ML12130A198

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2011 Radioactive Effluent Release Report
ML12130A198
Person / Time
Site: Braidwood  Constellation icon.png
Issue date: 04/26/2012
From: Enright D
Exelon Generation Co, Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BW120042
Download: ML12130A198 (239)
v • d • e


Text

Exelon Generation Company, LLC www.exe]oncorp.com Exeln NUClear Braidwood Station 35100 South Rt 53, Suite 84 Braceville, IL60407-9619 April 26, 2012 BW120042 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 Braidwood Station, Units I and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457

Subject:

2011 Radioactive Effluent Release Report The attached document includes the Radioactive Effluent Release Report for Braidwood Station. This report is beingsubmitted in accordance with 10 CFR 50.36a, "Technical specifications on effluents from nuclear power reactors," and Technical Specification 5.6.3, "Radioactive Effluent Release Report," and includes a summary of radiological liquid and gaseous effluents and solid waste released from the site from January 2011 through December 2011. In addition, a copy of the Braidwood Station Offsite Dose Calculation Manual is included in accordance with Technical Specification 5.5.1, "Offsite Dose Calculation Manual (ODCM)."

If you have any questions regarding this information, please contact Chris VanDenburgh Regulatory Assurance Manager, at (815) 417-2800.

Respectfully, Daniel J. Enright Site Vice President Braidwood Station cc: US NRC Regional Administrator, Region III US NRC Senior Resident Inspector - Braidwood Station NRR Project Manager - Braidwood Station Illinois Emergency Management Agency - Division of Nuclear Safety A~c9c

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2011 UNIT 1 AND 2 (Docket Numbers,50-456 and 50-457)

DOCUMENT INDEX General Overview/Discussion .......................................................................................................... 2 Unit 1 Gas Releases - Summation of All Releases ............................................................................... 6 Unit 1 Gas Releases - Continuous Mode and Batch Mode ................................................................. 7 Unit 2 Gas Releases - Summation of All Releases .............................................................................. 9 Unit 2 Gas Releases - Continuous Mode and Batch Mode ................................................................. 10 Unit 1 Liquid Releases - Summation of All Releases .......................................................................... 12 Unit 1 Liquid Releases - Continuous Mode and Batch Mode ............................................................... 13 Unit 2 Liquid Releases - Summation of All Releases .......................................................................... 14 Unit 2 Liquid Releases - Continuous Mode and Batch Mode ............................................................... 15 Solid Radioactive W aste Unit 1 and Unit 2 Combined .......................................................................... 16 S u m m a rie s ............................................................................................................................................... 18 A p p e n d ix A - LLD T a b le s .......................................................................................................................... 21 Appendix B - Supplemental Information .......................................... ............................................. 24 R E T D A S R e p o rts ..................................................................................................................................... 29 - W ind Direction and Stability Classes .......................................................................... 49 - Support Documentation of Engineering Change 375873 ................................................ 106 - Support Documentation of Engineering Change 378192 ................................................ 132 - Support Documentation of Engineering Change 362453 ................................................ 149 - Evaluation of Effluent Release Rates Incorporating a Proposed River Diffuser System at Braidwood Station ...................................................................................................... 161 - Teledyne Brown Engineering Sample Results for BD-22 Tritium .................................... 174 - Errata Corrections from 2010 Report ............................................................................... 236 - Offsite Dose Calculation Manual 1 of 238

RADIOACTIVE EFFLUENT RELEASE REPORT January - December 2011 Facility: BRAIDWOOD NUCLEAR POWER STATION Licensee: EXELON GENERATION COMPANY. LLC

1. Regulatory Limits
a. For Noble Gases:

Dose Rate

1) Less than 500 mrem/year to the whole body.
2) Less than 3000 mrem/year to the skin.

Dose Gamma Radiation

1) Less than or equal to 5 mrad/quarter.
2) Less than or equal to 10 mrad/year.

Dose Beta Radiation

1) Less than or equal to 10 mrad/quarter.
2) Less than or equal to 20 mrad/year.
b. Iodine: (summed with particulate, see below)
c. Particulates with half-lives > 8 days:

Dose Rate

1) Less than 1500 mrem/year to any organ.

Dose

1) Less than or equal to 7.5 mrem/quarter to any organ.
2) Less than or equal to 15 mrem/year to any organ.
d. For Liquid Dose
1) Less than or equal to 1.5 mrem to the whole body during any calendar quarter.
2) Less than or equal to 5 mrem to any organ during any calendar quarter.
3) Less than or equal to 3 mrem to the whole body during any calendar year.
4) Less than or equal to 10 mrem to any organ during any calendar year.

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2. Maximum Permissible Concentration
a. Fission and Activation Gases: 10CFR20 Appendix B Table 2
b. Iodine: 10CFR20 Appendix B Table 2
c. Particulates: 10CFR20 Appendix B Table 2
d. Liquid Effluents: 10 X 10CFR20 Appendix B Table 2
3. Average Energy This item is not applicable. Release rates are calculated using an isotopic mix rather than average energy.
4. Measurements and Approximations of Total Radioactivity
a. Fission and Activation Gases, lodines, and Particulates Before being discharged, containment batch releases are analyzed for noble gas and tritium via gamma spectroscopy and liquid scintillation, respectively. Gaseous decay tanks are analyzed for noble gases before being discharged via gamma spectroscopy. Released activity is normally calculated using volume of release, which is determined by change in tank or containment pressure.

The Auxiliary Building ventilation exhaust system is continually monitored for iodines and particulates. These samples are pulled every 7 days and analyzed via gamma spectroscopy.

The particulate samples are also analyzed quarterly for gross alpha and Sr-89/90.

Noble gas and tritium grab samples are pulled and analyzed weekly by gamma spectroscopy and liquid scintillation, respectively. The average flow at the release points and nuclide specific activity concentrations are used to calculate the activity released.

Volumes and activities of effluents discharged from systems that are common to both units are divided between both units.

The secondary side of both units contain tritium. Very small amounts of tritium are continually released to the atmosphere from secondary components through packing leaks, tank vents, the main condenser, etc. Bounding calculations have been performed to show that very large leaks (1000 gpd) for extended periods (1 month) at normal secondary tritium concentrations, would provide an insignificant increase (1.00E-5 mrem) in offsite dose.

Summary The calculated offsite dose to the public from station gaseous effluents remains low and a small percentage of the quarterly and annual ODCM limits.

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4. b. Liquid Effluents The liquid release tanks are analyzed before discharge via gamma spectroscopy and liquid scintillation. A representative portion of this sample is saved and is composited every 31 days with other discharges that occurred. The composites are analyzed for tritium and gross alpha. The batch composites are composited quarterly and sent to a vendor for Sr-89/90 and Fe-55 analysis. Circulating Water Blowdown, Condensate Polisher Sump and Waste Water Treatment are analyzed weekly by gamma spectroscopy and for tritium. These weekly samples are composited monthly. The monthly composites are then composited quarterly and sent to a vendor for Sr-89/90 and Fe-55 analysis.

Liquid release tank volumes and concentration activities are used to calculate the activity released during the time period. The total volume of water released and the nuclide specific concentration activities are used to calculate the final activity concentrations at the discharge point.

Volumes and activities of effluents discharged from systems that are common to both units are divided between both units.

There have been no indications of additional contamination since the start of the Exelon Pond remediation and the review of results of Exelon Pond analyses indicate the tritium concentration of the pond has been and remains below the level of detectability for the values described in the ODCM. Thus, the lack of sample analyses in these cases has not affected calculated offsite dose.

Instrument Issues On 6/10/11, it was noted that there was insufficient Exelon Pond sample for the week of 5/31/11 to 6/6/11. Operation's logbook entries indicate that the Exelon Pond pump operated for a 36 minute time period during this time frame. The compositor pulls a sample from the process stream every two hours during the Exelon Pond Pump's operation. The brief operation of the pond pump was insufficient for a sample to be obtained. IR 1227468 was written to document the missed sample based on insufficient pump run time and to capture the item in the 2011 ARERR.

The Exelon Pond composite sample that ended on 1/3/12 was found to be insufficient for analysis. Approximately 150 mL of sample was obtained when several liters was typical. IR 1309068 was written to document the occurrence. The compositor was adjusted to pull larger samples at the prescribed interval to ensure the weekly composite is large enough for analysis and further compositing.

Vacuum Breaker #1 compositor was found to be empty on 11/21/11. Heat tracing was operable and the compositor was cycling during the prescribed intervals. IR 1293134 was written to document the empty composite sample and the need for a grab sample. Upon investigation it was found that the compositor was working acceptably. No repair was necessary. Vaccum Breaker #1 compositor has been functioning without issue since then.

Summary The calculated offsite dose to the public from station liquid effluents remains low and a small percentage of the quarterly and annual Offsite Dose Calculation Manual (ODCM) limits.

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4. c. Less than the lower limit of detection (<LLD)

Samples are analyzed such that the Offsite Dose Calculation Manual (ODCM) LLD requirements are met. When a nuclide is not detected during the quarter then <LLD is reported.

d. Errata for Previous Annual Radioactive Effluent Release Reports IR 1273923 documents a condition in which a flow loop for the 2RY-PRO30C "AUX bldg ventstack WRGM I/E transmitter" was found to be out of tolerance by 17.44% between the as found condition and the expected value. The transmitter feeds the Unit 2 ventstack flow calculation. The flow loop instrument was last calibrated on 01/07/2010. All affected 2010 and 2011 effluent waste gas permits had their vent stack flow conservatively increased by 17.44% to account for the out of tolerance as found condition. The revised 2011 data that accounts for the flow discrepancy is a part of the 2011 data reported in this ARERR. The affected 2010 data has been revised and evaluated for applicable limit challenges. The change did not result in a significant increase in offsite dose or challenge any applicable offsite dose limits.

IR 1221439 documents an issue in which Fe-55 found in the 2010 second quarter Liquid Release Tank composite was not added to that quarter's permits, as required. The Fe-55 activity of 7.55E-06 uCi/mL has been added to the required permits to correct the specified timeframe. 2010 second quarter liquid effluent organ dose associated with the addition of Fe-55 saw an increase of 0.0002%. 2010 liquid effluent annual organ dose saw an increase of less that 0.0001%. 2010 second quarter liquid effluent whole body dose associated with the addition of Fe-55 saw an increase of 0.00025%. 2010 liquid effluent annual whole body dose associated with the addition of Fe-55 saw an increase of 0.0001%. Calculated dose to the public was not appreciably impacted by the correction. Model AR 1354440 has been created with a quarterly periodicity to review the vendor supplied results and update the affected permits, as required.

It was identified that the 2010 ARERR contained a unit error on page 26 of 104. The original 2010 ARERR had a "Total Activity Released (Ci)" of 4.31E+04. The unit error occurred by inserting the 4.31 E+04 jiCi. The correct value that should have been recorded was 4.31 E-02 Ci. The affected page has been corrected, in its entirety, and is included in Attachment 7 of this report. The affected page includes revision bars in the margin.

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BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2011 GAS RELEASES UNIT 1 (Docket Number 50-456)

SUMMATION OF ALL RELEASES Units 1st Qtr 2nd Qtr 3rd Qtr 4th Otr EstTrror%

A. Fission and Activation Gas Releases

1. Total Release Activity Ci 1.39E-01 5.82E-01 5.03E-03 3.OOE-03 7.59
2. Average Release Rate pCi/sec 1.79E-02 7.40E-02 6.33E-04 3.77E-04
3. Percent of ODCM Limit - gamma  % 2.56E-05 1.38E-04 8.02E-07 4.78E-07
4. Percent of ODCM Limit- beta  % 5.67E-05 2.59E-04 1.95E-06 1.16E-06 B. Iodine Releases
1. Total Iodine Ci 1.41E-06 2.36E-04 7.57E-06 7.30E-07 33.20
2. Average Release Rate j Ci/sec 1.81E-07 3.OOE-05 9.52E-07 9.18E-08
3. Percent of ODCM Limit - gamma  % 1.45E-05 1.81 E-04 1.45E-06 7.53E-06 C. Particulate (> 8 day half-life) Releases
1. Particulates with half-lives > 8 days Ci 1.04E+00 1.13E+00 1.08E+00 1.07E+00 19.80
2. Average Release Rate jiCi/sec 1.34E-01 1.44E-01 1.36E-01 1.35E-01
3. Percent of ODCM Limit  % 2.91E+00 3.16E+00 3.03E+00 3.00E+00
3. Gross Activity Ci <LLD <LLD <LLD <LLD D. Tritium Releases
1. Total Release Activity Ci 3.90E+01 4.17E+02 7.76E+01 1.86E+01 8.07
2. Average Release Rate ptCi/sec 5.02E+00 5.31E+01 9.76E+00 2.34E+00
3. Percent of ODCM Limit  % 7.58E-02 8.09E-01 1.50E-01 3.61E-01 E. Gross Alpha Releases
1. Total Release Activity Ci <LLD <LLD <LLD <LLD 19.80
2. Average Release Rate wCi/sec <LLD <LLD <LLD <LLD

______ * +

3. Percent of ODCM limit  % N/A N/A N/A N/A F. Carbon-14 Releases 1.Total Release Activity OCi 1.04E+00 1.13E+00 1.08E+00 1.07E+00

.Average Release Rate Ci/sec 1.34E-01 1.44E-01 1.36E-01 1.35E-01 Note: LLD Values are included in Appendix A of this report.

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BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2011 GAS RELEASES UNIT 1 (Docket Number 50-456)

CONTINUOUS MODE AND BATCH MODE Nuclides Released Continuous Mode Batch Mode Unit Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter 1 2 3 4 1 2 3 4

1. Fission Gases Ar-41 Ci <LLD <LLD <LLD <LLD <LLD 8.30E-05 <LLD <LLD Kr-85 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-85m Ci <LLD <LLD <LLD <LLD <LLD 5.18E-06 <LLD <LLD Kr-87 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-131m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-133 Ci <LLD <LLD <LLD <LLD 1.32E-01 5.08E-01 5.03E-03 3.OOE-03 Xe-133m Ci <LLD <LLD <LLD <LLD 2.16E-03 1.07E-02 <LLD <LLD Xe-135 Ci <LLD <LLD <LLD <LLD 4.82E-03 6.31E-02 <LLD <LLD Xe-135m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-138 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci <LLD <LLD <LLD <LLD 1.39E-01 5.82E-01 5.03E-03 3.OOE-03
2. lodines 1-131 Ci 1.41E-06 1.74E-05 <LLD 5.29E-07 <LLD 1.10E-08 1.66E-08 2.01E-07 1-132 Ci <LLD 2.19E-04 <LLD <LLD <LLD <LLD <LLD <LLD 1-133 Ci <LLD <LLD 7.55E-06 <LLD <LLD 1.67E-07 <LLD <LLD 1-134 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci 1.41 E-06 2.36E-04 7.55E-06 5.29E-07 <LLD 1.78E-07 1.66E-08 2.01 E-07
3. Particulates Cr-51 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mn-54 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Co-57 Ci <LLD <LLD 1.10E-06 <LLD <LLD <LLD <LLD <LLD Co-58 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Fe-59 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Co-60 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Zn-65 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Br-82 Ci 8.03E-06 1.86E-05 <LLD <LLD 1.65E-07 7.01 E-07 <LLD <LLD Sr-89 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ag-1 10m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Tc-99m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 7 of 238

BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORTýFOR 2011 GAS RELEASES UNIT 1 (Docket Number 50-456)

CONTINUOUS MODE AND BATCH MODE Nuclides Released - Continuous Mode I Batch Mode Unit Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter 1 2 3 4 1 2 3 4 Sn-1 17m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-137 Ci <LLD <LLD <LLD <LLD . <LLD <LLD <LLD <LLD Ba-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD La- 140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD 2.39E-06 <LLD <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Nd-147 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci 8.03E-06 1.86E-05 3.49E-06 <LLD 1.65E-07 7.01 E-07 <LLD <LLD

4. Tritium Ci 3.65E+01 4.12E+02 7.48E+01 1.59E+01 2.55E+00 5.14E+00 2.72E+00 2.73E+00
5. Gross Alpha Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD
6. Carbon-14 Ci 1.04E+00 1.13E+00 1.08E+00 1.07E+00 N/A N/A N/A N/A 8 of 238

BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2011 GAS RELEASES UNIT 2 (Docket Number 50-457)

  • SUMMATION OF ALL RELEASES Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Est. Total]

A. Fission and Activation Gas Releases

1. Total Activity Released Ci 1.39E-01 8.66E-01 5.03E-03 3.OOE-03 7.59
2. Average Release Rate j.tCi/sec 1.79E-02 1.10E-01 6.33E-04 3.77E-04
3. Percent of ODCM Limit - gamma  % 2.56E-05 1.83E-04 8.02E-07 4.78E-07
4. Percent of ODCM Limit- beta  % 5.67E-05 3.69E-04 1.95E-06 1.16E-06 B. Iodine Releases
1. Total Iodine Ci 8.41E-07 2.32E-04 1.77E-08 7.20E-07 33.20
2. Average Release Rate j.tCi/sec 1.08E-07 2.95E-05 2.23E-09 9.06E-08
3. Percent of ODCM Limit  % 8.66E-06 1.65E-04 1.81 E-07 7.42E-06 C. Particulate (> 8 day half-life) Releases
1. Particulates with half-lives > 8 days Ci 1.13E+00 9.32E-01 1.32E+00 1.46E+00 19.80
2. Average Release Rate 1 Ci/sec 1.45E-01 1.19E-01 1.66E-01 1.84E-01
3. Percent of OCDM Limit  % 3.16E+00 2.61E+00 3.69E+00 4.10E+00
4. Gross Activity Ci <LLD <LLD <LLD <LLD D. Tritium Releases
1. Total Release Activity Ci 5.77E+01 4.74E+02 3.99E+02 3.69E+01 8.07
2. Average Release Rate J Ci/sec 7.42E+00 6.03E+01 15.02E+01 4.64E+00
3. Percent of ODCM Limit  % 1.12E-01 9.19E-01 7.71E-01 7.17E-02 E. Gross Alpha Releases
1. Total Release Activity Ci <LLD <LLD <LLD <LLD 19.80
2. Average Release Rate ptCi/sec <LLD <LLD <LLD <LLD
3. Percent of ODCM Limit N/A N/A N/A N/A F. Carbon-14 Releases F2.. TotalRelease Activity Average Release Rate C

Ci lCi/sec 11.13E+00 9.32E-01 1.45E-01 1.19E-01 1.32E+00 1.46E+00 1.66E-01 1.84E-01 Note: LLD Values are included in Appendix A of this report.

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BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2011 GAS RELEASES UNIT 2 (Docket Number 50-457)

CONTINUOUS MODE AND BATCH MODE Nuclides Released [ Continuous Mode Batch Mode Unit Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter 1 2 3 4 1 2 3 4

1. Fission Gases Ar-41 Ci <LLD <LLD <LLD <LLD <LLD 8.31 E-05 <LLD <LLD Kr-85 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-85m Ci <LLD <LLD <LLD <LLD <LLD 5.18E0-6 <LLD <LLD Kr-87 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-131m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-133 Ci <LLD <LLD <LLD <LLD 1.32E-01 7.93E-01 5.03E-03 3.OOE-03 Xe- 133m Ci <LLD <LLD <LLD <LLD 2.16E-03 1.07E-02 <LLD <LLD Xe-135 Ci <LLD <LLD <LLD <LLD 4.82E-03 6.31E-02 <LLD <LLD Xe-135m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe- 138 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci <LLD <LLD <LLD <LLD 1.39E-01 8.66E-01 5.03E-03 3.OOE-03
2. lodines 1-131 Ci 8.41E-07 1.57E-05 <LLD <LLD <LLD 6.40E-09 1.77E-08 7.20E-07 1-132 Ci <LLD 2.17E-04 <LLD <LLD <LLD <LLD <LLD <LLD 1-133 Ci <LLD <LLD <LLD <LLD <LLD 3.11E-09 <LLD <LLD 1-134 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci 8.41 E-07 2.33E-04 <LLD <LLD <LLD 9.51 E-09 1.77E-08 7.20E-07
3. Particulates Cr-51 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mn-54 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Co-57 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Co-58 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Fe-59 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Co-60 Ci <LLD <LLD <LLD <LLD <LLD 1.96E-09 <LLD <LLD Zn-65 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Br-82 Ci <LLD <LLD <LLD <LLD 9.58E-08 4.26E-07 <LLD <LLD Sr-89 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ag-110m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Tc-99m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 10 of 238

BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2011 GAS RELEASES UNIT 2 (Docket Number 50-457)

CONTINUOUS MODE AND BATCH MODE LNuclides Released Continuous Mode Batch Mode Unit Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter 1 2 3 4 1 2 3 4 Sn-1 17m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cs-137 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ba-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-141 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Nd-147 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Te-132 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sn-113 Ci 1.61E-06 <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci 1.61 E-06 <LLD <LLD <LLD 9.58E-08 4.28E-07 <LLD <LLD

4. Tritium Ci 5.64E+01 4.70E+02 3.98E+02 3.38E+01 1.29E+00 4.06E+00 2.39E-01 3.04E+00
5. Gross Alpha Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD
6. Carbon-14 Ci 1.13E+00 9.32E-01 1.32E+00 1.46E+00 N/A N/A N/A N/A 11 of 238

BRAIDWOOD, NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2011 LIQUID RELEASES UNIT 1 (Docket Number 50-456)

SUMMATION OF ALL RELEASES Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Est. Total I I II I IError% I A. Fission and Activation Products

1. Total Release Ci 3.93E-02 2.54E-02 1.32E-03 1.14E-03 2.64
2. Average Diluted Concentration .LCi/ml 1.03E-08 4.55E-09 3.52E-10 3.20E-10
3. Percent of applicable limit  %*....

B. Tritium

1. Total Release Ci 1.10E+02 2.05E+02 5.90E+01 8.50E+01 5.85
2. Average Diluted Concentration pCi/ml 2.87E-05 3.67E-05 1.58E-05 2.38E-05
3. % of Limit (1E-2 ItCi/ml)  % 2.87E-01 3.67E-01 1.58E-01 2.38E-01 C. Dissolved Noble Gases
1. Total Release Ci O.OOE+00 3.77E-05 O.OOE+00 0.00E+00 2.64
2. Average Diluted Concentration I.Ci/ml 0.OOE+00 6.77E-12 0.OOE+00 0.OOE+00
3. % of Limit (2E-4 pCi/ml)  % O.OOE+00 3.38E-06 0.00E+00 0.OOE+00 D. Gross Alpha
1. Total Release Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 14.70 E. Volume of Waste Released liters 2.40E+05 4.52E+05 2.56E+05 2.90E+05 (prior to dilution)

IF. Volume of Dilution Water I liters I 7.62E+091 1.11 E+10 I 7.48E+091 7.14E+09 Note: LLD Values are included in Appendix A of this report.

Note: % Limit Values are included in Appendix B of this report.

  • This limit is equal to 10 times the concentration values in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402.
  • 12 of 238

BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENlT REPORT FOR 2011 LIQUID RELEASES UNIT 1 (Docket Numbers 50-456)

CONTINUOUS MODE & BATCH MODE Nuclides Released JContinuous Mode Batch Mode Unit Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter 1 2 3 4 1 2 3 4 Cr-51 Ci <LLD <LLD <LLD <LLD 5.07E-05 1.58E-04 <LLD <LLD Mn-54 Ci <LLD <LLD <LLD <LLD 9.21 E-04 5.96E-04 2.85E-05 1.51 E-05 Fe-55 Ci <LLD <LLD <LLD <LLD 1.55E-02 5.60E-03 <LLD <LLD Co-57 Ci <LLD <LLD <LLD <LLD 1.28E-04 1.24E-04 5.24E-06 5.50E-06 Co-58 Ci <LLD <LLD <LLD <LLD 5.32E-03 5.85E-03 3.46E-04 1.45E-04 Fe-59 Ci <LLD <LLD <LLD <LLD 3.37E-05 1.13E-05 <LLD <LLD Co-60 Ci <LLD <LLD <LLD <LLD 1.45E-02 1.10E-02 7.83E-04 6.23E-04 Ni-63 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD 5.70E-04 Zn-65 Ci <LLD <LLD <LLD <LLD 1.23E-04 3.59E-06 1.86E-06 <LLD Nb-95 Ci <LLD <LLD <LLD <LLD 2.55E-04 6.80E-05 <LLD <LLD Zr-95 Ci <LLD <LLD <LLD <LLD 1.28E-04 <LLD <LLD <LLD Nb-97 Ci <LLD <LLD <LLD <LLD 4.56E-04 3.61E-04 2.44E-05 3.13E-06 Zr-97 Ci <LLD <LLD <LLD <LLD 1.51 E-05 8.40E-06 <LLD <LLD Ag-110m Ci <LLD <LLD <LLD <LLD 4.77E-04 4.55E-04 2.60E-05 <LLD Sn-113 Ci <LLD <LLD <LLD <LLD 1.05E-04 7.11E-05 <LLD <LLD Sb-125 Ci <LLD <LLD <LLD <LLD 1.22E-03 1.04E-03 9.0OE-05 7.49E-05 1-134 Ci <LLD <LLD <LLD <LLD 7.75E-06 <LLD <LLD <LLD Cs-137 Ci <LLD <LLD <LLD <LLD 2.48E-06 1.40E-06 5.15E-06 4.20E-06 Ce-144 Ci <LLD <LLD <LLD <LLD 3.27E-05 <LLD <LLD <LLD Ag-i 10 Ci <LLD <LLD <LLD <LLD <LLD 6.35E-06 <LLD <LLD Te-123m Ci <LLD <LLD <LLD <LLD <LLD 2.08E-05 7.59E-06 1.01E-06 H-3 Ci 2.OOE+01 3.OOE+01 2,29E+01 2.59E+00 8.98E+01 1.75E+02 3.62E+01 8.26E+01 La-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1.76E-06 Sb-124 Ci <LLD <LLD <LLD <LLD <LLD 4.56E-06 2.72E-06 <LLD Ba-133 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD 4.30E-06 Cs-134 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1.78E-06 Ar-41 Ci <LLD <LLD <LLD <LLD <LLD 2.06E-06 <LLD <LLD Xe-133 Ci <LLD <LLD <LLD <LLD <LLD 3.23E-05 <LLD <LLD Xe-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-135m Ci <LLD <LLD <LLD <LLD <LLD 3.35E-06 <LLD <LLD Total for period Ci 2.OOE+01 3.OOE+01 2.29E+01 2.59E+00 8.98E+01 1.75E+02 3.62E+01 8.26E+M 1 13 of 238

BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2011 LIQUID RELEASES UNIT 2 (Docket Number 50-457)

SUMMATION OF ALL RELEASES lstQtr 2nd Qtr 3rd Qtr 4th Qtr Est'Trror%

IUnits A. Fission and Activation Products

1. Total Release Ci 3.93E-02 2.54E-02 1.32E-03 1.14E-03 2.64
2. Average Diluted Concentration ýtCi/ml 1.03E-08 4.55E-09 3.52E-10 3.20E-10
3. Percent of applicable limit  %*....

B. Tritium

1. Total Release Ci 1.10E+02 2.05E+02 5.90E+01 8.50E+01 5.85
2. Average Diluted Concentration PCi/ml 2.87E-05 3.67E-05 1.58E-05 2.38E-05
3. % of Limit (1E-2 tCi/ml)  % 2.87E-01 3.67E-01 1.58E-01 2.38E-01 C. Dissolved Noble Gases
1. Total Activity Released Ci 0.OOE+00 3.77E-05 0.OOE+00 0.OOE+00 2.64
2. Average Diluted Concentration 4Ci/ml 0.OOE+00 6.77E-12 0.00E+00 O.OOE+00
3. % of Limit (2E-4 pCi/ml)  % O.00E+00 3.38E-06 0.00E+00 O.OOE+00 D. Gross Alpha
1. Total Release Ci 10.OE+00 0.OOE+00 0.00E+00 0.OOE+00 14.70 E. Volume of Waste Released liters 2.40E+05 4.52E+05 2.56E+05 2.90E+05 (prior to dilution)

IF. Volume of Dilution Water I liters 7.62E+09 11.11 E+10 7.48E+091 7.14E+09 Note: LLD Values are included in Appendix A of this report.

Note: % Limit Values are included in Appendix B of this report.

  • This limit is equal to 10 times the concentration values in Appendix B, Table 2, Column 2 to 10CFR20.1001-2402.

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BRAIDWOOD NUCLEAR POWER STATION ANNUAL EFFLUENT REPORT FOR 2011 LIQUID RELEASES UNIT 2 (Docket Numbers 50-457)

CONTINUOUS MODE & BATCH MODE Nuclides Released Continuous Mode Batch Mode Unit Quarter Quarter Quarter Quarter Quarter Quarter Quarter Quarter 1 2 3 4 1 2 3 4 Cr-51 Ci <LLD <LLD <LLD <LLD 5.07E-05 1.58E-04 <LLD <LLD Mn-54 Ci <LLD <LLD <LLD <LLD 9.21E-04 5.96E-04 2.85E-05 1.51E-05 Fe-55 Ci <LLD <LLD <LLD <LLD 1.55E-02 5.60E-03 <LLD <LLD Co-57 Ci <LLD <LLD <LLD <LLD 1.28E-04 1.24E-04 5.24E-06 5.50E-06 Co-58 Ci <LLD <LLD <LLD <LLD 5.32E-03 5.85E-03 3.46E-04 1.45E-04 Fe-59 Ci <LLD <LLD <LLD <LLD 3.37E-05 1.13E-05 <LLD <LLD Co-60 Ci <LLD <LLD <LLD <LLD 1.45E-02 1.10E-02 7.83E-04 6.23E-04 Ni-63 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD 5.70E-04 Zn-65 Ci <LLD <LLD <LLD <LLD 1.23E-04 3.59E-06 1.86E-06 <LLD Nb-95 Ci <LLD <LLD <LLD <LLD 2.55E-04 6.80E-05 <LLD <LLD Zr-95 Ci <LLD <LLD <LLD <LLD 1.28E-04 <LLD <LLD <LLD Nb-97 Ci <LLD <LLD <LLD <LLD 4.56E-04 3.61E-04 2.44E-05 3.13E-06 Zr-97 Ci <LLD <LLD <LLD <LLD 1.51 E-05 8.40E-06 <LLD <LLD Ag-110m Ci <LLD <LLD <LLD <LLD 4.77E-04 4.55E-04 2.60E-05 <LLD Sn-113 Ci <LLD <LLD <LLD <LLD 1.05E-04 7.11E-05 <LLD <LLD Sb-125 Ci <LLD <LLD <LLD <LLD 1.22E-03 1.04E-03 9.OOE-05 7.49E-05 1-134 Ci <LLD <LLD <LLD <LLD 7.75E-06 <LLD <LLD <LLD Cs-137 Ci <LLD <LLD <LLD <LLD 2.48E-06 1.40E-06 5.15E-06 4.20E-06 Ce-144 Ci <LLD <LLD <LLD <LLD 3.27E-05 <LLD <LLD <LLD Ag-110 Ci <LLD <LLD <LLD <LLD <LLD 6.35E-06 <LLD <LLD Te-123m Ci <LLD <LLD <LLD <LLD <LLD 2.08E-05 7.59E-06 1.01E-06 H-3 Ci 2.OOE+01 3.OOE+01 2.29E+01 2.59E+00 8.98E+01 1.75E+02 3.62E+01 8.26E+01 La-140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1.76E-06 Sb-124 Ci <LLD <LLD <LLD <LLD <LLD 4.56E-06 2.72E-06 <LLD Ba-133 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD 4.30E-06 Cs-134 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1.78E-06 Ar-41 Ci <LLD <LLD <LLD <LLD <LLD 2.06E-06 <LLD <LLD Xe-133 Ci <LLD <LLD <LLD <LLD <LLD 3.23E-05 <LLD <LLD Xe-135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xe-135m Ci <LLD <LLD <LLD <LLD <LLD 3.35E-06 <LLD <LLD Total for period Ci 2.OOE+01 3.OOE+01 2.29E+01 2.59E+00 8.98E+01 1.75E+02 3.62E+01 8.26E+01 15 of 238

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE 1 REPORT FOR 2011 SOLID RADIOACTIVE WASTE UNIT 1 AND 2 COMBINED (Docket Numbers 50-456 and 50-457)

A. Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel)

1. Types of Waste Total Types of Waste Quantity Total Activity Period Est. Total (m3) (Ci) Error %
a. Spent resins, filter sludges, evaporator bottoms, etc 1.15 E+02 2.81 E+01 Jan - Dec 25 2011

-Dec

b. Dry compressible waste, contaminated equip, etc 2.27E+02 2.60E+00 Jan - Dec 25 Janc2011
c. Irradiated components, control rods, etc 4.40E-02 5.49E-02 Jan - Dec 25

__________ 2011 2

d. Other (oil, reverse osmosis reject water, soil, Lagoon O.00E+00 0.OOE+00 Jan - Dec N/A sediment) 2011
2. Estimate of major nuclide composition (by waste type)

Major Nuclide Composition  %

a. H-3 28.1 Mn-54 0.68 Fe-55 30.15 Co-58 1.52 Co-60 6.76 Ni-63 22.19
b. H-3 4.01 C-14 1.12 Mn-54 1.11 Fe-55 38.36 Co-58 12.54 Co-60 11.87 Ni-63 26.46
c. Fe-55 17.63 Co-60 78.88 Ni-63 1.22 Zn-65 2.16

.16 of 238 I--

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE-EFFLUENT RELEASE REPORT FOR 2011 SOLID RADIOACTIVE WASTE UNIT 1 AND 2 COMBINED (Docket Numbers 50-456 and 50-457)

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination Duratek (Energy Solutions), Oak Ridge, 1 Dibble Trucking TN 7 Hittman Transportation Duratek (Energy Solutions), Oak Ridge, TN Duratek Services (Energy Solutions),

1 Dibble Trucking Kingston, TN 6 Hittman Transportation Duratek Services (Energy Solutions),

Kingston, TN 5 Hittman Transportation Energy Solutions LLC., Clive, UT B. Irradiated Fuel Shipments (disposition)

No irradiated fuel shipments for January through December, 2011.

C. Changes to the Process Control Program There were no changes to the process control program in 2011. Current revision implemented on 4/21/2006.

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BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2011 UNIT 1 AND 2 COMBINED (Docket Numbers 50-456 and 50-457)

Summaries Process Control Program In 2011, there were no changes to the Process Control Program.

Effluent System Changes In 2011, there were no changes to the gaseous radwaste discharge system.

Three changes were made that impact the liquid radwaste discharge system. Engineering Change (EC) 375873 is the installation of a diffuser on the Kankakee River bed to provide better Circulating Water Blowdown mixing. EC 378192 discusses a change of piping configuration and the installation of a second Process Radiation Monitor for the pair of Liquid Release Tanks. The final EC 362453 discusses the installation of an ultra low flow discharge path. Each of these ECs and their assosicatedl0CFR50.59 screening forms can be found in Attachments 2, 3 and 4.

A report that evaluated the release practices at Braidwood Station prior to the installation of the liquid radwaste modifications is included in Attachment 5. The report discusses effluent concentration reduction proposals and the resultant BD-22 tritium concentrations.

A vendor's actual results obtained from sample location BD-22 can be reviewed in Attachment 6.

These supporting documents are included to satisfy ODCM requirement 12.6.4. All liquid effluent releases have been well under Federal limits.

Limits There were no liquid releases or gaseous releases that exceeded ODCM limits during 2011.

On 10/6/11 it was identified that the Aux Building Vent Stack WRGM 2RY-PRO30C I/E transmitter was found to be out of tolerance during its periodic calibration. The Aux Building out of tolerance condition yielded a potential under response of U-2 vent stack flow by 17.44%. The 2RY-PRO30C was last calibrated on 1/07/2010. The U-2 Aux Building Vent Stack flow was revised up by 17.44% for each 2011 continuous gaseous effluent permit. No limits were challenged by the upward revision. The issue was documented in IR 1273923.

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BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2011 UNIT 1 AND 2 COMBINED (Docket Numbers 50-456 and 50-457)

Abnormal Releases There were no abnormal liquid releases in 2011 resulting in an offsite discharge.

During the timeframe of March 1 through April 31, 2011, effluent iodine samples obtained from the Unit 1 and Unit 2 station vent stack identified detectable concentrations of iodine-131 and iodine-132. A total of 470 RCi of iodine-131/132 were released through these vents. This activity was most likely related to the events of March 2011 at the Dai-lchi atomic power plant, Fukushima Japan and the associated trans-Pacific transportation of airborne releases. The concentrations detected at the Braidwood Generating Station and calculated doses are conservatively included in this report for completeness. This issue was documented in IR 1191071.

Instrument Inoperability The following effluent monitoring instruments exceeded their specified inoperability time.

Liquid Radwaste Effluent Line Loop WX001 (flow instrument OF-WX001) exceeded its inoperability time on 4/27/07. At that time, required surveillances for this effluent instrument were taken to "suspend" and were not performed because the effluent flow path was no longer in use at Braidwood Station. A design change and modification to this flow path and this instrument was started in October 2010. It was declared operable with an initial use on 12/24/11. This issue has been entered into the Corrective Action Program as IR 723658.

Liquid Radwaste Effluent Line Radiation Monitor, ORE-PROO1, exceeded its inoperability time on 11/7/10.

The instrument was removed from service for modification related to the installation of an additional Liquid Radwaste Effluent Line Radiation Monitor, ORE-PRO90. The instrument was declared operable on 11/20/2011. This issue has been entered into the Corrective Action Program as IR 1136983.

Liquid Radwaste Effluent Line Radiation Monitor, ORE-PRO90, was installed in October 2010 during modification work on the liquid radwaste effluent path. This rad monitor exceeded its inoperability time on 12/28/10 due to continued installation and modification testing. The instrument was declared operable on 11/21/2011. All releases were performed in accordance with the requirements described in the ODCM for effluent releases with the instrument inoperable. This issue has been entered into the Corrective Action Program as IR 1206147.

The OPR02J Gaseous Radwaste Effluent Monitor's 14 day time clock expired on 3/3/2011 due to emergent work associated with a calibration and firmware update. Gaseous releases had already been terminated as the time the clock expired. Extended instrument inoperability was caused by the emergent need to fabricate a CPU card and decontaminate the sample chamber. Repair, calibration, and return to service completed on 3/11/2011, This issue was documented in IR 1182611.

19 of 238

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2011 UNIT 1 AND 2 COMBINED (Docket Numbers 50-456 and 50-457 ODCM Changes The ODCM was changed in 2011 to include the installation of an Independent Spent Fuel Storage Installation (ISFSI) and gaseous Carbon-14 methodology. No changes were made to the manner in which offsite dose is calculated.

40CFR190 NUREG-0543, Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part 190) states in section IV, "As long as a nuclear plant site operates at a level below the Appendix I reporting requirements, no extra analysis is required to demonstrate compliance with the 40 CFR Part 190."

The organ and whole body doses reported on pages 29 through 48 are determined using 10 CFR 50 Appendix I methodology. The doses are below the limits of Appendix I.

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BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2011 UNIT 1 AND 2 (Docket Numbers 50-456 and 50-457)

APPENDIX A LLD Tables 21 of 238

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2011 UNIT 1 AND 2 (Docket Numbers 50-456 and 50-457)

LLD VALUES FOR GASEOUS RELEASES Isotope LLD (4Ci/ml)

Gross Alpha 1.67E-12 H-3 6.35E-14 Ar-41 4.5913E-06 Mn-54 2.1497E-12 Co-58 1 .5877E-12 Fe-59 4.4966E- 12 Co-60 3.6342E-12 Zn-65 4.8392E-12 Kr-85 7.3546E-04 Kr-85m 3.6799E-06 Kr-87 3.1241E-06 Kr-88 8.1885E-06 Sr-89 2.58E-14 Sr-90 3.20E-15 Mo-99 1.3986E-12 1-131 8.8323E- 13 1-133 1.2082E-12 Xe-131m 1.3129E-04 Xe-133 9.5152E-06 Xe- 133m 2.9675E-05 Cs-134 1.1424E-12 Xe-135 3.3876E-06 Xe-135m 1.5886E-05 Cs- 137 2.2469E-1 2 Xe-138 2.9252E-05 Ce-141 1.8916E-12 Ce-144 8.9517E-12 NOTE: LLD Value for total activity released is based on LLD values for individual isotopes used in the calculation.

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BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2011 UNIT 1 AND 2 (Docket Numbers 50-456 and 50-457)

LLD VALUES FOR LIQUID RELEASES Isotope LLD tiCi/ml)

Gross Alpha 3.15E-14 H-3 6.76E- 12 Mn-54 5.8372E-08 Fe-55 8.60E-07 Co-58 7.1298E-08 Fe-59 1.4932E-07 Co-60 7.5278E-08 Zn-65 1.0877E-07 Sr-89 4.73E-08 Sr-90 9.40E-09 Mo-99 4.5639E-08 1-131 5.6082E-08 Xe-133 1.6782E-07 Cs-134 8.9794E-09 Cs-137 1.1319E-08 Kr-87 1.941 OE-07 Kr-88 2.1870E-07 Ce- 141 7.6146E-08 Ce-144 3.4518E-07 Xe- 133m 4.4.131 E-07 Xe-135 5.6966E-08 Xe-138 6.101OE-06 NOTE: LLD Value for Total Activity Released is based on LLD Values for individual isotopes used in the calculation.

23 of 238

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2011 UNIT 1 AND 2 (Docket Numbers 50-456 and 50-457)

APPENDIX B Supplemental Information 24 of 238

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2011 UNIT COMMON GASEOUS EFFLUENTS SUPPLEMENTAL RELEASE INFORMATION A. Batch Release 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total

1. Total Number of Batch 10 13 3 3 29 Releases
2. Total Time Period for Batch 837 7,833 3,569 2,348 1,079 Releases (minutes)
3. Maximum Time Period for a 730 632 N/A 1,490 996 Batch Release (minutes)
4. Average Time Period for a 360 357 181 279 N/A Batch Release (minutes)
5. Minimum Time Period for a 31 10 110 87 N/A Batch Release (minutes)

B. Abnormal Releases

1. Number of Releases 0 0 0 0 0
2. Total Activity Released (Ci) 0 0 0 0 0 25 of 238

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2011 UNIT 1 (Docket Number 50-456)

GASEOUS EFFLUENTS SUPPLEMENTAL RELEASE INFORMATION A. Batch Release 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total

1. Total Number of Batch 23 23 21 24 91 Releases
2. Total Time Period for Batch 14,746 13,062 4,916 8,295 41,019 Releases (minutes)
3. Maximum Time Period for 9,970 2,210 1,430 2,230 N/A a Batch Release (minutes)
4. Average Time Period for a 641 568 234 346 N/A Batch Release (minutes)
5. Minimum Time Period for a 23 13 18 13 N/A Batch Release (minutes)

B. Abnormal Releases

1. Number of Releases 0 0 0 0 0
2. Total Activity Released (Ci) 0 0 0 0 0 26 of 238

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2011 UNIT 2 (Docket Number 50-457)

GASEOUS EFFLUENTS SUPPLEMENTAL RELEASE INFORMATION A. Batch Release 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total

1. Total Number of Batch 22 26 25 30 103 Releases
2. Total Time Period for 43,810 2,878 21,924 1,368 17,640 Batch Releases (minutes)
3. Maximum Time Period for 833 2,530 575 2,520 N/A a Batch Release (minutes)
4. Average Time Period for a 588 N/A 131 843 55 Batch Release (minutes)
5. Minimum Time Period for N/A 14 18 11 3 a Batch Release (minutes)

B. Abnormal Releases

1. Number of Releases 0 0 0 0 0
2. Total Activity Released (Ci) 0 0 0 0 0 27 of 238

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2011 UNIT 1 AND 2 COMBINED (Docket Numbers 50-456 and 50-457)

BRAIDWOOD NUCLEAR POWER STATION LIQUID EFFLUENTS SUPPLEMENTAL RELEASE INFORMATION A. Batch Release 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total

1. Total Number of Batch 13 13 14 14 54 Releases
2. Total Time Period for Batch 3,591 5,846 4,368 8,116 21,921 Releases (minutes)
3. Maximum Time Period for a 562 466 1,100 3,740 N/A Batch Release (minutes)
4. Average Time Period for a 276 244 312 580 N/A Batch Release
5. Minimum Time Period for a 58 206 204 204 N/A Batch Release (minutes)
6. Average Stream Flow During Periods of Release of Effluent 1.08E+07 1.98E+07 3.72E+06 6.07E+06 N/A into a Flowing Stream (Iite rs/m in)

B. Abnormal Releases

1. Number of Releases 0 0 0 0 0
2. Total Activity Released (Ci) 0.00+00 0.00+00 0.00+00 0.OOE+00 O.OOE+00 28 of 238

RETDAS v3.6.3 <BRA> VSSI GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID ............. 1 All Gas Release Types Period Start Date .... .. 01/01/2011 00:00 Period End Date ......  :.01/01/2012 00:00 Period Duration (min): 5.256E+05 Coefficient Type ..... :.Historical Unit ..................... 1 RELEASE DATA Total Release Duration (minutes) ...................................... 5.921E+05 Total Release Volume (cf) ............................................. 7.529E+10 Average Release Flowrate (cfm) ........................................ 1.272E+05 Average Period Flowrate (cfm) 1. 432E+05

==NUCLIDE DATA Average ECrcent Nuclide uCi uCi/cc Ratio EC AR-41 8.31E+01 3.90E-14 3. 90E-06 1.OOE-08 KR-85M 5.18E+00 2.43E-15 2.43E-08 1.OOE-07 KR-85 0. OOE+00 0. OOE+00 0. OOE+00 7. OOE-07 XE-133M 1.28E+04 6.02E-12 1.OOE-05 6.OOE-07 KR-88 0. OOE+00 0. OOE+00 0. OOE+00 9.OOE-09 XE-131M 0. OOE+00 0. OOE+00 0. OOE+00 2 .OOE-06 XE-135 6. 79E+04 3.19E-11 4.55E-04 7.OOE-08 XE-133 6 .49E+05 3.04E-10 6. 08E-04 5. OOE-07 F&AG 7.30E+05 3.42E-10 1.08E-03 1-131 1. 96E+01 9.17E-15 4 .58E-05 2.OOE-10 1-132 2. 19E+02 1. 03E-13 5.13E-06 2.OOE-08 1-133 7. 72E+00 3.62E-15 3.62E-06 1. OOE-09 Iodine 2.46E+02 1.15E-13 5.46E-05 BR-82 2.75E+01 1.29E-14 2.58E-06 5.OOE-09 Other 2.75E+01 1.29E-14 2.58E-06 H-3 5.52E+08 2.59E-07 2.59E+00 1.OOE-07 H-3 5.52E+08 2.59E-07 2.59E+00 CO-57 1.10E+00 5.17E-16 5.75E-07 9. OE-10 C-14 4.32E+06 2. 02E-09 6.75E-01 3. OOE-09 CE-141 2. 39E+00 1.12E-15 1 .40E-06 8. OOE-10 4.32E+06 2.02E-09 6.75E-01 29 of 238

RETDAS v3.6.3 <BRA> VSSI GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID ........... 1 All Gas Release Types Period Start Date .... 01/01/2011 00:00 Period End Date ...... 01/01/2012 00:00 Period Duration (min): 5.256E+05 Coefficient Type ...... Historical Unit ..................

