ML20087F393

Public Version of Rev 13 to Crisis Mgt Implementing Procedure CMIP-11, Emergency Classification - Mcguire. W/ 920121 Release Memo

ML20087F393
Person / Time
Site:	Oconee, Mcguire, Catawba, McGuire
Issue date:	12/11/1991
From:	DUKE POWER CO.
To:
Shared Package
ML20087F358	List: ML20087F355 ML20087F393
References
CMIP-11-01, CMIP-11-1, NUDOCS 9201230129
Download: ML20087F393 (37)

Text

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DUKEPOWERCOhPkNY CRISIS MANAGEMENT IMPLEMENTING PROCEDURES I

December 11, 1991 l

92C1230129 920102 PDR ADOCK 05000269 PDR p

4 TABLE OF CONTENTS

( Volume 2 Tah Procedure Descriution CMIP-8 Oconee Crisis Phone Directory (Rev. 32)

CMIP-9 McGuire/ Catawba Crisia Phone Directory (Rev. 40) -

CMIP-10 Emergency Classification - Catawba (Rev. 4)

CMIP-11 Emergency Classification - McGuire (Rev. 13) 2MIP-12 Reserved for Future Use CMIP Notifications to States and Counties from the Crisis Management Center (Rev. 24)

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

CMIP-15 Oconee CMC Initial Activation - (Rev. 0)

CMIP-16 Crisis Management Data Transmittal System Access from the Crisis Management Center -

-(Rev. 11)

CMIP-17 Reserved for futare use-CMIP-18 Maintaining Emergency Preparedness (Rev. 5)

CMIP-19 Communications Test for McGuire/ Catawba CMC (Rev. 17)

CMIP-20 Communications Test for Oconee CMC (Rev . 11)

CMIP-21 Quarterly ' .entory Equipment Check (Rev. 37)

CMIP-22 Telephone Number Updates (Rev. 3)

December 11, 1991 l

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CRISIS MANAGEMENT IMPLEMENTING PROCEDURE i-CMIP-11 i-

Classification of Emergency for McGuire Nuclear Station I

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Rev. 13 December-11, 1991 t

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- - CMIP-11

_ (= .CLAS$1FICAT10N OF EMERGENCY FOR McGUIRE NUCLEAR STATION 1,0 SYMPT 0MS 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 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 occur _ red which involve an actual or potential substantial degradation'of the. level of safety _of-the plant.

1.E.2 Any. releases'are expected to be limited to small fractions-of the. EPA Protective Action Guideline exposure levels.

1,3 Sit.e Area' Emergency 7V 1,3.1 Events are-in process or have occurred which involve actual or likely' major failures of plant functions needed

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- 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 meltir.g with potential for loss of containment-integrity.

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

-more than the immediate site area.

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,

>j-and 2.4 below.

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4 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 the Emergency, compare plant conditions to the Initiating Conditions of Enclosure 4.1. To terminate the emergency,  ;

refer to the Termination Critoria in Enclosure 4.3.

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 E_!!C.LOSURES

- 4.1. Emergency Event List for Emergency Classes i-( 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 8-10 4.1.5 Loss of Shutdown Function- 11-15 4.1.6 Loss of Power 16-17 4.1,7 Fires and Security Actions 18-19 4.1.8 Spent T 1 Damage- 20-22 23-24

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4.1.9: Natural Disasters and Other Hazards 4.1.10 Other Abnormal Plant Conditions 25-29 k

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.4.2 Engineered Safety Features

({,i 4,3 Termination Criteria

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fl CMIP-11 m:cantE sectmut stATroN -r- 4.1 arutacanCY AcTlom I.EvELs FACE 1 OF 29 EVE 3ff 8 4.i.1 F9tDeutY N ART EXAE SITE AREA EMERGENCY CENE3tAL BKRIFIC& TION OF AIJUtf ENERGENCY UNDSUAL EVENT

1. Any NC systems 1suhage 1. Any IACA with failure of

1. Amy WC system leakage 1. Any WC systems leaharya BCCS greater than 50 gpa resulting in toes of greater 1-han Tech Spec 12 Modes 1-4. subcooling in Modes ilmits in Modes 1-4. 1-4.

• LOCA with failure of both O Grcster than 1 gpm trains of ECCS injection unidentifLed NC system e MC systeen leakage greater than 50 gpm in

• SI actuated or AND lockage in modes 1-4.

mades 1-4. required in Modes 1-4 AND AND NC subcooling cannot be AND maintained greater than O Lord reduction or plant Existing NV, NI and ND Deg. F.

cooldown initiated pursuant NC subcooling greater to Tech Spec 3.4.6.2. than O Deg. F. flow cannot maintain NC rubcoolknq greater AND than O Deg. F.

• LOCA with f ailure of both ,

trains of ECCS recirculation ,

O creater than 10 givn when recirculation required.

identified NC sy9tes leakage leak cannot.be isolated within 15 2. S/C tube leak with an AND ,

in modes 1-4.

sainutes .

unisolable secondary

,(main stem- or kI t NC subcooling cannot be AND feedwater) breal maintained greater than O

2. S/c tube leak with outside containment. Deg. F.

I Load reduction or plant

• cooldown init i4ted pureuant loss of offaite to Tech Spec 3.4.6.2. power.

+ Primary to cecondary leakage greater than

• LOCA

• S/G tube leak greater 50 gpn i 0 Creater than 500 gpd tube than 10 gpe AND leaksgo in any S/G in modes AND 1-4.

Plant conditions require AND_

Unisolable secondary entry into EP/1 or AND 2/A/5000/32.1 (Response to NC subcooling greater (main steam or Inadequate Core Cooling) than 0 Deg. F. feedwater) line break Load reduction or plant on the ruptured S/G cooldown initiated pursuant o'Itaide containment AND to Tech Spec 3.4.6.2.

Both Unit related main bus lines de-energized.

