ML20087L908

Public Version of Emergency Plan Implementing Procedures 20103, Classification of Emergencies & 20104, Emergency Roster & Jm Felton 840322 Release Memo

ML20087L908
Person / Time
Site:	Turkey Point
Issue date:	01/17/1984
From:	Baker C, Williams J FLORIDA POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
PROC-840117-01, NUDOCS 8403280110
Download: ML20087L908 (31)

Text

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FLORIDA POWER AND LIGHT COMPANY TURKEY POINT UNITS 3 AND 4 EMERGENCY PROCEDURE 20103 DECEMBER 15, 1983

1.0 Title

CLASS!FICATION OF EMERGENCIES 2.0 Approval and List of Effective Pages:

2.1 Approval

Change dated /) 15/W)Rev Awed by PNSC December 15, 1983 Approved by w ant Mgr-Nuclear,

[ 19 9f Approved by ///SMh Vice President of

[ Nuclear Energy w

/7 1h 2.2 List of Effective Pages:

Page Date Page Date Page Date Page DaTe 1 12/15/83 4 4/7/83 7 12/15/83 10 4/7/83 2 9/27/82 5 4/7/83 8 10/13/83 11 4/7/83 3 9/27/82 6 12/15/83 9 4/7/83 12 4/7/83 13 10/13/83

3.0 Scope

3.1 Purpose

This procedure provides instructions on the classification of emergencies at Turkey Point Plant.

3.2 Discussion

Four levels of emergency classification are established. Ir oroer of increasing seriousness, these are:

i l Unusual Event Alert Site Area Emergency General Emergency A graduation is provided to assure fuller response preparations for more serious conditions.

3.3 Authority

50'Mo This procedure implements the Turkey Point Plant Radiological Emergency Plans. g 8403280110 840117 PDR ADOCK 05000250 l F PDR l

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2W3 EMERGEN0Y PROCEDURE 20103, Pt 3E 2 CLASSIFICATION OF EMERCENCIES_

3.4 Definitions

l 3.4.1 Unusual Event - This classification is represented by off-nomal l events or conditions at the Plant for which no significant degradation of the level of safety of the plant has occurred or is expected. Any releases of radioactive material which have occurred or which may be expected are minor and constitute no appreciable health hazard.

3. 4. 2 Alert - This classification is represented by events which involve an actual or lootentiall degradation of the level of safety of the plant combined with a potential for limited uncontrolled radioactivity from the plant.

3.4.3 Site Area Emergency - This classification is composed of events which involve actual or likely major failures of plant functions needed for protection of the public combined with a potential for significant uncontrolled releases of -adioactivity from the plant.

3.4.4 General Emergency - This classification is composed of events which involve actual or inninent substantial core degradation and potential loss of containment integrity combined with a likelihood of significant uncontrolled releases of radioactivity from ,.the plant.

4.0 Precautions

4.1 Conflicting Information:

When apparently conflicting infomation is available, the condition shall be classified at the most serious level indicated.

4.2 Judgmental Decision:

If, in the judgment of the l Emergency Coordinatorl, a situation is more serious than indicated by instrtment readings or ~ other parameters, the emergency condition shall be classified at the more serious level.

5.0 Responsibilities

5.1 Plant Personnel All plant personel are required to promptly report the existence of an i emergency condition to the l Plant Supervisor _ - Puclearl by the fastest means possible.

5.2 l Plant Supervisor - Nuclearl 5.2.1 The lPla'nt Supervisor - Nuclearl shal1 promptly classify off-nomal situations into one of the four-defined categories.

5.2.2 If the diagnosis indicates that the condition is classified as an -

Unusual Event, Alert, Site Area Emergency, or General Emergency the .

Pl ant Supervisor - Nuclearl- shall follow the instructions in Dnergency Procedure 20101 Duties of Emergency Coordinator.

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EMERGErCY PROCEDURE 20103, PAGE 3 9/27/f 2 CLAS.!FICATION OF EMERGENCIES 5.2.3 If an emergency has been declared the l Plant Supervisor - Nuclear l shall become the Emergency Coordinator and retain this position until relieved.

6.0

References:

6.1 Turkey Point Plant lRadiologicall Emergency Plan 6.2 Emergency Procedure 23102, Duties of an Individual Who Discovers an Emergency Condition 6.3 Emergency Procedure 20101, Duties of Emergency Coordinator 7.0 . Records and Notification 3 None

8.0 Instructions

8.1 The l Plant Supervisor - Nuclear l Should initially classify a situation within 15 minutes of the time he has becone aware of it. The initial classification shall be made on the basis of readily available observations and should not rely on laboratory analyses, measurements, or calculations' which would require more than 15 minutes to perfom.

8.2 If subsequent infomation of a more detailed nature (e.g., sampling results) becomes available after the initial classification has been made, the event shall be reclassified by the Emergency Coordinator if appropriate.

8.3 The l Plant Supervisor - Nuclear (Emergency coordinator) shall classify events in accordance with the attached Classification Tables. The event shall be classified by matching the actual situation to the one most

, closely approximating it in the Classification Table.

NOTE: Within fifteen minutes after the initial classification, the state and/or local agencies listed in the appropriate check list in Emergency Procedure 20101, Duties of the Emergency Coordinatcr lmust be notified. Within one hour after the initial classification, the NRC Operations Center in Bethesda, Marylard must be notified l.

e hww

79 70lns 411/91 CL ASSIFICATION TAfftE Page 8 .

lAU5UAL EVEllT MIRT SITF ApfA iMFPfTPCT (41RRAt IMertPrv l

1. PRII4 ART DEPRf55tBITATI0ff - FCCS INITI ATID OUWWAIIY OR AUTSIATICMtY Flow as indicated on fI * *l13 (VP-D)

2. PRiptARY DEPRE554RITATI0le - FAlttRE OF A PittstAftr SAFFTY IWI Rttl[F vat W TO C10$f Sustained increased temperature on TI *-465, 467, 469 or Indication of flow through safetles on IEC flow indicators.

3. PRinARV 9tPRE554mIZAT1011 - TAlttat OF SECopeARY 5 Art!Y OR WItiff VALVE TA Ctest Any 2 of following 3:

Rapid and continuous decrease in steam generator pressure; rapid RCS cooldown; audible steam rettet noise lasting for longer than 10 minutes.

