ML13128A073: Difference between revisions
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The 2012 Annual Land Use Census identified no other exposure pathways. | The 2012 Annual Land Use Census identified no other exposure pathways. | ||
All dose calculations were performed using the methodology contained in the CPS ODCM, with the exception of dose due to C-14, which was calculated using methodology included in the EPRI Technical Report 1021106.-- page 34 of 109 -- | All dose calculations were performed using the methodology contained in the CPS ODCM, with the exception of dose due to C-14, which was calculated using methodology included in the EPRI Technical Report 1021106.-- page 34 of 109 -- | ||
FIGURE 4 AREAS WITHIN THE CPS SITE BOUNDARY OPEN TO MEMBERS OF THE PUBLIC kCL I N TO1N NOTES: 1.2.3.4.Road 0.3 miles in SE Sector Agricultural acreage 0.9 miles in SSW Sector Clinton Lake 0.2 miles in the NW Sector Department of Natural Resources Recreation Area 0.8 miles in ESE Sector Residence 0.8 miles in SW Sector Residence 1.5 miles in WSW Sector Residence 1.7 mites in SSE Sector 5.6.7.4--- page 35 of 109 -- | FIGURE 4 AREAS WITHIN THE CPS SITE BOUNDARY OPEN TO MEMBERS OF THE PUBLIC kCL I N TO1N NOTES: 1.2.3.4.Road 0.3 miles in SE Sector Agricultural acreage 0.9 miles in SSW Sector Clinton Lake 0.2 miles in the NW Sector Department of Natural Resources Recreation Area 0.8 miles in ESE Sector Residence | ||
===0.8 miles=== | |||
in SW Sector Residence | |||
===1.5 miles=== | |||
in WSW Sector Residence | |||
===1.7 mites=== | |||
in SSE Sector 5.6.7.4--- page 35 of 109 -- | |||
TABLE 9 CALCULATED DOSES TO MEMBERS OF THE PUBLIC DURING USE OF THE DEPARTMENT OF NATURAL RESOURCES RECREATION AREA IN THE EAST-SOUTHEAST SECTOR WITHIN THE CPS SITE BOUNDARY Data Period: 01 January 2012- 31 December 2012:. DESCRIPTION Total Body Dose Rate (Noble Gases)Skin Dose Rate (Noble Gases)Gamma Air Dose Beta Air Dose Total Body Dose (Particulates) | TABLE 9 CALCULATED DOSES TO MEMBERS OF THE PUBLIC DURING USE OF THE DEPARTMENT OF NATURAL RESOURCES RECREATION AREA IN THE EAST-SOUTHEAST SECTOR WITHIN THE CPS SITE BOUNDARY Data Period: 01 January 2012- 31 December 2012:. DESCRIPTION Total Body Dose Rate (Noble Gases)Skin Dose Rate (Noble Gases)Gamma Air Dose Beta Air Dose Total Body Dose (Particulates) | ||
Skin Dose (Particulates) | Skin Dose (Particulates) | ||
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SECTION 10 NEW LOCATIONS FOR DOSE CALCULATION AND /OR ENVIRONMENTAL MONITORING The following is a summary of the 2012 Annual Land', Use Census. I-lt shows changes in locations for dose. calculations and / or environmental monitoring identified by the Annual Land Use Census. The distance of the receptor is being listed in the report in lieu of the name of the resident.. | SECTION 10 NEW LOCATIONS FOR DOSE CALCULATION AND /OR ENVIRONMENTAL MONITORING The following is a summary of the 2012 Annual Land', Use Census. I-lt shows changes in locations for dose. calculations and / or environmental monitoring identified by the Annual Land Use Census. The distance of the receptor is being listed in the report in lieu of the name of the resident.. | ||
This is being doneto, maintain and respect the privacy of the residents. | This is being doneto, maintain and respect the privacy of the residents. | ||
1.0 Nearest Residence The nearest residents identified in each of the sixteen (16) sectors are shown below.2012 2011 SECTOR RESIDENT AGE GROUP RESIDENT AGE GROUP (miles) (miles)N 0.9 A 0.9 A NNE 0.9 A 0.9 A NE 1.3 A 1.3 A ENE 1.8 C, A 1.8 C, A E 1.0 A 1.0 A ESE 3.2 A 3.2 A SE 2.8 A 2.4 T, A SSE 1.8 A 1.8 A S 3.0 A 3.0 A SSW 2.9 A 2.9 A SW 3.5 T, A 0.7 A WSW 2.2 A 2.2 A W 1.2 C, T, A 1.2 C, T, A WNW 1.6 C, A 1.6 A NW 1.6 A 1.6 A NNW 1.3 A 1.3 A (I)nfant (C)hild (T)een (A)dult-- page 105 of 109 -- | |||
SECTION 10 (continued) 2.0 Broadleaf Garden Census Eighty-eight (88) gardens within a five. (5) mile radius were located in the sixteen (16) geographical sectors:.surrounding CPS. Twenty-six (26)-.gardens contained broad leaf vegetation. | ===1.0 Nearest=== | ||
Residence The nearest residents identified in each of the sixteen (16) sectors are shown below.2012 2011 SECTOR RESIDENT AGE GROUP RESIDENT AGE GROUP (miles) (miles)N 0.9 A 0.9 A NNE 0.9 A 0.9 A NE 1.3 A 1.3 A ENE 1.8 C, A 1.8 C, A E 1.0 A 1.0 A ESE 3.2 A 3.2 A SE 2.8 A 2.4 T, A SSE 1.8 A 1.8 A S 3.0 A 3.0 A SSW 2.9 A 2.9 A SW 3.5 T, A 0.7 A WSW 2.2 A 2.2 A W 1.2 C, T, A 1.2 C, T, A WNW 1.6 C, A 1.6 A NW 1.6 A 1.6 A NNW 1.3 A 1.3 A (I)nfant (C)hild (T)een (A)dult-- page 105 of 109 -- | |||
SECTION 10 (continued) | |||
===2.0 Broadleaf=== | |||
Garden Census Eighty-eight (88) gardens within a five. (5) mile radius were located in the sixteen (16) geographical sectors:.surrounding CPS. Twenty-six (26)-.gardens contained broad leaf vegetation. | |||
Although other crops were identified within, these areas, they are not add.ressed.as pa.rt. of this, report.,, The nearest gardens greater than fifty (50) square-meters and producing broadleaf vegetation identified in each of the sixteen (16) geographical sectors are shown below.2012 2011 SECTOR GARDENS AGE GROUPS GARDENS AGE GROUPS (miles) (miles)N 0.9 A 0.9 A NNE 2.3 C, T, A 3.0 T, A NE 4.3 A 2.1 A ENE 1.8 C, A 1.8 C, A E 1.0 A 2.5 C, A ESE 3.3 A 3.3 A SE >5 4.4 C, A SSE 2.7 C, A 2.8 A S 4.1 A 4.1 A SSW >5 >5 SW 3.5 T, A 3.6 C, A WSW 2.3 A 2.3 A W 2.0 A 2.0 C, A WNW 1.6 A 1.6 A NW 2.9 T, A >5 NNW 1.3 A 1.3 A (I)nfant (C)hild (T)een (A)dult-- page 106 of 109 -- | Although other crops were identified within, these areas, they are not add.ressed.as pa.rt. of this, report.,, The nearest gardens greater than fifty (50) square-meters and producing broadleaf vegetation identified in each of the sixteen (16) geographical sectors are shown below.2012 2011 SECTOR GARDENS AGE GROUPS GARDENS AGE GROUPS (miles) (miles)N 0.9 A 0.9 A NNE 2.3 C, T, A 3.0 T, A NE 4.3 A 2.1 A ENE 1.8 C, A 1.8 C, A E 1.0 A 2.5 C, A ESE 3.3 A 3.3 A SE >5 4.4 C, A SSE 2.7 C, A 2.8 A S 4.1 A 4.1 A SSW >5 >5 SW 3.5 T, A 3.6 C, A WSW 2.3 A 2.3 A W 2.0 A 2.0 C, A WNW 1.6 A 1.6 A NW 2.9 T, A >5 NNW 1.3 A 1.3 A (I)nfant (C)hild (T)een (A)dult-- page 106 of 109 -- | ||
SECTION 10 (continued) 3.0 Milking Animal Census Milking animals within the sixteen (16) geographical sectors were looated within five (5) miles surrounding CPS. These milking animals Were 'either Used for the nursing of their offspring or used for meat production for'their .owný personal use and sold commercially. | SECTION 10 (continued) | ||
===3.0 Milking=== | |||
Animal Census Milking animals within the sixteen (16) geographical sectors were looated within five (5) miles surrounding CPS. These milking animals Were 'either Used for the nursing of their offspring or used for meat production for'their .owný personal use and sold commercially. | |||
There were no residents that milked tfieir forhuman consumption. | There were no residents that milked tfieir forhuman consumption. | ||
Milking animals were specifically identified, for this report.' :Although other livestock were identified within these areas, they are not addressed as part of this report.The nearest milking animals sectors are shown below.identified in each of the sixteen (16) geographical SECTOR 2012 MILKING AGE 2011 MILKING AGE ANIMALS (miles) GROUPS ANIMALS (miles) GROUPS N 0.9 A 0.9 A NNE 2.3 A 2.3 A NE >5 >5.ENE >5 >5 E >5 >5 ESE >5 >5 SE >5 >5 SSE 2.8 T, A 2.8 T, A S 4.1 A >5 SSW >5 >5 SW >5 >5 WSW 3.4 A 3.4 A W >5 >5 WNW >5 >5 NW >5 >5 NNW 1.3 A 1.3 A (I)nfant (C)hild (T)een (A)dult-- page 107 of 109 -- | Milking animals were specifically identified, for this report.' :Although other livestock were identified within these areas, they are not addressed as part of this report.The nearest milking animals sectors are shown below.identified in each of the sixteen (16) geographical SECTOR 2012 MILKING AGE 2011 MILKING AGE ANIMALS (miles) GROUPS ANIMALS (miles) GROUPS N 0.9 A 0.9 A NNE 2.3 A 2.3 A NE >5 >5.ENE >5 >5 E >5 >5 ESE >5 >5 SE >5 >5 SSE 2.8 T, A 2.8 T, A S 4.1 A >5 SSW >5 >5 SW >5 >5 WSW 3.4 A 3.4 A W >5 >5 WNW >5 >5 NW >5 >5 NNW 1.3 A 1.3 A (I)nfant (C)hild (T)een (A)dult-- page 107 of 109 -- | ||
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SECTION 12 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL There were no changes to the.Offsite Dose Calculation Manual in 2012.-- page 109 of 109 -- | SECTION 12 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL There were no changes to the.Offsite Dose Calculation Manual in 2012.-- page 109 of 109 -- | ||
RW-AA-100 Revision 8 En 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 1OCFR 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. | RW-AA-100 Revision 8 En 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 1OCFR 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 1 OCFR Parts 20, 61 and 71, state regulations, and burial site requirements. | |||
2.2. Solidification | ====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 1 OCFR 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 1OCFR61 requirements. | Liquid waste processed to either an unstable or stable form per 1OCFR61 requirements. | ||
Waste solidified does not have to meet the 300-year free standing monolith criteria. | 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). | 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 | |||
===2.3. Stabilization=== | |||
Liquid waste processed to a "stable state" per 10CFR61 Requirements. | 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. | Established formulas, samples, and tests shall be approved by the NRC in order to meet solidification "stabilization" criteria. | ||
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-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. | -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).4.1.2. 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. | 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 1 OCFR 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 1 OCFR 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 Processing 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.4.2. General Waste Processing 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. | 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. | 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: | ||
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: 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. | : 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. | 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. | |||
====4.2.8. 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 1OCFR20.2004 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. | 4.2.10. Lubricants and oils contaminated as a consequence of normal operating and maintenance activities may be PROCESSED on-site (by incineration, for oils meeting 1OCFR20.2004 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 1 OCFR20.2002 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 49CFR171-172, 10CFR61, 10CFR71, and the acceptance criteria for the applicable burial site.4.4. Shipping 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. | 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 1 OCFR20.2002 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 49CFR171-172, 10CFR61, 10CFR71, and the acceptance criteria for the applicable burial site.4.4. Shipping 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. | |||
====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. | 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-1 06. Changes to the Licensees Controlled Documents, UFSAR, ORM, or TRM are controlled by the provisions of 10CFR 50.59. | |||
===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-1 06. 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 manu al proceduires,.-or botler vendor.waste processing/operating procedures shall be approved per RM-AAL-1.02-1006. | 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 manu al proceduires,.-or botler vendor.waste processing/operating procedures shall be approved per RM-AAL-1.02-1006. | ||
Procedures related to waste manifests, shipment inspections, and container activity determinations are CONTROLLED by Radiation Protection Standard. | 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. | 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. | : 2. Liquid. processed by vendor equipment shall be PERFORMED in accordance with vendor procedures. | ||
4.7. Waste TVDes. Point of Generation, and Processina 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. | |||
===4.7. Waste=== | |||
TVDes. Point of Generation, and Processina 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. | |||
WASTE STREAM POINTS OF GENERATION AVAILABLE WASTE PROCESSING METHODS Bead Resin Systems -Fuel Pool, Condensate, Dewatering, solidification to an Reactor Water Cleanup, Blowdown, unstable/stable state Equipment Drain, Chemical and 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 ThermalProcessing 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. | WASTE STREAM POINTS OF GENERATION AVAILABLE WASTE PROCESSING METHODS Bead Resin Systems -Fuel Pool, Condensate, Dewatering, solidification to an Reactor Water Cleanup, Blowdown, unstable/stable state Equipment Drain, Chemical and 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 ThermalProcessing 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 WASTE STREAM POINTS OF GENERATION AVAILABLE WASTE WASTESTREAM POINTSOFGENERATION_ | Revision 8 Page 8 of 9 WASTE STREAM POINTS OF GENERATION AVAILABLE WASTE WASTESTREAM POINTSOFGENERATION_ | ||
PROCESSING METHODS Filter cartridges Systems -Floor/Equipment Drains, Dewatering,: | 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: | 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: | |||
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. | 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. | ||
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. | 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. | ||
| Line 433: | Line 482: | ||
==References:== | ==References:== | ||
6.3.1. Quality Assurance Program (QATR)6.3.2. LS-AA-1 06, Plant Operations Review Committee 6.3.3. RM-AA-1 02-1006, Processing Vendor Documents 6.3.4. RP-AA-600 Series, Radioactive MaterialN/aste Shipments 6.3.5. CY-AA-170-2000, Annual Radioactive Effluent Release Report 6.4. Station Commitments: | ====6.3.1. Quality==== | ||
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). | Assurance Program (QATR)6.3.2. LS-AA-1 06, Plant Operations Review Committee 6.3.3. RM-AA-1 02-1006, Processing Vendor Documents 6.3.4. RP-AA-600 Series, Radioactive MaterialN/aste Shipments 6.3.5. CY-AA-170-2000, Annual Radioactive Effluent Release Report 6.4. Station Commitments: | ||
6.4.2. Limerick CM-2, T03896, 1 OCFR20.2002 permit granted to Limerick via letter dated July 10, 1996.7. ATTACHMENTS | |||
====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, 1 OCFR20.2002 permit granted to Limerick via letter dated July 10, 1996.7. ATTACHMENTS | |||
-None Document Site Approval Form Page 1 of 2 AD-AA-101-F-01 Revision 4 I See AD-AA- 101 for the procedural requirements associated with this Form. Facility: | -None Document Site Approval Form Page 1 of 2 AD-AA-101-F-01 Revision 4 I See AD-AA- 101 for the procedural requirements associated with this Form. Facility: | ||
CPS Desktop Instruction available on Intranet or through AD functional area.Document Number: RW-AA-100 Revision: | CPS Desktop Instruction available on Intranet or through AD functional area.Document Number: RW-AA-100 Revision: | ||
Revision as of 01:10, 13 October 2018
| ML13128A073 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 04/29/2013 |
| From: | Noll W G Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| U-604117 | |
| Download: ML13128A073 (125) | |
Text
A Exelon Generation.
Clinton Power Station 8401 Power Road Clinton, IL 61727 U-604117 1 0CFR50.36a April 29, 2013 Document Control Desk Nuclear Regulatory Commission Washington, D.C. 20555-0001 Clinton Power Station Facility Operating License No. NPF-62 NRC Docket No. 50-461
Subject:
Clinton Power Station 2012 Annual Radioactive Effluent Release Report Exelon Generating Company, LLC (Exelon), Clinton Power Station, is submitting the 2012 Annual Radioactive Effluent Release Report. This report is submitted in accordance with Technical Specification requirement 5.6.3, "Radioactive Effluent Release Report," and covers the period from January 1, 2012 through December 31, 2012.Questions on this letter may be directed to Mr. Jeffrey Stovall, Chemistry Manager, at 217-937-3200.
