Text

2016-09-Written Handouts Package
	ML16280A449
Person / Time
Site:	River Bend
Issue date:	09/30/2016
From:	Vincent Gaddy; Operations Branch IV
To:	;
References
	Download: ML16280A449 (50)
	v • d • e

Handouts for the exam

InvertersOperating 3.8.7 RIVER BEND 3.8-35 Amendment No. 81 18

3.8 ELECTRICAL POWER SYSTEMS 3.8.7 InvertersOperating LCO 3.8.7 The Division I and Division II inverters shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS

NOTE-----------------------------------------------------------------

Enter applicable Conditions and Required Actions of LCO 3.8.9, "Distribution SystemsOperating," with any AC vital bus de-energized.

CONDITION REQUIRED ACTION COMPLETION TIME A.

Division I or II inverter inoperable.

A.1 Restore Division I and II inverters to OPERABLE status.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months B.

Required Action and associated Completion Time of Condition A not met.

B.1 ------------NOTE-------------

LCO 3.0.4.a is not applicable when entering MODE 3.

Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify correct inverter voltage, frequency, and alignment to required AC vital buses.

7 days

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Distribution SystemsOperating 3.8.9 RIVER BEND 3.8-39 Amendment No. 81 95 18

ACTION (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

One or more Division I or II DC electrical power distribution subsystems inoperable.

C.1 Restore Division I and II DC electrical power distribution subsystems to OPERABLE status.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months AND 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet LCO D.

Required Action and associated Completion Time of Condition A, B, or C not met.

D.1

NOTE-------------

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Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months E.

One or more Division III AC or DC electrical power distribution subsystems inoperable.

E.1 Declare High Pressure Core Spray System and Standby Service Water System pump 2C inoperable.

Immediately F.

Two or more divisions with inoperable distribution subsystems that result in a loss of function.

F.1 Enter LCO 3.0.3.

Immediately

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PAM Instrumentation 3.3.3.1 RIVER BEND 3.3-19 Amendment No. 81, 156 3.3 INSTRUMENTATION 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3.1 The PAM instrumentation for each Function in Table 3.3.3.1-1 shall be OPERABLE.

APPLICABILITY:

MODES 1 and 2.

ACTIONS

NOTE-----------------------------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more Functions with one required channel inoperable.

A.1 Restore required channel to OPERABLE status.

30 days B.

Required Action and associated Completion Time of Condition A not met.

B.1 Initiate action to prepare and submit a Special Report.

Immediately C.

One or more Functions with two required channels inoperable.

C.1 Restore one required channel to OPERABLE status.

7 days (continued)

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PAM Instrumentation 3.3.3.1 RIVER BEND 3.3-21 Amendment No. 81 142, 168 SURVEILLANCE REQUIREMENTS

NOTE-----------------------------------------------------------

These SRs apply to each Function in Table 3.3.3.1-1.

SURVEILLANCE FREQUENCY SR 3.3.3.1.1 Perform CHANNEL CHECK.

31 days SR 3.3.3.1.2 Deleted SR 3.3.3.1.3 Perform CHANNEL CALIBRATION.

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Table R1 EAL THRESHOLD Method GENERAL DRMS Threshold SITE AREA DRMS Threshold ALERT DRMS Threshold NOUE DRMS Threshold Main Plant Primary Secondary 4GE125 4.50E+08 Ci/sec N/A 4GE125 4.50E+07 Ci/sec N/A 4GE125 3.06E+07 Ci/sec 1GE126 2.82E-01 Ci/ml 4GE125 3.06E+05 Ci/sec 1GE126 5.26E-03 Ci/ml FB Vent Primary Secondary 4GE005 1.00E+09 Ci/sec N/A 4GE005 1.00E+08 Ci/sec N/A 4GE005 2.19E+06 Ci/sec 5GE005 2.82E-01 Ci/ml 4GE005 2.19E+04 Ci/sec 5GE005 4.65E-03 Ci/ml RW Vent Primary Secondary N/A N/A 4GE006 2.58E+06 Ci/sec 5GE006 6.84E-02 Ci/ml 4GE006 2.58E+04 Ci/sec 5GE006 6.84E-04 Ci/ml FISSION PRODUCT BARRIER OPERATING MODES:

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT NOUE FPB Loss / Potential Loss FG1 Loss of ANY two barriers AND loss or potential loss of third barrier Emergency Action Level(s):

1.

Loss of any two barriers AND Loss or potential loss of the third barrier FS1 Loss or potential loss of ANY two barriers Emergency Action Level(s):

1.

Loss or potential loss of any two barriers FA1 ANY loss or ANY potential loss of EITHER fuel clad or RCS Emergency Action Level(s):

1. Any loss or any potential loss of fuel clad OR Any loss or any potential loss of RCS FU1 ANY loss or ANY potential loss of containment Emergency Action Level(s):

1.

Any loss or any potential loss of containment FUEL CLAD (FC) Barrier REACTOR COOLANT SYSTEM (RC) Barrier PRIMARY CONTAINMENT (PC) Barrier Parameter Loss Potential Loss Parameter Loss Potential Loss Parameter Loss Potential Loss FC1 Primary coolant activity level Coolant activity

> 300 µCi/gm dose equivalent I131 None RC1 Drywell pressure Drywell pressure > 1.68 psid with indications of reactor coolant leak in drywell.

None PC1 Primary containment conditions

1. Rapid unexplained loss of PC pressure following initial pressure rise OR

2. PC pressure response not consistent with LOCA conditions

1. PC pressure > 15 psig and rising OR

2. a. PC hydrogen in the unsafe zone of HDOL curve OR

b. DW hydrogen concentration > 9%

OR

3. RPV pressure and suppression pool temperature cannot be maintained below the HCTL FC2 Reactor vessel water level RPV water level cannot be restored and maintained above

-187 inches RPV water level cannot be restored and maintained above -162 inches or cannot be determined RC2 Reactor vessel water level RPV water level cannot be restored and maintained above -162 inches or cannot be determined None PC2 Reactor vessel water level None Entry into PC flooding procedures SAP-1 and SAP-2 FC3 Primary containment radiation monitors Containment radiation monitor RMS-RE16 reading > 3,000 R/hr None RC3 RCS Leak Rate

1. UNISOLABLE main steam line break as indicated by the failure of both MSIVs in any one line to close AND High MSL flow annunciator (P601-19A-A2)

OR

2. Indication of an UNISOLABLE HPCS, feedwater, RWCU or RCIC break OR

3. Emergency RPV depressurization is required

1. RCS leakage > 50 gpm inside the drywell OR

2. UNISOLABLE RCS leakage outside PC as indicated by exceeding either of the following:

a. Max Normal Operating Temperature (Table F2)

OR

b. Max Normal Area Radiation (Table F2)

PC3 Primary containment isolation failure or bypass

1. a. Failure of both valves in any one line to close AND

b. Direct downstream pathway to the environment exists after PC isolation OR 2.

