ML20117L503
| ML20117L503 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 08/29/1996 |
| From: | Mccollum W DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9609170007 | |
| Download: ML20117L503 (114) | |
Text
11 l Dahe hu er Company buu.:nt R 11:C aut p Catau ba Nuckar Generatmn Department L h e nni,knt 1800 Concord Road W1:c! i.m offi, e vik. scsts runis.nauna DUKEPOWER August 29, 1996 Document Control Desk U S Nuclear Regulatory Commission Washington, DC 20555
Subject:
Catawba Nuclear Site, Docket Nos. 50-413/50-414 Submission of Section D, Catawba Nuclear Site Emergency ,
Plan - Adoption of NUMARC/NESP-007, Rev. 2 Classification Scheme Duke Power Company is submitting the classification scheme !
provided in NUMARC/NESP-007, Rev. 2, for Catawba Nuclear Site.
Approval of the submittal is requested prior to final implementation. A table showing the disposition of NUMARC/NESP-007, Rev. 2 Initiating Conditions and Emergency Action Levels (EAL) in the Catawba EAL submittal is enclosed. A BASIS document is provided which cross-references the initiating conditions described in the NUMARC document. A copy of the classif.ication ,
procedure is also enclosed. This procedure has been reviewed by the state and local governments within the plume exposure EPZ. .
Their concurrence letters are enclosed. If there are any ;
questions regarding the submittal, please contact Gary L. j Mitchell at (803) 831-3235.
l Yours truly,
,dhh? r- ~ .
W.R. McCollum, .
Vice President i
Encl.: 1) Disposition of NUMARC/NESP-007, Rev. 2 Initiating Conditions and Emergency Action Levels (EAL) in the Catawba EAL submittal
- 2) Catawba Emergency Plan Section D
- 3) Catawba Procedure RP/0/A/5000/01
- 4) State and County concurrence letters 9609170007 960829 I PDR ADOCK 05000413 F ppg
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J US Wuclear Regulatory Commission August 29, 1996 !
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I cc: (w/ attachments) I Mr. Stewart Ebneter Regional Administrator US Nuclear Regulatory Commission i Region II 101 Marietta Street, NW, Suite 2900 )
Atlanta, GA 30323 i l
NRC Resident Inspector l
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ENCLOSURE 1 l Disposition of NUMARC/NESP-007, Rev. 2 j Initiating Conditions and Emergency Action Levels (EAL) l in Catawba EAL submittal i
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Catawba Nuclear Site Disposition of NUMARC/NESP-007, Rev. 2 IC/EAL in Catawba EAL Submittal NUMARC IC/EAL Catawba EAL Recognition Category and EAL Number Recognition Category A AUl/l Abnormal Rad Levels / Radiological Effluent 4.3.U.1-1 and -2 AUl/2 Abnormal Rad Levels / Radiological Effluent 4.3.U.1-3 and -4 AUl/3 Deleted -- Catawba does not have perimeter monitors
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AUl/4 Deleted -- Catawba does not have real time dose assessment AU2/1 Abnormal Rad Levels / Radiological Effluent 4.3.U.2-1 AU2/2 Abnormal Rad Levels / Radiological Effluent 4.3.U.2-2 AU2/3 Deleted -- Catawba does not have dry fuel storage AU2/4 Abnormal Rad Levels / Radiological Effluent 4.3.U.2-3 AAl/l Abnormal Rad Levels / Radiological Effluent 4.3.A.1-1 and -2 AAl/2 Abnormal Rad Levels / Radiological Effluent 4.3.A.1-3 and -4 AAl/3 Deleted -- Catawba does not have perimeter monitors
. AAl/4 Deleted -- Catawba does not have real time dose assessment AA2/1 Abnormal Rad Levels / Radiological Effluent 4.3.A.2-1 ,
AA2/2 Abnormal Rad Levels / Radiological Effluent 4.3.A.2-2 AA2/3 Abnormal Rad Levels / Radiological Effluent 4.3.A.2-3 AA2/4 Abnormal Rad Levels / Radiological Effluent 4.3.A.2-2 AA3/1 Abnormal Rad Levels / Radiological Effluent 4.3.A.3-1 AA3/2 Abnormal Rad Levels / Radiological Effluent 4.3.A.3-2 AS1/l Abnormal Rad Levels / Radiological Effluent 4.3.S.1-1 ASl/2 Deleted -- Catawba does not have perimeter monitors AS1/3 Abnormal Rad Levels / Radiological Effluent 4.3.S.1-2 AS1/4 Abnormal Rad Levels / Radiological Effluent 4.3.S.1-3 AGl/l Abnormal Rad Levels / Radiological Effluent 4.3.G.1-1 AGl/2 Deleted -- Catawba does not have perimeter menitors AGl/3 Abnormal Rad Levels / Radiological Effluent 4.3.G.1-2 AGl/4 Abnormal Rad Levels / Radiological Effluent 4.3.G.1-3 1
Catawba Nuclear Site Disposition of NUMARC/NESP-007, Rev. 2 IC/EAL in Catawba EAL Submittal NUMARC IC/EAL Catawba EAL Recognition Category and EAL Number Recognition Category F FPB Fuel /l Fission Product Barrier 4.1.F.1 FPB Fuel /2 Fission Product Barrier 4.1.F.2 FPB Fuel /3 Deleted -- Core exit thermocouples are monitored as part of Critical Safety Function (CSF) status. If the OAC is not available, manual monitoring is done per F/0, " Critical Safety Function Status" and will be used to classify.
FPB Fuel /4 Deleted -- Reactor Vessel level is monitored as part of CSF status. If the OAC is not available, manual monitoring is done per F/0, " Critical Safety Function Status" and will be used to classify.
FPB Fuel /5 Fission Product Barrier 4.1.F.3 FPB Fuel /6 Deleted -- Catawba does not believe additional indications are needed to determine Fuel Clad Barrier status. Air sampling (PAGS) results are not used, as containment monitors can be used to determine Fuel Clad status.
FPB Fueln Fission Product Barrier 4.1.F.4 FPB RCS/l Fission Product Barrier 4.1.N.1 FPB RCS/2 Fission Product Barrier 4.1.N.2 FPB RCS/3 Fission Product Barrier 4.1.N.3 Note: The classification procedure does not provide site specific criteria that a steam generator is ruptured.
Duke Power's philosophy is that diagnostic information of this type belongs in the Emergency Operating Procedures. Once the Emergency Coordinator / EOF Director determines that a steam generator is ruptured, the classification procedure can be used to determine the correct classification.
FPB RCS/4 Fission Product Barrier 4.1.N.4 FPB RCS/5 Deleted -- Catawba does not believe additional indications are needed to determine Reactor Coolant System Barrier status. Air sampling (PAGS) results are not used, as containment monitors can be used to determine Reactor Coolant System Barrier status.
FPB RCS/6 Fission Product Barrier 4.1.N.5 FPB Containment /l Fission Product Barrier 4.1.C.1 FPB Containment /2 Fission Product Barrier 4.1.C.2 FPB Containment /3 Fission Product Barrier 4.1.C.3 FPB Containment /4 Fission Product Barrier 4.1.C.4
- l FPB Containment /5 Fission Product Barrier 4.1.C.5 FPB Containment /6 Fission Product Barrier 4.1.C.6 Core exit thermocouples are monitored as part of CSF status. If the OAC is not available, manual monitoring is done per F/0, " Critical Safety Function Status" and will be used to classify. j FPB Containmentn Deleted -- no additional indications needed FPB Containment /8 Fission Product Barrier 4.1.C.7 2
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Catawba Nuclear Site l
Disposition of NUMARC/NESP-007, Rev. 2 IC/EAL in Catawba EAL Submittal '
NUMARC IC/EAL Catawba EAL Recognition Category and EAL Number Recognition Category H HUl/l Natural Disasters, Hazards, etc. 4.7.U.1-1 and -2 HUl/2 Natural Disasters, Hazards, etc. 4.7.U.1-3 HUl/3 Deleted -- Catawba considers this redundant to Emergency Director Judgement l HUl/4 Natural Disasters, Hazards, etc. 4.7 U.1-4 '
HUl/5 Fire and Security 4.6.U.1-2 HUl/6 Natural Disasters, Hazards, etc. 4.7.U.1-5 j HUln Deleted -- Catawba believes no additional items are needed based on !
current EAL experience HU2/1 Fire and Security 4.6.U.1-1 :
HU3/1 Natural Disasters, Hazards, etc. 4.7.U.2-1 !
l HU3/2 Natural Disasters, Hazards, etc. 4.7.U.2-2 HU4/1 Fire and Security 4.6.U.2-1 HU4/2 Fire and Security 4.6.U.1-2 and -3 HU5/1 Natural Disasters, Hazards, etc. 4.7.U.3-1 i HAl/l Natural Disasters, Hazards, etc. 4.7.A.1-1 - '
HA1/2 Natural Disasters, Hazards, etc. 4.7.A.1-2 HA1/3 Natural Disasters, Hazards, etc. 4.7.A.1-3 HA1/4 Natural Disasters, Hazards, etc. 4.7.A.1-3 l HA1/5 Natural Disasters, Hazards, etc. 4.7.A.1-3 l HA1/6 Natural Disasters, Hazards, etc. 4.7.A.1-3 HAin Natural Disasters, Hazards, etc. 4.7.A.1-3 HA2/1 Fire and Security 4.6.A.1-1 HA3/1 Natural Disasters, Hazards, etc. 4.7.A.2-1 HA3/2 Natural Disasters, Hazards, etc. 4.7.A.2-2 HA4/1 Fire and Security 4.6.A.2-1 HA4/2 Deleted -- Catawba believes no others Security Event EALs necessary based on current EAL experience HA5/1 Natural Disasters, Hazards, etc. 4.7.A.3-1 HA6/1 Natural Disasters, Hazards, etc. 4.7.A.4-1 1 HSl/l Fire and Security 4.6.S.1-1 HS1/2 Fire and Security 4.6.S.1-2 and -3 HS2/1 Natural Disasters, Hazards, etc. 4.7.S.1-1 ,
HS3/1 Natural Disasters, Hazards, etc. 4.7.S.2-1 4 HG1/1 Fire and Security 4.6.G.1-1 HG1/2 Fire and Security 4.6.G.1-2 HG2/1 Natural Disasters, Hazards, etc. 4.7.G.1-1 3
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1 Disposition of NUMARC/NESP-007, Rev. 2 IC/EAL in Catawba EAL Submittal l NUMARC IC/EAL Catawba EAL Recognition Category and EAL Number Recognition Category S SU1/1 Loss of Power 4.5.U.1-1 i SU2/1 System Malfunction 4.2.U.1-1 !
SU3/1 System Malfunction 4.2.U.2-1 {
SU4/1 Deleted -- Catawba has no failed fuel monitor. Reactor coolant -
1 sampling is used to determine fuel clad degradation. '
- SU4/2 System Malfunction 4.2.U.3-1 l SU5/1 System Malfunction 4.2.U.4-1, -2, and -3 j SU6/1 System Malfunction 4.2.U.5-1 and -2 SU7/1 Loss of Power 4.5.U.2-1 1 SA1/1 Loss of Power 4.5.A.1-1 i SA2/1 Loss of Shutdown Function 4.4.A.1-1
- SA3/1 Loss of Shutdown Function 4.4.A.2-1 and -2 SA4/1 System Malfunction 4.2.A.1-1 SA5/1 Loss of Power 4.5.A.2-1 i SS1/l Loss of Power 4.5.S.1-1 SS2/1 Loss of Shutdown Function 4.4.S.1-1 i SS3/1 Loss of Power 4.5.S.2-1 ;
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SS4/1 Loss of Shutdown Function 4.4.S.2-1, -2, and -3 1 SSS/1 Loss of Shutdown Function 4.4.S.3-1,-2, and -3 ,
SS6/1 System Malfunction 4.2.S.1-1 1 SG1/l .
Loss of Power 4.5.G.1-1 1
SG2/1 and 2 Loss of Shutdown Function 4.4.G.1-1 I
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ENCLOSURE 4.1 Catawba Nuclear Site FISSION PRODUCT BARRIER MATRIX Use EALs to determine Fission Product Barrier status (Intact, Potential Loss, or Loss). Add points for all 3 barriers. Classify according to the table below.
Note 1: This table is only applicable in Modes 1-4.
Note 2: Also, an event (or multiple events) could occur which results in the conclusion that exceeding the Loss or Potential Loss thresholds is IMMINENT (i.e., within 1-3 hours). In this IMMINENT loss situation, use judgernent and classify as if the thresholds are exceeded.
Unusual Event it - 3 Points) Alert f 4 - 6 Points) site Area Emeroency(7 General Emeroenev (11 - 13 Points)
- 10 Points)
. Any Potential Loss of Containrnent . Any Potential Loss or Loss of the . Loss of both NCS . Loss of any three barriers NCS and Fuel Qad
. Any Loss of Containment . Any Potential Loss or Loss of Fuet . Potential Loss of . Loss of any two barriers and the Poter:tial Loss of the Qad both NCS and Fuel third banier Qad
. Potenial Loss of either the NCS or Fuel Qad and Loss of anyadditional barrier CONTAINMENT 3AFIRIER NCS BARRIER FUEL CLAD BARRIER POTENTIAL LOSS - LOSS -(3 Point (s)) POTENTIAL LOSS- LOSS -(5 Point (s)) POTENTIAL LOSS -(5 Point (s))
(1 Point (s)) (4 Point (s)) LOSS-(4 Point (s))
1.CrthsalSaisty funcean Stahm 1.CrhicalSainty Furicton Status 1. Critical Salsty Function Stabas
- e Not apphtable e NCs k1teytyfted
- Nat apphcable
- Core Coolrq
- Core Cocing-Red ContammentftED orange
. Heat sr*4ted
. Heat sr*4ted 1 Canlainment Candilona 2.NCS lank Rate 1 Primary Coolant Actrvtty Level e Mapid unesphuned deceasein
- Unedableleak exceedngme
- GREATER THAN avalable
- Not apphcatie
- Coolant Acevey GREATER THAN 300 pCda:
e Contarvnent Pressure >15 contas1 ment pressurelocoung capaaty of one chargng pump makaup capa:ity as Dese Equivalentlodne(DEI)6-131 PstG inmal kcease la me nomialchargng node indcated by a loss of NCs
- H2 conconkahan > 9% utletcbun sciated sutxmoirg
- Contanment pressure or surg
- Contanment pressure greater levelresponse not conssient man 3 psig mithless man one uth LOCA condsons.
lud ran of Ns and a VXCARF operatry
ENCLOSURE 4.1 Catawba Nuclear Site FISSION PRODUCT BAPalER MATRIX CONTAINMENT BARRIER NCS BARRIER FUEL CLAD BARRIER POTENTIAL LOSS - LOSS -(3 Point (s)) POTENTIAL LOSS- LOSS -(5 Point (s)) POTENTIAL LOSS - LOSS -(5 Point (s))
(1 Point (s)) (4 Point (s)) (4 Point (s))
2 ContanmentisolationValvesStatus AfintContainmanilacIntlen 1 SG Tube Rushre 1 Containment Radletion MonMoring Achmalan
- Not appicable
- Contanment solabanis
- Pnmary*Secondaryleait rate e Inscanon mat a SG a Ruptured
- Contammert radiaton momtor 53 A or 538 readng >117 RMr mcorrplete and a release pam emmeds the capacey of one and has a Nonisolable fromcontamment omsts charging pur9inmenormal secondaryline tault ourgng mode meleidoun solated.
- Indcanon mat a SG e n@tured and a prolonged elease of cortamnated secondary cxAart a ocxumng trom me affected SG 2 es emnronment 4 SG Secondary Side Rainnes Widi PrhhSecondary Lankaas 4. Containment Hadlellon leonitoring 4. Energency CoorenatorEOF Director Judgement e Not apphcable
- Release of secondary sde b o Not apphcable + Unplanned Vandinp 11 alarm + Any condson, includng mabary to monitor te bamer, mat m ee apruan almosphere me prunary to on EMFs 38,39,or 40 d the Emergency CoorenatorEOF Dredor udcates LOSS or secondaryleakage GREATER POTENTIAL LOSS d lhe fuelclad bamer.
THAN Tech Spec anowable
- 5. Signacant Radoactive twentory in Containment i Emergency CoorenatorEOF Director %
- Contanmert Rai Mondor o Not appbcable
- Any condton, edudng mabity to monitor to bamer, tat m te opruan EMF 53A or 53B of me Emergency Coordnator EOF Dredor iiecales LOSS or Readng 0 trne ence POTENTIALLOSSof theNCSbamer.
shutdown.
> 470 Rhr G 0 -0.5 hr
> 170 RMr 0 0.5-2 hr
> 125 RMr 8 2 4 hr
> 90IWr 4 4 8 hr
> 53 fWr 9 > 8 tr L Core Coodng
+ Coremoing REDpamis
- Not appbcable mecated for > 15 run.
- 7. f_.-- C_ ^ -EOFE'- - '
. Any condson,indueng nabety m moner the ba.w. mat in me opaan of the Emergency Coordnator/ EOF Dredor indcates LOSS or POTENTIAL LOSS of me mnianmort bemer.
