View source for RA-14-032, Byron, Units 1 and 2, Attachment 3, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1002, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosures 3B, 3C, by 3-75 - by 3-157

{{Adams
| number = ML14164A061
| issue date = 05/30/2014
| title = Byron, Units 1 and 2, Attachment 3, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1002, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosures 3B, 3C, by 3-75 - by 3-157
| author name = 
| author affiliation = Exelon Generation Co, LLC
| addressee name = 
| addressee affiliation = NRC/FSME, NRC/NMSS, NRC/NRR
| docket = 05000454, 05000455
| license number = NPF-037, NPF-068
| contact person = 
| case reference number = NEI 99-01, Rev 6, RA-14-032, RS-14-115, TMI-14-046
| document report number = EP-AA-1002
| package number = ML14164A053
| document type = Emergency Preparedness-Emergency Plan, License-Application for Facility Operating License (Amend/Renewal) DKT 50
| page count = 198
}}

=Text=
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-N * ~U * *~=5 *U I~fl ~ ...~RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MSA59 Initiating Condition:
Hazardous event affecting a SAFETY SYSTEM needed-required for the current operating mode.Operating Mode Applicability:
1,2,3,4 Emergency Action Level (EAL): (4-) 1. a- The occurrence of ANY of the following hazardous events: " Seismic event (earthquake)" Internal or external flooding event" High winds or tornado strike" FIRE" EXPLOSION" (Site ,p. ci.,v )" Other events with similar hazard characteristics as determined by the Shift Manager AND 2.b-. EITHER of the following:
a.4- Event damage has caused indications of degraded performance in at least one train of a SAFETY SYSTEM needed-required by Technical Specifications for the current operating mode.OR b. 2. The event has caused VISIBLE DAMAGE to a SAFETY SYSTEM component or structure needed-required by Technical Specifications for the current operating mode.Basis: FIRE: Combustion characterized by heat and light. Sources of smoke such as slipping drive belts or overheated electrical equipment do not constitute FIRES. Observation of flame is preferred but is NOT required if large quantities of smoke and heat are observed.EXPLOSION:
A rapid, violent and catastrophic failure of a piece of equipment due to combustion, chemical reaction or overpressurization.
A release of steam (from high energy lines or components) or an electrical component failure (caused by short circuits, grounding, arcing, etc.) should not automatically be considered an explosion.
Such events may require a post-event inspection to determine if the attributes of an explosion are present.Month 20XX BY 3-75 EP-AA-1002 (Revision XX)
Annmw F::alnn hhilarlr ILrtr n~FvlnMai~
RECOGNITION CATEGORY SYSTEM MALFUNCTIONS SAFETY SYSTEM: A system required for safe plant operation, cooling down the plant and/or placing it in the cold shutdown condition, including the ECCS. These are typically systems classified as safety-related.
VISIBLE DAMAGE: Damage to a component or structure that is readily observable without measurements, testing, or analysis.
The visual impact of the damage is sufficient to cause concern regarding the operability or reliability of the affected component or structure.
This IC addresses a hazardous event that causes damage to a SAFETY SYSTEM, or a structure containing SAFETY SYSTEM components, needed-required for the current operating mode, "required", i.e. required to be operable by Technical Specifications for the current operating mode. This condition significantly reduces the margin to a loss or potential loss of a fission product barrier, and therefore represents an actual or potential substantial degradation of the level of safety of the plant. Manual or automatic electrical isolation of safety equipment due to flooding, in and of itself, does not constitute degraded performance and is classified under HU6.EAL I hbI 2.a addresses damage to a SAFETY SYSTEM train that is required to be operable by Technical Specifications for the current operating mode, and is in sewi e/operation since indications for it will be readily available.
The indications of degraded performance should be significant enough to cause concern regarding the operability or reliability of the SAFETY SYSTEM train. -EAL 1.b.2.b addresses damage to a SAFETY SYSTEM component that is required to be operable by Technical Specifications for the current operating mode, and is not in sewir.Woperation or readily apparent through indications alone, er-as well as damage to a structure containing SAFETY SYSTEM components.
Operators will make this determination based on the totality of available event and damage report information.
This is intended to be a brief assessment not requiring lengthy analysis or quantification of the damage.Escalation of the emergency classification level would be via IC FS1 or RAS1.If the EAL conditions of MA5 are not met then assess the event via HU3, HU4, or HU6.Basis Reference(s):
: 1. NEI 99-01, Rev 6 SA9 Month 20XX BY 3-76 EP-AA-1002 (Revision XX)
Explon Nuclear Byron Annex...e..n.N..
l...RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MSU641 Initiating Condition:
RCS leakage for 15 minutes or longer.Operating Mode Applicability:
1,2,3,4 Emergency Action Level (EAL):--Note: The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded. Em....gency Director should d,, ,aro the Unusual Event promptly upon dot8Frmining that 15 minutes has boon eXceeded, or will likely be exceeded 1. RCS unidentified or pressure boundary leakage gieater-than
> 10 gpm for > 15 minutes. (Site specif. value) for 15 minutes or longr.OR 2. RCS identified leakage gpm for > 15 minutes.(site specific value)For 15 m;inutes Or longer.OR 3. Leakage from the RCS to a location outside containment 
>25 gpm for_> 15 minutes.greater than 25 gpmR for 15 minutes Or longer.Basis: UNISOLABLE:
An open or breached system line that cannot be isolated, remotely or locally.This IC addresses RCS leakage which may be a precursor to a more significant event.In this case, RCS leakage has been detected and operators, following applicable procedures, have been unable to promptly isolate the leak. This condition is considered to be a potential degradation of the level of safety of the plant.EAL #1 and EAL #2 Basis These EALs are focused on a loss of mass from the RCS due to "unidentified leakage","pressure boundary leakage" or "identified leakage" (as these leakage types are defined in the plant Technical Specifications).
EAL #3 Basis This EAL addresses a RCS mass loss caused by an UNISOLABLE leak through an interfacing system.Month 20XX BY 3-77 EP-AA-1002 (Revision XX)
Rvron Annex Exallon Nuclear Rvrnn Annex Eeo ula RECOGNITION CATEGORY SYSTEM MALFUNCTIONS These EALs thus apply to leakage into the containment, a secondary-side system (e.g., steam generator tube leakage) or a location outside of containment.
The leak rate values for each EAL were selected because they are usually observable with normal Control Room indications.
Lesser values typically require time-consuming calculations to determine (e.g., a mass balance calculation).
EAL #1 uses a lower value that reflects the greater significance of unidentified or pressure boundary leakage.The release of mass from the RCS due to the as-designed/expected operation of a relief valve does not warrant an emergency classification.
An emergency classification would be required if a mass loss is caused by a relief valve that is not functioning as designed/expected (e.g., a relief valve sticks open and the line flow cannot be isolated).
The 15-minute threshold duration allows sufficient time for prompt operator actions to isolate the leakage, if possible.Escalation of the emergency classification level would be via ICs of Recognition Category RA or F.Basis Reference(s):
: 1. NEI 99-01 Rev 6, SU4 2. Technical Specifications 3.4.13 & 3.4.14 3. UFSAR. 6.2, 5.2 4. 1/2 BOSR 4.13.1-1 Unit One(Two) Reactor Coolant System Water Inventory Balance 72 Hour Surveillance
: 5. 1/2 BOL 4.15 LCOAR -RCS Leakage Detection Instrumentation
: 6. 1/2 BOL 4.13 LCOAR -RCS Operational Leakage 7. 1/2 BOA PRI-1 Excessive Primary Leakage Unit 1/2 8. 1/2 BOSR 0.1-4 Unit One(Two) Mode 4 Shiftly and Daily Operating Surveillance
: 9. 1/2 BOSR RF-1 Unit One(Two) Containment Floor Drain Monitoring System Non-Routine Surveillance
: 10. 0/1/2 BOSR XZB-R1, Unit 0/1/2 Meter Zone Banding Month 20XX BY 3-78 EP-AA-1002 (Revision XX)
Bvron Annex Exellon Nuclear RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MSU761 Initiating Condition:
Loss of all On-site or Off-site communications capabilities.
Operating Mode Applicability:
1,2,3,4 Emergency Action Level (EAL): 1. Loss of ALL Table M3 Onsite communications capability affecting the ability to perform routine operations.
OR 2. Loss of ALL Table M3 Offsite communication capability affecting the ability to perform offsite notifications.
OR 3. Loss of ALL Table M3 NRC communication capability affecting the ability to perform NRC notifications.
Table M3 -Communications Capability System Onsite Offsite NRC Radios X Plant page X Plant Telephone X System Commercial X X X Telephones NARS X ENS X X HPN X X Satellite phones X X 1. Less of ALL of tho followiRn-oncie communcaftion moethds.c: (cite eDocific list of communications mothod I f AU U f~i. f11. tU.i~ ~ .X I~.I.-4. 1=966 Of ALL u Of Tollow+IIWRig W...,w_ uoGM.M'_RunIR6n s) MffiHOU6: Month 20XX BY 3-79 EP-AA-1002 (Revision XX)
Bvron Annex Exellon Nuclear RECOGNITION CATEGORY SYSTEM MALFUNCTIONS (Site Spocific_
li6st Of co-mmunicationS mothods1)3. Loss6- of ALL of the foIo'.wmg NRC comnctionS Methos (Site specific !ict Of GGomMUnicatieon methods)Basis: This IC addresses a significant loss of on-site, offsite, or NRC communications capabilities.
While not a direct challenge to plant or personnel safety, this event warrants prompt notifications to Offsite Response Organizations (OROs) and the NRC.This IC should be assessed only when extraordinary means are being utilized to make communications possible (e.g., use of non-plant, privately owned equipment, relaying of on-site information via individuals or multiple radio transmission points, individuals being sent to offsite locations, etc.).EAL #1 Basis aAddresses a total loss of the communications methods used in support of routine plant operations.
EAL #2 Basis-aAddresses a total loss of the communications methods used to notify all OROs of an emergency declaration.
The OROs referred to here are listed in procedure EP-MW-114-100-F-01, Nuclear Accident Reporting System (NARS) Form. (see -., Nete4.EAL #3 Basis-aAddresses a total loss of the communications methods used to notify the NRC of an emergency declaration.
Basis Reference(s):
: 1. NEI 99-01 Rev 6, SU6 2. EP-MW-124-1001 Facilities Inventories And Equipment Tests Month 20XX BY 3-80 EP-AA-1002 (Revision XX)
Rvrnn Annoy Rvrnn Annex Exelon Nucla~r RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MSU8 7 Initiating Condition:
Failure to isolate containment or loss of containment pressure control.Operating Mode Applicability:
1,2,3,4 Emergency Action Level (EAL): 1. a. Failure of containment to isolate when required by an actuation signal.AND b. ANY required penetration remains open > 15 minutes of the actuation signal.ALL r.quir.d PnotratioRn t .lo. v' within 15 Minutes of tho a~twatensignal.
OR 2. a. Containment pressure > 20 psigg.roatr than (site S19ciGAG pr...u.AND b. Less than one full train of Containment Spray is operating per design for >15 minutoc ._. ,;, ,ytF .)-,,,;rtm or-long-r.
Basis: This IC addresses a failure of e-or-- moroany containment penetrations to automatically isolate (close) when required by an actuation signal. It also addresses an event that results in high containment pressure with a concurrent failure of containment pressure control systems. Absent challenges to another fission product barrier, either condition represents potential degradation of the level of safety of the plant.F-Gr-EAL #1 Basis ,-tThe containment isolation signal must be generated as the result on an off-normal/accident condition (e.g., a safety injection or high containment pressure);
a failure resulting from testing or maintenance does not warrant classification.
The determination of containment and penetration status -isolated or not isolated -should be made in accordance with the appropriate criteria contained in the plant AOPs and EOPs. The 15-minute criterion is included to allow operators time to manually isolate the required penetrations, if possible.EAL #2 Basis-aAddresses a condition where containment pressure is greater than the setpoint at which containment energy (heat) removal systems are designed to automatically Month 20XX BY 3-81 EP-AA-1002 (Revision XX)
Exelon Nuclear Byron Annex Eeo ula RECOGNITION CATEGORY SYSTEM MALFUNCTIONS actuate, and less than one full train of equipment is capable of operating per design.The 15-minute criterion is included to allow operators time to manually start equipment that may not have automatically started, if possible.
The inability to start the required equipment indicates that containment heat removal/depressurization systems (e.g., containment sprays or ice condenser fans) are either lost or performing in a degraded manner.This event would escalate to a Site Area Emergency in accordance with IC FS1 if there were a concurrent loss or potential loss of either the Fuel Clad or RCS fission product barriers.Basis Reference(s):
: 1. NEI 99-01 Rev 6, SU7 2. 1/2 BST-5 Containment Unit 1/2 Month 20XX BY 3-82 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CA121 Initiating Condition:
Loss of all offsite and all onsite AC power to emergency bussesbuses for 15 minutes or longer.Operating Mode Applicability:
5,6, D Emergency Action Level (EAL): Note: The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.
The Em8Fergeny Direcator should declare the Alert prom~ptly upon determining that 15 milnutos time has been exceeded, Or Will likely be exceeded.1. Loss of ALL offsite AC power to unit ESF buses.AND 2. Failure of DG 1A(2A) and DG 1B(2B) emergency diesel generators to supply power to unit ESF buses.AND 3. Failure to restore power to at least one unit ESF bus in < 15 minutes from the time of loss of both offsite and onsite AC power.Io , -,f , A IAL andI A InRitoA- C P "-we F to (site -pecificG emrge8,Mnc-Ry bu uses) for 15 Basis: SAFETY SYSTEM: A system required for safe plant operation, cooling down the plant and/or placing it in the cold shutdown condition, including the ECCS. These are typically systems classified as safety-related This IC addresses a total loss of AC power that compromises the performance of all SAFETY SYSTEMS requiring electric power including those necessary for emergency core cooling, containment heat removal/pressure control, spent fuel heat removal and the ultimate heat sink.When in the cold shutdown, refueling, or defueled mode, this condition is not classified as a Site Area Emergency because of the increased time available to restore an emergency bus to service. Additional time is available due to the reduced core decay heat load, and the lower temperatures and pressures in various plant systems. Thus, Month 20XX BY 3-83 EP-AA-1002 (Revision XX)
A nng~w=,v--Ien n khmel--r l uPnrlV I fl l .m n RECOGNITION CATEGORY COLD SHUTDOWN I REFUELING SYSTEM MALFUNCTIONS when in these modes, this condition represents an actual or potential substantial degradation of the level of safety of the plant.The emergency buses of the affected unit can be powered from the unaffected unit through the crosstie breakers.
Unit crosstie is considered an adequate source of offsite power when evaluating this EAL.Fifteen minutes was selected as a threshold to exclude transient or momentary power losses.Escalation of the emergency classification level would be via IC CS64 or RASI.Basis Reference(s):
: 1. NEI 99-01 Rev 6, CA2 2. 20E-0-4001 Station One Line Diagram 3. UFSAR 8.3.1 4. 1/2 BOA ELEC-3 Loss Of 4KV ESF Bus Unit 1/2 5. 1/2 BOA ELEC-4 Loss Of Offsite Power Unit 1/2 6. 1/2 BCA-0.0 Loss Of All AC Power Unit 1/2 7. 1/2 BCA-0.1 Loss Of All AC Power Recovery Without SI Required Unit 1/2 8. 1/2 BCA-0.2 Loss Of All AC Power Recovery With SI Required Unit 1/2 9. 1/2 BCA-0.3 Response To Opposite Unit Loss Of All AC Power Unit 1/2 10. BOP AP-51, Isolating Unit I System AUX Transformer 142-1 & 142-2 While Unit Is At Power 11. BOP AP-52, Restoring Unit 1 System AUX Transformer 142-1 & 142-2 During Power Operation 12. BOP AP-53, Isolating Unit 2 System AUX Transformer 242-1 & 242-2 While Unit Is At Power 13. BOP AP-54, Restoring Unit 2 System AUX Transformer 242-1 & 242-2 During Power Operation 14. Safety Evaluations of the Byron Station and Byron Station Responses to the Station Blackout (SBO) Rule (TAC NOS. 68522, 68523 AND 68515, 68516)Month 20XX BY 3-84 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CU12 Initiating Condition:
Loss of all but one AC power source to emergency buses for 15 minutes or longer.Operating Mode Applicability:
5,6, D Emergency Action Level (EAL): Note: The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.
The Emergency should do.lar, tho Unusual EV9nt prom.ptly upon dotoFrmining that 15 min'utes has becni excoodod, Or Will likely bo oxcoodod.1. AC power capability to unit ESF buses reduced to only one of the following power sources for > 15 minutes.* Affected unit SAT 142-1(242-1)
* Affected unit SAT 142-2(242-2)
* Emergency Diesel Generator DG 1A(2A)* Emergency Diesel Generator DG 1 B(2B)* Unit crosstie breakers AND 2. Any additional single power source failure will result in a loss of ALL AC power to SAFETY SYSTEMS.powor sourc-e- for I Fmintes or longer.AND 19. Any additional singlo poWer sourco failure Will result in loss of all AG powor to SAFETY SYSTEMS.Basis: SAFETY SYSTEM: A system required for safe plant operation, cooling down the plant and/or placing it in the cold shutdown condition, including the ECCS. These are typically systems classified as safety-related.
This IC describes a significant degradation of offsite and onsite AC power sources such that any additional single failure would result in a loss of all AC power to SAFETY SYSTEMS. In this condition, the sole AC power source may be powering one, or more than one, train of safety-related equipment.
Month 20XX BY 3-85 EP-AA-1002 (Revision XX)
Rvron Annex Explon Nuclear Bvrnn AnnexEelnNula RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS When in the cold shutdown, refueling, or defueled mode, this condition is not classified as an Alert because of the increased time available to restore another power source to service. Additional time is available due to the reduced core decay heat load, and the lower temperatures and pressures in various plant systems. Thus, when in these modes, this condition is considered to be a potential degradation of the level of safety of the plant.An "AC power source" is a source recognized in AOPs and EOPs, and capable of supplying required power to an emergency bus. Some examples of this condition are presented below." A loss of all offsite power with a concurrent failure of all but one emergency power source (e.g., an onsite diesel generator).
* A loss of all offsite power and loss of all emergency power sources (e.g., onsite diesel generators) with a single train of emergency buses being back-fed from the unit main generator." A loss of emergency power sources (e.g., onsite diesel generators) with a single train of emergency buses being back-fed from an offsite power source.Fifteen minutes was selected as a threshold to exclude transient or momentary losses of power.The subsequent loss of the remaining single power source would escalate the event to an Alert in accordance with IC CA12.Basis Reference(s):
: 1. NEI 99-01 Rev 6 CU2 2. 20E-0-4001 Station One Line Diagram 3. UFSAR 8.3.1 4. 1/2 BOA ELEC-3 Loss Of 4KV ESF Bus Unit 1/2 5. 1/2 BOA ELEC-4 Loss Of Offsite Power Unit 1/2 6. 1/2 BCA-0.0 Loss Of All AC Power Unit 1/2 7. 1/2 BCA-0.1 Loss Of All AC Power Recovery Without SI Required Unit 1/2 8. 1/2 BCA-0.2 Loss Of All AC Power Recovery With SI Required Unit 1/2 9. 1/2 BCA-0.3 Response To Opposite Unit Loss Of All AC Power Unit 1/2 10. BOP AP-51, Isolating Unit 1 System AUX Transformer 142-1 & 142-2 While Unit Is At Power 11. BOP AP-52, Restoring Unit 1 System AUX Transformer 142-1 & 142-2 During Power Operation Month 20XX BY 3-86 EP-AA-1002 (Revision XX)
Rvrnn  Bvrnn Annexv Exellon Nucilear RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS 12, BOP AP-53, Isolating Unit 2 System AUX Transformer 242-1 & 242-2 While Unit Is At Power 13. BOP AP-54, Restoring Unit 2 System AUX Transformer 242-1 & 242-2 During Power Operation 14. Safety Evaluations of the Byron Station and Byron Station Responses to the Station Blackout (SBO) Rule (TAC NOS. 68522, 68523 AND 68515, 68516)Month 20XX BY 3-87 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear Byro Annex.............
u.l...r RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CA261 Initiating Condition:
Hazardous event affecting SAFETY SYSTEM nieeded-required for the current operating mode.Operating Mode Applicability:
5,6 Emergency Action Level (EAL):: 1. a-. The occurrence of ANY of the following hazardous events:* Seismic event (earthquake)" Internal or external flooding event" High winds or tornado strike" FIRE" EXPLOSION" (Site cpocific hazards)" Other events with similar hazard characteristics as determined by the Shift Manager AND 2.b. EITHER of the following:
a.4-- Event damage has caused indications of degraded performance in at least one train of a SAFETY SYSTEM needed required by Technical Specifications for the current operating mode.OR b. 2 The event has caused VISIBLE DAMAGE to a SAFETY SYSTEM component or structure required by Technical Specifications for the current operating mode.Basis: FIRE: Combustion characterized by heat and light. Sources of smoke such as slipping drive belts or overheated electrical equipment do not constitute FIRES. Observation of flame is preferred but is NOT required if large quantities of smoke and heat are observed.EXPLOSION:
A rapid, violent and catastrophic failure of a piece of equipment due to combustion, chemical reaction or overpressurization.
A release of steam (from high energy lines or components) or an electrical component failure (caused by short circuits, grounding, arcing, etc.) should not automatically be considered an explosion.
Such events may require a post-event inspection to determine if the attributes of an explosion are present.Month 20XX BY 3-88 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN I REFUELING SYSTEM MALFUNCTIONS SAFETY SYSTEM: A system required for safe plant operation, cooling down the plant and/or placing it in the cold shutdown condition, including the ECCS. These are typically systems classified as safety-related.
VISIBLE DAMAGE: Damage to a component or structure that is readily observable without measurements, testing, or analysis.
The visual impact of the damage is sufficient to cause concern regarding the operability or reliability of the affected component or structure.
This IC addresses a hazardous event that causes damage to a SAFETY SYSTEM, or a structure containing SAFETY SYSTEM components, needed-required for the current operating mode, "required", i.e. required to be operable by Technical Specifications for the current operating mode. This condition significantly reduces the margin to a loss or potential loss of a fission product barrier, and therefore represents an actual or potential substantial degradation of the level of safety of the plant. Manual or automatic electrical isolation of safety equipment due to flooding, in and of itself, does not constitute degraded performance and is classified under HU6.EAL -1b-.#2.a addresses damage to a SAFETY SYSTEM train that is required to be operable by Technical Specifications for the current operating mode, and is in sewirei peration since indications for it will be readily available.
The indications of degraded performance should be significant enough to cause concern regarding the operability or reliability of the SAFETY SYSTEM train. -EAL 1.b.2#2.b addresses damage to a SAFETY SYSTEM component that is required to be operable by Technical Specifications for the current operating mode, and is not in see-iGeloperation or readily apparent through indications alone, or to a structure containing SAFETY SYSTEM components.
Operators will make this determination based on the totality of available event and damage report information.
This is intended to be a brief assessment not requiring lengthy analysis or quantification of the damage.Escalation of the emergency classification level would be via IC CS6 or RAS1.If the EAL conditions of CA2 are not met then assess the event via HU3, HU4, or HU6.Basis Reference(s):
: 1. NEI 99-01 Rev 6, CA6 Month 20XX BY 3-89 EP-AA-1002 (Revision XX)
P rrnn Annov I:valnn N"Anrl~AnJ vLn mi~~RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CU341 Initiating Condition:
Loss of Vital DC power for 15 minutes or longer.Operating Mode Applicability:
5,6 Emergency Action Level (EAL): Note: The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.
The Em~ergency Director Shoul-id doclaro tho Uinustual Evient prom~ptly upon determininig that 15 mninutes time har, boon exceeded, Or Will likely be exccoed.Voltage is < 108 VDC on required unit 125 VDC battery buses 111(211) and 112(212)for > 15 minutes.Indiatedvoltage is less than (site specific bus, voltage value) On required Vital DG buses6 foFr 15 minutes o ;,r Oer.Basis: SAFETY SYSTEM: A system required for safe plant operation, cooling down the plant and/or placing it in the cold shutdown condition, including the ECCS. These are typically systems classified as safety-related.
This IC addresses a loss of Vital DC power which compromises the ability to monitor and control operable SAFETY SYSTEMS when the plant is in the cold shutdown or refueling mode. In these modes, the core decay heat load has been significantly reduced, and coolant system temperatures and pressures are lower; these conditions inr-easerise the time available to restore a vital DC bus to service. Thus, this condition is considered to be a potential degradation of the level of safety of the plant.As used in this EAL, "required" means the Vital DC buses necessary to support operation of the in-service, or operable, train or trains of SAFETY SYSTEM equipment.
For example, if Train A is out-of-service (inoperable) for scheduled outage maintenance work and Train B is in-service (operable), then a loss of Vital DC power affecting Train B would require the declaration of an Unusual Event. A loss of Vital DC power to Train A would not warrant an emergency classification.
Fifteen minutes was selected as a threshold to exclude transient or momentary power I losses.Depending upon the event, escalation of the emergency classification level would be via IC CA64- or CA53, or an IC in Recognition Category IRA.Month 20XX BY 3-90 EP-AA-1002 (Revision XX)
Exelon Nuclear Bvron Annex Eeo ula RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS Basis Reference(s):
: 1. NEI 99-01 Rev 6, CU4 2. UFSAR 8.3.2.1.1 3. 6E-0-4001 Station One Line Diagram 4. 1/2 BOA ELEC -1 Loss of DC Bus Unit 1/2 5. BAR 1/2-21-E10 125V DC PNL 111/113 (211/213)
VOLT LOW 6. BAR 1/2-22-ElO 125V DC PNL 112/114 (212/214)
VOLT LOW Month 20XX BY 3-91 EP-AA-1002 (Revision XX)
Rrnn Annov Fi::alnn ?l,"lanr Ari A -nr li i U r RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CU45 I Initiating Condition:
Loss of all onsite or offsite communications capabilities.
Operating Mode Applicability:
5,6, D Emergency Action Level (EAL): 1. Loss of ALL Table C1 Onsite communications capability affecting the ability to perform routine operations.
OR 2. Loss of ALL Table C1 Offsite communication capability affecting the ability to perform offsite notifications.
OR 3. Loss of ALL Table C1 NRC communication capability affecting the ability to perform NRC notifications.
Table C1 -Communications Capability System Onsite Offsite NRC Radios X Plant page X Plant Telephone X System Commercial X X X Telephones NARS X ENS X X HPN X X Satellite phones X X 1. Los o ,f ALL of,- the followi;ng- commrunication methods:.(site specific list Of communications methods)2. Loss of.ALL olf the following ORO cormmunictonnsnr methods: (site sE~ecific lit Of communicsations methods)Month 20XX BY 3-92 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS 3 LoAs of A I of the ,i mothod, (649o SPOcifi liSt Of commFunications methods)Basis: This IC addresses a significant loss of on-site, -ei-offsite, or NRC communications capabilities.
While not a direct challenge to plant or personnel safety, this event warrants prompt notifications to Offsite Response Organizations (OROs) and the NRC.This IC should be assessed only when extraordinary means are being utilized to make communications possible (e.g., use of non-plant, privately owned equipment, relaying of on-site information via individuals or multiple radio transmission points, individuals being sent to offsite locations, etc.).EAL #1 Basis-aAddresses a total loss of the communications methods used in support of routine plant operations.
EAL #2 Basis aAddresses a total loss of the communications methods used to notify all OROs of an emergency declaration.
The OROs referred to here are listed in procedure EP-MW-114-100-F-01, Nuclear Accident Reporting System (NARS) Formrs,. -..,..,..Notes,).EAL #3 Basis aAddresses a total loss of the communications methods used to notify the NRC of an emergency declaration.
Basis Reference(s):
: 1. NEI 99-01 Rev 6, CU5 2. EP-MW-124-1001 Facilities Inventories And Equipment Tests Month 20XX BY 3-93 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CA531 Initiating Condition:
Inability to maintain the plant in cold shutdown.Operating Mode Applicability:
5,6 Emergency Action Level (EAL): Note: The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.
The Emergencay Dioctor chuld dcmlar Alort promptly upon determining that the applicable time has been oxceeded, Or Will likely, be exceeded.1. UNPLANNED rise in RCS temperature 
> 200&deg;F due to loss removal for > Table C2 duration.of decay heat Table C2 -RCS Heat-up Duration Thresholds RCS Containment Closure Heat-up Status Status Duration Intact Not Applicable 60 minutes*Not Intact Established 20 minutes*OR Reduced Inven Not Established 0 minutes Inventory (<397 ft.)* If an RCS heat removal system is in operation within this time frame and RCS temperature is being reduced, then EAL #1 is not applicable.
OR 2. UNPLANNED RCS pressure rise > 10 psig as a result of temperature rise due to loss of decay heat removal. (This EAL does not apply in solid plant conditions.)
I -u !x' u qnrn o ......m onur ooo~o an cm flCTC. -..........
I I l I n I zpima~ltlin ca lJtaon Gtemprl i.ature limit) t9F grFeatr tnFn tfle duatonBecified in the following table.Month 20XX BY 3-94 EP-AA-1002 (Revision XX)
Rrnn Anno=Y F:=alnn  RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS Table: RCS H.eat.up Duratio.n T_,hrs.ho.d.
RCS SatusContain-m-ent ClooSuro _______________
RGS-Sttus Het upsDratio IRtaGt btRet at.roducod in'Rotr Net-applilabl Not intact (Or at roducOd Estabfishe 20 9n*Uutes-nyiietai~y 
[PW4R] Not Establishod OlfUt8s* Ifan CS ootremvalsystem s n Opoation within this time framne and RCS2 tempertaturte is being reduced, the EAL is neet applicable.
2..UP 4 NE RCS preSSure9 inrGease greateAr t-han (cite SPecifi pressure readiRg). (This Al, doeS nort apply during wa'trolid plant fPWRI)Basis: UNPLANNED:
A parameter change or an event that is not 1) the result of an intended evolution or 2) an expected plant response to a transient.
The cause of the parameter change or event may be known or unknown.CONTAINMENT CLOSURE: The procedurally defined conditions or actions taken to secure containment and its associated structures, systems, and components as a functional barrier to fission product release under shutdown conditions.
RCS is intact when the RCS pressure boundary is in its normal condition for the Cold Shutdown mode of operation (e.g. no freeze seals, etc.).This IC addresses conditions involving a loss of decay heat removal capability or an addition of heat to the RCS in excess of that which can currently be removed. Either condition represents an actual or potential substantial degradation of the level of safety of the plant.A momentary UNPLANNED excursion above the Technical Specification cold shutdown temperature limit when the heat removal function is available does not warrant a classification.
The RCS Heat-up Duration Thresholds table addresses a4 ifisreaserise in RCS temperature when CONTAINMENT CLOSURE is established but the RCS is not intact, or RCS inventory is reduced (e.g., mid-loop operation in PWRs). The 20-minute criterion was included to allow time for operator action to address the temperature i i rise.The RCS Heat-up Duration Thresholds table also addresses ao inareaserise in RCS temperature with the RCS intact. The status of CONTAINMENT CLOSURE is not crucial in this condition since the intact RCS is providing a high pressure barrier to a Month 20XX BY 3-95 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN I REFUELING SYSTEM MALFUNCTIONS fission product release. The 60-minute time frame should allow sufficient time to address the temperature ,neaserise without a substantial degradation in plant safety.Finally, in the case where there is ai inGeaserise in RCS temperature, the RCS is not intact or is at reduced inventory 
[P/WR-, and CONTAINMENT CLOSURE is not established, no heat-up duration is allowed (i.e., 0 minutes).
This is because 1) the evaporated reactor coolant may be released directly into the Containment atmosphere and subsequently to the environment, and 2) there is reduced reactor coolant inventory above the top of irradiated fuel.EAL #2 Basis pProvides a pressure-based indication of RCS heat-up.Escalation of the emergency classification level would be via IC CS6 or RAS1.Basis Reference(s):
: 1. NEI 99-01 Rev 6, CA3 2. BOP PC-1 Containment Closure Tracking Capability
: 3. 1/2 BOSR 4.3.1-1 Reactor Coolant System Pressure Temperature Limit Surveillance
: 4. 1/2 BGP 100-1 Plant Heatup 5. 1/2 BGP 100-5, Plant Shutdown and Cool Down 6. 1/2 BGP 100-6, Unit I(Unit 2) Refueling Outage Month 20XX BY 3-96 EP-AA-1002 (Revision XX) iR rnn Annav I::alnn klnAnrl-r RurnAnJ vILnMuaa RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS Initiating Condition:
UNPLANNED ieaeerise in RCS temperature Operating Mode Applicability:
5,6 Emergency Action Level (EAL): Note: The Emergency Director should declare the event promptly upon c cun I letermining that the applicable time has been exceeded, or will likely be exceeded.
The Flnlrnannot, fI'm:r tnr fl-hnnllri d ,-I,-rn thn I~nnui , F al ,nn ll.-r l determinin.
that 15 minutes has boon eXco.do...
or.. ill.l.kel.
Wbe ..xeeded..v&deg;.1. UNPLANNED rise in RCS temperature 
> 200&deg;F due to loss of decay heat removal.OR 2. Loss of the following for >15 minutes.* ALL RCS temperature indications AND* ALL RCS level indications I1 J oJ:1 tLJI'J6A'i -x.r-ii InRGnna in Sa' *etnmnnmnim Wn C]Feannr Tflfl RI falACTI .---.---rnnk ~ M +;n Ql ^^10~nnfli 4 0 ka 1+l,4 +, ar i r,,,r in pvti xyd to.. 511- Own Umpord UK; m rp-l I .... I I. -- J l- -- --L! -- --- -- -- J P~~~~~~~.~~~ry 
&#xfd; ZJ.J.J S.,. I Ia; so aS ml &#xfd;Se S&#xfd;S .Sla*AIS W-.I VS.-a Sl a.m~inuters or longer.I I I I IV IVl I V Basis: UNPLANNED:
A parameter change or an event that is not 1) the result of an intended evolution or 2) an expected plant response to a transient.
The cause of the parameter change or event may be known or unknown.CONTAINMENT CLOSURE: The procedurally defined conditions or actions taken to secure containment and its associated structures, systems, and components as a functional barrier to fission product release under shutdown conditions.
This IC addresses an UNPLANNED Pir-easerise in RCS temperature above the Technical Specification cold shutdown temperature limit, or the inability to determine RCS temperature and level, represents a potential degradation of the level of safety of Month 20XX BY 3-97 EP-AA-1002 (Revision XX)
Exalon Nuclear Bvrnn Annex Eeo ula RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS the plant. If the RCS is not intact and CONTAINMENT CLOSURE is not established during this event, the Emergency Director should also refer to IC CA53.RCS is intact when the RCS pressure boundary is in its normal condition for the Cold Shutdown mode of operation (e.g. no freeze seals, etc.).A momentary UNPLANNED excursion above the Technical Specification cold shutdown temperature limit when the heat removal function is available does not warrant a classification.
EAL #1 involves a loss of decay heat removal capability, or an addition of heat to the RCS in excess of that which can currently be removed, such that reactor coolant temperature cannot be maintained below the cold shutdown temperature limit specified in Technical Specifications.
During this condition, there is no immediate threat of fuel damage because the core decay heat load has been reduced since the cessation of power operation.
During an outage, the level in the reactor vessel will normally be maintained above the reactor vessel flange. Refueling evolutions that lower water level below the reactor vessel flange are carefully planned and controlled.
A loss of forced decay heat removal at reduced inventory may result in a rapid ir-easerise in reactor coolant temperature depending on the time after shutdown.EAL #2 reflects a condition where there has been a significant loss of instrumentation capability necessary to monitor RCS conditions and operators would be unable to monitor key parameters necessary to assure core decay heat removal. During this condition, there is no immediate threat of fuel damage because the core decay heat load has been reduced since the cessation of power operation.