NUCLIDE DATA Average ECrcent Nuclide uCi uCi/cc Ratio EC Total 5.57E+08 2.61E-07 3.27E+00 30 of 238

RETDAS v3.6.3 <BRA> VSSI GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID ............. 1 All Gas Release Types Period Start Date .... 01/01/2011 00:00 Period End Date ...... 01/01/2012 00:00 Period Duration (min) : 5.256E+05 Coefficient Type ..... :.Historical Unit ................... 1 Receptor ............... 5 Composite Crit. Receptor - IP Distance (meters) ....  : 0.0 Compass Point .......... 0.0 PERIOD DOSE BY AGEGROUP, PATHWAY, ORGAN (mrem) -

Age/Path Bone Liver Thyroid Kidney Lung GI-Lli Skin TB AGPD 3.44E-07 3.44E-07 3 .44E-07 3.44E-07 3.44E-07 3 .44E-07 0.00E+00 3.44E-07 AINHL 2.89E-03 1.51E-02 1.52E-02 1.51E-02 1.51E-02 1.51E-02 0.00E+00 1.51E-02 AVEG 1.42E-01 5.46E-02 5.50E-02 5.46E-02 5.46E-02 5.46E-02 0 00E+00 5.46E-02 ACMEAT 5.29E-02 1.43E-02 1.44E-02 1.43E-02 1.43E-02 1.43E-02 0 00E+00 1.43E-02 ACMILK 5.77E-02 2.04E-02 2.18E-02 2.04E-02 2 .04E-02 2.04E-02 0 00E+00 2.04E-02 TGPD 3.44E-07 3.44E-07 3.44E-07 3.44E-07 3 .44E-07 3 .44E-07 0 00E+00 3.44E-07 TINHL 4.13E-03 1.55E-02 1.55E-02 1.55E-02 1 .55E-02 1.55E-02 0 00E+00 1.55E-02 TVEG 2.30E-01 7.62E-02 7 .65E-02 7. 62E-02 7. 62E-02 7. 62E-02 0 00E+00 7.62E-02 TCMEAT 4.46E-02 1.12E-02 1.12E-02 1. 12E-02 1.12E-02 1.12E-02 0.00E+00 1.12E-02 TCMILK 1. 06E-01 3.28E-02 3.50E-02 3 .28E-02 3 .28E-02 3 .28E-02 0.00E+00 3.28E-02 CGPD 3.44E-07 3.44E-07 3.44E-07 3 .44E-07 3.44E-07 3 .44E-07 0.00E+00 3.44E-07 CINHL 5.70E-03 1.41E-02 1.41E-02 1.41E-02 1.41E-02 1.41E-02 0.00E+00 1.41E-02 CVEG 5.56E-01 1.58E-01 1.58E-01 1.58E-01 1.58E-01 1.58E-01 0.00E+00 1.58E-01 CCMEAT 8.40E-02 1.96E-02 1.96E-02 1.96E-02 1.96E-02 1 .96E-02 0.00E+00 1.96E-02 CCMILK 2.62E-01 7.05E-02 7.49E-02 7.05E-02 7.05E-02 7.05E-02 0.00E+00 7.05E-02 IGPD 3.44E-07 3.44E-07 3.44E-07 3 .44E-07 3 .44E-07 3 .44E-07 0.00E+00 3.44E-07 IINHL 4.21E-03 8.33E-03 8. 34E- 03 8. 33E-03 8.33E-03 8.33E-03 0.00E+00 8.33E-03 ICMILK 5. 13E-01 1.37E-01 1.48E-01 1.37E-01 1.37E-01 1 .37E-01 0.00E+00 1.37E-01

==PERIOD DOSE BY AGEGROUP, ORGAN (mrem)

Agegroup Bone Liver Thyroid Kidney Lung GI-Lli Skin TB ADULT 2.56E-01 1.05E-01 1.06E-01 1.05E-01 1.05E-01 1.05E-01 0.00E+00 1.05E-01 TEEN 3.86E-01 1.36E-01 1.38E-01 1.36E-01 1.36E-01 1.36E-01 0.00E+00 1.36E-01 CHILD 9.08E-01 2.62E-01 2.67E-01 2.62E-01 2.62E-01 2.62E-01 0.00E+00 2.62E-01 INFANT 5.17E-01 1.45E-01 1.56E-01 1.45E-01 1.45E-01 1.45E-01 0.00E+00 1.45E-01 31 of 238

RETDAS v3.6.3 <BRA> VSSI GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID ............. 1 All Gas Release Types Period Start Date .... .. 01/01/2011 00:00 Period End Date ...... .. 01/01/2012 00:00 Period Duration (min): 5.256E+05 Coefficient Type ..... : Historical Unit ...................- 1 Receptor ..............- 5 Composite Crit. Receptor - IP Distance (meters) ....  : 0.0 Compass Point .......... 0.0 MAXIMUM PERIOD DOSE TO LIMIT (Any Organ)

Dose Age Dose Limit Admin Admin  % T.Spec T.Spec %

Period Group Organ (mrem) Period Limit of Limit Limit of Limit Strt->End CHILD BONE 9.08E--

Qrtr->End CHILD BONE 9.08E-' 0 1 31-day 2.25E-01 4.03E+02 3.OOE-01 3.03E+02 Year->End CHILD BONE 9.08E- 0 1 Quarter 5.63E+00 1.61E+01 7.50E+00 1.21E+01 01 Annual 1.13E+01 8.07E+00 1.50E+01 6.05E+00 Critical Pathway .......... 2 Vegetation (VEG)

Major Contributors ...... .. 0.0  % or greater to total Nuclide Percentage H-3 0.OOE+00 C-14 1.OOE+02 1-131 1.66E-03 1-132 1.75E-05 1-133 1.08E-05 CE-141 2.36E-06 MAXIMUM PERIOD DOSE TO LIMIT ( Tot Body))

Dose Age Dose Limit Admin Admin  % T.Spec T.Spec %

Period Group Organ (mrem) Period Limit of Limit Limit of Limit Strt->End CHILD TBODY 2.62E-01 Qrtr->End CHILD TBODY 2.62E-01 31-day 1.50E-01 1.75E+02 2.OOE-01 1.31E+02 Year->End CHILD TBODY 2.62E-01 Quarter 5.25E+00 4.99E+00 7.50E+00 3.49E+00 Annual 1.05E+01 2.50E+00 1.50E+01 1.75E+00 Critical Pathway ........ .. 2 Vegetation (VEG)

Major Contributors ...... .. 0.0  % or greater to total Nuclide Percentage H-3 3.07E+01 C-14 6.95E+01 1-131 3.32E-03 1-132 5.99E-05 1-133 1.95E-05 CE-141 6.60E-06 32 of 238

RETDAS v3.6.3 <BRA> VSSI GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID ............. 1 All Gas Release Types Period Start Date .... : 01/01/2011 00:00 Period End Date ...... .. 01/01/2012 00:00 Period Duration (min) : 5.256E+05 Coefficient Type ..... :.Historical Unit ................... 1 Receptor .............  : 4 Composite Crit. Receptor - NG Distance (meters) ....  : 0.0 Compass Point .......... 0.0 MAXIMUM PERIOD NG DOSE TO LIMIT (Gamma)

Dose Dose Limit Admin Admin  % T.Spec T.Spec %

Period Dose Type (mrad) Period Limit of Limit Limit of Limit Strt->End Gamma 8.22E-06 Qrtr->End Gamma 8.22E-06 31-day 1.50E-01 5.48E-03 2.OOE-01 4.11E-03 Year->End Gamma 8.22E-06 Quarter 3.75E+00 2.19E-04 5.OOE+00 1.64E-04 Annual 7.50E+00 1.10E-04 1.00E+01 8.22E-05 Major Contributors ...... 0.0  % or greater to total Nuclide Percentage AR-41 2.12E-01 KR-85M 1.75E-03 KR-85 0.OOE+00 XE-133M 1.15E+00 KR-88 0.OOE+00 XE-131M 0.OOE+00 XE-135 3.58E+01 XE-133 6.28E+01 MAXIMUM PERIOD NG DOSE TO LIMIT (Beta))

Dose Dose Limit Admin Admin  % T.Spec T.Spec %

Period Dose Type (mrad) Period Limit of Limit Limit of Limit Strt->End Beta 3.19E-05 Qrtr->End Beta 3.19E-05 31-day 3.OOE-01 1.06E-02 4.OOE-01 7.98E-03 Year->End Beta 3.19E-05 Quarter 7.50E+00 4.26E-04 1.OOE+01 3.19E-04 Annual 1.50E+01 2.13E-04 2.OOE+01 1.60E-04 Major Contributors ...... 0.0  % or greater to total Nuclide Percentage AR-41 3.14E-02 KR-85M 1.18E-03 KR-85 0.OOE+00 XE-133M 2.19E+00 KR-88 0.OOE+00 XE-131M 0.OOE+00 XE-135 1.93E+01 XE-133 7.85E+01 33 of 238

RETDAS v3.6.3 <BRA> VSSI LIQUID RELEASE AND DOSE

SUMMARY

REPORT

(PERIOD BASIS - BY UNIT)

Release ID .............  : 1 All Liquid Release Types Period Start Date ..... :.01/01/2011 00:00 Period End Date ....... 01/01/2012 00:00 Period Duration (mins): 5.256E+05 Unit ..................  : 1 MULTIPLE RELEASE POINT MESSAGE Undiluted and Diluted Flowrate(s) and Concentration(s) cannot be combined.

RELEASE DATA Total Release Duration (minutes) ..................................... 1.186E+06 Total Undiluted Volume Released (gallons) ............................ NA Average Undiluted Flowrate (gpm) ..................................... NA Total Dilution Volume (gallons) ...................................... NA Average Dilution Flowrate (gpm) ...................................... NA NUCLIDE DATA Nuclide uCi CO-57 2.63E+02 NB-97 8.44E+02 AG-l10 6.33E+00 SN-113 1.76E+02 SB-124 7.27E+00 SB-125 2.42E+03 BA-133 4.30E+00 TE-123M 2.94E+01 CR-51 2.09E+02 MN-54 1.56E+03 FE-59 4.50E+01 CO-58 1.17E+04 CO-60 2.69E+04 ZN-65 1.28E+02 ZR-95 1.28E+02 ZR-97 2.35E+01 NB-95 3.23E+02 AG-11OM 9.57E+02 1-134 7.73E+00 CS-134 1.78E+00 CS-137 1.32E+01 LA-140 1.76E+00 CE-144 3.26E+01 Gamma 4.58E+04

.AR-41 2.05E+00 XE-135M 3.35E+00 XE-133 3.23E+01 34 of 238

RETDAS v3.6.3 <BRA> vSSI LIQUID RELEASE AND DOSE

SUMMARY

REPORT

(PERIOD BASIS - BY UNIT)------

Release ID .............. 1 All Liquid Release Types Period Start Date ..... .. 01/01/2011 00:00 Period End Date .......  :.01/01/2012 00:00 Period Duration (mins) : 5.256E+05

=== NUCLIDE DATA Nuclide uCi D&EG 3. 77E+01 H-3 4. 58E+08 FE-55 2. 11E+04 NI-63 2 . 62E+02 Beta 4. 58E+08 Total 4. 58E+08 35 of 238

RETDAS v3.6.3 <BRA> VSSI LIQUID RELEASE AND DOSE

SUMMARY

REPORT

(PERIOD BASIS - BY UNIT)------

Release ID .............- 1 All Liquid Release Types Period Start Date ..... .. 01/01/2011 00:00 Period End Date ....... .. 01/01/2012 00:00 Period Duration (mins): 5.256E+05 Unit .................. 1 Receptor ...............  : 0 Liquid Receptor PERIOD DOSE BY AGEGROUP, PATHWAY, ORGAN (mrem)

Age/Path Bone Liver Thyroid Kidney Lung GI-Lli Skin TB APWtr 1.29E-05 8.69E-03 8 .68E-03 8 .68E-03 8 .68E-03 8.87E-03 0 00E+00 8 70E-03 AFWFSp 8.07E-04 4 .72E-03 3 .60E-03 3.89E-03 3. 76E-03 2 .12E-02 0 00E+00 4 42E-03 TPWtr 1.23E-05 6.13E-03 6 .11E-03 6.12E-03 6.12E-03 6.23E-03 0 00E+00 6 .14E-03 TFWFSp 8.35E-04 3.90E-03 2 .76E-03 3.05E-03 2 .96E-03 1.51E-02 0 00E+00 3.54E-03 CPWtr 3.73E-05 1.18E-02 1 .17E-02 1. 17E-02 1.17E-02 1 .18E-02 0 00E+00 1. 18E-02 CFWFSp 1.07E-03 3.27E-03 2 .29E-03 2.51E-03 2 .46E-03 6 .68E-03 0 00E+00 3.07E-03 IPWtr 2.91E-05 1. 16E-02 1. 15E-02 1. 15E-02 1.15E-02 1. 16E-02 0 00E+00 1. 16E-02 PERIOD DOSE BY AGEGROUP, ORGAN (mrem)

Agegroup Bone Liver Thyroid Kidney Lung GI-Lli Skin TB ADULT 8.20E-04 1.34E-02 1.23E-02 1.26E-02 1.24E-02 3.01E-02 0.00E+00 1.31E-02 TEEN 8.47E-04 1.00E-02 8.88E-03 9.16E-03 9.08E-03 2.14E-02 0.00E+00 9.67E-03 CHILD 1.10E-03 1.50E-02 1.40E-02 1.43E-02 1.42E-02 1.85E-02 0.00E+00 1.49E-02 INFANT 2.91E-05 1.16E-02 1.15E-02 1.15E-02 1.15E-02 1.16E-02 0.00E+00 1.16E-02 36 of 238

RETDAS v3.6.3 <BRA> VSSI LIQUID RELEASE AND DOSE

SUMMARY

REPORT

(PERIOD BASIS - BY UNIT)------

Release ID............... 1 All Liquid Release Types Period Start Date ....... 01/01/2011 00:00 Period End Date ......... 01/01/2012 00:00 Period Duration (mins) : 5.256E+05 Unit..................... 1 Receptor................. 0 Liquid Receptor

==MAXIMUM PERIOD DOSE TO LIMIT (Any Organ)---------------------

Dose Age Dose Limit Admin Admin  % T. Spec T.Spec %

Period Group Organ (mrem) Period Limit of Limit Limit of Limit Strt->End ADULT GILLI 3. 01E-02 31-day 1. 50E-01 2. 01E+01 2. OOE-01 1. 50E+01 Qrtr->End ADULT GILLI 3. 01E-02 Quarter 3.75E+00 8.02E-01 5. OOE+00 6.02E-01 Year->End ADULT GILLI 3. 01E-02 Annual 7 . 50E+00 4. 01E-01 1.OOE+01 3.01E-01 Critical Pathway ........ 1 Fresh Water Fish - Sport (FFSP)

Major Contributors ....... 0.0  % or greater to total Nuclide Percentage H-3 4.09E+01 CR-51 5.92E-03 MN-54 1.84E+00 FE-55 4.92E-01 FE-59 3.26E-02 CO-58 1.92E+00 CO-60 1.18E+01 NI-63 1.05E-02 ZN-65 5.19E-01 ZR-95 4.52E-03 ZR-97 2.82E-03 NB-95 4.26E+01 AG-IIOM 5.39E-02 1-134 6.95E-09 CS-134 1.92E-03 CS-137 1.17E-02 LA-140 9.24E-04 CE-144 3.56E-03 MAXIMUM PERIOD DOSE TO LIMIT (Tot Body))-

Dose Age Dose Limit Admin Admin  % T.Spec T.Spec %

Period Group Organ (mrem) Period Limit of Limit Limit of Limit Strt->End CHILD TBODY Qrtr->End CHILD TBODY 1.49E-0 2 31-day 4.50E-02 3.30E+01 6.OOE-02 2.48E+01 Year->End CHILD TBODY 1.49E-0 2 Quarter 1.13E+00 1.32E+00 1.50E+00 9.91E-01 1.49E-0 2 Annual 2.25E+00 6.61E-01 3.OOE+00 4.95E-01 Critical Pathway ..........  : 0 Potable Water (PWtr)

Major Contributors..;...: 0.0  % or greater to total Nuclide Percentage 37 of 238

RETDAS v3.6.3 <BRA> VSSI LIQUID RELEASE AND DOSE

SUMMARY

REPORT

(PERIOD BASIS - BY UNIT)

Release ID .............. 1 All Liquid Release Types Period Start Date ..... .. 01/01/2011 00:00 Period End Date ....... .. 01/01/2012 00:00 Period Duration (mins) : 5.256E+05 Major Contributors ...... .. 0.0  % or greater to total Nuclide Percentage H-3 9.42E+01 CR-51 5.29E-05 MN-54 2.50E-01 FE-55 5.79E-01 FE-59 8.68E-03 CO-58 4.88E-01 CO-60 3.19E+00 NI-63 6.93E-02 ZN-65 8.07E-01 ZR-95 3.19E-06 ZR-97 1.54E-08 NB-95 8.41E-03 AG-11OM 2.68E-04 1-134 7.53E-06 CS-134 4.OOE-02 CS-137 1.70E-01 LA-140 8.61E-09 CE-144 2.83E-06 38 of 238

RETDAS v3.6.3 <BRA> VSSI GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID ............. 1 All Gas Release Types Period Start Date .... .. 01/01/2011 00:00 Period End Date ......  :.01/01/2012 00:00 Period Duration (min): 5.256E+05 Coefficient Type ..... Historical Unit ..................- 2 RELEASE DATA Total Release Duration (minutes) ...................................... 5.597E+05 Total Release Volume (cf) ............................................. 6.877E+10 Average Release Flowrate (cfm) ........................................ 1.229E+05 Average Period Flowrate (cfm) ......................................... 1.308E+05 NUCLIDE DATA Average ECrcent Nuclide uCi uCi/cc Ratio EC AR-41 8.31E+01 4.27E-14 4.27E-06 1.00E-08 KR- 85M 5. 18E+00 2.66E-15 2.66E-08 1.00E-07 KR-85 0 OOE+00 0. OOE+00 0.00E+00 7.00E-07 XE-133M 1 28E+04 6.59E-12 1.10E-05 6.OOE-07 KR-88 0 OOE+00 0. OOE+00 0.00E+00 9.OOE-09 XE-131M 0 OOE+00 O.OOE+00 0.OOE+00 2.00E-06 XE-135 6 . 79E+04 3.49E-11 4.98E-04 7.OOE-08 XE-133 9. 33E+05 4.79E-10 9.58E-04 5.OOE-07 F&AG 1.01E+06 5.20E-10 1.47E-03 1-131 1. 73E+01 8.90E-15 4 .45E-05 2. 00E-10 1-132 2 . 17E+02 1.lIE-13 5.56E-06 2.00E-08 1-133 3. lE-03 1.60E-18 1. 60E-09 1.00E-09 Iodine 2 . 34E+02 1.20E-13 5. 01E-05 BR-82 5. 21E-01 2.68E-16 5 .36E-08 5.OOE-09 Other 5. 21E-01 2.68E-16 5.36E-08 H-3 9. 67E+08 4.97E-07 4. 97E+00 1.OOE-07 H-3 9. 67E+08 4.97E-07 4 . 97E+00 SN-113 1. 61E+00 8.24E-16 1. 03E-06 8.OOE-10 C-14 4 .84E+06 2 .48E-09 8.28E-01 3.00E-09 CO-60 1.96E-03 1.01E-18 2. 01E-08 5. 00E-11 P>=8 4.84E+06 2.48E-09 8.28E-01 39 of 238

RETDAS v3.6.3 <BRA> VSSI GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID ........... 1 All Gas Release Types Period Start Date .... 01/01/2011 00:00 Period End Date ...... 01/01/2012 00:00 Period Duration (min): 5.256E+05 Coefficient Type ...... Historical Unit .................. 2 NUCLIDE DATA Average ECrcent Nuclide uCi uCi/cc Ratio EC Total 9.73E+08 5.00E-07 5.80E+00 40 of 238

RETDAS v3.6.3 <BRA> VSSI GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID ............ 1 All Gas Release Types Period Start Date .... 01/01/2011 00:00 Period End Date ....... 01/01/2012 00:00 Period Duration (min): 5.256E+05 Coefficient Type .....  : Historical Unit ..................- 2 Receptor ............... 5 Composite Crit. Receptor - IP Distance (meters) ....  : 0.0 Compass Point .......... 0.0 PERIOD DOSE BY AGEGROUP, PATHWAY, ORGAN (mrem)

Age/Path Bone Liver Thyroid Kidney Lung GI-Lli Skin TB AGPD 3 .21E-07 3.21E-07 3 .21E-07 3 .21E-07 3 .21E-07 3.21E-07 0.00E+00 3 .21E-07 AINHL 3.24E-03 2.62E-02 2 .62E-02 2. 62E-02 2.62E-02 2.62E-02 0 00E+00 2 .62E-02 AVEG 1.60E-01 7. 78E-02 7.81E-02 7.78E-02 7.78E-02 7.78E-02 0 00E+00 7.78E-02 ACMEAT 5.93E-02 1 .85E-02 1 .85E-02 1.85E-02 1.85E-02 1.85E-02 0 00E+00 1 .85E-02 ACMILK 6.46E-02 2 84E-02 2. 97E-02 2.84E-02 2.84E-02 2.84E-02 0 00E+00 2 .84E-02 TGPD 3.21E-07 3. 21E-07 3 .21E-07 3.21E-07 3.21E-07 3.21E-07 0 00E+00 3.21E-07 TINHL 4.63E-03 2 .67E-02 2 .67E-02 2 .67E-02 2.67E-02 2.67E-02 0 00E+00 2.67E-02 TVEG 2.58E-01 1. 04E-01 1.05E-01 1.04E-01 1.04E-01 1.04E-01 0 00E+00 1.04E-01 TCMEAT 5.00E-02 1.39E-02 1.40E-02 1.39E-02 1.39E-02 1.39E-02 0 00E+00 1.39E-02 TCMILK 1. 19E-01 4 .40E-02 4 .60E-02 4 .40E-02 4.40E-02 4.40E-02 0 00E+00 4.40E-02 CGPD 3.21E-07 3. 21E-07 3 .21E-07 3 .21E-07 3.21E-07 3.21E-07 0 00E+00 3.21E-07 CINHL 6 .39E-03 2 .40E-02 2 .40E-02 2 .40E-02 2.40E-02 2.40E-02 0 00E+00 2.40E-02 CVEG 6.23E-01 2. 06E-01 2.07E-01 2.06E-01 2.06E-01 2.06E-01 0 00E+00 2.06E-01 CCMEAT 9.42E-02 2 .36E-02 2 .37E-02 2.36E-02 2.36E-02 2.36E-02 0 00E+00 2.36E-02 CCMILK 2.94E-01 9.05E-02 9 .44E-02 9.05E-02 9.05E-02 9.05E-02 0 00E+00 9.05E-02 IGPD 3.21E-07 3.21E-07 3.21E-07 3 .21E-07 3.21E-07 3.21E-07 0 00E+00 3.21E-07 IINHL 4 .72E-03 1.41E-02 1 .41E-02 1.41E-02 1.41E-02 1.41E-02 0 00E+00 1.41E-02 ICMILK 5.75E-01 1. 71E-01 1. 81E-01 1.71E-01 1.71E-01 1.71E-01 0 00E+00 1.71E-01 PERIOD DOSE BY AGEGROUP, ORGAN (mrem)

Agegroup Bone Liver Thyroid Kidney Lung GI-Lli Skin TB ADULT 2.87E-01 1.51E-01 1.52E-01 1.51E-01 1.51E-01 1.51E-01 0.00E+00 1.51E-01 TEEN 4.32E-01 1.89E-01 1.91E-01 1.89E-01 1.89E-01 1.89E-01 0.00E+00 1.89E-01 CHILD 1.02E+00 3.44E-01 3.49E-01 3.44E-01 3.44E-01 3.44E-01 0.00E+00 3.44E-01 INFANT 5.80E-01 1.85E-01 1.95E-01 1.85E-01 1.85E-01 1.85E-01 0.00E+00 1.85E-01 41 of 238

RETDAS v3.6.3 <BRA> VSSI GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID ............. 1 All Gas Release Types Period Start Date ....  :.01/01/2011 00:00 Period End Date ......  :.01/01/2012 00:00 Period Duration (min): 5.256E+05 Coefficient Type ..... :.Historical Unit ..................... 2 Receptor ............... 5 Composite Crit. Receptor - IP Distance (meters) ....  :.0.0 Compass Point .......... 0.0 MAXIMUM PERIOD DOSE TO LIMIT (Any Organ)

Dose Age Dose Limit Admin Admin % T.Spec T.Spec %

Period Group Organ (mrem) Period Limit of Limit Limit of Limit Strt->End CHILD BONE 1.02E+(

Qrtr->End CHILD BONE 1.02E+(000 31-day 2.25E-01 4.52E+02 3.OOE-01 3.39E+02 Year->End CHILD BONE 1.02E+ 00 Quarter 5.63E+00 1.81E+01 7.50E+00 1.36E+01 0 Annual 1.13E+01 9.04E+00 1.50E+01 6.78E+00 Critical Pathway .......... 2 Vegetation (VEG)

Major Contributors ...... 0.(  % or greater to total Nuclide Percentage H-3 0.OOE+00 C-14 1.OOE+02 CO-60 2.46E-06 1-131 1.32E-03 1-132 1.54E-05 1-133 3.87E-09 MAXIMUM PERIOD DOSE TO LIMIT (Tot Body))

Dose Age Dose Limit Admin Admin % T. Spec T.Spec %

Period Group Organ (mrem) Period Limit of Limit Limit of Limit Strt->End CHILD TBODY 3.44E-01 31-day 1.50E-01 2.30E+02 2.OOE-01 1 .72E+02 Qrtr->End CHILD TBODY 3.44E-01 Quarter 5.25E+00 6 . 56E+00 7. 50E+00 4 .59E+00 Year->End CHILD TBODY 3.44E-01 Annual 1.05E+01 3.28E+00 1. 50E+01 2.30E+00 Critical Pathway ....... 2 Vegetation (VEG)

Major Contributors ..... 0.0  % or greater to total Nuclide Percentage H-3 4.09E+01 C-14 5.89E+01 CO-60 7.69E-06 1-131 2.24E-03 1-132 4.50E-05 1-133 5.98E-09 42 of 238

RETDAS v3.6.3 <BRA> VSSI GASEOUS RELEASE AND DOSE

SUMMARY

REPORT - BY UNIT (Composite Critical Receptor - Limited Analysis)

Release ID ............. 1 All Gas Release Types Period Start Date .... 01/01/2011 00:00 Period End Date ...... .. 01/01/2012 00:00 Period Duration (min): 5.256E+05 Coefficient Type .....  :.Historical Unit ..................... 2 Receptor ............... 4 Composite Crit. Receptor - NG Distance (meters) ....  : 0.0 Compass Point ........  : 0.0 MAXIMUM PERIOD NG DOSE TO LIMIT (Gamma)

Dose Dose Limit Admin Admin  % T.Spec T.Spec %

Period Dose Type (mrad) Period Limit of Limit Limit of Limit Strt->End Gamma 1.05E-05 Qrtr->End Gamma 1.05E-05 31-day 1.50E-01 6.99E-03 2.00E-01 5.24E-03 Year->End Gamma 1.05E-05 Quarter 3.75E+00 2.80E-04 5.00E+00 2.10E-04 Annual 7.50E+00 1.40E-04 1.OOE+01 1.05E-04 Major Contributors ...... .. 0.0  % or greater to total Nuclide Percentage AR-41 1.66E-01 KR-85M 1.37E-03 KR-85 0.OOE+00 XE-133M 9.03E-01 KR-88 0.00E+00 XE-131M 0.OOE+00 XE-135 2.81E+01 XE-133 7.09E+01 MAXIMUM PERIOD NG DOSE TO LIMIT (Beta))

Dose Dose Limit Admin Admin  % T.Spec T.Spec %

Period Dose Type (mrad) Period Limit of Limit Limit of Limit Strt->End Beta 4.29E-05 Qrtr->End Beta 4.29E-05 31-day 3.OOE-01 1.43E-02 4.OOE-01 1.07E-02 Quarter 7.50E+00 5.72E-04 1.OOE+01 4.29E-04 Year->End Beta 4.29E-05 Annual 1.50E+01 2.86E-04 2.00E+01 2.15E-04 Major Contributors ...... .. 0.0  % or greater to total Nuclide Percentage AR-41 2.34E-02 KR-85M 8.75E-04 KR-85 0.00E+00 XE-133M 1.63E+00 KR-88 0.00E+00 XE-131M 0.OOE+00 XE-135 1.43E+01 XE-133 8.40E+01 43 of 238

RETDAS v3.6.3 <BRA> VSSI LIQUID RELEASE AND DOSE

SUMMARY

REPORT

(PERIOD BASIS - BY UNIT)------

Release ID .............. 1 All Liquid Release Types Period Start Date ..... .. 01/01/2011 00:00 Period End Date ....... 01/01/2012 00:00 Period Duration (mins) : 5.256E+05 Unit ..................  : 2 MULTIPLE RELEASE POINT MESSAGE Undiluted and Diluted Flowrate(s) and Concentration(s) cannot be combined.

RELEASE DATA --------

Total Release Duration (minutes) ...................................... 1.186E+06 Total Undiluted Volume Released (gallons) ............................ NA Average Undiluted Flowrate (gpm) ..................................... NA Total Dilution Volume (gallons) ...................................... NA Average Dilution Flowrate (gpm) ...................................... NA NUCLIDE DATA ------

Nuclide uCi CO-57 2.63E+02 NB-97 8.44E+02 AG-l10 6.33E+00 SN-113 1.76E+02 SB-124 7.27E+00 SB-125 2.42E+03 BA-133 4.30E+00 TE-123M 2.94E+01 CR-51 2.09E+02 MN-54 1.56E+03 FE-59 4.50E+01 CO-58 1.17E+04 CO-60 2.69E+04 ZN-65 1.28E+02 ZR-95 1.28E+02 ZR-97 2.35E+01 NB-95 3.23E+02 AG-11OM 9.57E+02 1-134 7.73E+00 CS-134 1.78E+00 CS-137 1.32E+01 LA-140 1.76E+00 CE-144 3.26E+01 Gamma 4.58E+04 AR-41 2.05E+00 XE-135M 3.35E+00 XE-133 3.23E+01 44 of 238

RETDAS v3.6.3 <BRA> VSSI LIQUID RELEASE AND DOSE

SUMMARY

REPORT

(PERIOD BASIS - BY UNIT)

Release ID .............. 1 All Liquid Release Types Period Start Date ..... :.01/01/2011 00:00 Period End Date ....... .. 01/01/2012 00:00 Period Duration (mins): 5.256E+05

ý== NUCLIDE DATA Nuclide uCi D&EG 3.77E+01 H-3 4.58E+08 FE-55 2.11E+04 NI-63 2.62E+02

- -eta 4.58E+08 Total 4.58E+08 45 of 238

RETDAS v3.6.3 <BRA> VSSI LIQUID RELEASE AND DOSE

SUMMARY

REPORT

(PERIOD BASIS - BY UNIT)------

Release ID .............. 1 All Liquid Release Types Period Start Date ..... :.01/01/2011 00:00 Period End Date .......  :.01/01/2012 00:00 Period Duration (mins): 5.256E205 Unit .................. 2 Receptor ................. 0 Liquid Receptor PERIOD DOSE BY AGEGROUP, PATHWAY, ORGAN (mrem)

Age/Path Bone Liver Thyroid Kidney Lung GI-Lli Skin TB APWtr 1.29E-05 8.69E-03 8.68E-03 8.68E-03 8.68E-03 8.87E-03 0.00E+00 8.70E-03 AFWFSp 8.07E-04 4.72E-03 3.60E-03 3.89E-03 3.76E-03 2.12E-02 0.00E+00 4.42E-03 TPWtr 1.23E-05 6.13E-03 6.11E-03 6.12E-03 6.12E-03 6.23E-03 0.00E+00 6.14E-03 TFWFSp 8.35E-04 3.90E-03 2.76E-03 3.05E-03 2.96E-03 1.51E-02 0.00E+00 3.54E-03 CPWtr 3.73E-05 1.18E-02 1.17E-02 1.17E-02 1.17E-02 1.18E-02 0.00E+00 1.18E-02 CFWFSp 1.07E-03 3.27E-03 2.29E-03 2.51E-03 2.46E-03 6.68E-03 0.00E+00 3.07E-03 IPWtr 2.91E-05 1.16E-02 1.15E-02 1.15E-02 1.15E-02 1.16E-02 0.OOE+00 1.16E-02 PERIOD DOSE BY AGEGROUP, ORGAN (mrem)

Agegroup Bone Liver Thyroid Kidney Lung GI-Lli Skin TB ADULT 8.20E-04 1.34E-02 1.23E-02 1.26E-02 1.24E-02 3.01E-02 0.00E+00 1.31E-02 TEEN 8.47E-04 1.00E-02 8.88E-03 9.16E-03 9.08E-03 2.14E-02 0.00E+00 9.67E-03 CHILD 1.10E-03 1.50E-02 1.40E-02 1.43E-02 1.42E-02 1.85E-02 0.00E+00 1.49E-02 INFANT 2.91E-05 1.16E-02 1.15E-02 1.15E-02 1.15E-02 1.16E-02 0.00E+00 1.16E-02 46 of 238

RETDAS v3.6.3 <BRA> VSSI LIQUID RELEASE AND DOSE

SUMMARY

REPORT

(PERIOD BASIS - BY UNIT)------

Release ID .............. 1 All Liquid Release Types Period Start Date ..... : 01/01/2011 00:00 Period End Date .......  :.01/01/2012 00:00 Period Duration (mins): 5.256E+05 Unit .................. 2 Receptor ................. 0 Liquid Receptor MAXIMUM PERIOD DOSE TO LIMIT (Any Organ)

Dose Age Dose Limit Admin Admin  % T.Spec T.Spec %

Period Group Organ (mrem) Period Limit of Limit Limit of Limit Strt->End ADULT GILLI 3. 01E-0 2 31-day 1.50E-01 2.01E+01 2.OOE-01 1.50E+01 Qrtr->End ADULT GILLI 3. 01E-0 2 Quarter 3.75E+00 8.02E-01 5.OOE+00 6.02E-01 Year->End ADULT GILLI 3. 01E-0 2 Annual 7.50E+00 4.01E-01 1.OOE+01 3.01E-01 Critical Pathway ........ 1 Fresh Water Fish - Sport (FFSP)

Major Contributors ...... 0.0  % or greater to total Nuclide Percentage H-3 4.09E+01 CR-51 5.92E-03 MN-54 1.84E+00 FE-55 4.92E-01 FE-59 3.26E-02 CO-58 1.92E+00 CO-60 1.18E+01 NI-63 1.05E-02 ZN-65 5.19E-01 ZR-95 4.52E-03 ZR-97 2 .82E-03 NB-95 4.26E+01 AG-1IOM 5.39E-02 1-134 6.95E-09 CS-134 1.92E-03 CS-137 1.17E-02 LA-140 9.24E-04 CE-144 3.56E-03 MAXIMUM PERIOD DOSE TO LIMIT (Tot Body))

Dose Age Dose Limit Admin Admin  % T.Spec T.Spec %

Period Group Organ (mrem) Period Limit of Limit Limit of Limit Strt->End CHILD TBODY 1.49E-0 Qrtr->End CHILD TBODY 1.49E-0 2 31-day 4.50E-02 3.30E+01 6.OOE-02 2.48E+01 Year->End CHILD TBODY 1.49E-0 2 Quarter 1.13E+00 1.32E+00 1.50E+00 9.91E-01 2 Annual 2.25E+00 6.61E-01 3.OOE+00 4.95E-01 Critical Pathway .......... 0 Potable Water (PWtr)

Major Contributors ...... 0.0  % or greater to total Nuclide Percentage 47 of 238

RETDAS v3.6.3 <BRA> VSSI LIQUID RELEASE AND DOSE

SUMMARY

REPORT

(PERIOD BASIS - BY UNIT)

Release ID .............. 1 All Liquid Release Types Period Start Date ..... .. 01/01/2011 00:00 Period End Date ....... .. 01/01/2012 00:00 Period Duration (mins) : 5.256E+05 Major Contributors ...... .. 0.0  % or greater to total Nuclide Percentage H-3 9.42E+01 CR-51 5.29E-05 MN-54 2.50E-01 FE-55 5.79E-01 FE-59 8.68E-03 CO-58 4.88E-01 CO-60 3.19E+00 NI-63 6.93E-02 ZN-65 8.07E-01 ZR-95 3.19E-06 ZR-97 1.54E-08 NB-95 8.41E-03 AG-11OM 2.68E-04 1-134 7.53E-06 CS-134 4.00E-02 CS-137 1.70E-01 LA-140 8.61E-09 CE-144 2.83E-06 48 of 238

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2011 UNIT 1 AND 2 (Docket Numbers 50-456 and 50-457)

ATTACHMENT 1 Wind Direction and Stability Classes 49 of 238

Braidwood Generating Station Period of Record: January - March 2011 Stability Class - Extremely Unstable 199Ft-3OFt Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 1 0 0 1 NNE 0 2 2 0 0 0 4 NE 0 6 10 0 0 0 16 ENE 0 11 4 0 0 0 15 E 0 7 2 0 0 0 9 ESE 0 0 3 0 0 0 3 SE 0 0 1 2 0 0 3 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 0 3 3 0 0 6 SW 0 0 0 0 0 0 0 WSW 0 0 4 1 1 0 6 W 0 2 4 6 0 0 12 WNW 0 7 12 3 0 0 22 NW 0 8 13 0 0 0 21 NNW 0 0 4 3 0 0 7 Variable 0 0 0 0 0 0 0 Total 0 43 62 19 1 0 125 J

Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 2 Hours of missing stability measurements in all stability classes: 4 50 of 238

Braidwood Generating Station Period of Record: January - March 2011 Stability Class - Moderately Unstable - 199Ft-3OFt Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 1 2 0 3 NNE 0 3 0 0 3 NE 0 1 5 0 6 ENE 0 3 3 0 6 E 0 5 1 0 6 ESE 0 2 0 0 2 SE 0 0 2 0 2 SSE 0 0 1 0 1 S 0 0 1 3 4 SSW 0 1 1 1 4 SW 0 0 2 1 3 WSW 0 0 5 1 6 W 0 2 1 2 5 WNW 0 3 1 0 4 NW 0 7 7 0 14 NNW 0 5 2 1 8 Variable 0 0 0 0 0 Total 0 33 34 9 1 0 77 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 1 Hours of missing stability measurements in all stability classes: 4 51 of 238

Braidwood Generating Station Period of Record: January - March 2011 Stability Class - Slightly Unstable - 199Ft-3OFt Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 1 2 NNE 0 6 7 NE 0 5 9 ENE 0 6 8 E 0 2 2 ESE 0 2 2 SE 0 0 3 SSE 0 0 7 S 0 0 2 SSW 0 0 8 SW 0 4 10 WSW 0 6 14 W 0 8 16 WNW 0 4 9 NW 0 4 6 NNW 0 5 9 Variable 0 1 1 Total 0 54 44 16 0 115 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 52 of 238

Braidwood Generating Station Period of Record: January - March 2011 Stability Class - Neutral - 199Ft-3OFt Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 14 56 8 78 NNE 2 13 26 7 48 NE 2 46 45 1 94 ENE 8 65 23 0 96 E 5 32 8 0 45 ESE 1 12 9 0 22 SE 1 19 33 7 60 SSE 1 29 27 4 61 S 0 8 43 7 58 SSW 0 12 32 15 59 SW 1 26 55 9 92 WSW 3 35 16 6 60 W 7 31 17 8 64 WNW 11 63 39 0 113 NW 9 32 24 1 66 NNW 4 26 34 8 72 Variable 2 0 0 0 2 Total 57 463 487 81 0 1090 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 2 Hours of missing stability measurements in all stability classes: 4 53 of 238

Braidwood Generating Station Period of Record: January - March 2011 Stability Class - Slightly Stable - 199Ft-3OFt Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 3 6 0 0 9 NNE 5 11 1 0 18 NE 11 22 1 7 46 ENE 18 35 3 0 56 E 22 10 0 0 32 ESE 5 10 6 0 21 SE 1 20 10 0 31 SSE 1 13 5 0 19 S 0 4 22 17 43 SSW 1 6 21 13 43 SW 0 20 47 10 77 WSW 4 25 7 3 39 W 11 22 12 7 52 WNW 18 43 12 3 76 NW 18 23 6 0 47 NNW 8 19 1 0 28 Variable 0 0 0 0 0 Total 126 289 154 60 0 637 Hours of calm in this stability class: 2 Hours of missing wind measurements in this stability class: 13 Hours of missing stability measurements in all stability classes: 4 54 of 238

Braidwood Generating Station Period of Record: January - March 2011 Stability Class - Moderately Stable - 199Ft-3OFt Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 0 0 0 0 NNE 1 0 0 0 0 0 1 NE 3 0 0 0 0 0 3 ENE 5 0 0 0 0 0 5 E 5 0 0 0 0 0 5 ESE 4 1 0 0 0 0 5 SE 1 0 0 0 0 0 1 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 1 0 0 0 0 0 1 SW 3 1 0 0 0 0 4 WSW 0 12 0 0 0 0 12 W 7 20 0 0 0 0 27 WNW 9 3 0 0 0 0 12 NW 7 0 0 0 0 0 7 NNW 3 1 0 0 0 0 4 Variable 0 0 0 0 0 0 0 Total 49 38 0 0 0 0 87 Hours of calm in this stability class: 1 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 55 of 238

Braidwood Generating Station Period of Record: January - March 2011 Stability Class - Extremely Stable - 199Ft-3OFt Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 NNE 1 0 1 NE 0 0 0 ENE 0 0 0 E 0 0 0 ESE 0 0 0 SE 0 0 0 SSE 0 0 0 S 0 0 0 SSW 0 0 0 SW 0 0 0 WSW 0 0 0 W 0 0 0 WNW 2 0 2 NW 1 0 1 NNW 0 0 0 Variable 0 0 0 Total 4 0 4 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 56 of 238

Braidwood Generating Station Period of Record: January - March 2011 Stability Class - Extremely Unstable - 199Ft-3OFt Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 1 0 0 1 NNE 0 2 0 0 0 2 NE 0 10 5 0 0 15 ENE 5 8 5 0 0 18 E 1 7 3 0 0 11 ESE 0 0 3 0 0 3 SE 0 0 0 3 0 3 SSE 0 0 0 0 0 0 S 0 0 0 0 0 0 SSW 0 1 2 3 0 6 SW 0 0 0 0 0 0 WSW 0 1 2 0 1 4 W 0 6 1 0 0 7 WNW 3 4 7 6 3 23 NW 4 10 10 3 1 28 NNW 0 0 4 2 0 6 Variable 0 0 0 0 0 0 Total 0 13 49 43 17 5 127 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 57 of 238

Braidwood Generating Station Period of Record: January - March 2011 Stability Class - Moderately Unstable - 199Ft-3OFt Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 2 2 0 0 0 4 NNE 0 2 1 1 0 0 4 NE 0 0 2 2 0 0 4 ENE 0 2 4 2 0 0 8 E 0 2 2 1 0 0 5 ESE 0 1 1 3 0 0 5 SE 0 0 0 1 0 0 1 SSE 0 0 1 0 0 0 1 S 0 0 0 1 3 0 4 SSW 0 1 1 1 0 1 4 SW 0 0 2 1 0 0 3 WSW 0 0 4 0 1 0 5 W 0 2 1 1 0 1 5 WNW 0 0 1 1 1 0 3 NW 0 3 6 6 1 0 16 NNW 0 1 3 2 0 0 6 Variable 0 0 0 0 0 0 0 Total 0 16 31 23 6 2 78 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 58 of 238

Braidwood Generating Station Period of Record: January - March 2011 Stability Class - Slightly Unstable - 199Ft-3OFt Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 2 0 0 0 2 NNE 0 4 3 0 0 0 7 NE 0 3 2 1 0 0 6 ENE 0 5 2 3 0 0 10 E 0 1 1 0 0 0 2 ESE 0 0 3 0 0 0 3 SE 0 0 2 0 1 0 3 SSE 0 0 0 4 3 0 7 S 0 0 0 0 2 0 2 SSW 0 0 0 3 1 2 6 SW 0 4 4 4 1 0 13 WSW 0 6 3 2 2 0 13 W 0 2 6 2 0 1 11 WNW 0 3 6 2 2 1 14 NW 0 1 2 2 1 0 6 NNW 0 3 2 2 2 0 9 Variable 0 1 0 0 0 0 1 Total 0 33 38 25 15 4 115 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability cl asses: 4 59 of 238

Braidwood Generating Station Period of Record: January - March 2011 Stability Class - Neutral - 199Ft-3OFt Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 8 23 40 8 80 NNE 1 6 12 16 7 43 NE 0 4 35 34 3 77 ENE 3 16 55 33 1 108 E 0 9 28 16 2 55 ESE 2 1 11 12 4 31 SE 0 2 14 27 13 58 SSE 0 4 24 13 9 50 S 0 0 26 34 5 67 SSW 0 2 16 28 15 63 SW 0 26 27 33 4 91 WSW 0 10 25 6 5 47 W 4 17 20 13 6 62 WNW 1 18 35 36 10 101 NW 2 13 33 39 9 96 NNW 1 9 21 23 6 62 Variable 0 1 0 0 0 1 Total 15 146 405 403 107 16 1092 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 60 of 238

Braidwood Generating Station Period of Record: January - March 2011 Stability Class - Slightly Stable - 199Ft-3OFt Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 1 9 1 0 0 12 NNE 3 4 7 3 0 1 18 NE 1 6 24 6 2 10 49 ENE 0 14 33 3 1 0 51 E 0 13 22 4 0 0 39 ESE 1 5 13 11 1 0 31 SE 0 1 8 18 3 0 30 SSE 0 3 10 8 1 0 22 S 0 0 4 10 22 1 37 SSW 0 0 6 26 22 4 58 SW 1 4 16 28 8 2 59 WSW 0 3 18 14 4 0 39 W 1 7 9 13 7 2 39 WNW 1 4 16 35 5 4 65 NW 2 3 37 28 1 0 71 NNW 2 2 25 3 0 0 32 Variable 0 0 0 0 0 0 0 Total 13 70 257 211 77 24 652 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 61 of 238

Braidwood Generating Station Period of Record: January - March 2011 Stability Class - Moderately Stable - 199Ft-3OFt Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 7 1 9 NNE 0 0 1 NE 0 0 0 ENE 3 0 6 E 2 0 5 ESE 2 1 5 SE 1 0 1 SSE 0 0 2 S 0 0 0 SSW 0 0 0 SW 0 0 1 WSW 3 2 6 W 5 11 16 WNW 9 10 20 NW 12 1 13 NNW 3 0 3 Variable 0 0 0 Total 2 13 47 26 0 0 88 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 62 of 238

Braidwood Generating Station Period of Record: January - March 2011 Stability Class - Extremely Stable - 199Ft-3OFt Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 2 0 0 0 2 NNE 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 0 0 0 0 0 0 0 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 1 0 0 0 0 1 W 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 1 0 0 0 0 0 1 NNW 0 0 0 0 0 0 0 Variable 0 0 0 0 0 0 0 Total 1 1 2 0 0 0 4 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 63 of 238