Intentional PC venting per EOPs or SAPs OR 3.

UNISOLABLE RCS leakage outside PC as indicated by exceeding either of the following:

a. Max Safe Operating Temperature (Table F1)

OR

b. Max Safe Area Radiation (Table F1)

None RC4 Drywell radiation Drywell radiation monitor RMS-RE20 reading > 100 R/hr due to reactor coolant leakage None PC4 Primary containment radiation monitors None Containment radiation monitor RMS-RE16 reading

> 10,000 R/hr FC4 Emergency Director judgment Any condition in the opinion of the Emergency Director that indicates loss of the Fuel Clad barrier Any condition in the opinion of the Emergency Director that indicates potential loss of the Fuel Clad barrier RC5 Emergency Director judgment Any condition in the opinion of the Emergency Director that indicates loss of the RCS barrier Any condition in the opinion of the Emergency Director that indicates potential loss of the RCS barrier PC5 Emergency Director judgment Any condition in the opinion of the Emergency Director that indicates loss of the Primary Containment barrier Any condition in the opinion of the Emergency Director that indicates potential loss of the Primary Containment barrier TABLE F1 PC 3 Loss of Primary Containment Parameter Area Temperature Max Safe Operating Value Area Radiation Level DRMS Grid 2 Max Safe Operating Value RHR A equip area 200º F 1213 9.5E+03 mR/hr RHR B equip area 200º F 1214 9.5E+03 mR/hr RHR C equip area N/A 1215 9.5E+03 mR/hr RCIC room 200º F 1219 9.5E+03 mR/hr MSL Tunnel 200º F N/A RWCU pump room 1 (A) / 2 (B) 200º F N/A TABLE F2 RC 3 Potential Loss of RCS Parameter Area Temperature (isolation temperature alarm)

Area Radiation Level DRMS Grid 2 Max Normal Operating Value RHR A equip area 117º F (P601-20A-B4) 1213 8.2E+01 mR/hr RHR B equip area 117º F (P601-20A-B4) 1214 8.2E+01 mR/hr RHR C equip area N/A 1215 8.2E+01 mR/hr RCIC room 182º F (P601-21A-B6) 1219 1.20E+02 mR/hr MSL Tunnel 173º F (P601-19A-A1/A3/B1/B3)

N/A RWCU pump room 1 (A) / 2 (B) 165º F (P680-1A-A2/B2)

N/A HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY OPERATING MODES:

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT NOUE SYSTEM MALFUNCTION OPERATING MODES:

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT NOUE Loss of AC Power SG1 Prolonged loss of all offsite and all onsite AC power to emergency busses Emergency Action Level(s):

1. a. Loss of all offsite and all onsite AC power to Div I, II and III ENS busses AND

b. Either of the following:

Restoration of at least one emergency bus in < 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months is not likely OR RPV level cannot be maintained

> -162 inches.

SS1 Loss of all offsite and all onsite AC power to emergency busses for > 15 minutes Emergency Action Level(s):

NOTE: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition has exceeded, or will likely exceed, the applicable time.

1.

Loss of all offsite power and all onsite AC power to Div I, II and III ENS busses for > 15 minutes SA1 AC power capability to emergency busses reduced to a single power source for > 15 minutes such that any additional single failure would result in station blackout Emergency Action Level(s):

NOTE: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition has exceeded, or will likely exceed, the applicable time.

1. a. AC power capability to Div I and Div II ENS busses reduced to a single power source for > 15 minutes AND

b. Any additional single failure will result in a station blackout SU1 Loss of all offsite AC power to emergency busses for > 15 minutes Emergency Action Level(s):

NOTE: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition has exceeded, or will likely exceed, the applicable time.

1.

Loss of all offsite AC power to Div I and II ENS busses for > 15 minutes Failure of Reactor Protection System SG3 Automatic scram and all manual actions fail to shutdown the reactor and indication of an extreme challenge to the ability to cool the core exists Emergency Action Level(s):

1.a.

An automatic scram failed to shutdown the reactor AND b.

All manual actions do not shutdown the reactor as indicated by reactor power > 5%

AND c.

Either of the following exist or have occurred due to continued power generation:

Core cooling is extremely challenged as indicated by RPV level cannot be restored and maintained > -187 inches OR Heat removal is extremely challenged as indicated by RPV pressure and Suppression Pool temperature cannot be maintained in the EOP Heat Capacity Temperature Limit (HCTL) Safe Zone SS3 Automatic scram fails to shutdown the reactor and the manual actions taken from the reactor control console are not successful in shutting down the reactor Emergency Action Level(s):

1.a. An automatic scram failed to shutdown the reactor AND

b. Manual actions taken at the reactor control console do not shutdown the reactor as indicated by reactor power > 5%

SA3 Automatic scram fails to shutdown the reactor and the manual actions taken from the reactor control console are successful in shutting down the reactor Emergency Action Level(s):

1. a. An automatic scram failed to shutdown the reactor AND

b. Manual actions taken at the reactor control console successfully shutdown the reactor as indicated by reactor power < 5%

Loss of DC Power SS4 Loss of all vital DC power for > 15 minutes Emergency Action Level(s):

NOTE: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition has exceeded, or will likely exceed, the applicable time.

1.

< 105 VDC on all vital DC busses > 15 minutes Loss of Annunciation / Indication SS6 Inability to monitor a SIGNIFICANT TRANSIENT in progress Emergency Action Level(s):

NOTE: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition has exceeded, or will likely exceed, the applicable time.

1. a. UNPLANNED loss of > approximately 75%

of the following for > 15 minutes:

Control Room safety system annunciation OR Control Room safety system indication AND

b. A SIGNIFICANT TRANSIENT is in progress AND

c. Compensatory indications are unavailable SA6 UNPLANNED loss of safety system annunciation or indication in the control room with either (1) a SIGNIFICANT TRANSIENT in progress, or (2) compensatory non-alarming indicators are not available Emergency Action Level(s):

NOTE: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition has exceeded, or will likely exceed, the applicable time.

