IR 05000338/2006302

North Anna Retake Exam 05000338-06-302 Draft Job Performance Measures (Part 2 of 2)

ML081840502
Person / Time
Site:	North Anna
Issue date:	07/02/2008
From:	- No Known Affiliation
To:	NRC/RGN-II
References
50-338/06-302
Download: ML081840502 (63)

Text

CRITICAL STEP EXPLANATIONS:

STEP#Explanation 1&2Requiredtodeterminepath'sdose.3Requiredtodeterminepathwithlowestdose

.NAPSAdmin-3Page6of7 NAPSAdmin-3Page7of7 CANDIDATE CUE SHEET(TOBE RETURNED TO EXAMINER UPON COMPLETIONOFTASK)INITIAL CONDITIONS:*Thecrewis attemptingtoplaceasystemin service ,buttheyareunableto remotelyopena valve.*Youhavebeentaskedwithentering containment and locallyopeningthe valve.*HealthPhysicspersonnelare currently unavailable to provide assistance.*Tworoutesare availabletothe valve: oRoute1consistsof two segments.*Segment1hasyouwalkthrougha 200mRlhrgeneralfieldfor2 minutes.*Segment2hasyouwalkina300 mRlhrgeneralfieldtothe valvefor8 minutes oRoute2consistsof two segments.*Segment1hasyouwalkthrougha50 mRlhrgeneralfieldfor4minutes.

• Segment2hasyouwalkina150 mRlhrgeneralfieldtothe valvefor12 minutes o The tworoutesas detailedaretobe considered separatelyandarelistedastheround-triptimetoandfromthemanual valve.INITIATING CUE:Youareto determinewhichrouteallowsthelowestexposur I" NAPS Admin-4Page1of7 DRAFT REGION II INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE Admin-4 EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE Determine highest EPIP classification.

CANDIDATE EXAMINER DRAFT NAPS Admin-4Page2of7REGIONIIINITIALLICENSEEXAMINATIONJOBPERFORMANCEMEASURE Classify an emergency event (EPIP-1.01)

.Alternate Path: Facility JPM#: KIA Rating(s):Gen2.4.29 (2.6/4.0)Task Standard: Event is classifiedasa NotificationofUnusualEvent(NOUE)perTABB.8 Preferred Evaluation Location: Preferred Evaluation Method: Simulate_X_Perform X Simulator X Classroom_....<..:..._

References:

EPIP-1.01,"EMERGENCY MANAGER CONTROLLING PROCEDURE ,Rev.42.EMERGENCY ACTION LEVEL TECHNICAL BASIS DOCUMENT,Rev.13ValidationTime:10min.Time Critical: NO===============================================

========================

Candidate:

NAME Time Start:_Time Finish:_Performance Rating:SATUNSAT_Performance Time_Examiner:_NAME SIGNATURE/DATE================

=========================

==============================Comments SIMULATOR OPERATOR INSTRUCTIONS:

NONENAPSAdmin-4Page3of7 NAPSAdmin-4Page4of7 Tools/Equipment/Procedures Needed: EPIP-1.01,"EMERGENCY MANAGER CONTROLLINGPROCEDURE,Rev42.

EMERGENCYACTIONLEVEL TECHNICALBASISDOCUMENT,Rev.13READTO OPERATOR DIRECTIONS TO STUDENT:Iwillexplaintheinit ialconditions,andstatethetasktobeperformed.Allcontrolroomstepsshallbe performedforthisJPM

,includinganyrequired communications

.Iwillprovideinitiatingcuesandreportsonotheractionswhendirectedbyyou.Ensureyouindicatetomewhenyou understandyourassignedtask.Toindicatethatyouhavecompletedyourass ignedtaskreturn the handoutsheetIprovidedyou.

INITIAL CONDITIONS:

Unit-1 ShutdownBankshadbeenpulledandanRCSdilutionwasabouttobegin,in preparationforaunitstart-up.Duetoanincreasein containmentsumppumpingrate,thecontrolroomcrewcompletesaleakratePTand determines that unidentified RCS leakageinsideUnit

-1 containmenthasincreasedto1.01gpm.TheleakratePTwas completedat0415hours.Theoperatingcrewenteredthe applicable Technical Specification.Effortsto determinethelocationoftheleakandreducetheleakagehavebeen unsuccessful.At1300hourstheshutdownbankswereinserted.At1415hours,theOATCoperatestheSteamDumpstobegincoolingdowntheunit.INITIATINGCUE:Youarerequestedtoclassifythe emergencyeventand determineanyProtectiveAction Recommendationifrequired.Assumeany support personnel designatedbythe procedureareperform ingasrequire START TIME:_NAPSAdmin-4 Page5of 7STEP1:Determinetheeventcategoryusingthe emergencyactionleveltableindex.

-SAT STANDARD:Eventis identifiedasa"Reactor CoolantSystem"event COMMENTS: UNSAT-STEP2:Reviewthe emergencyactionleveltab associatedwiththeevent category.SAT-STANDARD: Emergencyactionleveltabisreviewed.

COMMENTS: UNSAT-STEP3:Useavailableresourcestoobtain indications of emergency conditions.

-SAT STANDARD: Conditionsarereviewed.

COMMENTS: UNSAT-STEP4:Verifythatan emergencyactionlevelhasbeen exceeded.CRITICAL STEP STANDARD:Eventisclassifiedasa NotificationofUnusualEvent(NOUE)per SATTABB.8-COMMENTS: UNSAT-ENDOFTASK TIME STOP:_

NAPS Admin-4Page6of7 CRITICAL STEP EXPLANATIONS:

STEP#Explanation4ThecandidateneedstobeabletoutilizetheprocedureanddeterminethataNotificationofUnusualEvent(NOUE)needstobedeclare NAPS Admin-4Page7of7 CANDIDATE CUE SHEET(TOBE RETURNEDTOEXAMINERUPON COMPLETION OF TASK)INITIAL CONDITIONS:Unit-1ShutdownBankshadbeenpulledandanRCS dilutionwasabouttobegin,inpreparationforaunitstart-up.Duetoanincreasein containmentsumppumpingrate

,thecontrolroomcrew completes aleakratePTand determines that unidentif iedRCSleakageinsideUnit-1 containment has increasedto1.01gpm.TheleakratePTwascompletedat0415hours.Theoperatingcrewenteredthe applicable Technical Specification.Effortstodeterminethelocationoftheleakandreducethe leakagehavebeen unsuccessful.At1300hourstheshutdownbankswereinserted.At1415hours,theGATC operatestheSteamDumpstobegin coolingdowntheunit.INITIATINGCUE:Youarerequestedto classify the emergencyeventand determineanyProtectiveActionRecommendationifrequired.Assumeany support personne l designatedbythe procedureareperformingasrequire RCS Operational LEAKAGE 3.4.13 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.13 RCS Operational LEAKAGE LCO 3.4.13 RCS operational LEAKAGE shall be limited to: a.No pressure boundary LEAKAGE;b.1 gpm unidentified LEAKAGE;c.10 gpm identified LEAKAGE;d.1 gpm total primary to secondary LEAKAGE through all steam generators (SGs);and e.500 gallons per day primary to secondary LEAKAGE through anyone SG.APPLICABILITY:

MODES1,2,3, and 4.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.RCS LEAKAGEnotwithin A.1 Reduce LEAKAGEto4hours limitsforreasons within limits.other than pressure boundary LEAKAGE.B.Required Action and B.1 Be in MODE 3.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion TimeofConditionA ANDnotmet.B.2 Be in MODE 5.36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> OR Pressure boundary LEAKAGE exists.North AnnaUnits1 and 2 3.4.13-1 Amendments 231/212 RCS Operational LEAKAGE 3.4.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.4.13.1----------------

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

Not requiredtobe performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishmentofsteady state operation.

