ML20072S052

Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 9 to CMIP-11, Classification of Emergency for McGuire Nuclear Station & Rev 11 to CMIP-12, Classification of Emergency for Oconee Nuclear Station

ML20072S052
Person / Time
Site:	Oconee, Mcguire, Catawba, McGuire, Fort Saint Vrain
Issue date:	03/15/1991
From:	Harris R DUKE POWER CO.
To:
Shared Package
ML16148A983	List: ML16148A982 ML20072S052
References
PROC-910315, NUDOCS 9104090322
Download: ML20072S052 (49)

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DUKE POWER COMPANY CRISIS MANAGEMENT IMPLEMENTING PROCEDURES March 15, 1991 9104090322 910327 PDR ADOCK 05000269 F

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TABLE OF CONTENTS Volume 2 Tak Procedure.Descrintion CMIP-8 Oconee Crisir. Phone Directory (Rev. 29)

CMIP-9 McGuire/ Catawba Crisis Phone Directory (Rev. 37)

CMIP-10 Emergency Classification - Catawba (Rev. 3)

CMIP-11 Emergency Classification - McGuire (Rev. 9)

CMIP-12 Emergency Classification - Oconee (Rev. 11)

CMIP-13 Notifications to States and Counties from the Crisis Management Center (Rev. 22)

CMIP-14 Crisis Management Data Transmittal dystem Access for Offsite Agencies - (Rev. 3)

CMIP-15 Reserved for future use CMIP-16 Crisis Management Data Transmittal System Access from the Crisis Management Center -

(Rev. 11)

CMIP-17 Reserved for future use CMIP-10 Maintaining Emergency Preparedness (Rev. 5)

CMIP-19 Communications test for McGuire/ Catawba CMC (Rev. 16)

CMIP-20 Communications Test for Oconee CMC (Rev. 10)

CMIP-21 Quarterly Inventory Equipmer

' hock (Rev. 34)

CMIP-22 Telephone Number Updates (Rev. 3)

March 15, 1991 l

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CR1515 MANAGEMENT IMPLEMENTING PROCEDURE 1

CMIP-11 I

Classification of Emergency for

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McGuire Nuclear Station 1

i Rev. 9 March 15, 1991 l

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CMIP-11 CLASSIFICATION OF EMERGENCY FOR McGUIRE NUCLEAR STATION 1.0 SYMPTOMS 1.1 Notification of Unusual Event 1.1.1 Events are in progress or have occurred woich indicate a potential 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 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 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.

1,3.2 Any releases are not expected to exceed EPA Protection 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 of(site for more than the immediate site area.

2.0 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.

. _ _ _ _ ~., _._... _ _ _

1 ;

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i 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 I

emergency class is SITE AREA EMERGENCY or GENERAL EMERGENCY, determine protective action recommendations per CMIP-1 and transmit these 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 de-escalate or close out the Emergency, compare plant conditions to the Initiating Conditions of Enclosure 4.1.

Notify state (s), counties, and NRC by verbal summary of any reduc-tion 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) j 4.1,1 -Primary Coolant Leak 1-3 4.1.2 Fuel Damage 4-5 4.1.3 Steam System Failure 6-7 4.1.4 High Radiation / Radiological Effluents 8

4.1.5 Loss of Shutdown Function 9-12 4.1.6 Loss of Power 13 4.1.7 Fires and Security Actions 14 4.1.8 Spent Fuel Damage 15 4.1.9 Natural Disasters and Other Hazar.s 16-18 d

4.1.10 Other Abnormal Plant Conditions 19-23 l-

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4.2 Engineered Safety Features b

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McGUIRE

.JLEAR STATION CMIP-11 EMERGENCY ACTION LEVELS ENCLDSURE 4.1 EVENT # 4.1.1 PRIMARY COOLANT LEAK

.PAGE I 0F 25 NOTIFICATION OF ALERT' SITr.: AREA EMERGENCY GENERAL ENERGOICY UNUSUAL EVENT-

1. Any NC system leakage

1. Any NC system leakage

1. Any NC system leakage

1. Any LOCA with failure greater than Tech Spec greater than 50 gpa in-greater than available of ECCS limits in Modes 1-4.

Modes 1-4.

ECCS capacity.

+ LOCA with failure of

+ Greater than I gpm

+ NC system leakage

+ Safety Injection both trains of ECCS unidentified NC system greater than 50 gpm activated or required injection leakage in modes 1-4 in modes 1-4 AND AND AND AND Existing NV, NI and ND NC subcooling cannot be Load reduction or plant NC subcooling greater flow cannot maintain NC maintained greater than cooldown initiated than 0 Deg. F.

subcooling greater than 0 Deg. F.

pursuant to Tech Spec 0 Deg. F.

3.4.6.2.

ANE

+ LOCA with failure of

2. S/G tube leak with an both trains of ECCS

• Greater than 10 gpm Leak cannot be isolated unisolable steam line recircuiation identified NC system within 15 minutes.

break outside containment and AND leakage

2. S/G tube Teak with indication of fuel l

AND loss of offsite power damage.

NC subcooling cannot be maintained greater than l

Load reduction or plant

+ S/G tube leak greater

+ S/G tube leak greater 0 Deg. F.

cooldown initiated than 10 gpm than 50 gpm LOCA pursuant to Tech Spec 3.4.6.2.

AND AND AND

+ Greater than 500 gpd NC subcooling greater Unisolable steam line

. tube leakage in any S/G than 0 Deg. F.

break on the affected Plant conditions in modes 1-4 S/G outside containment require entry in EP/I Both Unit related main or 2/A/5000/12.1 AND bus lines de-energized.

AND (Response to Inadequate Core Cooling)

Load reduction or plant Fuel damage as cooldown initiated determined by Event pursuant to Tech Spec Category 4.1.2.

3.4.6.2.

END

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McGUIRE JLCAR STATION CMTP-11 EMERGENCY ACTION LEVELS ENCLOSURE 4.1

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l EVENTS 4.1.1 PRIMfRY COOLANT LEAK PAGE 2 0F 25 NOTIFICATION OF ALERT SITE AREA EMERGENCY GENERAL i

UNUSUAL EVENT EMERGENCY 4

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3. S/G tube leak with an

2. LOCA with initially l'

• Greater than 1 gpm, total tube leakage in unisolable steam line successful ECCS all S/G's.

' break outside followed by failure of j

containment.

ECCS heat sink and i

AND failure of containment

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+ S/G tube leak heat removal.

l Load reduction or plant greater than 10 gpm cooldown initiated pursuant to Tech Spec AND.

+

LOCA 3.4.6.2.

NC subcooling greater AND

• Any.NC system pressure than 0 Deg F 3

l boundary leakage in loss of recirculation modes 1-4.

AND heat sink

}

AND Unisolable steam line AND i

break outside Load reduction or plant containment loss of containment l

cooldown initiated spray heat sink j

pursuant to Tech Spec

• Unisolable steam line i

3.4.6.2.

break outside contain-END r

j ment

• Greater than I gpm j

leakage from any NC' AND pressure isolation valve at 2235 psig Field monitoring teams in modes 1-4 detect activity at the protected area fence at l

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.AND greater than or. equal i

j-to 2 mrem /hr whole Load reduction or plant body.

cooldown initiated pursuant to Tech Spec-END l

4 3.4.6.2.

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7 McGUIRt ILEAR STATION CMIP-L-EMERGENCY ACTION LEVELS ENCLOSURE 4.1

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EVENT # 4.1.1 PRIMARY C00UWT LEAK PAGE 3 0F 75 NOTIFICATION OF ALERT SITE AREA EMERGENCY GOIERAL I

UNUSUAL EVENT DIERGENCY i

3

• Greater.than 40 gpm controlled NC system l

leakage at 2235 psig i

in modes 1-4.

AND

+

Load reduction or plant cooldswn initiated i

pursuant to Tech Spec-3.4.6.2.

