ML111250514

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Beaver Valley - Rtl# A9.690E, 2010 Radioactive Effluent Release Report and 2010 Annual Radiological Environmental Operating Report, Enclosure 1 to L-11-041
ML111250514
Person / Time
Site: Beaver Valley
Issue date: 04/25/2011
From: Cress W M, Renz L M
FirstEnergy Nuclear Operating Co
To:
Office of Nuclear Reactor Regulation
References
L-11-041 RTL# A9.690E
Download: ML111250514 (91)
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Text

Enclosure A L-1 1-041 2010 Radioactive Effluent Release Report and 2010 Annual Radiological Environmental Operating Report (Report follows)

RTL# A9.690E FIRSTENERGY NUCLEAR OPERATING COMPANY BEAVER VALLEY POWER STATION 2010 RADIOACTIVE EFFLUENT RELEASE REPORT AND 2010 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: 2010 RADIOACTIVE EFFLUENT RELEASE REPORT AND 2010 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT UNITS NO. 1 AND 2 LICENSES DPR-66 AND NPF-73 Approved by: Donald J. Salera ate:

I

Subject:

Beaver Valley Power Station, Unit Nos. 1 and 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Radioactive Effluent Release Report for 2010, and Annual Radiological Environmental Operating Report for 2010 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) U Southwest Regional Office 400 Waterfront Drive Pittsburgh, PA 15222 INPO (Attn: Bill Nestel) I 700 Galleria Parkway SE Suite 100 Atlanta, GA 30339-5957 I

Distribution for Enclosures 1 -3: Page 2 Beaver County Cooperative Extension (Attn: JL Miller)156 Cowpath Road Aliquippa, PA 15001-5842 Hancock County Office of Emergency Services (Attn: JP Jones)PO Box 884 New Cumberland, WV 20647 Ohio Department of Health (Attn: RL Suppes)246 North High Street Columbus, OH 43266-0288 Ohio Emergency Management Agency (Attn: Carol O'Claire)2855 West Dublin Granville Road Columbus, OH 43235 East Liverpool Water Authority (Attn: Keith Clark)2220 Michigan Avenue East Liverpool, OH 43920 ORSANCO (Attn: Jerry Schulte)5735 Kellogg Avenue Cincinnati, OH 45228 B. F. Jones Memorial Library 663 Franklin Avenue Aliquippa, PA 15001 Mr. Robert Leidy, HP3 Bureau of Radiation Protection Ohio Department of Health Northeast District Office 161 South High Street, Suite 400 Akron, OH 44308-1612 Distribution for Enclosures

1. -3: I Page3 3 Copies of Report for FENOC Addressees:

MD Banko, BVPS; Supervisor, Nuclear Chemistry Services (A-BV-A)LM Renz, BVPS; Chemistry REMP and RETS Administrator (A-BV-A) 10 copies DJ Salera, BVPS; Manager, Site Chemistry (A-BV-A)K Nevins, Akron; Sr. Nuclear Specialist, Fleet Licensing (A-GO-2) 2 copies BH Furdak, BVPS; Sr. Nuclear Specialist, Operations Oversight (A-BV-NCD3)

RL Evans, Akron; Director, Environmental (A-GO- 13)DW Jenkins, Akron; Sr. Attorney II, Legal (A-GO-15)M Hall, Akron; Vice President, Energy Policy (A-GO- 18)MJ Jirousek, Akron; Manager, Environmental Generation Services (A-GO-13)K Yeager, Perry NPP RETS Administrator (A-PY-CCB 125) i 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 I BVRC -Keywords:

Radioactive Effluent Release Report, Annual Radiological Environmental Operating Report l l I I I I I I i RTL A9.690E Enclosure 2, Page i Beaver Valley Power Station -Units I & 2 2010 Radioactive Effluent Release Report FirstEnergy Nuclear Operating Company FENOC Beaver Valley Power Station -Units I & 2 Unit I License No. DPR-66 Unit 2 License No. NPF-73 Form 1/2-ENV-01.05.FO1 (page 2 of 39), Rev 3 Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2010 Index RTL# A9.690E I Enclosure 2, Page ii I Title Page Cover Index ii Executive Summary -Report Submittal Requirements iii Executive Summary -Liquid and Gaseous Effluent Control (Part 1 of 2) iv Executive Summary -Liquid and Gaseous Effluent Control (Part 2 of 2) v Executive Summary -Trends of Total Dose vi Executive Summary -Trends of Liquid Release Activity (Fission and Activation Products) vii Executive Summary -Trends of Liquid Release Activity (Tritium) viii Executive Summary -Trends of Liquid Release Offsite Dose Projections ix Executive Summary -Trends of Gaseous Release Activity (Fission and Activation Gas) x Executive Summary -Trends of Gaseous Release Activity (Particulates and Radioiodines) xi Executive Summary -Trends of Gaseous Release Activity (Tritium) xii Executive Summary -Trends of Unit 1 Gaseous Release Offsite Dose Projections xiii Executive Summary -Trends of Unit 2 Gaseous Release Offsite Dose Projections xiv Results of Abnormal Releases xv Results of Onsite Spills and Items Added to Decommissioning Files per 10CFR50.75(g) xvi Results of Onsite Groundwater Monitoring Program xvii Corrections to Previous Radioactive Effluent Release Reports xviii I I I I U I I SuoDlemental Information Paae 1 Table 1A Gaseous Effluents

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

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

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

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

-Ground Level Continuous Releases (Unit 1) 6 Table 1 C-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 I I I I I I I I I Attachment 1 Part 1: Joint Frequency Distribution Tables (35 ft)Part 2: Joint Frequency Distribution Tables (150 ft)Part 3: Joint Freauencv Distribution Tables (500 ft)Attachment 2 Unit 1 and 2 Offsite Dose Calculation Manual (Complete Copy)Attachment 3 IC-14 Dose Assessment for Routine Effluent Releases (from Key Solutions, Inc.)I Form 1/2-ENV-01.05.FO1 (page 3 of 39), Rev 3 RTL# A9.690E Beaver Valley Power Station -Units 1 & 2 Enclosure 2, Page iii Radioactive Effluent Release Report Calendar Year -2010 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-0 1.05, "Compliance with Regulatory Guide 1.21 and Technical Specifications" NUREG- 1301, "Offsite Dose Calculation Manual Guidance:

Standard Radiological Effluent Controls for Pressurized Water Reactors, Generic Letter 89-01, Supplement No. 1, April 1991" Regulatory Guide 1.21, "Measuring Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Material in Liquid and Gaseous Effluents from Light- Water Cooled Nuclear Power Plants, Revision 1, June 1974" BVPS Condition Report No. CRI0-77489, Revision needed for 1/2-ODC-2.03.

BVPS Condition Report No. CR10-78575, Missing filter papers for effluent release samples.BVPS Condition Report No. CRIO-79472, RM-DA-100 will be inoperable for greater than 30 days.BVPS Condition Report No. CRIO-80322, Reduced flow to PAB ventilation vent FR-VS-101.

BVPS Condition Report No. CRI 0-82309, Elevated tritium confirmed in 4 of 7 new groundwater wells.BVPS Condition Report No. CRIO-86844, 1/2-ODC-2.01, Liquid Effluents, requires mixing eductors for discharging tanks.

Form 1/2-ENV-01.05.F01 (page 4 of 39), Rev 3 Beaver Valley Power Station -Units I & 2 RTL# A9.690E Enclosure 2, Page iv I I I Radioactive Effluent Release Report Calendar Year -2010 Executive Summary -Liquid and Gaseous Effluent Control (Part I of 2)Onsite Groundwater Monitoring:

Seventeen (17) onsite monitoring wells existed prior to 2010. In 2010, two (2) wells were closed because of damage. One (1) of these two (2) wells was not part of the original sampling program because it had previously deteriorated.

In August 2010, seven (7) new wells were drilled, making a total of twenty-three (23) monitoring wells. Results from fifteen (15) wells were < 440 pCi/L (BVPS pre-operational mean). Results from two (2) wells were >440 pCi/L, but <2000 pCi/L.Results from five (5) wells (MW-12S/D

& MW-14S/D & MW-I 5) were >2000pCi/L, but <20,000 pCi/L.Results from one (1) well (MW-16) were >20,000 pCi/L, but <30,000 pCi/L. Because BVPS groundwater is not a source of drinking water, a limit of 30,000 pCi/L is the appropriate EPA Reporting Limit. The NEI/FENOC communication level was reached for MW-12S & MW-12D during 2007, and notification to local, state & federal agencies was performed on 10/08/07.

Additional communication for new well results was perfomed on 09/08/10.

No adverse effect to the offsite environment has been detected at this time, because all offsite groundwater, drinking water and surface water samples were <440 pCi/L.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 IOCFR50.75(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 Form 1/2-ENV-01.05,F01 (page 5 of 39), Rev 3 RTL# A9.690E Beaver Valley Power Station -Units 1 & 2 Enclosure 2, Page v Radioactive Effluent Release Report Calendar Year -2010 Executive Summary -Liquid and Gaseous Effluent Control (Part 1 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 was one (1) ODCM Surveillance Deficiency.

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

The Meteorological Data Recovery met the minimum requirement of at-least 90%, as specified in Section 5 of Revision I to Regulatory Guide 1.23, Meteorological Monitoring Programs for Nuclear Power Plants.Population Dose vs. Natural

Background:

The 0-50 mile total and average population doses were calculated using liquid and gaseous release quantities and real time meteorology.

The average population dose is based on four (4) million people within 0-50 miles of the BVPS site. The following comparison to natural background radiation demonstrates that BVPS operations did not adversely affect the surrounding environment.

476 man-mrem =BVPS Total Population Dose for the year 0.0001190 mrem = BVPS Average Individual Dose for the year 296 mrem = Natural Background Individual Dose for the year. This dose value is documented as natural background radiation exposure for an individual in a year from the 1990 BEIR V Report.Carbon-14 Dose Assessment:

The maximum bounding dose to a member of the public resulting from atmospheric C-14 releases from Unit I was determined to be less than 2.67 mremn to the bone and less than 0.53 mrem to all other organs. The child is the controlling age group. The maximum bounding dose to a member of the public resulting from atmospheric C-14 releases from Unit 2 releases from Unit 2 was determined to be less than 2.96 mremn to the bone and less than 0.59 mrem to all other organs. The child is the controlling age group. These calculations are included in Attachment 3 and were provided by Key Solutions, Inc.

Form 1/2-ENV-01.05.FO1 (page 6 of 39), Rev 3 Beaver Valley Power Station -Units I & 2 Radioactive Effluent Release Report Calendar Year -2010 Executive Summary -Trends of Total Dose RTL# A9.690E Enclosure 2, Page vi I I I I Trends of Total Dose: The following graph provides a comparison of the ODCM dose projections from all facility releases and direct radiation exposures to show compliance with Member of the Public dose limits from 10 CFR 20.1301 and 40 CFR Part 190. The graph reflects the results of the efforts to stabilize and reduce offsite dose.Unit 1 and Unit 2 Total Dose 100.0%E 10.0% ..... _°--<,~~~~~~~....

...... ........ ......0 o 0 0.1% .O Unit 1&2, Percent of 40 CFR 190.10(a)

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

Thyroid Dose Limit U-7T Unit 1&2, Percent of 10 CFR 20.1301(a)(1)

TEDE Dose Limit I I I I I I I I I I I Form 1/2-ENV-01.05.FO1 (page 7 of 39), Rev 3 Beaver Valley Power Station -Units 1 & 2 RTL# A9.690E Enclosure 2, Page vii Radioactive Effluent Release Report Calendar Year -2010 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 (n'00 0.0(j-I U.U1 Ib ChA P C§b SIP ýIýv Noi NOj 0 BVPS Unit 1 Ut-U-BVPS Unit 2 Form 1/2-ENV-01.05.FO1 (page 8 of 39), Rev 3 Beaver Valley Power Station -Units I & 2 RTL# A9.690E Enclosure 2, Page viii Radioactive Effluent Release Report Calendar Year -2010 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 -1000 --------W 0 1 00 0 -....-----.- ------------.- ----.-. .-.- ----------------------------------.- --.-------. ---. -----------------------------. ....1 0 10 I BVPS Unit1 -U-BVPS Unit 2 I I I I I I I I I I I i I I I I I Form 1/2-ENV-01.05.F01 (page 9 of 39), Rev 3 Beaver Valley Power Station -Units 1 & 2 RTL# A9.690E Enclosure 2, Page ix Radioactive Effluent Release Report Calendar Year -2010 Executive Summary -Trends of Liquid Release Offsite Dose Projections Liquid Release Offsite 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 I or Unit 2 Liquid Effluent Doseý100,0%E 4-0 10.0%1.0%0.10, Nb t q N N1 TIPCJ""0lUnit 1 or Unit 2, Percent of Maximum Organ Dose Limit 0 Unit 1 or Unit 2, Percent of Total Body Dose Limit Form 1/2-ENV-01.05.F01 (page 10 of 39), Rev 3 Beaver Valley Power Station -Units 1 & 2 I RTL# A9.690E Enclosure 2, Page x Radioactive Effluent Release Report Calendar Year -2010 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 10000.00 1000.00 '0 -------------

1000.00 c 1.00 0.10 --0.01 ,q "0 U I I I I I I I I 1 BVPS Unit 1 --W--BVPS Unit2 1 Form 1/2-ENV-01.05.FO1 (page 11 of 39), Rev 3 Beaver Valley Power Station -Units 1 & 2 RTL# A9.690E Enclosure 2, Page xi Radioactive Effluent Release Report Calendar Year -2010 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 variations are due to identification of Co-58 in weekly effluent pathway samples during refueling outages at both Units I and 2, while decreasing trends are due to extended hold-up periods of gas space prior to release.Gaseous Effluent Trends Particulates

& Radioiodines 1 .E-01 1 .E-02 1.E-03* 1 .E-04 U)1.E-05 1 .E-06 1.E-07ýC~v 'c Nq NCq5 If 1 0 BVPS Unit 1--M-BVPS Unit 2 1 Form 1/2-ENV-01.05.F01 (page 12 of 39), Rev 3 Beaver Valley Power Station -Units 1 & 2 RTL# A9.690E Enclosure 2, Page xii Radioactive Effluent Release Report Calendar Year -2010 Executive Summary -Trends of Gaseous Release Activity (Tritium)1 I I I Gaseous Release Activity (Tritium):

The following graph provides a comparison of total gaseous tritium discharged from the site from 1976 to present. The recent decreases were due to efforts to reduce overall offsite dose. Specifically, discharging liquid radioactive inventory provided the benefit of reduced total offsite dose, due to reduction in evaporative losses from the fuel pools.Gaseous Effluent Trends Tritium 1000 100 10 I I 1 I U I I I 10 5§1 '19& & NZ SBVPS Unit 1 -U-MBVPS Unit 2 I U I I I Form 1/2-ENV-01.05.FO1 (page 13 of 39), Rev 3 Beaver Valley Power Station -Units 1 & 2 RTL# A9.690E Enclosure 2, Page xiii Radioactive Effluent Release Report Calendar Year -2010 Executive Summary -Trends of Unit I Gaseous Release Offsite Dose Projections Unit 1 Gaseous Release Offsite Dose Projections:

The following graph provides a comparison of Unit I gaseous offsite dose projections that were calculated to the maximum individual per 10 CFR 50, Appendix I and the ODCM. The projections use ODCM default meteorological parameters for the atmospheric conditions surrounding the plant site, and were performed prior to release authorization.

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.E 01 100.0000000%

10.0000000%

1.0000000%

0.1000000%

0.0100000%

0.0010000%

0.0001000%

0.0000100%

0.0000010%--nt~~tn I D Unit I Gaseous Effluent Dose]U.UUUUrJJU I /O-0ýUnit 1, Percent of Gamma Air Dose Limit U Unit 1, Percent of Beta Air Dose Limit Unit 1, Percent of Highest Organ Dose Limit Form 1/2-ENV-01.05.F01 (page 14 of 39), Rev 3 Beaver Valley Power Station -Units 1 & 2 I RTL# A9.690E Enclosure 2, Page xiv i Radioactive Effluent Release Report Calendar Year -2010 Executive Summary -Trends of Unit 2 Gaseous Release Offsite Dose Projections Unit 2 Gaseous Release Offsite Dose Projections:

The following graph provides a comparison of Unit 2 gaseous offsite dose projections that were calculated to the maximum individual per 10 CFR 50, Appendix I and the ODCM. The projections use ODCM default meteorological parameters for the atmospheric conditions surrounding the plant site, and were performed prior to release authorization.