,+ 3r-tI CHIP-11 secounEt motsama starzam' meernacutE 4.1 EBERGEUICY ACTICE 12VELS PAGE 2 CF 29 EVENT ' S 4.1.1 FRDERY awwiin ney 33AE SITE AftEA N cEnEstAL NOTIFICATIOuB 0F AIJGtT ~ """"'""'Y . _ .

UNUSUAL EVENT

- 3. steem sy===rator tube 2. IACA with initially 0 Gr::cter than'1 gpm total 3. s/G tube leak'with an- leak with secoedary successful scCS followed by uniaolable escoedary failure of accs heat sink tube leakage in all S/G's in Line break outside line break inside modes 1-4. containment and and failure of contal===ot containment.. . indication of fuel best removal.

AND et== age.

Load reduction or plant

• S/G tube leak greater

• IACA than 10 gpm but less cooldown initiated pursuant than 50 gpm 4 Primary to secondary AND to Tech Spec 3.4.6.2. 1eakage greater than 50 gpo AND Loss of recirculation heat ,

0 Any NC syeten pressure AND sink NC sobcooling greater boundary leakage in modes 1- than O Deg. F AND

4. Unisolable secondary AND (main steam or Loss of containment spray ,

AND feedwater) break heat sink Unisolable secondary inside containment on lesd reduction or plant ecoldown initiated pursuant (main steam or the ruptured s/c END kI to Tech Spec 3.4.6.2. feedwater) line break AND outside containment on

' the ruptured S/G. Fuel clad failure O Gr' aster than 1 gym leakage greater than 5% per from any NC pressure chemistry analysis (or icolation valve at 2235 peig 4 Unisolable secondary (rnain steam valid reading on EMF-in modes 1-4. or feedwater)'line 51a or 51b of 117 break outside R/hr).

AND

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containment END Lo;d reduction or plant AND cooldown initiated pursuant to Tech Spec 3.4.6.2. Field monitoring teams detect activity at the protected area fence at greater than or equal to 2 sPRam/hr whole body..

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. _A sm; .m i l secotrutz nocsatan sThTICs CMIP-11 IgpennmarT ACTICE LEWlELS EBOC1 4 8 05tB 4. 1 EVEUIT # 4.1.1 FItDERRY CODEJharr LERK PACE 3 OF 29 SITE AREA E3EEBC150CT CEBWIEL

- NOTIFIchTICII OF ALERT EDEBEUIIBCY C150SuhL EVENT

'O creatcr than 40 gpus controlled NC syntsun leakage et 2235 pelg in modes,1-4.

AND Lord reduction or plant cooldown initiated purecant to Tech spec 3.4.6.2.

i 2. Any unimolable spC systen Jeakage greater than 50 gpus-in Modes 5 and 6.

3. Failure of an unisolable PS2 PORY or safety valver to close iollowing a reduction L*

of lec pressure.

END E

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1I CHIP-11 secaeram secxJuut sTaTrou ascroemer 4.1 unsassmCr acrios ramtLs FACE 4 OF 29 EVENT f 4.1.2 FUEL DAMAGE cmpumar, armar arTu Anna assear-==r r umacapCr morrrICnTrow or unusuAr. Everr

1. Degraded core with 1. Emes of 2 of 3 flesion

1. 90 r,ysta.a activity greater 1. Severe loss of feel poesible lose of g A t barriere with than Tech spec limits in cladding in teodes 1-cootable geoumetry. potentist for Ioes of 3rd 5.

Modes 1-5. barrier.

e valid increase of 1000 $ Average of five meres To clasef fy at this O Creater than 1.0 microcurie times background highest core exit per graan dose equivalent I- T/C's indicates level, at least com 131 for greater than 48 hre. setpoints of any greater than or equal condition from two of the continuous per chemistry containment radiation to 700 Deg. F. three cat ==gories (A,8,C) analysis in enodes 1-5. monitor in modes 1-5. must be satisfied and at least one consiition frtssa AND 4 Iener Range RVLIS less the third category meet be 4 Valid. increase of 1000 than 434 level during natisfied or have the Load reduction or plant times background a LOCA event. potential to be matLefied.

cooldown initiated pursuant setpoint of reactor to Tech Spee 3.4.8. coolant system process monitor (E'MF-48) in 4 RVLIS D/P setpoint at A. Imes of clad barrier modes 1-5. value which requires e Dose equivalent I-131 in ('

entry into Degraded excess of Tech Spec Figure core Cooling section 4 Total fuel clad failure

-3.4-1 per Chenaistry analysie e Chemistry analysis greater than 5s per indicates greater than of Emergency i.n tredes 1-5. Frocedures. Chemistry analysis.

or equal to 5% total AND fuel clad failure or increase of it fuel

• Containment hydrogen

• Containment EMF Sla or 51b Locd reduction or plant failures within 30 concentration greater valid reading of 117 PJhr cooldown initiated pursuant minutes in modes 1-5. .than or equal to 1% (equates to 51 fuel gap to Tech Spec 3.4.8. and increasing greater activity released to END than or equal to 0.1% containment) per hour. '

e Specific activity greater than 100/E eierocuries per

• Plant conditione require grr.:n per Chemistry analysis. 4 Containment mMF's (Sla entry into EP/1 or 2/A/5000/12.1 (mesponse to AMD

-~or 51b) valid reading Inadequate Core Cooling).

of 179 R/hr, Load reduction or plant BND cooldown initiated pursuant to Tech Spec 3.4.8 ENO

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C4IP-11 m sors === snTIoss unrs nauss: 4.1 anstmassser Acrrous Izents PAGE 5 OF 29 EvsDET 4 4.1.2 FUEL DflsEAGE GEEBERAL AL30tT . bIM AREA EsEPJGENCY HOTIFICRTICEt Or Emmecumcr owesuaL EvuxT

! s. rose of anactor coolant System barriec

• Deactor coolant system leak (including s/c tube leak) greater than 50 gpa.

