Text

Beaver Valley, Units 1 and 2, 2008 Radioactive Effluent Release Report and 2008 Annual Radiological Environmental Operating Report
	ML091200417
Person / Time
Site:	Beaver Valley
Issue date:	04/03/2009
From:	Lonnett A T, Powell-Campbell J L; FirstEnergy Nuclear Operating Co
To:	; Office of Nuclear Reactor Regulation
References
	L-09-098 RTL# A9.690E
	Download: ML091200417 (152)
	v • d • e

RTL# A9.690E FIRSTENERGY NUCLEAR OPERATING COMPANY BEAVER VALLEY POWER STATION 2008 RADIOACTIVE EFFLUENT RELEASE REPORT AND 2008 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: 2008 RADIOACTIVE EFFLUENT RELEASE REPORT AND 2008 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT UNITS NO. 1 AND 2 LICENSES DPR-66 AND NPF-73 Prepared by: Jennifer L. Powell-Campbell 19J a-(P .01, Prepared by: Anthony T. Lonnett Reviewed by: Michael D. Banko III Date: 0 ' -&0?O9 Date: Date: " C (r~Approved by: Donald J. Salera Date: 4 -C( vt

Subject:

Beaver Valley Power Station, Unit Nos. 1 and 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Radioactive Effluent Release Report for 2008, and Annual Radiological Environmental Operating Report for 2008 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 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 Glastonbury, CT 06033 Department of Environmental Protection (5 copies)Bureau of Radiation Protection

& Toxicology P.O. Box 2063 Harrisburg, PA 17120 Department of Environmental Protection (2 copies)Southwest Regional Office 400 Waterfront Drive Pittsburgh, PA 15222 INPO (Attn: Bill Nestel)700 Galleria Parkway SE Suite 100 Atlanta, GA 30339-5957 I Distribution for Enclosures 1 -3: Page2 2 Beaver County Cooperative Extension (Attn: JL Miller) I 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) 3 246 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) 3 2220 Michigan Avenue East Liverpool, OH 43920 ORSANCO (Attn: Jerry Schulte)5735 Kellogg Avenue Cincinnati, OH 45228 B. F. Jones Memorial Library 3 663 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 I I I I Distribution for Enclosures 1 -3: Page 3 Copies of Report for FENOC Addressees:

MD Banko, BVPS; Supervisor, Nuclear Chemistry Services (A-BV-A)JL Powell-Campbell, BVPS; Chemistry RETS & REMP Administrator (A-BV-A) 15 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)

DV Steen, Akron; Vice President, Environmental (A-GO- 13)DW Jenkins, Akron; Sr. Attorney, Legal (A-GO-18)M Hall, Akron; Vice President, Energy Policy (A-GO-18)MJ Jirousek, Akron; Manager, Environmental Reporting

&-Performance (A-GO- 13)M Dues, 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)

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 RTL A9.690E Enclosure 2, Page i Form 1/2-ENV-0t

.05.FQ1 (page 1 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 2008 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 -2008 Index RTL# A9.690E Enclosure 2, Page ii Cover Index Executive Summary -Report Submittal Requirements ii 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 Radiolodines) x 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 I I I I I I I I II I I I I I I I SuDplemental Information Paae 1 Table 1A Gaseous Effluents

-Summation Of All Releases 2 Table 1B3-EB Gaseous Effluents

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

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

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

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

-Ground Level Batch Releases (Unit 2) 7 Table 1C-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 Attachment 1 Part 1: Joint Frequency Distribution Tables (35 ft)Part 2: Joint Frequency Distribution Tables (150 ft)Part 3: Joint Frequency Distribution Tables (500 ft)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 -2008 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" NUJREG-1 30 1, "Offsite Dose Calculation Manual Guidance:

Standard Radiological Effluent Controls for Pressurized Water Reactors, Generic Letter 89-01, Supplement No.], 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. CR08-38484, and BVPS-SAP Order Number 200197646-0500 are associated with reporting of the failure to change out weekly filter media on gaseous effluent pathway radiation monitors.BVPS Condition Report No. CR08-49089, and BVPS-SAP Order Number 200197646-0680 are, associated.

with reporting of the failure to obtain a grab sample when a gaseous effluent pathway radiation monitor was inoperable.

BVPS Condition Report No. CR08-50899, and BVPS-SAP Order Number 200197646-0700 are associated with reporting the failure to return a liquid effluent radiation monitor to service withn 30 days.BVPS Condition Report No. CR09-56073, and BVPS-SAP Order Number 200197646-0800 are associated with reporting the failure to return a gaseous effluent radiation monitor to service withn 30 days.

Form 1/2-ENV-01.05.FO1 (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 -2008 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.Decommissioning 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 I I Form 1/2-ENV-01.05.FO1 (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 -2008 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 ODCM Surveillance Deficiencies.

They are described intable 8.ODCM Changes: There were no 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.

564 man-morem

=BVPS Total Population Dose for the year 0.0,001365 mremn = 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.F01 (page 6 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2008 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%:3 0, 1.0%-0.1% ...-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-M- Unit 1&2, Percent of 10 CFR20.1301 (a) (1) TE)E Dose Limit I I 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 -2008 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 1.00 0.10 0.01 NN N N' N N" I " v 1 BVPS Unit1 --s--BVPS Unit21 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 -2008 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.Liquid Effluent Trends Tritium 10000 1 o0 0 oo* 00l --- 0 --- ------------------10 T---------------------------------------------------------------------------

10ý ,-ý <Z 4 1 I BVPSUnztl

--4-BVPSUnit2I I I 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 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 -2008 Executive Summary -Trends of Liquid Release Offsite Dose Projections Liquid Release OMfsite 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 Dose 100.0%'0-0,10.0% __________

0.1%. .....Unit 1 or Unit 2, Percent of Maxirrum Organ Dose Lirit* Unit 1 or Unit 2, Percent of Total Body Dose LiUit Form 1/2-ENV-01

.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 -2008 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 steady decreases are due to extended hold-up periods of gas space prior to release.Gaseous Effluent Trends Fission and Activation Gas 10000.0 1000.0 100.0"i I I I I I I I I I I I I I I I I I I I<5j CK ý C!.S(!j I0 BVPS Unit 1 ---BVPS Unit2 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 -2008 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 recent increase at Unit I was due to identification of Co-58 in weekly effleunt pathway samples during a refueling outage. The increaseat at Unit 2 was due to identification of Co-58 and Co-60 in weekly effluent pathway samples during a refueling outage and due to a planned release of the pressurizer gas space after the refueling outage.Gaseous Effluent Trends Particulates

& Radioiodines 1.E-01 1.E-02 1,E-03 1t-04-0.1.E-05-1.E-06-1.E-07 K~ ~ ~~~ <~~~~ K ~~N 1 BVPS Unit 1 -a-BVPS Unit 21 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 -2008 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 1 0 BVPSUnit1

--BVPS Unit2]I I 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 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 -2008 Executive Summary -Trends of Unit 1 Gaseous Release Offsite Dose Projections Unit 1 Gaseous Release Offsite Dose Projections:

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.

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 -2008 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 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 I I I I I I I I I I I I I I Form 1/2-ENV-01.05.FO1 (page 15 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2008 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 RTL# A9.690E Beaver Valley Power Station -Units 1 & 2 Enclosure 2, Page xvi Radioactive Effluent Release Report Calendar Year -2008 Results of Onsite Spills and Items Added to Decommissioning Files per 10CFR50.75(g)

Summary of Onsite Spills (>100 gallons):

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

Files: None Form 1/2-ENV-01.05.F01 (page 17 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2008 Results of Onsite Groundwater Monitoring Program RTL# A9.690E Enclosure 2, Page xvii Summary of Onsite Groundwater Samples I 2008 2008 2008 Typical Requiredi Pre H-3 H-3 H-3 H-3 H-3 Operational Maximum Minimum Average LLD LLD Mean For H-3 (oCi/L) (oCi/L) (oCi/Lt (oCi/Lt (oCi/L) (DCi/L)Are Any H-3 Analyses Greater Than The Pre Operational Mean For H-3 ?NEI and FENOC Communication Level For H-3 (DCi/L)EPA Reporting Level For H-3 (pCi/L)1 1st Quarter 13356 177 17821 <200 <20001 440 Yesl 2000 20000 13rd Quarter1 115011 1441 1661 <2001 <20001 4401 Yesl 20001 200001 Sample Summary: Seventeen (17) onsite monitoring wells were sampled during the year. Each of these wells was sampled tw(c (2) times during the year, with exception of MW-12S & MW-1 2D, which were sampled three (3) times. I H-3 Summaryv Results from twelve (12) wells were<440 pCi/L (BVPS pre-operational mean). Results from three (3) wells were>440 pCi/L, but_<2000 pCi/L. Results from two (2) wells (MW-12S & MW-12D) were >2000 pCi/L, butk20,000 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 2008. No adverse effect to the offsite environment has been detected at this time, because all offsite groundwater, drinking water and surface water samples weret_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 fourteen (14) of the 3rd quarter samples. Th I 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. I Fe-55. Ni-63. Sr-89 & Sr-90: Baseline analyses were performed on the 3rd quarter samples from MW-1 2S & MW-12D. The FE 155 results were <LLD, the Ni-63 results were <LLD, the Sr-89 results were <LLD, and the Sr-90 results were <LLD. I BVPS (2007 -2008)Onsite Groundwater Monitoring H-3 Results<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------ Avg of All GWM Indicator Wells--MW-10: 67.0' deep, Upgradient Location-Typical LLD H-3 (<200 pCi/L)Pre- Operational Mean H-3 (440 pCiIL)Pre- Operational Maximum H-3 (800 pCiL)NNRC Required LLD H-3 (2,000 pCi/L)-EPA Reporting Level H-3 (20,000 pCi/L)100000o L A0000 -- 0.C., o 1000-8 ooo T lO.A J. A A , A ,

Form 1/2-ENV-01.05.FO1 (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 -2008 Supplemental Information PageT-" A-. WFM LEN__O C"". -,-A~tSZt 2 Max"imumi eriimssalse' oncentrations Used In.Determini£g

'Allowable Relebse RateIiOr.-o r cetratioh&914.>,, a Fissionandactiation gases. ,.. , Site Release Rate: 500 mrem/yr to Total Body, & 3000 mrem/yr to the Skin'-b lodinesl &paticlates, haf iives>_8 days. Site Release Rate: 1500 mrem/yr to Any Organ L.quid efflueits:...." -Site Release Concentration:

10 times 10 CFR 20 Appendix B, Table 2, EC's[.3 Aveage Energyj(Not.Aipiable T~o The BVPa S ODCM).0 .-. ...--.---,.M 6 Mes ure ment ianhd Apro imions of Toal Ra3dioactivt:

.. :, ietdsused to easutre orzapproximate the tt~r radoactijieen Mtes used tbdetermlnliriq., r'ad ibii,46l~d6pitiion' are as flllows" i 1 .i.~c ~iiL..and.activation gases.~ :_.: j Ge Gamma Spectrometry, Liquid Scintillation Counter-sb.6Ii-'e:! Ge Gamma Spectrometry afi.Pa dlculates,.hallf lves>8 days .. Ge Gamma Spectrometry, Proportional Counter I I I I I I I I I I 1 I U I I I I I I-I Liildueffl1ets

' I,;, -Le ,,,-lGe Gamma Spectrometry, Proportional Counter, Liquid Scintillation

,5. Batchl&,Ab-nOimal.Ralnfoiiition Fri- _i _ u iQ:r-Oua tr ......at,:S~iA-iiui

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

."" -,._ ,"D.___-.

...

' .... ...-, , -" if::.;'";- -Numberofbatch re eases, 47 43 52 45 187":" ".fi" tii-e period for batch releses miuin 22139 16429 12242 15766 66576-. .'Maxinmmtimebp~eriod ,forabatch'irlease'

ý mintes 2782 1628 1140 1080 2782.4;. egtime periodfor batch releases; minlutes .471 382 235 350 356 5.5- MiMnim4utime periodfora.batchhrelease minutes 80 83 3 90 3-196. Average river.flow during1release1periods.

uftlsec 85567 46300 15567 33933 45342 umber 11 22 10 9 52.1.L 2.Total time pelod1for batch releases minutes 5725 18209 3381 336 27651 3. pMa ,tim eriodfor a batch release mrnifuiteis, 3859 6610 2280 167 6610 k. ,.i i for batchreleaie ses inuadtesL 520 828 338 37 532 5.Mifilmih~tifrne~ik ldd for a 'biathireleas-e-minutesi 52 1 1671 21 1_6'c A bnral Liqui Rlases .1.. ___ ___ 4~1 Number Ofrelease.

I, .NONE NONE NONE NONE NONE.2. Ttlaii elease_.'uries 0 OOE+ 0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 dAbnorimall Gaseou Reess.*6.,11, Number of releases ..-NONE NONE NONE NONE NONE-2,TotaldactiVireleased

.- ., ue 0.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 nO.OE+00 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 -2008 Table 1A Gaseous Effluents

-Summation Of All Releases RTL # A9.690E Enclosure 2, Page 2 of 21ý,,,l nd: ~3rd> 4 th, Calendar Total: 7Unit' Quarter ~Quarter 'Quarter~

~Quarter Yea Error,~,A2.FiiSsi6

& ln ActivationGases_SUtetT l!,leas§ Ci 7.90E-02 1.67E+() O.OOE+00 O.OOE+00 1.75E+00 26.5%L_ , :3.85E-02 1.81 E-02. O.OOE+00 O.OOE+00 .5.66E-'02 2U t ses &Ci 4.06E-02 1.65E+00 0.00E+00 0.OOE+00 1.69E+00 2. er&a er efeasecrateiIfor.period uu 1.OOE-02 2.12E-01 0.OOE+00 0.O0E+00 5.55E-02 3. Percent 6fa licabie limit/ N/A N/A 'N/A N/A N/A 1 .SitTe dne>-l 6 l3-d O.OOE+00 .1.17E-07 O.OOE+00 O.OOE+00 1.17E-07 28.3%1 n a. O.OOE+00 5.85E-08 O.OOE+00 0.OOE+00 5.85E-08 i n Ci,:,,L O.OOE+00 5.85E-08 O.OOE+00 O.OOE+oo 5.85E-08 rla o rid Ci O.OOE+00 1.48E-08 O.OOE+00 0.OOE+00 3.71 E-09 3P~ercen t:. o !ical~le; lim it N/A N/A N/A N/A .N/A~C. Particulates.*-

1 .!0 culates withlivlfles 0.OOE+00 9.38E-05 O.OOE+00 O0OOE+00 9.38E-05 30.0%a JA ii'Iiiarticula0es, O.OOE+00 3.24E-05 O.OOE+00 0.OOE+00 3.24E-05,jO.OOE+00 6.14E-05 O.OOE+00 .OOE+O0 6.14E-05 z vealreelease rate for period, ,E utusec: O.OOE+00 1.19E-05 O.OOE+00 0.OOE+00 2.98E-06Pe ent.o applic limit: N/A N/A N/A N/A N/A D.o. G1I..... !§Ifeý'drosýýIpha

.... ... 0.OOE+00 O.00E+00 0.OOE+00 I 0.OOE+00 O.OOE+00 300].~ ~ZCi~~V1 O.OOE+OO I O.OOE+OOt O.OOE+OO I O.OOE+OO I O.00E+00O l a 'W ~ -nit r oss a pna O.OOE+00 0.OOE+00 0.OOE+00 .0.OOE+00 O.OOE+00 lberaUetrease.t for.peri uCiduse; O.OOE+00 0.OOE+O0 0.OOE+00 O.OOE+O0 O.OOE+0.,

plca 6 l~elimit;.o, N/A N/A N/A N/A N/A 4.21E+00 12.36E+0O j5.96E+00.j 3.46E+00 I 1.80E+00 15.61E+00 12.67E+00 I 5.34E-01 I 2'99E-01 I 7.56E-01 I 4.39E-01 I 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.F01 (page 20 of 38), Revw2 Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Repori Calendar Year -2008 Table IB-EB Gaseous Effluents

-Elevated Batch Releases RTL # A9.690E Enclosure 2, Page 3 of 21 I U I I 1. Fission gasesargon- J di 7j, LLD LLD LLD LLD LLD....yp..i-85..

LLD LLD LLD LLD LLD k kpopo 85rn J. LLD LLD LLD LLD LLD krijno787 i_ LLD LLD 'LLD LLD LLD kryRiflEi

> .Li_ LLD LLD LLD LLD LLD 31 iL CI LLD LLD LLD LLD LLD xen6n-133 C i LLD 4.99E-04 LLD LLD 4.99E-04 Sxenon-- 33m ' Ci LLD LLD LLD LLD ' LLD.... e .. ... Ci A LLD 3.24E-05 LLD LLD. 3.24E-05 SC- LLD LLD LLD LLD LLD , cenon-13, =_ LLD LLD LLD LLD LLD.