The steady decrease in highest organ dose was due to efforts to reduce overall offsite dose. Specifically, discharging liquid radioactive inventory provided the benefit of reduced total offsite dose, due to reduction in evaporative losses from the fuel pools.Unit 2 Gaseous Effluent Dose 100.0000000%

10.0000000%

E 1.loooo~ooo/

-- ----1.0.000000%

___ __ ______ ___,____-____

0.0100000%

CD>- 0.0010000%

0 o 0.0001000%

0.0000100%

0.0000010%

-0.0000001%

Unit 2, Percent of Gamma Air Dose Limit < Unit 2, Percent of Beta Air Dose Limit--Unit 2, Percent of Highest Organ Dose Limit I I I I I I I I I I I I I I I I I I Form 1/2-ENV-01.05.FO1 (page 15 of 39), Rev 3 Beaver Valley Power Station -Units I & 2 Radioactive Effluent Release Report Calendar Year -2010 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 39), Rev 3 RTL# A9.690E Beaver Valley Power Station -Units 1 & 2 Enclosure 2, Page xvi Radioactive Effluent Release Report Calendar Year -2010 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 IOCFR50.75(g)

Files: None Form 1/2-ENV-01.05.FO1 (page 17 of 39), Rev 3 Beaver Valley Power Station -Units I & 2 RTL# A9.690E Enclosure 2, Page xvii Radioactive Effluent Release Report Calendar Year -2010 Results of Onsite Groundwater Monitoring Program Summary of Onsite Groundwater Samples 2010 2010 2010 Typical H-3 H-3 H-3 H-3 Maximum Minimum Average LLD (pCi/L) (pCi/L) (pCi/L) (pCi/L)Required PrE H-3 Operationa LLD Mean For H-ý(pCi/L) (pCi/L I Are Any H-3 Analyses Greater Than I The Pre 3 Operational) Mean For H-3 ?NEI and FENOC EPA Communication Reporting Level Level For H-3 For H-3 (pCi/L) (pCi/L)I 1stQuarter 1 76391 1441 11551 <2001 <20001 4401 Yes 20001 30000]I Aug 1 223871 1831 49501 <2001 <20001 4401 Yes! 20001 3000 13rd Quarter 255831 1321 27661 <2001 <20001 4401 Yesl 20001 30000 1 Nov 1 231711 58601 85601 <2001 <20001 4401 Yesl 2000 30000 1 Dec 1 204881 48381 80991 <2001 <20001 4401 Yesl 20001 30000 H-3 Summary: Seventeen (17) onsite monitoring wells existed prior to 2010. In 2010, two (2) wells were closed because of damage. One (1) of these two (2) wells was not part of the original sampling program because it had previously deteriorated.

In August 2010, seven (7) new wells were drilled, making a total of twenty-three (23) monitoring wells. Results from fifteen (15)wells were < 440 pCi/L (BVPS pre-operational mean). Results from two (2) wells were >440 pCi/L, but <2000 pCi/L. Results from five (5) wells (MW-12S/D

& MW-14S/D & MW-15) were >2000pCiiL, but <20,000 pCi/L. Results from one (1) well (MW-16) were>20,000 pCi/L, but <30,000 pCi/L. Because BVPS groundwater is not a source of drinking water, a limit of 30,000 pCi/L is the appropriate EPA Reporting Limit. The NEI/FENOC communication level was reached for MW-12S & MW-12D during 2007, and notification to local, state & federal agencies was performed on 10/08/07.

Additional communication for new well results was perfomed on 09/08/10.

No adverse effect to the offsite environment has been detected at this time, because all offsite aroundwater, drinkinq water and surface water samples were <440 pCi/L.Principal Gamma Emmitter Summary: Twenty-three (23) onsite monitoring wells were sampled during the year, and analyzed for Principal Gamma Emitters.

The results showed no positive indication of Licensed Radioactive Material (LRM) in any of the analyses.BVPS (2007-2010)

Onsite Groundwater Monitoring Program H-3 Trends<200 pCi/I = Typical LLD 440 pCi/L = Pre-Operational Mean 800 pCi/L = Pre-Operational Max 2,000 pCi/L = NRC Required LLD (NEI Communication Level)20,000 & 30,000 pCi/L = Reporting Levels 100000-Max of All GWM Indicator Wells-Avg of All GWM Indicator Wells-A--- MW-10: 67.0' deep, Upgradient Location-Typical LLD H-3 (<200 pCi/LI Pre- Operational Mean H-3 (440 pCi/LI Pre- Operational Maximum H-3 (800 pCi/L)-NRc Required LLD H-3 (2,000 pCi/L)-EPA Reporting Level H-3 (20,000 pCi/LI-"EPA Reporting Level H-3 (30,000 pCi/L)i.2 0.10000 1000 A 100 Form 1/2-ENV-01.05.FO1 (page 18 of 39), Rev 3 Beaver Valley Power Station -Units 1 & 2 RTL# A9.690E Enclosure 2, Page xviii Radioactive Effluent Release Report Calendar Year -2010 Corrections to previous Radioactive Effluent Release Reports Correction(s) to Previous Radioactive Effluent Release Reports: None I I I I I I U I I I I I I I I I I I I Form 1/2-ENV-01.05.F01 (page 19 of 39), Rev 3 Beaver Valley Power Station -Units 1 & 2 I Radioactive Effluent Release Report Calendar Year -2010*Supplemental Information Page RTL# A9.690E Enclosure 2, Page 1 of 21 FACILITY:

B.V.P.S. Units I and 2 LICENSEE:

FENOC 1. Regulatory Limits ..... ...._....a Fission and activation gases: Annual Unit 1 or 2 Dose: 10 mrad from Gamma, & 20 mrad from Beta lodines &particulates, half-lives

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

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

a. Fission and activation gases: Site Release Rate: 500 mrem/yr to Total Body, & 3000 mrem/yr to the Skin b. lodines & particulates, half-lives

>8 days: Site Release Rate: 1500 mrem/yr to Any Organ c. Liquid effluents:

Site Release Concentration:

10 times 10 CFR 20 Appendix B, Table 2, EC's[3. Average Energy (Not Applicable To The BVPS ODCM)4. Measurements and Approximations of Total Radioactivity The methods used to measure or approximate the total radioactivity in effluents, and the methods used to determine radionuclide comnosition are as follows: a. Fission and activation ases: Ge Gamma Spectrometry, Liquid Scintillation Counter b. lodines: Ge Gamma Spectrometry

c. Particulates, half-lives

> 8 days: IGe Gamma Spectrometry, Proportional Counter d. Liquid effluents:

Ge Gamma Spectrometry, Proportional Counter, Liquid Scintillation 1st Unit IQuarte 2nd 3rd 4th Quarter I Quarter I Quarter Calendar Year 28 31 42 37 138 8130 8480 14963 12306 43879 1033 1000 990 955 1033 290 274 356 333 318 S 98 96 1 12 1 100 112 60167 33067 10100 32267 33900_ _11 8 9 18 46 5450 104 481 7756 13791 4759 58 405 3933 4759 495 13 53 431 300;ji 13 1 46 1 16 1 0.21 0 NONE NONE NONE [NONE NONE j2.ooE+00 o.ooE+00 I 0.OOE+00 0IOOE+00 0.OOE+00.I NONE NONE NONE INONE NONE Curies 0.OOE+00 I 0.OOE+00 I 0.OOE+00 0.OOE+00 0.OOE+00 Form 1/2-ENV-01.05.FO1 (page 20 of 39), Rev 3 Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2010 Table 1A Gaseous Effluents

-Summation Of All Releases RTL # A9.690E Enclosure 2, Page 2 of 21 1 I I 1st 2nd 3rd 4th Unit Quarter Quarter {Quarter IQ uarter Calendar Year Total Error, %I 7.85E-02 I 3.20E-01 I0.00E+00 I 7.93E-01 I 1.19E+00 26.5%I 3.93E-02 I0.OOE+00 I0.00E+00 I 4.08E-01 I 4.47E-01 I 4 + 4 3.93E-02 3.20E-01 10.OOE+00 I 3.85E-01 I 7.44E-01 9.96E-03 4.05E-02 10.OOE+00 1.01E-01 3.78E-02 N/A N/A N/A N/A N/A I I+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 28.3%-00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 I M 2AO.0E+00 I0.OOE+00 10.OOE+00 0,00E+00).OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 4 4 N/A N/A N/A N/A I 30.0% I 5.47E-06 0.OOE+00 3.10E-05 2.23E-04 2.60E-04 0.OOE+00 0.OOE+00 3.10E-05 2.14E-04 2.45E-04 5.47E-06 0.OOE+00 O.OOE+00 8.97E-06 1.44E-05 6.94E-07 0.OOE+00 3.93E-06 2.84E-05 8.24E-06 N/A N/A N/A N/A N/A I I I.OOE+00 0.OOE+00 I 0.OOE+00 I 0.OOE+00 0.OOE+00 30.0%1 M00 0.OOE+00 I0.OOE+00 10.OOE+00 0.00E+00ý00I0,00E+00 10.OOE+00 10.OOE+00 I .OOE+00).OOE+00 0.OOE+00 I0.OOE+00 I0.OOE+00 0.OOE+00 4 4 4 +N/A N/A N/A N/A I 32.9% I I I 2.35E+00 12.66E+00 13.87E+00 11.75E+00 I 1.06E+01 2.10E+00 12.01E+00 12.69E+00 11.50E+00 I 8.30E+00 2.49E-01 6.46E-01 1.18E+00 2.50E-01 2.33E+00 2.98E-01 3.37E-01 4.91 E-01 2.22E-01 3.37E-01 N/A N/A N/A N/A N/A N/A = Not Applicable The amount of time (in seconds) used to calculate the release rates specified in A.2, B.2, C.2, D.2 and E.2 is the average amount of seconds per calendar quarter (7.88E+06 seconds).I I

  • Form 1/2-ENV-01.05.FO1 (page 21 of 39), Rev 3 Beaver Valley Power Station -Units 1 & 2 I Radioactive Effluent Release Report Calendar Year -2010 Table 1B-EB Gaseous Effluents

-Elevated Batch Releases RTL # A9.690E Enclosure 2, Page 3 of 21 1st 2nd 3rd 4th Calendar Nuclides released Unit I "Quarter I1Quarter I Q r I 3 I I I LLD LLD LLD 5.80E-05 5.80E-05 LLD LLD LLD LLD LLD LLD LLD LLD 5.51E-06 5.51E-06 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 2.51E-03 2.51E-03 LLD LLD LLD 5.88E-03 5.88E-03 LLD LLD LLD 1.36E-04 1.36E-04 LLD LLD LLD 5.57E-04 5.57E-04 LLD LLD LLD 6.98E-05 6.98E-05 LLD LLD LLD LLD LLD unidentified ci NONE NONE NONE NONE NONE Totalforperiod Ci ND ND ND 9.22E-03 9.22E-03 2. lodlnes iodino-13i ci LLD LLD LLD LLD LLD iodine-433 ci LLD LLD LLD LLD LLD iodIne-135 Ci LLD LLD LLD LLD LLD Totalforperiod Ci ND N ND ] ND D ND ND 3. Particulates 3 ~chromumh-I~51 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 1.05E-06 1.05E-06 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 1.59E-05 1.59E-05 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD unidentified Ci NONE NONE I NONE NONE NONE Totaiforperiod Ci ND ND ND 1.70E-05 1.70E-05 LLD = Below the Lower Limit of Detectability, in uCi/cc (Table 4).ND = None Detected* Carbon-14 data provided in Attachment 3 from Key Solutions, Inc.

Form 1/2-ENV-01.05.F01 (page 22 of 39), Rev 3 Beaver Valley Power Station -Units I & 2 Radioactive Effluent Release Report Calendar Year -2010 Table 1B-EC Gaseous Effluents

-Elevated Continuous Releases RTL # A9.690E Enclosure 2, Page 4 of 21 I I I.....t .2nd 1 3rd ..4th 1.Calendar 3 Nuclides released Unit Quarter Quart*er Quarter Quarter Year 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 7.85E-02 LLD LLD 7.53E-01 8.32E-01 LLD LLD LLD LLD LLD LLD LLD LLD 8.31E-03 8.31E-03 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD undentfied Ci NONE NONE NONE NONE NONE Totalor period CI 7.85E-02 ND ND 7.61E-01 8.40E-01 i ine-131 i LLD LLD LLD LLD LLD i" LLD LLD LLD LLD LLD iodine435 Ci LLD LLD LLD LLD LLD Totalforperiod Ci ND ND ND ND ND LLD LLD LLD LLD LLD m e ci LLD LLD LLD LLD LLD....... ci LLD LLD LLD LLD LLD ci LLD LLD LLD LLD LLD c l ci LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD s t -LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD m d -i LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD b LLD LLD LLD LLD LLD cerium-141 i LLD LLD LLD LLD LLD c- i LLD LLD LLD LLD LLD LLD LLD LLD 9.86E-07 9.86E-07 uniden t ied Ci NONE NONE NONE NONE NONE Total for period Ci ND ND ND 9.86E-07 9.86E-07 I I 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* Carbon-14 data provided in Attachment 3 from Key Solutions, Inc.I Form 1/2-ENV-01.05.FO1 (page 23 of 39), Rev 3 Beaver Valley Power Station -Unit 1 RTL # A9.690E Enclosure 2, Page 5 of 21 Radioactive Effluent Release Report Calendar Year -2010 Table IC-GB1 Gaseous Effluents

-Ground Level Batch Releases (Unit 1)1st 2nd e I 4th I Calendar Nuclides released Unit I Quarter Quarter u arter Year 1. Fission gases argon-41 CI LLD LLD LLD LLD LLD krypton85 Ci LLD LLD LLD LLD LLD krypton-85m CI LLD LLD LLD LLD LLD krypton-87 Ci LLD LLD LLD LLD LLD krypton-88 Ci LLD LLD LLD LLD LLD xenon-131m Ci LLD LLD LLD LLD LLD xenon-133 Ci LLD LLD LLD 2.25E-02 2.25E-02 xenon-133m Ci LLD LLD LLD LLD LLD xenon-135 Ci LLD LLD LLD LLD LLD xenon-135m Ci LLD LLD LLD LLD LLD xenon-138 Ci LLD LLD LLD LLD LLD unidentified 0 Ci NONE NONE NONE NONE NONE Total for period Ci ND ND ND 2.25E-02 2.25E-02 2. lodines iodine-131 , Ci LLD LLD LLD LLD LLD iodlne-133 Ci LLD LLD LLD LLD LLD iodine-135 j Ci LLD LLD LLD LLD LLD Totalfor period CI ND ND ND ND ND 3. Particulates chromium-51 CI LLD LLD LLD LLD LLD manganese-54 Ci LLD LLD LLD LLD LLD iron-59 Ci LLD LLD LLD LLD LLD cobalt-57 Ci LLD LLD LLD LLD LLD Ci LLD LLD LLD LLD LLD cobalt-60 Ci LLD LLD LLD LLD LLD zinc4SI Ci LLD LLD LLD LLD LLD strontium-89 Ci LLD LLD LLD LLD LLD strontium-90 GCi LLD LLD LLD LLD LLD molybdenum-99 Ci LLD LLD LLD LLD LLD cesium-134 Ci LLD LLD LLD LLD LLD cesium-137 Ci LLD LLD LLD LLD LLD barium/lanthanum-140 Ci LLD LLD LLD LLD LLD cerium-141 Ci LLD LLD LLD LLD LLD cerlum-'144 Ci LLD LLD LLD LLD LLD Ci LLD LLD LLD LLD LLD carbon-14 Ci ...unidentified CI NONE NONE NONE NONE NONE Total for period Ci ND ND ND ND ND LLD = Below the Lower Limit of Detectability, in uCi/cc (Table 4).ND = None Detected* Carbon-14 data provided in Attachment 3 from Key Solutions, Inc.

Form 1/2-ENV-01.05.FO1 (page 24 of 39), Rev 3 Beaver Valley Power Station -Unit I RTL # A9.690E Enclosure 2, Page 6 of 21 I I I Radioactive Effluent Release Report Calendar Year -2010 Table 1C-GCI Gaseous Effluents

-Ground Level Continuous Releases (Unit 1)1st 2nd 3rd 4th Calendar Nuclides reiased Unit Quarter Quarter Quarter Quarter Year 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 I I I I I I I I unidentified C I NONE NONE NONE NONE NONE Total period Ci ND ND ND ND ND 2. lodifles ipohine-131 Cli LLD LLD J LLD J LLD LLD iodine 33 Cl LLD j LLD LLD j LLD LLD iodui6 I Ci I LLD LLD LLD j LLD LLD Total or period Cl ND J ND J ND ND ND chromium-51 ci LLDLLD LLD 4.25E-05 4.25E-05 m a e ci LLD LLD LLD LLD LLD irn5 i LDLLD LLD LLD LLD c1-7: LLD LLD LLD LLD LLD cbl58Ci, LLD LLD 8.77E-06 1.43E-04 1.52E-04 coat6 i LLD LLD 2.79E-06 1 .46E-05 1 .74E-05 zinc-65 ci LLD LLD LLD LLD LLD z n n u Cl LLD LLD LLD 5.41 E-06 5.41 E-06 zir" ................

