ML040550402
| ML040550402 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 02/13/2004 |
| From: | Consumers Energy |
| To: | Mcknight J Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML040550402 (38) | |
Text
Date Entered: Feb 13, 2004 TO:
USNRCIWASHIN JMCKNIGHT GTON Copy Number:
145 TRANSMITAL NUMBER:
216 H
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< TRANSMITAL NUMBER:
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?,E>S~,\\A\\A~sS~s\\E~,\\X PROCEDURE NUMBER: El-1 TITLE: EMERGENCY CLASSIFICATION AND ACTIONS TRANSMITTAL: LISTED BELOW ARE NEW/REVISED PROCEDURES WHICH MUST BE IMMEDIATELY INSERTED INTO OR DISCARDED FROM YOUR PROCEDURE MANUAL.
Action Required Section or Description REMOVE AND DESTROY El-1, R/43, ENTIRE PROCEDURE REPLACE WITH El-1, R/44, ENTIRE PROCEDURE SIGN, DATE, AND RETURN THE ACKNOWLEDGEMENTFORM WITHIN 10 DAYS TO THE PALISADES PLANT DOCUMENT CONTROL SIGNATURE OR INITIALS DATE If applicable, REMOVE ALL travelers and marked up pages in front of this procedure.
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Procedure No El-1 Revision 44 Effective Date 2113104 PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE
"' TITLE: EMERGENCY CLASSIFICATIO'N'AND ACTIONS""
Approved: NKBrott
- 1 2/13/04 Procedure Sponsor Date New Procedure/Revision Summary:
Revision 44 Specific Channes This revision was initiated to restore the emergency action level (EALs) basis to one document. Over time, the EALs were revised using the NUMARC basis in parts while retaining the overall NUREG 0654 basis. This was inappropriate. This revision removes the Fission Product Barriers/Fuel Damage Table I and restores specific EALs for the conditions covered in the Table 1. In addition, some set points for the EALs had been changed without prior NRC NRR approval. These set points needed to be returned. The changes in this revision are limited to Attachment 1 only.
Revision 43 - Summary of Changes 12/10/03 This revision was initiated to ensure consistency of the emergency action levels for the "Fission Product Barriers/Fuel Damage" Table-1 by changing the Fuel Clad Barrier - PCS Activity - Loss method of detection from 40 pCi/gm to 32 pCi/gm since due to dose concerns chemistry is not able to obtain results above 32 pCi/gm. Also the Note on Table-1 was clarified to include releases as a way to evaluate if a 'Direct' pathway exists to the environment under the Containment Barrier - Loss section.
Under the "Primary Coolant System Integrity" category for an Unusual Event, the primary to secondary leakage through any one SG was changed from <50 gpm to <40 gpm to align with the "Fission Product Barriers/Fuel Damage" Table-1 PCS Barrier Potential Loss section.
The order of actions from Attachment 2 was change to move the initiation of staff augmentation from #9 to #3 in order to improve the response of emergency personnel who must respond in 30 and 60 minutes.
Revision 42 Summary of Changes This revision was initiated in order to incorporate references to EOP Supplements 12, 13, 17, and 18, and Emergency Implementing Procedure El-1.1, Section 6.3 was added to include direction for classification during a credible security threat. Numerous editorial clarifications were added.
PALISADES NUCLEAR PLANT Proc No El-1 EMERGENCY IMPLEMENTING PROCEDURE Revision 44.
Page i K
TITLE: EMERGENCY CLASSIFICATION AND ACTIONS Table of Contents
.1.0 PERSONNEL RESPONSIBILITIES......................1........................................................1 2.0 PURPOSE.1-2.0U P
S 1
3.0 REFERENCES
2 3.1 SOURCE DOCUMENTS 2...........
3.2 EERNE 0IJ'-.
3.2 REFERENCE DO C UMIENTS..;
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.
7-6.3 DETERMINATION OF EMERGENCY CLASSIFICATION FOR A CREDIBLE SECURITY EVENT..
7 7.0 ATTACHMENTS..........
7 8.0 SPECIAL REVIEWS.............
8 ATTACHMENTS, "Site Emergency Plan Classification" Attachment. 2, "Emergency Actions/Notifications"
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PALISADES NUCLEAR PLANT Proc No El-i EMERGENCY IMPLEMENTING PROCEDURE Revision 44 Page I of 8 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
,X,,,
,all segments are complete.,
1.0 PERSONNEL RESPONSIBILITIES 1.1 The Shift Manager 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 SED can be found in Emergency Implementing Procedure El-2.1,'"Site Emergency Director." -
1.2 The normal line of succession for the SED shall conform to the individuals listed in the Delegation of Responsibility memo published by the Plant 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 will assume the role of the Plant Manager.
2.0 PURPOSE To classify those emergency conditions which necessitate the activation' to the Site Emergency Plan. To identify actions that should be taken to mitigate the consequences of an emergency.
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PALISADES NUCLEAR PLANT"'
Proc No El-1 EMERGENCY IMPLEMENTING PROCEDURE Revision 44 Page2of8 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 Ppeqraating.,rocedurq EOP 5.,'St,6amenerator.Tubp, Fluppre.
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 Emergency Operating Procedure Supplements #12 and #13 - "A" and "B" S/G - SGTR Isolation Checklist 3.1.8 Emergency Operating Procedure Supplements #17 and #18 - "A" and "B" SIG ESDE Isolation Checklist 3.1.9 NUREG 0654, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," Section D 3.1.10 Palisades Site Emergency Plan 3.1.11 EPPOS No 2, "Emergency Preparedness Position (EPPOS) on Timeliness of Classification of Emergency Conditions" 3.1.12 Engineering Analysis, EA-JBB-01-04, "Failed Fuel Dose Rates on NSSSPiping" 3.2 REFERENCE DOCUMENTS 3.2.1 Emergency Implementing Procedure El-1.1, "Emergency Response to Credible Security Threats" 3.2.2 Emergency Implementing Procedure El-2.1, "Site Emergency Director" 3.2.3 Emergency Implementing Procedure El-2.2, "Emergency Staff Augmentation" 3.2.4 Emergency Implementing Procedure El-3, "Communications and Notifications" 3.2.5 Emergency Implementing Procedure El-5.0, "Reentry"
PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE Proc No El-i
. Revision 44.
