ML20012D820
| ML20012D820 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 03/06/1990 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20012D812 | List: |
| References | |
| CMIP-10-01, CMIP-10-1, NUDOCS 9003280409 | |
| Download: ML20012D820 (32) | |
Text
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DUKE POWER COMPANY CRISIS MANAGEMENT IMPLEMENTING PROCEDURES March 6, 1990
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i TABLE OF CONTENTS Volume 2 i
1 TAk Procedure Descriotion CMIP-8 Oconee Crisis Phone Directory (Rev. 25) 7 CMIP-9 McGuire/ Catawba Crisis Phone Directory
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(Rev. 32)
CMIP-10 Emergency Classification - Catawba (Rev. 3)
CMIP-11 Emergency Classification - McGuire (Rev. 6) r CMIP-12 Emergency Classification - Oconee (Rev. 6)
CMIP-13 Notifications-to States and Counties from the Crisis Management Center (Rev. 19)
CMIP-14 Crisis Management Data Transmittal System Access for Offsite Agencies - (Rev. 1)
CMIP-15 Reserved for future use CMIP-16 Crisis Management Data Transmittal System i
Access from the Crisis Management Center -
l (Rev. 9)
CMIP-17 Public Alerting on Lake Norman (Rev. '6)
CMIP-18 Maintaining Emergency Preparedness (Rev. 3)
.CMIP-19 Communications Test for McGuire/ Catawba CMC (Rev. 16) l CMIP-20 Communications Test for Oconee CMC (Rev. 10) 1 L,
CMIP-21 Quarterly Inventory Equipment Check (Rev. 30)
CMIP-22 Telephone Number Updates (Rev. 1) 1' l-March 6, 1990 l
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CRISIS MANAGEMENT IMPLEMENTING-PROCEDURE i
-a CMIP-10 l
Classification.of Emergency for Catawba Nuclear Station Rev. 3 March 6, 1990 -
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?C Approved By Date
a.
s CMIP-10 CLASSIFICATION OF EMERGENCY FOR CATAWBA NUCLEAR STATION 1.0 SYMPTOMS 1.1 Notification of Unusual Event 1.1.1' Events are in progress or have occurred which indicate a potential degradation of the level y
.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 occurs.
1.2 Alert 1.2.1 Events are in progress 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 L
l -
1.3.1 Events are in process or have occurred which t
involve actual or likely major failures of l
~ plant functions needed for protection'of the public.
1.3.2 Any releases are not expected to exceed EPA Protective Action Guideline exposure levels except near the site boundary.
J 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.
= 6 :.
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5 2.O IMMEDIATE ACTIONS 2.1 Compare actual plant conditions to the Emergency Action Level (s) listed in Enclosure 4.1 then declare the appropriate Emergency Class as indicated.
~
If a change in the emergency class is made, perform steps 2.2, 2.3, and 2.4 below.
2.2 Instruct the State / County Communicator to notify. the state (s) and counties per CMIP-13 of any change in the emergency class.
If the emergency class is SITE AREA EMERGENCY o.r GENERAL EMERGENCY, determine protective dCtion recommendations per CMIP-1 and transmit these i
recommendations.
NOTE:
Notifications.to the state (s) and counties must be made within 15 minutes whenever there is a change in the emergency classification.
2.3 Announce the change in the emergency class to all CMC personnel and to the Emergency Coordinator at the TSC.
3.0 SUBSEQUENT ACTIONS 3.1 To escalate, de-escalate or close out the Emergency, compare plant conditions to the Emergency Action Levels of Enclosure 4.1.
Any decision to de-escalate from a General Emergency condition must be discussed with the senior NRC and State representatives.
Notify state (s), counties, and NRC by verbal summary of any reduction or termination in the emergency class followed by a written summary within eight (8) hours.
4.0 ENCLOSURES 4.1 Emergency Event List for Emergency Classes Event No.
Page(s) 4.1.1 Primary Coolant Leak 1-3 4.1.2 Fuel Damage 4-5 4.1.3 Steam System Failure 6-7
'I 4.1.4 High Radiation / Radiological Effluents 8-9 4.1.5 Loss of Shutdown Function 10-13 4.1.6 Loss of Power 14-15 4.1.7 Fires and Security Actions 16-17 I
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4.1.8 Spent Fuel Damage-18-19 4;1.9 Natural Disasters and Other Hazards 20-22 4.1.10.
Other Abnormal Plant Conditions 23-27 4
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' CATAWBA NUCli STATICIE.
CMIP-10 EMERGBOCY ACL set IEVELS Encibsure 4.1 page 1 of 27 EVENT B 4.1.1 PRIMARY COOLAIrr LEAK M&f1FICATICIE OF UNUSUAL EVENT AIERT SITE AREA MERGMCCY GEB8ERAL IDEGIG50CY 1.
MC System Icakage.
1.
NC System leakage 1.
NC System leakage 1.
Any IACA with failure greater than Tech Spec greater than 50 gym greater than available of ECCS.
limits in Modes 1-4.
in flodes 1-4.
ECCS capacity.
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o IDCA with f ailure of o Greater than 1 gpm o NC System leakage o S/I actuated or both trains of ECCS-unidentified NC System greater than 50 gpm required injection leakage in Modes 1-4 in Modes 1-4 W
M AND AND Existing NV, NI'and ND NC System subcooling Load reduction or plant NC System subcooling flow cannot maintain cannot be maintained cooldown initiated in greater than O'F NC System subcooling greater than O'F.
accordance with Tech greater than 0*F.