Fifteen minutes was selected as a threshold to exclude transient or momentary losses of indication.
Escalation to Alert would be via IC CA64- based on an inventory loss or IC CA53 based on exceeding plant configuration-specific time criteria.Basis Reference(s):
: 1. NEI 99-01 Rev 6, CU3 Month 20XX BY 3-98 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS
: 2. Technical Specifications Table 1.1-1 3. 1/2 BOSR 0.1-6 Unit One (Two) Mode 6 Shiftly And Daily Operating Surveillance
: 4. BOP RH-9 Pump Down of the Refueling Cavity to the RWST 5. BOP RC-4 Reactor Coolant System Drain 6. 1/2 BOSR 3.3.1-1 Unit One (Two) Accident Monitoring Instrumentation Monthly Channel Checks 7. 1/2 BOL 4.15, LCOAR -RCS Leakage Detection Instrumentation
: 8. 1/2 BOL 4.13, LCOAR -RCS Operational Leakage 9. 1/2 BOSR 4.3.1-1 Reactor Coolant System Pressure / Temperature Limit Surveillance Month 20XX BY 3-99 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS Initlati Loss o challer Opera 5,6 Emer Note: CG641 ing Condition:
if reactor vessel/RCS inventory affecting fuel clad integrity with containment nged.ting Mode Applicability:
;ency Action Level (EAL): The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.
Therrr,-~ h al.4 r h -,l --* rn n r % .n , L-4 -&#xfd;- &#xfd;- &#xfd;d e-ermi,-ing in: t aV MIRiW Has been uixcuuuu, er will i.kely be .A......1. a. RVLIS indicates 0% Plenum for > 30 minutes.OR Reactor Vessel Refueling Level Indicators LT-046 and LT-049 < 392 ft. el. for> 30 minutes.AND b. ANY Containment Challenge Indication (Table C4)OR 2. Reactor vessel level unknown for > 30 minutes.AND 3. Core uncovery is indicated by ANY of the following:
* Table C3 indications of a sufficient magnitude to indicate core uncovery.OR* Erratic Source Range Neutron Monitor indication.
OR* 1/2 RE-AR011 or 1/2 RE-AR12 Containment Fuel Handling Incident radiation monitors > 3000 mR/hr.AND 4. Any Containment Challenge Indication (Table C4)Month 20XX BY 3-100 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS Table C3 Indications of RCS Leakage* UNPLANNED Containment Sump level rise*" UNPLANNED Auxiliary Bldg. Sump level rise*" UNPLANNED Tank (rad waste) level rise** UNPLANNED rise in RCS makeup* Observation of leakage or inventory loss*Rise in level is attributed to a loss of reactor vessel/RCS inventory.
Table C4 -Containment Challenge Indications
* Hydrogen Concentration in Containment 
> 5%* UNPLANNED rise in containment pressure* CONTAINMENT CLOSURE not established*
0* if CONTAINMENT CLOSURE is re-established prior to exceeding the 30-minute core uncovery time limit, then escalation to a General Emergency is not required.1. a. (Reactor vossolfRG level less than (Site Specific leVel) for 30 minutes OF AND b. indic.a.tion from the Contuainm.e.nt Challenne (ce belo'-w.2. a. Reactor vossel/RCS level cannot be monitood for 30 mninutes Or longer.A bII%('e GAAI Inr'nAr" indS in b" ANY of the fallnmnr.... -*.spA*~r A..,.. t4t*' O~J~.fl ~t% = MhA~,% huI.JIJ iter indieatieft v A V TTT~ A TLT~T 0 ----A U Q-#A-Q--------n"--QuaQ a n" " magnitude to indieate or-e uneoveny BY 3-101 EP-AA-1002 (Revision XX)Month 20XX Byron Annex Exelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS 9 (Other- site specific indications)
AND G. ANY indic-zation fmrom the Containment Challenge Table (soe bolow).Containment Challenge-Tabe
&#xa3;(Explosive maiture) exists inside containment UUNPLANNED inces inntainment pressure*if CONTAIN4MENIT CLSU e esrootablished prior to oxcooding the 30 mrninute timne vtt te de ra~aie of al Ge, ne,, alvw Emve1 v, Iw vvi.,ni )t Fe vlqui  ,Basis: IMMINENT:
The trajectory of events or conditions is such that an EAL will be met within a relatively short period of time regardless of mitigation or corrective actions.CONTAINMENT CLOSURE: The procedurally defined conditions or actions taken to secure containment and its associated structures, systems, and components as a functional barrier to fission product release under shutdown conditions.
UNPLANNED:
A parameter change or an event that is not 1) the result of an intended evolution or 2) an expected plant response to a transient.
The cause of the parameter change or event may be known or unknown.This IC addresses the inability to restore and maintain reactor vessel level above the top of active fuel with containment challenged.
This condition represents actual or IMMINENT substantial core degradation or melting with potential for loss of containment integrity.
Releases can be reasonably expected to exceed EPA Protective action Guidelines (PAG) exposure levels offsite for more than the immediate site area.Following an extended loss of core decay heat removal and inventory makeup, decay heat will cause reactor coolant boiling and a further reduction in reactor vessel level. If RCS/reactor vessel level cannot be restored, fuel damage is probable.With CONTAINMENT CLOSURE not established, there is a high potential for a direct and unmonitored release of radioactivity to the environment.
If CONTAINMENT CLOSURE is re-established prior to exceeding the 30-minute time limit, then declaration of a General Emergency is not required.The existence of an explosive mixture means, at a minimum, that the containment atmospheric hydrogen concentration is sufficient to support a hydrogen burn (i.e., at the lower deflagration limit). A hydrogen burn will raise containment pressure and could Month 20XX BY 3-102 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN I REFUELING SYSTEM MALFUNCTIONS result in collateral equipment damage leading to a loss of containment integrity.
It therefore represents a challenge to Containment integrity.
In the early stages of a core uncovery event, it is unlikely that hydrogen buildup due to a core uncovery could result in an explosive gas mixture in containment.
If all installed hydrogen gas monitors are out-of-service during an event leading to fuel cladding damage, it may not be possible to obtain a containment hydrogen gas concentration reading as ambient conditions within the containment will preclude personnel access.During periods when installed containment hydrogen gas monitors are out-of-service, operators may use the other listed indications to assess whether or not containment is challenged.
tn-EAL #2 Basis.4, tThe 30-minute criterion is tied to a readily recognizable event start time (i.e., the total loss of ability to monitor level), and allows sufficient time to monitor, assess and correlate reactor and plant conditions to determine if core uncovery has actually occurred (i.e., to account for various accident progression and instrumentation uncertainties).
It also allows sufficient time for performance of actions to terminate leakage, recover inventory control/makeup equipment and/or restore level monitoring.
The inability to monitor reactor vessel/RCS level may be caused by instrumentation and/or power failures, or water level dropping below the range of available instrumentation.
If water level cannot be monitored, operators may determine that an inventory loss is occurring by observing changes in sump and/or tank levels. Sump and/or tank level changes must be evaluated against other potential sources of water flow to ensure they are indicative of leakage from the reactor vessel/RCS.
These EALs address concerns raised by Generic Letter 88-17, Loss of Decay Heat Removal; SECY 91-283, Evaluation of Shutdown and Low Power Risk Issues; NUREG-1449, Shutdown and Low-Power Operation at Commercial Nuclear Power Plants in the United States; and NUMARC 91-06, Guidelines for Industry Actions to Assess Shutdown Management.
Basis Reference(s):
: 1. NEI 99-01 Rev 6, CGI 2. BOP PC-I, Containment Closure Tracking Capability
: 3. UFSAR E.17, 6.2, 6.2.5.2.1 4. BOP RH-9 Pump Down of the Refueling Cavity to the RWST 5. BOP RC-4 Reactor Coolant System Drain 6. 1/2 BOSR 0.1-4 Unit One(Two) Mode 4 Shiftly and Daily Operating Surveillance
: 7. 1/2 BOSR RF-1 Unit One(Two) Containment Floor Drain Monitoring System Non-Routine Surveillance
: 8. 0/1/2 BOSR XZB-R1, Unit 0/1/2 Meter Zone Banding Month 20XX BY 3-103 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS
: 9. 1/2 BGP 100-2 Plant Startup 10. BGP 100-6T4 Core Alteration 
/ Fuel Movement Checklist 11. 1/2 BOSR 3.3.1-1 Unit One(Two) Accident Monitoring Instrumentation Monthly Channel Checks 12. 1/2 BFR-C.1, Response to Inadequate Core Cooling Unit 1/2 13. 1/2 BST-5 Containment Unit 1/2 14. NES-G-1 4.02, Calculation No. BYR99-010 
/ BRW-99-0017-1
: 15. EP-EAL-0501, Estimation Of Radiation Monitor Readings Indicating Core Uncovery During Refueling Month 20XX BY 3-104 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear Byron Annex Exelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN I REFUELING SYSTEM MALFUNCTIONS CS641 Initiating Condition:
Loss of reactor vessel/RCS inventory affecting core decay heat removal capability.
Operating Mode Applicability:
5,6 Emergency Action Level (EAL):--Note: The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.
The Emr-.g.ny should dockiro the Site Ahe- Em:erg...ncy exeeeded.1. With CONTAINMENT CLOSURE established EITHER: " RVLIS indicates 0% Plenum OR" Reactor Vessel Refueling Level Indicators LT-046 and LT-049 < 392 ft el.OR 2. With CONTAINMENT CLOSURE not established EITHER:* RVLIS < 15% Plenum OR* Reactor Vessel Refueling Level Indicators LT-046 and LT-049< 393 ft. el.OR 3. a. Reactor Vessel level unknown for >30 minutes.AND b. Core uncovery is indicated by ANY of the following: " Table C3 indications of a sufficient magnitude to indicate core uncovery OR" Erratic Source Range Neutron Monitor indication.
Month 20XX BY 3-105 EP-AA-1002 (Revision) i,.#v (X)_ \ _ w _
* Explon Nticlipar Byron Annex... ............
RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS OR* 1/2 RE-AR011 or 1/2 RE-AR12 Containment Fuel Handling Incident radiation monitors > 3000 mR/hr.Table C3 Indications of RCS Leakage... ..... tUNPIA Malni~i~e 
[rM" lvel rise** UNPLANNED Auxiliary Bldg. Sump level rise*" UNPLANNED Tank (rad waste) level rise** UNPLANNED rise in RCS makeup* Observation of leakage or inventory loss*Rise in level is attributed to a .loss of reactor vessel/RCS inventory.-AND wr %71rC7 OC20 0 M C2 OWK70 Vadl L J#level)-2. -A. C ONT I NM l *eT I i sbhed.k IQ^,&#xfd;,,+~
ii^&#xfd;,,^IIQ e rDIA101 ^r QQX/ rQ1A/CnX 1^%i^1 +knr% /,-;+,m I 6peoGifG eve L' ---'J L " .. ..Jl 3. a. (Reactor voccel!RCS 
[PWR] Or RPV [BRWRI) loVol cannot bo monitored for 30 minutec Or longe.ANM b. Co Unco ' iindicated by ANY of the following:
* Cgite seetite radiation moniator) rzeadln2e feater: tan (site seecifie valuc4 S~I.- rnvrrnl Y 0 Arrafte setroe range monitorfe inflai~eff t1" Month 20XX BY 3-106 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN I REFUELING SYSTEM MALFUNCTIONS
-UNPLANNED incr.eas.
in (site spe.ific sump and/.or tank) l.evels of sufficient maagnitudc to indicate cor-e uncover;" (Other- site speeifie indications)
Basis: CONTAINMENT CLOSURE: The procedurally defined conditions or actions taken to secure containment and its associated structures, systems, and components as a functional barrier to fission product release under shutdown conditions.
UNPLANNED:
A parameter change or an event that is not 1) the result of an intended evolution or 2) an expected plant response to a transient.
The cause of the parameter change or event may be known or unknown.This IC a
and loss of roac-tr inventor; Rnd makeup .apabi.ity lead,,,g to IMMINENT-fuel damag. The lost inventory may be due to a RCS component failure, a loss of configuration control or prolonged boiling of reactor coolant. These conditions entail major failures of plant functions needed for protection of the public and thus warrant a Site Area Emergency declaration.
Following an extended loss of core decay heat removal and inventory makeup, decay heat will cause reactor coolant boiling and a further reduction in reactor vessel level. If RCS/reactor vessel level cannot be restored, fuel damage is probable.Outage/shutdown contingency plans typically provide for re-establishing or verifying CONTAINMENT CLOSURE following a loss of heat removal or RCS inventory control functions.
The diffo....co in the Spocified RCSlroAcr verseo leyIl... of RAI 1 I.b anld 2.b rofloct thA facr-t that 4 sotih COCINITAINMIENT CLO E Ir -establishl-ed, theFe is a lower Ip. b .... y of a fission product reeloarco ton the en;Vironmen~t.
..-EAL--3Ta.-tThe 30-minute criterion is tied to a readily recognizable event start time (i.e., the total loss of ability to monitor level), and allows sufficient time to monitor, assess and correlate reactor and plant conditions to determine if core uncovery has actually occurred (i.e., to account for various accident progression and instrumentation uncertainties).
It also allows sufficient time for performance of actions to terminate leakage, recover inventory control/makeup equipment and/or restore level monitoring.
The inability to monitor reactor vessel/RCS level may be caused by instrumentation and/or power failures, or water level dropping below the range of available instrumentation.
If water level cannot be monitored, operators may determine that an inventory loss is occurring by observing changes in sump and/or tank levels. Sump and/or tank level changes must be evaluated against other potential sources of water flow to ensure they are indicative of leakage from the reactor vessel/RCS.
These EALs address concerns raised by Generic Letter 88-17, Loss of Decay Heat Removal; SECY 91-283, Evaluation of Shutdown and Low Power Risk Issues; NUREG-1449, Shutdown and Low-Power Operation at Commercial Nuclear Power Plants in the Month 20XX BY 3-107 EP-AA-1002 (Revision XX)
R ren Anng%,w P-enlnn Ih1i irla-nr RECOGNITION CATEGORY COLD SHUTDOWN I REFUELING SYSTEM MALFUNCTIONS United States; and NUMARC 91-06, Guidelines for Industry Actions to Assess Shutdown Management.
Escalation of the emergency classification level would be via IC CG46 or ARG1.Basis Reference(s):
: 1. NEI 99-01 Rev 6, CS1 2. UFSAR E.17, 6.2 3. BOP RH-9 Pump Down of the Refueling Cavity to the RWST 4. BOP RC-4 Reactor Coolant System Drain 5. 1/2 BOSR 0.1-4 Unit One (Two) Mode 4 Shiftly and Daily Operating Surveillance
: 6. 1/2 BOSR RF-1 Unit One (Two) Containment Floor Drain Monitoring System Non-Routine Surveillance
: 7. 0/1/2 BOSR XZB-R1, Unit 0/1/2 Meter Zone Banding 8. 1/2 BGP 100-2 Plant Startup 9. BGP 100-6T4 Core Alteration 
/ Fuel Movement Checklist 10. 1/2 BOSR 3.3.1-1 Unit One (Two) Accident Monitoring Instrumentation Monthly Channel Checks Month 20XX BY 3-108 EP-AA-1002 (Revision XX)
Rrnn AnnoY P:valrnn Nhme-laor RurnVI AnlIII IVolrlk RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CA64 I Initiating Condition:
Loss of reactor vessel/RCS inventory.
Operating Mode Applicability:
5,6 Emergency Action Level (EAL): Note: The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.
The Cw~fr~ier~nr-i 1 A  4 rnrrmr'.tl,,a 
,,r~rn rltrmnn th-at '--* l- A J -- ....I"1 I!1 L=. -=miinutu IT JL UUUI] PR G~UUU Ra&m"A A il IlleV Dei IXGliusli.
: 1. a. Loss of reactor vessel / RCS inventory as indicated RVLIS < 37% Plenum.OR b. Loss of reactor vessel / RSC inventory as indicated by LT-046 and LT-049< 393.5 ft. el.OR 2. a. Reactor vessel / RCS level unknown for > 15 minutes.AND b. Loss of reactor vessel / RCS inventory per Table C3 indications.
Table C3 Indications of RCS Leakage" UNPLANNED Containment Sump level rise** UNPLANNED Auxiliary Bldg. Sump level rise** UNPLANNED Tank (rad waste) level rise** UNPLANNED rise in RCS makeup* Observation of leakage or inventory loss*Rise in level is attributed to a loss of reactor vessel/RCS inventory.
Month 20XX BY 3-109 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN I REFUELING SYSTEM MALFUNCTIONS
: 1. 1Loss Of reactor vossel/RCS inVontory as indiratod by levol loss than (site SPecificG 2. a. Reactor vosselIRCS level cannot bomonitored for 15 minu tes, or longer AND b-. UNIPllNlIN llr-Ic ;nr-oase ;n (site specific sump a-ndor tank) levehls due toe a loss of reactor ose66l1RCS inventor;-.
Basis: UNPLANNED:
A parameter change or an event that is not 1) the result of an intended evolution or 2) an expected plant response to a transient.
The cause of the parameter change or event may be known or unknown.-.This IC addresses conditions that are precursors to a loss of the ability to adequately cool irradiated fuel (i.e., a precursor to a challenge to the fuel clad barrier).This condition represents a potential substantial reduction in the level of plant safety.F-r-EAL #1 BasisT aA lowering of water level below indicated RVLIS < 37% Plenum or LT-046 and LT-049 indicating 
< 393.5 ft. el. (site specific lev.e.l) indicates that operator actions have not been successful in restoring and maintaining reactor vessel/RCS water level. The heat-up rate of the coolant will ieieaserse as the available water inventory is reduced. A continuing deefeaee-drop in water level will lead to core uncovery.Although related, EAL #1 is concerned with the loss of RCS inventory and not the potential concurrent effects on systems needed for decay heat removal (e.g., loss of a Residual Heat Removal suction point). APR iGeeaserise in RCS temperature caused by a loss of decay heat removal capability is evaluated under IC CA53.FGr--EAL #2 Basis ,-4The inability to monitor reactor vessel/RCS level may be caused by instrumentation and/or power failures, or water level dropping below the range of available instrumentation.
If water level cannot be monitored, operators may determine that an inventory loss is occurring by observing changes in sump and/or tank levels. Sump and/or tank level changes must be evaluated against other potential sources of water flow to ensure they are indicative of leakage from the reactor vessel/RCS.
Month 20XX BY 3-110 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN I REFUELING SYSTEM MALFUNCTIONS The 15-minute duration for the loss of level indication was chosen because it is half of the EAL duration specified in IC CS64-If the reactor vessel/RCS inventory level continues to lower, then escalation to Site Area Emergency would be via IC CS61-.Basis Reference(s):
: 1. NEI 99-01 Rev 6, CA1 2. UFSAR 6.2 & E.17 3. 1/2 BOSR 0.1-4 Unit One(Two) Mode 4 Shiftly and Daily Operating Surveillance
: 4. 1/2 BOSR RF-1 Unit One(Two) Containment Floor Drain Monitoring System Non-Routine Surveillance
: 5. 0/1/2 BOSR XZB-R1, Unit 0/1/2 Meter Zone Banding 6. BOP RH-9 Pump Down of the Refueling Cavity to the RWST 7. BOP RC-4 Reactor Coolant System Drain Month 20XX BY 3-111 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CU64-1 Initiating Condition:
UNPLANNED loss of reactor vessel/RCS inventory for 15 minutes or longer.Operating Mode Applicability:
5,6 Emergency Action Level (EAL): Note:-The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.
T-he-pr -kf r U14 I. .. 0'Q U.... .....- n. ra m f! *V-1.v I q tl tf i t),l mi nue i11 eR elsatiiti i AF11v.l WI 1%ilIIl Ow EIX WV00"EI.I 1. UNPLANNED loss of reactor coolant results in the inability to restore and maintain reactor vessel / RCS level to > procedurally established lower limit for> 15 minutes.OR 2. a. Reactor vessel / RCS level unknown AND b. Loss of reactor vessel / RCS inventory per Table C3 indications.
41-Table C3 Indications of RCS Leakage* UNPLANNED Containment Sump level rise** UNPLANNED Auxiliary Bldg. Sump level rise** UNPLANNED Tank (rad waste) level rise** UNPLANNED rise in RCS makeup* Observation of leakage or inventory loss*Rise in level is attributed to a loss of reactor vessel/RCS inventory.
--
I .... I I------ il .....WrNPLANNED iO.s eT reactor cooiant rS in reacAor es oif G2. level less !Ran a ropird lowor lim~it forF 15 minutesO 1or oQ8F.*2. ,wvv a. Racto '.occo!Rv lovol cannot bo, molnitorodlv..
AND Month 20XX BY 3-112 EP-AA-1002 (Revision XX)
Rvron Annex ExAIon NuclAar Bvron Annex Exelon Nuceia~r RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS bh. UNPL'\NNIED onc-reamse in (sito SPocifi cumAp andlor tank) levels.Basis: UNPLANNED:
A parameter change or an event that is not 1) the result of an intended evolution or 2) an expected plant response to a transient.
The cause of the parameter change or event may be known or unknown.This IC addresses the inability to restore and maintain water level to a required minimum level (or the lower limit of a level band), or a loss of the ability to monitor reactor vessel/RCS level concurrent with indications of coolant leakage. Either of these conditions is considered to be a potential degradation of the level of safety of the plant.Refueling evolutions that decrease RCS water inventory are carefully planned and controlled.
An UNPLANNED event that results in water level decreasing below a procedurally required limit warrants the declaration of an Unusual Event due to the reduced water inventory that is available to keep the core covered.EAL #1 Basis fRecognizes that the minimum required reactor vessel/RCS level can change several times during the course of a refueling outage as different plant configurations and system lineups are implemented.
This -AL-Threshold is met if the minimum level, specified for the current plant conditions, cannot be maintained for 15 minutes or longer.The minimum level is typically specified in the applicable operating procedure but may be specified in another controlling document.The procedurally established lower limit is not an operational band established above the procedural limit to allow for operator action prior to exceeding the procedural limit, but it is the procedurally established lower limit.The 15-minute threshold duration allows sufficient time for prompt operator actions to restore and maintain the expected water level. This criterion excludes transient conditions causing a brief lowering of water level.EAL #2 Basis aAddresses a condition where all means to determine reactor vessel/RCS level have been lost. In this condition, operators may determine that an inventory loss is occurring by observing changes in sump and/or tank levels. Sump and/or tank level changes must be evaluated against other potential sources of water flow to ensure they are indicative of leakage from the reactor vessel/RCS.
Continued loss of RCS inventory may result in escalation to the Alert emergency classification level via either IC CA61- or CA53.Month 20XX BY 3-113 EP-AA-1002 (Revision XX)
Bvron  Byron Annex Exlon Nuclea.r RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS Basis Reference(s):
: 1. NEI 99-01, Rev. 6 CU1 2. UFSAR 6.2 & E.17 3. I/2BOSR 0.1-4 Unit One (Two) Modes 4 Shiftly and Daily Operating Surveillance
: 4. 1/2BOS RF-1 Unit One (Two) Containment Floor Drain Monitoring System Non-Routine Surveillance
: 5. 0/1/2 BOS XZB-R1 Unit 0/1/2 MCR Meter Zone Banding 6. BOP RH-9 Pump Down of the Reactor Cavity to the RWSTs 7. BOP RC-4 Reactor Coolant System Drain Month 20XX BY 3-114 EP-AA-1002 (Revision XX)
Rrnn AnnovY I::alnn NFPelnr Aun nvFvInMu~~
RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HG1 Initiating Condition:
HOSTILE ACTION resulting in loss of physical control of the facility.Operating Mode Applicability:
1, 2, 3, 4, 5, 6, D Emergency Action Level (EAL): 1. A notification from the Security Force that a HOSTILE ACTION is occurring or has occurred within the PROTECTED AREA.AND 2. a. ANY Table H1 safety function cannot be controlled or maintained.
OR b. Damage to spent fuel has occurred or is IMMINENT Table H1 -Safety Functions" Reactivity Control(ability to shut down the reactor and keep it shutdown)" Core Cooling (ability to cool the core)* RCS Heat Removal (ability to maintain heat sink)a. A. ACION i. 9ocurring orha,,. occurred within thePROTECTE AREA as reportod by the (site specifc 6ocurity Shiftsueiio.
AND b. EITHER of the feollwing has occurr.d, I. AN oI f the fello~Aing saft* functions caannot be controlledo" Reactivity eontfel" RCS heat r-emcval OR 2. Damaae to ..+ .nt fuel has oc-. .crrod or i IMMINENT.Month 20XX BY 3-115 EP-AA-1002 (Revision XX)
Rrnn Anna-z I~v--Ionn kiirl-anr RJrnAnvFw'LnM~~~
RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY Basis: HOSTILE ACTION: An act toward a NPP or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, PROJECTILEs, vehicles, or other devices used to deliver destructive force. Other acts that satisfy the overall intent may be included.
HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on the NPP. Non-terrorism-based EALs should be used to address such activities (i.e., this may include violent acts between individuals in the owner controlled area).HOSTAGE: A person(s) held as leverage against the station to ensure that demands will be met by the station.PROJECTILE:
An object directed toward a NPP that could cause concern for its continued operability, reliability, or personnel safety.PROTECTED AREA: An area that normally encompasses all controlled areas within the security protected area fence.IMMINENT:
The trajectory of events or conditions is such that an EAL will be met within a relatively short period of time regardless of mitigation or corrective actions.HOSTILE FORCE: Any individuals who are engaged in a determined assault, overtly or by stealth and deception, equipped with suitable weapons capable of killing, maiming, or causing destruction.
This IC addresses an event in which a HOSTILE FORCE has taken physical control of the facility to the extent that the plant staff can no longer operate equipment necessary to maintain key safety functions.
It also addresses a HOSTILE ACTION leading to a loss of physical control that results in actual or IMMINENT damage to spent fuel due to 1) damage to a spent fuel pool cooling system (e.g., pumps, heat exchangers, controls, etc.) or, 2) loss of spent fuel pool integrity such that sufficient water level cannot be maintained.
Timely and accurate communications between Security Shift Supervision and the Control Room is essential for proper classification of a security-related event.Security plans and terminology are based on the guidance provided by NEI 03-12, Template for the Security Plan, Training and Qualification Plan, Safeguards Contingency Plan [and Independent Spent Fuel Storage Installation Security Program].Emergency plans and implemeting procedures are public documents; theFrf-ro, EA's should not incorporateA Scr-AG3-ity sensitiVe inomto.This includes, informnation that mnay be Idvanageos to a potential adversary, such as the partiGUlars concernn specific throat Or thrcat location.
Security sensitive information should be Month 20XX BY 3-116 EP-AA-1002 (Revision XX)
Rrnn AnnovY I::alnn hi~r-lonr.,..l.S., A- nll F v lI I IrtIVI ar RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY contained on non pub,,l documents , uch a, the Scurit',' Basis Reference(s):
: 1. NEI 99-01, Rev. 6 HGI 5. Station Security Plan -Appendix C Month 20XX BY 3-117 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HSI Initiating Condition:
HOSTILE ACTION within the PROTECTED AREA.Operating Mode Applicability:
1,2,3,4,5,6, D Emergency Action Level (EAL): A notification from the Security Force that a HOSTILE ACTION is occurring or has occurred within the PROTECTED AREA.1. A HOSTILE ACTION' isAG ocring Or has occurrod within tho PROTECTED AREA as rcportod by the (site sepoific socurity shift supcriision)..Basis: HOSTILE ACTION: An act toward a NPP or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, PROJECTILEs, vehicles, or other devices used to deliver destructive force. Other acts that satisfy the overall intent may be included.
HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on the NPP. Non-terrorism-based EALs should be used to address such activities (i.e., this may include violent acts between individuals in the owner controlled area).HOSTAGE: A person(s) held as leverage against the station to ensure that demands will be met by the station.PROJECTILE:
An object directed toward a NPP that could cause concern for its continued operability, reliability, or personnel safety.PROTECTED AREA: An area that normally encompasses all controlled areas within the security protected area fence.HOSTILE FORCE: Any individuals who are engaged in a determined assault, overtly or by stealth and deception, equipped with suitable weapons capable of killing, maiming, or causing destruction.
INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI): A complex that is designed and constructed for the interim storage of spent nuclear fuel and other radioactive materials associated with spent fuel storage.This IC addresses the occurrence of a HOSTILE ACTION within the PROTECTED AREA. This event will require rapid response and assistance due to the possibility for damage to plant equipment.
Timely and accurate communications between Security Shift Supervision and the Control Room is essential for proper classification of a security-related event.Month 20XX BY 3-118 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY Security plans and terminology are based on the guidance provided by NEI 03-12, Template for the Security Plan, Training and Qualification Plan, Safeguards Contingency Plan [and Independent Spent Fuel Storage Installation Security Program].As time and conditions allow, these events require a heightened state of readiness by the plant staff and implementation of onsite protective measures (e.g., evacuation, dispersal or sheltering).
The Site Area Emergency declaration will mobilize ORO resources and have them available to develop and implement public protective actions in the unlikely event that the attack is successful in impairing multiple safety functions.
This IC does not apply to a HOSTILE ACTION directed at an ISFSI PROTECTED AREA located outside the plant PROTECTED AREA; such an attack should be assessed using IC HA1. It also does not apply to incidents that are accidental events, acts of civil disobedience, or otherwise are not a HOSTILE ACTION perpetrated by a HOSTILE FORCE. Examples include the crash of a small aircraft, shots from hunters, physical disputes between employees, etc. Reporting of these types of events is adequately addressed by other EALs, or the requirements of 10 CFR &sect; 73.71 or 10 CFR&sect; 50.72.Emergoncy plans and iMplomontin a...pbli thoroforo, EALs Should10 not incorpor9ate Socr-Wity sensiti'.'
information.
This ~nldsifrainthat mnay be advantageous, to a poten-ti-al -d-Vorsar',, such as tho partic-JulaS cocrnig SpocdfiG throat Or throat !ocatien.
Security sonsitivo infomation should bo contAn~od 
;A non PUbliG docGumonts euch as the Security Plan.Escalation of the emergency classification level would be via IC HG1.Basis Reference(s):
: 1. NEI 99-01 Rev 6, HS1 3. Station Security Plan -Appendix C Month 20XX BY 3-11lg EP-AA-1002 (Revision XX) irturnn Ann--v 1=,%rg%1#%n N"r-la!mr A~r~ nnv~~vnN..~a RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HAI Initiating Condition:
HOSTILE ACTION within the OWNER CONTROLLED AREA or airborne attack threat within 30 minutes.Operating Mode Applicability:
1, 2, 3, 4, 5, 6, D Emergency Action Level (EAL): 1. A validated notification from NRC of an aircraft attack threat < 30 minutes from the site.1 A HOS-08TILE ACTION is or- has occurred within the OWNER OR 2. Notification by the Security Force that a HOSTILE ACTION is occurring or has occurred within the OWNER CONTROLED AREA.A v.'alidated no;tificatin from NR, of an attack within 30 minut, , t Basis: HOSTILE ACTION: An act toward a NPP or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, PROJECTILEs, vehicles, or other devices used to deliver destructive force. Other acts that satisfy the overall intent may be included.
HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on the NPP. Non-terrorism-based EALs should be used to address such activities (i.e., this may include violent acts between individuals in the owner controlled area).HOSTAGE: A person(s) held as leverage against the station to ensure that demands will be met by the station.PROJECTILE:
An object directed toward a NPP that could cause concern for its continued operability, reliability, or personnel safety.OWNER CONTROLLED AREA (OCA): The property associated with the station and owned by the company. Access is normally limited to persons entering for official business.Month 20XX BY 3-120 EP-AA-1002 (Revision XX)
Rrnn Annia-I:,vg,1lnn hiirlatar ZrVil A in v l~ll ll.~-Ia
* U Sil RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY PROTECTED AREA: An area that normally encompasses all controlled areas within the security protected area fence.HOSTILE FORCE: Any individuals who are engaged in a determined assault, overtly or by stealth and deception, equipped with suitable weapons capable of killing, maiming, or causing destruction.
This IC addresses the occurrence of a HOSTILE ACTION within the OWNER CONTROLLED AREA or notification of an aircraft attack threat. This event will require rapid response and assistance due to the possibility of the attack progressing to the PROTECTED AREA, or the need to prepare the plant and staff for a potential aircraft impact.Timely and accurate communications between Security Shift Supervision and the Control Room is essential for proper classification of a security-related event.Security plans and terminology are based on the guidance provided by NEI 03-12, Template for the Security Plan, Training and Qualification Plan, Safeguards Contingency Plan [and Independent Spent Fuel Storage Installation Security Program].As time and conditions allow, these events require a heightened state of readiness by the plant staff and implementation of onsite protective measures (e.g., evacuation, dispersal or sheltering).
The Alert declaration will also heighten the awareness of Offsite Response Organizations, allowing them to be better prepared should it be necessary to consider further actions.This IC does not apply to incidents that are accidental events, acts of civil disobedience, or otherwise are not a HOSTILE ACTION perpetrated by a HOSTILE FORCE.Examples include the crash of a small aircraft, shots from hunters, physical disputes between employees, etc. Reporting of these types of events is adequately addressed by other EALs, or the requirements of 10 CFR &sect; 73.71 or 10 CFR &sect; 50.72.EAL #1 addresses the threat from the impact of an aircraft on the plant, and the anticipated arrival time is within 30 minutes. The intent of this EAL is to ensure that threat-related notifications are made in a timely manner so that plant personnel and OROs are in a heightened state of readiness.
This EAL is met when the threat-related information has been validated in accordance with OBOA Security-I, Security Threat.EAL #24- is applicable for any HOSTILE ACTION occurring, or that has occurred, in the OWNER CONTROLLED AREA. This includes any action directed against an ISFSI that is located outside the plant PROTECTED AREA.&AIL 02 addroccoc, tho t-hroat- from t-hompc of an aircraft On the plant, and the anticipatod arrival tome *6 within 30 minutoc. Tho *Rtont of this EAL= is to onSUro that.throat rolatod notifications aro mnado in a timely mnanore 6o that plant porsennol and O-ROc ro ;4ina hoightoAno-d s-ta-t~e ofreadiness.
This EAL ir, mot when the throat rolated informationA haS boon. -aidtod in accordance with (site epocific perocdure).
Month 20XX BY 3-121 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY The NRC Headquarters Operations Officer (HOO) will communicate to the licensee if the threat involves an aircraft.
The status and size of the plane may be provided by NORAD through the NRC.In some cases, it may not be readily apparent if an aircraft impact within the OWNER CONTROLLED AREA was intentional (i.e., a HOSTILE ACTION). It is expected, although not certain, that notification by an appropriate Federal agency to the site would clarify this point. In this case, the appropriate federal agency is intended to be NORAD, FBI, FAA or NRC. The emergency declaration, including one based on other ICs/EALs, should not be unduly delayed while awaiting notification by a Federal agency.EmoR8gonc';
plans and imlmnigprOcoduros aro public. docUmon~ts; thoroforo, EAI~s should- not incorpor-atok Soc-urity sonsitivoifomtin This inldcifrainthat ma" be to a pI 1tial advorsary, SUch as the parFt1icuIlars clcrning a sepoiG throeat or throat location.
SocurIFty sonsitiVo inform:ation Should 19o contained i non public documonts such as tho Socurity Plan.Escalation of the emergency classification level would be via IC HSI.Basis Reference(s):
1 .NEI 99-01 Rev 6, HAI 2. SY-AA-1 01-1 32, Security Assessment and Response to Unusual Activities
: 3. Station Security Plan -Appendix C 4. OBOA Security-i, Security Threat Unit 0 Month 20XX BY 3-122 EP-AA-1002 (Revision XX)
Rrnn Annoy I=Yalnn Nkwlan:r Ru nJvFLn Ma~~a RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HUI Initiating Condition:
Confirmed SECURITY CONDITION or threat.Operating Mode Applicability:
1, 2,3,4,5,6, D Emergency Action Level (EAL): 1. Notification of a credible security threat directed at the site as determined per SY-AA-101-132, Security Assessment and Response to Unusual Activities.
