ML17164A151

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Enclosure 3E - Procedure Matrix for R.E. Ginna Nuclear Power Station
ML17164A151
Person / Time
Site: Ginna  Constellation icon.png
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:
References
NMP1L3158
Download: ML17164A151 (24)
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Text

Ginna Annex Exelon Nuclear Month XXXX GN 2-1 EP-AA-10XX (Rev X)

HOT MATRIX HOT MATRIX 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 Level (EAL):

Notes:

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

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

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monitor is known to have stopped due to actions to isolate the release path, then the effluent monitor reading is no longer valid for classification purposes.

The pre-calculated effluent monitor values presented in EAL

  1. 1 should be used for emergency classification assessments until the results from a dose assessment using actual meteorology are available.
1.

Reading on ANY Table R1 Effluent Monitor > Table R1 column GE value for > 15 minutes.

OR

2.

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

a.

> 1000 mRem TEDE OR

b.

> 5000 mRem Thyroid CDE 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 Thyroid CDE 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 Level (EAL):

Notes:

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

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

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monitor is known to have stopped due to actions to isolate the release path, then the effluent monitor reading is no longer valid for classification purposes.

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

1.

Reading on ANY Table R1 Effluent Monitor > Table R1 column SAE value for > 15 minutes.

OR

2.

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

a. > 100 mRem TEDE OR
b. > 500 mRem Thyroid CDE 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 Thyroid CDE for 60 minutes of inhalation.

RA1 Release of gaseous or liquid 1 2 3 4 5 6 D radioactivity resulting in offsite dose greater than 10 mRem TEDE or 50 mRem thyroid CDE.

Emergency Action Level (EAL):

Notes:

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

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

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

The pre-calculated effluent monitor values presented in EAL

  1. 1 should be used for emergency classification assessments until the results from a dose assessment using actual meteorology are available.
1. Reading on ANY Table R1 Effluent Monitor > Table R1 column Alert value for > 15 minutes.

OR

2. Dose assessment using actual meteorology indicates doses at or beyond the site boundary of EITHER:
a. > 10 mRem TEDE OR
b. > 50 mRem Thyroid CDE 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 Thyroid CDE for 60 minutes of exposure OR
4. Field survey results at or beyond the site boundary indicate EITHER:
a. Gamma (closed window) dose rates > 10 mR/hr are expected to continue for > 60 minutes.

OR

b.
b. Analyses of field survey samples indicate

> 50 mRem Thyroid CDE 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 Level (EAL):

Notes:

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

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

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

1.

Reading on ANY of the following effluent monitors

> 2x the alarm set point established by a current radioactive release discharge permit for 60 minutes.

Liquid Radwaste Effluent Monitor (R-18) with no isolation.

Discharge Permit specified monitor OR

2.

Reading on ANY Table R1 effluent monitors > Table R1 column UE value 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 HOT MATRIX HOT MATRIX Table R1 Effluent Monitor Thresholds Monitor General Emergency (GE)

Site Area Emergency (SAE)

Alert Monitor Unusual Event (UE)

CNMT Vent Noble Gas High Range (R-12A) 2.56 E +01 µCi/cc 2.56 E +00 µCi/cc 2.56 E -01 µCi/cc CNMT Vent Noble Gas High Range (R-12A)

N/A Plant Vent Noble Gas High Range (R-14A) 1.41 E +02 µCi/cc 1.41 E +01 µCi/cc 1.41 E +00 µCi/cc Plant Vent Noble Gas High Range (R-14A) 3.63 E -01uCi/cc Air Ejector Noble Gas High Range (R-48) 2.17 E +03 µCi/cc 2.17 E +02 µCi/cc 2.17 E +01 µCi/cc Air Ejector and Gland Steam Exhaust Monitor (R-15) 2.29 E +06 cpm

Ginna Annex Exelon Nuclear Month XXXX GN 2-2 EP-AA-10XX (Rev X)

HOT MATRIX HOT MATRIX GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Abnormal Rad Levels / Radiological Effluents Radiological Effluents R

RG2 Spent fuel pool level cannot be 1 2 3 4 5 6 D restored to at least 251.67 ft. for 60 minutes or longer.