2. Any unisolable NC system leakage greater-than 50 gpm in Modes 5 and 6.

3. Failure of an unisolable PZR PORV or safety valve to close-following a reduction of NC pressure.

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END I

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McGUIRL, CLEAR STATION CMIP-11 EMERGENCY ACTION LEVELS ENCLOSURE 4.1 EVENT # 4.1.2 FUEL DAMAGE PAGE 4 0F 25 NOTIFICATION OF

' ALERT SITE AREA EMER6ENCY GENERAL UNCSUAL EVENT-EMERGENCY

1. NC system activity-

1. Severe loss of fuel

1. Degraded core with

1. Loss of 2 of 3 fission greater than Tech Spec cladding in Modes 1-5.

possible loss of product barriers with limits in Modes 1-5.

coolable geometry.

potential for loss of

'+ Valid increase of 1000 3rd barrier.

+ Greater than 1.0 times. background set-

+ Average of five highest microcurie per gram points of any contain-core exit T/d's NOTE: Satisfy 'A' and 'B' dose equivalent I-131

. ment radiation monitor indicates greater than for greater than 48 in modes 1-5.

or equal to 700 Deg. F.

A. Loss of clad or NC hrs. continuous per.

system barrier chemistry analysis in

+ Valid increase of 1000

+ Lower Range RVLIS modes 1-5.

times background set-less than 43% level

+ Total fuel clad failure point of reactor during a LOCA event.

greater than 20% per AND coolant system process Chemistry analysis.

monitor (EMF-48) in

• RVLIS D/P setpoint Load reduction or plant modes 1-5.

at value which requires

• Containment EMF's (5!a cooldown initiated entry into Degraded or 51b) valid reading pursuant to Tech Spec

+ Chemistry analysir Core Cooling section of 1100 R/hr (1 Rem WB 3.4.8.

indicates greater than of Emergency Proce-or 5 Rem thyroid at or equal to 5% total dures.

site boundary)

+ Oose equivalent 1-131 fuel clad failure or in excess of Tech Spec increase of 1% fuel

+ Containment hydrogen

+ Plant conditions Figure 3.4-1 per failures within 30 concentration greater require entry into Chemistry analysis in minutes in modes 1-5.

than or equal to 1%

EP/1 or 2/A/5000/12.1 modes 1-5.

and increasing great-(Response to Inadequate END er than or equal to Core Cooling).

AND 0.1% per hour.

+ Cpntainment atmosphere Load reduction or plant

+ Containment EMF's (51a H concentration cooldown initiated or 51b) valid reading greater than or equal pursuant to Tech Spec of 179 R/hr.

to 9%.

3.4.8.

END

+ Containment pressure greater than or equal to 60 psig.

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McGUIRL

. CLEAR STATI0if CNIP-11 EMERGENCY ACTION LEVELS ENCLOSURE 4.1' I

EVENT # 4.1.2 FUEL DAMAGE

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i NOTIFICATION OF AERT SITE AREA EMERGENCY GENERAL l

UNUSUAL EVENT ENERGENCY

+ Specific activity _

B. Loss of or threat to greater than 100/E barrier j

microcuries per gram

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per Chemistry analysis.

• Incomplete containment integrity AND

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+ Known containment j

leakage in excess of f

Load reduction or plant Tech Specs.

cooldown initiated pursuant'to Tech Spec

+ Containment atmosphere i

3.4.8 H2 concentration greater p.

than or equal to 9%.

1 END l

+ Containment pressure j

greater than or equal to l

60 psig.

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McGUIRL ELEAR STATION CMIP-11 i

EMERGENCY ACTION LEVELS ENCLOSURE 4.1 EVENT # 4.1.3 STEAM SYSTEM FAILURE PAGE 6 OF 25 NOTIFICATIO!G OF' ALERT SITE AREA ENERGENCY GENERAL UNUSUAL EVENT EERGENCY t

1. Steam line' break which

1. Unisolable steam line

1. Unisolable steam line

.N/A results in rapid break outside.

break outside i

j depressierization of.

containment.with a S/G containment with a S/G i

the secondary side.

tube leak.

tube leak and indication of fuel I

l.

• Steam line-

+ Unisolable steam line damage.

i depressurization break outside I

1 resulting in safety containment.

• Unisolable steam line j

injection or main steam breck on the affected isolation AND S/G outside containment.

END NC subcooling greater than or equal to.O AND degree F.

S/G tube leak greater AND-than 50 gpm.

i S/G tube leak

'AND i

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.greate-than 10 gpm.

l Fuel damage as

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+ Unisolable steam line determined by Event i

break outside 4.1.2.

4 containment.

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i END l

AND j

Field monitoring teams detect activity at the i

protected area fence at greater than or equal l

to 2 inRem/hr whole body.

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McGUIRL' CLEAR STATION CMIP ~

EERGENCY ACTION LEVELS ENCLOSURE 4.1 EVENT # 4.1.3 STEAM SYSTEM FAILIIRE PAGE 7 0F 25 l

NOTIFICATION OF-ALERT SITE AREA EMERGENCY GENERAL l

UNUSUAL EVENT EMERGLEY 2.-Steam line break with failure of ECCS or ESF.

+ Steam line depressurization resulting in safety injection signal.

AND Failure of both trains of ECCS u.-%ction.

l.

+ Steam line depres-surization resulting in Mair; Steam Isola-ti.on signal.

AND Failure of two or more Main Steam Isolation Valves to close.

END

McGUIRL: ILEAR STATION CNIP-EMERGENCY ACTION LEVELS ENCLOSURE 4.1 EVENT # 4.1.4 HIGH RADIATION / RADIOLOGICAL EFFLUENTS PAGE 8 0F 25 NOTIFICATION OF' ALERT SITE AREA EMERGENCY GENERAL UNUSUAL EVENT EMERGENCY

1. Liquid or gaseous

1. High radiation 1cvels

1. Accidental releases of

1. Accidental releases of' radiological effluents or high airborne gases gases exceed Tech. Spec.

contamination Limits as determined

• EMF-37 Trip II alarm.

• EMF-37 Trip It alarm.

by RP or Chemistry

• Any valid EMF reading Procedures.

greater than or equal AND AND to 1000 times trip I END setpoint EMF.?6L reading greater EMF-36H reading greater than 6.3E5 com.

than 1.4E3 cpm.

2. Liquid or gaseous AND AND radiological effluents exceed 10 times Tech Calculations verify 2 Hr dose calculation Spec. limits as that dose rates at the verifies dose rates at determined by RP or site boundary are the site boundary are Chemistry procedures.

greater than or equal greater than or equal to:

to:

END 50 mrem /hr EE ar 250 1 Rem VB l'

l mrem /hr thyte:44 for 30 minutes OR

+ Calculations determine 5 Rem thyroid dose rates or Field Monitoring Teams

• Dose calculations or l

measure activity at the field monitoring team Site Boundary greater ceasurements result in than or equal to:

a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> projection at the site boundary of:

50 mrem /hr WB or 250 mrem /hr thyroid for 1 Rem WB 30 minates.

03 END 5 Rem thyroid END

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McGUIRC.JCLEAR STATION CNIP-t EMERTNCY ACTION LEVELS ENCLOSURE 4.1 EVENT # 4.1.5 LOSS OF SHUTDOWN FUNCTIONS PAGE 9 0F 25 3

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NOTIFICATION OF ALERT SITE AREA EMERGENCY GENERAL UNUSUAL EVENT-EMERGENCY N/A-

1. Complete loss of any

1. Complete loss of any

1. Transient initiated by i

function needed to function needed for loss of CF and CM i

maintain core cooling hot shutdown

-ystems followed by

'in modes 5 and 6.

conditions failure of heat removal capability for i

+ Failure of heat sink

• F:tlure of heat sink an extended period.

results in the loss of results in the l

NC System subcooling.

inability to raintain

+ Loss of CM/CF feedwater hot shutdown.

flow capability.

i

2. Transient' with failure of the Reactor Protec-AND AND I

tion System to auto-natically initiate and NC subcooling cannot be CA flow cannot be complete a Rx trip maintained greater than estab!ished within 30 7

which brings the O Deg. F.

minutes.

Reactor Subcritical i

i (ATWS Event)

AND

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+ Inability to feed

3. Degradation of 5/G's from any' NC system feed and Secondary Heat Sink source in Mode 1-3.

bleed cannot be 4

established or I

4 AND maintained.

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• Loss of 5/G Capability i

from main feed pumps.