.Jji Ldi NONE NONE NONE NONE NONE ND 5.31E-04 ND ND 5.31E-04 iodine-1 i LLD LLD LLD .LLD LLD iodine-i33' c LLD LLD LLD LLD LLD K odinre-135 i ,LLD LLD LLD LLD

LLD F period- -i. ND ND ND ND ND O~~articulates~4

~chromiurm51

& LLD LLD LLD LLD LLDL 6 LLD LLD LLD LLD LLD iron- 9 LLD LLD LLD LLD LLD co~balt-57'

-cF LLD LLD LLD LLD LLD c , obaii'8,, ,&i LLD 1.52E-05 LLD LLD 1.52E-05 CJ Qb76 O. I -.C-i LLD LLD LLD LLD LLD znlC6 CC LLD LLD LLD LLD LLD s .tr~ntium 89 C I LLD LLD LLD LLD LLD st 9 C- LLD LLD LLD LLD LLD r nol c LLD LLD LLD LLD LLD L- cesiurIi-.I 34' i, LLD LLD LLD LLD LLD ces.iuD1374 LLD LLD LLD LLD LLD.bari m/aihanu .i4?,:. LLD LLDLLDE LLD c 41urii_ C LLD LLD LLD LLD LLD.ce num-44 LLD-LL LLD LLD LLD NONE NONE NONE NONE NONE pND 1.52E-05 ND ND 1.52E-05 I I I I I I I I I I I I 1 I LLD = Below the Lower Limit of Detectability, in uCi/cc (Table 4).ND = None Detected I Form 1/2-ENV-01.05.FO1 (page 21 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Reporl Calendar Year -2008 Table 1 B-EC Gaseous Effluents

-Elevated Continuous Releases RTL # A9.690E Enclosure 2, Page 4 of 21 2nd.dar:'NuLciides release~d;ý U4 h3 itý urr Quarter _urer urte, erw 7 Oj__ _r______ _ r4,1 -j. A LLD 3.57E-02 LLD LLD 3.57E-02._ff =on _ L -LLD LLD LLD LLD LLD Z1!Yp!Q: --, UJ LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD k r& LLD LLD LLD LLD LLD 3,1f : , LLD LLD LLD LLD LLD__,, _____ ___.-_ L CiY A 7.69E-02 LLD LLD LLD 7.69E-02____' " .. LLD LLD LLD LLD LLD-..,,- 1 ,. LLD LLD LLD LLD LLD.'nn Ci,.. LLD LLD LLD LLD LLD'~ ~~c~ LLD LLD LLD LLD LLD j NONE NONE NONE NONE NONE A. feo&'- 7.69E-02 3.57E-02 ND N D 1.13E-01 LLD 1.17E-07 LLD LLD 1.17E-07 M LLD LLD LLD LLD LLD 1_ 77 I LLD LLD LLD LLD LLD___ ND I1.17E-07 I ND I ND 1.17E-07.ilLcrmum.i, F t LLD LLD LLD LLD LLD_m___ ___. _ I7j4 !' LLD LLD LLD LLD LLD g "A ','I LLD LLD LLD LLD LLD 4." LLD LLD LLD LLD LLD Q--. ,-'!-. LLD LLD LLD LLD LLD.... .dV LLD LLD LLD LLD LLD* LLD LLD LLD LLD LLD-ýcesjum-9 a LLD LLD LLD LLD LLD~trim tO' ~ C LLD LLD LLDLDLD ,, alua LLD LLD LLD LLD LLD Floi~3 j~ ~~ 6 LLD LLD LLD LLD LLD.LLD LLD LLD LLD LLD C+.r LLD LLD LLD LLD LLD 14 4~~i~6~ LLD LLD LLD LLD LLD E?,ti LLD LLD LLD LLD LLD.NONE NONE NONE NONE NONE Lf 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 Radioactive Effluent Release Repori Calendar Year -2008 Table 1C-GB1 Gaseous Effluents

-Ground Level Batch Releases (Unit 1)"RTL # A9.690E Enclosure 2, Page 5 of 21 I I I I LLD LLD LLD LLD LLD LLD LLD LLD LLD. LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD-unidentfiqd IM CI NONE NONE NONE NONE NONE'oiIiI ND ND ND ND ND ioWi1iM MW LLD LLD LLD LLD LLD 9JI.OITO3 M ISM Ii'vCi LLD LLD LLD LLD LLD3 I LLD LLD LLD LLD LLD J ND ND ND j NDLLD LLD LLD LLD LLDLLD LLD LLD LLD LLD_____ _i,-__LLDLLD LLD LLD LLD M__ LLD LLD LLDLD L LLD LLD LLD coT_~ ____0___LLDLL LLD LLD LLD p LLD LLD LLD LLD LLD gi[C f LLD LLD LLD LLD LLD-strontim-0 LLD LLD LLD LLD LLD rma-n'u- 9 7 i _ LLD LLD LLD LLD LLD e-u9- i LLD LLD LLD LLD LLD eii' LLD LLD LLD LLD LLD_ LLD LLD LLD LLD LLD N erium51 LLD LLD LLD LLD LLD-.ýdI, LLD LLD LLD LLD LLD Und1ntiN1 NONE NONE NONE NONE NONE teI I ND ND ND ND ND i I I!I I ,I I I I I I I LLD = Below the Lower Limit of Detectability, in uCi/cc (Table 4).ND = None Detected I Form 1/2-ENV-01.05.F01 (page 23 of 38), Rev 2 Beaver Valley Power Station -Unit 1 RTL # A9.690E Enclosure 2, Page 6 of 21 Radioactive Effluent Release Report Calendar Year -2008 Table 1C-GO1 Gaseous Effluents-Ground LevelContinuous Releases (Unit 1)4 st~ --'2ndý 3rd M 4hlen._Mv-(relase -;,ni KQua'rt Qaer Quarter. `,`qaeu, artier !,. r~-_ LLD LLD LLD LLD LLD Iq -LLD LLD LLD LLD LLD 7yA-. I LLD LLD LLD LLD LLD e, ýkp LLD LLD LLD LLD LLD pt'j8 ,LLD LLD LLD LLD LLD qn9_nbi-3i133_.

jI LLD LLD LLD LLD LLD j qn,-~33 -IC T LLD LLD LLD LLD LLD 3i LLD LLD LLD LLD LLD bi -._ LLD LLD LLD LLD LLD Sci LLD LLD LLD LLD LLD.. ........ .......n L I L L D L L D L L D L L D S NONE ýNONE NONE NONE NONE~ ~ ~ ~ K~ ND ND ND ND ND In J37!um __ LLD LLD LLD LLD LLDg 5Ii LLD LLD LLD LLD LLD 7: 2ihei35 9 _ _- ,-',.V LLD LLD LLD LLD LLD!, t ,3 NLD N D N D N D N DLLD LLD LLD LLD LLD SLLD LLD LLD LLD LLD V.i L ,i LLD LLD LLD LLD LLD 97 Ci, ,-LLD LLD LLD LLD LLD"Q IM LLD 2.48E-05 LLD LLD 2.48E-05" o.... " ..LLD LLD LLD LLD LLD=n---jj; I LLD LLD LLD LDLLD zj~q U7 W 9S LLD LLD LLD LLD LLD=Icif~ ýIiuM .LLD LLD LLD LLD LLD SLLD LLD LLD LLD, LLD L-q 7es r~- LLD. LLD LLD LLD LLDýýj L rr ' LLD LLD LLD LLD LLD LLD -LLD LLD LLD LLD-Te~1§ LLD LLD LLD LLD LLD-J LLD LLD LLD LLD LLD 67L,7§~ & NONE NONE [ NONE* NONE NONE Orrm. N LND L4L-05 IND ND 2.48E-05 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 Report Calendar Year -2008 Table 1C-GB2 Gaseous Effluents

-Ground Level Batch Releases (Unit 2 4tua"-, e -~~~~~' Nuldsie~s t~ ua~ Qrua6rter.

Quarter~V' W Qu~rt'de Yar:I:I

>i'jjf?.:..

CI LLD 1.58E+00 LLD LLD 1.58E+00'~kypo-8 i LLD LLD LLD LLD LLD ,_rypt~o~n"-85m"...i LLD 3.23E-03 LLD LLD 3.23E-03 LLD 6.59E-03 LLD LLD 6.59E-03-,,r~tn-88.Ci LLD 8.43E-03 LLD LLD 8.43E-03 Ixe; n:"3"-,,, LLD LLD LLD LLD LLDxenon 33', <; ... LLD 1.42E-02 LLD LLD 1.42E-02 LLD ' LLD LLD LLD LLD! _ o,,-1,3 _._ ,, F.i LLD 2.01 E-02 LLD LLD 2.01 E-02~ < i LLD LLD LLD LLD LLD' I LD LLD LLD LLD LLD uldetiif-idl NONE NONE I NONE NONE NONE f ND 1.63E+00 ND ND 1.63E+00

LLD LLD LLD LLD LLD d' '.-iod'neij33j" , 7L* 77ji777L LL J LLD L LLD LLD ,dn13, LLD LLD LLD LLD LLDND ND ND ND T N D LLDdne~ LLD J LLD LLD LLD____Jm- ._ -LLD LLD LLD LLD LLD_ m ..1-. LLD LLD LLD LLD LLD.ro.nn,59.-. .i LLD LLD LLD LLD LLD SC¢obalt 57 -. ' LLD LLD LLD LLD LLD"_ ' LLD 1.38E-05 LLD LLD 1.38E-05 oba.t.-60

i. LLD 9.17E-07 LLD LLD 9.17E-07.-ii-.5, .i LLD LLD LLD LLD LLD s_.tron-tm89_

C LLD LLD LLD LLD LLD:._i ston~mo j... C" LLD LLD LLD LLD 1 ou o 97 Ci '9 LLD LLD LLD LLD LLD ds 'C_ LLD LLD LLD LLD LLD.CI LLD 9.17E-07 LLD LLD 9.17E-07.. ..r.u...ant

..n .. 140 C. LLD LLD LLD LLD LLD 7 4.'-,. .' LLD LLD LLD LLD LLDceriumIl44,. CIj LLD LLD LLD LLD LLD I._'uiiidentife4LtL,.-., Ci NONE NONE NONE NONE NONE tot fo pr6d C ND 1.56E-05 ND ND 1.56E-05 I I I I I I I I!U I I I 1 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 RTL # A9.690E Enclosure 2, Page 8 of 21 Radioactive Effluent Release Repori Calendar Year -2008 Table 1C-GC2 Gaseous Effluents

-Ground Level Continuous Releases (Unit 2)P,r s ,.. -chori -LLD LLD LLD LLD LLD....... C .LLD LLD LLD LLD LLD_____,____LLD LLD LLD LLD LLD jobt-7CF LLD LLD LLD LLD LLD c at 5 j , t' LLD 3.82E-05 LLD LLD 3.82E-05 1i LLD, LLD LLD LLD LLD.. Y LLD LLD LLD LLD LLD-ai'- LLD LLD LLD LLD LLD k.:ri-O~~~

~___LLD__

LLD LLD LLDLD zircg WiM/n6iobrum-95i LLD LLD LLD LLD LLD ,cei' LLD LLD LLD LLD LLD1 m :CIr LLD LLD LLD-1k, bari I nu-. 4O, ° CI LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I LLD LLD LLD LLD LLD~ intiI~d~j 4 i~ ~NONE ] ONE ]NONE ]NONE jo E__ _ND ]3.82E-05

] ND ] ND 3.82Eý-05 LLD = Below the Lower Limit of Detectability, in uCi/cc (Table 4).ND = None Detected Form 1/2-ENV-01.05.FO1 (page 26 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2008 Table 2A Liauid Effluents

-Summation Of All Releases RTL # A9.690E Enclosure 2, Page 9 of 21 I U I-- -I ..................................d.. ..T o t a l st,, I§ -4.. 0'2,Unit' QurtrQuarter Qarter ,uai ~~ v,,,a~ Erro, 0 oar s x 5.68E-02 6.76E-02 1 .97E-01 7.64E-02 3.97E-01 Ltt dAvera eAduea~concentratib .L uGi/mP 3.37E-08 5.47E-08 1.44E-07 4.97E-08 6.82E-08:3,,Percen of apicaSble limit 8-% 2.27E+00 2.70E+00 7.86E+00 3.06E+O0 3.97E+00 3. eizn-650oi'

.1, OM--ci 3.07E+02 5.OOE+02 1.54E+02 5.42E+02 1.50E+03 25 2....... ...diluted.concentration.

.1.82E-04 4.05E-04 1.13E-04 3.52E-04 2.58E-04 Sf~appIjoablellm!it

-_ /' 1.82E+00 4.05E+00 1.1 3E+00 3.52E+00 2.58E+00 b, U'-D-.G~ross alpla, radioactlvli oW :-,r.,,::-:;

C- i LLD LLLLlLDLL(t ta ele se),, ;',

V :1: LLD LLD LLD LLD LLD 2 8. I 28.9% I I e VOlumeof.te release: d liters,,l 2.34E+06 2.19E+06"-. (pior, to i, t on)0 ' " 2.41 E+06 2.43E+06 9.37E+06 11.2% I 0ý_ W "ILL, I.414 .44 '4 <.2 A-1 4 14V.'<%14 X .4~F:' Volume 6fdilUt16h'Wat~e-r6 6-d', "j!lite. 1.8E0 23+9 136+9 1.4+9 5.1E0 1.68E+09 1.23E+09 1.36E+09 1.54E+09 5.81 E+09 22.9% 3 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 Form 1/2-ENV-01.05.FO1 (page 27 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2008 Table 2B-B Liquid Effluents

-Batch Releases RTL # A9.690E Enclosure 2, Page 10 of 21 C *~'~ I* 77.... .aI , Ua 1- Qu Lrte LLD LLD LLD LLDLLD LLD LLD LLD LLD 51 .,& 3.21E-04 2.97E-03' 1.46E-03 LLD 4755-03 man gffese54!~

-Ci 1.28E-04 4.54E-04 4.40E-04 3.34E-04 1.36E-03 ron55 i 2 -02 8.31 E-03 1.01E-01 3.02E-02' 1.63E-01 iron5!' .. C, 4.94E-04 8.58E-04 1.21 E-03 1.64E-04 2.73E-03 cobalt57 Cii 1.67E-05 9.14E-05 2.66E-04 2.56E-04 6.30E-04 cobalt,58

,.l'.. 2.43E-03 3.48E-02 4.24E-02 2.13E-02 1.01E-01 nobalt-60

ý i <' --Ci 3.95E-03 3.41 E-03 1.24E-02 9.99E-03 2.97E-02-zinc-5.-

C Ci 1.95E-03 3.53E-04 6.02E-03 3.81E-03 1.21 E-02 ,srobntiumf-89 LC LLD LLD LLD LLD LLD Sstro ntium90- -CiL LLD LLD LLD LLD LLD zi~rconium/~niobium-95 hi 955.84E-05 9.58E-05 3.78E-04 2.80E-04 8.12E-04 izirc.oniu/nio

.6 i1uLn97 C 1 z .i. 8.16E-06 1.02E-05.

7.422-06 2.45E-05 -5.03E-05 mo b d- , ... LLD LLD LLD LLD LLD tin- I CIC LLD LLD LLD LLD LLD 6: -C 9.91E-04 1.42E-03 1.39E-03 1.04E-03 4.85E-03 a ntir68n71 2ý2U§ ZXi LLD 4.72E-04 LLD LLD 4.72E-04#antumonyl24

-"'C 1.41 E-03 2.17E-03 7.96E-04 LLD 4.37E-03' 644 -8Cij 2.14E-02 1.21E-02 2.85E-02 8.18E-03 .- 7.01E-02...i... .. .LLD LLD LLD LLD LLD i, 15Eesum034..71 4,. ` -.i 1.53E-05 4.71E-07 LLD. 3.78E-05 5.36E-05n ....... .- 3.65E-04 6.42E-05 3.52E-04 8.35E-04 1.62E-03___ i LLD LLD LLD LLD LLD-ceri, Iu ,i '4.4' Ci LLD LLD LLD LLD LLD u.. i ..... ...f.lie'd. Ci NONE, NONE NONE NONE NONE S a'

=rooi 5.68E-02 6.76E-02 1.97E-01 7.64E-02 3.97E-01 LLD = Below the Lower Limit of Detectability, in uCi/ml (Table 4)

Form 1/2-ENV-01.05.FO1 (page 28 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 RTL # A9.690E Enclosure 2, Page 11 of 21 Radioactive Effluent Release Report Calendar Year -2008 Table 2B-C Liquid Effluents

-Continuous Releases 1s *I Ujd ath C alendar Nuclidesrleased UnitQ Qure Quarter~ Quarter Qatr Ya ,oli,.,ýssion and activaton.

Orpducts berlonurr GVT_ N/A N/A N/A N/A N/A

., N/A N/A N/A N/A N/ACO~a ! -, o u i: T,.=,' .1-, 1T,, C N/A N/A N/A N/A N/A mansu anesume-54 N/A N/A N/A N/A N/A c _5!r__ti N/A N/A N/A N/A N/A z n6u, i N/A N/A N/A N/A N/A.i;u,,,,u N/A N/A N/A N/A N/A m.ol.-d...

..il N/A N/A N/A N/A N/At 6bint-5u m N/A N/A N/A N/A N/A c

-Ci o N/A N/A N/A N/A N/A 2 .i6 N/A N/A N/A N/A N/A;z.ic765iii ,IO,-, -1 N/A N/A N/A N/A N/A-n.C:. N/A N/A N/A N/A N/A trconeium.lum3Z 90 ,Ci N/A N/A N/A N/A N/A j N/A N/A N/A N/A N/A mecnetium-96 Ci N/A N/A N/A N/A N/A techntheium-99r3

-P Ci,. N/A N/A N/A N/A N/A ru -i N/A N/A N/A N/A N/A silTtf eo-124 'i -, -I < if N/A N/A N/A N/A N/A ani~n- 24C N/A N/A N/A N/A N/A ant-ironllhe1251

-,, Cl N/A N/A N/A N/A N/A>iodine-133j1,-.

-i N/A N/A N/A N/A N/A cesdmiun134~

-Ci N/A N/A N/A N/A N/A;cesium-i 37 I-C" N/A N/A N/A N/A N/A 6' ba umi/Ianthaniiiri 1 4Q,', C~j N/A N/A N/A N/A N/A ceriurn-1 41~ CI.l N~/A N/A N/A N/A N/A ,-,- ,iCeiun17144,'N/A N/A N/A N/A N/A-'uiidntfieid>

'J i- _ N/A N/A N/A N/A N/A jr~jota'or peiod C 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 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 RTL # A9.690E Enclosure 2, Page 12 of 21 Radioactive Effluent Release Report Calendar Year -2008 Table 3A Solid Waste And Irradiated Fuel Shipments (Part 1 of 3)L ---I. T So.as (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 30 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2008 Table 3B Solid Waste And Irradiated Fuel Shipments (Part 2 of 3)RTL # A9.690E Enclosure 2, Page 13 of 21 iASohd FiBrlOrrdtdfueI) -%:!: <, L :,: " :; -: .". D is osa (Not W r,::,,' " +,d ; nm m nae a.,-juipm ent .e

.1st Hal.tH If J, 2nd H alf k.L. j oir ...."Er ror :':" "..ip. .7=.,. 4.71E+01 m3 1.48E+02 m3 0.0% (1).v t u ried 6 .6 .._ .. 1.15E+02 m3 6.16E+01 m3 0.0% (1), oIv 3.07E-01 Ci 3.89E-01 Ci 30.0%1 .Estiffie'dt36fiadjo;Ndlift.

Composition V ,',.4. -S"~P~t4~A~ ~.' >: l-' , "0.98 % 1.90 %~ .L~.i0.47 IN 0.91'%, Cr51 .6.52 % 0.30 %.-Mn , --. .- ..1.45 % 2.12 %, FOe55, : , L ._.17.00 % 30.30 %L9_I4 _ -iZ r__ " 13.40 % 7.11 %-o:-60...