: 1. A SECURITY CONDITION that does not in'.'lye a HO0STILE ACTION as Fepefted by the (site specific security shift super-vision).
OR 2. A validated notification from the NRC providing information of an aircraft threat.2. Notification of a .r.edible security teat di.ected at the site.OR 3. Notification by the Security Force of a SECURITY CONDITION that does not involve a HOSTILE ACTION.3. A validated notification from the NRC proViding information of an aircraft throat.Basis: SECURITY CONDITION:
Any Security Event as listed in the approved security contingency plan that constitutes a threat/compromise to site security, threat/risk to site personnel, or a potential degradation to the level of safety of the plant. A SECURITY CONDITION does not involve a HOSTILE ACTION SAFETY SYSTEM: A system required for safe plant operation, cooling down the plant and/or placing it in the cold shutdown condition, including the ECCS. These are typically systems classified as safety-related.
HOSTILE ACTION: An act toward a NPP or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, PROJECTILEs, vehicles, or other devices used to deliver destructive force. Other acts that satisfy the overall intent may be included.
HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on the NPP. Non-terrorism-based EALs should be used to address such activities (i.e., this may include violent acts between individuals in the owner controlled area).HOSTAGE: A person(s) held as leverage against the station to ensure that demands will be met by the station.Month 20XX BY 3-123 EP-AA-1002 (Revision XX)
R ro~n A nna-v I::vg~l&,n Ndil,-nr-** J f L ~RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY PROJECTILE:
An object directed toward a NPP that could cause concern for its continued operability, reliability, or personnel safety.This IC addresses events that pose a threat to plant personnel or SAFETY SYSTEM equipment, and thus represent a potential degradation in the level of plant safety.Security events which do not meet one of these EALs are adequately addressed by the requirements of 10 CFR &sect; 73.71 or 10 CFR &sect; 50.72. Security events assessed as HOSTILE ACTIONS are classifiable under ICs HA1, HS1 and HGI.Timely and accurate communications between Security Shift Supervision and the Control Room is essential for proper classification of a security-related event.Classification of these events will initiate appropriate threat-related notifications to plant personnel and OROs.Security plans and terminology are based on the guidance provided by NEI 03-12, Template for the Security Plan, Training and Qualification Plan, Safeguards Contingency Plan [and Independent Spent Fuel Storage Installation Security Program].EAL #1 addresses the receipt of a credible security threat. The credibility of the threat is assessed in accordance with SY-AA-1 01-1 (site SpG.fi secGurit, shi.ft.uperiin) bocausoe thesee aaro the ind-Wdduals-trainoed toe conRFAr that. -a security ovont iS occurring or haS occu-rred.
TrInin onseurty oVont confirmAtion and asicaons controlled duo-l to tho_ naturo of Safeguards-ainid 
: 1. 0 CFR &sect; 2.39 infoFrmation.
EAL #2 addresses the threat from the impact of an aircraft on the plant. The NRC Headquarters Operations Officer (HOO) will communicate to the licensee if the threat involves an aircraft.
The status and size of the plane may also be provided by NORAD through the NRC. Validation of the threat is performed in accordance with OBOA Security-1, Security Threat(.it.
specific the rec.ipt of a credible security threat. The credibility of the threat is assessed in aor.dance with (site specific PFGGedu~e)-
EAL #3 references Security Force(sit.
specific scurity shift supe..isiO.) -because these are the individuals trained to confirm that a security event is occurring or has occurred.
Training on security event confirmation and classification is controlled due to the nature of Safeguards and 10 CFR &sect; 2.39 information.addresses the threat from the impact of an aircraft on the plant. The NRC Headquarters Operations Officer (HOO) will communicate to the licensee if the threat involves an aircraft.
The status and size of the plane may also be provided by NORAD through the NRC. Validation of the threat is performed in accordance with (site-specific procedure).
Emergency plans and procedures are pUblic docum.ents; E=AL^n rshould noRnopraeScrt SeRSitie information.
This inldsifrainthat mnay be advantageo ntial adver-sa-, such as the particul asoerne,,ing a speci. Secuty sshould be contained in non public documnents suha h euiyPlan.Month 20XX BY 3-124 EP-AA-1002 (Revision XX)
Exalon Nuclear B-ron Annex........N..
l...RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY Escalation of the emergency classification level would be via IC HA1.Basis Reference(s):
: 1. NEI 99-01 Rev 6, HU1 2. SY-AA-101-132, Security Assessment and Response to Unusual Activities
: 3. Station Security Plan -Appendix C 4. NRC Safeguards Advisory 10/6/01 5. Letter from Mr. B. A. Boger (NRC) to Ms. Lynette Hendricks (NEI) dated 2/4/02 6. 0BOA Security-I, Security Threat Unit 0 Month 20XX BY 3-125 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HS26 Initiating Condition:
Inability to control a key safety function from outside the Control Room.Operating Mode Applicability:
1, 2, 3, 4, 5, 6, D Emergency Action Level (EAL): Note: The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded. ..F' eGy DirFeGtor should dla-r the Site Aroa rEmoeronyvont promptly up.n determining that (site Spocifc Runubor of mninutes) has boon oxco'eedod, Or will likely be xceeodod.1. A Control Room evacuation has resulted in plant control being transferred from the Control Room to alternate locations per 1/213OA PRI-5, Control Room Inaccessibility.
AND 2. Control of ANY Table HI key safety function is not reestablished in < 15 minutes.Table HI -Safety Functions* Reactivity Control(ability to shut down the reactor and keep it shutdown)" Core Cooling (ability to cool the core)" RCS Heat Removal (ability to maintain heat sink)1 .a. An eyent has resulted in plant control being transferred panels and local coentrol1 stations).
from the Control Room to (site specifc remote shutdon b. Control of ANY of the folloWing key saf*~ functions is not reestablished WAithin (site specific number Of minute)." Reactivty G9ntrot" Core cooling [P WR] I RPV wAator level [BWRJ* RCS heat remo~val Month 20XX BY 3-126 EP-AA-1002 (Revision XX)
Rrfnn Anniav P:valenn klirla-nr f liM --llv Fv.Irv, n i arwadr RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY Basis: The time period to establish control of the plant starts when either: a. Control of the plant is no longer maintained in the Main Control Room OR b. The last Operator has left the Main Control Room.This IC addresses an evacuation of the Control Room that results in transfer of plant control to alternate locations, and the control of a key safety function cannot be reestablished in a timely manner. The failure to gain control of a key safety function following a transfer of plan control to alternate locations is a precursor to a challenge to Gon Or morany fission product barriers within a relatively short period of time.The determination of whether or not "control" is established at the remote safe shutdown location(s) is based on Emergency Director judgment.
The Emergency time fnr trneg 15 minutes whether or not the operating staff has control of key safety functions from the remote safe shutdown location(s).
Escalation of the emergency classification level would be via IC FG1 or CG64-.Basis Reference(s):
: 1. NEI 99-01, Rev 6 HS6 2. 1/2BOA PRI-5, Control Room Inaccessibility Unit 1/2 Month 20XX BY 3-127 EP-AA-1002 (Revision XX) 
-rnn Anna*Fvalnn N~tlonr~l_
RJrnAnL vIn mrI~RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HA261 Initiating Condition:
Control Room evacuation resulting in transfer of plant control to alternate locations.
Operating Mode Applicability:
1,2,3, 4,5,6, D Emergency Action Level (EAL): A Control Room evacuation has resulted in plant control being transferred from the Control Room to alternate locations per 1/2BOA PRI-5, Control Room Inaccessibility.
An oVont has rosultod in plant conrol1 being transferrod fromn the Control Room to (site specific roMOto shutdown panels and local control stations).
Basis: This IC addresses an evacuation of the Control Room that results in transfer of plant control to alternate locations outside the Control Room. The loss of the ability to control the plant from the Control Room is considered to be a potential substantial degradation in the level of plant safety.Following a Control Room evacuation, control of the plant will be transferred to alternate shutdown locations.
The necessity to control a plant shutdown from outside the Control Room, in addition to responding to the event that required the evacuation of the Control Room, will present challenges to plant operators and other on-shift personnel.
Activation of the ERO and emergency response facilities will assist in responding to these challenges.
Escalation of the emergency classification level would be via IC HS26.I Basis Reference(s):
: 1. NEI 99-01, Rev 6 HA6 2. 1/2BOA PRI-5, Control Room Inaccessibility Unit 1/2 Month 20XX BY 3-128 EP-AA-1002 (Revision XX)
Rvrnn Annoy Fwi:llnn NHIrlIar Rvrnn Anncw F~~Inn Niir~Ia~mr RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HU34 Initiating Condition:
FIRE potentially degrading the level of safety of the plant.Operating Mode Applicability:
1,2,3,4,5,6, D Emergency Action Level (EAL): Note: The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.
The. - Director should delare the Unusual Event promptly upon determining that e .De I I Ji I I v appi~able uimo has been eXceepop.
Or Will !!KeIV De oXcoeepop.
: 1. A FIRE in any Table H2 area is not extinguished in < 15-minutes of ANY of the following FIRE detection indications:
0 0 0 Report from the field (i.e., visual observation)
Receipt of multiple (more than 1) fire alarms or indications Field verification of a single fire alarm Table H2 -Vital Areas" Containment
* Auxiliary Building* Fuel Handling Building* Main Steam Tunnels* RWST's* Condensate Storage Tanks" Essential Service Water Cooling Towers 2.OR a. Receipt of a single fire alarm in any Table H2 area (i.e., no other indications of a FIRE).AND b. The existence of a FIRE is not verified in < 30 minutes of alarm receipt.OR Month 20XX BY 3-129 EP-AA-1002 (Revision XX)
Rvron Annex Exalon Nuclear Rvron AnnexEelnNula RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY 3 A FIRE within the plant PROTECTED AREA not extinguished in < 60-minutes of the initial report, alarm or indication.
OR 4 A FIRE within the plant PROTECTED AREA that requires firefighting support by an offsite fire response agency to extinguish.
(1) a. A FIRE is NOT extinguished within 15 minutes of ANY of the fG!!oWing FIRE detection idctos I a Ponort frnm thn fiAld (i A ~A~'i~I nhRnr'..'itinn~
e Rqe- ftmtefel -e,~ale~ ai v A C '. 1.4 ;A I A iI IEV VI II IV 0 a -eur- t7at "" " a 0 "M a ra C2 arr" AND TkaoID ;~ i + A ;+Ak;- ALIV af fh faIau1 , +~r~0. WtI V Tr *I W VS 11 I 10 trwr HUT p dr.i 1 U1 1b I!---f I!--L --t I L ....... \Isk spr-1in -.t o .p -a r-.mr e ----I'-. .. -I F" ...................
Im I I 0 I I IQ II (21 a. ReroAiat of a s*nalo tire alarm fi.e.. no ot~e no aications of a FIRE.\--I A N i iIIm F dI f II D I J no The I= is ioMated WItnin AN* of the Toliowing piant rooms or areas (Site specific 46t Of plant rooms Or area&)A.ND-L.. 2.1 G. The~ emxCWR~ r, a ofa IRE is. not vYruiuue withmI am nirnu-t.s of ala~n Iii u7upt ffitm ?na nman ri M40,1 ZSaod zrn flzfflTC -4I~1O S r%V1* i,... wl .-ll ,l. -.i , v
* rL r J,, j writ,, IV V5 t r 5
* S P arteted-- 
'Ar] PROTECTED AREA not extinguished within 60 mninutes, of the initial' roort. alarm or indication.
IAN A MIOM .pA+hir +km 1pln+ ^r IQ4:4I rfar qn~anc dfiAJ Qn I.Qr=QI nji,,#cigl thig nIf 3'L-4j tt5S~S5L~
l.S5U~.. '\1/Prtotetd Areal PRO TE-CTED AR.EA that requires firofighting support by an I V v I I A A: A.... .... uiIfen Wer rutjpuitWu 1b UII Lu I AI~y~Month 20XX BY 3-130 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY Basis: FIRE: Combustion characterized by heat and light. Sources of smoke such as slipping drive belts or overheated electrical equipment do not constitute FIRES. Observation of flame is preferred but is NOT required if large quantities of smoke and heat are observed.PROTECTED AREA: An area that normally encompasses all controlled areas within the security protected area fence.This IC addresses the magnitude and extent of FIRES that may be indicative of a potential degradation of the level of safety of the plant.EAL #1 Basis The intent of the 15-minute duration is to size the FIRE and to discriminate against small FIRES that are readily extinguished (e.g., smoldering waste paper basket). In addition to alarms, other indications of a FIRE could be a drop in fire main pressure, automatic activation of a suppression system, etc.Upon receipt, operators will take prompt actions to confirm the validity of an initial fire alarm, indication, or report. For EAL assessment purposes, the emergency declaration clock starts at the time that the initial alarm, indication, or report was received, and not the time that a subsequent verification action was performed.
Similarly, the fire duration clock also starts at the time of receipt of the initial alarms, indication or report.EAL #2 Basis This EAL addresses receipt of a single fire alarm, and the existence of a FIRE is not verified (i.e., proved or disproved) within 30-minutes of the alarm. Upon receipt, operators will take prompt actions to confirm the validity of a single fire alarm. For EAL assessment purposes, the 30-minute clock starts at the time that the initial alarm was received, and not the time that a subsequent verification action was performed.
A single fire alarm, absent other indication(s) of a FIRE, may be indicative of equipment failure or a spurious activation, and not an actual FIRE. For this reason, additional time is allowed to verify the validity of the alarm. The 30-minute period is a reasonable amount of time to determine if an actual FIRE exists; however, after that time, and absent information to the contrary, it is assumed that an actual FIRE is in progress.If an actual FIRE is verified by a report from the field, then EAL #1 is immediately applicable, and the emergency must be declared if the FIRE is not extinguished within 15-minutes of the report. If the alarm is verified to be due to an equipment failure or a spurious activation, and this verification occurs within 30-minutes of the receipt of the alarm, then this EAL is not applicable and no emergency declaration is warranted.
Month 20XX BY 3-131 EP-AA-1002 (Revision XX)
R rnn A nn,-v I::v,-Inn N.hil--or RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY EAL #3 Basis In addition to a FIRE addressed by EAL #1 or EAL #2, a FIRE within the plant PROTECTED AREA not extinguished within 60-minutes may also potentially degrade the level of plant safety. This extends to a FIRE cecurring within the PROTECTED AR..A of an ISFSI lecated ,utide the plant PROTECTED AREA.[Sentence for- plants %At an ISF-SI eutsidc the plant Protected Area]EAL #4 Basis If a FIRE within the plant OF 1SES, [for plants with an ISESI otside the plant P-otecte, Areal-PROTECTED AREA is of sufficient size to require a response by an offsite firefighting agency (e.g., a local town Fire Department), then the level of plant safety is potentially degraded.
The dispatch of an offsite firefighting agency to the site requires an emergency declaration only if it is needed to actively support firefighting efforts because the fire is beyond the capability of the Fire Brigade to extinguish.
Declaration is not necessary if the agency resources are placed on stand-by, or supporting post-extinguishment recovery or investigation actions.Basis-Related Requirements from Appendix R Appendix R to 10 CFR 50, states in part: Criterion 3 of Appendix A to this part specifies that "Structures, systems, and components important to safety shall be designed and located to minimize, consistent with other safety requirements, the probability and effect of fires and explosions." When considering the effects of fire, those systems associated with achieving and maintaining safe shutdown conditions assume major importance to safety because damage to them can lead to core damage resulting from loss of coolant through boil-off.Because fire may affect safe shutdown systems and because the loss of function of systems used to mitigate the consequences of design basis accidents under post-fire conditions does not per se impact public safety, the need to limit fire damage to systems required to achieve and maintain safe shutdown conditions is greater than the need to limit fire damage to those systems required to mitigate the consequences of design basis accidents.
In addition, Appendix R to 10 CFR 50, requires, among other considerations, the use of 1-hour fire barriers for the enclosure of cable and equipment and associated non-safety circuits of one redundant train (G.2.c). As used in EAL #2, the 30-minutes to verify a single alarm is well within this worst-case 1-hour time period.Depending upon the plant mode at the time of the event, escalation of the emergency classification level would be via IC CA26 or MA5SA9.Month 20XX BY 3-132 EP-AA-1002 (Revision XX)
Exalon Nuclear Bvron Annex.E......
Nu.l.ar RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY Basis Reference(s):
: 1. NEI 99-01, Rev 6 HU4 2. Drawing S-01A Composite Site Plan 3. UFSAR Section 3.02 4. BAP-1 100, Fire Protection Procedure Series Month 20XX BY 3-133 EP-AA-1002 (Revision XX)
Ilrnn Ann,-Y li=Yahrln kililorl,.
RurnAnvFLI~ 
~aI2 RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HU42 Initiating Condition:
Seismic event greater than OBE levels.Operating Mode Applicability:
1, 2,3,4,5,6, D Emergency Action Level (EAL): Seismic event > Operating Basis Earthquake (OBE) as indicated by seismic check at panel OPA02J.Soeis-mic-o'.'ot groator than Oporating Barsis Earthquako (01BE) as indicsatod by: a. (sito specific indication that a so;6n*mV8c ovnt t orexeo~edod OBE limi~tS)Basis: This IC addresses a seismic event that results in accelerations at the plant site greater than those specified for an Operating Basis Earthquake (OBE)'. An earthquake greater than an OBE but less than a Safe Shutdown Earthquake (SSE)2 should have no significant impact on safety-related systems, structures and components; however, some time may be required for the plant staff to ascertain the actual post-event condition of the plant (e.g., performs walk-downs and post-event inspections).
Given the time necessary to perform walk-downs and inspections, and fully understand any impacts, this event represents a potential degradation of the level of safety of the plant.Event verification with external sources should not be necessary during or following an OBE. Earthquakes of this magnitude should be readily felt by on-site personnel and recognized as a seismic event (e.g., typical lateral accelerations are in excess of 0.08g).The Shift Manager or Emergency Director may seek external verification if deemed appropriate (e.g., a call to the USGS, check internet news sources, etc.); however, the verification action must not preclude a timely emergency declaration.
Depending upon the plant mode at the time of the event, escalation of the emergency classification level would be via IC CA26 or MA5,A4.1 An OBE is vibratory ground motion for which those features of a nuclear power plant necessary for continued operation without undue risk to the health and safety of the?ublic will remain functional.
An SSE is vibratory ground motion for which certain (generally, safety-related) structures, systems, and components must be designed to remain functional.
Month 20XX BY 3-134 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY Basis Reference(s):
: 1. NEI 99-01, Rev 6 HU2 2. OBOA ENV-4 Earthquake
: 3. Annunciator 0-38-E5 Accelograph Accel High Month 20XX BY 3-135 EP-AA-1002 (Revision XX)
Rrnn Annay I=:alnn Nielanr RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HA5 Initiating Condition:
Gaseous release impeding access to equipment necessary for normal plant operations, cooldown or shutdown.Operating Mode Applicability:
1, 2, 3,4, 5, 6, D Emergency Action Level (EAL): Note: If the equipment in the listed room or area was already inoperable, or out of service, before the event occurred, then no emergency classification is warranted.
: 1. Release of a toxic, corrosive, asphyxiant or flammable gas in ANY Table H3 area.Table H3 Areas with Entry Related Mode Applicability Area Entry Related Mode Applicability Auxiliary Building*
Mode 4, 5, and 6*Areas required to establish shutdown cooling AND 2. Entry into the room or area is prohibited or impeded.Note: if the equipment in the listed room Or area was already inoperable Or out of sero~ico before the event occurred, then no) emnergency classification is a-Rcanted~-
(1) a. Reloase of a toxiccroio asphyxiant or flammable gar, into any of tho folleowi plat rooms or areas: ( Sit9 Specific list of plant rooms or areas with entr; related moedo appli cI ;lit, i b. Entr: onto the room or aroa is DrOhibited or knaed.Basis: This IC addresses an event involving a release of a hazardous gas that precludes or impedes access to equipment necessary to transition the plant from normal plant Month 20XX BY 3-136 EP-AA-1002 (Revision XX)
P rnn Anngw i:Yzalrn khe-nrlar RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY operation to cooldown and shutdown as specified in normal plant procedureswai4#ai nremal planit oporation orrqurd forA RFnoral plant cooldown and shutdown This condition represents an actual or potential substantial degradation of the level of safety of the plant.Table H3 is a list of plant rooms or areas with entry-related mode applicability that contain equipment which require a manual/local action necessary to transition the plant from normal plant operation to cooldown and shutdown as specified in normal operating procedures (establish shutdown cooling), where if this action is not completed the plant would not be able to attain and maintain cold shutdown.This Table does not include rooms or areas for which entry is required solely to perform actions of an administrative or record keeping nature (e.g., normal rounds or routine inspections).
This Table does not include the Control Room since adequate engineered safety/design features are in place to preclude a Control Room evacuation due to the release of a hazardous gas.An Alert declaration is warranted if entry into the affected room/area is, or may be, procedurally required during the plant operating mode in effect and the gaseous release preclude the ability to place shutdown cooling in serviccat tho time of the gascous release. The emergency classification is not contingent upon whether entry is actually necessary at the time of the release.Evaluation of the IC and EAL do not require atmospheric sampling; it only requires the Emergency Director's judgment that the gas concentration in the affected room/area is sufficient to preclude or significantly impede procedurally required access. This judgment may be based on a variety of factors including an existing job hazard analysis, report of ill effects on personnel, advice from a subject matter expert or operating experience with the same or similar hazards. Access should be considered as impeded if extraordinary measures are necessary to facilitate entry of personnel into the affected room/area (e.g., requiring use of protective equipment, such as SCBAs, that is not routinely employed).
An emergency declaration is not warranted if any of the following conditions apply." The plant is in an operating mode different than the mode specified for the affected room/area (i.e., entry is not required during the operating mode in effect at the time of the gaseous release).
For example, the plant is in Mode 1 when the gaseous release occurs, and the procedures used for normal operation, cooldown and shutdown do not require entry into the affected room until Mode 4.* The gas release is a planned activity that includes compensatory measures which address the temporary inaccessibility of a room or area (e.g., fire suppression system testing)." The action for which room/area entry is required is of an administrative or record keeping nature (e.g., normal rounds or routine inspections).
Month 20XX BY 3-137 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY* The access control measures are of a conservative or precautionary nature, and would not actually prevent or impede a required action.An asphyxiant is a gas capable of reducing the level of oxygen in the body to dangerous levels. Most commonly, asphyxiants work by merely displacing air in an enclosed environment.
This reduces the concentration of oxygen below the normal level of around 19%, which can lead to breathing difficulties, unconsciousness or even death.This EAL does not apply to firefighting activities that generate smoke or that automatically or manually activate a fire suppression system in an area.Escalation of the emergency classification level would be via Recognition Category RA, C or F ICs.Basis Reference(s):
: 1. NEI 99-01, Rev 6 HA5 2. Drawing S-01A Composite Site Plan 3. UFSAR Section 3.02 4. ACIT 660892-13, Station Halon Discharge IDLH Evaluation Month 20XX BY 3-138 EP-AA-1002 (Revision XX)
Rrnn  Fwi:: nn M, malar Run nc vln i ram RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HUl Initiating Condition:
Hazardous Event Operating Mode Applicability:
1,2,3,4,5,6, D Emergency Action Level (EAL): Note: EAL #4 does not apply to routine traffic impediments such as fog, snow, ice, or vehicle breakdowns or accidents.
: 1. Tornado strike within the PROTECTED AREA.OR 2. Internal room or area flooding of a magnitude sufficient to require manual or automatic electrical isolation of a SAFETY SYSTEM component required by Technical Specifications for the current operating mode.OR 31 3. Movement of personnel within the PROTECTED AREA is impeded due to an offsite event involving hazardous materials (e.g., an offsite chemical spill or toxic gas release).OR 4. A hazardous event that results in on-site conditions sufficient to prohibit the plant staff from accessing the site via personal vehicles.E Al #3 does not apply to routinr traffic impediments such as fog, sn,,ico, or vohrcle bhreak-dowN 9n o-t9r -Accirvdo en tsr..(1) A torn-ado-strike Mwith;in tho PROT"ECPTED AREA.(2) Intornal room or are-a flooding of a magnitude sufficient to require manual oi au--tomwatfic -a -r electrca 1 0A -Isoation o-.ef a S A mFTP 8Y SYST EM copnn neddfo h current eperating mode-.(3) IVIMA'MoRt.
of Personnel 
;'t-h*n t-ho PROTECTED AR impeded duo to an effsito_ event in'olylng hazardous mnaterials (o.g., an offeto chem~ical Spill Or toi gas Fee~aee)(4) A hazardous event that results on site conditions suffient t prohibit the plant staff from accossing t i i enal ehiles.Month 20XX BY 3-139 EP-AA-1002 (Revision XX)
P rnn Annoy R~,rnnAnn~vExelln Nuclea~r RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY (5) (Site SPS.ific li.t of natural or t,,hno,-gi.al hazard ev.e.nts)Basis: PROTECTED AREA: An area that normally encompasses all controlled areas within the security protected area fence.SAFETY SYSTEM: A system required for safe plant operation, cooling down the plant and/or placing it in the cold shutdown condition, including the ECCS. These are typically systems classified as safety-related.
This IC addresses hazardous events that are considered to represent a potential degradation of the level of safety of the plant.EAL #1 Basis aAddresses a tornado striking (touching down) within the Protected Area.EAL #2 Basis aAddresses flooding of a building room or area that results in operators isolating power to a SAFETY SYSTEM component due to water level or other wetting concerns.Classification is also required if the water level or related wetting causes an automatic isolation of a SAFETY SYSTEM component from its power source (e.g., a breaker or relay trip). To warrant classification, operability of the affected component must be required by Technical Specifications for the current operating mode. Manual isolation of power to a SAFETY SYSTEM component as a result of leakage is an event of lesser impact and would be expected to cause small and localized damage. The consequence of this type of event is adequately assessed and addressed in accordance with Technical Specifications.
EAL #3 Basis aAddresses a hazardous materials event originating at an offsite location and of sufficient magnitude to impede the movement of personnel within the PROTECTED AREA.EAL #4 Basis aAddresses a hazardous event that causes an on-site impediment to vehicle movement and significant enough to prohibit the plant staff from accessing the site using personal vehicles.
Examples of such an event include site flooding caused by a hurricane, heavy rains, up-river water releases, dam failure, etc., or an on-site train derailment blocking the access road.This EAL is not intended to apply to routine impediments such as fog, snow, ice, or vehicle breakdowns or accidents, but rather to more significant conditions such as the Hurricane Andrew strike on Turkey Point in 1992, the flooding around the Cooper Month 20XX BY 3-140 EP-AA-1002 (Revision XX)
Rurnn Annoy Rvrnn An~v FxelIn Nucle~ar RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY Station during the Midwest floods of 1993, or the flooding around Ft. Calhoun Station in 2011.E:AL ./#5 a-ddFres'e 
(;ito ep-cific.
Escalation of the emergency classification level would be based on ICs in Recognition Categories RA, F, MS, H or C.Basis Reference(s):
: 1. NEI 99-01, Rev 6 HU3 Month 20XX BY 3-141 EP-AA-1002 (Revision XX)
Rrnn Annov lFyaInn k~il"Aar Rurr~n Ann~v Fvnirn M..a~Ir-N I
* I ~ II I~fl ~ I ~RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HG7 Initiating Condition:
Other conditions exist which in the judgment of the Emergency Director warrant declaration of a GENERAL EMERGENCY.
Operating Mode Applicability:
1,2, 3, 4, 5, 6, D Emergency Action Level (EAL): (-1-) Other conditions exist which in the judgment of the Emergency Director indicate that events are in progress or have occurred which involve actual or IMMINENT substantial core degradation or melting with potential for loss of containment integrity or HOSTILE ACTION that results in an actual loss of physical control of the facility.Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area.Basis: IMMINENT:
The trajectory of events or conditions is such that an EAL will be met within a relatively short period of time regardless of mitigation or corrective actions.HOSTILE ACTION: An act toward a NPP or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, PROJECTILEs, vehicles, or other devices used to deliver destructive force. Other acts that satisfy the overall intent may be included.
HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on the NPP. Non-terrorism-based EALs should be used to address such activities (i.e., this may include violent acts between individuals in the owner controlled area).HOSTAGE: A person(s) held as leverage against the station to ensure that demands will be met by the station PROJECTILE:
An object directed toward a NPP that could cause concern for its continued operability, reliability, or personnel safety.This IC addresses unanticipated conditions not addressed explicitly elsewhere but that warrant declaration of an emergency because conditions exist which are believed by the Emergency Director to fall under the emergency classification level description for a General Emergency.
Basis Reference(s):
: 1. NEI 99-01, Rev 6 HG7 Month 20XX BY 3-142 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HS7 Initiating Condition:
Other conditions exist which in the judgment of the Emergency Director warrant declaration of a SITE AREA EMERGENCY.
Operating Mode Applicability:
1,2, 3, 4, 5, 6, D Emergency Action Level (EAL): (1-) Other conditions exist which in the judgment of the Emergency Director indicate that events are in progress or have occurred which involve actual or likely major failures of plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts, (1) toward site personnel or equipment that could lead to the likely failure of or, (2) that prevent effective access to equipment needed for the protection of the public. Any releases are not expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels beyond the site boundary.Basis: HOSTILE ACTION: An act toward a NPP or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, PROJECTILEs, vehicles, or other devices used to deliver destructive force. Other acts that satisfy the overall intent may be included.
HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on the NPP. Non-terrorism-based EALs should be used to address such activities (i.e., this may include violent acts between individuals in the owner controlled area).HOSTAGE: A person(s) held as leverage against the station to ensure that demands will be met by the station PROJECTILE:
An object directed toward a NPP that could cause concern for its continued operability, reliability, or personnel safety.This IC addresses unanticipated conditions not addressed explicitly elsewhere but that warrant declaration of an emergency because conditions exist which are believed by the Emergency Director to fall under the emergency classification level description for a Site Area Emergency.
Basis Reference(s):
: 1. NEI 99-01, Rev 6 HS7 Month 20XX BY 3-143 EP-AA-1002 (Revision XX) rnn AnnAv IPwv,-oIn kair-Inft-r J., &#xfd; 1 * .5 RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HA7 Initiating Condition:
Other conditions exist which in the judgment of the Emergency Director warrant declaration of an ALERT Operating Mode Applicability:
1,2,3, 4,5,6, D Emergency Action Level (EAL): (-1-) Other conditions exist which, in the judgment of the Emergency Director, indicate that events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of HOSTILE ACTION. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.Basis: HOSTILE ACTION: An act toward a NPP or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, PROJECTILEs, vehicles, or other devices used to deliver destructive force. Other acts that satisfy the overall intent may be included.
HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on the NPP. Non-terrorism-based EALs should be used to address such activities (i.e., this may include violent acts between individuals in the owner controlled area).HOSTAGE: A person(s) held as leverage against the station to ensure that demands will be met by the station PROJECTILE:
An object directed toward a NPP that could cause concern for its continued operability, reliability, or personnel safety.This IC addresses unanticipated conditions not addressed explicitly elsewhere but that warrant declaration of an emergency because conditions exist which are believed by the Emergency Director to fall under the emergency classification level description for an Alert.Basis Reference(s):
: 1. NEI 99-01, Rev 6 HA7 Month 20XX BY 3-144 EP-AA-1002 (Revision XX) i:trnn Anng~v I::alnn khiPlanr flurr~n Ann~v Frolnn M.rr4n~ar RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HU7 Initiating Condition:
Other conditions exist which in the judgment of the Emergency Director warrant declaration of an EVENT.Operating Mode Applicability:
1, 2, 3, 4, 5, 6, D Emergency Action Level (EAL): (-1-) Other conditions exist which in the judgment of the Emergency Director indicate that events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated.
No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.Basis: This IC addresses unanticipated conditions not addressed explicitly elsewhere but that warrant declaration of an emergency because conditions exist which are believed by the Emergency Director to fall under the emergency classification level description for an NQU=UNUSUAL EVENT.Basis Reference(s):
: 1. NEI 99-01, Rev 6 HU7 Month 20XX BY 3-145 EP-AA-1002 (Revision XX)
Fwallon Nucloar Byron Annex Ex...n........
RECOGNITION CATEGORY ISFSI MALFUNCTIONS E-HU1 Initiating Condition Damage to a loaded cask CONFINEMENT BOUNDARY.Operating Mode Applicability:
1,2, 3, 4, 5, 6, D Emergency Action Level (EAL): Damage to a loaded cask CONFINEMENT BOUNDARY as indicated by an on-contact radiation reading:* > 60mr/hr (gamma + neutron) on the top of the spent fuel cask OR* > 600mr/hr (gamma + neutron) on the side of the spent fuel cask, excluding inlet and outlet ducts (4)--Damag to a loadod- CONFINEMENT as, indicated by an On con-tac-t ra~diatinroa-AFdingq groator than (2 times the site S198G&i cask spocific tochnial ,pcification allowablo radiation level) on the A,.rfa, of the spent fuol cask.Basis: CONFINEMENT BOUNDARY:
The irradiated fuel dry storage cask barrier(s) between areas containing radioactive substances and the environment.
INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) : A complex that is designed and constructed for the interim storage of spent nuclear fuel and other radioactive materials associated with spent fuel storage.This IC addresses an event that results in damage to the CONFINEMENT BOUNDARY of a storage cask containing spent fuel. It applies to irradiated fuel that is licensed for dry storage beginning at the point that the loaded storage cask is sealed. The word cask, as used in this EAL, refers to the storage container in use at the site for dry storage of irradiated fuel. The issues of concern are the creation of a potential or actual release path to the environment, degradation of oen OFrmoreany fuel assemblies due to environmental factors, and configuration changes which could cause challenges in removing the cask or fuel from storage.The existence of "damage" is determined by radiological survey. The technical specification multiple of "2 times", which is also used in Recognition Category RA IC RAU1, is used here to distinguish between non-emergency and emergency conditions.
The emphasis for this classification is the degradation in the level of safety of the spent Month 20XX BY 3-146 EP-AA-1002 (Revision XX)
R renn Ann,,v I=yalnn M,,r-Iazar irn. i --Dt Fvolni Mi Ir4, 2r RECOGNITION CATEGORY ISFSI MALFUNCTIONS fuel cask and not the magnitude of the associated dose or dose rate. It is recognized that in the case of extreme damage to a loaded cask, the fact that the "on-contact" dose rate limit is exceeded may be determined based on measurement of a dose rate at some distance from the cask.Security-related events for ISFSIs are covered under ICs HUI1 and HAl.Basis Reference(s):
: 1. NEI 99-01, Rev 6 E-HU1 2. Certificate of Compliance No. 1014 Appendix A Section 5.7 Month 20XX BY 3-147 EP-AA-1002 (Revision XX)
RPrnn Annov Pv,-Inn Ndnelhat-r RECOGNITION CATEGORY ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENTS RG1 Initiating Condition:
Release of gaseous radioactivity resulting in offsite dose greater than 1000 mRem TEDE or 5000 mRem thyroid CDE.Operating Mode Applicability:
1, 2, 3, 4, 5, 6, D Emergency Action Level (EAL): Notes: " The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded." If an ongoing release is detected and the release start time is unknown, assume that the release duration has exceeded 15 minutes." Classification based on effluent monitor readings assumes that a release path to the environment is established.
If the effluent flow past an effluent monitor is known to have stopped due to actions to isolate the release path, then the effluent monitor reading is no longer valid for classification purposes." The pre-calculated effluent monitor values presented in EAL #1 should be used for emergency classification assessments until the results from a dose assessment using actual meteorology are available.
