ML20307A327
| ML20307A327 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Byron  |
| Issue date: | 10/31/2020 |
| From: | Exelon Generation Co |
| To: | Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20307A325 | List: |
| References | |
| RS-20-138 EP-AA-1002, Rev 37 | |
| Download: ML20307A327 (20) | |
Text
ATTACHMENT 2 Standardized Radiological Emergency Plan Revision EP-AA-1002, Revision 37, "Radiological Emergency Plan Annex for Byron Station"
EP-AA-1002 Revision 37 EXELON NUCLEAR RADIOLOGICAL EMERGENCY PLAN ANNEX FOR BYRON STATION
Byron Annex Exelon Nuclear October 2020 ii EP-AA-1002 (Revision 37)
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Byron Annex Exelon Nuclear October 2020 iii EP-AA-1002 (Revision 37)
Table of Contents Section Page Section 1: Introduction BY 1-1 1.1 Facility Description BY 1-1 1.2 Emergency Planning Zones BY 1-1 Section 2: Organizational Control of Emergencies BY 2-1 Section 3: Classification of Emergencies BY 3-1 Section 4: Emergency Measures BY 4-1 4.1 Notification of the Emergency Organization BY 4-1 4.2 Assessment Actions BY 4-1 4.3 Protective Actions for the Offsite Public BY 4-1 4.4 Protective Actions for Onsite Personnel BY 4-2 Section 5: Emergency Facilities and Equipment BY 5-1 5.1 Emergency Response Facilities BY 5-1 5.2 Assessment Resources BY 5-1 5.3 Protective Facilities and Equipment BY 5-5 5.4 First Aid and Medical Facilities BY 5-6 5.5 Law Enforcement Agencies BY 5-6 5.6 Fire Fighting Organizations BY 5-6 5.7 EMS Support BY 5-6 APPENDIXES Appendix 1: NUREG-0654 Cross-Reference Appendix 2: Station Letters of Agreement ADDENDUMS Addendum 1 On-Shift Staffing Technical Basis Addendum 2: Evacuation Time Estimates for Byron Generating Station Plume Exposure Pathway Emergency Planning Zone Addendum 3: Emergency Action Levels for Byron Station
Byron Annex Exelon Nuclear October 2020 iv EP-AA-1002 (Revision 37)
REVISION HISTORY Revision 1; September 1984 Revision 12, July 8, 2002 Revision 2; May 1986 Revision 13, October 4, 2002 Revision 3; June 1987 Revision 14, November 15, 2002 Revision 3b; May 1988 Revision 15, May 12, 2003 Revision 3c; May 1989 Revision 16, December 2004 Revision 3d; September 1989 Revision 17, January 2006 Revision 4; January 1991 Revision 18, March 2006 Revision 4a; April 1992 Revision 19, September 2006 Revision 4b; November 1992 Revision 20, May 2007 Revision 4c; February 1993 Revision 21, October 2007 Revision 4d; December 1993 Revision 22, March 2008 Revision 4e; January 1993 Revision 23, December 2008 Revision 4f; November 1994 Revision 24, April 2009 Revision 4h; November 1995 Revision 25, March 2010 Revision 4i; December 1995 Revision 26, May 2010 Revision 4k; June 1996 Revision 27, November 2010 Revision 4l; February 1997 Revision 28, March 2011 Revision 4m: January 5, 1998 Revision 29, May 2012 Revision 4n: August 14, 1998 Revision 30, November 2012 Revision 4p: October 16, 1998 Revision 31, December 2012 Revision 5: May 13, 1999 Revision 32, June 2013 Revision 6: June 23, 1999 Revision 33, June 2014 Revision 7: January 8, 2001 Revision 34, December 2014 Revision 8: October 8, 2001 Revision 35, November 2017 Revision 9, October 31, 2001 Revision 36, December 2019 Revision 10, November 1, 2001 Revision 37, October 2020 Revision 11, January 3, 2002
Byron Annex Exelon Nuclear October 2020 BY 1-1 EP-AA-1002 (Revision 37)
Section 1: Introduction As required in the conditions set forth by the Nuclear Regulatory Commission (NRC) for the operating license for the Byron Station, the management of Exelon recognizes its responsibility and authority to operate and maintain the nuclear power stations in such a manner as to provide for the safety of the general public.
