ML022470081

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Revised Epips, Including Rev. 127 to EPIP TOC, Rev. 2 to EPIP EAL-04, Rev. 2 to EPIP EAL-03, Rev. 2 to EPIP EAL-02 & Rev. 2 to EPIP EAL-01
ML022470081
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 08/08/2002
From:
Nuclear Management Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
EPIP EAL-01 Rev. 2, EPIP EAL-02 Rev. 2, EPIP EAL-03 Rev. 2, EPIP EAL-04 Rev. 2, EPIP EAL-TOC Rev. 2
Download: ML022470081 (11)
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Text

Committed to Nuclear Excellence DAEC EMERGENCY PLANNING DEPARTMENT PROCEDURE TRANSMITTAL ACKNOWLEDGEMENT MEMO (TAM-41)

To: NRC-NRR Document Control Desk US NRC

.Washington DC 20555 Re: Entire EPIP Document (Copy 28)

PSM

Title:

n/a Distribution Date: 08/08/2002 Effective Date of Change: 08/15/2002 Return by: 08/29/2002 Please perform the following to your assigned manual. If you have any questions regarding this TAM please contact Don A. Johnson at 319-851-7872.

REMOVE INSERT EPIP MASTER (PWR: -) Rev. 126 Rev. 127 EPIP EAL-04 (PWR: 17651) Rev. 1 Rev. 2 EPIP EAL-03 (PWR: 17649) Rev. I Rev. 2 Rev. 1 Rev. 2 EPIP EAL-02 (PWR: 17647)

EPIP EAL-01 (PWR: 17646) Rev. I Rev. 2 "s ifIkbýe, PERFORMED BY:

Print Name Sign Name Date Please return to: K Dunlap PSC/Emergency Planning 3313 DAEC Rd.

Palo, IA 52324 To be completed by DAEC EP personnelonly:

Date TAM retumed:

EPTools updated:

I

-Procedure_ Title Revision Date_

Number 1.1- 'Determination of Emergency Action . _19 09112101

_______ Levels - " ...

1.2- -Notification 26 08124/01 i 1.3 'Plant Assembly and Site Evacuation' 9 09/12/61 1.4...---- Release of Emergency-Related 3 091/12/01

, , 4. Information ""...

1.5' .- Activation and Operation of the EOF 3 , .10/16/00',

2.1 :.- 'Activation and Operation of the osc -.13 09/12/01 2.2 .. .Activation and operation of the TSC 22 02/22/02 2.3 1. Operation of the FTS-2001 Phone- 5- 09/12/01 -- I

___""____ Network 2.4' Activatiori and Operation of the ORAA '

81' 09112/01' 2.5 ;Control Room Emergency Response 14 " 10/15/01

_Operation 2.6 'Activation and Operation of the ORAL - 8 . - - 10/15/01 2.7 .Activation and Operation of the ODEF 6 . 10/15/01 2.8 . Security Threat, - . 1 11/16/01 t 3.1 In-Plant Radiological Monitoring 11 10/15/01 3.2 . Field-Radiological Monitoring 12. .. 1-0/15/01 3.3 - DoseAssessment'and Protective Action -- IT" 17 10/15/01 4.2 First Aid, Decontamination and Medical 6 10/15/01..

_______

  • _ ;Support 4.3 Rescue and Emergency Repair Work , ' 10 ' ' 10/15/01 4.5 'Administration 6f Potassium Iodide (KI) -6 ---- 10/15/01 5.2 :Recovery and Re-entry . 9 10/15/01

EMERGENCY PLAN IMPLEMENTING PROCEDURES Rev. 127

'INDEx PAGE 2 of 6 Form . Title - . Revision Referencing',

Number, Number Procedure CR-01 OSM/OSS Checklist '- " Rev. 2 EPIP 2.5 I CR-02 Back Panel Comiriunicator Checklist " - Rev.. I EPIP 2.5' CR-03 Dose Projection & ARM Data Sheet Rev.0 , EPIP 2.5 CR-04 Control Room to TSC Cdmmand and Control .. Rev.1 EPIP 2.5, Transfer Checklist.

EAL-01 Abnormal Rad Levels/Radioactive Effluent Table Rev. 2 EPIP 1.1 EAL-02 FMission Barrier Table ,-Rev. 2o, EPIP1.Il EAL-03 Hazards & Other Conditions Affecting Plant Safety 2 Rev: 2 EPIP 1.1 "

EAL-04 System Malfuncion Table - -Rev. 2' EPI* LI EOF - 02 NRC - HPN Communicator Checklist Rev. 3 EPIP 1.5 EOF - 03, Technical Recorder Checklist " '- Rev.2. EPIP 1.5" EOF -04 Summary of Computer Data Backup Collection - . ,Rev. 1 EPIP 1.5-,

Activities.

