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, 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; ML18037A793; ML18037A795;
References
	JAFP-018-0014
	Download: ML18037A795 (27)
	v • d • e

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Abnormal Rad Levels / Radiological Effluents RG1 1 2 3 4 5 D RS1 1 2 3 4 5 D RA1 1 2 3 4 5 D RU1 1 2 3 4 5 D Release of gaseous radioactivity resulting in offsite dose greater Release of gaseous radioactivity resulting in offsite dose greater Release of gaseous or liquid radioactivity resulting in offsite Release of gaseous or liquid radioactivity greater than 2 times than 1,000 mRem TEDE or 5,000 mRem thyroid CDE. than 100 mRem TEDE or 500 mRem thyroid CDE. dose greater than 10 mrem TEDE or 50 mrem thyroid CDE. the ODCM limits for 60 minutes or longer.

Emergency Action Level (EAL): Emergency Action Level (EAL): Emergency Action Level (EAL): Emergency Action Level (EAL):

Notes: Notes: Notes: Notes:

The Emergency Director should declare the event promptly

The Emergency Director should declare the event promptly

The Emergency Director should declare the event

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

If an ongoing release is detected and the release start time

If an ongoing release is detected and the release start time

If an ongoing release is detected and the release start

If an ongoing release is detected and the release start is unknown, assume that the release duration has is unknown, assume that the release duration has time is unknown, assume that the release duration has time is unknown, assume that the release duration has exceeded 15 minutes. exceeded 15 minutes. exceeded 15 minutes. exceeded 60 minutes.

Classification based on effluent monitor readings assumes

Classification based on effluent monitor readings assumes

Classification based on effluent monitor readings assumes

Classification based on effluent monitor readings assumes that a release path to the environment is established. If the that a release path to the environment is established. If the that a release path to the environment is established. If that a release path to the environment is established. If effluent flow past an effluent monitor is known to have effluent flow past an effluent monitor is known to have the effluent flow past an effluent monitor is known to have the effluent flow past an effluent monitor is known to have stopped due to actions to isolate the release path, then the stopped due to actions to isolate the release path, then the stopped due to actions to isolate the release path, then stopped due to actions to isolate the release path, then effluent monitor reading is no longer valid for classification effluent monitor reading is no longer valid for classification the effluent monitor reading is no longer valid for the effluent monitor reading is no longer valid for purposes. purposes. classification purposes. classification purposes.

Radiological Effluents

The pre-calculated effluent monitor values presented in

The pre-calculated effluent monitor values presented in

The pre-calculated effluent monitor values presented in EAL #1(Table R1) should be used for emergency EAL #1 (Table R1) should be used for emergency EAL #1 (Table R1) should be used for emergency classification assessments until the results from a dose classification assessments until the results from a dose classification assessments until the results from a dose 1. Reading on the Liquid Radwaste Effluent Monitor (17RM-assessment using actual meteorology are available. assessment using actual meteorology are available. assessment using actual meteorology are available. 350) > 2 times hi-hi trip for 60 minutes.

OR

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

1. Readings on ANY Table R1 Effluent Monitor > Table R1 value 1. Readings on ANY Table R1 Effluent Monitor > Table R1 value for > 15 minutes. 2. Readings on ANY Table R1 Effluent Monitor > Table R1 value for > 15 minutes. for > 15 minutes. for > 60 minutes.

OR OR OR 2. Dose assessment using actual meteorology indicates doses at OR

2. Dose assessment using actual meteorology indicates doses at or beyond the site boundary of EITHER:

2. Dose assessment using actual meteorology indicates doses at 3. Confirmed sample analyses for gaseous or liquid releases or beyond the site boundary of EITHER: a. > 10 mRem TEDE or beyond the site boundary of EITHER: indicate concentrations or release rates

a. > 1000 mRem TEDE OR

a. > 100 mRem TEDE > 2 times ODCM Limit with a release duration OR b. > 50 mRem CDE Thyroid of > 60 minutes.

b. > 5000 mRem CDE Thyroid OR OR OR b. > 500 mRem CDE Thyroid 3. Analysis of a liquid effluent sample indicates a concentration

3. Field survey results at or beyond the site boundary indicate or release rate that would result in doses greater than OR EITHER of the following at or beyond the site boundary.

EITHER:

a. Gamma (closed window) dose rates 3. Field survey results at or beyond the site boundary indicate a. 10 mRem TEDE for 60 minutes of exposure.

EITHER: OR

> 1000 mR/hr are expected to continue for > 60 minutes. b. 50 mRem CDE Thyroid for 60 minutes

a. Gamma (closed window) dose rates of exposure.

OR > 100 mR/hr are expected to continue for > 60 minutes. OR

b. Analyses of field survey samples indicate 4. Field survey results at or beyond the site boundary indicate

> 5000 mRem CDE Thyroid for 60 minutes OR EITHER:

of inhalation. a. Gamma (closed window) dose rates

b. Analyses of field survey samples indicate

> 500 mRem CDE Thyroid for 60 minutes > 10 mR/hr are expected to continue of inhalation. for > 60 minutes.

OR

b. Analyses of field survey samples indicate

> 50 mRem CDE Thyroid for 60 minutes of inhalation.

Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled Month 20XX HOT MATRIX JAF 2-1 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear 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)

Month 20XX HOT MATRIX JAF 2-2 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Abnormal Rad Levels / Radiological Effluents RG2 1 2 3 4 5 D RS2 1 2 3 4 5 D RA2 1 2 3 4 5 D RU2 1 2 3 4 5 D Spent fuel pool level cannot be restored to at least 1.00 foot Spent fuel pool level at 1.00 foot. Significant lowering of water level above, or damage to, UNPLANNED loss of water level above irradiated fuel.

for 60 minutes or longer. irradiated fuel.

Emergency Action Level (EAL): Emergency Action Level (EAL):

Emergency Action Levels (EAL): Emergency Action Level (EAL):

Lowering of spent fuel pool level to 1.00 foot as indicated

1. a. UNPLANNED water level drop in the REFUELING Note: The Emergency Director should declare the event on 19LI-60A or 19LI-60B.

PATHWAY as indicated by ANY of the following:

promptly upon determining that the applicable time 1. Uncovery of irradiated fuel in the REFUELING has been exceeded, or will likely be exceeded. PATHWAY.

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

OR Spent fuel pool level cannot be restored to at least OR 1.00 foot as indicated on19LI-60A or 19LI-60B 2. Damage to irradiated fuel resulting in a release of for > 60 minutes. radioactivity from the fuel as indicated by ANY

Indication or report of a drop in water level Table R2 Refuel Floor Radiation Monitors Table R2 Radiation Monitor Alarm. in the REFUELING PATHWAY.

OR AND

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

3. Lowering of spent fuel pool level to 11.00 feet as b. UNPLANNED Area Radiation Monitor reading rise

18RIA-051-14 New Fuel Vault (EPIC A-1231) indicated on 19LI-60A or 19LI-60B. on ANY Table R2 radiation monitor.

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

Radiological Effluents

17RIS-456A or B Refuel Floor Exhaust RA3 1 2 3 4 5 D RU3 1 2 3 Radiation levels that impede access to equipment necessary Reactor coolant activity greater than Technical for normal plant operations, cooldown or shutdown. Specification allowable limits.