: 1. The sum of readings on the Unit 1 and 2 Aux BLDG Vent WRGMs (1/2 RE-PR030)> 9.99 E+09 pCi/sec for > 15 minutes (as determined from Unit 1 & 2 PF430 or PPDS -Total Noble Gas Release Rate).OR 2. Dose assessment Using actual meteorology indicates doses at or beyond the site boundary of EITHER: a. > 1000 mRem TEDE OR b. > 5000 mRem CDE Thyroid OR Month XXXX BY 3-33 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY ABNORMAL RAD LEVELS I RADIOLOGICAL EFFLUENTS RGI (cont)Emergency Action Level (EAL) (cont): 3. Field survey results at or beyond the site boundary indicate EITHER: a. Gamma (closed window) dose rates >1000 mRem/hr are expected to continue for > 60 minutes.OR b. Analyses of field survey samples indicate > 5000 mRem CDE Thyroid for 60 minutes of inhalation.
Basis: This IC addresses a release of gaseous radioactivity that results in projected or actual offsite doses greater than or equal to the EPA Protective Action Guides (PAGs). It includes both monitored and un-monitored releases.
Releases of this magnitude will require implementation of protective actions for the public.Radiological effluent EALs are also included to provide a basis for classifying events and conditions that cannot be readily or appropriately classified on the basis of plant conditions alone. The inclusion of both plant condition and radiological effluent EALs more fully addresses the spectrum of possible accident events and conditions.
The TEDE dose is set at the EPA PAG of 1000 mRem while the 5000 mRem thyroid CDE was established in consideration of the 1:5 ratio of the EPA PAG for TEDE and thyroid CDE.Basis Reference(s):
: 1. NEI 99-01 Rev 6, AG1 2. EP-AA-112-500 Emergency Environmental Monitoring
: 3. EP-EAL-0602 Revision 1, Criteria for Choosing Radiological Gaseous Effluent EAL Threshold Values Byron Station Month XXXX BY 3-34 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY ABNORMAL RAD LEVELS I RADIOLOGICAL EFFLUENTS RS1 Initiating Condition:
Release of gaseous radioactivity resulting in offsite dose greater than 100 mRem TEDE or 500 mRem thyroid CDE.Operating Mode Applicability:
1, 2, 3, 4, 5, 6, D Emergency Action Level (EAL): Notes: " The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.* If an ongoing release is detected and the release start time is unknown, assume that the release duration has exceeded 15 minutes.* Classification based on effluent monitor readings assumes that a release path to the environment is established.
If the effluent flow past an effluent monitor is known to have stopped due to actions to isolate the release path, then the effluent monitor reading is no longer valid for classification purposes.The pre-calculated effluent monitor values presented in EAL #1 should be used for emergency classification assessments until the results from a dose assessment using actual meteorology are available.
: 1. The sum of readings on the Unit 1 and 2 Aux BLDG Vent WRGMs (1/2 RE-PR030)> 9.99 E+08 pCi/sec for > 15 minutes (as determined from Unit 1 & 2 PF430 or PPDS -Total Noble Gas Release Rate).OR 2. Dose assessment using actual meteorology indicates doses at or beyond the site boundary of EITHER: a. > 100 mRem TEDE OR b. > 500 mRem CDE Thyroid OR 3. Field survey results at or beyond the site boundary indicate EITHER: a. Gamma (closed window) dose rates >100 mR/hr are expected to continue for > 60 minutes.OR b. Analyses of field survey samples indicate > 500 mRem CDE Thyroid for 60 minutes of inhalation.
Month XXXX BY 3-35 EP-AA-1002 (Revision XX)
Rvrnn Annpx Rvrnn Annex Fvalnn Nw-lar~I RECOGNITION CATEGORY ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENTS RS1 (cont)Basis: This IC addresses a release of gaseous radioactivity that results in projected or actual offsite doses greater than or equal to 10% of the EPA Protective Action Guides (PAGs).It includes both monitored and un-monitored releases.
Releases of this magnitude are associated with the failure of plant systems needed for the protection of the public.Radiological effluent EALs are also included to provide a basis for classifying events and conditions that cannot be readily or appropriately classified on the basis of plant conditions alone. The inclusion of both plant condition and radiological effluent EALs more fully addresses the spectrum of possible accident events and conditions.
The TEDE dose is set at 10% of the EPA PAG of 1000 mRem while the 500 mRem thyroid CDE was established in consideration of the 1:5 ratio of the EPA PAG for TEDE and thyroid CDE.Escalation of the emergency classification level would be via IC RG1.Basis Reference(s):
: 1. NEI 99-01 Rev 6, AS1 2. EP-AA-1 12-500 Emergency Environmental Monitoring
: 3. EP-EAL-0602 Revision 1, Criteria for Choosing Radiological Gaseous Effluent EAL Threshold Values Byron Station Month XXXX BY 3-36 EP-AA-1 002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY ABNORMAL RAD LEVELS I RADIOLOGICAL EFFLUENTS RA1 Initiating Condition:
Release of gaseous or liquid radioactivity resulting in offsite dose greater than 10 mRem TEDE or 50 mRem thyroid CDE.Operating Mode Applicability:
1, 2, 3, 4, 5, 6, D Emergency Action Level (EAL): Notes:* The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded." If an ongoing release is detected and the release start time is unknown, assume that the release duration has exceeded 15 minutes." Classification based on effluent monitor readings assumes that a release path to the environment is established.
If the effluent flow past an effluent monitor is known to have stopped due to actions to isolate the release path, then the effluent monitor reading is no longer valid for classification purposes." The pre-calculated effluent monitor values presented in EAL #1 should be used for emergency classification assessments until the results from a dose assessment using actual meteorology are available.
: 1. The sum of readings on the Unit 1 and 2 Aux BLDG Vent WRGMs (1/2 RE-PR030)> 9.99 E+07 pCi/sec for > 15 minutes (as determined from Unit 1 & 2 PF430 or PPDS -Total Noble Gas Release Rate).OR 2. Dose assessment using actual meteorology indicates doses at or beyond the site boundary of EITHER: a. > 10 mRem TEDE OR b. > 50 mRem CDE Thyroid OR 3. Analysis of a liquid effluent sample indicates a concentration or release rate that would result in doses greater than EITHER of the following at or beyond the site boundary a. 10 mRem TEDE for 60 minutes of exposure OR b. 50 mRem CDE Thyroid for 60 minutes of exposure Month XXXX BY 3-37 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENTS RAI (cont)Emergency Action Level (EAL) (cont): OR 4. Field survey results at or beyond the site boundary indicate EITHER: a. Gamma (closed window) dose rates > 10 mR/hr are expected to continue for 2 60 minutes.OR b. Analyses of field survey samples indicate > 50 mRem CDE Thyroid for 60 minutes of inhalation.
Basis: This IC addresses a release of gaseous or liquid radioactivity that results in projected or actual offsite doses greater than or equal to 1% of the EPA Protective Action Guides (PAGs). It includes both monitored and un-monitored releases.
Releases of this magnitude represent an actual or potential substantial degradation of the level of safety of the plant as indicated by a radiological release that significantly exceeds regulatory limits (e.g., a significant uncontrolled release).Radiological effluent EALs are also included to provide a basis for classifying events and conditions that cannot be readily or appropriately classified on the basis of plant conditions alone. The inclusion of both plant condition and radiological effluent EALs more fully addresses the spectrum of possible accident events and conditions.
The TEDE dose is set at 1% of the EPA PAG of 1000 mRem while the 50 mRem thyroid CDE was established in consideration of the 1:5 ratio of the EPA PAG for TEDE and thyroid CDE.This EAL includes any release for which a radioactivity discharge permit was not prepared, or a release that exceeds the conditions (e.g., minimum dilution flow, maximum discharge flow, alarm setpoints, etc.) on the applicable permit.Escalation of the emergency classification level would be via IC RS1.Month XXXX BY 3-38 EP-AA-1002 (Revision XX)
R1urrn A nn-,v IPv-lnn ,,r-lanr RECOGNITION CATEGORY ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENTS Basis Reference(s):
: 1. NEI 99-01 Rev 6, AA1 2. UFSAR Section 11.5.2.3 3. OBISR 11 .a.3-002, Channel Operation Test of Liquid Radwaste Effluent Radiation Monitor OPR01J 4. ODCM, CY-BY-170-301, Section 3.0, Liquid Effluents 5. EP-EAL-0602 Revision 1, Criteria for Choosing Radiological Gaseous Effluent EAL Threshold Values Byron Station 6. EP-EAL-0619 Rev. 0, Byron Criteria for Choosing Radiological Liquid Effluents EAL Threshold Values.7. EP-EAL-0624 Rev. 0, Byron Criteria for Choosing Radiological Gaseous Effluents EAL Threshold Values for Waste Gas Decay Tanks Month XXXX BY 3-39 EP-AA-1 002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENTS RU1 Initiating Condition:
Release of gaseous or liquid radioactivity greater than 2 times the ODCM limits for 60 minutes or longer.Operating Mode Applicability:
1,2, 3, 4, 5, 6, D Emergency Action Level (EAL): Notes:* The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded." If an ongoing release is detected and the release start time is unknown, assume that the release duration has exceeded 60 minutes." Classification based on effluent monitor readings assumes that a release path to the environment is established.
If the effluent flow past an effluent monitor is known to have stopped due to actions to isolate the release path, then the effluent monitor reading is no longer valid for classification purposes.1. Reading on ANY of the following effluent monitors > 2 times alarm setpoint established by a current radioactive release discharge permit for > 60 minutes.* OPROO1, Liquid Radwaste Effluent Monitor* OPROO2, Gas Decay Tank Effluent Monitor* OPRO10, Station Blowdown Monitor* 1/2PROO1, Containment Purge Effluent Monitor* Discharge Permit specified monitor OR 2. The sum of readings on the Unit 1 and 2 Aux Bldg Vent WRGMs (1/2 RE-R030)> 1.14 E+06 pCi/sec for > 60 minutes (as determined from Unit 1 & 2 PF430 or PPDS -Total Noble Gas Release Rate).OR 3. Confirmed sample analyses for gaseous or liquid releases indicate concentrations or release rates > 2 times ODCM Limit with a release duration of > 60 minutes.Month XXXX BY 3-40 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENTS RUI (cont)Basis: This IC addresses a potential decrease in the level of safety of the plant as indicated by a low-level radiological release that exceeds regulatory commitments for an extended period of time (e.g., an uncontrolled release).
It includes any gaseous or liquid radiological release, monitored or un-monitored, including those for which a radioactivity discharge permit is normally prepared.Nuclear power plants incorporate design features intended to control the release of radioactive effluents to the environment.
Further, there are administrative controls established to prevent unintentional releases, and to control and monitor intentional releases.
The occurrence of an extended, uncontrolled radioactive release to the environment is indicative of degradation in these features and/or controls.Radiological effluent EALs are also included to provide a basis for classifying events and conditions that cannot be readily or appropriately classified on the basis of plant conditions alone. The inclusion of both plant condition and radiological effluent EALs more fully addresses the spectrum of possible accident events and conditions.
Releases should not be prorated or averaged.
For example, a release exceeding 4 times release limits for 30 minutes does not meet the EAL.EAL #1 Basis: This EAL addresses radioactivity releases that cause effluent radiation monitor readings to exceed 2 times the limit established by a radioactivity discharge permit. This EAL will typically be associated with planned batch releases from non-continuous release pathways (e.g., radwaste, waste gas).The effluent monitors listed are those normally used for planned discharges.
If a discharge is performed using a different flowpath or effluent monitor other than those listed (e.g., a portable or temporary effluent monitor), then the declaration criteria will be based on the monitor specified in the Discharge Permit.EAL #2 Basis: This EAL addresses normally occurring continuous radioactivity releases from monitored gaseous effluent pathways.EAL #3 Basis This EAL addresses uncontrolled gaseous or liquid releases that are detected by sample analyses or environmental surveys, particularly on unmonitored pathways (e.g., spills of radioactive liquids into storm drains, heat exchanger leakage in river water systems, etc.).Escalation of the emergency classification level would be via IC RAI.Month XXXX BY 3-41 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENTS RUI (cont)Basis Reference(s):
: 1. NEI 99-01 Rev 6, AU1 2. UFSAR Section 11.5.2.3 3. OBISR 11 .a.3-002, Channel Operation Test of Liquid Radwaste Effluent Radiation Monitor OPR01J 4. ODCM, CY-BY-170-301, Section 3.0, Liquid Effluents 5. EP-EAL-0602 Revision 1, Criteria for Choosing Radiological Gaseous Effluent EAL Threshold Values Byron Station Month XXXX BY 3-42 EP-AA-1002 (Revision XX)
Bvron Annex I=xelon Nuclear Byron Annex Exelon Nuclear RECOGNITION CATEGORY ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENTS RA2 Initiating Condition:
Significant lowering of water level above, or damage to, irradiated fuel.Operating Mode Applicability:
1, 2, 3, 4, 5, 6, D Emergency Action Level (EAL): 1. Uncovery of irradiated fuel in the REFUELING PATHWAY.OR 2. Damage to irradiated fuel resulting in a release of radioactivity from the fuel as indicated by ANY Table R1 Radiation Monitor reading >1000 mRem/hr Table R1 Fuel Handling Incident Radiation Monitors* Fuel Building Fuel Handling Incident Monitor ORE-AR055" Fuel Building Fuel Handling Incident Monitor ORE-AR056* Containment Fuel Handling Incident Monitor 1/2RE-AR01 1* Containment Fuel Handling Incident Monitor 1/2RE-AR012 Basis: REFUELING PATHWAY: all the cavities, tubes, canals and pools through which irradiated fuel may be moved or stored, but not including the reactor vessel below the flange.IMMINENT:
The trajectory of events or conditions is such that an EAL will be met within a relatively short period of time regardless of mitigation or corrective actions.CONFINEMENT BOUNDARY:
The irradiated fuel dry storage cask barrier(s) between areas containing radioactive substances and the environment.
This IC addresses events that have caused IMMINENT or actual damage to an irradiated fuel assembly.
These events present radiological safety challenges to plant personnel and are precursors to a release of radioactivity to the environment.
As such, they represent an actual or potential substantial degradation of the level of safety of the plant.This IC applies to irradiated fuel that is licensed for dry storage up to the point that the loaded storage cask is sealed. Once sealed, damage to a loaded cask causing loss of the CONFINEMENT BOUNDARY is classified in accordance with IC E-HU1.Month XXXX BY 3-43 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENTS RA2 (cont)Basis (cont): EAL #1 Basis: This EAL escalates from RU2 in that the loss of level, in the affected portion of the REFUELING PATHWAY, is of sufficient magnitude to have resulted in uncovery of irradiated fuel. Indications of irradiated fuel uncovery may include direct or indirect visual observation (e.g., reports from personnel or camera images), as well as significant changes in water and radiation levels, or other plant parameters.
Computational aids may also be used (e.g., a boil-off curve). Classification of an event using this EAL should be based on the totality of available indications, reports and observations.
While an area radiation monitor could detect a rise in a dose rate due to a lowering of water level in some portion of the REFUELING PATHWAY, the reading may not be a reliable indication of whether or not the fuel is actually uncovered.
To the degree possible, readings should be considered in combination with other available indications of inventory loss.A drop in water level above irradiated fuel within the reactor vessel may be classified in accordance Recognition Category C during the Cold Shutdown and Refueling modes.EAL #2 Basis: This EAL addresses a release of radioactive material caused by mechanical damage to irradiated fuel. Damaging events may include the dropping, bumping or binding of an assembly, or dropping a heavy load onto an assembly.
A rise in readings on radiation monitors should be considered in conjunction with in-plant reports or observations of a potential fuel damaging event (e.g., a fuel handling accident).
Escalation of the emergency would be based on either Recognition Category R or C ICs.Basis Reference(s):
: 1. NEI 99-01 Rev 6, AA2 2. UFSAR 11.5.2.2.6, 11.5.2.2.7, 15.7.4, Table 12.3-3 3. Technical Specification Table 3.3.6-1 4. 1/2 BOA REFUEL-1 Fuel Handling Emergency Unit 1/2 5. 1/2 BOA REFUEL-2 Refueling Cavity or Spent Fuel Pool Level Loss Unit 1/2 6. TRM 3.9.A, Refueling Operations, Decay Time 7. BAR 1-1-A2, 2-1-A2, CNMT DRAIN LEAK DETECT FLOW HIGH alarm Month XXXX BY 3-44 EP-AA-1002 (Revision XX)
Rvmn N.clnnr Rvrnn Annex .xavI=n Nu.cear RECOGNITION CATEGORY ABNORMAL RAD LEVELS I RADIOLOGICAL EFFLUENTS RU2 Initiating Condition:
UNPLANNED loss of water level above irradiated fuel.Operating Mode Applicability:
1,2, 3, 4, 5, 6, D Emergency Action Level (EAL): 1. a. UNPLANNED water level drop in the REFUELING PATHWAY as indicated by ANY of the following:
* Refueling Cavity water level < 23 ft. above the Reactor Flange (< 423 ft.indicated level).OR" Spent Fuel Pool water level < 23 ft. above the fuel (< 422 ft. 9 in.indicated level).OR* Indication or report of a drop in water level in the REFUELING PATHWAY.AND b. UNPLANNED Area Radiation Monitor reading rise on ANY radiation monitors in Table RI.Table R1 -Fuel Handling Incident Radiation Monitors* Fuel Building Fuel Handling Incident Monitor ORE-AR055" Fuel Building Fuel Handling Incident Monitor ORE-AR056* Containment Fuel Handling Incident Monitor 1/2RE-AR01 1" Containment Fuel Handling Incident Monitor 1/2RE-AR012 Basis: UNPLANNED:
A parameter change or an event that is not 1) the result of an intended evolution or 2) an expected plant response to a transient.
The cause of the parameter change or event may be known or unknown.REFUELING PATHWAY: all the cavities, tubes, canals and pools through which irradiated fuel may be moved or stored, but not including the reactor vessel below the flange.Month XXXX BY 3-45 EP-AA-1002 (Revision XX)
Rvrnn AnnexN.r.len r Rvrnn Annex FYAllnn Nuclea~r RECOGNITION CATEGORY ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENTS RU2 (cont)Basis (cont): This IC addresses a loss in water level above irradiated fuel sufficient to cause elevated radiation levels. This condition could be a precursor to a more serious event and is also indicative of a minor loss in the ability to control radiation levels within the plant. It is therefore a potential degradation in the level of safety of the plant.A water level loss will be primarily determined by indications from available level instrumentation.
Other sources of level indications may include reports from plant personnel (e.g., from a refueling crew) or video camera observations (if available) or from any other temporarily installed monitoring instrumentation.
A significant drop in the water level may also cause a rise in the radiation levels of adjacent areas that can be detected by monitors in those locations.
The effects of planned evolutions should be considered.
For example, a refueling bridge area radiation monitor reading may rise due to planned evolutions such as lifting of the reactor vessel head or movement of a fuel assembly.
Note that this EAL is applicable only in cases where the elevated reading is due to an UNPLANNED loss of water level.A drop in water level above irradiated fuel within the reactor vessel may be classified in accordance Recognition Category C during the Cold Shutdown and Refueling modes.Escalation of the emergency classification level would be via IC RA2.Basis Reference(s):
: 1. NEI 99-01 Rev 6, AU2 2. Technical Specifications 3.7.14 3. 1/2 BOA REFUEL-1 Fuel Handling Emergency Unit 1/2 4. 1/2 BOA REFUEL-2 Refueling Cavity Or Spent Fuel Pool Level Loss Unit 1/2 5. BAR 1-1-Cl SPENT FUEL PIT LEVEL HIGH LOW 6. 1/2 BOSR 0.1-6 Unit One(Two) Mode 6 Shiftly and Daily Operating Surveillance
: 7. BOP RH-8 Filling the Refueling Cavity for Refueling 8. BOP RH-9 Pump Down of the Refueling Cavity to the RWST 9. BOP RC-4 Reactor Coolant System Drain 10. BAR 1-6-C3 REFUELING CAVITY LVL HIGH/LOW Month XXXX BY 3-46 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENTS RA3 Initiating Condition:
Radiation levels that impede access to equipment necessary for normal plant operations, cooldown or shutdown.Operating Mode Applicability:
1, 2,3, 4,5,6, D Emergency Action Level (EAL): Note:* If the equipment in the room or area listed in Table R3 was already inoperable, or out of service, before the event occurred, then no emergency classification is warranted.
: 1. Dose rate > 15 mR/hr in ANY of the following Table R2 areas: Table R2 Areas Requiring Continuous Occupancy* Main Control Room -1/2RE-AR010" Central Alarm Station -(by survey)OR 2. UNPLANNED event results in radiation levels that prohibit or significantly impede access to ANY of the following Table R3 plant rooms or areas: Table R3 Areas with Entry Related Mode Applicability Area Entry Related Mode Applicability Auxiliary Building*
Mode 4, 5 and 6*Areas required to establish shutdown cooling Month XXXX BY 3-47 EP-AA-1002 (Revision XX)
Rvron AnnexN  Bvrnn Annex FvAlnn Nucler~I RECOGNITION CATEGORY ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENTS RA3 (cont)Basis: UNPLANNED:
A parameter change or an event that is not 1) the result of an intended evolution or 2) an expected plant response to a transient.
The cause of the parameter change or event may be known or unknown.This IC addresses elevated radiation levels in certain plant rooms/areas sufficient to preclude or impede personnel from performing actions necessary to transition the plant from normal plant operation to cooldown and shutdown as specified in normal plant procedures.
As such, it represents an actual or potential substantial degradation of the level of safety of the plant. The Emergency Director should consider the cause of the increased radiation levels and determine if another IC may be applicable.
Table R3 is a list of plant rooms or areas with entry-related mode applicability that contain equipment which require a manual/local action necessary to transition the plant from normal plant operation to cooldown and shutdown as specified in normal operating procedures (establish shutdown cooling), where if this action is not completed the plant would not be able to attain and maintain cold shutdown.
This Table does not include rooms or areas for which entry is required solely to perform actions of an administrative or record keeping nature (e.g., normal rounds or routine inspections).
Rooms and areas listed in EAL #1 do not need to be included in EAL #2, including the Control Room.For EAL #2, an Alert declaration is warranted if entry into the affected room/area is, or may be, procedurally required during the plant operating mode in effect and the elevated radiation levels preclude the ability to place shutdown cooling in service. The emergency classification is not contingent upon whether entry is actually necessary at the time of the increased radiation levels. Access should be considered as impeded if extraordinary measures are necessary to facilitate entry of personnel into the affected room/area (e.g., installing temporary shielding beyond that required by procedure, requiring use of non-routine protective equipment, requesting an extension in dose limits beyond normal administrative limits).An emergency declaration is not warranted if any of the following conditions apply." The plant is in an operating mode different than the mode specified for the affected room/area (i.e., entry is not required during the operating mode in effect at the time of the elevated radiation levels). For example, the plant is in Mode 1 when the radiation rise occurs, and the procedures used for normal operation, cooldown and shutdown do not require entry into the affected room until Mode 4.* The increased radiation levels are a result of a planned activity that includes compensatory measures which address the temporary inaccessibility of a room or area (e.g., radiography, spent filter or resin transfer, etc.)." The action for which room/area entry is required is of an administrative or record keeping nature (e.g., normal rounds or routine inspections).
Month XXXX BY 3-48 EP-AA-1002 (Revision XX)
Rvron Annex Fxelnn N r Rvrnn Annex Fxelnn NucleI~ar RECOGNITION CATEGORY ABNORMAL RAD LEVELS I RADIOLOGICAL EFFLUENTS RA3 (cont)Basis (cont):* The access control measures are of a conservative or precautionary nature, and would not actually prevent or impede a required action.Escalation of the emergency classification level would be via Recognition Category R, C or F ICs.Basis Reference(s):
: 1. NEI 99-01 Rev 6, AA3 2. UFSAR Chapter 3.02, UFSAR Table 3.2-1 Month XXXX BY 3-49 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENTS RU3 Initiating Condition:
Reactor coolant activity greater than Technical Specification allowable limits.Operating Mode Applicability:
1,2,3,4 Emergency Action Level (EAL): 1. Gross Failed Fuel Monitor 1/2RE-PRO06 (1/2 PS206-High energy) indicating 1-135 concentration 
> 5 pCi/cc.OR 2. Sample analysis indicates that: a. Dose Equivalent 1-131 specific coolant activity > 60.0 pCi/gm.OR b. Dose Equivalent XE-133 specific coolant activity>
603.0 pCi/gm.Basis: This IC addresses a reactor coolant activity value that exceeds an allowable limit specified in Technical Specifications.
This condition is a precursor to a more significant event and represents a potential degradation of the level of safety of the plant.Conditions that cause the specified monitor to alarm that are not related to fuel clad degradation should not result in the declaration of an Unusual Event.This EAL addresses site-specific radiation monitor readings that provide indication of a degradation of fuel clad integrity.
An Unusual Event is only warranted when actual fuel clad damage is the cause of the elevated coolant sample activity (as determined by laboratory confirmation).
Fuel clad damage should be assumed to be the cause of elevated Reactor Coolant activity unless another cause is known.Escalation of the emergency classification level would be via ICs FA1 or the Recognition Category R ICs.Basis Reference(s):
: 1. NEI 99-01 Rev 6, SU3 2. Technical Specifications 3.4.16 3. 1/2BOA PRI-4, High Reactor Coolant Activity Unit 1/2 4. PWR Letdown Rad Monitor Setpoint Calculation for Degraded Fuel Indication Month XXXX BY 3-50 EP-AA-1002 (Revision XX)
Rvrnn  Bvrnn Annexv Fyalnn N.rlIanr RECOGNITION CATEGORY FISSION PRODUCT BARRIER DEGRADATION FG1 Initiating Condition:
Loss of ANY Two Barriers AND Loss or Potential Loss of the third barrier.Operating Mode Applicability:
1,2,3,4 Emergency Action Level (EAL): Refer to Fission Product Barrier Loss and Potential Loss threshold values to determine barrier status.Basis: Fuel Cladding, RCS and Containment comprise the fission product barriers.At the General Emergency classification level each barrier is weighted equally.Basis Reference(s):
: 1. NEI 99-01 Rev 6, Table 9-F-3 Month XXXX BY 3-51 EP-AA-1002 (Revision XX)
Rvrnn Annex Pvalnn NiirIanar RECOGNITION CATEGORY FISSION PRODUCT BARRIER DEGRADATION FS1 Initiating Condition:
Loss or Potential Loss of ANY two barriers.Operating Mode Applicability:
1,2,3,4 Emergency Action Level (EAL): Refer to Fission Product Barrier Loss and Potential Loss threshold values to determine barrier status.Basis: Fuel Cladding, RCS and Containment comprise the fission product barriers.At the Site Area Emergency classification level, each barrier is weighted equally.Basis Reference(s):
: 1. NEI 99-01 Rev 6, Table 9-F-3 Month XXXX BY 3-52 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY FISSION PRODUCT BARRIER DEGRADATION FA1 Initiating Condition:
ANY Loss or ANY Potential Loss of either Fuel Clad or RCS.Operating Mode Applicability:
1,2,3,4 Emergency Action Level (EAL): Refer to Fission Product Barrier Loss and Potential Loss threshold values to determine barrier status.Basis: Fuel Cladding, RCS and Containment comprise the fission product barriers.At the Alert classification level, Fuel Cladding and RCS barriers are weighted more heavily than the Containment barrier. Unlike the Containment barrier, loss or potential loss of either the Fuel Cladding or RCS barrier may result in the relocation of radioactive materials or degradation of core cooling capability.
Note that the loss or potential loss of Containment barrier in combination with loss or potential loss of either Fuel Cladding or RCS barrier results in declaration of a Site Area Emergency under EAL FS1.Basis Reference(s):
: 1. NEI 99-01 Rev 6, Table 9-F-3 Month XXXX BY 3-53 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY FISSION PRODUCT BARRIER DEGRADATION FC1 Initiating Condition:
RCS or SG Tube Leakage Operating Mode Applicability:
1,2,3,4 Fission Product Barrier (FPB) Threshold:
POTENTIAL LOSS 1. Core Cooling CSF-Orange Path conditions exist Basis: There is no Loss threshold associated with RCS or SG Tube Leakage.Potential Loss Threshold 
#1 Basis: Core Cooling -ORANGE indicates subcooling has been lost and that some clad damage may occur.Basis Reference(s):
: 1. NEI 99-01 Rev 6, Table 9-F-3 2. 1/2 BFR-C.2 Response to Degraded Core Cooling Unit 1/2 Month XXXX BY 3-54 EP-AA-1002 (Revision XX)
Rurnn Annoy I=Ylnn kir-lanr~irnn Ann~v Fv~Ii~n Mmu~ki~r RECOGNITION CATEGORY FISSION PRODUCT BARRIER DEGRADATION FC2 Initiating Condition:
Inadequate Heat Removal Operating Mode Applicability:
1,2,3,4 Fission Product Barrier (FPB) Threshold:
LOSS 1. Core-Cooling CSF- Red Path conditions exist.POTENTIAL LOSS 2. Core Cooling CSF-Orange Path conditions exist.OR 3. Heat Sink CSF- Red Path conditions exist.Basis: Loss Threshold 
#1 Basis This reading indicates temperatures within the core are sufficient to cause significant superheating of reactor coolant.Core Cooling -RED indicates significant superheating and core uncovery and is considered to indicate loss of the Fuel Clad Barrier.Potential Loss Threshold 
#2 Basis This reading indicates temperatures within the core are sufficient to allow the onset of heat-induced cladding damage.Core Cooling -ORANGE indicates subcooling has been lost and that some clad damage may occur.Potential Loss Threshold 
#3 Basis This condition indicates an extreme challenge to the ability to remove RCS heat using the steam generators (i.e., loss of an effective secondary-side heat sink). This condition represents a potential loss of the Fuel Clad Barrier. The Heat Sink Critical Safety Function Red path condition exists if narrow range levels in all steam generators (S/Gs)are less than or equal to 10% -Unit 1 (31% adverse containment) and 14% -Unit 2 (34% adverse containment) and total feedwater flow to all S/Gs is less than or equal to 500 gpm. In accordance with EOPs, there may be unusual accident conditions during which operators intentionally reduce the heat removal capability of the steam generators by redpCing total feed flow to less than 500 gpm; during these conditions, classification using this threshold is not warranted.
Meeting this threshold results in a Site Area Emergency because this threshold is identical to RCS Barrier RC 2 Potential Loss threshold; both will be met. This condition warrants a Site Area Emergency declaration because inadequate RCS heat removal Month XXXX BY 3-55 EP-AA-1002 (Revision XX)
R rnn Annoy I=%--Inon kii, ,-I---r RECOGNITION CATEGORY FISSION PRODUCT BARRIER DEGRADATION FC2 (cont)Basis (cont): Meeting this threshold results in a Site Area Emergency because this threshold is identical to RCS Barrier RC 2 Potential Loss threshold; both will be met. This condition warrants a Site Area Emergency declaration because inadequate RCS heat removal may result in fuel heat-up sufficient to damage the cladding and rise RCS pressure to the point where mass will be lost from the system.Heat Sink -RED when heat sink is required indicates the ultimate heat sink function is under extreme challenge.
Basis Reference(s):
: 1. NEI 99-01 Rev 6, Table 9-F-3 2. 1/2 BST-2 Core Cooling Unit 1/2 3. 1/2 BFR-C.1 Response to Inadequate Core Cooling Unit 1/2 4 1/2 BFR-C.2 Response to Degraded Core Cooling Unit 1/2 5. 1/2 BST-3 Heat Sink Unit 1/2 6. 1/2 BFR H.1, Response to Loss of Secondary Heat Sink Unit 1/2 Month XXXX BY 3-56 EP-AA-1002 (Revision XX)
R nrnn Annoy P%::Aml, In n NieIgalar Zlll r nn -V lI u,'I*~r RECOGNITION CATEGORY FISSION PRODUCT BARRIER DEGRADATION FC3 Initiating Condition:
Containment Radiation 
/ RCS Activity Operating Mode Applicability:
1,2,3,4 Fission Product Barrier (FPB) Threshold:
LOSS 1. Containment radiation monitor (AR020(21))
reading > 1.95E+03 R/hr.OR 2. Coolant activity as sampled > 3001pCi/gm Dose Equivalent 1-131 Basis: Loss Threshold 
#1 Basis The radiation monitor reading corresponds to an instantaneous release of all reactor coolant mass into the containment, assuming that reactor coolant activity equals 300j.Ci/gm dose equivalent 1-131. Reactor coolant activity above this level is greater than that expected for iodine spikes and corresponds to an approximate range of 2% to 5% fuel clad damage. Since this condition indicates that a significant amount of fuel clad damage has occurred, it represents a loss of the Fuel Clad Barrier.The radiation monitor reading in this threshold is higher than that specified for RCS Barrier RC3 Loss Threshold since it indicates a loss of both the Fuel Clad Barrier and the RCS Barrier. Note that a combination of the two monitor readings appropriately escalates the emergency classification level to a Site Area Emergency.
Loss Threshold 
#2 Basis This threshold indicates that RCS radioactivity concentration is greater than 300 jiCi/gm dose equivalent 1-131. Reactor coolant activity above this level is greater than that expected for iodine spikes and corresponds to an approximate range of 2% to 5% fuel clad damage. Since this condition indicates that a significant amount of fuel clad damage has occurred, it represents a loss of the Fuel Clad Barrier.It is recognized that sample collection and analysis of reactor coolant with highly elevated activity levels could require several hours to complete.
Nonetheless, a sample-related threshold is included as a backup to other indications There is no Potential Loss threshold associated with RCS Activity / Containment Radiation.
Basis Reference(s):
: 1. NEI 99-01 Rev 6, Table 9-F-3 2. S&L calculation BB-ER-02, Rev 0 3. Core Damage Assessment Methodology (CDAM)Month XXXX BY 3-57 EP-AA-1002 (Revision XX)
RBrmn Annoy I~ynlrnn R~,rnn Ann~v Fvalrui Mi .,Ic~r RECOGNITION CATEGORY FISSION PRODUCT BARRIER DEGRADATION FC5 Initiating Condition:
Emergency Director Judgment.Operating Mode Applicability:
1,2,3,4 Fission Product Barrier (FPB) Threshold:
LOSS 1. Any condition in the opinion of the Emergency Director that indicates Loss of the Fuel Clad Barrier.POTENTIAL LOSS 2. Any condition in the opinion of the Emergency Director that indicates Potential Loss of the Fuel Clad Barrier.Basis: Loss Threshold 
#1 Basis This threshold addresses any other factors that may be used by the Emergency Director in determining whether the Fuel Clad Barrier is lost.Potential Loss Threshold 
#2 Basis This threshold addresses any other factors that may be used by the Emergency Director in determining whether the Fuel Clad Barrier is potentially lost. The Emergency Director should also consider whether or not to declare the barrier potentially lost in the event that barrier status cannot be monitored.
Basis Reference(s):
: 1. NEI 99-01 Rev 6, Table 9-F-3 Month XXXX BY 3-58 EP-AA-1002 (Revision XX)
I: rtin Annav I::vglrnn N, i-I-mar RECOGNITION CATEGORY FISSION PRODUCT BARRIER DEGRADATION RC1 Initiating Condition:
RCS or SG Tube Leakage Operating Mode Applicability:
1,2,3,4 Fission Product Barrier (FPB) Threshold:
LOSS 1. Automatic or manual SI actuation is required by EITHER of the following:
: a. UNISOLABLE RCS leakage OR b. Steam Generator tube RUPTURE.POTENTIAL LOSS 2. The capacity of one charging pump in the normal charging mode is exceeded due to EITHER of the following:
: a. UNISOLABLE RCS leakage OR b. Steam Generator tube RUPTURE.OR 3. RCS Integrity CSF- Red Path conditions exist.Basis: UNISOLABLE:
An open or breached system line that cannot be isolated, remotely or locally.RUPTURE(D):
The condition of a steam generator in which primary-to-secondary leakage is of sufficient magnitude to require a safety injection.
FAULTED: The term applied to a steam generator that has a steam leak on the secondary side of sufficient size to cause an uncontrolled drop in steam generator pressure or the steam generator to become completely depressurized.