Spec 3.4.6.2.
g Leak cannot be o IDCA with failure of isolated within (Continued)
'both trains of ECCS o Greater than 10 gpm 15 minutes.
recirculation capability identified NC System leakage in Modes 1-4
_AIED 2.
S/G tube leak with NC System subcooling loss of offsite power.
cannot be maintained Load reduction or plant greater than 0*F.
cooldown initiated in accordance with Tech o S/G tube leak greater spec 3.4.6.2.
than 10 gpm o thCA O
AIED o Greater than 500 gpd NC System subcooling
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primary to secondary greater than 0*F Plant conditions require leakage in any S/G entry into in Modes 1-4 g
EP/1(21/A/5000/2B1 Inadequate Core Cooling.
AND Both A and B main bus lines' Ix>ad reduction or plant de-energized.
cooldown initiated in (Continued) accordance with Tech Spec 3.4.6.2.
(Continued)
(Continued) e v
j" CATAWBA NUCLEAn STATICOs CM I P-10.- *i.'
EDERGB8CY ACTION 12VELS
.Esablosure 4.1-Page 2 of 27 EVENT I 4.1.1 PRIMARY COOLA8FF LEAft (continued)
Is0TIFICATION OF-SITE AREA EBERGBBCY GasERAL BERGBICY UNUSUAL EVENT ALERT o Greater than 1 gpen 3.
S/G tube leak with an 2.
S/G tube lea 8t greater 2
IACA with initially total primary to unisolable steaum line than 50 grus with a successful ECCS followed secondary leakage in break outside steam line break.
by failure of ECCS heat sink and failure of all S/Gs in Modes 1-4 Containment.
Containment heat removal.
o S/G tube leak greater M
o Known S/G tube leak
.than 50 gym o IDCA Load reduction or plant greater than 10 gpm cooldown initiated in
-AffD AseD accordance with Tech AND Spec 3.4.6.2.
' Steam line break Unisolable steam line inside containment Ioss of recirculation break outside on the ruptured S/G heat sink Containment
_AIOD
_ASED o Any NC System pressure boundary leakage in g
Valid indication on Loss of Containment Modes 1-4 NC System subcooling E8EF-53A or 53B spray heat sink.
M greater than 0*F.
reading greater than or equal to 290 R/hr.
Load reduction or plant esD cooldown initiated in accordance with Tech o Unisolable steam line Spec 3.4.6.2.
break outside o S/G tube leak greater Containment than 50 gpm M
M o Greater than 40 gpm controlled NC system Field monitoring teams Unisolable steam line leakage at 2235 psig detect activity at the break outside in Modes 1-4 Protected Area fense at Containment on the-greater than or equal ruptured S/G.
M to 2 mr/hr whole body.
Load reduction or. plant cooldown initiated in
.E accordance with Tech M
Spec 3.4.6.2.
(Continued)
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CtHP-10 CATAt8BA 98UCLEAR STATION
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EHERGISBCY ACTICIE LEVELS.1 Page 4 of 27 EVDET 9 4.1.2 FUEL DAftAGE MCyflFICATIODE OF UNUSUAL EVENT ALERT SITE AREA EIERGDOCY GDfERAL IWWIIGW8CY 1.
NC System activity greater 1.
Severe loss of fuel 1.
Degraded core with 1.
Loss of 2 of 3 fission than Tech Spec limits in cladding.
possible loss of product barriers with coolable geometry.
potential for loss of stodes 1-5.
the 3rd barrier. %e 3 barriers are the o valid indication on o Greater than 1.0 any Reactor Building o Plant conditions fuel cladding,Bec microcurie per gram dose EMF reading greater require entry into Systesa and Containment.
equivalent I-131 for more than or equal to EP/1(2)/A/5000/2B2, than 48 continuous hours 1000 times background Degraded Core Cooling.
per Chemistry analysis in value.
se(FrE: To classify at Modes 1-5 this level, you o Containment hydrogen unest satisfy at o valid indication on concentration greater least one condition g
Load reduction or plant EMF-48 reading greater than or equal to 1.0%
frame 2 of the 3 categories listed cooldown initiated in than or equal to 1000 accordance with Tech times background value.
AND (A, B,'C) and have
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Spec 3.4.8.
Hydrogen concentration satisfying at least.
increasing at a rate of one condition from o Chemistry analysis greater than or equal the resnaining o Dose equivalent I-131 indicates that primary to 0.1% per hour.
category.
in excess of Tech Spec coolant dose equivalent Figure 3.4-1 per I-131 concentration is Chemistry analysis in greater than or equal to Modes 1-5 300 microcuries per on1.
o valid *ndication on A. Loss of fuel cladding EMF-53A or 538 reading barrier.
greater than or equal to 290 R/hr.
o Chemistry analysis Load reduction or plant o Chemistry analysis indicates greater than cooldown initiated in indicates greater or equal to 20% total accordance with Tech than or equal to fuel clad failure, Spec 3.4.8.
5% total fuel clad stD failures.
o valid indication on (Continued)
EMF-53A or 53B reading o Chemistry analysis greater than or equal indicates an increase to 1100 R/hr.
of greater than 11 fuel failures within 30 minutes.