There are no commitments contained in this letter.Respecflf l ,, Q William G. Noll Site Vice President Clinton Power Station RWC/blf Attachment cc: Regional Administrator, Region III NRC Senior Resident Inspector
-Clinton Power Station Office of Nuclear Facility Safety -Illinois Emergency Management Agency Exelon.Nuclear 01 January 2012- 31 December 2012 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT CLINTON POWER STATION -DOCKET NUMBER 50-461 Prepared by: Clinton Power Station-- page 1 of 109 --
TABLE OF CONTENTS SECTION 1 2 3 4 5 6 7 8 9 10 11 12 TITLE Executive Summary Introduction Supplemental Information Radioactive Effluent Data Solid Waste Disposal Information Dose Measurements and Assessments Meteorological Data and Dispersion Estimates ODCM Operational Remedial Requirement Reports Changes to Radioactive Waste Treatment Systems New Locations for Dose Calculation and / or Environmental Monitoring Corrections to Data Reported in Previous Reports Changes to the Offsite Dose Calculation Manual PAGE 5 6 12 17 28 32 43 103 104 105 108 109-- page 2 of 109 --
LIST OF TABLES TABLE TITLE PAGE NUMBER Gaseous Effluents
-Summation of All Releases 17 1
- 1A Air Doses Due to Gaseous Releases 18 1B Doses to a Member of the Public Due to Radioiodines, 18 Tritium and Particulates in Gaseous Releases 2 Gaseous Effluents
-Nuclides Released 19 3 Radioactive Gaseous Waste LLD Values 20 4 Waterborne Effluents
-Summation of All Releases 22 5 Waterborne Effluents
-Nuclides Released 23 6 Radioactive Liquid Waste LLD Values 24 7 Solid Waste and Irradiated Fuel Shipments 29 8 Maximum Offsite Doses and Dose Commitments to Members of the Public In Each Sector Calculated Doses to Members of the Public During Use of the 9 Department of Natural Resources Recreation Area in the East- 36 Southeast Sector within the CPS Site Boundary 10 Calculated Doses to Members of the Public During Use of the Road in 37 the Southeast Sector within the CPS Site Boundary 11 Calculated Doses for the Residents in the South-Southeast Sector 38 within the CPS Site Boundary 12 Calculated Doses for the Residents in the Southwest Sector within the CPS Site Boundary Calculated Doses to Members of the Public During Use of the 13 Agricultural Acreage in the South-Southwest Sector within the CPS 40 Site Boundary 14 Calculated Doses for the Residents in the West-Southwest Sector 41 within the CPS Site Boundary 15 Calculated Doses to Members of the Public During Use of Clinton 42 Lake in the Northwest Sector within the CPS Site Boundary 16 Meteorological Data Availability 44 17 Classification of Atmospheric Stability 45 18 Joint Wind Frequency Distribution by Stability Class 46-- page 3 of 109 --
LIST OF FIGURES FIGURE TITLE PAGE NUMBER 1 CPS Airborne Effluent Release Points 7 2 CPS Waterborne Effluents Release Pathway 8 3 Effluent Exposure Pathways 11 4 Areas Within the CPS Site Boundary Open to Members of the Public 35-- page 4 of 109 --
.SECTION 1 EXECUTIVE
SUMMARY
The Annual Radioactive Effluent Release Report is, a detailed description of gaseous and liquid radioactive effluents released from Clinton Power Station [CPS] and the resulting radiation doses for the period of 01 January 2012 through 31 December 2012. This report also includes a detailed meteorological section providing weather history of the surrounding area during this period. This information is used to calculate the offsite dose to our public.The report also includes a summary of the amounts of radioactive material contained in solid waste that is packaged and shipped to a federally approved disposal/ burial facility offsite. Additionally, this report notifies the U.S. Nuclear Regulatory Commission
[NRC] staff of changes to CPS's Offsite Dose Calculation Manual [ODCM]and exceptions to the CPS effluent monitoring program that must be reported in accordance with ODCM Remedial Requirements 2.7.1.b and 3.9.2.b.The Report also includes a summary of events that are to be included per ODCM Remedial Requirements.
The NRC requires that nuclear power facilities be designed, constructed, and operated in such a manner as to maintain radioactive effluent releases to unrestricted areas As Low As Reasonably Achievable
[ALARA]. To ensure compliance with this criterion, the NRC has established limitations governing the release of radioactivity in effluents.
During 2012, CPS operations were well within these federally required limits.The maximum annual radiation dose delivered to the inhabitants of the area surrounding CPS -due to radioactivity released from the station -was 3.60E-02 [or 0.0360] mrem. The radiation dose to the public in the vicinity of CPS was calculated by using the concentration of radioactive nuclides from each gaseous effluent release coupled with historical weather conditions.
The dose from CPS gaseous radioactive effluents was only a small fraction of the limit for the maximum exposed member of the public. There were no liquid effluent releases in 2012. As such, there was no dose received by the public from the liquid radioactive effluent pathway.-- page 5 of 109 --
SECTION 2 INTRODUCTION CPS is located in Harp Township, DeWitt County approximately six (6) miles east of the city of Clinton in east-central Illinois.
CPS is a -1,140 megawatt gross electrical power output boiling water reactor. Initial fuel load commenced in September of 1986 with initial criticality of the reactor occurring on 27 February 1987. Commercial operation commenced in April 1987 and the reactor reached 100% power for the first time on 15 September 1987.CPS releases airborne effluents via two (2) gaseous effluent release points to the environment.
They are the Common Station Heating, Ventilating, and Air Conditioning
[HVAC] Vent and the Standby Gas Treatment System [SGTS] Vent [see Figure 1]. Each gaseous effluent release point is continuously monitored through a surveillance program of periodic sampling and analysis as specified in the ODCM.CPS is licensed to release radioactive liquid effluents in a batch mode, however there were no radioactive liquid releases in 2012 at CPS. Each release would have been sampled and analyzed prior to release. Depending upon the amount of activity in a release, liquid effluents would vary from 10 to 300 gallons per minute [GPM]. This volume is then further combined with both Plant Service Water flow [a minimum of approximately 5,000 GPM] along with Plant Circulating Water flow [0 to 567,000 GPM]in the seal well, just prior to entering the 3.4 mile discharge flume into Lake Clinton[see Figure 2].Processing and Monitoring CPS strictly controls effluents to ensure radioactivity released to the environment is maintained ALARA and does not exceed federal release limit criteria.Effluent controls include the operation of radiation monitoring systems within the plant as well as an offsite environmental analysis program. In-plant radiation monitoring systems are used to provide a continuous indication of radioactivity in effluent streams.Some are also used to collect particulate and radioiodine samples. Radioactive effluent related samples are analyzed in a controlled laboratory environment to identify the specific concentration of those radionuclides being released.
Sampling and analysis provides for a more sensitive and precise method of determining effluent composition to complement the information provided by real-time radiation monitoring instruments.
Beyond the plant itself, a Radiological Environmental Monitoring Program[REMP] is maintained in accordance with Federal Regulations.
The purpose of the REMP program is to assess the radiological impact on the environment due to the operation of CPS. Implicit in this charter is the license requirement to trend and assess radiation exposure rates and radioactivity concentrations that may contribute to dose to the public. The program consists of two phases; pre-operational and operational.
During the pre-operational phase of the program, the baseline for the local radiation environment was established.
The operational phase of the program includes the objective of making confirmatory measurements to verify that the in-plant controls for the release of radioactive material are functioning as designed.
Assessment of the operational impact of CPS on the environment is based on data collected since initial criticality of the reactor.-- page 6 of 109 --
Figure 1 CPS AIRBORNE EFFLUENT RELEASE POINTS Release Point Height (feet)Building Height (feet)Release Point Geometry Release Point Area (ft 2)Release Point Diameter (feet)Annual Average Flow Rate (ft 3/sec)Vertical Exit Velocity (feet/sec)
HVAC Exhaust Vent SGTS Exhaust Vent 200 200 190 190 Duct Pipe 120 2 12* 1 2,738 73 33 41* Effective 2(A/n)2 diameter-- page 7 of 109 --
Figure 2 CPS. WATERBORNE EFFLUENTS RELEASE PATHWAY PLANT SERVICE WATER/I LIQUID RADWASTE DISCHARGE UNE (10-60 OR 60-300 GPM).RADIATION MONITOR AJMJlmP SETP(O CAL1tM WSED 04 EACH BX= ISOTOPC WMLYSS NO (XUf FMOW N ISOLATION VALVE MMWE RELEASE OtN HGH RAMMMiOH.KGH R&LEAS FW RAME. OR LOW UON FMOW Row (AT LEAST 5000 GPM)O COMPOSIM SAMPLER CO0LLEGES APPROXIMJIY 20 ml EMVEY 60 MAMS FRM nThE RLUME FOR IA0IM'W 4AIIS SEALWELL P LANT CIRCULATING WATER (0-567.000 GPM)LAKE CLINTON ,; , , ,i I DISCHARGE FLUME 3.4 MILES-- page 8 of 109 --
Exposure Pathways A radiological exposure pathway is the vehicle by which the public may become exposed to radioactivity released from nuclear facilities.
The major pathways of concern are those that could cause the highest calculated radiation dose. These pathways are determined from the type and amount of radioactivity released, the environmental transport mechanism, and how .the plant environs are used (i.e., residence, gardens, etc.). The environmental transport mechanism includes the historical meteorological characteristics of the area that are defined by windslpeed and wind direction.
This information is used ito evaluate hIow the radionuclides will be distributed within the surrounding area. The most important factor in evaluating the exposure pathway is the use of the environment by the public living around CPS.Factors such as location of homes in the area, use of cattle for milk, and the growing of gardens for vegetable consumption are important considerations when evaluating exposure pathways.
Figure 3 illustrates the effluent exposure pathways that were considered.
The radioactive gaseous effluent exposure pathways include direct radiation, deposition on plants and soil, and inhalation by animals and humans. The radioactive liquid effluent exposure pathways include fish consumption and direct exposure from Clinton Lake.Dose Assessment Whole body radiation involves the exposure of all organs in the human body to ionizing radiation.
Most naturally occurring background radiation exposures consist of whole body exposure although specific organs can receive radiation exposure from distinct radionuclides.
These radionuclides enter the body through inhalation and ingestion and seek different organs depending on the nuclide. For example, radioactive iodine selectively concentrates in the thyroid, radioactive cesium collects in muscle and liver tissue, and radioactive strontium in mineralized bone.The total dose to organs from a given radionuclide also depends on the amount of activity in the organ and the amount of time that the radionuclide remains in the body. Some radionuclides remain for very short periods of time due to their rapid radioactive decay and / or elimination rate from the body, while others may remain longer.Radiation dose to the public in the area surrounding CPS is calculated for each release using historical weather conditions coupled with the concentrations of radioactive material present. The dose is calculated for all sixteen geographical sectors surrounding CPS and includes the location of the nearest residents, vegetable gardens producing broad leaf vegetables and dairy animals in all sectors. The calculated dose also uses the scientific concept of a "maximum exposed individual" and"standard man", and the maximum use factors for the environment, such as how much milk an average person consumes and how much air a person breathes in a year.Section 6 contains more detailed information on dose to the public.-- page9 of 109 --
Gaseous Effluents Gaseous effluent radioactivity released from CPS is classified into two (2)categories.
The first category is noble gases. The second category consists of 1-131, 1-133, H-3, C-14 and all radionuclides in particulate form with radioactive half-lives greater than eight (8) days. Noble gases -such as xenon and krypton -are biologically and chemically non-reactive.
As such, these radionuclides
-specifically Kr-85m , Xe-133 and Xe-135 -are the major contributors to external doses. Halogens 1-131 and I-133, H-3, C-14 and radionuclides in particulate form with radioactive half-lives greater than eight (8) days are the major contributors to internal doses.Liquid Effluents Liquid effluents may originate from two (2) sources at CPS. The first is effluent from the Radioactive Waste Treatment System. This water is demineralized prior to release. Samples are taken after the tank has been allowed to adequately recirculate.
The second is from heat exchanger leaks found in closed cooling water systems that service radioactively contaminated systems. This would be considered an abnormal release. As a matter of station management commitment, CPS strives to be a zero (0)radioactive liquid release plant. The last liquid release occurred in September of 1992.Solid Waste Shipments To reduce the radiation exposure to personnel and maintain the federally required ALARA concept, the NRC and the Department of Transportation
[DOT] have established limits on the types of radioactive waste and the amount of radioactivity that may be packaged and shipped offsite for burial or disposal.
To ensure that CPS is complying with these regulations, the types of waste and the radioactivity present are reported to the NRC.-- page 10 of 109--
FIGURE 3 EFFLUENT EXPOSURE PATHWAYS' ANIMALS (MILK, MEAT~Q, RELEASES DILUTED BY ATMOSPHERE.
AIRBORNE RELEASES SPLUME EXPOSURE AND INHALATION CONSUMED 91V I =CLINTON POWER STATION'IL t CONSUMED BY ANIMALS CONSUMED h I B PEOPLE LIQUID RELEASES PEOPLE 4cobSUMED BY PEOPLEDRINKING WATER SHORELINE-EXPOSURE RELEASES DILUTED BY LAKE F ISH--page 11 of 109--
SECTION 3 SUPPLEMENTAL INFORMATION I. REGULATORY, LIMITS The NRC requires nuclear power facilities to be designed, constructed and operated in such a way that the radioactivity in effluent releases to unrestricted areas are kept ALARA.: To ensure these criteria..are met, each license authorizing nuclear reactor operation includes the Offsite Dose Calculation Manual [ODCM] governing the release of radioactive effluents.
The ODCM designates the limits for release of effluents, as well as the limits for doses to the general public from the release of radioactive liquids and gases. These limits are taken from Title 10 of the Code of Federal Regulations, Part 50, Appendix I (10CFR50 Appendix I), Title 10 of the Code of Federal Regulations, Part 20.1301 (10CFR20.1301) and Section 5.5.1 of our Station's Technical Specifications.
Maintaining effluent releases within these operating limitations demonstrates compliance with ALARA principles.
These limits are just a fraction of the dose limits established by the Environmental Protection Agency [EPA]found within Environmental Dose Standard Title 40, Code of Federal Regulations, Part 190 [40CFR190].
The EPA has established dose limits for members of the public in the vicinity of a nuclear power plant. These dose limits are: Less than or equal to 25 mrem per year to the total body.Less than or equal to 75 mrem per year to the thyroid.-Less than or equal to 25 mrem per year to any other organ.Specific limit information is given below.A. Gaseous Effluents 1. The maximum permissible concentrations for gaseous effluents shall not exceed the values provided within Section 5.5.4.g of Station Technical Specifications.
To ensure these concentrations are not exceeded, dose rates due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site area boundary shall be limited to the following:
- a. Noble gases Less than or equal to 500 mrem/year to the total body.-Less than or equal to 3,000 mrem/year to the skin.b. 1-131, 1-133, H-3, C-14, and all radionuclides in particulate form with radioactive half-lives greater than eight (8) days: Less than or equal to 1,500 mrem/year to any organ.-- page12 of 109 --
- 2. In accordance with Title 10 of the Code of Federal Regulations, Part 50, Appendix I, (10CFR50 Appendix I) air dose due to noble gases released in gaseous effluents to areas at and beyond the site boundary shall be limited to the following:
- a. Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation during any'calendar quarter.b. Less than or equalto 10 mrad forgamma radiation and less than or equal to :20 mrad for beta radiation*
during -any calendar year.3. In accordance with Title 10 of the Code of Federal Regulations, Part 50, Appendix I, (10CFR50 Appendix I), dose to a member of the public (from 1-131, 1-133, H-3, C-14, and all radionuclides in particulate form with radioactive half-lives greater than eight (8) days) in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following values: a. Less than or equal to 7.5 mrem to any organ, during any calendar quarter.b. Less than or equal to 15 mrem to any organ, during any calendar year.B. Liquid Effluents 1. The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the values provided within Section 5.5.4.b of Station Technical Specifications for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 pCi/ml total activity.2. The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas shall be limited to: a. Less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ during any calendar quarter.b. Less than or equal to 3 mrem to the total body and less than or equal to 10 mrem to any organ during any calendar year.-- page 13 of 109 --
II. AVERAGE ENERGY The CPS ODCM limits the dose equivalent rates due to the release of fission and activation gases to less than or equal to 500 mrem per year to the total body and less than or equal to 3,000 mrem per year to the skin. These limits are based on dose calculations using actual isotopic concentrations from our effluent release streams and not based upon. the gross count rate from our monitoring systems. Therefore, the average.beta
- and gamma energies [E] for gaseous effluents as described in 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", are not applicable.
-- page 14 of 109 --
IIh. MEASUREMENT AND APPROXIMATIONS OF TOTAL RADIOACTIVITY A. Fission and Activation Gases 1. Gas samples are collected weekly and are counted on a high purity germanium detector (HPGe) fo'r' principal gamma emitters.The HVAC and SGTS release'points are continubusly monitored and the average release flow rates for each release point are used-to calculate the total activity released during a given time period.-2. Tritium is also collected by passing a known volume of the sample stream through a gas washer containing a known quantity of demineralized water. The collected samples are distilled and analyzed by liquid scintillation.
