temperature Slightly Unstable I Wind Speed (mph) Wind Direction N 0.6-3.5 8 3.6-7.5 9 7.6-12.5 0 12.6-18.5 0 18.6-24.5 0

                                                                                                          >24.6 0

Total 17 I NNE 5 2 0 NE ENE 4 10 0 1 0 0 0 0 0 0 0 0 0 0 0 7 5 10 I E 6 4 0 0 0 0 10 ESE SE SSE 8 4 3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8 4 3 I s SSW SW 4 1 3 II 1 9 0 0 14 0 0 0 0 0 0 0 0 0 5 10 28 I WSW 6 22 10 0 0 0 38 WNW w NW 9 6 8 24 16 11 4 2 1 0 0 0 0 0 0 0 0 0 37 24 20 I NNW 7 7 Total 92 117 31 0 0 0 0 0 0 0 14 240 I Calm Hours not Included above for: Variable Direction Hours for: Invalid Hours for: Total Total Total Period Period Period All All All Hours Hours Hours 240 0 26 I Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 240 8759 I I I

I Beaver Valley Power Station - Units 1 & 2 RTL A9.690E Enclosure 2, Attachment 1 (Part 1 of 3) Annual Radioactive Effluent Release Report I Calendar Year - 20 I 7 Attachment 1 I Part 1: Joint Frequency Distribution Tables (35ft) Page 4 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period All Hours I Period of Record Elevation:

                           =

Speed: SP35P 01 /01/2017 0 I :00 - 12/31/20 I 7 23 :00 Direction: DI35P Lapse: DTI50-35 I Stability Class: D Delta Temperature Neutral Wind Speed (mph) I Wind Direction N 0.6-3.5 58 3.6-7.5 36 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total 0 0 0 0 94 I NNE NE ENE 60 66 82 14 4 14 0 0 0 0 0 0 0 0 0 0 0 0 74 70 96 E 55 3 0 0 0 0 58 I ESE SE SSE 34 47 2 l 0 0 0 0 0 0 0 0 36 48 38 8 0 0 0 0 46 s I SSW SW 45 48 84 45 64 199 119 l 16 0 0 8 0 0 0 0 0 0 91 128 410 WSW 75 185 84 9 0 0 353 I WNW w NW 73 85 90 237 144 94 64 13 6 4 0 0 0 0 0 0 0 0 378 242 190 NNW I Total 74 1014 61 11 I I 308 5 21 0 0 0 0 0 140 2454 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 240 0 In valid Hours for: Total Period All Hours 26 I Number of Valid.Hours for this Table: Total Hours for the Period: Total Period All Hours 2454 8759 I I I I

RTL A9 .690E Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Attachment 1 (Part 1 of 3) I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Part 1: Joint Frequency Distribution Tables (35ft) Page 5 of 8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction I Total Period All Hours Period of Record Elevation:

                        =

Speed: SP35P 01 /01 /2017 0 I :00 - 12/31 /2017 23 :00 Direction: DI35P Lapse: DT150-35 I Stability Class: E Delta Temperature Slightly Stable I Wind Speed (mph) Wind Direction N 0.6-3.5 68 3.6-7.5 10 7.6-12.5 0 12.6-18.5 0 18.6-24.5 0

                                                                                                           >24.6       Total I 0          78 NNE NE ENE 84 160 197 3

4 25 0 0 0 0 0 0 0 0 0 0 0 0 87 164 222 I E 170 2 0 0 0 0 172 ESE SE SSE 133 11 3 122 0 3 1 0 0 0 0 0 0 0 0 0 0 134 113 I 0 0 125 s 141 SSW SW 170 123 28 63 110 3 9 45 0 0 2 0 0 0 0 0 0 172 242 280 I WSW 82 92 37 5 0 0 216 WNW w NW 48 61 61 82 40 26 18 7 0 0 0 0 0 0 0 0 0 0 148 108 87 I NNW 102 19 0 0 0 0 121 Total 1835 508 119 7 0 0 2469 Calm Hours not Included above for: Total Period All Hours 240 Variable Direction Hours for: Total Period All Hours 0 Invalid Hours for: Total Period All Hours 26 Number of Valid Hours for this Table: Total Period All Hours 2469 Total Hours for the Period: 8759 I I

I Beaver Valley Power Station - Units 1 & 2 RTL A9.690E Enclosure 2, Attachment 1 (Part 1 of 3) Annual Radioactive Effluent Release Report I Calendar Year - 2017 Attachment 1 I Part 1: Joint Frequency Distribution Tables (35ft) Page 6 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period All Hours I Period of Record Elevation:

                          =

Speed: SP35P 01 /0 1/2017 01 :00- 12/31 /2017 23:00 Direction: DI35P Lapse: DTl50-35 I Stability Class: F Delta Temperature Moderately Stable Wind Speed (mph) I Wind Direction N 0.6-3.5 15 3.6-7.5 I 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total 0 0 0 0 16 I NNE NE ENE 18 41 57 0 I 1 0 0 0 0 0 0 0 0 0 0 0 0 19 42 57 E 112 0 0 0 0 0 112 I ESE SE SSE 187 221 148 0 0 0 0 0 0 0 0 0 0 0 0 187 221 0 0 0 148 s 125 I SSW SW 66 34 4 13 9 0 0 0 0 0 0 0 0 0 0 0 0 129 79 43 WSW 23 I 0 0 0 0 24 I w WNW NW 13 10 8 2 1 0 0 0 0 0 0 0 0 0 0 0 0 0 14 12 8 NNW 17 I Total 1095 33 0 0 0 0 0 0 0 0 0 17 1128 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 240 0 Invalid Hours for: Total Period All Hours 26 I Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 1128 8759 I I I I

RTL A9.690E Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Attachment 1 (Part 1 of 3) Annual Radioactive Effluent Release Report Calendar Year - 2017 I Part 1: Joint Frequency Distribution Tables (35ft) Page 7 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction I Total Period All Hours Period of Record Elevation:

                        =

Speed: SP35P 01 /0I /2017 0 I :00 - 12/3 I/2017 23 :00 Direction: Dl35P Lapse: DTl50-35 I Stability Class: G Delta Temperature Extremely Stable I Wind Speed (mph) Wind Direction 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total I N 7 0 0 0 0 0 7 NNE NE ENE 12 23 37 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 12 23 37 I E 55 0 0 0 0 0 55 ESE SE 99 201 0 0 0 0 0 0 0 0 0 0 99 201 I SSE 62 0 0 0 0 0 62 SSW SW s 45 41 20 7 0 1 0 0 0 0 0 0 0 0 0 0 0 0 52 42 20 I WSW 11 0 0 0 0 0 11 w WNW 2 2 0 0 0 0 0 0 0 0 0 0 2 2 I NW 12 0 0 0 0 0 12 NNW Total 634 5 0 8 0 0 0 0 0 0 0 0 5 642 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 240 0 I Invalid Hours for: Total Period All Hours 26 Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 642 8759 I I I I I

I Beaver Valley Power Station - Units 1 & 2 RTL A9.690E Enclosure 2, Attachment 1 (Part 1 of 3) Annual Radioactive Effluent Release Report I Calendar Year - 2017 Attachment 1 I Part 1: Joint Frequency Distribution Tables (35ft) Page 8 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period All Hours I Period of Record Elevation:

                           =

Speed: SP35P 01 /01 /2017 0 I :00 - 12/31 /2017 23 :00 Direction: Dl35P Lapse: DT150-35 I Stability Class: ALL Delta Temperature Wind Speed (mph) I Wind Direction N 0.6-3.5 208 3.6-7.5 102 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total 0 0 0 0 310 I NNE NE ENE 215 342 452 53 17 61 0 0 0 0 0 0 0 0 0 0 0 0 268 359 513 E 427 34 0 0 0 0 461 I ESE SE 493 621 IO 11 0 0 0 0 0 0 0 0 503 632 SSE 389 19 0 0 0 0 408 s I SSW SW 383 347 292 112 208 404 5 41 215 0 0 13 0 0 0 0 0 0 500 596 924 WSW 236 428 156 15 0 0 835 I w WNW NW 192 216 240 507 308 187 109 29 IO 4 0 0 0 0 0 0 0 812 553 0 437 NNW I Total 242 5295 135 2596 5 570 0 32 0 0 0 0 382 8493 I Ca lm Hours not Included above for: Variable Direction Hours fo r: Total Total Period Period All All Hours Hours 240 0 Invalid Hours for: Total Period All Hours 26 I Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 8493 8759 I

1

'I I

RTLA9.690E Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Attachment 1 (Part 2 of 3) I Annual Radioactive Effluent Release Report Calendar Year - 2017 11I Part 1: Joint Frequency Distribution Tables ( 150ft) Page 1 of 8 IJ Joint Frequency Distribution I: Hours at Each Wind Speed and Direction I Total Period All Hours Period of Record = 0 I/0I /2017 0 I :00 - 12/3 I /2017 23 :00 Elevation: Speed: SP150P Direction: DI150P Lapse: DTl50-35 Stability Class: A Delta Temperature Extremely Unstable I Wind Speed (mph) Wind Direction N 0.6-3.5 8 3.6-7.5 48 7.6-12.5 32 12.6-18.5 1 18.6-24.5 >24.6 Total I 0 0 89 NNE NE ENE 8 6 3 27 25 39 22 11 24 2 0 0 0 0 0 0 0 0 59 42 66 I E 2 39 27 1 0 0 69 ESE SE SSE 3 1 0 27 25 19 17 15 13 0 2 0 0 0 0 0 47 43 I 0 0 32 s SSW SW 3 3 6 34 21 21 37 28 30 4 2 11 0 0 0 0 0 0 78 54 68 I WSW 15 28 70 15 0 0 128 WNW w NW 12 19 12 77 55 28 112 80 24 25 35 5 I 5 0 0 0 227 194 I 0 69 NNW Total 16 117 39 552 20 562 0 103 0 6 0 0 75 1340 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 9 0 I Invalid Hours for: Total Period All Hours 28 Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 1340 8759 I I I I I

I Beaver Valley Power Station - Units 1 & 2 RTL A9 .690E Enclosure 2, Attachment 1 (Part 2 of 3) Annual Radioactive Effluent Release Report I Calendar Year - 2017 Attachment I I Part I : Joint Frequency Distribution Tables ( 150ft) Page 2 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period All Hours I Period of Record Elevation:

                            =

Speed: SP! SOP 01 /01 /2017 01 :00 - 12/31 /2017 23:00 Direction: 01150P Lapse: DTIS0-35 I Stability Class: B Delta Temperature Moderately Unstable Wind Speed (mph) I Wind Direction 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total N 0 6 3 0 0 0 9 I NNE NE ENE 2 3 0 9 5 5 I I 6 0 0 0 0 0 0 0 0 0 12 11 9 E I 5 I 0 0 0 7 I ESE SE SSE 0 0 0 0 6 1 I 2 2 0 0 0 0 0 0 2 2 0 0 0 8 11 SSW SW s 0 0 0 4 I 5 7 0 8 0 0 0 0 6 19 0 10 8 0 0 18 WSW 2 IO 10 9 I 33 !1 WNW w NW 3 4 4 11 5 14 9 8 7 I 0 0 37 26 3 4 I 0 0 12 I NNW Total 21 2 76 5 78 2 41 0 0 3 0 220 9 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 9 0 Invalid Hours for: Total Period All Hours 28 I Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 220 8759 I

Beaver Valley Power Station - Units 1 & 2 RTLA9.690E Enclosure 2, Attachment 1 (Part 2 of 3) I Annual Radioactive Effluent Release Report Calendar Year - 2017 Attachment I I Part 1: Joint Frequency Distribution Tables ( 150ft) Page 3 of 8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction I Total Period All Hours Period of Record Elevation:

                        =

Speed: SP150P 01 /01 /2017 01:00- 12/31 /2017 23:00 Direction: DI150P Lapse: DTl 50-35 I Stability Class: C De lta Temperature Slightly Unstable I Wind Speed (mph) Wind Direction N 0.6-3.5 3 3.6-7.5 6 7.6-12.5 2 12.6-18.5 0 18.6-24.5 0

                                                                                                         >24.6 0

Total 11 I NNE NE ENE 4 2 2 7 5 I I 5 0 0 0 0 0 0 0 0 0 12 4 12 I E 1 4 5 0 0 0 10 ESE SE SSE 2 0 2 2 5 I 2 2 0 0 0 0 0 0 0 0 6 7 I 0 0 3 s SSW SW 1 0 I 6 2 1 4 5 8 0 1 6 0 0 0 0 0 0 11 7 17 I WSW 4 8 10 11 0 0 33 w WNW NW 6 2 1 9 11 7 21 12 8 10 10 2 0 1 0 0 0 46 36 18 I 0 NNW 0 3 4 0 Total 31 78 90 40 0 0 0 7 240 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 9 0 I Invalid Hours for: Total Period All Hours 28 Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 240 8759 I

I Beaver Valley Power Station - Units 1 & 2 RTL A9 .690E Enclosure 2, Attachment 1 (Part 2 of 3) Annual Radioactive Effluent Release Report I Calendar Year - 2017 Attachment I I Part l: Joint Frequency Distribution Tables (150ft) Page 4 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period All Hours I Period of Record Elevation:

                            =

Speed: SP150P 01 /01 /2017 0 I :00 - 12/31 /2017 23 :00 Direction: DI150P Lapse: DT150-35 I Stability Class: D Delta Temperature Neutral Wind Speed (mph) I Wind Direction 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total II N NNE NE 15 21 29 32 47 27 32 16 7 1 I 0 0 0 0 0 0 0 80 85 63 ENE 14 62 20 2 0 0 98 E 12 30 12 0 0 0 54 I ESE SE SSE 12 15 14 13 21 24 6 10 12 2 0 1 0 0 0 0 0 0 33 46 51 s I SSW SW 16 21 23 51 43 48 50 55 136 4 18 63 0 0 5 0 0 0 121 137 275 WSW 38 76 114 48 4 2 282 I WNW w NW 41 28 15 101 106 69 222 146 52 151 72 2 18 5 1 7 0 0 540 357 139 I NNW Total 15 329 31 781 33 923 4 369 33 0 0 9 83 2444 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 9 0 In valid Hours for: Total Period All Hours 28 I Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 2444 8759 I I I I

Beaver Valley Power Station - Units 1 & 2 RTL A9.690E Enclosure 2, Attachment 1 (Part 2 of 3) I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Part 1: Joint Frequency Distribution Tables ( 150ft) Page 5 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction I Total Period All Hours Period of Record Elevation:

                         =

Speed: SPl50P 0I /01 /2017 01 :00 - 12/3 1/20 17 23 :00 Direction: Dl150P Lapse: DT150-35 I Stability Class: E Delta Temperature Slightly Stable I Wind Speed (mph) Wind Direction 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total I N 45 25 17 0 0 0 87 NNE NE ENE 81 126 79 41 151 153 51 2 8 1 0 3 0 0 0 0 0 0 125 285 286 I E 41 50 11 1 0 0 103 ESE SE SSE 21 34 24 25 29 33 2 7 11 0 0 0 0 0 0 0 0 0 48 70 68 I SSW SW s 53 76 76 61 67 72 47 45 91 6 8 26 0 0 0 0 0 0 167 196 265 I WSW 47 59 62 16 I 0 185 WNW w 39 20 27 64 102 51 81 67 10 61 10 0 20 4 0 1 0 0 266 203 88 I NW NNW Total 19 808 35 1018 521 9 0 132 0 25 0 63 2505 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 9 0 I Invalid Hours for: Total Period All Hours 28 Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 2505 8759 I I I I I

I Beaver Valley Power Station - Units 1 & 2 RTL A9.690E Enclosure 2, Attachment 1 (Part 2 of 3) Annual Radioactive Effluent Release Report I Calendar Year - 2017 Attachment 1 I Part 1: Joint Frequency Distribution Tables ( 150ft) Page 6 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period All Hours I Period of Record Elevation:

                          =

Speed: SP150P 01 /0 I /2017 0 I :00 - 12/31 /2017 23 :00 Direction: DI150P Lapse: DT150-35 I Stability Class: F Delta Temperature Moderately Stable Wind Speed (mph) I Wind Direction N 0.6-3.5 50 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total 5 0 0 0 0 55 I NNE NE ENE 127 165 75 25 98 39 1 5 4 0 0 0 0 0 0 0 0 0 153 268 118 E 31 10 0 0 0 0 41 I ESE SE SSE 9 12 14 6 13 8 0 I 0 0 0 0 0 0 17 19 2 0 0 0 29 s I SSW SW 48 90 80 25 59 36 5 7 14 0 0 0 0 0 0 0 0 0 78 156 130 WSW 43 23 6 0 0 0 72 I w WNW NW 25 8 16 10 6 3 4 1 0 1 0 0 0 0 0 0 0 0 40 15 19 I NNW Total 27 820 12 378 0 50 0 0 0 0 0 39 1249 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 9 0 Invalid Hours for: Total Period All Hours 28 I Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 1249 8759 I I I I

Beaver Valley Power Station - Units 1 & 2 RTL A9.690E Enclosure 2, Attachment 1 (Part 2 of 3) I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Part I: Joint Frequency Distribution Tables (150ft) Page 7 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period All Hours I Period of Record Elevation:

                        =

Speed: SPl50P 01 /01 /2017 01 :00 - 12/31 /2017 23:00 Direction: DI150P Lapse: DTl 50-35 I Stability Class: G Delta Temperature Extremely Stable I Wind Speed (mph) Wind Direction N 0.6-3.5 41 3.6-7.5 4 7.6-12.5 0 12.6-18.5 0 18.6-24.5 0

                                                                                                         >24.6 0

Total 45 I NNE NE ENE 88 70 43 28 60 12 0 1 0 0 0 0 0 0 0 0 0 0 116 131 55 I E 10 6 0 0 0 0 16 ESE SE SSE 13 9 12 5 6 11 0 1 1 0 0 0 0 0 0 0 0 0 18 16 24 I s SSW SW 30 43 37 39 32 30 5 2 5 0 0 0 0 0 0 0 0 0 74 77 72 I WSW 15 9 2 0 0 0 26 WNW w NW 12 7 9 9 1 1 0 I 0 0 0 0 0 0 0 0 0 0 13 17 10 I NNW Total 12 451 2 255 0 18 0 0 0 0 0 0 14 724 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 9 0 I Invalid Hours for: Total Period All Hours 28 Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 724 8759 I I I I I

I Beaver Valley Power Station - Units 1 & 2 RTL A9 .690E Enclosure 2, Attachment 1 (Part 2 of 3) Annual Radioactive Effluent Release Report I Calendar Year - 2017 Attachment I I Part I : Joint Frequency Distribution Tables (150ft) Page 8 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period All Hours I Period of Record Elevation:

                           =

Speed: SPJ SOP 0I /01 /2017 0 I :00 - 12/31 /2017 23 :00 Direction: Dl150P Lapse: DTI 50-35 I Stability Class: ALL Delta Temperature Wind Speed (mph) I Wind Direction 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total N 162 126 86 2 0 0 376 I NNE NE ENE 331 401 216 184 367 315 43 34 110 4 0 5 0 0 0 0 0 0 562 802 646 E 98 144 56 2 0 0 300 I ESE SE 60 71 81 92 28 38 2 2 0 0 0 0 171 203 SSE 66 107 41 I 0 0 215 s I SSW SW 151 233 223 217 227 209 153 149 294 14 37 114 0 0 5 0 0 0 535 646 845 WSW 164 213 274 99 6 3 759 I WNW w NW 138 88 84 273 294 162 454 316 256 134 40 16 8 0 1169 848 98 10 1 0 355 I NNW Total 91 2577 127 3138 68 2242 686 4 68 0 0 11 290 8722 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 9 0 Invalid Hours for: Total Period All Hours 28 Number of Valid Hours for this Table: Total Period All Hours 8722 Total Hours for the Period: 8759

Beaver Valley Power Station - Units 1 & 2 RTL A9.690E Enclosure 2, Attachment 1 (Part 3 of 3) I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Part 1: Joint Frequency Distribution Tables (500ft) Page 1 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction I Total Period All Hours Period of Record Elevation:

                        =

Speed: SP500P 0I /01/2017 0 I :00 - 12/31 /2017 23 :00 Direction: DI500P Lapse: DTS00-35 I Stability Class: A Delta Temperature Extremely Unstable I Wind Speed (mph) Wind Direction 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total I N 0 0 2 3 0 0 5 NNE NE ENE 0 0 0 0 0 0 0 0 4 0 2 1 0 0 0 0 0 0 0 2 5 I E 0 3 5 0 0 0 8 ESE SE SSE 0 0 0 4 I 1 6 10 3 0 2 0 0 0 0 0 0 10 13 I 0 4 s SSW SW 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 I WSW 0 0 0 0 0 0 0 w WNW NW 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 1 0 I 0 0 0 0 NNW Total 0 0 0 10 30 0 0 8 0 0 0 0 48 0 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 6 0 I Invalid Hours for: Total Period All Hours 19 Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 48 8759 I I I I I

RTL A9.690E Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Attachment 1 (Part 3 of 3) Annual Radioactive Effluent Release Report I Calendar Year - 2017 Attachment I I Part I: Joint Frequency Distribution Tables (500ft) Page 2 of 8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period All Hours I Period of Record Elevation:

                          =

Speed: SP500P 01 /01 /2017 01 :00- 12/31 /2017 23 :00 Direction: DI500P Lapse: DTS00-35 I Stability Class: B Delta Temperature Moderately Unstable Wind Speed (mph) I Wind Direction N 0.6-3.5 1 3.6-7.5 2 7.6-12.5 4 12.6-18.5 18.6-24.5 >24.6 Total 0 0 0 7 I NNE NE ENE 0 0 0 3 0 2 6 2 1 I 0 0 0 0 0 0 0 0 10 2 3 E 1 4 6 0 0 0 11 I ESE SE SSE 1 0 10 8 6 1 2 2 0 0 0 0 19 11 0 3 1 I 0 0 5 s I SSW SW 0 0 0 2 0 5 5 2 2 1 0 0 0 0 0 0 0 0 11 4 2 WSW 0 I 0 I 0 0 2 I WNW w NW 0 0 0 0 0 0 0 2 0 0 5 0 0 2 0 0 0 0 0 9 0 I NNW Total 0 3 41 I 40 2 1 14 0 2 0 0 100 4 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 6 0 Invalid Hours for: Total Period All Hours 19 I Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 100 8759 I

Beaver Valley Power Station - Units 1 & 2 RTLA9 .690E Enclosure 2, Attachment 1 (Part 3 of 3) I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Part 1: Joint Frequency Distribution Tables (500ft) Page 3 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction I Total Period All Hours Period of Record = Elevation: Speed: SP500P 01 /01 /2017 01 :00 - 12/31 /2017 23 :00 Direction: DI500P Lapse: DT500-35 I Stability Class: C Delta Temperature Slightly Unstable I Wind Speed (mph) Wind Direction 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total I N 0 7 10 5 0 0 22 NNE NE ENE 1 0 0 4 9 2 6 3 4 1 1 2 0 0 0 0 0 0 12 13 8 I E 0 5 13 1 1 0 20 ESE SE 0 1 8 6 6 2 1 3 0 0 0 0 15 12 I SSE 0 2 7 1 0 0 10 s SSW SW 0 0 0 5 3 1 13 13 5 1 1 1 0 0 0 0 0 0 19 17 7 I WSW 1 0 8 3 0 0 12 WNW w 1 0 3 5 14 15 6 19 0 10 0 3 24 52 I NW 1 1 15 I 2 1 21 NNW Total I 6 4 65 138 4 49 2 0 13 0 4 11 275 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 6 0 I Invalid Hours for: Total Period All Hours 19 Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 275 8759 I

RTL A9.690E

1 Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Attachment 1 (Part 3 of 3)

Annual Radioactive Effluent Release Report I Calendar Year - 2017 Attachment 1 II Part 1: Joint Frequency Distribution Tables (500ft) Page 4 of8 I Joint Frequency Distribution Hours at Each Wind Speed and Direction Total Period All Hours Period of Record = 01 /01 /201701 :00 - 12/31 /2017 23 :00 Elevation: Speed: SP500P Direction: DI500P Lapse: DT500-35 I Stability Class: D De lta Temperature Neutral Wind Speed (mph) I Wind Direction 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total N 19 48 94 23 3 0 187 I NNE NE ENE 24 5 13 16 33 36 45 18 57 22 1 19 1 0 1 0 0 0 89 65 137 E 23 70 83 21 3 0 200 I ESE SE 23 13 6 64 35 24 78 36 12 19 2 3 0 0 179 106 SSE 51 12 2 0 95 s I SSW SW 12 17 16 23 26 21 65 76 111 46 124 233 30 95 4 0 1 5 150 274 481 WSW 18 60 120 194 51 9 452 I WNW w NW 39 18 16 73 76 45 170 227 176 315 298 86 158 110 21 47 33 4 802 762 348 I NNW Total 16 278 54 704 126 1533 34 1459 488 4 0 99 234 4561 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 6 0 In valid Hours for: Total Period All Hours 19 I Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 4561 8759 I I I I

Beaver Valley Power Station - Units 1 & 2 RTL A9.690E Enclosure 2, Attachment 1 (Part 3 of 3) I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Part 1: Joint Frequency Distribution Tables (500ft) Page 5 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction I Total Period All Hours Period of Record Elevation:

                        =

Speed: SP500P 01 /01 /2017 01 :00 - 12/31 /2017 23:00 Direction: D1500P Lapse: DT500-35 I Stability Class: E Delta Temperature Slightly Stable I Wind Speed (mph) Wind Direction N 0.6-3.5 28 3.6-7.5 14 7.6-12.5 25 12.6-18.5 13 18.6-24.5 0

                                                                                                       >24.6 0

Total 80 I NNE NE ENE 22 37 44 24 45 59 21 10 38 8 4 10 0 0 0 0 0 0 75 96 151 I E 52 80 50 11 0 0 193 ESE SE SSE 38 33 20 97 64 36 66 46 30 12 15 21 0 4 4 0 0 0 213 162 111 I s SSW SW 21 25 39 40 28 35 45 54 70 47 65 114 4 36 59 0 6 3 157 214 320 I WSW 47 75 45 33 6 3 209 w WNW 53 32 101 75 82 58 36 12 4 2 I 1 277 180 I NW 27 29 17 14 3 0 90 NNW Total 22 540 18 820 32 689 420 5 0 122 0 14 77 2605 I Calm Hours not Included above for: Total Period All Hours 6 Variable Direction Hours for: Total Period All Hours 0 Invalid Hours for: Total Period All Hours 19 Number of Valid Hours for this Table: Total Period All Hours 2605 Total Hours for the Period: 8759 I I

RTL A9 .690E I Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Attachment 1 (Part 3 of 3) Annual Radioactive Effluent Release Report I Calendar Year - 2017 Attachment I I Part I: Joint Frequency Distribution Tables (500ft) Page 6 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period All Hours

                          =

I Period of Record Elevation : Speed: SP500P 01/01 /2017 01 :00 - 12/31 /2017 23 :00 Direction: Dl500P Lapse: DT500-35 I Stability Class: F De lta Temperature Moderately Stable Wind Speed (mph) I Wind Direction N 0.6-3.5 13 3.6-7.5 7 7.6-12.5 5 12.6-18.5 1 18.6-24.5 0

                                                                                                           >24.6 0

Total 26 NNE I NE ENE 13 19 33 12 17 29 11 8 1 0 0 2 0 0 0 0 0 0 33 37 75 E 31 47 7 0 0 0 85 I ESE SE SSE 29 31 18 58 27 33 27 10 10 2 2 8 0 0 0 0 0 1 116 70 70 s 10 28 I SSW SW 16 19 20 18 37 24 36 17 31 36 0 3 11 0 0 I 92 94 121 WSW 23 34 9 3 I 0 70 I WNW w NW 17 16 15 22 17 8 13 6 2 I 0 1 0 0 0 0 0 0 53 39 26 NNW 10 3 3 0 0 I Total 313 380 209 104 15 0 2 16 1023 I Calm Hours not Included above for: Variable Direction Hours for: Invalid Hours for: Total Total Total Period Period Period All All Hours Hours 6 0 All Hours 19 I Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 1023 8759 I I I I

Beaver Valley Power Station - Units 1 & 2 RTL A9.690E Enclosure 2, Attachment 1 (Part 3 of 3) I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Part 1: Joint Frequency Distribution Tables (500ft) Page 7 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period All Hours I Period of Record Elevation:

                        =

Speed: SP500P 01 /01 /2017 01 :00 - 12/31 /2017 23 :00 Direction: Dl500P Lapse: DTS00-35 I Stability Class: G Delta Temperature Extremely Stable I Wind Speed (mph) Wind Direction N 0.6-3.5 0 3.6-7.5 0 7.6-12.5 0 12.6-18.5 0 18.6-24.5 0

                                                                                                         >24.6 0

Total 0 I NNE NE ENE 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 I E 4 2 0 0 0 0 6 ESE SE SSE 3 2 4 4 6 7 0 0 1 0 0 0 0 0 0 0 0 0 12 9 6 I s SSW SW 6 1 0 4 5 3 16 4 8 9 5 16 1 0 3 0 0 0 37 14 30 I WSW 0 0 3 0 1 0 4 w WNW NW 1 2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 I 2 0 I NNW Total 23 0 32 0 32 0 0 30 0 5 0 0 122 0 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 6 0 I Invalid Hours for: Total Period All Hours 19 Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 122 8759 I I I I I

RTL A9.690E I Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Attachment 1 (Part 3 of 3) Annual Radioactive Effluent Release Report I Calendar Year - 2017 Attachment l I Part I: Joint Frequency Distribution Tables (500ft) Page 8 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period All Hours I Period of Record Elevation:

                          =

Speed: SP500P 01 /01 /2017 01 :00 - 12/31 /2017 23 :00 Direction: Dl500P Lapse: DT500-35 I Stability Class: ALL Delta Temperature Wind Speed (mph) Wind Direction 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total N 61 78 140 45 3 0 327 NNE 41 59 86 32 1 0 219 NE 69 104 34 8 0 0 215 ENE 101 129 115 34 I 0 380 E 111 211 164 33 4 0 523 I ESE SE SSE 94 80 48 247 145 106 189 105 103 29 43 43 2 7 6 0 0 1 561 380 307 s 49 I SSW SW 59 74 106 83 78 181 173 232 121 226 400 69 168 9 0 7 9 466 617 961 WSW 89 170 185 234 59 12 749 I w WNW NW 111 68 59 200 173 83 279 308 210 358 334 102 162 124 26 48 37 5 1158 1044 485 49 80 167 42 4 342 I NNW Total 1163 2052 2671 2084 645 0 119 8734 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 6 0 Invalid Hours for: Total Period All Hours 19 I Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 8734 8759 I I I I

I I I I I I I I I ENCLOSURE 2, ATTACHMENT 2 I I I I I I I I I I

I Beaver Valley Power Station - Units 1 & 2 RTL # A9 .690E Enclosure 2, Attachment 2 I Annual Radioactive Effluent Release Report Calendar Year - 2017 Attachment 2 I Unit 1 and 2 Offsite Dose Calculation Manual Changes Attachment 2 I Enclosed is a complete copy of the ODCM that includes: I Change (42) of the ODCM (Effective: January, 2018) Attachment 2 Clarification I A complete copy of the ODCM has been provided to the following offices: I United States Nuclear Regulatory Commission Attention : Document Control Desk Washington , DC 20555-0001 I United States Nuclear Regulatory Commission Regional Administrator 2100 Renaissance Blvd ., Suite 100 I King of Prussia, PA 19406-2713 For a complete copy of the ODCM , contact Rad iological Effluents Administrator at 724-682-4255. I I I I I I I I I I

I I I I I I I I I ENCLOSURE2,ATTACHMENT3 I I I I I I I I I I

RTL# A9 .690E Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Attachment 3 Annual Annual Radioactive Effluent Release Repor1 Calendar Year - 2017 Attachment 3 I Unit 1 and 2 Carbon-14 (C-14) Dose Estimates Carbon-14 Methodology I Gaseous doses from carbon-14 were calculated in accordance with EPRI and Regulatory Guide 1.109 methodology. Other considerations were made in the calculations ; daylight hours and growing season . Liquid effluent release doses are considered to be insignificant and are not included in this report . This report does I not address the amount of carbon-14 disposed of in shipments of solid waste and irradiated fuel. The term "other" discussed below refers to liver, total body, thyroid , kidney , lung and GI. Doses for these organs are assumed to be equal. I The receptor chosen was selected based upon the default ODCM receptor - NW 1432 meters (0.89 miles) . It is assumed that only vegetation and inhalation exposure pathways are available . The maximum bounding dose to a member of the public resulting from atmospheric C-14 releases from Unit 1 was I determined to be less than 2.50 mrem to the bone and less than 1.07 mrem to all other organs. The maximum bounding dose to a member of the public resulting from atmospheric C-14 releases from Unit 2 was I determined to be less than 2.46 mrem to the bone and less than 1.04 mrem to all other organs. I Exposure Pathway Infant Dose Calculations for Unit 1 Child Teen Adult Bone Other Bone Other Bone Other Bone Other I Inhalation Vegetation lnqestion 0.06 0.01 0.08 2.42 0.02 0.48 0 .06 1.00 0.01 0.20 0.04 0.62 0.01 0.12 TOTAL 0.06 0.01 2.50 0.50 1.07 0.21 0.66 0.13 I Dose Calculations for Unit 2 I Exposure Pathway Bone Infant Other Bone Child Other Bone Teen Other Bone Adult Other Inhalation 0.05 0.01 0.07 0 .01 0.05 0.01 0.03 0.01 I Vegetation lnqestion TOTAL 0.05 0.01 2.40 2.46 0.48 0.49 0.99 1.04 0.20 0.21 0.60 0.64 0.12 0.13 I Dose Calculations for Site Infant Child Teen Adult I TOTAL Bone I Other 0.11 I 0.02 Bone I Other 4.97 I 0.99 Bone I Other 2.11 I 0.42 Bone 1.30 I Other I 0.26 I I I I

I Beaver Valley Power Station - Units 1 & 2 RTL A9.690E Enclosure 3 I I 2017 Annual Radiological Environmental Operating Report I I I I FirstEnergy Nuclear Operating Company I FENOC Beaver Valley Power Station - Units 1 & 2 I Unit 1 License No. DPR-66 Unit 2 License No. NPF-73 I I I I I I I I I I

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I EXECUTIVE

SUMMARY

and INDEX Report Preparation and Submittal Requirements: The Beaver Valley Power Station (BVPS) I Annual Radiological Environmental Operating Report (AREOR) was prepared and submitted in accordance with the requirements contained in the following documents: I

  • BVPS Integrated Technical Specifications, Administrative Control 5.6.1 I
  • Offsite Dose Calculation Manual (ODCM) procedure l/2-0DC-3.03 , Attachment T, Control 6.9.2, "Controls for RETS and REMP Programs" BVPS procedure 1/2-ENV-01.05, "Compliance with Regulatory Guide 1.21 and Technical I

Specifications " BVPS procedure 1/2-ENV-02.01 , "Radiological Environmental Monitoring Program " I

  • NUREG-1301 , "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors, Generic Letter 89-01 , Supplement N o.1 , April I

1991 " BVPS Condition Report No. CR-2017-04551: REMP Air Station #27 found OOS I BVPS Condition Report No. CR-2017-04706: REMP TLD #94 Missing BVPS Condition Report No. CR-2017-08225 : REMP Air Station #30 found OOS I

  • BVPS Condition Report No. CR-2017-09446: REMP Drinking Water Station #4 found OOS I
  • BVPS Condition Report No. CR-2017-10809: REMP Milk Station #96 August Analysis
  • BVPS Condition Report No. CR-2017-12347 : REMP Air Station #13 found OOS I
  • SAP Notification 601078879: 2017 RETS/REMP Tracking for ARERR/AREOR I

I I I I I I 11 I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure3 EXECUTIVE

SUMMARY

and INDEX I Report Overview: I The AREOR provides a detailed summary of the BVPS Radiological Environmental Monitoring Program (REMP). During the report period, samples of air, water, shoreline sediment, milk, I fish, food crops, feed crops, vegetation, and direct radiation (in the vicinity of the BVPS site) have been measured, analyzed, evaluated, and summarized. During the report period, the BVPS radioactive effluent releases (as performed in accordance with the Radiological Effluent Technical Specification (RETS) program), did not exceed the limits identified in the BVPS Operating License, Technical Specifications and/or the Offsite Dose Calculation Manual (ODCM). The results of REMP verify that the effluent releases did not impact the environment with a measurable concentration of radioactive materials and/or levels of radiation that are higher than expected. I Description of Pre-operational REMP (1974 - 1975): I A pre-operational REMP was performed during the period 1974 through 1975. At that time, samples were collected and analyzed to determine the amount of radioactivity present in the I environment prior to BVPS operation. The resulting values are considered a "baseline" to which current sample analyses can be compared. A summary of the pre-operational data is summarized I in Table 2-3 of this report. Description of Operational REMP (1976 - Present}: I The operational REMP was initiated during calendar year 1976 and continued through the report I period. During the past forty (40) years, radiation and radioactivity in the environment was monitored within a 10-mile radius of the site. A description of the operational REMP is outlined in Table 2-1 of this report. In general, two (2) types of samples were collected and compared I during the report period, and are described as follows:

  • Control Samples: These samples are collected from areas that are beyond measurable I influence of BVPS operation, and are used as reference data. Normal background radiation levels, or radiation present due to causes other than BVPS operation, can thus be compared to I the environment surrounding the BVPS site. During the report period, three hundred four (304) analyses were performed on samples from the control locations. This includes eight (8) analyses were completed for thermoluminescent dosimeters (TLDs) at the control I locations. Results of the analyses from the control locations are summarized in Table 2-2 of this report.

I

  • Indicator Samples: Indicator samples are collected to determine the radiological impact of BVPS operation in the environment. These samples are collected from various locations near I

I lll

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I EXECUTIVE

SUMMARY

and INDEX the BVPS site. At a minimum, the samples are collected from areas where the BVPS I contribution would indicate the most significant radiological impact. During the report period, one thousand five hundred forty-nine (1,549) analyses were performed on samples I collected from eighty-seven (87) indicator locations. In addition, five hundred twenty (520) analyses were completed for TLDs at the indicator locations. Results of the analyses from the indicator locations are also summarized in Table 2-2 ohhis report. I

  • Comparisons: Current analysis results from the indicator samples were compared to both I current control sample values and the pre-operational baseline to determine if changes in radioactivity levels were attributable to BVPS operation.

I Determination of Environmental Impact I

  • 2017 Sample Media and Analyses: Results for drinking water, surface water, shoreline stream sediment, fish, cow milk, goat milk, feedstuff, foodcrops, air particulate and air radioiodine media remained consistent with previous data. Minor increases and decreases I

were noted in most sample media, and any positive results attributable to the BVPS operation were consistent with station data of authorized radioactive discharges, and were within limits I permitted by the operating license and the ODCM. Other radioactivity detected was attributable to naturally occurring radionuclides, previous nuclear weapons tests, other man-made sources, and to the normal statistical fluctuation for activities near the Lower Limit of I Detection (LLD).

  • Airborne Exposure Pathway: This ODCM required pathway was evaluated via sampling of I

airborne radioiodine and airborne particulates. The results during this report period were similar to previous years. There was no notable increase in natural products and no I detectable fission products or other radionuclides in the airborne particulate media during the year attributed to effluent releases from BVPS. I

  • Direct Exposure Pathway: This ODCM required pathway was evaluated via measurement of environmental radiation doses by use of Thermo Luminescent Dosimeters (TLDs). The I results of TLD processing have indicated a stable trend and compare well with previous years. I
  • Ingestion Exposure Pathway: This ODCM required pathway was evaluated via sampling of milk, fish, and foodcrops (leafy vegetables). I For milk samples, strontium-90 (attributable to past atmospheric weapons testing), was detected at levels similar to those of previous years. The gamma spectrometry analyses I

I lV I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

SUMMARY

and INDEX indicated positive results for naturally occurring potassium-40 at average environmental levels. The fish samples indicated below LLD levels in each of the sample analyses. Foodcrop (leafy vegetation) samples indicated naturally occurring potassium-40 at average environmental levels. I

  • Waterborne Exposure Pathway: This ODCM pathway was evaluated via samples of I drinking water, ground (well) water, surface (river) water and river sediment.

I Water samples were analyzed for tritium and gamma-emitting radionuclides. Tritium was not identified in any of these water samples. Iodine-131 analysis of drinking water indicated positive analyses, but the values were consistent with iodine-131 at the upstream surface I (river) water control location, and was not due to liquid effluent releases from BVPS. Sediment samples were collected from upstream of the site, at the discharge point of BVPS I liquid effluent releases, and downstream of the site. Analysis of samples indicated naturally occurring radionuclides potassium-40, thallium-208, bismuth-214, lead-212, lead-214, I radium-226, and actinium-228 in all results. The analyses also indicated cesium-137, but the values were consistent with cesium-137 at the control location, and most likely caused by previous nuclear weapons tests. Cobalt-58 and cobalt-60 were identified in some of the I samples that were obtained at the shorelines of the BVPS Main Outfall Facility. This is not unusual because the BVPS site discharges cobalt-58 and cobalt-60 in liquid waste effluents. I The activity detected at these sample locations is consistent with discharge data of authorized liquid effluent releases, and all liquid effluent releases during the report period did not exceed the release concentration limits set forth in the ODCM. I

  • Other Exposure Pathways: In addition to the samples collected from the exposure I pathways described above, other media (i.e., feedstuff) were also collected. Results were consistent with previous years, with no degrading trends.

I

  • Offsite Groundwater Monitoring (Historical): There were a total of four (4) offsite groundwater samples collected and analyzed for tritium and by gamma spectrometry. The samples were collected on a semi-annual basis from two (2) locations within four (4) miles of I the site. The locations included one ( 1) well in Hookstown, PA; and one (1) well in Georgetown, PA. No gamma-emitting radionuclides were detected in the analyses. All I tritium results were less than the pre-operational value.

I I V

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I EXECUTIVE

SUMMARY

and INDEX

  • Supplemental Sample Sites: REMP includes supplemental sampling sites in addition to the I

required sites set forth in the ODCM. The supplemental sites include three (3 ) air sampling sites, one (1) sediment site, one (1) milk animal feedstuff site, and five (5) soil sampling I sites.

  • Population Dose vs. Natural

Background:

During the report period, the total calculated 0-I 50 mile population dose was 61 man-mrem (liquid releases), and 39 man-mrem (gaseous releases). The average individual population dose from BVPS operation was less than <1 I mrem. Accordingly, the typical dose to an individual from background (natural radiation exposure including radon) was estimated as an average of 296 mrem per year according to the National Academy of Sciences 1990 BEIR Report. In 2009, the NCRP Report No. 160:

  "Ionizing Radiation Exposure of the Population of the United States," Journal of Radiological Protection J Radio/. Prat. 29.3 (2009) defined the radiation exposure population dose to be 620 mrem per year. The following graph in Figure i-1 illustrates that the average individual population dose was not affected from BVPS operation.

I:I I Figure i-1 Gra h of Annual Avera ulation Dose: BVPS Dose and Natural Back round Dose I 1000.00000 100.00000 I 10.00000 I 1.00000 eCl) D::

  §.

Cl) 0.10000 I Ill I 0 0 0.01000 0.00100 0.000 10

                       ~            -                     ---                                               .

I 0.00001

                                                                                                                                 ~                              I
                 ~ ~,,~ # ## ~ ~~~ #~ ~~ ~ ~~~ ~~
            ......., BVPS Average Populatlcn Dose (mRem )   rl atural Backg-ourd P~ulatlon Dose (296 mRem ) - Radiation Exposure Popula:1on Dose (620 mRem)

I I I Vl I

Beaver Valley Power Station RTL A9 .690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

SUMMARY

and INDEX I

  • Summary: During the report period, radioactive effluent releases from the BVPS site did I not exceed the limits identified in the BVPS Operating License, Technical Specifications and/or the ODCM. The BVPS operational REMP program was followed throughout the report period. The results demonstrate the adequacy of radioactive effluent control at BVPS, I and that BVPS operation did not adversely affect the surrounding environment. Positive results were attributable to BVPS operation and were consistent with station data of I authorized radioactive discharges within limits permitted by the NRC license and the ODCM. Other radioactivity detected was attributable to naturally occurring radionuclides, previous nuclear weapons tests, other man-made sources, and to the normal statistical I fluctuation for activities near the LLD.

Inter-laboratory Comparison Programs: I

  • Split Sample Program: BVPS shared split samples with the Pennsylvania Department of I Environmental Protection (P ADEP) in support of their nuclear power plant monitoring program. The shared media and number of locations were typically comprised of milk (2),

surface water (3), river sediment (1), fish (1), foodcrops (2), co-located air particulate/air I iodine (4), and TLD (24). The split sample program was coordinated by the state, and the results are not provided with this report. I

  • Spike Sample Program: Spiked samples were provided by an independent laboratory and then analyzed by the REMP contractor laboratory. The samples were provided throughout I the report period and included water samples, milk samples, filter paper samples and charcoal cartridge samples. All one hundred eight (108) analyses performed by the contactor I laboratory on the spiked samples met the NRC comparison criteria.

Special Reports: I

  • Since no reporting levels were exceeded during 2017, no Special Reports were required. A I Special Report shall be submitted to the NRC when (1) levels of radioactivity in an environmental sampling medium exceeds the limits specified in ODCM procedure l /2-0DC-3.03 , Attachment Q Table 3.12-2, and when (2) the results of the following calculation are I ~ 1.0 (for calculations performed when more than one radionuclide is detected in the sampling medium):

I Concentration (1) + Concentration (2) + ... ~ 1.0 Limit Level (1) Limit Level (2) I I I Vll

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I EXECUTIVE

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and INDEX Land Use Census Results: I Highlights from the most recent Land Use Census are documented in letter NPD3NRE: 1250, dated October 23 , 2017 and are summarized as follows: I

  • Nearest Residence (0 to 5 mile radius): The location has not changed since the previous I census. The nearest inhabited residence is 209 Ferry Hill Road, Shippingport, PA (0.4 miles, east).

I

  • Nearest Garden >500 sgft: The location has not changed since the previous census. The closest garden location is the Colaber Residence, 1201 Virginia Avenue, Midland, PA 11 (1.033 miles, northwest). The Cox Residence, 238 State Route 168, Hookstown, PA (0.760 miles, south-southwest) was available for sampling cabbage this year but does not meet all the requirements of NUREG-1301.

I

  • Nearest Dairy Cow (0 to 5 mile radius): The location has not changed since the previous census. The location remains at Brunton Dairy, 3681 Ridge Road, Aliquippa, I

PA (6.067 miles, southeast). 11

  • Nearest Doe Goat (0 to 5 mile radius): The location has not changed since the previous census. The closest location is the Covert Residence, 930 Pine Street (Route 168),

Hookstown, PA (2.131 miles, southwest). I

  • Prevailing Winds: The prevailing wind direction for ground releases was identified by I showing the highest deposition parameters (D/Q) in the east (E) sector. The prevailing wind direction for elevated releases was identified by showing the highest D/Q in the east-southeast (ESE) sector. The REMP properly monitors the environment with air I

particulate sampling stations in some sectors and direct radiation TLDs in all sectors. I

  • 2017 Dairy Cow & Doe Goat Sampling Locations: The dairy cow sampling locations have not changed in 2017. The locations remain at Brunton Dairy, 3681 Ridge Road, Aliquippa, PA (6.067 miles, southeast), and Windsheimer Dairy, 20 Windsheimer Lane, I

Burgettstown, PA (10.475 miles, south-southwest). The doe goat sampling location has not changed since the previous census and remains at the Covert Residence, 930 Pine I Street (Route 168), Hookstown, PA (2.131 miles, southwest).

  • D/0 for Milch Animal Locations: The 2017 milch animal sampling locations have not I

experienced a >20% increase in D/Q. Therefore, a Special Report per ODCM Control 3.12.2 Action "a" and/or Action "b" is not required. I I Vlll I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

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and INDEX I

  • D/0 for Offsite Dose Determination: There is no adverse effect on the current ODCM I methodology used for offsite dose determination from effluent releases. Specifically, the analysis of D/Q did not yield any valid locations where the offsite dose could have increased >20% of the offsite dose previously calculated using current ODCM I methodology. Therefore, a Special Report per ODCM Control 3.12.2 Action "a" and/or Action "b" is not required.

I

  • D/0 Historical Trend Comparison: There is no adverse trend in D/Q when comparing 2003 to 2017 data to the ODCM default D/Q values. This validates that there is no I adverse effect on the current ODCM methodology used for offsite dose determination from effluent releases. Specifically, the analysis of D/Q did not yield any valid locations where the offsite dose could have increased >20% of the offsite dose previously I calculated using current ODCM methodology. Therefore, a change in ODCM Receptor location and/or a change to meteorology at the current ODCM Receptor location is not I required.

The 2017 Land Use Census results indicate that no significant changes are required in the current I Radiological Environmental Monitoring Program or to its methodology. I Deviations, Changes and Adjustments to the Normal Sampling Program

  • Deviation from Normal Milk Sampling & Analysis Schedule: There were two deviations I from the required milk sampling and analysis schedule occurred for the reporting period.

Sufficient milk samples were not available from locations within the 5 mile radius in 2017. I The unavailability of milk caused the REMP to not meet the ODCM sample requirements in l/2-0DC-2.03 and in l/2-0DC-3.03 , Attachment Q Table 3.12-1 stating that a minimum of four (4) milk locations shall be sampled. This initiated the ODCM requirement for sampling I two (2) additional garden locations based upon the highest predicted annual average D/Q when milk locations are not available. The other issue was documented through internal notification because it regarded a supplemental sample. I

  • Deviation from Normal Surface and Drinking Water Sampling and Analysis Schedule:

I There was one deviation from the ODCM required water sampling and analysis schedule during the report. The one issue was documented in Condition Report 2017-09446. I I I I lX

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I EXECUTIVE

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  • Deviation from Normal Air Particulate & Iodine Sampling and Analysis Schedule:

I There were three deviations from the required airborne particulate sampling and analysis schedule during the report period. These issues were documented in Condition Report 2017- I 04551 and 2017-08225.

  • Deviation from Normal Direct Radiation Monitoring: There was one deviation from the I

required direct radiation monitoring schedule during the report period. This issue was documented in Condition Report 2017-04706 I

  • Deviations from Previous Sampling and Analysis Schedule: Beginning in 2017, the REMP was modified to exclude non-required samples and analyses. These changes are I

documented in the REMP procedure. Two (2) Air Particulate and Radioiodine sampling points; Sherman Farm in Brighton I Township (Site No. 28, 8.6 miles N) and Friendship Ridge in Beaver (Site No. 29B 7.97 miles NE). I Two (2) Groundwater sampling points; Hookstown Borough (Site No. 14A, 2.61 miles SW) and Georgetown Borough (Site No. 15B, 3.75 miles WNW). I One (1) Sediment sample point; Upstream of New Cumberland Darn (Site No. 50, 11.77 1, miles WSW). I Three (3) Precipitation sample points; Cook's Ferry Substation in Shippingport (Site No. 30, 0.5 miles ENE), East Liverpool Water Department (Site No. 47, 4.88 miles WNW), I and Weirton Water Tower (Site No. 48, 16.4 miles SSW). I Five (5) Soil sample points; Old Meyer Farm in Hookstown (Site No. 13A, 1.49 miles SW), South of BVPS perimeter (Site No. 22, 0.28 miles SSE), Brunton Farm (Site No. 27, 6.16 miles SE), Nicol Farm in Beaver (Site No. 29A, 8.09 miles NE) and East I Liverpool Water Department (Site No. 47, 4.88 miles WNW). The analysis schedule of I-131 for both drinking and surface was changed from weekly to I biweekly. I I I I X I

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

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and INDEX I EXECUTIVE

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II I Report Preparation and Submittal Requirements........ .... ... .................... ... ...... .. .................. Report Overview ....................... ....................................... .................................................. u 111 11 Description of Pre-operational REMP (1974 - 1975) ....... ... ....... ....................................... Description of Operational REMP (1976 - Present) ...................... ... ............ .. ... .. ........... .. m m Determination of Environmental Impact............ ... ................. .. ... ............ ................. .. .... .... 1v Inter-laboratory Comparison Programs ......... ..... .. ............. ... ...... .... ... ........ ...... ............... ... . vu I Special Reports. .......................... .. ... ........... ........ ............................ ......... .. ......................... Land Use Census Results... ..................................... ...... .. ........... ........ ....... .......................... vu vu Deviations, Changes and Adjustments to the Normal Sampling Program ........................ 1x I SECTION 1 - INTRODUCTION I A. B. Radiation Fundamentals.......... .................................................................................... Radiation and Radioactivity ..................... ............. ......................... ... ................. ... ..... 1-1 1-1 C. Units of Measurement ........... .............. ........ ... .. ........... .... .............. ..... .... ................ .... 1-5 I D. E. Lower Limit of Detection......................... ....... .. ..... ... ......... ....................................... . Scope and Objectives of the REMP Program.. ................................ ............ .......... ... .. 1-6 1-6 F. Description of the Beaver Valley Site ................. ....... ................................................ 1-6 11 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM A. Radiological Environmental Monitoring Program..................... ... ... ... ........... ...... .. ... 2-1 I 1. Program Description .. .............. ............... ............................... .................. ..........

2. Summary of Results.... .... ............. ... .. .......................................... .......................

2-1 2-5

3. Quality Control Program. ........ ... ........................................... ........... ................ .. 2-5 I B.
4. Program Changes.................................. ........... ... ....... ...................... ........... ... ....

Air Monitoring. ... ... ... ........ ... ............ .... ...... ... .................................. ... .. .................. .... 2-5 2-23

1. Characterization of Air and Meteorology .. .. ..... ................................................. 2-23 I 2. Air Sampling Program and Analytical Techniques .................. ... ......................
3. Results and Conclusions. .. ...................................................... .. ....... ..................

2-23 2-24 C. Monitoring of Shoreline Stream Sediment and Soil... ........... .................................... 2-28 I 1. Characterization of Shoreline Stream Sediment and Soil. .. .... ... ...... ... ...............

2. Sampling Program and Analytical Techniques........................ ..........................

2-28 2-28

3. Results and Conclusions ............ ..................................... ................................... 2-29 I D. Monitoring ofFeedstuff and Foodcrops..... ..................... .... .. .. ..................................
1. Characterization of Farm Products....... ..............................................................

2-34 2-34

2. Sampling Program and Analytical Techniques........ ................... ....................... 2-35 I E.
3. Results and Conclusions.. ........ ... .......................................................................

Monitoring of Local Cow and Goat Milk.. ..... ......... .......................... .... .. ........... ....... 2-36 2-39 I 1. Description - Milch Animal Locations .............. ................................................

2. Sampling Program and Analytical Techniques ........... :........... ................... ........
3. Results and Conclusions .......... ....................... .................. .................................

2-39 2-39 2-41 I F. Environmental Radiation Monitoring..................... .. .................................................

1. Description of Regional Background Radiation and Sources.. ... ... .............. ......

2-45 2-45

2. Locations and Analytical Procedures.. ......... .................... ...... .. .............. .. ... .... ... 2-45 I 3. Results and Conclusions .................................................................................... 2-46 I XI

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I EXECUTIVE

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and INDEX G. Monitoring of Fish. .... ..................................... ................................................. .......... 2-50 I

1. Description ............ ... ....................................... ............................................... ....
2. Sampling Program and Analytical Techniques.................... ......... .. ............. .. ....
3. Results and Conclusions .. .............. ... ......................... .. ....... ............. .. ............... .

2-50 2-50 2-50 I H. Monitoring of Surface Water, Drinking Water, Groundwater and Precipitation..... .

1. Description of Water Sources ...................................................................... ......
2. Sampling and Analytical Techniques.. .. ................ .. .. .......... ............................. ..

2-53 2-53 2-53 I

3. Results and Conclusions......... .............................................................. ......... ....

I. Estimates of Radiation Dose to Man ........................................................... ........ ... ... 2-56 2-61 I

1. Pathways to Man - Calculational Models... ....................................... ............ .... 2-61
2. Results of Calculated Population Dose to Man - Liquid Effluent Releases......
3. Results of Calculated Population Dose to Man - Gaseous Effluent Releases ...

2-61 2-62 I

4. Conclusions.. .. ... .. .... ..................................................................................... ...... 2-62 SECTION 3 - LAND USE CENSUS I A.

