ML19353B097

Rev 6 to CMIP-11, Classification of Emergency for McGuire Nuclear Station

ML19353B097
Person / Time
Site:	McGuire, Mcguire
Issue date:	12/07/1989
From:	Harris R, Tucker H DUKE POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CMIP-11, NUDOCS 8912110190
Download: ML19353B097 (32)

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DUME POWEn Goxiwxy NUG1JsAH PHODUGTION del %HTMENT i

l'.O. DOX 33111D,422 Mot' Tit 011U14018 NTita'.1:T CitAlt1DTTI'., N.(L Ull242

. (704) ara 40.i December 7,-1989

r U.

S. Nuclear Regulatory Commission Document Control Desk washington, D. C.

20555

Subject:

McGuire Nuclear Station Docket Non. 50-369 and 50-370 Catawba Nuclear Station Docket Nos. 50-413 and 50-414 Oconee Nuclear Station Docket Nos. 50-269, 50-270 and 50-287 Crisis Management Implementing Procedures Gentlemen Attached for NRC use and review is Revision 6 dated November 30, 1989 to the Duke Power Company Crisis Management Implementing Procedure CMIP-11 (Classification of Emergency for McGuire Nuclear Station).

By copy of this letter two revisions are being provided to NRC, llegi on II, Atlanta.

Very truly yours, s

Hal B. Tucher, Vice President Nuclear Production KLC kic attachment s

8912110190 891205

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.PDR ADOCK 05000369' l

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PDC

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TABLE OF CONTENTS

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Volume 2 Tab Procedure Description f

CMIP-8 Oconeo Crisis Phone Directory (Rev. 25)

CMIP-9 McGuire/ Catawba Crisis Phone Directory (Rev. 31)

CMIP-10 Emergency Classification - Catawba (Rev. 2)

CMIP-11 Emergency Classification - McGuire (Rev. 6) i CMIP-12 Emergency Classification - Oconee (Rev. 5)

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. 0)

CMIP-15 HRC Notification Requirements (Rev. 3)

I' N CMIP-16 Crisis Management Data Transmittal System

(_-)

Access from the Crisis Management Center -

(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)

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

CMIP-21 Quarterly Inventory Equipment Check (Rev. 29)

CMIP-22 Telephone Number Updates (Rev. 1)

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December 1, 1989

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5 CRISIS MANAGEMENT IMPLEMENTING PROCEDURE

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CMIP-11 L

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Classification of Emergency for McGuire Nuclear Station Rev, 6 November 30, 1989 i

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CLASSIFICATION OF EMERGENCY FOR

(

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McGUIRE NUCLEAR STATION N/

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 of safety of the i

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 V

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, i

1.4.2 Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite 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.

O If a change in the emergency class is made, perform steps 2.2, 2.3, G

and 2.4 below.

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t 2.2 Instruct the State / County Communicator to notify the state (s) and (o) counties per CMIP-13 of any change in the emergency class.

If the emergency class is SITE AREA EMERGENCY or GENERAL EMERGENCY, v

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.

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 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 EN_ CLOSURES N

4.1 (Q

Emergency Event List for Emergency Classes Event No.

Pace (s) 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 Hazards 16-18 4.1.10 Other Abnormal Plant Conditions 19-23

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4.2 Engineered Safety Features i

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O IRfCLEAR STATIGI DOI BERG 01CY ACTION LEVELS B ICLDSU E 4.~1-EVOIT# 4.1.1 PRIftMtY C00UWT LEAK PAGE 10F 25 NDTIFICATION OF ALERT SITE AltEA BERGDICY G010tAL UNUSUAL EVOIT BERGDICY

1. Any NC system leakage

1. ' Any IIC system leakage

1. Any NC system leakage

1. Any LOCA with failure greater than Tech Spec greater than 50 gym in greater than available of ECCS i

limits in flodes 1-4.

flodes 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.

AND

+ LOCA with failure of i

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

+ Greater than 10 gpm Leak cannot be isolated unisolable steam line recirculation i

identified NC system within 15 minutes.

break outside leakage containment and AND

2. S/G tube leak with indication of fuel i

AND loss of offsite power damage.