Verify RCS operat ional LEAKAGE is within limits by performance of RCS waterinventorybalance.

FREQUENCY 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> SR 3.4.13.2 Verify steam generator tube integrity is inaccordancewiththe Steam Generator Tube Surveillance Program.Inaccordancewiththe Steam Generator Tube Surveillance Program North AnnaUnits1 and 2 3.4.13-2 Amendments 231/212 VIRGINIA POWER NORTH ANNA POWER STATION___EMERGENCY PLAN IMPLEMENTING*.ll.,;1'o r.3YJ_.-...NUMBER PROCEDURE TITLE REVISION EPIP-l.01 EMERGENCY MANAGER CONTROLLING PROCE DURE 42 (W ith 3 Attachments)

PAGE 1 of 7*PURPOSE To asses s potential emergency conditions and initiate corrective actions.ENTRY CONDITIONS Any of the following:

1.Another station procedure directs initiation of this procedure.

• 2.A potential emergency condition is reported to the Shift Manager.*Approvalson File Effective Date 7-I'D-t26

• NUMBER PROCEDURE TITLE REVISION EPIP-l.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 42 PAGE2of7 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED***************************************CAUTION: Declaration of the highest emergency class for wh ich an EmergencyActionLevel is exceeded shall be made.***************************************NOTE: The PCS is potentially unreliable in the eventofan earthquake.

Therefore.PCS parametersshouldbe evaluated for accuracy should this s ituation occur.*__1 EVALUATE EMERGENCY ACTION LEVELS:a)Determine event category usingAttachment1.

EMERGENCY ACTION LEVEL TABLE INDEX b)Review EAL Tab associated with event category c)Use Control Room monitors.PCS.and outside reports to get indications of emergency conditions listed in the EAL Table d)Verify EAL-CURRENTLY EXCEEDED (STEP 1 CONTINUED ON NEXT PAGE)d)1£basis for EAL no longer exists when discovered AND no other reason s exist for an emergency declaration

.THEN do the following:

• RETURN TO procedure in effect.*GO TO VPAP-2802.

NOTIFICA TIONS AND REPORTS.to make one-hour.non-emergency reports for classification without declaration.

1£EAL was NOT exceeded.THEN RETURN TO procedure in effec *NUMBER PROCEDURE TITLE REVISION EPIP-I.OI EMERGENCY MANAGER CONTROLLING PROCEDURE 42 PAGE3of7 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*I EVALUATE EMERGENCY ACTION LEVELS: (Continued)e)Record procedure initiation:*By: Date: Time: f)Initiate a chronologicallogof events g)Declare position of Station Emergency Manager NOTE: Assembly.accountability and/or initiation of facility staffing maynotbe desired during certain situations (e.g..security event.severe weather.anticipated grid disturbance)

or may have already been completed.

These activities shouldbeimplementedas quickly as achievable given the specific situation.*______2 CHECK-CONDITIONS ALLOW FOR NORMAL IMPLEMENTATION OF EMERGENCY RESPONSE ACTIONS 1£deviationfromnormalemergency response actions warranted.

THEN do the following:a)Referto Attachment 3.Considerations for Operations Response Under Abnormal Conditions.

b)Consider applicability of 50.54(x).c)1£classification/as sembly announcement deferred.THEN GO TOStep *NUMBER PROCEDURE TITLE REVISION EPI P-l.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 42 PAGE4of7 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED**__3 NOn FY PLANT STAFF OF ALERT OR HIGHER CLASSIFICATION:

a)Check classification

-ALERT OR HIGHER b)Check ifemergencyassemblyand accountability

-PREVIOUSLY CONDUCTED c)Have Control Room sound EMERGENCYalarmand makeannouncementon station Gai-Tronicssystemas follows: "(Emergency classification)

has been declared as the result of (event)d)Repeat Step 3.c a)GO TOStep4.b)Do the following:

1)Have Control Room sound EMERGENCYalarmand makeannouncementon station Gai-Tronicssystemas follows: "(Emergency classification)hasbeen declared as the result of (event)"All Emergency Response personnel report to your assigned stations""All contractor personnel not responding to theemergencyand all visitors report to the Security Building""All other personnel reporttoyour Emergency Assembly Areas"2)Repeat RNO Step 3.b.1.3)GO TOStep *NUMBER PROCEDURE TITLE REVISION EPIP-l.Ol EMERGENCY MANAGER CONTROLLING PROCEDURE 42 PAGE5of7 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION: Continue through this and all further instructions unless otherwise directed to hold.***************************************______4 INITIATE SUPPORTING PROCEDURES:

a)Direct Emergency Communicators to initiate the following procedures:

1)EPIP-2.0l.NOTIFICATION OF STATE AND LOCAL GOVERNMENTS 2)EPIP-2.02.

NOTIFICATION OF NRC b)Direct HP to initiate EPIP-4.0l.

RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE c)Establishcommunicationswith Security Team Leader: 1)Provide Security with current emergency classification 2)Notify Security which Operations Shift is designated for coverage 3)Direct Security to initiate EPIP-5.09.

SECURITY TEAM LEADER CONTROLLING PROCEDURE

• NUMBER PROCEDURE TITLE REVISION EPIP-l.OI EMERGENCY MANAGER CONTROLLING PROCEDURE 42 PAGE6of7 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*__5 CHECK TSC-ACTIVATED__6 IMPLEMENT EPI P FOR EMERGENCY CLASSIFICATION IN EFFECT:*Notification of EventGO TO EPIP-I.02, RESPONSE TO NOTIFICATION OF UNUSUAL EVENT*Alert-GO TO EPIP-I.03, RESPONSE TO ALERT*Site Area Emergency-GO TO EPIP-I.04, RESPONSE TO SITE AREA EMERGENCY*General Emergency-GO TO EPIP-I.05, RESPONSE TO GENERAL EMERGENCY 1£TSC NOT activated.

THEN do the following:

a)Have STA report to the Control Room.b)Notify Manager Nuclear Operations or Operations Manager On Call.c)Consider having Radiological Assessment Director report to the Control Room.d)WHEN relief SEM arrives.THEN perform turnover using EPIP-I.OI.

Attachment 2.Turnover Checklis *NUMBER PROCEDURE TITLE REVISION EPI P-l.01 EMERGENCY MANAGER CONTROLLING PROCEDURE 42 PAGE 7 of 7 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED**__7 NOTI FY OFFSITE AUTHORITI ES OF EMERGENCY TERMINATION:

a)State and local governments (made by LEOF or CEOF when activated)

b)NRC__8 NOTI FY STATION PERSONNEL ABOUT THE FOLLOWING:

• Emergency termination

• Facility de-activation

• Selective release of personnel*Completionand collection of procedures*Recovery__9 TERMINATE EPI P-l.01:*GivecompletedEPIPs.formsand other applicable records to Nuclear Emergency Preparedness (TSC Emergency Procedures Coordinator if TSC activated)*Completed By: Date: Time:-END-

• NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT PAGE INDEX 1 1 I"\-F L1.?*****************************************************************************

CAUTION:*Declaration of the highest emergency class forwhichan EAL is exceeded shall be made.*EmergencyActionLevels shall be conservatively classified based on actual or anticipated plant conditions.