Loss Threshold 
#1 Basis This threshold is based on an UNISOLABLE RCS leak of sufficient size to require an automatic or manual actuation of the Emergency Core Cooling System (ECCS). This condition clearly represents a loss of the RCS Barrier.This threshold is applicable to unidentified and pressure boundary leakage, as well as identified leakage. It is also applicable to UNISOLABLE RCS leakage through an interfacing system. The mass loss may be into any location -inside containment, to the secondary-side (i.e., steam generator tube leakage) or outside of containment.
Month XXXX BY 3-59 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY FISSION PRODUCT BARRIER DEGRADATION RC1 (cont)Basis (cont): A steam generator with primary-to-secondary leakage of sufficient magnitude to require a safety injection is considered to be RUPTURED.
If a RUPTURED steam generator is also FAULTED outside of containment, the declaration escalates to a Site Area Emergency since the Containment Barrier CT1 Loss threshold will also be met.Potential Loss Threshold 
#2 Basis This threshold is based on an UNISOLABLE RCS leak that results in the inability to maintain pressurizer level within specified limits by operation of a normally used charging (makeup) pump, but an ECCS (SI) actuation has not occurred.
The threshold is met when an operating procedure, or operating crew supervision, directs that a standby charging (makeup) pump be placed in service to restore and maintain pressurizer level.This threshold is applicable to unidentified and pressure boundary leakage, as well as identified leakage. It is also applicable to UNISOLABLE RCS leakage through an interfacing system. The mass loss may be into any location -inside containment, to the secondary-side (i.e., steam generator tube leakage) or outside of containment.
If a leaking steam generator is also FAULTED outside of containment, the declaration escalates to a Site Area Emergency since the Containment Barrier CT1 Loss Threshold will also be met.Potential Loss Threshold 
#3 Basis This condition indicates an extreme challenge to the integrity of the RCS pressure boundary due to pressurized thermal shock -a transient that causes rapid RCS cooldown while the RCS is in Mode 3 or higher (i.e., hot and pressurized).
RCS Integrity 
-RED indicates an extreme challenge to the safety function derived from appropriate instrument readings.Basis Reference(s):
: 1. NEI 99-01 Rev 6, Table 9-F-3 2. NES-G-14.02, Calculation No. BYR99-010 
/ BRW-99-0017-1
: 3. 1/2 BEP-0 Reactor Trip Or Safety Injection Unit 1/2 4. 1/2 BEP-3 Steam Generator Tube Rupture Unit 1/2 5. 1/2 BST-2 Core Cooling Unit 1/2 6. 1/2 BFR-C.1 Response to Inadequate Core Cooling Unit 1/2 7. NES-G-14.02, Calculation No. BYR99-010 
/ BRW-99-0017-1
: 8. UFSAR Fig. 6.3-4 Month XXXX BY 3-60 EP-AA-1002 (Revision XX)
Ft rr~n Annav Fi:ninn N~hmlrnr a RECOGNITION CATEGORY FISSION PRODUCT BARRIER DEGRADATION RC2 Initiating Condition:
Inadequate Heat Removal Operating Mode Applicability:
1,2,3,4 Fission Product Barrier (FPB) Threshold:
POTENTIAL LOSS Heat Sink CSF- Red Path conditions exist.Basis: There is no Loss threshold associated with Inadequate Heat Removal.Potential Loss Threshold Basis Heat Sink -RED when heat sink is required indicates the ultimate heat sink function is under extreme challenge.
This condition indicates an extreme challenge to the ability to remove RCS heat using the steam generators (i.e., loss of an effective secondary-side heat sink). This condition represents a potential loss of the RCS Barrier. The Heat Sink Critical Safety Function Red path condition exists if narrow range levels in all steam generators (S/Gs) are less than or equal to 10% -Unit 1 (31% adverse containment) and 14% -Unit 2 (34%adverse containment) and total feedwater flow to all S/Gs is less than or equal to 500 gpm. In accordance with EOPs, there may be unusual accident conditions during which operators intentionally reduce the heat removal capability of the steam generators by redpCing total feed flow to less than 500 gpm; during these conditions, classification using this threshold is not warranted.
Meeting this threshold results in a Site Area Emergency because this threshold is identical to Fuel Clad Barrier FC2 Potential Loss threshold 
# 3; both will be met. This condition warrants a Site Area Emergency declaration because inadequate RCS heat removal may result in fuel heat-up sufficient to damage the cladding and rise RCS pressure to the point where mass will be lost from the system.Basis Reference(s):
: 1. NEI 99-01 Rev 6, Table 9-F-3 2. 1/2 BST-3 Heat Sink Unit 1/2 Month XXXX BY 3-61 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear B-ron Annex Exelon Nuclear RECOGNITION CATEGORY FISSION PRODUCT BARRIER DEGRADATION RC3 Initiating Condition:
Containment Radiation 
/ RCS Activity Operating Mode Applicability:
1,2,3,4 Fission Product Barrier (FPB) Threshold:
LOSS Containment radiation monitor (AR020(21))
reading > 25 R/hr.Basis: Loss Threshold Basis The radiation monitor reading corresponds to an instantaneous release of all reactor coolant mass into the containment, assuming that reactor coolant activity equals Technical Specification allowable limits. This value is lower than that specified for Fuel Clad Barrier FC3 Loss Threshold 
#1 since it indicates a loss of the RCS Barrier only.There is no Potential Loss threshold associated with RCS Activity / Containment Radiation.
Basis Reference(s):
: 1. NEI 99-01 Rev 6, Table 9-F-3 Month XXXX BY 3-62 EP-AA-1002 (Revision XX)
R rnn Annoy IMv-Innn Nhio-lmr RECOGNITION CATEGORY FISSION PRODUCT BARRIER DEGRADATION RC5 Initiating Condition:
Emergency Director Judgment.Operating Mode Applicability:
1,2,3,4 Fission Product Barrier (FPB) Threshold:
LOSS 1. Any condition in the opinion of the Emergency Director that indicates Loss of the RCS Barrier.POTENTIAL LOSS 2. Any condition in the opinion of the Emergency Director that indicates Potential Loss of the RCS Barrier.Basis: Loss Threshold 
#1 Basis This threshold addresses any other factors that may be used by the Emergency Director in determining whether the RCS Barrier is lost.Potential Loss Threshold 
#2 Basis This threshold addresses any other factors that may be used by the Emergency Director in determining whether the RCS Barrier is potentially lost. The Emergency Director should also consider whether or not to declare the barrier potentially lost in the event that barrier status cannot be monitored.
Basis Reference(s):
: 1. NEI 99-01 Rev 6, Table 9-F-3 Month XXXX BY 3-63 EP-AA-1002 (Revision XX)
I=xelon Nuclear Byron Annex Exelon Nuclear RECOGNITION CATEGORY FISSION PRODUCT BARRIER DEGRADATION CT1 Initiating Condition:
RCS or SG Tube Leakage Operating Mode Applicability:
1,2,3,4 Fission Product Barrier (FPB) Threshold:
LOSS A leaking or RUPTURED SG is FAULTED outside of containment.
Basis: RUPTURE(D):
The condition of a steam generator in which primary-to-secondary leakage is of sufficient magnitude to require a safety injection.
FAULTED: The term applied to a steam generator that has a steam leak on the secondary side of sufficient size to cause an uncontrolled drop in steam generator pressure or the steam generator to become completely depressurized.
Loss Threshold Basis This threshold addresses a leaking or RUPTURED Steam Generator (SG) that is also FAULTED outside of containment.
The condition of the SG, whether leaking or RUPTURED, is determined in accordance with the thresholds for RCS Barrier RC1 Potential Loss Threshold 2.b and Loss Threshold 1.b, respectively.
This condition represents a bypass of the containment barrier.FAULTED is a defined term within the NEI 99-01 methodology; this determination is not necessarily dependent upon entry into, or diagnostic steps within, an EOP. For example, if the pressure in a steam generator is decreasing uncontrollably 
[part of the FAULTED definition]
and the faulted steam generator isolation procedure is not entered because EOP user rules are dictating implementation of another procedure to address a higher priority condition, the steam generator is still considered FAULTED for emergency classification purposes.The FAULTED criterion establishes an appropriate lower bound on the size of a steam release that may require an emergency classification.
Steam releases of this size are readily observable with normal Control Room indications.
The lower bound for this aspect of the containment barrier is analogous to the lower bound criteria specified in IC RU3 for the fuel clad barrier (i.e., RCS activity values) and IC MU6 for the RCS barrier (i.e., RCS leak rate values).This threshold also applies to prolonged steam releases necessitated by operational considerations such as the forced steaming of a leaking or RUPTURED steam generator directly to atmosphere to cooldown the plant, or to drive an auxiliary (emergency) feed water pump. These types of conditions will result in a significant and Month XXXX BY 3-64 EP-AA-1002 (Revision XX)
Byron Annex I=xelon Nuclear Byron Annex Exelon Nuclear RECOGNITION CATEGORY FISSION PRODUCT BARRIER DEGRADATION CT1 (cont)Basis (cont): sustained release of radioactive steam to the environment (and are thus similar to a FAULTED condition).
The inability to isolate the steam flow without an adverse effect on plant cooldown meets the intent of a loss of containment.
Steam releases associated with the expected operation of a SG power operated relief valve or safety relief valve do not meet the intent of this threshold.
Such releases may occur intermittently for a short period of time following a reactor trip as operators process through emergency operating procedures to bring the plant to a stable condition and prepare to initiate a plant cooldown.
Steam releases associated with the unexpected operation of a valve (e.g., a stuck-open safety valve) do meet this threshold.
Following an SG tube leak or rupture, there may be minor radiological releases through a secondary-side system component (e.g., air ejectors, glad seal exhausters, valve packing, etc.). These types of releases do not constitute a loss or potential loss of containment but should be evaluated using the Recognition Category R lCs.The emergency classification levels resulting from primary-to-secondary leakage, with or without a steam release from the FAULTED SG, are summarized below.Affected SG is FAULTED Outside of Containment?
Yes No Primary-to-Secondary Leak Rate Less than or equal to 25 gpm Greater than 25 gpm The capacity of one charging pump in the normal charging mode is exceeded (RCS Barrier Potential Loss)Requires an automatic or manual SI actuation (RCS Barrier Loss)No classification Unusual Event per MU6 Site Area Emergency per FS1 Site Area Emergency per FS1 No classification Unusual Event per MU6 Alert per FA1 Alert per FA1 There is no Potential Loss threshold associated with RCS or SG Tube Leakage.Month XXXX BY 3-65 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY FISSION PRODUCT BARRIER DEGRADATION CTM (cont)Basis Reference(s):
: 1. NEI 99-01 Rev 6, Table 9-F-3 2. 1/2 BEP-0 Reactor Trip Or Safety Injection Unit 1/2 3. 1/2 BEP-3 Steam Generator Tube Rupture Unit 1/2 4. 1/2 BOA SEC-8 Steam Generator Tube Leak Unit 1/2 Month XXXX BY 3-66 EP-AA-1002 (Revision XX)
Byron Annex Fxelnn  Bvron Annex FvAlnn Nucler~I RECOGNITION CATEGORY FISSION PRODUCT BARRIER DEGRADATION CT2 Initiating Condition:
Inadequate Heat Removal Operating Mode Applicability:
1,2,3,4 Fission Product Barrier (FPB) Threshold:
POTENTIAL LOSS Core-Cooling CSF- Red Path conditions exist AND Functional Restoration procedures not effective in < 15 minutes.Basis: IMMINENT:
The trajectory of events or conditions is such that an EAL will be met within a relatively short period of time regardless of mitigation or corrective actions.There is no Loss threshold associated with Inadequate Heat Removal.Potential Loss Threshold Basis This condition represents an IMMINENT core melt sequence which, if not corrected, could lead to vessel failure and an increased potential for containment failure. For this condition to occur, there must already have been a loss of the RCS Barrier and the Fuel Clad Barrier. If implementation of a procedure(s) to restore adequate core cooling is not effective (successful) within 15 minutes, it is assumed that the event trajectory will likely lead to core melting and a subsequent challenge of the Containment Barrier.The restoration procedure is considered "effective" if core exit thermocouple readings are decreasing and/or if reactor vessel level is increasing.
Whether or not the procedure(s) will be effective should be apparent within 15 minutes. The Emergency Director should escalate the emergency classification level as soon as it is determined that the procedure(s) will not be effective.
Severe accident analyses (e.g., NUREG-1 150) have concluded that function restoration procedures can arrest core degradation in a significant fraction of core damage scenarios, and that the likelihood of containment failure is very small in these events.Given this, it is appropriate to provide 15 minutes beyond the required entry point to determine if procedural actions can reverse the core melt sequence.Basis Reference(s):
: 1. NEI 99-01 Rev 6, Table 9-F-3 2. 1/2 BST-2 Core Cooling Unit 1/2 3. 1/2 BFR-C.1 Response to Inadequate Core Cooling Unit 1/2 Month XXXX BY 3-67 EP-AA-1002 (Revision XX)
Rvrnn Annpx Burnn Annex Pvalnn NiituIanr RECOGNITION CATEGORY FISSION PRODUCT BARRIER DEGRADATION CT3 Initiating Condition:
Containment Radiation 
/ RCS Activity Operating Mode Applicability:
1,2,3,4 Fission Product Barrier (FPB) Threshold:
POTENTIAL LOSS Containment radiation monitor (AR020(21))
reading > 4.40E+03 R/hr.Basis: There is no Loss threshold associated with RCS Activity / Containment Radiation.
Potential Loss Threshold Basis The radiation monitor reading corresponds to an instantaneous release of all reactor coolant mass into the containment, assuming that 20% of the fuel cladding has failed.This level of fuel clad failure is well above that used to determine the analogous Fuel Clad Barrier Loss and RCS Barrier Loss thresholds.
NUREG-1228, Source Estimations During Incident Response to Severe Nuclear Power Plant Accidents, indicates the fuel clad failure must be greater than approximately 20%in order for there to be a major release of radioactivity requiring offsite protective actions. For this condition to exist, there must already have been a loss of the RCS Barrier and the Fuel Clad Barrier. It is therefore prudent to treat this condition as a potential loss of containment which would then escalate the emergency classification level to a General Emergency.
Basis Reference(s):
: 1. NEI 99-01 Rev 6, Table 9-F-3 2. Core Damage Assessment Methodology (CDAM)Month XXXX BY 3-68 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear yr-n Annex...Exelon Nuclear RECOGNITION CATEGORY FISSION PRODUCT BARRIER DEGRADATION CT4 Initiating Condition:
Containment Integrity or Bypass Operating Mode Applicability:
1,2,3,4 Fission Product Barrier (FPB) Threshold:
LOSS 1. Containment isolation is required and EITHER of the following:
: a. UNPLANNED lowering in containment pressure or rise in radiation monitor readings outside of containment in the Emergency Directors judgment indicate a loss of containment integrity.
OR b. UNISOLABLE pathway from containment to the environment exists.OR 2. Indication of RCS leakage outside of containment POTENTIAL LOSS 3. Containment CSF Red Path conditions exist.OR 4. Hydrogen Concentration in Containment 
> 5%.OR 5. a. Containment pressure > 20 psig AND b. Less than one full train of Containment Spray is operating per design for>15 minutes.Basis: FAULTED: The term applied to a steam generator that has a steam leak on the secondary side of sufficient size to cause an uncontrolled drop in steam generator pressure or the steam generator to become completely depressurized.
UNISOLABLE:
An open or breached system line that cannot be isolated, remotely or locally.UNPLANNED:
A parameter change or an event that is not 1) the result of an intended evolution or 2) an expected plant response to a transient.
The cause of the parameter change or event may be known or unknown.Month XXXX BY 3-69 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY FISSION PRODUCT BARRIER DEGRADATION CT4 (cont)Basis (cont): Loss Threshold 
#1 Basis These thresholds address a situation where containment isolation is required and one of two conditions exists as discussed below. Users are reminded that there may be accident and release conditions that simultaneously meet both loss thresholds 1.a and 1.b.1.a -Containment integrity has been lost, i.e., the actual containment atmospheric leak rate likely exceeds that associated with allowable leakage (or sometimes referred to as design leakage).
Following the release of RCS mass into containment, containment pressure will fluctuate based on a variety of factors; a loss of containment integrity condition may (or may not) be accompanied by a noticeable drop in containment pressure.
Recognizing the inherent difficulties in determining a containment leak rate during accident conditions, it is expected that the Emergency Director will assess this threshold using judgment, and with due consideration given to current plant conditions, and available operational and radiological data (e.g., containment pressure, readings on radiation monitors outside containment, operating status of containment pressure control equipment, etc.).Refer to the middle piping run of Figure 3-F-1. Two simplified examples are provided.One is leakage from a penetration and the other is leakage from an in-service system valve. Depending upon radiation monitor locations and sensitivities, the leakage could be detected by any of the four monitors depicted in the figure.Another example would be a loss or potential loss of the RCS barrier, and the simultaneous occurrence of two FAULTED locations on a steam generator where one fault is located inside containment (e.g., on a steam or feedwater line) and the other outside of containment.
In this case, the associated steam line provides a pathway for the containment atmosphere to escape to an area outside the containment.
Following the leakage of RCS mass into containment and a rise in containment pressure, there may be minor radiological releases associated with allowable (design)containment leakage through various penetrations or system components.
These releases do not constitute a loss or potential loss of containment but should be evaluated using the Recognition Category R ICs.I.b -Conditions are such that there is an UNISOLABLE pathway for the migration of radioactive material from the containment atmosphere to the environment.
As used here, the term "environment" includes the atmosphere of a room or area, outside the containment, that may, in turn, communicate with the outside-the-plant atmosphere (e.g., through discharge of a ventilation system or atmospheric leakage).
Depending upon a variety of factors, this condition may or may not be accompanied by a noticeable drop in containment pressure.Month XXXX BY 3-70 EP-AA-1002 (Revision XX)
R rnn Annav I=v-mlInn N, ,&-I,2r Riirnn Ann~v Fv~Ir~n Mi ivIb~r RECOGNITION CATEGORY FISSION PRODUCT BARRIER DEGRADATION CT4 (cont)Basis (cont): Refer to the top piping run of Figure 3-F-1. In this simplified example, the inboard and outboard isolation valves remained open after a containment isolation was required (i.e., containment isolation was not successful).
There is now an UNISOLABLE pathway from the containment to the environment.
The existence of a filter is not considered in the threshold assessment.
Filters do not remove fission product noble gases. In addition, a filter could become ineffective due to iodine and/or particulate loading beyond design limits (i.e., retention ability has been exceeded) or water saturation from steam/high humidity in the release stream.Leakage between two interfacing liquid systems, by itself, does not meet this threshold.
Refer to the bottom piping run of Figure 3-F-1. In this simplified example, leakage in an RCP seal cooler is allowing radioactive material to enter the Auxiliary Building.
The radioactivity would be detected by the Process Monitor. If there is no leakage from the closed water cooling system to the Auxiliary Building, then no threshold has been met.If the pump or system piping developed a leak that allowed steam/water to enter the Auxiliary Building, then loss threshold 2 would be met. Depending upon radiation monitor locations and sensitivities, this leakage could be detected by any of the four monitors depicted in the figure and cause threshold 1.a to be met as well.Following the leakage of RCS mass into containment and a rise in containment pressure, there may be minor radiological releases associated with allowable (design)containment leakage through various penetrations or system components.
Minor releases may also occur if a containment isolation valve(s) fails to close but the containment atmosphere escapes to a closed system. These releases do not constitute a loss or potential loss of containment but should be evaluated using the Recognition Category R ICs.The status of the containment barrier during an event involving steam generator tube leakage is assessed using Containment Barrier CT1 Loss Threshold.
Loss Threshold 
#2 Basis Containment sump, temperature, pressure and/or radiation levels will rise if reactor coolant mass is leaking into the containment.
If these parameters have not increased, then the reactor coolant mass may be leaking outside of containment (i.e., a containment bypass sequence).
Rises in sump, temperature, pressure, flow and/or radiation level readings outside of the containment may indicate that the RCS mass is being lost outside of containment.
Unexpected elevated readings and alarms on radiation monitors with detectors outside containment should be corroborated with other available indications to confirm that the source is a loss of RCS mass outside of containment.
If the fuel clad barrier has not been lost, radiation monitor readings outside of containment may not rise significantly; however, other unexpected changes in sump levels, area temperatures or pressures, flow rates, etc. should be sufficient to determine if RCS mass is being lost outside of the containment.
Month XXXX BY 3-71 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY FISSION PRODUCT BARRIER DEGRADATION CT4 (cont)Basis (cont): Refer to the middle piping run of Figure 3-F-1. In this simplified example, a leak has occurred at a reducer on a pipe carrying reactor coolant in the Auxiliary Building.Depending upon radiation monitor locations and sensitivities, the leakage could be detected by any of the four monitors depicted in the figure and cause loss threshold I.a to be met as well.To ensure proper escalation of the emergency classification, the RCS leakage outside of containment must be related to the mass loss that is causing the RCS Barrier RC1 Loss Threshold I.a and/or Potential Loss threshold 2.a to be met.Potential Loss Threshold 
#3 Basis Containment CSF RED path indicates an extreme challenge to the safety function derived from appropriate instrument readings and/or sampling results, and thus represents a potential loss of containment.
If containment pressure exceeds the design pressure, there exists a potential to lose the Containment Barrier. To reach this level, there must be an inadequate core cooling condition for an extended period of time; therefore, the RCS and Fuel Clad barriers would already be lost. Thus, this threshold is a discriminator between a Site Area Emergency and General Emergency since there is now a potential to lose the third barrier.Potential Loss Threshold 
#4 Basis The existence of an explosive mixture means, at a minimum, that the containment atmospheric hydrogen concentration is sufficient to support a hydrogen burn (i.e., at the lower deflagration limit). A hydrogen burn will raise containment pressure and could result in collateral equipment damage leading to a loss of containment integrity.
It therefore represents a potential loss of the Containment Barrier.Potential Loss Threshold 
#5 Basis This threshold describes a condition where containment pressure is greater than the set point at which containment energy (heat) removal systems are designed to automatically actuate, and less than one full train of equipment is capable of operating per design. The 15-minute criterion is included to allow operators time to manually start equipment that may not have automatically started, if possible.
This threshold represents a potential loss of containment in that containment heat removal/depressurization systems (e.g., containment sprays, ice condenser fans, etc., but not including containment venting strategies) are either lost or performing in a degraded manner.Month XXXX BY 3-72 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY FISSION PRODUCT BARRIER DEGRADATION CT4 (cont)Basis Reference(s):
: 1. NEI 99-01 Rev 6, Table 9-F-3 2. UFSAR Section 15.6.5.2.1
: 3. NES-G-14.02, Calculation No. BYR99-010 
/ BRW-99-0017-1
: 4. Technical Specifications B 3.6.6, Containment Spray and Cooling Systems 5. 1/2BST-5 Containment Unit 1/2 Month XXXX BY 3-73 EP-AA-1002 (Revision XX)
Byror& ex Exelo cilear RECOGNITION CATEGORY FISSION PRODUCT BARRIER DEGRADATION Figure 3-F-1: PWR Containment Integrity or Bypass Examples...... 1.b -Airborne* : release from **. pathway t. ..Ve n t. ..RCP Seal Cooling Month XXXX BY 3-74 EP-AA-1002 (Revision XX)
Rvrnn Annoytdiiilhar RECOGNITION CATEGORY FISSION PRODUCT BARRIER DEGRADATION CT5 Initiating Condition:
Emergency Director Judgment.Operating Mode Applicability:
1,2,3,4 Fission Product Barrier (FPB) Threshold:
LOSS 1. Any condition in the opinion of the Emergency Director that indicates Loss of the Containment Barrier.POTENTIAL LOSS 2. Any condition in the opinion of the Emergency Director that indicates Potential Loss of the Containment Barrier.Basis: Loss Threshold 
#1 Basis This threshold addresses any other factors that may be used by the Emergency Director in determining whether the Containment Barrier is lost.Potential Loss Threshold 
#2 Basis This threshold addresses any other factors that may be used by the Emergency Director in determining whether the Containment Barrier is potentially lost. The Emergency Director should also consider whether or not to declare the barrier potentially lost in the event that barrier status cannot be monitored.
Basis Reference(s):
: 1. NEI 99-01 Rev 6, Table 9-F-3 Month XXXX BY 3-75 EP-AA-1002 (Revision XX)
Byron Annex Byron Annex Exelon Nuclear RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MG1 Initiating Condition:
Prolonged loss of all offsite and all onsite AC power to emergency buses.Operating Mode Applicability:
1,2,3,4 Emergency Action Level (EAL): Note:* The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.1. Loss of ALL offsite AC power to unit ESF buses.AND 2. Failure of DG 1A(2A) and DG 1B(2B) emergency diesel generators to supply power to unit ESF buses.AND 3. EITHER of the following:
: a. Restoration of at least one unit ESF bus in < 4 hours is not likely.OR b. Core Cooling CSF -Red Path conditions exist.Basis: SAFETY SYSTEM: A system required for safe plant operation, cooling down the plant and/or placing it in the cold shutdown condition, including the ECCS. These are typically systems classified as safety-related.
This IC addresses a prolonged loss of all power sources to AC emergency buses. A loss of all AC power compromises the performance of all SAFETY SYSTEMS requiring electric power including those necessary for emergency core cooling, containment heat removal/pressure control, spent fuel heat removal and the ultimate heat sink. A prolonged loss of these buses will lead to a loss of any fission product barriers.
In addition, fission product barrier monitoring capabilities may be degraded under these conditions.
The EAL should require declaration of a General Emergency prior to meeting the thresholds for IC FG1. This will allow additional time for implementation of offsite protective actions.Escalation of the emergency classification from Site Area Emergency will occur if it is projected that power cannot be restored to at least one AC emergency bus by the end of the analyzed station blackout coping period. Beyond this time, plant responses and Month XXXX BY 3-76 EP-AA-1002 (Revision XX)
R re~n Anng-v=,:vg%-Inr Ki, ,rlgnnr RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MG1 (cont)Basis (cont): event trajectory are subject to greater uncertainty, and there is an increased likelihood of challenges to multiple fission product barriers.The estimate for restoring at least one emergency bus should be based on a realistic appraisal of the situation.
Mitigation actions with a low probability of success should not be used as a basis for delaying a classification upgrade. The goal is to maximize the time available to prepare for, and implement, protective actions for the public.The emergency buses of the affected unit can be powered from the unaffected unit through the crosstie breakers.
Unit crosstie is considered an adequate source of offsite power when evaluating this EAL.The EAL will also require a General Emergency declaration if the loss of AC power results in parameters that indicate an inability to adequately remove decay heat from the core..Basis Reference(s):
: 1. NEI 99-01 Rev 6, SG1 2. 20E-0-4001 Station One Line Diagram 3. UFSAR 8.3.1 4. 1/2 BOA ELEC-3 Loss Of 4KV ESF Bus Unit 1/2 5. 1/2 BOA ELEC-4 Loss Of Offsite Power Unit 1/2 6. 1/2 BCA-0.0 Loss Of All AC Power Unit 1/2 7. 1/2 BCA-0.1 Loss Of All AC Power Recovery Without SI Required Unit 1/2 8. 1/2 BCA-0.2 Loss Of All AC Power Recovery With SI Required Unit 1/2 9. 1/2 BCA-0.3 Response To Opposite Unit Loss Of All AC Power Unit 1/2 10. BOP AP-51, Isolating Unit 1 System AUX Transformer 142-1 & 142-2 While Unit Is At Power 11. BOP AP-52, Restoring Unit 1 System AUX Transformer 142-1 & 142-2 During Power Operation 12. BOP AP-53, Isolating Unit 2 System AUX Transformer 242-1 & 242-2 While Unit Is At Power 13. BOP AP-54, Restoring Unit 2 System AUX Transformer 242-1 & 242-2 During Power Operation 14. Safety Evaluations of the Byron Station and Byron Station Responses to the Station Blackout (SBO) Rule (TAC NOS. 68522, 68523 AND 68515, 68516)15. 1/2 BST-2 Core Cooling Unit 1/2 16. 1/2 BFR-C.1 Response to Inadequate Core Cooling Unit 1/2 17. 1/2 BFR-C.2 Response to Degraded Core Cooling Unit 1/2 Month XXXX BY 3-77 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MS1 Initiating Condition:
Loss of all offsite and all onsite AC power to emergency buses for 15 minutes or longer.Operating Mode Applicability:
1,2,3,4 Emergency Action Level (EAL): Note:* The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.1. Loss of ALL offsite AC Power to unit ESF buses.AND 2. Failure of DG 1A(2A) and DG 1B(2B) emergency diesel generators to supply power to unit ESF buses.AND 3. Failure to restore power to at least one unit ESF bus in < 15 minutes from the time of loss of both offsite and onsite AC power Basis: SAFETY SYSTEM: A system required for safe plant operation, cooling down the plant and/or placing it in the cold shutdown condition, including the ECCS. These are typically systems classified as safety-related.
This IC addresses a total loss of AC power that compromises the performance of all SAFETY SYSTEMS requiring electric power including those necessary for emergency core cooling, containment heat removal/pressure control, spent fuel heat removal and the ultimate heat sink. In addition, fission product barrier monitoring capabilities may be degraded under these conditions.
This IC represents a condition that involves actual or likely major failures of plant functions needed for the protection of the public.The emergency buses of the affected unit can be powered from the unaffected unit through the crosstie breakers.
Unit crosstie is considered an adequate source of offsite power when evaluating this EAL.Fifteen minutes was selected as a threshold to exclude transient or momentary power losses.Escalation of the emergency classification level would be via ICs RG1, FG1 or MGI.Month XXXX BY 3-78 EP-AA-1002 (Revision XX)
Byron Annex Exelan Nuclear RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MS1 (cont)Basis Reference(s):
: 1. NEI 99-01 Rev 6, SS1 2. 20E-0-4001 Station One Line Diagram 3. UFSAR 8.3.1 4. 1/2 BOA ELEC-3 Loss Of 4KV ESF Bus Unit 1/2 5. 1/2 BOA ELEC-4 Loss Of Offsite Power Unit 1/2 6. 1/2 BCA-0.0 Loss Of All AC Power Unit 1/2 7. 1/2 BCA-0.1 Loss Of All AC Power Recovery Without SI Required Unit 1/2 8. 1/2 BCA-0.2 Loss Of All AC Power Recovery With SI Required Unit 1/2 9. 1/2 BCA-0.3 Response To Opposite Unit Loss Of All AC Power Unit 1/2 10. BOP AP-51, Isolating Unit 1 System AUX Transformer 142-1 & 142-2 While Unit Is At Power 11. BOP AP-52, Restoring Unit 1 System AUX Transformer 142-1 & 142-2 During Power Operation 12. BOP AP-53, Isolating Unit 2 System AUX Transformer 242-1 & 242-2 While Unit Is At Power 13. BOP AP-54, Restoring Unit 2 System AUX Transformer 242-1 & 242-2 During Power Operation 14. Safety Evaluations of the Byron Station and Byron Station Responses to the Station Blackout (SBO) Rule (TAC NOS. 68522, 68523 AND 68515, 68516)Month XXXX BY 3-79 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear r Annex.......Exelon Nuclear RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MAI Initiating Condition:
Loss of all but one AC power source to emergency buses for 15 minutes or longer.Operating Mode Applicability:
1,2,3,4 Emergency Action Level (EAL): Note:* The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.1. AC power capability to unit ESF buses reduced to only one of the following power sources for > 15 minutes.* Affected unit SAT 142-1(242-1)
* Affected unit SAT 142-2(242-2)
* Emergency Diesel Generator DG 1A(2A)* Emergency Diesel Generator DG 1 B(2B)* Unit crosstie breakers AND 2. Any additional single power source failure will result in a loss of ALL AC power to SAFETY SYSTEMS.Basis: SAFETY SYSTEM: A system required for safe plant operation, cooling down the plant and/or placing it in the cold shutdown condition, including the ECCS. These are typically systems classified as safety-related.
This IC describes a significant degradation of offsite and onsite AC power sources such that any additional single failure would result in a loss of all AC power to SAFETY SYSTEMS. In this condition, the sole AC power source may be powering one, or more than one, train of safety-related equipment.
This IC provides an escalation path from IC MUl.An "AC power source" is a source recognized in AOPs and EOPs, and capable of supplying required power to an emergency bus. Some examples of this condition are presented below.9 A loss of all offsite power with a concurrent failure of all but one emergency power source (e.g., an onsite diesel generator).
Month XXXX BY 3-80 EP-AA-1002 (Revision XX)
Rvrnn Annex Bvrnn Annex Exelnn NuclerIAi RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MA1 (cont)Basis (cont): " A loss of all offsite power and loss of all emergency power sources (e.g., onsite diesel generators) with a single train of emergency buses being back-fed from the unit main generator." A loss of emergency power sources (e.g., onsite diesel generators) with a single train of emergency buses being back-fed from an offsite power source.Fifteen minutes was selected as a threshold to exclude transient or momentary losses of power.Escalation of the emergency classification level would be via IC MS1.Basis Reference(s):
: 1. NEI 99-01 Rev 6, SA1 2. 20E-0-4001 Station One Line Diagram 3. UFSAR 8.3.1 4. 1/2 BOA ELEC-3 Loss Of 4KV ESF Bus Unit 1/2 5. 1/2 BOA ELEC-4 Loss Of Offsite Power Unit 1/2 6. 1/2 BCA-0.0 Loss Of All AC Power Unit 1/2 7. 1/2 BCA-0.1 Loss Of All AC Power Recovery Without SI Required Unit 1/2 8. 1/2 BCA-0.2 Loss Of All AC Power Recovery With SI Required Unit 1/2 9. 1/2 BCA-0.3 Response To Opposite Unit Loss Of All AC Power Unit 1/2 10. BOP AP-51, Isolating Unit 1 System AUX Transformer 142-1 & 142-2 While Unit Is At Power 11. BOP AP-52, Restoring Unit 1 System AUX Transformer 142-1 & 142-2 During Power Operation 12. BOP AP-53, Isolating Unit 2 System AUX Transformer 242-1 & 242-2 While Unit Is At Power 13. BOP AP-54, Restoring Unit 2 System AUX Transformer 242-1 & 242-2 During Power Operation 14. Safety Evaluations of the Byron Station and Byron Station Responses to the Station Blackout (SBO) Rule (TAG NOS. 68522, 68523 AND 68515, 68516)Month XXXX BY 3-81 EP-AA-1002 (Revision XX)
P rin Annv I= km..t-I^r RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MUl Initiating Condition:
Loss of all offsite AC power capability to emergency buses for 15 minutes or longer.Operating Mode Applicability:
1,2,3,4 Emergency Action Level (EAL): Note:* The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.Loss of ALL offsite AC power capability to unit ESF buses for > 15 minutes.Basis: This IC addresses a prolonged loss of offsite power. The loss of offsite power sources renders the plant more vulnerable to a complete loss of power to AC emergency buses.This condition represents a potential reduction in the level of safety of the plant.For emergency classification purposes, "capability" means that an offsite AC power source(s) is available to the emergency buses, whether or not the buses are powered from it. (e.g. unit cross-tie breakers)The emergency buses of the affected unit can be powered from the unaffected unit through the crosstie breakers.
