ML030290322

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Emergency Implementing Procedure, EI-1, Revision 41
ML030290322
Person / Time
Site: Palisades Entergy icon.png
Issue date: 01/14/2003
From: Snuggarud R
Consumers Energy, Consumers Power Co
To: Mcknight J
Document Control Desk, Office of Nuclear Security and Incident Response
References
233527 EI-1, Rev 41
Download: ML030290322 (37)
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Text

4 Date Entered: Jan 14, 2003 TO: USNRCNVASHINGTON JMCKNIGHT Copy Number: 145 TRANSMITAL NUMBER: 233527 PROCEDURE NUMBER: El-1 TITLE: EMERGENCY CLASSIFICATION AND ACTIONS TRANSMITTAL: LISTED BELOWARE NEW/REVISED PROCEDURES WHICH MUST BE IMMEDIATELY INSERTED INTO OR DISCARDED FROM YOUR PROCEDURE MANUAL.

Action Required Section or Description REMOVE AND DESTROY El-I, R/40, ENTIRE PROCEDURE REPLACE WITH El-l, R/41, ENTIRE PROCEDURE REVISION AND APPLICABILITY WORD 2000 CONVERSION SIGN, DATE, AND RETURN THE ACKNOWLEDGEMENT FORM WITHIN 10 DAYS TO THE PALISADES PLANT DOCUMENT CONTROL SIGNATURE OR INITIALS DATE

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Procedure No El-1 Revision 41 Issued Date 1/14/03 PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE TITLE: EMERGENCY CLASSIFICATION AND ACTIONS

/ V1 V16 2 Date Procedure Sponsor MGMlynarek 1/8/03 Technical Reviewer Date RSnuggerud 1/8/03 User Reviewer Date

PALISADES NUCLEAR PLANT Proc No El-1 EMERGENCY IMPLEMENTING PROCEDURE Revision 41

-- Page I TITLE: EMERGENCY CLASSIFICATION AND ACTIONS Table of Contents 1.0 PERSONNEL RESPONSIBILITIES ......................................................................... 1 2.0 PU R PO S E ...................................................................................................................... 1

3.0 REFERENCES

....................................................................................................... 2 3.1 SOURCE DOCUMENTS ............................................................................ 2 3.2 REFERENCE DOCUMENTS ..................................................................... 2 4.0 INITIAL CONDITIONS AND/OR REQUIREMENTS ................................................. 4 5.0 PRECAUTIONS AND LIMITATIONS ......................................................................... 4 6.0 EMERGENCY CLASSIFICATION ............................................................................. 5 6.1 CLASSIFICATION/RECLASSIFICATION ................................................. 5 6.2 DETERMINATION OF EMERGENCY ACTIONS/NOTIFICATIONS .......... 7 7.0 ATTACHMENTS .................................................................................................... 7 8.0 SPECIAL REVIEWS ................................................................................................. 7 ATTACHMENTS , "Site Emergency Plan Classification" , "Emergency Actions/Notifications"

PALISADES NUCLEAR PLANT Proc No El-1 EMERGENCY IMPLEMENTING PROCEDURE Revision 41 Page 1 of 7 TITLE: EMERGENCY CLASSIFICATION AND ACTIONS USER ALERT REFERENCE USE PROCEDURE Refer to the procedure-periodically to confirm that all procedure segments of an activity will

-be or are being performed. Where required, sign appropriate sign-off blanks to certify that all segments are complete.-

1.0 PERSONNEL RESPONSIBILITIES 1.1 The Shift Supervisor shall implement this procedure and assume the title and responsibilities of the Site Emergency Director (SED) until relieved by Plant Management identified below.

Responsibilities of the Site Emergency Director can be found in Emergency Implementing Procedure EI-2.1, "Site Emergency Director."

K...ý 1.2 The normal line of succession for the SED shall conform to the individuals as listed in the Delegation of Responsibility memo published by the Plant General Manager.

The succession of Delegation of Responsibility is required by Technical Specifications ADMIN 5.1.1.

For backshifts or weekends, the Duty and Call Superintendent assumes the role of the Plant General Manager.

2.0 PURPOSE To classify those emergency-conditions that necessitate the activation to the Site Emergency Plan. To identify actions that should be taken to mitigate the consequences of an emergency.

PALISADES NUCLEAR PLANT - Proc No El-1 EMERGENCY IMPLEMENTING PROCEDURE Revision 41 Page 2 of 7 TITLE: EMERGENCY CLASSIFICATION AND ACTIONS

3.0 REFERENCES

3.1 SOURCE DOCUMENTS 3.1.1 Emergency Operating Procedure EOP-2.0, "Reactor Trip Recovery" 3.1.2 Emergency Operating Procedure EOP-3.0, "Station Blackout Recovery" 3.1.3 Emergency Operating Procedure EOP-5.0, "Steam Generator Tube Rupture Recovery" 3.1.4 Emergency Operating Procedure EOP-6.0, "Excess Steam Demand Event" 3.1.5 Emergency Operating Procedure EOP-7.0, "Loss of All Feedwater Recovery" 3.1.6 Emergency Operating Procedure EOP-8.0, "Loss of Offsite Power/Forced Circulation Recovery" 3.1.7 NUREG 0654, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," Section D 3.1.8 Palisades Site Emergency Plan 3.1.9 EPPOS No 2, "Emergency Preparedness Position (EPPOS) on Timeliness of Classification of Emergency Conditions" 3.1.10 Engineering Analysis, EA-JBB-01-04, "Failed Fuel Dose Rates on NSSS Piping" 3.2 REFERENCE DOCUMENTS 3.2.1 Emergency Implementing Procedure EI-2.1, "Site Emergency Director" 3.2.2 Emergency Implementing Procedure EI-2.2, "Emergency Staff Augmentation" 3.2.3 Emergency Implementing Procedure EI-3, "Communications and Notifications" 3.2.4 Emergency Implementing Procedure EI-5.0, "Reentry" 3.2.5 Emergency Implementing Procedure EI-5.1, "Recovery" 3.2.6 Emergency Implementing Procedure EI-6.0, "Offsite Dose Calculation and Recommendations for Protective Actions"