C. Loes of Conta f ====et Barrier

• Inc M iete contsinnent integrity i

^ itnown containment leakage in ,

axcess of Tech specs.

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e containment pressure greater l than or equal to 60 peig ,

e containment atmosphere He concentration greater than or equal to 94

• Unisolable secoMary (main steam or feedwater) break outside contairroent on the ruptured S/G with S/G tube [

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1eak greater than 50 gym EttD

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, ge necewIEE anceme STATICE CMIP-ll EBERCEBICY ACTICK 12VELS EIsr rsusser 4.1 EVENT # 4.1.3 STEAft SYSTEM FAII,UBIE PACE 6 or 29 IUUTIFICATION Or - AIERY - SITE AftEA EplE5eEN8CT CM 098 USUAL EVENT hN

1. Secondary (anain steem or 1. Unisolable secnadary 1. Unisolable % N/A feewtwater) line break which (main steam or -(maim'steem oc resulta in rapid feer,' water) line break feeduster) break depressurization of the outside containment outside courtainment secondary side. with a s/c tube leak. with a's/C tube leak.

4 Secondary (main steam or

• Unisolable secondary

• Unisolable secondary feedwater) line break (main stears or (main steam or enucing depressuritation feedwater) line break feedwater) break which results in safety outside contaireent. outside containment.

injection or main steam isolction AND AND END NC eubcooling greater Primary to secondary than C Deg. F. 3eakage greater than ,

50 gpm on the faulted Awn s/c.

S/C tube leak greater i'

than 10 gpm, but less 2. maceuwaary ( a t n et m.

than 50 gpn on.the or feedwater) brea.\

faulted S/C inside containment with S/G tube leak ,

and indication of 4 Unisolable secondary fuel damage (main steam or feedwater) line break outside containment. 'o Unisolable~eecondary (main steam or A38D feedwater) break inside containment Field monitoring teams detect activity AND at the protected area fence at greater than Primary to secondary or equal to 2 mrem /hr led. age greater than whole body. 50 gym on the faulted S/G AND

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'l secoulu muwwem= sTATIan CHIP-11 EDERGENCE ACTION LEVELS EBClasWNE 4.1 EVENT f 4.1.3 sTEnst 3YSTEM FaTTJERE PRCE 7 0F 29 WDTIFICETION OF- ALEItT SITE ARNA W WWEBCT CRugsmL tmusuAL EvanT maapacumw'r

2. Secondary (ma 6 steen Fue1 clad failure or feedwater) line. greater than St per break with failure of cheelstry analysis (or ECCS or Main RFamm valid reading on EMF-  ;

Isolation. Sia or 51b of 117 R/hr.*

• Secondary (main steam END or feedwater) line .

break depressurization which results in safety injection signal. -

AND Failure of both trains of ECCS injection.

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• Secondary (main steam

-or feedwater)'line break depressurization which results in Main Steam Isolation signal.

AND ,

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

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BecGUUtN W Was WitRTION CMIP-11 EDERCENCY ACTION IRVELS ENCIfSUIRE 4.1 BVENT $ 4.1.4 HICH RADIATI(Et/MADIOtACICAL EFFIRENTS PACE 8 OF 29 NOTIFICATIOst OF ALERT SITE AREA E N CENERAL UNUSUAL EVIDFT EFERGENCY

1. Liquid or gaseous 1. Big. afistion levels 1. Accidental rel=.ames 1. Accidental releases of i

radiological effluents or hi,, airborne of games games azceed Tech spec Lleite em conta=8 atire determined by RP or Chemmistry Procedures. 4 Valid indication on # Valid indication on EMF-

• Any valid area EMF EMF-36(L) reading 36(H) reading greater than END reading greater than gre" ster than or equal or equal to 6.1E3 cpsn or equal to 1000 times to J.25E6 cpn (equates (equates to 1 REM to the WB background value to 50 mRee/hr WB at at site boundary integrated site boundary). over 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />;.

AND Exceesive area

• Valid indication on

• Valid indication on EMF-37 radiation levels due EMF-36(H) reading reading greater than or to either unknown or greater than or equal equal to 2.8E6 cpre (equates uncontrolled causes to 6.1E2 cpe (equates to 5 Rern to the thyroid at to 50 mReum/hr WB at site boundary integrated 4 Valid indication on I EMF-41 reading greater than or equal to 1000 4 Valid indication on

• Dose calculations based on times background value EMF-37 reading greater containment conditions than or equal to 2.8E5 project dose rates at the AND cpra. site boundary greater than or equal to 1 R/hr WB or 5 Excessive airborne R/hr thyroid integrated over levels due to either

• Dose calculations a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> period.

unknown or based on containment uncontrolled causes t.onditions project dose rates at the site t Field monitoring team boundary greater than measurements have determined

2. Cameous or liquid or equal to 50 mrem /hr dose rates at the site radiological WB or 250 mrem /hr -

boundary greate:. than or ,

effluenta emceed 10 thyroid equal to 1 R/hr Ma or 5 R/hr times Terb Spec thyroid integrated over a 2 limits. hour period.

END

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seccount scamst stans CflF-11 EDEU4GWOCT E0pt LEWEIS Mer%Q5URE 4.1 EvDET 3 4.1.4 WIG 3 RADIATION /3taDIOLOGICAL 17FLUsNDE PAGE 9 OF 29

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mrrrrIcmTIost oF AImtT SITE am m apoow ment cumuur.

EPEEDCRNCY UFEUSUAL'tVENT

• d monitoring team

• Valid indic-stion on EMF-3f- tesding g-eater 4tments have than or equal to 1C M aruined dose rates times Trip II setpoint at tra site boundary ,

greater than or equal )

to 50 mrem /hr et3 cr l

• Valid indication on 250 mRers/hr thyroid.

