ML20213F058
| ML20213F058 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/07/1987 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 5211-87-2086, NUDOCS 8705150221 | |
| Download: ML20213F058 (1) | |
Text
.
GPU Nuclear Corporation g
Ngggf Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
May 7, 1987 5211-87-2086 U.S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, DC 20555
Dear Sir:
Three Mile Island Nuclear Station, Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Revised Emergency Action Levels GPUN has revised the TMI-l Emergency Action Level (EAL) Matrix which is included in GPUN Procedure 6410-IMP-1300.01, Rev. 2 (attached to this letter). The revised EALs became effective April 15, 1987. The EALs were primarily revised to reflect plant modifications and formatted to reflect the revised radiation monitor setpoints.
GPUN has determined that the changes to the EALs have not decreased the effectiveness of the Emergency Plan.
These changes were discussed and agreed upon with the Commonwealth of Pennsylvania representative. The EALs continue to meet the requirements of 50.47(b) and Appendix E.
As such, prior NRC approval is not required as stated in 50.54(q). Accordingly this procedure revision is supplied for your information.
If you should have any questions, please contact Mr. Geno Sinonetti at (717) 948-8490.
Sincerely, I. D. H k 11 Vice President & Director, TMI-l HDH/DVH/spb:0862A cc:
W. T. Russell, USNRC R. Conte, USNRC Attachment
'b '
870D150221 070507
'P PDH ADOCK 05000289 g
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PDR GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation
Number
-(UClear TMI-1 Emergency Plan Implementinq Drocedure 6410-I"o-1100.01 Title Revision No.
Emergency Classi fication 2
Applicability / Scope Responsible Of f ace All Fmprgency plan f mnl eme n ta ti n n t in TNT.1
(;di n This document is important to safety 5 Yes O No Ef factive Date Listof Effective Peges Page Revision Page Revision Page Revision Page Revision 1.0 2
E2-15 2
2.0 2
E2-16 2
CONTROLLED COPY FCP l,.0 USE IN UNIT 1 ONLY 2
2 El-1 2
E2-19 2
.N El-2 2
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i E2-1 2
6 F2-2 2
E2-3 2
E2 d 2
E2-5 2
E2 6 2
E2-7 2
E2-8 2
E2-9 2
E2-10 2
E2-11 2
E2-12 2
E2-13 2
E2-14 2
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Number Nuclear THI-1 Emergency Plan Implementing Procedure 6410-IMP-1300.01 Title Rewsion No Emergency Classification 2
1.0 PURPOSE This procedure provides guidance for the Emergency Director for determination of emergency classification based on given initiating emergency conditions (emer-gency action levels). The emergency action levels stated in this procedure are TMI-I specific and consistent with federal guidance.
2.0 APPLICABILITY / SCOPE This procedure applies to all Emergency Plan Implementations in Unit 1.
3.0 DEFINITIONS Effluent Monitor -
An online instrument monitoring radiological conditions of a designed pathway to the environment (e.g., station ventilation exhaust).
Low Range Effluent Monitors - These are as follows:
RM-A-5 lo, RM-A-8 Gas lo. RM-A-9 Gas lo, RM-A-8 lodine, RM-A-9 Iodine, RM-A-14 Gas, RM-A-15 Gas.
High Range Effluent Monitors - These are as follows: RM-A-5 hl, RM-A-8 Gas hi, RM-A-9 Gas hl.
High-High Range Effluent Monitors - These are as follows:
RM-G-24, RM-G-25.
Emergency Action -
Those measures or steps taken to ensure that an emergency situation is assessed (assessment actions) and that the proper corrective and/or protective actions are taken.
Emergency Action Levels (EAL's)
Predetermined conditions or values, including radiological dose rates, specific contamination levels of airborne or waterborne concentrations or radioactive materials; events such as material disasters or fire; or specific instrument Indications which, when exceeded, require the implementa-tion of tha Emergency Plan.
Potential Loss The conditions exist that have the possibility to result in the failure of a protective barrier.
Unplanned An event occurring that was NOT projected or considered (i.e., something NOT EXPECTED) in the procedure or plan for operation.
Z.O N71 bed @S ee)
Number (ggy THI-I Emergency Plan Implementing Procedure 6410_ IMP-1300.01 Tstle Revron No Emergency Classification 2
Sabotage is defined as "Any person who Intentially and Sabotage willfully (e.g., eyewitness report or threat followed up with tangible evidence) causes or attempts to cause an interruption of normal operations of such a facility through the unauthorized use of or tampering with the machinery, components, or controls of any such facility,
...", Vandalism is also incl.uded in this category.