NC subcooling cannot be maintained greater than

[

AND 0 Deg. F.

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l All S/G's levels less than 5% (25%) HR level i

AND i

i Total CA flow to S/G's less than 450 gpm E

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CNIP McGUIR.

JCLEAR STATION EMERGENCY ACTION LEVELS ENCLOSURE 4.1 EVENT # 4.1.5 LOSS OF SHtITDOWN FUNCTIONS.

PAGE 10 0F 25 NOTIFICATION OF ALERT SITE AREA EMERGENCY GENERAL DiERGENCY UNUSUAL EVENT

2. Transient requiring

2. Transient requiring a operation of shutdown Rx trip with failure systems with failure to trip and failure of to trip (power core cooling.

generation continues).

+ Transient with failure

+ Transient with fatiure of the reactor of the reactor protection system to protection system to automatically initiate automatically initiate and complete a Rx trip and complete a Rx trip which brings the which brings the reactor subcritical reactor subcritical (ATWS event).

(ATW5 event).

AND AND Manual Rx trip from the Manual Rx trip from the control room fails to control room fails to bring the reactor sub-bring the reactor sub-critical.

critical.

Ay0 Chemistry analysis indicates greater than or equal to 5% total fuel clad failure or increase of 1% fuel failures with 30 minutes.

AND Plant conditions re-quire entry into EP/ lor 2/A/5000/12.1 (Response to Inade-l quate Core Cooling).

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McGUIRL..sCLEAR STATION CMIP.

ENERGENCY ACTION LEVELS ENCLOSURE 4.1 EVENT # 4.1.5 LOSS OF SIIUTDOWN FUNCTIONS PAGE 12 0F 25 NOTIFICATION OF ALERT SITE AREA OMERGENCY GENERAL UNUSUAL EVENT ENERGENCY

+ Failure of heat sink

auses loss of cold Either Train ultrasonic shutdown conditions in level indication less modes 5 and 6.

than 14 inches and de-creasing af ter initia-AND tion of NC System makeup.

Core Exit T/Cs inci-cate superheat at the l

+ Failure of heat sink core exit.

causes loss of cold shutdown conditions in AND modes 5 and 6.

Available make-up AND rate (as indicated by Flow Rate Instrumentation Reliable NC System or rate of FWST Lt.^1 i

level indication un-decrease) less than available due to NC applicable data book System pressurization.

curve.

AND Core exit T/C's or

+ Failure of heat sink AP/1 or 2/A/5500/19 causes loss of cold (Loss of Residual Heat shutdowti cenditions Removal) data indicate in modes 5 and 6.

boiling in the core.

AND AND Available make-up rate Available make-up rate (as indicated by Flow (as indicated by flow Rate Instrumentation or rate instrumentation or rate of FWST Level rate of FWST level de-decrease) less than crease) less than applicable data book app'icable data boot curve.

curve.

)

McGUIRL CLEAR STATION CMIP-EMERGENCY ACTION LEVELS enclosure 4.1 EVENT # 4.1.5 LOSS OF SHUTDOWN RSICTIONS l

. PAGE 13 0F 25 NOTIFIL% TION OF ALERT SITE AREA EMERGENCY GENERAL UNUSUAL EVENT

' EMERGENCY

. f.ND NC System level below bottom range of avei s-abic level indkn:c::.

90 Emergency Coonfinator judgement that core uncevery is iminent..

END f

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McGUIRE..JCLEAR STAT 105;-

CMIP-L EMERGEWCY ACTION LEVELS ENCLOSURE 4.L

.j EVENT # 4.1.6 LOSS OF PnWER PAGE 14 0F 25 NOTIFICATION OF ALERT SITE AREA EMERGENCY G9fEP1.L UNUSUAL EVENT EMERGENCY

1. Loss of offsite power.

1. Loss of offsite power

1. Loss of offsite power

1. Loss of offsite power in Modes 1-6.

and loss of all onsite and loss of all onsite and loss of all onsite

)

AC power for greater AC power for greater AC pcwer with total

+ Both unit related main than 15 minutes in-than 15. minutes in loss of S/G's feed-bus lines de-energized.

Modes 5 & 6.

Modes 1-4.

capability in Modes in modes 1-6.

1-4.

• Both 4160 V essential

+ Both 4160 V essential

2. Loss of or. site AC buses are de-energized buses are de-energized

+ Both 4160 V essential power capability in for greater than 15 for greater than 15 buses are de-energized Modes 1-4.

minutes in modes 5 and minutes'in Modes 3-4.

in modes 1-4 6.

+ Both D/G's are

2. Loss of all vital DC AND incapable ( for greater

2. Loss of all vital DC power for greater than

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than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) of power for greater than 15 minutes in Modes Loss of CM/CF feedwater l

powering the 4160 V 15 minutes in Modes 5 1-4.

flow capability.

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essential busses in

& 6.

modes 1-4

+ Both unit related EVDA ANT)

+ Bott unit related EVDA and EVDD buses

3. Loss of onsite AC and EVDD buses de-energized,for CA flow cannot be power capability in de-energized for greater than 15 established within 30

)

Modes 5 and 6.

greater than 15 minutes in Modes 1-4.

minutes.

minutes in modes 5 an' l

• Both D/G's are 6.

END END incapable (for greater than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) of END powertrig the 4160 V essentia!' busses in modes 5 and 6.

END s

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EMERGENCY ACTION LEVELS ENCL 0%,4 4.1 EVENT #'4.1.7 FIRES AND SECURITY ACTIONS PAGli 15 OF 25 NOTIFICAT'3N OF' ALERT SITE AREA EMERGC 7 GETERAL EMt3GENCY UNUSUAL tdENT.

1. Fire within the plant

1. Fires defeating safety

1. Fire compromising the

1.. Any major fire w se (see Note) that takes system fir.sctions required functions of shutdown curity threat which more than 10 minutes for curre'it operating mode.

systems.

could cause massive common damage to iL to extinguis.".

• Fire that results in '

plant systems.

+ Fire resulting.in

2. Security. threat.

loss of any required ESF inability to maintain functicn (both trains de-Hot Shutdown

2.. Loss of physical

(

+ Discovery of bomb

.feated or fire defeats the.

control of the plant.

withir Ue site single operable ~ train).

AND

'+ Physical attack on the bounda y.

+ Fire requiring Control-NC subcooling cannot be plant (see Note) has

• Civil d M urbance Room evacuation maintained greater than resulted in occupancy (hostile) 0 degrees F.

of the control room or AR auxiliary shutdown

+ Intrusion / Attempted panels by unauthorized Intrusion (Protected Co1 trol established (or

+ Fire requiring Control personnel.

l Area) in process of being Room evacuation estabiished) from the; END

+ Hostage Standby Shutdown AND situation / extortion Facility-(SSF)

Control cannot be

• Security threat as established from the Stand-determined by Emergency by Shutdown Facility (55.0).

Coordir.ator and AND Security END NC wbcooling cannot be maintained greater than NOTE:

Plant is defined 0 degrees F.

as:

Aux. Bldg, TB, SB, RB, D/G Rm, Doghouses, SSF, Interin Radwaste Facility

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McGUIRE..JCLEAR STATION CMIP-.;

EMERGENCY' ACTION LEVP.S ENCLOSURE 4.I

EVENT # 4.1.7 FIRES'AND SECURITY ACTIONS PAGE 1610F 25 N0flFICATION OF.

ALERT SITE AREA OERGENCY GENERAL ~

.. UNUSUAL EVENT EMERGENCY

2. (% going Security

2. Isusinent loss of compromise.

physical control of a plant vital area.

+ Adversaries commandeer an area of the plant

+ Physical atter.k L

but do not c.ntrol any resulting fu ir.inent plant vital' areas.

occupancy t' Oe Controi Room or

+ Discovery of breached-

.other vital areas barrier caused by intrusion or sabotage.

+. Discovery of bomb in in Vital Area a plant Vital Area.

