ML20101R017
| ML20101R017 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 07/14/1983 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20101Q984 | List: |
| References | |
| FOIA-84-253 PROC-830714, NUDOCS 8501180262 | |
| Download: ML20101R017 (450) | |
Text
- - - . ~ - . - . _ --_. -- . _ _ _ = . _.
DUKE POWER COMPANY -t CATAWBA NUCLEAR STATION INDEX EMERGENCY PLAN IMPLEMENTING PROCEDURES P'rocedure # Title RP/0/A/5000/01 Classification of Emergency RP/0/A/5000/02 Notification of Unusual Event J RP/0/A/5000/03 Alert RP/0/A/5000/04 Site Area Emergency l l
RP/0/A/5000/05 General Emergency RP/0/A/5000/06 Natural Disaster RP/0/A/5000/07 Earthquake .
RP/0/A/5000/08 Release of Toxic or Flammable Gas
- RP/0/A/5000/09 Collision / Explosion Ro/0/A/5000/10 Conducting A Site Assembly / Evacuation RP/0/A/5000/11 Offsite Dose Projections without OAC RP/0/B/5000/12 Control of Assessment and Repair Teams HP/0/B/1009/01 Health Physics Recovery Plan 4 HP/0/B/1009/03 Environmental Surveillance Following a Primary to Secondary Leak
- HP/0/B/1009/04 Environmental Monitoring for Emergency Conditions within the Ten Mile Radius of Catawba Nuclear Station HP/0/B/1009/05 Personnel Monitoring for Emergency Conditions
- HP/0/B/1009/06 Alternative Method for Determining Dose Rate Within the
- Reactor Building HP/0/B/1009/07 Inplant Particulate and Iodine Monitoring Under Accident Conditions HP/0/B/1009/08 Contamination Control During , Transportation of -
Contaminated Injured Individuals HP/0/B/1009/09 Guidelines for Accident & Emergency Response i HP/0/B/1009/12 Quantifying Gaseous Releases through Steam Relief Valves under Post-Accident Conditions l HP/0/B/1009/13 Offsite Dose Projection-Uncontrolled Release of Gaseous
{
Radioactive Material Through the Unit Vent HP/0/B/1009/14 Offsite Dose Projection-Uncontrolled Release of Liquid
! Radioactive Material i
HP/0/B/1009/15 Offsite Dose Projection-Uncontrolled Release of Gaseous Radioactive Material Other Than Through the Unit Vent l
- HP/0/B/1009/16 Distribution of Potassium Iodide Tablets in the Event of i a Radioiodine Release i HP/0/B/1009/17 Nuclear Post Accident Containmr.nt Air Sampling System
(
Operat' ion HP/0/B/1009/19 Emergency Radio System Operations, Maintenance and
- Communications
, CP/0/A/8700/11 Sampling at the Post Accident Liquid Sample Pane 1 CNS Directive 3.7.5 Response to Bomb Threat Emergencies CNS Directive 3.8.4 Onsite Emergency Organization I
CNS Directive 2.0.1 News Release CNS Directive 3.0.7 Site Assembly / Evacuation i HP/0/B/1000/06 Emergency Equipment Functional Check and Inventory PT/0/B/4600/06 Emergency Exercise pyl 62 840524
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Fenn 34731 (1941)
(Pennerh EPD.10021)
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1 DuxE P0utR costrAwr (1) ID no: RP/0/A/5000/01 PROCEDURE PREPARATICBI PROCESS RECORD Change (s) 1 to 1 Incorporated (2) STATION: PATAURA
{ (3) PROCEDURE TITLE: CLASSIFICATION OF EMERGENCY l
(4) PREPARED BY: Meh. hieh MTE: umr. 11. 1983 _
(5) REVIEWED BY: Ja **88 A>k _ MTE: bitIliAM-3 l
Cross-Disciplinary Review By: _O N/R:
i (6) TEMPORARY APPROVAL (IF MECESSARY): .
! By:
1 (SRO) Date:
l
- By
Date: ;
(7) APPROVED BY: LA Date:
' H/HfD
! (8) MISCELLANEOUS: G s i
.l Reviewed / Approved By: Date:
i Reviewed / Approved By: Date:
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RP/0/A/5000/01 DUKE POWER COMPANY CATAWBA NUCLEAR STATION CLASSIFICATION OF EMERGENCY 1.0 SYMPTOMS 1.1 Notification of Unusual Event 1.1.1 Events are in process or have occurred which indicate a potential degradation of the level of safety of the plant.
~
I 1.1.2 No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety occurs.
1.2 Alert -
1.2.1 Events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of-the plant.
1.2.2 A'ny releases are expected to be limited to small fractions
! of the EPA Protective Action Guide!ine exposure levels.
1.3 Site Area Emergency l
- 1. 3.'1 Events are in process or have occurred which involve t
- actual or likely major failures of plant functions needed for
] protection of the public.
l
- 1.3.2 Any releases are not expected to exceed EPA Protective j Action Guideline exposure levels except near the site ,
boundary. '
1.4 General Emergency i
- 1.4.1 Events are in process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity.
i 1.4.2 Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the inimediate site area.
2.0 IMMEDI ATE 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. '
t 1
i
RP/0/A/5000/01 Pege 2 of 2 2.2 Initiate the Emergency Response Procedure (RP) applicable to the Emergency Class as follows:
Notification of Unusual Event RP/0/A/5000/02 Alert RP/0/A/5000/03
, Site Area Emergency RP/0/A/5000/04 General Emergency RP/0/A/5000/05 3.0 SUBSEQUENT ACTIONS 3.1 To escalate, de-escalate or close out the Emergency, compare plant conditions to the initiating Conditions of Encicsure 4.2.
4.0 ENCLOSURES 4.1 Emergency Action Level (s) for Emergency Classes Event No. Page(s) 4.1.1 Primary Coolant Leak 1&2 4.1.2 Fuel Damage 3 l 4.1.3 Steam System Failure 4 4.1.4 High Radiation / Radiological Effluents 5 4.1.5 Loss of Shutdown Function 6 4.1.6 Loss of Power 7 4.1.7 Fires and Security Actions 8 i
4.1.8 Loss of Alarms and/or Communications 9 1
, 4.1.9 Natural Disasters and Other Hazards 10 4.1.10 Spent Fuel Damage 11 4
i 4.1.11 Other Abnormal Plant Conditions 12 L l'1
.1
) 4.1.12 Contaminated and injured Individual 14 4.2 Emergency Classification Guide Flowchart l
l
RP/0/A/5000/01 CL&SSITICATION OF EMERGENCY Enclosure 4.1 Emeraency Event List 4.1.1 Primary Coolant Leak j , 4.1.2 Fuel Damage 4.1.3 Steam System Failure 4.1.4 High Radiation / Radiological Effluents 4.1.5 Loss of Shutdown Function ,
4.1.6 Loss of Power 4.1.7 Fires and Security Actions 4.1.8 less of Alarms and/or Communications 4.1.9 Natural Disasters and Other Hazards 4.1.10 Spent Fuel Damage . ;
4.1.11 Other Abnormal Plant Conditions 4.1.12 Contaminated and Injured Individual :
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[recI seer 3 II .1 Page I or 14 CAIAWRA NUCLEAR SIA110N EMritctNCY ACTION LEVEL'S FOR 4 .
LyfMLJr 4.1.1 Primary Coolenf loak Cles, sentification or Alert Site Aree Emergency General [mergency untisesel 1: vent
- 1. IIC t enhage > Tech. 1. 30C teak > 50 spe wil f alliste or (CCS, Specs. ECO: capacity:
- 2. P-S Leak > 10 gpa las s to core melt:
e80C Lenk > 10 gem XYt!PTOMS 1dentIrIed prIsery fugit MOM,_)
er2R Iow Press Rx Trip leakage ePZR Low Press S/1 Signal eS/I signal ED( Rx trip a steen line break.
CD 500 gpd from any S/G elligh Containment Press Eyt4Pl0H1 ellIgh Contairument thsoIdIty elfg
' elli le Conta ltunent Steep Level CD 1 gee total P-S through erH -38, 39 ar 40 in alare eS/l ar 100 pumps not all S/G Rapidly decreasing:
rurmi ng ENC Tevg Several hundred spe P-S ,
oAny press botendary leakage 2.
leakage &lgg ePZR Press GS 1 gee sonidentitled er/R Level eS/1 riew Brullcates "No leakage eff0 AII0 FIow" loss or offsite power:
! C> 40 9pm controlled egg leakage at 2235 psig etMr-33 ar 34 In alsre.
C* I 9pm free 10C press estone Line Radiation eHigle Contelnment Steep 14oni tor in a la re on the ePIR low Press Alare Level Isolation valve at 2235 ePIR Low Prnas Rx Trly psig arrected S/G. Seell LOCA sted inittelty ePZR I.ow Level Alare 2.
Iallure or a PZR roRV or esteam Ilpe low Press stecces e rtel [CCS with 2.
! saroty valvo to cloon S/I signal yjgly orMF-33 ar 30s in als re rollure of MS System over increasiseg Contain- several leeters, feeds to rolicwisig a redssetton or i leC press: mont press ( E r break eSteam Line Radiation core melt and Failure or Va t ist acensestical les Corita ltunent ). Monitor in alarm on containmenti noseltar Isidication or time arrected S/O.
valva ra l l te se, l e etnam flow apd elllel ggJgeg$
elim tow favg ANI!
eP2R low press Rx trip IN alare on TKV buses ePZR low press S/l signal ENS Flow Indicators show "fle flow" ef ter > 2 hosers
= eIIC tempera ture i s ri s ing l 88fR ENS System Falls to remc t ion.
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CP/?/A/5000/OI Enclostare 0.1 Page 3 or 14 CAIAWRA flUCLEAR STAllO90 tMrRCrseCY ACT1088 LEVEL'S rOR [V_L8tl.J_.912: Tuol De_magg class platirication or Site Aree Emergency Ceneral Emergency Unusual Event Alert
- 1. Severe loss or fuel I. Degraded core ylgly 1. Loss or 2 or 3 rission
- 1. liigh coolant activity:
mechanical possible loss or prodtect barriers y11)g cclad ladding: fas lure: coolable geometry: a pot 9ntlet for loss of
- o. > 1 pCl/ gram Dose 3rd barrier:
rotelvalent I-131 og a. Very high ecolant eindgguqte_ Core Cooline activity semple
> 100_ ACl/ Cram 350 A Cl/mi to e. LOCA as identIrfed 1750 g.1/ml See EP/l/A/5000/25 in Event al.1.1 Site f Aree Emergency, equivalent 1-131.
gross activity. etteslisalcel Clad falluts Item #1 Luig
- h. > 0.1% Increase in b. Increase > 1.05 fuel by > 1750 g i/el I-131 fal tures (> 70psCl/mi rese l fallistes wittIn within 30 min.) e$eyerg_{Lse f .0ve rtemitf1All8In Incomplete Cont. Isol 30 min.
ps? gel 15 to 10% ralled fuel Indicated by 1300 to e51 to 251 total ruel 13,000 A cl/ml I-331 b. LOCA es identfried In 11 tn 51 ruel railures {>35Dgi/ml Site Area Emergency, rallieres 1-131) e[tjel_Hojt Item #1 FYM.fIEM4 .5% to 5% ralled fuel erMr-48 alarm Note: Determined by id:ficated by 1,180 to , M laboratory analysis, l l ,800ACl/mi 1-131 etHr-53A and/or 's Asto 80C poemp selrure leads to plote: Imtnemined by si
- 2. > 10 lt/hr Imboratory analysis. .
Cl-131 concentration resol railure: increases by 7 encl /ml over a 30 min, period EMPIOff1 g) eContairemeset press OR ellC pasap trly alarm > 14.8 pelg for at
~
l least 2 minutes ci-131 cosecentration NID 70p cl/mi to 350pcl/mi eRx trly on low flow 80nte: Dotormined by laboratory analysis Lull! ettw ronse > 15 ruel f a l liere s witteln 30 min. (> 70pCI/ml within 30 min.) 9 01 e5% total riso l rallures. (> 3 W Cl/ml I-139) scote: Deteralried by laboratory analysis Rev. 1
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4 RP/"/ A/50fMI/01 Enclos ro 4.1 Page 6 or 14 CATAWRA NUCLEAR STATION EMERCENCY ACTION LEVEL'S FOR . i [yfMT # 4.1.5: Loss or Shutdown rungglogg senti r an or Site Ares Emergency General Emergency thousua l Evesit Alert Complete loss or 1. Complete loss or func- 1. Transient restestring Rx trip i N/A 1. tions needed for plant with railure to screm. runction needed for Additional reflure or core plant gold ghytdgwD: h!LL Allest( _ cooling and ECCS sys4PloMS syMr_ ~
)
eND not f unc t iona l einabil'Ity to establish would feed to core molt: 1 NV pump injection gyMtJ ANO eRx remains critical _G!f1 ef ter A8pD all attempts to trip the einehlfity to malsiteln Rx are complete natieral or Forced cool- einability to estab11sh down. CA FIrv ANO
- 2. Failure or Llie Reactor 08 eNo ND s'nd Si riow Indicated.
i Protection System to initiate and complete einability to establish 0 13 a trip whicle brings the RC Flow, reactor subcrit tenI: eS/l Initiated, Reactor remains critical 2. IRANSIENI regtei ring 2. Transient initleted by loss j arter all attempts to operation or siteetdnwn or CF and CM Systems rollowed t trip have been completed, system with railure to by reilure or CA System for to ' rlp: extended perlod. Core molt-Ing la possible In several IMactor remains critical Meers witle teltlante rei f urn arter all attempts to or cosetalnennt Ilhely: trip have been completed. yMPTOMS Dx tr p on Lo-Lo S/G 1evel 899 wide range S/G level toward ofrecela low on all S/G No CA ow Indicated e CA passps not reenning and cannot be restored within 30 minutes M
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CP/0/A/50no/;l Encl;stero n. a I Page 8 of III CATAWBA NUCLEAR STAil001 EleERGENCY ACIl001 LEVEL'S FOR (YDILfJId T: rires en4_lecurity_Actlens CL*15 footirleetion or Site Area Emergency General Emerapency , unusual Event Alert rire (within protected 1. Fire potentially 1. F i re comp roel s trig the 1. Any mejor Internal or
- 1. reinctions or serety ex te rna l evest t s ( e . g. ,
cres ) lastirig more than errecting safety systems: systems: rires, earthq:eekes 10 minentes: siststantlaIly beyonel Observation of e Observation or a design levels) wtilch Obseevation or fire could cause messive detection sfera Fire that could mejor rire that arrect seroty systems. defeats redundant commets demoge to plant lastisig > In ministes, systems. seroty system or
- 2. Socierity threat 2. Deigoing Sectority rufic t ions.
compsomise: 2. Loss or physical control l
- 2. Imminent loss or or the recility:
og physical control or As reported by Security force the plant: Physical attack on the oAttempted entry recility has resulted j Physle.41 attack on its occupation of the .i DR time plant leic l6sd ing Control Room and Imminent occespeescy or auxlllery sleutdowrt oAttempted soliotage A s sent i t led by Control Room and panels, Secesri ty f orce. euxillery shistdown i panels, e e e 4 I
CP/0/A/50nG/21 Enclosure 4.I Page 9 or 14 CATAWilA IIUCLEAR STAil0lf E MERGE NCY AC T 1981 L EVEL' S roR [y1NT E 4.1 4: tqts of Alerag_ag![for Connautt ce_119D i i Clegg teottricetion or Site Area Emergency Gesteral Emergency Unuspel Event Alert
- 1. Most or all alarms 1. Most or all alarms N/A 1 Indications or alarms on process or ef fluent (anntenicetors) lost. (annesocia tors ) lost pasemeters not reinc t iona l for 15 ministes ED81 plant Is not in cold in Coestrol Room to an extent regeef ririg plant shutdown shestdowrt or other Og
. significent loss or assessment or comes il- Plant translant cation capability:
initiated while all jlWtJ06t$ alarms lost. eloss or process or e errlpent Radiation e moeiltorisig system 8 M . einst or all meteoro-logical Isis trismerita t ion ensito 0 81 oloss or all redlo/ teIcplentie commeenIce-tions capability orrslto.
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CP/2/A/50n0/01 Enclosure 4.1 Page 11 or 14 CATAWHA NUCLEAR STATION [MERCEDH;Y ACTION LEVEL'S FOR , [Yf U 4.1.19: 86etteral Disg1gers and Other lisZerds . Cles* Ientification or Site Area Emergency General Emergency unusual Evant Alert 1.e. Earthquake > onE: 1. When plant is not in 1. Any me.jo r I nte rna l o r 1.o. terthquake < ost rett in plant or detected: > 0.06g Horizotstal cold shutdown, external events (e.gsN - fires earthgesakes
- a. Earthquake > SSE: stentIstty beyond design
< 0.08g Mo ri zon ta l OLI levels) which could cause
> 0.15g isorizontal massive common demoge to OR > 0.0539 Vertical (IAD-4) OR
< 0.051g Vertical
> 0. log Vertical D teko level:' b. Lake level:
IIIges 597.4 ft. MSL Cigte > 580.9 ft. MSL Low < 559.g rt. Hst tow 559.se rt. Mst b. take Level: ,
- c. Any tornado on site c. Any tornado striking Illgh > 592.8s rt. MSL
- racility low < 559.4 ft. MSL
- d. Wistds > 73 mph c. Winds > 95 mph
- d. Winds opproaching 95 mph 2.o. Aircra f t crash nn- 2.a. Aircraf t crash on 2. Wisen plant l a asot cite 90 tenusual circrort activity recility In cold shutdown over site m. Alrctert crash caissing
- b. Missile Imr. net on damage or fire to Conteln-D. losin deralind racility meset Building. Control Room, nnsito. AsexIllary Riellding, fuel
- c. Explosion damage to racility arrecting Reillding or RN Intake Structeere
- e. Ienar site or onsite plant opesatf ors owplos loss
- d. Uncontrolled b. Damage from missile or Entry or toxic or explosion catsses
- d. Near site or onsite riammable gas into Issability to estabilsh:
toule or riammahle racility arrecting sore l j charging ptemp Injection gas release operation or pleret 2) CA Flow
- 3) MC or RN Flow o Iterhine rotating e. Iterbine rotating compossent composset L railsere roIItere cassaltig penette-causes rapid plant Lion or tierbleie c. Feitry or uncontrolled Lexic or FImanoble gases sisestdown casing.
into Control Room, Cable Sestadleeg Room, Caseto inment Stellding, Switchgeer Room, Auxiglery Shestdown Penels or Diesel Rooms, arrecting ssbre operation of plant. 9
CP/?/A/5000/0t Enclosure Is.I Page 12 or les CATAWBA IIUCLEAR SIAfl0ll TMf RCreeCY ACilO90 LEVIL'S IOR , [yllli X 4.1.11: Other Abnormel Plant _Cspditions Class IsotIricistion or Site Arite Emergency General Emergency unusual Event Alert 1 Ecc5 initiated: 1. Evacuation or Control 1. Evacasation of Control 1 Other plant conditions Room anticipated gr Room eDel cotstrol or owlet, f ree tdse teve r sace rce, that in the S/I signal vert rication required with control shistdown systems not by rediendant Indication or shutdows systems estehIlshed free joutgesent of the Shirt spel dlscharge into vessel. estabilshed from local local stations in Stepe rvi so r, the Opere-
- 2. Ahnormal conlant tempera- station. 15 e tniste s. tions Duty Engineer, the tnre and/or pressiero gr Superintendent of Opere-abnormal Reactor resel 2. Other plant conditions 2. Other plant conditions tions or the Plant tempe ra tiero: exist that in tise exist that in the Monsger sehe release of Jesdgeesosat of the Judgement or the Shift large amounts or redle-Figure 2.1-1 icch Specs shi r t Supe rvi so r, the Supe rv i so r, the Opere- activity in a short time c.weeeded spel core Spen. Operations Duty Llons Desty rngineer, period possible (e.g.,
cooIIng Mor:Itor less Engineer, the Super- tlee Stel erintendent or any co re me l t s i tten t ion), inan acceptable (flotow Intendent or Opera- pperations or the Plant curve) tions, or the Plant Manager wartent activa-Massager warrant pre- tion or ISC & CMC
- 3. loss or containment cesstionary activation and monitoring teams integrity requirisig or TSC & OSC. seed a precaistionary thistdown by Iccis. spec: pub 1Ic notirication.
gAny asetoontic conteln-actet isolation valve rasend to be open stod Isusperahin newt etnisolable. OR ellotti mir Inck doors nn a lock Irwsperable, or penntsations fait scah test per lects Spec wisen consta inment integrity la regos I red. at . toss nr enslineered sarety feettero or fire protection - system reanction requiring shutdown by lectinical Spectr8 cations: eEST actesation system rotwwl Inoperable. OR et Iro Protection Water . System rossnd lisope rable per Tech Spec.
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6 d Form 34731 (10-81) (Formerly SPD 10021)- DUKE POWER COMPANY (1) ID No: RP/0/A/5000/02 PROCEDURE PREPARATION Change (s) I to PROCESS RECORD 'L Incorporated (2) STATION: CATAWBA (3) PROCEDURE TITLE: NOTIFICATION OF UNUSUAL EVENT (4) PREPARED BY: M. E. Bolch DATE: 2/2/84 (5) REVIEWED BY: s A DATE: 3 b~NY Cross-Disciplinary Review By: N/R: b ('6) TEMPORARY APPROVAL (IF NECESSARY): By:- (SRO) Date: By: Date: (7) APPROVED BY: . v. ./ Date: /_. / d'/ (8) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: l l l 1 l I l
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RP/0/A/5000/02 DUKE POWER COMPANY CATAWBA NUCLEAR STATION
. NOTIFICATION OF UNUSUAL EVENT 1.0 SYMPTOMS 1.1 This condition exists when events are in process or have occurred which indicate a potential degradation of the level of safety of the olant.
2.0 IMMEDIATE ACTIONS 2.1 Make initial notifications to individuals and organizations. 2.1.1 Complete Enclosure 4.2 and Part I of Warning Message Form. (See' example Enclosure 4.3.) Record receivers name and time on Enclosure 4.2 and on Page 4 of Warning Message. NOTE: Emergency Coordinator shall initial forms when message is approved for transmission. NOTE: Warning Message Forms are kept in a notebook in the Control Room and TSC, ensure that all used forms are returned to the back of the notebook. 2.1.2 Transmit emergency information as indicated on Enclosure 4.1. NOTE: The State and County notification must be made within 15 minutes of declaration of the emergency. 3.0 SUBSEQUENT ACTIONS 3.1 Give follow-up messages to agencies listed in 4.1.3 of Enclosure 4.1 use the following schedule: 3.1.1 If the Unusual Event Situation lasts longer than one hour, then repeat each hour until closed out. 0E If there is any significant change to the situation. 9.C As agreed upon with the individual agencies. 3.1.2 Use Parts I r, ll of Warning Message Form as applicable. Mark all spaces "N/A' when information if "Not Applicable" and mcrk "Later" when information is not currently available. 3.2 Augment shift resources to assess and respond to the emergency situation as needed.
f M 7A F W E R G7t B Paga 2 cf 2 3.3 Assess the emergency condition, then remain in a Notification of Unusual Event, escalate to a more severe class or terminate the emergency. 3.4 The Licensing and Projects Engineer or delegate shall close out the emergency with verbal summary to county and state authorities, notified in 4.1.3 of Enclosure 4.1, followed by written summary within 24 hours. 4.0 ENCLOSURES I 4.1 Telephone Notification List ' 4.2 Emergency Message. Format 4.3 Example Warning Message: Nuclear Facility to State / Local Government .I 't
* *'***-*Nmmee- we 6 . . . , , , .%p, ,
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l l l l RP/0/A/5000/02 ( Enclosure 4.1 Page 1 of 2 TELEPHONE NOTIFICATION LIST 4.1.1 CNS Emergency Personnel Initial
- 1. Operations Duty Engineer - Plant Page P & T Pager - 637 or 277 A: See Current Operations Work List for Home Phone Number.
- 2. Station Manager - J. W. Hampton Office 2300 Home 803-366-5300 1st Aiter.iate - C. W. Graves Office 2304 Home 6 2nd Alternate - J. W. Cox Office 2303 Home @
3rd Alternate - G. T. Smith Office 2302 Home M 4th Alternate - A. R. Franklin Office 2305 Home M
- 3. License & Projects Engineer - C. L. Hartzell l Office 2785 Home 1st Alternate - M. E. Bolch ;
Office 2782 ! Home 6 2nd Alternate - F. N. Mack Office 2781 l Home M 4.1.2 Nuclear Production Duty Engineer 373-5491 l P & T Page 373-5214 #625 ,
** USE ENCLOSURE 4.2 ** l 1
l l .._ _ _ _
scoseceo o e. o
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. Page 2 cf 2 4.1.3 Stat, & County Emtroency Cantsrs (Within 15 minutzs)
- 1. N.C. State Warning Point, Raleigh - 919/733-3861
*** USE ENCLOSURE 4.3 ***
- 2. S.C. State Warning Point, Columbia P: 803-758-5548 7:30 a.m. - 5:00 p.m. Weekdays A: 803-758-5531 Afterhours, Week-ends & Holidays
*** USE ENCLOSURE 4.3 ***
- 3. Mecklenburg County Warning Point P: Selective Signal - 116 A: 704-374-3333 Back-up: Emergency Radio, Code: E
*** USE ENCLOSURE 4.3 ***
- 4. York County Warning Point P: Selective Signal - 513 A: 803-327-2021 Back-up: Emergency Radio, Code: 4_1
*** USE ENCLOSURE 4.3 ***
- 5. Gaston County Warning Point P: Selective Signal - 112 A: 704-866-3300 Back-up: Emergency Radio, Code 26 -
*** USE ENCLOSURE 4.3 ***
4.1.4 NRC Operations Center, Bethesda Md. P: ENS phone (red phone) A: 202-951-0550 4 I I
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' RP/0/A/5000/02 ENCLOSURE 4.2 PAGE 1 OF 1 DUKE POWER COMPANY CATAWBA NUCLEAR STATION
. EMERGENCY MESSAGE FORMAT
- 1. This is at Catawba Nuclear Station.
(Name and Title)
- 2. This is is not a drill. An Unusual Event Alert Site Area Emergency General Emergency was declared by the Emergency Coordinator at on Unit # .
(Time)
- 3. Initiating condition: (Give as close to the emergency plan descripti.on as possible together with station parameters used to determine emergency status).
- 4. Corrective measures being taken:
- 5. There have have not been any injuries to plant perscnnel.
- 6. Release of radioactivity: is taking place is not taking place
- 7. NRC Yes No; State Yes No;
- Counties Yes No; have been notified.
- 8. The Crisis Management Team should should not be activated.
Corporate Communications t, Company Management should be notified.
- 9. I can be reached at for follow-up information.
(Telephone Number)
- 10. Additional Comments:
Name of Person Contacted Date Time v-aw-- , s. , , ,._--,_i, , , , - m ,, , w e--,- --- .-,- .,--
Enclosure 4.3 g Paga 1 of 4 WARNING MESSAGE: NUCLEAR FACILITY TO STATE / LOCAL GOVERNMENT Instructions: A. For Sender:
- 1. Complete Part i for the Initial Warning Message.
- 2. Complete Parts I L ll for followup messages.
B. For Receiver:
- 1. Record the date, time and your name in the area below.
- 2. Authenticate this message by verifying the code word or by calling back to the facility. (See Part 1.5)
Time: Date: Message Received By: p s ;. ,. :.; e,q ;>; w .;.X.PART l 5 3:y._: :. 7 7 ;. e :.9 g.:.;.ty';; N.'jf.g f_
- 1. This is: Catawba Nuclear Station
- 2. My name is:
- 3. This message (number ):
(a) Reports a real emergency. (b) is an exercise message.
- 4. My telephone number / extension is:
- 5. Message authentication: USE MESSAGE AUTHENTICATION LIST (Verify code word or call back to facility)
- 6. The class of the emergency is: (a) Notification of Unusual Event X (b) Alert (c) Site Emergency (d) General Emergency
- 7. This classification of emergency was declared at: (a.m./p.m. ) on (date).
- 8. The initiating event causing the emergency' classification is:
- 9. The emergency condition: (a) Does not involve the release of radioactive materials from the plant.
(b) Involves the potential for a release, but no release is occurring. _ (c) Involves a release of radioactive material.
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- 10. Wa recommend tho following prot:ctivo acti::n:
(a) No protective action is recommended at this time. (b) People living in zones remain indoors with the doors and windows closed. (c) People in zones evacuate their homes and businesses. (d) Pregnant women and children in zones remain indoors with the doors and windows closed. (e) Pregnant women and children in zones evacuate to the nearest shelter / reception center. (f) Other recommendations:
- 11. There will be:
(a) A followup message Approved for Release (b) No further communications
- 12. I repeat, this message:
(a) Reports an actual emergency Emerg. Coord. Time (b) is an exercise message
- 13. RELAY THIS INFORMATION TO THE PERSONS INDICATED ON YOUR ALERT PROCEDURE FOR AN INCIDENT AT A NUCLEAR FACILITY.
***END OF INITIAL WARNING MESSAGE *** MWi E V-5A - M PART ll
- 1. The type of actual or projected release is:
! (a) Airborne (b) Waterborne (c) Surface spill (d) Other j
- 2. The source ancJ description of the release is:
l
- 3. (a) Release began /will begin at a.m./p.m.; time since ,
reactor trip is hours. ) (b) The estimated duration of the release is hours. l
BIAX6Uosu rO 4).6) Paga 3 of 4
- 4. D:se pr:Jectinn bass data:
Radiological release: curies, or curies /sec. Wind peed: mph Wind direction: From
- Stability class: ( A, B, C, D, E, F, or G)
Release height: Ft. Dose conversion factor: R/hr/Ci/m' (whole body) R/hr/Ci/m' (Child Thyroid) Precipitation: 4 Temperature at the site: *r i
- 5. Dose projections:
i
- Dose Commitment
- Whole Body (Child Thyroid) i Distance Rem / hour Rem / hour of inhalation Site boundarv 2 miles 5 miles 10 miles I
- Projected Integrated Dose in Rem
- Distance Whole Body Child Thyroid Site boundary 2 miles 5 miles 10 miles
- 6. Field measurement of dose rate or contamination (if available):
- 7. Emergency actions underway at the facility include:
- 8. Onsite support needed from offsite organizations:
- 9. Plant status:
(a) Reactor is: not tripped / tripped t (b) Plant is at: % power / hot shutdown / cold shutdown / cooling down (c) Prognosis is: stable / imp rovi n g/deg ra d i n g/u n know n l l _ _ . . _ _ . . _ _ . - . . . . . . - , _ . - . . . . _ . . . - ...~,.......,..s.. . - - , , , , . , . . . , . . .
Enc 0csuro 4.3 Pass 4 cf 4
- 10. I rcp:st, this mess ga: )
i (a) Reports an actual emergency. (b) is an exercise message. Approved for Release 11.~ Do you have any questions?
***END OF FOLLOW-UP MESSAGE *** -
NOTE: Record the name, title, date, time, 'and warning point notified. (Senders) Record the name, title, date, time, and persons notified per alert procedura. (Receivers)- 1. (name) (title) (date) (time) (warning point) 2. (name) (title) (date) (time) (warning point) 3. (name) (title) (date) (time) (warning point) 4. (name) (title) (date) (time) (warning point)
- 5. I (name) (title) !
(date) (time) (warning point) 6. (name) (title) (date) (time) (warning point) 7. (name) (title) l l (date) (time) (warning point) l I
. _ . . - . . . . . ~ , - - - -
Form 34731 (10 81) (Formerly SPD 10021) ~ DUKE POWER COMPANY (1) ID No: up/n/A/ son 0/03 PROCEDURE PREPARATION Change (s) I to PROCESS RECORD ~2. _Inctrporated (2) STATION: CATAWBA (3) PROCEDURE TITLE: ALERT (4) PREPARED BY: !!. E. Bolch DATE: 2-2-84 (5) REVIEWED BY: \ 5 DATE: 3 -I* 'I N Cross-Disciplinary Review By: N/R: b (6) TDfPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: By: Date: (7) APPROVED BY: W- Date: A!/ [5f (8) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: I l l
( RP/0/A/5000/03 DUKE POWER COMPANY CATAWBA NUCLEAR STATION ALERT 1.0 SYMPTOMS 1.1 Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. 2.0 IMMEDI ATE ACTIONS 2.1 Make initial notifications to individuals and organizations. 2.1.1 Complete Enclosure 4.2 and Part I of Warning Message Form (see example Enclosure 4.3). Record receiver's name and time on Enclosure 4.2 and on Page 4 of Warning Message. NOTE: Emergency Coordinator shall iaitial forms when message is approved for trans .iission. i NOTE: Warning Message forms are kept in a notebook in the Control Room and TSC, ensure that all used forms are returned to the back of the notebook. 2.1.2 Transmit emergency information as indicated on Enclosure 4.1. 2.1.3 Advise station personnel to activate TSC and OSC. NOTE: The State and County notification must be made within 15 minutes of declaration of the emergency. 3.0 SUBSEOUENT ACTIONS 3.1 Accident Assessment, the Emergency Coordinator shall: 3.1.1 Dispatch on site monitoring teams with associated communications equipment per HP/0/B/1009/09. i 3.2 Give Follow-up Messages to offsite agencies listed on 4.1.3 of Enclosure 4.1, use the following schedule: 3.2.1 Every half hour until the emergency is closed out. 0E If there is any significant change to the situation. 9E As agreed upon with the individual agencies. 3.2.2 Use Parts I L 11 of Warning Message Form as applicable. Mark all spaces "N/A" when information is "Not Applicable" , and mark "Later" when information is not currently available.
~ ~ ~ ~ ' --
K t'/ U/ A/ DUUU/ UJ Pega 2 cf 2 3.3 Recommend Protective Action Offsite ; NOTE
, Protective Action Recommendations are obtained from: OAC Program " Nuclear-23" or RP/0/A/5000/11 if the OAC is not operational.
3.4 If the amergency situation is rapidly degrading then conduct a Site Assembly per RP/0/A/5000/10. 3.5 Augment shift resources to assess and respond to the emergency
,ituation as needed.
3.6 Assess the emergency condition, then remain in an Alert, escalate to a more severe class, reduce the Emergency Class or terminate the emergency. 3.7 The Licensing' and Projects Engineer or delegate shall close out the emergency with verbal summary to county and stits authorities, notified in 4.1.3 of Enclosure 4.1, followed by written summary within 8 hours. 4.0 ENCLOSURES
- 4.1 Telephone Notification List i
4.2 Emergency Message Format 4.3 Example Warning Message: Nuclear Facility to State / Local Government I I
~........s. n. , , m . . . .
RP/0/A/5000/03 Enclosure 4.1 Page 1 of 2 TELEPHONE NOTIFICATION LIST l 4.1.1 CNS Emergency Personnel Initial i i
- 1. Operations Duty Engineer - Plant Fage ;
P & T Pager - 637 or 277 l A: See Current Operations Work List for Home Phone Number. !
- 2. Station Manager - J. W. Hampton Office Home @2300 l
1st Alternate - C. W. Graves Office 2304 ' Home 2nd Alternate - J. W. Cox , Office 2303 " Home M 3rd Alternate - G. T. Smith Office 2302 Home M 4th Alternate - A. R. Franklin Office 2305 Home g i
- 3. License L Projects Engineer - C. L. Hartzell Office 2785 Home M 1st Alternate - M. E. Bolch Office 2782 i Home M 2nd Alternate - F. N. Mack Office 2781 Home 6 l 4.1.2 Nuclear Production Duty Engineer 373-5491 l P L T Page 373-5214 #625
- ** USE ENCLOSURE 4.2 **
_. -- - . .= _ _ . _ .. __- _ . . - . . . _ . _. .- _ - Pag 2 2 cf 2 4.1.3 Stat, s Ceunty Emironney Centtrs (Within 15 minut:s)
- 1. N.C. State Warning Point, Raleigh - 919/733-3861
*** USE ENCLOSURE 4.3 ***
- 2. S.C. State Warning Point, Columbia P: 803-758-5548 7:30 a.m. - 5:00 p.m. Weekdays i A: 803-758-5531 Afterhours, Week-ends & Holidays
*** USE ENCLOSURE 4.3 ***
- 3. Mecklenburg County Warning Point P: Selective Signal - 116 A: 704-374-3333 Back-up: Emergency Radio, Code: 21 -
*** USE ENCLOSURE 4.3 ***
I 4. York County Warning Point P: Selective Signal - 513 ~ A: 803-327-2021 Back-up: Emergency Radio, Code: 41
*** USE ENCLOSURE 4.3 ***
l
- 5. Gaston County Warning Point
} P: Selective Signal - 112 A: 704-866-3300 Back-up: Emergency Radio, Code 26 _
*** USE ENCLOSURE 4.3 ***
I 4.1.4 NRC Operations Center, Bethesda Md. P: ENS phone (red phone) A: 202-951-0550 i i I
RP/0/A/5000/03 . ENCLOSURE 4.2 PAGE 1 OF 1 DUKE POWER COMPANY CATAWBA NUCLEAR STATION EMERGENCY MESSAGE FORMAT
- 1. This is at Catawba Nuclear Station.
(Name and Title) , 2. This is is not a drill. An Unusual Event Alert Site Area Emergency General Emergency i was declared by the Emergency Coordinator at on Unit # . (Time)
- 3. Initiating condition: (Give as close to the emergency plan description as possible together with station parameters used to determine emergency status).
- 4. Corrective measures being taken:
- 5. There have have not been any injuries to plant personnel.
- 6. Release of radioactivity: is taking place is not taking place
- 7. NRC Yes No; State Yes No; Counties __ Yes No; have been notified.
- 8. The Crisis Management Team should should not be activated.
Corporate Communications & Company Management should be notified.
- 9. I can be reached at for follow-up information.
(Telephone Number)
- 10. Additional Comments:
Name of Person Contacted Date Time
encissure 4. 3 NE Page 1 cf 4 WARNING MESSAGE: NUCLEAR FACILITY TO STATE / LOCAL GOVERNMENT Instructions: A. For Sender:
- 1. Complete Part I for the Initial Warning Message.
- 2. Complete Parts I L 11 for followup messages.
B. For Receiver:
- 1. Record the date, time and your name in the area below.
- 2. Authenticate this message by verifying the code word or by calling back to the facility. (See Part 1.5)
Tims: Date: Message Received By: PART I 4W N'N M '+ 'e - CW SUT-fxMA9IM
- 1. This is: Catawba Nuclear Station
- 2. My name is:
- 3. This message (number ):
(a) Reports a real emergency. (b) is an exercise message.
- 4. My telephone number / extension is:
- 5. Message authentication: USE MESSAGE AUTHENTICATION LIST (Verify code word or call back to facility)
- 6. The class of the emergency is: X (a) Notification of Unusual Event (b) Alert (c) Site Emergency (d) General Emergency
- 7. This classification of emergency was declared at: (a.m./p.m. ) on (date).
- 8. The initiating event causing the emergency classification is:
- 9. The emergency condition: (a) Does not involve the release of radioactive materials from the plant.
(b) Involves the potential for a release, but no release is occurring. (c) Involves a release of radioactive material.
..~_ - a wesarnaw.. n. , . .;;u.. .. . .w . - m . -. . ~ . ~-.
Pcge 2 ef 4
- 10. Wa recommend tha fsilowing pr;tetiva ccticn:
(a) No protective action is recommended at this time. (b) People living in zones
, remain indoors with the doors and windows closed.
(c) People in zones evacuate their homes and businesses. (d) Pregnant women and children in zones remain indoors with the doors and windows closed.
-(e) Pregnant w' omen and children in zones evacuate t'o the nearest shelter / reception center.
(f) Other recommendations:
- 11. There will be:
(a) A followup message (b) No further communications APPROVED FOR RELEASE
- 12. I repeat, this message:
(a) Reports an actual emergency Emerg. Coord. Time ) (b) is an exercise message
- 13. RELAY THIS INFORMATION TO THE PERSONS INDICATED ON YOUR ALERT PROCEDURE FOR AN INCIDENT AT A NUCLEAR FACILITY.
WM $ItMD.lNjNM ***END OF INITIAL WARNING MESSAGE *** PART 11
- 1. The type of actual or projected release is:
(a) Airborne (b) Waterborne (c) Surface spill (d) Other
- 2. The source and description of the release is:
l
- 3. (a) Release began /will begin at a.m./p.m.; time since ;
reactor trip is hours. (b) The estimated duration of the release is hours. but?iT2AO --^ ^ "tLMi.*f;.7 *TT*r" IT * . * "J. ;7! : v.c . h'-!Y:?ter w - -- .sm. ~- _
Paga 3 cf 4
- 4. Doso projecti:n base data:
Radiological release: curies, or curies /sec. Windspeed: mph
~ Wind direction: From Stability class: ( A, B,C,D,E, F, or G)
Release height: Ft. Dose conversion factor: R/hr/Ci/m' (whole body) R/hr/Ci/m* (Child Thyroid) Precipitation: Temperatere at the site: 'F
- 5. Dose projections: l l
- Dose Commitment
- l 1
Whole Body (Child Thyroid) Distance Rem / hour Rem / hour of inhalation Site boundary 2 miles l 5 miles 10 miles
- Projected Integrated Dose in Rem
- Distance Whole Body Child Thyroid Site boundary 2 miles 5 miles 10 miles 1
- 6. Field measurement of dose rate or contamination (if available):
- 7. Emergency actions underway at the facility include:
- 8. Onsite support needed from offsite organizations:
- 9. Plant status:
l (a) Reactor is: not tripped / tripped (b) Plant is at: % power / hot shutdown / cold shutdown / cooling down (t) . Prognosis is: stable / imp rovi n g/deg radin g/ u n kn ow n l m: - ?~" rMu e:: 33gm; 3_ --; y ^ q.
Enclssuro 4.3 l Page 4 cf 4
- 10. I rep:at, this messtga:
(a) Reports an actual emergency. (b) is an exercise message.
- 11. Do you have any questions?
kmerg. coord. Ti=e ')
***END OF FOLLOW-U.' MESSAGE ***
NOTE: Record the name, title, date, time, and warning point notified. (Senders) Record the name, title, .date, time, and persons notified per alert procedure. (Receivers) 1. (name) (title) (date) (time) (warning point) 2. (name) (title) (date) (time) (warning point) 3. (name) (title) (date) (time) (warning point) 4. (name) (title) (date) (time) (warning point) 5. (name) (title) . (date) (time) (warning point) 6. (name) (title) (date) (time) (warning point) 7. (name) (title) (date) (time) (warning point) l e ^ M .IM4.S hl $ M'% 4' E b Mg. 6% e 99.
W Form 34731 (10-81) (Formerly SPD.10021)' DUKE POWER COMPANY (1) ID No: Rp/n/A/5n00/04 PROCEDURE PREPARATION Change (s) I to PROCESS RECORD 7 Incorporated (2) STATION: CATAWBA (3) PROCEDURE TITLE: SITE ARFA EMFRCENCY (4) PREPARED BY: M. E. Bolet DATE: 2-2-84 (5) REVIEWED BY: A t a DATE: S-b 'b Cross-Disciplinary Review By: N/R: %di-(6) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: By: . Date: (7) APPROVED BY: -LA Date: 2 !/ !# (8) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: I t
RP/0/A/5000/04 DUKE POWER COMPANY CATAWBA NUCLEAR STATION SITE AREA EMERGENCY I 1.0 SYMPTOMS 1.1 Events are in process or have occurred which involve an actual or likely major failures of plant functions needed for protection of the public. t 2.0 IMMEDI ATE ACTIONS 2.1 Make initial notifications to individuals and organizations. 2.1.1 Complete Enclosure 4.2 and Part I of Warning Message Form i (see Enclosure 4.3). Record receiver's name and , time on Enclosure 4.2 a,d on Page 4 of Warning Message. NOTE: Emergent / Coordinator shall initial forms when message is approved for transmission. NOTE: Warning Message forms are kept in a notebook in the . Control Room and TSC, ensure that all used forms are returned to the back of the notebook. j 2.1.2 Notifications shall be as the order of Enclosure 4.1 i 4 indicates. - 2.1.3 Advise station personnel to activate TSC and OSC. NOTE: The State and County notification must be made within 15 minutes of declaration of the emergency. 2.2 Protective Action Offsite 2.2.1 Recommend to Offsite Agencies that the Alerting Sirens be sounded and that the EBS be activated to inform the public of a potential for later protective actions. , 2.3 Protective Action Onsite
- 2.3.1 Conduct a Site Assembly per RP/0/A/5000/10.
2.3.2 Consider evacuation of non-essential personnel to the Evacuation Relocation Centers per RP/0/A/5000/10. 3.0 SUBSEQUENT ACTIONS l j 3.1 Accident Assessment, the Emergency Coordinator shall: 3.1.1 Dispatch field monitoring teams with associated !
- communications equipment per HP/0/B/1009/04.
Pags 2 cf 3 3.2 ~ Givo fallsw-up m:ssaga to offsits eganciss listsd on 4.1.3 of Enclosure 4.1, use the following schedule: 3.2.1 Every half hour until the emergency is closed out. E if there is any significant change to the situation. E As agreed upon with the individual agencies. 3.2.2 Use Parts..I & 11 of Warning Message Form as applicable. Mark all spaces "N/A" when information is "Not Applicable" and mark "Later" when information is not currently available.
'3.3 Follow-up Recommend Protective Action Offsite NOTE Prot,ctive Action Recommendations are obtained from: OAC Prog. ram " Nuclear-23" or RP/0/A/5000/11, if the OAC is not available.
3.3.1 The Emergency Coordinator shali make Protective Action Recommendations to the affected county warning points and to both SC and NC state warning points (Emergenc/ Operations Center if established) or the designated state department as per the state's Radiological Emergency Response Plan. See Enc.losure 4.4 for aid in protective action decision making. NOTE This authority shal! not be delegated to other elements of the emergency organization. 3.3.2 If actual release of radioactive material will result in a projected dose to the population of: Whole Body Thyroid Recommendation
<1 Rem <5 Rem No Protective Action is Required.
I to <5 Rem 5 to <25 Rem Recommend seeking shelter and wait for further instruction. Consider evacuation particularly for children
& pregnant women. Control access to affected areas.
> 5 Rem > 25 Rem Recommend mandatory evacuation of population in the affected areas.
Control access to affected areas.
Paga 3 cf 3 NOTE Monitor environmental radiation levels to verify and adjust recommendations as necessary. 3.4 Augment shift resources to assess and respond to the emergency situation as needed. 3.5 Assess the emergency condition, then remain in a Site Area Emergency, escalate to a more severe class, reduce the emergency class, or terminate the emergency. 3.6 The Recovery Manager at the Crisis Management Center shall close out or recommend reduction of the emergency class, by briefing of offsite authorities at the Crisis Management Center of by phone if necessary, followed by written summary within 8 hours. 4.0 ENCLOSURES Telephone Notification List 4.1 4.2 Emergency Message Format 4.3 Example Warnins. Message: Nuclear Facility to State / Local Government 4.4 Protective Action Recommendation Flow Chart 4.5 10 Mile Emergency Planning Zone (EPZ) Map
i RP/0/A/5000/04 Enclosure 4.1 Page 1 of 2 TELEPHONE NOTIFICATION LIST 4.1.1 CNS Emergency Personnel Initial ) i
- 1. Operations Duty Engineer - Plant Page l P & T Pager - 637 or 277 A: See Current Operations Work List for Home Phone Number.
- 2. Station Manager - J. W. Hampton e
1st Alterrate - C. W. Graves Office 2304 Home 2nd Alternate - J. W. Cox Office 2303 Home M 3rd Alternate - G. T. Smith
. Office 2302 l
Home 6 4th Alternate - A. R. Franklin Office 2305 Home 6 .
- 3. License L Projects Engineer - C. L. Hartzell Office 2785 l Home M 1st Alternate - M. E. Bolch Office 2782 Home M 2nd Alternate - F. N. Mack l Office 2781 i
Home @ 4.1.2 Nuclear Production Duty Engineer 373-5491 P & T Page 373-5214 e625
** USE ENCLOSURE 4.2 M
- -- - ~~ ~ ~ ' ~
Pag 3 2 cf 2 4.1.3 Stat, & Ceunty Em2rgency Canters (Within 15 minut s)
- 1. N.C. State Warning Point, Raleigh - 919/733-3861
*** USE ENCLOSURE 4.3 ***
- 2. S.C. State Warning Point, Columbia P: 803-758-5548 7:30 a.m. - 5:00 p.m. Weekdays A: 803-758-5531 Afterhours, Week-ends & Holidays 1
*** USE ENCLOSURE 4.3 *** l
- 3. Mecklenburg County Warning Point 1 P: Selective Signal - 116 l A: 704-374-3333 I Back-up: Emergency Radio, Code: 21
*** USE ENCLOSURE 4.3 ***
- 4. York County Warning Point P: Selective Signal - 513 A: 803-327-2021 Back-up: Emergency Radio, Code: 41 .'
*** USE ENCLOSURE 4.3 ***
- 5. Gaston County Warning Point
; P: Selective Signal - 112
{ A: 704-866-3300 Back-up: Emergency Radio, Code 26
*** USE ENCLOSURE 4.3 ***
4.1.4 NRC Operations Center, Bethesda Md. P: ENS phone (red phone) A: 202-951-0550 i i l l i l i i j _ . . . . . . . . . . . . _ _ - ... .. . . .. ._
ENCLOSURET 2 PAGE 1 OF 1 DUKE POWER COMPANY CATAWBA NUCLEAR STATION
. EMERGENCY MESSAGE FORMAT
- 1. This is at Catawba Nuclear Station.
(Name and Title) !
- 2. This is is not a drill. An Unusual Event i Alert '
Site Area Emergency General Emergency was declared by the Emergency Coordinator at on Unit # . (Time)
- 3. Initiating condition: (Give as close to the emergency plan description as possible together with station parameters used to determine emergency status).
- 4. Corrective measures being taken:
- 5. There have have not been any injuries to plant personnel.
- 6. Release of radioactivity: is taking place is not taking place
- 7. NRC Yes No; State Yes No; Counties Yes No; have been notified.
- 8. The Crisis Management Team should should not be activated.
] Corporate Communications & Company Management should be notified.
- 9. I can be reached at for follow-up information.
(Telephone Number)
- 10. Additional Comments:
Name of Person Contacted Date Time 4
> - = + *, ,e...
J
-, , - - ~ .wr, -. ,,-. . -a. - -,,--,,-e.,--.,------v ,-,n- -, - - , - - - , , - , , - - , - , , , , . . , - - , , , , , - - , - , -e,-
y [RP/0/ A/5000/04 Enclosure 4.3 9 D(#Pl_E Paga 1 of 4 WARNING MESSAGE: NUCLEAR FACILITY TO STATE / LOCAL. GOVERNMENT Instructions: ~ A For Sender:
- 1. Complete Part I for the initial Warning Message.
- 2. Complete Parts l L ll for followup messages. l l
B. For Receiver:
)
- 1. Record the date, time and your name in 'the area below. !
- 2. Authenticate this message by, verifying the code word or by calling back to the facility. (See Part 1.5)
Time: Date:- -' Message Received By:
, PARTI i
- ~
- 1. This is: Catawoa Nuclear Station
- 2. My name is:
- 3. This message (number ):
(a) Reports a real emergency. (b) is an exercise message.
- 4. My telephone number / extension is:
- 5. Message authentication: USE FESSAGE AltrHENTICATION LIST (Verify code word or call back to facility)
- 6. The class of the emergency is: (a) Notification of Unusual Event (b) Ale rt'-
X (c) Site Emergency (d) General Emergency
- 7. This classification of emergency was declared at: (a.m./p.m. ) on (dsto).
- 8. The initiating event causing the emergency classification is:
- 9. The emergency condition: (a) Does not involve the release of radioactive materials from the plant.
(b) Involves the potential for a release, but no release is, occurring. (c) Involves a release of radioactive ! material. s
. .. .. , . . . . . ...i..... .-.....-. . --- .a - .
RP/0/A/5000/04 Enclssura 4.3 Paga 2 of 4
- 10. We recommend the following protective action:
(a) No protective action is recommended at this time.
. (b) People living in zones remain indoors with the doors and windows closed.
(c) People in zones evacuate their homes and businesses. (d) Pregnant women and children in zones remain indoors with the doors and windows closed. (e) Pregnant ' women and children in zones , evacuate to the nearest shelter / reception center. 1 (f) Other recommendations:
- 11. There will be:
(a) A followup message (b) No further communications
- 12. I repeat, this message: Emerg. coord. Time (a) Reports an actual emergency (b) 8s an exercise message
- 13. RELAY THIS INFORMATION TO THE PERSONS INDICATED ON YOUR ALERT PROCEDURE FOR AN INCIDENT AT A NUCLEAR FACILITY.
***END OF INITIAL WARNING MESSAGE ***
.. W W "ni V iv 4::n,b r.;;Y.cr '::' / PART II .. 5,:e~r Wts+tby-N*s!fb y ? %
- 1. The type of actual or projected release is: -
l (a) Airborne I (b) Waterborne (c) Surface spill ; I (d) Other
- 2. The source and description of the release is:
( l 3. (a) Release began /will begin at a.m./p.m.; time since i reactor trip is hours. i (b) The estimated duration of the release is hours.
. . . _ . , . . ... . . . . - . . . . . . . . . . . . . . . . . . . .. .. i
RP/0/A/5000/04 Enclosure 4.3 , Pcge 3 cf 4
- 4. Dose projection base data:
. Radiological r.elease: curies, or curies /sec.
. Windspeed: mph i
Wind direction: From
- Stability clase: ( A, B,C, D,E, F, or G)
Release height: Ft. Dose conversion factor: _ R/hr/Ci/m' (whole body) R/hr/Ci/m' (Child Thyroid)
- Precipitation
- Temperature at the site: 'F
- 5. Dose projections:
- Dose Commitment
- I -
Whole Body (Child Thyroid) Distance Rem / hour Rem / hour of inhalation Site boundary 2 miles 5 miles 10 mdes
- Projected integrated Dose in Rem
- Distance Whole Body Child Thyroid Site boundary 2 miles 5 miles 10 miles
- 6. Field measurement of dose rate or contamination (if available):
\ i
- 7. Emergency actions underway at the facility include:
- 8. Onsite support needed from offsite organizations:
- 9. Plant status:
(a) Reactor is: not tripped / tripped (b) Plant is at: % power / hot shutdown / cold shutdown / cooling down (c) Prognosis is: s table / imp rovi n g/deg radi n g/u n k nown l l . . . . . . .
RP/0/A/5000/04 Enclosura 4.3 Paga 4 cf 4
- 10. I repeat, this message:
(a) Reports an actual emergency. Approved for Release
, (b) is an exercise message.
Emerg. Coord. Time
- 11. Do you have any questions?
c a. ,.. m y: g gi a; . ***END OF FOLLOW-U P MESS AGE *** J%**%d#f 4-* *% c' NOTE: Record the name, title, date, time, and warning point notified. (Senders) Record the name, title, date, time, and persons notified per alert procedure. (Receivers) 1. (name) (title) (date) (time) (warning point) 2. (name) (title) (date) (time) (warning point) 3. (name) (title) (date) (time) (warning point) 4. (name) (title) (date) (time) (warning point) 5. (name) (title) l (dcte) (time) (warning point) i 6. l (name) (title) l (date) (time) (warning point) 7. (name) (title) (date) (time) (warning point)
ENCLOSURE 4.4 PROTECTIVE ACTION RECOMMENDATION FLOW CHART 4 l 'is the emergency classified " UNUSUAL -Yes ? No recommendations required
. EVENT" or " ALERT"?
I No 4 Is the emergency classified " SITE Yes-- m Recommend to offsite authorities that ) AREA EMERGENCY"? people in the 2 mile area be made 4 l aware of the situation and monitor . ' No EBS for further information. Consider ' 4 evacuation of nonessential station i Classification is a " GENERAL EMERGENCY" l personnel. l 4 i immediately recommend that people in the 2 mile area and 5 mile downwind go indoors, close all windows and doors, turn off ventilation equipment, and monitor EBS for information. As soon as possible, followup the recommendation with one based on an cxtensive evaluation of the two areas listed below. Evacuate non-essential station personnel. Compare projected downwind doses and Evaluate Core / Reactor Coolant field monitoring team measurements , - System / containment status and l with EPA PAG's (see 3.3.2). Determine compare with the following i appropriate actions. preselected recommendations. t 4 4 i Compare the recommendations developed For core melt sequences where from these two analyse and determine significant releases from containment the most appropriate of the two. If 4 are not yet taking place and large j :: lose projections or field team . amounts of fission products not yet in
- measurements are not available, e containment atmosphere, recommend a l l determine actions based solely on core 2 mile precautionary evacuation and
! melt analysis. sheltering to 5 miles. Recommend : ! A evacuation to 2 miles and to 5 miles Before making a final determination downwind if fission product activity consider these constraints: greater than gap activity is in 1 containment atmosphere.