Braidwood Generating Station Period of Record: April - June 2011 Stability Class - Extremely Unstable - 199Ft-3OFt Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 2 1 0 0 0 3 NNE 0 5 11 4 0 0 20 NE 0 7 20 1 0 0 28 ENE 0 13 1 0 0 0 14 E 0 13 0 0 0 0 13 ESE 1 12 3 0 0 0 16 SE 0 16 3 4 0 0 23 SSE 0 6 1 1 0 0 8 S 0 11 4 2 0 0 17 SSW 1 2 7 8 1 0 19 SW 1 2 11 7 0 0 21 WSW 0 4 4 3 0 0 11 W 1 7 19 10 0 0 37 WNW 0 13 18 1 0 0 32 NW 0 8 12 1 0 0 21 NNW 1 6 4 0 0 0 11 Variable 0 0 0 0 0 0 0 Total 5 127 119 42 I 0 294 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 27 64 of 238

Braidwood Generating Station Period of Record: April - June 2011 Stability Class - Moderately Unstable - 199Ft-3OFt Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 4 NNE 4 6 NE 3 11 ENE 1 5 E 0 3 ESE 0 2 SE 3 9 SSE 6 10 S 2 7 SSW 4 10 SW 1 7 WSW 2 8 W 5 10 WNW 0 2 NW 0 1 NNW 2 6 Variable 0 0 Total 9 38 35 16 3 0 101 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 27 65 of 238

Braidwood Generating Station Period of Record: April June 2011 Stability Class - Slightly Unstable - 199Ft-3OFt Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 1 0 0 0 0 1 NNE 2 1 2 2 0 0 7 NE 0 5 1 2 0 0 8 ENE 0 5 3 0 0 0 8 E 0 5 0 0 0 0 5 ESE 0 3 2 0 0 0 5 SE 2 2 0 1 0 0 5 SSE 0 2 4 0 0 0 6 S 1 5 7 2 0 0 15 SSW 0 0 2 3 0 0 5 SW 0 1 1 7 2 0 11 WSW 0 1 5 0 0 0 6 W 0 1 3 4 0 0 8 WNW 0 3 4 0 0 0 7 NW 0 4 1 0 0 0 5 NNW 2 1 0 0 0 0 3 Variable 0 0 0 0 0 0 0 Total 7 40 35 21 2 0 105 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 27 66 of 238

Braidwood Generating Station Period of Record: April - June 2011 Stability Class - Neutral - 199Ft-3OFt Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 11 4 1 18 NNE 21 68 21 113 NE 46 48 10 109 ENE 51 25 0 84 E 19 15 0 39 ESE 26 12 1 41 SE 23 23 5 57 SSE 25 17 2 47 S 18 24 12 59 SSW 3 23 17 53 SW 7 46 20 75 WSW 7 27 0 34 W 23 33 7 63 WNW 18 15 11 49 NW 11 17 0 30 NNW 12 3 0 16 Variable 0 0 0 0 Total 47 321 400 107 11 1 887 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 27 67 of 238

Braidwood Generating Station Period of Record: April - June 2011 Stability Class - Slightly Stable - 199Ft-3OFt Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 6 11 3 0 20 NNE 3 24 6 0 33 NE 9 12 6 2 29 ENE 18 24 10 0 52 E 27 14 5 0 46 ESE 12 32 10 0 54 SE 3 39 19 0 61 SSE 11 28 7 2 48 S 3 23 33 5 64 SSW 1 8 16 3 36 SW 1 15 21 1 39 WSW 5 24 12 3 44 W 11 14 5 0 30 WNW 9 13 7 0 29 NW 8 4 3 0 15 NNW 5 4 0 0 9 Variable 1 0 0 0 1 Total 133 289 163 16 3 610 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 27 68 of 238

Braidwood Generating Station Period of Record: April - June 2011 Stability Class - Moderately Stable - 199Ft-3OFt Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 1 1 0 0 0 3 NNE 3 1 0 0 0 0 4 NE 6 1 0 0 0 0 7 ENE 4 0 2 0 0 0 6 E 12 0 0 0 0 0 12 ESE 8 3 0 0 0 0 11 SE 5 1 0 0 0 0 6 SSE 4 3 0 0 0 0 7 S 1 3 0 0 0 0 4 SSW 3 0 0 0 0 0 3 SW 0 1 0 0 0 0 1 WSW 5 4 0 0 0 0 9 W 12 12 0 0 0 0 24 WNW 1 1 0 0 0 0 2 NW 1 0 0 0 0 0 1 NNW 3 0 0 0 0 0 3 Variable 1 0 0 0 0 0 1 Total 70 31 3 0 0 0 104 Hours of calm in this stability class: 3 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 27 69 of 238

Braidwood Generating Station Period of Record: April - June 2011 Stability Class - Extremely Stable - 199Ft-3OFt Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total 0 0 N 1 0 0 1 0 0 NNE 0 0 0 0 0 0 NE 6 3 0 9 0 0 ENE 11 0 0 11 0 0 E 2 0 0 2 0 0 ESE 4 0 0 4 0 0 SE 3 0 0 3 0 0 SSE 1 1 0 2 0 0 S 1 0 0 1 0 0 SSW 0 0 0 0 0 0 SW 0 0 0 0 0 0 WSW 2 0 0 2 0 0 W 5 0 0 5 0 0 WNW 3 0 0 3 0 0 NW 3 0 0 3 0 0 NNW 1 0 0 1 0 0 Variable 0 0 0 0 Total 43 4 0 0 0 0 47 Hours of calm in this stability class: 6 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 27 70 of 238

Braidwood Generating Station Period of Record: April - June 2011 Stability Class - Extremely Unstable - 199Ft-3OFt Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 1 2 1 0 0 4 NNE 0 1 9 6 1 0 17 NE 0 9 10 5 0 25 ENE 0 5 7 6 0 0 18 E 0 5 11 0 0 0 16 ESE 0 6 5 2 2 0 15 SE 0 8 7 4 0 3 22 SSE 0 3 3 0 0 2 8 S 0 3 7 3 2 0 15 SSW 0 4 5 6 5 2 22 SW 0 0 3 8 5 0 16 WSW 0 0 4 4 1 0 9 W 0 6 3 7 7 3 26 WNW 1 4 12 23 3 0 43 NW 0 4 9 9 5 0 27 NNW 1 2 3 5 0 0 11 Variable 0 0 0 0 0 0 0 Total 2 53 99 94 36 10 294 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability cl asses: 27 71 of 238

Braidwood Generating Station Period of Record: April June 2011 Stability Class - Moderately Unstable - 199Ft-30Ft Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 4 NNE 5 NE 11 ENE 5 E 4 ESE 2 SE 8 SSE 9 S 8 SSW 8 SW 10 WSW 3 W 12 WNW 5 NW 2 NNW 5 Variable 0 Total 5 22 26 31 11 6 101 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 27 72 of 238

Braidwood Generating Station Period of Record: April - June 2011 Stability Class - Slightly Unstable - 199Ft-3OFt Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 1 1 0 0 0 3 NNE 0 2 2 0 2 0 6 NE 0 0 5 2 2 0 9 ENE 0 3 2 2 0 0 7 E 0 1 3 1 0 0 5 ESE 0 3 0 0 2 0 5 SE 0 2 2 0 1 0 5 SSE 0 3 1 3 0 0 7 S 0 3 1 6 1 0 11 SSW 0 1 1 4 2 1 9 SW 0 0 1 1 6 2 10 WSW 0 0 1 2 0 0 3 W 0 1 0 5 3 0 9 WNW 0 2 3 2 2 0 9 NW 0 0 4 3 0 0 7 NNW 0 0 0 0 0 0 0 Variable 0 0 0 0 0 0 0 Total 1 22 27 31 21 3 105 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 27 73 of 238

Braidwood Generating Station Period of Record: April - June 2011 Stability Class - Neutral - 199Ft-3OFt Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 4 4 3 1 0 12 NNE 0 8 19 45 25 5 102 NE 0 10 45 31 17 0 103 ENE 0 14 41 33 2 0 90 E 0 11 12 19 10 4 56 ESE 2 6 7 16 7 2 40 SE 1 4 10 20 13 3 51 SSE 1 5 16 18 3 1 44 S 0 7 15 22 8 4 56 SSW 1 1 6 20 16 12 56 SW 0 4 16 28 14 4 66 WSW 0 2 10 27 5 0 44 W 0 4 8 23 7 0 42 WNW 0 3 21 23 13 8 68 NW 0 5 10 20 4 0 39 NNW 1 5 10 2 0 0 18 Variable 0 0 0 0 0 0 0 Total 6 93 250 350 145 43 887 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 27 74 of 238

Braidwood Generating Station Period of Record: April - June 2011 Stability Class - Slightly Stable - 199Ft-3OFt Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 5 6 5 0 0 16 NNE 4 13 16 0 0 33 NE 5 12 8 2 0 27 ENE 4 21 4 1 0 31 E 10 39 9 2 1 62 ESE 6 11 20 6 1 45 SE 8 16 37 7 0 68 SSE 4 14 13 6 0 37 S 3 25 18 17 1 64 SSW 4 9 24 1 12 50 SW 1 16 22 0 2 42 WSW 2 17 8 1 1 29 W 2 20 12 2 1 37 WNW 6 11 15 2 0 34 NW 5 10 7 0 0 22 NNW 4 8 1 0 0 13 Variable 0 0 0 0 0 0 Total 4 73 248 219 47 19 610 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 27 75 of 238

Braidwood Generating Station Period of Record: April June 2011 Stability Class - Moderately Stable - 199Ft-3OFt Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 4 2 1 0 0 7 NNE 0 1 2 0 0 0 3 NE 0 2 3 1 0 0 6 ENE 1 1 1 0 0 0 3 E 0 2 7 2 0 0 11 ESE 0 3 2 1 0 0 6 SE 0 1 4 1 0 0 6 SSE 0 2 5 1 0 0 8 S 0 2 7 2 0 0 11 SSW 0 0 1 0 0 0 1 SW 0 3 1 0 0 0 4 WSW 0 1 3 0 0 0 4 W 0 1 5 2 0 0 8 WNW 0 1 10 8 0 0 19 NW 0 2 2 2 0 0 6 NNW 1 2 0 0 0 0 3 Variable 0 1 0 0 0 0 1 Total 2 29 55 21 0 0 107 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 27 76 of 238

Braidwood Generating Station Period of Record: April - June 2011 Stability Class - Extremely Stable - 199Ft-3OFt Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total 0 0 N 0 4 2 0 6 0 0 NNE 1 1 2 0 4 1 0 NE 0 2 2 0 5 0 0 ENE 0 0 1 0 1 0 0 E 1 0 1 0 2 0 0 ESE 1 3 0 0 4 0 0 SE 0 0 2 0 2 1 0 SSE 0 0 1 0 2 0 0 S 1 5 1 0 7 0 0 SSW 0 2 0 0 2 0 0 SW 0 0 0 0 0 0 0 WSW 0 1 1 0 2 0 0 W 0 1 1 0 2 0 0 WNW 0 1 5 0 6 NW 1 0 0 1 0 0 2 NNW 1 1 3 0 0 0 5 Variable 0 0 0 0 0 0 0 Total 6 21 22 3 0 0 52 Hours of calm in this stability class: 1 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 27 77 of 238

Braidwood Generating Station Period of Record: July - September 2011 Stability Class - Extremely Unstable - 199Ft-30Ft Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 7 3 2 0 0 13 NNE 0 8 16 5 0 0 29 NE 0 16 10 0 0 0 26 ENE 4 13 1 0 0 0 18 E 2 4 0 0 0 0 6 ESE 1 20 0 0 0 0 21 SE 0 17 0 0 0 0 17 SSE 0 27 2 0 0 0 29 S 0 15 14 0 0 0 29 SSW 0 13 16 7 0 0 36 SW 1 11 12 1 0 0 25 WSW 0 13 27 3 0 0 43 W 0 19 13 0 0 0 32 WNW 1 20 4 0 0 0 25 NW 1 22 2 0 0 0 25 NNW 0 25 13 2 0 0 40 Variable 0 0 0 0 0 0 0 Total 11 250 133 20 0 0 414 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 78 of 238

Braidwood Generating Station Period of Record: July - September 2011 Stability Class - Moderately Unstable - 199Ft-3OFt Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 7 10 1 0 18 NNE 0 3 4 1 0 8 NE 1 4 2 0 0 7 ENE 5 6 0 0 0 11 E 4 1 0 0 0 5 ESE 0 2 0 0 0 2 SE 2 6 0 0 0 8 SSE 1 9 2 0 0 12 S 1 3 1 0 0 5 SSW 0 2 2 2 0 6 SW 0 3 7 0 0 10 WSW 0 2 6 0 0 8 W 1 10 1 0 0 12 WNW 4 5 0 0 0 9 NW 1 5 0 0 0 6 NNW 0 6 3 2 0 11 Variable 0 0 0 0 0 0 Total 20 74 38 6 0 0 138 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 79 of 238

Braidwood Generating Station Period of Record: July - September 2011 Stability Class - Slightly Unstable - 199Ft-3OFt Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 7 5 0 0 0 13 NNE 0 6 3 0 0 0 9 NE 2 4 0 0 0 0 6 ENE 4 2 0 0 0 0 6 E 2 1 0 0 0 0 3 ESE 1 1 0 0 0 0 2 SE 2 1 1 0 0 0 4 SSE 0 4 1 0 0 0 5 S 0 3 2 0 0 0 5 SSW 0 2 1 0 0 0 3 SW 1 2 6 2 0 0 11 WSW 0 3 2 0 0 0 5 W 3 6 2 0 0 0 11 WNW 1 7 1 0 0 0 9 NW 2 5 1 0 0 0 8 NNW 0 12 3 0 1 0 16 Variable 1 0 0 0 0 0 1 Total 20 66 28 2 1 0 117 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 80 of 238

Braidwood Generating Station Period of Record: July - September 2011 Stability Class - Neutral - 199Ft-30Ft Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 18 9 2 31 NNE 7 43 15 3 68 NE 14 20 0 0 34 ENE 16 15 0 0 31 E 7 4 0 0 11 ESE 5 14 1 0 20 SE 1 18 5 0 24 SSE 4 19 10 1 34 S 2 12 19 1 34 SSW 2 5 25 4 36 SW 1 13 22 2 38 WSW 0 13 7 1 21 W 8 15 2 0 25 WNW 11 14 3 0 28 NW 3 12 2 5 22 NNW 3 40 8 8 59 Variable 2 0 0 0 2 Total 88 275 128 27 0 518 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 81 of 238

Braidwood Generating Station Period of Record: July - Septemb er 2011 Stability Class - Slightly Stable - 199Ft- -30Ft Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 20 26 3 49 NNE 15 22 3 40 NE 27 10 0 37 ENE 51 4 0 55 E 31 4 0 35 ESE 14 29 0 43 SE 13 20 0 33 SSE 8 31 0 39 S 5 40 7 52 SSW 3 14 27 44 SW 1 11 26 38 WSW 6 14 0 20 W 19 11 2 32 WNW 18 2 1 21 NW 17 4 4 25 NNW 13 24 0 37 Variable 0 0 0 0 Total 261 266 73 0 0 0 600 Hours of calm in this stability class: 2 Hours of missing wind measurements in this stability class: 1 Hours of missing stability measurements in all stability classes: 4 82 of 238

. Braidwood Generating Station Period of Record: July - September 2011 Stability Class - Moderately Stable - 199Ft-3OFt Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 18 6 0 0 0 0 24 NNE 11 0 0 0 0 0 11 NE 12 0 0 0 0 0 12 ENE 12 0 0 0 0 0 12 E 27 0 0 0 0 0 27 ESE 16 4 0 0 0 0 20 SE 7 1 0 0 0 0 8 SSE 7 6 0 0 0 0 13 S 4 0 0 0 0 0 4 SSW 7 2 0 0 0 0 9 SW 3 2 0 0 0 0 5 WSW 12 7 0 0 0 0 19 W 26 2 0 0 0 0 28 WNW 15 0 0 0 0 0 15 NW 17 0 0 0 0 0 17 NNW 18 0 0 0 0 0 18 Variable 0 0 0 0 0 0 0 Total 212 30 0 0 0 0 242 Hours of calm in this stability class: 16 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 83 of 238

Braidwood Generating Station Period of Record: July - September 2011 Stability Class - Extremely Stable - 199Ft-3OFt Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total o 0 N 7 0 0 7 0 0 NNE 6 0 0 6 0 0 NE 2 0 0 2 0 0 ENE 11 0 0 11 0 0 E 9 0 0 9 0 0 ESE 7 0 0 7 0 0 SE 3 0 0 3 0 0 SSE 1 0 0 1 0 0 S 2 0 0 2 0 0 SSW 1 0 0 1 0 0 SW 7 0 0 7 WSW 8 2 0 0 0 10 W 20 4 0 0 0 24 WNW 6 0 0 0 0 6 NW 6 0 0 0 0 6 NNW 3 0 0 0 0 3 Variable 0 0 0 0 0 0 Total 99 6 0 0 0 105 Hours of calm in this stability class: 51 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability cl asses: 4 84 of 238

Braidwood Generating Station Period of Record: July - September 2011 Stability Class - Extremely Unstable - 199Ft-3OFt Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 4 5 2 0 0 11 NNE 0 4 7 9 6 0 26 NE 8 12 7 0 0 28 ENE 1 14 2 2 0 0 19 E 0 5 0 0 0 0 5 ESE 1 10 10 0 0 0 21 SE 0 14 5 0 0 19 SSE 0 14 7 1 0 22 S 0 11 13 2 0 28 SSW 0 8 21 8 0 44 SW 1 5 13 3 0 22 WSW 0 4 13 11 0 28 W 0 5 25 12 0 43 WNW 0 16 11 1 0 32 NW 0 10 10 1 0 21 NNW 0 18 22 2 0 45 Variable 0 0 0 0 0 0 Total 4 150 176 61 23 0 414 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 85 of 238

Braidwood Generating Station Period of Record: July - September 2011 Stability Class - Moderately Unstable - 199Ft-30Ft Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 1 8 6 1 0 16 NNE 0 3 2 3 1 0 9 NE 0 3 2 2 0 0 7 ENE 3 4 3 0 0 0 10 E 2 2 1 0 0 0 5 ESE 0 1 1 0 0 0 2 SE 0 5 1 0 0 0 6 SSE 0 9 3 2 0 0 14 S 0 3 0 0 0 0 3 SSW 0 4 0 2 1 0 7 SW 0 1 6 3 1 0 11 WSW 0 0 6 2 0 0 8 W 0 4 6 1 0 0 11 WNW 1 8 1 1 0 0 11 NW 0 3 3 0 0 0 6 NNW 1 3 5 2 1 0 12 Variable 0 0 0 0 0 0 0 Total 7 54 48 24 5 0 138 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 86 of 238

Braidwood Generating Station Period of Record: July - September 2011 Stability Class - Slightly Unstable - 199Ft-3OFt Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 3 6 2 0 0 11 NNE 1 3 3 3 0 0 10 NE 1 2 0 1 0 0 4 ENE 2 4 1 0 0 0 7 E 0 4 0 0 0 0 4 ESE 0 1 1 0 0 0 2 SE 0 0 0 0 1 0 1 SSE 1 3 1 0 1 0 6 S 0 2 2 0 1 0 5 SSW 0 0 0 2 0 0 2 SW 0 2 4 1 2 0 9 WSW 0 2 5 2 0 0 9 W 1 2 0 3 0 0 6 WNW 1 7 3 1 0 0 12 NW 2 4 5 1 0 0 12 NNW 0 6 8 1 1 0 16 Variable 1 0 0 0 0 0 1 Total 10 45 39 17 6 0 117 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 87 of 238

Braidwood Generating Station Period of Record: July - September 2011 Stability Class - Neutral - 199Ft-3OFt Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 6 8 8 26 NNE 2 15 12 14 46 NE 3 16 27 3 49 ENE 2 20 11 1 34 E 4 8 3 0 15 ESE 3 2 7 7 19 SE 2 3 7 9 22 SSE 0 8 11 11 32 S 0 4 10 10 32 SSW 1 3 5 19 33 SW 0 4 17 17 40 WSW 0 2 19 6 27 W 4 7 6 5 23 WNW 2 8 11 5 29 NW 4 6 13 2 31 NNW 1 8 35 8 59 Variable 1 0 0 0 1 Total 30 120 202 125 33 8 518 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 88 of 238

Braidwood Generating Station Period of Record: July - September 2011 Stability Class - Slightly Stable - 199Ft-3OFt Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 4 27 10 43 NNE 6 18 8 33 NE 10 26 2 39 ENE 30 25 0 56 E 19 27 0 49 ESE 4 17 16 38 SE 12 14 8 34 SSE 6 14 7 27 S 4 32 11 48 SSW 3 21 28 56 SW 4 17 27 50 WSW 4 13 1 18 W 4 11 2 19 WNW 8 16 2 27 NW 6 17 3 30 NNW 10 21 4 35 Variable 0 0 0 0 Total 13 134 316 129 9 602 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 1 Hours of missing stability measurements in all stability classes: 4 89 of 238

Braidwood Generating Station Period of Record: July - September 2011 Stability Class - Moderately Stable - 199Ft-3OFt Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 3 2 24 3 0 0 32 NNE 1 7 9 0 0 0 17 NE 0 3 5 0 0 0 8 ENE 2 9 2 0 0 0 13 E 1 6 11 1 0 0 19 ESE 3 5 2 2 0 0 12 SE 0 7 10 2 0 0 19 SSE 2 4 6 0 0 0 12 S 1 8 5 1 0 0 15 SSW 1 11 5 0 0 0 17 SW 1 8 2 0 0 0 11 WSW 1 7 5 0 0 0 13 W 1 5 10 2 0 0 18 WNW 0 4 13 1 0 0 18 NW 0 9 12 1 0 0 22 NNW 0 6 6 0 0 0 12 Variable 0 0 0 0 0 0 0 Total 17 101 127 13 0 0 258 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 90 of 238

Braidwood Generating Station Period of Record: July - September 2011 Stability Class - Extremely Stable - 199Ft-3OFt Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 0 15 NNE 0 0 6 NE 0 0 2 ENE 1 0 5 E 0 0 4 ESE 1 0 14 SE 0 0 6 SSE 1 0 10 S 2 0 7 SSW 2 0 9 SW 5 12 1 0 0 0 18 WSW 4 9 9 0 0 23 W 3 9 8 0 0 0 20 WNW 2 3 0 0 0 0 5 NW 1 3 4 0 0 0 8 NNW 2 1 1 0 0 0 4 Variable 0 0 0 0 0 0 0 Total 25 81 45 5 0 0 156 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 4 91 of 238

Braidwood Generating Station Period of Record: October - December 2011 Stability Class - Extremely Unstable - 199Ft-3OFt Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 3 0 0 3 NNE 0 0 1 0 0 1 NE 0 0 0 0 0 0 ENE 0 2 0 0 0 2 E 0 0 0 0 0 0 ESE 0 0 0 0 0 0 SE 0 1 2 0 0 3 SSE 0 8 0 0 0 8 S 0 4 10 0 0 14 SSW 0 1 3 0 0 4 SW 0 0 2 0 0 2 WSW 0 0 0 1 0 1 W 0 1 2 10 0 13 WNW 0 7 5 0 0 12 NW 0 7 5 0 0 12 NNW 0 2 0 0 0 2 Variable 0 0 0 0 0 0 Total 0 33 33 11 0 0 77 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3 92 of 238

Braidwood Generating Station Period of Record: October - December 2011 Stability Class - Moderately Unstable - 199Ft-3OFt Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 1 2 0 0 0 3 NNE 0 0 1 0 0 0 1 NE 0 0 0 0 0 0 0 ENE 0 1 0 0 0 0 1 E 0 0 0 0 0 0 0 ESE 0 1 0 0 0 0 1 SE 1 6 1 0 0 0 8 SSE 1 1 2 0 0 0 4 S 0 1 8 0 0 0 9 SSW 0 0 5 1 1 1 8 SW 0 1 3 0 0 0 4 WSW 0 2 3 2 0 0 7 W 0 6 4 2 0 0 12 WNW 1 6 2 0 0 0 9 NW 0 3 3 1 0 0 7 NNW 0 4 0 0 0 0 4 Variable 0 0 0 0 0 0 0 Total 3 33 34 6 1 1 78 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3 93 of 238

Braidwood Generating Station Period of Record: October - December 2011 Stability Class - Slightly Unstable - 199Ft- 30Ft Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total 0 1 2 N 0 0 3 0 1 1 NNE 0 0 2 0 0 2 NE 0 0 2 0 0 0 ENE 0 0 0 1 0 0 E 0 0 1 0 0 0 ESE 0 0 0 0 1 0 SE 0 0 1 SSE 0 5 2 0 0 7 S 1 2 7 2 2 14 SSW 2 2 5 11 0 20 SW 0 5 2 1 0 8 WSW 1 5 2 0 0 8 W 0 6 6 1 0 13 WNW 0 3 2 1 0 6 NW 1 1 1 0 0 3 NNW 0 4 3 0 0 7 Variable 0 0 0 0 0 0 Total 6 36 35 16 2 0 95 Hours of calm in this stability class: 0 Hours of missing wind measurements in this sta bility class: 0 Hours of missing stability measurements in all stabi lity classes: 3 94 of 238

Braidwood Generating Station Period of Record: October - December 2011 Stability Class - Neutral - 199Ft-30Ft Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 26 42 15 4 0 89 NNE 3 17 36 6 1 0 63 NE 5 22 17 4 0 0 48 ENE 2 33 0 0 0 0 35 E 4 5 0 0 0 0 9 ESE 3 2 1 0 0 0 6 SE 1 10 7 2 0 0 20 SSE 2 30 39 1 0 0 72 S 0 11 42 68 11 0 132 SSW 0 12 27 46 14 2 101 SW 0 12 38 9 2 2 63 WSW 3 30 19 0 0 0 52 W 6 21 28 15 0 0 70 WNW 9 31 13 5 0 0 58 NW 7 28 37 0 0 0 72 NNW 3 33 34 17 0 0 87 Variable 0 0 0 0 0 0 0 Total 50 323 380 188 32 4 977 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 9 Hours of missing stability measurements in all stability cl asses: 3 95 of 238

Braidwood Generating Station Period of Record: October - December 2011 Stability Class - Slightly Stable - 199Ft- 3OFt Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 5 8 1 0 14 NNE 1 7 3 0 11 NE 6 10 0 1 17 ENE 12 10 0 0 22 E 7 3 0 0 10 ESE 1 6 0 0 7 SE 2 23 13 0 38 SSE 4 57 25 3 89 S 1 42 59 26 128 SSW 3 29 37 8 79 SW 4 29 9 1 43 WSW 10 53 8 0 71 W 19 39 22 0 80 WNW 17 15 2 0 34 NW 5 16 8 0 29 NNW 2 14 1 0 17 Variable 0 0 0 0 0 Total 99 361 188 39 2 0 689 Hours of calm in this stability class: 2 Hours of missing wind measurements in this stability class: 3 Hours of missing stability measurements in all stability classes: 3 96 of 238

Braidwood Generating Station Period of Record: October December 2011 Stability Class - Moderately Stable - 199Ft-3OFt Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 1 0 0 0 0 1 NNE 1 1 0 0 0 0 2 NE 2 0 0 0 0 0 2 ENE 5 0 0 0 0 0 5 E 9 0 0 0 0 0 9 ESE 5 6 0 0 0 0 11 SE 8 12 0 0 0 0 20 SSE 4 7 0 0 0 0 11 S 4 0 0 0 0 0 4 SSW 4 5 4 0 0 0 13 SW 3 2 2 0 0 0 7 WSW 9 35 0 0 0 0 44 W 16 8 0 0 0 0 24 WNW 11 0 0 0 0 0 11 NW 4 0 0 0 0 0 4 NNW 4 1 0 0 0 0 5 Variable 0 0 0 0 0 0 0 Total 89 78 6 0 0 0 173 Hours of calm in this stability class: 4 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3 97 of 238

Braidwood Generating Station Period of Record: October - December 2011 Stability Class - Extremely Stable - 199Ft-30Ft Delta-T (F)

Winds Measured at 34 Feet Wind Speed (in mph) wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total 0 0 0 N 0 0 0 0 0 0 0 NNE 0 0 0 0 0 0 0 NE 1 0 0 1 0 0 0 ENE 1 0 0 1 0 0 0 ii E 11 0 0 2 0 0 8 ESE 6 0 0 0 0 0 13 SE 13 0 0 0 0 0 SSE 2 0 0 2 1 0 0 S 4 0 0 5 4 0 0 SSW 4 0 0 8 0 0 0 SW 3 0 0 3 0 0 0 WSW 3 0 0 3 0 0 0 W 12 0 0 12 0 0 0 WNW 9 0 0 9 0 0 0 NW 4 0 0 4 0 0 0 NNW 1 0 0 1 0 0 0 Variable 0 0 0 0 Total 74 7 0 0 0 0 81 Hours of calm in this stability class: 17 Hours of missing wind measurements in this stabil ity class: 0 Hours of missing stability measurements in all st ability classes: 3 98 of 238

Braidwood Generating Station Period of Record: October - December 2011 Stability Class - Extremely Unstable - 199Ft-3OFt Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 1 2 0 0 3 NNE 0 0 0 1 0 0 1 NE 0 0 0 0 0 0 0 ENE 0 0 0 0 0 0 0 E 0 0 2 0 0 0 2 ESE 0 0 0 0 0 0 0 SE 0 0 0 2 0 0 2 SSE 0 2 7 0 0 0 9 S 0 1 5 7 0 0 13 SSW 0 1 1 3 0 0 5 SW 0 0 0 2 0 0 2 WSW 0 0 0 0 0 0 0 W 0 0 0 0 2 1 3 WNW 0 4 5 3 10 2 24 NW 0 1 8 3 0 0 12 NNW 0 0 1 0 0 0 1 Variable 0 0 0 0 0 0 0 Total 0 9 30 23 12 3 77 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3 99 of 238

Braidwood Generating Station Period of Record: October - December 2011 Stability Class - Moderately Unstable - 199Ft-30Ft Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 0 0 0 2 NNE 0 1 0 0 1 NE 0 0 0 0 0 ENE 1 0 0 0 1 E 0 0 0 0 0 ESE 0 0 0 0 0 SE 3 1 0 0 7 SSE 1 1 0 0 4 S 1 5 0 0 7 SSW 3 6 1 2 12 SW 1 1 0 0 3 WSW 2 1 1 0 5 W 4 3 2 1 12 WNW 5 2 1 0 9 NW 2 1 1 0 8 NNW 4 1 1 0 7 Variable 0 0 0 0 0 Total 15 29 23 7 3 78 Hours of calm in this stability class: 0 Hours of missing wind measurements in this sta bility class: 0 Hours of missing stability measurements in all stability cliasses: 3 100 of 238

Braidwood Generating Station Period of Record: October - December 2011 Stability Class - Slightly Unstable - 199Ft-3OFt Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 3 0 0 0 3 NNE 0 0 1 1 0 0 2 NE 0 0 0 0 0 0 0 ENE 0 0 1 1 0 0 2 E 0 0 0 0 0 0 0 ESE 0 0 0 0 0 0 0 SE 0 0 0 0 0 0 0 SSE 1 2 3 1 0 0 7 S 2 1 3 5 0 0 11 SSW 0 4 4 3 7 4 22 SW 0 2 1 5 1 0 9 WSW 0 3 4 1 0 0 8 W 0 6 1 2 2 0 11 WNW 0 1 0 2 4 0 7 NW 0 3 3 0 0 0 6 NNW 0 0 4 3 0 0 7 Variable 0 0 0 0 0 0 0 Total 3 22 28 24 14 4 95 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3 101 of 238

Braidwood Generating Station Period of Record: October - December 2011 Stability Class - Neutral - 199Ft-3OFt Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 11 35 29 11 3 89 NNE 1 23 17 10 8 59 NE 4 15 23 9 1 55 ENE 7 24 4 1 0 36 E 6 14 0 0 0 20 ESE 1 2 1 0 0 6 SE 2 5 5 1 1 17 SSE 6 13 16 10 0 46 S 2 26 32 40 24 124 SSW 1 9 30 55 32 127 SW 4 27 24 13 10 78 WSW 12 19 13 1 1 46 W 14 11 20 6 2 55 WNW 11 13 19 13 9 65 NW 16 21 23 13 0 77 NNW 8 30 32 13 3 86 Variable 0 0 0 0 0 0 Total 15 106 287 288 196 94 986 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3 102 of 238

Braidwood Generating Station Period of Record: October - December 2011 Stability Class - Slightly Stable - 199Ft-3OFt Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 8 2 0 14 NNE 1 5 1 10 NE 7 2 0 13 ENE 15 0 0 24 E 10 0 0 11 ESE 4 4 0 8 SE 5 14 0 21 SSE 20 30 9 61 S 31 42 39 116 SSW 25 39 35 108 SW 27 22 4 59 WSW 22 18 0 48 W 33 39 7 89 WNW 12 25 1 47 NW 15 11 0 32 NNW 15 11 1 33 Variable 0 0 0 0 Total 7 67 250 264 97 9 694 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3 103 of 238

Braidwood Generating Station Period of Record: October - December 2011 Stability Class - Moderately Stable - 199Ft-3OFt Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 1 0 0 0 1 NNE 0 0 1 1 0 0 2 NE 0 2 0 2 0 0 4 ENE 0 1 3 0 0 0 4 E 0 2 1 0 0 0 3 ESE 0 0 3 2 0 0 5 SE 0 0 9 3 0 0 12 SSE 2 0 8 5 0 0 15 S 0 4 7 1 0 0 12 SSW 0 1 4 0 0 0 5 SW 0 5 3 6 2 0 16 WSW 0 0 2 4 0 0 6 W 0 6 16 25 0 0 47 WNW 1 2 15 1 0 0 19 NW 0 5 12 2 0 0 19 NNW 0 0 6 1 0 0 7 Variable 0 0 0 0 0 0 0 Total 3 28 91 53 2 0 177 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3 104 of 238

Braidwood Generating Station Period of Record: October - December 2011 Stability Class - Extremely Stable - 199Ft-3OFt Delta-T (F)

Winds Measured at 203 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total 1 2 0 N 0 0 0 3 1 0 0 NNE 0 0 0 1 0 0 0 NE 0 0 0 0 ENE 1 1 1 0 0 0 3 E 1 2 0 0 0 0 3 ESE 1 2 1 1 0 0 5 SE 0 1 4 1 0 0 6 SSE 1 2 5 2 0 0 10 S 0 2 8 0 0 0 10 SSW 0 1 4 0 0 0 5 SW 0 2 10 0 0 0 12 WSW 1 1 2 0 0 0 4 W 1 3 0 0 0 0 4 WNW 1 2 3 0 0 0 6 NW 1 1 5 5 0 0 12 NNW 1 3 5 1 0 0 10 Variable 0 0 0 0 0 0 0 Total 9 25 50 10 0 0 94 Hours of calm in this stability class: 4 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3 105 of 238

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2011 UNIT 1 AND 2 (Docket Numbers 50-456 and 50-457)

ATTACHMENT 2 Supporting Documentation of Engineering Change 375873 106 of 238

EC 375873 4.1.4.1 Basic System, Structure, or Cornmonent (SSC) Functions The function of the Circulating Water (CW) blowdown system is to transfer water from the cooling lake to the Kankakee River in order to maintain proper chemistry in the cooling lake. The lake blowdown system header is also used to transfer waste water from the Sewage Treatment Facility and contaminated water from the release tanks to the Kankakee River. The CW Blowdown System provides a design flow rate of approximately 25,000 gpm with both Units in operation. Due to the configuration of the existing CW Blowdown System line outfall structure and discharge canal, liquid releases may not achieve the desired levels of mixing in the river near the discharge location.

The installation work for the Braidwood CW Blowdown river diffuser project has been divided into three separate EC's for each phase of installation work. This EC 375873 will provide the third and final phase of the installation work which consists of routing the CW Blowdown System piping from the piping termination point located near the Kankakee River west bank from the design provided in Engineering Change (EC) 375872 to a new termination point at a discharge location within the Kankakee River.

A total of seven evenly spaced 16" OD branch lines (Equipment Part Numbers - EPNs: 0CW1 12AA through 0CW1 12AG) will be attached to the 30" OD CW pipe header (EPN: OCWE2B) that is encased in a concrete spillway. The configuration of each branch discharge line will consist of a weldolet fitting which attaches the discharge line to the 30" OD CW header pipe, a short 2 foot (approximate) segment of 16" OD pipe, and a 16" slip-on flange.

A vendor supplied flanged nozzle diffuser (EPNs: OCW1 14MA through 0CW1 14MG) will be bolted to the end of the CW discharge pipe at each of the seven nozzle locations. A restriction orifice plate (EPNs: 0CW1 13MA through OCW1 13MG) will be installed between the slip-on flange and the vendor supplied nozzle diffuser flange.

The orifice plate diameter will vary based on the nozzle diffuser location as shown in a table on Drawing M-900, Sheet 13C included with this EC. A gasket will be installed on only one side of the orifice plate to provide a mechanical seal between the metal slip-on flange and metal orifice plate for each of the seven nozzle locations.

The orifice plate diameter was selected for each discharge line in order to balance the flow passing through each nozzle diffuser to within 10% of each other and to help maintain a pressure above vapor pressure at the discharge of the 18" globe valves (EPNs: OCW260A/B).

A protective coating will be applied to external surfaces of the buried and submerged portions of the piping installed in this EC in order to mitigate corrosion on the external surfaces of the pipe.

A concrete spillway will be installed in this EC for the purpose of anchoring the CW blowdown line in the river bed and for dispersing CW blowdown flow exiting the nozzle diffusers in order to prevent potential erosion of the river bottom.

The nozzle diffuser configuration will consist of seven evenly spaced discharge points in order to improve the mixing of liquid releases into the Kankakee River, eliminate background noise levels and organic foam, enable improved alternative release strategies, and minimize operations constraints on timed releases.

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4.1.4.2 Safety Classification of Configuration Change The affected portions of the CW system are classified as non-safety related (Quality Class D, and Seismic Category II) and are not required for safe shutdown; therefore, this EC is classified as Non-Safety Related.

4.1.4.3 Seismic Classification The CW systems is classified as Seismic Category I1. Therefore, this EC is classified as Seismic Category I1.

4.1.5 Performance Requirements and Desiqn Conditions The CW system piping installed in this EC will have the following design conditions:

Design Pressure: 110 PSIG Design Temperature: 100'F Piping Design Table (PDT): 100BB The piping pressure and temperature ratings listed above are consistent with the design conditions for the existing CW Blowdown System piping (e.g., lines 0CW2CA-30", OCWC2CA-18, 0CW100A-1", and 0CW101A-1/2"). The pressure and temperature ratings for the existing lines were obtained from Passport.

As mentioned in Section 4.1.21 and 4.1.24, the positions of globe valves 0CW26OA/B and OCW152A/B will be changed in order to direct CW blowdown flow through the new nozzle diffusers installed in this EC. The valves positions of 0CW260A/B and 0CW 152A/B can be changed by manually adjusting the handwheels located in the modified instrument pit and the existing outfall structures respectively.

As discussed in Calculation BRW-02-0152-M, Revision 1, the hydraulic performance and physical parameters of the nozzle diffusers were obtained from the vendor's diffuser analysis. This analysis calculated that at the maximum NPDES allowable flow rate of 30,000 gpm, the head loss through the nozzle diffusers is 3.3 feet. This head loss was used as an input to the hydraulic model included in Calculation BRW-02-0152-M, Revision 2.

Vendor documentation indicates that the ethylene propylene diene monomer (EPDM) nozzle diffusers and gaskets have an operating temperature range of -50 deg F to +300 deg F. The temperatures that are anticipated at the nozzle diffuser installation location submerged beneath the surface of the Kankakee River are expected to be within the operating temperature range of the EPDM material. The vendor documentation listing the diffuser elastomer properties and applications is included in Tab 8 of this EC for reference.

Orifice plates of varying diameters are installed at the end of each of the seven 16" OD diffuser branch lines installed in this EC in order to balance the flow passing through each nozzle diffuser to within 10% of each other and to help maintain a pressure above vapor pressure at the discharge of the globe valves (EPNs: OCW26OA/B).

The design basis for the orifice plate diameters was provided in Calculation BRW-02-0152-M, Revision 2 which was provided in support of EC 375871. The design basis of the minimum required orifice plate thickness is included in Calculation BRW-06-0174-M, Revision 1 which is provided in support of this EC package. The orifice plate design details are shown on Drawing M-900, Sheet 13C included with this EC package.

The gasket and orifice plates are specified as full faced with the corresponding bolt holes in accordance with 150 lb. class ASME B16.5 pipe flange requirements. The surface finish of the gasket surface sealing areas of the orifice plates is specified in accordance with the requirements of ASME B16.5, Section 6.4.5.3 with a serrated concentric pattern. This surface finish will serve to provide a proper seal of the bolted nozzle diffuser connection to the end of the CW piping utilizing a full-faced gasket.

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The nozzle diffusers are manufactured of an EPDM elastomer material and are designed to act as a check valve to prevent reverse flow of the Kankakee River water or air back into the CW piping which could affect the performance of the CW blowdown system. There are a total of seven nozzle diffusers that will be installed in this EC for discharging the CW blowdown flow into the Kankakee River.

4.1.6 Design Requirements for Surveillance Testinq and Acceptance Testing The required testing for this EC is specified in accordance with procedure CC-AA-107-1001 with specific testing identified on Form CC-AA-107, Attachment 1, provided in this EC.

A Thermal Impact and Mixing Zone Analysis performed in 2009 by Hydroqual concluded that use of the new multi-port diffuser would significantly improve discharge dilution over the existing configuration which consists of two 18" discharge lines feeding a flume that discharges above the surface of the Kankakee River. Another study can be performed following installation if further information is needed on the thermal impact and mixing zone of the new multi-port diffuser but this is not required for this EC.

4.1.9 Affected Calculations or Design Analyses Calculation BRW-02-0152-M, Revision 1 (Circulating Water Blowdown Hydraulic Analysis) was provided in support of EC 375871 in order to model the alternate CW blowdown flow path through the nozzle diffusers. The calculation revision specified the diameters of new restriction orifice plates that are required to be installed at the end of lines 0CW 112AA through 0CW 112AG in order to balance the flow through the nozzle diffusers to within 10% of each other and to help maintain a pressure above vapor pressure at the discharge of the 18" globe valves (EPNs: OCW260A/B). The orifice diameters will vary at each nozzle diffuser location and are listed in a table on Drawing M-900, Sheet 13C included with this EC package. Minor revision 1A is provided in support of this EC package to document the diffuser spacing changing from 11' to 7' apart. The minor revision concludes that the revised diffuser spacing improves the ability of the blowdown booster pumps to meet the flow requirements in the analysis.

Calculation BRW-06-0073-M, Revision 3 (Hydraulic Transient Analysis of the Circulating Water Blowdown Pipeline) was provided in support of EC 375871 for the purpose of modeling the CW river diffuser flow path for various event scenarios that are described within the calculation. Major revision 4 is provided in support of EC 380017 to document the removal and addition of some vacuum breakers on the CW line but also to document the nozzle diffuser spacing changing from 11' to 7' apart. The major revision concludes that the revised diffuser spacing will not significantly impact the overall results of the transient analysis.

Calculation BRW-06-0174-M, Revision 2 (Orifice Sizing for CW blowdown Lines 0CWC2CA and OCWC2CB and the River Diffuser Branch Lines) is issued in support of this EC package to provide the basis for the minimum required thickness for diffuser orifice plates OCW1 13MA through 0CW1 13MG to ensure deformation of the orifice does not occur. The orifice plate thickness is provided on Drawing M-900, Sheet 13C included with this EC package.

The orifice plate material listed in the notes on Drawing M-900, Sheet 13C (ASTM A240 Gr. 304L) does not match the orifice plate material listed in Calculation BRW-06-0174-M (ASTM A312, TP 304L). However, as listed in the tables of ASME B31.1 Code, the maximum allowable stress value in tension (16.7 ksi for temperatures not exceeding -20 to 100 OF) for the ASTM A240 Gr. 304L material is greater than the maximum allowable stress value in tension (15.7 ksi for temperatures not exceeding -20 to 100 OF) for the ASTM A312, TP 304L material. As a result, using lower allowable stress values in Calculation BRW-06-0174-M, Revision 1 results in a conservatively larger orifice plate thickness and is therefore acceptable by engineering judgment.

The grade of stainless steel (304L) specified for both the ASTM A312 and ASTM A240 materials is the same.

Calculation 2.4.1-BRW-09-0073-S was updated and reissued under Revision 0 in support of this EC package to provide an evaluation of the concrete spillway for the loads transferred from the CW piping that is installed in this EC. Minor revision OA is also issued in support of this EC package to document the diffuser spacing changing from 11' to 7' apart. The design of the concrete spillway will remain adequate based on the revised diffuser spacing.

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4.1.13 Material Requirements The new CW system pipe and fitting materials installed in this EC are specified in accordance with Braidwood Station Piping System Installation Specification L-2739 in accordance with Piping Design Table (PDT) 1001BB with the exception of the 30" OD pipe, orifice plates, fasteners, and gasket materials.

The 30" OD pipe, 0.375" wall material specified for this EC will be ASTM A134, Gr. A283C, in lieu of ASTM A155, Gr. KC65 that is specified in PDT 1OOBB. The purpose for this material deviation is due to the discontinuation of the ASTM specification for the ASTM Al 55 material. A listing of the material composition and properties is provided in Table 1 that follows:

Table 1: Comparison of Materials for the 30" OD CW Piping Chemical Properties (max. wt% unless otherwise Mechanical Elongation ASTM; *UNS stated)ý __ "_ Pro-erties ksi) ( .

Standard" S Cu Yield 2

_____ _ _ C -Mn P SS

_Si Cu Tehsile (min) 8 inch inch A155 Gr.

KC65, A672Gr. K02800 0.28 2 0.9 0.035 0.035 0.15-0.4 - 65-85 35 19 23 B65, A515 Gr.

65 1 A134 Gr.

283C, 3 0.2 0.24 0.9 0.035 0.04 0.4 4 55-75 30 22 25 A283 IGr. K02401 C

Table 1 Notes:

1. These ASTM standards are equivalent in accordance with EPRI Report 1014670 "Carbon Steel Handbook"
2. Carbon content varies depending on material thickness: t < 1", C = 0.28, 1"< t < 4", C = 0.31, t > 4", C = 0.33
3. Silicon content varies depending on material thickness: t < 1.5", Si = 0.4, t > 1.5", Si = 0.15-0.4
4. This requirement applies only when copper steel is specified 110 of 238

A comparison of the chemical and mechanical properties of ASTM A134, Gr. A283C and ASTM A155, Gr. KC65 is provided as follows:

  • The ASTM A134, Gr. A283C material consists of similar mechanical properties to that of ASTM A155, Gr. KC65. The tensile strength and the minimum yield strength values of the ASTM A134, Gr.

A283C material are slightly less then ASTM A155, Gr. KC65. However, the high end of the range specified for tensile strength of ASTM Al 34, Gr. A283C, is within the range specified for ASTM A155, Gr. KC65.

  • The elongation percentage of the ASTM A134, Gr. A283C material is slightly greater then the elongation percentage of the ASTM A155, Gr. KC65 material. This mechanical property results in a slightly greater ductility of the ASTM A134, Gr. A283C material and, among other things, will enhance formability of the 30" pipe from the plate material.
  • The carbon content for ASTM A134, Gr. A283C material is less then the carbon content for the ASTM A155, Gr. KC65 material. The carbon content affects the aforementioned mechanical properties of the materials (primarily hardness and strength). In general, the greater the carbon content, the stronger the material.