+ Discovery of bomb in END the. protected area 1

'+ Ongoing security compromise as determined by Emergency-Coordinator and Security' END s

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McGUIRL. -CLEAR STATION EMERGENCY ACTION LEVEL)

ENCLOSURE '4.1 EVENT # 4.1.8 SPENT FUEL DAMACE P.4E:17 UF 25 NOTIFICATION OF ALERT SITE AREA EMERGENCY GENERAL-l 09ERGENCY -

UdUSUAL EVENT N/A

1. Damage to. Spent Fuel

1. Major damageLto_ spent N/A with release'of fuel with release of radioactivity.

radioactivity CONTAINMENT CONTAIN ENT l

+ Valid Trip II Alarm

+ Valid trip II Alarm I

on IEMF16 or 2 EMF 3 on'1 EMF 16 or 2 EMF 3

_AND AND l

Dose rate calculations Dose rate calculations using vent sample using unit vent sample analysis and flow rate analyses and flow rate data are in-excess of data equiva'ent to:

10 times limits established by Greater than or equal Technical to 50 mrem /hr WB or 250 Specificatiens mrem /hr Thyroid for 30 minutes at the site FUEL HANDLING BUILDING boundary

+ Valid Trip II Alarm FUEL HANDLING BUILDING on IEMF17 or. 2 EMF 4

+ Valid Trip II Alarm

.AND on IEMF17 or 2 EMF 4 Dose rate calculations AND using vent sample analysis and flow rate Dose rate calculations data are in excess of using unit vent sample 10 times limits analyses and flow rate established by data equivalent to:

Technical Spet!fications Greater than or equal to 50 mrem /hr WB or'250 END mrem /hr thyroid for 30 minutes. at the site boundary END

n McGUIRL.sCLEAR STATION CMIP.

EMERGENCY ACTION LEVELS EVENT # 4.1.9 NATURAL DISASTERS AND OTHER HAZARDS..

EELOSURE 4.1 PAGE'18 0F 25 NOTIFICATION OF ALERT SITE AREA EMERGEWCY GENERAL UNUSUAL EVENT EMERGENCY

1. Earthquake felt in.

1. - Earthquake greater

1. Earthquate greater

1. Any major natural or plant and detected by than 00E-than SSE-accidental event (s) (ie:

seismic monitoring aircraft impact, instruments

+ Greater than 0.08 g

+ Greater than 0.15 g earthquakes Horizontal Horizontal substantially beyond

+ Valid Alarm on "streng design levels) which motion accelerograph"

+ Greater than 0.053 g AND could cause massive Vertical cocoon damage to plant

+ Valid Alarm on " Peak Damage to plant equip-systems.

shock annunciator"

2. Damage from tornado, ment resulting in sustained winds, inability to maintain

+ Recovery Manager or

2. Low water level aircraft crash, train subcooling greater Emergency Coordinator derailment, missile, than 0 degrees F.

judgement.

• Lake Norman level 'less or explosion.

than or equal to 745

+ Greater than 0.10 g END ft.

+ Damage to plant Vertical equipment causing the

3. Any tornado / severe inability to maintain AND 6

weatheriwithin the cold shutdown in medes site boundary.

5 and 6.

Damage to plant equipment resulting in inability to

+ Tornado observed on

3. Release of toxic or maintain subcooling great-site flammable gas.

er than 0 degrees F.

AND

+ Uncontrolled entry of

2. Damage from toxic substance or-tornado, severe Physical camage flammable gas into any weather, missile, observed to plant area which explosion, aircraft equipment / structures jeopardizes the crash, or train within the site operation of systems derailment causing a bounda ry needed to maintain loss of functions cold shutdown in Modes needed for plant hot 5 and 6.

shutdown.

559

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McGUIRL CLEAR STATION'-

CMIP-EMERGENCY ACTION LEVELS ENCLOSURE 4.1 EVENT # 4.1.9 NATURAL DISASTERS.AND OTHER HAZARDS PAGE 19 0F:25 NOTIFICATION OF

- ALERT._

5ITE AREA EMERGENCY GENERAL UNUSUAL EVENT EERGENCY

]

q

• Sustained (greater than.

+ Failure'of heat sink ~

j

. 15 minutes) winds

'results in the.

greater than or equal inability to maintain to 60-mph Hot. Shutdown conditions AND

,AND-Physical damage NC'subcooling cannot be observed to maintained greater than equipment / structures _

0 degrees.F.

within the site boundary.

+ Inability.to feed S/Gs from any sou ce'-in

4. Aircraft crash Modes 1-3.

+ Aircraft crash within AND the site boundary.

NC_subcooling cannot.be i

5. Train derailment'on

. maintained greater than site.

O degrees F.

l

+ Train derailment

' 3. Release of toxic or resulting in physical flancable gas (Modes damage to equip _-

1-4).

ment /stru-ture within site boundary.

+ Uncontrolled entry of toxic substances or

6. Explosion within site clammable gas into any boundary.

plant area which prevents the operation-

• Explosion within the of systems needed to site boundary resulting maintain hot shutdown in structural damage to in modes 1-4.

buildings and/or injuries to personnel.

END

-_m#,'--

VcGUIRE..., CLEAR STATION L CMIP.-.

EMERGENCY ACTION LEVELS' ENCLOSURE'4.1.

~

EVENTF 4.1.3 NATURAL DISASTERS AND OTHER HAZARDS PAGE'20'0F 25 NOTIFICATION OF ALERT

~ SITE AREA EMERGENCY' GENERAL

~

UNUSUAL EVENT DERCENCY

7. Release of toxic or flasunable gases.

+ Release of toxic gas resulting in personnel-1 injury or any evacuation within the Protected Area.

r i

+ Release of flammable gas resulting in any evacuation within the Protected Area.

END i

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McGUIRL ELEAR' STATION CMIP-EMERGENCY ACTION LEVELS ENCLOSURE 4.1' EVENT # 4.1.10 OTliER ABNORMAL PLANT CONDITIONS PAGE 21 OF 25 NOTIFICATION OF ALERT SITE AREA EMERGENCY GENERAL UNUSUAL EVENT EMERGENCY

1. ECCS initiated.

1. Evacuc unn of Control

1. Evacuation of Control

1. Other unit conditions Room Roem.

exist, from whatever

+ Valid S/I signal source, that in the verified by redundant

+ Evacuation of Control

+ Evacuation 'of Control judgement of the' indication Room Room Recovery Manager.

make release of AND-AND AND large amounts of-radioactivity in discharge into the Control established (or Control cannot.be a short time vessel in process of'being established from the period possible.

4 t

.' established) from the auxiliary shutdown

2. Abnormal coolant Auxiliary Shutdown Panel panel or SSF END l

i temperature and/or pressure or abnormal

+ Inability to establish AND fuel temperature control from Auxiliary Shutdown Panel.

NC subcooling cannot be

• Figure 2.1-1 Tech Spec maintained greater than exceeded in modes 1 and 2 AND 0 degrees F.

4 Core sub-cooling margin Control established (or

+ Evacuation of Control less than acceptable in process of being Room in Modes 1-3

("Subcooling Margin established) from SSF.

Alert" annunciator).

.A_ND 1

+ Tech Spec (LCO 2.1.2)

Inablity to feed S/G's from Reactor Coolant System

2. Significant loss of any source, pressure exceeded in modes annunciator capability 3, 4, and 5.

in Modes 1-4.

'2. Other unit conditions exist that in the j

+ Loss of 507,or more of judgement of the the control room Rscovery Manager annunciators for warrant declaration greater than 15 of site Area Emergency.

i;

. minutes in Modes 1-4.

END i

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McGUIRL

, CLEAR STATION

~CMIP-EMERGENCY ACTION LEVELS

-ENCLOSURE 4;l EVENT # 4.1.10 OTHER ABNORMAL PLANT CONDITIONS PAGE'23 0F 25 NOTIFICATION OF ALERT-SITE AREA EMERGENCY-GENERAL

' UNUSUAL EVENT EMERGENCY-

4. Loss of ESF or' Fire Protection System function.

+ Both trains of any ESF system found inoperable (if caused by fire, see event #4.1.7 - Fires and Security Actions, Alert Classification).

l AND Load reduction or plant cooldown initiated in-accordance with Tech Specs.