The tritium released was calculated for each release point from the measured tritium concentration, the volume of the sample, the tritium collection efficiency, and the respective stack exhaust flow rates.3. Carbon-14 release values were estimated using the methodology included in the Electric Power Research Institute (EPRI) Technical Report 1021106, using the 2012 Clinton Power Station specific parameters of normalized Carbon-14 production rate of 5.049 Ci/GWt-yr, a gaseous release fraction of 0.99, a Carbon-14 carbon dioxide fraction of 0.95, a reactor power rating of 3473 MWt, and equivalent full power operation of 354.3 days.B. lodines Iodine is continuously collected on a silver zeolite cartridge filter via an isokinetic sampling assembly from each release point. Filters are normally exchanged once per week and then analyzed on an HPGe system. The average flow rates for each release point are averaged over the duration of the sampling period and these results -along with specific isotopic concentrations
-are then used to determine the total activity released during the time period in question.C. Particulates Particulates are continuously collected on a filter paper via an isokinetic sampling assembly on each release point. Filters are normally exchanged once per week and then analyzed on an HPGe system. The average flow rates for each release point are averaged over the duration of the sampling period and these results -along with specific isotopic concentrations
-are then used to determine the total activity released during the time period in question.-- page 15 of 109 --
D. Liquid Effluents Each tank of liquid radwaste, is recirculated for at least two (2) tank volumes, sampled, and analyzed for principal gamma emitters prior to release. Each sample tank is recirculated for a sufficient amount of time prior to sampling, ensuring that a representative sample is obtained., Samples are then analyzed on an HPGe system and liquid release permits.are generated based upon the values obtained from the isotopic analysis and the most recent values for H-3, gross alpha, Fe-55, Sr-89 and Sr-90. An aliquot based on release volume is saved and added to composite containers.
The concentrations of ýcomposited isotopes and the volumes of the releases associated with these composites establish the proportional relationships that are then utilized for calculating the total activity released for these isotopes.IV. DESCRIPTION OF ERROR ESTIMATES Estimates of measurement and analytical error for gaseous and liquid effluents are calculated as follows: E T = V[(E1)2 + (E 2)2 +...(En)2]
where: ET = total percent error, and El...EN = percent error due to calibration standards, laboratory analysis, instruments, sample flow, etc.-- page 16 of 109 --
SECTION 4 RADIOACTIVE EFFLUENT DATA TABLE 1 GASEOUS EFFLUENTS
-Summation Of All Releases Data Period: 01 January 2012 -31 December 2012 Continuous Mixed Mode Units Quarter Quarter Quarter Quarter Est.Total__ _ 1 2 3 4 Error, %A. Fission & Activation Gases 1. Total Release Ci O.OOE+01 O.OOE+01 8.31E-01 O.OOE+01 30 2. Average release pCi/sec O.OOE+O1 O.OOE+O1 1.05E-01 O.OOE+O1 rate for period _Ci/sec 0.00E+01 0.00E+01 1.5-1 00E0 3. Percent of ODCM Limit B. Iodines 1. Total Iodine-131 Ci O.OOE+01 O.OOE+01 2.21E-06 4.17E-06 31 2. Average release VCi/sec O.OOE+O1 O.OOE+O1 2.78E-07 5.25E-07 rate for period ___i/se 0.00E+01 0.00E+01 2.78E-07 5.25E-07 3. Percent of ODCM Limit C. Particulates
- 1. Particulates with Ci 2.18E-06 O.OOE+O1 O.OOE+O1 O.OOE+1 2 half-lives
>8 days Ci __.18E-06 0.00E+01 _.00E+01 _.0_E_1_ 2 2. Average release rate for period _Ci/sec 2.77E-07 0.00E+01 0.00E+01 0.00E+01 3. Percent of ODCM Limit 4. Gross alpha Ci O.OOE+01 O.OOE+O1 O.OOE+O1 O.OOE+O1 radioactivity 0.00E+01 0.00E+01 0.00E+01 0.00E+01 D. Tritium 1. Total Release Ci 2.72E+00 4.11E+00 7.22E+00 7.OOE+00 21 2. Average release rate for period pCi/sec 3.45E-01 5.23E-01 9.08E-01 8.80E-01 3. I Percent of1 ODCM Limit % *E. Carbon-14 1. Total Release Ci 4.02E+00 4.02E+00 4.07E+00 4.07E+00 2. Average release pCi/sec 5.11E-01 5.11E-01 5.12E-01 5.12E-01 Rate for period Applicable report.limits are expressed in terms of dose. See Tables 1A and 1B of this-- page 17 of 109 --
TABLE 1A Air Doses Due to Gaseous Releases Doses per Quarter Type of ODCM 1 st % of 2 nd % of 3rd % of 4 th % of Radiation Limit Quarter Limit Quarter Limit Quarter Limit Quarter Limit Gamma 5. mrad 0.OOE+01 0.00E+01 0.00E+01 0.OOE+01 4.12E-05 8.23E-04 0.OOE+01 0.OOE+01 Beta 10 mrad: 0.OOE+01 0.OOE+01 0.00E+01 0.00E+01 1.45E-05 1.45E-04 0.OOE+01 0.OOE+01 Doses per Year Type of ODOM Year % of Limit Radiation Limit Gamma 10 mrad 4.12E-05 4.12E-04 Beta 20 mrad 1.45E-05 7.26E-05 TABLE 1 B Doses to a Member of the Public Due to Radioiodines, Tritium, Carbon-14, and Particulates in Gaseous Releases Doses per Quarter Type of ODCM Quarter % of Quarter % of Quarter % of Quarter % of Organ Limit 1 Limit 2 Limit 3 Limit 4 Limit Bone 7.5 mrem 9.02E-03 1.20E-01 8.94E-03 1.19E-01 9.04E-03 1.21E-01 9.04E-03 1.21E-01 Liver 7.5 mrem 3.90E-05 5.20E-04 5.91E-05 7.88E-04 1.04E-04 1.38E-03 1.01 E-04 1.34E-03 TBody 7.5 mrem 3.40E-03 4.53E-02 1.84E-03 2.45E-02 1.90E-03 2.54E-02 1.90E-03 2.53E-02 Thyroid 7.5 mrem 3.91 E-05 5.21 E-04 5.91 E-05 7.89E-04 1.10E-04 1.47E-03 1.13E-04 1.50E-03 Kidney 7.5 mrem 3.91E-05 5.21E-04 5.91E-05 7.89E-04 1.04E-04 1.39E-03 1.01E-04 1.34E-03 Lung 7.5 mrem 3.92E-05 5.22E-04 5.91E-05 7.89E-04 1.04E-04 1.38E-03 1.01E-04 1.34E-03 GI LLI 7.5 mrem 4.17E-05 5.56E-04 5.91E-05 7.89E-04 1.04E-04 1.38E-03 1.01E-04 1.34E-03 Doses per Year Type of ODCM Year % of Organ Limit Limit Bone 15 mrem 3.60E-02 2.40E-01 Liver 15 mrem 3.03E-04 2.02E-03 TBody 15 mrem 7.50E-03 5.00E-02 Thyroid 15 mrem 3.21 E-04 2.14E-03 Kidney 15 mrem 3.03E-04 2.02E-03 Lung 15 mrem 3.03E-04 2.02E-03 GI LLI 15 mrem 3.05E-04 2.04E-03 All dose calculations were performed using the methodology contained in the CPS ODCM, with the exception of dose due to C-14, which was calculated using methodology included in the EPRI Technical Report 1021106.-- page 18 of 109 --
TABLE 2 CLINTON POWER STATION GASEOUS EFFLUENTS
-Nuclides Released YEAR:2012 Mixed Mode Release X Elevated Release Ground-Level Release Continuous Mode I x Batch Mode Units Quarter Quarter Quarter Quarter A. Fission Gases [1] 1 [2 2[2] 3[2] 4[2]Ar-41 Ci <LLD <LLD 8.31E-01 <LLD Kr-87 Ci <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD Xe-133 Ci <LLD <LLD <LLD <LLD Xe-133m Ci <LLD <LLD <LLD <LLD Xe-135 Ci <LLD <LLD <LLD <LLD Xe-1 38 Ci <LLD <LLD <LLD <LLD Total for Period Ci <LLD <LLD 8.31 E-01 <LLD B. lodines [1]1-131 Ci <LLD <LLD 2.21E-06 4.17E-06 1-133 Ci <LLD <LLD <LLD 8.96E-07 1-135 Ci <LLD <LLD <LLD <LLD Total for Period Ci <LLD <LLD 2.21E-06 5.07E-06 C. Particulates
[1]Cr-51 Ci <LLD <LLD <LLD <LLD Mn-54 Ci <LLD <LLD <LLD <LLD Co-58 Ci <LLD <LLD <LLD <LLD Fe-59 Ci <LLD <LLD <LLD <LLD Co-60 Ci <LLD <LLD <LLD <LLD Zn-65 Ci <LLD <LLD <LLD <LLD Sr-89 Ci <LLD <LLD <LLD <LLD Sr-90 Ci 2.18E-06 <LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD Cs-1 34 Ci <LLD <LLD <LLD <LLD Cs-137 Ci <LLD <LLD <LLD <LLD Ce-1 41 Ci <LLD <LLD <LLD <LLD Ce-144 Ci <LLD <LLD <LLD <LLD Gross Alpha Ci <LLD <LLD <LLD <LLD Total for Period Ci 2.18E-06 <LLD <LLD <LLD D. Tritium I1]Total for Period Ci 2.72E+0 4.11E,00 7.22E+00 7.00EO0 E. Carbon-14 "J Total for Period Ci 4.02E+00 4.02E+00 4.07E+00 4.07E+O0[1][2]Ten (10) times the values found in 10CFR20 Appendix B, Table 2, Column 1 are used for all Effluent Concentration Limit [ECL] calculations.
For dissolved and entrained noble gases, the concentration is limited to 2.OOE-04 pCi/cc total activity.The lower the value of the actual sample activity -with respect to background activity -the greater the counting error. Proportionally, large errors are reported for the various components of CPS gaseous effluents because of their consistent low sample activity.ODCM required LLD values are listed in Table 6. All analyses met the required LLD's.-- page 19 of 109 --
TABLE 3 RADIOACTIVE GASEOUS WASTE LLD VALUES ODCM Required Lower ATFACSIVT Limit of Detection (LLD)ANALYSIS a(~/c"(pCi/cc).Principal Gamma Emitters,[Noble Gases] bc <1.00E-04 H-3 <1.00E-06 1-131 d <1.00E-12 1-133 d _<1.00E-10 Principal Gamma Emitters,[Particulates]
b,e <1.00E-11 Sr-89, Sr-90f <1.O0E-11 Gross Alpha f -1.00E-1 1 Table 3 Notations aThe Lower Limit of Detection (LLD) as defined for purposes of these specifications, as an "a priori" determination of the smallest concentration of radioactive material in a sample that will yield a net count -above system background
-that will be detected with a 95% probability and with a low (5%) probability of incorrectly concluding that a blank observation represents a "real" signal.For a particular measurement system, which may include radiochemical separation:
4.66 sb LLD =E
- V *2.22 x 106 _ Y
- e-iiAt-- page 20 of 109 --
Table 3 Notations (continued)
Where: LLD is the "a priori" lower limit of detection as defined above, as pCi per unit. mass or volume, Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, in counts, per minute (cpm), E is the counting efficiency, in counts per disintegration, V is the sample size in units of mass or volume, 2.22E+06 is the number of disintegrations per minute (dpm) per microcurie, Y is the fractional radiochemical yield, when applicable, X is the radioactive decay constant for the particular radionuclide (sec-1)and At for plant effluents is the elapsed time between the midpoint of sample collection and th.e time of counting (sec).Typical values of E, V, Y, and At should be used in the calculation.
The LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
bThe principal gamma emitters for which the LLD specification applies include the following radionuclides:
Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, 1-131, Cs-134, Cs-137, Ce-141, and Ce-144 in iodine and particulate releases.
This list does not mean that only these nuclides are to be considered.
Other gamma peaks that are identifiable
-together with those of the above nuclides -shall also be analyzed and reported in the Radioactive Effluent Release Report.C Weekly grab sample and analysis dContinuous charcoal sample analyzed weekly e Continuous particulate sample analyzed weekly fComposite particulate sample analyzed monthly-- page 21 of 109 --
TABLE 4 WATERBORNE
'EFFLUENTS
-Summation Of-All Releases Data Period: 01 January 2012 through 31 December 2012 There were zero (0) liquid radwaste releases from CPS in 2012.Est.Units Quarter Quarter Quarter Quarter Total 1 .2 3 4 Error, %A. Fission & Activation Products 1. Total Release Ci O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 N/A Average diluted 2. concentration during pCi/ml 0.OOE+01 0.OOE+01 0.00E+01 0.OOE+01 period 3.Percent of ODM N/A N/A N/A N/A Limit B. Tritium 1. Total Release Ci O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 N/A Average diluted 2. concentration during pCi/mI 0.00E+01 0.OOE+01 0.OOE+01 0.OOE+01 period 3.Percent of ODM N/A N/A. N/A N/A Lim it III C. Dissolved and Entrained Gases 1. Total Release Ci O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 N/A Average diluted 2. concentration during pCi/ml 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 period 3 Percent of ODM N/A N/A N/A N/A Limit D. Gross Alpha Radioactivity Gross alphaO.OOE+1 O.OOE+1 O.OOE+1 O.OOE+1 N/A radioactivity C, 1 .1 .0.1 .0 0 1 N/ I E. Volume° oWaste Released (prior to Liters 0.00E+01 0.OOE+01 0.OOE+01 0.OOE+01 N/A Dilution)water used during period Liters 0.OOE+01 0.OOE+01 0.00E+01 0.00E+01 N/A-- page 22 of 109 --
TABLE 5 WATERBORNE EFFLUENTS
-Nuclides Released [I]Data Period: 01 January 2012 -31 December 2012 All Modes There were zero (0) liquid radwaste releases from CPS in,2012.LContinuous Mode I Batch Mode I X I Nuclide Units Quarter 1 Quarter 2 1 Quarter 3 Quarter4 A. Tritium H-3 Ci O.OOE+01 O.OOE+01 O.OOE+01 0.00E*01 B. Fission and Activation Products Sr-89 Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Sr-90 Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Cs-134 Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Cs-137 Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 1-131 Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Co-58 Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Co-60 Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Fe-59 Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Zn-65 Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Mn-54 Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Cr-51 Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Zr/Nb-95 Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Mo-99 Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Tc-99m Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Ba/La-140 Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Ce-141 Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Ce-144 Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Total Ci O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01 C. Dissolved and Entrained Noble Gases Xe-133 Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Xe-135 Ci 0.OOE+01 0.OOE+01 0.OOE+01 0.OOE+01 Total Ci O.OOE+01 O.OOE+01 O.OOE+01 O.OOE+01[1] A value corresponding to ten times the values found in 10CFR20 Appendix B, Table 2, Column 2 are used for all Effluent Concentration Limit (ECL) calculations.
For dissolved and entrained noble gases, the concentration is limited to 2.OOE-04 pCi/ml total activity.-- page 23 of 109 --
TABLE 6 RADIOACTIVE LIQUID WASTE LLD VALUES TYPE OF ACTIVITY ANALYSIS ODCM Required Lower Limit of Detection (LLD) a (gCi/mi)Principal Gamma Emitters b <5.00E-07 1-131 <1.00E-06 Dissolved and Entrained Gases (Gamma <1.00E-05 Emitters) c H-3 11.00E-05 Gross Alpha 11.00E-07 Sr-89, Sr-90 <5.OOE-08 Fe-55 <1.OOE-06 Table 6 Notations a The Lower Limit of Detection (LLD) as defined for purposes of these specifications, as an "a priori" determination of the smallest concentration of radioactive material in a sample that will yield a net count -above system background
-that will be detected with a 95% probability and with only a 5% probability of falsely concluding that a blank observation represents a "real" signal.For a particular measurement system, which may include radiochemical separation:
4.66
- s, LLD =E V .2.22 x 106 Y -eAt Where: LLD is the "a priori" lower limit of detection as defined above, as pCi per unit mass or volume, Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, in counts per minute (cpm),-- page 24 of 109 --
Table 6 Notations (continued)
E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22E+06 is the number of disintegrations per minute (dpm) per microcurie, Y is the fractional radiochemical yield, when applicable, X is the radioactive decay constant for the particular radionuclide (sec" 1)and At for plant effluents is the elapsed time between the midpoint of sample collection and the time of counting (sec).Typical values of E, V, Y, and Xt should be used in the calculation.
The LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact, MDA)limit for a particular measurement.
b The principal gamma emitters for which the LLD requirement applies include the following radionuclides:
Mn 5 4 , Fe 5 g, C058, Co 6 N, Zn 6 5 , Mo 9 9 , Cs 1 3 4 , Cs1 3 7 , Ce1 4 1 , and Ce144 shall also be measured, but with an LLD of 5.OE-06. This list does not mean that only these nuclides are detected and reported.