EVENT CATEGORY: I.2.3.4.5.*6.7.8.9.10.II.12.13.Safety, Shutdown,orAssessment System Event A Reactor CoolantSystemEvent B Fuel FailureorFuelHandling Accident CContai nment Event D Radioactivity Event E DELETED LossofSecondary Coolant.G Electrical Failure H Fire ISecuri ty Event JHazardto Station Operation K Natural Events L Miscellaneous Abnormal Events M NUMBER ATTACHMENT TITLE REVISION EPIP-l.01 EMERGENCY ACT ION LEVEL TABLE 42 ATTACHMENT (TAB A)PAGE SAFETY.SHUTDOWN.OR ASSESSMENT 1 SYSTEM EVENT2of42 CONDITION/APPLICABILITY INDICATION CLASSI FICATION CAUTION: EAL C.2 is duplicated below for cross-reference/comparison to EAL A.1: C.2.Probable large radioactivity release initiated by loss of heat sink leading to cor e degradation MODES1.2.3&4 Lossof Main Feedwater Sy stem.Conden sate Sy stem and Auxiliary Feedwater Sy stem G ENERAL E MERGENCY1.Lossof function needed for unit HSD condition MODES1.2.3&4*Total loss of the Charging/SI System OR Total loss of the Main Feedwate r and AuxiliaryFeedwatersystems SITE AREA EMERGENCY 2.Failure of the*Reactor trip setpoint and SITE AREA Reactor Protection coincidences

-EXCEEDED EMERGENCY System to init iate and complete a AND required trip while at power*Automatic trip from RPS-FAI LED MODES 1&2 AND*Manual t rip from Control Room-FAILED

• NUMBER ATTACHMENT TITLE REVISION EPIP-l.Ol EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB A)PAGE SAFETY*SHUTDOWN.OR ASSESSMENT 1 SYSTEM EVENTof 47 INDICATION CONDITION/APPLICABILITY 3.Inability to monitorasi gnifi cant transient in progress MODES1.2.3&4**Most (>75%)or all annunciatoralarmson panels"A" to"K"-NOT AVAILABLE ANDAllcomputer monitoring capability (e.g.*PCS)-NOT AVAILABLE AND CLASSI FI CATI ON SITE AREA EMERGENCY***4.Evacuation of Main Control Room with control not established within15minutes ALL MODES*Significant transient-IN PROGRESS (e.g.*reactor trip.SI actuation.

turbine runback>25%thermal reactorpower.thermal power oscillations

>10%)AND Inability to directly monitor anyone of the following using Control Room indications:

• Subcriticality*CoreCooling*HeatSink*Vessel Integrity*Containment Integrity EvacuationoftheControl Room SITE AREA with local shutdown control not EMERGENCY established within15minutes

• NUMBER ATTACHMENT TITLE REVISION EPI P-l.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB A)PAGE SAFETY, SHUTDOWN, OR ASSESSMENT 1 SYSTEM EVENT 4 of 47 INDICATION

• Lossofanyof the following systems:*Service Water*Component Cooling.RHR CONDITION/APPLICABILITY 5.Total loss of function needed for unit CSD condition MODES 5&6*Secondarysystem cooling capability

-UNAVAILABLE AND CLASSI FI CATI ON ALERT AND*RCS temperature GREATER THAN 140 0 F 6.Failureof the*Reactor trip setpoint and ALERT Reactor Protection coincidences

-EXCEEDED System to a*trip which ta es the AND Reactor Subcritical

• Automatic trip from RPS-MODES 1&2 FAI LED AND*Manual trip-REQUIRED AND*Manual trip from Contro l Room-SUCCESSFUL

• NUMBER ATTACHMENT TITLE REVISION EPIP-l.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB A)PAGE SAFETY.SHUTDOWN.OR ASSESSMENT 1 SYSTEM EVENT I)of4?INDICATION CONDITION/APPLICABILITY 7.Unplanned loss of safety system annunciators with compensatory indicators unavailableora transient in progress MODES1.2.3&4**Unplanned lossofmost (>75%)or all annunciator alarms on panels"A" to"K" for GREATER THAN 15 minutes ANDAllcomputer monitoring capability (e.g..PCS)-NOT AVAILABLE OR CLASSI FICATION ALERT*8.Evacuation of Main Control Room required ALL MODES Significant transientINITIATED OR IN PROGRESS (e.g..reactor trip.SI.turbinerunback>25%thermal reactor power.thermal power oscillations

>10%)Evacuation of the Control Room with shutdown control established within 15 minutes ALERT 9.Inability to reach required mode within technical specification limits*Intentional reduction inpower.loador temperature lAWT.S.Action StatementHAS COMMENCEDNonFICAn ON OF UNUSUAL EVENT*MODES1.2.3&4 AND*T.S.Action Statement time limit for modechange CANNOT BE MET

• NUMBER ATTACHMENT TITLE REVISION EPI P-l.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB A)PAGE SAFETY.SHUTDOWN.OR ASSESSMENT 1 SYSTEM EVENT6of42*Main Steam INDICATION CLASSI FI CATI ON*RCS NOTI FICATION OF UNUSUAL*RCS pressure-LESS EVENT THAN 2000 psig OR NOT Protection System-IN SERVICE AND*Any indication after lift or actuation that Pressurizer Safety or PORV-REMAINS OPEN AND*Flow-UNISOLABLE

• CONDITION/APPLICABILITY 10.Failureofa safety or relief valve to close after pressure reduction.

which may affect the health and safety of the public MODES1.2.3.4&5*Excessive Steam Generator Safety.PORV or DecayHeatReleaseflowas indicated by rapid RCS cool down rate AND*11.Unplanned loss ofmostor all safety system annunciators for greaterthan15 minutes MODES1.2.3&4**Main Steam pressure greaterthan100psi below setpoint of affected valve Unplanned lossofmost<>75%)or all annunciators on panels"A" to"K" for GREATER THAN15minutes NOTIFICATION OF UNUSUAL EVENT

• NUMBER ATTACHMENT TITLE REVISION EPI P-l.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (T AB A)PAGE SAFETY*SHUTDOWN.OR ASSESSMENT 1 SYSTEM EVENT 7 of 42**CONDITION/APPLICABILITY 12.Lossof communications capability ALL MODES INDICATION

