ML16280A449

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)

Text

Handouts for the exam

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

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

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

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

CONDITION REQUIRED ACTION COMPLETION TIME A. Division I or II inverter A.1 Restore Division I and II 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inoperable. inverters to OPERABLE status.

B. Required Action and B.1 ------------NOTE-------------

associated Completion LCO 3.0.4.a is not Time of Condition A not applicable when entering met. MODE 3.

Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify correct inverter voltage, frequency, and 7 days alignment to required AC vital buses.

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Distribution Systems Operating 3.8.9 ACTION (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more Division I or II C.1 Restore Division I and II 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> DC electrical power DC electrical power distribution subsystems distribution subsystems AND inoperable. to OPERABLE status.

16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> from discovery of failure to meet LCO D. Required Action and D.1 -----------NOTE-------------

associated Completion LCO 3.0.4.a is not Time of Condition A, B, applicable when or C not met. entering MODE 3.

Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> E. One or more Division III E.1 Declare High Pressure Immediately AC or DC electrical power Core Spray System and distribution subsystems Standby Service Water inoperable. System pump 2C inoperable.

F. Two or more divisions with F.1 Enter LCO 3.0.3. Immediately inoperable distribution subsystems that result in a loss of function.

RIVER BEND 3.8-39 Amendment No. 81 95 18

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PAM Instrumentation 3.3.3.1 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

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

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Restore required channel 30 days with one required channel to OPERABLE status.

inoperable.

B. Required Action and B.1 Initiate action to prepare Immediately associated Completion and submit a Special Time of Condition A not Report.

met.

C. One or more Functions C.1 Restore one required 7 days with two required channels channel to OPERABLE inoperable. status.

(continued)

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PAM Instrumentation 3.3.3.1 SURVEILLANCE REQUIREMENTS

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

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

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EIP-2-001 CLASSIFICATION USER AID ATTACHMENT 9 EMERGENCY CLASSIFICATION USER AID 1 MODES 1 - 3 Plant Modes (white boxes indicate applicable modes) 1 Power Operations 2 Startup 3 Hot Shutdown 4 Cold Shutdown 5 Refuel D Defueled PAGE 1 of 2 ABNORMAL RADIATION LEVELS / RADIOLOGICAL EFFLUENT OPERATING MODES: HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY OPERATING MODES: SYSTEM MALFUNCTION OPERATING MODES:

1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D GENERAL EMERGENCY SITE AREA EMERGENCY ALERT NOUE GENERAL EMERGENCY SITE AREA EMERGENCY ALERT NOUE GENERAL EMERGENCY SITE AREA EMERGENCY ALERT NOUE AG1 1 2 3 4 5 D AS1 1 2 3 4 5 D AA1 1 2 3 4 5 D AU1 1 2 3 4 5 D HG1 1 2 3 4 5 D HS1 1 2 3 4 5 D HA1 1 2 3 4 5 D HU1 1 2 3 4 5 D SG1 1 2 3 4 5 D SS1 1 2 3 4 5 D SA1 1 2 3 4 5 D SU1 1 2 3 4 5 D Offsite dose resulting from an actual or IMMINENT Offsite dose resulting from an actual or IMMINENT Any release of gaseous or liquid radioactivity to the Any release of gaseous or liquid radioactivity to the HOSTILE ACTION within the PROTECTED Confirmed SECURITY CONDITION or HOSTILE ACTION resulting in loss of HOSTILE ACTION within the OWNER release of gaseous radioactivity > 1000 mR TEDE or release of gaseous radioactivity > 100 mR TEDE or 500 environment > 200 times the ODCM limit for > 15 environment > 2 times the ODCM limit for > 60 minutes AREA threat which indicates a potential degradation Prolonged loss of all offsite and all onsite AC Loss of all offsite and all onsite AC power to AC power capability to emergency busses Loss of all offsite AC power to emergency physical control of the facility CONTROLLED AREA or airborne attack 5000 mR thyroid CDE for the actual or projected mR thyroid CDE for the actual or projected duration of minutes threat in the level of safety of the plant power to emergency busses emergency busses for > 15 minutes reduced to a single power source for > 15 busses for > 15 minutes Emergency Action Level(s): (1 or 2 or 3) duration of the release using actual meteorology the release Emergency Action Level(s): (1 or 2) minutes such that any additional single Emergency Action Level(s): (1 or 2 or 3) NOTE: The Emergency Director should not wait until the Emergency Action Level(s):

Emergency Action Level(s): (1 or 2) Emergency Action Level(s):(1 or 2 or 3) Emergency Action Level(s): Emergency Action Level(s): failure would result in station blackout Emergency Action Level(s):

Emergency Action Level: (1 or 2 or 3) 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 1. A HOSTILE ACTION has occurred such that 1. A HOSTILE ACTION is occurring or has 1. a. Loss of all offsite and all onsite AC power to NOTE: The Emergency Director should not wait NOTE: The Emergency Director should not wait NOTE: The Emergency Director should not wait until the NOTE: The Emergency Director should not wait until the applicable time has elapsed, but should declare the as soon as it is determined that the release duration has plant personnel are unable to operate 1. A HOSTILE ACTION is occurring or has 1. A SECURITY CONDITION that does NOT occurred within the PROTECTED AREA as Div I, II and III ENS busses until the applicable time has elapsed, but Emergency Action Level(s): until the applicable time has elapsed, but applicable time has elapsed, but should declare the event applicable time has elapsed, but should declare the event event as soon as it is determined that the release exceeded, or will likely exceed the applicable time. In the equipment required to maintain safety occurred within the OWNER CONTROLLED involve a HOSTILE ACTION as reported by reported by the RBS security shift AND should declare the event as soon as it is NOTE: The Emergency Director should not wait should declare the event as soon as it is as soon as it is determined that the condition will likely as soon as it is determined that the condition will likely duration has exceeded, or will likely exceed the absence of data to the contrary, assume that the release Security functions supervision AREA as reported by the RBS security shift the RBS security shift supervision

b. Either of the following: determined that the condition has exceeded, until the applicable time has elapsed, but determined that the condition has exceeded, or exceed the applicable time. If dose assessment results are exceed the applicable time. If dose assessment results are applicable time. In the absence of data to the duration has exceeded the applicable time if an ongoing OR supervision OR Restoration of at least one emergency bus or will likely exceed, the applicable time. should declare the event as soon as it is will likely exceed, the applicable time.

available, the classification should be based on EAL #2 available, the classification should be based on EAL #2 contrary, assume that the release duration has release is detected and the release start time is unknown. 2. A HOSTILE ACTION has caused failure of OR 2. A credible site specific security threat in < 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is not likely determined that the condition has exceeded, instead of EAL #1. Do not delay declaration awaiting instead of EAL #1. Do not delay declaration awaiting exceeded the applicable time if an ongoing release is notification Spent Fuel Cooling Systems and 2. A validated notification from NRC of an OR 1. Loss of all offsite power and all onsite AC or will likely exceed, the applicable time. 1. Loss of all offsite AC power to Div I and II dose assessment results. dose assessment results. detected and the release start time is unknown. 1. VALID reading on any of the radiation monitors in Table OR IMMINENT fuel damage is likely for a airliner attack threat within 30 minutes of the RPV level cannot be maintained power to Div I, II and III ENS busses for > 15 ENS busses for > 15 minutes Loss of AC Power R1 > the NOUE reading for > 60 minutes freshly off-loaded reactor core in pool site 3. A validated notification from NRC providing > -162 inches. minutes 1. a. AC power capability to Div I and Div II