97 LLD LLD LLD LLD LLD m I: LLD LLD LLD LLD LLD; su13 ci LLD LLD LLD LLD LLD..... ....... .. LLD LLD 1.94E-05 1.4 E-0 1.94E-05 ToaLoLp~od D NLD 2.79E-06 1.46E-05 1.74E-05 baimlataum10 C LLD LLD LLD LLD LLD cerium11 LLD LLD LLD LLD LLD cei,-44c LLD LLD LLD LLD LLD seeim7 Ci LLD LLD LLD LLD LLD Tota foLEro CD LLD 3109E-05 2.0ED0 2.36E-04 I I I I LLD = Below the Lower Limit of Detectability, in uCi/cc (Table 4).ND = None Detected* Carbon-14 data provided in Attachment 3 from Key Solutions, Inc.

Form 1/2-ENV-01.05.FO1 (page 25 of 39), Rev 3 Beaver Valley Power Station -Unit 2 I Radioactive Effluent Release Report RTL # A9690E Enclosure 2, Page 7 of 21 Calendar Year -2010 Table lC-GB2 Gaseous Effluents

-Ground Level Batch Releases (Unit 2)N 1 1st 2nd 3rd Qu4th Calendar INuclides released Unit I uareI Quarter IQuarter IQu~arter Year I 1. Fission gases argon-41 Ci LLD LLD LLD LLD LLD krypton-85 Ci LLD LLD LLD LLD LLD krypton-85m Ci LLD LLD LLD LLD LLD krypton-87 Ci LLD LLD LLD LLD LLD krypton-88 Ci LLD LLD LLD LLD LLD xenon-131m CI LLD LLD LLD LLD LLD xenon-133 ci LLD LLD LLD LLD LLD xenon-133m ci LLD LLD LLD LLD LLD xenon-135 CI LLD LLD LLD LLD LLD xenon-135m Ci LLD LLD LLD LLD LLD xenon-138 Ci LLD LLD LLD LLD LLD unidentified J Ci ( NONE NONE NONE NONE NONE Total for period -Ci ND ND ND ND ND 2. lodines iodine-131 Ci LLD LLD LLD LLD LLD iodine-133 Ci LLD LLD LLD LLD LLD iodine-135 J Ci LLD LLD LLD LLD LLD Total for period Cii ND ND ND ND ND 3. Particulates beryllium-7 Cl LLD LLD LLD LLD LLD chromium-51 Ci LLD LLD LLD LLD LLD manganese-54 Ci LLD LLD LLD LLD LLD cobalt-57 Ci LLD LLD LLD LLD LLD cobalt-58 Ci LLD LLD LLD LLD LLD cobaIt-60 Ci LLD LLD LLD LLD LLDCi LLD LLD LLD LLD LLD strontium4-9 Ci LLD LLD LLD LLD LLD strontium-90 CI LLD LLD LLD LLD LLD zlrconiumwniobium-97 Ci LLD LLD LLD LLD LLD cesium-I34 Ci LLD LLD LLD LLD LLD cesium-I37 Ci LLD LLD LLD LLD LLD barlum/lanthanum-140 Ci LLD LLD LLD LLD LLD cerium-141 Ci LLD LLD LLD LLD LLD cerlum-lI ci LLD LLD LLD LLD LLD selenium-75 Ci LLD LLD LLD LLD LLD carbon-14 Ci .....unidentified Ci NONE NONE NONE NONE NONE Total for period Ci ND ND ND ND ND LLD = Below the Lower Limit of Detectability, in uCi/cc (Table 4).ND = None Detected* Carbon-14 data provided in Attachment 3 from Key Solutions, Inc.I Form 1/2-ENV-01.05.FO1 (page 26 of 39), Rev 3 Beaver Valley Power Station -Unit 2 RTL # A9.690E Enclosure 2, Page 8 of 21 I U U Radioactive Effluent Release Report Calendar Year -2010 Table lC-GC2 Gaseous Effluents

-Ground Level Continuous Releases (Unit 2)3rd 4th Calendar Quarter Quarter Year LLD 2.37E-01 LLD LLD 2.37E-01 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 8.25E-02 LLD LLD 8.25E-02 U I I I LLD LLD LLD LLD LLD LLD LLD LLD NONE NONE ND 3.20E-01 I I LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD ND ND ND ND ND LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 3.13E-06 LLD LLD LLD 3.13E-06 2.34E-06 LLD LLD LLD 2.34E-06 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 I I I I i I I I unidentified Ci I NONE NONE NONE NONE NONE Totalfoperid CJ 5.47E-06 ND ND ND 5.47E-06 LLD = Below the Lower Limit of Detectability, in uCi/cc (Table 4).ND = None Detected* Carbon-14 data provided in Attachment 3 from Key Solutions, Inc. 3 Form 1/2-ENV-01.05.F01 (page 27 of 39), Rev 3 Beaver Valley Power Station -Units 1 & 2 1 Radioactive Effluent Release Report Calendar Year -2010 I Table 2A Liquid Effluents

-Summation Of All Releases RTL # A9.690E Enclosure 2, Page 9 of 21 1st 2nd 3rd 4th Calendar Total Unit Quarter Quarter Q Quarter Year A. Fission & activation products 1. Total release (excl. H-3, gas &alpha) -Ci 1.93E-02 2.68E-02 1.94E-02 4.95E-02 1.15E-01 26.1%1 2. Averagediluted concentration uCinml 2.96E-08 3.98E-08 1.03E-08 6.01 E-08 2.85E-08 3. Percent of applicable limit f 7.72E-01 1.07E+00 7.75E-01 1.98E+00 1.15E+00 B. Tritium 1. Total release..

Ci 1.02E+02 1.26E+02 5.94E+02 5.59E+02 1.38E+03 25.0%2. Average diluted concentration uCi/ml 1.56E-04 1.87E-04 3.14E-04 6.79E-04 3.42E-04 3. Percent of applicable limit % 1.56E+00 1.87E+00 3.14E+00 6.79E+00 3.42E+00 C. Dissolved and entrained gases 1.Total release Ci ND 3.47E-05 4.71 E-05 ND 8.18E-05 27.0%2. Average diluted concentration uCilml 5.14E-1 1 2.49E-11 2.02E-1 1 3. Percent of applicable limit _ %_ 2.57E-05 1.25E-05 1.01 E-05 D. Gross alpha radioactivity Ci LLD LLD LLD LLD LLD 28.9%(total release) I E. Volume of waste released liters 1.24E+06 1.39E+06 2.15E+06 1.92E+06 6.70E+06 11.2%(prior to dilution)

I I [ F. Volume of dilution water used liters 6.51E+08 6.74E+08 1.89E+09 8.21E+08 4.03E+09 22.9%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.OOE-2 uCi/ml C.3 is based on a ODCM limit of 2.OOE-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 1E+10 liters for BVPS-1 & 2 (ie.; -22,800 gpm is the total dilution flowrate from the site)

Form 1/2-ENV-01.05.FO1 (page 28 of 39), Rev 3 Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2010 Table 2B-B Liquid Effluents

-Batch Releases RTL # A9.690E Enclosure 2, Page 10 of 21 U I I iar r I I LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 3.42E-04 1.20E-03 1.54E-03 3.13E-05 5.67E-05 3.50E-05 2.48E-04 3.71 E-04 4.37E-03 1.50E-02 7.15E-03 LLD 2.65E-02 LLD LLD LLD LLD LLD 3.72E-05 LLD 7.57E-06 1.02E-04 1.47E-04 6.95E-03 1.46E-03 3.30E-03 3.17E-02 4.34E-02 1.15E-03 7.29E-04 2.93E-03 3.65E-03 8.46E-03 LLD LLD 1.83E-04 2.87E-04 4.70E-04 LLD LLD LLD LLD LLD 5.65E-05 LLD LLD LLD 5.65E-05 LLD LLD 7.59E-05 3.70E-04 4.46E-04 LLD 4.94E-03 LLD LLD 4.94E-03 LLD LLD 1.72E-06 LLD 1.72E-06 LLD LLD LLD LLD LLD 2.94E-04 2.81 E-03 2.09E-03 5.67E-04 5.76E-03 LLD LLD LLD LLD LLD 5.78E-04 LLD LLD 1.02E-03 1.60E-03 5.28E-03 1.58E-03 2.65E-03 7.97E-03 1.75E-02 LLD LLD 5.53E-06 2.27E-06 7.80E-06 LLD LLD 4.17E-06 LLD 4.17E-06 LLD LLD LLD 2.53E-05 2.53E-05 5,42E-04 2.72E-04 6.12E-04 2.36E-03 3.79E-03 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD I I I I I I I I I I!I I I I unidenifiedI C I NONE NONE NONE NONE NONE Total for pod Ci 1.93E-02 2.68E-02 1.94E-02 4.95E-02 1.15E-01 krp 5Ci LLD LLD LLD LLD LLD x, on-1......

LLD 3.47E-05 4.71E-05 LLD 8.18E-05 A CI LLD LLD LLD LLD LLD xnn1 # LLD LLD LLD LLD LLD ientifd C NONE NONE NONE NONE NONE Total r pod Ci ND 3.47E-05 4.71E-05 ND 8.18E-05 LLD = Below the Lower Limit of Detectability, in uCi/ml (Table 4)* Carbon-14 data provided in Attachment 3 from Key Solutions, Inc.

I Form 1/2-ENV-01.05.FO1 (page 29 of 39), Rev 3 Beaver Valley Power Station -Units 1 & 2 3 Radioactive Effluent Release Report Calendar Year -2010 Table 2B-C 3 Liquid Effluents

-Continuous Releases RTL # A9,690E Enclosure 2, Page 11 of 21 I Nuclides released 1st 2nd 3rd 4th I Calendar Unit Quarter Quarter Quarter Quarter Year 1. Fission and activation products beryllium-7 Ci N/A N/A N/A N/A N/A sodium-24 Ci N/A N/A N/A N/A N/A chromium-51 Ci N/A N/A N/A N/A N/A manganese-54 Ci N/A N/A N/A N/A N/A iron-55 Ci N/A N/A N/A N/A N/A iron-S9 Ci N/A N/A N/A N/A N/A cobalt-57 Ci N/A N/A N/A N/A N/A cobalt-58 Ci N/A N/A N/A N/A N/A cobalt-60 Ci N/A N/A N/A N/A N/A zinc-65 Ci N/A N/A N/A N/A N/A strontium-S9 Ci N/A N/A N/A N/A N/A strontium-9O Ci N/A N/A N/A N/A N/A zirconiumlnioblum-95 CI N/A N/A N/A N/A N/A zirconiumlniobium-97 Ci N/A N/A N/A N/A N/A molybdenum-99 Ci N/A N/A N/A N/A N/A technetium-99mn Ci N/A N/A N/A N/A N/A ruthenium-103 Ci N/A N/A N/A N/A N/A silver-110m Ci N/A N/A N/A N/A N/A antimony-124 CI N/A N/A N/A N/A N/A antimony-125 Ci N/A N/A N/A N/A N/A iodine-131 Ci N/A N/A N/A N/A NIA iodine-133 Ci N/A N/A N/A N/A N/A cesium-134 CIi N/A N/A N/A N/A N/A cesium-137 Ci N/A N/A N/A N/A N/A barium/lanthanum-140 Ci N/A N/A N/A N/A N/A cerum-141 Ci N/A N/A N/A N/A N/A cerium-144 Ci N/A N/A N/A N/A N/A unidentified

[ CI N/A N/A N/A N/A N/A Total for period I cl N/A N/A N/A N/A N/A 2. Dissolved and entrained gases argon-41 Ci N/A N/A N/A N/A N/A xenon-133 Ci N/A N/A N/A N/A N/A xenon-133m Ci N/A N/A N/A N/A N/A xenon-135 Ci N/A N/A N/A N/A N/A carbon-14 Ci N/A N/A N/A N/A N/A unidentified Ci N/A N/A N/A N/A N/A Total for period Ci N/A N/A N/A N/A N/A N/A = Not Applicable (liquids not discharged in a continuous mode during this period)

Form 1/2-ENV-01.05.FO1 (page 30 of 39), Rev 3 Beaver Valley Power Station -Units I & 2 Radioactive Effluent Release Report Calendar Year -2010 Table 3A Solid Waste And Irradiated Fuel Shipments (Part I of 3)RTL # A9.690E Enclosure 2, Page 12 of 21 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.I I Form 1/2-ENV-01.05.F01 (page 31 of 39), Rev 3 Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2010 Table 3B Solid Waste And Irradiated Fuel Shipments (Part 2 of 3)RTL # A9.690E Enclosure 2, Page 13 of 21 A. Solid Waste Shipped Offsite For Burial Or Disposal (Not irradiated fuel)1. Type of Waste (Dry Compressible Waste, Estimated Contaminated Equipment, etc.) 1st Half 2nd Half Total Error a. Volume Shipped 6.12E+01 m3 4.28E+02 m3 0.0% (1)b. Volume Buried 8.38E+01 m3 4.26E+01 m3 0.0% (1)c. Total Activity 1.22E-01 Ci I1.E-01 Ci 30.0%2. Estimate of Major Nuclide Composition bv TvDe of Waste On This Table (2)Percent (%)Percent (%)H-3 2.31 % 1.80 %C-14 1.48 % 1.04 %Mn-54 0.98 % 1.51 %Fe-55 44.60 % 29.50 %Co-58 3.42 % 1.63 %Co60 19.80 % 24.70 %Ni-59 0.38 % 0.28 %Ni-63 22.20 % 22.40 %Sr-90 0.05 % 0.01 %Nb-95 0.31 % 0.62 %Zn-65 0.55 % 6.03 %Zr-95 0.02 % 1.03 %Tc-99 0.02 % 0.00 %Ag-Ibm 0.00 % 5.64 %Sb-125 3.16 % 2.53 %Cs-137 0.45 % 0.64 %Pu-241 0.21 % 0.38 %3. Number of Shipments 1 7 a. Type LSA 1 7 of TypeA 0 0 Container Type B 0 0 Used Large Quantity 0 0 b. Solidification Cement 0 0 Agent Urea Formaldehyde 0 0 Used None 1 7 c. Mode of Truck 1 7 Transport Rail 0 0 S Other 0 0 d. Final Oak Ridge, TN 1 7 Destination Wampum, PA 0 0 e. Waste Class A 1 7 Class Class B 0 0 per Class C 0 0 10 CFR Part 61 > Class C 0 0 (1) Since container volumes are provided by the burial site, a calculational error of zero is assumed.(2) Percent values for any nuclide that are <0.01 % are not shown on this table. Data is available upon request.