- 1. Plume arrival time versus avecuation 4 time estimate (Do not evacuate the For core melt sequences where
- public in the plume). significant releases from containment
- 2. Do bridge L road conditions present are not yet taking place and an impediment to evi.cuation? containment failure is likely but not
- 3. Will weather conditions inhibit 6 imminent, and large amounts of fission evacuation? products in addition to noble gases
) 4. Can state / local agencies physically are in containment atmosphere, support the recommendations? consider precautionary evacuation to
- 5. Is this a " puff" or continuous release? 5 miles and to 10 miles downwind.
4 For core melt sequences where large amounts of fission products in addition to noble gases are in the containment i atmosphere and containment failure is judged imminent, recommend shelter for 3 those areas where evacuation cannot : be completed before transport of activity to that location. l 1
Enclosu 4.5 CATAWBA NUCLEAR STATION p 10-MILE EMERGENCT PLANNING ZONE (EPZ) MAP
==== Sone er 372 soundary .
3 h1 Ione Number
~
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hh l Y3 ht h t
)
h ( A
, /
A-3
/
E' & ,, f ' G i N i 5 , .
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/
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o' 5 (
) 3
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g i
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,,N \ '
, 's , %%
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, , , , , . . . . . . . - + - * * - ~ * * " ' * * **
Form 34731 (10 81) 4 (Formerly SPD 10021F DUKE POWER COMPANY (1) ID No: RP/0/A/5000/05 PROCEDURE PREPARATION Change (s) I to 4 PROCESS RECORD ~L Incorporated 4 (2) STATION: CATAWBA + (3) PROCEDURE TITLE: GENERAL EMERGENCY (4) PREPARED BY: M. E. Bole,h DATE: 2-2-84 l _s - (5) REVIEWED BY: h _ k Jh DATE: 4 0-Bi' Cross-Disciplinary Review By: . N/R: b (6) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: By: . Date: (7) APPROVED BY: M-1 Date: C!/ !#
- i (8) MISCELLANEOUS:
Reviewed / Approved By: Date: Reviewed / Approved By: Date: I j l l < ~ ~ ~ - - --
RP/0/A/5000/05 DUKE POWER COMPANY CATAWBA NUCLEAR STATION ! GENERAL EMERGENCY l 1.0 SYMPTOMS 1.1 Events are in process or have occurred which involve an actual or imminent substantial core degradation or melting with potential for loss of containment integrity. 2.0 IMMEDIATE ACTIONS 2.1 Make initial notifications to individuals and organizations. 2.1.1 Complete Enclosure 4.2 and Part I of Warning Message Form (see example Enclosure 4.3). Record receiver's name and time on Enclosure 4.2 and on Page 4 of Warning Message. NOTE: Emergency Coordinator shall initial forms when message is approved for transmission. NOTE: Warning Message forms are kept in a notebook in the Control Room a..d TSC, ensure that all used forms are returned to the back of the notebook. 2.1.2 Notifications shall be as the order of Enclosure 4.1 indicates. 2.1.3 Advise station personnel to activate TSC and OSC. NOTE: The State and County notification must be made within 15 minutes of declaration of the emergency. 2.2 Protective Actions Offsite 2.2.1 Recommend to Offsite Agencies that all residents of the 2 mile radius zone (A-0) and any zone 5 miles downwind of the plant seek immediate shelter and await futher instructions. See Enclosure 4.5 for 10 mile-EPZ Map. 2.3 Protective Action Onsite 2.3.1 Conduct a Site Assembly per RP/0/A/5000/10. 2.3.2 Evacuate non-essential personnel to the Evacuation Relocation Centers per RP/0/A/5000/10. 3.0 SUESEOUENT ACTIONS i 3.1 Accident Assessment, the Emergency Coordinator shall: 3.1.1 Dirpatch field monitoring teams with associated communications equipment per HP/0/B/1009/04.
~
r- HP/0/ A/50007 5~~ ~ Paga 2 cf 3 3.2 Give follow-up messages to offsite agencies listed on 4.1.3 of Enclosure 4.1, use the following schedule: 3.2.1 Every half hour until the emergency is closed out. E If there is any significant change to the situation. E As agreed upon with the individual agencies. 3.2.2 Use Parts l & 11 of Warning Message Form as applicable. Mark all spaces "N/A" when information is "Not Applicable" and mark "Later" when information is not currently available. 3.3 Follow-up Recommend Protective Action Offsite NOTE Protective Action Recommendation are obtained from: OAC Program " Nuclear-23" or RP/0/A/5000/11, if the OAC is not operational. 3.3.1 The Emergency Coordinator shall make Protective Action Recommendations to the affected county warning points and to both SC and NC state warning points (Emergency Operations Center if established) or the designated state department as per the state's Radiological Emergency Response Plan. See Enclosure 4.4 for aid in protective action decision making. NOTE This authority shall not be delegated to other elements of the emergency organization. 3.3.2 If actual release of radioactive material will result in a projected dose to the population of: Whole Body Thyroid Recommendation
<1 Rem <5 Rem No Protective Action is Required.
I to <5 Rem 5 to <25 Rem Recommend seeking shelter and wait for further instruction. Consider evacuation particularly for children
& pregnant women. Control access to affected areas.
>5 Rem >25 Rem Recommend mandatory evacuation of population in the affected areas.
Control access to affected areas. ,
~~
RP/0/A/5000/05 Pago 3 cf 3 NOTE l I Monitor environmental radiation levels to verify and adjust l recomme' ndations as necessary.
~
3.4 Augment on shift resources to assess and respond to the emergency situation as needed. 3.5 Assess the emergency condition, then remain in an General Emergency, reduce the emergency class or terminate the emergency. 3.6 The Recovery Manager at the Crisis Management Center shall close out the emergency or recommend reduction of the emergency class by briefir.g the offsite authorities at the Crisis Management Center or by phone if necessary, followed by written summary within 8 hours. 4.0 ENCLOSURES 4.1 Telephone Notification List , 4.2 Emergency Message Format 4.3 Example Warning Message: Nuclear Facility to State / Local Government 4.4 Protective Action Recommendation Flow Chart 4.5 10 Mile Emergency Planning Zone (EPZ) Map l l l
RP/0/A/5000/05 Enclosure 4.1 Page 1 of 2 , l TELEPHONE 1 NOTIFICATION LIST i 4.1.1 CNS Emergency Personnel Initial l
- 1. Operations Duty Engineer - Plant Page P & T Pager - 637 or 277 A: See Current Operations Work List for Home Phone Number.
- 2. Station Manager - J. W. Hampton e
1st Alternate - C. W. Graves Office 2304 Home 6 2nd Alternate - J. W. Cox Office 2303 Home 6 3rd Alternate - G. T. Smith Office 2302 Home 6 4th Alternate - A. R. Franklin ! Office 2305 Home M i 3. License & Projects Engineer - C. L. Hartzell , Office 2785 i l Home M 1st Alternate - M. E. Bolch Office 2782 l Home M l 2nd Alternate - F. N. Mack Office 2781 Home 6 1 4.1.2 Nuclear Production Duty Engineer 373-5491 P & T Page 373-5214 e625 l ** USE ENCLOSURE 4.2 ** l
s..s.v w.e ..
. Pega 2 cf 2 4.1.3 Stat, s Ceunty Emerg ncy C nt rs (Within 15 minut s)
- 1. N.C. State Warning Point, Raleigh - 919/733-3861
*** USE ENCLOSURE 4.3 ***
- 2. S.C. State Warning Point. Columbia P: 803-758-5548 7:30 a.m. - 5:00 p.m. Weekdays A: 803-758-5531 Afterhours, Week-ends & Holidays
*** USE ENCLOSURE 4.3 ***
- 3. Mecklenburg County Warning Point P: Selective Signal - 116 A: 704-374-3333 Back-up: Emergency Radio, Code: 21,
*** USE ENCLOSURE 4.3 ***
- 4. York County Warning Point P: Selective Signal - 513 A: 803-327-2021 Back-up: [mergency Radio, Code: 41 - .'
i
*** USE ENCLOSURE 4.3 ***
- 5. Gaston County Warning Point P: Selective Signal - 112 A: 704-866-3300 Back-upi Emergency Radio, Code 26 -
*** USE ENCLOSURE 4.3 ***
4.1.4 NRC Operations Center, Bethesda Md. P: ENS phone (red phone) A: 202-951-0550 l l l
=
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ENCLOSURE 4.2 PAGE 1 OF 1 DUKE POWER COMPANY CATAWBA NUCLEAR STATION EMERGENCY MESSAGE FORMAT
- 1. This is at Catawba Nuclear Station.
(Name and Title)
- 2. This is is not a drill. An Unusual Event Alert Site Area Emergency General Emergency was declared by the Emergency Coordinator at on Unit # .
(Time)
- 3. Initiating condition: (Give as close to the emergency plan description as possible together with station parametars used to determine emergen'cy status).
- 4. Corrective measures being taken:
- 5. There _ _ have have not L .en any injuries to plant personnel.
- 6. Release of eadioactivity: is taking place is not taking place
- 7. NRC Yes No; State Yes No; Counties Yes No; have been notified.
- 8. The Crisis Management Team should should not be activated.
Corporate Communications & Company Management should be notified.
- 9. I can be reached at for follow-up information.
(Telephone Number)
- 10. Additional Comments:
Name of Person Contacted Date Time
~ -~
tGF/@//A/MK0/@B Enclosure 4.3 ggp[p Pega 1 of 4 WARNING MESSAGE: NUCLEAR FACILITY TO STATE / LOCAL GOVERNMENT instructions: A. , For Sender:
- 1. Complete Part I for the Initial Warning Message.
- 2. Complete Parts i L 11 for followup messages.
B. For Receiver:
- 1. Record the date, time and your name in the area below.
- 2. Authenticate this message by verifying the code word or by calling back to the facility. (See Part 1.5)
Time: Date: Message Received By: PART I W r *- ,n<2s* E*-4F'9
- 1. This is: Catawba Nuclear Station
- 2. My name is:
- 3. This message (number ):
(a) Reports a real emergency. (b) is an exercise message.
- 4. My telephone number / extension is:
- 5. Message authentication: USE MESSAGE AUTHENTICATION LIST (Verify code word or call back to facility)
- 6. The class of the emergency is
- (a) Notification of Unusual Event l
(b) Alert (c) Site Emergency X (d) General Emergency
- 7. This classification of emergency was declared at: (a.m./p.m. ) on (date).
- 8. The initiating event causing the emergency classification is:
L i
- 9. The emergency condition: (a) Does not involve the release of radioactive materials from the plant.
(b) Involves the potential for a release, but no release is occurring. (c) Involves a release of radioactive material.
~ ~ ~
RP/0/A/5000/05 Encicsuro 4.3 Pago 2 cf 4
- 10. We recommend the following protective action:
(a) No protective action is recommended at this time.
~ _ (b) People living in zones _
remain indoors with the doors and windows closed. (c) People in zones evacuate their homes and businesses. (d) Pregnant women and children in zones remain indoors with the doors and windows closed. (e) Pregnant women and children in zones evacuate to the nearest shelter / reception center. (f) Other recommendations:
- 11. There will be:
(a) A followup message (b) No further communications ^EE# ** '# * ****
- 12. I repeat, this message:
Emerg. Coord. Time (a) Reports an actual emergency (b) is an exercise message 13. RELAY THIS INFORMATION TO THE PERSONS INDICATED ON YOUR ALERT PROCEDURE FOR AN INCIDENT AT A NUCLEAR FACILITY.
***END OF INITIAL WARNING MESSAGE ***
my '<'
;- PART li ~4 '* ' ^': % ' \
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- 1. The type of actual or projected release is:
(a) Airborne (b) Waterborne (c) Surface spill (d) Other
- 2. The source and description of the release is:
- 3. (a) Release began /will begin at a.m./p.m.; time since reactor trip is hours.
(b) The estimated duration of the release is hours. I 1 I
RP/0/A/5000/05 Encl: sura 4.3 Pega 3 cf 4
- 4. Dose projection base data:
Radiological release: curies, or curies /sec. 4 Windspeed: mph Wind direction: From
- Stability class: ( A, B, C', D, E, F, or G)
Release height: Ft. Dose conversion factor: R/hr/Ci/m* (whole Sody) R/hr/Ci/m* (Child Thyroid) Precipitation: Temperature at the site: 'F
- 5. Dose projections:
- Dose Commitment
- Whole Body (Child Thyroid) i Distance Rem / hour Rem / hour of inhalation Site boundary 2 miles 5 miles 10 miles
- Projected integrated Dose in Rem
- Distance Whole Body Child Thyroid Site boundary 2 miles 5 miles 10 miles
- 6. Field measurement of dose rate or contamination (if available):
i
- 7. Emergency actions underway at the facility include:
- 8. Onsite support needed from offsite organizations:
- 9. Plant status:
(a) Reactor is: not tripped / tripped (b) Plant is at: *. power / hot shutdown / cold shutdown / cooling down (c) Prognosis is: s ta ble/ imp rovin g /d eg ra din g/ u n k n own
. ... . ~ . . . . . . . .. .. . .. . . . . .. . . . . . . .
RP/0/A/5000/05 Enclosure 4.3 Paga 4 cf 4
- 10. I repeat, this message:
(a) Reports an actual emergency. (b) is an exercise message. Approved for Release
- 11. Do you have any questions?
Emera. Coord. Time
***END OF FOLLOW-UP MESS AGE ***
NOTE: Record the name, title, date, time, and warning point notified. (Senders) Record the name, title, date, time, and persons notified per alert procedure. (Receivers) 1. (name) (title) (date) (time) (warning point) 2. (name) (titie) (date) (time) (warning point) 3. (name) (title) (date) (time) (warning point) 4. (name) (title) (date) (time) (warning point) 5. (name) (title) (date) (time) (warning point) 6. (name) (title) (date) (time) (warning point) 7. (name) (title) (date) (time) (warning point)
ENCLOSURE 4.4 PROTECTIVE ACTION RECOMMENDATION FLOW CHART i I ( la the emergency classified " UNUSUAL -Yes % No recommendations required l ! a EVENT" or " ALERT"7 I . I ! No ! O
- Is the emergency classified " SITE Yes % Recommend to offsite authorities that j AREA EMERGENCY"? people in the 2 mile area be made '
I aware of the situation and monitor ' i No EBS for further information. Consider I 4 evacuation cf nonessential station 1 l Classification is a " GENERAL ENERGENCY" l personnel. l t A : j immediately recommend that people in the 2 mile area and 5 mile downwind go indoors, l j close all windows and doors, turn off ve~ntilation equipment, and monitor EBS for i information. As soon as possible, followup the recommendation with one based on an extensive evaluation of the two areas listed below. Evacuate non-essential station i personnel. I l Compare projected downwind doses and
' Evaluate Core / Reactor Coolant i field monitoring team measurements m u - System / containment status and with EPA PAG's (see 3.3.2). Determine compare with the following anoroorlate actions, preselected recommendations.
E
- i j Compare the recommendations developed For core melt sequences where t i from these two analyse and determine significant releases from containment i j the most appropriate of the two. If p are not yet taking place and large dose projections or field team l j
amounts of fission products not yet in ; i measurements are not available, e containment atmosphere, recommend a i determine actions based solely on core 2 mile precautionary evacuation and ; melt analvsis. sheltering to 5 miles. Recommend l 4 evacuation to 2 miles and to 5 miles Before making a final determination l l downwind if fission product activity ' l consider these constraints: greater than gap activity is in 1 containment atmosphere. ! , 1. Plume arrival time versus evacuation & ! time estimate (Do not evacuate the For core melt sequences where [ t public in the plume). significant releases from containment
- 2. Do bridge 8, road conditions present are not yet taking place and .
i an impediment to evacuation 7 containment failure is likely but not l ! 3. Will weather conditions inhibit imminent, and large amounts of fission evacuation? l i products in addition to noble gases l l 4. Can state / local agencies physically are in containment atmosphere, ! ! support the recommendations? consider precautionary evacuation to !
- 5. Is this a " puff" or continuous release? _5 miles and to 10 miles downwind.
jl ), l A , For core melt sequences where large l amounts of fission products in addition i to noble gases are in the containment l atmosphere and conlainment failure'is ' g Judged imminent, recommend shelter fer j those areas where evacuation cannot I be completed before transport of l activity to that location, i l
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l Form 34731 (1041) (Former,1y SPD 10021) DUKE POWER COMPANY (1) ID No:RP/0/A/5000/06 PROCEDURE PREPARATION Change (s) n to PROCESS RECORD n Incorporated (2) STATION: CATAWBA (3) PROCEDURE TITLE: NATURAL DISASTER (4) PREPARED BY: MIKE BOLCH DATE: (5) REVIEWED BY: 8. I 1 - - DATE: 3//r/s3 Cross-Disciplinary Review By: d- 3)/ O N/R: d[b 60!1D'
//
(6) TEMPORARY APPROVAL (IF NECESSAR : By: (SRO) Date: By: Date: (7) APPROVED BY: N .h .T4 LN N b Date: 3 T%!SI J J %' (8) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: O s
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. RP/0/A/5000/06 DUKE POWER COMPANY CATAWBA NUCLEAR STATION NATURAL DISASTER 1.0 SYMPTOMS ...._._.
1.1 Observation _of_ Hurricane, Tornado, Flood, Low Lake Level or Seiche (Lake Tidal Wave) , 1.2 Notification by: National Weather Service (NOAA Broadcast), System Dispatcher, Local Radio Broadcast 2.0 IMMEDI ATE ACTIONS Initicl/N/A 2.1 Shutdown Reactor (s) 2.1.1 Trip the reactor (s) and proceed to cold shutdown if the following conditions exist at the station: Sustained Winds t, Tornadoes High Lake Level Low Lake Level
> 95 mph > 593.5 Ft MSL < 550.4 Ft MSL NOTE: Seiche is same as High Lake Level.
i 2.2 Notification i 2.2.1 Classify the emergency by RP/0/A/5000/01, Classification of Emergency, and commence notification and/or other protective measures as directed by appropriate Emergency Response Procedure. 2.2.2 Announce the impending condition over the plant PA System when appropriate. 3.0 SUBSEOUENT ACTIONS 3.1 Contact the National Weather Service at 704-399-6000 to obtain the latest forecast /information. 3.2 If conditions permit, move the station vehicles inside the Turbine Building. . 3.3 Close or check closed all truck and personnel access doors on the Auxiliary and Turbine Buildings and Warehouse.
. RP/0/A/5000/06
- Pcg2 2 cf 2 1-'ti:Is/N/A 3.4 Minimize or stop all handling of radioactive materials and releases of radioactive waste to the environment for the duration of the emergency.
3.5 Monitor Ground Water Drainage System operation closely. 3.6 Monitor sump levels periodically. 3.7 On Low Low Lake Level of 554.4 ft. MSL, refer to AP/1/A/5500/20, i Loss of RN System, if RN swapover to the Standby Nuclear Service Water Pond has not occurred automatically. 3.8 When conditions permit, perform a survey of plant structures and equipment to determine the extent of damage, if any, and record in the Shift Supervisor's Log.
) 4.0 ENCLOSURES None 9
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Perm 34731 (1041) - (7 :- _:;i SPD 10021) DUEI POWER b MPANT (1) ID No:RF/0/A/5000/07 PROCEDURE PREFARATION Changa(s)1_to PROCESS RECORD 1 Incorporated i . l (2) STATION: rAvAuRA
-(3) FROCEDURE TITLE: FA*Tuonirr 4
(4) FREPARED BY: Mike Bolch , DATE: Nov. 07 lent (5) REVIEWED IT: DATE: //! Cross-Discip Ra By: ~O N/R:
- (6) TIMPORARY AFFROVAL (IF NECESSARY): l
! By: (SRO) Data:
By: e Datas (7) AFFROVED BY: [ A >=c !
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Date: // 7 ' 8I ( (8) MISCELLANEDUS: Reviewed / Approved By: Data Reviewed / Approved By: Data: i
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RP/0/A/5000/07 DUKE POWER COMPANY CATAWBA NUCLEAR STATION
~
. EARTHQUAKE 1.0 SYMPTOMS 1.1 Seismic event alarm SMA-3 on 1MC8 I
1.2 OBE Exceeded alarm on AD-4 (B-8). 1.3 Light on Peak Shock Annunciator PSA-1575 on 1MC8 1.4 Effects of an earthquake are seen, felt or heard.
- 2.0 IMMEDI ATE ACTIONS Initial /N/A 2.1 Shutdown Reactor (s) ;
2.1.1 If the Operational Basis Earthquake (OBE) Exceeded Alarm is received and the effects of an earthquake are felt, then immediately take Reactor (s) to Hot Standby. 2.1.2 Notify lt.E to remove the magnetic tapes from the SMA-3 recorder to evaluate and verify the raagnitude of the , earthquake in accordance with IP/0/B/3341/03. 1 2.1.3 If the earthquake intensity is >.15g horizontal and/or
>.lg vertical (SSE level)', then proceed to take the reactor (s) to Cold Shutdown.
2.2 Classify the emergency by RP/0/A/5000/01, Classification of Emergency and commence notification and/or other protective measures as directed by appropriate Emergency Response Procedure. 3.0 SUBSEQUENT ACTIONS 3.1 All records made by 'accelerographs and recorders shall be evaluated to verify the extent of the earthquake. 3.1.1 See Enclosure 4.1 for locations and procedure numbers of seismic instruments. .l 3.1.2 Seismic verification may be obtained by calling the National Earthquake Information Service at (303) 324-3994. 3.2 Perform a survey of the plant structures and equipment to determine the extent of damage, if any, and record in the Unit Supervisor *: . Log. * ;
I
)
3.2.1 Notify personnel from isE and Mechanical Maintenance to assist Operations in the evaluation of earthqua',e damage if necessary. ,.
. 3.2.2 Notify Health Physics personnel to survey the Reactor, l Auxiliary and Fuel Pool Buildings to ensure shielding '
integrity. 3.2.3 Notify Chemistry personnel to survey areas where damage may release dangerous chemicals (e.g. Sulfuric Acid Storage). 3.3 Closely monitor plant. parameters to ensure plant safety. 3.4 Reporting Requirements 3.4.1 If the earthquake was determined to be >OBE, the LLP Engineer or delegate shall make a report to the NRC (Regional Office) within 24 hours via telephone. (TS 6.9.1.12.g) 3.4.2 If the earthquake was detarmined to be <OBE but recorded I on station seismic instrumentation, the LEP Engineer or delegate shall make a written report to the NRC (Regional Office) within 10 days. (TS 4.3.3.4.2) 4.0 ENCLOSURES J h 4.1 Loc 4tions of Seismic Instruments and Procedure Numbers
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.,, - - . _ - - - . - - - - - - - - - - - - - - . - , , . - - , - . - - - ~ -. ,. . - -- - - - - . -- -- -- -. -
DUKE POWER COMPANY CATAWBA NUCLEAR STATION SEISMIC MONITORING INSTRUMENTS ype Instrument a Name Location Procedure e ' P 1MIMT-5010 Peak Accelerograph CA Pipe to S/G 1D IP/0/B/3341/05 P IMIMT-5020 Peak Accelerograph NC Pipe at PZR Surge Line IP/0/B/3341/05 P 1MIMT-5030 Peak Accelerograph NI Pump 1 A IP/0/8/3341/05 , 1 j A (1) IMIMT-5040 Spectrum Recorder RB Basement 0* IP/0/B/3341/04 i j P 1MIMT-5050 Spectrum Recorder PZR Lower Support IP/0/B/3341/04 P 1MIMT-5060 Spectrum Recorder Aux Bldg. 577 EL. (PP-56) IP/0/B/3341/04 A (2) 1MIMT-5000 Seismic Switch RB Basement O' IP/0/B/3341/01 l A 1MIMT-5070 Strong Motion RB Basement 0* IP/0/B/3341/03 Accelerograph j l ? ! A 1MlMT-5080 Strong Motion Annulus 619 EL 0* IP/0/B/3341/03 Accelerograph !
- 1MIMT-5090 Starter Unit for P 3 Basement 0* IP/0/B/3341/01 \
! . SMA-3 , I P- Passive (historical record) A - Active (remote read-out)' j Nste 1: Also provides input to Peak Shock Annunciator (PSA1575)
) Ncte 2: Provides indication of OBE Exceeded on AD4 (B-8) in Control Room :
I Seismic Remote Readouts k . { SMA-3 Triawial Time-History Accelerographs (Strong Motion l Accelerograph System) - in standby until 0.1g acceleration
! starts magnetic tape recorder unit - back up power supply from
! built in battery. . I
- SMP-1 Magnetic Tape Playback Unit - plays back one of three channels at a time onto strip chart for data evaluation.
! PSA-1575 Peak Shock Annunciator gives visual warning that >70% OBE i (amber light) or $100*. OBE (red light) has been exceeded at certain frequencies (2H t Z o 25.4 HZ) i
- 6 i
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F Form 34731 (10-81) (Formerly SPD 10021) DUKE POWER COMPANY (1) ID No: RP/0/A/5000/08 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD 0 Incorporated (2) STATION: CATAWBA (3) PROCEDURE TITLE: RELEASE OF T0XIC OR' FLAMMABLE GAS (4) PREPARED BY: MIKE BOLCH DATE: (5) REVIEWED BY: O./. M __ - DATE: 3-//-#3 Cross-Disciplinary Review By: w. 3 //r /D N/R: M[ (3/4 v ' ' ' (6) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: By: _ Date: (7) APPROVED BY: . b. ! ' Date: hb (8) MISCELMNEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date:
a C RP/0/A/5000/08 DUKE POWER COMPANY CATAWBA NUCLEAR STATION . RELEASE OF TOXIC OR FLAMMABLE GAS l 1.0 SYMPTOMS 1.1 This condition exists wh'en toxic or flammable gases released nearsite or onsite, (verified by analysis if deemed necessary) present a harzard to station personnel or property. 2.0 IMMEDIATE ACTIONS l Initial /N/A 2.1 Classify the emergency by RP/0/A/5000/01, Classification of Emergency and commence notification and/or other protective measures as directed by appropriate Emergency Response Procedure. 3.0 SUBSEOUENT ACTIONS 3.1 The Shift Supervisor will request the Station Safety Section to evaluate the hazardous condition. 3.2 The Shift Supervisor will take appropriate actions to ensure the safety of all persons and property in the potentially affected areas. 1 3.2.1 Initiate a Site Assembly and/or Evacuation if necessary. i 3.2.2 Notify outside services per Enclosu're 4.1 if help needed. 3.3 In the event that evacuation of the Control Room appears imminent, refer to AP/1/A/5500/17, Loss of Control Room. 4.0 ENCLOSURE 4.1 Emergency Telephone Numbers 4 1
[
'__ (' RP/0/A/5000/08 Enclssura 4.1 DUKE POWER COMPANY.
CATAWBA NUCLEAR STATION
' EMERGENCY TELEPHONE NUMBERS
* , l Ambut,ance r, Medical Piedmont Medical Center . . . . . . . (803) 329-9111 l
I l Rescue Squad York County Sheriff Department . . . (803) 327-2021 ! Fire Department Etethel Volunteer Fire Department . . . (803) 631-4112 1
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Form 34731 (10 81) - (Formerly SPD 10021) DUKE POWER COMPANY (1) ID No: RP/0/A/5000/09 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD 0 Incorporated (2) STATION: CATAWBA (3) PROCEDURE TITLE: COLLISION / EXPLOSION (4) PREPARED BY: MIKE BOLCH DATE: (5) REVIEWED BY: J . /2. A - DATE: 7- if- J3 Cross-Disciplinary Review By: w- 3/if f65 _ N/R: d C S3 As l / I (6) TEMPORARY APPROVAL (IF NECESSAR : By: (SRO) Date: By: Date: (7) APPROVED BY: ,b. Date: )D $) (8) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: I i l l
l RP/0// /5000/09 DUKE POWER COMPANY CATAWBA NUCLEAR STATION COLLISION /EXPLOSlON 1.0 SYMPTOMS 1.1 Observance of the following incident onsite or near site: 1.1.1 Aircraft crash or threatening aircraft activity - 1.1.2 Train derailment 1.1.3 Waterborne collision 1.1.4 Missile impact 1.1.5 Explosion 1.1.6 incider.t jeopardizing vital structures or safe shutdown equipment 2.0 IMMEDIATE ACTIONS itial/N/A 2.1 Classify the emergency by RP/0/A/5000/01, Classification of Emergency, and commence notification and/or other protective measures as directed by appropriate Emergency Response Procedure. 3.0 SUBSEQUENT ACTIONS
- 3.1 Take appropriate actions to ensure the safety of the reactor (s).
3.2 Perform emergency first aid as necessary. 3.3 Extinguish any fire (s) if applicable. 3.4 Notify Chemistry if there are any chemical implications. 3.5 Notify Health Physics if there are any radiological implications. 3.6 Notify applicable outside agencies as necessary. (Enclosure 4.1) l- 4.0 ENCLOSURES 4.1 Emergency Notification List , o These actions may be performed concurrently as appropriate i t
RP/0/A/5000/09 Enclosure 4.1 DUKE POWER COMPANY CATAWBA NUCLEAR STATION EMERGENCY TELEPHONE NUMBERS Ambulance & Medical Piedmont Medical Center . . . . . . . . (803) 329-9111 Rcscue Squad York County Sheriff Department . . . . (803) 327-2021 Fire Department Bethel Volunteer Fire Department . . . (803) 631-4112 Federal Aviation Administration - 24 Hr. Number . . . . . .. . (919) 761-3147 Duke Power Company Railroad Contact - Wayne Hallman . 77-2345 Days Home . . . . . . . . . M f
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Form 34731 (10-81) (Formerly SPD-10021) DUKE POWER COMPANY (1) ID No:RP/0/A/5000/10 PROCEDURE PREPARATION Change (s) n to PROCESS RECORD 1 Incorporated (2) STATION: CATAWBA (3) PROCEDURE TITLE: CONDU.CTING A SITE ASSEMBLY OR EVACUATION (4) PREPARED BY: Mike Bolch . DATE: 2-6-84 5 (5) REVIEWED BY: s [ DATE: A'0'O N Cross-Disciplinary Review By: N/R: M (6) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: By: Date: (7) APPROVED BY: - Date: A!/,!5[ v , , (8) MISCELMNEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: l l l l l 1 l I
RP/0/A/5000/10 DUKE POWER COMPANY CATAWBA NUCLEAR STATION
, CONDUCTING A SITE ASSEMBLY OR EVACUATION 1.0 SYMPTOMS 1.1 A Site Asserably is an occurance that warrants the accountability of all personnel on site for reasons of personnel safety or for dissemination of information.
1.1.1 Alert, if plant conditions are rapidly degrading. 1.1.2 Site Area Emergency or General Emergency. 1.1.3 Other plant conditions that, in the opinion of the Shift Supervisor / Emergency Coordinator, warrant a precautionary assembly 1.1.4 Auxiliary Building Radiation Levels 1.1.4.1 Radiation levels in unrestricted areas of Auxiliary Building > 2 mr/hr. 6 1.1.4.2 Airborne Radiation Levels > 1 x 10 e m by EM F-41. 1.2 A Site Evacuation is an occurance that necessitates the evacuation of non-essential personnel for reasons of safety. 1.2.1 Site Area Emergency, if plant conditions are rapidly degrading 1.2.2 General Emergency
. 1.2.3 Other plant conditions that, in the opinion of the Shift
- Supervisor / Emergency Coordinator, warrant a precautionary i evacuation.
2.0 IMMEDI ATE ACTIONS 2.1 Site Assembly 2.1.1 Contact the Security Shift Lieutenant or Clerk at extension 2393 to inform them that a Site Assembly is being initiated. 2.1.2 The Shift Supervisor or delegate shall sound a twenty 4 second blast of the Site Assembly alarm and make the following announcement on the plant page system:
Paga 2 of 3
- 1. "This is the Shift Supervisor, this is a Site Assembly. l This is a Site Assembly. There is/are i i ,
What
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in/at Where , All personnel and visitors report to their assembly l points (parking lot if a bomb threat)." NOTE: Assembly points are listed in Station Directive 3.0.7. 2.1.3 Repeat 2.1.2 in full. l 2.2 Site Evacuation (Must be preceeded by a Site Assembly) 2.2.1 Choosing an Evacuation-Relocation Site 2.2.1.1 Contact Health Physics Duty Supervisor for assistance in assessing the radiological hazard associated with the evacJation. Plant pager no. 7673-21t or 215. I 2.2.1.2 Site Alpha (Transmission Line Maintenance Warehouse, Newport, S.C.) is located 4.8 miles SW of the plant. ! 2.2.1.3 Site Bravo (Allen Steam Station, Belmont,- N.C.) j !s located 10 miles NNE of the plant. l 2.2.1.4 Choose the site most opposite the direction that i' the wind may be carrying any expected release. See Enclosure 4.1. l 2.2.2 Contact the Evacuation Coordinator listed in Station Directive 3.8.4, Enclosure 6, to inform him that an Evacuation is being initiated. 2.2.3 The Shift Supervisor or delegate shall sound a twenty second blast of the Site Evacuation alarm and make the i following announcement on the plant page system: l l
"This is the Shift Supervisor, this is a Site Evacuation. l This is a Site Evacuation. All non-essential personnel l proceed to ."
Site Alpha / Bravo 2.2.4 Repeat 2.2.3 in full. l 3.0 SUBSEOUENT ACTIONS 3.1 Notification 1 3.1.1 Notify the York County Sheriff's Department or the S.C. Highway Patrol to assist in traffic control. ) (Station i , Security shall direct traffic until their arrival.) 'l l l l l l j- . . . . . . . - . . . . . . . . l l
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A. York County Sheriff 327-2021 B. S.C. Highway Patrol 366-7668 3.1.2 Notify the chosen Evacuation-Relocation Site of the expected arrival of personnel. i A. Alpha - 373-7309 Transmission Line Maintenance Warehouse B. Bravo - 373-4646 Allen Steam Station 3.2 Continue to repeat Step 2.1.2 or 2.2.3 at 5-minute intervals until notification that the Site Assembly / Evacuation has been completed. 3.3 Securing from a Site Assembly 3.3.1 The Shift Supervisor or delegate shall make the following announcement on the plant page system:
"This is the Shift Supervisor, secure from Site Assembly.
Secure from Site Assembly. 3.3.2 Repeat 3.3.1 in full. 3.4 Securing from a Site Evacuation 3.4.1 The Emergency Coordinator / Shift Supervisor or Recovery Manager at the CMC shall notify the Evacuation Coordinator at the Evacuation-Relocation Site when evacuated personnel can return to their work location. 4.0 ENCLOSURE 4.1 Wind Direction Determination i 9
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O M h s l WIND DIRECTION FROM USE THIS SITE I 145' to 255' ALPHA 350' to 360' & 0' to 100* BRAVO l NOTE: Wind Direction is always stated in FROM I* a given direction. Example: 180* Wind is From 180' blowing toward 0*.
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Form 34731 (1041) l (Formerly SPD 10021)
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DUKE POWER COMPANY (1) ID No: RP/0/A/5000/11 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD 0 Incorporated (2) STATION: crrAURA (3) PROCEDURE TITLE: PROTECTIVE ACTION RECOMMENDATIONS WITHOUT THE OAC (4) PREPARED BY: Mike Bolch DATE: Dec. 01, 1983 (5) REVIEWED BY: - .
- DATE: $ ~ \ b -6S' Cross-Disciplinary Review By: : W- iL/A k N/R: 86 O /V V '
l (6) TEMPORARY APPROVAL (IF NECESSARY): By: - (SRO) D4te: By: Date: (7) APPROVED BY: L./ Date: Ek h (8) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: I v y -, ,_, . . ~ _ . . ._ _ _ . . . - . m.__ -
__ . . _ . _ _ .._. - . =-___ _ RP/0/A/5000/11 4 DUKE POWER COMPANY CATAWBA NUCLEAR STATION PROTECTIVE ACTION RECOMMENDATIONS WITHOUT THE DAC 1.0 SYMPTOMS 1.1 LOCA with: 1.1.1 EMF-53A or 53B, Containment High Range Radiation Monitor, in alarm, DE 1.1.2 EMF-36(L), Unit Vent Gas Monitor, in alarm. 1.2 Dose Assessment Program (later) unavailable.
- 2.0 IMMEDIATE ACTIONS 2.1 Check Rx Building or Unit Vent Radiation Level as Symptoms Indicate i
2.1.1 Check the Reactor Building radiation level by either of the following methods: 2.1.1.1 Record EMF-53A and EMF-538 readouts on Enclosure 4.2. 2.1.1.2 Obtain radiation level from Shift Health Physics using HP/0/B/1009/06 (Alternative Methods for Determining Dose Rate Within the
- ReactorBuilding). Record on Enclosure 4.2.
2.1.2 Record EMF-36(L) and EMF-36(H) readings on Enclosure 4.3. j 2.2 Perform the following based on radiation levels. 2.2.1 If the Reactor Building radiation level is 5 35 R/hr, i continue monitoring the Reactor Building radiation level. ( 2.2.2 If the Reactor Building radiation level is > 35 R/hr, complete ! Enclosures 4.1, 4.2 and 4.4. 2.2.3 If EMF-36(L) is 5 30,000 cpm, continue monitoring Unit Vent radiation level. t 2.2.4 If EMF-36(L) is > 30,000 cpm, complete Enclosures 4.1, 4.3 i and 4.4. ; 2.3 Recommendations , 2.3.1 Determine Protective Action Recommendations from Steps 1 and 2 of Enclosure 4.4.
~ . . . . . . . . . . . . . . . - - . . . . . . . - .
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hr/ U/ h/ DUUU/ L L. Page 2 of 2 l 2.3.2 Always include Zone A-0 in Recommendations. 2.3.3 See RP/0/A/5000/05 (General Emergency) for Recommendation Format.
- 3. 'O SUBSEQUENT ACTIONS 3.1 Determine the need for protective actions once every hour if:
3.1.1 The Reactor Building radiation level is > 35 R/hr for
> 1 hour, or 3.1.2 EMF-36(L) is > 30,000 cpm for > 1 hour.
4.0 ENCLOSURES i 4.1 Clock and Meteorological Data Sheet 4.2 Reactor Building Data - Calculation Sheet 4.3 Unit Vent Data - Calculation Sheet 4.4 Protective Action Recommendation Work Shett 4.5 Limits and Precautions l l
CAVASBA NUCLEAR STATION RP/0/A/5000/11 ENCLOSURE 4.1
)
CLOCK AND METEOROLOGICAL DATA SHEET Unit Protective Actions Determined By
- 1. Clock Data ,
Time Now Date Now f Time of Reactor Trip Date of Reactor Trip Hours Since Reactor Trip i
- 2. Meteorological Data (from station EEB system or National Weather ServicehS]at 704-399-6000)
Wind Direction - Upper Tower degrees
- Lower Tower degrees
- NWS degrees Wind Speed - Lower Tower mph
- Upper Tower mph
- NWS mph i
Actual AT - Lower to Upper Tower 'C Assumed AT - Time now of 1000 to 1600 -0.4*C .
- Time now of 1600 to 1000 ;
with wind speed > 15 mph -0.1*C with wind speed 5 15 mph +1.3*C NOTE: Assumed AT is for use when EEB system is inoperable. AT is not available from NWS. I i= i
smEn@99EMY17EfR9M ! RP/0/A/50C0/11 i ENCLOSURE 4.2 REACTOR BUILDING DATA - CALCULATION SHEET !
- 1. Based upon hours since reactor trip, determine the Reactor Trip time factor (RTTF) from the table below and record.
Hours Since Reactor Trip RTTF 0.0 - 1.0 12 1.1 - 2.0 17 2.1 - 5.0 27 5.1 .10.0 42
> 10.0 N/A*
After 10 hrs. TSC will perform dose calculations.
- 2. Reactor Building Dose Rate (RBDR).
a) EMF-53A R/hr. EMF-53B R/hr. NOTE: Use the highest EMF reading in calculations. b) HP/0/B/1009/06 R/hr. 3. Calculate Time Determined Dose (TDT). TDT = RBDR x RTTF 4. Calculate Wind Determined Dose (WDD) based on Wind Speed (WS). WDD = TDT
- WS NOTE 1: Lower WS is preferred. If not available, use upper WS, then WS from National Weather Service.
NOTE 2: If WS $ 1 mph then use the value of 1,.
- 5. Go to Enclosure 4.4. !
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CATNWsA NUCLEAR STATION RP/0/A/5000/11 # ENCLOSURE 4.3 UNIT VENT DATA - CALCULATION SHEET
- 1. Unit Vent EMF Readings EMF-36(L) = cpm EMF-36(H) = cpm Unit Vent Flow Rate = cfm
- 2. Calculate Time Determined. Dose (TDT). If EMF-36(H) is < 100 cpm, calculate DT with Section 2.1. If EMF-36(H) is > 100 cpm, calculate DT with Section 2.2.
2.1 TDT = EMF-36(L) cpm x cfm x 6.4E-7 2.2 TDT = EMF-36(H) cpm x cfm x 4.3E-3
- 3. Calculate Wind Determined Dose (WDD) based on Wind Speed.
WDD = TDT + WS NOTE 1: Lower WS is preferred. If not available, use upper WS, the WS from National Weather Service. NOTE 2: If WS < 1 mph then use the value of 1.
- 4. Go to Enclosure 4.4.
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r_,.- . . . . . DUKE POWER COMPANY CATAWBA NUCLEAR STAT 10N RP/0/A/5000/11 ENCLOSURE 4.4 PROTECTIVE ACTION RECOMMENDATION WORK SHEET
- 1. - Based on WD0 and AT, determine distances and level of protective action from Tables 1.1 and 1.2 below. Circle AT, WDD and Protective Action Recommendation.
Table 1.1 0-5 Mile Radius Protective Action Recommendations ; l WDD Values AT: < -0.6 < 4.10E6 4.10E6 to 2.00E7 > 2.00E7
-0.6 to -0.5 1 1.10E5 1.10E5 to 5.50E5 > 5.50E5
-0.4 to -0.2 1 3.50E4 3.50E4 to 1.70E5 > 1.70E5
-0.1 to +0.4 1 2.00E4 2.00E4 to 1.00E5 > 1.00E5
+0.5 to +1.2 1 9.80E3 9.80E3 to 4.90E4 > 4.90E4
> +1.2 5 4.50E3 4.50E3 to 2.20E4 > 2.20E4 :
Consider Protective Action NO ACTION EVACUATION PARTICU- EVACUATE i Recommendations LARLY FOR CHILDREN EVERYONE AND PREGNANT WOMEN l 1 Table 1.2 5-10 Mile Radius Protective Action Recommendations WDD Values l l l AT: < -0.6 < 2.00E7 2.00E7 to 1.00E8 > 1.00E8
-0.5 to -0.4 1 1.80E6 1.80E6 to 9.20E6 > 9.20E6
- -0.4 to -0.2 1 4.10E5 4.10E5 to 2.00E6 > 2.00E6
{ -0.1 to +0.4 1 2.00E5 2.00E5 to 1.00E6 > 1.00E6
+0.5 to +1.2 1 7.90E4 7.90E4 to 3.90E5 > 3.90E5
. > +1.2 1 2.90E4 2.90E4 to 1.40E5 > 1.40E5 l Consider l
Protective Action NO ACTION EVACUATION PARTICU- EVACUATE Recommendations LARLY FOR CHILDREN EVERYONE AND PREGNANT WOMEN I
DUKE POSER COMPANY CATAWBA NUCLEAR STATION RP/0/A/5000/11 ENCLOSURE 4.4 PROTECTIVE ACTION RECOMMENDATION WORK SHEET 2.. Based on wind direction (WD), determine the affected zones from the tables below. Circle the wind direction and affected zones. NOTE: Upper tower wind direction is preferred. If not available, use lower WD, then use WD from National Weather Service. A. IF WIND SPEED IS < 5 MPH, THE AFFECTED ZONES ARE A-0 A-1, B-1, C-1, 0-1, E-1 and F-1. B. IF WIND SPEED IS > 5" MPH, SELECT THE AFFECTED ZONES FROM THE TABLES BELOW AS APPLICABLE. Table 2.1 Table 2.2 0-5 Mile Radius Affected 5-10 Mile Radius Affected i Wind Direction Zones Wind Direction Zones 0.1* - 360* A-0 PLUS 0.1' - 22' C-1, D-1 0.1 - 27' C-2, D-2 22' - 73* C-1, D-1, E-1 27' - 69* C-2, D-2, E-2 73' - 108* C-1, D-1, E-1, F-1 69' - 95* D-2. E-2, F-2 108* - 120' D-1, E-1, F-1 95* - 132' D-2, E-2, F-2, F-3 120' - 159' E-1, F-1 132' - 144* E-2, F-2, F-3 159' - 207* E-1, F-1, A-1 144' - 160* E-2, F-2, F-3, A-2 207* - 247* F-1, A-1, B-1 160' - 201' F-2, F-3, A-2 247' - 265* A-1, B-1 201' - 229' F-2, F-3, A-2, B-2 t 265* - 298* A-1, B-1, C-1 229* - 249* F-3, A-2, B-2 298' - 338' B-1, C-1 249' - 259' A-2, A-3, B-2 338' - 360' B-1, C-1, 0-1 259' - 290* A-2, B-2, C-2, A-3 290' - 304* A-3, B-2, C-2 304' - 333* B-2, C-2 333' - 360 B-2, C-2, 0-2
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_gg DUKE POWER COMPANY CATAWBA NUCLEAR STATION RP/0/A/5000/11 ENCLOSURE 4.5 LIMITS AND FRECAUTIONS
- 1. This procedure is to be used by Control Room Operations personnel only in !
the event the Operator Aid Computer is not ava'ilable to perform the l calculation of protective action recommendation and the Technical Support j Center is not activated. NOTE: This procedure is applicable only in the first 10 hours after the Reactor Trip.
- 2. This precedure is conservative in its ability to protect the public in that:
- a. A 45' wide plume is assumed with an additional 22h* on each side of the plume,
- b. Wind determined dose (WDD) has a built in margin of safety. !
- c. There are three sources of meteorological data:
- 1) EEB System upper and lower towers
- 2) National Weather Service at Charlotte Office of National Weather Service
- 3) Established data from CNS FSAR
- 3. All protective action recommendations relate to child thyroid dose protective action guides.
4 The ratio of I-131 eq. to Xe-133 eq. in the unit vent is assumed to be 9.74E-3.
- 5. The basis for the unit vent method is HP/0/8/1009/13, Offsite Dose Projection - Uncontrolled Release of Radioactive Material Through the Unit Vent.
- 6. 6.4E-7 and 4.3E-3 are unitiess constants which relate unit vent data to the WDD value tables used to determine protective action recommendations.
I 1 i I l l
Form 34731 (1041) (Formerly SPD 10021) DUKE POWER COMPANY (1) ID No:RP/0/B/5000/12 PROCEDURE PREPARATION Change (s) n to PROCESS RECORD 0 Incorp6 rated (2) STATION: CATAWBA (3) PROCEDURE TITLE: CONTROL OF ASSESSMENT AND REPAIR TEAfS (4) PREPARED BY: Mike Bolch DATE: Jan. 19, 1984 (5) REVIEWED BY: . DATE: I-d=ON Cross-Disciplinary Review By: N/R: v (6) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: By: Date: (7) APPROVED BY: W. Date: /- /i- 6 Y (8) MISCELLANEOUS: Reviewed /Apprcved By: _ Date: Reviewed / Approved By: Date: l l
-. _ _-.- - -. - - . ~ - _ _ - . - _ - .
RP/0/B/5000/12 DUKE POWER COMPANY CATAWBA NUCLEAR STATION CONTROL OF ASSESSMENT AND REPAIR TEAMS 1.0 PURPOSE 1.1 To provide a means for dispatching teams of station personnel during an emergency, to assess damage or repair a component or area. 1.2 To provide a means for maintaining the dispatched personnel's accountability and safety, including protection from radiological hazards. 2.0 PRECAUTIONS 2.1 The following personnel shall be notified prior to dispatching a team into the Auxiliary Building or Containment: 2.1.1 Shift Supervisor 2.1.2 Operations Supervisor (OSC) 2.1.3 HP Supervisor (OSC) 2.1.4 HP S&C Coordinator (TSC) 2.2 All personnel who are assigned to perform a task under emergency conditions shall be logged in and out, on Enclosure 4.1. 3.0 PROCEDURE 3.1 The Operations Supervisor or delegate in charge of the OSC shall maintain a notebook (Enclosure 4.1) of assignments and shall contact the person in charge of the assignment at 20 minute intervals. 3.2 A briefing of all assigned personnel shall preceed the dispatching of assessment and repair teams. The location of the briefing to be determined as appropriate to the situation. 3.2.1 A summary of the assignment shall be given in the briefing, as follows: A. Radiological hazards expected to be encountered will be discussed during the briefing by the Health Physics Supervisor. B. Types of protective equipment and clothing will be reviewed during the briefing and documented on Enclosure 4.1. 3.3 The HP Supervisor in the OSC shall insure that records of the radiation exposure of each team member are maintained.
RP/0/B/5000/12 Page 2 of 2 l 3.4 The HP Supervisor shall review all Enclosure 4.1's of this l procedure and Enclosure 5.14 of HP/0/B/1009/09 for computer entry of exposure upon completion of the emergency condition. l
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3.5 Exposure from the emergency shall be entered into the computer i under a RWP/SRWP that will be written after the emergency condition ; is over. i 4.0 ENCLOSURES 4.1 Team Personnel List O r 't J ) i 1
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RP/0/B/5000/12 ENCLOSURE 4.1 TEAM PERSONNEL LISTS Team Date Assignment Location
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Leader Bldg./El Number of Personnel Communication Mode: Parsonnel Assigned: a Telephone o Messenger o Radio Group Name HP Badge No. Time Out Time In 1. 2. 3. 4. 5. 1 6. Special Hazards to be considered: Radiological Other (specify) o Toxic Fumes or Gases o Fire o Electrical Equipment / Clothing required: o Anti-C's Other (specify) o Respirators 1 o SCBA o Fire Brigade Turnout Clothing a Camera o Tools o Ventilation o Lights o Portable Shielding o Radiological Monitoring
.3C Operations Supervisor Team Leader OSC HP Supervisor
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Form 34731 (1041) (Formerly SPD 10021) e DuxE rouIR cceWANT (1)- ID No: RF/0/3/5000/12 - PROCEDURE PREPARATION Charge a (s) n to FROCESS RECORD n Incorporated (2) STATION: CAT M i (3) FROCEDURE TITLE: COMEOL OF ASSESSMER AND REFAIR TEAMS PREFARED BT: Mike Bolch
- MTE: Nov. 07, 1983
($) (5) REVIEWED BY:_ m DATE: // 7
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j Cross-Disciplinary Review By: Idm8 N/R: ! (6) TEMPORARY AFFRONAL (IF NECESSARY): i i By: (sRO) Date: ., e By: . b Date: (7) AFFR07ED BT: .- M* ' " x , , Date: //
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- Reviewed / Approved By: Date:
! Reviewed / Approved By: Date: l l
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t RP/0/B/5000/12 4 DUKE POWER COMPANY .- CATAWBA NUCLEAR STATION
. CONTROL OF ASSESSMENT AND REPAIR TEAMS 1.0 PURPOSE 1.1 To provide a means for dispatching teams of station personnel during an emergency, to assess damage or repair a component or area, i -
1.2 To provide a means.for maintaining the dispatched personnel's accountability and safety, including protection from radiological i hazards. 2.0 PRECAUTIONS 2.1 This procedure shall be coordinated between the Shift Supervisor on duty, the Shift Supervisor and HP Supervisor in the OSC and the ' l Emergency Coordinator in the TSC. 2.2 All personnel who are sent out to perform a task under emergency . l conditions shall h logged in and out, on the appropriate form. 3.0 PROCEDURE J' 3.1 The Shift Supervisor in charge of the OSC shall mainta n a log of personnel assignments and shall contact the person in charge of the i assignment every minutes. i 3.2 A briefing of all assigned personnel shall proceed the dispatching of assessment and repair teams. 3.2.1 A summary of the assignment shall be given in the briefing,. 3.2.2 Personnel hazards expected to be encountered will be discussed during the briefing. 3.2.3 Types of protective equipment and clothing will be reviewed during the b.-iefing. * ! 3.3 A list of teams dispatched during emergencies will be maintained in both the TSC and the OSC. 3.3.1 The list shall include assignment, number of personnel, ! location and method of communication. 3.3.2 Communications checks will be made to each team at
. approximately - minute intervals.
! 3.4 The HP Supervisor in the OSC shall maintai~n records of the radiation exposure of each team member, , I
4eO ENCLOSURES 4.1 Team Assignments 9 4.2 Team Personnel List - e 6 4 i 3 e 9 e e t 9 e 9
ENCLOSURE 4.8 ASSESSMENT AND REPAIR TEAM ASSIGNMENTS - Date Team Leader Assignment Location Out In Number of Personnel Communication Mode . Record of Communication Checks: Date _ Team Leader Assignment Location Out In Number of Personnel Communication Mode : Record of Communication Checks: Date Team Leader Assignment Location Out In Number of Personnel - Communication Mode Record of Communication Checks: 6 0 r-- -- , - - - - ,, -- -- .m. - - , - - - . - - - - - - - - - - - - . - --- -
TEAM PERSONNEL LISTS Team . Date eignment Location
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Leader Bldg./El - Number of Personnel Communication Mode Persennel Assigned: Group Name HP Badge NO. Time Out Time In 1. 2 3. 4. 5. l 6. Special Hazt-ds to be considered: e 2. 3. Equipment / Clothing required: 1. 2. l 3. 4. 5. 6. OSC Supervisor Initial Team Leader Initial
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/ Form 34731 (10-81)
-(Formerly SPD 10021)
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i i DUKE POWER COMPANY (1) ID No:HP/0/B/1000/06 PROCEDURE, PREPARATION Change (s) n to - PROCESS RECORD 1 Incorporated ) (2) STATION: Catawba Nuclear (3) PROCEDURE TITLE: Dnercency Ecuitment Functional Check and Inventory (4) PREPARED BY: '/dm s / h p 1 DATE: J/ -h (5) REVIEWED BY: M7M DATE: 2 N Cross-Disciplinary Review By: N/R: J. 7 M (6) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: f By: . Date: (7) APPROVED BY: M Date: 1. (8) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: l e I i - O o I . ...... ... . -
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- DUKE POWER COMPANY CATAWBA NUCLEAR STATION EMERGENCY EQUIPMENT FUNCTIONAL CHECK AND INVENTORY 1.0 . PURPOSE To provide for the availability and readiness of Emergency Equipment.
2.0 REFERENCES
2.1 HP/0/B/1005/Of; Respirator Quality Assurance 2.2 Catawba Nuclear Station Directive 2.11.13 2.3 Catawba Nuclear Station Directiva 3.2.2 2.4 Cata.ba Nuclear Station Directive 3.3.3 2.5 Catawba Nuclear Station Emergency Plan 2.6 Catawba Nuclear Station Technical Spectifications 6.10 2.7 10CFR50 Appendix E r 2.8 NUREG 0041, Chapters 5 and 9 2.9 NUREG 0654 3.0 LIMITS AND PRECAUTIONS 3.1 Seat belts shall be utilized by each person oteupying.any Vehicle
- y. + used in an emergency situation.
/ 3.2 Operation of the Portable Alternator 3.2.1 Gasoline shall never be added while the engine is running hot. 3.2.2 Smoking, open flames or sparks shall not be-allowed in the vicinity of fuel handling. 3.2.3 Avoid operating the unit while hands are wet or while standing in water. 3.2.4 Never run the unit in an enclosed space (hazardous fumes given off). 3.2.5 Do not operate with'the air cleaner removed. t 3 p..
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HP/0/B/1000/06 Peg 2 2 of 7 3.2.6 Do not touch the muffler, exhaust piping or engine as f* - serious burns may result.