+ Less than minimum channels of ESF.func-i tion inoperable.

AND Lead reduction or plant cooldown initiated in accordance with Tech Specs.

4

+ Loss of all main fire protection system water pumps.

i

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'McGUIRL ~; LEAR STATION' LCMIP-

' EMERGENCY ACTION LEVELS ENCLOSuME 4.1 EVENT # 4.1.10 OTHER ABNORMAL PLANT CONDITIONS.

PAGE 24 0F 25 NOTIFICATION OF ALERT SITE AREA EMERGENCY GENERAL UNUSUAL EVENT EMERGENCY

5. Transportation of a contaminated injured individual from the

-site to an offsite medical facility.

+ Decontamination efforts fail to reduce external contamination below 150 cpm beta gamma or injured may require immediate medical attention and decon-tamination efforts are f

waived.

so Radiation Protection personnel determine that radiological controls are required for offsite medical treatment

+ Internal contamination requiring medical

~

assessment / treatment

+ External exposure requiring medical essessment/ treatment

.f

.6,.'

-McGUIRE 2 LEAR STATION CMIP-EMERGENCY ACTION'IffELS 91 CLOSURE 4.1 EVENT # 4.1.10 0111ER ABNORMAL' PLANT CONDITIONS PAGE 25 0F 25 NOTIFICATION OF.

ALERT.

SITE AREA EMERGENCY GENERAL UNUSUAL EVENT EMERGENCY

6. Significant Loss of assessment capability or consnunication

. capability i

i

+ Loss of MNS communications l

capability with all offsite agencies f

+ Loss of 50% or more of l

the control room annunciators in Modes 5, 6 for greater t'han 15 minutes.

+ Loss of.all onsite meteorological instrumentation l

Inability to contact the National Weather 4

Service for backup source of data.

7. Other conditions exist that in the judgement of Shift Supervisor /

+

Emergency Coordinator varrant increased i

-awareness of local authortties.

l WD 4

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CMIP-11.2 Page 1 of 1 i

ENGINEERED SAFETY FEATURES

1) Containment Spray

2) Containment Air Return and Hydrogen Skimmer

3) Ice Condenser

4) Hydrogen Control (Hydrogen Recombiners Only)

5) Annulus Ventilation-

6) Auxiliary Feedwater

7) Nuclear Service Water

8) Component Cooling

9) Steam Line/Feedwater Line Isolation

10) Containment Pressure Control

11) ESF Inte locks

12) Turbine Trip

13) Reactor Protectiori System

'14) Emergency Diesel Generators

15) Emergency Switchgear

16) Loss of Power Actuation Circuit

17) Emergency Core Cooling System - Safety Injection, Residual Heat Removal, Cold Leg Accumulators, Upper Head Injection, Chemical and Volume Control System, Automatic Switchover

18) Containment Isolation - Phase "A" and Phase "B"

+.

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CRISIS MANAGEMENT IMPLEMENTING PROCEDURE CMIF-12 Classification of Emergency for Oconee Nuclear Station Rev. 11 March 15,1991 l

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I Appro M By ifa'te e

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CHIP-12 CLASSIFICATION OF EMERGENCY FOR OCONEE NVCLEAR STATION 1.0 SYMPTOMS 1.1 Notification of Unusual Event 1.1.1 Events are in process or have occurred which indicate a potential degradation of the level of safety of the plant.

1.1.2 ko 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 process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant.

1.2.2 Loss of one fission product barrier.

1.2.3 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.

1.3.2 Loss of two fission product barriers.

1.3.3 Releases do not, nor are they expected to, exceed EPA Prot 9c-tive Action Guideline exposure levels outside 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 Loss of two fission product barriers and failure or imminent failure of the third barrier.

1.4.3 Releases, if made, could be expected to exceed EPA Protective Action Guideline exposure levels outside the Site Boundary.

1

1 2.0 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 or GENERAL EMERGENCY, determine protective action recommendations per CMIP-1 and transmit these recommendations.

NOTE:

Notificat4 ns to the state (s) and counties must be made within '...ninutes whenever there is a change in the emergency classification.

2.3 Announce the change in the emergency class to a'll CMC personnel and to the-Emergency Coordinator at the TSC.

2.4 Instruct the NRC Communicator in the CMC Plant Assessment Group to notify NRC immediately and within one hour per CMIP-15.

3.0 SUBSE0 VENT ACTIO_NS 3.1 To de-escalate or close out the Emergency, compare plant conditions te the Initiating Conditions of Enclosure 4.1.

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 Action Level (s) f or Emergency Classes Event No.

Page(s) 4.1.1 Primary Coolant Leak 1&2 4.1.2 Fuel Integrity 3

4.1.3 Steam System Failure 4

4.1.4 High Radiation / Radiological Effluents 5

4.1.5 Loss of Shutdown Function 6

4.1.6 Loss of Power 7

4.1.7 Fires and Security Actions 8

4.1.8 Spent Fuel Damage 9 & 10

j 4.1.9 Natural Disasters and Other Hazards 11 4.1.10 Other Abnormal Plant Conditions 12 & 13

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ENCLOStrtE 4.1.1 CHIP-12 PRIMARY COOLANT LE AK PAGE 1 of 13 L2&fSUAL EVENT ALERT SITE AREA EMERGENCY GE>etM tt EMERGENCY 1.

RE ACTDR SJRJTDGet REEltJIRED BY RCS 1.

510S 11AKAE QtEATER THAM OR 1.

RCS IIAdulE GatEATER THAN 1.

SMALL Afe 1ASIE treras MrTH IEAKAE TS 3.I.6 ESIAL TD 50 059t AVAILAnti MAITLP PtDF CAPACITY FAIttstE OF ECCS-tIAIRS TO C11RE K LT.

OPEIATING t e E: HDT SIRITDGet OPERATIPs teDE: HDT SN.fiDOGE 1.

OPERATING teDE: STARTLF T)Stt!

THRU POGR OPERATIG8 115tU PC*ER OPERATTGG P(DER OPERAT1(DES

- tDCA SAE S1 EAL Ape EITHIR Reactor shutdown initiated Primary or-Primary /Secrwwiary Prismary or PrimaryEweerwwiary Loss of all injec don or

~

pursuant to TS 3.1.6 inaminent loss of injection Leak 2 50 one Full HPI mable to maintain capability ADe M_ ONE OF THE_FOttGGNU std> cooling >0* F

~ Ape On Primary laakage i midenti f ind i Sadiccoling 5 0*F 2.

STTIM LIE natEAK Emiergency actioM per EOP exceeds I gpm MITH P/S LEAK inadequinte core cooling section Total primary laakage Leak CApeci be isolated.

10 50 0896

- 1200* F.

Ape EstEATTR THAN OR ES.AAL are msuccessful - CETC -

~

f identified t exceeds 10 gwn 2.

LOCA MITH IMITIALLy =arrrwyt, 2.

STEAM LIK B3 TEAK OUTSIDE OPERATTNG PEDE: 9er s' SPRJTDGet ECCS MITH SLRESEEILENT FAIT 1BIE OF Total primary leakage CfD4TAIpetMT MITH P/S EfAK TisitJ PO(R OPERAT*. Opts ECCS KAT SIR Ass FAIllstE OF Iincluding returnablei CatEATER THAN OR EElllAL TD 10 GPM CIDtIADeWMT KAT IEEMOVAL exceeds 30 gpm IM5IDE CINTADetNF MITH CAPABItJTY IleICATION OF FAIT 1P TIEL SG ttd>e leakage ).35 gpm GPERATT)e teDE: HDT SH.fiDOpet

- LOCA SAE 81 E AL THIiB POER OPERATIGG Steam line pressure rapidly

_Afe Any reactor coolant leakage Steam line pressure rapidly decreasing i

evaluated as unsafe decreasing Loss of LPI heat removal Any leakage exists through Ape ETTER OF TE FOLLIMI)e

-Ape

_ Ape the RCS strength boundary SG ttd>e leak > 50 gpm Loss of heat removal t except SG tod>es i SG ttd>e leak > 10 gpm capability of RSCOs.