Form 1/2-ENV-01.05.FO1 (page 32 of 39), Rev 3 Beaver Valley Power Station -Units I & 2 Radioactive Effluent Release Report Calendar Year -2010 Table 3C Solid Waste And Irradiated Fuel Shipments (Part 3 of 3)i RTL # A9.690E Enclosure 2, Page 14 of 21 I I I I I I U 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.I I I Form 1/2-ENV-01.05.FO1 (page 33 of 39), Rev 3 Beaver Valley Power Station -Units I & 2 Radioactive Effluent Release Report Calendar Year -2010 Table 4 Lower Limits Of Detectability (LLD)RTL # A9.690E Enclosure 2, Page 15 of 21 RWDA-G 1000 cc Gas Grab Samole Cacuatd Required Nuclide L H-3 (4) 1.00E-06 15-06 Na-24 1.48E-08 1 E-04 Ar-41 4.48E-08 15-04 Cr41 4,53E-07 16-04 Mn-54 6.90E-08 1 E-04 Fe-55 ______Pg4B 1,37E-07 1 E-04 Co-5 4.54E-08 1 E-04 Co-58 4.29E-08 1 E-04 Co-60 5,79E-08 15-04 Zn-65 1.18E-07 1 E-04 Se.-75 _. .....Kr 45 1,96E-05 1E-04 Kr-85m 5.91 E-08 1 E-04 Kr-87 1.20E-07 15-04 Kr-88 1,57E-07 1E-04 Sr-SB89---

Sr-BO __ __ _Sr-B2 7.40E-08 15-04 Nb-95 2,88E-08 1 E-04 Nb-97 5.15E-08 1 E-04 zr-9B 1.15E-07 1E-04 Mo-99 4.97E-08 1 E-04 Tc-B9j 4.84E-08 1 E-04 Ag-11rn 5.35E-08 15-04 Sb-124 7.18E-08 1 E-04 Sb-125 1.96E-07 1 E-04 1-131 5.86E-08 1 E-04 1-133 5.95E-08 1 E-04 1-136 2.15E-07 15-04 Xe-1 31m 2.31E-06 15-04 Xe-133 1.47E-07 1 E-04 Xe-133m 5.57E-07 1 E-04 Xe-135 5.54E-08 1 E-04 X.-135m 3.64E-08 15-04 X-137 1.45E-07 1 E-04 Xe-1 38 1.63E-07 1E-04 C9-134 8.34E-08 15-04 is-137 5,96E-08 15-04 Ba-1 2.80E-07 1 E-04 Ba-140 2.55E-07 1 E-04 La-140 1.76E-08 16-04 Ce-141 9.23-08 1 E-04 Co-144 2.28E-06 15-04 Gross Alpha ----RWDA-L 1000 ml Liquid Grab Sample (3) ODCM Calculated Required LLD LLD (uCiml) (uCilml)1.00E-06 1 E-05 3.60E-09 5E-07 1.09E-08 5E-07 1.17E-07 5E-07 1,68E-08 5E-07 (1) 1.00E-06 1 E-06 3.35E-08 5E-07 1.35E-08 5E-07 1.04E-08 5E-07 1.41 E-08 5E-07 2.89E-08 5E-07 4.83E-06 1 E-05 1.69E-08 I E-05 3,02E-08 1E-05 4.31 E-08 1 E-05 (1) 5.005-08 5E-08 (1) 5,00E-08 5E-08 1,80E-08 5E-07 6.99E-09 5E-07 1 r26E-08 5E-07 2.79E-08 5E-07 1.44E-08 5E-07 1.40E-08 5E-07 1.30E-08 5E-07 1.76E-08 5E-07 4.92E-08 5E-07 1.49E-08 1E-06 1.476-08 5E-07 5.25E-08 5E-07 6.50E-07 1 E-05 5.07E-08 1E-05 1.50E-07 1E-05 1.48E-08 1 E-05 8.97E-09 1E-05 3.61 E-08 1E-05 4.32E-08 1E-05 2.04E-08 5E-07 1.45E-08 5E-07 7.89E-08 5E-07 6.27E-08 5E-07 4.27E-09 5E-07 2.66E-08 5E-07 2.10E-07 5E-07 (1) 1.00E-07 1E-07 Filter Paper / Charcoal Continuous Effluent Sample (3) ODCM Calculated Required (2) LLD LLD (ucilc) (Uci/cc)2.48E-14 15-11 7.09E-13 1E-11 1.58E-14 1E-11 3.61E-14 1E-11 6.07E-14 1E-11 8.49E-14 1E-11 9.67E-14 1E-11 1.61E-13 1E-11 8.71E-14 1E-11 (1) 1.00E-13 1E-11 (1) 1.00E-14 1 E-11 8.81E-14 1E-11 6.56E-14 15-11 9.19E-14 1E-11 8.28E-14 1E-11 4.55E-14 1E-11 4.43E-14 1E-11 8,54E-14 1E-11 6.59E-14 1E-11 1.61E-13 1E-11 7,22E-14 1E-12 7.36E-14 1E-10 8.78E-14 1E-11 6.63E-14 1E-11 1.17E-13 1E-11 3.42E-13 1E-11 3.00E-13 1E-11 2.97E-14 1E-11 1,02E-13 1E-11 3375E-13 1E-11 (1) 3.51E-15 1E-11 (1) Sample analyses performed by a contractor laboratory.

(2) These LLD calculations contain a default weekly continuous sample volume of 2.85E+8 cc.values reflect a different volume (ie; 10 cuft or 2.83E+5 cc).Therefore, grab sample LLD (3) The calculated LLD's, except those denoted by (1), are from a counter/detector calibration on 07126110.Detector geometry fixtures began being phased out mid-year and were replaced with a new design that slightly Increased counting efficiency.

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 34 of 39), Rev 3 Beaver Valley Power Station -Unit I Radioactive Effluent Release Report Calendar Year -2010 Table 5A Assessment Of Radiation Doses RTL # A9.690E Enclosure 2, Page 16 of 21 F-8.78E-03 0.1756 4.68E-03 0.0936 5.26E-03 0.1052 3.91E-02 0.7820 5.78E-02 0.5782 1.24E-02 0.2480 8.61E-03 0.1722 1.21E-02 0.2420 6.20E-02 1.2400 9.51E-02 0.9511 9.06E-03 0.6040 6.38E-03 0.4253 9.49E-03 0.6327 4.33E-02 2.8867 6.82E-02 2.2743 1.92E-03 0.0384 2.43E-03 0.0486 4.77E-03 0.0954 7.40E-03 0.1480 1.65E-02 0.1652 5.42E-03 0.1084 4.43E-03 0.0886 7.30E-03 0.1460 2.62E-02 0.5240 4.34E-02 0.4335 3.12E-03 0.0624 3.24E-03 0.0648 5.58E-03 0.1116 1.33E-02 0.2660 2.52E-02 0.2524 2.93E-03 0.0586 3.01E-03 0.0602 5.61E-03 0.1122 1.28E-02 0.2560 2.44E-02 0.2435 Unit 1 Gaseou~s Effluents 1stQurte 2d Qarer 3r Qure 4th Quarte Calendar Yer Dos ODM Dse DCM Dos ODM ose O~DC Doe OC LmtLmtLfimit LiitLii 2.15E-01 4.3000 1.09E-07 0.0000 0.OOE+00 0.0000 2.89E-05 0.0006 2.15E-01 2.1503 7.57E-02 0.7570 5.15E-10 0.0000 0.OOE+00 0.0000 7.71E-05 0.0008 7.58E-02 0.3789 0.OOE+00 0.0000 0.OOE+00 0.0000 0.OOE+00 0.0000 6.50E-04 0.0087 6.50E-04 0.0043 3.96E-02 0.5280 1.75E-02 0.2333 7.21E-03 0.0961 1.66E-02 0.2213 8.09E-02 0.5394 3.96E-02 0.5280 1.75E-02 0.2333 7.21E-03 0.0961 1.64E-02 0.2187 8.07E-02 0.5381 3.96E-02 0.5280 1.75E-02 0.2333 7.21E-03 0.0961 1.63E-02 0.2173 8.06E-02 0.5374 3.96E-02 0.5280 1.75E-02 0.2333 7.21E-03 0.0961 1.64E-02 0.2187 8.07E-02 0.5381 3.96E-02 0.5280 1.75E-02 0.2333 7.21E-03 0.0961 1.67E-02 0.2227 8.1OE-02 0.5401 3.96E-02 0.5280 1.75E-02 0.2333 7.21E-03 0.0961 1.64E-02 0.2187 8.07E-02 0.5381 I I I I I I I (1) These doses are listed in mrem; they are calculated for the maximum individual for all batch liquid effluents (2) These doses are listed in mrad; they are calculated at the site boundary for batch & continuous gaseous effluents (0.4 miles NW)(3) These doses are listed in mrem; they are calculated for the most likely exposed real individual (child) via all real pathways at 0.89 miles NW.Limits used for calculation of percent (%) are from ODCM procedure 112-ODC-3.03, Attachment H Control 3.11.1.2, Attachment L Control 3.11.2.2, and Attachment M Control 3.11.2.3 (considered to be the design objectives).

Form 1/2-ENV-01.05.FO1 (page 35 of 39), Rev 3 Beaver Valley Power Station -Unit 2 Radioactive Effluent Release Report U Calendar Year -2010 Table 5B Assessment Of Radiation Doses RTL # A9.690E Enclosure 2, Page 17 of 21 Unit 2 Liquid Effluents 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Calendar Year% of % of % of % of %of Batch Dose ODCM Dose ODCM Dose ODCM Dose ODCM Dose ODCM Releases Limit Limit Limit Limit Limit Bone 8.78E-03 0.1756 4.68E-03 0.0936 5.26E-03 0.1052 3.91E-02 0.7820 5.78E-02 0.5782 0 Liver 1.24E-02 0.2480 8.61E-03 0.1722 1.21E-02 0.2420 6.20E-02 1.2400 9.51E-02 0.9511 R Total Body 9.06E-03 0.6040 6.38E-03 0.4253 9.49E-03 0.6327 4.33E-02 2.8867 6.82E-02 2.2743 G Thyroid 1.92E-03 0.0384 2.43E-03 0.0486 4.77E-03 0.0954 7.40E-03 0.1480 1.65E-02 0.1652 A Kidney 5.42E-03 0.1084 4.43E-03 0.0886 7.30E-03 0.1460 2.62E-02 0.5240 4.34E-02 0.4335 N Lung 3.12E-03 0.0624 3.24E-03 0.0648 5.58E-03 0.1116 1.33E-02 0.2660 2.52E-02 0.2524 ()Gi-LLI 2.93E-03 0.0586 3.01E-03 0.0602 5.61E-03 0.1122 1.28E-02 0.2560 2.44E-02 0.2435 Unit 2 Gaseous Effluents 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Calendar Year Batch & %of %of %of %of %of Continuous Dose ODCM Dose ODCM Dose ODCM Dose ODCM Dose ODCM Releases Limit Limit Limit Limit Limit I2 Gamma Air 3.OOE-07 0.0000 1.09E-07 0.0000 2.02E-02 0.4040 2.95E-06 0.0001 2.02E-02 0.2020 (2) Be Air 1.41E-09 0.0000 5.15E-10 0.0000 8.39E-03 0.0839 1.40E-08 0.0000 8.39E-03 0.0420 Bone 9.85E-05 0.0013 0.OOE+00 0.0000 1.30E-12 0.0000 3.76E-06 0.0001 1.02E-04 0.0007 0 Liver 9.81E-03 0.1308 3.63E-04 0.0048 2.73E-04 0.0036 3.88E-04 0.0052 1.08E-02 0.0722 R Total Bod 9.81 E-03 0.1308 3.63E-04 0.0048 2.73E-04 0.0036 3.86E-04 0.0051 1.08E-02 0.0722 G Thyroid 9.81E-03 0.1308 3.63E-04 0.0048 2.73E-04 0.0036 3.86E-04 0.0051 1.08E-02 0.0722 A Kidne 9.81E-03 0.1308 3.63E-04 0.0048 2.73E-04 0.0036 3.86E-04 0.0051 1.08E-02 0.0722 N 9.88E-03 0.1317 3.63E-04 0.0048 2.73E-04 0.0036 3.86E-04 0.0051 1.09E-02 0.0727 3 GI-ILI 9.82E-03 0.1309 3.63E-04 0.0048 2.73E-04 0.0036 3.86E-04 0.0051 1.08E-02 0.0723 (1) These doses are listed in mrem; they are calculated for the maximum individual for all batch liquid effluents (2) These doses are listed in mrad; they are calculated at the site boundary for batch & continuous gaseous effluents (0.4 miles NW)(3) These doses are listed in mrem; they are calculated for the most likely exposed real individual (child) via all real pathways at 0.89 miles NW.Limits used for calculation of percent (%) are from ODCM procedure 1/2-ODC-3.03, Attachment H Control 3.11.1.2, Attachment L Control 3.11.2.2, and Attachment M Control 3.11.2.3 (considered to be the design objectives).

Form 1/2-ENV-01.05.FO1 (page 36 of 39), Rev 3 Beaver Valley Power Station -Units I & 2 Radioactive Effluent Release Report Calendar Year -2010 Table 6 RTL # A9.690E Enclosure 2, Page 18 of 21 Effluent Mlonitoring Instrumentation Channels Not Returned To Operable Status Withiln 30 Days[RM-1DA-1001

-Unit 1 Auxiliary Feed Pump Bay Drain Monitor On 06/09/10, this monitor was removed from service for performance of scheduled maintenance.

During calibration, it was determined that the sample pump would need to be replaced.

However, replacement parts were not immediately available and the monitor was out of service for greater than 30 days. The monitor was returned to operable status on 01/28/11.

This condition is identified in BVPS Condition Report No. CR 10-79472 and was tracked via BVPS-SAP Order 200404972-0060.

As required by ODCM procedure 1/2-ODC-3.03, "Controls for RETS and REMP Programs", (as referenced in procedure Attachment E, Control 3.3.3.9, Table 3.3-12, Action 24), effluent releases via this pathway may continue provided grab samples are analyzed once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.However, SINCE this liquid effluent pathway was diverted to the Tunnel Sump / Liquid Radwaste Treatment System on 06/09/10 (and remained diverted until the monitor was returned to operable status on 01/28/11), THEN there were no liquid releases through this effluent pathway.Therefore, grab sampling was not required.[FR-VS-1011

-Ventilation Vent Header Flow Recorder and [RM-AVS-1091 Ch-10 -Unit 1 Auxiliary Building Ventilation Exhauste Monitor Flow Device On 09/11/10 these flow devices were removed from service during routine maintenance because of the probe not working as expected.

The current probe design for FR-VS-1 01 is obsolete and replacement parts are not expected to be available until 05/31/11, therefore this instrumentation remains out of service for greater than 30 days. This condition is documented in BVPS Condition Report No. CR 10-80322 and SAP Notification 600639358/Order 200425622, and was tracked via SAP Order 200404972-0120.

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 28A), effluent releases via this pathway may continue provided that the system/process flow rate is estimate at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or assumed to be at the ODCM design value. Unit 1 Ventilation Vent flow rate has been assumed at the design value of 62,000 cfm.I I I I I I I Form 1/2-ENV-01.05.FO1 (page 37 of 39), Rev 3 Beaver Valley Power Station -Units 1 & 2 RTL # A9ý690E Enclosure 2, Page 19 of 21 Radioactive Effluent Release Report Calendar Year -2010 Table 7 Total Dose Commitments, Total Effective Dose Equivalents and Population Doses Total Dose Commitment From All Facility Releases To Members of the Public 40 CFR 190.10(a)

Environmental Doses (1) (2) % of ODCM or Organ Effluent Dose Direct Radiation Dose Total Dose 40 CFR 190 Limit (mrem) (mrem) (mrem)Bone 1.16E-01 0.OOE+00 1.16E-01 0.46%Liver 2.82E-01 O.OOE+00 2.82E-01 1.13%Total Body 4.63E-01 0.OOE+00 4.63E-01 1.85%Thyroid 1.24E-01 O.OOE+00 1.24E-01 0.17%Kidney 1.78E-01 0.00E+00 1.78E-01 0.71%Lung 1.42E-01 0.00E+00 1.42E-01 0.57%GI-LLI 1.40E-01 0.OOE+00 1.40E-01 0.56%(1) The cumulative dose contributions from liquid and gaseous effluents were determined in accordance with the applicable CONTROLS & SURVEILLANCE REQUIREMENTS listed in ODCM procedure 1l2-ODC-3.03.

The dose commitment limits for 40 CFR 190 MEMBERS OF THE PUBLIC (ODCM 112-ODC-3.03 Control 3.11.4.1) are as follows: a) < or 25 mrem / calendar year (for the total body, or any organ except the thyroid)b) < or = 75 mrem / calendar year (for the thyroid)(2) The dose contribution listed for the total body is for Direct Radiation.

This was calculated by comparing offsite TLD exposure at the 00CM controlling location (0.8 miles NW; Midland-, PA) to TLD exposure at the REMP control location (16.5 miles SSW; Weirton, WV).I Compliance to 100 mrem Limit of 10 CFR 20.1301 For Total Effective Dose Equivalent I Pursuant to 10 CFR 20.1301 (a)(1), the Total Effective Dose Equivalent from licensed operation to the maximum individual during the report period, is 3.35 mrem. This is a summation of Direct Radiation Exposure (calculated by comparing the maximum of all perimeter TLD exposures to TLD exposure at the REMP control location) plus Effluent Doses (calculated per the ODCM).Members of the Public Doses Due To Their Activities Inside The Site Boundary The radiation doses for MEMBER(S)

OF THE PUBLIC due to their activities inside the site boundary are not greater than the doses listed in this table to show compliance with 40 CFR Part 190 or 10 CFR 20.1301. Evaluations have shown that exposure time for individuals not occupationally associated with the plant site is minimal in comparison to the exposure time considered for the dose calculation at or beyond the site boundary.

Therefore, a separate assessment of radiation doses from radioactive effluents to MEMBER(S)

OF THE PUBLIC, due to their activities inside the site boundary, is not necessary for this report period.'05ý0 Mile Population Doses From Liquid and Gaseous Effluents 0-50 mile Total Population Dose from liquid and gaseous effluents

= 476 man-mrem (Total Body)0-50 mile Average Population Dose from liquid and gaseous effluents

= 0.0001190 man-mrem (Total Body)

Form 1/2-ENV-01.05.FO1 (page 38 of 39), Rev 3 RTL # A9.690E Beaver Valley Power Station -Units 1 & 2 Enclosure 2, Page 20 of 21 Radioactive Effluent Release Report Calendar Year -2010 Table 8 Ofst Dos Calcultio Mnal Su~rveillance Deficiencies Inability to Include a Filter Paper as Part of the Monthly Composite Particulate Sample The weekly particulate filter paper samples for 06/01, 06/02, 06/08, and 06/11/10 for the U2 Decon Building were unable to be located for inclusion in the monthly composite analysis.The Decon Building is monitored as required by OCDM procedure 1/2-ODC-3.03 as a I potential effluent pathway when the Roll-Up Door is opened for worker activities.