Valid (or Confirmed)
An indication that is conclusively justifled from alternate or supportive (backup) indicators e.g., other meters, manual calculations, etc. such that all doubt related to the Indicators operability is removed, including prior knowledge related to the indicator.
4.0 RESPONSIBILITIES The Emergency Director is responsible for implementing this procedure.
5.0 PROCEDURE l
' NOTE:
Initial upon completion or mark "N/A".
l 5.1 Upon recognition of an abnormal condition, refer to Enclosure 2, Emergency Action levels and compare existing plant conditions to those stated in the table. The emergency to be declared is the highest classification for which an emergency action level has been exceeded (i.e., General Emer.
gency, Site Area Emergency, Alert, Unusual Event). Contact the Emergency Olrector (senior man) in the Unit 2 Control Room, discuss the emergency conditions and reach an agreement as to which unit will assume the lead for notifications (the lead classification is in effect until the emer_
gency is closed out).
Implement 6410-IMP _1300.02 (1004.2), Emergency Direction, following declaration.
5.2 If none of the emergency action levels have been exceeded, refer to Administrative Procedure AP 1044, Incident Reporting Procedure to ensure that reporting requirements are met.
5.3 Ensure that the appropriate emergency operating procedures,are being implemented.
6.0 REFERENCES
6.1 GPUN Corporate Emergency Plan 6.2 Emergency Plan Implementing Documents 3.O N71thd V446)
Number Nuclear THI-1 Emergency Plan Implementing Procedure 6410-IMP-1300.01 Title Revision No Emergency Classification 2
6.3 NUREG 0645, Rev. 1/ FEMA-REP-1, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants".
6.4 6410-ADM-1300.03. "EAL Rationale and Cross Reference" l
7.0 ATTACHMENTS 7.1 - Emergency Action Level (EAL) Index 7.2 - Emergency Action Level (EAL) Matrix gnesio gee) i 4.0
Number
'(UClG8r TMI-1 Emergency Plan Implementing Procedure 6410-IMP-1300.01 Title Revision No Emergency Classification 2
ENCLOSURE 1 Emergency Action Level (EAL) INDEX PAGE 1.0 RADIOLOGICAL CONTROLS.........................
E2-1 1.1 Effluent Atmospheric Monitoring.................... E2-1 1.2 Liquid Effluent............................ E2-1 1.3 Reactor Coolant Activity........................ E2-2 1.4 Containment Building Activity..................... E2-2 1.5 Radioactive Material Control...................... E2-3 1.6 Transport Injured - Contaminated Personnel............... E2-3 2.0 CONTAINMENT INTEGRITY.
E2-4 3.0 SECURITY
.E2-5 4.0 GENERAL PLANT STATUS E2-6 5.0 PRESSURE. TEMPERATURE AND INVENTORY CONTROL...
E2-7 5.1 RCS Leakage..............................
E2-7 5.1.A Pressure Boundary, Un-ID, Total....................
E2-7 5.1.8 OTSG E2-8 5.2 RCS Temperature............................ E2-9 5.3 Depressurization/0vercoo11ng...................
E2-10 5.3.1 Loss of Subcooling E2-10 5.4 Rx. Trip - Loss of Normal Heat Transport................ E2-10 5.5 Rx. Trip - ESAS............................ E2-11 6.0 ELECTRICAL POWER E2-12 6.1 AC..................................
E2-12 6.2 DC E2-12 EI-1 Nnb@l@&46)
Number GUClear THI-1 Emergency Plan Implementing Procedure 6410-IMP-1300.01 Title Revision No Emergency Class 1fication 2
ENCLOSURE 1 (Cent'd)
PAGE 7.0 INSTRUMENTATION AND ACTUATION SYSTEM E2-13 7.1 Annunciators / Indicators........................
E2-13 7.1.1 Assessment Capability)
E2-13 7.1.2 Communications E2-13 7.2 Actuation Failure...........................
E2-14 7.2.1 Cold Shutdown Function E2-14 E2-15 8.0 NATURAL AND HAN-MADE PHENOMENA 8.1 Natural Phenomena..........
E2-15 8.1.A Earthquake E2-15 8.1.8 High River Level E2-15 8.1.C Low River Level...
