ML033570376
| ML033570376 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 12/15/2003 |
| From: | Consumers Energy |
| To: | Mcknight J Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 255804 EI-1, Rev 43 | |
| Download: ML033570376 (27) | |
Text
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Date Entered: Dec 15, 2003 TO: USNRCiWASHINGTON JMCKNIGHT Copy Number: 145 TRANSMITAL NUMBER:
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, ATTACHMENT 1 REPLACE WITH El-1, R/43, ATTACHMENT 1 COPYING CORRECTION SIGN, DATE, AND RETURN THEACKNOWLEDGEMENTFORM 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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- c. C . Proc No El-1 Attachment 1
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Revision 43 SITE EMERGENCY PLAN CLASSIFICATION Page 1 of 26 ALARMS/ANNUNCIATORS CLASSIFICATION 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, 5, 7, I (annunciators) in Control Room. 8, 9,10,11 Example - loss of DC Panel D21-2 Ref ONP-2.3 Subsequent: 15, 21, 22.
If-Needed: None It, .
SITE AREA Loss of most or all alarms Observation - Modes 1 and 2 OR Modes 3, 4, Mandatory: 1, 2, 3, 4, 5, 7, I EMERGENCY (annunciators) in Control Room 5, and 6 with transient in progress. 8,9, 10, 11, 14,15 AND Plant transient initiated or in progress. Example - loss of DC Panel 021-2 Subsequent: 17, 21, 22 Ref ONP-2.3 If Needed: 19, 20
C C Proc No El-1 Attachment 1 C.
Revision 43 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: 1,4, 5, 7, 8, communication capability. (ENS) and all other phones including satellite 12 phones that could be used to make NOTE: For failures of the Palisades notifications to Van Buren County, the State of Subsequent: 15, 22 Public Warning System, see Michigan and the NRC.
Palisades Administrative Procedure If Needed: None 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.
I
C (SA Proc No El-1 C Attachment 1 Revision 43 SITE EMERGENCY PLAN CLASSIFICATION Page 3 of 26 DRY FUEL STORAGE CASK-ISFSI CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS UNUSUAL EVENT Incident involving a loaded fuel storage Radiation level 2 1 rem/hr at 1 ft from a Dry Mandatory: 1,4, 5, 7, 8 I cask OUTSIDE the Auxiliary Building. Fuel Storage Cask.
Subsequent: 15, 22 OR If Needed: 11, 13,14 Radioactive contamination level 105 dpm/1 00cm 2 beta-gamma or 103 dpm/1 00cm 2 alpha from a Dry Fuel Storage Cask.
OR I1 Airborne radioactivity analysis indicating
> 10 times the Effluent Concentration levels from a Dry Fuel Storage Cask. (10 CFR 20, 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).,
( C. Proc No El-1 Attachment 1 C.
RevIsIon 43 SITE EMERGENCY PLAN CLASSIFICATION Page 4 of 26 ENGINEERED SAFETY FEATURES CLASSIFICATION JEMERGENCY ACTION LEVEL l METHOD OF DETECTION lACTIONS UNUSUAL EVENT Inability to reach a required mode within Plant is not brought to required Mandatory: 1, 4, 5, 7, 8 I.
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 (RPS) Instrumentation to complete or The Reactor Protection System (RPS)
Setpoint exceeded AND the Automatic Mandatory: 1, 2, 3, 4, 5, 7, 8, 9, 10,11 I
initiate an AUTOMATIC Reactor Scram RPS actuation did NOT OCCUR AND once a Reactor Protection System Manual Reactor Trip from C0-2 or Subsequent: 15, 21, 22 Setpoint has been exceeded AND a CO-6 was successful.
Manual Scram was successful. If Needed: 12,19 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 2000 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, 5, 7, 8, 9, I EMERGENCY Core Heat Removal. (EOP-9.0 Heat 10,11, 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 C0-2 and C0-6 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, EMERGENCY AUTOMATIC SCRAM AND Manual AUTOMATIC Reactor Trip AND the 9,10,11, 13, 14, 15, Scram was NOT successful AND there is Manual Reactor Trip from C0-2 and indication of an extreme challenge to the C0-6 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.)
