ML023520094

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DAEC Emergency Planning Dept Procedure Transmittal Acknowledgement Memo (TAM-18) Entire EPIP Document
ML023520094
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 12/13/2002
From: Dante Johnson
Nuclear Management Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML023520094 (11)
v • d • e


Text

S NMC Committed to Nuclear Excellence DAEC EMERGENCY PLANNING DEPARTMENT PROCEDURE TRANSMITTAL ACKNOWLEDGEMENT MEMO (TAM-18)

To: NRC-NRR Document Control Desk US NRC Washington DC 20555 Re: Entire EPIP Document (Copy 28)

PSM

Title:

n/a Distribution Date: 12/06/2002 Effective Date of Change: 12/13/2002 Return by: 12/27/2002 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 Rev. 131 Rev. 132 EPIP Table of Contents Revision Rev. 2 Rev. 3 EPIP EAL-01 (PWR: 19690)

Rev. 2 Rev. 3 EPIP EAL-02 (PWR: 18510)

Rev. 2 Rev. 3 EPIP EAL-04 (PWR: 19383)

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 personnel only:

Date TAM returned:

EPTools updated:

,AO(45

ýIiEMERGENCYPLAN -IMPLEMENTING PROCEDURES Rev. 132 INDEX PAGE 1 of 7 Procedure, Title Revision -Date' Number 1.1 Determination of Emergency Action Levels 19 -09112/01

- -1.2- -Notification 27 9/2/02 1.3 Plant Assembly and Site Evacuation .. '9 09/12/01 1.4 Release of Emergency-Related Information 4 09/04/02 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 23 10/23/02 2.3 Operation of the FTS-2001 Phone Network 6 09104/02 2.4 Activation and Operation of the ORAA 8 09/12/01 2.5 Control Room Emergency Response Operation '14 10/15/01

--2.6-.. Activation and Operation of the ORAL- - 8 10115/01 2.7 Activation and Operation of the ODEF 6 10/15101 2.8 Security Threat 1 11/16/01

-3.1 - In-Plant Radiological Monitoring 12 9/2/02 3.2 Field Radiological Monitoring -13 9/2/02 3.3 Dose Assessment and Protective Action' 18 9/2/02 4.2 First Aid, Decontamination andMedical Support - 7 8/23102 4.3 Rescue and Emergency Repair Work -11 8/23/02 4.5 Administration of Potassium Iodide (KI) 6 10/15/01

. 5.2 Recovery and Re-entry 9 10/15/01

-.,EMERGENCY PLAN IMPLEMENTING PROCEDURES ' Rev. 132 INDEX PAGE 2 of 7 I

Form Title Revision Referencing Number Number Procedure CR-01 OSM/OSS Checklist Rev. 2 EPIP 2.5 CR-02 Back Panel Communicator Checklist Rev. 1 EPIP 2.5 CR-03 Dose Projection & ARM Data Sheet Rev. 0 EPIP 2.5 CR-04 Control Room to TSC Command and Control Rev. 1 EPIP 2.5 Transfer Checklist EAL-01 Abnormal Rad Levels/Radioactive Effluent Table Rev. 3 EPIP 1.1 EAL-02 Fission Barrier Table Rev. 3 EPIP 1.1 EAL-03 Hazards & Other Conditions Affecting Plant Safety Rev. 2 EPIP 1.1 EAL-04 System Malfunction Table Rev. 3 EPIP 1.1 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. 3 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 - 08 Rad & EOF Manager Checklist Rev. 6 EPIP 1.5, 3.3 EOF - 09 EOF STAIOPS 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. 2 EPIP 1.5 EOF - 12 Field Team Director Checklist Rev. 0 EPIP 1.5, 3.3 EOF - 13 Radiological Data Communicator Checklist Rev. 0 EPIP 1.5, 3.3

EMERGENCY PLAN, IMPLEMENTING PROCEDURES:, Rev. 132 PAGE 3 of 7 INDEX EOF - 14 EOF MIDAS Operator Checklist Rev. I EPIP 1.5, 3.3 EOF- 15 Radiological Data Plotter Checklist - Rev. 0 EPIP 1.5, 3.3 16 Radiological Assessment Coordinator Checklist SEOF- Rev. I EPIP 1.5, 3.3 EOFF- 17 EOF Security Access Clerk Checklist Rev. 2 EPIP 1.5