PALISADES NUCLEAR PLANT Proc No El-1 EMERGENCY IMPLEMENTING PROCEDURE Revision 41 Page 3 of 7 TITLE: EMERGENCY CLASSIFICATION AND ACTIONS 3.2.7 Emergency Implementing Procedure EI-6.13, "Protective Action Recommendations for Offsite Populations" 3.2.8 Emergency Implementing Procedure EI-7.0, "Emergency Post Accident Sampling and Determination of Fuel Failure Using Dose Rates" 3.2.9 Emergency Implementing Procedure El-B, "Onsite Radiological Monitoring" 3.2.10 Emergency Implementing Procedure EI-9, "Offsite Radiological Monitoring" 3.2.11 Emergency Implementing Procedure El-10, "Accident Environmental Assessment" 3.2.12 Emergency Implementing Procedure E-1l1, "Determination of Extent of Core Damage" 3.2.13 Emergency Implementing Procedure EI-12.1, "Personnel Accountability and Assembly" 3.2.14 Emergency Implementing Procedure El-13, "Evacuations/Reassembly" Ki 3.2.15 Emergency Operating Procedure EOP-4.0, "Loss of Coolant Accident Recovery" 3.2.16 Emergency Operating Procedure EOP-9.0, "Functional Recovery Procedure" 3.2.17 Palisades Administrative Procedure 3.03, "Corrective Action Process" 3.2.18 Palisades Administrative Procedure 4.00, "Operations Organization, Responsibilities and Conduct" 3.2.19 Off Normal Procedure ONP-23.1, "Primary Coolant Leak" 3.2.20 Off Normal Procedure ONP-23.2, "Steam Generator Tube Leak" 3.2.21 System Operating Procedure SOP-34, "Palisades Plant Computer (PPC) System" 3.2.22 Palisades Oil and Hazardous Materials Spill Prevention Plan 3.2.23 Technical Specifications ADMIN 5.5.1 3.2.24 Palisades Offsite Dose Calculation Manual 3.2.25 Fire Protection Implementing Procedures 3.2.26 Severe Accident Management Guidelines

PALISADES NUCLEAR PLANT Proc No El-1 EMERGENCY IMPLEMENTING PROCEDURE Revision 41 Page 4 of 7 TITLE: EMERGENCY CLASSIFICATION AND ACTIONS 3.2.27 10 CFR 50.54(x) 3.2.28 Palisades Administrative Procedure 3.01, "Plant Review Committee" 4.0 INITIAL CONDITIONS AND/OR REQUIREMENTS 4.1 This procedure shall be implemented any time an event occurs or conditions exist which, in the opinion of the Shift Supervisor/SED, may require activation of the Site Emergency Plan (SEP).

OR When events occur or conditions exist after the activation of the SEP that, in the opinion of the SED, may require reclassification, either upgrading or downgrading.

4.2 A 15-minute goal is a reasonable period of time for assessing and classifying an emergency once indications are available to Control Room operators that an Emergency Action Level (EAL) has been exceeded.

5.0 PRECAUTIONS AND LIMITATIONS 5.1 Safeguards Contingency Procedures shall be activated if, during event response, signs of tampering, sabotage or other items of suspicious nature are indicated, or if the event affects security systems, ie, loss of detection systems, loss of communications, etc.

5.2 Security Safeguard measures can only be suspended by a currently licensed Senior Reactor Operator.

PALISADES NUCLEAR PLANT Proc No El-i EMERGENCY IMPLEMENTING PROCEDURE Revision 41 Page 5 of 7 TITLE: EMERGENCY CLASSIFICATION AND ACTIONS 6.0 EMERGENCY CLASSIFICATION USER ALERT REFERENCE USE PROCEDURE Refer to the procedure periodically to confirm that all procedure segments of an activity will be or are being performed.- Where required, sign appropriate sign-off blanks to certify, that all segments are complete.

6.1 CLASSIFICATION/RECLASSIFICATION

a. Emergencies are grouped into four classifications listed below in order of severity:

Unusual Event Events are in process or have occurred which indicate a potential degradation of the level of safety ofthe'Plant. Unusual Events involve minor situations that have the potential to escalate to more serious emergencies.

Alert Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the Plant. The consideration is, as in an Unusual Event, to prepare to cope with potentially more serious emergencies. Alerts may involve releases of radioactivity limited to small fractions of the EPA Protective Guidelines.

Site Area Emergency Events are in process or have occurred which involve actual or likely major failures of Plant functions needed for protection of the public. The potential for a situation hazardous to the general public is the major concern during a Site Area Emergency. Any releases are not expected to exceed EPA Protective Action Guidelines except near site boundary.

General Emergency Events are in process or have occurred which involve actual or imminent core degradation with the potential for loss of containment integrity per LCO 3.6.1.

Releases can reasonably be expected to exceed EPA Protective Action Guidelines exposure levels offsite for more than the immediate site area.

PALISADES NUCLEAR PLANT Proc No El-1 EMERGENCY IMPLEMENTING PROCEDURE Revision 41 Page 6 of 7 TITLE: EMERGENCY CLASSIFICATION AND ACTIONS /

b. The SED shall classify emergency conditions/events as follows:
1. Determine the category that conditions/events best fit from the list of keywords below:

Alarms/Annunciators - Attachment 1, Pg 1 Communication Loss - Attachment 1, Pg 2 Dry Fuel Storage Cask-ISFSI - Attachment 1, Pg 3 Engineered Safety Features - Attachment 1, Pg 4 Evacuation - Control Room - Attachment 1, Pg 5 Fire - Attachment 1, Pg 6 Fission Product Barriers/Fuel Damage - Attachment 1, Pg 7 Hazards - General - Attachment 1, Pg 10 Miscellaneous - Attachment 1, Pg 12 Natural Phenomenon - Attachment 1, Pg 13 Plant Power - Electrical - Attachment 1, Pg 15 Primary Coolant System Integrity - Attachment 1, Pg 17 Primary Coolant System - Temperature or Pressure Attachment 1, Pg 18 Radiation Levels - Attachment 1, Pg 19 Releases - Attachment 1, Pg 20 Safety Injection System - Attachment 1, Pg 24 Secondary Side - Attachment 1, Pg 25 Security - Attachment 1, Pg 26

2. Use the keyword identified above and Attachment 1, "Site Emergency Plan Classification," to classify the conditions/event.

T' PALISADES NUCLEAR PLANT Proc No El-1 EMERGENCY IMPLEMENTING PROCEDURE Revision 41 I Page 7 of 7 TITLE: EMERGENCY CLASSIFICATION AND ACTIONS 6.2 DETERMINATION OF EMERGENCY ACTIONS/NOTIFICATIONS NOTE: The SED may assign a person to complete Attachment 2, "Emergency Actions/Notifications."

a. The numbers in the right hand column of Attachment 1 (Site Emergency Plan Classification) identify actions that should be performed for each emergency.

