ML101310414

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Beaver Valley, Units 1 and 2, Rtl# A9.690E, 2009 Radioactive Effluent Release Report and 2009 Annual Radiological Environmental Operating Report.
ML101310414
Person / Time
Site: Beaver Valley
Issue date: 04/01/2010
From: Powell-Campbell J L, Renz L
FirstEnergy Nuclear Operating Co
To:
Office of Nuclear Reactor Regulation
References
L-10-050 RTL# A9.690E
Download: ML101310414 (168)
v • d • e


Text

RTL# A9.690E FIRSTENERGY NUCLEAR OPERATING COMPANY BEAVER VALLEY POWER STATION 2009 RADIOACTIVE EFFLUENT RELEASE REPORT AND 2009 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT UNITS NO. 1 AND 2 LICENSES DPR-66 AND NPF-73 RTL A9.690E Enclosure 1 BEAVER VALLEY POWER STATION ENVIRONMENTAL

& CHEMISTRY SECTION Technical Report Approval: 2009 RADIOACTIVE EFFLUENT RELEASE REPORT AND 2009 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT UNITS NO. 1 AND 2 LICENSES DPR-66 AND NPF-73 Prepared by: Jennifer L. Powell-Campbell

-,, (".A(2.Prepared by: Lara Renz -, Date: :4 -I -1 Date: Lcji~1 0 Date: I'Lp/s/R4 Reviewed by: Michael D. Banko III i,; L, 0_LI*1 Approved by: Donald J. Salera Date: 4-u--" 13

Subject:

Beaver Valley Power Station, Unit Nos. 1 and 2 I 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 2009, and Annual Radiological Environmental Operating Report for 2009 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: U. S. Nuclear Regulatory Commission I Ms. N. S. Morgan, NRR Project Manager U. S. Nuclear Regulatory Commission

  • Mr. D. L. Werkheiser, NRC Senior Resident Inspector U. S. Nuclear Regulatory Commission Mr. S. J. Collins, NRC Region I Administrator Copies of Report to Other Agencies: American Nuclear Insurers 95 Glastonbury Boulevard l Glastonbury, CT 06033 Department of Environmental Protection (5 copies) 1 Bureau of Radiation Protection

& Toxicology P.O. Box 2063 Harrisburg, PA 17120 Department of Environmental Protection (2 copies) m Southwest Regional Office 400 Waterfront Drive Pittsburgh, PA 15222 INPO (Attn: Bill Nestel)700 Galleria Parkway SE Suite 100 Atlanta, GA 30339-5957 Distribution for Enclosures 1 -3: Page 2 Beaver County Cooperative Extension (Attn: JL Miller)156 Cowpath Road Aliquippa, PA 15001-5842 Hancock County Office of Emergency Services (Attn: JP Jones)PO Box 884 New Cumberland, WV 20647 Ohio Department of Health (Attn: RL Suppes)246 North High Street Columbus, OH 43266-0288 Ohio Emergency Management Agency (Attn: Carol O'Claire)2855 West Dublin Granville Road Columbus, OH 43235 East Liverpool Water Authority (Attn: Keith Clark)2220 Michigan Avenue East Liverpool, OH 43920 ORSANCO (Attn: Jerry Schulte)5735 Kellogg Avenue Cincinnati, OH 45228 B. F. Jones Memorial Library 663 Franklin Avenue Aliquippa, PA 15001 Mr. Robert Leidy, HP3 Bureau of Radiation Protection Ohio Department of Health Northeast District Office 161 South High Street, Suite 400 Akron, OH 44308-1612 Distribution for Enclosures 1 -3: U Page 3 Copies of Report.for FENOC Addressees:

MD Banko, BVPS; Supervisor, Nuclear Chemistry Services (A-BV-A)JL Powell-Campbell, BVPS; Chemistry RETS Administrator (A-BV-A) 5 copies LM Renz, BVPS; Chemistry REMP Administrator (A-BV-A) 5 copies DJ Salera, BVPS; Manager, Site Chemistry (A-BV-A)K Nevins, Akron; Sr. Nuclear Specialist, Fleet Licensing (A-GO-2) 2 copies FA Cocivera, BVPS; Sr. Nuclear Specialist, Operations Oversight (A-BV-NCD3)

RL Evans, Akron; Director, Environmental (A-GO- 13)DW Jenkins, Akron; Sr. Attorney II, Legal (A-GO-15)M Hall, Akron; Vice President, Energy Policy (A-GO-18)MJ Jirousek, Akron; Manager, Environmental Generation Services (A-GO-13)K Yeager, Perry NPP RETS Administrator (A-PY-CCB 125)JP Balstad, Perry NPP REMP Administrator (A-PY-CCB 125)AM Percival, Davis-Besse RETS & REMP Administrator (A-DB-1041)

I B Grob, Manager, Environmental, Inc.RJ Dinello, Field Specialist, Environmental, Inc BVPS Document Control, RTL A9.690E BVRC -Keywords:

Radioactive Effluent Release Report, Annual Radiological Environmental Operating Report I I I I I I I I I RTL A9.690E Enclosure 2, Page i Form 1/2-ENV-01.05.FO1 (page 1 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 2009 Radioactive Effluent Release Report FirstEnergy Nuclear Operating Company FENOC Beaver Valley Power Station -Units 1 & 2 Unit 1 License No. DPR-66 Unit 2 License No. NPF-73 Form 1/2-ENV-01.05.FO1 (page 2 of 38), Rev 2 " Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2009 Index RTL# A9.690E Enclosure 2, Page ii Title Page Cover Index ii Executive Summary -Report Submittal Requirements iii Executive Summary -Liquid and Gaseous Effluent Control (Part 1 of 2) iv Executive Summary -Liquid and Gaseous Effluent Control (Part 2 of 2) v Executive Summary -Trends of Total Dose vi Executive Summary -Trends of Liquid Release Activity (Fission and Activation Products) vii Executive Summary -Trends of Liquid Release Activity (Tritium) viii Executive Summary -Trends of Liquid Release Offsite Dose Projections ix Executive Summary -Trends of Gaseous Release Activity (Fission and Activation Gas) x Executive Summary -Trends of Gaseous Release Activity (Particulates and Radioiodines) xi Executive Summary -Trends of Gaseous Release Activity (Tritium) xii Executive Summary -Trends of Unit 1 Gaseous Release Offsite Dose Projections xiii Executive Summary -Trends of Unit 2 Gaseous Release Offsite Dose Projections xiv Results of Abnormal Releases xv Results of Onsite Spills and Items Added to Decommissioning Files per 10CFR50.75(g) xvi Results of Onsite Groundwater Monitoring Program xvii I I I U I I I I I Supplemental Information Paoe 1 Table 1A Gaseous Effluents

-Summation Of All Releases 2 Table 1 B-EB Gaseous Effluents

-Elevated Batch Releases 3 Table 1 B-EC Gaseous Effluents

-Elevated Continuous Releases 4 Table 1C-GB1 Gaseous Effluents

-Ground Level Batch Releases (Unit 1) 5 Table 1 C-GC1 Gaseous Effluents

-Ground Level Continuous Releases (Unit 1) 6 Table 1 C-GB2 Gaseous Effluents

-Ground Level Batch Releases (Unit 2) 7 Table 1 C-GC2 Gaseous Effluents

-Ground Level Continuous Releases (Unit 2) 8 Table 2A Liquid Effluents

-Summation Of All Releases 9 Table 2B-B Liquid Effluents

-Batch Releases 10 Table 2B-C Liquid Effluents

-Continuous Releases 11 Table 3A Solid Waste And Irradiated Fuel Shipments (Part 1 of 3) 12 Table 3B Solid Waste And Irradiated Fuel Shipments (Part 2 of 3) 13 Table 3C Solid Waste And Irradiated Fuel Shipments (Part 3 of 3) 14 Table 4 Lower Limits Of Detectability 15 Table 5A Assessment Of Radiation Doses (Unit 1) 16 Table 5B Assessment Of Radiation Doses (Unit 2) 17 Table 6 Effluent Monitoring Instrumentation Channels Not Returned To Operable Status Within 30 Days 18 Table 7 Total Dose Commitments, Total Effective Dose Equivalents and Population Doses 19 Table 8 Offsite Dose Calculation Manual Surveillance Deficiencies 20 Table 9 Unit 1 and 2 Offsite Dose Calculation Manual Changes (Description) 21 I I I I I I I I I Attachment I Part 1: Joint Frequency Distribution Tables (35 ft)Part 2: Joint Frequency Distribution Tables (150 ft)Part 3: Joint Frequency Distribution Tables (500 ft)Attachment 2 [Unit 1 and 2 Offsite Dose Calculation Manual (Complete Copy)Note: The Total Error values (%) listed in this report are documented in Calculation Package No. ERS-ATL-04-002 Form 1/2-ENV-01.05.FO1 (page 3 of 38), Rev 2 RTL# A9.690E Beaver Valley Power Station -Units 1 & 2 Enclosure 2, Page iii Radioactive Effluent Release Report Calendar Year -2009 Executive Summary -Report Submittal Requirements Report Submittal and Requirements:

The report was prepared and submitted in accordance with the requirements contained in the following documents:

BVPS Integrated Technical Specifications, Administrative Control 5.6.2 Offsite Dose Calculation Manual (ODCM) procedure 1/2-ODC-3.03, "Controls for RETS and REMP Programs" , Attachment U, Control 6.9.3 BVPS procedure 1/2-ENV-01.05, "Compliance with Regulatory Guide 1.21 and Technical Specifications" NUREG- 1301," Offsite Dose Calculation Manual Guidance:'

Standard Radiological Effluent Controls for Pressurized Water Reactors, Generic Letter 89-01, Supplement No. 1, April 1991" Regulatory Guide 1.21, "Measuring Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Material in Liquid and Gaseous Effluents from Light-Water Cooled Nuclear Power Plants, Revision 1, June 1974" BVPS Condition Report No. CR 09-52947 and BVPS-SAP Order Number 200197646-0790 are associated with reporting the failure to return a gaseous effluent radiation monitor to service within 30 days.BVPS Condition Report No. CR 09-61459 is associated with reporting the failure to return a gaseous effluent radiation monitor to service within 30 days.BVPS Condition Report No. CR 09-64033 is associated with reporting the inability to include a filter paper as part of the monthly composite particulate sample.BVPS Condition Report No. CR 10-69838 is associated with reporting the inability to include a filter paper as part of the monthly composite particulate sample.

Form 1/2-ENV-01.05.F01 (page 4 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 RTL# A9.690E Enclosure 2, Page iv Radioactive Effluent Release Report Calendar Year -2009 Executive Summary -Liquid and Gaseous Effluent Control (Part 1 of 2)Onsite Groundwater Monitoring:

Tritium results from two (2) of seventeen (17) wells were >2000 pCi/L, which are similar to results initially communicated in 2007. All gamma spectrometry analyses were <LLD.No adverse effect has been detected in offsite groundwater, drinking water and surface water.Onsite Spills: There were no onsite spills >100 gallons.Decomnnissioning File Update: There were no items added to the site decommissioning files in accordance with 10CFR50.75(g).

Abnormal Liquid Releases:

There were no abnormal liquid releases.Abnormal Gaseous Releases:

There were no abnormal gaseous releases.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 liquid waste at the Unit of origin, or at the other Unit. Typically, when Unit 1 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.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 1 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 I I I I I I I I Form 1/2-ENV-01.05.F01 (page 5 of 38), Rev 2 RTL# A9.690E Beaver Valley Power Station -Units 1 & 2 Enclosure 2, Page v Radioactive Effluent Release Report Calendar Year -2009 Executive Summary -Liquid and Gaseous Effluent Control (Part 2 of 2)Lower Limits of Detectability (LLD): All a-priori calculated LLD met the minimum requirements specified in the ODCM.Effluent Monitoring Channels Inoperable

>30 Days: There were two (2) Effluent Monitoring Instrumentation Channels not returned to Operable status within 30 days. They are described in Table 6.ODCM Surveillance Deficiencies:

There were two (2) ODCM Surveillance Deficiencies.

They are described in Table 8.ODCM Changes: There were two (2) changes made to the ODCM.Meteorological Data Recovery:

The Meteorological Data Recovery met the minimum requirement of at-least 90%, as specified in Section 5 of Revision i to Regulatory Guide 1.23, Meteorological Monitoring Programs for Nuclear Power Plants.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 natural background radiation demonstrates that BVPS operations did not adversely affect the surrounding environment.

621 man-mrem =BVPS Total Population Dose for the year 0.000 1553 mrem = BVPS Average Individual Dose for the year 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 BEIR V Report.

Form 1/2-ENV-01.05.FO1 (page 6 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2009 Executive Summary -Trends of Total Dose RTL# A9.690E Enclosure 2, Page vi 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. The graph reflects the results of the efforts to stabilize and reduce offsite dose.Unit 1 and Unit 2 Total Dosel 100.0%E 10-0%/o 00.0.%,q- ý11 1110 OId 1-40,Unit 1&2, Percent of 40 CFR 190.10(a)

Total Body Dose Limit 0 Unit 1&2, Percent of 40 CFR190.10(a)

Thyroid Dose Limit 0- Unit 1&2, Percent of 10 CFR 20.1301(a)(1)

TEDE Dose Limit I I I I I I I I I I I I I I I I I Form 1/2-ENV-01.05.FO1 (page 7 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 RTL# A9.690E Enclosure 2, Page vii Radioactive Effluent Release Report Calendar Year -2009 Executive Summary -Trends of Liquid Release Activity (Fission and Activation Products)Liquid Release Activity (Fission and Activation Products):

The following graph provides a comparison of total liquid mixed fission and activation product (particulate) radioactivity discharged from the site from 1976 to present. The recent increases were due to efforts to reduce overall offsite dose. Specifically, discharging liquid radioactive inventory provided the benefit of reduced total offsite dose, due to reduction in evaporative losses from the fuel pools.Liquid Effluent Trends Mixed Fission and Activation Products 10.00 CD 00 0 0.10--------

0.01 I I I 1 1 1 1 0 BVPS Unit 1-.*-BVPS Unit 2 1 c VSUnt1.u.BP ni Form 1/2-ENV-01.05.FO1 (page 8 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 RTL# A9.690E Enclosure 2, Page viii Radioactive Effluent Release Report Calendar Year -2009 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 recent increases were due to efforts to reduce overall offsite dose. Specifically, discharging liquid radioactive inventory provided the benefit of reduced total offsite dose, due to reduction in evaporative losses from the fuel pools.I I I I I N I I I Liquid Effluent Trends Tritium 10000 1000 ---0 ,,,0 Jlll 0111ý" 100 --------------o 0 10 1.< ,91 ,k ,0,q, o , o I BVPS Unit 1 -a--BVPS Unit 2 1 I I I I I I I I I Form 1/2-ENV-01.05.F01 (page 9 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 RTL# A9.690E Enclosure 2, Page ix Radioactive Effluent Release Report Calendar Year -2009 Executive Summary -Trends of Liquid Release Offsite Dose Projections Liquid Release OfMsite Dose Projections:

The following graph provides a comparison of liquid offsite 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.

The recent increases were due to efforts to reduce overall offsite dose. Specifically, discharging liquid radioactive inventory provided the benefit of reduced total offsite dose, due to reduction in evaporative losses from the fuel pools.Unit 1 or Unit 2 Liquid Effluent Dosel 100.0%2 10.0%00 ci 0 00 001.0%0.1%. ..., , ,"41Unit 1 or Unit 2, Percent of Maximum Organ Dose Limit 0 Unit 1 or Unit 2, Percent of Total Body Dose Limit c~ ~ Q~O~

Form 1/2-ENV-O1.05.F01 (page 10 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 RTL# A9.690E Enclosure 2, Page x Radioactive Effluent Release Report Calendar Year -2009 Executive Summary -Trends of Gaseous Release Activity (Fission and Activation Gas)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 overall decreases are due to extended hold-up periods of gas space prior to release.Liquid Effluent Trends Mixed Fission and Activation Products 10000.00 0 -----100.00 0 1.00 ---------.-.

.-.--

0 .1 0 ------------------------------------0.01K~b~ ~K ,~b K~bo~Kb b b b b b C ,b ,, , (U I I I I N I I I I I 1 BVPS Unit 1 --m-BVPS Unit 2 I I I I I I I I Form 1/2-ENV-01.05.FO1 (page 11 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 RTL# A9.690E Enclosure 2, Page xi Radioactive Effluent Release Report Calendar Year -2009 Executive Summary -Trends of Gaseous Release Activity (Particulates and Radioiodines Gaseous Release Activity (Particulates and Radioiodines):

The following graph provides a comparison of total gaseous particulates and radioiodines discharged from the site from 1976 to present. The increase at at Unit 2 was due to identification of Co-58 and Co-60 in weekly effluent pathway samples during a refueling outage.Gaseous Effluent Trends Particulates

& Radioiodines l.E-Ol -1. E-01 0 1.E-02 -----00 1 .E-07 -, < ---------- , -----,---- --- ---,c~b -b -o , b ,b 1 0 BVPS Unit 1 --U--BVPS Unit 2 Form 1/2-ENV-01.05.FO1 (page 12 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 RTL# A9.690E Enclosure 2, Page xii Radioactive Effluent Release Report Calendar Year -2009 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 of reduced total offsite dose, due to reduction in evaporative losses from the fuel pools.Gaseous Effluent Trends Tritium 1000 100 10 10 , c KI -,C NN -? \,q I I I I I U I I I I ZIb Ip I

  • BVPS Unit 1 --BVPS Unit 2 -

Form 1/2-ENV-01.05.FO1 (page 13 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 RTL# A9.690E Enclosure 2, Page xiii Radioactive Effluent Release Report Calendar Year -2009 Executive Summary -Trends of Unit 1 Gaseous Release Offsite Dose Projections Unit 1 Gaseous Release Offsite Dose Proiections:

The following graph provides a comparison of Unit 1 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.

The steady decrease in highest organ dose was due to efforts to reduce overall offsite dose. Specifically, discharging liquid radioactive inventory provided the benefit of reduced total offsite dose, due to reduction in evaporative losses from the fuel pools.Unit 1 Gaseous Effluent Dosel 100.0000000%

-10.0000000%

1.0000000% ýo>1 0.0100000%

>- 0.0010000%

og 0.0001000%

0.0000100%

0.0000010%

0.0000001%

T--M-Unit 1, Percent of Gamma Air Dose Limit* Unit 1, Percent of Beta Air Dose Limit--- Unit 1, Percent of Highest Organ Dose Limit Form 1/2-ENV-01.05.FO1 (page 14 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 RTL# A9.690E Enclosure 2, Page xiv Radioactive Effluent Release Report Calendar Year -2009 Executive Summary -Trends of Unit 2 Gaseous Release Offsite Dose Projections 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 conditions surrounding the plant site, and were performed prior to release authorization.

The steady decrease in highest organ dose was due to efforts to reduce overall offsite dose. Specifically, discharging liquid radioactive inventory provided the benefit of reduced total offsite dose, due to reduction in evaporative losses from the fuel pools.I I I I I I I I I I IUnit 2 Gaseous Effluent Dosel 1 00.0000000%

10.0000000%

1.0000000%

0 M E 0.1000000%

00.A 0.0001000%

___0.0000100%

0.0000010%

0.0000001%

o * -"5"Unit 2, Percent of Gamma Air Dose Limit 0 Unit 2, Percent of Beta Air Dose Limit-Unit 2, Percent of Highest Organ Dose Limit I U I I U I I Form 1/2-ENV-O1.05.FO1 (page 15 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2009 Results of Abnormal Releases RTL# A9.690E Enclosure 2, Page xv Abnormal Liquid Releases:

None Abnormal Gas Releases:

None Form 1/2-ENV-01.05.FO1 (page 16 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 RTL# A9.690E Enclosure 2, Page xvi Radioactive Effluent Release Report Calendar Year -2009 Results of Onsite Spills and Items Added to Decommissioning Files per 10CFR50.75(g)

Summary of Onsite Spills (>100 gallons):

None SIummary of Items added to Decommissioning Files per 10CFR50.75(g)

Files: None I I I I I!i I I N I I I I I I I I I Form 1/2-ENV-01.05.F01 (page 17 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 RTL# A9.690E Enclosure 2, Page xvii Radioactive Effluent Release Report Calendar Year -2009 Results of Onsite Groundwater Monitoring Program Summary of Onsite Groundwater Samples I 2009 2009 H-3 H-3 Maximum Minimum (pCi/L) (pCi/L)2009 H_3 Average (pCi/L)Typicall Required Pre H-3ý H-3 Operational LLD LLD Mean For H-3 (pCi/L) (pCi/L) (pCi/L)Are Any H-3 Analyses Greater Than The Pre Operational Mean For H-3 ?NEI and FENOC Communication Level For H-3 (pCi/L)EPA Reporting Level For H-3 (pCi/L)I1stQuarter 109921 1481 17011 <2001 <20001 4401 Ye 20001 2000 13rd Quarterl 89861 1441 13061 <2001 <20001 4401 Yesl 20001 20000]Sample Summary: Seventeen (17) onsite monitoring wells were sampled during the year. Each of these wells was sampled twc (2) times during the year. I H-3 Summary; Results from eleven (11) wells were_<440 pCi/L (BVPS pre-operational mean). Results from four (4) wells were>440 pCi/L, but:<2000 pCi/L. Results from two (2) wells (MW-12S & MW-12D) were >2000 pCi/L, buk20,000 pCi/L. Results from no wells were >20,000 pCi/L. SINCE the NEI/FENOC communication level was reached for MW-12S & MW-12D during 2007, THEN notification to local, state & federal agencies was performed on 10/08/07.

No additional wells reached the NEI/FENOC communication level during 2009. 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.Principal Gamma Emitter Summary: Results showed <LLD for all principal gamma emitters associated with Licensed Radioactive Material (LRM).Gross Alpha & Gross Beta Summary: Baseline analyses were performed on 3rd quarter 2008 samples. The Gross Alpha results ranged from <MDA to 2.2 pCi/L, and the Gross Beta results ranged from 1.0 pCi/L to 5.6 pCi/L. Gross Alpha & Gross Bet4 analyses will be performed next during the 3rd quarter 2010 sampling event.Fe-55. NI-63. Sr-89 & Sr-90: Baseline analyses were performed on 3rd quarter 2008 samples for MW-12S & MW-12D. The Fe- 1 55 results were <LLD, the Ni-63 results were <LLD, the Sr-89 results were <LLD, and the Sr-90 results were <LLD. Fe-55, Ni-631 Sr-89 & Sr-90 analyses will be performed next during the 3rd quarter 2010 sampling event. I BVPS (2007-2009)

Onsite Groundwater Monitoring Program H-3 Trends<200 pCi/I = Typical LLD 440 pCi/L = Pre-Operational Mean 800 pCi/L = Pre-Operational Max 2,000 pCi/L = NRC Required LLD (NEI Communication Level)20,000 pCi/L = EPA Reporting Level 0 Max of All GWM Indicator Wells i Avg of All GWM Indicator Wells-A-----MW-10:

67.0' deep, Upgradient Location-Typical LLD H-3 (<200 pCV/L)Pre- Operational Mean H-3 (440 pCi/L)Pre- Operational Maximum H-3 (800 pCi/L)_" NRC Required LLD H-3 (2,000 pCi/L)-EPA Reporting Level H-3 (20,000 pCilL)10 U U 0 a.0000-1000o 100 a a a I a4 Form 1/2-ENV-01.05.F01 (page 18 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 RTL# A9.690E Enclosure 2, Page 1 of 21 Radioactive Effluent Release Report Calendar Year -2009 Supplemental Information Page FACILITY:-

B.V.P.s. Unitsl.and 2-_ L LICENSEE:

' FENo C I I I 11. Regulatory Limits 7 I a. Fission and activation gases: Annual Unit 1 or 2 Dose: 10 mrad from Gamma, & 20 mrad from Beta b. lodines & particulates, half-lives

> 8 days:. Annual Unit 1 or 2 Dose: 15 mrem to Any Organ c. Liquid effluents:

Annual Unit 1 or 2 Dose: 3 mrem to Total Body, & 10 mrem to Any Organ 2. Maximum Permissable Concentrations Used In Determining.

Allowable Release Rates Or Concentrations

a. Fission and activation gases: TSite Release Rate: 500 mrem/yr to Total Body, & 3000 mrem/yr to the Skin b. lodines,&

particulates, half-lives.>8 days:,, Site Release Rate: 1500 mrem/yr to Any Organ c. Liquid effluents:

I Site Release Concentration:

10 times 10 CFR 20 Appendix B, Table 2, EC's[3. Average Energy (Not Applicable To'The BVPS ODCM) .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 I I I radionuclide composition are as follows: a. Fissionand activation gases: Ge Gamma Spectrometry, Liquid Scintillation Counter b___odines:

Ge Gamma Spectrometry

c. Particulates, half-lives

> 8 days : Ge Gamma Spectrometry, Proportional Counter d.,Liquideffluents:, Ge Gamma Spectrometry, Proportional Counter, Liquid Scintillation

... 11st 2nd 3rd 4th Calendar 5. Batch & Abnormal Release Information Unit , Quarter Quarter Quarter Quarter Year a. Liquid Batch Releases .....1. Number of batch releases.

36 47 62 39 184 2. Total- time.period for batch releases minutes 11413 14433 17677 15577 59100 3. Maximum time period fora batch release minutes 1050 945 958 1020 1050 4. Average. time period for batch releases minutes. 317 307 285 399 321 5. Minimum time period for a batch release" minutes: 83 77 5 2 2 6. Average river flow during release periods, cuft/sec]

52550 40200 21000 30700 36113 b. Gaseous Batch Releases 1. Number of batch releases ____... 10 23 9 18 60 2. Total time period for batch releases -minutes 4615 19931 478 58574 83598 3. Maximum,time period for a batch release minutes, 763 7422 211 4592 7422 4. Average time period for~batch r.eleases, minutes' 462 867 53 3254 1393 5. Minimum time peiiod for.a batch releasei minutes 53 1 100 0.2 0.2",c. Abnormal Liquid Releases.]*

1.,Number of releases .NONE NONE NONE NONE NONE 2. Total activity released Curies 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 d. Abnormal Gaseous Releases 1. Number of releases , NONE NONE NONE NONE NONE 2. Total activity released Curies 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 I I I I I U I I I I I Form 1/2-ENV-01.05.FO1 (page 19 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2009 Table 1A Gaseous Effluents

-Summation Of All Releases RTL # A9.690E Enclosure 2, Page 2 of 21 Unit Quarter Quarter Quarter Quarter Year ,A lislon i & Activation Gases 1,,. _,siteTotal release .i 0.O0E+00 2.43E+00 0.OOE+00 4.96E+00 7.40E+00 26.5%]la Unit 1, Gases i 0.00E4-00 2.39E+00 0.00E+00 4.96E+00 7.35E+00 lb Unlt2 Gases , ".. Ci. 0.OOE+00 4.86E-02 0.00E+00 4.57E-03 5.31 E-02 2 Average ele re f. pe"iod '*1uCi/sec 0.00E+00 3.09E-01 0.00E+00 6.30E-01 2.35E-01 j Percbnt of. ppiicabl liriti _____ N/A N/A N/A N/A N/A 1 SiteTotaiodne

-31 G i 0.OOE+00 1.27E-07 6.52E-07 2.26E-07 1.01 E-06 28.3%1 l,:a. Lunit , Ci 0.00E+00 6.35E-08 0.OOE+00 1.13E-07 1.77E-07 bi ,Unitr2jidine-131__

... Ci 0.OOE+00 6.35E-08 6.52E-07 1.13E-07 8.29E-07 2 Average lease-rate foperiod UC-/sec 0.00E+00 1.61 E-08 8.27E-08 2.87E-08 3.19E-08 3 Percent 6f, appliCable -limit / N/A N/A N/A N/A' N/A'CParticulates 1' Par'ticulates Wit ih alf-lives r ays "Ci 0.00E+00 2.28E-04 0.OOE+00 8.12E-05 3.09E-04 30.0%1 ia. Unfit iPArticulates, Ci 0.00E+00 2.28E-04 0.00E+00 0.00E+00 2.28E-04 ,lb , UnJt-2Pntiiculates " Ci 0.OOE+00 0.OOE+00 0.00E+00 8.12E-05 8.12E-05 2 ,Avierage release ratefor period.' o uCisec 0.00E+00 2.90E-05 0.00E+00 1.03E-05 9.82E-06 3 P,,ýierc of.applicable limit .No N/A N/A N/A N/A N/A Di GroIss Alpha.1 Site, Gross alpha radioactivity Ci 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 30.0%-'Unit 1 Gross alpha Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 lb Unt2 GOssalpha

-.i 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 rate for'peri6d uCi/sec 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 3 Percent of'Eipplicable imit. -% N/A N/A N/A N/A N/A E. Tritiumr--it-'o r-eeas- Cr i 3.33E+00 11.47E+00 5.31E+00 2.12E+00I 1.22E+011 32.9%_ la. unit 1_Tritium,-.,.

Ci .I 2.23E+00 I 1.22E+00 14.31 E+00 I 1.44E+00 9.20E+00 i L, .b.-,UUnit2.Tritium

.C. : 1.10E+00 2.53E-01 1.OOE+00 6.80E-01 3.03E+00 2 v-.e-,re-ia bei' 4.23E-01 1.87-01 6.74E-01 2.69E-01 3.88E-01"1:- imit,ý .... ,I'41 $: N/A N/A N/A N/A N/A N/A = Not Applicable The amount of time (in seconds) used to calculate 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).

Form 1/2-ENV-01.05.FO1 (page 20 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Repori Calendar Year -2009 Table 1B-EB Gaseous Effluents

-Elevated Batch Releases RTL # A9.690E Enclosure 2, Page 3 of 21 I I I: -, 1s .2nd 3rd Mh I'b Nuclides released n t Quarter Quarter Quarter Quarter Year 1. Fission gases argon-41' ci LLD 1.87E-04 LLD LLD 1.87E-04 krypton-85 0Ci LLD LLD LLD LLD LLD krypton-85r.

Cil LLD 4.82E-05 LLD LLD 4.82E-05 krypton.87...

.i LLD LLD LLD LLD LLD kryptop-88

.. .r LLD LLD LLD LLD LLD xenon-131m

.i LLD LLD LLD LLD LLD xenon-133

.ii LLD 6.97E-02 LLD LLD 6.97E-02 xenon-1 33m qiv LLD 8.38E-04 LLD LLD 8.38E-04 xenon-135', ci LLD 6.21E-03 LLD LLD 6.21E-03 xenon-1 35m Ci LLD 5.43E-04 LLD LLD 5.43E-04 xenon-i38 Ci LLD LLD LLD LLD LLD unidentified

-ci NONE NONE NONE NONE NONE Total for period Ci".-I ND 7.75E-02 ND ND 7.75E-02 I I I I I 2. lodines I iodine-i131 Ci J LLD LLD LLD LLD LLD!odine7133 Ci " LLD LLD LLD LLD LLD iodine-i135 .Ci .LLD LLD LLD LLD LLD I I Ttalfo Period , I : ND ND ND ND ND.3. Particulates chromtum-51i Ci LLD LLD LLD LLD LLD nmanganese-54

._i LLD LLD LLD LLD LLD.iron5.9 Ci LLD LLD LLD LLD LLD cobalt 7 57 .. LLD LLD LLD LLD LLD cobalt-58

'i. LLD LLD LLD LLD LLD cobalt-60 .C LLD LLD LLD LLD LLD"znc65 .i .LLD LLD LLD LLD LLD-Zibrconait.niob-im95

'Ci LLD LLD LLD LLD LLD.Ltonium-89 Ci LLD LLD. LLD LLD LLD istrontium-90

"` .....Ci LLD LLD LLD LLD LLD.rn0ybdenum9

..i ,LLD LLD LLD LLD LLD sn.ium-34

.i 'LLD LLD LLD LLD LLD i LLD LLD LLD LLD LLD baium-/lanthanum-i140, C' LLD LLD LLD LLD LLD-erium-i,41 , ci LLD LLD LLD LLD LLD cerium-i-44

' .LLD LLD LLD LLD LLD.:.unidentified, "i. NONE NONE NONE NONE NONE TOtafWr Period d : i NDD ND ND ND ND I I I I I I I I LLD = Below the Lower Limit of Detectability, in uCi/cc (Table 4).ND None Detected Form 1/2-ENV-01.05.FO1 (page 21 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Repori Calendar Year -2009 Table 1B-EC Gaseous Effluents

-Elevated Continuous Releases RTL # A9.690E Enclosure 2, Page 4 of 21 I.: st 2hnd , 3ld 4th ICalen~dar,[ 'Nucl1ides4el'e se'd A~i~jQuarter Qiuarteir Quarter' Quarter ýWYi~r`1. Fission gases..argon,41 .'" C LLD LLD LLD LLD LLD". ryp; o .85Ciqi LLD LLD LLD LLD LLD kryp.o. n Iz,'C., LLD LLD LLD LLD LLD, , .LLD LLD LLD LLD LLD,i' LLD LLD LLD LLD LLD Xe'o' !': -.,. Cic LLD LLD LLD LLD LLD SCi,; LLD 1.96E-02 LLD LLD 1.96E-02'xe~noDn.138.