--- EOF - 18 EOF Staffig Accountability Roster Rev. 2 EPIP 1:5 EOF - 19 Drill Announcement Message Rev. 0 EPIP 1.4, 1.5 EOF - 20 Emergency Announcement Message Rev. 1 EPIP 1,4, 1.5 EOF- 21 -Personnel Access Log Rev. 1 EPIP 1.4, 1.5 EOF- 22 Registration Form - Rev. 0 EPIP 14, 1.5 EOF 2 23 Security Post Log Rev. 2 EPIP1.4,1.5 EOF- 24 First Floor Security Post Description - Rev. 2 EPIP 1.4;,1.5 EOF -25 Fourteenth'Floor Security Post Description-, Rev. 11 EPIP 1.5 EOF .27- -Status Update Message - EOF Communicator Rev. 0 EPIP 1.5 EOF - 28 Verbal Closeout Summary Rev: 0 EPIP 1.5 EOP - 29 Written Closeout'Summary Rev. 0 EPIP 1.5 EOF- 30 Status Board Rev. 0 , EPIP 1.5 EOF - 31 Access B adge Example ,- Rev. 0 EPIP, 1.5, EOF - 32 EOF Staff-Response Rev. 2 EPIP.15, EOF - 33 Recovery Issues . Rev.0 EPIP 5.2 EOF-34 EOF Activities ... .Rev. 0 - EPIP-5.2' EOF-35 Recovery Phase Plan Outline Guidance - Rev. 0 EPIP .52 EOF-"36 RE-EBtry Briefing Guide - Rev. 0 EPIP 5.2 EbOF -37 RE-Entry Debriefing Guide . Rev. 0 EPIP 5.2' EOF--38 EOF Messenger Checklist - - Rev.'0 - EPIP 1.5 EOF- 39 Plant Status Recorder Checklist-_ Rev. 0 - EPIP 'i.5, JPIC -01 JPIC Manager Checklist Rev. 4, EPIP 1.4 JPIC 03 Alliant Spokesperson Checklist Rev.3' 'EPIP 1'.4

EMERGENCY PLAN IMPLEMENTING PROCEDURES - Rev. 132 INDEX PAGE 4 of 7 JPIC - 04 Technical Liaison Checklist Rev. 4 EPIP 1.4 JPIC - 05 Sequence of Events Rev. 0 EPIP 1.4 JPIC - 06 Public Informiation Officer Support Checklist Rev. 5 EPIP 1.4 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 1.4 JPIC - 16 Assistant JPIC Manager Checklist Rev. 3 EPIP 1.4 JPIC- 17 JPIC Security Access Control Checklist Rev. 3 EPIP 1.4 K>_.

JPIC - 18 Sixth Floor Security Post Description Rev. 2 EPIP 1.4 JPIC - 19 JPIC Distribution List Rev. 2 EPIP 1.4 NOTE-01 ERO Notification - Off-hours Phone System Rev. 3 EPIP 1.2 Callout NOTE-02 ERO Notification - Alphanumeric Paging System Rev. 3 EPIP 1.2 Callout NOTE-03 Event Notification Worksheet Rev. 1 EPIP 1.2 NOTE-04 Plant Assembly Notification Rev. 2 EPIP 1.2 NOTE-05 Emergency Action Level Notification Rev. 4 EPIP 1.2 NOTE-06 Plant Page for Emergency Classification Changes Rev. 1 EPIP 1.2 NOTE-07 Basic Notification Flowpath Rev. 0 EPIP 1.2 ODEF-01 ODEF Decontamination Waiting Area Rev. 0 EPIP 2.7 ODEF-02 Floor Plan for ORAL/ODEF Rev. 0 EPIP 2.7 ODEF-03 Travel Route to ORAL/ODEF Rev. 0 EPIP 2.7 ODEF-04 12"h Avenue Entrance to ORAL/ODEF Rev. 0 EPIP 2.7

1;

-EMERGENCY PLAN IMPLEMENTING PROCEDURES Rev. 132 "INDEX PAGE 5 of 7 ORAA-01 Offsite Relocation and Assembly Area Supervisor's Rev. 1 EPIP 2.4, S..Checklist SORAA-02 Health Physics Support for the Offsite Relocation Rev.-0 EPIP 2.4

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

- Assembly Area ORAA-04 Offsite Relocation and Assembly Area . Rev. 0 EPIP 2.4 ORAA Offsite Relocation and Assembly Area Parklng and _Rev. 0 EPIP'2.4A" Vehicle Monitoring ... __,__.___

OSC-01 OSC Layout Rev. 0 'EPIP 2.1 OSC-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 OSC-07 Emergency Exposure Tracking Log Rev. 0 EPIP 2.1 OSC-08 - OSC Supervisor Checklist , Rev. 0 EPIP 2.1, OSC-09 H"ealthlPphysics Supervisor Checklist Rev.-O, EPIP 2.1 OSC-10 Electrical, Mechanical, I&C Maintenance Rev. 0 EPIP 2.1 Supervisor Checklist . ......