Other gamma peaks that are measurable
-together with those of the above nuclides -shall also be analyzed and reported in the Radioactive Effluent Release Report.133 135 138 87 88 cDissolved and entrained gases are: Xe , Xe'3 , Xe , Kr s, Kr 7 and Kr 8 8-- page 25 of 109 --
BATCH RELEASES There were zero (0) liquid radwaste releases from CPS in 2012.A. Batch Liquid Releases:
2012 1. Number of batch releases:
0 2. Total time period for batch releases:
N/A 3. Maximum time period for batch release: N/A 4. Average time period for batch release: N/A 5. Minimum time period for batch release: N/A 6. Average stream flow during periods of release: N/A 7. Total waste volume: N/A 8. Total dilution volume: N/A B. Batch Gaseous Releases:
2012 1. Number of batch releases:
0 2. Total time period for batch releases:
N/A 3. Maximum time period for batch release: N/A 4. Average time period for batch release N/A 5. Minimum time period for batch release: N/A*--page 26 of 109 --
ABNORMAL RELEASES Information concerning abnormal radioactive liquid and gaseous releases is presented below for the year 2012. There were no abnormal or unplanned liquid or gaseous releases from CPS in 2012.Liquid Releases: Number of Abnormal Liquid Releases:
Zero (0)Activity Released [Ci]Nuclides Activity [Ci]N/A 0.0 N/A 0.0 N/A 0.0 N/A 0.0 N/A 0.0 N/A 0.0 Total 0.0 Gaseous Releases: Number of Abnormal Gaseous Releases:
Zero (0)Activity Released [Ci]Nuclides Activity [Ci]N/A 0.0 N/A 0.0 N/A 0.0 N/A 0.0 N/A 0.0 N/A 0.0 Total 0.0-- page 27 of 109 --
SECTION 5 SOLID WASTE DISPOSAL INFORMATION During this reporting period -01 January 2012 through 31 December 2012 -there were Nineteen (19).radioactive waste shipments and zero (0) irradiated fuel shipments from CPS. In addition, the CPS ODCM requires reporting of the following information for solid ',aste shipped'offsite during the above reporting period: 1. Container volume: Class A Waste: 1.47E+04 ft 3 / Class B Waste: 0.0 ft 3 / Class C Waste: 0.0 ft 3 This total includes Dry Active Waste (DAW), resins, filter sludges and evaporator bottoms.2. Total curie quantity:
Class A Waste was 2.73E+02 curies and Class B Waste was 0.0 curies (determined by dose-to-curie and sample concentration methodology estimates) and Class C Waste was 0.0 curies in 2012.3. Principal radionuclides:
See A.2 for listing of measured radionuclides.
- 4. Source of waste and processing employed:
Resins, filter sludges and evaporator bottoms dewatered, non-compacted dry active waste, Sealand bags, and a B-25 box.5. Type of container:
Type A and Strong Tight Container.
- 6. Solidification agent or absorbent:
None.-- page 28 of 109 --
Table 7 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. Solid Waste Shipped Offsite for Burial or Disposal:
[NOT irradiated fuel]A T January June July -,December Est. Total A.1. Type of Waste. Units *202* " "' 2,1 "Ero%S2012 -2012 Error, %Spent resins, filter ft___ 1.43E+03 7. 33E+02 .a. sludges, evaporator , 9 25 bottoms, etc. Ci[ 8.89E+00 2.62E+02 _Dry compactable ft3 9.50E+03 2.60E+03 b. waste, contaminated
__ _ _ _ _ _ _ _ 25 equipment, etc. Ci 8.57E-01 4.70E-01 Irradiated ft3 0.OOE+01 O.OOE+01 c. components, control >~~~1.~ 25 rods, etc. Ci 0.OOE+01 0.00E+01 ft 3 4.80E+02 0.00E+01 d. Other Wastes ~ '9- ~25 Ci 6.94E-03 0.OOE+01* Total curie quantity and principal radionuclides were determined by measurements.
A.2. Estimate of major nuclide composition (by type of waste)1. Spent resins, filters, evaporator bottoms, etc.Waste Nuclide % Percent Class Name Abundance A C-14 0.12 3.24E-01.__,,_ Mn-54 4.42 1.20E+01______ Fe-55 80.35 2.18E+02______;- Co-60 13.33 3.62E+01'- Ni-63 0.86 2.32E+00"_____ Zn-65 0.58 1.57E+00_____ Other 0.46 1.24E+00 2. Dry compactable waste, contaminated equipment, etc.Waste Nuclide % Percent Class Name Abundance A Mn-54 22.39 2.97E-01-, Fe-55 36.70 4.87E-01., Co-60 38.96 5.17E-01Ni-63 0.84 1. 11E-02 Zn-65 0.88 1. 16E-02__ Other 0.24 3.20E-03-- page 29 of 109 --
Table 7 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS
[continued]
- 3. Other Wastes Waste Nuclide % Percent Class Name Abundance I I A I Mn-54 20.49 1.42E-03 Fe-55 37.23 2.58E-03 Co-60 40.45 2.81 E-03 Ni-63 0.89 6.19E-05 Zn-65 0.77 5.34E-05 Other 0.17 1.16E-05-- page 30 of 109 --
Table 7 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS
[continued]
A.3. Solid Waste Disposition:.
January -June 2012 _________,_.......____
Number of Shipments Mode of Transportation Destination 4 OClive Disposal Facility 4Hittman Transport(onanizd
_ (Containerized) 8 Hittman Transport Duratek/Bear Creek July -December 2012 Number of Shipments Mode of Transportation Destination 2 Hittman Transport Barnwell Processing Facility 1 Hittman Transport Clive Disposal Facility (Containerized) 4 Hittman Transport Duratek/Bear Creek B. Irradiated Fuel Shipments (Disposition)
_ Number of Shipments Mode of Transportation Destination N/A N/A N/A-- page 31 of 109 --
SECTION 6 DOSE MEASUREMENTS AND ASSESSMENTS, This section of the Annual Effluent Release Report provides the dose received by receptors around CPS from gaseous and liquid effluents.
The dose to the receptor that would have received, the highest dose in each sector (defined as the Critical Receptor for that sector) is listed within this report. This section also provides the dose to individuals who were inside the Site Boundary.
This section also summarizes CPS's compliance with the requirements found within 40CFR190..The 2012 maximum expected annual dose from Carbon-14 released from CPS has been calculated using the methodology included in the EPRI Technical Report 1021106 using the maximum gross thermal capacity maintained for 328.1 days of equivalent full power operation.
The assumptions used in determining dose values are as follows:* All receptors within a five (5) mile radius are included in the Annual Land Use Census. This Annual Census determines what dose pathways are present as well as the distance of each receptor from the site.* The annual average meteorological data for 2012 was used in conjunction with the Annual Land Use Census to determine the dose to each receptor within five (5)miles.* The doses for each receptor from each sector were determined using methodologies given in the ODCM, with the exception of dose due to C-14, which was calculated using methodology included in the EPRI Technical Report 1021106." The occupancy factor was taken into consideration by calculating the dose to individuals using areas inside the Site Boundary in non-residential areas. The occupancy factor is determined by dividing the number of hour[s] of occupancy per year (taken from the ODCM) and dividing that value by the total number of hour[s]per year.* Dose to individuals using areas inside the Site Boundary (that are not residences) was calculated using the Ground Plane and Inhalation pathways.-- page 32 of 109 --
TABLE 8 MAXIMUM OFFSITE DOSES AND DOSE COMMITMENTS TO MEMBERS OF THE PUBLIC IN EACH SECTOR Data Period: 01 January 2012- 31 December 2012 This table illustrates the dose that a member from the-public would most likely be exposed to from radioactive effluents in each sector-fromh CPS. " These values represent the maximum dose'likely to expose a member of the public in'each 'sector.;RECEPTOR INFORMATION AIRBORNE EFFLUENT DOSE WATERBORNE Iodine and Particulates (mrem) Noble Gases EFFLUENT DOSE 6 (mrad) (mrem) [1]Sector Distance Pathways Organ Age Total Body Skin Organ Gamma Beta Total Organ (miles) I I Body N 0.9 GP, I, M, V B A 7.57E-03 1.09E-08 3.60E-02 3.60E-05 1.27E-05 0.00E+00 0.00E+00 NNE 2.3 GP, 1, M B A 3.00E-03 3.25E-09 1.46E-02 1.98E-05 6.98E-06 NE 4.3 GP, I, V B A 4.74E-04 6.17E-10 2.06E-03 6.81E-06 2.40E-06 ENE 1.8 GP, I, V B C 1.03E-03 1.71 E-09 4.56E-03 8.53E-06 3.01 E-06 E 1.0 GP, I, V B A 1.06E-03 5.52E-09 4.60E-03 1.51E-05 5.32E-06 ESE 3.3 GP, I, V B A 7.19E-04 1.50E-09 3.12E-03 1.03E-05 3.64E-06 SE 2.8 GP, I B A 1.10E-04 1.81 E-09 4.04E-04 1.01 E-05 3.56E-06 SSE 2.7 GP, I, V B C 8.51 E-04 1.13E-09 3.78E-03 7.08E-06 2.50E-06 S 4.1 GP, I, M, V B A 1.37E-03 7.50E-10 6.54E-03 6.54E-06 2.31 E-06 SSW 2.9 GP, I B A 6.89E-05 9.61 E-10 2.52E-04 6.30E-06 2.22E-06 SW 3.5 GP, I, V B T 6.66E-04 9.53E-10 2.86E-03 9.43E-06 3.33E-06 WSW 3.4 GP, I, M B A 8.07E-04 5.04E-10 3.93E-03 5.34E-06 1.88E-06 W 2.0 GP, I, V B A 5.33E-04 1.01 E-09 2.31 E-03 7.64E-06 2.70E-06 WNW 1.6 GP, I, V B A 6.09E-04 1.06E-09 2.65E-03 8.75E-06 3.08E-06 NW 2.9 GP, I, V B T 6.81 E-04 7.07E-10 2.93E-03 9.65E-06 3.40E-06 NNW 1.3 GP, I, M, V B A 4.61 E-03 4.27E-09 2.19E-02 2.19E-05 7.73E-06 Key for Table 8 GP = Ground Plane I= Inhalation M = Cows Meat V = Vegetables B = Bone A = Adult T = Teen I= Infant C = Child[1] There were zero (0) liquid radwaste releases from CPS in 2012.All doses were within all regulatory limits, including limits from 40CFR190.All dose calculations were performed using the methodology contained in the CPS ODCM, with the exception of dose due to C-14, which was calculated using methodology included in the EPRI Technical Report 1021106.-- page 33 of 109 --
COMPLIANCE WITH 40CFR190 REQUIREMENTS Thermoluminescent dosimeters
[TLD] are stationed around CPS to measure the ambient gamma radiation field. Monitoring stations are placed near the site boundary and approximately five (5) miles from the reactor, in locations representing the sixteen (16) compass sectors. Other locations are chosen to measure the radiation field at places of special interest such as nearby residences, meeting places and population centers. Control sites are located further than ten (10) miles from the site, in areas that should not be affected by plant operations.
The results from the TLDs are reported in the Annual Radiological Environmental Monitoring Report [REMP]. The results from this effort indicated no excess dose to offsite areas.Additionally, NUREG-0543, METHODS FOR DEMONSTRATING LWR COMPLIANCE WITH THE EPA URANIUM FUEL CYCLE STANDARD (40 CFR PART 190) states in section IV, "As long as a nuclear plant site operates at a level below the Appendix I reporting requirements, no extra analysis is required to demonstrate compliance with 40 CFR Part 190." The organ and whole body doses reported in Table 8 are determined using 10 CFR 50 Appendix I methodology.
The doses reported are well below the limits of Appendix I.DOSE TO MEMBERS OF THE PUBLIC WITHIN THE SITE BOUNDARY CPS ODCM section 7.2 requires that the Radioactive Effluent Release Report include an assessment of the radiation doses from radioactive liquids and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY.
Within the CPS site boundary there are seven areas that are open to members of the public as identified by CPS ODCM Table 3.4-4 (see Figure 4):-The Department of Natural Resources Recreation Area at 1.287 kilometers (0.8 miles) in the ESE sector-A road at 0.495 kilometers (0.3 miles) in the SE sector-A residence at 2.736 kilometers (1.7 miles) in the SSE sector-A residence at 1.219 kilometers (0.8 miles) in the SW sector-Agricultural acreage at 1.372 kilometers (0.9 miles) in the SSW sector-A residence at 2.414 kilometers (1.5 miles) in the WSW sector-A portion of Clinton Lake at 0.335 kilometers (0.2 miles) in the NW sector At all of the above locations, the plume, inhalation and ground-plane exposure pathways are used for dose calculations.
The 2012 Annual Land Use Census identified no other exposure pathways.
All dose calculations were performed using the methodology contained in the CPS ODCM, with the exception of dose due to C-14, which was calculated using methodology included in the EPRI Technical Report 1021106.-- page 34 of 109 --
FIGURE 4 AREAS WITHIN THE CPS SITE BOUNDARY OPEN TO MEMBERS OF THE PUBLIC kCL I N TO1N NOTES: 1.2.3.4.Road 0.3 miles in SE Sector Agricultural acreage 0.9 miles in SSW Sector Clinton Lake 0.2 miles in the NW Sector Department of Natural Resources Recreation Area 0.8 miles in ESE Sector Residence
0.8 miles
in SW Sector Residence
1.5 miles
in WSW Sector Residence
1.7 mites
in SSE Sector 5.6.7.4--- page 35 of 109 --
TABLE 9 CALCULATED DOSES TO MEMBERS OF THE PUBLIC DURING USE OF THE DEPARTMENT OF NATURAL RESOURCES RECREATION AREA IN THE EAST-SOUTHEAST SECTOR WITHIN THE CPS SITE BOUNDARY Data Period: 01 January 2012- 31 December 2012:. DESCRIPTION Total Body Dose Rate (Noble Gases)Skin Dose Rate (Noble Gases)Gamma Air Dose Beta Air Dose Total Body Dose (Particulates)
Skin Dose (Particulates)
[ý1 DOSE UNITS 7.50E-06 mrem/year 1. 1OE-05 mrem/year 7.85E-06 mrad 2.78E-06 mrad 1.40E-04 mrem 3.OOE-09 mrem[1] DOSE includes the dose values resulting from the release of iodines, particulates (with half lives >8 days) tritium, and carbon-14 in gaseous effluents.
Highest Organ Dose by Age Group: Adult Bone Teen Bone Child Bone Infant Bone 3.13E-04 4.50E-04 6.20E-04 4.58E-04 mrem mrem mrem mrem-- page 36 of 109 --
TABLE 10 CALCULATED DOSES TO MEMBERS OF THE PUBLIC DURING USE OF THE ROAD IN THE SOUTHEAST SECTOR WITHIN THE CPS SITE BOUNDARY Data Period: 01 January 2012 -31 December 2012 DESCRIPTION Total Body Dose Rate (Noble Gases)Skin Dose Rate (Noble Gases)Gamma Air Dose Beta Air Dose Total Body Dose (Particulates)
Skin Dose (Particulates)
[1]DOSE 2.31 E-06 3.37E-06 2.63E-06 9.27E-07 4.71 E-05 1.04E-09'UNITS mrem/year mrem/year mrad m rad mrem mrem[1] DOSE includes the dose values resulting from the release of iodines, particulates (with half lives >8 days) tritium, and carbon-14 in gaseous effluents.
Highest Organ Dose by Age Group: Adult Bone Teen Bone Child Bone Infant Bone 1.05E-04 1.51 E-04 2.08E-04 1.53E-04 mrem mrem mrem-- page 37 of 109 --
TABLE 11 CALCULATED DOSES FOR THE RESIDENTS IN THE SOUTH-SOUTHEAST SECTOR (2.736 kilometers)
WITHIN THE CPS SITE BOUNDARY Data Period: 01 January 2012 -31 December 2012 DESCRIPTION DOSE UNITS Total BodyDose Rate (Noble Gases) 9.11E-06 mrem/year Skin Dose Rate (Noble Gases) 1.33E-05 mrem/year Gamma Air Dose 9.60E-06 mrad Beta Air Dose 3.39E-06 mrad Total Body Dose (Particulates) 1.71 E-04 mrem Skin Dose (Particulates)
[1] 2.1OE-09 mrem[1] DOSE includes the dose values resulting from the release of iodines, particulates (with half lives >8 days) tritium, and carbon-14 in gaseous effluents.
Highest Organ Dose by Age Group: Adult Bone 3.84E-04 mrem Teen Bone 5.50E-04 mrem Child Bone 7.59E-04 mrem Infant Bone 5.60E-04 mrem-- page 38 of 109 --
TABLE 12 CALCULATED DOSES FOR THE RESIDENTS IN THE SOUTHWEST SECTOR (1.219 kilometers)
WITHIN THE CPS SITE BOUNDARY Data Period: 01 January 2012 -31 December 2012 DESCRIPTION Total Body Dose Rate (Noble Gases)Skin Dose Rate (Noble Gases)Gamma Air Dose Beta Air Dose Total Body Dose (Particulates)
Skin Dose (Particulates)
[1]DOSE 2.29E-05 3.35E-05 2.42E-05 8.53E-06 4.33E-04 7.59E-09 UNITS mrem/year mrem/year m rad m rad mrem mrem[1] DOSE includes the dose values resulting from the release of iodines, particulates (with half lives >8 days) tritium, and carbon-14 in gaseous effluents.
