Text

Enclosure 2E - Procedure Matrix for Calvert Cliffs Nuclear Power Plant, Units 1 and 2
	ML17164A145
Person / Time
Site:	Calvert Cliffs
Issue date:	05/31/2017
From:	; Exelon Generation Co
To:	; Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
Shared Package
ML17164A149	List: ML17164A141; ML17164A142; ML17164A143; ML17164A145; ML17164A147; ML17164A148; ML17164A150; ML17164A151; ML17164A153; ML17164A154; ML17164A155; NMP1L3158, Enclosure 4E - Procedure Matrix for Nine Mile Point Nuclear Station, Unit 1;
References
	NMP1L3158
	Download: ML17164A145 (26)
	v • d • e

Calvert Cliffs Nuclear Power Plant HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX CC 2-1 HOT MATRIX EP-AA-1011 (Revision XX)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Abnormal Rad Levels / Radiological Effluents Radiological Effluents RG1 Release of gaseous radioactivity 1 2 3 4 5 6 D resulting in offsite dose greater than 1000 mRem TEDE or 5000 mRem thyroid CDE.

Emergency Action Levels (EAL) :

Notes:

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

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

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monitor is known to have stopped due to actions to isolate the release path, then the effluent monitor reading is no longer valid for classification purposes.

The pre-calculated effluent monitor values presented in EAL #1 should be used for emergency classification assessments until the results from a dose assessment using actual meteorology are available.

1. Reading on the sum of U1 and U2 WRNGM (RIC-5415)

Effluent Monitors > 1.94 E+09 µCi/sec 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 Release of gaseous radioactivity 1 2 3 4 5 6 D resulting in offsite dose greater than 100 mRem TEDE or 500 mRem thyroid CDE.

Emergency Action Levels (EAL) :

Notes:

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

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

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

The pre-calculated effluent monitor values presented in EAL #1 should be used for emergency classification assessments until the results from a dose assessment using actual meteorology are available.

1. Reading on the sum of U1 and U2 WRNGM (RIC-5415)

Effluent Monitors > 1.94 E+08 µCi/sec 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 Release of gaseous or liquid radioactivity 1 2 3 4 5 6 D resulting in offsite dose greater than 10 mRem TEDE or 50 mRem thyroid CDE.

Emergency Action Levels (EAL) :

Notes:

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

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

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

The pre-calculated effluent monitor values presented in EAL #1 should be used for emergency classification assessments until the results from a dose assessment using actual meteorology are available.

1. Reading on the sum of U1 and U2 WRNGM (RIC-5415)

Effluent Monitors > 1.94 E+07 µCi/sec 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

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 Release of gaseous or liquid 1 2 3 4 5 6 D radioactivity greater than 2 times the ODCM limit for 60 minutes or longer.

Emergency Action Levels (EAL) :

Notes:

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

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

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

1. Reading on ANY of the following effluent monitors > 2x the Adjustable / Maximum set point established by a current radioactive release discharge permit for 60 minutes.

Liquid Radwaste Effluent Monitor (0-RIC-2201)

S/G Blowdown Monitor (1/2-RIC-4095)

S/G Blowdown Tank Monitor (1/2-RIC-4014)

Gaseous Radwaste Processing System Monitor (0-RI-2191)

Wide Range Noble Gas Monitor (WRNGM)

(1/2-RIC-5415) (During WGDT release)

Main Vent Gas Monitor (1/2-RI-5415)

(During WGDT release)

Discharge Permit specified Monitor OR

2. Reading on the sum of U1 and U2 WRNGM (RIC-5415) Effluent Monitors > 5.09 E+05 µCi/sec for

> 60 minutes.

OR

3. Confirmed sample analyses for gaseous or liquid releases indicate concentrations or release rates

> 2 x ODCM Limit with a release duration of

> 60 minutes.

Mode:

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6-Refueling D - Defueled

Calvert Cliffs Nuclear Power Plant HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX CC 2-2 HOT MATRIX EP-AA-1011 (Revision XX)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Abnormal Rad Levels / Radiological Effluents Radiological Effluents RG2 Spent fuel pool level cannot be 1 2 3 4 5 6 D restored to at least 45.167 ft. 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 45.167 ft.

as indicated on EITHER 0-LI-2003 OR 0-LI-2003A for

> 60 minutes.