A minimum wall pipe evaluation was performed at the circulating water system design pressure (110 psig) for ASTM Al 34, Gr. A283C welded plate in accordance with Sargent and Lundy Mechanical Engineering Guideline MES-2.15, Revision 9, and it was determined that 0.375" wall pipe is adequate for this application. This evaluation was already included in EC 375872 and is also included in Tab 8 of this EC package for reference.

Sargent and Lundy Mechanical Engineering Guideline MES-2.15, Revision 9, Table MES-2.15-02, recommends specifying ASTM Al 34, Gr. A283C, for welded pipe material at operating temperatures of 200 OF or less for cold water service such as circulating water systems. As specified in Section 4.1.5 of the DCS, the pipe design temperature for the CW system is 100 OF which is within the temperatures specified in MES-2.15, Revision 9, Table MES-2.15-02.

In conclusion, the use of ASTM A134, Gr. A283C in lieu of ASTM A155, Gr. KC65 piping specified for the 30" OD pipe in this EC is acceptable.

Orifice plates will be installed at the ends of 16" OD lines 0CW1 12AA through 0CW1 12AG. The orifice plate material is specified as ASTM A312 TP304L. Calculation BRW-06-0174-M, Revision 1 (Orifice Sizing for CW blowdown Lines) is issued in support of this EC to provide the basis for the thickness of the new orifice plates installed in this EC. The calculation determines the minimum required thickness of the orifice plates to ensure that deformation of the orifice does not occur. Material properties for the allowable stress of the orifice plate are based on the ASTM material. The orifice plate material listed in the notes on Drawing M-900, Sheet 13C (ASTM A240 Gr. 304L) does not match the orifice plate material listed in Calculation BRW-06-0174-M (ASTM A312, TP 304L). However, as listed in the tables of ASME B31.1 Code, the maximum allowable stress value in tension (16.7 ksi for temperatures not exceeding -20 to 100 OF) for the ASTM A240 Gr. 304L material is greater than the maximum allowable stress value in tension (15.7 ksi for temperatures not exceeding -20 to 100 OF) for the ASTM A312, TP 304L material. As a result, using the lower allowable stress values in Calculation BRW-06-0174-M results in a conservatively larger orifice plate thickness and is therefore acceptable by engineering judgment.

The grade of stainless steel specified for both materials is the same.

The materials used to fasten the nozzle diffuser bolted flanged connections in this EC are stainless steel ASTM A193, Grade B8 Class 1 bolts and ASTM A194, Grade 8 nuts. This fastener material deviates from the requirements of PDT 100BB which specifies the use of ASTM A193, Gr. B7 bolts and ASTM A194, Gr. 2H nuts.

The fasteners will be used to attach the nozzle diffuser flanges to the CW pipe flanges and will be located below the surface of the Kankakee River; therefore, the stainless steel fastener materials have been selected for this application to offer corrosion protection.

Sargent & Lundy Technical Alert TA2003-0016, Issued October 28, 2003, states that if a "soft" gasket material (in lieu of a spiral wound metallic gasket) such as a elastomer material can be specified that can be adequately compressed to seal the joint with the use of a "low" strength stainless steel bolt material, then a low strength class 1 stainless steel bolt material (such as ASTM A193 Grade B8 Class 1) could be specified. As mentioned previously, the nozzle diffuser and gaskets supplied by the vendor for this EC are manufactured of an elastomer (EPDM) material.

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The stainless steel fastener materials have lower tensile and yield stress values when compared to the carbon steel fasteners; therefore, the specified bolt torque for the stainless steel fasteners will be less then carbon steel fasteners. The specified "floor" bolt torque value for 1" diameter, 8 Threads Per inch (T.P.I.) ASTM A193, Grade B8 bolts listed in Procedure MA-MW-736-600, Rev. 3, Attachment 2 is 91 ft-lbs (for soft joints). By comparison the recommended minimum torque values for 1" diameter, 8 T.P.I. bolts listed in the Tideflex Technologies Series 35/35-1 check valve Installation, Operation, and Maintenance Manual is 50 ft-lbs. Since the vendor recommended torque values are lower than the torque values specified in Procedure MA-MW-736-600, for ASTM A193 Grade B8 Class 1 bolting materials, the vendor specified torque values for the stainless steel bolts and nuts installed in this EC are acceptable by comparison.

It has been reported that stainless steel bolts and nuts are very susceptible to galling or 'cold welding' during tightening of the joint (Reference S&L Technical Alert TA2003-0016). To mitigate the concerns with galling of the fasteners during installation, an anti-seize compound will be applied to the surfaces of the bolts and nuts, as required, during installation. A fastener lubricant should be used that is compatible with the fastener material and the operating service conditions (system temperature and external environment). Chlorides, fluorides and sulfides present in a lubricant can cause stress corrosion cracking of the bolts, and should not be present in any such lubricants. Exelon procedure MA-MW-736-600 recommends the use of N5000 lubrication for stainless steel fasteners. In addition, the rotation speed is to be limited when tightening the stainless steel nuts in this EC.

The work planning instructions of this EC provides instructions for the installation of the stainless steel fasteners.

The materials specified for the CW system piping to nozzle diffuser connection consist of dissimilar metals. The flanged connection consists of a carbon steel CW pipe flange attached to a vendor supplied EPDM rubber nozzle diffuser with 316 stainless steel backing rings. As mentioned previously, a stainless steel orifice plate will be installed in between the pipe and nozzle flanges. A vendor supplied EPDM gasket will be installed between the carbon steel flange and orifice plate to provide a mechanical seal between the carbon steel and stainless steel metal surfaces. The flange gaskets are shown on Vendor Drawing TTS-35182 included with this EC package.

There will be no gasket installed between the orifice plate and nozzle diffuser flange. The fastener material that is specified will be stainless steel for the bolts and nuts. The stainless steel fasteners will be in contact with the carbon steel CW pipe flange. This dissimilar metal connection consists of the carbon steel (anode) to the stainless steel (cathode). The carbon steel will preferentially corrode with respect to the stainless steel material.

This accelerated corrosion will not be localized, but rather will be spread out over the area of the carbon steel anode. The area of the carbon steel anode is significantly greater than the area of the stainless steel cathode.

Therefore, the accelerated corrosion due to the galvanic action will be significantly minimized due to the area of the anode in relation to that of the cathode. In addition, the EPDM rubber gasket material will provide some electrical insulation between the stainless steel orifice plate-and the carbon steel flange which should minimize any potential galvanic corrosion between these dissimilar metal components.

For each unit, sodium hypochlorite is injected into the CW pump discharge (condenser supply) piping near the CW pumps in the lake screen house. The 24" CW Blowdown System lines tap off the CW supply piping further downstream, in the Turbine Building, just before the condenser inlet water boxes. The 24" CW blowdown lines from each unit combine into a common 36" blowdown line in the Turbine Building, which transitions to a 48" buried concrete blowdown pipe outdoors.

Sodium bisulfite is injected adjacent to the first vacuum breaker (0CW058) in the CW blowdown line located upstream of the nozzle diffusers to reduce the residual chlorine concentrations that are added upstream of this location. Sodium bisulfite injection is interlocked with the hypochlorite injection. However, once the hypochlorite injection is terminated, bisulfite injection must continue for a period of time to allow scavenging of residual sodium hypochlorite in the CW supply and blowdown lines as it travels from the hypochlorite injection point to the bisulfite injection point. Discussion for the sodium hypochlorite and sodium bisulfite injection into the CW system is provided in EC 351871, S&L Evaluation No. 2004-08051 (Evaluation of Constraints and Limitations For Sodium Bisulfite Injection into the CW Blowdown Line).

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Material suitability of the gasket and nozzle diffuser for this application was primarily derived from the results of a large number of laboratory tests. Companies that design and/or manufacture materials will generally perform a great deal of tests to determine how new materials compare to existing ones in a variety of corrosive environments. These materials are usually submerged in a variety of chemicals at different temperatures.

Performance is ranked according to the level of material degradation. These rankings are compiled in a chart and are usually made available to the public. By looking at the chemical compatibility of the materials listed in the charts, the suitability of many materials can be determined.

The chemical compatibility of EPDM material was obtained from an industry document Emerson Process Management, Rosemount Analytical, "Chemical Resistance Chart" PN 41-6018/rev. B, February 2005 included in Tab 8 of this EC. Based on the information provided in the compatibility chart, the EPDM material possesses suitable corrosion resistance to the chloride (-2 ppm) and sodium bisulfite (-3 ppm) concentrations expected to be present in the circulating water. Several chemical compatibility charts published by EPDM manufacturers and test laboratories indicate that EPDM's performance when exposed to sodium bisulfite is acceptable at 100°F or less. At low chloride concentrations (100 ppm or less) and temperatures (100°F or less), EPDM's performance is also acceptable. For these reasons, it is unlikely that the EPDM gasket material will experience accelerated degradation from the chloride and sodium bisulfite concentrations present in the CW Blowdown System water.

Protective coatings will be applied to the exterior surfaces of the buried carbon steel piping installed in this EC. A review of Braidwood Station Piping System Installation Specification L-2739, Form 276C "Standard Specification for Protective Coatings for Buried Piping" was conducted and it was determined that the coal tar pipe coating specified on Form 276C is not appropriate for this application due to the discontinuation of the use of this coating in the industry. Therefore, alternative protective coatings will be specified in this EC for the buried carbon steel piping.

The exterior surfaces of the carbon steel pipe installed in this EC will be shop coated in accordance with AWWA C213, Fusion-Bonded Epoxy Coating for the Interior and Exterior of Steel Water Pipelines. A fusion-bonded epoxy coating is recommended for un-insulated underwater, underground or embedded piping applications at temperatures less than or equal to 200 OF in accordance with Sargent & Lundy Mechanical Department Standard MES-21.4, Coatings and Linings. In addition, a fusion-bonded epoxy coating was previously specified for buried large bore piping installed in EC 372909 at Braidwood Station.

Sections of the new CW blowdown carbon steel pipe that could not be shop coated (e.g., circumferential weld locations) will be field coated in accordance with AWWA C210, Liquid-Epoxy Coating Systems for the Interior and Exterior of Steel Water Pipelines, due to the installation challenges associated with field installation of the fusion-bonded epoxy coating. This liquid epoxy coating is listed as an acceptable alternative coating as specified in AWWA C213, Paragraph 4.4.5.3.

The materials that are specified for a drain line which is attached to a blind flange that is temporarily installed to the end of the 16" OD branch line OCW1 12AG for pressure testing are consistent with the material requirements of PDT 100BB.

The blind flange material that is specified for the closure of the CW pipe at seven locations for pressure testing, ASTM A105, is consistent with the material requirements of PDT 100BB. The fastener materials that are specified for pressure testing are carbon steel ASTM A193, Gr. B7 bolts and ASTM A194 Grade 2H nuts. After pressure testing is complete, the fasteners will be discarded. The gaskets that are specified for pressure testing are Flexatallic Type 'CGI' for a full face flange which is consistent with the requirements of specification L-2739.

These gaskets will be used to provide a mechanical seal between the slip-on flange and the blind flange located at the end of 16" OD CW lines OCW 112AA through OCW 112AG during pressure testing and will be discarded after pressure testing is complete.

This EC will heat trace valves OCW152A/B along with a portion of 18" OD lines OCWC2CA/B located in the outfall structure upstream of globe valves OCW152A/B to prevent the water in the piping from freezing.

Insulation is required to be installed on the portion of the CW piping that is heat traced. The insulation that is specified for the CW piping is pre-formed 1V/2" thick insulation in accordance with ASTM C547 in accordance with the requirements of specification L-2828, Thermal Insulation.

The materials required for this EC have been specified on the Engineering Change Material List (ECML) included with this EC.

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4.1.14 Environmental Conditions and Impacts Form EN-AA-103, Attachments 1 and 2 were reviewed and it was determined that there are potential environmental impacts. Therefore, EN-AA-103, Attachment 1 and 2, and an Interfacing Department Review sheet (Form CC-AA-102, Attachment 10F) were forwarded to the station's chemistry department for input and approval. An environmental evaluation has been completed by the station's chemistry department in accordance with EN-AA-103-1001 and there were no negative impacts associated with the implementation of this EC. The environmental review checklist and environmental evaluation is included in Tab 8 of this EC package. A summary of the environmental evaluation is provided below:

EC 375873 will not result in chemical change in the characteristics of discharges, effluents, emissions or withdrawals. The proposed activity will result in a physical change in the characteristics of liquid effluents discharged to the Kankakee River; however, the proposed change increases the mixing zone and dilution characteristics of the river.

EC 375873 will alter the NPDES permit and process diagram. Application for Construction/Operation Permit (WPC-PS-1) has been submitted to the Illinois EPA which included a revision to the NPDES permit.

EC 375873 will be consistent with the site Operating License Appendix B. There will be no impact to the environment or an unanalyzed test or experiment associated with the installation of this system.

EC 375873, installed in accordance with Braidwood Station applicable procedures, Will not add or change the environmental impact, violate existing permits, or pose a change to the Final Environmental Statement.

4.1.16 Operating Experience Review The INPO site was searched for keywords to determine if relevant operating experiences were applicable to this modification. The following is a listing of results after searching the SER/SEORs and EPIX/NPRDS databases:

INPO Searched for: "Large Bore Globe Valve" Search Results: None INPO Searched for: "Circulating Water and Blowdown" Search Results:

OE 22903 - Leak at Circulating Water System Blowdown Line Vacuum Breaker - Braidwood Units 1 and 2

Background:

This OE describes a failure of a CW blowdown vacuum breaker due to low-stress, high-cycle fatigue, primarily caused by the lack of protection against pressure surges caused by the system operating methodology. The vacuum breaker failure resulted in significant amounts of water being discharged through the failed vacuum breaker over several days- The leak was not discovered until after a local resident reported water in a ditch adjacent to his property.

Summary:

This OE is particularly relevant to the river diffuser project because the vacuum breaker failure occurred upstream of the CW river diffuser branch line that is installed in EC 375871, EC 375872, and this EC. The river diffuser project will not make modifications or change the operation of the CW blowdown vacuum breakers. A major revision was issued against Calculations BRW-02-0152-M and BRW-06-0073-M for EC 375871 in order to provide a steady state and transient hydraulic model respectively of the new CW blowdown discharge flowpath.

The new CW flowpath will direct CW flow through nozzle diffusers which are installed in this EC. EC 375871 installed new 18" globe valves (EPNs: OCW26OA/B) which will be used to throttle the flow through the nozzle diffusers and to maintain adequate backpressure on to ensure the vacuum breakers remain properly seated.

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INPO Searched for: "Buried Pipinq and Freeze" Search Results:

OE 16497 - Aborted Discharge/Release of Processed Radioactive Effluent Because of a Frozen Line at Davis Besse.

Background:

While attempting a discharge/release of processed radioactive effluent during the winter from the Miscellaneous Waste Monitor Tank (MWMT) to the Collection Box outside of the protected area, no flow was observed on the associated flow meter. Further investigation found ice blockage in the line at the discharge point in the Collection Box.

No unmonitored release occurred. However, the potential existed for an unplanned and/or undiluted release of low level radioactive waste water to the environment if the pipe should freeze and burst at a point outside of the Collection Box. The piping was installed approximately 18" deep at the point of entrance to the Collection Box.

Summary:

This OE highlights the need to ensure buried piping and piping located outdoors is not exposed to freezing temperatures. This is particularly a concern when there is stagnant water in the piping which is exposed to freezing temperatures.

After implementation of EC 375873, blowdown flow will be directed through the new CW Blowdown System nozzle diffusers and will discharge directly into the Kankakee River. The old CW Blowdown System flow path, which directed CW blowdown flow through 18" OD lines OCWC2CA and OCWC2CB and discharged CW onto a concrete spillway located outside of the outfall structure, will be isolated by closing globe valves 0CW 152A/B. A portion of the isolated CW piping is located in the outfall structure and may be exposed to freezing temperatures during the winter months. To prevent freezing of the water within the CW piping, valves 0CW 152A/B as well as a portion of 18" OD lines OCWC2CA/B located within the outfall structure upstream of globe valves OCW 152A/B will be heat traced in this EC.

INPO Searched for: "Buried Piping and Corrosion" Search Results:

OE23565 - Unexpected fill conditions were found during an excavation of Buried Nuclear Service Water Piping -

Catawba Nuclear

Background:

Unexpected fill conditions were found during an excavation of buried nuclear service water piping. The piping was found enveloped in washed crushed stone instead of the expected earth fill at the location of excavation.

The excavation was performed to assess the extent of conditions of coating damage and externally initiated corrosion damage. Since the existing pipe conditions were excellent, the backfill plan was changed to use washed crushed stone based on the recommendations of subject matter experts.

Summary:

As stated in the work planning instructions of this EC, the pipe backfill material shall be a granular material with a maximum particle size of 0.75 inches [such as IDOT #67 aggregate (ASTM D448) or a finer gradation aggregate] as recommended in specification AWWA C210, Section 4.8.3 and specification AWWA C213, Section 4.6.3 respectively for coated buried piping. Alternatively, controlled low strength material (bash concrete) may be used in lieu of granular material for the bedding installation. No deviation of the backfill requirements is allowed without prior approval and concurrence of design engineering.

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4.1.19 System Operational Requirements This EC will change the operational requirements of the CW Blowdown System at Braidwood Station. After implementation of this EC, flow will be directed through the nozzle diffusers for discharge into the Kankakee River. The previous flow path for CW Blowdown System flow through 18" OD lines OCWC2CA/B located at the outfall structure concrete spillway will remain in place as a viable alternate flow path. Procedure BwOP CW-12, Circulating Water Blowdown system Fill, Startup, Operation, and Shutdown will be updated as a result of the new flow path for discharge of the CW Blowdown System.

4.1.21 Procedure Changes The CW Blowdown System mechanical line-up procedure, BwOp CW-M2, will be updated in this EC to list the position of the 18" globe valves (EPNs: OCW26OA/B) installed in the instrument pit extension as open. In addition, the 18" globe valves (EPNs: OCW152A/B) installed in the outfall structure will be listed as closed. The valves are shown on Drawings M-44, Sheet 13A and M-44, Sheet 13C and are included with this EC package.

This EC will install a new flow path for CW Blowdown System discharge to the Kankakee River. Therefore, Procedure BwOP CW-12, Circulating Water Blowdown System Fill, Startup, Operation, and Shutdown will require update in support of this EC.

Procedure OBWOS XFT-A5 will be updated to add a surveillance of the heat tracing that will be installed on the existing CW blowdown system 18" OD piping (lines: OCWC2CA/B) and globe valves 0CW 152A/B located in the outfall structure.

Minor updates will be required to the following procedures as a result of this EC:

  • BwOP TR-2
  • BwOP WX-501T2
  • BwOP WX-526T2
  • BwOP CW-1
  • BwOP CW-2
  • BwOP CW-13
  • BwOP CW-14 The aforementioned procedures have been listed on Attachment 9 of CC-AA-102, Attachment 9 and this form is included with this EC package. These procedures are also listed on the ADL of this EC package.

4.1.22 Training Requirements The procedure/training impact review form CC-AA-102, Attachment 9, has been included in this EC for the station to identify any potentially impacted training.

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4.1.24 Layout and Arrangement Requirements The routing of the CW piping that is provided with this EC has been developed in conjunction with input received from Exelon and their installation contractor. The contractor, 'D' Construction, provided a conceptual layout of the CW piping which would best accommodate their proposed location of a cofferdam in the Kankakee River.

The cofferdam will be required for the installation of piping as well as the diffuser nozzle ports which will discharge onto a concrete spillway located in the river bed as part of this EC.

Installation activities associated with the placement, welding, and coating of the buried CW piping installed in this EC will take place in an excavated trench. Adequate space will be required to inspect the pipe welds and apply the protective coating at the weld joints.

The 2" branch lines (0CW 111A/B) that were installed in EC 375872 will be utilized for pressure testing of the new CW piping installed in this EC. The 2" lines are located in the instrument pit extension downstream of globe valves OCW260A and 0CW260B. EC 375871 provided sections of removable grating installed at El. 555'-4" to allow for periodic valve maintenance. The grating section(s) can be removed, as required, in order to route test equipment (e.g., hoses) to the fill line for pressure testing of the CW pipe.

The CW piping installed in this EC will be hydrostatically pressure tested in accordance with the requirements of ASME B31.1. A threaded connection with threaded pipe cap is provided at the end of the fill and vent lines to allow for the attachment of test equipment and proper venting of the pipe respectively. The approximate volume of fluid required for hydrostatic pressure testing is 21,350 gallons and was determined in the work planning instructions of this EC. Blind flanges are installed at the end of the CW pipe to allow for hydrostatic pressure testing. A 2" line is attached to the blind flange at the end of 16" OD line 0CW1 12AG to allow for draining of the CW piping after pressure testing is complete. Globe valves OCW260A and OCW260B will remain closed during pressure testing.

After pressure testing of the CW piping is complete, the water within the CW piping that was used for testing will be drained, collected, and disposed of.

An orifice plate and nozzle diffuser will be installed at the end of 16" OD CW lines 0CW1 12AA through OCW1 12AG. The orientation and size of the orifice plates and nozzle diffusers is provided on Drawing M-900, Sheet 13C and Vendor Drawing TTS-35180 respectively included with this EC package. A gasket will be installed between the orifice plate and a slip-on flange connection at seven locations in order to provide a mechanical seal between the metal surfaces. According to the Tideflex Technologies Series 35/35-1 check valve Installation, Operation, and Maintenance Manual included in Tab 3 of this EC package, no gasket is required to be installed between the orifice plate and the nozzle diffuser flange.

As mentioned in Section 4.1.21, the valve positions associated with OCW26OA/B and OCW152A/B will be changed to direct CW blowdown flow through the new nozzle diffusers. The position of valves OCW26OA/B can be changed by manually adjusting the valve handwheel extension located above floor elevation 555'-4" within the enclosure over the modified instrument pit. The position of valves 0CW152A/B can be changed by manually adjusting the valve handwheel located above floor elevation 543'-6" in the existing outfall structure. Existing operating procedures will be revised in support of this EC to provide the steps required for manually adjusting the 18" globe valves located within the instrument pit and outfall structure. Additional adjustments of the globe valves hand wheels for OCW26OA/B may be required during startup of the CW Blowdown System to ensure adequate backpressure upstream of the valves to keep the vacuum breakers seated during normal operation.

4.1.26 Walkdowns An Installer's Walkdown is required to validate the design details presented in this EC. As a result of the walkdown, any changes to the EC drawings or documents will be processed as a planned revision to the EC. 117 of 238

4.1.28 Requirements for Handling, Storage, Cleaning, and ShiDping Protective coatings will be applied to the buried and submerged CW system piping and fittings installed in this EC. The protective coatings act as a barrier to prevent corrosion of the external surfaces of the buried carbon steel piping. If the coating is damaged, that portion of the pipe could be more susceptible to corrosion. The protective coatings will be applied to the piping surfaces both in the shop and in the field. Care shall be taken while handling, transporting, and installing the coated piping to ensure the protective coating is not damaged. In the case that the coating is damaged during installation, see AWWA C210 and AWWA C213 for direction on repair as directed in the WPI.

In addition, the backfilling operation should be carefully controlled to prevent damage to the exterior pipe coating applied to the CW piping. Special precautions during the backfilling operation are provided in the work planning instructions of this EC.

The Tideflex Technologies Series 35/35-1 check valve Installation, Operation, and Maintenance Manual includes considerations for storage of the nozzle diffusers and is included in Tab 3 of this EC package.

4.1.30 Industrial Safety Requirements The existing and modified instrument pit structure is a confined space. Appropriate safety precautions for confined space entry must be followed during installation of the EC and considered in procedures that require entry into the confined space. In addition, the work area in the instrument pit around the piping and valves is restricted. However, there is adequate lighting and access to the fill and vent valves during pressure testing conducted in this EC.

Steel grating may be removed in the instrument pit extension at elevation 555'-4" to allow for the routing of test equipment (e.g., hoses, valves, pumps, etc.) associated with the hydrostatic pressure testing of the CW piping installed in his EC. The removal of grating may pose a fall hazard for workers. Compensatory measures may be required to ensure the safety of workers in and around the removed portions of grating.

A portion of the installation work implemented in this EC will take place in cofferdam located in the Kankakee River. The installation contractor is responsible for the preparation and implementation of safety procedures for the cofferdam work.

4.1.33 Mechanical System Requirements The CW system piping installed in this EC is designed to Piping Design Table (PDT) 100BB and has a design pressure of 110 psig and a design temperature of 100°F which is consistent with the existing CW system requirements.

The required bolt torque values for fastening the blind flanges to the end of the CW piping for pressure testing are different then the bolt torque values for attachment of the nozzle diffusers to the end of the CW piping after pressure testing is complete. The bolt torque required for fastening the blind flanges for pressure testing has been specified in the work planning instructions for this EC and is in accordance with Exelon procedure MA-MW-736-600 Attachment 2 for 1"-8 T.P.I. stainless steel bolts. The required bolt torque values for attachment of the nozzle diffusers to the end of the CW piping is in accordance with the values provided in the installation, operation, and maintenance manual submitted by the vendor Tideflex Technologies. In accordance with Exelon procedure MA-MW-736-600 Section 3.2.5, the bolt torque values specified by a vendor shall take precedence over the torque values provided in the Exelon procedure. Therefore, the recommended torque values provided by Tideflex Technologies will be utilized for attachment of the nozzle diffusers to the end of the CW blowdown piping. These torque values have been specified in the work planning instructions of this EC. 118 of 238

As listed on Vendor Drawing TTS-35180 included with this EC, the nozzle diffusers are sized for a maximum back pressure of 27.5 feet. According to the nozzle diffuser vendor, a backpressure in excess of the rated pressure can invert the sleeve and cause nozzle diffuser failure. The maximum backpressure is based on the difference of the Kankakee River 100 year floor elevation (553-0") and the pipe centerline elevation (525'-6").

The pipe centerline elevation at the concrete spillway location is provided on Drawing M-900, Sheet 13C included with this EC package. The 100 year flood elevation obtained from drawing M-900 Sheet 5 is 550-6". However, an updated 100 year flood elevation was obtained from the Flood Insurance Rate Map (FIRM) map number 17197C0560 E for Will County, Illinois effective September 6, 1995, provided by the Federal Emergency Management Agency. Therefore, the elevation obtained from the FIRM map (553'-0") is used as a conservative value to determine the maximum backpressure.

In accordance with Procedure NSWP-M-05 (Pressure Testing) and the requirements in ASME B31.1 Code, the hydrostatic test pressure is 1.5 times the system design pressure (110 psig) which equals 165 psig. However, given the elevation difference from the pipe centerline at the high point (elevation 546'-0", From Drawing M-900, Sht. 13A) and the low point (elevation 525'-6", From Drawing M-900, Sheet 13C) the pressure at the low point in the CW Blowdown System piping is calculated as follows:

Hydrostatic Test Pressure: 165 psig Elevation difference: 546.0 ft - 525.5 ft = 20.5 ft Conversion from ft water to psi: 0.433 ft water/psi (From Crane Technical Paper 410, Flow of Fluids Through Valves, Fittings, and Pipe, Page B-11) 20.5 ft x 0.433 ft water/psi = 8.9 psig Corrected hydrostatic Test Pressure: 165 + 8.9 = 174 psig A half coupling will be welded to a blind flange which is temporary installed at the end of 16" OD line OCW1 12AG for pressure testing. A drain line is installed to this half coupling to allow for draining of the CW piping after pressure testing is complete. The fillet weld for the attachment of the half coupling to the blind flange is specified as 5/16" and is conservatively designed to withstand an applied pressure of 200 psig which is greater than the hydrostatic test pressure at this location (approximately 174 psig). In addition, the pressure rating of a 16" blind flange shown on Sketch SK-M-375873 used for pressure testing (150# Class, ASTM A105) of the CW Blowdown System pipe for temperatures -20 to 100 OF is 285 psig (Reference ASME B16.5-2009).

This EC will temporarily bolt blind flanges to the end of the CW piping at seven locations to provide pipe closure for pressure testing of the CW piping installed in this EC. After pressure testing is complete, the blind flanges will be removed and the nozzle diffusers will be bolted to the end of the CW system piping. The nozzle diffuser flange connections cannot be checked for leakage since the diffusers are open at one end and will be submerged beneath the Kankakee River during normal operation of the CW blowdown system. If leakage were to occur at the flanged nozzle diffuser connections installed at the end of lines OCW1 12AA through OCW1 12AG, the water would discharge into the Kankakee River just upstream of the intended discharge path through the nozzle diffusers.

Revisions to Calculations BRW-02-0152-M (Circulating Water Blowdown Hydraulic Analysis) and BRW-06-0073-M (Hydraulic Transient Analysis of the Circulating Water Blowdown Piping) were provided in EC 375871 in order to model the alternate CW Blowdown System flow path through the nozzle diffusers. Calculation BRW-02-0152-M specified that restriction orifice plates are required to be installed at the discharge of the CW Blowdown System piping into the Kankakee River in order to balance the flow passing through each nozzle diffuser to within 10% of each other and to help maintain a pressure above vapor pressure at the discharge of the 18" globe valves (EPNs: OCW26OA/B). The orifice diameters will vary based on the diffuser location and generally decrease in diameter towards the end of the concrete spillway. The orifice diameters are listed in a table on Drawing M-900, Sheet 13C included with this EC package.

Calculation BRW-06-0174-M, Revision 1 (Orifice Sizing for CW Blowdown Lines) is issued in support of this EC to calculate the minimum required orifice plate thickness to ensure deformation of the orifice does not occur.

The orifice plate thickness is shown on Drawing M-900, Sheet 13C included with this EC package.

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As mentioned in Section 4.1.21 and 4.1.24, the positions of globe valves 0CW260A/B and 0CW 152A/B will be changed in order to direct CW blowdown flow through the new nozzle diffusers installed in this EC. Existing operational and mechanical line-up procedures will require update based on the aforementioned changes to the globe valve positions as well as the changes to the operation of the CW blowdown system. The mechanical procedures that require update have been identified in Section 4.1.21 of the DCS.

A stagnant section of piping could exist in lines 0CWC2A-30", 0CWC2BA/B-24", and 0CWC2CA/B-18" located downstream of the 30" lateral fitting and upstream of globe valves 0CW 152A/B between the instrument pit and outfall structures.

For the scenario mentioned above, the potential for accelerated corrosion exists due to the stagnant water conditions in the CW Blowdown System piping caused by Microbiologically Induced Corrosion (MIC). Generally, there are higher risks for MIC when untreated natural waters (i.e., pond, lake, river water) are in contact with steel components. Action Request (AR #: 01098301) has been assigned to track actions to mitigate corrosion in portions of OCWC2A-30" and OCWC2A/B-18" downstream of the 30" lateral fitting inside of the instrument pit.

A portion of lines OCWC2CA-18" and OCWC2CB-18" located within the outfall structure upstream of globe valves OCW152A/B will be heat traced along with valves OCW152A/B to prevent the water in the CW piping from freezing. Insulation is required to be installed on the portion of the CW piping that is heat traced. The insulation requirements have been specified in Section 4.1.13 of the DCS. The basis for the selection of the heat trace cables is discussed in Section 4.1.35 of the DCS.

4.1.35 Electrical Requirements This EC provides the design for the installation of the Electrical Heat Tracing System for the exposed (inside the outfall structure) portions (OCWC2CA & OCWC2CB) of the 18" diameter pipes, which ties in to the existing Circulating Water (CW) blow-down header (line OCWC2A-30") in the blow down instrument pit located upstream of the Outfall Structure. Portions of the 18" exposed piping inside the outfall structure separated by globe valves will not be heat traced. Water will be present on these portions (following the globe valves) of the pipe only during continuous flow. Therefore these portions of the piping will not require heat tracing.

Two sections (CWC2A-18" & OCWC2B-18") of the pipe (prior to globe valves) inside the outfall structure will require heat tracing to prevent them from freezing since these sections of pipe may contain stagnant water. 120 VAC power for the heat tracing will be provided from Regular Lighting Cabinet (RLC) # 130C (which is added by EC 375871), Circuits #9 & #11. Heat tracing for pipe section OCWC2A-18" will be powered form RLC #130C, Circuit #9 and heat tracing section OCWC2B-1 8" will be powered form RLC #1 30C, Circuit #11.

A new power connection box with LED indication and a new thermostat will be installed in each section of the pipe to be heat traced. The heat trace, power connection box, and thermostat will be connected as indicated on drawing 20E-0-4030HT12 120 of 238

Design Condition & Pipe Heat Loss - Water Piping Location Above Ground (Inside outfall structure)

Maintain Temperature (TM) 40°F Maximum Temperature (TMax) 103 0F Min. Ambient Temp (TA) - 10°F Pipe Diameter & Material 18" - Carbon Steel Length of Pipe to be Heat Traced approximately 8' Thermal Insulation & Thickness 1.5 inch (ASTM C547)

Supply Voltage 120V Temperature differential:

AT = TM - TA

= 40'F - (- 10°F)

AT = 50°F Pipe Heat Loss:

From Table 1, for 18" diameter pipe with 1.5 inch insulation and AT = 50 0 F, the pipe heat loss (QB) will be obtained from Table 1 (pipe Heat Loss (watts per foot))

QB = 12.9 W/ft @ TM = 40'F Insulation Type:

Multiplying the base heat loss of the pipe (QB) from above by the insulation compensation factor (f) from the bottom of Table 1 to get the actual heat loss per foot of pipe (QT).

QT =QBxf

= 12.9 x 1

= 12.9 watts/ft @ 40°F Heating Cable:

From Tyco Table 4a - (Thermal Output Ratings for QTVR Heating Cables on insulated Metal Pipes) 15QTVR1-CT cable is selected for heat tracing. From the Table 4a, it is clear that the 15QTVR1-CT provides more than 15 watts/ft. Therefore, single layer of tracing of this cable type is adequate for this service.

Length of the heating cable required for each section of the piping:

Piping: 8 ft of pipe = 8 ft There is one globe valve. From Tyco Table for amount of heating cable required for each valve for a 18" diameter pipe is 9.4 ft of heating cable.

For one valve 18" = 9.4 ft There is one support shoe on each section of the pipe to be heat traced. Additional heat is required for each support shoe.

Heat Required QSUPPORT = 0.7L x (TM - TA), where L = support length (ft) - considering 1' This formula is based on a 0.25" steel welded shoe partially shielded from winds.

Heat loss from supports: 1 x (1 x 0.7 x 50) = 35 watts x 10% safety factor = 40 watts Heating cable power output is 15W/ft.

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Additional heating cable required for support:

40/15 = 2.7 ft or approximately 3' Total heating cable = 8 + 9.4 +3 = 20.4 feet Total power require = (20.4 feet x 15) = 306 watts Therefore, continuous current will be less than 3 amps at 120V.

Circuit Breaker Selection:

Total heating cable circuit length is 20.4 feet. From Table 7, the maximum heating cable length allowed for 15QTVR powered at 120 volts with a -0°F startup temperature on a 15A circuit breaker is 60 feet and on a 20A breaker, 80 feet. Selecting a 15A circuit breaker as the total length will be less than 21'. This is lowest size breaker shown on Tyco Table 7.

Ground-fault protection:

If the heating cable is improperly installed or physically damaged to the point that water contacts the bus wires, sustained arcing or fire could result. If arcing does occur, the fault current may be too low to trip conventional circuit breaker. A 15A Ground Fault Interrupting (GFI) type circuit breaker is selected for these services.

Feed Cable:

A #10 AWG feed cable is selected for each section of the heat tracing for the circulating water pipes tie-in sections. NEC Table 310.16 shows that in raceway at 900C the current carrying capacity of 3/C, 10 AWG cable is 40A at an ambient temperature of 300C. NEC Table also shows a temperature correction factor of 0.82 for an ambient temperature of 400C. Therefore, the current carrying capacity at an ambient temperature of 400C for a 3/C, #10 AWG cable is (40 x 0.82) 32.8A.

Since the current carrying capacity of 3/C, #10 AWG is higher feed breaker trip rating (15A) therefore, the feed breaker will protect the cable.

4.1.38 Civil/Structural Requirements A geotechnical investigation was performed by Patrick Engineering, Inc. in October 2008 to evaluate the subsoil conditions along the approximate location of the CW branch blowdown pipe and the diffuser header in the river.

Three (3) land borings and four (4) river borings were drilled. A final report documenting the results of the geotechnical investigation was subsequently issued by Patrick in December of 2008. In the land borings, the depth to the bedrock varied from about 7.2 feet to 16 feet. The subsoil consisted of sandy silt fill, sand/gravel fill, silty sand, gravel, and organic silt. The Standard Penetration Test (SPT) blow counts (N) varied from 5 to >50 blows/ft. The groundwater table was encountered four (4) to six (6) feet below grade. The bedrock is a moderately weathered shale with the Rock Quality Designation (RQD) values varying from 35 percent to 73 percent. In three of the river borings, brown sandy gravel was encountered above the shale bedrock in thickness that varied from 1.3 feet to 3.6 feet. In one boring, shale bedrock was encountered at the river bottom with no gravel overlying the rock. RQD of the rock cores obtained in the river varied from 16 to 86 percent. The unconfined compressive strength of the core samples varied from 240 to 2775 psi. Based on the buried pipe profiles shown on Drawing M-900, Sheet 13C, the minimum ground cover to the top of the CW piping will be 3'-

3" which is adequate to prevent freezing of any stagnant water in the CW blowdown piping.

Based on a survey drawing prepared by Atwell-Hicks, the existing land elevation between the Outfall Structure and the top of the east river bank is relatively constant (varying between 544 feet to 541 feet). At the time of the survey, the water elevation in the Kankakee River was approximately 536 feet. The river bottom elevation was also obtained at several locations across the river. The lowest river bottom elevation at approximately 527 feet.

The reinforced concrete spillway which encases the end of the CW blowdown line in the river bed and provides a ramp opposite the river nozzle diffusers to direct the blowdown discharge into the Kankakee River flow is detailed on Drawing S-308, Sheet 3 included with this EC package. The qualification of the spillway structure is provided in Calculation 2.4.1-BRW-09-0073-S, Revision 0 issued in support of this EC package. Minor revision OA is issued in support of this EC package and concludes that the concrete spillway structure is adequate based on the diffuser spacing changing from 11' to 7' apart.

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4.1.40 Personnel Requirements and Limitations For personnel requirements and limitations, see section 4 of the Work Package Instructions titled, "Special Installation Sequencing and Considerations."

4.1.42 Interfacing Department Review Interfacing department impacts are addressed in the applicable CC-AA-102, Attachment 10 forms included with this EC.

4.1.45 Sinqle Point Vulnerability (SPV) Review In accordance with CC-AA-102, the following questions were addressed:

Does the configuration change add any unnecessary challenges associated with the operation of the system?

No. This EC provides the Phase 3 scope of work for the completion of the CW blowdown river diffuser project.

CW blowdown flow will be directed through the nozzle diffusers which discharge directly into the Kankakee River.

Orifice plates of varying diameters will be installed between the CW pipe to nozzle diffuser flange connections.

The orifice plates are installed based on the results of the hydraulic analysis of the new CW blowdown river diffuser pipe routing for the purpose of balancing the flow to within 10% of each other and to help maintain a pressure above vapor pressure at the discharge of the 18" globe valves (EPNs: OCW26OA/B).

A protective coating will be applied to the CW piping installed in this EC in order to mitigate corrosion on the external surface of the CW piping. Stainless steel fasteners and orifice plates are specified in this EC to offer corrosion protection of the submerged components. Dissimilar metal corrosion may occur due to the connection of the stainless steel fasteners to the carbon steel CW flanges. However, this corrosion would not be localized, but rather will be spread out over the area of the carbon steel (anode). The area of the carbon steel (anode) is significantly greater then the area of the stainless steel (cathode). Therefore, the accelerated corrosion due to the galvanic action will be significantly minimized due to the area of the anode in relation to that of the cathode.

The gasket material specified in this EC will electrically insulate the stainless steel orifice to carbon steel CW flange connection and will prevent stray currents which could cause galvanic corrosion of the carbon steel flange and potentially lead to the galvanic corrosion of the metal.

According to the nozzle diffuser vendor, a backpressure in excess of the rated pressure can invert the nozzle sleeve and cause nozzle diffuser failure. The nozzle diffusers have been sized for a maximum backpressure of 27.5 feet which is based on the difference in the 100 year flood elevation (553-0") and the pipe centerline (525'-

6"). The 100 year flood elevation was obtained from an Flood Insurance Rate Map (FIRM) map number 17197C0560 E for Will County, Illinois effective September 6, 1995 provided by the Federal Emergency Management Agency in lieu of the elevations shown on M-900, Sheet 5 which will result in a conservatively larger elevation difference. The pipe centerline at the concrete spillway location is provided on Drawing M-900, Sheet 13C included with this EC package.

A portion of 18" OD lines OCWC2CA/B upstream of valves 0CW 152A/B located in the outfall structure will be heat traced along with valves OCW 152A/B to prevent water in the CW system piping from freezing.

Does the configuration change modify existing or reguire the development of new operating procedures, maintenance or system testing activities such that these procedures or activities could result in an unnecessary risk of losing the system function?

No. Existing procedures will require revision based on changes to the CW system manual valve line-ups as well as the changes to the operation of the CW blowdown system. The procedures will be modified to allow for CW blowdown flow to be directed through seven CW nozzle diffusers installed in this EC. The 18" globe valves OCW26OA/B installed in EC 375871 will be throttled to ensure there is adequate backpressure to keep the vacuum breakers seated during normal operation.

Could the configuration change lead to a plant SCRAM or Derate?

No. See disposition for the previous two questions.

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Do any proposed Instrument & Control (l&C) setting changes or dynamic compensation changes introduce a single point of vulnerability?

No, there are no I&C setting changes in this EC.

Can the fault tolerance of the system be adversely affected by any I&C setting changes so as to introduce a new single point of vulnerability?

No, disposition is the same as the previous question.

Would other I&C related changes that would cause an effective gain change to a control system adversely affect the fault tolerance so as to introduce a new single point of vulnerability?

No, disposition is the same as the previous two questions.

==

Conclusion:==

A single point vulnerability (SPV) review has been performed for the configuration change. The purpose for the review was to identify all events that can result in unplanned reactor SCRAMs in a proactive manner, with the intent of taking action to prevent such events. No relevant events were identified.

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10CFR50.59 Screening for EC 375873 50.59 Screening Questions (Check correct response and provide separate written response providing the basis for the answer to each question) (See Section 5 of the Resource Manual (RM) for additional guidance):

1. Does the proposed Activity involve a change to an SSC that adversely affects an UFSAR described design function? (See Section 5.2.2.1 of the RM)

El Yes 0 No The Braidwood Station is proposing to implement an activity to install an alternate Circulating Water System (CW) blowdown flow path that will direct the blowdown flow to a new multi-port diffuser for discharging CW directly into the Kankakee River. New piping will tie-in to the existing CW blowdown header (line OCWC2A-30") in the instrument pit located upstream of the outfall structure and will be routed underground to the Kankakee River. A multi-port diffuser will be installed in a concrete spillway in the river bed at the end of the new bypass line to discharge CW below the water surface directly into the river flow. The diffuser will consist of seven discharge points, each equipped with a flow balancing orifice, that will improve the mixing of liquid releases into the Kankakee River, eliminate background noise levels and organic foam, and enable an improved alternative release strategy. Studies have concluded that use of the aforementioned multi-port diffuser will significantly improve discharge dilution over the existing configuration which consists of two 18" discharge lines feeding a flume that discharges above the surface of the Kankakee River. The discharge configuration described above will be implemented as a preferred alternative to the existing discharge configuration as the primary method of CW blowdown. This activity will be segregated into three (3) separate Engineering Changes (EC), as indicated below, to allow for a phased installation approach. Phase 1 and Phase 2 when considered as stand-alone activities screened-in as commercial change activities that had operational boundaries that ensured that the proposed activities could not adversely impact a system, structure, or component as described in the UFSAR. The Phase 3 activities cannot be screened-in as a commercial change and requires evaluation per the 50.59 process. Phase 3, in-conjunction with the completed Phase 1 and Phase 2 activities will combine to implement modifications and additions to procedures that affect how the UFSAR described CW blowdown function is controlled. Therefore, all three phases of the proposed EC activities will be addressed by this 50.59 screening.

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Phase 1 Activities: EC 375871 will provide the first phase of the work consisting of a tie-in to the existing CW system blowdown OCWC2A-30" using a 30" x 30" lateral fitting, installation of two parallel 18" CW system lines (OCWE2BA-18" and 0CWE2BB-18") with 18" globe valves (0CW260A and 0CW260B) installed in each line, demolition of a portion of the south wall of the existing instrument pit and extending the east and west pit walls to accommodate the described new piping and valves. A new pre-fabricated metal building will be added to enclose the extended instrument pit. This EC will also install pressure gauges upstream of the new 18" globe valves, will relocate an existing blowdown sample probe (and associated equipment), and will provide a new sample tie-in, composite sampler and provisions for taking grab samples. Power will be supplied to the new instrument pit building for lighting, receptacles, composite sampler power feed, heat tracing for sample lines, and future tie-in for heat tracing existing piping lines 0CWC2CA-18" and OCWC2CB-18" (See Phase 3, EC 375873 activities). The non-safety related power feed will be supplied from existing lighting cabinet 1LL30JA located in the River Screen House via two spare cables (1CW582 and 1CW583) through a new 5kVA 120/24OVac single phase transformer and new power distribution panel located in the outfall structure pit.

Phase 2 Activities: EC 375872 will provide the second phase of the installation work that consists of routing the CW blowdown piping from the piping termination points in the first phase of installation work, located just outside of the instrument pit extension, to a location near the Kankakee River bank. Fill and vent lines will be added to both 18" branch lines to allow for pressure testing. The two 18" branch lines (0CWE2BA-1 8" and 0CWE2BB-18") installed in Phase 1 EC (375871) will converge back to a single 30" line outside of the instrument pit extension and will be routed underground approximately 380 feet to a location near the Kankakee River bank. The two 18" globe valves installed in Phase 2 will remain closed following pressure testing. The pipe will terminate near the river bank pending the third phase of installation work which will be provided in EC 375873.

Phase 3 Activities: EC 375873 will provide the third and final phase of the installation. This EC will continue the routing of the 30" line, installed in Phase 2, into a branch header provided with seven 16" diameter branch lines each equipped with a restriction orifice and diffuser nozzle which will discharge below the surface of the Kankakee River. A concrete spillway will be installed beneath the new diffuser nozzles and supply piping in order to prevent potential erosion of the river bottom. The 18" globe valves, 0CW260A and OCW260B, installed in Phase 1 will be opened to direct CW blowdown through the newly added diffuser piping branch and existing.

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DRP 13-057 will be processed to modify U FSAR Section 2.4.1.1 "Site and Facilities" to describe the additional method of CW blowdown discharge via the added diffuser spillway in addition to the flume. In addition, Section 2.4.8.1 "Pipelines" will be revised to differentiate between the maximum blowdown flowrate during normal operation and the maximum permissible blowdown flowrate allowed by the Braidwood National Pollutant Discharge Elimination System (NPDES) permit. DRP 13-057 will also correct a typographical error identified in UFSAR Section 2.4.11.5 relative to thermal mixing zone compliance with Illinois Pollution Control Board regulations. The aforementioned UFSAR changes are needed to describe an improved diverse method of CW blowdown discharge into the Kankakee River.

None of these changes adversely affect the function of the CW blowdown system as described below in the UFSAR.