4. PRIIIARY DEPRF551mtlAfl0p - ARNORetAt PRIMARY tf AK Raft (1) RCS water inventory balance RC5 Water inventory balance (l) Pressurlier low pressure Indicates leakage of ) 1 CPet Indicates leakage >$0 gin by: reactor trip or pr$ pressure from an unidentified source; (1) Decreasing pressurlier level decreasfag em entrollably OR . with all charging pumps running (2) E 5 water Inventory balance M fndicates leakage of ) 10 GPM; E High contalement pressure, or OR (3) R5 water Inventory balance (2) Mismatch of >50 GP9t between sunp level, or radiation level.

Indicates leakage to a charging and letdown (including connecting closed system >30 controlled leakage) ~

APn GPet but ( 50 GPM 5 team pressure f p one steam fontaltunent pressure t ; >?n pstn generalue swt sigeeifica.itly asal a t rw.A has m in . .,3 ,,, ..

lower than other two. In progress.

0R.-

(2) Rapit Jecrease in RC5 pressure with subcooled margin ( 30*F.

1 l Arilff J l Complete actions IIsted on Complete actions listed on remplete actions listed on rtunplet e ac t inas l i st ed on the UlIUSUAL EVENT CIIECKLIST. AttRT ClittrLIST. stir ARIA FrotarINCy regrrtl%T. rrNIRAI f ripff r[Y rigt r[ tst.

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f r PolM 4/ Fir 1 Page

• CLAssiflCAil0M TARtf (cont'd)

ALIRT SITE ARfA IlerRCIPCT CflTRAt IMIRfT KT UIRf5UAL EVERT

5. PRinpWT IIEPRf 551NillRiff1H . --, PittstAltT/5IUdiEMV LIAR RATE PRMS R-15 alarming and (I) A gross failure of one steam generator A rapid f ailure of stears generator A release has occurred or is in tubes with a loss of offsite power progress resulting la i P/hr ACS water inventory T lance tutte has occurred with a loss of indicates leakage >10 Gl?t. offsite power as indfcated by: has occurred as Indicated hy: wholebodyer5R{hrthyrnfd at site boundary. (I alle)

Loss of Voltage to both 41 fig V busses loss of voltage to both 4160V and one of the following: busses with:

tai Vaifd alarm en PRMs R-15 er R-19 (b) Decreastog RCS pressure or (1) no signiffcant increase in pressurlier level, contalrunent supip level or (c) Increasing water level in affected high range radiation and-steam generator. (2) a valid alarm on PPMNIE or R-19 or one steam generator's (2) A repfd failure of steam generator level increastng and tubes has occurred (leak of several (3) one of the followM;: reactor hundred CPM) as indicated by: trip on low pressurf rer pressure, RC5 pressure Valid alarm on R-15 or R-19 and not decreasing uncontrollably, sr sfgniffcant increase in contatruient safeguards inttfation on low sisap level with one of the followfog: pressurtter pressure, (a) rapidly decreasing RCS pressure.

j (h) reactor trf p on low pressurlier pressure ,

(c) safeguards inf tlation cn low pressurlier pressure, (d) one steam generator level increastag rapidly.

6. PRIMARY DEPRISIRt??ATIOft - STIMI DRIAlt

• i lacreasing containment pressure RC5 water inventory shows >10 (JH leak High Pl.5 1 131 activity or PRft$ A release has arrurred or is l R-20 alarming and PRMS R-15 or R-19 In progress resulting in I P/hr or unusually loud noise outside OR a valid alarm on PRMS R-15 or R-19 Tontainment R significantly above alarsi point an4 whnfe hMy of % R/hr thyrejd one of the following three: I of the following 2: at site boundary (1 mile).

NO (1) High steamline dif ferential safety

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In ection with: (1) Iffgh steamline delta P tafety l Steam pressure is abnormally lower (a High Contalrunent Pressure E Injection and high contafrvient l la one steam generator, or high (h liigh fontalnment Radiation or pressure with either high l , steam flow in coincidence with (c Audible Indication of Stese7reak containment radiation or alarm on l low I outside contalesment. OR PRMS R-15 or R-19.

l generNr(543*), or low steampressure (600steam (2) liigh psfg) flow In with low T]il9 or low OR I at least two cf the three steam steam generator pressure O (2) NTgh steam flow e 4 low T or generators. (3) liigh Steam flow Safety inEtton with steam flow Safety InjectfEwith f ailure of MSIV. PRMS 1t-15 or R-19 alarsf og.

l

• These criteria are hated upon ferrgency Procedure 20176, Offstte Dose falculations computations land will be I

ggnverted toIlmf l Activity Appendiz ts as perI -Plant Instrumentation Radlochemistry followf Tech.ogSpec.

Installation.ll.

3.1.4 O

l i ACrior l Complete actfons Ilsted on Complete actions Ilsted on templete actions IIsted on remplete actiaas listed on the uRustint tvtRT CHECKLIST. Atter CHrcrtisT. slit ARIA TMfRcine Ci tratist. rf rrest f wori erv rierrrt ist.

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TP ?rlet 12/15/P.1 ..

ftA15fFifATION TAetF rep 6 E[af SITT ASEA FEBCfKT WWpAL(WarTEY ,

_ (War

7. Agnank DC5 TEsotaAftpf AIS/OS petssuK (1) Core sutKooling determined t3 be 2ero by one of folloutag three:

(a) Subcooled margin moettor.

(t) Craph with RCS pressure and hfghest loop temperature.