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3.3 Silver zeolite cartridges shall be discarded if the seal has been broken. 3.4 Any radiation monitoring equipment located in an emergency kit that must be removed from service for any reason shall be replaced within four hours from the time it is removed from the kit. 3.5 Any emergency kit used during training or for drill purpcses shall be reinventoried as soon as possible. The individual responsible for the training or drill shall be responsible for inventory and restocking of all onsite kits. 3.5.1 Off-site kits shall be reinventoried as above and a list of deviations shall be given to the Respiratory / Instrument Calibration (R/IC) Supervisor. R/IC shall be responsible } for restocking off-site kits as soon as possible. 4.0 PROCEDURE 4.1 Monthly Emergency Equipment Check / Inventory 4.1.1 Portable Generator Check f' 4.1.1.1 The operability of the generators shall be
,, checked monthly.
4.1.1.2 Operation of the Portable Generators NOTE: If at any time during the operation of the unit problems arise, notify the Health Physics Respiratory Supervisor. 4.1.1.2.1 Check the oil prior to starting. Make sure the unit is level and remove the oil filler plug. Oil level should be to the point of overflowing. Add oil if needed. Replace plug. 4.1.1.2.2 Add a small amount of non-leaded gasoline (leaded-regular'may be substituted). 4.1.1.2.3 Push choke lever all the way to the right. NOTE: Never start the' unit with equipment plugged in. .- t 4 s
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HP/0/B/1000/06 Pega 3 of 7 4.1.1.2.4 Hold generator carrying handle grip with one hand. Grasp rope start f , , handle with other hand and pull out sharply. Do not let starter rope snap back. 4.1.1.2.5 When engine starts return choke lever to the far left position and ensure the engine is running smoothly. 4.1.1.2.6 Plug a portable air sampler into one of the generator outlets and turn on the sampler. Allow the
. generator to stabilize. Unplug the sampler and plug into the other outlet and again allow the generator to stablize.
4.1.1.2.7 Unplug the air sampler and shut off the engine by holding the spark plug shorting lever fi m1y against the spark plug rubber boot until the engine comes to a complete stop. 4.1.1.2.8 Remove any remaining gasoline from 4"~ the gas tank. 4.1.1.2.9 Scart engine as per 4.1.1.2.4 and run until engine stops. 4.1.1.2.10 Document the operability check (i.e., malfunctions, no problems...) on the Emergency Equipment Check Log Sheet (Enclosure 5.1). 4.1.2 Monthly Communications Check 4.1.2.1 Two-Way Low-Band n! Radios 4.1.2.1.1 Radios shall be checked monthly. 4.1.2.1.2 Call the Technical Support Center (TSC) and notify Health Physics personnel that you plan to contact them using the Two-Way Low-Band FM Radios. Record the name of the person notified on the Emergency Equipment Check Log Sheet (Sample Enclosure 5.1). 4.1.2.1.3 Drive to the intersection of . highways 55 and 321 (located hi - Clover) and call the (TSC) using
\. the radio. Operate the radio according to the Duke Power Company Radio Operator's Manual.
HP/0/B/1000/06 Pegs 4 of 7 Radio call sign- KB-36274 (Alpha, je , ~ Bravo, Charlie, Delta, Echo, Foxtrot) Control Room (Base) call sign- KNHB 778 4.1.2.1.4 If contact is not made with the (TSC) using the radio, initiate corrective action (move to different location, insure TSC has radio on...). 4.1. 2.1. 5 Document the rcdio check on the
- Emergency Equipment Check Log Sheet (Enclosurs 5.1).
4.1.2.1.6 Inoperable radios shall be removed from service. Contact Toddville Communications Shop Planner for instructions on disposition for repair. 4.1.2.1.7 Notify the Health Physics Respiratory Supervisor of any deviations. 4.1.2.2 Weather Information Check r (_ 4.1.2.2.1 Every month a call shall be placed to the National Weather Service located in Columbia, SC at 803-794-2330 or 803-794-2593. If these two numbers cannot be reached, an alternate number in Charlotte (704-399-6000) may be used. Obtain wind direction, wind speed, and cloud cover from one of these sources for the vicinity of Catawba Nuclear Station. Obtain the same information from the Catawba Nuclear Station Control Room. 4.1. 2. 2. 2 Record this information on the Weathsr Information Form (Enclosure 5.2). 4.1.2.2.3 Compare the information from the Control Room and the Weather l Bureau. If differences are found greater than 22* in wind direction 'I and/or 50* in wind speed, notify ; the Health Physics Respiratory-Supervisor. - 4.1.3 Monthly Emergency Equipment Kits Inventory 4.1. 3.1 ~ Enclosure 5.3 gives a list of the locations of all Emergency Equipment Kits. y - -- w ,-e -
HP/0/B/1000/06 Pago 5 of 7 4.1.3.2 Each kit shall be inventoried monthly and after each use using the appropriate Emergency Equipment
, Kit Checklist (Enclosures 5.4 - 5.13).
4.1.3.2.1 Perform a battery and response check on all Radiation Monitoring Instruments located in the kit and insure the instruments are within the current calibration date. NOTE: Batteries shall not be stored in the instrument. After-completing check, remove batteries. 4.1.3.2.2 Perform a functional check of the dosimeter charger / reader, and insure that the leak and source check dates on the dosimeters are current. 4.1.3.3.3 Insure the calibration is current on the Canberra Series - 10 Portable MCA. 4.1.3.2.4 Check respiratory equipment as per f' Reference 2.1. 4.1.3.2.5 Insure that air samplers are within current calibration dates. 4.1.3.2.6 Insure that the TLD's are the appropriate ones for the current quarter. 4.1.3.2.7 Insure the the Potassium Iodide tablets have not exceeded their , expiration date. 4.1.3.2.8 Insure the seal on the silver zeolite cartridges packet is not broken. l 4.1.3.2.9 Insure that all procedures are up to date with the current Control Copy. 4.1.3.2.10 Check all batteries for strength. i 4.1.3.2.11 Upon completion of the inventory, the kit shall be secured with a tamper seal (s) to maintain the integrity of the kit until the next . use or inspection. ,\ l
1
^1 i
HP/0/B/1000/05 ' Pes) 6 of 7 l 4.1.3.2.12 If any deviations are found, describe f any deviations in the deviations section of the applicable Emergency Equipment Kit Checklist (Enclosures 5.4 - 5.13) and document the deviations in the Emergency Equipment Deviation Authorization Sheet 1 (Enclosure 5.14). l 4.1.3.2.13 Following completion of the kit inventory sign off the appropriate kit on the Emergency Kits Inventory Log Sheet (Enclosure 5.15). 4.1.4 Monthly Emergency Respiratory Inventory 4.1.4.1 Insure that all emergency Self Contained Breathing Apparatus (SCBA's) are available. LOCATIONS MINIMUM UNITS Control Room 2 Upper Personnel Hatch 2 Lower Persennel Hatch 2 Health Physics Respiratory Storage Area
-( ,_ 4.1.4.2 Insure that six large bottles (min. of six 8
hours use for 5 people) of breathing air are located in the Control Room along with 5 airline respirators and associated airline hoses. 4.1.4.3 Steps 4.1.4.1 and 4.1.4.2 shall be documented per Reference 2.1. 4.1.4.4 Any deviations shall be reported to the Health i Physics Respiratory Supervisor. l 4.2 Deviation Authorization 1 j 4.2.1 The Station Health Physicist shall be made aware of any deviation recorded on Enclosure 3.14. 4.2.2 The Station Health Physicist shall have evaluated the l consequences the deviation may have upon the capability to respond to an emergency situation. 4.2.3 Enclosure 3.14 shall be used to state the action taken to l remedy the deviation, and to state the justification for l taking that action. 1 4
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HP/0/B/1000/06 Pegs 7 cf 7 4.2.4 Sign off the PT printout and forward as per Reference 2.3.
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, 4.3 Upon completion of this procedure all required documentation will be filed in the Emergency Equipment Functional Check and Inventory Log.
5.0 ENCLOSURES 5.1 Sample of Emergency Equipment Check Log Sheet 5.2 Sample of Weather Information Form 5.3 Sample of Emergency Equipment Kits and Locations 5.4 Sample of Recovery Kit Checklist 5.5 Sample of Environmental Survey Kit Checklist 5.6 Sample of Environmental Survey Kit Checklist (Helicopter) 5.7 Sample of Personnel Survey Kit Checklist j 5.8 Sample of Personnel Survey Kit Checklist (Evacuation Facility) 5.9 Sample of Medical Decontamination Kit Checklist
/~' 5.10 Sample of Medical Decontamination Kit Checklist (Piedmont Medical
,, Center) 5.11 Sample of Operations Support Center Kit Checklist 5.12 Sample of Technical Support Center Kit Checklist 5.13 Sample of Fuel Transfer Kit Checklist 5.14 Sample of Emergency Equipment Deviation Authorization Sheet 5.15 Sample of Emergency Kits Inventory Log Sheet i
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T E E l i i r S o i N C t O O IO c I T L R D A 0 A A K l R e T C v S R C E H Wts N ri D N A i t c A E e D e T T G m - r L N m W r C E E o O o U M L C L C N P 8 I A Y A U T A H Q R W-W E O 4 P O T Y W A 0 I C N e E d G a R M E M t E c e t i r o C r e b m u N e v r a t o lS a r l o i l r e a C G i o d a R 4 e e . t t a a D D
CATAWBA NUCLEAR STATION WEATHER IhTORMATION HP/0/B/1000/06 ENCLOSURE 5.2 p..
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National Weather Service Control Room Wind Direction Wind Speed 1 Cloud Cover Time Comparison difference: Wind Direction degrees Wind S;'eed . (L Signature /Date i 4 o N k T
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CATAWBA NUCLEAR STATION EMERGENCY EQUIPMEYr AND LOCATIONS HP/0/B/1000/06 ENCLOSURE 5.3 t' KITS LCCATION Recovery Kits (4) Allen Steam Station See.tity PAP Temp. Admin. Bldg. Transmission Line Maint. Bldg. Environmental Survey Kits (Vehicle) (4) Aux. Blds. Rm 517-B Environmental Survey Kits (Helicopter) Aux. Bldg. Rm 517-B Personnel Survey Kits (4) Construction Personnel Temp. Admin. Bldg. access area (Brass Gate) PAP Area Security Pap Evacy tion Facility (2) Transmission Line Maint. Bldg. Allen Steam Station Medical Decontamination Kit (2) Aux. Bldg. First Aid Room (' Piedmont Medical Center Operations Support Center Kit . Operations Support Center Technical Support Center Kit Technical Support Center Fuel Transfer Kit Temp. Admin. Bldg. t a i J O
- - , - - - ,,-,.y_ ,. ,,y,._.- -- - .- w ,
CATAWBA NUCLEAR STATION RECOVERY KITS CHECKLIST HP/0/B/1000/06 ENCLOSURE 5.4
/'
ITEM AMOUhT DEV.* List of Contents 1 Eberline E-520 w/HP-270 Probe 1 Exempt Source 1 Low /High Range Dosimeters (0-500 mR), (0-5R) 2 each Dose Cards 25 TLD Badges 6 Dosimeter Charger ,, 1 Boundary Ribbon or Rope (50 yd. roll) 1 Masking Tape (roll) 1 Rain Suits (set) 2 Protective Clothing (set) 2 Poly Bass (Various) 12 Caution Signs w/ inserts 2 Legal Pad 1 Instrument / Smear Survey (pad) 1 Pens 2 Grease Dancil 1 Full Face Respiratior With High Efficiency Filters 2 First Aid Kit 1 i Potassium lodide Tablets 'Irans. Line Maint. 275 bottles Security PAP 150 bottles f Temp. Admin. Bldg. 150 bottles
~ Allen Steam Station 275 bottles KI Distribution Data Sheet 100 Smears (box) 1 NuCon Smears 30 Flashlight 1 Batteries 4 Scissors 1 Small Sample Bottles Trans. Line Maint. 100 Security PAP 60 Temp. Admin. Bldg. 60 t
Allen Steam Station 100 HP/0/B/1003/12 1 HP/0/B/1009/16 1 This Kit has been inventoried and Steps 4.1.3.2.1 through 4.1.3.2.12, if applicable, have been completed. Signature /Date
*Any Deviations will be documented on the Emergency Equipment Deviation Authorization Sheet (Sample Enclosure 5.14).
s
Paga 1 cf 2 CATAWBA NUCLEAR STATION ENVIRONMENTAL SURVEY KITS CHECKLIST HP/0/B/1000/06 r ENCLOSURE 5.5 ITEM AMOUNT DEV.* List of Contents 1 Eberline E-520 w/HP-270 Probe 1 Eberline E-140N w/HP-210 Probe (or equivalent) 1 Exempt Source 1 Portable MCA** 1 Eberline PIC 6A 1 Emergency Radio Transmitter / Receiver 1 Radeco H809V Air Sampler 1 Gasoline Generator (Gasoline in Safety Cabinet) 1 Low /High Range Pocket Dosimeter (0-500 mR), (0-5R) 2 each Dose Cards 25 TLD Badge 6 Dosimeter Charger 1 Full Face Respirator With High Efficiency Filter 2 Potassium Iodide Tablets (bottle) 2 Protective Clothing (Full Set) 3 Poly Bags (Various Sizes) 6 Masking Tape (roll) 1 Limnological Sampler 1 (~ ' Cubitainers 6 1 Liter Wide Mouth Bottles 5 Stopwatch 1 Flashlight i Batteries 4 Silver Zeolite (CP-100G or GY-130) Filter Cartridges and Particulate Filters 30 Filter Cartridges Labels & Bags 100 Smears (box) 1 Nucon Smears 30 Instrument / Smear Survey (pad) 1 Map of Ten Mile Zone Sectors 1 Legal Pad 1 Pen 2 Hand Spade 1 Grease Pencil and refills 1 Dime Roll' 1 Scissors 1 Rain Suits 3 Telephone location maps 1 Field Monitoring Data Sheet 20 Field Monitoring Work Sheet 20
'KI Tablet Distribution Data Sheet 1 Radio Operator Manual 1 CPD1 Key 1 HP/0/B/1009/04 1 .
Pago 2 of 2 CATAWBA NUCLEAR STATION ENVIRONME WAL SURVEY KITS CHECKLIST HP/0/B/1000/06 f, ENCLOSURE 5.5 ITEM AMOUNT DEV.* HP/0/B/1009/16 - 1 HP/0/B/1003/02 1 HP/0/B/1003/05 1 HP/0/B/1003/12 1 HP/0/B/1003/17 , 1 HP/0/B/1009/19 1 HP/0/B/1003/31 or HP/0/B/1003/11 1 This Kit has been inventoried and Steps 4.1.3.2.1 through 4.1.3.2.12, if applicable, have been completed. Signature /Date
*Any Deviat.ons will be documented on the Emergency Equipment Dev.'ation Authorization Sheet (Sample Enclosure 3.14).
**This instrument is stored in the Health Physics Instrument Issue Area.
L i
V CATAb'BA NUCLEAR STATION 5
,. ENVIRONMENTAL SURVEY KITS CHECKLIST (llalictpter) c HP/0/B/1000/06 ENCI45URE 5.6 ITEM AMOUNT DEV.*
List of Contents 1 Eberline PIC-6A 1 Eberline E-520 w/HP-270 Probe 1 Exempt Source 1 Low /High Range Pocket Dosimeter (0-500 mR), (0-5R) 2 each Dose Cards 25 Field Monitoring Data Sheet . 20 TLD Badge 6 Dosimeter Charger 1 Full Face Respirator with High Efficiency Filter 2 Potassium Iodide Tablets (bottle) 2 KI Distribution Data Sheet 1 Stopwatch 1 Flashlight 1 Batteries 4 Map of Ten Mile Zone Sectors 1 Legal Pad 1 Pan 9 Rain Suits 2 Instrument / Smear Survey (pad) 1 Emergency Radio Transmitter / Receiver 1 F HP/0/B/1003/05 1 HP/0/8/1003/12 1 HP/0/B/1009/19 1 HP/0/8/1009/04 1 HP/0/B/1009/16 1 This Kit has been inventoried and Steps 4.1.3.2.1 through 4.1.3.2.12, if applicable, have been completed. Signature /Date -
\
*Any Deviation will be documented on the Emergency Equipment Deviation Authorization Sheet (Sample Enclosure 5.14).
e CATAWBA NUCLEAR STATION PERSONNEL SURVEY KITS CHECKLIST HP/0/B/1000/06 ENCLOSURE 5.7 C ITEM AMOUNT DEV.* List of Contents 1 Eberline E-140N w/HP-210 Probe (or equivalent)*** 3 Sample Slide Tray *** 1 Exempt Source 1 Emergency Radio Transmitter / Receiver ** 1 Radio Operator Manual 1 Low /High Range Dosimeters (0-500 mR/hr), (0-5 R/hr) 2 each Dose Cards 25 TLD Badges 2 Dosise er Charger 1 Full Face Respirator With High Efficiency Filter 2 Potassita Iodine Tablets (bottle) 2 KI Distribution Data Sheet 1 Protective Clothing (Full set) 6 f.oundary Ribbon or Rope (50 yd. roll) 1 Caution Signs w/ inserts 4 Masking Tape (roll) 1 Poly Bags (Various) 6 Smears (box) i NuCon Smears 25 Instrument /3mear Survey (pad) 1 { v Pens Grease Pencil & Refills 2 1 Legal Pad 1 Scissors 1 Rain Suits 3 Decon Kit i Station Directive 3.8.3 1 HP/0/B/1003/31 or HP/0/B/1003/11 1 HP/0/B/1004/06 1 HP/0/B/1009/05 1 HP/0/B/1009/16 1 HP/0/B/1009/19** 1 This Kit has been inventoried and Steps 4.1.3.2.1 through 4.1.3.2.12, if applicable, have been completed. Signature /Date
*Any Deviation will be documented on the Emergency Equipment Deviation Authorization Sheet (Sample Enclosure 5.14). . **0nly the Construction Personnel access area shall have an Emergency Radio and procedure. ***0nly the PAP Area shall have (3) E-140N w/HP-210 Probe and Sample Slide Tray.
CATAWBA NUCLEAR STATION PERSONNEL SURVEY KITS CHECKLIST (EVACUATION FACILITY) HP/0/B/1000/06 ENCLOSURE 5.8 ITEM AMOUNT DEV.* List of Contents 1 Eberline E-140N w/HP-210 Probe (or equivalent) 3 Exempt Source 1 Low /High Range Dosimeters (0-500 mR), (0-5R) 4 each Dose Cards 25 TLD Badges 4 Dosimeter Charger 1 Potassius Iodide Tablets (bottle) 2 KI Tablet Distribution Data Sheet, 1 Small Sample Bottles 3 Protective Clothing (Full Set) 6 Boundary Ribbon or Rope (50 yd. roll) 1 Caution Signs w/ inserts 4 Masking Tape (roll) 1 Poly Bass (Various) 6 Smears (box) 1 Instrument /Seear Survey (pad) 1 , Pens 2 Grease Pencil & Refills 1 Legal Pad 1 F Decen Kit 1 Scissors 1 Disposable Coveralls 40 Station Directive 3.8.3 1 Evacuation Personnel Dose Record 50 ~ HP/0/B/1003/31 or HP/0/B/1003/11 1 HP/0/B/1004/06 1 HP/0/B/1009/05 1 HP/0/B/1009/16 i This Kit has been inventoried and Steps 4.1.3.2.1 through 4.1.3.2.12, if
- applicable, have been completed.
Signature /Date
*Any Deviation will be documented on the Emergency Equipment Deviation Authorization Sheet (Sample Enclosure 5.14).
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CATAWBA NUCLEAR STATION MEDICAL DECONTAMINATION KITS CHECKLIST HP/0/B/1000/06 ENCLOSURE 5.9 r ITEM AMOUNT DEV.* List of Contents i Eberline E-140N v/HP-210 Probe (or equivalent) 1 Exempt Source
- 1 -
Poly Bass 20" x 40" 2 Poly Bass 12" x 18" 4 Seears (box) 1 Nucon Seears - 25 Protective Clothing (Full Set) 4 Rain Suits 2 Tape, Radioactive Material 1 Tape, Masking 2" 1 Tape, Duct 2" 1 Instrument / Smear Survey (pad) 1 Pens 2 Legal Pad 1
~
Caution Signs w/ inserts 3 Radioactive Material Tags 50 Scissors 1 Poly for Ambulances (bundles) 3 Protective Clothing for Ambulance Drivers (Sots) 2 HP/0/B/1003/31 or HP/0/B/1003/11 ( HP/0/B/1004/06 1 1 y HP/0/B/1009/08 1 1 This Kit has besn inventoried and Steps 4.1.3.2.1 through 4.1.3.2.12, if applicable, have been completed. Signature /Date ,
*Any Deviatien will be documented on the Emergency Equipment Deviation Authorization Sheet (Sample Enclosure 5.14).
i .. l l 1 l
CATAWBA NUCLEAR STATION MEDICAL DECONTAMINATION KITS CHECKLIST PIEDMONT MEDICAL CENTER HP/0/3/1000/06 ENCLOStlRE 5.10 7 .. ITEM AMOUNT DEV.* List of Contents 1
. Eberline E-520 w/HP-270 Probe 1 Eberline-E-140N W/210 Probe (or equivalent) 1 Exempt Source 1 Poly Bass 20" x 30" 10 Poly Bass 12" x 18" 4 Smears (box) i NuCon Smears 25 Tape Radioactive Material 1 Tape, Masking 2" 2 Tape, Duct 2" 2 Instrument / Smear Survey (pad) 1 Caution Signs w/ inserts 5 Rad Rope 1 TLD Badges 10 Pocket Dosimeters (0-500mR) 10 _
Dose Cceds 25 Dosimeter Charger 1 Radioactive Material Tags 50 Floor and Vent Covering i f Disposable Coveralis 25
,, Disposable Shoe Covers (pairs) 25 Cubitaners 5 Decen Kit 1 Cotton Gloves (pairs) 50 Rubber Gloves (pairs) 20 HP/0/B/1003/31 or HP/0/B/1003/11 1 1 HP/0/B/1003/12 1 1 HP/0/B/1004/06 1 HP/0/B/1009/08 1 This Kit has been inventoried and Steps 4.1.3.2.1 through 4.1.3.2.12, if applicable, have been completed.
Signature /Date
*Any Deviation will be documented on the Emergency Equipment Deviation Authorization Sheet (Sample Enclosure 5.14).
\
CATAVBA NUC2. EAR STATION OPERATIONS SUPPORT CESTER KITS CHECKLIST MP/0/8/1000/06 ENCLOSt1tE 5.11 o-ITEM AHOUNT DEV.* List of Contents 1 Protective Clothing (Set) 40 Full Face Respirators with High Efficiency Filters 10 Flashlights 11 Batteries 34 Eberline PIC 6A 5 E-140N w/HP-210 Probe (or equivalent) 1 Exempt Source 1 Camera (Polaroid) 1 Polaroid Film Paes 2 Masking Tape (Roll) 2 Dosimeters (0-100R), (0-SR) 5 Dose Cards 25 Dosimeter Charger 1 Small Sample bottles 10 Rain Suits 5 Poly Bass 20 Radeco H809V Air Sampler 3 Silver Zeollte (CP-100G or GY-130) Filter Cartridges and Particulate Filters 30
,,.. Filter Cartridge Labels 30 f Potassium Iodide Tablets (bottle) 20
-. KI Distribution Data Sheet 10 HP/0/B/1003/02 1 HP/0/8/1003/05 1 HP/0/B/1003/31 or HP/0/B/1003/11 1 HP/0/B/1004/06 1 OSC Respcase Personnel Dose Record 25 Decon Kit 1 Instrument / Smear Survey (pad) 1 Telephone 2 Post-Accident Containment Air Sampling Equipmont Kit 1 Pen 2 Grease Pencil (and refill) 1 This Kit has been inventoriod and Stops !. 1.3.2.1 through 4.1.3.2.12, if applicable, have been completed.
Signature /Date
*Any Deviation will be documented on the Emergency Equipment Deviation -
, Authorization Sheet (Sample Enclosure 5.14).
A ___ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _____.__.__.______.___.______._________._______.__________________.______.________;
CATAVBA NUCLEAR STATION TECHNICAL SUPPORT CENTER KIT CHECKLIST HP/0/3/1000/06 ENCLOSURE 5.12
/
. ITEM AMOUNT DEV.*
List of Contents 1 Protective Clothing (Set) 20 Full Face Respirators with High Efficiency Filters 6 . Eberline E-520 w/HP-270 Probe 1 Eberline PIC-6A 3 E-140N w/HP-210 Probe (or equivalent) 1 Exempt Source 1 Radeco H809V Air Sample i Dosimeter (0-100R), (0-5R) 6 each Dose Cards 25 Silver Zeolite (CP-100G or GY-130) Filter Cartridges and Particulate Filters 25 Filter Cartridge Labels 25 Dosimeter Charger 1 Potassium Iodide Tablets (bottle) 25 Boundary Ribbon or Rope (50 3d. roll) 1 Caution Signs w/ inserts 3 Rad Tape 2 Smears (box) 1 Poly Bags 6 Masking Tape (Roll) 1
.I Pen 2
_ Legal Pad 1 Greasi Pencil 1 Flashlights a Batteries 30 Small Sample Bottles 10 Rain Suits 6 Decon Kit i Instrument / Smear Survey (pad) 1 Aux. Blds. Drawings (set) 1 HP/0/B/1003/02 1 HP/0/8/1003/05
- 1 HP/0/B/1003/12 1 HP/0/B/1009/16 1 HP/0/8/1003/31 or HP/0/B/1003/11 '
1 HP/0/B/1004/06 i This Kit has been inventoried and Steps 4.1.3.2.1 through 4.1.3.2.12, if applicable, have been completed. Signature /Date ,,
' *Any Deviation will be documented on the Emergency Equipment Deviation Authorization Sheet (Saeple Enclosure 5.14).
Pass 1 ef 2 r CATAWBA NUCLEAR STATION i FUEL TRANSFER KIT CHECKLIST NP/0/3/1000/06
/' ENCIASURE 5.13 ITEM AMOUNT DEV.*
i List of Contents 1 Shoe Covers: disposable (pair) 20
' rubber (Pair) 6 Gloves disposable (bundle). 1 surgeons (box) 1 rubber (pair) 6 Covera 11st disposable 4 cloth 6 Moods 4 Wet Suit 2 Mard Hat 3 Full Face Respirators with Nish Efficiency Filters 2 Radeco N809V Air Sampler 1 Eberline E-140N w/NP-210 Probs (or equivalent) 1 Eberline PIC-6A 1
- Eberline E-320 w/NP-270 Probe 1 Exeert Source 1 Silver Zeolite Cartridges and Particulate Filters 10 Labels for Filters and Cartridges ' 10
[, Potassium Iodide Tablets (Bottle) 30
.. TLD Badge and Dose Record Card 5 Low /N'sh Range Dosimeter (0-500 mR), (0-5R) 5 each Dose l,ard 25 Dosineter Charger 1 Weather-Proof Caution Signs with Inserts 4
( Radiosevive Waste Signs (4" x 6") 12 l Caution: Radiatit.,n/ Radioactive Material Tags 12 50 yd. Roll of Barricade Tape (Magenta & Yellow) 4 Step Off Pads 3 Poly lags (20" x 40") 12 __ Nand Gardening Spade 1 Wide ~ Mouth Sample Bott1ss 4 Plastic Sample lottles 12 Kiswipes (bok) . 2 Nucon Seears 100 Copy of NAC-1 Drawings (Prints) 1 Copy of Loading and Unloading Instructions 1 - Duct Tape (Roll) 2 Masking Tape (1" and 2" Rolls) 1 Contact Pyroseter with Probe 2 Safety Glasses 5 Binoculars 1 Tool Kit 1 Batteries (9 Volt) 2 Flashlights 2 Batteries 4 e
\. Steno Fad with 2 Mechanical Lead Pencils 1 Pencil Refills 1 E__-___-___--_-- --L----------------- - - - ^ ^ - ~ ^ - - ^^ ^ ^^^^ ^
r PCs3 2 ef 2 CATAWBA NUCLEAR STATION FUEL TRANSFER KIT CHECKLIST HP/0/5/1000/06 p ENCLOSURE 5.13 ITEM AMOUNT DEV.* Grease Pencils 2 All Purpose Marker 2 Scotch Tape Roll and Dispenser i Roll of Dimes 1 Gasoline Generator (Gasoline Stored in Safety Cabinet) 1 Instrument /Seear Survey (pad) 1
- HP/0/B/1003/02 1 i HP/0/B/1003/05 1 i HP/0/B/1003/12 1 l HP/0/B/1009/16 1 l HP/0/3/1003/31 or HP/0/3/1003/11 c.
l This Kit has been inventoried and Steps 4.1.3.2.1 through 4.1.3.2.12, if applicable, have been completed. , Signature /Date
*Any Deviation will be documented on the Emergency Equipment Deviation Authorization Sheet (Sample Enclosure 5.14). ,
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Form 34731 (1H1) (7 ormerly SPD.10021)
. DUKE POWER COMPANY (1) ID No: HP/0/8/1009/01 PROCEDURE PREPARATION Chanse(s) O to PROCESS RECORD 0 Incorporated (2) STATION: Catawba (3) PROCEDURE TITLE: Health Physics Recovery Plan (4) PRDARED BY: d4 e DATE: 9h6/fl (5) REVIEWED BY: DATE: TJ Cross-Disciplinary Review By: N/R:
(6) TEMPORARY APPROVA1,(IF NECESSARY): By: (SRO) Date: By: Date: (7) APPROVED BY: b Tu k-ka -8'5 (8) MISCELLANEOUS: Mate: Reviewed / Approved By: Date: Reviewed / Approved By: Date: i 1 l L )
HP/0/5/1009/01 DUKE POWER COMPANY CATAWBA NUCLEAR gTATION HEAL 71 PHYSICS RECOVERY PLAN 1.0 PURPOSE 1
, 1.1 This procedure provides a general recovery plan for Health Physics following a notification of Unusual Event, Alert, Site Area Emergency, or a General Eswrgency.
1
2.0 REFERENCES
2.1 NUREG-0654 2.2 Catawba Emergency Plan 2.3 System Lealth Physics Manual i 3.0 LIMITS AND PRECAUTIONS 3.1 This procedure is not intended to anticipate all conditions that may be encountered in an emergency situation, but to address the general principles for developing a plan of action. i 3.2 Use appropriate Health Physics procedures. i 3.3 Comply with all s'tstion exposure and contamination lief ts and ALARA principles.
- 3.4 The station recovery phase will be carefully planned by Duke Power Company managesent with input from the appropriate government agencies.
3.5 On completion of recovery operations, ensure proper documentation of the accident and include all pertinent data involving the incident and recovery operation. i 4.0 PROCEDURE
- 4.1 The initial re-entry into the affected area vill be conducted by Health Physics personnel to evaluate radiological hazards and contamination levels.
4.2 The Health Physics recovery operation may proceed, after completion of 4.1, in accordance with the following case examples l 4.2.1 CASE "A" - General emergencies that have resulted in the spread of contamination, evacuation of an area of the station, injured personnel or a change in the operating status of the station.
4.2.1.1 Th3 Stction Manrg:r, St: tion Group Super-intendents, Station Health Physicist and his staff, the Recovery Manager at the Crisis Management Center and any other offsita agencies who say be involved will decide what procedures and precautions will be taken in the recovery . plan. 4.2.1.2 Review all available radiation survey data. l Determine station areas potentially affected by l radiological hazards. l i 4.2.1.3 Review radiation exposure history of all personnel scheduled to participate in the recovery operations. Determine the need for additional personnel. i 4.2.1.4 Review the adequacy of radiation survey I equipment available. Determine the need for additional equipment and a source of procurement. ! 4.2.1.5 Pre-plan survey team activities, including areas to be surveyed, anticipated radiation levels, survey equipment required, protective clothing requirements, access control procedures, exposure control procedures and communication ,, capabilities.
. 4.2.1.6 Health Physics will, during subsequent re-entrics, will conduct comprehensive radiation surveys of station facilities and define all radiological probles areas.
4.2.1.7 Perform visual inspection of station areas and equipment. , 4.2.1.8 All radiolog(cal conditions discovered and j existing in the facility as determined by the re-entry surveys will be evaluated by station
- management.
, 4.2.1.9 Upon evaluation of the radiological conditions, station management will determine what i procedures are required to restore the site to a , normal status. 4 1 l t
, v.. . , . - . . - - r -,, ,,,--.e - - - . .-- - ~ - - - - . - - , - - - - - - . . . - . - , - - - - - . - -- -- -.,- ..+- .-
Paga 3 of 3 4.2.1.10 Emergency Coordinators will take approprist's actions to insure that emergency personnel and equipment leaving the Radiation Control Area
, are within contamination and exposure limits, that radiological conditions at the scene of the emergency are properly defined, barricaded, and posted with appropriate signs.
4.2.1.11 The Station Manager, Station Group Super-intendents, and Station Health Physicist will
- make all necessary decisions to return the unit to normal status and to prevent a recurring i p'roblem.
4.2.2 CASE "B" - Site Area Emergencies that have resulted in the evacuation of a station area, the spread of contamination, and/or change in the operating status of the station. 4.2.2.1 The Station Manager Group Superintendents and Station health Physicist will make decisions related to their areas of responsibility to recover and normalize any affected areas. All paragraphs of CASE "A" may also be applicable for unit emergencies. 4.2.3 CASE "C" - Alert conditions or notification of Unusual Events that may have resulted in the spread of contamination, unsafe conditions, and/or evacuation of an area due to noxious gases being present. . 4.2.3.1 The Station Managor, Station Health Physicist, Station Safety Supervisor and Station Chemist , will make decisions related to their areas of responsibility to recover and normalize any affected areas. Applicable paragraphs of CASE "A may become pertinent in this case. 4.3 Formal reporting of the emergency and recovery shall be completed as required by the Duke Power Company Steam Production Department
- Administrative Policy Manual for Nuclear Stations.
5.0 ENCLOSURES N/A l l l l l
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Form 34731 (1041) ' (Formerly SPD 10021) j ID No HP/0/B/1009/03 l DUKE POWER COMPANY (1) PROCEDURE PREPARATION Change (s) O to l PROCESS RECORD 1 Incorporated (2) STATION: Catawba (3) PROCEDURE TITLE: Environmental Surveillance Followina A Primarv To Secondary leak - , O ~ (4) PREPARED BY-w- -
_ DATE: [ 20!cfd
! r (5) REVIEWED BY: dJ2 Jf ,/, (\
( ) DATE: //fo //] Cross-Disciplinary Raview By: N/R:_ / p A,( (6) T1!MPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: By: Date: (7) APPROVED BY: - Date: h (8) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: U h
HP/0/5/1009/03 DUKE POWER COMPANY
- CATAWBA NUCLEAR STATION ENVIRONMENTAL SURVEILLANCE FOLLOWING A PRIMARY TO SECONDARY LEAK 1.0 PURPOSE This procedure describes the mann~r e in which Health Physics personnel will
- monitor and account for the release of radioactivity to.the environment due to a primary to secondary leak.
2.0 REFERENCES
2.1 ,10CFR20 2.2 10CFR50 2.3 CNS Technical Specifications 2.4 HP/0/B/1000/02 - Ta'aing, Counting, and Recording Surveys 2.5 HP/0/B/1001/02 - Sample Preparation for Counting Room Equipment 2.6 HP/0/B/1001/12 - Gaseous Waste Sampling and Analysis 2.7 HP/0/B/1001/13 - Liquid Waste Sampling and Analysis 2.8 HP/0/B/1009/11 - EMF Loss 2.9 HP/0/B/1004/04 - Request for Liquid Radioactive Waste Release i 2.10 HP/0/B/1004/05 - Request for Gaseous Waste Release 3.0 LIMITS AND PRECAUTIONS 3.1 Insure that all controlled releases are within limits required in references 2.1, 2.2, and 2.3. 3.2 Sampling and batch releases shall be terminated when radioscrivity identified in two consecutive samples is below 10CFR20 limits and counted to the lower limit of detection (LLD) for principal samma emitters listed in Technical Specifications Table 4.11-1 and secondary activities have fallen below levels set in Section 4.0 of this
- procedure. '
4.0 PROCEDURE' l l 4.1 Upon notification that the Condersate Steam Air Ejectors (C.S.A.E.) { off gas-E!1F #33 has alarmed indicating a primary / secondary leak: ) l , i l ! l
I n?!UiniluGl c: i Pcg2 2 of 3 , i 4.1.1 The Health Physics Shift Technician on duty shall initiate the C.S.A.E Sample Log (See Sample Enclosure 5.1) and the Turbine Building Sump Sample Log (See Sample Enclosure 5.2). This form shall continue to be used until terminated under the direction of the station Health Physicist when
- requirements in 3.2 are met, unless the indicated activity is due to EMF malfunction.
4.1.2 The Health Physics Shift Technician on duty shall collect a 3500 al liquid sample from the T.B. sump .and a 4400 ml gaseous sample from the C.S. A.E. using new Harinelli beakers. The samples shall then be submitted to the Counting Room per references 2.o and 2.7 for analysis. ) 4.1.3 If the sample results find no not radioactivity above background, refer to reference 2.8. 4.1.4 If the C.S.A.E. sample results indicate net radioactivity j above background, but the T.B. sump EMF 31 does not alarm l and activity is below 10CFR20, Appendix B, Table II, ' Column II limits, sampling frequency shall be as stated for the following secondary side radioactivity levels. Notify Operations and Chemistry per C.S.A.E Sample Log (Sample Enclosure 5.1). i 4.1.4.1 When secondary side activity samples range between .005 uCi/gm and .01 pCi/gm of the I-131 equivalence, C.S.A.E. samples shall be collected once every eight (8) hours, and T.B. sump samples shall be collected once avery twenty-four (24) hours. 1 4.1.4.2 Whan secondary side activity samples are ' greater than .01 uCi/gm but less than or equal to .03 pCi/gm of the I-131 equivalency, then the C.S.A.E. samples shall be collected once every eight (8) hours, and the T.B. sump samples shall be collected once every twelve (12) hours. 4.1.4.3 When' secondary side activity samples are greater than .03 vCi/gm of the I-131 equivalency, the C.S. A.E. samples shall be collected once every four (4) hours and the T.B. sump sample shall be collected once every eight (8) hours. l 4.1.5 If the C.S.A.E. sample results exceed 10CFR20, Appendix B, Table II, Column I limits, the Health Physics Shift Technician on duty shall initiate reference 2.10. 4.2 Upon notification that the T.B. sump - E}!F 31 has alarmed, indicating a primary / secondary leak: i I i l
7 stro UJ Dr LU%'JJ Us Paga 3 of 3 4.2.1 The Health Physics Shift Technician on duty shall initiate the T.B. Sump Sample Log. (See Sample Enclosure 5.2.) This t' ora shall continue to be used until terminated under the direction of the Station Health Physicist when . requirements in 3.2 are set unless the indicated activity , is due to EMF malfunction. 4.2.2 The Health Physics Shift Technician on duty shall collect a 3500 m1 liquid sample using a new Marinelli beaker. The sample shall then be submitted to the Counting Room per reference 2.7. NOTE: If T.B. sump sample results indicate not activity above background and ENF-33 is out of service, refer to 4.1.2. 4.2.3 If the T.B. sump sample results indicate no not activity above background, refer to reference 2.8. 4.2.4 If the T.B. sump sample results indicate not radioactivity above background, notify Operations and Radwaste Chemistry per T.B. Sump Sample Log (Sample Enclosure 5.2). 4.2.4.1 Chemistry shall notify Health Physics Shift Technician on duty of any releases to be made. 4.2.4.2 For any liquid releases, refer to references , 2.7 and 2.9. 4.2.4.3 Sampling frequency of WC hixing and Settling l Pond and of groundwater drainage shall be determined by Health Physics shift supervision. 4.2.4.3.1 The samples shall be collected in a l new liquid Marinelli beaker and submitted to the Counting Roca per references 2.5 and 2.7. 5.0 ENCLOSURES , 5.1 Sample Enclosure C.S.A.E. Sample Log 3.2 Sample Enclosure T.B. Sump Sample Log
Pags 1 of 2 DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/03 SAMPLE ENCIASURE 5.1 C.S.A.E. SAMPLE LOG This form is to be used any time a primary to secondary leak is indicated. i t l l
- l. Upon notification from Operations that a primary to secondary leak is l; indicated per Condensate Steam Air Ejector (EMF-33), record the following:
i Operations Rep. Date/ Time / H.P. Rep. Receiving Call
- 2. Unit #
Remarks:
- 3. If C.S.A.E. Sample results indicate not radioactivity above background, notify:
Radvaste Chemistr Rep. Date/ Time / i
- Operations Rep. Date/ Time /
i Notified by H.P. Rep. 1
- 4. The sampling frequency may change during the primary / secondary leakage, as deemed necessary by supervision. Record all changes below.
Initiated New Health Physics H.P. Sampling Frequency Shift Technician Supervisor Once Every Date/ Time Recordina Channe Hours On / I Hours On / Hours On / Hours On / Hours On / Hours On /
rage 2 of 2 DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/03
. SAMPLE ENCLOSURE 5.1 C.S.A.E. SAMPLE LOG Sample Once Date/ Time Per _ Hrs. of Sample Signature Remarks i
e 4 i e
"' - , ~ ,,,
Pass 1 c: 2 DUKE POWER COMPAhT CATAWBA NUCLEAR STATION HP/0/B/1009/03 SAMPLE ENCIASURE 5.2
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T.B. SUMP SAMPLE LOG
'Ihis form is to be used any time a primary to secondary leak is indicated.
- 1. Upon notification from Operations that a primary to secondary leak is indicated per Turbine Building Sump (E.T-31), record the following:
Operations Rep. Date/ Time / H.P. Re.p. Receiving Call ,
- 2. Unit #
Remarks:
- 3. If T.B. Sump Sample results indicate radioactivity above 10CTR20 Table II Col. II, notify the following representatives that batch releasing is required:
Radweste Chemistry Rep. Date/ Time / Operations Rep. Date/ Time / Notified by H.P. Rep. I 4 The sampling frequency may change during the primary / secondary leakage, as deemed necessary by supervision. Record all changes below. Initiated New Health Physics H.P. Sampling Frequency Shift Technician Supervisor Once Everv Date/ Time Recording Channe - Hours On / Hours on / Hours On / Hours On / Hours On / Hours On /
Pags .: of 2
. DUKE Pob7.R COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/03 SAMPLE ENCLOSURE 5.2 . T.B. SUMP SAMPLE IDG Sample Once Date/ Time Per Mrs. of Sample Signature Remarks i
I (
i Form 34731 (10-81) (Formerly SPD 10021) DUKE POWER COMPANY (1) ID No: HP/0/B/1009/04 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD 0 Incorporated (2) STATION: CATANBA (3) PROCEDUR2 TITLE: DNI1ONENI'AL M2TIORING EUR ENERGENCY CCIEITIWS WITHIN THE TEN MIIZ RADIUS & CATAim NUCIEAR STATIN
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(4) PREPARED BY: A DATE:
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(5) REVIEWED BY: v- - v v I // 2 M . DATE: 2- /~ Cross-Disciplinary Review By: %(kN N/R: (6) TEMPORARY APPROVAL (IF NECESSARY): By: . (SRO) Date: By: Date: (7) APPROVED BY: W- Date: S1!8 y . . , (8) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: O e O e. _ r
HP/0/B/1009/04 DUKE POWER COMPANY l CATAVBA NUCLEAR STATION ENVIRONMEfffAL MONITORING FOR EMERGENCY CONDITIONS WITHIN THE i TEN MILE RADIUS OF CATAWBA NUCLEAR STATION 1.0 PURPOSE To provide a method for identifying gaseous plumes or liquid effluent, and obtaining field data indicative of the radiation exposure to the general public following.a suspected uncontrolled release of radioactivity. This procedure shall also be implemented by the Crisis Management Center once it is activated.
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2.0 REFERENCES
2.1 HP/0/B/1000/06 Emergency Equipment Functional Check and Inventory 2.2 HP/0/B/1002/04 Collection of Operational Environmental Weekly Sanples 2.3 HP/0/B/1002/05 Collection of Operational Environmental Monthly Samples 2.4 HP/0/B/1002/06 Collection- of Operational Environmental Quarterly Samples 2.5 HP/0/B/1002/08 Collection of Operational Environmental Semimonthly
- Samples I 2.6 '
HP/0/B/1002/10 Collection of Operational Environmental Semiannual Samples 2.7 HP/0/B/1003/05 Operating and Calibration Procedure: Eberline Model PIC-6A Portable Ion Chamber 2.8 HP/0/B/1003/12 Operating and Calibration Procedure: Eberline l
. Model E-520 Portable Beta-Gamma Geiger Counter 2.9 HP/0/B/1003/17 Operation and Calibration Procedure: Canberra Series - 10 Portable MCA ,
2.10 HP/0/B/1003/31 Operation and Calibration: Eberline Model E140N Portable Count Rate Meter 2.11 HP/0/B/1009/16 Distribution of Potassium Iodide Tablets in the Event of a Radioiodine Release i 2.12 HP/0/B/1009/19 Emergency Radio System Operations, Maintenance , and Communications 3.0 LIMITS AND PRECAUTIONS 3.1 The Field Monitoring Teams (nff) should park vehicles completely
,off the road when sampling.
1
HP/0/B/1009/04 P:gs 2 cf 5 3.2 Four (4) FMTs consisting of two (2) technicians per team and one (1) helicopter team (1 person) if necessary shall be formed as follows: Team Call Signs Transportation Alpha Land Vehicle Bravo Land Vehicle Charlie Land Vehicle Delta Land Vehicle Echo Helicopter 3.3 Each FMT shall use particulate masks and protective clothing whenever activity justifies it or wh2n directed by the Field Monitoring Coordinator (FMC). 3.4 If the team members are expected to be exposed to I-131 in excess of 10 MPC (9 x 10 pCi/ml), and directed by the FMC, each team member should ingest a tablet of potassium iodide per Reference 2.11. 3.5 Environmental sampling during emergency conditions shall not replace, but rather supplement normal environmental monitoring. 3.6 Each F1C shall maintain open radio communications with the FMC per Reference 2.12. If radio becomes inoperable, call in sample results on a phone at 831-8182 or,803/831-2282 (Lake Wylie/ Charlotte), 861-0331 (Gaston County), 324-3128 (Rock Hill and Fort Mill). 3.7 If any equipment becomes inoperable, notify the FMC and wait for furthe'r instructions.
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3.8 Annual training in the use of this procedure and the associated equip-ment and instrumentation shall be conducted and documented on TSR-10. 3.9 Portable MCA's shall be picked up at the Health Physics instrument issue point when directed uy the FMC. Ensure that the dewars are adequately filled per Reference 2.9. 3.10 When returning kits to the Emergency Kit Storage Room, perform an i equipment inventory check using the Environmental Survey Kit Checklist (Reference 2.1). Note deviations and forward to the Respiratory / Instrument Calibratien Supervisor. i 4.0 PROCEDURE 4.1 Activation 4.1.1 Upon notificaton and assembly (FMC), the FMT members shall: 4.1.1.1 Report to the Health Physics area on the i 609' elevation (on back shifts report to Administration Building) and wait for further instructions from the FMC. 4.1.1.2 Report to the Emergency Kit Storage Room in the Temporary Administration Building to get Environmental Survey Kits.
. HP/0/B/1009/04 l Paga 3 of 5 ;
4.1.1.3 Ensure the Portable Power Generator is operational and the gas can is fully fueled (Reference 2.1). 4.1.1.4 Ensure the tamper seal on the Environmental Survey kits have not been broken and inventory any that have (Reference 2.1). 4.1.1.5 Don TLD 'and pocket dosimetry and fill out dose cards. 4.1.1.6 Battery.and source check survey instruments and
. portable MCA for proper operation (References 2.7,
.2.8, 2.9, 2.10).
4.1.1.7 Ensure the portable radios are functional before leaving (Reference 2.12). 4.1.1.8 Obtain-emergency vehicles as directed in Enclosure 5.8. 4.1.1.9 Each FMT will proceed to the survey point assigned by the FMC (Enclosure 5.3). I 4.2 Locating and Tracking the Plume
; 4.2.1 At the assigned survey point, the FMT shall perform a general area Beta vs. Beta-Gamma survey. This method should be used to locate center and width of plume.
4.2.1.1 Record date, time, location and dose rate (ar/hr) on the Field Monitoring Data Sheet (Enclosure 5.4). 4.2.2 If survey results are less than or equal to expected background, call in the results to the FMC and wait for further Distructions. 4.2.3 If survey results are greater than background, take protective actions as necessary. Then, if directed, take an air sample (volume should be > 10' ml) equipped with a , Silver Zeolite Cartridge and particulate filter. , l 4.2.3.1 Insert cartridge with arrow pointing in. 4.2.3.2 Insert filter paper with smooth side facing out. 4 4.2.3.3 Calculate required sample time per Enclosure 5.5. 4.2.3.4 When air sample is completed, place the Silver Zeolite Cartridge in a poly bag for analysis. 4.2.3.5 Place filter in a separate poly bag, label and retain for later analysis. l
HP/0/B/1009/04 Paga 4 of 5 i
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4.2.3.6 Follow instructions on the Field Monitoring Team Work Sheet and the attached Operator Guidelines (Enclosure 5.6) to record air sample information and analyze the cartridge on the Canberra-10. 4.3 Special Sampling, as directed: 4.3.1 All sampling outside of Auxiliary, Service and Turbine Buildings should be done in conjunction with Operations Support Center (OSC) personnel. 4.3.2 ' Take smears and place them in separate poly bags, label and retain for later analysis. 4.3.3 Count smears on E140N and record on Field Monitoring Data Sheet (Enclosure 5.4). Call in results to FMC. 4.3.4 Collect water samples in cubitainers using good Health Physics practices and label and retain for later analysis. 4.3.5 Place TLD's in the environment. 4.3.6 Retrieve and replace air sampic and/or TLD's that are already located in the environment. Locations are listed in Enclosure 5.1. Place samples in separate poly
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bags, label and retain for later analysis. 4.3.7 Collect broad leaf vegetation sample (one square meter) label and retain for later analysis (R sference 2.12). 4.3.8 Collect shoreline sediment sample (one liter) label and retain for later analysis (Reference 2.6). 4.3.9 Collect milk sample (one full cubitainer) label and retain for later analysis (Reference 2.5). Locations are listed in Sample Enclosure 5.2. 4.4 Turnover 4.4.1 Each FMT shall be relieved as directed by the FMC. 4.4.2 Inform the relief FMT of the equipment inventory status. 4.4.3 Direct the relief FMT to don TLD's and pocket dosimetry and fill out dose cards. 4.4.4 Return all samples to the Emergency Kit Storage Room as directed by the FMC. 4 4.4.5 Turn in all data sheets. co the FMC or his designee. 5.0 ENCLOSURES 4 5.1 Air Sampler, TLD, and Water Sample Locations 5.2 Milk Sample Locations
HP/0/B/1009/04 Paga 5 of 5 5.3 Predetermined Sampling Locations 5.4 Sample of Field Monitoring Data Sheet
. 5.5 Sample Time Required For Minimum Sample Volume 5.6 Sample of Field Monitoring Team Work Sheet For Determining Iodine Activity 5.7 TSC Field Monitoring Organization 5.8 Emergency Vehicles
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O e ( 1 1
Pass 1 of 5 DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCIASURE 5.1 AIR SAMPLER, TLD, AND WATER SAMPLE LOCATIONS
. Air Sample Locations (need key CPD-1)
Zone & Radius (Mi) No. Description
. AC 1 1 Hwy 274-N, right Liberty Hill Rd., right in fork to end (Air CNS #200, need key).
A0 1 5 Left at Steam Production entrance on Concord Rd., left on Old Concord Rd., right on Acacia Rd., left on Crepe Myrtle Rd., left on Blue Bird Ln., through gate to end (Air CNS #201, need key). El 3 1 Hwy 49-N, right Hwy 160, right at Tega Cay sign (98), right before Tega Cay entrance into Duke Power Company substation (Air i CNS #212, need key). C2 10 5 Hwy 274-S, left Hwy 161, right Mt. Gallant Rd. (195), right Hwy 21-121 By-Pass, right on
' Hwy 72 - 121 By pass, left on dirt road (Trash. Pile Rd.) across from Wayne's Auto Service, go to Duke Power Company substation (Air CNS #217, need key).
A0 1 26 Behind Catawba Nuclear Station overlook (Air CNS #205, need key). 1 j TLD Locations I. Site Boundary TLD's i Zone & Radius (Mi) No. Description A0 44 1 Hwy 274-N, right Liberty Hill Rd., right in fork, pass softball field to large rocks at fence on right. TLD is on fence (TLD CNS #222). A0 1 1 Hwy 274-N, right Liberty Hill Rd., right in fork to end (TLD CNS #200, need key). A0 1 5 Left at Steam Production entrance on i Concord Rd., left on Old Concord Rd., right on Acacia Rd., left on Crepe Myrtle Rd., left on Blue Bird Ln., through gate to end (TLD CNS #201, need key). A0 1 8 Left at Steam Production entrance on 1 Concord Rd...left on Old Concord Rd., right on Acacia Rd., left on Crepe Myrtle Rd. Go to first drive on right past Paradise Pl. , ' TLD across road (TLD CNS #202).
raga 2 or 5 DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCIASURE 5.1 AIR SAMPLER, TLD. AND WATER SAMPLE LOCATIONS Zone & Radius (Mi) No. Description A0 1 11 Left at Steam Production entrance on Concord Rd., left on Old Concord Rd., right on Acacia Rd. TLD is .1 miles on left in curve (TLD CNS #223). A0 . I 14 Left at Steam Production entrance on Concord Rd., left on Old Concord Rd., right on Acacia Rd. TLD .2 miles on right (TLD CNS #224). A0 1 45 Left at Steam Production entrance on Concord Rd., left on Old Concord Rd. to end. TLD on fence on left (TLD CNS #203). A0 1 17 Left at Steam Production entrance on Concord Rd. to first transmission tower on left after bridge (TLD CNS #225). A0 1 20 Left at Steam Production entrance on Concord Rd., TLD on left across bridge just past fence (TLD CNS #226). A0 1 23 ' Left at Steam Production entrance on C'oncord Rd., TLD on left at beginning of guardrail posts (TLD CNS #204). A0 1 26 Behind Catawba Nuclear Station overlook (TLD CNS #205).
- A0 1 29 Left at Steam Production entrance on Concord Rd., TLD at Shady Shore Dr. on right corner at Bethel Community Clubhouse sign (TLD CNS #227).
4 A0 1 32 Right at Steam Production entrance on Concord Rd., TLD at first dirt left (Valelake Dr.) on right cornce (TLD CNS #228). A0 1 35 TLD on top of hill at Catawba Nuclear Station Construction entrance on North side of street (TLD CNS #206). A0 1 38 Hwy 274-N, right at Liberty Hill Rd., right i ' in fork to third power line on right, walk about 200 yds. South along boundary fence. TLD on fence (TLD CNS #229). A0 1 41 Hwy 274-N, right at Liberty Hill Rd., go
.8 miles (right in fork) TLD on fence on right (TLD CNS #207).
, - - - - . , ~ . , , , , , - - - - - ,-e < - -. ---
, - , - - - - - . . , . - - - - , - , , , - , - . - - , ~ - - - - - - .
Pega 3 of 5 DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCIASURE 5.1 AIR SAMPLER, TLD, AND WATER SAMPLE LOCATIONS Zone is Radius (Mi) No. Description II. 4-5 Mile TLD's F1 4 4 Hwy 49-N to River Hills Plantation rear entrance at Robinwood Rd. TLD behind green building on right corner (TLD CNS #230). i F1 4 6 Hwy 49-N to River Hills Plantation front entrance guardhouse (TLD CNS #231). Al 4' 2 Hwy 49-N to intersection of Pleasant Hill Rd. (1109), TLD on power line (TLD CNS #232). A1 4 4 Hwy 49-N, right Pleasant Hill Rd. (1109), right Youngblood Rd.(1102), left Zoar Rd. (1105)., right Thomas Rd. (1104), TLD behind second house on right (TLD CNS #233). l B2 4 2 Hwy 49-N, right Hwy 160 to Home Federal 4 Savings and Loan on left. TLD on left rear l corner'of building. (TIR CNS #234). - B1 4 3 Hwy 49-N, right Hwy 160, right on Das Rd. (99), last gravel right in sharp curve before Lake Wylie Dam, left through fence to substation, TLD on right of inner substation fence (TLD CNS #235). C1 4 1 Hwy 274-S, left Mt. Gallant Rd. (195), left India Hook Rd. (30) to S.C. Wildlife Resources Dept (TLD CNS #236). C1 4 3 Hwy 274-S, left Mt. Gallant Rd. (195), right Homestead Rd. (657) to end, TLD straight across intersection of Twin Lakes Rd. (TLD CNS #237). C1 4 5 Hwy 274-5, left Mt. Gallant Rd. (195), right W. Oak Dr. (962) to end at fork, TLD on left at fence (TLD CNS #238). D1 5 1 Hwy 274-S to Carter Lumber Co., TLD on fence near gate (TLD CNS #239). D1 4 2 Hwy 274-S, right Campbell Rd. (80), left on Paraham Rd. (54) to transmission tower on right, TLD on brown power pole (TLD CNS #240). D1 5 4 Hwy 274-5, right Campbell Rd, (80) for i about 3 miles, TLD on left at beginning of l horse fence (TLD CNS #241).
