SVP-13-031, Submittal of Radioactive Effluent Release Report for 2012: Difference between revisions

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SVP-13-031 10 CFR 50.36a April 26, 2013 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265  
SVP-13-031                                                                       10 CFR 50.36a April 26, 2013 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265


==Subject:==
==Subject:==
Radioactive Effluent Release Report for 2012 Pursuant to Technical Specifications Section 5.6.3 and 10 CFR 50.36a, enclosed is the Quad Cities Nuclear Power Station Radioactive Effluent Release Report for January through December 2012. There was one abnormal release that occurred during 2012. This release resulted in a
Radioactive Effluent Release Report for 2012 Pursuant to Technical Specifications Section 5.6.3 and 10 CFR 50.36a, enclosed is the Quad Cities Nuclear Power Station Radioactive Effluent Release Report for January through December 2012. There was one abnormal release that occurred during 2012. This release resulted in a minor contribution to normal plant radioactive effluents and is discussed in detail in the report.
In addition, pursuant to Section 12.7.3.4 of the Off-Site Dose Calculation Manual (ODCM),
enclosed (Attachment 2) is a copy of the Process Control Program for Radioactive Wastes (RW-AA-100, Revision 8) which was revised in 2012.
Should you have any questions concerning this letter, please contact Mr. Wally J. Beck at (309) 227-2800.
Respectfully, Ti~m Hawley                *lO Site Vice President Quad Cities Nuclear Power Station Attachments:
: 1. 2012 Annual Radioactive Effluent Release Report
: 2. RW-AA-100, Revision 8, Process Control Program for Radioactive Wastes cc:      Regional Administrator - NRC Region III NRC Senior Resident Inspector - Quad Cities Nuclear Power Station 41ý
 
Attachment 1 2012 Annual Radioactive Effluent Release Report
 
Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Effluent & Waste Disposable Summary Gaseous Effluents - Summation of all Releases Period:          January - December 2012
: f. Estimated Total Error Percent The estimated total error percents were calculated by taking the square root of the sum of the squares of errors for sampling and measurement parameters.
: f. Estimated Total Error Percent The estimated total error percents were calculated by taking the square root of the sum of the squares of errors for sampling and measurement parameters.
: g. Less than the Lower Limit of Detection
: g. Less than the Lower Limit of Detection (<LLD)
(<LLD)Samples are analyzed such that the Technical Specification LLD requirements are met. When a nuclide is not detected during the quarter, then <LLD is reported.
Samples are analyzed such that the Technical Specification LLD requirements are met. When a nuclide is not detected during the quarter, then <LLD is reported. The most conservative LLD's used for counting effluent samples are included in this report.
The most conservative LLD's used for counting effluent samples are included in this report.5. Batch Releases a. Liquid 1. Number of releases:
: 5. Batch Releases
0 2. Total time: N/A 3. Maximum time: N/A 4. Average time: N/A 5. Minimum time: N/A 6. Average stream flow: N/A b. Gaseous 1. NONE 6. Abnormal Releases Abnormal Releases a. Liquid A leak into the 1A RHR (Residual Heat Removal) heat exchanger, service water side, developed in May 2011. This leak has been subsequently repaired during Q1 R22 in March of 2013. This produced a monitored liquid effluent release via the continuous liquid release pathway each time that the "A" loop of the Unit-1 RHR system was started. The activity identified from the leak was included in the monthly effluent calculations and is included in the "continuous" liquid section of this report. A temporary modification to pressurize the service water side of the affected heat exchanger was installed in September 2011, which significantly reduced the leakage rate.Page 14 of 75 Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Supplemental Information
: a. Liquid
: b. Gaseous 1. NONE 8. Radiological Impact on Man a. Liquid Dose to a Member of the Public for 2012 Total Body: 2.78E-05 mrem Organ: 4.55E-05 mrem b. Gaseous Dose to a Member of the Public for 2012 Total Body: 4.32E-02 mrem Skin: 6.02E-04 mrem Organ (Particulate/lodine/Tritium/C-14):
: 1.     Number of releases:         0
2.07E-01 mrem The Quad Cities calculated annual doses from Carbon-14 releases have been calculated using the conservative bounding methodologies outlined in the ODCM. The resultant estimated releases of Carbon-14 resulted in a dose contribution of 3.71 E-02 mrem/yr to organ dose (17.9%) and 3.96E-02 mrem/yr to total dose (91.7%). The maximum expected annual dose contribution from Carbon-14 has been calculated to be 2.08E-01 mrem/yr organ dose and 4.15E-02 mrem/yr total body dose. This was obtained using maximum gross thermal capacity maintained for 365 days for both units.c. Uranium Fuel Cycle Dose to a Member of the Public for 2012 (40CFR1 90)The main component (7.74 mrem or 99.5%) of the Uranium Fuel Cycle dose for Quad Cities Station is BWR skyshine from N-16 within the turbine building.BWR skyshine at Quad Cities Station is conservatively determined to the hypothetical maximally exposed member of the public.Total Body: 7.78E+00 mrem (Skyshine  
: 2.     Total time:                 N/A
+ Total Body component of gaseous and liquid effluents) 31.1% of 40 CFR 190 Limit of 25 mrem/year (Whole Body and Organ).Thyroid dose of 2.76E-01%
: 3.     Maximum time:               N/A
of 40 CFR 190 Limit (75 mrem).Page 15 of 75 Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Supplemental Information
: 4.     Average time:               N/A
: 5.     Minimum time:               N/A
: 6.     Average stream flow:         N/A
: b. Gaseous
: 1. NONE
: 6. Abnormal Releases Abnormal Releases
: a. Liquid A leak into the 1A RHR (Residual Heat Removal) heat exchanger, service water side, developed in May 2011. This leak has been subsequently repaired during Q1 R22 in March of 2013. This produced a monitored liquid effluent release via the continuous liquid release pathway each time that the "A"loop of the Unit-1 RHR system was started. The activity identified from the leak was included in the monthly effluent calculations and is included in the "continuous" liquid section of this report. A temporary modification to pressurize the service water side of the affected heat exchanger was installed in September 2011, which significantly reduced the leakage rate.
Page 14 of 75
 
Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Supplemental Information
: b. Gaseous
: 1. NONE
: 8. Radiological Impact on Man
: a. Liquid Dose to a Member of the Public for 2012 Total Body: 2.78E-05 mrem Organ: 4.55E-05 mrem
: b. Gaseous Dose to a Member of the Public for 2012 Total Body: 4.32E-02 mrem Skin: 6.02E-04 mrem Organ (Particulate/lodine/Tritium/C-14): 2.07E-01 mrem The Quad Cities calculated annual doses from Carbon-14 releases have been calculated using the conservative bounding methodologies outlined in the ODCM. The resultant estimated releases of Carbon-14 resulted in a dose contribution of 3.71 E-02 mrem/yr to organ dose (17.9%) and 3.96E-02 mrem/yr to total dose (91.7%). The maximum expected annual dose contribution from Carbon-14 has been calculated to be 2.08E-01 mrem/yr organ dose and 4.15E-02 mrem/yr total body dose. This was obtained using maximum gross thermal capacity maintained for 365 days for both units.
: c. Uranium Fuel Cycle Dose to a Member of the Public for 2012 (40CFR1 90)
The main component (7.74 mrem or 99.5%) of the Uranium Fuel Cycle dose for Quad Cities Station is BWR skyshine from N-16 within the turbine building.
BWR skyshine at Quad Cities Station is conservatively determined to the hypothetical maximally exposed member of the public.
Total Body: 7.78E+00 mrem (Skyshine + Total Body component of gaseous and liquid effluents) 31.1% of 40 CFR 190 Limit of 25 mrem/year (Whole Body and Organ).
Thyroid dose of 2.76E-01% of 40 CFR 190 Limit (75 mrem).
Page 15 of 75
 
Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Supplemental Information
: d. Total Body Doses to the Population and Average Doses to Individuals in the Population from All Receiving-Water-Related-Pathways:
: d. Total Body Doses to the Population and Average Doses to Individuals in the Population from All Receiving-Water-Related-Pathways:
Not applicable for QCNPS e. Total Body Doses to the Population and Average Doses to Individuals in the Population from Gaseous Effluents to a Distance of 50 Miles: Not applicable for QCNPS ft Doses From Liquid and Gaseous Effluent to Members of the.Public Due to Their Activities Inside the Site Boundary for the Report Period: Not applicable for QCNPS. Any member of the public that is onsite for a significant period will be issued a dosimeter.
Not applicable for QCNPS
: e. Total Body Doses to the Population and Average Doses to Individuals in the Population from Gaseous Effluents to a Distance of 50 Miles:
Not applicable for QCNPS ft Doses From Liquid and Gaseous Effluent to Members of the.Public Due to Their Activities Inside the Site Boundary for the Report Period:
Not applicable for QCNPS. Any member of the public that is onsite for a significant period will be issued a dosimeter.
: g. Liquid and Gaseous Effluent Radiation Monitors and Instrumentation Unavailability for the Period Beyond the Requirements of the ODCM, Including Sampling Deviation:
: g. Liquid and Gaseous Effluent Radiation Monitors and Instrumentation Unavailability for the Period Beyond the Requirements of the ODCM, Including Sampling Deviation:
No ODCM monitors were unavailable for greater
No ODCM monitors were unavailable for greater than 30 days in 2012.
Page 16 of 75
 
Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report 10CFR20.1301(a)(1) Compliance Assessment Quad Cities Station Unit One and Unit Two Assessment Period      01/01/2012 THROUGH 12/31/2012 10CFR20.1301(a)(1) Limit      100.0 mrem/year Quad Cities Unit 1
                  . nd    .        d
* I  th  _
Submitted by:                                                      Date: 2  ,.
Reviewed by:                                                      Date: L -Z&                                    Page 17 of 75
 
Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Maximum Doses Resulting From Airborne Releases/Compliance Status Quad Cities Station - Unit One/Unit Two Unit One      Unit Two    10 CFR 50 APP. I  Unit One  Unit Two Type of Dose      Annual        Annual      Yearly Objective %ofAPP. I %ofAPP. I Gamma Air (mrad)            4.60E-04      4.60E-04          10.0        4.60E-03  4.60E-03 Beta Air (mrad)    2.36E-04      2.36E-04          20.0        1.18E-03  1.18E-03 Organ (mrem)      2.21 E-01    2.21


===2.2. Solidification===
===2.2. Solidification===
Liquid waste processed to either an unstable or stable form per 10CFR61 requirements. Waste solidified does not have to meet the 300-year free standing monolith criteria. Approved formulas, samples and tests do not have to meet NRC approval for wastes solidified in a container meeting stability criteria (e.g.
High Integrity Container).
===2.3. Stabilization===
Liquid waste processed to a "stable state" per 10CFR61 Requirements. Established formulas, samples, and tests shall be approved by the NRC in order to meet solidification "stabilization" criteria. This processing method is currently not available, because the NRC recognizes that waste packed in a High Integrity Container meets the 300-year stabilization criteria. In the event that this processing method becomes an acceptable method, then the NRC shall approve the stabilization formulas, samples, tests, etc.
RW-AA-100 Revision 8 Page 2 of 9 2.4. Solidification Media: An approved media (e.g. Barnwell - vinyl ester styrene, cement, bitumen) when waste containing nuclides with greater than 5-year half lives is solidified in a container with activity greater than 1 micro curie/cc. Waste solidified in a HIC is approved by the commission meeting the 10CFR61 stabilization criteria, including 1% free standing liquids by volume when the waste is packaged to a "stable" form and < 0.5% when waste is packaged to an "unstable" form. The formulas, sampling, analysis, and test do not require NRC approval, because the HIC meets the stability criteria.
2.4.1. Solidification to an unstable or stable state is performed by vendors, when applicable. Liquid waste solidified to meet stabilization criteria (10CFR61 and 01-91 Branch Technical Requirements) shall have documentation available that demonstrates that the process is approved by the NRC or disposal facility.


Liquid waste processed to either an unstable or stable form per 10CFR61 requirements.
===2.5. Dewatering===
Waste solidified does not have to meet the 300-year free standing monolith criteria.
The process of removing fluids from liquid waste streams to produce a waste form that meets the requirements of 10CFR Part 61 and applicable burial site criteria, <0.5% by volume when the waste is packaged to an "unstable" state, or
Approved formulas, samples and tests do not have to meet NRC approval for wastes solidified in a container meeting stability criteria (e.g.High Integrity Container).
      <1% by volume when the waste is packaged to a "stable" form.
2.6. High Integrity Container (HIC): A disposable container that is approved to the Requirements of 10CFR61. The use of HIC's is an alternative to solidification or encapsulation in a steel container to meet burial stability. HIC's are used to package dewatered liquid wastes, (e.g. filter cartridges, filter media, resin, sludges, etc), or dry active waste.


===2.3. Stabilization===
===2.7. Encapsulation===
The process of placing a component (e.g. cartridge filters or mechanical components) into a special purpose disposable container and then completely surrounding the waste material with an approved stabilization media, such as cement.
2.8. Liquid Waste Processing Systems: In-plant or vendor supplied processing systems consisting of equipment utilized for evaporation, filtration, demineralization, dewatering, compression dewatering, solidification, or reverse osmosis (RO) for the treatment of liquid wastes (such as Floor Drains, Chemical Drains and Equipment Drain inputs).
2.9. Incineration, RVR, and/or Glass Vitrification of Liquid or Solid: Dry or wet waste processed via incineration and/or thermal processing where the volume is reduced by thermal means meets 1OCFR61 requirements.
2.10. Compaction: When dry wastes such as paper, wood, plastic, cardboard, incinerator ash, and etc. are volume reduced through the use of a compactor.
2.11. Waste Streams: Consist of but are not limited to
      -        Filter media (powdered, bead resin and fiber),
      -        Filter cartridges,
      -        Pre-coat body feed material,
      -        Contaminated charcoal,


Liquid waste processed to a "stable state" per 10CFR61 Requirements.
RW-AA-100 Revision 8 Page 3 of 9
Established formulas, samples, and tests shall be approved by the NRC in order to meet solidification "stabilization" criteria.
      -     Fuel pool activated hardware,
This processing method is currently not available, because the NRC recognizes that waste packed in a High Integrity Container meets the 300-year stabilization criteria.
      -     Oil Dry absorbent material added to a container to absorb liquids
In the event that this processing method becomes an acceptable method, then the NRC shall approve the stabilization formulas, samples, tests, etc.
      -     Fuel Pool Crud
RW-AA-100 Revision 8 Page 2 of 9 2.4. Solidification Media: An approved media (e.g. Barnwell -vinyl ester styrene, cement, bitumen) when waste containing nuclides with greater than 5-year half lives is solidified in a container with activity greater than 1 micro curie/cc.
      -     Sump and tank sludges,
Waste solidified in a HIC is approved by the commission meeting the 10CFR61 stabilization criteria, including 1 % free standing liquids by volume when the waste is packaged to a"stable" form and < 0.5% when waste is packaged to an "unstable" form. The formulas, sampling, analysis, and test do not require NRC approval, because the HIC meets the stability criteria.2.4.1. Solidification to an unstable or stable state is performed by vendors, when applicable.
      -     High activity filter cartridges,
Liquid waste solidified to meet stabilization criteria (10CFR61 and 01-91 Branch Technical Requirements) shall have documentation available that demonstrates that the process is approved by the NRC or disposal facility.2.5. Dewatering:
      -     Concentrated liquids,
The process of removing fluids from liquid waste streams to produce a waste form that meets the requirements of 10CFR Part 61 and applicable burial site criteria, <0.5% by volume when the waste is packaged to an "unstable" state, or<1% by volume when the waste is packaged to a "stable" form.2.6. High Integrity Container (HIC): A disposable container that is approved to the Requirements of 10CFR61. The use of HIC's is an alternative to solidification or encapsulation in a steel container to meet burial stability.
      -     Contaminated waste oil,
HIC's are used to package dewatered liquid wastes, (e.g. filter cartridges, filter media, resin, sludges, etc), or dry active waste.2.7. Encapsulation:
      -     Dried sewage or wastewater plant waste,
The process of placing a component (e.g. cartridge filters or mechanical components) into a special purpose disposable container and then completely surrounding the waste material with an approved stabilization media, such as cement.2.8. Liquid Waste Processing Systems: In-plant or vendor supplied processing systems consisting of equipment utilized for evaporation, filtration, demineralization, dewatering, compression dewatering, solidification, or reverse osmosis (RO) for the treatment of liquid wastes (such as Floor Drains, Chemical Drains and Equipment Drain inputs).2.9. Incineration, RVR, and/or Glass Vitrification of Liquid or Solid: Dry or wet waste processed via incineration and/or thermal processing where the volume is reduced by thermal means meets 1 OCFR61 requirements.
      -     Dry Active Waste (DAW): Waste such as filters, air filters, low activity cartridge filters, paper, wood, glass, plastic, cardboard, hoses, cloth, and metals, etc, which have become contaminated as a consequence of normal operating, housekeeping and maintenance activities.
2.10. Compaction:
When dry wastes such as paper, wood, plastic, cardboard, incinerator ash, and etc. are volume reduced through the use of a compactor.
2.11. Waste Streams: Consist of but are not limited to-Filter media (powdered, bead resin and fiber),-Filter cartridges,-Pre-coat body feed material,-Contaminated
: charcoal, RW-AA-100 Revision 8 Page 3 of 9-Fuel pool activated hardware,-Oil Dry absorbent material added to a container to absorb liquids-Fuel Pool Crud-Sump and tank sludges,-High activity filter cartridges,-Concentrated liquids,-Contaminated waste oil,-Dried sewage or wastewater plant waste,-Dry Active Waste (DAW): Waste such as filters, air filters, low activity cartridge filters, paper, wood, glass, plastic, cardboard, hoses, cloth, and metals, etc, which have become contaminated as a consequence of normal operating, housekeeping and maintenance activities.
Other radioactive waste generated from cleanup of inadvertent contamination.
Other radioactive waste generated from cleanup of inadvertent contamination.
: 3. RESPONSIBILITIES 3.1. Implementation of this Process Control Program (PCP) is described in procedures at each station and is the responsibility of the each site to implement.
: 3. RESPONSIBILITIES 3.1. Implementation of this Process Control Program (PCP) is described in procedures at each station and is the responsibility of the each site to implement.
: 4. MAIN BODY 4.1. Process Control Program Requirements 4.1.1. A change to this PCP (Radioactive Waste Treatment Systems) may be made provided that the change is reported as part of the annual radioactive effluent release report, Regulatory Guide 1.21, and is approved by the Plant Operations Review Committee (PORC).4.1.2. Changes become effective upon acceptance per station requirements.
: 4. MAIN BODY 4.1. Process Control Program Requirements 4.1.1. A change to this PCP (Radioactive Waste Treatment Systems) may be made provided that the change is reported as part of the annual radioactive effluent release report, Regulatory Guide 1.21, and is approved by the Plant Operations Review Committee (PORC).
4.1.3. A solidification media, approved by the burial site, may be REQUIRED when liquid radwaste is solidified to a stable/unstable state.4.1.4. When processing liquid radwaste to meet solidification stability using a vendor supplied solidification system: 1. If the vendor has its own Quality Assurance (QA) Program, then the vendor shall ADHERE to its own QA Program and shall have SUBMITTED its process system topical report to the NRC or agreement state.2. If the vendor does not HAVE its own Quality Assurance Program, then the vendor shall ADHERE to an approved Quality Assurance Topical Report standard belonging to the Station or to another approved vendor.
4.1.2. Changes become effective upon acceptance per station requirements.
4.1.3. A solidification media, approved by the burial site, may be REQUIRED when liquid radwaste is solidified to a stable/unstable state.
4.1.4. When processing liquid radwaste to meet solidification stability using a vendor supplied solidification system:
: 1. If the vendor has its own Quality Assurance (QA) Program, then the vendor shall ADHERE to its own QA Program and shall have SUBMITTED its process system topical report to the NRC or agreement state.
: 2. If the vendor does not HAVE its own Quality Assurance Program, then the vendor shall ADHERE to an approved Quality Assurance Topical Report standard belonging to the Station or to another approved vendor.
 