_M OR Field Monitoring Teams mesasure Valid RIA 57 or 58 MIQt alarm activity at the Protected Area i630 R/hrI Fenca:

OtJTSIDE CINTADGENT

~> 2 mR/hr thisolable steam line break

-^**

SG ttd>e leak > 50 gpum

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1 ENCLOCURE 4.1.2 CMIP-12 FUEL INTEGRITY PAGE 3 of 13 UP23SUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY I

1.

MIQt RES ACTIV UY 1.

?TVERE LIISS OF FtEl CLADDDC 1.

BEEMADED rrer DEITM mTas r tggs5 a sFM OF 2 OF 3 FISSItst Purer"T OF CDOUBLE GEtNETRY BAINIEftS DEITM A PEFENTIAL Ftut LIISS OF 3stD SARRIER

- Total failed fuel is between

- Total failed fuel > 5% per

- Average of five highest CETC 1% - 5% per Chemistry analysis Chemistry analysis -

reading 3 700* F istM or dADDING BAftStIER Condition 1

- Total activity of RCS dm to

- 4Jrmble to sumintain stAccoling

- Total failed fuel is 3 5% per isotopes with half lives

. Area or process RfA monitors 3 0*F Chemistry analysis -

Condition 2

onger than 30 minutes exceeds in the RB aqual or exceed 224/E pei/ml 4wn the RX is

. limits stated in Enclosure 4.2

- RB hydrogen concentration.

l critical 3 0.5% and increasing at a

- RI A 57 or 58 A11RT Alarm rate of > 0.1% per hour i2500 R/hri j

- I-131 on secondary side

- valid RIA 57 or 58 HIOl Alarn

- Average of five hiS# west exceeds 1.4 pci/ml 1630 R/hr3 CETC reading 3 700*F 2.

ANEMMAL CDOLANT TDWTRAT13tE LDSS CIBfTADSENT BARItIER Ape /Det PMWW GJTSIDE TS t.DtITS

- RB penetratient s i are not i

isolated OPFf.ATDC DODE: AROVE EIXD

)

SIAJTDGet

- RS pg2 concentration is > 9%

- tn event has occurred *hich

- Contairement leakage exceeds rexpires operation in the 5.6E6 el/hr Thermal Shock Operating Pegion

- RB pressure > 59 psig

- TS pressure / temperature INDT )

s#m or aCS PerMme BARItIER limits violated

- LOCA 3 50 gpm anon-isolable fault 9

- SG tt6 leak 3 50 gpm I

ENCLOSURE 4.1.3 CMIP-12 STEAM SYSTEM FAILURE' PAGE 4 of 13 (DAJ50AL EVENT ALERT SITE AREA EMERGENCY CENERAL EMERGENCY 1.

RAPID DE PRESStRIZATION OF STUWW t.INE BREAft tr:51DE 1.

STEDE 1.DE BREAK MITM SEcopeARY SIDE CIDtTADDENT METH P/S LEAst F/S LEAft EEPEATER TMAN E3tEATER THAN OR ESRL TD 10 E39t

. OR EstRL TD 50 E891 OPEDtTIE PODE: SE7T 58effDEDet TNRU POER OPERATitDt5 -

(FERATDE SEWE: 3001 SDRJTD0 Bet OPERATDE PEDE: satrT SeeJTDEDee M5tU PG ER GTRATItPfS-1MIU PGEER OPERATIGES

- Visual observation of non-isolable leak on main steam

^~ Stean i.ine pressure rapidly DGIBE CIINTADeGrF MITM line rensiring plant shutd-decreasing iteIi5ii10ps 6F iAItID ftEt

~ -

- Steam line pressure rapidly Ape ETTER Or ugE FtR.IfDtING Steam line pressure rapidly decreasing decreasing SG tthe leak 3 10 gpm.

- Steam line break requiring Ape isolation pursuant to the O_R

~~

emergerwy operating precedare Field Monitoring Teams measure SG tihe leak 2 50 gpm activity at the Protected Area Fence:

_AfE5 3 2 mR/hr valid RIA 57 or 58 NIESE alarm 8630 R/hri OtJTsIDE CEDffADDENT i

Unisolable sisam line bre=A

_Ase SG ttee leak > 50 gpm I

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ENCLcSURE 4.1.4 CMIP-12 t'

HIGH RADIATION / RADIOLOGICAL EFFLUENTS' PAGE.5 of 13' IMfSUAL EVENT ALERT SITE AREA EMERGENCY GEM MAL EMERGENCY

,s 1.

CADIOLf3GICAL EFFLtDfT TS LIMET5 1.

MIM RADIAT10Bt LEVEL OR MIGE 1.

AEIBDETAL RELEJtSE OF GASES 1.

ACCIEDETAL DELEASE U~ GRSES DCEEDE D AIRB0pWE~ CIB8TAMDetTItSt

- Gaseous /Liqutd effluent being

- Area or process RIA moni wrs 19 TITS 1 A2 19tIY3 132 released exceed Sic 16.11.1 or exceed limits stated in StC16.11.2 limits as determined'.2'

- RIA 45 MIG 8 Alarm

- RIA 45 MIG 8 Almre by MP or Chersistry Procedures.

+

Ase

-ABS

- Activity detected at the Protected Area fence:

RIA 44 'twading 3 3000 cpe RIA 46 reading 3 60.500 cree -

3 2 mR/hr 2 tserr 5 tetrr s 2.

RADIOLOGICAL EFTl11MT5 DCEEDDEG 10 TIM.S TS

- RI A 45 ALINT Alarm

- RI A 45 ALf grr Alar.

- Gaseous /Liensid ef fluents being

'-A8@

-ACE released exceed 10 times $LC RIA 46 reading 3 230 cpe RIA 46 reading 3 4,600 cpe -

16.11.1 or SLC 16.11.2 limits as determined by HP or Channistry

- Calculations detemine dose

- Dose calculations or field Procedures rates or Field Monitoring Teams monitoring team measurements measure activity at the Site result in a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> cbse Botrwia ry projecticm at the site bcnndary af:

> 50 =P/hr e or 250 seR/hr Thyroid 3 1 Rose m ole Body CR 3 5 Rose Thyroid r

+

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CMIP-12 ENCLOSURE 4.1.5 PACE 6 of 13 LOSS OF SHLfTDO>e4 FLNCTIONS

{

SITE AREA EMERCENCY GENERAL EMERGENCY ALERT LNUSUAL EVENT 1.

EDSS OF f13CTICBES DEEDED TO 1.

ROSS Or FISCTItBES MEDED FOR 1.

TRANSIENT IMITIATEB SY m OF

- MAINTAIN PLANT COLD Set.fTDtBei PtDtT DEIT SSAJTDIDet FDet Ape CtseE7EATE SYSTEPts FDLtJ2EB BY FAILIAtE Or Erst rom GPERATIDE PEDE: CDLD $8tMD0D9e OPERATDE PEDE: HOT $8EJT80 Bee AN fXTU eED PERIOD T)sIU PtBER (PERATIEDES THIRJ REFMt.DE

- Inability to feed steam

- Unable to sumintain core

- SSF feeding steam generators generators from Af# source tenpersture < 200* f

- HPI forced cooling treble

~AND to misintain stix:noling > 0* r HPI forced cooling not available 2.

DECRADED FISCTICD4 Or SYSTUNSB 9EEDED TD MAIWTAIN PLANT HDT

- thable to maintain reactor 585H3000 CIseITI! DES stberitical 2.

TRANSIENT REGRARDC EDC TRIP NITM FAltistE TD SutAN Ape (PERATIDE PEBE: DEIT 58eJTDED00 2.

ANTICIPATED TRANSIENT MITMRJT TAIL 15tE Or N COOLDG TDWIIJ POER OPERATIEDtS SCRAft

- 2 or more RPS channels trip

- No HPI flow available OPERATING MODE: P0HER without automatic reactor OPERATIONS trip Ape

- HPI forced cooling initiated 2 or more RPS channels trip Emerdactions per EDP 3.