(C C( Proc No El-1 C,
Attachment 1 Revision 43 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, 5, 7, 8, 9, I anticipated or required with control of 10, 11 shutdown systems established at local Ref ONP-25.2 stations. Subsequent: 15, 21, 22
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ If N e e d e d : 12 SITE AREA Evacuation of Control Room and Observation. Mandatory: 1,2, 3, 4, 5, 7, 8, 9, I '
EMERGENCY control of shutdown systems not 10,11, 14,15 established at local stations within Ref ONP-25.2 15 minutes. Subsequent: 17, 21, 22, 23 If Needed: 12, 13, 19, 20
(: (C Proc No El-1 Attachment 1 C
Revision 43 SITE EMERGENCY PLAN CLASSIFICATION Page 6 of 26 FIRE lCLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION j ACTIONS l UNUSUAL EVENT Fire within the Plant lasting more than Observation Mandatory: 1,4, 5, 7, 8, 16 10 minutes.
OR Subsequent: 15,22 Fire detection alarm, confirmed by If Needed: 12, 18 observation.
ALERT Fire potentially affecting safety Fire can potentially disable equipment Mandatory: 1,2, 3, 4, 5, 7, 8, 9, systems. which will result in jeopardizing safety 10, 11, 16 function(s) OR SED opinion.
Subsequent: 15, 21, 22 Ref 0NP-25.1 If Needed: 12, 18 SITE AREA Fire compromising the function of Fire has disabled equipment resulting Mandatory: 1, 2, 3, 4, 5,7, 8, 9, EMERGENCY safety systems. in jeopardized safety function(s). 10, 11, 14, 15, 16 Ref QNP-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 Plant systems.
( (.E Proc No El-1 Attachment 1 C
Revision 43 SITE EMERGENCY PLAN CLASSIFICATION Page 7 of 26 FISSION PRODUCT BARRIERS/FUEL DAMAGE CLASSIFICATION I EMERGENCY ACTION LEVEL METHOD OF DETECTION l ACTIONS UNUSUAL EVENT Loss or Potential Loss SEE TABLE 1 Mandatory: 1, 4, 5,7,8 of Subsequent: 15, CONTAINMENT BARRIER 22 If Needed: None ALERT Loss or Potential Loss of SEE TABLE 1 Mandatory: 1, 2, 3,4,5,7,8,9,10, FUEL CLAD BARRIER 11 OR Subsequent: 15, 19, 21,22 PCS BARRIER If Needed: 12,13, Fuel damage/handling accident with Failed fuel as indicated by abnormally 14 release of radioactivity to Containment or High Area or Process Radiation Monitors Auxiliary Building.* in 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.