Table R2 Radiation Monitors RMS Area Monitored RI-5420 Fuel Handling Area Vent 0RIC-7023 Channel 4 SFP Area RM-320 EL-69 0RIC-7023 Channel 3 Spent Fuel Handling Machine RI-5316/A/B/C/D Unit1/2 CNTMT EL-69 RS2 Spent fuel pool level at 1 2 3 4 5 6 D 45.167 ft Emergency Action Level (EAL):

Lowering of spent fuel pool level to 45.167 ft. as indicated on EITHER 0-LI-2003 OR 0-LI-2003A.

Table R4 Areas with Entry Related Mode Applicability Area Entry Related Mode Applicability 45 West Electrical Penetration Rooms Modes 3, 4, and 5 69 Electrical Penetration Rooms Modes 3, 4, and 5 ECCS Pump Rooms Modes 3, 4, and 5 Charging Pump Rooms Modes 3, 4, and 5 Component Cooling Rooms Modes 3, 4, and 5 Table R3 Areas Requiring Continuous Occupancy Main Control Room (by survey)

Central Alarm Station (CAS) (by survey)

RA2 Significant lowering of water 1 2 3 4 5 6 D level above, or damage to, irradiated fuel.

Emergency Action Levels (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 50.167 ft. as indicated on EITHER 0-LI-2003 OR 0-LI-2003A.

RU2 UNPLANNED loss of water level 1 2 3 4 5 6 D above irradiated fuel.

Emergency Action Levels (EAL) :

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

Inability to restore and maintain SFP level >

Technical Specification limit (65 ft. 7 in)

Inability to restore and maintain RFP level >

Technical Specification limit (56 ft. 8.5 in)

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

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

RA3 Radiation levels that impede 1 2 3 4 5 6 D access to equipment necessary for normal plant operations, cooldown or shutdown.

Emergency Action Levels (EAL) :

Note: If the equipment in 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 contained in Table R3.

OR

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

RU3 Reactor coolant activity greater than 1 2 3 4 Technical Specification allowable limits.

Emergency Action Levels (EAL) :

1. Letdown monitor RY-202-1 high alarm (> 1E+06 cpm)

OR

2. Sample analysis indicates Coolant activity > ANY of the following:

Dose equivalent I-131 0.5 uCi/gm for 100 hrs.

continuous Dose equivalent I-131 acceptable region of T.S.

Fig. 3.4.15-1 Dose equivalent I-131 137.5 uCi/gm Gross activity 100/E-bar uCi/gm Mode:

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6-Refueling D - Defueled

Calvert Cliffs Nuclear Power Plant HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX CC 2-3 HOT MATRIX EP-AA-1011 (Revision XX)

Fission Product Barrier Matrix GNERAL EMERGENCY SITE AREA EMERGENCY ALERT FG1 Loss of ANY two barriers AND Loss or Potential Loss of the third barrier. 1 2 3 4 FS1 Loss or Potential Loss of ANY two barriers. 1 2 3 4 FA1 ANY Loss or ANY Potential Loss of either Fuel Clad or RCS 1 2 3 4 Sub-Category FC - Fuel Clad RC - Reactor Coolant System CT - Containment Loss Potential Loss Loss Potential Loss Loss Potential Loss

1. RCS or SG Tube Leakage None RVLMS indicates < 10 inch alarm

1. Automatic or manual ECCS (SIAS) actuation is required by EITHER of the following:

a. UNISOLABLE RCS leakage OR

b. SG tube RUPTURE.

2. RCS leak rate > 50 gpm with letdown isolated due to EITHER of the following:

a. UNISOLABLE RCS leakage OR

b. SG tube leakage.

OR

3. Uncontrolled RCS cooldown and to the left of Max Operating Pressure Curve (EOP, RCS Pressure Temperature Limits)

A leaking or RUPTURED S/G > 50 gpm is FAULTED outside containment.

None

2. Inadequate Heat Removal

1. Core Exit Thermocouple readings

> 1200°F

2. Core Exit Thermocouple readings

> 700°F OR

3. Once Through Core Cooling(OTCC) in effect.

None Once Through Core Cooling(OTCC) in effect.

None 1 a. Core Exit Thermocouple readings

> 1200°F AND

b. Restoration procedures not effective in < 15 minutes.

OR

2.

a. Core Exit Thermocouples > 700 ºF AND

b. RVLMS indicates < 10 inch alarm AND

c. Restoration procedures not effective in < 15 minutes.

3. Containment Radiation / RCS Activity

1. Containment radiation monitor (5317A/B) reading > 7,000 R/hr.

OR

2.

Coolant activity > 300 uCi/gm Dose Equivalent I-131 OR

3.

Post-accident sample dose rate

> 40mRem/hr. (1ft from sample)

None Containment radiation monitor (5317A/B) reading > 12 R/hr.