Page 3 of 8 TITLE: EMERGENCY CLASSIFICATION AND ACTIONS --
k 3.2.6 Emergency Implementing Procedure El-5.1, "Recovery" 3.2.7 Emergency Implementing Procedure El-6.0, "Offsite Dose Calculation and.
Recommendations for Protective Actions" 3.2.8 Emergency Implementing Procedure El-6.13, "Protective Action Recommendations for Offsite Populations" 3.2.9 Emergency Implementing Procedure El-7;0, "Emergency Post Accident Sampling and Determination of Fuel Failure'Using Dose Rates" 3.2.10 Emergency Implementing Proce.dure EI-8, "Onsite Radiological Monitoring" 3.2.11 Emergency Implementing Procedure El-9, "Offsite Radiological Monitoring" 3.2.12 Emergency Implementing Procedure El-10, "Accident Environmental Assessment" 3.2.13 Emergency Implementing Procedure El-1 1, "Determination of Extent of Core Damage" 3.2.14 Emergency Implementing Procedure El-i2.1, "Personnel Accountability and Assembly" 3.2.15 Emergency Implementing Procedure El-13, "Evacuation/Reassembly" 3.2.16 Emergency Operating Procedure EOP-4.0, "Loss of Coolant Accident Recovery" 3.2.17 Emergency Operating Procedure EOP-9.0, "Functional Recovery Procedure" 3.2.18 NMC Fleet Procedure FP-PA-ARP-01, "Action Request Process" l
3.2.19 Palisades Administrative Procedure 4.00, "Operations Organization', Responsibilities and Conduct" 3.2.20 Off Normal Procedure ONP-23.1, "Primary Coolant Leak" 3.2.21 Off Normal Procedure ONP-23.2, "Steam Generator Tube Leak" 3.2.22 System Operating Procedure SOP-34, "Palisades Plant Computer (PPC) System" 3.2.23 Palisades Oil and Hazardous Materials Spill Prevention Plan 3.2.24 Technical Specifications ADMIN 5.5.1 3.2.25 Palisades Offsite Dose Calculation Manual 1,1
PALISADES NUCLEAR PLANT -.::
EMERGENCY IMPLEMENTING PROCEDURE :
Proc No El-1 Revision 44.
Page 4 of 8 TITLE: EMERGENCY CLASSIFICATION AND ACTIONS*
3.2.26 Fire Protection Implementing Procedures 3.2.27 Severe Accident Management Guidelines 3.2.28 10 CFR 50.54(x) 3.2.29 Palisades Administrative Procedure 3.01, "Plant Review Committee" 3.3.30.
Palisades Administrative Procedure 10.41, "Procedure and Policy Processes" 4.0 INITIAL CONDITIONS AND/OR REQUIREMENTS 4.1 This procedure shall be implemented when an event occurs or conditions exist which, in the opinion of the Shift Manager/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, 6ither 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-1 EMERGENCY IMPLEMENTING PROCEDURE Revision 44 Page 5 of 8 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 performrbd. 'Wherd-rdquirbd; sign appropriate sign-off blanks to certify that all segments are complete..
6.1 CLASSIFICATION/RECLASSIFICATION
- a.
Emergencies are grouped ii6to`four classifications listed below in order of severity:
Unusual Event
' Events are in progress or have occurred which indicate a potential degradation of the level of safety of the Plant. Unusual Events involve minor situations that have'the potential to escalate to more serious emergencies.
Alert Events are in progress 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 progress orhave 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.
PALISADES NUCLEAR PLANT Proc No Eli EMERGENCY IMPLEMENTING PROCEDURE..
Revision 44 Page 6 of 8 TITLE: EMERGENCY CLASSIFICATION AND ACTIONS General Emergencv Events are in progress or have occurred which involve actual or imminent core degradation with the potential for loss of containment integrity per Technical Specifications 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.
- b.
The SED shall ddssify emergency conditio'n'slevent.s-fbllows'W.S'-
- 1.
Determine the category in which conditions/events best fit within 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 - Attachmnent 1, Pg 9 Miscellaneous - Attachment 1,, Pg, 1I
Natural Phenomenon - Attachment 1, Pg 12 Plant Power - Electrical - Attachment 1, Pg 15 Primary Coolant System Integrity - Attachment 1, Pg 16 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 condition/event.
PALISADES NUCLEAR PLANT EMERGENCY IMPLEMENTING PROCEDURE Proc No El-I Revision 44 Page 7 of 8 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 t~h.EnmergencyAc ions/N~otifications,istepoi in, a 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.
- 2.
Subsequent Actions (S) - Actions that should be performed in an expeditious manner as conditions, time, and personnel permit.
- 3.
If Needed Actions (1) - Actions that are not required in every case, but maybe 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.
DETERMINATION OF EMERGENCY CLASSIFICATION FOR A CREDIBLE SECURITY EVENT
- a.
When notified by the Security Shift Leader that the Plant has received a credible security threat, refer to Emergency Implementing Procedure El-1.1, "Emergency Response to Credible Security Threats."
ATTACHMENTS 6.3 7.0 7.1 K> 7.2, "Site Emergency Plan Classification", "Emergency Actions/Notifications"
PALISADES NUCLEAR PLANT' Proc No El-1 EMERGENCY IMPLEMENTING PROCEDURE Revision 44 Page 8 of 8 TITLE: EMERGENCY CLASSIFICATION AND ACTIONS 8.0 SPECIAL REVIEWS The scope of this procedure does not include activities that require a 50.59 review per Palisades Administrative Procedure 10.41, "Procedure and Policy Processes."