The Byron Emergency Preparedness Program consists of EP-BY-1000, the Byron Radiological Emergency Plan (E-Plan), EP-AA-1002, Radiological Emergency Plan Annex for Byron Station, Exelon emergency plan implementing procedures, and associated program administrative documents. The Byron Station Radiological Emergency Plan outlines the basis for response actions that would be implemented in an emergency.
This document serves as the Byron Station Emergency Plan Annex and contains information and guidance that is unique to the station. This includes facility geography location for a full understanding and representation of the stations emergency response capabilities. The Station Annex is subject to the same review and audit requirements as the Byron Radiological Emergency Plan.
1.1 Facility Description The Byron Station, Units 1 and 2, are located in Northern Illinois, approximately 3.7 miles south-southwest of the City of Byron in Ogle County. This site is situated near the center of the county in a predominantly agricultural area. At its closest approach, the Rock River is approximately 1.5 miles west of the western site boundary and 2.2 miles west-southwest of the actual plant location. Byron Station occupies approximately 1288 acres of land. The station site is somewhat rectangular in shape, with the plant structures occupying the southeast portion of the site.
Figure 1-1 shows the general location of Byron Station. More specific information on station siting may be found in the Updated Final Safety Analysis Report (UFSAR).
The plant consists of two identical pressurized water reactor (PWR) nuclear steam supply systems (NSSS) and turbine generators furnished by Westinghouse Electric Corporation. Each nuclear steam supply system is designed for a power output of 3645 MWt. Cooling for the plant is provided by two natural draft cooling towers for nonessential service cooling water and by mechanical draft cooling towers for essential service cooling water.
1.2 Emergency Planning Zone The plume exposure Emergency Planning Zone (EPZ) for Byron Station is an area surrounding the station with a radius of about ten miles. (Exact boundaries are determined by the State of Illinois). Refer to Figure 1-1.
The ingestion pathway EPZ for Byron Station is an area surrounding the station with a radius of about 50 miles.
Byron Annex Exelon Nuclear October 2020 BY 1-2 EP-AA-1002 (Revision 37)
Figure 1-1: Byron Station Location and 10 Mile EPZ
Byron Annex Exelon Nuclear October 2020 BY 2-1 EP-AA-1002 (Revision 37)
Section 2: Organizational Control of Emergencies Byrons Emergency Response Organization (ERO) and its key positions are described in the Byron Radiological Emergency Plan (EP-BY-1000).
Exelon Nuclear has contractual agreements with several companies whose services would be available in the event of a radiological emergency. These agencies and their available services are listed in Appendix 3 of the Byron Radiological Emergency Plan.
Site specific Agreements also exist on file at Byron Station with several support agencies. These agencies and their support roles are listed in Appendix 2, Station Letters of Agreement.
Byron Annex Exelon Nuclear October 2020 BY 3-1 EP-AA-1002 (Revision 37)
Section 3: Classification of Emergencies The Byron Emergency Action Levels and supporting information are re-located in EP-AA-1002, Addendum 3.
Byron Annex Exelon Nuclear October 2020 BY 4-1 EP-AA-1002 (Revision 37)
Section 4: Emergency Measures Byron emergency response actions are covered by Section E of the Byron Radiological Emergency Plan.
4.1 Notification of the Emergency Organization The Emergency Director is responsible for notifying the State of Illinois Emergency Management Agency (IEMA) via NARS. Ogle County will also be notified via NARS; however, IEMA will maintain responsibility of county notification. If a General Emergency is the initiating event, the Emergency Director is also responsible for notifying the following offsite agencies:
Ogle County 4.2 Assessment Actions Throughout each emergency situation, continuing assessment will occur.
Assessment actions at Byron Station may include an evaluation of plant conditions; in plant, onsite, and initial offsite radiological measurements; and initial estimates of offsite doses. Core damage information is used to refine dose assessments and confirm or extend initial protective action recommendations.
Byron Station utilizes WCAP-14696-A, Revision 1, (1999) as the basis for the methodology for post-accident core damage assessment. This methodology utilizes real-time plant indications. In addition, Byron Station may use samples of plant fluids and atmospheres as inputs to the CDAM (Core Damage Assessment Methodology) program for core damage estimation.
4.3 Protective Actions for the Offsite Public Protective actions concerning the public within the 10-mile EPZ involve prompt notification, evacuation and sheltering. Prompt notification involves the use of the permanently installed outdoor notification sirens located within the EPZ To aid the Emergency Response Organization during a developing emergency situation, EP-AA-111, "Emergency Classification and Protective Action Recommendations" has been developed based on Section J.10.m of the Byron Radiological Emergency Plan.