Table R4 Areas with Entry Related Mode Applicability Emergency Action Level (EAL): Emergency Action Level (EAL):

Table R3 Areas Requiring Continuous Occupancy Entry Note: If the equipment in the room or area listed in Table Related R4 was already inoperable, or out of service, before

Main Control Room - (by survey) Area 1 Offgas radiation > hi-hi alarm Mode the event occurred, then no emergency classification

Central Alarm Station - (by survey) Applicability is warranted. OR

Secondary Alarm Station - (by survey) 1. Dose rate > 15 mR/hr in ANY of the areas in Table R3. 2. Specific coolant activity > 2.0 µCi/gm I-131 dose

Reactor Building East Crescent equivalent.

OR

Reactor Building West Crescent

Reactor Building 272 Elevation 2. UNPLANNED event results in radiation levels that Mode 3, 4, prohibit or significantly impede access to ANY of the

Reactor Building 300 Elevation and 5 areas in Table R4.

Relay Room

North Cable Room Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled Month 20XX HOT MATRIX JAF 2-3 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear 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 FC - Fuel Clad RC - Reactor Coolant System CT - Containment Sub-Category Loss Potential Loss Loss Potential Loss Loss Potential Loss Coolant activity > 300 uCi/gm I-131 dose None None

1. RCS Activity None None None equivalent.

2. RPV water level cannot be restored and 1. RPV water level cannot be restored and

1. SAOG entry required maintained > 0 inches (TAF). maintained > 0 inches (TAF). SAOG entry required

2. RPV Water Level None None OR OR

3. RPV water level cannot be determined. 2. RPV water level cannot be determined.

3. Primary Containment pressure > 56 psig and rising.

OR

1. a. Primary Containment pressure 1. UNPLANNED rapid drop in Primary

4. a. Primary Containment hydrogen

3. Primary > 2.7 psig. Containment pressure following Primary concentration > 6%.

Containment AND Containment pressure rise.

None None None AND Pressure / b. Primary Containment pressure rise is OR Conditions b. Primary Containment oxygen concentration due to RCS leakage. 2. Primary Containment pressure response not

> 5%.

consistent with LOCA conditions.

OR

5. Heat Capacity Temperature Limit (HCTL)

(EOP-11) exceeded.

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

1. UNISOLABLE Main Steam Line (MSL),

HPCI, RWCU, RCIC, or Feedwater line a. Secondary Containment area temperature break. > EOP-5 Maximum Normal Operating

4. RCS Leak Rate None None Limit. None None OR

2. Emergency RPV Depressurization is OR required. b. Secondary Containment area radiation

> EOP-5 Maximum Normal Operating Limit.

5. Primary Drywell radiation monitor reading Drywell radiation monitor reading Drywell radiation monitor reading Containment None None None

> 1.8E+03 R/hr (1800 R/hr). > 63 R/hr. > 1.8E+04 R/hr (18,000 R/hr).

Radiation

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.

6. Primary OR Containment None None None None None Isolation Failure 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.

7. Emergency 1. Any Condition in the opinion of the 2. Any Condition in the opinion of the 1. Any Condition in the opinion of the 2. Any Condition in the opinion of the 1. Any Condition in the opinion of the 2. Any Condition in the opinion of the Director Emergency Director that indicates Loss Emergency Director that indicates Emergency Director that indicates Loss of Emergency Director that indicates Potential Emergency Director that indicates Loss of the Emergency Director that indicates Potential Judgment of the Fuel Clad Barrier. Potential Loss of the Fuel Clad Barrier. the RCS Barrier. Loss of the RCS Barrier. Containment Barrier. Loss of the Containment Barrier.

Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled Month 20XX HOT MATRIX JAF 2-4 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT System Malfunction MG1 1 2 3 MS1 1 2 3 MA1 1 2 3 MU1 1 2 3 Prolonged loss of all offsite and all onsite AC power to Loss of all offsite and onsite AC power to emergency Loss of all but one AC power source to emergency buses for Loss of all offsite AC power capability to emergency buses emergency buses. buses for 15 minutes or longer. 15 minutes or longer. for 15 minutes or longer.

Emergency Action Level (EAL): Emergency Action Level (EAL): Emergency Action Level (EAL): Emergency Action Level (EAL):

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

Loss of AC Power

1. Loss of ALL offsite and onsite AC power to 4160 V

1. Loss of ALL offsite and onsite AC power to 4160 V 1. AC power capability to 4160 V emergency buses 10500 Loss of ALL offsite AC power capability 4160 V emergency emergency buses 10500 and 10600.

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

AND sources for > 15 minutes.

2. EITHER of the following: AND

Reserve Station Transformer T-2

Reserve Station Transformer T-2

a. Restoration of at least one 4160 V emergency bus

Reserve Station Transformer T-3

2. Failure to restore power to at least one 4160 V

Reserve Station Transformer T-3 10500 or 10600 in < 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months is not likely. emergency bus 10500 or 10600 in < 15 minutes from

Station Service Transformer T-4 (While

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

OR the time of loss of both offsite and onsite AC power. backfeeding from Main Transformer)

b. RPV water level cannot be restored and maintained

EDG A

> -19 inches (MSCRWL).

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.

MG2 1 2 3 MS2 1 2 3 Loss of all AC and Vital DC power sources for 15 minutes or Loss of all Vital DC power for 15 minutes or longer.

longer.

Emergency Action Level (EAL):

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

been exceeded, or will likely be exceeded.

1. Loss of ALL offsite and onsite AC power to 4160 V Voltage is < 105 VDC on Vital DC buses 71BCB-2A emergency buses 10500 and 10600. and 71BCB-2B for > 15 minutes.

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.

Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled Month 20XX HOT MATRIX JAF 2-5 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT System Malfunction MS3 1 2 MA3 1 2 MU3 1 2 Inability to shutdown the reactor causing a challenge to RPV Automatic or manual scram fails to shutdown the Automatic or manual scram fails to shutdown the reactor.

water level or RCS heat removal. reactor, and subsequent manual actions taken at the Emergency Action Level (EAL):

Reactor Control Console are not successful in shutting Emergency Action Level (EAL):

down the reactor. Note: A manual action is any operator action, or set of

1. Automatic scram did not shutdown the reactor as actions, which causes the control rods to be rapidly Emergency Action Level (EAL):

indicated by Reactor Power > 2.5%. inserted into the core. This action does not include Note: A manual action is any operator action, or set of manually driving in control rods or implementation of AND actions, which causes the control rods to be rapidly boron injection strategies.

2. ALL manual / ARI actions to shutdown the reactor have inserted into the core. This action does not include

1. a. Automatic scram did not shutdown the reactor as been unsuccessful as indicated by Reactor Power manually driving in control rods or implementation of indicated by Reactor Power > 2.5%.

> 2.5%. boron injection strategies.

RPS Failure AND AND 1. Automatic or manual scram did not shutdown the

b. Subsequent manual / ARI action taken at the reactor as indicated by Reactor Power > 2.5%.

3. EITHER of the following conditions exist: Reactor Control Console is successful in shutting AND down the reactor as indicated by

RPV water level cannot be restored and maintained Reactor Power < 2.5%.

> -19 inches (MSCRWL). 2. Manual / ARI actions taken at the Reactor Control Console are not successful in shutting down the reactor OR OR as indicated by Reactor Power > 2.5%. 2. a. Manual scram did not shutdown the reactor as

Heat Capacity Temperature Limit (HCTL) indicated by Reactor Power > 2.5%.

