L-13-332, Radioactive Effluent Release Report Corrections

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Radioactive Effluent Release Report Corrections
ML13294A025
Person / Time
Site: Beaver Valley
Issue date: 10/16/2013
From: Emily Larson
FirstEnergy Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-13-332
Download: ML13294A025 (41)
v • d • e


Text

Beaver Valley Power Station P.O. Box 4 "Shippingport, PA 15077 FirstEnergy Nuclear Operating Company Eric A. Larson 724-682-5234 Site Vice President Fax: 724-643-8069 October 16, 2013 L-1 3-332 10 CFR 50.36a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Beaver Valley Power Station, Unit Nos. 1 and 2 Docket No. 50-334, License No. DPR-66 Docket No. 50-412, License No. NPF-73 Radioactive Effluent Release Report Corrections

References:

1. FENOC Letter L-10-050 dated April 30, 2010, Submittal of 2009 Radioactive Effluent Release Report and 2009 Annual Radiological and Non-Radiological Environmental Operating Reports
2. FENOC Letter L-11-041 dated April 29, 2011, Submittal of 2010 Radioactive Effluent Release Report and 2010 Annual Radiological and Non-Radiological Environmental Operating Reports
3. FENOC Letter L-12-085 dated April 30, 2012, Submittal of 2011 Radioactive Effluent Release Report and 2011 Annual Radiological and Non-Radiological Environmental Operating Reports
4. FENOC Letter L-13-129 dated April 25, 2013, Submittal of 2012 Radioactive Effluent Release Report and 2012 Annual Radiological and Non-Radiological Environmental Operating Reports In References 1, 2, 3 and 4, FirstEnergy Nuclear Operating Company (FENOC) submitted the Beaver Valley Power Station, Unit Nos. 1 and 2 (BVPS) Radioactive Effluent Release Report, Annual Radiological Environmental Operating Report and Annual Environmental Operating Report (Non-Radiological) for calendar years 2009, 2010, 2011 and 2012, respectively. FENOC has since determined that previously unknown abnormal liquid releases of small amounts of licensed radioactive material occurred on several occasions from an unmonitored release path since 2009. No Offsite Dose Calculation Manual or 10 CFR Part 20 limits were exceeded during these abnormal releases. The cause of the issue was investigated and corrective actions were taken in accordance with the corrective action program.

Attachments 1, 2, 3 and 4 provide the corrected pages to the Radioactive Effluent Release Report for calendar years 2009, 2010, 2011 and 2012, respectively, to account for these abnormal releases.

Beaver Valley Power Station, Unit Nos. 1 and 2 L-1 3-332 Page 2 There are no regulatory commitments contained. in this letter. If there are any questions or if additional information is required, please contact Mr. Brian F. Sepelak, Supervisor -

Regulatory Compliance, at (724) 682-4282.

Sincerely, Eric A. Larson Attachments:

1. 2009 Annual Radioactive Effluent Release Report (ARERR) Corrections
2. 2010 Annual Radioactive Effluent Release Report (ARERR) Corrections
3. 2011 Annual Radioactive Effluent Release Report (ARERR) Corrections
4. 2012 Annual Radioactive Effluent Release Report (ARERR) Corrections cc: NRC Region I Administrator NRC Resident Inspector NRR Project Manager Director BRP/DEP Site BRP/DEP Representative NRC Region I Health Physics Inspector

BEAVER VALLEY POWER STATION ENVIRONMENTAL & CHEMISTRY SECTION Technical Report Approval:

2009 ARERR Corrections Submitted October 2013 Attachment I Prepared by: Dr. Lara M. Renz Prepared by: Rebecca Novak IL ill" --

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Reviewed by: Beth H. Furdak Approved by: Donald Salera fy....-

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ARERR Correction - Submitted October 2013 RTL A9.690E, Page i Form 1/2-ENV-01.05.FO1 (page 1 of 38), Rev 2 Beaver Valley Power Station - Units 1 & 2 2009 Radioactive Effluent Release Report FirstEnergy Nuclear Operating Company FENOC Beaver Valley Power Station - Units I & 2 Unit I License No. DPR-66 Unit 2 License No. NPF-73

ARRER Correction - Submitted October 2013 Attachment I Form 1/2-ENV-01.05.F01 (page 3 of 38), Rev 2 RTL# A9.690E Beaver Valley Power Station - Units 1 & 2, Page iii Radioactive Effluent Release Report Calendar Year - 2009 Executive Summary - Report Submittal Requirements Report Submittal and Requirements: The report was prepared and submitted in accordance with the requirements contained in the following documents:

BVPS Integrated Technical Specifications, Administrative Control 5.6.2 Offsite Dose Calculation Manual (ODCM) procedure 1/2-ODC-3.03, "Controls for RETS and REMP Programs ", Attachment U, Control 6.9.3 BVPS procedure 1/2-ENV-01.05, "Compliance with Regulatory Guide 1.21 and Technical Specifications" NUREG-1301, "Offsite Dose Calculation Manual Guidance. Standard Radiological Effluent Controls for Pressurized Water Reactors, Generic Letter 89-01, Supplement No. 1, April 1991" Regulatory Guide 1.21, "Measuring Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Material in Liquid and Gaseous Effluents from Light-Water Cooled Nuclear Power Plants, Revision 1, June 1974" BVPS Condition Report No. CR 09-52947 and BVPS-SAP Order Number 200197646-0790 are associated with reporting the failure to return a gaseous effluent radiation monitor to service within 30 days.

BVPS Condition Report No. CR 09-61459 is associated with reporting the failure to return a gaseous effluent radiation monitor to service within 30 days.

BVPS Condition Report No. CR 09-64033 is associated with reporting the inability to include a filter paper as part of the monthly composite particulate sample.

BVPS Condition Report No. CR 10-69838 is associated with reporting the inability to include a filter paper as part of the monthly composite particulate sample.

BVPS Condition Report No. CR 13-09691 is associated with the reporting of Abnormal Liquid Releases of drainage from Unit 2 laboratory sinks to the Catch Basin System.

ARRER Correction - Submitted October 2013 Attachment I Form 1/2-ENV-01.05.FO1 (page 4 of 38), Rev 2 RTL# A9.690E Beaver Valley Power Station - Units 1 & 2, Page iv Radioactive Effluent Release Report Calendar Year - 2009 Executive Summary - Liquid and Gaseous Effluent Control (Part I of 2)

Onsite Groundwater Monitoring: Tritium results from two (2) of seventeen (17) wells were >2000 pCi/L, which are similar to results initially communicated in 2007. All gamma spectrometry analyses were

<LLD. No adverse effect has been detected in offsite groundwater, drinking water and surface water.

Onsite Spills: There were no onsite spills >100 gallons.

Decommissioning File Update: There were no items added to the site decommissioning files in accordance with I OCFR50.75(g).

Abnormal Liquid Releases: There were two abnormal liquid releases that occurred in the 4th quarter of 2009. Details are described on page xv of this report.

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.