EMERGENCY PLAN'IMPLEMENTING PROCEDURES;_: Rev. 132 INDEX PAGE 6 of 7 OSC-1 1 Emergency Assignment Staffing Board Duties Rev. 0 EPIP 2.1 OSC-12 External Exposure Limits Rev. 0 EPIP 4.3 OSC-13 Guidance on Dose Limits for Workers Performing Rev. 0 EPIP 4.3 Emergency Services OSC-14 Guidelines Regarding Selection of Volunteers Rev. 0 EPIP 4.3 OSC-15 OSC Repair Team Work Order Rev. 0 EPIP 4.3 OSC-16 Repair Team Datasheet Flowpath Rev. 0 EPIP 4.3 PAR - 01 PAR Decision Making - Recommendations Rev. 0 EPIP 3.3 PAR - 02 PAR Decision Making - Flowchart Rev. 0 EPIP 3.3 PASE-02 Onsite Assembly Locations Rev. 2 EPIP 1.3 PASE-05 Site Evacuation Routes Rev. 1 EPIP 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-03 Site Radiation Protection Coordinator Checklist Rev. 1 EPIP 2.2 TSC-04 Technical & Engineering Supervisor Checklist Rev. 3 EPIP 2.2 TSC-05 Quality Assurance Checklist Rev. 1 EPIP 2.2 TSC-06 Security & Support Supervisor Checklist Rev. 1 EPIP 2.2 TSC-07 Administrative Supervisor Checklist Rev. 1 EPIP 2.2 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 TSC-1 1 TSC-EOF-JPIC Communicator Checklist Rev. 1 EPIP 2.2 TSC-12 ENS Communicator Checklist Rev. 2 EPIP 2.2 TSC-13 HPN Communicator Checklist Rev. 1 EPIP 2.2 TSC-14 TSC/OSC Operations Liaison Checklist Rev. 2 EPIP 2.2 TSC-15 Radiological Support Staff Checklist Rev. 1 EPIP 2.2 I

TSC- 16 Radio Operator - Offsite Checklist Rev. 0 EPIP 2.2 L ________________ .1.

..'EMERGENC.Y PLAN IMPLEMENTING.PROCEDURES7 Rev. 132 INDEX PAGE 7 of 7 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 TSC-22 I & C Engineer Checklist Rev. 0 EPIP 2.2 TSC-23 Mechanical Engineer Checklist Rev. 0 EPIP 2.2 TSC-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 Rev. 3 EPIP 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 TSC-40 ARM Locations Rev. 0 EPIP 3.1/4.3 TSC-41 PASS Capabilities Rev. 0 EPIP 3.1 TSC-42 On-Site Map Rev. 0 EPIP 3.2 TSC-43 ESB Logon Instructions (TSC/CR/EOF) Rev. 0 EPIP 2.2

jAL ABLE ABNORMAL RAD LEVELS ,DIOACTIVE .. EFFLUENT EVENT UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY AU1 AA1 ASI AGI Any Unplanned Release of Gaseous or Any Unplanned Release of Gaseous or Site Boundary Dose Resulting from an Site Boundary Dose Resulting from an 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 Offsite that Exceeds 200X 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 I

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 1 E-3 iRCl/cc for more than 60 above 3 E-2 pCi/cc for more than 15 above 6 E-2 FICi/cc for more than 15 above 6 E-1 piCi/cc for more than 15 minutes. minutes. minutes. (Dose assessment not available) minutes. (Dose assessment not available)

OR 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 1 E-1 g.Ci/cc for more than reading above 6 E+0 pCVcc1 for more than reading above 4 E+1 .Ci/ccfor more than reading above 4 E+2 pCi/cc for more than 60 minutes. 15 minutes. 15 minutes. (Dose assessment not 15 minutes. (Dose assessment not OR OR available) available)

Valid LLRPSF (Kaman) rad monitor Valid LLRPSF (Kaman) rad monitor reading above 5 E-4 iCi/cc for more than reading above 1 E-1 pCi/cc for more than I OFFSITE RAD 60 minutes. OR 15 minutes. 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 1E+3 CPS for more monitor reading above 1E+5 CPS for more than 60 minutes. than 15 minutes.