(EOP-11) exceeded. 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%.

MA4 1 2 3 MU4 1 2 3 UNPLANNED loss of Control Room indications for 15 UNPLANNED loss of Control Room indications for 15 Control Room Indications minutes or longer with a significant transient in progress. minutes or longer.

Table M1 Control Room Parameters Table M2 Significant Transients Emergency Action Level (EAL): Emergency Action Level (EAL):

Reactor Power Note: The Emergency Director should declare the event Note: The Emergency Director should declare the event

Auto/Manual runback > 25% thermal reactor promptly upon determining that the applicable time promptly upon determining that the applicable time

RPV Water Level power has been exceeded, or will likely be exceeded. has been exceeded, or will likely be exceeded.

RPV Pressure

Electric load rejection > 25% full electric

Primary Containment Pressure load 1. UNPLANNED event results in the inability to monitor UNPLANNED event results in the inability to monitor ANY

Torus Level

Reactor Scram ANY Table M1 parameter from within the Control Room Table M1 parameter from within the Control Room for > 15 minutes. for > 15 minutes.

Torus Temperature

ECCS actuation AND

Thermal Power oscillations > 10% (peak to 2. ANY Table M2 transient in progress.

peak)

Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled Month 20XX HOT MATRIX JAF 2-6 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT System Malfunction 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 Hazard affects Safety System

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 Month 20XX HOT MATRIX JAF 2-7 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear 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.

MU7 1 2 3 Table M3 Communications Capability Loss of all onsite or offsite communication capabilities.

System Onsite Offsite NRC Emergency Action Level (EAL):

Page/Party System X 1. Loss of ALL Table M3 onsite communication (Gaitronics) capabilities affecting the ability to perform routine Control Room/Portable X operations.

Radio OR Plant Telephones (all X X X 2. Loss of ALL Table M3 offsite communication capabilities affecting the ability to perform offsite VOIP, switched, non-Communications notifications.

switched)

OR Out-of-Plant Cellular X X X 3. Loss of ALL Table M3 NRC communication Phones capabilities affecting the ability to perform NRC Plant Satellite Phones X X notifications.

RECS X Dedicated Phone Lines X X

(ENS)

HPN and FTS 2001 X X

Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled Month 20XX HOT MATRIX JAF 2-8 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Hazards and Other conditions Affecting Plant Safety HS1 1 2 3 4 5 D HA1 1 2 3 4 5 D HU1 1 2 3 4 5 D HOSTILE ACTION within the PROTECTED AREA. HOSTILE ACTION within the OWNER CONTROLLED Confirmed SECURITY CONDITION or threat.

AREA or airborne attack threat within 30 minutes.

Emergency Action Level (EAL): Emergency Action Level (EAL):

Emergency Action Level (EAL):

A notification from the Security Force that a HOSTILE 1. Notification of a credible security threat directed at the Hostile Action ACTION is occurring or has occurred within the 1. A validated notification from NRC from an aircraft site as determined per SY-AA-101-132, Security PROTECTED AREA. attack threat < 30 minutes of the site. Assessment and Response to Unusual Activities.

OR OR

2. A validated notification from the NRC providing

2. Notification by the Security Force that a HOSTILE information of an aircraft threat.

ACTION is occurring or has occurred within the OR OWNER CONTROLLED AREA.

3. Notification by the Security Force of a SECURITY CONDITION that does not involve a HOSTILE ACTION.

HS2 1 2 3 4 5 D HA2 1 2 3 4 5 D Inability to control a key safety function from outside the Control Room evacuation resulting in transfer of plant Table H1 Safety Functions Control Room. control to alternate locations.

Emergency Action Level (EAL): Emergency Action Level (EAL):

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

Note: The Emergency Director should declare the event A Control Room evacuation has resulted in plant control Transfer of Plant Control

RPV Water Level (ability to cool the core) promptly upon determining that the applicable time has being transferred from the Control Room to alternate been exceeded, or will likely be exceeded. locations per AOP-43, Plant Shutdown from Outside the

RCS Heat Removal (ability to maintain a heat sink) Control Room.

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.

Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled Month 20XX HOT MATRIX JAF 2-9 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Hazards and Other conditions Affecting Plant Safety HU3 1 2 3 4 5 D Table H2 Areas FIRE potentially degrading the level of safety of the plant.

Reactor Building (when inerted the Drywell is exempt) Emergency Action Level (EAL):

Control Room / Relay Room / Cable Note:

Run Rooms / Cable Spreading

The Emergency Director should declare the Room event promptly upon determining that the

Electric Bays applicable time has been exceeded, or will likely

Control Room AC Equipment Room be exceeded.

Control Room Chiller Room

Escalation of the emergency classification level would

Emergency Diesel Generator be via IC CA2 or MA5.

Building

1. A FIRE in ANY Table H2 area is not extinguished

Battery Rooms / Battery Room in < 15 minutes of ANY of the following FIRE detection Corridor indications:

RHRSW / ESW Pump Rooms

Report from the field (i.e., visual observation)

Cable Tunnels

Receipt of multiple (more than 1) fire alarms or

Remote Safe Shutdown Panels indications 25ASP-4 and 25ASP-5 (for MSIV /

Field verification of a single fire alarm ADS) OR Fire 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 Month 20XX HOT MATRIX JAF 2-10 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Hazards and Other conditions Affecting Plant Safety 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.

Earthquake 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 Month 20XX HOT MATRIX JAF 2-11 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Hazards and Other conditions Affecting Plant Safety HA5 3 4 5 Table H3 Areas with Entry Related Mode Applicability Gaseous release impeding access to equipment Entry Related necessary for normal plant operations, cooldown or Area Mode shutdown.

Applicability Toxic Gas Emergency Action Level (EAL):

Reactor Building East Crescent Note: If the equipment in the listed room or area was already inoperable, or out of service, before the

Reactor Building West Crescent event occurred, then no emergency classification

Reactor Building 272 Elevation Mode 3, 4, is warranted.

Reactor Building 300 Elevation and 5 1. Release of a toxic, corrosive, asphyxiant or

Relay Room flammable gas in ANY Table H3 area.

North Cable Room AND

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

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.

Hazardous Event

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 Month 20XX HOT MATRIX JAF 2-12 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Hazards and Other conditions Affecting Plant Safety HG7 1 2 3 4 5 D HS7 1 2 3 4 5 D HA7 1 2 3 4 5 D HU7 1 2 3 4 5 D Other conditions exist which in the judgment of the Other conditions exist which in the judgment of the Other conditions exist which in the judgment of the Other conditions exist which in the judgment of the Emergency Director warrant declaration of a GENERAL Emergency Director warrant declaration of a SITE AREA Emergency Director warrant declaration of an ALERT. Emergency Director warrant declaration of an UNUSUAL EMERGENCY. EMERGENCY. EVENT.