EMF-36(L) readicq greater than or equal IND to 10 times Trip II setpoint e va1LJ indication on EMF-37 readirig greater thus or equal to 10 times Trip II setpoint i

e valid indication on EMF-50 reading greater than or equal to 10 times Trip II metpoint e valid indication on EMF-31 reading greater than or c< psi to 10 tiratt w 7tip IT setpoint e valid indication on EMF-49 reading greater than or equal to 1G times Trip II setp3 tnt l

• Valid indication on EMF-44 reading greater than or equs1 to 10 times Trip II setpoint

.n #% - m mostm uncraan arnTre CHIP-11 N ACTim LEVEL 3 menr g 4,2 Everr # 4.1.4 EIGE RAD;Jtr20st/Rhntumstas. EFFIANErr5 Pace 10 w M m rrrrcmTI m W ALzar , r:TE amam ===me===nr emm-mar.

UncsWRL EVMyr

• Cameouse or liquid radiological effluents exceed 10 time , Tech spec limits as deter.akned by RP or chersistry procedures IND t

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ucsuIns mann sTmT2aut 011P-11 i EBENEENCY JtCTICEB IATE1A e m namme 4,1 i EvuurT f 4.1.5 rama or SsWTDouir FCuCTIcuss Faca 11 or 29 l NDTIFICATICEt OF AIJtRT SITE AINFA - -

UWU5UAL RVNBr? WWubCENCY

1. Imee of Decay meet wal 1. crumplete lose of any 2. Complete lose of any 2. Transient initiated by Ioes I in W 5 and 6 fuor-tion needed to function smeeded foc of Cr and CM systamme ,

maintain core cooling- not abutdown folloesed by failure of Ameet in modes 5 and 6. conditions rwooval capability foc an O Loes of decay heat removal artended g lod.

for greater than 10 tainutes POTE: If loss a: RHR '

in modes 5 and 6 due to lose of vitai

• Failure of Iwat sink AC or DC power, see in mode 4 results in

• Imes of CFJCF feedwater flow END Event 84.1.6, Loss of utrontro11e,1 heatup capability. l Power, site Area Deergenc, Initlating AND AND i Condition $3.

Core emit T/C*e CA flow cancot be '

• Failure of heat sink indicate greater than estalallehed within 30 in ::m. des 5 and 6 or equat to 350 Deg. minutes.

results in F. ,

uncontrolled heatup AND AND

• Inability to feed NC system feed and bleed I S/G's f rorn any sourc= cannot be established or (

Core exit T/C*e in % 1-3 maintained.

indicate greater than or equal to 200 Deg. F FN3 ,

2. Trammient requiring a Rm E Feed and ble.+d cooling trip with failure to trip  !

2. Transient with of the reactor core is with indication of failure of the l necessary to remove significaset fuel "-  ; -- or t neoctor Protection core decay heat. '

failure of core coef inny.

system to autommatically initiate and complete o Transient with failure of I a Rm trip which the reactor protection  !

brinsye time Deactor systems to automatically saberitical (A m initiate and complete a Rx Evect) trip which brings the reactor subcritical (ATtts event).

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l anemiser ==rw=mm sTnTsc5 CMIP-11 wammermerY ACTION LEVELg umrensrumar 4.1 EvnrT # 4.1.5 3 ASS OF SEUTDONE FIMCTIO N FACE 12 OF 29 WUTIFICATION OF ALIFT SITE AREA BERGENCY CN UNUSUAL EVENT ""'"""""Y l

} 3. Degradation of 2. Transisust requiring Actions taken per EP/1 or i Sancondary amat Simk operation of sesutdows 2/A/5 MO/11.1 (Response to systems with failure Nuclear Power Generation / l e fees of feed to trip. ATws) fail to bririg the  ;

capability to S/G's reactor euberitical. ,

from nain feed puerps. -

• Transient with fmilure AND  ;

A*:D of the reactor -

protection mystem to Chemistry analysis indicatee  !

All S/C's levele' lese autoscatically initiate greater than or equal to 5%

than 54 (25%) NR level and complete a Rx trip total fuel clad failure (or i which brings the valid reading on EMF-51a or

[ AND reactor outcritical 51b of 117 R/hr.

(ATWS event).

Total CA flow to S/G's j less than 450 gps AND

• Transient with failure of reactor protection systems i Control rode cannot be to autennatically initiate I

4. Commplete loss of any amanually tripped or and complete a Rm trip which i

! function newded to inserted from the brings the reactor '

{ achieve anode 5 wtaen Control Roca suberitical

. shutdown is respaired by Tech spec in modes AND i 1-4 [

Actions taken per EP/1 or 2/A/5 COO /11.1 (Response to '

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• Complete loss of any Muclear Power '

of the following ceneration/ATws) fell to a

' functions when bring the reactor L function is required suberitical.

to continuc shutdown 2

' AND  !

(a) Ability to borate; I i' (b) Ability to feed Plant conditions require l steam generators; sentry into EP/1 or  !

! (c) Ability to 2/A/5000/12.1 (meeponse to i establish decay heat Inadequate Core Coeling). t I

resmoval I~  !

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r mecumus a - =s= sTATIest CMIP *1 N ACT1on I2ntLs enerer 4.1 ETERIT S 4.1.5 IASS OF M FWWCTICME FRGE 14 OF 29 SITE ABIEh m c ommmm ar.

WOFIFICATIO88 OF AIJDtT M

UUUUSUAL BYIDff 9 Failure of heat sink 9 Failure of heat eink causes causes lose of Colet lose of cold shutdown Shetdown conditions in conditione in modes 5 and 5.

modes 5 and 6.

AND AND Available makeup rate (as Wither TraLn indicated by Flow Rate ultrasonic level Instrumentation or rate of indication less than FWST Level decrease) less 14 inches and than applicable data book decreasing after curve.

initiation of NC system makeup. AND NC System level below bottom range of available level  !

o Failure of heat einit I causes lose of cold indication.

shutdown conditions in I I

< modes 5 and 6. AND 1

AND W Coordinator judgement that core uncovery Reliable NC System is in-incot.

level indication unavaliable due to NC Ess3 system pressurization.