.8.38 % 17.60 %._N 59 .-.0.15 % 1.68 %_ Ni-3 -8.75 % 18.20 %Sr-9 .0.07 % 0.02 %WNb-95 , 23.00 % 2.74 %Zr;9"- "15.00 % 5.86 %L7._Tc-99

.< ..,".0.01 % 0.00 %~A-1O .0.09 % 0.00 %, Sb-25-_ 0.72 % 1.38 %0.01 % 0.00 %S-,'LC 34 .0.08 % 0.04 %-:: l ,-= ' 0.24 % 0.32 %.,- 0.09 % 0.26 %a yp3,i~ 8 4 , of .... Ty eA ,,0 0 Cnainer~i I-- Ty 0 0"Use-d --~ r Qatt 0 0 b. Solidification Ceen 0 0 Agent :ormaldlyde

-0 0 DUntd None- .Lm .- 8 4',6. Mode~ of Truck 8 4 Tanspor -Rail00______________

Oter0 0? ia -L ak i.gT L ~ 8 4 Desination

'Wa--M'mpumPA 0 Clas '- ~ClasB0 0-7 s",Class C }0 0.~-jOCR15W6

->lsC~ 0 0 I I I I I I 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 -2008 Table 3C Solid Waste And Irradiated Fuel Shipments (Part 3 of 3)RTL # A9.690E Enclosure 2, Page 14 of 21 1,13'INdjfradiatbdýFue hiiets , ,.eV~hi~`4-(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 32 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2008 Table 4 Lower Limits Of Detectability (LLD)RTL # A9.690E Enclosure 2, Page 15 of 21 7-"RWDA G 1 000 cc Gas:Grhb SamDle~:i 3) -~ ODCM ,"Calulated , equired L..id U L -:C > 1-u lLD (4) 1.OOE-06 1 E-06 7.17E-08 1E-04 o"! 1.54E-08 1 E-04 6.78E-07 1 E-04 154, i6.71 E-08 1 E-04 JFA55. :- .....Fe59 1.83E-07 1E-04 CO-., :, 6.55E-08 1 E-04 ,. '58

9.87E-08 1 E-04 Co_-'6_ "_ 9.96E-08 1 E-04 Zn-85. !. 1.82E-07 1 -04 Kr ,. 1.91 E-05 1E-04*K-85fn 7.65E-08 1E-04.Kr,-8 1.32E-07 15-04 ,., -* .2.20E-07 1 E-04 so~, ------- -.........,Sr-k .1.14E-07 1E-04 ,N195 8.26E-08 1 E-04 ,N-97 ,2.79E-08 1 E-04 1.12E-07 12E-04 L itZ6-9 5.75E-08 1 E-04.-99ni L,5.60E-08 1 E-04 S 1 2.89E-08 1 E-042.. 6.33E-08 1 E-04"_2.00E-07 1E-04 1-131 7.37E-08 1 E-04 1-133 j 9.04E-08 1E-04 13 il_ ",_2.86E-07 1E-04.

2.90E-06 1 E-04 Xe-133i 1.66E-07 1 E-04 Xe-133mi.

5.18E-07 1 E-04-Xe-ii5 7.98E-08 1 E-04 e- 135m 6.77E-08 1E-04.37 2.28E-07 1 E-04 e 1x38 Ii 2.19E-07 1E-04_ 6.88E-08 1 E-04:cs.137., : 4.56E-08 1 E-04 I Bal3.j 3.15E-07 1 E-04 3.76E-07 1 E-04" .-" a 1.92E-08 1 E-04 ,jejj41'_._

1.10E-07 1 E-04I 2.42E-06 1 E-04_ -r-ssAIha

..RWDA-L 2: 1000 ml Liquid Grab Samnple..

-.(3): ýODCM 1Ca6 Ulated JReui~LLD .u: ,_(Ci/im) (ueili/i)1.005-06 1 E-05 1.54E-08 5E-07 3.32E-09 5E-07 1.55E-07 5E-07 1.45E-08 5E-07 (1) 1.00E-06 1 E-06 3.94E-08 5E-07 1.76E-08 5E-07 2.13E-08 5E-07 2.15E-08 5E-07 3.92E-08 5E-07 4.19E-06 1 E-05 1.96E-08 1 E-05 2.96E-08 1 E-05 5.36E-08 1 E-05 (1) 5.00E-08 5E-08 (1) 5.00E-08 5E-08 2.44E-08 5E-07 1.79E-05 5E-07 6.04E-09 5E-07 2.41 E-08 5E-07 1.49E-08 5E-07 1.45E-08 5E-07 6.28E-09 5E-07 1.38E-08 5E-07 4.45E-08 5E-07 1.67E-08 1 E-06 1.98E-08 5E-07 6.17E-08 5E-07 7.29E-07 1 E-05 5.20E-08 1 E-05 1.23E-07 1 E-05 1.89E-08 1 E-05 1.49E-08 1 E-05 5.06E-08 1 E-05.5.14E-08 1E-05 1.50E-08 5E-07 9.90E-09 5E-07 7.91 E-08 5E-07 8.24E-08 5E-07 4.08E-09 5E-07 2.83E-08 5E-07 2.01 E-07 5E-07 (1) 1.005-07 1 E-07 FiltIter EfflenCharcbsal Continuous Effluent S;amble.(3) ,"ODCM.Catlculteid Recjulred 1.55E-13 1E-11 5.98E-13 1E-11 1.00E-13 1E-11 2.26E-13 1E-11 7.48E-14 1E-11 1.27E-13 1E-11 1.11E-13 1E-11 1.30E-13 1E-11 (1) 1.00E-13 1E-11 (1) 1.005-14 1E-11 3.18E-14 1E-11 7.60E-14 1 E-11 8.27E-14 1 E-11 1.66E-13 1E-11 7.53E-14 1 E-11 7.34E-14 1E-11 8.59E-14 1 E-11 1.08E-13 1 E-11 2.40E-13 1 E-11 1;1OE-13 1E-12 8.46E-14 1E-10 1.01E-13 1E-11 9.94E-14 1lE-11 1.11E-13 12-11 3.812-13 1E-11 4.12E-13 15-11 3.40E-14 12E-11 1.53E-13 1E-11 4.95E-13 1E-11 (1) 3.512E-15 1lE-11 I I I I I I I I I U 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 09102/08.

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.Fo1 (page 33 of 38), Rev 2 Beaver Valley Power Station -Unit 1 Radioactive Effluent Release Report Calendar Year -2008 Table 5A Assessment Of Radiation Doses RTL # A9.690E Enclosure 2, Page 16 of 21 ,,4C6 tihn'uo js,, Dje~ ~OD M/C ioU P kQ-DCM D"ose O" A imt r A Limt 66se I'i,,,--DMi

_____ 2.89E-07 0.0000 1.36E-09 0.0000 1.30E-06 0.0000 0.OOE+00 0.0000 1.59E-06 0.00001.36E-09 0.0000 6.80E-12 0.0000 1.95E-09 0.0000 0.OOE+00 0.0000 3.32E-09' 0.0000 Y B_.e&3._ 0.00E+00 0.0000, 9.03E-06 0.0001 0.OOE+00 0.0000 0.OOE+00 0.0000 9.03E-06 0.0001 O " e , 9.81 E-02 1.3080 3.90E-02 0.5200 1.93E-02 0.2573 2.25E-02 0.3000 1.79E-01 1.1927q~ati'26d 9.81E-02 1.3080 3.90E-02 0.5200 1.93E-02 0.2573 2.25E-02 0.3000 1.79E-01 1.1927 G:aTWyr~jd:Ci 9.81E-02 1.3080 3.90E-02 0.5200 1.93E-02 0.2573 2.25E-02 0.3000 1.79E-01 1.1927Kide ~ 9.81E-02 1.3080 3.90E-02 0;5200 1.93E-02 0.2573 2.25E-02 0.3000 1.79E-01 1.1927,Lung Ii 9.81E-02 1.3080 3.90E-02 0.5200 1.93E-02 0.2573 2.25E-02 0.3000 1.79E-01 1.1927 I 9.81E-02 1.3080 3.90E-02 0.5200 1.93E-02 0.2573 2.25E-02 0.3000 1.79E-01 1.1927 (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 Controi 3.11.2.3 (considered to be the design objectives).

Form 1/2-ENV-01.05.FO1 (page 34 of 38), Rev 2 Beaver Valley Power Station -Unit 2 Radioactive Effluent Release Report Calendar Year -2008 Table 5B Assessment Of Radiation Doses RTL # A9.690E Enclosure 2, Page 17 of 21 I1 I I I I I I I I I I I I I I I I I~Uni~ GeouEffj~4

~1sIdii~t~r

-i~'Qartt -I -dd!' gt~ arter-. I -lnarier-M': DOse ODOM ,Dose -"ZO3M 2).IG-amn , r .89E-07 0.0000 1.34E-05 0.0003 1.30E-06 0.0000 O.OOE+00 0.0000 1.50E-05 0.0001 B ~taAlr 1.36E-09 0.0000 4.79E-06 0.0000 1.95E-09 0.0000 O.OOE+00 0.0000 4.79E-06 0.0000 B'One o.00E+00 0.0000 3.97E-05 0.0005 0.OOE+00 0.0000 O.OOE+00 0.0000 3.97E-05 0.0003 ,O Liver 2.54E-03 0.0339 2.48E-03 0.0331 2.36E-03 0.0315 2.68E-03 0.0357 1.01 E-02 0.0671 2.54E03 0.0339 248E-03 0.0331 236E-03 00315 26E-03 00357 1.01E-0 0.0671 yR. TtaBodyI 2.54E-03 0.0339 2.48E-03 0.0331 2.36E-03 0.0315 2.68E-03 0.0357 1.01E-02 0.0671 G Thyrid 2.54E-03 0.0339 2.48E-03 0.0331 2.36E-03 0.0315 2.68E-03 0.0357 1.01E-02 0.0671 AN r 2.54E-03 0.0339 2.48E-03 0.0331 2.36E-03 0.0315 2.68E-03 0.0357 1.01E-02 0.0671 k.54E03 0.0339 248-03 0.0331 .36-03 0.0315 E-03 0035 1.01 E-02 0.0671 ( b GILAI 2.54E-03 0.0339 2.48E-03 0.0331 t2.36E-03 0.0315, 2.68E-03 0.0357 10 -2 007 (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.F01 (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 Repori Calendar Year -2008 Table 6 It Efe-it, it Instrumni`tation;Channels' Not Retur ned To Operaible Status Within. 30,Days$`,,, IRM-1DA--100]

-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. CR08-50435, CR08-50765, CR08-50899, CR09-52947, CR09-52964 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . 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.[2RMO-RO303]

-Unit 2 Waste Gas Storage Vault Vent Noble Gas Activity Monitor On 04/25/08 this monitor was removed from service due to a stuck check source. The thirty (30)day criteria was exceeded due to availability of rep5lacement solenoid, and an apparent misinterpretation of the required due date to return the monitor to Operable status. This condition and associated Corrective Actions are detailed in BVPS Condition Report No. CR09-56073, and BVPS-SAP Order Number 200197646-0800.

As required by ODCM procedure 1/2-ODC-3.03, "Controls for RETS and REMP Programs", (as referenced in procedure Attachment F, Control 3.3.3.10, Table 3.3-13, Action 29), effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and analyzed for gross radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . A total of 102 grab samples were obtained and analyzed until the monitor was returned to operable status on 05/29/08.

All gamma spectrometry analyses of these samples were less than LLD.

Form 1/2-ENV-01.05.FO1 (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 -2008 Table 7 Total Dose Commitments, Total Effective Dose Equivalents and Population Doses Total Dose CoommitmentFrom All Iacility Releases To Meembers,,of the Public 40ACFR 190.10(a)

Environmental Doses'(1) % (2) %ofODCMor Organ Effluent-Dose Direct Radiation Dose, Total Dose 40 CFR 190 Limit, (mrem) (mnem) (mreth): Bone 5.99E-02 O.OOE+0O 5.99E-02 0.24%iver .; 3.29E-01 O.OOE+00 3.29E-01 1.32%-Tot .'Bdoa2.81 E-01 O.OOE+O0 2.81 E-01 1.12%Thyroid- -2.17E-01 0.00E+00 2.17E-01 0.29%'Kidney. 2.71E-01 0.00E+00 2.71E-01 1.08%Lung .-2.24E-01 0.00E+00 2.24E-01 0.90%, GI-L-I ,2.75E-01 O.OOE+00 2.75E-01 1.10%(1) The, cumulative dose contributions from liquid and gaseouseffluents were determinedn accordance with the'applicabje CONTROLS & SURVEILLANCE REQUIREMENTS listed, in ODCM prbcedure.1!/2ODC-3.03.

The dose Scomitentrlimits' for 40 C=R 190 M EMBE OFi THE PUBLIC (ODCM aire-as follws: a), < or -25 mrerm calendar year (foar the total body, 9r any organ except the thyroid).b) < or 75 mrem/l'calendar year (for the thyroitd)

S I I I U I I I U U I I I I I I I I I-(2),,Tfie~dose'¢ont ibuUon listedl for the total' body, i for. DirectRadiation.

This was calculaied by *omparingffsite TLD"* exposure at the ODCM controlling location,(0.8 miles"NW; Midland, PA) to TLD exposure at the REMO coritrol'location (6.5 miles SSW;,Weirton, WV)..Compliance,t p'1 0 0 rnrern Limit of 10 CFR. 20.130i For Total Effectivde Dse Equivaliet 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 0.00 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).M-embers, 6f the P-ubi~c Doses Duse To Their Acivitidt

-Inside The site

-.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.Mle _ ypulatibn Dm ses From Liquid and, s Effluents 0-50 mile Total Population Dose from liquid and gaseous effluents

= 546 man-mrem (Total Body)0-50 mile Average Population Dose from liquid and gaseous effluents

= 0.0001365 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 -2008 Table 8'1'..; ~ffSite Dose:GCd~i6hW M Uh0iS~urvdillancedefcenisy-Failure to Change-Out Weekly Filter Media on Gaseous Effluent Monitors ODCM procedure 1/2-ODC-3.03 "Controls for RETS and REMP Programs", Attachment K, Surveillance Requirement 4.11.2.1.2, Table 4.11-2 requires weekly sampling (i.e.;change-out) of the particulate filter paper charcoal cartridge.

Contrary to this requirement, the DRMS filter media (for all five of the continuous gaseous effluent pathways) ran for a 14-day period (04/02/08

-04/16/08) instead of the required 7-day period (04/02/08

-04/09/08).

SINCE this is a Surveillance Deficiency of ODCM procedure 1/2-ODC-3.03, Attachment K, Surveillance Requirement 4.11.2.1.2, Table 4.11-2, THEN annotation is required in the 2008 Radioactive Effluent Release Report per the reporting requirements of ODCM procedure 1/2-ODC-3.03, Attachment U, Control 6.9.3.The five continuous gaseous effluent pathways that were not changed-out per the ODCM requirement are as follows: 1) VV-2, Unit 2 SLCRS Unfiltered Pathway [2HVS-RQ1 01]2) CV-2, Unit 2 SLCRS Filtered Pathway [2HVS-RQ1 09]3) DV-2, Unit 2 Decontamination Building Vent Pathway [2RMQ-RQ301]

4) WV-2, Unit 2 Waste Gas storage Vault Vent Pathway [2RMQ-RQ303]

5) CB-2, Unit 2 Condensate Polishing Building Vent Pathway [2HVL-RQ1 12]There were no consequences to the health and safety of the public by failing to obtain the samples on the required date. Specifically, no samples were lost, and a follow-up review of the sample analyses provided assurance that the effluent activity of the short-lived radionuclide of interest (e.g.; 1-131 with half-life

= 8.04 days) was not underestimated as a result of exceeding the normal sample period. This condition and associated Corrective Actions are detailed in BVPS Condition Report No. CR08-38484, and BVPS-SAP Order Number 200197646-0500.

Failure to Obtain a Grab Sample From an Inoperable Gaseous Effluent Monitor ODCM procedure 1/2-ODC-3.03 "Controls for RETS and REMP Programs", Attachment F, Control 3.3.3.10, Table 3.3-13, Action 29 requires that effluent releases may continue via this pathway provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .Contrary to this requirement, a grab sample for the radiation monitor on Unit 2 Condensate Polishing Building Vent Pathway [2HVL-RQ1 12] was missed during the inoperable period. The timeline of the condition indicated that on 10/23/08 the monitor was declared inoperable and the required once per shift grab samples were initiated.

On 11/06/08 at 1610 hours0.0186 days 0.447 hours 0.00266 weeks 6.12605e-4 months the monitor was prematurely declared operable following repair, valve line-ups and set point verifications and the ODCM actions listed above were prematurely exited. On 11/07/08 at 0430 hours0.00498 days 0.119 hours 7.109788e-4 weeks 1.63615e-4 months it was noted that the operations surveillance associated with the monitor was overdue, and the monitor was again declared inoperable.

In summary, since the monitor had been prematurely declared operable, then there was a failure to obtain a grab sample during an inoperable period.Sampling resumed until the monitor was properly returned to operable status on 11/07/08.This condition and associated Corrective Actions are detailed in BVPS Condition Report No. CR08-49089, and BVPS-SAP Order Number 200197646-0680.