• Station PBX phone systemFAI LED*Station Gai-tronics system-FAILED AND*Station UHF radio systemFAILED CLASSI FI CATI ON NOTI FICATION OF UNUSUAL EVENT NUMBER ATTACHMENT TITLE REVISION EPI P-1.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB B)PAGE REACTOR COOLANT SYSTEM EVENT 1 R of 47 Any t woofa).b)orc)e xist G ENERA Landthe third i s imminent: EM ERG ENCY a)Fuel clad integrity failur e a s indicated byanyo f th e fol lo wing:*RCS specific activity greaterthanorequalto300.0 dose equ ivalent 1-131 OR CONDI TION/APPLICABILITY1.Lossof2of3 fis sion product ba rri e rs w it h potential loss of3rdbar rier AL L MODES I NDICATION CLA SSI FICATION5or more cor e exit thermocou ple s great erthan1 200 0 F OR Conta inmen t H igh Range Radiation Monitor RM-RMS-165.-166or RM-RMS-265.-266 GR EATER T H A N 1.88xl0 2 R/hr b)Loss of RCS int egrity a s indirated byanyo f th e f o ll o wing:*RCS pressure greater than 2735psig OR Los sofReactor Coolantinp rogre ss c)Los sofcontainment integr i ty as indicated byanyoft he fol l o wing:*Containmen t pre s sur e g reater t han 60 psia a nd not decrea sing OR Releasepathto environment

-EXIST S

• NUMBER ATTACHMENT TITLE REVISION EPI P-l.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB B)PAGE REACTOR COOLANT SYSTEM EVENT 1 gof42 CONDITION/APPLICABILITY INDICATION

• • 2.Fuelfa ilure with steam generator tube rupture ALL MODES Any two of a),b)orc)exist and the third is imminent:a)Fuel clad integrity failure as ind icated byanyof the following:

• RCS specific activity greater than 300 dose equivalent 1-131 OR 5 or more core exit thermocouples GREATER THAN 1200 of OR High Range Letdown radiation monitor 1-CH-RI-128or2-CH-RI-228 GREATER THAN 5.9x10 4 mR/hr b)Steam Generator tube rupture as indicated bybothof the following:*SI coincidence

-SATISFIED AND*Steam Generator tube rupture-IN PROGRESS c)Loss of secondary integrity associated with ruptured steam generatorpathwayas indicated byanyof the following:*Steam Generator PORV-OPEN OR Main Steam Code Safety Valve-OPEN Lossofseconda ry coolant outside containment

-IN PROGRESS CLASSI FICATION GENERAL EMERGENCY NUMBER ATTACHMENT TITLE REVISION EPI P-l.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB B)PAGE REACTOR COOLANT SYSTEM EVENT 1 10of42 CLASSIFICATION SITE AREA EMERG ENCY INDICATION

• Primarysystem leak (LOCA)-IN PROGRESS AND Safety Injection-REQUIRED AND*RCS subcoolingbasedon Core Exit Thermocouple sLESS THAN 30°F 3.Res 1 eak rate exceeds*makeup capacity MODES 1.2.3.&4 CONDITION/APPLICABILITY OR RCS inventory cannot be maintainedbasedon pressurizer level or RVLIS indication

• • 4.Gross primary to secondary leakage with loss of offsite power MODES1.2.3.&4 Steam Generator Tube Rupture-IN PROGRESS AND Safety Injection-REQUIRED AND*VentVrntA MGPI Monitor SITE AREA EMERGENCY RM-VG-179 GREATER THAN 1.25x10 8 Steam Generator Blowdown monitor on affected pathway RM-SS-122.-222 RM-SS-123.-223 RM-SS-124.-2211 GREATER THAN 1x10 6 cpm AND*A subsequent loss of offsite power indicated by zero volts on voltmeters for 4160VbusesD.E.&F

• NUMBER ATTACHMENT TITLE REVISION EPI P-l.01 EMERGENCY ACTION LE VE L TABLE 42 ATTACHMENT (TAB B).PAGE REACTOR COOLANT SYSTEM EVENT 1 11 of 47*Pressurizer level cannot be ALERT maintained greater than 20%withone(1)

Charging/SI pump in operation AND*RCS inventory balance indicates leakage-greaterthan50 gpm CONDITION/APPLICABILITY 5.RCS leak rate limit-EXCEEDED MODES1.2.3.&4 INDICATION CLASSI FI CATI ON6.Gros s primary to'secondary leakage MODES1.2.3.&4 primary to leakage of offsite AND*VentVentA MGPI Monitor ALERT ALERT Intentional reduction in power.load or temperature lAW T.S.3.4.13to-secondary leakage LCO Action Statement Steam Generator Tube Rupture IN PROGRESS AND Safety Injection-REQUIRED*Exces sive secondary with loss power MODES 1.2.3.&4 7.*RM-VG-179 GREATER THAN 1.73x10 6 Steam Generator Blowdown monitor on affected pathway RM-SS-122.

-222 RM-SS-123.-223 RM-SS-124*-224 GREATER THAN 1x10 5 cpm AND*A subsequent loss of offsite power indicated by zero volts on voltmeters for 4160V buses D.E.&F

• NUMBER ATTACHMENT TITLE REVISION EPIP-l.01 EMERGENCY AC TION LEVEL TABLE 4 2 ATTACHMENT (TAB B)PAGE REACTOR COOLANT SYSTEM EVEN T 1 1 2 of 42**CONDITION/APPLICABILITY 8.RCS operational leakage requiring plant shutdown I AW 1.S.3.4.13 MODES1.2.3.&4 INDICATION Intentional reduction in power load or temperature lAW T.S.3.4.13 leakage limit action statement-HAS COMMENCED CLASSIFICATION NOTIFICATION OF UNUSUAL EVENT NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB C)PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT 1 n of 47 INDICATION CONDITION/APPLICABILITY 1.Probable large radioactivity release initiated by LOCA with ECCS failure leading to core degradation ALL MODES**Loss of reactor coolant in progress AND RCS specific activitygreaterthan300 dose equivalent 1-131 OR Containment High Range Radiation Monitor RM-RMS-165.

-166 or RM-RMS-265.

-266 GREATER THAN 1.88x10 2 R/hr CLASSI FI CATI ON GENERAL EMERGENCY AND*High or low head ECCS flownotbeing delivered to the core (if expected by plant conditions)

CAU TION: EAL A.l is duplicated belo w for cross-reference/comparison to EA L C.2: A.I.Lossof f unction*Total lossofthe needed for unitCharging/51System HSD con diti on SITE AREA EMERGENCY M ODES1.2.3&4 OR Total lossofthe Main Feed water and Auxiliary Fee d water syste ms 2.Probable large radioactivity release initiated by loss of heat sink leading to core degradation MODES1.2.3&4 Loss of MainFeedwaterSystem.

GENERALCondensateSystemand Auxiliary EMERGENCY Feedwater System

• NUMBER ATTACHMENT TITLE REVISION EPI P-l.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB C)PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT 1 14 of 42 INDICATION

• Turbine Driven Auxiliary Feedwater Pump not operable AND*Restoration of either of theabovenot likely within2hours**CONDITION/APPLICABILITY 3.Probable large radi oacti v i ty release initiated by failure of protectionsystemto bring Rx subcritical and causing core degradation ALL MODES 4.Probable large radioactivity release initiated by loss of AC power and all feedwater ALL MODES***Rx nuclear power after a trip-greater than 5%AND RCS pressure greater thanorequalto 2485 psig OR Containment pressure and temperature rapidly increasing Loss of all onsite and offs ite AC power AND CLASSI FI CATI ON GENERAL EMERGENCY GENERAL EMERGENCY

• NUMBER ATTACHMENT TITLE REVISION EPIP-l.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB C)PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT 1 15of42**CONDITION/APPLICABILITY 5.Probable large radioactivity release initiated by LOCA with loss of ECCS and containment cooling ALL MODES INDICATION*Lossof reactor coolant in progress AND*High or low head ECCS flow not being delivered to the core (if expected by plant conditions)*Containment RS sump temperature greater than 190 0F and NOT decreasing OR All QuenchSprayand Recirculation Spray systems-NOT OPERABLE CLASS!FICATION GENERAL EMERGENCY