Catawba Nuclear Site ENCLOSURE 4.2 SYSTEM MALFUNCTION UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.2.U.I Inability to Reach Required 4.2.A.I Unplanned Loss of Most or 4.2.S.1 Inability to Monitor a Shutdown Within All Safety System Significant Transient in Technical Specification Annunciation or Indication Progress Limits in Control Room With Either-(1) a Significant Transient in Progress, or (2) Compensatory Non-Alarming Indicators Unavailable 4.2.U.2 Unplanned Loss of Most or All Safety System Annunciation or Indication in the Control Room for Greater Than 15 Minutes 4.2.U.3 Fuel Clad Degradation 4.2.U.4 Reactor Coolant (NCS)
System Leakage 4.2.U.5 Unplanned Loss of All Onsite or Offsite Communications 2
h----- .- - _ _ _ _ _ . _ _ . _ _ . _ _ _ _ . _ _ _ . . _ _ _ _ _ _ _ _ _ . . _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , _ _ . _ _ _ _ _
Catawba Nuclear Site ENCLOSURE 4.3 ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENT UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.3.U.I Any Unplanned Release of 4.3.A.I Any Unplanned Release of 4.3.S.I Boundary Dose Resulting 4.3.G.1 Boundary Dose Resulting Gaseous or Liquid Gaseous or Liquid from an Actual or Imminent from an Actual or Radioactivity to the Radioactivity to the Release of Radioactivity Imminent Release of Environment that Exceeds Envircnment that Exceeds Exceeds 100 mrem TEDE Radioactivity that Exceeds Two Times the SLC Limits 200 Times the SLC Limits or 500 mrem CDE Adult 1000 mrem TEDE or 50(X) for 60 Minutes or Longer for 15 Minutes or Longer Hyroid for the Actual mrem CDE Adult Dyroid or Projected Duration of the for the Actual or Projected Release Duration of the Release 4.3.U.2 Unexpected Increase in 4.3.A.2 Major Damage to Irradiated Plant Radiation or Airborne Fuel or Loss of Water Concentration Level that Has or Will Result in the Uncovering ofIrradisted Fuel Outside the Reactor Vessel 4.3.A.3 Release of Radioactive Material or Increases in Radiation Levels Within the Facility Rat Impedes Operation of Systems Required to Maintain Safe' Operations or to Establish or Maintain Cold Shutdown
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Catawba Nuclear Site t
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,f ENCLOSURE 4.4 ,
LOSS OF SHUTDOWN FUNCTION ,,
UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENGI
,F 4.4.A.1 Failure of Reactor 4.4.S.I Failure of Reactor Protection 4.4.G.1 Failure of the Reactor Protection System System Instrumentation to Protection System to Instrumentation to Complete or Initiate an Complete an Automatic Complete or Initiate an Automatic Reactor Trip Trip and hianual Trip was Automatic ReactorTrip Once a Reactor Protection NOT Successful and Here Once a Reactor Protection System Setpoint lias Been is Indication of an Extreme System Setpoint lias Been Exceeded and hianual Trip Challenge to the Ability to Exceeded and hianual Trip Was NOT Successful Cool the Core Was Successful 4.4.A.2 Inability to hiaintain Plant 4.4.S.2 Complete Loss of Function in Cold Shutdown Needed to Achieve or hiaintain flot Shutdown 4.4.S.3 Loss of Water Level in the Reactor Vessel nat lias or Will Uncover Fuelin the Reactor Vessel 4
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Catawba Nuclear Site ENCLOSURE 4.5 LOSS OF POWER UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.5.U.1 Loss of All Offsite Power to 4.5.A.I Loss of All Offsite Power 4.5.S.I Loss of All Offsite Power 4.5.G.1 Prolonged Loss of All Essential Busses for Greater and Loss of All Onsite AC and Loss of All Onsite AC (Offsite and Onsite) AC Han 15 Minutes Power to Essential Busses Power to Essential Busses Power During Cold Shutdown Or Refueling Mode 4.5.U.2 Unplanned Loss of Required 4.5.A.2 AC power to essential 4.5.S.2 Loss of All Vital DC Power DC Power During Cold busses reduced to a single Shutdown or Refueling power source for greater Mode for Greater than 15 than 15 minutes such that Minutes an additional single failure could result in station blackout J
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Cataw ba Nuclear Site ENCLOSURE 4.6 FIRE / EXPLOSION AND SECURITY EVENTS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.6.U.I Fire or Explosion Within 4.6.A.I Fire or Explosion Affecting 4.6.S.I Security Event in a Plant 4.6.G.1 Security Event Resulting in Protected Area Boundary the Operability of Plant Vital Area Loss Of Ability to Reach Not Extinguished Within 15 Safety Systems Required to and Maintain Cold Minutes of Establish or Maintain Safe Shutdown Detection Shutdown 4.6.U.2 Confirmed Security Event 4.6.A.2 Fire or Explosion Affecting Which Indicates a Potential the Operability of Plant Degradation in the Level of Safety Systems Required to Safety of the Plant Establish or Maintain Safe Shutdown 4.6.A3 Security Event in a Plant Protected Area J
Catawba Nuclear Site ENCLOSURE 4.7 NATURAL DISASTERS, HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.7.U.I Natural and Destructive 4.7.A.1 Natural and Destructive 4.7.S.I Control Room Evacuation 4.7.G.! Other Conditions Existing Phenomena Affecting the Phenomena Affecting the Iles Been Initiated and Which in the Judgement of Protected Area Plant Vitai Area Plant Control Cannot Be the Ernergency Established Coordinator / EOF Director Warrant Declaration of General Emergency 4.7.U.2 Release of Toxic or 4.7.A.2 Release of Toxic or 4.7.S.2 Other Conditions Existing Flammable Gases Deemed Flammable Gases Within a Which in the Judgement of Detrimental to Safe Facility Structure Which the Emergency Operation of the Plant Jeopardizes Operation of Coordinator / EOF Director Systems Required to Warrant Declaration of Site Maintain Safe Operations Area Emergency or to Establish or Maintain Cold Shutdown 4.7.U.3 Other Conditions Existing 4.7.A.3 Control Room Evacuation Which in the Judgement of flas Been Initiated the Emergency Coordinator / EOF Director Warrant Declaration of an Unusual Event 4.7.A.4 Other Conditions Existing Which in the Judgement of the Emergency Coordinator / EOF Director J Warrant Declaration of an Alert
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l ENCLOSURE 2 Catawba Emergency Plan Section D 4
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D. EMERGENCY CLASSIFICATION SYSTEM
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- Regulatory Guide 1.101, Rev. 3, August 1992, approved the guidance provided by
- NUMARC/NESP-007, Revision 2, as an alternative methodology for the
[ development of Emergency Action Levels. Catawba Nuclear Site will use the i NUMARC guidance for the development of initiating conditions and emergeny j action levels.
- The emergency classification system utilizes four categories for classification of i emergency events.
j D.I.a UNUSUAL EVENT
{ Events are in process or have occurred which indicate a potential degradation of 1
the level of safety of the plant. No releases of radioactive material requiring offsite i response or monitoring are expected unless further degradation of safety systems occurs. -
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- The purpose of this class is to provide notification of the emergency to the station
- staff, State and Local Government representatives, and the NRC.
Specific initiating conditions and their corresponding emergency action levels are provided in the Basis Document beginning on page D-4.
3 D.l.b ALERT 1
! Events are in process or have occurred which involve an actual or potential l substantial degradation of the level of safety of the plant. Any releases are
- expected to be limited to small fractions of the EPA Protective Action Guideline j exposure levels.
The purpose of this class is to assure that emergency personnel are readily i available to:
i j 1. Activate the onsite response centers
! 2. Respond if the situation becomes more serious or to perform confirmatory j radiation monitoring if required ,
- 3. Provide offsite authorities current status information t
Specific initiating conditions and their corresponding emergency action levels are
- provided in the Basis Document beginning on page D-4.
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Catawba Nuclear Site D.I.c. 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. Any releases are not expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels except near the site boundary.
The purpose of the Site Area Emergency is to:
- 1. Activate the offsite response centers
- 2. Assure that monitoring teams are mobilized
- 3. Assure that personnel required for taking protective actions of near site areas are at duty stations should the situation become more serious.
- 4. Provide current information to the public and be available for consultation '
with offsite authorities Specific initiating conditions and their corresponding emergency action levels are provided in the Basis Document beginning on page D-4.
D.I.d. GENERAL EMERGENCY Events are in process or have occurred which involve actual or imminent -
substantial core degradation or melting with potential for loss of containment integrity. Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area.
The purpose of the General Emergency is to:
- 1. Initiate predetermined protective actions for the public
- 2. Provide continuous assessment ofinformation from onsite and offsite measurements
- 3. Initiate additional measures as indicated by event releases or potential l releases ,
- 4. Provide current information to the public and be available for consultation j with offsite authorities Specific initiating conditions and their corresponding emergency action levels are provided in the Basis Document beginning on page D-4.
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Catawba Nuclear Site t' i
D.2. INITIATING CONDITIONS i
The initiating conditions and their corresponding emergency actions levels are contained in the BASIS document beginning on page D-4.' A classification i procedure (RP/0/A/5000/01) will be used to classify events as they occur. ,
Specific response procedures are in place which delineate the required response -
during the appropriate classification. ;
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Catawba Nuclear Site ENCLOSURE 4.1 BASIS INFORMATION FOR FISSION PRODUCT BARRIER REFERENCE TABLE CONTAINMENT BARRIER EALs: (C.1 or C. 2 or C. 3 or C. 4 or C. 5 or C. 6 or C. 7)
The Containment Barrier includes the containment building, its connections up to and including the outermost containment isolation valves. This barrier also includes the main steam, feedwater, and blowdown line extensions outside the containment building up to and including the outermost secondary side isolation valve.
Critical Safety Function (CSF) indications are not meant to include transient alarm conditions which may appear during the start-up of engineered safeguards equipment. A CSF condition is satisfied when the alarmed state is valid and sustained.
4.1.C.1 Critical Safety Function Status Containment - RED indicates containment conditions which may challenge the containment integrity. Therefore, this condition represents a potential loss of the containment barrier.
There is no " Loss" EAL associated with this item.
4.1.C.2 Containment Conditions Containment pressure above 15 psig (the design pressure) indicates that the containment or its heat removal systems are not functioning as intended. This degradation of containment pressure control represents a potentialloss of containment integrity.
A containment hydrogen concentration of 9 volume percent is sufficient to expect that any ignition would result in complete combustion of the hydrogen in containment and a significant pressure rise. At some initial containment pressures, this pressure rise may exceed the capacity of the containment. Therefore, this level of hydr' ogen in the containment represents a potential loss of containment integrity.
Containment heat removal systems are actuated at the high-high containment pressure setpoint of 3 psig. At least one train of Containment Spray (NS) and one Containment Air (VX) Return Fan (CARF) should be actuated at that time (the CARF with a 10 minute delay). A failure to actuate the design basis heat removal capability or assure proper containment mixing represents a degradation in the control of the D-4
Catawba Nuclear Site containment conditions. Therefore, this situation represents a potential loss of containment integrity.
Rapid unexplained loss of pressure (i.e., not attributable to containment spray or condensation effects) following an initial pressure increase indicates a loss of ;
containment integrity.
]
Containment pressure and sump levels should increase as a result of the mass and energy release into containment from a Loss of Coolant Accident (LOCA). Thus, sump level or containment pressure not increasing indicates an interfacing systems LOCA which is a containment bypass and a loss of containment integrity, or some other containment pressure boundary failure.
4.1.C.3 Containment Isolation Valve Status After Containment Isolation Actuation Failure to isolate those containment pathways which would allow containment atmosphere to be released from containment is a loss of the containment barrier. .
There is no " Potential Loss" EAL associated with this item.
4.1.C.4 Steam Generator (SG) Secondary Side Release With Primary To Secondary Leakage Secondary side releases to atmosphere include those from the condenser air ejector, SG Power Operated Relief Valves (PORVs), atmospheric dump valves, faulted steam lines, and main steam safety valves. Steam releases, in combination with primary to secondary leakage, constitute a bypass of the containment and, therefore, a loss of the containment barrier.
The appropriate classification can be determined in combination with the SG Tube Rupture EAL under the Reactor Coolant System (NCS) barrier.
There is no " Potential Loss" EAL associated with this item.
4.1.C.5 Significant Radioactive Inventory in Containment These values indicate significant fuel damage wellin excess of the EALs associated with both loss of Fuel Clad and loss of NCS Barriers. NUREG-1228, Source Estimations During incident Response to Severe Nuclear Power Plant Accidents, indicates that such conditions do not exist when the amount of clad damage is less D5
l Catawba Nuclear Site I
than 20%. This amount of activity in containment, if released, could have such severe consequences that it is prudent to treat this as a potential loss of containment.
l By treating the radioactive inventory in containment as a potential loss, a General l Emergency will be declared when the conditions of the fuel clad and NCS barriers are included in the evaluation. This will allow the appropriate protective actions to be recommended.
There is no " Loss" EAL associated with this item.
NOTE: If EMF-53A and EMF-53B are unavailable, readings can be calculated from procedure HP/0/B/1009/06, " Alternative Method for Determining Dose Rates within the Reactor Building."
4.1.C.6 Core Cooling Core Cooling - RED for greater than 15 minutes in this potential loss EAL represents imminent core damage that, if not terminated, could lead to reactor vessel failure and an increased potential for containment failure. The potential for containment challenge as a result of events at reactor vessel failure makes it pmdent to consider an unmitigated core damage condition as a potential loss of the containment barrier.
Severe accident analyses (e.g., NUREG-1150) have concluded that function restoration procedures can arrest core degradation within the reactor vessel in a significant fraction of the core damage scenarios, and that the likelihood of containment failure is very small in these events. Given this, it is appropriate to provide a reasonable period to allow function restoration procedures to arrest the core melt sequence. Whether or not the procedures will be effective should be apparent within 15 minutes. The Emergency Coordinator / EOF Director should make the declaration as soon as it is determined that the procedures have been, or will be, ineffective.
There is no " Loss" EAL associated with this item.
4.1.C.7 Emergency Coordinator / EOF Director Judgement This EAL addresses any other factors that are to be used by the Emergency Coordinator / EOF Director in determining whether the containment barrier is lost or potentially lost. In addition, the inability to monitor the barrier should also be ,
incorporated in this EAL as a factor in Emergency Coordinator / EOF Director judgement that the barrier may be considered lost or potentially lost.
D-6
)
i
Catawba Nuclear Site REACTOR COOLANT SYSTEM (NCS) BARRIER EALs: (N.1 or N. 2 or N. 3 or N.4 or N.5)
The NCS Barrier includes the NCS primary side and its connections up to and including the pressurizer safety and relief valves, and other connections up to and including the primary isolation valves.
4.1.N.1 Critical Safety Function Status NCS Integrity - RED indicates NCS pressure and temperature conditions which may challenge the Reactor Vessel integrity. Heat Sink - RED indicates the ultimate heat sink function is under extreme challenge. Either of these conditions indicate a potentialloss of the NCS Barrier. -
There is no " Loss" EAL associated with this item.
4.1.N.2 NCS Leak Rate Small leaks may result in the inability to maintain normal liquid inventory within the NCS by operation of the Chemical and Volume Control System, which is considered as one centrifugal charging pump discharging to the charging header with the letdown line isolated. Ifletdown cannot be isolated, and a second charging pump is required, this is still considered a potentialloss of the NCS barrier. The need for compensatory action to maintain normal liquid inventory is an indication of a degraded NCS barrier and is considered to be a potential loss of the barrier.
The loss of subcooling is the fundamental indication that the inventory loss from the primary system exceeds the capacity of the inventory control systems. If the loss of subcooling is indicated, the NCS barrier is considered lost.
4.1.N.3 SG Tube Rupture Small Steam Generator tube leaks may result in the inability to maintain riormal liquid inventory within the Reactor Coolant System (NCS) by operation of the Chemical and Volume Control System, which is considered as one centrifugal charging pump discharging to the charging header with the letdown line isolated. If letdown cannot be isolated, and a second charging pump is required, this is still considered a potentialloss of the NCS barrier. The need for compensatory action to maintain normal liquid inventory is an indication of a degraded NCS barrier and is considered to be a potential loss of the barrier.
D-7
Catawba Nuclear Site A tube rupture with an unisolable secondary line fault is generally indicated by a reduction in primary coolant inventory, increased secondary radiation levels, and an uncontrolled or complete depressurization of the ruptured SG. This set of conditions represents a loss of the NCS and containment fission product barriers. In conjunction with containment barrier loss #4, this condition will result in the declaration of a Site Area Emergency. Escalation to a General Emergency would be indicated by at least a potentialloss of the fuel clad barrier.
Secondary radiation increases should be observed via radiation monitoring of Condenser Air Ejector Discharge, SG Blowdown, Main Steam, and/or SG Sampling System. Determination of the " uncontrolled" depressurization of the ruptured SG
. should be based on indication that the pressure decrease in the ruptured steam generator is not a function of operator action. This should prevent declaration based on a depressurization that results from an EOP induced cooldown of the NCS that does not involve the prolonged release of contaminated secondary coolant from the affected SG to the environment. This EAL should encompass steam breaks, feed breaks, and stuck open safety or relief valves. These conditions represents a loss of the NCS and containment fission product barriers.
4.1.N.4 Containment Radiation Monitoring An unplanned valid Trip II alarm on EMPs 38,39, or 40 indicates the release of reactor coolant to the containment. This reading is not valid without a corresponding decrease in NCS inventory and increased makeup rate to the NCS. The Trip II setpoint is selected to ensure compliance with Selected Licensee Commitment 16.11-
- 6. The indicated loss of reactor coolant is identification of a loss of the NCS barrier.
This reading will be less than that specified for Fuel Clad Barrier EAL #3. Thus, this EAL would be indicative of a NCS leak only. If the radiation monitor reading increased to that specified by Fuel Clad Barrier EAL #3, fuel damage would also be indicated.
There is no " Potential Loss" EAL associated with this item.
4.1.N.5 Emergency CoordinatorEOF Director Judgement This EAL addresses any other factors that are to be used by the Emergency Coordinator / EOF Director in determining whether the NCS barrier is lost or potentially lost. In addition, the inability to monitor the barrier should also be incorporated in this EAL as a factor in Emergency Coordinator / EOF Director judgement that the barrier may be considered lost or potentially lost.
D-8
]
Catawba Nuclear Site FUEL CLAD BARRIER EALs: (F.l or F. 2 or F. 3 or F. 4)
The Fuel Clad Barrier is the zircalloy tubes that contain the fuel pellets.
4.1.F.1 Critical Safety Function Status Core Cooling - ORANGE indicates subcooling has been lost and that some clad damage may occur. Heat Sink - RED indicates the ultimate heat sink function is under extreme challenge. Either of these conditions indicate a potentialloss of the Fuel Clad Barrier.
Core Cooling - RED indicates significant reactor coolant superheating and core uncovery. Clad damage under these conditions is likely; therefore, this is indication ofloss of the Fuel Clad Barrier. .
l 4.1.F.2 Primary Coolant Activity Level i l
The value of 300 pCi/cc Il31 equivalent coolant activity is well above that expected l for iodine spikes and corresponds to about 2% to 5% fuel clad damage. This amount of clad damage indicates significant clad damage and thus the Fuel Clad Barrier is .
considered lost. !