Form 1/2-ENV-01.05.FO1 (page 38 of 38), Rev 2 Beaver Valley Power Station -Units 1 & 2 RTL # A9.690E Enclosure 2, Page 21 of 21 Radioactive Effluent Release Report Calendar Year -2008 Table 9 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 -2008 Attachment 1 Joint Frequency Distribution Tables 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 2008 are similar to recent years. During 2008 there was a slight shift towards more unstable and correspondingly less neutral hours than in recent years. This was probably caused by a combination of normal year-to-year variation and a change in the nature of the ground around the tower from weeds and grass in previous years to just dirt in 2008. It should be returned to a more natural state in 2009.fMet-e6`or66oi6Al,'Mfa Fr~6ez-mtd 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 99.5% = Wind Speed 35'99.5% = Wind Speed 150'97.6% = Wind Speed 500'99.5% = Wind Direction 35'99.5% = Wind Direction 150'96.0% = Wind Direction 500'99.5% = Delta Temperature (150' -35') 1 P 99.5% = Delta Temperature (500' -35') 2P 99.5% = Temperature 35'99.5% = Precipitation 99% = Average Recovery of Individual Meteorological Parameters PERCENT RECOVERY OF COMPOSITE VARIABLES 99.5% = Wind Speed 35', Wind Direction 35', Delta Temperature 1 P 99.5% = Wind Speed 150', Wind Direction 150', Delta Temperature 1 P 97.7% = Wind Speed 500', Wind Direction 500', Delta Temperature 2P.99.2% =, Average Recovery of Composite Variables Ait-ilfi~iLj, , rii~t 'n- t'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 Enclosure 2, Attachment 1 (Part I of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2008 Attachment 1 Part 1: Joint Frequency Distribution Tables (35ft)Page 1 of 8 Hours at Each Wind Speed and Direction Total Period Period of Record =Elevation:

Speed: Stability Class A 1/1/2008 00:00 -12/31/2008 23:00 SP35P Direction:

D1351 Delta Temperature Lapse: DT150-35 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 4-8 8-13 13-19 19-25 >25 Total 17 22 15 19 6 18 19 9 7 5 14 21 20 24 17 22 49 39 20 36 23 33 23 15 18 41 73 139 182 101 61 50 0 0 0 0 0 0 0 0 1 7, 30 40 33 21 5 1 0 0 0 0 0 0 0 0 0 1 1 3 1 3 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 66 61 35 55 29 51 42 24 26 54 118 203 236 149 84 73 I I I I I I I I I I I I I U I I I I I Total 255 903 138 Calm Hours not Included above for: Variable Direction Hours for: Invalid Hours for: Valid Hours for this Stability Class for: Total Hours for Period 10 0 0 1306 Total Period Total Period Total Period Total Period 16 0 45 1306 8784 RTL A9.690E Enclosure 2, Attachment 1 (Part 1 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2008 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 = 1/1/2008 00:00 -12/31/2008 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 2 8 0 0 0 0 10 NNE 7 5 0 0 0 0 12 NE 10 4 0 0 0 0 14 ENE 5 2 0 0 0 0 7 E. 7 4 0 0 0 0 11 ESE 4 2 0 0 0 0 6 SE 1 1 0 0 0 0 2 SSE 3 0 0 0 0 0 3 S 2 2 0 0 0 0 4 SSW 3 1 1 0 0 0 5 SW 3 8 7 0 0 0 18 WSW 6 13 8 1 0 0 28 W 7 17 14 0 0 0 38 WNW, 4 21 5 1 0 0 31 NW -7 15 1 0 0 0 23 NNW 6 17 0 0 0 0 23 Total 77 120 36 2 0 0 235 Calm Hours not Included above for: Total Period 16 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 45 Valid Hours for this Stability Class for: Total Period 235 Total Hours for Period 8784 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 -2008 Attachment 1 Part 1: Joint Frequency Distribution Tables (35ft)Page 3 of 8 Hours at Each Wind Speed and Direction Total Period Period of Record= 1/1/2008 00:00 -12/31/2008 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 11 13 0 0 0 0 24 NNE 5 3 0 0 0 0 8 I NE 12 3 0 0 0 0 15 ENE 12 4 0 0 0 0 16 E 3 3 0 0 0 0 6 ESE 5 1 0 0 0 0 6 SE 3 1 0 0 0 0 4 SSE 0 0 0 0 0 0 0 S 2 4 0 0 0 0 6 SSW 2 6 3 0 0 0 11 SW 4 14 6 0 0 0 24 WSW 12 20 3 1 0 0 36 W 12 16 13 0 '0 0 41 WNW 7 12 6 0 0 0 25.NW 6 14 2 0 0 0 22 NNW 8 10 0 0 0 0 18 Total 104 124 33 1 0 0 262 Calm Hours not Included above for Total Period 16 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 45 Valid Hours for this Stability Class for: Total Period 262 I Total Hours for Period 8784 I I I I I RTL A9.690E Enclosure 2, Attachment 1 (Part I of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2008 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 =Elevation:

Speed: Stability Class D 1/1/2008 00:00 -12/31/2008 23:00 SP35P Direction:

D135P.Lapse: DT150-35 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 4-8 8-13 13-19 69 105 89 112 76 30 37 35 30 54 58 70 70 75 102 69 57 21 16 60 30 4 6 13 36 58 175 221 270 177 140 83 0 0 0 0 0 0 0 0 2 21 108 135 126 24 10 3 0 0 0 0 0 0 0 0 0 4 21 11 0 0 0 19-25 0.0.0 0 0 0 0 0 0 0*1 2 0 0 0 0> 25 Total 0 0 0 0 0 0 0 0*0 0 0 0 0 0 0 0 126 126 105 172 106 34 43 48 68 133 346 449 477 276 252 155 Total 1081 1367 429 Calm Hours not Included above for: Variable Direction Hours for: Invalid Hours for: Valid Hours for this Stability Class for: Total Hours for Period 36 3 0 2916 Total Period Total Period Total Period Total Period 16 0 45 2916 8784 RTL A9.690E Enclosure 2, Attachment 1 (Part 1 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2008 Attachment 1 Part 1: Joint Frequency Distribution Tables (35ft)Page 5 of 8 Hours at Each Wind Speed and Direction Total Period Period of Record =Elevation:

Speed: Stability Class E 1/1/2008 00:00' -12/31/2008 23:00 SP35P Direction:

D135P Lapse: DT150-35 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 1-4 4-8 8-13. 13-19 19-25> 25 Total 49 66 131 161 135 89 117 98 173 156 84 44 46 44 72 57 14 5 12 52 14 2 1 14 60 109 93 51 46 29 25 7 0 0 0 0 0 0 0 0 8 13 21 30 24 2 0 0 0 0 0 0 0 0 0 0 0 2 2 4 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0.63 71 143 213 149 91 118 112 241 280 200 129 117 75 97 64 I I I I I I I I I I I I I I I I I I I Total 1522 534 98 9 0 0 2163 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 16 0 45 2163 8784 RTL A9.690E Enclosure 2, Attachment 1 (Part 1 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2008 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 = 1/1/2008 00:00 -12/31/2008 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 10 0 0 0 0 0 10 NNE 19 1 0 0 0 0 20 NE 40 2 0 0 0 0 42 ENE 51 0 0 0 0 0 51 E 104 0 0 0 0 0 104 ESE 180 0 0 0 0 0 180 SE 243 0 0 0 0 0 243 SSE 174 0 0 0 0 0 174 S 126 7 0 0 0 0 133 SSW 69 14 0 0 0 0 83 SW 35 0 1 0 0 0 36 WSW 13 0 1 0 0 0 14 W 6 3 5 0 0 0 14 WNW 9 0 0 0 0 0 9 NW 11 1 0 0 0 0 12 NNW 9 1 0 0 0 0 10 Total 1099 29 7 0 0 0 1135 Calm Hours not Included above for: Total Period 16 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 45 Valid Hours for this Stability Class for: Total Period 1135 Total Hours for Period 8784 RTL A9.690E Enclosure 2, Attachment 1 (Part I of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2008 Attachment 1 Part 1: Joint Frequency Distribution Tables (35ft)Page 7 of 8 Hours at Each Wind Speed and Direction Total Period Period of Record =Elevation:

Speed: SP35P Stability Class G 1/1/2008 00:00 -12/31/2008 23:00 Direction:

D1351 Delta Temperature Lapse: Extremely Stable DT150-35 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 7 10 11 29 69 134 243 83 50 28 10 13 1 2.7 3 700 0 1 0 0 1 0 0 0 2 1 1 0 0 0 0 0 0 0 0 0 7 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 11 11 29 70 134 243 83 52 29 11 13 1 2 7 3 I I I I I I I I I I I I I U I I I I I 6 0 0 0 0 706 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 16 0 45 706 8784 RTL A9.690E Enclosure 2, Attachment 1 (Part 1 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2008 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 = 1/1/2008 00:00 -12/31/2008 23:00 Elevation:

Speed: SP35P Direction:

DI35P Lapse: DT150-35.Delta Temperature Wind Speed (mph)Wind Direction

1-4 4-8 8-13 13-19 19-25 > 25 Total N 165 141 0 0 0 0 306 NNE 234 75 0 0 0 0 309 NE 308 57 0 0 0 0 365 ENE 389 154 0 0 0 0 543 E 400 75 0 0 0 0 475 ESE 460 42 0 0 0 0 502 SE 663 32 0 0 0 0 695 SSE 402 42 0 0 0 0 444 S 390 129 11 0 0 0 530 SSW 317 230 45 3 0 0 595 SW 208 364 .173 7 1 0 753 WSW 179 444 217 30 2 0 872 W 162 534 215 13 0 0 924 WNW 165 340 58 .4. 0 0 567 NW 222 256 18 1 0 0 497 NNW 174 168 4 0 0 0 346 Total 4838 3083 741 58 3 0 8723 Calm Hours not Included above for: Total Period 16 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 45 Valid Hours for this Stability Class for: Total Period 8723 Total Hours for Period 8784 RTL A9.690E Enclosure 2, Attachment 1 (Part 2 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2008 Attachment 1 Part 2: Joint Frequency Distribution Tables (150ft)Page 1 of 8 Hours at Each Wind Speed and Direction Total Period Period of Record =Elevation:

Speed: Stability Class A 1/1/2008 00:00 -12/31/2008 23:00 SP150P Direction:

DI150 Delta Temperature)P Lapse: DT150-35 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 4-8 8-13 13-19 19-25> 25 Total 6 5 5 2 0 1 3 0 1 1 9 14 14 9 11 2 42 29 18 30 28 17 19 12 11 9 20 40 92 55 34 30 34 22 6 23 16 24 31 10 35 32 48 65 115 65 27 24 0 2 1 0 0 3 5 2 2 6 11 10 48 45 3 0 0 0 0 0 0 0 0 0 0 2 1 2 10 3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3 1 0 0 82 58 30 55 44 45 58 24 49 50 89 131 282 178 75 56 I I I I I I I I I I I I I I I I I I I Total 83 486 577 138 18 4 1306 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 45 1306 8784 RTL A9.690E Enclosure 2, Attachment 1 (Part 2 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2008 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 =Elevation:

Speed: Stability Class B SP150P 1/1/2008.

00:00 -12/31/2008 23:00 Direction:

DI150P Lapse: DT150-35 Delta Temperature Moderately Unstable Wind Speed (mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW 1-4 1 1 1 0 1 1 3 0 0 1 3 4 1 2 4 2 4-8 10 9 5 10 5 3 5 1 3 4 3 5 10 7 8 8 8 -13 3 2 1 3 2 2 0 0 1 2 6 6'12 13 8 9 13-19 19-25 0 0 0 0 0 0 1 0 1 0 0 0 0 0 0 0 0 0 1 0 3. 0 2 1 17 7 10 1 0 0 0 0> 25 0 0 0 0 0 0 0 0 0 0 0.0 0 0 0 0 Total 14 12 7 14 9 6 8 1 4 8 15 18 47 33 20 19 Total 25 96 Calm Hours not Included above for : Variable Direction Hours for: Invalid Hours for: Valid Hours for this Stability Class for: Total Hours for Period 70 35 9 0 235 Total Period 3 Total Period 0 Total Period 45 Total Period 235 8784 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 -2008 Attachment 1 Part 2: Joint Frequency Distribution Tables (150ft)Page 3 of 8 Hours at Each Wind Speed and Direction Total Period Period of Record = 1/1/2008 00:00 -12/31/2008 23:00 Elevation:

Speed: SP150P Direction:, DI150P. 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 2 9 9 0 0 0 20 NNE 2 9 3 0 0 0 14 I NE 1 8 1 0 0 0 10 ENE 1 10 4 1 0 0 16 E 0 6 1 0 0 0 7 I ESE 0 3 1 1 0 0 5 SE 0 6 1 0 0 0 7 SSE 1 1 2 0 0 0 4 S 0 1 7 0 0 0 8 SSW 1 6 5 1 0 0 13 SW 0 4, 10 3 0 0 17 WSW' 4 7 7 0 1 0 19 W 9 17 14 17 2 0 59 WNW 2 12 10 6 0 0 30 NW 1 8 8 1 0 0 18 NNW 2 8 5 0 0 0 15 Total 26 115 88 30 3 0 262 Calm Hours not Included above for: Total Period 3 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 45 Valid Hours for this Stability Class for: Total Period 262 I Total Hours for Period 8784 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 -2008 Attachment 1 Part 2: Joint Frequency Distribution Tables (150ft)Page 4 of 8 Hours at Each Wind Speed and Direction Total Period Period of Record = 1/1/2008 00:00 -12/31/2008 23:00 Elevation:

Speed: SP150P Direction:

DI150P Lapse: DT150-35 Stability Class D Delta Temperature Neutral Wind Speed (mph)Wind Direction 1-4 4-8 8-13 3 -19 19-25 > 25 Total N 36 82 25 0 0 0 143 NNE 33 63 20 1 0 0 117 NE 38 44 7 0 0 0 89 ENE 22 107 48 4 0. 0 181 E 19 57 15 0 0 0 91 ESE 12 28 8 0 0 0 48 SE 16 26 8 0 0 *0 50 SSE 9 24 14 0 0 0 47 S 12 38 38 3 0 0 91 SSW 7 36 60 12 0 0 115 SW 25 83 121 36 2 1 268 WSW 28 80 160 65 15 3 351 W 37 86 280 184 47 6 640 WNW 30, 114 156 56 4 0 360 NW 27 92 53 6 0- .0 178 NNW 30 88 27 2 0 0 147 Total 381 1048 1040- 369 68 10 2916 Calm Hours not Included above for: Total Period 3 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 45 Valid Hours for this Stability

'Class for: Total Period 2916 Total Hours for Period 8784 I RTL A9 .690E Enclosure 2, Attachment 1 (Part 2 of 3)Beaver Valley Power Station -Units I & 2 Radioactive Effluent Release Report Calendar Year -2008 Attachment 1 Part 2: Joint Frequency Distribution Tables (150ft)Page 5 of 8 i Hours at Each Wind Speed and Direction Total Period Period of Record = 1/1/2008 00:00 -12/31/2008 23:00 Elevation:

Speed: SP150P Direction:

DI150P 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 N 38 29 7 0 0 0 74 NNE 57 32 4 0 0 0 93 NE 76 77 3 0 0 0 156 ENE 61 141 40 1 0 0 243 E 46 51 18 0 0 0 115.ESE 19 29 12 0 0 0 60 SE 27 30 5 0 0 0 62 SSE 26 35 12 0 0 0 73 S 34 69 70 12 0 0 185 SSW 52 99 76 9 3 0 239 SW 71 75 71 9 2 0 228 WSW 47 58 39 11 3 0 158 I W 28 65 39 42 7 2 183 WNW 18 94 45 4 0 0 161 NW 17 43 5 0 0 0 65 i NNW 27 43 4 0. 0 0 74 Total 644 970 450 88 15 2 2169 Calm Hours not Included above for: Total Period 3 Variable Direction Hours for: Total Period 0.Invalid Hours for: Total Period 45 Valid Hours for this Stability Class for: Total Period 2169 I Total Hours for Period 8784 I I I I I RTL A9.690E Enclosure 2, Attachment I (Part 2 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2008 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 =Elevation:

Speed: Stability Class F SP150P 1/1/2008 00:00 -, 12/31/2008 23:00 Direction:

DI150P Lapse: DT150-35 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 Total' 1-4 77 114 112 56 26.12 12 14 28 57 ,86 , 48 ,23'12* 18 28 723 4 -8 13 18 55 54 17 13 4 12.21 43 49 26 15 17 5 5.367 8 -13 0 1 0 10 0 1 1 3 4 7 10 1 1 1 1 1 42 13-19 19-25 >_25*0 0' 0 0 0 .0 0 0 0 0 0 0 0 0 10 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 4 2, 0 0 0 0 0 0 0 0 0 0 5 * .2 0 Total Period Total Period Total Period Total Period'Total*90 i33 167 120 43 26 17 29 53 107 146'75 45 30 24 34 1139 3 0 45 1139 8784 Calm Hours not Included above for: Variable DirectionHours for: Invalid Hours for: Valid Hours for this Stability Class for: Total Hours for Period RTL A9.690E Enclosure 2, Attachment I (Part 2 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2008 Attachment 1 Part 2: Joint Frequency Distribution Tables (150ft), Page 7 of 8 Hours at Each Wind Speed and Direction Total Period Period of Record =Elevation:

Speed: Stability Class G SP150P 1/1/2008 00:00 -12/31/2008 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 32 93 77 25 18 13 10 6 11 39 52 18 11 12 15 7 4-8 3 38 39 39 11 9 4 12 26 40 17 9 3 2 4 1 8- 13 0 0 1 2 0 0 0 0 2 5 1 1 1 0 0 0 13 -19 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 19-25 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 35 131 117 66 29 22 14 18 39 84 70 28 15 14 19 8 I I I I I I U I I I I I I I I I I I I Total 439 257 Caln Hours not Included above for: Variable Direction Hours for: Invalid Hours for: Valid Hours for this Stability Class for: Total Hours for Period 13 0 ,0 0 709 Total Period 3 Total Period,- 0 Total Period 45 Total Period 709 8784 RTL A9.69013 Enclosure 2, Attachment 1 (Part 2 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2008 Attachment 1 Part 2: Joint Frequency Distribution Tables (iS0ft)Page 8 of 8 Hours at Each Wind Speed and Direction Summary of All Stability Classes Period of Record =Elevation:

Speed: SPI50P Total Period 1/1/2008 00:00 -12/31/2008 23:00 Direction:

D1150P 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 4-8 8-13 192. 188 78 305 198 52 310 246. 19 167 391 130 110 .175 52 58 102 48 71 94 46 56 97 41 86 169 157 158 237 187 246 251 267 163 225 279 123 288 462 85 301 290 93 194 102 98 183 70 13-19 19-25 0 0 3 0 1 0 7 0 1 0 4 0 5 .0 2 0 17 0 29 5 63 5 88 22 312 75 121 8 10 0 2 0> 25 0 0 0 0 0 0 0 0 0 0 1 3 0 0 Total 458 558 576, 695 338 212 216 196 429 616 833 780 1271 806 399 353 Total 2321 3339 2280 665 115 16 8736 Caln 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 45 8736 8784 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 -2008 Attachment 1 Part 3: Joint Frequency Distribution Tables (500ft)Page 1 of 8 Hours at Each Wind Speed and Direction 3 Total Period Period of Record = 1/1/2008 00:00 -12/31/2008 23:00 Elevation:

Speed: SP500P Direction:

DI500P Lapse: DT500-35 Stability Class A Delta Temperature Extremely Unstable Wind Speed (mph) 3 Wind Direction 1-4 4-8 8-13 13-19 19-25 > 25 Total N 0 1 5 0 0 0 6 NNE 0 1 3 0 0 0 4 I NE 0 1 3 0 0 0 4 ENE 0 2 2 0 0 0 4 E 0 0 3 0 0 0 3 ESE 0 0 7 0 0 0 7 SE 0 1 5 7 0 0 13 SSE 0 0 2 1 0 0 3 I S 0 0 6 0 0 0 6 SSW 0 1 1 0 0 0 2 SW 0 2 1 0 0 0 3 WSW 0 0 1 0 0 0 1 W 0 3 3 2 1 0 9 WNW 0 5 4 3 3 0 15 NW 0 1 1 0 1 0 3 3 NNW 0 0 2 0 0 0 2 Total 0 18 49 13 5 0 85 Calm Hours not Included above for: Total Period 4 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 522 Valid Hours for this Stability Class for: Total Period 85 I Total Hours for Period 8784 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 -2008 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 1/1/2008 00:00 -12/31/2008 23:00 Elevation:

Speed: SP500P Direction:

DI500P 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 2 8 0 0 0 10 NNE 0 1 3 0 0 0 4 NE 0 1 2 0 0 0 3 ENE 0 1 3 2 0 0 6 E 0 1 4 0 0 0 5 ESE 0 0 5 3 0 0 8 SE 0 0 7 2 1 0 10 SSE 0 0 1 2 0 0 3 S 0 0 1 0 0 0 1 SSW 0 0 1 3 0 0 4 SW 0 0 4 3 0 '0 7 WSW 0 0 3 2 0 0 5 W 1 2 10 1 2 0 16 WNW 0 2 9 8 5 1 25 NW 0 2 6 2 0 0 10 NNW 0 2 5 1 0 0 8 Total 1 14 72 '29 8 1 125 Calm Hours not Included above for: Total Period 4 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 522 Valid Hours for this Stability Class for: Total Period 125 Total Hours for Period 8784 RTL A9.690E Enclosure 2, Attachment 1 (Part 3 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2008 Attachment 1 Part 3: Joint Frequency Distribution Tables (500ft)Page 3 of 8 Hours at Each Wind Speed and Direction Total Period Period of Record =Elevation:

Speed: 'SP500P Stability Class C 1/1/2008 00:00 -12/31/2008 23:00 Direction:

DI500P Lapse: Delta Temperature Slightly Unstable Wind Speed (mph)DT500-35 Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW 1-4 4-8 8-13 13-19 19-25 >25 Total 0 0 1 0 0 0 0 0 0 0 0 0 1 2 0 0 3 2 1 6 2 5 1 1 0 1 4 2 11 8 3 1 13 5 1 5 4 4 6 2 0 9 9 13 17 14 7 4 3 1 0 1 2 2 2 0 3 2 6 9 5 7 2 1 0 0 0 0 0 0 1 0 0 2 1 5 3 7 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 0 0 0 19 8 3 12 8 11 10 3 3 14 20 29 39 38 12 6 I I I I I I I I I I I U I I I I I I I Total 4 51 113 46 19 2 235 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 4 0 522 235 8784 RTL A9.690E Enclosure 2, Attachment 1 (Part 3 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2008 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 = 1/1/2008 00:00 -12/31/2008 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 14 82 152 33 0 0 281.NNE 17 53 26 22 1 0 119 NE 17 42 19 11 1 0 90 ENE 15 46 54 35 3 0 153 E 14 71 105 18 1 0 209 ESE 15 81 85 33 4 0 218 SE 6 43 68 22 2 0 141 SSE 7 19 55 21 1 0 103 S 5 22 67 55 13 4 166 SSW 11 26 76 117. 31 7 268 SW 10 34 146 216 53 6 465 WSW 14 52 133 196 52 38 485.W 19 67 220 343 203 62 914 WNW 10 48 205 216 ..61 23 563'NW 9 32 140 75 7 0 263 NNW 11 47 151 ..25. 1 0 235 Total 194 765 1702 1438 434 140 4673 Calm Hours not Included above for: Total Period 4 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 522 Valid Hours for this Stability Class for: Total Period 4673-Total Hours for Period 8784 RTL A9.690E Enclosure 2, Attachment 1 (Part 3 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2008 Attachment 1 Part 3: Joint Frequency Distribution Tables (500ft)Page 5 of 8 Hours at Each Wind Speed and Direction Total Period Period of Record =Elevation:

Speed: Stability Class E 1/1/2008 00:00 -12/31/2008 23:00.SP500P Direction:

DI500P Lapse: DT500-35 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 15 13 24 13 23 33 29 16 21 11 29 39 44 24 24 14 16 19 25 32 40 39 30 24 26 12 30 58 79 48 19 22 29 18 16 47 56 40 44 39 50 58 53 36 91 44 26 17 14 8 2 6 10 10 25 15 68 86 112 21 36 9 6 8 1 0 0 1 0 2 7 8 25 33 33 5 8 0 0 0 0 0 0 0 0 0 1 1 3 6 3 1 7 2 0 0 75 58 67 99 129 124 136 103 193 206 260 160 265 127 75 61 I I I I I I I I I I I I I I U I I I I 372 519 664 436 123 24 2138 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 4 0 522 2138 8784 RTL A9.690E Enclosure 2, Attachment 1 (Part 3 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2008 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: Stability Class F Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW, W WNW NW NNW SP500P, 1-4 10 8 18 13 13 19 18 19 16 15 21 20 18 16 12 6 Total Period 1/1/2008 00:00 12/31/2008 23:00 Direction:

DI500P Lapse: DT500-35 Delta Temperature Moderately Stable Wind Speed (mph)4-8 4 9 18 49 44 40 31 29 20 20 21 37 23 26 7 3 8- 13 6 2 2 24 20 12 11 11 42 24 20 10 17 7'4 1 13 -19 2 0 0 3 0 0 5 6 20 21 23 2 2 1 1 0 19 -25 0 0 0.0 0 0 0 0 0 1 4 0 0 0 0 0> 25 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0'0 Total 22 19 38 89 77 71 65 65 98 81 90 69 60 50 24 10 Total.242 381 .213 86 5 1 928 Calm Hours not Included abovetfor:.

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 4 0 522 928 8784 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 -2008 Attachment 1 Part 3: Joint Frequency Distribution Tables (500ft)Page 7 of 8 I Hours at Each Wind Speed and Direction Total Period Period of Record = 1/1/2008 00:00 -12/31/2008 23:00 Elevation:

Speed: SP500P Direction:

ý DI500P Lapse: DT500-35 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 I NE 1 0 0 0 0 0 1 ENE 0 0 0 0 0 0 0 E 1 4 0 0 0 0 5 I ESE 2 3 1 0 0 0 6 SE 1 6 1 0 0 0 8 SSE 3 2 0 1 0 0 6 I S 4 7 5 2 0 0 18 SSW 3 4 5 6 0 0 18 SW 3 0 1 0 0 0 4 WSW 2 1 0 0 0 0 3I W 2 1 0 0 0 0 3 WNW 1 1 0 0 0 0 2 NW 0 0 0 0 0 0 0.NNW 0 0 0 0 0 0 0 Total 23 29 13 9 0 0 74 Calm Hours not Included above for: Total Period .1 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 522 Valid Hours for this Stability Class for: Total Period 74 Total Hours for Period 8784 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 -2008 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 = 1/1/2008 00:00 -12/31/2008 23:00 Elevation:

Speed: SP500P Direction:

DI500P Lapse: DT500-35 Delta Temperature Wind Speed (mph)Wind Direction 1-4 4-8 8-13 13-19 19-25 >25 Total N 39 108 213 52 1 0 413 NNE 38 85 57 31 1 0 212 NE 61 88 43 13 1 0 206 ENE 41 136 135 47 4 0 363 E 51 162 192 30 1 0 436 ESE 69 168 154 48 6 0 445 SE 54 112 142 63 11 1 383 SSE 45 75 110 46 9 1 286 S 46 75 171 148 38 7 485 SSW 40 64 174 235 67 13 593 SW 63 91 234 360 91 10 849 WSW 75 150 196 230 62 39 752 W 85 186 358 389 217 71 1306 WNW 53 138 283 244 76 26 820 NW 45 64 184 86 8 0 387 NNW 31 75 180 35 1 0 322 Total 836 1777 2826 2057 594 168 8258 Calm Hours not Included above for: Total Period 4 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 522 Valid Hours for this Stability Class for: Total Period 8258 Total Hours for Period 8784 RTL A9.690E Enclosure 3 Beaver Valley Power Station -Units 1 & 2 2008 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 2008 Annual Radiological Environmental Operating Rep ort Enclosure 3 SECTION 1 -INTRODUCTION A. Radiation Fundamentals 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'. Ali~matter consists of atoms, which are comprised of positively charged particles (protons), negatively charged particles (electrons), and non-chargedlneutral 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 The following provides an alphabetical glossary of terms associated with radiation, radioactivity, and the radioactive decay process. The termis discussed include Alpha Particles, Beta Particles, Gamma Rays, Genetic Effects, Half-life, Ionization, Isotopes, Neutrons, Radiation, Radioactive 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-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.

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 measurable charge or mass, and generally travel much farther than alpha or beta particles before being absorbed.

After repeated interactions, the gamma ray loses its energy and vanishes.

The range: of a gamma ray in air varies, depending on the ray's energy and interactions.

Very high-energy gamma radiation can travel a considerable distance, where-as, 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.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 terms 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, where as, radionuclides that have more frequent emissions have a short half-life.

1-1I Beaver Valley Power Station RTh A9.690E 2008 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.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 sameI 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 aI 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 as3 Iodine- 13 1, 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 envirounmental 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 beI 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 neu 'tron 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 easilyI Radiation:

This is the conveyance of energy through space. For instance, heat emanating from a stove is a form of radiation, as are light rays, microwaves, and radio waves. Ionizing radiation isI 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 2U 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.1-2I Beaver Valley Power Station 2008 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, andproduce 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 Thoriumn-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 portionof 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 E234+u 2.5E+5 Yr ZU4 [Pa*~' I 1.2 min 234Th 24 d 230Th 8.OE+4 Yr 2 2 6 Ra 1600 Yr 3.82 d Beta'Decay Alpha Decay 218p0'3.05 min 2 14 P% 1.6E-4 s 210~ 138.4 d 4 214~ 2 1 0 B I'19.7min Jj _5. 01 d 2 1 4 Pb 26.8 min 2 1 0 Pb 23 Yr 2068P Ptab 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 I 2008 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 I 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 I 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 I is usually given in rad/hr. 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 1I 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) I 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.1 1-4 1 Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 1 -INTRODUCTION 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 Monitoring Program (REMP) conducted by the FirstEnergy Nuclear Operating Company during the report period.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, 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 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 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 the Wheeling Dam ranged from 8,800 cubic feet per second (minimum monthly average) to 107,400 cubic feet per second (maximum monthly average).

The mean flow during the report period was 45,342 cubic feet per second.Water temperature of the Ohio River typically varies from 340 Fahrenheit to 75' 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 39.248 inches The average mean temperature during the report period was 50.90 Fahrenheit 1-5 Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report RTL A9.690E 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 2900 -megawatts thermal Beaver Valley Unit 2 2900 -megawatts thermal Licensed Power Level Type of Power No. of Reactor Coolant Loops No. of Steam Generators

& Type Steam Used by Main Turbine PWR PWR 3 3 3 -Vertical Saturated 3 -Vertical.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 tobegin another steam/water cycle.I I I I I I U I I I I I I I I I I I I 1-6 Beaver Valley Power Station 2008 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 0 20 40 MILES 1-7 Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM A. Environmental Radioactivity 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 summarized 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 through 2-I of this report.2-B -Air Monitoring 2-C -Monitoring of Sediment and Soil 2-D -Monitoring of Feedstuff and Foodcrops 2-E -Monitoring of Local Cow and Goat Milk 2-F -Environmental Radiation Monitorina 2-G -Monitoring of Fish 2-H- -Monitoring of Surface Water, Drinking Water, Groundwater and Precipitation 2-1 -Estimates of Radiation Dose to Man 2-1 Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Table 2-1 RTL A9.690E Enclosure 3 ODerational 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 Particulate

& 27 Aliquippa, PA (Brunton Farm) Sampling with Particulate (b)Radionuclide 28 Sherman Farm Sample 29B Beaver, Pa (Friendship Ridge) ' Collection at least Weekly -Charcoal Iodine-1 31 30 Shippingport, PA (Cook's Ferry Substation) weekly 32 Midland, PA (North Substation)

Quarterly Composite Gamma Scan 46.1 Industry, PA (McKeel's Service -Rt. 68) (c)47 East Liverpool, OH (Water Department) 48 (a) Weirton, WV (Water Tower -Collier Way)S 51 Aliquippa, PA (Sheffield Substation) 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 90 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)Milicreek 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 (i)Gamma Dose I I I i I I I I I I i I I I I I I 2-2 Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Table 2-1 RTL A9.690E I Enclosure 3 perational Radiological Environmental Monitoring Program -Sample Sample Sample Preparation

/ Al Section Type Site Sample Location Sample Frequency Analysis Frequency Alysis No.49a Weekly Grab 3 Surface 4a Industry, PA (Upstream of Montgomery Sample (h) Weekly Sample from Water (a) Dam) Site49 only Iodine-131 Weekly Intermittent Composite Sample Monthly Composite of 2.1 Midland, PA (ATI Allegheny.

Ludam) (h) Weekly Sample (c)Gamma Scan Daily Grab Sample 5 East Liverpool, OH (Water Department)

Collected Weekly Quarterly Composite (c)(h) -. Tritium (H-3)11 (a) Shippingport, PA (Upstream)

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

Semi-Annual Semi-Annual Ttim (H-3)15bb 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-131 Sample Collected Monthly Composite (d) Gamma Scan Weekly .Quarterly Composite (d) Tritium (H-3)2A BVPS Outfall.Vicinity 6 Shoreline 49a Industry, PA (Upstream of Montgomery Semi-Annual Semi-Annual Gamma Scan Sediment (a) Dam)so .New Cumberland, W.V (Upstream of Dam)7 Milk Weekly (e) Weekly Samples from Weekly 25 Hookstown, PA (Searight Farm) Searight only Iodine-1 31 from Searight"___ only 27a (k) Aliquippa, PA (Brunton Farm)69 (k) Aliquippa, PA (Collins Farm) Biweekly (f) When All other samples & .Gamma Scan 96 (a) Burgettstown, PA (Windsheimer Farm) animals are on analyses are Biweekly Iodine-1 31 113(k) Hookstown, PA (Halstead Farm) pasture; monthly at during grazing, but Strontium-89 other times Monthly during other Strontium-90

.114 (k) Hookstown, PA (Moore Farm.) .,times 8 " 2A BVPS Outfall Vicinity ' Gamma Scan 8 Fish Industry, PA (Upstream of Montgomery Semi-Annual

.Composite of edible on edible 49a Dam) _ parts by species (g) parts 10a Shippingporl, 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 (a) Weirton WV (Water Tower -Collier Way)51a Aliquippa, PA (Sheffield Substation)

Shippingport, PA (Cook's Ferry Weekly grab Substation) samples when Quarterly Composite (c) Gamma Scan 47 East Liverpool, OH (Water Department) available Tritium (H-3)48 (a) Weirton WV (Water Tower-Collier Way)2-3 Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Table 2-1 Operational Radiological Environmental Monitoring Program 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .(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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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 obtainedby 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.U I I I I I I I I I I I I I I I I I I 2-4 Beaver Valley Power Station, RTL A9.690E 2008 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

RTL A9.690E Enclosure 3 I 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 -2008 Medium: Air Particulate and Radioiodine Unit of Measurement: (pico Curies / cubic meter)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) (bý Name Mean (fraction)

N Reported Performed LLD (') Range Nb) Distance and Direction Range (b Distance and Direction Range (b) Measurements W Gross Beta < 0.004 0.025 ( 459 / 459 No. 47 East Liverpool, OH 0.026 ( 51 / 51 ) No. 48 Weirton, WV 0.025 ( 51 / 51 ) 0 510 0.011 -0.051 Water Department 0.013 -0.045 Water Tower 0.014 -0.048 4.88 miles WNW Collier Way 16.40 miles SSW 1-131 <0.04 LLD ( 0 /459 LLD( 0 /459) LLD ( 0 /51 0 510 Gamma 40 Be-7 NA 0.081 ( 36 I 36 ) No. 32 North Substation 0.085 ( 4 / 4 ) No. 48 Weirton, WV 0.081 ( 4 /4 NA 0.550 -0.101 Midland 0.068 -0.100 Water Tower 0.067 -0.098 0.75 Miles NW Collier Way 16.40 miles SSW Co-60 <0.0003 LLD( 0 /36 ) LLD( 0 /36 ) LLD( 0 /4 0 Cs-134 < 0.0004 LLD( 0 /36 ) LLD( 0 /36 ) LLD( 0 /4 0 Cs-137 < 0.0004 LLD ( 0 /36 ) LLD ( 0 /36 ) LLD ( 0 /4 0 Ba-La-140

< 0.0005 LLD( 0 /36 ) LLD( 0 /36 ) LLD( 0 /4 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) 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)I I I I I I I I I I I I I I 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 -2008 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) 4b) Name Mean (fraction) (b) Name Mean (fraction) (b) Reported Performed LLD (') Range tb) Distance and Direction Range ýb) Distance and Direction Range (b) Measurements 1-131 <0.5 0.650 ( 58 / 104 ) No. 5 East Liverpool, OH 0.700 ( 33 / 52 ) No. 49 Industry, PA 0.900 ( 42 / 52 ) 0 156 0.300 -2.000 Water Department 0.300 2.000 Upstream of 0.200 -2.600 4.90 miles WNW Montgomery Dam 4.92 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 / ) 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

< 15 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)

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 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 -2008 Medium: Surface Water Unit of Measurement: (pico Curies / liter)RTL A9.690E Enclosure 3 I I 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) (b) Reported Performed LLD (') Range (b) Distance and Direction Range N Distance and Direction Range M Measurements (a)1-131 <0.5 No. 49 Industry, PA 0.900 ( 42 / 52 0 52 Upstream of 0.200 -2.600 Montgomery Dam 4.92 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-Nlb-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

< 15 LLD( .0 /24 ) LLD( 0/24 ) LLD( 0 / 12) 0 a 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)I I I 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