CY Proc No El-1 Attachment 1 C
Revision 43 SITE EMERGENCY PLAN CLASSIFICATION Page 8 of 26 FISSION PRODUCT BARRIERS/FUEL DAMAGE CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION j ACTIONS SITE AREA Loss or Potential Loss SEE TABLE 1 Mandatory: 1,2, EMERGENCY of any 3,4,5,7,8,9, I TWO BARRIERS 10, 11,14, 15 Major damage to irradiated fuel in Fuel Large object damages fuel or water loss Handling Building below fuel level as indicated by abnormally Subsequent: 13, High Area Monitors in the Auxiliary Building. 17,19,21,22,23 If Needed: 12,
.___________________ _ .20 GENERAL Loss of any SEE TABLE 1 Mandatory: 1,2, EMERGENCY TWO BARRIERS 3,4, 5,6, 7, 8,9, 10,11,13,14, AND 15 Potential Loss of Subsequent:
THIRD BARRIER 17,19, 21, 22,23 If Needed: 12,
______ _______ _ ____ _ _ ___ ___ _ _ _ _ _ _ _ _ __ _ _ _ __ _ _ _ _ _ __ __ _ _ __ _ _ _ _ __ _ _ _ _ _ _ 20
(7 C Proc No El-1 Attachment 1
- Revision 43 SITE EMERGENCY PLAN CLASSIFICATION Page 9 of 26 FISSION PRODUCT BARRIERS/FUEL DAMAGE TABLE 1 lI u PCS Inventory CETs M Potential Reactor water level indicates < 11 inches CETs indicate > 700 0F r Loss above the bottom of the fuel alignment plate M
a PCS Activity CETs Containment Activity
-j Coolant Activity > 32 ;uCVgm Dose CETs indicate > 1200 0F Containment Gamma Monitor (RIA-2321 is Loss Equivalent Iodine OR RIA-2322) reading > 4.0 E3 Rf/hr See El-7.0 See El-1l PCS Inventory Unisolable leak exceeding the capacity of u Potential one charging pump (40 gpm) w Loss a: ... ,.
<: PCS Inventory PCS Inventory Co Leak greater than available makeup capacity SGTR that results in an SIAS
- c. Loss as indicated by < 25 0F of PCS subcooling Containment Atmosphere CETs Containment Isolation Containment Activity cc Pressure > 70 psia OR CETs > 1200OF for more than A steam leak that cannot Containment Gamma W H 2 conc > 4.0% OR 15 minutes OR or will not be isolated by Monitor (RIA-2321 or a Potential Pressure > 4.0 psig with less than one full CETs > 700 0F with reactor vessel EOP Supplements 17 and RIA-2322) reading
< Loss train of Containment Cooling Equipment level <11 inches above the 18 > 2.5 E4 f/hr m--- operating (EOP-9.0 CA-3 safety function not bottom of the fuel alignment plate z met) for more than 15 minutes E Containment Atmosphere SGTR Containment Isolation z Rapid unexplained pressure drop following Primary to Secondary leakrate greater Containment Isolation Valve(s) not closed Loss initial rise OR Containment pressure or than 10 gpm with a steam leak that cannot following completion of EOP Supp. 6 and/or z Ls 0 sump level response not consistent with LOCA conditions or will not be Isolated by EOP Supplements 12 and 13 on affected Steam a DIRECT pathway to the environment exists I
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) or releases to the environment (eg, elevated readings on RIA 2326 or RIA 2327 or by radiological monitoring teams) I should be evaluated to determine If they represent a 'DIRECT' pathway to the environment.
(7 Proc No El-1 Attachment 1 Revision 43 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, 4, 5, 7, 8 I activity over facility which could affect Plant operation. Subsequent: 15, 22 NOTE: Onsite is defined as the If Needed: 12, 18 Owner Controlled Area outside of the 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.
(. C( Proc No El-1 C Attachment 1 Revision 43 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, 5, 7, I 8,9,10,11 NOTE: Facility is defined as nonvital structures inside and outside of the Subsequent: 15, 21, 22 Protected Area.
If Needed: 12,16,18 Missile impact from whatever source Observation.
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, 5, 7, I EMERGENCY by impact or fire AND Plant not in 8, 9, 10, 11, 14, 15 Mode 5 or 6.
Subsequent: 17, 21, 22, 23 Severe damage to equipment required Observation.
for safe shutdown from missiles or If Needed: 12,13,16,18, explosion. 19, 20 Entry of uncontrolled flammable gas Observation OR SED's opinion OR detection into Vital areas OR entry of with portable instrumentation.
uncontrolled toxic gas into Vital areas that constitute a safety problem AND Plant not in Mode 5 or 6.