The CW System functions to provide heat rejection for the steam cycle by continuous circulation of cooling water through the main condenser and a cooling pond utilized to dissipate waste heat. Water chemistry, including dissolved solids concentration, in the cooling pond is controlled by continuous makeup from and blowdown to the Kankakee River (UFSAR Section 10.4.5). Effluent from the Liquid Radwaste System (after appropriate processing and monitoring) may be discharged to the environment via the CW blowdown line. Wastes from the Turbine Building floor drain tanks and Turbine Building Fire and Oil sump (via the Waste Treatment System), and discharge from the Condensate Polisher sump is discharged into the cooling pond at the CW discharge canal, where it mixes with circulating water prior to release to the Kankakee River via the CW blowdown line. In addition, temporary groundwater remediation activities, including collection of contaminated water from the Exelon Pond and surrounding groundwater is pumped into the CW blowdown line for release to the environment (UFSAR Section 11.2.3).

As identified in UFSAR Table 3.2-1, CW blowdown is considered a part of the Raw Water system and is considered a Safety Category II (non-safety related), Quality Group D, Non-IE (electrical classification) system. The CW system does not perform any safety function and is not required for safe shutdown of the plant and is not credited in any accident analyses.

This activity will not alter the safety classification or function of the CW system or CW blowdown as described in the UFSAR. This activity will not change any SSCs that would adversely impact the CW system blowdown function to maintain cooling pond water chemistry.

This activity will not alter the CW blowdown system interface with the Liquid Radwaste, Waste Treatment or Condensate Polishing systems and the quantity of liquid wastes that are fed into the CW blowdown system for discharge to the Kankakee River are not altered by this change. UFSAR described methods to monitor and isolate effluent discharge to the CW blowdown system are not altered by this activity. This activity will not change expected liquid radwaste annual radionuclide releases identified in Table 11.2-1.

The added piping, valves, piping appurtenances and instrumentation monitoring devices have the same safety classification as the existing CW blowdown piping components and are constructed to the same codes and standards as the original blowdown piping system.

A section of added instrumentation and isolated sections of the previous blowdown piping that normally contain water and are subjected to cold temperatures will be heat traced to preserve pressure integrity and prevent freezing damage. Power for the heat tracings, lighting, receptacles and the composite sampler equipment will be supplied from existing non-safety related River Screen House lighting cabinet 1LL30JA. This will have no adverse impact on the design of the station's electrical distribution system.

Based on the above description, the proposed activity does not involve a change to an SSC adversely affecting a UFSAR described design function.

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2. Does the proposed Activity involve a change to a procedure that adversely affects how UFSAR described SSC design functions are performed or controlled? (See Section 5.2.2.2 of the RM)

El Yes [No This activity will add new CW blowdown control valves and process controls for the new diverse (and preferred) CW blowdown flowpath to the added diffuser spillway. Station operating procedures will need to be revised to reflect the addition of these added components and associated valve lineups during system operation. Specifically, the added CW blowdown valves OCW26OA/B which will be placed in a normally open position (in conjunction with EC 375873) in addition to changing the position of existing blowdown valves OCW152A/B from normally "open" to normally "closed". The available CW blowdown controls, as described in Section 7.7.1.15 of the UFSAR are not affected by this activity. None of the aforementioned CW blowdown Station procedure changes affect how the UFSAR described CW blowdown function is performed or controlled.

No unwanted system/material interactions are introduced by this change.

This change will not introduce any changes to operator actions to plant accidents and transients as described in the UFSAR.

3. Does the proposed Activity involve an adverse change to an elements of a UFSAR described evaluation methodology, or use of an alternative evaluation methodology, that is used in establishing the design bases or used in the safety analyses? (See Section 5.2.2.3 of the RM).

LI Yes Z No The system and components being modified are not credited in any UFSAR safety analysis. There is no UFSAR described unique evaluation methodology associated with the CW blowdown system with the exception of the assessment of expected radioactive releases to the Kankakee River (UFSAR Section 11.2.1.3). However, the quantity and types of liquid wastes that are fed into the CW blowdown system for discharge to the Kankakee River are not altered by this change. UFSAR described methods to monitor effluent discharge to the CW blowdown system are not altered by this activity. The affected piping system maintains a Quality Group D, Safety Category II designation as defined in UFSAR Table 3.2-1 and is designed to the codes applicable to this quality group classification. The added piping, valves, electrical components and structures meet the same design codes and standards applicable to the original CW blowdown system components.

The proposed activity does not utilize any changes to methodology used to establish the UFSAR described design basis as summarized above.

4. Does the proposed Activity involve a test or experiment not described in the UFSAR, where an SSC utilized or controlled in a manner that is outside the reference bounds of the design for that SSC or is inconsistent with analyses or descriptions in the UFSAR? (See Section 5.2.2.4 of the RM)

El Yes Z No This activity adds piping, valves, controls and supporting structures required to direct CW blowdown flow to a new multi-port diffuser over an added concrete spillway in the Kankakee River. EC supporting analyses have been performed to ensure that the SSCs are not utilized or controlled beyond their design limitations. The only analyses associated with the CW blowdown system described in the UFSAR are the expected radioactive releases to the Kankakee River. However, the quantity and types of liquid wastes that are fed into the CW blowdown system for discharge to the Kankakee River are not altered by this change.

Therefore, this activity does not involve a test or experiment or subject CW blowdown system components in a manner outside their design bounds.

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5. Does the proposed Activity require a change to the Technical Specifications or Facility Operating License? (See Section 5.2.2.5 of the RM)

El Yes 0 No The CW blowdown system and components are not addressed in the Operating License or Technical Specifications. There is no impact from this activity on any component or systems that are covered by these documents. Therefore, there are no changes required.

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II. List the documents (e.g., UFSAR, Technical Specifications, other licensing basis, technical, commitments, etc.) reviewed, including sections numbers where relevant information was found (if not identified in the response to each question).

UFSAR Sections 2.1 GEOGRAPHY AND DEMOGRAPHY 2.1.1 Site Location and Description 2.1.1.2 Site Area Map 2.1.1.3 Boundaries for Establishing Effluent Release Limits 2.4 HYDROLOGIC ENGINEERING 2.4.1 Hydrologic Description 2.4.1.1 Site and Facilities 2.4.8 Cooling Water Canals and Reservoirs 2.4.8.1 Pipelines 2.4.11 Low Water Considerations 2.4.11.5 Plant Requirements 2.4.11.6 Heat Sink Dependability Requirements 2.4.13 Groundwater 2.4.13.2 .3 Effects of Seepage from Cooling Pond 3.2 CLASSIFICATION OF STRUCTURES, COMPONENTS, AND SYSTEMS 3.2.2 Quality Group Classification Table 3 .2-1 Safety Category and Quality Group Classification for Structures and Components 7.7 CONTROL SYSTEMS NOT REQUIRED FOR SAFETY 7.7.1 Description of Control Systems Not Required for Safety 7.7.1.15 Circulating Water System Controls 9.2 WATER SYSTEMS 9.2.5 Ultimate Heat Sink 9.2.5.2 System Description 10.4 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4.5 Circulating Water System 11.2 LIQUID WASTE MANAGEMENT SYSTEMS 11.2.1 Design Basis 11.2.1.1 Safety Design Basis 11.2.1.2 Power Generation Design Basis 11.2.1.3 Expected Radioactive Releases 11.2.2 System Description 11.2.2.2.7 Turbine Building Floor Drain 11.2.2.2.8 Turbine Building Fire and Oil Sump 11.2.2.2.9 Condensate Polisher Sump 11.2.2.2.10 Waste Treatment System 11.2.3 Radioactive Releases 11.2.3.1 Release Points Table 11.2-1 Expected Annual Average Releases of Radionuclides in Liquid Effluents Table 11.2-2 Parameters Used in the Gale-PWR Computer Program (Original & Uprated)

Table 11.2-4 Comparison of Expected Liquid Effluent Concentrations to 10 CFR 20 Limits Table 11.2-6 Design-Basis Annual Average and Maximum Waste Stream Flows 11.5 PROCESS AND EFFUENT RADIOLOGICAL MONITORING AND SAMPLING SYSTEMS 11.5.1 Design Bases 11.5.1.1 Design Objectives 11.5.2 System Description 11.5.2.3.7 Turbine Building Fire and Oil Sump 11.5.2.3.8 Condensate Cleanup Area Sumps Discharge 130 of 238

Other Documents:

NPDES Permit No. IL0048321 HydroQual Report EXCO.001, dated August 2, 2007.

HydroQual Report EXCO.003, dated February 13, 2009.

Addendum to February 13, 2009 HydroQual Report EXCO.003, dated May 6, 2010.

Ill. Select the appropriate conditions:

0 If all questions are answered NO, then a 50.59 Evaluation is not required.

E3 If question 1, 2, 3, or 4 is answered YES for any portion of an Activity and question 5 is answered NO, then a 50.59 Evaluation shall be performed for the affected portion of the Activity.

FD If question 5 is answered YES for any portion of an Activity and questions 1 through 4 are answered NO for the remaining portions of the Activity, then a License Amendment is required prior to implementation of the portion of the Activity that requires the amendment; however, a 50.59 Evaluation is not required for the remaining portions of the Activity.

El Ifquestion 5 is answered YES for any portion of an Activity and question 1, 2, 3, or 4 is answered YES for any of the remaining portions of the Activity, then a License Amendment is required prior to implementation of the portion of the Activity that requires the amendment and a 50.59 Evaluation is required for the remaining affected portions of the Activity.

IV. Screening Signoffs:

The 10CFR50.59 screening has been approved by the Site's Qualified Screening Process on 8/10/10.

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BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2011 UNIT 1 AND 2 (Docket Numbers 50-456 and 50-457)

ATTACHMENT 3 Supporting Documentation of Engineering Change 378192 132 of 238

EC 378192 Description of the Engineering Change (EC):

Revision 002 incorporates vendor drawings that were revised during the Factory Acceptance Test. DCS Sections 4.1.35 and 4.1.36 are revised to add reference to the radiation monitor internal wiring drawings that were issued after Revision 000.

Revision 001 did not revise the Design Considerations Summary.

The liquid contents of the Release Tanks 0WX01T and OWX26T are monitored by Radiation Monitor OPR01J in recirculation mode or discharge mode. Presently, this is the only monitor for both tanks. Both tanks are piped to a common header that discharges to Circulating Water (CW) blowdown. On detection of increased radiation in the blowdown effluent stream, Release Tank Discharge Header isolation valves 0WX353 and 0WX896 auto-close to terminate the effluent release. Because of the single monitor design, only one tank at a time can be monitored during a discharge. This prevents the other tank's effluent from being monitored until the previous release is completed. This inefficiency prevents the near continuous discharge of effluent.

To allow one tank to be monitored while the other tank is being discharged, a second radiation monitor skid equivalent to the existing OPR01J skid is added to the system configuration. The new radiation monitor OPR90J is located near 0PR01J and the release tanks. Its sample point monitors the discharge of release tank OWX26T.

The original common sample point to OPR01J is relocated such that it will monitor only tank OWX01T.

This EC provides the design to incorporate the new radiation monitor. It includes the skid installation, inlet and discharge piping, back flush water and drain, new cables for the 120 VAC power feed and connections into the RM-1 1 network, re-programming of the RM-1 1, and the revision of control circuits for the valves 0WX353, OWX896, 0WX889, and OWX890. The functionality of the new monitor will be identical to that of OPRO1J. A radiation condition at either monitor will alarm in the Radwaste Control Room Panel OPL01J and initiate an interlock into the discharge valve control circuits.

The revised Release Tank Discharge Header valve control circuits will allow the discharge of one tank as long as the other tank is isolated during recirculation. If a radiation condition occurs during the recirculation of an isolated tank, the discharge of the other tank will not be interrupted. If a radiation condition occurs during effluent release and discharge into CW blowdown, the discharge will be isolated and terminated.

The following items were identified in CC-AA-102, Attachment 1 as requiring consideration for the design of this configuration change:

4.1.4.1 Basic System, Structure, or Component (SSC) Functions The Radiation Monitoring System provides monitoring, sampling, measurement, indication, and control of radioactivity in those effluent streams which discharge to the environs outside the plant boundaries. The system provides a means to inform Operating personnel of liquid and airborne radiation levels in the plant. The OPR01J skid is a liquid process radiation monitor in the common discharge path of the release tanks OWX01T and OWX26T. It monitors effluent discharges into the station blowdown prior to discharge to the environment and interrupts an effluent discharge on a high radiation condition.

The liquid radwaste effluent radiation monitors are part of the Process and Effluent Radiation Monitoring and Sampling System as described in UFSAR Sections 11.5 and 7.7.1.19. The system function is to provide measurement, indication, and/or control of radioactivity in those streams which could conceivably be contaminated by radioactive substances. The system provides operating personnel with radiological measurements within the plant process systems. The objective of the effluent monitoring system is to sample and monitor each discharge path prior to discharge. UFSAR Table 11.5-2 describes that skid OPR01J has automatic interlocks in Section 11.5.2.3.1 for Liquid Radwaste Effluent Monitors. The interlocks require that the release tank discharge valves 0WX353 and 0WX896 close on high radiation.

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The Release Tanks OWX01T and OWX26T are the collection points for the plant liquid drains and waste effluents in the Liquid Radwaste system. After being monitored, the release tanks are individually discharged through a common header into the station blowdown line that discharges to the Kankakee River. Existing Radiation Monitor OPR01J monitors the common header and upon detection of radioactivity will automatically isolate the discharge flow by closing the release tank discharge isolation valves 0WX353 and 0WX896, which are in parallel discharge paths. Since the existing monitor is in the common discharge path, both tanks are isolated from a discharge when only one of the tanks may have elevated radioactivity in the effluent. A second monitor and revised valve control interlocks will provide operating flexibility for release tank discharges.

4.1.4.2 Safety Classification of Configuration Change This EC is classified Non-Safety Related. The affected portions of the PR, WX and WM systems are Non-Safety Related. This EC also affects control panel 0PL01J in the Radwaste Control Room in the Aux Building El. 383'.

0PL01J is a non-safety related panel.

4.1.4.3 Seismic Classification of SSC This EC is classified Seismic Category II (Non-Seismic). The 0PR01J and 0PR90J liquid process radiation monitors and associated monitor piping are classified Seismic Category II (Non-Seismic) and are located in the Unit 1 Turbine Building.

This EC also affects control panel OPLO1J in the Radwaste Control Room in the Aux. Building El 383'. The panel is classified as Seismic Category II (Non Seismic).

4.1.5 Performance Requirements and Design Conditions The performance requirements and design conditions are defined in UFSAR Section 11.5. The UFSAR invokes Standard ANSI N 13.10-1974 "Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents". ANSI N13.10-1974 has been re-designated as ANSI N42.18-2004. This standard is the basis of the technical requirements for the new radiation monitor from General Atomics.

Original radiation monitor OPR01J was procured under Specification L-2827. This spec included ANSI N13.10-1974 for the technical requirements. The new radiation monitor has the same function as 0PR01J; thus the same criteria apply.

Design Criteria from UFSAR 11.5 that is applicable to liquid effluent monitors:

  • Monitors are gamma-responsive scintillation detectors to provide maximum sensitivity to a water medium.
  • Shielding provided to reduce background and increase sensitivity.
  • Monitors are designed to fail in the interlock mode in the event of loss of power, loss of signal, or operate failure.
  • Alarms annunciate in the main control room.
  • Monitors provide readouts, alarms, and trending in the main control room.
  • Monitor components are readily accessible for maintenance.

" Designed for operability within the environmental conditions listed in UFSAR Table 3.11-2. See Section 4.1.14 for details.

" Alarm setpoints are adjustable over the range of the instrument.

" Two independent setpoints are available, one for alarm and one for initiating corrective action.

  • UFSAR Section 11.5.2.3.1 "Liquid Radwaste Effluent Monitor" describes that detector ORE-PRO01 monitors effluent from either 30,000-gallon release tank. The release tank discharge valves 0WX353 and 0WX896 close on high radiation. These required features are included in this design change that adds radiation monitor OPR90J.

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The process parameters applicable to OPR01J according to original procurement Spec L-2827 are:

  • Fluid = Water

" Pressure Max./Normal = 50 psig/50psig.

  • Flow Range = 1- 9 GPM (per vendor drawing 3582200)
  • Temp. Max./Normal = 122 OF/80°F
  • Pipe Sch./Size = Sch. 40S/6"
  • Pipe Material = ASTM A312/GR TP304

" Tubing Material = ASTM A213/ GR TP304 (per PDT 359BB)

" Seismic Category = I1.

" Quality Group = D.

These parameters are applicable to the new monitor OPR90J.

These design criteria for the new radiation monitor are included in Specification 29487-BRWO1 66-01. The specification is the basis of the radiation monitor procurement from General Atomics. The original procurement specification for radiation monitors was L-2827. Specification L-2827 requirements that are applicable to liquid monitors were incorporated in the new specification.

The radiation monitor requires a 120VAC single-phase power source and has a nominal load of 5 amps with a maximum load rating of 10 amps surge (200 msec).

UFSAR Section 11.5 and Table 11.5-2 have been revised (DRP 13-052) to address the new monitor.

4.1.6 Surveillance and Acceptance Testing The required post-modification testing is specified in accordance with procedure T&RM CC-AA-107-1001 with specific testing identified on form CC-AA-107, Attachment 1 contained in Tab 5 of the EC. A Vendor Factory Acceptance Test (FAT) is required and will be defined by the vendor's procedures. The test will be performed at the General Atomics Facility using radioactive sources as defined by Braidwood Station. The FAT is not part of this EC. Completion and acceptance of the FAT is tracked by Milestone 600 that will be signed by the System Manager.

The radiation monitor must be on a periodic surveillance program to the same frequency and criteria as monitor OPRO1J. Predefine activity PMID 00039329 covers OPRO1J. Procedure OBWIS RETS 2.1-1 is the 92-day frequency digital channel operational test for OPRO1J. Procedure BWIS RETS 2.1.B-201 is the 18-month surveillance calibration for Liquid Effluent Monitors. Similar predefine activities and surveillance procedures are required for the new radiation monitor OPR90J. Action Tracking Item ATI #01068985-03 is assigned.

4.1.7 Codes, Standards and Regulatory Requirements The following are applicable to this design change:

0 10CFR20, Standards for Protection Against Radiation

  • Regulatory Guide 1.143, Design Guidance for Radioactive Waste Management Systems, Structures and Components installed in Light-Water-Cooled Nuclear Power Plants 0 Regulatory Guide 8.8, Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations will be as Low As Is Reasonably Achievable"
  • ANSI N42.18-2004 Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents 0 ANSI B31.1, 1973 Edition with Summer 1975 Addenda Power Piping Code (Field Erected Piping/Tubing)
  • ASME B31.1, 2007 Edition Power Piping Code (Liquid Radiation Monitor)
  • Specification 29487-BRWO166-01 Rev. D "Liquid Radiation Monitor" 135 of 238

4.1.9 Affected Design Analyses The following design analyses and evaluations are issued to support this design change. The affected calculations are listed on the ADL.

Calculations are pending approval. HOLD milestone is created and will be signed off when calculations are approved.

Exelon Calculation ATD-0026, Calculation of Combustible Fire Loads is affected but not revised for this EC.

This calculation evaluates the impact of the new combustibles in Turbine Building Fire Zones. The added combustibles are cable insulation in trays. Exelon will revise this calculation based on TODI URS-BRW-10-002 from URS.

Piping Calculation 0PRF90 was created to document the piping and tubing in subsystem OPRF90.

Two Structural Calculations, 9.15.1 -BRW- 10-0103-S and 9.2.2-BRW-1 0-0104-S, evaluate the panel assembly attachments on the block wall and the skid weight on the floor slab loading.

4.1.12 Fire Protection and Appendix R Safe Shutdown Requirements The B/B Fire Protection Report (FPR) lists the Turbine Building Unit 1 Basement Level, fire zone 8.2-1 and Turbine Building Unit 1 Grade Level, fire zone 8.3.1. The FPR is being revised via FDRP 24-038 to account for changes in the combustible loading attributed to this design change. The added combustibles are cable insulation in cable tray. This activity has no affect on any Safe Shutdown equipment.

The changes in combustible loading are documented on the Fire Protection Program Design Change Impact Evaluation (CC-AA-209, attachment 1) included in Tab 7.

4.1.13 Material Requirements / Material Suitability Requirements All material and components for the radiation monitor skid are fabricated and furnished by General Atomics to the material requirements of Specification 29487-BRWO166-01.

Valve and piping/tubing material requirements from the applicable PDT are listed on the ECML, CC-AA-103 Att.

H, of this EC.

Cables and other critical engineered materials that are not part of the skid are listed on the ECML, CC-AA-103 Att. H in this EC.

4.1.14 Environmental Conditions or Impacts This design change was reviewed for possible environmental impacts in accordance with EN-AA-103, "Environmental Review". A review of EN-AA-103, Attachment 1, Environmental Review Checklist results in at least one "Yes" answer. Tanks that contain a chemical or fuel (Item 15) are affected since the release tanks OWX01T and OWX26T may contain tritiated water. Therefore, a review by Environmental personnel is applicable to this design change. The checklist is included in TAB 8.

The radiation monitors are located at elevation 401'-0" in the Turbine Building. The normal environmental design conditions at this elevation during normal plant operating conditions are as follows: (from B/B UFSAR Table 3.11-2)

  • Specifically for OPR01J and OPR90J, in the Turbine Building Environment: temperature maximum of 104 0 F; relative humidity range 70% to 8%; Pressure 0.0" water gage; Radiation maximum integrated exposure 350 rads over 40 years.

" These criteria are bounded by the technical requirements listed in original Procurement Specification L-2827 which was used to define the procurement requirements for the new monitor.

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4.1.16 OPEX Review - Operatinq Experience The OPEX database was searched using the following keywords: "radiation monitor" and "General Atomics" and "RM-80". While many operating experience reports on radiation monitors were identified in the INPO database, none were in the category of skid design failures.

General Atomics issued a Part 21 notice in 2009 regarding RM-80 firmware anomaly. It was applicable for safety-related applications and annunciator output applications. Firmware had to be replaced. Braidwood AR 992115 documents the evaluation for this issue. Monitor 0PR01J was identified as potentially affected and a testing procedure was done. This condition potentially applies to the new monitor since it has similar outputs as OPR01J. Testing will verify that the firmware anomaly does not impact the new radiation monitor.

4.1.17 EPIX Data Base Affected New radiation monitor OPR90J has the same functionality as monitor 0PR01J. The EPIX data base will be reviewed for radiation monitor applicability and updated as appropriate. ATI #01068985-05 is assigned for tracking.

4.1.19 System Operational Requirements Chanqes This design change affects the system operational requirements for release tank recirculation and discharges.

The addition of radiation monitor OPR90J and the relocation of the sample monitoring point for 0PR01J provide system configuration options for the Operating and Chemistry Departments that previously have not existed.

Upon completion of this EC, operations and chemistry will be able to independently monitor the two Liquid Release Tanks while isolated from the discharge path.

When tank 0WX01T is being monitored on recirculation, its discharge isolation valve 0WX889 will be closed.

During the recirculation, if high radiation is detected, an alarm notifies Operations. If a release is in progress from opposite tank 0WX26T, the release will not be interrupted since 0WX889 is closed.

Similarly, when tank 0WX26T is being monitored on recirculation, its discharge isolation valve 0WX890 will be closed. During the recirculation, if high radiation is detected, an alarm notifies Operations. If a release is in progress from opposite tank OWX01T, the release will not be interrupted since 0WX890 is closed.

Only one of the two release pump discharge valves 0WX889 or 0WX890 will be open at any one time by procedural control and interlock design.

The logic for the revised interlocks for release valves 0WX353 and 0WX896 is displayed in logic tables on the schematic diagrams 20E-0-4030WX040 and 20E-0-4030WX179.

During a tank release evolution, if a high radiation condition occurs for the tank being discharged, interlocks will cause the release to be terminated by closure of valves 0WX353 and 0WX896.

Numerous annunciator response procedures and operating procedures must be revised to address that tanks OWX01 T and OWX26T are monitored separately and to include 0PR90J in the various radiation monitor lineup and sorting list procedures.

4.1.20 Human Factors Requirements The new radiation monitor 0PR90J will alarm at Radwaste Control Room OPL01J at a common window with OPR01J. The window engraving "Release Tank Disch Header Radiation High" is not changed by this EC. The annunciator response procedure BwAR OPL01J-7-A9 is listed on the ADL and Operating Dept CC-AA-102 Att. 9 for revision to address the new monitor.

The system mimic layout on panel 0PL01J is updated for the revised sample position of 0PR01J and the new OPR90J.

The new radiation monitor will alarm in the Main Control Room RM-1 1 computer. The graphic displays must be revised as part of this EC to include the configuration of the new monitor. The vendor is providing software revision services. A Work Order Task is tracking this activity.

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4.1.21 Procedure Chanaes Operating, Instrument Maintenance, Rad Protection, System Engineering, and Chemistry Department procedures are affected. The procedures are listed on the ADL and on form CC-AA-102, Attachment 9 for each department.

A new calibration TRP (OR-PRO90) has been drafted for the new radiation monitor OPR90J and is included in Tab 8 of this EC. The TRP is based on functional similarity to radiation monitor 0PR01J. As vendor documentation becomes available, the TRP may need to be revised. This is tracked by AT 01068985-06.

4.1.22 Training Requirement Changes Training Requirements are documented on CC-AA-102, Attachment 9 and Attachment 10E.

4.1.23 System Interface Requirements The radiation monitor has interfaces with the Demineralized Water System, Liquid Radwaste System, Aux Power System, and the Process Monitoring RM-1 1 Computer.

The Plant Process Computer (PPC) is not a direct interfacing system; however, the PPC is also affected since the RM-1 1 data points are inputs to the PPC. With the addition of a new monitor, the PPC requires programming of a new data point.

The following sections 4.1.33, 4.1.35, and 4.1.36 discuss those interfaces in detail.

The Braidwood Simulator is affected and requires program changes to include the new radiation monitor. This is tracked by a Training Work Order listed on Attachment 1OE.

4.1.24 Layout The new radiation monitor location is adjacent to Release Tank OWX26T in a corner of the tank block wall room Unit 1 Turbine Building El. 401'. The vendor was challenged to provide a skid that does not require rear access due to limited access space in the location. Vendor responded with a more compact skid with front access panels and remote panels that met the space requirements. The design incorporates a remote mounted RM-80 microprocessor and front access junction boxes which allows the skid to be mounted directly against the wall.

The detector module is oriented such that it is removable in the north direction where the largest open space exists for maintenance and calibration activities.

4.1.25 RP/ALARA Concerns The work associated with this engineering change will be performed in a radiologically controlled (RCA) low radiation area in the Turbine Building at floor elevation 401'-0". The release tanks and skids are located inside the hollow block shield wall north of Unit 1 18-line. An ALARA Applicability review was performed using CC-AA-102, Attachment 5. It determined that ALARA considerations should apply to the design and installation. ALARA Design and Installation Reviews have been completed using CC-AA-212-1001, Att. 1 and Att. 2 and are included in Tab 8.

4.1.26 Need for Walkdowns Designer's Walkdowns were performed at various points during the conceptual and design phases. Form CC-AA-106-1001 Attachment 2 is included in Tab 8.

An Installer's Walkdown shall be performed prior to start of work activities to confirm spare circuit breaker position, spare limit switch contacts, and spare conductors in boxes that were not accessible during Designer's Walkdowns. A Work Order has been created.

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4.1.29 Effect on Emerqency Plan or Environmental and Discharge Monitoring This EC introduces no changes to the approved effluent discharge limits and discharge release administrative controls. The addition of the new monitor does not introduce a new or different release path. This EC provides a configuration that separately monitors both of the release tanks upstream of the discharge point into Circulating Water Blowdown.

A revision to the procedure CY-BR-170-301 "Offsite Dose Calculation Manual (ODCM)" is required to include the new monitor 0PR90J in the sections that address monitoring of liquid effluent. The procedure is included in the affected procedure list form CC-AA-102, Attachment 9 for the Chemistry Department.

4.1.30 Industrial Safety Requirements The radiation monitor skid power feed junction box is grounded in accordance with Nuclear-Electrical Installation Standard N-C-0003 and design drawing 20E-0-3391A.

4.1.33 Mechanical System Characteristics The new radiation monitor will require new sample lines from release pump (OWX53P) to the inlet of the monitor (0PR90J) and from the radiation monitor outlet to release tank (OWX26T). The new line will be routed between the tanks and along the south wall on 18 and will utilize existing pipe supports shown on M-6005 sheet 1 and new pipe supports shown on sketch PG-2617T-1 drawing detail 1. The new line and associated valves will be of stainless steel construction as specified in PDT 140BB. Remote operated valve 0WX848 will be locked closed as the flow path from the existing monitor (0PR01J) to release tank OWX26T will no longer be used as the monitoring for tank 0WX26T will be performed by the new radiation monitor, OPR90J. Piping, tubing, and valves will be installed as depicted on drawings M-48 sheet 1, M-836 sheet 3, and PG-2617T-1.

The sample point for monitor 0PR01J will be relocated upstream of isolation valve 0WX889 as a tapped connection. Relocation upstream of the isolation valve will allow for the individual monitoring of tank 0WX01T at release tank pump OWX01 P. Preliminary design included re-designing a sample probe in a new location. The vendor General Atomics recommended that a sample probe is not required to achieve the necessary process flow; see General Atomics letter AEE:647:001:10 dated March 17, 2010, in EC Tab 8. Therefore, the existing sample probe 0RX-PRO01 will be cutoff, capped, abandoned in place and placed on inactive status.

Line 0WX564B-3/4" will tap off of line 0WX454A-6" just upstream of valve 0WX890. New installed piping and tubing will become part of the PR system as it enters the monitor (OPR15B-3/4"), bypasses the monitor (OPR66B-3/4", OPR74A-3/4"), and exits the monitor (OPR16B-3/4")

Lines will be added for the new radiation monitor for demineralized water flushing (OWMV2B-3/4") and draining (OTEQ2B-1/2"). The monitor will require approximately 3 gpm for system flushing (vendor drawing 03582200 sheet 1).

P&ID M-48 Sheet 1 is being updated to reflect the locked close position of cross tie valve 0WX894 and the locked close position of return valve 0WX848.

P&ID M-48 Sheet 1 is revised with a Record Change to reflect that valve OWX890 is normally closed and normally de-energized. It has the same configuration as 0WX889.

4.1.35 Electrical Requirements The skid information cited below is based on preliminary radiation monitor outline diagrams and wiring interconnection diagrams from the vendor, General Atomics. A detailed schematic diagram incorporating the skid and RM-80 internal connection details has not yet been provided by the vendor. Drawing 20E-0-4030PR25 has been reserved as the schematic diagram for OPR90J. A revision to this EC may be required to incorporate the final drawings. This is tracked by AT 01068985-08.

Revision 002 incorporates the vendor drawings as revised during the Factory Acceptance Test. Reserved

'Schematic Drawing 20E-0-4030PR25 will not be issued and was removed from the EC in Revision 001. Vendor drawings 03582230 Shts. 1 & 2, 04600231 Sht. 1, and 03582231 Sht. 1 provide the radiation monitor internal wiring connections in lieu of a schematic drawing. Drawing 03582231 Sht. 1 was issued in Revision 001 and has not been changed since Revision 001.

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According to vendor drawing 03582200 Sheet 1, the skid has power requirements of single-phase 120 VAC +/-

10%, 5 amp nominal, 10 amp peak surge (200 msec). The skid does not require a pump to achieve sample flow. The skid power demand rating of 5 amp nominal is a load of 600 VA.

The power feed is from the 120/208 VAC distribution panel at MCC 134Y2. This distribution panel is powered from a 22.5KVA, 480-120/208V three-phase distribution transformer. The distribution panel loads shown on MCC Key Diagram 20E-1-4008CL and MCC wiring diagram 20E-1-4796C were evaluated to verify that the transformer has adequate capacity for the load additions. The total connected load on the transformer is less than 18 KVA. If load factors and a panel diversity factor were considered, the actual loading would be less.

Thus, there is adequate capacity to feed the new radiation monitor.

The feed cable to the rad monitor skid is #10 AWG which is adequate for the skid load of 5 amps (NEC Table 310.16). The feed cable is protected by a 20 amp circuit breaker as shown on MCC Key Diagram 20E-1-4008CL and MCC wiring diagram 20E-1-4796C.

A Division 12 power source is selected to power the new monitor to be consistent with the power feed to release tank pump OWX53P and discharge valve 0WX890. (Division 12). The new monitor is associated with pump OWX53P which is in the flow path of release tank OWX26T.

The skid is grounded in accordance with N-EIS standard No. N-C-0003 and drawing 20E-0-3391A, utilizing rigid steel conduit bonded to cable tray for a power circuit rated less than 600 amps.

One new cable is routed in control cable trays. SLICE Cable data program evaluated the cable routing and tray loading. No adverse loading conditions were identified by the cable addition.

4.1.36 Instrument and Control Requirements The skid information cited below is based on preliminary radiation monitor outline diagrams and wiring interconnection diagrams from the vendor, General Atomics. A detailed schematic diagram incorporating the skid and RM-80 internal connection details has not yet been provided by the vendor. Drawing 20E-0-4030PR25 has been reserved as the schematic diagram for OPR90J. A revision to this EC may be required to incorporate the final drawings. This is tracked by AT 01068985-08.

Revision 002 incorporates the vendor drawings as revised during the Factory Acceptance Test. Reserved Schematic Drawing 20E-0-4030PR25 will not be issued and was removed from the EC in Revision 001. Vendor drawings 03582230 Shts. 1 & 2, 04600231 Sht. 1, and 03582231 Sht. 1 provide the radiation monitor internal wiring connections in lieu of a schematic drawing. Drawing 03582231 Sht. 1 was issued in Revision 001 and has not been changed since Revision 001.

RM-1 1/RM-80 All plant radiation monitors interconnect into the RM-1 1 network. OPR90J is integrated into RM-1 1 communication Loop 3 and is assigned loop position 3-16. Communication Loop 3 is shown on drawing 20E 4705C. It will be electrically positioned between monitors OPR01J and 2PR27J by revising the existing signal cables between those two monitors and installing new signal cables from OPR90J to interconnect into the loop.

All other monitors in Loop 3 downstream of OPR90J (existing positions 3-16 through 3-21) will have their loop positions on drawings increased by one (new positions 3-17 through 3-22).

The RM-1 1 provides the Main Control Room alarm and indications for all plant monitors. Software changes in the RM-1 1 computer are required. The software must be revised to display the new monitor at operator's consoles and to develop the check and response commands that communicate with the new monitor. Vendor's support to edit the RM-1 1 "Online Database Builder" is required. OPR90J is the twenty-second (22nd) monitor in communication loop 3. It will be programmed in the RM-1 1 as octal address 26, displayed in Grid-1 screens.

The octal addresses of other loop 3 monitors will be unchanged; however, the loop positions for "downstream" monitors as shown on drawings are revised to maintain sequential numbering.

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The radiation monitor incorporates an RM-80 microprocessor for data acquisition and control, local indication, and develops 4-20 milliamp (ma) analog outputs for the external communication transmit and receive loop that interfaces with the station's RM-1 1 network. RM-80 includes history filing, continuous self-test, and online diagnostic capability. The alarm and interlock outputs are developed in the RM-80. Setpoints and calibrations are programmed through the RM-80. The RM-80 cabinet for OPR90J is remotely mounted near the monitor to allow a smaller skid footprint. The skid configuration is shown on General Atomics vendor drawings 03582200 Sheets 1 through 4, and 03582210 Sheets 1 and 2.

The skid includes an RM-23L local Control/Display module for local operator interface, digital display, status indication, and purge and checksource control.

The skid incorporates a flowmeter switch for visual indication of sample flow and for monitoring data in the RM-80.

Valve Control Circuits The control circuits of Release Tank Discharge Header valves 0WX353 and 0WX896 and Release Pump Discharge valves 0WX889 and 0WX890 are revised to add style AR440AR auxiliary relays. The continuous load rating for the AR440AR relay is 28 VA. The control circuits are each fused at 3 amps. The revised control circuit fuse loading was reviewed using standard E-l&C 10.01. The revised loadings on the fuses are acceptable.

Close limit switch contacts from release pump discharge valves 0WX889 and 0WX890 provide auxiliary relay interlocks in the control circuit logic of release valves 0WX353 and 0WX896. The interlocks are combined with the two radiation monitor high radiation interlocks to develop control circuit logic as described in Section 4.1.19 above.

Close limit switch contacts from release pump discharge valves 0WX889 and 0WX890 provide auxiliary relay permissive interlocks in the opening control circuit of the opposite valve. This is to assure that only one of the valves can be opened at any one time.

Reset pushbutton OHS-WX648 at OPL01J is modified with an added contact block to allow reset of the control circuit after a high radiation condition at OPR90J has been resolved. Existing contacts on the reset pushbutton provide the same reset functions for OPR01J high radiation condition and for a blowdown low flow condition.

Cyber Security/ Digital Asset The radiation monitor OPR90J will be added to the Exelon Critical Digital Asset (CDA) Database "Not in Scope -

BRW" group according to CC-AA-215. This is tracked by AT 01068985-02. The new radiation monitor provides a release tank monitoring and control function in the Liquid Radwaste System. It is interconnected into the RM-11 computer network and alarms in the Main Control Room. The RM-1 1 is only accessible from the Main Control Room which is a Vital area. The new component has a control function to interlock isolation valves in the release discharge path if the monitor has a high radiation condition. The radiation monitor skid is located inside a locked cubicle. Any changes to the skid programming requires authorized personnel access. Therefore, the radiation monitor was determined not to be a CDA. The subject component is non-safety related, non-critical, not Nuclear Significant, and does not affect Continuity of Power. No further cyber security evaluation is required.

The radiation monitor utilizes an RM-80 microprocessor. The software is Version - LIQ169.04. A DTSQA review is required to categorize and register the software. Vendor documentation is required to confirm the software ID.

This is tracked by AT 01068985-07.

PPC The Plant Process Computer (PPC) is also affected since the RM-1 1 data points are inputs to the PPC. The new PPC point for OPR90J is labeled RM-1 1 Monitor point 22, corresponding to octal address 26. The following table shows the Current Mapping and New Mapping for PPC points, as provided and controlled by the Exelon Corporate IT Department.

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For reference, RM-1 1 Point OPS1 01 below corresponds to monitor OPR01J.

Current Mapping PPC point RM-11 Point RM-11 loop RM-11 Monitor RM-11 Chan PPC offset PPC description RPOO01 OPS101 3 15 1 609 LIQUID RADWASTE EFF RP0200 OPS101 3 15 1 1433 LIQUID RADWASTE EFF 00-09 RP0201 OPS101 3 15 1 1435 LIQUID RADWASTE EFF 10-19 RP0202 OPS101 3 15 1 1437 LIQUID RADWASTE EFF 20-29 RP0203 OPS101 3 15 1 1439 LIQUID RADWASTE EFF 30-39 RP0204 OPS101 3 15 1 1441 LIQUID RADWASTE EFF 40-49 RP0205 OPS101 3 15 1 1443 LIQUID RADWASTE EFF 50-59 RP0132 2PS127 3 16 1 617 SJAE/GLAND STM EXH - GAS 2 RAD EVAP OA CONDENSATE RPOO07 OPS106 3 17 1 625 RETURN RAD EVAP 0B CONDENSATE RPOO08 OPS107 3 18 1 633 RETURN RAD EVAP 0C CONDENSATE RPOO09 OPS108 3 19 1 641 RETURN RP0106 2PS102 3 20 1 649 RCFC 2A/2C SX OUTLET RP0107 2PS103 3 21 1 657 RCFC 2B/2D SX OUTLET New Mapping- Italicized (Yellow) highlighting below indicates required change elements in the PPC.

RM-11 Monitor PPC point RM-11 Point RM-11 loop See Note RM-11 Chan PPC offset PPC description LIQUID RADWASTE EFF TANK RP0001 OPS101 3 15 1 609 OWXO1T RP0200 OPS101 3 15 1 1433 LIQUID RADWASTE EFF 00-09 RP0201 OPS101 3 15 1 1435 LIQUID RADWASTE EFF 10-19 RP0202 OPS101 3 15 1 1437 LIQUID RADWASTE EFF 20-29 RP0203 OPS101 3 15 1 1439 LIQUID RADWASTE EFF 30-39 RP0204 OPS101 3 15 1 1441 LIQUID RADWASTE EFF 40-49 RP0205 OPS101 3 15 1 1443 LIQUID RADWASTE EFF 50-59 RP0132 2PS127 3 17 1 617 SJAE/GLAND STM EXH - GAS 2 RAD EVAP OA CONDENSATE RPOO07 OPS106 3 18 1 625 RETURN RAD EVAP 0B CONDENSATE RP0008 OPS107 3 19 1 633 RETURN RAD EVAP OC CONDENSATE RPOO09 OPS108 3 2d 1 641 RETURN RP0106 2PS102 3 21 1 649 RCFC 2A/2C SX OUTLET RP0107 2PS103 3 22 1 657 RCFC 2B/2D SX OUTLET LIQUID RADWASTE EFFTANK RP0141 **OPS190 3 16 1 665 OWX26T Note: RM-1 1 Monitor Column is the physical position on the print (20E-0-4705C)

Proposed Point ID is consistent with ID mapping of existing radiation monitors. The RM-1 1 Points are display codes in Annunciator Response Procedures (e.g. BwAR RM-1 1 Grid-i)

Computer Database Change Request Form IT-AA-101-1502-F-01 has been reviewed and approved by IT and is included in EC Tab 8.

In order for the revised points to display in the HMI and graphics system, the PPC will require a restart that must coincide with the startup of the new monitor. A restart will need to occur on PPC's in both Unit 1 and Unit 2.

These will be accomplished by a Work Order task assigned to IT.

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4.1.38 Civil/Structural Requirements The configuration is a Seismic Category II SSC in the Turbine Building. The installation does not require seismic qualification or mounting.

This EC also affects liquid radwaste control panel 0PL01J in the Radwaste Control Room in the Aux Building El.

383'. The panel is classified as Seismic Category I1. The EC includes the addition of three auxiliary relays to the panel. By engineering judgment, the weight of the added relays has negligible impact on the structural integrity of the panel.

Calculation 9.2.2-BRW-10-01 04-S documents the mounting of the Radiation Monitor skid to the Unit 1 Turbine Building (ref: EL 401'0") reinforced concrete slab. The skid has an approximate weight of 3300 Ibs, which is mounted to the floor with anchors and a PL /2" x 2'4-1/2" x 2'4-1/2".

Calculation 9.15.1-BRW-10-0103-S documents the mounting of the Control Panel assembly to the existing masonry block wall. The control panel assembly weighs approximately 250 pounds and is mounted to the hollow masonry block wall adjacent to the Release Tanks in the Unit 1 Turbine Building El. 401' (ref: Col: 18). The control panel assembly consists of two panels and is approximately 42" x 31" overall dimension. It is mounted with 6 thru-wall threaded rods, washers, hex nuts, and a 1/4"backing plate on the exterior of the block wall in accordance with drawing 20E-1 -3432D01.

4.1.40 Personnel Requirements and Limitations The vendor General Atomics will provide technical personnel for radiation monitor checkout and startup support at the plant.

4.1.42 Interfacing Departments This modification will require reviews by several departments at Braidwood Station. The reviews are documented on the CC-AA-102, Attachment 10 forms in PASSPORT.

4.1.44 Conformance to NEIL Requirements The NEIL Loss Control Standards were reviewed for requirements specific to installing new radiation monitoring components. None were identified.

4.1.45 Single Point Vulnerability (SPV) identified in the Configuration Chanqe A single point vulnerability (SPV) review has been performed for the configuration change. The purpose of the review was to identify all events that can result in unplanned Reactor Scrams in a proactive manner, with the intent of taking action to prevent such events.

A review has been performed to identify any latent failures in redundant, non-safety related trip circuits that have the potential to cause a reactor scram. None of the systems or system components modified by this EC has the potential to cause a reactor scram. The control circuits for the radiation monitor and associated release isolation valves do not trip nor are interlocked with any SSCs that can cause a reactor scram. Therefore, there are no latent failures in the modified circuits.

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10CFR50.59 screening for EC 378192 50.59 Screening Questions (Check correct response and provide separate written response providing the basis for the answer to each question) (See Section 5 of the Resource Manual (RM) for additional guidance):

Does the proposed Activity involve a change to an SSC that adversely affects an UFSAR described design function? (See Section 5.2.2.1 of the RM)

El Yes N No The proposed activity affects the Process and Effluent Radiation Monitoring and Sampling System. It also affects the Non-i E Aux Power (AP), Liquid Radwaste (WX), and Demineralized Water (WM)

Systems. The proposed activity does not adversely affect the functions of these systems, as discussed below.

The proposed activity provides for a revised process monitoring capability in the Liquid Effluent Release path from Release Tanks OWX01T and OWX26T. The change provides plant operating flexibility for planning and executing the release of liquid effluents.

The Release Tanks OWX01T and OWX26T are the point of release to be discharged to the Kankakee River. After being monitored for radioactive contamination, the release tanks are individually discharged through a common header into the station blowdown line that discharges to the Kankakee River.

Existing Radiation Monitor OPR01J monitors the common header and upon detection of radioactivity will automatically isolate the discharge flow by closing the release tank discharge isolation valves 0WX353 and 0WX896. Only one tank is aligned for a discharge at any one time. A second monitor and revised valve control interlocks will provide operating flexibility for release tank discharges.

This activity installs a new liquid radwaste effluent radiation monitor OPR90J that will monitor only the liquid release tank OWX26T discharge path. The monitored process point is upstream of the common discharge header. The new monitor isolates tank OWX26T, if being discharged to the blowdown discharge line, if high radiation is detected in its flowpath. If the tank is only on recirculation while it is isolated from the blowdown discharge line, detection of a high radiation condition will not interrupt an in-progress release from the opposite tank.

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This activity also relocates the monitoring point of existing liquid radwaste effluent radiation monitor OPR01J from the common discharge path of release tanks OWX01T and OWX26T to monitor only the discharge from tank OWX01T. The high radiation interlock of OPR01J continues to interlock the discharge isolation valves 0WX353 and 0WX896 and will isolate a discharge to blowdown if high radiation is detected in the flowpath. If the tank is only on recirculation while it is isolated from the blowdown discharge line, detection of a high radiation condition will not interrupt an in-progress release to blowdown from the opposite tank.

The sample location for OPR01J is changed. Relocation of the existing sample probe for OPR01J (ORX-PRO01) was considered. The vendor General Atomics evaluated and determined that a sample probe is not required to achieve the necessary process flow. Therefore, the existing sample probe ORX-PRO01 will be cutoff, capped, abandoned in place and placed on inactive status.

The new monitor OPR90J is furnished with an RM-80 microprocessor which is integrated into the RM-1 1 communication loop to provide measurement data to the Control Room operators. There is no change to the communication from OPRO1J's RM-80 to the RM-1 1.

The control circuits for valves 0WX353, 0WX896, 0WX889, and 0WX890 are revised in the Liquid Radwaste Control Panel OPL01J to interlock with the new radiation monitor. Valves 0WX353 and 0WX896 are automatic isolation valves in the blowdown path. Their revised control circuits have new close interlocks from valves 0WX889 and 0WX890, the individual tank discharge pump isolation valves, to differentiate if a tank is on recirculation or is being released. If a tank is on recirculation it is isolated from the discharge header and is monitored by its respective radiation monitor. Valves 0WX889 and 0WX890 interlock each other such that only one can be open at a time. Detection of radiation during isolated recirculation results in alarms to the control room RM-1 1 computer and annunciation at OPLO1J, but does not auto-close the release isolation valves 0WX353 and 0WX896. This allows the opposite tank to continue its monitored discharge. Radiation detection by either monitor during discharge of its respective tank will auto-close the release discharge valves.