• NUMBER ATTACHMENT TITLE REVISION EPIP-l.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB C)PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT 116of42**CONDITION/APPLICABILITY6.Core damage with possible loss of coolable geometry MODES1.2.3.&4 INDICATIONa)Fuel clad failure as indicatedbyanyof the foll owi ng:*RCS Specific activity greater than 60/lCi/gram dose equivalent 1-131 OR High Range Letdown radiation monitor 1-CH-RI-128 or 2-CH-RI-228 GREATER THAN 1.2x10 4 mR/hr ANDb)Lossof cooling as indicatedbyanyof the following:*5 confirmed core exit thermocouples greater than 1200 0 F OR Core deltaT-zero OR Core deltaT-rapidly diverging CLASSI FICATION SITE AREA EMERGENCY

• NUMBER ATTACHMENT TITLE REVISION EPIP-l.Ol EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB C)PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT 117of47 INDICATION CONDITION/APPLICABILITY7.Major fuel damage accident with radioactivity release to containment or fuel buildings ALL MODES*Water level in Rx vessel during refueling below thetopof core Water level in spent fuel pool belowtopof spent fuel CLASSI FICATION SITE AREA EMERGENCY**AND*Verified damage to irradiated fuel resulting in reading s on Vent Vent"B" MGPI monitor RM-VG-180 GREATER THAN 2.69x10 8 8.SevereFuel Clad*High Range Letdown ALERT Damage radiation monitor MODES 1.2.3.&4l-CH-RI-128 or 2-CH-RI-228 Increases to GREATER THANHiHi Alarm setpoint (representing 1%fuel failure)within30minutesandremains for at least15minutes OR*ReS specifi c activity-greaterthan300 dose equivalent 1-131

• NUMBER ATTACHMENT TITLE REVISION EPI P-l.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB C)PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT 1 1R of 47 CLASSIFICATION ALERT INDICATION

• Verified accident involving damage to irradiated fuel AND*Health Physics confirm s fission product release from fuel OR CONDITION/APPLICABILITY9.Fuel damage accident with release of radioactivity to containment or fuel buildings ALL MODESVentVent"B" MGPI monitor RM-VG-180 GREATER THAN1.99x10 6

• 10.Potential for fuel damage to occur during refueling MODE 6 Continuing uncontrolled decrease of water level in Reactor Refueling Cavity orSpentFuel Pool ALERT*

• NUMBER ATTACHMENT TITLE REVISION EPI P-1.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB C)PAGE FUEL FAILURE OR FUEL HANDLING ACCIDENT 1 19 of 4?CONDITION/APPLICABILITY11.Fuel clad damage indication MODES1.2.3.&4 INDICATION

• Intentional reduction inpower.loador temperature lAW reactor coolant activityT.S.Action Statement-HAS COMMENCED OR High Range Letdown radiation monitorl-CH-RI-128or 2-CH-RI-228 Increases to GREATER THAN Hi Alarm setpoint (representing 0.1%fuel failure)within 30 minutesandremains for for at least 15 minutes CLASSI FICATI ON NOTI FICATION OF UNUSUAL EVENT**12.Independent Spent Fuel Storage Installation (lSFSI)event ALL MODES*Verified Sealed Surface Storage Cask (SSSC)seal leakage OR Sealed Surface Storage Cask (SSSC)droppedor mishandled NOTI FICATION OF UNUSUAL EVENT

• NUMBER ATTACHMENT TITLE REVISION EPI P-1.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB D)PAGE CONTAINMENT EVENT 1?O of 4?INDICATION CONDITION/APPLICABILITY1.Extremelyhigh containment radiation.

pressure and temperature MODES 1.2.3.&4*Containment High Range radiation monitor RM-RMS-165.-166or RM-RMS-265.

-266 GREATER THAN3.76x10 2 R/hr CLASSI FICATION GENERAL EMERGENCY*Containment pressure greaterthan45 psia and not decreasing

• 2.High-high containment radiation.

pressure.and temperature MODES1.2.3.&4*Containment temperature greater than 280 0F Containment High Range radiation monitor RM-RMS-165.-166or RM-RMS-265.-266 GREATER THAN 1.88x10 2 R/hr SITE AREA EMERGENCY**Containment pressuregreaterthan27.75 psia and not decreasing Containment temperaturegreater than 200 of

• NUMBER ATTACHMENT TITLE REVISION EPIP-l.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (T AB D)PAGE CONTAINMENT EVENT 1 21 of 42**CONDITION/APPLICABILITY 3.HighContai nment radiation.

pressure and temperature MODES1.2.3.&4 INDICATION*Containment High Range radiation monitor RM-RMS-165.-166or RM-RMS-265.

-266 GREATER THAN 8l.5R/hr*Containment pressure greater than 17 p sia OR Containment temperaturegreaterthan150 0F CLASSI FI CATION ALERT

• NUMBER ATTACHMENT TITLE REVISION EPI P-l.01 EMERGENCY ACTION LEV EL TABLE 42 ATTACHMENT (T AB E)PAGE RADIOACTIVITY EVENT 1 22 of 47 INDICATION CONDITION/APPLICABILITY 1.Release imm inent or in progress and siteboundarydoses projectedtoexceed 1.0 Rem TEDEor5.0 Rem Thyroid CDE ALL MODES*HP assessment indicates actual or projected dose s at or beyond site boundary greater than 1.0 Rem TEDE or 5.0 Rem Thyroid CDE CLA SSI FI CATION G ENERAL EMERGENCY**2.Releaseimminentor in progress and siteboundarydoses projected to exceed 0.1 Rem TEDE or 0.5 Rem Thyroid CDE ALL MODES*HP assessment indicates SITE AREA actual or projected dose at EMERGENCY or beyond Site Boundaryexceeds0.1 Rem TEDE or 0.5 Rem Thyroid CDE

• NUMBER ATTACHMENT TITLE REVISION EPIP-l.Ol EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB E)PAGE RADIOACTIVITY EVENT 1?1 of 47**CONDITION/APPLICABILITY 3.Effluent relea se greater than 10 times ODCM allowable 1 imit ALL MODES INDICATION a)Any of the following monitors indicate valid readings above the specified values for greater than15minute s*Clarifier Effluent RM-LW-l11 GREATER THAN 4.8 x 10 5 cpm*Discharge Canal RM-SW-130 or-230 GREATER THAN 5 x 10 4 cpm*VentVentA MGPI RM-VG-179 GREATER THAN 1.73 x 10 6*VentVentB MGPI RM-VG-180 GREATER THAN 1.99 x 106

• Process Vent MGPI RM-GW-178 GREATER THAN 1.35 x 10 7 OR b)HP assessment (sample resultsordose projections)

indicate greater than 10 times ODCM allowable 1 imit CLASSI FICATION ALERT

• NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB E)PAGE RADIOACTIVITY EVENT 1 24 of 47 CONDITION/APPLICABILITY 4.High radiation or airborne contamination levels indicate a severe degradation in control of radioactive material ALL MODES INDICATION Valid readingsonanyof the following monitors have increasedbya factorof1000andremain for at least 15 minutes:*Ventilation Ventsample gaseous or particulate monitor I RM-VG-106or-105*Control Room Area I RMS-157 CLASSI FICATION ALERT*Aux.Bldg.Control Area I RMS-154**Decon.Bldg.Area I RMS-151**Fuel PoolBridgeArea I RMS-153*New fuel storage Area I RMS-152*Laboratory Area I RMS-158*Sample Room Area I RMS-156