1. VALID reading on any of the radiation monitors in Table 1. VALID reading on any of the radiation monitors in Table 1. VALID reading on any of the radiation monitors in OR information of an aircraft threat ENS busses reduced to a single power R1 > the GENERAL EMERGENCY reading for > 15 R1 > the SITE AREA EMERGENCY reading for > 15 Table R1 > the Alert reading for > 15 minutes 2. VALID reading on RMS-RE107 effluent monitor > 2 source for > 15 minutes minutes minutes OR times the alarm setpoint established by a current OR OR 2. For RMS-RE107 effluent monitor: radioactivity discharge permit for > 60 minutes AND HG2 1 2 3 4 5 D HS2 1 2 3 4 5 D HA2 1 2 3 4 5 D HU2 1 2 3 4 5 D Radiological Effluents

2. Dose assessment using actual meteorology indicates 2. Dose assessment using actual meteorology indicates doses EITHER OR b. Any additional single failure will result in a doses > 1000 mR TEDE or 5000 mR thyroid CDE at or > 100 mR TEDE or 500 mR thyroid CDE at or beyond the VALID reading > 200 times the alarm setpoint 3. Confirmed sample analyses for gaseous or liquid releases Other conditions exist which in the judgment Other conditions exist which in the judgment station blackout Other conditions exist which in the judgment Other conditions exist which in the judgment beyond the SITE BOUNDARY SITE BOUNDARY established by a current radioactivity discharge permit indicate concentrations or release rates > 2 times the of the Emergency Director warrant of the Emergency Director warrant of the Emergency Director warrant of the Emergency Director warrant OR OR for > 15 minutes ODCM limit for > 60 minutes declaration of an ALERT declaration of a NOUE declaration of a General Emergency declaration of a SITE AREA EMERGENCY

3. Field survey results indicate closed window dose rates > 3. Field survey results indicate closed window dose rates > OR SG3 1 2 3 4 5 D SS3 1 2 3 4 5 D SA3 1 2 3 4 5 D 1000 mR/hr expected to continue for > 60 minutes; or 100 mR/hr expected to continue for > 60 minutes; or VALID reading > 1.27E-01 µCi/ml for > 15 minutes Emergency Action Level(s): Emergency Action Level(s): Emergency Action Level(s): Emergency Action Level(s):

analyses of field survey samples indicate thyroid CDE > analyses of field survey samples indicate thyroid CDE > OR 1. Other conditions exist which in the judgment 1. Other conditions exist which in the judgment Automatic scram and all manual actions fail Automatic scram fails to shutdown the reactor Automatic scram fails to shutdown the

1. Other conditions exist which in the judgment 1. Other conditions exist which in the judgment to shutdown the reactor and indication of an and the manual actions taken from the reactor reactor and the manual actions taken from 5000 mR for one hour of inhalation, at or beyond the 500 mR for one hour of inhalation, at or beyond the SITE 3. Confirmed sample analysis for gaseous or liquid of the Emergency Director indicate that events of the Emergency Director indicate that of the Emergency Director indicate that of the Emergency Director indicate that SITE BOUNDARY BOUNDARY releases indicate concentrations or release rates > 200 are in progress or have occurred extreme challenge to the ability to cool the control console are not successful in shutting the reactor control console are successful in events are in progress or have 1occurred 5 D 2 3 4which events are in progress or have 1occurred 5 D 2 3 4which 1 which 2 3 4involve 5 D events are in progress or have 1occurred 2 3 4which 5 D times the ODCM limit for > 15 minutes actual or likely potential substantial indicate a potential degradation of the level core exists down the reactor shutting down the reactor involve actual or IMMINENT substantial involve actual or likely major failures of degradation of the level of safety of the plant of safety of the plant or indicate a security core degradation or melting with potential for plant functions needed for protection of the or a security event that involves probable life threat to facility protection has been initiated. Emergency Action Level(s): Emergency Action Level(s): Emergency Action Level(s):

loss of containment integrity or HOSTILE public or HOSTILE ACTION that results in Discretionary threatening risk to site personnel or damage to No releases of radioactive material requiring 1.a. An automatic scram failed to shutdown the 1.a. An automatic scram failed to shutdown the 1. a. An automatic scram failed to shutdown the AA2 1 2 3 4 5 D AU2 1 2 3 4 5 D ACTION that results in an actual loss of intentional damage or malicious acts: (1) reactor reactor reactor physical control of the facility. Releases can toward site personnel or equipment that could site equipment because of HOSTILE ACTION. offsite response or monitoring are expected Damage to irradiated fuel or loss of water level that has UNPLANNED rise in plant radiation levels be reasonably expected to exceed EPA lead to the likely failure of or: (2) that Any releases are expected to be limited to unless further degradation of safety systems AND AND AND resulted or will result in the uncovering of irradiated Emergency Action Level(s): (1 or 2) small fractions of the EPA Protective Action occurs b. All manual actions do not shutdown the Protective Action Guideline exposure levels prevent effective access to equipment needed b. Manual actions taken at the reactor control b. Manual actions taken at the reactor control fuel outside the reactor vessel 1. a. UNPLANNED water level drop in a reactor refueling Guideline exposure levels reactor as indicated by reactor power > 5%

offsite for more than the immediate site area for the protection of the public. Any releases console do not shutdown the reactor as console successfully shutdown the reactor as Emergency Action Level(s): (1 or 2) pathway as indicated by any of the following: are not expected to result in exposure levels AND indicated by reactor power > 5% indicated by reactor power < 5%

1. A water level drop in the reactor refueling cavity, spent Water level drop in the reactor refueling cavity, spent which exceed EPA Protective Action fuel pool or fuel transfer canal that will result in fuel pool, or fuel transfer canal indication on Control c. Either of the following exist or have occurred Guideline exposure levels beyond the SITE due to continued power generation:

irradiated fuel becoming uncovered Room Panel 870 BOUNDARY OR Personnel observation by visual or remote means. Core cooling is extremely challenged as HS3 1 2 3 4 5 D HA3 1 2 3 4 5 D

2. A VALID reading on any of the following radiation AND indicated by RPV level cannot be restored monitors due to damage to irradiated fuel or loss of b. UNPLANNED VALID area radiation monitor alarm on Control room evacuation has been initiated Control room evacuation has been initiated and maintained > -187 inches Failure of Reactor Protection System water level: any of the following: and plant control cannot be established OR RMS-RE140 2000 mR/hr RMS-RE140 Emergency Action Level(s):