Emergency Action Level (EAL):

Note: The Emergency Director should declare the General Emergency 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 251.67 ft. as indicated on EITHER LI-310 or LI-311 for

> 60 minutes.

Table R2 Fuel Handling Radiation Monitors R-2 Containment (Mode 6 and D)

R-5 Spent Fuel Pool (All Modes)

RS2 Spent fuel pool level at 1 2 3 4 5 6 D 251.67 ft.

Emergency Action Level (EAL):

Lowering of spent fuel pool level to 251.67 ft. as indicated on EITHER LI-310 or LI-311.

Table R3 Areas Requiring Continuous Occupancy Main Control Room - R-1 Central Alarm Station - (by survey)

Table R4 Areas with Entry-Related Mode Applicability Area Entry-Related Mode Applicability Auxiliary Building Top Floor Mode 3, 4, and 5 Auxiliary Building Middle Level Auxiliary Building Basement RA2 Significant lowering of water 1 2 3 4 5 6 D level above, or damage to, irradiated fuel.

Emergency Action Level (EAL):

1. Uncovery of irradiated fuel in the REFUELING PATHWAY.

OR

2. Damage to irradiated fuel resulting in a release of radioactivity from the fuel as indicated by ANY Table R2 Radiation Monitor Alarm.

OR

3. Lowering of spent fuel pool level to 257.25 ft. as indicated on EITHER LI-310 or LI-311.

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

Emergency Action Level (EAL):

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

Refueling Cavity water level < 23 ft above the Reactor Flange OR Spent Fuel Pool water level < 23 ft.

(Equivalent to < 274.50 feet on EITHER LI-310 or LI-311) above the fuel OR Indication or report of a drop in water level in the REFUELING PATHWAY.

AND

b. UNPLANNED Area Radiation Monitor reading rise on ANY radiation monitors in Table 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 the rooms or areas 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 prevent or significantly impede access to ANY of the plant rooms or areas contained in Table R4.

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

Emergency Action Levels (EAL):

1. Letdown Monitor (R-9) reading > 4.8 R/hr OR
2. RCS specific activity > 60.0 Ci/gm Dose Equivalent I-131 OR
3. RCS specific activity > 650 µCi/gm Dose Equivalent Xe-133 Mode:

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

Ginna Annex Exelon Nuclear Month XXXX GN 2-3 EP-AA-10XX (Rev X)

HOT MATRIX HOT MATRIX Fission Product Barrier Matrix Hot Matrix GENERAL 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 barrier. 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 Orange Path conditions exist, F-0.2 Core Cooling
1. Automatic or manual SI actuation is required by EITHER of the following:
a. UNISOLABLE RCS leakage OR
b. Steam Generator tube RUPTURE.
2. RCS leak rate > 50 gpm with letdown isolated.

OR

3. Red path conditions exist, F-0.4 Integrity A leaking or RUPTURED SG > 50gpm is FAULTED outside of containment.

None

2. Inadequate Heat Removal
1. Red Path conditions exist, F-0.2 Core Cooling
2. Orange Path conditions exist., F-0.2 Core Cooling OR
3. Red Path conditions exist, F-0.3 Heat Sink None Red Path conditions exist, F-0.3 Heat Sink None Red Path conditions exist, F-0.2 Core Cooling AND Functional Restoration procedures not effective in < 15 minutes
3. Containment Radiation / RCS Activity
1. Containment radiation monitor R-29/

R-30 reading > 700 R/hr OR

2. Letdown Monitor reading (R-9)

> 24 R/hr with letdown in service OR

3. Coolant activity as sampled

> 300Ci/gm Dose Equivalent I-131.

None Containment radiation monitor R-29/R-30 reading > 10 R/hr None None Containment radiation monitor R-29/R-30 reading

> 7000 R/hr

4. Containment Integrity or Bypass None None None None
1. Containment isolation is required AND EITHER of the following:
a. UNPLANNED lowering in containment pressure or rise in radiation monitor readings outside of containment that in the Emergency Directors judgment indicate a loss of containment integrity.