• NUMBER ATTACHMENT TITLE REVISION EPIP-l.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB E)PAGE RADIOACTIVITY EVENT 1 25of42**CONDITION/APPLICABILITY 5.Effluent release greater than ODCM allowable limit ALL MODES INDICATION a)Any of the following monitors indicate valid readingsabovethe specified value for morethan1hour:

• Clarifier Effluent RM-LW-111 GREATER THAN 4.8x10 4 cpm*Discharge Canal RM-SW-130or-230 GREATER THAN 5 x 10 3 cpm*VentVent A MGPI RM-VG-179 GREATER THAN 1.73 x 10 5

• VentVent B MGPI RM-VG-180 GREATER THAN 1.99 x 10 5*Process Vent MGPI RM-GW-178 GREATER THAN 1.35 x 10 6 OR b)HP assessment (sample resultsordose projections)

indicates greater than ODCM allowable limit CLASSI FICATION NOTI FICATION OF UNUSUAL EVENT NUMBER ATTACHMENT TITLE REVISION EPI P-1.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB G)PAGE LOSS OF SECONDARY COOLANT 1 2fi of 42 CONDITION/APPLICABIL ITY INDICAT ION 1.Major secondary line break w it h sign ificant primary to secondary1eakageand fuel damage indicated Conditionsa)andb)exist with c): a)Uncontrolled loss of secondary coolant-IN PROGRESS AN D CLASSI F I CATION SITE AREA EMERGENCY b)RCS specific activity exceeds MODES1.2.3.&4 limitsofT.S.Figure 3.4.16-1 OR High Range Letdow n radiation monitor 1-CH-RI-128 o r 2-CH-RI-228 GREATER THAN Hi Alarm setpoint ANDc)Vent VentA MGPI Monitor RM-VG-179 GREATER THAN 6.21 x 107OR Affected path way Steam Gene rator S lo wdo wn monitor RM-SS-122.-123.-124.-222.-223.-224 GRE ATER THAN1x10 6 cpm OR Affecte d p at h way MainStea m Line Hig h Range monitor RM-MS-170.-171.-172.-270.-271.-272 GRE ATER THAN12.2 mR/hr

• NUMBER ATTACHMENT TITLE REVISION EPI P-l.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB G)PAGE LOSS OF SECONDARY COOLANT 1'17of4?***CONDITION/APPLICABILITY 2.Majo r secondary line break with significant primary to secondary leakage MODES1.2.3.&43.Major secondary line break MODES1.2.3.&4 INDICATION Uncont rolled loss of secondary coolant-IN PROGRESS AND*VentVentA MGPI Monitor RM-VG-179 GREATER THAN1.76x106 Steam Generator Blowdown monitor on affected pathway RM-SS-122.-123.-124 RM-SS-22 2.-223.-224 GREATER T HAN lx l05 cpm OR Main Steam Line High Range monitor on affected pathway RM-MS-170.-171.-172 RM-MS-270.

-271.-272 GREATER THAN 0.14 mR/hr Uncontrolled loss of secondary coolant-IN PROGRESS CLASSI FICATION ALERT NOTI FICATION OF UNUSUAL EVENT

• NUMBER ATTACHMENT TITLE REVISION EPI P-l.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB H)PAGE ELECTRICAL FAILURE 1 7R of 47 CONDITION/APPLICABILITY INDICATION CLASSIFICATION l.Lossof offsite and The following conditions exist SITE AREA onsite AC power for for greaterthan15 minutes: EMERGENCY more than 15 minutes*Ammeters for 4160V Reserve ALL MODES Station Service Buses D.E.&F all indicate-zero (0)amps AND*Ammeters for 4160V Station Service Buses A.B.&Call indicate-zero (0)amps AND*Ammeters for 4160V EmergencyBusesH&J both indicate-zero (0)amps2.Loss of all onsite The following conditions exist SITE AREA*DC power for greater for greater than 15 minutes: EMERGENCY than 15 minutes*All station battery ALL MODES voltmeters indicate zero (0)volts AND*No light indication available to Reserve Station Service breakers1501.15Eland15Fl

NUMBER ATTACHMENT TITLE REVISION EPI P-I.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB H)PAGE ELECTRICAL FAILURE 1?g o f 4?CONDITION/APPLICABILITY INDICATION CLASSI FICATION CAUTION: EAL A.l i s duplicat ed b elow for cros s-re f erenc e/c omparison to EAL H.3: A.I.Lossoffu nction needed for unit HSD condition MOD ES 1.2.3&4*Total lossoft he Charg ing/SI Sy stem OR Total loss of the Main Feed water and Auxiliary Feedw ater System s SITE A REA E ME R GENCY 3.Loss of all offsite*Ammeter s for 4160V Reserve ALERT and onsite AC power Station Service Bu ses D.E.&F all indicate-ze ro (0)ALL MODES amps AND*Ammeters for 4160V Station Service Buses A.B.&Call indicate-zero (0)amps AND*Ammeters for 4160V EmergencyBusesHand J both indicate-zero (0)amps 4.Lossof all onsite*All station battery ALERT DC power voltmeters indicate-zero (0)volts ALL MODES AND*No light indication availabletoReserve Station Service Breakers 1501.15E1and15Fl

• NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB H)PAGE ELECTRICAL FAILURE 1:i0of42*CONDITION/APPLICABILITY 5.Loss of offsite power or onsite AC power capabil ity ALL MODES INDICATION*Unit main generator and both emergency diesel generatorsoutof service OR Loss of all 34.5 KV reserve station service buses CLASSI FICATION NOTIFICATION OF UNUSUAL EVENT

• NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTI ON LEVEL TABLE 42 ATTACHMENT (TAB 1)PAGE FIRE 1 11 of 47***CONDITION/APPLICABILITY 1.Fire resulting in degradation of safety systems MODES1.2.3.&4 2.Fire potentially affecting station safety systems MODES1.2.3.&4 3.Fire lasting greater than 10 minutes in ProtectedAreaor Service Water Pump/Valve House ALL MODES INDICATION Fire which causes major degradationofa safety system function required for protection of the public AND*Affected systems are causedtobe NOT operable as definedbyTech.Specs.