These numbers relate to the Actions/Notifications listed in Attachment 2 of this procedure.

b. Each action may be categorized as either:
1. Mandatory Actions (M) - Actions that shall be performed within one hour of the declaration of the emergency.

OR

2. Subsequent Actions (S) - Actions that should be performed in an expeditious manner as conditions, time, and personnel permit.

OR

3. If Needed Actions (I) - Actions that are not required in every case, but may be needed.
c. Using the "Action" column of Attachment 2, circle each action as M (Mandatory), S (Subsequent), or I (If Needed).
d. Each action on Attachment 2 should be initialed when the action is completed.

7.0 ATTACHMENTS 7.1 Attachment 1, "Site Emergency Plan Classification" 7.2 Attachment 2, "Emergency Actions/Notifications" 8.0 SPECIAL REVIEWS The scope of this procedure does not include activities that require a 50.59 review.

However, the Palisades Site Emergency Plan does require that revisions to this procedure be reviewed and approved by the Plant Review Committee (PRC), in accordance with Palisades Administrative Procedure 3.01, "Plant Review Committee."

(I ( Proc( -I-1 Attachment I Revision 41 SITE EMERGENCY PLAN CLASSIFICATION Page I of 26 ALARMS/ANNUNCIATORS CLASSIFICATION I EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS ALERT Loss of most or all alarms Observation - Modes 3, 4, 5, and 6. Mandatory: 1, 2, 3, 4, 6, 7, 8, 9, (annunciators) in Control Room. 10, 11 Example - loss of DC Panel D21-2 Ref ONP-2.3 Subsequent: 15, 21, 22 If Needed: None SITE AREA Loss of most or all alarms Observation - Modes 1 and 2 OR Modes 3, 4, Mandatory: 1, 2, 3, 4, 6, 7, 8, 9, EMERGENCY (annunciators) in Control Room 5, and 6 with transient in progress. 10,11,14, 15 AND Plant transient initiated or in progress. Example - loss of DC Panel D21-2 Subsequent: 17, 21, 22 Ref ONP-2.3 If Needed: 19, 20

( C Proc( El-1 Attachment 1 Revision 41 SITE EMERGENCY PLAN CLASSIFICATION Page 2 of 26 COMMUNICATION LOSS CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS UNUSUAL EVENT Significant loss of offsite Loss of the Emergency Notification System Mandatory: 1, 3, 4, 6, 7,12 communication capability. (ENS), and all other phones including satellite phones, that could be used to make Subsequent: 15, 22 NOTE: For failures of the Palisades notifications to Van Buren County, the State of Public Warning System, see Michigan and the NRC. If Needed: None Palisades Administrative Procedure 4.00, "Operations Organization, NOTE: The availability of one phone is Responsibilities and Conduct," sufficient to inform offsite authorities of plant Section 5.5. problems.

( C Proc( El-1 Attachment 1 Revision 41 SITE EMERGENCY PLAN CLASSIFICATION Page 3 of 26 DRY FUEL STORAGE CASK-ISFSI CLASSIFICATION EMERGENCY ACTION LEVEL M METHOD OF DETECTION A ACTIONS UNUSUAL EVENT Incident involving a loaded fuel storage Radiation level >_1 rem/hr at 1 ft from a Dry Mandatory: 1, 3, 4, 6, 7 cask OUTSIDE the Auxiliary Building. Fuel Storage Cask. I Subsequent: 15, 22 OR If Needed: 11, 13,14 Radioactive contamination level 105 dpm/1OOcm 2 beta-gamma or 103 dpm/1 00cm 2 alpha from a Dry Fuel Storage Cask.

OR Airborne radioactivity analysis indicating 'a 10 times the Effluent Concentration levels from a Dry Fuel Storage Cask. (10CFR20, Appendix B, Table 2)

OR SED opinion based on direct observation that containment/shielding of a Dry Fuel Storage Cask has been degraded due to an operational event (cask drop, missile impact, etc).

( (. Proc(k 1 Attachment 1 Revision 41 SITE EMERGENCY PLAN CLASSIFICATION Page 4 of 26 ENGINEERED SAFETY FEATURES CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS UNUSUAL EVENT Inability to reach a required mode within Plant is not brought to required Mandatory: 1, 3, 4, 6, 7 Technical Specification limits, operating mode within Technical Subsequent: 15, 22 Specifications LCO Action Statement If Needed: None Limit.

ALERT Failure of the Reactor Protection System The Reactor Protection System (RPS) Mandatory: 1, 2, 3, 4, 6, 7, 8, 9, 10, 11 (RPS) Instrumentation to complete or Setpoint exceeded AND the Automatic initiate an AUTOMATIC Reactor Scram RPS actuation did NOT OCCUR AND Subsequent: 15, 21, 22 once a Reactor Protection System Manual Reactor Trip from CO-2 or Setpoint has been exceeded AND a CO-6 was successful. If Needed: 12, 19 Manual Scram was successful.

Complete loss of any functions needed for Both S/Gs are not available for PCS Mode 5. heat removal AND uncontrolled PCS heatup is in progress AND PCS temperature will exceed 200°F in the next hour (use actual heatup rate if available). Ref ONP-17 SITE AREA Complete loss of heat removal capability. Loss of Primary Coolant System and Mandatory: 1, 2, 3, 4, 6, 7, 8, 9, 10, 11, EMERGENCY Core Heat Removal. (EOP-9.0 Heat 14, 15 Removal (HR-3) Safety Function NOT Met.) Subsequent: 17, 21,22, 23 Failure of the RPS Instrumentation to An RPS Setpoint(s) exceeded AND complete or initiate an AUTOMATIC Automatic RPS actuation did NOT If Needed: 12, 13, 19, 20 Reactor Scram and a RPS Setpoint has occur AND manual reactor trip from been exceeded AND a Manual Scram was CO-2 and CO-6 was NOT successful.

NOT successful.