Unit crosstie is considered an adequate source of offsite power when evaluating this EAL.Fifteen minutes was selected as a threshold to exclude transient or momentary losses of offsite power.Escalation of the emergency classification level would be via IC MA1.Month XXXX BY 3-82 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MUI (cont)Basis Reference(s):
: 1. NEI 99-01 Rev 6, SU1 2. 20E-0-4001 Station One Line Diagram 3. UFSAR 8.3.1 4. 1/2 BOA ELEC-3 Loss Of 4KV ESF Bus Unit 1/2 5. 1/2 BOA ELEC-4 Loss Of Offsite Power Unit 1/2 6. 1/2 BCA-0.0 Loss Of All AC Power Unit 1/2 7. 1/2 BCA-0.1 Loss Of All AC Power Recovery Without SI Required Unit 1/2 8. 1/2 BCA-0.2 Loss Of All AC Power Recovery With SI Required Unit 1/2 9. 1/2 BCA-0.3 Response To Opposite Unit Loss Of All AC Power Unit 1/2 10. BOP AP-51, Isolating Unit 1 System AUX Transformer 142-1 & 142-2 While Unit Is At Power 11. BOP AP-52, Restoring Unit 1 System AUX Transformer 142-1 & 142-2 During Power Operation 12. BOP AP-53, Isolating Unit 2 System AUX Transformer 242-1 & 242-2 While Unit Is At Power 13. BOP AP-54, Restoring Unit 2 System AUX Transformer 242-1 & 242-2 During Power Operation Month XXXX BY 3-83 EP-AA-1002 (Revision XX)
Byron Annex I=xelon Nuclear Bvr-n Annex Ex...n Nucl.ear RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MG2 Initiating Condition:
Loss of all AC and Vital DC power sources for 15 minutes or longer.Operating Mode Applicability:
1,2,3,4 Emergency Action Level (EAL): Note:* The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.1. Loss of ALL offsite AC power to unit ESF buses.AND.2. Failure of DG 1A(2A) and DG 1B(2B) emergency diesel generators to supply power to unit ESF buses.AND 3. Voltage is < 108 VDC on unit 125 VDC battery buses 111(211) and 112(212)AND 4. ALL AC and Vital DC power sources have been lost for > 15 minutes.Basis: SAFETY SYSTEM: A system required for safe plant operation, cooling down the plant and/or placing it in the cold shutdown condition, including the ECCS. These are typically systems classified as safety-related.
This IC addresses a concurrent and prolonged loss of both AC and Vital DC power. A loss of all AC power compromises the performance of all SAFETY SYSTEMS requiring electric power including those necessary for emergency core cooling, containment heat removal/pressure control, spent fuel heat removal and the ultimate heat sink. A loss of Vital DC power compromises the ability to monitor and control SAFETY SYSTEMS. A sustained loss of both AC and DC power will lead to multiple challenges to fission product barriers.Fifteen minutes was selected as a threshold to exclude transient or momentary power losses. The 15-minute emergency declaration clock begins at the point when all EAL conditions are met.Month XXXX BY 3-84 EP-AA-1002 (Revision XX)
Rvron Annex FYAInn NnnrlAnr Bvrnn Annex ,,alnn  RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MG2 (cont)Basis Reference(s):
: 1. NEI 99-01 Rev 6, SG8 2. 20E-0-4001 Station One Line Diagram 3. UFSAR 8.3.1 4. 1/2 BOA ELEC-3 Loss Of 4KV ESF Bus Unit 1/2 5. 1/2 BOA ELEC-4 Loss Of Offsite Power Unit 1/2 6. 1/2 BCA-0.0 Loss Of All AC Power Unit 1/2 7. 1/2 BCA-0.1 Loss Of All AC Power Recovery Without SI Required Unit 1/2 8. 1/2 BCA-0.2 Loss Of All AC Power Recovery With SI Required Unit 1/2 9. 1/2 BCA-0.3 Response To Opposite Unit Loss Of All AC Power Unit 1/2 10. BOP AP-51, Isolating Unit 1 System AUX Transformer 142-1 & 142-2 While Unit Is At Power 13. BOP AP-52, Restoring Unit 1 System AUX Transformer 142-1 & 142-2 During Power Operation 14. BOP AP-53, Isolating Unit 2 System AUX Transformer 242-1 & 242-2 While Unit Is At Power 13. BOP AP-54, Restoring Unit 2 System AUX Transformer 242-1 & 242-2 During Power Operation 14. Safety Evaluations of the Byron Station and Byron Station Responses to the Station Blackout (SBO) Rule (TAC NOS. 68522, 68523 AND 68515, 68516)15. UFSAR 8.3.2.1.1 16. 6E-0-4001 Station One Line Diagram 17. BAR 1/2-21-El0 125V DC PNL 111/113 (211/213)
VOLT LOW 18. BAR 1/2-22-ElO 125V DC PNL 112/114 (212/214)
VOLT LOW 19. 1/2 BOA ELEC -1 Loss of DC Bus Unit 1/2 Month XXXX BY 3-85 EP-AA-1002 (Revision XX)
Rvrnn N,  R rn Annex FveInn Nrhanr~I~RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MS2 Initiating Condition:
Loss of all vital DC power for 15 minutes or longer.Operating Mode Applicability:
1,2,3,4 Emergency Action Level (EAL): Note:* The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.Voltage is < 108 VDC on unit 125 VDC battery buses 111(211) and 112(212) for >15 minutes.Basis: SAFETY SYSTEM: A system required for safe plant operation, cooling down the plant and/or placing it in the cold shutdown condition, including the ECOS. These are typically systems classified as safety-related.
This 1C addresses a loss of Vital DC power which compromises the ability to monitor and control SAFETY SYSTEMS. In modes above Cold Shutdown, this condition involves a major failure of plant functions needed for the protection of the public.Fifteen minutes was selected as a threshold to exclude transient or momentary power losses.Escalation of the emergency classification level would be via 1(s RG1, FG1 or MG3.Basis Reference(s):
: 1. NEI 99-01 Rev 6, SS8 2. UFSAR 8.3.2.1.1 3. 6E-0-4001 Station One Line Diagram 4. BAR 1/2-21-ElO 125V DC PNL 111/113 (211/213)
VOLT LOW 5. BAR 1/2-22-ElO 125V DC PNL 112/114 (212/214)
VOLT LOW 6. 1/2 BOA ELEC -1 Loss of DC Bus Unit 1/2 Month XXXX BY 3-86 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MS3 Initiating Condition:
Inability to shutdown the reactor causing a challenge to core cooling or RCS heat removal.Operating Mode Applicability:
1,2 Emergency Action Level (EAL): 1. Automatic or Manual Trip did not shutdown the reactor as indicated by Reactor Power > 5%.AND 2. ALL manual actions to shutdown the reactor have been unsuccessful as indicated by Reactor Power > 5%.AND 3. EITHER of the following conditions exist: a. Core Cooling CSF-RED Path conditions exist.OR b. Heat Sink CSF-RED Path conditions exist.Basis: This IC addresses a failure of the RPS to initiate or complete an automatic or manual reactor trip that results in a reactor shutdown, all subsequent operator manual actions, both inside and outside the Control Room including driving in control rods and boron injection, are unsuccessful, and continued power generation is challenging the capability to adequately remove heat from the core and/or the RCS. This condition will lead to fuel damage if additional mitigation actions are unsuccessful and thus warrants the declaration of a Site Area Emergency.
If Core Cooling CSF Red Path or Heat Sink CSF Red Path conditions exist prior to a successful reactor shutdown (i.e. < 5% reactor power) then entry is required.The Heat Sink Critical Safety Function Red path condition exists if narrow range levels in all steam generators (S/Gs) are less than or equal to 10% -Unit 1 (31% adverse containment) and 14% -Unit 2 (34% adverse containment) and total feedwater flow to all S/Gs is less than or equal to 500 gpm. If total feed flow is less than 500 gpm due to procedurally directed operator actions then this condition does not apply.In some instances, the emergency classification resulting from this IC/EAL may be higher than that resulting from an assessment of the plant responses and symptoms against the Recognition Category F ICs/EALs.
This is appropriate in that the Recognition Category F ICs/EALs do not address the additional threat posed by a failure to shutdown the reactor. The inclusion of this IC and EAL ensures the timely declaration of a Site Area Emergency in response to prolonged failure to shutdown the reactor.Month XXXX BY 3-87 EP-AA-1002 (Revision XX)
Rvrnn  Bvrnn Annex Pvalnn N,. rlcaar RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MS3 (cont)Basis (cont): A reactor shutdown is determined in accordance with applicable Emergency Operating Procedure criteria.Escalation of the emergency classification level would be via IC RGI or FG1.Basis Reference(s):
: 1. NEI 99-01 Rev 6, SS5 2. 1/2 BST-1 Subcriticality Unit 1/2 3. 1/2 BST-2 Core Cooling Unit 1/2 4. 1/2 BST-3 Heat Sink Unit 1/2 5. 1/2 BFR-S.1 Response to Nuclear Power Generation/ATWS Unit 1/2 6. 1/2 BFR H.1 Response to Loss of Secondary Heat Sink Unit 1/2 7. 1/2 BFR C.1 Response to Inadequate Core Cooling Unit 1/2 Month XXXX BY 3-88 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MA3 Initiating Condition:
Automatic or manual trip fails to shutdown the reactor, and subsequent manual actions taken at the reactor control consoles are not successful in shutting down the reactor.Operating Mode Applicability:
1,2 Emergency Action Level (EAL): Note:* A manual action is any operator action, or set of actions, which causes the control rods to be rapidly inserted into the core, and does not include manually driving in control rods or implementation of boron injection strategies.
: 1. Automatic or manual Trip did not shutdown the reactor as indicated by Reactor Power > 5%.AND 2. Manual actions taken at the Main Control Board are not successful in shutting down the reactor as indicated by Reactor Power > 5%.Basis: This IC addresses a failure of the RPS to initiate or complete an automatic or manual reactor trip that results in a reactor shutdown, and subsequent operator manual actions taken at the reactor control consoles to shutdown the reactor are also unsuccessful.
This condition represents an actual or potential substantial degradation of the level of safety of the plant. An emergency declaration is required even if the reactor is subsequently shutdown by an action taken away from the reactor control consoles since this event entails a significant failure of the RPS.A manual action at the Main Control Board is any operator action, or set of actions, which causes the control rods to be rapidly inserted into the core (e.g., initiating a manual reactor trip. This action does not include manually driving in control rods or implementation of boron injection strategies.
If this action(s) is unsuccessful, operators would immediately pursue additional manual actions at locations away from the reactor control consoles (e.g., locally opening breakers).
Actions taken at back-panels or other locations within the Control Room, or any location outside the Control Room, are not considered to be "at the Main Control Board".The plant response to the failure of an automatic or manual reactor trip will vary based upon several factors including the reactor power level prior to the event, availability of the condenser, performance of mitigation equipment and actions, other concurrent plant conditions, etc. If the failure to shutdown the reactor is prolonged enough to cause a challenge to the core cooling or RCS heat removal safety functions, the emergency Month XXXX BY 3-89 EP-AA-1002 (Revision XX)
Ryrnn Annex r RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MA3 (cont)Basis (cont): classification level will escalate to a Site Area Emergency via IC MS3. Depending upon plant responses and symptoms, escalation is also possible via IC FS1. Absent the plant conditions needed to meet either IC MS3 or FS1, an Alert declaration is appropriate for this event.It is recognized that plant responses or symptoms may also require an Alert declaration in accordance with the Recognition Category F ICs; however, this IC and EAL are included to ensure a timely emergency declaration.
A reactor shutdown is determined in accordance with applicable Emergency Operating Procedure criteria.Basis Reference(s):
: 1. NEI 99-01 Rev 6, SA5 2. 1/2 BST-1 Subcriticality Unit 1/2 3. 1/2 BFR-S.1 Response to Nuclear Power Generation/ATWS Unit 1/2 4. 1/2 BOSR 0.1-1,2,3 Unit One(Two) Mode 1,2, & 3 Shiftly and Daily Operating Surveillance Month XXXX BY 3-90 EP-AA-1002 (Revision XX)
Byron Annex Exalan Nuclear RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MU3 Initiating Condition:
Automatic or manual trip fails to shutdown the reactor.Operating Mode Applicability:
1,2 Emergency Action Level (EAL): Note:* A manual action is any operator action, or set of actions, which causes the control rods to be rapidly inserted into the core, and does not include manually driving in control rods or implementation of boron injection strategies.
: 1. a. Automatic Trip did not shutdown the reactor as indicated by Reactor Power> 5%.AND b. Subsequent manual action taken at the Main Control Board is successful in shutting down the reactor.OR 2. a. Manual Trip did not shutdown the reactor as indicated by Reactor Power > 5%.AND b. EITHER of the following:
: 1. Subsequent manual action taken at the Main Control Board is successful in shutting down the reactor.OR 2. Subsequent Automatic Trip is successful in shutting down the reactor.Basis: This IC addresses a failure of the RPS to initiate or complete an automatic or manual reactor trip that results in a reactor shutdown, and either a subsequent operator manual action taken at the reactor control consoles or an automatic trip is successful in shutting down the reactor. This event is a precursor to a more significant condition and thus represents a potential degradation of the level of safety of the plant.EAL #1 Basis Following the failure on an automatic reactor trip, operators will promptly initiate manual actions at the reactor control consoles to shutdown the reactor (e.g., initiate a manual reactor trip). If these manual actions are successful in shutting down the reactor, core heat generation will quickly fall to a level within the capabilities of the plant's decay heat removal systems.Month XXXX BY 3-91 EP-AA-1002 (Revision XX)
R rmn Annoy I:=v--Inn Kiii-hltr Rurnn Ann~~v Fvg~Ij~n Mi irLa~r RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MU3 (cont)Basis (cont): EAL #2 Basis If an initial manual reactor trip is unsuccessful, operators will promptly take manual action at another location(s) on the Main Control Board to shutdown the reactor (e.g., initiate a manual reactor trip using a different switch). Depending upon several factors, the initial or subsequent effort to manually trip the reactor, or a concurrent plant condition, may lead to the generation of an automatic reactor trip signal. If a subsequent manual or automatic trip is successful in shutting down the reactor, core heat generation will quickly fall to a level within the capabilities of the plant's decay heat removal systems.A manual action at the Main Control Board is any operator action, or set of actions, which causes the control rods to be rapidly inserted into the core (e.g., initiating a manual reactor trip). This action does not include manually driving in control rods or implementation of boron injection strategies.
Actions taken at back-panels or other locations within the Control Room, or any location outside the Control Room, are not considered to be "at the Main Control Board".The plant response to the failure of an automatic or manual reactor trip will vary based upon several factors including the reactor power level prior to the event, availability of the condenser, performance of mitigation equipment and actions, other concurrent plant conditions, etc. If subsequent operator manual actions taken at the Main Control Board are also unsuccessful in shutting down the reactor, then the emergency classification level will escalate to an Alert via IC MA3. Depending upon the plant response, escalation is also possible via IC FA1. Absent the plant conditions needed to meet either IC MA3 or FA1, an Unusual Event declaration is appropriate for this event.A reactor shutdown is determined in accordance with applicable Emergency Operating Procedure criteria.Should a reactor trip signal be generated as a result of plant work (e.g., RPS setpoint testing), the following classification guidance should be applied." If the signal generated as a result of plant work causes a plant transient that creates a real condition that should have included an automatic reactor trip and the RPS fails to automatically shutdown the reactor, then this IC and the EALs are applicable, and should be evaluated." If the signal generated as a result of plant work does not cause a plant transient but should have generated an RPS trip signal and the trip failure is determined through other means (e.g., assessment of test results), then this IC and the EALs are not applicable and no classification is warranted.
Basis Reference(s):
: 1. NEI 99-01 Rev 6, SU5 2. 1/2 BST-1 Subcriticality Unit 1/2 3. 1/2 BFR-S.1 Response to Nuclear Power Generation/ATWS Unit 1/2 Month XXXX BY 3-92 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MA4 Initiating Condition:
UNPLANNED loss of Control Room indications for 15 minutes or longer with a significant transient in progress.Operating Mode Applicability:
1,2,3,4 Emergency Action Level (EAL): Note:* The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.1. UNPLANNED event results in the inability to monitor ANY Table M1 from within the Control Room for >15 minutes.Table M1 -Control Room Parameters" Reactor Power" PZR Level" RCS Pressure* In Core/Core Exit Temperature" Narrow Range level in at least one Steam Generator* Steam generator Auxiliary Feed Water Flow AND 2. ANY Table M2 transient in progress.parameters I Table M2 -Significant Transients
* Automatic Turbine Runback >25% thermal reactor power* Electrical Load Rejection 
>25% full electrical load* Reactor Trip* Safety Injection Actuation Month XXXX BY 3-93 EP-AA-1002 (Revision XX)
P rmn Annay IPv,-mIon Mk u-l-sr R~,rnn Ann~v Fv~Ir~n Mii,4a~ar RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MA4 (cont)Basis: UNPLANNED:
A parameter change or an event that is not 1) the result of an intended evolution or 2) an expected plant response to a transient.
The cause of the parameter change or event may be known or unknown.SAFETY SYSTEM: A system required for safe plant operation, cooling down the plant and/or placing it in the cold shutdown condition, including the ECCS. These are typically systems classified as safety-related.
This IC addresses the difficulty associated with monitoring rapidly changing plant conditions during a transient without the ability to obtain SAFETY SYSTEM parameters from within the Control Room. During this condition, the margin to a potential fission product barrier challenge is reduced. It thus represents a potential substantial degradation in the level of safety of the plant.As used in this EAL, an "inability to monitor" means that values for any of the listed parameters cannot be determined from within the Control Room. This situation would require a loss of all of the Control Room sources for the given parameter(s).
For example, the reactor power level cannot be determined from any analog, computer point, digital and recorder source within the Control Room.An event involving a loss of plant indications, annunciators and/or display systems is evaluated in accordance with 10 CFR 50.72 (and associated guidance in NUREG-1022) to determine if an NRC event report is required.
The event would be reported if it significantly impaired the capability to perform emergency assessments.
In particular, emergency assessments necessary to implement abnormal operating procedures, emergency operating procedures, and emergency plan implementing procedures addressing emergency classification, accident assessment, or protective action decision-making.
This EAL is focused on a selected subset of plant parameters associated with the key safety functions of reactivity control, core cooling and RCS heat removal. The loss of the ability to determine any of these parameters from within the Control Room is considered to be more significant than simply a reportable condition.
In addition, if all indication sources for any of the listed parameters are lost, then the ability to determine the values of other SAFETY SYSTEM parameters may be impacted as well. For example, if the value for reactor vessel level cannot be determined from the indications and recorders on a main control board, the SPDS or the plant computer, the availability of other parameter values may be compromised as well.Fifteen minutes was selected as a threshold to exclude transient or momentary losses of indication.
Escalation of the emergency classification level would be via ICs FS1 or IC RS1.Basis Reference(s):
: 1. NEI 99-01 Rev 6, SA2 Month XXXX BY 3-94 EP-AA-1002 (Revision XX)
Byron Annex Explnn Nuclear RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MU4 Initiating Condition:
UNPLANNED loss of Control Room indications for 15 minutes or longer.Operating Mode Applicability:
1,2,3,4 Emergency Action Level (EAL): Note: e The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.UNPLANNED event results in the inability to monitor ANY Table M1 parameters from within the Control Room for > 15 minutes.Table M1 -Control Room Parameters
* Reactor Power 0 PZR Level* RCS Pressure* In Core/Core Exit Temperature
* Narrow Range level in at least one Steam Generator 9 Steam generator Auxiliary Feed Water Flow Basis: UNPLANNED:
A parameter change or an event that is not 1) the result of an intended evolution or 2) an expected plant response to a transient.
The cause of the parameter change or event may be known or unknown.SAFETY SYSTEM: A system required for safe plant operation, cooling down the plant and/or placing it in the cold shutdown condition, including the ECCS. These are typically systems classified as safety-related.
This IC addresses the difficulty associated with monitoring normal plant conditions without the ability to obtain SAFETY SYSTEM parameters from within the Control Room. This condition is a precursor to a more significant event and represents a potential degradation in the level of safety of the plant.As used in this EAL, an "inability to monitor" means that values for any of the listed parameters cannot be determined from within the Control Room. This situation would require a loss of all of the Control Room sources for the given parameter(s).
For example, the reactor power level cannot be determined from any analog, digital and recorder source within the Control Room. An event involving a loss of plant indications, Month XXXX BY 3-95 EP-AA-1002 (Revision XX)
Byron Annex Exalon Nuclear RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MU4 (cont)Basis (cont): annunciators and/or display systems is evaluated in accordance with 10 CFR 50.72 (and associated guidance in NUREG-1022) to determine if an NRC event report is required.
The event would be reported if it significantly impaired the capability to perform emergency assessments.
In particular, emergency assessments necessary to implement abnormal operating procedures, emergency operating procedures, and emergency plan implementing procedures addressing emergency classification, accident assessment, or protective action decision-making.
This EAL is focused on a selected subset of plant parameters associated with the key safety functions of reactivity control, core cooling and RCS heat removal. The loss of the ability to determine any of these parameters from within the Control Room is considered to be more significant than simply a reportable condition.
In addition, if all indication sources for any of the listed parameters are lost, then the ability to determine the values of other SAFETY SYSTEM parameters may be impacted as well. For example, if the value for reactor vessel level cannot be determined from the indications and recorders on a main control board, the SPDS or the plant computer, the availability of other parameter values may be compromised as well.Fifteen minutes was selected as a threshold to exclude transient or momentary losses of indication.
Escalation of the emergency classification level would be via IC MA4.Basis Reference(s):
: 1. NEI 99-01 Rev 6, SU2 Month XXXX BY 3-96 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MA5 Initiating Condition:
Hazardous event affecting a SAFETY SYSTEM required for the current operating mode.Operating Mode Applicability:
1,2,3,4 Emergency Action Level (EAL): 1. The occurrence of ANY of the following hazardous events: " Seismic event (earthquake)" Internal or external flooding event" High winds or tornado strike" FIRE" EXPLOSION* Other events with similar hazard characteristics as determined by the Shift Manager AND 2. EITHER of the following:
: a. Event damage has caused indications of degraded performance in at least one train of a SAFETY SYSTEM required by Technical Specifications for the current operating mode.OR b. The event has caused VISIBLE DAMAGE to a SAFETY SYSTEM component or structure required by Technical Specifications for the current operating mode.Basis: FIRE: Combustion characterized by heat and light. Sources of smoke such as slipping drive belts or overheated electrical equipment do not constitute FIRES. Observation of flame is preferred but is NOT required if large quantities of smoke and heat are observed.EXPLOSION:
A rapid, violent and catastrophic failure of a piece of equipment due to combustion, chemical reaction or overpressurization.
A release of steam (from high energy lines or components) or an electrical component failure (caused by short circuits, grounding, arcing, etc.) should not automatically be considered an explosion.
Such events may require a post-event inspection to determine if the attributes of an explosion are present.Month XXXX BY 3-97 EP-AA-1002 (Revision XX)
R rtnn Annoy I=,v--Irn Kirnn-Ig-,r R~,rr~n A nnav Fvnit~n Mi ir~I~~r-* .%e. .5~~* ** *~fl -fl~ * ~* * * * -~* L4*RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MA5 (cont)Basis (cont): SAFETY SYSTEM: A system required for safe plant operation, cooling down the plant and/or placing it in the cold shutdown condition, including the ECCS. These are typically systems classified as safety-related.
VISIBLE DAMAGE: Damage to a component or structure that is readily observable without measurements, testing, or analysis.
The visual impact of the damage is sufficient to cause concern regarding the operability or reliability of the affected component or structure.
This IC addresses a hazardous event that causes damage to a SAFETY SYSTEM, or a structure containing SAFETY SYSTEM components, required for the current operating mode, "required", i.e. required to be operable by Technical Specifications for the current operating mode. This condition significantly reduces the margin to a loss or potential loss of a fission product barrier, and therefore represents an actual or potential substantial degradation of the level of safety of the plant. Manual or automatic electrical isolation of safety equipment due to flooding, in and of itself, does not constitute degraded performance and is classified under HU6.EAL #2.a addresses damage to a SAFETY SYSTEM train that is required to be operable by Technical Specifications for the current operating mode, and is in operation since indications for it will be readily available.
The indications of degraded performance should be significant enough to cause concern regarding the operability or reliability of the SAFETY SYSTEM train.EAL #2.b addresses damage to a SAFETY SYSTEM component that is required to be operable by Technical Specifications for the current operating mode, and is not in operation or readily apparent through indications alone, as well as damage to a structure containing SAFETY SYSTEM components.
Operators will make this determination based on the totality of available event and damage report information.
This is intended to be a brief assessment not requiring lengthy analysis or quantification of the damage.Escalation of the emergency classification level would be via IC FS1 or RSI.If the EAL conditions of MA5 are not met then assess the event via HU3, HU4, or HU6.Basis Reference(s):
: 1. NEI 99-01, Rev 6 SA9 Month XXXX BY 3-98 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MU6 Initiating Condition:
RCS leakage for 15 minutes or longer.Operating Mode Applicability:
1,2,3,4 Emergency Action Level (EAL): Note:* The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.1. RCS unidentified or pressure boundary leakage > 10 gpm for > 15 minutes.OR 2. RCS identified leakage >25 gpm for > 15 minutes.OR 3. Leakage from the RCS to a location outside containment 
>25 gpm for > 15 minutes.Basis: UNISOLABLE:
An open or breached system line that cannot be isolated, remotely or locally.This IC addresses RCS leakage which may be a precursor to a more significant event.In this case, RCS leakage has been detected and operators, following applicable procedures, have been unable to promptly isolate the leak. This condition is considered to be a potential degradation of the level of safety of the plant.EAL #1 and EAL #2 Basis These EALs are focused on a loss of mass from the RCS due to "unidentified leakage","pressure boundary leakage" or "identified leakage" (as these leakage types are defined in the plant Technical Specifications).
EAL #3 Basis This EAL addresses a RCS mass loss caused by an UNISOLABLE leak through an interfacing system.These EALs thus apply to leakage into the containment, a secondary-side system (e.g., steam generator tube leakage) or a location outside of containment.
The leak rate values for each EAL were selected because they are usually observable with normal Control Room indications.
Lesser values typically require time-consuming calculations to determine (e.g., a mass balance calculation).
EAL #1 uses a lower value that reflects the greater significance of unidentified or pressure boundary leakage.Month XXXX BY 3-99 EP-AA-1002 (Revision XX)
Exelon Nuclear-vron Annex Exelon Nuclear RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MU6 (cont)Basis (cont): The release of mass from the RCS due to the as-designed/expected operation of a relief valve does not warrant an emergency classification.
An emergency classification would be required if a mass loss is caused by a relief valve that is not functioning as designed/expected (e.g., a relief valve sticks open and the line flow cannot be isolated).
The 15-minute threshold duration allows sufficient time for prompt operator actions to isolate the leakage, if possible.Escalation of the emergency classification level would be via ICs of Recognition Category R or F.Basis Reference(s):
: 1. NEI 99-01 Rev 6, SU4 2. Technical Specifications 3.4.13 & 3.4.14 3. UFSAR. 6.2, 5.2 4. 1/2 BOSR 4.13.1-1 Unit One(Two) Reactor Coolant System Water Inventory Balance 72 Hour Surveillance
: 5. 1/2 BOL 4.15 LCOAR -RCS Leakage Detection Instrumentation
: 6. 1/2 BOL 4.13 LCOAR -RCS Operational Leakage 7. 1/2 BOA PRI-1 Excessive Primary Leakage Unit 1/2 8. 1/2 BOSR 0.1-4 Unit One(Two) Mode 4 Shiftly and Daily Operating Surveillance
: 9. 1/2 BOSR RF-1 Unit One(Two) Containment Floor Drain Monitoring System Non-Routine Surveillance
: 10. 0/1/2 BOSR XZB-R1, Unit 0/1/2 Meter Zone Banding Month XXXX BY 3-100 EP-AA-1002 (Revision XX)
R rnn Annay I~valr~n Niu-lgar RJI. ll nlIv kAnIrII Mauj tIlll RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MU7 Initiating Condition:
Loss of all On-site or Off-site communications capabilities.
Operating Mode Applicability:
1,2,3,4 Emergency Action Level (EAL): 1. Loss of ALL Table M3 Onsite communications capability affecting the ability to perform routine operations.
OR 2. Loss of ALL Table M3 Offsite communication capability affecting the ability to perform offsite notifications.
OR 3. Loss of ALL Table M3 NRC communication capability affecting the ability to perform NRC notifications.
Table M3 -Communications Capability System Onsite Offsite NRC Radios X Plant page X Plant Telephone System _Commercial Telephones NARS X ENS X X HPN X X Satellite phones X X Basis: This IC addresses a significant loss of on-site, offsite, or NRC communications capabilities.
While not a direct challenge to plant or personnel safety, this event warrants prompt notifications to Offsite Response Organizations (OROs) and the NRC.This IC should be assessed only when extraordinary means are being utilized to make communications possible (e.g., use of non-plant, privately owned equipment, relaying of on-site information via individuals or multiple radio transmission points, individuals being sent to offsite locations, etc.).Month XXXX BY 3-101 EP-AA-1002 (Revision XX)
P mrnn Annav I~v--In~n im..d-I-nr JL RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MU7 (cont)Basis (cont): EAL #1 Basis Addresses a total loss of the communications methods used in support of routine plant operations.
EAL #2 Basis Addresses a total loss of the communications methods used to notify all OROs of an emergency declaration.
The OROs referred to here are listed in procedure EP-MW-114-1 00-F-01, Nuclear Accident Reporting System (NARS) Form.EAL #3 Basis Addresses a total loss of the communications methods used to notify the NRC of an emergency declaration.
Basis Reference(s):
: 1. NEI 99-01 Rev 6, SU6 2. EP-MW-124-1001 Facilities Inventories And Equipment Tests Month XXXX BY 3-102 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MU8 Initiating Condition:
Failure to isolate containment or loss of containment pressure control.Operating Mode Applicability:
1,2,3,4 Emergency Action Level (EAL): 1. a. Failure of containment to isolate when required by an actuation signal.AND b. ANY required penetration remains open > 15 minutes of the actuation signal.OR 2. a. Containment pressure > 20 psig.AND b. Less than one full train of Containment Spray is operating per design for> 15 minutes.Basis: This IC addresses a failure of any containment penetrations to automatically isolate (close) when required by an actuation signal. It also addresses an event that results in high containment pressure with a concurrent failure of containment pressure control systems. Absent challenges to another fission product barrier, either condition represents potential degradation of the level of safety of the plant.EAL #1 Basis The containment isolation signal must be generated as the result on an off-normal/accident condition (e.g., a safety injection or high containment pressure);
a failure resulting from testing or maintenance does not warrant classification.
The determination of containment and penetration status -isolated or not isolated -should be made in accordance with the appropriate criteria contained in the plant AOPs and EOPs. The 15-minute criterion is included to allow operators time to manually isolate the required penetrations, if possible.EAL #2 Basis Addresses a condition where containment pressure is greater than the setpoint at which containment energy (heat) removal systems are designed to automatically actuate, and less than one full train of equipment is capable of operating per design. The 15-minute criterion is included to allow operators time to manually start equipment that may not have automatically started, if possible.
The inability to start the required equipment indicates that containment heat removal/depressurization systems (e.g., containment sprays or ice condenser fans) are either lost or performing in a degraded manner.Month XXXX BY 3-103 EP-AA-1002 (Revision XX)
Byron Annex Exellon Nuclear RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MU8 (cont)Basis (cont): This event would escalate to a Site Area Emergency in accordance with IC FS1 if there were a concurrent loss or potential loss of either the Fuel Clad or RCS fission product barriers.Basis Reference(s):
: 1. NEI 99-01 Rev 6, SU7 2. 1/2 BST-5 Containment Unit 1/2 Month XXXX BY 3-104 EP-AA-1 002 (Revision XX)
I:),vrn n  Rvrnn Annex Fvy'Inn Miur-Io2r RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CA1 Initiating Condition:
Loss of all offsite and all onsite AC power to emergency buses for 15 minutes or longer.Operating Mode Applicability:
5,6, D Emergency Action Level (EAL): Note:* The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.1. Loss of ALL offsite AC power to unit ESF buses.AND 2. Failure of DG 1A(2A) and DG 1B(2B) emergency diesel generators to supply power to unit ESF buses.AND 3. Failure to restore power to at least one unit ESF bus in < 15 minutes from the time of loss of both offsite and onsite AC power.Basis: SAFETY SYSTEM: A system required for safe plant operation, cooling down the plant and/or placing it in the cold shutdown condition, including the ECCS. These are typically systems classified as safety-related This IC addresses a total loss of AC power that compromises the performance of all SAFETY SYSTEMS requiring electric power including those necessary for emergency core cooling, containment heat removal/pressure control, spent fuel heat removal and the ultimate heat sink.When in the cold shutdown, refueling, or defueled mode, this condition is not classified as a Site Area Emergency because of the increased time available to restore an emergency bus to service. Additional time is available due to the reduced core decay heat load, and the lower temperatures and pressures in various plant systems. Thus, when in these modes, this condition represents an actual or potential substantial degradation of the level of safety of the plant.The emergency buses of the affected unit can be powered from the unaffected unit through the crosstie breakers.
Unit crosstie is considered an adequate source of offsite power when evaluating this EAL.Fifteen minutes was selected as a threshold to exclude transient or momentary power losses.Escalation of the emergency classification level would be via IC CS6 or RSI.Month XXXX BY 3-105 EP-AA-1002 (Revision XX)
Rvrmn Annay Pvtalnn hi~rlanr J.rnn ni , ur~nu umm iu r RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CAI (cont)Basis Reference(s):
: 1. NEI 99-01 Rev 6, CA2 2. 20E-0-4001 Station One Line Diagram 3. UFSAR 8.3.1 4. 1/2 BOA ELEC-3 Loss Of 4KV ESF Bus Unit 1/2 5. 1/2 BOA ELEC-4 Loss Of Offsite Power Unit 1/2 6. 1/2 BCA-0.0 Loss Of All AC Power Unit 1/2 7. 1/2 BCA-0.1 Loss Of All AC Power Recovery Without SI Required Unit 1/2 8. 1/2 BCA-0.2 Loss Of All AC Power Recovery With SI Required Unit 1/2 9. 1/2 BCA-0.3 Response To Opposite Unit Loss Of All AC Power Unit 1/2 10. BOP AP-51, Isolating Unit 1 System AUX Transformer 142-1 & 142-2 While Unit Is At Power 11. BOP AP-52, Restoring Unit 1 System AUX Transformer 142-1 & 142-2 During Power Operation 12. BOP AP-53, Isolating Unit 2 System AUX Transformer 242-1 & 242-2 While Unit Is At Power 13. BOP AP-54, Restoring Unit 2 System AUX Transformer 242-1 & 242-2 During Power Operation 14. Safety Evaluations of the Byron Station and Byron Station Responses to the Station Blackout (SBO) Rule (TAC NOS. 68522, 68523 AND 68515, 68516)Month XXXX BY 3-106 EP-AA-1002 (Revision XX)
Byron Annoy I:valnn Khirilnr Rvrnn Anna~v Fvalnn Muur4i~ar RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS cul Initiating Condition:
Loss of all but one AC power source to emergency buses for 15 minutes or longer.Operating Mode Applicability:
5,6, D Emergency Action Level (EAL): Note:* The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.1. AC power capability to unit ESF buses reduced to only one of the following power sources for > 15 minutes.* Affected unit SAT 142-1(242-1)
* Affected unit SAT 142-2(242-2)
* Emergency Diesel Generator DG 1A(2A)* Emergency Diesel Generator DG 1B(2B)* Unit crosstie breakers AND 2. Any additional single power source failure will result in a loss of ALL AC power to SAFETY SYSTEMS.Basis: SAFETY SYSTEM: A system required for safe plant operation, cooling down the plant and/or placing it in the cold shutdown condition, including the ECCS. These are typically systems classified as safety-related.
This IC describes a significant degradation of offsite and onsite AC power sources such that any additional single failure would result in a loss of all AC power to SAFETY SYSTEMS. In this condition, the sole AC power source may be powering one, or more than one, train of safety-related equipment.