(c) pressurtzer temperature, and highest RCS temperature <

OP 620*F 02 4

(2) T(3) RN> essure T2535 pstg Da (4) BCS Pressure (1770 psig Tth valid core estt thermocouple 1 620*f.

a. CelsAmi pisip 5tl7uer wiTu Fwt easinct 8C5 finw decreastng rapidly and A release has occurred or is A release has occurred er is rest 5 R-20 alarming and RCS 131 activity in progress resulting in $n ap/br in progress resulttag in I p/hr whole body for 1/2 hour or 'WI whole body or

• p/hr thyrote at

->300fCt/em) mR/hr whole Ledy for 2 ritputes at the site houdary* (1 mile) site boudary (I mile).*

8 FWL NAIOLIIE ACCIKWT Fuel dameen het errurred Ms.for damage has cerured to ene nr ance A release has arcarred ne is in or is faminent as Indicated by: spent fuel assemblies as tedicated by: progress resulttaq 19 i R/hr whole body or 5 e/hr thyrold at (1) Nottitcation from the fuel handling (1) Motification from fuel handitag the site boundary (I ette).*

crew that a spent fuel assem6ly has crew of major damage (e.g. large been dropped or damaged, object damages fuel water level telow top of fuel) and

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AND (2) Any of the followinNgS channels sfontftcartly abcee the

. (2) Any of the following APMS Channels the alare point: 5-7. 8 7. P.

alarming: R-2, 5, 7. P. 19, 71. ??. IF. Ig. 21, 2.* or (3) ppm 5 R-17 or e-TT stentitcantly OR above the alare point ,

v-(3) paMS R-12 or R-14 alarming.

• These criterta are based upon Emergency procedure 20!?6. Of fsite Dose Calculations land util re converted to Appendtz I - Instrumentation Folloutng Installatten.

I 80lIUn l Camplete actions IIsted on Complete actions listed on Co wlete actions IIsted on rase! rte actions listed en AttRT CleffrtI5T. 5 fit fara Jrgpr.Itty CHFfrtIST. cturppt tmsprierv Rffrtist.

the UkU5tet (WthT CletCattST.

I

IP 7tilp3 IP/15/PO page 7 -

re autFICATION TAftlf SITE AAfA ftERGENCY ffMBAt tw arduCV AlfAT .

WassilAL EW NT 10.1055 0F SAff $8Effillhst FifRCTiftBS (1) A transient has occurred teactor remalas critical (1) Fallure of reactor protection system requf ring operetton of shutdown after transleet induced trty J to initiate and complete a Acram = ditch signal is inttf ated g brings the reactor subtritical as systems with f ailure to bring indicated by reactor remaining critical reactor subcritical with cont-el (1) Pr5 pressure ) safety rods and no care damage J after trip signal is inttf ated. tamedTaTely evident. valve settings on (e.g. PPM 5 R-20 not alarutag) f5 (2) THR system not operable or inattllty 08 (7) Entatament pressure d, to sustain forced or natural or temperature circulation as indicated by: (?) loss of function needed for hot Increasing rapidly.

shutdown:

3 Increasing RCS tegerature as seen on wide (a) Scram system inoperable or range loop temperature recorders or core (b) Condenser dwys, atmosph7e tc emit themocouples and dumps, and steen generator safettes inoperable or (a) StR punps not running or (c) Pio nomal and aust11ery feed (b) No flow indicated on 6 *-605 g water flow or (c) Bio flow on loop flow indicators. (d) Inahility tTaateup to the BCS (inadequate high pressure injection).

II. FWL ELEIENT FAftlM Core damage with inadeguate core Loss of 7 of 3 fission (1) popes a-20 alarming (1) RCS sample shows I-131 activity cooling determined by: product barriers with a Afs0 > 300 luCf/ enl potentfai for loss of the

• I (2) TEntfrued aC5 sample Tin (1)RC5l-131 activity >300luCf/eml third harrier:

Indicates that coolant (2) 7995 R-20 significantly above alarm Afsn activity is greater than point and latioratory analysis shows an (1) anown tera as defined in the Tech Spec limit for increase greater than it fuel fattures T7JpC5That > 670*F or care entt Site Area Imergency and thermocouple > 700*F. i todine spthe. In 30 minutes or a total fuel f ailure fuel fatlere as deft W in ,

(Tech Spec Figure 3.1-1) of 51.* linusual fuent with contatn- 1 meet pressure lacreasing to desfon limits or la cent W * - ~Itri has beca lost.

OR T/c tube breat as defined in Alert (het no loss of offstte power) with clad damage as defined in l*nusual Ivent and leselnent failure of PSIV.

• These criteria will be implemented upon installation of Appendis I f astrismentation. ' .

Mum l #

I Complete actions Ifsted on complete actions ilsted on Complete actions ilsted on Complete actions IIsted on Slit /PfA FMIPcterv CHttstIST. rf pf pet (Pf fr[h(f (Pf f rt l%f.

ALERT CHfftLIST.

the UIEISUAL EVE 81T CHECallsT. d I

f p 7nin $

Infl3/p1 Page P .

CLA55PFICATION TAett (cont'd)

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5ITE AREA EM#GINCY ENRAL (MMTEV ALERT

--:-- EVElf!

II. FML EIEMIIT FAllistE (continued)

(7) rnom tro as defined in

$tte Area Emergency with:

(a) containment f alltag to isolate ce (b) contatsument press-wrt red ) destgn Itetts N

. - T[G tube break as def fned te Alert class with:

(a) steam breat between l contalement and M%IV j

< OE I (h) Erstream break with failure of M51V tiliH EITHER Gs of f(C5 or loss of all AC or aC5 T

>670*F(foreenNt thermocoopte

> FfWl'F) and increasing d

(1) fled Apug,as defted to thusual Event and loss of ICCS capability with I of 3 following:

(a) Contalsweent integrity last OR (b) Yeamitne breat downstream l af n%IV with fatture of M51V f'n i

(c) Weenline breat between containment and MSIV.

12. ENREIICV COERDIIIRTOR DISCIIET10ll i

Emergency Coordinator's judgment that Imergency Coordinator's judgment Emergency Coordinator's judpent Emergency Coordinator's judgment that plant conditions entst which l that plant conditions esist which warrant plant condittens entst which warrant that plant conditions entst which activation of emergency centers make release of large amounts warrant facreased awareness on the precautionary activation of the Techafcal and monitoring teams or a of redinactivity, in a short l part of the operating staf f and/or Support Center and piscing near-stte precautionary cotification to the perind of time, possible (e.g.

ocal, o'fstte authorftles. Emergency Operatfons Facility any core melt situation).

l

' and other key emergency personnel pubite near the site.

--OELETED on stsadby.

l ACIIGII l l Cnaplete actInns list %I en Complete actlans listed on Complete actions Itsted on Complete actions I1sted on (I risAt (Pf ar4 prf Of f rt,itT. [

Attsf CHECtLI51 Silt Asf A IMisrEPCT CHirKtl5T.

ld LhellH_USilAt EvtllT CHECKil5T.

rP 70ln*

4/1/e1 .