GENERAL Failure of the RPS to complete an Failure of RPS to complete an Mandatory: 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, EMERGENCY AUTOMATIC SCRAM AND Manual AUTOMATIC Reactor Trip AND the 11, 13, 14, 15, Scram was NOT successful AND there is Manual Reactor Trip from CO-2 and indication of an extreme challenge to the CO-6 was NOT successful AND there Subsequent: 17, 19, 21, 22, 23 ability to cool the core. are indications of extreme challenge to the Primary Coolant System AND Core If Needed: 12, 20 Heat Removal. (EOP-9.0 Heat Removal (HR-3) Safety Function NOT Met)

(I ( Proc( -:I-1 Attachment 1 Revision 41 SITE EMERGENCY PLAN CLASSIFICATION Page 5 of 26 EVACUATION, CONTROL ROOM CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS ALERT Evacuation of Control Room Observation. Mandatory: 1,2, 3, 4, 6, 7, 8, 9, 10, anticipated or required with control of 11 shutdown systems established at local Ref ONP-25.2 stations. Subsequent: 15, 21, 22 If Needed: 12 SITE AREA Evacuation of Control Room and Observation. Mandatory: 1,2, 3, 4, 6, 7, 8, 9, 10, EMERGENCY control of shutdown systems not 11, 14,15 established at local stations within Ref ONP-25.2 15 minutes. Subsequent: 17, 21,22, 23 If Needed: 12, 13, 19, 20

(Proc( B-,1 Attachment 1 Revision 41 SITE EMERGENCY PLAN CLASSIFICATION Page 6 of 26 FIRE CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS UNUSUAL EVENT Fire within the Plant lasting more than Observation Mandatory: 1,3, 4, 6, 7, 16 10 minutes.

OR Subsequent: 15,22 Fire detection alarm, confirmed by IfNeeded: 12, 18 observation.

ALERT Fire potentially affecting safety Fire can potentially disable equipment Mandatory: 1, 2, 3, 4, 6, 7, 8, 9, 10, systems. which will result in jeopardizing safety 11,16 function(s) OR SED opinion.

Subsequent: 15, 21, 22 Ref ONP-25.1 If Needed: 12, 18 SITE AREA Fire compromising the function of Fire has disabled equipment resulting Mandatory: 1, 2, 3, 4, 6, 7, 8, 9, EMERGENCY safety systems. in jeopardized safety function(s). 10,11,14,15,16 Ref ONP-25.1 Subsequent: 17, 21,22 I

If Needed: 12, 18, 19, 20 NOTE: See General Emergency classification under the Miscellaneous category for a fire which could cause massive damage to Plant systems.

( ( ProcK. El-1 Attachment I Revision 41 SITE EMERGENCY PLAN CLASSIFICATION Page 7 of 26 FISSION PRODUCT BARRIERS/FUEL DAMAGE CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS UNUSUAL EVENT Loss or Potential Loss SEE TABLE I Mandatory: 1, 3, 4, 6, 7

of Subsequent: 15, 22 CONTAINMENT BARRIER If Needed: None ALERT Loss or Potential Loss of SEE TABLE 1 Mandatory: 1,2, 3, 4, 6,7,8,9,10,11 EITHER Subsequent: 15, 19, FUEL CLAD BARRIER 21,22 OR If Needed: 12,1 3,14 PCS BARRIER Fuel damage/handling accident with Failed fuel as indicated by abnormally High release of radioactivity to Containment or Area or Process Radiation Monitors in Auxiliary Building.* Containment and/or Auxiliary Building; confirmed by sample analysis OR SED's

  • Note: For incidents involving Dry Fuel opinion.

Storage Casks outside the Auxiliary Building. See Dry Fuel Storage Cask-ISFSI classification, page 3 of 26.

Proc No El-1 Attachment 1 Revision 41 SITE EMERGENCY PLAN CLASSIFICATION Page 8 of 26 FISSION PRODUCT BARRIERS/FUEL DAMAGE CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS SITE AREA Loss or Potential Loss SEE TABLE 1 Mandatory: 1, 2, 3, 4, EMERGENCY of any 6,7,8,9,10,11,14, TWO BARRIERS 15 Major damage to irradiated fuel in Fuel Large object damages fuel or water loss below Handling Building fuel level as indicated by abnormally High Area Subsequent: 13, Monitors in the Auxiliary Building. 17,19, 21,22,23 If Needed: 12, 20 GENERAL Loss of any SEE TABLE 1 Mandatory: 1,2, 3, 4, EMERGENCY TWO BARRIERS 5,6,7,8,9,10,11, AND 13,14,15 Potential Loss of Subsequent: 17,19, THIRD BARRIER 21,22,23 If Needed: 12, 20 K

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C Proo(, _I_-1 Attachment 1 Revision 41 SITE EMERGENCY PLAN CLASSIFICATION Page 9 of 26 FISSION PRODUCT BARRIERS/FUEL DAMAGE TABLE 1 PCS Inventory CETs LPotential Reactor water level indicates < 11 inches CETs indicate > 700°F c Loss above the bottom of the fuel alignment plate Activity CETs Containment Activity Coolant Activity > 40 iCi/gm Dose Equivalent GETs indicate > 1200°F Containment Gamma Monitor (RIA-2321 OR SLoss Iodine RIA-2322) reading > 4.0 E3 R/hr.

D See EI-7.0 See E1-11 PCS Inventory Unisolable leak exceeding the capacity of one Potential charging pump (40 gpm)

Loss X

I PCS Inventory PCS Inventory Leak greater than available makeup capacity SGTR that results in an SIAS

  • Loss as indicated by < 25°F of PCS subcooling a.

Containment Atmosphere CETs Containment Isolation Containment Activity

> 70 psia OR GETs > 1200OF for more than Asteam leak that cannot or Containm ent Gam maSPressure Potential H2 conc>4.0% OR 15 minutes OR will not be isolated by Monitor (RIA-2321 or cc Pressure > 4.0 psig with less than one full GETs > 700°F with reactor vessel EOP-5.0. RIA-2322) reading

< Loss train of Containment Cooling Equipment level < 11 inches above the > 2.5 E4 R/hr operating (EOP-9.0 CA-3 safety function not bottom of the fuel alignment plate Z et for more than 15 minutes_________ ____ ___________

ent Atm osphere SGTR Containm ent Isolation Rapid unexplained pressure drop following Primary to Secondary ieakrate greater than Containment Isolation Valve(s) not closed SLoss initial rise OR Containment pressure or sump 10 gpm with a steam leak that cannot or will following completion of EOP Supp. 6 and a o level response not consistent with LOCA not be isolated by EOP-5.0 on affected DIRECT pathway to the environment exist.

o conditions Steam Generator See NOTE 1 NOTE 1: 'DIRECT' pathways to the environment include release pathways through in-line charcoal filters. Pathways through interfacing liquid systems (eg, CCW, PCS Sample, Letdown, Demineralized Water, Clean Waste Receiver Tank Recirculation, Steam Generator Blowdown, Main Steam, Main Feedwater) should be evaluated to determine if they represent a 'DIRECT' pathway to the environment.