AND Core exit T/C's or AP/1 or 2/A/5500/19 (IA>es of Deeldeal Heat Removal) data indicate boiling in the core.

AarD

- - - ----__,____,_____,,_y _

- ,g .

secsunus samaan sistrias CMIP-11 mummmamurY ACTIW LEVEL 3

• marrammma 4.1 ITENT 4 4.1.5 IAISS or seWTECIM FWWCTI(MS 79CE IS OF 29 SITM JMEER EBERGEBBCY -

9KFTIFICRTICBE OF ALERT UNUSDIG. EVENT EBENCENCY Available makeup rate (as -indicated by (Icw rate instrumentation or rate of FWST 1evel decrease) less than applicable data book curve.

END t

.l e

i

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i

-- --_--______.__________.____.a

.~.

n ,m sescarnet sprv=== stat 1our CMIP-ll

- ACTICE 1aVEIE Jerrnerumar 4.1 Everr # 4.1.61485 or PosEER PACE 16 W 29 2

SITE AsuRh - -f nortrIctrIost or Asmutr UtWDSWAL EVEBrr WERGEIBCY

1. Imes of offsite power in 1. Imes of offeite power 1. Imee of offsite power 1. Loos of offsite power med and lose of all and lose of all lose of all onsite AC power seodes 1-6. with total lose of s/C's osoite AC power for onelte AC power for grisater than 1 minute greater them 15 feed enemhility in Seodes 1-in skxtee 1-4. =i M ee in seodes 1-4. 4.

O Both unit related mala bue lines de-energized in modes -

1--G .

• Both 4160 V essential

• Both 4160 V essential

• Both 47 V essential buses buses are de-energized buses are de-energized are dewnergized in modes 1-

2. Loos of easite AC power for greater than 1 for greater than 15 4.

capability in Modes 1-4. minute but less than sinutes in Modes 1-4.

or equal to 15 minutes AND in modes 1-4 0 Both D/G*e are incapable 2. Loos of all vital DC Ie:me of of/CF feedwater flow (for greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) power for greater capability.

of powering tho 4160 v 2. Imes of all vital DC than 15 mimetes in power for up to 15 Modes 1-4. JusD ,

essential buses in codes 1- i C. minutes in Modes 1-4.

CA flow cannot be , L

• Both unit related EVDA established within 30 i 3. Ice = of onsite AC power

• Both unit related EvDA and E7DD buses de- minutes. t capability in Modes 5 and and EVDD busce de- energized for greater energized for up to 15 than 15 spinutes in IDED [

G.

minutes in modes 1-4 Modes 1-4.

L 0 Both D/G's are incapable 3. Icos of all omette AC 4

(for greater than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) 3. Zees of of fsite power ce DC power for

of powering the 4160 V and loss of all greater than 15 essential buses in modes 5 oasite AC power for =1Mee with ,

mecostrolled reactor  !

and G. greater than 15

• 5 almutes in Modes 5 core heetup in sendee and 6. 5 and 6.

• Both 4160 V eeeentLal > aoth 4160 V eeeential l buses are de-energized bases are de-energized '

for greater than 15 for greater than 15 minutes in modes 5 and mLautes in modes 5 and i

6. 6  !

M L

=

s

5.

g, ,

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soccenuE suczmaa sTmTicar ptIP-11 EBEEIGENCY acTIM 1mWEELE maarmur 4.1 ETENT f 4.1.6 LOSS OF N PAGE 17 OF 29 SITE ASEh 1EREEmoEEEFF ggggggL WOTIFICRTICBf OF AE25tf N

, WIBUSUBkL WWENT C. Imes of all emelte AC or ac 4. Imes of all vital DC valid core exit power greater them 1 minste poner for greater tesuperature of greater but lees than 15 afnutes in than 15 minutes in than 200 Deg. F modem 5 and 6. peodes 5 and 6.

• Soth onit related EVDA O Both 4160 V essential buses

• Doth unit related EvDA and EvDD buses de-are de-energLted for greater and EvDD buseo de- energized for greater thr_n 1 minute but less than energized for greater than 15 minutes in 15 minutes in modes 5 and 6 than 15 minutes in modes 5 and 6 modes 5 and 6.

Jurp O Both unit related EvDA and END EVDO buses de-energized fcr valid core ezit grenter than 1 minute but temperature of greater less than 15 tainutes in than 200 Deg. F.

i modes 5 and 6 END END

" -Q necurset muuans sTnTraer CMIP-1I auscImscuer 4.1 spammrwer T ACTiourIXTELS avarr a 4.1.7 rImms mem ==r-Tr acTIouns Facs is or 29 SITE A#EA - GENERAL luprIFICATICet or ALERT N

De8DSUAL EVEIrr

1. Fires potentially 1.'Fize ctumspromislag the 1. Any major fire meti*-h could

1. Fire (as deter =3 = sed by the cause maeoive ev===r's damesp affecting safety function of safety shift Supervisor or to plant systems.

eyeteens. . systems.

designee) within the plant (see NOTR) lasting longer

• Fire regairing Control Room than 10 minutes. 6 Fire essulting in evacuation 9 Fire resulting in potential redar~ ant trains of EST semponente (see AND

2. security threat. deterioration (visible or assumed) to any ESF Encl. 4.2) or ESF (v-paients subsystems Control of Shutdown systems comuponent (see Encl.

4.2) or ESF Cu.-pant retr. sired by Tech Specs cannot be entabliatted frort 0,Diccovery of bomb within the any plant location cite boundary but outside subsystem required by for the current the-protected area. Tech Speca for the operating mode becoming incapable of AND currerst operating mode. performing their design function NC subcooling cannot be O Civil disturbance (hostile) (inopetable) maintained greater than O *

2. Ongoing security Deg. F.

O Intrusion /Atternpted compreunime.