OR

b. UNISOLABLE pathway from containment to the environment exists.

OR

2. Indication of RCS leakage outside of containment
3. Red path conditions exist, F-0.5 Containment.

OR

4. Hydrogen Concentration in Containment

> 4%.

OR

5. a. Containment pressure > 28 psig AND b.EITHER of the following conditions for

> 15 minutes:

< 2 CRFC units operating

< 1 CS pump 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.

HOT MATRIX HOT MATRIX

Ginna Annex Exelon Nuclear Month XXXX GN 2-4 EP-AA-10XX (Rev X)

HOT MATRIX HOT MATRIX 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 Level (EAL):

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

1. Loss of ALL offsite and ALL onsite AC power to 480V safeguards buses 14 and 16.

AND

2. EITHER of the following:
a. Restoration of 480V safeguards bus 14 or 16 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. Red Path conditions exist, F-0.2 Core Cooling.

MS1 Loss of all offsite and all onsite 1 2 3 4 AC power to emergency buses for 15 minutes or longer.

Emergency Action Level (EAL):

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

1. Loss of ALL offsite and ALL onsite AC power to 480V safeguards buses 14 and 16.

AND

2. Failure to restore power to 480V safeguards bus 14 or 16 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 Level (EAL):

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

1. AC power capability to 480V safeguards buses 14 and 16 reduced to only one of the following power sources for > 15 minutes.

Station Auxiliary Transformer 12A Station Auxiliary Transformer 12B Unit Auxiliary Transformer 11 backfeed Emergency Diesel Generator EDG 1A Emergency Diesel Generator EDG 1B AND

2. ANY additional single power source failure will result in a loss of ALL AC power to SAFETY SYSTEMS powered from 480V safeguards buses 14 and 16.

MU1 Loss of all offsite AC power 1 2 3 4 capability to emergency buses for 15 minutes or longer.

Emergency Action Level (EAL):

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

Loss of ALL of the following offsite AC power capability to 480V safeguards buses 14 and 16 for > 15 minutes.

Station Auxiliary Transformer 12A Station Auxiliary Transformer 12B Unit Auxiliary Transformer 11 backfeed 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 Level (EAL):

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

1. Loss of ALL offsite and ALL onsite AC power to 480V safeguards buses 14 and 16.

AND

2. Voltage is < 110.6 VDC on unit 125 VDC buses 1A and 1B.

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 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 < 110.6 VDC on unit 125 VDC buses 1A and 1B for > 15 minutes.

Mode:

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

Ginna Annex Exelon Nuclear Month XXXX GN 2-5 EP-AA-10XX (Rev X)

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

Emergency Action Level (EAL):

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

AND

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

> 5%.

AND

3. EITHER of the following conditions exist:
a. RED Path conditions exist, F-0.2 Core Cooling.

OR

b. RED Path conditions exist, F-0.3 Heat Sink.

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

Emergency Action Level (EAL):

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

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

AND

2. Manual actions taken at the reactor control console are not successful in shutting down the reactor as indicated by Reactor Power > 5%.

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

Emergency Action Level (EAL):

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

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

AND

b. Subsequent manual action taken at the reactor control console 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 manual action taken at the reactor control console is successful in shutting down the reactor as indicated by Reactor Power <5%.

OR

2. Subsequent 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 Core Exit Temperature Level in at least one Steam Generator 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 Level (EAL):

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

1. a. UNPLANNED event results in the inability to monitor ANY Table M1 parameter 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 Level (EAL):

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

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

> 15 minutes.