1. a. UNPLANNED loss of > approximately 75%

of the following for > 15 minutes:

Control Room safety system annunciation OR Control Room safety system indication AND

b. Either of the following:

A SIGNIFICANT TRANSIENT is in progress OR Compensatory indications unavailable SU6 UNPLANNED loss of safety system annunciation or indication in the Control Room for > 15 minutes Emergency Action Level(s):

NOTE: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition has exceeded, or will likely exceed, the applicable time.

1.

UNPLANNED loss of > approximately 75%

of the following for > 15 minutes:

a. Control Room safety system annunciation OR

b. Control Room safety system indication RCS Leakage SU7 RCS leakage Emergency Action Level(s): (1 or 2)

NOTE: A relief valve that operates and fails to close per design should be considered applicable if the relief valve cannot be isolated.

1.

Unidentified or pressure boundary leakage > 10 gpm OR 2.

Identified leakage > 35 gpm Loss of Communication SU8 Loss of all onsite or offsite communication capabilities Emergency Action Level(s): (1 or 2) 1.

Loss of all of the following onsite communications methods affecting the ability to perform routine operations:

Plant radio system Plant paging system Sound powered phones In-plant telephones OR 2.

Loss of all of the following offsite communications methods affecting the ability to perform offsite notifications:

All telephones NRC phones State of Louisiana Radio Offsite notifications system and hotline Cladding Degradation SU9 Fuel clad degradation Emergency Action Level(s): (1 or 2) 1.

Offgas pre-treatment radiation monitor reading

> the Table S1 Dose Rate Limit for the actual indicated offgas flow indicating fuel clad degradation > T.S. allowable limits OR 2.

Reactor coolant sample activity value indicating fuel clad degradation > T.S. allowable limits

> 4.0 µCi/gm dose equivalent I-131 OR

> 0.2 µCi/gm dose equivalent I-131 for > 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Inadvertent Criticality SU10 Inadvertent criticality Emergency Action Level(s):

1.

UNPLANNED sustained positive period observed on nuclear instrumentation TECH SPEC Time Limit Exceeded SU11 Inability to reach required operating mode within Technical Specification limits Emergency Action Level(s):

1.

Plant is not brought to required operating mode within Technical Specifications LCO Action Statement time EVENTS RELATED TO ISFSI OPERATING MODES:

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT NOUE Cask Damage E-HU1 Damage to a loaded cask CONFINEMENT BOUNDARY Emergency Action Level(s):

1.

Damage to a loaded cask CONFINEMENT BOUNDARY 1

2 3

4 5

D 1

2 3

4 5

D 1

2 3

4 5

D Plant Modes (white boxes indicate applicable modes) 1 Power Operations 2

Startup 3

Hot Shutdown 4

Cold Shutdown 5

Refuel D

Defueled EMERGENCY CLASSIFICATION USER AID 1 MODES 1 - 3 ABNORMAL RADIATION LEVELS / RADIOLOGICAL EFFLUENT OPERATING MODES:

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT NOUE Radiological Effluents AG1 Offsite dose resulting from an actual or IMMINENT release of gaseous radioactivity > 1000 mR TEDE or 5000 mR thyroid CDE for the actual or projected duration of the release using actual meteorology Emergency Action Level: (1 or 2 or 3)

NOTE: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time. If dose assessment results are available, the classification should be based on EAL #2 instead of EAL #1. Do not delay declaration awaiting dose assessment results.

1.

VALID reading on any of the radiation monitors in Table R1 > the GENERAL EMERGENCY reading for > 15 minutes OR 2.

Dose assessment using actual meteorology indicates doses > 1000 mR TEDE or 5000 mR thyroid CDE at or beyond the SITE BOUNDARY OR 3.

Field survey results indicate closed window dose rates >

1000 mR/hr expected to continue for > 60 minutes; or analyses of field survey samples indicate thyroid CDE >

5000 mR for one hour of inhalation, at or beyond the SITE BOUNDARY AS1 Offsite dose resulting from an actual or IMMINENT release of gaseous radioactivity > 100 mR TEDE or 500 mR thyroid CDE for the actual or projected duration of the release Emergency Action Level(s) (1 or 2 or 3)

NOTE: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time. If dose assessment results are available, the classification should be based on EAL #2 instead of EAL #1. Do not delay declaration awaiting dose assessment results.

1.

VALID reading on any of the radiation monitors in Table R1 > the SITE AREA EMERGENCY reading for > 15 minutes OR 2.

Dose assessment using actual meteorology indicates doses

> 100 mR TEDE or 500 mR thyroid CDE at or beyond the SITE BOUNDARY OR 3.

Field survey results indicate closed window dose rates >

100 mR/hr expected to continue for > 60 minutes; or analyses of field survey samples indicate thyroid CDE >

500 mR for one hour of inhalation, at or beyond the SITE BOUNDARY AA1 Any release of gaseous or liquid radioactivity to the environment > 200 times the ODCM limit for > 15 minutes Emergency Action Level(s): (1 or 2 or 3)

NOTE: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the release duration has exceeded, or will likely exceed the applicable time. In the absence of data to the contrary, assume that the release duration has exceeded the applicable time if an ongoing release is detected and the release start time is unknown.

1.

VALID reading on any of the radiation monitors in Table R1 > the Alert reading for > 15 minutes OR 2.

For RMS-RE107 effluent monitor:

EITHER VALID reading > 200 times the alarm setpoint established by a current radioactivity discharge permit for > 15 minutes OR VALID reading > 1.27E-01 µCi/ml for > 15 minutes OR 3.

Confirmed sample analysis for gaseous or liquid releases indicate concentrations or release rates > 200 times the ODCM limit for > 15 minutes AU1 Any release of gaseous or liquid radioactivity to the environment > 2 times the ODCM limit for > 60 minutes Emergency Action Level(s): (1 or 2 or 3)

NOTE: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the release duration has exceeded, or will likely exceed the applicable time. In the absence of data to the contrary, assume that the release duration has exceeded the applicable time if an ongoing release is detected and the release start time is unknown.

1.

VALID reading on any of the radiation monitors in Table R1 > the NOUE reading for > 60 minutes OR 2.

VALID reading on RMS-RE107 effluent monitor > 2 times the alarm setpoint established by a current radioactivity discharge permit for > 60 minutes OR 3.

Confirmed sample analyses for gaseous or liquid releases indicate concentrations or release rates > 2 times the ODCM limit for > 60 minutes 1

2 3

4 5

D Abnormal Radiation Levels AA2 Damage to irradiated fuel or loss of water level that has resulted or will result in the uncovering of irradiated fuel outside the reactor vessel Emergency Action Level(s): (1 or 2) 1.