,, C, LLD LLD LLD LLD LLD xenc, nLL5D__ _____ LLD LLD LLD LLD xnPfi LLD LLD LLD LLD LLD 4enn- LLD' I LLD LLD LLD LLD.nn .NONE NONE NONE NONE NONE t... ;.fqorpr°od

-d -i ND 1.96E-02 ND ND 1.96E-02 2.1 Iodines 1$ " io'dine-131_

-Ci LLD 1.27E-07 LLD 2.26E-07 3.53E-07.iodinre7133, -C.i, LLD LLD LLD LLD LLD

-Ci' LLD LLD LLD LLD LLD ToI for pro f 'i ND 1.27E-07 NDr -2.26E-07 3.53E-07 3. Particulates I h'm9i-f51

.Ci,., LLD LLD LLD LLD LLD.m'anganesi54.CiI.

LLD LLD LLD LLD LLD'iriM-5. 75C,,9 LLD LLD LLD LLD LLD co.bJt-57

.I Ci LLD LLD LLD LLD LLD.. q ,, ,C LLD LLD LLD LLD LLD.c.obalt-60 Ci LLD LLD LLD LLD LLD zroum5 Ci; 6 LLD LLD LLD LLD LLD ,ir i .-bium ,:, ! Ci, ,, .LLD LLD LLD LLD LLD..Oye 9,. Ci. LLD LLD LLD LLD LLD.sftoinit 4.2h C... .. G LLD LLD LLD LLD LLD c iesum 3 ... ""', Ci-.' 'LLD LLD LLD LLD LLD ceui~j? i LL LLD LLD LLD LLD ,i.ib l.1n.th.nmu

i. LLD LLD LLD LLD LLD b64rii~~i~u-0 ui LLD LLD LLD LLD LLD ,er!m-14,1, .. ,c,. .LLD LLD LLD LLD LLD erium.44., ,. , i, LLD LLD LLD LLD LLD I ýdi. Ci NONE NONE NONE NONE NONE I A perod ,. .i ND ND ND ND ND LLD = Below the Lower Limit of Detectability, in uCi/cc (Table 4).ND = None Detected Form 1/2-ENV-01.05.FO1 (page 22 of 38), Rev 2 Beaver Valley Power Station -Unit 1 RTL # A9.690E Enclosure 2, Page 5 of 21 I I I Radioactive Effluent Release Report Calendar Year -2009 Table 1C-GB1 Gaseous Effluents

-Ground Level Batch Releases (Unit 1)Ist 2nd 3rd 4th Calendar Nuclides released Unit Quarter Quarter Quarter Quarter 1 Year" 1., Fission gases argon-41 Ci LLD LLD LLD LLD LLD krypton-85 Ci LLD LLD LLD LLD LLD krypton-85m Ci LLD LLD LLD LLD LLD krypton-87 CiC LLD LLD LLD LLD LLD krypton-88 Ci LLD LLD LLD LLD LLD xenon-1 31m Ci LLD LLD LLD LLD LLD xenon-133.

Ci. LLD 2.67E-02 LLD LLD 2.67E-02 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-1-38 Ci LLD LLD LLD LLD LLD unentified Ci NONE NONE NONE NONE NONE Total for period ( Ci ND 2.67E-02 ND ND 2.67E-02 I I I I I 2. lodines I I iodine-131UCi LLD LLD LLD LLD LLD iodine-133' Ci, LLD LLD LLD LLD LLD iodine-135 Ci LLD LLD LLD LLD LLD I Total for period Ci ND ND ND ND ND'3. Particulates chromium-51 Ci LLD LLD LLD LLD LLD manganese-54 Ci LLD LLD LLD LLD LLD iron-59 Ci LLD LLD LLD LLD LLD cobalt:57 Ci LLD LLD LLD LLD LLD cobalt-58 Ci LLD 9.17E-06 LLD LLD 9.17E-06 cobalt-60 Ci LLD 6.11 E-07 LLD LLD 6.11 E-07*zinc-6.5 Ci LLD LLD LLD LLD LLD zircon iurm/!nio biu m-95 Ci' LLD LLD LLD LLD LLD strontium-89 Ci LLD LLD LLD LLD LLD strontium-90 Ci LLD LLD LLD LLD LLD molybdenum-99 Ci LLD LLD LLD LLD LLD cesium-134 Ci LLD LLD LLD LLD LLD cesium-137 Ci LLD 6.11 E-07 LLD LLD 6.11 E-07 bariur/llanthanum-140 Ci LLD LLD LLD LLD LLD cerium-141 Ci LLD LLD LLD LLD LLD cerium-i44 pCi LLD LLD LLD LLD LLD unidentified Ci NONE NONE NONE NONE NONE Ttal for, period' Ci" ND 1.04E-05 ND ND 1.04E-05 I I I I I I I I LLD = Below the Lower Limit of Detectability, in uCi/cc (Table 4).ND = None Detected

  • Form 1/2-ENV-01.05.F01 (page 23 of 38), Rev 2 Beaver Valley Power Station -Unit 1 i Radioactive Effluent Release Reporl Calendar Year -2009 Table IC-GO1 Gaseous Effluents

-Ground Level Continuous Releases (Unit 1)RTL # A9.690E Enclosure 2, Page 6 of 21 1st 1 2nd did 4th enCalendar~i Nu6l -Unit Quarter Quarter Quarter .-,,,-.h 1. Fission gases I..... j- ' .. i !LLD 2.31E+00 LLD 4.96E+00 7.27E+00..iryp~n85 ..... LLD LLD LLD LLD LLD Ik ' LLD LLD LLD LLD LLD_______________

Ci LLD LLD LLD LLD LLD x! n LLD LLD LLD LLD LLDýR ronr 3 LLD LLD LLD LLD LLD 71'xenon-135

, _____ LLD LLD LLD LLD LLD~ ~~-~ _LD LLD LLD LLD LLD kenonz1_35ý 1-,i LL LLD LLD LLD LLD-_____________

Cii -LLD LLD LLD LLDLD* xAenon-138'.", Ci LLD LLD LLD LLD LLD_ _unidentifeid[

'Ci NONE NONE NONE NONE NONE SJotalfker.od I '.-.i ND 2.31E+00 ND 4.96E+00 7.27E+00 2.1lodines , iodiejl.!J31 .i LLDLD LLD LLD LLD.Ci LLD LLD LLD LLD LLD, 'i *i LLD LLD LLD LLD LLD.tlfor ep&iod, Ci ND ND ND ND [ ND-3.,-Particulates"

., .i LLD LLD LLD LLD LLD ppaganesge:5,4, C411 LLD LLD LLD LLD LLD yoni,, LLD LLD LLD LLD LLD_ Ci LLD LLD LLD LLD LLD 3 Ci', LLD 2.02E-04 LLD LLD 2,02E-04-Ci ,, LLD 1.25E-05 LLD LLD 1.25E-05 zinC65,, LLD LLD LLD LLD LLD....rqj:n.obi~um 5, , i LLD 3.35E-06 LLD LLD 3.35E-06........ ........ C LLD LLD LLD LLD LLD 1'tri~iin T O _C LLD LLD LLD LLD LLD..Ci LLD LLD LLD LLD LLD______esiu____134________

4i. LLD LLD LLD LLD LLD_ _ _C..Gi. .LLD LLD LLD LLD LLD'.obFariubmJIatianum-1.O Ci -LLD LLD. LLD LLD LLD , Ci LLD LLD LLD LLD LLD.: LLD.. L rm

  • LLD LLD LLD LLD LLD u~nidentif C..i NONE NONE NONE NONE NONE-Ttal for period Ci ND 2.18E-04 ND ND 2.18E-04 LLD = Below the Lower Limit of Detectability, in uCi/cc (Table 4).ND = None Detected Form 1/2-ENV-01.05.FO1 (page 24 of 38), Rev 2 Beaver Valley Power Station -Unit 2 RTL # A9.690E Enclosure 2, Page 7 of 21 Radioactive Effluent Release Repori Calendar Year -2009 Table 1C-GB2 Gaseous Effluents

-Ground Level Batch Releases (Unit 2)I I I 1 st 2nd 3rd 4th Calendar Nuclides released Unit Quarter Quarter Quarter Quarter Year 1..Fission gases.,argon-41 Ci, LLD LLD LLD 5.84E-04 5.84E-04 krypton-85 , ci LLD LLD LLD LLD LLD krypton-85m Ci LLD LLD LLD 2.40E-05 2.40E-05 krypton-87 Ci LLD LLD LLD LLD LLD krypton-88 Ci LLD LLD LLD LLD LLD xenon-1 31m .Ci LLD LLD LLD LLD LLD xenon-1 33 Ci LLD LLD LLD 2.47E-03 2.47E-03.xenon-1 33m Ci LLD LLD LLD LLD LLD xenon-135

.Ci LLD LLD LLD 1.33E-03 1.33E-03 xenon-l,35m Ci LLD LLD LLD 1.60E-04 1.60E-04 xenon-138 1 Ci. LLD LLD LLD LLD LLD*unidentified

.Ci* NONE NONE NONE NONE NONE Total for period J Ci ND ND ND 4.57E-03 4.57E-03 I I I U I 2. lodines R iodine-131 Ci LLD LLD LLD LLD LLD ioline-133 Ci LLD LLD LLD LLD LLD iodine-1356 Ci J LLD LLD LLD LLD LLD I I L Total for period I C.] ND ND ND ND ND 3. Particulates chromium-51 Ci LLD LLD LLD LLD LLD manganese-54 Ci LLD LLD LLD LLD LLD iron-59 Ci LLD LLD LLD LLD LLD cobalt-57 CJ LLD LLD LLD LLD LLD cobalt-58 Ci LLD LLD LLD 9.17E-06 9.17E-06 cobalt-60 Ci LLD LLD LLD 6.11E-07 6.11E-07 zinc-65 Ci LLD LLD LLD LLD LLD zirconium/niobium-95 Ci LLD LLD LLD LLD LLD strontium-89 Ci LLD LLD LLD LLD LLD strontium-90 Ci LLD LLD LLD LLD LLD molybdenum-99 Ci LLD LLD LLD LLD LLD cesium-134 Ci LLD LLD LLD LLD LLD cesium-137 Ci- LLD LLD LLD 6.11E-07 6.11E-07 barium/lanthanum-i140.

Ci. LLD LLD LLD LLD LLD cerium- o4. Ci LLD LLD LLD LLD LLD cerium-i4,4 Ci LLD LLD LLD LLD LLD unidentified

' Ci NONE NONE NONE NONE NONE Total for period Pi ND ND ND 1.04E-05 1.04E-05 I I I I I I I I LLD = Below the Lower Limit of Detectability, in uCi/cc (Table 4).ND = None Detected Form 1/2-ENV-01.05.FO1 (page 25 of 38), Rev 2 Beaver Valley Power Station -Unit 2 Radioactive Effluent Release Repori Calendar Year -2009 Table 1C-GC2 Gaseous Effluents

-Ground Level Continuous Releases (Unit 2)RTL # A9.690E Enclosure 2, Page 8 of 21 It I '21ýd' 3rd" 4th' Gal61endarl N661ides rle~dýs unit d uuart ir arter rte ~ ureear 1' sin gqses a.. ci LLD LLD LLD LLD LLD Ci LLD LLD LLD LLD LLD Vr , MMQ% :> LLD LLD LLD LLD LLD S iiC , LLD LLD LLD LLD LLD i e~ryptn8 F LLD LLD LLD LLD LLD_JM ( LLD LLD LLD LLD LLD , i LLD LLD LLD LLD LLD____- K LLD LLD LLD LLD LLD-.ýxeon-135 17 LLD LLD LLD LLD LLD qnonajlL ..LLD LLD LLD LLD LLD:enon cl. C LLD LLD LLD LLD LLD'qn et~ifid "' NONE NONE NONE NONE NONE peidb ND ND ND ND ND C il , LLD LLD 6.52E-07 LLD 6.52E-07 ,' ý" i' LLD LLD LLD LLD LLD"img47n 5 ""d i,. LLD LLD LLD LLD LLD joa *~ofar period 6i ND ND (6.52E-07

[ ND J6.52E-07 3~Partictilates

-ouT: i9;rn'-' C, :LLD LLD LLD LLD LLD ,i' j LLD LLD LLD LLD irn.. .. ..LLD LLD LLD LLD LLD cobat;:,:

.6WC ' LLD LLD LLD LLD LLD.
" "i'" i LLD LDLLD LD -05 6.16E-05 obl-0 LLD LLD LLD 9.23E-06 9.23E-06 zi=CU-6 ' "LLD LLD LLD LLD LLD urn 9 CJ .. 6 LLD LLD LLD LLD LLD.__n__ 4i LLD LLD LLD LLD LLD.....r l ,LLD LLD LLD LLD LLD:1ý6iyo~de~9 L LLD LLD LLD LLD siuffi3l4.

C LLD LLD LLD LLD LLD ituern'4_

'- LLD LLD LLD LLD LLD)aium/Iaq-ithnr-14O C- LL LLD LLD LLD LLD cerium- :14.1. L LLD LLD LLD LLD qce-rIu~j4., LLD LLD LLD LDLLD-de*'un Qdnicv r.NONE NONE NONE NONE NONE Total fo-r period k i ND 7.08E-05 7.08E-05 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 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2009 Table 2A Liquid Effluents

-Summation Of All Releases RTL # A9.690E Enclosure 2, Page 9 of 21 I I'I 1st 2nid 3rd. 4th, "Cienda'r Total, Unit QuarteMaer Quarter Quarter Year- 'Error, 9c A. Fission & activation products 1. Total relea6se(excl.,H-3, gas & alpha) ci. 3.72E-02 3.56E-02 4.26E-02 1.05E-01 2.20E-01 26.1%2. AveaQe diluted concentrationm uC iml 4.42E-08 2.97E-08 2.15E-08 8.81E-08 4.23E-08 3. Percent of applicable limit % 1.49E+00 1.42E+00 1.70E+00 4.18E+00 2.20E+00 B. Tritium 1. Total release" Ci 4.15E+02 4.46E+02 3.71E+02 3.55E+02 1.59E+03 25.0%1 2. Average diluted concentration uCi/mIl 4.93E-04 3.72E-04 1.88E-04 2.99E-04 3.05E-04 3. Percent of applicable limit _____4.93E+00 3.72E+00 1.88E+00 2.99E+00 3.05E+00 C. Dissolved and entrainedgases

1. Total release Ci ND 1.98E-06 ND 4.24E-05 4.44E-05 27.0%1 2. Averagediluted concentratiorn uCi/ml 1.65E-12 3.57E-11 8.52E-12 3i Perce'ntiof applicable limit % ___%____8.26E-07 1.79E-05 4.26E-06 I I I I I I I D. Gross,alpha.

radioactivity (total release)Ci LLD LLD LLD LLD LLD 28.9%I E Volume of waste released liters 1.82E+06 2.31 E+06 3.09E+06 2.1 OE+06 9.32E+06 11.2%(prior to dilution)I F. Volume of dilution water used liters 8.40E+08 1.20E+09 1.98E+09 1.18E+09 f 5.20E+09 22.9% I I LLD = Below the Lower Limit of Detectability, in uCi/ml (Table 4)A.3 is based on a historical PA-DEP guide of 10 Ci/yr B.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 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 1 E+1 0 liters for BVPS-1 & 2 (ie.; -22,800 gpm is the total dilution flowrate from the site)I I I I ,I I Form 1/2-ENV-01.05.FO1 (page 27 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 I Radioactive Effluent Release Report Calendar Year -2009 Table 2B-B Liquid Effluents

-Batch Releases RTL # A9.690E Enclosure 2, Page 10 of 21*Nuclides released 1 st 2nd 3rd 4th Calendar Unit Quarter Quarter Quarter Quarter Year I 1. Fission and activation products , bryllium-7 Ci LLD LLD LLD LLD LLD sodium-24

.. Ci LLD LLD LLD LLD LLD". .. Ci 5.09E-04 LLD LLD 2.26E-03 2.77E-03 manganese-54 Ci 5.44E-04 5.38E-05 LLD 8.36E-04 1.43E-03 Jron-55 Ci 6.75E-03 1.66E-03 2.99E-03 1.29E-02 2.43E-02 iroA-59 Ci LLD LLD LLD 4.12E-04 4.12E-04 cOb'alt-57 Ci 3.64E-05 1.67E-05 7.51E-05 ' 2.81E-04 4.10E-04 cobalt_58 .i 2.87E-03 8.51 E-03 2.18E-02 7.07E-02 1.04E-01 cobaltA6o Ci 2.40E-03 5.49E-03 4.64E-03 7.56E-03 2.01 E-02 zinr-d65 Ci 9.44E-04 2.13E-03 7.57E-04 LLD 3.83E-03 strontium-_89

.ci LLD LLD LLD LLD LLD strontium'-:90 Ci LLD 1.30E-04 LLD LLD 1.30E-04 zizr l.dniurmniobium-95 Ci LLD 1.46E-05 LLD 2.15E-04 2.30E-04 zirconiumn/riiobium-97 " " Ci LLD 7.25E-06 4.08E-06 LLD 1.13E-05 rnomybdenum-99/teChnetium-99m Ci LLD 3.80E-06 LLD LLD 3.80E-06 tin,113 C-i LLD LLD LLD LLD LLD silver-110m.

Ci 1.64E-04 2.29E-04 5.05E-04 2.71E-03 3.61 E-03 antirmony-122 Ci LLD LLD LLD 3.16E-04 3.16E-04 antimony-124 Ci LLD 6.65E-04 5.83E-04 1.65E-03 2.90E-03 antimony-125 Ci 2.22E-02 1.592-02 1.09E-02 4.45E-03 5.35E-02* ' "Jiodine 7 1311 Ci LLD 2.70E-05 3.46E-05 LLD 6.17E-05 i0'die.133.

ci LLD 4.20E-05 8.14E-05 LLD 1.23E-04 cesiurnr134 Ci LLD LLD LLD LLD LLD-_cesiurn-137 ci 7.97E-04 6.92E-04 2.28E-04 2.98E-04 2.02E-03 bariumnlanthanumn-140 Ci LLD LLD LLD LLD LLD ceriurn,1,41 Ci LLD LLD LLD LLD LLD cerium-1 44- Ci LLD LLD LLD LLD LLD unidentified j Ci NONE NONE NONE NONE NONE period , " Ci 3.72E-02 3.56E-02 4.26E-02 1.052-01 2.20E-01 2. ,Di ssolved and entrained~gases kryptoqn85-Ci LLD LLD LLD LLD LLD xenon-133 Ci LLD LLD LLD 4.24E-05 4.24E-05 xenon-1-33mr Ci LLD LLD LLD LLD LLD , xen6nr135 .Ci LLD 1.98E-06 LLD LLD 1.98E-06 unidentified CiI NONE NONE NONE NONE NONE' Total for period ..... , : C "i IND 1.98E-06 ND 4.242-05 4.442-05 LLD = Below the Lower Limit of Detectability, in uCi/ml (Table 4)

Form 1/2-ENV-01.05.FO0 (page 28 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Repori Calendar Year -2009 Table 2B-C Liquid Effluents

-Continuous Releases RTL # A9.690E Enclosure 2, Page 11 of 21 I I I Nuclides released i1st 2nd 3rd 4th Calendar Unit Quarter Quarter Quarter Quarter Year 1 1. Fission and activation products!beryllium-7 Ci N/A N/A N/A N/A N/A sodium-24 Ci N/A N/A N/A N/A N/A chromium-51 Cil N/A N/A N/A N/A N/A manganese-54 Ci N/A N/A N/A N/A 'N/A iron-55 Ci N/A N/A N/A N/A N/A irdn-59 Ci N/A N/A N/A N/A N/A cobalt-57 Ci N/A N/A N/A N/A N/A cobalt-58 Ci N/A N/A N/A N/A N/A cobalt-60 Ci N/A N/A N/A N/A N/A zinc-65 Ci N/A N/A N/A N/A N/A strontium-89 Ci N/A N/A N/A N/A N/A strontium-90

'Ci N/A N/A N/A N/A N/A zirconium/niobium-95 mi N/A N/A N/A N/A N/A z irconium/niobium Ci, N/A N/A N/A N/A N/A molybdenum-99 -Ci N/A N/A N/A N/A N/A technetium-99m Ci N/A N/A N/A N/A N/A ruthenium-103 Ci N/A N/A N/A N/A N/A silver-110m Ci N/A N/A N/A N/A N/A antimony-1 24 Ci N/A N/A N/A N/A N/A antimony-125 Ci N/A N/A N/A N/A N/A iodine-131 Ci N/A N/A N/A N/A N/A iodinCe-133 Ci N/A N/A N/A N/A N/A cesium-134 Ciý N/A N/A N/A N/A N/A cesium-137

,, N/A N/A N/A N/A N/A b CiL N/A N/A N/A N/A N/A cerium-141 Ci. N/A N/A N/A N/A N/A cerium-l44 Ci N/A N/A N/A N/A N/A unidentified Ci'- N/A N/A N/A N/A N/A Total for period " Ci N/A N/A N/A N/A N/A 2. Dissolved and entrained gases argon-41 ,Ciý, N/A N/A N/A N/A N/A xenon-1 33 Cij, N/A N/A N/A N/A N/A xenon-i33m Ci N/A N/A N/A N/A N/A xenon-1i35 CiT' N/A N/A N/A N/A N/A unidentified, Cii N/A N/A N/A N/A N/A Totalfor period Ci:. N/A N/A N/A N/A N/A I I I I I I I I I I I I I I I N/A = Not Applicable (liquids not discharged in a continuous mode during this period)

Form 1/2-ENV-01.05.F01 (page 29 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2009 Table 3A Solid Waste And Irradiated Fuel Shipments (Part 1 of 3)RTL # A9.690E Enclosure 2, Page 12 of 21 A. Solid Waste Shipped Offsite For Burial Or Disposal.(Not irradiated fuel) .__ _______1. Type of Waste (Spent resins, Filter Estimated Sludges, Evaporator Bottoms, Oil) 1.lst Half 2nrd Half Total Error a. Volume Shipped. 2.15E+00 m3 2.24E+00 m3 0.0% (1)b. Volume Buried 2.15E+00 m3 2.24E+00 m3 0.0% (1)c. TotalActivity 2.59E+00 Ci 1.20E+01 Ci 30.0%2. Estimate of Major Nuclide Composition by Type of Waste OnThis Table.(.2)

Percent(%), Percent (%)Hr3 12.30 % 0.46 %-C1 4 2.99 % 2.52 %,Mn-54 0.52 % 5.10 %.Fe5 .12.30 % 29.80 %'Co-58 6.68 % 0.64 %Co,60 13.90 % 20.10 %INii-59 0.24 % 0.32 %ANi-63 22.70 % ,39.50 %.Zn-65 10.65 % 0.00 %S'b-125 1.64 % 0.54 %C s-134 0.54 % 0.05 %0s-137 14.80 % 0.44 %Ce-i 44/Pr-1 44 0.01 % 0.00 %Pu-238 0.00 % 0.00 %PU-241 0.11 % 0.01 %3. Number of Shipments 1 a..Type LSA 1 1 of Type.A. 0 0 Container Type B 0 0 Used LargeQuahtity 0 0 b. ,Solidification Cement 0 0 Agent Urea Formaldehyde 0 0.Used None 1 1 c. Mode of Truck 1 1:Transport Rail 0 0 d. Final .,rvwin TNV, 0 0 Destinatidon Oak Ridge,;TN

-1 1 e. Waste" elasiA .. 1 1 Class *- lass 0 0 per, tlassC _' 0 0 10CFRPart61, ClassC .0 0 (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 Form 1/2-ENV-01.05.F01 (page 30 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2009 Table 3B Solid Waste And Irradiated Fuel Shipments (Part 2 of 3)RTL # A9.690E Enclosure 2, Page 13 of 21 I I A. Solid Waste Shipped Offsite For Burial Or Disposal (Not irradiated fuel 1. type of Waste (Dry Compressible Waste, Estimated Contaminated Equipment, etc.). .1st Half 2nd Half Total Error a. Volume Shipped .6.11E+02 m3 7.11E+02 m3 0.0% (1)b. Volume Buried .-. .9.70E+01 m3 2.73E+02 m3 0.0% (1)c. Total Activity .-4.53E-01 Ci 3.51E-01 Ci 30.0%I I I I 2. Estimate of Major Nuclide Comp6sition by Type of Waste On This Table '(2)Percent'(%)-.Percent (%)H-3 0.84 % 2.29 %C-14 .0.44 % 1.47 %.Cr51 1.68 % 0.00 %Mn-54 0.03 % 0.91 %l.e-55 -" 19.50 % 44.00 %Co0-58 2.67 % 3.06 %.C.-60 -15.70 % 19.70 %Ni-59. ...... 0.18 % 0.38 %Ni-63 13.60 % 22.10 %Sr-90 0.14 % 0.06 %Nb-95 0.61 % 0.22 %Zr-95 0.31 % 0.00 %Tc-ý99 .0.11 % 0.00 %Ag- ..m 1 ..0.67 % 0.03 %Sb-124 " 0.00 % 0.00 %Sb-125 1.98 % 3.00 %1-129 0.08 % 0.01 %Cs-1 34 0.00 % 0.12%Cs-137 36.30 % 1.81 %Ce-144/Pr-144 0.00 % 0.00 %Pu-241 0.24 % 0.20 %3. Number of Shipments 12 a. Type LSA 10 12 of f TypeA. 0 0 Container Type B.. 0 0 Used .Large Quantity 0 0 b. Solidification

.Cement 0 0 Agent Urea Formnldehyde 0 0 Used None .., ... ..... 10 12 c.-Modeof Truck- " 10 12 transport

-.Rail 0 0__Other_ _1' -0 0 d. Final Oak Ridge,',TN 10 12 DestinatiOn , .wampum, .,, 0 0 e. Waste , ...ClassA A ."J 10 12 Class' ClassB K 0 0 per [- .: ClassC, ._ 0 0 10. CFRPart61

.>Class.C .0 0 I I I I I I I I I I I I 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.

Form 1/2-ENV-01.05.FO1 (page 31 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2009 Table 3C Solid Waste And Irradiated Fuel Shipments (Part 3 of 3)RTL # A9.690E Enclosure 2, Page 14 of 21 A. Solid Waste Shipped Offsite For Burial Or Disposal (Not irradiated fui)1. Type, of Waste (Irradiated.components, Estimat-ed" iontroIRods, etc) 1st Half 2nd Half. Totali Error,.a.. Volume Shipped .. 0.00E+00 m3 0.00E+00 m3 0.0% (1)-,!b Volume Buried O.OOE+00 m3 O.OOE+00 m3 0.0% (1)'c. Total Activity 0.OOE+00 Ci 0.OOE+00 Ci 0.0%2. E stimatb of Major Nuclide Composition by Type of Waste On, This Table (2)Percent (%)Percent (%)3. Number of Shipments.

.0 a. Type LSA 0 0 of -Type A 0 0 Container Type B 0 0 j -. -Used Large Quantity 0 0 b. Solidification Cement 0 0 Agent Urea Formaldehyde 0 0 Used '.None 0 0 c. Mode of Truck 0 0 ,Transport Rail 0 0.Other 0 0 d.':Final

.Barnwell, SC 0 0 Destination Qak'Ridge, TN. 0 0 e. Waste -Class`-A" 0 0 Class 0lass B1 0 0 per Class C' 0 0 10 CFR Part 61 > >ClassC 0 0 B. No' Irradiated Fuel Shipments (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.

Form 1/2-ENV-01.05.FO1 (page 32 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2009 Table 4 Lower Limits Of Detectability (LLD)RTL # A9.690E Enclosure 2, Page 15 of 21 RWDA-G 1000 cc Gas Grab Sample (3) ODCM Calculated Required Nuclide LLD LLD (uCi/cc) (uCi/cc)H-3 (4) 1.00E-06 1 E-06 Na-24 1,86E-08 1 E-04 Ar-41 5.61E-08 1 E-04 Cr-51 3.74E-07 1E-04 Mn-84 9.93E-08 1 E-04 Fe-,55 .............

Feý59 1.70E-07 1 E-04 Co-57 2.38E-08 1 E-04 Co-58 5.20E-08 1 E-04 Co-60 7.20E-08 1 E-04 Zn-65 8.46E-08 1 E-04 Kr-85 1.63E-05 1E-04 Kr-85m 3.17E-08 1 E-04 Kr-87 8.08E-08 1 E-04 Kr-88 8.06E-08 1 E-04 Sr-89 .....Sr-90 ...O.Sr-92 2.08E-08 1 E-04 Nb-95 4.91E-08 1 E-04 Nb-97 3.05E-08 1 E-04 Zr-95 8.76E-08 1 E-04 Mo-99 3.27E-08 1 E-04 Tc-99m 3.19E-08 1 E-04 Ag-11Om 3.17E-08 1E-04 Sb-124 4.86E-08 1 E-04 Sb-125 1.85E-07 1 E-04 1-131 4.84E-08 1 E-04 1-133 4.83E-08 1 E-04 1-135 1.90E-07 1 E-04 Xe-131m. 1.33E-06 1 E-04 Xe-1 33 5.45E-08 1 E-04 Xe-133m 2.74E-07 1 E-04 Xen135 3.36E-08 1 E-04 Xe-135m 6.60E-08 1 E-04 Xe-137 1.75E-07 1 E-04 Xe-138 1.16E-07 1 E-04 Cs-134 6.92E-08 1 E-04 Cs-137 1.00E-07 1 E-04 Ba-139 1.61 E-07 1 E-04 Ba-140 1.95E-07 1 E-04 La-140 7.17E-08 1 E-04 Ce-141, 5.47E-08 1E-04 ,Ce-144 2.01E-06 1 E-04 Gross Alpha .............

RWDA-L 100.0 ml Liquid Grab Sample (3) ODCM Calculated Required LLD LLD(u i/ml) (uCi/ml)1.O0E-06 1 E-05 4.33E-09 5E-07 1.32E-08 5E-07 1.O0E-07 5E-07 2.38E-08 5E-07 (1) 1.00E-06 1E-06 4.03E-08 5E-07 7.74E-09 5E-07 1.25E-08 5E-07 1.70E-08 5E-07 2.01 E-08 5E-07 4.05E-06 1 E-05 9.81 E-09 1E-05 2.08E-08 1 E-05 2.36E-08 1 E-05 (1) 5.00E-08 5E-08 (1) 5.00E-08 5E-08 4.86E-09 5E-07 1.18E-08 5E-07 7.44E-09 5E-07 2.11E-08 5E-07 1.03E-08 5E-07 1.OOE-08 5E-07 7.73E-09 5E-07 1.19E-08 5E-07 4.71 E-08 5E-07 1.27E-05 1 E-06 1.20E-08 5E-07 4.47E-08 5E-07 4.04E-07 1 E-05 2.04E-08 1 E-05 7.77E-08 1 E-05 9.40E-09 1 E-05 1.64E-08 1E-05 4.42E-08 1 E-05 3.24E-08 1 E-05 1.70E-08 5E-07 2.44E-08 5E-07 4.87E-08 5E-07 4.85E-08 5E-07 1.64E-08 5E-07 1.71 E-08 5E-07 2.03E-07 5E-07 (1) 1.00E-07 1 E-07 Filter Paper /'Charcoal Continuous Effluent Sample (3) ODCM Calculated Required (2) LLD LLD (uCi/cc). (uCi/cc)3.44E-14 1 E-11 6.21E-13 1E-11 6.82E-14 1E-11 1.57E-13 1E-11 2.73E-14 1E-11 2.11E-14 1E-11 2.97E-14 1E-11 1.56E-13 1E-11 (1) 1.00E-13 1E-11 (1) 1.00E-14 1E-11 1.73E-13 1E-11 8.89E-14 1E-11 7.77E-14 1E-11 3.54E-14 1E-11 4.03E-14 1E-11 3.93E-14 1E-11 8.08E-14 1 E-11 5.04E-14 1E-11 3.30E-13 1E-11 4.89E-14 1E-12 6.95E-14 1E-10 3.49E-13 1E-11 1.60E-14 12E-11 6.37E-14 12-11 3.03E-13 1E-11 4.172-14 1E-11 6.262-14 12-11 1.562-13 1E-11 (1) 3.512-15 12-11 I I I I I I I I I I I I I I I I I I I (1) Sample analyses performed by a contractor laboratory.