E2-15 8.1.0 High Winds E2-15 8.2 Man-Made Phenomena E2-16 8.2.A Plane / Train Accider.t E2-16 8.2.8 Explosion.
E2-16 8.2.C Chemicals...............................
E2-17 8.2.0 Turbine Failure............................
E2-17 8.3 Fire.................................
E2-17 8.4 Control Room Evacuation........................
E2-18 9.0 REACTIVITY CONTROL E2-19 9.1 Control Rods E2-19 9.2 Reactivity Insertions.........................
E2-19 E1-2 NMDf@646)
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q ytePLAlmelD condeteens below:
endicated by AhY of these er PROJfCit0 deses of indecates ACiuAt er VALID condetseas below:
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r ma a chile thyroid enests mRee child thyroid enests n
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- A' and
- S' steam the matemp ta=4 detreassag h
greerater t.bes) of at W at 2 en/mes. Saturated coe.dissoas besag not *Se & Pet. approached as sadesated by -Se pletted Reacter Coelaat System Press.re/lemperat re 7, q se et GR (Te6) O the s.bceoling meneter sadesateng <iS* (Det m 'aatse+ dame in atterdante meth Plaat PretederesI 3g m gaea n/A Primarr to Seteadary teak Primary to Seseadary teah as/A ~M o1 e te et a t (.MI h=t e54 (sPse Gate of 254 fPvt
- 8 s
rn w 3~ NQ &lG e 3 f*t et 3 toss of the acadenser toss of the gendeaser { *3 lesatt oon as sadesated by feasteen as endecated by eo one of the felle-eng: one of the falle sag: e D3 - i.,s of.ft-sete -,. - isss of ofis,te -,. 3a aere volts em 55.-t for aere welts en 55-3 for n the '4' and '8' bes. the '4' and "d* bes.
- 7
- A raped==4atecopated - A raped waastecepated (( decrease se steam decrease sa steam -g a pressere. pressere. dD - Atto.atsea of the steet - Act ovat sese of the seest Seah Protesteen 5,stee Sene Protesteen 5tstem (e:5PS) Nea f eed=4ter les5Pil staie feed ater Iselatsen. Iselateen. - Wes.al sade<atsen of a - Ves.at endecatsen of a steam lone breet. steam laae breat. - Condenser watesum <2) - Condenser eatense 423 nathes seg esches tog - t ess t han 2 s o rcelat ing - Less them 2 s errelat eeg 2 m Z oster pumps operatsag mater m s operetnaq g. c 3 O cr O a e 3 m m N Z Z O T 2 4 3 ~ ta OO O _8 e
0 Number Nuclear MI-1 Em rgency Plan Implementing Procedure 6410-IMP-1300.01 Title Revision No Emergency Clas'sification 2 35 12 32 2 I 1. i, .i - s dr 32}-;m - Cv : $g W 1,92, - 3 13 3-
- 3 *4 g
gr - 4 :~. 2, 325:21 2
- 14-1 1
- -1 224-t-
't .31* 1*r.~r V
- 0) "$g%,t_1 r
-#1- - -.1. w.21 ,g -3 1 a g - 3.... 2 3..g ; ; ?E 3 :j 13z t1 ,~ 3 a.ir :- = g.... I a ~ -* ! 2 4.25.! ! w, ..g s. s :~ -t.. Y 2 2 3 5.j 3: 2 I 24.2 rw t T - - E %.3 -,3 3 ' O.. 4 .}. g3 IT3j -tb.n 1I:s ,8 2:4 35*I*2 L G t 8 +Y e l E2 9 N710bd b)
2 INC105utt 2 (Cented) y De monsrv ACitans a fvit Mafatz r't 3 e UNU5uAt $IIf ARIA ..[Nf RAL s EwfMT AtFRf E MF BU nary [pyy 40 m 3n V S.) failere of a safety 08 A man-iselable steme leak Complete less of one of the N/A (Depresswaraatsen/ relief valve, se a safety that results en raped following fwastions needed b Overteeling) related systee, to close depressurisation of the f or maintaining het ce after opening to redece steam system shutdeun W the system pressere with an 'OPEN* walve position atC - ALL mesas se feed Arc sadecated by atovstical De OI% e heat remov from the flew measursag eg.epeent Actuation of the Heat Sint
- s. requiring HPg n