A water level drop in the reactor refueling cavity, spent fuel pool or fuel transfer canal that will result in irradiated fuel becoming uncovered OR 2.

A VALID reading on any of the following radiation monitors due to damage to irradiated fuel or loss of water level:

RMS-RE140 2000 mR/hr RMS-RE141 2000 mR/hr RMS-RE192 2000 mR/hr RMS-RE193 2000 mR/hr RMS-RE5A 1.64E+03 Ci/sec RMS-RE5B (GE) 5.29E-04 Ci/ml AU2 UNPLANNED rise in plant radiation levels Emergency Action Level(s): (1 or 2)

1. a. UNPLANNED water level drop in a reactor refueling pathway as indicated by any of the following:

Water level drop in the reactor refueling cavity, spent fuel pool, or fuel transfer canal indication on Control Room Panel 870 Personnel observation by visual or remote means.

AND

b. UNPLANNED VALID area radiation monitor alarm on any of the following:

RMS-RE140 RMS-RE141 RMS-RE192 RMS-RE193 OR 2.

UNPLANNED VALID area radiation monitor readings or survey results indicate a rise by a factor of 1000 over normal* levels NOTE: For area radiation monitors with ranges incapable of measuring 1000 times normal* levels, classification shall be based on VALID full scale indications unless surveys confirm that area radiation levels are below 1000 times normal* within 15 minutes of the area radiation monitor indications going full scale.

Normal can be considered the highest reading in the past 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months excluding the current peak value.

AA3 Rise in radiation levels within the facility that impedes operation of systems required to maintain plant safety functions Emergency Action Level: (s) 1.

Dose rate > 15 mR/hr in any of the following areas requiring continuous occupancy to maintain plant safety functions:

Main Control Room CAS 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D Control Room Evacuation HS3 Control room evacuation has been initiated and plant control cannot be established Emergency Action Level(s):

1. a. Control room evacuation has been initiated AND

b. Control of the plant cannot be established in accordance with AOP-0031, Shutdown from Outside the Main Control Room, within 15 minutes HA3 Control room evacuation has been initiated Emergency Action Level(s):

1.

AOP-0031, Shutdown from Outside the Main Control Room requires Control Room evacuation Fire HA4 FIRE or EXPLOSION affecting the operability of plant safety systems required to establish or maintain safe shutdown Emergency Action Level(s):

1.

FIRE or EXPLOSION resulting in VISIBLE DAMAGE to any of the structures or areas in Table H2 containing safety systems or components or Control Room indication of degraded performance of those safety systems HU4 FIRE within the PROTECTED AREA not extinguished within 15 minutes of detection or EXPLOSION within the PROTECTED AREA Emergency Action Level(s): (1 or 2)

NOTE: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the duration has exceeded, or will likely exceed, the applicable time.

1.

FIRE not extinguished within 15 minutes of Control Room notification or verification of a Control Room FIRE alarm in any Table H2 structure or area OR 2.

EXPLOSION within the PROTECTED AREA Toxic or Flammable Gasses HA5 Access to a VITAL AREA is prohibited due to toxic, corrosive, asphyxiant or flammable gases which jeopardize operation of operable equipment required to maintain safe operations or safely shutdown the reactor Emergency Action Level(s):

NOTE: If the equipment in the stated area was already inoperable, or out of service, before the event occurred, then this EAL should not be declared as it will have no adverse impact on the ability of the plant to safely operate or safely shutdown beyond that already allowed by Technical Specifications at the time of the event.

1.

Access to Main Control Room, Auxiliary Building, or 95 Control Building is prohibited due to toxic, corrosive, asphyxiant or flammable gases which jeopardize operation of systems required to maintain safe operations or safely shutdown the reactor HU5 Release of toxic, corrosive, asphyxiant or flammable gases deemed detrimental to NORMAL PLANT OPERATIONS Emergency Action Level(s) (1 or 2) 1.

Toxic, corrosive, asphyxiant or flammable gases in amounts that have or could adversely affect NORMAL PLANT OPERATIONS OR 2.

Report by West Feliciana Parish for evacuation or sheltering of site personnel based on an offsite event 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D Natural or Destructive Phenomena HA6 Natural or destructive phenomena affecting VITAL AREAS Emergency Action Level(s): (1 or 2 or 3 or 4 or 5 or 6) 1.a. Seismic event > Operating Basis Earthquake (OBE) as indicated by:

Annunciator Seismic Tape Recording System Start (P680-02A-D06)

AND Event Indicator on ERS-NBI-102 is white AND Receipt of EITHER 1 OR 2:

1.

Annunciator Seismic Event High (P680-02A-C06) 2.

Annunciator Seismic Event High-High (P680-02A-B06) AND amber light(s) on panel NBI-101 AND

b. Earthquake confirmedby any of the following:

Earthquake is felt in plant National Earthquake Center Control Room indication of degraded performance of systems required for safe shutdown of the plant OR 2.

Tornado striking resulting in VISIBLE DAMAGE to any of the Table H2 structures or areas containing safety systems or components or Control Room indication of degraded performance of those safety systems OR 3.

Internal flooding in Auxiliary Building 70 ft elevation resulting in an electrical shock hazard that precludes access to operate or monitor safety equipment or Control Room indication of degraded performance of those safety systems OR 4.

Turbine failure-generated PROJECTILES resulting in VISIBLE DAMAGE to or penetration of any of the Table H2 structures or areas containing safety systems or components or Control Room indication of degraded performance of those safety systems OR 5.

Vehicle crash resulting in VISIBLE DAMAGE to any of the Table H2 structures or areas containing safety systems or components or Control Room indication of degraded performance of those safety systems OR 6.

Hurricane or high SUSTAINED wind conditions > 74 mph within the PROTECTED AREA boundary and resulting in VISIBLE DAMAGE to any of the Table H2 structures or areas containing safety systems or components or Control Room indication of degraded performance of those safety systems HU6 Natural or destructive phenomena affecting the PROTECTED AREA Emergency Action Level(s):(1 or 2 or 3 or 4 or 5) 1.

Seismic event identified by any 2 of the following:

Seismic event confirmed by activated seismic switch as indicated by receipt of EITHER a OR b:

a.

Annunciator Seismic Tape Recording SYS Start (P680-02A-D06)

b. Event Indicator on ERS-NBI-102 is white Earthquake felt in plant National Earthquake Center OR 2.

Tornado striking within the PROTECTED AREA boundary OR 3.

