Text

Enclosure 2E- Procedure Matrix
	ML18037A795
Person / Time
Site:	FitzPatrick
Issue date:	01/31/2018
From:	; Exelon Generation Co
To:	; Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
Shared Package
ML18037A782	List: JAFP-18-0014, Attachment 1: License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors; JAFP-18-0014, Enclosure 2A- EAL Comparison Matrix Document; JAFP-18-0014, Enclosure 2C- EAL Basis Document; JAFP-18-0014, Enclosure 2D- EAL Front Matter; JAFP-18-0014, James A. FitzPatrick Nuclear Power Plant - License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors; ML18037A786; ML18037A787; ML18037A788; ML18037A790; ML18037A792; ML18037A795;
References
	JAFP-018-0014
	Download: ML18037A795 (27)
	v • d • e

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX JAF 2-1 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Abnormal Rad Levels / Radiological Effluents Radiological Effluents RG1 1 2 3 4 5 D Release of gaseous radioactivity resulting in offsite dose greater than 1,000 mRem TEDE or 5,000 mRem thyroid CDE.

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monitor is known to have stopped due to actions to isolate the release path, then the effluent monitor reading is no longer valid for classification purposes.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(Table R1) should be used for emergency classification assessments until the results from a dose assessment using actual meteorology are available.

1.

Readings on ANY Table R1 Effluent Monitor > Table R1 value for > 15 minutes.

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

3.

Field survey results at or beyond the site boundary indicate EITHER:

a.

Gamma (closed window) dose rates

> 1000 mR/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.

RS1 1 2 3 4 5 D Release of gaseous radioactivity resulting in offsite dose greater than 100 mRem TEDE or 500 mRem thyroid CDE.

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 (Table R1) should be used for emergency classification assessments until the results from a dose assessment using actual meteorology are available.

1.

Readings on ANY Table R1 Effluent Monitor > Table R1 value for > 15 minutes.

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.

RA1 1 2 3 4 5 D Release of gaseous or liquid radioactivity resulting in offsite dose greater than 10 mrem TEDE or 50 mrem thyroid CDE.

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 (Table R1) should be used for emergency classification assessments until the results from a dose assessment using actual meteorology are available.

1. Readings on ANY Table R1 Effluent Monitor > Table R1 value for > 15 minutes.

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.

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 > 60 minutes.

OR

b. Analyses of field survey samples indicate

> 50 mRem CDE Thyroid for 60 minutes of inhalation.

RU1 1 2 3 4 5 D Release of gaseous or liquid radioactivity greater than 2 times the ODCM limits for 60 minutes or longer.

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 the Liquid Radwaste Effluent Monitor (17RM-350) > 2 times hi-hi trip for 60 minutes.

OR

2. Readings on ANY Table R1 Effluent Monitor > Table R1 value for > 60 minutes.

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.

Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX JAF 2-2 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

Table R1 Effluent Monitor Thresholds Effluent Monitor General Emergency Site Area Emergency Alert Unusual Event Stack 7880 mR/hr 788 mR/hr 78.8 mR/hr 0.451 mR/hr (High Range Monitor)

Rx Bldg Exh N/A N/A N/A 9.50E+05 cpm (Low Range Monitor)

Turb Bldg Exh 2.44 mR/hr 0.244 mR/hr N/A 6.72E+05 cpm (Low Range Monitor)

Radw Bldg Exh 4.74 mR/hr 0.474 mR/hr N/A N/A Refuel Floor Exh N/A N/A N/A 9.28E+05 cpm (Low Range Monitor)

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX JAF 2-3 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Abnormal Rad Levels / Radiological Effluents Radiological Effluents RG2 1 2 3 4 5 D Spent fuel pool level cannot be restored to at least 1.00 foot for 60 minutes or longer.

Emergency Action Levels (EAL):

Note: The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.

Spent fuel pool level cannot be restored to at least 1.00 foot as indicated on19LI-60A or 19LI-60B for > 60 minutes.

Table R3 Areas Requiring Continuous Occupancy Main Control Room - (by survey)

Central Alarm Station - (by survey)

Secondary Alarm Station - (by survey)

RS2 1 2 3 4 5 D Spent fuel pool level at 1.00 foot.

Emergency Action Level (EAL):

Lowering of spent fuel pool level to 1.00 foot as indicated on 19LI-60A or 19LI-60B.

Table R4 Areas with Entry Related Mode Applicability Area Entry Related Mode Applicability Reactor Building East Crescent Reactor Building West Crescent Reactor Building 272 Elevation Reactor Building 300 Elevation Relay Room North Cable Room Mode 3, 4, and 5 Table R2 Refuel Floor Radiation Monitors

18RIA-051-12 Spent Fuel Pool (EPIC A-1229)

18RIA-051-14 New Fuel Vault (EPIC A-1231)

18RIA-052-30 Refuel Floor West (EPIC A-1247)

17RIS-456A or B Refuel Floor Exhaust RA2 1 2 3 4 5 D Significant lowering of water level above, or damage to, irradiated fuel.

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 R2 Radiation Monitor Alarm.

OR

3. Lowering of spent fuel pool level to 11.00 feet as indicated on 19LI-60A or 19LI-60B.

RU2 1 2 3 4 5 D UNPLANNED loss of water level above irradiated fuel.

Emergency Action Level (EAL):

1. a. UNPLANNED water level drop in the REFUELING PATHWAY as indicated by ANY of the following:

Inability to restore and maintain Spent Fuel Pool water level > low water level alarm.

OR Indication or report of a drop in water level in the REFUELING PATHWAY.

AND

b. UNPLANNED Area Radiation Monitor reading rise on ANY Table R2 radiation monitor.

RA3 1 2 3 4 5 D Radiation levels that impede access to equipment necessary for normal plant operations, cooldown or shutdown.

Emergency Action Level (EAL):

Note: If the equipment in the room or area listed in Table R4 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 areas in Table R3.

OR

2. UNPLANNED event results in radiation levels that prohibit or significantly impede access to ANY of the areas in Table R4.

RU3 1 2 3 Reactor coolant activity greater than Technical Specification allowable limits.