(2) These LLD calculations contain a default weekly continuous sample volume of 2.85E+8 cc. Therefore, grab sample LLD values reflect a different volume (ie; 10 cuft or 2.83E+5 cc).(3) The calculated LLD's, except those denoted by (1), are from a counter/detector calibration on 06108/09.

These values are typical for other counter/detectors used for effluent counting at BVPS.(4) Based on counting 50 ml of the water that was bubbled through a 20 liter air sample.

Form 1/2-ENV-01.05.F01 (page 33 of 38), Rev 2 Beaver Valley Power Station -Unit 1 RTL # A9.690E Enclosure 2, Page 16 of 21 Radioactive Effluent Release Report Calendar Year -2009 Table 5A Assessment Of Radiation Doses-Unit 1.Liquid ffluents 1sgQarter 2nd Qua'rter_

I3rd Quarter .'4th Qua~rter1 Calendar Year%'of %oof .of rof %0/*'of Batch Dose 00CM Dose 00OCM Dose. ODCM Dose D Dose ODCM ReleaseS Limit Limit Limit. Limfiit , LimiitýBone _ 1.35E-02 0.2700 1.33E-02 0.2660 3.56E-03 0.0712 7.83E-03 0.1566 3.82E-02 0.3819 0 LiVer -4.53E-02 0.9060 2.61E-02 0.5220 9.09E-03 0.1818 1.29E-02 0.2580 9.34E-02 0.9339 R ,ota!.B6dy 1.70E-02 1.1333 1.72E-02 1.1467 6.94E-03 0.4627 1.21E-02 0.8067 5.32E-02 1.7747 G Thyroid 5.37E-03 0.1074 5.51E-03 0.1102 4.02E-03 0.0804 6.49E-03 0.1298 2.14E-02 0.2139'A Kidney 1.25E-02 0.2500 1.41E-02 0.2820 5.91E-03 0.1182 8.52E-03 0.1704 4.10E-02 0.4103 N ...... 7.61E-03 0.1522 7.63E-03 0.1526 4.61E-03 0.0922 7.19E-03 0.1438 2.70E-02 0.2704 (1 ) GHL- 7.77E-03 0.1554 1.23E-02 0.2460 6.62E-03 0.1324 1.40E-02 0.2800 4.07E-02 0.4069 Unit 1 Gaseous Effluents.,_'__ _n_1stQuartner-_, ý2hndQuarter

,3r#dQuarter 4th' ularer Calear-Year Batchi& %of %of % of :of %of'Conitinudus Do;Se ODCM Dose 06)CM' Dose DCMj Dose '0DCM. Dboseo DCM..ls- Limit Limit Liffimt .. Lim~it Limitiwý(), GMW.maAir 0.OOE+00 0.0000 1.08E-01 2.1600 0.OOE+00 0.0000 0.OOE+00 0.0000 1.08E-01 1.0800 (2).Beta .ir 0.OOE+00 0.0000 3.80E-02 0.3800 0.OOE+00 0.0000 0.OOE+00 0.0000 3.80E-02 0.1900 B. '.:On i.i 0.OOE+00 0.0000 4.60E-04 0.0061 0.OOE+00 0.0000 1.19E-10 0.0000 4.60E-04 0.0031 0 Livegr' 3.16E-02 0.4213 2.71E-02 0.3613 1.91E-02 0.2547 5.32E-02 0.7093 1.31 E-01 0.8733 R ,otal B~dy 3.16E-02 0.4213 2.72E-02 0.3627 1.91E-02 0.2547 5.32E-02 0.7093 1.31E-01 0.8740 G' 1 ...3.16E-02 0.4213 2.71E-02 0.3613 1.91 E-02 0.2547 5.32E-02 0.7093 1.31E-01 0.8733 AiKidn.ey

...... 3.16E-02 0.4213 2.71E-02 0.3613 1.91E-02 0.2547 5.32E-02 0.7093 1.31E-01 0.8733 NWLung , .3.16E-02 0.4213 2.78E-02 0.3707 1.91 E-02 0.2547 5.32E-02 0.7093 1.32E-01 0.8780 3.16E-02 0.4213 2.73E-02 0.3640 1.91E-02 0.2547 5.32E-02 0.7093 1.31E&01 0.8747 (1) These doses are listed in mrem; they are calculated for the maximum individual for all batch liquid effluents (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.Limits used for calculation of percent (%) are from ODCM procedure 1/2-ODC-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).

Form 1/2-ENV-011.05.F01 (page 34 of 38), Rev 2 Beaver Valley Power Station -Unit 2 RTL # A9.690E Enclosure 2, Page 17 of 21 Radioactive Effluent Release Report Calendar Year -2009 Table 5B Assessment Of Radiation Doses Unit 2 Liquid Effluents I I I I 1st Quarter 2nd Quarter.3rd Quarter 4th Quarter Calendar Year of/ o / %of % Of % of % of Batch Dose ODOM Dose ,ODCM Dose ODCM Dose ODCM Dose ODCM Releases Limit .._.... Limit Limit Limit Limit.Bone 1.35E-02 0.2700 1.33E-02 0.2660 3.56E-03 0.0712 7.83E-03 0.1566 3.82E-02 0.3819 ,0 Liver 4.53E-02 0.9060 2.61E-02 0.5220 9.09E-03 0.1818 1.29E-02 0.2580 9.34E-02 0.9339 R- Total B.odyl 1.70E-02 1.1333 1,72E-02 1.1467 6.94E-03 0.4627 1.21E-02 0.8067 5.32E-02 1.7747 G Thyroid 5.37E-03 0.1074 5.51E-03 0.1102 4.02E-03 0.0804 6.49E-03 0.1298 2.14E-02 0.2139 A Kidney. 1.25E-02 0.2500 1.41E-02 0.2820 5.91E-03 0.1182 8.52E-03 0.1704 4.1OE-02 0.4103 N Lung 7.61E-03 0.1522 7.63E-03 0.1526 4.61E-03 0.0922 7.19E-03 0.1438 2.70E-02 0.2704 (1).GI-LLi

." 7.77E-03 0.1554 1.23E-02 0.2460 6.62E-03 0.1324 1.40E-02 0.2800 4.07E-02 0.4069 Unit 2 Gaseous Effluents I 1st Quarter _ 2ndQuarter

_J3rd Quarter' 4thQuarter Calendar Year Batch& %of % of %of %of % of Continuous Dose ODCMý Dose ODCM0 Dose ODCM Dose ODCM Dose, ODCM Releases Limit ..Limit Limit- Limit -imit (2)f GammaAir 0.OOE+00 0.0000 7.27E-08 0.0000 1.13E-01 2.2600 5.17E-08 0.0000 1.13E-01 1.1300 (2)' Beta Air 0.OOE+00 0.0000 3.42E-10 0.0000 3.98E-02 0.3980 1.77E-10 0.0000 3.98E-02 0.1990 B0one 0.OOE+00 0.0000 3.OOE-10 0.0000 2.10E-07 0.0000 1.87E-04 0.0025 1.87E-04 0.0012 0 Liver- 2.78E-03 0.0371 1.72E-03 0.0229 3.11E-04 0.0041 1.81E-02 0.2419 2.30E-02 0.1530 R, Total BOdy. 2.78E-03 0.0371 1.72E-03 0.0229 3.11E-04 0.0041 1.81E-02 0.2419 2.30E-02 0.1530 G Thyroid 2.78E-03 0.0371 1.72E-03 0.0229 3.76E-04 0.0050 1.81E-02 0.2413 2.30E-02 0.1532 A , Kidney 2.78E-03 0.0371 1.72E-03 0.0229 3.11E-04 0.0041 1.81E-02 0.2413 2.29E-02 0.1527 N ILung .2.78E-03 0.0371 1.72E-03 0.0229 3.11E-04 0.0041 1.83E-02 0.2440 2.31E-02 0.1541 (3I -LL 2.78E-03 0.0371 1.72E-03 0.0229 3.11E-04 0.0041 1.82E-02 0.2427 2.30E-02 0,1534 I I I I I I I I I I I (1) These doses are listed in mrem; they are calculated for the maximum individual for all batch liquid effluents (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.Limits used for calculation of percent (%) are from ODCM procedure 1/2-ODC-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.FO1 (page 35 of 38), Rev 2 RTL # A9.690E Beaver Valley Power Station -Units 1 & 2 Enclosure 2, Page 18 of 21 Radioactive Effluent Release Reporl Calendar Year -2009 Table 6 Effluent Monitoring Instrumentation Channels Not ReturnedTo Operable Status Within 30 Days[RM-1 DA-1 001 -Unit 1 Auxiliary Feed Pump Bay Drain Monitor On 11/16/08 this monitor was removed from service to perform the eighteen (18) month calibration.

The installed Model 843-32 detector failed calibration requirements, and several attempts to calibrate new detectors (that were located from old stock and other nuclear power plants) were also unsuccessful.

The thirty (30) day criteria was exceeded due to performance of Model 843-32 detectors that are no longer manufactured.

An upgraded detector (Model 843-32R) was purchased (which required an updated calibration geometry) and subsequent changes were made to applicable engineering documents, calculation packages and procedures.

The monitor was calibrated and returned to operable status on 02/05/09.

This condition and associated Corrective Actions are detailed in BVPS Condition Report No. CR 08-50435, CR 08-50765, CR 08-50899, CR 09-52947, CR 09-52964 and BVPS-SAP Order Number 200197646-0700.

As required by ODCM procedure 1/2-ODC-3.03, "Controls for RETS and REMP Programs", (as referenced in procedure Attachment E, Control 3.3.3.9, Table 3.3-12, Action 24), effluent releases via this pathway may continue provided grab samples are analyzed once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. However, SINCE this liquid effluent pathway was diverted to the Tunnel Sump / Liquid Radwaste Treatment System on 11/16/08 (and remained diverted until the monitor was returned to operable status on 02/05/09), THEN there were no liquid releases through this effluent pathway. Therefore, grab sampling was not required.[RM-lVS-109]

Ch-7 & Ch-9 -Unit 1 Auxiliary Building Ventilation System (Ventilation Vent) Noble Gas Activity Monitor On 06/07/09 this monitor was removed from service to perform the eighteen (18) month calibration.

The thirty (30) day criteria was exceeded due to additional work being required during the calibration.

The computer system did not respond as expected and required parts and repair work. The two monitor channels were calibrated and returned to operable status on 07/29/09.

This condition and associated Corrective Actions are detailed in BVPS Condition Report No. CR 09-61459.As required by ODCM procedure 1/2-ODC-3.03, "Controls for RETS and REMP Programs", (as referenced in procedure Attachment D, Control 3.3.3.1, Table 3.3-6, Action 35), effluent releases via this pathway may continue provided the preplanned alternate method of monitoring of appropriate parameters is imitated.

[RM-1 VS-111] Unit 1 Ventilation Vent is the first Preplanned Method of Monitoring and was in-service during the maintenance and calibration of [RM-1 VS-109].

Form 1/2-ENV-01.05.F01 (page 36 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 RTL # A9.690E Enclosure 2, Page 19 of 21 Radioactive Effluent Release Report Calendar Year -2009 Table 7 Total Dose Commitments, Total Effective Dose Equivalents and Population Doses Total Dose Commitment From All Facility Releases To Members of the Public 40 CFR 190.10(a)

Environmental Doses (1) (2) % of.ODCM or Organ Effluent Dose Direct Radiation Dose Total Dose 40 CFR 190 Limit (mrem) (mrem) (mrem)Bone 7.70E-02 0.00E+00 7.70E-02 0.31%Liver 3.41 E-01 0.OOE+00 3.41 E-01 1.36%Total Body 4.82E-01 0.00E+00 4.82E-01 1.93%Thyroid 1.97E-01 0.OOE+00 1.97E-01 0.26%Kidney 2.36E-01 0.OOE+00 2.36E-01 0.94%Lung 2.09E-01 0.OOE+00 2.09E-01 0.84%GI-LLI 2.36E-01 0.OOE+00 2.36E-01 0.94%(1) The cumulative dose contributions from liquid and gaseous effluents were determined in accordance with the applicable CONTROLS & SURVEILLANCE REQUIREMENTS listed in.ODCM procedure 112-ODC-3.03.

The dose commitment limits for 40 CFR 190 MEMBERS OF THE PUBLIC (ODCM 1/2-ODC-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)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 REMP'control location (16.5 miles SSW; Weirton, WV).I I I I I I I I I I I I I I I I-Compliance to 100 mrem Limit of 10 CFR 20.1301 For Total Effective Dose Equivalent Pursuant to 10 CFR 20.1301 (a)(1), the Total Effective Dose Equivalent from licensed operation to the maximum individual during the report period, is 2.74 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 (calculated per the ODCM).Members of the Public Doses Due To Their Activities Inside The Site Boundary 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 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.0-50 Mile Population Doses From Liquid and Gaseous Effluents 0-50 mile Total Population Dose from liquid and gaseous effluents

= 621 man-mrem (Total Body)0-50 mile Average Population Dose from liquid and gaseous effluents

= 0.0001553 man-mrem (Total Body)

Form 1/2-ENV-01.05.FO1 (page 37 of 38), Rev 2 RTL # A9.690E Beaver Valley Power Station -Units 1 & 2 Enclosure 2, Page 20 of 21 Radioactive Effluent Release Report Calendar Year -2009 Table 8-Offsite Dose Calculation Manual SurveillanceeDeficiencies Inability to Include a Filter Paper as Part of the Monthly Composite Particulate Sample The weekly particulate filter paper samples for the weeks of 07/05/09 to 07/12/09 and 11/01/09 to 11/08/09 for the Warehouse Extension Decon Facility were unable to be located for inclusion in the monthly composite analysis.

The Warehouse Extension Decon Facility is monitored as required by OCDM procedure 1/2-ODC-3.03 as an effluent pathway. The particulate filter paper samples from this area are included in the monthly composite analysis for Gross Alpha and Sr-89 and Sr-90. An extensive search was conducted to locate these filter papers but they were never located. Analysis data was available for 1-133, 1-131 and principle gamma emitters.

This condition and associated Corrective Actions are detailed in BVPS Condition Report No. CR 09-64033 and CR 10-69838.ODCM procedure 1/2-ODC-3.03, "Controls for RETS and REMP Programs", (as referenced in procedure Attachment K, Control 3.11.2.1, Table 4.11-2), requires a monthly composite for Gross Alpha, Sr-89 and Sr-90. Activity was estimated at Lower Levels of Detection for this release pathway based on the work that occurred in the facility during the time period the sample was collected.

Also the results from the monthly composite sample for the same time period were evaluated.

No Gross Specific Activity or activity from Sr-89 or Sr-90 was detected for the weeks prior to and after the time periods of the missing particulate filter paper samples.

Form 1/2-ENV-01.05.FO1 (page 38 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2009 Table 9 RTL # A9.690E Enclosure 2, Page 21 of 21 Unit 1 and 2 Offsite Dose Calculation Manual Changes (Description)

There were two changes made to the Unit 1 and 2 Offsite Dose Calculation Manual during this report period.Change 25 to the ODCM added the Emergency Planning &Preparedness Emergency Action Level Radiation Monitors (EPP-EAL).

This changed added the EAL Area Monitors and Process Monitors for both Units that were not specifically required by the ITS, LRM or ODCM.Shortly after the implementation of this change it was determined that the ODCM is not the appropriate document for control of the EPP-EAL monitors.

Change 26 removed the changes made during Change 25 and restored the affected ODCM documents to their previous content (Change 24).I I I I I I I I I I I I I I I I I I I RTL # A9.690E Enclosure 2, Attachment 1 Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2009 Attachment 1 Joint Frequency Distribution Tables-Attachment 1 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 distributions for 2009 returned to a more normal distribution than in 2008. During 2009 there were fewer hours of"D" stability and correspondingly more hours of "E" stability class than normally expected.

This was probably caused by a combination of normal year-to-year variation and the cooler and wetter than normal conditions that occurred in the Beaver Valley area during 2009..Meteorological Data Recdovery.-

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: PERCENT RECOVERY OF INDIVIDUAL METEOROLOGICAL PARAMETERS 99.4% = Wind Speed 35'99.4% = Wind Speed 150'98.3% = Wind Speed 500'99.4% = Wind Direction 35'99.4% = Wind Direction 150'99.4% = Wind Direction 500'99.4% = Delta Temperature (150'- 35') 1P 99.4% = Delta Temperature (500' -35' ) 2P 99.4% = Temperature 35'99.4% = Precipitation 99.3%= Average Recovery of Individual Meteorological Parameters PERCENT RECOVERY OF COMPOSITE VARIABLES 99.4% = Wind Speed 35', Wind Direction 35', Delta Temperature 1 P 99.4% = Wind Speed 150', Wind Direction 150', Delta Temperature 1P 99.0% = Wind Speed 500', Wind Direction 500', Delta Temperature 2P 99.3% = Average Recovery of Composite Variables Attachment 1 ClarifLcation Hourly meteorological data is not provided for specific periods of Abnormal Gaseous Release during the calendar 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 ODCM Dose Limits and the ODCM Dose Rate Limits are considered to be the design objectives.

2) There were no Abnormal Gaseous Releases during the calendar year.For a copy of the hourly meteorological data during the calendar quarters, contact Ms. Jennifer Powell-Campbell at 724-682-4209.

RTL A9.690E U Enclosure 2, Attachment 1 (Part 1 of 3)Beaver Valley Power Station -Units 1 & 2 i Radioactive Effluent Release Report Calendar Year -2009 Attachment 1 Part 1: Joint Frequency Distribution Tables (35ft)Page 1 of 8 Hours at Each Wind Speed and Direction Total Period I Period of Record = 1/1/2009 00:00 -12/31/2009 23:00 Elevation:

Speed: SP35P Direction:

D135P Lapse: DT150-35 Stability Class A Delta Temperature Extremely Unstable Wind Speed (mph)Wind Direction 1-4 4-8 8-13 13-19 19-25 >_25 Total N 9 30 1 0 0 0 40 NNE 19 22 2 0 0 0 43 NE 21 16 0 0 0 0 37 ENE 33 47 0 0 0 0 80 E 18 35 0 0 0 0 53 ESE 25 18 0 0 0 0 43 I SE 9 10 0 0 0 0 19 SSE 8 9 0 0 0 0 17 S 6 19 0 0 0 0 25 SSW 5 26 1 0 0 0 32 SW 3 31 15 0 0 0 49 WSW 2 35 40 0 0 0 77 W 7 97 25 0 0 0 129 WNW 6 41 10 0 0 0 57 NW 7 31 2 0 0 0 40 NNW 7 25 2 0 0 0 34 Total 185 492 98 0 0 0 775 Calm Hours not Included above for: Total Period 27 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 60 Valid Hours for this Stability Class for: Total Period 775 Total Hours for Period 8760 I I I I I I RTL A9.690E Enclosure 2, Attachment 1 (Part 1 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2009 Attachment 1 Part 1: Joint Frequency Distribution Tables (35ft)Page 2 of 8 Hours at Each Wind Speed and Direction Total Period Period of Record = 1/1/2009 00:00 -12/31/2009 23:00 Elevation:

Speed: SP35P Direction:

D135P Lapse: DT150-35 Stability Class B Delta Temperature Moderately Unstable Wind Speed (mph)Wind Direction 1-4 4-8 8-13 13-19 19-25 > 25 Total N 7 6 1 0 0 0 14 NNE 4 6 0 0 0 0 10 NE 8 1 0 0 0 0 9 ENE 10 5 0 0 0 0 15 E 5 9 0 0 0 0 14 ESE 6 0 0 0 0 0 6 SE 1 1 0 0 0 0 2 SSE 5 1 0 0 0 0 6 S 1 2 0 0 0 0 3 SSW 5 16 0 0 0 0 21 SW 1 9 7 1 0 0 18 WSW 2 17 12 1 0 0 32 W 3 34 8 0 0 0 45 WNW 4 15 3 0 0 0 22 NW 4 17 0 0 0 0 21 NNW 3 12 1 0 0 0 16 Total 69 151 32 2 0 0 254 Calm Hours not Included above for: Total Period 27 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 60 Valid Hours for this Stability Class for: Total Period 254 Total Hours for Period 8760 RTL A9.690E i Enclosure 2, Attachment 1 (Part 1 of 3)Beaver Valley Power Station -Units 1 & 2 1 Radioactive Effluent Release Report Calendar Year -2009 I Attachment 1 Part 1: Joint Frequency Distribution Tables (35ft)Page 3 of 8 Hours at Each Wind Speed and Direction Total Period i Period of Record = 1/1/2009 00:00 -12/31/2009 23:00 Elevation:

Speed: SP35P Direction:

D135P Lapse: DT150-35 Stability Class C Delta Temperature Slightly Unstable Wind Speed (mph)Wind Direction 1-4 4-8 8-13 13-19 19-25 > 25 Total N 8 12 2 0 0 0 22 NNE 5. 2 0 0 0 0 7 NE 4 3 0 0 0 0 7 ENE 10 10 0 0 0 0 20 E 6 5 0 0 0 0 11 ESE 2 2 0 0 0 0 4 I SE 4 0 0 0 0 0 4 SSE 6 0 0 0 0 0 6 S 1 1 0 0 0 0 2 SSW 2 12 2 0 0 0 16 SW 6 11 8 1 0 0 26 WSW 3 18 6 1 0 0 28 W 6 44 10 0 0 0 60 I WNW 4 17 2 0 0 0 23 NW 5 17 1 0 0 0 23 NNW 5 10 2 0 0 0 17 3 Total 77 164 33 2 0 0 276 Calm Hours not Included above for: Total Period 27 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 60 Valid Hours for this Stability Class for: Total Period 276 Total Hours for Period 8760 I I I I I I RTL A9.690E Enclosure 2, Attachment 1 (Part 1 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2009 Attachment 1 Part 1: Joint Frequency Distribution Tables (35ft)Page 4 of 8 Hours at Each Wind Speed and Direction Total Period Period of Record = 1/1/2009 00:00 -12/31/2009 23:00 Elevation:

Speed: SP35P Direction:

D135P Lapse: DT150-35 Stability Class D Delta Temperature Neutral Wind Speed (mph)Wind Direction 1-4 4-8 8-13 13-19 19-25 > 25 Total N 76 87 0 0 0 0 163 NNE 69 18 1 0 0 0 88 NE 110 14 0 0 0 0 124 ENE 114 63 0 0 0 0 177 E 74 28 0 0 0 0 102 ESE 28 4 0 0 0 0 32 SE 43 3 0 0 0 0 46 SSE 31 3 0 0 0 0 34 S 30 16 0 0 0 0 46 SSW 40 56 13 0 0 0 109 SW 68 147 101 3 1 0 320 WSW 94 201 127 17 1 0 440 W 83 257 97 10 0 0 447 WNW 87 145 34 0 0 0 266 NW 86 129 7 0 0 0 222 NNW 79 90 1 0 0 0 170 Total 1112 1261 381 30 2 0 2786 Calm Hours not Included above for: Total Period 27 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 60 Valid Hours for this Stability Class for: Total Period 2786 Total Hours for Period 8760 RTL A9.690E Enclosure 2, Attachment 1 (Part 1 of 3)Beaver Valley Power Station -Units 1 & 2 3 Radioactive Effluent Release Report Calendar Year -2009 Attachmentl I Part 1: Joint Frequency Distribution Tables (35ft)Page 5 of8 3 Hours at Each Wind Speed and Direction Total Period I Period of Record = 1/1/2009 00:00 -12/31/2009 23:00 Elevation:

Speed: SP35P Direction:

D135P Lapse: DT150-35 Stability Class E Delta Temperature Slightly Stable Wind Speed (mph)Wind Direction 1-4 4-8 8-13 13-19 19-25 > 25 Total U N 74 17 0 0 0 0 91 NNE 97 9 0 0 0 0 106 NE 166 24 0 0 0 0 190 I ENE 212 103 0 0 0 0 315 E 194 35 0 0 0 0 229 ESE 144 8 0 0 0 0 152 SE 140 3 0 0 0 0 143 SSE 139 11 0 0 0 0 150 S 182 21 0 0 0 0 203 SSW 153 57 7 1 0 0 218 I SW 121 74 41 2 0 0 238 WSW 76 92 59 8 1 0 236 W 75 62 18 1 0 0 156 WNW 69 29 2 0 0 0 100 NW 102 37 2 0 0 0 141 NNW 93 19 0 0 0 0 112 3 Total 2037 601 129 12 1 0 2780 Calm Hours not Included above for: Total Period 27 Variable Direction Hours for: Total Period 0 U Invalid Hours for: Total Period 60 Valid Hours for this Stability Class for: Total Period 2780 Total Hours for Period 8760 I I I I I RTL A9.690E Enclosure 2, Attachment 1 (Part 1 of 3)Beaver Valley Power Station -Units I & 2 Radioactive Effluent Release Report Calendar Year -2009 Attachment 1 Part 1: Joint Frequency Distribution Tables (35ft)Page 6 of 8 Hours at Each Wind Speed and Direction Total Period Period of Record 1/1/2009 00:00 -12/31/2009 23:00 Elevation:

Speed: SP35P Direction:

D135P Lapse: DT150-35 Stability Class F Delta Temperature Moderately Stable Wind Speed (mph)Wind Direction 1-4 4-8 8-13 13-19 19-25 >25 Total N 14 1 0 0 0 0 .15 NNE 15 0 0 0 0 0 15 NE 40 0 0 0 0 0 40 ENE 60 0 0 0 0 0 60 E 100 0 0 0 0 0 100 ESE 190 0 0 0 0 0 190 SE 219 1 0 0 0 0 220 SSE 167 1 0 0 0 0 168 S 114 2 0 0 0 0 116 SSW 85 13 1 1 0 0 100 SW 39 5 5 1 0 0 50 WSW 18 3 6 5 0 0 32 W 7 1 0 0 0 0 8 WNW 4 0 0 0 0 0 4 NW 15 1 0 0 0 0 16 NNW 8 0 0 0 0 0 8 Total 1095 28 12 7 0 0 1142 Calm Hours not Included above for: Total Period 27 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 60 Valid Hours for this Stability Class for: Total Period 1142 Total Hours for Period 8760 RTL A9.690E I Enclosure 2, Attachment 1 (Part 1 of 3)Beaver Valley Power Station -Units 1 & 2 3 Radioactive Effluent Release Report Calendar Year -2009 Attachment 11 Part 1: Joint Frequency Distribution Tables (35ft).Page 7 of 8 3 Hours at Each Wind Speed and Direction Total Period i Period of Record = 1/1/2009 00:00 -12/31/2009 23:00 Elevation:

Speed: SP35P Direction:

D135P Lapse: DT150-35 Stability Class G Delta Temperature Extremely Stable Wind Speed (mph) I Wind Direction 1-4 4-8 8-13 13-19 19-25 > 25 Total N 0 0 0 0 0 0 0 NNE 9 0 0 0 0 0 9 NE 13 0 0 0 0 0 13 ENE 15 0 0 0 0 0 15 E 42 0 0 0 0 0 42 ESE 98 0 0 0 0 0 98 I SE 197 0 0 0 0 0 197 SSE 124 0 0 0 0 0 124 S 67 1 0 0 0 0 68 SSW 27 5 0 0 0 0 32 SW 26 3 2 0 0 0 31 WSW 11 1 0 0 0 0 12 W 3 0 0 0 0 0 3 i WNW 1 0 0 0 0 0 1 NW 13 0 0 0 0 0 13 NNW 2 0 0 0 0 0 2 3 Total 648 10 2 0 0 0 660 Calm Hours not Included above for: Total Period 27 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 60 Valid Hours for this Stability Class for: Total Period 660 Total Hours for Period 8760 I I I I I I RTL A9.690E Enclosure 2, Attachment 1 (Part 1 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2009 Attachment 1 Part 1: Joint Frequency Distribution Tables (35ft)Page 8 of 8 Hours at Each Wind Speed and Direction Summary of All Stability Classes Total Period Period of Record = 1/1/2009 00:00 -12/31/2009 23:00 Elevation:

Speed: SP35P Direction:

D135P Lapse: DT150-35 Delta Temperature Wind Speed (mph)Wind Direction 1-4 4-8 8-13 13-19 19-25 > 25 Total N 188 153 4 0 0 0 345 NNE 218 57 3 0 0 0 278 NE 362 58 0 0 0 0 420 ENE 454 228 0 0 0 0 682 E 439 112 0 0 0 0 551 ESE 493 32 0 0 0 0 525 SE 613 18 0 0 0 0 631 SSE 480 25 0 0 0 0 505 S 401 62 0 0 0 0 463 SSW 317 185 24 2 0 0 528 SW 264 280 179 8 1 0 732 WSW 206 367 250 32 2 0 857 W 184 495 158 11 0 0 848 WNW 175 247 51 0 0 0 473 NW 232 232 12 0 0 0 476 NNW 197 156 6 0 0 0 359 Total 5223 2707 687 53 3 0 8673 Calm Hours not Included above for: Total Period 27 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 60 Valid Hours for this Stability Class for: Total Period 8673 Total Hours for Period 8760 RTL A9.690E Enclosure 2, Attachment 1 (Part 2 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2009 Attachment 1 Part 2: Joint Frequency Distribution Tables (150ft)Page 1 of 8 Hours at Each Wind Speed and Direction Period of Record =Elevation:

Speed: Stability Class A SP150P Total Period 1/1/2009 00:00 -12/31/2009 23:00 Direction:

DI150P Lapse: DT150-35 Delta Temperature Extremely Unstable Wind Speed (mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW 1-4 2 5 2 3 1 0 1 0 0 0 2 1 4 0 6 1 4-8 24 15 23 31 46 18 15 13 17 7 12 5 32 17 9 16 8- 13 17 16 9 32 27 21 14 7 18 12 8 34 54 46 15 11 13-19 6 5 0 3 0 0 2 1 2 1 5 21 27 25 0 0 19-25 0 0 0 0 0 0 0 0 0 0 0 1 5 2 0 0> 25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Total 49 41 34 69 74 39 32 21 37 20 27 62 122 90 30 28 I I I 1!I I I I I I I I I I I I I I Total 28 300 341 98 8 0 775 Calm Hours not Included above for: Variable Direction Hours for: Invalid Hours for: Valid Hours for this Stability Class for: Total Hours for Period Total Period Total Period Total Period Total Period 3 0 60 775 8760 RTL A9.690E Enclosure 2, Attachment 1 (Part 2 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2009 Attachment 1 Part 2: Joint Frequency Distribution Tables (150ft)Page 2 of 8 Hours at Each Wind Speed and Direction Total Period Period of Record = 1/1/2009 00:00 -12/31/2009 23:00 Elevation:

Speed: SP150P Direction:

DI150P Lapse: DT150-35 Stability Class B Delta Temperature Moderately Unstable Wind Speed (mph)Wind Direction 1-4 4-8 8-13 13-19 19-25 > 25 Total N 1 9 6 2 0 0 18 NNE 3 .4 3 0 0 0 10 NE 1 8 1 0 0 0 10 ENE 1 8 4 1 0 0 14 E 0 8 8 0 0 0 16 ESE 2 5 1 0 0 0 8 SE 0 4 0 1 0 0 5 SSE 1 4 1 0 *0 0 6 S 0 3 12 0 0 0 15 SSW 0 4 7 1 0 0 12 SW 1 1 5 5 0 0 12 WSW 0 3 7 4 1 0 15 W 1 16 22 12 2 1 54 WNW 2 15 8 5 2 0 32 NW 0 4 6 0 0 0 10 NNW 2 10 5 0 0 0 17 Total 15 106 96 31 5 1 254 Calm Hours not Included above for: Total Period 3 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 60 Valid Hours for this Stability Class for: Total Period 254 Total Hours for Period 8760 RTL A9.690E I Enclosure 2, Attachment 1 (Part 2 of 3)Beaver Valley Power Station -Units 1 & 2 3 Radioactive Effluent Release Report Calendar Year -2009 Attachment 1 Part 2: Joint Frequency Distribution Tables (150ft)Page 3 of 8 1 Hours at Each Wind Speed and Direction Total Period I Period of Record = 1/1/2009 00:00 -12/31/2009 23:00 Elevation:

Speed: SPI50P Direction:

DI150P Lapse: DT150-35 i Stability Class C Delta Temperature Slightly Unstable Wind Speed (mph) 1 Wind Direction 1-4 4-8 8-13 13-19 19-25 > 25 Total N 1 12 10 1 0 0 24 NNE 1 6 3 0 0 0 10 NE 1 1 2 0 0 0 4 ENE 0 9 7 0 0 0 16 E 0 10 5 0 0 0 15 ESE 0 5 1 0 0 0 6 U SE 1 6 3 0 0 0 10 SSE 0 1 4 0 0 0 5 S 1 2 5 1 0 0 9 1 SSW 1 4 4 1 0 0 10 SW 1 6 5 1 0 0 13 WSW 4 1 10 8 1 0 24 W 1 20 25 13 2 0 61 WNW 0 13 18 4 2 0 37 NW 3 8 6 0 0 0 17 NNW 1 9 5 0 0 0 15 Total 16 113 113 29 5 0 276 Calm Hours not Included above for: Total Period 3 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 60 Valid Hours for this Stability Class for: Total Period 276 Total Hours for Period 8760I I I I I I RTL A9.690E Enclosure 2, Attachment 1 (Part 2 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2009 Attachment 1 Part 2: Joint Frequency Distribution Tables (150ft)Page 4 of 8 Hours at Each Wind Speed and Direction Total Period 1/1/2009 00:00 -12/31/2009 23:00 Direction:

DI150P Lapse: Period of Record =Elevation:

Speed: SP150P Stability Class D DT15-35 Delta Temperature Neutral Wind Speed (mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW 1-4 31 24 32 24 9 8 12 9 10 23 21 41 45 25 29 22 4-8 87 55 49 101 59 25 24 28 28 35 52 82 126 128 84 75 8- 13 49 12 13 49 28 8 14 9 25 42 116 113 233 148 67 41 13- 19 6 6 0 1 1 1 0 0 1 8 34 50 173 54 5 0 19 -25 0 0 0 0 0 0.0 0 0 0 2 13 44 5 0 0> 25 0 0 0 0 0 0 0 0 0 0 0 3 9 0 0 0 Total 173 97 94 175 97 42 50 46 64 108 225 302 630 360 185 138 Total 365 1038 967 340 64 12 2786 Calm Hours not Included above for: Variable Direction Hours for: Invalid Hours for: Valid Hours for this Stability Class for: Total Hours for Period Total Period Total Period Total Period Total Period 3 0 60 2786 8760 RTL A9.690E Enclosure 2, Attachment 1 (Part 2 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2009 Attachment 1 I I Part 2: Joint Frequency Distribution Tables (150ft)Page 5 of 8 3 Hours at Each Wind Speed and Direction Total Period I Period of Record =Elevation:

Speed: SPI50P Stability Class E 1/1/2009 00:00 -12/31/2009 23:00 Direction:

DI150P Lapse: DT150-35 I Delta Temperature Slightly Stable Wind Speed (mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total 1-4 4-8 8-13 13-19 19-25 > 25 Total 65 90 98 81 48 28 34 33 46 70 87 78 54 31 29 31 41 40 67 249 63 35 58 40 61 65 74 79 84 115 69 40 12 8 11 111 41 13 11 22 37 36 60 57 81 43 19 1 0 0 0 2 4 0 0 0 1 5 21 28 46 7 0 0 0 0 0 0 0 0 0 0 0 1 0 5 14 1 0 0 0 0 0 0 0 0 0 0 0 0 1 1 1 0 0 0 118 138 176 443 156 76 103 95 145 177 243 248 280 197 117 72 903 1180 563 114 21 3 2784 Calm Hours not Included above for: Variable Direction Hours for: Invalid Hours for: Valid Hours for this Stability Class for: Total Hours for Period Total Period Total Period Total Period Total Period 3 0 60 2784 8760 I I 3 I U I I I I I I I U RTL A9.690E Enclosure 2, Attachment 1 (Part 2 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2009 Attachment 1 Part 2: Joint Frequency Distribution Tables (150ft)Page 6 of 8 Hours at Each Wind Speed and Direction Total Period Period of Record = 1/1/2009 00:00 -12/31/2009 23:00 Elevation:

Speed: SP150P Direction:

DI150P Lapse: DT150-35 Stability Class F Delta Temperature Moderately Stable Wind Speed (mph)Wind Direction 1-4 4-8 8-13 13-19 19-25 > 25 Total N 71 11 1 0 0 0 83 NNE 116 15 0 0 0 0 131 NE 85 58 1 0 0 0 144 ENE 52 66 3 0 0 0 121 E 29 20 0 0 0 0 49 ESE 16 4 0 0 0 0 20 SE 19 6 2 0 0 0 27 SSE 13 9 3 0 0 0 25 S 41 16 2 0 0 0 59 SSW 96 43 5 1 1 0 146 SW 83 51 16 3 0 0 153 WSW 42 25 5 3 2 3 80 W 26 14 1 2 0 1 44 WNW 10 13 3 0 0 0 26 NW 15 5 1 0 0 0 21 NNW 21 7 0 0 0 0 28 Total 735 363 43 9 3 4 1157 Calm Hours not Included above for: Total Period 3 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 60 Valid Hours for this Stability Class for: Total Period 1157 Total Hours for Period 8760 RTL A9.690E Enclosure 2, Attachment 1 (Part 2 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2009 Attachment 1 I I I Part 2: Joint Frequency Distribution Tables (150ft)Page 7 of8 8 Hours at Each Wind Speed and Direction Total Period Period of Record =Elevation:

Speed: Stability Class G SP150P 1/1/2009 00:00 -12/31/2009 23:00 Direction:

DI150P Lapse: DT150-35 Delta Temperature Extremely Stable Wind Speed (mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW 1-4 38 52 52 27 16 8 8 9 20 43 66 35 12 14 20 15 4-8 2 17 26 26 12 5 5 8 24 34 31 20 1 0 0 1 8- 13 0 0 2 2 0 0 1 3 0 0 3 5 1 0 0 0 13-19 19-25 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0> 25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Total 40 69 80 55 28 13 14 20 44 77 101 60 14 14 20 16 Total 435 212 17 1 0 0 665 I I I I I I I U!I!I I I Calm Hours not Included above for: Variable Direction Hours for: Invalid Hours for: Valid Hours for this Stability Class for: Total Hours for Period Total Period Total Period Total Period Total Period 3 0 60 665 8760 RTL A9.690E Enclosure 2, Attachment 1 (Part 2 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2009 Attachment 1 Part 2: Joint Frequency Distribution Tables (150ft)Page 8 of 8 Hours at Each Wind Speed and Direction Summary of All Stability Classes Total Period Period of Record =Elevation:

Speed: 1/1/2009 00:00 -12/31/2009 23:00 SP150P Direction:

DI150P Lapse: DT150-35 Delta Temperature Wind Speed (mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW 1-4 209 291 271 188 103 62 75 65 118 233 261 201 143 82 102 93 4-8 8-13 13-19 19-25 > 25 186 95 15 0 0 152 42 11 0 0 232 39 0 0 0 490 208 7 0 0 218 109 5 0 0 97 44 1 0 0 118 45 3 0 0 103 49 1 0 0 151 99 5 0 0 192 106 17 2 0 227 213 70 2 1 215 231 114 23 7 293 417 273 67 12 301 266 95 12 0 179 114 5 0 0 158 63 0 0 0 Total 505 496 542 893 435 204 241 218 373 550 774 791 1205 756 400 314 Total Calm Hours not I Variable Directio]Invalid Hours for Valid Hours for ti 2497 3312 2140 622 106 ncluded above for: Total Period n Hours for: Total Period Total Period his Stability Class for: Total Period 20 8697 3 0 60 8697 8760 Total Hours for Period RTL A9.690E U Enclosure 2, Attachment 1 (Part 3 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2009 Attachment 1 Part 3: Joint Frequency Distribution Tables (500ft)Page I of8 8 Hours at Each Wind Speed and Direction Total Period Period of Record = 1/1/2009 00:00 -12/31/2009 23:00 Elevation:

Speed: SP500P Direction:

DI500P Lapse: DT500-35 Stability Class A Delta Temperature Extremely Unstable Wind Speed (mph)Wind Direction 1-4 4-8 8-13 13-19 19-25 > 25 Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 1 1 0 0 0 2i ENE 0 0 2 0 0 0 2 E 0 0 0 0 0 0 0 ESE 0 0 1 0 0 0 1 SE 0 1 2 0 0 0 3 SSE 0 0 0 0 0 0 0 S 0 0 1 0 1 0 2 i SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 1 0 0 0 1 W 0 1 1 0 0 0 2 I WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 0 0 0 0 0 0 0 3 Total 0 3 9 0 1 0 13 Calm Hours not Included above for: Total Period 2 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 158 Valid Hours for this Stability Class for: Total Period 13 Total Hours for Period 8760 I i S I 3 I RTL A9.690E Enclosure 2, Attachment 1 (Part 3 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Cal endar Year -2009 Attachment 1 Part 3: Joint Frequency Distribution Tables (500ft)Page 2 of 8 Hours at Each Wind Speed and Direction Total Period Period of Record = 1/1/2009 00:00 -12/31/2009 23:00 Elevation:

Speed: SP500P Direction:

D1500P Lapse:. DT500-35 Stability Class B Delta Temperature Moderately Unstable Wind Speed (mph)Wind Direction 1-4 4-8 8-13 13-19 19-25 > 25 Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 2 5 3 0 0 10 E 0 3 11 0 0 0 14 ESE 0 0 2 2 0 0 4 SE 0 3 2 0 0 0 5 SSE 0 0 3 0 0 0 3 S 0 0 1 0 0 0 1 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 1 0 0 1 W 0 1 0 0 0 0 1 WNW 1 0 1 0 0 0 2 NW 0 0 0 0 0 0 0 NNW 0 0 1 0 0 0 1 Total 1 9 26 6 0 0 42 Calm Hours not Included above for: Total Period 2 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 158 Valid Hours for this Stability Class for: Total Period 42 Total Hours for Period 8760 RTL A9.690E Enclosure 2, Attachment 1 (Part 3 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2009 Attachment 1 Part 3: Joint Frequency Distribution Tables (500ft)Page 3 of8 8 Hours at Each Wind Speed and Direction Total Period I Period of Record = 1/1/2009 00:00 -12/31/2009 23:00 Elevation:

Speed: SP500P Direction:

DI500P Lapse: DT500-35 Stability Class C Delta Temperature Slightly Unstable Wind Speed (mph)Wind Direction 1-4 4-8 8-13 13-19 19-25 > 25 Total I N 0 2 7 1 0 0 10 NNE 0 0 3 0 0 0 3 NE 0 0 3 1 0 0 4 i ENE 0 6 12 2 0 0 20 E 0 5 8 4 0 0 17 ESE 0 4 7 2 0 0 13 I SE 0 2 2 2 0 0 6 SSE 0 1 6 0 0 0 7 S 0 2 11 0 0 0 13 SSW 0 2 3 4 1 0 10 U SW 1 2 3 0 1 0 7 WSW 0 0 4 1 0 0 5 W 0 1 7 7 1 0 16 I WNW 0 2 7 12 4 2 27 NW 0 0 6 0 0 0 6 NNW 0 3 2 0 0 0 5 Total 1 32 91 36 7 2 169 Calm Hours not Included above for: Total Period 2 Variable Direction Hours for: Total Period 0I Invalid Hours for: Total Period 158 Valid Hours for this Stability Class for: Total Period 169 Total Hours for Period 8760 I I I I i ,I RTL A9.690E Enclosure 2, Attachment I (Part 3 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2009 Attachment 1 Part 3: Joint Frequency Distribution Tables (500ft)Page 4 of 8 Hours at Each Wind Speed and Direction Total Period Period of Record = 1/1/2009 00:00 -12/31/2009 23:00 Elevation:

Speed: SP500P Direction:

DI500P Lapse: DT500-35 Stability Class D Delta Temperature Neutral Wind Speed (mph)Wind Direction 1-4 4-8 8-13 13-19 19-25 > 25 Total N 23 72 151 74 2 0 322 NNE 29 29 32 18 0 0 108 NE 17 57 32 5 0 0 111 ENE 21 64 126 54 2 0 267 E 18 113 185 46 2 0 364 ESE 19 72 90 46 7 0 234 SE 11 46 70 28 7 0 162 SSE 8 28 ,61 36 3 0 136 S 11 30 62 45 12 0 160 SSW 11 23 80 70 15 1 200 SW 15 29 118 202 63 12 439 WSW 27 56 133 172 85 49 522 W 19 64 249 283 148 55 818 WNW 20 76 245 170 71 12 594 NW 12 59 126 74 2 0 273 NNW 15 82 149 32 0 0 278 Total 276 900 1909 1355. 419 129 4988 Calm Hours not Included above for: Total Period 2 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 158 Valid Hours for this Stability Class for: Total Period 4988 Total Hours for Period 8"760 RTL A9.690E I Enclosure 2, Attachment 1 (Part 3 of 3)Beaver Valley Power Station -Units 1 & 2 l Radioactive Effluent Release Report Calendar Year -2009 Attachment 1 Part 3: Joint Frequency Distribution Tables (500ft)Page 5 of 8 Hours at Each Wind Speed and Direction Total Period I Period of Record = 1/1/2009 00:00 -12/31/2009 23:00 Elevation:

Speed: SP500P Direction:

DI500P Lapse: DT500-35 3 Stability Class E Delta Temperature Slightly Stable Wind Speed (mph) ,_Wind Direction 1-4 4-8 8-13 13-19 19-25 > 25 Total N 19 36 32 20 0 0 107 NNE 20 32 12 10 0 0 74 NE 37 31 36 7 0 0 111 i ENE 31 59 60 11 0 0 161 E 41 79 81 19 0 0 220 ESE 24 39 38 26 5 0 132 I SE 30 38 33 23 11 0 135 SSE 20 37 40 24 9 0 130 S 30 31 52 58 5 0 176 SSW 22 23 43 37 13 3 141 SW 42 45 57 72 42 14 272 WSW 57 63 36 12 6 6 180 W 37 92 122 25 5 3 284 I WNW 25 56 45 9 0 0 135 NW 18 27 27 8 0 0 80 NNW 17 22 26 7 0 0 72I Total 470 710 740 368 96. 26 2410 Calm Hours not Included above for: Total Period 2 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 158 Valid Hours for this Stability Class for: Total Period 2410 Total Hours for Period 8760 I I I I I RTL A9.690E Enclosure 2, Attachment 1 (Part 3 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2009 Attachment 1 Part 3: Joint Frequency Distribution Tables (500ft)Page 6 of 8 Hours at Each Wind Speed and Direction Period of Record =Elevation:

Speed: SP500P Stability Class F Total Period 1/1/2009 00:00 -12/31/2009 23:00 Direction:

DI500P Lapse: DT500-35 Delta Temperature Moderately Stable Wind Speed (mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW 1-4 12 10 21 16 16 10 19 16 18 12 10 11 17 20 13 10 4-8 13 10 19 46 23 27 22 25 10 25 25 30 18 27 15 6 8- 13 5 0 6 20 2 13 17 23 21 28 11 10 26 10 3 5 13 -19 1 0 1 6 0 1 7 1 7 11 12 2 6 0 1 1 19 -25 0 0 0 0 0 0 0 1 2 1 7 0 0 0 0 0> 25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Total 31 20 47 88 41 51 65 66 58 77 65 53 67 57 32 22 Total 231 341 200 Calm Hours not Included above for: Variable Direction Hours for: Invalid Hours for: Valid Hours for this Stability Class for: Total Hours for Period 57 11 0 840 Total Period Total Period Total Period Total Period 2 0 158 840 8760 RTL A9.690E I Enclosure 2, Attachment 1 (Part 3 of 3)Beaver Valley Power Station -Units 1 & 2 i Radioactive Effluent Release Report Calendar Year -2009 Attachment 1 Part 3: Joint Frequency Distribution Tables (500ft)Page 7 of 8 Hours at Each Wind Speed and Direction Total Period i Period of Record = 1/1/2009 00:00 -12/31/2009 23:00 Elevation:

Speed: SP500P Direction:

DI500P Lapse: DT500-35 3 Stability Class G Delta Temperature Extremely Stable Wind Speed (mph)Wind Direction 1-4 4-8 8-13 13-19 19-25 > 25 Total N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 5 NE 1 0 2 0 0 0 3 ENE 0 2 1 0 0 0 3 E 4 1 0 0 0 0 5 ESE 0 1 1 0 0 0 2 I SE 2 1 0 0 0 0 3 SSE 5 5 3 0 0 0 13 S 0 7 4 2 0 0 13 .SSW 4 3 15 9 0 0 31 SW 5 16 19 8 1 0 49 WSW 1 3 2 0 0 0 6 W 2 2 1 0 0 0 5 WNW 0 2 1 0 0 0 3 NW 0 1 0 0 0 0 1 NNW 0 1 0 0 0 0 1 Total 24 45 49 19 1 0 138 Calm Hours not Included above for: Total Period 2 Variable Direction Hours for: Total Period 0 i Invalid Hours for: Total Period 158 Valid Hours for this Stability Class for: Total Period 138 Total Hours for Period 8760 I I i I I RTL A9.690E Enclosure 2, Attachment I (Part 3 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2009 Attachment 1 Part 3: Joint Frequency Distribution Tables (500ft)Page 8 of 8 Hours at Each Wind Speed and Direction Summary of All Stability Classes Total Period Period of Record =Elevation:

Speed: SP500P 1/1/2009 00:00 -12/31/2009 23:00 Direction:

DI500P Lapse: DT500-35 Delta Temperature Wind Speed (mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW 1-4 4-8 54 123 59 71 76 108 68 179 79 224 53 143 62 113 49 96 59 80 49 76 73 117 96 152 75 179 66 163 43 102 42 114 8-13 13-19 19-25 195 96 2 47 28 0 80 14 0 226 76 2 287 69 2 152 77 12 126 60 18 136 61 13 152 112 20 169 131 30 208 294 114 186 188 91 406 321 154 309 191 75 162 83 2 183 40 0> 25 Total 0 470 0 205 0 278 0 551 0 661 0 437 0 379 0 355 0 423 4 459 26 832 55 768 58 1193 14 818 0 392 0 379 157 :3600 2 0 158:3600:3760 Total 1003 2040 3024 1841 535 Calm Hours not Included above for.: Variable Direction Hours for: Invalid Hours for: Valid Hours for this Stability Class for: Total Hours for Period Total Period Total Period Total Period Total Period RTL # A9.690E Enclosure 2, Attachment 2 Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2009 Attachment 2 Unit 1 and 2 Offsite Dose Calculation Manual Changes Attachment 2 Attached is a complete copy of the ODCM that includes: Change (26) of the ODCM (Effective:

May 2009)Attachment 2 Clarification A complete copy of the ODCM has been provided to the following offices: United States Nuclear Regulatory Commission Attention:

Document Control Desk Washington, DC 20555-0001 United States Nuclear Regulatory Commission Regional Administrator 475 Allendale Road King of Prussia, PA 19406 For a complete copy of the ODCM, contact Ms. Jennifer Powell-Campbell at 724-682-4209.

RTL A9.690E Enclosure 3 Beaver Valley Power Station -Units 1 & 2 2009 Annual Radiological Environmental Operating Report FirstEnergy Nuclear Operating Company FENOC Beaver Valley Power Station -Units 1 & 2 Unit 1 License No. DPR-66 Unit 2 License No. NPF-73 Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

SUMMARY

and INDEX Report Preparation and Submittal Requirements:

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

o BVPS Integrated Technical Specifications, Administrative Control 5.6.1 o Offsite Dose Calculation Manual (ODCM) procedure 1/2-ODC-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 Specifications" o BVPS procedure 1/2-ENV-02.01, "Description of Overall Radiological Environmental Monitoring Program" o NUREG-1301, "Offsite Dose Calculation Manual Guidance:

Standard Radiological Effluent Controls for Pressurized Water Reactors, Generic Letter 89-01, Supplement No.], April 1991'"" BVPS CR 09-64044:

Deficiencies found in previous REMP Land Use Census Reports o BVPS CR 09-65670:

REMP TLD Location #55 Removed/Discarded o BVPS CR 09-65940:

Vendor laboratory reports anomalous REMP data for location 2.1 o BVPS CR 09-66654:

Missed REMP Sample for the Month of September" BVPS SAP Order No. 200197646-0770 is associated with documenting upstream (control location) surface water 1-131 analyses above the reporting level." BVPS SAP Order No. 200197646-0820 is associated with documenting unusual gross beta analysis results of air particulate filter media.o BVPS SAP Order No. 200197646-0850 is associated with documenting the interruption of air particulate and iodine sampling.o BVPS SAP Order No. 200197646-0860 is associated with documenting missing thermoluminescent dosimeters (TLDs) in the field." BVPS SAP Order No. 200197646-0870 is associated with documenting an anomalous data report.o BVPS SAP Order No. 200197646-0880 is associated with documenting a missed Feedstuff sample.ii Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

SUMMARY

and INDEX Report Overview: 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, 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 ODCM. The results of the REMP verify that the effluent releases did not impact the environment with measurable concentration of radioactive materials and/or levels of radiation that are higher than expected.Description of Pre-operational REMIP (1974 -1975): A pre-operational REMP program 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 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 in Table 2-3 of this report.Description of Operational REMIP (1976 -Present): The operational REMP program was initiated during calendar year 1976 and continued through the report period. During the past thirty-four (34) years, radiation and radioactivity in the environment was monitored within a 10-mile radius of the site. A description of the operational REMP program is outlined in Table 2-1 of this report. In general, two (2) types of samples were collected and compared during the report period, and are described as follows: Control Samples: These samples are collected from areas that are beyond measurable 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 the environment surrounding the BVPS site. During the report period, three hundred fifty eight (358) analyses were performed on samples from the control locations.

In addition, eight (8) analyses were completed for TLDs at the control locations.

Results of the analyses from the control locations are summarized in Table 2-2 of this report.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 the BVPS site. At a minimum, the samples are collected from areas where the BVPS contribution would indicate the most significant radiological impact. During the report period, one thousand five hundred sixteen (1516) analyses were performed on samples collected from ninety one (91) indicator locations.

In addition, five hundred two (502)analyses were completed for TLDs at the indicator locations.

Results of the analyses from the indicator locations are also summarized in Table 2-2 of this report.iii Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

SUMMARY

and INDEX I Comparisons:

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

Determination of Environmental Impact 2009 Sample Media and Analyses:

Results for drinking water, surface water, precipitation, groundwater, 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 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 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 Detection (LLD).o Airborne Exposure Pathway: This ODCM required pathway was evaluated via sampling of 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 detectable fission products or other radionuclides in the airborne particulate media during the I year.* Direct Exposure Pathway: This ODCM required pathway was evaluated via measurement I of environmental radiation doses by use of Thermo-Luminescent Dosimeters (TLDs). The results of TLD processing have indicated a stable trend and compare well with previous years.* Ingestion Exposure Pathway: This ODCM required pathway was evaluated via sampling of milk, fish, and foodcrops (leafy vegetables).

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 only indicated positive results for naturally occurring Potassium-40 at average environmental levels. No other radionuclides were identified.

The fish samples indicated below LLD levels in each of the sample analyses.Foodcrop (leafy vegetation) samples indicated naturally occurring Potassium-40 at average I environmental levels.o Waterborne Exposure Pathway: This ODCM pathway was evaluated via samples of drinking water, ground (well) water, surface (river) water and river sediment.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 iv 3 Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

SUMMARY

and INDEX positive analyses, but the values were consistent with Iodine-131 at the upstream surface (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 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, 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 due from previous nuclear weapons tests. Cobalt-58, Cobalt-60 and Zinc-65 were identified in some of the samples that were obtained at the shoreline of the BVPS main outfall facility.

This is not unusual, because the BVPS site discharges Cobalt-58, Cobalt-60 and Zinc-65 in liquid waste effluents.

The activity detected at this sample location 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.o Other Exposure Pathways:

In addition to the samples collected from the exposure pathways described above, other media (i.e., precipitation, feedstuff and soil) were also collected.

Results were consistent with previous years, with no degrading trends.o Offsite Groundwater Monitoring:

A total of six (6) offsite groundwater samples were collected and analyzed for Tritium and by gamma spectrometry during the report period.The samples were collected on a semi-annual basis from three (3) locations within four (4)miles of the site. The locations included one (1) well in Shippingport PA, one (1) well in Hookstown PA, and one (1) well in Georgetown PA. No gamma-emitting radionuclides were detected in the analyses.

All tritium results were less than the pre-operational value.o Supplemental Sample Sites: The REMP program includes supplemental sampling sites in addition to the required sites set forth in the ODCM. The supplemental sites include five (5)air sampling sites, one (1) surface water site, three (3) groundwater sites, three (3)precipitation sites, two (2) sediment sites, ten (10) soil sites, one (1) local large dairy, and one (1) milk animal feedstuff site. The soil sites are on a triennial sample frequency.

They were sampled in 2009 and are scheduled to be sampled again in 2012.* Population Dose vs. Natural

Background:

During the report period, the total calculated 0-50 mile population dose was 422 man-mrem (liquid releases), and 199 man-mrem (gaseous releases).

The average individual population dose from BVPS operation was much less than<1 mrem. For information, the National Academy of Sciences 1990 BEIR Report shows that the typical dose to an individual from background (natural radiation exposure including radon) is an estimated average of 296 mrem per year. The following graph illustrates that the average individual population dose was not affected from BVPS operation.

v Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 EXECUTIVE

SUMMARY

and INDEX Figure i-I Graph of Annual Average Population Dose: BVPS Dose and Natural Background Dose Average Population Dose 1000.0000000 100.0000000 10.0000000 E 0 1.0000000 E o,1oooooo o 0.0100000 0.0010000 0.0001000 .t " 1 "' *-0.0000100

.......1-11: 9,0 4s, 10,~9, ~ -xn ~---BVPS Average Population Dose (mRaem)Natural Background Population Dose (296 mRem)I-0 Summary: During the report period, radioactive effluent releases from the BVPS site did 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, and that BVPS operation did not adversely affect the surrounding environment.

Positive results attributable to BVPS operation were consistent with station data of authorized radioactive discharges and were 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 fluctuation for activities near the Lower Limit of Detection (LLD).I I I I I I I I I I I I vi Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

SUMMARY

and INDEX Inter-laboratory Comparison Programs:* Split Sample Program: BVPS shared split samples with the Pennsylvania Department of Environmental Protection (PADEP) in support of their nuclear power plant monitoring program. The shared media and number of locations were typically comprised of; milk (1), surface water (3), river sediment (1), fish (1), foodcrops (2), co-located air particulate/air iodine (4), and TLD (24). The split sample program was coordinated by the state, and the results are not provided with this report.* Spike Sample Program: Spiked samples were provided by an independent laboratory and then analyzed by the REMP contractor laboratory.

The samples were provided throughout the report period and included water samples, milk samples, filter paper samples and charcoal cartridge samples. All one-hundred-thirteen (113) analyses performed by the contactor laboratory on the spiked samples met the NRC comparison criteria.Special Reports: o SINCE no reporting levels were exceeded during 2009, THEN no Special Reports were required.

For information, a 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 1/2-ODC-3.03, Attachment Q Table 3.12-2, and when (2) the results of the following calculation are >1.0 (for calculations performed when more than one radionuclide is detected in the sampling medium): Concentration (1) + Concentration (2) + ... > 1.0 Limit Level (1) Limit Level (2)Land Use Census Results: Highlights from the most recent Land Use Census are documented in letter NPD3NRE:0627, dated September 29, 2009 and are summarized as follows:* Nearest Residence:

The location of the Nearest Residence has not changed since the previous census. The Nearest Residence location remains at the Terwilliger Residence, 211 Ferry Hill Road, Shippingport, PA (0.406 miles, in the NE Sector).* Nearest Garden: The location of the nearest garden has changed since the previous census.The new location is at the Knisley Residence, 175 Kerona Road, Shippingport, PA (0.7 miles, NE). However, the previous sampling location at the Cox Residence, 238 State Route 168, Hookstown, PA (0.760 miles, in the SSW Sector) will remain the primary sample location because the Knisley Residence garden did not contain leafy vegetables most appropriate for sampling (cabbage) this year.* Nearest Dairy Cow: The nearest dairy cow milked has not changed since the previous census.The location remains at the Searight Dairy, 948 McCleary Road, RD 1, Hookstown, PA (2.097 miles SSW).vii Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

SUMMARY

and INDEX o Nearest Doe Goat: The nearest location has changed since the previous census. The new 3 location is at the Ferry Farm, 227 Calhoun Road, Aliquippa, PA (3.320 miles SE).o Nearest Beef Cattle: The Beef Cattle locations in each sector were not validated during the i current census. This was not performed because (1) the census of Beef Cattle is not required by ODCM Control 3.12.1, and (2) there has been a steady decline in total number of Beef Cattle from 1977 through 2007. All associated sections were removed from the report. i o Prevailing Winds: The prevailing wind direction for Ground Releases was identified by showing the highest D/Q in the East Sector. The prevailing wind direction for Elevated I Releases was identified by showing the highest D/Q in the ESE Sector. The REMP properly monitors the environment with air particulate sampling stations in some Sectors and direct radiation TLDs in all Sectors.o 2010 Dairy Cow Sampling Locations:

Using the results of the 2009 Land Use Census, the 2010 dairy cow milk sampling locations will remain at the same locations used in 2009. The I locations are; Searight Dairy, 948 McCleary Road, RD1, Hookstown, PA (2.097 miles SSW), Halstead Dairy, 104 Tellish Diive, Hookstown PA (5.079 miles SSW), Brunton Dairy, 3681 Ridge Road, Aliquippa, PA (6.158 miles SE), and Weindsheimer Dairy, RD 1 Burgettstown, PA (10.476 miles SSW).o 2010 Doe Goat Sampling Locations:

Using the results of the 2009 Land Use Census, the i 2010 Doe Goat sampling location will be at the Ferry Farm, 227 Calhoun Road, Aliquippa, PA (3.320 miles SE). 3 o D/O for Milch Animal Locations:

None of the 2009 milch animal sampling locations experienced a >20% increase in deposition parameter (D/Q). 3 o D/Q for Offsite Dose Determination:

There was no adverse effect on the current ODCM methodology used for offsite dose determination from effluent releases.

Specifically, a linear regression analysis of D/Q did not yield any valid locations where the offsite dose could have increased

>20% more than the offsite dose previously calculated using current ODCM methodology.

3 o D/Q Historical Comparison:

There was no adverse trend in D/Q when comparing data to the ODCM default D/Q values, which validates that there was no adverse effect on the current i 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% more than the offsite dose previously calculated using current ODCM i methodology.

Therefore, a change in ODCM Receptor location and/or a change to meteorology at the current ODCM Receptor location were not required.I viii i Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

SUMMARY

and INDEX Deviations, Changes and Adjustments to the Normal Sampling Program* Deviation from Normal Milk Sampling & Analysis Schedule:

Doe Goat sampling was not available from REMP Location #69, Collins Farm (3.5 miles, SE) because goats were dry for the whole season. Doe goat sampling was available to meet the program requirements from REMP Location #102, Ferry Farm (3.3 miles, SE).* Deviation from Normal Surface Water Sampling and Analysis Schedule:

There were no deviations to the surface water sampling and analysis schedule.* Deviation from Normal Air Particulate

& Iodine Sampling and Analysis Schedule:

The air particulate and iodine sampling stations were interrupted on six (6) separate occasions during the report period. This issue was documented in SAP Order 200197646-0850.

o Deviation from Normal Direct Radiation Monitoring:

The Direct Radiation Monitoring by Thermoluminescent Dosimeters (TLDs) was missing data from one sample location for one quarterly sample period. This issue was documented in Condition Report 09-65670 and SAP Order 200197646-0860.

o Deviation from Normal Feedstuff Monitoring:

The Feedstuff Monitoring was missing data from one monthly sample period. This issue was documented in Condition Report 09-66654 and SAP Order 200197646-0880.

ix Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 EXECUTIVE

SUMMARY

and INDEX EXECUTIVE

SUMMARY

Report Preparation and Submittal Requirements

...............................................

R eport O verview ..................................................................................

Description of Pre-operational REMP (1974 -1975) .........................................

Description of Operational REMP (1976 -Present) ..........................................

Determination of Environmental Impact .........................................................

Inter-laboratory Comparison Programs .........................................................

S pecial R eports ....................................................................................

L and U se C ensus R esults .........................................................................

Deviations, Changes and Adjustments to the Normal Sampling Program ................

ii viii iii iii iv vii vii vii ix SECTION 1 -INTRODUCTION A. Radiation Fundamentals

....................................................................

B. Radiation and Radioactivity

...............................................................

C .U nits of M easurem ent .......................................................................

D. Lower Limit of Detection

..................................................................

E. Scope and Objectives of the REMP Program ...........................................

F. Description of the Beaver Valley Site ....................................................

SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM A. Radiological Environmental Monitoring Program .....................................

1. Program D escription

..................................................................

2. Sum m ary of R esults ....................................................................
3. Quality Control Program ..............................................................
4. Program C hanges ......................................................................

B .A ir M onitoring

...............................................................................

1. Characterization of Air and Meteorology

..........................................

2. Air Sampling Program and Analytical Techniques

...............................