Internal flooding that has the potential to affect safety related equipment required by Technical Specifications for the current operating mode in any Table H1 area OR

4. Turbine failure resulting in casing penetration or damage to turbine or generator seals OR

5. Severe weather or hurricane conditions with indication of SUSTAINED high winds > 74 mph within the PROTECTED AREA boundary 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D EIP-2-001 ATT 9 USER AID 1 Revision F 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D EIP-2-001 CLASSIFICATION USER AID ATTACHMENT 9 PAGE 1 of 2 EIP-2-001 REV - 26 PAGE 143 of 144 1 2 3 4 5 D 1

2 3

4 5

D 1 2 3 4 5 D Table H2 Structures Containing Functions or Systems Required for Safe Shutdown Reactor Building Standby Cooling Tower Auxiliary Building Diesel Generator Building Control Building Tunnels (B, D, E, F, G)

Fuel Building Table H1 Uncontrolled Flooding Threshold Area Water Level Affected Location /

Parameter Max Safe Operating Value / Indicator Aux Bldg Crescent Area 70 EL 6 inches above floor (must be verified locally)

HPCS Room 70EL 4 inches above floor (P870-51A-G4)

RHR A Room 70EL 4 inches above floor (P870-51A-G4)

RHR B Room 70EL 4 inches above floor (P870-51A-G4)

RHR C Room 70EL 4 inches above floor (P870-51A-G4)

LPCS Room 70EL 4 inches above floor (P870-51A-G4)

RCIC Room 70EL 4 inches above floor (P870-51A-G4)

Security HG1 HOSTILE ACTION resulting in loss of physical control of the facility Emergency Action Level(s): (1 or 2) 1.

A HOSTILE ACTION has occurred such that plant personnel are unable to operate equipment required to maintain safety functions OR 2.

A HOSTILE ACTION has caused failure of Spent Fuel Cooling Systems and IMMINENT fuel damage is likely for a freshly off-loaded reactor core in pool HS1 HOSTILE ACTION within the PROTECTED AREA Emergency Action Level(s):

1.

A HOSTILE ACTION is occurring or has occurred within the PROTECTED AREA as reported by the RBS security shift supervision HA1 HOSTILE ACTION within the OWNER CONTROLLED AREA or airborne attack threat Emergency Action Level(s): (1 or 2) 1.

A HOSTILE ACTION is occurring or has occurred within the OWNER CONTROLLED AREA as reported by the RBS security shift supervision OR 2.

A validated notification from NRC of an airliner attack threat within 30 minutes of the site HU1 Confirmed SECURITY CONDITION or threat which indicates a potential degradation in the level of safety of the plant Emergency Action Level(s):(1 or 2 or 3) 1.

A SECURITY CONDITION that does NOT involve a HOSTILE ACTION as reported by the RBS security shift supervision OR 2.

A credible site specific security threat notification OR 3.

A validated notification from NRC providing information of an aircraft threat Discretionary HG2 Other conditions exist which in the judgment of the Emergency Director warrant declaration of a General Emergency Emergency Action Level(s):

1.

Other conditions exist which in the judgment of the Emergency Director indicate that events are in progress or have occurred which involve actual or IMMINENT substantial core degradation or melting with potential for loss of containment integrity or HOSTILE ACTION that results in an actual loss of physical control of the facility. Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area HS2 Other conditions exist which in the judgment of the Emergency Director warrant declaration of a SITE AREA EMERGENCY Emergency Action Level(s):

1.

Other conditions exist which in the judgment of the Emergency Director indicate that events are in progress or have occurred which involve actual or likely major failures of plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts: (1) toward site personnel or equipment that could lead to the likely failure of or: (2) that prevent effective access to equipment needed for the protection of the public. Any releases are not expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels beyond the SITE BOUNDARY HA2 Other conditions exist which in the judgment of the Emergency Director warrant declaration of an ALERT Emergency Action Level(s):

1.

Other conditions exist which in the judgment of the Emergency Director indicate that events are in progress or have occurred which involve actual or likely 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 HU2 Other conditions exist which in the judgment of the Emergency Director warrant declaration of a NOUE Emergency Action Level(s):

1.

Other conditions exist which in the judgment of the Emergency Director indicate that events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated.

No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D Table S1 Flow (cfm)

Dose Rate (mR/hr)

<15 9000

>15-17 8000

>17-20 7000

>20-25 5000

>25-30 4000

>30-60 2000

>60-140 1000

>140-200 700

EVENTS RELATED TO ISFSI OPERATING MODES:

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT NOUE Confinement Boundary damage / loss E-HU1 Damage to a loaded cask CONFINEMENT BOUNDARY Emergency Action Level(s):

1.

Damage to a loaded cask CONFINEMENT BOUNDARY EMERGENCY CLASSIFICATION USER AID 2 MODES 4, 5, and Defueled COLD SHUTDOWN / REFUELING OPERATING MODES:

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT NOUE Loss of RCS/RPV Inventory CG1 Loss of RCS/RPV inventory affecting fuel clad integrity with containment challenged Emergency Action Level(s): (1 or 2)

1. a. RPV level < -162 inches (TAF) for > 30 minutes AND

b. Any containment challenge indication in Table C1 OR

2. a. RCS level cannot be monitored with core uncovery indicated by any of the following for > 30 minutes:

RMS-RE16 reading > 100 R/hr

Erratic source range monitor indication

Unexplained rise in floor or equipment sump level, Suppression Pool level, vessel make-up rate or observation of leakage or inventory loss AND

b. Any containment challenge indication in Table C1 CS1 Loss of RCS/RPV inventory affecting core decay heat removal capability Emergency Action Level(s): (1 or 2 or 3)

NOTE: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.

1.

With CONTAINMENT CLOSURE not established, UNPLANNED RPV level < -49 inches OR 2.

With CONTAINMENT CLOSURE established, RPV level < -162 inches (TAF)

OR 3.

RCS level cannot be monitoredfor >

30 minutes with a loss of RCS inventory as indicatedby any of the following:

RMS-RE16 reading > 100 R/hr Erratic Source Range Monitor indication Unexplainedrise in floor or equipment sump level, Suppression Pool level, vessel make-up rate or observation of leakage or inventoryloss CA1 Loss of RCS/RPV inventory Emergency Action Level(s): (1 or 2)

NOTE: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.

1.

UNPLANNED loss of RCS inventory as indicated by RPV level < -43 inches (Level 2)

OR 2.

RCS level cannot be monitored for > 15 minutes with a loss of RCS inventory as indicated by an unexplained rise in floor or equipment sump level, Suppression Pool level, vessel make-up rate or observation of leakage or inventory loss CU1 RCS leakage Emergency Action Level(s):

NOTE: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.