Therefore, changes to this procedure do not require a 50.59 review.
Revisions of this procedure will be reviewed by State of Michigan personnel.
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SITE EMERGENCY PLAN CLASSIFICATION C.
Proc No El-1 Revision 44 Page 1 of 26 ALARMS/ANNUNCIATORS CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS ALERT Loss of most or all alarms (annunciators) In Observation Mandatory: 1, 2, 3, 4, 5, 7, 8, 9, Control Room.
1011 Example - loss of DC Panel D21-2 Subsequent: 15, 21, 22 Ref: ONP-2.3 If Needed: None Mandatory: 1, 2, 3, 4, 5, 7, 8, 9, SITE AREA Loss of most or all alarms (annunciators) in Observation 10,11, 14, 15 EMERGENCY Control Room AND Plant transient Initiated or in progress.
Example - loss of DC Panel D21-2 Subsequent: 17, 21, 22 and Reactor Trip.
e Ref: ONP-2.3 If Needed: 19, 20 f.
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Proc No El-1 Revision 44 Page 2 of 26 COMMUNICATION LOSS CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION:
ACTIONS Mandatory: 1, 4, 5, 7, 8 UNUSUAL EVENT Significant loss of offsite communication of the Emergency capability.
Notification System (ENS), and all Subsequent: 15, 22 other phones including satellite phones, that could be used to If Needed: None make notifications to Van Buren County, the State of Michigan and the NRC.
NOTE: The availability of one phone is sufficient to Inform offsite authorities of plant problems.
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Revision 44 Page 3 of 26 SITE EMERGENCY PLAN CLASSIFICATION DRY FUEL STORAGE CASK-ISFSI CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS Mandatory: 1, 4, 5, 7, 8 UNUSUAL EVENT Incident involving a loaded fuel storage cask Radiation level 2 1 rem/hr at 1 ft from OUTSIDE the Auxiliary Building.
a Dry Fuel Storage Cask.
Subsequent: 15, 22 OR If Needed: 11, 13,14 Radioactive contamination level 105 dpm/1OOcm2 beta-gamma or dpm/10Ocm2 alpha from a Dry Fuel Storage Cask.
.OR Airborne radioactivity-analysis -
indicating > 10 timres the Effluent Concentration levels from a Dry Fuel Storage Cask. (1 OCFR20, 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).
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ENGINEERED SAFETY FEATURES CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION-ACTIONS UNUSUAL EVENT inability to reach a required mode within Technical Plant is not brought to required Mandatory: 1, 4, 5, 7, 8 Specification limits.
operating mode within Technical Specifications LCO Action Statement Subsequent: 15, 22 Limit.
If Needed: None ALERT Failure of the Reactor Protection System to initiate An RPS setpoint exceeded AND the Mandatory: 1, 2, 3, 4, 5, 7, 8, 9, 10,.
and complete a trip AND the Reactor is not sub Automatic RPS actuation did NOT 11 critical.
occur AND Manual Reactor Trip from C-02 or C-06 was successful.
Subsequent: 15, 21, 22 Complete loss of any functions needed for cold Both S/Gs are not available for PCS shutdown.
heat removal AND uncontrolled PCS If Needed: 12,19 heatup is in progress.
SITE AREA Complete loss of any function needed for hot All AFW pumps/trains not available for Mandatory: 1, 2, 3, 4, 5, 7, 8, 9, 10, EMERGENCY shutdown.
less than 30 minutes AND Main 11,14,15 Feedwater/Condensate NOT feeding steam generators when required by Subsequent: 17, 21, 22, 23 e rapplicable EOP.
Transient requiring operation of shutdown systems An RPS setpoint exceeded AND the If Needed: 12, 13, 19, 20 with failure to trip (continued power generation, Automatic RPS actuation did NOT' but no core damage immediately evident).
occur AND Manual Reactor Trip (C-02 or C-06).
GENERAL EMERGENCY Transient requiring operation of shutdown system Rx Trip initiated AND any full length Mandatory: 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, with failure to trip, which results in core damage,'
CRD NOT Inserted AND Rx power 11, 13,14, 15 or additional failure of core cooling and makeup increasing or stable AND Rx power systems (which could lead to core melt).
greater than 1% AND either of the-Subsequent: 17, 19, 21, 22, 23 following:
LESS THAN 252F subcooled If Needed: 12, 20 OR failed fuel confirmed by sample analysis.
Transient initiated by loss of Feedwater and All AFW pumps/trains not available for Condensate System (principal heat removal greater than 30 minutes AND Main system), followed by failure of Auxiliary Feedwater Feedwater/Condensate NOT feeding System for an extended period. Core melting steam generators when required by
'possible in several hours.
applicable EOP.
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Revision 44 Page 5 of 26 SITE EMERGENCY PLAN CLASSIFICATION EVACUATION. CONTROL ROOM CLASSIFICATION EMERGENCY ACTION LEVEL.
METHOD OF DETECTION ACTIONS Mandatory: 1, 2, 3, 4, 5, 7, 8, 9, 1 i 1 1 ALERT Evacuation of Control Room anticipated or Observation.
required with control of shutdown systems established at local stations.
Ref: ONP-25.2 If Needed: 12 Mandatory, 1,2, 3, 4, 5,7, 8,9,10, 11,14, SITE AREA Evacuation of Control Room and control of Observation.
a 15 EMERGENCY shutdown systems not established at local stations within 15 minutes.
Ref: ONP-25.2 Subsequent: 17, 21, 22,23 if Needed: 12, 13, 19, 20 T
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Revision 44 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 10 Observation Mandatory: 1, 4, 5, 7, 8, 16 minutes.
OR Subsequent: 15, 22 Fire detection alarm, confirmed by If Needed: 12, 18 observation.
ALERT Fire potentially affecting safety systems.
SED opinion.