Pcgs 4 of 5 DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/04 4 ENCIDSURE 5.1 AIR SAMPLER, TLD, AND WATER SAMPLE LOCATIONS Zone & Radius (Mi) No. Description El 5 2 Hwy 49-S, right Paraham Rd, (54) to transmission tower on left after bridge (TLD CNS #242). El 5 3 Hwy 274-N, left Hwy 55, left Kingsberry Rd. (114) to transmission zover on left (TLD CNS #243).
- F1 4 1 Hwy 274-N, left Hwy 55 to Bethel School, 4
TLD on side of small building in back (TLD CNS #244). i F1 4 3 Hwy 274-N left on Glenvista Rd. to Crowder Creek Boat Landing, TLD to East of parking lot (TLD CNS #245). B2 8 1 Hwy 49-N, right Carowinds Blvd. (1441), left Choate Cir., TLD on inside of fence left of
, the guardhouse (TLD CNS #246).
B1 3 1 Hiry 49-N, right Hwy 160, right Tega Cay sign (98), right before Tega Cay entrance into Duke Power Company substation (TLD CNS #212). - 4 B2 7 6 Hwy 49-N, right Hwy 160 to Fort Mill, right Lee St., left Self St., TLD at Fort Mill Municipal Water Supply behind Springs Mill (TLD CNS #247). C2 7 3 Hwy 274-S, right on Herlong Ave. to j Piedmont Medical Center emergency entrance j i to back of hospital. TLD on fence at back right corner of Liquid Oxygen storage area (TLD CNS #248). i C2 10 5 Hwy 274-S to Newport, left at stop light, right on Rawlinson Rd., left Hwy 5, right I on Heckle Blvd. (901) to end, left on Hwy 72, right on dirt road just across from Wayne's Auto Service, go to Duke Power Company Substation (TLD CNS #217). C2 8 6 Hwy 274-S, left Hwy 161, right Rawlinson Rd. (56), left Hwy 5 to Rock Hill Career Development Center, TLD on transmission tower (TLD CNS #249). i k
Pags 5 of 5 DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCIDSURE 5.1 ' AIR SAMPLER, TLD, AND WATER SAMPLE LOCATIONS Zone & Radius (Mi) No. Description D2 10 4 Hwy 274-S, right Campbell Rd. (80), left Hwy 49-S, left Rd. 64, left Hwy 5. Go to Duke Power Company Appliance Center on left. TLD on fence in back (TLD CNS #250). E2 . 10 2 . Hwy 55 into Clover, TLD at Duke Power Company Appliance Center in rear lot on 4 inner fence (TLD CNS #251). Water Sample Locations F3 14 4 Hwy 274-N, right Pole Branch Rd. (279), right Hwy 273 into Belmont, right Catawba St., left at next light to Belmont Municipal Water 1 Supply (Water CNS #218). , C2 7 2 Evy 274-S, left Hwy 161, right Mt. Gallant Road (195) to end. Rock Hill Municipal Water St.pply across intersection on left } (Water.CNS #214). B2 7 6 Hwy 49-N, right Hwy 160 to Fort Mill, right Lee St., left Self St. , go to Fort Mill Municipal Water Supply behind Springs Mill (Water CNS #213). A0 1 46 Left exiting Steam Production entrance on Concord Ed., left just after canal bridge. Go to pier (water CNS #208, need key). B1 4 5 Hwy 49-N, right Hwy 160, right Dam Rd. (99), left Gray Rock Rd. (251) to Lake i Wylie Dam. Walk through plant to upstream side of the dam (water CNS #211). B1 4 6 Hwy 49-N, right Hwy 160, right Das Rd. (99), left Gray Rock Rd. , (251) to Lake Wylie Dam. Ride or walk to river access on downstream side of dam. C2 7 8 Hwy 274-S left Mt. Gallant Rd. (195), left Hwy 161, left Cherry Rd. (Hwy 21), left on
- dirt road at Fort-Rock Drive-In to end, go right to Rock Hill Municipal water intake.
A1 4 6 Hwy 49-N, left at Camp Steere sign after crossing Buster Boyd Bridge (Water CNS #215). 4
Fags 1 or 1 DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCLOSURE 5.2 MILK SAMPLE LOCATIONS Zone Radius (Mi) Milk D1 Hwy 274-S, right Hwy 161, left Rd. 1080 to 6 M Pursley Dairy. , D2 8 M Hwy 274-S, right Hwy 161, left Scism Dairy , and Equipment Co. (CASE sign). E2 6 M Hwy 274-N, left Hwy 55, left Clinton Dairy Rd.
- F1 3 M Hwy 274-N, right Lake Wylie Rd. (1099) to first house on left, (Ingram Richmond residence).
F2 7 M Hwy 274-N, Hwy 55, right Paraham Rd. (54), l left Hwy 557. Barnett Dairy 1 mile on left. D1 7 M Hwy 274-S to Newport, left at stop light, right Adnah Church Rd. (81). Woods Dairy 1.5 miles on left. 13 M Hwy 274-N, left Hwy 55, go through Clover,SC. Right on Lloyd White Rd. (148), left on Crowders Creek Rd. (1103), next paved right , (1125). Cates Dairy is half mile on left. 1 J t k l 4 4 1 -* - -, - _
regn 1 or au DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCLOSURE 5.3 PREDETERMINED SAMPLING I4 CATIONS Zone Radius (MI) No. Description A0 1 1 Hwy 274-N, right Liberty Hill Rd., right in fork to end (TLD & Air CNS #200, need key). A0 1 2 Hwy 274-N, right Lake Wylie Rd. (1099), right at Hudson Rd. fork, right at Commodore Pl. fork, left on Tioga Rd. to end. i A0 2 3 Hwy 274-N, right Lake Wylie Rd., (1099), left fork after pavement ends, on Hudson Rd. to end. A0 2 4 Hwy 49-N, right Pleasant Hill Rd. (1109), right Youngblood Rd. (1102) to dead and at Catawba Yacht Club. A0 1 5 Left exiting Steam Production entrance on 4 Concord Rd., left on Old Concord Rd., right ' on Acacia Rd., left on Crepe Myrtle Rd., left on Blue Bird Ln. through gate to end (TLD & Air CNS #201, need key). A0 r l 1 6 Hwy 49-N, right Pleasant Hill Rd. (1109), right Youngblood Rd. (1102), left on Snug Harbor Rd. (1357), right Coze Cove Rd. (1434) to end. ' A0 2 7 Hwy 49-N, right Pleasant Hill Rd. (1109), right Youngblood Rd. (1102), to intersection of Snug Harbor Rd. (1357). ' A0 1 8 Left exiting Steam Production entrance on Concord Rd., left on Old Concord Rd., right on Acacia Rd., left on Crepe Myrtle Rd. Go to first drive on right past Paradise Pl. , TLD across road (TLD CNS #202). A0 1 9 Hwy 49-N, right Pleasant Hill Rd. (1109), right Youngblood Rd. (1102), left Snug Harbor Rd. (1357) to end. A0 2 10 Hwy 49-N, right Pleasant Hill Rd. (1109), right Youngblood Rd. (1102), left Snus Harbor Rd. (1357), stay on Snug Harbor at Kalabash Rd. Fork, take first gravel left (Crosshavens Dr.) after fork to the end
'(Beware of dogs).
A0 1 11 Left exiting Steam Production entrance on Concord Rd., left on Old Concord Rd., right on Acacia Rd.. TLD is .1 miles on left in curve (TLD CNS #223).
-_ 1
Tags z ot 30 DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCLOSURE 5.3 PREDETERMINED SAMPLING LOCATIONS Zoge Radius (Mi) No. Description A0 1 12 Hwy 49-N, right Pleasant Hill Rd. (1109), right Youngblood Rd. (1102), left McKee Rd (1100),.right Bankhead Rd. to end. A0 2 13 Hwy 49-N, right Pleasant Hill Rd. (1109), right Youngblood Rd. (1102), left McKee Rd. (1100), right Bankhead Rd. to intersection of Bessbrook Rd. A0 1 14 Left exiting Steam Production entrance on Concord Rd., left on Old Concord Rd., right on Acacia Rd. TLD .2 miles on right (TLD CNS #224). A0 1 15 Left exiting Steam Production entrance on Concord Rd., take first dirt fork to left on Kingsberry Dr., Stop at Commodore Yacht Club. A0 Left exiting Steam Production entrance on 1 16 Concord Rd. to last big curve before pave-ment ends. A0 1 17 i. eft exiting Steam Production entrance on Concord Rd. to first transmission tower on left after bridge ("ILD CNS #225). A0 1 18 Left exiting Steam Production entrance on Concord Rd., go to end and turn right on Sandlapper Rd. Stop at transmission tower. ; A0 2 19 Hwy 274-S, left Allison Creek Rd. (1081) to end of pavement. { 1 I A0 2 20 Left exiting Steam Production entrance on l Concord Rd. TLD on left across bridge, just past fence (TLD CNS #226). A0 1 21 Left Hwy 274-S, left Allison Creek Rd. (1081), left Spratt Rd. , to end (Beware of dogs). A0 2 22 Hwy 274-S, left Allison Creek Rd. (1081) to intersection of Bardale Rd. A0 1 23 Left exiting Steam Production entrance on Concord Rd. TLD on left at beginning of guardrail posts (TLD CNS #204). i t
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, DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCLOSURE 5.3 PREDETERMINED SAMPLING LOCATIONS Zone Radius (Mi) No. Description , A0 - 1 24 Hwy 274-5, left Allison Creek Rd. (1081), left at Spratt Rd., left Morrison Rd., then right in next 2 forks, left in next fork to end. 1 , A0 2 25 Hwy 274 A S, left Allison Creek Rd. (1081), to intersection of Spratt Rd. !
- A0 1 26 Behind Catawba Nuclear Station overlook (TLD and Air CNS #205, need key).
A0 1 27 Right exiting Steam Production entrance en Concord Rd., first dirt left on Valelske Rd., left in fork to end. A0 2 28 Hwy 274-S, left Allison Creek Rd. (1081) to intersection of Colina Rd. A0 1 29 Left exiting Steam Production entrance on Concord Rd. TLD at Shady Shore Dr. on right corner at Bethel Community Clubhouse sign . (TLD CNS #227). A0 30 1 Right exiting Steam Production entrance on Concord Rd., first dirt left on Valelake Rd., right in fork to end. 1 A0 2 31 Hwy 274-S to intersection of Campbell Rd. (80). A0 1 32 Right exiting Steam Production entrance on
' Concord Rd. TLD at first dirt left (Valelake Dr.) on right corner (TLD CNS #228).
A0 33 1 Right exiting Steam Production entrance on Concord Rd., left on dirt road (Pine Pt. Dr.) just before Granny's Restaurant, stop
.5 miles.
A0 2 34 Hwy 274-S to Big Allison Creek bridge. A0 1 35 TLD on top of hill at intersection of Catawba Nuclear Station Construction entrance and Road 1132 (TLD CNS #206). J A0 1 36 Right exiting Steam Production entrance to transmission line just before Granny's { Restaurant on Concord Rd. (1132). A0 2 1 37 Hwy 274-N, left Liberty Hill Rd., take first left and go to end. J
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. Page 4 of 10
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DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCLOSURE 5.3 PREDETERMINED SAMPLING LOCATIONS Zone Radius (Mi) No. Description A0 1 38 Hwy 274-N, right at Liberty Hill Rd., right in fork to third transmission line on
' right, walk about 200 yds. South along 4
boundary fence. TLD is on fence (TLD CNS
#229).
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4 A0 1 39 Hwy 274-N, right at Liberty Hill Rd., right in fork to third transmission line on right. A0 2 40 Right exiting Steam Production entrance on Concord Rd. to end. Right on Hwy 274-N for 1 mile. A0 1 41 Hwy 274-N, right at Liberty Hill Rd., go .8 miles (right in fork), TLD on fence on right (TLD CNS #207). t A0 1 42 Hwy 274-N, right at Liberty Hill Rd., right in fork, go to softball field entrance. A0 2 43 H$y 274-N, right Lake Wylie Rd. (1099), right Beaver Creek Trail to end.
! A0 1 44 ' $wy 274-N, right at Liberty Hill Rd., right '
in fork, pass softball field to large rock piling on fence. TLD is on fence (TLD CNS
#222).
A0 45 1 Left exiting Steam Production entrance, left on Old Concord Rd. to end. TLD on fence on left (TLD CNS #203). ) t A0 1 46 Left exiting Steam Production entrance on i Concord Rd. Turn left just after canal bridge. Go to pier (water CNS #208, need key). Al 3 1 Hwy 49-N to NC side of Buster Boyd Bridge. , A1 4 2 Hwy 49-N to intersection of Pleasant Hill Rd. (1109), TLD on transmission tower (TLD CNS #232). Al 5 3 Hwy 49-N to Steele Creek Vol. Fire Dept. on
- right, f
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rage a os av DUKE POWER COMPANY, CATAWBA NUCLEAR STATION - _r HP/0/B/1009/04 ENCLOSURE 5.3 PREDETERMINED SAMPLING LOCATIONS Zone Radius (Mi) No. Description A1 4 4 Hwy 49-N, right Pleasant Hill Rd (1109), right Youngblood Rd. (1102), left Zoar Rd. l (1105), right Thomas Rd. (1104, TLD behind l second house on right in pines (TLD CNS
#233).
A1 5 5 Hwy 49-N, right Pleasant Hill Rd. (1109, right Youngblood Rd. (1102), left Hamilton Rd. (1106) to intersection of Hwy 160. A1 4 6 Hwy 49-N, left at Camp Steere sign after crossing Buster Boyd Bridge (Water
.CNS #215).
A2 10 1 Hwy 49-N to Fast Fare at Coffey Creek on left. A3 10 1 Hwy 49-N, right Carowinds Blvd. (1441), left Hwy 51 to Pineville, stop near Sugar Creek bridge. B1 3 1 Hwy 49-N, right Hwy 160, right on Gold Hill Rd. (98) at Tega Cay sign, right before Tega Cay entrance on gravel road into Duke Power Company substation (TLD & Air CNS #212, need key). B1 2 2 Hwy 49-N, right Pleasant Hill Rd..(1109), right Youngblood Rd. (1102), left McKee Rd (1100)., left Bankhead Rd., left Bessbrook Rd. to end. B1 4- 3 Hwy 49-N, right Hwy 160, right on Das Rd. (99), last gravel right in sharp curve before Lake Wylie Dam, left through fence to substation, TLD on right of inner substation fence (TLD CNS #235). 81 2 4 Hwy 49-N, right Hwy 160, right on Gold Hill Rd. (98) at Tega Cay sign, enter Tega Cay following Tega Cay Dr., right Windjammer Dr.,
# 6 miles, Right at circle, Left Kiwi Point to end.
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Pego 6 of 10 . DUKE POWER COMPAhT CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCI45URE 5.3 PREDETERMINED SAMPLING LOCATIONS j Zone Radius (Mi) No. Description B1 4 5 Hwy 49-N, right Hwy 160, right Das Rd. i (99), left Gray Rock Rd. (251) to Lake Wylie Dam. . Walk through plant to upstream
, side of the das (water CNS #211).
B1 . 4 6 Hwy 49-N, right Hwy 160, right Das Rd. l
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(99), left Gray Rock Rd. (251) to Lake Wylie Dam. Go to river access on downstream side of dam. B2 8 1 Hwy 49-N, right Carowinds Blvd. (1441), left Choate Circle, TLD on inside of fence left of the guardhouse (TLD CNS #246).
! B2 4 2 Hwy 49-N, right Hwy 160 to Home Federal Savings and Loan on left. TLD on left rear corner of building (TLD CNS #234). . B2 5 3 Hwy 49-N, right Hwy 160, left on Gold Hill l Rd. (98) at Home Federal Savings and Loan, i
stop at intersection of Whitley Rd. B2 10 4 Hwy 49-N, right Carowinds Blvd. (1441), left Hwy 51 to Pineville, right Hwy 521 4 (Polk St.) in Pineville, right on Dorman Rd., stop at state line. B2 5 5 Hwy 49-N, right Hwy 160, right Sutton Rd. l (49) to intersection of' Gray Rock Rd. (251). B2 7 6 Hwy 49-N, right Hwy 160 to Fort Mill, Right Lee St., left Self St. TLD at Fort Mill Municipal Water Supply on right behind l Springs Mill (TLD CNS #247, also Water CNS i
#213).
B2 10 7 Hwy 49-N, right Hwy 160 through Fort Mill to the Sugar Creek bridge. l 1 C1 4 1 Hwy 274-S, left Mt. Gallant (195), left India Hook Rd. (30) to SC Wildlife Resources Dept. (TLD CNS #236). i C1 5 2 Hwy 274-S, left Mt. Gallant Rd. (195), go l' beyond India Hook to Red Burketts Body Shop on right.
DUKE POWER COMPANY CATAVBA NUCLEAR STATION.
, HP/0/B/1009/04 ENCIASURE 5.3 PREDETERMINED SAMPLING LOCATIONS Zone Radius (Mi) No. Description C1 4 3 Hwy 274-S, left Mt. Gallant Rd. (195),
right Homestead Rd. (657) to end. TLD straight across intersection of Twin Lakes
.Rd. (TLD CNS #237).
C1 5 4 Hwy 274-S, left Mt. Gallant Rd. (195), right Homestead Rd. (657) to end. C1 4 5 Hwy 274-S, left Mt. Gallant Rd. (195),
- right W. Oak Dr. (962) to end at fork. TLD on left at fence (TLD CNS #238).
C1 5 '6 Hwy 274-S, left Mt. Gallant Rd. (195), right at York County Museum (658) to end at SC National Guard Armory. C1 5 7 Hwy 274-S to Carter Lumber Co. C2 10 1 Hwy 274-S, left Hwy 161, left in fork on Celanese Rd. (50) to intersection of Springdale Rd. C2 7 2 Hwy 274-S, left Hwy 161, right Mt. Gallant Rd. (195) to end. Go to Rock Hill Municipal Water Supply across intersection { on left (Water CNS #214).
- C2 7 3 Hwy 274-S, right on Herlong Ave. to Piedmont Medical Center emergency entrance to back of hospital. TLD on fence at back
' right corner of Liquid Oxygen storage area (TLD CNS #248). 4 i C2 10 4 Hwy 274-S, left Hwy 161, right Mt. Gallant Rd. (195), right Hwy 21-121 By pass to Fast Fare on left at intersection of Springsteen l Rd. C2 10 5 Hwy 274-S to Newport, left at stop light, right on Rawlinson Rd., left Hwy 5, right I on Heckle Blvd. (901) to end, left on Hwy l 72, right on dirt road across from Wayne's Auto Service. Go to Duke Power Company substation (TLD & Air CNS #217, need key). C2 8 6 Hwy 274-S, left Hwy 161, right Rawlinson Rd. (56), left Hwy 5 to Rock Hill Career Development Center, TLD on transmission tower (TLD CNS #249). , ~.:.-- . . . _.. . _ _- : ::: m - - - - r- n w ~~ ----re-~~~~~--- = ~ ~ -
rag o ut Av DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCLOSURE 5.3 PREDETERMINED SAMPLING LOCATIONS Zone Radius (Mi) No. Description J C2 10 7 Hwy 274-S, left Hwy 161, right Adnah Church Rd. (81), right on Hwy 5, left on Eastview Rd. (102) to intersection of Oak Park Rd. (103). C2 , 7 8 Hwy 274-S, left Mt. Gallant Rd, (195), left Hwy 161, left Hwy 21, left on dirt road at Fort-Rock Drive-In to end, go right to Rock Hill Municipal Water Intake. D1 5 1 Hwy 274-5 to Carter Lumber Co. TLD on fence near gate (TLD CNS #239). D1 4 2 Hwy 274-5, right Campbell Rd. (80), left Paraham Rd. (54) to transmission tower on right, TLD on power pole (TLD CNS #240).
- D1 5 3 Hwy 274-S, right Campbell Rd. (80), left Piraham Rd. (54), next right on Rd. 815 to j Allison Creek bridge.
D1 5 4 Ifwy 274-S, right Campbell Rd. (80) for about 3 miles, TLD on left at beginning of horse fence (TLD'CNS #241). D2 10 1 Hwy 274-S, left Hwy 161, right-Adnah Church Rd. (81), right Hwy 5, quick left on Eastview Rd. (102), right Holland Rd. (157) , right Turkey Farm Rd. (1172), left Russell Rd. (536), go .2 miles. D2 10 2 Hwy 274-S, left Hwy 161, right Adnah Chruch Rd. (81), right Hwy 5, left Billy Wilson l l Rd. (1451), right Turkey Farm Rd. (1172) to l Fishing Creek bridge. I D2 10 3 Hwy 274-S, right Campbell Rd. (80), left ' Hwy 49'-S, stop at Pantry before entering York. D2 10 4 Hwy 274-S, right. Campbell Rd. (80), left Hwy 49-S, left Rd. 64, left Hwy 5. Go to Duke Power Company Appliance Center on left. TLD on fence in back (TLD CNS #250). m _y _ew ._ m o O _ '- .m.. m--~m .,,
ress :P us av
. . . . DUKE POWER COMPANY CATAWBA NUCLEAR STATION KP/0/B/1009/04 ENCLOSURE 5.3 PREDETERMINED SAMPLING LOCATIONS Zone Radius (Mi) No. Description D2 10 5 Hwy 274-S, right Campbell Rd. (80), left 49-S, right Old Limestone Rd. (172) to end.
El 5 1 Hwy 274-S, right Campbell Rd. (80) to intersection of Hwy 49. El 5 2 Hwy 49-S, right Paraham Rd. (54) to transmission tower on left after bridge (TLD CNS #242). El 5 3 Hwy 274-N, left Hwy 55, left Kingsberry Rd. (114) to transmission tower on left (TLD CNS #243). El 5 4 Hwy 274-N, left Hwy 55 to intersection of Kingsberry Rd. (114). E2 5 1 Hwy 274-5, right Campbell Rd. (80), right Paraham Rd. (54) to intersection of Dr. Nichols Rd. (819). E2 10 2 Hwy 274-N, left Hwy 55 into Clover, go to Duke Power Company Appliance Center on left. TLD on fence in back (TLD CNS #251). E2 10 3 Hwy 274-N, left Hwy 55 to Pantry at intersection of Rwy 321 in Clover (behind Pantry). 'l , F1 4 1 Hwy 2n-N, w C: Hwy 55 to Bethel School. TLD on side of small building in back (TLD CNS #244). F1 5 2 Hwy 274-N, left Hwy 55, right Bethel School Rd. (152) to intersection of Ifollandale Dr. F1 4 3 Hwy 274-N left on Glenvista Rd. to Crowder Creek boat landing, TLD to east of parking lot (TLD CNS #245). i F1 4 4 Hwy 49-N to River Hills Plantation rear entrance at Robinwood Rd. TLD behind green building on right corner (TLD l I CNS #230). 7 ; x I
rags AU or 10 DUKE POWER COMPANY CATAWBA NUCLEAR STATION' HP/0/B/1009/04 ENCLOSURE 5.3
, PREDETERMINED SAMPLING LOCATIONS Zone Radius (Mi) No. Description F1 5 5 Hwy 49-N, left Sherer Church Rd. to end.
F1 4 6 Hwy 49-N to River Hills Plantation entrance guardhouse (TLD CNS #231). F1 5 7 Hwy 49-N, left Montgomery Rd. at the River l Rat Restaurant. Stop in horseshoe curve near lake. F2 10 1 Hwy 274-N, left Hwy 557, right Ridge Rd. (27) to Bowling Green Presbyterian Chruch. F2 5 2 Hwy 274-N, left Hwy 557 to Pine Grove Baptist Chruch. J F3 10 1 Hwy 274-N, left Hwy 557, next paved right on Oakridge Rd. at Bethel Fire Dept. (Rd. 435) to intersection of Hwy 274 (in NC). F3 10 2 }twy 274-N, right Pole Branch Rd. (279) to Friendship Baptist Church on left. F3 10 3 Hwy 274-N, right Pole Branch Rd. (279), right Hwy 273 to A11'en Steam Plant Bridge. F3 14 4 Hwy 274-N, right Pole Branch Rd. (279), right Hwy 273 into Belmont, right Catawba St., left at next light to Belmont Municipal Water Supply (Water CNS #218). e seemmen ammmye, e .-6, e o __ ,, - - - - '
Pegs 1 of 1 DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/8/1009/04 ENCLOSURE 5.4 FIELD MONITORING DATA SHEET Date Team Members / Call Sign /_ Inst. Type /No. / Smear > Sample Location Time Survey Taken Dose Rate (mR/hr) Activity (DPM)
=
e 1 4 9 l f i
.3 a wi 4 DUKE POWER COMPANY CATAWBA NUCLEt.R STATION HP/0/B/1009/04 ENCIDSURE 5.5 SAMPLE TIME REQUIRED FOR MINIMUM SAMPLE VOLUME FLOW- RATE MINIMUM REQUIRED SAMPLING TIME IN MINUTES CFM LPM
.5 = 14 . .. . . . . ..
1.0 = 28......
.'. . . . . . . 71
. ..... . .. . . . 36 1.5 = 42 . . . ... . . . ... . . . . . . . 24 2.0 = 56 . . . . . . . ..... . . . . . . 18 2.5 = 70 . . . . . . . . . . . . . . . . . 15
'3.0 = 84 . . . . . . . . . . . . . . . . . 12 3.5 - = 99 . . . .... . . . . . . . . . . 11 4.0 = 113 . ................. 9 4.5 = 127 . ................. 8 NOTE: When estimating time required to get a minimum volume of 1 x 10' m1 if flow rate for the air sampler in use is not on table, go to next Lower flow rate. The LPM are rounded off on the conservative side to be safe.
Example: Air Sampler flow rate = 106 LPM. Minimum time 11 minutes i 4 1 4 4
DUKE POWER COMPANY Pags 1 of 2 CATAWBA NCULEAR $TATION-HP/0/B/1009/04 ENCLOSURE 5.6 FIELD MONITORING TEAM WORK SHEET FOR DETERMINING IODINE ACTIVITY
-Tcan Members Date Air Sampler No.
Tcan Call Sign Canberra No. ' AIR SAMPLE INFORMATION ANALYSIS RESULTS f' A B C D E F Sample ID. Air Sampler Flow Rate Iodine Activity Dose Rate Results l No./ Time / Location Run Time (Min) (LPM) Microcuries/a1 area /hr Reported By:
/ /
/ /
/ /
/ /
/ /
/ /
/ / _.
_/ /
/ /
/ /
/ /
2
/ /
4 1 -
/ /
/ /
/ /
/ /
/ /
Column A) Number of Sample / Time it was Taken/ Sampling Location (ex. A0-2-10). Column B) Length of time the air sampler ran. i Column C) Air sampler meter flow rate. Cslumn D) Activity from Canberra. C31uan E) Dose rate from Canberra. , Column F) Signature of person that calls in results to FMC. l I s.6.1 MCA and Detector Set-Up 1 5.6.1.1 Disconnect DC power cord from unit. A
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DUKE POWER COMPANY Pcg2 2 of 2 CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCLOSURE 5.6 OPERATOR GUILELINES 5.6.1.2 'rurn the contrast switch on the front of the unit clockwise to the ON mode. i 5.6.1.3 Place sampit holder with Na-22 check source onto the detector. l 5.6.1.4 Press TEST SYSTEM. 5.6.1.5 Press ENTER to begin test. 5.6.1.6 If test failed, press CLEAR ENTRY and remove the instrument from service. -- 5.6.1.7. If test passed, press ENTER. 5.6.2 Collecting and Measuring Filter Cartridges NOTE: Record data on Field Monitoring Team Work Sheet for Determining Iodine Activity (Sample Enclosure 5.6). 5.6.2.1 Press ANALYZE FILTER SAMPLE. 5.6.2.2 Press ENTER. 5.6.2.3 For each sample: 5.6.2.3.1 Place.~ cartridge with the reco;nizable side toward the detector (in small poly bag) in sample holder. 5.6.2.3.2 Put detector and sample holder in shield. lI 5.6.2.3.3 Press ENTER to accept ID number. 5.6.2.3.4 Press ENTER to accept current Flow Rate (LPM). Otherwise, change number and press ENTER. 5.6.2.3.5 Press ENTER to accept current Flow Time (min). Otherwise, change number and press ENTER. 5.6.2.3.6 If the volume is determined to be too small, resample, press ENTER and return to Step 5.6.2.3. 5.6.2.3.7 Press ENTER to start Collect / Analyze. 5.6.2.3.8 Report / Record Iodine activity (yCi/ml) and dose rate (ares /hr). e 5.6.2.3.9 Press NEXT SAMPLE. 5.6.2.3.10 Label the cartridge and retain for later analysis. J 5.6.3 After sampling completion, turn the contract switch counter-clockwise to the STAND-BY mode. i s*=. o_ .
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l'Kgs 1 of 1 DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCLOSURE 5.7 TSC FIELD MONITORING ORGANIZATION
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POSITION NAME BUSINESS PHONE HOME PHONE Field Monitoring Coordinators: Primary: C. V. Vray 803/831-2282 6 Alternates: R. L. Rivard 803/831-2282 J. E. Threact 803/831-2282 TSC Radio Operators: Primary: D. E. Sexton 803/831-2282 6 Alternate: T. W. O'Donohue 803/831-2282
! Field Monitoring Teams:
All Health Physics personnel with Field Monitoring Training. k
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rage A or A DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/04 ENCIDSURE 5.8 EMERGENCY VEHICLES The two designated emergency vehicles are the Operations pick-up truck and the Techalcal Services vehicle used primarily by Chemistry. These two vehicles are to be obtained (as directed by the FMC) by getting the keys from the Health Physics key box. A member of the Health Physics Shift Group can open the key box. On back shifts the key can be obtained from the front desk Security Officer. Obtain any other Station vehicles (if available) as directed by the FMC. Voluntary use of personnal vehicles is another alternative that may be considered. O j
a f Porn SPD-1002-1
. DURE POWER COMPANY (1) ID No:HP/0/B/1009/05 PROCEDURE PREPARATION Change (s) o to PROCESS RECORD 1 Incorporated (2) STATION: Catawba (3) PROCEDURE TITLE: Personnel / Vehicle Monitorina For Emeraency Conditions (4) PREPARED BY: M- @> 7M DATE: / .21-/V (5) REVIEWED BY: ! re-, ;I[ DATE: !'d3 ~W Cross-Disciplinary Review By: NMdI. N/R:
(6) TEMPORARY APPROVAL (IF NECESSARY):. By: (SRO) Date: By. Date: (7) APPROVED BY: . - ei J (N Q Date: k-M-M (8) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: 1 - . . . . - - - - . . _ _ . . . _ _ _ _ . _ . . _ . . . . , _ _ _ . , _,,,_,,,_,,I i 1 e i e I f ' _.n _ _ _ _
HP/0/B/1009/05 DUKE POWER COMPANY CATAWBA NUCLEAR STATION
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PERSONNEL / VEHICLE MONITORING FOR EMERGENCY CONDITIONS 1.0 PURPOSE To provide guidance for personnel and vehicle monitoring during a site evacuation resulting from a radiological emergency. 2.0 REFEREN'CES 2.1 HP/0/B/1003/31, Operation and Calibration: Eberline Model E-140N Portable Count Rate Meter 2.2 HP/0/B/1004/06, Personnel Decontamination 2.3 HP/0/B/1004/21, Equipment Decontamination 2.4 HP/0/B/1009/09, Guideline for Accident and Emergency Responsa 2.5 HP/0/B/1009/16, Distribution of Potassium Iodide Tablets in the Event of a Radiciodine Release 2.6 RP/0/A/5000/10, Conducting a Site Assembly or Evacuation 2.7 Station Directive 3.0.7, Site Assembly / Evacuation 2.8 Station Directive 3.8.3, Contamination Provention, Control, and Decontamination Responsibilities 2.9 Catawba Nuclear Station Emergency Plan 2.10 System Health Physics Manual 3.0 LIMITS AND PRECAUTIONS 3.1 If survey teams are expected to be exposed to I-131 in excess of 10
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MPC (9 x 10 8 aC1/al), and as directed by S&C Coordinator, each team member should ingest one tablet of Potassium Iodide. 3.2 Ensure that the Radiation Monitoring equipment has been battery checked and source response checked as per HP/0/B/1003/31. 3.3 If emergency vehicle is found to be contaminated as per Catawba Nuclear Station Directive 3.8.3, Section 6, and alternative transportation is not available, that vehicle may be released if needed for assistance and be decontaminated to below i acceptable limits at the first opportunity as per Catawba Nuclear Station HP/0/B/1004/21 Equipment Decontamination.
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nr/v/o/ Auuyf ua
, Paga 2 of 4 4.0 PROCEDURE j ,
4.1 The surveillance and Control Coordinator shall designate a supervisor or lead technician to assume the responsibilities of the Reserve Personnel / Personnel Monitoring Leader (RP/PM Leader). 4.1.1 The RP/PM Leader shall be responsible for personnel monitoring when an-evacuation occurs due to a radiological
- incident and other responsibilities as outlined in Reference 2.4.
4.1.2 The RP/PM Leader shall discuss, per Step 4.4, with the , Surveillance and Control Coordinator the practicalities of relocating' monitoring stations when the background is
. above 350 cepe for friskers.
4.1.3 The RP/PM Leader shall also arrange for monitoring of the assembly points and initiate action when dose rates approach 2 ar/hr. , { 4.2 The RP/RM Leader shall dispatch an Emergency Personnel Monitoring { Team to the following locatrions upos initiation of a site assembly j resulting from a radiological incident. L . l 4.2.1 Personnel Access Portal (PAP)
- 4.2.2 Construction Personnel Exit Area (Brass Gate).
4.2.3 All on-site assembly points as listed in Reference 2.7. NOTE: Manpower shall be supplied with respect to the nature of the accident and the availability of Health Physics i Personnel. 1 4.2.4 Each survey team shall have a copy of HP/0/B/1009/05 l Personnel Monitoring for Emergency Conditions, Catawba Nuclear Station Directive 3.8.3 Contamination and : Decontamination Responsibilities and an Personnel ' Monitoring Kit.
- 4.2.5 Upon reaching their designated locations, the survey teams shall verify their position with the RP/PM Leader.
4.2.6 The Construction Personnel Exit Area Team shall insure all personnel receive proper monitoring leaving via this exit l during evacuation. i i 4.2.7 The PAP Area Survey Team shall insure that the portal monitors are used properly and provide additional monitoring in order to expedite evacuation. e
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nt/U/DILUU4/UD Page 3 ef 4 4.2.8 If an individual is found to be contaminated as per Catawba Nuclear Station Directive 3.8.3, the survey team shall:
- _ 4.2.8.1 Dress che individual in the appropriate f ,
protective clothing and when time permits, decontaminate as per Catsuba Nuclear Station HP/0/B/1004/06. i 4.2.8.2 Notify the RP/PM Leader of all cases of personnel i contamination. 4.2.9 Survey teams will be supplemented, relieved or secured as directed. 4 4.2.10 Survey teams will monir.or dose rates at exit areas.
- Should dose rates exceed 1 mr/hr, team will initiate discussion with RP/PM Leader to expedite any evacuation ~
- through that exit point. -
; 4.2.11 The RP/PM Leader shoul.d notify the Surveillance and j Control Coordinator of all action taken.
4.3 The RP/PM Leader shall assemble another Emergency Monitoring Team ! upon initiation of a site assembly from a radiological incident for random monitoring of empicyee vehicle and when site evacuation is , initiated, dispatch this team to the Evacuation Facility (site
- Alpha: Transmission Line Maintenance Warehouse near Hwy SC 274 and
, SC 161. Site Bravo: Allen Steam Station, Hwy NC 273, South of Belmont). i NOTE: Monitoring equipment for vehicles is located in the
- Personnel Monitoring Kit located in the PAP area.
i 4.3.1 If a vehicle is found to be contaminated as per Catawba i Nuclear Station Directive 3.8.3, the survey team shall: 4.3.1.1 Prevent' further movement of the vehicle. . 4.3.1.2 Post the vehicle as a contaminated area. t 4.3.1.3 Provide general informatica on contamination surveys to the RP/PM Leader. ! i
- 4.3.1.4 Monitor all vehicles in the area for contamination. l 4.3.1.5 Decontaminate Vehicle using best method (s) l available on property owned by Duke Power i
Company that does not drain to a water system. ! 4.3.2 Upon site , evacuation and notification of Evacuation Facility (Alpha or Bravo), the RP/PM Leader shall: 4.3.2.1 Move with the monitoring team to the Evacuation Facility. ' 4 1 l . l
~ , . , , . . . , , .
Pega 4 cf 4 l 4.3.2.2 Locate Personnel Survey Kit at evacuation Facility and prepare to monitor incoming personnel. Personnel Survey Kit storage locations are identified on the Evacuation
- Facility Layout Drawing, Enclosure 5.1.
4.3.2.3 Supervise the monitoring and release of personnel as described in Steps 4.2.3 through 4.2.9 and 4.2.10. 4.3.2.4 List all personnel's' names, social security number and Health Physics badge number on
' Evacuation Personnel Dose Record Sheet, l Enclosure 5.2. This form should be used for dose commitment at a later time.
4.3.2.5 Supervise monitoring of employee vehicles and take action as appropriate per Step 4.3.1. 4.3.2.6 Notify Surveillance and Control Coordinator of ' all actions taken. 4.4 If background radiation readings render frisker and/or portal monitor useless, the RP/P4 Leader shall: 4.4.1 Discuss with the Surveillance and Control Coordinator relocating the personnel monitoring location a location of lower background. l 4.4.2 Procure from the Temporary Administration Building at 20 .
, watt portamoble radio for communication with'the OSC.
! Check operability of the radio. l 4.4.3 Move with the monitoring teams to an area of lower i background where personnel control can be maintained and prepare to monitor personne1~. i
; 4.4.4 Supervise the monitoring and release of personnel as described in Steps 4.2.3 through 4.2.9 and 4.2.10. i l
4.4.5 Supervise monitoring of employee vehicles and take actions as appropriate per Step 4.3.1. i j 4.4.6 Notify Surveillance and Control Coordinator of all actions taken. . 4, i 5.0 ENCLOSURES 5.1 Evacuation Facilities Layout Drawings i 5.2 Evacuation Personnel Dose Record I 1 3 4
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Form 34731 (1041) (Formerly SPD 10021) DUKE POWER COMPANY (1) ID No: HP/0/B/1009/06 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD 0 Incorporated (2) STATION: CAT M (3) PROCEDURE TITLE: ALTERNATIVE METHOD FOR DETERMINING DOSE RATE WITHIN THE REACTOR BUILDING
~
(4) PREPARED BY: - DATE: / y (5) REVIEWED BY: I d'~ DATE: /J f Cross-Disciplinary Review By: M N/R: (6) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: By: _
., Date:
(7) APPROVED 3Y: W- Date: 11/!$ (8) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: I I l - l l l e ' i i
i 4 , HP/0/B/1009/06 DUKE POWER COMPANY
' CATAWBA NUCLEAR STATION ALTERNATIVE METHOD TOR DETERMINING :
DOSE RATE WITHIN THE REACTOR BUILDING
- 1.0 PURPOSE
) This procedure describes an alternative method for determining the dose ' rate within the Reactor Building in the event the Reactor Building monitor ' is inoperable.
2.0 REFERENCES
2.1 System Health Physics Manual 2.2 HP/0/B/1000/02 Taking, Counting and Recording Surveys 3.0 LIMITS AND PRECAtTTIONS 3.1 This procedure is written for'une unde. abnorasi conditions which could involve extremely high radiation levels. Only Health Physics management should authorize the use of this procedure when needed and should provide appropriate surveillance and control. l 3.2 Check that surrey instrument (s) to be used have been calibrated and 1 response checks have been performed. 3.3 The method described below for determining the Reactor Building
- dose rate is an approximation and consideration shall be given to interference to background sources in the area.
4.0 PROCEDURE a
- 4.1 Method Using Dose Rate at Upper Personnel Hatch i
4.1.1 - Using a high range survey meter, obtain the dose rate at the upper personnel hatch by placing the meter's detector A in contact with the center of the hatch's outside door. ! NOTE: Consider use of extendable probe instruments to
- limit dose.
4.1.2 Determine the Reactor Building dose rate from the following equation. 1 RB = 661 x RH
- Rg = Reactor Building Dose Rate (R/hr) ,
~
HP/0/B/1009/06 Y Pese 2 cf 2 RH = Survey Meter Dose Rate at Upper Personnel Hatch (R/hr) 661 = 1 2 * .001293 g/ca'
- 21.67 cm
- 2.7 E-2 ca'/g 4.2 Record results on appropriate HP forms as per Reference 2.2.
5.0 ENCLOSURES N/A l i l j
Form 34731 (10 81) . (Formerly SPD 10021) DUKE POWER COMPANY (1) ID No: HP/0/B/1009/07 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD 1 Incorporated (2) STATION: Catawba (3) PROCEDURE TITLE: In-Plant Particulate and Iodine Monitoring Under _ Accident Conditions (4) PREPARED BY: P>udh M, IdawLrrn DATE: I 2 5' 84 (5) REVIEWED BY: $. s,18 DATE: /-J s . 74/ Cross-Disciplinary Review By: IV\ ) N/R: (6) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: By: . Date: (7) APPROVED BY: }d- Date: l/Ir!E! (8) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: e l g 4 4
*" e
_ . . _ . . , , , _ _ . _ - . # - - , , _,y _ -_
HP/0/B/1009/07 9 DUKE POWER COMPANY l
. CATAWBA NUCLEAR STATION IN-PLahT PARTICULATE AND IODINE MONITORING UNDER ACCIDE!C CONDITIONS l 1,0 PURPOSE To provide a method of particulato and iodine assay in the plant under accident /eaergency conditions when normal analysis equipment is not available.
2.0 REFERENCES
2.1 HP/0/B/1000/02 - Taking, Counting, and Recording Surveys 2.2. NP/0/B/1003/02 - Operating and Calibration Procedure: Low Volume, Portable Air Samplers 2.3 HP/0/B/1009/16 - Distribution of Potassium Iodide Tablocs in the Event of a Radiciodine Release 2.4 Catawba Nuclear Station Emergency Plan - Section I.2
2.5 NUREG-0694
'nlI - Related Requirements for New Operating Licenses 3.0 LIMITS AND PRECAUTIONS 3.1 This procedure is written for uso only under abnormal accident /emer-gency conditions when normal methods of quantifying iodine are not available. 3.2 Purging of silver zeolito cartridges should be done under a filtered hood whenever practical. In all cases it should be done in an uncontaminated area. 3.3 The activity calculations performed in this procedure are no longer valid once more reliable counting methods, (e.g. MCA, etc.), become available. , 3.4 If exposure is expected fro:n I-131 in excess of 10 MPC 8 (9 x 10 uCi/ml), and directed by the S&C Coordinator, technicians should ingest one tablet uf Potassium Iodide as per Reference 2.3. 3.5 Respiratory protective equipment should be used where possible to limit uptakes. s' i .
. - ~
IIP /0/b/1009/07 Pcg3 2 of 3 4.0 PROCEDURE 4 4.1 Sample Collection and Preparation , s. . 4.1.1 Using filter paper and a silver zeolite cartridge, collect a representative sample per references 2.1 and 2.2. 4.1.2 Remove and separate the filtur and the cartridge. Place each in an individual sample bag and label accordingly. 4.1.3 In order to remove unwanted (i.e.; Xenon, act.) gases from ] the cartr'idge, purge as follows: ; i 4.1.3.1 Remove the cartridge from the sample bag and 1 place it in a sample holder with a clean filter. 1
. 4.1.3.2 Orient the sample holder such that flow will be
- in the same direction as during collection l 4.1.3.3 The sample shall be purged for a time about one-third the time of sample duration at a low '
4 purge flow rate. - , NOTE: Low purge flow rate can be obtained i r by cracking purge valve until flow !
- is noticed. Care should be taken
i since a high flow race could cause , a release of Radioactive Iodine from the cartridge. 4.1.3.4 Remove the cartridge and place in a clean sample 2 bag. Mark the bag with original sample informa-j tion, and note the purgo dato and time. ! ! 4.1.4 Transport samples to an adequato sample counting location, ! and complete the top portion of the Emergency Particulate / ! ] Iodine Assay Form (Samptu Enclosure 5.1). j 4.2 Iodine Activity Determination 4.2.1 Vith the c.artridge still in the bag determine the dose rate at 1/2 inch from the inlet face of the cartridge.
- t. 2.1.1 For samples reading >, .1 ares /hr above i background on a low range survey instrument, record the dose rate on Sample Enclosure 5.1.
NOTE: Deriv.1tions of formulas used on 5.1mpio E;: closure 5.1 are provided on inclosure 5.2. 4.2.1.2 For samples reading <.1 ares /hr above p,-~ ) background, use an RM-14/HP-260 or equivalent to a determine corrected counts per minute (ccpe).
~
HP/0/B/1009/07 Paga 3 of 3 Divide the cepe by 3600 (or other correction factor if available) to determine arem/hr, and record on Samplo Enclosure 5.1. 4.2.2 Complete the " Iodine Activity" section of Sample Enclosure 5.1 to determine Iodine Activity. 4.3 Particulate Activity Determination (Gross) 4.3.1 Remove the filter paper from bag for counting. 4.3.2 If a scaler is available, use it to count the filter paper and record results and other necessary data on Sample Enclosure 5.1. 4.3.3 If a scaler is not available, use an R.'l-14/HP-210 or
, equivalent and record the average corrected counts per minute. If no efficiency factor is available, use 10.
4.3.4 Complete the " Particulate Activity" section of Sample Enclosure 5.1 to determine particulato activity. 4.3.5 Return the filter paper to its bag. 4.4 Sample and data handling i 4.4.1 Attach the samples to a copy of the completed Sanple Enclosure 5.1 and hold for possible further analysis.
- 4'.4.2 Notify appropriate personnel of results.
5.0 ENCLOSURES 5.1 Sample Emergency Particulato/ Iodine Assay 5.2 Derivation of Activity Calculation Formulas I a
HP/0/8/1009/07 88" pre Kac.loamse 5.1.
,. . . t. .
EMERGENCY PARTICULATE / IODINE ASSAY Sample Location o Date - 5ta'rt Time Performed By Stop Time Air Sampler Type /No. / Sample Duration Flow Rate 2 o Sample Volume , ( 1 ft* = 2.83E4 cc ) f IODINE ACTIVITY Instrument Type /No. / Sample Dose Rate 8 1" = ' ares /'tr. (A) x 28.2 - Iodine Activity = = uCi (B) cc
- Where
- A = Sample Dose Rate in mrem /hr i
- r B = Sample Volume in cc (or mi)
! w PARTICULATE ACTIVITY ' Instrument Type /No. / Background Efficiency Factor i Total Counts + Count Time = cpm cpe - Background = ccpe (A) x (B) x A.5E-7
- Gross Particulate Activity = =
, , (C) uCi CC ,
Where: A = ccpe B = Efficiency Factor in dps/ cps ] C = Sample Volume in cc (or al) 1
, Remarks:
't W
+
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- HP/0/B/1009/07
, Sample Encirsure 5.2
, P 331 of 2 DERIVATION OF ACTIVITY CALCULATION FORMUI.AS a
- 1. , Iodine Activity I-131 E = .19 MeV for beta volume of cartridge, v = wr h8
= w (1.13 in x 2.54 cm/in)8 x (1.04 in x 2.54 cm/in)
= 67.76 cas mass of cartridge, m = 4 oz x 28.35 ge/oz = 113.4 gm
, density of cartridge, p = a = 113.4 mm = 1.67 gm/ca' v 67.76 cm 3 thickness of cartridge, x = 1.67 ge/cm a x (1.04 in x 2.54 cm/in)
= 4.41 am/ca 8
.19 HeV beta particle energy range = 40 mg/cm 8 (p. 123, Rad Health Handbook) absorption' coefficient, y =
{ ~ 1 40 mg/ca'
= .025 cm 8/mg self absorption correction: (p. 136, principles of Radioisotope Methodology, Third Ed.)
-ux fs=1-e is = self absorption coefficient yx y = absorption coefficient, cm /mg8 x = sample thickness, mg/cm 8 8
.025 cm /nes x 1000 mg/gm x 4.41 gm/cm 8 fs=1-e = .009 3
.025 cm /ag x 1000 mg/gm x 4.41 gm/cm 3 1 mR/hr x 87.8 ern/za x 1R x 1 MeV x 1 he x 1 uCi
-6 R 1000 mR 1.6 x 10 erg 3600 sec 3.7 x 10' dps x d x 113.4 sm = .245 pCi
.19 MeV -
i r- so, .245 uCi = .245 pC1/mR/hr
' ,, 1 mR/hr i
HP/0/B/1009/07 Sample Enc 1csuro 5.2 Pags 2 of 2
, DERIVATION OF ACTIVITY CALCULATION FORMULAS
- s. .
.245 pCi/mR/hr = 28.2 pC1/mR/hr
. .009 mR/hr x 28.2 uCi/mR/hr = pCi CC CC assume 1 mR = 1 mRen
- 2. . Particulate Activity
-7 Ceps x dom /Com x 4.5 x 10 uCi/ dom = pCi CC CC I
(* * , Y!
Form 34731 (10-81) (Formerly SPD 10021) DUKE POWER COMPANY (1) ID No: HP/0/B/1009/08 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD 0 Incorporated (2) STATION: CATAWBA (3) PROCEDURE TITLE: CONTAMINATION CONTROL DURING TRANSPORTATION OF CONTAMINATED INJURED INDIVIDUALS (4) PREPAkED BY: .
^
2.< .~u' 7, M h, - DATE: /-JO FF (5) REVIEWED BY: DATE: / - su-/'/ Cross-Disciplinary Review By: M N/R: 4 7 E.< (6) TEMPORARY APPROVAL (IF NECESSARY): By: . (SRO) Date: By: , Date: ) (7) APPROVED BY: M Date: //E le!$[ (8) MISCELLANEOUS: i , Reviewed / Approved By: Date Reviewed / Approved By: Date: I l l l s l f , i 1 . l
HP/0/B/1009/08 DUKE POWER COMPANY
, CATAWBA NUCLEAR STATION CONTAMINATION CONTROL DURING TRANSPORTATION OF CONTAMINATED INJURED INDIVIDUALS 1.0 PURPOSE To provide guidance for the control of radioactive contamination due to transportation of a contaminated injured individual (s):
A. At the accident scene. B. In the First Aid Room. C. In the Ambulance. - D. During initial treatment in the hospital.
2.0 REFERENCES
2.1 HP/0/B/1000/05, Delineation of RCZ's 2.2 KP/0/B/1003/31, Operation and Calibration: Eberline Model E140N Portable Count Rate Siter 2.3 HP/0/B/1004/06, Personnel Decontamination 2.4 HP/0/B/1004/21, Equipment Decontamination
~
2.5 HP/0/B/1009/02, Investigation of Possible Overexposure, Personnel Contamination and/or Unusual Radiological Occurrences 2.6 Catawba Nuclear Station Emergency Plan 2.7 NCRP Report No. 65 3.0 LIMITS AND PRECAUTIONS 3.1 Lifesaving first aid and the preservation of vital functions shall have priority over contamination control. l 3.2 Appropriate respiratory equipment shall"ce used to prevent or ; minimize internal exposure in any planned rescue attempt. , i 3.3 Utilize as few people as necessary for the rescue and treatment of contaminated injured individuals. 3.4 Ensure that all personn'el involved in the rescue and treatment of contaminated injured individus.ls receive proper monitoring and decontamination, if necessary. 3.5 If the emergency vehicle is found to be contaminated, that vehicle may be released if needed for assistance in life threatening situations and be decontaminated to below acceptable limits at the first opportunity as per Reference 2.4
' j i
-- -. . 9
-- - =. . - _ - _ - _ _ _ - _ _-_ _ _ _.
HP/0/B/1009/08 i Pego 2 of 6 3.6 Ensure that valuables which are collected from the injured person are monitored and turned over to security. 3.7 Ensure that the tamper seal on the Medical Decontamination Kit has not be broken. Inventory the kit if it has. 3.8 Ensure.that Security Supervision has been notified. 3.9 Body excretions a'nd vomitus should be collected in separate containers and transported with the injured person to the hospital. Containers, should be labeled with the type of sample, date, and time collection. All effluents should be returned to Health Physics for r'adiological analysis. 4.0 PROCEDURE 4.1 Control at Accident Scene i 4.1.1 Incapacitated Victims 4.1.1.1 Have victim brought to the RCZ exit nearest the accident scene. 4.1.1.2 Have rescue workers place injured on stretcher in such a way as to minimize cross
~
contamination. 4.1.1.3 Once victim is on stretcher, cover him/her with i blanket securely to prevent the spread of contamination while in motion. 4.1.1.4 Ensure a Health Physics representative is available in the first Aid Room to assist medical personnel. 4.1.2 Minor Injuries 4.1.2.1 For victims with minor injuries, have them exit their work area in the normal fashion. 4.1.2.2 Accompany victim to Contaminated Change Room and monitor with available frisker. If , contamination is found decontaminate in accordance with Rsference 2.3, using Contaminated Change Room facilities, i 4.1.2.3 Have victim report to contaminated First Aid Room (Auxiliary Building) to receive any additional treatment. 4.1.3' If' accident occurred in a normally non-contaminated area and the possibility of accident induced contamination exists, control access to the area as per Reference 2.1. 1 2 a - -r- , ..
. l
. HP/0/B/1009/08 Peg 2 3 of 6 4.1.4 After victis(s) have been evacuated from accident site and
.taken to Contaminated First Aid Room, smear survey the route taken. If contamination is found, post area as such 1 and take appropriate steps for decontamination.
4.2 Control in the Contaminated First Aid Room 4.2.1 Prepare victim laydown areas by covering them with a protective covering before placing victim down. 4.2.2 Prepare sufficient facilities for- the storage of contami-nated waste.. generated during first aid treatment. 4.2.3 Ensure that all personnel in the First Aid Room are wearing anti-contamination clothing appropriate for the levels of contamination expected. 4.2.4 Upon victim (s) arrival, collect their dosimetry and place in polyethylene bag for subsequent evaluation. 4.2.5 Line the covered victim laydown area (s) with blankets if- 1 available and place victim (s) there. 4.2.6 Personnel Monitoring 4.2.6.1 Victim's in Anti-C Clothing 4.2.6.1.1 Assume all victims in Anti-C's have surface contamination. 4.2.6.1.2 Remove Anti-C's by cutting midline and peeling to each side. 4.2.6.1.3 Place disrobed victim on clean blanket and fold AN'fI-C's into blanket that was previously under victim. 4.2.6.1.4 Proceed to monitor entire body surface I with an E140N and HP-210 probe. l 4.2.6.1.5 Note contamination levels on Personnel Contamination and Decontamination survey sheets. 4.2.6.2 Victims in Street Clothing I 4.2.6.2.1- Monitor victim with E140N and KP-210 probe. 4.2.6.2.2 If contamination is found, remove i clothing by cutting midline and - peeling to the sides.
.-. c. - ,-. -, ., , , . - . .
HP/0/B/1009/08 Pega 4 of 6 4.2.6.2.3 Place disrobed victim on clean
. blanket and fold clothing into blanket that was previously under victim.