EOF - 05, EOF Information Services Representative Checklist . Rev. 2., - EPIP 1.5":

EOF -06 DAEC Key Parameter Log , Rev; 0' EPIP 1.5,'

EOF - 07 Emergency Response and Recovery Director Rev- 3 EPIP 1.5 Checklist EOF Rad & EOF Mnager Checklist -Rev. 5 EPIP 1.5,3.3' EOF - 09 EOF STA/OPS Liaison Checklist Rev.0 EPIP 1.5-,

EOF - 10 EOF-TSC Communicator'Checklist Rev. 3 EPIP 1.5 EOF - 11 Support Services Coordinator Checklist Rev. 1 EPIP L5 12, SEOF-Field Team Director Checklist' - ' Re. 0 EPIP 1.53.33 EOF- i3 RadiologicalData Communicator Checklist *. ' " -Rev.0 EPIP 1.5,3.3, Ivý

EMERGENCY PLAN IMPLEMENTING PROCEDURES Rev -127.

"INDEX PAGE 3 of 6 I EOF -14 EOF MiDAS Operator Checklist - --Rev. I EPIP 1.5,3.3*

EOF-15-- Radiological DataPlotter Checklist - Rev. 0 EPIP 1.5,3.3 EOF-16-- Radiological Assessment Coordinator Checklist -Rev. I EPIP 1.5, 3.3 EOF - EOF Security Access Clerk Checklist - Rev. 1 EPIP 1.5 O"F - EOF Staffing Accountability Roster - Rev.w2 - EPIP 1.5 EOF -19 -DIlAnnouncement Message - --Rev. 0 EPIP 1.4, 1.5,

-tOF-'20 Emergency Announcement Message - -Rev. 0 -EPIP 1.4,-i.5 EOF Personnel Access Log .. ...- Rev. I EPIP 1.4,1.5 EOF- 22 Registration Form -, , - Rev. 0 EPIP 14,1.5 EOF - 23'- Security Post"Log - Rev.1 - -EPIP 1.4,1.5 EOF - 24 First Floor Security Post Description -"Rev.- I ... EPIP 1.4,1.5' EoF -.25 Fdurteenth Floor Security Post Description Rev. I -EPIP 1.5 K-i Rev.1.0 EPIP 1.5-1OF:-27, -Status Update Message - EOF Communicator, -

EOF - 28 Vrbal Closeout Summary Rev. 0 EPIP 1.5 EO'P- 29 Written Closeout Summary -Rev. 0, EPiPI.5 OF StatusBoard' - Rev.0 -EPIPI.5 EOF -31 Access B adge Example . , Rev.0 EPIP 1.5 EOFI32, EOFStaýfResponse , Rev.2_- . EPIP.15 EOF 733 -Recovery Issues Rev. 0"-- EPJP 5.2 i "EoF-34 EOF Activiti4es Rev. 0 EPIP 5.2 EOF-35. Recovery Phase Plan Outline Guidance -,Rev. 0 . EPIP .52 EOF -36, R-E--Entry* Briefing Guide Rev..0 EPIP 5.2 EOF, 37 "'RE-E*tryIDelriefing Guide -. . Rev. 0 EPIP 5.2 JPIC- 01 JPIC Manager Checklist Rev. 4 EPIP 1.4 JPIC5 0ý-3" Alliant Spokesperson Checklist Rev. 3 EPIp 1.4 JPIC -04 Technical Liaison Checklist -Rev. - .EPIP 1.4 JPIC - 05 Sequence of Events Rev. 0 EPIP 1.4

5,,.., -

Ji I- EMERGENCY PLAN IMPLEMENTING PROCEDURES Rev."127 L iNDEX jPAGE 4 of 6 of 6 JPIC - 07 Logistics Coordinator Checklist' -Rev. 4 . EPIP 1.4,.

JPIC - 08 Logistics Support Checklist Rev. 4 EPIP 1.4 JPIC- 09 Audiovisual Support Checklist Rev. 4 EPIP, 1.4 JPIC - 11 Rumor Control Coordinator I Checklist - Rev. 3 EPIP 1.4-"

JPIC - 12 Rumor Control Event Summary Log --Rev. 1 EPIP 1:4 JPIC -13 Rumor Control Coordinator II Checklist Rev. 2 EPIP 1.4 JPIC - 14 Public Rumor Control Checklist Rev. 2 EPIP 1.4 JPIC -15 News Media Rumor Control Checklist -"Rev. 4 EPIP 1A..

JPIC- 16 Assistant JPIC Manager Checklist Rev. 3 EPIP 1.4, JPIC - 17 JPIC Security Access Control Checklist- Rev. 3 EPIP 1.4 JPIC - 18 Sixth Floor SecurityPost Description - Rev. 2 EPIP 1:4 JPIC- 19 JPIC Distribution List .. Rev. 2 EPIP 1.4 NOTE-01 ERO Notification - Off-hours Phone System Callout Rev. 2 EPIP 1.2 NOTE-02 ERO Notification--Alphanumeric Paging System - Rev. 2 EPI, 1.2 2 Callout NOTE-03 EVent Notification Worksheet ---Rev. I EPIP 1.2' NOTE-04 Plant Asembly Notification Rev. 1" EPIP 1.2>