Firewhichhas potential for causing a safetysystemnotto be operable as defined by Tech.Specs.Fire within the Protected Area or Service Water Pump/Valve House which isnotunder control within10minutes after FireBrigade-DISPATCHED CLASSI FI CATION SITE AREA EMERGENCY ALERT NOTIFICATION OF UNUSUAL EVENT

• NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB J)PAGE SECURITY EVENT 1 1/of 4/**CONDITION/APPLICABILITY1.Lossof physical control of the facil ity ALL MODES 2.Immi nent loss of physical control of the plant ALL MODES 3.Ongoing Security compromise ALL MODES INDICATION A hostile force has taken control of plant equipment such that plant personnel are unable to operate equipment required to maintain safety functions*A confirmed security event within a plant Vital Area OR A notification from the site security force that an armed attack.explosive attack.airliner impact.or other hostile action is occurringorhas occurred within the Protected Area*A confirmed security event within the Protected Area A validated notification from NRCofan airliner attack threat less than 30 minutes away A notification from the site security forceofan armed attack.explosive attack.airliner impact.or other hostile action within the Owner Controlled Area CLASSIFICATION GENERAL EMERGENCY SITE AREA EMERGENCY ALERT

• NUMBER ATTACHMENT TITLE REVISION EPI P-l.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (T AB J)PAGE SECURITY EVENT 1 33 of 47 CONDITION/APPLICABILITY INDICATION CLASSIFICATION

• • 4.Security threat.unauthorized attempted entry.or attempted sabotage ALL MODES*A credible site-specific security threat notification OR A validated notification from NRC providing informationofan aircraft threat A confirmed security event which indicates a potential degradation in the level of safety of the plantsuchas a violent civil disturbance or strike action.attempted sabotage.a hostage/extortion situation.

or attempted intrusion in the Protected Area NOTI FICATION OF UNUSUAL EVENT

• NUMBER ATTACHMENT TITLE REVISION EPI P-l.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (T AB K)PAGE HAZARD TO STATION OPERATION 1 34 of 42 CONDITION/APPLICABILITY 1.Aircraft damage to vital plant systems MODES1.2.3.&4 2.Severe explosive damage MODES1.2.3.&4 INDICATION Aircraft crash which affect s vital structuresbyimpactor fire Explosion which results in severe degradationofanyof the following systems required for safe shutdown: CLASSI FICATION SITE AREA EMERGENCY SITE AREA EMERGENCY*CVCS System OR ECCS System OR**3.Entryof toxic or flammable gases into plant vital areas other than the Control Room MODES1.2.3.&4**Main/Auxiliary Feedwater System Uncontrolled release of toxicorflammable agents greater than life threatening or explosive limits in Vital A reas AND Evacuation of Vital Area other than Control RoomREOUIRED OR Significant degradation of plant safetysystems resulting in lossofa safety system function required for protection of the public SITE AREA EMERGENCY

• NUMBER ATTACHMENT TITLE REVISION EPI P-l.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB K)PAGE HAZARD TO STATION OPERATION 1 of 47 CONDITION/APPLICABILITY 4.Severe missile damage to safety systems MODES1.2.3.&4 INDICATION Missile impact causing severe degradation of safety systems required for unit shutdown CLASSI FICATION SITE AREA EMERGENCY 5.Aircraft crash on the facil ity ALL MODES Aircraft crash within the ProtectedAreaor Switchyard (other thanimpactfrom airliner attack-See TAB J)ALERT 6.Explosion damage to Unplanned explosion resulting ALERT facility in damage to plant structure or equipment that affects plant ALL MODES operations

• 7.Entry of toxic or Notification of uncontrolled ALERT flammable gases or release of toxicorflammable liquids into plant agent which causes: facil i ty*Evacuation of personnel ALL MODES from plant areas AND*Safety related equipment is rendered inoperable 8.Turbine failure or Failure of turbine/generator ALERT missile impact rotating equipment resulting in casing penetration MODES 1&2*

• NUMBER ATTACHMENT TITLE REVISION EPIP-l.Ol EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB K)PAGE HAZARD TO STATION OPERATION 1:if)of42 CONDITION/APPLICABILITY INDICATION CLASSI FICATION 9.Missile damage to safety relatedequipmentor structures MODES1.2.3.&4 Notification of missile impact ALERT causing damage to safety relatedequipmentor structure s*10.Aircraft crash or unusual aircraft activity ALL MODES*Confirmed notification of an aircraft crash within the site boundary (other thanimpactfrom airliner attack-See TAB J)OR Unusual aircraft activity in the vicinity of the siteasdeterm ined by the Operations Shift Ma nager/Station Emergency Manager or the Security Shift Supervisor NOTI FICATION O F UNUSUAL EVENT*11.Train derailment within Protected Area ALL MODES 12.Explosion within Protected Area ALL MODES 13.Onsite or nearsite release of toxic or flammable liquids or gases ALL MODES Confirmed report of train derailment within Pro tected Area Confirmed reportofunplanned explosion within Protected Area Notificationofunplanned release of toxicorflammable agent s which may affect safety of station personnel or equipment NOTIFICATION OF UNUSUAL EVENT NOTIFICATION OF UNUSUAL EVENT NOTI FICATION OF UNUSUAL EVENT

• NUMBER ATTACHMENT TITLE REVISION EPI P-l.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (T AB K)PAGE HAZARD TO STATION OPERATION 1: nof42**CONDITION/APPLICABILITY 14.Turbine rotating component failure with no casing penetration MODES 1&2 INDICATION Failure of turbine/generator rotating equipment resulting in immediate unit shutdown CLASSI FICATION NOTIFICATION OF UNUSUAL EVENT NUMBER ATTACHMENT TITLE REVISION EPIP-l.0 1 EME RG ENC Y ACTION LEVE L TAB LE 42 ATTACHMENT (TAB L)PAGE NA T URAL EV ENTS 1 3 8 o f 4 2 CON DITIO N/APPLIC ABILI TY I NDICATION C L AS SI FIC ATIO N l.Earthquak e greater*Confirmed earthquake SIT E AR EAthanorequa l to DB E whic h activate s the Event EMER GENCY le ve ls I n dicator on the Strong MotionAccelerograph MOD ES 1.2.3.&4 AND*Alarmsonthe Peak S hock Annunci ator i nd icate a horizon talmotionof g reaterthanorequalto 0.12gora vertical motion of greate rthanorequal to 0.08g 2.Su stainedwindsin Sustained w i nd s 1 50mph SITE AR EA excessofdesign OR GREATER experienced E MERGENCY level s experiencedorpro ject ed or projected M ODES1.2.3.&4 3.NOT USED

• NUMBER ATTACHMENT TITLE REVISION EPIP-l.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB l)PAGE NATURAL EVENTS 1of42 CONDITION/APPLICABILITY INDICATION CLASSIFICATION 4.Earthquake greater*Confirmed earthquake which ALERT thanorequalto OBE activates Event Indicator levels on the Strong Motion Accelerograph ALL MODES AND*Alarms on thePeakShock Annunciator indicate a horizontalmotionof greater thanorequalto 0.06gora verticalmotionof greater thanorequalto 0.04g 5.Tornado striking Tornado visually detected ALERT facil ity striking structures within the ProtectedAreaor Switchyard ALL MODES*6.Hurricane winds Hurricanewinds120 mph ALERT near design basis OR GREATER experienced level experienced or projected or projected ALL MODES*7.Flood near design levels ALL MODESFloodin the Lake Anna ALERT Reservoir with indicated levelgreater than 263 feet MSL

• NUMBER ATTACHMENT TITLE REVISION EPI P-l.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB l)PAGE NATURAL EVENTS 140of42 CONDITION/APPLICABILITY 8.Earthquake detected ALL MODES9.Tornado within Protected Area orSwitchyard ALL MODES INDICATION Confirmed earthquake which activatestheEvent Indicator on the Strong Motion Accelerograph Tornado visually detected within Protected Area or Switchyard CLASSI FICATION NOTI FICATION OF UNUSUAL EVENT NOTI FICATION OF UNUSUAL EVENT 10.Hurricane force*ConfirmationbyWeather NOTI FI CATION winds projected Center that hurricane force OF UNUSUAL ons ite within12 winds (greaterthan73 mph)EVENT hours onsite within 12 ours ALL MODES*1l.50 year floodFloodin the Lake Anna NOTI FICATION Reservoir with indicated level-OF UNUSUAL ALL MODES greater than 254 feet MSL EVENT*