Mandatory: 1, 2, 3, 4, 5, 7, 8, 9, 10, 11, 16 Subsequent: 15, 21, 22 Ref: ONP-25.1; if Needed: 12, 18 SITE AREA Fire compromising the function of safety Observation Mandatory, 1, 2, 3, 4, 5, 7, 8, 9, 10, 11, 14, 15, EMERGENCY systems.
16 Ref: ONP-25.1 Subsequent: 17, 21, 22 If Needed: 12, 18, 19, 20 NOTE: See General Emergency classification under the Miscellaneous category for a fire which could cause massive damage to the Plant systems.
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Proc No El-1 C
Attachment I Revision 44 Page 7 of 26 SITE EMERGENCY PLAN CLASSIFICATION FISSION PRODUCT BARRIERS/FUEL DAMAGE CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS UNUSUAL EVENT Primary Coolant lodine-131 dose Failed fuel as Indicated by Mandatory: 1, 4, 5, 7, 8 concentration equivalent > 1.0pCI/gm for abnormally high area or process more than 72 hrs radiation monitors in containment-Subsequent: 15, 22 and/or the auxiliary building; confirmed by sample analysis.
If Needed: None ALERT Primary Coolant lodine-131 dose Failed fuel as indicated by Mandatory: 1, 2, 3, 4, 5, 7, 8, 9, 10, 11 concentration equivalent >32,uCi/gm abnormally high area or process radiation monitors in containment-Subsequent: 15, 19, 21, 22 OR and/or the auxiliary building, confirmed by sample analysis OR If Needed: 12, 13,14
> 5% total failed fuel.
observatio NOTE: See Emergency Implementing Procedure El-7.0,
'Determination bf Extent of Core Damage Using Dose Rates," for.;
determining failed fuel between 1% and 5%.
Fuel damage/handling accident with release Radiation Monitor Alarm of radioactivity to Containment or Fuel confirmed after observation of Handling Building.' *accident OR observation of accident, confirmed by sample analysis OR SED's opinion.
- Note: For incidents involving Dry Fuel Storage Casks outside the Auxiliary Building. See Dry Fuel Storage Cask-ISFSI classification, page 4 of 34.
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Proc No El-1 Attachment I Revision 44 Page8of26 FISSION PRODUCT BARRIERS/FUEL DAMAGE CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION:
ACTIONS SITE AREA EMERGENCY Major damage to irradiated fuel in Radiation Monitor Alarm Mandatory: 1, 2, 3, 4,;5, 7, 8, 9, 10,11, Containment or Fuel Handling Building. (eg, confirmed after observation of 14,15 large object damages fuel or water loss below accident OR observation of fuel level) accident confirmed by sample Subsequent: 13, 17, 19, 21, 22, 23 analysis OR SED's opinion.
If Needed: 12, 20 Degraded core with possible loss of coolable Core exit temperature > 700 'F geometry.
OR subcooling margin < 0 'F OR Core uncovered AND Temperature rise across the core' increasing OR lack of temperature rise across the core OR SED's opinion.
GENERAL EMERGENCY Loss of 2 of 3 fission product barriers with Detection dependent upon which:
Mandatory: 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, potential loss of third fission product barrier barriers fail and to some extent, 11, 13, 14, 15 (eg, loss of Primary Coolant integrity, clad upon mechanism which causes failure, and high potential for loss of failure. Potential loss of Subsequent: 17, 19, 21, 22, 23 Containment).
Containment is defined as Containment Hydrogen If Needed: 12, 20 Concentration > 4.0% OR Containment pressure > 70 PSIA,
__R SED's opinion.
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Proc No El-1 Revision 44 Page 9 of 26 HAZARDS-G EN ERAL CLASSIFICATION EMERGENCY ACTION LEVEL
.METHOD OF DETECTION ACTIONS UNUSUAL EVENT Aircraft crash onsite or unusual aircraft Observation of event AND SED's Mandatory: 1, 4, 5, 7, 8 activity over facility which could affect Plant opinion.
operation.
Subsequent: 15, 22 NOTE: Onsite is defined as the Owner Controlled Area outside of the Protected If Needed: 12, 18 Area.
Near or onsite train derailment which could Observation of event AND SED's affect Plant operation opinion.
Near or onsite explosion which could affect Observation of event OR Plant operation.
notification from offsite authorities AND SED's opinion.
Near or onsite toxic or flammable gas which Observation of event OR could affect Plant operation.
notification from offsite authorities AND SEDs opinion.
ALERT Aircraft crash on facility.
Observation.
Mandatory: 1, 2, 3, 4, 5, 7, 8, 9,-1 0, 11 NOTE: Facility Is defined as Inside the Protected Area.
Subsequent: 15, 21, 22 Missile Impact from whatever source on Observation.
If Needed: 12, 16, 18 facility.
Known explosion damage to facility affecting Observation.
Plant operation.
Entry into facility environs of uncontrolled Observation OR warning from toxic or flammable gas.
offsite authorities OR detection with portable Instrumentation.
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Proc No El-i
- Revision 44 Page 10 of 26 SITE EMERGENCY PLAN CLASSIFICATION HAZARDS-GENERAL CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION-ACTIONS SITE AREA Mandatory: 1, 2,3,4,5,7,8,9,10, 11, 14,15 EMERGENCY Aircraft crash affecting Vital structures by Observation.
impact or fire AND Plant not in cold Subsequent: 17, 21, 22, 23 shutdown.
If Needed: 12,13,16,18,19, 20 Severe damage to equipment required for Observation.
safe shutdown from missiles or explosion - see ENGINEERED SAFETY FEATURES.
Entry of uncontrolled flammable gas into Vital Observation OR SED's opinion*
areas OR entry of uncontrolled toxic gas into OR detection with portable Vital areas that constitute a safety problem instrumentation.,
- AND Plant not in cold shutdown.
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Revision 44 Page 11 of 26 MISCELLANEOUS CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS UNUSUAL EVENT Plant conditions exist that warrant increased SED's opinion Mandatory: 1, 4, 5, 7, 8 awareness on the part of the Plant staff or state and/or local authorities, OR Involve Subsequent: 15,22 other than normal shutdown.