RMS-RE141 2000 mR/hr RMS-RE141 Emergency Action Level(s): 1. AOP-0031, Shutdown from Outside the Main Heat removal is extremely challenged as RMS-RE192 2000 mR/hr RMS-RE192 1. a. Control room evacuation has been initiated Control Room requires Control Room indicated by RPV pressure and Suppression RMS-RE193 2000 mR/hr RMS-RE193 AND evacuation Pool temperature cannot be maintained in RMS-RE5A 1.64E+03 Ci/sec OR b. Control of the plant cannot be established in the EOP Heat Capacity Temperature Limit RMS-RE5B (GE) 5.29E-04 Ci/ml 2. UNPLANNED VALID area radiation monitor readings accordance with AOP-0031, Shutdown from (HCTL) Safe Zone or survey results indicate a rise by a factor of 1000 over Outside the Main Control Room, within 15 Control Room Evacuation normal* levels minutes Abnormal Radiation Levels SS4 1 2 3 4 5 D NOTE: For area radiation monitors with ranges incapable of HA4 1 2 3 4 5 D HU4 1 2 3 4 5 D Loss of all vital DC power for > 15 minutes measuring 1000 times normal* levels, classification shall be based on VALID full scale indications unless surveys FIRE or EXPLOSION affecting the FIRE within the PROTECTED AREA not operability of plant safety systems required to extinguished within 15 minutes of detection or Emergency Action Level(s):

confirm that area radiation levels are below 1000 times NOTE: The Emergency Director should not wait normal* within 15 minutes of the area radiation monitor establish or maintain safe shutdown EXPLOSION within the PROTECTED AREA until the applicable time has elapsed, but indications going full scale. should declare the event as soon as it is Emergency Action Level(s):

1. FIRE or EXPLOSION resulting in VISIBLE Emergency Action Level(s): (1 or 2) determined that the condition has exceeded,

• Normal can be considered the highest reading in the past Loss of DC Power DAMAGE to any of the structures or areas in NOTE: The Emergency Director should not wait or will likely exceed, the applicable time.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> excluding the current peak value.

Table H2 containing safety systems or until the applicable time has elapsed, but components or Control Room indication of should declare the event as soon as it is 1. < 105 VDC on all vital DC busses > 15 AA3 1 2 3 4 5 D Fire degraded performance of those safety systems determined that the duration has exceeded, or minutes Rise in radiation levels within the facility that impedes will likely exceed, the applicable time.

SS6 1 2 3 4 5 D SA6 1 2 3 4 5 D SU6 1 2 3 4 5 D operation of systems required to maintain plant safety functions 1. FIRE not extinguished within 15 minutes of Inability to monitor a SIGNIFICANT UNPLANNED loss of safety system UNPLANNED loss of safety system Control Room notification or verification of a TRANSIENT in progress annunciation or indication in the control annunciation or indication in the Control Emergency Action Level: (s)

Control Room FIRE alarm in any Table H2 room with either (1) a SIGNIFICANT Room for > 15 minutes

1. Dose rate > 15 mR/hr in any of the following areas structure or area Emergency Action Level(s): TRANSIENT in progress, or (2) requiring continuous occupancy to maintain plant OR NOTE: The Emergency Director should not wait compensatory non-alarming indicators are Emergency Action Level(s):

safety functions:

2. EXPLOSION within the PROTECTED until the applicable time has elapsed, but not available NOTE: The Emergency Director should not wait Main Control Room AREA should declare the event as soon as it is until the applicable time has elapsed, but CAS determined that the condition has exceeded, Emergency Action Level(s): should declare the event as soon as it is or will likely exceed, the applicable time. NOTE: The Emergency Director should not wait determined that the condition has exceeded, or HA5 1 2 3 4 5 D HU5 1 2 3 4 5 D until the applicable time has elapsed, but will likely exceed, the applicable time.

Table R1 EAL THRESHOLD Access to a VITAL AREA is prohibited due to Release of toxic, corrosive, asphyxiant or 1. a. UNPLANNED loss of > approximately 75% should declare the event as soon as it is toxic, corrosive, asphyxiant or flammable flammable gases deemed detrimental to of the following for > 15 minutes: determined that the condition has exceeded, 1. UNPLANNED loss of > approximately 75%

gases which jeopardize operation of operable NORMAL PLANT OPERATIONS or will likely exceed, the applicable time. of the following for > 15 minutes:

GENERAL SITE AREA ALERT NOUE Control Room safety system annunciation Method equipment required to maintain safe DRMS Threshold DRMS Threshold DRMS Threshold DRMS Threshold OR 1. a. UNPLANNED loss of > approximately 75% a. Control Room safety system annunciation operations or safely shutdown the reactor Emergency Action Level(s) (1 or 2)

1. Toxic, corrosive, asphyxiant or flammable Control Room safety system indication of the following for > 15 minutes: OR Main Plant Emergency Action Level(s): gases in amounts that have or could adversely AND b. Control Room safety system indication Primary 4GE125 4.50E+08 Ci/sec 4GE125 4.50E+07 Ci/sec 4GE125 3.06E+07 Ci/sec 4GE125 3.06E+05 Ci/sec NOTE: If the equipment in the stated area was affect NORMAL PLANT OPERATIONS b. A SIGNIFICANT TRANSIENT is in Control Room safety system annunciation Secondary N/A N/A 1GE126 2.82E-01 Ci/ml 1GE126 5.26E-03 Ci/ml already inoperable, or out of service, before OR progress OR Loss of Annunciation / Indication the event occurred, then this EAL should not 2. Report by West Feliciana Parish for AND Control Room safety system indication FB Vent be declared as it will have no adverse impact evacuation or sheltering of site personnel c. Compensatory indications are unavailable AND Primary 4GE005 1.00E+09 Ci/sec 4GE005 1.00E+08 Ci/sec 4GE005 2.19E+06 Ci/sec 4GE005 2.19E+04 Ci/sec on the ability of the plant to safely operate or based on an offsite event b. Either of the following:

Secondary N/A N/A 5GE005 2.82E-01 Ci/ml 5GE005 4.65E-03 Ci/ml safely shutdown beyond that already allowed A SIGNIFICANT T RANSIENT is in by Technical Specifications at the time of the progress RW Vent event. OR 4GE006 2.58E+06 Ci/sec 4GE006 2.58E+04 Ci/sec Compensatory indications unavailable Primary N/A N/A Toxic or Flammable Gasses 5GE006 6.84E-02 Ci/ml 5GE006 6.84E-04 Ci/ml 1. Access to Main Control Room, Auxiliary Secondary Building, or 95 Control Building is prohibited due to toxic, corrosive, asphyxiant FISSION PRODUCT BARRIER OPERATING MODES: or flammable gases which jeopardize 1 2 3 4 5 D operation of systems required to maintain safe SU7 1 2 3 4 5 D operations or safely shutdown the reactor RCS leakage GENERAL EMERGENCY SITE AREA EMERGENCY ALERT NOUE Emergency Action Level(s): (1 or 2)