4.3.1 Alert and Notification System (ANS) Sirens The ANS consists of a permanently installed outdoor notification system within a ten-mile radius around the station. The ten-mile radius around the station is primarily an agricultural area with a population density below 2000 persons per square mile. The ANS as installed consists of mechanical and electronic sirens that will cover this entire area with a minimum sound level of 60 db. Additionally, the ANS will cover the heavily populated areas within the ten-mile radius around the station with a minimum sound level of 70 dB to ensure complete coverage.
Once the public has tuned to designated radio stations in an emergency, detailed instructional messages will be given to the public. State and local procedures provide for these messages.
Backup means of notification is achieved through Route Alerting, which is
Byron Annex Exelon Nuclear October 2020 BY 4-2 EP-AA-1002 (Revision 37) contained within the State and respective counties Radiological Emergency Response Plans and procedures. The means consists of utilizing vehicles with public address (PA) systems in the event the primary method of alerting and notification is unavailable. The backup method has the capability to alert and notify the public within the plume exposure pathway EPZ within a reasonable time, but does not need to meet the 15-minute design objective for the primary prompt public alert and notification system.
4.3.2 Evacuation Time Estimates The ETE study used population data from the 2010 census which includes parts of two counties in Illinois (Ogle and Winnebago). The evacuation times are based on a detailed consideration of the EPZ roadway network and population distribution. The ETE Study, contained in EP-AA-1002 Addendum 2, Evacuation Time Estimates for the Byron Generating Station Plume Exposure Pathway Emergency Planning Zone, presents evacuation times for daytime and nighttime scenarios under various weather conditions for the evacuation of various areas around the Byron Station, once a decision has been made to evacuate.
4.4 Protective Actions for Onsite Personnel Byron Station has a siren system to warn personnel of emergency conditions.
Upon hearing a continuous two (2) minute siren, all personnel not having emergency assignments have been instructed to assemble in predesignated assembly areas. Refer to Figure 4-1. Station ERO personnel report to the Technical Support Center and Control Room personnel report to the Main Control Room. Radiation Protection, Chemistry and Operations personnel not assigned to the Main Control Room report to the Operations Support Center.
If a site evacuation of non-essential personnel is required by Section J of the Byron Radiological Emergency Plan, personnel will be either relocated and monitored at the relocation centers or sent home if there is no release or radiological/safety concerns. The designated relocation centers for Byron Station are Morrison Relocation Center, Morrison, Illinois Quad Cities Station, Cordova, Illinois For evacuation routes, refer to EP-AA-113-F-18.
Traffic control for onsite areas will be handled by Byron Station personnel, if necessary.
Equipment and personnel would be available at the Morrison Relocation Center and Quad Cities Station for monitoring and decontamination of evacuated personnel. If major decontamination, follow-up, or bioassay samples are necessary, those persons would be sent to Quad Cities Station.
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Figure 4-1: Byron Station Assembly Areas and Onsite Emergency Response Facilities
Byron Annex Exelon Nuclear October 2020 BY 5-1 EP-AA-1002 (Revision 37)
Section 5: Emergency Facilities and Equipment 5.1 Emergency Response Facilities Refer to Figure 4-1 for the location of the Byron Station Control Room, Technical Support Center (TSC), and Operations Support Center (OSC) within the Station's Protected Area boundary.
5.1.1 Station Control Room The Byron Station Control Room is the initial onsite center of emergency control and is located on the 451' elevation of the Auxiliary Building.
5.1.2 Technical Support Center (TSC)
Byron Station has designated a TSC which exists at the south end of the Turbine Building. The TSC fully meets the requirements of Section H.1.b of the Byron Radiological Emergency Plan.
5.1.3 Operations Support Center (OSC)
Byron Station has designated a primary Operation Support Center. The primary OSC is the Response Center and Meeting Room #1 on the 451' elevation of the Service Building. The OSC conforms to the requirements of Section H.1.c of the Emergency Plan and is the location to which operations support personnel will report during an emergency and from which they will be dispatched for assignments in support of emergency operations.