3. Results and Conclusions

..............................................................

C. Monitoring of Shoreline Stream Sediment and Soil ....................................

1. Characterization of Shoreline Stream Sediment and Soil .........................
2. Sampling Program and Analytical Techniques

....................................

3. Results and Conclusions

..............................................................

D. Monitoring of Feedstuff and Foodcrops

..................................................

1. Characterization of Farm Products ...................................................
2. Sampling Program and Analytical Techniques

....................................

3. Results and Conclusions

..............................................................

E. Monitoring of Local Cow and Goat Milk .................................................

1. Description

-Milch Animal Locations

.............................................

2. Sampling Program and Analytical Techniques

....................................

3. Results and Conclusions

..............................................................

F. Environmental Radiation Monitoring

.....................................................

1. Description of Regional Background Radiation and Sources ....................
2. Locations and Analytical Techniques

...............................................

3. Results and Conclusions

..............................................................

1-1 1-1 1-4 1-4 1-4 1-5 2-1 2-1 2-5 2-5 2-5 2-23 2-23 2-23 2-24 2-29 2-29 2-29 2-30 2-35 2-35 2-36 2-37 2-40 2-40 2-40 2-42 2-46 2-46 2-46 2-46 U I I I I I I I I I I I I I U I I I x I Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

SUMMARY

and INDEX G .M onitoring of Fish ...........................................................................

2-51 1. Description

................................................

2-51 2. Sampling Program and Analytical Techniques

.........

...............

2-51 3. Results and Conclusions

..............................................................

2-51 H. Monitoring of Surface Water, Drinking Water, Groundwater and Precipitation

.... 2-54 1. Description of Water Sources ......................................................

2-54 2. Sampling and Analytical Techniques

................................................

2-55 3. Results and Conclusions

..............................................................

2-57 I. Estimates of Radiation Does to Man .......................................................

2-65 1. Pathways to Man -Calculational Models .... ........ ..............

2-65 2. Results of Calculated Population Dose to Man -Liquid Effluent Releases...

2-65 3. Results of Calculated Population Dose to Man -Gaseous Effluent Releases.

2-65 4 .C onclusions

.............................................................

...............

2-66 SECTION 3 -LAND USE CENSUS A. Land Use Census Overview ...............................................................

3-1 B .N earest R esidence ............................................................................

3-1 C. Nearest Garden >500 sqft ..................................................................

3-1 D. Nearest Dairy Cow ...... ........................................

3-1 E .N earest D oe G oat ............................................................................

3-1 F. Projections for 2010 Dairy Cow Sampling Locations

.........

..............

3-2 G. Projections for 2010 Doe Goat Sampling Locations

...................................

3-2 H. D/Q for Milch Animal Locations

.........................................................

3-2 I. D/Q for Offsite Dose Determination

.......................................................

3-2 J. D/Q Historical Comparison

................................................................

3-2 K. Discrepancies or Conditions of Note .....................................................

3-3 SECTION 4 -SPLIT SAMPLE AND SPIKE SAMPLE, INTER-LABORATORY COMPARISON PROGRAM A. Split Sample Program (Inter-Laboratory Comparison, Part 1 of 2) ..................

4-1 B. Spike Sample Program (Inter-Laboratory Comparison, Part 2 of 2).. ................

4-1 C .C onclusions

....................................................................................

4-3 xi Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

SUMMARY

and INDEX 3 AREOR TABLES Table 2-1 Operational Radiological Environmental Monitoring Program ......................

2-2 Table 2-2 Environmental Monitoring Program Results ...........................................

2-6 Table 2-3 Pre-Operational Environmental Radiological Monitoring Program Summary.....

2-20 Table 2-4 Comparison of Natural Radiation Exposure Versus Calculated Population Dose to M an -Liquid Effluent Releases ..............................................

2-67 Table 2-5 Comparison of Natural Radiation Exposure Versus Calculated Population Dose to M an -Gaseous Effluent Releases ..............................................

2-68 Table 3-1 Location of Nearest Residences, Gardens, Dairy Cows, Doe Goats .....................

34 3 Table 4-1 Inter-Laboratory Comparison Program, Spiked Samples -1 st Quarter ..............

4-4 Table 4-2 Inter-Laboratory Comparison Program, Spiked Samples -2 nd Quarter .............

4-5 1 Table 4-3 Inter-Laboratory Comparison Program, Spiked Samples -3rd Quarter .............

4-6 Table 4-4 Inter-Laboratory Comparison Program, Spiked Samples -4 th Quarter ..............

4-7 3 I I I I I U I I I xii I Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 EXECUTIVE

SUMMARY

and INDEX AREOR FIGURES Figure i-I Graph of Annual Average Population Dose: BVPS Dose and Natural B ackground D ose ...........................................................................

vi Figure 1-1 Geographical Map and Principal Communities in 50-mile Radius of the Beaver V alley Pow er Station ........................................................................

1-7 Figure 2-1 Environmental Monitoring Locations

-Air Sampling Stations ........................

2-27 Figure 2-2 Graph of Annual Average Concentration:

Gross Beta in Air Particulates

...........

2-28 Figure 2-3 Environmental Monitoring Locations

-Shoreline Sediments and Soil ...............

2-32 Figure 2z4 Graph of Annual Average Concentration:

Cesium-137, Cobalt-58

& 60 in Sedim ent ...................................................................

.................

2-33 Figure 2-5 Graph of Annual Average Concentration:

Cesium-137 in Soil ........................

2-34 Figure 2-6 Environmental Monitoring Locations

-Feedstuff and Foodcrops

....................

2-38 Figure 2-7 Graph of Annual Average Concentration:

Cesium-137 in Feedstuff and F o odcrops .....................................................................................

2-39 Figure 2-8 Environmental Monitoring Locations

-Milk ............................................

2-44 Figure 2-9 Graph of Annual Average Concentration:

Iodine-131

& Sr-90 in Milk ..............

2-45 Figure 2-10 Environmental Monitoring Locations

-TLDs ..........................................

2-48 Figure 2-11 Graph of Annual Average Exposure:

Direct Radiation in Environment

.............

2-50 Figure 2-12 Environmental Monitoring Locations

-Fish ...........................................

2-52 Figure 2-13 Graph of Annual Average Concentration:

Cesium-137 in Fish .......................

2-53 Figure 2-14 Environmental Monitoring Locations

-Ground Water, Surface Water, Drinking W ater and Precipitation

.....................................................................

2-60 Figure 2-15 Graph of Annual Average Concentration:

Iodine-131 in Surface Water, and D rinking W ater .............................................................

.................

2-61 Figure 2-16 Graph of Annual Average Concentration:

Tritium in Surface Water .................

2-62 Figure 2-17 Graph of Annual Average Concentration:

Tritium in Ground Water .................

2-63 Figure 2-18 Graph of Annual Average Concentration:

Tritium in Drinking Water ...............

2-64 xiii Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 1 -INTRODUCTION 3 A. Radiation Fundamentals 3 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 consists of atoms, which are comprised of positively charged particles (protons), negatively charged particles (electrons), and non-charged/neutral particles (neutrons).

The relatively 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 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 between the protons and neutrons keep the densely packed protons from repelling each other, and prevent the nucleus from breaking apart.B. Radiation and Radioactivity I The following provides an alphabetical glossary of terms associated with radiation, radioactivity, and the radioactive decay process. The terms discussed include Alpha Particles, Beta Particles, Gamma Rays, Genetic Effects, Half-life, Ionization, Isotopes, Neutrons, Radiation, Radioactive I Decay, Radionuclides and Somatic Effects.Alpha Particles:

Particulate and electromagnetic radiation each travel through matter differently because of their different properties.

Alpha particles contain 2 protons and 2 neutrons, are relatively I large, and carry an electrical charge of +2. Alpha particles are 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 atoms. As a result, a sheet of paper or a few centimeters of air can easily stop alpha particles.

3 Beta 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 collide and interact as often as alpha particles, so they can travel farther. Beta particles can usually travel through several meters of air, but may be stopped by a thin piece of metal or wood.Gamma Rays: Gamma rays are pure energy and travel at the speed of light. They have no 3 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- 3 energy gamma radiation can travel a considerable distance, where as, 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. 3 Genetic Effects: The effects of ionizing radiation which are observed in the offspring of the exposed individual that could occur as a result of ionizing radiation interacting with the genes in the human cells.Half-life:

The length of time an atom remains radioactive is defined in tenns of half-life, which is the amount of time required for a radioactive substance to lose half of its activity through the process of radioactive decay. Radionuclides that have infrequent emissions have a long half-life, I where as, radionuclides that have more frequent emissions have a short half-life.

I 1-1 1 Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 1 -INTRODUCTION Ionization:

Through interactions with atoms, alpha, beta, and gamma radiation lose their 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 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 biological systems.i Isotopes:

A group of identical atoms containing the same number of protons make up an 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. 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 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 deficit in the number of neutrons in the nucleus. Radionuclides such as Uranium-238, Berylium-7 and Potassium-40 occur naturally.

Others are man-made, such as Iodine-131, Cesium-137, and Cobalt-60.

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 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 deflections, the neutron has lost most of its energy., At this point, the neutron moves about as slowly 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.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 neutrons.

Concrete is also used to form an effective neutron shield because it contains water molecules and can be easily molded around odd shapes.Radiation:

This is the conveyance of energy through space. For instance, heatemanating from a stove is a form of radiation, as are light rays, microwaves, and radio waves. Ionizing 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 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 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.1-2 Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 SECTION 1 -INTRODUCTION 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 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 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, 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 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 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.

238u 4.5E+9 Yr 2 3 4 u 2.5E+5 Yr 2 3 4 Pa il 1.2 min JI 2 3 4 Th 24 d 2 3 0 Th 8.0E+4 Yr Jr 2 2 6 Ra 1600 Yr 222 Rn 3.82 d Ir Beta Decay Alpha Decay i U I I I i I I I I I I I I U I I U I I 2 1 8 po 3.05 min 214.P0 , 1.6E-4 s 2 1 0 P0 S138.4 d 214-Jr 214Bi1 02Bi J 19.7 5.01d 214 Pb 26.8 min 2 1 0 Pb 23 Yr 2 0 6 Pb stable Radionuclides:

See description for "isotopes".

Somatic Effects: The effects of ionizing radiation which 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 effects are a result of exposure to radiation over an extended period of time.1-3 Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 1 -INTRODUCTION C. Units of Measurement Activity (Curie): This relates the number of atoms in a sample that disintegrate (decay) per 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-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 discussing the low concentrations of radioactivity detected in environmental samples. For instance, the picocurie (pCi) represents one trillionth of a curie.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 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 = 100 erg/gm). The rate of absorbed dose is usually given in rad/hu. The rad is not used to quantify biological damage caused by ionizing radiation.

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 which cause dense local ionization, 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 radiation.

When the quality factor is multiplied by the absorbed dose (Rad), the result is the dose equivalent, which is an estimate of the possible biological damage resulting from exposure to a particular type of ionizing radiation.

The dose equivalent 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

= 20 rem. Since beta and gamma radiation each have a quality factor of 1, then 1 Rad of either beta or gamma radiation

= 1 rem. Neutrons have a quality factor ranging from 2 to 10.In terms of radiation, the rem is a relatively large unit. Therefore, a smaller unit, the millirem, is often used, where as, one millirem (mrem) is equal to 1/1000 of a rem.D. Lower Limit of Detection 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% probability, and with 5%probability of falsely concluding that a blank observation represents a real signal. A calculated LLD must consider such analytical variables as standard deviation of the background counting rate, the counting efficiency, the sample size, the fractional radiochemical yield, the radioactive decay constant, and the elapsed time between sample collection and time of counting.E. Scope and Objectives of the REMP Program The environmental program consists of environmental monitoring for radioactivity in the vicinity of BVPS. Environmental sampling and analyses include air, water, milk, vegetation, 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.

The Annual Radiological Environmental Operating Report (AREOR) for BVPS summarizes the Radiological Environmental 1-4 Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 1 -INTRODUCTION Monitoring Program (REMP) conducted by the FirstEnergy Nuclear Operating Company during the report period. I F. Description of the Beaver Valley Site £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 Pittsburgh, I 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. The population within a five mile radius of the plant is approximately 15,493 and the only area within the radius, of 5 concentrated population is the Borough of Midland, Pennsylvania, with a population of approximately 3,321.The site lies in a valley along the Ohio River. It extends from the river (elevation 665 feet above sea I level) to a ridge along the border south of the Beaver Valley Power Station at an elevation of 1,078 feet. Plant grade level is approximately 735 feet above sea level.BVPS is on the Ohio River at river mile 34.8, at a location on the New Cumberland Pool that is 3.3 river miles downstream from Montgomery Lock and Dam, and 19.4 miles upstream from 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.

During the report period, the Ohio River flow (as obtained from the Corps of Engineers

-Water Resources Engineering) at I the New Cumberland Dam ranged from 16,000 cubic feet per second (minimum monthly average) to 64,800 cubic feet per second (maximum monthly average).

The mean flow during the report period was 36,113 cubic feet per second. I Water temperature of the Ohio River typically varies from 340 Fahrenheit to 750 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 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 direction is typically from the southwest in summer and from the west southwest in winter. The National Climate Data Center (http://www.ncdc.noaa.gov/oa/climate/research/cag3/v4.html) indicates the following data for the Pittsburgh, PA area: " The total annual precipitation during the report period was 32.27 inches 5 o The average mean temperature during the report period was 51.00 Fahrenheit I I I 1-55 Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 1 -INTRODUCTION The basic features of the Beaver Valley Power Station Units 1 and 2 are tabulated below: Beaver Valley Unit 1 Beaver Valley Unit 2 Licensed Power Level 2900 -megawatts thermal 2900 -megawatts thermal Type of Power PWR PWR No. of Reactor Coolant Loops 3 3 No. of Steam Generators

& Type 3 -Vertical 3 -Vertical Steam Used by Main Turbine Saturated Saturated The BVPS units utilize two separate systems (primary and secondary) for transferring heat 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; therefore, -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 given up from the primary system to the secondary system in the steam generators, where steam is formed and delivered to the main unit turbine, which drives the electrical generator.

The steam is condensed after passing through the turbine, and returned to the steam generators to begin another steam/water cycle.1-6 Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report SECTION 1 -INTRODUCTION Figure 1-1 Geographical Map and Principal Communities in 50-mile Radius of the Beaver Valley Power Station RTL A9.690E Enclosure 3 I SHFNANGO I I I I I I i I U I I I I I I I I I I 0 20 40 MILES 1-7 Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM A. Radiological Environmental Monitoring Program 1. Program Description 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 sumnarized in Table 2-1. Further description of each portion of the program (Sampling Methods, Sample Analysis, Discussion and Results) are included in Sections 2-B tlhough 2-I of this report.2-B -Air Monitoring 2-C -Monitoring of Shoreline Stream Sediment and Soil 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 2-I -Estimates of Radiation Dose to Man 2-1 Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM RTL A9.690E Enclosure 3 Table 2-1 Operational Radiological Environmental Monitoring Program Section Sample Sample Sample Location Sample Sample Preparation/

Analysis Type Site No. Frequency Analysis Frequency 1 Air 13 Hookstown, PA (Old Meyer Farm) Continuous Weekly -Air Gross Beta (b)Particulate

& 27 Aliquippa, PA (Brunton Farm) Sampling with Particulate Radionuclide 28 Sherman Farm Sample Iodine-131 29B Beaver, Pa (Friendship Ridge) Collection at least Weekly- Charcoal 30 Shippingport, PA (Cook's Ferry Substation) weekly Gamma Scan 32 Midland, PA (North Substation)

Quarterly Composite (C)46.1 Industry, PA (McKeel's Service -Rt. 68)47 East Liverpool, OH (Water Department) 48 () Weirton, WV (Water Tower -Collier Way)51 Aliquippa, PA (Sheffield Substation)

I.. ..-.. .. ....2 Direct Radiation 10 13 14 15 27 28 29B 30 32 33-44 45 45.1 46 46.1 47 48 (a)51 52-56 59 60 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 9O 91 92 93 94 95 111-112 Shippingport, PA (Post Office)Hookstown, PA (Old Meyer Farm)Hookstown, PA Georgetown, PA (Post Office)Aliquippa, PA (Brunton Farm)Sherman Farm Beaver, PA (Friendship Ridge)Shippingport, PA (Cook's Ferry Substation)

Midland, PA (North Substation)

BVPS Site Perimeter Locations Raccoon Township, PA (Christian House Baptist Chapel -Rt. 18)Raccoon Township, PA (Kennedy's Corner)Industry, PA (Midway Drive)Industry, PA (McKeel's Service -Rt. 68)East Liverpool, OH (Water Department)

Weirton, WV (Water Tower -Collier Way)Aliquippa, PA (Sheffield Substation)

BVPS Site Perimeter Locations 236 Green Hill Road Georgetown, PA (444 Hill Road)Industry, PA (236 Engle Road)Brighton Township, PA (First Western Bank)Ohioview, PA (Lutheran Church -Rear)618 Squirrel Run Road Monaca, PA (37 Poplar Avenue -CCBC)Aliquippa, PA (117 Holt Road)Raccoon Township, PA (Elementary School)Aliquippa, PA (3614 Green Garden Road)Raccoon Township, PA (Municipal Building)106 Rt. 151 -Ted McWilliams Auto Body Raccoon Township, PA (Park Office -Rt. 18)Millcreek United Presbyterian, Church 2697 Rt. 18 735 Mill Creek Road Hancock County, WV (Senior Center)2048 Rt. 30 East Liverpool, OH (1090 Ohio Avenue)50103 Calcutta Smith's Ferry Road Midland, PA (110 Summit Road)Ohioville, PA (488 Smith Ferry Road)Midland, PA (6286 Tuscarawras Road)Pine Grove Road & Doyle Road Georgetown, PA (Georgetown Road Substation) 104 Linden -Sunrise Hills Hookstown, PA (McCleary

& Pole Cat Hollow Roads)Hookstown, PA (832 McCLeary Road)BVPS Site Perimeter Locations Continuous (TLD)Quarterly (1)Gamma Dose N I I I I I I I I I£I I I I I+I I I 2-2 Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Table 2-1 RTL A9.690E Enclosure 3 Operational Radiological Environmental Monitorin-Program Sample Sample Sample Preparation section Site Sample Location Sample Frequency Analysis Frequency Analysis Scin Type No. LAayi rqec 49A Weekly Grab 3 Surface )e) Industry, PA (Upstream of Montgomery Sample (h) Weekly Sample from Water Dam) Site49 only Iodine-131 Weekly Intermittent Composite Sample Monthly Composite of 2.1 Midland, PA (ATI Allegheny Ludlam) (h) Weekly Sample (C)Gamma Scan Daily Grab Sample 5 East Liverpool, OH (Water Department)

Collected Weekly Quarterly Composite

)(h) Tritium (H-3)11 Shippingport, PA (Upstream)

Gamma Scan 4 Groundwater 14A Hookstown, PA (Downstream)

Semi-Annual Semi-Annual Tritium (H-3)15B Georgetown.

PA (Downstream)

.......5 Drinking 4 Midland, PA (Water Department)

Weekly Composite of Water 5 East Liverpool, OH (Water Department)

Intermittent (d) Daily sample (d) Iodine-1 31 Sample Collected Monthly Composite (d) Gamma Scan Weekly Quarterly Composite (d) Tritium (H-3)2A BVPS Outfall Vicinity 6 Shoreline 4 Industry, PA (Upstream of Montgomery Semi-Annual Semi-Annual Gamma Scan Sediment Dam)New Cumberland, WV (Upstream of 50 Dam)7 Milk Weekly let Weekly Samples from Weekly 25 Hookstown, PA (Searight Farm) Searight only Iodine-1 31 from Searight only 27a- Aliquippa, PA (Brunton Farm)69 (k) Aliquippa, PA (Collins Farm) Biweekly When All other samples & Gamma Scan 96 (a) Burgettstown, PA (Windsheimer Farm) animals are on analyses are Biweekly Iodine-1 31 102 (k) Aliquippa, PA (Ferry Farm) pasture; monthly at during grazing, but Strontium-89 other times Monthly during other Strontium-90 113 (" times-13 Hookstown, PA (Halstead Farm) -ie 2A BVPS Outfall Vicinity Gamma Scan S Fish Industry, PA (Upstream of Montgomery Semi-Annual Composite of edible on edible 49A(') Dam) parts by species (g) parts 1OA/B Shippingport, PA Gamma Scan 9 Food 15A Georgetown, PA Annual at Harvest Composite of each Iodine-131 on Products 46A Industry, PA if available sample species green leafy 48A(-) Weirton, WV vegetables Feedstuff

& 25 Hookstown, PA (Searight Farm) Monthly Monthly Gamma Scan 10 Summer Forage 13A Hookstown, PA (Old Meyer Farm)11 Soil 22 South of BVPS, Transmission Lines Every Three (3) 12 Core Samples 3" Gamma Scan 27B Aliquippa, PA (Brunton Farm) Years Deep (2" diameter at (1997, 2000, 2003) each location approx. 10'29A Beaver, PA (Nicol Farm) radius)Shippingport, PA (Cook's Ferry 30A Substation) 32A Midland, PA (North Substation) 46B Industry, PA (Willows Inn -Rt. 68)47A East Liverpool, OH (Water Department) 48(') Weirton WV (Water Tower -Collier Way)51A Al quippa, PA (Sheffield Substation)

__., 30 Shippingport, PA (Cook's Ferry Weekly grab 1 12 Precipitation Substation) samples when Quarterly Composite (C) Gamma Scan 47 East Liv'erpool, OH (Water Department) available Tritium (H-3)48 () Weirton WV (Water Tower-Collier Way)2-3 Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Table 2-1 Operational Radiological Environmental Monitoring Program RTL A9.690E Enclosure 3 Notes for Table 2-1 (a) Control Sample Station: These Locations which are presumed to be outside the influence of plant effluents.

Particulate Samples are not counted within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after filter change. Perform Gamma (b) isotopic analysis on each sample when gross beta is greater than 10 times the yearly mean of control samples.(c) Long-term composite samples are obtained from short-term composite samples at the specified locations.(d) Composite samples are collected at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.(e) Weekly milk sample from the Searight Dairy is analyzed for Iodine-1 31 only.(f) Milk samples are collected bi-weekly when animals are grazing. The milk samples are collected 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 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.(h) Composite samples are obtained by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at location 2.1. The water treatment plant operator at location 5 obtains the weekly grab sample from the daily composite grab samples. For location 49a, the weekly grab sample is obtained by a field technician.(i) Two (2) TLDs are collected quarterly from each monitoring location.(k) ODCM procedure 1/2-ODC-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 this report (Monitoring of Local Cows Milk) for specific locations sampled.II II II!!II II II U II II I II II!I I U I I 2-4 Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM 2. Summary of Results All results of this monitoring program are summarized in Table 2-2. This table is prepared in the format specified by the NRC via the Branch Technical Position in NUREG-1301, and in accordance with Beaver Valley Power Station Offsite Dose Calculation Manual. Summaries of results of analysis of each media are discussed in Sections 2-B through 2-H and an 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 are generally in good agreement for both periods of time.Activity detected was attributed to naturally occurring radionuclides, BVPS effluents, previous nuclear weapons tests or to the normal statistical fluctuation for activities near the Lower Limit of Detection (LLD).The conclusion from all program data is that the operation of BVPS has resulted in no significant changes to the environment.

3. Quality Control Program The Quality Control Program implemented by BVPS to assure reliable performance by the contractor and the supporting QC data are presented and discussed in Section 4 of this report.4. Program Changes There were no changes of significance to the sampling program during the report period.2-5 Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility:

Beaver Valley Power Station Unit I and Unit 2 Docket No.: 50-334 / 50-412 Location of Facility:

Beaver County. Pennsylvania Reporting Period: Calendar Year -2009 Medium: Air Particulate and Radioiodine Unit of Measurement: (pico Curies / cubic meter)RTL A9.690E Enclosure 3 I U I U Type and Lower Number of Total Number Limit of All Indicator Location.

Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction)

ýb) Name Mean (fraction) (b) Name Mean (fraction) (b) Reported Performed LLD () Range (b) Distance and Direction Range (b) Distance and Direction Range (b) Measurements W Gross Beta < 0.002 0.024 ( 467 / 467 ) No. 47 East Liverpool, OH 0.027 ( 52 / 52 ) No. 48 Weirton, WV 0.025 ( 52 / 52 0 519 0.009 -0.045 Water Department 0,012 -0,045 Water Tower 0.011 -0.035 4.9 miles WNW Collier Way 16.3 miles SSW 1-131 <0.04 LLD ( 0/467) LLD ( 0/467 LLD ( 0/52 0 519 Gamma 40 Be-7 NA 0.088 ( 36 / 36 ) No. 30 Shippingport, PA 0,097 ( 4 / 4 ) No. 48 Weirton, WV 0.091 ( 4/4 ) NA 0.056 -0.112 Cook's Ferry Substation 0.075 -0.112 Water Tower 0.069 -0.115 0.5 miles ENE Collier Way 16.3 miles SSW Co-60 NA LLD( 0 / 36 ) LLD( 0 /36 ) LLD( 0 /4 ) NA Cs-134 < 0.0005 LLD ( 0 /36 ) LLD ( 0/36 ) LLD ( 0/4 ) 0 Cs-137 < 0.0005 LLD( 0 / 36 ) LLD( 0 /36 ) LLD( 0 /4 0 Ba-La-140 NA LLD( 0 / 36 ) LLD( 0 /36 ) LLD( 0 /4 ) NA Nominal Lower Limit of Detection Mean and range based upon detectable measurements only.Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM)2-6 Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

RTL A9.690E Enclosure 3 Name of Facility:

Beaver Valley Power Station Unit 1 and Unit 2 Docket No.: 50-334 / 50-412 Location of Facility:

Beaver County, Pennsylvania Reporting Period: Calendar Year -2009 Medium: Drinking Water Unit of Measurement: (pico Curies / liter)Type and Lower Number of Total Number Limit of All Indicator Location Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) b) Name Mean (fraction) tb) Name Mean (fraction)(b)

Reported Performed LLD (,) Range (') Distance and Direction Range N Distance and Direction Range (b) Measurements W 1-131 <0.5 0.6 ( 55 / 104 ) No. 4 Midland Water Dept. 0.6 ( 29 / 52 ) No. 49A Industry, PA 0.8 ( 43 /52 ) 0 165 0.2 1.5 1.3 miles NW 0.2 -1.5 Upstream of 0.3 -2.4 Montgomery Dam 5.0 miles NE H-3 < 200 LLD( 0 /8 ) LLD( 0 /4 ) LLD( 0/4 ) 0 12 Gamma 36 Mn-54 < 5 LLD( 0 /24) LLD( 0 /24) LLD( 0 /12) 0 Fe-59 < 10 LLD( 0 / 24 ) LLD( 0 /24 ) LLD( 0 /12) 0 Co-58 < 5 LLD( 0 /24 ) LLD( 0 /24 ) LLD( 0 / 12) 0 Co-60 < 5 LLD 0 /24 ) LLD ( 0/24 ) LLD ( 0/ 12) 0 Zn-65 < 10 LLD( 0 /24 ) LLD( 0 /24) LLD( 0 / 12) 0 Zr-Nb-95 < 5 LLD( 0 /24 ) LLD( 0 /24 ) LLD( 0 /12) 0 Cs-134 < 5 LLD( 0 /24 ) LLD( 0 /24 ) LLD( 0 /12) 0 Cs-137 < 5 LLD( 0 / 24 ) LLD( 0 /24 ) LLD( 0 /12) 0 B3a-La-140

< 10 LLD( 0 /24 ) LLD( 0 /24 ) LLD( 0 /12) 0 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) c Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM)2-7 Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM RTL A9.690E Enclosure 3 Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility:

Beaver Valley Power Station Unit I and Unit 2 Docket No.: 50-334 / 50-412 Location of Facility:

Beaver County. Pennsylvania Reporting Period: Calendar Year -2009 Medium: Surface Water Unit of Measurement: (pico Curies / liter)Type and Lower Number of Total Number Limit of All Indicator Locations Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction)

N Name Mean (fraction)

(" Name Mean (fraction) (b) Reported Performed LLD ( Range (bW Distance and Direction Range N Distance and Direction Range (b) Measurements 1-131 < 0.5 No. 49A Industry, PA 0.8 ( 43 / 52 ) 0 52 Upstream of 0.3 -2.4 Montgomery Dam 5.0 miles NE H-3 < 200 LLD( 0 /8 LLD( 0 /4 ) LLD( 0 /4 0 12 Gamma 36 Mn-54 < 5 LLD( 0 / 24 LLD( 0 /24 ) LLD( 0 / 12) 0 Fe-59 < 10 LLD( 0 /24 LLD( 0 /24 ) LLD( 0 /12) 0 Co-5 i< 5 LLD( 0 /24 LLD( 0/24 ) LLD( 0/12) 0 Co-60 < 5 LLD( 0 / 24 LLD( 0 /24 ) LLD( 0 /12) 0 Zn-65 < 10 LLD( 0 / 24 LLD( 0 /24 ) LLD( 0/12) 0 Zr-Nb-95 < 5 LLD( 0 / 24 LLD( 0 /24 ) LLD( 0/12) 0 Cs-134 < 5 LLD( 0 /24 LLD( 0 /24 ) LLD( 0 /12) 0 Cs-137 < 5 LLD( 0 /24 LLD( 0 /24 ) LLD( 0 /12) 0 Ba-La-140

< 10 LLD( 0 /24 ) LLD( 0 /24 ) LLD( 0 /12) 0 Nominal Lower Limit of Detection I I I I I I I I I I I Mean and range based upon detectable measurements only.Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM)2-8 Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility:

Beaver Valley Power Station Unit 1 and Unit 2 Docket No.: 50-334 / 50-412 Location of Facility:

Beaver County. Pennsylvania Reporting Period: Calendar Year -2009 Medium: Ground Water Unit of Measurement: (pico Curies / liter)RTL A9.690E Enclosure 3 Type and Lower Number of Total Number Limit of All Indicator Locations Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction)

Name Mean (fraction) cb) Name Mean (fraction)

N Reported Performed LLD (a) Range (b) Distance and Direction Range (b) Distance and Direction Range (b) Measurements H-3 < 200 LLD ( 0 /4 ) LLD ( 0 /4 ) No. 11Shippingport, PA LLD ( 0 /2 ) 0 6 Upstream 0.8 miles NE Gamma 6 Mn-54 < 5 LLD( 0 / 4 ) LLD( 0 /4 ) LLD( 0/2 ) 0 Fe-59 < 10 LLD( 0 /4 ) LLD( 0 /4 ) LLD( 0 /2) 0 Co-58 < 5 LLD( 0 /4 ) LLD( 0 /4 ) LLD( 0 /2 ) 0 Co-60 < 5 LLD( 0 /4 ) LLD( 0 /4 ) LLD( 0 /2 ) 0 Zn-65 < t0 LLD( 0 /4 ) LLD( 0 /4 ) LLD( 0 /2 ) 0 Zr-Nb-95 < 5 LLD( 0 /4 ) LLD( 0/4 ) LLD( 0 /2 ) 0 Cs-134 < 5 LLD 0/4 )LLD 0/4 )LLD 0/2 ) 0 Cs-137 < 5 LLD( 0 /4 ) LLD( 0 /4 ) LLD( 0 /2 ) 0 Ba-La-140

< 10 LLD( 0 /4 ) LLD( 0 /4 ) LLD( 0 /2 ) 0'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) c Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM)2-9 Beaver Valley Power Station 2008 Annual Radiological Enviromnental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility:

Beaver Valley Power Station Unit 1 and Unit 2 Docket No.: 50-334 / 50-412 Location of Facility:

Beaver County, Pennsylvania Reporting Period: Calendar Year -2009 Medium: Precipitation Water Unit of Measurement: (pico Curies / liter)RTL A9.690E Enclosure 3 Type and Lower Number of Total Number Limit of All Indicator Location Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) (b) Name Mean (fraction) (b) Name Mean (fraction)(")

Reported Performed LLD (a) Range (b) Distance and Direction Range Nb) Distance and Direction Range (b) Measurements H-3 < 200 195 ( 2 /8 No. 30 Shippingport, PA 208 ( 1/8 ) No. 48 Weirton, WV LLD ( 0 / 4 0 12 181 -208 Cook's Ferry Substation 208 208 Water Tower 0.5 miles ENE Collier Way 16.3 miles SSW Gamma 12 Mn-54 < 5 LLD( 0 / 8 ) LLD( 0 /8 LLD( 0 /4) 0 Fe-59 < 10 LLD( 0 / 8 ) LLD( 0 /8 LLD( 0 /4) 0 Co-58 < 5 LLD( 0 /8 ) LLD( 0 /8 LLD( 0/4 ) 0 Co-60 < 5 LLD( 0 / 8 ) LLD( 0 /8 ) LLD( 0/4 ) 0 Zn-65 < 10 LLD( 0 / 8 ) LLD( 0 /8 ) LLD( 0 /4) 0 Zr-Nb-95 < 5 LLD( 0/8 ) LLD( 0 /8 ) LLD( 0/4 ) 0 Cs-134 < 5 LLD( 0 / 8 ) LLD( 0 /8 ) LLD( 0 /4 ) 0 Cs-137 < 5 LLD( 0 / 8 ) LLD( 0 /8 ) LLD( 0/4 ) 0 Ba-La-140