Mode:

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

Ginna Annex Exelon Nuclear Month XXXX GN 2-6 EP-AA-10XX (Rev X)

HOT MATRIX HOT MATRIX 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 Level (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 1 2 3 4 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

> 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 HOT MATRIX HOT MATRIX

Ginna Annex Exelon Nuclear Month XXXX GN 2-7 EP-AA-10XX (Rev X)

HOT MATRIX HOT MATRIX GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT System Malfunction Communications Table M3 - Communications Capability System Onsite Offsite NRC Radios/Walkie Talkies X

Plant Page System X

Direct Dial POTS Lines (Blue Phones)

System X

X X

Commercial Phone System X

X X

FTS 2001 telephone system (ENS,HPN)

X X

Control Room Hard Wired Satellite Phone X

X Control Room Emergency Cell Phone X

X RECS X

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

Emergency Action Level (EAL):

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

OR

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

OR

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

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

Emergency Action Level (EAL):

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

AND

b. ANY required penetration remains open

> 15 minutes after the actuation signal.

OR

2. a. Containment pressure > 28 psig.

AND

b. Either of the following conditions for

> 15 minutes:

< 2 CRFC units operating

< 1 CS pump operating Mode:

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

Ginna Annex Exelon Nuclear Month XXXX GN 2-8 EP-AA-10XX (Rev X)

HOT MATRIX HOT MATRIX 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 Level (EAL):

A notification from the Security Force that a HOSTILE 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 Level (EAL):

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

OR

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

HU1 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 Cooling (ability to cool the core)

RCS Heat Removal (ability to 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 Level (EAL):

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

1. A Control Room evacuation has resulted in plant control being transferred from the Control Room to alternate locations per AP-CR.1 or the ER-FIRE series.

AND

2. Control of ANY Table H1 key safety function is not reestablished in < 35 minutes.

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

A Control Room evacuation has resulted in plant control being transferred from the Control Room to alternate locations per AP-CR.1 or the ER-FIRE series.

Mode:

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

Ginna Annex Exelon Nuclear Month XXXX GN 2-9 EP-AA-10XX (Rev X)

HOT MATRIX HOT MATRIX GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Hazards and Other conditions Affecting Plant Safety Fire Table H2 - Vital Areas Reactor Containment Building Auxiliary Building Control Building Intermediate Building Emergency Diesel Buildings SAFW Building Screenhouse Cable Tunnel Battery Rooms HU3 FIRE potentially degrading the level 1 2 3 4 5 6 D of safety of the plant.

Emergency Action Level (EAL):

Note:

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

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

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

< 15 minutes of ANY of the following FIRE detection indications:

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

Receipt of multiple (more than 1) fire alarms or indications Field verification of a single fire alarm OR

2. a. Receipt of a single fire alarm in ANY Table H2 area (i.e., no other indications of a FIRE).

AND

b. The existence of a FIRE is not verified in < 30 minutes of alarm receipt.

OR

3. A FIRE within the plant PROTECTED AREA not extinguished in < 60 minutes of the initial report, alarm or indication.

OR

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

Mode:

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

Ginna Annex Exelon Nuclear Month XXXX GN 2-10 EP-AA-10XX (Rev X)

HOT MATRIX HOT MATRIX 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 Level (EAL):

Note: Potential escalation of the emergency classification level would be via IC CA2 or MA5 For emergency classification if EAL #2 first three bullets are 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. Control Room personnel feel an actual or potential seismic event.

AND

2. 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.

If the above bullets are 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.

Mode:

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

Ginna Annex Exelon Nuclear Month XXXX GN 2-11 EP-AA-10XX (Rev X)

HOT MATRIX HOT MATRIX 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 Auxiliary Building Top Floor Mode 3, 4 and 5 Auxiliary Building Middle Level Auxiliary Building Basement HA5 Gaseous release impeding access to 3 4 5 equipment necessary for normal plant operations, cooldown or shutdown.

Emergency Action Level (EAL):

Note: If the equipment in the listed room or area was already inoperable, or out of service before the event occurred then no emergency classification is warranted.

1. Release of a toxic, corrosive, asphyxiant or flammable gas in ANY Table H3 area.

AND

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

Hazardous Event HU6 Hazardous Event 1 2 3 4 5 6 D Emergency Action Level (EAL):

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

Potential 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. Lake Level > 252 ft.

OR

6. Screenhouse suction bay water level < 19 ft. or < 17.5 ft.

by manual measurement.