NC subcooling cannot be maintained greater than i

Load reduction or plant

• S/G tube leak greater

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

cooldown initiated than 10 gpm than 50 gpa 3

pursuant to Tech Spec

+

LOCA l

j 3.4.6.2.

AND AND AND o Greater than 500 gpd NC subcooling greater Unisolable steam line

'l 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 1

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

i 3.4.6.2.

END

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-m IRICLEAR STATI(Ni Ott BERGBICY ACTICII LEVELS BI N 4.1 EVBIT# 4.1.1 PRIftnitY C00UWIT LEAK PAGE 2 0F 25 IIDTIFICATICII 0F ALERT SITE AREA BERGBICY GBERAL INRISUAL EVBIT BEMBEY

+ Greater than 1 gpm

3. S/G tube leak with an

2. LOCA with initially total. tube leakage in unisolabla steam line successfe! ECCS all S/G's.

break outside folleued by failure of containment.

ECCS heat sink and AND failure of containment

+ S/G tube leak heat removal.

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

+

LOCA 3.4.6.2.

NC subcooling greater AND o Any NC system pressure than D Deg F boundary leakage in Loss of recirculation I

modes 1-4.

AND heat sink AND Unisolable steam line AP80 4

break outside Load reduction or plant containment loss of containment cooldown initiated spray heat sink i

l pursuant to Tech Spec

+ Unisolable steam line 3.4.6.2.

break outside contain-END ment l

0 Greater than 1 gpm leakage from any NC AND pressure isolation l

valve at 2235 psig Field monitoring teams in modes 1-4 detect activity at the protected area fence at t

AND greater than or equal to 2 mrem /hr whole Load reduction or plant body.

cooldown initiated pursuant to Tech Spec END 3.4.6.2.

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IRfCLEAR STATIGI DII GEREBICY ACTIGI LEVELS BIN 4.-1 EVOITF 4.1.1 PRIIWWY C00UlflT LEAK PAGE 3 0F 25

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3 IIDTIFICATIGH OF ALERT SITE AREA DERGBICY GOERAL UIIUSUAL EVBfT BEMiBICY I

+ Greater than 40 gpm l

controlled NC system j

leakage at 2235 psig i

in modes 1-4.

AND I

Load reduction or plant cooldown initiated l.

pursuant to Tech Spec 3.4.6.2.

2. Any unisolable IIC system leakage greater than 50 gym in Modes 5 and 6.

3. Failure of an unisolabie PZR PORV or safety valve to close following a reduction of IIC pressure.

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IRfCMAR STATION DIIP-1 EERGOICY ACTIGI LEVELS Eur1rmsar 4.1 -

EVENT # 4.1.2 FUEL DAMAGE PAGE 4 0F 25 NOTIFICATION OF ALERT SITE AREA EERGOICY GBIERAL UNUSUAL EVENT EEREDICY

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.

4

• Greater than 1.0 times background set-

+ Average of five highest microcurie per gram points of any contain-core exit T/C'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 (Sla cooldown initiated entry into Degraded or 51b) valid reading pursuant to Tech Spec

+ Chemistry analysis 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)

+ Dose equivalent I-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 analy:is 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.

+Cgntainmentatmosphere Load reduction or plant

• Containment EMF's (51a H concentration cooldewn 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.

NUCLEAR STATIM ~

OtIP-1 BERGBICY ACTION LEVELS ENCLO5W E 4.1 EVBITF 4.1.2 REL DlWIGE PAGE 5 0F 25 i

NDTIFICATION OF ALERT SITE AREA BERGBICY GBERAL UNUSUAL EVBIT B E M BICY

+ Specific activity _

B. Loss of or threat to greater than 100/E barrier microcuries per gram per Chemistry analysis.

+ Incomplete containment j

integrity i

AND

• Known containment leakage in excess of Load reduction or plant Tech Specs.

cooldown initiated pursuant to Tech Spec

+ Containment atmosphere 3.4.8 H" concentration greater than or equal to 9%.

END

+ Containment pressure-greater than or equal to 60 psig.