RW-AA-100 Revision 8 Page 4 of 9 4.1.5. The vendor processing system(s) is/are controlled per the following:
RW-AA-100 Revision 8 Page 4 of 9 4.1.5. The vendor processing system(s) is/are controlled per the following:
: 1. A commercial vendor supplied processing system(s) may be USED for the processing of LLRW streams.2. Vendors that process liquid LLRW at the sites shall MEET applicable Quality Assurance Topical Report and Augmented Quality Requirements.
: 1.     A commercial vendor supplied processing system(s) may be USED for the processing of LLRW streams.
: 2.       Vendors that process liquid LLRW at the sites shall MEET applicable Quality Assurance Topical Report and Augmented Quality Requirements.
4.1.6. Vendor processing system(s) operated at the site shall be OPERATED and CONTROLLED in accordance with vendor approved procedures or station procedures based upon vendor approved documents.
4.1.6. Vendor processing system(s) operated at the site shall be OPERATED and CONTROLLED in accordance with vendor approved procedures or station procedures based upon vendor approved documents.
4.1.7. All waste streams processed for burial or long term on-site storage shall MEET the waste classification and characteristics specified in 10CFR Part 61.55, Part 61.56, the 5-83 Branch Technical Position for waste classification, and the applicable burial site acceptance criteria (for any burial site operating at the time the waste was processed).
4.1.7. All waste streams processed for burial or long term on-site storage shall MEET the waste classification and characteristics specified in 10CFR Part 61.55, Part 61.56, the 5-83 Branch Technical Position for waste classification, and the applicable burial site acceptance criteria (for any burial site operating at the time the waste was processed).
4.1.8. An Exelon Nuclear plant may store waste at another Exelon Nuclear plant, provided formal NRC approval has been RECEIVED for the transfer of waste.4.2. General Waste Processinq Requirements NOTE: On-site resin processing involves tank mixing and settling, transferring to the station or vendor processing system via resin water slurry or vacuuming into approved waste containers, and, when applicable, dewatering for burial.4.2.1. Vendor resin beds may be USED for decontamination of plant systems, such as, SFP (Spent Fuel Pool), RWCU (reactor water cleanup), and SDC (Shut Down Cooling).
4.1.8. An Exelon Nuclear plant may store waste at another Exelon Nuclear plant, provided formal NRC approval has been RECEIVED for the transfer of waste.
These resins are then PROCESSED via the station or vendor processing system.4.2.2. Various drains and sump discharges will be COLLECTED in tanks or suitable containers for processing treatment.
4.2. General Waste Processinq Requirements NOTE:       On-site resin processing involves tank mixing and settling, transferring to the station or vendor processing system via resin water slurry or vacuuming into approved waste containers, and, when applicable, dewatering for burial.
Water from these tanks may be SENT through a filter, demineralizer, concentrator or vendor supplied processing systems.4.2.3. Process waste (e.g. filter media, sludges, resin, etc) will be periodically DISCHARGED to the station or vendor processing system for onsite waste treatment or PACKAGED in containers for shipment to offsite vendor for volume reduction processing.
4.2.1. Vendor resin beds may be USED for decontamination of plant systems, such as, SFP (Spent Fuel Pool), RWCU (reactor water cleanup), and SDC (Shut Down Cooling). These resins are then PROCESSED via the station or vendor processing system.
4.2.2. Various drains and sump discharges will be COLLECTED in tanks or suitable containers for processing treatment. Water from these tanks may be SENT through a filter, demineralizer, concentrator or vendor supplied processing systems.
4.2.3. Process waste (e.g. filter media, sludges, resin, etc) will be periodically DISCHARGED to the station or vendor processing system for onsite waste treatment or PACKAGED in containers for shipment to offsite vendor for volume reduction processing.
4.2.4. Process water (e.g. chemical, floor drain, equipment drain, etc.) may be SENT to either the site waste processing systems or vendor waste processing systems for further filtration, demineralization for plant re-use, or discharge.
4.2.4. Process water (e.g. chemical, floor drain, equipment drain, etc.) may be SENT to either the site waste processing systems or vendor waste processing systems for further filtration, demineralization for plant re-use, or discharge.
4.2.5. All dewatering and solidification/stabilization will be PERFORMED by either utility site personnel or by on-site vendors or will be PACKAGED and SHIPPED to an off-site vendor low-level radwaste processing facility.
4.2.5. All dewatering and solidification/stabilization will be PERFORMED by either utility site personnel or by on-site vendors or will be PACKAGED and SHIPPED to an off-site vendor low-level radwaste processing facility.
RW-AA-100 Revision 8 Page 5 of 9 4.2.6. Dry Active Waste (DAW) will be HANDLED and PROCESSED per the following:
RW-AA-100 Revision 8 Page 5 of 9 4.2.6. Dry Active Waste (DAW) will be HANDLED and PROCESSED per the following:
: 1. DAW will be COLLECTED and SURVEYED and may be SORTED for compactable and non-compactable wastes.2. DAW may be packaged in containers to facilitate on-site pre-compaction and/or off-site vendor contract requirements.
: 1.     DAW will be COLLECTED and SURVEYED and may be SORTED for compactable and non-compactable wastes.
: 3. DAW items may be SURVEYED for release onsite or offsite when applicable.
: 2.     DAW may be packaged in containers to facilitate on-site pre-compaction and/or off-site vendor contract requirements.
: 4. Contaminated filter cartridges will be PLACED into a HIC or will be ENCAPSULATED in an in-situ liner for disposal or SHIPPED to an offsite waste processor in drums, boxes or steel liners per the vendor site criteria for processing and disposal.4.2.7. Filtering devices using pre-coat media may be USED for the removal of suspended solids from liquid waste streams. The pre-coat material or cartridges from these devices may be routinely REMOVED from the filter vessel and discharged to a Filter Sludge Tank or Liner/HIC.
: 3.     DAW items may be SURVEYED for release onsite or offsite when applicable.
Periodically, the filter sludge may be DISCHARGED to the vendor processing system for waste treatment onsite or PACKAGED in containers for shipment to offsite vendor for volume reduction processing.
: 4.     Contaminated filter cartridges will be PLACED into a HIC or will be ENCAPSULATED in an in-situ liner for disposal or SHIPPED to an offsite waste processor in drums, boxes or steel liners per the vendor site criteria for processing and disposal.
4.2.8. Activated hardware stored in the Spent Fuel Pools will be PROCESSED periodically using remote handling equipment and may then be PUT into a container for shipment or storage in the pool or loading the processed activated hardware into the Dry Cask storage system.4.2.9. High Integrity Containers (HIC): 1. For disposal at Barnwell, vendors supplying HIC's to the station shall PROVIDE a copy of the HIC Certificate of Compliance, which details specific limitations on use of the HIC.2. For disposal at Clive, vendors supplying HIC's to the station shall PROVIDE a copy of the HIC Certificate of Conformance, which details specific limitations on use of the HIC.3. Vendors supplying HIC's to the station shall PROVIDE a handling procedure which establishes guidelines for the utilization of the HIC. These guidelines serve to protect the integrity of the HIC and ensure the HIC is handled in accordance with the requirements of the Certificate of Compliance or Certificate of Conformance.
4.2.7. Filtering devices using pre-coat media may be USED for the removal of suspended solids from liquid waste streams. The pre-coat material or cartridges from these devices may be routinely REMOVED from the filter vessel and discharged to a Filter Sludge Tank or Liner/HIC. Periodically, the filter sludge may be DISCHARGED to the vendor processing system for waste treatment onsite or PACKAGED in containers for shipment to offsite vendor for volume reduction processing.
4.2.10. Lubricants and oils contaminated as a consequence of normal operating and maintenance activities may be PROCESSED on-site (by incineration, for oils meeting 10CFR20.2004 and applicable state requirements, or by an approved vendor process)or SHIPPED offsite (for incineration or other acceptable processing method).4.2.11. Former in-plant systems GE or Stock Drum Transfer Cart and Drum Storage Areas may be USED for higher dose DAW storage at Clinton, Dresden, Quad Cities, Braidwood and Byron.
4.2.8. Activated hardware stored in the Spent Fuel Pools will be PROCESSED periodically using remote handling equipment and may then be PUT into a container for shipment or storage in the pool or loading the processed activated hardware into the Dry Cask storage system.
RW-AA-100 Revision 8 Page 6 of 9 4.2.13 Certain waste, including flowable solids from holding pond, oily waste separator, cooling tower basin and emergency spray pond, may be disposed of onsite under the provisions of a 10CFR20.2002 permit. Specific requirements associated with the disposal shall be incorporated into station implementing procedures. (CM-2)4.3. Burial Site Requirements 4.3.1. Waste sent directly to burial shall COMPLY with the applicable parts of 49CFR1 71-172, 1 OCFR61, 1 OCFR71, and the acceptance criteria for the applicable burial site.4.4. Shippinq and Inspection Requirements 4.4.1. All shipping/storage containers shall be INSPECTED, as required by station procedures, for compliance with applicable requirements (Department of Transportation (DOT), Nuclear Regulatory Commission (NRC), station, on-site storage, and/or burial site requirements) prior to use.4.4.2. Containers of solidified liquid waste shall be INSPECTED for solidification quality and/or dewatering requirements per the burial site, offsite vendor acceptance, or station acceptance criteria, as applicable.
4.2.9. High Integrity Containers (HIC):
4.4.3. Shipments sent to an off site processor shall be INSPECTED to ensure that the applicable processor's waste acceptance criteria are being met.4.4.4. Shipments sent for off site storage shall MEET the storage site's waste acceptance criteria.4.5. Inspection and Corrective Action 4.5.1. Inspection results that indicate non-compliance with applicable NRC, State, vendor, or site requirements shall be IDENTIFIED and TRACKED through the Corrective Action Program.4.5.2. Administrative controls for preventing unsatisfactory waste forms from being released for shipment are described in applicable station procedures.
: 1.     For disposal at Barnwell, vendors supplying HIC's to the station shall PROVIDE a copy of the HIC Certificate of Compliance, which details specific limitations on use of the HIC.
If the provisions of the Process Control Program are not satisfied, then SUSPEND shipments of defectively packaged radioactive waste from the site. (CM-1)4.5.3. If freestanding water or solidification not meeting program requirements is observed, then samples of the particular series of batches shall be TAKEN to determine the cause. Additional samples shall be TAKEN, as warranted, to ensure that no freestanding water is present and solidification requirements are maintained.
: 2.     For disposal at Clive, vendors supplying HIC's to the station shall PROVIDE a copy of the HIC Certificate of Conformance, which details specific limitations on use of the HIC.
4.6. Procedure and Process Reviews 4.6.1. The Exelon Nuclear Process Control Program and subsequent changes (other than editorial/minor changes) shall be REVIEWED and APPROVED in accordance with the station procedures, plant-specific Technical Specifications (Tech Spec), Technical Requirements Manual (T&RM), Operation Requirements Manual (ORM), as applicable, for the respective station and LS-AA-106.
: 3.     Vendors supplying HIC's to the station shall PROVIDE a handling procedure which establishes guidelines for the utilization of the HIC. These guidelines serve to protect the integrity of the HIC and ensure the HIC is handled in accordance with the requirements of the Certificate of Compliance or Certificate of Conformance.
Changes to the Licensees Controlled Documents, UFSAR, ORM, or TRM are controlled by the provisions of 10CFR 50.59.
4.2.10. Lubricants and oils contaminated as a consequence of normal operating and maintenance activities may be PROCESSED on-site (by incineration, for oils meeting 10CFR20.2004 and applicable state requirements, or by an approved vendor process) or SHIPPED offsite (for incineration or other acceptable processing method).
RW-AA-100 Revision 8 Page 7 of 9 4.6.2. Any changes to the PCP shall be reviewed to determine if reportability is required in the Annual Radiological Effluent Release Report (ARERR). The Radwaste Specialist shall ensure correct information is SUBMITTED to the ODCM program owner prior to submittal of the ARERR.4.6.3. Station processes, applicable site-specific cask manual procedures, or other vendor waste processing/operating procedures shall be approved per RM-AA-102-1006.
4.2.11. Former in-plant systems GE or Stock Drum Transfer Cart and Drum Storage Areas may be USED for higher dose DAW storage at Clinton, Dresden, Quad Cities, Braidwood and Byron.
Procedures related to waste manifests, shipment inspections, and container activity determinations are CONTROLLED by Radiation Protection Standard Procedures (RP-AA-600 Series).1. Site waste processing IS CONTROLLED by site operating procedures.
 
: 2. Liquid processed by vendor equipment shall be PERFORMED in accordance with vendor procedures.
RW-AA-100 Revision 8 Page 6 of 9 4.2.13 Certain waste, including flowable solids from holding pond, oily waste separator, cooling tower basin and emergency spray pond, may be disposed of onsite under the provisions of a 10CFR20.2002 permit. Specific requirements associated with the disposal shall be incorporated into station implementing procedures. (CM-2) 4.3. Burial Site Requirements 4.3.1. Waste sent directly to burial shall COMPLY with the applicable parts of 49CFR1 71-172, 1OCFR61, 1OCFR71, and the acceptance criteria for the applicable burial site.
4.7.Waste Types, Point of Generation, and Processinq Method Methods of processing and individual vendors may CHANGE due to changing financial and regulatory options. The table below is a representative sample. It is not intended be all encompassing.
4.4. Shippinq and Inspection Requirements 4.4.1. All shipping/storage containers shall be INSPECTED, as required by station procedures, for compliance with applicable requirements (Department of Transportation (DOT), Nuclear Regulatory Commission (NRC), station, on-site storage, and/or burial site requirements) prior to use.
AVAILABLE WASTE WASTE STREAM POINTS OF GENERATION PROCESSING METHODS Bead Resin Systems -Fuel Pool, Condensate, Dewatering, solidification to an Reactor Water Cleanup, Blowdown, unstable/stable state Equipment Drain, Chemical and Thermal Processing Volume Control Systems, Floor Drain, Maximum Recycle, Blowdown, Boric Free Release to a Land Fill Acid Recycling System, Vendor Supplied Processing Systems, and Portable Demin System Powdered Resin Systems -(Condensate System, Floor Dewatering, solidification to an Drain/Equipment Drain filtration, Fuel unstable/stable state Pool) Thermal Processing Concentrated Waste Waste generated from Site Solidification to an unstable/stable Evaporators resulting typically from the state Floor Drain and Equipment Drain Thermal Processing Systems Sludge Sedimentation resulting from various Dewatering, solidification to an sumps, condensers, tanks, cooling unstable/stable state tower, emergency spray pond, holding Thermal Processing pond, and oily waste separators Evaporation on-site or at an offsite processor On-site disposal per 10CFR20.2002 permit RW-AA-100 Revision 8 Page 8 of 9 AVAI LABLE WASTE WASTE STREAM POINTS OF GENERATION POEING ME PROCESSING METHODS Filter cartridges Systems -Floor/Equipment Drains, Dewatering, solidification to an Fuel Pool; cartridge filters are typically unstable/stable state generated from clean up activities Processed by a vendor for volume within the fuel pool, torus, etc reduction Dry Active Waste Paper, wood, plastic, rubber, glass, Decon/Sorting for Free Release metal, and etc. resulting from daily Compaction/Super-compaction plant activities Thermal Processing by Incineration or glass vitrification Sorting for Free Release Metal melting to an ingot Contaminated Oil Oil contaminated with radioactive Solidification unstable state materials from any in-plant system. Thermal Processing by Incineration Free Release for recycling Drying Bed Sludge Sewage Treatment and Waste Water Free release to a landfill or burial Treatment Facilities Metals See DAW See DAW Irradiated Hardware Fuel Pool, Reactor Components Volume Reduction for packaging efficiencies 5.DOCUMENTATION 5.1.1. Records of reviews performed shall be retained license. This documentation shall contain: for the duration of the unit operating 1. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change, and 2. A determination which documents that the change will maintain the overall conformance of waste products to Federal (10CFR61 and the Branch Technical Position), State, or other applicable requirements, including applicable burial site criteria.REFERENCES Technical SDecifications:
4.4.2. Containers of solidified liquid waste shall be INSPECTED for solidification quality and/or dewatering requirements per the burial site, offsite vendor acceptance, or station acceptance criteria, as applicable.
6.6.1.6.1.1. The details contained in Current Tech Specs (CTS) or Improved Technical Specifications (ITS), as applicable, in regard to the Process Control Program (PCP), are to be relocated to the Licensee Controlled Documents.
4.4.3. Shipments sent to an off site processor shall be INSPECTED to ensure that the applicable processor's waste acceptance criteria are being met.
Some facilities have elected to relocate these details into the Operational Requirements Manual (ORM).Relocation of the description of the PCP from the CTS or ITS does not affect the safe operation of the facility.
4.4.4. Shipments sent for off site storage shall MEET the storage site's waste acceptance criteria.
Therefore, the relocation details are not required to be in the CTS or the ITS to provide adequate protection of the public health and safety.
4.5. Inspection and Corrective Action 4.5.1. Inspection results that indicate non-compliance with applicable NRC, State, vendor, or site requirements shall be IDENTIFIED and TRACKED through the Corrective Action Program.
4.5.2. Administrative controls for preventing unsatisfactory waste forms from being released for shipment are described in applicable station procedures. If the provisions of the Process Control Program are not satisfied, then SUSPEND shipments of defectively packaged radioactive waste from the site. (CM-1) 4.5.3. If freestanding water or solidification not meeting program requirements is observed, then samples of the particular series of batches shall be TAKEN to determine the cause. Additional samples shall be TAKEN, as warranted, to ensure that no freestanding water is present and solidification requirements are maintained.
4.6. Procedure and Process Reviews 4.6.1. The Exelon Nuclear Process Control Program and subsequent changes (other than editorial/minor changes) shall be REVIEWED and APPROVED in accordance with the station procedures, plant-specific Technical Specifications (Tech Spec),
Technical Requirements Manual (T&RM), Operation Requirements Manual (ORM),
as applicable, for the respective station and LS-AA-106. Changes to the Licensees Controlled Documents, UFSAR, ORM, or TRM are controlled by the provisions of 10CFR 50.59.
 