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 -2008 Medium: Ground Water Unit of Measurement: (pico Cunies 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) (b) Name Mean (fraction) (b) Reported Performed LLD (') Range N Distance and Direction Range (b) Distance and Direction Range N Measurements H-3 < 200 LLD( 0 /4 LLD( 0 /4 ) No. ll Shippingport, PA LLD( 0 /2 0 6 Upstream 0.94 miles NE Gamma No. 11 Shippingport, PA.6 Upstream 0.94 miles NE 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 < 10 LLD 0 /4 ) LLD (0/4 ) LID (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

< 15 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)

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 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 Countvy Pennsylvania Reporting Period: Calendar Year -2008 Medium: Precipitation Water Unit of Measurement: (pico Curies / liter)RTL A9.690E Enclosure 3 I I I I I Type and Lower Number of Total Number Limit of All Indicator Location., Locations with Highest Annual Mean Control Location Nonroutine of Anilysis 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 N') Measurements H-3 < 200 486 ( 2 /8 ) No. 47 East Liverpool, OH 790 ( 1 /4 ) No. 48Weirton, WV LLD ( 0 /4 ) 0 12 182 -790 Water Department 790 -790 Water Tower 4.88 miles WNW Collier Way 16.40( 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 / ) 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

<15 LLD( 0 / 8 ) LLD( 0 /8 ) LLD( 0 /4) 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)

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 2-10 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 Countv. Pennsylvania Reporting Period: Calendar Year -2008 Medium: Milk Unit of Measurement: (pico Curies / liter)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)

Name Mean (fraction) (b) Reported Performed LLD Range Distance and Direction Range Distance and Direction Range Measurements 1-131 <0.5 LLD( 0 /104) LLD( 0 /104) No. 96Burgettstown, PA LLD( 0/20 ) 0 124 Windsheimer Farm_ 10.48 miles SSW Sr-89 < 2.0 LLD ( 0 /72 ) LLD( 0/72 ) No.96Burgeustown,PA LLD ( .0 /20 ) n 0 92 Windsheimer Farm 10.48 miles SSW Sr-90 < 0.7 1.379 ( 66 / 72 ) No. 25 Hookstown, PA 1.845 (. 20 / 20 ) No. 96 Burgettstown, PA 0.995 ( 19 / 20 ) 0 92 0.600 -2.6 Searight Farm 1.300 -2.500 Windsheimer Farm 0.600 -1.900 2.10 miles SSW 10.48 miles SSW Gamma 92 K-40 <NA 1416 ( 72/ 72 ) No. 69 Alliquippa, PA 1630 ( 12 / 12 ) No. 96 Burgettstown, PA 1361 (20/ 20') NA 1067- 1746 Collings Farm 1489 -1746 Windsheimer Farm 1300 -1507 3.55 miles SE 10.48 miles SSW Mn-54 < 5 LLD( 0 / 72 ) LLD( 0/72 ) LLD( 0 /20) 0 Fe-59 < 10 LLD( 0 / 72) LLD( 0 /72 LLD( 0 /20) 0 Co-58 < 5 LLD( 0 /72) LLD (0/72 LLD (0 /20) 0 Co-60 < 5 LLD( 0 /72) LLD( 0/72) LLD( 0 /20) 0 Zn-65 < 10 LLD( 0 /72 ) LLD 0 /72 ) LLD( 0 /20) 0 Zr-Nb-95 < 5 LD( 0 /72) LLD( 0 /72) LLD( 0 /20) 0 Cs-134 <5 LLD( 0 /72) LLD( 0 /72) LLD (0/20) 0 Cs-,137 < 5 LLD( 0 /72 ) LLD( 0 /72 ) LLD( 0/20) 0 Ba-La-140

< 15 LLD( 0 /72 ) LLD( 0 /72 ) LLD( 0/20) 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)

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 RTL A9.690E Enclosure 3.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 -2008 Medium: Fish Unit of Measurement: (pico Curies / gram) Wet Type and Lower Number of Total Number Limit of Atl 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 (b) Distance and Direction Range (b) Measurements W Gamma 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 < 0.03 LLD( 0 / ) LLD( 0/ LLD( 0/ ) 0 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

< 0.07 LLD( 0 / ) LLD (-.0/ LLD( 0 / ) 0 Nominal Lower Limit of Detection I I I I I I I I'I I I I I I I I I I I 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)2-12 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 -2008 Medium: Foodcrops Unit of Measurement: (pico Curies / gram) Wet RTL A9.690E Enclosure 3 Type and Lower Number of Total Number Limit of Al Indicator Location Locations with Highest Annual Mean Control Location Nonroutine (b)NaeMa(fato)

Rpre of Analysis Detection Mean (fraction)

Name Mean (fraction) (b) Name Mean (fraction) (b) Reported Performed LLD (') Range (b) Distance and Direction Range (b) Distance and Direction Range N Measurements (c)1-131 <0.06 LLD( 0 /4 LLD( 0/4 ) LLD( 0/1 ) 0 5 Gamma 5 K-40 NA 2.160 ( 4/ 4 No. 15 Georgetown, PA 2.300 ( 1 / 1 ) No. 48a Weirton, WV 2.130 ( 1 / I NA 1.970 -2.300 321 Third Street 2.300 -2.300 Weirton Area 2.130 -2.130 3.7 miles WSW 16.54 miles SSW Mn-54 < 0.05 LLD( 0 /4 LLD( 0 /4 ) LLD( 0 /1 0 Fe-59 < 0.10 LLD( 0 /4 LLD( 0 /4 ) LLD( 0 /1 0 Co-58 < 0.05 LLD( 0 / 4 ) LLD( 0 /4 ) LLD( 0/ 1 0 Co-60 < 0.05 LLD( 0 / 4 LLD( 0/4 ) LLD( 0/1 0 Zn-65 <0.10 LLD( 0 /4 ) LLD (0/4 ) LLD ( 0/1 0 Zr-Nb-95 <0.03 LLD( 0 /4 ) LLD( 0 /4 ) LLD( 0 /1 0 Cs-134 < 0.05 LLD( 0 / 4 LLD( 0 /4 ) LLD( 0/1 0 Cs-137 < 0.05 LLD( 0 /4 ) LLD( 0 /4 ) LLD( 0/1 0 Ba-La-140

< 0.07 LLD( 0 / 4 LLD( 0 /4 ) LLD( 0/1 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)

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

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 -2008 Medium: Feedstuff Unit of Measurement: (pico Curies / gram) Wet 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)

ýb) Name Mean (fraction)

(ý). Reported Performed LLD (") Range N Distance and Direction Range (M) Distance and Direction Range M Measurements Gamma 12 Be-7 < NA 1.190( 5/ 12 ) No. 25 Searight Farm 1.190 ( 5/12 ) No. 25 Searight Farm 1.190 ( 5/12 ) NA 0.320 -2.550 948 McCleary Road 0.320 -2.550 948 McCleary Road 0.320 -2.550 Hookstown, PA Hookstown, PA 2.10 miles SSW 2.10 miles SSW K-40 <NA 11.04( 12/ 12 ) No. 25 SearighlFarm 11.04( 12/12 ) No. 25 Searight Farm 11.04 ( 12/12 NA 7.38 -15.05 948 McCleary Road 7.38 -15.05 948 McCleary Road 7.38 -15.05 Hookstown, PA Hookstown, PA 2.10 miles SSW 2.10 miles SSW Mn-54 < 0.05 LLD( 0 / 12 ) LLD( 0 /12 ) LLD( 0 /12) 0 Fe-59 < 0.10 LLD( 0 / 12.) LLD( 0 /12 ) LLD( 0 /12) 0 Co-58 < 0.05 LLD( 0 / 12 ) LLD( 0 /12 ) LLD 0/12) 0 Co-60 < 0.05 LLD( 0 / 12 ) LLD( 0 /12 ) LLD( 0 /12') 0 Zn-65 < 0.10 LLD( 0 / 12 ) LLD( 0 /12 ) LLD( 0 /12) 0 Zr-Nb-95 <0.03 LLD( 0 / 12 ) LLD( 0 /12 ) LLD( 0/12) 0 Ru-103 < 0.04 LLD ( 0 / 12 ) LLD ('0 /12 ) LLD 0 /12)1-131 < 0.06 LLD( 0 / 12 ) LLD( 0 /12 ) LLD( 0/12) 0 Cs-134 < 0.05 LLD( 0 / 12 ) LLD( 0 /12 ) LLD( 0 /12) 0 Cs-137 < 0.05 LLD( 0 / 12 ) LLD( 0 / 12 ) LLD( 0 /12) 0 Ba-La-140

< 0.07 LLD( 0 / 12 ) LLD( 0 / 12 ) LLD( 0 /12) 0 Nominal Lower Limit of Detection I I I I I I I I 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)2-14 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 1 and Unit 2 Docket No.: 50-334 / 50-412 Location of Facility:

Beaver County, Pennsylvania Reporting Period: Calendar Year -2008 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 with Highest Annual Mean Control Location Nonroutine of Analysis Detection Mean (fraction) (b) Name "" Mean (fraction) (b) Name fMean (fraction) (b) Reported Performed LLD t) Range (b) Distance and Direction Range (b) Distance and Direction lRange Nb) 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< 0.05< 0.10* 0.05< 0.05< 0.10< 0.03< 0.03< 0.05< 0.05< 0.07 NA 9.40( 4/ 4 7.29- 11.37)LLD( 0/4 )LLD( 0/4 )0.08( 2/4 )0.08.- 0.08 0.15( 2 /4 0.11 -0.19)LLD ( 0 /4 )No. 2A BVPS Outfall Vicinity 0.31 miles WSW No. 2A BVPS Outfall Vicinity 0.31 miles WSW No, 2A BVPS Outfall Vicinity 0.31 miles WSW No. 2A BVPS Outfall Vicinity 0.31 miles WSW No. 2A BVPS Outfall Vicinity 0.31 miles WSW 10.14( 2 / 2 8.90 -11.37)LID( 0/4 )LLD( 0/4 )0.08( 2/2 )0.08- 0.08 0.15,( 2/2 )0.11 -0.19 LLD( 0/4 )LLD( 0/4 )LLD( 0(4 )No. 49a Industry, PA Upstream of Montgomery Dam 4.93 miles NE No. 49a Industry, PA Upstream of Montgomery Dam 4.93 miles NrE No. 49a Industy, PA Upstream of Montgomery Dam 4.93 miles NE No. 49a Industry, PA Upstream of Montgomery Dam 4.93 miles NE No. 49a Industry, PA Upstream of Montgomery Dam 4.93 miles NE 9.48 ( 2/ 2 9.77 -9.91)LLD( 0/2 )LLD( 0/2 )LLD ( 0/2 )LLD( 0/2 )LLD LLD LLD 0/4 )0/4 0/4 LLD( 0/2 LLD( 0/2 LLD( 0/2 LLD ( 0/2 0.08( 2 /2 0.08, 0.08)))))NA 0 0 0 0 0 0 0 0 0 0 NA LLD( 0/4 0.10( 2/2 0.06- 0.13))0.10 ( 2 / 4.0.06- 0.13 LLD( 0 /4 0.31( 4/4 0.23 -0.39 LLD( 0/4 )0.34( 2 /2 0.29 -0.39 LLD( 0/2 )0.28( 2/2 )0.28- 0.28 L -A. .&. L .L 2-15 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 Vallev Power Station Unit 1 and Unit 2 Docket No.: 50-334 / 50-412 Location of Facility:

Beaver County. Pennsylvania Reporting Period: Calendar Year -2008 Medium: Sediment (page 2 of 2)Unit of Measurement: (pico Curies / gram) Dry 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) (b) Reported Performed LLD (") Range (b) Distance and Direction Range (b) Distance and Direction Range W .Measurements (L Bi-214 NA 0.78 ( 4 /4 ) No. 2A BVPS 0.83 ( 2 /2 No. 49a Industry, PA 0.72 ( /2 ) NA 0.58 -0.89 Outfall Vicinity 0.77 -0.89 Upstream of 0.69- 0.75 0.31 miles WSW Montgomery Dam 4.93 miles NE Pb-212 NA 1.17 ( 4 /4 ) No. 2A BVPS 1.28 ( 2 / 2 ) No. 49aIndustry, PA 1.02 ( 2/2 ) NA 0.94- 1.34 Outfall Vicinity 1.21- 1.34 Upstream of 0.89 -1.15 0.31 miles WSW Montgomery Dam 5 miles NE Pb-214 NA 0.81 ( 4 /4 ) No. 2ABVPS 0.87 ( 2 / 2 ) No. 49aIndustry, PA 0.79 ( .2/2 ) NA 0.59 -0.93 Outfall Vicinity 0.81 -0.93 Upstream of 0.74- 0.84 0.31 miles WSW Montgomery Dam 5 miles NE Ra-226 NA 1.67 ( 4 /4 ) No. 2ABVPS 1.92 2 /2 ) No. 49aIndustry, PA 1.67 ( 2/2 ) NA 1.09 -2.12 Outfall Vicinity 1.71 -2.12 Upstreamof 1:43 -1.91 0.31 miles WSW Montgomery Dam 5 miles NE Ac-228 NA 0.98 ( 4 /4 ) No. 2A BVPS 1.07 ( 2 /2 ) No. 49a Industry, PA 0.96 ( 2 /2 ) NA 0.75- 1.19 Outfall Vicinity 0.95- 1.19 Upstream of 0.90- 1.01 0.31 miles WSW Montgomery Dam 5 miles NE 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)

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)I I I I 1 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 -2008 Medium: Soil (page 1 of 2)Unit of Measurement: (pico Curies / gram) Dry Type antd 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)

Mo) Name Mein (fraction) (b) Reported Performed LLD (") Range (b) Distance and Direction Range (b) Distance and Direction Range (b) Measurements W Gamma Note: Soil Sampling performed ever three (3) years. Sampling was performed in 2006, and is next due in 2009.K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs- 134 Cs-137 2-17 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 -2008 Medium: Soil (page 2 of 2)Unit of Measurement: (pico Curies / gram) Dry Type and Lower Total Number Limit of All Indicator Location,, Locations with Highest Annual Mean Control Location of Analysis Detection Mean (fraction)(b)

Name Mean (fraction) (b) Name iMean (fr: Performed LLD (") Range (b) Distance and Direction fRange () Distance and Direction Range (b)Note: Soil Sampling performed every three (3) years. Sampling was performed in 2006, and is next due in 21 Ba-La-140 I .I I RTL A9.690E Enclosure 3 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)I I I I I 2-18 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 -2006 Medium: External Radiation Unit of Measurement: (mR / Quarter)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)

IbI 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 Gamma 4.6 18.4( 503/503 ) No. II2BVPSSite 23.0 ( 8/8 ) No. 48Weirton, WV 20.5( 8/8 ) 0 511 11.4 -26.0 Perimeter 20.0 -25.4 Water Tower 18.7 -24.0 Location Collier Way 16.40 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 2008 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 U I I I I I I I I I I I 2-20 Beaver Valley Power Station 2008 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) --...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 2008 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 U U I I I I I I I I I I I I I 2-22 Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM B. Air Monitoring

1. 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 stacking 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 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM i 3. Results and Conclusions A summary of data is presented in Table 2-2.a. AirborneRadioactive Particulates Gross Beta: A total of five-hundred-ten (510) weekly samples from ten (10) locations were analyzed for gross beta. Results were comparable to previous years. Figure 2-2 indicates the i weekly average concentration of gross beta in air particulates.

During the period 05/19/08 -05/27/08, the Gross Beta Results were unusually low.Specifically, the Gross Beta results for the ten (10) air particulate sample stations ranged from i 0.0 11 -0.014 pCi/cubic meter, where as the cumulative average ranged from 0.022 to 0.025 pCi/cubic meter. As noted, this condition existed at all nine (9) indicator locations and at the 3 one (1) control location.

This issue was discussed with the REMP Administrators at the other two FENOC sites (i.e.; Davis-Besse Nuclear Power Plant and the Perry Nuclear Power Plant), and they alsonoted similar decreases in Gross Beta results during this period. There is no consequence to unusually low sample results at the indicator and control locations.

The cause I is most likely due to cosmic phenomenon.

This issue is documented in SAP Order 200197646-0640.

I During the period 11/02/08 -11/10/08, the Gross Beta Results were unusually high.Specifically, the Gross Beta results for all ten (10) air particulate sample stations ranged from 0.034 -0.051 pCi/cubic meter, where as the cumulative average ranged from 0.024 to 0.026 I 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 two FENOC sites (i.e.; Davis-Besse Nuclear Power Plant and the Perry Nuclear Power Plant), I and they also noted similar increases in Gross Beta results during this period. There is no consequence to unusually high sample results at the indicator and control locations.

The cause is most likely due to cosmic phenomenon.

This issue is documented in SAP Order i 200197646-0640.

Gamma Spectrometry:

The weekly air particulate samples were composited into forty (40) 3 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 I the required airborne particulate sampling and analysis schedule during the report period.Specifically, during the sampling period of 02/25/08 -03/03/08, the Air Particulate and Iodine Sampling Station at the Shippingport, PA Cooks Ferry Substation (Site No. 30, 0.43 miles I ENE) was interrupted for 76 hours8.796296e-4 days 0.0211 hours 1.256614e-4 weeks 2.8918e-5 months due to an undeterminable power loss. During the sampling period of 03/24/08 -03/31/08, the Air Particulate and Iodine Sampling Station at East Liverpool, OH Water Department (Site No. 47, 4.88 miles WNW) was interrupted for 103 U hours due to shattered vanes in the sample pump. During the sampling periods of 06/02/08 -06/09/08, 06/16/08 -06/23/08, and 06/30/08 -07/05/08, the Air Particulate and Iodine Sampling Station at Hookstown, PA (Site No. 13, 1.49 miles SW) was interrupted for 23 I hours, 58 hours6.712963e-4 days 0.0161 hours 9.589947e-5 weeks 2.2069e-5 months and 45 hours5.208333e-4 days 0.0125 hours 7.440476e-5 weeks 1.71225e-5 months , respectively due to power losses from blown fuses. After each 2-24 i Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM of the power losses, the fuses were replaced and the sample pumps were successfully restarted.

The power loss condition was resolved on 07/07/08 by removing an extension cord not associated with BVPS-REMP air sampling equipment.

During the sampling period of 09/02/08 -09/08/08, the Air Particulate and Iodine Sampling Station at the Shippingport, PA Cooks Ferry Substation (Site No. 30, 0.43 miles ENE) was interrupted for 114 hours0.00132 days 0.0317 hours 1.884921e-4 weeks 4.3377e-5 months due to shattered vanes in the sample pump. All Air Particulate and Iodine Samples obtained for the sampling period of 09/02/08 -09/08/08 were discarded by the shipper, because they were damaged during shipment.