NOTE-05 Emergency Action Level Notification- Rev. 4- EPIP 1.2' NOTE-06 Plant Page f6riEmergency Classification Changes " Rev.0 EPIP 1.2 ODEF-01 ODEF Decontamination Waiting Area 'Rev. 0' EPIP 2'.7_1 ODEF-021 Fl6or Plan for ORATJODEF Rev., 0 EPIP 2.7 ObEF-03 Travel Route' to ORAIJODEF Rev. 0 EPIP 2.7 ODEF-04 12th Avehu&eEntrance to ORAL/ODEF Rev. 0 EPIP 2.7j ORAA Offsite Relocation and Assembly Area Supervisor's, Rev. I EPIP 2.4 Checklist ORAA-02 Health Physics Support for the Offsite Relocation and . Rev. 0- EPIP 2.4.

Assembly Area-ORAA-03 Security Support for the Offsite Relocation and Rev. 0' EPIP 2.4

_____ Assembl Area-

EMERGENCY PLAN IMPLEMENTING PROCEDURES Rev. 127:

"INDEX PAGE 5 of 6 I ORAA-05 Offsite Relocation ýnd Assembly AreaParking and Rev. 0 EPIP 2A b -

-- Vehicle Monitoring' . . . . .. . _.. . . __.______... .

OSC-01 OSCLayout.. . . .. Rev. 0 EPIP2.1, 6SC-02 OSC Organization Chart . .Rev. 0 -EPIP 2.1 OSC-03 Minimum Staffing Level - Rev. 0 ---- EPIP 2.1 OSC-04 Recommended Log Entry Topics Rev. 0 EPIP 2.1' OSC-05 -Emergency Event Log Sheet . Rev.0- EPIP 2.1 OSC-06 Personal Statement Concerning Incident Rev. 0 'EPIP 2.1-0SC-07 -Emergency Exposure Tracking Log Rev.- 0 EPIP 2.1 6SC-08 OSC Supe risor Checklist .Rev. 0 EPIP 2.1 OSC-09. Health Physics Sup6rvisor Checklist Rev. 0 "-EP.P 2.1 k-OS Eiectrical, Mechanical, 1&C Maintenance Supervisor Rev. 0 EPIP 2.1 Checklist OSC1I1 Emergency AMsignment Staffing Bb&d DMities Rev. 0 EPIP 2.1 PASE-02 OnsiteAsseniblyLocations Rev'. 2 EPiP 1.3 PASE-05 Site Evacuation Routes Rev.-O: EtAIP 1.3 SAM-01 - -EOP-SAG Transition Checklist ... . .Rev. 0 EPIP 2.2 TSC-01 Emergency Coordinator Checklist .. Rev. 3 -EPIP 2.2 TSC-02 TSC Supervisor Checklist . -Rev. -2 EPIP 2.2 TSC Site Radiation Protection Coordinator Checklist - Rev. 1 EPIP 2.2' TSC-04 Týchnical & Engineering Supervisor Checklist - __-Rev.'2 EPIP 2.2 TSC-05--- Quality Assurance Checklist - Rev. I -EPIP 2.2 TSC-066i Security & Support Supervisor Checklist . .Rev. -1 EPIP 2.2 TSC-07 Administrative Supervisor Checklist .- -...

Rev. 1 .

-TSC-08 - Material Management Supervisor Checklist Rev.1- , EPIP 2.2 TSC-09 -- TSC-CR-OSC Communicator Checklist --Rev. 2 - EPIP 2.2 TSC-10 CR-TSC-OSC Communicator Checklist - - Rev.2 - -EPIP 2.2 KK TS-....I

-TSC-1 TSC-EOF-JPIC C~mlntn Communicator Commudcto Checlist Checklist -..... Rv-]Rev: i - EPIP 2.2 T.Rr-l19 E-NkIR Cnmminml'tor rhodc.liqt 'Rev, 2 FPlP ?.9.

I F TSC-14 TSC/OSC Operations Liaison Checklist, Rev. 2 EPIP 2.2 TSC-15 Radiological Suppoit Staff Checklist Rev. 1EPIP 2.2 ,

TSC-16 Radio Operator - Offsite Checklist Rev. 0 EPIP-2.2i .

TSC-17 Radio Operator - Onsite Checklist Rev. 0- EPIP*2.2!