ARERR Correction - Submitted October 2013 Attachment I Form 1/2-ENV-01.05.F01 (page 15 of 38), Rev 2 RTL# A9.690E Beaver Valley Power Station - Units 1 & 2, Page xv Radioactive Effluent Release Report Calendar Year - 2009 Results of Abnormal Releases Abnormal Liquid Releases: On June 22, 2013 Cobalt-58 was identified in the Unit 2 Building and Yard Drain System.

The Cobalt-58 was identified during Chemistry sampling of the Unit 2 catch basin system as part of Beaver Valley's commitment to NRC Bulletin 80-10.

The event resulted in a release of Licensed Radioactive Material (LRM) from the site boundary. The event is characterized as an Abnormal Release in accordance with Regulatory Guide 1.21, Revision 1.

The source of radioisotopes found in the Unit 2 Building and Yard Drain System was determined to be from cup sink drains in the Unit 2 Hot Lab which by original plant design are routed to the Unit 2 Turbine Building drains.

The Unit 2 Turbine Building Drains discharge to the Unit 2 catch basin and conveyed to the Ohio River. Laboratory instruments used for RCS analysis are drained to the Unit 2 Hot Lab cup sink drains and can be confirmed to drain here during analyses since installation of new equipment in 2009.

Therefore, two Abnormal Release permits were calculated for the 4th quarter of 2009 and corrections were made to the 2009 Annual RETS and REMP Reports (CR#2013-09691).

Abnormal Gas Releases: None

ARRER Correction - Submitted October 2013 Attachment I Form 1/2-ENV-01.05.F01 (page 18 of 38), Rev 2 Beaver Valley Power Station - Units I & 2 Radioactive Effluent Release Report Calendar Year - 2009 Supplemental Information Page RTL# A9.690E, Page 1 of 21 Annual Unit 1 or 2 Dose: 15 mrem to Any Orqan Annual Unit 1 or 2 Dose: 3 mrem to Total Body, & 10 mrem to Any Organ Release Rate: 1500 mrem/yr to Any Organ ite Release Concentration: 10 times 10 CFR 20 ADoendix B. Table 2. EC's 77777777r777ý 7Tr,-,,,I--.,-"&

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r7 e Gamma Spectrometry, Proportional Counter Gamma Spectrometry, Proportional Counter, Liquid Scintillation I

0.OOE+00 I 0.OOE+00 I 0.OOE+00 I 0.OOE+00 I

ARERR Correction - Submitted October 2013 Attachment I Form 1/2-ENV-01.051F01 (page 27 of 38), Rev 2 Beaver Valley Power Station - Units 1 & 2 Radioactive Effluent Release Report Calendar Year - 2009 Table 2B-B Liquid Effluents - Batch Releases RTL # A9.690E, Page 10 of 21 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 5.09E-04 LLD LLD 2.26E-03 2.77E-03 5.44E-04 5.38E-05 LLD 8.36E-04 1.43E-03 6.75E-03 1.66E-03 2.99E-03 1.29E-02 2.43E-02 LLD

" LLD LLD 4.12E-04 4.12E-04 3.64E-05 1.67E-05 7.51E-05 2.82E-04 4.1OE-04 2.87E-03 8.51E-03 2.18E-02 7.12E-02 1.04E-01 2.40E-03 5.49E-03 4.64E-03 7.56E-03 2.01 E-02 9.44E-04 2.13E-03 7.57E-04 LLD 3.83E-03 LLD LLD LLD LLD LLD LLD 1.30E-04 LLD LLD 1.30E-04 LLD 1.46E-05 LLD 2.15E-04 2.30E-04 LLD 7.25E-06 4.08E-06 LLD 1.13E-05 LLD 3.80E-06 LLD LLD 3.80E-06 LLD LLD LLD 1.19E-09 1.19E-09 LLD LLD LLD 3.17E-09 3.17E-09 1.64E-04 2.29E-04 5.05E-04 2.71 E-03 3.61E-03 LLD LLD LLD 3.17E-04 3.17E-04 LLD 6.65E-04 5.83E-04 1.65E-03 2.90E-03 222E-02 1.59E-02 1.09E-02 4.45E-03 5.35E-02 LLD 2.70E-05 3.46E-05 LLD 6.17E-05 LLD 4.20E-05 8.14E-05 LLD 1.23E-04 LLD LLD LLD LLD LLD 7.97E-04 6.92E-04 2.28E-04 2.98E-04 2.02E-03 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 1.65E-05 1.65E-05 NON NE NONE 4NONE NONE 3.72E-02 3.56E-02 4.26E-02 1.05E-01 2.20E-01 LLD LLD LLD LLD LLD LLD LLD LLD 4.24E-05 4.24E-05 LLD LLD LLD LLD LLD LLD 198E-6 LLD LLD

.98-06 NONE NONE NONE NONE NONE ND I

1.98E-06 IND I

4.24E-05I 4.44E-05 LLD = Below the Lower Limit of Detectability, in uCi/ml (Table 4)

ARERR Correction - Submitted October 2013 Attachment I Form 1/2-ENV-01.05.FO1 (page 33 of 38), Rev 2 Beaver Valley Power Station - Unit I Radioactive Effluent Release Report Calendar Year - 2009 Table 5A Assessment Of Radiation Doses RTL # A9.690E, Page 16 of 21 1.35E-02 0.2700 I 1.33E-02 0.2660 I 3.56E-03 0.0712 I 7.83E-03 0.1566 I 3.82E-02 0.3819 4.53E-02 0.9060 2.61E-02 0.5220 9.09E-03 0.1818 1.31E-02 0.2620 9.36E-02 0.9359 1.70E-02 1.1333 1.72E-02 1.1467 6.94E-03 0.4627 1.25E-02 0.8333 5.36E-02 1.7880 5,37E-03 0.1074 5.51E-03 0.1102 4.02E-03 0.0804 6.49E-03 0.1298 2.14E-02 0.2139 1.25E-02 0.2500 1.41E-02 0.2820 5.91E-03 0.1182 8.52E-03 0.1704 4.1OE-02 0.4103 7.61E-03 0.1522 7.63E-03 0.1526 4.61E-03 0.0922 7.19E-03 0.1438 2.70E-02 0.2704 7.77E-03 0.1554 1.23E-02 0.2460 6.62E-03 0.1324 1.75E-02 0,3500 4.42E-02 0.4419 O.OOE+00 0.0000 1.08E-01 2.1600 O.OOE+00 0.0000 O.OOE+00 0.0000 1.08E-01 1.0800 O.OOE+00 0.0000 3.80E-02 0.3800 O.OOE+00 0.0000 O.OOE+00 0.0000 3.80E-02 0.1900 O.OOE+00 0.0000 4.60E-04 0.0061 O.OOE+00 0.0000 1.19E-10 0.0000 4.60E-04 0.0031 3.16E-02 0.4213 2.71E-02 0.3613 1.91E-02 0.2547 5.32E-02 0.7093 1.31E-01 0.8733 3.16E-02 0.4213 2.72E-02 0.3627 1.91E-02 0.2547 5.32E-02 0.7093 1.31E-01 0.8740 3.16E-02 0.4213 2.71E-02 0.3613 1.91E-02 0.2547 5.32E-02 0.7093 1.31E-01 0.8733 3.16E-02 0.4213 2.71E-02 0.3613 1.91E-02 0.2547 5.32E-02 0.7093 1.31E-01 0.8733 3.16E-02 0.4213 2.78E-02 0.3707 1.91E-02 0.2547 5.32E-02 0.7093 1.32E-01 0.8780 3.16E-02 0.4213 2.73E-02 0.3640 1.91E-02 0.2547 5.32E-02 0.7093 1.31E-01 0.8747 (1) These doses are listed in mrem; they are calculated for the maximum individual for all batch liquid effluents (2) These doses are listed in mrad; they are calculated at the site boundary for batch & continuous gaseous effluents (0.4 miles NW)

(3) These doses are listed in mrem; they are calculated for the most likely exposed real individual (child) via all real pathways at 0.89 miles NW.