B. C. Land Use Census Overview .................. ........ .. .. .......... .. .......... .... ......... .. .. ............. .... Nearest Residence.............. .............. ......... ....................... ........ ... .... .. .. ... ... ................. Nearest Garden >500 sqft ... .. ....... .. .......... ... ...................... .. ... ....... ....... ........... .......... 3-1 3-1 3-1 I D. E. F. Nearest Dairy Cow. .. .. ....... ..................................................... ........ ................. ........ .. Nearest Doe Goat............................................................................................... ........ Projection for 2017 Dairy Cow Sampling Locations..... ......................... .. .............. .. 3-1 3-1 3-2 I G. H. Projection for 2017 Doe Goat Sampling Locations........ ......................................... .. D/Q for Milch Animal Locations ... .. .................. ..... ....... ......... ...... ......... ................... I. D/Q for Offsite Dose Determination. .......... ......................... .. .... ............... .. .............. 3-2 3-2 3-2 I J. D/Q Historical Comparison........ ... ........................ .. .. .. .. ... ........ .......... ....................... SECTION 4 - SPLIT SAMPLE PROGRAM AND SPIKE SAMPLE INTER-3-2 I LABORATORY COMPARISON PROGRAM A. Split Sample Program (Inter-Laboratory Comparison, Part 1 of 2) .......................... 4-1 I

                       ~.~~~~~~.?~~~~~.~~~.~.~~~~~.~~:~~~~~~~~.~~~.~.~~.~~::::: : ::: ::::::::::::::: ::;                                       I 1
   ~:   ~i::i:s~:Js ~..

SECTION 5 - CORRECTIONS TO PREVIOUS RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT(S) I A. Corrections to Previous Radiological Environmental Operating Report( s) .. ............ 5-1 I I I I Xll I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

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and INDEX I AREOR TABLES I Table 2-1 Operational Radiological Environmental Monitoring Program ............................. .. 2-2 Table 2-2 Radiological Environmental Monitoring Program Summary ................................. . 2-6 I Table 2-3 Pre-Operational Environmental Radiological Monitoring Program Summary .... ... 2-20 Table 2-4 Local Cow and Goat Locations 2-40 I Table 2-5 Table 2-6 Calculated Population Dose to Man - Liquid Effluent Releases ........................ ..... Calculated Population Dose to Man - Gaseous Effluent Releases............. ............. 2-63 2-63 I Table 2-7 Natural and Medical Radiation Exposures.. ... ... .. ... .................................................. Table 3-1 Location ofNearest Residences, Gardens, Dairy Cows, Doe Goats......... ......... ..... 2-64 3-3 Table 4-1 Inter-Laboratory Comparison Program, Spiked Samples - pt Quarter.. .................. 4-4 I Table 4-2 Inter-Laboratory Comparison Program, Spiked Samples - 2nd Quarter. .... .... .......... 4-5 Table 4-3 Inter-Laboratory Comparison Program, Spiked Samples - 3rd Quarter. .... .............. 4-6 I Table 4-4 Inter-Laboratory Comparison Program, Spiked Samples - 4th Quarter ................... 4-7 I I I I I I I I I I I Xlll

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I EXECUTIVE

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and INDEX AREOR FIGURES I Figure i-1 Graph of Annual Average Population Dose: BVPS Dose and Natural Background Dose .......... .......................... .................................................................. v1 I Figure 1-1 Geographical Map and Principal Communities in 50-mile Radius of the Beaver Valley Power Station............................ .. .............................. ..................................... 1-8 I Figure 2-1 Environmental Monitoring Locations - Air Sampling Stations.......... .............. .. .... ... 2-26 Figure 2-2 Figure 2-3 Graph of Annual Average Concentration: Gross Beta in Air Particulates ........ .... .... 2-27 Environmental Monitoring Locations - Shoreline Sediments and Soil .. .......... ........ . 2-31 I Figure 2-4 Figure 2-5 Graph of Annual Average Concentration: Cesium-137, Cobalt-58 & 60 in Sediment ... .. .... ........... ...... ......... ..... .. ........................................................................ .. 2-32 Graph of Annual Average Concentration: Cesium-137 in Soil.. ............................ .. . 2-33 I Figure 2-6 Figure 2-7 Environmental Monitoring Locations - Feedstuff and Foodcrops .. ......... .. ............... 2-37 Graph of Annual Average Concentration: Cesium-13 7 in F eedstuff and I Foodcrops ..... ........................ ................. ..................................................... ........... ... . 2-38 Figure 2-8 Environmental Monitoring Locations - Milk...................... ................ .. ...... .............. 2-43 I Figure 2-9 Graph of Annual Average Concentration: Iodine-131 & Sr-90 in Milk ........ .. .. .... .. . 2-44 Figure 2-10 Figure 2-11 Environmental Monitoring Locations - TLDs .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. 2-4 7 Graph of Annual Average Exposure: Direct Radiation in Environment.................. . 2-49 I Figure 2-12 Environmental Monitoring Locations - Fish........... ....................... ........................ ... 2-51 Figure 2-13 Graph of Annual Average Concentration: Cesium-137 in Fish .... ...... .... .................. 2-52 I Figure 2-14 Environmental Monitoring Locations - Surface Water and Drinking Water ........ .. .. 2_58 Figure 2-15 Graph of Annual Average Concentration: Iodine-131 in Surface Water, and Drinking Water .... ...... .... ...... ................ ... ... ....... .... ....... .. ... ..... .. .... ... .......... ... .. ...... ...... 2-59 I Figure 2-16 Graph of Annual Average Concentration: Tritium in Surface Water .. .... .. ............... 2-59 Figure 2-17 Graph of Annual Average Concentration: Tritium in Drinking Water ........ .. .. .. ....... 2-60 I Figure 2-18 Graph of Annual Average Concentration: Tritium in Groundwater .. .. .............. ...... . 2-60 I I I I I I XIV I

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 1 - INTRODUCTION A. Radiation Fundamentals I Radiation is the conveyance of energy through space. For example, heat emanating from a stove is a form of radiation, as are light rays, microwaves, and radio waves. All matter I consists of atoms, which are comprised of positively charged particles (protons), negatively charged particles (electrons), and non-charged/neutral particles (neutrons). The relatively I large particles (protons and neutrons) are packed tightly together in a cluster at the center of the atom called the nucleus, while the smaller particles (electrons) orbit around the nucleus. In an electrically neutral atom, the negative charges of the electrons are balanced by the I positive charges of the protons. Due to their dissimilar charges, the protons and electrons have a strong attraction for each other. This holds the atom together. Other attractive forces I between the protons and neutrons keep the densely packed protons from repelling each other, and prevent the nucleus from breaking apart. I B. Radiation and Radioactivity The following provides an alphabetical glossary of terms associated with radiation, I radioactivity, and the radioactive decay process. The terms discussed include alpha particles, beta particles, gamma rays, genetic effects, half-life, ionization, isotopes, neutrons, radiation, I radioactive decay, radionuclides and somatic effects. Alpha Particles: Particulate and electromagnetic radiation each travel through matter I differently because of their different properties. Alpha particles contain 2 protons and 2 neutrons, are relatively large, and carry an electrical charge of +2. Alpha particles are I ejected from the nucleus of a radioactive atom at speeds ranging from 2,000 to 20,000 miles per second. However, due to its comparatively large size, an alpha particle usually does not travel very far before it loses most of its energy through collisions and interactions with other I atoms. As a result, a sheet of paper or a few centimeters of air can easily stop alpha particles. Beta Particles: Beta particles are very small, and comparatively fast particles, traveling at speeds near the speed of light (186,000 miles per second). Beta particles have an electrical charge of either + 1 or -1. Because they are so small and have a low charge, they do not I collide and interact as often as alpha particles, so they can travel farther. Beta particles can usually travel through several meters in air, but may be stopped by a thin piece of metal or I wood. I I I 1- 1

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 1 - INTRODUCTION Gamma Rays: Gamma rays are pure energy and travel at the speed of light. They have no measurable charge or mass and generally travel much farther than alpha or beta particles before being absorbed. After repeated interactions, the gamma ray loses its energy and vanishes. The range of a gamma ray in air varies, depending on the ray's energy and interactions. Very high-energy gamma radiation can travel a considerable distance, where as I low energy gamma radiation may travel only a few feet in air. Lead is used as shielding material for gamma radiation because of its density. Several inches of lead or concrete may be needed to effectively shield gamma rays. I Genetic Effects: The effects of ionizing radiation which are observed in the offspring of the I exposed individual that could occur as a result of ionizing radiation interacting with the genes in the human cells. I Half-life: The length of time an atom remains radioactive is defined in terms of half-life, which is the amount of time required for a radioactive substance to lose half of its activity I through the process of radioactive decay. Radionuclides that have infrequent emissions have a long half-life, where as, radionuclides that have more frequent emissions have a short half-life. I Ionization: Through interactions with atoms, alpha, beta, and gamma radiation lose their I energy. When these forms of radiation interact with any form of material, the energy they impart may cause atoms in that material to become ions, or charged particles. Normally, an atom has the same number of protons as electrons, thus, the number of positive and negative I charges cancel, in which the atom is electrically neutral. When one or more electrons are removed, an ion is formed. Ionization is one of the processes that may result in damage to I biological systems. Isotopes: A group of identical atoms containing the same number of protons make up an I element. In fact, the number of protons an atom contains determines its chemical identity. For instance, all atoms with one proton are hydrogen atoms, and all atoms with eight protons are oxygen atoms. However, the number of neutrons in the nucleus of an element may vary. I Atoms with the same number of protons but different numbers of neutrons are called isotopes. Different isotopes of the same element have the same chemical properties, and I many are stable or non-radioactive. An unstable or radioactive isotope of an element is called a radioisotope, a radioactive atom, or a radionuclide. Radionuclides usually contain an excess amount of energy in the nucleus. The excess energy is usually due to a surplus or I deficit in the number of neutrons in the nucleus. Radionuclides such as uranium-238, beryllium-7 and potassium-40 occur naturally. Others are man-made, such as iodine-131 , I cesium-137, and cobalt-60. I 1-2 I

I Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 1 - INTRODUCTION I Neutrons: Neutrons come from several sources, including the interactions of cosmic radiation with the earth's atmosphere and nuclear reactions within operating nuclear power reactors. However, neutrons are not of environmental concern since the neutron source at nuclear power stations is sealed within the containment building. Because neutrons have no charge, they are able to pass very close to the nuclei of the material through which they are I traveling. As a result, neutrons may be captured by one of these nuclei or they may be deflected. When deflected, the neutron loses some of its energy. After a series of these I deflections, the neutron has lost most of its energy. At this point, the neutron moves about as slow as the atoms of the material through which it is traveling, and is called a thermal neutron. In comparison, fast neutrons are much more energetic than thermal neutrons and have greater potential for causing damage to the material through which they travel. Fast neutrons can have from 200 thousand to 200 million times the energy of thermal neutrons. I Neutron shielding is designed to slow fast neutrons and absorb thermal neutrons. Neutron shielding materials commonly used to slow neutrons down are water or polyethylene. The shield is then completed with a material such as cadmium, to absorb the now thermal I neutrons. Concrete is also used to form an effective neutron shield because it contains water molecules and can be easily molded around odd shapes. I Radiation: This is the conveyance of energy through space. For instance, heat emanating from a stove is a form of radiation, as are light rays, microwaves, and radio waves. Ionizing I radiation is another type of radiation and has similar properties to those of the examples listed above. Ionizing radiation consists of both electromagnetic radiation and particulate I radiation. Electromagnetic radiation is energy with no measurable mass that travels with a wave-like motion through space. Included in this category are gamma rays and x-rays. Particulate radiation consists of tiny, fast moving particles which, if unhindered, travel in a I straight line through space. The three types of particulate radiation of concern to us are alpha particles, which are made up of 2 protons and 2 neutrons; beta particles, which are essentially free electrons; and neutrons. The properties of these types of radiation will be described more fully in the Range and Shielding section. I I 1-3

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 1 - INTRODUCTION I Radioactive Decay: Radioactive atoms, over time, will reach a stable, non-radioactive state through a process known as radioactive decay, which is the release of energy from an atom I through the emission of ionizing radiation. Radioactive atoms may decay directly to a stable state or may go through a series of decay stages, called a radioactive decay series, and produce several daughter products that eventually result in a stable atom. The loss of I energy through radioactive decay may transform the atom into a chemically different element. For example, when uranium-238 decays, it emits an alpha particle and, as a result, I the atom loses 2 protons and 2 neutrons. Since the number of protons in the nucleus of an atom determines its chemical identity, then when the uranium-238 atom loses the 2 protons and 2 neutrons, it is transformed into an atom of thorium-234. Thorium-234 is one of the 14 I successive daughter products of uranium-238. Radon is another daughter product, and the decay series ends with stable lead-206. The following example is part of a known I radioactive decay series, called the uranium series, which begins with uranium-238 and ends with lead-206. The information provided in the upper portion of each block is the isotope name, while the information provided in the lower portion of each block is the half-life. I 238U 234 LJ I 4.5E+9Yr 2 .SE+S Yr 234pa 1.2 min  ! I 234Th 24 d 230Th 8.0E+4 Yr I

                                      !                                    Beta Decay 22sRa 1600 Yr Alpha Decay I
                                      !                                                                I 222Rn 3.82 d I

218p 0 3.05 mi n .J( 214p0 1.6E-4 s .A 21op 0 138.4 d I

                                                          /                            /

214pb

                                          /

I.,.# 214Bi 19.7min 210pb

                                                                         /
                                                                           ~

210Bi 5.01 d  ! 206pb I 26 .8 min Radionuclides: See description for "isotopes". 23 Yr stable I I 1-4 I

I Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 1 - INTRODUCTION I Somatic Effects: The effects of ionizing radiation develop in the directly exposed individual, including an unborn child. Somatic effects can be divided further into acute and chronic effects. Acute effects develop shortly after exposure to large amount of radiation. Chronic I effects are a result of exposure to radiation over an extended period of time. I C. Units of Measurement Activity (Curie): This relates the number of atoms in a sample that disintegrate (decay) per I unit of time. Each time an atom disintegrates, radiation is emitted. The curie (Ci) is the unit used to describe the activity of a material and indicates the rate at which the atoms of a I radioactive substance are decaying. One curie indicates the disintegration of 37 billion atoms per second. A curie is a unit of activity, not a quantity of material. Thus, the amount of material required to produce one curie varies. A smaller unit of the curie is used when I discussing the low concentrations of radioactivity detected in environmental samples. For instance, the picocurie (pCi) represents one trillionth of a curie. I Absorbed Dose (rad): This is a term used to describe the radiation energy absorbed by any material exposed to ionizing radiation, and can be used for both particulate and I electromagnetic radiation. The rad is the unit used to measure the absorbed dose. It is defined as the energy of ionizing radiation deposited per gram of absorbing material ( 1 rad = I 100 erg/g). The rate of absorbed dose is usually given in rad/hr. The rad is not used to quantify biological damage caused by ionizing radiation. I Dose Equivalent (rem): Biological damage due to alpha, beta, gamma and neutron radiation may result from ionizing radiation. Some types of radiation, especially alpha particles, cause I dense local ionization and can result in up to 20 times the amount of biological damage for the same energy imparted as do gamma or x-rays. Therefore, a quality factor must be applied to account for the different ionizing capabilities of various types of ionizing I radiation. When the quality factor is multiplied by the absorbed dose (rad) the result is the dose equivalent. Dose equivalent is an estimate of the possible biological damage resulting I from exposure to a particular type of ionizing radiation and is measured in rem. An example of this conversion from absorbed dose (rad) to dose equivalent (rem) uses the quality factor for alpha radiation, which is equal to 20. Thus, 1 rad of alpha radiation is equal to 20 rem. I Since beta and gamma radiation each have a quality factor of 1, then 1 rad of either beta or gamma radiation is equal to 1 rem. Neutrons have a quality factor ranging from 2 to 10. In I terms of radiation, the rem is a relatively large unit. Therefore, a smaller unit known as the rnillirem, is often used and one millirem (mrem) is equal to 1/1000 of a rem. I I 1-5

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 1 - INTRODUCTION I D. Lower Limit of Detection I The Lower Limit of Detection (LLD) for environmental samples is a calculated value that represents an a-priori (before-the-fact) limit for the smallest concentration (i.e. ; pCi per unit mass or volume) of radioactive material in a sample that will be detected with 95% I probability, and with 5% probability of falsely concluding that a blank observation represents a real signal. A calculated LLD must consider analytical variables such as standard deviation I of the background counting rate, counting efficiency, sample size, fractional radiochemical yield, radioactive decay constant, and elapsed time between sample collection and time of counting. I E. Scope and Objectives of REMP I The environmental program consists of environmental monitoring for radioactivity in the vicinity of BVPS. Environmental sampling and analyses include air, water, milk, vegetation, I river sediments, fish, and ambient radiation levels in areas surrounding the site. The results of these media are assessed to determine impacts of the plant operation on the environment. I The AREOR for BVPS summarizes REMP conducted by the FirstEnergy Nuclear Operating Company during the report period. I F. Description of the Beaver Valley Site I BVPS is located on the south bank of the Ohio River in the Borough of Shippingport, Beaver County, Pennsylvania, on a 453 acre tract of land. The site is approximately one mile from Midland, Pennsylvania, five miles from East Liverpool, Ohio, and twenty-five miles from I Pittsburgh, Pennsylvania. Figure 1-1 shows the site location in relation to the principal population centers. Population density in the immediate vicinity of the site is relatively low. I The population within a five mile radius of the plant is approximately 15,000. The only area within the radius of concentrated population is the Borough of Midland, Pennsylvania, with a population of approximately 2,539 as determined from the 2016 U.S. Census. I The site lies in a valley along the Ohio River. It extends from the river ( elevation 665 feet I above sea level) to a ridge along the border south of the Beaver Valley Power Station at a maximum elevation of 1160 feet. Plant grade level is approximately 735 feet above sea level. I BVPS is on the Ohio River at river mile 34.8, a location on the New Cumberland Pool that is I 3 .1 river miles downstream from Montgomery Lock and Dam, and 19 .6 miles upstream from I 1-6 I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 1 - INTRODUCTION I New Cumberland Lock and Dam. The Pennsylvania-Ohio-West Virginia border is located 5.2 river miles downstream from the site. The river flow is regulated by a series of dams and reservoirs on the Beaver, Allegheny, Monongahela and Ohio Rivers and their tributaries. I During the report period, the Ohio River flow (as obtained from the Corps of Engineers - Water Resources Engineering) at the New Cumberland Dam ranged from 6,904 cubic feet I per second (minimum monthly average) to 204,852 cubic feet per second (maximum monthly average). The mean flow during the report period was approximately 49,837 cubic feet per second. Water temperature of the Ohio River typically varies from 33° Fahrenheit to I 80° Fahrenheit. The minimum temperatures occur in January and/or February and maximum temperatures in July and/or August. Water quality in the Ohio River at the site location is I affected primarily by the water quality of the Allegheny, Monongahela and Beaver rivers. The climate of the area may be classified as humid continental. The predominant wind I direction is typically from the southwest in summer and from the west in winter. The National Climatic Data Center indicates the following data for the Beaver Falls, PA area: I The total annual precipitation during the report period was 37.20 inches. The average mean temperature during the report period was 60.8° Fahrenheit. I The basic features of the Beaver Valley Power Station Units 1 and 2 are tabulated below: Beaver Valley Unit 1 Beaver Valley Unit 2 I Licensed Power Level 2900 - megawatts thermal 2900 - megawatts thermal Type of Power PWR PWR I No. of Reactor Coolant Loops No. of Steam Generators & Type 3 3 - Vertical 3 3 - Vertical I Steam Used by Main Turbine Saturated Saturated The BVPS units utilize two separate systems (primary and secondary) for transferring heat I from the source (the reactor) to the receiving component (turbine-generator). Because the two systems are isolated from each other, primary and secondary waters do not mix, and I radioactivity in the primary system water is normally isolated from the secondary system. Reactor coolant in the primary system is pumped through the reactor core and steam generators by means of reactor coolant pumps. Heat is transferred from the primary system I to the secondary system in the steam generators. The steam is then formed and delivered to the main unit turbine, which drives the electrical generator. The steam is condensed after I passing through the turbine, and returned to the steam generators to begin another steam/water cycle. I I 1-7

Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 1 - INTRODUCTION I Geographical Map and Principal Communities Figure 1-1 I in 50-mile Radius of the Beaver Valley Power Station I Ii

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Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM A. Radiological Environmental Monitoring Program I 1. Program Description I The program consists of monitoring water, air, soil, river bottoms (sediment), feedstuff, vegetation, foodcrops, cow's milk, ambient radiation levels in areas surrounding the site, and aquatic life as summarized in Table 2-1 . Further description of each portion of the I program (Sampling Methods, Sample Analysis, Discussion and Results) are included in Sections 2-B through 2-1 of this report. I 2-B - Air Monitoring I 2-C - Monitoring of Shoreline Stream Sediment and Soil I 2-D - Monitoring of Feedstuff and Foodcrops 2-E - Monitoring of Local Cow and Goat Milk 2-F - Environmental Radiation Monitoring 2-G - Monitoring of Fish 2-H - Monitoring of Surface Water, Drinking Water, Groundwater and Precipitation I 2 Estimates of Radiation Dose to Man I I I I 2-1

Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-1 I Sample 0 1perattona IRad.10 IO!!IC3 IE nv1ronmenta IMomtormg p rogram Sample Sample Sample I Section Site Sample Location Preparation / Analysis Type Frequency 1 Air Particulate & No. 13 27 Hookstown , PA (Old Meyer Farm) Aliquippa , PA (Brunton Farm) Continuous Sampling Analysis Frequency Weekly - Air Particulate Gross Beta <*> I Radionuclide 30 Shippingport, PA (Cook's Ferry Substation) with Sample lodine-131 32 46 .1 47 48 (a) Midland , PA (North Substation) Industry, PA (McKeel's Service - Rt. 68) East Liverpool , OH (Water Department) Collection at least weekly Weekly - Charcoal Quarterly Composite (c) Gamma Scan I Weirton , VW (Water Tower - Collier Way) 2 Direct Radiation 51 7-8 10 13 Aliouiooa , PA /Sheffield Substation) BVPS Site Perimeter Locations Shippingport, PA (Post Office) Hookstown, PA (Old Meyer Farm) Continuous (TLD) Quarterly<'> Gamma Dose I 14 Hookstown , PA 15 27 28 Georgetown , PA (Post Office) Aliquippa , PA (Brunton Farm) Sherman Farm I 298 Beaver, PA (Friendship Ridge) 30 32 33-44 Shippingport, PA (Cook's Ferry Substation) Midland, PA (North Substation) BVPS Site Perimeter Locations I 45 Raccoon Township , PA (Christian House Baptist I Chapel - Rt. 18) 45 .1 Raccoon Township , PA (Kennedy's Corner) 46 Industry, PA (Midway Drive) 46.1 Industry, PA (McKeel's Service - Rt. 68) 47 East Liverpool, OH (Water Department) 48 (a) 51 52-56 Weirton , VW (Water Tower - Collier Way) Aliquippa , PA (Sheffield Substation) BVPS Site Perimeter Locations I 59 236 Green Hill Road , Aliquippa , PA 60 70 71 72 444 Hill Road , Georgetown , PA 236 Engle Road, Industry, PA Brighton Township , PA (First Western Bank) Ohioview, PA (Lutheran Church - Rear) I 73 74 75 76 618 Squirrel Run Road , Industry, PA 37 Poplar Avenue, Monaca, PA (CCBC) 117 Holt Road , Aliquippa , PA Raccoon Township, PA (Elementary School) I 77 3614 Green Garden Road, Aliquippa , PA 78 79 80 Raccoon Township, PA (Municipal Building) 106 Rt. 151 , Aliquippa, PA Raccoon Township, PA (Park Office -Rt. 18) I Millcreek United Presbyterian , Church 81 82 83 84 Hookstown , PA 2697 Rt . 18, Raccoon Twp, PA 735 Mill Creek Road , Hookstown, PA Hancock County, VW (Senior Center) I I 85 2048 Rt. 30 , West Chester, VW 86 1090 Ohio Avenue , East Liverpool , OH 87 50103 Calcutta Smith Ferry Road, Calcutta , OH 88A Route 168, Midland Heights, PA 89 488 Smith Ferry Road , Ohioville , PA 90 91 92 6286 Tuscarawras Road , Midland, PA Pine Grove Road & Doyle Road , Industry, PA Georgetown , PA (Georgetown Road Substation) I 93 104 Linden , Midland, PA (Sunrise Hills) 94 95 111-112 Hookstown, PA (McCleary & Pole Cat Hollow Roads) 832 McCleary Road , Hookstown , PA) BVPS Site Perimeter Locations I' I 2-2 I

Beaver Valley Power Station RTL A9.690E 201 7 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-1 (Continued) 0 iperatlona IRad'10 I021ca IE nv1ronmenta IMomtorm p roe;ram Sample I Sample Sample Preparation I Section Site Sample Location Sample Frequency Analysis Type Analysis Frequency No. I Biweekly Sample lodine-131 Industry, PA (Upstream of Montgomery Weekly Grab 49A Surface l*I Dam) Sample 1*1 Monthly Composite of 3 Gamma Scan Water Weekly Sample 1°1 East Liverpool , OH (Water Daily Grab Sample 5 Quarterly Composite 1°1 Tritium (H-3) I 4 Groundwater Department) No sampling performed Collected Weekly 1*1 Biweekly Composite of 4 Midland , PA (Water Department) lodine-131 Daily sample 1*1 I 5 Drinking Water 5 East Liverpool , OH (Water Department) Intermittent 1*1 Sample Collected Weekly Month ly Composite 1*1 Gamma Scan Quarterly Composite 1*1 Tritium (H-3) I 6 Shoreline Sediment 2A 49Al*I BVPS Outfall Vicinity Industry, PA (Upstream of Montgomery Semi-Annual Semi-Annual Gamma Scan Dam) I 7 Milk 27 951*1 Aliquippa, PA (Brunton Farm) Burgettstown , PA (Windsheimer Farm) Biweekly 1~ When animals are on pasture; monthly at All other samples & analyses are Biweekly during grazing but Gamma Scan lodine-131 Strontiu m-89 Monthly during other other times Strontium-90 I 114 lkl 2A Hookstown, PA (Covert Residence) BVPS Outfall Vicinity times Composite of edible Gamma Scan 8 Fish Semi-Annual on edible 49Al*I Industry, PA (Upstream of Montgomery parts by species lgl I 10*l'llml Dam) Shippingport, PA parts 15*(lllml I Georgetown , PA 12 (!)(ml Racoon Township, PA Gamma Scan Annual at Harvest if Composite of each lodine-131 on 9 Food Crops available sample species green leafy 45*ll)(ml Industry, PA vegetables I 48*(*1(1X ml

                              * (l)(m)

Weirton , WV I 10 Feedstuff & Summer Foraae 27 Aliquippa, PA (Brunton Farm) Shippingport, PA (Cook's Ferry Monthly Monthly Gamma Scan 30A Substation) I 11 Soil 32A 468 Midland , PA (North Substation) Industry, PA (Willows Inn - Rt. 68) Every Five (5) 12 Core Samples 3" Deep (2" diameter at Years Gamma Scan each location approx . I 481*1 51A Weirton WV (Water Tower - Collier Way) Aliquippa, PA (Sheffield Substation) (2015 , 2020, 2025) 10' radius) I 12 Precipitation No sampling performed I I 2-3

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-1 (Continued) I Operational Radiological Environmental Monitoring Program I Notes for Table 2-1 I Control sample station: These Locations which are presumed to be outside the influence of (a) plant effluents. Particulate Samples are not counted within 24 hours after filter change. Perform gamma isotopic analysis on each sample when gross beta is greater than 10 times the yearly mean of (b) control samples. Long-term composite samples are obtained from short-term composite samples at the specified (c) locations. (d) Composite samples are collected at intervals not exceeding 2 hours. (e) Searight Dairy is no longer operational. (f) Milk samples are collected biweekly when animals are grazing . The milk samples are collected I monthly at other times. (g) The fish samples contain whatever species are available. IF adequate sample size is available, THEN the sample is separated according to species, and 11 compositing will provide one sample of each species. IF adequate sample size is not available, THEN separation by species is not practical. Therefore , edible parts of all fish in the sample are mixed to provide one sample. I (h) Composite samples are obtained by collecting an aliquot at intervals not exceeding 2 hours at location 2.1 . In December of 2016, location 2 .1 was closed. The water treatment plant operator at location 5 obtains the weekly grab sample from the daily composite grab samples. In I December of 2016 , location 5 was transitioned to a composite sample to replace location 2.1. For location 49A, the weekly grab sample is obtained by a field technician . I (i) Two (2) TLDs are collected quarterly from each monitoring location. (k) ODCM procedure 1/2-0DC-3.03, Attachment Q, Table 3.12-1 requires three (3) dairies to be selected on basis of highest potential thyroid dose using milch census data. See Section 2-E of I this report (Monitoring of Loca l Cow's Milk) for specific locations sampled. (I) Three (3) garden locations requ ired by 1/2-0DC-2.03, Attachment A Table 3 .0-1 ; Sites designated by 1/2-0DC-2.03 Attachment B Figure 3.0-5. Sampling locations may be altered by I the REMP Administrator at any time based on availability. When there are not enough milk sample locations available to meet the ODCM requirements, three (3) different types of broad leaf vegetation are to be sampled at each of two (2) indicator I locations based on the highest predicted annual average ground D/Q (as determined from the (m) previous year's Land Use Census results), in addition to those samples described in Note (I). Three (3) different types of broad leaf vegetation shall also be sampled at one (1) control I location when in this condition. I 11 2-4 I

I Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM ' 2. Summary of Results II All results of this monitoring program are summarized in Table 2-2. This table is II prepared in the format specified by the NRC via the Branch Technical Position in NUREG-1301 , and in accordance with Beaver Valley Power Station ODCM. Summaries of results of analysis of each media are discussed in Sections 2-B through 2-H and an I assessment of radiation doses are given in Section 2-I. Table 2-3 summarizes BVPS pre-operational ranges for the various sampling media during the years 1974 and 1975. Comparisons of pre-operational data with operational data indicate the ranges of values

I I

are generally in good agreement for both periods of time. II Activity detected was attributed to naturally occurring radionuclides, BVPS effluents, previous nuclear weapons tests and/or to the normal statistical fluctuation for activities near the LLD. I The conclusion from all program data is that the operation of BVPS has resulted in no I significant changes to the environment.

3. Quality Control Program I The Quality Control Program implemented by BVPS to assure reliable performance by I the contractor and the supporting QC data are presented and discussed in Section 4 of this report.

I 4. Program Changes I In January 2017, REMP sampling changes were made to remove non-ODCM samples, and they are as follows; two air particulate and radioiodine locations, two groundwater locations, one sediment location, three precipitation locations, and five soil locations. I Additionally, the frequency of drinking water analysis was changed to biweekly, surface water analysis #49A was changed to biweekly, and soil sample collection was changed to I quinquennial. I I I I 2-5

Beaver Valley Power Station 2016 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2-ENVIRONMENTAL MONITORING PROGRAM Table 2-2 I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Na me of Facility: Beaver Valley Power Station Unit I and Unit 2 I Docket No.: 50-334 / 50-412 Location of Facility: Beaver County, Penn sylvania Reporting Period: Calendar Year- 2017 Medi um: Air Particulate and Radioiodine Unit of Measurement: (picoCuries / cubi c meter) I Type and Lower Total Numbe, Limit of All Indicator Locations Locations with Highest Annual Mean Control Location Number of Non routine I of Analysis Performed Gross Beta 416 Detection Mean (fraction) <*> LLD<*>

              < 0.002 Range<*>

0.026 ( 364 I 0.009 - 0.065 364 ) Na me Distance and Direction No. 46 .1 Industry, PA 2.28 miles NE Mean (fracti on) <*> Range <*> 0.027 ( 52 / 52 0.0 12 - 0.056

                                                                                                                )

Name Distance and Direction No. 48 Weirton, WV Water Tower Mean (fraction) (bl Range<*> 0.025 ( 52 / 52 0.009 - 0.05 1

                                                                                                                                                             )

Reported Measurements (c) 0 I I Collier Way 16.4 mil es SSW 1-1 31 < 0.04 LLD ( 0 I 364 ) LLD ( 0 I 364 ) LLD ( 0 I 52 ) 0 4 16 Gamma 32 I Be-7 NA 0.080 ( 28 / 28 ) No. 46 .1 Ind ustry, PA 0.086 ( 4 14 ) No. 48 Weirton, WV 0.085 ( 4 14 ) 0 0.06 1 - 0.097 2.28 miles NE 0.075 - 0.097 Water Tower Collier Way 16.4 miles SSW 0.067 - 0. 100 I Co-60 NA LLD ( 0 I 28 ) LLD ( 0 / 28 ) LLD ( 0 I4 ) 0 Cs- 134 < 0.0005 LLD ( 0 I 28 ) LLD ( 0 / 28 ) LLD ( 0 14 ) 0 Cs- 137 < 0.0005 LLD ( 0 I 28 ) LLD ( 0 / 28 ) LLD ( 0 14 ) 0 Ba-La-140 NA LLD ( 0 I 28

  • No minal Lower Limit of Detection
                                                 )                                          LLD (      0 / 28   )                          LLD (     0 14    )         0 I

b Mean a nd range based upon detectable meas urements only. Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

            ' Nonroutine Reported Measurements (

Reference:

ODCM procedu r e l/2-0DC-3.03, Attachment Q, Control 3.12.1) I NA = No t Applicable (Naturally Occurrin g Radionuclides No t required by ODCM) I I I I I 2-6 I

I Beaver Valley Power Station 2016 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 (Continued) I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit 1 and Unit 2 Docket No.: 50-334 / 50-412 I Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar Year - 2017 Medium: Drink ing Water I Unit of Measurement: (picoCuri es / liter) Type and Lower Number of Total Number Limit of All Indicator Locations Locations with Highest Annual Mean Control Location I Nonroutine I of Analysis Performed 1- 13 1 76 Detection Mean (fraction) Cb> LLo <*>

                  < 0.5 Range (bl 0.3 (

LLD - 0.3 I / 50 ) Name Distance and Direction No. 5 East Liverpool Water 4.9 miles WN W Mean (fraction) Cb> Range (b) 0.3 ( I / 25 Name Distance and Direction

                                                                                                                      ) No. 49A Industry, PA Mean (fraction) (bl Range  (bl 0.7 (    3 / 26  )

Reported Measurements (c) 0 LL D - 0.3 Upstream o f 0.3

  • 1.3 I

Montgomery Dam 4.93 miles NE H-3 < 200 LLD ( 0 / 8 ) LLD ( 0 / 8 ) LLD ( 0 / 4 ) 0 12 I Gam ma 36 Mn-54 < 5 LLD ( 0 / 24 ) LLD ( 0 / 24 ) LLD ( 0 / 12 ) 0 I Fe-59 Co-58

                  < 10
                  < 5 LLD (

LLD ( 0 / 24 0 / 24

                                                     )
                                                     )

LLD ( LLD ( 0 / 24 0 / 24

                                                                                                                      )
                                                                                                                      )

LLD ( LLD ( 0 / 12 0 I 12

                                                                                                                                                                     )
                                                                                                                                                                     )

0 0 I Co-60 Zn-65

                  < 5
                  < 10 LLD (

LLD ( 0 I 24 0 / 24

                                                     )
                                                     )

LLD ( LL D ( 0 I 24 0 / 24

                                                                                                                      )
                                                                                                                      )

LLD ( LLD ( 0 / 12 0 I 12

                                                                                                                                                                     )
                                                                                                                                                                     )

0 0 'I Zr-Nb-95 Cs-1 34

                  <5
                  < 5 LLD (

LLD ( 0 I 24 0 I 24

                                                     )
                                                      )

LLD ( LLD ( 0 I 24 0 / 24

                                                                                                                      )
                                                                                                                      )

LLD ( LLD ( 0 I 12 0 I 12

                                                                                                                                                                     )
                                                                                                                                                                     )

0 0 Cs- 137 < 5 LLD ( 0 I 24 ) LLD ( 0 / 24 ) LLD ( 0 I 12 ) 0 I Ba-La- 140 < 10 LLD ( 0 I 24

  • Nominal Lower Limit of Detection
                                                      )                                          LLD (     0 I 24     )                            LLD (      0 I 12  )        0 I               b Mean and range based upon detectable measurements only.

Fraction of detectable measurements at s pecified locations is indicated in parentheses (fraction )

                ' Non r outine Reported Measuremenls (

Reference:

ODC M procedure l /2-0DC-3.03, Attachmenl Q, C ontrol 3. 12. 1) I A = No l Applicable (Naturally O ccurring Radionuclides ot required by ODCM) I I I I I 2-7

Beaver Valley Power Station 2016 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2- ENVIRONMENTAL MONITORING PROGRAM Table 2-2 (Continued) I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Na me of Facility: Beaver Valley Power Station Unit I and Unit 2 I Docket No.: 50-334 / 50-412 Location of Facility: Beaver Co unty, Pennsylvania Reporting Period: Ca lendar Year - 2017 I Medium: Surface Water Unit of Measurement: (picoCuries / liter) Type and Lower Total Numbe1 Limit of All Indicator Locations Locations with Highest Annual Mean Control Location Number of I Nonroutine .1 of Analysis Performed 1- 13 1 26 Detection Mean (fraction) (b) LLD > Range (b)

               < 0.5 Name Distance and Direction Mean (fraction) (b)

Range (b) Name Distance and Direction No. 49A Industry, PA Upstream of Mean (fraction) (b) Range<*> 0.7 ( 0.3 - 1.3 3 / 26 ) Reported Measurements (t) 0 I Montgomery Dam 4.93 miles NE H-3 < 200 LLD ( 0 I 4 ) LLD ( 0 I 4 ) LLD ( 0 I 4 ) 0 8 Gamma 36 Mn-54 < 5 LLD ( 0 I 24 ) LLD ( 0 / 24 ) LLD ( 0 I 12 ) 0 Fe-59 < 10 LLD ( 0 I 24 ) LLD ( 0 / 24 ) LLD ( 0 I 12 ) 0 Co-58 < 5 LLD ( 0 I 24 ) LLD ( 0 I 24 ) LLD ( 0 I 12 ) 0 Co-60 Zn-65

               < 5
               < 10 LLD (

LLD ( 0 I 24 0 I 24

                                                )
                                                )

LLD ( LLD ( 0 1 24 0 1 24

                                                                                                                 )
                                                                                                                 )

LLD ( LLD ( 0 I 12 0 I 12

                                                                                                                                                                )
                                                                                                                                                                )

0 0 I Zr- Nb-95 < 5 LLD ( 0 I 24 ) LLD ( 0 / 24 ) LLD ( 0 I 12 ) 0 Cs- 134 Cs-1 37

               < 5
               < 5 LLD (

LLD ( 0 I 24 0 I 24

                                                 )
                                                 )

LLD ( LLD ( 0 1 24 0 I 24

                                                                                                                 )
                                                                                                                 )

LLD ( LLD ( 0 I 12 0 I 12

                                                                                                                                                                )
                                                                                                                                                                )

0 0 I Ba-La-140 < 10 LLD ( 0 I 24

  • Nominal Lower Limit of Detection
                                                 )                                           LLD (     0 I 24    )                            LLD (     0 I 12  )        0 I

h Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (fraction) I

             ' Nonroutine Reported Measurements (

Reference:

ODCM procedure l/2-0DC-3.03, Attachment Q, Control 3.12.1) NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODC M) I I I I I 2-8 I

I Beaver Valley Power Station 2016 Annual Radiological Environmental Operating Report RTL A9. 690E Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 (Continued) I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facili ty : Beaver Valley Power Station Unit I and Unit 2 Docket No.: 50-334 / 50-412 I Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar Year - 2017 Medium: Ground Water Sample location s are no longer in use I Unit of Measurement: (picoCuries / liter) Type and Lower Total Number Limit of All Indicator Locations Locations with Highest Annual Mean Control Location Number of Nonroutine I Detection Mean (fraction) (bl Mean (fraction) (hJ Mean (fraction) (bl I of Analysis Name Name Reported Performed LLD <*l Range (hl Distance and Direction Range lh> Distance and Direction Range <*> Measurements (c) H-3 < 200 I Gamma Mn-54 < 5 I Fe-59 Co-58

                 < 10
                 < 5 I

Co-60 < 5 Zn-65 < 10 Zr-Nb-95 < 5 I Cs- 134 Cs- 137

                 < 5
                 < 5 I   Ba-La-1 40    < 10
  • Nominal Lower Limit of Detection I h Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

               ' Nonroutine Reported Measurements (

Reference:

ODC M procedure l/2-0DC-3.03, Attachment Q, Control 3.12.1) I NA = Not Applicable (Naturall y Occurring Radionuclides No t required by ODC M) I I I I I I 2-9

Beaver Valley Power Station 2016 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2- ENVIRONMENTAL MONITORING PROGRAM Table 2-2 (Continued) I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit I and Unit 2 I Docket No.: S0-334 / 50-412 Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar Year - 20 17 I Medium: Precipitation Water Sample locations are no longer in use Unit of Measurement: (picoCuries / liter)

                                                                                                                                                                               'I Type and Lower Total Numbe r Limit of All Indicator Locations    Locations with Highest Annual Mean                              Control Location Number of Nonroutine      I of Analysis Performed H-3 Detection Mean (fraction)<*>

LLo<*>

              < 200 Range <*>

Name Distance and Direction Mean (fraction)<*> Range <*> Name Distance and Direction Mean (fraction) (bl Range<*> Reported Measurements (c) II Gamma Mn-54 < 5 I Fe-59 Co-58

              < 10
              < 5 I
              < 5 11 Co-60 Zn-65      < 10 Zr-Nb-95     < 5 Cs-1 34     < 5 Cs-1 37     < 5 Ba-La-140    < 10
  • Nominal Lower Limit of Detection I

b Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in J>arentheses (fraction) I

            ' Nonrouti ne Reported Measurements (

Reference:

ODCM procedure l/2-0DC-3.03, Attachment Q, Control 3.12.1) NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM) I I I I I I 2-10 I

I Beaver Valley Power Station 2016 Annual Radiological Envi ronmental Operating Report RTL A9.690E Enclosure 3 I SECTIO N 2 - ENVIRONMENTA L MON ITORING PROGRAM Ta ble 2-2 (Continued) I RADIOLOGICA L ENVIRON MENTA L MONITORI NG PROGRAM SUM MA RY Na me of Facili ty: Beaver Valley Power Station Unit I a nd Unit 2 Docket No.: 50-334 / 50-412 I Location of Facility: Beaver C ounty, Penn sylvania Reporting Period: C alendar Year - 201 7 Medium: Milk I Unit of Measu rement: (picoCuries / liter) Type and Lowe r IN umber of I Total Number Limit of A ll Indicator Loca ti ons Loca tions with Hi ghes t A nnual Mea n Contro l Location Non routine I of Anal ysis De tec tion Mean ( fracti on) Cb> Nam e Mean (fracti on) Cb) Nam e M ea n (fraction) (b> Re ported Performed LLD 1' 1 Range Cb> Distance a nd Direction Ran ge Cbl Distance and Direction Ran ge (b) Measurements (r) 1- 13 1 < 0.5 LLD ( O I 42 ) LLD ( 0 I 42 ) No. 96 Burgettstown, PA 1.4 ( I / 21 ) 0 63 Windsheimer Farm LLD - 1.4 I 0.46 miles SSW I Sr-89 63 Sr-90

                 < 2.0
                 < 0.7 LLD (

0.6 ( 0 I 42 14 I 42

                                                          )
                                                          )    No. 11 4 Hookstown , PA LLD (

1.0 ( 0 I 37 9 I 21

                                                                                                                          )
                                                                                                                          )    No. 96 Burgett stown , PA LLD (      0 I 21 )

1.0 ( 16 / 2 1 ) 0 0 63 0.5 1.7 Covert Residence 0.6 - 1.7 Windsheimer Fann 0.5 - 1.2 I Gamma 63 2.13 miles SW 10.46 mi les SSW I K-40 < 150 1354 ( 32 I 42 ) No. 114 Hookstown, PA 1620 ( 11 / 21 ) No. 96 Burgettstown, PA 1382 ( 2 1 / 2 1 ) 0 1252 - 1899 Covert Residence 1339 - 1899 Windsheimer Fann 1228 - 1509

2. 13 miles SW I 0.46 miles SSW Mn-54 < 5 LLD ( 0 I 42 ) LLD ( 0 I 42 ) LLD ( 0 I 21 ) 0 I Fe-59 Co-58
                 < 10
                 < 5 LLD (

LLD ( 0 I 42 0 I 42

                                                          )
                                                           )

LLD ( LLD ( 0 I 42 0 I 42

                                                                                                                          )
                                                                                                                           )

LLD ( LLD ( 0 I 21 0 / 21

                                                                                                                                                                                )
                                                                                                                                                                                )

0 0 I Co-60 Zn-65

                 <5
                 < 10 LLD (

LLD ( 0 I 42 0 I 42

                                                           )
                                                           )

LLD ( LLD ( 0 / 42 0 I 42

                                                                                                                           )
                                                                                                                           )

LLD ( LLD ( 0 I 21 0 I 21

                                                                                                                                                                                )
                                                                                                                                                                                )

0 0 Zr-Nb-95 < 5 LLD ( 0 I 42 ) LLD ( 0 / 42 ) LLD ( 0 I 21 ) 0 I Cs- 134 <5 LLD ( 0 I 42 ) LLD ( 0 I 42 ) LLD ( oI 21 0 I 21

                                                                                                                                                                                )          0 Cs-1 37     < 5              LLD (        0 I 42      )                                            LLD (      0 / 42  )                               LLD (                )           0 I   Ba-La-140     < 10             LLD (        0 I 42
  • Nom inal Lower Limit of Detection
                                                           )                                            LLD (      0 I 42  )                               LLD (       0 I 21   )           0 I               b  Mean and range based upon detec table meas urements only.

Fraction of detectable measurements at specified locations is indica ted in parentheses (fraction)

               'Nonroutin e Re ported Measurem ents (

Reference:

ODCM procedure l/2-0DC-3.03, Attach men t Q, Co n t rol 3.1 2. 1) I NA = No t A pplica ble (Na tu ra lly Occ urrin g Radionuclides Not required by O DCM) I I I I 2-11

Beaver Valley Power Station 2016 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2- ENVIRONMENTAL MONITORCNG PROGRAM Table 2-2 (Continued) I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit I and Unit 2 I Docket No.: 50-334 / 50-412 Location of Facility : Beaver County, Pennsylvania Reporting Period: Calendar Year - 201 7 I Medium : Fish I I Unit of Measurement: {picoCuries / gram) Wet Type and Lower Number of Total Numbei Limit of All Indicator Loca tions l"L_o_c_a_tio_n_s_w_i_th_H ig._h_es_t_A_n_n_u_ a_lM_e_a".,....------,,.,...-+ c _o_nt_r_ol_L_o_c_a_ti_ on_ _ _ _"T"_ _ _ _ _ _~ Nonroutine of Analysis Detection Mean (fraction) (bl Performed LLD (*l Gamma 9 Range (bl Name Distance and Direction Mean (fraction) (bl Range (bl Name Distance and Direction No. 49A Industry, PA Upstream of Mean (fraction) (bl Range (b) Reported Measurements <c:J I Montgomery Dam Mn-54 Fe-59

                < 0.05
                < 0. 10 LLD (

LLD ( 0 I 5 0 I 5

                                                 )
                                                  )

LLD ( LLD ( oI5 0 I5 4.93 miles NE LLD( LLD( 0 / 4) 0 / 4) 0 I I Co-58 < 0.05 LLD ( 0 I 5 ) LLD ( 0 I5 LLD ( 0 /4 ) Co-60 < 0.05 LLD ( 0 I 5 ) LLD ( 0 I5 LLD ( 0 /4 ) Zn-65 < 0. 10 LLD ( 0 I 5 ) LLD ( 0 I5 LLD( 0 / 4) 0 Zr-Nb-95 Cs-1 34

                < 0.01
                < 0.05 LLD (

LLD ( 0 I 5 0 I 5

                                                  )
                                                  )

LLD ( LLD ( 0 I5 0 I5 LLD ( LLD( 0 /4 0 / 4)

                                                                                                                                                                                   )        0 I

Cs-1 37 Ba-La-1 40

                < 0.05
                < 0.0 1 LLD (

LLD ( 0 I 5 0 I 5

                                                  )
                                                  )

LLD ( LLD ( 0 I5 0 I5 LLD( LLD( 0 / 4) 0 / 4) 0 0 I 11 Nominal Lower Limit of Detection b Mean and range based upon detectable meas urements only. Fraction of detectable measurements at specified locations is indicated in parentheses (fraction) I NA

             'Nonroutine Reported Measurements (

Reference:

ODC M procedure l/2-0DC-3.03, Attachment Q, Control 3.12.1 )

                = Not Applicable (Naturally Occurring Radionuclides Not required by ODC M)

I I I I I I I 2-12 I

I Beaver Valley Power Station 2016 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2- ENVIRONMENTAL MONITORING PROGRAM Table 2-2 (Continued) I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Na me of Facility: Beaver Valley Power Station Unit l and Unit 2 Docket No.: 50-334 / 50-412 I Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar Year- 2017 Medium: Foodcrops I Unit of Measurement: (picoCuries / gram) Wet Type and Lower Total Numbei Limit of All Indicator Locations Locations with Highest Annual Mean Control Location Number of INonroutine I of Analysis Detection Mean (fraction) (bl Name Mean (fraction) c*> Name Mean (fraction) (b) Reported I Performed 1- 13 1 II LLD (*>

                 < 0.06 Range (h)

LLD ( 0 I 10 ) Distance and Direction Range Ch) LLD ( 0 / 10 ) Distance and Direction Range (b) LLD ( 0 I I ) Measurements 0 le) I Gamma II K-40 NA 2.85 ( 10 / I O ) No. 12 Racoon Township, PA 5.00 ( 10 / 10 ) No. 488 Weirton, WV 3.30 ( I / I ) 0

1. 80 - 9.40 2.74 miles E 2.60 - 9.40 16.52 miles SSW LLD - 3.30 I Mn-54 Fe-59 NA NA LLD (

LLD ( 0 I 10 0 I 10

                                                   )
                                                   )

LLD ( LLD ( 0 I 10 0 / 10

                                                                                                                   )
                                                                                                                   )

LLD ( LLD ( 0 / I 0 I I

                                                                                                                                                                 )
                                                                                                                                                                 )

0 0 I Co-58 Co-60 NA NA LLD ( LLD ( 0 I 10 0 I 10

                                                   )
                                                   )

LLD ( LLD ( 0 / 10 0 / 10

                                                                                                                   )
                                                                                                                   )

LLD ( LLD ( 0 I I 0 I I

                                                                                                                                                                 )
                                                                                                                                                                 )

0 0 NA I Zn-65 LLD ( 0 I 10 ) LLD ( 0 / 10 ) LLD ( 0 / I ) 0 Zr-Nb-95 NA LLD ( 0 I 10 ) LLD ( 0 I 10 ) LLD ( 0 / I ) 0 Cs-1 34 0.04 LLD ( 0 I 10 ) LLD ( 0 1 10 ) LLD ( oI l ) 0 I Cs- 137 Ba-La-1 40 0.06 NA LLD ( LLD ( 0 I 10 0 I 10

                                                   )
                                                   )

LLD ( LLD ( 0 / 10 0 I 10

                                                                                                                   )
                                                                                                                    )

LLD ( LLD ( 0 / I 0 / I )

                                                                                                                                                                  )         0 0

I

  • Nominal Lower Limit of Detection b Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction) I 'Nonroutine Reported Measurements (

Reference:

ODCM procedure l/2-0DC-3.03, Attachmen t Q, Control 3. 12.1) NA = No t Applicable (Naturally Occurring Radionuclides No t required by ODCM) I I I I I I 2-13

Beaver Valley Power Station RTL A9.690E II 2016 Annual Radio logical Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 (Continued) I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Na me of Facility: Beaver Va lley Powe r Station Unit I and Unit 2 I Docket No.: 50-334 / 50-412 Location of Faci lity: Beaver County, Pennsylvania Reporting Period: Calendar Year - 2017 I Medium: Feedstuff Unit of Measurement: (picoCuries / gram) Wet Type and Lower Total Numbe, Limit of All Indicator Locations Locations with Highest Annual Mean Control Location Number of Nonroutine .1 I I of Analysis Detection Mean (fraction) <*> Name Mean (fraction)<*> Name Mean (fraction) <bl Reported Performed LLD <*> Range <*> Distance and Direction Range <*> Distance and Direction Range <*> Measurements (c) Gamma 12 Be-7 < 0.2 0.34 ( 0.25 - 0.42 4 I 12 ) No. 27 Brunton Farm 368 1 Ridge Road Aliq uippa, PA 6.08 miles SE 0.34 ( 4 I 12 0.25 - 0.42

                                                                                                                  )   No. 27 Brunton Farm 368 1 Ridge Road Aliquippa, PA 6.08 miles SE 0.34 (    4 I 12 0.25 - 0.42
                                                                                                                                                                    )        0 I

K-40 < 0. 15 8.87 ( 12 / 12 6.78 - 11.48

                                                  )     No. 27 Brunton Fann 368 1 Ridge Road Aliquippa, PA 6.08 miles SE 8.87 ( 12 / 12 6 .78 - 11.48
                                                                                                                  )   No. 27 Brunton Fann 3681 Ridge Road Aliquippa, PA 6 .08 mi les SE 8.87 ( 12 / 12 6.78 - 11.48
                                                                                                                                                                    )        0 I

Mn-54 Fe-59

                < O.Q2
                < 0.04 LLD (

LLD ( 0 I 12 0 I 12

                                                  )
                                                  )

LLD ( LLD ( 0 I 12 0 I 12

                                                                                                                  )
                                                                                                                  )

LLD ( LLD ( 0 I 12 0 I 12

                                                                                                                                                                    )
                                                                                                                                                                    )

0 0 I Co-58 Co-60

                < O.Q2
                < 0.02 LLD (

LLD ( 0 I 12 0 I 12

                                                  )
                                                  )

LLD ( LLD ( 0 I 12 0 I 12

                                                                                                                  )
                                                                                                                  )

LLD ( LLD ( 0 I 12 0 I 12

                                                                                                                                                                    )
                                                                                                                                                                    )

0 0 I Zn-65 < 0.04 LLD ( 0 I 12 ) LLD ( 0 I 12 ) LLD ( 0 I 12 ) 0 Zr-Nb-95 Ru- 103

                < 0.03
                < 0.03 LLD (

LLD ( 0 I 12 0 I 12

                                                  )
                                                  )

LLD ( LLD ( 0 I 12 0 I 12

                                                                                                                  )
                                                                                                                  )

LLD ( LLD ( 0 I 12 0 I 12

                                                                                                                                                                    )
                                                                                                                                                                    )

0 0 I 1- 13 1 Cs- 134

                < 0.06
                < 0.04 LLD (

LLD ( 0 I 12 0 I 12

                                                  )
                                                  )

LLD ( LLD ( 0 I 12 0 I 12

                                                                                                                  )
                                                                                                                  )

LLD ( LLD ( 0 I 12 0 I 12

                                                                                                                                                                    )
                                                                                                                                                                    )

0 0 I I Cs- 137 < 0.06 LLD ( 0 I 12 ) LLD ( 0 I 12 ) LLD ( 0 I 12 ) 0 Ba-La- 140 < 0.0 1 LLD ( 0 I 12 ) LLD ( 0 I 12 ) LLD ( 0 I 12 ) 0

  • Nommal Lower Limit of Detechon b Mean and range based upon detecta ble meas urements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction) I NA

              'Nonro u tine Reported Measurements (

Reference:

ODCM procedure l /2-0DC-3.03, Attachment Q, Control 3. 12.1)

                = No t Applicable (Naturally Occurring Radionuclides Not required    by ODC M)

I I I I 2-14 I

I Beaver Valley Power Station 2016 Annual Radiological Environmental Operating Report RTLA9.690E Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 (Continued) I RADIOLOGICAL ENVIRONMENTAL MONITORI NG PROGRAM

SUMMARY

Name of Facility: Beave r Valley Power Station Unit I and Unit 2 Docket No.: 50-334 / 50-412 I Location of Facility: Beaver County, Penn sylvania Reporting Period: Calendar Year - 201 7 Medium: Sediment (page I of2) I Unit of Measurement: (picoCuries / gram) Dry Type and Total Numbei Lower Li m it of All Indica tor Locati ons i.:Lo=c;;;att;;;

                                                                   *o;;;n;;.

s ,;,; w,;;it.::.h..:; H;;;ig!:;h;.;;e;;.; st;.;A,;;n;;;n;.;;u;;;;al;..;M

                                                                                                                                     ;.;e;;;a; ; ; n , - - - - - - - - +C;;.o;;;n;.;.tr;.;o;.;.l.;;Lo.;.c;.;;a;;;ti.;;

Number of on;.;..._ _ _. . - - - - - - - - INonro utine I of Analys is Detection Mea n (fraction) Cb) Name Mean (fraction ) Cb) Name Mea n (fraction) Cb) Reported I Performed Gamma 4 LLD <*> Ran ge Cb) Distance and Direction Range Cb) Distance and Direction Ran ge Ch> Measurements(() I K-40 NA 10.50 ( 9.58 - I 1.42 2 / 2 ) No. 2A BVPS Outfall Vicini ty 0.3 I miles WSW 10.50 ( 2 / 2 9.58 - I 1.42

                                                                                                                                                                       ) No. 49A lndustty, PA 4.93 mi les NE Upstream of Montgomery Dam 12.45 (    2 / 2 I 1.86 - 13.04
                                                                                                                                                                                                                                                      )        0 I     Mn-54 Fe-59
               < 0.02
               < 0.03 LLD (

LLD ( 0 I 2 0 I 2 LLD ( LLD ( 0 / 2 0 / 2 LLD( LLD( 0 / 2) 0 / 2) 0 Co-58 < 0.02 0. 14 ( I / 2 ) No. 2A BVPS 0. 14 ( I / 2 LLD ( 0 / 2 ) 0 I < 0.02 LLD - 0. 14 Outfall Vicinity 0.3 I mi les WSW LLD - 0. 14 Co-60 0.14 ( 2 / 2 ) No. 2A BVPS 0. 14 ( 2 /2 LLD ( 0 /2 ) 0

0. 12 - 0. I 5 I
0. 12 - 0. 15 Outfall Vicinity 0.3 1 miles WSW Zn-65 < 0. 04 LLD ( 0 I 2 LLD ( 0 / 2 LLD( 0 / 2) 0 I Zr-95 Nb-95
               < 0.03
               < 0.03 LLD (

LLD ( 0 I2 0 I 2 LLD( LLD ( 0 / 2 0 / 2 LLD( LLD( 0 / 2) 0 / 2) 0 0 Cs- 134 < 0.06 LLD ( 0 / 2 LLD ( 0 / 2 LLD ( 0 / 2 ) 0 I Cs- I 37 < 0.08 0.07 ( 0.07 - 0.07 2 / 2 ) No. 2A BVPS Outfall Vicini ty 0.3 I miles WSW 0.07 ( 0.07 - 0.07 2 / 2 ) No. 49A lndustty, PA Upstream of Montgomery Dam 0.07 ( 2 / 2 0.05 - 0.08

                                                                                                                                                                                                                                                      )        0 4.93 miles NE I   Ba-La- 140  < 0.03         LLD (        0 / 2                                                                                                   LLD (       0 / 2                                                                 LLD(      0 / 2)          0 I

I I I I I 2-15

Beaver Valley Power Station 2016 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2- ENVIRONMENTAL MONITORING PROGRAM Table 2-2 (Continued) I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Na me of Facility: Beaver Valley Power Station Unit I and Unit 2 I Docket No.: 50-334 / 50-4 I 2 Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar Year- 2017 I Medium: Sediment (page 2 of2) I I Unit of Measurement: (picoCuries / gram) Dry Type and Lower Number of Total Number Limit of All Indicator Locations 1-Lo_c_an_*o_n_s_w_i_th_H_.ig__h_es_t_A_n_n_u_al_M_ea_n.,._ _ _ _ _ _ _-t_ C_o_nt_r_ol_Lo_c_a_ti_on_ _ _ _...,.._ _ _ _ _ _-fNonroutine of Analysis Detection Mean (fraction) (b) Name Mean (fraction) (b) Name Mean (fraction) (b) Reported Performed Tl-208 LLD (a) NA Range Cb> 0.35 ( 0.35 - 0.35 2 / 2 ) Distance and Direction No. 2A BVPS Outfall Vicinity Range Cb) 0.35 ( 2 / 2 0.35 - 0.35 Distance and Direction

                                                                                                                               ) No. 49A Industry, PA Upstream of Range (h}

0.34 ( 0.32 -

                                                                                                                                                                                         )

Measurements Cc> 0 I 0.31 miles WSW Montgomery Dam Bi-2 14 NA 0.81 ( 0.73 - 0.88 2 / 2 Same localionfor lhefo l/owing nuclides 0.73 ( 2 / 2 0.69 - 0.76

                                                                                                                               )

4.93 miles NE Same location/or

                                                                                                                                     !he fo llowing nuclides          0.82 ( 2 / 2 0.77 - 0.86
                                                                                                                                                                                         )        0 I

Pb-2 12 Pb-214 NA NA 11 8 ( 0.97 - 1.39 0.90 ( 2 / 2 2 / 2 1.1 8 ( 0.97 - 1.39 0.90 ( 2 / 2 2 / 2

                                                                                                                               )
                                                                                                                               )

0.99 ( 0.87 - I.I I 0.96 ( 2 / 2 2 /2 )

                                                                                                                                                                                         )

0 0 I 0.84 - 0.95 0.84 - 0.95 0.95 - 0.96 Ra-226 NA 2.35 (

2. 12 - 2.58 2 / 2 2.35 ( 2 / 2
2. 12 - 2.58
                                                                                                                               )                                       1.98 ( 2 / 2 1.80 - 2. 15
                                                                                                                                                                                         )                  I Ac-228         NA          1.15 (

1.05 - 1.25 2 / 2 1.15 ( 2 / 2 1.05 - 1. 25

                                                                                                                               )                                       1.20 (

I.II - 1.29 2 /2 ) 0 I

  • Nominal Lower Limit of Detection b Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction) I NA

             ' Nonroutine Reported Measurements (

Reference:

ODCM procedure l/2-0DC-3.03, Attachment Q, Control 3.12.1)

               = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM)

I I I I I I I 2-16 I

I Beaver Valley Power Station 2016 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2- ENVIRONMENTAL MONITORING PROGRAM Table 2-2 (Continued) I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit I and Unit 2 Docket No.: 50-334 / 50-412 I Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar Year - 2017 Medium: Soil (page I of2 ) Soil Sampling is performed every five (5) years. Next sampling is 2020. I Unit of Measurement: (picoCuries / gram) Dry Type and Lower Total Numbe, Limit of All Indicator Locations Locations with Highest Annual Mean Control Location Number of Nonroutine .1 of Analysis Detection Mean (fraction) <*> Name Mean (fraction) <*> Name Mean (fraction)<*> Reported I Performed Gamma LLo<*> Range<*> Distance and Direction Range<*> Distance and Direction Ranee<*> Measurements (r) I K-4 0 Mn-54 NA NA Fe-59 NA I Co-5 8 Co-60 NA NA I Zn-65 Zr-95 NA NA I Nb-95 NA Cs-1 34 NA Cs- 137 NA I Ba-La-140 NA I I I I I I I I 2-17

Beaver Valley Power Station 2016 Annual Radiological Environmental Operating Report RTLA9.690E Enclosure 3 I SECTION 2- ENVIRONMENTAL MONITORING PROGRAM Table 2-2 (Continued) I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit I and Unit 2 Docket No.: 50-334 / 50-412 I Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar Year - 2017 I Medium: Soil (page 2 of2) Soil Sampling is performed every five (5) years. Next sampling is 2020. Unit of Measurement: (picoCuries / gram) Dry Type and Lower Number of I Total Numbei Limit of All Indicator Locations Detection Mean (fraction)<*> Locations with Highest Annual Mean Mean (fraction)<*> Control Location Mean (fraction) <*> Nonroutine I I of Analysis Name Name Reported Performed LLo<*> Range <*> Dis tance and Direction Range (bl Dis tance and Direction Range <*> Measurements (cl Tl-208 NA Bi-2 14 NA Pb-212 Pb-214 NA NA I Ra-226 Ac-228 NA NA I

             ' Nominal Lower Limit of Detection b Mean and range based upon detectable measurements only.