OR OR 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 tmes ODAM limit Valid perimeter radiation monitor reading of OR OR greater than 0.10 mR/hr above normal OR Valid field survey reading outside the site Valid field survey reading outside the site background for 60 minutes. Valid site boundary radiation reading of boundary >100 mR/hr or >500 mR/hr CDE boundary >1,000 mRlhr or >5,OOOmR/hr greater than 10 mR/hr above normal Thyroid. CDE Thyroid.

OR background and expected to last for 15 Valid dose assessment indicating dose minutes or longer. OR OR rates beyond the site boundary above 0.1 Dose assessment determines integrated Dose assessment determines integrated mR/hr TEDE for a period greater than 60 OR accident dose projection outside the site accident dose projection outside the site minutes. Valid Indication on MIDAS of a release boundary above 100 mrem TEDE or above boundary above 1,000 mrem TEDE or greater than 200 times ODAM limit and 500 mrem CDE Thyroid. above 5,000 mrem CDE Thyroid.

expected to last for 15 minutes or longer.

Op. Modes: ALL Op. Modes: ALL Op. Modes: ALL Op. Modes: ALL AU2 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

- U-cntrole-dioss OTreactorscavity or fuel Report of-ANY of the following.- .

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, Refueling Floor South End, or New ONSITE 3413) below 36 feet and lowering RAD 0.* Valid WR GEMAC Floodup Indication Fuel Storage Area ARM Reading CONDITIONS (LI-4541) coming on scale. above 10 mR/hr

  • 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 Op. 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 (RE9162y). -

reading greater than 15 mR/hr in the Control Room.

OR Valid area radiation monitor (RE9168),

"North CRD Module", reading greater than 500mr/hr at the Remote Shutdown Panel, 1C388.

Op._Modes: ALL EAL-01 Rev. 3 I

EAL TABLE e'

FISSION BARRIER INDICATORS FUEL CLAD BARRIER RCS BARRIER PRIMARY CONTAINMENT BARRIER ONE BARRIER AFFECTED Loss Loss Loss - None

'L Fuel damage assessment (PASAP 7.2) determines at L Valid drywell rad monitor reading above 5 R/hr after C least 5% fuel clad damage OR reactor shutdown PotentialLoss monitor reading above 3E+3 R/hr Fuel damage is indicated by any of the following: Potential 0.ORValid Loss - None drywell rad or RADIATION I i reading above 7E+2 R/hr Valid drywell rad monitorRDTOROR Valid torus rad monitor readig above IE+2 R/hr AValid torus rad monitor reading above 3E+1 R/hr Core damage assessment determines at least 20%

CORE DAMAGE VLI OR fuel clad damage

[] Coolant activity above 300gjCi/gm DOSE EQUIVALENT 1-131 PotentialLoss - None Loss Loss Loss- None "TV0 BARRIERS AFFECTED RPV Level below-25 Inches that cannot be restored 'L'RPV Level below 15 inches PotentialLoss RPV LEVEL PotentialLoss PotentialLoss - None P RPV Level below -39 inches and no injection source Is available El" RPV Level below 15 inches that cannot be restored Loss - None Loss

[*] Failure of both Isolation valves and a downstream Potential Loss pathway to the environment exists LIRCS Leakage Is above 50 GPM OR OR Unisolable primary system leakage outside the drywell as indicated by area temps or ARMs exceeding the LEAKAGE None F-]Unisolable primary system leakage outside the drywell - Max Safe Limits per EOP 3, Table 6, after as indicated by area temps or ARMs exceeding the Containment Isolation.

Max Normal Umits per EOP 3, Table 6. OR

[D' Primary containment venting performed per EOPs PotentialLoss - None Lossm Loss El Drywell pressure above 2 psig and not caused by a loss of DW Cooling

[El Rapid unexplained decrease following initial increase in pressure OR PRIMARY CONTAINMENT None SPotential Loss - None FLI Drywell pressure response not consistent wth LOCA conditions ATMOSPHERE Potential Loss IP] Torus pressure reaches 53 psig OR 2-' Drywell or torus H2 CANNOT be determined to be below 6% AND Drywell or torus 02 CANNOT be C. 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 inthe EC/OSM's judgment indicates Op. Modes: Run, Startup, Hot SID 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 primary containment barrier due 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.