Limits used for calculation of percent (%) are from ODCM procedure 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).

ARERR Correction - Submitted October 2013 Attachment I Form 1/2-ENV-01.05.FO1 (page 34 of 38), Rev 2 Beaver Valley Power Station - Unit 2 Radioactive Effluent Release Report Calendar Year - 2009 Table 5B Assessment Of Radiation Doses RTL # A9.690E, Page 17 of 21 1.35E-02 0.2700 1.33E-02 0.2660 3.56E-03 0.0712 7.83E-03 0.1566 3.82E-02 0.3819.

4.53E-02 0.9060 2.61E-02 0.5220 9.09E-03 0.1818 1.31E-02 0.2620 9.36E-02 0.9359 1.70E-02 1.1333 1.72E-02 1.1467 6.94E-03 0.4627 1.25E-02 0.8333 5.36E-02 1.7880 5.37E-03 0.1074 5.51E-03 0.1102 4.02E-03 0.0804 6.49E-03 0.1298 2.14E-02 0.2139 1.25E-02 0.2500 1.41E-02 0.2820 5.91E-03 0.1182 852E-03 0.1704 4.10E-02 0.4103 7.61E-03 0.1522 7.63E-03 0.1526 4.61E-03 0.0922 7.19E-03 0.1438 2.70E-02 0.2704 7.77E-03 0.1554 1.23E-02 0.2460 6.62E-03 0.1324 1.75E-02 0.3500 4.42E-02 0,4419 0.00E+00 0.0000 7.27E-08 0.0000 1.13E-01 2.2600 5.17E-08 0.0000 1.13E-01 1.1300 0.00E+00 0.0000 3.42E-10 0.0000 3.98E-02 0.3980 1.77E-10 0.0000 3.98E-02 0.1990 0.OOE+00 0.0000 3.OOE-10 0.0000 2.1OE-07 0.0000 1,87E-04 0.0025 1.87E-04 0.0012 2.78E-03 0.0371 1.72E-03 0,0229 3.11E-04 0.0041 1.81E-02 0.2419 2.30E-02 0.1530 2.78E-03 0.0371 1.72E-03 0.0229 3.11E-04 0.0041 1.81E-02 0.2419 2.30E-02 0.1530 2.78E-03 0.0371 1.72E-03 0.0229 3.76E-04 0.0050 1.81E-02 0.2413 2.30E-02 0.1532 2.78E-03 0.0371 1.72E-03 0.0229 3.11E-04 0.0041 1.81E-02 0.2413 2.29E-02 0.1527 2.78E-03 0.0371 1.72E-03 0.0229 3.11E-04 0.0041 1.83E-02 0.2440 2.31E-02 0.1541 2.78E-03 0.0371 1.72E-03 0.0229 3.11E-04 0.0041 1.82E-02 0.2427 2.30E-02 0.1534 I

I (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).

BEAVER VALLEY POWER STATION ENVIRONMENTAL & CHEMISTRY SECTION Technical Report Approval:

2010 ARERR Corrections Submitted October 2013 Prepared by: Dr. Lara M. Renz D

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ARERR Correction - Submitted October 2013 RTL A9.690E, 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

ARERR Correction - Submitted October 2013 Form 1/2-ENV-O1.05.FO1 (page 3 of 39), Rev 3 RTL# A9.690E Beaver Valley Power Station - Units I & 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-01.05, "Compliance with Regulatory Guide 1.21 and Technical Specifications" NUREG-1301, "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors, Generic Letter 89-01, Supplement No. 1, April 1991" Regulatory Guide 1.21, "Measuring Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Material in Liquid and Gaseous Effluents from Light-Water Cooled Nuclear Power Plants, Revision 1, June 1974" BVPS Condition Report No. CRI 0-77489, Revision needed for 1/2-ODC-2.03.

BVPS Condition Report No. CRI 0-78575, Missing filter papers for effluent release samples.

BVPS Condition Report No. CR 10-79472, RM-DA-100 will be inoperable for greater than 30 days.

BVPS Condition Report No. CR10-80322, Reduced flow to PAB ventilation vent FR-VS-101.

BVPS Condition Report No. CR10-82309, Elevated tritium confirmed in 4 of 7 new groundwater wells.

BVPS Condition Report No. CR10-86844, 1/2-ODC-2.01, Liquid Effluents, requires mixing eductors for discharging tanks.

BVPS Condition Report No. CR 13-09691 is associated with the reporting of Abnormal Liquid Releases of drainage from Unit 2 laboratory sinks to the Catch Basin System.

ARERR Correction - Submitted October 2013 Form 1/2-ENV-01.05.F01 (page 4 of 39), Rev 3 RTL# A9.690E Beaver Valley Power Station - Units 1 & 2, Page Iv 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-I5) 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.

Decommissionin! File Update: There were no items added to the site decommissioning files in accordance with I OCFR50.75(g).

Abnormal Liquid Releases: There were two abnormal liquid releases that occurred in the 4th quarter of 2010. Details are described on page xv of this report.

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 I or 2 high level liquid waste was processed (e.g., coolant recovery waste) it was performed at Unit 1, because it has a carbon pre-conditioning filter.

Gaseous Radwaste Treatment System: The site operated via a shared Gaseous Radwaste Treatment System, even though each Unit has its own charcoal delay beds and storage/decay tanks. Shared operation allowed either Unit to process gaseous waste at the Unit of origin, or at the other Unit. Typically, when Unit I 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.

ARERR Correction - Submitted October 2013 Form 1/2-ENV-01.05.F01 (page 15 of 39), Rev 3 RTL# A9.690E Beaver Valley Power Station - Units I & 2, Page xv Radioactive Effluent Release Report Calendar Year - 2010 Results of Abnormal Releases Abnormal Liquid Releases: On June 22, 2013 Cobalt-58 was identified in the Unit 2 Building and Yard Drain System.

The Cobalt-58 was identified during Chemistry sampling of the Unit 2 catch basin system as part of Beaver Valley's commitment to NRC Bulletin 80-10.

The event resulted in a release of Licensed Radioactive Material (LRM) from the site boundary. The event is characterized as an Abnormal Release in accordance with Regulatory Guide 1.21, Revision 1.