TSC-18 TSC MIDAS Operator Checklist Rev 0 EPIP 2.2,:

TSC-19 Technical & Analysis Engineer Checklist Rev. 1 EPIP 2.2 TSC-20 TSC Operations Supervisor Rev. 2 EPIP 2.2 TSC-21 Electrical Engineer Checklist - Rev. 0 -EPIP 2.2

'2, TSC-22 I & C Engineer Cheklist Rev. 0 EPIP 2.2 TSC-23 Mechanical Engineei Checklist Rev. 0 EPIP 2.2 TS__-24 Reactor Engineer Checklist ....-_ _-" Rev. 2- EPIP 2.2, TSC-25 SPDS Operator Checklist Rev. 1 EPIP 2.2 TSC-26, Information Services Representative Checklist Rev. 2., EPIP 2.2 TSC-27, Fire Marshall Checklist Rev. 1 EPIP 2.2 TSC-28. NRC Roles During A Nuclear Power Plant Rev. 0 EPIP 2.2

- Emergency Checklist TSC-29 TSC Minimum Staffing Level Rev. 2 EPIP 2.2 Tsc-30 Emergency Action Request Log Rev. 0 EPIP 2.2 TSC-31 Radio Operator Log Rev. 0 EPIP 2.2 TSC-32 Status Board Recorder Rev. 1 EPIP 2.2 TSC-33 Typical Organization of the NRC Site Team Rev.-0 EPIP 2.2 TSC-34 TSC Organization Chart R6v. 2EPIP 2.2 TSC-35 Assignment Form Rev. 0 EPIP 5.2 TSC-36 Deactivation Report; Rev. 0 EPIP 5.2 TSC-37 Plant Operations Status - ReV. 0 EPIP 5.2 TSC-38 TSC/Control Room/OSC Activities Rev. 0 EPIP 5.2 TSC-39 TSC Clerical Checklist -Rev. 0 EPIP 2.2 3

EBO 'RLE ABNORMAL RAD LEVEL k, IOACTIVE EFFLUENT K-)

EVENT UNUSUAL EVENT ALERT SITE AREA EMERGENCY -GENERAL EMERGENCY TYPE "AU1 ' AA1 . ASI Site Boundary Dose Resulting from an AGI Site Bolndary Dose Resulting from an r.

Any Unplanned Release of Gaseous or Any Unplanned Release of Gaseous or Liquid Radioactivity to the Environment Liquid Radioactivity to the Environment Actual or Imminent Release of Gaseous Actual'or Imminent Release of Gaseous That Exceeds Two Times the Offslte that Exceeds 20OX the Offsite Dose Radioactivity Exceeds 100 mrem TEDE Radioactivity Exceeds,1000 mrem TEDE Dose Assessment Manual (ODAM) Limit Assessment Manual (ODAM) Limit and or 500 mrem CDE Thyroid for the Actual or 5000 mrem CDE Thyroid for the and Is Expected to Continue For 60 is Expected to Continue for 15 Minutes or Projected Duration of the Release Actual or Projected Duration of the Minutes or Longer or Longer Release Valid Reactor Building or Turbine Building Valid Reactor Building or Turbine Building Valid Reactor Building or Turbine Building Valid Reactor Building or Turbine Building ventilation (Kaman) rad monitor reading ventilation (Kaman) rad monitor reading ventilation (Kaman) rad monitor reading ventilation (Kaman) rad monitor reading above 6 E-2 pCi/cc for more than 15 above 6 E-1 gCi/cc for more than 15 above 1 E-3 pCVcc for more than 60 above 3 E-2 liCVcc for more than 15 minutes. (Dose assessment not available) minutes. (Dose assessment not available) minUtes. -" - minutes. -r-OR

, I ,I OR OR, OR Valid Offgas Stack (Kaman) rad monitor Valid Offgas Stack (Kaman) rad monitor Valid Offgas Stack (Kaman) rad monitor Valid Offgas Stack (Kaman) rad monitor reading above 4 E+1 j+/-COIcc for more than reading above 4 E+2 p.Cl/cc for more than reading above I E-1 p.Ci/cc for more than reading above 6 E+0 CVcc for more than 15 minutes. (Dose assessment not 15 mlnutes.,(Dose assessment not 60 minutes. 15 minutes. available) available)-------

OR OR Valid LLRPSF (Kaman) rad monitor Valid LLRPSF (Kaman) rad monitor reading above 5 E-4l tC1/cc for more than reading above I E-1 p.Ci/cc for more than 60 minutes. 15 minutes.

OFFSITE RAD OR OR CONDITIONS Valid GSW rad monitor reading above 3E+3 Valid GSW rad monitor reading above 3E+5 CPS for more than 60 minutes. CPS for more than 15 minutes...

OR" OR Valid RHRSW &ESW rad monitor reading Valid RHRSW & ESW rad monitor reading above 8E+2 CPS for more than 60 minutes, above 8E+4 CPS for more than 15 minutes.