Mode:

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

Ginna Annex Exelon Nuclear Month XXXX GN 2-12 EP-AA-10XX (Rev X)

HOT MATRIX HOT MATRIX 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 Level (EAL):

Other conditions exist which in the judgment of the Emergency Director indicate that events are in progress or have occurred which involve actual or IMMINENT substantial core degradation or melting with potential for loss of containment integrity or HOSTILE ACTION that results in an actual loss of physical control of the facility. Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area.

HS7 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 Level (EAL):

Other conditions exist which in the judgment of the Emergency Director indicate that events are in progress or have occurred which involve actual or likely major failures of plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts, (1) toward site personnel or equipment that could lead to the likely failure of or, (2) that prevent effective access to equipment needed for the protection of the public. Any releases are not expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels beyond the site boundary.

HA7 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 Level (EAL):

Other conditions exist which, in the judgment of the Emergency Director, indicate that events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of HOSTILE ACTION. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.

HU7 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 Level (EAL):

Other conditions exist which in the judgment of the Emergency Director indicate that events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.

Mode:

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

Ginna Annex Exelon Nuclear Month XXXX GN 2-13 EP-AA-10XX (Rev X)

HOT MATRIX HOT MATRIX GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT ISFSI Malfunction ISFSI E-HU1 Damage to a loaded cask 1 2 3 4 5 6 D CONFINEMENT BOUNDARY.

Emergency Action Level (EAL):

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

> 1600 mRem/hr on the Horizontal Storage Module (HSM) front surface OR

> 400 mRem/hr on the Horizontal Storage Module (HSM) door centerline OR

> 16 mRem/hr on the end shield wall exterior Mode:

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

Ginna Annex Exelon Nuclear Month XXXX GN 2-14 EP-AA-10XX (Rev X)

COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX 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 Level (EAL):

Notes:

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

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

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

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

1.

Reading on ANY Table R1 Effluent Monitor > Table R1 column GE value for > 15 minutes.

OR

2.

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

a.

> 1000 mRem TEDE OR

b.

> 5000 mRem Thyroid CDE 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 Thyroid CDE 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 Level (EAL):

Notes:

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

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

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

The pre-calculated effluent monitor values presented in EAL

  1. 1 should be used for emergency classification assessments until the results from a dose assessment using actual meteorology are available.
1.

Reading on ANY Table R1 Effluent Monitor > Table R1 column SAE value for > 15 minutes.

OR

2.

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

a. > 100 mRem TEDE OR
b. > 500 mRem Thyroid CDE 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 Thyroid CDE for 60 minutes of inhalation.

RA1 Release of gaseous or liquid 1 2 3 4 5 6 D radioactivity resulting in offsite dose greater than 10 mRem TEDE or 50 mRem thyroid CDE.

Emergency Action Level (EAL):

Notes:

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

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

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

The pre-calculated effluent monitor values presented in EAL

  1. 1 should be used for emergency classification assessments until the results from a dose assessment using actual meteorology are available.
1. Reading on ANY Table R1 Effluent Monitor > Table R1 column Alert value for > 15 minutes.

OR

2. Dose assessment using actual meteorology indicates doses at or beyond the site boundary of EITHER:
a. >10mRem TEDE OR b.> 50 mRem Thyroid CDE 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 Thyroid CDE for 60 minutes of exposure OR
4. Field survey results at or beyond the site boundary indicate EITHER:
a. Gamma (closed window) dose rates > 10 mR/hr are expected to continue for > 60 minutes.

OR

b.
b. Analyses of field survey samples indicate

> 50 mRem Thyroid CDE 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 Level (EAL):

Notes:

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

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

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

1.

Reading on ANY of the following effluent monitors

> 2 x the alarm set point established by a current radioactive release discharge permit for 60 minutes.

Liquid Radwaste Effluent Monitor (R-18) with no isolation Discharge Permit specified monitor OR

2.