5.1.4 Alternative Facility The Alternative Facility maintains the capability for staging the TSC/OSC emergency response organization personnel in the event of a hostile action. This alternative facility has the capability for communications with the emergency operations facility, control room, and plant security and the capability for engineering assessment activities, including damage control team planning and preparation. Consistent with NRC EPFAQ No. 2013-005, the EOF will satisfy the offsite notification responsibilities for the Alternative Facility. The Alternative Facility is located at 919 First Street, Dixon Illinois. (CM-1, ref. AR 1362747.44) 5.2 Assessment Resources 5.2.1 Onsite Meteorological Monitoring Instrumentation A 250-foot meteorological tower has been erected on the site approximately 3400 feet southwest of the Byron Station reactor building, the major plant structure closest to the tower.
Wind speed, wind direction and temperature are measured at 30 feet and 250 feet above grade level. Temperature difference is determined between the 30-foot and 250-foot levels. A precipitation gauge is utilized to measure rain and snowfall at ground level near the base of the tower.
The onsite meteorological monitoring program is covered in the contract specification and vendor procedures of the meteorological monitoring
Byron Annex Exelon Nuclear October 2020 BY 5-2 EP-AA-1002 (Revision 37) contractor. These data are used to generate wind roses and to provide estimates of airborne concentrations of gaseous effluents.
5.2.1.1 Instrumentation The meteorological tower is instrumented with equipment that conforms with the recommendations of Regulatory Guide 1.23 and ANSI/ANS 2.5 (1984). The equipment is placed on booms oriented into the generally prevailing wind at the site. Equipment signals are brought to an instrument shack with controlled environmental conditions. The shack at the base of the tower houses the recording equipment, signal conditioners, etc., used to process and re-transmit the data to the end point users.
5.2.1.2 Meteorological Measurement Program During a Disaster Cooperation between the corporate office and the meteorological contract assures that a timely restoration of any outage can be made. Emergency field visits to the site are made as quickly as possible after detection of a failure.
Should a disaster of sufficient magnitude occur to destroy the tower structure, a contract is maintained to have a temporary tower erected within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, weather conditions permitting.
Further, the meteorological contractor maintains two levels of sensors (wind speed, wind direction and temperature) in a state of readiness for use on the temporary tower.
Additionally, Exelon Nuclear's existing instrumented towers at other nuclear sites provide a high-density measurement network with multiple backup opportunities.
Meteorological data are available to the station Control Room, Technical Support Center, and Emergency Operations Facility for use in the Dose Projection Computer Model for estimating the environmental impact of unplanned releases of radioactivity from the station.
5.2.2 Onsite Radiation Monitoring Equipment The onsite radiation monitoring capability includes an installed process, effluent, and area radiation monitoring system; post accident sampling capability; portable survey instrumentation; counting equipment for radiochemical analysis; and a personnel dosimetry program to record integrated exposure. Some onsite equipment is particularly valuable for accident situations and is described in the following subsections.
5.2.2.1 Radiation Monitoring System Chapters 11 and 12 of the Byron UFSAR describe the radiation monitoring system (RMS) in detail. The installed RMS is designed to continuously monitor the containment atmosphere, plant effluents, and various inplant locations.
Byron Annex Exelon Nuclear October 2020 BY 5-3 EP-AA-1002 (Revision 37)
The system includes Control Room readouts and recorders for selected parameters that are monitored and an audible Control Room alarm when predetermined setpoints are exceeded. The system can be subdivided into process/effluent instrumentation and an area monitoring system.
The process/effluent instrumentation consists of pumps, filter samplers, detectors, and associated electronics to determine noble gas, iodine, and particulate concentrations in plant cubicles or liquid and gaseous effluents. Several monitored effluent pathways have control functions which will terminate the release at a predetermined setpoint. These setpoints are premised on compliance with federal regulations.
The area monitoring system provides information of existing radiation levels in various areas of the plant to ensure safe occupancy. It is equipped with Control Room and local readout and audible alarms to warn personnel of an increased radiation level.
Some onsite equipment is particularly valuable for accident situations and is described in the following sections.
5.2.2.2 Radiological Noble Gas Effluent Monitoring Two General Atomic Company wide-range gas monitors (WRGM) are installed for sampling the auxiliary building vent stacks which are the final release points for gaseous effluents. The monitors have a range of 1 x 10-7 uCi/cc to 1 x 105 uCi/cc. Each monitor includes the following:
One isokinetic nozzle located in the vent stack, a sample conditioning skid to filter out radioiodine and particulate activity, the wide range gas detector assembly including three gas detectors of the low, mid, and high ranges, two sample pumps (high flow used in the low range mode and low flow used for the mid/high range), and an auxiliary pump skid which boosts flow when using the mid/high range of the WRGM.