FG1 1 2 3 4 5 D FS1 1 2 3 4 5 D FA1 1 2 3 4 5 D FU1 1 2 3 4 5 D NOTE: A relief valve that operates and fails to HA6 1 2 3 4 5 D HU6 1 2 3 4 5 D close per design should be considered FPB Loss / Potential Loss of ANY two barriers AND loss or potential loss of third Loss or potential loss of ANY two barriers ANY loss or ANY potential loss of EITHER fuel clad or ANY loss or ANY potential loss of containment applicable if the relief valve cannot be isolated.

barrier RCS Natural or destructive phenomena affecting Natural or destructive phenomena affecting RCS Leakage Emergency Action Level(s): Emergency Action Level(s): Emergency Action Level(s): Emergency Action Level(s): VITAL AREAS the PROTECTED AREA 1. Unidentified or pressure boundary leakage > 10

1. Loss of any two barriers 1. Loss or potential loss of any two barriers 1. Any loss or any potential loss of fuel clad 1. Any loss or any potential loss of containment gpm AND OR Emergency Action Level(s): (1 or 2 or 3 or 4 or Emergency Action Level(s):(1 or 2 or 3 or 4 or 5) OR Loss Loss or potential loss of the third barrier Any loss or any potential loss of RCS 5 or 6) 1. Seismic event identified by any 2 of the 2. Identified leakage > 35 gpm 1.a. Seismic event > Operating Basis Earthquake following:

(OBE) as indicated by: Seismic event confirmed by activated SU8 1 2 3 4 5 D FUEL CLAD (FC) Barrier REACTOR COOLANT SYSTEM (RC) Barrier PRIMARY CONTAINMENT (PC) Barrier Annunciator Seismic Tape Recording seismic switch as indicated by receipt of Loss of all onsite or offsite communication System Start (P680-02A-D06) EITHER a OR b: capabilities Parameter Loss Potential Loss Parameter Loss Potential Loss Parameter Loss Potential Loss AND a. Annunciator Seismic Tape Emergency Action Level(s): (1 or 2)

Event Indicator on ERS-NBI-102 is white Recording SYS Start (P680-02A-

1. Loss of all of the following onsite FC1 Coolant activity None RC1 Drywell pressure > 1.68 psid None PC1 1. Rapid unexplained loss of PC 1. PC pressure > 15 psig and AND D06) communications methods affecting the ability to Primary > 300 µCi/gm dose equivalent I131 Drywell with indications of reactor Primary containment pressure following initial rising Receipt of EITHER 1 OR 2: b. Event Indicator on ERS-NBI-102 is perform routine operations:

coolant pressure coolant leak in drywell. conditions pressure rise OR 1. Annunciator Seismic Event High white Plant radio system activity level OR 2. a. PC hydrogen in the (P680-02A-C06) Earthquake felt in plant Plant paging system

2. PC pressure response not unsafe zone of HDOL 2. Annunciator Seismic Event High- National Earthquake Center Sound powered phones consistent with LOCA curve High (P680-02A-B06) AND amber OR In-plant telephones conditions OR light(s) on panel NBI-101 2. Tornado striking within the PROTECTED OR

b. DW hydrogen AND AREA boundary

2. Loss of all of the following offsite Loss of Communication concentration > 9% b. Earthquake confirmed by any of the OR communications methods affecting the ability to OR 3. Internal flooding that has the potential to following: perform offsite notifications:

3. RPV pressure and affect safety related equipment required by Earthquake is felt in plant All telephones suppression pool temperature Technical Specifications for the current National Earthquake Center NRC phones cannot be maintained below operating mode in any Table H1 area Control Room indication of degraded State of Louisiana Radio the HCTL OR performance of systems required for Offsite notifications system and hotline

4. Turbine failure resulting in casing penetration safe shutdown of the plant FC2 RPV water level cannot be RPV water level cannot be RC2 RPV water level cannot be None PC2 None Entry into PC flooding or damage to turbine or generator seals Table S1 SU9 1 2 3 4 5 D OR Reactor vessel restored and maintained above restored and maintained Reactor vessel restored and maintained Reactor vessel procedures SAP-1 and SAP-2 2. Tornado striking resulting in VISIBLE OR water level -187 inches above -162 inches or cannot water level above -162 inches or cannot water level 5. Severe weather or hurricane conditions with Flow Dose Rate Fuel clad degradation Table H2 DAMAGE to any of the Table H2 structures be determined be determined Structures Containing Functions or areas containing safety systems or indication of SUSTAINED high winds > 74 (cfm) (mR/hr) Emergency Action Level(s): (1 or 2) mph within the PROTECTED AREA FC3 Containment radiation monitor None RC3 1. UNISOLABLE main 1. RCS leakage > 50 gpm PC3 1. a. Failure of both valves in None or Systems Required for Safe components or Control Room indication of <15 9000 1. Offgas pre-treatment radiation monitor reading boundary Primary RMS-RE16 reading > 3,000 R/hr RCS Leak Rate steam line break as inside the drywell Primary any one line to close Shutdown degraded performance of those safety > the Table S1 Dose Rate Limit for the actual containment indicated by the failure of containment systems >15-17 8000 indicated offgas flow indicating fuel clad OR AND Table H1 Reactor Standby Cooling OR degradation > T.S. allowable limits radiation both MSIVs in any one line isolation failure or b. Direct downstream Uncontrolled Flooding Threshold

2. UNISOLABLE RCS Building Tower 3. Internal flooding in Auxiliary Building 70 ft >17-20 7000 monitors to close bypass pathway to the Area Water Level OR leakage outside PC as elevation resulting in an electrical shock AND indicated by exceeding environment exists after >20-25 5000 2. Reactor coolant sample activity value indicating Natural or Destructive Phenomena Auxiliary Diesel Generator hazard that precludes access to operate or PC isolation Affected Max Safe Operating fuel clad degradation > T.S. allowable limits Cladding Degradation High MSL flow either of the following: Building Building monitor safety equipment or Control Room >25-30 4000 annunciator (P601-19A- OR Location / Value / Indicator > 4.0 µCi/gm dose equivalent I-131 indication of degraded performance of those A2) a. Max Normal Operating Parameter OR

2. Intentional PC venting per Control Tunnels (B, D, E, F, safety systems >30-60 2000 OR Temperature (Table F2) EOPs or SAPs OR > 0.2 µCi/gm dose equivalent I-131 for > 48 Building G) Aux Bldg 6 inches above floor OR 4. Turbine failure-generated PROJECTILES >60-140 1000 hours

2. Indication of an OR Crescent Area (must be verified locally) resulting in VISIBLE DAMAGE to or 70 EL UNISOLABLE HPCS, b. Max Normal Area 3. UNISOLABLE RCS Fuel Building >140-200 700 SU10 1 2 3 4 5 D penetration of any of the Table H2 structures feedwater, RWCU or RCIC Radiation (Table F2) leakage outside PC as or areas containing safety systems or Inadvertent criticality break indicated by exceeding HPCS Room 4 inches above floor components or Control Room indication of Inadvertent either of the following: 70EL (P870-51A-G4)

OR degraded performance of those safety

a. Max Safe Operating Emergency Action Level(s):