Reading on ANY Table R1 effluent monitors > Table R1 column UE value 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 COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Table R1 Effluent Monitor Thresholds Monitor General Emergency (GE)

Site Area Emergency (SAE)

Alert Monitor Unusual Event (UE)

CNMT Vent Noble Gas High Range (R-12A) 2.56 E +01µCi/cc 2.56 E +00µCi/cc 2.56 E -01µCi/cc CNMT Vent Noble Gas High Range (R-12A)

N/A Plant Vent Noble Gas High Range (R-14A) 1.41 E +02µCi/cc 1.41 E +01µCi/cc 1.41 E +00µCi/cc Plant Vent Noble Gas High Range (R-14A) 3.63 E -01uCi/cc Air Ejector Noble Gas High Range (R-48) 2.17 E +03µCi/cc 2.17 E +02µCi/cc 2.17 E +01µCi/cc Air Ejector and Gland Steam Exhaust Monitor (R-15) 2.29 E +06 cpm

Ginna Annex Exelon Nuclear Month XXXX GN 2-15 EP-AA-10XX (Rev X)

COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Abnormal Rad Levels / Radiological Effluents Radiological Effluents R

RG2 Spent fuel pool level cannot be 1 2 3 4 5 6 D restored to at least 251.67 ft. for 60 minutes or longer.

Emergency Action Level (EAL):

Note: The Emergency Director should declare the General Emergency 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 251.67 ft. as indicated on EITHER LI-310 or LI-311 for

> 60 minutes.

Table R2 Fuel Handling Radiation Monitors R-2 Containment (Mode 6 and D)

R-5 Spent Fuel Pool (All Modes)

RS2 Spent fuel pool level at 1 2 3 4 5 6 D 251.67 ft.

Emergency Action Level (EAL):

Lowering of spent fuel pool level to 251.67 ft. as indicated on EITHER LI-310 or LI-311.

Table R3 Areas Requiring Continuous Occupancy Main Control Room - R-1 Central Alarm Station - (by survey)

Table R4 Areas with Entry-Related Mode Applicability Area Entry-Related Mode Applicability Auxiliary Building Top Floor Mode 3, 4, and 5 Auxiliary Building Middle Level Auxiliary Building Basement RA2 Significant lowering of water 1 2 3 4 5 6 D level above, or damage to, irradiated fuel.

Emergency Action Level (EAL):

1. Uncovery of irradiated fuel in the REFUELING PATHWAY.

OR

2. Damage to irradiated fuel resulting in a release of radioactivity from the fuel as indicated by ANY Table R2 Radiation Monitor Alarm.

OR

3. Lowering of spent fuel pool level to 257.25 ft. as indicated on EITHER LI-310 or LI-311.

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

Emergency Action Level (EAL):

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

Refueling Cavity water level <23 ft above the Reactor Flange OR Spent Fuel Pool water level < 23 ft.

(Equivalent to < 274.50 feet on EITHER LI-310 or LI-311) above the fuel OR Indication or report of a drop in water level in the REFUELING PATHWAY.

AND

b. UNPLANNED Area Radiation Monitor reading rise on ANY radiation monitors in Table 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 Level (EAL):

Note: If the equipment in the l rooms or areas 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 prevent or significantly impede access to ANY of the plant rooms or areas contained in Table R4.

Mode:

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6 - Refueling D - Defueled COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX

Ginna Annex Exelon Nuclear Month XXXX GN 2-16 EP-AA-10XX (Rev X)

COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Mode:

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6 - Refueling D - Defueled COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX 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 buses for 15 minutes or longer.

Emergency Action Level (EAL):

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

1. Loss of ALL offsite and ALL onsite AC power to 480V safeguards buses 14 and 16.

AND

2. Failure to restore power to 480V safeguards bus 14 or 16 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 Level (EAL):

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

1. AC power capability to 480V safeguards buses 14 and 16 reduced to only one of the following power sources for > 15 minutes.

Station Auxiliary Transformer 12A Station Auxiliary Transformer 12B Unit Auxiliary Transformer 11 backfeed Emergency Diesel Generator EDG 1A Emergency Diesel Generator EDG 1B AND

2. Any additional single power source failure will result in a loss of ALL AC power to SAFETY SYSTEMS powered from 480V safeguards buses 14 and 16.