Highest Organ Dose by Age Group: Adult Bone Teen Bone Child Bone Infant Bone 9.68E-04 1.39E-03 1.91 E-03 1.41 E-03 mrem mrem mrem mrem*--page 39of 109 --
TABLE 13 CALCULATED DOSES TO MEMBERS OF THE PUBLIC DURING USE OF THE AGRICULTURAL ACREAGE IN THE SOUTH-SOUTHWEST SECTOR WITHIN THE CPS SITE BOUNDARY Data Period: 01 January 2012 -31 December 2012 DESCRIPTION DOSE UNITS Total Body Dose Rate (Noble Gases) 1.60E-06 mrem/year Skin Dose Rate (Noble Gases) 2.34E-06 mrem/year Gamma Air Dose 1.68E-06 mrad Beta Air Dose 5.94E-07 mrad Total Body Dose (Particulates) 2.39E-05 mrem Skin Dose (Particulates)[1 6.55E-10 mrem[1] DOSE includes the dose values resulting from the release of iodines, particulates (with half lives >8 days) tritium, and carbon-14 in gaseous effluents.
Highest Organ Dose by Age Group: Adult Bone 6.74E-05 mrem Teen Bone 9.65E-05 mrem Child Bone N/A [2] mrem Infant Bone N/A [2] mrem[2] Dose calculated only for the age groups likely to be in the field.-- page 40 of 109 --
TABLE 14 CALCULATED DOSES FOR THE RESIDENTS IN THE WEST-SOUTHWEST SECTOR WITHIN THE CPS SITE BOUNDARY Data Period: 01 January 2012 -31 December 2012 DESCRIPTION DOSE UNITS Total Body Dose Rate (Noble Gases) 7.72E-06 .mrem/year Skin Dose Rate (Noble Gases) 1.13E-05 mrem/year Gamma Air Dose 8.13E-06 mrad Beta Air Dose 2.87E-06 mrad Total Body Dose (Particulates) 1.46E-04 mrem Skin Dose (Particulates)
Ill 1.63E-09 mrem[1] DOSE includes the dose values resulting from the release of iodines, particulates (with half lives >8 days) tritium, and carbon-14 in gaseous effluents.
Highest Organ Dose by Age Group: Adult Bone 3.25E-04 mrem Teen Bone 4.66E-04 mrem Child Bone 6.43E-04 mrem Infant Bone 4.74E-04 mrem-- page 41 of 109 --
TABLE 15 CALCULATED DOSES TO MEMBERS OF THE PUBLIC DURING USE OF CLINTON LAKE IN THE NORTHWEST SECTOR WITHIN THE CPS SITE BOUNDARY Data Period: 01 January 2012 -31 December 2012 DESCRIPTION DOSE UNITS Total Body Dose Rate (Noble Gases) 1.89E-05 mrem/year Skin Dose Rate (Noble Gases) 2.76E-05 mrem/year Gamma Air Dose 1.97E-05 mrad Beta Air Dose 6.95E-06 mrad Total Body Dose (Particulates) 3.53E-04 mrem Skin Dose (Particulates)
[1] 3.73E-09 mrem[1] DOSE includes the dose values resulting from the release of iodines, particulates (with half lives >8 days) tritium, and carbon-14 in gaseous effluents.
Highest Organ Dose by Age Group: Adult Bone 7.91 E-04 mrem Teen Bone 1.13E-03 mrem Child Bone 1.56E-03 mrem Infant Bone 1.15E-03 mrem-- page 42 of 109 --
SECTION 7 METEOROLOGICAL DATA AND DISPERSION ESTIMATES On 13 April 1972, the meteorological monitoring program commenced at the Clinton Power Station site. The meteorological system consists of a tower 199 feet high with two (2) levels of instrumentation at the 10-meter and 60-meter elevations.
A combined cup and vane sensor measures wind direction and wind speed[s] at the 10-meter and 60-meter levels. An aspirated dual temperature sensor senses the temperatures at these levels. One-half of the dual sensors at each elevation are used for ambient temperature while the other half is used to *provide a differential temperature between the 10-meter and 60-meter levels.Meteorological monitoring instruments have been placed on the Clinton Power Station microwave tower at the 10-meter level to serve as a backup to the primary meteorological tower.Clinton Power Station meteorological data is transmitted to the Main Control Room [MCR] via a dedicated communication link. Once the signals are received at the MCR, they are then converted to a 4 to 20 milliamp signal and fed individually to a microprocessor and chart recorders.
The microprocessor is part of the Clinton Power Station Radiation Monitoring System [RMS]. Meteorological data is available via the microprocessors in the Main Control Room and the Technical Support Center [TSC].Dispersion modeling for effluents for normal operation of Clinton Power Station is a straight-line, sector-averaged Gaussian plume model designed to estimate average relative concentration at various receptor points. The model was developed in accordance with routine release analysis procedures specified in Regulatory Guide 1.111. For joint frequency input data, periods of calm are distributed in accordance with a directional distribution.
For hourly input data, periods of calm are the previous hour's wind direction.
Periods of calm are assigned a wind speed value of half the specified instrument threshold value. Reference Table 18 for more detailed information on meteorology and dispersion data.-- page 43 of109 --
TABLE 16 METEOROLOGICAL DATA AVAILABILITY Data Period: 01 January 2012 -31 December 2012 PERCENT OF VALID PARAMETER HOURS (%)PARAMETER Quarter 1 T Quarter.2 Quarter 3 ] Quarter 4 1. Wind Speed a. 10-Meter sensor 99.5 99.8 100.0 99.9 b. 60 Meter sensor 99.5 99.9 100.0 99.9 2. Wind Direction
__ _ MAI'11M a. 10-Meter sensor 99.5 99.9 100.0 99.9 b. 60 Meter sensor 99.5 98.5 100.0 99.9 3. Temperature
____a. 10-Meter sensor 99.5 99.9 100.0 99.9 b. 60 Meter sensor 99.8 99.6 100.0 99.9 c. Temperature Difference (10m-60m) 99.5 99.9 100.0 99.9 4. Percent of hours for which valid 10-meter Wind Speed, Wind Direction, and Delta Temperature were available 99.5 99.8 100.0 99.9 5. Percent of hours for which valid 60-meter Wind Speed, Wind Direction, and Delta Temperature were available 99.5 98.5 100.0 99.9 Clinton Power Station was able to achieve 99.6% Meteorological Recoverable Data during 2012 exceeding the minimum criteria of 90% as delineated within Regulatory Guide 1.23.-- page 44 of 109 --
TABLE 17 CLASSIFICATION OF ATMOSPHERIC STABILITY Stability Classification Pasquill Category.
Defining Conditions Extremely unstable A ------ <AT <-1.042 Moderately unstable B -1.042 <AT< -0.933 Slightly unstable C -0.933 <AT< -0.823 Neutral D -0.823 <AT< -0.274 Slightly stable E -0.274 <AT< 0.823 Moderately stable F 0.823 <AT< 2.195 Extremely stable G 2.195 <AT< ------AT = temperature difference in degrees Fahrenheit per 100 feet-- page 45of109 --
TABLE 18 JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Reporting Period: 01 January 2012 through 31 December 2012 The following table contains the joint wind frequency tables for CPS. The tables are segregated by sensor elevation and calendar quarter. All tabled values are in hours.-- page 46 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: January -2012'Class -Extremely.
Unstable -60m-10m Delta.-T.
%(F)1I,,ý, Stability Winds Measured at 10 Meters Wind Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 0 0 0 0 0 0 0 1 0 0 0 0 1 0 0 0 0 0 1 2 2 0 2 0 2 1 2 3 3 4 1 3 0 0 8-12 13-18 19-24 > 24 6 0 0 0 7 1 0 0 3 0 0 0 5 0 0 0 1 0 0 0 2 0 0 0 7 0 0 0 2 0 0 0 10 7 0 0 14 7 0 0 4 0 2 0 2 0 0 0 8 3 0 0 7 18 0 0 9 11 2 0 4 0 0 0 0 0 0 0 Total 6 9 5 7 1 4 7 5 18 23 9 5 16 26 25 4 0 Total 2 26 91 47 4 0 170 Hours of calm in this stability class: Hours of missing wind measurements in this Hours of missing stability measurements in 0 stability class: 0 all stability classes: 11-- page 47 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: January -March 2012 Class -Moderately Unstable -60m-10m Delta-T (F)Stability Winds Measured at 10 Meters Wind Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24 > 24 0 0 4 1 0 0 0 0 1 0 0 0 0 3 2 0 0 0 0 2 8 1 0 0 0 0 0 1 0 0 0 3 0 0 0 0 0 0 3 0 0 0 0 2 0 1 0 0 0 3 6 7 1 0 0 3 7 5 3 0 0 0 1 2 3 1 0 1 10 1 0 0 0 1 3 4 0 0 0 0 6 3 4 0 0 5 2 2 0 0 0 1 0 1 0 0 0 0 0 0 0 0 Total 5 1 5 11 1 3 3 3 17 18 7 12 8 13 9 2 0 Total 0 24 53 29 11 1 118 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: 11-- page 48 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS: Clinton Power Station Period of Record: January -March 2012 Stability Class --Slightly Unstable Winds Measured at-60m-iOm Delta-T (F)10 Meters .Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable Wind Speed (in mph)1-3 4-7 8-12 13-18 19-24 > 24 Total 8 3 4 5 5 3 5 9 16 17 8 7 11 10 16 4 0 Total 2 22 56 33 16 2 131 Hours of calm in this stability class: Hours of missing wind measurements in this Hours of missing stability measurements in 0 stability class: 0 all stability classes: 11-- page 49 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITYCLASS Clinton Power Station.-Period of Record: January.-
March .2012 Stability Class -Neutral'Winds Measured at-60m-10m Delta-T (F)10 Meters Wind Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24 > 24 Total 12 8 15 7 8 21 14 13 8 8 6 5 7 12 8 10 0 17 13 31 22 15 9 28 53 37 29 22 17 35 45 28 14 0 1 0 9 11 1 0 2 23 18 26 7 11 50 37 26 8 0 0 0 0 0 0 0 0 0 1 9 0 7 19 36 15 7 0 31 22 56 40 24 31 45 94 66 80 35 42 114 131 77 41 0 Total 16 162 415 230 94 12 929 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: 11-- page 50 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: January -March 2012 Class -Slightly Stable -60m-10m Delta-T:(F)
Stability Winds Measured at 10 Meters Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable Wind Speed (in mph)1-3 4-7 8-12 13-18 19-24 > 24 Total 10 6 12 10 17 27 30 37 33 11 10 8 12 14 21 8 0 1 7 6 3 5 2 6 39 24 34 30 8 13 15 16 0 0 0 1 0 0 0 0 0 3 16 35 14 3 7 2 0 0 0 81 14 14 21 14 25 38 42 80 78 91 59 25 36 34 40 11 0 Total 58 266 209 8 0 622 Hours of calm in this stability class: 0 Hours of missing wind measurements in this sg Hours of missing stability measurements in a.tability class: 11 stability cl 0 asses: 11-- page 51 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period.of Record: January -March 2012 Stability Class.- Moderately Stable Winds Measured at-60m-10m Delta-T (F)10 Meters Wind Speed (in mph)Wind Direction 1-3 4-7 N 3 NNE 1 NE 2 ENE 4 E 2 ESE 1 SE 1 SSE 2 S 2 SSW 5 SW 3 WSW 2 W 3 WNW 1 NW 0 NNW 1 Variable 0 5 10 10 8 2 7 10 2 8 5 8 10 13 11 6 1 0 8-12 13-18 19-24 > 24 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 12 0 0 0 1 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 Total 9 11 12 12 4 8 11 4 11 22 12 13 16 12 6 3 0 Total 33 116 17 0 0 0 166 Hours of calm in this stability class: Hours of missing wind measurements in this Hours of missing stability measurements in 0 stability class: 0 all stability classes: 11-- page 52 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BYSTABILITY CLASS Clinton Power Station Period of Record: January -.March 2012 Stability Class- Extremely Stable Winds Measured at 60m-10m Delta-T '(F)10 Meters Wind Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 0 1 2 3 0 1 0 0 1 5 3 2 0 0 1 0 0 0 1 5 1 0 2 4 1 0 2 1 0 0 1 0 0 0 8-12 13-18 19-24 > 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Total 0 2 7 4 0 3 4 1 1 7 4 2 0 1 1 0 0 Total 19 18 0 0 0 0 37 Hours of calm in Hours of missing this stability class: wind measurements in this 0 stability class: 0 all stability classes: Hours of missing stability measurements in 11-- page 53 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: January -March 2012 Stability Class .Extremely Unstable -60m-10m Delta-T (F)Winds Measured at 60 Meters Wind Speed (in mph)Wind Direction 1-3 4-7 N 0 NNE 0 NE 0 ENE 0 E 0 ESE 0 SE 0 SSE 0 S 0 SSW 0 SW 0 WSW 0 W 0 WNW 0 NW 0 NNW 0 Variable 0 0 0 2 1 0 0 0 1 2 4 2 3 1 3 1 1 0 8-12 13-18 19-24 > 24 1 5 0 0 2 4 0 0 3 2 0 0 1 2 0 0 2 0 3 0 3 1 0 0 1 6 0 0 1 1 0 0 4 6 8 0 5 12 3 0 3 1 0 2 1 1 0 0 4 6 2 0 1 13 7 1 3 12 8 2 1 4 1 0 0 0 0 0 Total 6 6 7 4 5 4 7 3 20 24 8 5 13 25 26 7 0 Total 0 21 36 76 32 5 170 Hours of calm in this stability class: Hours of missing wind measurements in this Hours of missing stability measurements in 0 stability class: 0 all stability classes: 11-- page 54 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS'Clinton Power Station Period of Record: January March 2012 Stability Class -Moderately Unstable -,60m-10m Delta-T (F)Winds Measured at 60 Meters Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable Wind Speed (in mph)1-3 4-7 8-12 13-18 19-24 > 24 Total 6 0 5 10 3 2 4 3 16 19 6 14 6 14 9 1 0 Total 0 13 32 36 21 16 118 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: 11-- page 55 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: January -March 2012 Stability Wind Direction"lass -Slightly Unstable-Winds Measured at-60m-10m Delta-T (F)60 Meters Wind Speed (in mph)1-3 4-7 N 0 0 NNE 0 1 NE 0 2 ENE 0 0 E 0 0 ESE 0 0 SE 0 1 SSE 0 1 S 1 0 SSW 0 1 SW 0 0 WSW 1 0 W 0 0 WNW 0 0 NW 0 0 NNW 0 0 Variable 0 0 8-12 13-18 19-24 > 24 6 3 0 0 0 0 0 0 1 2 0 0 2 1 0 0 2 2 2 0 3 2 0 0 3 1 0 0 1 3 2 0 2 4 2 8 1 7 4 5 1 5 0 2 2 4 0 1 2 3 4 2 0 3 2 4 5 2 5 3 4 0 0 0 0 0 0 0 Total 9 1 5 3 6 5 5 7 17 18 8 8 11 9 15 4 0 Total 2 6 35 42 21 25 131 Hours of calm in this stability class: Hours of missing wind measurements in this Hours of missing stability measurements in 0 stability class: all stability cl 0 asses: 11-- page 56 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: January -.March '2012 Stability Class -Neutral -60m-l0m Delta-TT;(F)
Winds Measured at 60 Meters Wind Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24 > 24 Total 15 11 12 8 2 12 11 7 11 8 11 14 16 8 16 13 0 8 9 17 13 19 13 29 33 30 17 20 8 22 33 27 9 0 1 0 7 20 8 3 1 39 16 26 6 9 37 31 23 10 0 7 0 2 5 1 0 0 8 12 18 1 4 26 51 18 2 0 37 24 41 48 33 30 48 94 72 72 39 36 106 126 86 37 0 929 Total 8 47 175 307 237 155 Hours of calm in this stability class: Hours of missing wind measurements in this Hours of missing stability measurements in 0 stability class: 0 all stability classes: 11-- page 57 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station-Period,.of Record: January -March 2012 Stability Class -Slightly Stable -60m-10m Delta-T (F)Winds Measured.