1.

RCS leakage results in the inability to maintain or restore RPV level > +9.7 inches (Level 3) for > 15 minutes Loss of RCS/RPV Inventory CU2 UNPLANNED loss of RCS/RPV inventory Emergency Action Level(s): (1 or 2)

NOTE: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.

1.

UNPLANNED RCS level drop as indicated by either of the following:

a. RCS water level drop below the RPV flange for > 15 minutes when the RCS level band is established above the RPV flange OR

b. RCS water level drop below the RPV level band for > 15 minutes when the RCS level band is established below the RPV flange OR 2.

RCS level cannot be monitored with a loss of RCS inventory as indicated by an unexplained rise in floor or equipment sump level, Suppression Pool level, vessel make-up rate or observation of leakage or inventory loss Loss of Decay Heat Removal CA3 Inability to maintain plant in cold shutdown Emergency Action Level(s): (1or 2) 1.

An UNPLANNED event results in RCS temperature > 200 °F > the specified duration in Table C2 OR 2.

An UNPLANNED event results in RCS pressure rise > 10 psig due to a loss of RCS cooling CU3 UNPLANNED loss of decay heat removal capability with irradiated fuel in the RPV Emergency Action Level(s): (1 or 2)

NOTE: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.

1.

An UNPLANNED event results in RCS temperature exceeding 200°F OR 2.

Loss of all RCS temperature and RCS/RPV level indication for > 15 minutes Loss of AC Power CA5 Loss of all offsite and all onsite AC power to emergency busses for > 15 minutes Emergency Action Level(s):

NOTE: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.

1.

Loss of all offsite and all onsite AC power to Div I and Div II ENS busses for > 15 minutes CU5 AC power capability to emergency busses reduced to a single power source for > 15 minutes such that any additional single failure would result in station blackout Emergency Action Level(s):

NOTE: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.

1. a. AC power capability to Div I and Div II ENS busses reduced to a single power source for > 15 minutes AND

b. Any additional single power source failure will result in station blackout Loss of DC Power CU6 Loss of required DC power for > 15 minutes Emergency Action Level(s):

NOTE: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time.

1.

< 105 VDC on required Vital DC busses for > 15 minutes Inadvertent Criticality CU7 Inadvertent criticality Emergency Action Level(s):

1.

UNPLANNED sustained positive period observed on nuclear instrumentation Loss of Communications CU8 Loss of all onsite or offsite communications capabilities Emergency Action Level(s): (1 or 2) 1.

Loss of all of the following onsite communication methods affecting the ability to perform routine operations:

Plant radio system Plant paging system Sound powered phones In-plant telephones OR 2.

Loss of all of the following offsite communication methods affecting the ability to perform offsite notifications:

All telephones NRC phones State of Louisiana Radio Offsite notification system and hotline Table C1 Containment Challenge Indications CONTAINMENT CLOSURE not established Explosive mixture inside containment UNPLANNED rise in containment pressure Secondary containment area radiation monitor above EOP Max Safe OperatingValue below:

Area DRMS Grid 2 Max Safe Operating Value RHR Equip Rm A 1213 9.5E+03 mR/hr RHR Equip Rm B 1214 9.5E+03 mR/hr RHR Equip Rm C 1215 9.5E+03 mR/hr 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D ATTACHMENT 9 PAGE 2 of 2 EIP-2-001 CLASSIFICATION USER AID 1

2 3

4 5

D 1

2 3

4 5

D EIP-2-001 ATT 9 USER AID 2 Revision F Plant Modes (white boxes indicate applicable modes) 1 Power Operations 2

Startup 3

Hot Shutdown 4

Cold Shutdown 5

Refuel D

Defueled EIP-2-001 REV - 26 PAGE 144 of 144 Table C2 RCS Reheat Duration Thresholds RCS Containment Closure Duration Intact N/A 60 minutes*

Not intact Established 20 minutes*

Not Established 0 minutes

If and RCS heat removal system is in operation within this time frame and RCS temperature is being reduced, then the EAL is not applicable.

Table R1 EAL THRESHOLD Method GENERAL DRMS Threshold SITE AREA DRMS Threshold ALERT DRMS Threshold NOUE DRMS Threshold Main Plant Primary Secondary 4GE125 4.50E+08 Ci/sec N/A 4GE125 4.50E+07 Ci/sec N/A 4GE125 3.06E+07 Ci/sec 1GE126 2.82E-01 Ci/ml 4GE125 3.06E+05 Ci/sec 1GE126 5.26E-03 Ci/ml FB Vent Primary Secondary 4GE005 1.00E+09 Ci/sec N/A 4GE005 1.00E+08 Ci/sec N/A 4GE005 2.19E+06 Ci/sec 5GE005 2.82E-01 Ci/ml 4GE005 2.19E+04 Ci/sec 5GE005 4.65E-03 Ci/ml RW Vent Primary Secondary N/A N/A 4GE006 2.58E+06 Ci/sec 5GE006 6.84E-02 Ci/ml 4GE006 2.58E+04 Ci/sec 5GE006 6.84E-04 Ci/ml ABNORMAL RADIATION LEVELS / RADIOLOGICAL EFFLUENT OPERATING MODES:

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT NOUE Radiological Effluents AG1 Offsite dose resulting from an actual or IMMINENT release of gaseous radioactivity > 1000 mR TEDE or 5000 mR thyroid CDE for the actual or projected duration of the release using actual meteorology Emergency Action Level: (1 or 2 or 3)

NOTE: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time. If dose assessment results are available, the classification should be based on EAL #2 instead of EAL #1. Do not delay declaration awaiting dose assessment results.

1.

VALID reading on any of the radiation monitors in Table R1 > the GENERAL EMERGENCY reading for > 15 minutes OR 2.

Dose assessment using actual meteorology indicates doses > 1000 mR TEDE or 5000 mR thyroid CDE at or beyond the SITE BOUNDARY OR 3.

Field survey results indicate closed window dose rates >

1000 mR/hr expected to continue for > 60 minutes; or analyses of field survey samples indicate thyroid CDE >

5000 mR for one hour of inhalation, at or beyond the SITE BOUNDARY AS1 Offsite dose resulting from an actual or IMMINENT release of gaseous radioactivity > 100 mR TEDE or 500 mR thyroid CDE for the actual or projected duration of the release Emergency Action Level(s): (1 or 2 or 3)

NOTE: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the condition will likely exceed the applicable time. If dose assessment results are available, the classification should be based on EAL #2 instead of EAL #1. Do not delay declaration awaiting dose assessment results.