RW-AA-100 Revision 8 Page 7 of 9 4.6.2. Any changes to the PCP shall be reviewed to determine if reportability is required in the Annual Radiological Effluent Release Report (ARERR). The Radwaste Specialist shall ensure correct information is SUBMITTED to the ODCM program owner prior to submittal of the ARERR.
4.6.3. Station processes, applicable site-specific cask manual procedures, or other vendor waste processing/operating procedures shall be approved per RM-AA-102-1006.
Procedures related to waste manifests, shipment inspections, and container activity determinations are CONTROLLED by Radiation Protection Standard Procedures (RP-AA-600 Series).
: 1.     Site waste processing IS CONTROLLED by site operating procedures.
: 2.     Liquid processed by vendor equipment shall be PERFORMED in accordance with vendor procedures.
4.7.     Waste Types, Point of Generation, and Processinq Method Methods of processing and individual vendors may CHANGE due to changing financial and regulatory options. The table below is a representative sample. It is not intended be all encompassing.
AVAILABLE WASTE WASTE STREAM               POINTS OF GENERATION                     PROCESSING METHODS Bead Resin             Systems - Fuel Pool, Condensate,         Dewatering, solidification to an Reactor Water Cleanup, Blowdown,         unstable/stable state Equipment Drain, Chemical and           Thermal Processing Volume Control Systems, Floor Drain, Maximum Recycle, Blowdown, Boric         Free Release to a Land Fill Acid Recycling System, Vendor Supplied Processing Systems, and Portable Demin System Powdered Resin         Systems - (Condensate System, Floor     Dewatering, solidification to an Drain/Equipment Drain filtration, Fuel   unstable/stable state Pool)                                   Thermal Processing Concentrated Waste     Waste generated from Site               Solidification to an unstable/stable Evaporators resulting typically from the state Floor Drain and Equipment Drain         Thermal Processing Systems Sludge                 Sedimentation resulting from various     Dewatering, solidification to an sumps, condensers, tanks, cooling       unstable/stable state tower, emergency spray pond, holding     Thermal Processing pond, and oily waste separators Evaporation on-site or at an offsite processor On-site disposal per 10CFR20.2002 permit
 
RW-AA-100 Revision 8 Page 8 of 9 AVAI LABLE WASTE POEING            ME WASTE STREAM                 POINTS OF GENERATION                       PROCESSING METHODS Filter cartridges         Systems - Floor/Equipment Drains,         Dewatering, solidification to an Fuel Pool; cartridge filters are typically unstable/stable state generated from clean up activities         Processed by a vendor for volume within the fuel pool, torus, etc           reduction Dry Active Waste           Paper, wood, plastic, rubber, glass,       Decon/Sorting for Free Release metal, and etc. resulting from daily       Compaction/Super-compaction plant activities Thermal Processing by Incineration or glass vitrification Sorting for Free Release Metal melting to an ingot Contaminated Oil           Oil contaminated with radioactive         Solidification unstable state materials from any in-plant system.       Thermal Processing by Incineration Free Release for recycling Drying Bed Sludge         Sewage Treatment and Waste Water           Free release to a landfill or burial Treatment Facilities Metals                     See DAW                                   See DAW Irradiated Hardware       Fuel Pool, Reactor Components             Volume Reduction for packaging efficiencies
: 5.           DOCUMENTATION 5.1.1.       Records of reviews performed shall be retained for the duration of the unit operating license. This documentation shall contain:
: 1. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change, and
: 2. A determination which documents that the change will maintain the overall conformance of waste products to Federal (10CFR61 and the Branch Technical Position), State, or other applicable requirements, including applicable burial site criteria.
: 6.           REFERENCES 6.1.         Technical SDecifications:
6.1.1.       The details contained in Current Tech Specs (CTS) or Improved Technical Specifications (ITS), as applicable, in regard to the Process Control Program (PCP),
are to be relocated to the Licensee Controlled Documents. Some facilities have elected to relocate these details into the Operational Requirements Manual (ORM).
Relocation of the description of the PCP from the CTS or ITS does not affect the safe operation of the facility. Therefore, the relocation details are not required to be in the CTS or the ITS to provide adequate protection of the public health and safety.
 
RW-AA-100 Revision 8 Page 9 of 9 6.2. Writers'  
RW-AA-100 Revision 8 Page 9 of 9 6.2. Writers'  


==References:==
==References:==


6.2.1. Code of Federal Regulations:
6.2.1. Code of Federal Regulations: 10 CFR Part 20, Part 61, Part 71,49 CFR Parts 171-172 6.2.2. Low Level Waste Licensing Branch Technical Position on Radioactive Waste Classification, May 1983 6.2.3. Technical Position on Waste Form (Revision 1), January 1991 6.2.4. Branch Technical Position on Concentration Averaging and Encapsulation, January 1995 6.2.5. Regulatory Guide 1.21, Measuring Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants 6.2.6. I.E. Circular 80.18, 10CFR 50.59 Safety Evaluation for Changes to Radioactive Waste Treatment Systems 6.3. Users'  
10 CFR Part 20, Part 61, Part 71,49 CFR Parts 171-172 6.2.2. Low Level Waste Licensing Branch Technical Position on Radioactive Waste Classification, May 1983 6.2.3. Technical Position on Waste Form (Revision 1), January 1991 6.2.4. Branch Technical Position on Concentration Averaging and Encapsulation, January 1995 6.2.5. Regulatory Guide 1.21, Measuring Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants 6.2.6. I.E. Circular 80.18, 10CFR 50.59 Safety Evaluation for Changes to Radioactive Waste Treatment Systems 6.3. Users'  


==References:==
==References:==


6.3.1. Quality Assurance Program (QATR)6.3.2. LS-AA-106, Plant Operations Review Committee 6.3.3. RM-AA-102-1006, Processing Vendor Documents 6.3.4. RP-AA-600 Series, Radioactive Material/Waste Shipments 6.3.5. CY-AA-170-2000, Annual Radioactive Effluent Release Report 6.4. Station Commitments:
6.3.1. Quality Assurance Program (QATR) 6.3.2. LS-AA-106, Plant Operations Review Committee 6.3.3. RM-AA-102-1006, Processing Vendor Documents 6.3.4. RP-AA-600 Series, Radioactive Material/Waste Shipments 6.3.5. CY-AA-170-2000, Annual Radioactive Effluent Release Report 6.4. Station Commitments:
6.4.1. Peach Bottom CM-1, T03819, Letter from G.A. Hunger, Jr., dated Sept. 29 1994, transmitting TSCR 93-16 (Improved Technical Specifications).
6.4.1. Peach Bottom CM-1, T03819, Letter from G.A. Hunger, Jr., dated Sept. 29 1994, transmitting TSCR 93-16 (Improved Technical Specifications).
6.4.2. Limerick CM-2, T03896, 1OCFR20.2002 permit granted to Limerick via letter dated July 10, 1996.7. ATTACHMENTS  
6.4.2. Limerick CM-2, T03896, 1OCFR20.2002 permit granted to Limerick via letter dated July 10, 1996.
-None}}
: 7. ATTACHMENTS - None}}

Revision as of 20:04, 4 November 2019

Submittal of Radioactive Effluent Release Report for 2012
ML13121A076
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 04/26/2013
From: Hanley T
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
SVP-13-031
Download: ML13121A076 (87)
v • d • e


Text

M Exelon Generation.

SVP-13-031 10 CFR 50.36a April 26, 2013 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265

Subject:

Radioactive Effluent Release Report for 2012 Pursuant to Technical Specifications Section 5.6.3 and 10 CFR 50.36a, enclosed is the Quad Cities Nuclear Power Station Radioactive Effluent Release Report for January through December 2012. There was one abnormal release that occurred during 2012. This release resulted in a minor contribution to normal plant radioactive effluents and is discussed in detail in the report.

In addition, pursuant to Section 12.7.3.4 of the Off-Site Dose Calculation Manual (ODCM),

enclosed (Attachment 2) is a copy of the Process Control Program for Radioactive Wastes (RW-AA-100, Revision 8) which was revised in 2012.

Should you have any questions concerning this letter, please contact Mr. Wally J. Beck at (309) 227-2800.

Respectfully, Ti~m Hawley *lO Site Vice President Quad Cities Nuclear Power Station Attachments:

1. 2012 Annual Radioactive Effluent Release Report
2. RW-AA-100, Revision 8, Process Control Program for Radioactive Wastes cc: Regional Administrator - NRC Region III NRC Senior Resident Inspector - Quad Cities Nuclear Power Station 41ý

Attachment 1 2012 Annual Radioactive Effluent Release Report

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Effluent & Waste Disposable Summary Gaseous Effluents - Summation of all Releases Period: January - December 2012 Unit: 1 &2 A. Fission & Activation Gases Unit Quarter Quarter Quarter Quarter Total Est.

1 2 3 4 Total Error %

1. Total Release Ci 3.07E+01 3.07E+01 2.98E+01 3.18E+01 1.23E+02 12.7
2. Average release rate for the period VCi/sec 3.91 E+00 3.91 E+00 3.74E+00 4.OOE+00
3. Percent of ODCM limit(1 ) %Y 3.01 E-03 3.02E-03 2.89E-03 3.11 E-03

%_ 7.70E-04 7.72E-04 7.42E-04 7.95E-04 B. Iodine

1. Total Iodine- 131 Ci 4.12E-04 3.68E-04 1.51E-04 9.35E-05 1.02E-03I 41.7 I
2. Average release rate for the period [tCi/sec 5.24E-05 4.68E-05 1.90E-05 1.18E-05
3. Percent of ODCM limit  % N/A(2) N/A(2) N/A(2) N/A(2)

C. Particulates(3)

1. Particulates with half-lives >8 days Ci 4.67E-04 5.27E-04 2.16E-04 2.86E-04 1.50E-03 1I 3i2.2I
2. Average release rate for the period pCi/sec 5.94E-05 6.70E-05 2.72E-05 3.60E-05
3. Percent of ODCM limit  % N/A(2) N/A(2) N/A12) N/A(2)
4. Gross alpha radioactivity Ci <LLD(4 ) <LLD(4) <LLD(4) <LLD(4 )

D. Tritium

1. Total Release Ci 1.47E+01 2.26E+01 2.58E+01 2.OOE+01 8.32E+01 6.3
2. Average release rate for the period VCi/sec 1.88E+00 2.87E+00 3.24E+00 2.52E+00
3. Percent of ODCM limit  % N/A(2) N/A(2) N/A(2) N/A(2)

E. Carbon- 14

1. Total Release Ci 6.93E+00 6.65E+00 7.57E+00 7.58E+00 2.88E+01 N/A
2. Average release rate for the period uCi/sec I 8.81E-01 I 8.46E-01 1 9.52&~01 1 9.53E-01
3. Percent of ODCM limit  % N/A(2) N/A(2) 1 N/A(2) N/A(2 )

F. Iodine 131 & 133, Tritium, Particulate >8 day, and C-14

1. Percent of ODCM limit  % 1.01E+00 9.16E-01 7.10E-01 7.13E01 (1)  % Noble gas gamma (%y)/noble gas beta (%13) dose limits (2) Percent of ODCM Limit is captured in aggregate in section F (3) Nuclides with less than 8-day half-lives are not included per the ODCM, with the exception of those with regulatory required LLDs (La-140 and Mo-99)

(4) Gaseous LLDs reported on page 6 of 75 Page 1 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Effluent & Waste Disposable Summary Gaseous Effluents Release Point Main Chimney (Elevated)

Period: January - December 2012 Unit: 1 &2 Nuclides Continuous Mode Batch Mode Released 11 Quarter

1. Fission
1. Un Quarter Quarter Quarter Quarter Total Quarter Quarter Quarter Quarter gases it 1 2 3 4 1 2 3 4 Kr-85 Ci <LLD") <LLD"1 ) <LLD( ) 1

<LLD(') <LLD(') NA(2) NA(2) NA(2) NA1 Kr-85m Ci 1.34E-01 1.32E-01 1.34E-01 1.49E-01 5.49E-01 NA12) NA(2) NA(2) NA1 Kr-87 Ci 8.65E-01 8.28E-01 8.03E-01 8.59E-01 3.36E+00 NA(2) NA(2) NA(2) NA1 Kr-88 Ci 5.26E-01 5.06E-01 4.85E-01 5.21E-01 2.04E+00 NA(2) NA(2) NA(2) NA1 Xe-133 Ci 2.31E-01 2.54E-01 3.48E-01 3.61E-01 1.19E+00 NA(2) NA(2) NA(2) NA1 Xe-135 Ci 7.90E-01I 7.62E-01 9.61E-01 7.72E-01 3.29E+00 NA(2) NA(2) NA(2) NA1 Xe-135m Ci 5.87E+00 5.79E+00 5.55E+00 5.94E+00 2.32E+01 NA(2) NA(2) NA(2) NA1 Xe-138 Ci 2.22E+01 2.23E+01 2.13E+01 2.29E+01 8.87E+01 NA(2) NA(2) NA(2) NA(

Ar-41 Ci 1.20E-01 1.29E-01 2.19E-01 2.62E-01 7.30E-01 NA121 NA121 NAe21 NA1 Total for Period Ci 3.07E+01 3.07E+01 2.98E+01 3.18E+01 1.23E+02 NA121 NA1 2) NA(2) NA1

2. lodines 1-131 Ci 4.12E-04 3.68E-04 1.51E-04 9.35E-05 1.02E-03 NA(2) NA1(2) NA(2) NA(2) NA(2) 1-133 Ci 1.96E-03 2.29E-03 2.07E-03 1.72E-03 8.04E-03 NA(2) NA1(2) NA(2) NA(2) NA(2) 1-135 Ci <LLD(') <LLD(') IDF <LLD(')

< LLD( NA(2) NA(2) NA(2) NA(2) NA(2)

Total for Period Ci 2.37E-03 2.66E-03 2.22E-03 1.82E-03 9.06E-03 NA(2) NA(2) NA(2) NA(2) NA(2)

3. Particulates Fe-55 Ci <LLD(1 ) <LLD(') <LLD(') <LLD(1 ) <LLD(') NA(

Ni-63 Ci <LLD(1 ) <LLD(1 ) <LLD(') <LLD(') <LLD(1 ) NA1 Sr-89 Ci 1.74E-04 1.69E-04 1.46E-04 1.25E-04 6.14E-04 NAl Sr-90 Ci <LLD(') <LLD(') <LLD(') <LLD(1 ) <LLD(') NA(

Cs-1 34 Ci <LLD(1 ) <LLD(1 ) <LLD(1 ) <LLD(1 ) <LLD(') NA1 Cs-1 37 Ci <LLD(') <LLD(') <LLD(') <LLD <LLD(') NA1 Ba-140 Ci <LLD(1 ) 1.35E-04 3.66E-05 4.96E-05 2.21E-04 NA1 La-14013) Ci <LLD(') 1.35E-04 3.66E-05 4.96E-05 2.21E-04 NA1 Cr-51 Ci <LLD(1 ) <LLD(') <LLD(') <LLD(') <LLD(1 ) NA1 Mn-54 Ci <LLD(') <LLD(1 ) <LLD(1 ) <LLD(') <LLD(1 ) NA1 Co-58 Ci <LLD(1 ) <LLD(1 ) <LLD(') <LLD(1 ) <LLD(1 ) NA1 Co-60 Ci 8.35E-05 3.89E-05 <LLD(') 3.82E-05 1.61 E-04 NA1 Mo-99 Ci <LLD(1 ) <LLD(') <LLD(') <LLD(') <LLD(1 ) NA1 Ag-110m Ci <LLD(') <LLD(1 ) <LLD(') <LLD(1 ) <LLD(1 ) NA1 Ce-141 Ci <LLD(1 ) <LLD(1 ) <LLD(') <LLD(1 ) <LLD(1 ) NA1 Ce-144 Ci <LLD(') <LLD(') <LLD(1 ) <LLD(1 ) <LLD(') NA1 Total for Period Ci 2.58E-04 3.43E-04 1.90E-04 2.12E-04 1.ooE-03 NA1 (1) Gaseous LLD's reported on page 6 of 75 (2) No gaseous batch releases (3) Not included on summary page due to half-life <8 days Page 2 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Effluent & Waste Disposable Summary Gaseous Effluents Release Point Reactor Vents (Mixed Mode)

Period: January - December 2012 Unit: 1 &2 Nuclides I Continuous Mode Batch Mode Released I I

1. Fission Unit Quarter Quarter Quarter Quarter Total Quarter Quarter Quarter Quarter Total gases 1 2 3 4 1 2 3 4 Kr-85 Ci <LLD(1 " <LLD(1 ) <LLD(1 ) <LLD(1 ) <LLD(') NA(2) NA(2) NA(2) NA(2) NA(2)

Ci <LLD(') <LLD(1 ) <LLD(1 ) <LLD(') <LLD(') NA(2) NA(2) NA(2) NA(2) NA(2)

Kr-85m K r-87 Ci <LLD ( ) <LLD 1 ( )

1

<LLD 11 ( ) <LLD 1 ( ) <LLD 1 ( ) NA12 (1 NA'122211 NA12 NA( 2 NA1(2)

Kr-88 ci <LLD(') <LLD(') <LLD( ) <LLD(') <LLD(') NA121 NA NA121 NA121 NA 21 Xe-133 Ci <LLD(1 ) <LLD(') <LLD(1 ) <LLD(') <LLD(') NA(2) NA(2) NA(2) NA(2) NA(2)

Xe-1 33m Ci <LLD(') <LLD(') <LLD(') <LLD(') <LLD(') NA(2) NA(2) NA(2) NA(2) NA(2) 1 Xe-135 Ci <LLD(')

<LL (1 Ci<LLD(

Xe-35m <LD() ) <LLD(1 ) <LLD(1 ) <LLD017 NA(2) NA(2) NA(2) NA(2) NA(2)

<LD*) LL (1) <LD(* N (2) N (2) N (2)