C ( Proc(. :l-i Attachment 1 Revision 41 SITE EMERGENCY PLAN CLASSIFICATION Page 10 of 26 HAZARDS-GENERAL CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS UNUSUAL EVENT Aircraft crash onsite or unusual aircraft Observation of event AND SED's opinion. Mandatory: 1, 3, 4, 6, 7 activity over facility which could affect Plant operation.  ! 1 Subsequent: 15, 22 NOTE: Onsite is defined as the Owner Controlled Area outside of the If Needed: 12, 18 Protected Area, not including structures.

Near or onsite explosion which could Observation of event OR notification from affect Plant operation. offsite authorities AND SED's opinion.

Near or onsite toxic or flammable gas Observation of event OR notification from which could affect Plant operation. offsite authorities AND SED's opinion.

NOTE: Refer to the Oil and Hazardous Materials Spill Prevention Plan.

Proc No El-1 Attachment 1 Revision 41 SITE EMERGENCY PLAN CLASSIFICATION Page 11 of 26 HAZARDS-GENERAL CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS ALERT Aircraft crash on facility. Observation. Mandatory: 1, 2, 3, 4, 6, 7, 8, NOTE: Facility is defined as nonvital 9,10,11 structures inside and outside of the Protected Area. Subsequent: 15, 21,22 Missile impact from whatever source Observation. If Needed: 12, 16, 18 on facility.

Known explosion damage to facility Observation.

affecting Plant operation.

Entry into facility environs of Observation OR warning from offsite authorities uncontrolled toxic or flammable gas OR detection with portable instrumentation which does affect Plant operation. AND SED's opinion.

NOTE: Refer to the Oil and Hazardous Materials Spill Prevention Plan.

SITE AREA Aircraft crash affecting Vital structures Observation. Mandatory: 1, 2, 3, 4, 6, 7, 8, EMERGENCY by impact or fire AND Plant not in 9,10, 11, 14, 15 Mode 5 or 6.

Severe damage to equipment required Observation.

for safe shutdown from missiles or Subsequent: 17,21,22,23 explosion.

Entry of uncontrolled flammable gas Observation OR SED's opinion OR detection If Needed: 12,13, 16,18,19, into Vital areas OR entry of with portable instrumentation. 20 uncontrolled toxic gas into Vital areas that constitute a safety problem AND Plant not in Mode 5 or 6.

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( C Proc( ,1 Attachment 1 Revision 41 SITE EMERGENCY PLAN CLASSIFICATION Page 12 of 26 MISCELLANEOUS CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS UNUSUAL EVENT Plant conditions exist that warrant SED's opinion. Mandatory: 1, 3, 4, 6, 7 increased awareness on the part of the Plant staff or state and/or local authorities. Subsequent: 15,22 NOTE: For Rx trips from high PCS pressure (initiating event), see "Primary If Needed: 12 Coolant System Temperature or Pressure" category. For coolant radioactivity exceeding Technical Specifications, see "Fission Product Barriers/Fuel Damage."

ALERT Plant conditions exist that warrant SED's opinion OR when 10CFR50.54(x) is Mandatory: 1, 2, 3, 4, 6, 7, 8, precautionary activation of Technical invoked. 9,10, 11 Support Center and placing Emergency Operations Facility and other emergency Subsequent: 15, 21, 22 personnel on standby.

If Needed: 12 SITE AREA Plant conditions warrant the activation of SED's opinion OR continued power Mandatory: 1, 2, 3, 4, 6, 7, 8, EMERGENCY State and County Emergency Operations operation outside the Plant's licensed 9,10, 11, 14,15 Centers and monitoring teams or a basis, when 10CFR50.54(x) is invoked.

precautionary notification to the public near Subsequent: 17, 21, 22, 23 the site.

If Needed: 12, 13, 19, 20 GENERAL Conditions exist that make release of large SED's opinion. Mandatory: 1, 2, 3, 4, 5, 6, 7, EMERGENCY amounts of radioactivity in a short time 8, 9, 10, 11, 13,14,15 possible (eg, any core melt situation).

Subsequent: 17, 19, 21,22, Any major internal or external events (eg, SED's opinion. 23 fires, earthquakes, substantially beyond design basis) which could cause massive If Needed: 12, 16, 18, 20 common damage to Plant systems.

( Proc .J-1 Attachment I Revision 41 SITE EMERGENCY PLAN CLASSIFICATION Page 13 of 26 NATURAL PHENOMENON CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS UNUSUAL EVENT Any earthquake felt in-Plant or detected on Observation (see Note 1), or Mandatory: -1, 3, 4, 6, 7 station seismic instrumentation which does NOT measurement (see Note 2).

cause damage to Plant equipment or structures.

Abnormal water levels including flood or low Flood, seiche - observation of water Subsequent: 15, 22 water or seiche. approaching 590' level.

Low water - Ultimate Heat Sink level lowers to _ 572'0" (216" below Intake Structure floor level; LI-1338)

Tornado onsite. Observation If Needed: 12 ALERT Any earthquake that exceeds operating base Observation (see Note'), or Mandatory: 1, 2, 3, 4, 6, 7, earthquake surface acceleration levels of 0.1G, measurement (see Note 2). - 8, 9,10,11 but not greater than 0.2G; no damage to equipment required for safe shutdown.

Flood, low water, or seiche near design basis. Flood, seiche - observation of water Subsequent: 15, 21, 22.

above 590' level.

Low water - Ultimate Heat Sink level lowers to 569' (LI-1 338).

Tornado striking facility. Observation If Needed: 12, 16, 18 NOTE: Facility is defined as nonvital structures inside and outside of the Protected Area.

NOTE 1 : Information on seismic disturbances can be obtained by calling the National Earthquake Information Center, Denver, Colorado, at 1-303-273-8500 (normal hours), or 1-303-273-8427, or 1-303-273-8428 (off normal hours).

NOTE 2: Seismic instrumentation is available onsite for post emergency assessment of earthquakes. There are 4 peak recording accelerometers located in Containment on elevations 590', 607', 625', and 649'; these accelerometers require offsite analysis. One strong motion accelerometer is located in the switchyard battery room; this accelerometer is capable of onsite PC analysis. Surveillance checks on these instruments are performed by the I&C Department.