4.2.6.2.4 Resurvey victim. 4.2.6.2.5 Fill out Personnel Contamination and Decontamination Survey Sheet. (Enclosure 5.1). NOTE: .Now, victim (s) can be handled according to their ; contamination level. , 4.2.7 Health Physics in conjunction with medical personnel will determine if victim decontamination should be initiated or if immediate transporation to hospital is necessary. 4.2.8 If decontamination is to be initiated in accordance with Reference 2.3, attempt to use shower, if victim cannot be showered, perform decontamination utilizing damp towels and wiping specific areas. 4.2.9 After decontamination, resurvey victim and complete (Enclosure 5.1). , . 4.2.10 Prior to victims laydown on ambulance stretcher, insure that the area is securely covered with a protective covering. i 4.2.11 Pass victims through double doors of Contaminated First Aid Room to ambulance personnel, being sure to minimize the spread of contamination. r 4.2.12 Prior to loading on ambulance, cover all contaminated victims (ex: blankets, sheets), and cover necessary aracs of the - ambulance to minimize the spread of centamination. 4.2.13 Have a Health Physics Technician and Nurse (if available) i accompany the contaminated victim to the hospital with the ! following items: i Enclosure 5.1 ! E140N and HP-210 Probe . NOTE: If there is significant contamination, } additional support should be dispatched to I hospital, j ' i 4.2.14 First Aid Room should be posted.for radiation and i contamination present until decontamination can be i performed. l 1 I
l
, HP/0/B/1009/08 Pega 5 cf 6 l 4.3 Control in the Ambulance 4.3.1 Reference (Enclosure 5.1) to obtain degree of ,
contamination present. Contamination control can be determined with the use of this information. 4.3.2 Ensure that ambulance personnel are adequately dressed for I degree of contamination present. 4.3.3 Provide polyethylene bag for disposal of all items coming in contact with the victim and return to Catawba Nuclear
. Station for.. decontamination or disposal.
4.3.4 Upon arrival at hospital, secure bags appropriately. 4.3.5 Instruct ambulance personnel in proper Health Physics practices while involved in treating the contaminated injured individual. 4.3.6 Upon victims transfer from ambulance to hospital, see that all doors and windows of ambulance are secured and post as a potentially contaminated area antil further monitorir s can be performed. 4.4 Control During Initial Treatment In Hospital 4.4.1 Ensures that all personnel in the treatment area are wearing proper dosimetry, and that dosimetry has been properly labelod and that dose :ards have been filled out befora returning ther to Health Physics for evaluation. 4.4.2 Control or minimize spread of contamination when entering facility as not to hinder access to emergency room in regards to non-radiological patients and personnel. 4.4.2.1 RCZ should be set up in accordance with 4 Reference 2.1 at the entrance of the treatment area. 4.4.2.2 Ensure that floor covering is taped to the floor of the treatment area. , 4.4.2.3 Ensure that ventilation ducts in the treatment area are secured by taping a covering over them. 4.4.3 Control or minimize spread of contamination in regards to treatment. ! 4.4.3.1 Monitor personnel and equipment leaving the treatment area. 4.4.3.2 Ensure that all personnel in the treatment area . are wearing anti-contamination clothing appropriate l for the levels of contamination present and that l diagnostic equipment is prcperly covered. l l 9
, - - - , , - y , , , - -
HP/0/B/1009/08 Pcg3 6 of 6 4.4.3.3 Prepare sufficient facilities for the storage of contaminated waste generated during treatment. 4.4.4 During treatment, depending on urgency of treatment, instruct hospital personnel in proper Health Physics practices by radiological advisement and assessment. NOTE: Do not interfere with trearment. 4.4.5 After treatment, monitor room and equipment. If centaminated, initiate decontamination. This procedure involves proper wrapping and tagging of materials. Transportation of contaminated materials should be a consideration. 5.0 ENCLOSURES 5.1 Sample of Personnel Contam'ination and Decontamination Survey Shest G 4 m ----
. ,( , ~ rit'/U/u/4w /vo IE'ESTIGATICM 0.r Pr.1:SY,r;;. ::or~ia't;SATION (CONTM11NAT*0N/DEC05'i A':iNAl' h..;; :i' hVE't ' SHEET)
Date _ _ _ . _ Date and Time of Contamine:ica , , , _ _ , _ , _ , ,.
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Name of Individus1 ,
,,_,,, itP Bady,c Number Individual's Supervisor _ .ork Group Job Description (R'JP/SK'4?) ___
Cause of-Personnel Contamination Check and answer in the space belce: () Ac: en reccmmended to prevent a racurre::ce of Personnel C.'r.:a a inst ion . ( ; ;m.ccata=ina:icn Methcd used in iiucenr. amination of Pc:sonnel. 2 Use additional shee:s .ts vecessary Use the re. vers e - f or recording :n:. :m:na.ti.a . . ve 1:, on P .::::,,nnel Use addi:icna: snee:s as necessarf dur:ng ,de..t...t.iaina:1.m ci t'e r vinne l . HP Instruments U.;cd: Type __,_,,, Senher _, EF /F sv E....fr
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Background:
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I Form SPD-1002-1 DUKE POWER COMPANY (1) ID No:NP/o/n/1nn9/09 PROCEDURE PREPARATION PROCESS RECORD Chan e(s) A to JL . ncorporated (2) STATION: Catawba . (3) PROCEDURE TITLE: Guidelines For Accident and 'Emernency Resoonse l 1 (4) PREPARED BY: M 7 /4 4 DATE: / /V (5) REVIEWED BY: *M/ DATE: /M2 Cross-Disciplinary Review By: W[ N/R: (6) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: By: Date: (7) APPROVED BY: . . bi Qt7 Date: )-TM-M D (8) MISCELLANEOUS: , Reviewed / Approved By: Date: Reviewed / Approved By: Date: _ O e 9 9 e
HP/0/B/1009/09 DUKE POWER COMPANY CATAWBA NUCLEAR STATION , GUIDELINES FOR ACCIDENT l AND EMERGENCY RESPONSE 1.0 PURPOSE 1.1 To provide ' guidance for notification / activation of the Health Physics Organization in the event of an emergency situation. 1.2. To assure proper assignment of responsibility. 1.3 To give general guidance for initial response of the Health Physics organization. 1.4 To give general guidance for continuing response of the Health Physics organization.
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2.0 REFERENCES
2.1 Catawba Nuclear Station Emergency Plan. 2.2 HP/0/B/1009/04, Environmental Monitoring for Emergency Conditions Within the Ten Mile Radius of Catawba Nuclear Station 2.3 HP/0/B/1009/05, Personnel Monitoring for Emergency Conditions. 2.4 HP/0/B/1009/06, Alternative Method for Determining Dose Rate Within the Reactor Building. - ' 2.5 HF/0/B/1009/07, In-plant Particulate and Iodine Monitoring Under Accident Conditions. 2.6 HP/0/B/1009/08, Contamination Control During Transportation of l Contaminated Injured Individuals. l 2.7 HP/0/B/1009/10, Body Burden Analysis Following Suspected Uptakes of l Mixed Fission or Activation Products. 2.8 HP/0/1009/12, Quantifying Gaseous Releases Through Steam Relief Valves Under Post-Accident Conditions. 2.9 HP/0/B/1009/13, Off-Site Dose Projection - Uncontrolled Release of Radioactive Material nrough the Unit Vent. I ! 2.10 HP/0/B/1009/14, Off-Site Dose Projection - Uncontrolled Release of ' Liquid Radioactive Material. 2.11 HP/0/B/1009/15, Off-Site Dose Projection - Uncontrolled Release of Gaseous Radioactive Material Other Than Through the Unit Vent. m -- '- -' '7'y
HP/0/B/1009/09 Pags 2 of 3 4 2.12 HP/0/B/1009/16, Distribution of Potassium Iodide Tablets in the Event of a Radiciodine Release. 2.13 HP/0/8/1009/17, Nuclear Post Accident Containment Air System Operation. 2.14 HP/0/B/1009/19, Emergency. Radio System Operations, Maintenance, and Communications.
- 2. 15 System Health Physics Manual
)
1 2.16 ~Catsuba Nuclear Station, Station Directive 3.8.4, Onsite Emergency ' Organization ' 3.0 LIMITS AND PRECAtTTIONS 3.1 This procedure shall only be initiated at the direction of Health Physics Supervision. 0.2 This procedure may be initiated in part or whole, depending on the
- type and severity of emergency. ~
3.3 This procedure prov! des general guidance for initial response. Any particular situation may require actions not addressed in this , procedure. * , i . l 3.4 For incidents occurring during backshifts, Health Physics shife j personnel shall be responsible for on-site response caly until directed otherwise by the Station Health Physicist. 4.0 PROCEDURE i t.1 Upon notification of an emergency condition, the Station Heslth Physicist shall activate the Health Physics organization by notifying one or all of the following: , 4.1.1 Surveillance and Control Coordinator. 4.1.2 Support Functions Coordinator. ; 4.1.3 Staff Coordinator. 4.1.4 Shift Technician (To advise, if during back shift). 4.2 Individual coordinators will notify alternates and supervisors to be under their direction during the emergency, and will make arrangements through the supervisors for the notification of non-exempt persounal. 1 4.3 If the emergency is classified above the Notification of Unusual Event category, the Station Health Physicist shall proceed to the l I Technical Support Center (TSC), and coordinate the overall Health Physics response. Enclosures 5.2 and 5.3 provide general j guidelines for response. I
HP/0/B/1009/09 Pego 3 cf 3 4.4 When notified to respond to an emergency, the Surveillance and Control Coordinator shall assume alternate responsibility for the Station Health Physicist, and shall activate the S&C Coordinator identified in Reference 2.16 who will act according to Enclosures 5.4 and 5.5. 4.5 When notified to respond to an emergency, the Support Functions Coordinator shall assume alternate responsibility for the Station ' Health Physicist and shall activate the Support Functions l Coordinator identified in Reference 2.16 who will act according to Enclosures 5.6 and 5.7. l 4.6 When notified to respond to an emergency, the Staff Coordinator shall act according to Enclosures 5.8 and 5.9. 4.7 When notified to respond to an emergency, the Field Monitoring Coordinator shall act according to Enclosures 5.10 and 5.11.
- 4.8 When notified to respond to an emergency, the Operation Support
.Conter (OSC) Supervisor shall act according to Enclosures 5.12 and 5.13. ,
5.0 pjCLOSURES . 5.1 Guidelines For Planned Emergency Exposures 5.2 Station Health Physicist - Initial Response 5.3 Station Health Physicist.'- Continuing Response 5.4 Surveillance and Control Coordinator - Initial Response 5.5 Surveillance and Control Coordinator - Continuing Response
! 5.6 Support Functions Coordinator - Initial Response 5.7 Support Functions Coordinator - Continuing Respense 5.8 Staff Data Analysis Coordinator - Initial Response 5.9 Staff Data Analysis Coordinator - Continuing Response 5.10 Field Monicoring Coordinator - Initial Response 5.11 Field Monitoring Coordinator - Continuing Response 5.12 OSC Supervisor - Initial Response 5.13 OSC Supervisor - Continuing Response 5.14 Reserve Personnel / Personnel Monitoring Leader Response 5.15 OSC Responte Personnel Dose Record Form 5.16 Procurement of Helicopters for Aerial Environmental Surveillance
Paga 1 of 2 HP/0/B/1009/09
, ENCLOSURE 5.1
^ GUIDELINES FOR PLANNED EMERGENCY EXPOSURES
- 1. 0" Obtain the verbal or written approval of the Emergency Coordinator to exceed planned maximum limits.
2.0 If it is necessary to remedy a situation immediately hazardous to life and property, an individual (Duke Power personnel, or Outside Services) may receive arposure up to: Whole Body 5 rems (25 rem)* l Skin of the Whole Body 30 rems (125 rem)* or Thyroid Extremities 75 rems
- Doses up to this limit may be authorized by the Recovery Manager.
3.0 If it is necessary to save lives or prevent loss of lives and/or extensive damare to property, an individual may volunteer to receive exposure up to: Whole Body 25 rems (75 rem)* Skin of the Whole Body 150 rems or Thyroid - Extremities 4
. 375 rams Doses up to this lbsit may be authorized by the Recovery Manager, Station Manager or Emergency Coordinator. ,
4.0 If possible, the individual (s) should be selected by the following conditions: 4.1 Personnel should be volunteers or professional rescue personnel. 4.2 Personnel should be broadly familiar with the potential consequences of such exposure. 4.3 Women capable of reproduction should not take part in these actions. 4.4 All factors being equal, volunteers above the age of 45 should be selected. 5.0 Exposure shall be maintained ALARA. 6.0 Internal exposure should be minimized by the use of the best available respiratory protection, and the contamination should be controlled by the use of available protective clothing. . 7.0 Exposures below the guidelines of Section 3.0 may require an occupational penalty. 8.0 Exposures above the guidelines of Section 3.0 should be authorized by the Recovery Manager, Station Manager or Emergency Coordinator and will require a medical decision as to whether the individual may continue ir. i
. radiological work and should be limited to once in a lifetime.
rags 4 us 4 HP/0/B/1009/09 ENCICSURE 5.1 l 9.0 Planned emergency doses shall be recorded, estimated if necessary, and l included in the individual's exposure history record, l l 1 10.0 Reports of planned emergency exposures shall be reported as per Catawba Nuclear Station Directive 2.8.1 (Reporting Requirements). e s O e
Pags 1 of 1 HP/0/B/1009/09 ENCLOSURE 5.2 STATION HEALTH PHYSICIST INITIAL RESPONSE i 5.2.1 Assemble supporting materials and take to TSC. 5.2.2 The Station Health Physicist shall as necessary: 5.2.2.1 Establish the exposure limit for blanket dose extension, for Exposure Class 1 to a maximum of 1000 mrem /qtr; for Exposure Class 3 to a maximum of 2500 mrem; for Exposure Class 2 personnel (pregnant females) they shall not be extended above their weekly limit, and should be reassigned..to work locations in the Administration Building until radiation levels are evaluated. 5.2.2.2 Govern planned emer3ency exposures by Enclosure 5.1 (Guidelines For Pla:saed Emergency Exposures). 5.2.2.3 Coordinate the overall Health Physics response. 5.2.2.4 Recommend protectios action on-site for assembled personnel and those with work duties. 5.2.2.5 Recommend off-site protective action to the Emergency Coordinator until the CMC (Crisis Management Center) is activated. , , 5.2.2.6 Initiate, as necessary. HP/0/B/1009/16, Distribution of Potassium Iodide Tablet in the Event of a Radioactive Release. ( 1 3 4 -
rega i or i HP/0/B/1009/09 ENCLOSURE 5.3 STATION HEALTH PHYSICIST CONTINUING RESPONSE 5.3.1 Interface with the CMC when it is activated. 5.3.2 Coordinate Health Physics shift rotation and augmentation of personnel and equipment. 5.3.3 Should evacuation be required; coordinate the identification of "Non-Essential" personnel with other T3C groups. ~ 5.3.3.1 All females should be given first consideration due to limited use in a radiological exposure situation. 5.3.3.2 Sufficient personnel should be retained to support need for backup personnel. 5.3.4 Direct trending of available information to support Health Physics TSC response. 5.3.5 When CMC is in place, continue Protective Action assessment and recommendations as a confirming response. e t e
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Pcg3 1 of 1 HP/0/B/1009/09 ENCLOSURE 5.1 SURVEILLANCE AND CONTROL COORDINATOR INITIAL RESPONSE 5.4.1- Assemble supporting materials and take to TSC. 5.4.2 Establish radiological access controls for the Station and Control Room. 5.4.2.1 Initiate, as necessary, HP/0/B/1009/07, In-Plant l i Particulate and Iodine Monitoring Under Accident Conditions. i 5.4.2.2 Initiate,,as necessary, HP/0/B/1009/08, Contamination Control During Transportation of Contaminated Injured Individuals. 5.4.2.3 Initiate discussions by need for Buddy System for radiological conditions. 5.4.3 If the emergency is classified above the Notification of Unusual Event category: 5.4.3.1 Send the following personnel as necessary to the Operations Support Center (OSC): 5.4.3.1.1 One Supervisor to coordinate Health Physics support and' communicate with the TSC and shall act according to Enclosures 5.12 and 5.13. 5.4.3.1.2 One Technician to provide job coverage (sampling, operation maintenance, etc.). 5.4.3.1.3 Two Technicians to monitor and report plant radiological status. 5.4.3.1.4 Two Technicians to provide fire / medical emergency / rescue team / damage control coverage. 5.4.3.1.5 Direct sufficient personnel to the Administra-tion Building, DRC office, as staging area. 5.4.3.2 Identify a Supervisor or Lead Technician to Reserve Personnel / Personnel Monitoring Leader and he/she shall act according to Enclosure 5.14 5.4 3.3 Proceed to the TSC and coordinate Surveillance and Control response, with emphasis upon OSC activities. 5.4.3.4 Request TSC Security staff to provide locations of officers remaining on post. Evaluate exposure potential for these officers and recommend protective actions as necessary.
rego 1 or i HP/0/B/1009/09 ENCLOSURE 5.5 SURVEILLANCE AND CONTROL COORDINATOR CONTINUING RESPONSE 1 5.5.1 The S&C Coordinator shall, as necessary: 5.5.1.1 Initiate through RP/PM Leader HP/0/B/1009/05, Personnel i Monitoring for Emergency Conditions, when a site assembly occurs due to radiological conditions. 5.5.1.2 Initiate, as necessary, HP/0/B/1009/17, Nuclear Post Accident Containment Air Systems Operation. 5.5.2 Provida direction and support to the OSC Health Physics Supervisor: 1 5.5.2.1 Coordinate in plant and on-site monitoring in support of TSC needs. $ 5.5.2.2 Keep OSC Supervisor appraised of TSC events and activities that may require OSC response (planned maintenance, operation, sampling). - ! 5.5.:.3 Coordinate with OSC and TSC groups to ensure adequate pre planning occurs to limit radiation exposures. 5.5.2.4 Obtain additional emergency kit items and supplies to support OSC if needed. 3 5.5.3 Monitor dose rate in TSC. Initiate discussion with Station Health Physicist on the need to evaluate the TSC should dose rate exceed 5 mR/hr and be expected to continue. s
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Pcgs 1 of 2 HP/0/B/1009/09 ENCLOSURE 5.6 SUPPORT FUNCTIONS COORDINATOR INITIAL RESPONSE 5.6.1 Assemble supporting materials and take to TSC. 5.6.2 ~ Evaluate the need to establish an alternate location for sample analysis. 5.6.3 Establish a count room sample priority list if emergency radiological sampling is in progress or is going to begin. 5.6.4 Initiate, as necessary, HP/0/B/1009/10, Body Burden Analysis ! Following Suspected Uptake of Mixed Fission or Activation Products.
- 5.6.5 If the emergency is classified above the Notification of Unusual Event category
5.6.5.1 Establish alternate dosimetry issue points for personnel and high range dosimetry, as necessary. ! 5.6.5.2 Issue blanket dose extensions for OSC personnel, to the limit established by the Station Health Physicist. 5.6.5.3 Provide representatives from Dosimetry and Records Control in the OSC to: - 5.6.5.3.1 Record the following information on the OSC Response Personnel Dose Record Form (Sample Enclosure 5.14) as emergency response personnel enter che OSC. 5.6.5.3.1.1 Name 5.6.5.3.1.2 Health Physics Badge Humbers 5.6.5.3.1.3 Social Security Number ! 5.6.5.3.1.4 Birthdate l 5.6.5.3.1.5 Age l 5.6.5.3.1.6 Exposure Class 5.6.5.3.1.7 Work Group f 1 5.6.5.3.1.8 Quarterly and yearly dose to date I
#l 1
5.6.5.3.1.9 Permissible lifetime dose i 1 5.6.5.3.1.10 Total lifetime dose to date ! This may be obtained at the first NOTE: I available opportunity. l
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HP/0/B/1009/09 ENCLOSURE 5.6 i CONTINUED i l 3.6.5.3.2 As personnel return to OSC from entering a
, radiation field, dosimeters shall be checked for rezeroing and the following information recorded on the OSC Response Personnel Dose Record Form (Sample Enclosure 5.14):
5.6.5.3.2.1 Date, Time . 5.6.5.3.2.2 Dosimeter Reading 5.6.5.3.2.3 Retotal of quarterly dose. 5.6.5.4 Proceed to the TSC and coordinate Support Function Response. O e
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l'tg3 1 CI 1 HP/0/B/1009/09 ENCLOSURE 5.7 SUPPORT FUNCTIONS COORDINATOR CO EINUING RESPONSE 5.7.1 Ensure collection and retention of collected samples is adequate to recon.truct data following the emergency. 5.7.2 Acquire additional anti-contamination clothing, dosimetry, respiratory or monitoring equipment from: Existing Station Stock CMC Admin and Logistics Groups 5.7.3 Direct implementation of HP/0/B/1001/12, Technical Specification Gaseous Waste Sampling and Analysis as necessary to collect containment and unit vent samples. All sampling will be coordinated with OSC Health Physics personnel to determine habitability and RWP requirements. 5.7.4 Retrieve radiation instrumentation from Instrument Issue arsa and stage in DRC office. O 9 l
Faga 1 or i HP/0/B/1009/09 ENCLOSURE 5.8 l
, STAFT (DATA ANALYSIS) COORDINATOR l INITIAL RESPONSE l 5.8.1 Assemble supporting materials and take to TSC.
5.8.2 Initiate the following procedures as necessary. 5.8.2.1 HP/0/B/1009/13, Off-Site Dose Projection - Uncontrolled Release of Radioactive Material through the Unit Vent. 5.8.2.2 HP/0/B/1009/14, Off-Site Dose Projection - Uncontrolled ~ Release of Liquid Radioactive Material. 5.8.2.3 HP/0/B/1009/15, Off-Site Dose Projection - Uncontrolled Release of Gaseous Radioactive Material other than through the Unit Vent. 5.8.3 Assume the duties of the Data Analysis Coordinator if the emergency is classified above the Notification of Unusual Event Category and: 5.8.3.1 Proceed to the TSC. 5.8.3.2 Initiate activation of the Field Monitoring Organization by notifying the Field Monitoring Coordinator to respond according to Enclosure 5.10 and 5.11. 5.8.3.3 Initiate the following procedures is necessary: 5.8.3.3.1 HP/0/B/1009/06, Alternate Methods for Determ'ining Dose Rates Within the Reactor Building. 5.8.3.3.2 HP/0/B/1009/12, Quantifying Gaseous Release through Steam Relief Valves Under Post-Accident Conditions. ! 5.8.3.4 Provide special evaluation in areas such as shielding, off-site consquences of a containment loss or steam generator tube rupture, BBA, etc.
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HP/0/B/1009/09 ENCLOSURE 5.9 , STAFF (DATA ANALYSIS) COORDINATOR ! CO.VIINUING RESPONSE 5.9.1 Evaluate'the need to recalculate dose projections based upon:
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5.9.1.1 Known changes in meterological status (wind speed, wind direction, AT, percipitation). 5.9.1.2 Known changes in EHF readings. 5.9.1.3 Projected change in meterological conditions. 5.9.2 Evaluate total effect of dose projections when making multiple releases (containment, vent releases, etc.). 5.9.3 Evaluate total effect of dose projections when releases are expected to continue for longer than two hours, or to otherwise be effected by extended evacuation times. O e .l 4
rocs a ws a HP/0/B/1009/09 ENCLOSURE 5.10 FIELD MONITORING COORDINATOR INITIAL RESPONSE 5.10.1 Assemble supporting materials and take to TSC. 5.10.1 Initial Response 5.10.2.1 Activate the field monitoring organization by: 5.10.2.1.1 Notifying the TSC Radio Operator to report to the TSC and initiate KP/0/B/1009/19,
, Emergency Radio Operations, Maintenance and Communications.
5.10.2.1.2 Selecting nine (9) Catawba Nuclear Station Field Monitoring Team (FMT) members to be organized as follows: Team Call Sign Number of Members Transportation Alpha 2 Land Vehicle i Bravo 2 Land Vehicle Charlie 2 Land Vehicle Delta . 2 Land Vehicle Echo 1 Helicopter 1 5.10.2.1.3 Instruct FMT's to complete checkout steps from HP/0/B/1009/04, Environmental Moni-toring for Emergency Conditions Within the f Ten Mile Radius of Catawba Nuclear Station. 5.10.2.2 Obtain plant radiological status and evaluate the potential or existence of an off-site release of radioactive material-(liquid or gaseous). 5.10.2.3 Obtain meterological information and determine initial i sample direction. 5.10.2.4 Determine the need for aerial environmental surveillanca based on plant radiological status and meterological information. 5.10.2.4.1 If immediately needed, obtain helicopter support per Enclosure 5.15, Procurement of Helicopters for Aerial Environmental Surveillance. 5.10.2.4.2' If the possibility exist for future need, put helicopter support on standby per Enclosure 5.15. k 5.10.2.5 Proceed to the TSC.
Pago 1 of 2 HP/0/B/1009/09 ENCLOSURE 5.11 FIELD MONITORING COORDINATOR CONTINUING RESPONSE 5.11.1 Continuing Response 5.11.1.1 Dispatch FMT's based on plant radiological status and meterological information to sample locations listed in HP/0/B/1009/04. 5.11.1.1.1 Plume location strategy should be to send FMI's back and forth across sectors to locate the plume. Only after the plume is located should detailed field monitoring begin. 3.11.1.2 Direct and implement field monitoring strategies by: 3.11.1.2.1 Reviewing plant radiological status, field data and meterological information approximately every 15 minutes for changes which might affect field monitoring strategies. 5.11.1.2.2 Directing FMT's to monitor locations. 5.11.1.2.3 Instructing FMT's to take, as needed, special samples per HP/0/B/1009/04. 5.11.1.3 Advise the Data Analysis Coordinator to field monitoring results. . 5.11.1.4 Maintain an up-to-date 10 mile radius map by: 5.11.1.4.1 Posting current FTM locations. 5.11.1.4.2 Posting latest instrument survey results for each monitoring location. 5.11.1.4.3 Illustrating approximate plume shape and location. 5.11.1.5 Maintain an organized file of all sample results/ data generated from FNT activities. 5.11.1.6 Maintain FMT equipment and supplies including protective I clothing, liquid nitrogen, etc.; and schedule shift l coverage. i 5.11.2 CMC Turnover ' 5.11.2.1 Once CMC is established, coordinate turnover of FMT's to CMC control. 5.11.2.2 Turnover of TSC FMT's to CMC Control shall occur at the intersection of SC 274 and SC 49. Should plume location interfere, alternate turnover location may be established.
Pega 2 of 2 HP/0/B/1009/09 ENCIOSURE 5.11
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FIELD MONITORING COORDINATOR CONTINUING RESPONSE 5.11.2.3 Once CMC has assumed control of FMT's, notify the Data Analysis Coordinator and dissolve TSC field monitoring organization. b e e 9 l l l
,I. ' HP/0/B/1009/09 l ENCLOSURE 5.12 l l - OPERATION SUPPORT CENTER l HEALTH PHYSICS SUPERVISOR - IFITIAL RESPONSE 1 5.12.1 Assemble supporting materials and take to OSC. I 5.12.2 Contact OSC Operation Supervisor and coordinate Health Physics support for OSC activities. Assist in implementation of RP/0/B/5000/12. 5.12.3' Provide immediate job coverage as necessary. Give due consideration to the fact that plant conditions may be unstable and radiological conditions unknown. 5.12.4 Provide immediate Health Physics coverage as necessary to support Fire Brigade, damage control, medical emergency and other emergency activities. 5.12.5 Direct technicians to obtain preliminary radiological information ' available in Control Room. 5.12.5.1' Emphasis should be placed upon determining the areas of the plant experiencing increasing radiation levels. 1 5.12.6 Based upon initial Control. Room indications, direct technicians to monitor and report radiological status which will support OSC activities. 5.12.7 Establish control over all OSC personnel radiation exposure and s limit to blanket dose extension levels. 5.12.7.1 All activities which cause these levels to be approached or exceeded, require pre planning and coordination with TSC S&C Coordinator. 5.12.8 Direct assignment of additional dosimetry to provide adequate monitoring for the conditions expected. 5.12.9 Direct the use of protective clothing to limit the spread of contamination consistent with the conditions expected. 5.12.10 Obtain additional instrumentation to support OSC activities (Teletector, neutron instrument alpha instrument, friskers), if
- necessary.
5.2.11 Require each exit from OSC to Auxiliary Building be proceeded-by a briefing on task to be done and radiological conditions expected when applicable. 5.2.12 Coordinate Health Physics activities for assessment and repair teams in accordance with RP/0/B/5000/12. I 5.2.13 Post blanket dose extension valves. i 4
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Paga 1 of 1 HP/0/B/1009/09 ENCLOSURE 5.13' OPERATION SUPPORT CENTER HEALTH PHYSICS SUPERVISOR - C0hTINUING RESPONSE i
' 5.13.1 Maintain routine contact with TSC S&C Coordinator to provide update ,
on OSC activities and to re;eive plant status reports. I 5.13.2, Obtain thru S&C Functions Coordinator additional dosimetry / protective clothing / emergency kit items necessary to i support OSC activities. 5.13.3 Coordinate OSC activities requiring pre planning. 5.13.3.1 ' Emphasis should be placed upon: Dosimetry (Whole Body & Extremities) ' Protective Clothing Route to and from task Respiratory equipment Need for Buddy System because of safety hazard ' (radiological and non-radiological) Establishing dose limits and/or dose rate considerations for high exposure jobs on unknown situations Communications equipment Additional monitoring instrumentation 5.13.4 Monitor dose rate in OSC. Shculd General Area reach 5 mR/hr., l initiate discussion with S&C Coordinatar on the need to evacuate the i OSC, should dose rate be e'pected x to continue. 5.13.5 All RE-ENTRY efforts should consider the special problems that may exint. {, High gamma fields Increased Beta fields i ) - High Contamination levels High airborne rad levels l i i e f i r i
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f . reso 1 oz 1 HP/0/B/1009/09 . ENCLOSURE 5.14 RESERVE PERSONNEL / PERSONNEL MONITORING LEADER r 5.14.1 Assemble all Health Physics personnel not initially required for emergency response. Non essential personnel should be evaluated for
, use in the emergency.
5.14.2 Identify personnel and/or personnel monitoring teams for the following locations. 5.14.2.1 All on-site assembly areas are identified in Station
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, Directive 3.0.7. . i 5.14.2.2 PAP Area. j 5.14.2.3 Construction Personnel Exit Area (Brass Gate). ! 5.14.2.4 Evacuation Facility (Alpha or Bravo). Two monitoring teams if both location are used. 5.14.3 Initiate, as necessary, HP/0/B/1009/05, Personnel Monitoring for Emergency Conditions.
- 5.14.4 Initiate random monitoring of vehicles located in the upper and
' lower parking lots starting with vehicles nearest the affected unit. The monitoring team. identified in Step 5.14.2.4 should be used for this purpose.
5.14.5 Coordinate with the TSC Surveillance and Control Coordinator on relocating personnel monitoring teams if background radiation 4 renders normal monitoring locations unfit. 5.14.6 Supervise Health Physics efforts at the Evacuation Facility (s) as per 2.4. 1 5.14.7 Provide direction to reserve Health Physics personnel: , 5.14.7.1 Direct and' control personnel in the staging area (DRC of fice in' the Administration Building) . 5.14.7.2 Coordinate with Surveillance and Control Coordinator to provide addition manpower,_as necessary. 5.14.7.3 Coordinate with Support Functions Coordinator to provide additional manpower, as necessary.
- 5.14.7.4 Direct activities of Field Monitoring Teams if relieved by CMC personnel.
5.14.7.5 - Begin scheduling activities for Health Physics personnel, f
roga i or A
, HP/0/B/1009/09 ENCLOSURE 5.16 PROCUREMENT OF HELICOPTERS FOR AERIAL ENVIRONMENTAL SURVEILLANCE Inland Airways, Myrtle Beach, S.C., is under contract to Duke Power Company to furnish one helicopter upon request and an additional helicopter within six hours following notification. Once a helicoptar is requested, there is a maximum elapsed time of three hours for the helicopter to arrive at Catawba Nuclear Station or other dispatched locations.
Helicopter service is limited to daylight hours and adequate flying weather. The helicopters will hold three people, the pilot and two passengers. To perform surveys, instrumentation may limit the passenger . pace. To obtain helicopter (s) for emergency service contact: Office Home
- 1. B. A. Turpin 704-331-4319
- 2. L. W. Johnson 704-331-4172
- 3. L. M. Whisonant 704-331-4173 M 4 D. M. Staggs 704-331-4157 6 NOTE: Thase contacts are in Duke Power Company Transmission Dept.,
Line Division. The microtlave extension for the office numbers is 220. l l l 1
l l HP/0/B/1009/12 QUANTIFYING GASEOUS RELEASE THROUGH S1T.AM RELIEF VALVES UNDER POST ACCIDENT CONDITIONS (DECEMBER 1983) 1 s 4 8 1 e _ , - - - -_~_
Form 34731 (1041) (Formerly SPD 10021) i DUKE POWER COMPANY (1) ID No: HP/0/B/1009/13 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD 1 Incorporated (2) STATION: CATAWBA (3) PROCEDURE TITLE:0FFSITE ' DOSE PROJECTION - UNCONTROLLED RELEASE OF RADIOACTIVE MATI.J.IAL THROUGH THE UNIT VENT (4) PREPARED B kW '- r - JATE: &!4!/ (5) REVIEWED BY k b. # I DATE: 7- [- Cross-Disciplinary Review By: N/R: J7.h.A. (6) TEMPORARY APPROVAL (IF NECESSARY): ! I By: (SRO) Date: j i By: Date: I (7) APPROVED BY: U-Date: k (8) MISCELLANEOUS: i Reviewed / Approved By: Date: , Reviewed / Approved By - l Date , i i [ i i l l' \ I
l 1 HP/0/3/1009/13 { DUKE POWER COMPANY CATAWBA NUCLEAR STATION OFFSITE DOSE PROJECTION - UNCONIlt0LLED RELEASE OF RADI0 ACTIVE MATERIAL 110t00GH THE UNIT VENT 1.0 PURPOSE This procedure describes the method for projecting the potential offsite dose following an uncontrolled release of radioactive materials through the unit vent.
2.0 REFERENCES
2.1 EPA-520/1-75-001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents 2.2 Regulatory Guide 1.109, Calculation of Annual Doses to Man From ' Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I 2.3 Letter from Civil / Environmental Division CN-1108.1, 1434.00, 1227.00 Atmospheric Dispersion Factor for Emergency Planning 2.4 Regulatory Guide 1.4, Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors-l 3.0 IMITS AND PRECAUTIONS 3.1 Use actual sample data when possible. Radiation monitor readings are susceptible to several sources of error. When radiation monitor readings are used for downwind concentrations, nota this in the report of offsite dose assessment. i 3.2 Environmental data should be collected and analyzed to verify these calculations. This procedure considers all releases to be ground level releases. 3.3 This procedure applies to releases made from Catawba Nuclear Station only. Many of the values contained in this procedure are site specific. 4.0 PROCEDURE 4.1 Obtain the following information from the Control Room and record it 4 on Enclosure 5.1 (Vent Release Data Sheet). , 4.1.1 Time of reactor trip.
- 4.1.2 Lower tower wind speed in MPH.
- _ . _ . ~ ,_ . - - . - ~ . _ . - -
KP/0/B/1009/13 Paga 2 cf 5 4.1.3 Direction from which the wind is blowing in degrees from North (Tower Wind). 4.1.4 Temperature gradient in degrees C. 4.1.5 Vent discharge flow rate in CFM. 4.1.6 Available weather forecast information.
, 4.2 Determine the release concentration as follows:
4.2.1 If vent sample analysis is not available, go to Step 4.2.4. 4.2.2 Obtain the following vent sample analysis results and record on Enclosure 5.1. Date/ time of sample. 4 4.2.2.1 4.2.2.2 Gross noble gas concentration in pCi/al. i 2 4.2.2.3 Iodine equivalent conc 6ntration (or data for calculation). 4.2.2.4 Gamma E-bar value in mov/ dis (or data for . calculation). 4.2.3 Go to Step 4.3 l l 4.2.4 Obtain the following unit vent data and record on . sample Enclosure 5.1: I 4.2.3.1 Date/ Time of collection. ! i 4.2.3.2 EMF 36 Low and High range readings in cps (gas I monitor). ! 4.2.3.3 AEMF37 reading in cpm (iodine monitor). t 4.2.3.4 At in minutes tur AEMF37 reading. , 4.2.3.5 Calculate release concentrations as shown on Enclosure 5.1. 4.3 Project the impact of the release on the downwind population by using the manual calculations outlined below. !, 4.3.1 Determine the X/Q values for each point of interest 1 downwind as fallows.
^
I NOTE: If no points have been requested, use the .5, 2, 5 and 10 mile values. i
. i
- , - . ..,-,-n-,,,_, - , ,.g.-, , , ., - - - - . , - - - - - .n-, - -,e -
HP/0/B/1009/13 Pcgo 3 ef 5 4.3.1.1 From Enclosure 5.2 (Table of h o-Hour Relative Concentration Factors), locate the relative two hour concentration value (CH) for each point , and record on sample Enclosure 5.3 (Manual j Calculation Worksheet), (Reference 2.3). j 4.3.1.2 Convert these values to X/Q by, 1 CH(MPH-Sec/m*) IN
- Wind Speed (MPH) 4.3.1.3 Record results on Enclosure 5.3 (Nanual Calculation Worksheet).
4.3.2 Calculate the gas and iodine downwind concentrations for each point using the equation, Coney = Coney *F y
- X/Q
- U DWC l where, l
Conc = wnwind concentration (uci/ml) DW Coney = vent discharge concentration (yCi/ml) Fy = vent discharge flow rate (CFM) X/Q = dispersion factor in sec/m* U DWC = unit c nversions derived from (2.832E-2m 3
/fts ),
(0.017 min /sec) = 4.8E-4 ft*
- see Sample Enclosure 5.3 provides work space for this calculation.
l 4.3.3 Determine the potential whole body gamma dose downwind i using the gas concentrations calculated in 4.3.2 and the equatica, D WB "U * * *
- G "*DW I
j where, i l kB = wh le body gamma dose due to submersion in a cloud of radioactive gas (res) l 1 I l
HP/0/B/1009/13 Pass 4 cf 5 U " **'* *******I " ** "' G 3.7E4 (dis /sec-pC1)(1cc/1.2E-33) (1.602E-6 erg /MeV) (g - res/100 ergs)
*~#**~""
1/2 = 2.5E-1 pCi-sec-MeV (2.5E-1 is-res-es ( 0 see) pCi-hr-Mev hr ! #**~'"
= 9.00 E2 pCi-hr-Mev NOTE: 1/2 is the constant used (in the case of gamma radiation) when assuming that the receptor is exposed to only one-half the cloud owing to the presence of the ground, (Reference 2.4).
Coney = downwind concentration (pCi/al) Time = projected duration of exposure (hrs); use 2 hours unless otherwise directed. E = average gamma energy per disintegration (Mov/ dis) I NOTE: If 5 cannot be obtained from the sample results, the following values may be used: Nours from Trip E_fMev/ dis) 0-12 0.40 12-48 0.20 48-= 0.10 4.3.3.1 Record results on Enclosure 5.3. 4.3.4 Determine the potential child thyroid dose downwind using the iodine concentrations calculated in 4.3.2 and the equation, Dg =U
- Conc *
- 7 DW where, Dg = thyroid dose due to uptake of radioactive iodine (rea) t
HP/0/3/1009/13 Page 5 cf 5 Ug = constants derived from a child's breathina rate (1.17E2 cc/sec.), I-131 dose conversion factor (4.39 E-3 ares /pci), and coversion of pCi to 6 WCi (10 ), ares to roe (10 a), and hrs. to sec cc
- Rea (3600 secs /hr) = 1.86E6 yci
- hr Conc = downwind concentration of iodine (uCi/ml)
CW Time = projected exposure time (hrs); use 2 hours uriless otherwise directed.
. 4.3.4.1 Record results on sample Enclosure 5.3.
4.3.4.2 Project the adult thyroid dose by dividing the child dose by two (2).
- l. 3.4.3 Record results of all calculations on Enclosure 5.5 (Dose Assessment Report).
4.4 Determine .he poten:ially affected area using the method outlined in Enclosure 5.4. 4.4.1 Record sectors on Enclosure 5.5. 4.5 Complete sample Enclosure 5.5 and submit it to the Station Health Physicist. Include any comments and information pertinent to the evaluation of offsite hazards. 4.6 Maintain a file of all worksheets and printouts used in dose calculations. 5.0 ENCLOSURES 5.1 Sample of Vent Release Data Sheet 5.2 Table of "No Hour Relative Concentration Factors 5.3 Sample of Manual Calculation Worksheet 5.4 Evaluation of Plume Location 5.5 Sample of Dose Assessment Report l l
Pegs 1 of 1 ENCIASURE 5.1 NP/0/3/1009/13 VENT RELEASE DATA SHEET Unit Dite/ time of Rx trip / METEOROLOGICAL DATA
- 1) Lower Tower Wind Speed MPH
- 2) Lower Tower Wind Direction From
- 3) Temp. Gradient (AT) *C
- 4) Vent Flow CFM
- 5) Date/ time /
VENT SAMPLE ANALYSIS
- 1) Total Gas yC1/ml
- 2) I-131 1.quiv. _ pCi/ml
- 3) Gas E Mev/ dis (Gamma)
VEST MONITOR DATA
- 1) EMF-36L (lo range) CPM
- 2) EM-36H (hi range) CPM
- 3) AEE -37 (iodine) CPM; At min CALCULATED DISCHARGE CONCENTRATION
- 1) Gas (Use hi readings if EMF-36H is > 100 CPM)
" Coney ,y = (EMF 36L CPM) = VCi/ml, or Conc "( ~
"} "
V-hi
"'I "'"
-2.70E7 4.0E3 pCi pCi pCi/ml
- 2) Iodine Coney,7 = (AEMF-37 CPM) (2.4E-10) = pCi/ml At
I8ect csunl' 5.2 alp /0/"/1009/13 TWO-HOUR RELATIVE C001CENIRATIO81 FACTORS (Cil) feeperature Stability Olstance (Miles) Clfference Class (*C) .5 l 2 3 4 5 6 7 8 9 IP
)< .6 A 1.4E-5 1.2E-6 5.9E-7 4.1E-7 3.2[-7 2.5E-7 2.oE-7 1.9E-7 1.80-7 1.6E-7 1.5E-7
- 2) .6 to .5 8 1.5E-4 4.5E-5 1.3E-5 6.3E-6 3.9E- 6 2.7E-6 1.9E-6 1.4E-6 1.lE-6 8.3E-7 7.8E-7
- 3) -0.4 to-0.2 C 3.8E-4 1.4E-4 4.9E-5 2.7E-5 1.7E-5 1.2E-5 9.2E-6 7.3E-6 6.0E-6 5.0E-6 4.3E-6
- 4) -0.1 te+.4 0 6.9E-4 2.5E-4 9.6E-5 5.5E-5 3.5E-5 2.5E-5 2.0E-5 1.6E-5 1.3E-5 1.1E-5 9.7E-6
- 5) 4.5 to +1.2 E 1.1E-3 5.1E-4 2.0E-4 1.2E-4 8.2E-5 6.3E-5 5.1E-5 4.30-5 3.80-5 3.3E-5 3.0E-5
- 6) > 1.2 E 1.8E-3 1.10-3 4.3E-4 2.7E-4 2.0E-4 1.7E-4 1.3E-4 1.2E-4 8.6E-5 7.8E-5 7.3E-5 f rom other sources of meteorological data (Section 4.1) use the wind speed and time of day to determine which row of CH values to use:
ideo er Day Wind Sc9.gd Row # 13300 A.M. - 4:00 P.M. N/A 3 000 P.M. - 10:00 A.M. > 15 MPil 4 C800 P.M. - 10:00 A.M. 5 IS MPH 6 a
ENCI.05URC 5.3 . Ill*/0/ll/1009/13 . MANUAL cal.CULAT10N WORKSilEET s . ) Dischare;e Concentratio'n (Conc,): 2) Vent Dischar! s> flow Ra te: 3) Wind Speed: ,
. Gas =. __. _
i,c i/ml f y= ._. ....._...__...CfM .. ._ _ _ .MI'l l lodine = __ _ _ ,__.__pci/ml . ) Two llour Relative Conc. Iactors 5) llownwinal Concentrations 3 fb sec-a h/m - X/ ) = bl/n h sec/m ) Conc D.W
= Coneyfy X/4 - (4.8E-4 y- 7 {c)
A) Gas 8) Indine 3 O-- Cil = ; X/Q = __.__.,_____ Sec/m
.M i Conc g3g
=
.--...---...pCi/ml Conc DW
=
- pCi/mi 9 Mi ,_; X/Q = __ _._.,_ _ Sec/m Cll = _. _ __ Conc DU
=
---- pC i/ml Conc)W 1
=
1,C I/m" 3 P 'Mi CII = ; X/Q = _ _ ____,Sec/m =
- - _ _ __.pCi/ml Conc py pCi/m' ConcI )W =_____
O ili Cll = ; X/Q = ,_ i Sec/m - _ pCi/ml ConcDW = - Conc DW
=
- - ------ -_pC i /m'
- 6) I'otential Whole llody Gansna Dose; 7) Potential Child Thyroid Dose; Time = hours Dyg = (9.00E7) Conc C Tine r (1.86E6) Tine DW D(gy ConcDW b" _ . . . . . . . . _ . _ . Mev/ dis 0 -_ . . .M i D yg = li ggy = . _ _ ___ _ ._,_ _ .. Rem
. _ , , _ _ . . Rem H.--.------..- _ _ _...M i Dwg =
. . _ . . . . . _ __. . . . . .R e m D Igy =
. . . . . . . ltem
=
N . - - - - _ ..._ . . . .
.H i D 93 . . . _ _ . _ __ _ _ . item D gny = ........ ____. ___ _ llem 9
---.__......_..__..Mi l',;g =
, . . . . . . _ _ . . ___ . . . . R e m D IIIy . . . _ .. . . ... . . .. . .R em
r. Pcga 1 ef 2 ENCLOSURE 5.4 HP/0/3/1009/13 EVALUATION OF PLLHE I4 CATION
- 1. Acquire the following information from Enclosure 5.1 and record on
- Enclosure 5.5.
a) wind direction in degrees from north b) wind speed (sph)
- c) AT (*C) d) Stability Class -
e) thyroid and whole body doses
- 2. Protective action guides submitted to the Station Health Physicist are to be made based on the calculated dose on Enclosure 5.1 and the fol'1owing information.
a) For doses:
> 5 Rem Whole Body or,
> 25 Rem Thyroid Recommend Evacuation of Population in Affected Area.
B) For doses: 1-5 Rea Whole Bony or, 5-25 Res Thyroid Recommend evacuation of children and pregnant women, and sheltering of remainder of personnel in the affected area. ( C) For doses:
< 1 Rem Whole Body or,
< 5 Rem Thyroid -
Recommend no action.
- 3. Determine the affected zones, based on wind direction and wind speed, with the following tables.
Table 3.1 0-2 Mile Affected Zones Wind Direction Affected Zone 0* - 360* A0
-- , +- - . , , - - , - - . - - -
Y ENCLOSURE 5.4 i l HP/0/3/1009/13 EVALUATION OF PLUME LOCATION l Table 3.2 2-5 Mile Affected Zonas Wind Speed < 5 mph Wind Speed > 5 mph Wind Direction Affected Zones Wind Direction Affected Zones 0* - 360* A1,Bl,C1,D1,El,F1 0.1* - 22' C1, D1 22.1* - 73* C1, D1, El 73.1* - 108' C1,D1,El,F1 108.1* - 120' D1, E1, F1 120.1* - 159' El, F1 159.1* - 207' El, F1, Al 207.1* - 247' F1, A1, B1 247.1* - 265* A1, B1 265.1* - 298* A1, B1, C1 298.1* - 338' B1, C1 338.1 - 360* B1, C1, D1 Table 3.* 5-10 Mile Affected Zones i Vind Direction Affected Zones i 0.1* - 27' C2, D2 27.1* - 69' C2, D2, E2 69.1* - 95* D2, E2, F2 95.1* - 132' D2, E2, F2, F3 132.1* - 144' E2, F2, F3 144.1* - 160* E2, F2, F3, A2 160.1* - 201' F2, F3, A2 l 201.1* - 229' F2, F3, A2, B2
- 229.1* - 249' F3, A2, B2 249.1' - 259' A2, A3, B2 259.1* - 290* A2, A3, B2, C2
. 290.1* - 304* A3, B2, C2 304.1* - 333' B2, C2 4
333.1* - 360' B2, C2, D2
- 4. Record sectors requiring protective action on Sample Enclosure S.S along with the recommended protective action.
i a S
Y ENCIDSURE 5.5 DOSE ASSESSMENT REPORT EP/0/3/1009/13 Duke Power Company Crisis Management Plan Off-site Dose Report - Catawba Prepared By Date/ Time / Emergency Drill (Circle One) Meteorology Wind Speed MPH Wind Direction Degrees from North Vertical Temp. Diff. Degrees C/100ft. Stability Class (Circle One) ABCDEFE i Source Tern Time Noble Gas 1-31 es. I Containment Rad. Monitor R/hr. R/hr Containment Sample pCi/el' WCi/mi 4 Unit Vent (Sample or EMF) pCi/mi DCi/mi ! Curie Release Rate Ci/see Ci/se: Corresponds to: LOCA LOCA through filter ! Core Damage Core Damage through filter j Tube rupture Gas Decay Tank i New Fuel Old fuel Other Dose Projections
.5 mi 2 mi 5 mi 10 mi 2 hr Dose (rea) based Whole Body
- _
on Containment release Child thyroid 9 al/hr 2 hr Dose (rea) based Whole Body on Unit Vent release Child thyroid j $ cfm ) ......................................... 4 I 2 hr Dose (rea) based Whole Body on Steam release Child thyroid 0 l 2 hr Dose (rea) based Whole Body
- on release Child thyroid i @
l Field Monitoring Data j Location Distance Direction Dose Rate (ares /hr) Contamination l , (mi) Whole Body Child Thyroid (dpe/100 cm2) i I i i Affected Zones 0-2 mi 2-5 mi 5-10 mi 9-10 mi (Circle Zones) A0 Al 31 C1 D1 El F1 A2 B2 C2 D2 C2 F2 A3 F3 ,, Comments: . i XC: Data Analysis Coordinator, Station Health Physicist l l
T Form 34731 (1041) (Formerly SPD 10021) DUKE POWER COMPANY (1) ID No: HP/0/B/1009/14 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD 0 Incorporated (2) STATION: CATAWBA (3) PROCEDURE TITLE: HEALTH PHYSICS ACTIONS FOLLOWING AN UNCONTROLLED RELEASE OF LIOUID RADI0AC*tIVE MATERIAL (4) PREPARED B ' kN '-
- _ DATE: 2,
/
t /
/
(5) REVIEWED BY: k. ). /N'- DATE: J -/- k Cross-Disciplinary Review By: N/R: A >>2 A4 (6) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: By: Date: (7) APPROVED BY: y U-I Date R[1 I I
$[
(8) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: l l i l l
HP/0/3/1009/14 DUKE POWER COMPANY
, CATAWBA NUCIE.AR STATION MEALTH PHYSICS ACTIONS FOLLOWING AN UNCONIt0LLED RELEASE OF LIQUID RADI0 ACTIVE MATERIAL 1.0 PURPOSE
- D is procedure describes the methods to be used for calculating the radionuclide concentration at area water intakes following an uncontrolled release of liquid radioactive material, and the subsequent actions to be taken when the concentration exceeds Technical Specifications.
2.0 REFERENCES
2.1 HP/0/B/1009/04, Environmental Monitoring for Emergency Conditions Within the Ten Mile Radius of Catawba Nuclear Station 2.2 I Control Room Unit Data Book ^ 2.3 10CFR20, Appendix B Table II, Column 2 2.4 CNS FSAR Sections 2, 11, 12 and 15 I 1 2.5 CNS Technical Specifications Sections 3/4.3, 3/4.11 and 5.0 l 2.6 Letter to Master File CN-1227.00 Dilution Factor - Rock Hi1* Intake from Design Engineering dated February 23, 1983 I l ] -2.7 CNS Emergency Plan l 3.0 LIMITS AND PRECAUTIONS 3.1 The full implementation of this procedure should be used in emergency situations that could result in the contr ina? ion and possible shutdown of area water supply intakes. 3.2 Full implementation of the protective actions in this prococ are require station management authorization. ! i 3.3 This procedure is for use under abnormal conditions and results in conservative reconnendations. Care must be exercised to ensure only appropriate actions are taken. 3.4 Conservatism exists in the calculations utilized in this procedure and includes, but is not limited to: 3.4.1 Decay 3.4.2 Dilution factor I 3.5 Transit time from CNS to the nearest municipal water intake is reduced from three days to one-half day under extreme meteorological conditions (Ref CNS FSAR 2.4.12). I
HP/0/B/1009/14 Paga 2 cf 3 i j 4.0 PROCEDURE 4 ?1 Health' Physics will determine concentration of effluent released
, from site boundary by the following method (s):
4.1.1 Determine effluent concentration from EMF-49 if possible. Concentration may be determined from analysis of sample drawn directly from EMF sample tap, if necessary. NOTE: Conversion graph for EMF data from CPM to uCi/ml ,
! located in Control Room Unit Data Book. '
, 4.1.2 Determine effluent concentration from volume and activity i
; if release is made from other than through Waste Liquid Systes, if possible.
4.1.3 Collect representative sample from Environmental Sampling Pier (Location Site #A0 1 46) at Station Service Water Discharge Canal and analyze sample for concentration. 4.1.4 Should utilize most restrictive (highest) concentration from applicable procedure Steps 4.1.1, 4.1.2, 4.1.3 above. 4.2 Determine the potential for contamination of area water supplies
; using Enclosure 5.1 (Transit Time /Radionuclide Concentration Calculations) and saepling data from Health Physics.
- 4.3 If data indicates that a release made through the Station Service I'ater Discharge Canal to Lake Wylie will exceed 10CFR20, Appendix B, Table II, Column 2 limits at affected area water intakes, Health Physics shall recommend the following to the Emergency Coordinator:
4.3.1 Request minimum flow at Lake Wylie Hydro Station from Systes Load Dispatcher (to extend transit time). NOTE: Transit time to Rock Hill water intake is approximately 14 days with NO FLOW through Lake l Wylie Dam, (based on das leakage rate). l ! 4.3.2 Request Field Monitoring Teams (FMT) to track the release { by sampling and evaluation of sample concentrations taken ! ! from discharge point at Environmental Sampling Pier 1 (Location Site # A0 1 46), above Lake Wylie Dam (Location ' l Site # B14 5), directly below Lake Wylie Dam (Location l 1 Site # B1 4 6), and at Rock Hill municipal water intake l j structure (Location Site # C2 7 8), per Ref. 2.1, as deemed q necessary. , NOTE: Transit time is calculated as three days under j normal meteorological conditions with all units in operation at Lake Wylie Hydro Station. 4.3.3 Notify (through the State) the area water supply pumping i stations that a release of radioactive saterials to Lake Wylie has occurred and that limited protective actions ] (sampling and analysis) are being taken. ?
^' HP/0/5/1009/14 Page 3 ef 3 4.3.3.1 In the event that sampling confirms the contamination levels at area water intakes will exceed 10CTR20, Appendix B, Table II, Column 2
~
limits, request (through the state) that area water pumping stations cease operations during the period of time contaminated water is passing the pumping station intakes (see Enclosure 5.2). 4.3.4 Request System Load Dispatcher regulate flow through das as required.
~
NOTE: Maximum flow'through das will allow " boxcar" to pass critical areas in least time. 4.4 Discontinue environmental surveillance efforts when concentration (contamination levels) indicate that protective actions are no
, longer appropriate.
5.0 ENCLOSURES 5.1 Transit Time /Radionuclide Concentration Calculation 3
DUKE P0b7.R COMPANY Pcg3 1 cf 2 - CATAWBA NUCLEAR STATION EP/0/3/1009/14 i
' SAMPLE ENCLOSURE 5.1 TRANSIT TIME /RADIONUCLIDE CONCENTRATION CAICULATION
]
DESCRIPTION Transit time (s) and radionuclide coricentration(s) for an uncontrolled release of liquid radioactive asterials from a Catawba Nuclear Station release point to the municipal (or industrial) water intake structures of Rock Hill, Celanese Tibers Company (Rock Hill), Fort Mill and Springs Mills, Inc. (Fort Hill). ; NOTE #1: All municipal or industrial water intake concentration calculations
, are based on Rock Hill water intake sampling point unless specified l otherwise by Station Health Physicist or Emergency Coordinator.