at 60 Meters Wind Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24 > 24 Total 9 8 3 4 3 7 27 11 17 8 7 7 7 3 15 12 0 1 6 7 14 13 19 18 34 34 15 29 4 14 14 19 2 0 0 0 0 1 1 4 0 22 31 26 23 9 8 12 1 1 0 0 0 0 0 0 0 0 0 19 17 2 1 1 0 0 0 0 14 15 11 20 19 33 52 71 106 69 63 24 37 33 39 16 0 Total 8 44 148 243 139 40 622 Hours of calm in Hours of missing this stability class: wind measurements in this 0 stability class: 0 all stability classes: Hours of missing stability measurements in 11-- page 58 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: January -March- 2012 las's -Moderately Stable -. 60m-l0m Deltai-T (F)Stability C Winds Measured at Wind Speed Wind 60 Meters (in mph)Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24 > 24 Total 1 8 5 10 3 2 5 1 0 1 5 3 3 4 6 2 0 2 12 6 17 7 3 13 9 10 6 19 11 18 13 13 7 0 Total 2 16 59 77 12 0 166 Hours of calm in this stability class: Hours of missing wind measurements in this 0 stability class: 0 Hours of missing stability measurements in all stability classes: 11-- page 59 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: January -March 2012 Stability Class -Extremely Stable Winds Measured at-60m-10m Delta-T (F)60 Meters Wind Speed (in mph)Wind Direction 1-3 4-7 N 0 NNE 0 NE 0 ENE 0 E 0 ESE 0 SE 1 SSE 0 S 0 SSW 0 SW 0 WSW 0 W 0 WNW 0 NW 0 NNW 0 Variable 0 0 0 0 1 1 1 0 1 1 0 1 1 2 0 0 0 0 8-12 13-18 19-24 > 24 1 0 0 0 0 0 0 0 1 4 0 0 2 0 0 0 1 0 0 0 1 0 0 0 1 1 0 0 1 2 0 0 1 1 0 0 1 0 0 0 2 2 0 0 3 1 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 Total 1 0 5 3 2 2 3 4 3 1 5 5 2 0 1 0 0 Total 1 9 16 11 0 0 37 Hours of calm in Hours of missing this stability class: wind measurements in this 0 stability class: 0 all stability classes: Hours of missing stability measurements in 11-- page 60 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: April -June 2012 Stability Class -Extremely Unstable -60m-10m Delta-T (F)Winds Measured at 10 Meters Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable Wind Speed (in mph)8-12 13-18 1-3 4-7 19-24 > 24 Total 5 6 0 6 9 7 6 13 11 5 4 1 2 1 3 7 0 32 19 6 6 4 4 7 7 16 26 16 5 6 13 19 6 0 7 5 16 2 0 0 0 2 2 8 6 6 1 3 15 4 0 77 44 32 22 14 13 11 13 22 30 39 26 12 12 18 37 17 0 Total 1 86 192 6 0 362 Hours of calm in this stability class: 0 Hours of missing wind measurements in this si Hours of missing stability measurements in a.tability class: 11 stability cl 1 asses: 3-- page 61 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: April -June 2012.Class 7 Moderately.Unstable
-60m-10m Delta-T (F)Stability.Winds Measured at 10 Meters Wind Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24 > 24 Total 4 8 2 1 4 2 3 2 11 15 11 2 5 5 3 4 0 7 13 7 8 8 6 7 6 23 25 19 7 10 9 7 8 0 Total 5 58 82 23 2 0 170 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 62 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: April -June 2012 Stability Class'- Slightly Unstable -60in-lOm 'Delta-T (F)Winds Measured at 10 Meters.Wind Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 .8-12 13-18 19-24 > 24 0 0 2 1 0 0 1 2 3 1 1 0 0 3 2 3 0 0 0 1 5 0 0 0 1 3 3 0 0 0 1 3 0 0 0 0 0 1 0 0 0 0 0 8 1 1 0 0 0 8 4 2 1 0 0 2 12 3 0 0 0 2 5 3 0 0 1 4 1 0 0 0 0 0 2 0 1 0 1 2 2 1 0 0 1 1 7 0 0 0 1 2 4 1 0 0 0 0 0 0 0 0 Total 3 8 8 6 7 4 1 10 15 17 10 6 3 6 9 8 0 Total 7 42 53 16 3 0 121 0 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: Hours of missing stability measurements in all stability classes: 3-- page 63 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: April -June 2012 Stability Class 7 Neutral..Winds Measured at-60m-10m Delta-T (F)10 Meters Wind ,Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24 > 24 Total 8 4 16 8 14 22 14 12 15 12 8 5 5 9 6 9 0 23 5 33 23 19 11 6 18 28 44 18 8 11 7 15 24 0 3 7 21 0 0 0 0 4 10 22 2 2 2 3 3 4 0 34 16 73 31 36 34 21 38 58 85 32 20 20 19 27 38 0 Total 23 167 293 83 16 0 582 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: 3-- page 64 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: April -June 2012 Stability Class -Slightly Stable Winds Measured at* 60mi-10m Delta-T- (F)10 Meters Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable Wind Speed (in mph)4-7 8-12 13-18 1-3 19-24 > 24 Total 14 11 25 15 27 31 49 45 40 18 12 10 5 17 6 12 0 9 6 21 6 3 5 0 7 25 55 13 11 4 9 7 9 0 0 2 4 0 0 0 0 0 4 12 4 0 1 0 2 0 0 29 24 20 52 25 35 46 52 56 75 86 32 22 13 30 17 22 0 Total 49 337 190 2 0 607 Hours of calm in Hours of missing this stability class: wind measurements in this 0 stability class: 0 all stability classes: Hours of missing stability measurements in 3-- page 65 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: April -June ý 2012 Stability Class -Moderately Stable Winds Measured at Wind Speed-60m-.10m Delta-T (F)10 Meters (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 3 11 34 13 10 17 14 10 20 12 5 5 4 10 16 8 0 3 13 40 17 15 21 16 14 21 15 9 13 10 17 19 12 0 Total 52 192 11 0 0 0 255 Hours of calm in this stability class: Hours of missing wind measurements in this 1 stability class: 0 Hours of missing stability measurements in all stability classes: 3-- page 66 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: April -June' 2012 Stability Class -Extremely Stable --60m-10m Delta-T IF)Winds Measured at 10 Meters Wind Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24.. >24 Total 6 4 13 8 2 1 1 2 2 5 3 6 5 4 14 1 0 Total 59 18 0 0 0 0 77 Hours of calm in this stability class: 5 Hours of missing wind measurements in this si Hours of missing stability measurements in a.tability class: 0 11 stability classes: 3-- page 67 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: April 7 June. 2012 Stability Class -Extremely Unstable -60m-.10m Delta-T (F)Winds Measured at 60 Meters Wind Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3. 4-7. 8-12 13-18 19-24 > 24 Total 13 19 0 5 8 7 6 12 10 11 6 0 2 6 3 3 0 17 13 2 3 3 5 5 1 13 24 9 10 4 8 19 6 0 4 2 16 9 1 0 0 1 0 3 4 2 1 2 10 2 0 37 40 18 18 14 13 13 24 33 38 21 13 9 20 37 14 0 Total 0 40 ill 142 57 12 362 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: 3-- page 68 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: April'- June 2012 class -Moderately Unstable -60m-1i0m Delta-T (F)Stability Winds Measured at 60 Meters Wind Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24. j > 24 Total 4 12 10 8 8 8 7 7 24 22 19 8 10 8 7 8 0 Total 3 34 51 58 17 7 170 Hours of calm in this stability class: 0 Hours of missing wind measurements in this s tability class: 0 Hours of missing stability measurements in all stability classes: 3-- page 69 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: April 7 June.. 2012 Stability .Class -Slightly Unstable-,60m-G10m Delta-T (F)Winds Measured at 60 Meters Wind Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 , 8-12 0 1 0 1 1 1 1 5 4 2 2 2 0 1 1 2 0 13-18 19-24 > 24 Total 2 7 7 7 7 5 3 10 15 16 9 5 5 4 5 12 0 Total 4 28 24 43 13 7 119 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: 3-- page 70 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: April --June 2012 Stability Class -Neutral -60m.10m Delta-T.(F)
Winds Measured at 60 Meters Wind Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24 > 24 Total 8 3 5 8 6 12 13 9 13 14 8 4 7 7 5 6 0 17 4 12 9 20 11 8 12 30 26 16 7 7 8 11 20 0 5 7 23 19 10 8 0 9 8 14 1 3 2 3 2 6 0 0 0 12 1 1 0 0 1 11 17 1 5 1 1 1 0 0 31 15 55 43 40 33 23 35 67 76 31 20 19 24 22 35 0 Total 9 42 128 218 120 52 569 Hours of calm in Hours of missing Hours of missing this stability class: wind measurements in this stability measurements in 0 stability class: 13 all stability classes: 3-- page 71 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: April June 2012.Stability Class -Slightly Stable -60m-10m Delta-T (F)Winds Measured at 60 Meters Wind Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 .8-12 13-18 19-24 > 24 Total 2 3 3 9 10 18 47 25 21 3 7 3 2 6 4 4 0 21 13 22 17 19 20 5 25 61 32 16 15 10 14 13 11 0 1 1 6 6 2 4 0 2 9 29 4 2 1 2 1 0 0 26 18 34 33 34 43 57 54 98 71 29 22 14 26 21 16 0 Total 2 32 167 314 70 11 596 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: 11 Hours of missing stability measurements in all stability classes: 3-- page 72 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: April -June 2012 Stability Class -Moderately-Stable
-60m-10m Delta-T '(F)Winds Measured at 60 Meters Wind Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24 > 24 Total 3 5 2 7 5 10 22 5 6 12 2 1 3 11 6 3 0 3 1 23 12 8 7 0 6 20 10 4 3 3 5 5 12 0 7 8 31 20 14 19 23 13 28 23 7 7 7 18 12 16 0 Total 5 16 103 stability class: 122 7 0 253 Hours of calm in this Hours of missing wind 0 measurements in this stab)ility class: 3 stability classes: Hours of missing stability measurements in all 3-- page 73 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: April -June 2012 Stability Class -Extremely Stable -60m-10m Delta-T (F)Winds Measured at 60 Meters Wind Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 2 1 0 2 0 1 2 0 1 0 0 0 0 0 1 2 0 4-7 0 2 0 0 0 0 0 0 2 3 4 2 0 4 0 6 0 8-12 13-18 19-24 > 24 Total 6 5 2 10 4 6 2 0 4 5 6 4 4 8 5 11 0 Total 12 23 36 11 0 0 82 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 74 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: July -September 2012 Stability Class -Extremely Unstable -60m-10m Delta-T (F)Winds Measured at 10 Meters Wind Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24 > 24 0 6 16 6 0 0 0 5 16 1 0 0 0 15 13 3 0 0 0 8 2 0 0 0 0 7 3 0 0 0 0 4 0 0 0 0 0 20 3 0 0 0 1 19 3 0 0 0 0 32 12 3 0 0 1 12 17 6 0 0 0 7 11 3 0 0 0 17 14 1 0 0 0 6 9 4 0 0 0 5 10 3 0 0 0 20 15 6 0 0 0 9 17 5 0 0 0 0 0 0 0 0 Total 28 22 31 10 10 4 23 23 47 36 21 32 19 18 41 31 0 Total 2 192 161 41 0 0 396 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 75 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: July -September.2012 Stability Class- Moderately Unstable r 60m-linm Delta-T (F)Winds Measured at 10 Meters Wind Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24 > 24 Total 4 6 4 4 3 5 6 7 11 9 3 3 3 4 11 6 0 8 12 7 4 4 5 6 10 15 14 7 10 6 5 17 10 0 Total 2 89 45 4 0 0 140 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 76 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period Of Record: July -Stability Class -Slightly Unstable'September 2012.-60M10m Delta-T,(F)
Winds Measured at 10 Meter Wind Speed (in mph)S Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 0 0 1 0 1 1 1 3 0 0 0 0 0 0 0 0 0 5 3 8 3 2 2 9 9 5 7 3 2 5 3 12 4 0 8-12 13-18 19-24 > 24 8 0 0 0 10 0 0 0 4 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 0 0 0 2 0 0 0 4 0 0 0 4 1 0 0 4 0 0 0 1 0 0 0 3 0 0 0 4 0 0 0 1 1 0 0 4 0 0 0 0 0 0 0 Total 13 13 13 3 3 3 12 14 9 12 7 3 8 7 14 8 0 Total 7 82 51 2 0 0 142 Hours of calm in this stability class: Hours of missing wind measurements in this Hours of missing stability measurements in 0 stability class: 0 all stability classes: 1-- page 77 of 109 --
TABLE 18. (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station.Period of Record: July -Stability Class -Neutral....Winds Measured at September 2012-60m-10m Delta-T (F)10 Meters Wind Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3. 4-7 8-12 13-18 19-24 > 24 Total 15 11 25 11 16 18 16 20 27 16 18 16 10 10 18 13 0 43 21 28 5 4 3 6 7 8 15 13 6 0 5 18 16 0 63 35 56 17 23 22 23 32 38 39 34 24 10 17 37 30 0 Total 27 260 198 15 0 0 500 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 78 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: July-.Stability Class -Slightly Stable'Winds Measured at Wind Speed Wind September 2012* 60m-lom Delta-T (F)10 Meters (in mph)Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24 > 24 Total 2 2 4 10 9 5 12 13 9 4 3 2 1 2 5 1 0 17 11 20 15 6 28 27 34 52 45 35 6 3 8 12 6 0 6 3 11 1 1 1 0 0 7 25 11 4 3 1 2 0 0 76 25 16 35 26 16 34 39 47 68 75 49 12 7 11 19 7 0 Total 84 325 1 0 0 486 Hours of calm in Hours of missing this stability class: wind measurements in this 0 stability class: 0 all stability classes: Hours of missing stability measurements in 1-- page 79 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of.Record:
July -September 2012 Stability Class.- Moderately Stable -60m-10m Delta-T (F)..Winds Measured at 10 Meters Wind Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24 > 24 Total 5 5 14 4 10 7 6 6 5 3 9 2 2 6 5 3 0 4 8 35 2 6 11 7 17 25 21 11 7 8 12 15 2 0 9 13 50 6 16 18 13 23 31 27 20 9 11 18 20 5 0 Total 92 191 6 0 0 0 289 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: 1-- page 80 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS, Clinton Power Station Stability Wind Period of Record: July'--Class- Extremely Stable Winds Measured at Wind Speed September 2012..*.. 60m-10m Delta-T (F)10 Meters (in mph)Direction 1-3 4-7 8-12 13-18 19-24 > 24 N 9 1 0 0 0 0 NNE 8 7 0 0 0 0 NE 32 32 0 0 0 0 ENE 11 5 0 0 0 0 E 9 1 0 0 0 0 ESE 8 0 0 0 0 0 SE 2 2 0 0 0 0 SSE 3 1 0 0 0 0 S 7 0 0 0 0 0 SSW 3 4 0 0 0 0 SW 8 6 0 0 0 0 WSW 4 5 0 0 0 0 W 8 5 0 0 0 0 WNW 16 6 0 0 0 0 NW 16 14 0 0 0 0 NNW 8 1 0 0 0 0 Variable 1 0 0 0 0 0 Total 10 15 64 16 10 8 4'4 7 7 14 9 13 22 30 9 1 Total 153 90 0 0 0 0 243 0 Hours of calm in this stability class: 7 Hours of missing Hours of missing wind measurements in this stability class: stability measurements in all stability classes: 1-- page 81 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station.Period of Record: July -September 2012 Stability Class -Extremely Unstable -60m-10m Delta-T (F)Winds Measured at 60 Meters Wind. Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24> 24 Total 1 4 5 5 4 5 13 14 12 6 6 7 2 3 6 4 0 10 3 19 7 4 2 14 5 20 15 9 13 11 9 18 13 0 16 9 8 1 1 0 0 1 10 8 9 6 5 9 9 12 0 29 16 33 13 9 7 27 20 47 33 25 26 20 21 38 32 0 Total 0 97 172 104 22 396 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: Hours of missing stability measurements in all stability cl.0 asses: 1-- page 82 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record:*July
-'September 2012 Class -Moderately Unstable ' 60m-10m Delta-T' (F)Stability Winds Measured at 60 Meters Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable Wind Speed (in mph)1-3 4-7 8-12 13-18 19-24 > 24 Total 6 4 4 0 1 2 2 2 10 6 3 4 1 3 5 4 0 8 9 10 5 2 6 8 7 22 10 5 9 6 6 17 10 0 Total 1 53 57 26 3 0 140 Hours of calm in this Hours of missing wind stability class: measurements in this 0 stability class: 0 all stability classes: Hours of missing stability measurements in 1-- page 83 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION.
BY STABILITY CLASS Clinton Power Station Period. of Record: July -Stability Class -Slightly Unstable Winds Measured at Wind Speed September 2012-60m-10m Delta-T (F)60 Meters (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 8-12 .13-18 19-24 > 24 Total 3 4 10 0 0 1 1 4 4 6 4 1 1 3 4 5 0 12 9 14 6 2 3 11 16 9 10 7 4 8 7 13 11 0 Total 2 58 51 29 1 1 142 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 84 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: July -September 2012 Class"- Neutral -60m-l0m Delta-T (F)Stability Winds Measured'at 60'Meters Wind Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24 > 24 Total 2 4 7 4 5 5 9 5 6 9 7 6 9 6 10 7 0 23 7 11 6 3 10 12 11 27 8 16 13 6 0 7 12 0 30 17 25 16 12 8 5 7 8 11 11 3 0 5 10 21 0 65 29 45 28 21 25 28 25 44 34 36 24 15 12 28 41 0 Total 16 101 172 189 20 2 500 Hours of calm in Hours of missing Hours of missing this stability class: wind measurements in this stability measurements in 0 stability class: 0 all stability classes: I-- page 85 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY.
DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period: of. Record: July -September_
2012 Stability Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable Class -7 Slightly Stable * -60m-.Winds Measured at 60 Meters , Wind Speed (in mph)10m Delta-T (F)1-3 4-7 8-12 13-18 19-24 > 24 7 8 16 0 0 2 7 3 2 0 2 6 18 0 0 4 8 11 0 0 5 3 4 0 0 4 11 4 0 0 14 37 3 0 0 14 27 3 0 0 7 37 37 0 0 5 28 32 4 0 1 23 22 0 0 3 12 7 0 0 2 2 2 1 0 1 3 3 0 0 1 7 3 0 0 2 8 3 0 0 0 0 0 0 0 Total 31 14 26 23 13 21 55 46 81 69 46 22 7 8 11 13 0 Total 7 74 227 171 7 0 486 Hours of calm in this stability class: Hours of missing Hours of missing wind measurements in this stability measurements in 0 stability all stabil class: 0 ity classes: 1-- page 86 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Periodof Record: July- September 2012 Stability Class -Moderately Stable 60m-10m Delta-T (F)Winds Measured at 60 Meters Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable Wind Speed (in mph)1-3 4-7 8-12 13-18 19-24 > 24 Total 0 3 3 1 6 6 10 6 3 3 1 1 2 1 2 7 0 4 3 8 3 7 3 10 13 14 15 10 7 7 7 6 15 0 1 4 13 10 3 6 0 4 20 12 13 2 7 3 0 1 0 99 5 11 25 15 16 16 20 24 38 30 24 10 16 12 8 23 0 Total 5 55 132 2 0 293 Hours of calm in this stability class: Hours of missing wind measurements in this 0 stability class: 0 Hours of missing stability measurements in all stability classes: 1-- page87 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station-Period of Record:. July -September 2012 Stability Class- Extremely,.Stable
-60m-10m Delta-T (F)Winds Measured at 60 Meters Wind Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 8-12 .13-18 19-24 > 24 Total 11 8 11 10 20 3 4 7 5 6 8 3 6 9 5 7 0 18 16 18 27 29 12 11 17 9 14 15 6 13 19 9 17 0 Total 18 68 123 39 2 0 250 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 88 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: October -December2012 Stability Class -Extremely Unstable -60m-10m Delta-T (F)Winds Measited at 10 Meters Wind Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8-12 13-18 19-24 > 24 3 5 0 0 4 1 0 0 1 0 0 0 2 0 0 0 3 0 0 0 0 0 0 0 0 0 0 0 2 0 0 0 1 0 0 0 5 4 0 0 1 4 0 0 0 0 0 0 0 3 0 0 0 0 2 0 4 9 0 0 1 0 0 0 0 0 0 0 Total 8 5 1 2 3 0 0 2 1 9 5 0 3 2 13 1 0 Total 0 0 27 26 2 0 55 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stabili Hours of missing stability measurements in all sta ty class: bility cl 0 asses: 3-- page 89 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: October -December2012 Stability Class- Moderately Unstable -60m-10m Delta-T (F)Winds Measured at 10 Meters Wind Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24 > 24 Total 4 5 4 2 3 0 3 9 12 14 8 2 6 5 7 0 0 Total 0 26 34 23 1 0 84 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 90 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Recbrd: October-Decembe r2012 10m Delta-T: (F)Stability Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable Class -Slightly Unstable "-"'- 60mi-Winds Measured at 10 Meters Wind Speed (in mph)1-3 4-7 8-12 13-18 '19-24 > 24 4 6 7 1 0 1 1 3 13 5 7 2 7 6 5 1 0 Total 10 10 7 1 1 2 4 9 25 15 11 7 12 16 12 6 0 Total 5 44 69 20 10 0 148 Hours of calm in Hours of missing this stability class: wind measurements in thi 0 s stability class: n all stability cl 0 asses: Hours of missing stability measurements i1 3-- page 91 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period.of Record: October -December2012 Stability Wind Direction.N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable Class -Neutral -60m-K Winds Measured at 10 Meters Wind Speed (in mph)1-3 4-7 8-12 13-18 P 10m Delta-T (F)9-24 > 24 Total----- ----- ----- ----- ----- -----28 14 22 9 8 10 21 37 19 17 16 9 10 30 35 33 0 44 22 14 16 25 5 4 45 50 40 30 14 16 51 38 24 0 7 5 6 0 0 0 2 5 26 45 11 9 14 54 24 13 0 1 9 2 0 0 0 0 0 9 7 7 1 3 22 3 1 0 65 87 52 45 25 35 16 29 89 106 110 65 35 47 170 104 77 0 Total 42 318 438 221 8 1092 Hours of calm in this stability class: Hours of missing wind measurements in this 0 stability class: 0 Hours of missing stability measurements in all stabi lity classes: 3-- page 92 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS'Clinton Power Station Periodof Record: October- December2012 Stability C Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable'lass *-Slightly Stable Winds Measured at Wind Speed* 60m-10m Delta-T.(F) 10 Meters (in mph)1-3: 4-7 1 0 2 5 2 2 7 4 3 1 1 2 2 2 1 1 0 12 13 12 4 9 9 27 51 47 27 16 19 10 12 3 5 0 8-12 13-18 19-24 > 24 28 2 0 0 24 1 0 0 2 0 0 0 1 0 0 0 1 0 0 0 1 0 0 0 2 0 0 0 23 1 0 0 79 12 0 0 62 7 0 0 12 0 0 0 6 2 0 0 7 0 1 0 41 1 0 0 9 0 0 0 7 0 0 0 0 0 0 0 Total 43 38 16 10 12 12 36 79 141 97 29 29 20 56 13 13 0 Total 36 276 305 26 I 0 644 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 93 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period .of Record: October -December2012 Stability Class -Moderately.
Stable -60m-i0m Delta-T (F)Winds Measured at 10 Meters Wind Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 .8-12 13-18 5 0 1 0 1 5 0 0 0 10 0 0 3 2 0 0 4 1 0 0 7 10 0 0 4 13 0 0 2 17 1 0 3 7 2 0 3 7 1 0 1 2 0 0 5 2 0 0 2 3 0 0 0 4 1 0 3 6 0 0 0 0 2 0 0 0 0 0 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0> 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Total 6 6 10 5 5 17 17 20 12 11 3 7 5 5 9 2 0 Total 43 89 8 0 0 0 140 Hours of calm in Hours of missing Hours of missing this stability class: wind measurements in this 2 stability class: 0 all stability classes: stability measurements in 3-- page 94 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Stability Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable Period of Record: October Class -Extremely Stable Winds Measured at Wind Speed-December2012
-60m-10m Delta-T (F)i0 Meters (in mph)1-3 4-7 2 1 1 0 1 4 0 1 1 1 2 0 3 0 1 2 0 0 0 7 2 0 0 0 1 0 1 0 0 0 0 7 0 0 8-12 13-18 19-24 > 24 Total 0 0 0 0 2 0 0 0 0 1 0 0 0 0 8 0 0 0 0 2 0 0 0 0 1 0 0 0 0 4 0 0 0 0 0 0 0 0 0 2 0 0 0 0 1 0 0 0 0 2 0 0 0 0 2 0 0 0 0 0 0 0 0 0 3 0 0 0 0 0 0 0 0 0 8 0 0 0 0 8 0 0 0 b 2 0 0 0 0 0 Total 20 18 0 0 0 0 38 Hours of calm in this stability class: 1 Hours of missing Hours of missing wind measurements in this stability class: 0 stability measurements in all stability classes: 3-- page 95 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY.CLASS Clinton Power Station Period of Record: October -December2012 Class Extremely Unstable -60m-10m Delta-T Stability (F)Winds Measured at 60 Meters Wind Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 8-12 13-18 0 6 0 4 0 1 1 1 0 3 0 0 0 0 2 0 0 1 0 6 0 3 0 0 0 0 0 0 2 9 0 1 0 0 19-24 2 1 0 0 0 0 0 0 0 4 1 0 3 1 1 0 0> 24 0 0 0 0 0 0 0 0 0 0 0 0 0 2 0 0 0 Total 8 5 1 2 3 0 0 2 1 10 4 0 3 3 12 1 0 Total 0 0 5 35 13 2 55 Hours of calm in this stability class: 0 Hours of missing wind measurements in this stability class: Hours of missing stability measurements in all stability cl 0 asses: 3-- page 96 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record- Octobetr-'
December2012 Stability Class -Moderately Unstable'
-60m-10m Delta-T (F)Winds Measured at 60 Meters Wind Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24 >24 Total 5 3 5 1 4 0 3 9 10 16 8 2 6 5 7 0 0 Total 0 12 27 30 14 1 84 Hours of calm in Hours of missing this stability class: wind measurements in this 0 stability class: 0 all stability classes: Hours of missing stability measurements in 3-- page 97 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station* period of. Record: October -. December2012 Stability Class -Slightly Unstable -60mT10m Delta-T (F)Winds Measured at 60 Meters Wind Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24 > 24 Total 8 12 7 1 1 2 4 11 22 16 10 9 13 13 13 6 0 Total 4 29 47 44 12 12 148 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 98 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: October -December2012 Stability Wind Directior N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable Class -Neutral ... .60m-,[Winds Measured at 60 Meters Wind-Speed (in mph)10m Delta-T (F)1-3 4-7 8-12 13-18 19-24 > 24 Total 22 8 8 2 3 3 7 8 6 6 5 3 6 2 17 9 0 30 12 17 7 9 4 19 38 18 21 14 13 9 39 39 35 0 30 13 6 16 20 5 2 23 35 24 29 11 19 36 35 16 0 6 5 5 2 9 3 3 9 35 23 7 9 6 47 14 14 0 1 9 4 0 0 0 0 2 24 27 6 2 5 35 5 1 0 89 49 40 27 41 15 31 80 121 101 63 38 45 161 115 76 0 Total 15 115 324 320 197 121 1092 Hours of calm in Hours of missing Hours of missing this stability class: wind measurements in this stability measurements in 0 stability class: 0 all stability classes: 3-- page 99 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: October-December2012 Stability.Class -Slightly Stable -60m-10m Delta-T (F)Winds Measured at 60 Meters 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 1 1 2 1 2 3 10 2 1 3 3 1 2 4 0 2 0 8 7 5 4 3 1 22 23 13 16 12 10 9 10 6 3 0 18 32 5 3 6 6 2 39 79 63 17 10 10 28 19 7 0 11 3 2 0 1 1 0 3 38 23 4 1 2 5 1 0 0 1 0 0 0 0 0 0 1 10 1 0 0 1 0 0 0 0 39 44 14 8 12 11 34 68 141 106 36 22 24 47 26 13 0 Total 2 38 152 stability class: 344 95 14 645 Hours of calm in this Hours of missing wind 0 measurements in this stabili tv class: 0 Hours of missing stability measurements in all stabi lity classes: 3-- page 100 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: October Stability Class -Moderately Stable Winds Measured at-December2012
-60m-l10m Delta-T (F)60 Meters Wind Speed (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 8-12 13-18 19-24 *> 24 Total 8 1 9 12 2 8 9 25 23 16 6 7 4 4 4 3 0 Total 3 24 54 60 0 0 141 Hours of calm in this Hours of missing wind stability class: measurements in this 1 stability class: 0 all stability classes: Hours of missing stability measurements in 3-- page 101 of 109 --
TABLE 18 (continued)
JOINT WIND FREQUENCY DISTRIBUTION BY STABILITY CLASS Clinton Power Station Period of Record: October'," Stability Class -<Extremely Stable'Winds Measured at Wind Speed-December2012 6- 0m-10m Delta-T (F)60 Meters (in mph)Wind Direction N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW Variable 1-3 4-7 0 0 0 0 0 1 0 3 1 0 1 0 0 0 0 0 0 0 3 0 1 0 0 2 3 2 2 0 0 0 0 0 2 0 8-12 13-18 1 0 0 0 0 0 1 1 4 1 0 0 0 0 0 0 0 1 0 0 2 0 1 0 0 0 0 0 1 1 3 0 0 0 19-24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0> 24 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 Total 1 3 0 3 5 1 2 6 4 2 3 1 0 0 2 5 0 Total 6 15 13 4 0 0 38 Hours of calm in this stability class: 1 Hours of missing wind measurements in this stabi Hours of missing stability measurements in all s lity class: 0 tability classes: 3-- page 102 of 109 --
SECTION 8 ODCM OPERATIONAL REMEDIAL REQUIREMENT REPORTS In accordance with CPS ODOM section[s]
2.7.1 and 3.9.2, INOPERABLE radioactive liquid and gaseous effluent monitoring instrumentation channels remaining in an INOPERABLE condition for greater than 30 days shall be reported in the Annual Radioactive Effluent Release Report.During the course of 2012, there were zero (0) instances when either a radioactive liquid or gaseous effluent instrumentation channel[s]
was INOPERABLE for greater than any 30 day period.During the course of 2012, there were no occurances where Surveillance requirements were not met.-- page 103 of 109 --
SECTION 9 CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS In accordance with Section 7.2 of the CPS ODCM, licensee-.initiated changes to the liquid, gaseous or solid radioactive waste treatment systems shall be reported in the Annual Radioactive Effluent Release Report.The Process Control Program (PCP) for radioactive wastes is controlled by procedure RW-AA-100, with* revision*
8 (implemented in 2012) as the last revision.All changes made to the document are denoted by "Revision Bars" in the right hand margin. No changes were made in the procedure impacting Clinton Power Station solid waste treatment systems. The changes were reviewed under the 1OCFR Part 50.59 and the Plant Operational Review Committee processes.
Revision 8 was approved on 7/18/2012.
A copy of revision 8 to RW-AA-100 is attached to this report, along with the associated approval paperwork.
-- page 104 of 109 --
SECTION 10 NEW LOCATIONS FOR DOSE CALCULATION AND /OR ENVIRONMENTAL MONITORING The following is a summary of the 2012 Annual Land', Use Census. I-lt shows changes in locations for dose. calculations and / or environmental monitoring identified by the Annual Land Use Census. The distance of the receptor is being listed in the report in lieu of the name of the resident..
This is being doneto, maintain and respect the privacy of the residents.
1.0 Nearest
Residence The nearest residents identified in each of the sixteen (16) sectors are shown below.2012 2011 SECTOR RESIDENT AGE GROUP RESIDENT AGE GROUP (miles) (miles)N 0.9 A 0.9 A NNE 0.9 A 0.9 A NE 1.3 A 1.3 A ENE 1.8 C, A 1.8 C, A E 1.0 A 1.0 A ESE 3.2 A 3.2 A SE 2.8 A 2.4 T, A SSE 1.8 A 1.8 A S 3.0 A 3.0 A SSW 2.9 A 2.9 A SW 3.5 T, A 0.7 A WSW 2.2 A 2.2 A W 1.2 C, T, A 1.2 C, T, A WNW 1.6 C, A 1.6 A NW 1.6 A 1.6 A NNW 1.3 A 1.3 A (I)nfant (C)hild (T)een (A)dult-- page 105 of 109 --
SECTION 10 (continued)
2.0 Broadleaf
Garden Census Eighty-eight (88) gardens within a five. (5) mile radius were located in the sixteen (16) geographical sectors:.surrounding CPS. Twenty-six (26)-.gardens contained broad leaf vegetation.
Although other crops were identified within, these areas, they are not add.ressed.as pa.rt. of this, report.,, The nearest gardens greater than fifty (50) square-meters and producing broadleaf vegetation identified in each of the sixteen (16) geographical sectors are shown below.2012 2011 SECTOR GARDENS AGE GROUPS GARDENS AGE GROUPS (miles) (miles)N 0.9 A 0.9 A NNE 2.3 C, T, A 3.0 T, A NE 4.3 A 2.1 A ENE 1.8 C, A 1.8 C, A E 1.0 A 2.5 C, A ESE 3.3 A 3.3 A SE >5 4.4 C, A SSE 2.7 C, A 2.8 A S 4.1 A 4.1 A SSW >5 >5 SW 3.5 T, A 3.6 C, A WSW 2.3 A 2.3 A W 2.0 A 2.0 C, A WNW 1.6 A 1.6 A NW 2.9 T, A >5 NNW 1.3 A 1.3 A (I)nfant (C)hild (T)een (A)dult-- page 106 of 109 --
SECTION 10 (continued)
3.0 Milking
Animal Census Milking animals within the sixteen (16) geographical sectors were looated within five (5) miles surrounding CPS. These milking animals Were 'either Used for the nursing of their offspring or used for meat production for'their .owný personal use and sold commercially.
There were no residents that milked tfieir forhuman consumption.
Milking animals were specifically identified, for this report.' :Although other livestock were identified within these areas, they are not addressed as part of this report.The nearest milking animals sectors are shown below.identified in each of the sixteen (16) geographical SECTOR 2012 MILKING AGE 2011 MILKING AGE ANIMALS (miles) GROUPS ANIMALS (miles) GROUPS N 0.9 A 0.9 A NNE 2.3 A 2.3 A NE >5 >5.ENE >5 >5 E >5 >5 ESE >5 >5 SE >5 >5 SSE 2.8 T, A 2.8 T, A S 4.1 A >5 SSW >5 >5 SW >5 >5 WSW 3.4 A 3.4 A W >5 >5 WNW >5 >5 NW >5 >5 NNW 1.3 A 1.3 A (I)nfant (C)hild (T)een (A)dult-- page 107 of 109 --
SECTION 11 CORRECTIONS TO.DATA REPORTED IN PREVIOUS REPORTS There were no administrative changes identified in 2012 against previously submitted Annual Radioactive Effluent Release Report[s]
resulting in an errata data submittal to the Commission.