Emergency Action Level (EAL):

Emergency Action Level (EAL): Emergency Action Level (EAL): Emergency Action Level (EAL):

Other conditions exist which, in the judgment of the Other conditions exist which in the judgment of the Other conditions exist which in the judgment of the Emergency Director, indicate that events are in progress or Other conditions exist which in the judgment of the Emergency Emergency Director indicate that events are in progress or Emergency Director indicate that events are in progress or have occurred which involve an actual or potential Director indicate that events are in progress or have occurred have occurred which involve actual or IMMINENT substantial have occurred which involve actual or likely major failures of substantial degradation of the level of safety of the plant or a which indicate a potential degradation of the level of safety of core degradation or melting with potential for loss of plant functions needed for protection of the public or HOSTILE security event that involves probable life threatening risk to the plant or indicate a security threat to facility protection has containment integrity or HOSTILE ACTION that results in an ACTION that results in intentional damage or malicious acts, site personnel or damage to site equipment because of been initiated. No releases of radioactive material requiring actual loss of physical control of the facility. Releases can be (1) toward site personnel or equipment that could lead to the HOSTILE ACTION. Any releases are expected to be limited offsite response or monitoring are expected unless further reasonably expected to exceed EPA Protective Action likely failure of or, (2) that prevent effective access to to small fractions of the EPA Protective Action Guideline degradation of safety systems occurs.

Guideline exposure levels offsite for more than the immediate equipment needed for the protection of the public. Any exposure levels.

site area. releases are not expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels Emergency Director Judgment beyond the site boundary.

Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled Month 20XX HOT MATRIX JAF 2-13 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT ISFSI Malfunction 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 Overpack Overpack Overpack Serial Average Serial Average Surface Number Surface Dose Number Dose Rates Rates mrem/hr mrem/hr (gamma+neutron) HI- (gamma+neutron)

STORM 100S (XXX)

HI- 80 on the side S/N - 220 on the side STORM 0186, 100S 20 on the top 0187, 40 on the top ISFSI 32 at the inlet 0188 S/N - 15, 16, 17 and outlet vent ducts S/N -

0307, 0308, 0309, 0310, 0311, HI- 100 on the side 0312, STORM 20 on the top 0679, 100S 600 on the side 0680, (232) 90 at the inlet 0681, 60 on the top S/N - and outlet 0682, 0169, vent ducts 0683, 0170, 0690, 0171 0691, 0692, 0693, 0694, 0695 Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled Month 20XX HOT MATRIX JAF 2-14 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Abnormal Rad Levels / Radiological Effluents RG1 1 2 3 4 5 D RS1 1 2 3 4 5 D RA1 1 2 3 4 5 D RU1 1 2 3 4 5 D Release of gaseous radioactivity resulting in offsite dose greater Release of gaseous radioactivity resulting in offsite dose greater Release of gaseous or liquid radioactivity resulting in offsite dose Release of gaseous or liquid radioactivity greater than 2 than 1,000 mRem TEDE or 5,000 mRem thyroid CDE. than 100 mRem TEDE or 500 mRem thyroid CDE. greater than 10 mrem TEDE or 50 mrem thyroid CDE. times the ODCM limits for 60 minutes or longer.

Emergency Action Level (EAL): Emergency Action Level (EAL): Emergency Action Level (EAL): Emergency Action Level (EAL):

Notes: Notes: Notes: Notes:

The Emergency Director should declare the event promptly

The Emergency Director should declare the event promptly

The Emergency Director should declare the event promptly

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

If an ongoing release is detected and the release start time

If an ongoing release is detected and the release start time

If an ongoing release is detected and the release start time is

If an ongoing release is detected and the release start is unknown, assume that the release duration has is unknown, assume that the release duration has unknown, assume that the release duration has exceeded 15 time is unknown, assume that the release duration has exceeded 15 minutes. exceeded 15 minutes. minutes. exceeded 60 minutes.

Classification based on effluent monitor readings assumes

Classification based on effluent monitor readings assumes

Classification based on effluent monitor readings assumes that

Classification based on effluent monitor readings that a release path to the environment is established. If the that a release path to the environment is established. If the a release path to the environment is established. If the effluent assumes that a release path to the environment is effluent flow past an effluent monitor is known to have effluent flow past an effluent monitor is known to have flow past an effluent monitor is known to have stopped due to established. If the effluent flow past an effluent monitor stopped due to actions to isolate the release path, then the stopped due to actions to isolate the release path, then the actions to isolate the release path, then the effluent monitor is known to have stopped due to actions to isolate the effluent monitor reading is no longer valid for classification effluent monitor reading is no longer valid for classification reading is no longer valid for classification purposes. release path, then the effluent monitor reading is no Radiological Effluents purposes. purposes.

The pre-calculated effluent monitor values presented in EAL longer valid for classification purposes.

The pre-calculated effluent monitor values presented in

The pre-calculated effluent monitor values presented in #1(Table R1) should be used for emergency classification EAL #1(Table R1) should be used for emergency EAL #1(Table R1) should be used for emergency assessments until the results from a dose assessment using classification assessments until the results from a dose classification assessments until the results from a dose actual meteorology are available. 1. Reading on the Liquid Radwaste Effluent Monitor assessment using actual meteorology are available. assessment using actual meteorology are available. (LWS-RE206) > 2 times DRMS High (red) established by a current radioactive release discharge

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

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

for > 15 minutes. for > 15 minutes. OR OR OR OR 2. Dose assessment using actual meteorology indicates doses at or 2. Readings on ANY Table R1 Effluent Monitor > Table R1

2. Dose assessment Using actual meteorology indicates doses at beyond the site boundary of EITHER: value for > 60 minutes.

2. Dose assessment using actual meteorology indicates doses at a. > 10 mRem TEDE or beyond the site boundary of EITHER: OR or beyond the site boundary of EITHER: OR

a. > 1000 mRem TEDE

a. > 100 mRem TEDE b. > 50 mRem CDE Thyroid 3. Confirmed sample analyses for gaseous or liquid releases OR OR indicate concentrations or release rates

b. > 5000 mRem CDE Thyroid OR > 2 times ODCM Limit with a release duration

3. Analysis of a liquid effluent sample indicates a concentration or OR b. > 500 mRem CDE Thyroid release rate that would result in doses greater than EITHER of of > 60 minutes.

3. Field survey results at or beyond the site boundary indicate OR the following at or beyond the site boundary EITHER: a. 10 mRem TEDE for 60 minutes of exposure

a. Gamma (closed window) dose rates 3. Field survey results at or beyond the site boundary indicate OR EITHER:

> 1000 mR/hr are expected to continue b. 50 mRem CDE Thyroid for 60 minutes for > 60 minutes. a. Gamma (closed window) dose rates of exposure OR > 100 mR/hr are expected to continue OR

b. Analyses of field survey samples indicate for > 60 minutes. 4. Field survey results at or beyond the site boundary indicate

> 5000 mRem CDE Thyroid for 60 minutes OR EITHER:

of inhalation. a. Gamma (closed window) dose rates

b. Analyses of field survey samples indicate

> 500 mRem CDE Thyroid for 60 minutes > 10 mR/hr are expected to continue of inhalation. for > 60 minutes.

OR

b. Analyses of field survey samples indicate

> 50 mRem CDE Thyroid for 60 minutes of inhalation.

Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled Month 20XX COLD SHUTDOWN/REFUELING MATRIX JAF 2-15 COLD SHUTDOWN/REFUELING MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear 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)

Month 20XX COLD SHUTDOWN/REFUELING MATRIX JAF 2-16 COLD SHUTDOWN/REFUELING MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Abnormal Rad Levels / Radiological Effluents RG2 1 2 3 4 5 D RS2 1 2 3 4 5 D RA2 1 2 3 4 5 D RU2 1 2 3 4 5 D Spent fuel pool level cannot be restored to at least 1.00 foot Spent fuel pool level at 1.00 foot. Significant lowering of water level above, or damage to, UNPLANNED loss of water level above irradiated fuel.

for 60 minutes or longer. irradiated fuel.