• NUMBER ATTACHMENT TITLE REVISION EPIP-l.01 EMERGENCY ACTION LEVEL TABLE 42 ATTACHMENT (TAB M)PAGE MISCELLANEOUS ABNORMAL EVENTS 1 41of42 CONDITION/APPLICABILITY INDICATION CLASSI FICATION 1.Any major internal or external events which singlyorin combination cause massive damage to station facilities or may warrant evacuation of the public ALL MODES Shift Manager/Station Emergency GENERAL Manager judgement EMERGENCY 2.Station conditions Shift Manager/Station Emergency SITE AREA which may warrant Manager judgement EMERGENCY notification of the public near the site ALL MODES*3.Station cond itions Shift Manager/Station Emergency ALERTwhichhave the Manager judgement potential to degrade or are actually degrading the level of safety of the station ALL MODES*

• NUMBER ATTACHMENT TITLE REVISION EPIP-l.Ol EMERGENCY ACTION LEVEL TABLE.42 ATTACHMENT (TAB M)PAGE MISCELLANEOUS ABNORMAL EVENTS 142nf42 INDICATION Shift Manager/Station Emergency Manager judgement that any of the following exist:**CONDITION/APPLICABILITY 4.Station conditions which warrant increased awareness of state and/or local autho rities ALL MODES*Unitshutdown is other thanaco ntrolled shutdown Unit isinan uncontrolled condition during opera tion A condition exists which has the potential for escalation and therefore warrants notification CLASSI FICATION NOTI FI CATI ON OF UNUSUAL EVENT

• • • NUMBER ATTACHMENT TITLE REVISION EPIP-I.OI TURNOVER CHECKLIST 42 ATTACHMENT PAGE 21of1Conducta turnover between the on shift and relief SEMinac cordance with the following checklist.

U se placekeeping aid at left of item."".to track comp letion.1.Determine the status of primary responder notification.

2.Det ermine the statusof"Report of Emergency to StateandLocal Governments." EPIP-2.0I.Attachment2.Get completed copies if available.

3.Determine status of the"Report of Radiological Conditions to the S t ate." EPIP-2.01.

Attachment3.Get completed copy if available.

4.Determine stat us of Emergency Notification Sy stem (ENS)commun ications and completion statu s of NRC Event Notification Work sheet (EPIP-2.02 Attachment 1).5.Review clas sification and initial PAR status.6.Review present plant conditions and status.Getcopy of Critica l Safety Function s form.7.Review status of station firewatches and r e-establish if conditions allow.8.Determine readines s of TSC for activation.

9.Afte r all information i s obtained.transfer location to TSC.(Consider direct tran sfer of State&local notificatio ns to LEOF/CEOF.)10.Call the Control Room and asses sanychanges that may have occurred during transition to the TSC.11.When sufficient pe rsonnel are available.

the relief SEM is to assume the follow ing responsibilities from the onshift Station Emergency Manager:a.Recla ssification.

b.Protective Action Recommendations until LEOF act ivated.c.Notifications (i.e..state.local.&NRC).Upon LEOF activation.

transfer notification responsibilitie s except for the NRC ENS.d.Site evacuation authorization.

e.Emergency exposure authorization.

f.Command/controlof onsite response.12.Formally relieve the Interim SEMandas sume control i n the TSC.Announce name and facility act ivation status to facilit ***NUMBER ATTACHMENT TITLE REVISION EPIP-I.OI CONSIDERATIONS FOR OPERATIONS RESPONSE 42 ATTACHMENT UNDER ABNORMAL CONDITIONS PAGE 3Iof2 This attachment provides procedural guidance for controll ing selected emergency response actions when their implementationwouldhave adver se results.Station Emergency Manager (SEM)approval is required before any required action is postponed.

suspended or modified.The guidancebelowi s not all-inclusive.

UNANTICIPATED HAZARD EXISTS (e.g..security event.tornado or toxic release): II notifying off-duty augmentation could create a safety hazard for personnel coming to the station.THEN consider the following alternatives:

• Station Security (if available)canbe directed to notify off-duty personnel to report to the remote mustering area (Louisa Fire Training Center).*Corporate Security.at 804-273-3161.canbe directed to notify off-duty personnel to report to the remote mustering area (Louisa Fire Training Center).*Corporate Security.at 804-273-3161.canbe directed to notify corporate emergency response organizationonlyu sing CPIP-3.4.INNSBROOK SECURITY SUPPORT.*Notificationscanbe deferred unti l hazardous cond itions are resolved.II implementationofemergency response actions could compromise Security Plan response strategies.

THEN consider postponing or suspending emergency response actions until threathasbeen resolved.e.g..on-site announcement directingassemblyandemergency response facility activation.

pager activation andoutper EPIP-3.05.AUGMENTATION OF EMERGENCY RESPONSE ORGANIZATION.

dispatch of Security Team members to the LEOF per EPIP-3.04.ACTIVATION OF LOCAL EMERGENCY OPERATIONS FACILITY.and stagingofroad blocks per EPIP-5.04.

ACCESS CONT ROL.II assembling on-site personnel for accountability or activationofemergency response facilities could endanger plant personnel.

THEN consider postponingemergencyassembly until hazardous conditions are resolved.Corporate Security.at 804-273-3161.canbe directed to notify corporate emergency response organization only using CPIP-3.4.INNSBROOK SECURITY SUPPORT.Personnel in unaffected areas on-sitecanbe notified selectively.

II primary ingress/egress route is NO T available.

THEN evaluate alternate route for use during site evacuation or off-duty augmentation (e.g..access via Dyke 1).

NUMBER ATTACHMENT TITLE REVISION EPIP-I.OI CONSIDERATIONS FOR OPERATIONS RESPONSE 42 ATTACHMENT UNDER ABNORMAL CONDITIONS PAGE 32of2 ANTICIPATED SITUA TIO N (e.g., forecasted severe weatheror grid d isturbance)

1£allorpa rtoft he EROhasbeen staged i n ant icipationofa predicted event , THENnotify Securitytoomitperformanceof augmentation notification (as describedinEPIP-3.05, AUGMENTATION OF EMERGENCY RESPONSE ORGANIZATION)

.1£ade quate con trols havebeen estab lishedt o continua lly accou nt forp er s onnel stagedin a nticipationofap re dicted event, T HE N notify Securitytoomit perfo r manceofin itia l accountability (as describedin EPIP-5.03, PERSO NNEL ACCOUNTABILITY)

.1£a decision hasbeen madeto staff t he Central EOF in lieuof the LEOF , THE N n otif y Security t hatperformanceof EPIP-3.04, ACTIVA TION OF LOCA L EMERGENCY OPERAT IONS FACILITY ,isnotreq uired.1£environmental conditions are hazardous , THEN consult with Security TeamLeadera bout suspending procedural requirements for staging road blocks (lAW EPIP-5.04,A C CESSC O NTRO L).