Xe-1 35 <LLD(1 ) N (2) N (2)

Ci Ar-41 ~ ~~~~

<L() <LLD(1 ) <LLD(1 ) <LLD(') <LLD(1 ) 2

<L() NA(2) NA' 2' NA12'

<L() <L() <L()Ci N(2)~ ~NA'

~ '

N(2) N(2) N(2)

NA 1 21 N(2)

Xe-1r35m Ci <LLD(1') <LLD(') <LLD(') <LLD(1 ) <LLD(') NA'(2 NA121 NA121 NA12' NA1 21 r-134 Ci I-1 LD()

<LLD(') 1 C<LLD( 1

< <LD*) ') <LLD(')

LLD*) <LLD(

<LL (1) 1

) <LLD(')

<L D(* NA(2 N (2) 1 NA121 NA121 NA'2 ' NA12' N (2) N (2) N (2) N (2) 1 21 NA22' NA( 2' NA(21 Total for Period 2.

r-413 lodines 1-131

[ Ci Ci Ci

<LLD(')

<LLD(')

<LLD(')

-__

<LLD('

<LLD(')

<LLD(')

<LLD(')

<LLD(')

<LLD( ) 1

<LLD( )

<LLD(')

<LLD( ')1

<LLD(')

<LLD(')

NA'

<LLD(') 11 NA472)

NA(2)

NA (2)

NA(2)

NA (2) 1 NA (2)

NA(2) NA(2)

NA(2)

NA (2)

NA(2)

Sr-89 1 Ci <LLD ( ) 7<LLD <LLD(1 ) <LLD(') <LLD(1 ) NA1 21 NA1 21 NA1 2' NA1 21 NA'21 1-135 Ci <LLD( 1

) <LLD(') <LLD(1 ) <LLD(') <LLD(1 ) NA(2)1 NA12' NA12 ) NA121 NA(2)

Ni-3 3 C i <LLD(' ) L MLD1) LD71 L Total for Period Ci <LLD(') <LLD(') <LLD(') <LLD(D1(')) < D

<LLD( 1(

) N (2)

NA(2) N (2)

NA(2) N1(2)

NA (2) N (2)

NA(2) N (2)

NA(2)

3. Particulates[ - _ _ _-_ _ _ _ _ _-_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Fe-55 Ci <LLD(1 ) <LLD(') <LLD(') <LLD(1 ) <LLD(1 ) NA(2) NA(2) NA1(2) NA1(2) NA(2)

Mn-63 Ci <LLD111 <LLD111 <LLD(F <LLD(11 <LLD(11 NA'2 ' NA'2 ' NA' 2' NA12' NA' 2' S0-589 Ci <LLD11' <LLD(11 1 <LLD(1 ) <LLD11'

<LLD( NA'2 ' NA'21 NA' 21 NA' 21 NA121 M0-99 Ci <LLD'11 <LLD(1 <LLD 1) <LLD111 <LLD111 21 2 121

4. 0 -.

NA'(A 2 NA (2')

NA' NA12 NA NA12 NA' 2

' NA122' NA' cg-i134 110 -0 2E 0 )

Cs - 60 cici _.0 7 E11

<LLD - 0' 4 i.3 8 E <LLD

<LLD(* <LLD11

-.

NA'2 '

c e-14M-9 ci Ci <LLD(') <LLD(11'))

<LLD( <LLD(')

<LLDT 1 1)

) <LLD(

<LLD(')

<LLD(') _<LLD( 11 '

<LLD(') NA 12 NA(2) NA( 21 NA12 NA(2) NA(

NA 1221 NA(2) NA NA(1221 NA(2) NA 121 NA(2) 1 111 1 Ba-141 Mn-65 Ci <LLD(

<LLD 1 <LLD(') '

<LLDE-05 <LLD(')

<LLD 111

<LLD111 <LLD()<LLD NA(2) 21 NA(2) 12 NA(2) NA(2) NA(2)

Ag-horn ci <LLD('1 4 1OELD05 <LLD(') <LLD(')4 1 <LLDE-05 OEL05 I NA(12 NA NA12' NA121 NA12 1 NA1212

'

ot fr P Ci <LLD20- <LLD (' <4 L2LDTT <LLD (') <LLD(') NA121 NA(2) NA(2) NA12' NA12' Ce-i5i ci <LLD(') <LLD(') <LLD(') <LLD(') <LLD(') NA (2 ) NA'(2 ) NA1(2 ) NA (2 ) NA (2 )

ce-i 4 ci <LLD(') <LLD(') <LLD(') <LLD(') <LLD(') NA1(2 ) NA (2 ) NA (2 ) NA (2 ) NA (2 )

Cn-58 ci <LLD(') <LLD(') <LLD(') <LLD(') <LLD(') NA1(2 ) NA (2 ) NA (2 ) NA (2 ) NA (2 )

Totalfo eidci 2.07E-04 1.384E-04 2.12E-05 6.38E-05 4.30E-04 NA1(2' NA'(21 NA'(21 NA1(2' NA1(2' (1) Gaseous LLD's reported on page 6 of 75 (2) No gaseous batch releases (3) Not included on summary page due to half-life <8 days Page 3 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Effluent & Waste Disposal Summary Liquid Effluents - Summation of all Releases Period: January - December 2012 Unit: 1 &2 A. Fission & Activation Products Unit Quarter Quarter Quarter Quarter Total Est.

1 2 3 4 Total Error %

1. Total Release (not including tritium, Ci 6.67E-03 2.25E-04 2.39E-04 3.01 E-05 7.16E-03 4.8 D&E gases &alpha) (4) 2 Average diluted concentration during plCi/mL 2.34E-1 1 5.07E-13 4.83E-13 8.57E-14 period
3. Percent of applicable limit(') WB 1.79E-05 4.02E-05 4.63E-05 7.62E-07 Organ 8.92E-04 2.09E-05 2.44E-05 1.62E-06 Maximum diluted concentration during piCi/mL NA(3) NA(3) NA(3) NA(3) 4.

batch discharges IIIII B. Tritium I

1. Total Release (4) j Ci 8.13E-02 I 2.05E-03 I 4.33E-03 [ 3.94E-04 8.81E-02 4.1
2. Average diluted concentration during paCi/ml- 2.86E-10 4.62E-12 8.76E-12 1.12E-12 period
3. Percent of applicable limit  % 9.53E-06 I 1.54E-07 I 2.92E-07 I 3.73E-08 C. Dissolved & Entrained Gases
1. Total Release
2. Average diluted concentration during period
3. Percent of applicable limit D. Gross Alpha Activity 1I
1. Total Release Ci <LLD(2 ) <LLD(2 ' <LLD(2 ) <LLD(2 ) <LLD(2 ) 14.8 E. Volume Of Waste Released (prior Liters 9.23E+04 4.95E+04 4.95E+04 5.57E+04 2.47E+05 to dilution)

F. Volume Of Dilution Water Used Liters 2.85E+11 4.43E+11 4.95E+11 3.51E+11 1.57E+12 During Period (1) Whole body/organ (ODCM)

(2) Liquid LLD's reported on page 7 of 75 (3) No Batch dicharges in 2012 (4) Total Ci's are those reported as the Abnormal Liquid Release Page 4 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Effluent & Waste Disposal Summary Liquid Effluents Release Point MississiDoi River Period:

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

JanuaryJr - December

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

2012 Unit: 1 &2 Nuclides I Continuous Mode Batch Mode Released 171I Unit Quarter Quarter Quarter Quarter Total Quarter Quarter Quarter Quarter Total 1 2 3 4 1 2 3 4 Sr-89 Ci <LLD(1 ) <LLD(1 ) <LLD(') <LLD(') <LLD(') NA(2) NA( 2) NA(2) NA(2) NA(2) 1 NA(2) NA(2) NA(2) NA(2) NA(2)

Sr-90 Ci <LLD(') <LLD(") <LLD(') <LLD( ) <LLD(')

Cs-134 Ci 6.53E-06 <LLD(') <LLD(') <LLD(') 6.53E-06 NA(2) NA(2) NA(2) NA (2) NA_(2)

Cs-137 Ci 1.43E-04 4.87E-06 6.36E-06 <LLD(1) 1.54E-04 NA(2 ) NA(2) NA(2) NA(2) NA(2) 1-131 Ci <LLD(') <LLD(1 ) <LLD(') <LLD(') <LLD(1 ) NA(2) NA(2) NA(2) NA(2) NA(2)

Co-58 Ci 2.16E-04 2.37E-06 1

<LLD( ) <LLD(') 2.18E-04 NA(2) NA(2) NA(2) NA(2) NA(2)

Co-60 Ci 5.06E-03 1.76E-04 1.95E-04 2.48E-05 5.45E-03 NA(2) NA(2) NA(2) NA(2) NA(2) 2 Fe-55 Ci <LLD(1 ) <LLD(1 ) <LLD(') <LLD(') <LLD(') NA (2) NA(N ) NA (2) _NA_(2) NA(2) 2 Fe-59 Ci <LLD(1 ) <LLD(1 ) <LLD(1 ) <LLD(1 ) <LLD(1 ) NA(2) NA( ) NA(2) NA(2) NA(2) 1 2 NA(2) NA (2) NA_(2)

Zn-65 Ci 2.25E-04 6.25E-06 4.41E-06 <LLD( ) 2.35E-04 NA( ) NA(2)

Mn-54 Ci 1.02E-03 3.47E-05 3.35E-05 5.24E-06 1.10E-03 NA(2) NA (2) NA_(2) NA (2) NA_(2)

Cr-51 Ci <LLD(') <LLD(1 ) <LLD(') <LLD(') <LLD(') NA(2) NA(2) NA(2) NA(2) NA(2) 1 1 NA(2) NA(2) NA(2) NA(2)

Mo-99 Ci <LLD( ) <LLD(') <LLD(') <LLD(') <LLD( ) NA(2) 1 1 1 Ag-110m Ci <LLD( ) <LLD( ) <LLD(') <LLD( ) <LLD(1)N A 2 NA NA_2_ NA(2 ) NA(2) 1 1 1 1 1 NA(2) NA(2) NA(2) NA(2)

Ni-63 Ci <LLD( ) <LLD( ) <LLD( ) <LLD( ) <LLD( ) NA(2)

Total for Ci 6.67E-03 2.25E-04 2.39E-04 3.01 E-05 7.16E-03 NA(2) NA(2) NA(2) NA(2) NA(2)

Period Kr-85 Ci <LLD(') <LLD(1 ) <LLD(') <LLD(') <LLD(') NA(2) NA(2) NA(2) NA(2) NA(2) 1 1 NA(2) NA(2) NA(2) NA(2)

Kr-85m Ci <LLD(') <LLD(') <LLD( ) <LLD(') <LLD( ) NA(2) 1 1 NA(2) NA(2) NA(2)

Kr-87 Ci <LLD(') <LLD(') <LLD(') <LLD( ) <LLD( ) NA(2) NA(2)

Kr-88 Ci 1

<LLD( ) <LLD(') 1

<LLD( ) <LLD(') 1

<LLD(') NA(2) NA 2 ) NA(2) NA(2) NA(2) 1 1 NA(2) NA(2) NA(2) NA(2)

Xe-133 Ci <LLD( ) <LLD(') <LLD( ) <LLD(') <LLD(') NA(2)

Xe-133m Ci <LLD(') <LLD" ) 1

<LLD(') <LLD(') <LLD(') NA(2) N 2)

NAN NA(2) NA_(2) NA(2) 1 NA(2)

Xe-1 35 Ci <LLD(') <LLD(') <LLD(') <LLD(') <LLD( ) NA(2) NA(2) NA(2) NA(2) 1 1 2 Xe-135m Ci <LLD(') <LLD(') <LLD(') <LLD( ) <LLD( ) NA(2) NA( ) NA(2) NA(2) NA(2) 1 1 1 NA(2) NA(2) NA(2) NA(2)

Xe-138 Ci <LLD( ) <LLD( ) <LLD( ) <LLD(') <LLD(') NA(2) 2 Ar-41 Ci <LLD(') <LLD(') <LLD(1 ) <LLD(1 ) <LLD(') NA(2) NA( ) NA(2) NA(2) NA(2)

(1) Liquid LLD's reported on page 7 of 75 (2) No batch releases during 2012 Page 5 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Effluent & Waste Disposable Summary GASEOUS EFFLUENT LLD's (Most Restrictive)

CONTINUOUS MODE NUCLIDE LOWER LIMITS OF DETECTION (LLD's) UNIT LLD Value ODCM Required LLD

1. Fission gases Kr-85 uCi/cc 3.70E-06 None Kr-85m uCi/cc 1.38E-08 None Kr-87 uCi/cc 3.40E-08 1E-04 Kr-88 uCi/cc 5.41 E-08 1E-04 Xe-133 uCi/cc 2.70E-08 1E-04 Xe-133m uCi/cc 8.71E-08 1E-04 Xe-135 uCi/cc 1.26E-08 1E-04 Xe-135m uCi/cc 1.03E-06 None Xe-138 uCi/cc 2.43E-06 1E-04 Ar-41 uCi/cc 9.00e-09 None NUCLIDE LOWER LIMITS OF DETECTION (LLD's) UNIT LLD Value ODCM Required LLD*
2. lodines 1-131 uCi/cc 8.27E-13 1E-12 1-133 uCi/cc 1.1E-11 1E-10 1-135 uCi/cc 1.29E-08 None NUCLIDE LOWER LIMITS OF DETECTION (LLD's) UNIT LLD Value ODCM Required LLD*
3. Particulates and Tritium H-3 uCi/cc 1.01 E-1 1 1E-06 Fe-55 uCi/cc 7.76E-13 None Ni-63 uCi/cc 1.83e-14 None Sr-89 uCi/cC 4.63E-14 1E-11 Sr-90 uCi/cc 1.26E-13 1E-11 Cs-134 uCi/cc 4.72E-13 1E-11 Cs-137 uCi/cc 5.09E-13 1E-11 Ba-140 uCi/cc 1.63E-12 None La-140 uCi/cc 2.79E-12 None Mn-54 uCi/cc 2.97E-13 1E-11 Co-58 uCi/cc 4.38E-13 1E-11 Fe-59 uCi/cc 8.77E-13 1E-11 Co-60 uCi/cc 8.85E-13 1E-lt Zn-65 uCi/cc 9.42E-13 1E-11 Mo-99 uCi/cc 8.44E-12 1E-11 Ce-141 uCi/cc 5.87E-13 1E-11 Ce-144 uCi/cc 2.43E-12 1E-11 Aq-110m uCi/cc 3.25E-13 None Cr-51 uCi/cc 2.95E-12 None Gross Alpha uCi/cc 2.24E-12 1E-11
  • ODCM REC LLD's for weekly samples. These may be increased by a factor of 10 for daily samples Page 6 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Effluent & Waste Disposable Summary LIQUID EFFLUENT LLD's (Most Restrictive)

BATCH MODE NUCLIDE LOWER LIMITS OF DETECTION (LLD's) ODCM Required LLD UNIT LLD Value

3. Liquids H-3 uCi/cc 1.06E-06 1E-05 Sr-89 uCi/cc 5.OOE-08 5E-08 Sr-90 uCi/cc 2.58E-08 5E-08 Fe-55 uCi/cc 6.78E-07 1E-06 Ar-41 uCi/cc 9.55E-08 None Kr-85 uCi/cc 1.33E-05 None Kr-85m uCi/cc 6.29E-08 None Kr-87 uCi/cc 1.84E-07 1E-05 Kr-88 uCi/cc 1.79E-07 1E-05 Xe-133 uCi/cc 1.49E-07 1E-05 Xe-133m uCi/cc 4.34E-07 1E-05 Xe-135 uCi/cc 4.64E-08 1E-05 Xe-135m uCi/cc 1.84E-06 None Xe-138 uCi/cc 6.65E-06 1E-05 Mn-54 uCi/cc 4.88E-08 5E-07 Co-58 uCi/cc 4.87E-08 5E-07 Co-60 uCi/cc 1.05E-07 5E-07 Zn-65 uCi/cc 1.29E-07 5E-07 Mo-99 uCi/cc 4.66E-07 5E-07 1-131 uCi/cc 5.10E-08 1E-06 Cs-134 uCi/cc 5.59E-08 5E-07 Cs-137 uCi/cc 7.46E-08 5E-07 Ce-141 uCi/cc 7.95E-08 5E-07 Ce-144 uCi/cc 3.61E-07 5E-06 Gross Alpha uCi/cc 9.68E-08 1E-07 Fe-59 uCi/cc 1.18E-07 5E-07 Ni-63 uCi/cc 5.87E-07 None Cr-51 uCi/cc 4.75E-07 None Ag-110m uCi/cc 6.13E-08 None Page 7 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Supplemental Information Discussion of Radiation and Radioactivity (1)

Radiation and Radioactivity All matter is made of atoms. An atom is the smallest part into which matter can be broken down and still maintain all its chemical properties. Nuclear radiation is energy, in the form of waves or particles that is given off by unstable, radioactive atoms. Radioactive material exists naturally and has always been a part of our environment. The earth's crust, for example, contains radioactive uranium, radium, thorium, and potassium. Some radioactivity is a result of nuclear weapons testing. Examples of radioactive fallout that is normally present in environmental samples are cesium-137 and strontium-90. Some examples of radioactive materials released from a nuclear power plant are cesium-1 37, iodine-1 31, strontium-90, and cobalt-60. Radiation is measured in units of millirem; much like temperature is measured in degrees. A millirem is a measure of the biological effect of the energy deposited in tissue.

The natural and man-made radiation dose received in one year by the average American is 300 to 400 mrem (References 2, 3, 4 in Table - 1 below). Radioactivity is measured in curies.

A curie is that amount of radioactive material needed to produce 37,000,000,000 nuclear disintegrations per second. This is an extremely large amount of radioactivity in comparison to environmental radioactivity. That is why radioactivity in the environment is measured in picocuries. One picocurie is equal to one trillionth of a curie.

Sources of Radiation As mentioned previously, naturally occurring radioactivity has always been a part of our environment. Table - 1 shows the sources and doses of radiation from natural and man-made sources.