None None Containment radiation monitor (5317A/B) reading > 70,000 R/hr.

4. Containment Integrity or Bypass None None None

1. Containment isolation is required AND ANY of the following:

a. UNPLANNED lowering in containment pressure following initial pressure rise OR

b. Containment pressure or sump level response not consistent with LOCA conditions.

OR

c. UNISOLABLE pathway from containment to the environment exists.

OR

2. Indication of RCS leakage outside of containment.

3. Containment Pressure > 50 psig and rising.

OR

4. Hydrogen Concentration in Containment

> 4%.

OR

5. a. Containment pressure > 4.25 psig AND

b. Cannot meet containment design cooling by at least one of the following for > 15 minutes:

2 Containment Spray Pumps Operating OR 3 CACs Operating OR 1 Containment Spray Pump and 2 CACs Operating

5. 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.

Mode:

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6-Refueling D - Defueled

Calvert Cliffs Nuclear Power Plant HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX CC 2-4 HOT MATRIX EP-AA-1011 (Revision XX)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT System Malfunction Loss of AC Power MG1 Prolonged loss of all offsite 1 2 3 4 and all onsite AC power to emergency buses.

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.

1. Loss of ALL offsite and onsite AC power to 4kV vital buses 11(21) and 14(24).

AND

2. EITHER of the following:

a. Restoration of at least one 4kV vital bus in

< 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is not likely.

OR

b. Core exit thermocouples > 1200°F.

MS1 Loss of all offsite and all onsite 1 2 3 4 AC power to emergency busses for 15 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

1. Loss of ALL offsite and onsite AC power to 4kV vital buses 11(21) and 14(24).

AND

2. Failure to restore power to at least one 4kV vital bus in

< 15 minutes from the time of loss of both offsite and onsite AC power.

MA1 Loss of all but one AC power 1 2 3 4 source to emergency buses for 15 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

1. AC power capability to 4kV vital buses 11(21) and 14(24) reduced to only one of the following power sources for > 15 minutes.

500kV transmission line 5051*

500kV transmission line 5052*

500kV transmission line 5072*

SMECO line, if aligned Emergency Diesel Generator 1(2)A DG Emergency Diesel Generator 1(2)B DG Emergency Diesel Generator 0C DG, if aligned

A credited 500kV line must have an independent 13kV service transformer AND

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

MU1 Loss of all offsite AC power 1 2 3 4 capability to emergency buses for 15 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 Loss of ALL offsite AC power capability to 4kV vital buses 11(21) and 14(24) for > 15 minutes.

500kV transmission line 5051*

500kV transmission line 5052*

500kV transmission line 5072*

SMECO line, if aligned

A credited 500kV line must have an independent 13kV service transformer Mode:

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6-Refueling D - Defueled

Calvert Cliffs Nuclear Power Plant HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX CC 2-5 HOT MATRIX EP-AA-1011 (Revision XX)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT System Malfunction Loss of DC Power MG2 Loss of all AC and Vital DC 1 2 3 4 power sources for 15 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

1. Loss of ALL offsite and onsite AC power to 4kV vital buses 11(21) and 14(24).

AND

2. Voltage is < 105 VDC on 125 VDC buses 11, 12, 21, and

22.

AND

3. ALL AC and Vital DC power sources have been lost for

> 15 minutes.

MS2 Loss of all Vital DC power for 1 2 3 4 15 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 Voltage is < 105 VDC on 125 VDC busses 11, 12, 21, and 22 for > 15 minutes.

Mode:

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6-Refueling D - Defueled

Calvert Cliffs Nuclear Power Plant HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX CC 2-6 HOT MATRIX EP-AA-1011 (Revision XX)

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

Emergency Action Levels (EAL) :

1. Automatic or Manual Trip did not shutdown the reactor as indicated by Reactor Power > 5%.

AND

2. All DSS / manual actions to shutdown the reactor have been unsuccessful as indicated by Reactor Power > 5%.

AND

3. ANY of the following conditions exist:

a. Core exit thermocouples > 1200°F.

OR

b. Once Through Core Cooling(OTCC) in effect.

MA3 Automatic or manual trip fails to shutdown 1 2 the reactor, and subsequent manual actions taken at the reactor control consoles are not successful in shutting down the reactor.

Emergency Action Levels (EAL) :

Note: A manual action is any operator action, or set of actions, which causes the control rods to be rapidly inserted into the core, and does not include manually driving in control rods or implementation of boron injection strategies.

1. Automatic or manual Trip did not shutdown the reactor as indicated by Reactor Power > 5%.

AND

2. DSS / manual actions taken at the Console Center are not successful in shutting down the reactor as indicated by Reactor Power > 5%.