Emergency Action Level (EAL):

1 Offgas radiation > hi-hi alarm OR

2. Specific coolant activity > 2.0 µCi/gm I-131 dose equivalent.

Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX JAF 2-4 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT FG1 Loss of ANY two barriers AND Loss or Potential Loss of third barrier. 1 2 3 FS1 Loss or Potential Loss of ANY two barriers. 1 2 3 FA1 ANY Loss or ANY Potential Loss of either Fuel Clad or RCS. 1 2 3 Sub-Category FC - Fuel Clad RC - Reactor Coolant System CT - Containment Loss Potential Loss Loss Potential Loss Loss Potential Loss

1. RCS Activity Coolant activity > 300 uCi/gm I-131 dose equivalent.

None None None None None

2. RPV Water Level

1. SAOG entry required

2. RPV water level cannot be restored and maintained > 0 inches (TAF).

OR

3. RPV water level cannot be determined.

1. RPV water level cannot be restored and maintained > 0 inches (TAF).

OR

2. RPV water level cannot be determined.

None None SAOG entry required

3. Primary Containment Pressure /

Conditions None None

1. a. Primary Containment pressure

> 2.7 psig.

AND

b. Primary Containment pressure rise is due to RCS leakage.

None

1. UNPLANNED rapid drop in Primary Containment pressure following Primary Containment pressure rise.

OR

2. Primary Containment pressure response not consistent with LOCA conditions.

3. Primary Containment pressure > 56 psig and rising.

OR

4. a. Primary Containment hydrogen concentration > 6%.

AND

b. Primary Containment oxygen concentration

> 5%.

OR

5. Heat Capacity Temperature Limit (HCTL)

(EOP-11) exceeded.

4. RCS Leak Rate None None

1. UNISOLABLE Main Steam Line (MSL),

HPCI, RWCU, RCIC, or Feedwater line break.

OR

2. Emergency RPV Depressurization is required.

3. UNISOLABLE primary system leakage that results in EITHER of the following:

a. Secondary Containment area temperature

> EOP-5 Maximum Normal Operating Limit.

OR

b. Secondary Containment area radiation

> EOP-5 Maximum Normal Operating Limit.

None None

5. Primary Containment Radiation Drywell radiation monitor reading

> 1.8E+03 R/hr (1800 R/hr).

None Drywell radiation monitor reading

> 63 R/hr.

None None Drywell radiation monitor reading

> 1.8E+04 R/hr (18,000 R/hr).

6. Primary Containment Isolation Failure None None None None

1. UNISOLABLE direct downstream pathway to the environment exists after Primary Containment isolation signal.

OR

2. Intentional Primary Containment venting or purging per EOPs or SAOGs due to accident conditions.

OR

3. UNISOLABLE primary system leakage that results in EITHER of the following:

a. Secondary Containment area temperature

> EOP-5 Maximum Safe Operating Limit.

OR

b. Secondary Containment area radiation

> EOP-5 Maximum Safe Operating Limit.

None

7. Emergency Director Judgment

1. Any Condition in the opinion of the Emergency Director that indicates Loss of the Fuel Clad Barrier.

2. Any Condition in the opinion of the Emergency Director that indicates Potential Loss of the Fuel Clad Barrier.

1. Any Condition in the opinion of the Emergency Director that indicates Loss of the RCS Barrier.

2. Any Condition in the opinion of the Emergency Director that indicates Potential Loss of the RCS Barrier.

1. Any Condition in the opinion of the Emergency Director that indicates Loss of the Containment Barrier.

2. Any Condition in the opinion of the Emergency Director that indicates Potential Loss of the Containment Barrier.

Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX JAF 2-5 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT System Malfunction Loss of AC Power MG1 1 2 3 Prolonged loss of all offsite and all onsite AC power to emergency buses.

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 and onsite AC power to 4160 V emergency buses 10500 and 10600.

AND

2. EITHER of the following:

a. Restoration of at least one 4160 V emergency bus 10500 or 10600 in < 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months is not likely.

OR

b. RPV water level cannot be restored and maintained

> -19 inches (MSCRWL).

MS1 1 2 3 Loss of all offsite and onsite AC power to emergency buses for 15 minutes or longer.

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 and onsite AC power to 4160 V emergency buses 10500 and 10600.

AND

2. Failure to restore power to at least one 4160 V emergency bus 10500 or 10600 in < 15 minutes from the time of loss of both offsite and onsite AC power.

MA1 1 2 3 Loss of all but one AC power source to emergency buses for 15 minutes or longer.

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 4160 V emergency buses 10500 and 10600 reduced to only one of the following power sources for > 15 minutes.

Reserve Station Transformer T-2 Reserve Station Transformer T-3 Station Service Transformer T-4 (While backfeeding from Main Transformer)

EDG A EDG B EDG C EDG D Main Generator via T-4 AND

2. ANY additional single power source failure will result in a loss of ALL AC power to SAFETY SYSTEMS.

MU1 1 2 3 Loss of all offsite AC power capability to emergency buses for 15 minutes or longer.

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 4160 V emergency buses 10500 and 10600 for > 15 minutes.

Reserve Station Transformer T-2 Reserve Station Transformer T-3 Station Service Transformer T-4 (While backfeeding from Main Transformer)

Loss of DC Power MG2 1 2 3 Loss of all AC and Vital DC power sources for 15 minutes or longer.

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 and onsite AC power to 4160 V emergency buses 10500 and 10600.

AND

2. Voltage is < 105 VDC on Vital DC buses 71BCB-2A and 71BCB-2B.

AND

3. Conditions in EALs #1 and #2 have existed for > 15 minutes.

MS2 1 2 3 Loss of all Vital DC power for 15 minutes or longer.

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 < 105 VDC on Vital DC buses 71BCB-2A and 71BCB-2B for > 15 minutes.

Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX JAF 2-6 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT System Malfunction RPS Failure MS3 1 2 Inability to shutdown the reactor causing a challenge to RPV water level or RCS heat removal.