(1) This section adapted with permission of Ken Sejkora, Pilgrim Nuclear Power Station Page 8 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Supplemental Information Table - 1 Radiation Sources and Corresponding Doses (1)

NATURAL MAN-MADE Radiation Dose Radiation Dose (millirem/year) (millirem/year)

Internal, inhalation (2) 228 Medical (3) 300 External, space 33 Consumer (4) 13 Internal, ingestion 29 Industrial(5) 0.3 External, terrestrial 21 Occupational 0.5 Weapons Fallout <1 Nuclear Power Plants <1 Approximate Total 311 Approximate Total 314 (1) Information from NCRP Reports 160 and 94 (2) Primarily from airborne radon and its radioactive progeny (3) Includes CT (147 mrem), nuclear medicine (77 mrem), interventional fluoroscopy (43 mrem) and conventional radiography and fluoroscopy (33 mrem)

(4) Primarily from cigarette smoking (4.6 mrem), commercial air travel (3.4 mrem), building materials (3.5 mrem), and mining and agriculture (0.8 mrem)

(5) Industrial, security, medical, educational, and research Cosmic radiation from the sun and outer space penetrates the earth's atmosphere and continuously interacts with us via rays and charged particles. Some of this cosmic radiation interacts with gases and particles in the atmosphere, making them radioactive in turn. These radioactive byproducts from cosmic ray interaction are referred to as cosmogenic radionuclides. Isotopes such as beryllium-7 and carbon-14 are formed in this way. Exposure to cosmic and cosmogenic sources of radioactivity results in about 33 mrem of radiation dose per year.

Additionally, natural radioactivity is in our body and in the food we eat (about 29 millirem/yr),

the ground we walk on (about 21 millirem/yr) and the air we breathe (about 228 millirem/yr).

The majority of a person's annual dose results from exposure to radon and thoron in the air we Page 9 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Supplemental Information breathe. These gases and their radioactive decay products arise from the decay of naturally occurring uranium, thorium and radium in the soil and building products such as brick, stone, and concrete. Radon and thoron levels vary greatly with location, primarily due to changes in the concentration of uranium and thorium in the soil. Residents at some locations in Colorado, New York, Pennsylvania, and New Jersey have a higher annual dose as a result of higher levels of radon/thoron gases in these areas. In total, these various sources of naturally-occurring radiation and radioactivity contribute to a total dose of about 311 mrem per year.

In addition to natural radiation, we are normally exposed to radiation from a number of man-made sources. The single largest doses from man-made sources result from therapeutic and diagnostic applications of x-rays and radiopharmaceuticals. The annual dose to an individual in the U.S. from medical and dental exposure is about 300 mrem. Consumer products, such as televisions and smoke detectors, contribute about 13 mrem/yr. Much smaller doses result from weapons fallout (less than 1 mrem/yr) and nuclear power plants. Typically, the average person in the United States receives about 314 mrem per year from man-made sources.

Page 10 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Supplemental Information Facility: Quad Cities Nuclear Power Station (QCNPS) January - December 2012 Licensee: Exelon Generation Company

1. Regulatory Limits
a. For Noble Gases:

Dose rate (per site)

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

Dose Gamma Radiation (per unit)

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

Beta Radiation (per unit)

1. Less than or equal to 10 mrad/quarter.
2. Less than or equal to 20 mrad/year.

b,c. For Iodine-1 31, Iodine-1 33, Tritium, Carbon-14, and for all radionuclides in particulate form with half-lives greater than 8 days.

Dose Rate

1. Less than 1500 mrem/year. (per site)

Dose (per unit)

1. Less than or equal to 7.5 mrem/quarter.
2. Less than or equal to 15 mrem/year.
d. For Liquid: (per unit)

Less than or equal to 1.5 mrem to the whole body during any calendar quarter.

Less than or equal to 5 mrem to any organ during any calendar quarter.

Less than or equal to 3 mrem to the whole body during any calendar year.

Less than or equal to 10 mrem to any organ during any calendar year.

Page 11 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Supplemental Information

2. Maximum Permissible Concentration a,b,c. For fission and activation gases, iodines, and particulates with half-lives greater than 8 days, allowable release limits are calculated by solving equations 2.0-5 and 2.0-6 from the Offsite Dose Calculation Manual Part II Chapter 2. The alarm setpoint is conservatively set at approximately 10% of the 1OCFR20 limit.
d. For liquid effluents, with the exception of tritium and dissolved & entrained noble gasses, allowable release limits are calculated by solving equations 2.0-1 and 2.0-2 from the Offsite Dose Calculation Manual Part II Chapter 2. The MPC values used for the monitors were as follows:

Radwaste discharge 3.03E-07 gCi/ml Service water 1.OOE-05 iCi/ml The allowable release limits for tritium and dissolved & entrained noble gases are as follows :

Tritium : 3.OOE-03 uCi/mL taken from Reg Guide 1.21 Dissolved & Entrained noble gases: 2.OOE-04 uCi/mL taken from NUREG 1302

3. Average Energy The average gamma energy used to calculate the alarm setpoints for the noble gas monitors was:

9.63E-01 MeV for Quarter 1 9.64E-01 MeV for Quarter 2 9.65E-01 MeV for Quarter 3 9.56E-01 MeV for Quarter 4

4. Measurements and Approximations of Total Radioactivity
a. Fission and Activation Gases
b. lodines
c. Particulates a,b,c. The main chimney and reactor building ventilation exhaust systems are continually monitored for iodines and particulates. These samples are pulled every 7 days and analyzed by gamma isotopic. The particulate papers are composited every 31 days and sent to a vendor for Sr-89/90 and gross alpha analysis. Noble gas grab samples are pulled and analyzed by gamma isotopic weekly. Tritium samples are pulled and analyzed every month.

Page 12 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Supplemental Information The Sr-89/90 and gross alpha curies released values reported are actual. On a real time basis, the portion of the "percent of applicable limit" for these contributors is reported based on projections using the previous available data.

The actual results are obtained by editing the ODCM software inputs when the vendor results become available. Therefore, the "percent of applicable limits" in this report are actual.

The continuous strip chart recorders for the monitors on the release points are reviewed for spikes and the activity released is calculated. An additional calculated activity for noble gases is added to the main chimney release each month. This calculation is done because most of the grab samples show less than the lower limit of detection due to the low amount of activity and the large dilution flow at the sample point. The calculation takes into account the normal offgas train and the gland steam contribution to the release.

The average flow at the release points is used to calculate the curies released.

There are no ground level releases from QCNPS. All monitored releases are considered either elevated or mixed mode.

d. Carbon-14 Quad Cities has estimated its Carbon-14 generation and release in accordance with EPRI Technical Report 1021106, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents". The Quad Cities estimate of 2.88E+01 Ci of Carbon-14 and the resultant 2.88E+01 Ci 14CO2 released is based upon a normalized Carbon-14 production rate of 5.1OE+00 Ci/GWTh-yr, a gaseous release fraction of 1.00, a Carbon-14 C02 fraction of 1.00, a reactor power rating of 2957 MWTh/unit for 2 units, and a calculated Effective Full Power days based upon Total Core Therms data.
e. Liquid Effluents The River Discharge Tanks are analyzed before discharge by gamma isotopic. A composite representative portion of this sample is saved. This is composited with other discharges that occurred every 31 days and is analyzed for tritium and gross alpha. The monthly composites are composited quarterly and sent to a vendor for Sr-89/90 and Fe-55 analyses. The discharge bay is sampled every 31 days and analyzed by gamma isotopic for tritium and gross alpha. It is sampled quarterly and sent to a vendor for Sr-89/90 and Fe-55 analysis. On a real time basis, the portion of the "percent of applicable limit" for these contributors is based on projections using scaling factors. The actual results are obtained by editing the ODCM software inputs when the vendor results become available.

Therefore, the "percent of applicable limits" in this report are actual.

Page 13 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Supplemental Information The tank volumes and activities are used to calculate the curies released for the River Discharge Tank. The total water released during the quarter and the activity is used to calculate the diluted activity released at the discharge bay, from batch discharges.

f. Estimated Total Error Percent The estimated total error percents were calculated by taking the square root of the sum of the squares of errors for sampling and measurement parameters.
g. Less than the Lower Limit of Detection (<LLD)

Samples are analyzed such that the Technical Specification LLD requirements are met. When a nuclide is not detected during the quarter, then <LLD is reported. The most conservative LLD's used for counting effluent samples are included in this report.

5. Batch Releases
a. Liquid
1. Number of releases: 0
2. Total time: N/A
3. Maximum time: N/A
4. Average time: N/A
5. Minimum time: N/A
6. Average stream flow: N/A
b. Gaseous
1. NONE
6. Abnormal Releases Abnormal Releases
a. Liquid A leak into the 1A RHR (Residual Heat Removal) heat exchanger, service water side, developed in May 2011. This leak has been subsequently repaired during Q1 R22 in March of 2013. This produced a monitored liquid effluent release via the continuous liquid release pathway each time that the "A"loop of the Unit-1 RHR system was started. The activity identified from the leak was included in the monthly effluent calculations and is included in the "continuous" liquid section of this report. A temporary modification to pressurize the service water side of the affected heat exchanger was installed in September 2011, which significantly reduced the leakage rate.

Page 14 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Supplemental Information

b. Gaseous
1. NONE
8. Radiological Impact on Man
a. Liquid Dose to a Member of the Public for 2012 Total Body: 2.78E-05 mrem Organ: 4.55E-05 mrem
b. Gaseous Dose to a Member of the Public for 2012 Total Body: 4.32E-02 mrem Skin: 6.02E-04 mrem Organ (Particulate/lodine/Tritium/C-14): 2.07E-01 mrem The Quad Cities calculated annual doses from Carbon-14 releases have been calculated using the conservative bounding methodologies outlined in the ODCM. The resultant estimated releases of Carbon-14 resulted in a dose contribution of 3.71 E-02 mrem/yr to organ dose (17.9%) and 3.96E-02 mrem/yr to total dose (91.7%). The maximum expected annual dose contribution from Carbon-14 has been calculated to be 2.08E-01 mrem/yr organ dose and 4.15E-02 mrem/yr total body dose. This was obtained using maximum gross thermal capacity maintained for 365 days for both units.
c. Uranium Fuel Cycle Dose to a Member of the Public for 2012 (40CFR1 90)

The main component (7.74 mrem or 99.5%) of the Uranium Fuel Cycle dose for Quad Cities Station is BWR skyshine from N-16 within the turbine building.

BWR skyshine at Quad Cities Station is conservatively determined to the hypothetical maximally exposed member of the public.

Total Body: 7.78E+00 mrem (Skyshine + Total Body component of gaseous and liquid effluents) 31.1% of 40 CFR 190 Limit of 25 mrem/year (Whole Body and Organ).

Thyroid dose of 2.76E-01% of 40 CFR 190 Limit (75 mrem).

Page 15 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Supplemental Information

d. Total Body Doses to the Population and Average Doses to Individuals in the Population from All Receiving-Water-Related-Pathways:

Not applicable for QCNPS

e. Total Body Doses to the Population and Average Doses to Individuals in the Population from Gaseous Effluents to a Distance of 50 Miles:

Not applicable for QCNPS ft Doses From Liquid and Gaseous Effluent to Members of the.Public Due to Their Activities Inside the Site Boundary for the Report Period:

Not applicable for QCNPS. Any member of the public that is onsite for a significant period will be issued a dosimeter.

g. Liquid and Gaseous Effluent Radiation Monitors and Instrumentation Unavailability for the Period Beyond the Requirements of the ODCM, Including Sampling Deviation:

No ODCM monitors were unavailable for greater than 30 days in 2012.

Page 16 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report 10CFR20.1301(a)(1) Compliance Assessment Quad Cities Station Unit One and Unit Two Assessment Period 01/01/2012 THROUGH 12/31/2012 10CFR20.1301(a)(1) Limit 100.0 mrem/year Quad Cities Unit 1

. nd . d

  • I th _

Submitted by: Date: 2 ,.

Reviewed by: Date: L -Z& Page 17 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Maximum Doses Resulting From Airborne Releases/Compliance Status Quad Cities Station - Unit One/Unit Two Unit One Unit Two 10 CFR 50 APP. I Unit One Unit Two Type of Dose Annual Annual Yearly Objective %ofAPP. I %ofAPP. I Gamma Air (mrad) 4.60E-04 4.60E-04 10.0 4.60E-03 4.60E-03 Beta Air (mrad) 2.36E-04 2.36E-04 20.0 1.18E-03 1.18E-03 Organ (mrem) 2.21 E-01 2.21 E-01 15.0 1.47E+00 1.47E+00 Critical Person Child Child Critical Organ Bone Bone The calculation of the above doses was done by an independent contractor utilizing GASPAR, an NRC approved program. The calculation was done with current year meteorological data and equation multipliers outlined in Reg Guide 1.109 and NUREG 0133.

Page 18 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: January - March 2012 Stability Class - Extremely Unstable - 196Ft-33Ft Delta-T (F)

Winds Measured at 33 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 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 5 0 0 0 5 SE 0 1 7 1 0 0 9 SSE 0 7 7 0 0 0 14 S 0 11 17 0 0 0 28 SSW 0 11 5 0 0 0 16 SW 0 4 13 0 0 0 17 WSW 0 0 1 0 0 0 1 W 0 2 2 0 0 0 4 WNW 0 0 5 0 0 0 5 NW 0 0 6 10 0 0 16 NNW 0 0 3 0 0 0 3 variable 0 0 0 0 0 0 0 Total 0 36 71 11 0 0 118 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: 5 Page 19 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: January - March 2012 Stability Class - Moderately Unstable - 196Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW Variable Total 0 11 15 1 0 0 27 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: 5 Page 20 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: January - March 2012 Stability Class - Slightly Unstable - 196Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 2 0 6 NNE 0 1 0 NE 0 2 0 2 ENE 0 1 0 1 E 0 1 0 1 ESE 0 4 0 6 SE 0 0 2 SSE 0 8 0 *8 S 0 4 0 4 SSW 0 4 0 8 SW 0 0 4 WSW 0 4 0 7 W 0 1 8 0 9 WNW 0 1 5 0 8

  • NW 0 3 12 2 0 0 17 NNW 0 1 2 0 0 0 3 Variable 0 0 0 0 0 0 0 Total 0 36 45 6 0 0 87 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stabili ty class: 0 Hours of missing stability measurements in all sta bility cl asses: 5 Page 21 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: January - March 2012 Stability Class - Neutral - 196Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 24 8 5 0 38 NNE 0 14 3 2 0 19 NE 1 7 18 0 0 26 ENE 3 13 8 0 0 24 E 3 14 17 0 0 34 ESE 3 16 17 1 0 37 SE 5 16 15 0 0 36 SSE 2 17 4 0 0 23 S 3 17 3 0 0 23 SSW 2 2 4 0 0 8 SW 0 28 13 3 0 44 WSW 0 19 14 4 0 0 37 W 2 41 54 25 0 0 122 WNW 1 29 74 33 0 0 137

-NW 1 32 81 18 0 0 132 NNW 0 16 14 1 0 0 31 Variable 1 0 0 0 0 0 1 Total 28 305 347 92 0 0 772 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stabili ty class: 0 Hours of missing stability measurements in all sta bility classes: 5 Page 22 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: January - March 2012 Stability Class - Slightly Stable - 196Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 13 15 4 0 32 NNE 7 13 3 0 23 NE 6 15 10 0 31 ENE 9 29 9 0 47 E 9 21 4 0 34 ESE 8 25 11 0 44 SE 15 43 34 0 92 SSE 17 36 15 0 68 S 15 37 3 0 55 SSW 4 19 4 0 27 sw 17 33 16 0 67 WSW 10 47 12 0 70 W 6 57 23 0 90 WNW 10 68 7 0 86 NW 6 35 17 0 60 NNW 8 13 4 0 25 Variable 0 0 0 0 0 Total 160 506 176 0 851 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: 5 Page 23 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: January - March 2012 Stability Class - Moderately Stable - 196Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 5 1 0 0 0 0 6 NNE 3 0 0 0 0 0 3 NE 8 0 0 0 0 0 8 ENE 4 0 0 0 0 S E 8 2 0 0 0 0 10 ESE 16 18 0 34 SE 16 10 0 26 SSE 25 14 0 39 S 16 8 0 24 SSW 2 2 0 5 SW 6 5 0 11 WSW 6 1 0 7 W 1 0 0 1 WNW 5 1 0 6 NW 5 1 0 6 NNW 1 0 0 1 Variable 1 0 0 1 Total 128 64 1 0 0 0 193 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: 5 Page 24 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables.