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END B

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WCLEAR STATI(NI OSIP-I v '

genRICY ACTI(NI LEVELS EN 4.1 '

EVBfT# 4.1.3 STENI SYSTDI FAILURE PAGE 6 0F 25 IIDTIFICATION OF ALERT SITE AREA DERGOICY GUERAL INIUSUAL EVOIT BEMBICY l

1. Steam line break which

1. Unisolable steam line

1. Unisolable steam line N/A results in rapid break outside break outside depressurization of containment with a S/G containment with a S/G I

the secondary side.

tube leak..

tube leak and

)

indication of fuel 2

+ Steam line

.+ Unisolable steam line' damage.

depressurization break outside resulting in safety containment.

+ Unisolable steam ifne injection or main steam break on the affected i

isolation AND S/G outside j

containment.

1 END NC subcooling greater than or equal to O AND i

degree F.

S/G tube leak greater AND than 50 gps.

I S/G tube leak AND j

greater than 10 gpm.

Fuel damage as j

+ Unisolable steam line determined by Event break outside 4.1.2.

containment.

END AND 4

Field monitoring teams l

detect activity at the protected area fence at j

greater than or equal l

to 2 mrem /hr whole j

body.

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EVBIT# 4.1.3 STEAN SYSTBI FAILURE PAGE 7 0F 25 IIDTIFICATION OF ALERT SITE AREA BERG 01CY GBERM.

tNIUSUAL EVBIT B E M ERICY

2. Steam' line tweak with failure of ECCS or 4

ESF.

1

+ Steam line i

depressurization resulting in safety I

injection signal.

AND Failure of both trains of ECCS injection.

+ Steam line depres-surization resulting i

in Main Steam Isola-l tion signal.

AND 4

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

1 END l

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4 IWCtFAR STATIGI 1

BElE01CY ACTIGI LEVELS E N 4.1 EVOIT# 4.1.4 HIGI 1RADIATIGH/ItADIOLOGICAL EFFLUENTS PAGE 8 0F 25.-

NOTIFICATION OF ALERT SITE AREA DIEIEDICY GBI0tAL l

UNUSUAL EVOIT DERGOICY

1. Liquid or gaseous

1. High radiation levels

1. Accidental releases of

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

contamination f

Limits as determined

+ EMF-37 Trip II alarm.

• EMF-37 Trip II alarm.

by RP or Chemistry

+ Any valid EMF reading Procedures.

greater than or equal AND AND to 1000 times trip I l

END setpoint EMF-36L reading greater EMF-36H reading greater than 6.3E5 cpm.

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 WB or 250 1 Rem WB mrem /hr thyroid for 30 minutes O_R

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

• Dose calculations or measure activity at the field monitoring team Site Boundary greater measurements 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 minutes.

_OR END 5 Rem thyroid END

O

.A IRICtfAR STATI(NI

&11 BEMiBICY ACTI(Ni LEVELS AN1mMEF Q.1

• EVOIT# 4.1.5 LD55 0F SIRITDMAI RSICTICIIS PAEiE 9 0F 25

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HDTIFICATION OF ALERT SITE AREA BERiiDICY EiBERAL UIIUSUAL EV9fT SEREiBEY 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 CH maintain core cooling hot shutdown systems followed by in modes 5 and 6.

conditions failure of heat I

removal capability for j

+ Failure of heat sink

+ Failure of heat sink an entended period.

j results in the loss of results in the l

NC System subcooling.

inability to maintain

• Loss of CM/CF feedwater hot shutdown.

flow capability.

2. Transient with failure i

of the Reactor Protec-AND AND tion System to auto-natically initiate and NC subcooling cannot be CA flow cannot be i

complete a Rx trip maintained greater than established within 30 which brings the O Deg. F.

minutes.

Ileactor Subcritical 3

(ATWS Event)

AND

• Inability to feed END S/G's from any NC system feed and l

source in Mode I-3.

bleed cannot be established or AND maintained.

f, NC subcooling cannot be l

maintained greater than O Deg. F.

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NUCLEAR STATION 1

DENGOICY ACTION LEVELS DEsnasar g.1

• EVENT # 4.1.5 LDSS OF SHUTDIESI FUNCTIONS PAGE 10 0F 25 9

NOTIFICATION OF ALERT SITE AREA DENGDICY GBIDIAL UNUSUAL EVENT BENGBICY

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 failure 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).