The source of radioisotopes found in the Unit 2 Building and Yard Drain System was determined to be from cup sink drains in the Unit 2 Hot Lab which by original plant design are routed to the Unit 2 Turbine Building drains.

The Unit 2 Turbine Building Drains discharge to the Unit 2 catch basin and conveyed to the Ohio River. Laboratory instruments used for RCS analysis are drained to the Unit 2 Hot Lab cup sink drains and can be confirmed to drain here during analyses since installation of new equipment in 2009.

Therefore, two Abnormal Release permits were calculated for the 4th quarter of 2010 and corrections were made to the 2010 Annual RETS and REMP Reports (CR#2013-09691).

Abnormal Gas Releases: None

ARERR Correction - Submitted October 2013 Form 1/2-ENV-01.05.F01 (page 19 of 39), Rev 3 Beaver Valley Power Station - Units 1 & 2 Radioactive Effluent Release Report Calendar Year - 2010 Supplemental Information Page RTL# A9.690E, Page 1 of 21 Annual Unit 1 or2 Dose: 15 mrem to Any Organ al Unit 1 or 2 Dose: 3 mrem to Total Body, & 10 mrem to Any Oroan Release Rate: 500 mrem/vr to Total Body. &

Site Release Rate: 1500 mremlyr to Any Organ Site Release Concentration: 10 times 10 CFR 20 Appendix B, Table 2, EC's e Gamma Spectrometry, Liquid Scintillation Counter Gamma Soectrometrv. Prooortional Counter 3e Gamma Spectrometry, Proportional Counter, Liquid Scintillation 2J NONE I

NONE I

NONE I NONE I

0.OOE+00 I 0.00E+00 I 0.OOE+00 1I 00FO+00 I

ARERR Correction - Submitted October 2013 Form 1/2-ENV-01.05.FOI (page 28 of 39), Rev 3 Beaver Valley Power Station - Units I & 2 Radioactive Effluent Release Report Calendar Year - 2010 Table 2B-B Liquid Effluents - Batch Releases RTL # A9.690E, Page 10 of 21 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 3.71E-04 4.37E-03 1.50E-02 7.15E-03 LLD 2.65E-02 LLD LLD LLD 3.41 E-09 3.41 E-09 3.72E-05 LLD 7.57E-06 1.02E-04 1.47E-04 6.95E-03 1.46E-03 3.30E-03 3.18E-02 4.35E-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 1.55E-09 4.94E-03 LLD LLD 1.72E-06 LLD 1.72E-06 LLD LLD LLD 5.60E-10 5.60E-10 LLD LLD LLD 8.30E-1 1 8.30E-1 1 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 4.54E-10 4.54E-10 NONE I

NONE NONE NONE NONE 1.93E-02 2.68E-02I 1.94E-02 I 4.96E-02 I 1.15E-01 LLD LLD LLD LLD LLDNON LLD 3.47E-05 4.71E-05 LLD 8.18E-05 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD NONE I NNE NON J

ONENONE ND 347E-5 4.1 E-5 ND 8.18E-05 LLD = Below the Lower Limit of Detectability, in uCi/mi (Table 4)

  • Carbon-14 data provided in Attachment 3 from Key Solutions, Inc.

I

ARERR Correction - Submitted October 2013 Form 1/2-ENV-01.05.F01 (page 34 of 39), Rev 3 Beaver Valley Power Station - Unit 1 Radioactive Effluent Release Report Calendar Year - 2010 Table 5A Assessment Of Radiation Doses RTL # A9.690E, Page 16 of 21 I

2.15E-01 4.3000 I 1.09E-07 0.0000 I 0.OOE+00 0.0000 2.89E-05 0.0006 1 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 7.21 E-03 0.0961 1.64E-02 0.2187 8.07E-02 0.5381 (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).

I

ARERR Correction - Submitted October 2013 Form 1/2-ENV-011.05.F01 (page 35 of 39), Rev 3 Beaver Valley Power Station - Unit 2 Radioactive Effluent Release Report Calendar Year - 2010 Table 5B Assessment Of Radiation Doses RTL # A9.690E, Page 17 of 21 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).

6 ARERR Correction - Submitted October 2013 Form 1/2-ENV-01.05.F01 (page 37 of 39), Rev 3 Beaver Valley Power Station - Units I & 2 RTL # A9.690E, Page 19 of 21 Radioactive Effluent Release Report Calendar Year - 2010 Table 7 Total Dose Commitments, Total Effective Dose Equivalents and Population Doses 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).

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 reDort oeriod.

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)

BEAVER VALLEY POWER STATION ENVIRONMENTAL & CHEMISTRY SECTION Technical Report Approval:

2011 ARERR Corrections Submitted October 2013 Prepared by: Dr. Lara M. Renz C)

Date: 7s-,

Date:

i2 j Prepared by: Rebecca Novak 1A 4,

Reviewed by: Beth H. Furdak Date:

tl,/115 Approved by: Donald Salera Date:

ARERR Correction - Submitted October 2013 RTL A9.690E, Page i Form 1/2-ENV-01.05.F01 (page 1 of 39), Rev 3 Beaver Valley Power Station - Units I & 2 2011 Radioactive Effluent Release Report FirstEnergy Nuclear Operating Company FENOC Beaver Valley Power Station - Units I & 2 Unit 1 License No. DPR-66 Unit 2 License No. NPF-73

ARERR Correction - Submitted October 2013 Form 1/2-ENV-01.05.FO1 (page 3 of 39), Rev 3 RTL# A9.690E Beaver Valley Power Station - Units I & 2, Page III Radioactive Effluent Release Report Calendar Year - 2011 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 I/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 Pressuri~ed 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. 10-80322, Reduced Flow to PAB Ventilation Vent FR-VS-101 BVPS Condition Report No. 10-82309, Elevated Tritium Confirmed in 4 of 7 New Groundwater Wells BVPS Condition Report No. 10-85877, Se-75 Discharge via the UI/U2 Process Vent BVPS Condition Report No. 11-89832, Repeat Maintenance - 2HVS-RQI 09B, C. and D Loss of Process Flow BVPS Condition Report No. 11-92214, Documentation of 1-131 in BVPS Samples After Fukushima Crisis BVPS Condition Report No. 11-92328, RM-IMS-100C Failed Downscale During IOST-43.5 Performance BVPS Condition Report No. 11-92850, U-2 Aux Boiler Room Contamination Event BVPS Condition Report No. 11-93037, Documentation of 1-131 Found in REMP Milk Sample After Fukushima BVPS Condition Report No. 11-93095, Failure of Aux Feedwater Drain Rad Monitor BVPS Condition Report No. 11-94162, RM-IMS-100C Not Returned to Operable Within 30 Days BVPS Condition Report No. 11-96782, IOCFR50.75(G) Files Not Updated with Groundwater Well Data BVPS Condition Report No. 11-97516, REMP TLD Station 488 Repeatedly Vandalized BVPS Condition Report No. 11-97853, 2MSS-RQIOIC Alarms BVPS Condition Report No. 2011-00106. Evaluate Spiking Trend for 2MSS-RQIOIC, Main Steam Rad Monitor BVPS Condition Report No. 2011-00386, RM-IVS-109 Ch 10 Does Not Read Correctly on Return to Service BVPS Condition Report No. 2011-00688, Damaged Detector on BV-1VS-I 10 BVPS Condition Report No. 2011-00749, 2MSS-RQIOIC High/Alert alarms during 20ST-24.4 BVPS Condition Report No. 2011-01038, Rx Building/SLCRS Rad Monitor Exceeds 30 Days Inoperable BVPS Condition Report No. 2011-01525, ECP Setpoint Change Not Effectively Implemented, Resulting in Wasted Technician Time - Error Trap BVPS Condition Report No. 2011-02332, Inability to Meet ODCM Requirements for REMP Milk Sampling in 2011 BVPS Condition Report No. 2011-02350, 2MSS-RQI01C Not Returned to Service Within 30 Days BVPS Condition Report No. 2012-04412, Unable to Meet Required LLD for Ce-144 in Liquid Liter Bottle Geometry BVPS Condition Report No. CR 13-09691 is associated with the reporting of Abnormal Liquid Releases of drainage from Unit 2 laboratory sinks to the Catch Basin System.