CLA553rICATION TA8t[ (cont'd) Pagn a tilRfSilAL [VElli AlfRT SITF ARIA IMIltCIPCT f4PIRAt FPfROFPrf l 13. UNC0ffTR0ttfD IFF1W9ff Rfl[ASF A release has occurred or is in A release that has occurrwt or 15 in A release has occurred or is A rflease has occurred or is le progress which is greater than the progress which is greater than 10 times in progress resulting in 50 mR/hr progress resultlewt in l P/hr Tech. Spec. Ilmit as Indicated by the Tech. Spec. Ifmit as indicated t,y the whole bovfy or 750 rd/hr thyroid whole fiody or an Inteorated dose Pki$ R.14 jlerming and reading plant vent te9C in the alann condfilon for 1/? hour or 500 mR/hr whole of SR thyrnto at site houndary*

> 2.5 x 10 cpn (approntmately and readtng significantly greater than body or 7500 W/hr thyroid for ? (I mile) or r ctainment o lilah 5 thes the alarin set point. alarm point (arpronteately 4n,000 minutes at the site boundary

• Range Radfption Ponitor cpm) . (I mile) or Containment High ~> l.1 3 10 m/hr.

i At 0 Radition Monitor > l.3 m Fim e-14 should he alarmf an and Rap la R /br.

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pegged off scale high.

14. HirAt RAplATI0ff IEWt$ IN PI AffT (1) Any valid and onespected area monitor alarin with meter near or greater than full scale deflection (10 mR/hr)

ER.

(2) Ifnexpected plant fodine or particulate airborne concentration) 1000 HPC as per 10 CFR 20 Appendfx C T ble I, as seen in routine surveying or sampling.

I I

i

>

• These criteria are based upon [mergency Procedure 70l?6, Of fsite Dose Calculations M will be converted to Apperwfix I - Instrassentation Following Installation.}

l AC T10tf l

Complete actfons IIsted on Complete actfons Itsted on Complete actions IIsted on rmplete actinns listed an the UltHSUAL EVEPT CHICrtlST. ALERT CitrCRLIST. $11E ARIA FMIRC[NCY fHICrtlST. ri t'r Rf;ller nri t'ry retrri Isf. ,

FP 70101 a/7/P1 CLA551FICAll0N TABLE (cont'd) Page to

• team ENRT ARIR T SITF ARfA IN RE RCT stNaat IMREftY

15. Oilta sitailllCAKI EWitTS TilAT ColRD (EAD 10 Ciutt Mtl (t) A known tfVA as defined in Site Area Faergency and fatfure of FCC% to deliver flew to the core has occurred resulting te clad damage as ineficated by containment area monitors pFMt P l-3 or P 3 6 or fontainmert l'igh Range Radiatfor Mnnitor alarmtrg.

OR T7) Peactor trip oc low steam ger.erator levels with wiv'e range levels decreasing toward iern with one of the followine twn:

(a) loss of main enedenser, loss of austlf ary feed finw (with high head Safety Inject fon capahflit y).

OR (h) IIst of main coedenser, Ints of ausillary feed flow and no high head $afety injectine capability and 30 minutes hat elapsed witFTm low head Safety Injection capahflity or at.illfary feed flow.

OR TT) A 6pown inre as def f ned in Site Area Faergency has ercurred M one of follow!nq 7:

(a) RHR flow IndicaMr is F l *

(415 reads rero for I/7 home af ter rectrculation phase is attempted ard prt temperature is rfsfeg i'P (b) Failure of contalment-spray and mergency coolers to prevent rantaltenent temperature frren rising enressively.

l l ACIIOP Complete actions 1Isted on Complete actfons listed on Complete actfons listed on l

Conplete actlens listed on the UlIUSUAL EVENT CMCKLIST. AlfRT CllECKLIST. SilE ARFA EPFRGENCY CMCFL IST. (:IPIRAt #MIRr4 Pry rl4Crtiti.

! fi' Fin 1 4 / 7/p1 Ci AtStrlCATION TAalE (cont'd) rage Il Al f R T SITF ARIA tierRCTPCV (JMRpt TNtarTrrt INIUSUAL EVENT l 1(. 1055 0F POWIR CatelT10f'S l

Sustained Loss of offsite power or- (1) Loss of cf fsite and onsite AC power (1) toss of of fstte power and Inss of offstte pcwar aed Inss ensite AC power capability as Capability as in3Tcated by: loss of onsite A.C. power of onsite P.C. power cafahilit y l Indicated by: capahfilty for > 15 minutes as defined in plert, with Inst as indicated by: of all feedwater capahtittles (a) 4kV bus "A" and "B" low voltage alarms for T I hour.

(!) Respective supply breakers open (a) 4kV bus "A" and "B" low voltage OR alarms for > 15 minutes OR TE) 4kV bus "A" and "R" voltage and OR (h) EV hus "A" and "P" voltage and

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amp meters reading zero (2) Voltage and/or amp meters OR amp meters reading Fero for indicate zero. Tc) Ali supply breakers open with failure > 15 minutes of emergency diesel generators to OR power their respective 4kV bus either (c) Mi supply breakers open and both autnmattrelly or hy e nval action rmergeney die 91 yacra'nrs fall from the Control Room. See NOTE Al. to power their respective 4 kV bus OR ef ther automatically er by manual (2) Ess of all vital onstte D.C. power- as action from the Control Room or fndicated by DC load trouhle alarms on local for. trol Paard. See Pair al all 11.C. busses or decreasing voltage OR on all D.C. busses below alarm point. (?) E ss of all vital onsite D.C.

See NOTE al. power for >l5 minutes as indicated by D.C. load center trouble alarms or voltage decreasing below the alarm point on all D.C. husses.

See NOTE al. -

NOTE 1: An Alert should be declared as soon as a loss of power Is experienced. A Site Area Imergency should be declared if the loss lasts for > 15 min., or if the Emergency Coordinator leaves the Contal Room during the first 15 minu'*s.