The system also includes a microprocessor which utilizes digital processing techniques to analyze data and control monitor functions. Readouts are available in the control room with associated audible alarms. Two General Atomic Company RD-12 detectors are provided for each of the four main steam lines upstream of the safety and relief valves. The range of the monitor is 10-1 mR/hr to 104 mR/hr. The monitors will be mounted external to the main steam line piping and corrections made for the loss of low energy gammas.
Byron Annex Exelon Nuclear October 2020 BY 5-4 EP-AA-1002 (Revision 37) 5.2.2.3 Radioiodine and Particulate Effluent Monitoring The General Atomic Company wide range gas monitor includes a sampling rack for collection of the auxiliary building vent stack particulate and radioiodine samples. Filter holders and valves are provided to allow grab sample collection for isotopic analyses in the station's counting rooms. The sampling rack is shielded to minimize personnel exposure. The sampling media will be analyzed by a gamma ray spectrometer which utilizes a gamma spectrometer system detector. In addition, silver zeolite cartridges are available to further reduce the interference of noble gases.
5.2.2.4 High-Range Containment Radiation Monitors Two high range containment radiation monitors are installed for each operating reactor. The monitors will detect and measure the radiation level within the reactor containment during and following an accident. The range of the monitors is 1 rad/hr to 107 rads/hr.
5.2.2.5 In-plant Iodine Instrumentation Effective monitoring of increasing iodine levels in buildings under accident conditions will include the use of portable instruments using silver zeolite as a sample media. Auxiliary counting room locations have been identified within the Turbine Building. It is expected that a sample can be obtained and analyzed for iodine content within a two-hour time frame.
5.2.3 Onsite Process Monitors An adequate monitoring capability exists to properly assess the plant status for all modes of operation and is described in the Byron UFSAR.
The operability of the post-accident instrumentation ensures information is available on selected plant parameters to monitor and assess important variables following an accident. Instrumentation is available to monitor the parameters and ranges given in Technical Specifications. Byron Station Emergency Operating Procedures aid personnel in recognizing inadequate core cooling using applicable instrumentation.
5.2.4 Onsite Fire Detection Instrumentation The fire detection system is designed in accordance with applicable National Fire Protection Association (NFPA) Standards. The system is equipped with electrically supervised ionization smoke and heat detectors to quickly detect any fires and the instrumentation to provide local indication and Control Room annunciation. In addition to the smoke and heat detection systems, each fire protection carbon dioxide, halon, or water system is instrumented to inform the Control Room of its actuation or of system trouble. In the event that a portion of the fire detection instrumentation is inoperable, fire watches in affected areas may be required.
Byron Annex Exelon Nuclear October 2020 BY 5-5 EP-AA-1002 (Revision 37) 5.2.5 Facilities and Equipment for Offsite Monitoring Consult Chapter 11 of the station specific Offsite Dose Calculation Manual (ODCM) for the most current location for fixed continuous air samplers and DLR locations. Byron Station maintains a supply of emergency equipment and supplies for offsite monitoring and sampling by environmental field teams.
5.2.6 Site Hydrological Characteristics The hydrological characteristics of the Byron Station vicinity are described in the Byron UFSAR. The river screen house is the only structure that could be affected by flooding on the Rock River and is designed for a combined event flood, where a combined event flood is defined as a flood on the Rock River having a 1 x 10-6 annual probability of being exceeded at a 90% confidence level. All other Byron Station structures are 161 feet or more above the Probable Maximum Flood level of the Rock River.
The minimum design operating level of the essential service water makeup pumps is 3.8 feet lower than the water level for the 1-day 100-year low flow drought condition. In the unlikely event that emergency make-up water requirements cannot be satisfied by surface water withdrawals from the Rock River, groundwater wells will serve for makeup to the essential service water cooling towers.
Because of the site hydrological characteristics given above, plant operation should not be affected by Rock River water level conditions and therefore, hydrological monitors have not been installed. The Rock River is not used for any public water supply. There are no recorded plans for any future public water supply usage from the Rock River. The nearest surface water users downstream from Byron Station are on the Mississippi River over 115 miles away. This allows for sufficient mixing that makes permanently installed hydrological monitors unnecessary. In performing dose calculations from liquid releases, Byron Station uses a historical average river flow value, Fw, as a parameter in the liquid release model.