Safety System CA2 Hazardous event affecting a SAFETY 5 6 SYSTEM required for the current operating mode.

Emergency Action Level (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.

Ginna Annex Exelon Nuclear Month XXXX GN 2-17 EP-AA-10XX (Rev X)

COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Mode:

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6 - Refueling D - Defueled COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX 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 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 < 110.6 VDC on required unit 125 VDC buses 1A and 1B for > 15 minutes.

Communications Table C1 - Communications Capability System Onsite Offsite NRC Radios/Walkie Talkies X

Plant Page System X

Direct Dial POTS Lines (Blue Phones)

System X

X X

Commercial Phone System X

X X

FTS 2001 telephone system (ENS,HPN)

X X

Control Room Hard Wired Satellite Phone X

X Control Room Emergency Cell Phone X

X RECS X

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

Emergency Action Level (EAL):

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

OR

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

OR

3. Loss of ALL Table C1 NRC communications 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 the plant in cold 5 6 shutdown 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.

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

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

> Table C2 duration.

OR

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

CU5 UNPLANNED rise in RCS temperature 5 6 Emergency Action Level (EAL):

Note:

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

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

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

OR

2. Loss of the following for > 15 minutes.

ALL RCS temperature indications AND ALL RCS level indications

Ginna Annex Exelon Nuclear Month XXXX GN 2-18 EP-AA-10XX (Rev X)

COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX Mode:

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6 - Refueling D - Defueled COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX 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 Level (EAL):

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

1. a. 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 Source Range Neutron Monitor indication.

OR Containment Radiation R-29 or R-30

> 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 capability.

Emergency Action Level (EAL):

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

1. a. 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 Source Range Neutron Monitor indication.

OR Containment Radiation R-29 or R-30

> 3 R/hr.

CA6 Loss of Reactor Vessel / RCS inventory 5 6 Emergency Action Level (EAL):

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

1. Loss of Reactor Vessel / RCS inventory as indicated by RCS water level < 6 in. on Loop B indicator (LI432B) OR Loop A compensated indication (LI-432A corrected).

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 Level (EAL):

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

1. UNPLANNED loss of reactor coolant results in the inability to restore and maintain Reactor Vessel / RCS level to > procedurally established lower limit for

>15 minutes.

OR

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

AND

b. Loss of Reactor Vessel / RCS inventory per Table C3 indications Table C3 - Indications of RCS Leakage UNPLANNED Containment Sump A level rise*

UNPLANNED Containment Sump B level rise*

UNPLANNED Auxiliary Bldg. Sump/Tank level rise*

UNPLANNED RCDT 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 time limit, then declaration of a General Emergency is not required.

Ginna Annex Exelon Nuclear Month XXXX GN 2-19 EP-AA-10XX (Rev X)

COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX 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 Level (EAL):

A notification from the Security Force that a HOSTILE 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 Level (EAL):

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

OR

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

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

Emergency Action Level (EAL):

1. Notification of a credible security threat directed at the site as determined per SY-AA-101-132, Security Assessment and Response to Unusual Activities.

OR

2. A validated notification from the NRC providing information of an aircraft threat.

OR

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

Transfer of Plant Control Table H1 - Safety Functions Reactivity Control (ability to shut down the reactor and keep it shutdown)

Core Cooling (ability to cool the core)

RCS Heat Removal (ability to 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 Level (EAL):

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

1. A Control Room evacuation has resulted in plant control being transferred from the Control Room to alternate locations per AP-CR.1 or the ER-FIRE series.

AND

2. Control of ANY Table H1 key safety function is not reestablished in < 35 minutes.

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

A Control Room evacuation has resulted in plant control being transferred from the Control Room to alternate locations per AP-CR.1 or the ER-FIRE series.

Mode:

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6 - Refueling D - Defueled COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX

Ginna Annex Exelon Nuclear Month XXXX GN 2-20 EP-AA-10XX (Rev X)

COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Hazards and Other conditions Affecting Plant Safety Fire Table H2 - Vital Areas Reactor Containment Building Auxiliary Building Control Building Intermediate Building Emergency Diesel Buildings SAFW Building Screenhouse Cable Tunnel Battery Rooms HU3 FIRE potentially degrading the level 1 2 3 4 5 6 D of safety of the plant.