Emergency Action Level (EAL):

1. Automatic scram did not shutdown the reactor as indicated by Reactor Power > 2.5%.

AND

2. ALL manual / ARI actions to shutdown the reactor have been unsuccessful as indicated by Reactor Power

> 2.5%.

AND

3. EITHER of the following conditions exist:

RPV water level cannot be restored and maintained

> -19 inches (MSCRWL).

OR Heat Capacity Temperature Limit (HCTL)

(EOP-11) exceeded.

MA3 1 2 Automatic or manual scram fails to shutdown the reactor, and subsequent manual actions taken at the Reactor Control Console are not successful in shutting down the reactor.

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. This action does not include manually driving in control rods or implementation of boron injection strategies.

1. Automatic or manual scram did not shutdown the reactor as indicated by Reactor Power > 2.5%.

AND

2. Manual / ARI actions taken at the Reactor Control Console are not successful in shutting down the reactor as indicated by Reactor Power > 2.5%.

MU3 1 2 Automatic or manual scram fails to shutdown the reactor.

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. This action does not include manually driving in control rods or implementation of boron injection strategies.

1. a. Automatic scram did not shutdown the reactor as indicated by Reactor Power > 2.5%.

AND

b. Subsequent manual / ARI action taken at the Reactor Control Console is successful in shutting down the reactor as indicated by Reactor Power < 2.5%.

OR

2. a. Manual scram did not shutdown the reactor as indicated by Reactor Power > 2.5%.

AND

b. EITHER of the following:

1. Subsequent manual / ARI action taken at the Reactor Control Console is successful in shutting down the reactor as indicated by Reactor Power < 2.5%.

OR

2. Subsequent automatic scram / ARI is successful in shutting down the reactor as indicated by Reactor Power < 2.5%.

Control Room Indications Table M1 Control Room Parameters Reactor Power RPV Water Level RPV Pressure Primary Containment Pressure Torus Level Torus Temperature Table M2 Significant Transients Auto/Manual runback > 25% thermal reactor power Electric load rejection > 25% full electric load Reactor Scram ECCS actuation Thermal Power oscillations > 10% (peak to peak)

MA4 1 2 3 UNPLANNED loss of Control Room indications for 15 minutes or longer with a significant transient in progress.

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 parameter from within the Control Room for > 15 minutes.

AND

2. ANY Table M2 transient in progress.

MU4 1 2 3 UNPLANNED loss of Control Room indications for 15 minutes or longer.

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.

UNPLANNED event results in the inability to monitor ANY Table M1 parameter from within the Control Room for > 15 minutes.

Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX JAF 2-7 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT System Malfunction Hazard affects Safety System MA5 1 2 3 Hazardous event affecting a SAFETY SYSTEM required for the current operating mode.

Emergency Action Level (EAL):

Note:

If the only affected SAFETY SYSTEM train was already inoperable or out of service before the hazardous event occurred, then this emergency classification is not warranted.

For SAFETY SYSTEMS with multiple trains if the hazardous event only resulted in VISIBLE DAMAGE or degraded performance to the one train, then this emergency classification is not warranted.

If it is determined that the conditions of MA5 are not met then assess the event via HU3, HU4, or HU6.

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.

a. Event damage has caused indications of degraded performance or VISIBLE DAMAGE to one train of a SAFETY SYSTEM required by Technical Specifications for the current operating mode.

AND

b. ANY of the following for SAFETY SYSTEMS with multiple trains:

Event damage has caused indications of degraded performance to a second train of the SAFETY SYSTEM required by Technical Specifications for the current operating mode.

OR

Event damage has resulted in VISIBLE DAMAGE to a second train of the SAFETY SYSTEM required by Technical Specifications for the current operating mode.

OR

An additional train of the SAFETY SYSTEM is inoperable or out of service.

Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX JAF 2-8 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT System Malfunction MU6 1 2 3 RCS leakage for 15 minutes or longer.

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 in the Drywell > 10 gpm for > 15 minutes.

OR

2. RCS identified leakage in the Drywell > 25 gpm for> 15 minutes.

OR

3. Leakage from the RCS to a location outside the Drywell > 25 gpm for > 15 minutes.

Communications Table M3 Communications Capability System Onsite Offsite NRC Page/Party System (Gaitronics)

X Control Room/Portable Radio X

Plant Telephones (all VOIP, switched, non-switched)

X X

X Out-of-Plant Cellular Phones X

X X

Plant Satellite Phones X

X RECS X

Dedicated Phone Lines (ENS)

X X

HPN and FTS 2001 X

X MU7 1 2 3 Loss of all onsite or offsite communication capabilities.

Emergency Action Level (EAL):

1. Loss of ALL Table M3 onsite communication capabilities affecting the ability to perform routine operations.

OR

2. Loss of ALL Table M3 offsite communication capabilities affecting the ability to perform offsite notifications.

OR

3. Loss of ALL Table M3 NRC communication capabilities affecting the ability to perform NRC notifications.

Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX JAF 2-9 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Hazards and Other conditions Affecting Plant Safety Hostile Action HS1 1 2 3 4 5 D HOSTILE ACTION within the PROTECTED AREA.

Emergency Action Level (EAL):

A notification from the Security Force that a HOSTILE ACTION is occurring or has occurred within the PROTECTED AREA.

HA1 1 2 3 4 5 D HOSTILE ACTION within the OWNER CONTROLLED AREA or airborne attack threat within 30 minutes.

Emergency Action Level (EAL):

1. A validated notification from NRC from an aircraft attack threat < 30 minutes of the site.

OR

2. Notification by the Security Force that a HOSTILE ACTION is occurring or has occurred within the OWNER CONTROLLED AREA.

HU1 1 2 3 4 5 D Confirmed SECURITY CONDITION or threat.

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.

Transfer of Plant Control Table H1 Safety Functions

Reactivity Control (ability to shutdown the reactor and keep it shutdown)

RPV Water Level (ability to cool the core)

RCS Heat Removal (ability to maintain a heat sink)

HS2 1 2 3 4 5 D Inability to control a key safety function from outside the Control Room.

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 AOP-43, Plant Shutdown from Outside the Control Room.