Proc No El-1 Attachment 1 Revision 41 SITE EMERGENCY PLAN CLASSIFICATION Page 14 of 26 NATURAL PHENOMENON CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS SITE AREA Any earthquake that exceeds safe shutdown Measurement. Mandatory: 1, 2, 3, 4, 6, 7, EMERGENCY earthquake surface acceleration levels or 0.2G. (See Note 2 Page 13) 8,9, 10, 11, 14,15 Any earthquake that is of sufficient magnitude to Observation. Subsequent: 17,21,22 cause damage to equipment and structures (See Note 1 Page 13) needed to safely shut down the Plant. If Needed: 12, 13, 16, 18, Flood, low water, or seiche greater than design Flood, seiche - observation of water 19,20 levels OR failure of protection of Vital above 594' level.

equipment at lower levels. Low water - loss of Ultimate Heat Sink resulting in inability to operate any Service Water Pump to provide adequate cooling to vital equipment for greater than 15 minutes. This equates to an Ultimate Heat Sink level of

_<565'9" (LI-1338).

Others - observation of equipment damage.

Tornado or sustained winds in excess of design Observation.

level; ie, of sufficient magnitude to cause Notification by offsite agencies.

damage to equipment and structures needed to safely shut down the Plant.

NOTE: For earthquakes substantially beyond Design Basis, see "Miscellaneous" category under General Emergency classification.

C. (. Proc(' -I-1 Attachment 1 Revision 41 SITE EMERGENCY PLAN CLASSIFICATION Page 15 of 26 PLANT POWER - ELECTRICAL CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS UNUSUAL Both Station Batteries not available. Both battery breakers open for greater than one Mandatory: 1, 3, 4, 6, 7 EVENT hour AND EK-0548 125 DC Bus undervoltage trouble NOT alarming AND PCS temperature Subsequent: 15, 22 greater than 200OF highest TH/Tc.

If Needed: 12 Loss of offsite AC power. Loss of all qualified circuits from offsite AND onsite power is being supplied by diesel generator(s).

Loss of emergency onsite AC power. Both Emergency Diesel Generators inoperable for greater than two hours AND PCS temperature is greater than 200°F highest TH/Tc. I ALERT Loss of offsite AND onsite AC power Bus 1C AND 1D low voltage (C-04). Mandatory: 1, 2, 3, 4, 6, 7, for less than 15 minutes. 8, 9, 10, 11 Loss of all onsite DC power. DC Bus D11 A AND D21A de-energized OR both DC Bus voltages less than 105V. Subsequent: 15, 21, 22 EVI-27D1 & EVI-27D2 (D-30LID-30R) If Needed: 12 SITE AREA Loss of offsite AND onsite AC power Bus 1C AND 1D low voltage (C-04). Mandatory: 1, 2, 3, 4, 6, 7, EMERGENCY for more than 15 minutes. 8, 9,10, 11, 14, 15 Loss of all vital onsite DC power for DC Bus D1 1A AND D21A deenergized OR both more than 15 minutes, AND Plant not DC Bus voltages less than 105V. Subsequent: 17, 21, 22 EVI-27D1 & EVI-27D2 (D-30LJD-30R) If in Mode 5 or 6. I IIf Needed: 12,' 13, 19, 20 I '

NOTE: The SED should direct the Engineering Support Team and Operations Support Team to evaluate the need to recommend and implement fuel oil conservation measures in the event offsite power has been lost.

Proc No El-1 Attachment 1 Revision 41 SITE EMERGENCY PLAN CLASSIFICATION Page 16 of 26 PLANT POWER - ELECTRICAL CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS GENERAL Loss of offsite and onsite AC power Bus 1C AND 1 D low voltage (C-04) AND there Mandatory: 1, 2, 3, 4, 5, 6, 7, EMERGENCY AND there is indication of extreme are indications of extreme challenge to the 8,9,10,11,13, 14, 15 challenge to ability to cool the core. Primary Coolant System AND Core Heat Removal. (EOP-9.0 Heat Removal (HR-3) Subsequent: 17, 19, 21,22, Safety Function NOT met.) 23 1If Needed: 12, 20 NOTE: The SED should direct the Engineering Support Team and Operations Support Team to evaluate the need to recommend and implement fuel oil conservation measures in the event offsite power has been lost.

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(. ( Proc (" .1-1 Attachment 1 Revision 41 SITE EMERGENCY PLAN CLASSIFICATION Page 17 of 26 PRIMARY COOLANT SYSTEM INTEGRITY CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS UNUSUAL EVENT Unidentified or pressure boundary Calculation, OR implementation of Off Mandatory: 1, 3, 4, 6, 7 leakage >10 gpm. Normal Procedure ONP-23.1, "Primary Identified leakage >25 gpm. Coolant Leak," OR SED opinion that Subsequent: 15, 22 leak rate indications warrant activation of Emergency Plan. (See NOTE 1) If Needed: None Steam Generator secondary water S/G sample analysis.

activity > 0.1 jICi/gm dose equivalent 1-131.

Primary to secondary leakage Calculation, OR implementation of Off through any one SG >432 gallons Normal Procedure ONP-23.2, "Steam per day (0.3 gpm) but <50 gpm. Generator Tube Leak."

ALERT NOTE: Refer to Fission Product Barrier/Fuel Damage SITE AREA EMERGENCY NOTE: Refer to Fission Product Barrier/Fuel Damage GENERAL EMERGENCY NOTE: Refer to Fission Product Barrier/Fuel Damage NOTE: 1. Lifting of RV-2006 (Letdown Relief) as expected for plant conditions or evolutions does not require activating the emergency plan.

( ( Proc(

Attachment 1 l-i1 Revision 41 SITE EMERGENCY PLAN CLASSIFICATION Page 18 of 26 PRIMARY COOLANT SYSTEM - TEMPERATURE OR PRESSURE CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS UNUSUAL EVENT Any challenge to Over-Pressure Annunciation of PORV operation. Mandatory: 1, 3, 4, 6, 7 Protection System (LTOP).

NOTE: Momentary PORV activations EK-1 373 (SV and/or PORV OPEN)

Subsequent: 15, 22 I

which occur during PORV Isolation Valve opening shall not be considered If Needed: None as a challenge to the LTOP System.

Reactor high-pressure trip. (Initiating Annunciator (RPS alarms) OR event recorder.

event)

Pressurizer code safety valve Observation.

operation.

ALERT PCS temperature < 25°F subcooled. Observation, AND Plant above Mode 5. Mandatory: 1, 2, 3, 4, 6, 7, 8,

  • SMM 0114/0124 with PCP 9,10,11
  • CETs without PCP PPC point TCETMAR Subsequent: 15, 21, 22 If Needed: None

(' ( Proc -:1-1 Attachment 1 Revision 41 SITE EMERGENCY PLAN CLASSIFICATION Page 19 of 26 RADIATION LEVELS CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS ALERT Radiation levels or airborne Radiation monitors increase by a factor of Mandatory: 1, 2, 3, 4, 6, 7, contamination indicates a 1000, confirmed OR unexpected Plant area 8, 9,10, 11 severe degradation in control of iodine or particulate airborne concentrations radioactive materials. > 1000 DAC (per 10CFR20, Appendix B Subsequent: 15, 21,22 Table 1).