g for W of the felle-eag Protection System Main cooling = valves f ece=ater Isolat sen - ALL means to teatrol Reacter Coslant System O - Pressursser Safety Pressure 3 Welvels) - Ihe means to sentrol the - Pe=er Operated Relief matew, pumps 08 Valve (PORV) makeup flow control - 01% Safety valveis) - 01% Atmospheric Relief Walvels) M - Decay Heat Removal h Systee Relief Valve (s) 2 I 3 "* r1 ru 8 3 g g.6 N/A N/A Subcoelang aanster N/A e, rvt 3 O (test e8 SutHoolengl indecates saturateen am conditions (Determinateen )) deae in accordante with e Plaat Procedures) m3sn OM CA --* g.4 Reagter Irsp (Alare f-I-Il N/A N/A N/A C (mesator Irep/tess of caused by a VALID to= e esermal stemt Iransport) Reatter (oolant System flow following the failure of any kratter (molent Pump QM (Idl Iotal less el t he ab o l i t y to f eed the Ol%*s with main feed water. "O 2 m 3 C $ ? E, 2 N Z
- E O
D B W E O E O. O. w
Number (UClear THI-1 Emergency Plan Implementing Procedure 6410-IMP-1300.01 Tatte Revision No EmergencyClapification 2 1: t a-32 3 sr 5 4 .3 tr 1 Fd .E 3 5 d i ~$ i 3 i } a5 = o y* 3 e t
- gt :
2 - a;: E Ed i .2 % !.2 : 5.* 5 a*05 : a ci : : .51 : t
- -] $ *
~ ~ A :~: : r 3 ? 3 a o: 1 AS E2-11 N7tsd $546)
(NCt05uRE 2 (Cont'd) rrn IME h(J NCT Af fl0N MEL MA1Rit UNUSOAL SIIC ARfA C4NERAL C EVENI AllRI EN RfJ herY f per arJ esfy 9 3 6.0 IifCIRECAL P0wtR nw n a 6.1 Reactor Trip caused by a Reactor Trip caused by a Reactor Irip caused by a N/A o, w (AC) loss of offsite power with loss of offsste power with loss of offsite power with M the diesel generators IROUDLL Alarms on 001d IRQLalLL Alares on SQld ,O operating. Diesel Generators and the Diesel Generators and the 10 and if 4EV Busses are ID and it 4 KV Susses are NOI raergized for less WI energized for greater n than 15 minutes. than or equal to 15 minutes. l \\ 3 b.l.1 Loss of the ability to N/A N/A N/A meet the timiting Condition for Operation Technical Specification w 3.7.2 during power 9H operation requiring the 3[ reactor to be shutdown. so g 9-M g I r.e B co N b.2 N/A Loss of ALL onsite DC toss of ALL onsite DC N/A 3 9 (DC ) Power moth the battery power with the battery CO voltmeters indicating zero voltmeters indicating sero with 'to DC lighting or with IID DC lighting or ,n 3 n control power available control power available OM for less than 15 minutes, for greater than or equal $g to 15 minutes, c1 90 C, 3 ID ammaannassannamansnausammasamasassssemassasammammuunsaamaansanssanssannassmaananassassanssaumassmannassaunanumansamanasammassmaassanssamanassassmassuna 2 m Z b C 3 E, 5 2 N Z I o o 0 O O. O w
~' =e INC1050Rt 2 (Cont'd) m B emf kCE NCY ACIIQf(MEL MAIRII t 9 UNU5UAL 5IIE AREA GtNERAL [vigi Al. I R i iper Rf1te Y [ME RfJ berY 3 r n ( 7.0 IN5lRUMlNIATION AND ACTUATION SYSTEM M n 7.5 INDICATIONS or ALARMS on HOST (>50%) on ALL MD$f (>50%) or ALL N/A e (Annunciators / PROCE55 or [Ff10ENT ANNJNCIAIORS Iost which ANNUNCIATORS lost M e m Indications) parameters not functional may involve an ACTUAL or plant IRAN 51[NI 15 a in the c ntrol room to an FO?f.; flat substantial de-INIIIAffD or is IN entent requiring the plant grad s.on of the level of PROGRf 55 which may involve { to be in a shutdown safe., of the plant. as ACIUAL or IP9ttletNI major gp condition. as determined cotermined by the Shift failures of plant rt by the Shif t Supervisor /tmergency functions needee for the g Supervisor /[mergency Director. protection of the public. 3 Director. as determined by the Shif t Supervisor / Emergency Director. $q /.l.1 A VAL!D and W 1 M LD N/A N/A N/A si nificant loss of ur (Assessment Capability) 9 -M primary M backup
- 8 assessment capablisty