Emergency Action Level (EAL): Emergency Action Level (EAL):

Emergency Action Levels (EAL): Emergency Action Level (EAL):

Lowering of spent fuel pool level to 1.00 foot as indicated

1. a. UNPLANNED water level drop in the REFUELING Note: The Emergency Director should declare the event on 19LI-60-A or 19LI-60B.

PATHWAY as indicated by ANY of the following:

promptly upon determining that the applicable time 1. Uncovery of irradiated fuel in the REFUELING has been exceeded, or will likely be exceeded. PATHWAY.

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

OR Spent fuel pool level cannot be restored to at least OR 1.00 foot as indicated on 19LI-60A or 19LI-60B 2. Damage to irradiated fuel resulting in a release of for > 60 minutes. radioactivity from the fuel as indicated by ANY

Indication or report of a drop in water level in Table R2 Refuel Floor Radiation Monitors Table R2 Radiation Monitor Alarm. the REFUELING PATHWAY.

OR AND

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

3. Lowering of spent fuel pool level to 11.00 feet as b. UNPLANNED Area Radiation Monitor reading rise

18RIA-051-14 New Fuel Vault (EPIC A-1231) indicated on 19LI-60A or 19LI-60B. on ANY Table R2 radiation monitor.

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

Radiological Effluents

17RIS-456A or B Refuel Floor Exhaust RA3 1 2 3 4 5 D Radiation levels that impede access to equipment necessary for normal plant operations, cooldown or shutdown.

Table R4 Emergency Action Level (EAL):

Areas with Entry Related Mode Applicability Table R3 Note: If the equipment in the room or area listed in Table Areas Requiring Continuous Occupancy Entry R4 was already inoperable, or out of service, before Related the event occurred, then no emergency classification

Main Control Room - (by survey) Area Mode is warranted.

Central Alarm Station - (by survey) Applicability

1. Dose rate > 15 mR/hr in ANY of the areas in Table R3.

Secondary Alarm Station - (by survey)

Reactor Building East Crescent OR

Reactor Building West Crescent 2. UNPLANNED event results in radiation levels that

Reactor Building 272 Elevation prohibit or significantly impede access to ANY of the Mode 3, 4, areas in Table R4.

Reactor Building 300 Elevation and 5

Relay Room

North Cable Room Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled Month 20XX COLD SHUTDOWN/REFUELING MATRIX JAF 2-17 COLD SHUTDOWN/REFUELING MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Cold Shutdown / Refueling System Malfunctions CA1 4 5 D CU1 4 5 D Loss of all offsite and onsite AC power to emergency buses for Loss of all but one AC power source to emergency buses for 15 minutes or longer. 15 minutes or longer.

Emergency Action Level (EAL): Emergency Action Level (EAL):

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

1. Loss of ALL offsite and onsite AC power to 4160 V 1. AC power capability to 4160 V emergency buses 10500 and emergency buses 10500 and 10600. 10600 reduced to only one of the following power sources for > 15 minutes.

AND

Reserve Station Transformer T-2

2. Failure to restore power to at least one 4160 V emergency

Reserve Station Transformer T-3 bus 10500 or 10600 in < 15 minutes from the time of loss

Station Service Transformer T-4 (While backfeeding of both offsite and onsite AC power.

from Main Transformer)

EDG A

EDG B

EDG C Loss of AC Power

EDG D AND

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

Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled Month 20XX COLD SHUTDOWN/REFUELING MATRIX JAF 2-18 COLD SHUTDOWN/REFUELING MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Cold Shutdown / Refueling System Malfunctions 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:

Safety System

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 Month 20XX COLD SHUTDOWN/REFUELING MATRIX JAF 2-19 COLD SHUTDOWN/REFUELING MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Cold Shutdown / Refueling System Malfunctions CU3 4 5 Loss of Vital DC power for 15 minutes or longer.

DC Power 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.

CU4 4 5 D Table C1 Communication Capabilities Loss of all onsite or offsite communication capabilities.

System Onsite Offsite NRC Page/Party System X Emergency Action Level (EAL):

Communications (Gaitronics) 1. Loss of ALL Table C1 onsite communication Control Room/Portable X capabilities affecting the ability to perform routine Radio operations.

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

2. Loss of ALL Table C1 offsite communication Out-of-Plant Cellular Phones X X X capabilities affecting the ability to perform offsite Plant Satellite Phones X X notifications.

RECS X OR Dedicated Phone Lines X X 3. Loss of ALL Table C1 NRC communication (ENS) capabilities affecting the ability to perform NRC HPN and FTS 2001 X X notifications.

CA5 4 5 CU5 4 5 Table C2 RCS Heat-up Duration Thresholds RCS Containment Heat-up Inability to maintain plant in cold shutdown. UNPLANNED rise in RCS temperature.

Status Closure Status Duration Emergency Action Levels (EAL):

Emergency Action Levels (EAL):

Intact Not Applicable 60 minutes*

Note: Note:

Established 20 minutes*

The Emergency Director should declare the event

The Emergency Director should declare the event promptly upon determining that the applicable time promptly upon determining that the applicable time Heat Sink Not Intact has been exceeded, or will likely be exceeded.

has been exceeded, or will likely be exceeded.

A momentary UNPLANNED excursion above the

A momentary UNPLANNED excursion above the Not Established 0 minutes Technical Specification cold shutdown temperature Technical Specification cold shutdown temperature limit when heat removal function is available does limit when heat removal function is available does

If an RCS heat removal system is in operation not warrant classification. not warrant classification.

within this time frame and RCS temperature is being 1. UNPLANNED rise in RCS temperature > 212 ºF 1. UNPLANNED rise in RCS temperature > 212 ºF.

reduced, then EAL #1 is not applicable. for > Table C2 duration. OR OR 2. Loss of the following for > 15 minutes.

2. UNPLANNED RPV pressure rise > 10 psig as a

ALL RCS temperature indications result of temperature rise AND

ALL RPV water level indications Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled Month 20XX COLD SHUTDOWN/REFUELING MATRIX JAF 2-20 COLD SHUTDOWN/REFUELING MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Cold Shutdown / Refueling System Malfunctions CG6 4 5 CS6 4 5 CA6 4 5 CU6 4 5 Loss of RPV inventory affecting fuel clad integrity with Loss of RPV inventory affecting core decay heat removal Loss of RPV inventory. UNPLANNED loss of RP inventory for 15 minutes or containment challenged. capabilities. longer.

Emergency Action Level (EAL):

Emergency Action Level (EAL): Emergency Action Level (EAL): Emergency Action Level (EAL):

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

1. Loss of RPV inventory as indicated by 1 a. RPV water level < 0 inches (TAF) for 1. With CONTAINMENT CLOSURE not established, level < 126.5 inches. 1. UNPLANNED loss of reactor coolant results in the

> 30 minutes. RPV water level < 120.5 inches. inability to restore and maintain RPV level to above the OR AND OR procedurally established lower limit

2. With CONTAINMENT CLOSURE established, RPV 2. a. RPV water level cannot be monitored for > 15 minutes.

b. Any Table C4 Containment Challenge Indication.

water level < 0 inches (TAF). for > 15 minutes.