1.

VALID reading on any of the radiation monitors in Table R1 > the SITE AREA EMERGENCY reading for > 15 minutes OR 2.

Dose assessment using actual meteorology indicates doses

> 100 mR TEDE or 500 mR thyroid CDE at or beyond the SITE BOUNDARY OR 3.

Field survey results indicate closed window dose rates >

100 mR/hr expected to continue for > 60 minutes; or analyses of field survey samples indicate thyroid CDE >

500 mR for one hour of inhalation, at or beyond the SITE BOUNDARY AA1 Any release of gaseous or liquid radioactivity to the environment > 200 times the ODCM limit for > 15 minutes Emergency Action Level(s): (1 or 2 or 3)

NOTE: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the release duration has exceeded, or will likely exceed the applicable time. In the absence of data to the contrary, assume that the release duration has exceeded the applicable time if an ongoing release is detected and the release start time is unknown.

1.

VALID reading on any of the radiation monitors in Table R1 > the Alert reading for > 15 minutes OR 2.

For RMS-RE107 effluent monitor:

EITHER VALID reading > 200 times the alarm setpoint established by a current radioactivity discharge permit for > 15 minutes OR VALID reading > 1.27E-01 µCi/ml for > 15 minutes OR 3.

Confirmed sample analysis for gaseous or liquid releases indicate concentrations or release rates > 200 times the ODCM limit for > 15 minutes AU1 Any release of gaseous or liquid radioactivity to the environment > 2 times the ODCM limit for > 60 minutes Emergency Action Level(s): (1 or 2 or 3)

NOTE: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the release duration has exceeded, or will likely exceed the applicable time. In the absence of data to the contrary, assume that the release duration has exceeded the applicable time if an ongoing release is detected and the release start time is unknown.

1.

VALID reading on any of the radiation monitors in Table R1 > the NOUE reading for > 60 minutes OR 2.

VALID reading on RMS-RE107 effluent monitor > 2 times the alarm setpoint established by a current radioactivity discharge permit for > 60 minutes OR 3.

Confirmed sample analyses for gaseous or liquid releases indicate concentrations or release rates > 2 times the ODCM limit for > 60 minutes 1

2 3

4 5

D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D Abnormal Radiation Levels AA2 Damage to irradiated fuel or loss of water level that has resulted or will result in the uncovering of irradiated fuel outside the reactor vessel Emergency Action Level(s): (1 or 2) 1.

A water level drop in the reactor refueling cavity, spent fuel pool or fuel transfer canal that will result in irradiated fuel becoming uncovered OR 2.

A VALID reading on any of the following radiation monitors due to damage to irradiated fuel or loss of water level:

RMS-RE140 2000 mR/hr RMS-RE141 2000 mR/hr RMS-RE192 2000 mR/hr RMS-RE193 2000 mR/hr RMS-RE5A 1.64E+03 Ci/sec RMS-RE5B (GE) 5.29E-04 Ci/ml AU2 UNPLANNED rise in plant radiation levels Emergency Action Level(s): (1 or 2)

1. a. UNPLANNED water level drop in a reactor refueling pathway as indicated by any of the following:

Water level drop in the reactor refueling cavity, spent fuel pool, or fuel transfer canal indication on Control Room Panel 870 Personnel observation by visual or remote means.

AND

b. UNPLANNED VALID area radiation monitor alarm on any of the following:

RMS-RE140 RMS-RE141 RMS-RE192 RMS-RE193 OR 2.

UNPLANNED VALID area radiation monitor readings or survey results indicate a rise by a factor of 1000 over normal* levels NOTE: For area radiation monitors with ranges incapable of measuring 1000 times normal* levels, classification shall be based on VALID full scale indications unless surveys confirm that area radiation levels are below 1000 times normal* within 15 minutes of the area radiation monitor indications going full scale.

Normal can be considered the highest reading in the past 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months excluding the current peak value.

AA3 Rise in radiation levels within the facility that impedes operation of systems required to maintain plant safety functions Emergency Action Level: (s) 1.

Dose rate > 15 mR/hr in any of the following areas requiring continuous occupancy to maintain plant safety functions:

Main Control Room CAS 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY OPERATING MODES:

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT NOUE 1

2 3

4 5

D Security HG1 HOSTILE ACTION resulting in loss of physical control of the facility Emergency Action Level(s): (1 or 2) 1.

A HOSTILE ACTION has occurred such that plant personnel are unable to operate equipment required to maintain safety functions OR 2.

A HOSTILE ACTION has caused failure of Spent Fuel Cooling Systems and IMMINENT fuel damage is likely for a freshly off-loaded reactor core in pool HS1 HOSTILE ACTION within the PROTECTED AREA Emergency Action Level(s):

1.

A HOSTILE ACTION is occurring or has occurred within the PROTECTED AREA as reported by the RBS security shift supervision HA1 HOSTILE ACTION within the OWNER CONTROLLED AREA or airborne attack threat Emergency Action Level(s): (1 or 2) 1.

A HOSTILE ACTION is occurring or has occurred within the OWNER CONTROLLED AREA as reported by the RBS security shift supervision OR 2.

A validated notification from NRC of an airliner attack threat within 30 minutes of the site HU1 Confirmed SECURITY CONDITION or threat which indicates a potential degradation in the level of safety of the plant Emergency Action Level(s): (1 or 2 or 3) 1.

A SECURITY CONDITION that does not involve a HOSTILE ACTION as reported by the RBS security shift supervision OR 2.

A credible site specific security threat notification OR 3.

A validated notification from NRC providing information of an aircraft threat Discretionary HG2 Other conditions exist which in the judgment of the Emergency Director warrant declaration of a General Emergency Emergency Action Level(s):

1.

Other conditions exist which in the judgment of the Emergency Director indicate that events are in progress or have occurred which involve actual or IMMINENT substantial core degradation or melting with potential for loss of containment integrity or HOSTILE ACTION that results in an actual loss of physical control of the facility. Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area HS2 Other conditions exist which in the judgment of the Emergency Director warrant declaration of a SITE AREA EMERGENCY Emergency Action Level(s):

1.

Other conditions exist which in the judgment of the Emergency Director indicate that events are in progress or have occurred which involve actual or likely major failures of plant functions needed for protection of the public or HOSTILE ACTION that results in intentional damage or malicious acts: (1) toward site personnel or equipment that could lead to the likely failure of or: (2) that prevent effective access to equipment needed for the protection of the public. Any releases are not expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels beyond the SITE BOUNDARY HA2 Other conditions exist which in the judgment of the Emergency Director warrant declaration of an ALERT Emergency Action Level(s):

1.