ARERR Correction - Submitted October 2013 Form 1/2-ENV-01.05.F01 (page 4 of 39), Rev 3 RTL# A9.690E Beaver Valley Power Station - Units 1 & 2, Page iv Radioactive Effluent Release Report Calendar Year - 2011 Executive Summary - Liquid and Gaseous Effluent Control (Part I of 2)

Onsite Groundwater Monitoring: Twenty-three (23) on-site monitoring wells were sampled in both sampling periods in 2011. No new wells were installed and no wells were retired. Fifteen (15) wells were less than the pre-operational mean (440 pCi/L) during all sample periods in 2011. Two (2) wells were >440 pCi/L, but <2000 pCi/L. Six (6) wells were >2000 pCi/L, but <30,000 pCi/L with only a single well (MW-16)

>20,000 pCi/L. The NEI/FENOC communication level was reached for MW-12S & MW-I 2D during 2007.

Notification to local, state & federal agencies was performed on 10/08/07. Additional communication for new well results was performed on 09/08/10 for those new wells that exceeded 2000 pCi/L. There were no wells that reached the 2000 pCi/L Communication Level for the first time in 2011. 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: Two items were added to the site decommissioning files in accordance with IOCFR50.75(g). These items included extending the condition of onsite groundwater contamination for the new 2010 monitoring wells and the discovery of Licensed Radioactive Material (LRM) in the Unit I and Unit 2 Nitrogen Systems. See Enclosure 2, page xvi for additional details.

Abnormal Liquid Releases: There were two abnormal liquid releases that occurred in the 1st and 2nd quarters of 2011. Details are described on page xv of this report.

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 I, 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 I or 2 went to a shutdown condition, the gaseous waste was transferred for storage and decay at Unit 2, because Unit 2 has four (4) additional storage tanks.

ARERR Correction - Submitted October 2013 Form 1/2-ENV-01.05.FO1 (page 15 of 39), Rev 3 RTL# A9.690E Beaver Valley Power Station - Units I & 2, Page xv Radioactive Effluent Release Report Calendar Year - 2011 Results of Abnormal Releases Abnormal Liquid Releases: On June 22, 2013 Cobalt-58 was identified in the Unit 2 Building and Yard Drain System.

The Cobalt-58 was identified during Chemistry sampling of the Unit 2 catch basin system as part of Beaver Valley's commitment to NRC Bulletin 80-10. The event resulted in a release of Licensed Radioactive Material (LRM) from the site boundary. The event is characterized as an Abnormal Release in accordance with Regulatory Guide 1.21, Revision 1.

The source of radioisotopes found in the Unit 2 Building and Yard Drain System was determined to be from cup sink drains in the Unit 2 Hot Lab which by original plant design are routed to the Unit 2 Turbine Building drains.

The Unit 2 Turbine Building Drains discharge to the Unit 2 catch basin and conveyed to the Ohio River. Laboratory instruments used for RCS analysis are drained to the Unit 2 Hot Lab cup sink drains and can be confirmed to drain here during analyses since installation of new equipment in 2009.

Therefore, two Abnormal Release permits were calculated for the 1 st and 2nd quarters of 2011 and corrections were made to the 2011 Annual RETS and REMP Reports (CR#2013-09691).

Abnormal Gas Releases: None

ARERR Correction - Submitted October 2013 Form 1/2-ENV-01.05.FO1 (page 19 of 39), Rev 3 Beaver Valley Power Station - Units 1 & 2 Radioactive Effluent Release Report Calendar Year - 2011 Supplemental Information Page RTL# A9.690E, Page 1 of 22

,nnual Unit 1 or 2 Dose: 10 mrad from Gamma. & 20 mrad from Beta il Unit 1 or 2 Dose: 15 mrem to Anv Oraan

,nnual Unit 1 or 2 Dose: 3 mrem to Total Body, & 10 mrem to Any Oroan Site Release Rate: 500 mrem/yr to Total Body, & 3000 mrem/yr to the Skin I Site Release Rate: 1500 mrem/vr to Anv Oman Site Release Concentration: 10 times 10 CFR 20 Apoendix B, Table 2. EC'sI 3e Gamma Spectrometry, Liquid Scintillation Counter 3e Gamma Soectrometrv. Proportional Counter Se Gamma Spectrometry. Proportional Counter. Liauid Scintillation NONE I NONE I NONE I NONE I

0.OOE+00 I 0.OOE+00 I 0.00E+00 I 0.OOE+00 I

ARERR Correction - Submitted October 2013 Form 1/2-ENV-01.05.FO1 (page 28 of 39), Rev 3 Beaver Valley Power Station - Units I & 2 Radioactive Effluent Release Report Calendar Year - 2011 Table 2B-B Liquid Effluents - Batch Releases RTL # A9.690E, Page 10 of 22 LLD LLD LLD LLD LLD 4,98E-05 LLD LLD LLD 4.98E-05 1.38E-04 1.25E-03 LLD LLD 1.39E-03 1.39E-04 4.72E-06 4.OOE-05 LLD 1.84E-04 2.58E-03 2.03E-03 4.25E-03 2.34E-03 1.12E-02 6.42E-05 1.88E-03 6.39E-05 LLD 2.01E-03 7.73E-05 1.41E-05 1.54E-04 4.45E-04 6.91E-04 1.66E-02 1.50E-02 1.20E-02 2.75E-03 4.64E-02 4.42E-03 1.20E-03 1.66E-03 6.22E-04 7.90E-03 1.85E-04 LLD LLD 2.16E-05 2.07E-04 4.26E-05 LLD LLD LLD 4.26E-05 9.13E-05 LLD LLD LLD 9.13E-05 1.70E-05 2.93E-04 4.27E-04 2.54E-06 7.40E-04 3.21 E-04 LLD LLD LLD 3.21 E-04 LLD LLD LLD LLD LLD 3.44E-08 LLD LLD LLD 3.44E-08 LLD 5.58E-05 LLD LLD 5.58E-05 1.59E-03 2.09E-04 4.29E-03 1.95E-04 6.28E-03 9.24E-06 LLD LLD LLD 9.24E-06 1.70E-04 1.51 E-03 1.35E-03 2.39E-04 3.28E-03 5.09E-03 3.79E-03 5.38E-03 1.74E-03 1.60E-02 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 3.13E-03 2.21E-03 4.19E-05 4.47E-05 5.43E-03 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD NONE NONE NONE NONE NONE 3.47E-02 2.95E-02 2.97E-02 8.40E-03 1.02E-01 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 7.06E-06 LLD LLD LLD 7.06E-06 N/A N/A N/A N/A N/A I