17. ROSS OF COPTAIISEINT INTTGtlTV Violation of containment fntegrity I as deffned in Section 1.5 of Technical Spectfications unless the reactor is in the cold shutdown or violation of

[

condition; containment7ntegrity as deff nett in

Section 1.5 of Technical Specffctions when the reactor vessel head is removed unless the reactor j is in the refueling shutdown

.. condition. ~ j l PCil0N l f.omplete acticas listed on Complete actions listed on rmplete actions listed on fomplete utions IIsted on the UNU5UAL EVENT ClitutlST. At FRi CITCttl5T. SilI ARIA TMrprJPCY CHICrtI%T. rI PI R AI It4Rrs ery retral ist.

rp 7pini elH9' .

CLA55IriCAll0N taste (cont'd) Page 17

• AlfRT SITE ARfA EVERGINCY GNIRAL E11FoffpCY INRISIIRL EVENT a

1R. C0ffTAMIIIATFD PtRSONNIl Transportation of loolential or confirmed contaminated l Injured Individual (s) from the site to an offsite facility.

19. LOSS OF A55E551 tiff FIseCTI0tts Significant loss of effluent Most or all enranciator alanus lost All annunciator alarms Inst for .

monitoring capability, meteoro- with plant not at cold shutdown > 15 minutes and a plant transtent logical lastrements, communications, during transient conditions M has been inttlated or is in 4tc., which impairs ability to inahility to famediately restore progress.

perform energency assessement. power to annunciators.

20. PATURAL pHEIGIINA (1)lootification'bytheweather _1)

( lootification by the weather bureau Plant not in a cold shutdown A major internal or bureau of a hurricane of the approach of a hurrfcane with . condition and any one of the enternal event (e.g. fires, n rning or tornado sighted wf nds up to design basis (??S aph) levels following ( Eee: earthquakes, plane crashes) in the Owner Controlled OR any tornado striking plant has occurred, which contre Area structures. (a)Motificationbytheweather cause massive comanon elanage bureau of the approach of a to plant systeins resultinet hurricane with winds > 775 mph. In any of the other reneral Olt . Alt OR Faergency 1pitiating conditfons.

(2) Ky certhquake felt or '(t) Tn'y earthquake that could cause, or (ts) Tn'y earthquake that causes detected on installed seismic already caused shutdown of turbine shutdown of turbine generator instrumentation. generator and/or reactor. and/or reactor coupled with degradation of safety systems.

OR OR-OR (3) Wrricane surges or floods (3) Any finod or hurricane surge that raises' (c) TTood or hurricene surge, that is that limit access to the site. the water level to at or near the > design level of in feet and causes design level of 18 feet above M.I .W. shutdown of ti.rbine generator and/or reactor with degradation of safety systens.

21. HAZARDS TO stall 0ll DPERAfl0p (1) Any aircraft cessh on-site or (1) Afrcraft crash on-site involving Plant not at cold shutdown unusual aircraft act Wity over plant structures M f ac il f ty OR OR '(2) W ssile impacts from any source 4

. (2) E site explosion involving plant structures or components (a) Afrcraft crash resulting in Dei OR damage to vital structures or (3) Toxic or flammable gas release (3) Emage to plant structures or components crinronents by tapact or fire, near or on-site could from an emplosion CR threaten personnel OR, (b) NTssfle tapact or emplosion fa (4) Detection by portahle instrumentation, resulting in damage to safety

(4) Epid turbine shutdown due to or notification from off-site sources systems j turbine generator failure. that gases greater than their tonic or

= , flamnable limits have entered OR

{' the factilty. (c) Tntry of gases greater than their OR tonic or flaunable limits l'nto l- (5) Turbine shutdown wfth observation of control or vital areas and which i casing penetration. renders one train of a safet? '

j related myttom inaparahle.

l AC110P l 6M 1

Complete actions 11sted on Complete actions Ilsted on remplete acttons listed on 'ons litted on g i the tilRISUAL EVElli CHECKLIST. ALERT CIsFrKLIST. SIIE ARIA EMier.FliCV Clairrt IST. rI n g ' , irry ferrrrl ltr.

l' l o s . , s .<

l In/I3/R1 l CLA55fFICATI0ff TAptE (cont'd) rag,11 I ,

l IRRISIIE EUEIIT ALERT SITE AREA ENRERCT' EEPfitR IMRSEptY l

22. 5EClutITY TistIAT l

Security contingency resulting in A security emergency declared as A security emergency involving Physical attack on the plant l_

initiation of PTP Safequerds deffned in the Safeguards Contingency fassinent occupancy of the rmtrol resultf sg in occuoatfon of Contingency Plan to one or mere Plan. room or other vital areas to the centrol room or other vital of the ftens Ifsted below. reactor system as defined in the areas.

I. Bomb threat Safeguards Contingency Plan.

2. Attack threat

3. Civil disturbance

4. Protected area intrusion

5. Sabotage attempt

6. Internal disturbance

7. Vital area intrusfon

8. Sechrity Force strike.

23. Colmt0L ROGI EVACUATI0fl Evacuation of control room Evacuation of control rene sad anticipated or required utth control control of shutdown systems not of shutdown systems established from estahlf shed from local stations local stations. In 15 minutes.

24. FIRE (1) Uncontrolled fire onsite Uncontrolled fire, potentfally Fire resulting in degradation lasting longer than 10 affecting safety systems y d of safety systems.

minutes requirfng offstte support.

OR (2) TTre requiring offsste , .

support

25. LO55 0F ElIGIKERED 15AFETTl FEAftstES/ FIRE FIl0TECTICII ST5TEft5 Loss of any equf pment listed .

In the Techefcal Specificatfoes Section 3.4 requiring plant shutdown; g loss of any fastrementation If sted in Technical Specifications Section 3.5 requiring plant shutdown; g, loss of any fire protection systems Ifsted in Technical Specf ficattens Section 3.14; requfrIog plant shutd w and Industy to make these sysians operable ir provide compensatory measuresl within.the specified time limits of 4- lasolicableTechnicalSpecfficationsl.

An URU5UAL Event shall be declared actualloadreductionbeginsl. -

l l ACTif1H j Complete actions IIsted on Complete actions IIsted on l Complete actions IIsted on ranplete actions listed oc i

. the UNUSUAL EVENT CHECKLIST. ALERT CHECKLIST. , C rlP[ pat (MIsr.F>ry rHrrrtI V.

SIIEAREAEMERGENCYCHECKQ5T.