< 10 LLD( 0 / 8 ) LLD( 0 /8 ) LLD( 0/4 ) 0 I I I I I I I I 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)

Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM)2-10 Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTA L. MONITORING PROGRAM SI MMA RV RTL A9.690E Enclosure 3 Name of Facility:

Beaver Valley Power Station Unit I and Unit 2 Docket No.: 50-334 / 50-412 Location of Facility:

Beaver County, Pennsylvania Reporting Period: Calendar Year -2009 Medium: Milk Unit of Measurement: (pico Curies / liter)Type and Lower Number of Total Number Limit of All Indicator Locatiow, Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) (b) Name Mean (fraction) (b) Name Mean (fraction) (b) Reported Performed LLD Range (5) Distance and Direction Range (b) Distance and Direction Range (b) Measurements (0 1-131 < 0.5 LLD ( 0 / 106 ) LLD ( 0 / 106 ) No. 96Burgettstown, PA LLD ( 0 /20 ) 0 126 Windsheimer Farm 10.4 miles SSW Sr-89 < 2.0 LLD C 0 / 74 ) LLD ( 0 /74 ) No. 96Burgettstown, PA LLD ( 0 /20 ) NA 94 Windsheimer Farm 10.4 miles SSW Sr-90 < 0.7 1.5 ( 66 / 74 ) No. 102 Aliquippa, PA 2.8 ( 14 / 14 ) No. 96 Burgettstown, PA 1.2 ( 20 / 20 ) NA 94 0.6 -4.0 Ferry Farm 2.0 -4.0 Windsheimer Farm 0.9 -1.9 3.3 miles SE 10.4 miles SSW Gamma 94 K-40 < 150 1415 ( 74 / 74 ) No. 102 Aliquippa, PA 1703 ( 14 / 14 ) No. 96 Burgettstown, PA 1410 ( 20 / 20 ) NA 1086- 1960 Ferry Farm 1484 -1960 Windsheimer Farm 1296 -1519 3.3 miles SE 10.4 miles SSW Mn-54 < 5 LLD( 0 / 74 ) LLD( 0 /74 ) LLD( 0 /20) NA Fe-59 < 10 LLD( 0 / 74 ) LLD( 0 /74 ) LLD( 0 /20) NA Co-58 < 5 LLD 0 / 74 ) LLD( 0 /74 ) LLD( 0 /20) NA Co-60 <5 LLD( 0 /74 ) LLD( 0/74 ) LLD( 0/20) NA Zn-65 < 10 LLD( 0 / 74 ) LLD( 0/74 ) LLD( 0 /20) NA Zr-Nb-95 < 5 LLD( 0 /74 ) LLD( 0/74 ) LLD( 0/20) NA Cs-134 < 5 LLD( 0 / 74 ) LLD( 0 /74 ) LLD( 0 /20) 0 Cs-137 < 5 LLD( 0 / 74 ) LLD( 0 /74 ) LLD( 0 /20) 0 Ba-La-140

< 10 LLD( 0 / 74 ) LLD( 0 /74 ) LLD( 0 /20) 0 Nominal Lower Limit of Detection Mean and range based upon detectable measurements only.Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM)2-11 Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

RTL A9.690E Enclosure 3 Name of Facility:

Beaver Valley Power Station Unit I and Unit 2 Docket No.: 50-334 / 50-412 Location of Facility:

Beaver Countv. Pennsylvania Reporting Period: Calendar Year -2009 Medium: Fish Unit of Measurement: (pico Curies / grain) Wet Type and Lower Number of Total Number Limit of All Indicator Locatior Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) (b) Name Mean (fraction) (b) Name Mean (fraction) (b) Reported Performed LLD (') Range (b) Distance and Direction Range (b) Distance and Direction Range (b) Measurements W No. 49A Industry, PA Gamma Upstream of Montgomery Dam 5.0 miles NE Mn-54 < 0.05 LLD( 0 / ) LLD( 0 / ) LLD( 0/ ) 0 Fe-59 < 0.10 LLD( 0 / ) LLD( 0 / ) LLD( 0/ ) 0 Co-58 < 0.05 LLD( 0 / ) LLD( 0/ ) LLD( 0/ ) 0 Co-60 < 0.05 LLD( 0 / ) LLD( 0 / ) LLD( 0/ ) 0 Zn-65 < 0.10 LLD( 0 / ) LLD( 0 / ) LLD( 0/ ) 0 Zr-Nb-95 < 0.01 LLD( 0 / ) LLD( 0/ ) LLD( 0/ ) NA Cs-134 < 0.05 LLD( 0 / ) LLD( 0 / ) LLD( 0/ ) 0 Cs-137 < 0.05 LLD( 0 / ) LLD( 0/ ) LLD( 0/ ) .0 Ba-La-140

< 0.01 LLD( 0 / ) LLD( 0/ ) LLD 0/ ) NA Nominal Lower Limit of Detection Mean and range based upon detectable measurements only.Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

'Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM)I I I I I I 2-12 Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

RTL A9.690E Enclosure 3 Name of Facility:

Beaver Valley Power Station Unit 1 and Unit 2 Docket No.: 50-334 / 50-412 Location of Facility:

Beaver County, Pennsylvania Reporting Period: Calendar Year -2009 Medium: Foodcrops Unit of Measurement: (pico Curies / gramn) Wet Type and Lower Number of Total Number Limit of All Indicator Locatiom Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) b Name Mean (fraction) (b) Name Mean (fraction)

Reported Performed LLD ý') Range (b) Distance and Direction Range (b) Distance and Direction Range (b) Measurements 1-131 < 0.06 LLD ( 0 /4 ) LLD( 0/4 ) LLD( 0 / 1) 0 5 Gamma 5 K-40 NA 1.95( 4/ 4 ) No. 46A Industry, PA 2.06 1 /1 ) No. 48AWeirton, WV 2.62 ( l1 1 NA 1.75 -2.13 Rosepiler Garden 2.06 -2.06 Weirton Area 2.62 -2.62 3.1 miles NNE 16.5 miles SSW Mn-54 NA LLD ( 0 /4 ) LLD( 0/4 ) LLD( 0/1 ) NA Fe-59 NA LLD ( 0 /4 ) LLD( 0 /4 ) LLD( 0/1 ) NA Co-58 NA LLD ( 0 /4 ) LLD( 0/4 ) LLD( 0 /1) NA Co-60 NA LLD ( 0 /4 ) LLD( 0 /4 ) LLD( 0/1 ) NA Zn-65 NA LLD ( 0 /4 ) LLD( 0/4 LLD( 0 /1) NA Zr-Nb-95 NA LLD ( 0 /4 ) LLD( 0/4 ) LLD( 0 /1 ) NA CS-134 0.04 LLD ( 0 /4 ) LLD( 0/4 ) LLD( 0/1 ) 0 C5-137 0.06 LLD ( 0 /4 ) LLD( 0/4 ) LLD( 0 /1 ) 0 Ba-La-140 NA LLD ( 0 /4 ) LLD ( 0/4 ) LLD( 0/1 ) NA Nominal Lower Limit of Detection Mean and range based upon detectable measurements only.Fraction of detectable measurements at specified locations is indicated in parentheses (fraction) c Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM)2-13 Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

RTL A9.690E Enclosure 3 I I I I Name of Facility:

Beaver Valley Power Station Unit 1 and Unit 2 Docket No.: 50-334 / 50-412 Location of Facility:

Beaver County. Pennsylvania Reporting Period: Calendar Year -2009 Medium: Feedstuff Unit of Measurement: (pico Curies / gram) Wet Type and Lower Number of Total Number Limit of All Indicator Location Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) (b Name Mean (fraction) (b) Name Mean (fraction) (b) Reported Performed LLD (a) Range (b) Distance and Direction Range (b) Distance and Direction Range (b) Measurements Gamma 11 Be-7 < 0.2 0.65 ( 4/ 11 ) No. 25 Searight Farm 0.65 4/ 11 ) No. 25 Searight Farm 0.65 ( 4/ 11) NA 0.39- 1.14 948 McCleary Road 0.39- 1.14 948 McCleary Road 0.39- 1.14 Hookstown, PA Hookstowo, PA 2.1 miles SSW 2.1 miles SSW K-40 <0.15 10.26( 11l 11 ) No. 25 Searight Farm 10.26 ( 1/ It ) No. 25 Searight Farm 10.26 ( .11 / 11 ) NA 8.35- 12.27 948 McCleary Road 8.35- 12.27 948 McCleary Road 8.35- 12.27 Hookstown, PA Hookstown, PA 2.1 miles SSW 2.1 miles SSW Mn-54 <0.02 LLD( 0 /11 ) LLD( 0/ 11 LLD( 0 / 11) NA Fe-59 < 0.04 LLD( 0 ) LLD 0/ 11 LLD( 0/ 11) NA Co-58 <0.02 LLD( 0 / 11 LLD( 0/ 11 ) LLD( 0 / 11) NA Co-60 < 0.02 LLD( 0 / 11 ) LLD( 0/11 ) LLD( 0/ 11) NA Zn-65 < 0.04 LLD( 0 /1 ) LLD( 0 / 11 ) LLD( 0/11) NA Zr-ND-95 < 0.03 LLD( 0 / 11 ) LLD( 0/ 11 ) LLD( 0/ 11) NA Ru-103 < 0.03 LLD( 0 / 11 ) LLD( 0/ 11 ) LLD( 0/ 11) NA 1-131 < 0.06 LLD( 0 / 11) LLD( 0 /11 ) LLD( 0/11) 0 Cs-134 < 0.04 LLD( 0 / 11 ) LLD( 0/11 ) LLD( 0/11) 0 Cs-137 < 0.06 LLD( 0 /11 ) LLD( 0 / 11 ) LLD( 0/11) 0 Ba-La-140

< 0.01 LLD( 0 / 11 ) LLD( 0/ 11 ) LLD( 0 / 11) NA Nominal Lower Limnit of Detection b Mean and range based upon detectable measurements only.Fraction of detectable measurements at specified locations is indicated in parentheses (fraction) a Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM)U I I I 2-14 Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility:

Beaver Valley Power Station Unit I and Unit 2 Docket No.: 50-334 / 50-412 Location of Facility:

Beaver County, Pennsylvania Reporting Period: Calendar Year -2009 Medium: Sediment (page 1 of 2)Unit of Measurement: (pico Curies / gram) Dry Type and Lower Number of total Number Limit of All Indicator Locations Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) (b) Name Mean (fraction) (b) Name Mean (fraction) (b) Reported Performed LLD (') Range Distance and Direction Range (b) Distance and Direction Range (b) Measurements Gamma 6 K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-La-140 TI-208 NA< 0.02< 0.03< 0.02* 0.02< 0.04< 0.03< 0.03< 0.06< 0.08* 0.03 NA 9.69( 4/ 4 7.97- 11.41 LLD( 0 /4 LLD( 0 /4 0.51( 1 /4 0.51- 0.51 0.61( 2 /4 0.34- 0.88 0.12 ( 1 /4 0.12- 0.12)'No. 50 Upstream of New Cumberland Dam 11.8 miles WSW No. 2A BVPS Outfall Vicinity 0.2 miles WSW No. 2A BVPS Outfall Vicinity 0.2 miles WSW No. 2A BVPS Outfall Vicinity 0.2 miles WSW No. 2A BVPS Outfall Vicinity 0.2 miles WSW No. 50 Upstream of New Cumberland Dam 11.8 miles WSW 11.23( 2 /2 11.05- 11.41 LLD( 0 /4 LLD( 0/4 0.51( 1 /2 0.51 -0.51 No. 49A Industry, PA Upstream of Montgomery Dam 5.0 miles NE 13.35( 212 )13.11- 13.59 LLD( 0/2 ))1 LLD LLD 0/2 )0/2)0.61 ( 2 /2 0.34- 0.88 0.12 ( 1 /4 0.12- 0.12 LLD ( 0/4 LLD( 0 /4 LLD( 0/4 )LLD( 0 /4 0.11 ( 3 / 4 0.07- 0.15 LLD( 0 /4 0.33( 4/4 )0.27- 0.39 No. 49A Industry, PA Upstream of Montgomery Dam 5.0 miles NE No. 49A Industry, PA Upstream of Montgomery Dam 5.0 miles NE No. 49A Industry, PA Upstream of Montgomery Dam 5.0 miles NE No. 49A Industry, PA Upstream of Montgomery Dam 5.0 miles NE No. 49A Industry, PA Upstream of Montgomery Darm 5.0 miles NE LLD( 0 / 2 LLD( 0 /2 LLD( 0/2 )LLD( 0/2 )LLD( 0/2 )0.11 ( 2/2 0.11- 0.11 NA NA NA NA NA NA NA NA 0 0 NA NA LLD( 0/4 LLD( 0/4 0.15( 2/2 0.14- 0.15 LLD( 0 /4 0.37( 2/2 0.35 -0.39 LLD( 0 / 2 0.42( 2 /2 0.41 -0.43))2-15 Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility:

Beaver Valley Power Station Unit 1 and Unit 2 Docket No.: 50-334 / 50-412 Location of Facility:

Beaver County, Pennsylvania Reporting Period: Calendar Year -2009 Medium: Sediment (page 2 of 2)Unit of Measurement: (pico Curies / gram) Dry Type and Lower Number of Totil Number Limit of All Indicator Location Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) (b) Name Mean (fraction) b) Name Mean (fraction)(b)

Reported Performed LLD ra) Range (b) Distance and Direction Range (b) Distance and Direction Range (b) Measurements (Bi-214 NA 0.79 ( 4 / 4 ) No. 50 Upstream of 0.90 ( 2 /2 ) No. 49A Industry, PA 1.08 ( 2 /2 ) NA 0.65- 0.91 New Cumberland Dam 0.88- 0.91 Upstream of 1.08- 1.08 11.8 miles WSW Montgomery Dam 5.0 miles NE Pb-212 NA 0.93 ( 4 /4 ) No. 50 Upstream of 1.10 ( 2 / 2 ) No. 49A Industry, PA 1.36 ( 2 /2 NA 0.69- 1.19 New Cumberland Dam 1.01- 1.19 Upstreamof 1.20- 1.51 11.8 miles WSW Montgomery Dam 5.0 miles NE Pb-214 NA 0.89 ( 4 /4 ) No. 50 Upstream of 0.97 ( 2 / 2 ) No. 49AIndustry, PA 1.15 ( 2/2 ) NA 0.79- 1.03 New Cumberland Dam 0.90- 1.03 Upstreamof 1.09- 1.20 11.8 miles WSW Montgomery Dam 5.0 miles NE 1Za-226 NA 1.79 ( 4 /4 ) No. 50 Upstream of 1.90 ( 2 / 2 ) No. 49A Industry, PA 2.40 ( 2 / 2 ) NA 1.45- 1.97 New Cumberland Dam 1.82- 1.97 Upstream of 2.32- 2.48 11.8 miles WSW Montgomery Dam 5.0 miles NE Ac-228 NA 0.99 ( 4 /4 ) No. 50 Upstream of 1.08 ( 2/2 ) No. 49A Industry, PA 1.35 ( 2 /2 ) NA 0.81 -1.12 New Cumberland Dam 1.03- 1.12 Upstream of 1.30- 1.39 11.8 miles WSW Montgomery Dam 5.0 miles NE I I I I I I I I I I I I Nominal Lower Limit of Detection Mean and range based upon detectable measurements only.Fraction of detectable measurements at specified locations is indicated in parentheses (fraction)

'Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM)I I I I U 2-16 Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility:

Beaver Valley Power Station Unit 1 and Unit 2 Docket No.: 50-334 / 50-412 Location of Facility:

Beaver County, Pennsylvania Reporting Period: Calendar Year -2009 Medium: Soil (page 1 of 2)Unit of Measurement: (pico Curies / gcam) Dry Type and Lower Number of Total Number Limit of All Indicator Location Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) (b) Name Mean (fraction) (b) Name I Mean (fraction) (b) Reported Performed LLD (') Range N5) Distance and Direction Range b) Distance and Direction Range (b) Measurements W Gamma 10 K-40 NA 12.43 ( 9 /9 ) No. 22 South of BVPS 17.18 ( 1 / 1 ) No. 48 Weirton, WV 14.16 ( 1/1 ) NA 9.42- 17.18 Transmission Line 17.18- 17.18 Water Tower 14.16- 14.16 0.3 miles SSE Collier Way 16.3 miles SSW Mn-54 NA LLD( 0 /9 LLD( 0 9 LLD( 0 / ) NA Fe-59 NA LLD( 0 /9 LLD( 0 /9 LLD( 0/1 ) NA Co-58 NA LLD( 0 / 9 ) LLD( 0 /9 ) LLD( 0/1 ) NA Co-60 NA LLD( 0 /9 ) LLD( 0 /9 ) LLD( 0/1 ) NA Zn-65 NA LLD( 0 /9 LLD( 0/9 ) LLD( 0/1 ) NA Zr-95 NA LLD( 0 /9 LLD( 0/9 ) LLD( 0 /1) NA Nb-95 NA LLD( 0 / 9 LLD( 0 /9 ) LLD( 0/1 ) NA Cs-134 NA LLD( 0 /9 LLD( 0 /9 ) LLD( 0/1 ) NA Cs-137 NA 0.20 ( 9 / 9 ) No. 13A Hookstown, PA 0.26 1 1 / 1 ) No. 48 Weirton, WV 0.25 ( 1 / 1 ) NA 0.13- 0.26 Old Meyer Farm 0.26- 0.26 Water Tower 0.25 -0.25 1.4 miles SW Collier Way 16.3 miles SSW No. 51A Aliquippa, PA 0.26 ( 1 / 1 Sheffield Substation 0.26 -0.26 8.0 miles SW 2-17 Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

I I I I Name of Facility:

Beaver Valley Power Station Unit 1 and Unit 2 Docket No.: 50-334/ 50-412 Location of Facility:

Beaver County, Pennsylvania Reporting Period: Calendar Year -2009 Medium: Soil (page 2 of 2)Unit of Measurement: (pico Curies / gram) Dry I Type and Lower Number of Total Number Limit of All Indicator Location Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) (b) Name Mean (fraction) (b) Name Mean (fraction) (b) Reported Performed LLD (') Range (b) Distance and Direction Range Nb) Distance and Direction Range (b) Measurements W Ba-La-140 NA LLD( 0 /9 ) LLD( 0 /9 ) LLD( 0 /1 ) NA TI-208 NA 0.36 ( 9 /9 ) No. 22 South of BVPS 0.48 ( 1 /1 ) No. 48Weirton, WV 0.36 ( 1 /1 ) NA 0.24- 0.48 Transmission Line 0.48- 0.48 Water Tower 0.36- 0.36 0.3 miles SSE Collier Way 16.3 miles SSW Bi-214 NA 0.83 ( 9 /9 ) No. 29A Beaver, PA 1.10 ( I / 1 ) No. 48 Weirton, WV 1.02 ( 1 /1 NA 0.57- 1.10 Nicol Farm 1.10- 1.10 Water Tower 1.02- 1.02 8.3 miles NE Collier Way 16.3 miles SSW Pb-212 NA 1.11 ( 9 /9 ) No. 29ABeaver, PA 1.48 ( 1 /I ) No. 48Weirton, WV 1.11 ( 1 / I NA 0.82- 1.48 Nicol Farm 1.48- 1.48 Water Tower 1.11 -1.11 8.3 miles NIE Corner Way 16.3 miles SSW Pb-214 NA 0.90 ( 9 /9 ) No. 29A Beaver, PA 1.18 ( 1 /1 ) No. 48 Weirton, WV 1.07 (1 /1 NA 0.57- 1.18 Nicol Farm 1.18- 1.18 Water Tower 1.07- 1.07 8.3 miles NE Collier Way 16.3 miles SSW Ra-226 NA 2.07 ( 9 / 9 ) No. 29A Beaver, PA 2.72 ( 1 / I ) No. 48 Weirton, WV 2.78 ( 1 / I NA 1.34- 2.72 Nicol Farm 2.72- 2.72 Water Tower 2.78- 2.78 8.3 miles NE Collier Way 16.3 miles SSW Ac-228 NA 1.13 ( 9 /9 ) No. 22 South of BVPS 1.40 ( I / I ) No. 48 Weirton, WV 1.10 ( 1 / 1 NA 0.72- 1.40 Transmission Line 1.40 -1.40 Water Tower 1.10- 1.10 0.3 miles SSE Corner Way 16.3 miles SSW 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)

SNonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM)2-18 I I I I I I I I I I I I I I I Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM RTL A9.690E Enclosure 3 Table 2-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Name of Facility:

Beaver Valley Power Station Unit I and Unit 2 Docket No.: 50-334 / 50-412 Location of Facility:

Beaver County, Pennsylvania Reporting Period: Calendar Year -2006 Medium: External Radiation Unit of Measurement: (mR / Quarter)Type and Lower Number of Total Number Limit of All Indicator Location Locations with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction)

() Name Mean (fraction) (b) Name Mean (fraction)

>b> Reported Performed LLD Range c> Distance and Direction Range (b) Distance and Direction Range Nb> Measurements Gamma 4.6 18.5 502 / 502 ) No. 112 BVPS Site 23.4 ( 8 / 8 ) No. 48 Weirton, WV 21.2 ( 8/8 0 510 12.9 -25.8 Perimeter Location 21.3 -25.8 Water Tower 20.2 -22.1 0.3 miles SSE Collier Way 16.4 miles SSW 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)

Nonroutine Reported Measurements (

Reference:

ODCM procedure 1/2-ODC-3.03, Attachment Q, Control 3.12.1)NA = Not Applicable (Naturally Occurring Radionuclides Not required by ODCM)2-19 Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM RTL A9.690E Enclosure 3 Table 2-3 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 Medium or Pathway Analysis and Total Lower Limit All Indicator Locations Sampled Number of Analysis of Detection Mean, (f) Range (Unit of Measurement)

Performed (LLD)Sediments Gross Alpha (0) ....(pico Curie/gram) dry Gross Beta (33) 1 18 (33/33) 5 -30 Sr-90 (0) ....U-234, 235,238 (0) --Gamma (33) -- 13 (33/33) 2 -30 K-40 1.5 13 (33/33) 2 -30 Cs-137 0.1 0.4 (21/33) 0.1 -0.6 Zr/Nb-95 0.05 0.8 (12/33) 0.2 -3.2 Ce-144 0.3 0.5 (3/33) 0.4 -0.7 Ru-106(a) 0.3 1.5 (3/33) 1.3 -1.8 Others --< LLD Foodcrops Gamma (8) ....(pico Curie /gram) dry K-40 1 33 (8/8) 10 -53 Cs-137 0.1 0.2 (1/8) --Zr/Nb-95 0.05 0.2 (1/8) --Ru-106(a) 0.3 0.8 (1/8) --Others -- < LLD Feedstuff Gross Beta (80) 0.05 19 (80/80) 8 -50 (pico Curie /gram) dry Sr-89 (81) 0.025 0.2 (33/81) 0.04 -0.93 Sr-90 (81) 0.005 0.4 (78/81) 0.02 -0.81 Gamma (81) ....K-40 1 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 Gross Alpha (0) --..-Template Samples -Gross Beta (64) 1 22 (64/64) 14 -32 Sr-89 (64) 0.25 0.4 (1/64) --(pico Curie /gram) dry Sr-90 (64) 0.05 0.3 (48/64) 0.1 -1.3 U-234, 235,238 (0) --Gamma (64) ....K-40 1.5 13 (63/64) 5 -24 Cs-137 0.1 1.5 (56/64) 0.1 -6.8 Ce-144 0.3 1.1 (7/64) 0.2 -3 Zr/Nb-95 0.05 0.3 (13/64) 0.1 -2 Ru-106(a) 0.3 1.1 (3/64) 0.5 -2 Others --< LLD (f) Fraction of detectable measurements at specified location.I I I I I I I I I I I I I U I I I I 2-20 I Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Table 2-3 (Continued)

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 Medium or Pathway Analysis and Total Lower Limit All Indicator Locations Sampled Number of Analysis of Detection Mean, (f) Range (Unit of Measurement)

Performed (LLD)Soil Gross Alpha (0) ....-Core Samples -Gross Beta (8) 1 21 (8/8) 16 -28 (pico Curie /gram) dry Sr-89 (8) 0.25 < LLD Sr-90 (8) 0.05 0.2 (5/8) 0.08 -0.5 Gamma (8) ....K-40 1.5 13 (8/8) 7 -20 Cs-137 0.1 1.2 (7/8) 0.2 -2.4 Co-60 0.1 0.2 (1/8) --Others < LLD Surface Water Gross Alpha (40) 0.3 0.75 (5/40) 0.6- 1.1 (pico Curie / liter) Gross Beta (120) 0.6 4.4 (120/120) 2.5- 11.4 Gamma (1) 10-60 < LLD Tritium (121) 100 300 (120/121) 180-800 Sr-89 (0) ....Sr-90 (0)C-14 (0)Drinking Water 1-131 (0) ....(pico Curie / liter) Gross Alpha (50) 0.3 0.6 (4/50) 0.4 -0.8 Gross Beta (208) 0.6 3.8 (208/208) 2.3 -6.4 Gamma (0) .I.Tritium (211) 100 310 (211/211) 130- 1000 C-14 (0) ....Sr-89 (0) --Sr-90 (0) --Ground Water Gross Alpha (19) 0.3 < LLD (pico Curie / liter) Gross Beta (76) 0.6 2.9 (73/75)(b) 1.3 -8.0 Tritium (81) 100 440 (77/81) 80 -800 Gamma (1) 10-60 < LLD Air Particulates Gross Alpha (188) 0.001 0.003 (35/188) 0.002 -0.004 and Gaseous Gross Beta (927) 0.006 0.07 (927/927) 0.02 -0.32 (pico Curie /cubic meter) Sr-89 (0) ....Sr-90 (0) ....1-131 (816) 0.04 0.08 (2/816) 0.07 -0.08 Gamma (197) ....Zr/Nb-95 0.005 0.04 (122/197) 0.01 -0.16 Ru-106 0.010 0.04 (50/197) 0.02 -0.09 Ce-141 0.010 0.02 (3/197) 0.01 -0.04 Ce-144 0.010 0.02 (44/197) 0.01 -0.04 Others < LLD (f) Fraction of detectable measurements at specified location.2-21 Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM RTL A9.690E Enclosure 3 Table 2-3 (Continued)

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 Medium or Pathway Analysis and Total Lower Limit All Indicator Locations Sampled Number of Analysis of Detection Mean, (f) Range (Unit of Measurement)

Performed (LLD)Milk 1-131 (91) 0.25 0.6 (4/91) 0.3 -0.8 (pico Curie / liter) Sr-89 (134) 5 7 (4/134) 6 -11 Sr-90 (134) 1 5.3 (132/134) 1.5 -12.8 Gamma (134) --Cs-137 10 13 (19/134) 11 -16 Others < LLD External Radiation y -Monthly (599) 0.5 mR* 0.20 (599/599) 0.08 -0.51 (milli Roentgen / day) y -Quarterly (195) 0.5 mR* 0.20 (195/195) 0.11 -0.38 y -Annual (48) 0.5 mR* 0.19 (48/48) 0.11 -0.30 Fish Gross Beta (17) 0.01 1.9 (15/17) 1.0 -3.2 (pico Curie / gram) wet Sr-90 (17) 0.005 0.14 (17/17) 0.02 -0.50 Gamma (17) 0.5 K-40 2.4 (17/17) 1.0 -3.7 Others < LLD LLD in units of mR -Lower end of useful integrated exposure detectability range for a passive radiation detector (TLD).(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).(f) Fraction of detectable measurements at specified location.I I I I I I I I I I I I I I I I I I I 2-22 Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM B. Air Monitoring I. Characterization of Air and Meteorology The air in the vicinity of the site contains pollutants typical for an industrial area. Air flow is generally from the southwest in summer and from the northwest in the winter.2. Air Sampling Program and Analytical Techniques

a. Program The air is sampled for gaseous radioiodine and radioactive particulates at each of ten (10)offsite air sampling stations.

The locations of these stations are listed in Table 2-1 and shown on a map in Figure 2-1.Samples are collected at each of these stations by continuously drawing two cubic 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 collected on a weekly basis.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 from short-lived naturally occurring radioactivity (e.g.; radon and thorium), the glass fiber filter papers are decayed prior to performing beta analysis in a low background counting system.b. Procedures.

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 and analyzing it'in a low background, gas flow proportional counter.Gamma Emitter Analysis of Filter Paper: Analysis is performed by sta~king all of the glass fiber filter papers collected from each monitoring station during the quarter and scanning this composite on a high resolution germanium gamma spectrometer.

Iodine-131 Analysis of Charcoal Cartridge:

Analysis is performed by a gamma scan of each charcoal cartridge.

2-23 Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM 3. Results and Conclusions A summary of data is presented in Table 2-2. i a. Airborne Radioactive Particulates Gross Beta: A total of five-hundred-nineteen (519) weekly samples from ten (10) locations were analyzed for gross beta. Results were comparable to previous years. Figure 2-2 indicates the weekly average concentration of gross beta in air particulates.

During the period 03/23/09 -03/30/09, the Gross Beta Results were unusually low.Specifically, the Gross Beta results for the ten (10) air particulate sample stations ranged from I 0.014 to 0.019 pCi/cubic meter, whereas the cumulative average ranged from 0.021 to 0.027 pCi/cubic meter. As noted, this condition existed at all nine (9) indicator locations and at the one (1) control location.

This issue was discussed with the REMP Administrators at the other i two FENOC sites (i.e. Davis-Besse Nuclear Power Plant and the Perry Nuclear Power Plant), and they also noticed similar decreases in Gross Beta results during this period. There is no consequence to unusually low sample results and the cause is most likely due to cosmic interference.

This issue is documented in SAP Order 200197646-0820.

During the period 05/26/09 -06/01/09, the Gross Beta Results were unusually low.Specifically, the Gross Beta results for the ten (10) air particulate sample stations ranged from 0.010 to 0.015 pCi/cubic meter, whereas the cumulative average ranged from 0.020 to 0.025 pCi/cubic meter. As noted, this condition existed at all nine (9) indicator locations and at the one (1) control location.

This issue was discussed with the REMP Administrators from two other FENOC sites (i.e. Davis-Besse Nuclear Power Plant and Perry Nuclear Power Plant), and they also noticed similardecreases in Gross Beta results during this period. There is no consequence to unusually low sample results and the cause is most likely due to cosmic interference.

This issue is documented in SAP Order 200197646-0820.

During the period 06/15/09 -06/22/09, the Gross Beta Results were unusually low. i Specifically, the Gross Beta results for the ten (10) air particulate sample stations ranged from 0.0 13 to 0.022 pCi/cubic meter, whereas the cumulative average ranged from 0.021 to 0.025 pCi/cubic meter. As noted, this condition existed at all nine (9) indicator locations and at the I one (1) control location, although the control location did not decrease as much. This issue was discussed with the REMP Administrators from two other FENOC sites (i.e. Davis-Besse Nuclear Power Plant and Perry Nuclear Power Plant), and they also noticed similar decreases i in Gross Beta results during this period. There is no consequence to unusually low sample results and the cause is most likely due to cosmic interference.

This issue is documented in SAP Order 200197646-0820.

During the period 10/05/09 -10/12/09, the Gross Beta Results were unusually low.Specifically, the Gross Beta results for the ten (10) air particulate sample stations ranged from 0.009 to 0.016 pCi/cubic meter, where as the cumulative average ranged from 0.021 to 0.026 pCi/cubic meter. As noted, this condition existed at all nine (9) indicator locations and at the one (1) control location.

There is no consequence to unusually low sample results and the cause is most likely due to cosmic interference.

This issue is documented in SAP Order 200197646-0820.

I 2-24i Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Gamma Spectrometry:

The weekly air particulate samples were composited into forty (40)quarterly samples which were analyzed by gamma spectrometry.

Naturally occurring Beryllium-7 was identified in thirty-six of thirty-six (36 of 36) indicator samples, and four of four (4 of 4) control samples. No other radionuclides were detected.