If Needed: 12 NOTE: For Rx trips from high PCS pressure (initiating event), see 'Primary 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 Mandatory: 1, 2, 3, 4, 5, 7, 8, 9, 10, 11 precautionary activation of Technical Support Center and placing Emergency Operations Subsequent: 15,21,22 Facility and other emergency personnel on standby.
If Needed: 12 SITE AREA EMERGENCY Plant conditions warrant the activation of SED's opinion Mandatory: 1, 2, 3, 4, 5, 7, 8, 9, 10, 11,14, State and County Emergency Operations 15 Centers and monitoring teams or a precautionary. notification to the public near Subsequent: 17, 21, 22, 23 the site.
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If Needed: 12, 13, 19, 20 GENERAL EMERGENCY Conditions exist that make release of large SED's opinion.
Mandatory: 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, amounts of radioactivity in a short time
.13, 14, 15 possible (eg, any core melt situation).
Any major internal or external events (eg, SED's opinion.
Subsequent: 17, 19, 21, 22, 23 fires, earthquakes, substantially beyond design basis) which could cause massive If Needed: 12, 16, 18, 20 common damage to Plant systems.
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Proc No El-1 Revision 44 Page 12 of 26 SITE EMERGENCY PLAN CLASSIFICATION NATURAL PHENOMENON CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS UNUSUAL EVENT Any earthquake felt In-Plant.
Observation (see Note!)
Mandatory: 1, 4, 5, 7, 8 Abnormal water levels Including flood or low Flood, seiche - observation of Subsequent: 15, 22 water or selche.
water approaching 590' level.
Low water - Ultimate Heat Sink If Needed: 12 level lowers to < 572'0 (216m below Intake Structure floor level; LI-1 338)
Tornado onsite.
Observation ALERT Any earthquake that exceeds operating Observation (see Note'), or Mandatory: 1,- 2, 3, 4, 5, 7, 8, 9, 10, 11 base earthquake surface acceleration levels measurement (see Note2)..
of 0.1G, but not greater than 0.2G; no Subsequent: 15, 21, 22 damage to equipment required for safe shutdown.
If Needed: 12, 16, 18 Flood, low water, or selche near design Flood, seiche - observation of basis.
water above 590' level.
Low water - Ultimate Heat Sink level lowers to 569' (LI-1 338).
Tornado striking facility.
Observation NOTE: Facility Is defined as inside the Protected Area.
NOTE':
Information on seismic disturbances can be obtained by calling the National Earthquake Information Center, Denver, Colorado, at 1-303-273-8500 (normal hours), or 1-303-273-8428 (off normal hours).
NOTE2:
Seismic instrumentation is available onsite for post emergency assessment of earthquakes. 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.
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SITE EMERGENCY PLAN CLASSIFICATION
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Proc No El-1 Revision 44 Page 13 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, 5, 7, 8, 9, 10, 11, 14, 15 EMERGENCY earthquake surface acceleration levels or (See Note2 Page 12) 0.2G.
Subsequent: 17, 21, 22 Flood, low water, or seiche greater than Flood, seiche - observation of design levels OR failure of protection of Vital water above 594' level.
If Needed: 12, 13, 16,18, 19,20 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. This equates to an Ultimate Heat Sink level of < 565'97 (LI-1 338)..
Others - observation of equipment damage.
Tornado or sustained winds in excess of Observation.
design level; ie, of sufficient magnitude to Notification by offsite agencies.
cause 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.
1
C SITE EMERGENCY PLAN CLASSIFICATION C.
Proc No El-1 Revision 44 Page 14 of 26 PLANT POWER-ELECTRICAL CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS UNUSUAL EVEN Loss of offsite AC power.
Loss of Safeguards AND Startup Mandatory: 1, 4, 5, 7, 8 Power transformers AND Onsite AC power is being supplied by Subsequent: 15, 22 Emergency Diesel Generators.
Loss of emergency onsite AC power.
Observation: both Emergency If Needed: 12 Diesel Generators inoperable.
NOTE: Does not include Technical Specification prescribed operability testing for common cause failure analysis.
ALERT Loss of offsite AND onsite AC power for Bus 1 C AND 1 D low voltage.
Mandatory: 1, 2, 3, 4, 5, 7, 8, 9, 10, 11 less than 15 minutes.
Sub~equent: 15, 21, 22 Loss of all onsite DC power for less than 15 DC Bus D 1 A AND D21A de-minutes.
energized OR both DC Bus If Needed: 12 voltages less than 1 05V.
EVI-27D1 & EVI-27D2 (D-30UD-30R) 9
C
-SITE EMERGENCY PLAN CLASSIFICATION C.
Proc No El-1
- Attachment 1 Revision 44 Page 15 of 26 PLANT POWER-ELECTRICAL CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS SITE AREA Loss of offsite AND onsite AC power for Bus 1 C AND 1 D low voltage.
Mandatory: 1, 2, 3, 4, 5, 7, 8, 9, 10, 11, 14, 15 EMERGENCY more than 15 minutes.
Subsequent: 17, 21, 22 Loss of all vital onsite DC power for more DC Bus D1 1A AND D21A than 15 minutes, AND Plant not In cold de-energized OR both DC Bus If Needed: 12, 13, 19, 20 shutdown.
voltages less than 105V.
EVI-27D1 & EVI-27D2 (D-30L/D-30R)
GENERAL Loss of offsite and onsite AC power AND Bus 1 C AND 1 D low voltage AND all Mandatory: 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 13, 14, EMERGENCY total loss of auxiliary feedwater makeup AFW pumps/trains not available for 15 capability for greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Subsequent: 17, 19, 21, 22, 23 If Needed: 12, 20-NOTE: The SED should direct the Engineering Support Team and Operations Support Team to evaluate the need tolrecommend and Implement fuel oil conservation measures In the event offsite power has been lost.