3. Emergency RPV systems 1. UNPLANNED sustained positive period Temperature (Table F1) OR RHR A Room 4 inches above floor Criticality depressurization is required OR observed on nuclear instrumentation

5. Vehicle crash resulting in VISIBLE 70EL (P870-51A-G4)

b. Max Safe Area Radiation DAMAGE to any of the Table H2 structures (Table F1) or areas containing safety systems or RHR B Room 4 inches above floor SU11 1 2 3 4 5 D components or Control Room indication of 70EL (P870-51A-G4)

RC4 Drywell radiation monitor None PC4 None Containment radiation monitor degraded performance of those safety Inability to reach required operating mode Drywell RMS-RE20 reading > 100 Primary containment RMS-RE16 reading systems within Technical Specification limits radiation R/hr due to reactor coolant radiation monitors > 10,000 R/hr RHR C Room 4 inches above floor OR leakage 70EL (P870-51A-G4) Emergency Action Level(s):

6. Hurricane or high SUSTAINED wind conditions > 74 mph within the 1. Plant is not brought to required operating mode FC4 Any condition in the opinion of Any condition in the opinion RC5 Any condition in the opinion Any condition in the opinion PC5 Any condition in the opinion of Any condition in the opinion of PROTECTED AREA boundary and resulting LPCS Room 4 inches above floor within Technical Specifications LCO Action Emergency the Emergency Director that of the Emergency Director Emergency of the Emergency Director of the Emergency Director Emergency Director the Emergency Director that the Emergency Director that in VISIBLE DAMAGE to any of the Table 70EL (P870-51A-G4) Statement time Director indicates loss of the Fuel Clad that indicates potential loss Director that indicates loss of the RCS that indicates potential loss of judgment indicates loss of the Primary indicates potential loss of the H2 structures or areas containing safety judgment barrier of the Fuel Clad barrier judgment barrier the RCS barrier Containment barrier Primary Containment barrier systems or components or Control Room RCIC Room 4 inches above floor indication of degraded performance of those 70EL (P870-51A-G4) safety systems TABLE F2 TABLE F1 EVENTS RELATED TO ISFSI OPERATING MODES:

1 2 3 4 5 D RC 3 Potential Loss of RCS PC 3 Loss of Primary Containment GENERAL EMERGENCY SITE AREA EMERGENCY ALERT NOUE 1 2 3 4 5 D TECH SPEC Time Limit Exceeded Parameter Area Temperature Area Radiation Level E-HU1 Parameter Area Temperature Area Radiation Level (isolation temperature alarm) DRMS Grid 2 Max Normal Operating Max Safe Operating Value DRMS Grid 2 Max Safe Operating Damage to a loaded cask CONFINEMENT Value Value BOUNDARY Cask Damage RHR A equip area 117º F (P601-20A-B4) 1213 8.2E+01 mR/hr RHR A equip area 200º F 1213 9.5E+03 mR/hr Emergency Action Level(s):

1. Damage to a loaded cask CONFINEMENT RHR B equip area 117º F (P601-20A-B4) 1214 8.2E+01 mR/hr RHR B equip area 200º F 1214 9.5E+03 mR/hr BOUNDARY RHR C equip area N/A 1215 8.2E+01 mR/hr RHR C equip area N/A 1215 9.5E+03 mR/hr RCIC room 182º F (P601-21A-B6) 1219 1.20E+02 mR/hr RCIC room 200º F 1219 9.5E+03 mR/hr MSL Tunnel 173º F (P601-19A-A1/A3/B1/B3) N/A MSL Tunnel 200º F N/A EIP-2-001 ATT 9 USER AID 1 Revision F RWCU pump room 1 (A) / 2 (B) 165º F (P680-1A-A2/B2) N/A RWCU pump room 1 (A) / 2 (B) 200º F N/A EIP-2-001 REV - 26 PAGE 143 of 144

EIP-2-001 CLASSIFICATION USER AID ATTACHMENT 9 PAGE 2 of 2 EMERGENCY CLASSIFICATION USER AID 2 MODES 4, 5, and Defueled Plant Modes (white boxes indicate applicable modes) 1 Power Operations 2 Startup 3 Hot Shutdown 4 Cold Shutdown 5 Refuel D Defueled ABNORMAL RADIATION LEVELS / RADIOLOGICAL EFFLUENT OPERATING MODES: HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY OPERATING MODES: COLD SHUTDOWN / REFUELING OPERATING MODES:

1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D GENERAL EMERGENCY SITE AREA EMERGENCY ALERT NOUE GENERAL EMERGENCY SITE AREA EMERGENCY ALERT NOUE GENERAL EMERGENCY SITE AREA EMERGENCY ALERT NOUE 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D 1 2 3 4 5 D CG1 1 2 3 4 5 D CS1 1 2 3 4 5 D CA1 1 2 3 4 5 D CU1 1 2 3 4 5 D AG1 AS1 AA1 AU1 HG1 1 2 3 4 5 D HS1 1 2 3 4 5 D HA1 1 2 3 4 5 D HU1 1 2 3 4 5 D Offsite dose resulting from an actual or IMMINENT Offsite dose resulting from an actual or IMMINENT Any release of gaseous or liquid radioactivity to the Any release of gaseous or liquid radioactivity to the HOSTILE ACTION within the PROTECTED Confirmed SECURITY CONDITION or Loss of RCS/RPV inventory affecting fuel Loss of RCS/RPV inventory affecting core Loss of RCS/RPV inventory RCS leakage HOSTILE ACTION resulting in loss of HOSTILE ACTION within the OWNER release of gaseous radioactivity > 1000 mR TEDE or release of gaseous radioactivity > 100 mR TEDE or 500 environment > 200 times the ODCM limit for > 15 environment > 2 times the ODCM limit for > 60 minutes AREA threat which indicates a potential degradation clad integrity with containment decay heat removal capability physical control of the facility CONTROLLED AREA or airborne attack 5000 mR thyroid CDE for the actual or projected mR thyroid CDE for the actual or projected duration of minutes Emergency Action Level(s): (1 or 2 or 3) in the level of safety of the plant challenged Emergency Action Level(s): (1 or 2) Emergency Action Level(s):

threat duration of the release using actual meteorology the release Emergency Action Level(s): (1 or 2 or 3) NOTE: The Emergency Director should not wait until the Emergency Action Level(s): (1 or 2 or 3)

Emergency Action Level(s): (1 or 2) Emergency Action Level(s): Emergency Action Level(s): (1 or 2) NOTE: The Emergency Director should not wait NOTE: The Emergency Director should not wait Emergency Action Level: (1 or 2 or 3) 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 Emergency Action Level(s): (1 or 2) Emergency Action Level(s): (1 or 2 or 3) NOTE: The Emergency Director should not wait until the applicable time has elapsed, but until the applicable time has elapsed, but