OR OR Valid RHRSW &ESW Discharge Canal rad Valid RHRSW & ESW Discharge Canal rad monitor reading above 1IE+3 CPS for more monitor reading above 1E+5 CPS for more than 60 minutes. OR than 15 minutes. O'R Confirmed sample analyses for gaseous or Confirmed sample analyses for gaseous or liquid releases Indicates concentrations or liquid releases Indicates concentrations or release rates In excess of 2 times ODAM release rates with a release duration limits for greater than 60 minutes. expected to last for 15 minutes or longer in OR excess of 200 times ODAM limit, OR OR Valid perimeter radiation monitor reading of Valid field survey reading outside the site Valid field survey reading outside the site greater than 0.10 mR/hr above normal OR boundary >100 mR/hr or >500 mR/hr CDE boundary >1,000 mR/hr or >5,000mR/hr background for 60 minutes. Valid site boundary radiation reading of Thyroid. CDE Thyroid.

greater than 10 mR/hr above normal OR background and expected to last for 15 OR OR Valid dose assessment Indicating dose minutes or longer. Dose assessment determines Integrated Dose assessment determines Integrated rates beyond the site boundary above 0.1 accident dose projection outside the site accident dose projection outside the site mRPhr TEDE for a period greater than 60 OR boundary above 100 mrem TEDE or above boundary above 1,000 mrem TEDE or minutes. Valid indication on MIDAS of a release 500 mrem CDE Thyroid. above 5,000 mrem CDE Thyroid.

greater than 200 times ODAM limit and expected to last for 15 minutes or longer.

Op. Modes: ALL Op. Modes: ALL Op. Modes: ALL Op. Modes: ALL AUJ2 AA2 Unexpected Increase In Plant Radiation Major Damage to Irradiated Fuel or Loss of Water Level that Has or Will Result in the Uncovering of Irradiated Fuel Outside the Reactor Vessel "UR*--h6l&- 16-ssf reabcrto*rvity- or-fu'elf Repo-rofrtof AWNY of th-Fe-n0llowing:

pool water level with all spent fuel 0 Valid ARM HI RAD alarm for the assemblies remaining water covered as Refueling Floor North End, Refueling indicated by ANY of the following: Floor South End, New Fuel Storage

"* Report to control room Area, or Spent Fuel Storage Area

"* Valid fuel pool level Indication (LI-

  • Valid Refueling Floor North End, ONSITE 3413) below 36 feet and lowering Refueling Floor South End, or New RAD
  • Valid WR GEMAC Floodup indication Fuel Storage Area ARM Reading CONDITIONS (LI-4541) coming on scale, above 10 mR/hr 0 Valid Spent Fuel Storage Area ARM OR Reading above 100 mR/hr Unexpected ARM reading offscale high or OR above 1000 times normal reading. Report of visual observation of Irradiated Fuel uncovered Op. Modes: ALL OR Water level reading below 450" as Indicated on L14541 (floodup) for the Reactor Refueling Cavity that will result in Irradiated Fuel uncovering OR Valid Fuel Pool water level indication (LI-3413) below 16 feet.

O_,. Modes: ALL AA3 Release of Radioactive Material or Increases In Radiation Levels Within the Facility That Impedes Operation of Systems Required to Maintain Safe Operations or to Establish or to Maintain Cold Shutdown Valid area radiation monitor (RE9162)

- eadlnggreatertham'l5TtRPflrflne-Cotr1 Room.

OR Vaild area radiation monitor (RE9168) ,

reading greater than 500 mR/hr at the Remote Shutdown Panel, 1C388.

Op._Modes:_ALL EAL-01 Rev. 2 I

EAL TABLE FISSION BARRIER INDICATORS FUEL CLAD BARRIER RCS BARRIER PRIMARY CONTAINMENT BARRIER C ELI Fuel damage dad least 5% fuel Loss assessment (PASAP 7.2) determines at damageOR

[~J Loss Valid drywell rad monitor reading above 5 R/hr after reactor shutdown E Loss- None PotentialLoss Fuel damage is indicated by any of the following: PotentialLoss - None Valid drywell rad monitorORreading above 3E+3 R/hr monitor reading above 711+21/hr Valid torus rad monitor reading above I1E+2 R/hr RADIATION I jjC D.lidOR ryel rad Valid drywell admoiOR raigaoe7+ /rL.JOR r v Core damage assessment determines at least 20%

CORE DAMAGE Valid torus rad monitor reading above 3E+1 P/hr fuel clad damage OR WL- Coolant activity above 300pCilgm DOSE EQUIVALENT 1-131 PotentialLoss - None Loss Loss Loss- None EL RPV Level below -25 Inches U RPV Level below 15 inches PotentialLoss RPV LEVEL PotentialLoss Potential Loss - None []RPV Level w inches RLVRPV Level below 15 inchesRV l w i Loss- None Loss M] Failure of both Isolation valves and a downstream PotentialLoss pathway to the environment exists LI RCS Leakage is above 50 GPM OR [10 OR Unisolable primary system leakage outside the drywell as indicated by area temps or ARMs exceeding the LEAKAGE None jjUnisolable primary system leakage outside the drywell as indicated by area temps or ARMs exceeding the Max Safe Limits per EOP 3, Table 6, after Containment Isolation.