( (i.e. loss of the plant k~ s computer, safety parameter am rt 9 desplay system) as W determined by the Shif t {* Supervisor / Emergency eo Director. <n m3sn oy n 7.1.2 A YALID and UNELANtiLD N/A N/A N/A
- D (Communications) significant loss of c p, comununicat ion capabilit ies
-s s (i.e. Offsite Notificatsen to the NRC, BNP, Ofigste Duty Roster Personnel) such that PiQ means of notification to offsite agencies are available, as determined by the Shift Supervisor / Emergency
- Director, ch 2
u c ,r g O g e 3 -= m N Z 3' O N m O O. O w S
1 -4 thCt050Rt 2 (Cont'd) di n1 E nf er.e urY AC llDN tf VEL MATEXX Ele UNUSUAL Slif ARIA GE NE RAI h$ EvfNT AlfRI [MI ELI Nf Y [Mf krJ ury np 3 r1 1: 7.2 A plant shutdown required failure of the Reactor failure of day actuated N/A () (Actuation failure) by one of the following Prot ection System (RP5 Emergency (are Cooling conditions: Irip String) to automati-System (lactudes HPI. LPI $"l sumus - Personnel frror cally INIII Af f &ND COM-and Core flood) te start e4 - Procedure inadequacy Ptflf a Reactor Irip when and run following an
== - Inability to meet the any tr6p set point es automats. System "2 Limiting Condit6en for esteeded. Initiatio.a. with an EC(5 l Operation technical setpoint esteeded, such De e3 E4l l Specif6 cation 3.3 that the number of re i (Engineered Safety components available is C) features) or 3.18 (fire below the minimum assumed
- 3 Protection) for accident analysis as determined by the Shif t Supervisor / Emergency Director.
p. EB -4 7.2.1 N/A Complete loss of a func-N/A N/A TJ ]E (Cold Shutdown function) tion needed to maintain l ("$ d. the plant in a cold rn shutdown condelion ce ha (average temperature s rn 1, (200'f) as indscated by: [i ll ds
- 3 -s loss of the Nuclear W3 W3 Instrumentation (Source na and Intermediate Range) 2f[$
with the shutdown margin () %c treactivity) less than 1% r CL -= 08 (fWG) c: ou -1
- 3 i
tess than one operable 'D l Deray Heat Removal string AND the RC5 temperature is > 140*f and increasing. a ss a sa na n a s s a ma m a sa mmasam masa ma n m aam m m a assasuss assass===s sa ma m masa na m masass oassuassa nsassanssamasm usm ana m n ussa mmaa s sama nssassumsm amaassammassammassassa l _E.m 3 C 5 i' S,I a bJ 2! 3C o 13 I .a DJ E. () g; C. ) c_) w
.f ENCt050RE 2 (Cont'd) rn Enractury ACf1DN LEVEL MAfflI E3
- D UNU5UAL SITE AREA GtN(RAL EVfMT AlfRT
[Mr ar.r ur Y f MI RrJ MrY np ~3 8.0 NAIUNAL AND MAN-MADE PHfh0MfMA I:: (1 g 8.8 Natural phenomena being Severe natural phenomena Severe natural phenomena N/A f* gp (Natural Phenomena) esperienced QB projected being esperienced as being emperienced Qg munug beyond usual levels as indicated by one of the projected as indicated by indicated by one of the f ollowing conditions, one of the following following conditions. during operation at power: conditions AND the plant [I during operation at power; is HQI in cold shutdown: rs E4[ os rt 8.8.A VALID alare PRF-I-2 VALID alarm Paf-I-3 VALID " Safe Shutdown N/A {" tearthquake) " threshold Seismic " Operating Basis Earth-Earthquake Candition" =3 Condition" (20.0lg but quake" (20.06g but <0.12g (30.12g Horizontal <0.06g Horizontal Horisontal Acceleration Acceleration ANQl0B 20.08g Acceleration ANQl0B 10.019 &NQ/QR 20.04g but eg.CSg vertical Acceleration but <0.049 vertical Vertical Acceleration Acceleration >g E3 -4 13 JE 8.1. s 2302 ft. PRQJLLILD river 2 302 f t. but < 307 f t. 2307 ft. &CIU&L river N/A Q" _,* (High River tevel) stage at the river water &Clual river stage at the stage at the rever water ra gg p, intake structure (50 year river water intake intake structure. na flood level) structure.