(I. C Proc No El-1 -
Attachment 1 Revision 43
. 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, 4, 5, 7, 8 I 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 If Needed: 12 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 OR when 10 CFR 50.54(x) Mandatory: 1,2, 3, 4, 5, 7, precautionary activation of Technical is invoked. 8, 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, 5, 7, EMERGENCY State and County. Emergency Operations operation outside the Plant's licensed 8, 9,10,11, 14, 15 Centers and monitoring teams or a basis, when 10 CFR 50.54(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, EMERGENCY amounts of radioactivity in a short time 7, 8, 9, 10, 11, 13, 14,15 possible (eg, any core melt situation).
Subsequent: 17, 19, 21, Any major internal or external events (eg, SED's opinion. 22S, 23 fires, earthquakes, substantially beyond design basis) which could cause massive If Needed: 12, 16, 18, 20 common damage to Plant systems.
( C. Proc No El-1 Attachment 1 C
Revision 43 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'), or Mandatory: 1,4, 5, 7, 8 I station seismic instrumentation which does NOT measurement (see Note2).
cause damage to Plant equipment or structures. Subsequent: 15,22 Abnormal water levels including flood or low Flood, seiche - observation of water water or seiche. approaching 590' level. If Needed: 12 Low water - Ultimate Heat Sink level lowers to < 572' 0" (216" below Intake Structure floor level; LI-1338)
Tornado onsite. Observation ALERT Any earthquake that exceeds operating base Observation (see Note'), or Mandatory: 1,2, 3, 4, 5, I earthquake surface acceleration levels of 0.1G, measurement (see Note2). 7, 8, 9,10,11 but not greater than 0.2G; no damage to equipment required for safe shutdown. Subsequent: 15, 21, 22 Flood, low water, or seiche near design basis. Flood, seiche - observation of water above 590' level. If Needed: 12, 16, 18 Low water - Ultimate Heat Sink level lowers to 569' (LI-1338).
Tornado striking facility. Observation NOTE: Facility is defined as nonvital structures
,inside and outside of 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 1-303-273-8427, or 1-303-273-8428 (off normal hours).
NOTE2: 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 l&C Department.
C. C. Proc No El-1 Attachment 1
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Revision 43 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, 5, I EMERGENCY earthquake surface acceleration levels or 0.2G. (See Note2 Page 13) 7, 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' Page 13) needed to safely shut down the Plant. If Needed: 12,13,16, Flood, low water, or seiche greater than design Flood, seiche - observation of water 18, 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-1 338).
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.
(7 C Proc No El-1i Attachment 1 Revislon 43 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, 4, 5, 7, 8 I EVENT hour AND EK-0548 125 DC Bus undervoltage trouble NOT alarming AND PCS temperature Subsequent: 15, 22 greater than 200 0F 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 0F highest T,/Tc.
0 ALERT Loss of offsite AND onsite AC power for less than 15 minutes.
Bus 1C AND I D low voltage (C-04). Mandatory: 1, 2, 3, 4, 5, 1I 7,8,9,10,11 Loss of all onsite DC power. DC Bus Di IA AND D21 A de-energized OR both DC Bus voltages less than 105V. Subsequent: 15, 21, 22 EVI-27D1 & EVI-27D2 (D-30L/D-30R)
If Needed: 12 SITE AREA EMERGENCY Loss of offsite AND onsite AC power for more than 15 minutes.
Bus 1C AND 1D low voltage (C-04). Mandatory: 1, 2, 3, 4, 5, I 7,8, 9,10,11,14,15 Loss of all vital onsite DC power for DC Bus DI1 A AND D21 A deenergized OR both more than 15 minutes, AND Plant not DC Bus voltages less than 105V. Subsequent: 17, 21, 22 in Mode 5 or 6. EVI-27D1 & EVI-27D2 (D-30UD-30R)
If Needed: 12, 13, 19, 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.
( C. Proc No El-1 Attachment 1
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Revision 43 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 1D 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 If 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.