Max Normal Limits per EOP 3, Table 6. OR C [q Pnmary containment venting performed per EOPs PotentialLoss - None Loss m Loss SDrywell pressure above 2 psig and not caused by a .LIRapid unexplained decrease following initial increase loss of DW Cooling in pressure PRIMARY OR PotentialLoss - None Drywell pressure response not consistent with LOCA CONTAINMENT None conditions ATMOSPHERE PotentialLoss

[]PTorus pressure reaches 53 pslg OR

[ Drywell or torus H2 CANNOT be determined to be below 6% AND Drywell or torus 02 CANNOT be determined to be below 5%

Any condition which in the EC/OSM's judgment indicates Any condition which in the EC/OSM's judgment indicates Any condition which in the EC/OSM's judgment indicates EC/OSM loss or potential loss of the fuel clad barrier due to loss or potential loss of the RCS barrier due to Imminent loss or potential loss of the prirnary containment barrier due Op. Modes: Run, Startup, Hot S/ID JUDGMENT Imminent barrier degradation Degraded fission barrier barrier degradation OR Degraded fission barrier monitoring to Imminent barrier degradation OR Degraded fission monitoring capability. capability, barrier monitoring capability.

SLoss OR R Potential Loss *] Loss OR H Potential Loss El Loss OR F1 Potential Loss IMMINENT - No turnaround In safety system performance Is expected and escalation to General Emergency conditions Is expected within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

NOTE: Step 1; for all indicators, move from left to fight across table, marking all applicable "L's and P's"for each barrier,based on plant indications. Then, step 2, transcribeall "L's" and 'P's" marked on Barrier Table to the Logic Diagram (at right). "L's"and "P's should be marked for each affected barrier(working top to bottom) on the flowchart.Step 3, an "L or "P' marked for each associatedbarrierwill constitute a Logic I input. When coincidence is met, then the EAL can I be declared.

[= Loss (of a fission product barrier) - A severe challenge to a fission product barrier exists such that the barrier Is considered incapable of performing its safety function.

r*= PotentialLoss (of a fission product barrier) - A challenge to a fission product barrier exists such that the barrier is considered degraded in its ability to perform its safety function.

e.AL-02 Rev. 2

K_> K>

EAL TABLE HAZARDS and OTHER CONDITIONS AFFECTING PLANT SAFETY EVENT UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY TYPE HUI HAI Natural and Destructive Phenomena Natural and Destructive Phenomena Affecting the Protected Area Affecting the Plant Vital Area Earthquake detected per AOP 901, Earthquake peak horizontal acceleration Earthquake. above + 0.06 Gravity.

OR OR Report of tornado touching down within plant Report of tornado striking plant vital area. Safe Shutdown Areas protected area or within switchyard. Category Area OR OR Electrical Power Switchyard, 1G31 DG and Day Tank Rooms, IG21 DG Assessment has occurred,by the control room that an event Report to controlareas,.n safe shutdown room of damage affectingyaR and Day Tank Rooms, a akRos OR OR Battery Rooms, Essential Switchgear Rooms, Cable Vehicle crash into plant structures or systems Vehicle crash affecting plant vital areas. Spreading Room within protected area boundary. Heat Sink/ Torus Room, Intake Structure, Pumphouse OR OR Coolant Supply NATURAL Report of an unanticipated explosion within Sustained wind speed above 95 MPH. Containment Drywell, Torus DISASTERS the protected area boundary resulting in Emergency NE, NW, SE Comer Rooms, HPCI Room, RCIC Room, visible damage to structures or equipment. Systems RHR Valve Room, North CRD Area, South CRD Area OR OR Other Control Building, Remote Shutdown Panel 1C388 Area, Turbine failure resulting Incasing penetration Missiles affecting safe shutdown areas. Panel 1C56 Area, SBGT Room or damage to turbine or generator seals.

OR OR River level above 757 feet. River level above 767 feet. Water Level Operating Limits OR OR Max Normal Max Safe Any area water level above Max Normal Water level above Max Safe Operating Limit Room Area Indicator Operating Operating Operating Limit. In2 or more areas AND Reactor shutdown is Limit (inches) Limit (inches)

ORrequiredRHPCI Room Area LI13768 2 6 River level below 725 feet 6 Inches. River level below 724 feet 6 Inches. RCIC Room Area LI13769 3 6 A RHR Comer Room SE Area LI 3770 2 10 Op. Modes: ALL Op. Modes: ALL B RHR ComerRoom NW Area LI 3771 2 10 HU2 HA2 Torus Area LI 3772 2 12 Fire Within PROTECTED AREA Not Fire Affecting the Operability of Plant I Extinguished Within 15 Minutes of Safety Systems Required to Establish or Detection Maintain Safe Shutdown Systems &Equipment of Concern Fire inbuildings or areas contiguous to any of Fire or explosion inany of the following areas: 0 Reactivity Control the following areas not extinguished within 15 a Reactor, Turbine, Control, Admin/Secunty 9 Containment (Drywell/Torus) minutes of control room notification or v Intake structure 0 RHRICore Spray/SRV's FIRE verification of a control room alarm: @ Pump house 0 HPCI/RCIC

"*Reactor, Turbine, Control, Admin/Security AND 0 RHRSW/River Water/ESW

" Intake structure Affected system parameter Indications show 0 Onsite AC Power/EDG's

"*Pump house degraded performance or plant personnel 0 Offslte AC Power report visible damage to permanent structures 0 Instrument AC or equipment within the specified area. 0 DC Power Op. Modes: ALL Op. Modes: ALL I Remote Shutdown Capability HU3 HA3 Release of Toxic or Flammable Gases Release of Toxic or Flammable Gases

-Deemed Detrimental to Safe Operation of .-... Within a Facility Structure Which .....

the Plant Jeopardizes Operation of Systems Required to Maintain Safe Operations or to Establish or Maintain Cold Shutdown OTHER Toxic or flammable gas release affecting Toxic or flammable gas making safe HAZARDS normal operation. shutdown areas uninhabitable or Inaccessible.