(ATWS 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.

(

i AND AND 1

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

minutes.

l AND l

l Plant conditions re-quire entry into EP/ lor 2/A/50C0/12.1 (Response to Inade-i l

quate Core Cooling).

i

WCLEAR STATIM 11.

I-BEMiBICY ACTIM LEVELS DELD5M E 4.1*

EVENft 4.1.5 LD55 0F SIRITDIRSI RNICTI(NIS PNE 110F 25 l

IIDTIFICATIGH OF ALERT SITE AIIEA BERGOICY GBERAL UNUSUAL EVOIT DIDuiBICY

3. Inability to maintain

- 3. Loss of heat sinet with I,

cold shutdown with s W core i

loss of reactor vessel uncovery in flodes 5 coolant inventory in and 6.

flodes 5 and 6.

• Failure of heat sink-

+ Failure of heat sink causes loss of cold causes loss of cold shutdown conditions in shutdown conditions in modes 5 and 6.

modes 5 and 6.

4 AND j

AND Lower Range RVLIS level Lower Range RVLIS level indicates core remains decreasing after inita-substantially uncover-tion of NC System ed (less than 43%

Makeup.

level).

+ Failure of heat sink causes loss of coTd shutdown conditions in modes 5 znd 6.

4 AND NC System narrow range level less than 14 inches and decreasing after initiation of NC System Makeup.

+ Failure of heat sink causes loss of Cold Shutdown conditions in modes 5 and 6.

AND

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WCLEAR STATION 11 B G GENCY ACTIM LEVELS ENCtD5W E 4.1*

EVENT # 4.1.5 LDSS OF SWTDERM FUNCTIONS PAGE 12 0F 25 NDTIFICATION OF ALERT SITE AREA B U GENCY GENERAL UNUSUAL EVENT D H GENCY

+ Failure of heat sink causes loss of cold Either Train ultrasonic shutdown conditions in level indication less modes 5 and 6.

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

Core Exit T/Cs indi-cate superheat at the 4

+ 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 Level 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 shutdown conditions 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 applicable data book curve.

curve.

1 END y

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3 IRfCLEAR STATI(NI o

d._.-11 DOGBICY ACTI(NI LEVELS Fuer1 maser '4.1

. EV0fif 4.1.5 LOSS OF SIRITD(NSI RBICTICIts PAGE 13 0F 25 NDTIFICATION OF ALERT SITE AftEA BUGBICY GBERAL INRISUAL EVOfT 4

BEEiBEY ANO

$l NC System level below

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bottom range of avail-i able level indication.

4 AND I

Emergency Coordinator judgement that core uncovery is imminent.

i h.

END t

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WCLEAR STATIM 1

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BEMENCY ACTI(NI LEVELS Eursanser 4.1

• EVENTS 4.1.6 LOSS OF PERER PAGE 14 0F 25 NOTIFICATION OF ALERT SITE AREA BERGBICY GHENAL UNUSUAL EVBIT BENmarY

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 power with total o Both unit.related main than 15 minutes in then 15 minutes in loss of 5/G's feed bus lines de-energized.

Modes 5 & 6.

Modes 1-4.

capability in Modes in modes 1-6.

1-4.

• Both 4169 V essential

+ Both 4160 V essential

2. Loss of onsite AC buses are A A rgized buses are de-energized

• Both 4160 V essentia?

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 1-4.

in modes 1-4.

6.

O 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 i

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.

essential busses in

& 6.

l modes 1-4.

+ Both unit related EVDA AND

+ Both unit related EVDA and EVDD buses l

3. Loss of onsite AC and EVDD buses de-energized for CA flow cannot be j

power capability in de-energized for greater than 15 established within 30 i

Modes 5 and 6.

greater than 15 minutes in Modes 1-4.

minutes.

minutes in meezs 5 and i

o Both D/G's are 6.

END END l

incapable (for greater j

than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) of END i

powering the 4160 V essential busses in modes 5 and 6.