I Fraction of detectable measurements at s pecified locations is indicated in parentheses (fraction)

             ' Nonroutine Reported Measurements (

Reference:

ODCM procedure l/2-0DC-3.03, Attachment Q, Control 3. 12. l ) I NA = Not Applicable ( a tu rally Occurring Radionuclides Not required by ODCM) I I I I I I I I 2-18 I

Beaver Valley Power Station RTLA9.690E 2016 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 (Continued) I RADIOLOGICAL ENVIRONMENT AL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Va lley Power Station Unit I and Unit 2 Docket No.: 50-334 / 50-412 I Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar Year - 2017 Medium: External Radiation I Unit of Measurement: (mR / Quarter) Type and Lower Total Number Limit of All Indicator Locations 1-L_o.;;c_a_ti..;.on_s.;;w_it_h_H_i.,.g_he_s_t_A_n_n..;.u.;;a.;;l.;;M.;;e.;;a;.;,n--------+C.;;o..;.n..;.tr.;;o..;.l.;;Lo;.;.;;ca..;.ti..;..o.;;n;.__ _ _......--------INonroutine Number of I I of Analysis Detection Mean (fraction) <*> Name Mean (fraction) <*> Name Mean (fraction)<*> Reported Performed LLD <*> Range <*> Distance and Direction Range <h> Distance and Direction Range (bl Measurements (c> Gamma 4.6 18.3 ( 520 I 520 ) No. 7 BYPS Site 25 .2 ( 8 / 8 ) No. 48 Weirton, WV 19.5 ( 8 I 8 ) 0 528 12.6 - 26.8 Perimeter Location 23 .8 - 26.8 Water Tower 14.8 - 23.9 I 0.25 miles SSE Collier Way 16.4 miles SSW I

  • Nominal Lower Limit of Detection b Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction) I ' Nonroutine Reported Measurements (

Reference:

ODCM procedure l/2-0DC-3.03, Attachment Q, Control 3.12.1) NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM) I I I I I I I I I I 2-19

Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-3 I Pre-Operational Environmental Radiological Monitoring Program Summary Name of Facility: Beaver Valley Power Station Docket No.: 50-334 I Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar years 1974 - 1975 Medium or Pathway Analysis and Total Lower Limit All Indicator Locations I Sampled Number of Analysis of Detection Mean, Fraction (c), Range (Unit of Measurement) Sediments (dry) Performed Gross Alpha (0) (LLD) I [picocurie /gram] Gross Beta (33) I 18 (33/33) 5 - 30 Sr-90 U-234, 235, 238 (0) (0) I Gamma (33) -- 13 (33/33) 2 - 30 K-40 Cs-137 Zr/Nb-95 1.5 0.1 0.05 13 0.4 0.8 (33/33) (21 /33) ( 12/33) 2 - 30 0.1 - 0.6 0.2 - 3.2 I Ce-144 0.3 0.5 (3/33) 0.4 - 0.7 Ru-I 06(a) Others 0.3 1.5 (3/33)

                                                                             < LLD 1.3 - 1.8  I Foodcrops (dry)      Gamma                 (8)         --                --

[picocurie /gram] K-40 Cs-137 I 0.1 33 0.2 (8/8) (1/8) 10 - 53 I Zr/Nb-95 0.05 0.2 (1 /8) -- Ru- I 06(a) Others 0.3 0.8 (1 /8)

                                                                             < LLD I

Feedstuff (dry) Gross Beta (80) 0.05 19 (80/80) 8 - 50 [picocurie /gram] Sr-89 Sr-90 Gamma (81) (81) (81) 0.025 0.005 0.2 0.4 (33/81) (78/81) 0.04 - 0.93 0.02 - 0.81 I K-40 I 19 (75/81) 5 - 46 Cs-137 0.1 0.5 (6/81) 0.2 - 1.6 Ce-144 0.3 1.5 (5/81) 0.9 - 2.6 Zr/Nb-95 0.05 0.8 (13/81) 0.2 - 1.8 Ru-106(a) 0.3 1.4 (12/81) 0.6 - 2.3 Others -- < LLD Soil (dry) Gross Alpha (0) -- --

 - Template Samples -

[picocurie /gram] Gross Beta Sr-89 Sr-90 (64) (64) (64) I 0.25 0.05 22 0.4 0.3 (64/64) ( 1/64) (48/64) 14 - 32 0.1-1.3 I U-234,235,238 (0) -- -- Gamma K-40 (64) -- 1.5 13 (63 /64) 5 - 24 I Cs-137 0.1 1.5 (56/64) 0.1 - 6.8 Ce-144 Zr/Nb-95 Ru-106(a) 0.3 0.05 0.3 I. I 0.3 I. I (7/64) (13/64) (3/64) 0.2 - 3 0.1 - 2 0.5 - 2 I Others -- < LLD I I 2-20 I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2- ENVIRONMENTAL MONITORING PROGRAM I Table 2-3 (Continued) I Pre-Operational Environmental Radiological Monitoring Program Summary Name of Facility: Beaver Valley Power Station Docket No.: 50-334 Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar years 1974 - 1975 I Medium or Pathway Analysis and Total Lower Limit All Indicator Locations Sampled Number of Analysis I (Unit of Measurement) Performed of Detection (LLD) Mean, Fraction (c), Range Soil (dry) Gross Alpha (0) -- -- I - Core Samples - [picocurie /gram] Gross Beta Sr-89 Sr-90 (8) (8) (8) 1 0.25 0.05 21 0.2 (8/8)

                                                                                 < LLD (5/8) 16 - 28 0.08 - 0.5 Gamma                 (8)          --                --

I K-40 Cs-137 1.5 0.1 13 1.2 (8/8) (7/8) 7 - 20 0.2 - 2.4 Co-60 0.1 0.2 (1/8) -- I Surface Water Others Gross Alpha (40) 0.3 0.75

                                                                                 < LLD (5/40)       0.6 - I.I

[picocurie / liter] Gross Beta (120) 0.6 4.4 (120/ 120) 2.5 - 11.4 I Gamma Tritium Sr-89 (1) (121) (0) 10 - 60 100 300

                                                                                 < LLD (120/ 121) 180 - 800 Sr-90                (0)           --               --

I Drinking Water C-14 I-131 (0) (0) [picocurie / liter] Gross Alpha (50) 0.3 0.6 (4/50) 0.4 - 0.8 I Gross Beta Gamma (208) (0) 0.6 3.8 (208/208) 2 .3 - 6.4 Tritium (211) 100 310 (211/211) 130 - 1000 I C-14 Sr-89 Sr-90 (0) (0) (0) I Ground Water [picocurie / liter] Gross Alpha Gross Beta Tritium (19) (76) (81) 100 0.3 0.6 2.9 440

                                                                                 < LLD (73/75)(b)

(77/81) 1.3 - 8.0 80 - 800 Gamma (I) 10 - 60 < LLD I Air Particulates and Gaseous Gross Alpha Gross Beta (188) (927) 0.001 0.006 0.003 0.07 (35/ 188) (927/927) 0.002 - 0.004 0.02 - 0.32 [picocurie /cubic meter] Sr-89 (0) -- -- I Sr-90 I-131 (0) (816) 0.04 0.08 (2/816) 0.07 - 0.08 Gamma (197) -- -- I Zr/Nb-95 Ru-106 Ce-141 0.005 0.010 0.010 0.04 0 .04 0.02 (122/ 197) (50/197) (3/ 197) 0.01-0.16 0.02 - 0.09 0.01 - 0.04 Ce-144 0.010 0.02 (44/197) 0.01 - 0.04 I Others < LLD I I 2-21

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-3 (Continued) I Pre-Operational Environmental Radiological Monitoring Program Summary Name of Facility: Beaver Valley Power Station Docket No.: 50-334 I Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar years 1974 - 1975 Medium or Pathway Analysis and Total Lower Limit All Indicator Locations I Sampled Number of Analysis (Unit of Measurement) Milk I-13 I Performed (91) of Detection (LLD) 0.25 0.6 Mean, Fraction (c), Range (4/91) 0.3 - 0.8 I [picocurie / liter] Sr-89 Sr-90 Gamma (134) (134) (134) 5 I 7 5.3 (4/134) (132/134) 6 - 11 1.5 - 12.8 I External Radiation Cs-137 Others y- Monthly (599) 10 0.5 mR* 13 0.20 (19/134)

                                                                                   < LLD (599/599) 11 - 16 0.08 - 0.51 I

[milliRoentgen / day] y - Quarterly y- Annual (195) (48) 0.5 mR* 0.5 mR* 0.20 0.19 (195/195) (48/48) 0.11 - 0.38 0.11 - 0.30 I Fish (wet) Gross Beta (17) 0.01 1.9 (15/17) 1.0 - 3.2 [picocurie / gram] Sr-90 Gamma (17) (17) 0.005 0.5 0.14 (17/ 17) 0.02 - 0.50 I K-40 -- 2.4 (17/ 17) 1.0-3.7 Others -- < LLD I

  • LLD in units of mR - Lower end of useful integrated exposure detectability range for a passive radiation detector (TLD).

I (a) May include Ru-106, Ru-103, Be-7. (b) One outlier not included in mean. (Water taken from dried-up spring with high sediment and potassium content. Not considered typical groundwater sample). I (c) Fraction of detectable measurements at specified location, indicated in parenthese. I I I I I I 2-22 I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 11 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM I B. Air Monitoring 11 1. Characterization of Air and Meteorology I The air near the site contains pollutants typical for an industrial area. generally from the southwest in summer and from the west in the winter. Air flow 1s I 2. Air Sampling Program and Analytical Techniques I a. Program I The air is sampled for gaseous radioiodine and radioactive particulates at each of eight (8) offsite air sampling stations. The locations of these stations are listed in Table 2-1 and shown on a map in Figure 2-1. I Samples are collected at each of these stations by continuously drawing two cubic I feet per minute of atmosphere air through a glass fiber filter paper and a charcoal cartridge. The glass fiber filter paper is used for collection of airborne particulates, while the charcoal cartridge is used for collection of radioiodine. Samples are I collected on a weekly basis. I The charcoal cartridge is used in the weekly analysis of airborne iodine-131. The glass fiber filter papers are analyzed each week for gross beta, then composited by station each quarter for gamma spectrometry analysis. In order to reduce interference I from short-lived naturally occurring radioactivity (e.g. radon and thorium), the glass fiber filter papers are allowed to decay prior to performing beta analysis in a low background counting system. I

b. Procedures I Gross Beta Analysis of Filter Paper: Analysis is performed by placing the glass fiber filter paper from the weekly air sample in a 2-inch planchet followed by analysis in a I low background, gas flow proportional counter.

I Gamma Emitter Analysis of Filter Paper: Analysis is performed by stacking all of the glass fiber filter papers collected from each monitoring station during the quarter and scanning the composite on a high-resolution germanium gamma spectrometer. I Iodine-131 Analysis of Charcoal Cartridge: Analysis is performed by a gamma scan 11 of each charcoal cartridge. I I 2-23

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

3. Results and Conclusions I

A summary of data is presented in Table 2-2. I

a. Airborne Radioactive Particulates I Gross Beta: A total of four hundred sixteen (416) weekly samples from eight (8) locations were analyzed for gross beta. The results were comparable to that of I previous years. Figure 2-2 indicates the weekly average concentration of gross beta in air particulates. I Gamma Spectrometry: A total of thirty-two (32) quarterly samples were composited from eight (8) locations and analyzed for gamma spectrometry. Naturally occurring I beryllium-7 was identified in twenty-eight of twenty-eight (28 of 28) indicator samples, and four of four (4 of 4) control samples. No other gammas were identified.

A summary of the analysis results during the report period are listed in Table 2-2. A I trend graph of analyses (including the pre-operational period through the report period) is shown on Figure 2-2. I Deviations from Required Sampling and Analysis Schedule: There were two deviations from the required airborne particulate sampling and analysis schedule I during the report period. I During the sampling period of 04/10/17-04/17/17, REMP Air Particulate and Iodine sampling station at Brunton's Dairy in Aliquippa (Site No. 27, 6.16 miles SE) was found to be out of service. The cause was a tripped breaker on the totalizer due to I thunderstorms over the weekend. The breaker was reset during the change out for the next week. The sample station was out of service for approximately 22 hours as I reported by the REMP technician. (CR-2017-04551) During the sampling period of 12/1/17-12/18/17, REMP Air Particulate and Iodine I sampling station at Cook's Ferry Substation in Shippingport (Site No. 30, 0.5 miles ENE) was found to be out of service. The cause was a malfunctioning totalizer. The I components of the air station were replaced and returned to service. The sample station was out of service for approximately 70 hours as reported by the REMP technician. (CR-2017-08225) I During the sampling period of 07/31 /17-08/07 /17, REMP Air Particulate and Iodine I sampling station at Old Meyer Farm in Hookstown (Site No. 13, 1.49 miles SW) was found to be out of service. The cause was shattered carbon vanes. They were I 2-24 I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM replaced, and components of the air station were restored and returned to service. The I sample station was out of service for approximately 83 hours as reported by the REMP technician. (CR-2017-12347) I Summary: Based on the analytical results, the operation of BVPS did not contribute any measurable increase in air particulate radioactivity during the report period. I b. Airborne Radioiodine I Iodine-131 : A total of four hundred sixteen (416) weekly charcoal filter samples were analyzed for iodine-131. Iodine-131 was not identified in any of the three hundred

I sixty-four (364) indicator samples, nor was it identified in any of the fifty-two (52) control samples.

Deviations from Required Sampling and Analysis Schedule: The deviations are the same as described above for airborne particulates. Summary: Based on analytical results, the operation ofBVPS did not contribute any measurable increase in airborne radioiodine during the report period. I I 11 I I I I I I 11 2-25 I

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I Figure 2-1 Environmental Monitoring Locations - Air Sampling Stations I I

                                     *~*,, ... ,   . tfl l
  • f,.NJ I
                                                                     ',,                                                                                    I
                       ,1, l 'a t1*,1c , ~,II I

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            #48 not shown (10 mi radius shown)                                                                                                                f' l II I t 11*
                                                                                                                                                /\III I I

Sample Type Site No. Sector Distance (miles) Sample Point Description I 13 11-SW ' 1.49 Hookstown , PA (Old Meyer Farm) 27 30 32 7-SE 4-ENE 15-NW 6.14 0.43 0.75 Aliquippa , Pa (Brunton Farm) Shippingport, PA (Cook's Ferry Substation) Midland , PA (N orth Substation - Rt. 68) I Air Particulate & Radioiodine 46.1 47 2-NNE/ 3-NE 14-WNW 2.28 4.88 Industry, PA (McKeels Service - Rt. 68) East Liverpool , OH ( Water Department) I 48 10-SSW 16.40 Weirton , VW ( Water Tower, Collier Way) 51 5-E 8.00 Aliquippa, PA (Sheffield Substation) I 2-26 I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I Figure 2-2 Graph of Annual Average Concentration: Gross Beta in Air Particulates I  :::: ..-_-..-_

                      . _-__-_ -__-__-__-_-__-_ -__ -__-_-___-_-__-__-________ _ _ _____________-__-_-_-_-_--~-_-__--_-_-_- ----_-_-_*-1 I    '?0.16 u
    ~ 0.14 I    .e:
    ~ 0.12 a,

E

     ., 0.10                                                                                      --------------------------------------------------

I :a:,

    ~
    'C a,

0.08 --------------------- 8 o.oo I 0

    -[ 0.04 0.02 I         0.00 +-+--1-+--+---+--+-+--1-+--+---+--+-+--f-+--+--+--+-+--f-+--+--+--l-+--f-+--+--+--l-+--l---l-+--l--l-+-l---l-+--I--I
             "~     A      ,.q,        "       ?.,      b        ~       9J     "       r.>   b    "                  ~     b        "     2>    "   ~   ~  '.\
            ~,~*~,~~#~#~~~~~-#####~~~~
                                                                                                        ..-'ll  "

I Pre-Operational value (0 07 pCI i ci.blc meter) -

                                                                                               ---*--- Control Location Required LLD (0 0 1 pC I / ci.blc meter)

I I I I I I I I I 2-27

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM C. Monitoring of Shoreline Stream Sediment and Soil I

1. Characterization of Shoreline Stream Sediment and Soil I

The stream sediment (river bottoms) consists largely of sand and silt. Soil samples may vary from sand and silt to a heavy clay with variable amounts of organic material. I

2. Sampling Program and Analytical Techniques I
a. Program I Shoreline stream sediment was collected semi-annually above the Montgomery Dam, and near the BVPS outfall structure. A Ponar or Eckman dredge is used to collect the I sample. The sampling locations are also listed in Table 2-1 and are shown in Figure 2-3. I Although not required by the ODCM, soil samples were collected at each of the nine (9) locations in 2015 . In 2017, the locations were reduced from ten (10) to five (5), I as well as the sample frequency was revised from once per three years to once every five years. Soil was last sampled in 2015 and will be performed in 2020. At each location, twelve (12) core samples (3" diameter by 2" deep) are gathered at prescribed I

points on a 10 foot radius circle. Each location is permanently marked with reference pins. Each set of samples is systematically selected by moving along the radius in I such a manner as to assure representative undisturbed samples. Sampling locations are listed in Table 2-1 and are shown in Figure 2-3. I Shoreline stream sediment and soil are analyzed for gamma-emitting radionuclides. I

b. Analytical Procedures Gamma Emitter Analysis of Stream Sediment: Analysis is performed in a 300 mL I

plastic bottle and analyzed by gamma spectrometry. I Gamma Emitter Analysis of Soil: Although not required by the ODCM, analysis is performed in a 300 rnL plastic bottle and analyzed by gamma spectrometry. I I I 2-28 I

Beaver Valley Power Station RTL A9.690E I 201 7 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

3. Results and Conclusions I A summary of the analysis results during the report period are listed in Table 2-2. A trend graph of analyses (including the pre-operational period through the report period) is I shown on Figure 2-4 and Figure 2-5.

I a. Shoreline Stream Sediment Gamma Spectrometry: A total of four (4) sediment samples were analyzed by gamma I spectrometry during the report period. Naturally occurring potassium-40, thallium-208, lead-212, lead-214, bismuth-214, radium-226 and actinum-228, were detected in I two of two (2 of 2) indicator samples and two of two (2 of2) control samples. Cesium-137: Radionuclide cesium-137 was identified in two of two (2 of 2) indicator I samples and two of two (2 of 2) control samples. The results were comparable to that of previous years (current annual range = 0.05 to 0.08 picocurie / gram) and less than I the pre-operational level of 0.4 picocurie / gram. Also, because cesium-13 7 was identified at the control location (upstream), then it was not due to plant effluent releases and is most likely residual contamination due from previous nuclear weapons I tests. I Cobalt-58: Radionuclide cobalt-58 was identified in one of two (1 of 2) indicator samples and zero of two (0 of 2) control samples. The sample, which indicated cobalt-58, was obtained at the shore line of the BVPS Main Outfall Facility. The I result was comparable to the previous years (current annual range = LLD to O.14 picocurie / gram) and the data is slightly higher than the BVPS Main Outfall Facility I pre-operational level of 0.098 picocurie / gram. Cobalt-60: Radionuclide cobalt-60 was identified in two of two (2 of 2) indicator I samples and zero of two (0 of 2) control samples. The samples, which indicated cobalt-60, were obtained at the shore line of the BVPS Main Outfall Facility. The results were comparable to previous years (current annual range = 0 .12 to O.15 I picocurie / gram), and the data is currently lower than the BVPS Main Outfall Facility pre-operational level of 0.4 picocurie / gram. I Deviations from Required Sampling and Analysis Schedule: There were no deviations from the required sediment sampling and analysis schedule during the I report period. I I 2-29

I Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 11 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM 11 Summary: The identification of cobalt-58 and cobalt-60 m the shoreline stream sediment near the main outfall facility is not unusual because the plant discharges these radionuclides in liquid effluent releases. The analyses are consistent with II discharge data of authorized liquid effluent releases, and all liquid effluent releases during the report period did not exceed the release limits set forth in the ODCM. I

b. Soil I I Soil sampling is not an ODCM requirement. Soil was last sampled in 2015 and will be performed in 2020. I I

I I I I I I I I I I I 2-30 I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-3 I Environmental Monitoring Locations - Shoreline Sediments and Soil

                                         ,...,,, ,.,,   I l/111 l       J I         Cl.:i*     n

( * .' ,. , , I I (, I t: J I l a:; 1 Li*,* ,po ol I 2* I _,. I ( .' ,, 1-a*r ,en I I Harsh,JVtll V I ( ) _mpi*~ Rae o ,fl Cr

                ' . .,                                                            Sa P< r I                #48 not shown (10 mi radius shown)                                                  ;:m fort Ghntc,n I

i='i tW-,u, temo t1, (\ ,. " I Sample Type Site No. Sector Distance (miles) Sample Point Description I 30A 32A 4-ENE 15-NW 0.43 0.74 Shippingport, PA (Cooks Ferry Substation) Midland , PA (North Substation) Soil 46B 3-NE 2.66 Industry, PA (Willows Inn - Rt. 68) I 48 51A 10-SSW 5-E 16.40 7.99 Weirton , WV (Collier Way Water Tower) Aliquippa, PA (Sheffield Substation) I Sediment 2A 49A 12-WSW 3-NE 0.31 4.93 Shippingport, PA (BVPS Outfall Vicinity) Industry, PA (Upstream Montgomery Dam) I I 2-31

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-4 I Gra h of Annual Avera e Concentration: Cesium-137, Cobalt-58 & Cobalt-60 in Sediment 1000.00 I 100.00 - - - - - - * * * * * - - - - * - - ** -- - - --------------*--------**-*-*--- C

  ~

I ett 10 .00 ************-***************-----------*-*- --* - * - -*- - - - - -- - -***-***-****--**---******-**-****-**-***--****************-*-***-****************-**-***-*******- 0 Sa E I

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 "§ 0

0 Q. 1.00 -****--*-*--- -*-********--- I 0.10 I 0.01 +-+-+-+-+--+--+--t--t--t--it--i---l--+--+--+--+--+--+--+-+--+--+---+---+---+--+--+--+--+--+-+-+-+-+-+-+-+-+-t--i---1---1

              ~~#~#~##~#~~~~#~#~~~~~

I __ _. ___ Cs- 137 ._.__ Control Location Cs-137 Cs -137 Pre-ope rational Resu11s (O 4 pc11gm ) - - Cs-137 Required LLD ( 1BO pCl,gm) 100.00 -* - - I I 1000 - ~ - 1-- - - - - - - - - - - - - - - - * - * - - - *-- -* *--**- . *--- * - - - - * - - * * * - I

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           ..._o,*f:,
                  -            co-58                     Unit 2 Pre.Operational Mean Co-58 (O 098 pc11gm )      __..__ Co-60           * * * * * *
  • Unit 2 Pre.Operatlonal r..iean Co-00 (O 40 pc11gran)

I I 2-32 I

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-5 I Graph of Annual Average Concentration: Cesium-137 in Soil I

          "l-=--

I I 1.2 - -------------------------------; II -1 .0 E

     !?

0 E:

      ~ 0.8          ....

I 'C 0 0.6 0 a" I 0.2 ---*--- I 0.0 +--- - t -- - - t - - - - - - + -- - - + - - - t - - - - t - - - - - 1 1 - - - - - + - -- -+----+-- --+-----i

           .._o,"l'o I                                        ..-.- cs-137  _._ Control Location       Cs-137 Pre-operational (1 2 pCI/ gram)

I I I I I I I I I 2-33

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM D. Monitoring of Feedstuff and Foodcrops I

1. Characterization of Farm Products I According to the 2012 Census of Agriculture (ll, there were six hundred and forty-six (646) farms in Beaver County . Total market value of production was $20,913 ,000 .00 and of the total market I

value, $10,879,000.00 from crops and $10,035 ,000.00 from livestock. Some of the principal sources of revenue (>$25 ,000.00) are as follows: I Milk and Other Dairy Products from Cows $5,271,000.00 Grains, Oil Seeds, Dry Beans and Dry Peas $4,419,000.00 I Cattle and Calves $3 ,331 ,000.00 Other Crops and Hay $2,673 ,000.00 I Nursery, Greenhouse, Floriculture and Sod $1,989,000.00 Vegetables, Melons, Potatoes and Sweet Potatoes $826,000.00 .I Other Animals and Other Animal Products $89,000.00 Sheep, Goats and their Products Poultry and Eggs

                                                                                                         $59,000.00
                                                                                                         $38,000.00 I

Fruits, Tree Nuts and Berries Cut Christmas Trees, and Short Rotation Woody Crops Undisclosed Amount Undisclosed Amount I Horses, Ponies, Mules, Burros, and Donkeys Hogs & Pigs Undisclosed Amount Undisclosed Amount I Tobacco Undisclosed Amount I I ( 1) http://www .agcensus.usda.gov/Pu blications/2012/0nline_ Resources/County_ Profiles/Pennsy Ivan ia/cp42007. pdf I I I I I 2-34 I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I 2. Sampling Program and Analytical Techniques I a. Program I Feedstuff: Although not required by the ODCM, representative samples of feedstuff (cattle feed) are collected monthly from the nearest dairy farm (Brunton Dairy) and I analyzed by gamma spectrometry. See Figure 2-6. Foodcrops (leafy vegetables): Foodcrops are collected at garden locations during the I growing season. Leafy vegetables (e.g. cabbage) are obtained from Shippingport, Raccoon, Georgetown, and Industry, Pennsylvania. Samples are obtained from two I (2) additional locations based upon the highest predicted annual average ground D/Q when milk locations are unavailable. Samples are also obtained from the control location in Weirton, West Virginia. All samples are analyzed for gamma emitters by I gamma spectrometry. Samples are also analyzed by radiochemical analysis for iodine- I 31. I b. Procedures I Gamma Emitter Analysis of Foodcrops: Analysis is performed by scanning a dried, homogenized sample with a gamma spectrometry system. A high-resolution I germanium detector is utilized with this system. Samples of feedstuff and foodcrops are loaded into tare weight 150 or 300 mL plastic bottles or I-liter Marinelli containers, weighed and the net weight of the sample is determined prior to scanning I for gamma emitters. Gamma Emitter Analysis of Feedstuff: Although not required by the ODCM, analysis I is performed by scanning a dried, homogenized sample with a gamma spectrometry system. A high-resolution germanium detector is utilized with this system. Samples I of feedstuff and foodcrops are loaded into tare weight 150 or 300 mL plastic bottles or 1-liter Marinelli containers, weighed and the net weight of the sample is determined prior to scanning for gamma emitters. I Iodine-131 Analysis of Foodcrops: Analysis is performed by radiochemistry. A I stable iodide carrier is added to a chopped sample, which is then leached with a sodium hydroxide solution, evaporated to dryness and fused in a muffle furnace. The melt is dissolved in water, filtered and then treated with sodium hypochlorite. The I iodate is then reduced to iodine with hydroxylarnine hydrochloride and is extracted with toluene. It is then back-extracted as iodide into sodium bisulfite solution and I I 2-35

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM precipitated as palladium iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchet for low level beta counting.

3. Results and Conclusions A summary of the analysis results during the report period are listed in Table 2-2. A trend graph of analyses (including the pre-operational period through the report period) is I

shown on Figure 2-7.

a. F eedstuff Gamma Spectrometry: Although not required by the ODCM, a total of twelve (12) samples were analyzed by gamma spectrometry. Naturally occurring potassium-40 was identified in twelve of twelve (12 of 12) sample,s. Naturally occurring beryllium- I 7 was found in four of twelve (4 of 12) samples.

Deviations from Required Sampling and Analysis Schedule: There were no I deviations from the required feedstuff sampling and analysis schedule during the report period. I Summary: The data from the feedstuff analyses was consistent with previous data. Based on the analytical results, the operation of BVPS did not contribute any I measurable increase in radioactivity in the feedstuff during the report period. I

b. Foodcrops Iodine-131: A total of ten (10) samples were analyzed for iodine-131. No detectable I

concentrations were present in the ten ( 10) indicator samples or the one (1) control sample. I Gamma Spectrometry: A total of ten (10) samples were analyzed by gamma spectrometry. Naturally occurring potassium-40 was identified in ten or ten (10 of I

10) samples indicator samples and the one ( 1) control sample.

I Deviations from Required Sampling and Analysis Schedule: There were no deviations from the required foodstuff sampling and analysis schedule during the report period. I Summary: The data from the foodcrops analyses was consistent with previous data. I Based on the analytical results, the operation of BVPS did not contribute any measurable increase in radioactivity in the foodcrops during the report period. I 2-36 I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-6 I Environmental Monitoring Locations - Feedstuff and Foodcrops I I I 1'1 I I I '.*, I".'

, Q JI P I

I . I

              #48 not shown I         (5 mile radius shown)

I Sample Type Feed Site No. 27 Sector 7-SE Distance (miles) 6.16 Sample Point Description A liquippa , PA (Brunton Farm) 1O* *

  • Shippingport, PA I Food 15*

46* Georgetown , PA Industry, PA 48* *

  • Weirton , WV I * *
  • 2 locations based on hiohest predicted D/Q Individual garden locations may change based upon availability. The requirements are met as long as one garden is sampled from each of these commun ities.

I I 2-37

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-7 I Graph of Annual Average Concentration: Cesium-137 in Feedstuff and Foodcrops I 100 ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ I 10 *************---*********-----********--**-**** I I-;; 0 E I Ii 1 **-**-*******- *-**********-------****-- --- * --------****------****---********-*-*- **-**-*****--*-**--**-********-*-*--.! I I

 .2 j

0 0 I

   "                                                                                                                                                     _________J a.

0.1 I 0.01 +-t---t--+-+--+--+--+-+-+-t---t--+-+--+--+--+--+-t---t--+-+--+--+--+-+-+--t---t--+-+--+--+--+--+-t---t--+-+--+--+--i I

          ~~~ #~ ~#~##~#~~#~~¢~~~
               -- * --- Cs- 137 (Feedstull)              --+- Cs- 137 (Foodc rops)     Cs-137 Pre-operational Resuns - - Cs-137 Required LLD (60 pCl1l<g) Wet         I I

I I I I I I 2-38

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM E. Monitoring of Local Cow and Goat Milk I 1. Description - Milch Animal Locations I Samples of fresh milk are obtained from milch animals at locations and frequencies noted in Table 2-1 . The milk is analyzed for its radioiodine content, gamma emitters, I strontium-89 and strontium-90. Detailed field surveys are performed during the grazing season to locate and enumerate I milch animals within a five (5) mile radius of the site. Survey data for the most recent survey conducted is shown in Section 3, Land Use Census. I 2. Sampling Program and Analytical Techniques

a. Program Cow milk was collected from the one (1) reference dairy farm within a IO-mile radius of the BVPS, Brunton Dairy Farm (6.076 miles southeast) and one (1) control location dairy farm outside of the 10-mile radius, Windsheimer Dairy Farm (10.475 I miles south-southwest).

Dairy cow sampling is performed at Brunton Dairy since 2016, due to the closure of Halstead Dairy and Searight Dairy in 2014. Additionally, one goat location was available for sampling and samples were obtained at the Covert Residence (2.131 miles southwest). The dairies are subject to change based upon availability of milk or when more recent data (milch animal census, and/or change in meteorological conditions) indicate other locations are more appropriate. The milk samples are collected and analyzed biweekly when the animals are on pasture and monthly at other times. The monthly and/or biweekly sample is analyzed for principle gamma emitters (including cesium-13 7 by high resolution germanium gamma spectrometry), and iodine-131 high sensitivity analysis. Although not I required by the ODCM, the monthly and/or biweekly sample is also analyzed for strontium-89, strontium-90. I The location of each is shown in Figure 2-8 and described below. I I 2-39

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-4 I Local Cow and Goat Locations I Approximate Distance and Direction Collection Site Dairy Number of Animals being Milked from Midpoint between Unit 1 and Unit 2 Period I Reactor 25* Searight Dairy Dairy Closed end of January thru I 948 McCleary Road 2.107 miles SSW 27 Hookstown, PA Brunton Dairy 2013 December I January thru 3681 Ridge Road Aliquippa, PA 104 Cows 6.076 miles SE December I 96 Windsheimer Dairy 20 Windsheimer Lane 76 Cows 10.475 miles SSW January thru December I Burgettstown, PA 113* Halstead Dairy 104 Tellish Drive Dairy Closed beginning of 2014 5.184 miles SSW January thru December I Hookstown, PA Covert Residence January thru I 114 930 Pine Street (Route 168) 9 Goats 2.131 miles SW Hookstown, PA

  • Highest potential pathway dairies based on evaluation of deposition parameters December I

I I I I IiI I I 2-40 I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

b. Procedure I Iodine-131 Analysis of Milk: The milk samples are chemically prepared, and then analyzed with a low-level beta counting system.

I Gamma Emitter Analysis of Milk: This is determined by gamma spectrometry I analysis of a 1 liter Marinelli container of milk. Strontium-90 Analysis of Milk: Although not required by the ODCM, the milk I samples are prepared by adding a stable strontium carrier and evaporating to dryness, then ashing in a muffle furnace, followed by precipitating phosphates. Strontium is I purified in all samples by the Argonne method using 3 grams of extraction material in a chromatographic column. Stable yttrium carrier is added, and the sample is allowed to stand for a minimum of 5 days for the in-growth of yttrium-90 (Y-90). Yttrium is I then precipitated as hydroxide dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low-level beta counter to I infer strontium-90 activity. Strontium-89 Analysis of Milk: Although not required by the ODCM, the strontiurn-I 89 activity is determined by precipitating strontium carbonate (SrC03) from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting. I Chemical yields of strontium and yttrium are determined by gravimetric means. I 3. Results and Conclusions A summary of the analysis results during the report period are listed in Table 2-2. A I trend graph of iodine-131 and strontium-90 analyses (including the pre-operational period through the report period) is shown on Figure 2-9. I a. Strontium-89: Although not required by the ODCM, a total of sixty-three (63) milk samples were analyzed for strontium-89 during the report period. Strontium-89 was I not detected in any of the forty-two (42) indicator samples, nor was it detected in any of the twenty-one (21) control samples. I b. Strontiurn-90: Although not required by the ODCM, a total of sixty-three (63) milk samples were analyzed for strontium-90 during the report period. Strontium-90 was I detected in fourteen of forty-two (14 of 42) indicator samples and sixteen of twenty-I I 2-41

Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 11 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I one (16 of 21) control samples. The levels detected were attributed to previous nuclear weapons tests and are within the expected range. I

c. Gamma Spectrometry: A total of sixty-three (63) milk samples were analyzed by gamma spectrometry during the report period. Naturally occurring potassium-40 was present in thirty-two of forty-two (32 of 42) indicator samples and twenty-one of I

twenty-one (21 of 21) control samples. No other gamma-emitting radionuclides were identified during analysis. I

d. Iodine-131: A total of sixty-three (63) milk samples were analyzed for iodine-131 during the report period. Iodine-131 was not detected in any of the forty-two (42)

I indicator samples, but was it detected in one of twenty-one (21) control samples. This anomaly was under the reportable limit and was documented for trending. I

e. Deviations from Required Sampling and Analysis: There were two deviations from the required milk sampling and analysis schedule occurred for the reporting period.

I Sufficient milk samples were not available from locations within the 5 mile radius in I 2017. The unavailability of milk caused the REMP to not meet the ODCM sample requirements in l/2-0DC-2.03 and in l/2-0DC-3.03, Attachment Q Table 3.12-1 stating that a minimum of four (4) milk locations shall be sampled. This initiated the I ODCM requirement for sampling two (2) additional garden locations based upon the highest predicted annual average D/Q when milk locations are not available. I During the sampling period, 07/09/2017 - 07/15/201 7, REMP milk (goat) sampling location at the Covert' s Residence in Hookstown, PA (Site No. 114, 2.131 miles SW) I was unavailable. The owner and goats were out of town during the sampling period. (Notification 601078879, Line 6) I

f. Summary: Based on all the analytical results and the comparison to pre-operational I

levels, the operation of BVPS did not contribute any measurable increase m radioactivity in the milk during the report period compared to previous years. I I I I 2-42 I

I Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-8 I Environmental Monitoring Locations - Milk I I I I 01 l(o *. il I I .ll ::br ,j Ea , _,.. i: co . I I )

                                  }
                                                                                                 ' ( c:*

h I Ulp 3 r ,rt , . I I I I' Ch ton I 10 mile radius shown I Sample Type Site -No. Sector Distance (miles) Sample Point Description 27 7-SE 6.1 Aliquippa, PA (Brunton Farm) I Milk 96 114 10-SSW 11-SW 10.4 1.9 Burgettstown , PA (Windsheimer Farm) Hookstown , PA (Covert Residence) I I 2-43

Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-9 I 14.0 Gra h of Annual Avera e Concentration: Iodine-131 & Sr-90 in Milk I 12 .0

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                                   ~          Average at the Indicator Location         ---* --- Control Location                               1-131 Pre-Operatlcnal value (O 6 pa / lite
                                  - 131 RequlredLLD (1 pCl 111ter)                  - 131 Reporting Levll (3 pCI , liter')

I 10 9 ----*--*- I I 8 -**************-**-**-***- - - - - - - - - - * - - - - 7 *****-*-**-***-****--*************-----*********---- - - -- - - - - -- - 5

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                     **********-************--*-*******--**--*--****-*--*----~                   -     - - --       - - -*- - - - *-*-**********...:k ... -.:.=..-.*--**-~ ~....._ ..._ _~ --

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         ..._o,'l.<o I

_,,.__ Avg of Indic ator ux: ations -- -. --- Control Loc ation Sr-90 Pre-Operational value (5 3 pCi I liter) I I 2-44 I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM F. Environmental Radiation Monitoring I 1. Description of Regional Background Radiation and Sources I Historical information for regional background was obtained from Reuter-Stokes instruments that were previously located within a five (5) mile radius of the BVPS site. I Data is no longer available from these instruments, but historical data indicated that the background exposure rates ranged from 6 µR/hr to 12 µR/hr. I The sources of background radiation are affected by the terrain in the vicinity of BVPS, whereas, the local hills (i.e. altitude variations of 300-400 feet) and densely wooded areas I contribute to variations in background radiation. Other sources (e.g. radon) are affected by the geological features of the region, which are characterized by nearly flat-laying sedimentary beds of the Pennsylvania age. For information, the local sedimentary beds I of limestone alternate with sandstone and shale with abundant interbedded coal layers. Pleistocene glacial deposits partially cover the older sedimentary deposits in the I northwest. Most of the region is underlain by shale, sandstone, and some coal beds of the Conemaugh Formation. Outcrops of sandstone, shale, and limestone of the Allegheny Formation exist within the Ohio River Valley and along major tributary streams. I 2. Locations and Analytical Procedures I Ambient external radiation levels around the site were measured using TLDs. I During the report period, there were a total of sixty-six (66) environmental TLD locations. This is comprised of forty-four (44) offsite locations, along with twenty-two I (22) fence perimeter locations. The offsite TLD locations are plotted on Figure 2-10, but the fence perimeter locations are not plotted due to the large scale of the figure. I The TLDs were annealed at the Contractor Central Laboratory shortly before placing the TLDs in their field locations. The radiation dose accumulated in-transit between the I Central Laboratory, the field location, and the Central Laboratory was corrected by transit controls maintained in lead shields at both the Central Laboratory and the field office. All dosimeters were exposed in the field for a calendar quarter, in a specific I holder that contains two (2) TLDs at each location. I I I 2-45

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2- ENVIRONMENTAL MONITORING PROGRAM

3. Results and Conclusions I

A summary of the TLD results during the report period are listed in Table 2-2. A trend I graph of analyses (including the pre-operational period through the report period) is shown on Figure 2-11. I TLD Analysis: During the report period, the average quarterly external exposure rate (as measured from TLD) was 18.9 mR at the sixty-six (66) indicator locations, and 19.5 mR I at the control location. This external exposure rate is comparable to previous years. As expected, there was some variation in external exposure rate among locations and seasons. I Deviations from Required Sampling and Analysis Schedule: There was one deviation from the required direct radiation monitoring schedule during the report period. On Thursday January 5, 2017, the REMP technician was performing the scheduled quarterly TLD changeout. During the work, it was noticed that Station #94 (McCleary Road & Pole Cat Hollow Rd, 2.37 miles SSW) was missing both of its two TLDs for the 4th quarter for 2016. The TLDs have been replaced at this location for 1st quarter collection (CR-2017-04706). I Summary: The quarterly TLD external exposure rates are comparable to that of the previous decade. There was no evidence ,of anomalies that could be attributed to the I operation of BVPS. It should also be noted that the average external exposure rate at the indicator locations was less than average external exposure rate at the control location. Based on all the analytical results and the comparison to pre-operational levels, the I operation of BVPS did not contribute any measurable increase in external exposure in the vicinity of the site during the report period. The TLD exposure rates also confirm that I changes from natural radiation levels, if any, are negligible. I I I I I 2-46 I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-10 I Environmental Monitoring Locations - TLDs I ' \I II 't I Cl It !:O I

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I I I I 2-47

Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9. 690E Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-10 (Continued) I TLD Locations NORTHEAST QUADRANT I I Site Distance Site Di stance Sector Location Sector Location No. (miles) No. (miles) 10 3-NE 0.94 Post Office 70 1-N 3.36 236 Engle Road 4-ENE Shippingport, PA Industry, PA 1-N 8.60 Shennan Fann 71 2-NNE 60 1 First Western Bank I 28 Brighton Twp, PA Brighton Township, PA 298 3-NE 7.97 Friendship Ridge 72 3-NE 3.25 Ohiov iew Lutheran Church - Rear Beaver, PA Raccoon Twp, PA 30 4-ENE 0.43 Cook ' s Ferry Substation 73 4-ENE 2.48 61 8 Squirrel Run Road 45 5-E 2.19 Shippingport, PA Christian House Baptist C hapel, State Rte 18 Raccoon Township, PA 74 4-ENE 6.92 Monaca, PA 137 Poplar Avenue (CC BC) Monaca, PA I 46 3-NE 2.49 Midway Drive 75 5-E 4.08 11 7 Holt Road

46. 1 2-NNE 3-NE 2.28 lndustrv, PA McKeel' s Serv ice, State Route 68 lndustrv, PA 91 2-NNE 3.89 Aliquippa, PA Pine Grove Road & Doyle Road Industry, PA I

SOUTHEAST QUADRANT Site No. 27 Sector 7-SE Distance (miles) 6.14 Brunton Dairy Fann Location Site No. 78 Sector 7-SE Distance (miles) 2.72 Location Racoon Twp Municipal Building I Aliquippa, PA Raccoon Township, PA

45. 1 51 6-ESE 5-E 1.92 8.00 Kennedy' s Comers Raccoon Township, PA Sheffield Substation 79 80 8-SSE 9-S 4.46 8.27 I 06 State Route 15 1 Green Twp.

Aliquippa, PA Park Office, State Route 18 I Aliquippa, PA Raccoon Township, PA 59 76 6-ESE 6-ESE 0.99 3.80 236 Green Hill Road Aliquippa, PA Raccoon Elementary Schoo l 82 94 9-S 8-SSE 6.99 2.25 2697 State Route 18 Raccoon Twp, PA McCleary & Pol e Cat Hollow Road I Raccoon Township, PA Hookstown, PA 77 6-ESE 5.52 36 14 Green Garden Road Aliquippa, PA SOUTHWEST QUADRANT I Site Distance Site Di stance No. 13 Sector I I-SW (miles) 1.49 Ol d Meyer Fann Hookstown, PA Location No. 84 Sector II-SW (miles) 8.35 Senior Center Location Hancock County, WV I 14 I I-SW 2.53 Hookstown, PA 85 12- 5.73 2048 State Route 30 48 10-SSW 16.40 Coll ier Way Water Tower Weirton, WV 92 WSW 12-WS W 2.8 1 West Chester, WV Georgetown Road Substation Georgetown, PA I 81 9-S 3.69 Mi ll creek United Presbyterian Church 95 IO-SSW 2.37 832 McC leary Road 83 10-SSW 4.26 Hookstown, PA 735 Mill Creek Road, Hookstown, PA NORTHWEST QUADRANT Hookstown, PA I Site Dis tance Site Di stance No. 15 Sector 14-WNW (miles) 3.75 Post Office Georgetown, PA Location No. 87 Sector 14-WN W (miles) 7.04 Locati on 50 I 03 Calcutta Smith Ferry Road Calcutta, OH I 32 15-NW 0.75 North Substati on 88A 15-N W 2.8 Route 168 47 14-WNW 4.88 Midland, PA Water Department East Liverpool, OH 89 15-NW 4.72 Midland Heights PA 488 Smith 's Ferry Road Ohioville, PA I 60 13-W 2.5 1 444 Hill Road 90 16-NN W 5.20 6286 Tuscarawras Road 86 13-W 6.18 Georgetown, PA 1090 Ohio Avenue East Liverpool, OH 93 16-NN W I. I 0 Midl and, PA I 04 Linden - Sunrise Hills Midl and, PA I I 2-48 I

I Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-11 I Graph of Annual Average Exposure: Direct Radiation in Environment II 0.24 - - - * - * - - -* 11 0.22 -*-**-*--- .. *- * * - -...... _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ 0.20 I  ! 0.18 E I f E 0.16 - - - - * * - - - -* I 0.14 -----**----**-*---*****- 0.12 - - - - - * * -*- - - -----*----**-*--*-*-*- ..****--*-***---**-****....- ....- ......... . I 0.10 +--+--+---<,--+,--+--+-+-+--+--+--+--+--+--+-+--+--+--.........._--+-+-+--+--+--+--+--+--+-+--+--+--..........--+--+--+-+-<

         #~ # ~# # #~~~~~~ ~ ~~~~~~

I - Average or 66 lndlcator Loc ations ---* --- Control Location (Wel~on WV) Pre-Operational Value (0 2 mrem , day) I I I I I I I I I 2-49

Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I G. Monitoring of Fish

1. Description I

During the report period, fish species collected for the radiological monitoring program included rock bass, striped bass, channel catfish, bullhead catfish, brown catfish, and *1 freshwater drum. I

2. Sampling Program and Analytical Techniques
a. Program I

Fish samples are collected semi-annually in the New Cumberland pool of the Ohio I River at the Beaver Valley effluent discharge point and upstream of the Montgomery Dam. The edible portion of each species caught is analyzed by gamma spectroscopy. Fish sampling locations are shown in Figure 2-12. I

b. Procedure I A sample is prepared in a standard tare weight 300 rnL plastic bottle and scanned for gamma emitting nuclides with gamma spectrometry system which utilizes a high-resolution germanium detector.