- ) 09 e
re 53 on 3 -s -- n> wa ua 8.1.C <272 ft. PROJLCILD river <271 f t. PROJLLILD river <271 ft. &CIU&L river N/A M3 (to. Rever level) stage at the rever water stage at the river water stage at the river water 2[f( intake structure (50 year intake structure. intake structure. c) se low level) r1 n> 13 ct _ c: Du -s :3 8.l.0 A sustained wind speed of A sustained wind speed of A sustained wind speed of N/A G3 (High Winds) greater than b0 mph as greater than 74 mph as greater than 80 mph as indicated on Wind Speed indicated on Wind Speed indicated on Wind Speed Rec order ( NDS -50 9 ). Recorder (ND5-501). Recorder (NDS-501). 08 (two) 08 (TWO) Dg (IWO) Ihree' Mile Island is the National Weather lhe National Weather entluded in a National Serv a c e ( NW5) is fore-Service (NWS) is Weather Service (NW5) casting sustained winds in forecasting sustained jD gg 25 tornado or hurricane excess of 74 mph for the winds in escess of 80 mph C " WARNING" area. Harrisburg ared within d for the Harrisburg area {~
- hours, within 4 hours, o
g a 3 >g Qg (rHatt) Qg (IHkit) na 25 Jt o la 1 Z LJ E C) C. ) C) V i
2ee thCLO50RE 2 (Cont'el ret t m BCh ACTION LEVEL MAIRIX 3 {D UNUSUAt SITE AR[A us EVENT ALERT C(MIRAL n> [MfBCrurY [Mr ecr ury j3 lll
- 8. 8.D (Cont'd)
C4 The NWS espects a tornado The NWS espects a tornado h to track directly over the of f5 intensity to track g7 gy facility. directly over the facility. 3: ENER 08 (FOUR) QR (f00R) [I Any tornado striking the Any tornado of f5 facility. intensity striking the '!( facility. (( () 3 8./ Other HAlARD5 being Other more 51 VERI HAJARDS Other HAJARDS being N/A (Man-Made Phenomena) EXPERIENCf D or PROJECIED. being I XPikIE NCEO. during EXPERilNCID or PROJECitD during operation at power operatson at power. and-AND the plant is HDI IN indicated by one of the icated by one of the C0tD SHUIDOWN (Average -4 f ollowing conditions. as f ollowing conditions. as temperature <200*F) Eg -4 determined by the Shif t determined by the Shaf t indicated by one of 13 3C Supervisor /tmergency Supervisor /tmergency f ollowing conditions. as f7".* pn Director: Derector: determined by the Shift gg ha no 8 Supervisor /fmergency
- 3 09 Director:
(([! o 8.7,A Onsite aircraft crash Aircraf t crash QR ether Aercraft crash which N/A ,g[$ u3 da (Plane /Irain Accident) outside the protected ared messile impact within the affects vital structures fence &HD HQ1 impacting protected area QB ento any by inpact QR by fire. s r1 permanent plant structures permanent plant structure. C) %C 08 a, train derailment [ 9 within the exclusion area ct D. c: su -t
- 3 MD 8.2.8 Unanticipated emplosion Known emplosion damage to Emplosion QB missile N/A (taplosion) detected near the site QR any permaneat plant impact which causes severe onsite.