(C C. Proc No El-1 Attachment 1 C
Revision 43 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: 1,4, 5, 7, 8 I 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) If Needed: None Steam Generator secondary water S/G sample analysis.
activity > 0.1 ItCi/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 < 40 gpm. Generator Tube Leak." I 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: Lifting of RV-2006 (Letdown Relief) as expected for Plant conditions or evolutions does not require activating the emergency plan.
C SC.Y Proc No El-1 C Attachment 1 Revision 43 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, 4, 5, 7, 8 I Protection System (LTOP). EK-1 373 (SV and/or PORV OPEN)
Subsequent: 15, 22 NOTE: Momentary PORV activations which occur during PORV Isolation If Needed: None Valve opening shall not be considered 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 < 250F subcooled. Observation, AND Plant above Mode 5. Mandatory: 1, 2, 3, 4, 5, 7, I
- PPC point TOETMAR Subsequent: 15, 21, 22 If Needed: None
C( (1- Proc No El-i c Attachment 1
-Revision 43 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, 5, I contamination indicates a 1000, confirmed OR unexpected Plant area. 7, 8, 9,10,11 severe degradation in control of iodine or particulate airborne concentrations radioactive materials. > 1000 DAC (per 10 CFR 20, Appendix B Subsequent: 15, 21, 22 Table 1).
_ If N eeded: 13 , 14
(C Proc No E-1i Attachment 1 Revision 43 SITE EMERGENCY PLAN CLASSIFICATION Page 20 of 26 RELEASES CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS UNUSUAL EVENT Short-term radiological effluent The stack monitor (RIA-2326) reaches Alert Mandatory: 1, 4, 5, 7, 8 ODCM limits exceeded. alarm setpoint for greater than one hour, 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 40 CFR threatened offsite release. 302 notifications are
__ ___ _ _ _ _ _ _ _ _ _ __,_ _ _ _ _ _ _ _ _ __._ _ _ _ _ _ _ _ _ _ _ , _ __ __ n e ce ssar y .
ALERT Radiological effluent > 10 times the A valid stack monitor (RIA-2326) reading of Mandatory: 1, 2, 3, 4, 6, ODCM instantaneous release rate Ž1.6E+5 cpm above background for longer than 7, 8, 9,10,11 limit. one hour, OR Liquid Waste Discharge Monitor (RIA-1 049) reaches 10 times alarm setpoint and Subsequent: 13, 14, 15, automatic discharge trip function fails, confirmed 21, 22 by sample analysis.
If Needed: 19, 20
( Proc No El-1 Attachment 1 Revision 43 ;
SITE EMERGENCY PLAN CLASSIFICATION Page 21 of 26 RELEASES CLASSIFICATION I EMERGENCY ACTION LEVEL M METHOD OF DETECTION l ACTIONS SITE AREA Effluent monitors detect levels 1. Any of the following valid Radiation Monitor Mandatory: 1, 2, 3, 4, 5, I EMERGENCY corresponding to > 50 mrem/hr readings for greater than 30 mins: 7, 8, 9,10,11,13,14,15 TEDE for Y/2 hour or > 500 mrem/hr TEDE for 2 minutes (or 5 times these (a) RIA-2326 2 1.3E+6 CPM above Subsequent: 17,'19, 20, levels to the Adult Thyroid CDE) at background. 21, 22, 23 the site boundary for adverse meteorological conditions. These (b) RIA-2323/RIA-2324 2 215 CPM above If Needed: None levels are projected based on other background AND steam release in Plant parameters (eg, radiation level progress.
in Containment with leak rate appropriate for existing Containment (c) RIA-2321/RIA-2322 2 5.1 E+4 rem/hr pE pressure) or are measured in the above background AND Containment environs. EPA Protective Action integrity intact; OR Guidelines (see Emergency implementing Procedure El-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 2 11 mrem/hr above site boundary. 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 1 .1 J
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Proc No El-1 C.
Attachment 1 Revision 43 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 EMERGENCY . indicate any of the following:
(Cont'd) (a) TEDE Rate > 50 mrem/hr for 30 minutes.