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

Emergency Action Levels (EAL) :

Note: A manual action is any operator action, or set of actions, which causes the control rods to be rapidly inserted into the core, and does not include manually driving in control rods or implementation of boron injection strategies.

1. a. Automatic Trip did not shutdown the reactor as indicated by Reactor Power > 5%.

AND

b. Subsequent DSS / manual action taken at the Console Center is successful in shutting down the reactor as indicated by Reactor Power <5%.

OR

2. a. Manual Trip did not shutdown the reactor as indicated by Reactor Power > 5%.

AND

b. EITHER of the following:

1. Subsequent DSS / manual action taken at the Console Center is successful in shutting down the reactor as indicated by Reactor Power <5%.

OR

2. Subsequent DSS / automatic Trip is successful in shutting down the reactor as indicated by Reactor Power <5%.

Control Room Indications Table M1 Control Room Parameters Reactor Power PZR Level RCS Pressure In Core/Core Exit Temperature Level in at least one Steam Generator.

Auxiliary Feed Water Flow Table M2 Significant Transients Automatic Turbine Runback >25% thermal reactor power Electrical Load Rejection >25% full electrical load Reactor Trip Safety Injection Actuation MA4 UNPLANNED loss of Control Room 1 2 3 4 indications for 15 minutes or longer with a significant transient in progress.

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

1. a UNPLANNED event results in the inability to monitor one or more Table M1 parameters from within the Control Room for > 15 minutes.

AND

b. ANY Table M2 transient in progress.

MU4 UNPLANNED loss of Control Room 1 2 3 4 indications for 15 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 UNPLANNED event results in the inability to monitor one or more Table M1 parameters from within the Control Room for

> 15 minutes.

Mode:

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6-Refueling D - Defueled

Calvert Cliffs Nuclear Power Plant HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX CC 2-7 HOT MATRIX EP-AA-1011 (Revision XX)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT System Malfunction Hazard affects Safety System MA5 Hazardous event affecting a 1 2 3 4 SAFETY SYSTEM required for the current operating mode.

Emergency Action Levels (EAL) :

Note: 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. EITHER of the following:

a. Event damage has caused indications of degraded performance in at least one train of a SAFETY SYSTEM required by Technical Specifications for the current operating mode.

OR

b. The event has caused VISIBLE DAMAGE to a SAFETY SYSTEM component or structure required by Technical Specifications for the current operating mode.

RCS Leak MU6 RCS leakage for 15 minutes or longer. 1 2 3 4 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

1. RCS unidentified or pressure boundary leakage

> 10 gpm for > 15 minutes OR

2. RCS identified leakage >25 gpm for > 15 minutes OR

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

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6-Refueling D - Defueled

Calvert Cliffs Nuclear Power Plant HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX CC 2-8 HOT MATRIX EP-AA-1011 (Revision XX)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT System Malfunction Communications Table M3 Communications Capability System Onsite Offsite NRC Plant Page System X

CCNPP Radio System X

X Commercial landline telephones X

X X

FTS 2001 telephone system (HPN, ENS)

X Satellite Phone System X

X MU7 Loss of all onsite or offsite communication 1 2 3 4 capabilities.

Emergency Action Levels (EAL) :

1. Loss of ALL Table M3 Onsite communications capability affecting the ability to perform routine operations.

OR

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

OR

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

Containment MU8 Failure to isolate containment or loss of 1 2 3 4 containment pressure control.

Emergency Action Levels (EAL) :

1. a. Failure of containment to isolate when required by an actuation signal.

AND

b. ANY required penetration remains open

> 15 minutes from the actuation signal.

OR

2. a. Containment pressure > 4.25 psig AND

b. Cannot meet containment design cooling by at least one of the following for > 15 minuets:

2 Containment Spray Pumps Operating 3 CACs Operating 1 Containment Spray Pump and 2 CACs Operating Mode:

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6-Refueling D - Defueled

Calvert Cliffs Nuclear Power Plant HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX CC 2-9 HOT MATRIX EP-AA-1011 (Revision XX)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Hazards and Other conditions Affecting Plant Safety Hostile Action HS1 HOSTILE ACTION within the 1 2 3 4 5 6 D PROTECTED AREA Emergency Action Levels (EAL) :

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

HA1 HOSTILE ACTION within the 1 2 3 4 5 6 D OWNER CONTROLLED AREA or airborne attack threat within 30 minutes.

Emergency Action Levels (EAL) :

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

OR

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

HU1 Confirmed SECURITY CONDITION 1 2 3 4 5 6 D or threat.