Although these are not missed samples (i.e., the samples were obtained), no sample analyses are available for this sample period. During the sampling periods 09/08/08 -09/15/08, and 09/15/08 -09/22/08, the nine (9) Air Particulate and Iodine Sampling Stations (Indicator Locations) were interrupted for various periods of time. The interruptions were all related to power outages caused by hurricane Ike thunderstorms that entered the area on 09/14/08.

During this period, sampling was interrupted for periods from 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . During the sampling period of 11/17/08 -11/24/08, the Air Particulate and Iodine Sampling Station at the Midland, PA North Substation (Site No. 32, 0.75 miles NW) was interrupted for 93 hours0.00108 days 0.0258 hours 1.537698e-4 weeks 3.53865e-5 months due to shattered vanes in the sample pump. 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.This condition is documented in SAP order 200197646-0490.

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-ten (510) 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 described above for airborne particulates.

Summary: Based on analytical results, the operation of BVPS did not contribute any measurable increase in airborne radioiodine during the report period.2-25 Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Figure 2-1 Environmental Monitoring Locations

-Air Sampling Stations I I I I I I U I I I I I I I I I U I I 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) 2-26 Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM 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=E"- Average of 9 Indicator Locations 3 0.16 A--- Control Location 0.14 ------------------------------

Pre-Operational value (0.07 p/ cubic meter)0.12 --,-,,,,,,,--

Required LLD (0.01 pCi / liter)E 0.10 -No- -"-- "--N Reporting Level for Gross Beta 0.06 o 0.08 U A 0.02 ..- --..-.-.-.-.-.-

0.00 NqNU 2-27 Beaver Valley Power Station RTL A9.690E 2008 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 I a. Program Shoreline stream sediment were collected semi-annually above the Montgomery Dam, in I 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 2006 and are not due to be collected again until 2009. 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 I Gamma Emitter 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 I I I I 2-28 I Beaver Valley Power Station RTL A9.690E 2008 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 2-4 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 two of four (2 of 4) indicator samples and two of two (2 of 2) control samples. The results were similar to previous years (current years range = 0.06 to 0.13 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 two of four (2 of 4) indicator samples and zero of two (0 of 2) control samples. The samples that indicated Cobalt-58 were obtained at the shore line of the main outfall facility.

The results were similar to previous years (current years range = 0.08 to 0.08 pico Curie / gram), and this data is currently less than the pre-operational level of 0.098 pico Curie / gram.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 = 0.11 to 0.19 pico Curie / gram), and this data is currently less than the pre-operational level of 0.4 pico Curie / gram 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 and Cobalt-60 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.2-29 Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 I I SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM b. Soil Although not required by the ODCM, soil is sampled every three years and was sampled in 2006. Soil sampling will be performed during calendar year 2009.I I I I I U I I I I I I I I I I I 2-30 Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Figure 2-3 RTL A9.690E Enclosure 3 Environmental Monitoring Locations

-Shoreline Sediments and Soil Sample Site Distance Type No. Sector (miles) Sample Point Description 13a 11-SW 1.49 Hookstown, PA (Old Meyer Farm)22 8-SSE 0.28 South of BVPS, Transmission Lines 27b 7-SE 6.19 Aliquippa, PA (Brunton Farm)29A 3-NE 8.09 Beaver, PA (Nicol Farm)Shippingport, PA (Cooks Ferry Soil 30a 4-ENE 0.43 Substation) 32a 15-NW 0.74 Midland, PA (North Substation) 46b 3-NE 2.66 Industry, PA (Willows Inn -Rt. 68)47a 14-WNW 4.89 East Liverpool, OH ( Water Department) 48 10-SSW 16.40 -Weirton, WV (Collier Way Water Tower)51a 5-E 7.99 Aliquippa, PA (Sheffield Substation) 2A 12-WSW 0.31 Shippingport, PA (BVPS Outfall Vicinity)Sediment 49a 3-NE 4.93 Industry, PA (Upstream Montgomery Dam)50 12-WSW 11.77 New Cumberland, WV (Upstream of Dam 2-31 Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM RTL A9.690E Enclosure 3 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 100.0 100.00 E E 0 0L 10.00 1.00---- Cs-137--- Control Location Cs-137 -......................... ..Cs-137 Pre-operational Results (0.4 pCVgm)Cs- 137 Required LLD (180 pCVgrm I No Reporting Level for Sedirrent---" ---... ---0.10 0.01 14AII ~ ~ \ 14A Nq~ 14e 141; N11. 14. b 4,11 101 11A l I I I I I I I I I I I I I I I I I I I Beaver Valley Power Station REMP Co-58 & Co-60 Sediment Trends -Outfall Vicinity 100.00-a-- Co-58-Unit 2 Pre-Operational Mean: Co-58 (0.098 pcVgm)A Co-60 Unit 2 Pre-Operational Mean: C0-60 (0.40 pCigram)No Required LLD for CD-58 or CD-60-No Reproting Linit for C0-58 or Co-60----------------------E e,-it 10.00 1.00'A I'Aj---~~ A AA Al A A II I ~e A A A/1 A 1 A A A ..L~- --A A! N *I A'~ I'~ ~A'~.1 \A~A (.C 0.011 2-32 Beaver Valley Power Station 2008 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) 1 1.2 _ _ .3 j ~-*---Cs-137 1.0 --------.

.------------------------------------

Control Location Pre-operational Cs-137 (1.2 p0I/gram)E 0.8 ---------------

--- ------ --------------------------------

N eotn eefrSi 0 0.2 0.00 2-33 Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM D. Monitoring of Feedstuff and Foodcrops RTL A9.690E Enclosure 3 1. Characterization of Farm Products According to the 2007 Census of Agriculture (1), 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 I (1) http://www.agcensus.usda.gov/Publcations/2007/Onine-Highlights/County-Prordes/Pennsylvania/index.asp 2-34 Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM 2. Sampling Program and Analytical Techniques

a. Program Feedstuff:

Although not required by the ODCM, representative samples of Feedstuff (cattle feed) are collected monthly from the nearest dairy farm (Searight Dairy). See 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 gamma spectrometry.

Samples are also analyzed by radiochemical analysis for Iodine-131.

b. Procedures 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 tare weight 300 or 150 ml plastic bottles or 1-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 carrier is added to a chopped sample, which is then leached with a sodium'hydroxide solution, evaporated to dryness and fused in amuffle furnace. The melt is 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 palladium iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchet for low level beta counting.2-35 Beaver Valley Power Station RTL A9.690E I 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM I 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. i a. Feedstuff Gamma Spectrometry:

Although not required by the ODCM, a total of twelve (12) i samples were analyzed by gamma spectrometry.

Naturally occurring Potassium-40 was identified in twelve of twelve (12 of 12) samples. Naturally occurring Beryllium-7 was found in five of twelve (5 of 12) samples.Deviations from Required Sampling and Analysis Schedule:

There were no deviations from the required feedstuff sampling and analysis schedule during the report period.Surmnary:

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.i i I I I 2-36 I Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Figure 2-6 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 1.02 Shippingport, PA Food 15a 14-WNW 3.55 Georgetown, PA 46a 3-NE 3.39 Industry, PA 48a 10 -SSW 16.54 Weirton, WV 2-37 Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Figure 2-7 Graph of Annual Average Concentration:

Cesium-137 in Feedstuff and Foodcrops 100.C.a-:2 0 C.)0 U 0'J 10 Beaver Valley Power Station REMP Cs-137 Feedstuff and Foodcrops Trends* -.- C- -s-137 (Feedstuff)

-- Cs-137 (Foodcrops)

Cs-137 Pre-operational Results--- -----s-137 Required LLD (80 pi/kg) Wet-----------------

-,No Reporting Level for Feed of Food-------------------------------------------. -.- .- ------------------------i 1 0.1 0.01 I q-"o 140.1ý1 q"ý e 140j, ()qb '4P e e e e e 2-38 Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM 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 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.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 (2.10 miles SSW) and the Brunton Dairy Farm (6.16 miles SE).Cow milk and goat milk were also collected from two (2) other dairy farms within a 10-mile radius of the BVPS site. The goat milk samples obtained at the Collins Dairy Farm (3.55 miles SE) and the cow milk samples obtainedat the Halstead Dairy Farm (5.08 miles SSW) were selected based on milch animal surveys and evaluations of meteorological data (i.e.; 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, 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 (10.48 miles SSW).The cow milk sample from the Searight Dairy Farm (2.10 miles SSW) is collected and analyzed weekly for Iodine-131 using a method that ensures a high sensitivity.

Samples from each ofthe 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.

During the 2008 Land Use Census, it was determined that a new heard of doe goats is located at the Sullivan Farm (4.285 miles ESE), and the Ferry Farm (3.32 miles SE) has again obtained a doe goat. No goat milk samples were available from either of these locations during 2008, because, the goats were already dry at time of the Land Use Census.However, both locations may provide goat milk samples during 2009.2-39 Beaver Valley Power Station 2008 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 38 Cows 2.10 miles SSW January thru 948 McCleary Road December Hookstown, PA 27a Brunton Dairy 108 Cows 6.16 miles SE January thru 3681 Ridge Road December Aliquippa, PA 69* Collins Dairy 1 Goats 3.55 miles SE March thru 289 Calhoun Road August Aliquippa, PA 96 Windsheimer Dairy 75 Cows 10.48 miles SSW January thru RD#11 December Burgettstown, PA Halstead Dairy 60 Cows 5.08 miles SSW, January thru 113* 104 Tellish Drive December Hookstown, PA Ferry Farm 1 Goat 3.32 miles SE Not Applicable:

102 227 Calhoun Rd No goat milk available Aliquippa, PA during 2008 Sullivan Farm 5 Goats 4.29 miles ESE Not Applicable:

115 198 Wilson Lane No goat milk available Aliquippa, PA during 2008 Highest potential pathway dairies based on evaluation of deposition parameters I U I I I I I I I I I I I I I I I U 2-40 I Beaver Valley Power Station RTL A9.690E 2008 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.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 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 planchetand 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' 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 the report period) is shown on Figure 2-9.a. Strontium-89:

Although not required by the ODCM, a total of ninety-two (92) milk samples were analyzed for Strontium-89 during the report period. Strontium-89 was not detected in any of the seventy-two (72) indicator samples, nor was it detected in any of the twenty (20) control samples.b. Strontium-90:

Although not required by the ODCM, a total of ninety-two (92) milk samples were analyzed for Strontium-90 during the report period. Strontium-90 was detected in sixty-six of seventy-two (66 of 72) indicator samples and nineteen of twenty (19 of 20) control samples. The levels detected were attributable to previous nuclear weapons tests and are within the normally expected range.c. Gamma Spectrometry:

A total of ninety-two (92) milk samples were analyzed by gamma spectrometry during the report period. Naturally occurring Potassium-40 was present in seventy-two of seventy-two (72 of 72) indicator samples and twenty of twenty (20 of 20)control samples. No other gamma-emitting radionuclides were identified during analysis.2-41 I Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM d. Iodine-13 1: A total of one hundred twenty-four (124) milk samples were analyzed for I Iodine-131 during the report period. Iodine-131 was not detected in any of the one hundred four (104) 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:

The Bi-weekly Doe Goat milk sampling at the only Doe Goat Location (Site No. 69, 3.547 miles SE), as identified in the Land Use Census, were interrupted during 2008. Specifically, the Doe Goats at this location ceased production of milk in September 2008. Although the Doe Goats could not be sampled during that period, the minimum Bi-weekly milk sampling requirements of ODCM procedure 1/2-ODC-3.03, Attachment Q, Table 3.12-1 were still met. Specifically, SINCE only 4 Bi-Weekly Dairy Cow and/or Doe Goat locations are required to be sampled, THEN the minimum requirement was met with 4 Dairy Cow milk samples.Also, two (2) of the four (4) Bi-weekly milk samples obtained on 09/08/08 were discarded by the shipper, because they were damaged during shipment.

Although the samples were obtained, no sample analyses for the Brunton Dairy (Site No. 27a, 6.16 miles SE) and the Windsheimer Dairy (Site No. 96, 10.48 miles SSW) were available for this Bi-weekly.

sample period. This condition is documented in SAP Order 200197646-0650.

f. Summary: Based on all the analytical results and the comparison to pre-operational levels, I 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.I I I I I I I I 2-42 Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM.Figure-2-8 RTL A9.690E Enclosure 3 Environmental Monitoring Locations

-Milk Site Distance Sample Type No. Sector (miles) Sample Point Description 25 10-SSW 2.10 Hookstown, PA (Searight Farm)27a 7-SE 6.16 Aliquippa, PA (Brunton Farm)Milk 69* 7-SE 3.55 Aliquippa, PA (Collins Farm)96 10-SSW 10.48 Burgettstown, PA (Windsheimer Farm)113* 10-SSW 5.08 Hookstown, PA (Halstead Farm)114* 11-SW 2.12 Hookstown, PA (Moore Farm)* Dairies selected based on evaluation of deposition parameters 2-43 Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM RTL A9.690E Enclosure 3 Figure 2-9 Graph of Annual Average Concentration:

Iodine-131

& Sr-90 in Milk Beaver Valley Power Station REM P 1-131 Concentrations in Milk 14.0I Chernobyl Accident 10.0 .. ..o.197 ss WeaponsTe-tin-g_

-_! _$ 8.0 -- -- Average at the Indicator Location ,. A-- -Control Location Pre-Operational value (0.6 pa /liter)S6.0-------

-- -- -- -- -- -- -- -- -- ---- -- -- -- -- --- -RequiredLLD (1 p0 /liter)0 Reporting Level (3 pCi / liter)" t 4.0 ... -- -----2.01 oe 1-11 le le 140 le 111 £44 Ae 141, lieAA*Beaver Valley Power Station REMP Sr-90 Concentrations in Milk 10 9--------------------------------

-- ---*.-- Avg. of Indicator Locations 8- --A- --Control Location Pre-Operational value (5.3 p0 / liter)7 C-, 4 -" --' --" ----- -- ---4Z 3 ' A. .A&t DA-------......----. ..--------4, , 2-44 Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM F. Environmental Radiation Monitoring I. Description of Regional Background Radiation and Sources Historical information for regional background was obtained from Reuter-Stokes instruments that were previously located within a five (5) mile radius of the BVPS site. Data is no longer available from these instruments, but historical data indicated that the background exposure rates ranged from 6 jtR/hr to 12 gR/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 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 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).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 locations.

The offsite TLD locations are plotted on Figurem2-10, 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 of analyses (including the pre-operational period through the report period) is shown on Figure 2-11.TLD Analysis:

During the report period, the average quarterly external exposure rate (as measured from TLD) was 18.4 mR at the sixty-four (64) indicator locations, and 20.5 mR at the Control location.

This external exposure rate is comparable to previous years. As expected, there was some variation in external exposure rate among locations and seasons.2-45 I Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Adjustments to TLD Placement:

In regards to operating experience at Clinton Power Station I (OE26003), BVPS TLD sites were evaluated during 2008 against criteria established in ANSI N545-1975 (Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry).

As a result of this evaluation, several of the TLD sites were lowered and/or relocated to adjacent/nearby sites. For TLD sites that were relocated; (1) no changes were necessary to the distances specified in this and previous reports, and (2) no changes were necessary to the distances specified in the Offsite Dose Calculation Manual. In summary, the I reported exposure results of all previous BVPS TLD data for the sixty-four (64) TLD sites are considered valid and do not require adjustment.

Results of the evaluation were documented in SAP Order 200197646-0610 and letter NPD3NRE:0538.

TLD Trend Evaluation:

As discussed inithe 2007 report, the trends of the environmental TLD data during the period 2001 thru 2007 showed a small increase for the indicator locations, and n 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 were no deviations from the required sampling schedule (i.e.; TLD change out frequency) and analysis schedule (i.e.; TLD processing frequency) during the report period.Summary: The quarterly TLD external exposure rates are comparable to those of previous years, except for the increase described above in the TLD Trend Evaluation.

There was no I 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 I 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.

I I I I U I 2-46 Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM RTL A9.690E Enclosure 3 Figure 2-10 Environmental Monitoring Locations

-TLDs 2-47 Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Figure 2-10 (Continued)

TLD Locations RTL A9.690E Enclosure 3 I I I SOUTHEAST QUADRANT Site Sector Distance Location Site Sector Distance Location No. (miles) No. (miles)27 7-SE 6.14 Brunton Dairy Farm 78 7-SE 2.72 Racoon Twsp Municipal Building Aliquippa, PA Raccoon Township, PA 45.1 6-ESE '1.92 Kennedy's Corners 79 8-SSE 4.46 106 State Route 151 Raccoon Township, PA Ted McWilliams Auto Body 51 5-E 8.00 Sheffield Substation 80 9-S 8.27 Park Office, State Route 18 Aliquippa, PA Raccoon Township, PA 59 6-ESE 0.99 236 Green Hill Road 82 9-S 6.99 2697 State Route 18 Aliquippa, PA Aliquippa, PA 76 6-ESE 3.80 Raccoon Elementary School 94 8-SSE 2.25 McCleary & Pole Cat Hollow Road SRaccoon Township, PA Hookstown, PA 77 6-ESE 5.52 3614 Green Garden Road Aliquippa, 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 _ Industy, PA 28 1-N 8.60 Sherman Farm 71 2-NNE 6.01 First Western Bank Beaver Falls, PA Brighton Township, PA 29B 3-NE 7.97 Friendship Ridge 72 3-NE 3.25 Ohioview Lutheran Church -Rear Beaver, PA Industry, 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 SOUTHWEST QUADRANT I I I I I I I I I I I I I I I Site No.Sector Distance (miles)Location Site No.Sector Distance (miles)Location 13 11-SW 1.49 Old Meyer Farm Hookstown, PA 14 11-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 84 11-SW 8.35 Senior Center Hancock County, WV 85 12- 5.73 2048 State Route 30 WSW 92 12- 2.81 Georgetown Road Substation WSW Georgetown, PA 95 10-SSW 2.37 832 McCleary Road Hookstown, PA 2-48 I Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Figure 2-11 Graph of Annual Average Exposure:

Direct Radiation in Environment Beaver Valley Power Station REMPI Environmental TLD Trends I 0.24 0.22 ] .. ..........-.0.20 A 4,-0. 18 0 .16 ------------------------E E E 0.14 0.12--s- Average of 63 Indicator Locations--- --- Control Location (Weirton WV)Pre-Operational Value (0.2 nriem / day)0.10 1 , , ., .I I 2-49 I Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM G. Monitoring of Fish 3 1. Description During the report period, fish collected for the radiological monitoring program included carp, channel catfish, quillback, red horse and smallmouth bass.2. Sampling Program and Analytical Techniques

a. Program 3 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 I sampling locations are shown in Figure 2-12.b. Procedure 3 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 I germanium detector.3. Results and Conclusions 3 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 nine (9) fish samples were analyzed by gamma spectrometry during the report period. Gamma emitting radionuclides were not detected in any of the four I (4) indicator samples, nor were they detected in any of the five (5) control samples.Deviations from Required Sampling and Analysis Schedule:

There were no deviations from the i 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 I I U 2-50 3 Beaver Valley Power Station 2008 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 Montgomery 49a 3-NE 4.93 Dam)2-51 Beaver Valley Power Station 2008 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 REMPI Cs-137 Concentrations

-Fish 10000.000 1000.000 S, 100.000.10.000 E oh 1.000 o 0.100 0 0.010 0.001-- -Cs-137-Control Location -MVontgormery Dam Unit 2 Preoperational (0.014 pa / gin)-Required LLD (150 pa / gm)-Reporting Level (2000 p0i/gm).e .-A .- --- --------..-'" --" ...-- ------ ----...-* ----- ---" ----.-.- -- .-----I146 14111 1* 1406" 1_0ý3 14P, 14* 1* 14c", 1441b 110, le 1ý4 2-52 Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM H. Monitoring of Surface Water, Drinking 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 diminishes considerably in the bedrock underlying the site. Normal well yields in the bedrock are less than 10 gallons per minute (gpm) 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 39.24 inches.2-53 I Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM 2. Sampling and Analytical Techniques I a. Surface (Raw River) Water i 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 41.2], and the made into a weekly composite sample. One automatic river water sampler is located at the ATI-Allegheny Ludlam (formerly J&L 3 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. I 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. i An automatic sampler at each location collects 20-40 il 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.