I

3. Results and Conclusions I A summary of the analysis results during the report period are listed in Table 2-2. A trend graph of analyses (including the pre-operational period through the report period) is I

shown on Figure 2-13 . I Gamma Spectrometry: A total of nine (9) fish samples were analyzed by gamma spectrometry during the report period. Gamma emitting radionuclides were not detected in any of the five (5) indicator samples, nor were they detected in any of the four (4) I control samples. I Deviations from Required Sampling and Analysis Schedule: There were no deviations from the required fish sampling and analysis schedule during the report period. I Summary: Based on the analytical results, the operation of BVPS did not contribute any measurable increase in radioactivity in the Ohio River fish population during the report I period. I 2-50 I

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-12 I Environmental Monitoring Locations - Fish I  ! I Ir I 1d < d I ~

                                                          ~

I I I nl ' t*lhn I I r I [l@;] I I 5 mile radius shown I Sample Type Site No. 2A Sector 12-WSW Distance (miles) 0.31 Sample Point Description BVPS Outfall Vi cinity Fish I 49A 3-NE 4.93 Industry, PA (Upstream Montgomery Dam) I 2-51

Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9 .690E Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-13 I Graph of Annual Average Concentration: Cesium-137 in Fish I 10000.000 1000.000 I 100.000 ------------------------------- - - -- -- - - - - - - - - - - - - - - - - - - - - - - ----**-****----*******-*****-*-****-----*-************ I E 10.000 -------------------- ----------------***-***-****-----****---------------- I I! I 0 1.000 ------------------- - - - - - - - - - - - - - - * * * - - * ***--***-***-**-****-------------

 "C 0

0 Q. 0.100 -------------------------- ----- I I

                       ---* --- Cs-137
                       - - Requlrl!d LLD (150 pCI / gm )

_._. Control Location- Mootgomery Dam

                                                                 - - Repor1lng Level (2000 pCI I gm)

Unit 2 Preq.,erauaial (0 014 pCi , gn I I I I I I I I 2-52 I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM H. Monitoring of Surface Water, Drinking Water, Groundwater, and Precipitation I 1. Description of Water Sources I The Ohio River is the main body of water in the area and is the main surface water supply for drinking water in the area. The Beaver Valley Power Station obtains water I from the Ohio River for plant make-up water and discharges water to the Ohio River via National Pollutant Discharge Elimination System (NPDES) discharge points (e.g. cooling tower blowdown, liquid effluent releases, etc.). I The Ohio River is the main surface water supply source for towns, municipalities, and I industries both upstream and downstream of the BVPS site. The nearest user of the Ohio River as a potable water source is Midland Borough Municipal Water Authority. The intake of the treatment plant is approximately 1.5 miles downstream of the Midland I Borough Municipal Water Authority and is located on the opposite side of the river. The next downstream user is East Liverpool, Ohio and is approximately 6 miles downstream. I The heavy industries in Midland, as well as other users downstream, also use river water for cooling purposes. I Groundwater occurs in large volumes in the gravel terraces which lie along the river, and diminishes considerably in the bedrock underlying the site. Normal well yields in the I bedrock are less than ten (10) gallons per minute (gpm) with occasional wells yielding up to 60 gpm. I In general, the BVPS site experiences cool winters and moderately warm summers with ample annual precipitation evenly distributed throughout the year. The National Climate I Data Center indicated the total annual precipitation during the report period for the Beaver Falls, PA area was 37.2 inches. I 2. Sampling and Analytical Techniques I a. Surface (Raw River) Water The sampling program of river water included three (3) sampling points along the I Ohio River for most of 2016. In December 2016, one of the locations closed in which the program now includes two (2) sampling points. I Furthermore, Site No. 2.1 , Sector 14, Midland - ATI Allegheny Ludlum, the downstream sample, is no longer a viable sample location. ATI permanently closed I the Midland facility in 2016. As of December 2016, surface water samples were no I 2-53

Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2 - ENVIRONMENT AL MONITORING PROGRAM I longer available. Site No. 5, Sector 14, East Liverpool Water Department was an additional downstream sample location in which grab samples were taken. The East Liverpool site was transitioned to a composite sample location thus replacing A TI I Allegheny Ludlum. Raw water samples were collected daily at the Water Treatment Plant in East I Liverpool, OH, sample location 5, [River Mile 41.2], and then made into a weekly composite sample. Now the water sample is collected with a composite water I sampler. .The automatic sampler takes a 20-40 mL sample every 15 minutes and samples are collected on a weekly basis. The weekly samples are then combined for a monthly composite sample for each location. The monthly composite samples are I analyzed for gamma emitters. In addition, a quarterly composite sample is prepared from the monthly composites for each sample point. Quarterly composites are I analyzed for hydrogen-3 (tritium). One automatic river water sampler that was located at the ATI-Allegheny Ludlum (formerly J&L Steel) river water intake, sample location 2.1 , [River Mile 36.2] and was transitioned to East Liverpool due to I the closing of the facility . I A weekly grab sample is taken upstream of the Montgomery Dam, sample location 49 [River Mile 29.6]. This upstream sample at the Montgomery Dam is the control sample. The weekly grab samples upstream of the Montgomery Dam are analyzed for I iodine-131 . Weekly grab samples are then made into monthly composites and are analyzed for gamma emitters. Quarterly composites are prepared from each of the I monthly composites. The quarterly composites are analyzed for tritium. Locations of each sample point are shown in Figure 2-14. I

b. Drinking Water (Public Supplies)

I Drinking water (i.e. treated water) is collected at both the Water Treatment Plant in Midland, PA, sample location 4, and the Water Treatment Plant in East Liverpool, OH, sample location 5. An automatic sampler at each location collects 20-40 mL I every 20 minutes, which is then combined for a weekly composite sample. The weekly composite sample from each location is analyzed for iodine-131. Monthly I composites are prepared from the weekly samples and are analyzed by gamma spectrometry. In addition, a quarterly composite sample is prepared for each sample 11 point from the monthly composites. Quarterly composites are analyzed for tritium. A weekly grab sample is taken upstream of the Montgomery Dam, sample location 49A [River Mile 29.6]. This upstream sample at the Montgomery Dam is the control I sample. The weekly grab samples upstream of the Montgomery Dam are analyzed for iodine-131 . Weekly grab samples are then made into monthly composites and are I 2-54 I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM analyzed by gamma spectrometry. Quarterly composites are prepared from each of I the monthly composites. The quarterly composites are analyzed for tritium. Locations of each sample point are shown in Figure 2-14. I c. Groundwater I For historical information, groundwater was collected semiannually by grab samples at locations within four (4) miles of the site (see Figure 2-14), one (1) well in Hookstown, PA and one (1) well in Georgetown, PA. Each ground water sample was I analyzed for tritium and is analyzed by gamma spectrometry. I d. Precipitation For historical information, prec1p1tation was collected in Shippingport, PA, East I Liverpool, OH, and Weirton, WV. Precipitation, when available, was collected each week and combined for quarterly composite samples from the weekly samples. The I quarterly composites were analyzed for tritium and gamma emitters.

e. Procedures I Gamma Analysis of Drinking Water and Surface Water: The analysis is performed by I placing one liter of the sample into a Marinelli container and analyzing on a high-resolution germanium gamma spectrometry system. Although not required by the ODCM, this analysis is also performed on groundwater and precipitation samples.

I Tritium Analysis of Drinking Water and Surface Water: The tritium is determined in I water samples by liquid scintillation analysis. Although not required by the ODCM, this analysis is also performed on surface water, groundwater and precipitation samples. I Iodine-131 Analysis of Drinking Water: The sample is chemically prepared and I analyzed with a low-level beta counting system. Although not required by the ODCM, this analysis is also performed on surface water samples. I I I I 2-55

RTL A9.690E Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

3. Results and Conclusions I

A summary of the analysis results of water samples (surface water, drinking water, I ground water, and precipitation) during the report period are listed in Table 2-2. A trend graph of analyses (including the pre-operational period through the report period) is shown in Figures 2-15 through 2-18. I

a. Surface Water I

Tritium: A total of eight (8) surface water samples were analyzed for tritium during the report period. Tritium was not detected in the four (4) indicator samples, nor was I it detected in the four (4) control samples. I Gamma Spectrometry: A total of twenty-four (24) surface water samples were analyzed by gamma spectrometry during the report period. Gamma emitting radionuclides were not detected in the twelve (12) indicator samples, nor were they I detected in the twelve (12) control samples. I Iodine-131: Although not required by the ODCM, a total of twenty-six (26) surface water control samples were analyzed for iodine-131 using radiochemical methods during the report period. Iodine-131 was detected in three of twenty-six (3 of 26) I weekly control samples, of which zero (0) analysis exceeded the reporting level of 2 picocurie / liter. The results were similar to previous years, (current annual range = I 0.3 to 1.3 picocurie / liter). The positive results were detected at the control location, which is five (5) miles upstream (not influenced by BVPS operation). Identification of iodine-131 during the report period was most likely due to medical diagnostic and I treatment procedures performed at upstream facilities . I

b. Drinking Water Tritium: A total of twelve (12) drinking water samples were analyzed for tritium I

during the report period. Tritium was not detected in the eight (8) indicator samples and was not detected in any of the four (4) control samples. I Gamma Spectrometry: A total of thirty-six (36) drinking water samples were analyzed by gamma spectrometry during the report period. Gamma emitting I radionuclides were not detected in any of the twenty-four (24) indicator samples, nor were they detected in any of the twelve (12) control samples. I I 2-56 I

I Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Iodine-131: A total of fifty ( 50) drinking water samples were analyzed for iodine-131 I (using radiochemical methods) during the report period. Iodine-131 was detected in one of fifty ( 1 of 50) indicator samples and three of twenty-six (3 of 26) surface water control samples. There was one positive result at the downstream location that was I similar to the positive results from the upstream surface water control location, and none of these analyses exceeded the reporting level of 2 picocurie / liter. Because I positive results were detected in the upstream control sample, some positive results are most likely due to medical diagnostic and treatment procedures performed at upstream facilities, and not caused by BVPS operations. I c. Groundwater I Since these samples are not required, they will no longer be collected as of 201 7.

d. Precipitation I Since these samples are not required, they will no longer be collected as of 2017.

I e. Deviations from Required Sampling and Analysis Schedule: There was one deviation from the ODCM required water sampling and analysis schedule during the report. I During the sampling period of 09/05/17-09/12/17, REMP Drinking water sampling station at Midland Water Department in Midland (Site No. 4, 1.26 miles NW) was I found to be out of service. The cause was the timing component that triggers the sample collection. No sample was lost because the trigger failed open causing the collection container to overflow. The component was replaced, and the water sampler I was returned to service. The sample station was out of service for approximately 4 hours while performing maintenance as reported by the REMP technician (CR-2017-I 09446).

f. Summary: Data from the water sample analyses demonstrate that BVPS did not I contribute a significant increase of radioactivity in the local river, in the drinking water, in the well water, or in the precipitation. The analytical results confirm that I the station assessments, prior to authorizing radioactive discharges, are adequate and that the environmental monitoring program is sufficiently sensitive.

I I I I 2-57

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-14 I Environmental Monitoring Locations - Surface Water and Drinking Water I I r Cr *k Off:!*( I t* .. I I I I pping O l I ( 'I O i I I ock!: OW i I I I I 17 :ile radius shown I Site Distance Sample Type No. 4 Sector 15-NW (miles) 1.26 Sample Point Description Midland, PA (Water Department) I Drinking Water 5 5 14-WNW 14-WNW 4.90 4.90 East Liverpool , OH (Water Department) East Liverpool , OH (Water Department) I Surface Water 49A 3-NE 4.93 Industry, PA (Upstream Montgomery Dam) I 2-58 I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-15 I Graph of Annual Average Concentration: Iodine-131 in Surface Water & Drinking Water 25 I 2.0 ----------------------------------------t I s

      ~ 15 I       ~
      'C 0

f 10 I I Site 2.1 no longer available 00+-................................................_ .......-+-......-+--+--+--+--+-+-+--+--1--<--+-+-+-+-+-+--+--+--+--+--+--+--+-+-+--+--,_.. I #~##~~#~~~~~~~#~#~~~~

                               - . - Down Stre.-n Dr1nklng Water
  • Midland - Down Strean Drinking Wau,* . East Liverpool __.,_. Control l ocation . Up Strean Surface waier Unit 2 OW Preoperationa (0 23 pCI / liter) - ReqUlred LLD (1 pCI , 11ter) - - Reporting Leve (2 pCI I ,ie~

I Figure 2-16 Graph of Annual Average Concentration: Tritium in Surface Water I 100000 I I - 10000

                                                                                        ,          \
                                                                                                    \

0 E:

                                                         /'*-           .', ~..       ,/
       ;i:

1000 *-----~

                              . ... ,/

I ';;

       '§ 0

0 Q.

                                       ---.. i I                 100 I                  10 +-+--1--<--+-+-+-+--+--+--+--+--+-+ -+--<>-+-+-+-+--+--+--+--+-+-+--+--<--+-+- +-+--+--+--+--+--+-+-+--1--<--t
                   ..._o,'{o I                             --- * --- Indicator Mean (pC1 fl )
                             - - Requi red LLD C2 000 pCI~)

___.._ Control Location (pCi , I)

                                                                                   - - Reportln Leva Su/face \'later (30 000 pCt,1)

Pre- Operauonal (300 pCl1I) I I 2-59

Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-17 I 100000 Graph of Annual Average Concentration: Tritium in Drinking Water I Ii

   -u 10000 I
    ~
    ~
     ~

0 I 8 a. 100 I I 10 +-+--+--l--l--t-+-+-+--+--t--+--t--+--+-+-+-+--t-------1--t--t-+-+--+--t---t--t--t--+--+-+-+--+--t--l--l--t-+-+--+-i

                          -- ... --- lndlcanr f.1ean
                         - - Required LLD (2 000 pCl1l)

__.__ Control LOC a t1on (pC1I I)

                                                                         - - Reporting Level Drwlking w ater (20 000 pCIII)

Pre. Operanaial (31 0 pCl!I) I Figure 2-18 Graph of Annual Average Concentration: Tritium in Groundwater I 1UUOOO I 10000 I

      -g I;
       ~

Control Location No Longer Available I 1UUU

      !0 I

5. I Groundwater sampling no longer conducted 10 - t --t

                  ,°'"<o '°'"'I:,
                                         -r
                                          '°',§>
                                                 --t   - t
                                                         '°l:,'I,
                                                                                                                          ..--+ - I          ,-             - - t--,-               I 111.lllo.llOI f,h.*m q~1 I I)
                               - ..:qui*t.:d LLD {2 000 l)C1!I)
                                                                           -     Cor>ll'.JI lUl d l.:.>f
  • u.<"1, *i
                                                                          - - 111..-~v-1\ n Lt.:vd C*uurnJ.\ Jl.1..1 (J.0 000 .,C t1t)

I I 2-60 I

I Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I. Estimates of Radiation Dose to Man 11 1. Pathways to Man - Calculation Models I The radiation doses to man as a result of BVPS operations were calculated for both gaseous and liquid effluent pathways using computer codes for the ARERAS/MIDAS computer system. These computer codes are equivalent to NRC computer codes I XOQDOQ2, GASPAR, and LADTAP. Dose factors listed in the ODCM are used to calculate doses from radioactive noble gases in discharge plumes. BVPS effluent data, I based on sample analysis were used as the radionuclide activity input. All liquid and gaseous effluent radionuclides listed in the Annual Radioactive Effluent I Release Report were used as input source terms to the computer codes. All batch and continuous gaseous effluent releases were included in the dose assessment I calculations. The release activities are based on laboratory analysis. Meteorological data collected by the BVPS Meteorology System was also used as input to the computer I codes. The usage factors were obtained from the BVPS Final Environmental Statements or Regulatory Guide 1.109, except when more recent or specific data was available. I All radioactive liquid effluents are released by batch mode after analysis by gamma spectrometry. Each batch is diluted by cooling tower blowdown water prior to discharge into the Ohio River via the main outfall [River Mile 35.0]. The actual data from these I analyses are tabulated and used as the radionuclide source term input to the computer code. The usage factors were obtained from the BVPS Final Environmental Statements I or Regulatory Guide 1.109, except when more recent or specific data was available. The total population doses were evaluated for all liquid and gaseous effluent pathways up I to 50 miles. For these evaluations, a total population of approximately 4 million people was used. An estimate of the populations are listed in the BVPS-2 UFSAR Section I 2.1.3.1 for 0-10 miles and Section 2.1.3.2 for 10-50 miles.

2. Results of Calculated Population Dose to Man - Liquid Effluent Releases I During the report period, the calculated dose to the entire population within 50 miles of the plant is presented in Table 2-4 for BVPS liquid effluent releases. Also shown in the I Table 2-6 is a comparison to natural radiation exposure.

I I I 2-61

Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2- ENVIRONMENTAL MONITORING PROGRAM I

3. Results of Calculated Population Dose to Man - Gaseous Effluent Releases During the report period, the calculated dose to the entire population within 50 miles of I the plant is presented in Table 2-5 for BVPS airborne effluent releases. Also shown in the Table 2-6 is a comparison to natural radiation exposure. The doses include the contribution of all pathways.

I

4. Conclusions I Based upon the estimated dose to individuals from the natural background radiation exposure in Tables 2-4 and 2-5 , the incremental increase in total body dose to the 50-mile I population from the operation of BVPS - Unit 1 and 2, is 0.00000403% of the annual radiation exposure. I The calculated doses to the public from the operation of BVPS - Unit 1 and 2, are below ODCM annual limits and resulted in only a small incremental dose to that which area residents already received as a result of natural background. The doses constituted no I

meaningful risk to the public. I I I I I 2-62

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-5: Calculated Population Dose to Man I Liquid Effluent Releases 0-50 mile Population Dose from BVPS Liquid Effluent Releas es I Man-millirem Largest Isotope Contributor Total Dose 61 Tritium I Average Dose (oer Individual) 0.0000153 Tritium I Comparison of Individual Dose BVPS Liquid Effluent Releas es Versus I Natural and Medical Radiation Exposure millirem BVPS Liquid Effluent Release Dose 0.0000153 I Radiation Exposure 620 I Table 2-6: Calculated Population Dose to Man Gaseous Effluent Releases I 0-50 mile Population Dose from BVPS Gaseous Effluent Relea ses Largest I Total Dose Man-millirem 39 Isotope Contributor Tritium I Average Dose (per Individual) 0.0000097 Tritium I Comparison of Individual Dose BVPS Gaseous Effluent Relea ses Versus Natural and Medical Radiation Exposure I BVPS Gaseous Effluent Release Dose millirem 0.0000097 I Radiation Exposure 620 I I I I 2-63

Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I Table 2-7: Natural and Medical Radiation Exposures TYPICAL DOSE TO INDIVIDUALS I FROM RADIATION EXPOSURE (a) I Ubiquitous background Internal, inhalation

                                                           = 311 millirem I year 228 millirem / year I

Internal, ingestion External, space 29 millirem I year 33 millirem I year I External, terrestrial 21 millirem / year Medical CT 300 millirem I year 14 7 millirem I year I Nuclear medicine lnterventional fluoroscopy 77 millirem I year 43 millirem I year I Conventional radiography 33 millirem I year Consumer = 13 millirem I year I Industrial, security, educational, research = 0.3 millirem I year Occupational Average Individual 0.5 millirem I year

                                                           = 620 millirem / year I

(Total from all sources shown above) (a) NCRP Report No. 160: Ionizing Radiation Exposure of the I Population of the United States." Journal of Radiological Protection J. Radio!. Prat. 29.3 (2009) I I I I I I I 2-64 I

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 3 - LAND USE CENSUS A. Land Use Census Overview: A Land Use Census was conducted June 1 through September 1, 2017 to comply with:

  • Offsite Dose Calculation Manual procedure l/2-0DC-3.03, "Controls for RETS and REMP Programs ", Attachment R, Control 3.12.2, and Surveillance Requirement I 4.12.2.1
  • BVPS REMP procedure 1/2-ENV-04.02, "Milch Animal Sampling Location I Determination & ODCM Procedure 1/2-0DC-3. 03, Control 3.12.2 Action Statements a and b Compliance Determination "

I The Land Use Census indicated that no changes were required in the current sampling locations, and no changes were required to the methodology used for determination of I offsite dose from plant releases. A numerical summary of the Land Use Census results are provided in Table 3-1. The following information is also provided to clarify the Land I Use Census as documented in letter NPD3NRE:1250, dated October 27, 2017: B. Nearest Residence: The location has not changed since the previous census. The nearest I inhabited residence is 209 Ferry Hill Road, Shippingport, PA (0.438 miles, east-northeast). I C. Nearest Garden >500 sq ft: The location has changed since the previous census. The closest garden location is now the Colaber Residence, 1201 Virginia Avenue, Midland, I PA (1.03 miles, northwest). The previous sampling location at the Cox Residence, 238 State Route 168, Hookstown, PA (0.76 miles, south-southwest) was available for I sampling cabbage this year but does not meet all the requirements of NUREG-1301 Ref (h), I D. Nearest Dairv Cow: The location has not changed since the previous census. The location remains at Brunton Dairy, 3681 Ridge Road, Aliquippa, PA (6.076 miles, I southeast). E. Nearest Doe Goat: The location has not changed since the previous census. The closest I location is the Covert Residence, 930 Pine Street, Hookstown, PA (2.131 miles, southwest). I I 3-1 I

Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 3 - LAND USE CENSUS I F. Projection for 2017 Dairy Cow Sampling Locations: Using a linear regression analysis of deposition parameters (D/Q), Dairy Cow sampling locations were determined I to remain at the same locations used in 2017: Brunton Dairy, 3681 Ridge Road, Aliquippa, PA (6.076 miles southeast) Windsheimer Dairy, 20 Windsheimer Lane, Burgettstown, PA (10.475 miles south-I southwest) I G. Projection for 201 7 Doe Goat Sampling Locations: The linear regression analysis also indicated that there will be a Doe Goat sampling location in 201 7. The Doe Goat sampling location for 2017 may be as follows if Goat Milk continues to be available from I this site: Covert Residence, 930 Pine Street, Hookstown PA (2.131 miles, southwest) I H. D/0 for Milch Animal Locations: None of the 2017 milch animal sampling locations experienced a >20% increase in D/Q. Therefore, a Special Report per ODCM procedure l/2-0DC-3.03 , Attachment R, Control 3.12.2 Action "a" and/or Action "b" was not I required. I I. D/0 for Offsite Dose Determination: There was no adverse effect on the current ODCM methodology used for offsite dose determination from effluent releases. Specifically, the analysis of D/Q did not yield any valid locations where the offsite dose I could have increased >20% of the offsite dose previously calculated using current ODCM methodology. Therefore, a Special Report per ODCM Control 3.12.2 Action "a" I and/or Action "b" is not required. J. D/0 Historical Comparison: There is no adverse trend in D/Q when comparing 2003 to I 2017 data to the ODCM default D/Q values. This validates that there is no adverse effect on the current ODCM methodology used for offsite dose determination from effluent I releases. Specifically, the analysis of D/Q did not yield any valid locations where the offsite dose could have increased >20% of the offsite dose previously calculated using current ODCM methodology. Therefore, a change in ODCM receptor location and/or a I change to meteorology at the current ODCM receptor location are not required. I I I I 3-2 I

I Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 3 - LAND USE CENSUS I Table 3-1 Location of Nearest Residences, Gardens, Dairy Cows and Doe Goats I DAIRY RESIDENCES GARDENS cows DOE GOATS I SECTOR 0 to Smiles 0 to Smiles 0 to Smiles 0 to Smiles (miles) (miles) (miles) (miles) I N 1.604 2.92 None None .I NNE 1.643 1.79 None None NE 0.474 4.86 None None I ENE 0.438 b 1.05 None None I E ESE 1.20 1.92 None 3.413 0.852 1.24 None None I SE 1.534 1.56 None 8 None SSE I s 2.106 1.367 4.36 1.48 None None None None I SSW 0.765 2.22 C None None SW 1.463 1.34 None 2.131 I WSW 1.417 239 None None I w 2.222 None None None WNW 2.30 3.62 None None I NW 0.892 1.03 None None I NNW 0.910 2.41 2.442 None I a Although there are no Dairy Cows within 5 miles in this sector, a large local dairy located at 6.076 miles is included in the milk sampling program. b Distance is the nearest location for that receptor. I c No garden at receptor location, distances is the nearest location in the sector. 3-3 I

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 4 - SPLIT SAMPLE PROGRAM and SPIKE SAMPLE INTER-LABORATORY COMPARISON PROGRAM I A. Split Sample Program (Inter-Laboratory Comparison, Part 1 of 2): BVPS participates in a split sample program with the Pennsylvania Department of Environmental Protection (P ADEP) I in support of their nuclear power plant monitoring program. I

  • BVPS provided split samples to PADEP throughout the report period. The shared media and number of locations were typically comprised of milk (1), surface water (3), sediment (1), fish (1), and food crops (2) .

I

  • PADEP has co-located continuous air particulate & air iodine sample stations with four (4) I of the BVPS locations.
  • PADEP has co-located TLDs with twenty-four (24) of the BVPS TLDs.

I B. Spike Sample Program (Inter-Laboratory Comparison, Part 2 of 2): BVPS participates in I a spike sample program with an Independent Laboratory. This program is used to independently verify sample analyses performed by the BVPS Contractor Laboratory. I

  • Acceptance Criteria: The NRC criteria listed in NRC Inspection Procedure 84750, 03/ 15/94, Inspection Guidance 84750-03 is used as acceptance criteria for comparisons of I results of spiked samples between the Contractor Lab and the Independent Lab. These comparisons are performed by dividing the comparison standard (Independent Lab result) by its associated uncertainty to obtain the resolution. The comparison standard value is I

multiplied by the ratio values obtained from the following table to find the acceptance band for the result to be compared. However, in such cases in which the counting precision of I the standard yields a resolution of less than 4, a valid comparison is not practical, and therefore, not performed. I NRC Criteria Resolution

                                     <4 Ratio I

4-7 8 - 15 16 - 50 0.50 - 2.00 0.60 - 1.66 0.75 - 1.33 I 51 - 200

                                    > 200 0.80 - 1.25 0.85 - 1.18                                  I Ii i

11I 4-1 I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 4 - SPLIT SAMPLE PROGRAM and SPIKE SAMPLE I INTER-LABORATORY COMPARISON PROGRAM Participation in an Inter-Laboratory Comparison Program is required by BVPS Unit 1 and 2 ODCM procedure l/2-0DC-3 .03 Attachment S Control 3.12.3. For the report period, the requirement was met by the Contractor Lab analyzing NIST traceable spiked samples supplied by an Independent Lab. During the report period, BVPS used (Environmental, Inc., Midwest Laboratory - Northbrook, IL) as the Contractor Laboratory, and (Eckert & Ziegler Analytics - Atlanta, GA) as the Independent Laboratory. I The spiked samples included air particulate filter papers, charcoal cartridges, water samples, I and milk samples. The samples were submitted by the Independent Laboratory to the Contractor Laboratory for analysis. The "spiked to" values were used for calculating comparison Acceptance Criteria. I

  • Spiked Milk & Water Samples: .The spiked sample results (i.e. the BVPS criteria) for I each calendar quarter are reported in Table 4-1 through Table 4-4, respectively. The following summary is provided:

I A total of forty-eight (48) gamma spectrometry radionuclide analyses were performed by the Contractor Laboratory on four (4) milk samples. I A total of forty-eight (48) gamma spectrometry radionuclide analyses were performed by the Contractor Laboratory on four (4) water samples. I A total of four (4) chemical analyses for 1-131 were performed by the Contractor I Laboratory on four (4) milk samples. A total of four (4) 1-131 analyses were performed by the Contractor Laboratory on four I (4) water samples. A total of four (4) tritium analyses were performed by the Contractor Laboratory on I four (4) water samples. I Comparison of results of the spiked milk and water samples showed acceptable agreement with the NRC acceptance criteria. All one hundred eight (108) analyses met the NRC acceptance criteria. I I I 4-2

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 4 - SPLIT SAMPLE PROGRAM and SPIKE SAMPLE INTER-LABORATORY COMPARISON PROGRAM I

  • Spiked Filter Paper and Charcoal Cartridge Samples: .The spiked sample results for each calendar quarter are reported in Table 4-1 through Table 4-4, respectively. The I

following summary is provided: I Gross Beta (cesium-137) analyses were performed by the Contractor Laboratory on two (2) filter paper samples. I Iodine-131 analyses were performed by the Contractor Laboratory on two (2) charcoal cartridge samples. I Comparison of results of the spiked filter paper and charcoal cartridge samples showed acceptable agreement with the NRC acceptance criteria. All four (4) analyses I performed by the Contractor Laboratory met the NRC acceptance criteria. I C. Conclusions

  • Results of Split Sample Program: The split sample program is coordinated by the state, I

and the results are not included in this report. I

  • Results of Spike Sample Program: Based on the Inter-Laboratory comparison data, BVPS considers all analyses provided throughout the report period by the Contractor Laboratory to be acceptable with respect to both accuracy and measurement. A I

comparison of the data is provided in the following tables. All analyses for the 2017 report period were within the NRC Acceptance Criteria. I I I I I I I 4-3 I

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 4 - SPLIT SAMPLE PROGRAM and SPIKE SAMPLE INTER-LABORATORY COMPARISON PROGRAM II Table 4-1 Inter-Laboratory Comparison Program Spiked Samples -1 51 Quarter I Sample Date, Type and Identification No. Resolution Resolution Required Ratio Band Ratio Env Inc: Analytics Comparison I Sr-89 Sr-90 60 60 0.80 - 1.25 0.80 - 1.25 0.92 0.94 AGREEMENT AGREEMENT 1-131 60 0.80 - 1.25 0.97 AGREEMENT I 03/16/17 1-131 Ce-141 60 60 0.80 - 1.25 0.80 - 1.25 1.04 1.22 AGREEMENT AGREEMENT Cr-51 60 0.80 - 1.25 1.05 AGREEMENT I Water Ind Lab : E11780 Cs-134 Cs-137 60 60 0.80 - 1.25 0.80 - 1.25 0.94 1.02 AGREEMENT AGREEMENT Con. Lab: SPW-1054 Co-58 60 0.80 - 1.25 1.01 AGREEMENT I Mn-54 Fe-59 60 60 0.80 - 1.25 0.80 - 1.25 1.04 1.06 AGREEMENT AGREEMENT 60 0.80 - 1.25 1.05 AGREEMENT I 03/16/17 Zn-65 Co-60 60 0.80 - 1.25 1.02 AGREEMENT Water I Ind. Lab : E11779 H-3 60 0.80 - 1.25 0.98 AGREEMENT Con. Lab: SPW-1052 I Sr-89 Sr-90 60 60 0.80 - 1.25 0.80 - 1.25 0.82 0.91 AGREEMENT AGREEMENT 1-131 60 0.80 - 1.25 1.04 AGREEMENT I 03/16/17 1-131 Ce-141 60 60 0.80 - 1.25 0.80 - 1.25 1.03 0.93 AGREEMENT AGREEMENT Milk Cr-51 60 0.80 - 1.25 1.05 AGREEMENT I Ind. Lab: E11781 Con. Lab: SPMl-1053 Cs-134 Cs-137 60 60 0.80 - 1.25 0.80 - 1.25 0.91 1.06 AGREEMENT AGREEMENT Co-58 60 0.80 - 1.25 1.02 AGREEMENT I Mn-54 Fe-59 60 60 0.80 - 1.25 0.80 - 1.25 1.04 1.06 AGREEMENT AGREEMENT Zn-65 60 0.80 - 1.25 1.04 AGREEMENT I 03/16/17 Co-60 60 0.80 - 1.25 1.01 AGREEMENT Filter Paper I Ind. Lab: E11782 Cs-137 (Gross Beta) 60 0.80 - 1.25 1.02 AGREEMENT Con. Lab: SPAP-1055 I 03/16/17 Charcoal Cartridge 60 0.80 - 1.25 0.93 AGREEMENT 1-131 I Ind. Lab: E11783 Con . Lab: SPCH-1056 I 4-4

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 4 - SPLIT SAMPLE PROGRAM and SPIKE SAMPLE INTER-LABORATORY COMPARISON PROGRAM I Table 4-2 Inter-Laboratory Comparison Program Spiked Samples - 2nd Quarter I Sample Date, Type and Identification No. Resolution Resolution Required Ratio Band Ratio Env Inc: Analytics Comparison I Sr-89 Sr-90 60 60 60 0.80 - 1.25 0.80 - 1.25 0.80 - 1.25 1.02 0.98 0.99 AGREEMENT AGREEMENT AGREEMENT I 1-131 06/08/17 1-131 Ce-141 60 60 0.80 - 1.25 0.80 - 1.25 1.02 1.02 AGREEMENT AGREEMENT I Cr-51 60 0.80 - 1.25 1.05 AGREEMENT Water Ind Lab: E11882 Cs-134 Cs-137 60 60 0.80 - 1.25 0.80 - 1.25 0.83 1.01 AGREEMENT AGREEMENT I Con. Lab: SPW-2787 Co-58 60 0.80 - 1.25 1.00 AGREEMENT Mn-54 Fe-59 60 60 0.80 - 1.25 0.80 - 1.25 1.00 1.06 AGREEMENT AGREEMENT I 0.80 - 1.25 1.00 06/08/17 Zn-65 Co-60 60 60 0.80 - 1.25 0.99 AGREEMENT AGREEMENT I Water Ind . Lab: E11881 H-3 60 0.80 - 1.25 0.97 AGREEMENT I Con. Lab: SPW-2784 Sr-89 Sr-90 60 60 60 0.80 - 1.25 0.80 - 1.25 0.80 - 1.25 0.95 0.94 0.99 AGREEMENT AGREEMENT AGREEMENT I 1-131

  • 06/08/17 1-131 Ce-141 Cr-51 60 60 60 0.80 - 1.25 0.80 - 1.25 0.80 - 1.25 1.01 0.99 1.00 AGREEMENT AGREEMENT AGREEMENT I

Milk Ind. Lab : E11883 Con. Lab: SPMl-2785 Cs-134 Cs-137 Co-58 60 60 60 0.80 - 1.25 0.80 - 1.25 0.80 - 1.25 0.91 1.01 0.98 AGREEMENT AGREEMENT AGREEMENT I Mn-54 Fe-59 60 60 0.80 - 1.25 0.80 - 1.25 0.80 - 1.25 1.00 1.06 0.99 AGREEMENT AGREEMENT I Zn-65 60 AGREEMENT Co-60 60 0.80 - 1.25 1.00 AGREEMENT I I I I 4-5 I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 4 - SPLIT SAMPLE PROGRAM and SPIKE SAMPLE INTER-LABORATORY COMPARISON PROGRAM I Table 4-3 Inter-Laboratory Comparison Program Spiked Samples - 3rd Quarter I Sample Date, Type and Identification No. Resolution Resolution Required Ratio Band Ratio Env Inc: Analytics Comparison 60 0.80 - 1.25 1.01 AGREEMENT I Sr-?9 Sr-90 1-131 60 60 0.80 - 1.25 0.80 - 1.25 0.99 0.94 AGREEMENT AGREEMENT I 09/14/17 1-131 Ce-141 Cr-51 60 60 60 0.80 - 1.25 0.80 - 1.25 0.80 - 1.25 1.02 1.10 1.08 AGREEMENT AGREEMENT AGREEMENT I Water Ind Lab: E11936 Cs-134 Cs-137 60 60 0.80 - 1.25 0.80 - 1.25 0.90 1.00 AGREEMENT AGREEMENT Con. Lab: SPW-4710 Co-58 60 0.80 - 1.25 0.98 AGREEMENT I Mn-54 Fe-59 60 60 0.80 - 1.25 0.80 - 1.25 1.04 1.05 AGREEMENT AGREEMENT Zn-65 60 0.80 - 1.25 1.06 AGREEMENT I 09/14/17 Co-60 60 0.80 - 1.25 0.99 AGREEMENT Water I Ind. Lab: E11935 Con. Lab: SPW-4709 H-3 60 0.80 - 1.25 0.95 AGREEMENT I Sr-89 Sr-90 1-131 60 60 60 0.80 - 1.25 0.80 - 1.25 0.80 - 1.25 0.96 0.95 0.83 AGREEMENT AGREEMENT AGREEMENT 60 0.80 - 1.25 1.00 AGREEMENT I 09/14/17 Milk 1-131 Ce-141 Cr-51 60 60 0.80 - 1.25 0.80 - 1.25 1.02 1.14 AGREEMENT AGREEMENT AGREEMENT I Ind. Lab: E11937 Con. Lab: SPMl-4712 Cs-134 Cs-137 Co-58 60 60 60 0.80 - 1.25 0.80 - 1.25 0.80 - 1.25 0.86 1.00 1.00 AGREEMENT AGREEMENT I Mn-54 Fe-59 Zn-65 60 60 60 0.80 - 1.25 0.80 - 1.25 0.80 - 1.25 1.02 1.07 1.05 AGREEMENT AGREEMENT AGREEMENT I 09/14/17 Co-60 60 0.80 - 1.25 0.97 AGREEMENT Filter Paper Cs-137 I Ind. Lab: E11938 Con. Lab: SPAP-4715 (Gross Beta) 60 0.80 - 1.25 0.95 AGREEMENT I 09/14/17 Charcoal Cartridge 60 0.80 - 1.25 0.99 AGREEMENT Ind. Lab: E11939A 1-131 I Con . Lab: SPCH-4717 I 4-6

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 4 - SPLIT SAMPLE PROGRAM and SPIKE SAMPLE INTER-LABORATORY COMPARISON PROGRAM I Table 4-4 Inter-Laboratory Comparison Program Spiked Samples - 4th Quarter I Sample Date, Type and Identification No. Resolution Resolution Required Ratio Band Ratio Env Inc: Analytics Comparison I Sr-89 Sr-90 1-131 60 60 60 0.80 - 1.25 0.80 - 1.25 0.80 - 1.25 0.98 1.11 0.96 AGREEMENT AGREEMENT AGREEMENT I 12/07/167 1-131 Ce-141 60 60 0.80 - 1.25 0.80 - 1.25 1.05 1.01 AGREEMENT AGREEMENT I Cr-51 60 0.80 - 1.25 0.95 AGREEMENT Water Ind Lab : E12045 Cs-134 Cs-137 60 60 0.80 - 1.25 0.80 - 1.25 0.93 1.02 AGREEMENT AGREEMENT I Con . Lab: SPW-6378 Co-58 60 0.80 - 1.25 1.00 AGREEMENT Mn-54 Fe-59 60 60 0.80 - 1.25 0.80 - 1.25 1.06 1.01 AGREEMENT AGREEMENT I Zn-65 60 0.80 - 1.25 1.02 AGREEMENT Co-60 60 0.80 - 1.25 1.03 AGREEMENT I 12/07/1 Water Ind. Lab: E12044 H-3 60 0.80 - 1.25 1.00 AGREEMENT I Con. Lab: SPW-6405 Sr-89 Sr-90 60 60 0.80 - 1.25 0.80 - 1.25 1.02 1.12 AGREEMENT AGREEMENT I 1-131 60 0.80 - 1.25 1.04 AGREEMENT 12/07/17 1-131 Ce-141 60 60 0.80 - 1.25 0.80 - 1.25 1.10 1.13 AGREEMENT AGREEMENT I Cr-51 60 0.80 - 1.25 1.08 AGREEMENT Milk Ind . Lab: E12043 Cs-134 Cs-137 60 60 0.80 - 1.25 0.80 - 1.25 0.95 1.12 AGREEMENT AGREEMENT I Con. Lab: SPMl-6404 Co-58 60 0.80 - 1.25 1.08 AGREEMENT Mn-54 Fe-59 60 60 0.80 - 1.25 0.80 - 1.25 1.14 1.13 AGREEMENT AGREEMENT I Zn-65 60 0.80 - 1.25 1.11 AGREEMENT Co-60 60 0.80 - 1.25 1.07 AGREEMENT I I I I 4-7 I

I Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 5 - CORRECTIONS TO PREVIOUS RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT(S) I A. Corrections to Previous Radiological Environmental Operating Report(s): There are no corrections to previous reports at this time. I I I I I I I I I I I I 11 I I 5-1 I

r I RTL# A9.690E ,,I FIRSTENERGY NUCLEAR OPERA TING COMPANY

 ,I         BEAVER VALLEY POWER STATION I

I I I I I I I I I 2017 I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (ARERR) I AND ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERA TING REPORT (AREOR) I UNITS NO. 1 AND 2

 ,I                  LICENSES DPR-66 AND NPF-73 I

I

I RTLA9.690E Enclosure 1 I BEAVER VALLEY POWER STATION I ENVIRONMENTAL & CHEMISTRY SECTION I Technical Report Approval: I 2017 I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (ARERR) I AND ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (AREOR) I UNITS NO. 1 AND 2 I LICENSES DPR-66 AND NPF-73 I Prepared by: Patrick C. Seidel ,? ~ Date: 5 //I'll 2~18 I

                                  ;(klwA--{_~. J~ ~                       /,o / 18 I  Reviewed by: Susan L. Vicinie                     ,*_J        Date:  1f I

I I I I I

Subject:

Beaver Valley Power Station, Unit Nos. 1 and 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Radioactive Effluent Release Report for 2017, and Annual Radiological Environmental Operating Report for 2017 Distribution for Enclosures 1 - 3: Original Report to: U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Copies of Report to Other USNRC: I U.S. Nuclear Regulatory Commission NRR Project Manager I U. S. Nuclear Regulatory Commission NRC Senior Resident Inspector I U.S. Nuclear Regulatory Commission NRC Region I Administrator I U.S. Nuclear Regulatory Commission NRC Region I Health Physics Inspector I Copies o{Report to Other Agencies: I American Nuclear Insurers 95 Glastonbury Boulevard I Glastonbury, CT 06033 Department of Environmental Protection (5 copies) I Bureau of Radiation Protection & Toxicology P.O. Box 2063 Harrisburg, PA 17105-2063 I Department of Environmental Protection (2 copies) Southwest Regional Office I 400 Waterfront Drive Pittsburgh, PA 15222 I I I

Distribution for Enclosures 1 - 3: I Page 2

                                                ,I INPO 700 Galleria Parkway SE Suite 100 I

Atlanta, GA 30339-5957 11 Beaver County Cooperative Extension 156 Cowpath Road Aliquippa, PA 15001-5842 I Hancock County Office of Emergency Services PO Box 884 I New Cumberland, WV 26047 Ohio Department of Health I 246 North High Street Columbus, OH 43215-3363 I Ohio Emergency Management Agency 2855 West Dublin Granville Road I Columbus, OH 43235 East Liverpool Water Authority I 2220 Michigan Avenue East Liverpool, OH 43920 I ORSANCO 5735 Kellogg Avenue I Cincinnati, OH 45228 B. F. Jones Memorial Library I 663 Franklin Avenue Aliquippa, PA 15001 I Bureau of Radiation Protection HP3 Ohio Department of Health I Northeast District Office 161 South High Street, Suite 400 Akron, OH 44308-1612 11 11 I I

, Distribution for Enclosures 1 - 3:

Page 3 I Copies of Report for FENOC Addressees: I TE Migdal, BVPS; Manager, Site Chemistry (A-BV-A) SL Vicinie, BVPS; Supervisor, Nuclear Chemistry Services (A-BV-A) I RR Winters, BVPS; Supervisor, Nuclear Chemistry Services (A-BV-A) PC Seidel, BVPS; Chemistry Services, RETS (A-BV-A) 5 copies I PH Lashley, Akron; Fleet Licensing (A-WAC-Bl) 2 copies JB Bowden, BVPS; Operations Oversight (A-BV-NCD3) K Gillespie, BVPS, Radiation Monitor System Engineer (A-BV-SOSB6) I DJ Min1rns, BVPS, Radiation Monitor System Engineer (A-BV-SOSB6)

  • BVPS, Liquid Waste System Engineer (A-BV-SOSB6)

RG Garver, BVPS, BOP Systems Engineer Supervisor (A-BV-SOSB-6) I

  • Akron; Director, Environmental (A-G0-13)

DW Jenkins, Akron; Sr. Attorney II, Legal (A-G0-15)

  • Akron; Vice President, Energy Policy (A-G0-18)

I MJ Jirousek, Akron; Manager, Environmental Generation Services (A-G0-13) SA Wender, Akron; Manager, Fleet Chemistry/Environmental (A-WAC-A3) I MR Baker, Perry RETS & REMP Administrator (A-PY-CCB125) KA Filar, Davis-Besse RETS & REMP Administrator (A-DB-1041) A Banavali, Manager, Environmental, Inc. I RJ Dinello, Field Specialist, Environmental, Inc I BVPS Document Control, RTL A9.690E BVRC - Keywords: Radioactive Effluent Release Report, I Annual Radiological Environmental Operating Report I I I I I I I

I Form 1/2-ENV-01 .05.F01 (page 1 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTLA9.690E Enclosure 2, Page i I I 2017 Annual Radioactive Effluent Release Report I I I I FirstEnergy Nuclear Operating Company FENOC I Beaver Valley Power Station - Units 1 & 2 Unit 1 License No. DPR-66 Unit 2 License No. NPF-73 I I I I I I 11 ii I I I

Form 1/2-ENV-01.05.F01 (page 2 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page ii I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Index Title Page I Cover Index i ii I Executive Summary - Report Submittal Reauirements iii Executive Summary - Liquid and Gaseous Effluent Control (Part 1 of 2) Executive Summary - Liquid and Gaseous Effluent Control (Part 2 of 2) iv V I Executive Summary - Trends of Tota l Dose vi Executive Summary - Trends of Liquid Release Activity (Fission and Activation Products) Executive Summary - Trends of Liquid Release Activity (Tritium) vii viii I Executive Summary - Trends of Liquid Release Offsite Dose Projections ix Executive Summary - Trends of Gaseous Release Activity (Fission and Activation Gas) Executive Summary - Trends of Gaseous Release Activity (Particulates and Radioiodines) X xi I: Executive Summary - Trends of Gaseous Release Activity (Tritium) xii Executive Summary - Trends of Unit 1 Gaseous Release Offsite Dose Projections Executive Summary - Trends of Unit 2 Gaseous Re lease Offsite Dose Projections xiii xiv I Results of Abnormal Releases xv Results of Onsite Spills and Items Added to Decommissionina Files per 10CFR50.75(a) Results of Onsite Groundwater Monitorina Proaram xvi xvi i I Corrections to Previous Annual Radioactive Effluent Release Reports xviii Table 1A Supplemental Information Page Gaseous Effluents - Summation Of All Releases 1 2 I Table 1B-EB Gaseous Effluents - Elevated Batch Releases 3 Table 1B-EC Gaseous Effluents - Elevated Continuous Releases Table 1C-GB1 Gaseous Effluents - Ground Level Batch Releases (Unit 1) 4 5 I Table 1C-GC1 Gaseous Effluents - Ground Level Continuous Releases (Unit 1) 6 Table 1C-GB2 Gaseous Effluents - Ground Level Batch Releases (Unit 2) Table 1C-GC2 Gaseous Effluents - Ground Level Continuous Releases (Unit 2) 7 8 I Table 2A Liauid Effluents - Summation Of All Releases 9 Table 2B-B Table 2B-C Liau id Effluents - Batch Releases Liauid Effluents - Continuous Releases 10 11 I Table 3A Solid Waste And Irradiated Fuel Shipments (Part 1 of 3) 12 Table 38 Table 3C Solid Waste And Irradiated Fuel Shipments (Part 2 of 3) Solid Waste And Irradiated Fuel Shipments (Part 3 of 3) 13 14 I Table 4 Lower Limits Of Detectabilitv 15 Table 5A Table 58 Assessment Of Radiation Doses (Unit 1) Assessment Of Radiation Doses (Unit 2) 16 17 I Table 6 Effluent Monitoring Instrumentation Channels Not Returned To Operable Status Within 30 Days 18 Table 7 Table 8 Total Dose Commitments , Total Effective Dose Equivalents and Population Doses Offsite Dose Calculation Manual Surveillance Deficiencies 19 20 I Table 9 Unit 1 and 2 Offsite Dose Calculation Manual Cha naes (Description) 21 Attachment 1 Part 1: Joint Frequency Distribution Tables (35 ft) Part 2: Joint Frequency Distribution Tables (150 ft) I Part 3: Joint Freauency Distribution Tables (500 ft) Attachment 2 Un it 1 and 2 Offsite Dose Calculation Manual (Complete Copy) Note: The Total Error va lues(%) listed in this report are documented in Calculation Package No. ERS-ATL-04-002 I I

I Form 1/2-ENV-01 .05.F01 (page 3 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page iii I Annual Radioactive Effluent Release Report Calendar Year - 2017 Executive Summary - Report Submittal Requirements I Report Submittal and Requirements: The report was prepared and submitted in accordance with the I requirements contained in the following documents: BVPS Integrated Technical Specifications, Administrative Control 5.6.2 I Offsite Dose Calculation Manual (ODCM) procedure 1/2-0DC-3 .03, 'Controls for RETS and REMP Programs ", Attachment U, Control 6.9.3 I BVPS procedure l/2-ENV-01.05, "Compliance with Regulatory Guide 1.21 and Technical Specifications " I NUREG-1301 , " Offsite Dose Calculation Manual Guidance: Standard Radiological Ejjl.uent Controls for Pressurized Water Reactors, Generic Letter 89-01, Supplement No.I, April 1991 " I Regulatory Guide 1.21 , "Measuring Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Material in Liquid and Gaseous Ejjl.uents from Light-Water Cooled Nuclear Power Plants, Revision I , June 1974 " I BVPS Condition Report No. CR-2017-04211 , Lack of isokinetic sampling for ODCM requirements BVPS Condition Report No. CR-2017-04541 , RM-1MS-100C not returned to service within 30 days I BVPS Condition Report No. CR-2017-07282, U2 MSCV sump sample cannot be located, ODCM surveillance missed I BVPS Condition Report No. CR-2017-12446, RM-I LW-104 Not Returned to Service Within 30 days as Required by the ODCM I BVPS Condition Report No. CR-2018-00126, Annual Catch Basin samples were unable to be obtained I BVPS Condition Report No. CR-2018-02122, REMP Control Location TLD #48 exposure abnormally low BVPS SAP Order No. 601078879, 2017 RETS/REMP Tracking for ARERR/AREOR I I I I I I

Form 1/2-ENV-01 05.F01 (page 4 of 39), Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page iv I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Executive Summary - Liquid and Gaseous Effluent Control (Part 1 of 2) I Onsite Groundwater Monitoring: H-3 Summary: In 2017, twenty three (23) on-site monitoring wells were sampled in the spring and fall sampling periods. No new wells were installed, nor were any wells retired. MW-16 was sampled twelve (12) times throughout 2017, two (2) of which were included in the I yearly biannual sampling. These samples that were taken account for the highest concentrations. No adverse effect to the offsite environment has been detected at this time, because all offsite groundwater, drinking water and surface water samples were <440 pCi/L. See Enclosure 2, Page xvii for additional I details. Onsite Spills: There were no onsite spills > 100 gallons. I Decommissioning File Update: There were no items added to the site decommissioning files in accordance with 10CFR50.75(g). I Abnormal Liquid Releases: There were no abnormal liquid releases. Abnormal Gaseous Releases: There were two abnormal gaseous releases. I Liquid Radwaste Treatment System: The site operated via a shared Liquid Radwaste Treatment System, even though each Unit has its own ion-exchange vessels. Shared operation allowed either Unit to process I liquid waste at the Unit of origin, or at the other Unit. Typically, when Unit I or 2 high level liquid waste was processed (e.g., coolant recovery waste) it was performed at Unit 1, because it has a carbon pre-conditioning filter. I Gaseous Radwaste Treatment System: The site operated via a shared Gaseous Radwaste Treatment System, even though each Unit has its own charcoal delay beds and storage/decay tanks. Shared operation allowed either Unit to process gaseous waste at the Unit of origin, or at the other Unit. Typically, when Unit I I or 2 went to a shutdown condition, the gaseous waste was transferred for storage and decay at Unit 2, because Unit 2 has four (4) additional storage tanks. I I I I I I I I

I Form 1/2-ENV-01 .05 .F01 (page 5 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page v I Annual Radioactive Effluent Release Report Ca~ndarYear-2017 Executive Summary - Liquid and Gaseous Effluent Control (Part 1 of 2) I Lower Limits of Detectability (LLD): All a-priori calculated LLD met the minimum requirements I specified in the ODCM. Effluent Monitoring Channels Inoperable >30 Days:There were two (2) Effl uent Monitoring I Instrumentation Channels not returned to Operable status within 30 days. ODCM Surveillance Deficiencies: There were two (2) ODCM Surveillance Deficiencies. I ODCM Changes: There was one (1) changes made to the ODCM. Meteorological Data Recovery: The Meteorological Data Recovery met the minimum requirement of at-I least 90%, as specified in Section 5 of Revision 1 to Regulatory Guide 1.23, Meteorological Monitoring Programs for Nuclear Power Plants. I Population Dose vs. Natural

Background:

The 0-50 mile total and average population doses were calculated using liquid and gaseous release quantities and real time meteorology. The average population dose is based on four (4) million people within 0-50 miles of the BVPS site. The following comparison to I natural background radiation demonstrates that BVPS operations did not adversely affect the surround ing environment. I 99.96 man-mrem =BVPS Total Population Dose for the year 0.0000250 mrem = BVPS Average Individual Dose for the year I 296 mrem = Natural Background Individual Dose for the year. This dose value is documented as natural background radiation exposure for an individual in a year from the 1990 BElR V Report. I Carbon-14 Dose Assessment: Carbon-1 4 dose was calcu lated using EPRI & RG-1 .109 calculation methods and the default ODCM receptor. The highest organ doses were to the bone (child). Details of the I dose assessment due to releases of Carbon-14 in gaseous effluents are provided in Attachment 3 of this report. I I I I I I

Form 1/2-ENV-01 .05 F01 (page 6 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9 .690E Enclosure 2, Page vi I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Executive Summary -Trends of Total Dose I Trends of Total Dose: The following graph provides a comparison of the ODCM dose projections from all facility releases and direct radiation exposures to show compliance with Member of the Public dose limits from 10 CFR 20.1301 and 40 CFR Part 190. I 100.0% - - - - -- - - - -- - - - - - - - - - - - - - - - - - - - - - - -- ~ I I I I I 0.1% + - - l - - - + - - - - + - - + - - - - + - - + - - - - - + - - + - - - t - - - + - - - + - - + - - - + - - - - + - - - + - - - - + - - l

          ~,~###~##,###~~~~~~~~
                 " ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

unit 1&2, Percent of 40 CFR 190.10(a)Total Body Dose Limit o Unit 1&2 , Percent of 40 CFR190.10(a) Thyroid Dose Limit I

               - - - Unit 1&2, Percent of 10 CFR 20.1301(a)(1) TEDE Dose Limit I

I I I I I I I I

I Form 1/2-ENV-01 .05.F01 (page 7 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page vii I Annual Radioactive Effluent Release Report Calendar Year - 2017 Executive Summary - Trends of Liquid Release Activity (Fission and Activation Products) I Liquid Release Activity (Fission and Activation Products): The following graph provides a comparison I of total liquid mixed fission and activation product (particulate) radioactivity discharged from the site from 1976 to present. I 10.00 - - --* I 1.00 +-- - - - - - - - ---,1-- - - - - - - - - - - - - - - - - - - - - l I en Q)

    *c I

(.) I I 0.01 ;--t-+-t--+-+--t--+-+-+-t-+-+--+-+--t--+-+--+-t-+-+--+-+-+--+-+-+-,t-+-t-+-+--t--t--+-+-,t-+-t--t--i

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                                               -svPs Unit 1 -       svPs Unit 2 I

I I I I I I I I

Form 1/2-ENV-01 .05.F01 (page 8 of 39) , Rev 5 RTL# A9 .690E Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Page viii Annual Radioactive Effluent Release Report Calendar Year - 2017 I Executive Summary - Trends of Liquid Release Activity (Tritium) Liquid Release Activity (Tritium): The following graph provides a comparison of total liquid tritium radioactivity discharged from the site from 1976 to present. The latest increases were due to the increase power of the reactor, or power uprate, which lead to increased tritium. I 10000 I I

   <fl
  -~     100 +-'IF--- -----*- - - - - - - - - - - - -- -- - - - - - - - - - - - - - - <

I

   =,

0 I I I I I

                                            -BVPS Unit 1   -    BVPS Unit 2 [

I I I I I I I I

I Form 1/2-ENV-01 .05.F01 (page 9 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page ix I Annual Radioactive Effluent Release Report Calendar Year - 2017 II Executive Summary - Trends of Liquid Release Offsite Dose Projections Liquid Release Offsite Dose Projections: The following graph provides a comparison of liquid offsite I dose projections that were calculated to the maximum individual per 10 CFR 50, Appendix I and the ODCM. The projections use ODCM default flow rates for the receiving water (Ohio River), and were performed prior to release authorization. I 100.0% ~ - - - - - - - -- - -- - - - - - - -- - - - - -- - - -- -- ~ I I ~ E

J 10.0%

I -.: 0 0 ns 0 0 QI 0

     >-                                                                        0           0 0               0 0                                                            0                                                     0 0
     ~      1.0%

I 0 0 I 0.1% +----t---+---+---,--+---+--t----+--t--+----+---+--+----+---+---+---,--+---+---1

               ~#~~~,,~#,#~#~~~~~~~~

I - u nit 1 or Unit 2, Percent of Maximum Organ Dose Limit o Unit 1 or Unit 2, Perce nt of Total Bod y Dose Limit I I I I I I I

Form 1/2-ENV-01 .05 .F01 (page 10 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page x I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Executive Summary - Trends of Gaseous Release Activity (Fission and Activation Gas) I Gaseous Release Activity (Fission and Activation Gas): The following graph provides a comparison of total gaseous fission and activation gas discharged from the site from 1976 to present. The steady decreases are due to extended hold-up periods of gas space prior to release. The differences between the units are I relative to the outages that occured that year. I 10000.00 1000.00 I 100.00 I

  <fl Q)
 *c
I

(.) 10.00 I 1.00 0.10 I 0.01

               ~ro  ~~  'br:::i  'b'l.,  ~  'bro   'b~  !')r:::i  !')'l.,  *  !))ro  !))~  Rlr:::i  Rl'l.,  Rib<  Rlro  RI~  "r;:;, "'l., "b-. "ro I
             ~     ~   ~        ~       ~  ~      ~    ~         ~        ~  ~      ~     ~        ~       ~     ~     ~    ~ ~ ~ ~

I -svPs Unit 1 - svPs Unit 2 I I I I I I I I 11 I

I I Form 1/2-ENV-01 .05 .F01 (page 11 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page xi I Annual Radioactive Effluent Release Report Calendar Year - 2017 Executive Summary - Trends of Gaseous Release Activity (Particulates and Radioiodines; I Gaseous Release Activity {Particulates and Radioiodines): The following graph provides a comparison I of total gaseous particulates and radioiodines discharged from the site from 1976 to present. The differences between the units are relative to the outages that occured that year. I 1.E-01 I 1.E-02 I Cl) (I) 1.E-03

      '§   1.E-04 I    0 1.E-05 I         1.E-06 I         1.E-07 I                                               -BVPS Unit 1   -    BVPS Unit 2 I