I If Needed: 13, 14

(i CIPro ,1 Attachment 1 Revision 41 SITE EMERGENCY PLAN CLASSIFICATION Page 20 of 26 RELEASES CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS UNUSUAL EVENT Short term radiological effluent ODCM limits exceeded.

The stack monitor (RIA-2326) reaches Alert alarm setpoint for greater than one hour, Mandatory: 1, 3, 4, 6, 7 I confirmed by sample analysis, OR Liquid Waste Subsequent: 15, 22 Discharge Monitor (RIA-1049) reaches alarm setpoint and automatic discharge trip function If Needed: 11, 14 fails. Confirmed by sample analysis.

Significant solid or liquid waste spill Observation confirmed by survey results OR Notify Rad Services to outside restricted areas with SED's opinion, evaluate whether 40CFR302 threatened offsite release. notifications are necessary.

ALERT Radiological effluent > 10 times the A valid stack monitor (RIA-2326) reading of , Mandatory 1,2, 3, 4, 6, 7,. 8, ODCM instantaneous release rate > 1.6E+5 cpm above background for longer than 9,10,11 limit, one hour, OR Liquid Waste Discharge Monitor (RIA-1 049) reaches 10 times alarm setpoint and Subsequent: 13, 14, 15, 21, automatic discharge trip function fails, confirmed 22 by sample analysis.

If Needed: 19, 20

Proc No El-1 Attachment 1 Revision 41 SITE EMERGENCY PLAN CLASSIFICATION Page 21 of 26 RELEASES CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS SITE AREA Effluent monitors detect levels 1. Any of the following valid Radiation Monitor Mandatory: 1, 2, 3, 4, 6, 7, 8, EMERGENCY corresponding to > 50 mrem/hr readings for greater than 30 mins: 9, 10, 11, 13, 14, 15 TEDE for /2 hour or > 500 mrem/hr TEDE for 2 minutes (or 5 times these (a) RIA-2326 > 1.3E+6 CPM above Subsequent: 17,19, 20, 21, levels to the Adult Thyroid CDE) at background. 22, 23 the site boundary for adverse meteorological conditions. These (b) RIA-2323/RIA-2324 > 215 CPM above If Needed:

levels are projected based on other background AND steam release in Plant parameters (eg, radiation level progress. None in Containment with leak rate appropriate for existing Containment (c) RIA-2321/RIA-2322 > 5.1 E+4 rem/hr pressure) or are measured in the above background AND Containment environs. EPA Protective Action integrity intact; OR Guidelines (see Emergency Implementing Procedure EI-6.13, 2. Any of the following valid Radiation Monitor "Protective Action Recommendations readings for greater than 2 minutes:

for Offsite Populations") are projected to be exceeded outside the (a) RIA-2327 > 11 mrem/hr above site boundary. background.

(b) RIA-2323/RIA-2324 Ž> 630 CPM above background AND steam release in progress.

(c) RIA-2321/RIA-2322 > 5.1 E+5 rem/hr above background AND Containment integrity intact; OR

C C proc( ,11 Attachment 1 Revision 41 SITE EMERGENCY PLAN CLASSIFICATION Page 22 of 26 RELEASES CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS SITE AREA 3. Measured radiation levels at site boundary indicate any of the following:

EMERGENCY (Cont'd) (a) TEDE Rate > 50 mrem/hr for S30 minutes.

(b) TEDE Rate > 500 mrem/hr for 2 minutes.

(c) Adult Thyroid CDE Rate > 250 mrem/hr for 30 minutes.

(d) Adult Thyroid CDE Rate > 2500 mrem/hr for 2 minutes.

Proc No El-1 Attachment 1 Revision 41 SITE EMERGENCY PLAN CLASSIFICATION Page 23 of 26 RELEASES CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS GENERAL Effluent monitors detect levels 1. Any of the following Radiation Monitor readings Mandatory: 1, 2, 3, 4, 5, 6, 7, EMERGENCY corresponding to 1 rem/hr TEDE or nay indicate a General Emergency: 8, 9, 10, 11, 13, 14, 15, 5 rem/hr Adult Thyroid CDE Rate at the site boundary under actual (a) RIA-2327 o 22 mrem/hr above Subsequent: 17, 19, 20, 21, meteorologqical conditions. These background. 22, 23 levels are projected based on other Plant parameters (eg, radiation (b) RIA-2323/RIA-2324 > 1260 CPM above levels in Containment with leak rate background AN.D main steam release appropriate for existing Containment occurrng.

pressure) or are measured in the (c) RIA-2321/RIA-2322 -e1.OE+6 rem/hr environs. above background AND Containment leakage within design limits; OR NOTE: Refer to Emergency Implementing Procedure EI-6.13, 2. Dose Projection from Emergency Implementing "Protective Action Recommendations Procedure EI-6.0, "Offsite Dose Calculation and for Offsite Populations." Recommendations for Protective Actions,"

indicate any of the following with Existing Meteorological Conditions, at or beyond the site boundary:

(a) TEDE Rate > 1 rem integrated over a period of one hour.

(b) Adult Thyroid CDE Rate > 5 rem integrated over a period of one hour.

3. Measured radiation levels at or beyond the site boundary indicate any of the following:

(a) TEDE Rate > 1 rem integrated over a period of one hour.

(b) Adult Thyroid CDE Rate > 5 rem integrated over a period of one hour.

K

Proc( ,-1 Attachment I Revision 41 SITE EMERGENCY PLAN CLASSIFICATION Page 24 of 26 SAFETY INJECTION SYSTEM CLASSIFICATION JEMERGENCY ACTION LEVEL METHOD OF DETECTION T ACTIONS UNUSUAL EVENT Safety Injection initiated AND Annunciation AND flow verification. Mandatory: 1, 3, 4, 6, 7 discharged to vessel (Ref EOP Supplement 4)

NOTE: Applies to HPSI, LPSI, or Subsequent: 15, 22 SIT Injection only. For injections

  • FI-0307A to FI-0314A solely from charging pumps/BA If Needed: None pumps to PCS due to SIS, include as part of one hour (or four hours) nonemergency report per Palisades Administrative Procedure 4.00, "Operations Organization, Responsibilities and Conduct." i. -

(I Proc( 'l-1 Attachment 1 Revision 41 SITE EMERGENCY PLAN CLASSIFICATION Page 25 of 26 SECONDARY SIDE CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS UNUSUAL EVENT Failure of a safety or relief valve in a Annunciation AND pressure indications, OR Mandatory: 1, 3, 4, 6, 7 safety-related system to close observation.

following reduction of applicable Subsequent: 15, 22 pressure.