Emergency Action Levels (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 shut down the reactor and keep it shutdown)

Core and RCS Heat Removal (ability to cool the core and maintain heat sink)

HS2 Inability to control a key safety 1 2 3 4 5 6 D function from outside the Control Room 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.

1. A Control Room evacuation has resulted in plant control being transferred from the Control Room to alternate locations per:

AOP-9A Control Room Evacuation and Safe Shutdown Due to a Severe Control Room Fire OR AOP-11 Control Room Evacuation and Safe Shutdown - Non-Fire Conditions AND

2. Control of ANY Table H1 key safety function is not reestablished in < 15 minutes.

HA2 Control Room evacuation resulting 1 2 3 4 5 6 D in transfer of plant control to alternate locations Emergency Action Levels (EAL) :

A Control Room evacuation has resulted in plant control being transferred from the Control Room to alternate locations per:

AOP-9A Control Room Evacuation and Safe Shutdown Due to a Severe Control Room Fire OR AOP-11 Control Room Evacuation and Safe Shutdown - Non-Fire Conditions Mode:

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6-Refueling D - Defueled

Calvert Cliffs Nuclear Power Plant HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX CC 2-10 HOT MATRIX EP-AA-1011 (Revision XX)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Hazards and Other conditions Affecting Plant Safety Fire Table H2 Vital Areas Containment Building Auxiliary Building Diesel Generator Rooms Intake Structure 1A/0C DG Buildings RWT RWT Rooms CST N0.12 FOST No.21 Auxiliary Feed Pump Rooms HU3 FIRE potentially degrading the 1 2 3 4 5 6 D level of safety of the plant.

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.

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 or ISFSI PROTECTED AREA not extinguished in < 60-minutes of the initial report, alarm or indication.

OR

4. A FIRE within the plant PROTECTED AREA or ISFSI PROTECTED AREA that requires firefighting support by an offsite fire response agency to extinguish.

Mode:

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6-Refueling D - Defueled

Calvert Cliffs Nuclear Power Plant HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX CC 2-11 HOT MATRIX EP-AA-1011 (Revision XX)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Hazards and Other conditions Affecting Plant Safety Earthquake HU4 Seismic event greater than OBE 1 2 3 4 5 6 D levels Emergency Action Levels (EAL) :

Note: Escalation of the emergency classification level would be via IC CA2 or MA5 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 Shift Manager or Emergency Director in < 15 mins of the event.

1. Seismic Acceleration Recorded (0-YRC-001) Event Indicator indicates > Operating Basis Earthquake (OBE)

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 mins 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.

Mode:

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6-Refueling D - Defueled

Calvert Cliffs Nuclear Power Plant HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX CC 2-12 HOT MATRIX EP-AA-1011 (Revision XX)

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 45 West Electrical Penetration Rooms Modes 3, 4, and 5 69 Electrical Penetration Rooms Modes 3, 4, and 5 ECCS Pump Rooms Modes 3, 4, and 5 Charging Pump Rooms Modes 3, 4, and 5 Component Cooling Rooms Modes 3, 4, and 5 HA5 Gaseous release impeding access to 3 4 5 equipment necessary for normal plant operations, cooldown or shutdown.

Emergency Action Levels (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 Hazardous Event 1 2 3 4 5 6 D Emergency Action Levels (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. Abnormal Bay water level, as indicated by EITHER:

a. Bay water level > bottom of the traveling screen cover housing (+120 in. Mean Sea Level)

OR

b. Bay water level< 13.6 feet below intake concrete level (-43.2 in. Mean Sea Level)

Mode:

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6-Refueling D - Defueled

Calvert Cliffs Nuclear Power Plant HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX CC 2-13 HOT MATRIX EP-AA-1011 (Revision XX)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Hazards and Other conditions Affecting Plant Safety Emergency Director Judgment HG7 Other conditions exist which in the 1 2 3 4 5 6 D judgment of the Emergency Director warrant declaration of a General Emergency.

Emergency Action Levels (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 Other conditions exist which in the 1 2 3 4 5 6 D judgment of the Emergency Director warrant declaration of a Site Area Emergency.

Emergency Action Levels (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 Other conditions exist which in the 1 2 3 4 5 6 D judgment of the Emergency Director warrant declaration of an Alert.

Emergency Action Levels (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 Other conditions exist which in the 1 2 3 4 5 6 D judgment of the Emergency Director warrant declaration of an Unusual Event.

Emergency Action Levels (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.