AND

2. Control of ANY Table H1 key safety function is not reestablished in < 30 minutes.

HA2 1 2 3 4 5 D Control Room evacuation resulting in transfer of plant control to alternate locations.

Emergency Action Level (EAL):

A Control Room evacuation has resulted in plant control being transferred from the Control Room to alternate locations per AOP-43, Plant Shutdown from Outside the Control Room.

Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX JAF 2-10 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Hazards and Other conditions Affecting Plant Safety Fire Table H2 Areas Reactor Building (when inerted the Drywell is exempt)

Control Room / Relay Room / Cable Run Rooms / Cable Spreading Room Electric Bays Control Room AC Equipment Room Control Room Chiller Room Emergency Diesel Generator Building Battery Rooms / Battery Room Corridor RHRSW / ESW Pump Rooms Cable Tunnels Remote Safe Shutdown Panels 25ASP-4 and 25ASP-5 (for MSIV /

ADS)

HU3 1 2 3 4 5 D FIRE potentially degrading the level of safety of the plant.

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.

Escalation of the emergency classification level would be via IC CA2 or MA5.

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.

Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX JAF 2-11 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Hazards and Other conditions Affecting Plant Safety Earthquake HU4 1 2 3 4 5 D Seismic event greater than OBE levels.

Emergency Action Level (EAL):

Note:

For emergency classification if EAL # 2.b is not able to be confirmed, then the occurrence of a seismic event is confirmed in manner deemed appropriate by the Emergency Director in < 15 minutes of the event.

Escalation of the emergency classification level would be via IC CA2 or MA5.

1. Seismic event > Operating Basis Earthquake (OBE) as determined by seismic monitoring system in accordance with AOP-14 Earthquake.

OR

2. When Seismic Monitoring Equipment is not available:

a. Control Room personnel feel an actual or potential seismic event.

AND

b. ANY one of the following confirmed in < 15 minutes of the event:

The earthquake resulted in Modified Mercalli Intensity (MMI) > VI and occurred < 3.5 miles of the plant.

The earthquake was magnitude > 6.0 The earthquake was magnitude > 5.0 and occurred < 125 miles of the plant.

Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX JAF 2-12 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Hazards and Other conditions Affecting Plant Safety Toxic Gas Table H3 Areas with Entry Related Mode Applicability Area Entry Related Mode Applicability Reactor Building East Crescent Reactor Building West Crescent Reactor Building 272 Elevation Reactor Building 300 Elevation Relay Room North Cable Room Mode 3, 4, and 5 HA5 3 4 5 Gaseous release impeding access to equipment necessary for normal plant operations, cooldown or shutdown.

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.

AND

2. Entry into the room or area is prohibited or impeded.

Hazardous Event HU6 1 2 3 4 5 D Hazardous Event Emergency Action Level (EAL):

Note:

EAL #4 does not apply to routine traffic impediments such as fog, snow, ice, or vehicle breakdowns or accidents.

Escalation of the emergency classification level would be via IC CA2 or MA5.

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.

OR

5. Intake Water Level > 255 feet.

OR

6. ESW intake bay water level < 237 feet.

Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX JAF 2-13 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Hazards and Other conditions Affecting Plant Safety Emergency Director Judgment HG7 1 2 3 4 5 D Other conditions exist which in the judgment of the Emergency Director warrant declaration of a GENERAL EMERGENCY.

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.

HS7 1 2 3 4 5 D Other conditions exist which in the judgment of the Emergency Director warrant declaration of a SITE AREA EMERGENCY.

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.

HA7 1 2 3 4 5 D Other conditions exist which in the judgment of the Emergency Director warrant declaration of an ALERT.

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.

HU7 1 2 3 4 5 D Other conditions exist which in the judgment of the Emergency Director warrant declaration of an UNUSUAL EVENT.

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.

Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX JAF 2-14 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT ISFSI Malfunction ISFSI E-HU1 1 2 3 4 5 D Damage to a loaded cask CONFINEMENT BOUNDARY.

Emergency Action Level (EAL):

Damage to a loaded cask CONFINEMENT BOUNDARY as indicated by a radiation reading > Table E-1 values:

Table E-1 Radiation Reading Overpack Serial Number Overpack Average Surface Dose Rates mrem/hr (gamma+neutron)

Overpack Serial Number HI-STORM 100S (XXX)

Overpack Average Surface Dose Rates mrem/hr (gamma+neutron)

HI-STORM 100S S/N - 15, 16, 17 80 on the side 20 on the top 32 at the inlet and outlet vent ducts S/N -

0186, 0187, 0188 220 on the side 40 on the top S/N -

0307, 0308,

0309, 0310,

0311, 0312,

0679, 0680,

0681, 0682,

0683, 0690,

0691, 0692,

0693, 0694, 0695 600 on the side 60 on the top HI-STORM 100S (232)

S/N -

0169, 0170, 0171 100 on the side 20 on the top 90 at the inlet and outlet vent ducts Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled

James A. FitzPatrick Nuclear Power Plant Annex COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear Month 20XX COLD SHUTDOWN/REFUELING MATRIX JAF 2-15 COLD SHUTDOWN/REFUELING MATRIX EP-AA-1014 Addendum 3 (Rev.X)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Abnormal Rad Levels / Radiological Effluents Radiological Effluents RG1 1 2 3 4 5 D Release of gaseous radioactivity resulting in offsite dose greater than 1,000 mRem TEDE or 5,000 mRem thyroid CDE.

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(Table R1) should be used for emergency classification assessments until the results from a dose assessment using actual meteorology are available.

1.

Readings on ANY Table R1 Effluent Monitor > Table R1 value for > 15 minutes.

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

3.

Field survey results at or beyond the site boundary indicate EITHER:

a.

Gamma (closed window) dose rates

> 1000 mR/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.

RS1 1 2 3 4 5 D Release of gaseous radioactivity resulting in offsite dose greater than 100 mRem TEDE or 500 mRem thyroid CDE.

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(Table R1) should be used for emergency classification assessments until the results from a dose assessment using actual meteorology are available.

1.

Readings on ANY Table R1 Effluent Monitor > Table R1 value for > 15 minutes.