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 shown on Figure 2-2.Deviations from Required Sampling and Analysis Schedule:

There were some deviations from the required airborne particulate sampling and analysis schedule during the report period. Specifically, the following events occurred: During the sampling period of 06/22/09 -06/29/09, the Air Particulate and Iodine Sampling Station at Shippingport, PA, Cooks Ferry Substation (Site No. 30, 0.43 miles ENE) was interrupted for 83 hours9.606481e-4 days <br />0.0231 hours <br />1.372354e-4 weeks <br />3.15815e-5 months <br /> and 53 minutes. The problem was traced to tripped breaker that apparently occurred during thunderstorm during that time period.On 07/06/09, the Air Particulate and Iodine Sampling Station at Industry -Mckeel's Service Rt. 68, (Site No. 46.1, 2.28 miles NNE/NE) did not pass the leak check after the Air Particulate and Iodine sampling media were collected.

The station sample pump was replaced and the leak check passed. The station was then calibrated and returned to service the same day.On 07/20/09, the Air Particulate and Iodine Sampling Station at Weirton Water Tower, Collier Way (Site No.48, 16.40 miles SSW) was found with "0.0" flow rate on Totalizer.

Air Particulate and Iodine Sampling media were changed and the Air Sample Station was returned to service. Sample volume for the week was estimated.

During the sampling period of 08/10/09 -08/17/09, the Air Particulate and Iodine Sampling Station at Brunton's Dairy Farm (Site No. 27, 6.14 miles, SE), was found out of service due to a power outage. Total out of service time was estimated to be 164 hours0.0019 days <br />0.0456 hours <br />2.71164e-4 weeks <br />6.2402e-5 months <br /> and 30 minutes. Air Particulate and Iodine Sampling media were changed, the breaker was reset, and the air sampling station was returned to service on 08/17/09.During the sampling period of 08/17/009

-08/24/09, the Air Particulate and Iodine Sampling Station at Shippingport, Cook's Ferry S.S. (Site No. 30, 0.43 miles, ENE) was found out of service due to a tripped breaker, possibly from storms during that week. The total out of service time was approximately 86 hours9.953704e-4 days <br />0.0239 hours <br />1.421958e-4 weeks <br />3.2723e-5 months <br /> and 16 minutes for the week, and the air sampling station was returned to service on 08/24/09.During the sampling period of 08/17/09 -08/24/09, the Air Particulate and Iodine Sampling Station at East Liver Pool Water Department (Site No. 47, 4.88 miles, WNW) was found out of service due to a tripped breaker, possibly from storms during that week. The total out of service time was approximately 99 hours0.00115 days <br />0.0275 hours <br />1.636905e-4 weeks <br />3.76695e-5 months <br /> and 35 minutes for the week, and the air sampling station was returned to service on 08/24/09.SINCE BVPS uses ten (10) airborne particulate sample stations versus five (5) required by the ODCM, THEN there was no consequence to interruption of sample collection during these periods. These conditions are documented in SAP order 200197646-0850.

2-25 Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Summary: Based on the analytical results, the operation of BVPS did not contribute any measurable increase in air particulate radioactivity during the report period.b. Airborne Radioiodine Iodine-131:

A total of five-hundred-nineteen (519) weekly charcoal filter samples were analyzed for Iodine-131.

No detectable concentrations were present at any locations.

Deviations from Required Sampling and Analysis Schedule:

The deviations are the same as I described above for airborne particulates.

Summary: Based on analytical results, the operation of BVPS did not contribute any I measurable increase in airborne radioiodine during the report period.I I I I I I I I I I I 2-26 I Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Figure 2-1 RTL A9.690E Enclosure 3 Environmental Monitoring Locations

-Air Sampling Stations Site Distance Sample Type No. Sector (miles) Sample Point Description 13 11-SW 1.49 Hookstown, PA (Old Meyer Farm)27 7-SE 6.14 Aliquippa, Pa (Brunton Farm)28 1-N 8.60 Beaver Falls, PA (Sherman Farm)29B 3-NE 7.97 Beaver, PA (Friendship Ridge)Air Particulate 30 4-ENE 0.43 Shippingport, PA (Cook's Ferry Substation)

& Radioiodine 32 15-NW 0.75 Midland, PA (North Substation

-Rt. 68)2-NNE 46.1 3-NE 2.28 Industry, PA (McKeels Service -Rt. 68)47 14-WNW 4.88 East Liverpool, OH ( Water Department) 48 10-SSW 16.40 Weirton, WV (Water Tower, Collier Way)51 5-E 8.00 Aliquippa, PA (Sheffield Substation) 2-27 Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM RTL A9.690E Enclosure 3 Figure 2-2 Graph of Annual Average Concentration:

Gross Beta in Air Particulates Beaver Valley Power Station REM P Environmental Air Particulate Samples -Gross Beta 0.20 0.18 ----------------

&-----------------------------------

E 0.16 -----Average of 9 Indicator Locations 0. --- A --- Control Location LO 0.14 -- --- -- -----------

Pre-Operational value (0.07 pQi/cubic meter)0.12 --Required LLD (0.01 pi / cubic meter)0D -No Reporting Level for Gross Beta E 0.10 --_-_-__-_-_--_-_-__-_-_--_-_-__-_-_--_-_-_

0 0.08--------------

0 0.04 -- -... -. .-----U ---~ 0.02------------------------

0.00 I i i I I I I IO:r :0 0 0:O coO C¢ I I I I I I I I I I 2-28 Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM C. Monitoring of Shoreline Stream Sediment and Soil 1. Characterization of Shoreline Stream Sediment and Soil 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.2. Sampling Program and Analytical Techniques

a. Program Shoreline stream sediment were collected semi-annually above the Montgomery Dam, in the vicinity of the BVPS outfall structure, and above the New Cumberland Dam. A Ponar or Eckman dredge is used to collect the sample. The sampling locations are also listed in Table 2-1 and are shown in Figure 2-3.Although not required by the ODCM, soil samples are collected every three years. They were collected at each of ten (10) locations during 2009 and are scheduled to be collected again in 2012. At each location, twelve (12) core samples (3" diameter by 2" deep) are gathered at prescribed 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 such a manner as to assure representative undisturbed samples.Sampling locations are listed in Table 2-1 and are shown in Figure 2-3.Shoreline stream sediment and soil are analyzed for gamma-emitting radionuclides.
b. Analytical Procedures Gamma Ermitter Analysis of Stream Sediment:

Analysis is performed in a 300 ml plastic bottle, which is analyzed by gamma spectrometry.

Gamma Emitter Analysis of Soil: Although not required by the ODCM, analysis is performed in a 300 ml plastic bottle, which is analyzed by gamma spectrometry 2-29 Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM 3. Results and Conclusions A summary of the analysis 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 2-4 and Figure 2-5.a. Shoreline Stream Sediment Gamma Spectrometry:

A total of six (6) sediment samples were analyzed by gamma spectrometry during the report period. Naturally occurring Potassium-40, Thalium-208, Lead-212, Lead-214, Bismuth-214, Radium-226 and Actinum-228, were detected in four of four (4 of 4) indicator samples and two of two (2 of 2) control samples.Cesium-137:

This radionuclide was identified in three of four (3 of 4) indicator samples and two of two (2 of 2) control samples. The results were similar to previous years (current years range = 0.07 to 0.15 pico Curie / gram) and less than the pre-operational level of 0.4 pico Curie / gram. Also, SINCE Cesium-137 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 tests.Cobalt-58:

Radionuclide Cobalt-58 was identified in one of four (1 of 4) indicator samples and zero of two (0 of 2) control samples. The samples which indicated Cobalt-58 was I obtained at the shore line of the main outfall facility.

The results were similar to previous years (current years range = 0.51 to 0.51 pico Curie / gram), although this data is NOT currently less than the pre-operational level of 0.098 pico Curie / gram. I Cobalt-60:

Radionuclide Cobalt-60 was identified in two of four (2 of 4) indicator samples and zero of two (0 of 2) control samples. The samples that indicated Cobalt-60 were obtained at the shore line of the main outfall facility.

The results were similar to previous years (current years range = 0.34 to 0.88 pico Curie / gram), although this data is NOT currently less than the pre-operational level of 0.4 pico Curie / gram.Zinc-65: Radionuclide Zinc-65 was identified in one of four (1 of 4) indicator samples and zero of two (0 of 2) control samples. The samples that indicated Zinc-65 were obtained at the shore line of the main outfall facility.

Although this data is NOT currently less than the pre-operational level of 0.4 pico Curie / gram, it is not an unlikely result for shoreline stream sediment near the main outfall. The plant discharges this radionuclide in liquid effluent releases.Deviations from Required Sampling and Analysis Schedule:

There were no deviations from the required sediment sampling and analysis schedule during the report period.Summary: The identification of Cobalt-58, Cobalt-60 and Zinc-65 in 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 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 2-30 Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM b. Soil Gamma Spectrometry:

A total of ten (10) soil samples were analyzed by gamma spectrometry during the report period. Naturally occurring Potassium-40, Thalium-208, Lead-212, Lead-214, Bismuth-214, Radium-226 and Actinum-228 was detected in nine of nine (9 of 9) indicator samples and one of one (1 of 1) control samples.Cesium-137:

This radionuclide was identified in nine of nine (9 of 9) indicator samples and one of one (1 of 1) control samples. SINCE Cesium-137 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 tests.Deviations from Required Sampling and Analysis Schedule:

There were no deviations from the required sediment sampling and analysis schedule during the report period.Summary: The identification of Cesium-137 in the soil surrounding BVPS is not unusual.The analyses are consistent with 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.2-31 Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM RTL A9.690E Enclosure 3 I I I Figure 2-3 Environmental Monitoring Locations

-Shoreline Sediments and Soil I I I I I I I I I I I I I I I 2-32 I Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Figure 2-4 Graph of Annual Average Concentration:

Cesium-137, Cobalt-58

& Cobalt-60 in Sediment Beaver Valley Power Station REM P Cs-137 Sediment Trends -Outfall Vicinity 1000.00 100.00 E E 1.00 8 e-...- Cs-137* Control Location Cs- 137--Cs- 137 Pre-operational Results (0.4 pCtgm)-Cs-137 Required LLD (180 -No Reporting Level lor Sedirrent--.- ..--- -. -. -° -.-.* -. -. ----0.10 0.01 1111o 110 'It" 1411 1115 1110 "bi 1101 114, "', lqp 1161 le e e lop 10" e Beaver Valley Power Station REMP Co-58 & Co-60 Sediment Trends -Outfall VicinityI 100.00 10.00 a E 1.00 L)00.10 0.01--- CO-58 Unit 2 Fre-Operational Mean: Co-58 (0.098 pcVgm)A Co-60 Unit 2 Pre-Operational Mean: Co-60 (0.40 pCi/gram)-No Required LLD for 0o-58 or Co-60-No Reproting Linit for 0o-58 or Co-60----------

.I i--------------------------------------

Atp A A A 1k-A -------A / k--'-----------------------------------------

j ~A A it\ I ~A A A 11 N/ A'I

  • 5 -S I 'I&..a' u-il b'I I, a I NIIo11 'l I'l N 1ý 116 "Z N e 114 144 N@ý 110 I'll e l P 2-33 Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Figure 2-5 Graph of Annual Average Concentration:

Cesium-137 in Soil RTL A9.690E Enclosure 3 Beaver Valley Power Station REM P Cs-137 Soil Trends (Tri-Ennial)

I I 0.CL 1.4 -1.2 1.0 -0.8 0.6 0.4 0.2 0.0--------------------

--- Cs-137--- Control Location Pre-operational Cs- 137 (1.2 pa/ gram)No Reporting Level for Soil C~, '1-@ra 2-34 Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM D. Monitoring of Feedstuff and Foodcrops 1. Characterization of Farm Products According to the 2007 Census of Agriculture

('), there were 824 farms in Beaver County. Total market value of production (Crops and Livestock) was $15,187,000.00.

Some of the principal sources of revenue (>$50,000.00) are as follows: Milk and Other Dairy Products from Cows $5,647,000.00 Nursery, Greenhouse, Floriculture and Sod $2,813,000.00 Grains, Oil Seeds, Dry Beans and Dry Peas $1,243,000.00 Other Crops and Hay $1,120,000.00 Vegetables, Melons, Potatoes and Sweet Potatoes $989,000.00 Fruits, Tree Nuts and Berries $449,000.00 Poultry and Eggs $327,000.00 Cut Christmas Trees, and Short Rotation Woody Crops $204,000.00 Horses, Ponies, Mules, Burros, and Donkeys $182,000.00 Sheep, Goats and their Products $90,000.00 Hogs & Pigs Undisclosed Amount Aquaculture Undisclosed Amount Cattle and Calves Undisclosed Amount Other Animals and Other Animal Products Undisclosed Amount (1) http://www.agcensus.usda.gov/Publications/2007/Online-Highlights/County-Profiles/Pernsylvania/index.asp 2-35 Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM 2. Sampling Program and Analytical Techniques

a. Program I Feedstuff:

Although not required by the ODCM, representative samples of Feedstuff (cattle feed) are collected monthly from the nearest dairy farm (Searight Dairy). See l Figure 2-6. Each sample is analyzed by gamma spectrometry.

Foodcrops (leafy vegetables):

Foodcrops are collected at garden locations during the growing season. Leafy vegetables, (e.g.; cabbage) are obtained from Shippingport, Georgetown, and Industry, Pennsylvania.

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-131.

b. Procedures 3 Gamma Emitter Analysis of Foodcrops:

Analysis is performed by scanning a dried, homogenized sample with a gamma spectrometry system. A high resolution germanium detector is utilized with this system. Samples of feedstuff and foodcrops are loaded into I tare weight 300 or 150 ml plastic bottles or I-liter Marinelli containers, weighed and the net weight of the sample is determined prior to scanning for gamma emitters.Gamma Emitter Analysis of Feedstuff:

Although not required by the ODCM, analysis is performed by scanning a dried, homogenized sample with a gamma spectrometry system.A high resolution germanium detector is utilized with this system. Samples of feedstuff and foodcrops are loaded into tare weight 300 or 150 ml plastic bottles or I-liter Marinelli containers, weighed and the net weight of the sample is determined prior to scanning for gamma emitters.Iodine-131 Analysis of Foodcrops:

Analysis is performed by radiochemistry.

A stable iodide canrier 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 I dissolved in water, filtered and treated with sodium hypochlorite.

The iodate is then reduced to iodine with hydroxylamine hydrochloride and is extracted into toluene. It is then back-extracted as iodide into sodium bisulfite solution and is precipitated as I palladium iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchet for low level beta counting.I I i I 2-36 3 Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM 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 shown on Figure 2-7.a. Feedstuff Gamma Spectrometry:

Although not required by the ODCM, a total of eleven (11) samples were analyzed by gamma spectrometry.

Naturally occurring Potassium-40 was identified in eleven of eleven (11 of 11) samples. Naturally occurring Beryllium-7 was found in four of eleven (4 of 11) samples.Deviations from Required Sampling and Analysis Schedule:

The September monthly Feedstuff sample was not obtained.

A monthly Feedstuff sample from REMP Sample Site#25, Searight's Dairy, is required per procedure 1/2-ENV-02.01, but is NOT required per the BVPS Offsite Dose Calculation Manual (ODCM). REMP procedures'and forms were enhanced to prevent future occurrences.

This condition was documented in CR 09-66654 and SAP Order 200197646-0880.

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 measurable increase in radioactivity in the feedstuff in the vicinity of the site during the report period b. Foodcrops Iodine-131:

A total of five (5) samples were analyzed for Iodine-131.

No detectable concentrations were present in the four (4) indicator samples or the one (1) control sample.Gamma Spectrometry:

A total of five (5) samples were analyzed by gamma spectrometry.

Naturally occurring Potassium-40 was identified in four of four (4 of 4) indicator samples and one of one (lof 1) control samples. No other radionuclides were identified.

Deviations from Required Sampling and Analysis Schedule:

There were no deviations from the required foodstuff sampling and analysis schedule during the report period.Summary: The data from the foodcrops analyses was consistent with previous data. Based on the analytical results, the operation of BVPS did not contribute any measurable increase in radioactivity in the foodcrops in the vicinity of the site during the report period.2-37 Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM RTL A9.690E Enclosure 3 Figure 2-6 I I I I I I I I I I I I I I I I I I I Environmental Monitoring Locations

-Feedstuff and Foodcrops Sample Site Distance Type No. Sector (miles) Sample Point Description Feed 25 10-SSW 2.10 Hookstown, PA (Searight Farm)10A 4-ENE 0.8 Shippingport, PA Food 10B 4-ENE 1.0 Shippingport, PA 15A 14-WNW 3.6 Georgetown, PA 46A 3-NE 3.1 Industry, PA 48B 10-SSW 16.5 Weirton, WV 2-38 Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM RTL A9.690E Enclosure 3 Figure 2-7 Graph of Annual Average Concentration:

Cesium-137 in Feedstuff and Foodcrops Beaver Valley Power Station REM P Cs-137 Feedstuff and Foodcrops Trends*---.--- Cs-137 (Feedstuff)-o---- Cs-137 (Foodcrops)

Cs-137 Pre-operational Results 10 ----------------

Cs-137 Required LLD (80 p01/kg) Wet ---,-No Reporting Level for Feed of Food EC0 v 1 2-39 Beaver Valley Power Station RTL A9.690E I 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM i E. Monitoring of Local Cow and Goat Milk 1. Description

-Milch Animal Locations Samples of fresh milk are obtained from milch animals at locations and frequencies noted in i Table 2-1. The milk is analyzed for its radioiodine content, gamma emitters, Strontium-89 and Strontium-90.

Detailed field surveys are performed during the grazing season to locate and enumerate 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 two (2) reference dairy farms within a 10-mile radius of the BVPS. These milk samples were obtained at the Searight Dairy Farm (2.1 miles SSW)and the Brunton Dairy Farm (6.1 miles SE).Cow milk and goat milk were also collected from two (2) other dairy farms within a 10- I mile radius of the BVPS site. The goat milk samples obtained at the Ferry Farm (3.3 miles SE) and the cow milk samples obtained at the Halstead Dairy Farm (5.1 miles SSW) were selected based on milch animal surveys and evaluations of meteorological data (i.e.; 1 deposition parameters).

They were added to the sampling program to ensure the highest potential milk pathway for radioiodine uptake is evaluated.

The dairies are subject to change based upon availability of milk or when more recent data (milch animal census, I and/or change in meteorological conditions) indicate other locations are more appropriate.

Cow milk was also collected from the one (1) control location dairy farm outside of the 10-mile radius. These milk samples were obtained at the Windsheimer Dairy Farm (10.4 miles SSW).The cow milk sample from the Searight Dairy Farm (2.1 miles SSW) is collected and i analyzed weekly for Iodine-131 using a method that ensures a high sensitivity.

Samples from each of the other dairies are collected monthly when cows are indoors and bi-weekly when cows are grazing. The monthly and/or bi-weekly sample is analyzed for principle gamma emitters (including Cesium-137 by high resolution germanium gamma spectrometry), and Iodine-131 high sensitivity analysis.

Although not required by the ODCM, the monthly and/or bi-weekly sample is also analyzed for Strontium-89, Strontium-90.

It was determined early in the year that all doe goats from the Collin's Dairy Farm (3.5 miles SE) would be dry for the entire milking season. The Ferry Farm (3.3 miles SE)agreed to participate in the sampling program during the milking season. Both sampling locations will be evaluated during 2010 for participation in the sampling program. I I 2-40 I Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM The location of each is shown in Figure 2-8 and described below.RTL A9.690E Enclosure 3 Approximate Distance and Direction Collection Number of Animals from Midpoint between Period being Milked Unit 1 and Unit 2 Reactor 25 Searight Dairy 40 Cows 2.1 miles SSW January thru 948 McCleary Road December Hookstown, PA 27a Brunton Dairy 101 Cows 6.1 miles SE January thru 3681 Ridge Road. December Aliquippa, PA 69 Collins Dairy 0 Goats 3.5 miles SE Not Applicable:

289 Calhoun Road No goat milk Aliquippa, PA available during 2009 96 Windsheimer Dairy 80 Cows 10.4 miles SSW January thru RD #11 December Burgettstown, PA Ferry Farm 2 Goats 3.3 miles SE March thru 102* 227 Calhoun Rd September Aliquippa, PA Halstead Dairy 67 Cows 5.1 miles SSW January thru 113" 104 Tellish Drive December Hookstown, PA* Highest potential pathway dairies based on evaluation of deposition parameters 2-41 Beaver Valley Power Station RTL A9.690E I 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM b. Procedure Iodine-131 Analysis of Milk: The milk samples are chemically prepared, and then analyzed with a low-level beta counting system. 3 Gamma Emitter Analysis of Milk: This is determined by gamma spectrometry analysis of a 1 liter Marinelli container of milk.Strontium-90 Analysis of Milk: Although not required by the ODCM, the milk 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 purified in all samples I 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 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 infer Strontium-90 activity.Strontium-89 Analysis of Milk: Although not required by the ODCM, the Strontium-89 I activity is determined by precipitating strontium carbonate (SrCO 3) from the sample after yttrium separation.

This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm 2 aluminum absorber for low level beta counting.

Chemical yields of strontium and yttrium are determined by gravimetric means.3. Results and Conclusions A summary of the analysis results during the report period are listed in Table 2-2. A trend graph of Iodine-131 and Strontium-90 analyses (including the pre-operational period through I the report period) is shown on Figure 2-9.a. Strontium-89:

Although not required by the ODCM, a total of ninety-four (94) milk 3 samples were analyzed for Strontium-89 during the report period. Strontium-89 was not detected in any of the seventy-four (74) indicator samples, nor was it detected in any of the twenty (20) control samples. i b. Strontium-90:

Although not required by the ODCM, a total of ninety-four (94) milk samples were analyzed for Strontium-90 during the report period. Strontium-90 was detected in sixty-six of seventy-four (66 of 74) indicator samples and twenty of twenty (20 of 20) control samples. The levels detected were attributable to previous nuclear weapons tests and are within the normally expected range. n c. Gamma Spectrometry:

A total of ninety-four (94) milk samples were analyzed by gamma spectrometry during the report period. Naturally occurring Potassium-40 was present in seventy-four of seventy-four (74 of 74) indicator samples and twenty of twenty (20 of 20) I control samples. No other gamma-emitting radionuclides were identified during analysis.I I 2-42 I Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM d. Iodine-131:

A total of one hundred twenty-six (126) milk samples were analyzed for Iodine-131 during the report period. Iodine-131 was not detected in any of the one hundred six (106) indicator samples, nor was it detected in any of the twenty (20) control samples.All analyses were less than the 0.5 pico Curie / liter LLD value.e. Deviations from Required Sampling and Analysis:

There were no deviations from the required milk sampling and analysis schedule for the reporting period.f. Summary: Based on all the analytical results and the comparison to pre-operational levels, the operation of BVPS did not contribute any measurable increase in radioactivity in the milk in the vicinity of the site during the report period.2-43 Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Figure 2-8 Environmental Monitoring Locations

-Milk RTL A9.690E Enclosure 3 I I I I I I I I I I I I I I I I I Site Distance Sample Type No. Sector (miles) Sample Point Description 25 10-SSW 2.1 Hookstown, PA (Searight Farm)27A 7-SE 6.1 Aliquippa, PA (Brunton Farm)Milk 69 7-SE 3.5 Aliquippa, PA (Collins Farm)96 10-SSW 10.4 Burgettstown, PA (Windsheimer Farm)102* 7-SE 3.3 Aliquippa, PA (Ferry Farm)113* 10-SSW 5.1 Hookstown, PA (Halstead Farm)* Dairies selected based on evaluation of deposition parameters 2-44 Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Figure 2-9 Graph of Annual Average Concentration:

Iodine-131

& Sr-90 in Milk 0 0 ole le~ le 60"Il le le 14pl 0ele le e Beaver Valley Power Station REMP Sr-90 Concentrations in Milk 10-" 7 0 6-: 5 0)8 4 0 3 O.10 ý,e le ý,e -0ý1 1-1'.'b le le le le le e e 10k e e 2-45 Beaver Valley Power Station RTL A9.690E I 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMEiVNTAL MONITORING PROGRAM I F. Environmental Radiation Monitoring

1. Description of Regional Background Radiation and Sources Historical information for regional background was obtained from Reuter-Stokes instruments i that were previously located within a five (5) mile radius of the BVPS site. Data is no longer available from these instruments, but historical data indicated that the background exposure rates ranged from 6 ptR/hr to 12 WtR/hr.The sources of background radiation are affected by the terrain in the vicinity of BVPS, where as, the local hills (i.e., with altitude variations of 300-400 feet) and densely wooded areas I contribute to differences in background radiation level. 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 of i limestone alternate with sandstone and shale with abundant interbedded coal layers. Pleistocene glacial deposits partially cover the older sedimentary deposits in the 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.2. Locations and Analytical Procedures Ambient external radiation levels around the site were measured using thermoluminescent dosimeters (TLDs). I During the report period, there were a total of sixty-four (64) environmental TLD locations.

This is comprised of forty-four (44) offsite locations, along with twenty (20) fence perimeter I 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.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 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 holder that contains two (2) TLDs at each location.3. Results and Conclusions A summary of the TLD results during the report period are listed in Table 2-2. A trend graph i of analyses (including the pre-operational period through the report period) is shown on Figure 2-11. 3 TLD Analysis:

During the report period, the average quarterly external exposure rate (as measured from TLD) was 18.5 mR at the sixty-four (64) indicator locations, and 21.2 mR at the Control location.

This external exposure rate is comparable to previous years. As l expected, there was some variation in external exposure rate among locations and seasons.I 2-46 I Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM TLD Trend Evaluation:

As discussed in the 2007 report, the trends of the environmental TLD data during the period 2001 thru 2007 showed a small increase for the indicator locations, and a step (level) increase for the Control location.

The increase was traced to a change made in late 2001 with regards to the environmental TLD field holders, which resulted in an increased sensitivity to natural background beta radiation.

In summary, the increase in TLD data was consistent at all locations (including the control location), was most likely due to increased sensitivity to natural background beta radiation, and was not a consequence of BVPS gaseous effluent releases.

This issue is documented in SAP Order No. 200197646-0400.

Deviations from Required Sampling and Analysis Schedule:

There was one deviation from the required sampling schedule (i.e.; TLD change out frequency) and analysis schedule (i.e.; TLD processing frequency) during the report period. Specifically, REMP TLD location #55-Shippingport Bridge (0.3 miles NE), was inadvertently discarded during construction activities on the bridge during the third quarter of 2009. This condition was found on 10/8/09, during the scheduled quarterly TLD change-out.

The location is considered an onsite TLD because it resides within the site boundary and is therefore not a required sample by the ODCM. This issue is documented in Condition Report 09-65670 and SAP Order No. 200197646-0860.

Summary: The quarterly TLD external exposure rates are comparable to those of previous years, except for the overall increase in 2001, as described above in the TLD Trend Evaluation.

There was no evidence of anomalies that could be attributed to the 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 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 changes from natural radiation levels, if any, are negligible.

2-47 Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Figure 2-10 Environmental Monitoring Locations

-TLDs RTL A9.690E Enclosure 3 2-48 Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Figure 2-10 (Continued)

TLD Locations SOUTHEAST QUADRANT Site No.Sector Distance (miles)Location Site No.Sector Distance (miles)Location 27 7-SE 6.14 Brunton Dairy Farm Aliquippa, PA 45.1 6-ESE 1.92 Kennedy's Comers Raccoon Township, PA 51 5-E 8.00 Sheffield Substation Aliquippa, PA 59 6-ESE 0.99 236 Green Hill Road Aliquippa, PA 76 6-ESE 3.80 Raccoon Elementary School Raccoon Township, PA 77 6-ESE 5.52 3614 Green Garden Road I Aliquippa, PA 78 7-SE 2.72 Racoon Twsp Municipal Building Raccoon Township, PA 79 8-SSE 4.46 106 State Route 151 Green Twp.Ted McWilliams Auto Body 80 9-S 8.27 Park Office, State Route 18 Raccoon Township, PA 82 9-S 6.99 2697 State Route 18 Raccoon Twp, PA 94 8-SSE 2.25 McCleary & Pole Cat Hollow Road Hookstown, PA NORTHWEST QUADRANT Site Sector Distance Location Site Sector Distance Location No. (miles) No. (miles)15 14-WNW 3.75 Post Office 87 14- 7.04 50103 Calcutta Smith's Ferry Road Georgetown, PA WNW , 32 15-NW 0.75 North Substation 88 15-NW 2.74 110 Summit Road Midland, PA Midland, PA 47 14-WNW 4.88 Water Department 89 15-NW 4.72 488 Smith's Ferry Road East Liverpool, OH Ohioville, PA 60 13-W 2.51 444 Hill Road 90 16-NNW 5.20 6286 Tuscarawras Road Georgetown, PA Midland, PA 86 13-W 6.18 1090 Ohio Avenue 93 16-NNW 1.10 104 Linden -Sunrise Hills East Liverpool, OH Midland, PA NORTHEAST QUADRANT Site Sector Distance Location Site Sector Distance 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 28 1-N 8.60 Sherman Farm 71 2-NNE 6.01 First Western Bank Brighton Twp, PA Brighton Township, PA 29B 3-NE 7.97 Friendship Ridge 72 3-NE 3.25 Ohioview Lutheran Church -Rear Beaver, PA Raccoon Twp, PA 30 4-ENE 0.43 Cook's Ferry Substation 73 4-ENE 2.48 618 Squirrel Run Road Shippingport, PA Industry, PA 45 5-E 2.19 Christian House Baptist Chapel, State Rte 18 74 4-ENE 6.92 137 Poplar Avenue (CCBC)Raccoon Township, PA Monaca, PA 46 3-NE 2.49 Midway Drive 75 5-E 4.08 117 Holt Road Industry, PA Aliquippa, PA 46.1 2-NNE 2.28 McKeel's Service, State Route 68 91 2-NNE 3.89 Pine Grove Road & Doyle Road 3-NE Industry, PA Industry SOUTHWEST QUADRANT Site No.Sector Distance (miles)Location Site No.Sector Distance (miles)Location 13 11-SW 1.49 Old Meyer Farm Hookstown, PA 14 1 I-SW 2.53 Hookstown, PA 48 10-SSW 16.40 Collier Way Water Tower Weirton, WV 81 9-S 3.69 Millcreek United Presbyterian Church 83 10-SSW 4.26 735 Mill Creek Road, Hookstown 84 11-SW 8.35 Senior Center Hancock County, WV 85 12- 5.73 2048 State Route 30 WSW West Chester, WV 92 12- 2.81 Georgetown Road Substation WSW Georgetown, PA 95 10-SSW 2.37 832 McCleary Road Hookstown, PA 2-49 Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM RTL A9.690E Enclosure 3 Figure 2-11 Graph of Annual Average Exposure:

Direct Radiation in Environment Beaver Valley Power Station REMPI Environmental TLD Trends 1 0.24.,A 0.22-------------------------------------------------------

_EA 0.124 .-4-- Average.A."r-prtoaCnrlLtonf 63 lndicatOrvau(ero(,LocatiOnSwvme

/a) ] ..................0.12/ .'. ook A. '2-50 Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM G. Monitoring of Fish 1. Description During the report period, fish collected for the radiological monitoring program included carp, channel catfish, flathead catfish, quillback, red horse, sheepshead, gizzard shad and smallmouth bass.2. Sampling Program and Analytical Techniques

a. Program Fish samples are collected semi-annually in the New Cumberland pool of the Ohio River at the Beaver Valley effluent discharge point and upstream of the Montgomery Dam. The edible portion of each different species caught is analyzed by gamma spectroscopy.

Fish sampling locations are shown in Figure 2-12.b. Procedure A sample is prepared in a standard tare weight 300 ml plastic bottle and scanned for gamma emitting nuclides with gamma spectrometry system which utilizes a high resolution germanium detector.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 shown on Figure 2-13.Gamma Spectrometry:

A total of eleven (11) fish samples were analyzed by ganmna 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 six (6) control samples.Deviations from Required Sampling and Analysis Schedule:

There were no deviations from the required fish sampling and analysis schedule during the report period.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 period.2-51 Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM RTL A9.690E Enclosure 3 Figure 2-12 Environmental Monitoring Locations

-Fish Site Distance Sample Type No. Sector (miles) Sample Point Description 2A 12-WSW 0.31 BVPS Outfall Vicinity Fish Industry, PA (Upstream Montgome 49A 3-NE 493 I____ ___ _ __ __ ___ __ _ ___ ___ Dam)2-52 Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Figure 2-13 Graph of Annual Average Concentration:

Cesium-137 in Fish RTL A9.690E Enclosure 3 Beaver Valley Power Station REMP Cs-1 37 Concentrations

-Fish 10000.000 1000.000-, 100.000-T ---0--- Cs-137.6 10.00-- ------ ---------

Control Location -Mobntgomery Dam E Unit 2 Preoperational (0.014 pCa / gin)E-.... Required LLD (150 pCA / gm)0T 1.00-------------

-- -- -- -- -- ---- Reporting Level (2000 pO /gm)-----------------------

o 0.100-o-- -- --- ---- --, '- --,-- ---. , .--...... ......... ....0.001 2-53 Beaver Valley Power Station RTL A9.690E I 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM I H. Monitorin2 of Surface Water, Drinkine Water, Groundwater and Precipitation

1. Description of Water Sources The Ohio River is the main body of water in the area. It is the main surface water supply for generation of drinking water in the area. The Beaver Valley Power Station obtains water from the Ohio River for plant make-up water and discharges water to the Ohio River via NPDES discharge points (e.g. cooling tower blowdown, liquid effluent releases, etc).The Ohio River is the main surface water supply source for towns, municipalities and 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 and on the opposite side of the river.The next downstream user is East Liverpool, Ohio which is approximately 6 miles downstream.