These liquid radwaste effluent radiation monitors are part of the Process and Effluent Radiation Monitoring and Sampling System as described in UFSAR Sections 11.5 and 7.7.1.19. The system function is to provide measurement, indication, and/or control of radioactivity in those streams which could conceivably be contaminated by radioactive substances. The system provides operating personnel with radiological measurements within the plant process systems. The objective of the effluent monitoring system is to sample and monitor each discharge path prior to discharge. UFSAR Table 11.5-2 describes that skid OPR01J has automatic interlocks per Section 11.5.2.3.1 for Liquid Radwaste Effluent Monitors. The interlocks require that the release tank discharge valves 0WX353 and 0WX896 close on high radiation. The addition of new monitor OPR90J accomplishes the measurement and interlock functions. The revision to OPR01J interlocks continues to accomplish these functions. OPR90J is added to the UFSAR as tracked by DRP13-052.

New monitor OPR90J is furnished by the original supplier of Braidwood's process monitors, General Atomics, to the same technical criteria as monitor OPRO1J. The new monitor will have equivalent performance and measurement parameters as OPRO1J. Thus, it will provide the process monitoring function no differently than OPRO1J.

The capability to monitor liquid effluent discharges from the Liquid Radwaste system release tanks and to isolate radioactive effluents is not changed by this EC activity.

New piping and conduit are designed and installed appropriately in accordance with original Design Criteria for a non-Safety Related application in a non-seismic (Category II)structure.

The new monitor skid is a new load on the Non-lE Aux Power system from the 120/208VAC distribution panel at MCC 134Y2. The load addition is within the rating capability of the MCC distribution panel and does not adversely affect the function of the Non-1 E Aux Power system to distribute power to non-safety related loads.

The new monitor skid requires a supply of demineralized water for manual flushing of the skid. The change does not adversely affect the function of the system to supply water for the waste disposal system.

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The proposed activity adds combustible material in the form of cable insulation in Turbine Building Fire Zones.

The amount of added combustible is small and does not adversely impact the fire protection features for the affected zones. There is no adverse affect on Safe Shutdown systems.

The activity does not affect any design basis limit for fission product barrier because no SSCs are modified that pertain to fuel cladding, the reactor coolant system pressure boundary, or primary containment.

Based on the above, the proposed activity does not involve a change to any SSC that adversely affects a UFSAR described design function, and does not involve a change to any design basis limit for a fission product barrier.

2. Does the proposed Activity involve a change to a procedure that adversely affects how UFSAR described SSC design functions are performed or controlled? (See Section 5.2.2.2 of the RM)

El Yes Z No The proposed activity introduces a new liquid effluent radiation monitor which affects Operating, Chemistry, and Maintenance procedures. Operating interface with the control room RM-1 1 computer network is affected and PR skid lineup procedures are affected. Chemistry Department release control procedures will be affected such that the release tanks are separately monitored. Also, the ODCM is affected to incorporate the new monitor. New Maintenance calibration procedures must be developed unique to the new skid. The procedures are revised to incorporate the new monitor to the same controls and criteria as the existing monitor OPRO1J. The affected procedures are implied in the UFSAR as controls for releases to the environment. The affected procedures will continue to implement the Liquid Radwaste Effluent monitoring functions as described in the UFSAR. Therefore, the proposed activity does not adversely affect how any UFSAR described SSC design functions are performed or controlled.

3. Does the proposed Activity involve an adverse change to an elements of a UFSAR described evaluation methodology, or use of an alternative evaluation methodology, that is used in establishing the design bases or used in the safety analyses? (See Section 5.2.2.3 of the RM).

EZ Yes Z No With the addition of another radiation monitor, the methodology for tank sampling, tank content analysis, or calculation of volume is not changed. The methodology of analysis of the monitor's loading impact on the Turbine Building Structure is not changed.

No calculations, analysis, or other evaluation methodology explicitly or implicitly stated in the UFSAR are adversely affected by the proposed activity.

4. Does the proposed Activity involve a test or experiment not described in the UFSAR, where an SSC utilized or controlled in a manner that is outside the reference bounds of the design for that SSC or is inconsistent with analyses or descriptions in the UFSAR? (See Section 5.2.2.4 of the RM)

El Yes Z No The proposed activity adds a radiation monitor into the Liquid Radwaste system that provides operating flexibility for releasing effluent. The release paths are unchanged by this activity. Tank effluent testing is unchanged.

The required testing associated with this change is post-modification testing of valve interlocks and monitor communication with the RM-1 1 system in the control room.

Testing/calibration of the new monitor will be to the equivalent criteria as for existing liquid effluent radiation monitors. Post-modification testing of revised valve control circuits and interlocks is performed to prove that high radiation detected in an unisolated release path will auto-close release valves 0WX353 and 0WX896, which is UFSAR criteria. Thus, the proposed activity does not involve a test or experiment not described in the UFSAR, and it does not utilize an SSC outside the reference bounds of the plant design.

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5. Does the proposed Activity require a change to the Technical Specifications or Facility Operating License? (See Section 5.2.2.5 of the RM) n Yes M No This activity adds a new radiation monitor for liquid effluent monitoring as controlled by the ODCM. Tech Spec Section 5.5.1 that describes the Offsite Dose Calculation Manual (ODCM) program is unchanged.

Tech Spec Section 5.5.4 that describes the Radioactive Effluent Controls Program is unchanged. This activity does not affect the contents of any release tank and thus does not affect the NPDES Permit.

Thus, this activity does not require a change to the Technical Specifications or Operating License.

IIL List the documents (e.g., UFSAR, Technical Specifications, other licensing basis, technical, commitments, etc.) reviewed, including sections numbers where relevant information was found (if not identified in the response to each question).

UFSAR Sections 7.7.1.17 Process Radiation Monitoring Instruments and Control 7.7.1.19 Liquid Radwaste System Instruments and Controls 8.3.1.1.1 Auxiliary Power System Non-1 E Distribution 9.2.3 Demineralized Water Makeup System 11.5 PROCESS AND EFFLUENT RADIOLOGICAL MONITORING AND SAMPLING SYSTEMS 11.5.2.3.1 Liquid Radwaste Effluent Monitor Table 3.2-1 Safety Category and Quality Group Classification for Structures and Components Table 11.5-2 Process Liquid Monitors Technical Specifications & Bases Offsite Dose Calculation Manual (ODCM)

NPDES Permit Technical Requirements Manual (BRW-TRM) Latest Revision in EDMS 3.3.p Radiation Monitoring Instrumentation Appendix A ODCM and Radiological Controls Reports and Program Appendix D Radioactive Effluent Controls Program UFSAR Change Log - Effective UFSAR Changes Reviewed, not affected. This activity will require a change to the UFSAR Table 11.5-2 and Section 11.5.2.3.1 DRP 13-052 tracks the update.

III. Select the appropriate conditions:

[ If all questions are answered NO, then a 50.59 Evaluation is not required.

E If question 1, 2, 3, or 4 is answered YES for any portion of an Activity and question 5 is answered NO, then a 50.59 Evaluation shall be performed for the affected portion of the Activity.

El Ifquestion 5 is answered YES for any portion of an Activity and questions 1 through 4 are answered NO for the remaining portions of the Activity, then a License Amendment is required prior to implementation of the portion of the Activity that requires the amendment; however, a 50.59 Evaluation is not required for the remaining portions of the Activity.

LI Ifquestion 5 is answered YES for any portion of an Activity and question 1, 2, 3, or 4 is answered YES for any of the remaining portions of the Activity, then a License Amendment is required prior to implementation of the portion of the Activity that requires the amendment and a 50.59 Evaluation is required for the remaining affected portions of the Activity.

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IV. Screening Signoffs:

The 10CFR50.59 screening has been approved by the Site's Qualified Screening Process on 11/4/10.

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ATTACHMENT 4 Supporting Documentation of Engineering Change 362453 149 of 238

EC 362453 The design attributes addressed in this document are those identified in Attachment 1, "Design Change Attribute Review", of procedure CC-AA-102 and are numbered accordingly.

Background - Blowdown of processed liquid radioactive waste is being re-evaluated to optimize the release process at Braidwood. Recycling processes have been introduced to reduce the volume of processed water to be returned to the river. This reduces the amount of blowdown to the river. Diffusers are being added to the discharge into the river to provide more complete dilution of tritium in the river (EC 375871, EC 375872 and EC 375873). Release to the river through the low-low flow controlled path, via control valve 0WX302, is planned with a blowdown rate of 0.5 gpm to 20 gpm to provide for additional operation flexibility while limiting release flows below procedurally controlled maximum limits. The plant original blowdown system was designed to release and monitor blowdown flows up to 500 gpm based on Release Tank Pump capacity. The current low-low flow release line design, installed under previous revisions of EC 362453, provides a flow rate between 0.5 and 5 gpm. The existing low-low flow regulating equipment must be modified to allow for measurement and control over the new range (0.5 gpm to 20 gpm) of flow rates. In order to control and monitor blowdown at these low-low rates, the current low-low flow blowdown control valve and associated piping will be replaced with a larger (1") valve (including the new actuator) and associated piping. The flow element will be replaced with a larger diameter flow element to allow for more accurate monitoring of the blowdown flow on the 0.5 to 20 gpm range. The existing control components (e.g., flow indicator, recorder, integrator, etc.) will be used with the new valve with the exception that OWX302 control valve limit switches will be replaced. The new valve will have the same operating method and failure position as the existing valve. The indicator, recorder controller, and computer point ranges will be re-scaled for a larger flow range (0 to 30 gpm).

4.1.4.1 Basic System Functions This equipment forms a control loop that regulates the flow rate of processed primary system letdown after it has been monitored and accepted for release in the WX release tanks (OWX01T and OWX26T). The flow rate is set manually at the flow controller OFC-WX001 located in panel 1PA20JB. The flow is measured by OFE-WX001 and OFT-WX001 and the difference between the flow and the set point produces a valve position signal. The valve position signal is converted from a current signal to a pressure signal by OIY-WX001. Currently this signal is connected directly to the valve actuator. Valve 0WX353 provides isolation of flow in this line and automatically closes on high radiation.

4.1.4.2 Configuration Change Safety Classification The Solid Radwaste Reprocessing and Disposal (WX) System is considered a Safety Category II (Non-Safety Related), Quality Group D system as identified in UFSAR Table 3.2.1. The WX system does not perform any safety related function, is not required for safe shutdown of the plant and is not credited in any accident analysis.

Therefore, this EC is classified as Non-Safety Related.

4.1.4.3 Seismic Classification The WX System is classified as Seismic Category II as identified in UFSAR Table 3.2.1, therefore the associated components will be Seismic Category II components.

4.1.5 Performance Requirements and Design Conditions Prior to modification EC 362453, Rev. 000, the blowdown release line was designed for a discharge up to 500 gpm. The full flow blowdown valve and flow measuring devices were replaced with a low-low flow control valve and flow measuring devices for a design flow rate of 0.5 to 5 gpm. After implementation of this modification (EC 362453, Rev. 005) the low flow blowdown through the release line will be increased to 0.5 to 20 gpm. The associated instrumentation is being calibrated to read flows in the range of 0 to 30 gpm.

The design conditions are determined by the WX release tank pump head. The design conditions are 75 psig at 120 0F.

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4.1.6 Surveillance and Acceptance Testinq There are no surveillance tests associated with this non-safety related control valve and associated piping. Form CC-AA-107, Attachment 1 for this EC provides the testing requirements for this modification.

4.1.7 Codes, Standards, and Regulatory Requirements The codes, standards and regulatory requirements that apply to this work are listed in the Work Planning Instructions (WPI), CC-AA-103, Attachment C for this EC.

The new 50.59 screening BRW-S-2010-43 supersedes Rev. 1 of BRW-S-2007-159 and supplements Rev. 0 of BRW-S-2007-159 performed in the previous revisions 4.1.9 Calculations and Design Analysis The original 6" WX pipe was analyzed as part of subsystem 1CW 14. This analysis was revised to incorporate the piping size changes in EC 362453 Rev. 000. This analysis is being revised as part of EC 362453 Rev. 005.

Impacted Design Analysis (031203 Rev. 002B) is identified in the ADL of this EC.

Hydraulic calculation (BRW-10-0030-M) was prepared to document upstream and downstream pressure for flow control valve 0WX302 and the fluid flow velocity in the release path. This calculation is identified in the ADL of this EC. See discussion regarding this analysis in the Revision Summary Notes Topic.

4.1.13 Material Requirements Equipment and materials associated with this modification are classified as non-safety-related and are included in the ECML for this EC package.

Material requirements are specified in the applicable drawing included in the ADL. The ECML is not a complete list of the required parts. Standard required materials shall be identified, as applicable, during work planning and work package preparation activities.

Material specified for this EC is based on the applicable Piping Design Tables (PDTs) and they are suitable for this application.

4.1.14 Environmental Conditions and Environmental Impacts This EC has been reviewed in accordance with EN-AA-103 and no environmental condition changes or impacts have been identified. This EC is associated with providing a flow path for releases and does not authorize or control radioactive waste releases.

4.1.15 Environmental Qualification of Equipment Based on CC-AA-102, Attachment 3, EQ Screening Considerations and Checklist no Environmental qualifications are required.

4.1.16 Operating Experience Searches of INPO's operating experience and SER/SOER data base was performed in accordance with LS-AA-115 and did not result in anything germane to AOVs used in liquid radwaste systems. The operating experience on AOV's that leaked or failed to operate in critical service were too many to list. However, there was no trend on Fisher Baumann valves globe style valves. Therefore, the results of the industry operating experience review are not applicable to this modification.

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4.1.19 Operational Requirement Change The maximum flow through the alternate low flow release line has changed from 5 gpm to 20 gpm when valve 0WX302 is opened. The scale on the flow controller has been recalibrated to accommodate the increased flow requirement. The flow through the existing low flow line (0WX897) remains unchanged. The releases from the 0WX01T and OWX26T release tanks are assessed and controlled via procedures BwOP WX-526T1 "Liquid Release Tank OWX26T Release Form" and BwOP WX-501T1 "Liquid Release Tank 0WX01T Release Form".

These procedures limit the maximum effluent discharge rate from the release tanks to 50 gpm. The change in release tank blowdown control valve 0WX302 capacity from 0.5 - >5 gpm to 0.5 - >20 gpm will maintain maximum release rates within established procedural limits. See CC-AA-102 Attachment 9 for procedures that require revisions due to this EC.

4.1.20 Human Factors Requirements Human interface devices are not replaced or relocated within this change package. The scale of flow indicators, recorders and controllers are revised to maintain the expected flow at the same fraction of full scale as it is prior to the change. Control Room and remote shutdown panels are not affected.

4.1.21 Procedure Changes Operating procedures requiring revision are listed in CC-AA-102 Attachment 9 and the ADL These procedures define the steps to be taken to release liquids from the Liquid Release Tanks (OWX01T and OWX26T). The procedures provide release volumes and flow rates that are to be maintained. The flow rates are revised by this EC. This revision of the EC provides for a low flow release path that can control releases at higher flow rates than are currently possible, but does not authorize or control radioactive waste releases, which are controlled in accordance with CY-AA-170-200. The revised ultra low flow releases remains less than the original flow releases (500 gpm) through the same release path.

Operating Procedure BwAR OPL01J-7-B9, Rev 53 shall be revised to reflect the elimination of the High Flow Path. The recommended set point of the new Ultra Low Flow Path high flow alarm is 22.2 (Ref. OFSH-WX001).

4.1.22 Additional Training Requirements Training requirements are identified in CC-AA-102 Attachment 9.

4.1.23 System Interfaces The alternate low flow liquid release line is part of the WX system. It interfaces with the CW system to provide dilution flow and a path to release fluids to the river. This revision of the EC increases the size of the low flow release line flow control valve (0WX302) to the CW system. The revised flow through the alternate low flow release line is larger than then the current low flow through this release line. It also interfaces with Instrument Air (IA) system. The tubing from the replaced flow element, the air signal to the valve and the instrument air supply to the valve's positioner will be field routed.

4.1.24 Layout and Arrangement Requirements This revision of the EC replaces the flow control valve, flow element and associated piping with larger components and piping. It also relocates the flow element by approximately 6" south from its current location.

The piping and component layout is shown on the physical drawings referenced in the ADL.

4.1.25 Radiation Protection/ALARA This EC has been screened in accordance with CC-AA-102 Attachment 5. This EC modifies the release line which is a portion of the WX system. Therefore, ALARA is applicable. However, the radiation levels in this line are minimal and the fluid is suitable to release off-site. There is no measurable dose from this line. The flow control equipment is not located in a radiation area. The modification to the minimum flow recirculation line is in the Release Tank Pump Room. The fluid in this line has passed through demineralizers and filters in the WX system and does not contain contamination that could build up as CRUD in the piping.

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4.1.26 Walkdowns A designer's walkdown determined that there is sufficient room in the area to perform the configuration changes required in this revision of the EC.

A walkdown report in accordance with CC-AA-106-1001, Attachment 2 is included in this EC.

4.1.27 Access for Maintenance, Repair, ISI and IST The flow control valve is covered by the AOV PCM template. There is sufficient room around the flow control valve (0WX302) to connect diagnostic equipment or to disassemble the valve for repair.

4.1.29 Emergency Plan and Environmental Impact This modification increases the size of the existing control valve and piping used for planned release of processed liquid from the site. The original 4" flow control valve in the 6" size piping (before EC 362453 modification) allowed larger release flow rate (up to 500 gpm) than the revised low flow control valve (current release flow rate up to 5 gpm). This modification will increase the release flow rate to a maximum of 20 gpm.

The maximum possible off site release rate is not changed. The liquid is monitored prior to entering the release tank. It is also sampled during the release. This modification does not change any of the monitoring equipment or functions. The discharge rate is under manual control during planned releases. This modification does not affect the offsite release of radiation during postulated accidents. This EC provides for an alternate low flow path and does not control or authorize radioactive waste releases.

4.1.33 Mechanical System Characteristics EC 362453, Rev. 007 piping is non-ASME and non-safety related, located in Unit 2 Turbine Building. The original piping was computer analyzed in subsystem 1CW14; therefore, the revised piping was also computer analyzed. The design analysis in the ADL for this EC captures the impacted portion of piping in this revision of the EC. This is a moderate energy line in the non-safety related building; no line break analyses are affected.

This piping transports water at ambient temperatures and low pressures. There are no significant stress changes to cause fatigue in the pipe. Due to concerns regarding potential transients in the CW blowdown line, this line is analyzed for 1" of displacement at the connection to the CW line for additional conservatism. The pipe in the modified area is also analyzed for acceleration of 0.5 g's in two directions to address potential operational vibratory loads. There are no postulated transients in the WX system. Pipe supports (guides) have been designed to address these potential vibratory loads during operation (Design Analysis 031203, Rev. 002B).

Fouling and corrosion have been considered for this EC. The piping size for this release line is increased in the proximity of the control valve. The flow velocity will remain below 10 fps in these stainless steel lines. Flow Induced Corrosion will not be a concern. The water transported through this line is demineralized water in stainless steel systems. There should be no source of sediment or corrosion products. This EC does not create dead ends that would be susceptible to Micro Induced Corrosion. The lines are stainless steel and are not susceptible to corrosion by demineralized water. The control valve was specified and reviewed to ensure that valve cavitation would not be present to cause pipe erosion. CC-AA-107, Attachment 1 requires an assessment of potential cavitations during testing.

ORX-PRO01 Liquid Radwaste Probe supplies Liquid Radwaste Effluent Radiation Monitor/Detector ORE-PROO1.

Review of the current PASSPORT Equipment Data for ORX-PRO0t indicates that Parameter "Process Flow Max" provides a range of a max flow of 600 GPM and a min flow of 130 GPM. The minimum flow of 130 GPM will not be met when the flow path provided by this EC is used. Note that Operating procedures BwOP WX-501T1, Rev. 57, and BwOP WX-526T1, Rev. 58 have limited the release flow rate to 50 gpm. IR 1043521 has addressed this condition and concluded that the ORX-PRO01 130 gpm flow rate limitation is deemed unnecessary. Probe ORX-PRO01 is located less than 50 ft away from the discharge of release pumps OWX01 P and OWX53P. Therefore adequate mixing is generated by the pump impellers and the use of the probe to ensure that the sample to the PR skid is representative based on flow rate requirements is deemed unnecessary. The General Atomic Letter included in the Technical Eval Topic of the EC evaluates mixing based on turbulent flow criteria to address potential flow requirements and need for a sampling probe for the new Radiation Monitor skid that is being installed in accordance with EC 378192. Since turbulent flow conditions are an indication of sufficient flow mixing, the basis for the ability of the radiation monitor skid to receive a representative sample is the fact that the probe is in the proximity and downstream of the release pumps.

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It should be noted that a sample probe is not relied upon to provide sufficient flow through the Liquid Radwaste Effluent Radiation Monitor/Detector ORE-PROO. The system is designed to use pump discharge pressure and the flow control valve to develop a driving head through the rad monitor. Lower release flow will increase this driving head and therefore low sample flows are not anticipated due to low release flow. If low sample flow were to occur (less than 1 gpm in flow indicator OFIS-PR173, Ref. Test Report Package OR-PROO) the low flow condition will be detected/alarmed.

The EPN record for ORX-PRO01 will be revised to provide this explanation regarding flow requirements in the "Process Flow Max" parameter notes.

Previous revisions to this EC sized the recirculation line and restricting orifices to maintain a safe minimum flow for the pump when the blowdown of the low flow line was 0 - 5 gpm. This revision increases the maximum flow of blowdown to 20 gpm. No additional changes are required for the recirculation line and restricting orifices due to the increased blowdown flow rate due to the conservative nature of the blowdown flow rate change with regard to the recirculation line. Pump run out for the ultra low flow path is not a concern since the pumps were designed for higher flow rates in excess of 500 gpm.

4.1.35 Electrical Requirements The existing valve limit switches will be replaced with Topworx Go Switch to provide more sensitive monitoring of the valve position. The existing flexible conduits and cables (reworked under EC 362453 prior to Rev. 005) may be re-used or replaced to reach the replacement switches. The new limit switches are SPDT with a normally open and a normally closed contact. The limit switches include a pigtail with four (4) conductors. Normally open, normally closed, common, and ground. The ground conductor will be terminated to the junction box metal of 1JB1 18T. The limit switch contacts will be wired to provide the same valve status indication as the existing limit switches. When the valve is fully open, the valve open indicating light will be lit, and the valve closed indicating light will be off. When the valve is fully closed, the valve closed indicating light will be lit, and the valve open indicating light will be off. When the valve is in transition (not fully open or not fully closed) both the open and closed valve indicating lights will be lit.

4.1.36 Instrument and Control Requirements EC 362453 Rev. 5 changes the control and measurement range of the flow in the release line. The existing control components will remain the same. A new flow element will be installed to accurately measure the increased flow in the larger one inch line from 0 to 30 GPM. The flow element is located such that there is adequate upstream and downstream straight pipe to prevent flow disturbances from affecting the accuracy of the flow reading. See Panel TIMD071 for OFE-WX001 in Passport for the updated flow element parameters. The differential pressure across the new flow element will change from the existing 0 to 400 in wc to approximately 0 to 100 in wc (Reference, revision summary Notes Topic).

The flow control loop will be recalibrated for a range 0 to 30 gpm. The existing flow transmitter will be recalibrated for a measured differential pressure of 0 to 200 in wc with an output of 0 to 20 mA equivalent to a flow of 0 to 30 gpm. The flow recorder OFR-WX630 on OPL01J will be rescaled and calibrated to match the output of the transmitter a full flow of 30 gpm to accommodate the lower design flow. The calibration factor and counts per hour for the linear indicator OFQ-WX001, and totalizing indicators OFQI-WX001A and B on OPLO1J will be revised to accurately measure the required counts/minute for the new flow range. The setpoint for analog comparator OFSH-WX001 will be revised to be compatible with the new flow range.

The setpoint voltage for flow controller OFC-WX001 will remain the same. With the new flow range of 0 to 30 gpm, this will be equivalent to approximately 15 gpm. The scale on computer point F0001A will also be revised to accommodate the new flow rate of 0 to 30 gpm. The control signal from the auto driver OFY-WX001 E is 4 - 20 mA. This is the required input range for the positioner on the valve. The control cable that went to the I/P will be extended to connect to the positioner on the valve. The instrument air line required for the positioner shall be field routed from the existing instrument air connection to the new I/P location.

See additional discussion of the I&C considerations in the revision summary Notes Topic.

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4.1.38 Civil/Structural The impacted pipe supports are located in the Unit 2 Turbine Building and are classified as non-safety related and non-seismic, with no Category II over Category I interaction concerns. The impacted piping subsystem, 1CW 14, was analyzed for loads from weight plus thermal plus 0.5g Seismic. The load for 0.5g Seismic was included in the piping analysis for conservatism to account for vibration concerns. However, it is not considered as a Design Basis Load (Design Analysis 031203, Rev. 002B). The original support qualifications are documented in Calculation 14.1.12-BRW-07-0009-S.

The stress analysis for EC 362453 Rev. 005 changes did not result in higher loads than the loads utilized for the supports qualification in calculation 14.1.12-BRW-07-0009-S. The support locations and/or support structural members are not changed other than the u-bolts have been replaced to accommodate larger size pipe. This will require additional hole drilled in the structural member. However, this change will not adversely affect the carrying capacity of the supports.

4.1.42 Interfacing Department Review See PASSPORT milestones and Attributes for Interfacing Department reviews.

4.4 Configuration Control Activities Configuration Control Activities (if required) are identified in CC-AA-102, Attachment 7.

4.5 Program Impact Program impact (if required) is identified in CC-AA-102, Attachment 8 155 of 238

10CFR50.59 screening for EC 362453 50.59 Screening Questions (Check correct response and provide separate written response providing the basis for the answer to each question) (See Section 5 of the Resource Manual (RM) for additional guidance):

Does the proposed Activity involve a change to an SSC that adversely affects an UFSAR described design function? (See Section 5.2.2.1 of the RM)

M Yes M No EC 362453 Rev. 005 allows for replacement of the existing /2" size liquid radwaste release tank blowdown control valve, 0WX302, and associated '/2" size piping and 1/2" pipe sized flow element (OFE-WX001) installed in previous revisions of EC 362453 with a 1" size control valve (with actuator and limit switches) and associated 1" size piping and 1" pipe sized flow element to increase blowdown control rate from 0.5 - >5 gpm to 0.5 - >20 gpm. The existing controls components will be used on the new valve, however, the flow indicator, recorder, integrator and computer points are being rescaled and recalibrated to a span of 0 to 30 gpm to envelope the larger flow range and the valve limit switches will be replaced.

Pipe support changes will be needed to accommodate the larger/heavier valve. The new valve will have the same operating method and failure position as the replaced valve.

The function of the liquid waste system (WX) to collect, monitor, recycle or release potentially radioactive liquid wastes, as described in UFSAR Section 11.2 " Liquid Waste Management Systems" of the UFSAR is not impacted by this proposed change. Potentially radioactive releases from Release Tanks OWX01T and OWX26T will continue to be sampled and monitored and releases controlled to ensure that radioactive releases are within Technical Specification requirements as discussed in Sections 11.2.1.1, 11.2.1.3, 11.2.1.10, 11.2.2.3 and 11.2.3 of the UFSAR. The modified components have been designed in accordance with the original design criteria and the liquid radwaste system continues to be capable of processing maximum expected liquid waste inputs as a result of normal operation, including anticipated abnormal occurrences for Units 1 and 2. UFSAR Table 11.2-4 "Comparison of Expected Liquid Effluent Concentration tol OCFR20 Limits (Braidwood) and Table 11.2-5 "Liquid Radwaste System Components and Design Parameters per Station" are not impacted by the changes proposed by EC 362453 Rev. 005.

Following implementation of this change, liquid Radwaste System releases will continue to be performed on a batch basis with release rates from the Release Tanks determined by Station Operating procedures including BwOP WX-526T1 and BwOP WX-501T1.

The interface between the WX system and Circulating Water (CW) system which functions to maintain water chemistry by continuous makeup from and blowdown to the Kankakee River is not impacted by this change (UFSAR Section 10.4.5).

The interface between the WX system and Instrument Air (IA) system which functions to provide dry, oil-free compressed air for both nonessential and essential components and instruments as described in UFSAR Section 9.3.1, is not impacted by this activity.

The monitoring of liquid effluents as described in UFSAR Section 11.5.2.3.1 "Liquid Radwaste Effluent Monitor" is not affected by this change.

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The function of "Liquid Radwaste System Instruments and Controls", as described in UFSAR Section 7.7.1.19 is not affected by this change.

The changes being implemented by EC 362453 Rev. 005 meet the requirements of Regulatory Guide 1.143, Design Guidance for Radioactive Waste Management Systems, Structures and Components Installed in Light-Water-Cooled Nuclear Power Plants referenced in UFSAR Appendix Al.143.

The supporting of the replacement control valve including the new configuration of associated piping, supports, and components have been evaluated and have been found to be acceptable.

The WX, CW (considered a part of the Raw Water system) and IA systems are considered Safety Category II (non-safety related), Quality Group D systems as identified in UFSAR Table 3.2-1. The WX,CW and IA systems do not perform any safety function and are not required for safe shutdown of the plant and are not credited in any accident analyses.

Based on the above, the proposed activities do not involve a change to an SSC that adversely affects an UFSAR described design function.

2. Does the proposed Activity involve a change to a procedure that adversely affects how UFSAR described SSC design functions are performed or controlled? (See Section 5.2.2.2 of the RM)

El Yes 0 No The procedures utilized to monitor and control effluent discharge from the release tanks, as described in UFSAR Section 11.2.2.3 "Operating Procedures" are not impacted by the introduction of the revised effluent flow rate capability. Potentially radioactive releases from Release Tanks OWX01T and OWX26T will continue to be sampled and monitored and release controlled to ensure that radioactive releases are within acceptable limits in accordance with station procedures. Specifically, Liquid radwaste is governed by a programs and procedures including CY-AA-170-000 "Radioactive Effluent and Environmental Monitoring Programs", CY-AA-170-200 "Radioactive Effluent Controls Program" and CY-BR-170-301 "Offsite Dose Calculation Manual (ODCM)". The releases from the OWX01T and OWX26T release tanks are assessed and controlled via BwOP WX-526T1, "Liquid Release Tank OWX26T Release Form" and BwOP WX-501T1, "Liquid Release Tank OWX01T Release Form". These procedures limit the maximum effluent discharge rate from the release tanks to 50 gpm. The change in release tank blowdown control valve 0WX302 capacity from 0.5 - >5 gpm to 0.5 - >20 gpm will maintain maximum release rates within established procedural limits.

Therefore, replacement of release tank blowdown control valve 0WX302 and associated components, and the increase in valve flow capacity from 0.5 - >5 gpm to 0.5 - >20 gpm will not change an existing procedure or create a new procedure that adversely affects how UFSAR described SSC design functions are performed or controlled.

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3. Does the proposed Activity involve an adverse change to an elements of a UFSAR described evaluation methodology, or use of an alternative evaluation methodology, that is used in establishing the design bases or used in the safety analyses? (See Section 5.2.2.3 of the RM).

El Yes Z No The systems and components being modified are not credited in any UFSAR safety analysis. This activity does not change the effluent monitoring process or methodology including the effluent monitoring as described in the UFSAR. This activity involves hardware changes to a release path in order to allow better flexibility and control at low release rates from the OWX01T and 0WX26T release tanks. The modified system is evaluated in accordance with the original design criteria. The computer program (PIPSYS) utilized to analyze the piping has been documented for use in UFSAR Appendix D.8.1. No new methodology was used in determining the adequacy of the configuration of associated piping, supports, and components. There are no changes to the evaluation methodology of liquid releases as a result of this EC. There are no changes to the performance characteristics or design functions of any SSC that results in adverse changes to an element of a UFSAR described evaluation methodology. The subject activities do not introduce or use an alternative evaluation methodology that is used in establishing the design bases or used in the safety analyses.

4. Does the proposed Activity involve a test or experiment not described in the UFSAR, where an SSC utilized or controlled in a manner that is outside the reference bounds of the design for that SSC or is inconsistent with analyses or descriptions in the UFSAR? (See Section 5.2.2.4 of the RM)

ED Yes ZNo This activity replaces control valve hardware in the existing flow path from the release tanks to CW blowdown interface. The modified WX system components will be tested in accordance with the requirements of the applicable construction codes and approved procedures to ensure the modified system continues to meet its performance requirements and design functions. The testing requirements associated with this activity does not utilize or control an SSC of the WX system or supporting CW and IA systems in a manner that is outside the reference bounds of the design for the associated SSCs as described in the UFSAR. The design function of the WX system and supporting CW and IA systems is not altered as a result of the subject activities and no experiments are performed.

5. Does the proposed Activity require a change to the Technical Specifications or Facility Operating License? (See Section 5.2.2.5 of the RM)

El Yes 0 No No changes to the Technical Specifications or Operating License are required.

The effluent line flow rate is not a parameter in the Technical Specifications or Operating License. TS Section 5.5.1 requires that the offsite releases be controlled by the ODCM. TS Section 5.5.4 describes the radioactive effluent controls program. TS Section 5.6 describes effluent report requirements. TRM 5.2 "Procedures and Programs" describes requirements regarding Process Control Programs including:

In-Plant Radiation Monitoring, Radiological Environmental Monitoring Program, Radiation Protection Programs and ODCM. None of these aforementioned documents define a specific release tank blowdown flow rate. The releases from the OWX01T and OWX26T release tanks will continue to be assessed and controlled via BwOP WX-526T1, "Liquid Release Tank OWX26T Release Form" and BwOP WX-501T1, "Liquid Release Tank OWX01T Release Form" to ensure that releases are in compliance with 10CFR20, 10CFR50 and NPDES permit limitations.

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II. List the documents (e.g., UFSAR, Technical Specifications, other licensing basis, technical, commitments, etc.) reviewed, including sections numbers where relevant information was found (if not identified in the response to each question).

UFSAR Sections 3.2 CLASSIFICATION OF STRUCTURES, COMPONENTS, AND SYSTEMS 3.2.2 Quality Group Classification Table 3.2-1 Safety Category and Quality Group Classification for Structures and Component 7.7 CONTROL SYSTEMS NOT REQUIRED FOR SAFETY 7.7.1.19 Liquid Radwaste System Instruments and Controls 9.3 PROCESS AUXILIARIES 9.3.1 Compressed Air Systems 10.4 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4.5 Circulating Water System 11.2 LIQUID WASTE MANAGEMENT SYSTEMS 11.2.1.1 Safety Design Basis 11.2.1.3 Expected Radioactive Releases 11.2.1.10 Prevention of Uncontrolled Releases 11.2.2.3 Operating Procedures 11.2.3 Radioactive Releases Table 11.2-4 Comparison of Expected Liquid Effluent Concentrations to 10 CFR 20 Limits Table 11.2-5 Liquid Radwaste System Components and Design Parameters Per Station 11.5 PROCESS AND EFFUENT RADIOLOGICAL MONITORING AND SAMPLING SYSTEMS 11.5.2.3.1 Liquid Radwaste Effluent Monitor App Al.143 Regulatory Guide 1.143, "Design Guidance for Radioactive Waste Management Systems, Structures and Components Installed in Light-Water-Cooled Nuclear Power Plants" App D.8 Piping Analysis Programs Technical Specifications & Bases 5.5.1 Offsite Dose Calculation Manual (ODCM) 5.5.4 Radioactive Effluent Controls Program 5.6 Reporting Requirements Technical Requirements Manual (BRW-TRM) Latest Revision in EDMS 5.2 Procedures and Programs Pending UFSAR Change Logq Exelon Procedures CY-AA-170-000, Radioactive Effluent and Environmental Monitoring Programs CY-AA-170-200, Radioactive Effluent Controls Program CY-BR-170-301, Offsite Dose Calculation Manual (ODCM)

BwOP WX-501T1, Liquid Release Tank 0WX01T Release Form BwOP WX-526T1, Liquid Release Tank OWX26T Release Form 50.59 Screenings:

BWR-S-2007-159 R/O BWR-S-2007-159 R/1 159 of 238

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2011 UNIT 1 AND 2 (Docket Numbers 50-456 and 50-457)

III. Select the appropriate conditions:

0 Ifall questions are answered NO, then a 50.59 Evaluation is not required.

El Ifquestion 1, 2, 3, or 4 is answered YES for any portion of an Activity and question 5 is answered NO, then a 50.59 Evaluation shall be performed for the affected portion of the Activity.

LI Ifquestion 5 is answered YES for any portion of an Activity and questions 1 through 4 are answered NO for the remaining portions of the Activity, then a License Amendment is required prior to implementation of the portion of the Activity that requires the amendment; however, a 50.59 Evaluation is not required for the remaining portions of the Activity.

LI Ifquestion 5 is answered YES for any portion of an Activity and question 1, 2, 3, or 4 is answered YES for any of the remaining portions of the Activity, then a License Amendment is required prior to implementation of the portion of the Activity that requires the amendment and a 50.59 Evaluation is required for the remaining affected portions of the Activity.

IV. Screening Signoffs:

The 10CFR50.59 screening has been approved by the Site's Qualified Screening Process on 10/6/11.

160 of 238

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2011 UNIT 1 AND 2 (Docket Numbers 50-456 and 50-457)

ATTACHMENT 5 EVALUATION OF EFFLUENT RELEASE RATES INCORPORATING A PROPOSED RIVER DIFFUSER SYSTEM AT BRAINDWOOD STATION 161 of 238

' ChemStaff Evaluation of the Liquid Effluent Release Practices Incorporating a Proposed River Diffuser System at Braidwood Station

==

Introduction:==

Since tritium cannot be easily separated from water, tritium management requires long range planning and consideration in most liquid effluent optimization decisions. Programmatic extremes such as releasing all plant liquid or zero liquid release without considering all impacts will likely cause unintended consequences. A zero release strategy will eventually result in elevated tritium concentrations in plant systems, requiring potentially extensive personnel monitoring programs. In addition, evaporative losses will result in increased tritium releases via gaseous pathways. Tritium releases as water vapor via gaseous pathways have a high probability of deposition on site or near the site boundary.

The station produces approximately 2000 to 2400 Curies of tritium on an annual average. This report uses tritium mass balance and a tritium management models to project how program changes might affect long-term in-plant and liquid effluent tritium levels and is based on a typical dual outage calendar year to demonstrate seasonal and operational effects. The liquid effluent program is governed by guidance found in the Braidwood Station Offsite Dose Calculation Manual. The Offsite Dose Calculation Manual (ODCM) presents a discussion of the following:

" The basic concepts applied in calculating offsite doses from nuclear plant effluents.

" The regulations and requirements for the ODCM and related programs.

" The methodology and parameters for the offsite dose calculations used by the nuclear power stations to assess impact on the environment and compliance with regulations.

It has been a past station practice to release liquid effluent at a rate ranging from 50 gallons per minute up to 450 gallons per minute which was allowed by plant design. Releases had been completed typically in two to six hours to a side-stream discharge design at the Kankakee River. This design is able to achieve only approximately 25% mixing with total river flow which resulted in a short duration plume with instantaneous tritium concentration down stream calculated to range from 103 to 150,233 pCi/L.

Historical River Tritium Concentrations (calendar year 2004)

S00 450 400T 350 2504 200 150 50 1 ,0 1c I I I. . . .

162 of 238

Historical River Tritium Concentrations (calendar year 2004) 160000 140000

[20000 j 100000 80000 60000 S40000 20000 0 1 .14 -, - Uq . pas

..... - ý .

// lelofIef1/ 141 This evaluation will assess the plants ability to release liquid effluents at a rate that will yield the target tritium concentrations, calculate the amount of tritium that will be released by meeting these target concentrations, and calculate the overall tritium balance within the plant as a result of meeting the target tritium concentrations. The goal is to determine the ideal target river concentration and the resulting effects on the current operational practices including recycle and feed and bleed, as well as the effect on proposed disposal options including solidification and offsite disposal.

The proposed river diffusion system in combination with the ultra-low flow release tank regulator 362453 installed in 2007 would significantly alter the station's liquid effluent release practice by achieving greater river flow mixing and regulated low flow release rates. The practice would effectively regulate liquid effluent release rates based on maintaining a constant river concentration well under Federal limits at all times thereby minimizing impacts down stream of the station.

The basis for river dilution characteristics is from the Tritium Dilution Analysis Report (EXCE003) prepared by HydroQual Environmental Engineers and Scientists in February 2009. This effort was to determine allowable tritium discharge concentrations from the Exelon Braidwood Nuclear facility that meet downstream tritium targets at the Wilmington Dam of 200, 400, 600, 800 and 1,000 pCi/L. Three alternative discharge scenarios were assessed which included 3-port submerged diffuser, 5-port submerged diffuser, and 7-port submerged diffuser.

163 of 238

Summary:

The goal of this evaluation was to evaluate liquid effluent release rates controlled to maintain down stream river concentrations at specific target values well below federal limits at all times and the resulting impact to the overall tritium balance in the plant. To maintain a balance between total liquid effluent volume and total tritium curies generated, the station has employed or proposed to employ a combination of tritium effluent management options including release, recycle, and solidification/disposal. The results, which are further detailed in this report, indicate that setting an environmentally conscious minimum river tritium concentration goal down stream of the diffuser of approximately 600 pCi/L will achieve the liquid effluent release requirements. The 600 pCi/L down stream river concentration goal remains well below federal limits, allows discontinuation of recycle and Feed and bleed operation, restores the PW system to "clean",

allows effective use of RST as a valuable forward thinking asset, and will minimize or eliminate the need for solidification/disposal.

The following table provides a tritium balance summary based on the down stream river targets:

Annual Plant Tritium Balance River Liquid Effluent Recycle Solidification/

Concentration To PWST Disposal Goal Volume Curies Volume Curies Volume Curies gallons gallons gallons 200 pCi/L 730,000 892 1,009,000 1259 9,000 49 400 pCi/L 1,460,000 1786 277,000 346 12,000 68 600 pCi/L 2,194,000 2860 0 0 0 0 800 pCi/L 2,926,000 3574 0 0 0 0 1000 pCi/L 3,658,000 4468 0 0 0 0 164 of .238

General Discussion:

This report evaluates several aspects of a regulated liquid effluent release program and the resulting concentrations based on the river mixing study performed by HydroQual in February 2009 (EXCO.003).

This evaluation works backward from river dilution and concentration data into plant to assess plant operation, practices, and liquid effluent generation rates to determine if target river concentrations can be met.

As requested by Exelon, the target river concentrations at the dam were 200, 400, 600, 800 and 1,000 pCi/L. As per 40 CFR 141.66 (Table A) and subsection 611.330 of Title 35, subtitle F, Chapter I of the Illinois General Assembly Administrative Code, the average annual concentration of beta particle and photon radioactivity from man-made radionuclides in drinking water must not produce an annual dose equivalent to the total body or any internal organ greater than 4 millirem/year (mrem/yr). This relates to an average annual concentration in drinking water of 20,000 pCi/L, which is much greater than the chosen target river concentrations at the dam just upstream from the Wilmington water intake.

Liquid effluent release rates, liquid effluent volume and liquid effluent tritium curie content in the plant were calculated from the river concentration goals. From these values, an assessment was made to determine if the plant could operate in a manner that would allow liquid effluents to meet the river concentration goals. The viable operational practices will be used to develop a water management plan which will manage liquid effluent generation, direct appropriate processing and purification, implement logical movement and storage of liquid effluent, and regulate release of liquid effluents within accepted goals.

Evaluation Assumptions Parameter Assumption Reference Federal Limit 20,000 pCi/L 40 CFR 141.66 (Table A) and State Limit subsection 611.330 of Title 35, subtitle F, Chapter I of the Illinois General Assembly Administrative Code Federal LLD 2,000 pCi/L Achievable LLD 200 pCi/L Average Release Tank 0.33 uCi/mL Steady State Release Tank Concentration concentration average from 2008 0.62 uCi/mI Outage Release Tank concentration average from 2008 Average and Annual Liquid 2 gpm Effluent Generation Rate 1,739,200 gallons Average input to Total generation in Dual Outage Year 1,939,200 gallons Total Generation in Dual Outage Year plus One Forced Outage (worst case)

RCS Feed and Bleed 50,000 gallons per unit @ 300 w/ H3 >1.5 uCi/mI at RST EFPD Average and Annual River USGS (1969- 2008)

Flows Blowdown System Availability 90%

From the HyrdoQual Report, the following baseline data was used to calculate the plant effects of a three, five, and seven port diffuser system over a 200, 400, 600, 800, and 1000 pCi/L range of river tritium concentrations:

165 of 238

[b0hege flow - 19.000 gpn RI.-e Con-eM-d-n .1 D0m (PiCVL)

....n.. 3-PO Off.....m 200 400 Go0 Goo 1000 Moths Mthly A1 . Flow

- lJ~ln D0..n Al bo Oltolna.D e TrDlO..m Canoe5ln C (p-WL)

(8,)

(ale) (1 Ge-2006)

Jm.uel 8.228 1220 26.5-M 50.130 70.720 100.3O2 192.870 Febm-- 6.810 145.0 32.010 00.020 87.030 118,04D 14.5050 h 8,874 180.0 37.80D 75f610 113.410 151 .10 180.020 8p.l a506 183.1 36,63D 7.3250 100.80 148I)00 1853180

  • ly 7,513 180.0 32.OD8 84,010 08.010 128010 180.8W mune 853 130*0 27.8O 55.810 835410 111.210 1S.COD J.b. 3.185 82.2 16.440 22.8*0 4.0,20 85,780 82,200 uguet 2.451 52-2 10.440 2D.880 31.20 41.760 52200 Rap~e..b. 2.88 a 57.2 11,440 2-880 34,20 45.770 57 "210 Ootb~r2,887 83.68 12.7,T0 2843 25.80' 50.000 83.830 80a~mbar 4,1 3 87.0 17.58 SL%.170 52.750 70M.40 87*920 0 Am annual 1 (1mldl "08-0,7*0 nnua3 5.553 1142S 4.2 1.2 I8-)4.

008e.fw (1-6913- 5,9.54 114.0 22,10 45*_1.220 114.040 0b8h-ef. 1 - 1900 lap-gpmn R C lamaeon d* 0 m (PC*VL)

OPt~m8, 5-P85 btle... .200 4mc 80 Go I ac 1;00 hoh. tM Av g Flow n 0. A ....ble Dd.heW.ne L Trfli*e C-oent-mi . (pCVL)

W-l) V(1980m208 (8B.)

8.238y GA3 124.1 2.620 526.,5 80a70 107.8WC 134;110 t 6.810 148.4 32.280 21.580 87.850 117,130 148.410 M- r "74 190.8 18.18 ,0 6.32* 114,480 1=.00 190.780 A8. f -5.9 14.6 58.070 75.940 1109100 14,00 114,850 hy7.515 181.5 322.8W 84,810 908.10 132P.w 161.8W Jue 8.ý532 140-2 28.08D 56.120 84,190 1l2.0 140.520 ptioS.859 D1.... 8..0 3.1900 4 0780 686970 8070 Jul.4*51 52.7 1a.40 21.080 31.610 42.150 .2,800 S Jept-lenb 2.88 1 57.7 2.1CO 21.50 34,850 48.200 57.740 2967 84.2 12.,80 25.690 S3.540 513,78 8002 0 4.128 63.7 17.750 35.5m0 55.250 71,.00 00.70 Oeoa rber 8 070 135 132,100 52.200 782,00 104.*0o0 120.T o( r f..200a) 5,55a 119.4 28.880 4.7810 7I.-40 85.520 1-19.40 008) 0.dl.n-u)110 a.eg fle (1989o. 52354 j 115.1A.2 8008.809.9 1.1 Oloh-9.9 fl.- - 19,000 Up-, RIO..