structure. damage to safe shutdown equipment. 33 EE CN 7 _s_m a C 5 j) ai 3 ~ PJ 2E ]C O 73 3 1 J -a LJ C) C) 9
e. 2e (NCLOSURE 2 (C ont 'd) rn EMISCINCY ACIION LfVEL MAIBIX f UNUSUAL .s $1!E ARIA GE NE RAL J3 EVLgf AlfRI [Mf erf ury [Mf arf ury D n 1:: 8.2.C Near the site or onsite Rele'ase of 10XIC - Entry of 10XIC - ItAMMA8tE N/A (][ (Chemicals) IDXIC - ftAMMA8tf GA5 or FI AMMA8tf GAS into the GA5 into vital areas which LIQUID release which could plant which affects the affects the operation of W' e EEEE pu affect the habitability safe operation of the safe shutdown equipment. (( required for normal plant plant as determined by the operability. Shift Supervisor /[mergency -g Director. [] aqg rv 8.2.0 Turbine rotating equipment Turbine failure resulting N/A N/A 23 (lurbene f ailurel failure causing a reattor in casing penetration trip. 8.1 fire in a permanent plant Fire which jeopardines the fire which comprumises the N/A E3 -4 (fire) structure which CANNQI be operability of a safety functions of a safety 13,3k controlled by the fire systes system trenders it inoper-brigade within 10 minutes able) as determined 9 -- n> t h3 of discovery by the Shift Superwesor/ "$ pq e Emergency Osrector. 08 (two) OR (two) c, a -a - 80
- s -s An outside plant structure A permanent plant fire requiring offsite structure (instde the 90 23 fire fighting assistance prutected area) fire which
~1 r) to control the fire as requires offsete fire ff < determined by the Shift fighting capabilities as Supervisor /fmergency determined by the $hift na 10 CL -- Director. Supervisor /imergency. Ej (( 40 33 Ch 2E as c 3 T C) er O g a 3 hJ 35 JC O 10 2E I Ef LJ C) C. ) C) ~* 29
o = 2 INCLOSURE 2 (Cont'd) s m Em auseCY ACIlON LLVEL MAIR11 9m UNUSUAt 5 TIE AR(A CENfRAL EVENT AliRT EM Bu serY iser au nary m 3n C 8.4 N/A fvacuation of the control fvacuation of the control N/A O (Control Room Ivacuation) room is ANIICIPAIED or room has OCCURRIO and h REQUIRED and CONfROL of CONTROL of all the m all the following shutdown following shutdown 5YSIEMS we. SV5IfM5 or (QUIPMtNI as or (QUIPMLNI is @l established from local established f rom local stations within 15 minutes stations within 15 minutes n as determined by the Shif t as determined by the Shift se Supervisor /Emergenc y Supervisor / Emergency M Director: Director: O 3 - [mergenc y f eedwater - Emergency feedwater System System - Ivrbine Bypass Valves or - Turbine Bypass Valves or Atmosphersc Steam Dump Atmospheric Steam Dump Valves Valves - Nheep pumps - Nkeup pumps g - Nheup flow control valve - Nkeup flow control valve gw - letdown flow control - Letdown flow control UZ e-o assassaamassassmasanssammassammassmannassammassammaassammassammanasaasmannassusassmasassammamansumassmanammanussammaanansammanaamassaammassanssaamass 3.1 fD m N o I 3 m3 et m W 3 "s O 90m %3 -s n O S< n m "O G-C & m"s 3 3 Ch 2 7 A C 3 5 ? X, o N 2 T O T c.a I O E O. O W a
e a fe (NC105URE 2 (Cont'd) m EMRCf NCY ACIl0N LEVEL MATRIX UNUSUAL Silf ARIA CJ NIRAt so EVENI AlIRI E W RU t#Y f M RUNCY 9.0 Rf ACIIVIIV (ONTROL w 9.1 When a plant shutdown is When a plant shutdown is Complete loss of control N/k (Control Rods) required for QtlL sontrol requered for tGRL._J11Ad QtiL of the control rods (A vs M rod SIUCK 001 or 5100K IN control rod 51UCK 001 or function needed for hot d or DROPPED. $ltKK IN or DROPPfD. shutdown) when the reactor is ' critical' with the average temperature at n is25 r. 9 O i 3 \\ 92 Unanticipated positive Control red ejection N/A N/A I (React;wity Insertions) reactivity insertion, indstated by a reactor potentially degrading the trip due to high neutron level of safety of the flu. coincident with loss { plant. indicated by anyone of coolant endications. M of f ollowing conditions as determined by the Shift @y Supervisor /[mergency a Derector. e i 3~ m av An uncoopensated operating 3 m 8 reactivity change n3 ] resulting in a M LID high - 8D reactor coolant outlet )) I temperature alare. e ) m3 -s n QR (IWD) k* Unanticipated Criticality .og~ 08 (IHRIE ) n3 e laadvertent rod withdrawal during operations resulting in a reactor trip. Og (FOUR) Inadvertent moderator I dilution resultsng in a: [ 3 ML]D high reactor 1a o q l coolant outlet Q { g temperature alare. g 7 y 08 O 'u } 1 1 h Reactor Trip [ o _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _}}