The particulate filter paper samples from this area are included in the monthly composite analysis for Gross Alpha and Sr-89 and Sr-90. Analysis data was available for 1-133,1-131 and principle gamma emitters.

This condition and associated Corrective Actions are detailed in BVPS Condition Report No. CR 10-78575.I ODCM procedure 1/2-ODC-3.03, "Controls for RETS and REMP Programs", (as referenced in procedure Attachment K, Control 3.11.2.1, Table 4.11-2), requires a monthly composite for I Gross Alpha, Sr-89 and Sr-90. Activity was estimated at Lower Levels of Detection for this release pathway based on the work that occurred in the facility during the time period the sample was collected.

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

No Licensed Radioactive Material or activity from Sr-89 or Sr-90 was detected for the weeks prior to and after the time periods of the missing particulate filter paper samples. I I I I I I I I I Form 112-ENV-01.05.F01 (page 39 of 39), Rev 3 RTL # A9.690E Beaver Valley Power Station -Units 1 & 2 Enclosure 2, Page 21 of 21 Radioactive Effluent Release Report Calendar Year -2010 Table 9 Unit 1 and 2 Offsite Dose Calculation Manual Changes (Description)

There were two changes made to the Unit 1 and 2 Offsite Dose Calculation Manual during this report period.Change 27 to the ODCM in August 2010 added the revision history to capture Changes 25 and 26, removed the requirement for PORC review and acceptance of changes made to the ODCM, removed references to retired NPDES Outfalls, incorporated setpoints for detector upgrades to RM-1 DA-1 00, added the Coolant Recovery Tanks [1BR-TK-4A/B]

as Liquid Waste Discharge Tanks, corrected REMP sampling designations, clarified alternates for use with Action 25A for cooling tower blowdown flow rate measuring devices, and updated procedure references throughout the document.Change 28 to the ODCM in December 2010 removed references to the CTS and ITS conversion project and removed the description that batch releases of liquid waste are processed by recirculation through eductors.

This change also deleted Attachment B which referenced minimum liquid waste batch release recirculation times and added a description that liquid waste recirculation times to achieve two tank volumes are calculated based upon actual tank volume and pump capacity.

Enclosure 2, Attachment 1

RTL # A9.690E Enclosure 2, Attachment 1 Beaver Valley Power Station -Units I & 2 Radioactive Effluent Release Report Calendar Year -2010 Attachment I Joint Frequency Distribution Tables Attachment 1 As specified in the ODCM, an annual summary of hourly meteorological data (in the form of joint frequency distribution) is provided for the calendar year.Meteorological Data Recovery 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 96.6% = Wind Speed 35'99.1% = Wind Speed 150'98.5% = Wind Speed 500'99.6% = Wind Direction 35'99.4% = Wind Direction 150'99.0% = Wind Direction 500'99.6% = Delta Temperature (150' -35') 1 P 99.6% = Delta Temperature (500' -35' ) 2P 99.6% = Temperature 35'99.6% = Precipitation 99.4% Average Recovery of Individual Meteorological Parameters PERCENT RECOVERY OF COMPOSITE VARIABLES 99.6% = Wind Speed 35', Wind Direction 35', Delta Temperature 1 P 98.8% = Wind Speed 150', Wind Direction 150', Delta Temperature 1 P 97.8% = Wind Speed 500', Wind Direction 500', Delta Temperature 2P 99.3% = Average Recovery of Composite Variables Attachment i Clarification 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. Lara Renz at 724-682-4255.

RTL A9.690E Enclosure 2, Attachment 1 (Part 1 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2010 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= 1/1/2010 00:00 -12/31/2010 23:00 Elevation:

Speed: SP35P Direction:

D135P Lapse: DT150-35 Stability Class A Delta Temperature Extremely Unstable Wind Speed (mph)Wind Direction 1-4 4-8 8-13 13-19 19-25 > 25 Total N 22 40 0 0 0 0 62 NNE 19 25 1 0 0 0 45 NE 18 9 0 0 0 0 27 ENE 27 20 0 0 0 0 47 E 15 20 0 0 0. 0 35 ESE 14 9 0 0 0 0 23 SE 16 3 0 0 0 0 19 SSE 4 4 0 0 0 0 8 S 6 12 1 0 0 0 19 SSW 6 32 3 0 0 0 41 SW 14 44 30 2 0 0 90 WSW 6 81 35 0 0 0 122 W 9 162 25 0 0 0 196 WNW 25 110 6 0 0 0 141 NW 18 69 4 0 0 0 91 NNW 24 43 1 0 0 0 68 Total 243 683 106 2 0 0 1034 Calm Hours not Included above for: Total Period 65 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 34 Valid Hours for this Stability Class for: Total Period 1034 Total Hours for Period 8760 RTL A9.690E Enclosure 2, Attachment 1 (Part 1 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2010 Attaclunent I Part 1: Joint Frequency Distribution Tables (35ft)Page 2 of 8 Hours at Each Wind Speed and Direction Total Period Period of Record= 1/1/2010 00:00 -12/31/2010 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 8 6 0 0 0 0 14 NNE 3 5 0 0 0 0 8 NE 9 1 0 0 0 0 10 ENE 9 2 0 0 0 0 11 E 1 2 0 0 0 0 3 ESE 4 0 0 0 0 0 4 SE 0 0 0 0 0 0 0 SSE 2 0 0 0 0 0 2 S 2 1 0 0 0 0 3 SSW 2 1 1 0 0 0 4 SW 2 20 11 0 0 0 33 WSW 4 15 5 0 0 0 24 W 5 29 7 0 0 0 41 WNW 8 13 0 0 0 0 21 NW 7 9 0 0 0 0 16 NNW 10 9 0 0 0 0 19 Total 76 113 24 0 0 0 213 Calm Hours not Included above for: Total Period 65 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 34 Valid Hours for this Stability Class for: Total Period 213 Total Hours for Period 8760 RTL A9.690E Enclosure 2, Attachment 1 (Part I of 3)Beaver Valley Power Station -Units I & 2 Radioactive Effluent Release Report Calendar Year -2010 Attachment 1 I I I I I Part 1: Joint Frequency Distribution Tables (35ft)Page 3 of 8 Hours at Each Wind Speed and Direction Total Period Period of Record =Elevation:

Speed: Stability Class C SP35P 1/1/2010 00:00 -12/31/2010 23:00 Direction:

D135P Lapse: Delta Temperature Slightly Unstable DT150-35 I Wind Speed (mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW 1-4 7 4 5 7 4 3 1 0 1 4 4 5 7 4 8 3 4-8 10 2 4 2 1 2 1 2 1 2 12 31 38 18 8 14 8- 13 0 0 0 0 0 0 0 0 1 0 9 14 15 0 3 1 13-19 19-25 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0> 25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Total 17 6 9 9 5 5 2 2 3 6 26 50 60 22 19 18 Total 67 148 43 1 0 0 259 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 65 0 34 259 8760 I I I I I I I I I RTL A9.690E Enclosure 2, Attachment 1 (Part 1 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2010 Attachment 1 Part 1: Joint Frequency Distribution Tables (35ft)Page 4 of 8 Hours at Each Wind Speed and Direction Total Period Period of Record= 1/1/2010 00:00 -12/31/2010 23:00 Elevation:

Speed: SP35P Direction:

D135P Lapse: DT150-35 Stability Class D Delta Temperature Neutral Wind Speed (mph)Wind Direction 1-4 4-8 8-13 13-19 19-25 > 25 Total N 62 52 0 0 0 0 114 NNE 70 15 0 0 0 0 85 NE 65 8 0 0 0 0 73 ENE 68 31 0 0 0 0 99 E 56 18 2 0 0 0 76 ESE 33 0 0 0 0 0 33 SE 20 0 0 0 0 0 20 SSE 24 1 0 0 0 0 25 S 26 10 3 0 0 0 39 SSW 44 26 3 0 0 0 73 SW 67 148 77 4 0 0 296 WSW 92 235 100 12 0 0 439 W 102 447 127 0 0 0 676 WNW 122 220 23 0 0 0 365 NW 134 142 3 0 0 0 279 NNW 82 101 3 0 0 0 186 Total 1067 1454 341 16 0 0 2878 Calm Hours not Included above for: Total Period 65 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 34 Valid Hours for this Stability Class for: Total Period 2878 Total Hours for Period 8760 RTL A9.690E i Enclosure 2, Attachment 1 (Part 1 of 3)Beaver Valley Power Station -Units I & 2 i Radioactive Effluent Release Report Calendar Year -2010 Attachment 1 Part 1: Joint Frequency Distribution Tables (35ft)Page 5 of 8 l Hours at Each Wind Speed and Direction Total Period Period of Record= 1/1/2010 00:00 -12/31/2010 23:00 Elevation:

Speed: SP35P Direction:

D135P Lapse: DT150-35 I Stability Class E Delta Temperature Slightly Stable Wind Speed (mph)1 Wind Direction 1-4 4-8 8-13 13-19 19-25 > 25 Total N 69 27 0 0 0 0 96 NNE 61 10 0 0 0 0 71 NE 133 17 0 0 0 0 150 ENE 147 98 1 0 .0 0 246 E 114 26 1 0 0 0 141 ESE 96 2 0 0 0 0 98 SE 98 0 0 0 0 0 98 SSE 90 3 0 0 0 0 93 S 143 17 0 0 0 0 160 l SSW 154 47 3 0 0 0 204 SW 109 75 15 1 0 0 200 WSW 82 75 20 1 0 0 178 W 58 102 10 0 0 0 170 WNW 76 38 0 0 0 0 114 NW 94 24 0 0 0 0 118 NNW 87 14 0 0 0 0 101 Total 1611 575 50 2 0 0 2238 Calm Hours not Included above for: Total Period 65 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 34 Valid Hours for this Stability Class for: Total Period 2238 Total Hours for Period 8760 RTL A9.690E Enclosure 2, Attachment 1 (Part 1 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2010 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= 1/1/2010 00:00 -12/31/2010 23:00 Elevation:

Speed: SP35P Direction:

D135P Lapse: DT150-35 Stability Class F Delta Temperature Moderately Stable Wind Speed (mph)Wind Direction 1-4 4-8 8-13 13-19 19-25 >25 Total N 14 1 0 0 0 0 15 NNE 21 2 0 0 0 0 23 NE 37 0 0 0 0 0 37 ENE 42 3 0 0 0 0 45 E 85 2 0 0 0 0 87 ESE 182 2 0 0 0 0 184 SE 279 1 0 0 0 0 280 SSE 164 0 0 0 0 0 164 S 174 9 0 0 0 0 183 SSW 95 12 2 0 0 0 109 SW 47 12 2 0 0 0 61 WSW 16 12 5 0 0 0 33 W 8 2 3 0 0 0 13 WNW 15 3 0 0 0 0 18 NW 8 0 0 0 0 0 8 NNW 11 0 0 0 0 0 11 Total 1198 61 12 0 0 0 1271 Calm Hours not Included above for: Total Period 65 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 34 Valid Hours for this Stability Class for: Total Period 1271 Total Hours for Period 8760 RTL A9.690E Enclosure 2, Attachment 1 (Part 1 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2010 Attachment 1 Part 1: Joint Frequency Distribution Tables (35ft)Page 7 of 8 Period of Record =Elevation:

Speed: Stability Class G Hours at Each Wind Speed and Direction Total Period 1/1/2010 00:00 -12/31/2010 23:00 Direction:

D135P Lapse: DT150-35 Delta Temperature Extremely Stable Wind Speed-(mph)

SP35P Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Total 1-4 3 7 14 28 40 135 228 155 77 32 18 2 5 6 7 2 759 4-8 0 0 0 0 0 0 0 0 1 5 3 0 0 0 0 0 8-13 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 13-19 19-25 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> 25 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Total 3 7 14 28 40 135 228 155 78 37 21 2 5 6 7 2 I I I I I I I I I I I I I I I 9 0 0 0 0 768 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 65 0 34 768 8760 RTL A9.690E Enclosure 2, Attachment 1 (Part 1 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2010 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= 1/1/2010 00:00 -12/31/2010 23:00 Elevation:

Speed: SP35P Direction:

D135P Lapse: DT150-35 Delta Temperature Wind Speed (mph)Wind Direction 1-4 4-8 8-13 13-19 19-25 > 25 Total N 185 136 0 0 0 0 321 NNE 185 59 1. 0 0 0 245 NE 281 39 0 0 0 0 320 ENE 328 156 1 0 0 0 485 E 315 69 3 0 0 0 387 ESE 467 15 0 0 0 0 482 SE 642 5 0 0 0 0 647 SSE 439 10 0 0 0 0 449 S 429 51 5 0 0 0 485 SSW 337 125 12 0 0 0 474 SW 261 314 144 8 0 0 727 WSW 207 449 179 13 0 0 848 W 194 780 187 0 0 0 1161 WNW 256 402 29 0 0 0 687 NW 276 252 10 0 0 0 538 NNW 219 181 5 0 0 0 405 Total 5021 3043 576 21 0 0 8661 Calm Hours not Included above for: Total Period 65 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 34 Valid Hours for this Stability Class for: Total Period 8661 Total Hours for Period 8760 RTL A9.690E Enclosure 2, Attachment 1 (Part 2 of 3)Beaver Valley Power Station -Units 1 & 2 E Radioactive Effluent Release Report Calendar Year -2010 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 1/1/2010 00:00 -12/31/2010 23:00 Elevation:

Speed: SP150P Direction:

DI150P Lapse: DT150-35 Stability Class A Delta Temperature Extremely Unstable Wind Speed (mph)Wind Direction 1-4 4-8 8-13 13-19 19-25 > 25 Total N 3 39 32 1 0 0 75 NNE 2 25 16 2 0 0 45 NE 5 10 2 0 0 0 17 ENE 2 25 15 0 0 0 42 E 1 32 18 0 0 0 51 ESE 0 15 10 1 0 0 26 SE 0 14 9 0 0 0 23 SSE 0 9 5 0 0 0 14 S 0 14 16 2 0 0 32 SSW 1 11 15 3 1 0 31 SW 5 9 34 16 0 0 64 WSW 6 17 53 14 1 0 91 W 1 59 95 33 1 0 189 WNW 2 56 87 34 2 0 181 NW 7 30 30 3 0 0 70 NNW 7 37 22 0 0 0 66 Total 42 402 459 109 5 0 1017 Calm Hours not Included above for: Total Period 4 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 108 Valid Hours for this Stability Class for: Total Period 1017 Total Hours for Period 8760 RTL A9.690E Enclosure 2, Attachment 1 (Part 2 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2010 Attachment 1 Part 2: Joint Frequency Distribution Tables (150ft)Page 2 of 8 Hours at Each Wind Speed and Direction Total Period Period of Record 1/1/2010 00:00 -12/31/2010 23:00 Elevation:

Speed: SP150P Direction:

DI150P Lapse: DT150-35 Stability Class B Delta Temperature Moderately Unstable Wind Speed (mph)Wind Direction 1-4 4-8 8-13 13-19 19-25 > 25 Total N 2 13 5 0 0 0 20 NNE 2 4 4 0 0 0 10 NE 1 6 0 0 0 0 7 ENE 0 6 2 0 0 0 8 E 0 5 3 0 0 0 8 ESE 0 4 0 0 0 0 4 SE 1 2 0 0 0 0 3 SSE 1 1 0 0 0 0 2 S 0 1 0 0 0 0 1 SSW 0 4 1 2 0 0 7 SW 3 4 17 1 0 0 25 WSW 1 4 11 2 0 0 18 W 4 14 16 9 0 0 43 WNW 2 13 12 4 0 0 31 NW 2 6 2 0 0 0 10 NNW 2 5 7 0 0 0 14 Total 21 92 80 18 0 0 211 Calm Hours not Included above for: Total Period 4 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 108 Valid Hours for this Stability Class for: Total Period 211 Total Hours for Period 8760 RTL A9.690E Enclosure 2, Attachment 1 (Part 2 of 3)Beaver Valley Power Station -Units 1 & 2 i Radioactive Effluent Release Report Calendar Year -2010 Attachment 1 Part 2: Joint Frequency Distribution Tables (15Oft)Page 3 of 8 Hours at Each Wind Speed and Direction Total Period Period of Record= 1/1/2010 00:00 -12/31/2010 23:00 Elevation:

Speed: SP150P Direction:

DI150P Lapse: DT150-35 Stability Class C Delta Temperature Slightly Unstable Wind Speed (mph) 3 Wind Direction 1-4 4-8 8-13 13-19 19-25 > 25 Total N 2 10 4 0 0 0 16 NNE 3 1 2 0 0 0 6 I NE 1 6 1 0 0 0 8 ENE 2 3 3 0 0 0 8 E 1 5 0 0 0 0 6 ESE 0 2 1 2 0 0 5i SE 0 2 1 0 0 0 3 SSE 0 1 3 0 0 0 4 S 1 0 1 1 0 0 3 SSW 1 1 0 1 0 0 3 SW 2 3 7 3 1 0 16 WSW 2 9 25 5 0 0 41 W 2 18 27 20 0 0 67 WNW 3 9 19 6 0 0 37 NW 0 6 6 1 0 0 13 NNW 3 9 9 0 0 0 21 Total 23 85 109 39 1 0 257 Calm Hours not Included above for: Total Period 4 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 108 Valid Hours for this Stability Class for: Total Period 257 Total Hours for Period 8760 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 -2010 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 1/1/2010 00:00 -12/31/2010 23:00 Elevation:

Speed: SPI50P Direction:

DI150P Lapse: DT150-35 Stability Class D Delta Temperature Neutral Wind Speed (mph)Wind Direction 1-4 4-8 8-13 13-19 19-25 > 25 Total N 22 65 38 2 0 0 127 NNE 35 43 13 1 0 0 92 NE 24 33 4 1 0 0 62 ENE 21 73 27 1 0 0 122 E 15 40 12 2 0 0 69 ESE 11 13 3 0 0 0 27 SE 10 12 2 0 0 0 24 SSE 10 8 1 0 0 0 19 S 8 18 11 4 0 0 41 SSW 12 26 21 2 0 0 61 SW 35 38 93 25 1 0 192 WSW 39 98 126 42 4 1 310 W

  • 45 152 409 244 19 3 872 WNW 27 195 198 56 1 1 478 NW 35 121 56 2 0 0 214 NNW 30 82 43 2 0 0 157 Total 379 1017 1057 384 25 5 2867 Calm Hours not Included above for: Total Period 4 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 108 Valid Hours for this Stability Class for: Total Period 2867 Total Hours for Period 8760 RTL A9.690E I Enclosure 2, Attachment 1 (Part 2 of 3)Beaver Valley Power Station -Units 1 & 2 1 Radioactive Effluent Release Report Calendar Year -2010 Attachment 1 Part 2: Joint Frequency Distribution Tables (150ft)Page 5 of 8 I Hours at Each Wind Speed and Direction Total Period I Period of Record= 1/1/2010 00:00 -12/31/2010 23:00 Elevation:

Speed: SP150P Direction:

DI150P Lapse: DT150-35 Stability Class E Delta Temperature Slightly Stable I Wind Speed (mph)Wind Direction 1-4 4-8 8-13 13-19 19-25 > 25 Total I N 40 38 23 1 0 0 102 NNE 79 31 12 1 0 0 123 NE 83 57 6 2 0 0 148 I ENE 56 156 83 5 0 0 300 E 38 83 24 6 0 0 151 ESE 18 22 3 0 0 0 43 SE 17 19 4 0 0 0 40 SSE 22 18 3 2 0 0. 45 S 30 21 18 6 0 0 75 SSW 45 58 22 1 0 0 126 I SW 76 75 41 7 1 0 200 WSW 67 107 37 12 1 0 224 W 37 104 100 28 5 0 274 WNW 27 122 57 11 0 0 217 NW 21 66 9 0 0 0 96 NNW 29 45 2 0 0 0 76 Total 685 1022 444 82 7 0 2240 Calm Hours not Included above for: Total Period 4 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 108 Valid Hours for this Stability Class for: Total Period 2240 Total Hours for Period 8760 RTL A9.690E Enclosure 2, Attachment 1 (Part 2 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2010 Attachment 1 Part 2: Joint Frequency Distribution Tables (150ft)Page 6 of 8 Hours at Each Wind Speed and Direction Total Period Period of Record= 1/1/2010 00:00 -12/31/2010 23:00 Elevation:

Speed: SPI50P Direction:

DII50P 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 82 7 1 0 0 0 90 NNE 138 27 0 0 0 0 165 NE 117 52 2 0 0 0 171 ENE 50 40 4 0 0 0 94 E 16 12 2 0 0 0 30 ESE 10 8 0 0 0 0 18 SE 13 9 3 0 0 0 25 SSE 9 7 1 0 0 0 17 S 31 17 9 0 0 0 57 SSW 62 52 3 1 0 0 118 SW 119 46 12 1 0 0 178 WSW 60 75 6 4 0 0 145 W 28 32 8 5 1 0 74 WNW 18 23 4 3 0 0 48 NW 15 11 1 0 0 0 27 NNW 23 15 0 0 0 0 38 Total 791 433 56 14 1 0 1295 Calm Hours not Included above for : Total Period 4 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 108 Valid Hours for this Stability Class for: Total Period 1295 Total Hours for Period 8760 I RTL A9.690E Enclosure 2, Attachment 1 (Part 2 of 3) 1 Beaver Valley Power Station -Units 1 & 2 E Radioactive Effluent Release Report Calendar Year -2010 3 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 1/1/2010 00:00 -12/31/2010 23:00 Elevation:

Speed: SP150P Direction:

DI150P Lapse: DT150-35 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 38 5 0 0 0 0 43 NNE 67 18 0 0 0 0 85 NE 77 38 0 0 0 0 115 ENE 23 22 0 0 0 0 45 E 15 4 0 0 0 0 19 ESE 7 4 0 0 0 0 11 SE 7 3 0 0 0 0 10 SSE 9 11 2 0 0 0 22 S 11 29 11 0 0 0 51 SSW 53 40 0 0 0 0 93 SW 87 38 5 0 0 0 130 WSW 41 21 5 0 0 0 67 I W 19 6 0 0 0 0 25 WNW 9 5 0 0 0 0 14 NW 10 1 0 0 0 0 11 NNW 18 2 0 0 0 0 20 Total 491 247 23 0 0 0 761 Calm Hours not Included above for : Total Period 4 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 108 Valid Hours for this Stability Class for: Total Period 761 Total Hours for Period 8760 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 -2010 Attachment I Part 2: Joint Frequency Distribution Tables (1 50ft)Page 8 of 8 Hours at Each Wind Speed and Direction Summary of All Stability Classes Total Period Period of Record= 1/1/2010 00:00 -12/31/2010 23:00 Elevation:

Speed: SP150P Direction:

DI150P Lapse: DT150-35 Delta Temperature Wind Speed (mph)Wind Direction 1-4 4-8 8-13 13-19 19-25 >25 Total N 189 177 103 4 0 0 473 NNE 326 149 47 4 0 0 526 NE 308 202 15 3 0 0 528 ENE 154 325 134 6 0 0 619 E 86 181 59 8 0 0 334 ESE 46 68 17 3 0 0 134 SE 48 61 19 0 0 0 128 SSE 51 55 15 2 0 0 123 S 81 100 66 13 0 0 260 SSW 174 192 62 10 1 0 439 SW 327 213 209 53 3 0 805 WSW 216 331 263 79 6 1 896 W 136 385 655 339 26 3 1544 WNW 88 423 377 114 3 1 1006 NW 90 241 104 6 0 0 441 NNW 112 195 83 2 0 0 392 Total 2432 3298 2228 646 39 5 8648 Calm Hours not Included above for : Total Period 4 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 108 Valid Hours for this Stability Class for: Total Period 8648 Total Hours for Period 8760 RTL A9.690E Enclosure 2, Attachment 1 (Part 3 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2010 Attachment 1 Part 3: Joint Frequency Distribution Tables (500ft)Page 1 of 8 I Hours at Each Wind Speed and Direction Total Period Period of Record 1/1/2010 00:00 -12/31/2010 23:00 Elevation:

Speed: SP500P Direction:

DI500P Lapse: DT500-35 I Stability Class A Delta Temperature Extremely Unstable Wind Speed (mph)Wind Direction 1-4 4-8 8-13 13-19 19-25 > 25 Total N 0 3 1 0 0 0 4 NNE 0 2 2 0 0 0 4 NE 0 1 0 0 0 0 1 ENE 2 0 2 0 0 0 4 E 0 3 0 0 0 0 3 ESE 0 3 3 0 0 0 6 SE 0 3 1 0 0 0 4 SSE 0 2 0 0 0 0 2 S 0 2 1 0 0 0 3 SSW 0 1 1 1 0 0 3 SW 0 2 0 0 0 0 2 WSW 0 1 4 0 0 0 5 W 0 0 6 0 0 0 6 WNW 0 1 3 4 1 0 9 NW 0 1 1 0 0 0 2 NNW 0 1 0 2 0 0 3 Total 2 26 25 7 1 0 61 Calm Hours not Included above for : Total Period 6 3 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 174 Valid Hours for this Stability Class for: Total Period 61 Total Hours for Period 8760 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 -2010 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 1/1/2010 00:00 -12/31/2010 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 1 5 13 2 0 0 21 NNE 0 0 2 0 0 0 2 NE 0 3 1 0 0 0 4 ENE 1 2 9 0 0 0 12 E 1 7 5 0 0 0 13 ESE 0 2 8 3 0 0 13 SE 0 1 3 1 0 0 5 SSE 0 2 3 1 0 0 6 S 0 1 7 2 0 0 10 SSW 0 4 1 1 0 0 6 SW 1 1 3 1 2 0 8 WSW 0 1 8 6 0 0 15 W 0 7 6 4 1 0 18 WNW 0 3 14 6 3 0 26 NW 0 4 6 2 0 0 12 NNW 0 6 5 1 0 0 12 Total 4 49 94 30 6 0 183 Calm Hours not Included above for: Total Period 6 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 174 Valid Hours for this Stability Class for: Total Period 183 Total Hours for Period 8760 RTL A9.690E i Enclosure 2, Attachment 1 (Part 3 of 3)Beaver Valley Power Station -Units 1 & 2 1 Radioactive Effluent Release Report Calendar Year -2010 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= 1/1/2010 00:00 -12/31/2010 23:00 Elevation:

Speed: SP500P Direction:

DI500P Lapse: DT500-35 Stability Class C Delta Temperature Slightly Unstable Wind Speed (mph)Wind Direction 1-4 4-8 8-13 13-19 19-25 > 25 Total N 2 13 17 5 0 0 37 NNE 1 3 4 0 0 0 8 1 NE 0 3 1 0 0 0 4 ENE 0 5 6 0 0 0 11 E 2 4 2 2 0 0 10 ESE 0 8 5 0 0 0 13 SE 0 3 2 0 0 0 5 SSE 0 2 2 0 0 0 4 S 3 1 4 0 0 0 8 SSW 0 1 10 6 0 0 17 SW 2 1 19 8 4 0 34 WSW 1 7 20 11 1 0 40 W 2 6 28 18 8 1 63 WNW 1 11 27 18 4 1 62 NW 0 4 11 5 1 0 21 NNW 0 4 16 5 0 0 25 Total 14 76 174 78 18 2 362 Calm Hours not Included above for: Total Period 6 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 174 Valid Hours for this Stability Class for: Total Period 362 Total Hours for Period 8760 I RTL A9.690E Enclosure 2, Attachment I (Part 3 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2010 Attachment I Part 3: Joint Frequency Distribution Tables (500ft)Page 4 of 8 Hours at Each Wind Speed and Direction Total Period Period of Record- 1/1/2010 00:00 -12/31/2010 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 17 48 115 41 2 0 223 NNE 24 39 30 18 3 0 114 NE 18 39 8 10 3 0 78 ENE 24 47 87 29 2 0 189 E 24 58 85 31 6 0 204 ESE 14 30 60 33 3 0 140 SE 10 28 26 11 2 0 77 SSE 11 14 11 5 0 1 42 S 10 12 31 16 4 1 74 SSW 8 11 35 39 13 2 108 SW 21 21 73 155 46 6 322 WSW 20 58 158 185 44 6 471 W 28 80 270 437 193 20 1028 WNW 28 82 344 231 73 6 764 NW 11 70 167 58 5 0 311 NNW 8 63 164 39 2 0 276 Total 276 700 1664 1338 401 42 4421 Calm Hours not Included above for: Total Period 6 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 174 Valid Hours for this Stability Class for: Total Period 4421 Total Hours for Period 8760 RTL A9.690E Enclosure 2, Attachment 1 (Part 3 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2010 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 1/1/2010 00:00 -12/31/2010 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 1-4 4-8 8-13 13-19 19-25 > 25 Total 20 18 23 38 45 25 21 21 21 16 35 45 53 28 15 7 19 17 19 63 63 59 30 26 18 16 31 94 132 64 20 20 37 17 7 40 40 27 23 17 27 21 52 65 123 67 20 34 17 16 4 20 11 28 28 21 23 37 102 32 52 16 17 12 0 0 0 2 3 1 1 4 7 18 37 3 13 4 0 0 0 0 0 0 0 0 0 1 0 0 3 0 4 1 0 0 93 68 53 163 162 140 103 90 96 108 260 239 377 180 72 73 1 I I I I I I I I I I I I Total 431 691 617 436 93 9 2277 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 6 0 174 2277 8760 RTL A9.690E Enclosure 2, Attachment 1 (Part 3 of 3)Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2010 Attachment 1 Part 3: Joint Frequency Distribution Tables (500ft)Page 6 of 8 Hours at Each Wind Speed and Direction Total Period Period ofRecord 1/1/2010 00:00 -12/31/2010 23:00 Elevation:

Speed: SP500P Direction:

DI500P Lapse: DT500-35 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 13 18 12 4 0 0 47 NNE 8 12 2 .0 0 0 22 NE 19 9 1 0 0 0 29 ENE 25 23 9 1 0 0 58 E 20 50 4 0 0 0 74 ESE 19 27 11 1 0 0 58 SE 24 16 6 4 0 0 50 SSE 15 25 15 5 0 0 60 S 12 24 22 19 2 0 79 SSW 16 16 17 13 1 0 63 SW 25 39 38 27 9 0 138 WSW 26 51 40 4 0 0 121 W 32 56 40 3 0 0 131 WNW 16 50 18 1 0 0 85 NW 20 20 6 0 0 0 46 NNW 22 12 4 0 0 0 38 Total 312 448 245 82 12 0 1099 Calm Hours not Included above for: Total Period 6 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 174 Valid Hours for this Stability Class for: Total Period 1099 Total Hours for Period 8760 RTL A9.690E I Enclosure 2, Attachment 1 (Part 3 of 3)Beaver Valley Power Station -Units I & 2 1 Radioactive Effluent Release Report Calendar Year -2010 Attachment 1 Part 3: Joint Frequency Distribution Tables (500ft)Page 7 of 8 Hours at Each Wind Speed and Direction Total Period Period of Record 1/1/2010 00:00 -12/31/2010 23:00 Elevation:

Speed: SP500P Direction:

DI500P Lapse: DT500-35 I 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 1 0 0 0 0 0 1 NNE 5 2 0 0 0 0 7 I NE 1 3 0 0 0 0 4 ENE 1 5 1 0 0 0 7 E 2 10 0 0 0 0 12 ES ESE 5 7 2 0 0 0 14 SE 0 7 3 0 0 0 10 SSE 2 16 4 1 0. 0 23 S 2 11 12 7 1 0 33 SSW 2 8 7 2 1 0 20 SW 2 4 6 2 0 0 14 WSW 2 5 5 0 0 0 12 W 0 1 8 2 0 0 11 WNW 1 3 0 0 0 0 4 NW 2 2 1 0 0 0 5 NNW 0 0 0 0 0 0 0 Total 28 84 49 14 2 0 177 Calm Hours not Included above for: Total Period 6 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 174 Valid Hours for this Stability Class for: Total Period 177 Total Hours for Period 8760 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 -2010 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= 1/1/201.0 00:00 -12/31/2010 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 54 106 195 69 2 0 426 NNE 56 75 57 34 3 0 225 NE 61 77 18 14 3 0 173 ENE 91 145 154 50 4 0 444 E 94 195 136 44 9 0 478 ESE 63 136 116 65 4 0 384 SE 55 88 64 44 3 0 254 SSE 49 87 52 33 4 2 227 S 48 69 104 67 14 1 303 SSW 42 57 92 99 33 2 325 SW 86 99 191 295 98 9 778 WSW 94 217 300 238 48 6 903 W 115 282 481 516 215 25 1634 WNW 74 214 473 276 85 8 1130 NW 48 121 212 82 6 0 469 NNW 37 106 223 59 2 0 427 Total 1067 2074 2868 1985 533 53 8580 Calm Hours not Included above for : Total Period 6 Variable Direction Hours for: Total Period 0 Invalid Hours for: Total Period 174 Valid Hours for this Stability Class for: Total Period 8580 Total Hours for Period 8760 Enclosure 2, Attachment 2

RTL # A9.690E Enclosure 2, Attachment 2 Beaver Valley Power Station -Units 1 & 2 Radioactive Effluent Release Report Calendar Year -2010 Attachment 2 Unit I and 2 Offsite Dose Calculation Manual Changes Attachment 2 Attached is a complete copy of the ODCM that includes: Change (28) of the ODCM (Effective:

December 2010)Attachment 2 Clarification A complete copy of the ODCM has been provided to the following offices: United States Nuclear Regulatory Commission Attention:

Document Control Desk Washington, DC 20555-0001 United States Nuclear Regulatory Commission Regional Administrator 475 Allendale Road King of Prussia, PA 19406 For a complete copy of the ODCM, contact Ms. Lara Renz at 724-682-4255.