I There is no equivalent " Potential Loss" EAL for this item. i i
)
4.1.F.3 Containment Radiation Monitoring j l
A reading of 117 R/hr on EMF-53A or B is a value which indicates the release of j reactor coolant, with elevated activity indicative of fuel damage, into the containment.
Reactor coolant concentrations of this magnitude are several times larger than the maximum concentrations (including iodine spiking) allowed within technical specifications and are therefore indicative of fuel damage (approximately 5% clad l failure depending on core inventory and NCS volume). This value is higher than that I specified for NCS barrier Loss EAL #4. Thus, this EAL indicates a loss of both the !
fuel clad barrier and a loss of NCS barrier.
There is no " Potential Loss" EAL associated with this item.
NOTE: If EMF-53A and EMF-53B are unavailable, readings can be calculated from I
procedure HP/0/B/1009/06," Alternative Method for determining Dose Rates within the Reactor Building."
D9
Catawba Nuclear Site I
4.1.F.4 Emergency Coordinator / EOF Director Judgement j l
This EAL addresses any other factors that are to be used by the Emergency l Coordinator / EOF Director in determining whether the Fuel Clad barrier is lost or potentially lost. In addition, the inability to monitor the barrier should also be incorporated in this EAL as a factor in Emergency Coordinator / EOF Director judgement that the barrier may be considered lost or potentially lost.
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, BASIS INFORMATION FOR TABLE 4 D-10 l
I Catawba Nuclear Site i 1
i ENCLOSURE 4.2 SYSTEM MALFUNCTION UNUSUAL EVENT 4.2.U.1 Inability to Reach Required Shutdown Within Technical Specification Limits.
OPERATING MODE APPLICABILITY: Mode 1 (Power Operation)
Mode 2 (Startup)
Mode 3 (Hot Standby)
Mode 4 (Hot Shutdown) ,
EMERGENCY ACTION LEVEL:
4.2.U.1-1 Plant is not brought to required operating mode within Technical Specifications LCO Action Statement Time.
BASIS:
Limiting Conditions of Operation (LCOs) require the plant to be brought to a required shutdown mode when the Technical Specification required configuration cannot be restored. Depending on the circumstances, this may or may not be an emergency or precursor to a more severe condition.
In any case, the initiation of plant shutdown required by the site Technical Specifications requires a one hour report under 10 CFR 50.72 (b) Non-emergency events. The plant is within its safety envelope when being shut down within the allowable action statement time in the Technical Specifications. An immediate Notification of an Unusual Event is required when the plant is not brought to the required operating mode within the allowable action statement time in the Technical Specifications. Declaration of an Unusual Event is based on the time at which the LCO-specified action statement time period elapses under the site Technical Specifications and is not related to how long a condition may have existed. Other required Technical Specification shutdowns that involve precursors to more serious events are addressed by other System Malfunction, Hazards, or Fission Product Barrier Degradation ICs.
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, SU2 D-11
l l
l 1
Catawba Nuclear Site SYSTENT MALFUNCTION 4 l
l UNUSUAL EVENT l 4.2.U.2 Unplanned Loss of Most or All Safety System Annunciation or Indication in the Control Room for Greater Than 15 Minutes.
OPERATING MODE APPLICABILITY: Mode 1 (Power Operation)
Mode 2 (Startup)
Mode 3 (Hot Standby)
Mode 4 (Hot Shutdown)
EMERGENCY ACTION LEVEL:
4.2.U.2-1 The following conditions exist: -
)
- a. Unplanned loss of most (>50%) annunciators associated with safety systems for greater than 15 minutes.
AND
- b. In the opinion of the Operations Shift ManagerEmergency CoordinatorEOF Director, the loss of the annunciators or indicators requires additional personnel (beyond normal shift compliment) to safely operate the unit.
BASIS:
This Initiating Condition (IC) and its associated EAL are intended to recognize the difficulty associated with monitoring changing plant conditions without the use of a major portion of the annunciation or indication equipment. " Unplanned" loss of annunciators or indicator excludes scheduled maintenance and testing activities. Quantification of "most" is arbitrary; however, this judgement is supported by the specific opinion of the Operations Shift ManagerEmergency CoordinatorEOF Director that additional operating personnel will be requeed to provide increased monitoring of system operation to safely operate the unit. Fifteen minutes was selected as a threshold to exclude transient or momentary power losses.
This Unusual Event will be escalated to an Alert if a transient is in progress during the loss of annunciation or indication.
Due to the limited number of safety systems in operation during cold shutdown, refueling, and defueled modes, no IC is indicated during these modes of operation.
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, SU3 D-12
1 Catawba Nuclear Site SYSTENI MALFUNCTION I
UNUSUAL EVENT 4.2.U.3 Fuel Clad Degradation.
OPERATING MODE APPLICABILITY: All i
- EMERGENCY ACTION LEVEL:
1 )
4.2.U.3-1 Dose Equivalent I-131 greater than the Technical Specification allowabb inmit.
. BASIS:
1 I
This IC is included as an Unusual Event because it is considered to be a potential degradation in i the level of safety of the plant and a potential precursor of more serious problems. The EAL addresses coolant samples exceeding coolant technical specifications for iodine spike. Escalation of this IC to the Alert level is via the Fission Product Barrier Degradation Monitoring ICs. i l
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, SU4 i
i M
D-13
Catawba Nuclear Site i
SYSTEM MALFUNCTION UNUSUAL EVENT
- 4.2.U.4 Reactor Coolant System (NCS) Leakage.
OPERATING MODE APPLICABILITY: Mode 1 (Power Operation)
Mode 2 (Startup)
Mode 3 (Hot Standby)
Mode 4 (Hot Shutdown)
EMERGENCY ACTION LEVELS:
4.2.U.41 Unidentified leakage 210 gpm l 4.2.U.4 2 Pressure boundary leakage 210 gpm 4.2.U.4-3 Identified leakage 2 25 gpm BASIS:
i l This IC is included as an Unusual Event because it may be a precursor of more serious conditions and, as a result, is considered to be a potential degradation of the level of safety of the plant. The 10 gpm value for the unidentified and pressure boundary leakage was selected as it is observable with normal control room i indications. Lesser values must generally be determined through time-consuming surveillance tests (e.g.,
mass balances). The EAL for identified leakage is set at a higher value due to the lesser significance of identified leakage in comparison to unidentified or pressure boundary leakage. In either case, escalation of this IC to the Alert level is via Fission Product Barrier Degradation ICs or IC, " Inability to Maintain Plant in Cold Shutdown."
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, SUS 1
a 4
D-14
I Catawba Nuclear Site SYSTEM MALFUNCTION UNUSUAL EVENT 4.2.U.5 Unplanned Loss of All Onsite or Offsite Communications.
OPERATING MODE APPLICABILITY: All EMERGENCY ACTION LEVELS:
4.2.U.51 Loss of all onsite communications capability (internal phone system, PA system, onsite radio system) affecting the ability to perform routine operations. l 4.2.U.5 2 Loss of all offsite communications capability (Selective Signaling, NRC FTS lines, offsite radio system, commercial phone system) affecting the ability to communicate with offsite authorities.
BASIS:
The purpose of this IC and its associated EALs is to recognize a loss of communications capability that either defeats the plant operations staff ability to perform routine tasks necessary for plant operations or the ability to communicate problems with offsite authorities. The loss of offsite communications ability is expected to be significantly more comprehensive than the condition addressed by 10 CFR 50.72.
This EAL is intended to be used only when extraordinary means are being utilized to make communications possible (relaying ofinformation from radio transmissions, individuals being sent to offsite locations, etc.).
REFERENCE:
NUMARC/NESP-007, REV. 2, 0182, SU6 D-15
Catawba Nuclear Site i SYSTEM MALFUNCTION ALERT
, 4.2.A.1 Unplanned Loss of Most or All Safety System Annunciation or Indication in 1
Control Room With Either (1) a Significant Transient in Progress, or (2)
Compensatory Non-Alarming Indicators Unavailable.
2 OPERATING MODE APPLICABILITY: Mode 1 (Power Operation)
Mode 2 (Startup)
S Mode 3 (Hot Standby)
Mode 4 (Hot Shutdown)
EMERGENCY ACTION LEVEL: l 1
4.2.A.1-1 The following conditions exist: I
- a. Unplanned loss of most (>50%) annunciators associated with safety systems for greater than 15 minutes.
AND
- b. In the opinion of the Operations Shift ManagerEmergency CoordinatorEOF l
. Director, the loss of the annunciators or indicators requires additional personnel (beyond normal shift compliment) to safely operate the unit.
AND
- c. Either of the following:
- A significant plant transient is in progress.
. Loss of the Operator Aid Computer (OAC).
BASIS:
n This IC and its associated EAL are intended to recognize the difficulty associated with monitoring changing plant conditions without the use of a major portion of the annunciation or indication equipment during a transient. Quantification of "Most" is arbitrary; however, this judgement is supported by the specific opinion of the Operations Shift ManagerEmergency CoordinatorEOF Director that additional operating personnel will be required to provide increased monitoring of system operation to safely operate the unit. Fifteen minutes was selected as a threshold to exclude transient or momentary power losses.
D-16
Catawba Nuclear Site Refer to Operations Procedure OP/l(2)/A/6700/03, " Operating with OAC Out of Service."
"Significant Transient" includes response to automatic or manually initiated functions such as reactor trips, runbacks involving greater than 25% thermal power change, ECCS injections, or thermal power oscillations of 10% or greater.
Significant indication is available from the OAC. Loss of the OAC in conjunction with the loss of other indications would further impair the ability to monitor plant parameters.
Due to the limited number of safety systems in operation during cold shutdown, refueling and defueled modes, no IC is indicated during these modes of operation.
This Alert will be escalated to a Site Area Emergency if the operating crew cannot monitor the transient in progress.
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, SA4 D-17
Catawba Nuclear Site SYSTEM MALFUNCTION SITE AREA EMERGENCY 4.2.S.1 Inability to Monitor a Significant Transient in Progress.
OPERATING MODE APPLICABILITY: Mode 1 (Power Operation)
Mode 2 (Startup)
Mode 3 (Hot Standby)
Mode 4 (Hot Shutdown)
EMERGENCY ACTION LEVEL:
4.2.S.1-1 The following conditions exist: .
- a. Unplanned loss of most (>50%) annunciators associated with safety systems for greater than 15 minutes.
AND
- b. A significant plant transient is in progress.
AND
- c. Loss of the OAC.
AND
- d. Inability to provide manual monitoring, independent of the OAC Critical Safety Function Status Tree program, of any one of the following Critical Safety Functions:
e subcriticality e core cooling
. heat sink e containment ,
BASIS:
This IC and its associated EAL are intended to recognize the inability of the control room staff to monitor the plant response to a transient. A Site Area Emergency is considered to exist if the control room staff cannot monitor safety functions needed for protection of the public.
D-18
~ . - - . . _ . ~ _ . -. - . . . . . . _ . - . . _ . .
l I
Catawba Nuclear Site "Significant Transient" includes response to automatic or manually initiated functions such as ;
trips, runbacks involving greater than 25% thermal power change, ECCS injections, or thermal power oscillations of 10% or greater.
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, SS6 l
l M
D-19
I Catawba Nuclear Site ENCLOSURE 4.3 ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENT UNUSUAL EVENT ,
4.3.U.1 Any Unplanned Release of Gaseous or Liquid Radioactivity to the Environment that Exceeds Two Times the SLC Limits for 60 Minutes or Longer.
OPERATING MODE APPLICABILITY: All l EMERGENCY ACTION LEVELS: l l
4.3.U.1-1 a. A valid TRIP 2 alarm on radiation monitor EMF-49L or EMF-57 i AND -
- b. Failure of the release path to cutomatically isolate
. i AND l
- c. The liquid radioactive release to the environment exceeds two times the SLC limit i for 60 minutes or longer.
4.3.U.1-2 A valid indication on radiation monitor EMF-36L of 2 1.08 E+04 cpm for 2 60 ;
minutes.
4.3.U.1-3 Gaseous effluent being released exceeds two times SLC 16.11-1 for2 60 minutes as determined by Radiation Protection (RP) procedure.
4.3.U.1-4 Liquid effluent being released exceeds two times SLC 16.11-6 for 2 60 minutes as determined by RP procedure.
NOTE: If monitor reading is sustained for the time period indicated in the EAL and the required assessments (procedure calculations) cannot be completed within this period, declaration must be made based on the valid radiation monitor reging. i BASIS:
The term " Unplanned", as used in this context, includes any release for which a liquid waste release (LWR) or gaseous waste release (GWR) package was not prepared, or a release that exceeds the conditions (e.g., minimum dilution flow, maximum discharge flow, alarm set points, etc.) on the applicable package.
D-20
Catawba Nuclear Site Valid means that a radiation monitor reading has been confirmed to be correct.
Unplanned releases in excess of two times the site Selected Licensee Commitments (SLC) that continue for 60 minutes or longer represent an uncontrolled situation and hence, a potential degradation in the level of safety. It is not intended that the release be averaged over 60 minutes.
The event should be declared as soon as it is determined that the release duration has or will likely exceed 60 minutes.
The gaseous release rate SLC are based on limiting gaseous release rates to the SITE BOUNDARY to 500 mr/ year total body.
The liquid release rate SLC are based on limiting liquid release rates to the UNRESTRICTED AREA to 10 times the Effluent Concentration (EC) valves given in 10CFR20.1001-20.2401, Appendix B, Table 2, Column 2.
- Monitor indications are based on the methodology of the site Offsite Dose Calculation Manual 3
(ODCM) using most restrictive dispersion coefficient 3.5IE-5 sec/m . Worst case annual aven.ge meteorology has been used. Radiation Protection will use HP/0/B/1009/23,
" Investigation of Unusual Radiological Occurrences" to quantify a release.
REFERENCE:
NUMARC/NESP-007, REV. 2, 0182, A Ul I
i D-21
I Catawba Nudear Site ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENT UNUSUAL EVENT l 4.3.U.2 Unexpected Increase in Plant Radiation or Airborne Concentration.
OPERATING MODE APPLICABILITY: All EMERGENCY ACTION LEVELS:
4.3.U.2-1 Indication of uncontrolled water level decrease of greater than 6 inches in the reactor refueling cavity with all irradiated fuel assemblies remaining covered by water.
4.3.U.2-2 Uncontrolled water level decrease of greater than 6 inches in the spent fuel pool and fuel transfer canal with all irradiated fuel assemblies remaining covered by water.
4.3.U.2-3 Unplanned valid area radiation monitor (EMF) reading increases by a factor of 1000 over normal levels.
GASIS:
Valid means that a radiation monitor reading has been confirmed to be correct.
All of the above events tend to have long lead times relative to potential for radiological l release outside the site boundary; thus, impact to public health and safety is very low.
In light of reactor cavity seal failure incidents, explicit coverage of these types of events via l EALs 1 and 2 is appropriate given their potential for increased doses to plant staff. A threshold value of 6 inches is used to allow time for mitigating actions to successfully terminate the inventory loss. Credit should not be taken for inventory additions to maintain level above the 6 inch threshold. Classification as an Unusual Event is warranted as a precursor to a more serious event.
EAL 3 addresses unplanned increases in in-plant radiation levels that represent a degradation in the control of radioactive material, and represent a potential degradation in the level of safety of the plant. This EAL escalates to an Alert if the increases impair safe operation.
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, AU2 D-22
Catawba Nuclear Site ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENT ;
1 ALERT 4.3.A.1 Any Unplanned Release of Gaseous or Liquid Radioactivity to the Environment that Exceeds 200 Times the SLC limits for 15 Minutes or Longer.
OPERATING MODE APPLICABILITY: All EMERGENCY ACTION LEVELS:
4.3.A.1-1 a. A val'id TRIP 2 alarm on radiation monitor EMF-49L or EMF-57 AND .
i b. Failure of the release path to automatically isolate AND 4
- c. The liquid radioactive release to the environment exceeds 200 times the SLC limit j for 15 minutes or longer.
4.3.A.1-2 A valid indication on radiation monitor EMF-36L of 21.08 E+06 cpm for 215 1 minutes.
4.3.A.1-3 Gaseous effluent being released exceeds 200 times the level of SLC 16.11-1 for 215 nunutes as determined by RP procedure.
)'
4.3.A.1-4 Liquid effluent being released exceeds 200 times the level of SLC 16.11-6 for 215 minutes as determined by RP procedure.
NOTE: If monitor reading is sustained for the time period indicated in the EAL and
- the required assessments (precedure calculations) cannot be completed within this period, declaration must be made based on the valid radiation monitor reading.
BASIS:
The term " Unplanned", as used in this context, includes any release for which a liquid waste release (LWR) or gaseous waste release (GWR) package was not prepared, or a release that exceeds the conditions (e.g., minimum dilution flow, maximum discharge flow, alarm set points, etc.) on the applicable package.
Valid means that a radiation monitor reading has been confirmed to be correct.
D-23
Catawba Nuclear Site This event escalates from the Unusual Event by escalating the magnitude of the release by a factor of 100.
l It is not intended that the release be averaged over 15 minutes. The event should be declared as i soon as it is determined that the release duration has or will likely exceed 15 minutes.
The gaseous release rate SLC are based on limiting gaseous release rates to the SITE BOUNDARY to 500 mr/ year total body.
The liquid release rate SLC are based on limiting liquid release rates to the UNRESTRICTED AREA to 10 times the Effluent Concentration (EC) valves given in 10CFR20.1001-20.2401, Appendix B, Table 2, Column 2.
Monitor indications are based on the methodology of the site Offsite Dose Calculation Manual (ODCM) using most restrictive dispersion coefficient 3.51E-5 sec/m 3. Worst case annual average meteorology has been used. Radiation Protection will use HP/0/B/1009/23,
" Investigation of Unusual Radiological Occurrences" to quantify a release.