C .W~~rom 0081 D- 807 Optio.: 7-p-n 01f.,. 200 400 80 Goo 1000 oo 0

MoMbo oeeg Flow 8.41n Dan,1 D iehlgeW Trill... Camoeri.n, C(pCýVL)

G.

Cr4.) (1960-2005) (a..)

Jmenly ea, Feo.M.-.y nnual eregerf 6,23S 8,810 141.8 124.8 1 22320 0.980 I 58.840 81.830 64,960 92.750 113,280 123.660 141.8W 154.580 M0.oh 8.674 321. 40.290 60.58.0 120,870 181.150 201.440 Ap.8 8,500 195.2 030l 78.070 117.100 156,13D 105.100 May 7.51 M 170-5 34,110 66.210 102.320 138.A20 17M.530 Jun 0.527 '148.2 32.830 59.2W0 88.890 118-532D 148.18 Jut,3,80 07.8 17.520 35.040 52-580 70.080 67.800 Ag-2451I 55.0 11.130 22.250 25.380 44,500 5.5 Septelnbe 2.680 81.0 12,180 24.390 S8,560 48.770 80.070 On0r2.987 87.8 13.5w0 32.13 40,890 542087.810 No~nbr4,1l28 03.7 18.ý740 37.480 58.220 74,080 03.700 I

008.1b.r 8.G70 157.8 27.5w 55.110 82.870 1102320 13.7,7W 0I99-5008) 5,55 I0.1 -. 21 1-,-___________

m:.-- ann-a.0 48 1.9;eg lloe (1989- 5,82 2152,2 1 72L.8 97.2S5 12154 166 of 238

The Kankakee River flow data shows consistent trends in total volume every month over the course of a year. River flow data analyzed over a forty time period indicates December through June typically have monthly average flow rates greater than 4000 cfm. July through November is typically less than 4000 cfm.

These trends in high flow and low flow are a necessary fundamental in meeting liquid effluent release criteria.

Monthly Aeerage Flow (cls) (1969-2008) 10.000 9.000 8,000 7,000 6.000 S5000 0.aW 32000 January February March April May June July August September October November December Comparing the three, five, and seven port diffuser systems against the average river flow by month indicates similar effectiveness in the three and five port design. The seven port design however shows significantly greater effectiveness. The tritium concentrations shown below are the concentration at the diffuser required to meet the down stream river target concentrations and in effect would be the concentration of the circulating water system blowdown at the point of exit into the river.

250,000 2OOOOO7-porl 3-pout G200 02o0 pCiL

2. 5-port @800 pCVL pCi/

i 5-porl 0400 pCi/L j 0-port

  • 4oopCVL 3-port @040 p*i(
  • -- 5port0600pCWL 1 soooo7-port eowo pc iý 3-port *a0m pCi/L 7-porl GaOOpCa/

--,WP-3-port 0 1000 pCVL 50.OW 167 of 238

Using an average release tank concentration and calculating the release rate (gpm) to achieve the tritium concentration goal at the diffuser, the annual volume of liquid effluent (gal) attainable can be estimated.

Again similar effectiveness in the three and five port design is noted. The seven port design however shows significantly greater effectiveriese. Further, this estimation indicates that the 200 and 400 pCi/L downstream river concentration goals do not allow the plant to release all of the anticipated liquid effluent generation. The estimated annual volume generated in a dual outage year would be 1,739,200 gallons and in a worse case dual outage yer wJth one forced outage is ,1,939q2Q gallons. Releasing the full allowed volume at the 200 and 400 pCVL down stream river concentration goals would result in an excess liquid effluent volume of approximately 1,009,000 gallons and 277,000 gallons respectively. This volume of low tritium concentration effluent would need to be dispositioned by recycle, surge capacity or solidification/disposal. These cases far exceed current surge capacity, therefore only recycle and solidification/disposal remain as viable options.

200-400 will require the plant to continue the current recycle operation and the current reactor coolant system feed and bleed for processing to the proposed solidification/disposal facility. Reactor coolant, PW, and spent fuel pool would all continue to increase in nominal tritium concentration until equilibrium is achieved again around 2017.

Nominal Tritium Nominal Tritium Nominal Tritium Concentration prior to Concentration Currently Concentration in 2017 2007 (equilibrium)

Reactor Coolant System 2.0 jiCi/ml 2.5 gCi/ml 3.5 gCi/ml Primary Water 0 PiCi/ml 0.24 laCi/ml 1.25 pCi/ml Spent Fuel Pool 0.1 PiCi/ml 0.4 pCi/ml 0.91iCi/ml The Ž>500 pCi/L down stream river concentration goal remains well below federal limits at all times, allows discontinuation of recycle operation, restores PW system to "clean", allows effective use of RST as a valuable forward thinking asset, and will minimize or eliminate the need for solidification/disposal.

Annual Effluent Release Volume Comparison of Rier Concentration Goals J 3-pat GpY-a- &PbrtGPY 7-PonGPY 4,50OO0

~2,500,00 o2,00,00 1.500,000 200 400 Aive Concemrealo, Goal(pCII L)

A closer examination using only the three port model demonstrates on a month-by-month basis that the 200 pCi/L downstream river concentration goal never meets monthly plant release volume requirements and 400 pCi/L downstream river concentration goal meets the monthly plant release volume requirements in only 6 of 12 months.

168 of 238

Release Roe Galons per Month with 3-Pod Model JI 200PCK = 730,2t rPY ý 400 PQIL= 1A62294 (PY 600P(d. 2 94M8 (PY - S PCt =2i,9O7 GPY -U- IWOj.C.¶ -3.67,82 (PY I 5E 100O00

-aaY ,-..uy - a, JWW

- jWY P4J9W SOPM1I

.fl w4or These two charts indicate the minimum downstream river concentration goal necessary to meet annual or monthly plant release volume requirements begins at 600 pCi/L. The estimated annual volume generated in a dual outage year would be 1,739,200 gallons and in a worse case dual outage year with one forced outage is 1,939,200 gallons. Releasing the full allowed volume at the >600 pCi/L down stream river concentration goals would result in the ability to release all liquid effluents generated plus an additional 455,000 gallons during a dual outage year. A dual outage year with one force outage would result in an excess liquid effluent volume of approximately 255,000 gallons. This volume of low tritium concentration effluent would need to be dispositioned by recycle, surge capacity or solidification/disposal. This volume is within the current surge capacity; therefore surge (via the RST) would be the viable option.

Curies per Month Gallons per Month 200 400 600 800 1000 DCi/L 200 400 600 800 1000 85.2 1170.5 1 255.8 341.1 426.4 Jan 68278 1 136697 205090 273483 1 341902 84.0 168.1 252.2 336.3 420.5 Feb 74558 149232 223907 298581 373255 121.2 242.6 363.9 485.3 606.7 Mar 97184 194511 291811 389111 486437 113.7 227.4 341.2 455.0 568.8 Apr 94173 188436 282724 376987 471276 102.6 205.3 308.1 410.8 513.6 May 82255 164651 247022 329392 411789 86.2 172.6 259.0 345.4 431.8 Jun 71444 143029 214588 286148 357733 52.6 105.4 158.2 211.0 263.7 Jul 42202 84520 126838 169156 211474 33.4 66.9 100.4 133.9 167.4 Aug 26758 53631 80504 107378 134251 35.4 70.9 106.5 142.1 177.6 Sep 29332 58779 88227 117700 147147 40.7 81.6 122.4 163.3 204.1 Oct 32652 65395 98163 130905 163673 54.5 109.1 163.7 218.4 273.0 Nov 45137 90415 135667 180945 226197 82.9 165.9 248.9 331.9 414.9 Dec 66450 132990 199556 266121 332687 892 1786 2680 3574 4468 730,421 1,462,284 2,194,096 2,925,907 3,657,822 Consequently, comparing annual average river flows to the effect on liquid effluent discharge at >600 pCi/L down stream river concentration goal generally indicates that any period where the river flow is greater than 4000 cfs the plant will be able to release all the liquid effluent generated plus some reserve volume. At the periods of the month where the river flow is less than 4000 cfs the plant will not be able to release all the liquid effluent generated and available surge capacity will be required.

169 of 238

t4Wy Agu Flw H- g-2ooe)

Augu So.p 0 . D .

.- J h Ju.e Jut Ag 3.OOO 2.OOO.

FIST Surge Trend vs River Flow 600 pCiIL Model 200000 10,000 9o000 10030 2L000 50000 6,000

] o ,.OoW

-,000

-150000-1.000

-200000O 0 The RST was evaluated against this data to determine if adequate surge capacity exists based on the excess liquid release volumes calculated for the low river flow months. The RST has a total capacity of 500,000 gallons. Assuming an initial volume of 125,000 gallons at the beginning of the calendar year, excess discharge volumes above the routine monthly liquid effluent generation could occur due to the higher river flows during the first quarter of the year. These excess releases would reduce the RST to minimal levels until surge capacity is again required due to the higher liquid effluent generation rates incurred by the spring outage. The RST level would be minimized again until the average river flow drops below 4000 cfm. During these months, liquid effluent releases will not keep pace with generation rates and the RST will serve as surge capacity through the summer and the fall outage.

By January of the following year, higher river flows will allow normal release frequencies plus the reduction of the RST volume again to minimal levels over the next few months.

170 of 238

Volume of RST Over Time ecWPM kW" 150DOO 100000 5O000 This case is built on a dual outage year to demonstrate the effects of river flow and setting the appropriate minimum down stream concentration goal. In calendar years where no spring outage is planned, the RST surge trend line would remain flat. In calendar years where no fall outage is planned, the RST surge trend line would continue to build at a gradual pace. By January of the following year, higher river flows will allow normal release frequencies plus the reduction of the RST volume again to minimal levels over the next few months.

Analysis of the release rate data identified several operational concerns. Release tank release rates at the 200 and 400 pCi/L downstream river concentration goals at all times of the year will not meet the plant resource commitments. Generally, release tank release rates remain so low that a total release (25,000 gallons) would span 4 to 29 days to completion. Significant changes in Operations oversight and implementation would be required to achieve these downstream goals. Surge volume in the RST or waste processing system is inadequate to retain this excess volume of liquid effluent resulting in significant recycle and solidification/disposal. Release tank release rates >600 pCi/L downstream river concentration goal will meet most operational concerns except during the low river flow periods. As previously discussed, available RST surge capacity is adequate to retain the excess liquid effluent volume in the short term. This is also the case when abnormally low river flows are observed outside of the normal months.

River Goal pCi/L 200 400 600 800 1000 Jan 1.5 3.1 4.6 6.1 7.7 Feb 1.7 3.3 5.0 6.7 8.4 Release Mar 2.2 4.4 6.5 8.7 10.9 Tank Apr 2.1 4.2 6.3 8.4 10.6 Release May 1.8 3.7 5.5 7.4 9.2 Rate Jun 1.6 3.2 4.8 6.4 8.0 WPM)

Jul 0.9 1.9 2.8 3.8 4.7 Aug 0.6 1.2 1.8 2.4 3.0 Sep 0.7 1.3 2.0 2.6 3.3 Oct 0.7 1.5 2.2 2.9 3.7 Nov 1.0 2.0 3.0 4.1 5.1 Dec 1.5 3.0 4.5 6.0 7.5 171 of 238

Release Tanks per Month Days per Release Tank Release 200 400 600 800 1000 pOL 200 400 600 800 1000 3 1 5 8 1 11 1 14 Jan 11.4 1 5.7 3.8 2.8 2.3 3 6 9 12 15 Feb 10.4 5.2 3.5 2.6 2.1 4 8 12 16 19 Mar 8.0 4.0 2.7 2.0 1.6 4 8 11 15 19 Apr 8.2 4.1 2.7 2.1 1.6 3 7 10 13 16 May 9.4 4.7 3.1 2.4 1.9 3 6 9 11 14 Jun 10.8 5.4 3.6 2.7 2.2 2 3 5 7 8 Jul 18.4 9.2 6.1 4.6 3.7 1 2 3 4 5 Aug 29.0 14.5 9.6 7.2 5.8 1 2 4 5 6 Sep 26.4 13.2 8.8 6.6 5.3 1 3 4 5 7 Oct 23.7 11.9 7.9 5.9 4.7 2 4 5 7 9 Nov 17.2 8.6 5.7 4.3 3.4 3 5 8 11 13 Dec 11.7 5.8 3.9 2.9 2.3

==

Conclusion:==

In order to effectively implement the river diffuser system and achieve net zero water balance, net zero tritium balance, net zero recycle, and net zero solidification/disposal a down stream river tritium concentration goal >600 pCi/L is required.

PWST Tritium Dual Outage Year w/ No Recycle Model 500.

450 400 360 250' 200 150 100 50.

0 1 102912"0 12/191200 2/WM11 V2SIM1 5117/291 74&~ WWO 012M0 o14/2(9 MUM0~9 112M1010 1--*W.OPWST-08 PWST]

172 of 238

Spent Fuel Pool Tritium Dual Outage Year w/ No Recycle Model 400 350 30O 250 200 150 100 50 10/29/2008 12/18/2008 2/612009 3(28/2009 5/17/2009 7/5/2009 8/25/2009 10/14/2009 12/312009 1/22/2010 Recycle to PWST 500000 450000 400000 350000 300000 250000 200000 150000 100000 50000 0

0F 10 10 T, a.* 14 P I ;I 173 of 238

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2011 UNIT 1 AND 2 (Docket Numbers 50-456 and 50-457)

ATTACHMENT 6 TELEDYNE BROWN ENGINEERING SAMPLE RESULTS FOR BD-22 TRITIUM 174 of 238

,AVPVh I .UDUNt BROWN ENGINEERING, INC.

At dV-T,,h"ed*mdagsCoMw 250 Quality Lane Knoxvifleý TN 37931-3133 L48912 pg I of 7 865-690-6819 Eric Cicsykiewicz" Braidwood Station Exelon Generation Company LLC 35100 South Ric 53, Suite 84 Braceville, IL 60407-9619 Report of Analysis/Certificate of Conformance 01/24/2012 LIMS #: L48912 Project ]D#: EXOOI-3EREMPBRAID-05 Received: 12/28/2011 Delivery Date: 02/0112012

. P.O.#: 01000298 REL#00018 Release #:

SDG#:

This is to certify that Teledyne Brown Engineering - Environmental Services located at 2508 Quality Lane, Knoxville, Tennessee, 37931, has analyzed, tested and documented samples, as received by the laboratory, as specified in the applicable purchase order.

This also certifies that requirements of applicable codes, standards and specifications have been fully met and that any quality assurance documentation which verified conformance to the purchase order is on file and may be examined upon request.

I hereby certify that the above statements are true and correct.

Keith Jeter (U Operations Manager CrossReference Table Client ID Laboratory ID Station ID (if applicable)

BD-22 L48912-1 I BD-22 Method Reference Numbers Matrix Analysis Method Reference H-3 (DS1)

HWD j EPA 906.0 This report shall not be reproduced or distributed except in its entirety.

Page I of 2 175 of 238

Report of Analysis TELEDYNE BROWN ENGINEERING, INC.

01/24/12 12:30 ATeledMT c Tch*nota CnmpsMy L48912 L48912 pg 2 of 7 Braidwood Station EX00I-3EREMPBRAID-05 Sample ID: BD-22 CollcctStart: 12/15/2011 15:40 Matrix: DrinkingWater (WD)

Station: BD-22 Collect Stop: 12/22/2011 15:20 Volume:

Description:

Wilmington" Reccivc Date: 12/28/2011  % Moisture:

L1MS Number:. "8912-1 Count Count Radionuclide SOP#

1Activity Cone Uncertainty 2 Sigma j DC Units Run IAliquot IAliquot

  1. Volume Units Reference Date Count Date I Time Units Flag Values H-3 (DIST) 2011 -2.68E+01 I 1.12E+02 [ 1.88E+02 -1 pCi/L 10 1 ml - -- 01/15/121 60 I M U I I I 1-131 (LOW LVL) I 2012 I 1.06E-01 I 3.19E-01 I 6.17E-01 '1 pCi/L I 1 4000 1 ml 112/22/1t 15:20 I 01/18/121 300 I M IU I I I Comment: I Weekly composite-hold for monthly composite 0) 03 N.)

00 Flag Values

= Compound/Analyte not detected (< MDC) or less than 2 sigma No - Peak not identified in gamma spectrum U

+ - Activity concentration exceeds MDC and 2 sigma; peak identified(gamma only) Yes - Peak identified in gamma spectrun U* = CompoundlAnalyte not detected. Peak not identified, but forced activity concentration exceeds MDC and 2 sigma

        • Unless otherwise noted, the analytical results reported High = Activity concentration exceeds customer reporting value Spec - MDC exceeds customer tedcnical specification are related only to the samples tested in the condition they L = Low recovery are received by the laboratory.

H - High recovery MDC - Minimum Detectable Concntration Bolded text indicates reportable value. Page 2 of 2

4N~2 (P~ of7 Braidwood Generating Station Sample Collecdion/Recelpt Sheet Public Water Sample EXELON NUCLEAR Sample Sample Lab. No. Client ID Station Code Medium Stae date Sart lime StaP date Stop trne Size Analysis "_Commnts, H-3 (DLO V),e-13 o

... Wilmington BD-22 DW 12/15/2011 15:40 12/22/2011 15:20 ,2 pl._ (LOW LVt.) Weekly composite-hold for monthly composite 0

DO Collected by- A. Lxvda Date: 12122/2011.D-22 Composite weekly sample for Monthly Composite for Gamma, GR-B Shippedby: F/E Date: 12t27/2011 -Hold for Quaztely H-3 Composite.

Received by:L- Date: 1,1Z ,' tr BD-22 1ov17

Environmental, Inc. SR NO. i5535i J Midwest Laboratory An Allegheny Technologies Company Shipping Re(dlst°"

MIDWEST LABORATORY 700 LANOWEHR ROAD

  • NORTHSROOK, IL60052-2310 * (847) 564-0700 FAX (847) 564-4517 NOTEII When returning or replacing this material, please reference SIR No. on all documents.

PART I (To be completed by originator) 0. Control Data:

A. Description of items (include, Quantity, Model No.,

Type, Serial No., and Gov't Property No.)

Vendor 9 nallnR Rrl-22 P.O. No.

W.O./Acct. No.

Location of material Ship no later than Ship v Collect:

Prepaid E C

No. Pcs.Ictns. - Cu. Ft.

B. Purpose of Shipment Weight Est. Val.

o Return for credit-No replacement Part II (To be completed by 0 Return for rework or replacement at Vendor's expense.

Shipping Dept.)

O Return for rework or replacement at Environmental, Inc's expense.

Actual method of shipment Federal Express O Furnished on Consignment for use on P.O. No.

o Other (explain) Date Shipped 12/27/2011 C. Comments or Instructions to Vendor: Collect Prepaid FOB point Waybill No.

Misc.

SHIPTO: TBE L.B.

ORIGa4ATORa INITIALS ATTN: _________________

178 of 238

12/28/11 13:14 Teledyne Brown Engineering SSR 81 SR013:14 R #:SR30013 Sample Receipt Verification/Variance Report Client: Exelon Project #: EXOO1-3EPEMPBRA1D-05 t12 Pk44;12 Initiated By: JSIMMONS Init Date: 12/28/11 Receive Date: 12/28/11 Notification of Variance Person Notified: Contacted By:

Notify Date:

Notify Method:

Notify Comment:

Client Response Person Responding:

Response Date:

Response Method:

Response Comment Criteria Yes No NA Comment l Shippinglesntisted c nustody sealsdpresent NA and intact.

2 Sample container custody seals present NA and intact.

3 Sample containers receivedin good Y condition 4 Chain of custody received with samples Y 5 All samples listed on chain of custody Y received 6 Sample container labels present and y legible.

7 Information on container labels Y correspond with chain of custody 8 Sample(s) properly preserved and in NA appropriate container(s) 9 Other (Describe) NA 179 of 238

Raw Data Sheet (rawdata) 01/24/12 12:30 Page 1 of 1 Work Order: 148912 Customer: Exelo, L48912 pg 6 of 7 Analysis: H-3 Project: EXO01-3EREMPBRAM-05 Decay a Sample ID Run Analysis Reference Volume/ Scavenge Milking Mount Count Detector Total Sample Bkg Bkg Eff. Ingrowth Client ID 0 Date/Time Aliquot Date/Time Date/Time Weight Recovery Date/Time ID Counts dt Counts dt Factor Analyst L48912-1 H-3 (DIST) 0 01-15-12 LS7 110 60 117 60 .203 DW 10 06:24 1 M BD-22 ml Activity: -2.68E+01 Error: 1.12E+02 MDC: 1.883+02 pCi/L L48912-1 H-3 (DIST) 0--3 C0 00

Raw Data Sheet (rawdata) 01/24/12 12:30 Page 1 of.I Work Order:; A8912 Customer: E*elon L48912 pg 7 of 7 Analysis: I -131 Project: EX0O1-3Er3EMPUAID-05 Decay a Sample ID Run Analysis Reference volume/ Scavenge Milking Mount Count Detector Total Sample Bkg Bkg Eff. Ingrowth Client ID # Date/Time Aliquot Date/Time DaLe/Time Weight Recovery Date/Time ID Counts dt Counts dt Factor Analysi L48912-1 1-131 (LOW LVL)22-dec-li .0211 92.95 01-18-12 YlC 114 300 282 Boo .32 .098 BP 15:20 4000 16:22 M M BD-22 mi Activity: 1.06E-01 Error: 3.19E-01 MDC: 6.178-01 pCi/L L48912-1 1-131 (LOW LVL) 03 00-3 00

I p qmTELEDYNE BROWN ENGINEERING, INC.

A TorTe. Compm boa~sde 2508 Quality Lane L48967 pg 1 of 7 Knoxville, TN 37931-3133 865-690-6819 Eric Cieszkewiez Braidwood Station Exelon Generation Company LLC 35100 South Rte 53, Suite 84 Braceville, IL 60407-9619 Report of Analysis/Certificate of Conformance 01/30t2012 LIMS #: IA8967 Project ID#: EX001-3EREMPBRAID-05 Received: 01104/2012 Delivery Date: 02108/2012 P.O.X: 01000298 REL#00018 Release #:

SDG#:

This is to certify that Teledyne Brown Engineering - Environmental Services located at 2508 Quality Lane, Knoxville, Tennessee, 37931, has analyzed, tested and documented samples, as received by the laboratory, as specified in the applicable purchase order.

This also certifies that requirements of applicable codes, standards and specifications have been fully met and that any quality assurance documentation which verified conformance to the purchase order is on file and may be examined upon request.

I hereby certify that the above statements are true and correct Keith Jeter Operations Manager Cross Reference Table Client ID Laboratory ID Station ID (if aplicable)

BD-22 LA8967-1 BD-22 Method Reference Numbers Mathix Analysis Method Reference 1 WD H-3 (DIST) j EPA 906.0 This report shall not be reproduced or distributed except in its entirety.

Page I of 2 z ( 182 of 238

Report of Analysis .ApL TELEDYNE BROWN ENGINEERING, INC.

01/30/12 11:07 AT T pdgo2 oc f 7arr L48967 L48967 pg 2 of 7 Braidwood Station EX00I-3EREMPBRAID-05 SampleIJD: BD-22 Collect Start: 12/22/2011 15:20 Matrix: Drinking Water (WD)

Station: BD-22 Collect Stop: 12/29/2011 17:20 Volume:

Description:

Wilmington Recxive Date: 01/04/2012  % Moisture:

LIMS Number. L48967-1 RadionucRunAtvt ncranyfu Io# Aliquot Aliquoti Reference Count Cou.nt Coun Vaue Radionclide SOP# Cone 2 Sigma MDC un # Volume Units Date Date Time Units H-3 (DIST) I2011 2.83E-02 1.26E+02 1 1.80E+02 pCi/L I 1 10 -mu 01/13/121 0 M + I- I 1-131 (LOW LVL) ] 2012 1 -5.86E-03 i 3.31E-01 I 6.59E-01 pCi/L 1 I 5000 1 ml 1 12/29/11 17:20 1 01/26/121 300 I M I U I Comment: I Weekly compositc-hold for monthly composite

  • "') tj-1r &t-0 ia.z "'ETiA. *'-J4Aý-

'17F~ If- X-OtZ A/AL. UVL 6PKAT'r4 Tf0A,jL-h e 'Z-.-&-

00 0)

Flag Va]ues U Compound/Analytc not detected (< MDC) or less than 2 sigma No = Peak not identified in gamma spectrum U = Acoivity concenration exceeds MDC and 2 sigma, peak identfied(gamma oaly) Yes Ptak identified in gamma spectrum CompoundlAnalyte not detected. Peak not identified, but forced activity concentration wceds MDC and 2 sigma **** Unless otherwise noted, the analytical results reported High Activity concentration exceeds customer repoting value Spec = MDC exceeds customer technical specification are relaled only to the samples tested in the condition they L - Low re~overy am received by the laboratory.

H High recovery MIDC- Minimum Detectable Concentration Bolded tex t indicates reportable value.

Page 2 of 2

It-LI Braldwood Generatlng Station Public Water Sample Sample CollectionlReceipt Sheet Lj4 q67 EXELON NUCLEAR Sample Sample Lab.No. Client ID Stadon Code Mediaee San date Suta time Stop date Stoptime Size Analysis Commeot H4-3(DIST),1-l3l Wilmington BD-22 DW 12/2212011 15:20 12/29/2011 17:20 2 gal. (LOW LVL) Weekly composite-hold for monthly composite

.00 rO Co Collected by: A. 1 *s Date: 12/29/2012 BD-22 Composite weeldy sample for Monthly Composite for Gamma, GR-B Shipped by:*F .*

I Date:; 0 3/2212 Hold for Quarterly H-3 Composite.

Received by: ,;w ý Date: I / 1L . BD-22 O-*I

.7/

Environmental, Inc. SR NO. 15_5_40 I Shipping Reo"sto1 Midwest Laboratory 7 An Allegheny Technologies Company MIDWEST LABORATORY 700 LANDWEHR ROAD - NORTHBROOK, IL 60062-2310 - (847) 584-0700 FAX(847) 584-4517 NOTE!I When returning or replacing this material, please reference S/R No. on all documents, PART I (To be completed by originator) D. Control Data:

A. Description of items (include, Quantity, Model No.,

Type, Serial No., and Gov't Property No.)

Vendor Braidwood: P.O. No.

RD-72 W.O./Acct. No.

Location of material Ship no later than Collect Prepaid I]C B. Purpose of Shipment: No. Pcs./ctns. __ Cu. Ft.

Weight - Est. Val.

o Return for credit-No replacement:

Part II (To be completed by 0 Return for rework or replacement at Vendor's expense.

Shipping Dept.)

o Return for rework or replacement at Environmental, Inc's expense.

Actual method of shipment Federal Express

- Furnished on Consignment for use on P.O. No.

o Other (explain)

Date Shipped 01-03-2012 C. Comments or Instructions to Vendor. Colled Prepaid FOB point Waybill No.

Misc.

SHIP TO: TBE LR~tL ORIGINATW ATTN:

185 of 238

01/04/12 10:46 Teledyne Brown Engineering Sample Receipt Verification/Variance Report SR,#:" SR30067 L4W.%*5 of 7 Client: Exelon Project #: EXOO1-3EREMPBRAID-05 L48967 Initiated By: JSIMMONS Init Date: 01/04/12 Receive Date: 01/04/12 Notification of Variance Person Notified: Contacted By:

Notify Date:

Notify Method:

Notify Comment:

Client Response Person Responding:

Response Date:

Response Method:

Response Comment Criteria Yes No NA Comment 1 Shipping container custody seals present NA and intact.

2 Sample container custody seals present NA and intact.

3 Sample containers received in good Y condition 4 Chain of custody received with samples Y 5 All samples listed on chain of custody Y received 6 Sample container labels present and Y legible.

7. Information on container labels Y correspond with chain of custody 8 Sample(s) properly preserved and in NA appropriate container(s) 9 Other (Describe) NA 186 of 238

Raw Data Sheet (rawdata) 01/30/12 11:07 -Page 1 dO 1 Work Order: L48967 Customer: Exelon L48967 pg 6 of 7 Analysis: f-3 Project: RX001-3EREWPBRAID-05 Decay C Sample ID Run Analysis Reference Volume/ Scavenge Milking Mount Count Detector Total Sample Bkg Skg Eff. Ingrowth Date/Time Aliquot Date/Time Date/Time Weight Recovery Date/Time ID Counts dt Counts dt Factor Analyst Client ID

  • L48967-1 H-3 (DIST) 0 01-13-12 LS7 201 60 120.6 60 .214 DW I0 07:56 H M 2D-22 Activity: 2.033+02 Error: 1.26E+02 MDC: 1.80+02 pCi/L L48967-1 f-3 (DIST)

-4 0

00

Raw Data Sheet (rawdata) 01/30/12 11:07 Page 1 of 1 Work Order: L48967 Customer: Exelon L48967 pg 7 of 7 Analysis: X:-131 Project: MM0O-3E3MPBRaAM-05 Decay G Sample ID Run Analysis Reference Volume/ Scavenge Milking Mount Count Detector Total Sample Bkg Bkg Eff. Ingrowth Client ID # Date/Time Aliquot Date/Time Date/Time Weight Recovery Date/Time ID Counts dt Counts dt Factor Analyst L48967-1 1-131 (LOW LVL) 29-dec-l1 .0208 91.63 01-26-12 X4C 145 300 388 800 .309 .091 SP 17:20 5000 16:36 N BD-22 ml Activity: -5.86E-03 Error: 3.31E-01 MDC: 6.599-01 pCi/L L48967-1 1-131 (LOW LVL) 00 CO 0

00

4FAq TELEDYNE BROWN ENGINEERING, INC, AldwwTe toafstCMPIM 250oQuality Lane L49059 pg l of 7 Knoxville, TN 37931-3133 865-690-6819 Eric Cieszkiewicz Braidwood Station Exrlon Gcnmation Company LLC 35100 South Rte 53, Suite 84 Braceville, IL 60407-9619 Report of Analysis/Certificate of Conformance 02/02/2012 LIMS 4: L49059 Projmt ID#: EX001-3EREMPBRAID-05 Received: 01/10/2012 Delivery Date: 02/14/2012 P.O.#: 01000298 REL.100018 Release #:

SDG#:

This is to certify that Teledyne Brown Engineering - Environmental Services located at 2508 Quality Lane, Knoxville, Tennessee, 37931, has analyzed, tested and documented samples, as received by the laboratory, as specified in the applicable purchase order.

This also certifies that requirements of applicable codes, standards and specifications have been fully met and that any quality assurance documentation which verified conformance to the purchase order is on file and may be examined upon request.

I hereby certify that the above statements are true and correct.

Kbith Jeter Operations "Manager CrossReference Table Clieat 1D Laboratory ID Station 11)(if applicable)

BD-22 L49059-1 BD-22 Method Reference Numbers jMatrix Analysis IMethod Reference WD H-3 (DISM) EPA 906.0 This report shall not be reproduced or distributed except in its entirety.

Page I of 2 189 of 238

Report of Analysis ,ffOR11 TELEDYNE BROWN ENGINEERING, INC.

02/02/12 10:45 ATe&lWas.Teslaolqn* Campanv IA9059 L49059 pg 2 of 7 Braidwood Station EX001-3EREMPBRAID-05 Sample ID: BD-22 Collect Start: 12/29/2011 17:20 Matrix: Drinking Water (WD)

Station: BD-22 Collect Stop: 01/05/2012 16:00 Volume:

Description:

Wilmington Receive Date: 01/10/2012  % Moisture:

LIMS Number: 1A9059-1 W Activity UncertaintyUnits IRu Aliquot Aliquot Reference Count Count Count Radionudide SOP# Cone 2 Sigma MDC Units Volume Units Date Date Time Units Flag Values H-3 (DIST) 2011 iý.6E0 .E+2 .7 0- piI10l 01/23/1ý 60 MW--

1-131 (LOWLVL) 2012 6.62E-02 3.41E-01 6.42E-"1 pCiUL 4000 ml 01/05/12 16:00 0H/31/12 400 M U Comment: I Weekly composite-hold for monthly composite Co 0

0 FRoValues U = Co vnd/Analyte not detected (< MDC) or less than 2 sigma No = Peak not identified in gamma spectrum

+ = Activity concentralion exceeds MDC and 2 sigma; peak identified(gsamma only) Yes - Peak identified in garmma spectrum U4 = Copound/Analyte not detected. Peak not identified, but forced activity concentration excteds MDC and 2 sigma a*0* Unless otherwise noted, the analytical results reported High - Activity concentration exceeds customer reporting value Spec = MDC exceeds customer technical specification are related only to the samples tested in the condition they L = Low recovery are received by the laboratosy.

H = High -ecovery MDC - Minimum Detectable Conoenblatlon BRlded text indicates reportable value. Page 2 of 2

LIqo~g L49059 3f Bralmoood Generating Station Sample CollectlorReceipt Sheet

\,) 'J x Public Water Sample EXELON NUCLEAR

&unple Sawple Lab. No. Climrt ID Stada= Code Medium Start date Stut time Stop date Stoptime Size Awlis Comments H-3 (DIST),I- 131 Wilmington BD-22 DW 12/2912011 17:20 01/05/2012 16:00 2 al. (LOW LVL) Weeldy cotrposite-hold for monthly composite CD 0

N\)

CC)

.1 4-I 4-4 1-1.-f 4 I 4 1-1. 4 4 4-1-4 4 Collected by: A. Lw Datu: 01105/2012 BD-22 Composite weekly sample for Monthly Composite for Gamma, OR-B Shipped by: F4 Date: 0l9/2012 Hold for Quarterly H-3 Composite.

Received by: A DBD-22

Environmental, Inc. SR NO. 15556 Midwest Laboratory An Allegheny Technologies Company Shipping Recft 0t°"

MIDWEST LABORATORY 700 LANDWEHR ROAD

  • NORTHBROOK IL 60062-2310 - (847) 584-0700 FAX(847) 584-4517 NOTEII When returning or replacing this material, please reference SIR No. on all documents.

PART I (To be completed by originator) D. Control Data:

A. Description of Items (Include, Quantity, Model No.,

Type, Serial No., and Gov't Property No.)

Vendor P.O. No.

Braidwood:

W.O./Acct. No.

BD-22-2 gallons Location of material Ship no later than Ship via Collect E]

Prepaid 0 No. Pcs.Ictns. __ Cu. Ft.

B. Purpose of Shipment Weight Est. Val.

o Return for credit-No replacement o Return for rework or replacement at Vendors expense.

Part II (To be completed by Shipping Dept.)

o Return for rework or replacement at Environmental, Inc's expense.

Actual method of shipment Federal Express o Furnished on Consignment for use on P.O. No.

O3Other (explain) Date Shipped 01-09-2012 C. Comments or Instructions to Vendor: Collect Prepaid FOB point Waybill No.

Misc.

SHIP TO: TBE L.B.

ORIGINATOR'SINrTALS ATTN:

192 of 238

01/10/12 10:29 STeledyne Brown Engineering Sample Receipt Verification/Variance Report SR #: SR30127 L49059 pj.5 of 7 Client: Exelon Project #: EXO01-3EREMPBRAID-05 LIMS L49059 Initiated By: JSIMMONS Init Date: 01/10/12 Receive Date: 01/10/12 Notification of Variance Person Notified: Contacted By:

Notify Date:

Notify Method:

Notify Comment:

Client Response Person Responding:

Response Date:

Response Method:

Response Comment Criteria Yes No NA Comment 1 Shipping container custody seals present NA and intact.

2 Sample container custody seals present NA and intact.

3 Sample containers received in good Y condition 4 Chain of custody received with samples Y 5 All samples listed on chain of custody Y received 6 Sample container labels present and y legible.

7 Information on container labels Y correspond with chain of custody 8 Sample(s) properly preserved and in NA appropriate container(s) 9 Other (Describe) NA 193 of 238

Raw Data Sheet (rawdata) 02/02/12 10:45 Page I of 1 Work Order: L49059 Customer: Exelon L49059 pg 6 of 7 Analysis: 8-3 Project: EXO01-3EREmKPMD-05 Decay &

Sample ID Run Analysis Reference Volume/ Scavenge Milking Mount Count Detector Total Sample Bkg Bkg Eff. Ingrowth Client ID # Date/Time Aliquot Date/TiMe Date/Time Weight Recovery Date/Time ID Counts dt Counts dt Factor Analyst L49059-1 H-3 (DIST) 0 01-23-12 LS7 144 60 102.6 60 .199 DW 10 22:18 I M BD-22 ml Activity: 1.56E+02 Error: 1.19E+02 MDC: 1.78z+02 pCi/L L49059-1 H-3 (DIST)

(o 0

N)

CA)

Raw Data Sheet (rawdata) 02/02/12 10:45 Page 1 of 1 Work Order: L49059 Customer: Bielon L49059 pg 7 of 7 Analysis: 1-131 Project: 3xOOl-3RREIJBRA33-05 Decay &

Sample ID Run Analysis Reference Volume/ Scavenge Milking Mount Count Detector Total Sample Bkg Bkg Eff. Ingrowth Client ID # Date/Time Aliquot Date/Time Date/Time Weight Recovery Date/Time ID Counts dt Counts dt Factor Analyst L49059-1 1-131 (LOW LVL) 05-jan-12 .0197 89.14 01-31-12 Y4C 189 400 365 000 .289 .107 BP 16:00 4000 16:45 M M 3D-22 ml Activity: 6.62E-02 Error: 3.41E-01 MDC: 6.42E-01 pCi/L L49059-1 1-131 (LOW LVL)

(0 0--

0 N)

CA) 00

47 !L TELEDYNE BROWN ENGINEERING, INC.

AT~duT.Chm4og,,t~.ey 2508 Quality Lane -48995 pg I of 12 Knoxville, TN 37931-3133 865-690-6819 Eric Cieszkiewicz Braidwood Station Exelon Generation Company LLC 35100 South Rte 53, Suite 84 Braceville, IL 60407-9619 Report of Analysis/Certificate of Conformance 01/20/2012 LIMS #: IA8995 Project ID#- EX00I-3E1REMPBRAID-05 Received: 01/06/2012 Delivery Date: 01/20/2012 P.0.1: 01000298 REL.#00018 Release #:

SDG#:

This is to certify that Teledyne Brown Engineering - Environmental Services located at 2508 Quality Lane, Knoxville, Tennessee, 37931, has analyzed, tested and documented samples, as received by the laboratory, as specified in the applicable purchase order.

This also certifies that requirements of applicable codes, standards and specifications have been fully met and that any quality assurance documentation which verified conformance to the purchase order is on file and may be examined upon request.

I hthy cavtie statements are true and correct.

Keith Jeter -

Operations Manager Cross Reference Table Clienit CD) Laboatory IDSttn Difp cal)~

Dec 1IBD-22 L48995-1 BD-22 Method Reference Numbers

[i~irixAnalysis Meioleferncc IWD GAMMA EPA 901.1 WD j GR-B EPA 900.0 IWI IfH-3 (D1ST) EPA 906.0 Page 1 of3 196 of 238

TELEDYNE rq

, BROWN ENGINEERING, INC.

A T.lWdvoT.dMogi..Caý 2508 Quality Lane 2 L48995 pg or.12 Knoxvitte. TN 37931-3133 865-690-6819 This report shall not be reproduced or distributed except in its entirety.

Page 2 of 3 197 of 238

Report of Analysis 01/20/12 10:54 I ;hJELEOYNE BROWN ENGINEERING, INC.

ATWM~oaTsh*avhusCouw" 148995 L48995 pg 3of 12 Braidwood Station EXO0l-3EREMPBRAID-05 Sunp*iile: DBettl 1B-22 CollectSt: 12/01/2011 1M.40 Matrixi DrainkagWate" (WI))

Station: BD-22 CollectStop: 12/29/2011 17:20 Volume: 000E+00

Description:

Receive Date: 01/06/2012 %Moisture:

LIMS Number: .A8995-1 IP Activity lUncertsijuty I Run Aliquot Aliquot Reference I Count! Count Count Radionuclide SP Cane;2S, m MDC URn # Volume Units Date ate Time Units lag Values 7-R- 200 3.3SFW4T FibW ...

  • Ci/U-- . . .- 500 fl-I/13/12 .0o/122 60 -MM..

100- 1 -

Mm M--- T I.

31LW LVL) 269 I -3.44"-U1 1 4012 I.86E-01 i 3.73E-0l pci/I . 3500 I ml 12/29111172 0/11112 500 M I 11 K-A7 .2 7.6h..... O-2236 s0- 3.i441-001" 1" 00 Ci/ I 3599.57 1 ml 12/2911/ 11:20 01I12/12 ISe 4237 IU i N CO-40 F 2007 1-3-E+oi'-1-.-7I 101/12/12 i-i /L7 I 3]599.571--m---'-112./29/ 11 7120 4257 S1e U N FE.65 C.0-5 59 ____ F2071.34fl 2007 4I-LWP1 401+1 2007 1 43- 0713.1200-6.10 1&S+O ~

I 4.11K-O+00-IpCi/L 0--2.1-470 00 iI.39.7 PCi/,L 359.577 F-ml-

  • - 3597--

Iu2I/2-ml 1129/11720 t1/2 I 01/12/12 45 42571 ml.'I 12/29/1117:20 01/12/121 4257. "(* c -I-U"-

e See tI

-No

!22/I12 No I NIO-15 2007 r 6.1-01 1 .(6*-*7*-

7"2.'-+O0 pCi*- 399.57- 1

-20 m Tl112/29/11- 01/12/12 4257 --Se* UI U No-f (0

N.).

0Zo Fi-19 2007 1 5 T'- F9T1--r7+00 I jI - -1 1-20 1 'FNo I -- -s.. TIT - I-Z-15Ci/ 3599.57. m 12/29/ F7:2010112/1271 4257 See U - nS]"

00

[CS-l3 12907-1 -3.71-0-1. '-*I *L.;***1-44730--- pC-l---i 35-F.57-1 ml 12/9/It 17:29101/2/2 4257-7 sF S UI No -

MCS-137 CE-Ni950 2 ioo 01-0 276.6511+006 T 413E00 .PC//L . -. 3599.57 395 5§I mlI 1l2/29/il17:20101/12/12!

iiW 22/11:9iIIi 4257 [SSw 4257 UF) IiNo N

71-134 1-2007 1 4271*111 --- T* 1-3599.57-

ýp,/I- 1 ml !1219/11*17:20 i 01112/1214257.Se -...- .

S-2 ........ 00.T 1.03E+00

. 1 9*-911+0 1 5110050 1 p-C-i--T- 3599.571 ml 112/29/1117:20101/*1- - 1.S*---

s .No I427 I -

F 7fH-232 1 2007 -1i43211+001 Ug313+01 1-2 1+0---

1- --T-j397.57 1 I -2ml i-2911 17:20 1-01/12-12;-4257 I...... o"0--

I-Ing Values U - l ountno"/Aoaly)c notdclteal,< MDC)ot Ils tham2siguto No - Peaknot identified gammaSpoctmrnm c cooce teius mmL.MDCand2 tigma;peakidontifiod(gamnm Acoivity owly) Yea Peakidentifiedin g umsptru-nm U. - Compound/Ana1~l) not deectcd.Peaknot ideailid, butforcedactivityconceatratinoex=,*s MDCntW2sgnm *-* Untkmotherwise noted,theanlytical resuls reporte Htigh - Activityoonccaentrini exceedscustom rerportingvaueo Spec MDCexceeds ciuotuer technicalspecification =erelatedonlyto [besamplestted inthe conditi tihy L. = Lowrecovery n receivedbythulaitablry.

I Hi0breea*v~y MMC-MinitnuntDetestable Conemiuation Bolded text indicates reportable value. Pg3of 3

Composite Report EX001-3EREMPBRAID-05 12/01/2011 12/29/2011 L48995-1 .o000E4" L48995 pg 4of 12 Samiple#/ SItation Done Matrix StMICoIlect S Ceollect Volume Units Shelf Peeceo COMP L48776-1 BD1-22

  • WD 12/01/l) 18:40 12/08/11 15:40 MT2OD 1-49953-1 813-22
  • WD 12/08/1151:40 12/1511 15:40 WH-22C IA9912-1 813-22
  • WD 12/15111 15:40 12/22/11 15:20 W821 C L489G7-l BD3-22
  • WD 12/22/11 15:20 12/29/11 17.20 VIM413 Count- A 199 of 238

Raw Data Sheet (rawdataý 01/20112 1.0,:54 Page I of I Work Order;: L48995 Customer: WErlon L48995 pg 5 of 12 Analysis: GR-B Project: ZX001-3EREMPBRAXD-05 Decay 6 Sample ID Run Analysis Reference Volume/ Scavenge Milking Mount Count Detector Total Sample Bkg Bkg Elf. Ingrowtb CLient ID # Date/TiMe Aliquot Date/Time Date/Time Weight Recovery Date/Time ID Counts dt Counts dt Factor Analyst L48995--1 0D-B .00E+00 ,01-13-12 2D 254 100 135 100 .316 DW Soo 2.2:06 M 1 Dec11 0D-22 ml Activity: 3.398+00 Error: I..12E+00 MDC: 1.54E+03 pCi/L L48995-1 Ga-B C-C P'O 0

cN

Raw Data She0t(rawdata) 01/20/12 T6:5'4 Page I of I Work Order: L48.95 Cutoumert Eelon L48995 pg 6 of 12 Analysis: H-3 Project: ZXOOI-3RMOSRAlM-05 Decay &

Sample 1D Run Analysis Reference Volume/ Scavenge Milking Moent Count Detector Total Sample Bkg Bkg EOf.Ingrowth Client 'D I Date/Time Aliquot Data/Time Date/Time Weight Recovery Date/Time ID Counts dt Counts dt Factor Analyst

. 40995-1

.... 4-3 (DISTI .D0k12 0.. 01-12-212.0 12... . 40 2 -

10 20:53 ii Decti BD-22 mt Activity: 1.02E-02 Error: 1.01S0D2 MDC: 1. 569+02 PCi/t L49995-1 113 (DIST)

N) 0 0

N)

GD w3

Raw Data Sheet (rawdata) 011/20/12 10:54 Page 1 ot I Work Ordet: L 48995 Customer: Exlon L48995 pg 7 of 12 Analysis: 1: -131 Project: aX001-3EEMUpMaID-05 Decay Sample ID Ru. Analysis Reference Volume/ Seavenge Milking Mount Count Detector Total Sample Dkg 9kg E+/-f. Ingrowth Client ID 4 Date/Time Aliquot Date/Time Date/Time Weight Vecovery Date/Time I1 Counts dt Counts dt Factor Analyst 0-11-(L-- ("L'-L29-decY-11-000 ... . .020- 8. F- 0-1---12 ....... 6. 500 372 . 00 .3 .182 BF 17:20 3500 16:22 M M Decll aD-22 ml Activity: -3.44E-01 Error: 1,865-01 MDC; 3.73E-01 pCi/L L489895- 1-131

LOWLVL)

N) 0 0

NJ Co) 00

Sec. Rvjiew: Analys L48995 pg.of 8 12 VAX/VMS Teledyne Brown Eng. Laboratory Gamma Report: 12-JAN-2012 11:33:04.72 TBEO1 P-20651A HpGe ******* Aquisition Date/Time: 12-JA.N-2012 10:22:00.51 LIMS No., Customer Name, Client ID: L48995-1 WD BRAIDWOOD STATION Sample ID 01L48995-1 Smple Date: 29-DEC-2011 17:20:00.