I I II I I I I I

Form 1/2-ENV-01 .05.F01 (page 12 of 39), Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page xii I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Executive Summary - Trends of Gaseous Release Activity (Tritium) Gaseous Release Activity (Tritium): The following graph provides a comparison of total gaseous tritium discharged from the site from 1976 to present. The recent decreases were due to efforts to reduce overall offsite dose. Specifically, discharging liquid radioactive inventory provided the benefit ofreduced total I offsite dose, due to reduction in evaporative losses from the fuel pools. The increase in Unit I tritium was due to the steam releases from the Forced Outage in November. I 11 I

   <I)

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J

(..) I I I

         ~~~$~~~~~*~~~~~~~~~~~
         ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

J -BVPS Unit 1 - BVPS Unit2 I I I I I I I I I

I Form 1/2-ENV-01.05.F01 (page 13 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Page xiii RTL# A9.690E I Annual Radioactive Effluent Release Report Calendar Year - 2017 Executive Summary - Trends of Unit 1 Gaseous Release Offsite Dose Projections I Unit 1 Gaseous Release Offsite Dose Projections: The following graph provides a comparison of Unit I I gaseous offsite dose projections that were calculated to the maximum individual per 10 CFR 50, Appendix I and the ODCM. The projections use ODCM default meteorological parameters for the atmospheric conditions surrounding the plant site, and were performed prior to release authorization. I 100.0000000% I 10.0000000% 1.0000000% I ~ E

J 0.1000000%

0.0100000%

     ~

I ~ C'CI

     ....0 0.0010000%

0.0001000%

     ~

I 0 0.0000100% 0.0000010% I 0.0000001% 0.0000000% .L.....-f--+--+----+--+------i--+--+---+--+---+___..c...-+--+---+--+---+-~ - - t-L--+-- +="r

                       ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
                      ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

I Unit 1, Percent of Gamma Air Dose limit ~ Unit 1, Percent of Beta Air Dose Limit . - - - Unit 1, Percent of Hig hest Organ Dose Limit I I I

1

'I I I I

Form 1/2-ENV-01 .05 .F01 (page 14 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Page xiv RTL# A9.690E I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Executive Summary - Trends of Unit 1 Gaseous Release Offsite Dose Projections I Unit 2 Gaseous Release Offsite Dose Projections: The following graph provides a comparison of Unit 2 gaseous offsite dose projections that were calculated to the maximum individual per 10 CFR 50, Appendix I and the ODCM. The projections use ODCM default meteorological parameters for the atmospheric I conditions surrounding the plant site, and were performed prior to release authorization. I 100.0000000% 10.0000000% I 1.0000000%

  ~
i E

0.1000000% I 0.0100000% I 111 Q)

  >-     0.0010000%

0

  ~      0.0001000%

0 0.0000100% I 0.0000010% I Unit 2, Percent of Gamma Air Dose Limit - unit 2, Percent of Beta Air Dose Limit - - - Unit 2, Percent of Highest Organ Dose Limit I I I I I I I I I

Form 1/2-ENV-01 .05 .F01 (page 15 of 39) , Rev 5 RTL# A9 .690E Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Page xv Annual Radioactive Effluent Release Report Calendar Year - 2017 Results of Abnormal Releases I Description of Abnormal Release(s) I I Abnormal Liquid Releases : NONE 11 Abnormal Gaseous Releases : There were two abnormal discharges are from the Unit 1 Force Outage that was due to a reactor trip caused by generator overcurrent. One discharge is from the Auxiliary Feedwater Terry Turbine trip va lve and the other is for the Residual Heat Removal valves . These discharges were steam releases and are an expected response to a reactor trip . Tritium was the only radioactive isotope associated with them and no ODCM limits I were exceeded (reference CR-2017-11134). I I I I I I I I I I I I

Form 1/2-ENV-01 .05.F01 (page 16 of 39), Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page xvi I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Results of Onsite Spills and Items Added to Decommissioning Files per 10CFR50.75(g) Description of Spills or Items added to 10CFR50.75(g) I I Summary of Onsite Spills (>100 gallons): NONE I Summary of Items added to Decommissioning Files per 10CFR50.75(g) Files: NONE I 1: I I I I I I I I I I I I

i I Form 1/2-ENV-01 .05 .F01 (page 17 of 39), Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page xvii Annual Radioactive Effluent Release Report I Ca~ndarYear-2017 Results of Onsite Groundwater Monitoring Program I Summary of Onsite Groundwater Samples Are Any H-3 Analyses NEI and FENOC EPA 2017 2017 2017 Typical Required Pre Greater Than Communication Reporting I H-3 (pCi/Ll H-3 Maximum Minimum Average (pCi/L) H-3 (pCi/L) H-3 LLD (pCi/Ll H-3 LLD (pCi/L) Operational Mean For H-3 (pCi/Ll The Pre Operational Mean For H-3 ? Level For H-3 (pCi/Ll Level For H-3 (pCi/Ll I sering (02) I I I I <200 I <2000 I I I I I I I Fall (04) I 6517 14219 I 148 148 I 611 926 I <200 I <2000 I 440 440 I Yes Yes I 2000 2000 I 20000 20000 I I I I I I <200 I <2000 I I I I I I MW-16 15516 5916 8894 440 Yes 2000 20000 Tritium (H-3) Summary In 2017 , twenty three (23) on-site monitoring wells were sampled in the spring and fall sampling periods. No new wells were installed, nor were any wells retired . MW-16 was sampled twelve (12) times throughout 2017 , two (2) of which were included in I the yearly biannual sampling . These samples that were taken account for the highest concentrations . Sixteen (16) wells returned results of less than the pre-operational mean (440 pCi/L) during all sample periods in 2017. Seven (7) wells returned results >440 pCi/L, but <2000 pCi/l. One (1) well returned results >2000 pCi/L. No wells exceeded 20,000 pCi/L with the highest concentration recorded as 15,516 pCi/L. I The NEUFENOC communication level was reached for MW-12S & MW-12D during 2007. Notification to local, state & federal agencies was performed on 10/08/07. Additional communication for new well results was performed on 09/08/1 O for those new wells that exceeded 2000 pCi/L. The newly installed well MW-20D exceeded 2,000 pCi/L on its first sample, but this was expected since the well was installed to monitor the previously identified plume intercepting MW-16. No adverse effect to the I offsite environment has been detected at this time, because all offsite groundwater, drinking water and surface water samples were <440 pCi/l. Mitigation activities (catch basin sleeving) to prevent tritiated condensate water from reach ing the groundwater were completed 12/17/11 . Remediation well , EW-1, was installed and began operation in October 2013. This equipment captures the tritium plume and it I becomes a permitted discharge. Samples are taken monthly to provide the concentration of the discharge. Remediation will continue until the suspected plume is depleted and tritium levels stabilize. Principal Gamma Emmitter Summary I All onsite monitoring wells were sampled during the year, and analyzed for Principal Gamma Emitters. The results showed no positive indication of Licensed Radioactive Material (LRM) in any of the analyses. I 100000 Onsite Groundwater Monitoring Well Program H-3 Trends New Wells Installed Summer 2010 yes (2001 ~ 2011) _ _ _ __ I I I - - MW-10 (Upgradient Control Well) Avg . of all Samples Pre-Operational Mean H-3 (440 pCi/L)

                                                                           - - Maximum Tritium Sample
                                                                           -     H-3 LLD (typically <200 pCi/L)

Pre-Operational Max H-3

        -     NRC Required LLD (2,000 pCi/L) NEI Commun icati on Level     -     EPA Reporting Level (Non-Drinking Water) 30,000 pCi/L I

I

Form 1/2-ENV-01 .05 .F01 (page 18 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page xviii I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Corrections to previous Annual Radioactive Effluent Release Reports I Description of Corrections Made to RERR(s) I Correction(s) to Previous Annual Radioactive Effluent Release Reports: NONI I I I I I I I I I I I I I I I

I Form 1/2-ENV-01 .05 .F01 (page 19 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9 .690E Enclosure 2, Page 1 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 Supplemental Information Page I I FACILITY: B.V.P.S. Units 1 and 2 I 1. Regulatory Limits

a. Fission and activation gases: Annual Unit 1 or 2 Dose : 10 mrad from Gamma , & 20 mrad from Beta
b. Iodines & particulates, half-lives > 8 days: Annual Unit 1 or 2 Dose: 15 mrem to Any Orqan I c. Liauid effluents: Annual Unit 1 or 2 Dose: 3 mrem to Total Body , & 10 mrem to Any Oman
2. Maximum Permissable Concentrations Used In Determining Allowable Release Rates Or Concentrations I a. Fission and activation gases:
b. Iodines & particulates, half-lives > 8 days:

Site Release Rate: 500 mrem/yr to Total Body, & 3000 mrem/yr to the Skin Site Release Rate : 1500 mrem/yr to Any Orqan I c. Liauid effluents: j 3. Average Energy (Not Applicable To The BVPS ODCM) Site Release Concentration : 10 times 10 CFR 20 Aooendix B, Table 2, EC's I 4. Measurements and Approximations of Total Radioactivity The methods used to measure or approximate the total radioactivity in effluents, and the methods used to determine I radionuclide composition are as follows:

a. Fission and activation gases: Ge Gamma Spectrometry , Liquid Scintillation Counter
b. Iodines: Ge Gamma Spectrometry I c. Particulates, half-lives > 8 days:
d. Liauid effluents:

Ge Gamma Spectrometry, Proportional Cou nter Ge Gamma Spectrometry , Proportional Counter, Liquid Scintillation Calendar

5. Batch & Abnormal Release Information unit Q1 Q2 Q3 Q4 Year
a. Liquid Batch Releases
1. Number of batch releases 18 21 37 17 93
2. Total time period for batch releases min 7466 13930 8741 7276 37413 I 3. Maximum time period for a batch release
4. Average time period for batch releases
5. Minimum time period for a batch release min min 3939 415 4135 663 4390 236 4445 428 4445 402 min 190 13 13 13 13 I 6. Average river flow during release periods
b. Gaseous Batch Releases cuft/sec 74911 64447 25186 34803 49837
1. Number of batch releases 6 12 2 5 25 I 2. Total time period for batch releases
3. Maximum time period for a batch release min min 4385 3595 11405 4972 282 176 7861 7210 23933 7210
4. Averaae time period for batch releases min 731 950 141 1572 957 I 5. Minimum time oeriod for a batch release
c. Abnormal Liquid Releases min 1 1 106 94 1
1. Number of releases NONE NONE NONE NONE NONE I 2. Total activity released
d. Abnormal Gaseous Releases Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO I 1. Number of releases
2. Total activity released Ci NONE O.OOE+OO NONE O.OOE+OO NONE O.OOE+OO 2

1.78E+06 1.78E+06 2 I

Form 1/2-ENV-01 .05.F01 (page 20 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page 2 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Table 1A Gaseous Effluents - Summation Of All Releases I Calendar Total unit Q1 Q2 Q3 Q4 Year Error% I A. Fission & Activation Gases

1. Site Total release 1a. Unit 1 Gases Cl Ci O.OOE+OO O.OOE+OO 1.48E-01 7.41E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.48E-01 7.41E-02 26.5%1 I 1b. Unit 2 Gases
2. Average release rate for period
3. Percent of applicable limit Cl uCi/sec O.OOE+OO O.OOE+OO N/A 7.41E-02 1.88E-02 N/A O.OOE+OO O.OOE+OO N/A O.OOE+OO O.OOE+OO N/A 7.41E-02 4.70E-03 N/A I

B. Iodines

1. Site Total iodine -131 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 28.3% 1 I

1a. Unit 1 iodine -131 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1b. Unit 2 iodine - 131

2. Average release rate for period
3. Percent of applicable limit Cl uCi/sec O.OOE+OO O.OOE+OO N/A O.OOE+OO O.OOE+OO N/A O.OOE+OO O.OOE+OO N/A O.OOE+OO O.OOE+OO N/A O.OOE+OO O.OOE+OO N/A I

C. Particulates

1. Particulates with half-lives > 8 days Ci O.OOE+OO 5.29E-04 5.17E-07 O.OOE+OO 5.30E-04 30.0%1 I

1a. Unit 1 Particulates 1b. Unit 2 Particulates

2. Average release rate for period Ci Ci uCl/sec O.OOE+OO O.OOE+OO O.OOE+OO 6.59E-07 5.29E-04 6.72E-05 2.59E-07 2.59E-07 6.57E-08 O.OOE+OO O.OOE+OO O.OOE+OO 9.18E-07 5.29E-04 1.68E-05 I
3. Percent of applicable limit  % N/A N/A N/A N/A N/A D. Gross Alpha I
1. Site Gross alpha radioactivity Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 30.0%1 1a. Unit 1 Gross alpha 1b. Unit 2 Gross alpha
2. Average release rate for period Ci Ci uCi/sec O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO I
3. Percent of applicable limit E. Tritium
                                                  %          N/A         N/A          N/A         N/A            N/A I
1. Site Total release 1a. Unit 1 Tritium 1b. Unit 2 Tritium Ci Ci Ci 5.82E-01 2.45E-01 3.38E-01 4.26E-01 3.52E-01 7.41E-02 8.10E-01 5.84E-01 2.26E-01 2.76E+OO 2.29E+OO 4.69E-01 4.58E+OO 3.47E+OO 1.11E+OO 32.9%

I

2. Average release rate for period uCi/sec 7.39E-02 5.41 E-02 1.03E-01 3.SOE-01 1.45E-01
3. Percent of applicable limit  % N/A N/A N/A N/A N/A I

F. Carbon-14

1. Site Total release 1a. Unit 1 Carbon-14 1b. Unit 2 Carbon-14 Ci Ci Ci 4.59E+OO 2.30E+OO 2.29E+OO 3.81E+OO 4.69E+OO 4.54E+OO 2.33E+OO 2.35E+OO 2.20E+OO 1.48E+OO 2.34E+OO 2.34E+OO 1.76E+01 9.18E+OO 8.45E+OO 41.1% 1 I
2. Average release rate for period
3. Percent of applicable limit uCi/sec 5.83E-01
                                                  %          N/A 4.83E-01 5.95E-01 5.76E-01 N/A          N/A          N/A 5.59E-01 N/A                 I NIA = Not Applicable The amount of time (in seconds) used to calcu late the release rates specified in A.2, B.2, C.2, D.2 and E.2 is the average amount of seconds per calendar quarter (7.88E+06 seconds) .

I I

11 Form 1/2-ENV-01 .05.F01 (page 21 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page 3 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Table 18-EB Gaseous Effluents - Elevated Batch Releases (Unit 1 & 2) I Nuclides released unit Q1 Q2 Q3 Q4 Calendar Year I A. Fission gases argon-41 Ci LLD 8.53E-06 LLD LLD 8.53E-06 I krypton-85 krypton-85m krypton-87 Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I krypton-88 xenon-131m xenon-133 Ci Ci Ci LLD LLD LLD LLD LLD 1.93E-03 LLD LLD LLD LLD LLD LLD LLD LLD 1.93E-03 xenon-133m Ci LLD LLD LLD LLD LLD I xenon-135 xenon-135m Ci Ci LLD LLD 7.45E-04 8.16E-05 LLD LLD LLD LLD 7.45E-04 8.16E-05 xenon-138 Ci LLD LLD LLD LLD LLD I Total for period Ci ND 2.??E-03 ND ND 2.??E-03 B. Iodines I iodine-131 iodine-133 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD iodine-135 Ci LLD LLD LLD LLD LLD I Total for period Ci ND ND ND ND ND C. Particulates I chromium-51 manganese-54 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I cobalt-57 cobait-58 cobalt-60 Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD zinc-65 Ci LLD LLD LLD LLD LLD selenium-75 Ci LLD LLD LLD LLD LLD zirconium/niobium-95 Ci LLD LLD LLD LLD LLD zirconium/niobium-97 Ci LLD LLD LLD LLD LLD cesium-134 Ci LLD LLD LLD LLD LLD cesium-137 Ci LLD LLD LLD LLD LLD cerium-141 Ci LLD LLD LLD LLD LLD cerium-144 Ci LLD LLD LLD LLD LLD strontium-89 Ci LLD LLD LLD LLD LLD strontium-90 Ci LLD LLD LLD LLD LLD I Total for period Ci ND ND ND ND ND I NOTE: Unit 1/2 Process Vent LLD= Below the Lower Limit of Detectability, in uCi/cc (Table 4) . ND= None Detected I

Form 1/2-ENV-01 .05.F01 (page 22 of 39), Rev 5 RTL# A9.690E Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Page 4 of 21 Annual Radioactive Effluent Release Report Calendar Year - 2017 Table 18-EC Gaseous Effluents - Elevated Continuous Releases (Unit 1 & 2) Calendar Nuclides released unit Q1 Q2 Q3 Q4 Year A. Fission gases argon-41 Ci LLD LLD LLD LLD LLD I krypton-85 krypton-85m krypton-87 Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I krypton-88 xenon-131m xenon-133 Ci Ci Ci LLD LLD LLD LLD LLD 1.45E-01 LLD LLD LLD LLD LLD LLD LLD LLD 1.45E-01 I xenon-133m Ci LLD LLD LLD LLD LLD xenon-135 xenon-135m Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I xenon-138 Ci LLD LLD LLD LLD LLD Total for period Ci ND 1.45E-01 ND ND 1.45E-01 I B. Iodines iodine-131 iodine-133 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I iodine-135 Ci LLD LLD LLD LLD LLD Total for period Ci ND ND ND ND ND I C. Particulates chromium-51 manganese-54 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I cobalt-57 cobalt-58 cobalt-GO Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I zinc-65 Ci LLD LLD LLD LLD LLD selenium-75 zirconium/niobium-95 Ci Ci LLD LLD 1.32E-06 LLD 5.17E-07 LLD LLD LLD 1.84E-06 LLD I zirconium/niobium-97 Ci LLD LLD LLD LLD LLD cesium-134 cesium-137 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I cerium-141 Ci LLD LLD LLD LLD LLD cerium-144 strontium-89 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I strontium-90 Ci LLD LLD LLD LLD LLD Total for period Ci ND 1.32E-06 5.17E-07 ND 1.84E-06 I NOTE : Unit 1/2 Process Vent LLD= Below the Lower Limit of Detectability, in uCi/cc (Table 4). ND = None Detected I I

I Form 1/2-ENV-01.05.F01 (page 23 of 39) , Rev 5 Beaver Valley Power Station - Unit 1 RTL# A9.690E Enclosure 2, Page 5 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Table 1C-GB1 Gaseous Effluents - Ground Level Batch Releases (Unit 1) I Nuclides released unit Q1 Q2 Q3 Q4 Calendar Year I A. Fission gases argon-41 Ci LLD LLD LLD LLD LLD I krypton-BS krypton-BSm krypton-B7 Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I krypton-BB xenon-131m xenon-133 Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD xenon-133m Ci LLD LLD LLD LLD LLD I xenon-13S xenon-13Sm Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD xenon-13B Ci LLD LLD LLD LLD LLD I Total for period Ci ND ND ND ND ND B. Iodines I iodine-131 iodine-133 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD iodine-13S Ci LLD LLD LLD LLD LLD I Total for period Ci ND ND ND ND ND I C. Particulates chromium-S1 Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD manganese-54 Ci LLD I cobalt-S7 cobalt-SB cobalt-60 Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I zinc-6S Ci selenium-7S Ci LLD LLD LLD LLD LLD zirconiumfnioblum-9S Ci LLD LLD LLD LLD LLD zirconiumfniobium-97 Ci LLD LLD LLD LLD LLD I cesium-134 cesium-137 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD cerium-141 Ci LLD LLD LLD LLD LLD I cerium-144 strontium-B9 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD strontium-90 Ci LLD LLD LLD LLD LLD I Total for period Ci ND ND ND ND ND NOTE: Unit 1 Ventilation & Containment Vent I LLD= Below the Lower Limit of Detectability, in uCi/cc (Table 4). ND= None Detected I

Form 1/2-ENV-01 .05.F01 (page 24 of 39), Rev 5 Beaver Valley Power Station - Unit 1 RTL# A9.690E Enclosure 2, Page 6 of 21 I Annual Radioactive Effluent Release Report I Calendar Year - 2017 Table 1C-GC1 Gaseous Effluents - Ground Level Continuous Releases (Unit 1) I Nuclides released unit Q1 Q2 Q3 Q4 Calendar Year I A. Fission gases Ii argon-41 Ci LLD LLD LLD LLD LLD krypton-85 krypton-85m krypton-87 Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I krypton-88 xenon-131m xenon-133 Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I xenon-133m Ci LLD LLD LLD LLD LLD xenon-135 Ci LLD LLD LLD LLD LLD xenon-135m Ci LLD LLD LLD LLD LLD xenon-138 Ci LLD LLD LLD LLD LLD Total for period Ci ND ND ND ND ND B. Iodines iodine-131 iodine-133 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I iodine-135 Ci LLD LLD LLD LLD LLD Total for period Ci ND ND ND ND ND I C. Particulates chromium-51 manganese-54 Ci Ci LLD LLD LLD LLD LLD LLD LLD I LLD LLD LLD cobalt-57 cobalt-58 cobalt-60 Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 11I zinc-65 selenium-75 zirconium/niobium-95 Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I zirconium/niobium-97 Ci LLD LLD LLD LLD LLD cesium-134 cesium-137 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I cerium-141 Ci LLD LLD LLD LLD LLD cerium-144 strontium-89 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I strontium-90 Ci LLD LLD LLD LLD LLD Total for period Ci ND ND ND ND ND I NOTE: Unit 1 Ventilation & Containment Vent LLD= Below the Lower Limit of Detectability , in uCi/cc (Table 4) . ND = None Detected I I

Form 1/2-ENV-01 .05.F01 (page 25 of 39) , Rev 5 RTL# A9.690E Beaver Valley Power Station - Unit 2 Enclosure 2, Page 7 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Table 1C-GB2 Gaseous Effluents - Ground Level Batch Releases (Unit 2) I Nuclides released unit Q1 Q2 Q3 Q4 Calendar Year I A. Fission gases argon-41 Ci LLD LLD LLD LLD LLD I krypton-85 krypton-85m krypton-87 Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD krypton-88 Ci LLD LLD LLD LLD LLD I xenon-131m xenon-133 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD xenon-133m Ci LLD LLD LLD LLD LLD I xenon-135 xenon-135m Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD xenon-138 Ci LLD LLD LLD LLD LLD I Total for period Ci ND ND ND ND ND B. Iodines I iodine-131 iodine-133 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD iodine-135 Ci LLD LLD LLD LLD LLD I Total for period Ci ND ND ND ND ND C. Particulates I chromium-51 manganese-54 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I cobalt-57 cobalt-58 cobalt-60 Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD zinc-65 Ci LLD LLD LLD LLD LLD I selenium-75 zirconium/niobium-95 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD zirconium/niobium-97 Ci LLD LLD LLD LLD LLD I cesium-134 cesium-137 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD cerium-141 Ci LLD LLD LLD LLD LLD I cerium-144 strontium-89 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD strontium-90 Ci LLD LLD LLD LLD LLD I Total for period Ci ND ND ND ND ND NOTE: Unit 2 Ventilation , Containment, Decontamination Bldg , Waste Gas Vault, & Condensate Polishing Bldg . Vent I LLD= Below the Lower Limit of Detectability, in uCi/cc (Table 4) . ND = None Detected

Form 1/2-ENV-01.05.F01 (page 26 of 39), Rev 5 Beaver Valley Power Station - Unit 2 RTL# A9.690E Enclosure 2, Page 8 of 21 I Annual Radioactive Effluent Release Report I Calendar Year - 2017 Table 1C-GC2 Gaseous Effluents - Ground Level Continuous Releases (Unit 2) I Nuclides released unit Q1 Q2 Q3 Q4 Calendar Year I A. Fission gases I argon-41 Ci LLD LLD LLD LLD LLD krypton-85 krypton-BSm krypton-B7 Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I krypton-BB xenon-131m xenon-133 Ci Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I xenon-133m Ci LLD LLD LLD LLD LLD xenon-135 xenon-135m Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I xenon-138 Ci LLD LLD LLD LLD LLD Total for period Ci ND ND ND ND ND I B. Iodines iodine-131 iodine-133 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I iodine-135 Ci LLD LLD LLD LLD LLD Total for period Ci ND ND ND ND ND I C. Particulates chromium-51 manganese-54 Ci Ci LLD LLD 1.24E-04 2.58E-06 LLD LLD LLD LLD 1.24E-04 2.58E-06 I cobalt-57 cobalt-SB cobalt-GO Ci Ci Ci LLD LLD LLD LLD 2.83E-04 3.29E-05 LLD LLD LLD LLD LLD LLD LLD 2.83E-04 3.29E-05 I I zinc-65 Ci LLD LLD LLD LLD LLD selenium-75 Ci LLD LLD LLD LLD LLD zirconium/niobium-95 Ci LLD 8.56E-05 LLD LLD 8.56E-05 zirconium/niobium-97 Ci LLD LLD LLD LLD LLD cesium-134 cesium-137 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I cerium-141 Ci LLD LLD LLD LLD LLD cerium-144 strontium-89 Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I strontium-90 Ci LLD LLD LLD LLD LLD Total for period Ci ND 5.28E-04 ND ND 5.28E-04 I NOTE : Unit 2 Ventilation , Containment, Decontamination Bldg , Waste Gas Vault, & Condensate Polishing Bldg . Vent LLD= Below the Lower Limit of Detectability , in uCi/cc (Table 4) . ND = None Detected I

I Form 1/2-ENV-01.05.F01 (page 27 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page 9 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 Table 2A I Liquid Effluents - Summation Of All Releases Calendar Total I unit Q1 Q2 Q3 Q4 Year Error % I A. Fission & activation products

1. Total release (excl. H-3, gas & alpha) Ci 1.10E-02 3.62E-02 1.93E-02 4 .39E-03 7.09E-02 26.1 % I
2. Average diluted concentration uCi/ml 2.65E-09 7.94E-09 4.37E-09 1.02E-09 4.06E-09 I 3. Percent of applicable limit  % 4.42E-01 1.45E+OO 7.72E-01 1.76E-01 7.09E-01
8. Tritium I 1. Total release Ci 2.20E+02 3.18E+02 2.03E+02 4.79E+02 1.22E+03 25.0% I
2. Average diluted concentration uCi/ml 5.28E-05 6.97E-05 4.59E-05 1.11 E-04 6.99E-05 I 3. Percent of applicable limit  % 5.28E-01 6.97E-01 4.59E-01 1.11E+OO 6.99E-01 C. Dissolved and entrained gases I 1. Total release
2. Average diluted concentration Ci uCi/mL ND 1.27E-04 2.78E-11 ND ND 1.27E-04 7.26E-12 27.0% I
3. Percent of applicable limit  % 1.39E-05 3.63E-06 I D. Gross alpha radioactivity Ci LLD LLD LLD LLD LLD 28 .9%

(total release) I E. Volume of waste released L 1.26E+07 1.34E+07 1.32E+07 1.27E+07 5.19E+07 11 .2% (prior to dilution) I F. Volume of dilution water used L 4.16E+09 4.54E+09 4.41 E+09 4.30E+09 1.74E+10 22 .9% I LLD= Below the Lower Limit of Detectability, in uCi/mL (Table 4) I A.3 is based on a historical PA-DEP guide of 10 Ci/yr 8 .3 is based on a ODCM limit of 1.00E-2 uCi/mL C.3 is based on a ODCM limit of 2.00E-04 uCi/mL I The values listed at F. are the volumes during actual liquid waste discharge periods. The total dilution volume for a continuous calendar quarter is approximately 1E+10 liters for BVPS-1 & 2 (ie.; - 22,800 gpm is the total dilution flow rate from the site) I I

Form 1/2-ENV-01 .05 .F01 (page 28 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page 10 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Table 28-B Liquid Effluents - Batch Releases I Calendar Nuclides released unit Q1 Q2 Q3 Q4 Year I A. Fission & Activation Products berylllum-7 sodium-24 chromlum-61 Cl Cl Cl LLD LLD LLD LLD LLD 2.SSE-03 LLD LLD 5.SOE-05 LLD LLD LLD LLD LLD 2.63E-03 I manganese-64 iron-69 cobalt-67 cobalt-58 Cl Cl Cl Cl 2.20E-04 LLD 3.73E-05 5.64E-04 3.23E-04 LLD 5.0SE-05 1.47E-02 3.47E-03 9.71E-06 4.30E-05 5.91E-03 1.07E-05 LLD 1.14E-05 1.11E-03 4.02E-03 9.71E-06 1.42E-04 2.23E-02 I cobalt-60 zlnc-66 zfrconium/nloblum-96 Cl Cl Cl 4.82E-03 2.19E-05 LLD 5.76E-03 LLD 9.21E-04 2.29E-03 LLD 2.04E-04 5.57E-04 LLD 3.70E-05 1.34E-02 2.19E-05 1.16E-03 I zfrconium/nlobfum-97 Ci 6.0?E-06 LLD 2.66E-05 3.0?E-05 6.33E-05 molybdenum-99/technetlum-99m ruthenfum-103 ruthenlum-106 Ci er Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I sllver-110m Cl 2.45 E-03 1.66E-03 3.SOE-04 7.SSE-05 4.53E-03 tln-113 tln-117m antlmony-122 Ci Cl Cl LLD LLD LLD 1.BSE-04 LLD 5.0BE-05 LLD LLD LLD LLD LLD LLD 1.BSE-04 LLD 5.0BE-05 I antrmony-124 Cl LLD 3.60E-04 1.79E-04 LLD 5.38E-04 antlmony-125 iodlne-131 lodlne-133 Cl Cl Cl 1.61E-03 LLD LLD 5.76E-03 LLD LLD 2.98E-03 LLD LLD 1.16E-03 LLD LLD

1. 15E-02 LLD LLD I

lodlne-136 Cl LLD LLD LLD LLD LLD ceslum-134 ceslum-137 barlum/lanthanum-140 Cl Cl Cl LLD 3.48E-05 LLD LLD 8.00E-05 LLD LLD 8.71E-07 LLD LLD 2.77E-06 LLD LLD 1.18E-04 LLD I cerfum-141 cerfum-144 iron-65 Cl Cl Ci LLD LLD 1.28E-03 LLD LLD 3.77E-03 LLD LLD 3.78E-03 LLD LLD 1.40E-03 LLD LLD 1.02E-02 I strontium-89 Cl LLD LLD LLD LLD LLD strontlum-90 Total for period Cl Cl LLD 1.10E-02 LLD 3.62E-02 LLD 1.93E-02 LLD 4.39E-03 LLD 7.09E-02 I B. Tritum hydrogen-3 Cl I 2.20E+02 I 3. 17E+02 I 2.02E+02 I 4.79E+02 I 1.22E+03 I I Total for period Cl I 2.20E+02 I 3. 17E+02 I 2.02E+02 I 4.79E+02 I 1.22E+03 I C. Dissolved & Entrained Gases I argon-41 Cl LLD LLD LLD LLD LLD krvpton-85 xenon-131m xenon-133 Ci Cl Cl LLD LLD LLD LLD LLD 1.27E-04 LLD LLD LLD LLD LLD LLD LLD LLD 1.27E-04 I' xenon-133m Cl LLD LLD LLD LLD LLD xenon-135 Ci LLD LLD LLD LLD LLD xenon-136m Ci LLD LLD LLD LLD LLD Total for period Cl ND 1.27E-04 ND ND 1.27E-04 LLD= Below the Lower Limit of Detectability , in uCi/mL (Table 4) ND= None Detected I I

I Form 1/2-ENV-01 .05.F01 (page 29 of 39), Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9 .690E Enclosure 2, Page 11 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 Table 2B-C I Liquid Effluents - Continuous Releases Calendar Nuclides released unit Q1 Q2 Q3 Q4 Year A. Fission & Activation Products I beryllium-7 sodlum-24 Ci Cl LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD chromlum-51 Cl LLD LLD LLD LLD LLD manganese-64 Cl LLD LLD LLD LLD LLD lron-69 Ci LLD LLD LLD LLD LLD cobalt-67 Ci LLD LLD LLD LLD LLD cobalt-68 Ci LLD LLD LLD LLD LLD cobalt-SO Cl LLD LLD LLD LLD LLD zinc-66 Ci LLD LLD LLD LLD LLD zlrconlum/nlobium-96 Cl LLD LLD LLD LLD LLD zirconlum/nloblum-97 Cl LLD LLD LLD LLD LLD I molybdenum-99/technetlum-99m ruthenlum-103 ruthenlum-106 Cl Cl Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD sllver-110m Cl LLD LLD LLD LLD LLD I tln-113 tln-117m antlmony-122 Cl Cl Cl LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD antlmony-124 Cl LLD LLD LLD LLD LLD I antlmony-125 iodlne-131 lodlne-133 Cl Cl Cl LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD lodlne-135 Cl LLD LLD LLD LLD LLD I ceslum-134 ceslum-137 barlum/lanthanum-140 Cl Ci Cl LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I cerlum-141 cerlum-144 iron-55 Ci Cl Cl LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD strontlum-89 Ci LLD LLD LLD LLD LLD I strontlum-90 Total for period Cl Ci LLD ND LLD ND LLD ND LLD ND LLD ND I B. Tritum hydrogen-3 Cl I 1.43E-01 I 1.82E-01 I 2.69E-01 I 2.33E-01 I 8.28E-01 I Total for period Ci I 1.43E-01 I 1.82E-01 I 2.69E-01 I 2.33E-01 I 8.28E-01 I I C. Dissolved & Entrained Gases ar11on-41 Cl LLD LLD LLD LLD LLD I krvpton-86 xenon-131m xenon-133 Cl Ci Ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD xenon-133m Cl LLD LLD LLD LLD LLD I xenon-135 xenon-135m Cl Cl LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD Total for period Ci ND ND ND ND ND I LLD= Below the Lower Limit of Detectability , in uCi/mL (Table 4) ND= None Detected II I

Form 1/2-ENV-01.05.F01 (page 30 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9 .690E Enclosure 2, Page 12 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Table 3A Solid Waste And Irradiated Fuel Shipments (Part 1 of 3) I A. Solid Waste Shipped Offsite For Burial Or Disposal (Not irradiated fuel)

1. Type of Waste (Spent resins, Filter Sludges, Evaporator Bottoms, Oil)

Jan -Jun Jul - Dec Estimated Total Error I

a. Volume Shipped 12.40 m 3 11 .52 m 3 0.0% (1)
b. Volume Buried
c. Total Activity 2.80 m 3 43 .10 Ci 8.80 m 3 36.36 Ci 0.0% (1) 30.0%

I

2. Estimate of Major Nuclide Composition by Tvoe of Waste On This TablE ( >

H-3 2 Percent(%) 1.08 % Percent(%) 1.64 % I C-14 4.41 % 2.48 % Mn-54 Fe-55 0.416 % 9.68 % 0.88 % 7.72 % I Co-58 6.98 % 2.01 % Co-60 Ni-59 13.22 % 0.694 % 19 04 % 0.34 % I Ni-63 58 .80 % 60.84 % Zn-65 Zr-95 0.327 % 0.38 % 0.48 % 0.11 % I Nb-95 0.786 % 0.24 % Sb-125 Cs-137 1.61 % 0.38 % 3.03 % 0.64 % I

3. Number of Shipments 7 4
a. Type of LSA Type A 7

0 4 0 I Container Used

b. Solidification Type B Large Quantity Cement 0

0 0 0 0 0 I Agent UreaFormaldehyde 0 0 Used

c. Mode of None Truck 7

7 4 4 I Transport Rail 0 0

d. Final Other Oak Ridge, TN 0

6 0 3 I Destination Erwin, TN 1 1

e. Waste Class Class A Class B 2

1 4 0 I per Class C 4 0 10 CFR Part 61 > Class C 0 0 I (1) Since container volumes are provided by the burial site, a calcu lational error of zero is assumed . (2) Percent va lues for any nuclide that are <0.01 % are not shown on this table . Data is available upon request. I I I

I Form 1/2-ENV-01.05.F01 (page 31 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page 13 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 Table 38 I Solid Waste And Irradiated Fuel Shipments (Part 2 of 3) A. Solid Waste Shipped Offsite For Burial Or Disposal (Not irradiated fuel) I 1. Type of Waste (Dry Compressible Waste, Contaminated Equipment, etc.) Jan -Jun Jul - Dec Estimated Total Error

a. Volume Shipped 275.00 m 3 366 .13 m 3 0.0% (1)

I b. Volume Buried

c. Total Activity 28.82 m 0.63 Ci 3

27 .20 m 3 1.73 Ci 0.0% (1) 30.0%

2. Estimate of Major Nuclide Composition I by Type of Waste On This Table <2>

H-3 Percent(%) 4.34 % Percent(%) 0.10 % C-14 1.19 % 1.48 % I Cr-51 Mn-54 0.41 % 0.57 % 0.085 % 0.36 % Fe-55 28.1 % 21 .30 % I Co-58 Co-60 15.54 % 18.6 % 4.57 % 14.62 % Ni-59 0.07 % 0.0 % I Ni-63 Zn-65 26.9 % 0.03 % 0.2 % 0.0 % Zr-95 0.61 % 0.2 % I Nb-95 Ag-110m 1.0 % 0.08 % 0.39 % 0.13 % Sn-113 0.0 % 0.002 % I Sb-125 Cs-134 1.37 % 0.0 % 2.17 % 0.5 % Cs-137 8.0 % 7.0 % I 3. Number of Shipments

a. Type LSA 6

6 5 5 of Type A 0 0 I Container Used Type B Large Quantity 0 0 0 0

b. Solidification Cement 0 0 I Agent Used UreaFormaldehyde None 0

6 0 5

c. Mode of Truck 6 5 I Transport Rail Other 0

0 0 0

d. Final Oak Ridge, TN 6 5 I Destination
e. Waste Wampum, PA Class A 0

6 0 5 Class Class B 0 0 I per 10 CFR Part 61 Class C

                                            > Class C 0

0 0 0 I (1) Since container volumes are provided by the burial site , a calculational error of zero is assumed . (2) Percent values for any nuclide that are <0.01 % are not shown on this table . Data is available upon request. I

Form 1/2-ENV-01 .05.F01 (page 32 of 39), Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL # A9 .690E Enclosure 2, Page 14 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Table 3C Solid Waste And Irradiated Fuel Shipments (Part 3 of 3) I A. Solid Waste Shipped Offsite For Burial Or Disposal (Not irradiated fuel)

1. Type of Waste (Irradiated components, Control Rods, etc)

Jan -Jun Jul - Dec Estimated Total Error I

a. Volume Shipped m3 m3
b. Volume Buried m3 m3
c. Total Activity Ci Ci 0.0%
2. Estimate of Major Nuclide Composition Percent(%) Percent(%)

by Tvoe of Waste On This TablEl 2> I I I

3. Number of Shipments a.Type of LSA Type A I

Container Type B Used

b. Solidification Large Quantity Cement I

Agent Urea Formaldehyde Used

c. Mode of None Truck I

Transport Rail

d. Final Other Oak Ridge, TN I

Destination Barnwell, SC

e. Waste Class Class A Class B I

per Class C 10 CFR Part 61 > Class C I B. No Irradiated Fuel Shipments I (1) Since container volumes are provided by the burial site, a calculational error of zero is assumed . (2) Percent values for any nuclide that are <0.01 % are not shown on this table. Data is available upon request. I I I

I Form 1/2-ENV-01 .05.F01 (page 33 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page 15 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 Table 4 I Lower Limits Of Detectability (LLD) RWDA-G RWDA-L Filter Paper/ Charcoal I 1000 cc Gas Grab Sample Calculated (3) ODCM Required 1000 ml Liauid Grab Samole Calculated (3) ODCM Required Continuous Effluent Sam le Calculated (3) ODCM Required Nuclide LLD LLD LLD LLD (2) LLD LLD I H-3 Na-24 (4) (uCi/ccl 1.00E-06 7.33 E-08 (uCi/cc) 1E-06 1E-04 (uCi/mL) 1.00E-06 1.63E-08 (uCi/mL) 1E-06 SE-07 uCi/cc uCi/cc 1E-11 Ar-41 1.09E-07 1E-04 2.42E-08 SE-07 I Cr-51 Mn-54 Fe-55 3.29E-07 5.35E-08 1E-04 1E-04 (1) 7.98E-08 1.22E-08 1.00E-06 SE-07 SE-07 1E-06 1E-11 1E-11 Fe-59 1.15E-07 1E-04 2.59E-08 SE-07 2.91E-13 1E-11 I Co-57 Co-58 Co-60 4.61 E-08 4.71 E-08 5.29E-08 1E-04 1E-04 1E-04 1.25E-08 1.07E-08 1.18E-08 SE-07 5E-07 SE-07 7.44E-14 1.99E-13 2.99E-13 1E-11 1E-11 1E-11 Zn-65 1.77E-07 1E-04 3.96E-08 SE-07 5.74E-13 1E-11 I Se-75 Kr-85 Kr-85m 1.21 E-05

6. 17E-08 1E-04 1E-04 2.86E-06 1.60E-08 1E-05 1E-05 9.33 E-14 1E-11 Kr-87 1.22E-07 1E-04 2.93E-08 1E-05 I Kr-88 Sr-89 Sr-90 1.78E-07 1E-04 (1)

(1) 4.48E-08 5.00E-08 5.00E-08 1E-05 SE-08 SE-08 Sr-92 1.22 E-07 1E-04 2.71E-08 SE-07 2.26E-13 1E-11 I Nb-95 Nb-97 Zr-95 6.75 E-08 7.44E-08 1.00E-07 1E-04 1E-04 1E-04 1.55E-08 1.72E-08 2.30E-08 SE-07 SE-07 SE-07 1.43E- 13 1.47E-13 2.76 E-13 1E-11 1E-1 1 1E-11 Mo-99 5.37E-07 1E-04 1.23E-07 SE-07 1.70E-12 1E-1 1 I Tc-99m Aci-11 0m Sb-124 4.BOE-08 6.64E-08 5.43E-08 1E-04 1E-04 1E-04 1.27E-08 1.54E-08 1.27 E-08 SE-07 5E-07 SE-07 8.92E-14 1.40E-13 1.BOE-13 1E-11 1E-11 1E-11 Sb-125 1.62E-07 1E-04 3.87E-08 SE-07 2.97 E-13 1E-11 I 1-131 1-133 1-135 6.27E-08 4.42E-08 3.45E-07 1E-04 1E-04 1E-04 1.51E-08 1.04E-08 7.68E-08 1E-06 5E-07 SE-07 1.25E-13 1.98E-13 1E-12 1E-10 Xe-131m 1.89E-06 1E-04 4.85E-07 1E-05 Xe-133 1.29 E-07 1E-04 4.32E-08 1E-05 Xe-133m 3.99E-07 1E-04 9.87E-08 1E-05 Xe-135 4.24E-08 1E-04 1.04E-08 1E-05 Xe-135m 7.71 E-08 1E-04 1.81E-08 1E-05 Xe-137 7.07E-07 1E-04 1.68E-07 1E-05 Xe-138 2.16E-07 1E-04 5.30E-08 1E-05 Cs-134 4.73 E-08 1E-04 1.10E-08 SE-07 1.28E-13 1E-11 Cs-137 7.11 E-08 1E-04 1.64E-08 SE-07 1.49E-13 1E-11 I Ba-139 Ba-140 La-140 1.90E-07 1.58E-07 6.94E-08 1E-04 1E-04 1E-04 4.87E-08 3.71 E-08 1.55E-08 SE-07 SE-07 SE-07 2.67E-1 3 3.79 E-13 2.82E-13 1E-11 1E-11 1E-11 Ce-141 8.32E-08 1E-04 2.18E-08 5E-07 1.66E-13 1E-11 I Ce-144 Gross Alpha 3.19E-07 (1) Sample analyses perform ed by a contractor laboratory. 1E-04 (1) 8.52E-08 1.00E-07 5E-07 1E-07 8.47E-13 3.51E-1 5 1E-1 1 1E-1 1 I (2) These LLD calculations contain a default weekly continuous sample volu me of 2.85 E+8 cc. Therefore, grab sample LLD val ues reflect a different volume (ie; 10 cuft or 2.83E+5 cc) . (3) T he calculated LLD's are for Unit 2 Detector 2, except those denoted by (1) , are from a counter/detector cal ibration on 11 /16/17. I These values are typical for other counter/d etectors used for effluent counti ng at BVPS. (4) Based on counting 50 ml of the water that was bubbled through a 20 liter air sampl e. I

Form 1/2-ENV-01 .05.F01 (page 34 of 39) , Rev 5 Beaver Valley Power Station - Unit 1 RTL# A9 .690E Enclosure 2, Page 16 of 21 I Annual Radioactive Effluent Release Report I Calendar Year - 2017 Table 5A Assessment Of Radiation Doses I Unit 1 Liquid Effluents I 1st Quarter

                                        % of 2nd Quarter
                                                                   % of 3rd Quarter
                                                                                            % of 4th Quarter
                                                                                                                           % of Calendar Year
                                                                                                                                             % of    I Batch              Dose         ODCM          Dose ODCM                 Dose ODCM                   Dose          ODCM       Dose ODCM Releases Bone              5.94E-04 Limit 0.0119     2.13E-03 Limit 0.0426     4.27E-05 Limit 0.0009        7.78E-05 Limit 0.0016  2.85E-03 Limit 0.0285 I

0 Liver 6 .96E-03 0.1392 1.55E-02 0.3110 6.17E-03 0.1235 6.05E-03 0.1209 3.47E-02 0.3473 R G Total Body Thyroid 6.70E-03 6.10E-03 0.4469 0.1220 1.48E-02 1.31 E-02 0.9880 0.2619 6.18E-03 6.08E-03 0.4123 0.1217 6.01E-03 5.96E-03 0.4007 0.1192 3.37E-02 3.12E-02 1.1239 0.3124 I A N (1) Kidney Lung GI-LLI 6.39E-03 6.18E-03 7.15E-03 0.1278 0.1237 0.1430 1.38E-02 1.34E-02 1.84E-02 0.2758 0.2680 0.3681 6.09E-03 6.10E-03 6.93E-03 0.1219 0.1219 0.1386 5.98E-03 5.98E-03 6.14E-03 0.1195 0.1197 0.1228 3.23E-02 3.17E-02 3.86E-02 0.3225 0.3166 0.3863 I I Unit 1 Gaseous Effluents 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Calendar Year I

                                        % of                        % of                    % of                           % of Batch &

Continuous Releases Dose ODCM Limit Dose ODCM Limit Dose ODCM Limit Dose ODCM Limit Dose ODCM

                                                                                                                                             %of Limit I

(2) Gamma Air (2) Beta Air O.OOE+OO O.OOE+OO 0.0000 0.0000 5.59E-07 2.65E-09 0.0000 0.0000 O.OOE+OO O.OOE+OO 0.0000 0.0000 O.OOE+OO O.OOE+OO 0.0000 0.0000 5.59E-07 2.65E-09 0.0000 0.0000 I Bone O.OOE+OO 0.0000 3.65E-09 0.0000 1.38E-08 0.0000 O.OOE+OO 0.0000 1.74E-08 0.0000 0 Liver R Total Body 2.82E-03 2.82E-03 0.0376 0.0376 3.72E-03 3.72E-03 0.0496 0.0496 5.31 E-03 5.31E-03 0.0708 0.0708 1.03E-02 1.03E-02 0.1374 0.1374 2.22E-02 2.22E-02 0.1477 0.1477 I G Thyroid 2.82E-03 0.0376 3.72E-03 0.0496 5.31E-03 0.0708 1.03E-02 0.1374 2.22E-02 0.1477 A Kidney N Lung 2.82E-03 2.82E-03 0.0376 0.0376 3.72E-03 3.72E-03 0.0496 0.0496 5.31E-03 5.31E-03 0.0708 0.0708 1.03E-02 1.03E-02 0.1374 0.1374 2.22E-02 2.22E-02 0.1477 0.1477 I (3) GI-LLI 2.82E-03 0.0376 3.72E-03 0.0496 5.31 E-03 0.0708 1.03E-02 0.1374 2.22E-02 0.1477 (1) These doses are listed in mrem ; they are calculated for the maximum individual for all batch liquid effluents I (2) These doses are listed in mrad ; they are calculated at the site boundary for batch & continuous gaseous effluents (0.4 miles NW) (3) These doses are listed in mrem ; they are calculated for the most likely exposed real individual (ch ild) via all real pathways at 0.89 miles NW. I Limits used for calculation of percent(%) are from ODCM procedure 1/2-0DC-3.03, Attachment H Control 3.11.1.2, Attachment L Control 3.11.2.2, and Attachment M Control 3.11.2.3 (considered to be the design objectives). I I I

I Form 1/2-ENV-01 .05.F01 (page 35 of 39), Rev 5 Beaver Valley Power Station - Unit 2 RTL# A9.690E Enclosure 2, Page 17 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Table 58 Assessment Of Radiation Doses I Unit 2 Liquid Effluents I 1st Quarter

                                          % of 2nd Quarter
                                                                     % of 3rd Quarter
                                                                                              % of 4th Quarter
                                                                                                                            % of Calendar Year
                                                                                                                                              % of Batch              Dose ODCM                  Dose ODCM                 Dose ODCM                  Dose ODCM                Dose ODCM I        Releases Bone              5.94E-04 Limit 0.01 19    2.13E-03 Limit 0.0426     4.27E-05 Limit 0.0009       7.78E-05 Limit 0.0016  2.85E-03 Limit 0.0285 0     Liver             6.96E-03        0.1392     1.55E-02        0.31 10    6.17E-03      0.1235       6 .05E-03        0.1209  3.47E-02  0.3473 I  R G

Total Body Thyroid 6.70E-03 6.10E-03 0.4469 0.1220 1.48E-02 1.31 E-02 0.9880 0.2619 6.18E-03 6.08E-03 0.4123 0.1217 6.01E-03 5.96E-03 0.4007 0.1192 3.37E-02 3.12E-02 1.1239 0.3124 I A N Kidney Lung 6.39E-03 6.18E-03 0.1278 0.1237 1.38E-02 1.34E-02 0.2758 0.2680 6.09E-03 6.10E-03 0.1219 0.1219 5.98E-03 5.98E-03 0.1195 0.1197 3.23E-02 3.17E-02 0.3225 0.3166 (1) GI-LLI 7.15E-03 0.1430 1.84E-02 0.3681 6.93E-03 0.1386 6.14E-03 0.1228 3.86E-02 0.3863 I I 1st Quarter 2nd Quarter Unit 2 Gaseous Effluents 3rd Quarter 4th Quarter Calendar Year I Batch & Continuous Releases Dose ODCM

                                          % of Limit Dose ODCM
                                                                     % of Limit Dose ODCM
                                                                                              % of Limit Dose ODCM
                                                                                                                            % of Limit Dose ODCM
                                                                                                                                              % of Limit I (2) Gamma Air O.OOE+OO (2) Beta Air             O.OOE+OO 0.0000 0.0000 5.59E-07 2.65E-09 0.0000 0.0000 O.OOE+OO O.OOE+OO 0.0000 0.0000 O.OOE+OO O.OOE+OO 0.0000 0.0000 5.59E-07 2.65E-09 0.0000 0.0000 Bone              O.OOE+OO        0.0000      3.67E-04        0.0049    1.38E-08       0.0000     O.OOE+OO          0.0000  3.67E-04  0.0024 I  0 Liver R Total Body 8.84E-04 8.84E-04        0.0118 0.0118 9.35E-04 9.62E-04 0.01 25 0.0128 7.60E-04 7.60E-04 0.0101 0.0101 8.60E-04 8.60E-04 0.0115 0.0115 3.44E-03 3.47E-03 0.0229 0.0231 G Thyroid                8.84E-04       0.0118      9.20E-04        0.01 23   7.60E-04       0.0101      8.60E-04         0.0115  3.42E-03   0.0228 I  A Kidney N Lung 8.84E-04 8.84E-04 0.0118 0.0118 9.22E-04 1.42E-03 0.0123 0.0190 7.60E-04 7.60E-04 0.0101 0.0101 8.60E-04 8.60E-04 0.0115 0.0115 3.43E-03 3.93E-03 0.0228 0.0262 (3) GI-LLI I                           8.84E-04       0.0118      1.03E-03        0.0137    7.60E-04       0.0101      8.60E-04 (1) These doses are listed in mrem ; they are calculated for the maximum individual for all batch liquid effluents 0.0115  3.53E-03   0.0236 I (2) These doses are listed in mrad ; they are calculated at the site boundary for batch & continuous gaseous effluents (0.4 miles NW)

(3) These doses are listed in mrem ; they are calculated for the most likely exposed real individual (child) via all real pathways at 0.89 miles NW I Limits used for calculation of percent(%) are from ODCM procedure 1/2-0DC-3.03, Attachment H Control 3.11 .1.2, Attachment L Control 3.11.2.2, and Attachment M Control 3. 11.2.3 (considered to be the design objectives). I I

Form 1/2-ENV-01 .05 .F01 (page 36 of 39), Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page 18 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Table 6 I Effluent Monitoring Instrumentation Channels Not Returned To Operable Status Within 30 Days I There were two Effluent Monitoring Instrumentation Channels that were not returned to operable status within 30 days.

1) Unit 1 Main Steam Effluent Monitor, RM-1 MS-1 OOC On 03/25/17 the monitor was taken out of service to inspect and repair with regards to spiking . It was determined that the detector and preamp were to be replaced . Due to the location of the detector, it must be replaced during an outage . The monitor is currently out of service and is schedu led to be replaced during 1R25. (reference CR-2017-04541 ).
2) Unit 1 Liquid Waste Effluent Monitor, RM-1LW-104 On 11/26/17 the monitor was taken out of service in support of ECP 16-0113-001 that would replace and install new digital rate meters. Due to Engineering and vendor issues with parts, the replacement was delayed. The monitor was returned to I

service on 02/01/2018 (reference CR-2017-12446). I I I I I I I I I

I Form 1/2-ENV-01 .05.F01 (page 37 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9 .690E Enclosure 2, Page 19 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Table 7 Total Dose Commitments, Total Effective Dose Equivalents and Population Doses I Total Dose Commitment From All Facility Releases To Members of the Public 40 CFR 190.10(a) Environmental Doses Effluent Dose 11 l Direct Radiation Dose 121 Total Dose  % ofODCM or ,I Organ Bone (mrem) 6 .06E-03 (mrem) O.OOE+OO (mrem) 6.06E-03 40 CFR 190 Limit 0.02% 'I Liver Total Body 9 .50E-02 9.30E-02 O.OOE+OO O.OOE+OO 9.50E-02 9.30E-02 0.38% 0 .37% Thyroid 8 .80E-02 O.OOE+OO 8.80E-02 0.12% I Kidney Lung 9 .01E-02 8.94E-02 O.OOE+OO O.OOE+OO 9.01E-02 8.94E-02 0.36% 0.36% GI-LLI 1.03E-01 O.OOE+OO 1.03E-01 0.41% I (1) The cumulative dose contributions from liquid and gaseous effluents were determined in accordance with the applicable CONTROLS & SURVEILLANCE REQUIREMENTS listed in ODCM procedure 1/2-0DC-3.03. I The dose commitment limits for 40 CFR 190 MEMBERS OF THE PUBLIC (ODCM 1/2-0DC-3.03 Control 3.11.4.1) are as follows : a) <or= 25 mrem / calendar year (for the total body, or any organ except the thyroid) I b) < or= 75 mrem / calendar year (for the thyroid) (2) The dose contribution listed for the total body is for Direct Radiation . This was calculated by comparing offsite TLD exposure at the ODCM controlling location (0 .8 miles NW; Midland, PA) to TLD exposure at the I REMP control location (16 .5 miles SSW; Weirton , WV) . Compliance to 100 mrem Limit of 10 CFR 20.1301 For Total Effective Dose Equivalent I Pursuant to 10 CFR 20.1301(a)(1), the Tota l Effective Dose Equivalent from licensed operation to the maximum individual during the report period , is 5.06 mrem. This is a summation of Direct Radiation Exposure (calculated by comparing the maximum of all perimeter TLD exposures to TLD exposure at the REMP control location) plus Effluent Doses (calcu lated per the ODCM). I Members of the Public Doses Due To Their Activities Inside The Site Boundary I The radiation doses for MEMBER(S) OF THE PUBLIC due to their activities inside the site boundary are not greater than the doses listed in this table to show compliance with 40 CFR Part 190 or 10 CFR 20.1301 . Evaluations have shown that exposure time for individuals not occupationally associated with the plant site is minimal in comparison to the exposure time considered I for the dose calculation at or beyond the site boundary. Therefore , a separate assessment of radiation doses from radioactive effluents to MEMBER(S) OF THE PUBLIC , due to their activities inside the site boundary , is not necessary for this report period. I 0-50 Mile Population Doses From Liquid and Gaseous Effluents 0-50 mile Total Population Dose from liquid and gaseous effluents= 99.96 man-mrem (Total Body) 0-50 mile Average Population Dose from liquid and gaseous effluents = 0.0000250 man-mrem (Total Body) I I I

Form 1/2-ENV-01 .05.F01 (page 38 of 39) , Rev 5 Beaver Valley Power Station - Units 1 & 2 RTL# A9.690E Enclosure 2, Page 20 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Table 8 I Offsite Dose Calculation Manual Surveillance Deficiencies I There were three Offsite Dose Calculation Manual Surveillance Deficiencies during this report period .