Enclosure 2, Attachment 3

RTL #A9.690E Enclosure 2, Attachment 3 UoStions C-14 Dose Assessment for Routine Effluent Releases Prepared for Beaver Valley Power Station, First Energy Corp.By James F. Key, Jr.Key Solutions, Inc.Introduction The U.S. Nuclear Regulatory Commission (NRC) is now requiring nuclear power plants to assess the dose impact from C-14 to members of the public which can arise due to routine releases in radiological effluents.

Until 2010 the industry was not required to do so because the dose impact of C-14 releases had been considered negligible as compared to the doses from noble gases, tritium, particulates and radioiodines.

The regulatory guidance for the radiological effluent technical specifications (RETS) simply ignored releases of C-14 [USNRC (1978b), USNRC(1978c), USNRC (1991a), USNRC (199 lb)].The rationale was based on studies by the EPA [USEPA (1979)] and others [(Till (1978), Key (2010)] The NRC stated its position to exclude the requirement for C- 14 dose assessment in 1981 [Willis(1981)].

There is little regulatory guidance on the details as to how C-14 dose calculations are to be performed.

Key Solutions, Inc. was contracted to perform the C-14 offsite dose assessment for the 2010 annual radiological effluent release report. This document describes the methodology, bases and results of that assessment for the Beaver Valley Power Station (BVPS).Technical Discussion Total C- 14 Activity Released to the Atmosphere C-14 atmospheric releases were not addressed in NRC guidance for the establishment of Standard Radiological Effluent Technical Specifications (SRETS). As a result the nuclear industry, with a few exceptions, performs no monitoring of releases of C- 14 to the environment.

As there has been, and still is, no regulatory guidance addressing C-14 releases, the NRC has indicated that various methods of estimating C-14 releases are acceptable.

At present, lacking any analytical quantification of release activity, the general accepted industry practice is to estimate annual C-14 release activity based on C-14 production in reactor coolant.1 RTL #A9.690E Enclosure 2, Attachment 3

For PWRs, NRCP Report 81 provides a conservative approximation based on GW(e)-yr for individual power reactors.

Section 3.4.2.4 suggest C-14 activity releases be derived assuming an atmospheric release of about 6 Curies per gigawatt-electical per year (GW(e)-yr).

Most recently EPRI has published estimations of C-14 released to the atmosphere based upon thermal power [EPRI(2010)].

This EPRI document proposes 3.4 -3.9 GW(th)-yr (or 10.0 -11.5 GW(e) -yr) as an industry proxy value for PWRs.EPRI considers the 1 7 0(n,a)1 4 C and 1 4 N(n,p)14C reactions to be the principal production mechanisms in the reactor coolant and presumes 100% of the C-14 generated in the coolant is released in gaseous effluents.

The C-14 activity discharged in liquid effluents is considered negligible and has little potential environmental or dose impact. An estimate of C-14 dose resulting from liquid effluents is reported here in mrem per Ci of C-14 released annually.This report only considers C-14 released in liquid and gaseous effluents and does not address shipments of solid waste and irradiated fuel.Chemical Form of Interest U C-14 being a pure beta emitter generates no dose from direct radiation.

C-14 is inhaled in the form of C02 and is incorporated into all body tissue. However, inhaled C02 enters body compartments with high turnover and thus the predominate exposure pathway C-14 i is though ingestion

[NCRP(1985)].

The dose from C-14 via the potable water pathway is determined using the specific i activity approach [Faw(1999), IAEA(2001), NCRP(1984), USNRC(1983)]

but is applicable only to the dose limits for liquid effluents.

The ingestion of total carbon and therefore C-14 in drinking water is very small as compared to the dose resulting from I ingestion of food stuffs. For Beaver Valley the C-14 liquid effluent dose was estimated to be approximately 4.5E-3 mrem per Ci of C-14 released.What remains of concern is that portion of C- 14 incorporated into the human food chain through vegetation by the photosynthesis process. The only chemical form of C-14 incorporated into plant matter is C02. All other chemical forms of C-14 have inconsequential dose impact on the human food chain. Studies have found that the chemical species of C-14 can vary greatly depending on the reactor type (PWR or BWR)[Hayes(1977), Killough(1978), Till(1978)].

Organic forms include: methane, ethane, propane and butane, all of which are not incorporated into vegetation.

In the case of BVPS the fraction of carbon released to the atmosphere in C02 form (C02 Fraction) was taken to be 0.4. This is based on the EPRI study [EPRI(2010)]

which states that for PWRs operating without a recombiner, release of carbon to the atmosphere is primarily in I RTL #A9.690E Enclosure 2, Attachment 3 olutions organic form. Only a small fraction is released as C02. EPRI suggests a C02 fraction 0.05 to 0.3.As already indicated, C-14 enters the human food chain only in C02 form and only when it is incorporated into plant matter with subsequent direct ingestion of vegetation.

Human ingestion of C-14 also occurs as a result of consumption of animal products from livestock feeding on contaminated vegetation.

Environmental Transport The carbon incorporated into plant matter comes only from atmospheric C02. Therefore the concentration of C- 14 in plant materials is directly dependant on the airborne concentration.

The atmospheric dispersion value X/Q is used to model airborne concentration of C02 at locations of interest.

Ground plane deposition of C02 is negligible in the environs local (within 5 miles) of the point of release and therefore is not addressed.

Modeling the concentration of C-14 in plant matter as well as animal food products assumes that C-14 is in equilibrium in all ingested food. The assumption of equilibrium, while conservative, simplifies the modeling of C-14 in the human food chain. The specific activity of C-14 in the food stuffs is considered to be the same as the atmospheric specific activity.

In turn, the total uptake of C- 14 by humans is derived from the total carbon dietary intake. This approach provides an upper bound on C-14 ingestion in food stuffs as the specific activity in vegetation, milk or meat can never exceed the airborne specific activity.Meteorology The BVPS ODCM contains dispersion values (X/Q) for various locations of interest.

X/Q is a function of meteorology, mode of release and receptor location.

ODCM Table 2.3-1 lists the release points at BVPS and the associated release modes. X/Q tables (Tables 2.3-3 to 2.3-7 and Attachment M, Tables 2.3-35 to 2.3-37) provide dispersion values for the locations of dose pathways identified in land use census.ODCM Table 2.2-4, 2.2-5 and 2.2-7 provide receptor X/Q values for ground level releases from containment vent (CV-1 and CV-2), ventilation vent (VV-1 and VV-2) and turbine building vent (TV2). The X/Q values represent annual average dispersion and are derived from historical meteorological data. The annual average X/Qs are applied to the case of continuous releases.Table 2.2-6 lists process vent (PV-1/2) X/Q values for continuous elevated releases.3 RTL #A9.690E Enclosure 2, Attachment 3 oSlutions Intermittent releases (batch releases) can make use of annual average dispersion values provided such releases are made under random meteorological conditions

[USNRC(1982a)].

It is also possible to calculate "short term" X/Qs from historical meteorology and apply to batch releases [USNRC(1978) and USNRC(1982a)].

The short term X/Q is a statistically weighted value and only provides a level of conservatism.

It does not improve the accuracy of the dispersion values.Intermittent releases are classified as short term if the cumulative release time is less than 500 per year. Intermittent releases with cumulative duration greater than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per year can be considered as long term releases and be modeled using annual average X/Qs.The BVPS 2009 Radioactive Effluent Release Report reports the total batch release period for theyear as being 83,598 minutes (- 1393 hrs). It is assumed that 2010 cumulative batch release times also exceeded 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per year and can therefore be modeled using annual average X/Q if so desired.ODCM Attachment D, Tables 2.2-2a and 2.2-2b lists the FSAR source terms for Units 1 I and 2. It details the unit's atmospheric release points and expected nuclide mix for that discharge path. For both units, the C-14 source term is given as 8 Ci/yr with 12.5 % being released from containment venting and 87.5% processed by the gaseous waste system and released through the process vent (PV). This study assumed a 20% ground level and 80% elevated release apportionment.

Methodology for Calculation of C-14 Dose Determination of C-14 concentration in food products is based on specific activity and assumes that the ratio of C-14 to stable carbon reaches equilibrium in all food products.The incorporation of C02 into the human food chain occurs only through direct or indirect vegetation ingestion.

This process is complex and very dynamic; therefore, it is unlikely that true equilibrium is ever reached. The specific activity approach assumes I constant environmental concentrations and is therefore admittedly conservative.

However, the specific activity methodology does provide an upper bound of the maximum possible concentration of C-14 in food stuffs and currently is the de-facto approach used for C-14 as well as for H-3 [Killough(1978), NCRP(1985), USNRC(1983)].

The vegetation ingestion dose model presented here is derived from Equation C-8 of Regulatory Guide 1.109, Appendix C.3 [USNRC(1977a)].

However the 1.109 default value for the concentration of natural carbon in the atmosphere has been updated to reflect the increase of anthropomorphic C02 over the past several decades. The default value of 0.16 gm/mi 3 has been changed to 0.19 gm/m 3 based on the current EPA published value of 383 ppm atmospheric C02. Equation C-8 only addresses C-14 4 I RTL #A9.690E Enclosure 2, Attachment 3 uolutions concentration in vegetation, but it does not address C-14 concentration in meat or milk products.Equation C-8 makes use of a fractional equilibrium ratio (defined as parameter "p"). This parameter was intended to correct for growing season photosynthesis but is improperly applied and has been dropped [Faw(1999), Killough(1978), USNRC(1983)].

The methodology presented in Reg Guide 1.109 to model the C- 14 concentrations in meat and milk lacks sound technical bases. C-14 concentration in food products is more appropriately modeled using the same approach as for vegetation.

That is to say, a specific activity equilibrium model [Faw(1999), Killough(1978), IAEA(2001), NCRP(1985) and USNRC(1983)].

The methodology used in this report for milk and meat concentrations is based on the specific activity equilibrium model.C-14 Dose Factors The NRC continues to require the reporting of organ doses for demonstration of compliance with 10 CFR 50, Appendix I. EPA 40 CFR 190 also is stated in terms of organ dose, Factors for organ doses are derived from the internal dosimetry methodology of International Commission on Radiological Protection Publication 2 or ICRP-2[ICRP(1 959)]. ICRP 2 has long been superseded by more recent methodology.

Nevertheless, organ doses must still be reported to demonstrate compliance with NRC and EPA regulations.

The ICRP 2 organ dose conversion factors used are taken from Reg Guide 1.109.Inhalation and Ingestion dose conversion factors (Table 1) are taken from Tables E-7 through E-14 of Reg Guide 1.109. Dose factors are provided for infant, child, teen and adult age groups and for 7 organs. In the case of C-14, 6 organ (liver, total body, thyroid, kidney, lung, gi-tract) dose factors are the same. Only the bone dose factor is different.

Table 1. Reg Guide 1.109 Organ Dose Conversion Factors Reg Guide 1.109 Tables E-7 to E-14 Age Bone Liver TBody Thyroid Kidney Lung GI-LLI Group Infant 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Child 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Teen 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 Adult 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Infant 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Child 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 Ingestion Teen 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 Adult 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5 RTL #A9.690E Enclosure 2, Attachment 3 olutions Inhalation Dose Methodology 3 The dose from the inhalation exposure pathway is given as: D"n = 3.17x10' "X/Q'BRa "DFIC-1 4 Qc-4 4 Where: I D = C-14 dose from the Inhalation Pathway for age group a and organj in mrem/yr.3.17x=104 Conversion factor: 3.17x10-8 yr/sec x 1012 pCi/Ci.X/Q = Atmospheric dispersion for location of interest.

Ground level or elevated 3 dispersion values are used as appropriate.

The units are sec/mr 3.BRa = Annual breathing rate in m 3/year for age group a. From Reg Guide 1.109, Table E-5.DFI C-14 C-14 Inhalation Dose Conversion Factor for age group a and organj from Reg Guide 1.109, Tables E-7 to E- 10. Units are mrem per pCi inhaled.QC-14= Total C-14 released to the atmosphere in Ci for the period of interest.

For inhalation this is the total C-14 annual atmospheric release.Vegetation Dose Methodology The vegetation dose methodology is based on the assumption of specific activity equilibrium between atmospheric C-14 and vegetative C-14. The dose from the vegetation ingestion exposure pathway is given as: I Da- =3.17xl0-/Q'U, "0. 11/0.19"DFLa-' "C-Where: DVeg D ae C-14 dose from the Vegetation Ingestion Pathway for age group a and organj in mrem/yr.3.17x 10' Conversion factor: 3.17 x 10.8 yr/sec x 1012 pCi/Ci x 103 gm/Kg.6 RTL #A9.690E Enclosure, 2, Attachment 3 Bolutions X/Q = Atmospheric Dispersion for location of interest.

Ground level or elevated dispersion values are used as appropriate.

The units are sec/m 3.Uveg Annual local garden vegetation ingestion for age group a in Kg-Vegetation per year. From Reg Guide 1.109, Table E-5.0.11 Fraction of plant mass that is carbon in kg-carbon per kg-plant.

Taken from Reg Guide 1.109, Equation C-8.0.19 Atmospheric concentration of natural carbon in gm/m 3 based on current EPA published value of 383 ppm.DFLc-1 4 = C-14 Ingestion Dose Conversion Factor for age group a and organj from Reg Guide 1.109, Tables E- 11 to E- 14. Units are mrem per pCi ingested.C = Total C-14 (in Curies) released to the atmosphere as C02 during the C-14 period of interest.Milk Dose Methodology The milk dose methodology is based on the assumption of specific activity equilibrium among atmospheric C-14, vegetation C-14 and animal milk. The dose from the milk ingestion exposure pathway is given as: D m ik = 3.17x107 .X/Q.UaIk

.0. 11/0.19.DFLC-4 (co2 aj aa C-14 Where: Dmiak C-14 dose from the Milk Ingestion Pathway for age group a and organ] in mrem/yr.3.17x10 7 Conversion factor: 3.17 x 10.8 yr/sec x 1012 pCi/Ci x 10 3 gm/liter.X/Q = Atmospheric Dispersion for location of interest.

Ground level or elevated dispersion values are used as appropriate.

The units are sec/m 3.UMilk Annual consumption of locally supplied milk for age group a in liters-milk per year. From Reg Guide 1.109, Table E-5.0.11 Fraction of plant mass that is carbon in kg-carbon per kg-plant.

Taken from Reg Guide 1.109, Equation C-8.7 RTL #A9.690E Enclosure 2, Attachment 3 S olutions 0.19 = Atmospheric concentration of natural carbon in gm/mr 3 based on current EPA published value of 383 ppm.DFLc-1 4 = C-14 Ingestion Dose Conversion Factor for age group a and organj from 3 Reg Guide 1.109, Tables E-l Ito E-14. Units are mrem per pCi ingested.C = Total C-14 (in Curies) released to the atmosphere as C02 during the I C-14 period of interest.Meat Dose Methodology The meat dose methodology is based on the assumption of specific activity equilibrium among atmospheric C-14, vegetation C-14 and animal meat. The dose from the meat ingestion exposure pathway is given as: Mat = 3. 7 Mea 10 CO X/ a DaV =3.17x1 ./QU m a .0. 11/0.19.DFLC-4 ., C_14 Where: I DMea t = C-14 dose from the Meat Ingestion Pathway for age group a and organj in mrem/yr.3.17x10 7 Conversion factor: 3.17 x 10-8 yr/sec x 1012 pCi/Ci x 10 3 gm/Kg.X/Q = Atmospheric Dispersion for location of interest.

Ground level or elevated dispersion values are used as appropriate.

The units are sec/mi 3.I u Meat Annual consumption of locally supplied meat for age group a in Kg-meat per year. From Reg Guide 1.109, Table E-5.0.11 = Fraction of plant mass that is carbon in kg-carbon per kg-plant.

Taken from Reg Guide 1.109, Equation C-8.0.19 = Atmospheric concentration of natural carbon in gm/m 3 based on current I EPA published value of 383 ppm.DFLc-1 4 C-14 Ingestion Dose Conversion Factor for age group a and organj from i Reg Guide 1.109, Tables E-1 1 to E-14. Units are mrem per pCi ingested.Co14 Total C-14 (in Curies) released to the atmosphere as C02 during the period of interest.8 RTL #A9.690E Enclosure 2, Attachment 3 L L olutions Dose Assessment Results Dose to a member of the public was determined for various scenarios as detailed in Table 3. Dose is dependent on consumption and usage habits as well as organ mass and metabolism; thus it is appropriate to calculate dose for different age groups. Reg Guide 1.109 defines four age groups: infant (0 to 1 year), child (I to 11 years), teen (11 to 17 years), adult (17 years and older). Lacking site specific information, all four age groups were assumed to be present and consuming at the location of interest.Consumption rates (Table 2) were those associated with the maximum individual for each age group as defined in Reg Guide 1.109, Section B. Values were taken from Table E-5 of the same document.