(Continued)
CATAWBA NUCIEAsa STATIoft CylP210
- ~t*f' EDIERGEOCY ACTIGit 12VELS Enclostare 4.1 Page 5 of 27 EVDFT B 4.1.2 FUEL DAfthGE (continued)
ISOTIFICATIoft OF UNUSUAL EVDfr ALERT SITE AREA EDE3tGEBOCY GEBOERAL B ERIGNOCY o Plant conditions o specific activity _
require entry into greater than 100/E EP/l(23/A/5000/281, microcuries per Inadequate Core gram per Chemistry Cooling.
analysis in Modes 1-5' M
B.
Loss of DOC Systese Load reduction or plant barrier.
cooldown initiated in accordance with Tech Spec 3.4.8.
o MC System leakage greater than 50 gpm.
M C. I4>ss of Containement barrier.
o Incomplete Containment integrity.
o Known Containment leakage in excess of Tech Specs.
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o Containsnent pressure greater than or equal
-to 60 psig.
o Containment hydrogen concentration greater than or equal to 9%.
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9 CidiP-10 CATAWBA NUCLEAR STATIose:
L EIEMG50CY ACTICBI 12VELS.1 Page 6 of 27 EVEBrr 8 4'.1.~ 3 STEast SYSTEft FAILURE l
te(yrIFICATIOi4 OF UNUSUAL EVENT ALERT SITE AREA EBEItGUICY GEBSERAL SERGEBICY 1.
Steam line break which 1.
Unisolable steam line 1.
Steam line break with a N/A results in rapid break outside:
S/G tube leak greater depressurization of Contairusent with a than 50 M.
the secondary side.
S/G tube leak.
o Steam line break o steam line o Unisolable steam inside containment depressurization line break outside on the ruptured resulting in Safety Containment S/G Injection or Main Steam Isolation.
_AISD g
Known S/G tube leak S/G tube leak greater greater than 10 gpm' than 50 gpm END M
M' MC System subcooling Valid indication on greater than O'F.
EB9F-53A or 53B l
reading greater than or equal to 290 R/hr.
o Unisolable steam line break outside Containment o Unisolz.ble steam line break cutside
~AIOD Contain. ment on the ruptured S/G Field monitoring teams detect activity at the g
Protected Area fence at greater than or S/G tube leak greater equal to 2 mr/hr than 50 gpm.
whole body.
E (Continued)
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CATAtSA ISUCI2AR STATICIe CMIP-10 ENERGEBOCY ACTION 12VELS.1
.Page 7 of 27 EVEBtr 0 4.1.3 STEAft SYSTEN FAILURE (Continised) 30GTIFICATICI6 OF
-UNUSUA1 EVEBIT ALERT SITE AREA EDERGEleCY GENERAL E N 2.
Steam line break with failure of ECCS or Itain Steam Isolation.
O Steam line depressurization resulting in Safety Injection signal ~
W Failure of both trains of ECCS injection.
o Steam line depressurization resulting in Main Steam Isolation signal M
The failure of two or more MSIVs to close results in the depressurization of two or more S/Gs.
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CMIP-10 CATAtfBA 95UCLEAD STATI0s:
EIENGENCY ACT 12VELS
-Enclosure 4.1 Patse 4 of.*27 ' -
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EVENT 3 4.1.4 HIGER RADI ATI005/RADIOt4GICAL EFFLUENTS NOTIFICATIoss OF UNUSUAL EVENT ALERT SITE AREA EDERGENCY GE55ERAL IDERIGEBOCY 1.
Gaseous or liquid 1.
High radiation levels 1.
Accidental releases 1.
Act; atal releases of gases.
radiological cffluents or high airborne of gases.
exceed Tech Spec limits.
contamination.
o valid indication on E3EF-361, o valid indication on reading greater than or o Gaseous radiological o valid indication on EMF-36L reading greater equal to 7.6 E5 cym.
effluents exceed Tech any area EMF reading than or equal 3.8 E4 Spec limits as greater than or cpm.
(See NOTE) determined by equal to 1000 times o Valid indication on EMF-36H Radiation Protection background value.
reading greater than or calculations.
o valid indication on equal to 3.5 E2 cym.
. EMF-37 has increased by o valid indication on greater than or equal o valid indication on EMF-41 reading greater to 2.4 E3 cpm over any EMF-58 reading greater than or equal to 1000 1 minute period. Refer o Valid indication on EMF-37 than or equal to 50 times background value.
to computer points P0129, has increased by greater times the TRIP 2 P0130, P0131, P1822.
than or equal to 4.8 E4 setpoint.
(See NOTE) cpm over any 1 minute period. Refer to 2.
Gaseous or liquid
-computer points P0129, radiological effluents P0130, P0131, P1822.
o Valid TRIP 2 alarm on exceed 10 times hch o Dose assessment team EMF-49L or EMF-57 Spec limits.
calculations project a dose rate at the Site Boundary of o Dose assessment team o valid indication on greater than or equal calculations or field Failure of the release any of the following to 50 mr/hr whole monitoring team path to automatically effluent monitors body or 250 mr/hr measurements result in a isolate.
reading greater than thyroid.