1. A HOSTILE ACTION has occurred such that 1. A HOSTILE ACTION is occurring or has 1. a. RPV level < -162 inches (TAF) for > 30 NOTE: The Emergency Director should not wait until the NOTE: The Emergency Director should not wait until the applicable time has elapsed, but should declare the as soon as it is determined that the release duration has 1. A SECURITY CONDITION that does not until the applicable time has elapsed, but should declare the event as soon as it is should declare the event as soon as it is plant personnel are unable to operate occurred within the PROTECTED AREA as 1. A HOSTILE ACTION is occurring or has minutes applicable time has elapsed, but should declare the event applicable time has elapsed, but should declare the event event as soon as it is determined that the release exceeded, or will likely exceed the applicable time. In the should declare the event as soon as it is determined that the condition will likely determined that the condition will likely equipment required to maintain safety reported by the RBS security shift occurred within the OWNER CONTROLLED involve a HOSTILE ACTION as reported by AND as soon as it is determined that the condition will likely as soon as it is determined that the condition will likely duration has exceeded, or will likely exceed the absence of data to the contrary, assume that the release determined that the condition will likely exceed the applicable time. exceed the applicable time.

functions AREA as reported by the RBS security shift the RBS security shift supervision supervision Security exceed the applicable time. If dose assessment results are exceed the applicable time. If dose assessment results are applicable time. In the absence of data to the duration has exceeded the applicable time if an ongoing b. Any containment challenge indication in exceed the applicable time.

OR supervision OR available, the classification should be based on EAL #2 available, the classification should be based on EAL #2 contrary, assume that the release duration has release is detected and the release start time is unknown. Table C1

2. A HOSTILE ACTION has caused failure of OR 2. A credible site specific security threat 1. UNPLANNED loss of RCS inventory as 1. RCS leakage results in the inability to instead of EAL #1. Do not delay declaration awaiting instead of EAL #1. Do not delay declaration awaiting exceeded the applicable time if an ongoing release is OR dose assessment results. dose assessment results. detected and the release start time is unknown. 1. VALID reading on any of the radiation monitors in Table Spent Fuel Cooling Systems and 2. A validated notification from NRC of an notification 1. With CONTAINMENT CLOSURE not indicated by RPV level < -43 inches (Level maintain or restore RPV level > +9.7 inches OR 2. a. RCS level cannot be monitored with core established, UNPLANNED RPV level < -49 2) (Level 3) for > 15 minutes R1 > the NOUE reading for > 60 minutes IMMINENT fuel damage is likely for a airliner attack threat within 30 minutes of the uncovery indicated by any of the inches OR

1. VALID reading on any of the radiation monitors in Table 1. VALID reading on any of the radiation monitors in Table 1. VALID reading on any of the radiation monitors in OR freshly off-loaded reactor core in pool site 3. A validated notification from NRC providing following for > 30 minutes: OR 2. RCS level cannot be monitored for > 15 R1 > the GENERAL EMERGENCY reading for > 15 R1 > the SITE AREA EMERGENCY reading for > 15 Table R1 > the Alert reading for > 15 minutes 2. VALID reading on RMS-RE107 effluent monitor > 2 information of an aircraft threat minutes minutes OR times the alarm setpoint established by a current

• RMS-RE16 reading > 100 R/hr 2. With CONTAINMENT CLOSURE minutes with a loss of RCS inventory as OR OR 2. For RMS-RE107 effluent monitor: radioactivity discharge permit for > 60 minutes

• Erratic source range monitor established, RPV level < -162 inches (TAF) indicated by an unexplained rise in floor or

2. Dose assessment using actual meteorology indicates 2. Dose assessment using actual meteorology indicates doses EITHER OR HG2 1 2 3 4 5 D HS2 1 2 3 4 5 D HA2 1 2 3 4 5 D HU2 1 2 3 4 5 D indication OR equipment sump level, Suppression Pool Radiological Effluents doses > 1000 mR TEDE or 5000 mR thyroid CDE at or > 100 mR TEDE or 500 mR thyroid CDE at or beyond the VALID reading > 200 times the alarm setpoint 3. Confirmed sample analyses for gaseous or liquid releases

• Unexplained rise in floor or 3. RCS level cannot be monitored for > level, vessel make-up rate or observation of Other conditions exist which in the judgment Other conditions exist which in the judgment leakage or inventory loss beyond the SITE BOUNDARY SITE BOUNDARY established by a current radioactivity discharge permit indicate concentrations or release rates > 2 times the Other conditions exist which in the judgment Other conditions exist which in the judgment equipment sump level, Suppression 30 minutes with a loss of RCS of the Emergency Director warrant of the Emergency Director warrant OR OR for > 15 minutes ODCM limit for > 60 minutes of the Emergency Director warrant of the Emergency Director warrant Pool level, vessel make-up rate or inventory as indicated by any of the declaration of an ALERT declaration of a NOUE Loss of RCS/RPV Inventory

3. Field survey results indicate closed window dose rates > 3. Field survey results indicate closed window dose rates > OR declaration of a General Emergency declaration of a SITE AREA EMERGENCY observation of leakage or inventory following:

1000 mR/hr expected to continue for > 60 minutes; or 100 mR/hr expected to continue for > 60 minutes; or VALID reading > 1.27E-01 µCi/ml for > 15 minutes loss Emergency Action Level(s): Emergency Action Level(s): RMS-RE16 reading > 100 R/hr analyses of field survey samples indicate thyroid CDE > analyses of field survey samples indicate thyroid CDE > OR Emergency Action Level(s): Emergency Action Level(s): AND

1. Other conditions exist which in the judgment 1. Other conditions exist which in the judgment 1. Other conditions exist which in the judgment 1. Other conditions exist which in the judgment Erratic Source Range Monitor 5000 mR for one hour of inhalation, at or beyond the 500 mR for one hour of inhalation, at or beyond the SITE 3. Confirmed sample analysis for gaseous or liquid b. Any containment challenge indication in of the Emergency Director indicate that of the Emergency Director indicate that of the Emergency Director indicate that events of the Emergency Director indicate that indication SITE BOUNDARY BOUNDARY releases indicate concentrations or release rates > 200 are in progress or have occurred which involve events are in progress or have occurred which Table C1 Unexplained rise in floor or times the ODCM limit for > 15 minutes events are in progress or have occurred which events are in progress or have occurred which actual or likely potential substantial indicate a potential degradation of the level equipment sump level, involve actual or IMMINENT substantial involve actual or likely major failures of degradation of the level of safety of the plant of safety of the plant or indicate a security Table C1 core degradation or melting with potential for plant functions needed for protection of the Suppression Pool level, vessel or a security event that involves probable life threat to facility protection has been initiated. Containment Challenge loss of containment integrity or HOSTILE public or HOSTILE ACTION that results in make-up rate or observation of Discretionary ACTION that results in an actual loss of intentional damage or malicious acts: (1) threatening risk to site personnel or damage to No releases of radioactive material requiring Indications site equipment because of HOSTILE ACTION. offsite response or monitoring are expected leakage or inventory loss physical control of the facility. Releases can toward site personnel or equipment that could Any releases are expected to be limited to unless further degradation of safety systems CONTAINMENT CLOSURE not AA2 1 2 3 4 5 D AU2 1 2 3 4 5 D be reasonably expected to exceed EPA lead to the likely failure of or: (2) that small fractions of the EPA Protective Action occurs established Damage to irradiated fuel or loss of water level that has UNPLANNED rise in plant radiation levels Protective Action Guideline exposure levels prevent effective access to equipment needed Guideline exposure levels Explosive mixture inside containment resulted or will result in the uncovering of irradiated offsite for more than the immediate site area for the protection of the public. Any releases Emergency Action Level(s): (1 or 2) UNPLANNED rise in containment fuel outside the reactor vessel are not expected to result in exposure levels