OR OR OR AND

2. a. RPV water level cannot be monitored 3. a. RPV water level cannot be monitored for 2. a. RPV water level cannot be monitored.

for > 30 minutes. b. Loss of RPV inventory per Table C3 indications.

> 30 minutes. AND AND AND RCS Leakage / Inventory

b. Loss of RPV inventory per Table C3 indications.

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

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

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

OR OR

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

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

1247) Rad monitor > 3 R/hr.

AND

c. ANY Table C4 Containment Challenge Indication.

Table C3 Indications of RCS Leakage

UNPLANNED Drywell equipment drain sump level Table C4 Containment Challenge Indications rise*

Primary Containment Hydrogen Concentration

UNPLANNED Drywell floor drain sump level rise*

> 6% and Oxygen > 5%

UNPLANNED Reactor Building equipment sump level rise*

UNPLANNED rise in containment pressure

UNPLANNED Reactor Building floor drain sump level

CONTAINMENT CLOSURE not established*

rise*

Secondary Containment area radiation > ANY

UNPLANNED Torus level rise* Maximum Safe Operating Limit (EOP-5)

UNPLANNED RPV make up rate rise*

if CONTAINMENT CLOSURE is re-established prior

Observation of leakage or inventory loss to exceeding the 30-minute core uncovery time limit, then escalation to a General Emergency is not

Rise in level is attributed to a loss of RPV inventory required.

Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled Month 20XX COLD SHUTDOWN/REFUELING MATRIX JAF 2-21 COLD SHUTDOWN/REFUELING MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Hazards and Other conditions Affecting Plant Safety HS1 1 2 3 4 5 D HA1 1 2 3 4 5 D HU1 1 2 3 4 5 D HOSTILE ACTION within the PROTECTED AREA. HOSTILE ACTION within the OWNER CONTROLLED Confirmed SECURITY CONDITION or threat.

AREA or airborne attack threat within 30 minutes.

Emergency Action Level (EAL): Emergency Action Level (EAL):

Emergency Action Level (EAL):

A notification from the Security Force that a HOSTILE 1. Notification of a credible security threat directed at Hostile Action ACTION is occurring or has occurred within the 1. A validated notification from NRC of an aircraft the site as determined per SY-AA-101-132, Security PROTECTED AREA. attack threat < 30 minutes from the site. Assessment and Response to Unusual Activities.

OR OR

2. A validated notification from the NRC providing

2. Notification by the Security Force that a HOSTILE information of an aircraft threat.

ACTION is occurring or has occurred within the OR OWNER CONTROLLED AREA.

3. Notification by the Security Force of a SECURITY CONDITION that does not involve a HOSTILE ACTION.

HS2 1 2 3 4 5 D HA2 1 2 3 4 5 D Inability to control a key safety function from outside the Control Room evacuation resulting in transfer of plant Table H1 Safety Functions Control Room. control to alternate locations.

Emergency Action Level (EAL): Emergency Action Level (EAL):

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

Note: The Emergency Director should declare the event A Control Room evacuation has resulted in plant control Transfer of Plant Control

RPV Water Level (ability to cool the core) promptly upon determining that the applicable time has being transferred from the Control Room to alternate been exceeded, or will likely be exceeded. locations per AOP-43, Plant Shutdown from Outside the

RCS Heat Removal (ability to maintain a heat sink) Control Room.

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.

Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled Month 20XX COLD SHUTDOWN/REFUELING MATRIX JAF 2-22 COLD SHUTDOWN/REFUELING MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Hazards and Other conditions Affecting Plant Safety Table H2 Areas HU3 1 2 3 4 5 D

Reactor Building (when inerted the FIRE potentially degrading the level of safety of the plant.

Drywell is exempt) Emergency Action Level (EAL):

Control Room / Relay Room / Cable Note:

Run Rooms / Cable Spreading Room

The Emergency Director should declare the

Electric Bays event promptly upon determining that the applicable time has been exceeded, or will likely

Control Room AC Equipment Room be exceeded.

Control Room Chiller Room

Escalation of the emergency classification level would

Emergency Diesel Generator be via IC CA2 or MA5 Building

Battery Rooms / Battery Room 1. A FIRE in ANY Table H2 area is not extinguished in Corridor < 15 minutes of ANY of the following FIRE detection

RHRSW / ESW Pump Rooms indications:

Cable Tunnels

Report from the field (i.e., visual observation)

Receipt of multiple (more than 1) fire alarms or

Remote Safe Shutdown Panels indications 25ASP-4 and 25ASP-5 (for MSIV /

Field verification of a single fire alarm ADS)

OR

2. a. Receipt of a single fire alarm in ANY Table H2 area Fire (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 Month 20XX COLD SHUTDOWN/REFUELING MATRIX JAF 2-23 COLD SHUTDOWN/REFUELING MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Hazards and Other conditions Affecting Plant Safety 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.

Earthquake 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 Month 20XX COLD SHUTDOWN/REFUELING MATRIX JAF 2-24 COLD SHUTDOWN/REFUELING MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Hazards and Other conditions Affecting Plant Safety HA5 3 4 5 Table H3 Gaseous release impeding access to equipment Areas with Entry Related Mode Applicability necessary for normal plant operations, cooldown or shutdown.

Entry Related Emergency Action Level (EAL):

Toxic Gas Area Mode Note: If the equipment in the listed room or area was Applicability already inoperable, or out of service, before the event occurred, then no emergency classification

Reactor Building East Crescent is warranted.

Reactor Building West Crescent

Reactor Building 272 Elevation 1. Release of a toxic, corrosive, asphyxiant or Mode 3, 4, flammable gas in ANY Table H3 area.

Reactor Building 300 Elevation

Relay Room and 5 AND

North Cable Room 2. Entry into the room or area is prohibited or impeded 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 Hazardous Event

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 Month 20XX COLD SHUTDOWN/REFUELING MATRIX JAF 2-25 COLD SHUTDOWN/REFUELING MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Hazards and Other conditions Affecting Plant Safety HG7 1 2 3 4 5 D HS7 1 2 3 4 5 D HA7 1 2 3 4 5 D HU7 1 2 3 4 5 D Other conditions exist which in the judgment of the Other conditions exist which in the judgment of the Other conditions exist which in the judgment of the Other conditions exist which in the judgment of the Emergency Director warrant declaration of a GENERAL Emergency Director warrant declaration of a SITE AREA Emergency Director warrant declaration of an ALERT. Emergency Director warrant declaration of an UNUSUAL EMERGENCY. EMERGENCY. EVENT.