1) Main Steam Cable Vault (Fire Sump) sample On 5/22/17 the main steam cable vault was discharged. Two independent samples were obtained by Radiation I

Protection and no isotopes were identified. However, the samples were discarded before Chemistry could analyze them for tritium . The discharge was documented and based on the tritium from the most recent sump discharge (reference CR-2017-07282) . I

2) Catch Basin (Yard Drain) Sample Catch Basin 17A, 1CB-17A, is sampled annually. During Q4 2017 , there was no flow observed at this location and no sample could be obtained. Th is location is the first sample point of the yard drains around Unit 1 and samples I

were obtained downstream of 1CB-17A and had no LRM detected . (reference CR-2018-00126)

3) Beaver Valley Representative Sampling I

It was determined that, due to incorrectly sized nozzles and variations the ventilation stack flows , the effluent monitor sampling skid does not provide representative sampling of particulate isotopes (especially of larger particle sizes) under all normally occurring ventilation conditions at all of Unit 1 pathways and Unit 2 Ventilation Vent and Condensate Polishing Building Vent pathways. This condition was identified and questioned during a Unit 1 sample I pump replacement in April 2017. Due to the limited amount of particu late that is released from the site, it does not significantly affect dose or dose rates to the pub lic, nor challenge any regulatory limits (reference CR-2017-04211 ). I I I I I I I I I I

Form 1/2-ENV-01 .05.F01 (page 39 of 39), Rev 5 RTL# A9 .690E Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Page 21 of 21 I Annual Radioactive Effluent Release Report Calendar Year - 2017 Table 9 I Offsite Dose Calculation Manual Changes (Description) I There was one (1) change made to the ODCM during the report period. See ODCM procedure 1/2-0DC-1 .01 , I "ODCM : Index, Matrix and History ODCM Changes" for a complete description of the change and the change justification. A brief description of the change is as follows :

1) Change (41) to the ODCM (Effective January 2017)

I <> Procedure 1/2-0DC-1.01 , "ODCM : Index, Matrix and History of ODCM Changes" (Rev 24) Updated the History of ODCM changes to include this change I <> Procedure 1/2-0DC-2.03, "ODCM : Radiological Environmental Monitoring Program" (Rev 8) Updated for the relocation of waterbourne surface sample location from #2 .1 to #5 and added milk sample location #114 . Maps for all sample locations were updated . I I I I I I I I I I I I

I I I I I I I I I ENCL0SURE2,ATTACHMENT1 I I I I I I I I I I

I Beaver Valley Power Station - Units 1 & 2 RTL # A9.690E Enclosure 2, Attachment 1 I Annual Radioactive Effluent Release Report Calendar Year - 2017 Attachment 1 Joint Frequency Distribution Tables Attachment 1 I As specified in the ODCM , an annual summary of hourly meteorological data (in the form of joint frequency distribution) is provided for the calendar year. In summary , the joint frequency distribution data is similar to previous years and close to long-term normals. I Meteorological Data Recovery I The Meteorological Data Recovery for the calendar year met the minimum requirement of at-least 90% (as specified in Section 5 of Revision 1 to Regulatory Guide 1.23, Meteorological Monitoring Programs for Nuclear Power Plants) . The actual Meteorological Data Recovery is shown in the following table : I PERCENT RECOVERY OF INDIVIDUAL METEOROLOGICAL PARAMETERS 99.5% =Wind Speed 35' 98 .1% =Wind Speed 150' 99.9% =Wind Speed 500' I 99.9% =Wind Direction 35' 99.9% =Wind Direction 150' 99.8% =Wind Direction 500' I 99.8% =Delta Temperature (150' - 35') 1P 99.8% =Delta Temperature (500' - 35' ) 2P 99.8% =Temperature 35' 99 .9% =Precipitation I 99.6% =Average Recovery of Individual Meteorological Parameters PERCENT RECOVERY OF COMPOSITE VARIABLES I 99.7% =Wind Speed 35', Wind Direction 35', Delta Temperature 1P 98.1% =Wind Speed 150', Wind Direction 150', Delta Temperature 1P 99.7% =Wind Speed 500', Wind Direction 500', Delta Temperature 2P

                                          =Average Recovery of Composite Variables I                                 99.5%

Attachment 1 Clarification Hourly meteorological data is not provided for specific periods of Abnormal Gaseous Release during the calendar I quarters (as indicated in Regulatory Guide 1.21 ), for the following reasons :

1) All routine Gaseous Releases for the calendar year were determined to be within design objectives, where as, the I ODCM Dose Limits and the ODCM Dose Rate Limits are considered to be the design objectives.
2) There were two Abnormal Gaseous Releases during the calendar year, neither exceeded design objectives.

I For a copy of the hourly meteorological data during the calendar quarters, contact Radiological Effluents Administrator at 724-682-4255. I I I I

RTL A9.690E Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Attachment 1 (Part 1 of 3) Annual Radioactive Effluent Release Report Calendar Year - 2017 I Part 1: Joint Frequency Distribution Tables (35ft) Page 1 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period All Hours I Period of Record Elevation:

                        =

Speed: SP35P 01/01 /2017 0 I :00 - 12/31 /2017 23 :00 Direction: DI35P Lapse: DT150-35 I Stability Class: A Delta Temperature Extremely Unstable Ii Wind Speed (mph) Wind Direction 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total Ii N 43 42 0 0 0 0 85 NNE NE ENE 34 41 59 28 7 18 0 0 0 0 0 0 0 0 0 0 0 0 62 48 77 I E 25 24 0 0 0 0 49 ESE SE SSE 30 31 11 7 9 6 0 0 0 0 0 0 0 0 0 0 0 0 37 40 17 I s 21 24 1 0 0 0 46 SSW SW 19 26 49 66 24 9 0 0 0 0 0 0 77 116 I WSW 32 104 17 0 0 0 153 w 39 143 17 0 0 0 199 WNW 47 98 6 0 0 0 151 NW 52 50 2 0 0 0 104 NNW 35 44 0 0 0 0 79 Total 545 719 76 0 0 0 1340 Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 240 0 I' Invalid Hours for: Total Period All Hours 26 Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 1340 8759 I I I I

I Beaver Valley Power Station - Units 1 & 2 RTLA9.690E Enclosure 2, Attachment 1 (Part 1 of 3) Annual Radioactive Effluent Release Report I Calendar Year - 20 17 Attachment 1 I Part I : Joint Frequency Distribution Tables (35ft) Page 2 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period All Hours I Period of Record Elevation:

                           =

Speed: SP35P 01/01 /2017 01:00- 12/31 /2017 23:00 Direction: DI35P Lapse: DT150-35 I Stability Class: B Delta Temperature Moderately Unstable Wind Speed (mph) I Wind Direction N 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total 9 4 0 0 0 0 13 I NNE NE ENE 2 7 10 5 0 4 0 0 0 0 0 0 0 0 0 0 0 0 7 7 14 E 4 1 0 0 0 0 5 I ESE SE SSE 2 4 5 0 2 1 0 0 0 0 0 0 0 0 0 0 0 0 2 5 7 s I SSW SW 2 2 2 3 9 9 0 7 13 0 0 3 0 0 0 0 0 0 5 18 27 WSW 7 24 8 I 0 0 40 I WNW w NW 8 5 9 20 8 6 1 0 0 0 0 0 0 34 14 6 I 0 0 0 16 NNW I Total 80 2 4 100 36 0 0 4 0 0 0 0 220 6 I Calm Hours not Included above for: Variable Direction Hours for: Invalid Hours for: Total Total Period Period All All Hours Hours 240 0 Total Period All Hours 26 I Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 220 8759 I I I I

RTL A9.690E Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Attachment 1 (Part 1 of 3) I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Part 1: Joint Frequency Distribution Tables (35ft) Page 3 of 8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period I All Hours Period of Record Elevation:

                        =

Speed: SP35P 01 /01/2017 0 I :00 - 12/31 /2017 23 :00 Direction: Dl35P Lapse: DT150-35 I Stability Class: C Delta Temperature Slightly Unstable I Wind Speed (mph) Wind Direction N 0.6-3.5 8 3.6-7.5 9 7.6-12.5 0 12.6-18.5 0 18.6-24.5 0

                                                                                                          >24.6 0

Total 17 I NNE 5 2 0 NE ENE 4 10 0 1 0 0 0 0 0 0 0 0 0 0 0 7 5 10 I E 6 4 0 0 0 0 10 ESE SE SSE 8 4 3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8 4 3 I s SSW SW 4 1 3 II 1 9 0 0 14 0 0 0 0 0 0 0 0 0 5 10 28 I WSW 6 22 10 0 0 0 38 WNW w NW 9 6 8 24 16 11 4 2 1 0 0 0 0 0 0 0 0 0 37 24 20 I NNW 7 7 Total 92 117 31 0 0 0 0 0 0 0 14 240 I Calm Hours not Included above for: Variable Direction Hours for: Invalid Hours for: Total Total Total Period Period Period All All All Hours Hours Hours 240 0 26 I Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 240 8759 I I I

I Beaver Valley Power Station - Units 1 & 2 RTL A9.690E Enclosure 2, Attachment 1 (Part 1 of 3) Annual Radioactive Effluent Release Report I Calendar Year - 20 I 7 Attachment 1 I Part 1: Joint Frequency Distribution Tables (35ft) Page 4 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period All Hours I Period of Record Elevation:

                           =

Speed: SP35P 01 /01/2017 0 I :00 - 12/31/20 I 7 23 :00 Direction: DI35P Lapse: DTI50-35 I Stability Class: D Delta Temperature Neutral Wind Speed (mph) I Wind Direction N 0.6-3.5 58 3.6-7.5 36 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total 0 0 0 0 94 I NNE NE ENE 60 66 82 14 4 14 0 0 0 0 0 0 0 0 0 0 0 0 74 70 96 E 55 3 0 0 0 0 58 I ESE SE SSE 34 47 2 l 0 0 0 0 0 0 0 0 36 48 38 8 0 0 0 0 46 s I SSW SW 45 48 84 45 64 199 119 l 16 0 0 8 0 0 0 0 0 0 91 128 410 WSW 75 185 84 9 0 0 353 I WNW w NW 73 85 90 237 144 94 64 13 6 4 0 0 0 0 0 0 0 0 378 242 190 NNW I Total 74 1014 61 11 I I 308 5 21 0 0 0 0 0 140 2454 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 240 0 In valid Hours for: Total Period All Hours 26 I Number of Valid.Hours for this Table: Total Hours for the Period: Total Period All Hours 2454 8759 I I I I

RTL A9 .690E Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Attachment 1 (Part 1 of 3) I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Part 1: Joint Frequency Distribution Tables (35ft) Page 5 of 8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction I Total Period All Hours Period of Record Elevation:

                        =

Speed: SP35P 01 /01 /2017 0 I :00 - 12/31 /2017 23 :00 Direction: DI35P Lapse: DT150-35 I Stability Class: E Delta Temperature Slightly Stable I Wind Speed (mph) Wind Direction N 0.6-3.5 68 3.6-7.5 10 7.6-12.5 0 12.6-18.5 0 18.6-24.5 0

                                                                                                           >24.6       Total I 0          78 NNE NE ENE 84 160 197 3

4 25 0 0 0 0 0 0 0 0 0 0 0 0 87 164 222 I E 170 2 0 0 0 0 172 ESE SE SSE 133 11 3 122 0 3 1 0 0 0 0 0 0 0 0 0 0 134 113 I 0 0 125 s 141 SSW SW 170 123 28 63 110 3 9 45 0 0 2 0 0 0 0 0 0 172 242 280 I WSW 82 92 37 5 0 0 216 WNW w NW 48 61 61 82 40 26 18 7 0 0 0 0 0 0 0 0 0 0 148 108 87 I NNW 102 19 0 0 0 0 121 Total 1835 508 119 7 0 0 2469 Calm Hours not Included above for: Total Period All Hours 240 Variable Direction Hours for: Total Period All Hours 0 Invalid Hours for: Total Period All Hours 26 Number of Valid Hours for this Table: Total Period All Hours 2469 Total Hours for the Period: 8759 I I

I Beaver Valley Power Station - Units 1 & 2 RTL A9.690E Enclosure 2, Attachment 1 (Part 1 of 3) Annual Radioactive Effluent Release Report I Calendar Year - 2017 Attachment 1 I Part 1: Joint Frequency Distribution Tables (35ft) Page 6 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period All Hours I Period of Record Elevation:

                          =

Speed: SP35P 01 /0 1/2017 01 :00- 12/31 /2017 23:00 Direction: DI35P Lapse: DTl50-35 I Stability Class: F Delta Temperature Moderately Stable Wind Speed (mph) I Wind Direction N 0.6-3.5 15 3.6-7.5 I 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total 0 0 0 0 16 I NNE NE ENE 18 41 57 0 I 1 0 0 0 0 0 0 0 0 0 0 0 0 19 42 57 E 112 0 0 0 0 0 112 I ESE SE SSE 187 221 148 0 0 0 0 0 0 0 0 0 0 0 0 187 221 0 0 0 148 s 125 I SSW SW 66 34 4 13 9 0 0 0 0 0 0 0 0 0 0 0 0 129 79 43 WSW 23 I 0 0 0 0 24 I w WNW NW 13 10 8 2 1 0 0 0 0 0 0 0 0 0 0 0 0 0 14 12 8 NNW 17 I Total 1095 33 0 0 0 0 0 0 0 0 0 17 1128 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 240 0 Invalid Hours for: Total Period All Hours 26 I Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 1128 8759 I I I I

RTL A9.690E Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Attachment 1 (Part 1 of 3) Annual Radioactive Effluent Release Report Calendar Year - 2017 I Part 1: Joint Frequency Distribution Tables (35ft) Page 7 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction I Total Period All Hours Period of Record Elevation:

                        =

Speed: SP35P 01 /0I /2017 0 I :00 - 12/3 I/2017 23 :00 Direction: Dl35P Lapse: DTl50-35 I Stability Class: G Delta Temperature Extremely Stable I Wind Speed (mph) Wind Direction 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total I N 7 0 0 0 0 0 7 NNE NE ENE 12 23 37 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 12 23 37 I E 55 0 0 0 0 0 55 ESE SE 99 201 0 0 0 0 0 0 0 0 0 0 99 201 I SSE 62 0 0 0 0 0 62 SSW SW s 45 41 20 7 0 1 0 0 0 0 0 0 0 0 0 0 0 0 52 42 20 I WSW 11 0 0 0 0 0 11 w WNW 2 2 0 0 0 0 0 0 0 0 0 0 2 2 I NW 12 0 0 0 0 0 12 NNW Total 634 5 0 8 0 0 0 0 0 0 0 0 5 642 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 240 0 I Invalid Hours for: Total Period All Hours 26 Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 642 8759 I I I I I

I Beaver Valley Power Station - Units 1 & 2 RTL A9.690E Enclosure 2, Attachment 1 (Part 1 of 3) Annual Radioactive Effluent Release Report I Calendar Year - 2017 Attachment 1 I Part 1: Joint Frequency Distribution Tables (35ft) Page 8 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period All Hours I Period of Record Elevation:

                           =

Speed: SP35P 01 /01 /2017 0 I :00 - 12/31 /2017 23 :00 Direction: Dl35P Lapse: DT150-35 I Stability Class: ALL Delta Temperature Wind Speed (mph) I Wind Direction N 0.6-3.5 208 3.6-7.5 102 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total 0 0 0 0 310 I NNE NE ENE 215 342 452 53 17 61 0 0 0 0 0 0 0 0 0 0 0 0 268 359 513 E 427 34 0 0 0 0 461 I ESE SE 493 621 IO 11 0 0 0 0 0 0 0 0 503 632 SSE 389 19 0 0 0 0 408 s I SSW SW 383 347 292 112 208 404 5 41 215 0 0 13 0 0 0 0 0 0 500 596 924 WSW 236 428 156 15 0 0 835 I w WNW NW 192 216 240 507 308 187 109 29 IO 4 0 0 0 0 0 0 0 812 553 0 437 NNW I Total 242 5295 135 2596 5 570 0 32 0 0 0 0 382 8493 I Ca lm Hours not Included above for: Variable Direction Hours fo r: Total Total Period Period All All Hours Hours 240 0 Invalid Hours for: Total Period All Hours 26 I Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 8493 8759 I

1

'I I

RTLA9.690E Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Attachment 1 (Part 2 of 3) I Annual Radioactive Effluent Release Report Calendar Year - 2017 11I Part 1: Joint Frequency Distribution Tables ( 150ft) Page 1 of 8 IJ Joint Frequency Distribution I: Hours at Each Wind Speed and Direction I Total Period All Hours Period of Record = 0 I/0I /2017 0 I :00 - 12/3 I /2017 23 :00 Elevation: Speed: SP150P Direction: DI150P Lapse: DTl50-35 Stability Class: A Delta Temperature Extremely Unstable I Wind Speed (mph) Wind Direction N 0.6-3.5 8 3.6-7.5 48 7.6-12.5 32 12.6-18.5 1 18.6-24.5 >24.6 Total I 0 0 89 NNE NE ENE 8 6 3 27 25 39 22 11 24 2 0 0 0 0 0 0 0 0 59 42 66 I E 2 39 27 1 0 0 69 ESE SE SSE 3 1 0 27 25 19 17 15 13 0 2 0 0 0 0 0 47 43 I 0 0 32 s SSW SW 3 3 6 34 21 21 37 28 30 4 2 11 0 0 0 0 0 0 78 54 68 I WSW 15 28 70 15 0 0 128 WNW w NW 12 19 12 77 55 28 112 80 24 25 35 5 I 5 0 0 0 227 194 I 0 69 NNW Total 16 117 39 552 20 562 0 103 0 6 0 0 75 1340 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 9 0 I Invalid Hours for: Total Period All Hours 28 Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 1340 8759 I I I I I

I Beaver Valley Power Station - Units 1 & 2 RTL A9 .690E Enclosure 2, Attachment 1 (Part 2 of 3) Annual Radioactive Effluent Release Report I Calendar Year - 2017 Attachment I I Part I : Joint Frequency Distribution Tables ( 150ft) Page 2 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period All Hours I Period of Record Elevation:

                            =

Speed: SP! SOP 01 /01 /2017 01 :00 - 12/31 /2017 23:00 Direction: 01150P Lapse: DTIS0-35 I Stability Class: B Delta Temperature Moderately Unstable Wind Speed (mph) I Wind Direction 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total N 0 6 3 0 0 0 9 I NNE NE ENE 2 3 0 9 5 5 I I 6 0 0 0 0 0 0 0 0 0 12 11 9 E I 5 I 0 0 0 7 I ESE SE SSE 0 0 0 0 6 1 I 2 2 0 0 0 0 0 0 2 2 0 0 0 8 11 SSW SW s 0 0 0 4 I 5 7 0 8 0 0 0 0 6 19 0 10 8 0 0 18 WSW 2 IO 10 9 I 33 !1 WNW w NW 3 4 4 11 5 14 9 8 7 I 0 0 37 26 3 4 I 0 0 12 I NNW Total 21 2 76 5 78 2 41 0 0 3 0 220 9 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 9 0 Invalid Hours for: Total Period All Hours 28 I Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 220 8759 I

Beaver Valley Power Station - Units 1 & 2 RTLA9.690E Enclosure 2, Attachment 1 (Part 2 of 3) I Annual Radioactive Effluent Release Report Calendar Year - 2017 Attachment I I Part 1: Joint Frequency Distribution Tables ( 150ft) Page 3 of 8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction I Total Period All Hours Period of Record Elevation:

                        =

Speed: SP150P 01 /01 /2017 01:00- 12/31 /2017 23:00 Direction: DI150P Lapse: DTl 50-35 I Stability Class: C De lta Temperature Slightly Unstable I Wind Speed (mph) Wind Direction N 0.6-3.5 3 3.6-7.5 6 7.6-12.5 2 12.6-18.5 0 18.6-24.5 0

                                                                                                         >24.6 0

Total 11 I NNE NE ENE 4 2 2 7 5 I I 5 0 0 0 0 0 0 0 0 0 12 4 12 I E 1 4 5 0 0 0 10 ESE SE SSE 2 0 2 2 5 I 2 2 0 0 0 0 0 0 0 0 6 7 I 0 0 3 s SSW SW 1 0 I 6 2 1 4 5 8 0 1 6 0 0 0 0 0 0 11 7 17 I WSW 4 8 10 11 0 0 33 w WNW NW 6 2 1 9 11 7 21 12 8 10 10 2 0 1 0 0 0 46 36 18 I 0 NNW 0 3 4 0 Total 31 78 90 40 0 0 0 7 240 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 9 0 I Invalid Hours for: Total Period All Hours 28 Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 240 8759 I

I Beaver Valley Power Station - Units 1 & 2 RTL A9 .690E Enclosure 2, Attachment 1 (Part 2 of 3) Annual Radioactive Effluent Release Report I Calendar Year - 2017 Attachment I I Part l: Joint Frequency Distribution Tables (150ft) Page 4 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period All Hours I Period of Record Elevation:

                            =

Speed: SP150P 01 /01 /2017 0 I :00 - 12/31 /2017 23 :00 Direction: DI150P Lapse: DT150-35 I Stability Class: D Delta Temperature Neutral Wind Speed (mph) I Wind Direction 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total II N NNE NE 15 21 29 32 47 27 32 16 7 1 I 0 0 0 0 0 0 0 80 85 63 ENE 14 62 20 2 0 0 98 E 12 30 12 0 0 0 54 I ESE SE SSE 12 15 14 13 21 24 6 10 12 2 0 1 0 0 0 0 0 0 33 46 51 s I SSW SW 16 21 23 51 43 48 50 55 136 4 18 63 0 0 5 0 0 0 121 137 275 WSW 38 76 114 48 4 2 282 I WNW w NW 41 28 15 101 106 69 222 146 52 151 72 2 18 5 1 7 0 0 540 357 139 I NNW Total 15 329 31 781 33 923 4 369 33 0 0 9 83 2444 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 9 0 In valid Hours for: Total Period All Hours 28 I Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 2444 8759 I I I I

Beaver Valley Power Station - Units 1 & 2 RTL A9.690E Enclosure 2, Attachment 1 (Part 2 of 3) I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Part 1: Joint Frequency Distribution Tables ( 150ft) Page 5 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction I Total Period All Hours Period of Record Elevation:

                         =

Speed: SPl50P 0I /01 /2017 01 :00 - 12/3 1/20 17 23 :00 Direction: Dl150P Lapse: DT150-35 I Stability Class: E Delta Temperature Slightly Stable I Wind Speed (mph) Wind Direction 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total I N 45 25 17 0 0 0 87 NNE NE ENE 81 126 79 41 151 153 51 2 8 1 0 3 0 0 0 0 0 0 125 285 286 I E 41 50 11 1 0 0 103 ESE SE SSE 21 34 24 25 29 33 2 7 11 0 0 0 0 0 0 0 0 0 48 70 68 I SSW SW s 53 76 76 61 67 72 47 45 91 6 8 26 0 0 0 0 0 0 167 196 265 I WSW 47 59 62 16 I 0 185 WNW w 39 20 27 64 102 51 81 67 10 61 10 0 20 4 0 1 0 0 266 203 88 I NW NNW Total 19 808 35 1018 521 9 0 132 0 25 0 63 2505 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 9 0 I Invalid Hours for: Total Period All Hours 28 Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 2505 8759 I I I I I

I Beaver Valley Power Station - Units 1 & 2 RTL A9.690E Enclosure 2, Attachment 1 (Part 2 of 3) Annual Radioactive Effluent Release Report I Calendar Year - 2017 Attachment 1 I Part 1: Joint Frequency Distribution Tables ( 150ft) Page 6 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period All Hours I Period of Record Elevation:

                          =

Speed: SP150P 01 /0 I /2017 0 I :00 - 12/31 /2017 23 :00 Direction: DI150P Lapse: DT150-35 I Stability Class: F Delta Temperature Moderately Stable Wind Speed (mph) I Wind Direction N 0.6-3.5 50 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total 5 0 0 0 0 55 I NNE NE ENE 127 165 75 25 98 39 1 5 4 0 0 0 0 0 0 0 0 0 153 268 118 E 31 10 0 0 0 0 41 I ESE SE SSE 9 12 14 6 13 8 0 I 0 0 0 0 0 0 17 19 2 0 0 0 29 s I SSW SW 48 90 80 25 59 36 5 7 14 0 0 0 0 0 0 0 0 0 78 156 130 WSW 43 23 6 0 0 0 72 I w WNW NW 25 8 16 10 6 3 4 1 0 1 0 0 0 0 0 0 0 0 40 15 19 I NNW Total 27 820 12 378 0 50 0 0 0 0 0 39 1249 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 9 0 Invalid Hours for: Total Period All Hours 28 I Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 1249 8759 I I I I

Beaver Valley Power Station - Units 1 & 2 RTL A9.690E Enclosure 2, Attachment 1 (Part 2 of 3) I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Part I: Joint Frequency Distribution Tables (150ft) Page 7 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period All Hours I Period of Record Elevation:

                        =

Speed: SPl50P 01 /01 /2017 01 :00 - 12/31 /2017 23:00 Direction: DI150P Lapse: DTl 50-35 I Stability Class: G Delta Temperature Extremely Stable I Wind Speed (mph) Wind Direction N 0.6-3.5 41 3.6-7.5 4 7.6-12.5 0 12.6-18.5 0 18.6-24.5 0

                                                                                                         >24.6 0

Total 45 I NNE NE ENE 88 70 43 28 60 12 0 1 0 0 0 0 0 0 0 0 0 0 116 131 55 I E 10 6 0 0 0 0 16 ESE SE SSE 13 9 12 5 6 11 0 1 1 0 0 0 0 0 0 0 0 0 18 16 24 I s SSW SW 30 43 37 39 32 30 5 2 5 0 0 0 0 0 0 0 0 0 74 77 72 I WSW 15 9 2 0 0 0 26 WNW w NW 12 7 9 9 1 1 0 I 0 0 0 0 0 0 0 0 0 0 13 17 10 I NNW Total 12 451 2 255 0 18 0 0 0 0 0 0 14 724 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 9 0 I Invalid Hours for: Total Period All Hours 28 Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 724 8759 I I I I I

I Beaver Valley Power Station - Units 1 & 2 RTL A9 .690E Enclosure 2, Attachment 1 (Part 2 of 3) Annual Radioactive Effluent Release Report I Calendar Year - 2017 Attachment I I Part I : Joint Frequency Distribution Tables (150ft) Page 8 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period All Hours I Period of Record Elevation:

                           =

Speed: SPJ SOP 0I /01 /2017 0 I :00 - 12/31 /2017 23 :00 Direction: Dl150P Lapse: DTI 50-35 I Stability Class: ALL Delta Temperature Wind Speed (mph) I Wind Direction 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total N 162 126 86 2 0 0 376 I NNE NE ENE 331 401 216 184 367 315 43 34 110 4 0 5 0 0 0 0 0 0 562 802 646 E 98 144 56 2 0 0 300 I ESE SE 60 71 81 92 28 38 2 2 0 0 0 0 171 203 SSE 66 107 41 I 0 0 215 s I SSW SW 151 233 223 217 227 209 153 149 294 14 37 114 0 0 5 0 0 0 535 646 845 WSW 164 213 274 99 6 3 759 I WNW w NW 138 88 84 273 294 162 454 316 256 134 40 16 8 0 1169 848 98 10 1 0 355 I NNW Total 91 2577 127 3138 68 2242 686 4 68 0 0 11 290 8722 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 9 0 Invalid Hours for: Total Period All Hours 28 Number of Valid Hours for this Table: Total Period All Hours 8722 Total Hours for the Period: 8759

Beaver Valley Power Station - Units 1 & 2 RTL A9.690E Enclosure 2, Attachment 1 (Part 3 of 3) I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Part 1: Joint Frequency Distribution Tables (500ft) Page 1 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction I Total Period All Hours Period of Record Elevation:

                        =

Speed: SP500P 0I /01/2017 0 I :00 - 12/31 /2017 23 :00 Direction: DI500P Lapse: DTS00-35 I Stability Class: A Delta Temperature Extremely Unstable I Wind Speed (mph) Wind Direction 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total I N 0 0 2 3 0 0 5 NNE NE ENE 0 0 0 0 0 0 0 0 4 0 2 1 0 0 0 0 0 0 0 2 5 I E 0 3 5 0 0 0 8 ESE SE SSE 0 0 0 4 I 1 6 10 3 0 2 0 0 0 0 0 0 10 13 I 0 4 s SSW SW 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 I WSW 0 0 0 0 0 0 0 w WNW NW 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 1 0 I 0 0 0 0 NNW Total 0 0 0 10 30 0 0 8 0 0 0 0 48 0 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 6 0 I Invalid Hours for: Total Period All Hours 19 Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 48 8759 I I I I I

RTL A9.690E Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Attachment 1 (Part 3 of 3) Annual Radioactive Effluent Release Report I Calendar Year - 2017 Attachment I I Part I: Joint Frequency Distribution Tables (500ft) Page 2 of 8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period All Hours I Period of Record Elevation:

                          =

Speed: SP500P 01 /01 /2017 01 :00- 12/31 /2017 23 :00 Direction: DI500P Lapse: DTS00-35 I Stability Class: B Delta Temperature Moderately Unstable Wind Speed (mph) I Wind Direction N 0.6-3.5 1 3.6-7.5 2 7.6-12.5 4 12.6-18.5 18.6-24.5 >24.6 Total 0 0 0 7 I NNE NE ENE 0 0 0 3 0 2 6 2 1 I 0 0 0 0 0 0 0 0 10 2 3 E 1 4 6 0 0 0 11 I ESE SE SSE 1 0 10 8 6 1 2 2 0 0 0 0 19 11 0 3 1 I 0 0 5 s I SSW SW 0 0 0 2 0 5 5 2 2 1 0 0 0 0 0 0 0 0 11 4 2 WSW 0 I 0 I 0 0 2 I WNW w NW 0 0 0 0 0 0 0 2 0 0 5 0 0 2 0 0 0 0 0 9 0 I NNW Total 0 3 41 I 40 2 1 14 0 2 0 0 100 4 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 6 0 Invalid Hours for: Total Period All Hours 19 I Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 100 8759 I

Beaver Valley Power Station - Units 1 & 2 RTLA9 .690E Enclosure 2, Attachment 1 (Part 3 of 3) I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Part 1: Joint Frequency Distribution Tables (500ft) Page 3 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction I Total Period All Hours Period of Record = Elevation: Speed: SP500P 01 /01 /2017 01 :00 - 12/31 /2017 23 :00 Direction: DI500P Lapse: DT500-35 I Stability Class: C Delta Temperature Slightly Unstable I Wind Speed (mph) Wind Direction 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total I N 0 7 10 5 0 0 22 NNE NE ENE 1 0 0 4 9 2 6 3 4 1 1 2 0 0 0 0 0 0 12 13 8 I E 0 5 13 1 1 0 20 ESE SE 0 1 8 6 6 2 1 3 0 0 0 0 15 12 I SSE 0 2 7 1 0 0 10 s SSW SW 0 0 0 5 3 1 13 13 5 1 1 1 0 0 0 0 0 0 19 17 7 I WSW 1 0 8 3 0 0 12 WNW w 1 0 3 5 14 15 6 19 0 10 0 3 24 52 I NW 1 1 15 I 2 1 21 NNW Total I 6 4 65 138 4 49 2 0 13 0 4 11 275 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 6 0 I Invalid Hours for: Total Period All Hours 19 Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 275 8759 I

RTL A9.690E

1 Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Attachment 1 (Part 3 of 3)

Annual Radioactive Effluent Release Report I Calendar Year - 2017 Attachment 1 II Part 1: Joint Frequency Distribution Tables (500ft) Page 4 of8 I Joint Frequency Distribution Hours at Each Wind Speed and Direction Total Period All Hours Period of Record = 01 /01 /201701 :00 - 12/31 /2017 23 :00 Elevation: Speed: SP500P Direction: DI500P Lapse: DT500-35 I Stability Class: D De lta Temperature Neutral Wind Speed (mph) I Wind Direction 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total N 19 48 94 23 3 0 187 I NNE NE ENE 24 5 13 16 33 36 45 18 57 22 1 19 1 0 1 0 0 0 89 65 137 E 23 70 83 21 3 0 200 I ESE SE 23 13 6 64 35 24 78 36 12 19 2 3 0 0 179 106 SSE 51 12 2 0 95 s I SSW SW 12 17 16 23 26 21 65 76 111 46 124 233 30 95 4 0 1 5 150 274 481 WSW 18 60 120 194 51 9 452 I WNW w NW 39 18 16 73 76 45 170 227 176 315 298 86 158 110 21 47 33 4 802 762 348 I NNW Total 16 278 54 704 126 1533 34 1459 488 4 0 99 234 4561 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 6 0 In valid Hours for: Total Period All Hours 19 I Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 4561 8759 I I I I

Beaver Valley Power Station - Units 1 & 2 RTL A9.690E Enclosure 2, Attachment 1 (Part 3 of 3) I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Part 1: Joint Frequency Distribution Tables (500ft) Page 5 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction I Total Period All Hours Period of Record Elevation:

                        =

Speed: SP500P 01 /01 /2017 01 :00 - 12/31 /2017 23:00 Direction: D1500P Lapse: DT500-35 I Stability Class: E Delta Temperature Slightly Stable I Wind Speed (mph) Wind Direction N 0.6-3.5 28 3.6-7.5 14 7.6-12.5 25 12.6-18.5 13 18.6-24.5 0

                                                                                                       >24.6 0

Total 80 I NNE NE ENE 22 37 44 24 45 59 21 10 38 8 4 10 0 0 0 0 0 0 75 96 151 I E 52 80 50 11 0 0 193 ESE SE SSE 38 33 20 97 64 36 66 46 30 12 15 21 0 4 4 0 0 0 213 162 111 I s SSW SW 21 25 39 40 28 35 45 54 70 47 65 114 4 36 59 0 6 3 157 214 320 I WSW 47 75 45 33 6 3 209 w WNW 53 32 101 75 82 58 36 12 4 2 I 1 277 180 I NW 27 29 17 14 3 0 90 NNW Total 22 540 18 820 32 689 420 5 0 122 0 14 77 2605 I Calm Hours not Included above for: Total Period All Hours 6 Variable Direction Hours for: Total Period All Hours 0 Invalid Hours for: Total Period All Hours 19 Number of Valid Hours for this Table: Total Period All Hours 2605 Total Hours for the Period: 8759 I I

RTL A9 .690E I Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Attachment 1 (Part 3 of 3) Annual Radioactive Effluent Release Report I Calendar Year - 2017 Attachment I I Part I: Joint Frequency Distribution Tables (500ft) Page 6 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period All Hours

                          =

I Period of Record Elevation : Speed: SP500P 01/01 /2017 01 :00 - 12/31 /2017 23 :00 Direction: Dl500P Lapse: DT500-35 I Stability Class: F De lta Temperature Moderately Stable Wind Speed (mph) I Wind Direction N 0.6-3.5 13 3.6-7.5 7 7.6-12.5 5 12.6-18.5 1 18.6-24.5 0

                                                                                                           >24.6 0

Total 26 NNE I NE ENE 13 19 33 12 17 29 11 8 1 0 0 2 0 0 0 0 0 0 33 37 75 E 31 47 7 0 0 0 85 I ESE SE SSE 29 31 18 58 27 33 27 10 10 2 2 8 0 0 0 0 0 1 116 70 70 s 10 28 I SSW SW 16 19 20 18 37 24 36 17 31 36 0 3 11 0 0 I 92 94 121 WSW 23 34 9 3 I 0 70 I WNW w NW 17 16 15 22 17 8 13 6 2 I 0 1 0 0 0 0 0 0 53 39 26 NNW 10 3 3 0 0 I Total 313 380 209 104 15 0 2 16 1023 I Calm Hours not Included above for: Variable Direction Hours for: Invalid Hours for: Total Total Total Period Period Period All All Hours Hours 6 0 All Hours 19 I Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 1023 8759 I I I I

Beaver Valley Power Station - Units 1 & 2 RTL A9.690E Enclosure 2, Attachment 1 (Part 3 of 3) I Annual Radioactive Effluent Release Report Calendar Year - 2017 I Part 1: Joint Frequency Distribution Tables (500ft) Page 7 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period All Hours I Period of Record Elevation:

                        =

Speed: SP500P 01 /01 /2017 01 :00 - 12/31 /2017 23 :00 Direction: Dl500P Lapse: DTS00-35 I Stability Class: G Delta Temperature Extremely Stable I Wind Speed (mph) Wind Direction N 0.6-3.5 0 3.6-7.5 0 7.6-12.5 0 12.6-18.5 0 18.6-24.5 0

                                                                                                         >24.6 0

Total 0 I NNE NE ENE 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 I E 4 2 0 0 0 0 6 ESE SE SSE 3 2 4 4 6 7 0 0 1 0 0 0 0 0 0 0 0 0 12 9 6 I s SSW SW 6 1 0 4 5 3 16 4 8 9 5 16 1 0 3 0 0 0 37 14 30 I WSW 0 0 3 0 1 0 4 w WNW NW 1 2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 I 2 0 I NNW Total 23 0 32 0 32 0 0 30 0 5 0 0 122 0 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 6 0 I Invalid Hours for: Total Period All Hours 19 Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 122 8759 I I I I I

RTL A9.690E I Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Attachment 1 (Part 3 of 3) Annual Radioactive Effluent Release Report I Calendar Year - 2017 Attachment l I Part I: Joint Frequency Distribution Tables (500ft) Page 8 of8 I Joint Frequency Distribution I Hours at Each Wind Speed and Direction Total Period All Hours I Period of Record Elevation:

                          =

Speed: SP500P 01 /01 /2017 01 :00 - 12/31 /2017 23 :00 Direction: Dl500P Lapse: DT500-35 I Stability Class: ALL Delta Temperature Wind Speed (mph) Wind Direction 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 >24.6 Total N 61 78 140 45 3 0 327 NNE 41 59 86 32 1 0 219 NE 69 104 34 8 0 0 215 ENE 101 129 115 34 I 0 380 E 111 211 164 33 4 0 523 I ESE SE SSE 94 80 48 247 145 106 189 105 103 29 43 43 2 7 6 0 0 1 561 380 307 s 49 I SSW SW 59 74 106 83 78 181 173 232 121 226 400 69 168 9 0 7 9 466 617 961 WSW 89 170 185 234 59 12 749 I w WNW NW 111 68 59 200 173 83 279 308 210 358 334 102 162 124 26 48 37 5 1158 1044 485 49 80 167 42 4 342 I NNW Total 1163 2052 2671 2084 645 0 119 8734 I Calm Hours not Included above for: Variable Direction Hours for: Total Total Period Period All All Hours Hours 6 0 Invalid Hours for: Total Period All Hours 19 I Number of Valid Hours for this Table: Total Hours for the Period: Total Period All Hours 8734 8759 I I I I

I I I I I I I I I ENCLOSURE 2, ATTACHMENT 2 I I I I I I I I I I

I Beaver Valley Power Station - Units 1 & 2 RTL # A9 .690E Enclosure 2, Attachment 2 I Annual Radioactive Effluent Release Report Calendar Year - 2017 Attachment 2 I Unit 1 and 2 Offsite Dose Calculation Manual Changes Attachment 2 I Enclosed is a complete copy of the ODCM that includes: I Change (42) of the ODCM (Effective: January, 2018) Attachment 2 Clarification I A complete copy of the ODCM has been provided to the following offices: I United States Nuclear Regulatory Commission Attention : Document Control Desk Washington , DC 20555-0001 I United States Nuclear Regulatory Commission Regional Administrator 2100 Renaissance Blvd ., Suite 100 I King of Prussia, PA 19406-2713 For a complete copy of the ODCM , contact Rad iological Effluents Administrator at 724-682-4255. I I I I I I I I I I

I I I I I I I I I ENCLOSURE2,ATTACHMENT3 I I I I I I I I I I

RTL# A9 .690E Beaver Valley Power Station - Units 1 & 2 Enclosure 2, Attachment 3 Annual Annual Radioactive Effluent Release Repor1 Calendar Year - 2017 Attachment 3 I Unit 1 and 2 Carbon-14 (C-14) Dose Estimates Carbon-14 Methodology I Gaseous doses from carbon-14 were calculated in accordance with EPRI and Regulatory Guide 1.109 methodology. Other considerations were made in the calculations ; daylight hours and growing season . Liquid effluent release doses are considered to be insignificant and are not included in this report . This report does I not address the amount of carbon-14 disposed of in shipments of solid waste and irradiated fuel. The term "other" discussed below refers to liver, total body, thyroid , kidney , lung and GI. Doses for these organs are assumed to be equal. I The receptor chosen was selected based upon the default ODCM receptor - NW 1432 meters (0.89 miles) . It is assumed that only vegetation and inhalation exposure pathways are available . The maximum bounding dose to a member of the public resulting from atmospheric C-14 releases from Unit 1 was I determined to be less than 2.50 mrem to the bone and less than 1.07 mrem to all other organs. The maximum bounding dose to a member of the public resulting from atmospheric C-14 releases from Unit 2 was I determined to be less than 2.46 mrem to the bone and less than 1.04 mrem to all other organs. I Exposure Pathway Infant Dose Calculations for Unit 1 Child Teen Adult Bone Other Bone Other Bone Other Bone Other I Inhalation Vegetation lnqestion 0.06 0.01 0.08 2.42 0.02 0.48 0 .06 1.00 0.01 0.20 0.04 0.62 0.01 0.12 TOTAL 0.06 0.01 2.50 0.50 1.07 0.21 0.66 0.13 I Dose Calculations for Unit 2 I Exposure Pathway Bone Infant Other Bone Child Other Bone Teen Other Bone Adult Other Inhalation 0.05 0.01 0.07 0 .01 0.05 0.01 0.03 0.01 I Vegetation lnqestion TOTAL 0.05 0.01 2.40 2.46 0.48 0.49 0.99 1.04 0.20 0.21 0.60 0.64 0.12 0.13 I Dose Calculations for Site Infant Child Teen Adult I TOTAL Bone I Other 0.11 I 0.02 Bone I Other 4.97 I 0.99 Bone I Other 2.11 I 0.42 Bone 1.30 I Other I 0.26 I I I I

I Beaver Valley Power Station - Units 1 & 2 RTL A9.690E Enclosure 3 I I 2017 Annual Radiological Environmental Operating Report I I I I FirstEnergy Nuclear Operating Company I FENOC Beaver Valley Power Station - Units 1 & 2 I Unit 1 License No. DPR-66 Unit 2 License No. NPF-73 I I I I I I I I I I

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I EXECUTIVE

SUMMARY

and INDEX Report Preparation and Submittal Requirements: The Beaver Valley Power Station (BVPS) I Annual Radiological Environmental Operating Report (AREOR) was prepared and submitted in accordance with the requirements contained in the following documents: I

  • BVPS Integrated Technical Specifications, Administrative Control 5.6.1 I
  • Offsite Dose Calculation Manual (ODCM) procedure l/2-0DC-3.03 , Attachment T, Control 6.9.2, "Controls for RETS and REMP Programs" BVPS procedure 1/2-ENV-01.05, "Compliance with Regulatory Guide 1.21 and Technical I

Specifications " BVPS procedure 1/2-ENV-02.01 , "Radiological Environmental Monitoring Program " I

  • NUREG-1301 , "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors, Generic Letter 89-01 , Supplement N o.1 , April I

1991 " BVPS Condition Report No. CR-2017-04551: REMP Air Station #27 found OOS I BVPS Condition Report No. CR-2017-04706: REMP TLD #94 Missing BVPS Condition Report No. CR-2017-08225 : REMP Air Station #30 found OOS I

  • BVPS Condition Report No. CR-2017-09446: REMP Drinking Water Station #4 found OOS I
  • BVPS Condition Report No. CR-2017-10809: REMP Milk Station #96 August Analysis
  • BVPS Condition Report No. CR-2017-12347 : REMP Air Station #13 found OOS I
  • SAP Notification 601078879: 2017 RETS/REMP Tracking for ARERR/AREOR I

I I I I I I 11 I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure3 EXECUTIVE

SUMMARY

and INDEX I Report Overview: I The AREOR provides a detailed summary of the BVPS Radiological Environmental Monitoring Program (REMP). During the report period, samples of air, water, shoreline sediment, milk, I fish, food crops, feed crops, vegetation, and direct radiation (in the vicinity of the BVPS site) have been measured, analyzed, evaluated, and summarized. During the report period, the BVPS radioactive effluent releases (as performed in accordance with the Radiological Effluent Technical Specification (RETS) program), did not exceed the limits identified in the BVPS Operating License, Technical Specifications and/or the Offsite Dose Calculation Manual (ODCM). The results of REMP verify that the effluent releases did not impact the environment with a measurable concentration of radioactive materials and/or levels of radiation that are higher than expected. I Description of Pre-operational REMP (1974 - 1975): I A pre-operational REMP was performed during the period 1974 through 1975. At that time, samples were collected and analyzed to determine the amount of radioactivity present in the I environment prior to BVPS operation. The resulting values are considered a "baseline" to which current sample analyses can be compared. A summary of the pre-operational data is summarized I in Table 2-3 of this report. Description of Operational REMP (1976 - Present}: I The operational REMP was initiated during calendar year 1976 and continued through the report I period. During the past forty (40) years, radiation and radioactivity in the environment was monitored within a 10-mile radius of the site. A description of the operational REMP is outlined in Table 2-1 of this report. In general, two (2) types of samples were collected and compared I during the report period, and are described as follows:

  • Control Samples: These samples are collected from areas that are beyond measurable I influence of BVPS operation, and are used as reference data. Normal background radiation levels, or radiation present due to causes other than BVPS operation, can thus be compared to I the environment surrounding the BVPS site. During the report period, three hundred four (304) analyses were performed on samples from the control locations. This includes eight (8) analyses were completed for thermoluminescent dosimeters (TLDs) at the control I locations. Results of the analyses from the control locations are summarized in Table 2-2 of this report.

I

  • Indicator Samples: Indicator samples are collected to determine the radiological impact of BVPS operation in the environment. These samples are collected from various locations near I

I lll

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I EXECUTIVE

SUMMARY

and INDEX the BVPS site. At a minimum, the samples are collected from areas where the BVPS I contribution would indicate the most significant radiological impact. During the report period, one thousand five hundred forty-nine (1,549) analyses were performed on samples I collected from eighty-seven (87) indicator locations. In addition, five hundred twenty (520) analyses were completed for TLDs at the indicator locations. Results of the analyses from the indicator locations are also summarized in Table 2-2 ohhis report. I

  • Comparisons: Current analysis results from the indicator samples were compared to both I current control sample values and the pre-operational baseline to determine if changes in radioactivity levels were attributable to BVPS operation.

I Determination of Environmental Impact I

  • 2017 Sample Media and Analyses: Results for drinking water, surface water, shoreline stream sediment, fish, cow milk, goat milk, feedstuff, foodcrops, air particulate and air radioiodine media remained consistent with previous data. Minor increases and decreases I

were noted in most sample media, and any positive results attributable to the BVPS operation were consistent with station data of authorized radioactive discharges, and were within limits I permitted by the operating license and the ODCM. Other radioactivity detected was attributable to naturally occurring radionuclides, previous nuclear weapons tests, other man-made sources, and to the normal statistical fluctuation for activities near the Lower Limit of I Detection (LLD).

  • Airborne Exposure Pathway: This ODCM required pathway was evaluated via sampling of I

airborne radioiodine and airborne particulates. The results during this report period were similar to previous years. There was no notable increase in natural products and no I detectable fission products or other radionuclides in the airborne particulate media during the year attributed to effluent releases from BVPS. I

  • Direct Exposure Pathway: This ODCM required pathway was evaluated via measurement of environmental radiation doses by use of Thermo Luminescent Dosimeters (TLDs). The I results of TLD processing have indicated a stable trend and compare well with previous years. I
  • Ingestion Exposure Pathway: This ODCM required pathway was evaluated via sampling of milk, fish, and foodcrops (leafy vegetables). I For milk samples, strontium-90 (attributable to past atmospheric weapons testing), was detected at levels similar to those of previous years. The gamma spectrometry analyses I

I lV I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

SUMMARY

and INDEX indicated positive results for naturally occurring potassium-40 at average environmental levels. The fish samples indicated below LLD levels in each of the sample analyses. Foodcrop (leafy vegetation) samples indicated naturally occurring potassium-40 at average environmental levels. I

  • Waterborne Exposure Pathway: This ODCM pathway was evaluated via samples of I drinking water, ground (well) water, surface (river) water and river sediment.

I Water samples were analyzed for tritium and gamma-emitting radionuclides. Tritium was not identified in any of these water samples. Iodine-131 analysis of drinking water indicated positive analyses, but the values were consistent with iodine-131 at the upstream surface I (river) water control location, and was not due to liquid effluent releases from BVPS. Sediment samples were collected from upstream of the site, at the discharge point of BVPS I liquid effluent releases, and downstream of the site. Analysis of samples indicated naturally occurring radionuclides potassium-40, thallium-208, bismuth-214, lead-212, lead-214, I radium-226, and actinium-228 in all results. The analyses also indicated cesium-137, but the values were consistent with cesium-137 at the control location, and most likely caused by previous nuclear weapons tests. Cobalt-58 and cobalt-60 were identified in some of the I samples that were obtained at the shorelines of the BVPS Main Outfall Facility. This is not unusual because the BVPS site discharges cobalt-58 and cobalt-60 in liquid waste effluents. I The activity detected at these sample locations is consistent with discharge data of authorized liquid effluent releases, and all liquid effluent releases during the report period did not exceed the release concentration limits set forth in the ODCM. I

  • Other Exposure Pathways: In addition to the samples collected from the exposure I pathways described above, other media (i.e., feedstuff) were also collected. Results were consistent with previous years, with no degrading trends.

I

  • Offsite Groundwater Monitoring (Historical): There were a total of four (4) offsite groundwater samples collected and analyzed for tritium and by gamma spectrometry. The samples were collected on a semi-annual basis from two (2) locations within four (4) miles of I the site. The locations included one ( 1) well in Hookstown, PA; and one (1) well in Georgetown, PA. No gamma-emitting radionuclides were detected in the analyses. All I tritium results were less than the pre-operational value.

I I V

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I EXECUTIVE

SUMMARY

and INDEX

  • Supplemental Sample Sites: REMP includes supplemental sampling sites in addition to the I

required sites set forth in the ODCM. The supplemental sites include three (3 ) air sampling sites, one (1) sediment site, one (1) milk animal feedstuff site, and five (5) soil sampling I sites.

  • Population Dose vs. Natural

Background:

During the report period, the total calculated 0-I 50 mile population dose was 61 man-mrem (liquid releases), and 39 man-mrem (gaseous releases). The average individual population dose from BVPS operation was less than <1 I mrem. Accordingly, the typical dose to an individual from background (natural radiation exposure including radon) was estimated as an average of 296 mrem per year according to the National Academy of Sciences 1990 BEIR Report. In 2009, the NCRP Report No. 160:

  "Ionizing Radiation Exposure of the Population of the United States," Journal of Radiological Protection J Radio/. Prat. 29.3 (2009) defined the radiation exposure population dose to be 620 mrem per year. The following graph in Figure i-1 illustrates that the average individual population dose was not affected from BVPS operation.

I:I I Figure i-1 Gra h of Annual Avera ulation Dose: BVPS Dose and Natural Back round Dose I 1000.00000 100.00000 I 10.00000 I 1.00000 eCl) D::

  §.

Cl) 0.10000 I Ill I 0 0 0.01000 0.00100 0.000 10

                       ~            -                     ---                                               .

I 0.00001

                                                                                                                                 ~                              I
                 ~ ~,,~ # ## ~ ~~~ #~ ~~ ~ ~~~ ~~
            ......., BVPS Average Populatlcn Dose (mRem )   rl atural Backg-ourd P~ulatlon Dose (296 mRem ) - Radiation Exposure Popula:1on Dose (620 mRem)

I I I Vl I

Beaver Valley Power Station RTL A9 .690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

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and INDEX I

  • Summary: During the report period, radioactive effluent releases from the BVPS site did I not exceed the limits identified in the BVPS Operating License, Technical Specifications and/or the ODCM. The BVPS operational REMP program was followed throughout the report period. The results demonstrate the adequacy of radioactive effluent control at BVPS, I and that BVPS operation did not adversely affect the surrounding environment. Positive results were attributable to BVPS operation and were consistent with station data of I authorized radioactive discharges within limits permitted by the NRC license and the ODCM. Other radioactivity detected was attributable to naturally occurring radionuclides, previous nuclear weapons tests, other man-made sources, and to the normal statistical I fluctuation for activities near the LLD.

Inter-laboratory Comparison Programs: I

  • Split Sample Program: BVPS shared split samples with the Pennsylvania Department of I Environmental Protection (P ADEP) in support of their nuclear power plant monitoring program. The shared media and number of locations were typically comprised of milk (2),

surface water (3), river sediment (1), fish (1), foodcrops (2), co-located air particulate/air I iodine (4), and TLD (24). The split sample program was coordinated by the state, and the results are not provided with this report. I

  • Spike Sample Program: Spiked samples were provided by an independent laboratory and then analyzed by the REMP contractor laboratory. The samples were provided throughout I the report period and included water samples, milk samples, filter paper samples and charcoal cartridge samples. All one hundred eight (108) analyses performed by the contactor I laboratory on the spiked samples met the NRC comparison criteria.

Special Reports: I

  • Since no reporting levels were exceeded during 2017, no Special Reports were required. A I Special Report shall be submitted to the NRC when (1) levels of radioactivity in an environmental sampling medium exceeds the limits specified in ODCM procedure l /2-0DC-3.03 , Attachment Q Table 3.12-2, and when (2) the results of the following calculation are I ~ 1.0 (for calculations performed when more than one radionuclide is detected in the sampling medium):

I Concentration (1) + Concentration (2) + ... ~ 1.0 Limit Level (1) Limit Level (2) I I I Vll

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I EXECUTIVE

SUMMARY

and INDEX Land Use Census Results: I Highlights from the most recent Land Use Census are documented in letter NPD3NRE: 1250, dated October 23 , 2017 and are summarized as follows: I

  • Nearest Residence (0 to 5 mile radius): The location has not changed since the previous I census. The nearest inhabited residence is 209 Ferry Hill Road, Shippingport, PA (0.4 miles, east).

I

  • Nearest Garden >500 sgft: The location has not changed since the previous census. The closest garden location is the Colaber Residence, 1201 Virginia Avenue, Midland, PA 11 (1.033 miles, northwest). The Cox Residence, 238 State Route 168, Hookstown, PA (0.760 miles, south-southwest) was available for sampling cabbage this year but does not meet all the requirements of NUREG-1301.

I

  • Nearest Dairy Cow (0 to 5 mile radius): The location has not changed since the previous census. The location remains at Brunton Dairy, 3681 Ridge Road, Aliquippa, I

PA (6.067 miles, southeast). 11

  • Nearest Doe Goat (0 to 5 mile radius): The location has not changed since the previous census. The closest location is the Covert Residence, 930 Pine Street (Route 168),

Hookstown, PA (2.131 miles, southwest). I

  • Prevailing Winds: The prevailing wind direction for ground releases was identified by I showing the highest deposition parameters (D/Q) in the east (E) sector. The prevailing wind direction for elevated releases was identified by showing the highest D/Q in the east-southeast (ESE) sector. The REMP properly monitors the environment with air I

particulate sampling stations in some sectors and direct radiation TLDs in all sectors. I

  • 2017 Dairy Cow & Doe Goat Sampling Locations: The dairy cow sampling locations have not changed in 2017. The locations remain at Brunton Dairy, 3681 Ridge Road, Aliquippa, PA (6.067 miles, southeast), and Windsheimer Dairy, 20 Windsheimer Lane, I

Burgettstown, PA (10.475 miles, south-southwest). The doe goat sampling location has not changed since the previous census and remains at the Covert Residence, 930 Pine I Street (Route 168), Hookstown, PA (2.131 miles, southwest).

  • D/0 for Milch Animal Locations: The 2017 milch animal sampling locations have not I

experienced a >20% increase in D/Q. Therefore, a Special Report per ODCM Control 3.12.2 Action "a" and/or Action "b" is not required. I I Vlll I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

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and INDEX I

  • D/0 for Offsite Dose Determination: There is no adverse effect on the current ODCM I methodology used for offsite dose determination from effluent releases. Specifically, the analysis of D/Q did not yield any valid locations where the offsite dose could have increased >20% of the offsite dose previously calculated using current ODCM I methodology. Therefore, a Special Report per ODCM Control 3.12.2 Action "a" and/or Action "b" is not required.