1. a. UNPLANNED water level drop in a reactor refueling which exceed EPA Protective Action pressure CU2 1 2 3 4 5 D Emergency Action Level(s): (1 or 2) pathway as indicated by any of the following: Guideline exposure levels beyond the SITE Secondary containment area radiation

1. A water level drop in the reactor refueling cavity, spent Water level drop in the reactor refueling cavity, spent UNPLANNED loss of RCS/RPV inventory BOUNDARY monitor above EOP Max Safe fuel pool or fuel transfer canal that will result in fuel pool, or fuel transfer canal indication on Control irradiated fuel becoming uncovered Room Panel 870 HS3 1 2 3 4 5 D HA3 1 2 3 4 5 D Operating Value below:

Emergency Action Level(s): (1 or 2)

OR Personnel observation by visual or remote means. Control room evacuation has been initiated Control room evacuation has been initiated Area DRMS Max Safe

2. A VALID reading on any of the following radiation AND and plant control cannot be established NOTE: The Emergency Director should not wait Grid 2 Operating monitors due to damage to irradiated fuel or loss of b. UNPLANNED VALID area radiation monitor alarm on Emergency Action Level(s): Value until the applicable time has elapsed, but water level: any of the following: Emergency Action Level(s): 1. AOP-0031, Shutdown from Outside the Main should declare the event as soon as it is RMS-RE140 2000 mR/hr RMS-RE140 1. a. Control room evacuation has been initiated Control Room requires Control Room determined that the condition will likely RMS-RE141 2000 mR/hr RMS-RE141 RHR 1213 9.5E+03 mR/hr exceed the applicable time.

AND evacuation RMS-RE192 2000 mR/hr RMS-RE192 Equip

b. Control of the plant cannot be established in RMS-RE193 2000 mR/hr RMS-RE193 Rm A 1. UNPLANNED RCS level drop as indicated accordance with AOP-0031, Shutdown from RMS-RE5A 1.64E+03 Ci/sec OR by either of the following:

Outside the Main Control Room, within 15 Control Room Evacuation RMS-RE5B (GE) 5.29E-04 Ci/ml 2. UNPLANNED VALID area radiation monitor readings RHR 1214 9.5E+03 mR/hr minutes Equip or survey results indicate a rise by a factor of 1000 over a. RCS water level drop below the RPV flange normal* levels Rm B for > 15 minutes when the RCS level band HA4 1 2 3 4 5 D HU4 1 2 3 4 5 D is established above the RPV flange RHR 1215 9.5E+03 mR/hr NOTE: For area radiation monitors with ranges incapable of FIRE or EXPLOSION affecting the FIRE within the PROTECTED AREA not OR Abnormal Radiation Levels Equip Loss of RCS/RPV Inventory measuring 1000 times normal* levels, classification operability of plant safety systems required to extinguished within 15 minutes of detection or Rm C b. RCS water level drop below the RPV level shall be based on VALID full scale indications unless establish or maintain safe shutdown EXPLOSION within the PROTECTED band for > 15 minutes when the RCS level surveys confirm that area radiation levels are below AREA band is established below the RPV flange 1000 times normal* within 15 minutes of the area Emergency Action Level(s): OR radiation monitor indications going full scale. 1. FIRE or EXPLOSION resulting in VISIBLE Emergency Action Level(s): (1 or 2) 2. RCS level cannot be monitored with a loss DAMAGE to any of the structures or areas in NOTE: The Emergency Director should not wait of RCS inventory as indicated by an

• Normal can be considered the highest reading in the past Table H2 containing safety systems or until the applicable time has elapsed, but unexplained rise in floor or equipment sump 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> excluding the current peak value. components or Control Room indication of should declare the event as soon as it is level, Suppression Pool level, vessel make-Fire degraded performance of those safety systems determined that the duration has exceeded, or up rate or observation of leakage or will likely exceed, the applicable time. inventory loss

1. FIRE not extinguished within 15 minutes of CA3 1 2 3 4 5 D CU3 1 2 3 4 5 D Control Room notification or verification of a Control Room FIRE alarm in any Table H2 Inability to maintain plant in cold shutdown UNPLANNED loss of decay heat removal 1 2 3 4 5 D structure or area capability with irradiated fuel in the RPV AA3 Emergency Action Level(s): (1or 2)

Rise in radiation levels within the facility that impedes OR 1. An UNPLANNED event results in RCS Emergency Action Level(s): (1 or 2) operation of systems required to maintain plant safety temperature > 200 °F > the specified NOTE: The Emergency Director should not wait functions 2. EXPLOSION within the PROTECTED duration in Table C2 until the applicable time has elapsed, but AREA OR should declare the event as soon as it is Emergency Action Level: (s)

2. An UNPLANNED event results in RCS determined that the condition will likely

1. Dose rate > 15 mR/hr in any of the following areas pressure rise > 10 psig due to a loss of RCS exceed the applicable time.

requiring continuous occupancy to maintain plant HA5 1 2 3 4 5 D HU5 1 2 3 4 5 D cooling safety functions:

Access to a VITAL AREA is prohibited due to Release of toxic, corrosive, asphyxiant or 1. An UNPLANNED event results in RCS Main Control Room toxic, corrosive, asphyxiant or flammable flammable gases deemed detrimental to temperature exceeding 200°F CAS Table C2 gases which jeopardize operation of operable NORMAL PLANT OPERATIONS OR RCS Reheat Duration Thresholds equipment required to maintain safe 2. Loss of all RCS temperature and RCS/RPV operations or safely shutdown the reactor Emergency Action Level(s): (1 or 2) level indication for > 15 minutes RCS Containment Duration

1. Toxic, corrosive, asphyxiant or flammable Closure Table R1 EAL THRESHOLD Emergency Action Level(s): gases in amounts that have or could adversely NOTE: If the equipment in the stated area was affect NORMAL PLANT OPERATIONS Intact N/A 60 minutes*

Loss of Decay Heat Removal already inoperable, or out of service, before OR GENERAL SITE AREA ALERT NOUE the event occurred, then this EAL should not 2. Report by West Feliciana Parish for Method Not Established 20 minutes*

DRMS Threshold DRMS Threshold DRMS Threshold DRMS Threshold be declared as it will have no adverse impact evacuation or sheltering of site personnel intact on the ability of the plant to safely operate or based on an offsite event Not 0 minutes Main Plant safely shutdown beyond that already allowed Established Primary 4GE125 4.50E+08 Ci/sec 4GE125 4.50E+07 Ci/sec 4GE125 3.06E+07 Ci/sec 4GE125 3.06E+05 Ci/sec by Technical Specifications at the time of the Secondary N/A N/A 1GE126 2.82E-01 Ci/ml 1GE126 5.26E-03 Ci/ml event. *If and RCS heat removal system is in Toxic or Flammable Gasses operation within this time frame and RCS FB Vent 1. Access to Main Control Room, Auxiliary temperature is being reduced, then the EAL is Primary 4GE005 1.00E+09 Ci/sec 4GE005 1.00E+08 Ci/sec 4GE005 2.19E+06 Ci/sec 4GE005 2.19E+04 Ci/sec Building, or 95 Control Building is not applicable.