CNS Discharge Formula Test Water Transit Time Dilution ( 1 ) Formula Point Criteria Intake (NOTE #2) Factor ft' Required via WL System Conc and Vol Rock Hill 3 days 4 x 10 #1 (dischs header) known .
~
other than Conc and Vol Rock Hill 3 days 4 x 10 ' #2 i WL System known via WL System Cone and Vol Rock Hill 3 days 4 x 10 #3 (dischs header) unknown other than Conc and Vol Rock Hill 3 days 4 x 10 #3 j WL System unknown 4 i
' 7TE #2: Transit time assumes all units in operation at Lake Wylie Hydro Station.
BR, . FORMULAS: #1 - C, = C,x D x (time (RR, + RRd )} * . Ed
#2 -
C, = C, x D x Vk '
#3 -
C, = C, x D x V, (see NOTE #3) ! Where: C , = Radionuclide concentration at municipal water intake (uC1/al) l C, = Undiluted discharge point concentration (uci/al) D = dilution factor (4 x 10 I) ft' time = taken from WL Release Worksheet (sec) - (time,WPfr pump is running) l i
^
DL'XI P0bT.F COMPANY Paga 2 ef 2 CATAVIA NUCLEAR STATION
- HP/0/5/1009/14 SAMPLE ENCIOSURT 5.1 {
TRANSIT TIME /RADIONUCLIDE CONCENTRATION CAIIULA ( RR, = effluent release rate (cfs) - (from VL Release Worksheet) , RR , d = RL (and RN) flow rate (s) (cfs) 1 RR, = dilution variable (no units) RR d Vk = known volume (ft.8) 8 V, = 13,268,000 ft [dischargecanalvolume)
~
Conversion Factors: cfs = (2.22'x 10 8 cfs/gpa (Xgpm) ft* = gal /7.481 NOTE #3: When using formula #3, must assume entire con (Undiluted effluent concentration). e W e
Form 34731 (1041) (Formerly SPD 10021) ' DUKE POWER COMPANY (1) ID No: HP/0/B/1009/15 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD 0 Incorporated (2) STATION: CATAWBA (3) PROCEDURE TITLE: OFFSITE DOSE PROJECTIONS - UNCONTROLLED RELEASE OF RADIOACTIVE MATERIAL OTHER *4.dN THROUGH THE UNIT VENT (4) PREPARED BY: ,_ DATE: / by / (5) REVIEWED BY: k 3. UI DATE: - Cross-Disciplinary Review By: MN N/R: (6) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: By: Date: (7) APPROVED BY: R- Date: / M (8) MISCELIANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: e
. . j D e 8 "O t
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j 1 s 1 ! l HP/0/B/1009/15 DUKE POWER COMPANY CATAWBA NUCLEAR STATION OFFSITE DOSE PROJECTIONS UNCONTROLLED RELEASE OF GASEOUS RADI0 ACTIVE MATERIAL OTHER THAN THROUGH THE UNIT VENT { 1.0 PURPOSE - i To describe an approved method for projecting dose commitment from a i,. noble gas or iodine release, other than a unit vent release, during an emergency. .
2.0 REFERENCES
. 2.1 Reg Guide 1.109 l 2.2 Reg Guide 1.4
) i 2.3' HP/0/B/1009/06, Alternative. Method for Determining Dose Rate Within
- the Reactor Building I
; 2.4 Variables used in HP/0/B/1009/15, Letter File Number CN.: 134.10 3.0 LIMITS AND PRECAUTIONS l
l 3.1 It is assumed that the iodine whole body dose from a release is very i smell compared to the iodine thyroid dose. Thus, iodine whole body
- dose is not considered here.
- 3.2 This procedure applies to releases made from Catawba Nuclear Station
! only. Many of the values contained in this procedure are site specific. 3.3 This procedure considers all releases to be ground level releases. { 4.0 PROCEDURE
- 4.1 Acquire the following information and record on sample Enclosure 5.1.
4 NOTE: Should site meteorological data be unavailable, obtain wind speed and wind direction from the National Weather .: j Service (United States Government - National Oceanic & Atmospheric Administration). i NOTE: If appropriate, obtain advance meteorological data to calculate doses due to changing meteorological conditions. 4.1.1 Reactor Unit, date and time of reactor trip. i 4.1.2 Iower tower wind speed (aph). ~
\
4.1.3 Tower wind direction in degrees from North (North = 0'). i
- t
! 4.1.4 Temperature gradient (AT*C).
HP/0/B/1009/15 Pega 2 cf 4 4.1.5 Radiation Monitor (EMF 53A or 535) reading (R/hr) or calculated per Reference 2.3. 4.1.6 Date and time of calculations. 4.2 Determine the Containment Building leakage rate (LR) and record it on sample Enclosure 5.1. 4.2.1 LR (al/hr) is the total leak rate for the containment which is one of the following: 4.2.1.1 a "best guess" assumption, 2 4.2.1.2 the measured leak rate where suitable means are available; 4.2.1.3 The design leakage rate (LRDM) "hi*h i* d***#"i"'d by: LRDM = Containment Volume
- Des!.gn Leak Constant
= 2.83 x to al
- 0.0025 ,_ day day 24 hr s
= 2.95 x 10 al/hr 4.3 Determine the X/Q values for each point of interest downwind acd record on Enclosure 5.1.
If no points have been requested, use the .5, 2, 5 and 10 mile values. 4.3.1 Locate the relative svo-hout downwind concentration value (CH) for each point from Enclosure 5.2 and record onto sample Enclosure 5.1. 4.3.2 Convert these values to X/Q by, , X/Q = CH (MPH-Sec/m8 ) Tower Wind Speed (MPH) 4.4 Determine the potential whole body dose from submersion in a cloud of noble gas and record on Enclosure 5.1. 4.4.1 Calculate the whole body two (2) hour dose commitment, Dyg = DRg
- M
- X/Q
- UNG Where, kB = Whole body two (2) hour dose commitment DR3 = Monitor dose rate
HP/0/B/1009/15 Pag 2 3 cf 4 ADC = Average Decay constant for noble gases = 2.2622E-2 DCi
- MeV*hr 8 s1*d*R LR = Containment leakage rate in al/hr X/Q = dispersion factor in sec/m a (3.7E4/sec*uci) (1.6E-6erms/MeV) X ADC =
U NG
= 2 (100 orgs/g-rad) (1.2E-3 3/ca 8) (1E6cm*/a*)
5.7E-9 hr 8-e8 - rad al-R-sec 4.5 Determine the potential thyroid dose from uptake of radiciodine and record on Enclosure 5.1. 4.5.1 Locate the time plus one (1) hour after trip on Enclosure 5.3 and record the corresponding Decay Constant on Enclosure 5.1. 4.5.2 Calculate a child's thyroid two (2) hour dose commitment using time plus one (1) hour, DR = DRg
- DC
- LR
- X/Q
- U y T
Where, DR = thyisid two (2) hour dose commitment T , DRg = monitor dose rate uCi
- mees *hr8 DC = Decay Constant in e1
- pCi
- R for time plus one (1) hour (see Enclosure 5.3)
LR = Leak rate in al/hr 4
- X/Q dispersion in sec/m a Ug = breathing rate for child times uCi to pCi conversion factor DCi-rem s 8 -pCi-res 8
(1.17E-4a /sec) 1E3 pCi-area = 1.17E-1 see -uci-ares
, .--,.y . _ - . . -m - , , , .- _.___....w. _.. .- - - . _ , , , - _, .
HP/0/8/1009/15. Paga 4 ef 4 4.6 Determine the potentially affected zones using Enclosure 5.4. Record the affected zones on Enclosure 5.5.
, 4.7 Complete Enclosure 5.5 and submit it to the Data Analysis Coordinator. Include any comments pertinent to the evaluation of offsite hazards.
5.0 ENCLOSURES 5.1 Sample Projected Offsite Dese Released From Containment 5.2 Sample Table of Two Hour Relative Concentration Factors (C ) H 5.3 Sample Table of Iodine and Noble Decay Constant (DC) 5.4 Sample of Evaluation of Plume Location 5.5 Sample Dose Assessment Report 5.6 Estimation of Containment Leak Rate i 4
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Page 1 of 2 ENCLOSLRE 5.1 HP/0/B/1009/15 PROJECTED OFFSITE DOSE RELEASED FR0!! CONTAINMEST Unit Date/ Time of Reactor Trip / METEOROLOGICAL DATA
- 1. Tower wind speed sph
- 2. Tower wind direction *
- 3. Temperature gradient (AT) *C MONITOR DATA
- 1. E!!F 53A or 53B/ Survey Inst. # , DR = R/hr 3
(Circle One) NOTE: If containment monitor information is not useable, refer to Reference 2.3. DOSE CALCULATION DATE/ TIME
- 1. LR ml/hr
- 2. CH 0 "I* * ' /0 " ***/"'
Cg@ mi. = , X/Q = sec/m' Cg 8 mi. = , X/Q = sec/m 8 CH 8 "i* " ' X/0 " ***/"' A. Whole Body 2 hr. dose projection from noble gases: by Dgg = DR3 *LR
- X/Q
- 5.7E-9, Miles Out g.B 2 hr Dose Commitment
l Page 2 of 2 ENCLOSURE 5.1 HP/0/B/1009/15 PROJECTED OFFSITE DOSE RELEASED FROM CONTAIN}iEST B. Thyroid 2 hr. dose projection from iodine: DC , by DR = DRg
- DC
- LR
- X/Q * (1.'17E-1),
T Miles Out D WB DEFINITIONS D WB
= whole body 2 hour dose commitment from noble gases thyroid 2 hr dose commitment from iodine '
DRT= LR = containment leakage rate X/Q = " Chi over Q" is downwind concentration correction factor i
=
C H 2 hr relative downwind concentration - MPH (X/Q
- HPH) [
t DC = Decay constant ! DR 3
= dose rate at the containment monitor
{
+
l 6
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[NCLCSUME 5.2 , ilP/0/8/ID09/15 TWO-MOUR RELATIVE CONCENTRATION FACIORS (C ) II . T empe ra ture Stability Distance (Miles) . Ca rre rence Class ('C) .5 1 2 3 4 5 6 7 ,,8 9 30
- 1) < .6 A 1.4E-5 1.2E-6 5.9E-7 4.1E-7 3.2E-7 2.5E-7 2.0E 1.9E-7 1.8E-7 1.6E-7 1.5C-7
- 2) .6 to .5 ,
8 1.5E-4 4.5E-5 1.3E-5 6.3E-6 3.9E-6 2.7E-6 1.9E-6 1.4E-6 1.1E-6 8.30-7 7.8E-7
- 3) -0.4 to -0.2 C 3.8E-4 1.4E-4 4.9E-5 2.7E-5 1.7E-5 1.2E-5 9.2E-6 7.3E-6 6.0E-6 5.0E-6 4.3E-6
- 4) -0.1 to +.4 D 6.9E-4 2.5E-4 9.6E-5 5.5E-5 3.5E-5 2.5E-5 2.0E-5 1.6E-5 1.3E-5 1.1E-5 9.7E-6
- 5) +.5 to +1.2 E 1.1E-3 5.1E-4 2.0E-4 1.2E-4 8.2E-5 6.3E-5 5.1E-5 4.3C-5 3.8E-5 3.3E-5 3.0E-5
- 6) > 1.2 F 1.8E-3 1.1E-3 4.3E-4 2.7E-4 2.0E-4 1.7E-4 1.3E-4 1.2E-4 8.6E-5 7.8E-5 7.3!-5 from otleer sosarces of meteorological data (Section 4.1) use the wind speed and time or day to determine which row of C valves to use: il lire or D4x Wind soeeg gow_s 12:00 A.M. - 4:00 P.M. N/A 3 4:00 P.M. - 10:00 A.M. > 15 MPH 4 4:00 P.M. - 10:00 A.M. 5 15 MPil 6 i
t
ENCLOSURE 5.3 PACE 1 OF 1 TABLE IODINE & NOBLE DECAY CONSTANT (DC) 0 - 498 HRS ]h HP/0/B/1009/15 HOUR DC HOUR DC HOUR DC HOUR DC HOUR DC 0 2.0649E-05 100 5 6125E-04 200 6.8707E-04 700 7.4438E-04 400 7.9109E-04 2 5.7902E-05 102 5.6595E-04 202 6.8925E-04 302 7.4537E-04 402 7 9197E-04 4 8.1506E-05 104 5.7050E-04 204 6.9060E-04 304 7.4636E-04 404 7.9285E-04 6 1.0296E-04 106 5.7492E-04 206 6 9194E-04 306 7.4735E-04 406 7.9373E-04 8 1.2295E-04 100 5 7920E-04 208 6.9326E-04 308 7.4833E-04 408 7.9460E-04 10 1.4170E-04 110 5 8335E-04 210 6.9457E-04 310 7.4932E-04 410 7.9548E-04 12 1.5933E-04 112 5.8737E-04 212 6.9506E-04 312 7.502?E-04 412 7 9635E-04 14 1.7591E-04 114 5.9127E-04 214 6.9714E-04 314 7.5127E-04 414 7.9722E-04 16 1 9159E-04 116 5.9504E-04 216 6.9840E-04 316 7.5224E-04 416 7.9809E-04 18 2.0648E-04 118 5.9870E-04 218 6.9965E-04 318 7.5321E-04 418 7.9396E-04 20 2 2071E-04 120 6.0225E-04 220 7.0089E-04 320 7.5418E-04 420 7.9982E-04 22 2 3439E-04 122 6.0569E-09 222 7.0212E-04 322 7.5515E-04 422 3.0068E-04 24 2 4757E-04 124 6.0903E-04 224 7.0333E-04 324 7.5611E-04 424 8.0155E-04 26 2 6034E-04 126 6.1226E-04 226 7.0454E-04 326 7.5707E-04 426 8.0240E-04 20 2 7272E-04 120 6.1540E-04 228 7.0074E-04 328 7.5803E-04 428 8.0326E-04 30 2 8475E-04 130 6.18446-04 230 7.0692E-04 330 7.5899E-04 430 8.0412E-04 32 2.9645E-04 132 6 2140E-04 232 7.0310E-04 332 7.5994E-04 432 8.0497E-04 34 3.0784E-04 134 6.2426E-04 234 7.0926E-04 334 7.6089E-04 434 8.0583E-04 36 3 1893E-04 136 6.2705E-04 236 7.1042E-04 336 7.6184E-04 436 e.0668e-04 38 3 2975E-04 138 6 2975E-04 238 7.1157E-04 339 7.6279E-04 430 8.0753E-04 g 40 3.4029E-04 140 6.3238E-04 240 7.1272E-04 340 7.6373E-04 440 8.0837E-04 7 42 3 5058E-04 142 6.3493E-04 242 7.1385E-04 342 7.6467E-04 442 8.0922E-04 44 3 6062E-04 144 6.3741E-04 244 7.1998E-04 344 7.6561E-04 444 8.1006E-04 46 3.7042E-04 146 6.3933E-04 246 7.1610E-04 346 7.6655E-04 446 8.1090E-04 48 3 7999E-04 148 6.9218E-04 248 7.1721E-04 348 7.6748E-04 448 8.1174E-04 50 3 8933E-04 150 6.4447E-04 250 7.1832E-04 350 7.6842E-04 450 8.1258E-04 52 3.9846E-04 152 6.4670E-04 252 7.1942E-04 352 7.6935E-04 452 8 1342E-04 54 4 0738E-04 154 6.4887E-04 254 7.2051E-04 354 7.7028E-04 454 8.1925E-04 56 4 1609E-04 156 6.5099E-04 256 7.2160E-04 356 7.7120E-04 456 8.1509E-04 58 4.2460E-04 158.6 5306E-04 258 7.2268E-04 358 7.7213E-04 458 8.1592E-04 60 4 3291E-04 160 6.5508E-04 260 7.2376E-04 360 7.7305E-04 460 8.1675E-04 62 4.4103E-04 162 6.5705E-04 262 7.2483E-04 362 7.7397E-04 462 8.1757E-04 64 4 4896E-04 164 6.5897E-04 264 7.2590E-04 364 7.7489E-04 464 8.1840E-04 66 4 5669E-04 166 6.6085E-04 266 7.2696E-04 366 7.7581E-04 466 8.1923E-04 68 4 6425E-04 168 6.6269E-04 268 7.2802E-04 368 7.7672E-04 468 8 2005E-04 70 4.7161E-04 170 6.6450E-04 270 7.2907E-04 370 7.7763E-04 470 8 2007E-04 72 4.7879E-04 172 6.6626E-04 272 7.3012E-04 372 7.7854E-04 472 8 2169E-04 74 4.8579E-04 L74 6.6799E-04 274 7.3116E-04 379 7.7945E-04 474 8.2250E-04 76 4 9262E-04 176 6.6969E-04 276 7.3220E-04 376 7.8036E-04 476 8 2332E-C 78 4.9926E-04 178 6.7135E-04 278 7.3323E-04 373 7.8126E-04 478 8.2413E-G4 80 5 0573E-04 180 6.7298E-04 280 7.3427E-04 300 7.8217E-04 480 8.2495E-04 82 5 1202E-04 182 6.7458E-04 282 7.3529E-04 332 7.8307E-04 482 8.2576E-04 84 5 1815E-04 184 6.7615E-04 284 7.3632E-04 384 7.8397E-04 484 8.2657E-04 86 5 2410E-04 186 6.7770E-04 286 7.3734E-04 386 7.8486E-04 486 8.2737E-04 08 5 2989E-04 188 6.7922E-04 288 7.3835E-04 388 7.8576E-04 488 8.2818E-04 90 5.3551E-04 190 6.8072E-04 290 7.3936E-04 390 7.8665E-04 490 8.2398E-04 4 92 5 4097E-04 192 6.8219E-04 292 7.4037E-04 392 7.8754E-04 492 8.2978E-04 94 5 4627E-04 194 6.8364E-04 294 7.4138E-04 394 7.3843E-04 494 8 3058E-04 96 5.5142E-04 196 6.8507E-04 296 7e4238E-04 396 7.8932E-04 496 8.3138E-0^ 98 5.5641E-04 198 6.8648E-04 298 7.4338E-04 39G 7.9020E-04 498 8.3218E-O'
Page 1 of 3 DUKE POWER COMPANY CATAWBA NUCLEAR STATION , ENCLOSURE 5.4 HP/0/B/1009/15 EVALUATION OF PII'ME LOCATION 5.4.1. Acquire the following information from sample Enclosure 5.1 and record on sample Enclosure 5.5. 5.4.1.1 Wind direction in degrees from North 5.4.1.2 Wind spee'd (mph) 5.4.1.3 AT (*C) 5.4.1.4 Stability class 5.4.1.5 Thyroid and whole body dose 2 5.4.2. Determine the affected zones, based on wind direction and wind speed, with the following tables: Table 3.1 0-2 Mile Affected Zones , Wind Direction Affected Zones O' - 360* A0 Table 3.2 2-5 Mile Affected Zones Wind Speed < 5 mph Wind Speed > 5 mph Wind Direction Affected Zones Windbirection Affected Zones 0* - 360* A1,51,C1,D1,E1,F1 0.1* - 22*' C1, D1 22.1* - 73* C1, D1, El 73.1* - 108* C1,D1,El,F1 108.1* - 120* D1, El, F1 120.1* -159* El, F1 159.1* - 207'f El, F1, Al 207.1* - 247' F1, A1, B1 - 247.1* - 265* 'A1, B1 265.1* - 298* A1, B1, C1 298.1* - 338' B1, C1 338.1* - 360* B1, C1,-D1
Page 2 of 3 DUKE POWER COMPANY CATAWBA NUCLEAR STATION ENCLOSURE 5.4 HP/0/B/1009/15 EVALUATION OF PLUME LOCATION Table 3.3 5-10 Mile Affected Zones . Vind Direction Affected Zones 0.1* - 27' C2, D2 27.1* - 69* C2, D2, E2 69.1* - 95* D2, E2, F2 95.1* - 132' D2, E2, F2, F3 , 132.1* - 144' E2, F2, F3 144.1* - 160* E2, F2, F3, A2 160.1* - 201* F2, F3, A2 201.1* - 229' F2, F3 A2, B2 229.1* - 249' F3, A2, B2 249.1* - 259' A2, A3, B2 259.1* - 290* A2, A*', B2, C2 290.1* - 304* A3, B2, C2 304.1* - 333* B2, C2 333.1* - 360* B2, C2, D2 o 5.4.3 Determine the protective action guides (PAG), based on the calcu-laced dose (s) on Sample Enclosure 5.1 and the following information: 5.4.3.1 For doses:
< 1 Rem Whole Body or,
< 5 Rem Thyroid Recommend no action.
5.4.3.2 For doses: 1-5 Rem Whole Body or, 5-25 Rom Thyroid
~ Recommend evacuation of children and pregnant women and sheltering of remainder of personnel in the affected area.
l
Page 3 of 3 DUKE POWER COMPANY CATAWBA NUCLEAR STATION ENCLOSURE 5.4 HP/0/B/1009/15 EVALUATION OF PLUME LOCATION 5.4.3.3 For doses:
> 5 Rem Whole Body or,
> 25 Rem Thyroid Recommend Evacuation of Population in Affected Area.
. 5.4.4. Record only the affected zones requiring protective action on sample Enclosure 5.5 along with the recommended protective action.
%e i
l l
DUKE POWER COMPANY Pegs 1 of 1 CATAWBA NUCLEAR STATION HP/0/B/1009/15 ' ENCLOSURE 5.5 DOSE ASSESSMENT REPORT Duke Power Crisis Company Managament Plan Off-Site Dose Report . CATAWBA Prepar'ed By Date/ Time / Emergency Drill (circle one) Meteorology Wind Speed MPH
- Wind Direction degrees from North Vertical Tesp. Diff. degrees C/100 ft.
Stability Class (circle one) A B C D E F G Source Term Time Noble Gas I-131 equivalent Containment Rad. Monitor R/hr R/hr Containment Sample ,pci/ml pCi/ml Unit Vent (Sample of EMF) DCi/el DCi/ml , Curie Release Rate Ci/sec Ci/sec Corresponds to: LOCA LOCA through filter Core damage Core damage through filter Tube rupture Gas Decay Tank New fuel Old fuel Other
' Dose Projections
.5 mi 2 mi 5 mi 10 mi 2hr Dose (rem). based Whole Body on Containment release Child thyroid 4
@ al/hr 2hr Dose (ree) based Whole Body on Unit Vent release Child thyroid
@ cfm 2hr Dose (rea) based Whole Body on Steam release Child thyroid 2hr Dose (rem) based Whole Body on release Child thyroid Field Monitoring Data Location Distance Direction Dose Rate (arem/hr) Contamination 2
(mi) Whole body Child thyroid (dpm/100 cm ) Affected Zones 0-2 mi 2-5 mi 5-10 mi 9-10 mi (circle zones) A0 A181 C1 D1 El F1 A2 B2 C2 D2 E2 F2 A3 F3 COMMENTS: xc: Data Analysis Coordinator, Station Health Physicist
__. _ ,..__i a.. ... s
._2 . . - - . - , .
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- -- -~ ~--n ENCLOSURE 5.6 HP/0/B/1009/15 Page 1 of 5
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l Form 34731 (10-81) ~ (Formerly SPD 10021) DUKE POWER COMPANY (1) ID No: HP/0/B/1009/16 PFOCEDURE PREPARATION Change (s) O to PROCESS RECORD 0 Incorporated l l (2) STATION: Cataba (3) PROCEDURE TITLE: Distribtition of Potassium Iodide Tablets in the Event of a Radiciodine Release (4) PREPARED BY: d 1 /. fz2s neerrry) DATE: / /9 84 (5) REVIEWED BY: . m DATE: /-//-f[ Cross-Disciplinary Review By: b(b , N/R: (6) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: By: . Date: (7) APPROVED BY: W' Date: IfM $/ (8) MISCELLANEOUS: Reviewed / Approved By: - Date: Reviewed / Approved By: Date: O O
HP/0/B/1009/16 DUKE POWER COMPANY CATAWBA NUCLEAR STATION 4 DISTRIBUTION OF POTASSIUM IODIDE TABLETS
, IN THE EVENT OF A RADI0 IODINE RELEASE 1.0 PURPOSE This procedure provides information necessary to distribute Active Potassius Iodide (KI) tablets to in plant personnel in the event of a release of radioiodine. Also, it outlines storage and supply information to assure sufficient quality and quantity of thyroid blocking material.
2.0 REFERENCES
l 2.1 NCRP Report No. 55; Protection of the Thyroid Gland in the Event of Releases of Radiolodine 1977 2.2 NCRP Report No. 651; Management of Persons Accidentally Contaminated l With Radiciodine 1980 2.3 HP/0/B/1001/09, Operation / Calibration Procedure for the Body Burden l Analyze-2.4 HP/0/B/1009/10, Body Burden Analysis Following Suspected Uptakes of l
- Mixed Fission or Activation Products 2.5 System Health Physics Manual 2.6 NUREG 0654 3.0 LIMITS AND PRECAtTTIONS 3.1 KI must not be administered to a person who knows he (she) is allergic to iodide.
} 3.2 If a person has an allergic reaction or has severe side effects . from taking KI tablets, they should stop taking KI tablets and I consult a doctor or public health authority for instructions. 3.3 Personnel shall be advised not to deviate from the prescribed dosages and dosage rates. 3.4 Best results will be achieved when KI tablets are administered immediately (within 2 hours) after an exposure, although administration as ltte as 24 hours after an emergency will provide some protection. 3,5 Discciored or disfigured tablets, tablets that have reached the expiration date listed on the bottle, and bottles of KI with loose tops shall be discarded. 3.6 Hands of anyone touching the KI tablets must be free of radioactive contamination prior to taking the KI tablets. l ____-~3 __
=
. =. - . . . _
HP/0/B/1009/16
, Pcgs 2 of 4 4.0 PROCEDURE 4.1 Responsibilities For Distribution
~
4.1.1 The Station Health Physicist, in conjunction with i available medical advice, shall control the distri- l , bution of KI tablets. 4.1.2 Persons suspected of having been in the affected area prior to the detection and during the release, persons present in the affected area and persons who will enter the area while a significant amount of radiciodine is present will be instructed by the Health Physics Supervisian to immediately register in the KI distribution center (for example, the Technical Support Center). 4.1.2.1 A significant amount of radiciodine for short duration in plant exposure is that amount taken into the body that would result in a quarterly permissible occupational dose or more. For example, exposure to 4.6 x 10 8 pC1/ml airborne iodine for one hour would result in such an exposure. This corresponds to 520 MPC-hrs which is the quarterly limit. 4.1.2.2 A significant amount of radioicdine for emergency workers in the field is 10 MPC (9 x 10 ' pCi/ml) I-131. ! 4.2 Registration of persons exposed to a significant amount of radio-iodine. 4.2.1 When persons notified by Health Physics arrive at thn d -tribution area, record appropriate data per Enclosure 5.1. 4.2.2 With the approval of the Station Health Physicist, the Health Physics representative shall give one (1) tablet to each person and instructions concerning the use of the tablet. Then issue to each person one bottle containing nine (9) KI tablets, and the package insert for the use of the tablets (refer to Enclosure 5.2 for an example of the General Manufacturers Guidelines). 4.2.2.1 Tablets are to be taken only as directed. One (1) tablet per day for the length of the emergency. ! 4.2.2.2 After the initial dose of KI, subsequent doses will be taken on a daily basis. Tablets should be taken as near a 24-hour schedule as possible. NOTE: For best results, emphasis must be placed upon the proper use of these tablets.
._ m
HP/0/B/1009/16
., Pegs 3 of 4 4.2.3 Tablets removed from full bottle of KI should be stored in 10 ml plastic vials. The expiration date on the bottle from which the tablets were taken and the name of the Health Physics representative shall be recorded on the 10ml
. vials Tablets stored in 10 ml plastic vials should then be used for single tablet initial issuance of KI to affected persons.
4.2.4 As directed by the Field Monitoring Coordinator (FMC) or the S&C Coordinator, team members shall ingest one (1) tablet of Potassium Iodide. 4 4.2.4.1 The FMC and/or S&C Coordinator will provide the information for Enclosure 5.1 and will ensure that distribution of KI per Step 4.2.2 is accomplished by team members. 4.3 Thyroid Burden Analysis Fo'llowing Radiciodine Exposure 4 4.3.1 All persons receiving KI tablets should receive a thyroid scan. If the number of people render this step inpractical, the Count Roca Supervisor will select a representative sample of persons listed on Enclosure 5.1 who received KI tablses. NOTE: Subsequent action involving thyroid burden analysis should follow guidelines established by HP/0/B/1009/10. 4.3.2 Records of thyroid . scan shall be maintained per procedure. NOTE: Distribute KI before analyzing thyroid concentration. Thyroid scans immediately after an accident could lengthen KI dis-tribution time and cause confusion among , personnel. 4.4 Storage Requirements 4.4.1 There are three major storage requirements to be observed: 4.4.1.1 Store in a temperature range of 59' to 86*F. 4.4.1.2 Store in a low humidity area (avoid direct exposure to liquids). 4.4.1.3 Store in an area protected from exposure to light. , 4.4.2 Upon receiving a shipment of KI tablets, boxes shall be opened as soon as possible and bottles examined to ensure that an air-tight seal has been maintained. Bottles must be returned to boxes, and boxes must be sealed shut, so as to avoid exposure to light.
HP/0/B/1009/16 Pcg3 4 of 4 4.4.3 To ensure a sufficient supply of tablets, a minimum of 1,000 bottles with 14 tablets per bottle should be maintained on site.
. 4.5 Shelf Life and Changeout of KI Tablets 4.5.1 Thyro-Block tablet bottles are labeled with an expiration date from the factory. As tablets reach the expiration dates, the tablets must be discarded.
NOTE: Replacement tablets should be ordered at least three (3) sonths prior to the date of expiration listed on the bottles of KI. 4.5.2 Upon receiving a shipment of KI tablats, supplies should be shifted so as to use older tablets before new tablets. 5.0 ENCLOSURES
, 5.1 Potassium Iodide Tablet Distribution Data Sheet 5.2 Manufacturers Guidelines for. Thyro-Block Tablets and Solution 6
J , l l l 1 i 1 , . . . . . - . . . . . . . . _ . . . . . - . - - - __ m J
Enclosure 5.1 POTASSIUM IODIDE TABII.T I)lSTRIBUTION DA'l A SiiEET lip BADGE DATE & TIME OF DATE & TIME OF "NUl!BER NAME DEPARTHENT SUSPEC'IT.D EXPOSURE INITIAL ISSUANCE
. ..e s
I na.riore :. 2 l'6 :'.5: 1 .i t 2
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t THYRO. BLOCK" j (POTAS$1UM 800100 (stoncunced pos TA*;;;*,... siei ..r. :,.. - l l.iut.ausitiv 1 H ' I iA3LETS a.,c SQL Ulse m U :; e ' I : 1 3
'1 AKE E l OTASSIUS! IODIDE UNI.Y Wi!EN l't ' lit.l E l
!!EAf.Tl! OFFICIALS TEl.L YOU. IN A ItADIAT!ON .
ENtEftOENCY, ItADIDACTIVI: :aDINE Cutil.D !E i P.ELEASED INTO Ti!E A!!L l'OT,i::SIUit lunibE sa i FO!!At OF IODINE) CAN Ilh!.I' PitOTECT YOU. j
. IF YOt! AftE TOLD TO TAK!: Tills 31 Edit'shE.TAKE IT l l ONE TIStE EVEltY 24 IlOUlts. Dr> No rr 'I Ahl: IT 11010; i OlTEN. 51DilE WILL NOT !!ELi' Yuti Mil NIAY IN .
CliEASE Ti!E IllSK OF SIDE 1 FFECTS. !su NtJT ntlil l Tills HitUG !F YOU NNUIV YOU rild ell.l.ElitiH.* Te> l IODIDL: ISCE SIDE EFFECTS IlELOW.I i
. . . . _ . ....._.J 9 IN31 CATIONS T!!Y!!O!D llLOCMING IN A 1!ADIATiiri 1:\li.ittiENCY ON!.Y.
CIRFCTIONO FOR US.! Us.e oaty na ilirected by si at e or local pi.bi c 1.e.d. . h ri.ilu.a .:ir i i.. the event of a rushnuun cancrgency. DOSC Tablet t ADill/f:i ANil t'll!!.!11:1-:.*i . 'a 1: A:( OF AGE Uit OI.1#Elt. Dr.c :., is.o.'. L n.ce a day. Crush for s untli!. ls. n IIAlllE . L.NUElt 's 1. Al; OF AtiE: Oneladf it,a subl. t care a day C: u ,!. fir. L Solution: ADUllfS AND C;;ls.Di!FN 1 Yr.' it OF AGE 011 OLIJElt: Adil ti alrup, to one-half gla.: of he;us.1 ami orudt tacti das . IIAulES UNDi.it 1 )EAlt t,P AGE: Add 3 drops to rt snuli amrue.t of tr;uid I
. unes a day. l for : t cloeage forr*.s. Take for iU dava ubs . .he.v . .! ..:s.e r wr.c I by State or local public health mutt orp.uw. j Storc at con: rutted rourn teinperature!. roc. i l/ as !:a. Ct.7) to $ti'Fl. Keep cont.uner tightly r!m.c.: a aii ;n.. rt tri.m sigl.t. 1 Do not use the sututionifit ag'pcars liric.va.i li, d.c . c. ..n: ahe 1 bott!c. i WARNINi,1 1 l'oraesium iodide shou!J not b used kv perpl. cl.'.es.c ta tv.lu:. \
Keep out of the reach of chddre i. la r.i.a i.! .. c ri.. c..r a;;crgic ) tc.ction contact a physicien ..r the public health a t!. .rity. ) 8 Each TilYltO !1!.0CKW TAlli.ET potassium iodido. DESCalPTION r.. .s. anni . . . e.ig of Esch drnp o! TilYHO UI.OCK 5.01.1.T,G'. c.. .t an.i'.'1 :u:.: uf potaniuta iodide. O
' *n .: I m.u n: 5.2 hir,t: 2 of 2 0 llOW POTASSIUM IOD:CE WORKS Ceru.iu for:ns ofiudme hrt, your ihy .iul giusai ..ain sight. 'lu.t
. puuple gut the iodine they tard asum 1.a l hai imhnd malt un .
fe h. The thyroid saa % turi
- ur 1.ul.1 valy si L.ai auun . uf suglatly, in a r.adiation cmergency, radianst ti.u unhne :.. 3 t,e re h use d m the air. This matersal may be brea'heu i.r .me!! owed itsney inter the thyroid t;!and and duana ;e it 11... tamage wouldl ui.
Lably not show ituull for years Cl lJren oss a...,t e.ku y su 1.as a thyroid danauge
!! yens take putas Aum six!.de it tall hil up ,s u .. ts.yrca, gland.
'TLs rtsluces the chanto t!ut hxn. tut suita.attive aniline wi!i enter the thyruid C l385 I-WHO SHOULD NOT TAKE POTASSIUM IODIDE The only peop le shu sh4,u d not ti.c r.'uver m i.asale arr; s sple ,
wno know they are slicrgic tu .6da's Y.a. ... v r es.: p..t a v..um iudale even if you are takice :acdici.e i t. r 4 i hys..id pr.,bh-an ifur caemp!c. a thyroid hura;une sa antni: :...? :: .; l'icsn.u.t at:.1 nursing woman ar.d Lab;r $ nnd . i.::.h sn m... =14. o.hr t!.r de us. HOW AND WilEN TO TAKE POI".S:;iL*M IOul0C
!'ota .sium *odidu .hou!J 1 o ta;:: n m. .-m : 35 p..*.il.:. o f.M pubhd la alth offie;als ted sou *a .,u :.imu!.; I k . .v :te.eet vi y *.:I twu.a. .Wro wdl amt he;;. wt u.t u . ta. tla :..e i ... "hr.l. l" ..n-13 hmited amounts ri! ! J.nc.1.u:ps a . . .u!. .n. i . a r . he . i k of ule riferts You w..! pa s.le.si ty i t .u: i... 1.. seJe tin e!r: g for mere ti..n tu sing O
GiOE !.l Li.1:;
';$c.t!!v. aid.: s lfet v. .f ;.. .r. uai, n l.. . ! .o t.-:. wl.s n :n o;.le.
take h 3;her dur.er, for . sung e c. (ou .: . o.i : . in! not t u t ks* 8.u.Ia. tlip:t Ihe. Ut ous :i" . hit s' e o a.e
- i' t .r h.:.v.. r ilisen yuss are t.dd. Edu tilusta eu u.6%.43 in.4.s.w ..I .nc.ow 6.~ .ai..I thu short Orno you u i1,o toi.p.8 thic ..ri.4 l's Amblo side effects mch..lo r kin e.e- un. :. rlin g . e alw .ahs ar.-
glands, and **;cdiam"(metalhe taste. N.. .ng se .utn ne.st Lt.tu t. w,re terth and gurcs, s):r.ptusas u: a .wau su!d. and somttia.es stan.ach upset and diatriarul A few peuplo have an al or,oc tresti.us wit!. n..n : ern,us syrug> terns. Those could be frver and joint pains,i.r eclinig of paa t:, uf tho farv and body and at t m.6: sus es u nhui t nu s ..I bacath a tigmt-ing immediato medical attos. tion. Tak ng iodado may rarely cau:.u uvera.uu:. of the thyrnid gland, underactivity of ttw thyrna.i gir:id. er cr.largenu nt of the Lt.> roid gland (goiteth WHAT TO 00 IF SIDE CFF:-CTS OCCUR
. If the side ellects are ovvere or d ye.n !.ase ar. .l!.rgie ti action.
= top taking potassiu:n iudn!t Then. :; .uvobic, cnil a duetor ne public health authursty for mstrar r.a*
HCW SUF ALIE3 i Tl!Y;tO DLOCK rst Tali!.1-;rS iP..t i..unn 6.wi.d4 li S.I'.I Irot t!ca uf 14 tableta lNtJC 00.1.50472 .a l ;..ch white. rnuis!. ered tablet cor.tains I;10 aug putassit:1 irtia.c. Tl!Y1tO-uLOCK rSt sul.UTit a'. ti . :.e.=h. n lus.u:e Mlu. oa.
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Form 34731 (10 81) (Formerly SPD 10021) DUKE POWER COMPANY (1) ID No:HP/1/B/1009/17 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD 0 Incorporated i
- (2) STATION
- CATAWBA (3) PROCEDURE TITLE: POST-ACCIDENT CONTAINMENT AIR SAMPLING SYSTEM
'(4) PREPARED BY: _. DATE: / V /
/ '/
(5) REVIEWED BY: k 3. f/d1I DATE: / -J/- P i Cross-Disciplinary Review By: MTAd .$ N/R: (6) TEMPORARY APPROVAL (IF NECESSARY): By: * (SRO) Date: By: Date: (7) APPROVED BY: L~/* Dato: /kCM (8) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: l I e e n ,- y,. .w+-, --m,w -w - - , -
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e HP/1/B/1009/17 DUKE POWER COMPANY CATAWBA NUCLEAR STATION POST-ACCIDENT C0!frAINMENT AIR SAMPLING SYSTEM 1.0 PURPOSE To describe a method for obtaining a containment air sample after a nuclear reactor accident using the Nuclear Post-Accident Containment Air Sampling System (PACS)..
2.0 REFERENCES
- 2.1 HP/0/B/1009/06, Alternative Methods for Determining Dose Rate
. Within the Reactor Building 2.2 OP/1/A/6450/10, Containment Hydrogen Contirol Systems 2.3 RP/0/B/5000/12, Control of Assessment and Repair Teams 2.4 Duke Power Company Nuclear Station Dost-Accident Containment Air Sampling System Manual 2.5 Post-Accident Containment Air Sampling System - Qualifications, File No.: CN-134.10 .
3.0 LIMITS AND PRECAUTIONS i 3.1 Exposure from the samples have the potential to be very high; therefore, appropriate surveillance and control of personnel shall be provided by Health Physics when taking samples. Entry and exit
- route to sample panel and control panel area are to be determined i
1 by Health Physics surveys. 3.2 The Recire Pump shall never be used at any pressure other than 0" of I Hg. 3.3 Moving the Selector switch (#9) from one mode to another stops all current system operations. Depressing the Activate pushbutton (#10) starts operation of the newly selected mode. 3.3.1 Numbers within parentheses (ex. #9) ar.: locations on I Enclosure 5.5 and on the control panel. l 3.3.2 (SP) to the left of the enclosure step number requires a person to go to the sample panel. 3.4 The Radiation-Monitor (#3) on the control panel should provide i ' background levels of radiation prior to, during, and after sampling, and an indication of contaaination within the system or panel for progressive samples. 3.5 If the needle of the Radiation Monitor (#3) exceeds the upper end. of the meter scale while the lower scale (mR/hr) is being used, immediately turn.the selector knob to the higher scale (R/hr).
HP/1/B/1009/17 Paga 2 of 3 3.6 If the Radiation Monitor (#3) reading cannot be reduced below 10 R/hr do not return to the sample panel, but contact the OSC Health Physics Supervisor immediately for further instructions. 3.7 If problems with the Radiation Monitor (#3) are evident (e.g. no indication of radiation on the meter), notify the OSC Health Physics Supervisor and rely on Health Physics surveys to determine access to the sample panel. 3.8 If thiosulfate comes in contact with the skin during preparation, transferal or dilution, wash the affected area as soon as possible with soap and lukewarm water. Consult station nurse for further instructions. 3.9 Dispose of contaminated syringes, septums, rubber gloves, etc. , in appropriate radioactive waste receptacles. 3.10 Individuals that have been trained on this procedure are the individuals qualified to use this procedure. Individuals shall be trained and tested every six (6) months and documented in Reference 2.5. 3.11 Due to the nature of this procedure, a Working Copy shall be used to ensure compliance. 4.0 PROCEDURE i 4.1 Follow steps on the OSC Health Phys tu Supervisor PACS Checklist
- (Enclosure 5.1).
4.2 Follow steps on Post-Accident Containment Air Sampling Set-Up (Enclosure 5.2). 4.3 Follow steps on Taking Post-Accident Containment Air Samples (Enclosure 5.3) and complete Post-Accident Containment Air Sample Data Sheet (Enclosure 5.4) for each containment air sample request. 4.3.1 If applicable, determine containment dose rate per Referttee 2.1. 4.4 Ensure the isotopic analysis of each containment air sample and its associated Enclosure 5.4 are submitted to the Station Health Physicist. 4.5 Follow steps on Post-Accident Containment Air Sampling Shut-Down (Enclosure 5.5). 1 4.6 File enclosures and associated calculations in the Health Physics Satellite Master File. 4.7 Connect an appropriate transfer container and drain the sump by turning the Key Iock switch (#48) to Sump Pump. Accompanying power light should illuminate. 5.0 ENCLOSURES 5.1 OSC Health Physics Supervisor PACS Checklist
,-.e- wp eg-g,--+ -- ---.--p-, - -my - .-- .,m -- % y 9 -+ _ _
HP/1/B/1009/17 Pago 3 of 3 5.2 Post-Accident Containment Air Sampling Set-Up 5.3 Taking Post-Accident Containment Air Samples 5.4 Sample of Post-Accident Containment Air Sample Data Sheet 5.5 Post-Accident Containment Air Sampling Shut-Down 5.6 Post-Accident Containment Air Sampling Control Panel (PACP) Diagram 5.7 Post-Accident Containment Air Sampling Sampi.e Panel-(PASP) Diagram 5.8 Location of PACP and PASP 4 4 4 1
, _ . . - . _ _ . _ _--_m_. ___
Pega 1 of 2 DUKE POWER COMPANY CATAWBA NUCLEAR STATION dP/1/B/1009/17 ENCLOSURE 5.1 ! OSC HEALTH PHYSICS SUPERVISOR PACS CHECKLIST I Date/ Time / Unit Check Action i 5.1.1 After completion of Team Personnel Lists of Reference 2.3, consider the following for the PACS:
- MSA SCBA's
- Operable' breathing cir bookups ;
- Throat mikes i
- Portable instruments (PIC-6A, Teletector) [
- High range dosimetry
- Extremity dosimetry I
- To and from route to PACS EMF-2 Control Room readout {
- Flashlight :
- Radios !
- Control Points '
5.1.2 Request assistance in acquiring needed equipment from the Technical Support Center (TSC). h 5.1.3 Prepare Counting Room to receive sample. Consider:
- RCZ setup
- Shielding
- Disposal of sample
- MCA setup !
- Personnel
- Dosimetry (high, extremity) ,
5.1. 4 Select one qualified individual based on PACS training and I MSA training (refer to Reference 2.5, Health Physics file ! 134.10-4 or the OSC Health Physics Notebook). Select j another individual to accompany the other. Consider: +
- Age
- Accumulated exposure '
- Sex !
- Ability to carry 100 lbs. together
- Respiratory printout i
5.1.5 If necessary, complete dose extension forms. ' 5.1.6 -Obtain a High Radiation Area key. 5.1.7 Have equipment prepared for conditions at PACS. Consider: t
- Taping wheels on porta pig !
- Bagging loose items i
+
Page 2 of 2 DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/1/B/1009/17 ENCLOSURE 5.1 OSC EALTH PHYSICS SUPERVISOR PACS CECKLIST Check Action 5.1.8 Inform selected individuals of precautions, Safety and Health Physics concerns and then have them obtain the sample per Enclosure 5.2. 9
. .- = . - - . __ . _ = - - - - . . -- - - _ _-_ _
Paga 1 of 2 DUKE POWER COMPANY + CATAWBA NUCLEAR STATION
- HP/1/B/1009/17 ENCLOSURE 5.2 POST-ACCIDENT CONTAINMENT AIR SAMPLING SET-UP Date/ Time / Unit
. Check Action i 5.2.1 Inform the Shift Supervisor that gas sampling will be , performed and that one Hydrogen Analyzer will need to be ! inoperable:during sampling. Request that Operations complete the Setup Section for Post-Accident Containment l Air Sampling of procedure OP/1/A/6450/10 (see Reference ; 2.2). I
. 5.2.2 After notification that Operations has completed the PACS Setup Section, obtain the Post-Accident Containment Air Sampling Equipment located in the OSC Emergency Kit.
The equipment should be the following: l
- Quantity Item !
j 1 - Post-Accident Control Panel (PACP) Key f 2 - 500 ml Nalgene bottle labeled "2.42 x 10~8M NaOH" 2 - vials of .3003 gm Na2S0 3 5H 0 - , 2 - 500 ml graduated bottle labeled " Iodine Sample" 2 - 100 ml gas bomb ! ! 2 - 60 ml Nalgene bottle - labeled " Iodine Sample" { l - Stop watch i i 5.2.3 Prepare thiosulfate solution by adding one vial of
- Na
- S 03 -5H 0 to one bottle of NaOH. Shake vigorously until all of the crystals are dissolved. Relabel as
! " Thiosulfate". 5.2.4 Verify that the Selector switch (#9) is in the Off position. I 5.2.5 Move the System Purae toggle switch (#20) to the Normal position. 5.2.6 Move the Refill toggle switch (#24) to the Off (down) position. I 5.2.7 Turn Key Lock switch (#48) to Power On. Accompanying ! power light should illuminate. l 5.2.8 Turn the Radiation Monitor (#3) On by moving the toggle switch (located below the meter) to the Un position. _ . , - . _ . . ~ . _ . . _ _ _ _ __ _ . _ , . . _ ._ _ __ __ _. _ _ , _ . _
Pcga 2 of 2 DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/1/B/1009/17 ENCLOSURE 5.2 POST-ACCIDENT CONTAINMENT AIR SAMPLING SET-UP Check Action 5.2.9 Turn the Radiation Monitor (#3) selector to BATT and verify that the needle is in the " red test region" on the right and of the scale. If reading is below the test region, rely on Health Physics surveys to determine access to the sample panel. 5.2.10 Select the appropriate rate so that the needle is on ths meter scale by first turning the selector knob to higher scale (R/hr) and, if necessary, to the lower scale (mR/hr). - ^ (SP) 5.2.11 Pour thiosulfate solution into the thiosulfate tank, located on top of the sample panel. Leave the cap off . of the thiosulfate tank after transferring the thiosulfate solution. , (SP) 5.2.12 Open all four (4) service valves DI, VI, Na and TS by turning handles one quarter turn counterclockwise. The DI, VI, and N valves are located on the outside upper I left side of the sample panel, and the TS valve is located on top of the sample panel. i I t
+
Psgs 1 of 4 DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/1/B/1009/17 ENCLOSURE 5.3 TAKING POST-ACCIDENT CONTAINMENT AIR SAMPLES Date/ Time / Unit Check Action 5.3.1 Turn Key Lock switch (#48) to On. 5.3.2 Turn Selector switch (#9) to System Purge. 5.3.3 Move System Purge toggle switch (#20) to Sample Purge.
- 5.3.4 Depress Activate pushbutton (#10).
5.3.5 Depress Evac pushbutton (#17) (Evac light should illuminate) and watch the vacuum gauge (#6) drop to
-25" of Hg.
5.3.6 When the vacuum gauge (#6) reaches -25" of Hg, depress the Stop pushbutton (#19). 5.3.7 Press down che Gas Purge toggle switch (#16) and watch the vacuum gauge (#6) rise to +10" of Hg. , 5.3.8 When the vacuum gauge (#6) reaches +10" of Hz, return toggle switch (#16) to center position and depress the Stop pushbutton (#19). 5.3.9 Depress the Evac pushbutton (#17) and watch the vacuum gauge (#6) drop to 0" of Hz. l 5.3.10 When vacuum gauge (#6) reaches 0" of Hz, depress the Stop pushbutton (#19). 5.3.11 Depress PumE Pushbutton (#18) and wait for thirty (30) seconds. l 5.3.12 Depress Stop pushbutton (#19). 5.3.13 Move System Purge toggle switch (#20) to Normal. l 5.3.14 Turn Selector switch (#9) to Solution Changeout. i l 5.3.15 Ensure gas bomb valves are open. (SP) 5.3.16 Attach an " Iodine Sample" bottle to the sample panel by inserting the plastic hose into the bottle located 6n the lower left side of the panel. Attach a gas bomb to c the sample panel on the lower right side of panel.
- -- ,r -, - ---- - - -
P 32 2 of 4 DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/1/B/1009/17 ENCLOSURE 5.3 TAKING POST-ACCIDENT C0tfrAINMENT AIR SAMPLES Check Action 5.3.17 Record the Radiation Moniter (#3) reading as a background
; reference: R/hr
- 5. 3.13 Record' sample line temperature reading (#4): 'C 3.3.19 Depress Activate pushbutton (#10).
t 5.3.20 Depress Flush pushbutton (#22) and hold five (5) seconds. 5.'3.21 D'epress Purge pushbutton (#23) and hold ten (10) seconds. 5.3.22 Depress Empty pushbutton (#21) and hold for thirty (30) seconds. 5.3.23 Move the Refill toggle switch (#24) to ON (up) position and wait two (2) minutes and then move the toggle switch ba-k to the Off (down) position. 5.3.24 Turn Selector switch (#9) to Dilution Volume Evacuation. i 5.3.25 Depress the Activate pushbutton (#10) and watch the vacuum gauge (#6) drop to -25" of Hz. 5.3.26 When the vacuum gauge (#6) reaches -25" of Ha, turn Selector switch (#9) to Sample Recire. 5.3.27 Depress Activate pushbutton (#10) and wait for five (5) minutes. 5.3.28 Record sample inlet line pressure (psig) reading (#5): Psig 1 4 5.3.29 Depress Samole pushbutten (#11) and wait for thirty (30) seconds. 5.3.30 Depress Trap pushbutton (#12) and wait for ten (10) seconds. 1
'5 .3. 31 Enter time of sample trap: (ex. 1355) '
5.3.32 Turn Selector switch (#9) to Sample Dilution.
~
5.3.33 Depress Activate pushbutton (#10). 5.3.34 Depress Slow pushbutton-(#13) and watch vacuum gauge (#6) rise to 0" of Ha.
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Pega 3 of 4 DUKE POWER COMPANY CATAWBA NUCIZAR STATION HP/1/B/1009/17 ENCLOSURE 5.3 TAKING POST-ACCIDENT CONTAINMENT AIR SAMPLES Ch'eck Action 5.3.35 When the vacuum gauge (#6) reaches 0" of Hz, depress the Stop pushbutton (#14). 5.3.36 Depress the Reci_rc pushbutton (#15) and wait for five (5) minutes. (SP) 5.3.37 Close the 3as bomb outlet valve, wait five~(5) seconds and close the inlet valve. 5.3.38 Depress the Stop pushbutton (#14). 5.3.39 Turn Selector switch (#9) to Solution Chanzeout. 5.3.40 Depress Activate pushbutton (#10).
- 5.3.41 Depress the TS Sample pushbutton (#25).
5.3.42 Depress and hold the Empty pushbutton (#21) for -five (5) minutes. Thiosulfate should transfer into the TS sample bottle. 5.3.43 Depress Purze pushbutton (#23) and hold thirty (30) seconds. 5.3.44 Depress TS Sample Grab pushbutton (#26). 5.3.45 Turn Selector S;. itch (#9) to System Purae. 5.3.46 Move System Purae toggle switch (#20) to Sample Purne. 5.3.47 Repeat steps 5.3.4 through 5.3.12 as needed until no noticeable decrease is observed on the Radiation Monitor (#3) from one purge to the next. Check blank in steps 5.3.4 through 5.3.12 each time the step is performed. 4 5.3.48 Record the Radiation Monitor (#3) reading. ] 5.3.49 Turn Key Lock switch (#48) to Off. 1 (SP) 5.3.50 Tightly cap the " Iodine Sample" bottle and disconnect the gas bomb from the sample panel. l l l (',, __ _ _ _ _ _ - - - - - -
Page 4 of 4 DUKE POWER COMPANY CATAWBA NUCIZAR STATION HP/1/B/1009/17 ENCLOSURE 5.3 TAKING POST-ACCIDENT CONTAINMENT AIR SAMPIIS Check Action 5.3.51 Determine the Thiosulfate Sample Volume (TSV) and record this value as TSV: ml 5.3.52 Using standard chemistry Itboratory techniques and under a sample hood, transfer 50 al of the " Iodine Sample" into the 60 al Nalgene bottle. Contact Radwaste Chemistry for instructions on disposal of excess sample. 5.3.53 Place the 60 ml " Iodine Sample" bottle and the gas bomb into a shielded container. 5.3.54 Transfer the " Iodine Sample" and gas bomb to the Health Physics Counting Room for isotopic analysis. 5.3.55 Using a monitoring instrument (such as the R02A or PIC-6A) take a contact dose rate reading on the top of the gas bomb and on the side of the " Iodine Sample" bottle: R/hr gas bomb, R/hr " Iodine Saeple"
Pago 1 cf 1 DUKE POWER COMPANT CATAWBA NUCLEAR STATION HP/1/B/1009/17 ENCLOSURE 5.4 SAMPLE OF POST-ACCIDENT CONTAINMINT AIR SAMPLE DATA SHEET i Date/Tima: / Unit l l .. Prepared By: Emertency - Drill l (Circle One) , First Radiation Monitor Reading from 5.3.17 R/hr l l Sample Line Temperature from 5.3.18 *C Sample Inlet Line Pressure from 5.3.28 psig Sample Trap Time from 5.3.31 Second Radiation Monitcr Reading from 5.3.48 R/hr Contact reading on gas bomb from 5.3.52 R/hr (Top) Contact reading on " Iodine Sample" bottle from 5.3.52 R/hr (Side) Containment Sample Volume -- 293*K (14.7 psig + psig) CSV = 1.3 al * (273*C + "C)*K 14.7 psig
= al at standard temperature and pressure Section volume of CSV trapped in " Iodine Sample" bottle --
SV7 = 50 ml = ml ml (CSV)
- al (TSV) i where 50 m1 sample size + Thiosulfate Sample Volume from 5.3.54 Section volume of CSV trapped in gas bomb --
SV G
=
al (CSV) * .01 = al where .01 = 100 ml gas bomb + 10,000 ml volume of dilution 1 Station Health Physicist Data i
, Paga 1 of 1 DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/1/B/1009/17 ~
ENCLOSURE 5.5 POST-ACCIDENT CONTAINMENT AIR SAMPLING SHUTDOWN Date/ Time / Unit Check Action 5.5.1 Turn Selector switch (#9) to Off. _. 5.5.2 Turn Radiation Monitor (#3) Off. (SP) 5.5.3 Replace the top to the TS tank. (SP) 5.5.4 Close all four (4) service valves DI, VI, N: and TS by turning handles one-quarter turn clockwise. 5.5.5 Request that Operations complete the Shutdows Section for Post-Accident Containment Air Sampling of procedure OP/1/A/6450/10 (see Reference 2.2). 5.5.6 Notify Shift Supervisor of sampling completion and that the H Analyzer used during sampling is not required for sampling.