AND OR FAILURES Report by local, county or State official for potential evacuation of site personnel based on offsite event.

Op. Modes: ALL Op. Modes: ALL HU4 HA4 HSI HGI Confirmed Security Event Which Indicates Security Event In a Plant Protected Area Security Event In a Plant Vital Area Security Event Resulting in Loss of a Potential Degradation in the Level of Ability to Reach and Maintain Cold Safety of the Plant Shutdown Suspected sabotage device discovered within Intrusion Into plant protected area by a hostile Intrusion Into plant vital area by a hostile Loss of physical control of the Control SECURITY plant protected area and outside plant vital force. force. Room.

area.

OR OR OR OR Suspected sabotage device discovered In Sabotage device discovered Inthe plant Sabotage device discovered In the plant vital Loss of physical control of remote plant switchyard. protected area. area. shutdown capability.

OR OR "LO" Credible Security Threat "HI" Credible Security Threat Op. Modes: ALL Op. Modes: ALL

_____________ Op. Modes: ALL Op. Modes: ALL _________________________________

HA5 HS2 Control Room Evacuation Has Been Control Room Evacuation Has Been None Initiated Initiated and Established Plant Control Cannot Be None CONTROL ROOM Control roomnevacuation initiated perControl room has been evacuated iNŽD

-EVACUATION -AOP 915, Shutdown Outside Control Room control of plant from Remote Shutdown Panel 1C388 NOT established within 20 minutes.

Op. Modes: ALL Op. Modes: ALL HU5 HA 6 HS3 HG2 Other Conditions Existing Which inthe Other Conditions Existing Which In the Other Conditions Existing Which In the Other Conditions Existing Which inthe Judgment of the ECIOSM Warrant Judgment of the EC/OSM Warrant Judgment of the ECIOSM Warrant Judgment of the ECIOSM Warrant Declaration of an Unusual Event Declaration of an Alert Declaration of a Site Area Emergency Declaration of a General Emergency Other conditions exist which in the judgment Other conditions exist which Inthe judgment Other conditions exist which Inthe judgment Other conditions exist which In the of the EC/OSM indicate potential degradation of the EC/OSM indicate that plant systems of the EC/OSM Indicate actual or likely major judgment of the EC/OSM Indicate EITHER:

ECIOSM of the level of safety of the plant. may be degraded and that Increased failures of plant functions needed for 0 Actual or Imminent substantial core JUDGMENT monitoring of plant functions is warranted. protection of the public, degradation with potential for loss of containment.

0 Potential for uncontrolled radionuclide releases which can reasonably be expected to exceed EPA PAG plume exposure levels outside the site boundary.

Op. Modes: ALL Op. Modes: ALL Op. Modes: ALL Op. Modes: ALL EAL-03 Rev. 2

.1 EAL I3m-LE K)

SYSTEM MALFUNCTION C,

EVENT TYPE UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY SUl SA1 SS1 SG1 Loss of All Offslte Power to Essential Loss of All Offsite Power and Loss of All Loss of All Offslte Power and Loss of All Prolonged Loss of All Offslte Power and Prolonged Busses for Greater Than 15 Minutes Onsite AC Power to Essential Busses Onslte AC Power to Essential Busses Loss of All Onslte AC Power During Cold Conditions vhan 15 minutes Loss of Offsite Power Lasting More Than 15 Loss of Voltage on Buses 1A3 and 1A4 lasting Loss of Voltage on Buses 1A3 and 1A4 and ANY of the Minutes more than 15 minutes following Restoration of power to either Bus 1A3 or 1A4 is Op. Modes: Cold SID, Refuel, Defueled NOT likely within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Op._Modes__ALLOp._Modes: Run, Startup, Hot SID RPV level indeterminate LOSS OF POWER SU7 Unplanned Loss of Required DC Power AC Power Capability SA5 to Essential Busses SS3 Loss of All Vital DC Power