FLORIDA POWEP AND LIGHT EOMPANY TURKEY POINI UNITS 3 ANC 4 l EMERGENCY PROCEDURE 20104 l DECEMBER 15, 1983 l

1.0 Title

EMERGENCY RCSTER 2.0 Approval and List of Effective Pages:

2.1 Approval

Change dated [ /15/AT) Reviewee by PNSC December 15, 1983 Approved by !

, ~ Plant Mgr.-Nuc >h . [ 19 b O Vice President of JM4 Approved by Nuclear Energy _19 k 2.2 List of Effective Pages:  ! _

^

Page Date Page Date Pg Date Page Date 1 12/15/83 5 12/15/83 9 12/15/83 13 12/15/83 2 12/15/83 6 12/15/83 10 12/15/83 14 5/5/P3 3 5/20/83 7 12/15/83 11 12/15/83 15 5/20/P3 4 5/5/83 8 12/15/93 12 12/15/83 16 5/5/P3

3.0 Scope

3. '1

Purpose:

This procedure provides the phone nunters of personnel involved with emergency response.

3.2 Authority

This procedure implements the Turkey Pcint Plant Radiological Emergency Plans.

4.0 Precautions

None

5. 0 Responsibilities:

5.1 The Energency ~ Planning Coordinator shall be responsible for periodic-verification and updating of this procedure.

5.2. FPL personnel in this procedJre should notify the Emergcacy : Planning Coordinator.when a change pertinent to irfonnation appearing in the roster occurs.

.a w. s a .m,r-,-r-m- y

EMES 3ENCY PROCEDURE 20104, PAGE 2 EFEPGENCY POSTEP 6.0

References:

6.1 Turkey Point Plant Radiological Emergency Plan 6.2 Emergency Procedure 20105, Activation of the On-Site Support Centers 7.0 Records and Notifications:

None

8.0 Instructions

8.1 Every plant condition which requires initiation of the Emergency Plan will be classified as an Unusual Event Alert, Site Area Emergency, or General Emergency by the Energency Coordinator, who will so inform the Puty Call .

Superviscr. The Dety Call Supervisor shall follow the instructions below I on who needs to be notified by him for each of the four categories. A list of the actual alteraates and telephone ntsnbers is attached in Appendix A.

8.2 Unusual Event 8.2.1 For all Unusual Events, the Duty Call Supervisor shall notify the fc11owing or their alternates:

Errergency Control Officer (See Appendix A) i Sitc Manager (See Appendix A)

Plant Manager - Nuclear (See Appendix A)

NRC Resident Inspector (See Appendix A) 8.2.2 For Unusual Events, the Duty Call Supervisor shall call any aeditional plant management or supervision which he or the Emergency Cc ordinator deems appropriate to provide assistance in remedying the ccndition.

8.2.3 Ir addition, when the Unusual Event is a hurricane wartsing, the Duty i Call Supervisor should call the following or their alternates, urless they have already been notified or are already on site.

Security Supervisor (See Appendix A) i Orerations Superintendent-Nuclear (See Appendix'A)

Miintenance Superintendent-Nuclear. (See Appendix A)

T(chnical Si.pervisor (See Appendix A)

I and C Supervisor (See Appendix A)

Ltnd Managenent Site Manager (SeeAppendixA}

I 8.2.4 It additior, when the Unusual ~ Event involves iritiation of the S(curity Contingency Plan, the Duty Call Supervisor shall notify the St:curity Supervisor or his alternate unless .he ias already been notified or is already on site. l(See Appendix d -

8.3 Alert 8.3.1 For all Alerts, the Duty Call Supervisor shall notify the following or their alternates:

UIDA3 EMERGENCY PROCEDURE 20:04, PAGE 3 EMERGENCY ROSTiR Emergency Control Of ficer (See Appendix A)

Site Manager See Appendix A)

Plant Manager - Nuclear (SeeAppendixA)

NRC Resident Inspector (See Appendix A)l 1 8.3.2 For any Alert, the Duty Call Supervisor shall call any additional i plant management or supervision which he or the Emergency Coordinator

deems appropriate to provide assistance in renedying the condition, j (Reference Emergency Procedure 20105, Activation of On-Site Support j Centers).

I 8.3.3 Refer to Appendixes D and E.

8.4 Site Area Emergency i

! 8.4.1 For all Site Area Emergencies, the Duty Call Supervisor shall notify

! the following or their alternates:

1 I

Emergency Control Officer _

LSeeAppendixA)

Site Manager LSee Appendix A) i Plant Manager - Nuclear

NRC Resident inspector (SeeAppendixA)l (See Appendix A) ,

8.4.2 For any Site Area Emergency which might require site evacuation, the L Duty call Supervisor shall notify the- following or his alternate

[ unless he has already been notified or is on site:

i l Security Supervisor l(See Appendix A)l l

8. 4.'3 For any Site Area Emergency tre Duty Call Supervisor shall call any additional plant management or supervision which he or the Emergency

] Coordinator deems appropriate to provide assistance in remedying the l condition. (Reference Emergency Procedure 20105, ' Activation of On-l Site Support Centers).

l 8.4.4 Refer to Appendixes D and E. i i

8. 5 General Emergency l 8.5.1 For all General Emergencies, the Duty Call Supervisor shall notify the following or their alternates:

Emer. Control Dificer . SeeAppendixA)

Site Manager s Appendix A)

Plant Manager-Nuclear (See Appendix A)

NRC Resident Insp.

Security Supervisor- (See Appendix (See Appendix A) A)l t

8.5.2 For any General Emergency the Duty Call Supervisor shall cal _1 any additional . plant management or supervision which . he or' the .

Emergency Coordinator deems appropriate to provide assistance in -

remedying the ' condition. _ (Reference Emergency Procedure 20105, Activation of On-Site Support Centers).

1

.- .- _. =.

E*ERGENCY PROCEDURE 20104, PAGE 4 EMERGENCY ROSTER 8.5.3 Refer to Appendixes D and E.

8.6 Appendix B is the Security Team Leader's Call List of personnel who shall be notified during an energency.

8. 7 Appendix C contains miscellaneous phone numbers that may be needed during an emergency.