5.3 Protective Facilities and Equipment The principal onsite assembly areas for Byron Station are the Machine Shop on the 401-foot elevation of the Service Building and the Unit #1 Turbine Building track-way. These areas are suitable because:
- 1. They are large open areas suitable for assembling a large number of people in a short time;
- 2. They can be easily exited if a site evacuation is deemed necessary following an assembly; and
- 3. They have a low probability of being affected by a serious accident involving the Reactor and its primary systems.
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The offsite relocation centers for Byron Station are discussed in Section 4 of this annex. These locations are suitable, depending on the emergency condition.
These locations are owned by Exelon; thus, personnel, supplies, and communications are readily available.
5.4 First Aid and Medical Facilities Byron Station has an in plant first aid/decontamination room on the 426-foot elevation of the auxiliary building near the station laboratory complex. This room is provided with a sink, a shower, and a supply cabinet. First aid kits, stretchers, sinks, eyewashes, and emergency showers have been placed in strategic locations throughout the station.
Medical treatment given to injured persons at the station is of a "first aid" nature.
When more professional care is needed, injured persons are transported to a local hospital or clinic. Javon Bea Hospital-Rockton in Rockford, Illinois is the designated support hospital. Amita Health St. Joseph Hospital in Joliet, Illinois is the backup medical facility.
Both hospitals agree in the event of a Radiological Event, including a hostile action-based event, to ensure the capability for the evaluation of radiation exposure and uptake, including assurance that persons providing these services are adequately prepared to handle contaminated individuals and capable of providing medical support for any contaminated injured individual.
5.5 Law Enforcement Agencies A Letter of Agreement is established for Local Law Enforcement to support Byron Station to respond to a Radiological Event including a Hostile Action Based Event, in conjunction with the National Incident Management System upon notification by the station in accordance with the established communications protocol.
5.6 Fire Fighting Organizations A Letter of Agreement is established for the local Fire Department to respond to a Radiological Event, including a Hostile Action Based Event, in conjunction with the Mutual Aid Box Alarm System (MABAS) as requested via the 911 Dispatch System.
5.7 EMS Support A Letter of Agreement is established for the Local Fire Department to provide Emergency Medical Services in respond to a Radiological Event including a Hostile Action Based Event, This includes transportation of patients from the Byron Station, including those who may have been exposed to radiation or may have injuries complicated by radioactive contamination, to Javon Bea Hospital-Rockton by use of the communications via the 911 Dispatch System.
Byron Annex Exelon Nuclear October 2020 Appendix 1-1 EP-AA-1002 (Revision 37)
Appendix 1: NUREG-0654 Cross-Reference Annex Section NUREG-0654 1.0 Part I, Section A 1.1 Part I, Section C 1.2 Part I, Section D Figure 1-1 Part I, Section D 2.0 Part II, Section A.4 2.1 Part II, Section A.3 3.0 Part II, Section D 4.1 Part II, Section E.1 & J.7 4.2 Part II,Section I.2 & 3 4.3 Part II, Section J.10.m 4.3.1 Part II, Section E.6 4.3.2 Part II, Section J.8 4.4 Part II, Section J.1-5 EP-AA-111 Part II, Section J.10.m EP-AA-1002, Addendum 2 Part II, Section J.8 & 10.b Figure 4-1 Part II, Section J.5 4.4 Part II, Section J.2 & 3 5.1 Part II, Section H.1 & G.3 5.2.1 Part II, Section H.5.a & 8 5.2.2 Part II, Section H.5.b & I.2 5.2.3 Part II, Section H.5.c 5.2.4 Part II, Section H.5.d 5.2.5 Part II, Section H.6.b & 7 5.2.6 Part II, Section H.5.a & 6.a 5.3 Part II, Section J.1-5 5.4 Part II, Section L.1 & 2
Byron Annex Exelon Nuclear October 2020 Appendix 2-1 EP-AA-1002 (Revision 37)
Appendix 2: Station Letters of Agreement
- 1. Byron Fire Protection District and Rescue - fire protection.
- 2. Javon Bea Hospital-Rockton - medical services.
- 3. The Ogle County Sheriff's Office - law enforcement.
- 4. Amita Health St. Joseph Hospital of Joliet, Illinois, acts as the back-up supporting medical facility for Byron Station.