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.

RA1 1 2 3 4 5 D Release of gaseous or liquid radioactivity resulting in offsite dose greater than 10 mrem TEDE or 50 mrem thyroid CDE.

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(Table R1) should be used for emergency classification assessments until the results from a dose assessment using actual meteorology are available.

1. Readings on ANY Table R1 Effluent Monitor > Table R1 value for

> 15 minutes.

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 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 > 60 minutes.

OR

b. Analyses of field survey samples indicate

> 50 mRem CDE Thyroid for 60 minutes of inhalation.

RU1 1 2 3 4 5 D Release of gaseous or liquid radioactivity greater than 2 times the ODCM limits for 60 minutes or longer.

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 the Liquid Radwaste Effluent Monitor (LWS-RE206) > 2 times DRMS High (red) established by a current radioactive release discharge permit for 60 minutes.

OR

2. Readings on ANY Table R1 Effluent Monitor > Table R1 value for > 60 minutes.

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.

Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled

James A. FitzPatrick Nuclear Power Plant Annex COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear Month 20XX COLD SHUTDOWN/REFUELING MATRIX JAF 2-16 COLD SHUTDOWN/REFUELING MATRIX EP-AA-1014 Addendum 3 (Rev.X)

Table R1 Effluent Monitor Thresholds Effluent Monitor General Emergency Site Area Emergency Alert Unusual Event Stack 7880 mR/hr 788 mR/hr 78.8 mR/hr 0.451 mR/hr (High Range Monitor)

Rx Bldg Exh N/A N/A N/A 9.50E+05 cpm (Low Range Monitor)

Turb Bldg Exh 2.44 mR/hr 0.244 mR/hr N/A 6.72E+05 cpm (Low Range Monitor)

Radw Bldg Exh 4.74 mR/hr 0.474 mR/hr N/A N/A Refuel Floor Exh N/A N/A N/A 9.28E+05 cpm (Low Range Monitor)

James A. FitzPatrick Nuclear Power Plant Annex COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear Month 20XX COLD SHUTDOWN/REFUELING MATRIX JAF 2-17 COLD SHUTDOWN/REFUELING MATRIX EP-AA-1014 Addendum 3 (Rev.X)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Abnormal Rad Levels / Radiological Effluents Radiological Effluents RG2 1 2 3 4 5 D Spent fuel pool level cannot be restored to at least 1.00 foot for 60 minutes or longer.

Emergency Action Levels (EAL):

Note: The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.

Spent fuel pool level cannot be restored to at least 1.00 foot as indicated on 19LI-60A or 19LI-60B for > 60 minutes.

Table R3 Areas Requiring Continuous Occupancy Main Control Room - (by survey)

Central Alarm Station - (by survey)

Secondary Alarm Station - (by survey)

RS2 1 2 3 4 5 D Spent fuel pool level at 1.00 foot.

Emergency Action Level (EAL):

Lowering of spent fuel pool level to 1.00 foot as indicated on 19LI-60-A or 19LI-60B.

Table R4 Areas with Entry Related Mode Applicability Area Entry Related Mode Applicability Reactor Building East Crescent Reactor Building West Crescent Reactor Building 272 Elevation Reactor Building 300 Elevation Relay Room North Cable Room Mode 3, 4, and 5 Table R2 Refuel Floor Radiation Monitors

18RIA-051-12 Spent Fuel Pool (EPIC A-1229)

18RIA-051-14 New Fuel Vault (EPIC A-1231)

18RIA-052-30 Refuel Floor West (EPIC A-1247)

17RIS-456A or B Refuel Floor Exhaust RA2 1 2 3 4 5 D Significant lowering of water level above, or damage to, irradiated fuel.

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 R2 Radiation Monitor Alarm.

OR

3. Lowering of spent fuel pool level to 11.00 feet as indicated on 19LI-60A or 19LI-60B.

RU2 1 2 3 4 5 D UNPLANNED loss of water level above irradiated fuel.

Emergency Action Level (EAL):

1. a. UNPLANNED water level drop in the REFUELING PATHWAY as indicated by ANY of the following:

Inability to restore and maintain Spent Fuel Pool water level > low water level alarm.

OR Indication or report of a drop in water level in the REFUELING PATHWAY.

AND

b. UNPLANNED Area Radiation Monitor reading rise on ANY Table R2 radiation monitor.

RA3 1 2 3 4 5 D Radiation levels that impede access to equipment necessary for normal plant operations, cooldown or shutdown.

Emergency Action Level (EAL):

Note: If the equipment in the room or area listed in Table R4 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 areas in Table R3.

OR

2. UNPLANNED event results in radiation levels that prohibit or significantly impede access to ANY of the areas in Table R4.

Modes:

1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled

James A. FitzPatrick Nuclear Power Plant Annex COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear Month 20XX COLD SHUTDOWN/REFUELING MATRIX JAF 2-18 COLD SHUTDOWN/REFUELING MATRIX EP-AA-1014 Addendum 3 (Rev.X)

Modes:

1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Cold Shutdown / Refueling System Malfunctions Loss of AC Power CA1 4 5 D Loss of all offsite and onsite AC power to emergency buses for 15 minutes or longer.

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 and onsite AC power to 4160 V emergency buses 10500 and 10600.

AND

2. Failure to restore power to at least one 4160 V emergency bus 10500 or 10600 in < 15 minutes from the time of loss of both offsite and onsite AC power.

CU1 4 5 D Loss of all but one AC power source to emergency buses for 15 minutes or longer.

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 4160 V emergency buses 10500 and 10600 reduced to only one of the following power sources for > 15 minutes.

Reserve Station Transformer T-2 Reserve Station Transformer T-3 Station Service Transformer T-4 (While backfeeding from Main Transformer)

EDG A EDG B EDG C EDG D AND

2. ANY additional single power source failure will result in a loss of ALL AC power to SAFETY SYSTEMS.

James A. FitzPatrick Nuclear Power Plant Annex COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear Month 20XX COLD SHUTDOWN/REFUELING MATRIX JAF 2-19 COLD SHUTDOWN/REFUELING MATRIX EP-AA-1014 Addendum 3 (Rev.X)

Modes:

1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Cold Shutdown / Refueling System Malfunctions Safety System CA2 4 5 Hazardous event affecting SAFETY SYSTEM required for the current operating mode.