2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> integrated dose or equal to 10 times projection at the Site the TRIP 2 setpoint:
Boundary of greater than or equal to I rem whole o Liquid radiological o EMF-35L o Field monitoring team body or 5 rem thyroid.
effluents exceed Tech o EMF-36L measurements determine Spec limits as o EMF-37.
the dose rate at tl'e determined by Site Boundary is greater Radiation Protection than or equal to ID8D calculations.
50 mr/hr whole body (Continued) or 250 mr/hr thyroid.
M M
teorE: "Ihis ENF setpoint is calculated based on Stability Class "C" meteorology, and a Unit Vent flowrate of 1.9 E5 cfm.
Calculations by the dose assessment team use actual meteorology and Unit Vent flowrate. *1heref ore, this Egr setpoint should not be used if dose assessment team calculations are available.
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'CMIP-10 EDEWGWICY ACTICII IRVELS Encloseste 4.1 ~
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Page 9 of 27
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EVElff 9 4.1.4 HIGH RADIATI(MI/RADIGIA)GICAL EFFLUEBrTS (continesed)
N MIFICATICII OF UlftfSUAL EVENT AIERT
' SITE AREA EIGERGGICY GWEERAL IDERNGBBCY o valid indication on l
EMF-58 reading greatet
-than or equal to 500 times the TRIP 2 setpoint.
o Valid' indication on EMF-49L or EMF-57 reading greater-than or equal to 10 times the TRIP 2 setpoint Failure of the release-
. path to automatically isolate.
o Radiological effluents' exceed.10 times Tech Spec limits as determined by Radiation Protection calculations.
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-N 33 m-CATAMBA 18UCI2 Alt STATIose CMTP-10 EBEltGIBOCY ACTION 12VELS.1 2
Fage 19 of 27 EVE 3rr 9 4.1.5 IDSS OF SHLN FUNCTICIOS
'NorrIFICATION OF UNUSUAL EVENF ALEftT SITE AftEA E9EBIGNOCY GEBIEItAL IBWIIGNICY N/A 1.
Complete loss of any 1.
Complete Aoss of any
. 1.
Transiest initiated try function needed to function aceded for loss of CF and GI Systems maintain core cooling
. Not Shutdown conditions followed try failure of in teodes 5 and 6.
in peodes 1-4.
' heat removal capability for an 4atended period in stodes 1-4.
o Failure of heat sink o Failure of heat sink causes loss of Cold results in the Shutdown conditions inability to e Loss of CM/CF in Modes 5 and 6 maintain Hot Shutdown fecesater flow (Mode 4)-
capabilit/ in
- _AIED Modes 1-4.
ASED
'HC System subcooling
_AIED cannot be maintained MC System subcooling greater than O'F.
cannot be maintained CA flow cannot be greater than 0*F.
established within 30 minutes (Continued)
Age o Inability to feed S/Gs
~
from any source in NC System feed and Modes 1-3 bleed flow cannot be established or
,Ag maintained.
NC System subcooling cannot be maintained greater than 0*F.
(Continued)
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EBERGESCY ACTA.. 12VELS teclosure 4.15
-Paise 11.of 27 EVENT B 4.1.5 IDSS OF SIRFItalRE FINICTICBtS (continued).
N0rrIFICATIott OF:
UNUSUAL EVEfff ALERT SITE AREA EBERGENCY GSOERAL IBERGEBOCY 2.
Transient with failure 2.
Transient requiring..
2.
Transient requiring a Rm of the Reactor-operation of shutdown trip with failure to trip Protection Systesa to systems with failure to and failure of core cooling.
aestoumatically initiate trip (power generation and complete a Rx trip continues).
which brings the-o Transient with failure of--
Reactor subcritical the Reactor Protection
( ADtS).
o Transient with failure Systesa to autoumatically
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of the Reactor initiate and complete a Protection System to
.Rx trip which brings the automatically initiate Reactor suberitical ( ADfS)
Eng.
and complete a Rx trip which brings the AseD Reactor subcritical (ATWS)
Actions taken per EP/l(21/A/5000/2A1, Nuclear
_ASED Power Generation /ATwS,
. fail to bring the Reactor Controi rods cannot suberitical be manually tripped or inserted from the AMD' Control Room.
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Plant conditions require entry into EP/1(2)/A/5000/2B2, (Continued)
Degraded Core Cooling.
(Continued)
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- TAT!aN CM I P-10 --
FJEERGBOCY-ACTls LEVELS Emplosure'4.1 Pak 12 of:27 EVEstr 8 4.1.5 InsS OF saarrnoems FUNCTroteS (continued)
.NOTIFICATIolf OF.
UNUSUAL EVENT ALERT SITE AREA EDE5IGEISCY GENERAL IBERGEOCY
. 3.'
Inability to maintain 3.
Imss of heat sink with Cold Shutdown with subsequent core uncovery loss of peactor Vessel in stodes 5 and 6.
Coolant Inventory in stodes 5 and 6.
o Failure of heat sink
~causes loss of Cold" o Failure of heat sink Shutdown conditions causes loss of Cold in stodes 5 and 6 Shutdown conditions in Modes 5 end 6
_Alep AIOD lower Range RVLIS level indicates core is NC System level less uncovered.
than 111 and continues to decrease after initiation of NC
. System make-up.
o Failure of heat sink j
causes loss of Cold Shutdown conditions.
[
in Modes 5 and.6 l
o Failure of heat sink causes loss of Cold
-AIUD Shutdown conditions i
in Modes 5 and 6 Core Exit T/Cs indicate superheat at the core l
_AIED exit.