END t

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MK3. EAR STATIENI 1

DEMEIET ACTI(M LEVELS

'4. I -

• EVBIT# 4.1.7 FIES AIS SECURITY ACTI(NES PNE 15 0F 25 NOTIFICATION OF ALERT SITE AKA BENGBICY EiHERM.

INRfSUAL EVBIT BENEIEY

1. Fire within the plant

1. Fires defeating safety

1. Fire compromising the

1. Amy major fire or se-(see Note) that takes system functions required functions of shutdown carity threat which more than 10 minutes for current operating mode.

systems.

could cause messive to extinguish.

common demoge to

+ Fire resulting in

+ Fire that results in plant systems.

2. Security threat.

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

2. Less of physical i

o Discovery of bomb feated or fire defeats the control of the plant.

within the site single operable train).

AND boundary.

+ Physical attack on the l

+ Fire requiring Control NC subcooling cannot be plant (see Note) has o Civil disturbance Room evacuation maintained greater than resulted in occupancy (hostile) 0 degrees F.

of the control room or AND auxiliary shutdown j

o Intrusion / Attempted panels by unauthorized Intrusion (Protected Control established (or

• Fire reouiring Control personnel.

Area) in process of being Room evacuation established)'from the END 1

o Hostage Standby Shutdown AND situation / extortion Facility (SSF).

Cor. trol cannot be o Security threat as established from the Stand-determined by Emergency by Shutdown Facility (SSF).

Coordinator and Security AND l

END NC subcooling cannot be maintained greater than NOTE: Plant is defined 0 degrees F.

as: Aux. Bldg, TB, SB, RB, D/G Rm, Doghouses, SSF, Interim Radwaste Facility

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IRfCLEAR STATI(NI-11 b1 BEIEEBICY ACTI(NI LEVELS BELOM '4.1 "

EVENT # 4.1.7 FIltES Afe SECURITY ACTICItS-

. PAGE 16 0F 25 '.,

g WJTfFICATION OF ALERT SITE AREA BERGBICY GEIERAL UHuiUAL EVBIT BERGBICY

2. Ongoing Security

2. Imminent loss'of.

compromise.

physical controlLof~

a plant vital area.

+ Adversaries commandeer-

an area of the. plant

+ Physical attack but do not control any resulting in imminent-plant vital areas.

occupancy of the Control Room or i

+ 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

+ Ongoing security I

compromise as i

determined by Emergency Coordinator and Security END t

i t

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e IRICLEAR STATI(N1 1

1 'g BERGENCY ACTI(B1 LEVELS O N 4.1 EVENT # 4.1.8' SPENT FUEL DAMAGE PAGE 17 0F 25.

NOTIFICATION OF ALERT SITE AREA BERGENCY GENERAL UNUStRL EVENT BENiENCY N/A

1. Damage to Spent Fuel

1. Major damage to spent N/A with release of fuel with release of radioactivity.

. radioactivity CONTAIISENT CONTAll0ENT

+ Valid Trip II Alarm

+ Valid trip II Alarm on IEMF16 or 2 EMF 3 on IEMF16 or 2 EMF 3 AND AND-Dose rate calculations Dose rate calculations i

using vent sample using unit vent sample l

analysis and flow rate analyses and flow rate data are in excess of data equivalent to:

10 times limits established by Greater than or equal Technical to 50 mrem /hr WB or 250 Specifications mrem /hr Thyroid for 30 minutes at the site.

l FUEL HAfBLIl0G BUILDIllG boundary l

+ Valid Trip II Alarm FUEL HAfBLING BUILDIllG 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 f

Specifications Greater than or equal-to 50 mrem /hr WB or 250 l

END mrem /hr thyroid for 30 l

minutes at the site boundary END i

..m -m.

. m

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~

NUCLEAR STATION L /11 -

BERGENCY ACTION LEVELS BICLOSURE 4.1 EVENT # 4.1.9 NATURAL DISASTERS Als OTER HAZARDS

PAGE 18 0F 25 NOTIFICATION OF ALERT SITE AREA BERGENCY GBERAL UNUSUAL EVENT BEMBICY

1. Earthquake felt in

1. Earthquake greater

1. Earthquake greater

1. Any major natural er.

plant and detected by than OBE

~

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 " strong design ievels) which motion accelerograph"

+ Greater than 0.053 g AND could cause massive Vertical-common 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 i

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 j

3. Any tornado / severe inability to maintain AND weather within the cold shutdown in modes i

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 fl amable gas.

er than 0 degrees F.