Emergency Action Level (EAL):

Note:

If the only affected SAFETY SYSTEM train was already inoperable or out of service before the hazardous event occurred, then this emergency classification is not warranted.

For SAFETY SYSTEMS with multiple trains if the hazardous event only resulted in VISIBLE DAMAGE or degraded performance to the one train, then this emergency classification is not warranted.

If it is determined that the conditions of CA2 are not met then assess the event via HU3, HU4, or HU6.

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. a. Event damage has caused indications of degraded performance or VISIBLE DAMAGE to one train of a SAFETY SYSTEM required by Technical Specifications for the current operating mode.

AND

b. ANY of the following for SAFETY SYSTEMS with multiple trains:

Event damage has caused indications of degraded performance to a second train of the SAFETY SYSTEM required by Technical Specifications for the current operating mode.

OR

Event damage has resulted in VISIBLE DAMAGE to a second train of the SAFETY SYSTEM required by Technical Specifications for the current operating mode.

OR

An additional train of the SAFETY SYSTEM is inoperable or out of service.

James A. FitzPatrick Nuclear Power Plant Annex COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear Month 20XX COLD SHUTDOWN/REFUELING MATRIX JAF 2-20 COLD SHUTDOWN/REFUELING MATRIX EP-AA-1014 Addendum 3 (Rev.X)

Modes:

1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Cold Shutdown / Refueling System Malfunctions DC Power CU3 4 5 Loss of Vital DC power for 15 minutes or longer.

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 < 105 VDC on required Vital DC buses 71BCB-2A and 71BCB-2B for > 15 minutes.

Communications Table C1 Communication Capabilities System Onsite Offsite NRC Page/Party System (Gaitronics)

X Control Room/Portable Radio X

Plant Telephones (all VOIP, switched, non-switched)

X X

X Out-of-Plant Cellular Phones X

X X

Plant Satellite Phones X

X RECS X

Dedicated Phone Lines (ENS)

X X

HPN and FTS 2001 X

X CU4 4 5 D Loss of all onsite or offsite communication capabilities.

Emergency Action Level (EAL):

1. Loss of ALL Table C1 onsite communication capabilities affecting the ability to perform routine operations.

OR

2. Loss of ALL Table C1 offsite communication capabilities affecting the ability to perform offsite notifications.

OR

3. Loss of ALL Table C1 NRC communication capabilities affecting the ability to perform NRC notifications.

Heat Sink Table C2 RCS Heat-up Duration Thresholds RCS Status Containment Closure Status Heat-up Duration Intact Not Applicable 60 minutes*

Not Intact Established 20 minutes*

Not Established 0 minutes

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.

CA5 4 5 Inability to maintain plant in cold shutdown.

Emergency Action Levels (EAL):

Note:

The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.

A momentary UNPLANNED excursion above the Technical Specification cold shutdown temperature limit when heat removal function is available does not warrant classification.

1. UNPLANNED rise in RCS temperature > 212 ºF for > Table C2 duration.

OR

2. UNPLANNED RPV pressure rise > 10 psig as a result of temperature rise CU5 4 5 UNPLANNED rise in RCS temperature.

Emergency Action Levels (EAL):

Note:

The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.

A momentary UNPLANNED excursion above the Technical Specification cold shutdown temperature limit when heat removal function is available does not warrant classification.

1. UNPLANNED rise in RCS temperature > 212 ºF.

OR

2. Loss of the following for > 15 minutes.

ALL RCS temperature indications AND ALL RPV water level indications

James A. FitzPatrick Nuclear Power Plant Annex COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear Month 20XX COLD SHUTDOWN/REFUELING MATRIX JAF 2-21 COLD SHUTDOWN/REFUELING MATRIX EP-AA-1014 Addendum 3 (Rev.X)

Modes:

1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Cold Shutdown / Refueling System Malfunctions RCS Leakage / Inventory CG6 4 5 Loss of RPV inventory affecting fuel clad integrity with containment challenged.

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. RPV water level < 0 inches (TAF) for

> 30 minutes.

AND

b. Any Table C4 Containment Challenge Indication.

OR

2. a. RPV water level cannot be monitored for > 30 minutes.

AND

b. Core uncovery is indicated by ANY of the following:

Table C3 indication of a sufficient magnitude to indicate core uncovery.

OR

18RIA-052-30 Refuel Floor West (EPIC A-1247) Rad monitor > 3 R/hr.

AND

c. ANY Table C4 Containment Challenge Indication.

CS6 4 5 Loss of RPV inventory affecting core decay heat removal capabilities.

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 not established, RPV water level < 120.5 inches.

OR

2. With CONTAINMENT CLOSURE established, RPV water level < 0 inches (TAF).

OR

3. a. RPV water level cannot be monitored for

> 30 minutes.

AND

b. Core uncovery is indicated by ANY of the following:

Table C3 indication of a sufficient magnitude to indicate core uncovery.

OR 18RIA-052-30 Refuel Floor West (EPIC A-1247) Rad monitor > 3 R/hr.

CA6 4 5 Loss of RPV inventory.

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 RPV inventory as indicated by level < 126.5 inches.

OR

2.

a. RPV water level cannot be monitored for > 15 minutes.

AND

b. Loss of RPV inventory per Table C3 indications.

CU6 4 5 UNPLANNED loss of RP inventory for 15 minutes or longer.

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 RPV level to above the procedurally established lower limit for > 15 minutes.

OR

2. a. RPV water level cannot be monitored.

AND

b. Loss of RPV inventory per Table C3 indications.