I NONE NONE NONE NONE

[

NONE 7.06E-06 ND ND ND 7.06E-06 LLD = Below the Lower Limit of Detectability, in uCi/ml (Table 4)

ARERR Correction - Submitted October 2013 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 - 2011 Table 5A Assessment Of Radiation Doses RTL # A9.690E, Page 16 of 22 5.89E-02 1.1780 4.15E-02 0.8300 5.26E-04 0.0105 7.07E-04 0.0141 1.02E-01 1.0163 8.24E-02 1.6480 6.31E-02 1.2620 1,80E-03 0.0360 3.1OE-03 0.0620 1.50E-01 1.5040 5.60E-02 3.7333 4.35E-02 2.9000 1.59E-03 0.1060 2.75E-03 0.1833 1.04E-01 3.4613 3.70E-03 0.0740 6.20E-03 0.1240 1.1OE-03 0.0220 2.12E-03 0.0424 1.31E-02 0.1312 3.06E-02 0.6120 2.54E-02 0.5080 1.31E-03 0.0262 2.45E-03 0.0490 5.98E-02 0.5976 1.25E-02 0.2500 1.26E-02 0.2520 1.20E-03 0.0240 2.23E-03 0.0446 2.85E-02 0.2853 1.22E-02 0.2440 9.95E-03 0.1990 2.OOE-03 0.0400 2.54E-03 0.0508 2.67E-02 0.2669 2.97E-07 0.0000 3.12E-01 6.2400 0.OOE+00 0.0000 0.OOE+00 0.0000 3.12E-01 3.1200 6.27E-10 0.0000 1.16E-01 1.1600 0.OOE+00 0.0000 0.OOE+00 0.0000 1.16E-01 0.5800 1.71E-08 0.0000 3.29E-08 0.0000 3.77E-09 0.0000 1.11E-09 0.0000 5.49E-08 0.0000 2.40E-02 0.3200 1.35E-02 0.1800 7.31E-03 0.0975 1.39E-02 0.1853 5.87E-02 0.3914 2.40E-02 0.3200 1.35E-02 0.1800 7.31E-03 0.0975 1.39E-02 0.1853 5.87E-02 0.3914 2.40E-02 0.3200 1.35E-02 0.1800 7.31E-03 0.0975 1.39E-02 0.1853 5.87E-02 0.3914 2.40E-02 0.3200 1.35E-02 0.1800 7.31E-03 0.0975 1.39E-02 0.1853 5.87E-02 0.3914 2.40E-02 0.3200 1.35E-02 0.1800 7.31E-03 0.0975 1.39E-02 0.1853 5.87E-02 0.3914 2.40E-02 0.3200 1.35E-02 0.1800 7.31E-03 0.0975 1.39E-02 0.1853 5.87E-02 0.3914 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).

ARERR Correction - Submitted October 2013 Form 1/2-ENV-01.05.FO1 (page 35 of 39), Rev 3 Beaver Valley Power Station - Unit 2 Radioactive Effluent Release Report Calendar Year - 2011 Table 5B Assessment Of Radiation Doses RTL # A9.690E, Page 17 of 22 5.89E-02 1.1780 4.15E-02 0.8300 5.26E-04 0.0105 7.07E-04 0.0141 1.02E-01 1.0163 8.24E-02 1.6480 6.31E-02 1.2620 1.80E-03 0.0360 3.1OE-03 0.0620 1.50E-01 1.5040 5.60E-02 3.7333 4.35E-02 2.9000 1.59E-03 0.1060 2.75E-03 0.1833 1.04E-01 3.4613 3.70E-03 0.0740 6.20E-03 0.1240 1.10E-03 0.0220 2.12E-03 0.0424 1.31E-02 0.1312 3.06E-02 0.6120 2.54E-02 0.5080 1.31E-03 0.0262 2.45E-03 0.0490 5.98E-02 0.5976 1.25E-02 0.2500 1.26E-02 0.2520 1.20E-03 0.0240 2.23E-03 0.0446 2.85E-02 0.2853 1.22E-02 0.2440 9.95E-03 0.1990 2.00E-03 0.0400 2.54E-03 0.0508 2.67E-02 0.2669 1.36E-02 0.2720 2,22E-03 0.0444 0.OOE+00 0.0000 1.03E-01 2.0600 1.19E-01 1.1882 2.26E-02 0.2260 1.79E-03 0.0179 0.OOE+00 0.0000 3.80E-02 0.3800 6.24E-02 0.3120 1.71E-08 0.0000 1.20E-04 0.0016 2.08E-05 0.0003 1.71E-04 0.0023 3.12E-04 0.0021 5.77E-04 0.0077 1.14E-03 0.0152 1.38E-03 0.0184 1,06E-03 0.0141 4.16E-03 0.0277 5.77E-04 0.0077 1.15E-03 0.0153 1.38E-03 0.0184 1.07E-03 0.0143 4.18E-03 0.0278 5.77E-04 0.0077 1.25E-03 0.0167 1.38E-03 0.0184 1.06E-03 0.0141 4.27E-03 0.0284 5.77E-04 0.0077 1.13E-03 0.0151 1.38E-03 0.0184 1.06E-03 0.0141 4.15E-03 0.0276 5.77E-04 0.0077 1.28E-03 0.0171 1.39E-03 0.0185 1.14E-03 0.0152 4.39E-03 0.0292 5.77E-04 0.0077 1.17E-03 0.0156 1.38E-03 0.0184 1.07E-03 0.0143 4.20E-03 0.0280 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).

ARERR Correction - Submitted October 2013 Form 1/2-ENV-01.05.FO1 (page 37 of 39), Rev 3 Beaver Valley Power Station - Units I & 2 Radioactive Effluent Release Report Calendar Year - 2011 Table 7 Total Dose Commitments, Total Effective Dose Equivalents and Population Doses RTL # A9.690E, Page 20 of 22 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 3.66 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).

The radiation doses for MEMBER(S) OF THE PUBLIC due to their activities inside the site boundary are not greater than the doses listed in this table to show compliance with 40 CFR Part 190 or 10 CFR 20.1301. Evaluations have shown that exposure time for Individuals not occupationally associated with the plant site is minimal in comparison to the exposure time considered for the dose calculation at or beyond the site boundary. Therefore, a separate assessment of radiation doses from radioactive effluents to MEMBER(S) OF THE PUBLIC, due to their activities inside the site boundary, is not necessary for this report period.