Lower Range RVLIS level decreasing after initiation of (Continued)
NC System make-up.
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'EndIosure ".1" 4
Page 13.of 27 EVErr 0 4.1.5 IDSS OF SMUTDONN FUNCTIONS (continued)
MCFflFICATION OF UNUSUAL EVErr ALERT SITE AREA EDERGENCY GENERAL EBERGENCY o Failure of heat sink o' Failure of heat sink causes loss'of Cold
'causes loss of Cold Shutdown conditions Shutdown conditions in Modes 5 and 6 in Modes 5 and 6 AND AND Reliable NC System NC System level below level indication bottom range of unavailable available level indicators M
Core exit.T/Cs or
~AND AP/l(21/A/5500/19, Available NC System Loss of ND, Enclosure make-up flow'is less-3, indicate boiling than applicable in core value given in AP/1(21/A/5500/19, M
Loss of MD,.
Available MC System make-up flow is less
.g than applicable value given in
' Emergency Coordinator AP/l(21/A/5500/19, judgement that core Loss of ND, uncovery is inuminent..
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4 CATAWBA ISUCLEW STATICOI CMIP-10.
EBEstGIBICY AC 4 LEVELS -.1 Ppge.14 of;27',
EVEIFF 5 4.1.6 14S5 OF POWER L
300FIFICATION OF UIGUSUAL EVE 3rr ALERT SI'rE AREA EBEDIGENCY GENEstAL EBBBIGNICY
-1.
loss of offsite power in 1.
. Loss of.offsitu power 1.
' Loss of offsite power and.
peodes 1-6.
and loss of all onsite' and loss of all onsite loss of all'onsite AC AC powar for greater AC power for greater power with total loss of' than 1 minute but less than 15 minutes in S/G feed <* P ility in:
h o Both A and B main bus than or equal to 15 98 odes 1-4.
900 des 1-4.
lines de-energized in minutes in stodes 1-4.
riodes 1-6.
o Both 4160V Essential
- o Both 4160V Essential o Both 4160V Essential Buses are de-energized' Buses are de-energized
' Buses are de-energized for greater than 15 in Modes 1-4 2.
Ioss of onsite AC power for greater than 1 minutes in Modes 1-4.
ABID In Modes 1-4.
minute L.tt less than or equal to 15 minutes loss of CM/CF feedwater In Modes 1-4.
o Both D/Ss are incapable (Continued) flow capacity (for greater than 2 AleD hours) of powering the 4160V Essential Buses 2.
Ioss of offsite power in Modes 1-4.
and loss of all onsite CA Flow cannot be established within AC power for greater 30 minutes.
than 15 minutes in stodes 5 and 6.
3.
Ioss of onsite AC power in stodes 5 and 6.
o Both 4160V Essential
_E38D Buses are de-energized o Both D/Gs are incapable for greater than 15 (for greater than 8 minutes in Modes 5-hours) of powering the and 6.
4160V Essential Buses in Modes 5 and 6.
(Continued)
EN_O
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~ Enclosure 4.1.
J.
EBIERGeeCY ACTICNE LEVELS Page 15 of 27-EVBrF $ 4.1.6 T m 9 OF POWEN HCTIFICATION OF UtfUSUAL EVEBfT ALERT SITE AREA EFE5tGEBOCY GEB8ERAL NERGIBOCY 3.
Loss of all vital.DC 2.
Ioss of all vital DC power for greater than.
power for greater than 1 minute but less than 15 minutes in geodes 1-4..
or equal to 15 minutes in stodes 1-4.
o Vital DC Buses EDA, EDO, EDE and EDF o vital DC Buses EDA, de-energized for EDD, EDE and EDF
.. greater than 15 de-energized for
. minutes in Modes greater than 1 minute 1-4.
but less than or
' equal to 15 minutes in Modes 1-4.
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4.
Loss of all vital DC-power for greater than 15 minutes in seodes 5 and 6.
o vital DC Buses EDA, EDD, EDE and EDF de-energized for greater than 15 minutes in Modes 5 and 6.
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'CMIP-10.
l-23ERGENCY ACT.
IAVEI.,-
Enclosure *4,1
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l Pdge_16 of'27 EVElfr 8 4.1.7 FIRES AND SECURITY ACTIONS NOTIFICATION OF UNUSUAL EVENF ALERT SITE AREA IDERGENCY GENERAL EBERGENCY l.
Fire within the Plant 1.
Fires potentially 1.
Fire compromising the
'l'..Any major fire which' (see NUTE) that takes affecting safety functions of shutdown could cause massive more than 10 minuter.
systems needed for.
systems.
damage to the Unit.
to extinguish.
current operating mode.
o Observation of a fire o Fire requiring that defeats both evacuation of the 2.
Security threat.
o Observation of a trains (or the single Control Room fire that could operable train) of adversely affect safety systems needed
_AND o Discovery of a bomb safety systems-for current operating within the Site Boundary.
needed for current mode.
Control of shutdown operating mode.
systems cannot be established from any plant location.
O Civil disturbance o Fire requiring (hostile).
o Fire requiring evacuation of the evacuation cf the Control Room Control Room (Continued)
AND o Intrusion / attempted AND intrusion (Protected Control of shutdown Area).