The heavy industries in Midland, as well as others downstream, also use river water for cooling purposes.Groundwater occurs in large volumes in the gravel terraces which lie along the river, and I diminishes considerably in the bedrock underlying the site. Normal well yields in the bedrock are less than 10 gallons per minute (gpin) with occasional wells yielding up to 60 gpm.In general, the BVPS site experiences cool winters and moderately warm summers with ample annual precipitation evenly distributed throughout the year. The National Climate Data Center (http://www.ncdc.noaa.gov/oa/climate/research/cag3/v4.html) indicates the total annual precipitation during the report period for the Pittsburgh, PA area was 32.27 inches.I I I I I I I I 2-54 I Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM 2. Sampling and Analytical Techniques

a. Surface (Raw River) Water The sampling program of river water includes three (3) sampling points along the Ohio River.Raw water samples are collected daily at the East Liverpool (Ohio) Water Treatment Plant, sample location 5, [River Mile 41.21, and the made into a weekly composite sample. One automatic river water sampler is located at the ATI-Allegheny Ludlam (formerly J&L Steel) river water intake, sample location 2.1, [River Mile 36.2]. 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 made into a monthly composite sample for each location.The monthly composite samples are analyzed for gamma emitters.

In addition, a quarterly composite sample is prepared for each sample point from the monthly composites.

Quarterly composites are analyzed for Hydrogen-3 (Tritium).

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 Iodine- 131.Weekly grab samples are then made into monthly composites are analyzed for gamma emitters.

Quarterly composite are prepared from each of the monthly composites.

The quarterly composites are analyzed for Tritium.Locations of each sample point are shown in Figure 2-14.b. Drinking Water (Public Supplies)Drinking water (i.e.; treated water) is collected at both the Midland, PA Water Treating Plant, sample location 4, and East Liverpool, OH Water Treating Plant, sample location 5.An automatic sampler at each location collects 20-40 ml every 20 minutes, which is then made into a weekly composite sample. The weekly composite sample from each location is analyzed for Iodine-131.

Monthly composites are made from the weekly samples and are analyzed by gamma spectrometry.

In addition, a quarterly composite sample is prepared for each sample point from the monthly composites.

Quarterly composites are analyzed for Tritium.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 Iodine- 131.Weekly grab samples are then made into monthly composites are analyzed by gamma spectrometry.

Quarterly composite are prepared from each of the monthly composites.

The quarterly composites are analyzed for Tritium.Locations of each sample point are shown in Figure 2-14.2-55 Beaver Valley Power Station RTL A9.690E U 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM c. Groundwater 3 Although not required by the ODCM, semi-annual grab samples were collected from three (3) locations within four (4) miles of the site (see Figure 2-14). These locations are: One (1) well in Shippingport, PA One (1) well in Hookstown, PA I One (1) well in Georgetown, PA Each ground water sample is analyzed for tritium and is analyzed by gamma spectrometry.

d. Precipitation Although not required by the ODCM, precipitation is collected in Shippingport PA, East Liverpool OH, and Weirton WV. Precipitation, when available, is collected each week and then made into quarterly composite samples from the weekly samples. The quarterly composites are analyzed for Tritium and gamma emitters.

Locations of each of the sample points are shown in Figure 2-14. 3 e. Procedures Gamma Analysis of Drinking Water and Surface Water: The analysis is performed on 3 water samples by placing one liter of the sample into a Marinelli container and analyzing the sample on a high resolution germanium galmna spectrometry system. Although not required by the ODCM, this analysis is also performed on Groundwater and Precipitation.

Tritium Analysis of Drinking Water and Surface Water: The Tritium is determined in water samples by liquid scintillation analysis.

Although not required by the ODCM, this 3 analysis is also performed on Surface Water, Groundwater and Precipitation.

Iodine-131 Analysis of Drinking Water: The sample is chemically prepared and analyzed with a low-level beta counting system. Although not required by the ODCM, this analysis is also performed on Surface Water.I I I I I 2-56 Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM 3. Results and Conclusions A summary of the analysis results of water samples (surface water, drinking water, 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 on Figures 2-15 through 2-18.a. Surface Water Tritium: A total of twelve (12) surface water samples were analyzed for Tritium during the report period. Tritium was not detected in any of the eight (8) indicator samples, nor was it detected in any of the four (4) control samples.Gamma Spectrometry:

A total of thirty-six (36) surface water samples: were analyzed by gamma spectrometry during the report period. Gamma emitting 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.Iodine- 131: Although not required by the ODCM, a total of fifty-two (52) surface water control samples were analyzed for Iodine-131 using radiochemical methods during the report period. Iodinel31 was detected in forty-three of fifty-two (43 of 52) weekly control samples, of which one (1) analysis exceeded the reporting level of 2 pico Curie / liter. The results were similar to previous years, (current years range = 0.3 to 2.4 pico Curie ! 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 treatment procedures from upstream facilities.

This issue is documented in SAP Order 200197646-0770.

b. Drinking Water Tritium: A total of twelve (12) drinking water samples were analyzed for Tritium during the report period. Tritium was not detected in any of the eight (8) indicator samples, nor was it detected in any of the four (4) control samples.Gamma Spectrometry:

A total of thirty-six (36) drinking water samples were analyzed by gamma spectrometry during the report period. Gamma emitting 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.Iodine-13 1: A total of one hundred-fifty-six (156) drinking water samples were analyzed for Iodine-131 (using radiochemical methods) during the report period. Iodine-131 was detected in fifty-five of one hundred four (55 of 104) indicator samples and forty-three of fifty-two (43 of 52) control samples. Some of the positive results at the downstream location exceeded the positive results from the upstream surface water Control location, but none of these analyses exceeded the reporting level of 2 pico Curieý / liter. Because positive results were detected in the upstream control sample, some positive results are most likely due to medical diagnostic and treatment procedures from upstream facilities, and not caused by BVPS operations.

However, the analyses are also consistent with 2-57 Beaver Valley Power Station RTL A9.690E I 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM I 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.c. Groundwater Tritium: Although not required by ODCM, a total of six (6) groundwater samples were analyzed for Tritium during the report period. Tritium was not detected in any of the four (4) indicator samples, nor was it detected in any of the two (2) control samples.Gamma Spectrometry:

Although not required by ODCM, a total of six (6) groundwater samples were analyzed by gamma spectrometry during the report period. Gamma emitting I radionuclides were not detected in any of the four (4) indicator samples, nor were they detected in any of the two (2)ycontrol samples.d. Precipitation n Tritium: Although not required by ODCM, a total of twelve (12) precipitation samples were analyzed for Tritium during the report period. Tritium was detected in two of eight (2 of 8) indicator samples, but was not detected in any of the four (4) control samples. The positive results at the Cooks Ferry Substation in Shippingport, PA (current range = 208 pico Curie / liter, with an LLD of 152 pico Curie / liter) and the East Liverpool Water I Department, in East Liverpool, OH (current range = 181 pico Curie / liter, with an LLD of 152 pico Curie / liter), are less than the pre-operational level of 300 pico Curie / liter, and are consistent with washout of tritium (from gaseous releases) during precipitation events. I Specifically, identification oftritium at this location is not unusual, because the plant discharges tritium in gaseous waste effluents, and washout does occur during precipitation.

Also, the liquid tritium activity is less than the tritium discharge data of authorized gaseous I effluent releases.

All gaseous effluent releases during the report period did not exceed the release limits set forth in the Offsite Dose Calculation Manual. U Gamna Spectrometry:

Although not required by ODCM, a total of twelve (12)precipitation samples were analyzed by gamma spectrometry during the report period.Gamma emitting radionuclides were not detected in any of the eight (8) indicator samples, nor were they detected in any of the four (4) control samples.e. Deviations from Required Sampling and Analysis Schedule:

The monthly surface water composite sample at ATI-Allegheny Ludlam in Midland, PA (Site No. 2.1, 1.43 miles WNW) from September was inaccurately reported.

A positive result for Iodine-131 of 11.1 pico Curies/Liter was reported.

The ODCM does not require Iodine-131 analysis at this sample location.

Upon investigation, it was determined that the analysis was performed using gamma spectroscopy, which is not the preferred method of analysis for Iodine-131.

Additionally, it was determined that the Lower Level of Detection (LLD) for Iodine-131 by gamma spectroscopy is 15 pico Curies/ Liter. Therefore, the initial analysis I was inaccurately reported as a positive result when it was actually lower then the gamma spectroscopy LLD. To confirm the initial sample result, it was requested that the same sample be analyzed utilizing the wet chemical separation method for Iodine- 131 (EPA I Method 7500-I C). Results from the Iodine-131 wet chemical separation method were less than detectable.

This condition is documented in Condition Report 09-65940 and SAP Order No. 200197646-0870.

I 2-58 I Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM f. Summary: Data from the water sample analyses demonstrate that BVPS did not 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 the station assessments, prior to authorizing radioactive discharges, are adequate and that the environmental monitoring program is sufficiently sensitive.

2-59 Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Figure 2-14 Environmental Monitoring Locations

-Ground Water, Surface Water, Drinking Water and Precipitation I I I I I I I I I I I I I I I I I I I Site Distance Sample Type No. Sector (miles) Sample Point Description Drinking 4 15-NW 1.26 Midland, PA (Water Department)

Water 5 14-WNW 4.90 East Liverpool, OH ( Water Department)

Surface 2.1 14-WNW 1.43 Midland, PA (ATI Allegheny Ludlam)Water 5 14-WNW 4.90 East Liverpool, OH ( Water Department) 49A 3-NE 4.93 Industry, PA (Upstream Montgomery Dam)Ground 11 3-NE 0.94 Shippingport, PA Water 14A 11-SW 2.61 Hookstown, PA 15B 14-WNW 3.75 Georgetown, PA 30 4-ENE 0.43 Shippingport, PA (Cook's Ferry Substation)

Precipitation 47 14-WNW 4.88 East Liverpool, OH (Water Department) 1 48 10-SSW 16.40 Weirton WV (Water Tower, Collier Way)2-60 Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Figure 2-15 Graph of Annual Average Concentration:

Iodine-131 in Surface Water & Drinking Water Beaver Valley Power Station REMP 1-131 Surface Water & Drinking Water Trends 2.5 2.0o* Dow n Stream Drinking Water -Midland X Dow n Stream Drinking Water -East Liverpool CL-A. Control Location -Up Stream Surface Water' 1.5- Unit 2 DW Reoperational (0.23 pai/ liter)-Required LLD (1 pa / liter)-Reporting Level (2 pCi / liter)0.5- A 0. e le e\ e l/e \e 4, le.N .toJ. .o 2-61 Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM RTL A9.690E Enclosure 3 Figure 2-16 Graph of Annual Average Concentration:

Tritium in Surface Water Beaver Valley Power Station REM PI Tritium Trends -Surface Water 100000-.. ----indicator Mean (pai / 1)]A. Control Location (pai / 1)Pre- Operational (300 pCi/I)10000- -Required LLD (2,000 pC/l) P Level Surface Water (30O,000 pCUX/I) -1000 10 10 2-62 Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM RTL A9.690E Enclosure 3 Figure 2-17 Graph of Annual Average Concentration:

Tritium in Ground Water Beaver Valley Power Station REMPI 100-Tritium Trends -Groundwater I 100000--- Indicator Mean (pa / I)10000 _ _ _ Control Location (pCi / I) -................

Pre- Operational (440 pWl/)-- Required LLD (2,000 pCi/l)Reporting Level Groundwater (30,000 pC/I)-1000 0)C)100 10lO. ..2-63 Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Figure 2-18 Graph of Annual Average Concentration:

Tritium in Drinking Water Beaver Valley Power Station REMPI 1-Tritium Trends -Drinking Water 100000--A-- Control Location (pCi / 1)Pre- Operational (310 pCi/I)100)00 -Required LLD (2,000 pCi/I)-- --- --- ---- --- ----- ---- ---- ------ -*,,,,,,,,.-Reporting Level Drinking Water (20,000 pCi/I)c3 4. a * -,.o 100 --" ----------104 I I I I I U I I I I I 2-64 Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM I. Estimates of Radiation Dose to Man 1. Pathways to Man -Calculational Models 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 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, based on sample analysis were used as the radionuclide activity input.All liquid and gaseous effluent radionuclides listed in the Annual Radioactive Effluent Release Report were input as source terms to the computer codes.All batch and continuous gaseous effluent releases were included in the dose assessment 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 codes.Except when more recent or specific data was available, the usage factors were obtained from the BVPS Final Environmental Statements or Regulatory Guide 1.109.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 analyses are tabulated and used as the radionuclide source term input to the computer code. Except when more recent or specific data was available, the usage factors were obtained from the BVPS Final Environmental Statements or Regulatory Guide 1.109.The total population doses were evaluated for all liquid and gaseous effluent pathways out to 50 miles. For these evaluations, a total population of -4 million people was used. An estimate of the populations are listed in the BVPS-2 UFSAR Section 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 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 this table is a comparison to natural radiation exposure.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 the plant is presented in Table 2-5 for BVPS airborne effluent releases.

Also shown in this table is a comparison to natural radiation exposure.

The doses include the contribution of all pathways.2-65 Beaver Valley Power Station RTL A9.690E I 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM I 4. Conclusions 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 population from the operation of BVPS -Unit 1 and 2, is less than 0.00005% of the annual background dose.The calculated doses to the public from the operation of BVPS -Unit 1 and 2, are below I ODCM annual limits and resulted in only a small incremental dose to that which area residents already received as aresult of natural background.

The doses constituted no meaningful risk to the public.I I I I I U I I I I I I 2-66 Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Table 2-4 Comparison of Natural Radiation Exposure Versus Calculated Population Dose to Man -Liquid Effluent Releases RTL A9.690E Enclosure 3 TYPICAL DOSE TO INDIVIDUALS FROM NATURAL RADIATION EXPOSURE (a)Ambient Gamma Radiation Radionuclides in Body Global Fallout Radon Average Individual (Total from all sources shown above)58 millirem / year 40 millirem / y6ar<1 millirem / year 198 millirem / year 296 millirem / year (a) National Academy of Sciences, "The Effects on Populations of Exposure to Low Levels of Ionizing Radiation," BEIR Report, 1990 0-50 mile Population Dose from BVPS Liquid Effluent Releases Man-millirem Largest Isotope Contributor Total Dose 422 Tritium Average Dose 0.0001055 Tritium (per Individual) 0 Comparison of Individual Dose BVPS Liquid Effluent Releases Versus Natural Background Radiation millirem BVPS Liquid Effluent Release Dose 0.0001055 Natural Radiation Exposure 296 2-67 Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Table 2-5 Comparison of Natural Radiation Exposure Versus Calculated Population Dose to Man -Gaseous Effluent Releases TYPICAL DOSE TO INDIVIDUALS FROM NATURAL RADIATION EXPOSURE (a)Ambient Gamma Radiation Radionuclides in Body Global Fallout Radon Average Individual (Total from all sources shown above)= 58 millirem / year= 40 millirem / year S < 1 millirem year 198 millirem / year= 296 millirem / year (b) National Academy of Sciences, "The Effects on Populations of Exposure to Low Levels of Ionizing Radiation," BEIR Report, 1990 I I I I I I I I I I I I I U I I I I I 0-50 mile Population Dose from BVPS Gaseous Effluent Releases Man-millirem Largest Isotope Contributor Total 199 Tritium Average 0.0000498 Tritium (per Individual)

Comparison of Individual Dose BVPS Gaseous Effluent Releases Versus Natural Background Radiation millirem BVPS Gaseous Effluent Release Dose 0.0000498 Natural Radiation Exposure 296 2-68 Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 3 -LAND USE CENSUS A. Land Use Census Overview:

A Land Use Census was conducted August 6 through September 25, 2009 to comply with: " Offsite Dose Calculation Manual procedure 1/2-ODC-3.03, "Controls for RETS and REMP Programs", Attachment R, Control 3.12.2, and Surveillance Requirement 4.12.2.1 o BVPS REMP procedure 1/2-ENV-04.02, "Milch Animal Sampling Location Determination

& ODCM Procedure 1/2-ODC-3.03, Control 3.12.2 Action Statements a and b Compliance Determination" 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 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 Use Census as documented in letter NPD3NRE:0627, dated September 29, 2009: B. Nearest Residence:

The current location has not changed since the previous census.The current location is at 211 Ferry Hill Road, Shippingport, PA (0.406 miles NE).C. Nearest Garden >500 scift: The location of the nearest garden has changed since the previous census. The new location is at the Knisley Residence, 175 Kerona Road, Shippingport, PA (0.7 miles, NE).However, the previous sampling location at the Cox Residence, 238 State Route 168, Hookstown, PA (0.760 miles, in the SSW Sector) will remain the primary sample location because the Knisley Residence did not contain leafy vegetables most appropriate for sampling (cabbage) this year.D. Nearest Dairy Cow: The current location has not changed since the previous census.The current location is at the Searight Dairy, 948 McCleary Road, RD 1, Hookstown, PA (2.097 miles SSW).E. Nearest Doe Goat: The nearest location has not changed since the previous census. The location remains at the Ferry Farm, 227 Calhoun Road, Aliquippa, PA (3.320 miles SE). During 2009, the goat sampling location changed. The goats at the previous sampling location, (Collin's Farm 289 Calhoun Road, Aliquippa, PA -3.547 miles SE), went dry, and goats at the Ferry Farm became available for milk sampling.3-1 Beaver Valley Power Station RTL A9.690E U 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 3 -LAND USE CENSUS 1 F. Projection for 2010 Dairy Cow Samplina Locations:

Using a linear regression analysis of deposition parameters (D/Q), Dairy Cow sampling locations were determined to remain at the same locations used in 2009:-Searight Dairy, 948 McCleary Road, RD1, Hookstown, PA (2.097 miles SSW) l-Halstead Dairy, 104 Tellish Drive, Hookstown, PA (5.079 miles SSW)-Brunton Dairy, 3681 Ridge Road, Aliquippa, PA (6.158 miles SE)-Windsheimer Dairy, RD 1 Burgettstown, PA (10.476 miles SSW)G. Projection for 2010 Doe Goat Sampling Locations:

The linear regression analysis also indicated that there may be a Doe Goat sampling location in 2010. The Doe Goat sampling location for 2010 may be as follows:-Ferry Farm, 227 Calhoun Road, Aliquippa, PA (3.320 miles SE) 3 H. D/O for Milch Animal Locations:

None of the 2009 milch animal sampling locations experienced a >20% increase in D/Q.Therefore, a Special Report per ODCM procedure 1/2-ODC-3.03, Attachment R, Control 3.12.2 Action "a" and/or Action "b" was not required.I. D/I for Offsite Dose Determination:

There was no adverse effect on the current ODCM methodology used for offsite dose determination from effluent releases.

Specifically, a linear regression analysis of D/Q did 3 not yield any valid locations where the offsite dose could have increased

>20% more than the offsite dose previously calculated using current ODCM methodology.

Therefore, a Special Report per ODCM procedure 1/2-ODC-3.03, Attachment R, Control 3.12.2 I Action "a" and/or Action "b" was not required.J. D/) Historical Comparison:

3 There was no adverse trend in D/Q when comparing 1997 to 2009 data to the ODCM default D/Q values. This validates that 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 could have increased

>20% more than the offsite dose previously calculated using current ODCM methodology.

Therefore, a change in ODCM Receptor location and/or a change to meteorology at the current ODCM Receptor location are not required.I 3 I 3-2 Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 3 -LAND USE CENSUS K. Discrepancies or Conditions of Note: During performance of the 2009 Land Use Census, discrepancies were discovered and documented in Condition Report 09-64044.

These discrepancies are summarized below.For years 2005-2008, two sectors (13-W and 14-WNW) within the five mile radius were erroneously reported as containing no Gardens. In 2009, communications with property owners revealed that between the years 2005-2008, Gardens were in fact present in sectors 13-W and 14WNW. These Gardens are co-located with the Nearest Residence of the sectors. During the investigation of these oversights, it was discovered that the format of the Land Use Census report changed in 2005 and these two Gardens were mistakenly omitted from the 2005-2008 Land Use Census Reports.Although Gardens were identified in the North sector (1-N), it was not until 2009 that the Nearest Garden co-located with the Nearest Residence of this sector was identified.

Upon review of historical Land Use Census Reports, it was determined that this Garden had not been previously identified.

In 2008, 5 out of 16 sectors were reported to contain no Gardens within the five mile radius. In 2009, 16 out of 16 sectors were reported to contain Gardens within the five mile radius; only one Garden was identified outside of the three mile radius (8-SSE).3-3 Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report SECTION 3 -LAND USE CENSUS RTL A9.690E Enclosure 3 S Table 3-1 Location of Nearest Residences, Gardens, Dairy Cows and Doe Goats DAIRY CTOR RESIDENCES GARDENS COWS DOE GOA 0 to 5 miles 0 to 5 miles 0 to 5 miles 0 to 5 mil (miles) (miles) (miles) (miles)N 1.584 1.584 None None NNE 1.661 2.0 None None NE 0.406 b 0.7 b None None ENE 0.603 1.047 None None E 0.429 2.252 None 3.402 ESE 0.476 1.713 None None SE 1.583 1.5 None a 3.320 b SSE 1.102 3.1 None None S 1.399 2.354 3.851 None SSW 0.760 0.760 2.097 b None SW 1.453 1.453 None None WSW 1.394 2.5 None None W 2.204 2.2 None None WNW 2.742 2.742 None None NW 0.885 1.033 None None NNW 0.902 2.413 2.442 None TS es a Although there are no Dairy Cows within 5 miles in this sector, a large local dairy located at 6.158 miles is included in the milk sampling program.b Distances shown in Bold print are the nearest location for that receptor.3-4 Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 4 -SPLIT SAMPLE PROGRAM and SPIKE SAMPLE INTER-LABORATORY COMPARISON PROGRAM 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 (PADEP) in support of their nuclear power plant monitoring program.o 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).o PADEP has co-located continuous air particulate

& air iodine sample stations with four (4)of the BVPS locations." PADEP has co-located TLDs with twenty-four (24) of the BVPS TLDs.B. Spike Sample Program (Inter-Laboratory Comparison, Part 2 of 2):. BVPS participates in a spike sample program with an Independent Laboratory.

This program is used to independently verify sample analyses performed by the BVPS Contractor Laboratory.

o .Acceptance Criteria 1:. The NRC criteria listed in NRC Inspection Procedure 84750, 12/4/90, Inspection Guidance 84750-03 is used as acceptance criteria for comparisons of 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 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 where the counting precision of the standard yields a resolution of less than 4, a valid comparison is not practical, and therefore, not performed.

NRC Criteria Resolution Ratio<4 --4-7 0.50-2.00 8-15 0.60-1.66 16 -50 0.75 -1.33 51-200 0.80-1.25> 200 0.85-1.18.Acceptance Criteria 2:. BVPS also has self imposed acceptance criteria.

That criteria requires the percent difference between the Contractor Lab Activity and the Independent Lab Calculated Activity to agree by .+. 20%.4-1 Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 4 -SPLIT SAMPLE PROGRAM and SPIKE SAMPLE 3 INTER-LABORATORY COMPARISON PROGRAM Participation in an Inter-Laboratory Comparison Program is required by BVPS Unit 1 and 2 Offsite Dose Calculation Manual procedure 1/2-ODC-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 (Analytics

-Atlanta, GA) as the Independent l Laboratory.

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.o Spiked Milk & Water Samples:.

The spiked sample results (i.e.; the BVPS criteria) for each calendar quarter are reported in Table 4-1 through Table 4-4, respectively.

The following summary is provided:-A total of forty-eight (48) gamma spectrometry radionuclide analyses were I performed by the Contractor Laboratory on four (4) milk samples.-A total of forty-eight (48) gamma spectrometry radionuclide analyses were i performed by the Contractor Laboratory on four (4) water samples.-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) chemical analyses for 1-131 analyses were performed by the I Contractor Laboratory on four (4) water samples.-A total of four (4) tritium analyses were performed by the Contractor Laboratory on i four (4) water samples.-Comparison of results of the spiked milk and water samples showed acceptable i agreement with the NRC acceptance criteria.

All one-hundred-eight (108) analyses met the NRC acceptance criteria.

3-Comparison of results of the spiked milk and water samples showed acceptable agreement with BVPS acceptance criteria.

All but one (1) of the one-hundred-eight (108) analyses met the BVPS acceptance criteria.I 4-2i Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 4 -SPLIT SAMPLE PROGRAM and SPIKE SAMPLE INTER-LABORATORY COMPARISON PROGRAM.,Spiked Filter Paper and Charcoal Cartridge Samples: The spiked sample results for each calendar quarter are also reported in Table 4-1 through Table 4-4, respectively.

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

All four (4)analyses performed by the Contractor Laboratory met the NRC acceptance criteria.-Comparison of results of the spiked filter paper and charcoal cartridge samples showed acceptable agreement with the BVPS acceptance criteria.

All four (4)analyses performed by the Contractor Laboratory met the BVPS, acceptance criteria.C. Conclusions

  • Results of Split Sample Program:.The split sample program is coordinated by the state, and the results are not provided with this report.* 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 comparison of the data, to the BVPS Acceptance Criteria, is provided in the following tables. There was one sample that is not within the BVPS Acceptance Criteria.

Although this sample analysis is not within the BVPS Acceptance Criteria, it is within the NRC Acceptance Criteria.

The BVPS acceptance criteria are self imposed FENOC internal goals and can be considered stringent compared to the NRC acceptance criteria.

The deviation occurred in the second quarter for milk for Sr-90 (-34.73%).

4-3 Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 4 -SPLIT SAMPLE PROGRAM and SPIKE SAMPLE INTER-LABORATORY COMPARISON PROGRAM Table 4-1 Inter-Laboratory Comparison Program Spiked Samples -Vst Quarter Percent Difference Between Sample Type and Contractor Lab Activity and Sample Date Identification No. Sample Analyses Independent Lab Calculated Activity (Contr. Lab -Ind. Lab) Ind. Lab Sr-89 -11.43%Sr-90 -12.58%1-131 (Chemical) 6.23%1-131 0.72%Ce-141 2.00%Water Cr-51 4.21%03/19/2009 Ind Lab: E6573-93 Cs-1 34 -8.74%Con. Lab: SPW-891 Cs-i 37 0.21%Co-58 -1.99%Mn-54 2.90%Fe-59 3.78%Zn-65 2.39%Co-60 2.50%Water 03/19/2009 Ind. Lab: E6572-93 H-3 13.17%Con. Lab: SPW-890 Sr-89 -9.42%Sr-90 -10.90%1-131 (Chemical) 14.88%1-131 1.64%Milk Ce-141 4.64%Cr-51 2.52%03/19/2009 Ind. Lab: E6574-93 Cs-134 -9.39%Con. Lab: SPMI-892 Cs-1 37 0.90%Co-58 -3.28%Mn-54 2.27%Fe-59 4.30%Zn-65 1.15%Co-60 2.46%Filter Paper Cs-137 03/19/2009 Ind. Lab: E6575-93 12.56%Con. Lab: SPAP-893 (Gross Beta)Charcoal Cartridge 03/19/2009 Ind. Lab: E6576-93 1-131 -5.31%Con. Lab: SPCH-894 I I I I I I I I I I I 3 I I I I I I U 4-4 Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 SECTION 4 -SPLIT SAMPLE PROGRAM and SPIKE SAMPLE INTER-LABORATORY COMPARISON PROGRAM Table 4-2 Inter-Laboratory Comparison Program nd Spiked Samples -2. Quarter Percent Difference Between Sample Type and Contractor Lab Activity and Sample Date Identification No. Sample Analyses Independent Lab Calculated Activity (Contr. Lab -Ind. Lab) Ind. Lab Sr-89 0.22%Sr-90 -7.35%1-131 (Chemical)

-4.08%1-131 0.91%Ce-141 -8.19%Water Cr-51 3.85%06/18/2009 Ind. Lab: E6727-93 Cs-1 34 -15.24%Cs-137 :1.16%Con. Lab: SPW -3032 C o- 58 0.00%Co-58 0.00%Mn-54 0.10%Fe-59 5.60%Zn-65 5.86%Co-60 -0.51%Water 06/18/2009 Ind. Lab: E6726-93 H-3 0.77%Con. Lab: SPW-3031 Sr-89 -14.73%Sr-90 -34.73%1-131 (Chemical)

'-5.98%1-131 -2.94%Milk Ce-141 -6.44%Cr-51 -3.70%06/18/2009 Id. Lab: E6728-93 Cs-1 34 -13.92%Cs-137 -3.70%Con. Lab: SPMI-3033 Co-58 -3.26%Mn-54 -2.99%Fe-59 -0.98%Zn-65 3.94%Co-60 -3.30%4-5 Beaver Valley Power Station RTL A9.690E 2009 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 4 -SPLIT SAMPLE PROGRAM and SPIKE SAMPLE INTER-LABORATORY COMPARISON PROGRAM Table 4-3 Inter-Laboratory Comparison Program Spiked Samples -3 rd Quarter Percent Difference Between Sample Type and Contractor Lab Activity and Sample Date Identification No. Sample Analyses Independent Lab Calculated Activity (Contr. Lab -Ind. Lab) I Ind. Lab Sr-89 15.24%Sr-90 4.32%1-131 (Chemical)

-8.43%1-131 -0.10%Ce-141 0.64%Water Cr-51 8.11%09/17/2009 Ind. Lab: E6858-93 Cs-1 34 -8.98%Con. Lab: SPW-4828 Cs-i 37 395%Co-58 1.99%Mn-54 4.55%Fe-59 7.94%Zn-65 10.62%Co-60 -0.45%Water 09/17/2009 Ind. Lab: E6857-93 H-3 3.09%Con. Lab: SPW-4827 Sr-89 -10.93%Sr-90 -15.43%1-131 (Chemical)

-8.92%1-131 2.03%Ce-141 -2.29%Milk Cr-51 2.13%09/17/2009 Ind. Lab: E6859-93 Cs-134 -10.57%Con. Lab: SPMI-4829 Cs-137 0.92%Co-58 1.01%Mn-54 2.04%Fe-59 4.90%Zn-65 6.67%Co-60 -0.44%Filter Paper Cs-i137 09/17/2009 Ind. Lab: E6860-93 8.55%Con. Lab: SPAP-4830 (Gross Beta)Charcoal Cartridge 09/17/2009 Ind. Lab: E6861-93 1-131 -12.54%Con. Lab: SPCH-4831 I I I I I I I I I I I I I I I I I I 1 4-6 Beaver Valley Power Station 2009 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 SECTION 4 -SPLIT SAMPLE PROGRAM and SPIKE SAMPLE INTER-LABORATORY COMPARISON PROGRAM Table 4-4 Inter-Laboratory Comparison Program Spiked Samples -4 th Quarter Percent Difference Between Contractor Lab Activity and Sample Type and Independent La b Calc .ulated Activity Sample Date Identification No. Sample Analyses (Contr. Lab -Ind. Lab) / Ind. Lab Sr-89 -5.95%Sr-90 7.19%1-131 (Chemical)

-2.91%1-131 2.19%Ce-141 -,1.18%Water Cr-51 -1.90%12/10/2009 Ind. Lab: E6955-93 Cs-134 8.63%Cs-137 3.43%Con. Lab: SPW-6797 Co-58 -0.80%Mn-54 2.46%Fe-59 4.47%Zn-65 3.19%Co-60 -3.06%Water 12/10/2009 Ind. Lab: E6954-93 H-3 5.01%Con. Lab: SPW-6762 Sr-89 -8.55%Sr-90 -8.94%1-131 (Chemical)

-12.60%1-131 -0.92%Ce-141 -2.87%Milk Cr-51 -1.92%12/10/2009 Ind. Lab: E6956-93 Cs-134 -11.74%Cs-137 1.51%Con. Lab: SPMI-6763 Co-58 -1.37%Mn-54 3.76%Fe-59 2.02%Zn-65 2.43%Co-60 -3.40%4-7

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