Emergency Action Level (EAL):

Note:

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

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

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

< 15 minutes of ANY of the following FIRE detection indications:

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

Receipt of multiple (more than 1) fire alarms or indications Field verification of a single fire alarm OR

2. a. Receipt of a single fire alarm in ANY Table H2 area (i.e., no other indications of a FIRE).

AND

b. The existence of a FIRE is not verified in < 30 minutes of alarm receipt.

OR

3. A FIRE within the plant PROTECTED AREA not extinguished in < 60 minutes of the initial report, alarm or indication.

OR

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

Mode:

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6 - Refueling D - Defueled COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX

Ginna Annex Exelon Nuclear Month XXXX GN 2-21 EP-AA-10XX (Rev X)

COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX 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 Level (EAL):

Note: Potential escalation of the emergency classification level would be via IC CA2 or MA5 For emergency classification if EAL #2 first three bullets are 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. Control Room personnel feel an actual or potential seismic event.

AND

2. 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.

If the above bullets are 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.

Mode:

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6 - Refueling D - Defueled COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX

Ginna Annex Exelon Nuclear Month XXXX GN 2-22 EP-AA-10XX (Rev X)

COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX 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 Auxiliary Building Top Floor Mode 3, 4 and 5 Auxiliary Building Middle Level Auxiliary Building Basement HA5 Gaseous release impeding access to 3 4 5 equipment necessary for normal plant operations, cooldown or shutdown.

Emergency Action Level (EAL):

Note: If the equipment in the listed room or area was already inoperable or out of service, before the event occurred then no emergency classification is warranted.

1. Release of a toxic, corrosive, asphyxiant or flammable gas in ANY Table H3 area.

AND

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

Hazardous Event HU6 Hazardous Event 1 2 3 4 5 6 D Emergency Action Level (EAL):

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

Potential 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. Lake level > 252 ft.

OR

6. Screenhouse Suction Bay water level < 19 ft. or < 17.5 ft.

by manual measurement.

Mode:

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6 - Refueling D - Defueled COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX

Ginna Annex Exelon Nuclear Month XXXX GN 2-23 EP-AA-10XX (Rev X)

COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX 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 Level (EAL):

Other conditions exist which in the judgment of the Emergency Director indicate that events are in progress or have occurred which involve actual or IMMINENT substantial core degradation or melting with potential for loss of containment integrity or HOSTILE ACTION that results in an actual loss of physical control of the facility. Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area.

HS7 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 Level (EAL):

Other conditions exist which in the judgment of the Emergency Director indicate that events are in progress or have occurred which involve actual or likely major failures of plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts, (1) toward site personnel or equipment that could lead to the likely failure of or, (2) that prevent effective access to equipment needed for the protection of the public. Any releases are not expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels beyond the site boundary.

HA7 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 Level (EAL):

Other conditions exist which, in the judgment of the Emergency Director, indicate that events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of HOSTILE ACTION. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.

HU7 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 Level (EAL):

Other conditions exist which in the judgment of the Emergency Director indicate that events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.

Mode:

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6 - Refueling D - Defueled COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX

Ginna Annex Exelon Nuclear Month XXXX GN 2-24 EP-AA-10XX (Rev X)

COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT ISFSI Malfunction ISFSI E-HU1 Damage to a loaded cask 1 2 3 4 5 6 D CONFINEMENT BOUNDARY.

Emergency Action Level (EAL):

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

> 1600 mRem/hr on the Horizontal Storage Module (HSM) front surface OR

> 400 mRem/hr on the Horizontal Storage Module (HSM) door centerline OR

> 16 mRem/hr on the end shield wall exterior Mode:

1 - Power Operations 2 - Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6 - Refueling D - Defueled COLD SHUTDOWN/REFUELING MATRIX COLD SHUTDOWN/REFUELING MATRIX

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