If Needed: None Main Steam Line/Main Feedwater Observation of isolated excess Steam Line break outside Containment Demand Event conditions.

which is isolated by Main Steam isolation signal (manually or auto).

Turbine rotating component failure Turbine trip (other than required for normal causing turbine trip. Plant shutdown) AND observation of turbine malfunction or failure.

ALERT Main Steam Line/Main Feedwater Observation of excess Steam Demand Event Mandatory: 1, 2, 3, 4, 6, "*,8, Line break inside or outside conditions. 9,10,11 Containment which is not isolated.

Subsequent: 15, 21, 22 If Needed: None Turbine failure causing casing Observation AND turbine trip.

penetration.

NOTE: For accidents involving Main Steam Line/Main Feedwater Line breaks and failed Fuel/Steam Generator tube leaks, see "Primary Coolant System Integrity."

NOTE: For accidents involving primary to secondary leakage, see "Primary Coolant System Integrity."

(7 (. Proc( ,l-1 Attachment 1 Revision 41 SITE EMERGENCY PLAN CLASSIFICATION Page 26 of 26 SECURITY CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS UNUSUAL EVENT Credible Security threat or Security alarms OR observation AND Mandatory:1 *, 3, 4, 6, 7, 12 attempted entry or attempted activation of Safeguards Contingency sabotage. Procedures. Subsequent: 15, 22 NOTE: Refer to Emergency Implementing Procedure El-1.1, "Emergency Response To If Needed: None Credible Security Threats," for direction regarding declaration of, and response to, "credible" security threats as determined by the NMC Director of Security, Palisades Security Manager, or the Palisades Security Shift Leader.

ALERT Security threat exists that results in Security Alarms OR observation AND Mandatory: 1*, 2*, 3, 4, 6,'7, adversaries commandeering an activation of Safeguards Contingency 8*, 9", 10, 11*, 12 area of the Plant, but not control Procedures.

over shutdown capability or of any Subsequent: 15, 21, 22 Vital areas.

If Needed: 15, 19 SITE AREA Physical attack on the Plant Security alarms OR observation AND Mandatory: 1*, 2%, 3, 4, 6, 7, 8*,

EMERGENCY involving imminent occupancy of activation of Safeguards Contingency 9*, 10, 11*, 12,14*, 15 the Control Room, auxiliary Procedures.

shutdown panels, or other Vital Subsequent: 17*, 21,22 areas.

If Needed: 13, 19, 20 GENERAL Physical attack on the Plant has Security alarms OR observation AND Mandatory: 1*, 2*, 3, 4, 5, 6, EMERGENCY resulted in unauthorized personnel activation of Safeguards Contingency 7, 8*, 9*, 10, 11*, 12, 13, 14*,

occupying the Control Room or Procedures. 15 any other Vital areas.

Subsequent: 17*, 21, 22, 23 If Needed: 16, 18, 19, 20

  • NOTE: Performance of this action may be delayed until the safety of personnel is assured.

Proc No El-1 Attachment 2 EMERGENCY kOCTIONS/NOTI FICATIONS Revision 41 Page 1 of 1

"*--' EVENT TYPE (Circle one): UE / ALERT! SAE / GENERAL Date:

SACTION 1 (INITIAL) I ITEM (circle) DESCRIPTION OF ACTION REF DONE?

1 MS I Announce Emergency on PA EI-3 2 MS I Sound Emergency Siren EI-3 3 MS I Notify Van Buren County (within 15 min of declaration) See Notes 2 and 3 below EI-3 4 MS I Notify State of Michigan (within 15 min of declaration) See Notes 2 and 3 below EI-3 5 MS I Provide Protective Action Recommendation EI-6.13 6 MS I Call Duty and Call Superintendent N/A 7 MS I Notify NRC See Note 1 below EI-3 8 MS I Perform Personnel Accountability - Notify Security at Ext 2278 El-1 2.1 9 MS I Initiate Staff Augmentation - Notify Security at Ext 2278 See Note 4 below EI-2.2 10 MS I Activate ERDS SOP-34 11 MS I Initiate Onsite Monitoring EI-8 12 MS I Activate Safeguards Contingency Procedures N/A 13 MS I Perform Offsite Dose Assessment EI-6.0 14 MS I Initiate Offsite Monitoring EI-9 15 MS I Notify Public Affairs - Day @ 764-8931 Night @ 637-5170 EI-3 16 MS I Activate Fire Protection Plan FPIPs 17 MS I Evacuate Nonessential Personnel EI-13 18 MS I Notify Covert Fire Dept and Call Security @ 2278 EI-3 19 MS I Perform Core Damage Calculation EI-7.0/EI-1 1 20 MS I Perform Environmental Assessment EI-10 21 MS I Initiate Re-entry/Recovery El-5 22 MS I Initiate Condition Report Admin 3.03 23 MS I Monitor Severe Accident Management Guideline for Implementation SAMGs LEGEND AND NOTES: M=MANDATORY S=SUBSEQUENT I=IF NEEDED NOTES: 1. = 10CFR50.72(c) REQUIRES THAT CONSUMERS ENERGY MAINTAIN AN OPEN, CONTINUOUS COMMUNICATION CHANNEL WITH THE NRC OPERATIONS UPON REQUEST OF THE NRC"

2. = 15 MINUTE UPDATES REQUIRED WHEN ABOVE UE
3. = REFER TO EI-3 ATTACHMENT 2, FOR BACKUP PHONE NUMBERS (IF NEEDED)
4. = FOR DAYSHIFT ON WEEKDAYS, SOUND THE EMERGENCY SIREN AND PERFORM PERSONNEL ACCOUNTABILITY ALL OTHER SHIFTS INCLUDING WEEKENDS AND HOLIDAYS. NOTIFY THE SECURITY SHIFT LIEUTENANT AT (EXT 2278) WHO WILL INITIATE THE EMERGENCY AUGMENTATION NOTIFICATION SYSTEM.

NOTE: Completed forms shall be transmitted to Plant Licensing within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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