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SITE EMERGENCY PLAN CLASSIFICATION (C.
Proc No El-I Revision 44 Page 16 of 26 PRIMARY COOLANT SYSTEM INTEGRITY CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS UNUSUAL EVENT PCS leak rate in excess of Technical Calculation, OR SED opinion that leak rate Mandatory 1, 4, 5, 7, 8 Specifications, but indications warrant activation of Emergency:
< 50 gpm.
Plan.
Subsequent: 15, 22 NOTE: Lifting of RV-2006 (Letdown Relief)
If Needed: None as expected for Plant conditions or evolutions does not require activating the emergency plan.
Steam Generator secondary water activity S/G sample analysis.
> 0.1 pCVgm dose equivalent 1-131.
Primary to secondary leakage rate Calculation exceeds Technical Specifications limits of 432 gallons per day primary to secondary LEAKAGE through any one SG but
<50gpm.
ALERT PCS leak rate > 50 gpm, but less than Observation of excessive PCS leakage Mandatory: 1, 2, 3, 4, 5, 7, 8, 9, 10, 11 charging pump capacity.
conditions.
Steam line break with > 10 GPM primary to Observation of Steam Generator tube leak Subsequent: 15, 19, 21, 22 secondary leak rate.
OR rupture conditions AND observation of :
excess steam demand event inside or If Needed: 12, 13, 14 outside Containment.
Rapid gross failure of one Steam Offgas monitor (**RIA-0631) alarm Generator tube with loss of offsite power.
confirmed by sample analysls-AND Decreasing pressurizer level AND Observation of loss of offsite power. NOTE:
Primary to secondary leakage LESS THAN available charging pump capacity.
Rapid failure of Steam Generator tubes Offgas monitor (**RIA-0631) alarm resulting in primary to secondary leak rate confirmed by sample analysis OR Rapidly.
of several hundred GPM.
decreasing pressurizer low level (**L.
0103A). NOTE: Primary to secondary leakage LESS THAN available charging pump capacity.
NOTE:
For incidents involving loss of Primary Coolant System Integrity AND loss of a second fission product barrier AND potential loss of the third fission product barrier, see FISSION PRODUCT BARRIER/FUEL DAMAGE under General Emergency classification.
(70 C.
Proc No El-1
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Revision 44 Page 17 of 26
.SITE EMERGENCY PLAN CLASSIFICATION PRIMARY COOLANT SYSTEM INTEGRITY CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS 4
SITE AREA EMERGENCY Loss of coolant accident greater than charging pump capacity.
Observation of LOCA Mandatory: 1, 2, 3, 4, 5, 7,- 8, 9, 10,11, 14,15 Rapid failure of Steam Generator tubes Observation of Steam Generator (several hundred GPM) with loss of offsite tube rupture conditions AND loss of power.
Startup transformers and Safeguards transformer.
-NOTE: Primary to secondary leakage GREATER THAN available
'charging pump capacity.
Subsequent: 13, 17, If Needed: 12; 20 19, 21,22,23 Primary to secondary leak rate
> 50 gpm AND steam line break outside Containment and downstream from MSIVs AND indication of fuel damage.
Observation of Steam Generator tube leak/rupture conditions AND observation of excess steam demand events outside Containment and downstream from MSIVs AND fuel damage confirmed by PCS sample analysis.
i GENERAL EMERGENCY Small and large LOCAs with failure of SIS leading to severe core degradation.
Observation of LOCA conditions AND Safety Injection System flow inadequate (per Emergency Operating Procedure EOP 4.0, 'Loss of Accident Coolant Accident Recovery,", or EOP 9.0, "Functional Recovery Procedure") AND fuel failure confirmed by sample analysis.
Mandatory: 1, 2, 3, 4, 5, 6, 7, 8, 9, 15 Subsequent: 17, 19, 21, 22, 23 10,11,13,14, If Needed: 12, 20 J.
Small or large LOCA and initially successful Safety Injection System.
Subsequent failure of Containment heat removal system over several hours.
Decreasing pressurizer level OR pressurizer low-pressure alarm AND Safety Injection System actuation alarm AND observation -'failure of containment cooling for> 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
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.1. ____________________________________
n
- NOTE:
For incidents involving loss of Primary Coolant System Integrity AND loss of a second fission product barrier AND potential loss of the third fission product barrier, see FISSION PRODUCT BARRIER/FUEL DAMAGE under General Emergency classification.
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C.
(7 Proc No El-1 Revision 44 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 Protection Annunciation of PORV operation.
Mandatory: 1, 4, 5, 7, 8 System (LTOP).
NOTE: Momentary PORV activations which Subsequent: 15, 22 occur during PORV Isolation Valve opening shall not be considered as a challenge to the If Needed: None LTOP System.
Reactor high-pressure trip. (Initiating event)
Annunciator (RPS alarms) OR
- event recorder.
Pressurizer code safety valve operation.
Observation.
ALERT PCS temperature < 25 0F subcooled Observation, AND Plant above Mandatory-1, 2, 3, 4, 5, 7, 8, 9, 10, 11 sustained for more than 5 minutes or < 25 0F cold shutdown.
subcooled, and subcooling margin SMM 0114/0124 with PCP Subsequent: 15, 21, 22 decreasing. Not applicable when Plant is In C GETs without PCP cold shutdown or refueling shutdown PPC point TOETMAR If Needed: None condition.
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Proc No El-1
- Attachment 1.
Revision 44 Page 19 of 26 SITE EMERGENCY PLAN CLASSIFICATION RADIATION LEVELS CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS ALERT Radiation levels or airborne contamination Radiation monitors increase by a Mandatory: 1, 2, 3, 4, 5, 7, 8, 9, 10, 11 indicates a severe degradation in control of factor of 1000, confirmed OR radioactive materials, unexpected Plant area iodine or Subsequent: 15, 21, 22 particulate airborne concentrations
> 1000 DAC (per 1 OCFR20, If Needed: 13, 14
.Appendix B Table 1).