• Fire requiring control 2. Security threat resulting Intrusion (Protected Area) Room cvacuation in lose of pteysical contrut of the plant.

• Adversarlee commandeer an area of the plant AND O Bostage situation / extortion but do not control any

• Physical attack on the plant plant vital areas. Control of shutdown (see Note) has eeeulted i.a systems has been occupancy of the control O Security threat as determined by Emeroency establishel or is in room or other vital areas.

Coordinator and Security

• Discovery of breached the prt>cese of bei.ng established fross the END barrier caused try END intrusion cr sabotage SSF.

in Vital Area myrE: Plant is defined as: 2. Immineet loss of Auu. Gidq, TB, 58, RB, D/G Mum, 4 Discovery of bomb in physical control of a Doghouses, SS?, Interim the protected area plant vital area.

RadwaMe yacilit y.

n, .

~

i nocorum sucuuma starneur CMIP-11 N ACTIM IEfELS PmCIJIguagg 4.1 NWEarT f 4.1.7 FIREE ABB NTTY ACTIM F-G3 19 (y 29 WDFIFICRTIM OF' AIJiptr SITE AREE umaracummr -

UEFUSWAL EVEBIT 1m me n e mmar y i

• Ongoing security

• Physical attack

- comproentse as resulting in imminent determined by occupancy of the  ;

Emergency Coordinator -Control Room or other and security vital areas.

END

• Discovery of borab in a plant vital Area.

END 4

1 d

i l'

._ s- .

m secconut marrase STAT 1sm C11P-11 EMERGENCY ACTIM LETE13 m . m 4.1 EVENT # 4.1.8 8 PENT FUEL DA8WhCE PACE 20 OF 29 EJYIFICATION OF ALERT

• SITE AREA - -r UNUSUAL EVENT N _

M/A 1. Damage to Spent Fasel 1. Major '-- ,- to spent N/A with release of feel with release of radioactivity. radioactivity.

00NTAIMMuurT CX)srrRIsseur?

o valid Trip II Alarm on e Valid Trip II Alarm on 1ENF-39 1De*-16 (for Unit 1) or 2 EMF-3 (for Unit 2)

AND AND Report of fuel damage due to loads dropped Valid 1(2) EMF ~9 cff into core or during scale high core alterations or movement of opent fuel AND in Containment Report of fuel damage due to loads dropped 9 Valid Trip 21 alarm on into core or during 2 EMF-39 core alterations or movement of spent fuel AND in Containment Report of fue.<te g AND due to loada dropped into core or during Dose rats inside core alterations or Cbntainment coupled movement of opent fuel with known Containment in contairroent. leak rate reeults in

, calculated dose rate at the SLte Boundary of greater than or equal to 50 mesm/hr MB or 250 aren/hr thyroid.

S'

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7-seecuzan -=== sTmTIeur 011P-11

- - =rT ACTIM LEVELS EWC14Sep!E 4.1 '

atVENT S 4.1.4 SPENT FUEL DeseCE Phos 21 or 29 EBOTIFICRTIcet OF ALERT - SITE ABBA ENEguramrT CEUE3thL UIOUSUBLI. EVItuT EgeggGEEBCY FUEL BAIOLING BUILDIMC FUEL BMIDLIWC BUIIAIDC

• valid Trip II Alarm on

• Valid Trip II Alarm o 1 EMF-17 (or '1E3F-17 (or equivalenc) equivalent)

AMD mfd valid Trip II Alarm on valid Trip II Alaris on 1 EMF-42 1 EMF-42 AND AM9 Report of fuel damage valid indication on during movement of. 1 EMF-36 reading opent fuel or loada greater than or equal

dropped into spent to 3.25E6 cpm.

fwel. pool resulting in possible fuel damage. AprD Report of fuel damage e valid Trip II Alarm on during movement of "

2 EMF-4 (or equivalent) opent fuel or loade dropped into opent AND fuel pool resulting in possible fuel damage.

Valid Trip II Alarm on 2 EMF-42 '

• Valid Trip II Alarm on AND 2 EMF-4 l

~

Report of fuel damage AND during wunt of opent fuel or loads valid Trip II Alarm on dropped into opent 2 EMF-42 fuel pool resulting in poeeible fsel <ta-ary=. AIID .

END t

_ _ . _- m_ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ - - _ _ _ _ _ ___.._._ _ . __

.n ,, ,-;~ m

~

taccEmur -=== sinTxcur CMIP-11

- JhCTIM LEVELS m . 4.1 avgeger a 4.1.5 sFeurr FUEL DABSCE PSEE 22 4X 9t9 EUTIFICRTICEI Or ALEPT SITE AREE NeeBCEBBCY GENEEEutL UNUSUAL E7EBIT muerw"1rurY valid indication on 2 EMF-36 reading greater than er equal to 3.2SE6 cpm AND Report of fuel dwege s _ ..t of during i.,;

spent fuel or loads dropped into opent fuel pool resulting in poselble fuel damnege.

END Y

, - --~n- ~ . . - - --- - _ - _ . _ _ _ - _ _ _ _ _ _ _

. .  % fa -s -

I N nutzana sunfrom C11P-11

- acr2m 12WE13 eerw - 4.1 i Em 9 4.1.9 m BISASTuns W m ======= Men 23 or 29 styrIFItarrom Or

~

ALERT SITE A m N -r j UNUSupm EVE 3rr -

1. Earthquaha felt im plant 1. E.arther* greater 1.*Eartheynahm greater 1. may amice natural or I and detected by se M ie than our than ssE hs =ad=e 1- accidental evest(e) (iet monitoring imetrummets 4.- aircraft lopect,  ;

mer* ' ': suhetastially

• Creater than 0.08 g beyond design levolc) wenich ,

..O valid Alarm on " strong Horizontal

• Creater than 0.15 g comid c==== memoive -  !

sotion accelerograph* Horizontal damage to plant sy=* .  ;

• Creater than 0.053 g ** __. ,-acy Cooufinator  ;

o valid Alarm on " Peak shock vertical

• Creater than 0.10 g jedgeonent.  !

cnnunciator" vertical RND l

2. Damage frem tornado, '

2. Low wateur level sueuined winde, 2. W from tornado,  ;

aircraft creek, sustalmed winde, '

mloelle, or aircraft crash. l

- 0 Laka Norman level less than . emplosion. missile, or [

->r equal to 745 ft. emplosion.