-- page 108 of 109 --
SECTION 12 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL There were no changes to the.Offsite Dose Calculation Manual in 2012.-- page 109 of 109 --
RW-AA-100 Revision 8 En 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 1OCFR 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 1 OCFR 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 1OCFR61 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 (1OCFR61 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 1OCFR 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, dem ineralization, 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 filtercartridges-,:
-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 1 OCFR 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 Processing 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 beCOLLECTED and SURVEYED-and may be'SORTED for compactable and non-compactabl
- Wastes., 2. DAW may be packaged in containers to. facilitateon-site 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 1OCFR20.2004 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 1 OCFR20.2002 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 49CFR171-172, 10CFR61, 10CFR71, and the acceptance criteria for the applicable burial site.4.4. Shipping 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-1 06. 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 manu al proceduires,.-or botler vendor.waste processing/operating procedures shall be approved per RM-AAL-1.02-1006.
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
TVDes. Point of Generation, and Processina 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.
WASTE STREAM POINTS OF GENERATION AVAILABLE WASTE PROCESSING METHODS Bead Resin Systems -Fuel Pool, Condensate, Dewatering, solidification to an Reactor Water Cleanup, Blowdown, unstable/stable state Equipment Drain, Chemical and 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 ThermalProcessing 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 WASTE STREAM POINTS OF GENERATION AVAILABLE WASTE WASTESTREAM POINTSOFGENERATION_
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:
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.
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 1:983 .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-1 06, Plant Operations Review Committee 6.3.3. RM-AA-1 02-1006, Processing Vendor Documents 6.3.4. RP-AA-600 Series, Radioactive MaterialN/aste 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, 1 OCFR20.2002 permit granted to Limerick via letter dated July 10, 1996.7. ATTACHMENTS
-None Document Site Approval Form Page 1 of 2 AD-AA-101-F-01 Revision 4 I See AD-AA- 101 for the procedural requirements associated with this Form. Facility:
CPS Desktop Instruction available on Intranet or through AD functional area.Document Number: RW-AA-100 Revision:
8 Title: Process Control Program for Radioactive Wastes Superseded Documents:
N/A Z or List: El Check this box if superseding a document containing commitments, notify the Commitment Tracking Coordinator per LS-AA-1 10 so the CTD can be updated as appropriate.
Environmental Review Applicability
-Is an Environmental Review applicable per EN-AA-1 03? No Z or Yes El If Yes, then attach Environmental Review documentation required per EN-AA-103.
Is this a Fleet Standard Document being processed with form AD-AA-1O1-F-09?
No El or Yes 0 If yes, then attach the completed form AD-AA- 101-F-09, skip the following section, and go to Continuation A.Batch -Are multiple document creations/revisions/cancelations being issued to add/revise/cancel them for similar reauirements?
No nl or Yes nl If Yes, then identify the hiahest level Document and Issue TVDe below.Check only one Document Type: Check only one Issue Type: Incorporated Site Items (EC, AR, Level 1 -Continuous Use Procedure E] New E] PCR, etc): Level 2 -Reference Use Procedure El Revision El Level 3 -Information Use Procedure El Cancel Document El T&RM [] Cancel Revision E1 T&rm ENon-Permanent E]Form 'Z' Editorial Revision El Revision Summary: (Attach additional description if required)CONFIRM that no commitments (i.e., those steps annotated with CM-X) have been changed or deleted unless evaluated via completion of LS-AA-1 10 commitment change/deletion form and INITIAL [Preparer]:
__Preparer Print Date Extension Validation
-Is substantiating this document's usability via mockup, simulated performance, field walkdown, or bench top review required?
No [E or Yes El If Yes, then attach validation documentation.
If Yes, then print name & sign for completed validation:
NOS Review -Excluding NDE, ISI, Peer Inspection or Independent Verification, is this document used to perform independent inspection for acceptance (including field installation inspections, fabrication inspections, receipt inspections, new fuel inspection, etc.), or for certification of Inspection personnel?No
[] or Yes El If Yes, then NOS Reviewer to print name & sign for acceptance:
Continuation A -Is this a T&RM, Form, or Editorial Revision?
No E or Yes L] If yes, then skip the following section and go Continuation B.Impact on Operating and Design Margins -N/A 0 or explain: (Attach additional description if required)0 No 0l Yes 10CFR50.59 Applicable?
[0 No [I Yes 10CFR72.48 Applicable?
0 No El Yes Other Regulatory Process Applicable?
0 No E] Yes Potential security impact per SY-AA-500-12 0 No 0] Yes Surveillance Coordinator Review Required Cross Discipline Reviews: (list below)N/A Tracking Number: Other Regulatory Process Number: If Yes, then Security Reviewer acceptance documented by cross discipline review below If Yes, then Surveillance Coordinator Review documented by cross discipline review below Print Print Signature Signature Date Disdpline or Org.Date Discipline or Org.Date Disocpline or Org.Print Signature Attnrch it ,rnr'd.....................
1-d SQR Approval indicates that all required Cross-Disciplinary reviews have been performed a e rviewers have signed this form. This procedure is technically and functionally accurate for all functional D-AA-102_6O.AAAi
! i SOR Approval:
0 ' (c (46c-/ _ _-1__""___11__1__
Print and Sign Date Discpline Document Site Approval Form Page 2 of 2 AD-AA-101-F-01, Revision 4 I Continuation B -Is this a T&RM, or Form? No 0 or Yes El If yes, then skip the following section and go Continuation C. ..1.U I PORC Required: El No 0 Yes If yes, then enter PORC Number (after PORCpro, .)" Plant Manaaer Print and Sian (when reauired S. .....I --. .....- --.. .... -...Continuation C-, :Is this an' EditorialRevision?
No. or Yes'El If yes, then skip the following section and go to Continuation
., Applicable Site Contact/Site Change Agents (SME): Krampholz-Responsible for Change Management information in El this form or Dl HU-AA-1 101 Checklist (attached)
-Responsible to shepherd the document through site review, approval/authorization, and implementation.
Affected Functional Area(s) or Individuals:
Gary Krampholz
--'-7 g/ "/'i/201 ZL- Chem/Env Print 7 Signiture Pate Affected FA Print Signature Date Affected FA Print Signature Date Affected'FA Attach additional if req d Resources needed to Implement Change: N/A (Only list, if other than Level of Effort.)For ongoing impacts, estimate number of Full Time Equivalents (FTE). If additional resources are needed go to HU-AA-1101.Communication Plan: N/A (e.g., e-mail, Site Paper, Supervisor Briefing, Voice Mail, etc.)Training Required / Qualifications affected:
Z No [] Yes If yes, list: __(e.g., Supervisory Briefing, Tailgate Briefing, Required Reading, Formal Training, recertification etc.)Update to information infrastructure (e.g. PassPort, PIMS, EDMS workflows, etc.) required to support implementation (including updated forms loaded into" PassPort):
N/A Controlled Document distribution (ref. RM-AA-1 02) or Records Retention Schedule (ref. RM-AA-101
-1004)impacted:
0 No E] Yes If yes, describe change and list Records Manager contacted:
N/A I Continuation D -If all procedurally required activities associated with this document revision have been completed and the document is ready for implementation, then SFAM to print name, sign & date for authorization to implement.
Provide implementation date or, if the Implementation Date is blank or N/A then implementation will be upon the issuance by Records Management per RM requirements.
Authorization below indicates the SFAM or a designee of the SFAM has verified the document does not alter or negatively impact compliance with regulatory requirements or station commitments.
Interim Chg #Authorization:
---SFAM Print and Sign Date ImpI. Date Exp. Date SRRS Number 1B.100 Fleet Standard Document -Corporate Approval Form Page 1 of 2 AD-AA-101-F-09 Revision 0 See AD-AA- 101 for the procedural requirements associated with this Form.Desktop Instruction available on Intranet or through AD functional area.Document Number: RW-AA-100 Revision:
8 Title: Process Control Program for Radioactive Wastes :I-Superseded Fleet Standard Documents:
NIA.0 or List- : ......Batch -Are multiple document creations/revisions/cancelationsbeing issuedtoadd revise cancel a No r1 nr rIif Yep. idlpntifv the le~vnl flnt~lment Ik'w Tvne belnW. "*""r'e ................
No , .. ... ... ........ ....... or ....... M If. .......-the ..... thele el oc m Check only one Document Type: Check only one Issue Type: Incorporated, Fleet Items:d Level 1 -Continuous Use Procedure El New El Level 2 -Reference Use Procedure El Revision 0 Level 3 -Information Use Procedure.
0]. Editorial Revision El T&RM 81 Cancel Document El Form Cancel Revision El Revision Summary: See attached Summary of Changes.(Attach additional description if required)CONFIRM that no commitments (i.e., those steps annotated with CM-X) have been changed or deleted unless evaluated via completion of LS-AA-1 10 commitment change/deletion form and INITIAL [Preparer]:
RMC Preparer Robert Claes 03/07/12 Cantera/6303372629 Print Date Location and Fxt Site Applicability and Contacts -Check box and provide name: BRW 0 Michael Gorge ORE 10 Sandy Uvecchl OYS 0 Gonzalo Lamela TMI 0 Tamara Hanlon BYR 0 Norma Gordon LAS 0 Lynn Kofold-Durdan PEA 0 George Tharpe ZIN [1 CPS 0 Anthony Kilbum LIM 0 Unda Knapp QDC 0 Debra Cline Other 0[Affected Functional Area (FA) -Check box & provide Corporate contact name if FA is affected by this revision: AD [-_ _ ER C_ NO __ RW[ ['AR r'_ _ HR []_ OP E_ SA [I BOO _ _HU __ OU 0_ SMO _Cc __ IT _ _ _ PC __ SY 0_CY 0_ LR 0_ PI _ _ TO 0_El 0_ LS [I PL 0_ WC 0_EN __ MA [I RMO _ _0_ _EPO NF C_ RP 0 _ _0_Validation
-Is substantiating this document's usability via mockup, simulated performance, field walkdown, or bench top review required?
No 0 or Yes [] If Yes, then attach validation documentation.
If Yes, then print name & sign for completed validation:
NOS Review -Excluding NDE, ISI, Peer Inspection or Independent Verification, is this document used to perform independent inspection for acceptance (including field instailation inspections, fabrication inspections, receipt inspections, new fuel inspection, etc.), or for certification of Inspection personnel?
No 0 or Yes E]If Yes, then NOS Reviewer to print name & sign for acceptance:
Common Training -Is common training material being provided? (Document in the change management how the common training material will be developed and 9 pevided to the sites or attach.) No 0 or Yes E]Change Management provided in: HU-AA-y61 C/a.,rge Checklist Attached E] or: As directed by SFAM 0 CFAM Approval Miguel Azar/ 03/07/12 Canterai3240 Cru PriftandISif
,..-v Date Location and Ext SRRS Number 1B.100 Fleet Standard Document -Corporate Approval Form AD-AA-101-F-09 Page 2 of 2 Revision 0 1. Step 4.1.8 suggested wording should read: "An Exelon Nuclear plant may store waste at another Exelon Nuclear plant, provided formal NRC approval has been received for the, transfer of waste." 2.. Add a step under section 4.4 "Shipment sent for off site storage shall meet the storage site's waste acceptance cnteria 3. Add step 4.1.8 "It also possible to store waste from one nuclear plant at another nuclear plant, if formal NRC approval has been received." 4. Modify step 4.2.8 by adding the following words at the end of sentence "in the pool or loading the processed activated hardware into Dry Case storage system.
50.59 APPLICABILITY REVIEW FORM LS-AA-104-1002 Revision 4 ,~age I of I Activity/1acument Number: R iki .4 4 -10 0 -Revision.
Number: Title: tOCeSSCW+/-
~ CZ~Address the questions below for all aspects of the Activity.
If the answer is yes foi any portionothe Activioyf apply, the identified process(es) to that portion of the Activity.
Note that it is not unusual to have more than one process apply toa g kefivity.
See Section 4 of the Resource Manual (RM) for additional guidance.
..I. Does the proposed Activity involve a change: I. Technical Specifications or FacilityOperating License (IOCFRSO.90)?
WNO E] YES See Section:4.2.1.1 of the RM 2. Conditions of License Quality Assurance program (I0CFR50.54(a))?
I NO E YES Security Plan (I0CFR50.54(p))?
INO E] YES See Section 4.2.1.2 of the RM Emergency Plan (IOCFR50.54(q))?
9 NO El YES 3. Codes and Standards IST Program Plan (IOCFR50.55a(f)?
D4NO E] YES See Section 4.2.1.3 of the RM ISI Program Plan (IOCFR50.55a(g))?
0? NO El YES 4. ECCS Acceptance Criteria (IOCFR5O.46)?
ONO E] YES See Section 4.2.1.4 of the RM 5. Specific Exemptions (IOCFR50.12)?
[NO E] YES See Section 4.2.1.5 of the RM 6. Radiation Protection Program (IOCFR20)?
I]NO El YES See Section 4.2.1.6 of the RM 7. Fire Protection Program (applicable UFSAR or operating license NO YES See Section 4.2.1.7 of the RM condition)?
___O___ES__Setin
_.2..7ofthR
- 8. Programs controlled by the Operating License or the Technical E NO YES See Section 4.2.1.7 of the RM Specifications (such as the ODCM). ___O___Y__eeecion4.._._oth
__9. Environmental Protection Program [INO E] YES See Section 4.2.1.7 of the RM 10. Other programs controlled by other regulations.
[K NO [] YES See Section 4.2.1 of the RM II. Does the proposed Activity involve maintenance which restores SSCs to their original condition or involve a temporary alteration supporting N NO ED YES See Section 4.2.2 of the RM maintenance that will be in effect during at-power operations for 90 days or less?Ill. Does the proposed Activity involve a change to the: I. UFSAR (including documents incorporated by reference) that is limited to reformatting, simplification, removing excessive detail, or minor C] NO E] YES See Section 4.2.3 of the RM editorial changes as discussed in NEI 96-07 or NEI 98-03?2. Managerial or administrative procedures governing the conduct of facility operations (subject to the control of 10CFR50, Appendix B) E NO I' YES See Section 4.2.4 of the RM 3. Procedures for performing maintenance activities (subject to IOCFR50, NO E YES See Section 4.2.4 of the RM Appendix B)? __4. Regulatory commitment not covered by another regulation based change AmNO E YES See Section 4.2.3/4.2.4 of the RM process (see NEI 99-04)?7V Does the proposed Activity involve a change to the Independent Spent Fuel NO []YES See Section 4.2.6 of the RM Storage Installation (ISFSI) (subject to control by 10 CFR 72.48) __] NO [_YS ecio_42.6ofth R Check one of the following:If all aspects of the Activity are controlled by one or more of the above processes, then a 50.59 Screening is not required and the Activity may be implemented in accordance with its governing procedure.
I if any portion of the Activity is not controlled by one or more of the above processes, then process a 50.59 Screening for the portion not covered by any of the above processes.
The remaining portion of the activity should be implemented in accordance with its governing procedure.
Signoff: 50.59 Screener/50.59 Evaluator:
E','- sW. AviSign: -__._.__._.__Date:
__/_1/12 (Circle One) (Print name) (Signature) 50.59 REVIEW COVERSHEET FORM LS-AA-104-1001 Revision 3 Page I of I I) ¢" L141 6 /Station/Unit(s):
L. r 3 Activity/Document Number: Title: -C/-,O C ST)
-]£/6 Revision Number: NOTE: For 50.59 Evaluations, information on this form will provide the basis for preparing the biennial summary report submitted to the NRC in accordance with the requirements of 10 CFR 50.59(d)(2).
Description of Activity: (Provide a bref, concise descriptioo yf what th propsedctivity involvys.)
Reason for Activity: (Discuss why the proposed activity is being performed.)
", .1i L C. C Do ,- rpo t 1 24 & o<a <.,,-r , 4~~Af' sp/,4 wA Effect of Activity: (Discuss how the activity impacts plant operations, design bases, or safety analyses described in the UFSAR.).li-oe,,, ,',,, A/?,dM ,,7, £ p,.<.%L ,, .Ae o1 ,,t,-f/..--4, 5,_Summary of Conclusioi for the Activity's 50.59 'Review: (Provide justification for the conclusion, including sufficient detail to recognize and understand the essential arguments leading to the conclusion.
Provide more than a simple statement that a 50.59 Screening, 50.59 Evaluation, or a License Amendment Request, as applicable, is not required.)
Attachments:
Attach all 50.59 Review forms completed, as appropriate.
Forms Attached: (Check all that apply.)bd Applicability Review El 50.59 Screening M 50.59 Evaluation 50.59 Screening No.50.59 Evaluation No.Rev.Rev.