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Page 1 of I C Duke Power Company Catawba Nuclear Station HP/1/B/1009/17 Enclosure 5.6 Post-Accident Containment Air Sampling Sample Panel (PASP) Diagram
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i DUKE POWER COMPANY Page 1 of 1 ' CATAWBA NUCLEAR STATION HP/1/B/1009/17 l Enclosure 5.7 O.. Location of PACP and PASP
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CATAWBA NUCLEAR STATICI 224
i T l i l HP/0/B/1009/18 ! , ENVIRONMEffrAL MONITORING FOR EMERGENCY CONDITIONS !
. WITHIN THE TEN MILE RADIUS OF CATAWBA NUCLEAR STATION (AUGUST 1983) er
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(Permarty W010021) DUEF, POWER CGIFANY (1) ID No:l'P/0/8/1009/19
. PROCEDURE PREFARATI(N Change (s) O to FRCCESS RECORD 0 Incorporated
) - (2) STATION: Catauba _- (3) FROCEDURE TITLE: Emergency Radio System Operation, Maintenance, and
. g. _Comunsdcgion
"""'~~~7R JREF N [ M /p 3 'V d :
- % MTE: 9 #.5 (5) _. _ ._ BY: __ N4 M >>
DATE: /> e. rs REVIEWED
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cross-Disciplinary Review By: N/R: f_ C
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(6) TEMPORARY APPROVAL (IF NECESSARY): l j . ,..___ By: (ERO) Date: , 1 a ---
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- (7) AFFROVED BY:ibe _
( \ AA'I Date: 3 NhI.[) (3) merri amunrre: a j Reviewed / Approved By: Date:
- i j Beviewed/ Approved By: Date:
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. DUEE POWER COMPANY CATAWBA NUCLEAR STATION EMERGENCY RADIO SYSTEM OPERATION, MAINTENANCE, AND COMMUNICATION 1.0 PURPOSE To describe the Emergency Radio System activation, maintenance and uso during an emergency event or drill.
2.0 R$FERENCES 2.1 RP/0/3/1009/04 Environmental Monitoring for Emersoney Conditions within the ten mile radius of Catawba Nuclear Station . 4 2.2 DPC Forn 06005, Radio Operators Manual 2.3 Crisis Management Plan, Implementing Plans, 5.3.6 Radiological Support Group, Revision 6 2.4 FT/0/3/4600/06 I argency Exercises and Drills 2.5 HP/0/B/1000/06 Emergency Equipment Functional Check and Inventory d' 3.0 LIM 111 AND PRECAUTIONS "'h 4 ii.; O g, s. . W ~ . ,, 4 3.1 The Emergency Radio Network is specifically limited to use in an l emergency drill, event, or operability check. 3.2 The Technical Support Center.(TSC) Base Station Remote Radio should
; be used to support operability checks of " Porta-Mobile" Field Monitoring Team Radios. ,
) 3.2.1 Emergency Radio System Base Stations and County / State j _,. . Coded Squelch Radios are checked for operability by . .. l FT/0/B/4600/06 (Reference 2.4).
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3.3 The following locations have radio capabilities for temporary emergency communications between: 3.3.1 Control Room and Allen Plant Steam Station (Evacuatior. Point) - Production and Transmission Frequency 47.98 nL j 3.3.2 Nuclear Production PAP (Security Zone ti2) or Construction
- Personnel Access (Security Zone #22) and Security Base l
Station (located in Control Room) or TSC Security i Representative - Dedicated Security Frequency i I NOTE: Relay messages through Security radio closest to locations in Step 3.4.2. 3.4 Emergency radio system operates on n! low-band dedicated frequency of 68.50 MHz except where noted in Sample Enclosure 3.1.
- ~- . ,
Pags 2 of e 3.5 Use telephone numbe'rs listed in Sample Enclosure 5.1 as primary communication links between TSC/ CMC and the following Evacuation Points: 3.5.1 Allen Steam Station 3.5,2. Transmission Line Maintenance Bu'.4 ding 3.6 Use HP/0/B/1009/04 (Reference 2.1) as information guide for field monitoring locations, directions and sampling. 4.0 PROCEDURE . - _ _ _ _ _ ,
. - ..- - . - . .A 1_. _ General Guidance for Emergency Radio Communications ,
L11 Onorate radios in accordance with Duke Power Company -. -
" Radio Operators Manual", (Reference 2.2). l
. - . . . J ___ ~~ ~
4.1.1.1 Use call signs and identifiers listed in Sample t .. . _ _ _ . _ .. Enclosure 5.1. i 4.1.1.2 Use Sample Enclosure 5.3 (Examples of Emergency Radio Communications) as format guidance for
- ! communicasions . ,
i ! i 4 si.2_,.
. ,M_inimise the length of transmissions by using code numbers !
{' t.:' and/or words listed in Sample Enclosure 5.2 as practicabler 4.1.3 Minimize the number of transmissions by: l . - Speaktus slowly and distinctly in a slightly -~ ; l 4.1.3.1
- louder than normal voice. r l
4.1.3.2 Transsisting numbers one digit at a time except .! I when reporting even thousands or time (hundreds l,,. . , ,, , of hours) as practicable. , , l l 4.1.3.3 Using phonetic alphabet listed in Enclosure 5.2 i when transmitting letters or when spelling : words. i 4.1.4 Precede transmissions with the asstage "this is a drill" during emergency drills. 4.2 Location of Emergency Radios , i 4.2.1 Obtain radics from storage locations listed in Sample j Enclosure 5.1. j
~
l 4.3 Emergency Radio Systes Activation ; i 4.3.1 Base Station Remote Radios : 4.3.1.1 Locate antenna lead and plug into modular (telephone-type) receptacle.
_ _ . ~ . _ _ _ _ _ . . l Pago 3 of 4
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4.3.1.2 Select AC switch on Base Station and energize by plugging power cord into AC receptacle. 4.3.1.2.1 Select DC switch an Base Station and energise by connecting DC leads to twin battery pack if AC power is not available. 4.3.2 " Porta-Mobile"/ Field Monitoring Team Radios 4.3.2.1 Turn power control switch to "0N" positioc. 4.3.2.2 Adjust squelch control knob clockwise until static is heard, then turn counterclockwise _. _ until static is just eliminated. 4.4 Emergency Radio System Operation 4.4.1 Base Station Remote Radios 4.4.1.1 Press key on microphone and hold to transmit messages; release key to receive transmissions. 4.4.1.2 Select " Intercom Mode" key for communication i between the following Base Stations:
@ 4.4.1.2.1 Transmission Line Maintenance , ,_
' , ~~;--- , ,
1 Building Base Station Remote.-- -
- 4. 4.1. 2. 2 Technical Support Center (TSC) Base Stat. ion 5tomoto.
I 4.4.1.2.3 Nearsite Crisis Management Center (CMC) Base Station Remote. I* Signal County and/or State coded squelch radios 4.4.1.3 l to receive specific transmissions by keying the I i , proper encoding numbers listed in Sample Enclosure 5.1.
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- 4.4.1.4 Record sample results received from Field ~' "
Monitoring Teams on Sample Enclosure 5.4. 4.4.1.5 Route Enclosure 5.4 (Sample Results Received By j The Radio Operator From Field Monitoring Teams) to Station Emergency Preparedness Coordinator for disposition as soon as practicable after event / drill is completed. 4.4.2 " Porta-Mobile" FMT Radios 4.4.2.1 Press key son microphone and hold to transmit messages; release key to rece,ive transmissions. 4.4.2.2 Hold microphone to the side of the mouth (at an angle) when transmitting messages.
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4.5 Inoperab a Radios .
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4.5.1 Base Station Remotes 4.5.1.1 Contact Station Emergency Preparedness Coordinator to report problems with Base Station radio operation. 4.5.2 " Porta-Mobile"/ Field Monitoring Team Radios 4.5.2.1 Refer to HP/0/8/1000/06 (Reference 2.5) for problems with radios normally stored in Health Physics Emergency kits. - - - 4.5.2.2 Use back-up " Porta-Hobile" radios in the event failures occur with primary " Porta-Mobile" radios. k I l l I i
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AKE rObi.R Co.'1I AM CATAWBA NUCLEAR STATION HP/0/3/1009/19
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SAMPLE ENCIASURE 5.1
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. .~ RADIO SPECIFIC DATA BASO STATION REM (YTE RADIOS g S1 DRED OPERATED CALL SIGN IDENTIFIER
- 1. Technical Support Center TSC TSC TBAL Base One
, 2. Nearsite CMC (G.O.) WC2314 WC1222 TBAL Base Two l
i COUTIT/STA1T CODED SOUEICH RADIOS USER ENCODING NUMBER CALL SIGN IDENTIFIER
- 1. Gaston County EOC TBAL TBAL Gaston County
- 2. York County EOC TBAL TBAL York County
; 3. Mecklenburg County EOC TBAL TRAL Mecklenburg County
- 4. S.C. State FEOC TBAL TBAL S.C. State
- 5. N.C. SERT TBAL TBAL N.C. State i
FIELD MONITORING TEAM RADIOS i USER STORED CALL SIGN IDENTIFIER , i h 1. Field Monitoring Team
- 2. Field Monitoring Team Aux 5143 5175 Aux 3143 517B TBAL TBAL Alpha Team Bravo Team
- 3. Field Monitoring Team Aux Blds 5175 TBAL Charlie Team
- 4. Field Monitoring Team Aux Blds 5178 TBAL Delta Team
- 5. Helicopter Team Aux Blds 5173 TBAL Echo Team
]
TEMPORARY DIERGENCY USE RADIOS 4 ) l *lT.LEP50lE I USER TYPE RADIO CALL SIGN IDENTIFIER FREQUENCY NUMBERS l 1. Allen Steam Station Base Station TRAL TBAL 47.96 MHz MW 373-4646 4 Bell (704) 525-2022
- 2. Transmission-Line Base Station TBAL TBAL 48.50 MHz MW 373-7309 Maint. 31ds. Bell 366-4777 l
- 3. Security (Constr. Handie-Talkie N/A Security TBAL TBAL 7 Personnel Access) Zone #22
- 4. Security (Nuc. Handie-Talkie N/A Security TBAL TBAL Prod. PAP) Zone #2
- 5. Security (Control Base Station TBAL TBAL TBAL TBAL Room)
- 6. Security (TSC Handie-Talkie N/A TBAL TBAL TBAL Representative) l .. - - - - ..... - ...-- -- --.- .-...--..-- -
.A . . . , , , ,, , ,
DJa Poi.ER CO.'1FANY CATAWBA NUCLEAR STATION
,. MP/0/3/1009/19 f e# SAMPIZ ENCLOSURE 5.1 RADIO SPECIFIC DATA LEGEND: EOC -
Emergency Operations Center FEOC - Forward Emergency Operations Center SERT - State Emergency Response Team CMC - Crisis Management Center PAP - Personnel Access Portal WC - Wachovia Center Offices
*nAL - To Be Added Later i
h i i i l O 1 b i l r
DlIE P0hT.R CO.TASY CATAWBA NUCLEAR STATION
'dP/0/B/1009/19
. C
SAMPLE ENCIASURE 5'.2 RADIO CODE SIGNALS CODE NUMBERS 1- Reporting On 2- Reporting Off 3- Stand By 4- VIP or Outsider Present 5-
... 6-7- Message Received and Understood or "Yes"
. . . 8 . Repeat (Message.not understood) .
9- Ca11.....t.......................By Phone 10- Read (Reread) Meter 11- Relay Message to ........................ 12- Fire (Give location) 13- Check for Trouble 14- Nothing for You 15 - Give Your Location 16- Trouble Cleared 17- Cancel Call 18- ' 19-20- Radio Test (How do you receive my signal?)
* *i,'
21- Request Assignment (Do you have anything for me?)
- n- . .
23-1 24- I Have an Emergency Situatt.on. P1' ease Give location. How Long Will It Take for You to Get into the Clear? 25-26-27-99- EMERGENCY ASSISTANCE NEEDED AT .......... (Give location)(Use only when serious threat to life or safety exists) CODE WORDS " PHONETIC AIAPHABET i 4 . . OVER - End of caeversation and A- Alpha N- November l avaiting reply 8- Bravo 0- Oscar i
.- 007 -
End of transmission and C- Charlie P .. Papa .-l no answer is expected D- Delts Q- Quebec End of transmission and CLEAR - E- Echo R- Romeo no answer is expected F- Foxtrot S- Sierra l NEGATIVE - No or incorrect G- Golf T- Tango ! ROGER - Affirmative or Yes II - Hotel U- Uniform l STAND-BY - Wait for further information I- India V- Victor l or instructions J- Juliette W- Whiskey i SAY AGAIN - Repeat last transmission K- Kilo X- X-Ray i WRONG - Message is being repeated L- Lima Y- Yankee i back incorrectly H- Mike Z- Zulu '
, WAIT -
Pause for a few seconds '
-- , .-...--,,.-----,,.m . - - , - . . . - . - . . , - - - . . , - . - , . - - - - - - - - , - - - , , . - .--
, _ .-= - - .
...r-DUKE POWER COMPAST CATAWBA NUCLEAR STATION HP/0/B/1009/19 8
SAMP2 ENCIASURE 5.3 j EXAMP2S OF EMERGENCY RADIO COMMUNICATIONS l i NOTE: The following call signs and identifiers are for example only. CNS TBAL ; l ! 5.3.1 Example of Base Station Signing On: BASE: WQC 699 BASE 1 (BASE 2 for CMC) CODE 1 (Signing On) BASE: BASE.1 to KA82139 (Team Name - Alpha, Bravo, Charlie, Delta Echo or Foxtrot) MOSI2: KA82139 ALPHA to BASE I CODE 7 (Go Ahead) BASE: STANDSY FOR FURTHER INSTRUCTIONS
; N08ILE: CODE 7 (Message Received) EA82139 ALPHA OLTT BASE: WQC 699 BASE 1 OUT 5.3.2 Example of Field Monitoring Team Signing On:
i MOBILE: KA82139 M to BASE 1 BASE: BASE 1 to M MOBILE: CODE 1 (Raporting On) { BASE: CODE 7 (Message Received) WQC 699 RASE 1 OUT l MOBILE: KA82139 ALPHA OUT 5.3.3 Example of Field Monitoring Team
- Reporting Data:
1 MOBILE: KA82139 3RAVO to BASE 1 BASE: BASE 1 to BRAVO l MOBILE: LOCATION M TIME 2015 HOURS ! DOSE BATE HEASUREMDrr .02 mR/hr r
- IODINE ACTIVITY 5.1 x 10 gCi/ml i BASE: WQC 669 BASE 1 OUT .
NOTE: DATA is recorded by base station radio operator on Enclosure 5.5 of Procedure CP/0/3/4003/01. 5.3.4 Example of Base Station Operator Dispatching Field Monitoring Team to New Sampling Location: l BASE: WQC 669 BASE 1 to KA82139 CHARLIE MOBILE: KA82139 CHARLIE TEAM to BASE 1 GO l BASE: CHARLIE TEAM PROCEED TO LOCATION M-1 I MEASURE AND REPORT DOSE RATE AND IODINE ACTIVITY MOBILE: LOCATION M , CODE 7, CHARLIE OUT BASE: WQC 669 BASE 1 OLTT i _ - . . _ - - _ _ . , . . _ . _ ., , ~ . -
. ., . , ~ . . .
DCiG. POWER CO.MPANY CATAWSA NUCLEAR STATION RP/0/3/1009/19 SAMP2 ENCIDSURE 5.3 EXAMPLES OF EMERGE. E Y RADIO COMMLHICATIONS 5.3.5 Example of Field Monitoring Teas Signing Off: - - . - - - l MOBILE: KA82139 DELTA TEAM to BASE 1 ! BASE: BASE 1 to DELTA TEAM MDRI2: CODE 2 (Reporting Off) , BASE: CODE 7, WQ 669 BASE 1 OUT ' NOTE: BASE"1 should sign off when all mobile teams have signed off.: EXAMPLE: WQ 669 BASE 1 , CODE 2 -- 5.3.6 Example of Communication Check: BASE: WQC 699 BASE 1 (BASE 2 for CMC) CODE 1 (Signing On) BASE: BASE 1 to KA82139 (Team Name - Alpha, Bravo, Charlie. Delte Echo or Foxtrot) i I i MOBILE: KA82139 ALPHA to BASE 1 CODE 7 (Go Ahead) l g.,, BASE: NOW DO YOU RECEIVE MY SIGNAL 7 i
&, MOBIII: IAUD AND CLEAR KA82139 ALPHA OUT
- l BASE: WQC 699 RASE 1 OUT _
t . i e I i G h eem e ee e. e. - 4 l .. _ j f + 4
- I l l l
i i t i . l I i I a . i - !
l - -
.* - e . . . . .-- .. . .. ,, , .
t .... , ,, ., DUKE POWER COMPANY
. CATAWBA NUCLEAR STATION
. MP/0/3/2009/19
. FS. SAMPIZ ENCLOSURE 5.4
. .b
. SAMPLE RESULT 5 RECEIVED BY 11IE RADIO OPERA 7DR FROH FIELD MONITORING TEAMS DATE RADIO OPERATOR 1
nan I TEAM SAMPIZ TIME DOSE I l LOCATION SAMPLE
- RATE ACTIVITT DOSE RATE i TAKEN mR/hr pC1/m1 ares /hr l l
O
.m=
9 l t 9 1
Fom SPD-1002-1 DUKE POWER COMPANY (1)' ID No: HP/0/B/1009/20
, PROCEDURE PREPARATION Change (s) 4 to PROCESS RECORD d Incorporated (2) STATION: Catawba (3) PROCFDURE TITLE: Procedure For Estimatino Food Chain nnset lindar pnet Accident Conditions (4) PREPARED BY: , /) [Y M DATE: /-/b~ - 73 (5) REVIEWED BY: DATE: tN 3
' ' // ~ / / /
Cross-Disciplinary Review By: N/R: (6) TEMPORARY APPROVAL (IF NECESSARY): 't By: (SRO)* Date: By: -- a Date: (7) APPROVED BY:
- Date: b (8) MISCELLANEOUS:
Reviewed / Approved By: Date: Revie.ved/ Approved By: Date: . [ i
- i I
i
?
i
f 1 HP/0/B/1009/20 DUKE POWER COMPANY { CATAWBA NUCLEAR STATION PROCEDURE FOR ESTIMATING FOOD CHAIN DOSES UNDER POST ACCIDENT CONDITIONS 1.0 PURPOSE ) Usually the determination of potential areas of concern in the ingestion pathway under post-accidest conditions will be made by the Recovery Manager, the Offsite Radiological Coordinator or the Emergency Coordinat r based initially upon station releases, prevailing meteorological and hydrological conditions, and confirmatory measurements of dose rates and air sample results by field monitoring teams. This procedure describes the method to be used in order to rapidly estimate offsite doses through significant food chain dose pathways under pcst-accident conditions. It is to be used only at the request of the
- State (s) or under the direction of the Recovery Manager, the Offsite
- Radiological Coordinator or the Emergency Coordinator.
2.0 REFERENCE .
- U. S. NRC Reg. Guide 1.109 3.0 LIMITS AND PRECAUTIONS l 3.1 Reg. Guide 1.109 is intended to guide the calculation of doses under long term steady state conditions. The body of this procedure i
t contains notes covering cases in which the calculation of doses under accident conditions differs from the calculation of doses under routine conditions. 3.2 This procedure covers only the calculation of the food chain pathway doses most likely to be limiting under post-accident conditions. Other food chain doses must be calculated using the methods of the Duke Power Company Offsite Dose Calculation Manual or Reg. Guide 1.109. General Office Health Physics personnel shall be consulted when these other food chain doses are calculated. 3.3 The errors in the doses calculated through the use of this procedure are not necessarily conservative (on the high sidp). 3.4 The assumptions outlined in this procedure shall be carefully compared with existing post-accident conditions before this procedure is used. 3.5 This procedure calculates doses by relating concentration to the uptake by the individual and the associated dose factor (ares /pci).
HP/0/B/1009/20 Pcga 2 of 6 4 4-3.6 It is expected that the samples will be collected by Field Monitoring teams under the direction of the Offsite Radiological Coordinator. These samples shall be analyzed at the Radiological Environmental Laboratory. 4.0 PROCEDURE 3 4.1 Vegetation + Cow or Goat Milk + Consumer Dose Pathway for Radioiodine
4.1.1 Assumptions
Child (Infant) milk consumption: 900 al/ day (2 pints approx.) Adult milk consumption: 850 al/ day (2 pints approx.) Decay time between iodine deposition on vegetation and milk consumption: 2 days. All (100%) of the milk animals' feed is fresh pasture i vegetation; if this is known not to be the case, calculate . the concentration eaten by the animal by multiplying the j concentration in the pasture vegetation by the fraction of
, feed which is fresh pasture vegetation.
l
! The contribution to dose of I-132 and I-134 is negligible because of the short half-lives and small dose factors for these radionuclides.
4.1.2 Doses can be calculated on the basis of radiciodine ' ) concentrations measured in or on either grass (or other i vegetation consumed by milk animals) or milk. Doses calculated on the basis of milk radioiodine concentracions will be much more_ accurate than those calculated on the basis of vegetation radiciodine concentrations. However, the measurement of vegetation radiciodine concentrations i l permits the prediction of approximate doses due to milk consumption one or two days later. l Follow-up vegetation radioiodine analysis with milk , radioiodine analysis for several days to ensure accurate { dose assessments. i f 4.1.3 Calculation of doses through vegetation analysis: l 4.1.3.1 Collect samples of vegetation eaten by milk
, animals and analyze on GeLi counter. Compute i
radiciodine concentrations in WC1/ gram of undried vegetation. j NOTE: All calculations for vegetation samples are done for cows; however, if the dose from goat milk is desired, j simply multiply the dose from cow milk ingestion by 1.2. . 5 l ! I i
- - , - , . , . - , , , - - _ . , . , , - , - . . . . , - , , - , , , - . - - - , - - _ - - - . g--, e.r.,,,- , - - - - , , , . -
,,a - --,.-------n.--,,--m n.,,,--
HP/0/B/1009/20
. Pagt 3 of 6 4.1.3.2 Calculate thyroid doses by use of the following equations:
D TCV = 3200 Cgg31, + 180 Cy133y + 1.1 C I135v U TAV " 1131v 1133v +
- 1135v whsre: Dg = human child (infant) thyroid dose commitment in rems per day milk animal consumes contaminated vegetation.
DTAV = Same as above for human adult. Cy131, = Concentration of I131 in vegetation (pCi/g). C I133v " ""*"*#8*I " ' '" **8*** ' " l (uCi/g). Z C I135v " ""*"E'**I " I '" Y*8****I " (bCi/g).
?
4.1.4 Calculation of doses through milk concentrations: 4.1.4.1 Collect samples of milk and analyze on GeLi counter. Compute radioiodine concentrations in pCi/ml. 4.1.4.2 Calculate thyroid doses by use of the following equations: DTCH = 13000 Cyg33,+ 3000 CI133m + 590 CI135m DTM = 1700 Cgg33,+ 300 Cyg33,+ 65 CI135m where: D = human child (infant) thyroid dose TCt! commitment in rems per day of consumption of contaminated milk. D M1 = Same as above for human adult. Cgg3g,= Concentration of 1133 h a m (pCi/ml) Cyg33, = Concentration of 1133 in am (WCi/ml) C ""*"****I " ' II3$ '" " I135m " (DC1/ml) NOTE: Whole body doses due to radiciodine insestion will always be much smaller than the thyroid dose.
HP/0/B/1009/20 Pega 4 of 6 4.2 Drinking Water
- Consumer Pathway For Radioiodine
4.2.1 Assumptions
Child (Infant) water consumption: 900 al/ day (2 pints approx.) Adjust water consumption: 2000 al/ day (4 1/3 pints approx.) Decay time in water distribution system: 1 day. The contribution to dose of I-132 and I-134 is negligible 4 because of the short half-lives and small dose factors of
, these radionuclides.
4.2.2 Calculation of doses through water concentrations: 1 4.2.2.1 Collect water samples and analyze on GeLi counter. Compute radioiodine concentrations in DCi/nl.
- 4.2.2.2 Calculate thyroid doses by use of the following
] equations: 4 DTW = 12000 CI131w + 1400 CI133w + 50 CI135w DTAW = 3700 Cyg33,+ 320 CI133w + 1 C I135w where: DTCW = human child (infant) thyroid dose commitment in rems per day of consumption of contaminated water. l _ Dgg = Same as above for human adult. Cgg33, = Concentration of H31 h water l (UCi/ml) Cg133, = Concentration of H 33 in water (DCi/ml) CI135w = Concentration of I135 in water ! (DCi/ml) NOTE: Whole body doses due to radiciodine
- ingestion will always be much smaller than the thyroid dose.
l 4.3 Water + Fish
- Consumer Pathway For Radiocesium
4.3.1 Assumptions
Child (teen) fish consumption: 44 g/ day (1) oz approx.) Adult fish consumption: 57 g/ day (2 oz. approx.) l Bioaccumulation factor for cesium in fish: 2000. The contribution to dose of Cs-138 is negligible because of its short half-life and small dose factor.
- c. . .- ._ - - -
HP/0/B/1009/20
., Pass 5 of 6 4.3.2 Doses can be calculated on the basis of radiocesium concentrations in either water or fish. Doses calculated
~ on the basis of concentrations in fish will be more l j , accurate than those calculated on the basis of concentration in water. However, the measurement of water radiocesium concentrations permits the prediction of doses due to future consumption of fish.
4.3.3 Calculation of Doses Through Water Analysis: 4.3.3.1 Collect water samples and analyze on GeLi counter. Compute radiocesium concentrations in pCi/ml. l
! 4.3.3.2 Calculate whole body doses by use of the following equations:
D BCW = 8000 CCs134w + 2000 CCs136w + 4600 CCs137v D BAW = 14000 CCs134w + 200 CCs136w + 8200 CCs137w 1 where: DBCW = human child (teen) whole body dose commitment in rees per day j fish are exposed to contaminated water. I , DBAW = Same as above for human adult. C = Concentration of Cs134 in water (DC1/ml) Cs134w C Cs136w = Concentration of Cs136 in water (pCi/al)
=
l C Cs137w ncentrati n f s 37 h water (DC1/al) 4.3.4 Calculation of Doses Through Fish Concentrations: 4 4.3.4.1 Collect fish samples and analyze in GeLi
- counter. Compute radiocesium concentrations in pCi/ gram (wet weight).
4.3.4.2 Calculate whole body doses by use of the following equations: . DBCF = 4.0 CCs134F + 1.0 CCs136F + 2.3 CCs137F ] D 1 BAF = 6.9 CCs134F + 1.1 CCs136F + 4.1 CCs137F where: D = Human child (teen) whcle body BCF dose commitment in reas per-i day of consumption (at 44 g/ day) of contaminated fish. i D BAF = Human adjult infinity whole 1 body dose commitment in reos per day of consumption (at 4 57 g/ day) of contaminated fish.
HP/0/B/1009/20 Pego 6 cf 6 C Cs134F " ""*"****I " ' "I ' fish (pCi/g) i
= ncentrati n s136 in Cs136F fish (pCi/3)
C Cs137F = Concentration of Cs137 in fish (pCi/g). NOTE: In any one day, a person may easily consume 5 or even 10 times the assumed daily quantity of fish. Liver doses due to radiocesium ingestion are about two times the whole body doses; therefore, the whole body doses are limiting. 4 5.0 ENCLOSURES 1 5.1 Food Chain Dose Calculations Worksheet 4 J
, l ENCLOSURE 5.1 FOOD CHAIN DOSE CALCULATIONS WORKSHEET t
, DATE: PERFORMED BY: 1 I.- Dose to Thyroid From Radioiodine A. Vegetation
- Cow or Goat Milk
- Consumer Dose Pathway
- 1. Vegetation Analysis: Date Sampled Location Multiplying Factor Age Isotope Concentration In (res/d)
Group Dose (I- ) Veneration (uCi/m) (uCi/z) (res/d) Child 131
- 3200** =
(Infant) 133
- 180** =
135 * ] .1.1** = Total Dose = Adult 131
- 420** =
133
- 20** =
135 * = 0.1** 11 Total Dose = 1
**All multiplying factors for vegetatien are for cow milk, if the dose fron goat milk is desired, multiply the dose from cow milk calculations by 1.2. l
- 2. Milk Analysis: Date Sampled Location Multiplying Factor Age Isotope Concentration In (res/d)
Group Dose (I- ) Milk (uCi/ml) (uCi/ml) (res/d) Child . 131
- 13000 =
(Infant) 133
- 3000 =
i 135
- 590 =
t Total Dose = ! Adult 131
- 1700 =
l 133
- 300 =
135
- 65 =
Total Dose = [ i
ENCLOSURE 5.1 (centinued) , B. Drinking Water
- Consumer Dose Pathway:
Date Sampled Location Multiplying Factor Age Isotope Concentration In (res/d) Dose G,roup (I- ) Vater (DCi/ml) * (yCi/ml) (res/d) Child 131
- 12000 =
(Infant)' 133
- 1400 =
135'
- 50 =
Total Cost = 4 Adult 131
- 3700 =
133
- 320 =
135
- 12 =
Total Cost = II. Dose to Whole Body From Radiocesium: A. Water
- Fish + Consumer Dose Pathway
- 1. Water Analysis: Date Sampled Location Multiplying Factor Age Isotope Concentratica In (res/d) Dose Group ) Water (pCi/ml) (VCi/ml)
(I- (res/d) Child 134
- 8000 =
(Infant) 136
- 2000 =
137
- 4600 =
Total Cost = Adult 134
- 14000 =
136
- 2200 =
137
- 8200 =
Total Cost =
ENCLOSURE 5.1 (Continu:d)
- 2. Fish Analysis: Date Sampled Location Mulciplying Factor Age Isotope Concentration In (res/d) Dose Group (Cs- ) Fish (vC1/a) (uci/m) (res/d)
Child 134
- 4.0 m (Infant) 136
- 1.0 =
137
- 2.3 =
Total Dose = Adult 134
- 6.9 =
136
- 1.1 =
- 137
- 4.1 =
Total Dose = x O r ~
( - - + l CP/0/A/8700/11 SAMPLING AT THE POST ACCIDENT LIQUID SAMPLE PANEL
* (LATER)
e
. Catawba Nuclear Station Directive 3.7.5 (AS)
Revision No. 1 ,Date /2 - 2./ - 3 k Approval, 'b A ) r i
/ \
~
DUKE POWER Cot!PANY
- l CATAWBA NDCIIAR STATION -
RESPONSE TD 30tG TEREAT 1.0 PURPOSE To provide guidanc for the safe and orderly response to bomb threat " emergency situations which may endanger the station or station personnel and provide for the subsequent investigation and reporting. 2.0 SPECITIC RESPONSIBILITIES 2.1 Employee Receiving Threat Call 2.1.1 Respond tp .sil as stipulated, in Section 3.1 of this Directive. 2.2 Station hanager 2.2.1 Orders site evacuation depending upon review of circumstances prevailing and establishes assembly locations.
2.2.2 Notify
Appropriate Department / Company Management Corporate Comunmications NRC Region II (404) 221-5529 2.3 Chief of Security 2.3.1 Coordinates activities between the Security Force and j - site /coc@any management. 2.3.2 When time and circumstances permit, order search of the area by ' Security Force members who are to be augmented by fire brigade personnel. 2.3.3 Notify local law enforcement agencias as appropriate: York County Sheriff Dept. 327-2021 FBI - Columbia, SC 234-3011 SLID - Columbia, SC 758-6000 SCHP - Rock Hill, SC 366-7668 2.4 Security Captain . _ 2.4.1 Directs Security Force activities acecrding to situational demands.
l CNS Directive 3.7.5 Page 2 of 4 2.5 Security Shift Supervisor 2.5.1 Receive, review and pass on data from search team leaders. 2.3.2 Receive threat call informatica from Construction foremen on backshifts and pass it on to the Operations Shift Supervisor.
, 2.5.3 Nc;ify Security management as necessazy on backshifts.
2.6 Security yozco Personnel
- 2.6.1 Conduct search of assigned area and report fin %== to the Security Shift Supervisor. -
2.6.2 Provide for personnel access control as directed by the Security Shift Supervisor. 2.7 Station Personnel 2.7.1 In the event of a partial or complete site evacuation, when time and circumstances permit, station personnel will remove all hand carried personal items from their assigned work area. 3.0 RITERENCIS 3.1 Casauba Nuclear Station Contingency Plan 3.2 Catawba Nuclear Station Security Procedures 3.3 Catawba Nuclea: Station Imergency Plan 4.0 ADDITIONAL INFORMATION 4.1 The safe e d orderly response to bomb threat situations depends upon the coordination cf activities among employees, station management and outside agencies . This coordination will result from the proper education and direction of those involved. 5.0 PROCIDURE 5.1 Roteipt of threat I l 5.1.1 As soon as it is descrained that the call is related to a bomb threat, turn on the tape recorder. 5.' 1
*dsten to caller carefully for background sounds, speech dsfacts, accent or repeated words or phrases. Keep caller ;
on the phone as long as pcssible. 5.1.3 Find out as much infernation as possible about the explosive, I such as: type, location, time device is ices to go off; and I motive for placing the bomb. I l i r
CNS Directive 3.7.5 Page 3 of 4 m 5.1.4 Advise the caller that the building is occupied and the detonation of a bomb could result in death or serious ~ injury to many innocent people. 3.1.5 lamediately notify the Chief of Security T. K. Anderson (2326), Security Captian, J. H. Roach (2452) or the Shift Supervisor (2337). 5.1.6 Complete the attached form, " Bomb Threat calls". 5.1.7 Take the tape to the Security Shift Lieutenant. 5.2 Security Force Actions 5.2.1 The. Security Force will be notified through Security . supervision. 5.2.2 Based on the situation, the Security Shift Lieutenant will assign areas to be searched by Security Force Members. 5.2.3 All emergency evacuation routes will be set:ched by security prier to evacuation, if time and circumstances permit. 5.2.4 If no explosive / incendiary dsvice is found by the Security Force Member, he vill so report to the Se'curity Shift ,, Lieutenant. The Security Shift Lieutenant and Station Management contact will be located in a mutually agreed upon place established at the time of the initial call for sa:urity assistance. 3.2.5 If an explosive / incendiary device is located, then the area shall be evacuated, if no already done so, and properly ) identified and protected against re-entry. The Security Force Member will notify the Security Shift Lieutenan . Upon notifiestion, the Bcab Disposal Unit. 48th Ordinance Detachment. For: Jackson. S.C. (803-731-3126 will be called. The Security yorce Member will not attempt to clea the { explosive. j 5.2.6 In the event that an explosive or incendiary device is
\
l actuated, the procedures as listed in the Station Contingency 1 Plan anc F.mergency Plan will be followed. I i If there are injuries, Station Directive 211.~ Personal l Injury Procedure, wf11 be followed. ! 5.2.7 After completion of the search and i: has been deternised 1 that there is no bomb, all personnel will be directed to return to their normal work area by the Station . Manager. O l l
c-CNS Directive 3.7.5 Page 4 of 4 5.3 Site Evacuation 5.3.1 At the time the site evacuation is ordered, the assembly location will be established for each group /section by the person ordering the evacuation. 3.3.2 When the evacuation and assembly is complete, the section supervisor will notify the appropriate station management that all subordinates are accounted for. 5.3.3 h Security Shift Supervisor should be notified of any personnel
- unaccounted for.
5.3.4 All plant visitors will report to the receptionist area upon notification of site evacuation unless directed otherwise by site managesent. 5.4 Bomb Threat Investigation 5.4.1 As soon as practical, security management will initiate an investigation of the incident. 5.4.2 Tork County Sheriff, SEED, FBI assistance will be requested, as appropriate. b site Security Force will provide assistance as necessary to the ILEA with lead responsibility.
~
5.4.3 Security will provide documentation and reports as appropriate. l 1 l 1 1 0
,e l
e l t
susD m p3.7.5 CATAWBA NUCLEAR STATION AN' TELEPHONE PROCEDURES B0ps THP2AT CHECKLIST t i INSTRUCTION Be cals, courteous and listen; do not interrupt the caller. Date and Time TelepFone line call received on of call. QutiSTIONS'TO ASK: EXACT WORDING 0F THE THREAT:
- 1. When is bomb going to explode? I
- 2. Where is it right now?
- 3. What does it look like?
4 What kind of bomb is it? Explosive: Incendiary:
- 5. What will cause it to explode? !
t
- 6. Did you place the bomb?
- 7. Why? I S. What is your address? I
- 9. What is your name?
Sex of caller Age
- 1 Race Length of call CALLER'S VOICE:
1 Cala Laughing Lisp Angry Crying Disguised i Raspy Accent Excited Normal Deep ! i i Slow Distinct Familiar ! i _ Rapid Slurred Ragged Clearing' Throat H ice is familiar, ' Soft Nasal who did it sound like? Deep Breathing Loud Stutter' Cracking Voice BACKGROUND SOUNDS: l Street Noises House Noises Factory l Crockery Motor Local Voices Machinery Long Distance PA System Office Anima Noises Booth l Machinery Clear Other , ( Music Static i I i THREAT LANGUAGE: i i Well Spoken Foul ! Incoherent Message read by ' (Educated) Irrational Taped threat maker -- Other NOTIFIED: i l Chief of Security AM-PM; Superintendent of Administration _ !
, Supervisor AM-PM; Operations AM-PM; Securi'.y Shift Supervisor AM-PM; Other i
AM-FM. SIGNATURE l I t r
CATAWBA NUCLEAR STATION DIRECTIVE 3.8.4 (TS) REV. NO. 6 DATE E-7-N APPROVAL If. I . Ak
/ /
DUKE POWER C0!!PANY v . CATAWBA NUCLEAR STATION ONSITE EMERGENCY ORGANIZATION i 1.0 PURPOSE t To define the role of the Emergency Coordinator and other members of the Onsite Emergency Organization in implementing the station Emergency Plan and to provide for augmentat.d.on of the normal operating shift during an emergency situation. I
2.0 REFERENCES
i 2.1 Catawba Nuclear Station Emergency Plan j l 2.2 Catawba Nuclear Station Operations Management Procedure 1-8,
" Authority and Responsibility of Licensed Reactor Operators and !
Licensed Senior Reactor Operators" - 2.3 Station Directive 2.8.1 (TS) " Reporting Requirements" 2.4 Catawba Nuclear Station Operations Management Procedure 2-15
" Notification of Proper Authority".
2.5 Station Directive 3.0.7 (TS), Site Asse=bly/Evacuatien. 3.0 SPECIFIC RESPONSIBILITIES 3.1 Shift Supervisor - All emergtncies are initis1;y .:2nd".c by .he Shift Supervisor. The Shif*. Supervisor on duty will caura -hat all immediate actions required by station emergency or abnertal procedures, applicable to the situation, are performed and that all actions necessary for the protection and safety of personnel and property are being taken. 3.2 Emergency Coordinator - The Shift Supervisor shall assume the function of the Emergency Coordinator until the arrival of the
, Station Manager or his designee at which time the functions of the Emergency Coordinator are transferred to the Station Manager or his designee.
The Shift Supervisor shall then continue to take acticns necessary to ensure that the .;;;:rgency situation is brought under control. 3.3 Recovery Manager - The responsibilities of the Emergency Coordinator will be assumed by the Recovery Manager at the Crisis Management
S.so u44aw.4.. s.w.- - -= **
.-a=
Center (CMC) as this organization is staffed and ready to assume its function. This assumption of the Emergency Coordinator functions by the Recovery Manager, will take place for the Site Area Emergency and General Emergency classifications. The Emersency Coordinator shall continue to take actions necessary to ensure that the emergency situation is brought under control and shall coordinate activities between the station and the CMC. 4.0 DUTIES 4.1 Shift Supervisor / Emergency Coordinator - immediate duties incitie the following: 4.1.1 Determine from the initiating conditions what Emergency Class the Station is in. 4.1.2 Declare the Emergency as necessary and assume control as the Faergency Coordinator.
; 4.1.3 Assign someone from the shift to begin the notifications as per applicable p acedure.
4.1.4 Take necessary cn site remedial actions. 4.1.5 Initiate activitation of the Technical Support Center and
; Operations Support Center.
4 1.6 Providing protective action recommendations to authorities responsible for implementing offsite emergency measures. NOTE: This authority and responsibility shall not be delegated to other elements of the station emergency organization. 4.2 Station Manager /Ecergency Coordinator - relieves the Shift Supervisor of the Emergency Cerrdinc.cr's duties and assumes the responsibility for implemen i:q :he s ::ica Emergency Plan including: 4.2.1 Staffing the Technicsi 5 p;.cr: Canter and Operations Support Center with those perscanel deemed necessary to . effectively assess the e=erger.cy condition. I 4.2.2 Instituting those procedures :,ecessary to allow the Control Room to gain immediate centrol of the emergency situation. 4.2.3 Notification and activation of Crisis Management Team, county and state organisations and the Nuclear j Regulatory Commission. 4.2.4 Providing protective action recommendations to authorities responsible for implementing off-site emergency measures. NOTE: This authority and responsibility shall not be delegated to other elements of the station emergency organization. l_ ............--.3..-.
.r - .... ,
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,'CNS Dircetiva 3.8.4 -
Pago 4 of 13
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regarding solutions to operational problems. He shall provide technical expertise to other members of the TSC in the areas of Health Physics, Chemistry, Performance and Reactor Engineering and in Licensing and Engineering support programs. He shall ensure that all areas of responsibility under"his direction are staffed with competent personnel, prcperly trained and prepared to support any operational emergency condition. This individual shall.be the second alternate to the Emergency Coordinator in the event the Station Manager is unavailable. B. The Health Physics Section of the TSC
- 1. The Station Health Physicist shall assume the duties c,2 the Superintendent of Technical Services when so designated. He will provide technical expertise to the Superintendent of
- Technical Services, the Station Manager and other members of the TSC as required. He will provide for the calculation and distributin of offsite dose determinations f ar releases of radioactive materials to the atmosphere and make reccamendations to the Station Manager through the Superintendent of Technical Services on Protective Actions necessary for limiting exposure to station personnel and members of the public. He shall ,l also be re'sponsible for directing decontamination acti'ities. The Station Health Physicist shall also work closely with the appropriate members of I the Crisis Management Center to assure that j
radiological hazards during any emergency i situations are minimized. The Station Health Physicist shall ensure that all areas under his direction are staffed and prepared to manage Health Physics support for any emergency condition.
- 2. Health Physics S&C Coordinator shall coordinate and direct the actions of in plant radiological monitoring teams and provide data on plant radiological status,
- 3. H. P. Supoort Coordinator shall direct the i actions of the. remainder of the Health' Physics !
functions and maintain contact with the Health ! Physics personnel . stationed at the Operations ' Support Center (OSC) to provide support for any emergency condition. l
- 4. Data Analysis Coordinator shall provide for the calculation and distribution of Off-site Dose ; !
' projections and field monitoring information j assessable by Health Physics personnel and relay . this to the Station Health Physicist. i
..., . . . . . . . . . . ~
F. The Licensing and Projects Engineer shall' assume the I duties of the Superintendent of Technical Services when so designated. He will provide technical expertise to the superintendent of Technical Services and to the members of the TSC as required. He is responsible for coordinating station activities with regulating agencies, coordinating the reporting and investigation of all incidents and for providing review of appropriate station technical matters. The License and Projects Engineer shall ensure that all areas under his direction are staffed and prepared to manage technical support for any emergency condition.
, G. TSC fonkeeper shall record events that occur from the time of activation of the TSC and shall be directed by ;
the Emergency Coordinator. This individual will be an engineer from the station's Projects group. H. Offsite Communicator shall make followup I notifications to State and/or County EOC's. This individual shall be an engineer from the Station's Licensing and Projects Group. 4.3.3 Administrative Group: ' A. The Superintendent of Administration when designated - shall assume the duties of the Station Manager. He
' will provide techical expertise to the Station Manager and to the Shift Supervisor (via the Operating Engineer) regarding solutions to administrat'ive problems associated with emergency conditions at the station. He shall provide technical expertise to other members of the TSC in the area of Contract Services, Security, Training and Safety, and Administrative Coordination. He shall ensure that all areas under his direction are staffed and prepared to manage administrative support for any emergency condition. This individual shall be the fourth
' alternate to the Emergency Coordinator in the event the Station Manager is unavailable. {
B. The Chief of Security shall assume the duties of the ! Superintendent of Administration when so designated. i 4 He will provide technical expertise to the ; Superintendent of Administration and to other members of the TSC as required. He is responsible for j coordinating Security and Contract Services for the station. The Security Chief shall ensure that all' areas under his direction are staffed and prepared to manage Security and Contract Services for any emergency condition. C. The Administrative Coordinator shall assume the duties i of the Superintendent of Administration when so { designated. She will provide technical expartise to ! i t __1 m 2-m - - r 1 -- - - - - -- ~~ ~~ '
chd utrcctiva J.o.o rage o or ta C. The Planninz Enzineer shall assume the duties of the Superintendent of Maintenance when so designated. He will provide technical expertise to the Superintendent of Maintentice and to other members of the TSC as required. He is responsible for the implementation and evaluation of the maintenance management program and for the administration of the materials procurement program. The Planning Engineer shall insure that all areas under his direction are staffed and prepared to manage planning and materials support for any emergency conditior.. D. The Instrument and Electrical Engineer shall assume the duties of the Superintendent of Maintenance when so designated. He will provide technical expertise to the Superintendent of Maintenance and to other members of the TSC as required. He is responsible for maintaining all station I&E equipment in an operational state. The Instrument and Electrical Engineer shall ensure that all areas under his direction are staffed and prepared to manage I&E support for any emergency condition. 4.4 Operations Support Center Staff 4.4.1 The Operations Support Center (OSC), location shown in Enclosure 5, shall be activated by the Emergency Coordinator in accordance with the applicable Emergency Procedure. The
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0.S.C. will be staffed and organized as per Enclosure (3) or as deemed necessary by the Shift Supervisor or Station Manager. Those personnel assigned to the 0.5.C. shall be under the supervision of a Shift Supervisor or other 7 Operations Group Supervisor designated by the Emergency Coordinator. 4.4.2 The Operations Support Center sh:11 irt;ude as a minimum the following personnel: A. Operations: Operators on shift wh: Are :.o. actually assigned to the control room and additicna: cperations people on site or called out as required by the Shift Supervisor or Station Manager. B. Health Physics: A Health-Physics Supervisor and five technicians as deemed necessary by the Station Health ! Physicist. The Health Physics Supervisor shall work closely with the Shift Supervisor in charge and shall maintain contact with the HP Support and S & C Coordinators ) in the TSC. { C. Other station groups as necessary. 4.4.3' In the event that the Operations Support Center becomes environmentally uninhabitable due te radiological or other conditions, the OSC shall move to the rear of the Control Room or to other fscilities as applicable.
.y . . .
1 l l l 5.3 Phase II of the Technical Support Center 5.3.1 Phase II of the Technical Support Center organization shall be staffed and organized as indicated below or as deemed
. necessary by the Station Hanager.
A. Operating Engineer B. Assistant Operating Engineer C. The Station Chemist D. The Reactor Engineer E. Performance Technician (s) F. The Licensing & Projects Engineer G. The Mechanical Maintenance Engineer H. The Cliief of Security I I. The Training and Safety Coordinator l 5.3.2 Personnel assigned to Phase II of TSC shall be capabl6 of supplementing the on-shift Emergency Response within 45 to J 75 minutes of notification 5.3.3 In the event that the Technical Support Center becomes environmentally uninhabitable due to radiological or other conditions, Phase II of the T.S.C. shall move to the Administration Building or to other facilities as applicable, when directed by the Station Manager. 5.4 Other TSC Personnel 5.4.1 Full activation of the TSC is as shown in Enclosure (1). Other personnel not specified as part of the Phase I and II staff but still necessary for TSC are as indicated below: A. The Administrative Coordinator B. The Planning Engineer C. Clerks as needed, determined by Group Superintendents D. TSC Logkeeper E. Radio Operator 5.e. This group shall be activated as soon as practicable. ' [ 5.5 OSC Sotification 5.5.1 Operations personnel will be notified by the Operation's Duty Engineer or someone designated either by station phone ' or home phone as required. I t 5.5.2 Health Physics personnel will be notified by the Station l j Health Physicist or alternate either by station phone or i home phone as required. ! 6.0 EMERGENCY ORGANIZATION SUPPORT 6.1 Clerical assistance for the Station Manager and the four stetion superintendents will be provided by one of their normally assigned 1 I k t
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4 A. This position reports to the Emergency Coordinator or his designee for matters pertaining to personnel disposition, seals and status of the evacuation.
. B. All evacuated supervisory personnel will in turn report to the Evacuation Coordinator.
6.5.2 The Emergency Coordinator shall notify the Evacuation Coordinator of the need for a Site Evacuation. See Enclosure (6). 7.0 TRAINING & DRILLS 7.1 Initial Training 7.1.1' Training will be provided for Onsite Emergency Organizations personnel listed in Enclosure 1 of this directive as per Station Directive 2.5.2 (TS). 7.1.2 Operations personnel, Security personnel and Fire. Brigade members will receive training as a part of their regular shift training or as scheduled by the Training Coordinator. 7.1.3 New personnel brought into the Emergency Organization will be given initial training on a yearly basis. 7.2 Annual Training 7.2.1 t,11 Emergency Organization personnel .Lil receive annual overview retraining as per part 0 of the Emergency Plan. 7.3 Special Training 7.3.1 Training will be given to the following groups on an
, annual basis, the following areas will be covered:
A. Offsite and onsite monitoring to H.P. ! B. Information transmission to offsite agencies to Offsite Communicators and Operations C. Dose calculations to H.P. and Operations l l D. Data transmission / retrieval to Performance Technicians ! E. Protective action recommendations and emergency class-ification to Emergency Coordinators, Station Health Physicist & Emergency Preparedness Coordinator. F. Repair and recovery training to Maintenance Section Engineers, Coordinators, Supervisors and Technical Specialists.
e 4-
- ONSITE EME RGEleCY ORGANIZATION TECHeteCAL SUPPORT CENTE R ST AF F EMEAGENCY S O 3 8 4 E9eCL lll COORDINATOR RE VISION 6 P. J W HAMPTON g A. C. W GRAVES J.W.COM G. 7. SMITH A R F R ANK L IN l .
I I 7 OPE R ATIOoss i 1 TECH. SE RVICE S
*- C. f4 GR AVE S ' g MAISITE NA8sCE ADestN SERVICES P: J W COM A P: C T SM8TH P: A R FRAfeKLpN A: T. E. CR AWF ORO A: W. P. DE AL C. Q. MUSE 4: O R. ROGERS A: T. K. AfeOE ASO8e R. H. CHAREST A 8 WILSON J. H. K NUTI W. R. McC/)LLUM J A. LAfeselesG D. TOWER W W McCOLLOUGH P C tecAseULTY C. L HARTZE LL I .. . . . . .
OPERATiesG EfeGR HE ALTH PHYSICS CHEMISTRY PERFORMANCE - LICENSE & R T. E. CRAWFORO P: W P DE AL P: R H. CHAREST gg
- P: W. R McCOLLUM **
PROJECTS A: C E. ASUSE A: R. L. CL E tatet R 4: L 0 EVANS : C. L HART 2 ELL A: W. F. BE AVE R J. H KNUTI G. T. AeOOE R. L PAINTER R S ASERNATHY
- n. TOWER A: F. N. MACK A OUCKWORTli
+ P. COORDINATOf DATA ANALYSIS H. P. COORDIN ATOR RE ACTOR E NGR. PE RF ORMA8eCE 4&E S&C PLANN680G esECHANICAL COORDINATOR SUPPORT P: D 88 ROSINSON TECH. P: D.R ROGERS P: H.7.AM NVALE P: R. D. KINARD P R S WILSOce P: W. W tec(MR LOUGH P: G. A. VApsOERVELDE A: - . P: J. L. LOWE RY A: J. D. LE E A: D. L. L ANNIDIC A: C.O.STEELE A: L. O. SCHLISE A: G. L COURTNEY A: F. L WILSON 3 E ggLtggy C M SAHesS J. M ST ACKLEY R COM W. L. AseFIN P. N. McNAMAR A O.WELLDAute A: G. FORO J M CAneERON M.HAWES R.ASHLEY R.5LESSafeG T. HUNTER I O. FINLEY ** **
gg D. ALLENDER l l TEST ENGINEE R SECURITY A0044NISTRAffvE TResG. & SAFE TV
**
- P: W. F. SE AVE R P: T K. ANDE R$0N COOROtseATOg P: P. C. ter ANUL T ASST. OPE R. E NGR. F BE LD MONITOR!NG A: A.S SHATNAGAR A: J H. ROACH P: J A LApeselesG A: O.L.WAftn5 P: dl1 N CAST ER R. A. JONES L J. RYLEY N. J GOSSE TT COORDINATOR A: Jt LAY G G OARRET A: G. L MITCHELL P. C V. WRAY G. L ANOREWS D. H Adat t E R A: R. L RIVARD g l J E. THRE ATT P: PRIMARY TSC LOGKE EPE R i l A: ALTERNATE P. O. C. GOOLSeV C I TOR
- P. H JACKSON
- p. J M AYCOCK RADIO OPE RATOR A: W. L KE LLER P O E. SE XTON A: J C. ADAMS A: P. G. LE ROY P. GE RR ALO "C""'"
A: T. W. 01DONOHUE *- Phase I T '"^"^Y OROCE"'"
**- Phase II l
l . l
S.D. 3.8.4 Rav. 6 ONSITE EMERGENCY ORGANIZATION Enclosura 2 TELEPHONE ACTIVATION Pags 1 of 4 All telephone number will be AREA CODE 803 unless otherwise noted. l Emergency Coordinator / Station Manager P: J. W. Hampton 0: 2300 A: C. W. Graves H: 0: M2304 A: J. W. Cox H: 0: m 2303 H: M A: G. T. Swith 0: 2302 H: M A: A. R. Franklin 0: 2305 H: M
' Superintendent of Operations Superintendent of Technical Service P: C. W. Graves 0: 2304 P: J. W. Cox 0: 2393 A: T. E. Crawford 0:
H: 2384 6 A: W. P. Deal H: M ' 0: 2599 H: 6 H: M A: C. E. Muse 0: 2385 A: E. H. Charest 0: 2531 H: 6 H: 6 A: J. H. Knuti 0: 2426 A: W. R. McCollum 0: 2396 H: M H: 6 A: D. Tower 0: 2427 A: C. L. Hartzell 0: 2785 H: M H: M I Superintendent of Adminsitration ,Suoerintendent of Maintenance ' 1 P: A. R. Franklin 0: 2305 P: G. T. Smith 0: 2302 A: H: M H: 6 T. K. Anderson 0: 2326 A: D. R. Rogers 0: 2359 A: J. A. Lanning 0: H: 62310 H: 6 A: R. B. Wilson 0: 2394 H: M H: M A: P. McAnulty 0: 2319 A: W. W. McCollough 0: 2390 H: M H: 6 NOTE P: Primary A: Alternate 0: Office H: Home
S.D. 3.8.4 Rev. 6 ONSITE EMERGENCY ORGANIZATION Enclosura 2 TELEPHONE ACTIVATION Page 2 of 4 All telephone number will be AREA CODE 803 unless otherwise noted. Operating Engineer Asst. Operating Engineer P: T. E. Crawford 0: 2384 P: R. N. Casler 0: 2418 H: M H: 6 A: C. E. Muse 0: 2385 A: G. Mitchell 0: 2290 H: 6 H: M A: J. H. Knuti 0: 2426 A: W. H. Miller 0: 2430 H: 6 H: M A: D. Tower 0: 2427 H: 6 1 Health Physics Field Monitoring Coordinator P- W. P. Deal 0: 2599 P: C. V. Wray 0: 2598 ^t l H: M H: M l A- R. L. Clesuner 0: 2575 A: R. L. Rivard 0: 2561 A: G. T. Mode H: 0: M 2557 A: H: J. E. Threatt 0: W 2588 H: M H: M Data Analysis Coordinator H. P. Suoport Coodinator P: R. D. Kinard 0: 2587 P: G. A. Vandervelde 0: 2597 H: M H: M A: G. L. Courtney 0: 2595 A: F. L. Wilson 0: 2558 A: H: M H: M P. N. McNamare 0: 2586 H: M Licensing & Proiects Engineer A: J. M. Cameron 0: 2851 Chemistry H: M P: C. L. Hartzell 0: 2785 i H: M A: F. N. Mack 0: 2781 i l P: R. H. Charest 0: 2531 H: M H: 6 A: L. D. Evans 0: ' 2533 Performance Technician A: H: M B. Painter 0: 2532 P: M. Sahms 0: 2278 A: H: M H: 6
- A. .kworth 0: 2473 P: J. Lowery 0: 2447 H: M H: N A: G. Ford 0: 2371 Performance Engineer A: R. Ashley H:
0: W 2414 P: .. R. McCollum 0: 2369 H: 6 l l A: W. F. Beaver H: 0: 6A: 2370 T. Hunter 0: 2415 H: 6 H: M A: D. Allender 0: 2371 I A: R. Abernathy 0: 2412 H: M i H: 6 l I l i .. _ _ , , , , , .. --
S.D. 3.8.4 Rsv. 6 ONSITE EMERGENCY ORGANIZATION Enclosure 2 TELEPHONE ACTIVATION Paga 3 of 4 All telephone number will be AREA CODE 803 unless otherwise noted. J Reactor Engineer Radio Operator P: D. M. Robinson 0: 2386 P: D. E. Sexton 0: 2581 H: M A: H: 6 T. W. O'Donohue 0: 2579 A: S. M. Bellamy 0: 2278 H: O H: 6 A: D. We11baum 0: 2396 A: M. Hawes 2413 0: H: 6 A: R. Blessing H: M 0: 2299 H: M
. Planning Engineer I&E Engineer P: R. Wilson 0: 2394 P: D. R. Rogers 0: 2359 H: 6 H:
A: D. Lanning 0: H: 2717 M A: J. Lee 0: @2621 A: R. Cox 2708 H: M 0: A: J. Stackley 0: 2624 ! H: M H: 6 Mechanical Engineer Chief of Security P: W. W. McCollough 0: 2390 P: T. K. Anderson 0: 2326 A: C. D. Steele H: M H: 6 g 0: 2439 A: J. Roach 0: 2452 A: W. L. Anfin H: 6 H: M 0: 2702 A: L. Ryley 0: 2644 H: M H: M Administrative Coordinator Training & Safety P: J. Lanning 0: 2310 P: P. McAnulty 0: 2319 A: J. Lay H: 6 H: 6 0: 2321 A: D. Waters 0: 2740 A: G. Andrews H: 6 H: M 0: 2309 A: J. Gossett 0: 2734 i H: 6 H: M A: ! G. Barrett 0: 2322 i H: M i NOTE P: Primary A: Alternate 0: Office H: Home
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S.D. 3.8.4 Rsv. 6 y ONSITE EMERGENCY ORGANIZATION Enc 1cauro 2 TELEPHONE ACTIVATION Pegs 4 of 4 All telephone numbers will be AREA CODE 803 unless otherwise noted. TSC Leakeeper TSC Clerks P: D. C. Goolsby 0: 2793 P: Y. Jackson 0: 2301 H: M H: 2308M A: J. Adams- 0: 2791 A: W. Keller 0: A: T. Nahay H: M ' H: 6 0: 2790 A: P. Gerrald 0: 2600 H: M H: 6 A: D. Rowell 0: 2306 Offsite Communicator H: @ P: J. H. Aycock 0: 2795 H.P. Coordinator S&C P: P. G. LeRoy H: M 0: 278 P: H. F. McInvale 0: 2584 A: P. W. Germeroth H: 0: M H: 6 2789 A: L. D. Schlise 0: 2573 A: R. Proctor H: 0: W2794 H: M l j H: M Test Engineer ' i P: W. F. Beaver 0: 2370 l W H: i A: A. S. Bhatnagar 0: 2376 ! i At R. A. Jones H: m 0: 2432 H: M i i t I l i i l I si s
Stttion Dircativo 3.6.4 Rev. 4 Enclosure (3) a- o ONSITE EMERGENCY ORGANIZATION OPERATIONS SUPPORT CEhTER r--- .-----_- CONTROL , I ROOM i l 1 i I i I TECHNICAL I SUPPORT I 1 CEN"IR )- i h----------- - + ASST. OPERAT-H . P . *- - - - - - - - - - - ,
, COORD- g ING ENG INATOR g
i i e i OPERATIONS SUPPORT CENTER l
- t. - - - - - - - - *SHITT SUPERVISOR t i
AUXILIARY HEAI.Tri PHYSICS I OPERATORS I On-Shif and On- H . P . Suoe rvis e r + - - - - - - -J Site Operators not Supervisor an: 5 actually assigned te:hn:::ans c be to the Control assigned by S a .cn Room and other Health Physicis: as Operations needed fror. H.P. personnal called- du y list. out as deemed l necessary by the Health Physics Technicians Emergency Coord-inator or Supt.