(b) TEDE Rate > 500 mremlhr for 2 minutes. I (c) Adult Thyroid CDE Rate > 250 mrem/hr for 30 minutes.
(d) Adult Thyroid CDE Rate > 2500 mrem/hr for 2 minutes.
C Proc No El-1 Attachment 1 C
Revision 43 SITE EMERGENCY PLAN CLASSIFICATION Page 23 of 26 RELEASES CLASSIFICATION I EMERGENCY ACTION LEVEL I METHOD OF DETECTION l ACTIONS GENERAL Effluent monitors detect levels 1. Any of the following Radiation Monitor readings Mandatory: 1, 2, 3, 4, 5, EMERGENCY corresponding to 1 rem/hr TEDE or may indicate a General Emergency: 6,7,8,9,10,11,13,14, 5 rem/hr Adult Thyroid CDE Rate at 15, the site boundary under actual (a) RIA-2327 2 22 mrem/hr above meteorological conditions. These background. Subsequent: 17, 19, 20, levels are projected based on other 21,22, 23 (b) RIA-2323/RIA-2324 2 1260 CPM above Plant parameters (eg, radiation background AND main steam release levels in Containment with leak rate occurring.
appropriate for existing Containment pressure) or are measured in the (c) RIA-2321/RIA-2322 Ž1.OE+6 rem/hr environs. above background AND Containment leakage within design limits; OR NOTE: Refer to Emergency Implementing Procedure El-6.13, 2. Dose Projection from Emergency Implementing "Protective Action Recommendations Procedure El-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 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 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.
(7 Proc No El-1 C Attachment 1 Revision 43 SITE EMERGENCY PLAN CLASSIFICATION Page 24 of 26 SAFETY INJECTION SYSTEM CLASSIFICATION EMERGENCY ACTION LEVEL METHOD OF DETECTION ACTIONS
.~~~~~~ ______________._____________ .. ~~~~~~~~~~~~~~~~~
UNUSUAL EVENT Safety Injection initiated AND Annunciation AND flow verification. Mandatory: 1, 4, 5, 7, 8 I discharged to vessel (Ref EOP Supplement 4)
Subsequent: 15, 22 NOTE: Applies to HPSI, LPSI, or
- FI-0307A to FI-0314A SIT Injection only. For injections If Needed: None solely from charging pumps/BA 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."
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Revision 43 SITE EMERGENCY PLAN CLASSIFICATION Page 25 of 26 SECONDARY SIDE I~~
CLASSIFICATION
~ _ _ _ _ . EMERGENCY ACTION LEVEL
.. METHOD OF DETECTION ACTIONS I
UNUSUAL EVENT Failure of a safety or relief valve in a Annunciation AND pressure indications, OR Mandatory: 1, 4, 5, 7, 8 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, 5, 7, 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.
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."
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Revislon 43 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*, 4, 5, 7, 8, 12 I attempted entry or attempted activation of Safeguards Contingency sabotage. Procedures. Subsequent: 15, 22 See NOTE 1 If Needed: None ALERT Security threat exists that results in Security Alarms OR observation AND Mandatory: 1*, 2*, 3*, 4, 5, adversaries commandeering an activation of Safeguards Contingency 7, 8, 9*, 10, 11*, 12 area of the Plant, but not having Procedures.
control over shutdown capability or See NOTE 1 Subsequent: 15, 21, 22 of any Vital areas.
.___________________________________ If N eeded: 15,19 U'
SITE AREA Physical attack on the Plant Security alarms OR observation AND Mandatory: 1*, 2*, 3* 4, 5, EMERGENCY involving imminent occupancy of activation of Safeguards Contingency 7, 8, 9* 10, 11*, 12, 14*, 15 I 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, I EMERGENCY resulted in unauthorized personnel activation of Safeguards Contingency 6, 7, 8*, 9* 10,11*, 12, 13, occupying the Control Room or Procedures. 14, 15 any other Vital areas.
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.