REFERENCE:
NUMARC/NESP-007, REV. 2, 0182, AAl i
D-24
I Catawba Nuclear Site ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENT ALERT 4.3.A.2 Major Damage to Irradiated Fuel or Loss of Water Level that Has or Will l
Result in the Uncovering of Irradlated Fuel Outside the Reactor Vessel.
l l
OPERATING MODE APPLICABILITY: All EMERGENCY ACTION LEVELS:
4.3.A.2-1 An unplanned valid trip II alarm on any of the following radiation monitors:
- a. Spent Fuel Building Refueling Bridge IEMF-15 -
2 EMF-4
- b. Spent Fuel Pool Ventilation ,
IEMF-42 2 EMF-42
- c. Reactor Building Refueling Bridge IEMF-17 2 EMF-2
- d. Containment Noble Gas Monitors IEMF-39 2 EMF-39 4.3.A.2-2 Plant personnel report that water level drop in reactor refueling cavity, spent fuel pool, or fuel transfer canal has or will exceed makeup capacity such that irradiated fuel will become uncovered.
4.3.A.2-3 NC system wide range level < 95 % after initiation of NC system make-up AND n
Any irradiated fuel assembly not capable of being lowered into spent fuel pool or reactor vessel AND KF-122 cannot be closed.
D-25
l l
Catawba Nuclear Site l
BASIS:
This IC applies to spent fuel requiring water coverage. There is time available to take corrective actions, and there is little potential for substantial fuel damage. Thus, an Alert Classification for this event is appropriate. Escalation, if appropriate, would occur via Abnorraal Rad Level / Radiological Effluent or Emergency Coordinator / EOF Director Judgement.
l
REFERENCE:
NUMARC/NESP-007, REV. 2, 0182, AA2 l
l
.+
D-26
Catawba Nuclear Site ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENT ALERT 4.3.A.3 Release of Radioactive Material or Increases in Radiation Levels Within the Facility That Impedes Operation of Systems Required to Maintain Safe !
Operations or to Establish or Maintain Cold Shutdown.
3 I
, OPERATING MODE APPLICABILITY: All I 1
EMERGENCY ACTION LEVELS:
i 3
4.3.A.3-1 Valid radiation monitor reading indicating greater than 15 mR/hr in the control l room or PAP.
4.3.A.3-2 Valid radiation monitor reading of >5 R/hr in a plant vital area.
1 BASIS:
Valid means that a radiation monitor reading has been confirmed to be correct.
This initiating condition (IC) addresses increased radiation levels that impede necessary access to operating stations, or other areas containing equipment that must be operated manually, in order to i maintain safe operation or perform a safe shutdown. It is this impaired ability to operate the plant that
, results in the actual or potential substantial degradation of the level of safety of the plant.
This IC is not intended to apply to anticipated temporary increases due to planned events (e.g., incore j detector movement, radwaste container movement, depleted resin transfers, etc.)
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, AA3 4
D-27
Catawba Nuclear Site 1
ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENT ;
I SITE AREA EMERGENCY I l
4.3.S.1 Boundary Dose Resulting from an Actual or Imminent Release of l Radioactivity Exceeds 100 mrem TEDE or 500 mrem CDE Adult Thyroid for the Actual or Projected Duration of the Release.
OPERATING MODE APPLICABILITY: All l EMERGENCY ACTION LEVELS:
4.3.S.1-1 A valid indication on radiation monitor EMF-36L 21.08 E +07 cpm.
4.3.S.1-2 Dose assessment team calculations indicate dose consequences greater than 100 mrem TEDE or 500 mrem CDE Adult Thyroid at the site boundary.
4.3.S.1-3 Analysis of field survey results or field survey samples indicates dose consequences greater than 100 mrem TEDE or 500 mrem CDE Adult Thyroid at the site boundary.
NOTE 1: These EMF readings are calculated based on worst case average annual meteorology, a sixty minute release duration, and design unit vent flow rate.
Calculations by the dose assessment team use actual meteorology, duration, and unit vent flow rate. Therefore, these EMF readings should not be used if dose assessment team calculations are available.
NOTE 2: If dose assessment team calculations cannot be completed in 15 minutes, then valid monitor readings should be used for emergency classification.
BASIS:
Valid means that a radiation monitor reading has been confirmed to be correct.
The 100 mrem integrated dose in this initiating condition is based on 10 CFR 20 annual average population exposure. This value also provides a desirable gradient (one order of magnitude) between the Alert, Site Area Emergency, and General Emergency classes. These values are 10% of the EPA Protective Action Guide (PAG) values given in EPA-400-R 001.
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, ASl D-28
Catawba Nuclear Site ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENT GENERAL EMERGENCY 4.3.G.1 Boundary Dose Resulting from an Actual or Imminent Release of Radioactivity that Exceeds 1000 mrem TEDE or 5000 mrem CDE Adult Thyroid for the Actual or Projected Duration of the Release.
OPERATING MODE APPLICABILITY: All EMERGENCY ACTION LEVELS:
4.3.G.1-1 A valid indication on radiation monitor EMF-36H 21.72 E +04 cpm.
4.3.G.1-2 Dose assessment team calculations indicate dose consequences greater than 1000 l mrem TEDE or 5000 mrem CDE Adult Thyroid at the site boundary.
l 4.3.G.1-3 Analysis of field survey results or field survey samples indicates dose .
consequences greater than 1000 mrem TEDE or 5000 mrem CDE Adult Thyroid I at the site boundary.
NOTE 1: These EMF readings are calculated based on worst case average annual meteorology, a sixty minute release duration, and design unit vent flow rate.
Calculations by the dose assessment team use actual meteorology, duration, and unit vent flow rate. Therefore, these EMF readings should not be used if dose assessment team calculations are available.
NOTE 2: If dose assessment team calculations cannot be completed in 15 minutes, then valid monitor readings should be used for emergency classification.
BASIS:
Valid means that a radiation monitor reading has been confirmed to be correct.
The 1000 mrem TEDE and 5000 mrem CDE thyroid integrated doses are based on the EPA PAG values given in EPA-400-R-92-001, which indicates that public protective actions are indicated if doses exceed these values. This is consistent with the emergency class description of a general emergency.
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, AGl D-29
Catawba Nuclear Site ENCLOSURE 4.4 LOSS OF SHUTDOWN FUNCTIONS ALERT l i
4.4.A.1 Failure of Reactor Protection System Instrumentation to Complete or Initiate an i Automatic Reactor Trip Once a Reactor Protection System Setpoint Has Been l Exceeded and Manual Trip was Successful.
OPERATING MODE APPLICABILITY: Mode 1 (Power Operation)
Mode 2 (Startup)
Mode 3 (Hot Standby)
EMERGENCY ACTION LEVEL:
4.4.A.1-1 The following conditions exist: )
- a. Valid reactor trip signal received or required.
AND
- b. Manual reactor trip from the control room is successful and reactor power is less than 5% and decreasing.
BASIS:
This candition indicates failure of the automatic protection system to trip the reactor. This condition is more than a potential degradation of a safety system in that a front line automatic j protection system did not function in response to a plant transient and thus the plant safety has been compromised, and design limits of the fuel may have been exceeded. An Alert is indicated I because conditions exist that lead to potential loss of fuel clad or NCS. Reactor protection system setpoint being exceeded (rather than limiting safety system setpoint being exceeded) is specified here because failure of the automatic protection system is the issue. A manual trip is any set of actions by the reactor operator (s) at the reactor control console which causes control i rods to be RAPIDLY inserted into the core and brings the reactor suberitical. Operator action to drive rods does NOT constitute a reactor trip, i.e. does not meet the rapid insertion criterion.
n Failure of manual trip would escalate the event to a Site Area Emergency.
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, SA2 D-30
4 Catawba Nuclear Site LOSS OF SHUTDOWN FUNCTIONS ALERT 4.4.A.2 Inability to Maintain Plant in Cold Shutdown.
OPERATING MODE APPLICABILITY: Mode 5 (Cold Shutdown)
Mode 6 (Refueling) ,
1 EMERGENCY ACTION LEVEL,S: i 4.4.A.2-1 Total loss of Residual Heat Removal (ND) and/or j Nuclear Service Water (RN) and/or ,
Component Cooling (KC) l AND l Inability to maintain reactor coolant temperature below 200 F.
BASIS:
1 This EAL addresses loss of functions required for core cooling during cold shutdown and l refueling conditions. This IC and associated EALs are based on concerns raised by Generic Letter 88-17 " Loss of Decay Heat Removal." A number of phenomena such as pressurization, j vortexing, steam generator U-tube draining, NCS level differences when operating at a mid-loop condition, decay heat removal system design, and level instrumentation problems can lead to conditions where decay heat removal is lost and core unco'very can occur. NRC analyses show that sequences that can cause core uncovery in 15 to 20 minutes and severe core damage within an hour after decay heat removal is lost.
Escalation to the Site Area Emergency is by, " Loss of Water Level in the Reactor Vessel That Has or Will Uncover Fuel in the Reactor Vessel," or by Abnormal Rad Levels / Radiological Effluent ICs.
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, SA3 ,
D-31
Catawba Nuclear Site LOSS OF SHUTDOWN FUNCTIONS SITE AREA EMERGENCY 4.4.S.1 Failure of Reactor Protection System Instrumentation to Complete or Initiate an Automatic Reactor Trip Once a Reactor Protection System Setpoint Has Been Exceeded and Manual Trip WAS NOT Successful.
OPERATING MODE APPLICABILITY: Mode 1 (Power Operation) !
EMERGENCY ACTION LEVEL:
4.4.S.1-1 The following conditions exist:
- a. Valid reactor trip signal received or required. ,
AND
- b. Manual reactor trip from the control room was not successful in reducing l reactor power to less than 5% and decreasing.
BASIS:
Automatic and manual trip are not considered successful if action away from the reactor control console is required to trip the reactor. This EAL is equivalent to the Subcriticality CSF-RED.
Under these conditions, the reactor is producing more heat than the maximum decay heat load for i which the safety systems are designed. A Site Area Emergency is indicated because conditions l exist that lead to imminent loss or potential loss of both fuel clad and NCS. Although this IC may be viewed as redundant to the Fission Product Barrier Degradation IC,its inclusion is necessary to better assure timely recognition and emergency response. Escalation of this event to a General Emergency would be via Fission Product Barrier Degradation or Emergency Coordinator / EOF Director Judgement ICs.
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, SS2 D-32
Catawba Nuclear Site LOSS OF SHUTDOWN FUNCTIONS SITE AREA EMERGENCY 4.4.S.2 Complete Loss of Function Needed to Achieve or Maintain Hot Shutdown.
OPERATING MODE APPLICABILITY: Mode 1 (Power Operation)
Mode 2 (Startup)
Mode 3 (Hot Standby)
Mode 4 (Hot Shutdown)
EMERGENCY ACTION LEVELS:
. 4.4.S.2-1 Core Cooling CSF-RED 4.4.S.2-2 Heat Sink CSF-RED 4.4.S.2-3 Suberiticality CSF-RED BASIS:
This EAL addresses complete loss of functions, including ultimate heat sink and reactivity control, required for hot shutdown with the reactor at pressure and temperature. Under these ;
conditions, there is an actual major failure of a system intended for protection of the public. l Thus, declaration of a Site Area Emergency is warranted. Escalation to General Emergency would be via Abnormal Rad Levels / Radiological Effluent, Emergency Coordinator / EOF Director l Judgement, or Fission Product Barrier Degradation ICs.
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, SS4 D-33
l Catawba Nuclear Site LOSS OF SHUTDOWN FUNCTIONS SITE AREA EMERGENCY 4.4.S.3 Loss of Water Level in the Reactor Vessel That Has or Will Uncover Fuel in the '
Reactor Vessel.
OPERATING MODE APPLICABILITY: Mode 5 (Cold Shutdown)
Mode 6 (Refueling)
EMERGENCY ACTION LEVELS:
4.4.S.3-1 a. Failure of heat sink causes loss of cold shutdown conditions.
AND ,
- b. Lower range Reactor Vessel Level Indication System (RVLIS) decreasing after initiation of NC system makeup.
4.4.S.3-2 a. Failure of heat sink causes loss of cold shutdown conditions.
AND
- b. Reactor Coolant (NC) system narrow range level less than 11% and decreasing after initiation of NC system makeup.
4.4.S.3-3 a. Failure of heat sink causes loss of cold shutdown conditions.
AND
- b. Either train ultrasonic level indication less than 7.25% and decreasing after initiation of NC system makeup.
BASIS:
Under the conditions specified by this IC, severe core damage may be imminent due4o prolonged boiling following loss of decay heat removal.
Thus, declaration of a Site Area Emergency is warranted under the conditions specified by the IC. Escalation to a General Emergency is via radiological effluent IC.
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92. SS5 D-34
r j Catawba Nuclear Site LOSS OF SHUTDOWN FUNCTIONS GENERAL EMERGENCY l
l 4.4.G.1 Failure of the Reactor Protection System to Complete an Automatic Trip and Manual Trip was NOT Successful and There is Indication of an Extreme Challenge to the Ability to Cool the Core.
OPERATING MODE APPLICABILITY: Mode 1 (Power Operation)
EMERGENCY ACTION LEVEL:
4.4.G.1-1 The following conditions exist:
- a. Valid reactor trip signal received or required. -
AND 1
4
- b. Manual reactor trip from the control room was not successful in reducing reactor power to less than 5% and decreasing.
AND
- c. Either of the following conditions exist:
- Core Cooling CSF-RED e Heat Sink CSF-RED BASIS Automatic and manual trip are not considered successful if action away from the reactor control console is required to trip the reactor.
Under the conditions of this IC and its associated EALs, the efforts to bring the reactor subcritical have been unsuccessful and, as a result, the reactor is producing more heg than the maximum decay heat load for which the safety systems were designed.
l The extreme challenge to the ability to cool the core is intended to mean that the core exit temperatures are at or approaching 1200 F or that the reactor vessel water level is below the top of active fuel. This equates to a Core Cooling-RED condition.
Another consideration is the inability to initially remove heat during the early stages of this sequence. If emergency feedwater flow is insufficient to remove the amount of heat required by D-35 1
.. . . . . .- . . _ . . . - . - - . _ ~ . _ . _ . _ . . . . - . _ - _ -. . _. - . __
i.
l l Catawba Nuclear Site design from at least one steam generator, an extreme challenge should be considered to exist.
This equates to a Heat Sink-RED condition.
i In the event either of these challenges occurs during or following a time that the reactor has not -
i
!; been brought below the power associated with the safety system design, core damage may be imminent. For this reason, the General Emergency declaration is intended to be anticipatory of l the fission product barrier matrix declaration to permit maximum offsite intervention time.
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, SG2 D-36
Catawba Nuclear Site ENCLOSURE 4.5 LOSS OF POWER UNUSUAL EVENT 4.5.U.1 Loss of All Offsite Power to Essential Busses for Greater Than 15 Minutes.
OPERATING MODE APPLICABILITY: All EMERGENCY ACTION LEVEL:
4.5.U.1-1 The following conditions exist:
- a. Loss of offsite power to essential buses ETA and ETB for greater than 15 minutes. .
AND
- b. Each emergency diesel generator is supplying power to its respective essential bus.
BASIS:
Prolonged loss of AC power reduces required redundancy and potentially degrades the level of safety of the plant by rendering the plant more vulnerable to a complete Loss of AC Power (Station Blackout). Fifteen minutes was selected as a threshold to exclude transient or momentary power losses.
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, SU1 '
D-37
l l
l Catawba Nuclear Site !
1 k
LOSS OF POWER '
4 UNUSUAL EVENT l J
l 4.5.U.2 Unplanned Loss of Required DC Power During Cold Shutdown or Refueling l
4 Mode for Greater than 15 Minutes.
OPERATING MODE APPLICABILITY: Mode 5 (Cold Shutdown) i Mode 6 (Refueling)
! EMERGENCY ACTION LEVEL:
l l 4.5.U.2-1 The following conditions exist:
- a. Unplanned loss of both unit related busses: EB A and EBD both < 112 VDC, and EBB and EBC both < 109 VDC.
! AND
- b. Failure to restore power to at least one required DC bus within 15 minutes from the time ofloss.
i BASIS:
The purpose of this IC and its associated EALs is to recognize a loss of DC power compromising the ability to monitor and control the removal of decay heat during Celd Shutdown or Refueling operations. This EAL is intended to be anticipatory in as much as the operating crew may not have necessary indication and control of equipment needed to respond to the loss.
" Unplanned" is included in this IC and EAL to preclude the declaration of an emergency as a result of planned maintenance activities.
If this loss results in the inability to maintain cold shutdown, the escalation to an Alert is via
" Inability to Maintain Plant in Cold Shutdown."
~
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, SU7 l
D-38
l Catawba Nuclear Site LOSS OF POWER ALERT l
4.5.A.1 Loss of All Offsite Power and Loss of All Onsite AC Power to Essential Busses l During Cold Shutdown Or Refueling Mode.
l OPERATING MODE APPLICABILITY: Mode 5 (Cold Shutdown)
Mode 6 (Refueling) l No Mode (Defueled)
EMERGENCY ACTION LEVEL:
4.5.A.1-1 Loss of all offsite and onsite AC power as indicated by:
- a. Loss of power on essential buses ETA and ETB.
AND
- b. Failure to restore power to at least one essential bus within 15 minutes.
BASIS:
Loss of all AC power compromises all plant safety systems requiring electric power including Residual Heat Removal (RHR), Emergency Core Cooling Systems (ECCS), Containment Heat i Removal, Spent Fuel Heat Removal and the Ultimate Heat Sink. When in cold shutdown, l refueling, or defueled mode the event can be classified as an Alert, because of the significantly ;
reduced decay heat, lower temperature and pressure, increasing the time to restore one of the essential busses, relative to that specified for the Site Area Emergency EAL. Escalating to Site Area Emergency, if appropriate, is by Abnormal Rad Levels / Radiological Effluent, or Emergency !
Coordinator / EOF Director Judgement ICs. Fifteen minutes was selected as a threshold to j exclude transient or momentary power losses.
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, SAI \
D-39 ;
1 i
Catawba Nuclear Site LOSS OF POWER ALERT 4.5.A.2 AC power to essential busses reduced to a single power source for greater than 15 minutes such that an additional single failure could result in station blackout.
OPERATING MODE APPLICABILITY: Mode 1 (Power Operation) 1 Mode 2 (Startup) )
Mode 3 (Hot Standby)
Mode 4 (Hot Shutdown)
EMERGENCY ACTION LEVEL:
4.5.A.2-1 The following condition exists: .
AC power capability has been degraded to one essential bus powered from a single ;
power source for > 15 min. due to the loss of all but one of: i SATA ;
SATB ATC ATD D/G A D/G B l BASIS: !