Other conditions exist which in the judgment of the Emergency Director indicate that events are in progress or have occurred which involve actual or likely 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 HU2 Other conditions exist which in the judgment of the Emergency Director warrant declaration of a NOUE Emergency Action Level(s):

1.

Other conditions exist which in the judgment of the Emergency Director indicate that events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated.

No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs Control Room Evacuation HS3 Control room evacuation has been initiated and plant control cannot be established Emergency Action Level(s):

1. a. Control room evacuation has been initiated AND

b. Control of the plant cannot be established in accordance with AOP-0031, Shutdown from Outside the Main Control Room, within 15 minutes HA3 Control room evacuation has been initiated Emergency Action Level(s):

1.

AOP-0031, Shutdown from Outside the Main Control Room requires Control Room evacuation Fire HA4 FIRE or EXPLOSION affecting the operability of plant safety systems required to establish or maintain safe shutdown Emergency Action Level(s):

1.

FIRE or EXPLOSION resulting in VISIBLE DAMAGE to any of the structures or areas in Table H2 containing safety systems or components or Control Room indication of degraded performance of those safety systems HU4 FIRE within the PROTECTED AREA not extinguished within 15 minutes of detection or EXPLOSION within the PROTECTED AREA Emergency Action Level(s): (1 or 2)

NOTE: The Emergency Director should not wait until the applicable time has elapsed, but should declare the event as soon as it is determined that the duration has exceeded, or will likely exceed, the applicable time.

1.

FIRE not extinguished within 15 minutes of Control Room notification or verification of a Control Room FIRE alarm in any Table H2 structure or area OR 2.

EXPLOSION within the PROTECTED AREA Toxic or Flammable Gasses HA5 Access to a VITAL AREA is prohibited due to toxic, corrosive, asphyxiant or flammable gases which jeopardize operation of operable equipment required to maintain safe operations or safely shutdown the reactor Emergency Action Level(s):

NOTE: If the equipment in the stated area was already inoperable, or out of service, before the event occurred, then this EAL should not be declared as it will have no adverse impact on the ability of the plant to safely operate or safely shutdown beyond that already allowed by Technical Specifications at the time of the event.

1.

Access to Main Control Room, Auxiliary Building, or 95 Control Building is prohibited due to toxic, corrosive, asphyxiant or flammable gases which jeopardize operation of systems required to maintain safe operations or safely shutdown the reactor HU5 Release of toxic, corrosive, asphyxiant or flammable gases deemed detrimental to NORMAL PLANT OPERATIONS Emergency Action Level(s): (1 or 2) 1.

Toxic, corrosive, asphyxiant or flammable gases in amounts that have or could adversely affect NORMAL PLANT OPERATIONS OR 2.

Report by West Feliciana Parish for evacuation or sheltering of site personnel based on an offsite event Natural or Destructive Phenomena HA6 Natural or destructive phenomena affecting VITAL AREAS Emergency Action Level(s): (1 or 2 or 3 or 4 or 5 or 6) 1.a. Seismic event > Operating Basis Earthquake (OBE) as indicated by:

Annunciator Seismic Tape Recording System Start (P680-02A-D06)

AND Event Indicator on ERS-NBI-102 is white AND Receipt of EITHER 1 OR 2:

1. Annunciator Seismic Event High (P680-02A-C06)

2. Annunciator Seismic Event High-High (P680-02A-B06) AND amber light(s) on panel NBI-101 AND

b. Earthquake confirmedby any of the following:

Earthquake is felt in plant National Earthquake Center Control Room indication of degraded performance of systems required for safe shutdown of the plant OR 2.

Tornado striking resulting in VISIBLE DAMAGE to any of the Table H2 structures or areas containing safety systems or components or Control Room indication of degraded performance of those safety systems OR 3.

Internal flooding in Auxiliary Building 70 ft elevation resulting in an electrical shock hazard that precludes access to operate or monitor safety equipment or Control Room indication of degraded performance of those safety systems OR 4.

Turbine failure-generated PROJECTILES resulting in VISIBLE DAMAGE to or penetration of any of the Table H2 structures or areas containing safety systems or components or Control Room indication of degraded performance of those safety systems OR 5.

Vehicle crash resulting in VISIBLE DAMAGE to any of the Table H2 structures or areas containing safety systems or components or Control Room indication of degraded performance of those safety systems OR 6.

Hurricane or high SUSTAINED wind conditions > 74 mph within the PROTECTED AREA boundary and resulting in VISIBLE DAMAGE to any of the Table H2 structures or areas containing safety systems or components or Control Room indication of degraded performance of those safety systems HU6 Natural or destructive phenomena affecting the PROTECTED AREA Emergency Action Level(s):(1 or 2 or 3 or 4 or 5)

1. Seismic event identified by any 2 of the following:

Seismic event confirmed by activated seismic switch as indicated by receipt of EITHER a OR b:

a.

Annunciator Seismic Tape Recording SYS Start (P680-02A-D06) b.

Event Indicator on ERS-NBI-102 is white Earthquake felt in plant National Earthquake Center OR

2. Tornado striking within the PROTECTED AREA boundary OR

3. Internal flooding that has the potential to affect safety related equipment required by Technical Specifications for the current operating mode in any Table H1 area OR

4. Turbine failure resulting in casing penetration or damage to turbine or generator seals OR

5. Severe weather or hurricane conditions with indication of SUSTAINED high winds > 74 mph within the PROTECTED AREA boundary Table H2 Structures Containing Functions or Systems Required for Safe Shutdown Reactor Building Standby Cooling Tower Auxiliary Building Diesel Generator Building Control Building Tunnels (B, D, E, F, G)

Fuel Building 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D Table H1 Uncontrolled Flooding Threshold Area Water Level Affected Location /

Parameter Max Safe Operating Value / Indicator Aux Bldg Crescent Area 70 EL 6 inches above floor (must be verified locally)

HPCS Room 70EL 4 inches above floor (P870-51A-G4)

RHR A Room 70EL 4 inches above floor (P870-51A-G4)

RHR B Room 70EL 4 inches above floor (P870-51A-G4)

RHR C Room 70EL 4 inches above floor (P870-51A-G4)

LPCS Room 70EL 4 inches above floor (P870-51A-G4)

RCIC Room 70EL 4 inches above floor (P870-51A-G4)

ML16280A449

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