Quad Cities Generating Station Period of Record: January - March 2012 Stability Class - Extremely Stable - 196Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 4 0 0 0 0 0 4 NNE 4 0 0 0 0 0 4 NE 2 0 0 0 0 0 2 ENE 7 0 0 0 0 0 7 E 11 0 0 0 0 0 11 ESE 18 16 0 34 SE 13 0 14 SSE 10 0 10 S 8 0 8 SSW 1 0 2 SW 4 0 4 WSW 0 0 0 W 4 0 4 WNW 4 0 4 NW 0 0 0 NNW 0 0 0 Variable 0 0 0 Total 90 18 0 108 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: 5 Page 25 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: January - March 2012 Stability Class - Extremely Unstable - 296Ft-33Ft Delta-T (F)

Winds Measured at 296 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 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 2 0 0 2 SE 0 0 0 2 3 0 5 SSE 0 0 1 2 S 9 S 0 0 5 11 6 7 29 SSW 0 0 2 7 1 10 SW 0 0 0 1 0 1 WSW 0 0 0 W 0 0 0 0 0 0 WNW 0 0 0 0 0 0 NW 0 0 0 0 0 0 NNW 0 0 0 0 0 0 Variable 0 0 0 0 0 0 Total 0 6 19 22 9 56 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: 5 Page 26 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: January - March 2012 Stability Class - Moderately Unstable - 296Ft-33Ft Delta-T (F)

Winds Measured at 296 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 NNE 0 0 0 0 0 NE 0 0 0 0 0 ENE 0 0 0 0 0 E 0 0 0 0 1 ESE 1 0 0 3 SE 0 1 0 2 SSE 0 0 1 8 S 0 1 1 7 SSW 0 2 6 SW 0 0 1 1 WSW 0 0 0 4 W 0 2 0 2 WNW 0 1 1 8 NW 0 4 1 8 NNW 0 0 0 4 Variable 0 0 0 0 Total 0 1 19 17 11 6 54 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: 5 Page 27 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: January - March 2012 Stability Class - Slightly Unstable - 296Ft-33Ft Delta-T (F)

Winds Measured at 296 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 2 1 1 0 0 4 NNE 0 1 2 0 0 0 3 NE 0 0 1 0 0 0 1 ENE 0 0 1 0 0 0 1 E 0 1 0 0 1 0 2 ESE 0 3 5 0 10 0 1 0 1 1 3 SSE 0 0 2 2 0 6 S 0 2 2 0 1 6 SSW 0 0 1 0 1 2 SW 0 2 0 0 4 WSW 0 3 1 0 6 W 0 0 0 4 4 9 WNW 0 0 2 6 3 16 NW 0 0 6 7 3 18 NNW 0 1 0 3 0 4 Variable 0 0 0 0 0 0 Total 0 13 24 30 15 13 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: 5 Page 28 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: January - March 2012 Stability Class - Neutral - 296Ft-33Ft Delta-T (F)

Winds Measured at 296 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 10 19 6 9 1 46 NNE 3 5 11 14 4 0 37 NE 2 10 10 22 10 0 54 ENE 3 11 26 23 4 0 67 4 3 13 9 9 1 39 ESE 4 8 6 8 12 1 39 SE 0 9 10 28 19 5 71 SSE 2 5 7 13 8 2 37 S 0 4 10 16 13 5 48 SSW 6 8 13 8 11 47 SW 0 2 13 24 10 8 57 WSW 0 4 21 27 10 7 69 W 5 8 38 40 53 20 164 WNW 3 3 36 52 81 27 202 NW 2 13 16 29 46 10 116 NNW 1 14 13 9 6 1 44 Variable 1 0 0 0 0 0 1 Total 32 115 257 333 302 99 1138 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: 5 Page 29 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: January - March 2012 Stability Class - Slightly Stable - 296Ft-33Ft Delta-T (F)

Winds Measured at 296 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 .8-12 13-18 19-24 > 24 Total N 1 1 6 6 0 0 14 NNE 0 1 8 6 0 0 15 NE 0 3 2 5 0 0 10 ENE 1 2 2 3 0 0 8 E 1 3 3 4 0 0 11 ESE 0 2 3 8 8 2 23 SE 0 3 7 19 11 1 41 SSE 1 0 12 23 16 19 71 S 1 14 43 23 11 93 SSW 0 2 3 13 14 17 49 SW 0 1 7 15 17 2 42 WSW 2 1 4 22 9 0 38 W 2 6 8 31 8 0 55 WNW 0 4 7 38 8 0 57 NW 3 5 8 14 1 0 31 NNW 1 3 16 4 0 0 24 Variable 0 0 0 0 0 0 0 Total 13 38 110 254 115 52 582 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: 5 Page 30 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: January - March 2012 Stability Class - Moderately Stable - 296Ft-33Ft Delta-T (F)

Winds Measured at 296 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 5 2 2 0 0 9 NNE 0 3 1 1 0 0 5 NE 4 0 2 0 0 7 ENE 0 0 0 0 0 0 0 E 0 10 2 0 0 0 12 ESE 0 6 9 7 3 0 25 SE 1 2 4 13 0 24 SSE 0 2 5 12 0 26 S 1 1 6 12 0 24 SSW 0 3 3 11 0 25 SW 4 3 1 0 9 WSW 2 2 2 0 7 W 1 1 4 4 0 10 WNW 1 0 1 0 3 NW 0 0 1 1 0 2 NNW 1 0 2 2 0 5 Variable 0 0 0 0 0 0 Total 12 41 43 71 26 0 193 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: 5 Page 31 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: January - March 2012 Stability Class - Extremely Stable -. 296Ft-33Ft Delta-T (F)

Winds Measured at 296 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 0 0 0 0 0 0 0 NE 0 0 0 0 0 0 0 ENE 0 4 0 0 0 0 4 E 0 2 2 0 0 0 4 ESE 0 0 0 2 0 0 2 SE 0 1 3 0 6 SSE 0 0 1 0 0 2 S 0 0 1 2 0 9 6

SSW 1 1 6 12 0 20 SW 0 1 5 0 0 6 WSW 0 2 3 0 0 5 W 0 1 0 0 0 1 WNW 1 0 0 0 0 1 0 0 0 0 1 NW NNW 0 0 0 0 0 0 Variable 0 0 0 0 0 0 Total 3 19 17 19 0 61 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: 5 Page 32 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: April June 2012 Stability Class - Extremely Unstable 196Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 2 9 2 0 0 13 NNE 0 5 17 1 0 0 23 NE 0 6 13 0 0 0 19 ENE 0 12 20 0 0 0 32 E 0 5 5 2 0 0 12 ESE 0 2 6 9 0 0 17 SE 0 7 12 1 0 0 20 SSE 0 28 12 0 0 0 40 S 0 16 8 0 0 0 24 SSW 0 24 8 0 0 0 32 SW 0 44 26 0 0 0 70 WSW 0 4 5 0 0 0 9 W 0 11 10 2 0 0 23 WNW 0 7 6 3 0 0 16 NW 0 2 17 4 0 0 23 NNW 0 3 13 0 0 0 16 Variable 0 0 0 0 0 0 0 Total 0 178 187 24 0 0 389 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: 0 Page 33 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: April June 2012 Stability Class - Moderately Unstable - 196Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 4 NNE 0 2 0 3 NE 0 3 0 6 ENE 0 2 0 5 E 0 1 0 4 ESE 0 2 0 6 SE 0 4 0 6 SSE 0 2 0 3 S 0 0 0 0 SSW 0 2 0 3 SW 0 5 0 6 WSW 0 5 0 9 W 0 7 0 8 WNW 0 2 2 0 6 NW 0 3 1 0 4 NNW 0 0 0 0 1 Variable 0 0 0 0 0 Total 0 40 30 4 0 0 74 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: 0 Page 34 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: April - June 2012 Stability Class - Slightly Unstable - 196Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 3 0 0 0 4 NNE 0 8 s 0 0 0 13 NE 0 S 1 0 0 0 6 ENE 0 6 2 0 0 0 8 E 0 1 4 0 0 0 s ESE 0 8 2 0 0 0 10 SE 0 6 7 0 0 0 13 SSE 0 9 0 0 0 0 9 S 0 4 0 0 0 0 4 SSW 2 8 0 0 0 11 SW 1 13 4 0 0 0 18 WSW 2 10 3 0 0 0 15 W 0 6 0 2 0 0 8 WNW 0 4 S 3 0 0 12 NW 0 5 2 0 0 0 7 NNW 0 6 2 0 0 0 8 Variable 0 0 0 0 0 0 0 Total 5 102 39 5 0 0 151 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: 0 Page 35 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Peri od of Record: April - June 2012 Stability Clas s - Neutral - 196Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 10 16 2 0 28 NNE 2 11 5 1 0 19 NE 3 12 16 0 0 31 ENE 1 20 11 0 0 32 E 6 29 39 2 0 76 ESE 4 11 11 1 0 27 SE 1 21 10 0 0 32 SSE 2 20 0 0 0 22 S 3 9 2 0 0 14 SSW 4 14 4 0 0 22 SW 4 29 9 0 0 0 42 WSW 3 16 8 2 0 0 29 W 6 13 6 4 3 0 32 WNW 4 13 10 0 0 0 27 NW 0 16 11 2 0 0 29 NNW 2 4 4 0 0 0 10 Variable 0 0 0 0 0 0 0 Total 45 248 162 14 3 0 472 Hours of calm in this stability class: 1 Hours of missing wind measurements in this stability class: 1 Hours of missing stability measurements in all stability classes: 0 Page 36 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period, of Record: April - June 2012 Stability Class - Slightly Stable - 196Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 3 20 7 0 31 NNE 6 10 1 0 17 NE 8 14 3 0 25 ENE 5 44 7 0 56 E 9 34 13 0 58 ESE 15 40 7 0 62 SE 18 39 2 0 59 SSE 18 21 2 0 41 S 9 31 3 0 43 SSW 4 32 6 0 42 SW 10 25 5 0 40 WSW 10 24 2 0 36 WN 5 20 3 0 28 WNW 14 35 3 0 52 NW 13 44 2 0 59 NNW 5 27 1 0 33 Variable 0 0 0 0 0 Total 152 460 67 0 682 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stabili ty class: 0 Hours of missing stability measurements in all stability classes: 0 Page 37 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: April - June 2012 Stability Class - Moderately Stable - 196Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 2 3 NNE 12 0 12 NE 6 2 8 ENE 9 3 12 E 22 1 23 ESE 38 21 59 SE 30 3 34 SSE 14 0 14 S 6 1 7 SSW 12 2 14 SW 10 2 12 WSW 5 1 6 W 9 1 10 WNW 10 3 14 NW 2 2 4 NNW 4 0 0 4 Variable 0 1 0 1 Total 190 45 0 237 Hours of calm in this stability class: 8 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 0 Page 38 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: April - June 2012 Stability Class - Extremely Stable - 196Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 0 0 0 0 0 2 NNE 8 0 0 0 0 0 8 NE 8 0 0 0 0 0 8 ENE 4 0 0 0 0 0 4 E 12 0 12 ESE 30 0 32 SE 13 0 14 SSE 4 0 4 S 0 0 0 SSW 1 0 1 SW 9 0 9 WSW 9 0 9 W 3 0 3 WNW 9 0 11 NW 1 0 1 NNW 2 0 2 Variable 0 0 0 Total 115 0 120 Hours of calm in this stability class: 46 Hours of missing wind measurements in this stability class: 2 Hours of missing stability measurements in all stability classes: 0 Page 39 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: April - June 2012 Stability Class - Extremely Unstable - 296Ft-33Ft Delta-T (F)

Winds Measured at 296 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 3 0 6 NNE 4 2 9 NE 9 4 15 ENE 4 1 6 E 0 0 0 ESE 0 4 4 SE 5 0 5 SSE 9 3 23 S 12 15 34 SSW 21 13 45 SW 1 1 5 WSW 0 0 0 W 1 1 4 WNW 1 1 6 NW 12 3 18 NNW 5 0 7 Variable 0 0 0 Total 0 0 37 87 48 15 187 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: 0 Page 40 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: April - June 2012 Stability Class - Moderately Unstable - 296Ft-33Ft Delta-T (F)

Winds Measured at 296 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 5 2 2 0 9 NNE 0 0 7 7 0 0 14 NE 0 7 4 0 13

- ENE 0 0 8 2 2 0 12 E 0 1 11 2 0 1 15 ESE 0 0 3 0 4 1 8 SE 0 0 2 4 2 1 9 SSE 0 3 4 2 0 10 S 0 0 2 5 2 1 10 SSW 0 2 7 5 5 5 24 SW 0 4 4 2 0 11 WSW 0 0 3 0 0 0 3 W 0 2 3 3 3 0 11 WNW 0 1 5 3 2 2 13 NW 0 0 2 2 2 0 6 NNW 0 0 1 10 1 0 12 Variable 0 0 0 0 0 0 0 Total 0 11 74 55 29 11 180 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: 0 Page 41 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: April - June 2012 Stability Class - Slightly Unstable - 296Ft-33Ft Delta-T (F)

Winds Measured at 296 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 8 NNE 3 14 NE 1 7 ENE 2 E 2 8 ESE 0 13 SE 0 11 SSE 1 11 S 4 10 SSW 11 27 SW 6 20 WSW 6 10 W 3 11 WNW 8 15 V

NW 3 11 NNW 2 9 Variable 0 0 Total 0 54 65 36 25 11 191 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: 0 Page 42 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: April - June 2012 Stability Class - Neutral - 296Ft-33Ft Delta-T (F)

Winds Measured at 296 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 9 6 14 7 0 36 NNE 0 7 7 10 3 0 27 NE 0 5 9 25 8 0 47 ENE 1 5 1L5 29 3 0 53 E 1 7 20 32 21 5 86 ESE 3 4 8 17 9 1 42 SE 4 15 8 9 1 38 SSE 0 2 5 8 10 4 29 S 0 3 5 14 13 6 41 SSW 1 12 8 11 17 9 58 SW 1 6 6 2 8 5 28 WSW 2 14 5 8 3 1 33 W 2 4 8 10 9 12 45 WNW 2 6 10 14 3 1 36 NW 3 2 4 17 10 2 38 NNW 2 0 4 11 6 0 23 Variable 0 0 0 0 0 0 0 Total 19 90 135 230 139 47 660 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: 0 Page 43 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: April - June 2012 Stability Class - Slightly Stable - 296Ft-33Ft Delta-T (F)

Winds Measured at 296 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 1 10 12 1 24 NNE 0 3 7 4 1 15 NE 0 3 9 8 2 22 ENE 0 4 15 22 3 44 E 0 2 12 11 1 26 ESE 0 1 7 23 9 40 SE 0 5 6 27 3 42 SSE 0 1 12 23 8 45 S 0 6 8 35 26 82 SSW 1 2 8 21 32 71 SW 1 1 5 10 1 18 WSW 1 1 13 12 1 28 W 0 5 8 7 1 22 WNW 0 2 10 26 0 38 NW 1 4 9 35 3 52 NNW 0 3 16 20 0 39 Variable 0 0 0 b 0 0 Total 4 44 155 296 92 17 608 Hours of calm in this stab~ility class: 0 Hours of missing wind measurements in this stability class: 4 Hours of missing stability measurements in all stability classes: 0 Page 44 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: April - June 2012 Stability Class - Moderately Stable - 296Ft-33Ft Delta-T (F)

Winds Measured at 296 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 5 2 1 0 0 8 NNE 1 3 4 0 0 9 NE 2 3 2 0 0 0 7 ENE 0 5 2 0 0 0 7 E 1 2 5 5 0 0 13 ESE 0 2 3 11 5 0 21 SE 0 3 9 20 1 0 33 SSE 1 3 9 37 2 0 52 S 1 3 9 14 0 28 SSW 1 5 5 4 0 0 15 SW 1 5 5 1 0 13 WSW 0 4 1 2. 0 0 7 W 1 1 1 4 0 0 7 WNW 0 1 1 7 0 0 9 NW 2 2 3 3 0 0 10 NNW 0 4 1 3 0 0 8 Variable 0 1 0 0 0 0 1 Total 11 48 62 117 10 0 248 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: 0 Page 45 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: April - June 2012 Stability Class - Extremely Stable - 296Ft-33Ft Delta-T (F)

Winds Measured at 296 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 0 0 10 NNE 0 0 0 8 NE 0 0 0 5 ENE 0 0 0 7 E 0 0 0 6 ESE 1 0 0 5 SE 2 0 0 4 SSE 8 0 14 S 1 0 0 4 SSW 2 0 0 9 SW 1 0 0 7 WSW 2 0 0 6 W 4 0 0 5 WNW 2 0 0 5 NW 2 0 0 S NNW 0 0 0 2 Variable 0 0 0 0 Total 4 36 35 26 1 0 102 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stabi lity class: 2 Hours of missing stability measurements in all s tability classes: 0 Page 46 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: July - September 2012 Stability Class - Extremely Unstable - 196Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 8 17 25 NNE 3 10 13 NE 4 3 7 ENE 11 14 25 E 6 6 12 ESE 5 2 7 SE 7 1 8 SSE 15 2 17 S 17 1 18 SSW .35 7 42 SW 73 10 83 WSW 42 4 46 W 14 3 17 WNW 11 11 22 NW 17 16 33 NNW 16 13 29 Variable 0 0 0 Total 0 284 120 0 0 0 404 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 Page 47 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: July - September 2012 Stability Class - Moderately Unstable - 196Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 6 NNE 0 6 NE 0 3 ENE 0 2 E 0 2 ESE 0 4 SE 0 5 SSE 0 1 S 0 0 SSW 0 3 SW 0 16 1 0 0 0 17 WSW 0 11 2 0 0 0 13 W 0 7 1 0 0 0 8 WNW 0 4 3 0 0 0 7 NW 0 3 2 0 0 0 5 NNW 0 2 1 0 0 0 3 Variable 0 0 0 0 0 0 0 Total 0 72 13 0 0 0 85 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 Page 48 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: July - September 2012 Stability Class - Slightly Unstable - 196Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 4 2 0 6 NNE 0 7 1 0 8 NE 0 6 1 0 7 ENE 0 9 3 0 12 E 1 4 0 0 5 ESE 0 4 0 0 4 SE 1 6 0 0 7 SSE 0 5 0 0 5 S 0 3 0 0 3 SSW 0 7 0 0 7 SW 1 17 0 0 0 0 18 WSW 0 16 0 0 0 0 16 W 0 22 1 0 0 0 23 WNW 0 3 0 0 0 4 NW 0 17 2 0 0 0 19 NNW 0 7 2 0 0 0 9 Variable 0 0 0 0 0 1 Total 3 138 13 0 0 0 154 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 Page 49 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: July - September 2012 Stability Class - Neutral - 196Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Directior 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 17 15 0 0 0 32 NNE 1 19 6 1 0 0 27 NE 6 35 10 0 0 0 51 ENE 10 25 14 0 0 0 49 E 5 14 2 0 0 0 21 ESE 7 12 0 0 0 0 19 SE 6 11 0 0 0 0 17 SSE 5 4 0 0 0 0 9 S 5 8 1 0 0 0 14 SSW 6 10 0 0 0 0 16 SW 6 12 2 0 0 0 20 WSW 3 18 0 0 0 0 21 W 8 23 4 0 0 0 35 WNW 6 13 3 0 0 0 22 NW 8 25 4 0 0 0 37 NNW 0 12 4 1 0 0 17 Variable 1 0 0 0 0 0 1 Total 83 258 65 2 0 0 408 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 Page 50 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: July - September 2012 Stability Class - Slightly Stable - 196Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 9 2 0 0 0 13 NNE 2 S 0 0 0 0 7 NE 13 10 1 0 0 0 24 ENE 13 13 0 0 0 0 26 E 18 6 2 0 0 0 26 ESE 12 12 0 0 0 0 24 SE 9 11 1 0 0 0 21 SSE 15 8 0 0 0 0 23 S 9 9 0 0 0 0 18 SSW 11 14 1 0 0 0 26 SW 33 18 4 0 0 0 55 WSW 16 13 2 0 0 0 31 W 13 16 0 0 0 0 29 WNW 24 21 1 0 0 0 46 NW 17 49 1 0 0 0 67 NNW 5 16 3 0 0 0 24 Variable 0 0 0 0 0 0 0 Total 212 230 18 0 0 0 460 Hours of calm in this stability class: S Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3 Page 51 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: July - September 2012 Stability Class - Moderately Stable - 196Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 7 0 0 0 0 0 7 NNE 10 0 ii NE 9 0 9 ENE 13 0 13 E 12 0 14 ESE 20 0 22 SE 37 0 39 SSE 18 0 20 S 13 0 16 SSW 9 0 9 SW 14 0 14 WSW 9 2 0 0 0 0 11 W 19 3 0 0 0 0 22 WNW 25 8 0 0 0 0 33 NW 17 8 0 0 0 0 25 NNW 12 1 0 0 0 0 13 Variable 1 2 0 0 0 0 3 Total 245 36 0 0 0 0 281 Hours of calm in this stability class: 9 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3 Page 52 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: July - September 2012 Stability Class - Extremely Stable - 196Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 12 0 12 NNE 14 0 14 NE 12 0 12 ENE 14 0 14 E 18 0 18 ESE 58 0 59 SE 40 0 40 SSE 22 0 22 S 7 0 7 SSW 10 0 10 SW 12 0 0 0 0 0 12 WSW 12 1 0 0 0 0 13 W 12 1 0 0 0 0 13 WNW 16 1 0 0 0 0 17 NW 12 0 0 0 0 0 12 NNW 2 0 0 0 0 0 2 Variable 1 0 0 0 0 0 1 Total 274 4 0 0 0 0 278 Hours of calm in this stability class: 121 Hours of missing wind measurements in this stability class: 0 Hours of missing stability measurements in all stability classes: 3 Page 53 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: July - September 2012 Stability Class - Extremely Unstable - 296Ft-33Ft Delta-T (F)