0-60 mile Total Population Dose from liquid and gaseous effluents a 376 man-mrem (Total Body) 0-60 mile Average Population Dose from liquid and gaseous effluents 0 0.0000941 man-mrem (Total Body)

BEAVER VALLEY POWER STATION ENVIRONMENTAL & CHEMISTRY SECTION Technical Report Approval:

2012 ARERR Corrections Submitted October 2013 Prepared by: Dr. Lara M. Renz Date:

Prepared by: Rebecca Novak Date:

.\\Z!\\\\

Reviewed by: Beth H. Furdak Date:

9/f//3 Approved by: Donald Salera Date:_________

ARERR Correction - Submitted October 2013 RTL A9.690E, Page i Form 1/2-ENV-01.05.FO1 (page 1 of 39), Rev 3 Beaver Valley Power Station - Units 1 & 2 2012 Radioactive Effluent Release Report FirstEnergy Nuclear Operating Company FENOC Beaver Valley Power Station - Units I & 2 Unit 1 License No. DPR-66 Unit 2 License No. NPF-73

ARERR Correction - Submitted October 2013 Form 1/2-ENV-01.05.FO1 (page 3 of 39), Rev 3 RTL# A9.690E Beaver Valley Power Station - Units 1 & 2, Page iii Radioactive Effluent Release Report Calendar Year - 2012 Executive Summary - Report Submittal Requirements Report Submittal and Requirements: The report was prepared and submitted in accordance with the requirements contained in the following documents:

BVPS Integrated Technical Specifications, Administrative Control 5.6.2 Offsite Dose Calculation Manual (ODCM) procedure 1/2-ODC-3.03, "Controls for RETS and REMP Programs, " Attachment U, Control 6.9.3 BVPS procedure 1/2-ENV-01.05, "Compliance with Regulatory Guide 1.21 and Technical Specifications" NUREG-1301, "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors, Generic Letter 89-01, Supplement No. 1, April 1991" Regulatory Guide 1.21, "Measuring Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Material in Liquid and Gaseous Effluents from Light-Water Cooled Nuclear Power Plants, Revision 1, June 1974" BVPS Condition Report No. 2012-04412, Unable to meet required LLD for Ce-144 in Liquid Liter Bottle Geometry.

BVPS Condition Report No. 2012-02583, DIE process for Phase 2 of Coolant Recovery Project did not address ODCM..

BVPS Condition Report No. 2012-05875, Antimony-126 identified in the liquid waste system.

BVPS Condition Report No. 2012-10428, Co-58 identified in the Catch Basin System.

BVPS Condition Report No 2012-10727 -Groundwater Well Analysis Could Not Achieve Lower Limit of Detection (LLD) for Ba-La-140 due to Sample Age BVPS Condition Report No. 2012-15547, Co-58 identified in the Catch Basin System.

BVPS SAP Notification No. 600739155, 2012 RETS and REMP Report BVPS SAP Notification No. 600747531, Update 1/2-ODC-2.01 for RM-1RW-100 BVPS Condition Report No. CR 13-09691 is associated with the reporting of Abnormal Liquid Releases of drainage from Unit 2 laboratory sinks to the Catch Basin System.

ARERR Correction - Submitted October 2013 Form 1/2-ENV-01.05.FO0 (page 4 of 39), Rev 3 RTL# A9.690E Beaver Valley Power Station - Units I & 2, Page iv Radioactive Effluent Release Report Calendar Year - 2012 Executive Summary - Liquid and Gaseous Effluent Control (Part I of 2)

Onsite Groundwater Monitoring: Twenty-three (23) on-site monitoring wells were sampled in the spring and fall sampling periods in 2012. The six (6) highest concentration monitoring wells were sampled in a summer sampling period for additional trend data. No new wells were installed and no wells were retired.

Sixteen (16) wells returned results of less than the pre-operational mean (440 pCi/L) during all sample periods in 2012. One (1) well returned results >440 pCi/L, but <2000 pCi/L. Six (6) wells returned results

>2000 pCi/L. No wells exceeded 20,000 pCi/L with the highest concentration recorded as 19,200 pCi/L.

The NEI/FENOC communication level was reached for MW-12S & MW-12D during 2007. Notification to local, state & federal agencies was performed on 10/08/07. Additional communication for new well results was performed on 09/08/10 for those new wells that exceeded 2000 pCi/L. There were no wells that reached the 2000 pCi/L Communication Level for the first time in 2012. 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. Mitigation activities (catch basin sleeving) to prevent tritiated condensate water from reaching the groundwater were completed 12/17/11.

Onsite Spills: There were no onsite liquid spills >100 gallons.

Decommissioning File Update: One item was added to the site decommissioning files in accordance with 10CFR50.75(g). This item included the discovery of Licensed Radioactive Material (LRM) in the Unit 2 Catch Basin System. See Enclosure 2, Page xvi for additional details.

Abnormal Liquid Releases: There were four abnormal liquid releases that occurred in the 2 nd and 4t quarters of 2012. Details are described on page xv of this report.

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.

ARERR Correction - Submitted October 2013 Form 1/2-ENV-01.05.F01 (page 15 of 39), Rev 3 RTL# A9.690E Beaver Valley Power Station - Units I & 2, Page xv Radioactive Effluent Release Report Calendar Year - 2012 Results of Abnormal Releases Abnormal Liquid Releases: On June 22, 2013 Cobalt-58 was identified in the Unit 2 Building and Yard Drain System.

The Cobalt-58 was identified during Chemistry sampling of the Unit 2 catch basin system as part of Beaver Valley's commitment to NRC Bulletin 80-10.

The event resulted in a release of Licensed Radioactive Material (LRM) from the site boundary. The event is characterized as an Abnormal Release in accordance with Regulatory Guide 1.21, Revision 1.

The source of radioisotopes found in the Unit 2 Building and Yard Drain System was determined to be from cup sink drains in the Unit 2 Hot Lab which by original plant design are routed to the Unit 2 Turbine Building drains, The Unit 2 Turbine Building Drains discharge to the Unit 2 catch basin and conveyed to the Ohio River.

Laboratory instruments used for RCS analysis are drained to the Unit 2 Hot Lab cup sink drains and can be confirmed to drain here during analyses since installation of new equipment in 2009.

Therefore, four Abnormal Release permits were calculated for the 2nd and 4th quarters of 2012 and corrections were made to the 2012 Annual RETS and REMP Reports (CR#2013-09691).