Table C3 Indications of RCS Leakage UNPLANNED Drywell equipment drain sump level rise*

UNPLANNED Drywell floor drain sump level rise*

UNPLANNED Reactor Building equipment sump level rise*

UNPLANNED Reactor Building floor drain sump level rise*

UNPLANNED Torus level rise*

UNPLANNED RPV make up rate rise*

Observation of leakage or inventory loss

Rise in level is attributed to a loss of RPV inventory Table C4 Containment Challenge Indications Primary Containment Hydrogen Concentration

> 6% and Oxygen > 5%

UNPLANNED rise in containment pressure CONTAINMENT CLOSURE not established*

Secondary Containment area radiation > ANY Maximum Safe Operating Limit (EOP-5)

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.

James A. FitzPatrick Nuclear Power Plant Annex COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear Month 20XX COLD SHUTDOWN/REFUELING MATRIX JAF 2-22 COLD SHUTDOWN/REFUELING MATRIX EP-AA-1014 Addendum 3 (Rev.X)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Hazards and Other conditions Affecting Plant Safety Hostile Action HS1 1 2 3 4 5 D HOSTILE ACTION within the PROTECTED AREA.

Emergency Action Level (EAL):

A notification from the Security Force that a HOSTILE ACTION is occurring or has occurred within the PROTECTED AREA.

HA1 1 2 3 4 5 D HOSTILE ACTION within the OWNER CONTROLLED AREA or airborne attack threat within 30 minutes.

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 CONTROLLED AREA.

HU1 1 2 3 4 5 D Confirmed SECURITY CONDITION or threat.

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.

Transfer of Plant Control Table H1 Safety Functions

Reactivity Control (ability to shutdown the reactor and keep it shutdown)

RPV Water Level (ability to cool the core)

RCS Heat Removal (ability to maintain a heat sink)

HS2 1 2 3 4 5 D Inability to control a key safety function from outside the Control Room.

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 AOP-43, Plant Shutdown from Outside the Control Room.

AND

2. Control of ANY Table H1 key safety function is not reestablished in < 30 minutes.

HA2 1 2 3 4 5 D Control Room evacuation resulting in transfer of plant control to alternate locations.

Emergency Action Level (EAL):

A Control Room evacuation has resulted in plant control being transferred from the Control Room to alternate locations per AOP-43, Plant Shutdown from Outside the Control Room.

Modes:

1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled

James A. FitzPatrick Nuclear Power Plant Annex COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear Month 20XX COLD SHUTDOWN/REFUELING MATRIX JAF 2-23 COLD SHUTDOWN/REFUELING MATRIX EP-AA-1014 Addendum 3 (Rev.X)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Hazards and Other conditions Affecting Plant Safety Fire Table H2 Areas Reactor Building (when inerted the Drywell is exempt)

Control Room / Relay Room / Cable Run Rooms / Cable Spreading Room Electric Bays Control Room AC Equipment Room Control Room Chiller Room Emergency Diesel Generator Building Battery Rooms / Battery Room Corridor RHRSW / ESW Pump Rooms Cable Tunnels Remote Safe Shutdown Panels 25ASP-4 and 25ASP-5 (for MSIV /

ADS)

HU3 1 2 3 4 5 D FIRE potentially degrading the level of safety of the plant.

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.

Escalation of the emergency classification level would be via IC CA2 or MA5

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.

Modes:

1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled

James A. FitzPatrick Nuclear Power Plant Annex COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear Month 20XX COLD SHUTDOWN/REFUELING MATRIX JAF 2-24 COLD SHUTDOWN/REFUELING MATRIX EP-AA-1014 Addendum 3 (Rev.X)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Hazards and Other conditions Affecting Plant Safety Earthquake HU4 1 2 3 4 5 D Seismic event greater than OBE levels.

Emergency Action Level (EAL):

Note:

For emergency classification if EAL # 2.b is not able to be confirmed, then the occurrence of a seismic event is confirmed in manner deemed appropriate by the Emergency Director in < 15 minutes of the event Escalation of the emergency classification level would be via IC CA2 or MA5.

1. Seismic event > Operating Basis Earthquake (OBE) as determined by seismic monitoring system in accordance with AOP-14 Earthquake.

OR

2. When Seismic Monitoring Equipment is not available:

a. Control Room personnel feel an actual or potential seismic event.

AND

b. ANY one of the following confirmed in < 15 minutes of the event:

The earthquake resulted in Modified Mercalli Intensity (MMI) > VI and occurred < 3.5 miles of the plant.

The earthquake was magnitude > 6.0 The earthquake was magnitude > 5.0 and occurred

< 125 miles of the plant.

Modes:

1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled

James A. FitzPatrick Nuclear Power Plant Annex COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear Month 20XX COLD SHUTDOWN/REFUELING MATRIX JAF 2-25 COLD SHUTDOWN/REFUELING MATRIX EP-AA-1014 Addendum 3 (Rev.X)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Hazards and Other conditions Affecting Plant Safety Toxic Gas Table H3 Areas with Entry Related Mode Applicability Area Entry Related Mode Applicability Reactor Building East Crescent Reactor Building West Crescent Reactor Building 272 Elevation Reactor Building 300 Elevation Relay Room North Cable Room Mode 3, 4, and 5 HA5 3 4 5 Gaseous release impeding access to equipment necessary for normal plant operations, cooldown or shutdown.

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.

AND

2. Entry into the room or area is prohibited or impeded Hazardous Event HU6 1 2 3 4 5 D Hazardous Event Emergency Action Level (EAL):

Note:

EAL #4 does not apply to routine traffic impediments such as fog, snow, ice, or vehicle breakdowns or accidents.

Escalation of the emergency classification level would be via IC CA2 or MA5

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.

OR

5. Intake Water Level > 255 feet.

OR

6. ESW intake bay water level < 237 feet.

Modes:

1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled

James A. FitzPatrick Nuclear Power Plant Annex COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear Month 20XX COLD SHUTDOWN/REFUELING MATRIX JAF 2-26 COLD SHUTDOWN/REFUELING MATRIX EP-AA-1014 Addendum 3 (Rev.X)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Hazards and Other conditions Affecting Plant Safety Emergency Director Judgment HG7 1 2 3 4 5 D Other conditions exist which in the judgment of the Emergency Director warrant declaration of a GENERAL EMERGENCY.