AND

+ Uncontrolled entry of

2. Damage from toxic substance or tornado, severe Physical damage flammable gas into any weather, missile, observed to plant area which explosion, aircraft equipment / structures jeopardizes the crash,-or train i

within the site operation of systems-derailment causing a boundary needed to maintain loss of functions cold shutdown in Modes needed for plant hot 5 and 6.

shutdown.

END

- i

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yon,

o a lefCLEAR STATION 3II' BERGENCY ACTION LEVELS BICs smar 4.1

EVENT # 4.1.9 NATURAL DISASTERS AIO OTIER HAZARDS PAGE 19 0F 25 NOTIFICATION OF ALERT -

SITE AREA BERGOICY GBERAL UNUSUAL EVENT BEMBICY

+ Sustained (greater than

+ Failure of heat sink 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 source in

4. Aircraft crash Modes 1-i.

+ Aircraft crash within AND the site boundary.

NC subcooling cannot be

5. Train derailment on maintained greater than site.

O degrees F.

+ Train derailment

3. Release of toxic or resulting in physical flammable gas (Modes damage to equip-1-4).

ment / structure within site boundary.

+ Uncontrolled entry of toxic substances or

6. Explosion within site flammable gas into any boundary.

plant area which prevents the operation o 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

u

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4og4 IRfCLEAR STATI(NI 1-m BERGBICY ACTION LEVELS' B N 4;1*'

EVENT # 4.1.9 IIATURAL DISASTERS Alm OTIER HAZARDS PAGE 20 0F 2E NOTIFICATION OF ALERT SITE AREA BERGBICY GBERAL UNUSUAL EVENT BEIEBICY j

l

7. Release of toxic or l

flammable gases.~

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

I o Release of flamable gas resulting in any evacuation within the Protected Area.

l END i

i I

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_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _. _ _ _ _ _ - _ _ _ _ - _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ = _ _ _ _ _ _ _ _. _ _ _ - - _ _ _. _ _ _ _,. - - _...- a

c A IRfCLEAR STATI(NI g11:

.g BEMGBICY ACTION LEVELS BICs maEF i1 EVENT # 4.1.10 UTIER AINI0lWI4L PLAIIT COIR)ITI(NIS

- PAGE 21 OF 25..:

NOTIFICATION OF ALERT SITE AREA BERGBICY GBERAL UNUSUAL EVENT BEMiBICY

1. ECCS initiated.

1. Evacuation of Control 1.. Evacuation of Control

1. Other unit conditions-Room Room exist, from whatever

+ Valid S/I signal so m e, that in the.

I j

' verified by redundant

.+ Evacuation of Control

+ Evacuation of Control judgement of~the indication Room Room Recovery Manager make release of 1

AND AND AND large amounts of radioactivity in i

discharge into the Control established (or Control cannot be a short time vessel in process of being established from the period possible.

established) from the auxiliary shutdown i

2. Abnormal coolant Auxiliary Shutdown Panel panel or SSF END temperature and/or pressure or abnormal

+ Inability to establish AND fuel temperature control from Auxiliary i

Shutdown Panel.

NC subcooling cannot be

+ Figure 2.1-1 Tech Spec maintained greater than t

exceeded in modes 1 and 2.

AND 0 degrees F.

1

+ Core sub-cooling margin Control established (or

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

("Subcooling Margin established) from.SSF.

l Alert" annunciator).

AND

+ 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 ca@Hty -

l 3, 4, and 5.

in s 1 '

2. Other unit conditions exist that in the

+ Loss of 50% or more of judgement of the the control room i

Recovery Manager annunciators for warrant declaration greater than 15 of site Area Emergency.

minutes in Modes 1-4.

END i

i 4

I

IRACLEAR STATION 1-

.70-F BERGBICY ACTION LEVELS ENCIASIIRE 4.1' EVENT # 4.1.10 OTHER ABN0lWIAL PUUIT COISITIONS PAGE 22 0F 25,

l NOTIFICATION OF ALERT SITE AREA EMIIGOICY GBERAL i-UNUSUAL EVENT BIERGBICY 3.