Sample Type WD Geometry  : 0135L121508 Quantity 3.59957E+00 1 BKGFILE  : 01BG120911MT Start Channel 90 Energy Tol  : 2.00000 Real Time : 0 01:10:57.56 End Channel 4090 Pk Srch Sens: 5.00000 Live time : 0 01:10:56.97 MDA Constant 0.00 Library Used: LIBD Pk It Energy Area Bkgnd FWHM Channel %Eff Cts/Sec %Err Fit 1 1 66.49* 35 117 0.97 133.08 4.78E-01 8.15E-03 57.5 8. 74E-01 2 1 92.66* 6 116 1.16 185.35 1. 28E+00 1.47E-03336.3 2. OOE+00 3 1 141.89* 114 171 6. 96 283.67 1. 98E+00 2.68E-02 30.6 2. 57E+00 4 1 185.57* 6 70 1 .02 370.92 1. 98E+00 1.39E-03280.3 1. 78E+00 5 1 198.61* 30 94 1.57 396.96 1. 95E+00 7.14E-03 64.8 3. 03E+00 6 1 238.71* 15 75 1.12 477.05 1.81E+00 3.41E-03116.1 1. 25E+00 7 1 352.28* 17 39 2.38 703.94 1.44E+00 4.08E-03 76.2 4. 87E+00 8 1 609.12* 30 14 1.55 1217.21 9.83E-01 7.02E-03 33.4 2.19E+00 9 1 1460.59* 7 10 2.22 2920.16 5.37E-01 1.56E-03116.0 8. OOE-01 Flag: "*" = Peak area was modified by background subtraction Nuclide Line Activity Report Nuclide Type: natural Uncorrected Decay Corr 2-Sigma Nuclide Energy Area %Abn %Eff pCi/l pCi/l %Error K-40 1460.81 7 10.67* 5. 372E-01 2.040E+01 2.040E+01 231.94 RA-226 186.21 6 3.28* 1. 984E+00 1.601E+01 1.601E+01 560.65 TH-228 238.63 15 44.60* 1. 808E+00 3.179E+00 3.223E+00 232.15 240.98 3.95 1. 800E+00 Line Not Found U-235 143.76 114 10. 50* 1. 976E+00 9.685E+01 9.685E+01 61.15 163.35 4.70 2. 015E+00 Line Not Found 185.71 6 54.00 1. 984E+00 9.727E-01 9.727E-01 560.65 205.31 4.70 1. 927E+00 Line Not Found Flag: "*" = Keyline 203 of 238

Summary of Nuclide Activity Page: 2 Sample ID : 01L48995-1 Acquisition date  : 12- -919*-:122:00 Total number of lines in spectrum 9 Number of unidentified lines 5 Number of lines tentatively identified by NID 4 44.44%

Nuclide Type  : natural Uncorrected Decay Corr Decay Corr 2-Sigma Nuclide Hlife Decay pCi/l pCi/l 2-Sigma Error %Error Flags K-40 1. 28E+09Y 1.00 2.040E+01 2.040E+01 4.731E+01 231.94 RA-226 1600.OOY 1.00 1.601E+01 1.601E+01 8.978E+01 560.65 TH- 228 1. 91Y 1.01 3.179E+00 3. 223E+00 7.482E+00 232.15 U-235 7.04E+08Y 1.00 9.685E+01 9.685E+01 5.922E+01 61.15 Total Activity  : 1.364E+02 1.365E+02 Grand Total Activity  : 1.364E+02 1.365E+02 Flags: "K" = Keyline not found "M" = Manually accepted "E" = Manually edited "A" = Nuclide specific abn. limit 204 of 238

Unidentified Energy Lines Pa 3 Sample ID  : 01L48995-l Acquisition date  ; 12-bAW0M W2:00 It Energy Area Bkgnd FWHM Channel Left Pw Cts/Sec %Err %Eff Flags 1 66.49 35 117 0.97 133.08 129 8 8.15E-03 **** 4.78E-01 1 92.66 6 116 1.16 185.35 182 9 1.47E-03 l.28E+00 1

1 198.61 30 94 1.57 396.96 392 10 7.14E-03

  • 1.95E+00 1 352.28 17 39 2.38 703.94 700 9 4.08E-03 **** 1.44E+00 1 609.12 30 14 1.55 1217.21 1212 9 7.02E-03 66.9 9.83E-01 Flags: "T" = Tentatively associated Summary of Nuclide Activity Total number of lines in spectrum 9 Number of unidentified lines 5 Number of lines tentatively identified by NID 4 44.44%

Nuclide Type : natural Wtd Mean Wtd Mean Uncorrected Decay Corr Decay Corr 2-Sigma Nuclide Hlife Decay pCi/l pCi/l 2-Sigma Error %Error Flags K-40 1.28E+09Y 1.00 2.040E+01 2.040E+01 4.731E+01 231.94 TH-228 1.91Y 1.01 3.179E+00 3 . 223E+00 7.482E+00 232.15 U-235 7.04E+08Y 1.00 9.727E-01 9. 727E- 01 54.53E-01 560.65 Total Activity  : 2.455E+01 2.459E+01 Grand Total Activity  : 2.455E+01 2.459E+01 Flags: "K" = Keyline not found "M" = Manually accepted "E" = Manually edited "Al = Nuclide specific abn. limit Interference Report Interfering Interfered Nuclide Line Nuc lide 1,ine U-235 185.71 RA -226 18 6.21 Combined Activity-MDA Report Identified Nuclides Activity Act error MDA MDA error Act/MDA Nuclide (pci/l) (pCi/l)

K-40 2.040E+01 4.731E+01 3. 664E+01 0. OOOE+00 0.557 TH-228 3.223E+00 7.482E+00 9. 590E+00 0. OOOE+00 0.336 U-235 9.727E-01 5,453E+00 3. 414E+01 0. OOOE+00 0.028 Non-Identified Nuclides ----

Key-Line Activity K.L. Act error MDA MDA error Act/MDA Nuclide (pCi/l) Ided (pCi/i) 205 of 238

BE- 7 5. 628E+00 2.359E+01 3. 939E+01 0.10%NM II (f 120 .143 NA-24 -5.753E+05 8.985E+06 1.482E+07 0.OOOE+00 -0.039 CR-51 -3.161E+01 3.286E+01 4. 835E+01 0.000E+00 -0.654 MN-54 -1.156E+00 2. 691E+00 4. 114E+00 0.OOOE+00 281 CO-57 5. 060E-01 3. 122E+00 5.355E+00 0.OOOE+00 0.094 CO-58 -1.392E+00 2. 727E+00 4. 079E+00 0.OOOE+00 -0,341 FE-59 6.780E-01 4. 796E+00 8. 080E+00 0.OOOE+00 0.084 CO-60 3. 433E-01 3. 123E+00 5.164E+00 0.000E+00 0.066 ZN- 65 -4. 145E+00 6. 101E+00 8.504E+00 0.OOOE+00 -0.487 SE-75 2.305E+00 3.893E+00 6.784E+00 0.000E+00 0.340 SR-85 -9. 802E+00 4.493E+00 5.594E+00 0000E+00 -1.752 Y-88 2. 589E+00 3. 280E+00 6.362E+00 0.OOOE+00 0.407 NBE-94 1. 375E+00 3.312E+00 5.766E+00 0.000E+00 0.238 NB-95 -2.456E-01 2. 815E+00 4.606E+00 0.OOOE+00 -0.053 ZR- 95 -9.204E-01 4. 942E+00 7.949E+00 0.OOOE+00 -0.116 MO- 99 6. 847E+01 5. 882E+02 9.976E+02 0.OOOE+00 0.069 RU-103 6.615E-01 4. 170E+00 6.821E+00 0.OOOE+00 0.097 RU-106 -9.294E+00 2. 825E+01 4.547E+01 0.0OOE+00 -0.204 AG-II0m 1.157E+00 2. 433E+00 4.371E+00 0.OOOE+00 0.265 SN-113 1.296E+00 4. 071E+00 6. 851E+00 0OOOE+00 0.189 SB- 124 2.053E+00 3. 317E+00 5.585E+00 0.000E+00 0.368 SB-125 -3.432E+00 6. 961E+00 1. 042E+01 0,000E+00 -0.329 TE-129M -1.015E+01 4. 377E+01 6.852E+01 0.OOOE+00 -0.148 1-131 -3.563E+00 8.865E400 1.376E+01 0.OOOE+00 -0.259 TE-132 1. 134E+01 4.543E+01 7. 712E+01 0.OOOE+00 0.147 BA-133 2. 134E+00 4.342E+00 6. 668E+00 0.OOOE+00 0.320 CS-134 -3.672E-01 3.116E+00 4.466E+00 0.OOOE+00 -0.082 CS-136 2. 955E+00 5.443E+00 9. 776E+00 0.OOOE+00 0.302 CS-137 1. 034E+00 2.909E+00 5. 112E+00 0.OOOE+00 0.202 CE-139 -3.673E-01 3.040E+00 5. 069E+00 0.OOOE+00 -0.072 BA- 140 5. 077E+00 2.225E+01 3. 670E+01 0.OOOE+00 0.138 LA-140 5.485E+00 6.201E+00 1.226E+01 0.0OOE+00 0.447 CE-141 9. 001E-01 6.650E+00 1. 031E+01 0.OOOE+00 0.087 CE-144 -1.271E+01 2.744E+01 3. 927E+01 0.OOOE+00 -0.324 EU-152 -3.734E+00 9.209E+00 1.442E+01 0.OOOE+00 -0.259 EU-154 -4. 904E-01 6.426E+00 1. 085E+01 0.OOOE+00 -0.045 RA-226 1. 601E+01 8.978E+01 1. 377E+02 0.OOOE+00 0.116 AC-228 4. 943E+00 1.132E+01 2. 120E+01 0.OOOE+00 0.233 TH-232 4. 920E+00 1.127E+01 2. 111E+01 0.OOOE+00 0.233 U-238 -1. 201E+02 3.410E+02 5. 685E+02 0.OOOE+00 -0.211 AM-241 2.929E+01 4.468E+01 7. 584E+01 0.OOOE+00 0.386 206 of 238

A, 01L48995-1 ,01/12/2012 11:33,12/29/2011 17:20, 3.600E+00 L48995-1 WD BR B,01L48995-1 ,LIBD ,01/12/2012 09:47,0135Ljl9g 12 of 12 C,K-40 ,YES, 2.040E+01, 4.731E+01, 3.664E+01,, 0.557 C,TH-228 ,YES, 3.223E+00, 7.482E+00, 9.590E+00,, 0.336 C,U-235 ,YES, 9.727E-01, 5.453E+00, 3.414E+01,, 0.028 C,BE-7 ,NO 5.628E+00, 2.359E+01, 3.939E+01,, 0.143 C,NA-24 ,NO -5.753E+05, 8.985E+06, 1.482E+07,, -0.039 C,CR-51 ,NO -3.161E+01, 3.286E+01, 4.835E+01,, -0.654 C,MN-54 ,NO -1.156E+00, 2.691E+00, 4.114E+00,, -0.281 C,CO-57 ,NO 5.060E-01, 3.122E+00, 5.355E+00,, 0.094 C,CO-58 ,NO -1.392E+00, 2.727E+00, 4.079E+00,, -0.341 C,FE-59 ,NO 6.780E-01, 4.796E+00, 8.080E+00,, 0.084 C,CO-60 ,NO 3.433E-01, 3.123E+00, 5.164E+00,, 0.066 C,ZN-65 ,NO -4.145E+00, 6.101E+00, 8.504E+00,, -0.487 C,SE-75 ,NO 2. 305E+00, 3.893E+00, 6.784E+00,, 0.340 C,SR-85 ,NO -9.802E+00, 4.493E+00, 5.594E+00,, -1.752 C,Y-88 ,NO 2.589E+00, 3.280E+00, 6.362E+00,, 0.407 C,NB-94 ,NO 1.375E+00, 3.312E+00, 5.766E+00,, 0.238 C,NB-95 ,NO -2.456E-01, 2.815E+00, 4.606E+00,, -0.053 C,ZR-95 ,NO -9.204E-01, 4.942E+00, 7.949E+00,, -0.116 C,MO-99 ,NO 6.847E+01, 5.882E+02, 9.976E+02,, 0.069 C,RU-103 ,NO 6.615E-01, 4.170E+00, 6.821E+00, 0.097 C,RU-106 ,NO -9.294E+00, 2.825E+01, 4.547E+01, -0.204 C,AG-0lrn ,NO 1.157E+00, 2.433E+00, 4.371E+00, 0.265 C,SN-113 ,NO 1.296E+00, 4.071E+00, 6.851E+00,, 0.189 C,SB-124 ,NO 2. 053E+00, 3.317E+00, 5.585E+00,, 0.368 C,SB-125 ,NO -3.432E+00, 6.961E+00, 1.042E+01,, -0.329 C,TE-129M ,NO -1.015E+01, 4.377E+01, 6.852E+01,, -0.148 C,1-131 ,NO -3.563E+00, 8.865E+00, 1.376E+01,, -0.259 C,TE-132 ,NO 1.134E+01, 4.543E+01, 7.712E+01,, 0.147 C,BA-133 ,NO 2.134E+00, 4.342E+00, 6.668E+00,, 0.320 C,CS-134 ,NO -3.672E-01, 3.116E+00, 4.466E+00,, -0.082 C,CS-136 ,NO 2.955E+00, 5.443E+00, 9.776E+00,, 0.302 C,CS-137 ,NO 1.034E+00, 2.909E+00, 5.112E+00,, 0.202 C,CE-139 ,NO -3.673E-01, 3.040E+00, 5.069E+00,, -0.072 C,BA-140 ,NO 5. 077E+00, 2.225E+01, 3.670E+01,, 0.138 C,LA-140 ,NO 5.485E+00, 6.201E+00, 1.226E+01,, 0.447 C,CE-141 NO 9.001E-01, 6.650E+00, 1.031E+01,, 0.087 C,CE-144 NO -1.271E+01, 2.744E+01, 3.927E+01,, -0.324 C,EU-152 NO -3.734E+00, 9.209E+00, 1.442E+01,, -0.259 C,EU-154 NO -4.904E-01, 6.426E+00, 1.085E+01,, -0.045 C,RA-226 NO 1.601E+01, 8.978E+01, 1.377E+02,, 0.116 C,AC-228 NO 4.943E+00, 1.132E+01, 2.120E+01,, 0.233 C,TH-232 NO 4.920E+00, 1.127E+01, 2.111E+01,, 0.233 C,U-238 NO -1.201E+02, 3.410E+02, 5.685E+02,, -0.211 C,AM-241 NO 2. 929E+01, 4.468E+01, 7.584E+01,, 0.386 207 of 238

W, TELEDYNE fAb,,

F BROWN ENGINEERING, INC.

ATek,*dym* ACs pw, 2508 Quality Lane 1,49145 pg I of 7 Knxvile, TN 37931-3133 865-690-6819 Eric Cicszkiewicz Bridwood Station Exelon Generation Company UJC 35100 South Rte 53, Suite 84 Braceville, IL 60407-9619 Report of Analysis/Certificate of Conformance 02/09/2012 LIMS #: LA9145 Projec ID)#: EXOO1-3EREMPBRAID-05 Received: 01/17/2012 Delivery Date: 02/21/2012 P.O.#: 01000298 REL.#00018 Release #:

SDG#:

This is to certify that Teledyne Brown Engineering - Environmental Services located at 2508 Quality Lane, Knoxville, Tennessee, 37931, has analyzed, tested and documented samples, as received by the laboratory, as specified in the applicable purchase order.

This also certifies that requirements of applicable codes, standards and specifications have been fully met and that any quality assurance documentation which verified conformance to the purchase order is on file and may be examined upon request.

I hereby certify that the above statements are true and correct Keith jetera Operations Manager Crows Reference Table Client ID Laboratory ID Station I)ifapplicable)

BD-22 L49145-1 I BD-22 -

Mehod Reference Numbers Matrx Analynsis- Method Reference WI H-3 (DIST) IEPA 906.0 This report shall not be reproduced or distributed except in its entirety.

Page I of 2 208 of 238

Report of Analysis WL TELEDYNE BROWN ENGINEERING, INC.

02/09/12 10:11 AT.44Tlnlah* Company L49145 L49145 pg 2 of 7 Braidwood Station EX001-3EREMPBRAID-05 Sample ID: BD-22 Collect Start: 01105/2012 16:00 Matrix: Drinking Water (WD))

Station: BD-22 Collect Stop: 01/12/2012 17:00 Volume:

Description:

Wilmington Receive Date: 01/17/2012  % Moisture:

LfMS Numrber: IA9145-t SRadiouelide Activity I Uncertainty ' D Run Aliquot Aliquot Reference CounttI Count i Count SACone 2tSigmal Unts ft Valu Time nits F 1130S)2011

[!_.!3..._.[*

W _-_V-- .... _ .1 L*2cnt:

2.0E1)

-j.46E-01 I2.32E-01 I tM I.1+2 4.04&g01 piI l i.u +5+2

  • p(i.l ._ ._+/-__.!* _. _.ml_. 1/12/1_.2.17.:.. 02107/_12...80. .. M .J__ t _. __*

_0 01poi

.. Comment:L. I Weekl ~compositc-hold frmnhj__vst 0

0 COZ flag Values U = Compouund/Analyte not detected (< MDC) or less than 2 sigma No - Peak not identified in gamma spectrum

+ Activity concentration exceeds MDC and 2 sigma; peakidentifitl(ganman only) Yes - Peak identified in gammia spectrum U- = Compound/Analyte not detected, Peaknot identilied, bit forced activity concentration exceeds MDC mid 2 sigma *n*oUnless otherwise noted, the analytical reaults reported fligh = Activity concentration exreedscustomer reporting value Spec - MDC exceeds customer technical specification am related only to the samples tested in the condition they L - Low recovery are received by the lahoratory.

H - High recovery MDC - Minimum tWeectable Concentration Boided text indicates reportable value. Page2 of 2

L49145 pg 3 of 7 Breidwood Generating Station Sample CoulectlionrRecelpt Sheet Vj,t42" Public Water Sample EXELON NUCLEAR Samrple ,eerple Loib.No. Clit ID itation Code Medium Start dote Slo thee S dotte Stp tice Size Carenmcnot 11-3(DIST),I- 131 Wilmington 13-22 DW 01/05/20112 16.00 0l/12'012 17:00 2 al. (LOW I.VL) Weekly composito-hold for monthly composite K) 0 K)

(00 Colleoned by: A. Jlewis Date: 0112,12012 B1D-2.2Composite weekly sample for Monthly Composite for Gommra.

rR-IB Shipped by: kK Dole: 0 120 Hold for Quarterly H-3 Comrposite.

Received by: "D'r e:

vaw:8D.2

Environmental, Inc. SR NO. 15_574 _

Midwest Laboratory An Allegheny Technologies Company Shipping Reqttof7 MIDWEST LABORATORY 700 LANDWEHR ROAD

  • NORTHBROOK. It.88062-2310 - (847) 584-0700 FAX(847)564-4517 NOTE!! When returing or replacing this material, please reference SIR No. on all documents.

PART I (To be completed by originator) D. Control Data:

A. Depcription of items (Include, Quantity, Model No.,

Type, Serial No., and Gov't Property No.)

Vendor P.O. No.

Braid0yood: _ ___

BP-22 W.OJAcct. No.

Location of material Ship no later than ..

Ship via Cotiact []

Prepaid F1 B. Purpose of Shipment: No. Pcs.lcens. Cu. Ft.

Weight - Est. Val.

o3 Return for credit-No replacement:

Part II (To be completed by o Return for rework or replacement at Vendor's expense.

Shipping Dept.)

o Return for rework or replacement at Environmental, Inc's expense.

Actual method of shipment f reSS 01 Furnished on Consignment for use on P.O. No.

03 Other(explain) Date Shipped 1-6-2012.

C. Comments or instructions to Vendor: Collt -t Prepaid FOB point Waybill No.

Misc. -

SHIP TO: TBE L.B.

GRIGINA-109SINITIALS ATTN:

211 of 238

01/17/12 14:05 Teledyne Brown Engineering Sample Receipt Verification/Variance Report SR #: SR30200 Client: Exelon Project 0: EX001-3EWMPSRAID-05 L* P ,945 Initiated By: JSIMMONS Init Date: 01/17/12 Receive Date: 01/17/12 Notification of Variance Person Notified: Contacted By:

Notify Date:

Notify Method:

Notify Comment:

Client Response Person Responding:

Response Date:

Response Method:

Response Comment Criteria Yes No NA Comment 1 Shipping container custody seals present NA and intact.

2 Sample container custody seals present NA and intact.

3 Sample containers received in good Y condition 4 Chain of custody received with samples Y 5 All samples listed on chain of custody Y received 6 Sample container labels present and Y legible.

7 information on container labels Y correspond with chain of custody 8 Sample(s) properly preserved and in NA appropriate container(s) 9 Other (Describe) NA 212 of 238

Raw Data Shat (rawdata) 02/09/12 10:11 Page I of I WOX Order: L49145 Customer: UEmaon L49145 pg 6 of 7 Analysis: 9-3 Project: EXoO1-3zRflPaRAiv-q5 Decay &

Sample ID Run Analysis Reference Volume/ Scavenge Milking Mount Count Dotector Total Sample Bkg Bkg Eff. Ingrowth Client ID # Date/Time Aliquot Date/Time Date/Time Weight Recovery Date/Time ID Counts dt Counts dt Factor Analyst

... 01- - . 1-,--

.01--2-6 -*-1*

2 LS8 ......- 9-3... 6..0-.. 130.2 .. 6 .234 05 10 22:26 M M BD-22 mi.

Activi-tY; 2.0zm.+02 Erroz: 1.15Efl,02 MDC; 1.71E+02 pCi/L L49145-1 u-3 (121ST)

N) co 00

R~aw Data Sheot Crawdata) 102/09/12 10:11. Page I of 1 Work Order: L49145 Customer: Exelon L49145 pg 7 of 7 Analysis: 1-131 Project: EX001-3BERMPBIRAID-05 Decay &

Sample ID Run Analysis Reference Volume./ Scavenge Milking Mount Count Detector Total Sample 5kg Bkg Eff. Ingrowth Client ID

  • Date/Time Aliquot Date/Time Date/Time Weight Recovery Date/Time ID Counts dt Counts C3t Factor Analyst 1.0212 95.93 02-07-12 Y3 295 80* 1729600 .3 .109 BP 17:00 4000 16:50 N M BD-22 ml Activity: -2.46E-01 Error: 2.32E;-01 MDC: 4.043-01 pCi/I L49145-1 1-131 (LOW LVL)

N) 0 K) 0:1

,AIL4k TELEDYNE 01 BROWN ENGINEERING, INC.

2508 Quality L49228 pg I of 7 Knoxville, TN 37931-3133 865-690-6819 Eric Cieskiawcz Brmidwood Station Exelon Generation Company LLC 35100 South Rte 53, Suite 84 BRmcville, IL 60407-9619 Report of Analysis/Certificate of Conformance 02/09/2012 LIMS #: LA9228 Project ID#: EX001-3EREMPBRAID-05 Received: 01/24)2012 Delivery Date: 0212812012 P.O.#: 01000298 REL#00018 Release #:

SDG#:

This is to certify that Teledyne Brown Engineering - Environmental Services located at 2508 Quality Lane, Knoxville, Tennessee, 37931, has analyzed, tested and documented samples, as received by the laboratory, as specified in the applicable purchase order.

This also certifies that requirements of applicable codes, standards and specifications have been fully met and that any quality assurance documentation which verified conformance to the purchase order is on file and may be examined upon request.

I hereby certify that the above statements are true and correct.

Keith Jeter Operations Manager CrossReference Table

[Client ID l~aboratory 0) ___StationID('ff~appliecable]

BD-22 L49228-i BD BD-22 Method Reference rumbers Matrix Analysis Method Reference iWD H-3 (DIST) EPA 906.0 This report shall not be reproduced or distributed except in its entirety.

Page I of 2 215 of 238

Report of Analysis 7 b TELEDYNE BROWN ENGINEERING, INC.

02/A9/12 10:12 ATetedyneTocmtno-lqaCompany L49228 L49228 pg 2 of 7 Braidwood Station EX00 i-3EREMPBRAID-05 Sample ID:

Station:

81 BI)-22 j-22 Collect St: 01/l2/2012 17:00 Collect Stop: 0 119l2012 0 17:40 Matrix:

Volu e:

0 Drinking Water (WD)

Description:

W ilmingtou Receive Date: 01 /24/2012  % Moisture:

LMS Number: L449228-1I Activity Uncertainty Run Aliquot Aliquot I Reference Count Count Radionudide

-2011 ..- ,.54+O _ .6813.iL to ml _ 60. M U __L__

11-13(tOW LVL N)

CA)

'00 Flag Values 13 - Compound(Analyte not detected (< M4D) or less than 2 sigma No = Peak not identified in gamma spectrum

+ - Activity concentration exceeds MDC and 2 sigma; peak idcntified(garnma only) Yes - Peak identifed in gamma spectrum U* = Compound/Analyte not detected. Peak not identified, but forced activity concentration exceeds MDC and 2 sigma lighb Activity concentration exceeds customer reporting value ... Unless otherwise noted, the analytical results reported Spec - MDC exceeds customer technical specification are ratced only to the samples tested in the condition they L = Low rTovery ae received by the laboratory.

it . High recovery MDC - Minimum Detectable Concentration Iolded text indicates reportable value.

Page 2 uf12

L L49228 pg 3 of 7 Snaldwcoc Generating Station Sample Collectlion/Receipt Sheet W ýJAl2- ý1 Public Water Sample EXELON NUCLEAR Sample Sample Lab. No. Client ID Statifn Code Medium Starndam Start time Stop date Sv 6- Size Analysis Conments H-3 (DIST),1-131 Wilminipon BD-22 OW 01112/2012 17:00 01/19/2012 17:40 2 gat (LOW IVL) Weekly composite-hold for monthly Compostec

.... r 0

00)

Date: 01/19/2012 BD-22 Composite weekly sample for Monthly Composite for Gamma, OR-B 47-6 Date: 01123M]2 Hold for Quarterly 11-3Composite.

Rlkceived b --.

  • 42 Date: it I /IR, -22 1~'* t)0/4

(

Environmental, Inc. SR NO. 558I Midwest Laboratory An Allegheny Technologies Company Shipping Req dsto'7 MIDWESTLABORATORY 700 LANDWEHR ROAD. NORTHBROOK. IL6OD62-2310* (847) 564-0700 FAX(847) 5e4-4517 NOTE!! When returning or repladng this material, please reference SIR No. on all documents.

PART I (To be completed by originator) D. Control Data:

A. Description of Items (Include, Quantity, Model No.,

Type, Serial No., and Gov't Property No.)

Vendor P.O. No._

Braidwood:

BD-22: WO.OAccl. No.

5 ..qallVllns v, welI water f'dl fllmllo es Location of material Ship no later than Ship via Collect 1 Prepaid LI

8. Purpose of Shipment: No. Pcs.lctns. ____- Cu. Ft.

Weight Est. Val.

O Return for credIt-No replacement:

Part II (To be completed by O Return for rework or replacement at Vendor's expense.

Shipping Dept)

O Return for rework or replacernent at Environmental, Inc's expense.

Ac*ual method of shipment Federal Express 0 Furnished on Consignment for use on P.O. No.

O1Other (explain) Date Shipped 01-23-2012 C. Comments or Instructions to Vendor: Collect Prepaid ..-...

FOB point Waybill No.

Misc.

SHIP TO: TBE L.B ORJGSIATORS INIrIALS ATTN:

218 of 238

01/25/12 09:-04 Teledyne Brown Engineering Sample Receipt Verification/Variance Report SR #: SR30281 1,49212&P0 5

  • Client: Exelon Project #: EX001-3EREMPBRAID-05 MS ILALS Initiated By: JSIMMONS Init Date: 01/25/12 Receive Date: 01/24/12 Notification of Variance Person Notified: Contacted By:

Notify Date:

Notify Method:

Notify Comment:

Client Response Person Responding:

Response Date:

Response Method:

Response Comment Criteria Yes No NA Comment I Shipping container custody seals present NA and intact.

2 Sample container custody seals present NA and intact, 3 Sample containers received in good Y condition 4 Chain of custody received with samples Y 5 All samples listed on chain of custody Y received 6 Sample container labels present and Y legible.

7 Information on container labels Y correspond with chain of custody 8 Sample(s) properly preserved and in NA appropriate container(s) 9 Other (Describe) NA 219 of 238

Raw Data Sheet (rawdata)

Work Order: L49228 Customer: EXQIon L49228 pg 6 of 7 Analysis;: H-3 Project: FXOO1-3EPJ!MBRFAID-O05 Decay &

Sample ID Run Analysis Beference Volume/ Scavenge Milking Moun t Count Detector Total Sample Bkg 13kg kff. Ingrowth C,lieni:tD # Date/Time Aliquot Date/Time Date/Time Weight Recovery Oat:O/TimG ID Counts dt Counts dt Factor Analyst

,DST 0 02-01-1. LSS i 04 0 12.. 60 .3 W 10 14:54 M M 8D-22 ml ActlviLy: -6.545F+01 Error: 9.68E+01 HDC; 1.66E+02 pCi/L L49228-1 H-3 (DIST) 0 0

OD

Raw Data Sheet (rawdata) 02/09/12 10:12 Page I of I Work Order: L49228 Customer: Exelon L49228 pg 7 of 7 Analysis: 1-131 Project: Er=01-33RdPBPRAIO-O5 Decay &

Sample ID Run Analysis Reference Volume/ Scavenge Milking Mount Count Detector Total Sample Bkg Bkg Eff. Ingrowth Client 10 0 Date/Time Aliquot Date/Time Date/Time Weight Recovery Date/Time ID Counts dt Counts dt Factor Analyst L49226-I 1-131 (Low LVI.)19-jan.-12 0275 -24,43 02-07-12 T1I 166 400 349 600 .294 .197 BP 17:40 4000 16:50 M M BD-22 ml Act.vlty; -3.32E-02 Error: 1.24E-01 MOC - W.40E-01 pCi/L L49228-I 1-131 (LOW LVI.)

0 W

cn 0O

, ~ TELEDYNE BROWN ENGINEERING, INC.

AfT~ch-TkknC-"nyW L49281 1 of 7 2508 Quality Law Knoxville, TN 37931-3133 865-690-6819 Eric Cicszkiewicz Binidwood Station Exelon Generation Company LLC 35100 South Rte 53, Suite 84 Braceville, IL 60407-9619 Report of AnalysislCertificate of Conformance 02/16/2012 LIMS #: IA9281 Project ID#: EX001-3EREMPBRAID-05 Received: 01131/2012 Delivery Date: 03106/2012 P.O.#: 01000298 REL.#00018 Release #:

SDG#:

This is to certify that Teledyne Brown Engineering - Environmental Services located at 2508 Quality Lane, Knoxville, Tennessee, 37931, has analyzed, tested and documented samples, as received by the laboratory, as specified in the applicable purchase order.

This also certifies that requirements of applicable codes, standards and specifications have been fully met and that any quality assurance documentation which verified conformance to the purchase order is on file and may be examined upon request.

I hereby certify that the above statements are true and correct.

Keith Jeter C Operations Manager (ross Reference Table Client ID Laboratory ID Station ID( oiable) pif __ __ _

BD-22 LA9281-1 j lD-22 Method Reference NAumbers

!Mt Analysis Method~eeec

[WD i H-3 (DIST) EPA 906.0 This report shall not be reproduced or distributed except in its entirety.

Page I of 2 222 of 238

Report of Analysis -w TELEDYNE BROWN ENGINEERING, INC.

02116112 08:48 ATaladymn "Tchtnaliloas Compayw L49281 Braidwood Station LXO0 !-3EREMPBRAID-05 Sample ID: BD-22 Colloct Start: 01/ 19/2012 17:40 Matrix: Drinking Water (Wi))

Station: 131D-22 CollectStop: 01/26/2012 17:00 Volume:

)cscription: Wilmington Receive Date: 01/31/2012  % Moisture:

LIMS Numbe: 149281-1 S Activity Uncert"nty Run Aliquot Aliquot Reference Count Count Count Radionuclide sej Con 2 Sigma MDC Units # Volume Units Date Date Time Units Flag Values Ir-(E+01 i 1.04E,+02 -1. 02 pCi/L *- 10 ml 02 09/1 60 Mr- -

1113 (OWLV) 2012 L-1,43"i-2 3.06E 5.41"lO pCi/i. ] 40 l 1/62170 0/14/12 10 M Commuent t Wet~~st-lodfrmnh~opst __

K)

N)

NJ 00 Cr)

Flag Values U - Coarpound/Analyte not detected (< MICX,) or less than 2 sigma No = Peak not identified in gamma spectrum 4- - Activity concentration exceeds M1%DC and 2 sigma; peak identified(gamma only) Yes . Peak identified in gamma spectrum U* - Compound/Analyte not detected. Peak not identified, but forced activity concentration cxceds MDC and 2 sigma 1-igh Activity concentration exceeds customer reporting value **** Unless otherwise noted, the analytical results reported Spec - MDC exceeds customer technical specification are related only to the samples tested in the condition they L - Low recovery are received by the laboratory. *o

-1 - High recovery eo MDC - Minimum Detectable Concentration o Boided text indicates reportable value.

-q Page 2 ol"2

L~ ý-

Braidwood Generating Station Sample Collectlon/Racelpt Sheet Public Water Sample EXELON NUCLEAR Sample SePle Lob. Sa. Client 1I) Station Code Medium Stet date Sun o¢ S Sttme tie Size A..alytL, Cornmcnts It-3 (DISI),-t3 I Wilmington f)D-22 DW 01IL9/2012 1740 01/26/2012 17:00 2 gal, (LOW LVL) Weekly cornposite-hold for monthly compotihe N)

N) 00 02 Collected by A et I' Date: .01/26/2012 HD-22 Composite weekly sample for Monthly Composite for Gamnta. GR-B Shinped by: -ed;- ' ) , J-- V Date: 0 1 3202 Hoid for Quarterly H-3 Composite.

Rccciýcd by: lxffý Doate: YB-2 U

1/

0

Environmental, Inc. SR NO., o58, 1401[7 Midwest Laboratory An Allegheny Technologies Company Shipping Request MIDWEST LABORATORY 700 LANDWEHR ROAD

  • NORTHBROOK if.60062-2310 * (847) 564-0100 FAX(847) 584-4517 NOTEII When returning or replacing this material, please reference S/R No. on atl documents.

PART I (To be completed by originator) D. Control Data:

A. Description of Items (Include, Quantity, Model No.,

Type, Serial No., and Gov't Property No.)

Vendor P.O. No.

W.O./Acct No.

2_gallons__BOD-22 Location of material Ship no later than Ship via Collect L0 Prepaid LI No. Pcs./ctns. -- - -- Cu. Ft.

B. Purpose of ShIpment:

Weight -_ Est. Val.

O1Return for credit-No replacement:

Part II (To be completed by O Return for rework or replacement at Vendor's expense. Shipping Dept.)

o Return for rework or replacement at Environmental, Inc's expense.

Actual method of shipment .ederal Expess o Furnished on Consignment for use on P.O. No.

o Other (explain) ..... .. .... ..... .... Date Shipped 01-30-2012 C. Comments or Instructions to Vendor: Collect - Prepaid FOB point Waybill No.

Misc_

SHIP TO: TBE L.B.

ORIGINATOR'SINMAiS Al-N: ------

225 of 238

01/31/12 13:45 Teledyne Brown Engineering SR #: SR30331 Sample Receipt Verification/Variance Report L49281 5of7 Client: Exelon Project 0: EX001-3ERZMPBRAID--05 LIMS #L49281 Initiated By: JSIMMONS Init Date: 01/31/12 Receive Date: 01/31/12 Notification of Variance Person Notified: Contacted By:

Notify Date; Notify Method:

Notify Comment:

Client Response Person Responding:

Response Date:

Response Method:

Response Comment Criteria Yes No NA Comment I Shipping container custody seals present MA and intact.

2 Sample container custody seals present NA and intact.

3 Sample containers received in good Y condition 4 Chain of custody received with samples Y 5 All samples listed on chain of custody Y received 6 Sample container labels present and Y legible.

7 Information on container labels y correspond with chain of custody 8 Sample(s) properly preserved and in NA appropriate container(s) 9 Other (Describe) NA 226 of 238

Raw Data Sheet (rawdata) 02/16/12 08:40 Page 1 of I Work Order: L49281 Customer: EKolon Analysis; H-3 Project: MX01I-3ERMPOSRAM-05 Decay 6 Sample ID Run Analysis Reference Volume/ Scavenge Milking mount Count Detector Total Sample 5kg Bkg "ff. Ingrowth client to # Date/Time Aliquot Date/Time Date/Time Weight Recovery Date/Time ID Counts dt Counts dt Factor Analyst L490.....-3Di- ST . 0.2-09-12-.... 1. 0 1 .6 60 .24 DW 10 20:39 M M BD-22 M4 Activity: 7.51E+C-0 Error: 1.04Ei02 MDC: 1.649+02 pCI/L L49201-1 H-3 (DTST)

--4 0

N)

(A) 001 4.

a 0:

0

Raw Data Sheet (rawdata) 02/16/12 08:48 Page 1 of 1 Work Order: xA9281 Customer: Exelon Ana.lys.s: 1-131 Project: ZX001-3EXIWR*xD-05 Decay &

Sariple ITD Rn Analysis Roference Volume/ Scavenge Milking Mount Count Detactor Total Sample Rkg 3kg Eff. Ingrowth Clie~nt ID # Date/Time Aliquot Date/Time Date/Time Weight Recovery Date/Time ID Counts dt Counts dt Factor Analyst

-1 T -- "3 14 ------08 . 0 2 5 5 2 0 21 4-12 11:00 4000 11:00 M 3D--22 ml Activity: -1. 43E--02 rtrror: 3.06E-01 Unc: 5.41S-01. pCi/L L49281-1 1-131 (LOW LVLI 0o CO 0

4W TELEDYNE BROWN ENGINEERING, INC.

2508 Quality Lane 1,49356 pg 1 of'7 Knoxville, TN 37931-3133 865-690-6819 Eric Ciekdewicz Braidwood Station Exclon Generation Company LLC 35100 South Rte 53, Suite 84

.Braceville, IL 60407-9619 Report of Analysis/Certificate of Conformance 02/28/2012 LIMS #: L49356 Project ID#: EX001-3EREMPBRAID-05 Received: 02107/2012 Delivery Date: 03/13/2012 P.O.1- 01000298 REL#00018 Release #:

SDG#:

This is to certify that Teledyne Brown Engineering - Environmental Services located at 2508 Quality Lane, Knoxville, Tennessee, 37931, has analyzed, tested and documented samples, as received by the laboratory, as specified in the applicable purchase order.

This also certifies that requirements of applicable codes, standards and specifications have been fully met and that any quality assurance documentation which verified conformance to the purchase order is on file and may be examined upon request.

I here fla i above statements are true and correct

/teith Jete/

Operations Manager CrossReference Table Client ID Laboratory ID Stio (f ppbicabe).

BD-22 IA93 BD-22 Method Reference Numbers Matrix - .Analysis Method Reference WWD H-3 (DIST) EPA 906.0 This report shall not be reproduced or distributed except in its entirety.

Page I of 2 229 of 238

Report of Analysis .~.,

P TELEDYNE BROWN ENGINEERING, INC.

02/28/12 11:06 ATeledm* Teotaotagiel-CompswN L49356 L49356 pg 2 of 7 Braidwood Station EXOGI-3EREMPBRAID-05 Station: BD-22 CollectStop: 02t02/2012 16:40 volume:

Description:

Wilmington, Receive Date., 02!07/2012  % Moisture:

LNIMSNumber: 1-49356-1 S Activit Uertainty lIRun[ Aliquot IAliquot Reference Count Count Count Rudionnclide SOP n 2 Sigma L DC Units N Volume 1 Units De Da te Time, Units Flag Values ll-3!ST) .20)1~~ 2.70E+ 02 -I-:-Z7fz'ýp~/1 0 l02/16/L2 - 6 1.4- 2 1.3+2 pib I-31-(LOW -L-) 2Lo2 -1.6E-01 4.24E-0l7.17 "lOi pCiL . .. 40 0 . . m ml 002/2/12-140 O24/1 __ -*200

______- "M 1 1 -' - ._

Comment: I Wcekl composite-hold for monthly--com_-posite ..

0o N0 Ns) wr Flag Values U = Compound/Analyte not detected (< MIC) or less than 2 sigma No - Peak not idcntifed in gamma spectrum

+ - Activily concentration exceeds M.C and 2 sigma; peak identified(gamma only) Ys - Peak identified in gamma spectrum U* Compound/Analyte not detected. Peak not identified, but ftxcd activity concentration exceeds MDC aid 2 sigtma **** Unless otherwise noted, the analytical results reported Iligh Activity concentration exceeds customer reporting value Spec = MDC exceeds customer technical specification are related only to the samples tested in the condition they L = Low recovery " aFc *reeived by the laboratory.

t = Htigh recovery MDC - Minimum Detectable Concentration Solded text indicates reportable value.

Page 2 of 2

L49356 pg 3 of 7 Braidwood Generating Station Sample C A1 Sheet NUCLtion/Rcoipt Public Water Sample EXitLON NUCLEAR Sample Sample tab. No. Client ID Station Code Meditum S tart date Start time Stun date Stop lime Siz.e Analysis Comments Hmg-3(DISBID1L Wf3

_____Wilmington 130-22 13W 01/26/2012 t7:00 02/02/2012 16:40 2 aol. (,LOW LVI,) Weekly, composite-hold for tmoothly composite N)

G?

I\.

C,,

00 Collected by7 ' AYLýwt Date: 02/02/2012 BIM-22 Composite weekly sample for Monthly Composite for Ganmms, GR-B Shipped IFeIIIZZIýII ty: Date: 02/06/2012 Hold for Quarterly 11-3 Composite.

Received b, Dote: BD-22

(

Environmental, Inc. SR NO. 15594 1 Midwest Laboratory An Allegheny Technologies Company Shipping Rec69tf" MIDWEST LABORATORY 700 LANDWEHR ROAD - NORTHBROOK, IL 60M82-2310 - (847) 564-0700 FAX(847) 5644517 NOTElI When returning or replacing this material, please reference S/R No. on all documents.

PART I (To be completed by originator) D. Control Data:

A. Description of Items (Include, Quantity, Model No.,

Type. Serial No., and Gov't Property No.)

Vendor P.O. No..

Br22od:

B D-2 2 .. _ W.OJAccL No.

Location of material Ship no later than Ship via Collect Prepaid F' B. Purpose of Shipment: No. Pcs.ctns ..... Cu. Ft.

Weight Est. Val.

o Return for credit-No replacement:

Part 11 (To be completed by 03 Return for rework or replacement at Vendor's expense.

Shipping Dept) o] Return for rework or replacement at Environmental, Inc's expense.

Actual method of shipment Federal Express o3 Furnished on Consignment for use on P.O. No.

O3 Other (explain)

Date Shipped 02-06-2012 C. Comments or instructions to Vendor: Collect Prepaid FOB point ____ ____

WaybdilNo.-.

Miac __________

SHIP TO: TBE LB.

ORIGINATORS IHTmAI.S ATTrN:

232 of 238

02/07/12 10:56 Teledyne Brown Engineering SR/0#/1SR10394 SR #: SR30394 Sample Receipt Verification/Variance Report L49356 p15 of 7 Client: Exelon Project #: EX001-3EREMPBRAID-05 LIMS L49356 Initiated By: JSIMMONS

, it Date: 02/07/12 Receive Date: 02/07/12 Notification of Variance Person Notified: Contacted By:

Notify Date:

Notify Mezhod:

Notify Conment:

Client Response Person Raspondinc:

Response Date:

Response Method:

Response Comment Criteria Yes No NA Comment 1 Shipping container custody seals present NA ant in~act.

2 Samfole container custody seals present NA and incact.

3 Sarple conzainers received in good Y condition 4 Chain of custody received with samples Y 5 All sampies listed on chain of custody Y received 6 Samle container labels present and Y legiblie.

7 Information on container labels Y correspond with chain of custody 8 Saiple.(s) properly preserved and in NA appropriate container(s) 9 Other !Describe) NA 233 of 238

Raw Data Sheet (rawdata) 02/29/12 11:06 Page I of I Work Order: L49356 Customer: xelon LICDU pg o O I Analysis: H-3 Project: ZX001-3RRESPBRAIf-05 Decay r Sa-mple ID on Analysis Reference Volume/ Scavenge Milking Mount Count Detector Total Sample Bkg Skg Eff. Ingrowth Client ID 4 DaTe/Time Aliquot Date/Time Date/rime Weight Recovery Date/Time ID counts dt Counts dt: Factor Analyst 9 6 EVJA g -------- 0 02-16-12 LS7 1 60 114 6 10 23:19 M M BD-22 m Ac~tivity: 2270EZ-02 Error: 1.34L+~02 MDC: 1.93E+02 p01/L L49356-1 H-3 (DIST)

KO 0

003

Raw Data Sheet (rawdsta) 02/28/12 11:06 Page 1 of 1 Work Order: L49356 Customer: Zxelon L49356 pg 7 of 7 Analysis: 1-131 Project: EX001-3XPz*WBRAID-05 De*Cay 6 Sample ID Run Analysis Reference Volumoe/ Scavenge Milking Mount Count Detector Total Sample BKg Bkg Eff. Lngrowth client ID

  • Date/Time Aliquot Date/Time Date/Time Weight Recovery Date/Time ID Counts dt Counts dt Factor Analyst 200 129 200 .296 .151 BF 16:40 4000 17:08 M M B0-22 ml Activity: -1.76E-01 Error: 4.24E-01 MDC: 7.17M-01 pCi/L L49356-1 1-131 (LOW LVL)

N)

(Ol 0

00

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2011 UNIT 1 AND 2 (Docket Numbers 50-456 and 50-457)

ATTACHMENT 7 ERRATA CORRECTIONS FROM 2010 REPORT 236 of 238

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2010 UNIT 1 (Docket Number 50-456)

GASEOUS EFFLUENTS SUPPLEMENTAL RELEASE INFORMATION A. Batch Release 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total

1. Total Number of Batch 20 18 20 23 81 Releases
2. Total Time Period for Batch 1,158 984 778 35,138 38,058 Releases (minutes)
3. Maximum Time Period for 305 414 103 14,400 N/A a Batch Release (minutes)
4. Average Time Period for a 58 55 39 1,528 N/A Batch Release (minutes)
5. Minimum Time Period for a 20 22 21 22 N/A Batch Release (minutes)

B. Abnormal Releases

1. Number of Releases 0 0 1 0 1
2. Total Activity Released (Ci) 0 0 4.31 E-02 0 0 237 of 238

BRAIDWOOD NUCLEAR POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2011 UNIT 1 AND 2 (Docket Numbers 50-456 and 50-457)

ATTACHMENT 8 OFFSITE DOSE CALCULATION MANUAL (ODCM) 238 of 238

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