,

• Any tornado striking

3. Any tornmeo/mevere wuenther plant structures

• Any tornado striking within the site boendary. within the protected any plant vital area area fence structure resulting in lose of any N io Any tornado observed ienction required for touching down within the

• Approaching hurricane the currect operating cite boundary with sustained mode.

(greater than 15 minutee) winde greater Io sustnined (greater than 15 ,than 75 but less than 4 Approaching hurricane i minutes) winde greater than 95 mph ao reported by with sustained or equal to 60 cph the National Weather (greater than 15 i Servi. e minutes) winde greater

than 95 mph as 4 C. Aircraft crash reported by the

4 Aircraft crash within National weather

the protected area Service.

j 0 Aircraft crash within the feece affecting safe

cito boundary. operation of the unit.

3 4

4- . . - g , , . - -

n - n

-l seenerna innve== starzes: CMIP-11

- AcT1cm IzvuB.s umrsamer 4.1 RVEErr # 4.1.9 IERTUWEL CI3 ASTERS Am N M Pacut 24 W 29 I NKFIIFIChTICIE OF ALERT SITE ABIEh unarurmgary ammmmar I Upgr43DhL ETE3r? EmmerEMar"Y l

' 5. Trala derailmant on site

• Explosion damage

• Aircraft crash causing within the protected damage or fire to the area fence affecting Cottainment Building, O Troia derailment resulting safe operation of the control Room, in physical damage to unit. Auxiliary Building, equipment /etructure within Fuel Building, or oite boundary. SMSWP Intake Structure

3. Release of tomi.c or in modes 1-4.

f1 - hle gas.

' O. Emplosion within site boundary.

• Damage frorn miseile or

• Uncontrolled entry of explosion in modec 1-4 toxic or. flaarsable gas causes inability to

'O Cuplosion within the site within protected area maintain or esteblish boundary reeutting in fence affecting safe functions required for

, structural damage to operation of the unit. hot shutdown.

3 buildings and/or injuries to

personnel. EMD

3. helmene of toxic or f1====hle gas (Deudes

7. melease of tosic or 1-4).

fi - hle gemee.

4

• Uncontrolled entry of

'O Release of tonic gas tou te or f1====hle resulting in personnel gases into the control

.' injury or any evacuation Room, cable Spreading within the Protected Area. Rooms, Contvinment Building, Switchgear l Rocese, Auxiliary O melease of f1====hle gas Shutdown panels area resulting in any evacuation (CA puwp roome), or within the Protected Area. Beergency Diesel Generator Roome 4 END affecting safe operation of the unit in modes 1-4.

E30 i

j

- ~

~3 .

m neastas sumana starrass CMIP-11

• waaracm=Y ACTTW LEVELS umrarncrmr 4.1 '

NVENT S 4.1.10 Engsim ammenammar FLAbiT tvunnITIWS PRCE 25 OF 29 WerIFICATIOst OF ALEftT - SITE ARER BW5t3EBBCY e'ummmma r i

UNUSUAL EVENT E3praramCT  ;

1. B Ts initiated. 1. rescuation of Control 1. Evacuation of C:mtrol 1. zwecuation of courtrol Rooms.

Room. Rooms.

• Evacuation of Control Rocc=  !

O valid S/I signal Wrified by redundant indication

• Evacuation of Control 9 Evacuatice of Control AND Room Room in anodes 1-3 AND Control cannot be AND A.neD established fram any plant Discha.rge into the vessel. location Control established Inability to feed (or in procese of 5/G's frome any source AND

2. Abnorunal coolant being estabtished) teumperature anaf /or preeemere from the Auxiliary 18C subcooling cannot ba or abnormal feel Shutdown Panel less

• Evacmation of Control siaintained greater than O temperature. than or equal to 15 Roarn in P6 odes 1-3.

minutes.

De?. F.

AND 2. Other malt conditione

o Figure 2.3-1 Tech Spec 2. significant lose of exist, frams whatever exceeded in roodes 1 and 2 annunciator Inability to establish source, that in the capability in Modem control from Auxiliary j ^ , t of the shift 1-4. Shutdown pane 1 within Supervisor /- -Mr o Core sub-cooling margin )=se 15 minutee. rw,wdinator meane release of than acceptable ("Subcooling large amounts of Purgin Alert" annunciator).

• toes of 50% or mora of radioactivity in a short the control room o Evacuation of Co:-trol time patriod possible.

annunciators for Roarn

,O Tech Spec (LCO 2.1.2) greater than 15 END Resctor Coolant systern minutes in Podes 1-4. AND preneure exceeded in modes 3, 4, and 5. Inability to establish

3. Other unit conditt - control from Auxiliary exist that in the shutdown par.+1 l 3. Imes of containment p W of the integrity requiring Shift Supervisor AfED mhe.tdown by Tech Spec. /1__. Af coordinator unrrant Control establiebed declaration of the (or in procese of

O Any motomatic contaiamment Alert claemification. beleg metablished)

isolction valve open and frous 5s7.

inoperable and unisolable. END

pv =3 ~

i m ,a e, .. CMIP-11 MWicWICT ACTIM LETEEK mm 4.1 EVIDFF S 4.1.10 Ot1Elt. h 7 MJhsr MITIONE Pact 26 er 29 WOTIFICRTION OF AUGt? SITE Mlag g -r DUIUSUAL WMtisT StERCseCY Alen 2. Othec melt conditions eniet. that la the Load reduction or plant i im of the cooldown initi.ated pursuant '

Shl.ft Supervisoc to' Tech Spec 3.6.3. /- , -1 Coordimetoc marrant declaration of Jite O Both air locktJoore of a Area - _ 7-1 cingle airlock inoperable -

4 Ano E Imad reduction or plant

- roold>wn initisted pursuant to Tech Spec 3.6.1.3.