Emergency Action Level (EAL):

Emergency Action Level (EAL): Emergency Action Level (EAL): Emergency Action Level (EAL):

Other conditions exist which, in the judgment of the Other conditions exist which in the judgment of the Other conditions exist which in the judgment of the Emergency Director, indicate that events are in progress or Other conditions exist which in the judgment of the Emergency Emergency Director indicate that events are in progress or Emergency Director indicate that events are in progress or have occurred which involve an actual or potential Director indicate that events are in progress or have occurred have occurred which involve actual or IMMINENT substantial have occurred which involve actual or likely major failures of substantial degradation of the level of safety of the plant or a which indicate a potential degradation of the level of safety of core degradation or melting with potential for loss of plant functions needed for protection of the public or HOSTILE security event that involves probable life threatening risk to the plant or indicate a security threat to facility protection has containment integrity or HOSTILE ACTION that results in an ACTION that results in intentional damage or malicious acts, site personnel or damage to site equipment because of been initiated. No releases of radioactive material requiring actual loss of physical control of the facility. Releases can be (1) toward site personnel or equipment that could lead to the HOSTILE ACTION. Any releases are expected to be limited offsite response or monitoring are expected unless further reasonably expected to exceed EPA Protective Action likely failure of or, (2) that prevent effective access to to small fractions of the EPA Protective Action Guideline degradation of safety systems occurs.

Guideline exposure levels offsite for more than the immediate equipment needed for the protection of the public. Any exposure levels.

site area. releases are not expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels Emergency Director Judgment beyond the site boundary.

Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled Month 20XX COLD SHUTDOWN/REFUELING MATRIX JAF 2-26 COLD SHUTDOWN/REFUELING MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT ISFSI Malfunction 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 Overpack Overpack Overpack Serial Average Serial Average Surface Number Surface Dose Number Dose Rates Rates mrem/hr mrem/hr (gamma+neutron) HI- (gamma+neutron)

STORM 100S (XXX)

HI- 80 on the side S/N - 220 on the side STORM 0186, 100S 20 on the top 0187, 40 on the top 32 at the inlet 0188 S/N - 15, and outlet ISFSI 16, 17 vent ducts S/N -

0307, 0308, 0309, 0310, 0311, HI- 100 on the side 0312, STORM 20 on the top 0679, 100S 600 on the side 0680, (232) 90 at the inlet 0681, 60 on the top S/N - and outlet 0682, 0169, vent ducts 0683, 0170, 0690, 0171 0691, 0692, 0693, 0694, 0695 Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled Month 20XX COLD SHUTDOWN/REFUELING MATRIX JAF 2-27 COLD SHUTDOWN/REFUELING MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Abnormal Rad Levels / Radiological Effluents RG1 1 2 3 4 5 D RS1 1 2 3 4 5 D RA1 1 2 3 4 5 D RU1 1 2 3 4 5 D Release of gaseous radioactivity resulting in offsite dose greater Release of gaseous radioactivity resulting in offsite dose greater Release of gaseous or liquid radioactivity resulting in offsite Release of gaseous or liquid radioactivity greater than 2 times than 1,000 mRem TEDE or 5,000 mRem thyroid CDE. than 100 mRem TEDE or 500 mRem thyroid CDE. dose greater than 10 mrem TEDE or 50 mrem thyroid CDE. the ODCM limits for 60 minutes or longer.

Emergency Action Level (EAL): Emergency Action Level (EAL): Emergency Action Level (EAL): Emergency Action Level (EAL):

Notes: Notes: Notes: Notes:

The Emergency Director should declare the event promptly

The Emergency Director should declare the event promptly

The Emergency Director should declare the event

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

If an ongoing release is detected and the release start time

If an ongoing release is detected and the release start time

If an ongoing release is detected and the release start

If an ongoing release is detected and the release start is unknown, assume that the release duration has is unknown, assume that the release duration has time is unknown, assume that the release duration has time is unknown, assume that the release duration has exceeded 15 minutes. exceeded 15 minutes. exceeded 15 minutes. exceeded 60 minutes.

Classification based on effluent monitor readings assumes

Classification based on effluent monitor readings assumes

Classification based on effluent monitor readings assumes

Classification based on effluent monitor readings assumes that a release path to the environment is established. If the that a release path to the environment is established. If the that a release path to the environment is established. If that a release path to the environment is established. If effluent flow past an effluent monitor is known to have effluent flow past an effluent monitor is known to have the effluent flow past an effluent monitor is known to have the effluent flow past an effluent monitor is known to have stopped due to actions to isolate the release path, then the stopped due to actions to isolate the release path, then the stopped due to actions to isolate the release path, then stopped due to actions to isolate the release path, then effluent monitor reading is no longer valid for classification effluent monitor reading is no longer valid for classification the effluent monitor reading is no longer valid for the effluent monitor reading is no longer valid for purposes. purposes. classification purposes. classification purposes.

Radiological Effluents

The pre-calculated effluent monitor values presented in

The pre-calculated effluent monitor values presented in

The pre-calculated effluent monitor values presented in EAL #1(Table R1) should be used for emergency EAL #1 (Table R1) should be used for emergency EAL #1 (Table R1) should be used for emergency classification assessments until the results from a dose classification assessments until the results from a dose classification assessments until the results from a dose 1. Reading on the Liquid Radwaste Effluent Monitor (17RM-assessment using actual meteorology are available. assessment using actual meteorology are available. assessment using actual meteorology are available. 350) > 2 times hi-hi trip for 60 minutes.

OR

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

1. Readings on ANY Table R1 Effluent Monitor > Table R1 value 1. Readings on ANY Table R1 Effluent Monitor > Table R1 value for > 15 minutes. 2. Readings on ANY Table R1 Effluent Monitor > Table R1 value for > 15 minutes. for > 15 minutes. for > 60 minutes.

OR OR OR 2. Dose assessment using actual meteorology indicates doses at OR

2. Dose assessment using actual meteorology indicates doses at or beyond the site boundary of EITHER:

2. Dose assessment using actual meteorology indicates doses at 3. Confirmed sample analyses for gaseous or liquid releases or beyond the site boundary of EITHER: a. > 10 mRem TEDE or beyond the site boundary of EITHER: indicate concentrations or release rates

a. > 1000 mRem TEDE OR

a. > 100 mRem TEDE > 2 times ODCM Limit with a release duration OR b. > 50 mRem CDE Thyroid of > 60 minutes.

b. > 5000 mRem CDE Thyroid OR OR OR b. > 500 mRem CDE Thyroid 3. Analysis of a liquid effluent sample indicates a concentration

3. Field survey results at or beyond the site boundary indicate or release rate that would result in doses greater than OR EITHER of the following at or beyond the site boundary.

EITHER:

a. Gamma (closed window) dose rates 3. Field survey results at or beyond the site boundary indicate a. 10 mRem TEDE for 60 minutes of exposure.

EITHER: OR

> 1000 mR/hr are expected to continue for > 60 minutes. b. 50 mRem CDE Thyroid for 60 minutes

a. Gamma (closed window) dose rates of exposure.

OR > 100 mR/hr are expected to continue for > 60 minutes. OR

b. Analyses of field survey samples indicate 4. Field survey results at or beyond the site boundary indicate

> 5000 mRem CDE Thyroid for 60 minutes OR EITHER:

of inhalation. a. Gamma (closed window) dose rates

b. Analyses of field survey samples indicate

> 500 mRem CDE Thyroid for 60 minutes > 10 mR/hr are expected to continue of inhalation. for > 60 minutes.

OR

b. Analyses of field survey samples indicate

> 50 mRem CDE Thyroid for 60 minutes of inhalation.

Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled Month 20XX HOT MATRIX JAF 2-1 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear 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)

Month 20XX HOT MATRIX JAF 2-2 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Abnormal Rad Levels / Radiological Effluents RG2 1 2 3 4 5 D RS2 1 2 3 4 5 D RA2 1 2 3 4 5 D RU2 1 2 3 4 5 D Spent fuel pool level cannot be restored to at least 1.00 foot Spent fuel pool level at 1.00 foot. Significant lowering of water level above, or damage to, UNPLANNED loss of water level above irradiated fuel.

for 60 minutes or longer. irradiated fuel.