Control of shutdown systems cannot be systems has been established from the established or is Auxiliary Shutdown in the process of Panels o Hostage situation /.
being established extortion.
from the Auxiliary
_AND Shutdown Panels.
Control of shutdown-systems has been o Security threat as.
(Continued) the process of being established or in the determined by Shift Supervisor / Emergency established from the Coordinator and Standby Shutdown Security.
Facility.
END (Coatinued) pare: Plant is defined as Auxiliary Building, Turbine Building,. Service Building, Reactor Building, Diesel Generator Rooms, Doghouses, Spent Fuel Building, Standby Shutdown Facility, RN Pumphouse and Nonitor Tank Building.
n
m.m o
. 4ie- :
CMIP-10 CATass9a nuclJ STAtless NapCWBCY AC1..412TELS.1 -
Piege 17 of 27 Evert g 4.1.7 FIstBS Assp SBcWUtlTY ACTicses (continesed)
BearIFICATlost OF UleUSUAL EVEBF1' ALEltT
- SITE AftEA BEIBGSOCy GBIERAL N 2.
Ongoing security 2.
lemurinent loss of 2.
Less of perysical control commpromise.
ptrysical control of of the Plant. (See SJEF.T 1) the Plant.
(See says 1) o Adversaries casumandeer o Ptrysical attack on the an area of the Plant Plant (see segrE 1) has but do not control any o Physical attack on resulted la occupation vital areas.
the Plant (see seUTE 1) of the CotArol Poom and-(See segrES I and 2) which leads to the Auxiliary shutdown imuninent occupancy Panels.
of the Control Room and Auxiliary o Discovery of a breached Shutdown Panels.
barrier caused by
~ asp intrusion or sabotage in a vital area.
(See searE 2) o Disesvery of a bomb withi.,a vital area.
(See learE 2) o Discovery of a bomb within the Protected Area.
_ BID o Ongoing security cosnproseise as determined by Emergency Coordinator and Security.
_END Plant is defined as Auxiliary Building,1%Kbine Buildisag, Service Buildises, Eleactor Duildiseg, Diesel Generator leprE: 1)
Moons, Dogleouses, Spent resel Building, Stanesy Shutdonne Facility, NE PenupOtoesse and SOnnitor Tank Buildiseq.
- 2) For classificatiosi pearposes, casesider the NE Penupleouse as a vital area.
CArmiseA essCI.r STAT 10ss CMIP-10 ENERGWBCY AC ' 4IRTELS Esclosure 4.1,
Page 18 of'27
+
EVWrr 9 4.1.8 SPer? FUEL DeWWhGE scorrIFICATICBI OF UNUSUAL EVENT Al25tT SITE AREA N GWWWRAL IEWIDGWBCY l
N/A 1.
Damege to spent fuel 1.
Stojor demoge to spent N/A with release of fuel with release of radioactivity.
radioactivity.
l CIEFTAI M CGrFAIIWWrr o *Ialid M IP 2 alarm o valid DIP 2 alatta +xi
]
on IEFIF-17 (2WIF-2) 1Escr-17 (2EBEF-2)
(Reactor Bldg Refuel (Reactor Bldg Refuel Bridge)
Bridge)
Asso asso valid indication valid indication on on any of the Eser-36L reading greater following effluent than or equal to 3.8 E4 monitors reading egun.
(See ISOTE) greater than or equal to 10 times the M IP 2 setpoint:
o valid TRIP 2 alarm o E34F-35L on IENT-17 (2EHF-2) o Der-36L (Reactor Bldq Refuel o EMF-37.
Bridge)
W_.
4 j
(Continued)
Dose assessment team l
calculations project a dose rate at the Site Boundary of greater than or equal i
to 50 mr/hr whole body or 250 mr/hr thyroid.
(Centinued)
NOPIT: His EBF setpoint is calc;nlated bened ces Stability Class "G" meteorology and a Uusit Vent flowrate of 1.9 E5 cie.
t Calculations by the dose assessment team use actual meteorology and unit veset flowrote. Derefore, this WIF setroint should not be used it dose asx--
..t team calculations are,available.
O e
cAvaneA esucLeAR STATICES GMIP-10 WWacancT AcTross IAVELS anclosure 4.1 Page 19 of 27 EVErr G 4.1.8 SFWrf FUEL D*JERGE (centineed) 980TIFICATIGE OF ifgIUSUAL EVWrr A12RT SITE AftEA N GBIERAL IBERGWBCY SFWrr FUEL FOOL SFWff FUEL 700t.
o Valid 71tlP 2 alarm o valid TRIF 2 alarm on IEMF-15 (2 EMF-4) on IEMF-15 12 EMF-4)
(Spent Fuel Bldg (Spent Fuel Bldq Refuel Bridge)
Refuel Bridge)
E E
Valid indication on valid indication on any of the following EMF-36L reading greater effluent monitors than or equal to 3.8 E4 reading greater than cym.
(See leUTE) or equal to 10 times the TRIF 2 setpoint:
o EMF-35L o Valid TRIF 2 alarm on o EMF-36L lEMF-15 (2 EMF-4) o EMF-37.
(Spent Fuel Bldg Refuel Bridge)
Asse WED
~
Dose assessment team i
calculations project a dose rate at the Site Boundary of greater than or equal to 50 mr/hr whole body or 250 ar/hr thyroid.