Mode:

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6-Refueling D - Defueled

Calvert Cliffs Nuclear Power Plant HOT MATRIX HOT MATRIX Exelon Nuclear Month 20XX HOT MATRIX CC 2-14 HOT MATRIX EP-AA-1011 (Revision XX)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT ISFSI Malfunctions ISFSI E-HU1 Damage to a loaded cask 1 2 3 4 5 6 D CONFINEMENT BOUNDARY Emergency Action Levels (EAL) :

Damage to a loaded cask CONFINEMENT BOUNDARY as indicated by an on-contact radiation reading:

> 200 mr/hr on the Horizontal Storgage Module (HSM) access door OR

> 40 mr/hr on the Horizontal Storage Module (HMS) sides Mode:

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6-Refueling D - Defueled

Calvert Cliffs Nuclear Power Plant COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear Month 20XX COLD SHUTDOWN/REFUELING MATRIX CC 2-15 COLD SHUTDOWN/REFUELING MATRIX EP-AA-XXXX (Revision XX)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Abnormal Rad Levels / Radiological Effluents Radiological Effluents RG1 Release of gaseous radioactivity 1 2 3 4 5 6 D resulting in offsite dose greater than 1000 mRem TEDE or 5000 mRem thyroid CDE.

Emergency Action Levels (EAL) :

Notes:

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

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

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

The pre-calculated effluent monitor values presented in EAL #1 should be used for emergency classification assessments until the results from a dose assessment using actual meteorology are available.

1. Reading on the sum of U1 and U2 WRNGM (RIC-5415)

Effluent Monitors > 1.94 E+09 µCi/sec 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 Release of gaseous radioactivity 1 2 3 4 5 6 D resulting in offsite dose greater than 100 mRem TEDE or 500 mRem thyroid CDE.

Emergency Action Levels (EAL) :

Notes:

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

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

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

The pre-calculated effluent monitor values presented in EAL #1 should be used for emergency classification assessments until the results from a dose assessment using actual meteorology are available.

1.

Reading on the sum of U1 and U2 WRNGM (RIC-5415)

Effluent Monitors > 1.94 E+08 µCi/sec 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 Release of gaseous or liquid radioactivity 1 2 3 4 5 6 D resulting in offsite dose greater than 10 mRem TEDE or 50 mRem thyroid CDE.

Emergency Action Levels (EAL) :

Notes:

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

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

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

The pre-calculated effluent monitor values presented in EAL #1 should be used for emergency classification assessments until the results from a dose assessment using actual meteorology are available.

1. Reading on the sum of U1 and U2 WRNGM (RIC-5415)

Effluent Monitors > 1.94 E+07 µCi/sec 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

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 Release of gaseous or liquid 1 2 3 4 5 6 D radioactivity greater than 2 times the ODCM limits for 60 minutes or longer.

Emergency Action Levels (EAL) :

Notes:

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

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

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

1. Reading on ANY of the following effluent monitors >

2x the Adjustable / Maximum set point established by a current radioactive release discharge permit for 60 minutes.

Liquid Radwaste Effluent Monitor (0-RIC-2201)

S/G Blowdown Monitor (1/2-RIC-4095)

S/G Blowdown Tank Monitor (1/2-RIC-4014)

Gaseous Radwaste Processing System Monitor (0-RI-2191)

Wide Range Noble Gas Monitor (WRNGM) (1/2-RIC-5415) (During WGDT release)

Main Vent Gas Monitor (1/2-RI-5415) (During WGDT release)

Discharge Permit specified Monitor OR

2. Reading on the sum of U1 and U2 WRNGM (RIC-5415)

Effluent Monitors > 5.09 E+05 µCi/sec for

> 60 minutes.

OR

3. Confirmed sample analyses for gaseous or liquid releases indicate concentrations or release rates

> 2xODCM Limit with a release duration of

> 60 minutes.

Mode:

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6-Refueling D - Defueled

Calvert Cliffs Nuclear Power Plant COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear Month 20XX COLD SHUTDOWN/REFUELING MATRIX CC 2-16 COLD SHUTDOWN/REFUELING MATRIX EP-AA-XXXX (Revision XX)

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Abnormal Rad Levels / Radiological Effluents Radiological Effluents RG2 Spent fuel pool level cannot be 1 2 3 4 5 6 D restored to at least 45.167 ft. 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 45.167 ft as indicated on EITHER 0-LI-2003 OR 0-LI-2003A for

> 60 minutes.