ANTICIPATED TRANSIENT MITIENJT withcut automatic reactor trip fail to bring reactor sthcritical Ape SCRAM Control roa remain withdrawn and CANNOT be manually tripped Age OPERATING MODE: P0HER OPERATION or inserted from the control RCS SJx:oolEng < 0* F

- 2 or more RPS channels trip room without automatic reactor trip age -

Centrol re Tdare capable of being inserted Imanual trip or driven t f rom the control room

.~

CMIP-12 ENCLOSURE 4.1.6 PAGE 7 of 13 LOSS OF POHER tJPAJSUAL EVENT ALERT SITE AREA EPERGENCY GENERAL EMERGEPCY 1.

LOSS OF OFFSITE AC PGER tm LDSS 1.

LDSS OF OFFSITE AC PGER ABW 1.

im OF OFFSITE AC POER Age 1.

FAILimE OF OFFSITE Ages EDESITE OF GESITE AC PGER CAPABILITY LOSS OF ALL OB(SITE AC PGER f m OF ALL OtSITE AC PGER AC PGER ALABC MITM TM MFTAL Im OF EFDet N cal %SILITY CPECATDC PODE: COLD SMJTDGet OPERAIDC PODE: CDLD SMJTD(Dei (PERATDE PODE: COLD SptJTDGot TNRtj REf1ELING TMilli REFIKLDC TieRJ REf1ELDE OPERATDE POIBE: ABOYE CDLD

• JeJTBGod

- MFB 1 and 2 de-energized for

- MFB 1 and 2 de-energized for

- MFB 1 and 2 de-energized for

>l but (15 minutes

> 15 minutes

>15 minutes

- No AC power iBlack-outi AVD GPEE.ATING DODE: ABOVE CDLD OPERATING 900E: A80VE CDLD TemperatureTn the core is

_A88

>200*F SatJTDGed StRJTDoped:

Inability to feed steam

- Shutdown initiated pursuant

- MFB 1 and 2 de-energized OPERATDC DODE: ABOVE COLD generators from A*rf sosrce i

(Includes the SSFR to T.S. 3.7 for >1 but <15 minutes SPRJTBGee

- Loss of offsite AC power 2.

LOSS OF ALL VITAL GESITE DC

- MFB 1 and 2 de-energized

> 15 minutes and unit auxiliaries being PopER powered through CT4 or CTS OPERATING PODE: CDtB SDEJTDaget 2.

1 DSS OF ALL VITAL (DESITE IPC 2.

LDSS OF ALL VITAL GC5ITE DC TisitJ REF11LDE PtBER PGEQ EDLD S8EJTDGet

- Losa of DC power io a11 vita 1 OPERATDC PODE:

OPEI.ATD E PODE: COLD SatJTDuped panalboards for >15 minutes TieRJ REf1ELDeG T1stu REf1fLDC ABOVE COLD

- Sustained loss of DC pmera to OPERATDC HDDE:

all vital panelboards for f

- Momentary loss of DC power to SHtJIDased

>15 minutes all vital panelboards >l but Afe (15 minutes

- Momentary loss of DC power to all vital panalboards Temereture T the core is

> 1 but < 15 minutes

>200*F 3.

STEAft CEDERATDR TERE LEAK 9(ITN OPERATDdG PODE: ABOYE CDt3 LD'sS OF OFfMTE AC POER SSRJTDGet CPERATDE MODE: ABOWE COLD

- Sustained loss of CC power to SHUTDGot all vital panelboards for

> 15 minutes

- SG tiAe leak > 10 gpm Are S(bcooling Ergin > 0* F Loss of 6900V power to all RCPs

4 ENCLOSURE 4.1.7 CMIP-12 FIRES AND SECURITY ACTIONS PAGE 8 of 13 LHJSUAL EVENT ALERT SITE AREA ENERGENCY GE9ERAL EMERGENCY 1.

FIltE NITMIM PtANT LASTDE 1.

FIRE PUTENTIALLY AFTLCTDC SAFETY 1.

FIRE CIDRIt387*tTE TIE ftSCTItBtS 1.

ANT pas war INTEIWOM. OR EXTEment.

tore DIAN 10 MDeJTES SYSTDts OF SAFETY SYSTEMS EvDir tetICM CatRD CJMSE setSSIVE CIBGEDI IMeenGE TD TE PtANF DUTE: Hathin the plant means:

- Visual observation of fire

- Observation of a fire causing the Aux Bldg. TB, RB, steowee potentially affecting safety loss of rockndant trains of safety

- thit cannot be emaintained at -

swipment required by Tednical equipsnent required by Tedhnical hot shutdown free any location Hydro Specifications for current Specs. for current anode of operation

- Ef forts to extinguish a fire mode af operation 2.

LOSS OF PNYSTCAL CIBffM0t_ OF TE within the plant last

- Fire in Control Rooge requiring PLANT ISEE DGITEel

> 10 seinutes

- Fire in the Control Room evacuation and thit camot be requiring evacuation and thit semintained at I.ot shutdown being snaintained at hot free the auxiliary shutdown

- Physical attad resulting an 2.

SEClifITY DetEAT OR ATTDWFTED shutdown frors the auxiliary panel (nauthorized persomel ENTRY OR SABOTACE (SFT NOTEeI shutdown panel ocopying the CR or any other 2.

DetDENT LOSS Of~ PHYSICAL vital areas 2.

(BEXHE SEE15tITY CIWWWWEISE C13t!RDL OF TE PLANT ISEE BEITE*)

- Discovery of bomb within the (SEE NDTEe3 site hotndary

- Physical atiacA resuliing

- Civil disturbance lhostile)

- Adversaries cosesandeer an area in invoinent ocxxpancy of of the plant but not control control roon or other vital r

- Intrusion /Attes,ted Intrusion over snit shutdown capability areas (Protected Areal

- Discovery of breached barrier

- Discovery of bond > in the l

- Hostage situation / extortion e security-related 6 caused by vital Areas intrusion or sabotage in vital Area DUTTe: RP/0/B/1000/07 shall be l

used in conjtnction with

- Ducovery of boob in the all security related Protected Area energency classifications l

l I

m Ab.

w

~i.

]

a ENCLOSURE 4.1.8 CMIP-12" srENT FUEL DAMAGE PAGE.9 of 13 (D&EUAL EVENT AtIRT SITE AREA EMERGENCY GENERAL EPERGE?CY 1.

BanaGE TO SPfMT M L MITM 1.

paa en DAMAGE TU Sperr Mi DJTM RELEASE OF RADIOACTIVITY RELEASE OF RABIGACTIVITY Activity at pmtected area - fence:

EranADeE3rr 3 2 mR/hr De Valid RIA 57/58 NIEst Alarm f630 R/hrI 19ETS 1 or 2 Valid RI A 2. 3, or 4 NIESI

' iiiff ADetEi~

alam and RIA 49 of fscale high Valad RIA 2, 3, or 4 NI M Alam or RIA 49 MIG 88 alarm

-AfD cose rate I5 side RB cxxpled -

_ Ape with RB leak rate results in calculated dose rate at Site Open flow path exists from Botndary:

)

contairveent rtJEL naseLIpes surtmpsc

-> 50 mR/hr te or 250 mR/hr Thyroid Valid RIA 6 MIE88 Alare or

_f1ELMApetDE BUILDDE RI A 41 ALERT alarm

~

(SETS 142 Valid RIA-6 NIGet or RIA 41 g

ALENT Alarm RIA 46 HIGBR Alam.

AfD l

d verified by RIA 45 9 RIA 45 AH WT alarm l

A0e A08 RIA 46 reading > 3000 cgne Release rate calculations using vent sample analysis and tsET 3 flow rate data are in excess of 10 times limits established Valid RIA-6 NIEat or RIA 41 by Technical Specifications ALEET Alarm Ane icontinuedt RIA 45 AdKT alarm Age RIA 46 reading 2 230 cpse

_-~_-_

f M

- I.

ENCLOSURE 4.1.8

. CHIP-12 SPENT FUEL DAMAGr PAGE 10 of 13 LDOSUAL EVENT ALERT SITE AREA EPERGENCY -

GENERAL EPERGENCY' 2.