  • RPV Level below +15 inches During Cold Shutdown or Refuel Mode Reduced to a Single Power Source for For Greater Than 15 Minutes Greater Than 15 Minutes Such That Any Additional Single Failure Would Result In Station Blackout Unplanned Loss of Div I and Div 2 Only one AC power source remains available Unplanned Loss of Div I and Div 2 125 VDC busses based on bus voltage less to supply Bus 1A3 or Bus 1A4 AND if It Is 125 VOC busses Lasting More Than 15 than 105 VDC Indicated lost, a Station Blackout will occur. Minutes AND Faiure to restore power to at least one required 125 VDC bus within 15 minutes from time of loss Op. Modes: Cold SID, Refuel Op. Modes: Run, Startup, Hot SID Op. Modes: Run, Startup, Hot SID Op. Modes: Run, Startup, Hot S/D SA2 SS2 SG2 Failure of Reactor Protection System Failure of Reactor Protection System Failure of the Reactor Protection System to Instrumentation to Complete or Initiate an Instrumentation to Complete or Initiate on Complete an Automatic Scram and Manual Scram Automatic Reactor Scram Once a Reactor Automatic Reactor Scram Once a Reactor was NOT successful and There Is Indication of an Protection System Setpoint Has Been Protection System Setpoint Has Been Extreme Challenge to the Ability to Cool the Core Exceeded and Manual Scram Was Exceeded and Manual Scram Was NOT Successful Successful RPS FAILURE Auto Scram Failure In ATWS EOP Entry into ATWS EOP- RPV Control is required AND AND AND Operator actions to reduce power are Reactor power above the APRM Downscale RPV level cannot be maintained above -25 inches None SUCCESSFUL as indicated by either Alarm on ANY valid APRM Instrument, OR OR HCL Curve (EOP Graph 4) exceeded ALL Rods Full-In. Boron Injection Initiation Temperature (BIIT)

OR Curve (EOP Graph 6) exceeded Reactor Shutdown Under All Conditions Without Boron, OR Reactor power below the APRM Downscale Alarm on ALL valid APRM Instruments Op. Modes: Run, Startup Op. Modes: Run, Startup Op. Modes: Run, Startup SU2 SA3 SS4 Inability to Reach Required Shutdown Inability to Maintain Plant In Cold Complete Loss of Function Needed to Within Technical Specification Limits Shutdown Achieve or Maintain Hot Shutdown Plant NOT brought to required mode within 1. Loss of decay heat removal systems EOP Graph 4 Heat Capacity Limit Is exceeded applicable LCO Action Statement Time Umits required to maintain cold shutdown. OR AND Reactor CANNOT be brought subcntical

2. With CONTAINMENT CLOSURE Doi See Fisson Bamer Table established, temperature conditions exist Op. Modes: Run, Startup, Hot SID

--- INABILITY"TO ----- - ..... that either - -

MAINTAIN SS5 SHUTDOWN (a) Cause reactor coolant temperature Loss of Water Level In the Reactor Vessel to exceed the Technical That Has or Will Uncover Fuel In the CONDITIONS Specification limit of 212"-F. Reactor Vessel OR (b) Result In uncontrolled temperature NO cooling method lined up or available AND rise approaching 212*F. RPV Level below 15 Inches Op. Modes: Run, Startup, Hot SID Op. Modes: Cold SID, Refuel Op, Modes: Cold SID, Refuel SU3 SA4 SS6 Unplanned Loss of All Safety System Unplanned Loss of Most or All Safety Inability to Monitor a Significant Transient Annunlcation or Indication In the Control System Annunicatlon or Indication In In Progress Room for Greater Than 15 Minutes Control Room With Either (1) a Significant Transient In Progress, or (2)

Compensatory Non-Alarming Indicators are Unavailable See Fission Bamer Table Unplanned loss of most annunciators on Unplanned loss of most annunciators on Significant transient In progress and BOTH of panels 1C03, 1C04 and 1C05 lasting more panels 1C03, 1C04 and IC05 lasting more the following than 15 minutes AND compensatory non than 15 minutes and EITHER.

alarming Indications are available

  • Significant transient in progress 1C04 and IC05 INSTRUMENTATION / Op. Modes: Run, Startup, Hot S/D AND COMMUNICATION Loss of compensatory non-alarming
  • Loss of compensatory non-alarming

$U6 Indications, Indications Unplanned Loss of All Onsite or Offslte Communications Capabilities Loss of ALL onsite telephone and radio communication methods (PABX, direct-ring.

UHF, and radiological survey radio systems)

OR Loss of ALL electronic communication methods with government agencies (PABX.

direct-nng. ENS. microwave and police radio) - - -i - - . - -* . - I -

Op. Modes: ALL Op. Modes: Run, Startup, Hot S/D Op Modes: Run, Startup, Hot S/D SU4 Fuel Clad Degradation Valid Pretreat RM-4104 rad monitor reading above 4E+3 mR/hr COOLANT ACTIVITY OR See Fission Bamer Table See Fission Bamer Table See Fission Barrier Table Coolant activity above 1.2 pCiml DOSE EQUIVALENT 1-131 Op. Modes: Run, Startup, Hot SD SU5 RCS Leakage Unidentified or pressure boundary leakage COOLANT LEAKAGE greater than 10 GPM.

OR See Fission Barrier Table See Fission Barrier Table See Fission Bamer Table Identified leakage greater than 25 GPM OR Main steam line break as determined from annunciators or plant personnel report IOp. Modes- Run, Startup, Hot SID0 I EAL-04 Rev. 2

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