Table R2 Radiation Monitors RMS Area Monitored RI-5420 Fuel Handling Area Vent 0RIC-7023 Channel 4 SFP Area RM-320 EL-69 0RIC-7023 Channel 3 Spent Fuel Handling Machine RI-5316/A/B/C/D Unit1/2 CNTMT EL-69 RS2 Spent fuel pool level at 1 2 3 4 5 6 D 45.167 ft.

Emergency Action Level (EAL):

Lowering of spent fuel pool level to 45.167 ft. as indicated on EITHER 0-LI-2003 OR 0-LI-2003A.

Table R4 Areas with Entry Related Mode Applicability Area Entry Related Mode Applicability 45 West Electrical Penetration Rooms Modes 3, 4, and 5 69 Electrical Penetration Rooms Modes 3, 4, and 5 ECCS Pump Rooms Modes 3, 4, and 5 Charging Pump Rooms Modes 3, 4, and 5 Component Cooling Rooms Modes 3, 4, and 5 Table R3 Areas Requiring Continuous Occupancy Main Control Room (by survey)

Central Alarm Station (CAS) (by survey)

RA2 Significant lowering of water 1 2 3 4 5 6 D level above, or damage to, irradiated fuel.

Emergency Action Levels (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 50.167 ft. as indicated on EITHER 0-LI-2003 OR 0-LI-2003A.

RU2 UNPLANNED loss of water level 1 2 3 4 5 6 D above irradiated fuel.

Emergency Action Levels (EAL) :

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

Inability to restore and maintain SFP level >

Technical Specification limit (65 ft 7 in)

Inability to restore and maintain RFP level >

Technical Specification limit (56 ft 8.5 in)

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

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

RA3 Radiation levels that impede 1 2 3 4 5 6 D access to equipment necessary for normal plant operations, cooldown or shutdown.

Emergency Action Levels (EAL) :

Note: If the equipment in 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 contained in Table R3.

OR

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

Mode:

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6-Refueling D - Defueled

Calvert Cliffs Nuclear Power Plant COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear Month 20XX COLD SHUTDOWN/REFUELING MATRIX CC 2-17 COLD SHUTDOWN/REFUELING MATRIX EP-AA-XXXX (Revision XX)

Mode:

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6-Refueling D - Defueled GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Cold Shutdown / Refueling System Malfunctions Loss of AC Power CA1 Loss of all offsite and all onsite AC power 5 6 D to emergency busses for 15 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.

1. Loss of ALL offsite and onsite AC power to 4kV vital buses 11(21) and 14(24).

AND

2. Failure to restore power to at least one 4kV vital bus in < 15 minutes from the time of loss of both offsite and onsite AC power.

CU1 Loss of all but one AC power source 5 6 D to emergency buses for 15 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.

1. AC power capability to 4kV vital buses 11(21) and 14(24) reduced to only one of the following power sources for > 15 minutes.

500kV transmission line 5051*

500kV transmission line 5052*

500kV transmission line 5072*

SMECO line, if aligned Emergency Diesel Generator 1(2)A DG Emergency Diesel Generator 1(2)B DG Emergency Diesel Generator 0C DG, if aligned

A credited 500kV line must have an independent 13kV service transformer AND

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

Calvert Cliffs Nuclear Power Plant COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear Month 20XX COLD SHUTDOWN/REFUELING MATRIX CC 2-18 COLD SHUTDOWN/REFUELING MATRIX EP-AA-XXXX (Revision XX)

Mode:

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6-Refueling D - Defueled GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Cold Shutdown / Refueling System Malfunctions Loss of AC Power CA2 Hazardous event affecting 5 6 SAFETY SYSTEM required for the current operating mode.

Emergency Action Levels (EAL) :

Note: 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. EITHER of the following:

a. Event damage has caused indications of degraded performance in at least one train of a SAFETY SYSTEM required by Technical Specifications for the current operating mode.

OR

b. The event has caused VISIBLE DAMAGE to a SAFETY SYSTEM component or structure required by Technical Specifications for the current operating mode.

Calvert Cliffs Nuclear Power Plant COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear Month 20XX COLD SHUTDOWN/REFUELING MATRIX CC 2-19 COLD SHUTDOWN/REFUELING MATRIX EP-AA-XXXX (Revision XX)

Mode:

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6-Refueling D - Defueled GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Cold Shutdown / Refueling System Malfunctions DC Power CU3 Loss of Vital DC power for 15 minutes 5 6 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 Voltage is < 105 VDC on required 125 VDC busses 11, 12, 21, and 22 for > 15 minutes.