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SITE EMERGENCY PLAN CLASSIFICATION
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Proc No El-1 Revision 44 Page 20 of 26 RELEASES CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS UNUSUAL EVENT Short-term radiological effluent ODCM limits The stack monitor (RIA-2326)
Mandatory: 1, 4, 5, 7, 8 exceeded.
reaches Alert alarm setpoint for greater than one hour, confirmed Subsequent: 15, 22 by sample analysis, OR Liquid Waste Discharge Monitor If Needed: 11, 14 (RIA-1049) reaches alarm setpoint and automatic discharge trip Notify Rad Services to evaluate whether 40 function fails. Confirmed by CFR 302 notifications are necessary.
sample analysis.
Significant solid or liquid waste spill outside Observation confirmed by survey restricted areas with threatened offsite results OR SED's opinion.
release.
ALERT Radiological effluent > 10 times the ODCM A valid stack monitor (RIA-2326)
Mandatory: 1, 2, 3, 4, 5, 7, 8, 9, 10,11 instantaneous release rate limit.
reading of 2 1.6E+5 cpm above background for longer than one Subsequent: 13, 14, 15, 21, 22 hour2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />, OR Liquid Waste Discharge Monitor (RIA-1 049) reaches 10 If Needed: 19, 20 -
times alarm setpoint and automatic discharge trip function fails, confirmed by sample analysis.
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Proc No El-1
- Attachment 1.
Revision 44 Page 21 of 26
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SITE EMERGENCY PLAN CLASSIFICATION RELEASES CLASSIFICATION EMERGENCY ACTION LEVEL.
METHOD OF DETECTION ACTIONS SITE AREA EMERGENCY Effluent monitors detect levels corresponding
- 1. Any of the following valid Mandatory. 1, 2, 3, 4, 5,7, 8, 9,10, 11, 13, to > 50 mrem/hr TEDE for Y2 hour or*
Radiation Monitor readings for 14,15
> 500 mrem/hr TEDE for 2 minutes (or greater than 30 mins:
5 times these levels to the Adult Thyroid Subsequent: 17, 19, 20, 21, 22, 23 CDE) at the site boundary for adverse (a) RIA-2326 2 1.3E+6 CPM meteorological conditions. These levels are above background.
If Needed: None projected based on other Plant parameters (eg, radiation level in Containment with leak (b)
RIA-2323/RIA-2324 rate appropriate for existing Containment 2 215 CPM above pressure) or are measured in the environs.
background AND steam EPA Protective Action Guidelines (see release In progress. -
Emergency Implementing Procedure El-6.13, "Protective Action Recommendations for (c) RIA-2321/RIA-2322 Offsite Populations") are projected to be 2 5.1 E+4 rem/hr above exceeded outside the site boundary.
background AND Containment integrity intact; OR
- 2. Any of the following valid Radiation Monitor readings for greater than 2 minutes:
(a) RIA-2327 2 11 mrem/hr above background.
(b) RIA-2323/RIA-2324 2 630 CPM above background AND steam release in progress.
(c)
RIA-2321/RIA-2322 2 5.1 E+5 rem/hr above background AND-Containment Integrity intact; OR
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SITE EMERGENCY PLAN CLASSIFICATION
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Proc No El-1
-Attachment 1
Revision 44 I
Page 22 of 26 RELEASES CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS SITE AREA EMERGENCY
- 3. Measured radiation levels at (Cont'd) site boundary indicate any of the following:
(a) TEDE Rate > 50 mrem/hr for 30 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.
GENERAL EMERGENCY Effluent monitors detect levels corresponding
- 1.
Any of the following Radiation Mandatory: 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, to 1 rem/hr TEDE or 5 rem/hr Adult Thyroid Monitor readings may 13,14, 15 CDE Rate at the site boundary-under actual indicate a General.
meteorological conditions. These levels are Emergency:
Subsequent: 17, 19, 20, 21, 22, 23 projected based on other Plant parameters (a)
RIA-2327 > 22 mrem/hr (eg, radiation levels in Containment with leak.
above background.
rate appropriate for existing Containment (b)
RIA-2323/RIA-2324 pressure) or are measured in the environs.
2 1260 CPM above background AND main NOTE: Refer to Emergency Implementing steam release Procedure El-6.13, Protective Action occurring.
Recommendations for Offsite Populatlons.3 (c) RIA-2321/RIA-2322 2 1.0E+6 rem/hr above background AND Containment leakage within design limits; OR
C Proc No El-1i Revision 44 Page 23 of 26 SITE EMERGENCY PLAN CLASSIFICATION RELEASES CLASSIFICATION EMERGENCY ACTION LEVEL I METHOD OF DETECTION ACTIONS GENERAL EMERGENCY
- 2.
Dose Projection from (Cont'd)
Emergency Implementing Procedure El-6.0, "Offsite Dose Calculation and Recommendations for Protective Actions," Indicate any of the following with Existing Meteorological Conditions, at or beyond the site boundary:
(a) TEDE Rate 2 1 rem integrated over a period of one hour.
(b)
Adult Thyroid CDE Rate 2 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 21 rem Integrated over a period of one hour.
(b)
Adult Thyroid CDE Rate 2 5 rem integrated over a period of one hour.
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C SITE EMERGENCY PLAN CLASSIFICATION
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Proc No El-1 Revision 44 Page 24 of 26 SAFETY INJECTION SYSTEM CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION -
ACTIONS UNUSUAL EVENT Safety Injection initiated AND discharged to Annunciation AND flow Mandatory: 1, 4, 5, 7, 8 vessel verification.
NOTE: Applies to HPSI, LPSI, or SIT (Ref EOP Supplement 4)
Subsequent: 15, 22.