When in the cold shutdown, refueling, or defueled mode, this condition is not classified as an Alert because of the increased time available to restore another power source to service. Additional time is available due to the reduced core decay heat load, and the lower temperatures and pressures in various plant systems. Thus, when in these modes, this condition is considered to be a potential degradation of the level of safety of the plant.Month XXXX BY 3-107 EP-AA-1002 (Revision XX)
Byron Annex Exellon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CUI (cont)Basis (cont): An "AC power source" is a source recognized in AOPs and EOPs, and capable of supplying required power to an emergency bus. Some examples of this condition are presented below.* A loss of all offsite power with a concurrent failure of all but one emergency power source (e.g., an onsite diesel generator)." A loss of all offsite power and loss of all emergency power sources (e.g., onsite diesel generators) with a single train of emergency buses being back-fed from the unit main generator.
* A loss of emergency power sources (e.g., onsite diesel generators) with a single train of emergency buses being back-fed from an offsite power source.Fifteen minutes was selected as a threshold to exclude transient or momentary losses of power.The subsequent loss of the remaining single power source would escalate the event to an Alert in accordance with IC CAl.Basis Reference(s):
: 1. NEI 99-01 Rev 6 CU2 2. 20E-0-4001 Station One Line Diagram 3. UFSAR 8.3.1 4. 1/2 BOA ELEC-3 Loss Of 4KV ESF Bus Unit 1/2 5. 1/2 BOA ELEC-4 Loss Of Offsite Power Unit 1/2 6. 1/2 BCA-0.0 Loss Of All AC Power Unit 1/2 7. 1/2 BCA-0.1 Loss Of All AC Power Recovery Without SI Required Unit 1/2 8. 1/2 BCA-0.2 Loss Of All AC Power Recovery With SI Required Unit 1/2 9. 1/2 BCA-0.3 Response To Opposite Unit Loss Of All AC Power Unit 1/2 10. BOP AP-51, Isolating Unit 1 System AUX Transformer 142-1 & 142-2 While Unit Is At Power 11. BOP AP-52, Restoring Unit 1 System AUX Transformer 142-1 & 142-2 During Power Operation 12. BOP AP-53, Isolating Unit 2 System AUX Transformer 242-1 & 242-2 While Unit Is At Power 13. BOP AP-54, Restoring Unit 2 System AUX Transformer 242-1 & 242-2 During Power Operation 14. Safety Evaluations of the Byron Station and Byron Station Responses to the Station Blackout (SBO) Rule (TAC NOS. 68522, 68523 AND 68515, 68516)Month XXXX BY 3-108 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CA2 Initiating Condition:
Hazardous event affecting SAFETY SYSTEM required for the current operating mode.Operating Mode Applicability:
5,6 Emergency Action Level (EAL): 1. The occurrence of ANY of the following hazardous events:* Seismic event (earthquake)
* Internal or external flooding event" High winds or tornado strike" FIRE" EXPLOSION* Other events with similar hazard characteristics as determined by the Shift Manager AND 2. EITHER of the following:
: a. Event damage has caused indications of degraded performance in at least one train of a SAFETY SYSTEM required by Technical Specifications for the current operating mode.OR b. The event has caused VISIBLE DAMAGE to a SAFETY SYSTEM component or structure required by Technical Specifications for the current operating mode.Basis: FIRE: Combustion characterized by heat and light. Sources of smoke such as slipping drive belts or overheated electrical equipment do not constitute FIRES. Observation of flame is preferred but is NOT required if large quantities of smoke and heat are observed.EXPLOSION:
A rapid, violent and catastrophic failure of a piece of equipment due to combustion, chemical reaction or overpressurization.
A release of steam (from high energy lines or components) or an electrical component failure (caused by short circuits, grounding, arcing, etc.) should not automatically be considered an explosion.
Such events may require a post-event inspection to determine if the attributes of an explosion are present.SAFETY SYSTEM: A system required for safe plant operation, cooling down the plant and/or placing it in the cold shutdown condition, including the ECCS. These are typically systems classified as safety-related.
Month XXXX BY 3-109 EP-AA-1002 (Revision XX)
Byron Annex ByronAnnexExellon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CA2 (cont)Basis (cont): VISIBLE DAMAGE: Damage to a component or structure that is readily observable without measurements, testing, or analysis.
The visual impact of the damage is sufficient to cause concern regarding the operability or reliability of the affected component or structure.
This IC addresses a hazardous event that causes damage to a SAFETY SYSTEM, or a structure containing SAFETY SYSTEM components, required for the current operating mode, "required", i.e. required to be operable by Technical Specifications for the current operating mode. This condition significantly reduces the margin to a loss or potential loss of a fission product barrier, and therefore represents an actual or potential substantial degradation of the level of safety of the plant. Manual or automatic electrical isolation of safety equipment due to flooding, in and of itself, does not constitute degraded performance and is classified under HU6.EAL #2.a addresses damage to a SAFETY SYSTEM train that is required to be operable by Technical Specifications for the current operating mode, and is in operation since indications for it will be readily available.
The indications of degraded performance should be significant enough to cause concern regarding the operability or reliability of the SAFETY SYSTEM train.EAL #2.b addresses damage to a SAFETY SYSTEM component that is required to be operable by Technical Specifications for the current operating mode, and is not in operation or readily apparent through indications alone, or to a structure containing SAFETY SYSTEM components.
Operators will make this determination based on the totality of available event and damage report information.
This is intended to be a brief assessment not requiring lengthy analysis or quantification of the damage.Escalation of the emergency classification level would be via IC CS6 or RS1.If the EAL conditions of CA2 are not met then assess the event via HU3, HU4, or HU6.Basis Reference(s):
: 1. NEI 99-01 Rev 6, CA6 Month XXXX BY 3-110 EP-AA-1002 (Revision XX)
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* 5~'*** .~n ~ * ~* * .* -~RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CU3 Initiating Condition:
Loss of Vital DC power for 15 minutes or longer.Operating Mode Applicability:
5,6 Emergency Action Level (EAL): Note:* The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.Voltage is < 108 VDC on required unit 125 VDC battery buses 111(211) and 112(212)for > 15 minutes.Basis: SAFETY SYSTEM: A system required for safe plant operation, cooling down the plant and/or placing it in the cold shutdown condition, including the ECCS. These are typically systems classified as safety-related.
This IC addresses a loss of Vital DC power which compromises the ability to monitor and control operable SAFETY SYSTEMS when the plant is in the cold shutdown or refueling mode. In these modes, the core decay heat load has been significantly reduced, and coolant system temperatures and pressures are lower; these conditions rise the time available to restore a vital DC bus to service. Thus, this condition is considered to be a potential degradation of the level of safety of the plant.As used in this EAL, "required" means the Vital DC buses necessary to support operation of the in-service, or operable, train or trains of SAFETY SYSTEM equipment.
For example, if Train A is out-of-service (inoperable) for scheduled outage maintenance work and Train B is in-service (operable), then a loss of Vital DC power affecting Train B would require the declaration of an Unusual Event. A loss of Vital DC power to Train A would not warrant an emergency classification.
Fifteen minutes was selected as a threshold to exclude transient or momentary power losses.Depending upon the event, escalation of the emergency classification level would be via IC CA6 or CA5, or an IC in Recognition Category R.Month XXXX BY 3-111 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CU3 (cont)Basis Reference(s):
: 1. NEI 99-01 Rev 6, CU4 2. UFSAR 8.3.2.1.1 3. 6E-0-4001 Station One Line Diagram 4. 1/2 BOA ELEC -1 Loss of DC Bus Unit 1/2 5. BAR 1/2-21-E10 125V DC PNL 111/113 (211/213)
VOLT LOW 6. BAR 1/2-22-E10 125V DC PNL 112/114 (212/214)
VOLT LOW Month XXXX BY 3-112 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CU4 Initiating Condition:
Loss of all onsite or offsite communications capabilities.
Operating Mode Applicability:
5,6, D Emergency Action Level (EAL): 1. Loss of ALL Table C1 Onsite communications capability affecting the ability to perform routine operations.
OR 2. Loss of ALL Table C1 Offsite communication capability affecting the ability to perform offsite notifications.
OR 3. Loss of ALL Table C1 NRC communication capability affecting the ability to perform NRC notifications.
Table C1 -Communications Capability System Onsite Offsite NRC Radios X Plant page X Plant Telephone X System Commercial X X X Telephones NARS X ENS X X HPN X X Satellite phones X X Basis: This IC addresses a significant loss of on-site, offsite, or NRC communications capabilities.
While not a direct challenge to plant or personnel safety, this event warrants prompt notifications to Offsite Response Organizations (OROs) and the NRC.This IC should be assessed only when extraordinary means are being utilized to make communications possible (e.g., use of non-plant, privately owned equipment, relaying of on-site information via individuals or multiple radio transmission points, individuals being sent to offsite locations, etc.).Month XXXX BY 3-113 EP-AA-1002 (Revision XX)
Byron Annex Exellon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CU4 (cont)Basis (cont): EAL #1 Basis Addresses a total loss of the communications methods used in support of routine plant operations.
EAL #2 Basis Addresses a total loss of the communications methods used to notify all OROs of an emergency declaration.
The OROs referred to here are listed in procedure EP-MW-114-100-F-01, Nuclear Accident Reporting System (NARS) Form.EAL #3 Basis Addresses a total loss of the communications methods used to notify the NRC of an emergency declaration.
Basis Reference(s):
: 1. NEI 99-01 Rev 6, CU5 2. EP-MW-124-1001 Facilities Inventories And Equipment Tests Month XXXX BY 3-114 EP-AA-1002 (Revision XX)
Rvrmn Annov=,Vglrn K1110-leNnr RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CA5 Initiating Condition:
Inability to maintain the plant in cold shutdown.Operating Mode Applicability:
5,6 Emergency Action Level (EAL): Note:* The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.1. UNPLANNED rise in RCS temperature 
> 200OF due to loss of decay heat removal for > Table C2 duration.OR 2. UNPLANNED RCS pressure rise > 10 psig as a result of temperature rise due to loss of decay heat removal. (This EAL does not apply in solid plant conditions.)
Table C2 -RCS Heat-up Duration Thresholds RCS Containment Closure Heat-up Status Status Duration Intact Not Applicable 60 minutes*Not Intact Established 20 minutes*OR Reduced Not Established 0 minutes Inventory (<397 ft.)* If an RCS heat removal system is in operation within this time frame and RCS temperature is being reduced, then EAL #1 is not applicable.
Month XXXX BY 3-115 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CA5 (cont)Basis: UNPLANNED:
A parameter change or an event that is not 1) the result of an intended evolution or 2) an expected plant response to a transient.
The cause of the parameter change or event may be known or unknown.CONTAINMENT CLOSURE: The procedurally defined conditions or actions taken to secure containment and its associated structures, systems, and components as a functional barrier to fission product release under shutdown conditions.
RCS is intact when the RCS pressure boundary is in its normal condition for the Cold Shutdown mode of operation (e.g. no freeze seals, etc.).This IC addresses conditions involving a loss of decay heat removal capability or an addition of heat to the RCS in excess of that which can currently be removed. Either condition represents an actual or potential substantial degradation of the level of safety of the plant.A momentary UNPLANNED excursion above the Technical Specification cold shutdown temperature limit when the heat removal function is available does not warrant a classification.
The RCS Heat-up Duration Thresholds table addresses a rise in RCS temperature when CONTAINMENT CLOSURE is established but the RCS is not intact, or RCS inventory is reduced (e.g., mid-loop operation in PWRs). The 20-minute criterion was included to allow time for operator action to address the temperature rise.The RCS Heat-up Duration Thresholds table also addresses a rise in RCS temperature with the RCS intact. The status of CONTAINMENT CLOSURE is not crpCial in this condition since the intact RCS is providing a high pressure barrier to a fission product release. The 60-minute time frame should allow sufficient time to address the temperature rise without a substantial degradation in plant safety.Finally, in the case where there is a rise in RCS temperature, the RCS is not intact or is at reduced inventory , and CONTAINMENT CLOSURE is not established, no heat-up duration is allowed (i.e., 0 minutes).
This is because 1) the evaporated reactor coolant may be released directly into the Containment atmosphere and subsequently to the environment, and 2) there is reduced reactor coolant inventory above the top of irradiated fuel.EAL #2 Basis Provides a pressure-based indication of RCS heat-up.Escalation of the emergency classification level would be via IC.CS6 or RS1.Month XXXX BY 3-116 EP-AA-1002 (Revision XX)
Byron Annex Exelon  B -ron Annex Ex.lon Nucle....ar RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CA5 (cont)Basis Reference(s):
: 1. NEI 99-01 Rev 6, CA3 2. BOP PC-1 Containment Closure Tracking Capability
: 3. 1/2 BOSR 4.3.1-1 Reactor Coolant System Pressure Temperature Limit Surveillance
: 4. 1/2 BGP 100-1 Plant Heatup 5. 1/2 BGP 100-5, Plant Shutdown and Cool Down 6. 1/2 BGP 100-6, Unit 1(Unit 2) Refueling Outage Month XXXX BY 3-117 EP-AA-1002 (Revision XX)
Bvran Annex Exelon Nuclear Bvn Annex...Exelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CU5 Initiating Condition:
UNPLANNED rise in RCS temperature Operating Mode Applicability:
5,6 Emergency Action Level (EAL): Note: The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.1. UNPLANNED rise in RCS temperature 
> 200OF due to loss of decay heat removal.OR 2. Loss of the following for >15 minutes.* ALL RCS temperature indications AND* ALL RCS level indications Basis: UNPLANNED:
A parameter change or an event that is not 1) the result of an intended evolution or 2) an expected plant response to a transient.
The cause of the parameter change or event may be known or unknown.CONTAINMENT CLOSURE: The procedurally defined conditions or actions taken to secure containment and its associated structures, systems, and components as a functional barrier to fission product release under shutdown conditions.
This IC addresses an UNPLANNED rise in RCS temperature above the Technical Specification cold shutdown temperature limit, or the inability to determine RCS temperature and level, represents a potential degradation of the level of safety of the plant. If the RCS is not intact and CONTAINMENT CLOSURE is not established during this event, the Emergency Director should also refer to IC CA5.RCS is intact when the RCS pressure boundary is in its normal condition for the Cold Shutdown mode of operation (e.g. no freeze seals, etc.).A momentary UNPLANNED excursion above the Technical Specification cold shutdown temperature limit when the heat removal function is available does not warrant a classification.
Month XXXX BY 3-118 EP-AA-1002 (Revision XX)
Rvron Annex Exelon Nuclear ByronAnnexExelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CU5 (cont)Basis (cont): EAL #1 involves a loss of decay heat removal capability, or an addition of heat to the RCS in excess of that which can currently be removed, such that reactor coolant temperature cannot be maintained below the cold shutdown temperature limit specified in Technical Specifications.
During this condition, there is no immediate threat of fuel damage because the core decay heat load has been reduced since the cessation of power operation.
During an outage, the level in the reactor vessel will normally be maintained above the reactor vessel flange. Refueling evolutions that lower water level below the reactor vessel flange are carefully planned and controlled.
A loss of forced decay heat removal at reduced inventory may result in a rapid rise in reactor coolant temperature depending on the time after shutdown.EAL #2 reflects a condition where there has been a significant loss of instrumentation capability necessary to monitor RCS conditions and operators would be unable to monitor key parameters necessary to assure core decay heat removal. During this condition, there is no immediate threat of fuel damage because the core decay heat load has been reduced since the cessation of power operation.
Fifteen minutes was selected as a threshold to exclude transient or momentary losses of indication.
Escalation to Alert would be via IC CA6 based on an inventory loss or IC CA5 based on exceeding plant configuration-specific time criteria.Basis Reference(s):
: 1. NEI 99-01 Rev 6, CU3 2. Technical Specifications Table 1.1-1 3. 1/2 BOSR 0.1-6 Unit One (Two) Mode 6 Shiftly And Daily Operating Surveillance
: 4. BOP RH-9 Pump Down of the Refueling Cavity to the RWST 5. BOP RC-4 Reactor Coolant System Drain 6. 1/2 BOSR 3.3.1-1 Unit One (Two) Accident Monitoring Instrumentation Monthly Channel Checks 7. 1/2 BOL 4.15, LCOAR -RCS Leakage Detection Instrumentation
: 8. 1/2 BOL 4.13, LCOAR -RCS Operational Leakage 9. 1/2 BOSR 4.3.1-1 Reactor Coolant System Pressure / Temperature Limit Surveillance Month XXXX BY 3-119 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CG6 Initiating Condition:
Loss of reactor vessel/RCS inventory affecting fuel clad integrity with containment challenged.
Operating Mode Applicability:
5,6 Emergency Action Level (EAL): Note:* The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.1. a. RVLIS indicates 0% Plenum for > 30 minutes.OR Reactor Vessel Refueling Level Indicators LT-046 and LT-049 < 392 ft. el. for> 30 minutes.AND b. ANY Containment Challenge Indication (Table C4)OR 2. Reactor Vessel level unknown for > 30 minutes.AND 3. Core uncovery is indicated by ANY of the following:
0 Table C3 indications of a sufficient magnitude to indicate core uncovery.OR* Erratic Source Range Neutron Monitor indication.
OR* 1/2 RE-AR011 or 1/2 RE-AR12 Containment Fuel Handling Incident radiation monitors > 3000 mR/hr.AND 4. Any Containment Challenge Indication (Table C4)Month XXXX BY 3-120 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CG6 (cont)Emergency Action Level (EAL) (cont): Table C3 -Indications of RCS Leakage* UNPLANNED Containment Sump level rise** UNPLANNED Auxiliary Bldg. Sump level rise*" UNPLANNED Tank level (rad waste) rise** UNPLANNED rise in RCS makeup* Observation of leakage or inventory loss*Rise in level is attributed to a loss of reactor vessel/RCS inventory.
Table C4 -Containment Challenge Indications" Hydrogen Concentration in Containment 
> 5%* UNPLANNED rise in containment pressure" CONTAINMENT CLOSURE not established*
* if CONTAINMENT CLOSURE is re-established prior to exceeding the 30-minute core uncovery time limit, then escalation to a General Emergency is not required.Basis: IMMINENT:
The trajectory of events or conditions is such that an EAL will be met within a relatively short period of time regardless of mitigation or corrective actions.CONTAINMENT CLOSURE: The procedurally defined conditions or actions taken to secure containment and its associated structures, systems, and components as a functional barrier to fission product release under shutdown conditions.
UNPLANNED:
A parameter change or an event that is not 1) the result of an intended evolution or 2) an expected plant response to a transient.
The cause of the parameter change or event may be known or unknown.This IC addresses the inability to restore and maintain reactor vessel level above the top of active fuel with containment challenged.
This condition represents actual or IMMINENT substantial core degradation or melting with potential for loss of containment integrity.
Releases can be reasonably expected to exceed EPA Protective Action Guidelines (PAG) exposure levels offsite for more than the immediate site area.Month XXXX BY 3-121 EP-AA-1002 (Revision XX)
Byron Annex Exellon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CG6 (cont)Basis (cont): Following an extended loss of core decay heat removal and inventory makeup, decay heat will cause reactor coolant boiling and a further reduction in reactor vessel level. If RCS/reactor vessel level cannot be restored, fuel damage is probable.With CONTAINMENT CLOSURE not established, there is a high potential for a direct and unmonitored release of radioactivity to the environment.
If CONTAINMENT CLOSURE is re-established prior to exceeding the 30-minute time limit, then declaration of a General Emergency is not required.The existence of an explosive mixture means, at a minimum, that the containment atmospheric hydrogen concentration is sufficient to support a hydrogen burn (i.e., at the lower deflagration limit). A hydrogen burn will raise containment pressure and could result in collateral equipment damage leading to a loss of containment integrity.
It therefore represents a challenge to Containment integrity.
In the early stages of a core uncovery event, it is unlikely that hydrogen buildup due to a core uncovery could result in an explosive gas mixture in containment.
If all installed hydrogen gas monitors are out-of-service during an event leading to fuel cladding damage, it may not be possible to obtain a containment hydrogen gas concentration reading as ambient conditions within the containment will preclude personnel access.During periods when installed containment hydrogen gas monitors are out-of-service, operators may use the other listed indications to assess whether or not containment is challenged.
The 30-minute criterion is tied to a readily recognizable event start time (i.e., the total loss of ability to monitor level), and allows sufficient time to monitor, assess and correlate reactor and plant conditions to determine if core uncovery has actually occurred (i.e., to account for various accident progression and instrumentation uncertainties).
It also allows sufficient time for performance of actions to terminate leakage, recover inventory control/makeup equipment and/or restore level monitoring.
The inability to monitor reactor vessel/RCS level may be caused by instrumentation and/or power failures, or water level dropping below the range of available instrumentation.
If water level cannot be monitored, operators may determine that an inventory loss is occurring by observing changes in sump and/or tank levels. Sump and/or tank level changes must be evaluated against other potential sources of water flow to ensure they are indicative of leakage from the reactor vessel/RCS.
These EALs address concerns raised by Generic Letter 88-17, Loss of Decay Heat Removal; SECY 91-283, Evaluation of Shutdown and Low Power Risk Issues; NUREG-1449, Shutdown and Low-Power Operation at Commercial Nuclear Power Plants in the United States; and NUMARC 91-06, Guidelines for Industry Actions to Assess Shutdown Management.
Month XXXX BY 3-122 EP-AA-1002 (Revision XX)
R rmn Annoy IPwalnn N, irlator~urnn Anngw ~vaIr~n Nim.v4a~ar RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CG6 (cont)Basis Reference(s):
: 1. NEI 99-01 Rev 6, CG1 2. BOP PC-i, Containment Closure Tracking Capability
: 3. UFSAR E.17, 6.2, 6.2.5.2.1 4. BOP RH-9 Pump Down of the Refueling Cavity to the RWST 5. BOP RC-4 Reactor Coolant System Drain 6. 1/2 BOSR 0.1-4 Unit One(Two) Mode 4 Shiftly and Daily Operating Surveillance
: 7. 1/2 BOSR RF-1 Unit One(Two) Containment Floor Drain Monitoring System Non-Routine Surveillance
: 8. 0/1/2 BOSR XZB-R1, Unit 0/1/2 Meter Zone Banding 9. 1/2 BGP 100-2 Plant Startup 10. BGP 100-6T4 Core Alteration 
/ Fuel Movement Checklist 11. 1/2 BOSR 3.3.1-1 Unit One(Two) Accident Monitoring Instrumentation Monthly Channel Checks 12. 1/2 BFR-C.1, Response to Inadequate Core Cooling Unit 1/2 13. 1/2 BST-5 Containment Unit 1/2 14. NES-G-14.02, Calculation No. BYR99-010 
/ BRW-99-0017-1
: 15. EP-EAL-0501, Estimation Of Radiation Monitor Readings Indicating Core Uncovery During Refueling Month XXXX BY 3-123 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CS6 Initiating Condition:
Loss of reactor vessel/RCS inventory affecting core decay heat removal capability.
Operating Mode Applicability:
5,6 Emergency Action Level (EAL): Note: The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.1. With CONTAINMENT CLOSURE established EITHER:* RVLIS indicates 0% Plenum OR" Reactor Vessel Refueling Level Indicators LT-046 and LT-049 < 392 ft el.OR 2. With CONTAINMENT CLOSURE not established EITHER:* RVLIS < 15% Plenum OR" Reactor Vessel Refueling Level Indicators LT-046 and LT-049< 393 ft. el.OR 3. a. Reactor Vessel level unknown for >30 minutes.AND b. Core uncovery is indicated by ANY of the following:
0 Table C3 indications of a sufficient magnitude to indicate core uncovery.OR* Erratic Source Range Neutron Monitor indication.
OR* 1/2 RE-AR01 1 or 1/2 RE-AR12 Containment Fuel Handling Incident radiation monitors > 3000 mR/hr.Month XXXX BY 3-124 EP-AA-1002 (Revision XX)
Byvron Annex Exelon Nuclear B-ro Annex. .E.....n.Nu..e..
RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CS6 (cont)Emergency Action Level (EAL) (cont): Table C3 -Indications of RCS Leakage" UNPLANNED Containment Sump level rise*" UNPLANNED Auxiliary Bldg. Sump level rise** UNPLANNED Tank level (rad waste) rise** UNPLANNED rise in RCS makeup* Observation of leakage or inventory loss*Rise in level is attributed to a loss of reactor vessel/RCS inventory.
Basis: CONTAINMENT CLOSURE: The procedurally defined conditions or actions taken to secure containment and its associated structures, systems, and components as a functional barrier to fission product release under shutdown conditions.
UNPLANNED:
A parameter change or an event that is not 1) the result of an intended evolution or 2) an expected plant response to a transient.
The cause of the parameter change or event may be known or unknown.The lost inventory may be due to a RCS component failure, a loss of configuration control or prolonged boiling of reactor coolant. These conditions entail major failures of plant functions needed for protection of the public and thus warrant a Site Area Emergency declaration.
Following an extended loss of core decay heat removal and inventory makeup, decay heat will cause reactor coolant boiling and a further reduction in reactor vessel level. If RCS/reactor vessel level cannot be restored, fuel damage is probable.Outage/shutdown contingency plans typically provide for re-establishing or verifying CONTAINMENT CLOSURE following a loss of heat removal or RCS inventory control functions.
The 30-minute criterion is tied to a readily recognizable event start time (i.e., the total loss of ability to monitor level), and allows sufficient time to monitor, assess and correlate reactor and plant conditions to determine if core uncovery has actually occurred (i.e., to account for various accident progression and instrumentation uncertainties).
It also allows sufficient time for performance of actions to terminate leakage, recover inventory control/makeup equipment and/or restore level monitoring.
Month XXXX BY 3-125 EP-AA-1002 (Revision XX)
Rvrmn Annoy P:v--Itn Nwr-lanr RECOGNITION CATEGORY COLD SHUTDOWN I REFUELING SYSTEM MALFUNCTIONS CS6 (cont)Basis (cont): The inability to monitor reactor vessel/RCS level may be caused by instrumentation and/or power failures, or water level dropping below the range of available instrumentation.
If water level cannot be monitored, operators may determine that an inventory loss is occurring by observing changes in sump and/or tank levels. Sump and/or tank level changes must be evaluated against other potential sources of water flow to ensure they are indicative of leakage from the reactor vessel/RCS.
These EALs address concerns raised by Generic Letter 88-17, Loss of Decay Heat Removal; SECY 91-283, Evaluation of Shutdown and Low Power Risk Issues; NUREG-1449, Shutdown and Low-Power Operation at Commercial Nuclear Power Plants in the United States; and NUMARC 91-06, Guidelines for Industry Actions to Assess Shutdown Management.
Escalation of the emergency classification level would be via IC CG6 or RGI.Basis Reference(s):
: 1. NEI 99-01 Rev 6, CS1 2. UFSAR E.17, 6.2 3. BOP RH-9 Pump Down of the Refueling Cavity to the RWST 4. BOP RC-4 Reactor Coolant System Drain 5. 1/2 BOSR 0.1-4 Unit One (Two) Mode 4 Shiftly and Daily Operating Surveillance
: 6. 1/2 BOSR RF-1 Unit One (Two) Containment Floor Drain Monitoring System Non-Routine Surveillance
: 7. 0/1/2 BOSR XZB-R1, Unit 0/1/2 Meter Zone Banding 8. 1/2 BGP 100-2 Plant Startup 9. BGP 100-6T4 Core Alteration 
/ Fuel Movement Checklist 10. 1/2 BOSR 3.3.1-1 Unit One (Two) Accident Monitoring Instrumentation Monthly Channel Checks Month XXXX BY 3-126 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CA6 Initiating Condition:
Loss of reactor vessel/RCS inventory.
Operating Mode Applicability:
5,6 Emergency Action Level (EAL): Note:* The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.1. a. Loss of RCS / Reactor Vessel inventory as indicated RVLIS < 37% Plenum.OR b. Loss of RSC / Reactor Vessel inventory as indicated by LT-046 and LT-049< 393.5 ft. el.OR 2. a. RCS / Reactor Vessel level unknown for > 15 minutes.AND b. Loss of RCS / Reactor Vessel inventory per Table C3 indications.
Table C3 -Indications of RCS Leakage* UNPLANNED Containment Sump level rise** UNPLANNED Auxiliary Bldg. Sump level rise** UNPLANNED Tank level (rad wase) rise*" UNPLANNED rise in RCS makeup* Observation of leakage or inventory loss*Rise in level is attributed to a loss of reactor vessel/RCS inventory.
Month XXXX BY 3-127 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CA6 (cont)Basis: UNPLANNED:
A parameter change or an event that is not 1) the result of an intended evolution or 2) an expected plant response to a transient.
The cause of the parameter change or event may be known or unknown.This IC addresses conditions that are precursors to a loss of the ability to adequately cool irradiated fuel (i.e., a precursor to a challenge to the fuel clad barrier).
This condition represents a potential substantial reduction in the level of plant safety.A lowering of water level below indicated RVLIS < 37% Plenum or LT-046 and LT-049 indicating 
< 393.5 ft. el. indicates that operator actions have not been successful in restoring and maintaining reactor vessel/RCS water level. The heat-up rate of the coolant will rise as the available water inventory is reduced. A continuing drop in water level will lead to core uncovery.Although related, EAL #1 is concerned with the loss of RCS inventory and not the potential concurrent effects on systems needed for decay heat removal (e.g., loss of a Residual Heat Removal suction point). A rise in RCS temperature caused by a loss of decay heat removal capability is evaluated under IC CA5.The inability to monitor reactor vessel/RCS level may be caused by instrumentation and/or power failures, or water level dropping below the range of available instrumentation.
If water level cannot be monitored, operators may determine that an inventory loss is occurring by observing changes in sump and/or tank levels. Sump and/or tank level changes must be evaluated against other potential sources of water flow to ensure they are indicative of leakage from the reactor vessel/RCS.
The 15-minute duration for the loss of level indication was chosen because it is half of the Threshold duration specified in IC CS6 If the reactor vessel/RCS inventory level continues to lower, then escalation to Site Area Emergency would be via IC CS6.Basis Reference(s):
: 1. NEI 99-01 Rev 6, CA1 2. UFSAR 6.2 & E.17 3. 1/2 BOSR 0.1-4 Unit One(Two) Mode 4 Shiftly and Daily Operating Surveillance
: 4. 1/2 BOSR RF-1 Unit One(Two) Containment Floor Drain Monitoring System Non-Routine Surveillance
: 5. 0/1/2 BOSR XZB-R1, Unit 0/1/2 Meter Zone Banding 6. BOP RH-9 Pump Down of the Refueling Cavity to the RWST 7. BOP RC-4 Reactor Coolant System Drain Month XXXX BY 3-128 EP-AA-1002 (Revision XX)
Bvron Annex ByronAnnexExelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CU6 Initiating Condition:
UNPLANNED loss of reactor vessel/RCS inventory for 15 minutes or longer.Operating Mode Applicability:
5,6 Emergency Action Level (EAL): Note:* The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.1. UNPLANNED loss of reactor coolant results in the inability to restore and maintain Reactor Vessel / RCS level to > procedurally established lower limit for > 15 minutes.OR 2. a. Reactor Vessel / RCS level unknown.AND b. Loss of RCS / Reactor Vessel inventory per Table C3 indications.
Table C3 -Indications of RCS Leakage" UNPLANNED Containment Sump level rise*" UNPLANNED Auxiliary Bldg. Sump level rise*" UNPLANNED Tank level (rad waste) rise** UNPLANNED rise in RCS makeup* Observation of leakage or inventory loss*Rise in level is attributed to a loss of reactor vessel/RCS inventory.
Basis: UNPLANNED:
A parameter change or an event that is not 1) the result of an intended evolution or 2) an expected plant response to a transient.
The cause of the parameter change or event may be known or unknown.This IC addresses the inability to restore and maintain water level to a required minimum level (or the lower limit of a level band), or a loss of the ability to monitor reactor vessel/RCS level concurrent with indications of coolant leakage. Either of these conditions is considered to be a potential degradation of the level of safety of the plant.Month XXXX BY 3-129 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CU6 (cont)Basis (cont): Refueling evolutions that decrease RCS water inventory are carefully planned and controlled.
An UNPLANNED event that results in water level decreasing below a procedurally required limit warrants the declaration of an Unusual Event due to the reduced water inventory that is available to keep the core covered.EAL #1 recognizes that the minimum required reactor vessel/RCS level can change several times during the course of a refueling outage as different plant configurations and system lineups are implemented.
This EAL is met if the minimum level, specified for the current plant conditions, cannot be maintained for 15 minutes or longer. The minimum level is typically specified in the applicable operating procedure but may be specified in another controlling document.The procedurally established lower limit is not an operational band established above the procedural limit to allow for operator action prior to exceeding the procedural limit, but it is the procedurally established lower limit.The 15-minute threshold duration allows sufficient time for prompt operator actions to restore and maintain the expected water level. This criterion excludes transient conditions causing a brief lowering of water level.EAL #2 addresses a condition where all means to determine have been lost. In this condition, operators may determine occurring by observing changes in sump and/or tank levels.changes must be evaluated against other potential sources of are indicative of leakage from the reactor vessel/RCS.
Continued loss of RCS inventory may result in escalation classification level via either IC CA6 or CA5.reactor vessel/RCS level that an inventory loss is Sump and/or tank level water flow to ensure they to the Alert emergency Month XXXX BY 3-130 EP-AA-1002 (Revision XX)
Rvrnn  Fxp-lon Nuclear r-t rnn AnnexEelnNula RECOGNITION CATEGORY COLD SHUTDOWN / REFUELING SYSTEM MALFUNCTIONS CU6 (cont)Basis Reference(s):
: 1. NEI 99-01, Rev. 6 CUl 2. UFSAR 6.2 & E. 17 3. 1/2 BOSR 0.1-4 Unit One (Two) Mode 4 Shiftly and Daily Operating Surveillance
: 4. 1/2 BOS RF-1 Unit One (Two) Containment Floor Drain Monitoring System Non-Routine Surveillance
: 5. 0/1/2 BOSR XZB-R1, Unit 0/1/2 Meter Zone Banding 6. BOP RH-9 Pump Down of the Refueling Cavity to the RWST 7. BOP RC-4 Reactor Coolant System Drain Month XXXX BY 3-131 EP-AA-1002 (Revision XX)
Rvrnn N  Rurnn Annex Fvelnon NucleI~ar RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HG1 Initiating Condition:
HOSTILE ACTION resulting in loss of physical control of the facility.Operating Mode Applicability:
1, 2, 3, 4, 5, 6, D Emergency Action Level (EAL): 1. A notification from the Security Force that a HOSTILE ACTION is occurring or has occurred within the PROTECTED AREA.AND 2. a. ANY Table H1 safety function cannot be controlled or maintained.
OR b. Damage to spent fuel has occurred or is IMMINENT Table H1 -Safety Functions* Reactivity Control(ability to shut down the reactor and keep it shutdown)* Core Cooling (ability to cool the core)" RCS Heat Removal (ability to maintain heat sink)Basis: HOSTILE ACTION: An act toward a NPP or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, PROJECTILEs, vehicles, or other devices used to deliver destructive force. Other acts that satisfy the overall intent may be included.
HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on the NPP. Non-terrorism-based EALs should be used to address such activities (i.e., this may include violent acts between individuals in the owner controlled area).HOSTAGE: A person(s) held as leverage against the station to ensure that demands will be met by the station.PROJECTILE:
An object directed toward a NPP that could cause concern for its continued operability, reliability, or personnel safety.PROTECTED AREA: An area that normally encompasses all controlled areas within the security protected area fence.IMMINENT:
The trajectory of events or conditions is such that an EAL will be met within a relatively short period of time regardless of mitigation or corrective actions.Month XXXX BY 3-132 EP-AA-1002 (Revision XX)
Byvron Annex Exelon Nuclear--. Annex....Exelon Nuc.lear RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HG1 (cont)Basis (cont): HOSTILE FORCE: Any individuals who are engaged in a determined assault, overtly or by stealth and deception, equipped with suitable weapons capable of killing, maiming, or causing destruction.
This IC addresses an event in which a HOSTILE FORCE has taken physical control of the facility to the extent that the plant staff can no longer operate equipment necessary to maintain key safety functions.