Emergency Action Level (EAL): Emergency Action Level (EAL):

Emergency Action Levels (EAL): Emergency Action Level (EAL):

Lowering of spent fuel pool level to 1.00 foot as indicated

1. a. UNPLANNED water level drop in the REFUELING Note: The Emergency Director should declare the event on 19LI-60A or 19LI-60B.

PATHWAY as indicated by ANY of the following:

promptly upon determining that the applicable time 1. Uncovery of irradiated fuel in the REFUELING has been exceeded, or will likely be exceeded. PATHWAY.

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

OR Spent fuel pool level cannot be restored to at least OR 1.00 foot as indicated on19LI-60A or 19LI-60B 2. Damage to irradiated fuel resulting in a release of for > 60 minutes. radioactivity from the fuel as indicated by ANY

Indication or report of a drop in water level Table R2 Refuel Floor Radiation Monitors Table R2 Radiation Monitor Alarm. in the REFUELING PATHWAY.

OR AND

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

3. Lowering of spent fuel pool level to 11.00 feet as b. UNPLANNED Area Radiation Monitor reading rise

18RIA-051-14 New Fuel Vault (EPIC A-1231) indicated on 19LI-60A or 19LI-60B. on ANY Table R2 radiation monitor.

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

Radiological Effluents

17RIS-456A or B Refuel Floor Exhaust RA3 1 2 3 4 5 D RU3 1 2 3 Radiation levels that impede access to equipment necessary Reactor coolant activity greater than Technical for normal plant operations, cooldown or shutdown. Specification allowable limits.

Table R4 Areas with Entry Related Mode Applicability Emergency Action Level (EAL): Emergency Action Level (EAL):

Table R3 Areas Requiring Continuous Occupancy Entry Note: If the equipment in the room or area listed in Table Related R4 was already inoperable, or out of service, before

Main Control Room - (by survey) Area 1 Offgas radiation > hi-hi alarm Mode the event occurred, then no emergency classification

Central Alarm Station - (by survey) Applicability is warranted. OR

Secondary Alarm Station - (by survey) 1. Dose rate > 15 mR/hr in ANY of the areas in Table R3. 2. Specific coolant activity > 2.0 µCi/gm I-131 dose

Reactor Building East Crescent equivalent.

OR

Reactor Building West Crescent

Reactor Building 272 Elevation 2. UNPLANNED event results in radiation levels that Mode 3, 4, prohibit or significantly impede access to ANY of the

Reactor Building 300 Elevation and 5 areas in Table R4.

Relay Room

North Cable Room Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled Month 20XX HOT MATRIX JAF 2-3 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear 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 FC - Fuel Clad RC - Reactor Coolant System CT - Containment Sub-Category Loss Potential Loss Loss Potential Loss Loss Potential Loss Coolant activity > 300 uCi/gm I-131 dose None None

1. RCS Activity None None None equivalent.

2. RPV water level cannot be restored and 1. RPV water level cannot be restored and

1. SAOG entry required maintained > 0 inches (TAF). maintained > 0 inches (TAF). SAOG entry required

2. RPV Water Level None None OR OR

3. RPV water level cannot be determined. 2. RPV water level cannot be determined.

3. Primary Containment pressure > 56 psig and rising.

OR

1. a. Primary Containment pressure 1. UNPLANNED rapid drop in Primary

4. a. Primary Containment hydrogen

3. Primary > 2.7 psig. Containment pressure following Primary concentration > 6%.

Containment AND Containment pressure rise.

None None None AND Pressure / b. Primary Containment pressure rise is OR Conditions b. Primary Containment oxygen concentration due to RCS leakage. 2. Primary Containment pressure response not

> 5%.

consistent with LOCA conditions.

OR

5. Heat Capacity Temperature Limit (HCTL)

(EOP-11) exceeded.

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

1. UNISOLABLE Main Steam Line (MSL),

HPCI, RWCU, RCIC, or Feedwater line a. Secondary Containment area temperature break. > EOP-5 Maximum Normal Operating

4. RCS Leak Rate None None Limit. None None OR

2. Emergency RPV Depressurization is OR required. b. Secondary Containment area radiation

> EOP-5 Maximum Normal Operating Limit.

5. Primary Drywell radiation monitor reading Drywell radiation monitor reading Drywell radiation monitor reading Containment None None None

> 1.8E+03 R/hr (1800 R/hr). > 63 R/hr. > 1.8E+04 R/hr (18,000 R/hr).

Radiation

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.

6. Primary OR Containment None None None None None Isolation Failure 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.

7. Emergency 1. Any Condition in the opinion of the 2. Any Condition in the opinion of the 1. Any Condition in the opinion of the 2. Any Condition in the opinion of the 1. Any Condition in the opinion of the 2. Any Condition in the opinion of the Director Emergency Director that indicates Loss Emergency Director that indicates Emergency Director that indicates Loss of Emergency Director that indicates Potential Emergency Director that indicates Loss of the Emergency Director that indicates Potential Judgment of the Fuel Clad Barrier. Potential Loss of the Fuel Clad Barrier. the RCS Barrier. Loss of the RCS Barrier. Containment Barrier. Loss of the Containment Barrier.

Modes: 1 - Power Operation 2 - Startup 3 - Hot Shutdown 4 - Cold Shutdown 5 - Refueling D - Defueled Month 20XX HOT MATRIX JAF 2-4 HOT MATRIX EP-AA-1014 Addendum 3 (Rev.X)

James A. FitzPatrick Nuclear Power Plant Annex HOT MATRIX HOT MATRIX Exelon Nuclear GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT System Malfunction MG1 1 2 3 MS1 1 2 3 MA1 1 2 3 MU1 1 2 3 Prolonged loss of all offsite and all onsite AC power to Loss of all offsite and onsite AC power to emergency Loss of all but one AC power source to emergency buses for Loss of all offsite AC power capability to emergency buses emergency buses. buses for 15 minutes or longer. 15 minutes or longer. for 15 minutes or longer.

Emergency Action Level (EAL): Emergency Action Level (EAL): Emergency Action Level (EAL): Emergency Action Level (EAL):

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

Loss of AC Power

1. Loss of ALL offsite and onsite AC power to 4160 V

1. Loss of ALL offsite and onsite AC power to 4160 V 1. AC power capability to 4160 V emergency buses 10500 Loss of ALL offsite AC power capability 4160 V emergency emergency buses 10500 and 10600.

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

AND sources for > 15 minutes.

2. EITHER of the following: AND

Reserve Station Transformer T-2

Reserve Station Transformer T-2

a. Restoration of at least one 4160 V emergency bus

Reserve Station Transformer T-3

2. Failure to restore power to at least one 4160 V

Reserve Station Transformer T-3 10500 or 10600 in < 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months is not likely. emergency bus 10500 or 10600 in < 15 minutes from

Station Service Transformer T-4 (While

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

OR the time of loss of both offsite and onsite AC power. backfeeding from Main Transformer)

b. RPV water level cannot be restored and maintained

EDG A

> -19 inches (MSCRWL).

EDG B

EDG C

EDG D

Main Generator via T-4 AND