Loss of containment

3. Other unit conditions integrity requiring exist that in-the shutdown by Tech Spec

, judgement of.the Shift Supervisor / Emergency o Any automatic Coordinator warrant containment isolation declaration of the valve open and Alert classification.

inoperable and

~ unisolable.

END AND i

o Load reduction or plant cooldown initiated 4

pursuant to Tech Spec i

3.6.3.

4 j

o Both air lock doors i

of a single airlock inoperable l

AND o Load reduction or plant cooldown initiated pursuant to Tech Spec 3.6.1.3.

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.IRICl. EAR' STATION '

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1' EDERGENCY ACTION LEVELS E N 4.1-EVENT # 4.1.10 UTHER ABNDIBI4L PLANT CGIBITIONS PAGE 23 0F 25.,s.-

NOTIFICATION OF ALERT-~

SITE AREA EDERGBICY GENERAL

'Se UliUSUAL EVENT BERGENCY

4. Loss of ESF or Fire Protection System function.

l

+ Both trains of any ESF system found inoperable i

(if caused by fire, see 3

event #4.1.7 - Fires and Security Actions, Alert Classification).

AND i

i Load reduction or plant t

cooldown initiated in t

accordance with Tech Specs.

I o less than minimum channels of ESF func-j tion inoperable.

I AND t

Load reduction or plant l'

cooldown initiated in accordance with Tech i

Specs.

+ Loss of all main fire protection system water pumps.

9

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IRfCLEAR STATI(NI

^ L. Al

. %c BERGBICY ACTIO11 LEVELS BICIfMEF G.1 i

EVBIT# 4'.1.10 OTHER AINIDINIAL' PLAffT COWITICIts PAGE240F.25[,.'

e.

IIOTIFICATION OF ALERT' SITE AREA BElIGOICY GBERAL UIRISUAL EVBfT BEMBICY

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 1

immediate medical attention and decon-tamination efforts are waived.

AND i

Radiation Protection personnel determine j

that radiological j

controls are required for offsite medical treatment

+ Internal contamination requiring medical assessment / treatment

+ External exposure requiring medical t

assessment / treatment I

[

l

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f'5,L j {ll: c, g. --

.o IRICLEAR STATION BERGENCY ' ACTION LEVELS

~ BEIDSWE 4.1.

EVENT # 4.1.10 OTHER ABIDIWI4L PLANT CGGITIONS -

PAGE'25 0F 251,4 NDTIFICATION OF

. ALERT SITE AREA BERGOICY GBERAL UhtlSUAL EVENT j

BERGBICY I

6. Significant Loss of assessment capability or conmunication capability

+ Loss of MNS communications capability with all offsite agencies

+ Loss of 50% or more of the control room annunciators in Modes 5, 6 for greater than 15 minutes.

+ Loss of all onsite j

meteorological instrumentation j

AND l

Inability to contact the National Weather

(

Service for backup source of data.

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

Emergency. Coordinator warrant increased awareness of local authorities.

END

CMIP-11:.

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i..2'

.Page 1 of 1 i

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ENGINEERED SAFETY FEATURES

.1)- Containment Spray

2) Containment Air Return and Hydrogen Skimmer

?

3) Ice Condenser

4) Hydrogen Control (Hydrogen Recombiners Only)

D

5) Annulus Ventilation l

L

6) Auxiliary Feedwater

7) Nuclear Service Water 8)-Component' Cooling

-9) Steam Line/Feedwater Line Isolation

/N

.10) Containment Pressure Control

)

l- #

11). ESF Interlocks

12). Turbine Trip

13) Reactor Protection System

14) Emergency Diesel Generators l.

15). Emergency Switchgear 3

l-L

16) Loss of Power Actuation Circuit 17)- Emergency Core Cooling System - Safety Injection, Residual Heat Removal, L

Cold Leg Accumulators, Upper Head Injection,. Chemical and Volume Control

. System, Automatic Switchover i

l

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

l.

.LJ

_