Injection only. For injections solely from charging pumps/BA pumps to PCS due to FI-0307A to FI-0314A If Needed: None SIS, include as part of one hour (or four
. hours) nonemergency report per Palisades Administrative Procedure 4.00, "Operations Organization, Responsibilities and Conduct."
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- (S SITE EMERGENCY PLAN CLASSIFICATION Proc No El-1 (C
Revision 44 Page 25 of 26 SECONDARY SIDE CLASSIFICATION EMERGENCY ACTION LEVEL.
l METHOD OF DETECTION l ACTIONS UNUSUALEVENT Failure of a safety or relief valve In a safety-Annunciation AND pressure Mandatory: 1, 4, 5, 7, 8 related system to close following reduction of indications, OR observation.
applicable. pressure.
Subsequent: 15,22 Main Steam Line/Main Feedwater Line break Observation of isolated excess outside Containment which Is Isolated by Steam Demand Event conditions.
If Needed: None Main Steam Isolation signal (manually or auto).
Turbine rotating component failure causing Turbine trip AND observation of Plant shutdown.
turbine malfunction or failure.
ALERT Main Steam Line/Main Feedwater Line break Observation of excess Steam.
Mandatory: 1, 2, 3, 4, 5, 7, 8, 9, 1 0, 11 Inside or outside Containment which Is not Demafid Event conditions.
Isolated.
Subsequent: 15, 21, 22 Turbine failure causing casing penetration.
Observation AND turbine trip.
- If Needed
- None NOTE:
For accidents involving Main Steam i-ne/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."
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f' Proc No El-1 Revision 44 Page 26 of 26 SITE EMERGENCY PLAN CLASSIFICATION I
SECURITY CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS UNUSUAL EVENT Credible Security threat or attempted entry or Security alarms OR observation Mandatory: 1', 4, 5, 7, 8, 12 attempted sabotage.
AND activation of Safeguards Contingency Procedures.
Subsequent: 15, 22 SEE "NOTE 1 If Needed: None ALERT Security threat exists that results in Security Alarms OR observation Mandatory: 1-, 2, 3, 4, 5, 7, 8, 9*, 10, 11*,
adversaries commandeering an area of the AND activation of Safeguards 12 Plant, but not control over shutdown Contingency Procedures.
S capability or of any Vital areas.
Subsequent: 15, 21, 22 SEE "NOTE1
_If Needed: 15,19 SITE AREA EMERGENCY Physical attack on the Plant Involving.
Security alarms OR observation Mandatory: 1*, 2^, 3*, 4, 5, 7, 8, 9*, 10, 11*,
imminent occupancy of the Control Room, AND activation of Safeguards 112,14", 15 auxiliary shutdown panels, or other Vital Contingency Procedures.
areas.
Subsequent: 17*, 21, 22 If.Needed: 13,19, 20 GENERALEMERGENCY Physical attack on the Plant has resulted in Security alarms OR observation.
Mandatory,. 1', 2*, 3*, 4, 5, 6, 7, 8*, 9*, 10, unauthorized personnel occupying the, AND activation of Safeguards 1 11*, 12, 13, 14*, 15 Control Room or any other Vital areas.
Contingency Procedures.
Subsequent: 17*, 21, 22, 23 If Needed: 16, 18, 19, 20 NOTE 1:
Refer to Emergency Implementing Procedure El-1.1, "Emergency Response To 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.
- Performance of this action may be delayed until the safety of Personnel Is assured.
EMERGENCY ACTIONS/NOTIFICATIONS Proc No El-1
- - Revision 44 Page 1 of 1
_f' EVENT TYPE (Circle one): UE / ALERT I SAE / GENERAL Date:
ACTION (INITIAL)]
ITEM (circle)
DESCRIPTION OF ACTION REF DONE? l 1
M S I Announce Emergency on PA E1-3 2
M S I Sound Emergency Siren El-3 3
M S I Initiate Staff Augmentation - Notify Security at Ext 2278 See Note 4 El-2.2 below 4
M S I Notify Van Buren' County (within 15 min of declaration) See Notes 2 and 3. El-3 below 5
MS I Notify State of Michigan 4within 15 minofdeclaration) See Notes 2. and 3... El-3..
below 6
MS I Provide Protective Action Recommendation El-6.13 7
M S I Call Duty and Call Superintendent, N/A 8
M S I Notify NRC See Ndte 1.below_.
El-3_
9 M S I Perform Personnel Accountability - Notify Security at Ext 2278 El-12.1 10 MSI Activate ERDS SOP-34 11 M S I Initiate Onsite Monitoring El-8 12 M S I Activate Safeguards Contingency Procedures N/A 13 M S I Perform Offsite Dose Assessment El-6.0.
14 M S I Initiate Offsite Monitoring E1-9 15 M S I Notify Public Affairs - Day @ 764-8931 Night @.637-5170 El-3 16 M S I Activate Fire Protection Plan FPIPs 17 M S I Evacuate Nonessential Personnel El-13 18 M S I Notify Covert Fire Dept and Call Security @ 2278 El-3 19 M S I Perform Core Damage Calculation El-7.0/E-1 1 20 M S I Perform Environmental Assessment El-10 21 M S I Initiate Re-entry/Recovery El-5.0/EI-5.1 22 M S I Initiate Action Request FP-PA-ARP-01 l
23 M S I Monitor Severe Accident Management Guideline for Implementation SAMGs I
LEGENDS: M=MANDATORY S=SUBSEQUENT I=IF NEEDED NOTES:
- 1. =
10CFR50.72(c) REQUIRES THAT CONSUMERS ENERGY/NMC MAINTAIN AN OPEN. CONTINUOUS COMMUNICATION CHANNEL WITH THE NRC OPERATIONS UPON REQUEST OF THE NRC'
- 2. =
30 MINUTE UPDATES REQUIRED WHEN ABOVE UE
- 3. =
REFER TO El-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 CAPTAIN AT (EXT 2278) WHO WILL INITIATE THE EMERGENCY AUGMENTATION NOTIFICATION SYSTEM.
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 />.