2 IO. Loos of ESF or Fire'

Protection syeten fonction.

I.0 Both trains of any ESF function found inoperable

'(if caused by fire see event

1. 4.3.7 - Fires and Security I

Actions, Site Area Emergency i'

cicesification).

AND l

Load reduction or plant cooldown initiated in j .accordance with INach Space.

q t

D w *- m__ -__.. __.__._ _ _ _ - _ _ _ _ _ _ _ . . _ _ _ . _

- =nr5 =a= mTran CMIP-11 N JhCTICE LEVELE m amuur 4.1 BVENT f 4.1.10 OTHElt AE50gushL PLAstr emITEGES Pace 27 cr 29 1BOTIFICATION OF AIJDtr SITE A3Eh - N UWUSUAL EVENT -

O Lees than ministas channels of Csr function operable.

AND Load redmetion or plant '

cooldown initiated in.

accordance with Tech Specs.

O Ines of all s. min fire protection systesa water pumpe.

5. Tr-- ,- : r-tatice of a coetasaisetad injured individual from that site to an offelteamedical facility.

O Decontamination efforte fait to reduce external contamination be1ow 150 cpm beto-gamma or injured many require Lausediate medical cttention and ,

decontassination efforte are waived.

AND Radiation Protection personnel determine that radiological controle are requiced for offsite amedical treatraent.

Tv

. - in

• msowIma - man starren CMIP-11 MERGENCY ACTICgg m numrvammmer 4.1 EVEBET f 4.1.20 Otism mr PLANT CDEEDITMMS pmGE 28 or 29 EstFFIFICRTICEI OF ALE 5tf SITE ABIRA N emmunumar WlEUSUAL ETEIrr m"Y t

G IntGraal contmanination ~

requirirug medical caseemment/treatmerit 0 Cxternal exposure . requiring i medical aseesament/ treatment C. Cignificant Idsee of amoeem capabu.ity or i

, -:- _icatloc capsbL11ty.

O Losa of P!NS comemnicatione ccpability with all offsite agencies i O Loes of 50% or more of the control room annunciators in Modes 5, 6 for greater than 15 minutes 1

O Imes of all onsite  !

meteorological '

instrumentation AIED ,

Inability to contact the

! ' Cctional weather Service for

• i

)

backup oource of data.

i-a u , _ _ _ _ _ _ _ . __a-.._ _....- - - _---- --

___. ,. n sermerve sure=== ararscur OtIP-11 zumacumscr acyrous uavur.s - n=r== 4.1 1

runsrr # 4.1.10 annet ====n===mr ruurr camerTrams pasa 29 or 29 4

starrricarica w ar_zstT arra ama usummausser suussuu. -

UBUDSWAL DEMrf- W "

i 4

'7. Othec coeditions emiet Chat in the et of ,

Shift Sepervisor/Lauergency Ocrvnlinator warrant increased awareness of local authorities.

f i

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i

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i 4

6

. _ _ _ - - _ . . .. . _ . _ _ _ _ _ - _ _ _ . , _ _ _ _ . _ _ _ _ . _ ____m~.___.-_ _

CMIP-11

. Enclosure 4.2 Pace 1 of 1 b

ENGINEERED SAFETY FEATURES

1) Containment Spray

2) Containment Air Return and Hydrogen Skimmer

3) Ice Condenser

4) Hydrogen Control (Hydrogen Recombiners Only)  ;

5) Annulus Venti ation 6)' Auxiliary Feedwater

7) Nuclear Service Water

8) Component Cooling

9) Steiim Line/Feedwater,Line Isolation

+

} 10) Containment Pressure Control

11) ESF Interlocks

12) Turbine Trip

13) Reactor Protection 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 Syst u , Automatic Switchover

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

i

. I CMIP-11 1

- Enclosure 4.3 i

• - Page 1 of 1 l l

TERMINATION CRITERIA

- (- _ 1._ Existing conditions no longer meet the emergency classification l criteria and it appears unlikely that conditions will deteriorate further.

2. No surveillance relative to off-site protective actions is needed, except for the control of foodstuffs and water, and off-site contamination, or environmental assessment activities.

3. Radiation levels in affected in-plant areas are stable or decreasing to below acceptable levels.

4. Releases.of radioactive-material to the environment greater than Technical Specifications are under control or have ceased.

5. The potential for qan uncontrolled release of radioactive material is at an acceptably low level.

6. Containment pressure is within Technical Specification requirements.

. 7. Adequate long-term core cooling is available.

8. Adequate' shutdown margin of the core has been verif.ied.

A fire, flood, earthquake or similar emergency condition is 9;

'ls controlled or has ceased,

10. Offsite power is available per Technical Specifications.

. -11. Any contaminated / injured personnel have been-transported offsite and are receiving appropriate medical care.

__. _ 12. A11' emergency action level notifications have been completed.

__ 13. Access to radiologically controlled areas of the plant necessary for operation durir,g recovery are being monitored by '

the Radiation' protection Section.

14. Offsite conditions will not limit. access of personnel and support resources.

__ 15. - Discussions have been held with the News Director to_ determine the impact of termination on public in; tation management.

16. ~ Discussions have been held with Senior NRC and-State representatives to determine the impact of termination on their activities.

-t l

Rev. 10 June 10, 1991

_