It also addresses a HOSTILE ACTION leading to a loss of physical control that results in actual or IMMINENT damage to spent fuel due to 1) damage to a spent fuel pool cooling system (e.g., pumps, heat exchangers, controls, etc.) or, 2) loss of spent fuel pool integrity such that sufficient water level cannot be maintained.
Timely and accurate communications between Security Shift Supervision and the Control Room is essential for proper classification of a security-related event.Security plans and terminology are based on the guidance provided by NEI 03-12, Template for the Security Plan, Training and Qualification Plan, Safeguards Contingency Plan [and Independent Spent Fuel Storage Installation Security Program].Basis Reference(s):
: 1. NEI 99-01, Rev. 6 HG1 5. Station Security Plan -Appendix C Month XXXX BY 3-133 EP-AA-1002 (Revision XX)
Byvron Annex Exelon Nuclear yr-n Annex...Exelon Nuclear RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HS1 Initiating Condition:
HOSTILE ACTION within the PROTECTED AREA.Operating Mode Applicability:
1, 2, 3, 4, 5, 6, D Emergency Action Level (EAL): A notification from the Security Force that a HOSTILE ACTION is occurring or has occurred within the PROTECTED AREA.Basis: HOSTILE ACTION: An act toward a NPP or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, PROJECTILEs, vehicles, or other devices used to deliver destructive force. Other acts that satisfy the overall intent may be included.
HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on the NPP. Non-terrorism-based EALs should be used to address such activities (i.e., this may include violent acts between individuals in the owner controlled area).HOSTAGE: A person(s) held as leverage against the station to ensure that demands will be met by the station.PROJECTILE:
An object directed toward a NPP that could cause concern for its continued operability, reliability, or personnel safety.PROTECTED AREA: An area that normally encompasses all controlled areas within the security protected area fence.HOSTILE FORCE: Any individuals who are engaged in a determined assault, overtly or by stealth and deception, equipped with suitable weapons capable of killing, maiming, or causing destruction.
INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI): A complex that is designed and constructed for the interim storage of spent nuclear fuel and other radioactive materials associated with spent fuel storage.This IC addresses the occurrence of a HOSTILE ACTION within the PROTECTED AREA. This event will require rapid response and assistance due to the possibility for damage to plant equipment.
Timely and accurate communications between Security Shift Supervision and the Control Room is essential for proper classification of a security-related event.Month XXXX BY 3-134 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear Br Annex......Exelon Nuclear RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HSl (cont)Basis (cont): Security plans and terminology are based on the guidance provided by NEI 03-12, Template for the Security Plan, Training and Qualification Plan, Safeguards Contingency Plan [and Independent Spent Fuel Storage Installation Security Program].As time and conditions allow, these events require a heightened state of readiness by the plant staff and implementation of onsite protective measures (e.g., evacuation, dispersal or sheltering).
The Site Area Emergency declaration will mobilize ORO resources and have them available to develop and implement public protective actions in the unlikely event that the attack is successful in impairing multiple safety functions.
This IC does not apply to a HOSTILE ACTION directed at an ISFSI PROTECTED AREA located outside the plant PROTECTED AREA; such an attack should be assessed using IC HA1. It also does not apply to incidents that are accidental events, acts of civil disobedience, or otherwise are not a HOSTILE ACTION perpetrated by a HOSTILE FORCE. Examples include the crash of a small aircraft, shots from hunters, physical disputes between employees, etc. Reporting of these types of events is adequately addressed by other EALs, or the requirements of 10 CFR &sect; 73.71 or 10 CFR&sect; 50.72.Escalation of the emergency classification level would be via IC HG1.Basis Reference(s):
: 1. NEI 99-01 Rev 6, HS1 3. Station Security Plan -Appendix C Month XXXX BY 3-135 EP-AA-1002 (Revision XX)
Byvron Annex Exelon Nuclear ByronAnnexExelon NuceIar RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HA1 Initiating Condition:
HOSTILE ACTION within the OWNER CONTROLLED AREA or airborne attack threat within 30 minutes.Operating Mode Applicability:
1, 2, 3, 4, 5, 6, D Emergency Action Level (EAL): 1. A validated notification from NRC of an aircraft attack threat < 30 minutes from the site.OR 2. Notification by the Security Force that a HOSTILE ACTION is occurring or has occurred within the OWNER CONTROLED AREA.Basis: HOSTILE ACTION: An act toward a NPP or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, PROJECTILEs, vehicles, or other devices used to deliver destructive force. Other acts that satisfy the overall intent may be included.
HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on the NPP. Non-terrorism-based EALs should be used to address such activities (i.e., this may include violent acts between individuals in the owner controlled area).HOSTAGE: A person(s) held as leverage against the station to ensure that demands will be met by the station.PROJECTILE:
An object directed toward a NPP that could cause concern for its continued operability, reliability, or personnel safety.OWNER CONTROLLED AREA (OCA): The property associated with the station and owned by the company. Access is normally limited to persons entering for official business.PROTECTED AREA: An area that normally encompasses all controlled areas within the security protected area fence.HOSTILE FORCE: Any individuals who are engaged in a determined assault, overtly or by stealth and deception, equipped with suitable weapons capable of killing, maiming, or causing destruction.
This IC addresses the occurrence of a HOSTILE ACTION within the OWNER CONTROLLED AREA or notification of an aircraft attack threat. This event will require rapid response and assistance due to the possibility of the attack progressing to the PROTECTED AREA, or the need to prepare the plant and staff for a potential aircraft impact.Month XXXX BY 3-136 EP-AA-1002 (Revision XX)
R rtnn Ann-v=~vnlrn k::lp--onr RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HA1 (cont)Basis (cont): Timely and accurate communications between Security Shift Supervision and the Control Room is essential for proper classification of a security-related event.Security plans and terminology are based on the guidance provided by NEI 03-12, Template for the Security Plan, Training and Qualification Plan, Safeguards Contingency Plan [and Independent Spent Fuel Storage Installation Security Program].As time and conditions allow, these events require a heightened state of readiness by the plant staff and implementation of onsite protective measures (e.g., evacuation, dispersal or sheltering).
The Alert declaration will also heighten the awareness of Offsite Response Organizations, allowing them to be better prepared should it be necessary to consider further actions.This IC does not apply to incidents that are accidental events, acts of civil disobedience, or otherwise are not a HOSTILE ACTION perpetrated by a HOSTILE FORCE.Examples include the crash of a small aircraft, shots from hunters, physical disputes between employees, etc. Reporting of these types of events is adequately addressed by other EALs, or the requirements of 10 CFR &sect; 73.71 or 10 CFR &sect; 50.72.EAL #1 addresses the threat from the impact of an aircraft on the plant, and the anticipated arrival time is within 30 minutes. The intent of this EAL is to ensure that threat-related notifications are made in a timely manner so that plant personnel and OROs are in a heightened state of readiness.
This EAL is met when the threat-related information has been validated in accordance with 0BOA Security-I, Security Threat.EAL #2 is applicable for any HOSTILE ACTION occurring, or that has occurred, in the OWNER CONTROLLED AREA. This includes any action directed against an ISFSI that is located outside the plant PROTECTED AREA.The NRC Headquarters Operations Officer (HOO) will communicate to the licensee if the threat involves an aircraft.
The status and size of the plane may be provided by NORAD through the NRC.In some cases, it may not be readily apparent if an aircraft impact within the OWNER CONTROLLED AREA was intentional (i.e., a HOSTILE ACTION). It is expected, although not certain, that notification by an appropriate Federal agency to the site would clarify this point. In this case, the appropriate federal agency is intended to be NORAD, FBI, FAA or NRC. The emergency declaration, including one based on other ICs/EALs, should not be unduly delayed while awaiting notification by a Federal agency.Escalation of the emergency classification level would be via IC HS1.Month XXXX BY 3-137 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HAI (cont)Basis Reference(s):
: 1. NEI 99-01 Rev 6, HA1 2. SY-AA-101-132, Security Assessment and Response to Unusual Activities
: 3. Station Security Plan -Appendix C 4. 0BOA Security-I, Security Threat Unit 0 Month XXXX BY 3-138 EP-AA-1002 (Revision XX)
Rvron Annex I=xelon Nuclear Bvrnn Annex Exelon Nuclanr RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HU1 Initiating Condition:
Confirmed SECURITY CONDITION or threat.Operating Mode Applicability:
1, 2, 3, 4, 5, 6, D Emergency Action Level (EAL): 1. Notification of a credible security threat directed at the site as determined per SY-AA-101-132, Security Assessment and Response to Unusual Activities.
OR 2. A validated notification from the NRC providing information of an aircraft threat.OR 3. Notification by the Security Force of a SECURITY CONDITION that does not involve a HOSTILE ACTION.Basis: SECURITY CONDITION:
Any Security Event as listed in the approved security contingency plan that constitutes a threat/compromise to site security, threat/risk to site personnel, or a potential degradation to the level of safety of the plant. A SECURITY CONDITION does not involve a HOSTILE ACTION SAFETY SYSTEM: A system required for safe plant operation, cooling down the plant and/or placing it in the cold shutdown condition, including the ECCS. These are typically systems classified as safety-related.
HOSTILE ACTION: An act toward a NPP or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, PROJECTILEs, vehicles, or other devices used to deliver destructive force. Other acts that satisfy the overall intent may be included.
HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on the NPP. Non-terrorism-based EALs should be used to address such activities (i.e., this may include violent acts between individuals in the owner controlled area).HOSTAGE: A person(s) held as leverage against the station to ensure that demands will be met by the station.PROJECTILE:
An object directed toward a NPP that could cause concern for its continued operability, reliability, or personnel safety.Month XXXX BY 3-139 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HUI (cont)Basis (cont): This IC addresses events that pose a threat to plant personnel or SAFETY SYSTEM equipment, and thus represent a potential degradation in the level of plant safety.Security events which do not meet one of these EALs are adequately addressed by the requirements of 10 CFR &sect; 73.71 or 10 CFR &sect; 50.72. Security events assessed as HOSTILE ACTIONS are classifiable under ICs HA1, HS1 and HG1.Timely and accurate communications between Security Shift Supervision and the Control Room is essential for proper classification of a security-related event.Classification of these events will initiate appropriate threat-related notifications to plant personnel and OROs.Security plans and terminology are based on the guidance provided by NEI 03-12, Template for the Security Plan, Training and Qualification Plan, Safeguards Contingency Plan [and Independent Spent Fuel Storage Installation Security Program].EAL #1 Basis Addresses the receipt of a credible security threat. The credibility of the threat is assessed in accordance with SY-AA-101-132, Security Assessment and Response to Unusual Events..EAL #2 Basis Addresses the threat from the impact of an aircraft on the plant. The NRC Headquarters Operations Officer (HOO) will communicate to the licensee if the threat involves an aircraft.
The status and size of the plane may also be provided by NORAD through the NRC. Validation of the threat is performed in accordance with OBOA Security-I, Security Threat.EAL #3 Basis References Security Force because these are the individuals trained to confirm that a security event is occurring or has occurred.
Training on security event confirmation and classification is controlled due to the nature of Safeguards and 10 CFR &sect; 2.39 information.
Escalation of the emergency classification level would be via IC HA1.Basis Reference(s):
: 1. NEI 99-01 Rev 6, HU1 2. SY-AA-101-132, Security Assessment and Response to Unusual Activities
: 3. Station Security Plan -Appendix C 4. NRC Safeguards Advisory 10/6/01 5. Letter from Mr. B. A. Boger (NRC) to Ms. Lynette Hendricks (NEI) dated 2/4/02 6. OBOA Security-i, Security Threat Unit 0 Month XXXX BY 3-140 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear Byron Annex Exelon Nuclear RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HS2 Initiating Condition:
Inability to control a key safety function from outside the Control Room.Operating Mode Applicability:
1,2,3, 4,5,6, D Emergency Action Level (EAL): Note:* The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.1. A Control Room evacuation has resulted in plant control being transferred from the Control Room to alternate locations per 1/2BOA PRI-5, Control Room Inaccessibility.
AND 2. Control of ANY Table H1 key safety function is not reestablished in < 15 minutes.Table H1 -Safety Functions* Reactivity Control(ability to shut down the reactor and keep it shutdown)* Core Cooling (ability to cool the core)* RCS Heat Removal (ability to maintain heat sink)Basis: The time period to establish control of the plant starts when either: a. Control of the plant is no longer maintained in the Main Control Room OR b. The last Operator has left the Main Control Room.This IC addresses an evacuation of the Control Room that results in transfer of plant control to alternate locations, and the control of a key safety function cannot be reestablished in a timely manner. The failure to gain control of a key safety function following a transfer of plan control to alternate locations is a precursor to a challenge to any fission product barriers within a relatively short period of time.The determination of whether or not "control" is established at the remote safe shutdown location(s) is based on Emergency Director judgment.
The Emergency Director is expected to make a reasonable, informed judgment within 15 minutes whether or not the operating staff has control of key safety functions from the remote safe shutdown location(s).
Month XXXX BY 3-141 EP-AA-1002 (Revision XX)
Byron Annex Exellon Nuclear RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HS2 (cont)Basis (cont): Escalation of the emergency classification level would be via IC FG1 or CG6.Basis Reference(s):
: 1. NEI 99-01, Rev 6 HS6 2. 1/2BOA PRI-5, Control Room Inaccessibility Unit 1/2 Month XXXX BY 3-142 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HA2 Initiating Condition:
Control Room evacuation resulting in transfer of plant control to alternate locations.
Operating Mode Applicability:
1, 2, 3, 4, 5, 6, D Emergency Action Level (EAL): A Control Room evacuation has resulted in plant control being transferred from the Control Room to alternate locations per 1/2BOA PRI-5, Control Room Inaccessibility.
Basis: This IC addresses an evacuation of the Control Room that results in transfer of plant control to alternate locations outside the Control Room. The loss of the ability to control the plant from the Control Room is considered to be a potential substantial degradation in the level of plant safety.Following a Control Room evacuation, control of the plant will be transferred to alternate shutdown locations.
The necessity to control a plant shutdown from outside the Control Room, in addition to responding to the event that required the evacuation of the Control Room, will present challenges to plant operators and other on-shift personnel.
Activation of the ERO and emergency response facilities will assist in responding to these challenges.
Escalation of the emergency classification level would be via IC HS2.Basis Reference(s):
: 1. NEI 99-01, Rev 6 HA6 2. 1/2BOA PRI-5, Control Room Inaccessibility Unit 1/2 Month XXXX BY 3-143 EP-AA-1002 (Revision XX)
Rvrnn  Rvrnn Annexv FYAlnn Nwilor~I RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HU3 Initiating Condition:
FIRE potentially degrading the level of safety of the plant.Operating Mode Applicability:
1, 2, 3, 4, 5, 6, D Emergency Action Level (EAL): Note:* The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.1. A FIRE in ANY Table H2 area is not extinguished in < 15-minutes of ANY of the following FIRE detection indications:
* Report from the field (i.e., visual observation)" Receipt of multiple (more than 1) fire alarms or indications" Field verification of a single fire alarm OR 2. a. Receipt of a single fire alarm in ANY Table H2 area (i.e., no other indications of a FIRE).AND b. The existence of a FIRE is not verified in < 30 minutes of alarm receipt.OR 3. A FIRE within the plant PROTECTED AREA not extinguished in < 60-minutes of the initial report, alarm or indication.
OR 4. A FIRE within the plant PROTECTED AREA that requires firefighting support by an offsite fire response agency to extinguish.
Table H2 -Vital Areas" Containment" Auxiliary Building* Fuel Handling Building* Main Steam Tunnels" RWST's" Condensate Storage Tanks" Essential Service Water Cooling Towers Month XXXX BY 3-144 EP-AA-1002 (Revision XX)
Rvrnn  I::Y,-.Inn Bvron Annoy Pvgalnn khig-hanr RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HU3 (cont)Basis: FIRE: Combustion characterized by heat and light. Sources of smoke such as slipping drive belts or overheated electrical equipment do not constitute FIRES. Observation of flame is preferred but is NOT required if large quantities of smoke and heat are observed.PROTECTED AREA: An area that normally encompasses all controlled areas within the security protected area fence.This IC addresses the magnitude and extent of FIRES that may be indicative of a potential degradation of the level of safety of the plant.EAL #1 Basis The intent of the 15-minute duration is to size the FIRE and to discriminate against small FIRES that are readily extinguished (e.g., smoldering waste paper basket). In addition to alarms, other indications of a FIRE could be a drop in fire main pressure, automatic activation of a suppression system, etc.Upon receipt, operators will take prompt actions to confirm the validity of an initial fire alarm, indication, or report. For EAL assessment purposes, the emergency declaration clock starts at the time that the initial alarm, indication, or report was received, and not the time that a subsequent verification action was performed.
Similarly, the fire duration clock also starts at the time of receipt of the initial alarms, indication or report.EAL #2 Basis This EAL addresses receipt of a single fire alarm, and the existence of a FIRE is not verified (i.e., proved or disproved) within 30-minutes of the alarm. Upon receipt, operators will take prompt actions to confirm the validity of a single fire alarm. For EAL assessment purposes, the 30-minute clock starts at the time that the initial alarm was received, and not the time that a subsequent verification action was performed.
A single fire alarm, absent other indication(s) of a FIRE, may be indicative of equipment failure or a spurious activation, and not an actual FIRE. For this reason, additional time is allowed to verify the validity of the alarm. The 30-minute period is a reasonable amount of time to determine if an actual FIRE exists; however, after that time, and absent information to the contrary, it is assumed that an actual FIRE is in progress.If an actual FIRE is verified by a report from the field, then EAL #1 is immediately applicable, and the emergency must be declared if the FIRE is not extinguished within 15-minutes of the report. If the alarm is verified to be due to an equipment failure or a spurious activation, and this verification occurs within 30-minutes of the receipt of the alarm, then this EAL is not applicable and no emergency declaration is warranted.
EAL #3 Basis In addition to a FIRE addressed by EAL #1 or EAL #2, a FIRE within the plant PROTECTED AREA not extinguished within 60-minutes may also potentially degrade the level of plant safety.Month XXXX BY 3-145 EP-AA-1002 (Revision XX) iQl A nndav Ivgalrnn Kh,,rlimr RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HU3 (cont)Basis (cont): EAL #4 Basis If a FIRE within the plant PROTECTED AREA is of sufficient size to require a response by an offsite firefighting agency (e.g., a local town Fire Department), then the level of plant safety is potentially degraded.
The dispatch of an offsite firefighting agency to the site requires an emergency declaration only if it is needed to actively support firefighting efforts because the fire is beyond the capability of the Fire Brigade to extinguish.
Declaration is not necessary if the agency resources are placed on stand-by, or supporting post-extinguishment recovery or investigation actions.Basis-Related Requirements from Appendix R Appendix R to 10 CFR 50, states in part: Criterion 3 of Appendix A to this part specifies that "Structures, systems, and components important to safety shall be designed and located to minimize, consistent with other safety requirements, the probability and effect of fires and explosions." When considering the effects of fire, those systems associated with achieving and maintaining safe shutdown conditions assume major importance to safety because damage to them can lead to core damage resulting from loss of coolant through boil-off.Because fire may affect safe shutdown systems and because the loss of function of systems used to mitigate the consequences of design basis accidents under post-fire conditions does not per se impact public safety, the need to limit fire damage to systems required to achieve and maintain safe shutdown conditions is greater than the need to limit fire damage to those systems required to mitigate the consequences of design basis accidents.
In addition, Appendix R to 10 CFR 50, requires, among other considerations, the use of 1-hour fire barriers for the enclosure of cable and equipment and associated non-safety circuits of one redundant train (G.2.c). As used in EAL #2, the 30-minutes to verify a single alarm is well within this worst-case 1-hour time period.Depending upon the plant mode at the time of the event, escalation of the emergency classification level would be via IC CA2 or MA5.Basis Reference(s):
: 1. NEI 99-01, Rev 6 HU4 2. Drawing S-01A Composite Site Plan 3. UFSAR Section 3.02 4. BAP-1 100, Fire Protection Procedure Series Month XXXX BY 3-146 EP-AA-1002 (Revision XX)
Bvron Annex Exelon Nuclear ByronAnnexExelon Nucla~r RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HU4 Initiating Condition:
Seismic event greater than OBE levels.Operating Mode Applicability:
1,2, 3, 4, 5, 6, D Emergency Action Level (EAL): Seismic event > Operating Basis Earthquake (OBE) as indicated by seismic check at panel OPA02J.Basis: This IC addresses a seismic event that results in accelerations at the plant site greater than those specified for an Operating Basis Earthquake (OBE)1.An earthquake greater than an OBE but less than a Safe Shutdown Earthquake (SSE)2 should have no significant impact on safety-related systems, structures and components; however, some time may be required for the plant staff to ascertain the actual post-event condition of the plant (e.g., performs walk-downs and post-event inspections).
Given the time necessary to perform walk-downs and inspections, and fully understand any impacts, this event represents a potential degradation of the level of safety of the plant.Event verification with external sources should not be necessary during or following an OBE. Earthquakes of this magnitude should be readily felt by on-site personnel and recognized as a seismic event (e.g., typical lateral accelerations are in excess of 0.08g).The Shift Manager or Emergency Director may seek external verification if deemed appropriate (e.g., a call to the USGS, check internet news sources, etc.); however, the verification action must not preclude a timely emergency declaration.
Depending upon the plant mode at the time of the event, escalation of the emergency classification level would be via IC CA2 or MA5.Basis Reference(s):
: 1. NEI 99-01, Rev 6 HU2 2. OBOA ENV-4 Earthquake
: 3. Annunciator 0-38-E5 Accelograph Accel High 1 An OBE is vibratory ground motion for which those features of a nuclear power plant necessary for continued operation without undue risk to the health and safety of the?ublic will remain functional.
An SSE is vibratory ground motion for which certain (generally, safety-related) structures, systems, and components must be designed to remain functional.
Month XXXX BY 3-147 EP-AA-1002 (Revision XX)
P. rrn Annv P::vgmln KI~d-lgmr-* * ..rTh. .. .n ~ .~. ...--~RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HA5 Initiating Condition:
Gaseous release impeding access to equipment necessary for normal plant operations, cooldown or shutdown.Operating Mode Applicability:
1,2, 3, 4, 5, 6, D Emergency Action Level (EAL): Note:* If the equipment in the listed room or area was already inoperable, or out of service, before the event occurred, then no emergency classification is warranted.
: 1. Release of a toxic, corrosive, asphyxiant or flammable gas in ANY Table H3 area.Table H3 Areas with Entry Related Mode Applicability Area Entry Related Mode Applicability Auxiliary Building*
Mode 4, 5, and 6*Areas required to establish shutdown cooling AND 2. Entry into the room or area is prohibited or impeded.Basis: This IC addresses an event involving a release of a hazardous gas that precludes or impedes access to equipment necessary to transition the plant from normal plant operation to cooldown and shutdown as specified in normal plant procedures.
This condition represents an actual or potential substantial degradation of the level of safety of the plant.Table H3 is a list of plant rooms or areas with entry-related mode applicability that contain equipment which require a manual/local action necessary to transition the plant from normal plant operation to cooldown and shutdown as specified in normal operating procedures (establish shutdown cooling), where if this action is not completed the plant would not be able to attain and maintain cold shutdown.Month XXXX BY 3-148 EP-AA-1002 (Revision XX)
Byron Annex Exallon Nuclear RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HA5 (cont)Basis (cont): This Table does not include rooms or areas for which entry is required solely to perform actions of an administrative or record keeping nature (e.g., normal rounds or routine inspections).
This Table does not include the Control Room since adequate engineered safety/design features are in place to preclude a Control Room evacuation due to the release of a hazardous gas.An Alert declaration is warranted if entry into the affected room/area is, or may be, procedurally required during the plant operating mode in effect and the gaseous release preclude the ability to place shutdown cooling in service. The emergency classification is not contingent upon whether entry is actually necessary at the time of the release.Evaluation of the IC and EAL do not require atmospheric sampling; it only requires the Emergency Director's judgment that the gas concentration in the affected room/area is sufficient to preclude or significantly impede procedurally required access. This judgment may be based on a variety of factors including an existing job hazard analysis, report of ill effects on personnel, advice from a subject matter expert or operating experience with the same or similar hazards. Access should be considered as impeded if extraordinary measures are necessary to facilitate entry of personnel into the affected room/area (e.g., requiring use of protective equipment, such as SCBAs, that is not routinely employed).
An emergency declaration is not warranted if any of the following conditions apply.* The plant is in an operating mode different than the mode specified for the affected room/area (i.e., entry is not required during the operating mode in effect at the time of the gaseous release).
For example, the plant is in Mode 1 when the gaseous release occurs, and the procedures used for normal operation, cooldown and shutdown do not require entry into the affected room until Mode 4." The gas release is a planned activity that includes compensatory measures which address the temporary inaccessibility of a room or area (e.g., fire suppression system testing)." The action for which room/area entry is required is of an administrative or record keeping nature (e.g., normal rounds or routine inspections)." The access control measures are of a conservative or precautionary nature, and would not actually prevent or impede a required action.Month XXXX BY 3-149 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear Byron Annex..Exelon Nuclear RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HA5 (cont)Basis (cont): An asphyxiant is a gas capable of redpCing the level of oxygen in the body to dangerous levels. Most commonly, asphyxiants work by merely displacing air in an enclosed environment.
This reduces the concentration of oxygen below the normal level of around 19%, which can lead to breathing difficulties, unconsciousness or even death.This EAL does not apply to firefighting activities, that generate smoke or that automatically or manually activate a fire suppression system in an area.Escalation of the emergency classification level would be via Recognition Category R, C or F 1Cs.Basis Reference(s):
: 1. NEI 99-01, Rev 6 HA5 2. Drawing S-01A Composite Site Plan 3. UFSAR Section 3.02 4. ACIT 660892-13, Station Halon Discharge IDLH Evaluation Month XXXX BY 3-150 EP-AA-1002 (Revision XX)
R rnn A nn-av Pv--I1rn Khir-lmr RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HU6 Initiating Condition:
Hazardous Event Operating Mode Applicability:
1, 2,3,4,5,6, D Emergency Action Level (EAL): Note: EAL #4 does not apply to routine traffic impediments such as fog, snow, ice, or vehicle breakdowns or accidents.
: 1. Tornado strike within the PROTECTED AREA.OR 2. Internal room or area flooding of a magnitude sufficient to require manual or automatic electrical isolation of a SAFETY SYSTEM component required by Technical Specifications for the current operating mode.OR 3. Movement of personnel within the PROTECTED AREA is impeded due to an offsite event involving hazardous materials (e.g., an offsite chemical spill or toxic gas release).OR 4. A hazardous event that results in on-site conditions sufficient to prohibit the plant staff from accessing the site via personal vehicles.Basis: PROTECTED AREA: An area that normally encompasses all controlled areas within the security protected area fence.SAFETY SYSTEM: A system required for safe plant operation, cooling down the plant and/or placing it in the cold shutdown condition, including the ECCS. These are typically systems classified as safety-related.
This IC addresses hazardous events that are considered to represent a potential degradation of the level of safety of the plant.EAL #1 Basis Addresses a tornado striking (touching down) within the Protected Area.Month XXXX BY 3-151 EP-AA-1002 (Revision XX)
Rvron Annex Exelan Nuclear Bvrnn Annex Exelnon Nucleamr RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HU6 (cont)Basis (cont): EAL #2 Basis Addresses flooding of a building room or area that results in operators isolating power to a SAFETY SYSTEM component due to water level or other wetting concerns.Classification is also required if the water level or related wetting causes an automatic isolation of a SAFETY SYSTEM component from its power source (e.g., a breaker or relay trip). To warrant classification, operability of the affected component must be required by Technical Specifications for the current operating mode. Manual isolation of power to a SAFETY SYSTEM component as a result of leakage is an event of lesser impact and would be expected to cause small and localized damage. The consequence of this type of event is adequately assessed and addressed in accordance with Technical Specifications.
EAL #3 Basis Addresses a hazardous materials event originating at an offsite location and of sufficient magnitude to impede the movement of personnel within the PROTECTED AREA.EAL #4 Basis Addresses a hazardous event that causes an on-site impediment to vehicle movement and significant enough to prohibit the plant staff from accessing the site using personal vehicles.
Examples of such an event include site flooding caused by a hurricane, heavy rains, up-river water releases, dam failure, etc., or an on-site train derailment blocking the access road.This EAL is not intended to apply to routine impediments such as fog, snow, ice, or vehicle breakdowns or accidents, but rather to more significant conditions such as the Hurricane Andrew strike on Turkey Point in 1992, the flooding around the Cooper Station during the Midwest floods of 1993, or the flooding around Ft. Calhoun Station in 2011.Escalation of the emergency classification level would be based on ICs in Recognition Categories R, F, M, H or C.Basis Reference(s):
: 1. NEI 99-01, Rev 6 HU3 Month XXXX BY 3-152 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HG7 Initiating Condition:
Other conditions exist which in the judgment of the Emergency Director warrant declaration of a GENERAL EMERGENCY.
Operating Mode Applicability:
1, 2, 3, 4, 5, 6, D Emergency Action Level (EAL): Other conditions exist which in the judgment of the Emergency Director indicate that events are in progress or have occurred which involve actual or IMMINENT substantial core degradation or melting with potential for loss of containment integrity or HOSTILE ACTION that results in an actual loss of physical control of the facility.
Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area.Basis: IMMINENT:
The trajectory of events or conditions is such that an EAL will be met within a relatively short period of time regardless of mitigation or corrective actions.HOSTILE ACTION: An act toward a NPP or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, PROJECTILEs, vehicles, or other devices used to deliver destructive force. Other acts that satisfy the overall intent may be included.
HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on the NPP. Non-terrorism-based EALs should be used to address such activities (i.e., this may include violent acts between individuals in the owner controlled area).HOSTAGE: A person(s) held as leverage against the station to ensure that demands will be met by the station PROJECTILE:
An object directed toward a NPP that could cause concern for its continued operability, reliability, or personnel safety.This IC addresses unanticipated conditions not addressed explicitly elsewhere but that warrant declaration of an emergency because conditions exist which are believed by the Emergency Director to fall under the emergency classification level description for a General Emergency.
Basis Reference(s):
: 1. NEI 99-01, Rev 6 HG7 Month XXXX BY 3-153 EP-AA-1002 (Revision XX)
Rvron Bvrnn Annex FwAlnn Nucler~I RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HS7 Initiating Condition:
Other conditions exist which in the judgment of the Emergency Director warrant declaration of a SITE AREA EMERGENCY.
Operating Mode Applicability:
1, 2, 3, 4, 5, 6, D Emergency Action Level (EAL): Other conditions exist which in the judgment of the Emergency Director indicate that events are in progress or have occurred which involve actual or likely major failures of plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts, (1) toward site personnel or equipment that could lead to the likely failure of or, (2) that prevent effective access to equipment needed for the protection of the public. Any releases are not expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels beyond the site boundary.Basis: HOSTILE ACTION: An act toward a NPP or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, PROJECTILEs, vehicles, or other devices used to deliver destructive force. Other acts that satisfy the overall intent may be included.
HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on the NPP. Non-terrorism-based EALs should be used to address such activities (i.e., this may include violent acts between individuals in the owner controlled area).HOSTAGE: A person(s) held as leverage against the station to ensure that demands will be met by the station PROJECTILE:
An object directed toward a NPP that could cause concern for its continued operability, reliability, or personnel safety.This IC addresses unanticipated conditions not addressed explicitly elsewhere but that warrant declaration of an emergency because conditions exist which are believed by the Emergency Director to fall under the emergency classification level description for a Site Area Emergency.
Basis Reference(s):
: 1. NEI 99-01, Rev 6 HS7 Month XXXX BY 3-154 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HA7 Initiating Condition:
Other conditions exist which in the judgment of the Emergency Director warrant declaration of an ALERT.Operating Mode Applicability:
1,2,3, 4,5,6, D Emergency Action Level (EAL): Other conditions exist which, in the judgment of the Emergency Director, indicate that events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of HOSTILE ACTION. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.Basis: HOSTILE ACTION: An act toward a NPP or its personnel that includes the use of violent force to destroy equipment, take HOSTAGES, and/or intimidate the licensee to achieve an end. This includes attack by air, land, or water using guns, explosives, PROJECTILEs, vehicles, or other devices used to deliver destructive force. Other acts that satisfy the overall intent may be included.
HOSTILE ACTION should not be construed to include acts of civil disobedience or felonious acts that are not part of a concerted attack on the NPP. Non-terrorism-based EALs should be used to address such activities (i.e., this may include violent acts between individuals in the owner controlled area).HOSTAGE: A person(s) held as leverage against the station to ensure that demands will be met by the station PROJECTILE:
An object directed toward a NPP that could cause concern for its continued operability, reliability, or personnel safety.This IC addresses unanticipated conditions not addressed explicitly elsewhere but that warrant declaration of an emergency because conditions exist which are believed by the Emergency Director to fall under the emergency classification level description for an Alert.Basis Reference(s):
: 1. NEI 99-01, Rev 6 HA7 Month XXXX BY 3-155 EP-AA-1002 (Revision XX)
Byron Annex Exelon Nuclear Byron Annex Exelon Nucl.ear RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY HU7 Initiating Condition:
Other conditions exist which in the judgment of the Emergency Director warrant declaration of an UNUSUAL EVENT.Operating Mode Applicability:
1, 2,3, 4,5,6, D Emergency Action Level (EAL): Other conditions exist which in the judgment of the Emergency Director indicate that events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated.
No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.Basis: This IC addresses unanticipated conditions not addressed explicitly elsewhere but that warrant declaration of an emergency because conditions exist which are believed by the Emergency Director to fall under the emergency classification level description for an UNUSUAL EVENT.Basis Reference(s):
: 1. NEI 99-01, Rev 6 HU7 Month XXXX BY 3-156 EP-AA-1002 (Revision XX)
Rvrnn Annoy lFvalnn Milimlar Rvrnn AnnexFAn Ni~Au RECOGNITION CATEGORY ISFSI MALFUNCTIONS E-HU1 Initiating Condition Damage to a loaded cask CONFINEMENT BOUNDARY.Operating Mode Applicability:
1,2, 3, 4, 5, 6, D Emergency Action Level (EAL): Damage to a loaded cask CONFINEMENT BOUNDARY as indicated by an on-contact radiation reading:* > 60mr/hr (gamma + neutron) on the top of the spent fuel cask OR* > 600mr/hr (gamma + neutron) on the side of the spent fuel cask, excluding inlet and outlet ducts Basis: CONFINEMENT BOUNDARY:
The irradiated fuel dry storage cask barrier(s) between areas containing radioactive substances and the environment.
INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) : A complex that is designed and constructed for the interim storage of spent nuclear fuel and other radioactive materials associated with spent fuel storage.This IC addresses an event that results in damage to the CONFINEMENT BOUNDARY of a storage cask containing spent fuel. It applies to irradiated fuel that is licensed for dry storage beginning at the point that the loaded storage cask is sealed. The word cask, as used in this EAL, refers to the storage container in use at the site for dry storage of irradiated fuel. The issues of concern are the creation of a potential or actual release path to the environment, degradation of any fuel assemblies due to environmental factors, and configuration changes which could cause challenges in removing the cask or fuel from storage.The existence of "damage" is determined by radiological survey. The technical specification multiple of "2 times", which is also used in Recognition Category R IC RU1, is used here to distinguish between non-emergency and emergency conditions.
The emphasis for this classification is the degradation in the level of safety of the spent fuel cask and not the magnitude of the associated dose or dose rate. It is recognized that in the case of extreme damage to a loaded cask, the fact that the "on-contact" dose rate limit is exceeded may be determined based on measurement of a dose rate at some distance from the cask.Security-related events for ISFSls are covered under ICs HU1 and HAl.Basis Reference(s):
: 1. NEI 99-01, Rev 6 E-HU1 2. Certificate of Compliance No. 1014 Appendix A Section 5.7 Month XXXX BY 3-157 EP-AA-1002 (Revision XX)}}