I

  • D/0 Historical Trend Comparison: There is no adverse trend in D/Q when comparing 2003 to 2017 data to the ODCM default D/Q values. This validates that there is no I adverse effect on the current ODCM methodology used for offsite dose determination from effluent releases. Specifically, the analysis of D/Q did not yield any valid locations where the offsite dose could have increased >20% of the offsite dose previously I calculated using current ODCM methodology. Therefore, a change in ODCM Receptor location and/or a change to meteorology at the current ODCM Receptor location is not I required.

The 2017 Land Use Census results indicate that no significant changes are required in the current I Radiological Environmental Monitoring Program or to its methodology. I Deviations, Changes and Adjustments to the Normal Sampling Program

  • Deviation from Normal Milk Sampling & Analysis Schedule: There were two deviations I from the required milk sampling and analysis schedule occurred for the reporting period.

Sufficient milk samples were not available from locations within the 5 mile radius in 2017. I The unavailability of milk caused the REMP to not meet the ODCM sample requirements in l/2-0DC-2.03 and in l/2-0DC-3.03 , Attachment Q Table 3.12-1 stating that a minimum of four (4) milk locations shall be sampled. This initiated the ODCM requirement for sampling I two (2) additional garden locations based upon the highest predicted annual average D/Q when milk locations are not available. The other issue was documented through internal notification because it regarded a supplemental sample. I

  • Deviation from Normal Surface and Drinking Water Sampling and Analysis Schedule:

I There was one deviation from the ODCM required water sampling and analysis schedule during the report. The one issue was documented in Condition Report 2017-09446. I I I I lX

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I EXECUTIVE

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and INDEX

  • Deviation from Normal Air Particulate & Iodine Sampling and Analysis Schedule:

I There were three deviations from the required airborne particulate sampling and analysis schedule during the report period. These issues were documented in Condition Report 2017- I 04551 and 2017-08225.

  • Deviation from Normal Direct Radiation Monitoring: There was one deviation from the I

required direct radiation monitoring schedule during the report period. This issue was documented in Condition Report 2017-04706 I

  • Deviations from Previous Sampling and Analysis Schedule: Beginning in 2017, the REMP was modified to exclude non-required samples and analyses. These changes are I

documented in the REMP procedure. Two (2) Air Particulate and Radioiodine sampling points; Sherman Farm in Brighton I Township (Site No. 28, 8.6 miles N) and Friendship Ridge in Beaver (Site No. 29B 7.97 miles NE). I Two (2) Groundwater sampling points; Hookstown Borough (Site No. 14A, 2.61 miles SW) and Georgetown Borough (Site No. 15B, 3.75 miles WNW). I One (1) Sediment sample point; Upstream of New Cumberland Darn (Site No. 50, 11.77 1, miles WSW). I Three (3) Precipitation sample points; Cook's Ferry Substation in Shippingport (Site No. 30, 0.5 miles ENE), East Liverpool Water Department (Site No. 47, 4.88 miles WNW), I and Weirton Water Tower (Site No. 48, 16.4 miles SSW). I Five (5) Soil sample points; Old Meyer Farm in Hookstown (Site No. 13A, 1.49 miles SW), South of BVPS perimeter (Site No. 22, 0.28 miles SSE), Brunton Farm (Site No. 27, 6.16 miles SE), Nicol Farm in Beaver (Site No. 29A, 8.09 miles NE) and East I Liverpool Water Department (Site No. 47, 4.88 miles WNW). The analysis schedule of I-131 for both drinking and surface was changed from weekly to I biweekly. I I I I X I

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

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and INDEX I EXECUTIVE

SUMMARY

II I Report Preparation and Submittal Requirements........ .... ... .................... ... ...... .. .................. Report Overview ....................... ....................................... .................................................. u 111 11 Description of Pre-operational REMP (1974 - 1975) ....... ... ....... ....................................... Description of Operational REMP (1976 - Present) ...................... ... ............ .. ... .. ........... .. m m Determination of Environmental Impact............ ... ................. .. ... ............ ................. .. .... .... 1v Inter-laboratory Comparison Programs ......... ..... .. ............. ... ...... .... ... ........ ...... ............... ... . vu I Special Reports. .......................... .. ... ........... ........ ............................ ......... .. ......................... Land Use Census Results... ..................................... ...... .. ........... ........ ....... .......................... vu vu Deviations, Changes and Adjustments to the Normal Sampling Program ........................ 1x I SECTION 1 - INTRODUCTION I A. B. Radiation Fundamentals.......... .................................................................................... Radiation and Radioactivity ..................... ............. ......................... ... ................. ... ..... 1-1 1-1 C. Units of Measurement ........... .............. ........ ... .. ........... .... .............. ..... .... ................ .... 1-5 I D. E. Lower Limit of Detection......................... ....... .. ..... ... ......... ....................................... . Scope and Objectives of the REMP Program.. ................................ ............ .......... ... .. 1-6 1-6 F. Description of the Beaver Valley Site ................. ....... ................................................ 1-6 11 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM A. Radiological Environmental Monitoring Program..................... ... ... ... ........... ...... .. ... 2-1 I 1. Program Description .. .............. ............... ............................... .................. ..........

2. Summary of Results.... .... ............. ... .. .......................................... .......................

2-1 2-5

3. Quality Control Program. ........ ... ........................................... ........... ................ .. 2-5 I B.
4. Program Changes.................................. ........... ... ....... ...................... ........... ... ....

Air Monitoring. ... ... ... ........ ... ............ .... ...... ... .................................. ... .. .................. .... 2-5 2-23

1. Characterization of Air and Meteorology .. .. ..... ................................................. 2-23 I 2. Air Sampling Program and Analytical Techniques .................. ... ......................
3. Results and Conclusions. .. ...................................................... .. ....... ..................

2-23 2-24 C. Monitoring of Shoreline Stream Sediment and Soil... ........... .................................... 2-28 I 1. Characterization of Shoreline Stream Sediment and Soil. .. .... ... ...... ... ...............

2. Sampling Program and Analytical Techniques........................ ..........................

2-28 2-28

3. Results and Conclusions ............ ..................................... ................................... 2-29 I D. Monitoring ofFeedstuff and Foodcrops..... ..................... .... .. .. ..................................
1. Characterization of Farm Products....... ..............................................................

2-34 2-34

2. Sampling Program and Analytical Techniques........ ................... ....................... 2-35 I E.
3. Results and Conclusions.. ........ ... .......................................................................

Monitoring of Local Cow and Goat Milk.. ..... ......... .......................... .... .. ........... ....... 2-36 2-39 I 1. Description - Milch Animal Locations .............. ................................................

2. Sampling Program and Analytical Techniques ........... :........... ................... ........
3. Results and Conclusions .......... ....................... .................. .................................

2-39 2-39 2-41 I F. Environmental Radiation Monitoring..................... .. .................................................

1. Description of Regional Background Radiation and Sources.. ... ... .............. ......

2-45 2-45

2. Locations and Analytical Procedures.. ......... .................... ...... .. .............. .. ... .... ... 2-45 I 3. Results and Conclusions .................................................................................... 2-46 I XI

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I EXECUTIVE

SUMMARY

and INDEX G. Monitoring of Fish. .... ..................................... ................................................. .......... 2-50 I

1. Description ............ ... ....................................... ............................................... ....
2. Sampling Program and Analytical Techniques.................... ......... .. ............. .. ....
3. Results and Conclusions .. .............. ... ......................... .. ....... ............. .. ............... .

2-50 2-50 2-50 I H. Monitoring of Surface Water, Drinking Water, Groundwater and Precipitation..... .

1. Description of Water Sources ...................................................................... ......
2. Sampling and Analytical Techniques.. .. ................ .. .. .......... ............................. ..

2-53 2-53 2-53 I

3. Results and Conclusions......... .............................................................. ......... ....

I. Estimates of Radiation Dose to Man ........................................................... ........ ... ... 2-56 2-61 I

1. Pathways to Man - Calculational Models... ....................................... ............ .... 2-61
2. Results of Calculated Population Dose to Man - Liquid Effluent Releases......
3. Results of Calculated Population Dose to Man - Gaseous Effluent Releases ...

2-61 2-62 I

4. Conclusions.. .. ... .. .... ..................................................................................... ...... 2-62 SECTION 3 - LAND USE CENSUS I A.

B. C. Land Use Census Overview .................. ........ .. .. .......... .. .......... .... ......... .. .. ............. .... Nearest Residence.............. .............. ......... ....................... ........ ... .... .. .. ... ... ................. Nearest Garden >500 sqft ... .. ....... .. .......... ... ...................... .. ... ....... ....... ........... .......... 3-1 3-1 3-1 I D. E. F. Nearest Dairy Cow. .. .. ....... ..................................................... ........ ................. ........ .. Nearest Doe Goat............................................................................................... ........ Projection for 2017 Dairy Cow Sampling Locations..... ......................... .. .............. .. 3-1 3-1 3-2 I G. H. Projection for 2017 Doe Goat Sampling Locations........ ......................................... .. D/Q for Milch Animal Locations ... .. .................. ..... ....... ......... ...... ......... ................... I. D/Q for Offsite Dose Determination. .......... ......................... .. .... ............... .. .............. 3-2 3-2 3-2 I J. D/Q Historical Comparison........ ... ........................ .. .. .. .. ... ........ .......... ....................... SECTION 4 - SPLIT SAMPLE PROGRAM AND SPIKE SAMPLE INTER-3-2 I LABORATORY COMPARISON PROGRAM A. Split Sample Program (Inter-Laboratory Comparison, Part 1 of 2) .......................... 4-1 I

                       ~.~~~~~~.?~~~~~.~~~.~.~~~~~.~~:~~~~~~~~.~~~.~.~~.~~::::: : ::: ::::::::::::::: ::;                                       I 1
   ~:   ~i::i:s~:Js ~..

SECTION 5 - CORRECTIONS TO PREVIOUS RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT(S) I A. Corrections to Previous Radiological Environmental Operating Report( s) .. ............ 5-1 I I I I Xll I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

SUMMARY

and INDEX I AREOR TABLES I Table 2-1 Operational Radiological Environmental Monitoring Program ............................. .. 2-2 Table 2-2 Radiological Environmental Monitoring Program Summary ................................. . 2-6 I Table 2-3 Pre-Operational Environmental Radiological Monitoring Program Summary .... ... 2-20 Table 2-4 Local Cow and Goat Locations 2-40 I Table 2-5 Table 2-6 Calculated Population Dose to Man - Liquid Effluent Releases ........................ ..... Calculated Population Dose to Man - Gaseous Effluent Releases............. ............. 2-63 2-63 I Table 2-7 Natural and Medical Radiation Exposures.. ... ... .. ... .................................................. Table 3-1 Location ofNearest Residences, Gardens, Dairy Cows, Doe Goats......... ......... ..... 2-64 3-3 Table 4-1 Inter-Laboratory Comparison Program, Spiked Samples - pt Quarter.. .................. 4-4 I Table 4-2 Inter-Laboratory Comparison Program, Spiked Samples - 2nd Quarter. .... .... .......... 4-5 Table 4-3 Inter-Laboratory Comparison Program, Spiked Samples - 3rd Quarter. .... .............. 4-6 I Table 4-4 Inter-Laboratory Comparison Program, Spiked Samples - 4th Quarter ................... 4-7 I I I I I I I I I I I Xlll

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I EXECUTIVE

SUMMARY

and INDEX AREOR FIGURES I Figure i-1 Graph of Annual Average Population Dose: BVPS Dose and Natural Background Dose .......... .......................... .................................................................. v1 I Figure 1-1 Geographical Map and Principal Communities in 50-mile Radius of the Beaver Valley Power Station............................ .. .............................. ..................................... 1-8 I Figure 2-1 Environmental Monitoring Locations - Air Sampling Stations.......... .............. .. .... ... 2-26 Figure 2-2 Figure 2-3 Graph of Annual Average Concentration: Gross Beta in Air Particulates ........ .... .... 2-27 Environmental Monitoring Locations - Shoreline Sediments and Soil .. .......... ........ . 2-31 I Figure 2-4 Figure 2-5 Graph of Annual Average Concentration: Cesium-137, Cobalt-58 & 60 in Sediment ... .. .... ........... ...... ......... ..... .. ........................................................................ .. 2-32 Graph of Annual Average Concentration: Cesium-137 in Soil.. ............................ .. . 2-33 I Figure 2-6 Figure 2-7 Environmental Monitoring Locations - Feedstuff and Foodcrops .. ......... .. ............... 2-37 Graph of Annual Average Concentration: Cesium-13 7 in F eedstuff and I Foodcrops ..... ........................ ................. ..................................................... ........... ... . 2-38 Figure 2-8 Environmental Monitoring Locations - Milk...................... ................ .. ...... .............. 2-43 I Figure 2-9 Graph of Annual Average Concentration: Iodine-131 & Sr-90 in Milk ........ .. .. .... .. . 2-44 Figure 2-10 Figure 2-11 Environmental Monitoring Locations - TLDs .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. 2-4 7 Graph of Annual Average Exposure: Direct Radiation in Environment.................. . 2-49 I Figure 2-12 Environmental Monitoring Locations - Fish........... ....................... ........................ ... 2-51 Figure 2-13 Graph of Annual Average Concentration: Cesium-137 in Fish .... ...... .... .................. 2-52 I Figure 2-14 Environmental Monitoring Locations - Surface Water and Drinking Water ........ .. .. 2_58 Figure 2-15 Graph of Annual Average Concentration: Iodine-131 in Surface Water, and Drinking Water .... ...... .... ...... ................ ... ... ....... .... ....... .. ... ..... .. .... ... .......... ... .. ...... ...... 2-59 I Figure 2-16 Graph of Annual Average Concentration: Tritium in Surface Water .. .... .. ............... 2-59 Figure 2-17 Graph of Annual Average Concentration: Tritium in Drinking Water ........ .. .. .. ....... 2-60 I Figure 2-18 Graph of Annual Average Concentration: Tritium in Groundwater .. .. .............. ...... . 2-60 I I I I I I XIV I

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 1 - INTRODUCTION A. Radiation Fundamentals I Radiation is the conveyance of energy through space. For example, heat emanating from a stove is a form of radiation, as are light rays, microwaves, and radio waves. All matter I consists of atoms, which are comprised of positively charged particles (protons), negatively charged particles (electrons), and non-charged/neutral particles (neutrons). The relatively I large particles (protons and neutrons) are packed tightly together in a cluster at the center of the atom called the nucleus, while the smaller particles (electrons) orbit around the nucleus. In an electrically neutral atom, the negative charges of the electrons are balanced by the I positive charges of the protons. Due to their dissimilar charges, the protons and electrons have a strong attraction for each other. This holds the atom together. Other attractive forces I between the protons and neutrons keep the densely packed protons from repelling each other, and prevent the nucleus from breaking apart. I B. Radiation and Radioactivity The following provides an alphabetical glossary of terms associated with radiation, I radioactivity, and the radioactive decay process. The terms discussed include alpha particles, beta particles, gamma rays, genetic effects, half-life, ionization, isotopes, neutrons, radiation, I radioactive decay, radionuclides and somatic effects. Alpha Particles: Particulate and electromagnetic radiation each travel through matter I differently because of their different properties. Alpha particles contain 2 protons and 2 neutrons, are relatively large, and carry an electrical charge of +2. Alpha particles are I ejected from the nucleus of a radioactive atom at speeds ranging from 2,000 to 20,000 miles per second. However, due to its comparatively large size, an alpha particle usually does not travel very far before it loses most of its energy through collisions and interactions with other I atoms. As a result, a sheet of paper or a few centimeters of air can easily stop alpha particles. Beta Particles: Beta particles are very small, and comparatively fast particles, traveling at speeds near the speed of light (186,000 miles per second). Beta particles have an electrical charge of either + 1 or -1. Because they are so small and have a low charge, they do not I collide and interact as often as alpha particles, so they can travel farther. Beta particles can usually travel through several meters in air, but may be stopped by a thin piece of metal or I wood. I I I 1- 1

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 1 - INTRODUCTION Gamma Rays: Gamma rays are pure energy and travel at the speed of light. They have no measurable charge or mass and generally travel much farther than alpha or beta particles before being absorbed. After repeated interactions, the gamma ray loses its energy and vanishes. The range of a gamma ray in air varies, depending on the ray's energy and interactions. Very high-energy gamma radiation can travel a considerable distance, where as I low energy gamma radiation may travel only a few feet in air. Lead is used as shielding material for gamma radiation because of its density. Several inches of lead or concrete may be needed to effectively shield gamma rays. I Genetic Effects: The effects of ionizing radiation which are observed in the offspring of the I exposed individual that could occur as a result of ionizing radiation interacting with the genes in the human cells. I Half-life: The length of time an atom remains radioactive is defined in terms of half-life, which is the amount of time required for a radioactive substance to lose half of its activity I through the process of radioactive decay. Radionuclides that have infrequent emissions have a long half-life, where as, radionuclides that have more frequent emissions have a short half-life. I Ionization: Through interactions with atoms, alpha, beta, and gamma radiation lose their I energy. When these forms of radiation interact with any form of material, the energy they impart may cause atoms in that material to become ions, or charged particles. Normally, an atom has the same number of protons as electrons, thus, the number of positive and negative I charges cancel, in which the atom is electrically neutral. When one or more electrons are removed, an ion is formed. Ionization is one of the processes that may result in damage to I biological systems. Isotopes: A group of identical atoms containing the same number of protons make up an I element. In fact, the number of protons an atom contains determines its chemical identity. For instance, all atoms with one proton are hydrogen atoms, and all atoms with eight protons are oxygen atoms. However, the number of neutrons in the nucleus of an element may vary. I Atoms with the same number of protons but different numbers of neutrons are called isotopes. Different isotopes of the same element have the same chemical properties, and I many are stable or non-radioactive. An unstable or radioactive isotope of an element is called a radioisotope, a radioactive atom, or a radionuclide. Radionuclides usually contain an excess amount of energy in the nucleus. The excess energy is usually due to a surplus or I deficit in the number of neutrons in the nucleus. Radionuclides such as uranium-238, beryllium-7 and potassium-40 occur naturally. Others are man-made, such as iodine-131 , I cesium-137, and cobalt-60. I 1-2 I

I Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 1 - INTRODUCTION I Neutrons: Neutrons come from several sources, including the interactions of cosmic radiation with the earth's atmosphere and nuclear reactions within operating nuclear power reactors. However, neutrons are not of environmental concern since the neutron source at nuclear power stations is sealed within the containment building. Because neutrons have no charge, they are able to pass very close to the nuclei of the material through which they are I traveling. As a result, neutrons may be captured by one of these nuclei or they may be deflected. When deflected, the neutron loses some of its energy. After a series of these I deflections, the neutron has lost most of its energy. At this point, the neutron moves about as slow as the atoms of the material through which it is traveling, and is called a thermal neutron. In comparison, fast neutrons are much more energetic than thermal neutrons and have greater potential for causing damage to the material through which they travel. Fast neutrons can have from 200 thousand to 200 million times the energy of thermal neutrons. I Neutron shielding is designed to slow fast neutrons and absorb thermal neutrons. Neutron shielding materials commonly used to slow neutrons down are water or polyethylene. The shield is then completed with a material such as cadmium, to absorb the now thermal I neutrons. Concrete is also used to form an effective neutron shield because it contains water molecules and can be easily molded around odd shapes. I Radiation: This is the conveyance of energy through space. For instance, heat emanating from a stove is a form of radiation, as are light rays, microwaves, and radio waves. Ionizing I radiation is another type of radiation and has similar properties to those of the examples listed above. Ionizing radiation consists of both electromagnetic radiation and particulate I radiation. Electromagnetic radiation is energy with no measurable mass that travels with a wave-like motion through space. Included in this category are gamma rays and x-rays. Particulate radiation consists of tiny, fast moving particles which, if unhindered, travel in a I straight line through space. The three types of particulate radiation of concern to us are alpha particles, which are made up of 2 protons and 2 neutrons; beta particles, which are essentially free electrons; and neutrons. The properties of these types of radiation will be described more fully in the Range and Shielding section. I I 1-3

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 1 - INTRODUCTION I Radioactive Decay: Radioactive atoms, over time, will reach a stable, non-radioactive state through a process known as radioactive decay, which is the release of energy from an atom I through the emission of ionizing radiation. Radioactive atoms may decay directly to a stable state or may go through a series of decay stages, called a radioactive decay series, and produce several daughter products that eventually result in a stable atom. The loss of I energy through radioactive decay may transform the atom into a chemically different element. For example, when uranium-238 decays, it emits an alpha particle and, as a result, I the atom loses 2 protons and 2 neutrons. Since the number of protons in the nucleus of an atom determines its chemical identity, then when the uranium-238 atom loses the 2 protons and 2 neutrons, it is transformed into an atom of thorium-234. Thorium-234 is one of the 14 I successive daughter products of uranium-238. Radon is another daughter product, and the decay series ends with stable lead-206. The following example is part of a known I radioactive decay series, called the uranium series, which begins with uranium-238 and ends with lead-206. The information provided in the upper portion of each block is the isotope name, while the information provided in the lower portion of each block is the half-life. I 238U 234 LJ I 4.5E+9Yr 2 .SE+S Yr 234pa 1.2 min  ! I 234Th 24 d 230Th 8.0E+4 Yr I

                                      !                                    Beta Decay 22sRa 1600 Yr Alpha Decay I
                                      !                                                                I 222Rn 3.82 d I

218p 0 3.05 mi n .J( 214p0 1.6E-4 s .A 21op 0 138.4 d I

                                                          /                            /

214pb

                                          /

I.,.# 214Bi 19.7min 210pb

                                                                         /
                                                                           ~

210Bi 5.01 d  ! 206pb I 26 .8 min Radionuclides: See description for "isotopes". 23 Yr stable I I 1-4 I

I Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 1 - INTRODUCTION I Somatic Effects: The effects of ionizing radiation develop in the directly exposed individual, including an unborn child. Somatic effects can be divided further into acute and chronic effects. Acute effects develop shortly after exposure to large amount of radiation. Chronic I effects are a result of exposure to radiation over an extended period of time. I C. Units of Measurement Activity (Curie): This relates the number of atoms in a sample that disintegrate (decay) per I unit of time. Each time an atom disintegrates, radiation is emitted. The curie (Ci) is the unit used to describe the activity of a material and indicates the rate at which the atoms of a I radioactive substance are decaying. One curie indicates the disintegration of 37 billion atoms per second. A curie is a unit of activity, not a quantity of material. Thus, the amount of material required to produce one curie varies. A smaller unit of the curie is used when I discussing the low concentrations of radioactivity detected in environmental samples. For instance, the picocurie (pCi) represents one trillionth of a curie. I Absorbed Dose (rad): This is a term used to describe the radiation energy absorbed by any material exposed to ionizing radiation, and can be used for both particulate and I electromagnetic radiation. The rad is the unit used to measure the absorbed dose. It is defined as the energy of ionizing radiation deposited per gram of absorbing material ( 1 rad = I 100 erg/g). The rate of absorbed dose is usually given in rad/hr. The rad is not used to quantify biological damage caused by ionizing radiation. I Dose Equivalent (rem): Biological damage due to alpha, beta, gamma and neutron radiation may result from ionizing radiation. Some types of radiation, especially alpha particles, cause I dense local ionization and can result in up to 20 times the amount of biological damage for the same energy imparted as do gamma or x-rays. Therefore, a quality factor must be applied to account for the different ionizing capabilities of various types of ionizing I radiation. When the quality factor is multiplied by the absorbed dose (rad) the result is the dose equivalent. Dose equivalent is an estimate of the possible biological damage resulting I from exposure to a particular type of ionizing radiation and is measured in rem. An example of this conversion from absorbed dose (rad) to dose equivalent (rem) uses the quality factor for alpha radiation, which is equal to 20. Thus, 1 rad of alpha radiation is equal to 20 rem. I Since beta and gamma radiation each have a quality factor of 1, then 1 rad of either beta or gamma radiation is equal to 1 rem. Neutrons have a quality factor ranging from 2 to 10. In I terms of radiation, the rem is a relatively large unit. Therefore, a smaller unit known as the rnillirem, is often used and one millirem (mrem) is equal to 1/1000 of a rem. I I 1-5

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 1 - INTRODUCTION I D. Lower Limit of Detection I The Lower Limit of Detection (LLD) for environmental samples is a calculated value that represents an a-priori (before-the-fact) limit for the smallest concentration (i.e. ; pCi per unit mass or volume) of radioactive material in a sample that will be detected with 95% I probability, and with 5% probability of falsely concluding that a blank observation represents a real signal. A calculated LLD must consider analytical variables such as standard deviation I of the background counting rate, counting efficiency, sample size, fractional radiochemical yield, radioactive decay constant, and elapsed time between sample collection and time of counting. I E. Scope and Objectives of REMP I The environmental program consists of environmental monitoring for radioactivity in the vicinity of BVPS. Environmental sampling and analyses include air, water, milk, vegetation, I river sediments, fish, and ambient radiation levels in areas surrounding the site. The results of these media are assessed to determine impacts of the plant operation on the environment. I The AREOR for BVPS summarizes REMP conducted by the FirstEnergy Nuclear Operating Company during the report period. I F. Description of the Beaver Valley Site I BVPS is located on the south bank of the Ohio River in the Borough of Shippingport, Beaver County, Pennsylvania, on a 453 acre tract of land. The site is approximately one mile from Midland, Pennsylvania, five miles from East Liverpool, Ohio, and twenty-five miles from I Pittsburgh, Pennsylvania. Figure 1-1 shows the site location in relation to the principal population centers. Population density in the immediate vicinity of the site is relatively low. I The population within a five mile radius of the plant is approximately 15,000. The only area within the radius of concentrated population is the Borough of Midland, Pennsylvania, with a population of approximately 2,539 as determined from the 2016 U.S. Census. I The site lies in a valley along the Ohio River. It extends from the river ( elevation 665 feet I above sea level) to a ridge along the border south of the Beaver Valley Power Station at a maximum elevation of 1160 feet. Plant grade level is approximately 735 feet above sea level. I BVPS is on the Ohio River at river mile 34.8, a location on the New Cumberland Pool that is I 3 .1 river miles downstream from Montgomery Lock and Dam, and 19 .6 miles upstream from I 1-6 I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 1 - INTRODUCTION I New Cumberland Lock and Dam. The Pennsylvania-Ohio-West Virginia border is located 5.2 river miles downstream from the site. The river flow is regulated by a series of dams and reservoirs on the Beaver, Allegheny, Monongahela and Ohio Rivers and their tributaries. I During the report period, the Ohio River flow (as obtained from the Corps of Engineers - Water Resources Engineering) at the New Cumberland Dam ranged from 6,904 cubic feet I per second (minimum monthly average) to 204,852 cubic feet per second (maximum monthly average). The mean flow during the report period was approximately 49,837 cubic feet per second. Water temperature of the Ohio River typically varies from 33° Fahrenheit to I 80° Fahrenheit. The minimum temperatures occur in January and/or February and maximum temperatures in July and/or August. Water quality in the Ohio River at the site location is I affected primarily by the water quality of the Allegheny, Monongahela and Beaver rivers. The climate of the area may be classified as humid continental. The predominant wind I direction is typically from the southwest in summer and from the west in winter. The National Climatic Data Center indicates the following data for the Beaver Falls, PA area: I The total annual precipitation during the report period was 37.20 inches. The average mean temperature during the report period was 60.8° Fahrenheit. I The basic features of the Beaver Valley Power Station Units 1 and 2 are tabulated below: Beaver Valley Unit 1 Beaver Valley Unit 2 I Licensed Power Level 2900 - megawatts thermal 2900 - megawatts thermal Type of Power PWR PWR I No. of Reactor Coolant Loops No. of Steam Generators & Type 3 3 - Vertical 3 3 - Vertical I Steam Used by Main Turbine Saturated Saturated The BVPS units utilize two separate systems (primary and secondary) for transferring heat I from the source (the reactor) to the receiving component (turbine-generator). Because the two systems are isolated from each other, primary and secondary waters do not mix, and I radioactivity in the primary system water is normally isolated from the secondary system. Reactor coolant in the primary system is pumped through the reactor core and steam generators by means of reactor coolant pumps. Heat is transferred from the primary system I to the secondary system in the steam generators. The steam is then formed and delivered to the main unit turbine, which drives the electrical generator. The steam is condensed after I passing through the turbine, and returned to the steam generators to begin another steam/water cycle. I I 1-7

Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 1 - INTRODUCTION I Geographical Map and Principal Communities Figure 1-1 I in 50-mile Radius of the Beaver Valley Power Station I Ii

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Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM A. Radiological Environmental Monitoring Program I 1. Program Description I The program consists of monitoring water, air, soil, river bottoms (sediment), feedstuff, vegetation, foodcrops, cow's milk, ambient radiation levels in areas surrounding the site, and aquatic life as summarized in Table 2-1 . Further description of each portion of the I program (Sampling Methods, Sample Analysis, Discussion and Results) are included in Sections 2-B through 2-1 of this report. I 2-B - Air Monitoring I 2-C - Monitoring of Shoreline Stream Sediment and Soil I 2-D - Monitoring of Feedstuff and Foodcrops 2-E - Monitoring of Local Cow and Goat Milk 2-F - Environmental Radiation Monitoring 2-G - Monitoring of Fish 2-H - Monitoring of Surface Water, Drinking Water, Groundwater and Precipitation I 2 Estimates of Radiation Dose to Man I I I I 2-1

Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-1 I Sample 0 1perattona IRad.10 IO!!IC3 IE nv1ronmenta IMomtormg p rogram Sample Sample Sample I Section Site Sample Location Preparation / Analysis Type Frequency 1 Air Particulate & No. 13 27 Hookstown , PA (Old Meyer Farm) Aliquippa , PA (Brunton Farm) Continuous Sampling Analysis Frequency Weekly - Air Particulate Gross Beta <*> I Radionuclide 30 Shippingport, PA (Cook's Ferry Substation) with Sample lodine-131 32 46 .1 47 48 (a) Midland , PA (North Substation) Industry, PA (McKeel's Service - Rt. 68) East Liverpool , OH (Water Department) Collection at least weekly Weekly - Charcoal Quarterly Composite (c) Gamma Scan I Weirton , VW (Water Tower - Collier Way) 2 Direct Radiation 51 7-8 10 13 Aliouiooa , PA /Sheffield Substation) BVPS Site Perimeter Locations Shippingport, PA (Post Office) Hookstown, PA (Old Meyer Farm) Continuous (TLD) Quarterly<'> Gamma Dose I 14 Hookstown , PA 15 27 28 Georgetown , PA (Post Office) Aliquippa , PA (Brunton Farm) Sherman Farm I 298 Beaver, PA (Friendship Ridge) 30 32 33-44 Shippingport, PA (Cook's Ferry Substation) Midland, PA (North Substation) BVPS Site Perimeter Locations I 45 Raccoon Township , PA (Christian House Baptist I Chapel - Rt. 18) 45 .1 Raccoon Township , PA (Kennedy's Corner) 46 Industry, PA (Midway Drive) 46.1 Industry, PA (McKeel's Service - Rt. 68) 47 East Liverpool, OH (Water Department) 48 (a) 51 52-56 Weirton , VW (Water Tower - Collier Way) Aliquippa , PA (Sheffield Substation) BVPS Site Perimeter Locations I 59 236 Green Hill Road , Aliquippa , PA 60 70 71 72 444 Hill Road , Georgetown , PA 236 Engle Road, Industry, PA Brighton Township , PA (First Western Bank) Ohioview, PA (Lutheran Church - Rear) I 73 74 75 76 618 Squirrel Run Road , Industry, PA 37 Poplar Avenue, Monaca, PA (CCBC) 117 Holt Road , Aliquippa , PA Raccoon Township, PA (Elementary School) I 77 3614 Green Garden Road, Aliquippa , PA 78 79 80 Raccoon Township, PA (Municipal Building) 106 Rt. 151 , Aliquippa, PA Raccoon Township, PA (Park Office -Rt. 18) I Millcreek United Presbyterian , Church 81 82 83 84 Hookstown , PA 2697 Rt . 18, Raccoon Twp, PA 735 Mill Creek Road , Hookstown, PA Hancock County, VW (Senior Center) I I 85 2048 Rt. 30 , West Chester, VW 86 1090 Ohio Avenue , East Liverpool , OH 87 50103 Calcutta Smith Ferry Road, Calcutta , OH 88A Route 168, Midland Heights, PA 89 488 Smith Ferry Road , Ohioville , PA 90 91 92 6286 Tuscarawras Road , Midland, PA Pine Grove Road & Doyle Road , Industry, PA Georgetown , PA (Georgetown Road Substation) I 93 104 Linden , Midland, PA (Sunrise Hills) 94 95 111-112 Hookstown, PA (McCleary & Pole Cat Hollow Roads) 832 McCleary Road , Hookstown , PA) BVPS Site Perimeter Locations I' I 2-2 I

Beaver Valley Power Station RTL A9.690E 201 7 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-1 (Continued) 0 iperatlona IRad'10 I021ca IE nv1ronmenta IMomtorm p roe;ram Sample I Sample Sample Preparation I Section Site Sample Location Sample Frequency Analysis Type Analysis Frequency No. I Biweekly Sample lodine-131 Industry, PA (Upstream of Montgomery Weekly Grab 49A Surface l*I Dam) Sample 1*1 Monthly Composite of 3 Gamma Scan Water Weekly Sample 1°1 East Liverpool , OH (Water Daily Grab Sample 5 Quarterly Composite 1°1 Tritium (H-3) I 4 Groundwater Department) No sampling performed Collected Weekly 1*1 Biweekly Composite of 4 Midland , PA (Water Department) lodine-131 Daily sample 1*1 I 5 Drinking Water 5 East Liverpool , OH (Water Department) Intermittent 1*1 Sample Collected Weekly Month ly Composite 1*1 Gamma Scan Quarterly Composite 1*1 Tritium (H-3) I 6 Shoreline Sediment 2A 49Al*I BVPS Outfall Vicinity Industry, PA (Upstream of Montgomery Semi-Annual Semi-Annual Gamma Scan Dam) I 7 Milk 27 951*1 Aliquippa, PA (Brunton Farm) Burgettstown , PA (Windsheimer Farm) Biweekly 1~ When animals are on pasture; monthly at All other samples & analyses are Biweekly during grazing but Gamma Scan lodine-131 Strontiu m-89 Monthly during other other times Strontium-90 I 114 lkl 2A Hookstown, PA (Covert Residence) BVPS Outfall Vicinity times Composite of edible Gamma Scan 8 Fish Semi-Annual on edible 49Al*I Industry, PA (Upstream of Montgomery parts by species lgl I 10*l'llml Dam) Shippingport, PA parts 15*(lllml I Georgetown , PA 12 (!)(ml Racoon Township, PA Gamma Scan Annual at Harvest if Composite of each lodine-131 on 9 Food Crops available sample species green leafy 45*ll)(ml Industry, PA vegetables I 48*(*1(1X ml

                              * (l)(m)

Weirton , WV I 10 Feedstuff & Summer Foraae 27 Aliquippa, PA (Brunton Farm) Shippingport, PA (Cook's Ferry Monthly Monthly Gamma Scan 30A Substation) I 11 Soil 32A 468 Midland , PA (North Substation) Industry, PA (Willows Inn - Rt. 68) Every Five (5) 12 Core Samples 3" Deep (2" diameter at Years Gamma Scan each location approx . I 481*1 51A Weirton WV (Water Tower - Collier Way) Aliquippa, PA (Sheffield Substation) (2015 , 2020, 2025) 10' radius) I 12 Precipitation No sampling performed I I 2-3

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-1 (Continued) I Operational Radiological Environmental Monitoring Program I Notes for Table 2-1 I Control sample station: These Locations which are presumed to be outside the influence of (a) plant effluents. Particulate Samples are not counted within 24 hours after filter change. Perform gamma isotopic analysis on each sample when gross beta is greater than 10 times the yearly mean of (b) control samples. Long-term composite samples are obtained from short-term composite samples at the specified (c) locations. (d) Composite samples are collected at intervals not exceeding 2 hours. (e) Searight Dairy is no longer operational. (f) Milk samples are collected biweekly when animals are grazing . The milk samples are collected I monthly at other times. (g) The fish samples contain whatever species are available. IF adequate sample size is available, THEN the sample is separated according to species, and 11 compositing will provide one sample of each species. IF adequate sample size is not available, THEN separation by species is not practical. Therefore , edible parts of all fish in the sample are mixed to provide one sample. I (h) Composite samples are obtained by collecting an aliquot at intervals not exceeding 2 hours at location 2.1 . In December of 2016, location 2 .1 was closed. The water treatment plant operator at location 5 obtains the weekly grab sample from the daily composite grab samples. In I December of 2016 , location 5 was transitioned to a composite sample to replace location 2.1. For location 49A, the weekly grab sample is obtained by a field technician . I (i) Two (2) TLDs are collected quarterly from each monitoring location. (k) ODCM procedure 1/2-0DC-3.03, Attachment Q, Table 3.12-1 requires three (3) dairies to be selected on basis of highest potential thyroid dose using milch census data. See Section 2-E of I this report (Monitoring of Loca l Cow's Milk) for specific locations sampled. (I) Three (3) garden locations requ ired by 1/2-0DC-2.03, Attachment A Table 3 .0-1 ; Sites designated by 1/2-0DC-2.03 Attachment B Figure 3.0-5. Sampling locations may be altered by I the REMP Administrator at any time based on availability. When there are not enough milk sample locations available to meet the ODCM requirements, three (3) different types of broad leaf vegetation are to be sampled at each of two (2) indicator I locations based on the highest predicted annual average ground D/Q (as determined from the (m) previous year's Land Use Census results), in addition to those samples described in Note (I). Three (3) different types of broad leaf vegetation shall also be sampled at one (1) control I location when in this condition. I 11 2-4 I

I Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM ' 2. Summary of Results II All results of this monitoring program are summarized in Table 2-2. This table is II prepared in the format specified by the NRC via the Branch Technical Position in NUREG-1301 , and in accordance with Beaver Valley Power Station ODCM. Summaries of results of analysis of each media are discussed in Sections 2-B through 2-H and an I assessment of radiation doses are given in Section 2-I. Table 2-3 summarizes BVPS pre-operational ranges for the various sampling media during the years 1974 and 1975. Comparisons of pre-operational data with operational data indicate the ranges of values

I I

are generally in good agreement for both periods of time. II Activity detected was attributed to naturally occurring radionuclides, BVPS effluents, previous nuclear weapons tests and/or to the normal statistical fluctuation for activities near the LLD. I The conclusion from all program data is that the operation of BVPS has resulted in no I significant changes to the environment.

3. Quality Control Program I The Quality Control Program implemented by BVPS to assure reliable performance by I the contractor and the supporting QC data are presented and discussed in Section 4 of this report.

I 4. Program Changes I In January 2017, REMP sampling changes were made to remove non-ODCM samples, and they are as follows; two air particulate and radioiodine locations, two groundwater locations, one sediment location, three precipitation locations, and five soil locations. I Additionally, the frequency of drinking water analysis was changed to biweekly, surface water analysis #49A was changed to biweekly, and soil sample collection was changed to I quinquennial. I I I I 2-5

Beaver Valley Power Station 2016 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2-ENVIRONMENTAL MONITORING PROGRAM Table 2-2 I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Na me of Facility: Beaver Valley Power Station Unit I and Unit 2 I Docket No.: 50-334 / 50-412 Location of Facility: Beaver County, Penn sylvania Reporting Period: Calendar Year- 2017 Medi um: Air Particulate and Radioiodine Unit of Measurement: (picoCuries / cubi c meter) I Type and Lower Total Numbe, Limit of All Indicator Locations Locations with Highest Annual Mean Control Location Number of Non routine I of Analysis Performed Gross Beta 416 Detection Mean (fraction) <*> LLD<*>

              < 0.002 Range<*>

0.026 ( 364 I 0.009 - 0.065 364 ) Na me Distance and Direction No. 46 .1 Industry, PA 2.28 miles NE Mean (fracti on) <*> Range <*> 0.027 ( 52 / 52 0.0 12 - 0.056

                                                                                                                )

Name Distance and Direction No. 48 Weirton, WV Water Tower Mean (fraction) (bl Range<*> 0.025 ( 52 / 52 0.009 - 0.05 1

                                                                                                                                                             )

Reported Measurements (c) 0 I I Collier Way 16.4 mil es SSW 1-1 31 < 0.04 LLD ( 0 I 364 ) LLD ( 0 I 364 ) LLD ( 0 I 52 ) 0 4 16 Gamma 32 I Be-7 NA 0.080 ( 28 / 28 ) No. 46 .1 Ind ustry, PA 0.086 ( 4 14 ) No. 48 Weirton, WV 0.085 ( 4 14 ) 0 0.06 1 - 0.097 2.28 miles NE 0.075 - 0.097 Water Tower Collier Way 16.4 miles SSW 0.067 - 0. 100 I Co-60 NA LLD ( 0 I 28 ) LLD ( 0 / 28 ) LLD ( 0 I4 ) 0 Cs- 134 < 0.0005 LLD ( 0 I 28 ) LLD ( 0 / 28 ) LLD ( 0 14 ) 0 Cs- 137 < 0.0005 LLD ( 0 I 28 ) LLD ( 0 / 28 ) LLD ( 0 14 ) 0 Ba-La-140 NA LLD ( 0 I 28

  • No minal Lower Limit of Detection
                                                 )                                          LLD (      0 / 28   )                          LLD (     0 14    )         0 I

b Mean a nd range based upon detectable meas urements only. Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

            ' Nonroutine Reported Measurements (

Reference:

ODCM procedu r e l/2-0DC-3.03, Attachment Q, Control 3.12.1) I NA = No t Applicable (Naturally Occurrin g Radionuclides No t required by ODCM) I I I I I 2-6 I

I Beaver Valley Power Station 2016 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 (Continued) I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit 1 and Unit 2 Docket No.: 50-334 / 50-412 I Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar Year - 2017 Medium: Drink ing Water I Unit of Measurement: (picoCuri es / liter) Type and Lower Number of Total Number Limit of All Indicator Locations Locations with Highest Annual Mean Control Location I Nonroutine I of Analysis Performed 1- 13 1 76 Detection Mean (fraction) Cb> LLo <*>

                  < 0.5 Range (bl 0.3 (

LLD - 0.3 I / 50 ) Name Distance and Direction No. 5 East Liverpool Water 4.9 miles WN W Mean (fraction) Cb> Range (b) 0.3 ( I / 25 Name Distance and Direction

                                                                                                                      ) No. 49A Industry, PA Mean (fraction) (bl Range  (bl 0.7 (    3 / 26  )

Reported Measurements (c) 0 LL D - 0.3 Upstream o f 0.3

  • 1.3 I

Montgomery Dam 4.93 miles NE H-3 < 200 LLD ( 0 / 8 ) LLD ( 0 / 8 ) LLD ( 0 / 4 ) 0 12 I Gam ma 36 Mn-54 < 5 LLD ( 0 / 24 ) LLD ( 0 / 24 ) LLD ( 0 / 12 ) 0 I Fe-59 Co-58

                  < 10
                  < 5 LLD (

LLD ( 0 / 24 0 / 24

                                                     )
                                                     )

LLD ( LLD ( 0 / 24 0 / 24

                                                                                                                      )
                                                                                                                      )

LLD ( LLD ( 0 / 12 0 I 12

                                                                                                                                                                     )
                                                                                                                                                                     )

0 0 I Co-60 Zn-65

                  < 5
                  < 10 LLD (

LLD ( 0 I 24 0 / 24

                                                     )
                                                     )

LLD ( LL D ( 0 I 24 0 / 24

                                                                                                                      )
                                                                                                                      )

LLD ( LLD ( 0 / 12 0 I 12

                                                                                                                                                                     )
                                                                                                                                                                     )

0 0 'I Zr-Nb-95 Cs-1 34

                  <5
                  < 5 LLD (

LLD ( 0 I 24 0 I 24

                                                     )
                                                      )

LLD ( LLD ( 0 I 24 0 / 24

                                                                                                                      )
                                                                                                                      )

LLD ( LLD ( 0 I 12 0 I 12

                                                                                                                                                                     )
                                                                                                                                                                     )

0 0 Cs- 137 < 5 LLD ( 0 I 24 ) LLD ( 0 / 24 ) LLD ( 0 I 12 ) 0 I Ba-La- 140 < 10 LLD ( 0 I 24

  • Nominal Lower Limit of Detection
                                                      )                                          LLD (     0 I 24     )                            LLD (      0 I 12  )        0 I               b Mean and range based upon detectable measurements only.

Fraction of detectable measurements at s pecified locations is indicated in parentheses (fraction )

                ' Non r outine Reported Measuremenls (

Reference:

ODC M procedure l /2-0DC-3.03, Attachmenl Q, C ontrol 3. 12. 1) I A = No l Applicable (Naturally O ccurring Radionuclides ot required by ODCM) I I I I I 2-7

Beaver Valley Power Station 2016 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2- ENVIRONMENTAL MONITORING PROGRAM Table 2-2 (Continued) I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Na me of Facility: Beaver Valley Power Station Unit I and Unit 2 I Docket No.: 50-334 / 50-412 Location of Facility: Beaver Co unty, Pennsylvania Reporting Period: Ca lendar Year - 2017 I Medium: Surface Water Unit of Measurement: (picoCuries / liter) Type and Lower Total Numbe1 Limit of All Indicator Locations Locations with Highest Annual Mean Control Location Number of I Nonroutine .1 of Analysis Performed 1- 13 1 26 Detection Mean (fraction) (b) LLD > Range (b)

               < 0.5 Name Distance and Direction Mean (fraction) (b)

Range (b) Name Distance and Direction No. 49A Industry, PA Upstream of Mean (fraction) (b) Range<*> 0.7 ( 0.3 - 1.3 3 / 26 ) Reported Measurements (t) 0 I Montgomery Dam 4.93 miles NE H-3 < 200 LLD ( 0 I 4 ) LLD ( 0 I 4 ) LLD ( 0 I 4 ) 0 8 Gamma 36 Mn-54 < 5 LLD ( 0 I 24 ) LLD ( 0 / 24 ) LLD ( 0 I 12 ) 0 Fe-59 < 10 LLD ( 0 I 24 ) LLD ( 0 / 24 ) LLD ( 0 I 12 ) 0 Co-58 < 5 LLD ( 0 I 24 ) LLD ( 0 I 24 ) LLD ( 0 I 12 ) 0 Co-60 Zn-65

               < 5
               < 10 LLD (

LLD ( 0 I 24 0 I 24

                                                )
                                                )

LLD ( LLD ( 0 1 24 0 1 24

                                                                                                                 )
                                                                                                                 )

LLD ( LLD ( 0 I 12 0 I 12

                                                                                                                                                                )
                                                                                                                                                                )

0 0 I Zr- Nb-95 < 5 LLD ( 0 I 24 ) LLD ( 0 / 24 ) LLD ( 0 I 12 ) 0 Cs- 134 Cs-1 37

               < 5
               < 5 LLD (

LLD ( 0 I 24 0 I 24

                                                 )
                                                 )

LLD ( LLD ( 0 1 24 0 I 24

                                                                                                                 )
                                                                                                                 )

LLD ( LLD ( 0 I 12 0 I 12

                                                                                                                                                                )
                                                                                                                                                                )

0 0 I Ba-La-140 < 10 LLD ( 0 I 24

  • Nominal Lower Limit of Detection
                                                 )                                           LLD (     0 I 24    )                            LLD (     0 I 12  )        0 I

h Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (fraction) I

             ' Nonroutine Reported Measurements (

Reference:

ODCM procedure l/2-0DC-3.03, Attachment Q, Control 3.12.1) NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODC M) I I I I I 2-8 I

I Beaver Valley Power Station 2016 Annual Radiological Environmental Operating Report RTL A9. 690E Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 (Continued) I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facili ty : Beaver Valley Power Station Unit I and Unit 2 Docket No.: 50-334 / 50-412 I Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar Year - 2017 Medium: Ground Water Sample location s are no longer in use I Unit of Measurement: (picoCuries / liter) Type and Lower Total Number Limit of All Indicator Locations Locations with Highest Annual Mean Control Location Number of Nonroutine I Detection Mean (fraction) (bl Mean (fraction) (hJ Mean (fraction) (bl I of Analysis Name Name Reported Performed LLD <*l Range (hl Distance and Direction Range lh> Distance and Direction Range <*> Measurements (c) H-3 < 200 I Gamma Mn-54 < 5 I Fe-59 Co-58

                 < 10
                 < 5 I

Co-60 < 5 Zn-65 < 10 Zr-Nb-95 < 5 I Cs- 134 Cs- 137

                 < 5
                 < 5 I   Ba-La-1 40    < 10
  • Nominal Lower Limit of Detection I h Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

               ' Nonroutine Reported Measurements (

Reference:

ODC M procedure l/2-0DC-3.03, Attachment Q, Control 3.12.1) I NA = Not Applicable (Naturall y Occurring Radionuclides No t required by ODC M) I I I I I I 2-9

Beaver Valley Power Station 2016 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2- ENVIRONMENTAL MONITORING PROGRAM Table 2-2 (Continued) I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit I and Unit 2 I Docket No.: S0-334 / 50-412 Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar Year - 20 17 I Medium: Precipitation Water Sample locations are no longer in use Unit of Measurement: (picoCuries / liter)

                                                                                                                                                                               'I Type and Lower Total Numbe r Limit of All Indicator Locations    Locations with Highest Annual Mean                              Control Location Number of Nonroutine      I of Analysis Performed H-3 Detection Mean (fraction)<*>

LLo<*>

              < 200 Range <*>

Name Distance and Direction Mean (fraction)<*> Range <*> Name Distance and Direction Mean (fraction) (bl Range<*> Reported Measurements (c) II Gamma Mn-54 < 5 I Fe-59 Co-58

              < 10
              < 5 I
              < 5 11 Co-60 Zn-65      < 10 Zr-Nb-95     < 5 Cs-1 34     < 5 Cs-1 37     < 5 Ba-La-140    < 10
  • Nominal Lower Limit of Detection I

b Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in J>arentheses (fraction) I

            ' Nonrouti ne Reported Measurements (

Reference:

ODCM procedure l/2-0DC-3.03, Attachment Q, Control 3.12.1) NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM) I I I I I I 2-10 I

I Beaver Valley Power Station 2016 Annual Radiological Envi ronmental Operating Report RTL A9.690E Enclosure 3 I SECTIO N 2 - ENVIRONMENTA L MON ITORING PROGRAM Ta ble 2-2 (Continued) I RADIOLOGICA L ENVIRON MENTA L MONITORI NG PROGRAM SUM MA RY Na me of Facili ty: Beaver Valley Power Station Unit I a nd Unit 2 Docket No.: 50-334 / 50-412 I Location of Facility: Beaver C ounty, Penn sylvania Reporting Period: C alendar Year - 201 7 Medium: Milk I Unit of Measu rement: (picoCuries / liter) Type and Lowe r IN umber of I Total Number Limit of A ll Indicator Loca ti ons Loca tions with Hi ghes t A nnual Mea n Contro l Location Non routine I of Anal ysis De tec tion Mean ( fracti on) Cb> Nam e Mean (fracti on) Cb) Nam e M ea n (fraction) (b> Re ported Performed LLD 1' 1 Range Cb> Distance a nd Direction Ran ge Cbl Distance and Direction Ran ge (b) Measurements (r) 1- 13 1 < 0.5 LLD ( O I 42 ) LLD ( 0 I 42 ) No. 96 Burgettstown, PA 1.4 ( I / 21 ) 0 63 Windsheimer Farm LLD - 1.4 I 0.46 miles SSW I Sr-89 63 Sr-90

                 < 2.0
                 < 0.7 LLD (

0.6 ( 0 I 42 14 I 42

                                                          )
                                                          )    No. 11 4 Hookstown , PA LLD (

1.0 ( 0 I 37 9 I 21

                                                                                                                          )
                                                                                                                          )    No. 96 Burgett stown , PA LLD (      0 I 21 )

1.0 ( 16 / 2 1 ) 0 0 63 0.5 1.7 Covert Residence 0.6 - 1.7 Windsheimer Fann 0.5 - 1.2 I Gamma 63 2.13 miles SW 10.46 mi les SSW I K-40 < 150 1354 ( 32 I 42 ) No. 114 Hookstown, PA 1620 ( 11 / 21 ) No. 96 Burgettstown, PA 1382 ( 2 1 / 2 1 ) 0 1252 - 1899 Covert Residence 1339 - 1899 Windsheimer Fann 1228 - 1509

2. 13 miles SW I 0.46 miles SSW Mn-54 < 5 LLD ( 0 I 42 ) LLD ( 0 I 42 ) LLD ( 0 I 21 ) 0 I Fe-59 Co-58
                 < 10
                 < 5 LLD (

LLD ( 0 I 42 0 I 42

                                                          )
                                                           )

LLD ( LLD ( 0 I 42 0 I 42

                                                                                                                          )
                                                                                                                           )

LLD ( LLD ( 0 I 21 0 / 21

                                                                                                                                                                                )
                                                                                                                                                                                )

0 0 I Co-60 Zn-65

                 <5
                 < 10 LLD (

LLD ( 0 I 42 0 I 42

                                                           )
                                                           )

LLD ( LLD ( 0 / 42 0 I 42

                                                                                                                           )
                                                                                                                           )

LLD ( LLD ( 0 I 21 0 I 21

                                                                                                                                                                                )
                                                                                                                                                                                )

0 0 Zr-Nb-95 < 5 LLD ( 0 I 42 ) LLD ( 0 / 42 ) LLD ( 0 I 21 ) 0 I Cs- 134 <5 LLD ( 0 I 42 ) LLD ( 0 I 42 ) LLD ( oI 21 0 I 21

                                                                                                                                                                                )          0 Cs-1 37     < 5              LLD (        0 I 42      )                                            LLD (      0 / 42  )                               LLD (                )           0 I   Ba-La-140     < 10             LLD (        0 I 42
  • Nom inal Lower Limit of Detection
                                                           )                                            LLD (      0 I 42  )                               LLD (       0 I 21   )           0 I               b  Mean and range based upon detec table meas urements only.