E se&rE: This IBUF setpoint is calculated based on Stability Class *G* meteorolosyy and a Unit vent flourrate of 1.9 E5 cie.
Calculations by the done asp-
..t team use actual meteorology and Unit Vent flanerate. Therefore, this WF setpoint should noj be used if dose assessment team calculations are,available.
...--..s
e
'o CATAAfBA IIUCLEAft STATICII
' CMI 10 IBERGWICY ACTICIE IEFELS.3 Page 29 of 27 EVWrr B 4.1.9 ISATUUtAL DISASTERS ABID 0115R MAZAftDS 2
teurIFICATICIE OF UIEtfSUAL EVEBrr ALERT SITE AftEA IBERGEBBCY GEBIBRAL IBERGWICT I
1.
Earthquake felt in plant 1.
Eartheguake igreater 1.
Earthapesake greater these 1.
Asvy mejor leeternal or i
and detected by seisusic than OPE level.
SSE level.
esternel event (e.g.
monitoring instrumments.
aircraft impact, eertDeepushes emelbstantia11y j
o valid *0BE EXCEEDED" o Earthquake intensity beyond desigue basis) w0nicts o valid " Peak Shock annunciator alarm greater than C.15g consid e--
mesolve desege Annunciator" alarm.
(IAD-4, B-8).
Horizontal or 0.10g to the tpnit.
Vertical (SSE level).
o valid alarm on " Strong (Continued)
__ IBID 790 tion Accelerograph."
2.
Imer water level.
o Lake level less than 2.
Iow water level.
or equal to 557.5 f t ASED o Lake level less than or equel to 557.5 ft SetSwP is not available.
_A88D SteSWP is available.
(Continesed) 4 4
(Contineed) a
+
~ww g
-.xe o
s
-ee
+s
__.,_,..,,_x amu a
. o.-
CATAnseA saucupo STATIoss CMIP-10 IBEERGEleCY AC'
' 12VELS Enclosurc 4.1 Page*21 of'27*
EVEstr 9 4.1.9 IEAftfRAL DISASTERS Age m myaanc (continued)
IstyrIFICATIOgg OF UIEUSUAL EVEBIT ALERT SITE ARBA WERGWICY GEBEERAL M 3.
Any tornado / severe 2.
Damage from tornado, 3.
Demsge fram tornado, weather within the Site severe weather, alssile severe weather, missile, Boundary.
explosion, aircraft esplosion, aircraft crash, crash or train or train derailment derailment causing a causing a loss of any o Tornado / severe weather loss of any function function needed for flot onsite needed for Cold Stoutd== conditions in.
Shutdown conditions teodes 1-4.
_AssD in stodes 5 and 6.
Physica1 damage observed o Damage to plant equipuent to equipment / structures o Damage to plant results in the inability within the Site Boundary equipment causing to establish or maintain needed for plant operation.
the inability to not Shutdown conditions maintain Cold in h s 1-4 Shutdown conditions in 190 des 5 and 6 ABID 4.
Aircraft crash.
-AIOD NC System subcooling cannot be maintainM o Aircraft crash within MC System subcooling greater than O'F.
the Site Boundary.
cannot be maintained greater than 0*F..
(Centinued)
IContinued)
(contineedI
(
i e
4 l
O
~ O CATAWBA IEUCI2mst STATIcer '
~ ChlP'-10 * **
EBWIIGNICY ACTIcal 12VELS.1 Fage 22 of 27 EVENT $ 4.1.9 IWATURAL DISASTERS Age e maanc (contineed)
ISUFIFICATICIE OF UNUSUAL EVWrr A12 BIT
~
SITF. AftEA WERGWICY GWIERAL N 5.
Train derailment onsite.
3.
Release of toxic or 4.
IIelease of toalc or flassmable gas in flasumable gas in pendes stodes 5 and 6.
1-4.
~
o Train derailment resulting in physica!
dannage to equipment /
o Entry of an o Entry of uncontrolled structures within the uncontrolled toxic toxic or flasmaable gas Site Boundary needed or flaammable gas into any plant area for plant operation.
into any plant area which prevents the which prevents the operation of systems operation of needed to establish systems needed or maintain Not 6.
Explosion within the Site to maintain Cold Shutdown conditions Boundary.
Shutdown conditions in stodes 1-4 in stodes 5 and 6 AIED o Explosion within the Site M
Boundary resulting in IOC system subcooling physical damage to NC System subcooling cannot be maintained equipment / structures cannot be maintained greater than O'F.
needed for plant operation greater than O'F.
or injuries to personnel.
E 7.
Release of toxic or
-asD fl h le gases.
O Release of toxic or flansnable gas resulting in personnel injury or evacuation within the protected Area.
_END 4
.r e,
g y
.usw.-,
e
~- _
.m__.,_m_.,,_.
am.
m.m m_. _ _, __._-,___
mm. m..m
o cayangen geger esWt STATIOut CMIP o BWBGWBCy J
'.El LEVELS.1 Page 23.of.27 EVEIET E 4.1.19 m - PLAlry CWWITIGIS k
geUTIFICATIost OF UI5 USUAL EVBrr ALENT SITE AkEA WWIIGGOCy GWEERAL N 1.
ECC's initiated.
1.
Evacuation of Control I.
Evacuation of Control 1.
Evacuation of Control Itoems.
Room.