This IC and the associated EAL is intended to provide an escalation from IC, " Loss of All Offsite Power To Essential Busses for Greater Than 15 Minutes." The condition indicated by this IC is the degradation of the offsite and onsite power systems such that an additional single failure could result in a station blackout. This condition could occur due to a loss of offsite power with a concurrent failure of one emergency generator to supply power to its essential busses. Another related condition could be the loss of all offsite power and loss of onsite emergency diesels with only one train of essential busses being back fed from the unit main generator, or the loss of onsite emergency diesels with only one train of essential busses being back fed fronfbffsite power. The subsequent loss of this single power source would escalate the event to a Site Area Emergency in accordance with IC, " Loss of All Offsite and Loss of All Onsite AC Power to Essential Busses."
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, SA5 D-40
1 Catawba Nuclear Site LOSS OF POWER SITE AREA EMERGENCY 4.5.S.1 Loss of All Offsite Power and Loss of All Onsite AC Power to Essential Busses.
OPERATING MODE APPLICABILITY: Mode 1 (Power Operation)
Mode 2 (Startup)
Mode 3 (Hot Standhy)
Mode 4 (Hot Shutdown)
EMERGENCY ACTION LEVEL:
4.5.S.1-1 Loss of all offsite and onsite AC power as indicated by:
- a. Loss of power on essential buses ETA and ETB.
AND l
- b. Failure to restore power to at least one essential bus within 15 minutes.
BASIS:
1 Loss of all AC power compromises all plant safety systems requiring electric power including i RHR, ECCS, Containment Heat Removal and the Ultimate Heat Sink. Prolonged loss of all AC l power will cause core uncovering and loss of containment integrity; thus, this event can escalate to a General Emergency.
Escalation to General Emergency is via Fission Product Barrier Degradation or IC, " Prolonged Loss of All Offsite Power and Prolonged Loss of All Onsite AC Power."
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, SS1 D-41
Catawba Nuclear Site i
LOSS OF POWER l l SITE AREA EMERGENCY l 1 4.5.S.2 Loss of All Vital DC Power.
OPERATING MODE APPLICABILITY: Mode 1 (Power Operation)
Mode 2 (Startup)
Mode 3 (Hot Standby)
Mode 4 (Hot Shutdown)
EMERGENCY ACTION LEVEL:
l 4.5.S.2-1 The following conditions exist:
I a. Unplanned loss of both unit related busses: EBA and EBD both < 112'VDC, and EBB and EBC both <109 VDC.
j AND i
3 b. Failure to restore power to at ledst one required DC bus within 15 minutes from the time ofloss.
BASIS:
Loss of all DC power compromises ability to monitor and control plant safety functions.
Prolonged loss of all DC power will cause core uncovering and loss of containment integrity when there is significant decay beat and sensible heat in the reactor system. Escalation to a
- General Emergency would occur by Abnormal Rad Levels / Radiological Effluent, Fission Product Barrier Degradation, or Emergency Coordinator / EOF Director Judgement ICs. Fifteen minutes was selected as a threshold to exclude transient or momentary power losses.
I
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, SS3 N
D-42
Catawba Nuclear Site LOSS OF POWER GENERAL EMERGFNCY 4.5.G.1 Prolonged Loss of All(Offsite and Onsite) AC Power.
OPERATING MODE APPLICABILITY: Mode 1 (Power Operation)
Mode 2 (Startup)
Mode 3 (Hot Standby)
Mode 4 (Hot Shutdown)
EMERGENCY ACTION LEVEL:
4.5.G.1-1 Prolonged loss of all offsite and onsite AC power as indicated by:
- a. Loss of power on essential buses ETA and ETB for greater than 15 minutes.
AND
- b. Standby Shutdown Facility (SSF) fails to maintain hot standby AND
- c. At least one of the following conditions exist:
- Restoration of at least one essential bus within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is NOTlikely.
- Indication of continuing degradation of core cooling based on Fission Product Barrier monitoring.
BASIS:
Loss of all AC power compromises all plant safety systems requiring electric power including RHR, ECCS, Containment Heat Removal and the Ultimate Heat Sink. Prolonged loss of all those functions necessary to maintain hot shutdown will lead to loss of fuel clad, NCS, and containment.
- The SSF is capable of providing the necessary functions to maintain a hot shutdown condition for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. No fission product barrier degradation would be expected if the SSF is functioning as intended.
D-43
l l
Catawba Nuclear Site i
Analysis in support of the station blackout coping study indicates that the plant can cope with a station blackout for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> without core damage.
The likelihood of restoring at least one essential bus should be based on a realistic appraisal of the situation since a delay in an upgrade decision based on only a chance of mitigating the event could result in a loss of valuable time in preparing and implementing public protective actions.
In addition, under these conditions, fission product barrier monitoring capability may be degraded. Although it may be difficult to predict when power can be restored, it is necessary to give the Emergency Coordinator / EOF Director a reasonable idea of how quickly (s)he may need to declare a General Emergency based on two major considerations:
I
- 1. Are there any present indications that core cooling is already degraded to the point that Loss or Potential Loss of Fission Product Barriers is IMMINENT? ;
l
- 2. If there are no present indications of such core cooling degradation, how likely is it that power can be restored in time to assure that a loss of two barriers with a potential loss of the third barrier can be prevented? ;
Thus, indication of continuing core cooling degradation must be based on Fission Product Barrier monitoring with particular emphasis on Emergency Coordinator / EOF Directorjudgement as it relates to IMMINENT Loss or Potential Loss of fission product barriers and degraded ability to l monitor fission product barriers. i I
l
REFERENCE:
NUMARC/NESP-C07, REV. 2, 0182, SG1 :
s I
D-44
Catawba Nuclear Site ENCLOSURE 4.6 FIRF1 EXPLOSION AND SECURITY EVENTS UNUSUAL EVENT 4.6.U.1 Fire or Explosion Within Protected Area Boundary Not Extinguished Within 15 Minutes of Detection.
1 OPERATING MODE APPLICABILITY: All l
i EMERGENCY ACTION LEVEL: '
4.6.U.1 1 Fire in any of the following areas not extinguished within 15 minutes of control room notification or verification of a control room fire alarm.
. Reactor Building
. Auxiliary Building
. Diesel Generator Rooms
. Control Room
. RN Pumphouse
. Standby Shutdown Facility (SSF)
Central Alarm Station (CAS)
. Doghouses
. Refueling Water Storage Tank (FWST)
. Turbine Building
. Service Building
. Interim Radwaste Building 4.6.U.1-2 Report by plant personnel of an unanticipated explosion within protected area l boundary resulting in visible damage to permanent structure or equipment.
BASIS:
EAL 1: The purpose of this EAL is to address the magnitude and extent of fires that may be potentially significant precursors to damage to safety systems. Fire is combustion characterized by heat and light. Sources of smoke such as slipping drive belts or overheated electrical equipment do not constitute fires. Observation of flames is preferred but is NOT required iflarge quantities of smoke and heat are observed. This excludes such items as fires within administration buildings outside the protected area. Waste-basket fires, and other small fires of no safety consequence should easily be extinguished within 15 minutes of detection. This IC applies to buildings and areas contiguous to plant vital areas or other significant buildings or areas. Verification of the alarm in this context means those actions taken in the control room to determine that the control room alarm is not spurious.
l D-45
l Catawba Nuclear Site I
\
EAL 2: Only those explosions of sufficient force to damage permanent structures or equipment within the protected area should be considered. As used here, an explosion is a rapid, violent, unconfined combustion, or a catastrophic failure of pressurized equipment, that potentially i imparts significant energy to near-by structures and materials. No attempt is made in this EAL to assess the actual magnitude of the damage. The occurrence of the explosion with reports of evidence of damage (e.g., deformation, scorching) is sufficient for declaration. The Emergency Coordinator / EOF Director also needs to consider any security aspects of the explosion, if applicable.
Escalation to a higher emergency class is by, " Fire Affecting the Operability of Plant Safety Systems Required to Establish or Maintain Safe Shutdown".
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, HU2
)
i l
D-46
Catawba Nuclear Site l
i FIRE / EXPLOSION AND SECURITY EVENTS
]
UNUSUAL EVENT 4.6.U.2 Confirmed Security Event Which Indicates a Potential Degradation in the Level of Safety of the Plant.
OPERATING MODE APPLICABILITY: All EMERGENCY ACTION LEVELS:
4.6.U.2-1 Security confirmed bomb device discovered within plant Protected Area and outside Vital Areas.
4.6.U.2-2 Hostage situation / extortion -
l 4.6.U.2-3 A violent civil disturbance within the owner controlled area.
BASIS:
The above situations represent a potential degradation in the level of safety of the plant. i A civil disturbance is to be considered violent when force has been used in an attempt to injure site personnel or damage plant property.
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, HU4 n
D-47
l l
l Catawba Nuclear Site FIRF/ EXPLOSION AND SECURITY EVENTS ALERT 4.6.A.1 Fire or Explosion Affecting the Operability of Plant Safety Systems Required to Establish or Maintain Safe Shutdown.
OPERATING MODE APPLICABILITY: Mode 1 (Power Operation)
Mode 2 (Startup)
Mode 3 (Hot Standby)
Mode 4 (Hot Shutdown)
EMERGENCY ACTION LEVEL:
4.6.A.1-1 The following conditions exist:
- a. Fire or explosion in any of the following areas:
. Reactor Building
. Auxiliary Building
. Diesel Generator Rooms
. Control Room
. RN Pumphouse i
. SSF
. CAS
. Doghouses
. FWST AND 1
- b. One of the following:
- Affected safety system parameter indications show degraded performance
- Plant personnel report visible damage to permanent structures or equipment within the specified area.
- Note: Only one train of a system needs to be affected or damaged in order to satisfy this condition.
D-48 a
Catawba Nuclear Site BASIS:
With regard to explosions, only those explosions of sufficient force to damage permanent structures or equipment required for safe operation within the identified plant area should be considered. As used here, an explosion is a rapid, violent, unconfined combustion, or a catastrophic failure of pressurized equipment, that potentially imparts significant energy to near-by structures and materials. Fire is combustion characterized by heat and light. Sources of ;
smoke such as slipping drive belts or overheated electrical equipment do not constitute fires. !
Observation of flames is preferred but is NOT required iflarge quantities of smoke and heat are l observed. The inclusion of a "repon of visible damage" should not be interpreted as mandating a
]
lengthy damage assessment prior to classification.
The key to classifying fires / explosions as an Alert is the damage as a result of the incident. The fact that safety-related equipment required for safe shutdown of the unit has been affected or damaged as a result of the fire / explosion is the driving force for declaring the Alert. It is
- Important to note that this EAL addresses a fire / explosion and not just the degradation of a safety system. The reference to damage of the systems is used to identify the magnitude of the fire / explosion and to discriminate against minor fires / explosions.
Escalation to a higher emergency class, if appropriate, will be based on System Malfunction, Fission Product Barrier Degradation, Abnormal Rad Levels / Radiological Effluent, or Emergency Coordinator / EOF Director Judgement ICs.
1
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, HA2 n l D-49
Catawba Nuclear Site FIRF1 EXPLOSION AND SECURITY EVENTS ALERT 4.6.A.2 Fire or Explosion Affecting the Operability of Plant Safety Systems Required to l Establish or Maintain Safe Shutdown.
l OPERATING MODE APPLICABILITY: Mode 5 (Cold Shutdown)
Mode 6 (Refueling) !
I EMERGENCY ACTION LEVEL:
4.6.A.2-1 The following conditions exist:
- a. Fire or explosion in any of the following areas: -
. Reactor Building
. Auxiliary Building
. Diesel Generator Rooms ,
. Control Room
. RN Pumphouse
. SSF
. CAS
. FWST AND {
- b. One of the following:
- Affected safety system parameter indications show degraded performance e Plant personnel report visible damage to permanent structures or equipment within the specified area.
Note: Only one train of a system needs to be affected or damaged in order to satisfy this condition. ,
BASIS:
With regard to explosions, only those explosions of sufficient force to damage permanent stnictures or equipment required for safe operation within the identified plant area should be considered. As used here, an explosion is a rapid, violent, unconfined combustion, or a catastrophic failure of pressurized equipment, that potentially imparts significant energy to near-by structures and materials. Fire is combustion characterized by heat and light. Sources of D-50
Catawba Nuclear Site l l
smoke such as slipping drive belts or overheated electrical equipment do not constitute fires.
Observation of flames is preferred but is NOT required if large quantities of smoke and heat are observed. The inclusion of a " report of visible damage" should not be interpreted as mandating a lengthy damage assessment prior to classification.
The key to classifying fires / explosions as an Alert is the damage as a result of the incident. The fact that safety-related equipment required for safe shutdown of the unit has been affected or damaged as a result of the fire / explosion is the driving force for declaring the Alert. It is important to note that this EAL addresses a fire / explosion and not just the degradation of a safety system. The reference to damage of the systems is used to identify the magnitude of the fire / explosion and to discriminate against minor fires / explosions.
Escalation to a higher emergency class, if appropriate, will be based on System Malfunction, Fission Product Barrier Degradation, Abnormal Rad Levels / Radiological Effluent, or Emergency Coordinator / EOF Director Judgement ICs. -
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, HA2 D-51
Catawba Nuclear Site FIRE / EXPLOSION AND SECURITY EVENTS ALERT 4.6.A.3 Security Event in a Plant Protected Area.
OPERATING MODE APPLICABILITY: All EMERGENCY ACTION LEVEL:
4.6.A.3-1 Intrusion into plant protected area by a hostile force.
BASIS:
This class of security events represents an escalated threat to plant safety above that contained in the Unusual Event. A civil disturbance which penetrates the protected area boundary can be considered a hostile force. Intrusion into a vital area by a hostile force will escalate this event to l J
a Site Area Emergency. )
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REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, HA4 \
l D-52
Catawba Nuclear Site FIRF1 EXPLOSION AND SECURITY EVENTS
] SITE AREA EMERGENCY 4.6.S.1 Security Event in a Plant Vital Area.
OPERATING MODE APPLICABILITY: All EMERGENCY ACTION LEVELS:
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i 4.6.S.1-1 Intrusion into any of the following plant areas by a hostile force:
. Reactor Building
. Auxiliary Building
. Diesel Generator Rooms
. Control Room
. RN Pumphouse
. SSF I . Doghouses CAS l
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4.6.S.1-2 Security confirmed bomb discovered / exploded in a vital area.
4.6.S.1-3 Security confirmed sabotage in a plant vital area.
BASIS:
i This class of security events represents an escalated threat to plant safety above that contained in i the Alert IC in that a hostile force has progressed from the Protected Area to the Vital Area.
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, HS1 i
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D-53 4
Catawba Nuclear Site FIRF1 EXPLOSION AND SECURITY EVENTS GENERAL EMERGENCY 4.6.G.1 Security Event Resulting in Loss Of Ability to Reach and Maintain Cold Shutdown.
OPERATING MODE APPLICABILITY: All EMERGENCY ACTION LEVELS: l 4.6.G.1-1 Loss of physical control of the control room due to security event.
4.6.G.1-2 Loss of physical control of the SSF and Auxiliary Shutdown Panel (ASP) due to security event. .
BASIS:
This IC encompasses conditions under which a hostile force has taken physical control of vital area required to reach and maintain safe shutdown.
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, HG1 I
D-54
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ENCLOSURE 4.7 I NATURAL DISASTERS, HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY UNUSUAL EVENT 4.7.U.1 Natural and Destructive Phenomena Affecting the Protected Area. l OPERATING MODE APPLICABILITY: All
- EMERGENCY ACTION LEVELS
4.7.U.1-1 Tremor felt and valid alarm on the " strong motion accelerograph".
4.7.U.1-2 Tremor felt and valid alarm on the " Peak shock annunciator". -
3 4.7.U.1-3 Report by plant personnel of tornado striking within protected area boundary.
4.7.U.1-4 Vehicle crash into plant structures or systems within protected area boundary.
j 4.7.U.1-5 Report of turbine failure resulting in casing penetration or damage to turbine or i
generator seals.
BASIS:
1 The protected area boundary is typically that part within the security isolation zone and is defined in the site security plan.
- EALs 1&2
- Damage may be caused to some portions of the site, but should not affect ability of safety functions to operate. Method of detection can be based on instmmentation, validated by a reliable source, or operator assessment. As defined in the EPRI-sponsored " Guidelines for Nuclear Plant Response to an Earthquake", dated October 1989, a " felt earthquake" is:
An earthquake of sufficient intensity such that: (a) the vibratory ground motion is felt at
- the nuclear plant site and recognized as an earthquake based on a consensus of control
- room operators, and (b) valid alarm on seismic instrumentation occurs. ,
EAL 3: A tornado striking (touching down) within the protected boundary may have potentially damaged plant structures containing functions or systems required for safe shutdown of the plant.
If such damage is confirmed visually or by other in-plant indications, the event may be escalated to Alert.
D-55
Catawba Nuclear Site EAL 4: Addresses such items as a car, truck, plane, helicopter, or train crash that may potentially damage plant structures containing functions and systems required for safe shutdown of the plant.
If the crash is confirmed to affect a plant vital area, the event may be escalated to Alert.
EAL 5: Addresses main turbine rotating component failures of sufficient magnitude to cause observable damage to the turbine casing or to the seals of the turbine generator. Of major concern is the potential for leakage of combustible fluids (lubricating oils) and gases (hydrogen cooling) to the plant environs. Actual fires and flammable gas build up are appropriately classified via other EALs. This EAL is consistent with the definition of an Unusual Event while maintaining the anticipatory nature desired and recognizing the risk to non-safety related equipment. Escalation of the emergency classification is based on potential damage done by the missiles generated by the failure or by the radiological releases in conjunction with a steam generator tube rupture. These latter events would be classified by the Radiological ICs or Fission Product Barrier ICs.