Winds Measured at 296 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 3 4 0 0 7 NNE 0 0 0 0 1 0 1 NE 0 0 1 2 0 0 3 ENE 0 0 10 4 0 0 14 E 0 0 2 0 0 0 2 ESE 0 0 4 0 0 0 4 SE 0 0 3 0 0 0 3 SSE 0 2 4 2 2 0 10 S 0 0 9 3 3 0 15 SSW 0 0 16 27 0 4 47 SW 0 1 11 6 4 0 22 WSW 0 1 15 3 0 0 19 W 0 0 1 0 0 0 1 WNW 0 0 4 1 2 0 7 NW 0 0 7 8 0 0 15 NNW 0 0 4 6 1 0 11 Variable 0 0 0 0 0 0 0 Total 0 4 94 66 13 4 181 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 Page 54 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: July - September 2012 Stability Class - Moderately Unstable - 296Ft-33Ft Delta-T (F)

Winds Measured at 296 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 1 9 5 0 0 15 NNE 0 0 6 2 0 0 8 NE 0 3 1 0 0 5 ENE 0 2 6 2 0 0 10 E 0 1 7 0 0 0 8 ESE 0 1 4 0 0 0 5 SE 0 0 3 0 0 0 3 SSE 0 5 3 0 0 9 S 0 2 4 1 1 0 8 SSW 0 3 10 4 0 1 18 SW 0 14 7 5 1 0 27 WSW 0 8 13 0 0 0 21 W 0 0 4 0 0 0 4 WNW 0 1 7 4 0 0 12 NW 0 2 11 7 2 0 22 NNW 0 4 10 3 0 0 17 Variable 0 0 0 0 0 0 0 Total 0 41 109 37 4 1 192 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 Page 55 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: July - September 2012 Stability Class - Slightly Unstable - 296Ft-33Ft Delta-T (F)

Winds Measured at 296 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 3 7 2 0 0 12 NNE 0 9 1 1 0 12 NE 0 3 6 0 0 0 9 ENE 0 1 6 3 0 0 10 E 0 3 0 0 0 4 ESE 0 3 0 0 0 0 3 SE 0 3 4 0 0 0 7 SSE 0 3 1 0 0 0 4 S 0 1 2 0 0 0 3 SSW 0 9 6 2 0 0 17 SW 0 27 6 3 1 0 37 WSW 0 16 10 3 0 0 29 W 0 5 5 4 0 0 14 WNW 0 6 3 4 2 0 15 NW 0 9 7 4 2 0 22 NNW 0 8 3 2 0 0 13 Variable 0 0 0 0 0 1 Total 0 100 78 28 6 0 212 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 Page 56 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: July - September 2012 Stability Class - Neutral - 296Ft-33Ft Delta-T (F)

Winds Measured at 296 Feet Wind Speed (in mph)

Wind Directio 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 10 7 16 6 0 40 NNE 2 6 12 9 4 1 34 NE 2 11 12 20 10 0 55 ENE 0 10 15 12 4 0 41 E 3 15 3 4 0 0 25 ESE 2 7 1 0 0 0 10 SE 1 5 3 0 0 0 9 SSE 0 5 6 4 0 0 15 S 0 4 10 3 2 0 19 SSW 2 5 14 4 0 2 27 SW 1 14 15 2 1 0 33 WSW 0 12 12 4 0 0 28 W 0 11 12 8 0 0 31 WNW 2 5 5 4 0 0 16 NW 1 9 12 10 5 0 37 NNW 1 10 10 6 2 2 31 Variable 1 0 0 0 0 0 1 Total 19 139 149 106 34 5 452 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 Page 57 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: July - September 2012 Stability Class - Slightly Stable - 296Ft-33Ft Delta-T (F)

Winds Measured at 296 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 3 10 4 1 0 20 NNE 0 8 0 0 10 NE 0 7 8 7 2 0 24 ENE 0 8 14 4 1 0 27 E 0 5 12 7 0 0 24 ESE 0 1 8 18 0 0 27 SE 4 11 13 1 1 30 SSE 1 9 11 0 0 21 S 2 9 10 5 0 28 SSW 4 14 22 15 4 59 SW 6 19 20 3 1 49 WSW 5 14 7 0 1 27 W 3 8 10 0 0 21 WNW 6 5 10 1 0 22 NW 4 17 22 3 0 46 NNW 3 20 24 0 48 Variable 0 0 0 0 0 0 Total 4 63 186 190 33 7 483 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 Page 58 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: July - September 2012 Stability Class - Moderately Stable - 296Ft-33Ft Delta-T (F)

Winds Measured at 296 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 6 15 10 31 NNE 1 13 4 18 NE 4 8 0 14 ENE 7 4 2 16 E 11 15 4 30 ESE 1 10 6 17 SE 5 6 3 14 SSE 3 3 17 29 S 3 9 21 39 SSW 4 17 33 56 SW 1 20 15 37 WSW 0 6 4 11 W 5 6 2 13 WNW 6 10 11 28 NW 2 9 8 19 NNW s 14 4 23 Variable 0 0 0 0 Total 13 64 165 144 9 0 395 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 Page 59 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: July - September 2012 Stability Class - Extremely Stable - 296Ft-33Ft Delta-T (F)

Winds Measured at 296 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 2 2 0 0 0 6 NNE 1 1 7 0 0 0 9 NE .0 4 12 1 0 0 18 ENE 0 5 11 1 0 0 17 E 1 10 8 3 0 0 22 ESE 0 7 3 2 0 0 12 SE 2 4 12 2 0 0 20 SSE 1 7 13 0 22 S 2 5 10 10 0 27 SSW 0 9 16 23 0 49 SW 1 7 15 11 0 34 WSW 3 3 9 0 0 15 W 1 3 4 1 0 9 WNW 1 5 9 2 0 17 NW 1 4 1 0 0 6 NNW 1 3 1 0 6 Variable 0 0 0 0 0 0 Total 18 73 127 70 1 0 289 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: 3 Page 60 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: October - December 2012 Stability Class - Extremely Unstable - 196Ft-33Ft Delta-T (F)

Winds Measured at 33 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 2 0 0 0 0 2 NE 0 0 2 0 0 0 2 ENE 0 1 0 0 0 2 E 0 2 0 0 0 3 ESE 0 3 5 0 0 0 8 SE 0 4 4 0 0 0 8 SSE 0 14 2 0 16 S 3 10 7 0 20 SSW 2 11 5 0 18 SW 2 3 13 0 18 WSW 1 0 3 0 4 W 0 4 3 0 7 WNW 0 3 2 0 5 NW 0 6 0 7 NNW 0 0 7 0 7 Variable 0 0 0 0 0 Total 8 57 64 0 129 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: 1 Page 61 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: October - December 2012 Stability Class - Moderately Unstable - 196Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 2 1 NNE 0 3 0 0 NE 0 4 1 0 ENE 0 0 0 0 E 0 2 1 0 ESE 0 1 4 0 SE 0 3 0 0 SSE 0 3 0 0 S 0 2 0 0 SSW 0 4 2 0 SW 0 1 5 0 WSW 0 1 0 0 W 1 3 0 0 WNW 0 0 2 2 NW 0 0 2 0 NNW 0 0 2 0 Variable 0 0 0 Total 1 27 21 3 0 0 *52 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: 1 Page 62 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: October - December 2012 Stability Class - Slightly Unstable - 196Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 4 0 0 6 NNE 0 1 NE 0 6 ENE 0 4 E 0 3 ESE 0 3 SE 0 6 SSE 0 3 S 0 4 SSW 0 11 SW 0 8 WSW 0 7 W 1 8 6 0 0 0 15 WNW 0 2 0 2 0 0 4 NW 0 5 6 0 0 0 11 NNW 0 4 2 0 0 0 6 Variable 0 0 0 0 0 0 0 Total 2 66 25 5 0 0 98 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:

Page 63 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: October - December 2012 Stability Class - Neutral - 196Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 6 36 28 3 74 NNE 4 18 9 2 33 NE 9 18 3 0 30 ENE 7 41 8 2 58 E 6 22 4 0 32 ESE 5 31 6 0 42 SE 1 24 9 0 34 SSE 5 26 1 0 32 S 8 35 5 0 48 SSW 3 19 12 0 34 SW 9 29 11 0 49 WSW 9 22 17 0 48 W 3 39 51 6 99 WNW 7 67 67 28 169 NW 13 71 32 10 126 NNW 10 17 4 3 34 Variable 0 0 0 0 0 Total 105 515 267 54 0 942 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:

Page 64 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: October - December 2012 Stability Class -- Slightly Stable - 196Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 2 30 0 0 0 32 NNE 3 8 0 0 0 0 11 NE 5 8 3 0 0 0 16 ENE 11 17 0 0 0 0 28 E 8 7 0 0 0 15 ESE 15 32 0 0 47 SE 14 31 2 0 47 SSE 21 31 1 0 53 S 13 42 7 0 62 SSW 7 37 6 0 50 SW 11 26 6 0 43 WSW 10 12 2 0 24 W 8 36 3 0 47 WNW 11 44 4 0 59 NW 9 41 0 0 50 NNW 4 23 2 0 29 Variable 0 0 0 0 0 Total 152 425 36 0 613 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: 1 Page 65 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: October - December 2012 Stability Class - Moderately Stable - 196Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 7 2 0 0 0 0 9 NNE 9 0 0 0 0 0 9 NE 7 1 0 0 0 0 8 ENE 4 3 0 0 0 0 7 E 9 2 0 11 ESE 25 37 0 62 SE 29 12 0 41 SSE 11 0 16 S 1 0 9 SSW 1 0 2 SW 0 1 WSW 2 0 2 W 2 0 5 WNW 3 0 6 NW 3 0 8 NNW 9 0 13 Variable 0 0 0 Total 123 86 0 0 0 0 209 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:

Page 66 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: October - December 2012 Stability Class - Extremely Stable - 196Ft-33Ft Delta-T (F)

Winds Measured at 33 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 4 0 0 0 0 0 4 NNE 8 0 0 0 0 0 8 NE 3 0 0 0 0 0 3 ENE 3 0 0 0 0 0 3 E 17 2 0 0 0 0 19 ESE 25 33 0 58 SE 21 2 0 23 SSE 10 0 0 10 S 1 0 0 1 SSW 0 0 1 SW 2 0 0 2 WSW 2 0 0 2 W 0 0 1 WNW 5 1 0 6 NW 8 2 0 10 NNW 3 0 0 3 Variable 1 0 0 1 Total 115 40 0 0 0 0 155 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:

Page 67 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: October - December 2012 Stability Class - Extremely Unstable - 296Ft-33Ft Delta-T (F)

Winds Measured at 296 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 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 2 0 0 2 SSE 0 0 1 1 2 4 S 0 0 7 1 12 SSW 0 3 2 9 SW 0 2 0 2 WSW 0 1 0 1 W 0 0 0 0 WNW 0 0 0 0 NW 0 2 0 2 NNW 0 0 0 0 Variable 0 0 0 0 Total 1 18 5 32 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stabi lity c lass: 0 Hours of missing stability measurements in all s tabili ty classes: 97 Page 68 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: October - December 2012 Stability Class - Moderately Unstable - 296Ft-33Ft Delta-T (F)

Winds Measured at 296 *Feet Wind Speed (in mph)

Wind Directio 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 0 0 0 0 NNE 0 0 0 0 0 0 NE 0 1 1 0 0 2 ENE 0 0 0 0 0 0 E 0 3 0 0 0 3 ESE 0 2 .1 0 0 3 SE 0 2 0 0 0 2 SSE 0 3 0 1 0 4 S 0 1 4 2 1 10 SSW 0 2 1 1 0 5 SW 0 0 2 2 0 4 WSW 0 0 1 1 0 2 W 0 2 1 0 0 3 WNW 0 1 1 1 0 3 NW 0 2 5 0 0 7 NNW 0 0 0 3 0 3 Variable 0 0 0 0 0 0 Total 0 3 19 17 11 1 51 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: 97 Page 69 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: October - December 2012 Stability Class - Slightly Unstable - 296Ft-33Ft Delta-T (F)

Winds Measured at 296 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 0 0 1 1 0 0 2 NNE 0 1 5 0 0 0 6 NE 0 4 5 0 0 10 ENE 0 0 0 0 0 1 E 0 0 0 0 0 4 ESE 0 0 3 0 0 6 SE 0 0 2 0 0 6 SSE 0 0 0 0 8 S 0 0 1 2 0 8 SSW 0 5 0 7 1 19 SW 1 0 2 0 0 3 WSW 0 2 1 0 5 W 0 1 1 1 0 7 WNW 0 0 0 2 2 5 NW 0 0 2 0 0 7 NNW 0 0 3 2 0 9 Variable 0 0 0 0 0 0 Total 1 15 55 17 15 3 106 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stabil ity class: 0 Hours of missing stability measurements in all st ability classes: 97 '

Page 70 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: October - December 2012 Stability Class - Neutral - 296Ft-33Ft Delta-T (F)

Winds Measured at 296 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 11 27 25 3 3 71 NNE 3 19 12 2 1 40 NE 9 18 9 1 0 42 ENE 14 28 6 S 1 55 E 4 18 8 0 0 32 ESE 5 13 8 2 1 31 SE 7 17 9 6 1 40 SSE 4 11 13 4 1 33 S 3 17 27 9 8 65 SSW 9 16 16 11 8 60 SW 8 6 11 2 0 30 WSW 13 6 16 11 1 50 W 12 11 31 27 2 85 WNW 11 31 60 29 24 158 NW 16 47 48. 13 9 134 NNW 12 17 13 2 3 48 Variable 0 0 0 0 0 0 Total 29 141 302 312 127 63 974 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: 97 Page 71 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: October - December 2012 Stability Class - Slightly Stable - 296Ft-33Ft Delta-T (F)

Winds Measured at 296 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 13 22 0 0 37 NNE 0 0 10 8 0 0 18 NE 0 4 10 5 3 0 22 ENE 1 1 8 1 0 0 11 E 1 3 11 6 0 0 21 ESE 0 0 2 12 0 0 14 SE 0 0 8 25 5 0 38 SSE 0 4 12 38 S 2 61 S 4 18 28 39 7 97 SSW 1 6 8 28 42 1 86 SW 2 4 9 11 0 27 WSW 1 1 12 2 1 1 18 W 0 2 17 14 4 0 37 WNW 0 1 14 25 2 0 42 NW 1 3. 7 21 0 0 32 NNW 0 7 14 21 5 0 47 Variable 0 0 0 0 0 0 0 Total 8 39 168 265 117 11 608 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: 97 Page 72 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: October - December 2012 Stability Class - Moderately Stable - 296Ft-33Ft Delta-T (F)

Winds Measured at 296 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 2 3 2 0 9 NNE 0 5 13 0 0 19 NE 1 8 5 0 0 15 ENE 1 3 5 2 0 0 11 E 2 7 3 2 0 0 14 ESE 0 2 2 3 1 0 8 SE 0 2 3 23 6 0 34 SSE 0 4 15 31 1 0 51 S 0 3 10 16 3 0 32 SSW 0 1 4 19 2 0 26 SW 0 0 2 2 0 0 4 WSW 0 0 0 0 0 0 0 W 1 1 2 0 0 0 4 WNW 0 2 2 1 0 0 5 NW 0 6 0 0 8 NNW 0 1 0 1 0 0 2 Variable 0 0 0 0 0 0 0 Total 7 29 64 127 15 0 242 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: 97 Page 73 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Joint Frequency Tables Quad Cities Generating Station Period of Record: October - December 2012 Stability Class - Extremely Stable - 296Ft-33Ft Delta-T (F)

Winds Measured at 296 Feet Wind Speed (in mph)

Wind Direction 1-3 4-7 8-12 13-18 19-24 > 24 Total N 1 0 2 1 0 0 4 NNE 0 3 3 1 0 0 7 NE 0 4 0 0 0 0 4 ENE 0 2 1 1 0 0 4 E 0 0 1 1 0 0 2 ESE 0 0 2 2 0 0 4 SE 0 0 0 1 0 0 SSE 0 1 3 12 0 19 S 0 2 2 16 0 20 SSW 0 0 6 16 0 22 SW 0 0 2 4 0 6 WSW 1 0 0 0 0 1 W 0 0 0 0 0 0 WNW 0 0 0 0 0 0 NW 0 0 0 0 0 0 NNW 0 0 0 2 Variable 0 0 0 0 0 0 Total 2 13 23 55 0 96 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: 97 Page 74 of 75

Quad Cities Nuclear Power Station 2012 Annual Radioactive Effluent Release Report Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel)

1. Types of Waste Types of Waste Total Total Period Est. Total Quantity Activity (Ci) Error %
a. Spent resins, filter sludges, evaporator bottoms, etc 1.37E+02 1.19E+03 2012 2.50E+01
b. Dry compressible waste, contaminated equip, etc 1.30E+03 1.45E+01 2012 2.50E+01
c. Irradiated components, control rods, etc N/A N/A N/A N/A
d. Other (describe) Combined Packages of a. and b. N/A N/A N/A N/A
2. Estimate of major nuclide composition (by waste type)

Major Nuclide Composition  %

a. Co-60 6.64E+01 Fe-55 2.69E+01 Cs-137 4.OOE+00 Ni-63 1.22E+00
b. Mn-54 8.01 E+00 Fe-55 2.08E+01 Co-60 4.27E+01 Zn-65 1.24E+01 Co-58 6.33E+00 Cr-51 3.OOE+00 Ag-110m 1.06E+00
c. N/A N/A
d. N/A N/A
3. Solid Waste Disposition Number of Shipments Mode of TransDortation Destination 31 Highway .Processor 31 Highway Disposal B. Irradiated Fuel Shipments (disposition)

Number of Shipments Mode of Transportation Destination N/A Highway Disposal C. Changes to the Process Control Program

  • Submitted with this report, as Attachment 2, is Revision 8 of RW-AA-100, Process Control Program for Radioactive Wastes. All changes made to the document are denoted by "Revision Bars" in the right hand margin.