Room.
o valid S/I signal o Evacuation of the Control verified by redundant o Evacuation of the o Evacuation of the Room required indications Control Room required Control Rooms required M
M't!
!ED MEE]
Control of shutdown systems ECCS injection into Control of shutdown Control of shutdown cannot be established fross the vessel has systems has been systems cannot be any plant location.
occurred.
established or is established fross in the process of the Auxiliary Shutdown b=ing established Panels from the Atix111ary 2.
Other tenit conditions esist 2.
Abnormal IOC Systeem Shutdown Panels.
_AIED that in the judgessent of time parasmeters.
amergency coordinator create Control of shutdown the possibility of a release systems has been of large asmounts of o Tech Spec figure 2.1-1 2.
peost or all annunciator established or is radioectivity in a short limits exceeded in capability lost in in the process of period of time.
Modes 1 and 2.
Beodes 1-4.
being established l
fross the Standby Shutdown Facility.
4 o Ioss of 50% or.more EIED o NC System pressure has of the Control Room exceeded 2735 psig in annunciators in Moses Modes 1-5.
1-4 for greater thas.
2.
Other Unit conditions 15 minutes.
esist that in the judgemeent of the h rgency coordinator (Continued) warrant declaration 1
3.
Other Unit conditions of Site Area heergency.
]
exist that in the jendgemeent of the muergency Coordinator warrant entry into
_M W the Alert classification.
o
~ ~,
m
o.
o:
O cATea m a seuCr *ma STnT10ss CMIP-13 musteemeCr i. oss Laver.s unclosure c.1 Everr 5 4.1.10 Ortmut ammnment. PtJerr CoseDITIouts (continued)
DeGrlFICATIoIE OF UBfUSUAL EVWrr ALERT SITE AREA WWIIGWBCY 8'8MmW WWIIGWBCY 3.
Loss of containment integrity requiring shutdown try Tech Specs in geodes 1-4.
o Any autosnatic Containment isolation valve which is open, inoperable and unisolable in Modes 1-4 ABID._
Load reduction or plant cooldown initiated in accordance with Tech Specs 3.6.1.1 and 3.6.3.
o Both airlock doors of a single airlock are inoperable in Modes 1-4
_A88D Load reduction or plant cooldown initiated in accordance with Tech Specs 3.6.1.1 and 3.6.1.3.
l o Any Containsment penetration fails leak test per Tech Spec in Modes 1-4 a
W Load reduction or plant cooldown initiated in accordance with Tech Specs 3.6.1.1 and 3.6.1.2.
(Continued)
S
'.N t;r.. '*
e..
CATResBA II4pCLEAst STATICES -
CMIP-10
-o r WERGEICT F
'(28 IANLS Itseclosure 4.1 g
- Page 25 of,27 EVIBff 9 4.1.10 (mWR PIJWrr CtNeITICIts (contimesed)
~
k leUTIFICATICIE OF
~
UOIUSUAL EM ALEBtT SITE AftEA WWIIGWBCT GBOWtAL WWIIGWBCT 4.
Ioss of ESF or Fire Protection Systema ftenction.
o Both trains of an ESF function or ESF
-actuation system found inoperable (if caused by 11re, see Event 94.1.7, under Alert classification)
M89 Load reduction or plant cooldown initiated in accordance with Tech Specs.
o Loss of all main Fire Protection System pumps.
1 (Continued) 4 n.r...
c.-
t e
m
.m mm m
.m
____,_m._. _
- cy cmTanen sBe a svarnCes CMiP-10 ISERIGGICY A 1055 LEVELS.t
- Page 26 of 27 EvBrf G 4.1.10 UrtWR namnemar. PfJWF COOWITICIES (continued) getyrIr1CATICBE OF UHtfSUnL EVEBfT ALEBt?
SITE AftEA WERGWBCY
-u WWIIGWBCY 5.
significant loss of assessment or communication capability.-
o Loss of all onsite meteorological instrumentation
_AfsD a
Inability to contact the National Weather Service for backup source of meteorological data.
i o Loss of all radio and telephone comumunication capability with all offsite agencies.
o Loss of 50% or more of the Control Room annunciators in Modes 5 and 6 for greater than 15 minutes.
(Continued) l l
l H.-i.--m.._.,. _, - _ -. ---'i -
w
"'" ' - ' ^ - --"-
i o-
- E O,
C Arau eA sitr. wt statices CMIP-lO N.
scar IJtVELs
- encloedre't.1
'Page 27 of 27 EYWrr S 4.1.Ig m asunummar. pgANF (XMWfTI(MIS (coatimuedi N(FrIFICATIN (X.
UBOUSUAL EVWFF ALERT SITE A3 TEA BERGWICY GWIWIAL WWIIGGICY 6.
Transportation of a contaminated.. Injured individual from the site to an offsite medical facility.
o Injured contaminated individual is transported offsite with a j
contamination level of greateg than 5000 dpm/
100 cm. (See 300TE) o Internal contamination requiring medical assessment / treatment.
O External exposure requiring medical assessment / treatment.
4 7.
Other Unit conditions exist that in the judgement of the Shitt Supervisor /amergency Coordinator warrant increased awareness of local authorities.
4
.D._0_
te0FE: 5000 dsum/100 cm corresponds to 150 ciem (above backgroundt beta-gamme as measured with a thin windeer pancake e detector at one half inch frome the bety surface.
i b
1
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..