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, HU1 NOTE: NUMARC EAL #5 moved to Fire / Security Recognition Category i
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'I D-56 4
-- a sn . .- , ., . - . . , - - - - -. , . -n -. , - ,e- ,.-,
I Catawba Nuclear Site NATURAL DISASTERS. HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY j l
UNUSUAL EVENT l 4.7.U.2 Release of Toxic or Flammable Gases Deemed Detrimental to Safe Operation of the Plant. :
l OPERATING MODE APPLICABILITY: All EMERGENCY ACTION LEVELS:
l 4.7.U.2-1 Report or detection of toxic or flammable gases that could enter within the site area boundary in amounts that can affect safe operation of the plant.
l 4.7.U.2-2 Report by Local, County or State Officials for potential evacuation of site personnel )
based on offsite event. l I
BASIS:
This IC is based on releases in concentrations within the site boundary that will affect the health of plant personnel or the safe operation of the plant with the plant being within the evacuation l area of an offsite event (i.e., tanker truck accident releasing toxic gases, etc.).
Gases within the owner controlled area that are below life threatening or flammable !
concentrations do not meet this EAL.
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92. HU3 n
D-57
Catawba Nuclear Site NATURAL DISASTERS. HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY UNUSUAL EVENT 4.7.U.3 Other Conditions Existing Which in the Judgement of the Emergency Coordinator / EOF Director Warrant Declaration of an Unusual Event.
OPERATING MODE APPLICABILITY: All EMERGENCY ACTION LEVEL:
4.7.U.3-1 Other conditions exist which in the judgement of the Emergency Coordinator / EOF Director indicate a potential degradation of the level of safety of the plant.
BASIS:
This EAL is intended to address unanticipated conditions not addressed explicitly elsewhere but that warrant declaration of an emergency because conditions exist which are believed by the Emergency Coordinator / EOF Director to fall under the Unusual Event emergency class.
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, HUS l
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D-58
l Catawba Nuclear Site NATURAL DISASTERS. HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY l
l ALERT i l
l 4.7.A.1 Natural and Destructive Phenomena Affecting the Plant Vital Area.
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OPERATING MODE APPLICABILITY: All I
EMERGENCY ACTION LEVELS.
4.7.A.I-1 Valid seismic accelerations greater than the operating basis earthquake (OBE):
0.08 g horizontal ;
. 1 OR 0.053 g vertical.
4.7.A.1-2 Tornado or high winds:
Tornado striking plant stmetures within the vital area i
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sustained winds 2 74 mph for > 15 minutes.
4.7.A.1-3 Turbine failure generated missiles, vehicle crashes or other catastrophic events causing visible stmetural damage on any of the following plant structures:
. Reactor Building i . Auxiliary Building l
. Refueling Water Storage Tank (FWST) !
. Diesel Generator Rooms
. Control Room
. RN Pumphouse ,
. Standby Shutdown Facility (SSF)
. Doghouses i .
Central Alarm Station (CAS) i i
D-59 ;
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Catawba Nuclear Site BASIS:
EAL 1: Based on the FSAR design basis. Seismic events of this magnitude (> OBE) can cause damage to safety functions.
EAL 2: Based on the available instrumentation ( 90 mph maximum range) and the FSAR design basis. which is 95 mph Wind loads of this magnitude (74 mph hurricane force winds) are approaching speeds that could cause damage to safety functions.
EAL 3: This EAL is intended to address the threat to safety related structures or equipment from uncontrollable and possibly catastrophic events. This list of areas includes areas containing safety-related equipment, their controls, and their power supplies. This EAL is, therefore, consistent with the definition of an ALERT in that if events have damaged areas containing safety-related equipment the potential exists for substantial degradation of the level of safety of the plant.
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, HA1 .
D-60 '
Catawba Nuclear Site NATURAL DISASTERS. HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY ALERT 4.7.A.2 Release of Toxic or Flammable Gases Within a Facility Structure Which Jeopardizes Operation of Systems Required to Maintain Safe Operations or to Establish or Maintain Cold Shutdown.
OPERATING MODE APPLICABILITY: All EMERGENCY ACTION LEVELS:
3.7.A.2-1 Repon or detection of toxic gases within a Facility Structure in concentrations that will be life threatening to plant personnel. '
4.7.A.2-2 Report or detection of flammable gases within a Facility Structure in concentrations that will affect the safe operation of the plant.
Structures for above EALs:
. Reactor Building
. Auxiliary Building
. Diesel Generator Rooms
.. RN Pumphouse
. Control Room l
. SSF
. Doghouses
. CAS BASIS:
This IC is based on gases that have entered a plant structure affecting the safe operation of the plant. Safe operations are affected when the area can not be accessed by plant personnel to l
ensure continued operability or availability of safety systems / components. This IC applies to buildings and areas contiguous to plant Vital Areas or other significant buildings or geas. The ,
intent of this IC is not to include buildings (i.e., warehouses) or other areas that are not contiguous or immediately adjacent to plant Vital Areas. It is appropriate that increased monitoring be done to ascertain whether consequential damage has occurred. Escalation to a higher emergency class, if appropriate, will be based on System Malfunction, Fission Product Barrier Degradation, Abnormal Rad Levels / Radioactive Effluent, or Emergency Coordinator / EOF Director Judgement ICs.
REFERENCE:
NUMARC/NESP-007. REV. 2, 01/92, HA3 D-61 D
I Catawba Nuclear Site NATURAL DISASTERS. HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY ALERT 4.7.A.3 Control Room Evacuation Has Been Initiated. ;
OPERATING MODE APPLICABILITY: All l EMERGENCY ACTION LEVEL:
4.7.A.3-1 Evacuation of the ccntrol room and control is, or is in the process of being, established from the Auxiliary Shutdown Panel (ASP) or the SSF.
BASIS:
With the control room evacuated, additional support, monitoring and direction through the ,
Technical Support Center and/or Emergency Operations Facility is necessary. Inability to i establish plant control from outside the control room, as evidenced by the inability to maintain NCS or SG inventories, will escalate this event to a Site Area Emergency.
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REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, HA5 D-62
h Catawba Nuclear Site l
NATURAL DISASTERS. HAZARDS AND OTHER CONDITIONS
, AFFECTING PLANT SAFETY ALERT 4.7.A.4 Other Conditions Existing Which in the Judgement of the Emergency Coordinator / EOF Director Warrant Declaration of an Alert.
OPERATING MODE APPLICABILITY: All EMERGENCY ACTION LEVEL:
4.7.A.4-1 Other conditions exist which in the Judgement of the Emergency Coordinator / EOF Director indicate that plant safety systems may be degraded and that increased monitoring of plant functions is warranted.
BASIS:
This EAL is intended to address unanticipated conditions not addressed explicitly elsewhere but that warrant declaration of an emergency because conditions exist which are believed by the Emergency Coordinator / EOF Director to fall under the Alert emergency class.
REFERENCE:
NUMARC/NESP-007, REV. 2, OH92, HA6 D-63
l Catawba Nuclear Site NATURAL DISASTERS. HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY SITE AREA EMERGENCY I 1
4.7.S.1 Control Room Evacuation Has Been Initiated and Plant Control Cannot Be i Established. I l
i OPERATING MODE APPLICABILITY: All EMERGENCY ACTION LEVEL:
4.7.S.1-1 The following conditions exist:
- a. Control room evacuation has been initiated. -
1 AND
- b. Control of the plant cannot be established from the ASP or the SSF within 15 minutes.
BASIS:
The timely transfer of control to alternate control areas has not been accomplished. This failure to transfer control would be evidenced by deteriorating reactor coolant system or steam generator parameters. For purposes of classification, the 15 minutes begins at the time that the determination to staff the alternate location is made. For most conditions, Reactor Coolant Pump seal LOCAs or steam generator dryout would be indications of failure to accomplish the transfer in the necessary time.
Escalation of this event,if appropriate, would be by Fission Product Barrier Degradation, Abnormal Rad Levels / Radiological Effluent, or Emergency Coordinator / EOF Director Judgement ICs.
REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, HS2 n
D-64
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l Catawba Nuclear Site NATURAL DISASTERS. HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY SITE AREA EMERGENCY 4.7.S.2 Other Conditions Existing Which in the Judgement of the Emergency Coordinator / EOF Director Warrant Declaration of Site Area Emergency.
1 OPERATING MODE APPLICABILITY: All EMERGENCY ACTION LEVEL:
i 4.7.S.2-1 Other conditions exist which in the Judgement of the Emergency Coordinator / EOF Director indicate actual or likely major failures of plant functions needed for i protection of the public. '
l l BASIS:
This EAL is intended to address unanticipated conditions not addressed explicitly elsewhere but that warrant declaration of ra emergency because conditions exist which are believed by the l Emergency Coordinator / EOF Director to fall under the emergency class description for Site Area l
Emergency.
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REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, HS3 l
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D-65 l
i Catawba Nuclear Site NATURAL DISASTERS. HAZARDS AND OTHER CONDITIONS AFFECTING PLANT SAFETY GENERAL EMERGENCY I
4.7.G.1 Other Conditions Existing Which in the Judgement of the Emergency Coordinator / EOF Director Warrant Declaration of General Emergency.
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OPERATING MODE APPLICABILITY: All EMERGENCY ACTION LEVEL:
i 4.7.G.1-1 Other conditions exist which in the Judgement of the Emergency Coordinator / EOF i Director indicate:
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- e actual or imminent substantial core degradation with potential for loss of j containment
,! OR e potential for uncontrolled radionuclide releases These releases can reasonably be expected to exceed Environmental Protection l Agency Protective Action Guideline levels outside the site boundary.
{ BASIS:
l l This EAL is intended to address unanticipated conditions flot addressed explicitly elsewhere but l
that warrant declaration of an emergency because conditions exist which are believed by the 4
Emergency Coordinator / EOF Director to fall under the General Emergency class.
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REFERENCE:
NUMARC/NESP-007, REV. 2, 01/92, HG2 l
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ENCLOSURE 3 Catawba Procedure RP/0/A/5000/01, i
" Classification of Emergency" 4
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RP/0/A/5000/01 l DUKE POWER COMPANY CATAWBA NUCLEAR SITE CLASSIFICATION OF EMERGENCY l.0 SYMPTOMS
! 1.1 Notification of Unusual Event
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- 1.1.1 Events are in process or have occurred which indicate a potential i
degradation of the level of safety of the plant.
1.1.2 No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.
1.2 Alert .
1.2.1 Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant.
1.2.2 Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels.
1.3 Site Area Emergency 1.3.1 Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public.
l 1.3.2 Any rebases are not expected to result in exposure levels which I exceed EPA Protective Action Guideline exposure levels except near the site boundary.
1.4 General Emergency 1.4.1 Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. **
1.4.2 Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area.
RP/0/A/5000/01 l Page 2 of 2 l 2.0 IMMEDIATE ACTIONS 2.1 Determine operating mode that existed at the time the event occurred prior to any protection system or operator action initiated in response of the
- j event.
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, 2.2 If the plant was in Mode 1-4 and a valid condition affects fission product j barriers, then proceed to Enclosure 4.1.
j 2.3 If the condition does not affect fission product barriers, then review the j listing of enclosures to determine if the event is applicable to one of the
! categories shown.
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! 2.4 Compare actual plant conditions to the Emergency Action Levels listed,
- then declare the appropriate Emergency Class as indicated.
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2.5 Implement the applicable Emergency Response Procedure (RP) for that
- classification and continue with subsequent steps of this procedure.
I l Notification of Unusual Event RP/0/A/5000/02 i Alert RP/0/A/5000/03 Site Area Emergency RP/0/A/5000/04 General Emergency RP/0/A/5000/05 1
4 3.0 SUBSEOUENT ACTIONS 1
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- 3.1 To escalate, de-escalate, or terminate the Emergency, compare plant !
conditions to the Initiating Conditions of Enclosures 4.1 through 4.7.
3.2 Refer to enclosure 4.9, Emergency Declaration Guidelines, as needed.
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4.0 ENCLOSURES l
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{ 4.1 Fission Product Barrier Matrix l 4.2 Systems Malfunctions 4.3 Abnormal Rad Levels / Radiological Effluent 3
4.4 Loss of Shutdown Functions 4.5 Loss of Power
} 4.6 Fires / Explosions and Security Events 4.7 Natural Disasters, Hazards and Other Conditions j Affecting Plant Safety J 4.8 Definitions / Acronyms 4.9 Emergency Declaration Guidelines i
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RP/0/A/5000M1 Enclosure 4.1 Page 1 of 3 CATAWBA NUCLEAR SITE EMERGENCY ACTION LEVELS FISSION PRODUCT BARRIER MATRIX Use EALs to determine Fission Product Barrier status (Intact, Potential Loss, or Loss). Add points for all 3 barriers. Classify according to the table below.
Note 1: This table is only applicable in Modes 1-4.
Note 2: Also, an event (or multiple events) could occur which results in the conclusion that exceeding the Loss or Potential Loss thresholds is IMMINENT (i.e., within 1-3 hours). In this IMMINENT Loss Situation, use judgement and classify as if the thresholds are exceeded.
Unusual Event II - 3 Pointal Alert f4 - 6 Pointal Site Aree Emereency (7- 10 Points) General Emereency (11 - 13 Points)
. Any Potential Loss of Contamment . Any Potential Loss or Loss of the . Loss of both NCS and Fuel Ctr 3 . Loss of any three barriers NCS
. Any Loss of Containtnent . Any Potential Loss or Loss of Fuel . Potential Loss of both NCS and Fuel . Los. of any two barriers and the Clad Clad Potential Loss of the third barrier
. Potenial Loss of either the NCS or Fuel Clad and Loss of any additional barrier NOTE: Take highest points for each barrier and add together in chart below. Do not take more than one number for each barrier. "Not applicables" are included in this table as place holders only, and no points are assigned.
Containment TOTAL POINTS NCS 1-3 Unusual Event 4-6 Alert Fuel Clad 7-10 Site Arca Emergency 11-13 General Emergency Total Points 1 l
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RP/0/A/5000/01 Enclosure 4.1 Page 2 of 3 CATAWBA NUCLEAR SITE EMERGENCY ACTION LEVELS FISSION PRODUCT BARRIER MATRIX CONTAINMENT BARRIER NCS BARRIER FUEL CLAD BARRIER POTENTIAL LOSS-(1 LOSS -(3 Points) POTENTIAL LOSS-(4 LOSS -(5 Points) POTENTIAL LOSS -(4 LOSS -(5 Points)
Point) Points) Points) t Cducal Salsty Funcean Stamas tCntalSainty Functor:Semius t Cttlical Sainty Funchen Stake e ContanmortMD e e NCS heptyfled
- Not appbcable e Core Coahng4 range e Core CoohrgRed Nol an[* nMa e Heat Sekhd + Heat Smkfled 1 Containment Cenigdone litCS Laak Rats 1 Primary Cociant ActMiy Level e Contanment Pressure > 15 e Rapd unexplaned decreasein e Unisolatdeleakexceedng the e GREATER THAN avalable o Not apptrnNa e CoolmW ACbvty GREATER PSIG contammert pressure kdoming capaaty of one chargng pump makeup capacay asindcated THAN 300 pCWcc Dose abalmcrease in me normaldiaryng made by a loss of NCS stixxdng. Equivalent kxine (DEI)I131
+ H2 concercanon > 9% weletdown notated e Contamment pressure or sump
+ Contanment pressure gester level response not conssumt than3 psigumlessthanone wth LOCA condmons.
hdIran d NS and a VXf., ARF operabng.
1 ContainmentIsaisson Valves Status After Containment isoladon 1 SG Tulie.fhallire 1 Containment Radiationihnitoring Actuadon e e PnmapSacondaryleak rate o kdcanon that a SG e e Ncd apohcabhp e Contammert radaban mondor e Ncd appbcable Contanment solaban is incomplete and a estesse path exceeds the capaaty alone Ruptured and has a Nord 53Aor538 readng>t17Rtr from contamment exsis chargog purmin me normal isolable secondary hne lault dsaryng mode wihletdown notami e Indcator mat e SGis Ruptured and a prolonged mease of contarinaied seconday cooiartis caxanno from the anecsed SG e the eneronmort
- 4. SG Secondary Side Reinase With Primary 4o Secondary Lankaps & Canisinannt Redenen Monitoring & Eniergency CoorMOF Director Aulgament e Notag4 cable o Release of secondary sde b e Not apphe=Na e Unplanned Valid Tnp Ialann e Any andson indudng mately to morwar lhe bamer, hat in the opnon of alnosphere aih pnmary to on EMFs 38,39, or 40 he Emergency CoordnakrfOF Drector inostes LOSS or POTENTIAL secondary leakage GREATER LOSS or the FuelClad bemer THAN Tedt Spec allowatdo END
( _ __ _ _ _ _ _ __________________________________ __. __________ __ - __________________-____________________
__ _ _ . _ _ _ . . _ _ . . _ _ . . . . _ _ ~ _ _ _ _ _ _ __ . _ _ . . _ . . _ . . _
RP/0/A/5000/01 Enclosure 4.1 Page 3 of 3 CATAWBA NUCLEAR SITE EMERGENCY ACTION LEVELS FISSION PRODUCT BARRIER MATRIX CONTAINMENT BARRIER NCS BARRIER FUEL CLAD BARRIER POTENTIAL LOSS - LOSS - (3 Points) POTENTIAL LOSS - LOSS -(5 Points) POTENTIAL LOSS - LOSS -(5 Points)
(1 Point) (4 Points) (4 Points) i signancant numancew hvenemy m consumment i Emmgancy CoordnsindEOF Director Judgunant
- ContsnmentRad Mon 6x e Not appbcable Any mndhon, sddng nathy to nmlor the terner, em m the opnen d the ,
EMF 53A or 538 Ernergency CoordnmorEOF Duodor rdcates LOSS or POTENTIAL LOSS d RenGng 0 tens ance lho NCS bemer.
shuaswt
>470 Rtr 4 0 0.5 tr END
>170 RMr e 0 5-2 hr
>125 Rhr e 2-4 hr
> 90 Rtr e 4 - 8 tr
> 53 Rtr e > 8 tr idGftS91dDS
+ Core cooing ftED pathis e Not apphcable indcatedlor > 15 rrurt
- 7. Emergency Coordinaler EOF Director Jwigsmant
. Any coneson. rddng inatmy to amtor the barner, that m ihe opnon d the Emegency CoordnatorEOF Dueaar recates a LOSS or POTENTIAL LOSS d the Contamment bemer.
END J
CATAWBA NUCLEAR SITE -
RP/0/A/500001 EMERGENCY ACTION LEVELS Enclosure 4.2 SYSTEM MALFUNCTION Page 1 of 2 ALERT SITE AREA EMERGENCY GENERAL EMERGENCY UNUSUAL EVENT
- 1. Inabliity to Reach Required Shutdown 1. Unplanned Loss of Most or All Safety 1. Inability to Monitor a Significant Within Technical Specification Limits. System Annunciation or Indication in Transient in Progress.