The maximum individual represents a person with reasonable consumption habits greater than that of the average for the population in general.Table 2. Maximum Exposed Individual Usage Reg Guide 1.109 -Table E-5 Age Group Pathway Infant Child Teen Adult Inhalation 1400 m 3/yr 3700 m 3/yr 8000 m 3/yr 8000 m 3/yr Vegetation

-Leafy 26 kg/yr 42 kg/yr 64 kg/yr Vegetation

-Produce 520 kg/yr 630 kg/yr 520 kg/yr Vegetation

-Total -546 kg/yr 672 kg/yr 584 kg/yr Cow Milk 330 liters/yr 330 liters/yr 400 liters/yr 310 liters/yr Cow Meat -41 kg/yr 65 kg/yr 110 kg/yr Doses were calculated at those locations with the highest dose potential as determined by exposure pathways.For information purposes, doses for all potentially significant pathways (inhalation, vegetation, milk and meat) are shown regardless of whether the pathways were or were not present. Doses are also calculated for the real pathways present as documented in the ODCM. The inhalation pathway was assumed to be present at all locations where ingestion pathways were considered.

Dispersion (X/Q) Values Dispersion values are taken from ODCM Attachment F, Tables 2.2-4 through 2.2-7 and Attachment M, Table 2.3-37. Dispersion values were selected based on receptor locations as described in ODCM Attachment F, Table 2.2-3. Tables 2.2-4, 2.2-5 and 2.2-7 list X/Q values for ground mode release points. The highest ground level X/Q for a location of interest was selected from among these tables.9 RTL #A9.690E 3 Enclosure 2, Attachment 3 f i For elevated releases from the process vent, annual average X/Q values were taken from Table 2.2-6. Elevated short term X/Q values come from Table 2.3-37 3 Other Considerations 3 Residency time was assumed to be 100%. And 100% of ingested food stuffs was assumed to be grown and consumed at the receptor location.

3 The annual source term (11 Ci ) was determined using the PWR proxy value as provided in EPRI guidance [EPRI(201 1)]. The capacity factor for Unit 1 was 90% based on the 32 day 2010 outage of September 23 to October 25. A 100% capacity factor was assumed for Unit 2.Doses were based on the assumed continual release of the calculated source term spread H out over an entire year.Releases were apportioned as 20% ground level and 80% elevated based on ODCM Attachment D, Tables 2.2-2a and 2.2-2b.Estimated Critical Receptor Dose The critical receptor is defined to be that individual located where the combination of existing pathways and receptor age groups have the highest dose potential.

The critical receptor for this report was determined to be located in the Northwest sector at 1432 l meters.Doses for various scenarios were calculated and are shown in Table 3. They are listed in i order of increasing technical sophistication.

Scenarios 1 and 2 assume an arbitrary C-14 release of 20 Ci per year per unit. These 3 reflect simplistic calculations based on the conservative assumption that all releases were ground mode and 100% of the C-14 present in C02 form. Scenario 1 dose incorporates for all pathways (All) of interest whether actually present or not. Scenario 2 dose I addresses actual pathways (Inhalation and Vegetation) indicated by the ODCM. These scenarios obviously reflect an unreasonable level of conservatism and the dose estimates are unrealistic.

Scenarios 3 and 4 utilized the EPRI C-14 proxy source term (11 Ci/yr) released as 100%C02. Scenario 3 assumes ground level releases and the presence of all pathways.

As the I milk and meat pathways are known to be absent at this location, this provides an overly conservative estimate, but has been included for comparison.

Scenario 4 assumes ground level release and considers only those exposure pathways actually present.10 i I RTL #A9.690E Enclosure 2, Attachment 3 soltions Scenario 5 uses the conservative C02 fraction of 40%; the other 60% being in organic form. For the inhalation exposure pathway 100% of the C-14 source term was used. For ingestion pathways, 40%. The EPRI proxy source term was used and the release mode was assumed to be ground level.Scenario 6 apportions 20% of the C-14 release to ground level and 80% to elevated release points. Only doses for the existing pathways were considered.

The X/Q used for the elevated release is the annual average dispersion for the nearest residence in the NW sector at 1464 meters. This assumes short term releases from the process vent can be modeled using annual average X/Q. The basis for this is from the observation that cumulative releases from the process vent exceeded 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per year for 2009. It was assumed that process vent releases during 2010 would also exceed 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per year.Scenario 7 apportions 20% of the C-14 release to ground level and 80% to elevated release points. Only doses for the existing pathways were considered.

The X/Q used for the elevated release is the short term dispersion value for the nearest residence in the NW sector at 1464 meters. This value was taken from ODCM Attachment M, Table 2.3-37.Scenarios 8 and 9 provide estimates of meat (WNW @ 3605 meters) and milk (WNW at 4538 meters) exposure pathways at the locations of the highest dose potential.

It was assumed that inhalation and vegetation exposure pathways were also present.11 RTL #A9.690E Enclosure 2, Attachment 3 n olutons Table 3.C-14 Dose Assessment Scenarios Elev Total Critical Bone Body Scenario Description Ground Elevated GndCi Ci C02 Exposure Age Dose Body X/Q X/Q Per yr Per Fraction Pathways Group mrem/yr Dose yGru mrmyr mrem/yr Arbitrary release of 20 Ci/yr.1 Nearest residence.

All 2.71E-5 20 1 All Child 111.0 22.2 pathways.

Ground release. NW -1432m (Bone)Arbitrary release of 20 Ci/yr. Inhalation Child 2 Nearest residence.

Real 2.71E-5 20 1 Vegetation 66.3 27.6 pathways.

Ground release. NW -1432m (Bone)C-14 EPRI PWR value. All Child 3 Ground release. 2.71E-5 11 NW- 1432m (Bone) 61.0 12.2 C-14 EPRI PWR value. -Inhalation Child 4 Ground release. Real 2.71E-5 11 Vegetation (Bone) 36.5 15.2 pathways.

NW -1432m C-14 EPRI PWR value. Inhalation Child 5 Ground release. Real 2.71E-5 11 .4 Vegetation (Bone) 14.8 3.0 pathways.

40% C02 NW -1432m C-14 EPRI PWR value. Inhalation 6 Ground and elevated release 2.71E-5 7.30E-9 2.2 8.8 .4 Vegetation Child points. Short term X/Q. 40% NB28e o 3.0 0.6 C02 NW -1432m C-14 EPRI PWR value.Critical receptor.

Inhalation Child Short term elevated X/Q. 2.71E-5 3.31E-8 2.2 8.8 .4 Vegetation (Bone)40% C02 NW- 1432m C-14 EPRI PWR value. Inhalation Highest meat pathway. Vgtto hl 8 Short term elevated X/Q. 4.8E-6 2.53E-7 2.2 8.8 .4 Vegetation 1.3 0.3 Shr emeeae /.Meat (Bone) 1.03 40% C02. WNW @ 3605 m C-14 EPRI PWR value. Inhalation Highest milk pathway. Vgtto hl Short term elevated X/Q. 3.5E-6 1.78E-7 2.2 8.8 .4 Vegetation Child 1.2 0.2 40%Milk (Bone)O1.20.

40% C02. _______ __ __ ___WNW@g 4538m ___ ______12 M M M M M M M M M M M M M M M M M M RTL #A9.690E Enclosure 2, Attachment 3 n' olutions Discussion Scenarios 7, 8 and 9 reflect the most technically detailed dose calculation.

Nevertheless the reported doses are still conservative based upon the following presumptions:

o 100% of C-14 generated in reactor coolant is released in effluents.

o 100% of C-14 released in effluents is released to the atmosphere.

o The C02 fraction was assumed to be 40%. Actual values expected to be 5%-30%based on EPRI guidelines.

o Releases were apportioned as 20% ground level and 80% elevated.

ODCM Attachment D, Tables 2.2-2a and 2.2-2b indicate 12.5% and 87.5%.o The most radio-sensitive age group is actually present.o The receptor consumes at the maximum individual rate as given in Reg Guide 1.09, Table E-5.o All food products are produced in the immediate vicinity of the receptor.o 100% of the receptors annual consumption for vegetation, milk and/or meat come from locally produced products.o The specific activity of carbon-14 has reached equilibrium in all environmental compartments.

Scenario 7 gives the dose estimate for the maximum exposed individual (critical receptor)based on pathways actually present at 1432 meters in the NW direction.

Values were 3.0 mrem for bone and 0.6 mrem for all other body organs, the critical age group being child.Scenario 8 provides the dose estimate at the location of the highest real meat exposure pathway (WNW at 3605 meters). Inhalation and vegetation pathways were considered present as indicated by ODCM Table 2.2-3.Scenario 9 provides the dose estimate at the location of the highest real milk exposure pathway (WNW at 4539 meters). Although ODCM Table 2.2-3 shows no inhalation or vegetation present at this location, these exposure pathways were included.Summary Liquid effluent release doses were found to be insignificant

-less than 5.0 E-3 mrem per Ci of C-14 released in liquid effluents.

The adult was the controlling age group.The highest airborne dose potential was determined to be at the location of the nearest garden in the NW direction at 1432 meters. Best estimates for C-14 organ dose to the receptors in each age group at this location for Units 1 and 2 are shown in Tables 4a and 4b.13 RTL #A9.690E Enclosure 2, Attachment 3 L LolutionsI Table 4a.BVPS Unit 1 -90% Capacity Factor C-14 Dose in mrem/yr at Highest Dose Receptor NW at 1332 meters Exposure Infant Child Teen Adult Pathway Bone Other* Bone Other* Bone Other* Bone Other*Inhalation 4.51E-02 9.04E-03 6.11E-02 1.15E-02 4.43E-02 8.30E-03 3.09E-02 5.80E-03 Vegetation

--2.61 E+00 5.21E-01 1.08E+00 2.15E-01 6.54E-01 1.31E-01 Ingestion Total 0.05 0.01 2.67 0.53 1.12 0.22 0.68 0.14* "Other" refers to liver, total body, thyroid, kidney, lung and GI. Doses for these organs are assumed to be equal.Table 4b.BVPS Unit 2 -100% Capacity Factor C-14 Dose in mrem/yr at Highest Dose Receptor NW at 1332 meters Exposure Infant Child Teen Adult Pathway Bone Other* Bone Other* Bone Other* Bone Other*Inhalation 5.01E-02 1.OOE-02 6.79E-02 1.27E-02 4.92E-02 9.22E-03 3.44E-02 6.45E-03 Vegetation 2.89E+00 5.79E-01 1.20E+00 2.39E-01 7.27E-01 1.45E-01 Ingestion Total 0.05 0.01 2.96 0.59 1.24 0.25 0.76 0.15* "Other" refers to liver, total body, thyroid, kidney, lung and GI. Doses for these organs are assumed to be equal.The maximum bounding dose to a member of the public resulting from atmospheric C-14 releases from Unit 1 was determined to be less than 2.67 mrem to the bone and less than 0.53 mrem to all other organs. The child is the controlling age group.The maximum bounding dose to a member of the public resulting from atmospheric C-14 releases from Unit 2 was determined to be less than 2.96 mrem to the bone and less than 0.59 mrem to all other organs. The child is the controlling age group.14 I I I I I I I I I I I RTL #A9.690E Enclosure 2, Attachment 3 Uolutions REFERENCES EPRI (2011). Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents, Electric Power Institute, Palo Alto, California.

December, 2010.Faw (1999). Radiological Assessment:

Sources and Doses, Ist ed., Faw, R. E. and J. K.Shultis. American Nuclear Society, Inc., 1999.Hayes (1977). Carbon-14 Production by the Nuclear Power Industry.

Hayes, D. W. &MacMurdo, K. W. (1977). Health Physics Journal.IAEA (2001). International Atomic Energy Agency, Generic Models for Use in Assessing the Impact of Discharges of Radioactive Substances to the Environment, IAEA Safety Series Report No. 19 (International Atomic Energy Agency, Vienna).ICRP (1959). Report of Committee Il for Permissible Dose for Internal Radiation, International Commission on Radiological Protection.

Pergamon Press, New York, 1959.Key (2010). C-14 -A Historical Perspective.

Key, James F., Jr., Presented at RETS/REMP Workshop, San Jose, CA, 2010.Killough (1978). "A New Look at the Dosimetry of 14C Released to the Atmosphere as Carbon Dioxide," Killough, G. G. and Rohwer, P.S. 1978. Health Physics 34(2), 141-59.Kunz (1982). Measurement of C]4 Production and Discharge From the Ginna Nuclear Power Reactor. Kunz, C., New York State Department of Health, Albany, NY.Kunz (1984). Carbon-14 Discharge at Three Light-Water Reactors.

Kunz, C., Health Physics Journal.NCRP (1984). National Council on Radiation Protection and Measurements, Radiological Assessment:

Predicting the Transport, Bioaccumulation, and Uptake by Man of Radionuclides Released to the Environment, NCRP Report No. 76 (National Council on Radiation Protection and Measurements, Washington).

NCRP (1985). National Council on Radiation Protection and Measurements, Carbon- 14 in the Environment, NCRP Report No. 81 (National Council on Radiation Protection and Measurements, Washington).

NOAA (2011). http://www.srrb.noaa.

gov/highlights/sunrise/gen.html.

NOAA web site.Accessed January 2011. (National Oceanic and Atmospheric Administration, Washington, D.C.).Till (1978). Scenarios of C-14 Releases to the Atmosphere by the World Nuclear Industry and Estimated Radiological Impacts. Till, J. E. & Killough, G. G. In: Tagungsbericht Radioaktivitdt und Umwelt, 12. Jahrestagung, Norderney, 2.-6. Oktober 1978, 15 RTL #A9.690E I Enclosure 2, Attachment 3 U Lolutions Fachverband ftir Strahlenschutz e.V.: 680-695. Norderney, Federal Republic of Germany.USEPA (1979). U.S. Environmental Protection Agency, Health Impact Assessment of Carbon-14 Emission From Normal Operations of Uranium Fuel Cycle Facilities.

Environmental Protection Agency. Fowler, T. W. & Nelson, C. B. (1979), US EPA I 520/5-80-004. (U.S. Environmental Protection Agency, Washington, D.C.)USNRC (1974). U.S. Nuclear Regulatory Commission, Measuring, Evaluating, and I Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light- Water-Cooled Nuclear Power Plants. Regulatory Guide 1.21 Revision 1 (U.S. Nuclear Regulatory Commission, Washington, D.C.)USNRC (1977a). U.S. Nuclear Regulatory Commission, Calculation ofAnnual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Compliance with 10 CFR Part 50, Appendix I. Regulatory Guide 1.109 Revision 1 (U.S. Nuclear Regulatory Commission, Washington, D.C.)USNRC (1977b). U.S. Nuclear Regulatory Commission, Methods for Estimation Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light- Water-Cooled Reactors.

Regulatory Guide 1.111 Revision 1 (U.S. Nuclear Regulatory Commission, Washington, D.C.)USNRC (1978). U.S. Nuclear Regulatory Commission, Preparation ofRadiological Effluent Technical Specifications for Nuclear Power Plants. Report No. NUREG-0133 (U.S. Nuclear Regulatory Commission, Washington, D.C.) 3 USNRC (1982a), U.S. Nuclear Regulatory Commission, XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations.

NUREG/CR-2919 (U.S. Nuclear Regulatory Commission, Washington, D.C.)USNRC (1982b), U.S. Nuclear Regulatory Commission, Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors.

(1982), NUREG-0472 (U.S.Nuclear Regulatory Commission, Washington, D.C.)USNRC (1982c), U.S. Nuclear Regulatory Commission, Standard Radiological Effluent Technical Specifications for Boiling Water Reactors.

(1982), NUJREG-0473 (U.S.Nuclear Regulatory Commission, Washington, D.C.)USNRC (1983), U.S. Nuclear Regulatory Commission, Radiological Assessment:

A Textbook on Environmental Dose Analysis.

Till, J. E. and H. R. Meyer Eds. (1983), I Report No. NUREG/CR-3332, ORNL-5968 (U.S. Nuclear Regulatory Commission, Washington, D.C.)16 RTL #A9.690E Enclosure 2, Attachment 3 n" olutions USNRC (199 la). U.S. Nuclear Regulatory Commission, Offsite Dose Calculation Manual Guidance.

Standard Radiological Effluent Controls for Pressurized Water Reactors.

NUREG- 1301 (U.S. Nuclear Regulatory Commission, Washington, D.C.)USNRC (1991 b). U.S. Nuclear Regulatory Commission, Offsite Dose Calculation Manual Guidance:

Standard Radiological Effluent Controls for Boiling Water Reactors.NUREG-1302 (U.S. Nuclear Regulatory Commission, Washington, D.C.)Willis (1981). Letter to Pandey, S., Franklin Research Center, Philadelphia, PA, November 20, 1981. Willis, C.A., USNRC, NRR.17

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