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.

HS7 1 2 3 4 5 D Other conditions exist which in the judgment of the Emergency Director warrant declaration of a SITE AREA EMERGENCY.

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.

HA7 1 2 3 4 5 D Other conditions exist which in the judgment of the Emergency Director warrant declaration of an ALERT.

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.

HU7 1 2 3 4 5 D Other conditions exist which in the judgment of the Emergency Director warrant declaration of an UNUSUAL EVENT.

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.

Modes:

1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled

James A. FitzPatrick Nuclear Power Plant Annex COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear Month 20XX COLD SHUTDOWN/REFUELING MATRIX JAF 2-27 COLD SHUTDOWN/REFUELING MATRIX EP-AA-1014 Addendum 3 (Rev.X)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT ISFSI Malfunction ISFSI E-HU1 1 2 3 4 5 D Damage to a loaded cask CONFINEMENT BOUNDARY.

Emergency Action Level (EAL):

Damage to a loaded cask CONFINEMENT BOUNDARY as indicated by a radiation reading > Table E-1 values:

Table E-1 Radiation Reading Overpack Serial Number Overpack Average Surface Dose Rates mrem/hr (gamma+neutron)

Overpack Serial Number HI-STORM 100S (XXX)

Overpack Average Surface Dose Rates mrem/hr (gamma+neutron)

HI-STORM 100S S/N - 15, 16, 17 80 on the side 20 on the top 32 at the inlet and outlet vent ducts S/N -

0186, 0187, 0188 220 on the side 40 on the top S/N -

0307, 0308,

0309, 0310,

0311, 0312,

0679, 0680,

0681, 0682,

0683, 0690,

0691, 0692,

0693, 0694, 0695 600 on the side 60 on the top HI-STORM 100S (232)

S/N -

0169, 0170, 0171 100 on the side 20 on the top 90 at the inlet and outlet vent ducts Modes:

1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX JAF 2-1 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Abnormal Rad Levels / Radiological Effluents Radiological Effluents RG1 1 2 3 4 5 D Release of gaseous radioactivity resulting in offsite dose greater than 1,000 mRem TEDE or 5,000 mRem thyroid CDE.

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(Table R1) should be used for emergency classification assessments until the results from a dose assessment using actual meteorology are available.

1.

Readings on ANY Table R1 Effluent Monitor > Table R1 value for > 15 minutes.

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

3.

Field survey results at or beyond the site boundary indicate EITHER:

a.

Gamma (closed window) dose rates

> 1000 mR/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.

RS1 1 2 3 4 5 D Release of gaseous radioactivity resulting in offsite dose greater than 100 mRem TEDE or 500 mRem thyroid CDE.

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 (Table R1) should be used for emergency classification assessments until the results from a dose assessment using actual meteorology are available.

1.

Readings on ANY Table R1 Effluent Monitor > Table R1 value for > 15 minutes.

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.

RA1 1 2 3 4 5 D Release of gaseous or liquid radioactivity resulting in offsite dose greater than 10 mrem TEDE or 50 mrem thyroid CDE.

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 (Table R1) should be used for emergency classification assessments until the results from a dose assessment using actual meteorology are available.

1. Readings on ANY Table R1 Effluent Monitor > Table R1 value for > 15 minutes.

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.

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 > 60 minutes.

OR

b. Analyses of field survey samples indicate

> 50 mRem CDE Thyroid for 60 minutes of inhalation.

RU1 1 2 3 4 5 D Release of gaseous or liquid radioactivity greater than 2 times the ODCM limits for 60 minutes or longer.

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 the Liquid Radwaste Effluent Monitor (17RM-350) > 2 times hi-hi trip for 60 minutes.

OR

2. Readings on ANY Table R1 Effluent Monitor > Table R1 value for > 60 minutes.

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.

Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX JAF 2-2 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

Table R1 Effluent Monitor Thresholds Effluent Monitor General Emergency Site Area Emergency Alert Unusual Event Stack 7880 mR/hr 788 mR/hr 78.8 mR/hr 0.451 mR/hr (High Range Monitor)

Rx Bldg Exh N/A N/A N/A 9.50E+05 cpm (Low Range Monitor)

Turb Bldg Exh 2.44 mR/hr 0.244 mR/hr N/A 6.72E+05 cpm (Low Range Monitor)

Radw Bldg Exh 4.74 mR/hr 0.474 mR/hr N/A N/A Refuel Floor Exh N/A N/A N/A 9.28E+05 cpm (Low Range Monitor)

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX JAF 2-3 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Abnormal Rad Levels / Radiological Effluents Radiological Effluents RG2 1 2 3 4 5 D Spent fuel pool level cannot be restored to at least 1.00 foot for 60 minutes or longer.

Emergency Action Levels (EAL):

Note: The Emergency Director should declare the event promptly upon determining that the applicable time has been exceeded, or will likely be exceeded.

Spent fuel pool level cannot be restored to at least 1.00 foot as indicated on19LI-60A or 19LI-60B for > 60 minutes.

Table R3 Areas Requiring Continuous Occupancy Main Control Room - (by survey)

Central Alarm Station - (by survey)

Secondary Alarm Station - (by survey)

RS2 1 2 3 4 5 D Spent fuel pool level at 1.00 foot.

Emergency Action Level (EAL):

Lowering of spent fuel pool level to 1.00 foot as indicated on 19LI-60A or 19LI-60B.

Table R4 Areas with Entry Related Mode Applicability Area Entry Related Mode Applicability Reactor Building East Crescent Reactor Building West Crescent Reactor Building 272 Elevation Reactor Building 300 Elevation Relay Room North Cable Room Mode 3, 4, and 5 Table R2 Refuel Floor Radiation Monitors

18RIA-051-12 Spent Fuel Pool (EPIC A-1229)

18RIA-051-14 New Fuel Vault (EPIC A-1231)

18RIA-052-30 Refuel Floor West (EPIC A-1247)

17RIS-456A or B Refuel Floor Exhaust RA2 1 2 3 4 5 D Significant lowering of water level above, or damage to, irradiated fuel.