Control Room With Either:
OPERATING MODE: 1,2,3,4 (1) a Significant Transient in Progress, OPERATING MODE: 1,2,3,4 or e Plant is not brought to required operating (2) Compensatory Non-Alarming e The following conditions exist:
mode within Technical Specifications LCO Indicators Unavailable.
Action Statement Time. Unplanned loss of most (>50%)
OPERATING MODE: 1,2,3,4 annunciators associated with safety
- 2. Unplanned Loss of Most or All Safety systems for greater than 15 minutes.
System Annunciation or Indication in . The following conditions exist the Control Room for Groeter Than AND 15 Minutes. Unplanned loss of most (>50%)
annunciators associated with safety A significant plant transient is in OPERATING MODE: 1,2,3,4 systems for greater than 15 minutes. progress, e The following conditions exist AND 4 J Unplanned loss of most (>50%) in the opirvon of the Operatums Shift Loss of the OAC.
annunciators associated with safety ManagerEmergency systems for greater than 15 minutes. CoordmatorEOF Director, the loss of AND the annunciators orindicators AND requires additional personnel Inability to provide manual (beyond normal shift ,,t) to monitoring, independent of the OAC in the opinion of the Operations Shift safety operate the unit. Critical Safety Functxm Status Tree ManagerEmergency program, of any one of the following CoordmatorEOF Director, the loss of AND Critical Safety Functions:
the annunciators or indicators requires additional personnel EITHER of the following: . subcriticality (beyond normal shift compliment) to e core cooling safely operate the unit. y e A significant plant transientis e heat sink in progress. + containment
- 3. Fuel Clad Degradation. '
- Loss of the OAC.
OPERATING MODE: ALL M e Dose Equivalent 1-131 greater than the M Technical Specification allowable limit.
CATAWBA NUCLEAR SITE RPMA/5000M1 EMERGENCY ACTION LEVELS Enclosure 4.2 SYSTEM MALFUP1CTION Page 2 of 2 UNUSUAL EVENT ALERT SITE AREA EMERGEP'SX GENERAL EMERGENCY
- 4. Reector Cootent System (NCS)
Leekage.
OPERATING MODE. 1,2,3,4 e Unidentinedleakage21 0gpm o Pressure boundary leakage z to gpm e identifeed leakage 2 25 gpm
- 5. Unplanned Loss of All Onsite or Offsite Communications.
OPERATING MODE: ALL e Loss of an onsite communications capability (intemal phone system, PA system, onsite radio system) affecting the ability to perform routine operations.
- Loss of au offsite communications capatety (Selective Signahng, NRC FTS lines, offsite radio system, commercial phone system) affecting the ability to communicate with offsite authonties.
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CATAWBA NUCLEAR SITE RP/0/A/5000/01 EMERGENCY ACTION LEVELS Enclosure 4.3 ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENT Page 1 of 3 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY
- 1. Any Unplanned Release of n==aans or 1. Any Unplanned Reloose of 1. Boundary Dose Resulting from an 1. Boundary Dose Resulting from an Liquid Radioactivity to the naamans or Liquid Radioactivity to Actual or Imminent Release of Actual or Imminent Release of Environment that Exceeds Two Times the Environment that Exceeds 200 Radioactivity Exceeds 100 mRom Radioactivity that Exceeds 1000 the SLC Limits for 60 Minutes or Times the SLC limits for 15 TEDE or 500 mRom CDE Adult mRom TEDE or 5000 mRom CDE Longer. Minutes or Longer. Thyroid for the Actual or Projected Adult Thyroid for the Actual or Duration of the Release. Projected Duration of the Release ~
OPERATING MODE. ALL OPERATING MODE: ALL OPERATING MODE: ALL OPERATING MODE. ALL e a. A valid TRIP 2 alarm on radiation e a. A valid TRIP 2 alarm on radiation monitor EMF- 49L or EMF-57 monnor EMF- 49L or EMF-57
- A valid indication on radiation
- A valid indication on radiation monitor EMF-36L of2 1.08 E+07 monitor EMF-36H of2 1.72 E + 04 AND AND cpm cpm
- b. Failure of the release path to b. Failure of the release path to . Dose assessment team calculabons . Dose assessment team calculations automatically isolate automatically isolate indicate dose consequences indicate dose consequences greater than 100 mrem TEDE or greater than 1000 mrem TEDE or AND AND 500 mrem CDE Adult Thyroid at the 5000 mrem CDE Adult Thyroid at site boundary, the site boundary.
- c. The liquid radioachve release to the c. The liquid radioachve release to the environment exceeds two times the environment exceeds 200 times the
- Analysis of field survey results or . Analysis of field survey results or SLC limit for 60 minutes or longer. SLC limit for 15 minutes or longer. field survey samples indicates dose field survey samples indicates dose consequences consequences e A valid indication on radiation morutor e A valid Indication on radiation monitor greater than 100 mrem TEDE or greater than 1000 mrem TEDE or EMF- 36L of 21.08 E+04 cpm for260 EMF- 36L of 21.08 E+06 cpm for 215 500 mrem CDE Adult Thyroid at the 5000 mrem CDE Adult Thyroid at minutes. minutes. site boundary, the site boundary.
.e Gaseous effluent being released exceeds = Gaseous effluent being released exceeds Note 1: These EMF readings are ca!culated Note 1:These EMF readengs are calculated two times SLC 16.11-1 for z 60 minutes 200 times the level of SLC 16.11-1 for 2 based on worst case average annual based on worst case average annual as determoed by Radiation Protection 15 minutes as detemunod by RP meteorology, a sixty minute release duration, meteorology, a sixty minute release duration, (RP) procedure. procedure. and design unit vent flow rate. Calculations by and design unit vent flow rate. Calculations by the dose assessment team use actual the dose assessment team use actual e Liquid effluent being released exceeds! . Liquid effluent being released exceeds meteorology, duration, and unit vent flow rate. meteorology, duration, and unit vent flow rate.
two tunes SLC 16.11-6 for z 60 minutes 200 times the level of SLC 16.11-6 for z Therefore, these EMF readings should not be Therefore, these EMF readings should not be as determined by RP procedure. 15 minutes as determoed by RP used if dose assessment team calculations are used if dose assessment team calculations are procedure. available. available.
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CATAWBA NUCLEAR SITE RPMAAiO0041 EMERGENCY ACTION LEVELS Enclosure 4.3 ABNORMAL RAD LEVELS / RADIOLOGICAL EFFLUENT Page 3 of 3 UNUSUAL EVENT ALERT SITE AREA ERIERGENCY GENERAL ERAERGOdCY e Plant personnel report that water level drop in reactor refueling cavity, spent fuel pool, or fuel transfer canal has or wiB exceed makeup capacity such that irradiated fuel win become uncovered.
- NC system wide range level <95 %
after initiatlon of NC system make-up Alm Any irradiated fuel assembly not capable of being lowered into spent fuel pool or reactor vessel AND KF-122 cannot be closed.
- 3. Reloose of Radioactive 80etorial or increases in Radletion Levelo Within the Facility That Impedes operation of Systeme Required to assentain Sese Operemone or to Establish or RAelnteln Cold Shutdown.
OPERATING RIODE: ALL
= Valid radiaton rnonitor reading indicatmg greater han 15 mR/tw in j
the control room or PAP.
~
e Valid radiation monitor reading of >5 R/hr in a plant vital area. - j EtE
CATAWBA NUCLEAR SITE -
RP/0/A/500041 EMERGENCY ACTION LEVELS - Enclosure 4.4 LOSS OF SHUTDOWN FUNCTIONS Page 1 of 2 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY ENQ Failure of Reactor Protection System 1. Failure of Reactor Protection System 1. Failure of the Reactor Protection 1.
Instrumentation to Complete or Initiate instrumentation to Complete or initiate System to Complete an Automatic Trip an Automatic Reactor Trip Once e an Automatic Reactor Trip Once a and Manual Trip was NOT Successful Reactor Protection System Setpoint Reactor Protection System Setpoint and There is indication of en Extreme Hee Been Exceeded and Manual Trip Has Been Exceeded and Manuel Trip Challenge to the Ability to Cool the WAS Successful WAS NOT Successful. Core.
OPERATING MODE: 1,2,3 OPERATING MODE: 1 OPERATING MODE: 1
. The followmg condrbons exist . The following conditions exist . The following conditions exist Valid reactor trip signal received Valid reactor trip signt i Valid reactor trip signal received or or requred. received or required. required.
AND AND AND Manual reactor trip from the control Manual reactor trip from the control Manual reactor trip from the control room is successful and reactor room was not successfulin reducing room was not successfulin reducing ;
power is less than 5% and reactor power to less than 5% and reactor power to less than 5% and decreasing. decreasing. decreasing.
- 2. Inability to Maintain Plant in Cold 2. Complete Loss of Function Needed to AND Shutdown. Achieve or Maintain Hot Shutdown.
EITHER of the following conditions OPERATING MODE. 5, 6 OPERATING MODE: 1,2,3,4 exist
. Totalloss of ND and/or RN and/or KC . Core Cooling CSF-RED = Core Cooling CSF-RED l AND = Heat Sink CSF-RED . Heat Sink CSF-RED
. Suberiticality CSF-RED E y inatnhty to mamtam ry coolant temperature below 200 F.
~
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CATAWBA NUCLEAR SITE RPA)/A/5000/01 EMERGENCY ACTION LEVELS Enclosure 4.4 LOSS OF SHUTDOWN FUNCTIONS Page 2 of 2 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY
- 3. Loss of Water Levelin the Reactor Vessel That Has or Will Uncover Fuel in the Reactor Vessel OPERATING MODE. 5, 6
- Failure of heat sink causes loss of cold shutdown conditions.
AND Lower range Reactor Vessel Level Indication System (RVLIS) decreasing after initiation of NC system makeup.
- Failure of heat sink causes loss of cold shutdown conditions.
AND Reactor Coolant (NC) system narrow range levelless than 11% and decreasing after initiation of NC system makeup.
- Failure of heat sink causes loss of cold shu'down conditions.
AND 4 Either train ultrasonic level indication less than 7.25% and decreasing after initiation of NC system makeup.
E!E
CATAWBA NUCLEAR SITE RP/0/A/500041 EMERGENCY ACTION LEVELS Enclosure 4.5 LOSS OF POWER Page 1 of 1 USUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY
- 1. Loss of AM 953!I3Power to 1. Loss of All OffsNe Power and Loss 1. Loss of All Offsite Power and Loss 1. Prolonged Loss of All(Offsite and Essential Buseos for Groeter Then of All9g3llg AC Powerto of AN Onsite AC Power to Onsite) AC Power.
15 Minutes. Essential Busses During Cold Essential Busses.
Shutdown Or Refueling Mode. OPERATING MODE. 1,2,3,4 OPERATING MODE: ALL OPERATING MODE- 1,2,3,4 OPERATING MODE: 5,6, No Mode . Prolonged loss of an offsite and
. The following cordtions exist . Loss of all offsite and onsite AC onsite AC power as indicated by-
. Loss of at offsite and onsite AC power as indicated by-Loss of offsite power to essenbal power as indicated by: Loss of power on essential buses buses ETA and ETB for greater than Loss of power on essential buses ETA and ETB for greater than 15 15 minutes. Loss of power on essential buses ETA and ETB. minutes.
ETA and ETB.
AND AND AND AND Each emergency diesel generator is Failure to restore power to at least Standby Shutdown Facility (SSF) supplymg power to its respective Failure to restore power to at least one essenhal bus within 15 minutes. fails to maintain hot standby.
essenbalbus. one essental bus within 15 mmutes
- 2. Loss of All Vital DC Power. AND
- 2. Unplanned Loss of Reautrod DC 2. AC power to essential busees Power During Cold Shutdown or reduced to e single power source OPERATING MODE: 1,2,3,4 At least one of the following Refueling Mode for Grooter then for grooter then 15 minutes such Mikris exist 15 Minutes. that an additional single failure . The following condibons exist could result in stellon blackout. . Restorabonof atleastone OPERATING MODE. 5,6 Unplanned loss of both unit related essenbal bus within 4 OPERATING MODE: 1,2,3,4 busses: EBA amd EBD both <112 hours is NOTlikely.
. The followng mndrtons exist VDC, and EBB and EBC both <109
. The following condibon exists: VDC. . Indication of continuing Unplanned loss of both unit related degradation of core coolmg busses EBA amd EBD both <112 AC power rapahihty has been based on Fission Product VDC, and EBB ar4 EBC both <109 degraded to one essenbal bus AND Barrier n w.7 ming.
VDC. y powered from a single power source AND for > 15 min. due to :ne loss of au but Failure to restore power to at least M one of: one required DC bus within 15 Failure to restore power to at least SATA SATB minutes from the bme'of loss.
one required DC bus within 15 ATC ATD minutes from the bme of loss. D/G A D/G B M M M
f CATAWBA NUCLEAR SITE RP/0/A/5000/01 EMERGENCY ACTION LEVELS Enclosure 4.6 FIRE / EXPLOSION AND SECURITY EVENTS Page 1 of 2 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY
- 1. Fire or Explosion Within Protected 1. Fire or Exploolon Affecting the 1. Security Event in a Plant Vital Area. 1. Security Event Resulting in Loos Of Aree Boundary Not Extinguished Operstdlity of Plant Safety Systems Ability to Reach and Maintain Cold Within 15 Minutes of Detection. Required to Establish or Maintain Safe OPERATING MODE. ALL Shutdown.
Shutdown.
OPERATING MODE: ALL e intrusion into any of the following plant OPERATING MODE. ALL OPERATING MODE. 1,2,3,4 areas by a hostile force:
- Fire in any of the fotowing areas not
- Reactor Buddog
- Loss of physscal contrd of the control extnguished within 15 minutes of control e The following conditons exist
- Auxiliary Building room due to secunty event.
room noldcaton or venfication of a
- Diesel Generator Rooms control room fire alarm. Fire or ==& in any of the fotowmg
- Control Room = Loss of physicci control of the SSF and areas-
- RN Pump House ASP due to security event.
- Reactor Buildmg
- SSF
= Auxiliary Buildmg
- Reactor Buddmg -* Doghouses E!E
- Diesel Generator Rooms
- An=hary Buddag
- Control Room . Diesel Generator Rooms
- RN Pump House a Control Room . Security confirmed bomb
= SSF
- RN Pump House discovered / exploded in a vital area.
- SSF.
- Doghouses
- Secunty confirmed sabotage in a plant 4
- FWST
- Doghouses vital area.
- Turtune Building
- FWST ,
- Service Bidg. E!E
- Interim Radweste Badg. Afe e Reportbyplantpersonnelof an Oneof thefollowing-unenecipated explosion within protected area boundary resulung in visible . Affected safety system damage to permanent structure or parameter indications show equement. degraded perfom.ance
. Plant personnel report vielble 4 damage to permanent structures or equipment within the specded area. .
Note applies to Mode 1,2,3,4,5,6.
Note: Only one train of a system needs to be affected or damaged in order to satisfy this condrbon.
CATAWBA NUCLEAR SITE RP/0/A/5000N)1 EMERGENCY ACTION LEVELS Enclosure 4.6 FIRE / EXPLOSION AND SECURITY EVENTS Page 2 of 2 UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY
- 2. Confirmed Security Event Which 7 g, gg indicates a Potentiel Degradetion in the OperabilMy of Plant Safety Systems tM Nnt Required to EstatWish or Maintain Sefe Shutdown.
OPERATING MODE: All
- Secunty confirmed bomb device discovered within plant Protected Area and outside Vital Areas. . The follomng coruttions exist Fire or explosion in any of the following
- Mdh areas:
e A violent civil disturbance within the
- Reactor Building owner controlled area. . Auxiliary Building
- Diesel Generator Rooms
- Control Room
+ RN Pump House a SSF
= CAS
. FWST AND One of the follomng
- Affected safety system parameter indications show degraded Performance
= Plant personnel report visitne damage to permanent structures or equipment within the specified area.
- 3. Security Event in a Plant Protected 4 Area.
OPERATING MODE.- ALL .
- Area by Intrusion into plant Protected a hostile force.
E!!E
CATAWBA NUCLEAR SITE -
RP/0/A/5000/01 EMERGENCY ACTION LEVELS Enclosure 4.7 NATURAL DISASTERS, HAZARDS, AND OTHER CONDITIONS Page 1 of 3 AFFECTING PLANT SAFETY UNUSUAL EVENT AL_E_RT, SITE AREA EMERGENCY GENERAL EMERGENCY
- 1. Natural and Destructive Phenomena 1. Natural and Destructive Phenomena 1. Control Room Evacuation Has Been 1. Other Conditions Existing Which in the Affecting the Protected Area. Affecting the Plant Vital Area. Initiated and Plant Control Cannot Bo Judgement of the Emergency Established. CoordinatorEOF Director Warrant OPERATING MODE: ALL OPERATING MODE: ALL Declaration of General Emergency.