I The quarterly composites are analyzed for Tritium.Locations of each sample point are shown in Figure 2-14.2 2-54i Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM c. Groundwater 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 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.e. Procedures Gamma Analysis of Drinking Water and Surface Water: The analysis is performed on water samples by placing one liter of the sample into a Marinelli container and analyzing the sample on a high resolution germanium gamma 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 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.2-55 Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM 3. Results and Conclusions S 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 I analyses (including the pre-operational period through the report period) is shown on Figures 2-15 through 2-18. 5 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 I it detected in any of the four (4) control samples.Gamma Spectrometry:

A total of thirty-six (36) surface water samples were analyzed by I 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 S report period. Iodinel31 was detected in forty-two of fifty-two (42 of 52) weekly control samples, of which three (3) analysis exceeded the reporting level of 2 pico Curie / liter.The results were similar to previous years, (current years range = 0.2 to 2.6 pico Curie / I 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 I upstream facilities.

This issue is documented in SAP Order 200197646-0440.

b. Drinking Water 5 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 I detected in any of the twenty-four (24) indicator samples, nor were they detected in any of the twelve (12) control samples.Iodine- 131: 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-eight of one hundred four (58 of 104) indicator samples and forty-two of I fifty-two (42 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 Curie / liter. Also, I SINCE all of the liquid effluent discharges during the report period from BVPS did not have detectable Iodine-131, THEN the positive results were not influenced by BVPS operation, and were most likely due to medical diagnostic and treatment procedures from upstream facilities.

2-56 Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM'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 radionuclides were not detected in any of the four (4) indicator samples, nor were they detected in any of the two (2) control samples.d. Precipitation 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.Some of the positive results at the Cooks Ferry Substation in Shippingport, PA (current range = 182 pico Curie / liter, with an LLD of 133 pico Curie / liter) and the East Liverpool Water Department, in East Liverpool, OH (current range = 790 pico Curie / liter, with an LLD of 143 pico Curie / liter), are greater than the pre-operational level of 300 pico Curie / liter, but is consistent with washout of tritium (from gaseous releases) during precipitation events. Specifically, identification of tritium 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 effluent releases.

All. gaseous effluent releases during the report period did not exceed the release limits set forth in the Offsite Dose Calculation Manual.Gamma 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 weekly surface water sample at ATI-Allegheny Ludlam in Midland, PA (Site No. 2.1, 1.43 miles WNW) was not collected for the week of 4/22/08 to 04/29/08.

Although this weekly downstream surface water sample was missed, the minimum weekly surface water sampling requirements of ODCM procedure 1/2-ODC-3.03, Attachment Q, Table 3.12-1 were still met. Specifically, SINCE the ODCM only requires-one (1) upstream sample and one (1)downstream sample, THEN the minimum requirements were met with the upstream sample from Industry, PA (Site No. 49a, 4.93 miles NE), and the downstream sample from East Liverpool, OH (Site No. 5, 4.90 miles WNW). This condition is documented in SAP Order 200197646-0720.

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.

2-57 Beaver Valley Power Station 2008 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 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 111-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) 48 10-SSW 16.40 Weirton WV (Water Tower, Collier Way)2-58 I Beaver Valley Power Station RTL A9.690E 2008 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 2.0 C.1.5 1.0 0 a .0.5--- Dow n Stream Drinking Water -Midland---- Dow n Stream Drinking Water -East Liverpool Control Location -Up Stream Surface Water Unit 2 DW Preoperational (0.23 pQi / liter)-Required LLD (1 pa / liter)Reporting Level (2 pO / liter)0.0 t ~ : 1' ' -i ~ .X~ ; 9! ; 1 1 X! 1 1 1 1 le l le 1411 141 14, 4P 41, 10, 'CO 1CP lqb 4ý, , 4 lop 2-59 Beaver Valley Power Station 2008 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 a.. -- --indicator Mean (pCi / I)& Control Location / 1)Pre- Operational (300 pCi/),,,,,--Required LLD (2,000 pCO/)_ ..10000 ---,- Reporting Level Surface Water (30,000 pc/I) -'1 0 0 0 ....... .--. .....---------I- ---., ----- .......,-- ---------------------------00 00 10 A, ,4A , 4 ,z 41 40C ,9 ,4 ,4 ,4 le 10ýo 160 2-60 Beaver Valley Power Station 2008 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 Tritium Trends -Groundwater 100000 a --- Indicator Mean (p0 / I)10000 --a---Control Location (pa / I)Pre- Operational (440 pC/I)-" Required LLD (2,000 pO/I)t -Reporting Level Groundwater (30,000 pCiI)-1000 C.,.0 10 ,10 ....2-61 Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Figure 2-18 Graph of Annual Average Concentration:

Tritium in Drinking Water Beaver Valley Power Station REMPI Tritium Trends -Drinking Water 100000-- ---- Indicator Mean Control Location (pai / 1)Pre- Operational (310 pCVI)10000 -... Required LLD (2,000 pCi/I)

Level Drinl~ing Water (20,000 pCi/I)C-z3 10-,oA'iý 1",1,6c" , 160"' 140-A ,c e ,e ,10

q" ,r q 2-62 Beaver Valley Power Station RTL A9.690E 2008 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.2.1 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.2-63 I Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure.3 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM 4. Conclusions U 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. 3 The calculated doses to the public from the operation of BVPS -Unit 1 and 2, are below ODCM annual limits and resulted in only a small incremental dose to that which area residents already received as a result of natural background.

The doses constituted no meaningful risk to I the public.I I I I I I I I I I 2-64 3 Beaver Valley Power Station 2008 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

= 58 millirem / year= 40 millirem / year= < 1 millirem / year= 198 millirem / year= 296 millirem / year (Total from all sources shown above)(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-milfirem.

Largest Isotope Contributor Total Dose 402 Tritium Average Dose Avrg oe 0.0001005 Tritium (per Individual)

Comparison of Individual Dose BVPS Liquid Effluent Releases Versus Natural Background Radiation millirem BVPS Liquid Effluent Release Dose 0.0001005 Natural Radiation Exposure 296 2-65 Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 2 -ENVIRONMENTAL MONITORING PROGRAM Table 2-5 Comparison of Natural Background 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

= 58 millirem / year= 40 millirem / year= < 1 millirem / year= 198 millirem / year= 296 millirem / year (Total from all sources shown above)(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 I I I I I 0-50 mile Population Dose from BVPS Gaseous Effluent Releases Man-millirem Largest Isotope Contributor Total 144 Tritium Average 0.0000359 Tritium (per Individual)

Comparison of Individual Dose BVPS Gaseous Effluent Releases Versus Natural Background Radiation~millirem BVIPS Gaseous Effluent Release Dose 0.0000359 Natural Radiation Exposure 296 2-66 I Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 3 -LAND USE CENSUS A. Land Use Census Overview:

A Land Use Census was conducted September 4 through September 24, 2008 to comply with: 0 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 0 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:0542, dated September 29, 2008: 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 sqft: The current location has not changed since the previous census.The ctrrent location is at 238 State Route 168, Hookstown,.PA (0.760 miles SSW).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 changed since the previous census. However, SINCE the new location at 227 Calhoun Road, Aliquippa, PA (3.320 miles SE) cannot provide enough milk for sample analysis, THEN the location of the nearest Doe Goat milked will remain at 289 Calhoun Road, Aliquippa, PA (3.547 miles SE).F. Proiection for 2009 Dairy Cow Samplin2 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 2008:-Searight Dairy, 948 McCleary Road, RD1, Hookstown, PA (2.097 miles SSW)-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).3-1 Beaver Valley Power Station RTL A9.690E I 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 3 -LAND USE CENSUS I G. Projection for 2009 Doe Goat Sampling Locations:

3 The linear regression analysis also indicated that there may be up to two (2) Doe Goat sampling location in 2009. The Doe Goat sampling location for 2009 may be as follows:-Collins Farm, 289 Calhoun Road, Aliquippa, PA (3.547 miles, SE).-Sullivan Farm, 198 Wilson Drive, Aliquippa, PA (4.285 miles ESE).H. D/O for Milch Animal Locations:

3 None of the 2008 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/O 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.

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.

3 J. D/O Historical Comparison:

There was no adverse trend in D/Q when comparing 1997 to 2008 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 was not required.I IlI I I I 3-2 I Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report SECTION 3 -LAND USE CENSUS RTh A9.690E Enclosure 3 Table 3-1 Location of Nearest Residences, Gardens, Dairy Cows and Doe Goats SECTOR RESIDENCES 0 to 5 miles (miles)N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW`NNW 1.584 1.661 0.406 (2)0.603 0.429 0.476 1.583 1.102 1.399 0.760 1.453 1.394 2.204 2.742 0.885 0.902 GARDENS 0 to 5 miles (miles)None None None 1.04:7 2.252 1.713 1.802 1.983 2.276 0.760 (2)1.453 2.832 None None 1.033 2.413 0 to 5 miles (miles)None None None None None None None (1)None 3.85 1 2.097 (2)None None None None None 2.442 DOE GOATS 0 -to 5 miles (miles)None None None None 3.402-4.285 3.320 (2)None None None None None None None None None (1) 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.(2) Distances shown in Bold print are the nearest location for that receptor.3-3 Beaver Valley Power Station RTL A9.690E 2008 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.* 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).* 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.

0 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 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 4 -SPLIT SAMPLE PROGRAM and SPIKE SAMPLE INTER-LABORATORY COMPARISON PROGRAM Participation in an Inter-Laboratory Comparison Program is required by BVPS Unit 1 and 2 m 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.7-During the report period, BVPS used (Environmental, Inc., Midwest Laboratory

-Northbrook, IL) as the Contractor Laboratory, and (Analytics

-Atlanta, GA) as the Independent Laboratory.

The spiked samples included air particulate filter papers, charcoal cartridges, water samples, 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.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 performed by the Contractor Laboratory on four (4) milk samples.-A total of forty-eight (48) gamma spectrometry radionuclide analyses were 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 Laboratory on four (4) milk samples.-A total of four (4) chemical analyses for 1-131 analyses were performed by the Contractor Laboratory on four (4) water samples.-A total of four (4) tritium analyses were performed by the Contractor Laboratory on four (4) water samples.'-Comparison of results of the spiked milk and water samples showed acceptable agreement with the NRC acceptance criteria.

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

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

All but two (2) of the one-hundred-eight 3 (108) analyses met the BVPS acceptance criteria.I 4-2 I Beaver Valley Power Station RTL A9.690E 2008 Annual Radiological Environmental Operating Report Enclosure 3 SECTION 4 -SPLIT SAMPLE PROGRAM and SPIKE SAMPLE INTER-LABORATORY COMPARISON PROGRAM 0 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. The two samples that are not within the BVPS Acceptance Criteria are in the same sample type and are for two different sample analyses.

Although these sample analyses are not within the BVPS Acceptance Criteria, they are. within the NRC Acceptance Criteria.

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

The first of the two deviations occurred in the second quarter for milk for Sr-90 (-20.89%).

The second occurred in the third quarter, also for milk, but for Sr-89 (-21.79%).

4-3 Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report RTL A9.690E Enclosure 3 SECTION 4 -SPLIT SAMPLE PROGRAM and SPIKE SAMPLE INTER-LABORATORY COMPARISON PROGRAM Table 4-1 Inter-Laboratory Comparison Program Spiked Samples -1s 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 -5.84%Sr-90 15.75%1-131 (Chemical) 4.69%1-131 4.83%Ce-141 -0.15%Water Cr-51 0.77%03/20/2008 Ind Lab: E5862-93 Cs-134 -7.92%Con. Lab: SPW-1093 Cs-137 2.24%Co-58 4.26%Mn-54 4.40%Fe-59 5.65%Zn-65 5.32%Co-60 -0.05%Water 03/20/2008 Ind. Lab: E5861-93 H-3 3.57%Con. Lab: SPW-1092 Sr-89 -4.38%Sr-90 -5.43%1-131 (Chemical)

-1.67%1-131 5.00%Milk Ce-141 -0.48%Cr-51 1.64%03/20/2008 Ind. Lab: E5863-93 Cs-134 -6.24%Con. Lab: SPMI-1094 Cs-1 37 0.62%Co-58 2.40%Mn-54 5.31%Fe-59 1.76%Zn-65 6.64%Co-60 2.16%Filter Paper Cs- 137 03/20/2008 Ind. Lab: E5864-93 10.81%Con. Lab: SPAP-1095 (Gross Beta)Charcoal Cartridge 03/20/2008 Ind. Lab: E5865-93 1-131 -8.04%Con. Lab: SPCH-1096 I U I I I I I I I I I I I I I I I I II 4-4 Beaver Valley Power Station 2008 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 Spiked Samples -2 nd Quarter Percent Difference Between SmlTpanContractor Lab Activity and SampleType and ,Independent Lab Calculated Activity Sample Date Identification No. Sample Analyses (Contr. Lab -Ind. Lab) Ind. Lab Sr-89 -0.46%Sr-90 17.50%1-131 (Chemical)

I -5.74%1-131 3.75%Ce-141 -0.68%Water Cr-51 9.04%06/19/2008 Ind. Lab: E5937-93 Cs-134 -5.10%Cs-i137 0.95%Con. Lab: SPW-3057 Co-58 -2.02%Mn-54 6.14%Fe-59 5.84%Zn-65 5.70%.Co-6O 0.49%Water 06/19/2008 Ind. Lab: E5936-93 H-3 1.94%Con. Lab: SPW-3056 Sr-89 -5.65%Sr-90 -20.89%1-131 (Chemical)

-0.56%1-131 0.98%Milk Ce-141 2.76%Cr-51 7.68%06/19/2008 Id. Lab: E5938-93 Cs-134 -6.52%Cs-137 1.29%* Con. Lab: SPMI-3058 Co-58 -1.94%Mn-54 5.70%Fe-59 6.54%Zn-65 5.28%Co-60 2.31%4-5 Beaver Valley Power Station 2008 Annual Radiological Environmental Operating Report RTL A9.690E 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 Contractor Lab Activity and SampleType and Independent Lab Calculated Activity Sample Date Identification No. Sample Analyses_(Contr. Lab -Ind. Lab) / Ind. Lab Sr-89 -3.46%Sr-90 9.15%1-131 (Chemical) 6.10%1-131 1.24%Ce-141 6.36%Water Cr-51 5.09%09/18/2008 Ind. Lab: E6304-93 Cs-134 -7.40%Con. Lab: SPW-5026 Cs-137 2.71%Co-58 0.00%Mn-54 7.64%Fe-59 6.80%Zn-65 1.56%Co-60 1.03%Water'09/18/2008 Ind. Lab: E6303-93 H-3 3.96%Con. Lab: SPW-5025 Sr-89 -21.79%Sr-90 -17.27%1-131 (Chemical) 1.91%1-131 -3.39%Ce-141 1.12%Milk Cr-51 -2.99%09/18/2008 Ind. Lab: E6305-93 Cs-134 -10.65%Cs-i137 -2.28%Con. Lab: SPMI-5027 Co-58 -4.28%Co-58 -4.25%Mn-54 3.61%Fe-59 2.43%Zn-65 -0.13%Co-60 -4.27%Filter Paper Cs-i137 09/18/2008 Ind. Lab: E6306-93 5.38%Con. Lab: SPAP-5028 (Gross Beta)Charcoal Cartridge 09/18/2008 Ind. Lab: E6307-93' 1-131 -14.75%Con. Lab: SPCH-5029 I I I I I I I I I I I N I I I I I I I 4-6 Beaver Valley Power Station 2008 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 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 6.35%Sr-90 -0.75%1-131 (Chemical)

-5.30%1-131 -1.25%Ce-141 1.34%Water Cr-51 3.37%12/11/2008 Ind. Lab: E6370-93 Cs-134 -8.28%Cs-137 0.71%Con. Lab: SPW-6982 Co-58 -3.11%Mn-54 0.73%Fe-59 4.36%Zn-65 2.57%Co-60 1.41%Water 12/11/2008 Ind. Lab: E6369-93 H-3 4.16%Con. Lab: SPW-6981 Sr-89 -11.64%Sr-90 -1.59%1-131 (Chemical)

-5.26%1-131 -1.25%Ce-141 1.41%Milk Cr-51 -0.65%12/11/2008 Ind. Lab: E6371-93 Cs-1 34 -8.88%cs-i137 0.33%Con. Lab: SPMI-6983 Co-58 -1.63%Mn-54 1.38%Fe-59 7.60%Zn-65 0.44%Co-60 .0.83%4-7

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