8.8 Appendix D contains the TSC Emergency Response Staff Call list 8.9 Appendix E contains the OSC Dnergency Response Staff Call List 8.10 l Appendix F contains the TSC and OSC Communication Lines Directory.1 e

o l

l

EMTRCENCY PROCEDURE 20104, PEiE 5 EMERGENCY POSTEP APPENDIX A DUTY CALL SUPERVISOR'S CALL LIST TITLE NAME PHONE BEEPER h0ME l CFFICE Emergency Control Officer 1st Alternate 2nc Alternate l Alternates l Rotte for EC0 Nuclear Energy Duty Officers

~

l l

l l

l

1. If the Emergency Control Officer or his alte-nates cannot be rea:hed, the appropriate Nuclear Energy Duty Officer should be contacted. The approp iate Duty Officer will be one of those listed above and is listed on the Nuclear Energy Duty Officer Roster for the week involved.

___2_ _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . . _ ___ -._N.

~ ~

EMERGENCY PROCEDURE 20104, F1GE F EMERGENCY ROSTEP l APPENDIX A DUTY CALL SUPERVISOR'S CALL LIST TITLE NAME TELEPHONE HOME l OFFICE I BEEPER 3 Site Manager 1st Alternate Plant Manager - N

, 1st Alternate 2nd Alternate NRC Resident Inspector Security Supv. '

Ist Alternate  !

2nd Alternate Maintenance Supv.-N 1st Alternate 2nd Alternate Technical Supv.

i ist Alternate 2nd Alternate I and C Supervisor 1st Alternate 2nd Alternate Land Management Site Mgr.

1st Alternate 2nd Alternate

• PTP telephone numbers

__ m- _.__- - - - _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ . . _ _ - _ __ _ _ _ - _ .

EMERGEt Y PROCEDURE 20104, PAGE 7 EMERGENCY ROSTEP APPENDIX A DUTY CALI. SUPERVISOR'S CALL LIST (cont'd)

Ti1LE NAME PHONE / BEEPER HOME ADDITIONAL PLANT PER50!4NEL WHO IT MAY BE APPROPEIATE TO CONTACT Nuc. Operations Supv.

Startup Supt.-Nuclear Plant Manager - Fossil l

Oper. Supt. - Fossil Plant Supervisor -

Fossil Results Maint. Supt. - Fossil Plant Supervisor I -

Fossil Operations P1 ant Supv. - Nuc.

Plant Supv. - Nuc.

Plant Supv. - Nuc.

Plant Supv. - Nuc.

Plant Supv. - Nuc.

l Plant Supv. I - Nuc _f, Quality Assurance -

Turkey Point Plant Plant Construction Emergency Plan Coord.-

a m

-- - _ _ - _ - _ . - _ . - _ _-_-______-._.m_2._____-.___.__a

12ilitF 3 EMERGENCY PROCEDURE 20104, PAGE P EMERGENCY ROSTEP APPENDIX B SECURITY TEAM LEADER'S CA 6 L LIST s

TITLE PH KE l U. S. Air Force Sea Survival School Training Facility 248 84P7 j l

l Bechtel Corporation Land Management (Cooling Canals)

TELEPHCFE TITLE NAME/ ADDRESS FOME OFFICE Land Management -

Site Manager Alternates:

t

EMERGENCY PRO :EDURE 20104, PAGE 9 4

EMERC-:NCY ROSTER A3PENDIX C ADDITIONAL USEFUL NUMBERS l

This section lists numbers, not included in any of the call lists, which may be of use during an energency condition. j i

l FUNCTION LOCATION TELEPHONE On Site Emergency Turkey Point Units 3 and 4 Control Station Control Rcom On Site Energency Turkey Point I Control Station Main Entrance Station

, Operational 1st Floor Support Center I and C Building St. Lucie Plant Unit 1 General Office Info. General Office (business hours only)

Assembly Area, Florida City Substation All Personnel 16100 SW 344 Street (Palm Drive)

Technical Support Turkey Point Center North and adjacent to IC Building  !

Emergency General Office Operations Facility Conference Dining Area-Juno Office Juno Beach Building i (Business Hours only) l c

i eg

- - - - - - . . =.-

12/15/P 3 EMERGENCY PROCEDURE 20106, PAGE 10 EMERGENCY ROSTER APPENDIX C ADDITIONAL USEFUL NUMBERS (cont'd)

ORGANIZATION TELEPHONE l Hot Ring Down Telephone No 22l State Warning Point, Tallahassee 1-904-488-1320 ALTERNATE 1-904-488-5757 Nuclear Regulatory Commission ENS Hot Line f ALTERNATE NO. I 1-202-951-0550 ALTERNATE NO. 2 1-301-427-4056

. ALTERNATE NO. 3 1-301-492-7000  ;

1 Dade County lEnergency Management Officel 596-8700 or 4

911 and ask for SETft Commander OFF HOURS 596-8176 or -

911 and ask for ShTft Comander Monroe County Civil Defense Officel 1-294-9581 0FF HOURS 1-296-2424 HAFB Command Past Direct Line or 257-8425 or 257-8426 or 257-8427 Dade County Fire Rescue l595-6263l j l

Randle Eastern Ambulance 642-6400-

'l REEF Notification:

Mount Sinai Hospital (Primary) 673-2183

. Baptist Hospital (Backup)- 271-6024 Division Load Dispatcher System Load Dispatcher U. S. Coast Guard Operations Center 350-5611 l

l n- - ,,y. + e- - ,- m C e e--e ~

i 12/15/P3 EMERGEf(CY PROCEDURE 20104, PAGE 11 EMERGENCY ROSTER ,

APPENDIX D TSC Emergency Response Staff Call List FUNCTION TELEPHONE NAME Energency Coordinator Alternate TSC Supervisor First Alternate Second Alternate Third Alternate Fourth Alternate Ops. Supt. - N.

First Alternate Second Alternate Third Alternate Fourth Alternate Fifth Alternate Maint. Supt. - N. ,

First Alternate Second Alternate Third Alternate QC Supv.

Al ternate Tech. Supp. Elec.

Al ternate Tech. Supp. Mech.

Al ternate Tech. Supp. I and C Al ternate Tech. Supp. Projects l Alternate Tech. Supp. Rx Eng.

Alternate Alternate Tech.-Supp. Sys. Prot.

First Alternate Second Alternate

-Tech. Supp. Chem.

Alternate Tech. Supp. Nuc. Ing.

Alternate .