OPERATING MODE: ALL e Tremor felt and valid alarm on the
- strong . Valid seismic accelerations greater than OPERATING MODE: ALL the operating basis earthquake (OBE): The following w dbn6 exist:
motum accelerograph". . ;
. Other conditions exist which in the e Tremor felt and valid alarm on the ' Peak 0.08 g horizontal Contro! room evacuation has been Judgement of the Emergency shock annunciator". OR initiated. CoordinatorEOF Director indicate:
0.053 g vertical. ;
e Report by plant personnel of tomado AND (1) actual or imminent substantial core i striking within protected area boundary. . Tomado or high winds: degradation with potential for loss of Control of the plant cannot be containment, o Vehicle crash into plant structures or Tomado sinking plant structures established from the ASP or the SSF ,
systems within protected area boundary. within the vital area within 15 minutes. OR OR e Report of turbine failure resulting in casing sustained winds 2 74 mph for > 15 2. Other Conditions Existing Which in the (2) potential for uncontrolled radionuclide penetration or damage to turbine or minutes. Judgement of the Emergency releases. These releases can generator seals. CoordinatorEOF Director Warrant reasonably be expected to exceed
. Turbine failure generated missiles. vehicle Declaration of Site Area Emergency. Environmental Protection Agency
- 2. Release of Toxic or Flammable Gases crashes or other catastrophic events Protective Action Guideline levels Deemed Detrimental to Safe Operation causing visible structural damage on any OPERATING MODE: ALL outside the site boundary.
of the Plant. of the following plant structure -
= Other conditions exist which in the M OPERATING MODE: ALL
- Reactor Buikkng Judgement of the Emergency
. Auxiliary Building CoordinatorEOF Director indicate actual e Report or detection of toxic or flammable . FWST or likely major failures of plant functions gases that could enter within the site area . Diesel Generator Rooms needed for protection of the public.
boundary in amoursts that can affect safe . Control Room coeration of the olant. . RN Pump House M
. SSF
= Doghouses
. CAS
CATAWBA NUCLEAR SITE RP/0/A/5000N)1 EMERGENCY ACTION LEVELS Enclosure 4.7 NATURAL DISASTERS, HAZARDS, AND OTHER CONDITIONS Page 2 of 3 AFFECTING PLANT SAFETY UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY e Report by Local, County or State Officials 2. Release of Toxic or Flemmable Geses for potential evacuation of site personnel Within a Facility Structure Which based on offsite event. Jeopardtros Operation of Systems Required to Maintain Solo Operations
- 3. Other Conditions Existing Which in the or to Establish or Maintain Cold Judgement of the Emergency Shutdown.
CoordinatorEOF Director Warrant Declaration of en Unusual Event. OPERA 11NG MODE. ALL OPERATING MODE: ALL = Report or detection of toxic gases within a Facility Structure in concentrations that
- Other mubi. exist which in the will be life threatenina to plant personnel-Judgement of the Emergency Coordinator / EOF Director indicate a . Report or detection of Rammable gases potentialdegradation of thelevelof safety within a Facility Structure in concentra-of the plant. tions where lack of access to the following plant structures wiR affect the safe Efg operation of the plant
. Reactor Building
. Auxiliary Building
. Diesel Generator Rooms
. Control Room
. RN Pump House
. SSF
. Doghouses
. CAS 2
CATAWBA NUCLEAR SITE RP/0/A/5000/01 EMERGENCY ACTION LEVELS Enclosure 4.7 NATURAL DISASTERS, HAZARDS, AND OTHER CONDITIONS Page 3 of 3 AFFECTING PLANT SAFETY UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY
- 3. Control Room Evacuation Has Been initleted.
OPERATING Mord ALL
- Emtion of the control room and control is, or is in the process c' being, estathshed from the ASP or the SSF.
- 4. Other Conditions Existing Which in the Judgement of the Emergency CoordinatorEOF Director Warrant Declaration of an Alert.
OPERATING MODE. ALL
= Other conditions exist which in the Judgement of the Emergency CoordinatorEOF Directorindicate that plant safety systems may be degraded and that increased monitoring of plant functons is warranted.
ele 2
e
I RP/0/A/5000/01 l Encio mre 4.8 Page 1 of 3 DEFINITIONS / ACRONYMS ALERT- Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. Any releases are expected to be limited to small fractions of the EPA protective action guideline exposure levels.
BOMB- A fused explosive device CARF- Containment Air Return Fan CIVIL DISTURBANCE - A group of people violently protesting station operations or activities at the site. A civil disturbance is considered to be violent when force has been used in an attempt to injure site personnel or damage plant propeny.
i EPA PAG - Environmental Protection Agency Protective Action Guidelines for exposure '
to a release of radioactive material.
EXPLOSION - A rapid, violent unconfined combustion, or a catastrophic failure of
- pressurized equipment that impans energy of sufficient force to potentially damage permanent structures, systems or components.
EXTORTION - An attempt to cause an action at the site by threat of force.
FIRE - Combustion characterized by heat and light. Sources of smoke such as slipping drive belts or overheated electrical equipment do not constitute fires. Observation of flames is preferred but is NOT required if large quantities of smoke and heat are observed.
l FUNCTIONAL - A component is fully capable of meeting its design function. It would be declared INOPERABLE if unable to meet Technical Specifications.
GENERAL EMERGENCY- Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of l containment integrity. Releases can be reasonably expected to exceed EPA protective l action guideline exposure levels outside the Site Boundary. l HOSTAGE - A person or object held as leverage against the site to ensure demands will be met by the site.
HOSTILE FORCE - One or more individuals present in a PROTECTED AREA without authorization that may have or have threatened to use force in an attempt to injure site l personnel or damage plant property.
IMMINENT - Expected to occur within 1-3 hours.
l
.-, , . . , --- .- .~ -. -. -.
RP/0/A/5000/01 Enclosure 4.8 Page 2 of 3 INABILITY TO DIRECTLY MONITOR - Operational Aid Computer data points are unavailable or gauges / panel indications are not readily available to the operator.
INOPERABLE - A component does not meet Technical Specifications. The component may be functional, capable of meeting its design.
INTRUSION / INTRUDER - Suspected hostile individual present in a PROTECTED AREA without authorization.
LOSS - A component is INOPERABLE and not FUNCTIONAL.
PROLONGED - A duration beyond normal limits, defined as " greater than 15 minutes" or as determined by the judgement of the Emergency Coordinator.
PROTECTED AREA - Encompasses all owner controlled areas within the security perimeter fence.
RUlrrURED (As relates to Steam Generator) - Existence of primary to secondary leakage of a magnitude sufficient to require or cause a reactor trip and safety injection.
SABOTAGE - Deliberate damage, misalignment, or misoperation of plant equipment with the intent to render the equipment unavailable.
SIGNIFICANT TRANSIENT- An unplanned event involving one or more of the following: (1) Automatic turbine runback >25% thermal reactor power, (2) Electrical load rejection >25% full electrical load; (3) Reactor Trip, (4) Safety Injection SITE AREA EMERGENCY - Events are in process or have occurred which involve actual or likely major failures of plant functions needed for the protection of the public.
Any releases are NOT expected to result in exposure levels which exceed EPA protective action guideline exposure levels outside the Site Boundary.
SITE BOUNDARY - That area, including the protected area, in which Duke Power Company has the authority to control all activities, inc;uding exclusion or removal of personnel and property.
SLC - Selected Licensee Commitments e
SECURITY EVENT - A security related emergency situation for which prompt response by the Security Force, immediate action by plant personnel, and/or assistance from offsite agencies may be required to apprehend intruders and mitigate the effects of or prevent radiological sabotage.
_- .~ . ._-
I RP/0/A/5000/01 l Enclosure 4.8 Page 3 of 3 l
SUSTAINED - A duration of time long enough to confirm that the CSF is valid (not momentary).
TERMINATION - Exiting the emergency condition.
TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE) - The sum of external dose exposure to radioactive plume, to radionuclides deposited on the ground by the plume, and the intemal exposure inhaled radionuclides deposited in the body.
TOXIC GAS - A gas that is dangerous to life or health by reason ofinhalation or skin contact (e.g. chlorine).
UNCONTROLLED - Event is not the result of planned actions by the plant staff.
UNPLANNED - An event or action is UNPLANNED if it is not the expected result of '
normal cperations, testing, or maintenance. Events that result in corrective or mitigative actions being taken in accordance with abnormal or emergency procedures are UNPLANNED.
UNUSUAL EVENT- Events are in process or have occurred which indicate a potential degradation of the level of safety of the plant. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.
VALID - An indication or report or condition is considered to be VALID when it is conclusively verified by: (1 ) an instrument channel check, or (2) indications on related or redundant instrumentation, or (3) by direct observation by plant personnel such that doubt related to the instrument's operability, the condition's existence or the report's accuracy is ;
removed. Implicit in this definition is the need for timely assessment.
VIOLENT - Force has been used in an attempt to injure site personnel or damage plant property.
I VISIBLE DAMAGE - Damage to equipment or stmeture that is readily observable without measurements, testing, or analyses. Damage is sufficient to cause concern regarding the continued operability or reliability of affected safety stmeture, system 4r component. Example damage: deformation due to heat or impact, denting, penetration, rupture, cracking, paint blistering.
VITAL AREA - Areas within the PROTECTED AREA that house equipment important for nuclear safety. Access to a VITAL AREA is allowed only if an individual has been authorized to be in that area.
RP/0/A/5000/01 l Enclosure 4.9 .
Page 1 of 2 !
EMERGENCY DECLARATION GUIDELINES THE FOLLOWING GUIDANCE IS TO BE USED BY THE EMERGENCY COORDINATOR IN ASSESSING EMERGENCY CONDITIONS.
- The Emergency Coordinator shall review all applicable initiating events to ensure proper classification.
e The BASIS Document (located in Section D of the Catawba Nuclear Site Emergency Plan) is available for review if any questions arise over proper classification.
- If an event occurs on more than one unit concurrently, the event with the higher classification will be classified on the emergency notification form. Information relating to the problem on the other unit will be captured on the emergency notification form.
- If an event occurs, and a lower or higher plant operating mode is reached before the classification can be made, the classification shall be based on the mode that existed at the time the event occurred.
- The fission product barrier matrix is applicable only to those events that occur at (Mode 1-4) hot shutdown or higher. An event that is recognized at cold shutdown or lower (Mode 5 or 6) shall not be classified using the fission product barrier matrix. Reference would be made to the additional enclosures that provide emergency action levels for specific events (e.g. severe weather, fire, security).
- If a transient event should occur, the following guidance is provided.
- 1. Some emergency action levels specify a specific duration. For these EALs, the classification is made when the Emergency Coordinator assessment concludes that the specified duration is exceeded or will be exceeded (i.e. condition cannot be reasonably corrected before the duration elapses), whichever is sooner.
- 2. If a plant condition exceeding EAL criteria is corrected before the specified duration time is exceeded, the event is NOT classified by that EAL. Lower l Severity EALs, if any, shall be reviewed for possible applicability in these cases. j
- 3. If a plant condition exceeding EAL criteria is not recognized at the tilhe of I occurrence, but is identified well after the condition has occurred (e.g. as a result of routine log or record review) and the condition no longer exists, an emergency shall NOT be declared. Reponing under 10CFR50.72 may be required. Such a condition could occur, for example, if a follow-up evaluation of an abnormal condition uncovers evidence that the condition was more severe than earlier believed.
l RP/0/A/5000/01 1 Enclosure 4.9 Page 2 of 2
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j 4. If an emergency classification was warranted, but the plant condition has been corrected prior to declaration and notification, the Emergency Coordinator must
- consider the potential that the initiating condition (e.g. Failure of Reactor j Protection System) may have caused plant damage that warrants augmenting the l on-shift personnel via activation of the Emergency Response Organization. The l following are applicable
j a. For UNUSUAL EVENTS, the condition shall be teported. The event may be terminated in the same notification or in a follow-up notification.
- b. For ALERT, SITE AREA EMERGENCY, and GENERAL EMERGENCY, the event shall be declared and the emergency response organization activated.
DETERMINATION OF " EVENT TIME" (TIME THE 15 MINUTE CLOCK STARTS)
- 1. If plant conditions require implementation of EP/1 or 2/A/5000/E0 (Reactor Trip or Safety Injection), increased emphasis shall be given to evaluation of plant conditions for ,
determination of EAL(s) when "kickout" of the diagnostic procedure occurs. " Event Time" is the time at which the EAL(s) is determined.
- 2. If plant conditions do not require implementation of EP/1 or 2/A/5000/E0 (Reactor Trip or Safety Injection), and conditions of a specific EAL are met, the " Event Time" is the time at which the EAL(s) is determined.
- 3. The time the event is classified shall be entered on the initial emergency notification form.
MOMENTARY ENTRY INTO A HIGHER CLASSIFICATION If, while in an emergency classification, the specified EALs of a higher classification are met momentarily, and in the judgment of the Emergency Coordinator are not likely to recur, the entry into the higher classification must be acknowledged. Acknowledgment is performed as follows:
If this condition occurs prior to the initial notification to the emergency response organization and off site agencies, the initial message should note that the site is currently in the lower classification, but had momentarily met the criteria forIhe higher classification. It should also be noted that plant conditions have improved and stabilized to the point that the criteria for the higher classification are not l expected to be repeated. l W- . v- - -,s. .--- - - r-- - - ,-,r e
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l ENCLOSURE 4 State and County Concurrence Letters 1
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} Duke Pouer Company i PO Box 1006 Charlotte. NC 252011006 f;
DUKEPOWER i November 21,1995 i
l Mr. Billy Ray Cameron Mr. Stan McKmney l NC Division of Emergency Management SC Es.gewy Preparedness Division j Mr. Bob Phillips Mr. Cotton Howell
- Gaston County Erregecy Mer.e.er.1. York County Eireg-cy Preparedness i
3 Mr. Wayne Broome Mr. Iarry DL.cs Charlotte /Mechburg Emergency Mgmt. Iredell County Emergency M==i-- =^
Mr. Rick Spake Mr. Charles Moody Lincoln County Emergency Management Catawba County Emergency Mer.e .m
! Gentien-l Duke Power is required by 10CFR50, Appaadiv E, Part IV.B, Assessment Actmas, to discuss and agree upon Erre.-cf Actmn levels (EALs) prior to implementarian Duke Poweris
- proposing to convert to Eir .-cy Acton Ievels based upon =iid- cantainad in 1 NUMARC/NESP-007, Reymon 2, which was approved by the NRC in Reg. Guide 1.101 l Revision 3 in August 1992 as an see pt=ble substitute to the EAL Guidehnes e*=iaad in i NUREG-0654, Appendix I. 'Ibese EALs are used as critena for deternunmg the need for
- nordientian and participation oflocal and state agencies and for d=- - ~ --g whm and what type of protective measures should be considered outside the site boundary.
I have provuled the procedure (s) containing the proposed NUMARC/NESP-007, Rev. 2, based Es. A levels for McGuire and Catawba Nuclear Site (as appropriate for your cf ction agency), and ask that you review this t-:-:- = - Upon completma of your reyww, please sign
.; and return the attached sheet imhcatmg your concurrence with the EALs and providmg any comments you may have. Please provide your response by December 1,1995.
If you have any questions, please call me at (704) 382-3151 or Gary Mitchell at (803) 831-3235. ,
Yours truly, r
,M A -
Tina Kuhr 1 Nuclear Eme.g-cy Planmng Consultant i
- At+=eha-=*
r~wnre wuceocaw
Gl}e 9 tate of Soutl} Garolina Siliturg Bepartment OFFICE OF THE ADJUTANT GENERAL 8TANHOPE S. SPEARS MAJOR GENERAL mEananmf aENEnal December 11,1995 Mr. Gary Mitchell Emergency Planning Manager Catawba Nuclear Station - -
4800 Concord Road York, SC 29745 SUBJEC 995 Catawba Nuclear Station EAL Review.
(.V
Dear . itc 11:
Enclosed is this agency's review and signature document for the subject EALs. Thank you for the opportunity to comment.
Have a wonderful Christmas holiday.
/'ere W Tim Murphy Area 2, Coordinator SMM:TM:tm C \TYJmCNEMEMOOGEAL LTR . -
4 Emergency Preparedness Division Rutledge Building 1429 Senate Street Columtds, South CaroHna 29201 (803) 734-8020 Fax (803) 734-8062
Renew of PrW 5== 7 Ah Imels EAla) based upon NUMARC/NESP-007 Rev. 2 I haw rn-2-M Um proposed E-gwy Action Incis for MsGuire/ Catawba Nuclear Site and agree that they are adequate for ewat elmaninentian and protectiw accan recomrnendarians.
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N : stan u. Merinnney. Director Agnacy: S C Emergency Preparedness Division Date: December 18, 1995 I haw rn-2d the proposed Ewegwy Action Imels for McGuue/ Catawba Nuclear Site and agree that they are W *- for ennt cimincarian and protectiw action the except for the followmg comments:
COMMENTS:
Aguacy:
M e d
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Review of Proposed Emerwency Acunn lxvels (EM}
based ueon NUMARC/NESP-007 Rev 2 I have reviewed the proposed Emergency Acton Levels for McGuire/ Catawba Nuclear Site and agree that they are usequate for event clanificatson and protective action arcommendauons.
Name: -
\
Agency:kd h[(. o[ .
Da: -..!2/W9s_....
I have neviewed the proposed Eme:gency Action Levels for McGuise/ Catawba Nuclear Site +
and agree that they are adequate for event classification and protecuve action recommendations except for the following comments:
COMMENTS .. -. ...
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1 Agency: _. _ __
Date: __
l Review of Pic_=A R===v Adian Levels (EALs) ha*M unon NUMARC/NESP-007 Rev. 2 I have reviewed the proposed Emergency Action Levels for McGuire/ Catawba Nuclear Site and agree that they are adequate for event classification and protective action recommendations. .
Name: A Agency: he o w 0* . $ m , $ 4 /pi/
Date: Odd,/8 p /99d I have reviewed the proposed Erne. wy Action Levels for McGuire/ Catawba Nuclear Site and agree that they are =%'* for event claneihtina and protective action iss== 4= dons except forthe following comments:
COMMENTS:
Name: __
Agency:
- Date: __
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l Review of Proposed E.rwu.- y Anim Levels MALs) based upon NUMARC/NESP-007 Rev. 2
- I bve reviewed the proposed Emergency Actim Levels for McGuire/ Catawba Nuclear Site j asw agree that they are adequate for event classification and protective action j rm. mss.tions.
/ !
Name: V Agency: ,/0 I
4 (ou ~k.
Date: //-/ H F i 1
l I have reviewed the proposed Emergency Action Imels for McGuire/ Catawba Nuclear Site
- and agree that they are adequate for event classi6 cation and protective action recomn-htions
! except for the following comments-COMMENTS:
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Name: ;
- I Agency:
Date:
I Review of Proposed Eresawcv Aman Levels EALs) based unon NUMARC/NESP-007 Rev. 2 l I have reviewed the proposed Emergency Action Ievels for McGuire/ Catawba Nuclear Site and agree that they are adequate for event classification and protective action tw. .= 4= dons.
Name:
N Agency: Cart /oMF-Madc/ pub; EM O
.. Date: lI 2)" D9 I have reviewed the proposed Ereigecy Action levels for McGuire/ Catawba Nuclear Site and agree that they are adequate for event classifimtian and protective action r= =-.u 4= dons except for the following comments-COMMENTS:
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Name:
n Date:
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