Abnormal Gas Releases: None

ARERR Correction - Submitted October 2013 Form 1/2-ENV-01.05.F01 (page 19 of 39), Rev 3 Beaver Valley Power Station - Units 1 & 2 Radioactive Effluent Release Report Calendar Year - 2012 Supplemental Information Page RTL# A9.690E, Page 1 of 21 Annual Unit 1 or 2 Dose: 10 mrad from Gamma, & 20 mrad from Beta 1 or 2 Dose: 15 mrem to Anv Oraan nual Unit 1 or 2 Dose: 3 mrem to Total Body. & 10 mrem to Any Oroan 3ite Release Rate: 500 mrem/yr to Total Body, & 3000 mrem/yr to the Skin I Site Release Rate: 1500 mrem/yr to Any Organ Release Concentration: 10 times 10 CFR 20 ADDendix B. Table 2. EC'sI

,e Gamma Soectrometrv. Prooortional Counter SDectrometrv. Prooortional Counter. Liauid Scintillation NONE I NONE I NONE I NONE I

0.OOE+00 I 0.OOE+00 I 0,OOE+00 I 0.OOE+00 I

ARERR Correction - Submitted October 2013 Form 1/2-ENV-01.05.FO1 (page 28 of 39), Rev 3 Beaver Valley Power Station - Units I & 2 Radioactive Effluent Release Report Calendar Year - 2012 Table 2B-B Liquid Effluents - Batch Releases RTL # A9.690E, Page 10 of 21 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 5.68E-04 LLD 5.39E-04 1.11 E-03 8.41 E-06 3.45E-05 5.27E-06 4.89E-05 9.71 E-05 2.72E-03 2.50E-03 9.63E-04 1.11E-03 7.29E-03 LLD 2.30E-09 LLD 3.07E-04 3.07E-04 1.31E-05 3.OOE-05 LLD 2.84E-05 7.15E-05 1.70E-03 5.49E-03 1.49E-03 1.47E-02 2.33E-02 1.65E-03 2.55E-03 6.08E-04 1.29E-03 6.10E-03 LLD 3.09E-05 LLD 2.91 E-05 6.01 E-05 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD 2.18E-04 LLD 2.52E-04 4.71E-04 LLD 2.38E-09 LLD LLD 2.38E-09 LLD LLD LLD LLD LLD LLD 3.81E-10 LLD 7.53E-09 7.91E-09 LLD 9.25E-1 1 LLD 1.04E-05 1.04E-05 2.65E-04 4.17E-04 3.40E-04 3.32E-04 1.35E-03 LLD 3.54E-05 LLD 4.64E-07 3.58E-05 1.01E-04 1.56E-04 7.30E-05 4.56E-04 7.86E-04 1.89E-03 1.07E-03 2.15E-03 2.92E-03 8.03E-03 LLD LLD LLD LLD LLD LLD LLD 1.22E-06 LLD 1.22E-06 LLD LLD LLD LLD LLD 1.66E-04 4.34E-04 1 02E-03 1.73E-03 3.35E-03 LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD LLD NONEI NONE INONE NONE NONE]

8.51 E-03 1.35E-02 6.65E-03 2.37E-02 5.24E-02 LLD LLD LLD LLD LLD LLD LLD 1.00E-05 3.52E-05 4.52E-05 LLD LLD LLD LLD LLD LLD LLD LLD LLD

,LLD N/A N/A N/A N/A LLD NONE NONE NONE NONE NONE ND ND 1.00E-05 3.52E-05 4.52E-05 LLD = Below the Lower Limit of Detectability, in uCi/ml (Table 4)

ARERR Correction - Submitted October 2013 Form 1/2-ENV-01.05.F01 (page 34 of 39), Rev 3 Beaver Valley Power Station - Unit I Radioactive Effluent Release Report Calendar Year - 2012 Table 5A Assessment Of Radiation Doses RTL # A9.690E, Page 16 of 21 2.60E-03 0.0520 I 6.49E-03 0.1298 I 9.08E-03 0.1816 I 2.56E-02 0.5120 I 4.38E-02 0.4377 1.72E-02 0.3440 2.23E-02 0.4460 1.98E-02 0.3960 4.74E-02 0.9480 1.07E-01 1.0670 1.59E-02 1.0600 1.92E-02 1.2800 1.56E-02 1.0400 3.54E-02 2.3600 8.61E-02 2.8700 1.36E-02 0.2720 1.33E-02 0.2660 7.43E-03 0.1486 1.21E-02 0.2420 4.64E-02 0.4643 1.48E-02 0.2960 1.64E-02 0.3280 1.16E-02 0.2320 2.40E-02 0.4800 6.68E-02 0.6680 1.41E-02 0.2820 1.43E-02 0.2860 8.83E-03 0.1766 1.61E-02 0.3220 5.33E-02 0.5333]

1.42E-02 0.2840 1.53E-02 0.3060 7.81E-03 0.1562 1.67E-02 0.3340 5.40E-02 0.5401 1.28E-01 2.5600 1.22E-07 0.0000 8.96E-07 0.0000 4.66E-08 0.0000 1.28E-01 1.2800 4.69E-02 0.4690 5.35E-10 0.0000 1.81E-09 0.0000 2.18E-10 0.0000 4.69E-02 0.2345 2.91E-06 0.0000 1.22E-03 0.0163 4.12E-05 0.0005 5.43E-06 0.0001 1.27E-03 0.0085 1.17E-02 0.1560 1.35E-02 0.1800 1.45E-02 0.1933 9.77E-03 0.1303 4.95E-02 0.3298 1.17E-02 0.1560 1.35E-02 0.1800 1.45E-02 0.1933 9.77E-03 0.1303 4.95E-02 0.3298 1,17E-02 0.1560 1.34E-02 0.1787 1.45E-02 0.1933 9.77E-03 0.1303 4.94E-02 0.3291 1.17E-02 0.1560 1.34E-02 0.1787 1.45E-02 0.1933 9.77E-03 0.1303 4.94E-02 0.3291 1.18E-02 0.1573 1.43E-02 0.1907 1.45E-02 0.1933 9.78E-03 0.1304 5.04E-02 0.3359 1.18E-02 0.1573 1.36E-02 0.1813 1.45E-02 0.1933 9.77E-03 0.1303 4.97E-02 0.3311 (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).

ARERR Correction - Submitted October 2013 Form 1/2-ENV-01.05.F01 (page 35 of 39), Rev 3 Beaver Valley Power Station - Unit 2 Radioactive Effluent Release Report Calendar Year - 2012 Table 5B Assessment Of Radiation Doses RTL # A9.690E, Page 17 of 21 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).

ARERR Correction - Submitted October 2013 Form 1/2-ENV-01.05.FO1 (page 37 of 39), Rev 3 Beaver Valley Power Station - Units 1 & 2 RTL # A9.690E, Page 19 of 21 Radioactive Effluent Release Report Calendar Year - 2012 Table 7 Total Dose Commitments, Total Effective Dose Equivalents and Population Doses I

I 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 4.13 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).

The radiation doses for MEMBER(S) OF THE PUBLIC due to their activities inside the site boundary are not greater than the doses listed in this table to show compliance with 40 CFR Part 190 or 10 CFR 20.1301. Evaluations have shown that exposure time for individuals not occupationally associated with the plant site is minimal in comparison to the exposure time considered for the dose calculation at or beyond the site boundary. Therefore, a separate assessment of radiation doses from radioactive effluents to MEMBER(S) OF THE PUBLIC, due to their activities inside the site boundary, is not necessary for this report period.

0-50 mile Total Population Dose from liquid and gaseous effluents =

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

0.0001142 man-mrem (Total 8ody)

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