IT] Loss OR 0 ]Potential Loss E- Loss OR El Potential Loss L Loss OR El]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 allIndicators, move from left to right across table, marking all applicable"L's and "P's"for each barrier, based on plantindications. Then, step Z transcribe all L's" and P's"marked on Barrier Table to the Logic Diagram (at right). "L's" and 'Ps" should be marked for each affected bamer (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 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.

F] =PotentialLoss (of a fission product barrier) - A challenge to a fission product bamer exists such that the barrier Is considered degraded in its ability to perform its safety function.

EAL-02 Rev. 3

EAL "ISLE SYSTEM MALFUNCTION EVENT TYPE UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY SUl SAl SSI SGI Loss of All Offslte Power to Essential Loss of All Offslte 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 Onsite AC Power to Essential Busses Loss of All Onslte AC Power During Cold Conditions Loss of Offsite Power Lasting More Than 15 Loss of Offsite Power and Loss of All Onsite Loss of Voltage on Buses 1A3 and 1A4 lasting Loss of Voltage on Buses 1A3 and 1A4 and ANY of the Minutes AC Power Lasting More Than 15 Minutes more than 15 minutes following

. Restoration of power to either Bus 1A3 or 1A4 Is 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: ALL Op. Modes:.Cold SID, Refuel, Defueled Op Modes: Run, Startup, Hot SID RPV level Indeterminate SU7 SA5 SS3 LOSS OF POWER Unplanned Loss of Required DC Power AC Power Capability to Essential Busses 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 1 and Div 2 Only one AC power source remains available Unplanned Loss of Div 1 and DIV2 125 VDC busses based on bus voltage less to supply Bus 1A3 or Bus 1A4 AND ifItIs 125 VDC busses Lasting More Than 15 than 105 VDC Indicated lost, a Station Blackout will occur. Minutes.

AND Failure to restore power to at least one required 125 VDC bus within 15 minutes from time of lass Op. Modes: Cold SID, Refuel Op. Modes: Run, Startup, Hot SID Op. Modes: Run, Startup, Hot SID Op. Modes: Run, Startup, Hot SID 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 EntryInto 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 Limits required to maintain cold shutdown OR AND Reactor CANNOT be brought subcntical See Fission Barrer Table nst

2. With CONTAINMENT CLOSURE established, temperature conditions exist Op. Modes- Run, Startup, Hot SID INABILITY TO that either SS5 MAINTAIN SHUTDOWN (a) Cause reactor coolant temperature Loss of Water Level Inthe Reactor Vessel SHUTDOWN 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 nse approaching 212°F RPV Level below 15 Inches Op. Modes: Run, Startup, Hot SD 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 Annunication or Indication in the Control System AnnunIcation 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 1C05 lasting more the following than 15 minutes AND compensatory non- than 15 minutes and EITHER, alarming Indications are available

  • Loss of annunciators on panels 1C03, Significant transient In progress 1C04 and 1C05 AND INSTRUMENTATION I Op. Modes: Run, Startup, Hot SID Loss of compensatory non-alarming
  • Loss of compensatory non-alarming COMMUNICATION .

Indications SU6 Indications Unplanned Loss of All OnsIte or OffsIte 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-f*ng .ENS,microwave and police . . .

radio) Op. Modes. ALL Op. Modes- Run, Startup, Hot SID Op. Modes: Run, Startup, Hot SID SU4 Fuel Clad Degradation Valid Pretreat RM-4104 rad monitor reading above 4E+3 mRPhr See Fission BamerTable See Fission Barrier Table See Fission Barner Table COOLANT ACTIVITY OR Coolant activity above 1.2 iCI/ml DOSE EQUIVALENT 1-131 Op. Modes* Run, Startup, Hot S0D SU5 RCS Leakage Unidentified or pressure boundary leakage COOLANTLEAKAGE greater than 10 GPMOR See Fission Barner Table See Fission Bamer Table See Fission Barrier Table Identified leakage greater than 25 GPM OR Main steam line break as determined from annunciators or plant personnel report.

OpModes* Run, Startup, Hot SID5 I EAL-04 Rev. 3

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