Page 75 of 75

Attachment 2 RW-AA-100, Revision 8, Process Control Program for Radioactive Wastes

RW-AA-100 Revision 8 Page 1 of 9 Nuclear Level 3 - Information Use PROCESS CONTROL PROGRAM FOR RADIOACTIVE WASTES

1. PURPOSE 1.1. The purpose of the Process Control Program (PCP) is to:

1.1.1. Establish the process and boundary conditions for the preparation of specific procedures for processing, sampling, analysis, packaging, storage, and shipment of solid radwaste in accordance with local, state, and federal requirements. (CM-1) 1.1.2. Establish parameters which will provide reasonable assurance that all Low Level Radioactive Wastes (LLRW), processed by the in-plant waste process systems on-site OR by on-site vendor supplied waste processing systems, meet the acceptance criteria to a Licensed Burial Facility, as required by 10CFR Part 20, 1OCFR Part 61, 1OCFR Part 71, 49CFR Parts 171-172, "Technical Position on Waste Form (Revision 1)" [1/91], "Low-Level Waste Licensing Branch Technical Position on Radioactive Waste Classification" [5/83], and the Station Technical Specifications, as applicable.

1.1.3. Provide reasonable assurance that waste placed in "on-site storage" meets the requirements as addressed within the Safety Analysis Reports for the low level radwaste storage facilities for dry and/or processed wet waste.

2. TERMS AND DEFINITIONS 2.1. Process Control Program (PCP): The program which contains the current formulas, sampling, analysis, tests, and determinations to be made to ensure that processing and packaging of solid radioactive waste based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure the waste meets the stabilization criteria specified in 10CFR Parts 20, 61 and 71, state regulations, and burial site requirements.

2.2. Solidification

Liquid waste processed to either an unstable or stable form per 10CFR61 requirements. Waste solidified does not have to meet the 300-year free standing monolith criteria. Approved formulas, samples and tests do not have to meet NRC approval for wastes solidified in a container meeting stability criteria (e.g.

High Integrity Container).

2.3. Stabilization

Liquid waste processed to a "stable state" per 10CFR61 Requirements. Established formulas, samples, and tests shall be approved by the NRC in order to meet solidification "stabilization" criteria. This processing method is currently not available, because the NRC recognizes that waste packed in a High Integrity Container meets the 300-year stabilization criteria. In the event that this processing method becomes an acceptable method, then the NRC shall approve the stabilization formulas, samples, tests, etc.

RW-AA-100 Revision 8 Page 2 of 9 2.4. Solidification Media: An approved media (e.g. Barnwell - vinyl ester styrene, cement, bitumen) when waste containing nuclides with greater than 5-year half lives is solidified in a container with activity greater than 1 micro curie/cc. Waste solidified in a HIC is approved by the commission meeting the 10CFR61 stabilization criteria, including 1% free standing liquids by volume when the waste is packaged to a "stable" form and < 0.5% when waste is packaged to an "unstable" form. The formulas, sampling, analysis, and test do not require NRC approval, because the HIC meets the stability criteria.

2.4.1. Solidification to an unstable or stable state is performed by vendors, when applicable. Liquid waste solidified to meet stabilization criteria (10CFR61 and 01-91 Branch Technical Requirements) shall have documentation available that demonstrates that the process is approved by the NRC or disposal facility.

2.5. Dewatering

The process of removing fluids from liquid waste streams to produce a waste form that meets the requirements of 10CFR Part 61 and applicable burial site criteria, <0.5% by volume when the waste is packaged to an "unstable" state, or

<1% by volume when the waste is packaged to a "stable" form.

2.6. High Integrity Container (HIC): A disposable container that is approved to the Requirements of 10CFR61. The use of HIC's is an alternative to solidification or encapsulation in a steel container to meet burial stability. HIC's are used to package dewatered liquid wastes, (e.g. filter cartridges, filter media, resin, sludges, etc), or dry active waste.

2.7. Encapsulation

The process of placing a component (e.g. cartridge filters or mechanical components) into a special purpose disposable container and then completely surrounding the waste material with an approved stabilization media, such as cement.

2.8. Liquid Waste Processing Systems: In-plant or vendor supplied processing systems consisting of equipment utilized for evaporation, filtration, demineralization, dewatering, compression dewatering, solidification, or reverse osmosis (RO) for the treatment of liquid wastes (such as Floor Drains, Chemical Drains and Equipment Drain inputs).

2.9. Incineration, RVR, and/or Glass Vitrification of Liquid or Solid: Dry or wet waste processed via incineration and/or thermal processing where the volume is reduced by thermal means meets 1OCFR61 requirements.

2.10. Compaction: When dry wastes such as paper, wood, plastic, cardboard, incinerator ash, and etc. are volume reduced through the use of a compactor.

2.11. Waste Streams: Consist of but are not limited to

- Filter media (powdered, bead resin and fiber),

- Filter cartridges,

- Pre-coat body feed material,

- Contaminated charcoal,

RW-AA-100 Revision 8 Page 3 of 9

- Fuel pool activated hardware,

- Oil Dry absorbent material added to a container to absorb liquids

- Fuel Pool Crud

- Sump and tank sludges,

- High activity filter cartridges,

- Concentrated liquids,

- Contaminated waste oil,

- Dried sewage or wastewater plant waste,

- Dry Active Waste (DAW): Waste such as filters, air filters, low activity cartridge filters, paper, wood, glass, plastic, cardboard, hoses, cloth, and metals, etc, which have become contaminated as a consequence of normal operating, housekeeping and maintenance activities.

Other radioactive waste generated from cleanup of inadvertent contamination.

3. RESPONSIBILITIES 3.1. Implementation of this Process Control Program (PCP) is described in procedures at each station and is the responsibility of the each site to implement.
4. MAIN BODY 4.1. Process Control Program Requirements 4.1.1. A change to this PCP (Radioactive Waste Treatment Systems) may be made provided that the change is reported as part of the annual radioactive effluent release report, Regulatory Guide 1.21, and is approved by the Plant Operations Review Committee (PORC).

4.1.2. Changes become effective upon acceptance per station requirements.

4.1.3. A solidification media, approved by the burial site, may be REQUIRED when liquid radwaste is solidified to a stable/unstable state.

4.1.4. When processing liquid radwaste to meet solidification stability using a vendor supplied solidification system:

1. If the vendor has its own Quality Assurance (QA) Program, then the vendor shall ADHERE to its own QA Program and shall have SUBMITTED its process system topical report to the NRC or agreement state.
2. If the vendor does not HAVE its own Quality Assurance Program, then the vendor shall ADHERE to an approved Quality Assurance Topical Report standard belonging to the Station or to another approved vendor.

RW-AA-100 Revision 8 Page 4 of 9 4.1.5. The vendor processing system(s) is/are controlled per the following:

1. A commercial vendor supplied processing system(s) may be USED for the processing of LLRW streams.
2. Vendors that process liquid LLRW at the sites shall MEET applicable Quality Assurance Topical Report and Augmented Quality Requirements.

4.1.6. Vendor processing system(s) operated at the site shall be OPERATED and CONTROLLED in accordance with vendor approved procedures or station procedures based upon vendor approved documents.

4.1.7. All waste streams processed for burial or long term on-site storage shall MEET the waste classification and characteristics specified in 10CFR Part 61.55, Part 61.56, the 5-83 Branch Technical Position for waste classification, and the applicable burial site acceptance criteria (for any burial site operating at the time the waste was processed).

4.1.8. An Exelon Nuclear plant may store waste at another Exelon Nuclear plant, provided formal NRC approval has been RECEIVED for the transfer of waste.

4.2. General Waste Processinq Requirements NOTE: On-site resin processing involves tank mixing and settling, transferring to the station or vendor processing system via resin water slurry or vacuuming into approved waste containers, and, when applicable, dewatering for burial.

4.2.1. Vendor resin beds may be USED for decontamination of plant systems, such as, SFP (Spent Fuel Pool), RWCU (reactor water cleanup), and SDC (Shut Down Cooling). These resins are then PROCESSED via the station or vendor processing system.

4.2.2. Various drains and sump discharges will be COLLECTED in tanks or suitable containers for processing treatment. Water from these tanks may be SENT through a filter, demineralizer, concentrator or vendor supplied processing systems.

4.2.3. Process waste (e.g. filter media, sludges, resin, etc) will be periodically DISCHARGED to the station or vendor processing system for onsite waste treatment or PACKAGED in containers for shipment to offsite vendor for volume reduction processing.

4.2.4. Process water (e.g. chemical, floor drain, equipment drain, etc.) may be SENT to either the site waste processing systems or vendor waste processing systems for further filtration, demineralization for plant re-use, or discharge.

4.2.5. All dewatering and solidification/stabilization will be PERFORMED by either utility site personnel or by on-site vendors or will be PACKAGED and SHIPPED to an off-site vendor low-level radwaste processing facility.

RW-AA-100 Revision 8 Page 5 of 9 4.2.6. Dry Active Waste (DAW) will be HANDLED and PROCESSED per the following:

1. DAW will be COLLECTED and SURVEYED and may be SORTED for compactable and non-compactable wastes.
2. DAW may be packaged in containers to facilitate on-site pre-compaction and/or off-site vendor contract requirements.
3. DAW items may be SURVEYED for release onsite or offsite when applicable.
4. Contaminated filter cartridges will be PLACED into a HIC or will be ENCAPSULATED in an in-situ liner for disposal or SHIPPED to an offsite waste processor in drums, boxes or steel liners per the vendor site criteria for processing and disposal.

4.2.7. Filtering devices using pre-coat media may be USED for the removal of suspended solids from liquid waste streams. The pre-coat material or cartridges from these devices may be routinely REMOVED from the filter vessel and discharged to a Filter Sludge Tank or Liner/HIC. Periodically, the filter sludge may be DISCHARGED to the vendor processing system for waste treatment onsite or PACKAGED in containers for shipment to offsite vendor for volume reduction processing.

4.2.8. Activated hardware stored in the Spent Fuel Pools will be PROCESSED periodically using remote handling equipment and may then be PUT into a container for shipment or storage in the pool or loading the processed activated hardware into the Dry Cask storage system.

4.2.9. High Integrity Containers (HIC):

1. For disposal at Barnwell, vendors supplying HIC's to the station shall PROVIDE a copy of the HIC Certificate of Compliance, which details specific limitations on use of the HIC.
2. For disposal at Clive, vendors supplying HIC's to the station shall PROVIDE a copy of the HIC Certificate of Conformance, which details specific limitations on use of the HIC.
3. Vendors supplying HIC's to the station shall PROVIDE a handling procedure which establishes guidelines for the utilization of the HIC. These guidelines serve to protect the integrity of the HIC and ensure the HIC is handled in accordance with the requirements of the Certificate of Compliance or Certificate of Conformance.

4.2.10. Lubricants and oils contaminated as a consequence of normal operating and maintenance activities may be PROCESSED on-site (by incineration, for oils meeting 10CFR20.2004 and applicable state requirements, or by an approved vendor process) or SHIPPED offsite (for incineration or other acceptable processing method).

4.2.11. Former in-plant systems GE or Stock Drum Transfer Cart and Drum Storage Areas may be USED for higher dose DAW storage at Clinton, Dresden, Quad Cities, Braidwood and Byron.

RW-AA-100 Revision 8 Page 6 of 9 4.2.13 Certain waste, including flowable solids from holding pond, oily waste separator, cooling tower basin and emergency spray pond, may be disposed of onsite under the provisions of a 10CFR20.2002 permit. Specific requirements associated with the disposal shall be incorporated into station implementing procedures. (CM-2) 4.3. Burial Site Requirements 4.3.1. Waste sent directly to burial shall COMPLY with the applicable parts of 49CFR1 71-172, 1OCFR61, 1OCFR71, and the acceptance criteria for the applicable burial site.

4.4. Shippinq and Inspection Requirements 4.4.1. All shipping/storage containers shall be INSPECTED, as required by station procedures, for compliance with applicable requirements (Department of Transportation (DOT), Nuclear Regulatory Commission (NRC), station, on-site storage, and/or burial site requirements) prior to use.

4.4.2. Containers of solidified liquid waste shall be INSPECTED for solidification quality and/or dewatering requirements per the burial site, offsite vendor acceptance, or station acceptance criteria, as applicable.

4.4.3. Shipments sent to an off site processor shall be INSPECTED to ensure that the applicable processor's waste acceptance criteria are being met.

4.4.4. Shipments sent for off site storage shall MEET the storage site's waste acceptance criteria.

4.5. Inspection and Corrective Action 4.5.1. Inspection results that indicate non-compliance with applicable NRC, State, vendor, or site requirements shall be IDENTIFIED and TRACKED through the Corrective Action Program.

4.5.2. Administrative controls for preventing unsatisfactory waste forms from being released for shipment are described in applicable station procedures. If the provisions of the Process Control Program are not satisfied, then SUSPEND shipments of defectively packaged radioactive waste from the site. (CM-1) 4.5.3. If freestanding water or solidification not meeting program requirements is observed, then samples of the particular series of batches shall be TAKEN to determine the cause. Additional samples shall be TAKEN, as warranted, to ensure that no freestanding water is present and solidification requirements are maintained.

4.6. Procedure and Process Reviews 4.6.1. The Exelon Nuclear Process Control Program and subsequent changes (other than editorial/minor changes) shall be REVIEWED and APPROVED in accordance with the station procedures, plant-specific Technical Specifications (Tech Spec),

Technical Requirements Manual (T&RM), Operation Requirements Manual (ORM),

as applicable, for the respective station and LS-AA-106. Changes to the Licensees Controlled Documents, UFSAR, ORM, or TRM are controlled by the provisions of 10CFR 50.59.

RW-AA-100 Revision 8 Page 7 of 9 4.6.2. Any changes to the PCP shall be reviewed to determine if reportability is required in the Annual Radiological Effluent Release Report (ARERR). The Radwaste Specialist shall ensure correct information is SUBMITTED to the ODCM program owner prior to submittal of the ARERR.

4.6.3. Station processes, applicable site-specific cask manual procedures, or other vendor waste processing/operating procedures shall be approved per RM-AA-102-1006.

Procedures related to waste manifests, shipment inspections, and container activity determinations are CONTROLLED by Radiation Protection Standard Procedures (RP-AA-600 Series).

1. Site waste processing IS CONTROLLED by site operating procedures.
2. Liquid processed by vendor equipment shall be PERFORMED in accordance with vendor procedures.

4.7. Waste Types, Point of Generation, and Processinq Method Methods of processing and individual vendors may CHANGE due to changing financial and regulatory options. The table below is a representative sample. It is not intended be all encompassing.

AVAILABLE WASTE WASTE STREAM POINTS OF GENERATION PROCESSING METHODS Bead Resin Systems - Fuel Pool, Condensate, Dewatering, solidification to an Reactor Water Cleanup, Blowdown, unstable/stable state Equipment Drain, Chemical and Thermal Processing Volume Control Systems, Floor Drain, Maximum Recycle, Blowdown, Boric Free Release to a Land Fill Acid Recycling System, Vendor Supplied Processing Systems, and Portable Demin System Powdered Resin Systems - (Condensate System, Floor Dewatering, solidification to an Drain/Equipment Drain filtration, Fuel unstable/stable state Pool) Thermal Processing Concentrated Waste Waste generated from Site Solidification to an unstable/stable Evaporators resulting typically from the state Floor Drain and Equipment Drain Thermal Processing Systems Sludge Sedimentation resulting from various Dewatering, solidification to an sumps, condensers, tanks, cooling unstable/stable state tower, emergency spray pond, holding Thermal Processing pond, and oily waste separators Evaporation on-site or at an offsite processor On-site disposal per 10CFR20.2002 permit

RW-AA-100 Revision 8 Page 8 of 9 AVAI LABLE WASTE POEING ME WASTE STREAM POINTS OF GENERATION PROCESSING METHODS Filter cartridges Systems - Floor/Equipment Drains, Dewatering, solidification to an Fuel Pool; cartridge filters are typically unstable/stable state generated from clean up activities Processed by a vendor for volume within the fuel pool, torus, etc reduction Dry Active Waste Paper, wood, plastic, rubber, glass, Decon/Sorting for Free Release metal, and etc. resulting from daily Compaction/Super-compaction plant activities Thermal Processing by Incineration or glass vitrification Sorting for Free Release Metal melting to an ingot Contaminated Oil Oil contaminated with radioactive Solidification unstable state materials from any in-plant system. Thermal Processing by Incineration Free Release for recycling Drying Bed Sludge Sewage Treatment and Waste Water Free release to a landfill or burial Treatment Facilities Metals See DAW See DAW Irradiated Hardware Fuel Pool, Reactor Components Volume Reduction for packaging efficiencies

5. DOCUMENTATION 5.1.1. Records of reviews performed shall be retained for the duration of the unit operating license. This documentation shall contain:
1. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change, and
2. A determination which documents that the change will maintain the overall conformance of waste products to Federal (10CFR61 and the Branch Technical Position), State, or other applicable requirements, including applicable burial site criteria.
6. REFERENCES 6.1. Technical SDecifications:

6.1.1. The details contained in Current Tech Specs (CTS) or Improved Technical Specifications (ITS), as applicable, in regard to the Process Control Program (PCP),

are to be relocated to the Licensee Controlled Documents. Some facilities have elected to relocate these details into the Operational Requirements Manual (ORM).

Relocation of the description of the PCP from the CTS or ITS does not affect the safe operation of the facility. Therefore, the relocation details are not required to be in the CTS or the ITS to provide adequate protection of the public health and safety.

RW-AA-100 Revision 8 Page 9 of 9 6.2. Writers'

References:

6.2.1. Code of Federal Regulations: 10 CFR Part 20, Part 61, Part 71,49 CFR Parts 171-172 6.2.2. Low Level Waste Licensing Branch Technical Position on Radioactive Waste Classification, May 1983 6.2.3. Technical Position on Waste Form (Revision 1), January 1991 6.2.4. Branch Technical Position on Concentration Averaging and Encapsulation, January 1995 6.2.5. Regulatory Guide 1.21, Measuring Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants 6.2.6. I.E. Circular 80.18, 10CFR 50.59 Safety Evaluation for Changes to Radioactive Waste Treatment Systems 6.3. Users'

References:

6.3.1. Quality Assurance Program (QATR) 6.3.2. LS-AA-106, Plant Operations Review Committee 6.3.3. RM-AA-102-1006, Processing Vendor Documents 6.3.4. RP-AA-600 Series, Radioactive Material/Waste Shipments 6.3.5. CY-AA-170-2000, Annual Radioactive Effluent Release Report 6.4. Station Commitments:

6.4.1. Peach Bottom CM-1, T03819, Letter from G.A. Hunger, Jr., dated Sept. 29 1994, transmitting TSCR 93-16 (Improved Technical Specifications).

6.4.2. Limerick CM-2, T03896, 1OCFR20.2002 permit granted to Limerick via letter dated July 10, 1996.

7. ATTACHMENTS - None
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