Fraction of detectable measurements at specified locations is indica ted in parentheses (fraction)

               'Nonroutin e Re ported Measurem ents (

Reference:

ODCM procedure l/2-0DC-3.03, Attach men t Q, Co n t rol 3.1 2. 1) I NA = No t A pplica ble (Na tu ra lly Occ urrin g Radionuclides Not required by O DCM) I I I I 2-11

Beaver Valley Power Station 2016 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2- ENVIRONMENTAL MONITORCNG PROGRAM Table 2-2 (Continued) I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit I and Unit 2 I Docket No.: 50-334 / 50-412 Location of Facility : Beaver County, Pennsylvania Reporting Period: Calendar Year - 201 7 I Medium : Fish I I Unit of Measurement: {picoCuries / gram) Wet Type and Lower Number of Total Numbei Limit of All Indicator Loca tions l"L_o_c_a_tio_n_s_w_i_th_H ig._h_es_t_A_n_n_u_ a_lM_e_a".,....------,,.,...-+ c _o_nt_r_ol_L_o_c_a_ti_ on_ _ _ _"T"_ _ _ _ _ _~ Nonroutine of Analysis Detection Mean (fraction) (bl Performed LLD (*l Gamma 9 Range (bl Name Distance and Direction Mean (fraction) (bl Range (bl Name Distance and Direction No. 49A Industry, PA Upstream of Mean (fraction) (bl Range (b) Reported Measurements <c:J I Montgomery Dam Mn-54 Fe-59

                < 0.05
                < 0. 10 LLD (

LLD ( 0 I 5 0 I 5

                                                 )
                                                  )

LLD ( LLD ( oI5 0 I5 4.93 miles NE LLD( LLD( 0 / 4) 0 / 4) 0 I I Co-58 < 0.05 LLD ( 0 I 5 ) LLD ( 0 I5 LLD ( 0 /4 ) Co-60 < 0.05 LLD ( 0 I 5 ) LLD ( 0 I5 LLD ( 0 /4 ) Zn-65 < 0. 10 LLD ( 0 I 5 ) LLD ( 0 I5 LLD( 0 / 4) 0 Zr-Nb-95 Cs-1 34

                < 0.01
                < 0.05 LLD (

LLD ( 0 I 5 0 I 5

                                                  )
                                                  )

LLD ( LLD ( 0 I5 0 I5 LLD ( LLD( 0 /4 0 / 4)

                                                                                                                                                                                   )        0 I

Cs-1 37 Ba-La-1 40

                < 0.05
                < 0.0 1 LLD (

LLD ( 0 I 5 0 I 5

                                                  )
                                                  )

LLD ( LLD ( 0 I5 0 I5 LLD( LLD( 0 / 4) 0 / 4) 0 0 I 11 Nominal Lower Limit of Detection b Mean and range based upon detectable meas urements only. Fraction of detectable measurements at specified locations is indicated in parentheses (fraction) I NA

             'Nonroutine Reported Measurements (

Reference:

ODC M procedure l/2-0DC-3.03, Attachment Q, Control 3.12.1 )

                = Not Applicable (Naturally Occurring Radionuclides Not required by ODC M)

I I I I I I I 2-12 I

I Beaver Valley Power Station 2016 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2- ENVIRONMENTAL MONITORING PROGRAM Table 2-2 (Continued) I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Na me of Facility: Beaver Valley Power Station Unit l and Unit 2 Docket No.: 50-334 / 50-412 I Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar Year- 2017 Medium: Foodcrops I Unit of Measurement: (picoCuries / gram) Wet Type and Lower Total Numbei Limit of All Indicator Locations Locations with Highest Annual Mean Control Location Number of INonroutine I of Analysis Detection Mean (fraction) (bl Name Mean (fraction) c*> Name Mean (fraction) (b) Reported I Performed 1- 13 1 II LLD (*>

                 < 0.06 Range (h)

LLD ( 0 I 10 ) Distance and Direction Range Ch) LLD ( 0 / 10 ) Distance and Direction Range (b) LLD ( 0 I I ) Measurements 0 le) I Gamma II K-40 NA 2.85 ( 10 / I O ) No. 12 Racoon Township, PA 5.00 ( 10 / 10 ) No. 488 Weirton, WV 3.30 ( I / I ) 0

1. 80 - 9.40 2.74 miles E 2.60 - 9.40 16.52 miles SSW LLD - 3.30 I Mn-54 Fe-59 NA NA LLD (

LLD ( 0 I 10 0 I 10

                                                   )
                                                   )

LLD ( LLD ( 0 I 10 0 / 10

                                                                                                                   )
                                                                                                                   )

LLD ( LLD ( 0 / I 0 I I

                                                                                                                                                                 )
                                                                                                                                                                 )

0 0 I Co-58 Co-60 NA NA LLD ( LLD ( 0 I 10 0 I 10

                                                   )
                                                   )

LLD ( LLD ( 0 / 10 0 / 10

                                                                                                                   )
                                                                                                                   )

LLD ( LLD ( 0 I I 0 I I

                                                                                                                                                                 )
                                                                                                                                                                 )

0 0 NA I Zn-65 LLD ( 0 I 10 ) LLD ( 0 / 10 ) LLD ( 0 / I ) 0 Zr-Nb-95 NA LLD ( 0 I 10 ) LLD ( 0 I 10 ) LLD ( 0 / I ) 0 Cs-1 34 0.04 LLD ( 0 I 10 ) LLD ( 0 1 10 ) LLD ( oI l ) 0 I Cs- 137 Ba-La-1 40 0.06 NA LLD ( LLD ( 0 I 10 0 I 10

                                                   )
                                                   )

LLD ( LLD ( 0 / 10 0 I 10

                                                                                                                   )
                                                                                                                    )

LLD ( LLD ( 0 / I 0 / I )

                                                                                                                                                                  )         0 0

I

  • Nominal Lower Limit of Detection b Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction) I 'Nonroutine Reported Measurements (

Reference:

ODCM procedure l/2-0DC-3.03, Attachmen t Q, Control 3. 12.1) NA = No t Applicable (Naturally Occurring Radionuclides No t required by ODCM) I I I I I I 2-13

Beaver Valley Power Station RTL A9.690E II 2016 Annual Radio logical Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 (Continued) I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Na me of Facility: Beaver Va lley Powe r Station Unit I and Unit 2 I Docket No.: 50-334 / 50-412 Location of Faci lity: Beaver County, Pennsylvania Reporting Period: Calendar Year - 2017 I Medium: Feedstuff Unit of Measurement: (picoCuries / gram) Wet Type and Lower Total Numbe, Limit of All Indicator Locations Locations with Highest Annual Mean Control Location Number of Nonroutine .1 I I of Analysis Detection Mean (fraction) <*> Name Mean (fraction)<*> Name Mean (fraction) <bl Reported Performed LLD <*> Range <*> Distance and Direction Range <*> Distance and Direction Range <*> Measurements (c) Gamma 12 Be-7 < 0.2 0.34 ( 0.25 - 0.42 4 I 12 ) No. 27 Brunton Farm 368 1 Ridge Road Aliq uippa, PA 6.08 miles SE 0.34 ( 4 I 12 0.25 - 0.42

                                                                                                                  )   No. 27 Brunton Farm 368 1 Ridge Road Aliquippa, PA 6.08 miles SE 0.34 (    4 I 12 0.25 - 0.42
                                                                                                                                                                    )        0 I

K-40 < 0. 15 8.87 ( 12 / 12 6.78 - 11.48

                                                  )     No. 27 Brunton Fann 368 1 Ridge Road Aliquippa, PA 6.08 miles SE 8.87 ( 12 / 12 6 .78 - 11.48
                                                                                                                  )   No. 27 Brunton Fann 3681 Ridge Road Aliquippa, PA 6 .08 mi les SE 8.87 ( 12 / 12 6.78 - 11.48
                                                                                                                                                                    )        0 I

Mn-54 Fe-59

                < O.Q2
                < 0.04 LLD (

LLD ( 0 I 12 0 I 12

                                                  )
                                                  )

LLD ( LLD ( 0 I 12 0 I 12

                                                                                                                  )
                                                                                                                  )

LLD ( LLD ( 0 I 12 0 I 12

                                                                                                                                                                    )
                                                                                                                                                                    )

0 0 I Co-58 Co-60

                < O.Q2
                < 0.02 LLD (

LLD ( 0 I 12 0 I 12

                                                  )
                                                  )

LLD ( LLD ( 0 I 12 0 I 12

                                                                                                                  )
                                                                                                                  )

LLD ( LLD ( 0 I 12 0 I 12

                                                                                                                                                                    )
                                                                                                                                                                    )

0 0 I Zn-65 < 0.04 LLD ( 0 I 12 ) LLD ( 0 I 12 ) LLD ( 0 I 12 ) 0 Zr-Nb-95 Ru- 103

                < 0.03
                < 0.03 LLD (

LLD ( 0 I 12 0 I 12

                                                  )
                                                  )

LLD ( LLD ( 0 I 12 0 I 12

                                                                                                                  )
                                                                                                                  )

LLD ( LLD ( 0 I 12 0 I 12

                                                                                                                                                                    )
                                                                                                                                                                    )

0 0 I 1- 13 1 Cs- 134

                < 0.06
                < 0.04 LLD (

LLD ( 0 I 12 0 I 12

                                                  )
                                                  )

LLD ( LLD ( 0 I 12 0 I 12

                                                                                                                  )
                                                                                                                  )

LLD ( LLD ( 0 I 12 0 I 12

                                                                                                                                                                    )
                                                                                                                                                                    )

0 0 I I Cs- 137 < 0.06 LLD ( 0 I 12 ) LLD ( 0 I 12 ) LLD ( 0 I 12 ) 0 Ba-La- 140 < 0.0 1 LLD ( 0 I 12 ) LLD ( 0 I 12 ) LLD ( 0 I 12 ) 0

  • Nommal Lower Limit of Detechon b Mean and range based upon detecta ble meas urements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction) I NA

              'Nonro u tine Reported Measurements (

Reference:

ODCM procedure l /2-0DC-3.03, Attachment Q, Control 3. 12.1)

                = No t Applicable (Naturally Occurring Radionuclides Not required    by ODC M)

I I I I 2-14 I

I Beaver Valley Power Station 2016 Annual Radiological Environmental Operating Report RTLA9.690E Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 (Continued) I RADIOLOGICAL ENVIRONMENTAL MONITORI NG PROGRAM

SUMMARY

Name of Facility: Beave r Valley Power Station Unit I and Unit 2 Docket No.: 50-334 / 50-412 I Location of Facility: Beaver County, Penn sylvania Reporting Period: Calendar Year - 201 7 Medium: Sediment (page I of2) I Unit of Measurement: (picoCuries / gram) Dry Type and Total Numbei Lower Li m it of All Indica tor Locati ons i.:Lo=c;;;att;;;

                                                                   *o;;;n;;.

s ,;,; w,;;it.::.h..:; H;;;ig!:;h;.;;e;;.; st;.;A,;;n;;;n;.;;u;;;;al;..;M

                                                                                                                                     ;.;e;;;a; ; ; n , - - - - - - - - +C;;.o;;;n;.;.tr;.;o;.;.l.;;Lo.;.c;.;;a;;;ti.;;

Number of on;.;..._ _ _. . - - - - - - - - INonro utine I of Analys is Detection Mea n (fraction) Cb) Name Mean (fraction ) Cb) Name Mea n (fraction) Cb) Reported I Performed Gamma 4 LLD <*> Ran ge Cb) Distance and Direction Range Cb) Distance and Direction Ran ge Ch> Measurements(() I K-40 NA 10.50 ( 9.58 - I 1.42 2 / 2 ) No. 2A BVPS Outfall Vicini ty 0.3 I miles WSW 10.50 ( 2 / 2 9.58 - I 1.42

                                                                                                                                                                       ) No. 49A lndustty, PA 4.93 mi les NE Upstream of Montgomery Dam 12.45 (    2 / 2 I 1.86 - 13.04
                                                                                                                                                                                                                                                      )        0 I     Mn-54 Fe-59
               < 0.02
               < 0.03 LLD (

LLD ( 0 I 2 0 I 2 LLD ( LLD ( 0 / 2 0 / 2 LLD( LLD( 0 / 2) 0 / 2) 0 Co-58 < 0.02 0. 14 ( I / 2 ) No. 2A BVPS 0. 14 ( I / 2 LLD ( 0 / 2 ) 0 I < 0.02 LLD - 0. 14 Outfall Vicinity 0.3 I mi les WSW LLD - 0. 14 Co-60 0.14 ( 2 / 2 ) No. 2A BVPS 0. 14 ( 2 /2 LLD ( 0 /2 ) 0

0. 12 - 0. I 5 I
0. 12 - 0. 15 Outfall Vicinity 0.3 1 miles WSW Zn-65 < 0. 04 LLD ( 0 I 2 LLD ( 0 / 2 LLD( 0 / 2) 0 I Zr-95 Nb-95
               < 0.03
               < 0.03 LLD (

LLD ( 0 I2 0 I 2 LLD( LLD ( 0 / 2 0 / 2 LLD( LLD( 0 / 2) 0 / 2) 0 0 Cs- 134 < 0.06 LLD ( 0 / 2 LLD ( 0 / 2 LLD ( 0 / 2 ) 0 I Cs- I 37 < 0.08 0.07 ( 0.07 - 0.07 2 / 2 ) No. 2A BVPS Outfall Vicini ty 0.3 I miles WSW 0.07 ( 0.07 - 0.07 2 / 2 ) No. 49A lndustty, PA Upstream of Montgomery Dam 0.07 ( 2 / 2 0.05 - 0.08

                                                                                                                                                                                                                                                      )        0 4.93 miles NE I   Ba-La- 140  < 0.03         LLD (        0 / 2                                                                                                   LLD (       0 / 2                                                                 LLD(      0 / 2)          0 I

I I I I I 2-15

Beaver Valley Power Station 2016 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2- ENVIRONMENTAL MONITORING PROGRAM Table 2-2 (Continued) I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Na me of Facility: Beaver Valley Power Station Unit I and Unit 2 I Docket No.: 50-334 / 50-4 I 2 Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar Year- 2017 I Medium: Sediment (page 2 of2) I I Unit of Measurement: (picoCuries / gram) Dry Type and Lower Number of Total Number Limit of All Indicator Locations 1-Lo_c_an_*o_n_s_w_i_th_H_.ig__h_es_t_A_n_n_u_al_M_ea_n.,._ _ _ _ _ _ _-t_ C_o_nt_r_ol_Lo_c_a_ti_on_ _ _ _...,.._ _ _ _ _ _-fNonroutine of Analysis Detection Mean (fraction) (b) Name Mean (fraction) (b) Name Mean (fraction) (b) Reported Performed Tl-208 LLD (a) NA Range Cb> 0.35 ( 0.35 - 0.35 2 / 2 ) Distance and Direction No. 2A BVPS Outfall Vicinity Range Cb) 0.35 ( 2 / 2 0.35 - 0.35 Distance and Direction

                                                                                                                               ) No. 49A Industry, PA Upstream of Range (h}

0.34 ( 0.32 -

                                                                                                                                                                                         )

Measurements Cc> 0 I 0.31 miles WSW Montgomery Dam Bi-2 14 NA 0.81 ( 0.73 - 0.88 2 / 2 Same localionfor lhefo l/owing nuclides 0.73 ( 2 / 2 0.69 - 0.76

                                                                                                                               )

4.93 miles NE Same location/or

                                                                                                                                     !he fo llowing nuclides          0.82 ( 2 / 2 0.77 - 0.86
                                                                                                                                                                                         )        0 I

Pb-2 12 Pb-214 NA NA 11 8 ( 0.97 - 1.39 0.90 ( 2 / 2 2 / 2 1.1 8 ( 0.97 - 1.39 0.90 ( 2 / 2 2 / 2

                                                                                                                               )
                                                                                                                               )

0.99 ( 0.87 - I.I I 0.96 ( 2 / 2 2 /2 )

                                                                                                                                                                                         )

0 0 I 0.84 - 0.95 0.84 - 0.95 0.95 - 0.96 Ra-226 NA 2.35 (

2. 12 - 2.58 2 / 2 2.35 ( 2 / 2
2. 12 - 2.58
                                                                                                                               )                                       1.98 ( 2 / 2 1.80 - 2. 15
                                                                                                                                                                                         )                  I Ac-228         NA          1.15 (

1.05 - 1.25 2 / 2 1.15 ( 2 / 2 1.05 - 1. 25

                                                                                                                               )                                       1.20 (

I.II - 1.29 2 /2 ) 0 I

  • Nominal Lower Limit of Detection b Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction) I NA

             ' Nonroutine Reported Measurements (

Reference:

ODCM procedure l/2-0DC-3.03, Attachment Q, Control 3.12.1)

               = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM)

I I I I I I I 2-16 I

I Beaver Valley Power Station 2016 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2- ENVIRONMENTAL MONITORING PROGRAM Table 2-2 (Continued) I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit I and Unit 2 Docket No.: 50-334 / 50-412 I Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar Year - 2017 Medium: Soil (page I of2 ) Soil Sampling is performed every five (5) years. Next sampling is 2020. I Unit of Measurement: (picoCuries / gram) Dry Type and Lower Total Numbe, Limit of All Indicator Locations Locations with Highest Annual Mean Control Location Number of Nonroutine .1 of Analysis Detection Mean (fraction) <*> Name Mean (fraction) <*> Name Mean (fraction)<*> Reported I Performed Gamma LLo<*> Range<*> Distance and Direction Range<*> Distance and Direction Ranee<*> Measurements (r) I K-4 0 Mn-54 NA NA Fe-59 NA I Co-5 8 Co-60 NA NA I Zn-65 Zr-95 NA NA I Nb-95 NA Cs-1 34 NA Cs- 137 NA I Ba-La-140 NA I I I I I I I I 2-17

Beaver Valley Power Station 2016 Annual Radiological Environmental Operating Report RTLA9.690E Enclosure 3 I SECTION 2- ENVIRONMENTAL MONITORING PROGRAM Table 2-2 (Continued) I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Valley Power Station Unit I and Unit 2 Docket No.: 50-334 / 50-412 I Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar Year - 2017 I Medium: Soil (page 2 of2) Soil Sampling is performed every five (5) years. Next sampling is 2020. Unit of Measurement: (picoCuries / gram) Dry Type and Lower Number of I Total Numbei Limit of All Indicator Locations Detection Mean (fraction)<*> Locations with Highest Annual Mean Mean (fraction)<*> Control Location Mean (fraction) <*> Nonroutine I I of Analysis Name Name Reported Performed LLo<*> Range <*> Dis tance and Direction Range (bl Dis tance and Direction Range <*> Measurements (cl Tl-208 NA Bi-2 14 NA Pb-212 Pb-214 NA NA I Ra-226 Ac-228 NA NA I

             ' Nominal Lower Limit of Detection b Mean and range based upon detectable measurements only.

I Fraction of detectable measurements at s pecified locations is indicated in parentheses (fraction)

             ' Nonroutine Reported Measurements (

Reference:

ODCM procedure l/2-0DC-3.03, Attachment Q, Control 3. 12. l ) I NA = Not Applicable ( a tu rally Occurring Radionuclides Not required by ODCM) I I I I I I I I 2-18 I

Beaver Valley Power Station RTLA9.690E 2016 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-2 (Continued) I RADIOLOGICAL ENVIRONMENT AL MONITORING PROGRAM

SUMMARY

Name of Facility: Beaver Va lley Power Station Unit I and Unit 2 Docket No.: 50-334 / 50-412 I Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar Year - 2017 Medium: External Radiation I Unit of Measurement: (mR / Quarter) Type and Lower Total Number Limit of All Indicator Locations 1-L_o.;;c_a_ti..;.on_s.;;w_it_h_H_i.,.g_he_s_t_A_n_n..;.u.;;a.;;l.;;M.;;e.;;a;.;,n--------+C.;;o..;.n..;.tr.;;o..;.l.;;Lo;.;.;;ca..;.ti..;..o.;;n;.__ _ _......--------INonroutine Number of I I of Analysis Detection Mean (fraction) <*> Name Mean (fraction) <*> Name Mean (fraction)<*> Reported Performed LLD <*> Range <*> Distance and Direction Range <h> Distance and Direction Range (bl Measurements (c> Gamma 4.6 18.3 ( 520 I 520 ) No. 7 BYPS Site 25 .2 ( 8 / 8 ) No. 48 Weirton, WV 19.5 ( 8 I 8 ) 0 528 12.6 - 26.8 Perimeter Location 23 .8 - 26.8 Water Tower 14.8 - 23.9 I 0.25 miles SSE Collier Way 16.4 miles SSW I

  • Nominal Lower Limit of Detection b Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (fraction) I ' Nonroutine Reported Measurements (

Reference:

ODCM procedure l/2-0DC-3.03, Attachment Q, Control 3.12.1) NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM) I I I I I I I I I I 2-19

Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-3 I Pre-Operational Environmental Radiological Monitoring Program Summary Name of Facility: Beaver Valley Power Station Docket No.: 50-334 I Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar years 1974 - 1975 Medium or Pathway Analysis and Total Lower Limit All Indicator Locations I Sampled Number of Analysis of Detection Mean, Fraction (c), Range (Unit of Measurement) Sediments (dry) Performed Gross Alpha (0) (LLD) I [picocurie /gram] Gross Beta (33) I 18 (33/33) 5 - 30 Sr-90 U-234, 235, 238 (0) (0) I Gamma (33) -- 13 (33/33) 2 - 30 K-40 Cs-137 Zr/Nb-95 1.5 0.1 0.05 13 0.4 0.8 (33/33) (21 /33) ( 12/33) 2 - 30 0.1 - 0.6 0.2 - 3.2 I Ce-144 0.3 0.5 (3/33) 0.4 - 0.7 Ru-I 06(a) Others 0.3 1.5 (3/33)

                                                                             < LLD 1.3 - 1.8  I Foodcrops (dry)      Gamma                 (8)         --                --

[picocurie /gram] K-40 Cs-137 I 0.1 33 0.2 (8/8) (1/8) 10 - 53 I Zr/Nb-95 0.05 0.2 (1 /8) -- Ru- I 06(a) Others 0.3 0.8 (1 /8)

                                                                             < LLD I

Feedstuff (dry) Gross Beta (80) 0.05 19 (80/80) 8 - 50 [picocurie /gram] Sr-89 Sr-90 Gamma (81) (81) (81) 0.025 0.005 0.2 0.4 (33/81) (78/81) 0.04 - 0.93 0.02 - 0.81 I K-40 I 19 (75/81) 5 - 46 Cs-137 0.1 0.5 (6/81) 0.2 - 1.6 Ce-144 0.3 1.5 (5/81) 0.9 - 2.6 Zr/Nb-95 0.05 0.8 (13/81) 0.2 - 1.8 Ru-106(a) 0.3 1.4 (12/81) 0.6 - 2.3 Others -- < LLD Soil (dry) Gross Alpha (0) -- --

 - Template Samples -

[picocurie /gram] Gross Beta Sr-89 Sr-90 (64) (64) (64) I 0.25 0.05 22 0.4 0.3 (64/64) ( 1/64) (48/64) 14 - 32 0.1-1.3 I U-234,235,238 (0) -- -- Gamma K-40 (64) -- 1.5 13 (63 /64) 5 - 24 I Cs-137 0.1 1.5 (56/64) 0.1 - 6.8 Ce-144 Zr/Nb-95 Ru-106(a) 0.3 0.05 0.3 I. I 0.3 I. I (7/64) (13/64) (3/64) 0.2 - 3 0.1 - 2 0.5 - 2 I Others -- < LLD I I 2-20 I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2- ENVIRONMENTAL MONITORING PROGRAM I Table 2-3 (Continued) I Pre-Operational Environmental Radiological Monitoring Program Summary Name of Facility: Beaver Valley Power Station Docket No.: 50-334 Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar years 1974 - 1975 I Medium or Pathway Analysis and Total Lower Limit All Indicator Locations Sampled Number of Analysis I (Unit of Measurement) Performed of Detection (LLD) Mean, Fraction (c), Range Soil (dry) Gross Alpha (0) -- -- I - Core Samples - [picocurie /gram] Gross Beta Sr-89 Sr-90 (8) (8) (8) 1 0.25 0.05 21 0.2 (8/8)

                                                                                 < LLD (5/8) 16 - 28 0.08 - 0.5 Gamma                 (8)          --                --

I K-40 Cs-137 1.5 0.1 13 1.2 (8/8) (7/8) 7 - 20 0.2 - 2.4 Co-60 0.1 0.2 (1/8) -- I Surface Water Others Gross Alpha (40) 0.3 0.75

                                                                                 < LLD (5/40)       0.6 - I.I

[picocurie / liter] Gross Beta (120) 0.6 4.4 (120/ 120) 2.5 - 11.4 I Gamma Tritium Sr-89 (1) (121) (0) 10 - 60 100 300

                                                                                 < LLD (120/ 121) 180 - 800 Sr-90                (0)           --               --

I Drinking Water C-14 I-131 (0) (0) [picocurie / liter] Gross Alpha (50) 0.3 0.6 (4/50) 0.4 - 0.8 I Gross Beta Gamma (208) (0) 0.6 3.8 (208/208) 2 .3 - 6.4 Tritium (211) 100 310 (211/211) 130 - 1000 I C-14 Sr-89 Sr-90 (0) (0) (0) I Ground Water [picocurie / liter] Gross Alpha Gross Beta Tritium (19) (76) (81) 100 0.3 0.6 2.9 440

                                                                                 < LLD (73/75)(b)

(77/81) 1.3 - 8.0 80 - 800 Gamma (I) 10 - 60 < LLD I Air Particulates and Gaseous Gross Alpha Gross Beta (188) (927) 0.001 0.006 0.003 0.07 (35/ 188) (927/927) 0.002 - 0.004 0.02 - 0.32 [picocurie /cubic meter] Sr-89 (0) -- -- I Sr-90 I-131 (0) (816) 0.04 0.08 (2/816) 0.07 - 0.08 Gamma (197) -- -- I Zr/Nb-95 Ru-106 Ce-141 0.005 0.010 0.010 0.04 0 .04 0.02 (122/ 197) (50/197) (3/ 197) 0.01-0.16 0.02 - 0.09 0.01 - 0.04 Ce-144 0.010 0.02 (44/197) 0.01 - 0.04 I Others < LLD I I 2-21

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-3 (Continued) I Pre-Operational Environmental Radiological Monitoring Program Summary Name of Facility: Beaver Valley Power Station Docket No.: 50-334 I Location of Facility: Beaver County, Pennsylvania Reporting Period: Calendar years 1974 - 1975 Medium or Pathway Analysis and Total Lower Limit All Indicator Locations I Sampled Number of Analysis (Unit of Measurement) Milk I-13 I Performed (91) of Detection (LLD) 0.25 0.6 Mean, Fraction (c), Range (4/91) 0.3 - 0.8 I [picocurie / liter] Sr-89 Sr-90 Gamma (134) (134) (134) 5 I 7 5.3 (4/134) (132/134) 6 - 11 1.5 - 12.8 I External Radiation Cs-137 Others y- Monthly (599) 10 0.5 mR* 13 0.20 (19/134)

                                                                                   < LLD (599/599) 11 - 16 0.08 - 0.51 I

[milliRoentgen / day] y - Quarterly y- Annual (195) (48) 0.5 mR* 0.5 mR* 0.20 0.19 (195/195) (48/48) 0.11 - 0.38 0.11 - 0.30 I Fish (wet) Gross Beta (17) 0.01 1.9 (15/17) 1.0 - 3.2 [picocurie / gram] Sr-90 Gamma (17) (17) 0.005 0.5 0.14 (17/ 17) 0.02 - 0.50 I K-40 -- 2.4 (17/ 17) 1.0-3.7 Others -- < LLD I

  • LLD in units of mR - Lower end of useful integrated exposure detectability range for a passive radiation detector (TLD).

I (a) May include Ru-106, Ru-103, Be-7. (b) One outlier not included in mean. (Water taken from dried-up spring with high sediment and potassium content. Not considered typical groundwater sample). I (c) Fraction of detectable measurements at specified location, indicated in parenthese. I I I I I I 2-22 I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 11 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM I B. Air Monitoring 11 1. Characterization of Air and Meteorology I The air near the site contains pollutants typical for an industrial area. generally from the southwest in summer and from the west in the winter. Air flow 1s I 2. Air Sampling Program and Analytical Techniques I a. Program I The air is sampled for gaseous radioiodine and radioactive particulates at each of eight (8) offsite air sampling stations. The locations of these stations are listed in Table 2-1 and shown on a map in Figure 2-1. I Samples are collected at each of these stations by continuously drawing two cubic I feet per minute of atmosphere air through a glass fiber filter paper and a charcoal cartridge. The glass fiber filter paper is used for collection of airborne particulates, while the charcoal cartridge is used for collection of radioiodine. Samples are I collected on a weekly basis. I The charcoal cartridge is used in the weekly analysis of airborne iodine-131. The glass fiber filter papers are analyzed each week for gross beta, then composited by station each quarter for gamma spectrometry analysis. In order to reduce interference I from short-lived naturally occurring radioactivity (e.g. radon and thorium), the glass fiber filter papers are allowed to decay prior to performing beta analysis in a low background counting system. I

b. Procedures I Gross Beta Analysis of Filter Paper: Analysis is performed by placing the glass fiber filter paper from the weekly air sample in a 2-inch planchet followed by analysis in a I low background, gas flow proportional counter.

I Gamma Emitter Analysis of Filter Paper: Analysis is performed by stacking all of the glass fiber filter papers collected from each monitoring station during the quarter and scanning the composite on a high-resolution germanium gamma spectrometer. I Iodine-131 Analysis of Charcoal Cartridge: Analysis is performed by a gamma scan 11 of each charcoal cartridge. I I 2-23

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

3. Results and Conclusions I

A summary of data is presented in Table 2-2. I

a. Airborne Radioactive Particulates I Gross Beta: A total of four hundred sixteen (416) weekly samples from eight (8) locations were analyzed for gross beta. The results were comparable to that of I previous years. Figure 2-2 indicates the weekly average concentration of gross beta in air particulates. I Gamma Spectrometry: A total of thirty-two (32) quarterly samples were composited from eight (8) locations and analyzed for gamma spectrometry. Naturally occurring I beryllium-7 was identified in twenty-eight of twenty-eight (28 of 28) indicator samples, and four of four (4 of 4) control samples. No other gammas were identified.

A summary of the analysis results during the report period are listed in Table 2-2. A I trend graph of analyses (including the pre-operational period through the report period) is shown on Figure 2-2. I Deviations from Required Sampling and Analysis Schedule: There were two deviations from the required airborne particulate sampling and analysis schedule I during the report period. I During the sampling period of 04/10/17-04/17/17, REMP Air Particulate and Iodine sampling station at Brunton's Dairy in Aliquippa (Site No. 27, 6.16 miles SE) was found to be out of service. The cause was a tripped breaker on the totalizer due to I thunderstorms over the weekend. The breaker was reset during the change out for the next week. The sample station was out of service for approximately 22 hours as I reported by the REMP technician. (CR-2017-04551) During the sampling period of 12/1/17-12/18/17, REMP Air Particulate and Iodine I sampling station at Cook's Ferry Substation in Shippingport (Site No. 30, 0.5 miles ENE) was found to be out of service. The cause was a malfunctioning totalizer. The I components of the air station were replaced and returned to service. The sample station was out of service for approximately 70 hours as reported by the REMP technician. (CR-2017-08225) I During the sampling period of 07/31 /17-08/07 /17, REMP Air Particulate and Iodine I sampling station at Old Meyer Farm in Hookstown (Site No. 13, 1.49 miles SW) was found to be out of service. The cause was shattered carbon vanes. They were I 2-24 I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM replaced, and components of the air station were restored and returned to service. The I sample station was out of service for approximately 83 hours as reported by the REMP technician. (CR-2017-12347) I Summary: Based on the analytical results, the operation of BVPS did not contribute any measurable increase in air particulate radioactivity during the report period. I b. Airborne Radioiodine I Iodine-131 : A total of four hundred sixteen (416) weekly charcoal filter samples were analyzed for iodine-131. Iodine-131 was not identified in any of the three hundred

I sixty-four (364) indicator samples, nor was it identified in any of the fifty-two (52) control samples.

Deviations from Required Sampling and Analysis Schedule: The deviations are the same as described above for airborne particulates. Summary: Based on analytical results, the operation ofBVPS did not contribute any measurable increase in airborne radioiodine during the report period. I I 11 I I I I I I 11 2-25 I

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I Figure 2-1 Environmental Monitoring Locations - Air Sampling Stations I I

                                     *~*,, ... ,   . tfl l
  • f,.NJ I
                                                                     ',,                                                                                    I
                       ,1, l 'a t1*,1c , ~,II I

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            #48 not shown (10 mi radius shown)                                                                                                                f' l II I t 11*
                                                                                                                                                /\III I I

Sample Type Site No. Sector Distance (miles) Sample Point Description I 13 11-SW ' 1.49 Hookstown , PA (Old Meyer Farm) 27 30 32 7-SE 4-ENE 15-NW 6.14 0.43 0.75 Aliquippa , Pa (Brunton Farm) Shippingport, PA (Cook's Ferry Substation) Midland , PA (N orth Substation - Rt. 68) I Air Particulate & Radioiodine 46.1 47 2-NNE/ 3-NE 14-WNW 2.28 4.88 Industry, PA (McKeels Service - Rt. 68) East Liverpool , OH ( Water Department) I 48 10-SSW 16.40 Weirton , VW ( Water Tower, Collier Way) 51 5-E 8.00 Aliquippa, PA (Sheffield Substation) I 2-26 I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I Figure 2-2 Graph of Annual Average Concentration: Gross Beta in Air Particulates I  :::: ..-_-..-_

                      . _-__-_ -__-__-__-_-__-_ -__ -__-_-___-_-__-__-________ _ _ _____________-__-_-_-_-_--~-_-__--_-_-_- ----_-_-_*-1 I    '?0.16 u
    ~ 0.14 I    .e:
    ~ 0.12 a,

E

     ., 0.10                                                                                      --------------------------------------------------

I :a:,

    ~
    'C a,

0.08 --------------------- 8 o.oo I 0

    -[ 0.04 0.02 I         0.00 +-+--1-+--+---+--+-+--1-+--+---+--+-+--f-+--+--+--+-+--f-+--+--+--l-+--f-+--+--+--l-+--l---l-+--l--l-+-l---l-+--I--I
             "~     A      ,.q,        "       ?.,      b        ~       9J     "       r.>   b    "                  ~     b        "     2>    "   ~   ~  '.\
            ~,~*~,~~#~#~~~~~-#####~~~~
                                                                                                        ..-'ll  "

I Pre-Operational value (0 07 pCI i ci.blc meter) -

                                                                                               ---*--- Control Location Required LLD (0 0 1 pC I / ci.blc meter)

I I I I I I I I I 2-27

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM C. Monitoring of Shoreline Stream Sediment and Soil I

1. Characterization of Shoreline Stream Sediment and Soil I

The stream sediment (river bottoms) consists largely of sand and silt. Soil samples may vary from sand and silt to a heavy clay with variable amounts of organic material. I

2. Sampling Program and Analytical Techniques I
a. Program I Shoreline stream sediment was collected semi-annually above the Montgomery Dam, and near the BVPS outfall structure. A Ponar or Eckman dredge is used to collect the I sample. The sampling locations are also listed in Table 2-1 and are shown in Figure 2-3. I Although not required by the ODCM, soil samples were collected at each of the nine (9) locations in 2015 . In 2017, the locations were reduced from ten (10) to five (5), I as well as the sample frequency was revised from once per three years to once every five years. Soil was last sampled in 2015 and will be performed in 2020. At each location, twelve (12) core samples (3" diameter by 2" deep) are gathered at prescribed I

points on a 10 foot radius circle. Each location is permanently marked with reference pins. Each set of samples is systematically selected by moving along the radius in I such a manner as to assure representative undisturbed samples. Sampling locations are listed in Table 2-1 and are shown in Figure 2-3. I Shoreline stream sediment and soil are analyzed for gamma-emitting radionuclides. I

b. Analytical Procedures Gamma Emitter Analysis of Stream Sediment: Analysis is performed in a 300 mL I

plastic bottle and analyzed by gamma spectrometry. I Gamma Emitter Analysis of Soil: Although not required by the ODCM, analysis is performed in a 300 rnL plastic bottle and analyzed by gamma spectrometry. I I I 2-28 I

Beaver Valley Power Station RTL A9.690E I 201 7 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

3. Results and Conclusions I A summary of the analysis results during the report period are listed in Table 2-2. A trend graph of analyses (including the pre-operational period through the report period) is I shown on Figure 2-4 and Figure 2-5.

I a. Shoreline Stream Sediment Gamma Spectrometry: A total of four (4) sediment samples were analyzed by gamma I spectrometry during the report period. Naturally occurring potassium-40, thallium-208, lead-212, lead-214, bismuth-214, radium-226 and actinum-228, were detected in I two of two (2 of 2) indicator samples and two of two (2 of2) control samples. Cesium-137: Radionuclide cesium-137 was identified in two of two (2 of 2) indicator I samples and two of two (2 of 2) control samples. The results were comparable to that of previous years (current annual range = 0.05 to 0.08 picocurie / gram) and less than I the pre-operational level of 0.4 picocurie / gram. Also, because cesium-13 7 was identified at the control location (upstream), then it was not due to plant effluent releases and is most likely residual contamination due from previous nuclear weapons I tests. I Cobalt-58: Radionuclide cobalt-58 was identified in one of two (1 of 2) indicator samples and zero of two (0 of 2) control samples. The sample, which indicated cobalt-58, was obtained at the shore line of the BVPS Main Outfall Facility. The I result was comparable to the previous years (current annual range = LLD to O.14 picocurie / gram) and the data is slightly higher than the BVPS Main Outfall Facility I pre-operational level of 0.098 picocurie / gram. Cobalt-60: Radionuclide cobalt-60 was identified in two of two (2 of 2) indicator I samples and zero of two (0 of 2) control samples. The samples, which indicated cobalt-60, were obtained at the shore line of the BVPS Main Outfall Facility. The results were comparable to previous years (current annual range = 0 .12 to O.15 I picocurie / gram), and the data is currently lower than the BVPS Main Outfall Facility pre-operational level of 0.4 picocurie / gram. I Deviations from Required Sampling and Analysis Schedule: There were no deviations from the required sediment sampling and analysis schedule during the I report period. I I 2-29

I Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 11 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM 11 Summary: The identification of cobalt-58 and cobalt-60 m the shoreline stream sediment near the main outfall facility is not unusual because the plant discharges these radionuclides in liquid effluent releases. The analyses are consistent with II discharge data of authorized liquid effluent releases, and all liquid effluent releases during the report period did not exceed the release limits set forth in the ODCM. I

b. Soil I I Soil sampling is not an ODCM requirement. Soil was last sampled in 2015 and will be performed in 2020. I I

I I I I I I I I I I I 2-30 I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-3 I Environmental Monitoring Locations - Shoreline Sediments and Soil

                                         ,...,,, ,.,,   I l/111 l       J I         Cl.:i*     n

( * .' ,. , , I I (, I t: J I l a:; 1 Li*,* ,po ol I 2* I _,. I ( .' ,, 1-a*r ,en I I Harsh,JVtll V I ( ) _mpi*~ Rae o ,fl Cr

                ' . .,                                                            Sa P< r I                #48 not shown (10 mi radius shown)                                                  ;:m fort Ghntc,n I

i='i tW-,u, temo t1, (\ ,. " I Sample Type Site No. Sector Distance (miles) Sample Point Description I 30A 32A 4-ENE 15-NW 0.43 0.74 Shippingport, PA (Cooks Ferry Substation) Midland , PA (North Substation) Soil 46B 3-NE 2.66 Industry, PA (Willows Inn - Rt. 68) I 48 51A 10-SSW 5-E 16.40 7.99 Weirton , WV (Collier Way Water Tower) Aliquippa, PA (Sheffield Substation) I Sediment 2A 49A 12-WSW 3-NE 0.31 4.93 Shippingport, PA (BVPS Outfall Vicinity) Industry, PA (Upstream Montgomery Dam) I I 2-31

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-4 I Gra h of Annual Avera e Concentration: Cesium-137, Cobalt-58 & Cobalt-60 in Sediment 1000.00 I 100.00 - - - - - - * * * * * - - - - * - - ** -- - - --------------*--------**-*-*--- C

  ~

I ett 10 .00 ************-***************-----------*-*- --* - * - -*- - - - - -- - -***-***-****--**---******-**-****-**-***--****************-*-***-****************-**-***-*******- 0 Sa E I

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 "§ 0

0 Q. 1.00 -****--*-*--- -*-********--- I 0.10 I 0.01 +-+-+-+-+--+--+--t--t--t--it--i---l--+--+--+--+--+--+--+-+--+--+---+---+---+--+--+--+--+--+-+-+-+-+-+-+-+-+-t--i---1---1

              ~~#~#~##~#~~~~#~#~~~~~

I __ _. ___ Cs- 137 ._.__ Control Location Cs-137 Cs -137 Pre-ope rational Resu11s (O 4 pc11gm ) - - Cs-137 Required LLD ( 1BO pCl,gm) 100.00 -* - - I I 1000 - ~ - 1-- - - - - - - - - - - - - - - - * - * - - - *-- -* *--**- . *--- * - - - - * - - * * * - I

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           ..._o,*f:,
                  -            co-58                     Unit 2 Pre.Operational Mean Co-58 (O 098 pc11gm )      __..__ Co-60           * * * * * *
  • Unit 2 Pre.Operatlonal r..iean Co-00 (O 40 pc11gran)

I I 2-32 I

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-5 I Graph of Annual Average Concentration: Cesium-137 in Soil I

          "l-=--

I I 1.2 - -------------------------------; II -1 .0 E

     !?

0 E:

      ~ 0.8          ....

I 'C 0 0.6 0 a" I 0.2 ---*--- I 0.0 +--- - t -- - - t - - - - - - + -- - - + - - - t - - - - t - - - - - 1 1 - - - - - + - -- -+----+-- --+-----i

           .._o,"l'o I                                        ..-.- cs-137  _._ Control Location       Cs-137 Pre-operational (1 2 pCI/ gram)

I I I I I I I I I 2-33

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM D. Monitoring of Feedstuff and Foodcrops I

1. Characterization of Farm Products I According to the 2012 Census of Agriculture (ll, there were six hundred and forty-six (646) farms in Beaver County . Total market value of production was $20,913 ,000 .00 and of the total market I

value, $10,879,000.00 from crops and $10,035 ,000.00 from livestock. Some of the principal sources of revenue (>$25 ,000.00) are as follows: I Milk and Other Dairy Products from Cows $5,271,000.00 Grains, Oil Seeds, Dry Beans and Dry Peas $4,419,000.00 I Cattle and Calves $3 ,331 ,000.00 Other Crops and Hay $2,673 ,000.00 I Nursery, Greenhouse, Floriculture and Sod $1,989,000.00 Vegetables, Melons, Potatoes and Sweet Potatoes $826,000.00 .I Other Animals and Other Animal Products $89,000.00 Sheep, Goats and their Products Poultry and Eggs

                                                                                                         $59,000.00
                                                                                                         $38,000.00 I

Fruits, Tree Nuts and Berries Cut Christmas Trees, and Short Rotation Woody Crops Undisclosed Amount Undisclosed Amount I Horses, Ponies, Mules, Burros, and Donkeys Hogs & Pigs Undisclosed Amount Undisclosed Amount I Tobacco Undisclosed Amount I I ( 1) http://www .agcensus.usda.gov/Pu blications/2012/0nline_ Resources/County_ Profiles/Pennsy Ivan ia/cp42007. pdf I I I I I 2-34 I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I 2. Sampling Program and Analytical Techniques I a. Program I Feedstuff: Although not required by the ODCM, representative samples of feedstuff (cattle feed) are collected monthly from the nearest dairy farm (Brunton Dairy) and I analyzed by gamma spectrometry. See Figure 2-6. Foodcrops (leafy vegetables): Foodcrops are collected at garden locations during the I growing season. Leafy vegetables (e.g. cabbage) are obtained from Shippingport, Raccoon, Georgetown, and Industry, Pennsylvania. Samples are obtained from two I (2) additional locations based upon the highest predicted annual average ground D/Q when milk locations are unavailable. Samples are also obtained from the control location in Weirton, West Virginia. All samples are analyzed for gamma emitters by I gamma spectrometry. Samples are also analyzed by radiochemical analysis for iodine- I 31. I b. Procedures I Gamma Emitter Analysis of Foodcrops: Analysis is performed by scanning a dried, homogenized sample with a gamma spectrometry system. A high-resolution I germanium detector is utilized with this system. Samples of feedstuff and foodcrops are loaded into tare weight 150 or 300 mL plastic bottles or I-liter Marinelli containers, weighed and the net weight of the sample is determined prior to scanning I for gamma emitters. Gamma Emitter Analysis of Feedstuff: Although not required by the ODCM, analysis I is performed by scanning a dried, homogenized sample with a gamma spectrometry system. A high-resolution germanium detector is utilized with this system. Samples I of feedstuff and foodcrops are loaded into tare weight 150 or 300 mL plastic bottles or 1-liter Marinelli containers, weighed and the net weight of the sample is determined prior to scanning for gamma emitters. I Iodine-131 Analysis of Foodcrops: Analysis is performed by radiochemistry. A I stable iodide carrier is added to a chopped sample, which is then leached with a sodium hydroxide solution, evaporated to dryness and fused in a muffle furnace. The melt is dissolved in water, filtered and then treated with sodium hypochlorite. The I iodate is then reduced to iodine with hydroxylarnine hydrochloride and is extracted with toluene. It is then back-extracted as iodide into sodium bisulfite solution and I I 2-35

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM precipitated as palladium iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchet for low level beta counting.

3. Results and Conclusions A summary of the analysis results during the report period are listed in Table 2-2. A trend graph of analyses (including the pre-operational period through the report period) is I

shown on Figure 2-7.

a. F eedstuff Gamma Spectrometry: Although not required by the ODCM, a total of twelve (12) samples were analyzed by gamma spectrometry. Naturally occurring potassium-40 was identified in twelve of twelve (12 of 12) sample,s. Naturally occurring beryllium- I 7 was found in four of twelve (4 of 12) samples.

Deviations from Required Sampling and Analysis Schedule: There were no I deviations from the required feedstuff sampling and analysis schedule during the report period. I Summary: The data from the feedstuff analyses was consistent with previous data. Based on the analytical results, the operation of BVPS did not contribute any I measurable increase in radioactivity in the feedstuff during the report period. I

b. Foodcrops Iodine-131: A total of ten (10) samples were analyzed for iodine-131. No detectable I

concentrations were present in the ten ( 10) indicator samples or the one (1) control sample. I Gamma Spectrometry: A total of ten (10) samples were analyzed by gamma spectrometry. Naturally occurring potassium-40 was identified in ten or ten (10 of I

10) samples indicator samples and the one ( 1) control sample.

I Deviations from Required Sampling and Analysis Schedule: There were no deviations from the required foodstuff sampling and analysis schedule during the report period. I Summary: The data from the foodcrops analyses was consistent with previous data. I Based on the analytical results, the operation of BVPS did not contribute any measurable increase in radioactivity in the foodcrops during the report period. I 2-36 I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-6 I Environmental Monitoring Locations - Feedstuff and Foodcrops I I I 1'1 I I I '.*, I".'

, Q JI P I

I . I

              #48 not shown I         (5 mile radius shown)

I Sample Type Feed Site No. 27 Sector 7-SE Distance (miles) 6.16 Sample Point Description A liquippa , PA (Brunton Farm) 1O* *

  • Shippingport, PA I Food 15*

46* Georgetown , PA Industry, PA 48* *

  • Weirton , WV I * *
  • 2 locations based on hiohest predicted D/Q Individual garden locations may change based upon availability. The requirements are met as long as one garden is sampled from each of these commun ities.

I I 2-37

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-7 I Graph of Annual Average Concentration: Cesium-137 in Feedstuff and Foodcrops I 100 ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ I 10 *************---*********-----********--**-**** I I-;; 0 E I Ii 1 **-**-*******- *-**********-------****-- --- * --------****------****---********-*-*- **-**-*****--*-**--**-********-*-*--.! I I

 .2 j

0 0 I

   "                                                                                                                                                     _________J a.

0.1 I 0.01 +-t---t--+-+--+--+--+-+-+-t---t--+-+--+--+--+--+-t---t--+-+--+--+--+-+-+--t---t--+-+--+--+--+--+-t---t--+-+--+--+--i I

          ~~~ #~ ~#~##~#~~#~~¢~~~
               -- * --- Cs- 137 (Feedstull)              --+- Cs- 137 (Foodc rops)     Cs-137 Pre-operational Resuns - - Cs-137 Required LLD (60 pCl1l<g) Wet         I I

I I I I I I 2-38

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM E. Monitoring of Local Cow and Goat Milk I 1. Description - Milch Animal Locations I Samples of fresh milk are obtained from milch animals at locations and frequencies noted in Table 2-1 . The milk is analyzed for its radioiodine content, gamma emitters, I strontium-89 and strontium-90. Detailed field surveys are performed during the grazing season to locate and enumerate I milch animals within a five (5) mile radius of the site. Survey data for the most recent survey conducted is shown in Section 3, Land Use Census. I 2. Sampling Program and Analytical Techniques

a. Program Cow milk was collected from the one (1) reference dairy farm within a IO-mile radius of the BVPS, Brunton Dairy Farm (6.076 miles southeast) and one (1) control location dairy farm outside of the 10-mile radius, Windsheimer Dairy Farm (10.475 I miles south-southwest).

Dairy cow sampling is performed at Brunton Dairy since 2016, due to the closure of Halstead Dairy and Searight Dairy in 2014. Additionally, one goat location was available for sampling and samples were obtained at the Covert Residence (2.131 miles southwest). The dairies are subject to change based upon availability of milk or when more recent data (milch animal census, and/or change in meteorological conditions) indicate other locations are more appropriate. The milk samples are collected and analyzed biweekly when the animals are on pasture and monthly at other times. The monthly and/or biweekly sample is analyzed for principle gamma emitters (including cesium-13 7 by high resolution germanium gamma spectrometry), and iodine-131 high sensitivity analysis. Although not I required by the ODCM, the monthly and/or biweekly sample is also analyzed for strontium-89, strontium-90. I The location of each is shown in Figure 2-8 and described below. I I 2-39

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Table 2-4 I Local Cow and Goat Locations I Approximate Distance and Direction Collection Site Dairy Number of Animals being Milked from Midpoint between Unit 1 and Unit 2 Period I Reactor 25* Searight Dairy Dairy Closed end of January thru I 948 McCleary Road 2.107 miles SSW 27 Hookstown, PA Brunton Dairy 2013 December I January thru 3681 Ridge Road Aliquippa, PA 104 Cows 6.076 miles SE December I 96 Windsheimer Dairy 20 Windsheimer Lane 76 Cows 10.475 miles SSW January thru December I Burgettstown, PA 113* Halstead Dairy 104 Tellish Drive Dairy Closed beginning of 2014 5.184 miles SSW January thru December I Hookstown, PA Covert Residence January thru I 114 930 Pine Street (Route 168) 9 Goats 2.131 miles SW Hookstown, PA

  • Highest potential pathway dairies based on evaluation of deposition parameters December I

I I I I IiI I I 2-40 I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM

b. Procedure I Iodine-131 Analysis of Milk: The milk samples are chemically prepared, and then analyzed with a low-level beta counting system.

I Gamma Emitter Analysis of Milk: This is determined by gamma spectrometry I analysis of a 1 liter Marinelli container of milk. Strontium-90 Analysis of Milk: Although not required by the ODCM, the milk I samples are prepared by adding a stable strontium carrier and evaporating to dryness, then ashing in a muffle furnace, followed by precipitating phosphates. Strontium is I purified in all samples by the Argonne method using 3 grams of extraction material in a chromatographic column. Stable yttrium carrier is added, and the sample is allowed to stand for a minimum of 5 days for the in-growth of yttrium-90 (Y-90). Yttrium is I then precipitated as hydroxide dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low-level beta counter to I infer strontium-90 activity. Strontium-89 Analysis of Milk: Although not required by the ODCM, the strontiurn-I 89 activity is determined by precipitating strontium carbonate (SrC03) from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting. I Chemical yields of strontium and yttrium are determined by gravimetric means. I 3. Results and Conclusions A summary of the analysis results during the report period are listed in Table 2-2. A I trend graph of iodine-131 and strontium-90 analyses (including the pre-operational period through the report period) is shown on Figure 2-9. I a. Strontium-89: Although not required by the ODCM, a total of sixty-three (63) milk samples were analyzed for strontium-89 during the report period. Strontium-89 was I not detected in any of the forty-two (42) indicator samples, nor was it detected in any of the twenty-one (21) control samples. I b. Strontiurn-90: Although not required by the ODCM, a total of sixty-three (63) milk samples were analyzed for strontium-90 during the report period. Strontium-90 was I detected in fourteen of forty-two (14 of 42) indicator samples and sixteen of twenty-I I 2-41

Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 11 SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM I one (16 of 21) control samples. The levels detected were attributed to previous nuclear weapons tests and are within the expected range. I

c. Gamma Spectrometry: A total of sixty-three (63) milk samples were analyzed by gamma spectrometry during the report period. Naturally occurring potassium-40 was present in thirty-two of forty-two (32 of 42) indicator samples and twenty-one of I

twenty-one (21 of 21) control samples. No other gamma-emitting radionuclides were identified during analysis. I

d. Iodine-131: A total of sixty-three (63) milk samples were analyzed for iodine-131 during the report period. Iodine-131 was not detected in any of the forty-two (42)

I indicator samples, but was it detected in one of twenty-one (21) control samples. This anomaly was under the reportable limit and was documented for trending. I

e. Deviations from Required Sampling and Analysis: There were two deviations from the required milk sampling and analysis schedule occurred for the reporting period.

I Sufficient milk samples were not available from locations within the 5 mile radius in I 2017. The unavailability of milk caused the REMP to not meet the ODCM sample requirements in l/2-0DC-2.03 and in l/2-0DC-3.03, Attachment Q Table 3.12-1 stating that a minimum of four (4) milk locations shall be sampled. This initiated the I ODCM requirement for sampling two (2) additional garden locations based upon the highest predicted annual average D/Q when milk locations are not available. I During the sampling period, 07/09/2017 - 07/15/201 7, REMP milk (goat) sampling location at the Covert' s Residence in Hookstown, PA (Site No. 114, 2.131 miles SW) I was unavailable. The owner and goats were out of town during the sampling period. (Notification 601078879, Line 6) I

f. Summary: Based on all the analytical results and the comparison to pre-operational I

levels, the operation of BVPS did not contribute any measurable increase m radioactivity in the milk during the report period compared to previous years. I I I I 2-42 I

I Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-8 I Environmental Monitoring Locations - Milk I I I I 01 l(o *. il I I .ll ::br ,j Ea , _,.. i: co . I I )

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h I Ulp 3 r ,rt , . I I I I' Ch ton I 10 mile radius shown I Sample Type Site -No. Sector Distance (miles) Sample Point Description 27 7-SE 6.1 Aliquippa, PA (Brunton Farm) I Milk 96 114 10-SSW 11-SW 10.4 1.9 Burgettstown , PA (Windsheimer Farm) Hookstown , PA (Covert Residence) I I 2-43

Beaver Valley Power Station 2017 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-9 I 14.0 Gra h of Annual Avera e Concentration: Iodine-131 & Sr-90 in Milk I 12 .0

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Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM F. Environmental Radiation Monitoring I 1. Description of Regional Background Radiation and Sources I Historical information for regional background was obtained from Reuter-Stokes instruments that were previously located within a five (5) mile radius of the BVPS site. I Data is no longer available from these instruments, but historical data indicated that the background exposure rates ranged from 6 µR/hr to 12 µR/hr. I The sources of background radiation are affected by the terrain in the vicinity of BVPS, whereas, the local hills (i.e. altitude variations of 300-400 feet) and densely wooded areas I contribute to variations in background radiation. Other sources (e.g. radon) are affected by the geological features of the region, which are characterized by nearly flat-laying sedimentary beds of the Pennsylvania age. For information, the local sedimentary beds I of limestone alternate with sandstone and shale with abundant interbedded coal layers. Pleistocene glacial deposits partially cover the older sedimentary deposits in the I northwest. Most of the region is underlain by shale, sandstone, and some coal beds of the Conemaugh Formation. Outcrops of sandstone, shale, and limestone of the Allegheny Formation exist within the Ohio River Valley and along major tributary streams. I 2. Locations and Analytical Procedures I Ambient external radiation levels around the site were measured using TLDs. I During the report period, there were a total of sixty-six (66) environmental TLD locations. This is comprised of forty-four (44) offsite locations, along with twenty-two I (22) fence perimeter locations. The offsite TLD locations are plotted on Figure 2-10, but the fence perimeter locations are not plotted due to the large scale of the figure. I The TLDs were annealed at the Contractor Central Laboratory shortly before placing the TLDs in their field locations. The radiation dose accumulated in-transit between the I Central Laboratory, the field location, and the Central Laboratory was corrected by transit controls maintained in lead shields at both the Central Laboratory and the field office. All dosimeters were exposed in the field for a calendar quarter, in a specific I holder that contains two (2) TLDs at each location. I I I 2-45

Beaver Valley Power Station RTL A9.690E 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2- ENVIRONMENTAL MONITORING PROGRAM

3. Results and Conclusions I

A summary of the TLD results during the report period are listed in Table 2-2. A trend I graph of analyses (including the pre-operational period through the report period) is shown on Figure 2-11. I TLD Analysis: During the report period, the average quarterly external exposure rate (as measured from TLD) was 18.9 mR at the sixty-six (66) indicator locations, and 19.5 mR I at the control location. This external exposure rate is comparable to previous years. As expected, there was some variation in external exposure rate among locations and seasons. I Deviations from Required Sampling and Analysis Schedule: There was one deviation from the required direct radiation monitoring schedule during the report period. On Thursday January 5, 2017, the REMP technician was performing the scheduled quarterly TLD changeout. During the work, it was noticed that Station #94 (McCleary Road & Pole Cat Hollow Rd, 2.37 miles SSW) was missing both of its two TLDs for the 4th quarter for 2016. The TLDs have been replaced at this location for 1st quarter collection (CR-2017-04706). I Summary: The quarterly TLD external exposure rates are comparable to that of the previous decade. There was no evidence ,of anomalies that could be attributed to the I operation of BVPS. It should also be noted that the average external exposure rate at the indicator locations was less than average external exposure rate at the control location. Based on all the analytical results and the comparison to pre-operational levels, the I operation of BVPS did not contribute any measurable increase in external exposure in the vicinity of the site during the report period. The TLD exposure rates also confirm that I changes from natural radiation levels, if any, are negligible. I I I I I 2-46 I

Beaver Valley Power Station RTL A9.690E I 2017 Annual Radiological Environmental Operating Report Enclosure 3 I SECTION 2 - ENVIRONMENTAL MONITORING PROGRAM Figure 2-10 I Environmental Monitoring Locations - TLDs I ' \I II 't I Cl It !:O I

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