Secondary N/A N/A 5GE005 2.82E-01 Ci/ml 5GE005 4.65E-03 Ci/ml prohibited due to toxic, corrosive, asphyxiant or flammable gases which jeopardize operation of systems required to maintain safe RW Vent CA5 1 2 3 4 5 D CU5 1 2 3 4 5 D 4GE006 2.58E+06 Ci/sec 4GE006 2.58E+04 Ci/sec operations or safely shutdown the reactor Primary N/A N/A 5GE006 6.84E-02 Ci/ml 5GE006 6.84E-04 Ci/ml AC power capability to emergency busses Secondary Loss of all offsite and all onsite AC power to emergency busses for > 15 minutes reduced to a single power source for > 15 HA6 1 2 3 4 5 D HU6 1 2 3 4 5 D minutes such that any additional single Emergency Action Level(s): failure would result in station blackout Natural or destructive phenomena affecting Natural or destructive phenomena affecting the NOTE: The Emergency Director should not wait VITAL AREAS PROTECTED AREA until the applicable time has elapsed, but Emergency Action Level(s):

should declare the event as soon as it is NOTE: The Emergency Director should not wait Emergency Action Level(s): (1 or 2 or 3 or 4 or Emergency Action Level(s):(1 or 2 or 3 or 4 or 5) determined that the condition will likely until the applicable time has elapsed, but 5 or 6) 1. Seismic event identified by any 2 of the exceed the applicable time. should declare the event as soon as it is EVENTS RELATED TO ISFSI OPERATING MODES: 1.a. Seismic event > Operating Basis Earthquake following: determined that the condition will likely 1 2 3 4 5 D (OBE) as indicated by: Seismic event confirmed by activated 1. Loss of all offsite and all onsite AC power to exceed the applicable time.

Loss of AC Power Annunciator Seismic Tape Recording seismic switch as indicated by receipt of Div I and Div II ENS busses for > 15 GENERAL EMERGENCY SITE AREA EMERGENCY ALERT NOUE System Start (P680-02A-D06) EITHER a OR b: 1. a. AC power capability to Div I and Div II minutes AND a. Annunciator Seismic Tape Recording ENS busses reduced to a single power 1 2 3 4 5 D Event Indicator on ERS-NBI-102 is white SYS Start (P680-02A-D06) source for > 15 minutes E-HU1 AND b. Event Indicator on ERS-NBI-102 is AND Receipt of EITHER 1 OR 2: white b. Any additional single power source failure Damage to a loaded cask CONFINEMENT BOUNDARY

1. Annunciator Seismic Event High Earthquake felt in plant will result in station blackout Emergency Action Level(s): (P680-02A-C06) National Earthquake Center

1. Damage to a loaded cask CONFINEMENT BOUNDARY 2. Annunciator Seismic Event High- OR CU6 1 2 3 4 5 D High (P680-02A-B06) AND amber 2. Tornado striking within the PROTECTED light(s) on panel NBI-101 AREA boundary OR Loss of required DC power for > 15 AND

3. Internal flooding that has the potential to affect minutes

b. Earthquake confirmed by any of the Emergency Action Level(s):

following: safety related equipment required by Technical Specifications for the current operating mode NOTE: The Emergency Director should not wait Earthquake is felt in plant until the applicable time has elapsed, but Confinement Boundary damage / loss National Earthquake Center in any Table H1 area OR should declare the event as soon as it is Control Room indication of degraded determined that the condition will likely performance of systems required for 4. Turbine failure resulting in casing penetration Loss of DC Power or damage to turbine or generator seals exceed the applicable time.

safe shutdown of the plant OR OR

5. Severe weather or hurricane conditions with 1. < 105 VDC on required Vital DC busses Table H2 2. Tornado striking resulting in VISIBLE indication of SUSTAINED high winds > 74 for > 15 minutes Structures Containing Functions DAMAGE to any of the Table H2 structures or Systems Required for Safe or areas containing safety systems or mph within the PROTECTED AREA Shutdown boundary CU7 1 2 3 4 5 D components or Control Room indication of degraded performance of those safety Inadvertent criticality systems Reactor Standby Cooling Table H1 Emergency Action Level(s):

OR Building Tower Uncontrolled Flooding Threshold 1. UNPLANNED sustained positive period

3. Internal flooding in Auxiliary Building 70 ft Area Water Level observed on nuclear instrumentation elevation resulting in an electrical shock Auxiliary Diesel Generator hazard that precludes access to operate or Building Building Affected Max Safe Operating Inadvertent Criticality monitor safety equipment or Control Room Natural or Destructive Phenomena indication of degraded performance of those Location / Value / Indicator Control Tunnels (B, D, E, F, safety systems Parameter CU8 1 2 3 4 5 D Building G) OR

4. Turbine failure-generated PROJECTILES Loss of all onsite or offsite communications Aux Bldg 6 inches above floor resulting in VISIBLE DAMAGE to or capabilities Fuel Building Crescent Area (must be verified locally) penetration of any of the Table H2 structures 70 EL Emergency Action Level(s): (1 or 2) or areas containing safety systems or 1. Loss of all of the following onsite components or Control Room indication of communication methods affecting the degraded performance of those safety HPCS Room 4 inches above floor ability to perform routine operations:

systems 70EL (P870-51A-G4) Plant radio system OR Plant paging system

5. Vehicle crash resulting in VISIBLE RHR A Room 4 inches above floor Sound powered phones DAMAGE to any of the Table H2 structures 70EL (P870-51A-G4) In-plant telephones or areas containing safety systems or OR components or Control Room indication of RHR B Room 4 inches above floor 2. Loss of all of the following offsite Loss of Communications degraded performance of those safety 70EL (P870-51A-G4) communication methods affecting the systems ability to perform offsite notifications:

OR All telephones RHR C Room 4 inches above floor

6. Hurricane or high SUSTAINED wind NRC phones 70EL (P870-51A-G4) conditions > 74 mph within the State of Louisiana Radio PROTECTED AREA boundary and resulting Offsite notification system and in VISIBLE DAMAGE to any of the Table LPCS Room 4 inches above floor hotline H2 structures or areas containing safety 70EL (P870-51A-G4) systems or components or Control Room indication of degraded performance of those RCIC Room 4 inches above floor safety systems 70EL (P870-51A-G4)

EIP-2-001 ATT 9 USER AID 2 Revision F EIP-2-001 REV - 26 PAGE 144 of 144