BapMEE TO SPDfT REL DEETH REIFAW OF RADI0 ACTIVITY tstIT 3 CIBRAD00fr valid RIA Z, 3. or 4 NIGI

Alarm or RIA 49 AlfRT alarm

-^**

Open flow path exists from contairement -

RKL stesetDs su1Lanc

- ' valid RI A 6 IEIEME Alarm or.

RIA 41 ALENT alarm

~Ane l

RI A 46 ALERT Alarm tvarified by RIA 45) 4

. Ase

~---

Release rate calculations

.using m t saeple analysis ard fl e rate data are.in excess of 30 times limits established.

by Technical Specifications I

o e< '

(NCLOSURE 4.1,9 CMIP-12 NAYURAL DISASTERS AND OTHER HAZARDS PAGE 11 of 13 UP4JStJAL. EVENT ALERT SITE AftEA E;ERGENCY GENERAL ENERGENCY 1.

EARTHIRAAKE DETECTES 1.

DESIGI SASIS EAfrD99L3AKE -

1.

BArt4GE F9tyt EAR!MULMILE, AIItr3tAFT 1.

AE?f 8WL50R INTUsent OR EXTUppl CRASM, TN, MISS11E St EVENTtS9 8i.e.

FIItE3, FtDEMti.

- Tremor felt and strong motion

- Tremor felt and seismic EARTMQUAftE EARTMetIndLES SEEtSTANTIALLY BETC90 BESIGN LEVELSI 900CM CAMS accilero paph actu tes 60.01 gt trigger alarm actuates MASS 7 VE CIPMDt BAMAGE TD Pt. ANT 10.05 99 OPERA.IMG f(MME: AaMWE CUL7 2.

LAFI LEVEL iKiDEE 3 SPRntstBCs SYST7M5 2.

DAMSE TEtEPt AYNC5tATT CRASH,

- Level < 780 ft.

TDetNADO, MT"TLE OR DTLD5ftPI

- Danage observed to safety Uni: cannot be maintairwd at Ape.

equipment causing 4he inability hot shutdown from any location tCnit shutdown initiated per to establish and maintain hot TS 3.3.7 ILPSH operability t

- Damage observed to shutdown from the' control 4

safety equipment causing room or the euxiliary 3.

DAMAE FRtyt AIstCMAFT CRASH the inability to establish shutdown panel TDRNADO MISSLL DIt EXPLD5134 and maintain cold shut-down

- Tramor felt and peak.a:aleration

- Damage incurred to recorder readig > 0.10g equipment / structures within 3.

MAZAstDOLG SLBSTAfCE OR FLAf9ttBLE the Site Boundary GAS IEELEASE 2.

MAZAftsotE '3et'tTApCE Out Ff Aff98tf GAS stELEASE 4.

MAZARDOLS 9WMTANCE OR FIAre*JhBLE

- thcontrolled entry of a AIM CI3tp GA3 3 RELEASE toxic stbstance or flamable OPERATDE 98ADE:

gas into an area of the plant SfUTIEDet

- A spill or release deter *ined

,hich jeopardizes the operation l to be reportable pursuant to of equipment re essary

- thcontrolled entry ei a ir 'e c

RP/0/B/1000/17, Hazardous to esiablish and maintain sthstance or flessemble sh substance Release cold sM tdo m '

into eny eron of the plant which prevents the W Ntican of agaipment necessary to astelish and saintAin hot shutdown l

r

y

,.m.

ENCLOSURE 4.1.10 CMIP-12 OTHE3t ABNORMAL PLAffT CONDITIONS PAGE 12 of 13 tha3SUAL EVENT ALERT-SITE AREA EN{;XMCY_

GENERAL EfERGENCY 1.

EECS INITIATED 1.

STKR PLApff CIDeITIOts CKIST 1.

tffER PLANT CtDOTTItH5 EXIST 1.

ODER PLANT CIDWITIIDES EXIST 1 MAT 94 ARRANT PetECFJfftDe4RY TMAT tetRRA88T CUtSSIFICATitM OF A FIRDI DetATEVER SERNICE TMAT MAKE '

OPECATING PODE: PEDER OPERATIEDs CLASSITICATICD6 OF AN ALERT '

STTE AREft EM RGOdCY Pmm E A RELEASE tw e ascr ApetDffS OF RADIOACTIVITY IN A

- Es systent s ) required to be

- Emergency Coordinator

- Eme+gency Coordinator or Trecovery

$sd0RT TDE PERIOD operable per TS judonent Manager, @ t

- Emergency actions per the Aae AutorinIIE or manual ES 2,

EviE11AT10N t$ EIDERDL 8tO(M 2.

EVAtllATItSt OF CIDrnt0L Rourt '

EOP' inadequate core cooling section are snsuccessful -

actuation on VALID sispal or indica tion

- Evaasetion of Control Room

- Evacuatiors of Control Room CETC > 1200*F l

Ace A0e Hater inJ'ected to RCS or core' thii beidmaintained at hot

• Ae as a result of ES actustion deutdcmas from the Auxilisry Unit camot be maintained at shutdcom Panel hot shutdown from the i

2.

LOSS or CIDITADeENT INTECRITY auxiliary dustdan panel ef etIIRING SIUTD(Det BY TS 3.

tBSS of a M N

- Unst shutdawn initiated per iPERATING PEMIE: eFTT SSRJTD(Det l

TS 3.o IContairenant InlagrityI H5tu MBER OPERAfftDG

- Loss of $0% or siore of a 3.

1055 0F ES FEATUtE OR FIRE unit's applicable statalarm l

PRDIYCTION SYSTEM INCTION panels for > 15 minutes l

Rf ER.f1RDeG SteJTD0 Bet SY TS APPLICABl_E STATAUuet PADELS

- thit staatdown initiated per TS 3.3 (ES systems )

tMIT 3A3 ISAl-9, 14-16, 18

- thit dutdown initiated per 3 sal-9, 14-16, 18 TS 3.17 (Fire PrMactiers Systems inclurles flecwee tDGT 2 Hydroe found inoperable 2 sal-9, 14-16 I

i

- - + -

h a

f py y-.

a m

n ORP-11 EtttC5URE 4.1.19 PAGE 13 of 13 OTNER ABM08P%L PLANT CMIEN '

GEIERAL EVERGE8CY Af 7RT

$1T{ ANEA E9ENGENCY

_ tMELL EVENT 4.

SISMf1CJP',f ifES OF 25M35BGET 3.

M StittAEBE N -

em ChvACATitst CareLItJTY

- TB flood reonrtre use of AP/1.2.3/A/17th*10 ph e

- Loss of accident muz3itoring in-b irollable Flooding of I.

stes.sientation tTable 3.5.6-1)

Turtrine Building I

and snit slutche initiated per TS 3.5.6

- Loss of OPG comentmicetions espability with all offsite A m ies from the control Room 5.

TWST96ff OF PERSEBSEL AT.

OFfSITE 805PITAL

- Dec#.eeninntion of forts fail to nch extemm1, contmknation below 150 wse beta gassen Age Health Phics detemifws that radiologit.a1 controls are recnired for offsite medical treatment

- Intemel cetamination requiring medical assessment /

treat = nt

- Extemm1 agosure requiring medical essessment/trem nant o

l l

r g; p

CMIP-12.2 Page 1 of 1 AREA MONITORS Mr/Hr Monitor l

Numben Unit 1 Un't_2 Unit 3 RIA-1 IL000 35,000 (RB) RIA-4 40,000 55,000 80,000 RIA-7 25,000 RIA-8 40,000 RIA-9 15,000 RIA-10 15,000 35,000 50,000 RIA-11 10,000 20,000 RIA-12 35,000 40,000 RIA-13 45,000 50,000 RIA-15 NIS 25,000 RIA-19 20,000 PROCESS MONITORS CPM Monitor i

Number Unit 1 Unit 2 Unit 3 RIA-31 1,000,000 1,000,000 (RB) RIA-47 10,000,000 10,000,000 1,000,000 (RB) RIA-48 10,000,000 10,000,000 1,000,000 (RB) RIA-49 1,400,000 1,400,000 1,000,000 (RB) RIA-49A 5,000 5,000 RIA-51 1,000,000 1,000,000 110,000

-. _ _, _