Communications Table C1 Communications Capability System Onsite Offsite NRC Plant Page System X

CCNPP Radio System X

X Commercial landline telephones X

X X

FTS 2001 telephone system (HPN, ENS)

X Satellite Phone System X

X CU4 Loss of all onsite or offsite communication 5 6 D capabilities.

Emergency Action Levels (EAL) :

1. Loss of ALL Table C1 Onsite communications capability affecting the ability to perform routine operations.

OR

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

OR

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

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

Not Intact OR Reduced Inventory 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 Inability to maintain plant in cold shutdown 5 6 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 the heat removal function is available does not warrant a classification.

1. UNPLANNED rise in RCS temperature > 200ºF for >

Table C2 duration.

OR

2. UNPLANNED RCS pressure rise > 10 psig as a result of temperature rise. (This EAL does not apply in solid plant conditions.)

CU5 UNPLANNED rise in RCS temperature. 5 6 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 the heat removal function is available does not warrant a classification.

1. UNPLANNED rise in RCS temperature > 200ºF.

OR

2. Loss of the following for > 15 minutes.

ALL RCS temperature indications AND ALL reactor vessel/RCS level indications

Calvert Cliffs Nuclear Power Plant COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear Month 20XX COLD SHUTDOWN/REFUELING MATRIX CC 2-20 COLD SHUTDOWN/REFUELING MATRIX EP-AA-XXXX (Revision XX)

Mode:

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6-Refueling D - Defueled GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Cold Shutdown / Refueling System Malfunctions RCS Leakage / Inventory CG6 Loss of reactor vessel / RCS inventory 5 6 affecting fuel clad integrity with containment challenged.

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

1. a. RCS Level < 32.9 ft. (10 in. 8th alarm on RVLMS*) for

> 30 minutes.

This alarm is 10 in. above top of active fuel, use only when a valid RFP/RCS level indication is not available.

AND

b. ANY Containment Challenge Indication (Table C4)

OR

2. a. Reactor vessel / RCS level cannot be monitored for

> 30 minutes.

AND

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

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

OR Erratic WRNI indication.

OR Containment Radiation reading > 3 R/hr.

AND

c. ANY Containment Challenge Indication (Table C4)

CS6 Loss of reactor vessel / RCS inventory 5 6 affecting core decay heat removal capabilities.

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

1. With CONTAINMENT CLOSURE established RCS Level < 32.9 ft. (10 in. 8th alarm on RVLMS*)

This alarm is 10 in. above top of active fuel, use only when a valid RFP/RCS level indication is not available.

OR

2. With CONTAINMENT CLOSURE not established RCS Level < 34.7 ft. (19 in. 7th alarm on RVLMS)

OR

3.

a. Reactor vessel / RCS level cannot be monitored for >30 minutes.

AND

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

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

OR Erratic WRNI indication.

OR Containment Radiation reading > 3 R/hr.

CA6 Loss of reactor vessel / RCS inventory 5 6 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

1. Loss of reactor vessel / RCS inventory as indicated by RCS Level < 35.6 ft. (29 in. 6th alarm on RVLMS).

OR

2. a. Reactor vessel / RCS level cannot be monitored for > 15 minutes.

AND

b. Loss of reactor vessel / RCS inventory per Table C3 indications.

CU6 UNPLANNED loss of reactor vessel / RCS 5 6 inventory for 15 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

1. UNPLANNED loss of reactor coolant results in the inability to restore and maintain reactor vessel / RCS level to

> procedurally established lower limit for > 15 minutes.

OR

2. a. Reactor vessel / RCS level cannot be monitored.

AND

b. Loss of reactor vessel / RCS inventory per Table C3 indications.

Table C3 Indications of RCS Leakage UNPLANNED Containment Sump level rise*

UNPLANNED Auxiliary Bldg. Sump level rise*

UNPLANNED Miscellaneous Waste System Tank level rise*

UNPLANNED RWT level rise*

UNPLANNED RC Waste System Tank level rise*

UNPLANNED rise in RCS makeup Observation of leakage or inventory loss

Rise in level is attributed to a loss of reactor vessel/RCS inventory.

Table C4 Containment Challenge Indications Hydrogen Concentration in Containment > 4%

UNPLANNED rise in containment pressure CONTAINMENT CLOSURE not established*

If CONTAINMENT CLOSURE is re-established prior to exceeding the 30-minute core uncovery time limit, then escalation to a General Emergency is not required for this containment challenge.

Calvert Cliffs Nuclear Power Plant COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Exelon Nuclear Month 20XX COLD SHUTDOWN/REFUELING MATRIX CC 2-21 COLD SHUTDOWN/REFUELING MATRIX EP-AA-XXXX (Revision XX)