! Tech. Supp. D.C. l l Alternate -l l Tech. Supp. JPE Rep. I l

Alternate I Tech. Supp. Fire Prot.

Alternate HP Supp. Team Lead. l Alternate / Team Member l HP Supp. Teem Member HP Supp. Team Member

EM RGENCY PROCECURE '0104, PAGE 12 12/l ~e/8

EMERGENCY RCSTER APPENDIX D (cont'd)

TSC Emergency Response Staff Call List l-

l. NAME FUNCTIOh TELEPHONE Chem. Supp. Teae Member -

Chem. Supp. Tear Member Plt. Data Comm.

Alternate Tech. Supp. W Rep.

Tech. Supp. Tech. Dept. Eng. Supy Alternate

- Corporate Commuricator Management Assistant Off-Duty STA Tech. Su )p. Lead Engr.

Control toon Communicator Alternate -

Alternate ,,

4

1 12/15/P3 1 EMERGENCY PROCEDURE 20104, PAGE 13 l EMERGENCY ROSTER l APPENDIX E OSC Emergency Response Staff Call List NAME FUNCTION TELEPHON.E OSC Supv.

Alternate Sys. Prot. Engr.

Al ternate Mech. Team Leader

~~

Alternate Elec. Team Leader

~~

Alternate Chem. Team Leader Alternate I and C Team Leader Alternate NOTE 1: Additional staff members will be notified by the corresponding team leaders or by TSC staff members. --

NOTE 2: Refer to Energency Procedure 20105, Appendixes A ano B for OSC Emergency Response Team Poster and Notifications Flowpath.

1 l

l

. . ~ . . _

l 5/5/83 EMERGENCY PROCEDURE 20104, 3 AGE 14 1 EMEPGENCY ROSTER l APPENDIX Fl On-Site Support Centers Telephone Directory; Technical Support Center Erergency Management Center Emergency Coordinator - Location 1 Direct Outside Line ENS - NRC (Red Phone) GPO-1496 Management Phone (Ivory Phone) Ext. 24 Circuit Numbers 70 PLNT 2145 2146 2147 Maintenance Superinter/Jent - Location 2

!xt. with headset.

Plant (Pax) Phone Ext.

Operations Superintendent - Location 3 Ext with headset Ext. with speaker box-Corporate Communications - Location 4 Ext Direct outside line - Notepad Direct outside line - Omnifax Technical Support Group - Location 5 Ext.

Ext. with speaker box Ext. with headset Direct uutside line Plant (Pax) Phone Ext. ~

ji. P. and Chemistry Support Group - Location 6 Ext.

Ext.

Ext. with headset Ext. with speaker box J1 rect outside line Plant (Pax) Phone Ext.

l

~

5/20/P3 EMERG:t:CY PROCEDURE 20104, PAGE 15 EMERGENCY ROSTER l APPENDIX F (cont'd)l NRC Conference Room - Location 7 Ext.

Ext.

Ext.

Direct Outside - Onnifax

. Direct Outside Line Direct Private Outside Line ENS (Red Phone) CKT. GP 01496 HPfl (Of f-white Phone) CKT. GDA 02062 Code 93 Broadcast 25 j Managenent Phone (Ivory) Ext. 24 CKT. 70 PLNT 2145 2116 2117 Plant (Pax) Phone Ext. 189 Plant Page (P. A.) Equi 3 ment Plant Data Connunications - Location 8 A switchboard available in the set TSC. is located at this area which contains all extensions of 245-2910 Also the following direct outside lir.es are available:

l Radio Canmunications - Location 9 State Hot Ring down phone CKT 33 PLNT 310414 NOTE:

Local Government Radio (LTG) -

Load Dispatcher Radio -

Plant (Pax) phone Ext.

Plant Page (P. A.) equipment DDS Operations - Location 10 Ext.

Plant (Pax) phone Ext.

Security Area - Location 11 Plant (Pax) phone Ext.

Plant Page (P. A.) equipment L .. ..

. . . ---_-_-----_.-------------A------ - '

~

I l

5/5/83 EMERGENCY PROCEDURE 20104, PAGE 16 l

EMERGEP'CY ROS *ER i

l APPENDIX Fl (cont'd)

Mechanical Equipment Room - Location 12 Plant (Pax) phone Ext. I Plant Page (P. A.) equipment l OSC Management Center Bell Phone Ext.

Plant (Pax) Phone Ext.

Plant Page (PA) Equipment OSC Assembly Area l

Bell Phone Ext.

Plant (Pax) Phone Ext.  ;

4

~

1 l

L -

P O Box 14000. JLNO BEACH. FL 03408 FLORIDA POWER & LIGHT COMPANY January 23, 1984 L-84-18 Mr. Jees P. O'Reilly Regional Administrator, Region II U.S. Nuclear Regul atory Commission 101 Marietta Street, Suite 2900 At1 anta, Georgi a 30303

Dear Mr. O'Reilly:

Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 In accordance with 10 CFR 50, Appendix E, enclosed is 1 copy of Emergency Plan Implementing Procedures:

Number Title ,

20103 Cl assification of Emergencies 20104 Emergency Roster Names, home telephone numbers, and unlisted telephone numbers have been deleted for personal privacy.

Two copies .of the P1an have been forwarded to the Document Control Center by copy of this correspondence.

Very truly yours, O

.W. Willi as Y

Vice President Nuclear Energy Department JWW/ ROM /dc Att achments

! cc: )

Harold F. Reis. Esquire PNS-LI-84-28/L1 PNS-EP-84-9/L1

d. "" i'UAiyo

-- ==E;;;>

%O

'{ t PEOPLE . TR AVING PEOPLE

O Karg

1. c, UNITED STATES 8 ' 'n NUCLEAR REGULATORY COMMISSION I

{ . t WASHINGTON, D. C. 20555 March 22, 1984 l

%g * . * * * ,/

50-250/251 Turkey Point MEMORANDUM FOR: Chief, Document Management Branch, TIDC FROM: Director, Divison of Rules and Records, ADM

SUBJECT:

REVIEW 0F UTILITY EMERGENCY PLAN DOCUMENTATION The submitter of the attached document has expressed no desire to withhold any information contained therein. Therefore, this material may now be made publicly available.

3 J. M. Felton, Director Division of Rules and Records Office of Administration

Attachment:

As stated

,