- of Operations !
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- ROOM .
L T e CATAW8 A NUCLE AR STATION -
+ O OPS.
O TECHNICAL SUFFORT CENTER TECH. p_ p MAINT. o MANAGER m -4
& SUPT.
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---- MOVEABLE PARTITION 3________ gI STATUS BOARD
- OPS. ENGR. PE RF. ENGR. NSSS I & E EpiGR. 5N O ADMIN. S$
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STA.H.P. ANALYSIS SAFETY w I a o oee o o I onts - I NHC Altt A SUPPORT S & C COORD. COORD. PLANNING MECH. E NGR. l 9 (M o o lo lo l l .o F'EL ONT.
'N OFFSsTE COMMUNICATOR
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o e a o A TYPES OF COMMUNICATIONS O - rtAm raiONE 4 111NGDOWN PilONE Q - EMERG. NOTIFICATION SYS. TO NRC O - OPERATIONS INTERCOM O ~ OUTSIDF
~~
lifil 10 RFCOVERY MGR. O IIE ALTit PilYSICS NETWORK _ __ _ __
Stetien Dirsceiva 3.8.4 Rev. (6) ' Enclosure 6 Page 1 of 1 (
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ONSITE EMERGENCY ORGANIZATION EVACUATION COORDINATOR Primary: C.L.Jensen Office: 2436 Beeper: 808 l Home: Alternates: R. M*Elvee Office: 2706 Beeper: Home: m B.J.Moseley Office: 2504 Beeper: 225 Home: p E.L.Feeser Office: 2505 Beeper: 224 Home: 6 i i l i l
4 Catawba Nuclear Station Directive 2.0.1 (TS) Revision No. 1 Da e / 2./-8/ Approval ,-w/ . DUKE POWER COMPANY CATAWBA NUCLEAR STATION
, NEWS RELEASES 1.0 OBJECTIVE To convey to the public accurate and factual information on its operations the Company frequently issues official releases of such information to the news media.
2.0 APPLICABILITY It is the responsibility of the Co.rporate Communications Department to prepare and issue all of the Company's official news' releases after receiving complete and accurate information from the Department (s) involved. The Steam Production Department will provide the necessary information to Corporate Communications for all news release items involving the operations of the Company's present nuclear generating facilities. News releases may involve matters such as equipment or unit outages, serious personnel accidents, damage to equipment during natural (or other) disasters, etc. 3.0 PROCEDURE 3.1 The Operations Support Section Duty Engineer in the General Office should be notified by the Station Manager or the Licensing Engineer so that issuance of a news release may be considered when any of the following conditions exist: A. A shutdown, scheduled or unscheduled, of a unit. B. Any shutdown of a day or more of a nuclear unit resulting from failure of or damage to safety related equipment. C. Any damage to any safety related equipment, if the time to repair the equipment is likely to exceed Technical Specifications for time allowed for maintenance. D. Any inadvertent release of radioactive material and all releases of radioactive material in excess of allowable Technical Specifications. 4 m I
CNS Dirsctiva 2.0.1 Paga 2 of 2 c E. Any significant radiological event offsite occurring during fuel or waste transport or other nuclear related activities. N
. F. Violations of EPA or state water and air permits with significant effect on public health or that might result in enforcement action against the company.
G. Any injury requiring the use of emergency vehicles, involving radiation exposure above allowable limits or requiring hospitalization. H. 5 Any " unusual event" that requires notification of state and/or county emergency centers. I I. Any other incident considered to be of general public interest. j 3.2 The Operations Support Section Duty Engineer in the General Office can be reached at phone number 5504 or the General Office exchange. At night and on weekends, a recording will tell you how to reach the Duty Engineer. 3.3 It will be the responsibility of the Operations Support Section Duty Engineer to notify Corporate Communications so that a decision on a news release may be made. 3.4 i Corporate Communications shall be responsible for distributing the news release to the appropriate agencies and telecopying a copy to l the Station Manager.
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3.5 Station personnel should refer all inquiries from the news media to personnel in Corporate Communications, unless specifically authorized to release information. If an inquiry is made, the Station Manager , or the Licensing Engineer should notify the Operations Support Section Duty Engineer so that he can inform Corporate Communications that an inquiry has been referred to them. 3.6 All news reporters should be handled in a friendly and courteous manner. l 3.7 Corporate Communications has a 24-hour, 7-day phone line (704-527-5970). Normally, the Operations Support S'ection Duty Engineer will be contacting Corporate Communications concerning news releases. However, if for some reason the Operations Support Section Duty Engineer cannot be reached, the Station Manager or the Licensing 2ngineer should contact Corporate Communications on that number. Duke use only. Do not refer news media to that number since it is for I [ 3.8 If for some reason Corporate Communications cannot be contacted, the Station Manager or the the Licensing Engineer may authorize a news f release using the News Relase Form (Attachment 1). { ! i l I.
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NEWS RELEASE FORM N., ATTACEMENT 1
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At on a (Time) (Fire, Radiation, Contamination, Nuclear Accident, act.) occured at the Catawba Nuclear Station near Clover, South Carolina, i The - accident was: * (Fire, Radiation, Contamination, Nuclear, etc.) (Pick One) , (1) confined solely to the plant site and did not involve the nuclear reactor; (2) confined solely to the plant site and did involve the nuclear reactor; (3) confined solely to the plant site and exclusion area and does not of for any radiation problem to local area residents; (4) not only involved the plant site and exclusion area but has spread some contamination into the local area at . t (Exact Location)
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1 In this case, County, State and Federal Authorities have been notified by Duke Fover Company and proper measures are being carried out to insure the health and safety of all, persons involved. There is no danger beyond the areas noted above. (Extent of Injuries) i- As a result of this accident, persons who work at Catawba (number) l Station have been . They are presently being treated j (inj ur ed , e tc. ) l st . (Hospital / Clinic) Addition information will be released as soon as it is available. 1 Signature Title 9 4 - ,v ,- - - , , , . - - - .--s ,- ,- - - e, - ,,
CATAWBA NUCLEAR STATION DIRECTIVE 3.0.7 (TS) REVISION NO. 2 DATE 2-7 b APPROVAL L DUKE POWER COMPANY CATAWBA NUCLEAR ST ION i SITE ASSEMBLY / EVACUATION 1.0 PURPOSE . 1.1 To account for station personnel, contractor personnel, other Duke Power Company employees and visitors onsite in an emergency situation. 1.2 To ensure personnel safety by evacuation to a predesignated location offsite when the situation warrants. . 1.3 To provide for the control of evacuated employees until the emergency situation is returned to normal or until other disposition
'is made.
- 1.4 To provide training and drills on assembly and evacuation to plant .
, personnel and others with unescorted access to station. 2.0 SPECIFIC RESPONSIBILITIES 2.1 All station employees, contractor personnel, visitor and other Duke-i Power Company employees onsite are required to comply with the , actuation of a Site Assembly or Evacuation and are responsible for 3 knowing the location of their' assembly point (indicated on back of their security badge), who they are to contact upon assembly and to
- where they are to evacuate.
j 2.2 The Shift Supervisor / Emergency Coordinator is responsible for imp 1'eaenting the Site Assembly or Evacuation depending upon the situation. 2.3 Station sections are responsible for accounting for their onsite personnel to the Security Shift Clerk or Sergeant at extension 2393. See section 4.1.2.2 A through N. Personnel shall notify their Supervisor, who in turn report to Coordinator and higher levels as applicable. 2.4 During evening and night shift er on weekends or holidays, personnel without -their supervisor onsite will report to the Security Shift Clerk or Sergeant at extension 2393. 2.5 Construction personnel are responsible for reporting to their supervisor, who will report on to the Construction Project Manager. I 2.6 QA personnel are responsible for reporting to the Senior QA Engineer. i l i
. _ n.~ _.n r . ..o. - o .... c;mp g . . . , 6 .+. e 9 - , . .- - --- - ~ - - - ~ ~ ~ " - ' ~ ~ - ' '
1 Catawba Nuc1ccr Statica Directive 3.0.7 Pass 2 cf 9 f i 2.7 Vendor and contractor personnel are responsible for reporting to ; their supervisor. ' 2.8 Station Sections, and other organizations as listed in 4.1.2.2 A through N, after assembling shall report to the Security Shift Clerk or Sergeant at extension 2393. All personnel shall be accounted for within 30 minutes of the announcement. 2.9 If personnel are directed to proceed to either or both-of the i Evacuation Relocation Sites, the Evacuation Coordinator at that site will be responsible for: 2.9.1 Obtaining .the keys to Site Alpha from Security, if necessary. 2.9.2 Maintaining communication with the Shift ' Supervisor / Emergency Coordinator. 2.9.3 Accounting for station personnel and others as they arrive
, at the site and reporting to Shift Supervisor / Emergency Coordinator the status of the evacuated employees.
2.9.4 Disseminating status reports to evacuated personnel. 1 l 2.9.5 Interfacing with the management of the relocation site. 2.10 The Security Shift Lt., Clerk or Sergeant shall receive the reports of personnel accountability, noting all personnel who are unaccounted for on Enclosure 1 and report to the Chief of Security or to the Emergency Coordinator in the Control Room or the TSC. 2.11 The Shift Supervisor / Emergency Coordinator is responsible for securing from the Site Assembly or Evacuation when the situation has returned to a normal status. 2.12 Health Physics will monitor personne1' exiting from PAP and Construction Exits, during a Site Evacuation, and will have , personnel available at the Evacuation Relocation Site per Reference l 3.5. 2.13 Health Physics will monitor assembly locations and exit points to assure radiation protection of these personnel assembled. 1
3.0 REFERENCES
3.1 Catawba Nuclear Station Emergency Plan 3.2
~
Catawba Nuclear Station Directive 3.8.4 ,1 3.3 System Health Physics Manual
.3.4 RP/0/A/5000/10, Conducting a Site Assembly / Evacuation
, 3.5 HP/0/B/1009/05, Personnel Monitoring for Emergency Conditions
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l' t t ++...~.----mw. _ - - < . ._
C;tawb3 Nuclocr Statica Pirectiva 3.0.7 Pcgo 4 of 9 Group Primary Assembly Point Secondary Assembly Point A. Operations
- 1) Staff & other Operations Office Area Conf. Rm. #3 personnel not SB 594* Admin. Bldg.
on shift
- 2) On shift Control Room or N/A personnel OSC
- 3) Training Classroom in Classroom groups High Rise ** Admin. Bldg.**
B. Administrative Service
- 1) Administrative Document Control Training Service Personnel, or DDP Room Office Admin. Bldg.*
Clerical, DDP and Tra.ning Service
- 2) Safety /ledical Safety Office
- Training Service Office Admin. Bldg.
- 3) Security Security Assembly Rm.* Conf. Rm. #4 Admin. Bldg.
. NOTE: Securit. , rsonnel on assignment remain "0N POST".
- 4) K-MAC & Ve.ndor K-MAC Office Conf. Rm. #4 High Rise
- Admin. Bldg.
- 5) Personnel in Classroom ** Classroom **
training C. Technical Services
- 1) Licensing & L&P Office
- Body Burden Room Projects
- 2) Performance Performance Office
- Body Burden Room
- 3) Power Chemistry CT Lab Body Burden Room Environmental Chemistry Water Treatment Bldg. Body Burden Room Staff & Radwaste Chemistry Office
- Body Burden Room
- 4) Health Physics HP Office 608 El.* 3ody Burden Room !
D. Maintenance 4
- 1) Mechanical Mechanical Shop Area
- Interface Room Admin. Bldg.
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)
l C:ttwbs Nuc1 car Statitn Directivo 3.0.7 Peg 2 6 of 9 ) l l I 4.1.2.3 Upon initiation of a Site Assembly, Security shall prevent entry into or exit from the Protected Area through the PAP except for the following essential personnel: A. Emergency Organization personnel specified in Catawba Nuclear Station Directive 3.8.4 ; B. Operation shift Personnel i C. Catawba Nuclear Station Fire Brigade personnel
.. D. Catawba Nuclear Station Field Monitoring team ,
personnel . E. Crisis Management Team personnel with proper I identification F. NRC personnel G. Security personnel H. Others as directed by the Emergency : Coordinator. 4.1.3 Acccanting for Personnel 4.1.3.1 Unaccounted for personnel will be reported to the Shift Supervisor / Emergency Coordinator, by Security after the first 30 minute accounting period. Efforts to locate the missing person (s); i will begin approximately 45 minutes after thw l assembly is initiated. 4.1.3.2 If necessary, the Security Fire Brigade members will institute Search and Rescue operations to locate and retrieve unaccounted for personnel. : Other station groups will be called upon to assist, as necessary, the station Safety group , shall coordinate the search. . 4.1.3.3 The status of unaccounted for personnel will be ! maintained in the Central Alarm Station. (See Enclosure 1) i 4.1.4 Maintenance of Accountability ? 4.1.4.1 If the requirement for an assembly no-longer , exists, permission to retura to normal duties , will be given by the Emergency Coordicator. . I 4.1.4.2 Plant conditions may require evacuation of the ! station. Instructions will be given by the Emergency Coordinator.
,__ ~ ~* '
Catsuba Nucloer Station Directive 3.0.7 Pego 8 of 9 4.2.2.1.1 The Shift Supervisor / Emergency l I ' ' Coordinator or delegate shall call the listed phone number or radio to
, inform them of the planned evacuation. If there is no response ;
to the call, the keys to the i varehouse are kept by Catawba Nuclear Station Security and can be obtained to open the warehouse by Catawba Nuclear Station personnel. 4.2.2.1.2 Phone Numbers: 373-7309 (803) 366-4777 4.2.2.1.3 Radio via Dispatcher's frequency. 4.2.2.2 Site " Bravo" - Duke Power Company Allen, Steam Station on Southpoint Road (Knclosure 3) 4.2.2.2.1 The Shift Superv;;or/ Emergency Coordinator or dalegate shall call the listed phone number or radio to ' inform them of the planned evacuation. Since Allen Steam Station is operabic e- all times, no i backup access is re ed. 4.2.2.2.2 Phone Numbers: 373-4646 (704)d25-2022 4.2.2.2.3 Radio via' Dispatcher's Frequency 4.2.3 Implementation 4.2.3.1 Site Evacuations are activated only after l l station personnel have been accounted for j through a Site Assembly. 1 4.2.3.2 The Shift Supervisor / Emergency Coordinator shall determine which Evacuation-Relocation Site to evacuate to based on current meteorological conditions and the nature of the emergency. 4.2.3.3 Tite snift Supervisor / Emergency Coordinator or delegate shall sound the Site Evacuation alarm followed by an announcement on the plant page system per RP/0/A/5000/10, Conducting A Site Assembly / Evacuation. l
STATION DIECTIST 3.0.7 (75) l ENCLD5tX 1 l l l UNACCDLH"ID TOK PERSO.%IL i NAE GROUP SUPERV]SOK IAST KN0kT LOCATION STATUS I e 9 9 N s 1 1 l l
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! ~ 1 l
l l i ~ l I CATAWBA NUCLEAR STATION ' STATION DIRECTIVE 3 0.7 (TS) ENCLOSURE 3 EVACUATION / RELOCATION SITE "BRAV0" DUKE POWER CO. ALLEN STEAM STATION SOUIEPOINT ROAD (SR2524) CASTON COUNTY Ewy. 273 TO BEDf0NT d
; ALLEN STEAM
'O CASTONIA 8 STATION Jl SR 2524 SOUTHPOINT RD.
HWY 274 Pole Branch Rd. [
# TO CHARLOTTE l
5'WY 4 CATAWBA NUO. EAR STATION
- BRIDGE v .
HWY 274 ^ STMBOL
- I
s' l Form 34731 (10 81) I (Formerly SPD 10021)- ' DUKE POWER COMPANY (1) ID No: PT/0/B/4600/06 PROCEDURE PREPARATION Change (s) to PROCESS RECORD Incorporated (2) STATION: CATAWBA (3) PROCEDURE TITLE: Emerg'ency Exercises and Drills (4) PREPARED BY: Mike Bolch DATE:_ 3-23-83
// ~ - ..
(5) REVIEWED BY: . / U/ DATE: Cross-DiscipJinary Re 'i w By: . N/R: S-\6 -63 (6) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: By: Date: (7) APPROVED BY: . b. ur M Date: i l1Sl 83 (8) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: l l
PT/0/B/4600/06 DUKE POWER COMPANY CATAWBA NUCLEAR STATION EMERGENCY EXERCISES AND DRILLS i 1.0 PURPOSE This procedure provides for periodic exercises / drills to be conducted to evaluate major portions of the emergency response capability, and to develop and maintain key _ skills. Corrective actions and recommendations identified as a result of an exercise or drill will be corrected, and records maintained in accordance with this procedure.
2.0 REFERENCES
2.1 Catawba Nuclear Station Emergency Plan 2.2 Crisis Management Plan 3.0 TIME REQUIRED Varied 4.0 PREREQUISITE TESTS N/A 5.0 TEST EQUIPMENT N/A 6.0 LIMITS AND PRECAtTTIONS 6.1 Exercise scenario's should be varied from year to year to test emergency team response to many of the initiating conditions listed in procedure RP/0/A/5000/01, Classification of Emergency. 6.2 Exercises should be scheduled to start between 6:00 PM and midnight and another between midnight and 6:00 AM once every six years. 6.3 Drills should be conducted more frequently than exercises and shall be supervised and evaluated by a drill instructor. 7.0 REQUIRED STATION STATUS N/A 8.0 PREREQUISITE SYSTEM CONDITIONS N/A 9.0 TEST METHOD N/A
PT/0/B/4600/06 Paga 2 of 4 10.0 DATA REQUIRED l Enclosure 13.1 Exercise / Drill Format and Critique Findings Enclosure 13.2 Exercise / Drill, Controller / Evaluator Report 11.0 ACCEPTANCE CRITERIA ! 11.1 Completion of required exercise or drill and the subsequent critique. 12.0 PROCEDURE 12.1 Exercises i 12.1.1 A full-scale exercise is an event that tests the integrated capability and a major portion of the basic elements existing within emergency preparedness plans and t organizations. A full-scale exercise shall include mobilization of state and local personnel and resources j adequate to verify the capability to respond to an ! accident scenario requiring response. A full-scale .i excrcise will be supervised and evaluated by a qualified ; exercise director. A full-scale exercise will be held no ' less than once every 5 years. ! 12.1.2 A small-scale exercise is an event which tests the adequacy of communication links, establishes that response agencies at the utility and local level understand the emergency action levels, and tests at-least one other component (e.g. medical or offsite monitoring) of the { emergency plan. A small-scale exercise will be conducted j each year that a full-scale exercise is not held at the i station. A small-scale exercise will be supervised and evaluated by a qualified exercise director. l 12.1.3 An exercise will simulate an emergency that results in i j offsite protective actions and requires response by j offsite agencies. , 12.1.4 An exercise scenario shall provide.for a critique of the exercise by all concerned personnel and organizations. 12.2 Drills 12.2.1 A drill is a supervised instruction period aimed at f testing, developing and maintaining skills in a particular l , operation. A drill is often a component of an exercise. I A drill will be supervised and evaluated by~a qualified l drill instructor. 12.2.2 Drills will be conducted at the frequencies indicated
- below
h (a) Communication drills with state and local government ? located within the 10 mile Emergency Planning Zone shall be conducted monthly.
- 6
_ _ . -_ f
PT/0/B/4600/06 7 Pegs 3 of 4 4 . (b) Communication drills with Federal Emergency Response Organizations and states within the 50 mile Ingestion
. Pathway shall be conducted quarterly.
(c) Communication drills with state and local emergency operations centers and field assessment teams shall be
- conducted annually, i
NOTE: Sample message information for the above communication drills shall test the ability to 4 understand the content of messages. l (d) Fire drill shall be conducted in accordance with Station Directive 2.12.2 and documented by the Safety Department. 4 (e) Medical emergency drills involving a simulated contaminated individual shall be conducted annually. This drill will involve participation by the Piedmont Medical Center and Ambulance Service and Charlotte Memorial Hospital. A communication check to REAC/TS in Oakridge, Tennessee as the provider of backup medical support shall be conducted during this drill. ] (f) A radiological monitoring drill involving onsite and offsite radiological monitoring teams will be conducted annually. The monitoring teams will actually collect and analyze air samples, as appropriate. Soil and water samples will not be taken as this is done on a weekly basis at the station. The exercise controllers will provide them simulated analysis results indicative of contamination or plume location. I (g) Health Physics' drills shall be conducted semi-annually , which involve response to, and analysis of, simulated 1 l elevated airborne and liquid samples and direct radiation j measurements in the environment. 1 (h) Health Physics drills shall be conducted annually which i involve analysis of inplant liquid samples with actual radiation levels, including use of the post-accident sampling system. (i) Site assembly drills shall be conducted semi-annually. These drills shall provide for the capability to account for all individuals onsite at the' time'of the emergency i and to ascertain the names of missing individuals within 30 minutes of the announcement of the emergency
-condition. The capability to account for onsite individuals continuously after the initial accountability shall be included.
i 5
PT/0/B/4600/06 Page 4 of 4 (j) Site evacuatinn drills shall be conducted annually. These drills will demonstrate the ability of the station
, personnel to leave the station and arrive at the Evacuation-Relocation Site, to account for evacuated i personnel, to use supplies kept at the site and to control the disposition of personnel until the emergency situation is returned to normal. The evacuation will be simulated except for a small group of non-essential employees who will actually proceed to the Evacuation Relocation Site.
12.3 Scheduling / Documentation l 12.3.1 Exercises shall be scheduled by the Nuclear Production Emergency Response Coordinator 12.3.2 All documentation of emergency exercises shall be maintained by the Emergency Response Coordinator. Corrective actions and recommendations will be compiled from the " Critique Action Item List" by the Emergency Response Coordinator. 12.3.3 Drills shall be scheduled by the station Emergency Preparedness Coordinator and included in the Emergency Plan Bi-Monthly Activity Schedule. l 12.3.4 Documentation of tirills shall be maintained by the ! Emergency Preparedness Coordinator. Corrective actions I and recommendations will be compiled on Exercise / Drill l Format and Critique Findings, Enclosure 13.1, by the Emergency Preparedness Coordinator. 13.0 ENCLOSURES 13.1 Exercise / Drill Format and Critique Findings 13.2 Exercise / Drill, Controller / Evaluator Report l l L l I l I
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Pags 1 of 3 CATAWBA NUCLEAR STATION EXERCISE / DRILL FORMAT AND CRITIQUE FINDINGS PT/0/B/4600/06 ENCLOSURE 13.1 1.0 Classification of Exercise / Drill. (Check appropriate box) / [] - Emergency Exercise, 12.1 [] - Communication Drill (state and local government within 10 mile EPZ), 12.2.2, a. (monthly) [] - Communication Drill (Emergency response organizations and state within 50 mile I.P.Z.), 12.2.2, b. (quarterly) [] - Communication Drill (State and local Emergency Operations Centers and Field Assessment Teams), 12.2.2, c. (annually) [] - Medical Emergency Drill, 12.2.2, e. (annually) [] - Radiological Monitoring Drill, 12.2.2, f. (annually) [] - Health Phygics Drill, 12.2.2, g. (semi-annually) []- Health Physics Drill, 12.2.2, h. (annually) [] - Site Assembly Drill, 12.2.2, 1. (semi-annually) [] - Site Evacuation Dril, 12.2.2, J. (annually) 2.0 Drill Instructor / Exercise Director: (Name) Critique Director: (Name) 3.0 Date/ Time Exercise / Drill to be conducted: / (Date) (Time) 4.0 Exercise / Drill Objectives: a
PT/0/B/4600/06 ENCLOSURE 13.1 PAGE 2 OF 3 5.0 Plant system / ares (s).affected: 6.0 Work groups to be involved: 7.0 Time sequence of postulated events: 8.0 Assigned Observers (Controllers / Evaluators) and their stations: 9.0 Critique to be conducted at / (Date) (Time) (Location) 10.0 Personnel to attend critique: L' .
PT/0/B/4600/06 ENCLOSURE 13.1 PAGE 3 0F 3 l 11.0 Critique Findings, Recommendations, Required Action (s), Etc.: l i 12.0 Corrective Actions taken: (List actions taken to ensure all findings in 11.0 are identified and corrected: i NOTE: Include all Exercise / Drill or other information provided as an , attachment. ' i (Drill Instructor / Exercise Director) (Signature) (Critique Director) ' (Signature) i cc: File No. I Station Manager Group Superintendents ' i
CATAWBA NUCLEAR STATION EXERCISE / DRILL CONTROLLER / EVALUATOR REPORT PT/0/B/4600/06 ENCLOSURE 13.2 1.U Drill Classification: 2.0 Summary of Exercise / Drill:
]
3.0 Exercise / Drill initiated: / I (Date) (Time) ; i 4.0 Observation / Comments / Recommendations: 5.0 Exercise / Drill completed at: / 1 (Data) (Time) Controller / Evaluator (Signature) cc: File No. Assigned Controller / Evaluator (s)
'6 DuzzP :: ,
P. u qpgl A W .seses f))l mALB.TUCERR nammons
== - ga ([(704) evi>eso
, 3" 53 tcWD A 9 : 3 8 Mr. L'srold R. Denton, Director Office of Nuclear Reactor Regulation
- U. S. Nucicar Regulatory Commission i Wachington. D. C. 20555 '
Attention: Ms. E. G. Adensam. Chief Licensing Branch No. 4 Re: Catawba Nr.cles tion Docket Nos. -413 nd 50-414 k Dese Mr. Denton: Duke Power Company is submitting herewith Revisior 3 to the Emergency Plan for the Catawba Nuclear Station. In accordance with 10 CFR 50.54(q). three . copies (one copy to the Regional Admin 1strator) are being submitted. , it is requested that privacy information cuch as home telephone numbers and home addresses be deleted from the Emergency Plan prior to its being placed . ~ in the Public Document Rooms. This request is being made pursuant to Darrell G. Eisenhut's letter of July 9, 1981 (Generic Letter 81-27). Very truly yours,
- 28. rd m Hal B. Tucker ROS/php Attachment ces (w/ attachment) e Mr. James P. O'Reilly. Regional Administsator U. S. Nuclear Regulatory Commission Region 11 101 Marietta Street. NW. Suite 2900 8 Atlanta Georgia 30303 (w/o attachment) .,
NRC P.csident Inspaccor # Catavia Nuclear Station [ 9'I [ N h //* f Y oW4a en 3d yf poh _
Mr. Barold 1. Denton, Director July 6, 1983 ! Page 2 . cc: (w/o attachment) Mr. Robert Guild, Esq. . Attorney-st-Law P. O. Box 12097 Charleston, South Carolina 29412 Palmetto Alliance 21351s Devine Street Columbia, South Carolina 29205 Mr. Jesse L. Riley Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207 1 Kr. Henry A. Presler, Chairman Charlotte-Mecklenburg Environmental Coalition
- 943 Henley Place Charlotte, North Carolina 28207 i
l i l l 2 1
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c4-i DUKE POWER COMPANY CATAWBA NUCLEAR STATION
~
EMERGENCY PLAN 1 i APPROVED:
?
L Jh. . A ' W.Himptufi,Mafager .
/ atawba Nuclear Station l
i t
- J 1
Dated - August 1980' . Revision 3 - June 1983 4-
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, DUKE POWER COMPANY I CATAWBA NUCLEAR STATION
, EMERGENCY PLAN Table of Contents Page #
- i. -Introduction A. Purpose 1-1 B. Scope .
1-1 C. Planning Basis 1-3 3 A. Assignment of Responsibility A.I.a Oraanization A-1 A.I.b Concept of Operations A-3 A.I.c Block Diagram Interrelationships A-3 A.I.d Key Decisionmaking A-3 A.I.e 24 Hour Emergency Response A-4 A.2.a Responsibility for and Functions of Emergency A-4 Response Organization i A.2.b Legal Basis for Authority A-4 A.3 Agreement Letters for Emergency Response Support A-4 A.4 Individuals Responsible for Continuity of Resources A-4 B. Onsite Emergency Organization ; B.1 Plant Staff Under Emergency Conditions B-1 > B.2 Station Emergency Coordinator B-1 B.3 Station Emergency Coordinator (line of succession) B-1 B.4 i Protective Action Recommendations B-2 i B.5 Minimum Staffing Requirements B-2 B.6 Onsite Functional Area Interfaces B-6 , B.7 Corporate Support of Onsite Emergency Organization B-6 * , B.8 Contractor and Private Organizations B-6 B.9 Local Agency Support Services B-7 B.9.a Law Enforcement, Emergency Traffic Control, Related B-7 Police Matters B.9.b Early Warning or Evacuation of the Populace B-7 B.9.c Radiological Emergency Monitoring Assistance B-7
- B.9.d Hospitals, Medical Support B-8 B.9.e Ambulance Service B-8 B.9.f Fire-fighting B-8 B.9.g Public Health and Safety, Evaluation of.the B-8 Radiological Situation '
B.9.h Local, State and Federal Support Responsibilities B-8 ; C. Emergency Response Support and Resources ! C.I.a Individuals Authorized to Request Federal Assistance C-1 { C.I.b Federal Resources Arrival Time C-1 ! C.1.c Crisis Management Resources Available to Federal Response C-1 Organizations { C.2.a State and County Representation at the Crisis Management C-1 l Center (CMC) t C.2.b Local Agency Liason C-1 C.3 Radiological Laboratories-Availability and Capability C-1 C.4 Emergency Support From Other Organizations C-1 Rev. 3 June 1983 ;
Table of Contents Page # l l Emergency Classification System D. D.1/D.2 Emergency Classification-Initiating Conditions, D-1 Emergency Action Levels D.3 State and ~ Local Organization-Emergency Classification D-2 System D.4 State and Local Organization-Procedures for Taking D-2
. Emergency Actions E. Notification Methods and Procedures -
E.1 Notification of Response Organization E-1 l E.2 Activation of Emergency Organizations E-1 i E.2.a Notification of Unusual Events E-1 E.2.b Alert E-2 i E.2.c Site Area Emergency- E-4 E.2.d General Emergency E-6 : E.3 Emergency Message Format (Initial) E-9 E.4 Emergency Message Format (Follow-up) E-9 ? E.5 State and Local Organizations-Disseminating Public E-9 Information E.6 Alert and Notification System E-9 E.7 Supporting Information for Public Information Messages E-10 F. Emergency Communications F.1.a 24 Hours Notification Capability F-1 F.1.b Communications With State / Local Government F-1 F.1.c Communications With Federal Organizations F-1 F.1.d Communications Between Station, CMC, EOC's and F-1 Monitoring Teams F.1.e Activation of Emergency Personnel F-2 , F.1.f Communications Between NRC, CMC and Monitoring Teams F-2 i F.2 Medical Support Communications F-2 F.3 Communications System Testing F-2 G. Public Education and Information G.1/G.2 Public Education and Information Program G-1 G3 Crisis News G-1 G.3.a Contact G-1 G.3.b Space G-1 G.4 Spokesperson - News Release G-1 G.4.a Spokesperson G-1 G.4.b Information Exchange G-1 G.4.c Rumor Control G-1 G.5 News Media Training G-1 H. Emergency Facilities and Equipment i H.1 Technical Support Center / Operations Support Center H-1 4 - H.I.a Control Room H-1 g I H.1.b Technical Support Center (TSC) H-1 j i H.I.c Operations Support Center (OSC) H-2 . H.2 Crisis Management Center (CMC) H-2 i H.3 Direction and Control H-2 , H.4 Activation and Staffing H-2 i H.5 Assessment Actions H-2 l Rev. 3 June 1983
Table of Contents Page 0 H.S.a Meterological, Hydrologic and Seismic H-2 H.5.b Radiological Mo.:itor H-4 H.5.c Plant Parameter H-4 H.S.d Fire Detection H-4
.H.6 Data, Monitoring Equipment and Analysis Facilities H-5 H.7 Offsite Radiological Monitoring H-5 H.8 Meteorology Instrumentation and Procedures H-5 i H.9 Operations Support Center H-5 H.10 Emergency Equipment / Instrumentation Inspection, h-5 Inventory, Operational Check, Calibration H.11 Emergency Kits H-5 H.12 Receipt and Analysis of Field Monitoring Data H-6 I. Accident Assessment -
I.1 Emergency Action Level Procedures I-1 1.2 Onsite Capability and Resources to Provide Initial Values I-i l and Continuing Assessment i I.2.a Post Accident Sampling I-1
- ' I.2.b Radiation and Effluent Monitors I-1 I.2.c In plant Iodine Instrumentation .
I-1
- I.3.a/ Method for Determining Release Source Term I-2
. I.3.b I.4 Effluent Monitor Readings Vs Onsite/Offsite Exposure I-2 I.5 Meteorological Information Availability I-2
! I.6 Release Rates / Projected Doses for Offscale I-2 i I.7/ Field Monitoring Within the EPZ I-2 i I.8
! I.9 Detect and Measure hdioidine Concentration in the EPZ I-3 l I.10 Relationship Between Contamination Levels and Integrated I-3
- Dose / Dose Rates l 1.11 Plume Tracking I-3
, J. Protective Response J.1.a Onsite Alerting and Notification J-1 thru l J.1.d i l J.2 Evacuation Routes and Transportation J-1 ; i J.3 Personnel Monitoring J-2 ! J.4 Site Evacuation Procedures - Decontamination J-2 ! J.5 Site Evacuation Procedures - Personnel Accountability J-2 !- J.6 Protective Equipment Breathing Apparatus, Protective J-2 ! Clothing, Potassium Iodine ! J.7 Protective Action Recommendations J-3 i J.8 Evacuation Time Estimates J-3 ! J.9 Implementing Protective Measures J-3 L J.10 Implementation of Protective Measures for Plume J-3 . Exposure Pathway J.10.a EPZ Maps J-3 J.10.b EPZ Population Distribution Map J-3 J.10.c EPZ Population Alerting and Notification J-4 i J.10.d EPZ Protecting Immobile Persons J-4 J.10.e Use of Radio protective Drugs for Persons in EPZ J-4 ! J.10.f Conditions for Use of Radio protective Drugs J-4 ! J.10.g State and County Relocation Plans J-4 1 Rev. 2 g Jan. 1983
Table of Contents Page # J.10.h Relocation Center Locations J-4 J.10.1 Evacuation Route - Traffic Capacities J-4 J.10.j Evacuated Area Access Control J-4 J.10.k Planning for Contingencies in Evacuation J-4
. J.10.1 State and County Evacuation Time Estimates J-4 J.10.m Beses for Protective Action Recommendations J-5 J.11 Ingestion Pathwsy Planning J-5 J.12 Relocation Center - Registering and Monitoring J-5 K. Radiological Exposure Control l K.1 Onsite Exposure Guidelines K-1 K.2 Doses in Excess of 10CFR Part 20 K-2 K.3 Emergency Personne'l Exposure and Records K-2
*4.3.a Distribution of D'osimetry K-2 K.3.b Dose Records K-2 K.4 County and State FNF Plans K-2 K.5 Decontamination K-2 K.5.a Action Levels for Determining the Need for Decontamination K-2 K.5.b Radiological Decontamination K-2 K.6 Contamination Control Measures K-3 K.6.a Area Access Control K-3 l K.6.b Drinking Water and Food Supplies K-3 ;
K.6.c Recovery Efforts K-3 ' K.7 Decontamination of Personnel at Relocation Assembly Area K-3 L. Medical and Public Health Support t L.1 Local and Back-up Hospital and Medical Services L-1 L.2 Onsite First Aid Capability L-1 L.3 Public, Private, Military Hospitals, Emergency Medical L-1 1' Facilities L.4 Transportation of Accident Victims L-1 M. Recovery and Re-entry Planning and Post-Accident Operations M.1 Re-entry / Recovery Plans and Procedures ! M-1 l M.I.a Outline of Station Recovery Plans M-1 M.2 Recovery Organization M-2 M.3 Information to Members of Recovery Organization M-2 M.4 Total Population Exposure Estimates M-3 l N. Exercises and Drills i N.I.a Exercises N-1 ; N.I.b Exercise Scena:to/ Response N-1 ! N.2 Drills N-1 N.2.a Communication Drills N-1 l N.2.b Fire Drills N-1 4 N.2.c Medical Emergency Drills N-1 N.2.d Radiological Monitoring Drills N-1 J N.2.e Health Physics Drills N-2 N.3 Exercises and Drills: Execution N-2 N.4 Exercise Critique N-2 N.5 Critique Action Items q N-2 l
- 0. Radiological Emergency Response Training
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0.1 Offsite Agency Training 0-1 0.1.a Site Specific Training 0-1 Rev. 2 Jan. 1983
Table of Contents Page # 0.1.b Offsite Support Agency - Participation in Training 0-1 0.2 Onsite Organization Training 0-1 0.3 First Aid Training 0-1 0.4 Training Radiological Emergency Response Personnel 0-1 0.5 Retraining of Emergency Response Personnel 0-2 P. Responsibility for the Planning Effort P.1 Emergency Planner Training P-1 P.2 Corporate Emergency Response Training P-1 4 P.3 Station Emergency Preparedness Coordinator P-1 P.4 Review of Emergency Plan P-1 P.5 Distribution of Revised Plans P-1 P.6 Supporting Plans P-1 P.7 Implementing Procedures P-1 P.8 Table of Contents P-2 P.9 Audit of Emergency Plan P-2 P.10 Telephone Number Updates P-2 Q. Appendices Index Q.1 Appendix 1 Definitions Q-1.1 Appendix 2 Meteorology System Description Q-2.1 Appendix 3 Alert and Notification System Description Q-3.1 Appendix 4 Summary of Evacuation Time Estimates Q-4.1 Appendix 5 Agreement Letters Q-5.1 Appendix 6 Catawba Nuclear Station Emergency Plan Distribution Q-6.1 l l l i l i Rev. 3 1 June 1983 i l
LIST OF FIGURES' FIGURE . NO. , TITLE PAGE # i-1 10 Mile EPZ 1-6 1-2 50 Mile EPZ 1-7 B-1 Minimum Staffing Requirements B-10 B-2 Catawba Technical Support Center Interfaces B-13 D-1 Notification of Unusual Event - EAL's and Initiating Conditions D-3 D-2 Alert - EAL's and Initiating Conditions D-4 D-3 Site Area Emergency - EAL's and Initiating Conditions D-6 D-4 General Emergency - EAL's and Initiating Conditions D-7 E-1 Warning Message: Nuclear Facility to State / Local Government E-11 E-2 Emergency Message Format E-15 E-3 Technical Support Center Activation Checklist E-16 E-4 Emergency Response Organization - Emergency Activation Message E-17 F-1 Emergency Communication Layout Prior to TSC Activation F-3 F-2 Emergency Communication Layout After TSC Activation F-4 G-1 Catawba Nuclear Station Brochure G-2 , G-2 Brochure Distribution List (later) G-3 , I H-1 Catawba Nuclear Station Technical Suppet Center H-7 H-2 Catawba Nuclear Station Operations Support Center H-8 H-3 Protective Equipment and Supplies Locations H-9 H-4 Recovery Kit Checklist H-10 H-5 Environmental Survey Kit Checklist H-11 - H-6 Technical Support Center Kit Checklist H-13 H-7 Operatt.ns Support Center Kit Checklist H-15 , H-8 Personnel Survey Kit Checklist H-16 ' Rev. 3
., June 1983
1 l H-9 Medical Decontamination Kit Checklist (Station) H-17 H-1Q Medical Decontamination Kit Checklist (Hospital) H-18 H-11 Verification of Emergency Communications H-19 H-12 Environmental Survey Kit Checklist (Helicopter) H-20 H-13 Fuel Transfer Kit Checklist H-21 H-14 Personnel Survey Kit Checklist (Evacuation Facility) H-23 H-15 TLD Locations H-24 H-16 Air dampling Locations H-26 I-1 Plant Data and Status Sheet I-4 J-1 . Population Distribution of the Catawba EPZ and Zones J-6 J-2 Protective Action Guides J-7 J-3 Evacuation Routes J-11
- J-4 Protective Action Recommendation Flow Chart J-12 0-1 Support Personnel Training Outline 0-3 0-2 Station Personnel Training Outline 0-12 i I
P-1 . Supporting Plans P-3 j l P-2 Emergency Plan Implementing Procedures P-4 t P-3 Emergency Plan Implementing Procedures Distribution P-5 Rev. 3 June 1983 r l
INTRODUCTION A. PURPOSE This Emergency Plan for the Catawba Nuclear Station is established for the protection of life and property in all emergency and acci-dent situations. It particularly applies to those radiological situations (radiation, contamination and reactor accidents) where the health and safety of station personnel and the general public may be involved; but it also includes other general industrial emergency and accident conditions involving radioactive materials such as fire, vehicular accidents, natural disasters, medical injury or illness and industrial security. The plan described herein will be implemented at Catawba by incorpo-rating it into detailed station Emergency Procedures; as such, it will be coordinated with station operating, radiological control, industrial security procedures and corporate emergency plans. B. SCOPE The Emergency Plan is a coordinated effort involving station person-nel; station facilities and equipment; the emergency resources of the Crisis Management Plan of the Duke Power Company corporate organizations; emergency services of various local, state and federal agencies having appropriate jurisdiction or concern for public health and safety, particularly the radiological-emergency and emergency plans of local county Preparedness Agencies; Emergency Preparedness Division of South Carolina Adjutant General, the South Carolina Department of Health and Environmental Control, Bureau of Radiological Health; the North Carolina Department of Crime Control and Public Safety, and the North Carolina Human Resources Department, Radiation Protection Branch. The Emergency Plan organization and the emergency organizations that have responsibilities in the management of an emergency condition at the station are identified throughout the Plan. The Emergency : Planning Zone concept is shown in NUREG-0654, Rev. 1, and is utilized ' in this plan. The key elements of the Emergency Plan include:
- a. An essentially uniform means of reporting and handling any emergency or accident situation.
- b. A graded emergency classification system of increasing severity, based on specific criteria, Emergency Action Levels (EAL) and a method for relating EAL's to Protective Action Guides (PAG).
- c. A corporate Crisis Management Plan which is integrated into the station Emergency Plan.
Rev. 2 i-1 Jan. 1983
E
, d. Interaction with the emergency plans of appropriate local, state and federal agencies concerned with public health and safety in
. the event of a reactor accident.
The Emergency Plan is compatible with facility design features, site, layout and site location, with respect to such considerations as access routes, surrounding population distributions and lake and land use. Agreements have been made with local, state and federal authorities for coordination of activities in the event of an emergency. Local , l agencies provide fire (irotection , medical support, and ambulance l rescue service upon request. In addition, the emergency plans of the , Emergency Preparedness Agencies of the counties involved provides assistance and logistical support in the event that evacuation of portions of- the Plume Exposure Emergency Planning Zone becomes necessary. The disaster plans of the Emergency Preparedness Agencies in York County where the station is located, and of the Emergency Management Agencies in the adjacent counties (Mecklenburg and Gaston) [ as they relate to the protection of the public who may be affected by 4 an accident situation at Catawba, all include the following aspects: i i
- a. Notification of their own Emergency Preparedness Agency l j personnel and other emergency services involved in their j Emergency Plans. l i
l b. Law enforcement and traffic control.
- c. Notification or warning of persons in affected areas.
j d. Evacuation as necessary to designated schools or other public ! buildings out of the affected area, where shelter, food, over-
- night accommodations, medical care, etc., would be made
- available.
i
- e. Assistance and cooperation with related agencies in other j counties, Duke Power Company and other state and federal agencies.
i Means have been developed for notification and coordination of emergency activities with persons and groups onsite as well as within j the Exclusion Area, including portions on Lake Wylie which might be affected by an accident, as well as water authorities of nearby cities and industries downstream. l l Duke Power intends to meet 'all of the requirements for early warning of the public and will continuously evaluate the resources necessary j to provide this capability. 1 Radiological emergency situations, if they occur at all, are expected t for the most part, to be highly localized, and only station property
- and station personnel are subject to any major hazard. Cognizance has been taken of the fact that construction crews are onsite during l
Rev. 2 I i-2 Jan. 1983
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public are also within the Exclusion Area at-various times (highway
, traffic, station visitors, boating and recreation on Lake Wylie, 1 etc.). In case of a major accidental release of radioactivity, the general public and preperty in the Emergency Planning Zone may also be affected. The plan includes for the protec tion of all persons in the plume exposure pathway, as well as in the ingestion pathway, of the Emergency Planning Zone.
C. PLANNING BASIS l i The basis for this plan"is the upgraded Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, NUREG-0654/ FEMA-REP 1, Rev. 1. ^ The overall objective of the Emergency Plan is to provide for early detection, warning and protective action response and recommenda-tions for emergency conditions at Catawba that may affect the station proper and/or off-site areas. The range of emergency conditions is very large, starting with a zero point requiring no planning at all, up to planning for the worst possible accident scenario, regardless
- of its extremely low likelihood. Although the planning basis is independent of specific accident scenarios, a number of emergency
! conditions were considered in the development of this plan, including j core melt release sequences. The planning basis also considers time frames between initial acci-j dent recognition, response actions, and recommendation of appropriate protective cctions in the event a potential for, or an actual release of radioactive materials is taking place. Knowledge of the potential for and the kinds of radioactive materials released, duration of. the release and the time available to activate protective response on-site and off-site is important in determining what instructions / l recommendations are to be given. Location of the population affected i and communication mechanisms to those authorities responsible for 4 activating protective action is also an important part of the planning basis. { Emergency preparedness is related to two predominant exposure path-ways. They are: ~ Plume exposure pathway - The principle exposure sources from this ' ) pathway are: i i
- Whole body external exposure to gamma radiation from the plume and !
from deposited material; and inhalation exposure from the passing radioactive plume. ' I The duration of the release leading to potential exposure could range i from one-half hour to several days. For ' the Plume exposure pathway, l shelter and/or evacuation would likely be the principle immediate protective action recommended. This protective action will generally involve a 360* area around the station to a distance of about two to five miles, although initial effort would be in the general downwind i Rev. 1
.1-3 Dec. 1981
direction. .This concept is indicated in Figure 1 of NUREG 0654, Response Area For Emergency Planning. The precise boundaries of such
. protective action zones are largely determined by political boundaries and do not fit the precise pattern of Figure 1, NUREG 0654. The ability to best reduce potential exposure under actual conditions will determine the appropriate response by plant, corporate, state and local organizations.
Ingestion exposure pathway - The principle exposure from this path- , way would be from ingestion of contaminated water or foodstuffs. The I duration of potential ex'posure could range in length from hours to i months. For the ingestion. exposure pathway, the planning effort involves the identification of major exposure pathways from contami-nated food and water and the associated control points and methods. The ingestion pathway exposures in general would represent a longer term problem, although some early protective actions to minimize subsequent contamination of milk or other supplies should be initi-ated (e.g. remove cows from pasture and put on stored feed). The area that could be affected should an accident happen at Catawba is called the Emergency Planning Zone (EPZ). This area has a radius beginning at Catawba and extending out to about 50 miles. The choice of the size of the EPZ is defined in NUREG-0654 and below. In a particular emergency, protective actions might well be restricted to a small portion of the EPZ. On the other hand, for the worst possible accident conditions, protective actions may need to be taken to the outer parameters of the EPZ. In regard to the area over which planning efforts should be carried out, the EPZ is defined both for the "short term" plume exposure pathway (Figure 1-1) and for the " longer term" ingestion exposure ! pathway (Figure 1-2) in accordance with NUREG-0654, Rev.1. t , The size of the plus exposure EPZ (about 10 miles) is based pri-marily on the following considerations: ' ! Projected doses from traditional design basis accidents with release to the environment would not exceec Protective Action l j Guide levels outside the 10 mile zone. . l Projected doses from most core melt sequences with release to the environment would not exceed Protective Action Guide levels l
'outside the 10 mile zone. l For the worse core melt sequences with release to the environ-ment immediate life threatening doses would generally not occur.
( outside the 10' mile zone. Detailed planning within the 10 mile EPZ will' provide a sub-l- stantial base for ' expansion of response efforts if the need i arises. Rev. 1 l i-4 Dec. 1981 1 1
~ . . - . . -
The size of the ingestion exposure EPZ (about 50 miles radius) is based on the' following considerations: , The downwind range within which' significant contamination could l occur would generally be limited to about 50 miles from Catawba ; because of wind shifts during a release and because of long ! travel times. There may be conversion of atmospheric iodine, (i .e. , iodine suspended in the atmosphere for long time periods) to chemical forms which do not readily enter the ingestion pathway. Much of any particulate material in a radioactive plume would have been deposited on the ground within about 50 miles of the station. The likelihood of exceeding ingestion pathway Protective Action Guide levels at 50 miles is comparable to the likelihood of l exceecing plume exposure pathway Protective Action Guides at 10 miles. Ru.2
. 1-5 Jan. 1983
DUKE POWER COMPANY CATAWBA NUCLEAR STATION FIGURE i-1 10 MILE EPZ l
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1 A. Assignment of Responsibility Planning Objective To assure that State, Locai, Federal, private sector, Duke Power Corporate and Catawba Nuclear Station organizations that are part of. the overall response organization within the Catawba Emergency Planning Zone are identified. A.I.a Organization The principle organizations that are part of the overall response organization within the Catawba Emergency Planning Zone are listed below: Federal (Note 1) l 4 The principle Federal agencies that can provide assistance are: i Nuclear Regulatory Commission Department of Energy Environmental Protection Agency l Department of Health and Human Services Food and Drug Administration Department of Defense Federal Emergency Management Agency Department of Agriculture Department of Transportation National Weather Service Oak Ridge National Laboratories South Carolina State i The Emergency Preparedness Division of the S.C. Adjutant General (Note 2) l The Department of Health and Environmental Control Bureau of Radiological Health North Carolina State The Department of Crime Control and Public Safety, Emergency Preparedness Division (Note 2) l The Department of Human Resources, Radiation Protection Section local Government The county governments and municipal governments (within the counties) to include the emergency service departments and other agencies interrelated to these local governments within the 10-mile EPZ (plume exposure pathway) of Catawba Nuclear Station are: York Gaston Mecklenburg Rev. 2 A-1 Jan. 1983
The county governments (and municipal govern ents within the counties) to include the emergency service departments and other agencies interrelated to these local governments within a 50-mile EPZ. - (ingestion exposure pathway) of Catawba Nuclear
. Station are: -South Carolina (Note 1)
Cherokee Lancaster Chester Newberry Chesterfield Spartanburg Fairfield Union Kershaw York
-North Carolina (Note 1)
Anson Cleveland Mecklenburg Union Burke Gaston Rowan Cabarrus Iredell Rutherford Catawba Lincoln Stanley Note 1: Agreement letters with these agencies are not a part of the Catawba Nuclear Station Emergency Plan ur.less specifically noted in A-3. Note 2: This agency has the principle state responsibility for emergency response. Private Sector The principle organizations in the private sector that are part of the overall response organization for the EPZ are: Westinghouse Southern Bell Telephone Company The Independent Telephone Companies Radio and Television Stations Bethel Volunteer Fire Department Clover Rescue Squad Various vendors such as Rad Service and K-MAC Charlotte Memorial Hospital and Medical Center Piedmont Emergency Medicine Associates l Member's Southeastern Electric Exchange The Salvation Army The American Red Cross Piedmont Medical Center (Rock Hill, SC) g Rev. 3 A-2 June 1983
A.1.b Concept of Operations
. All emergencies or accident situations at the station are handled initially by the Shift Supervisor. When an abnormal situation occurs, the Shift Supervisor is able, utilizing -
- station operating and emergency procedures and from background, training and experience, to determine if the abnormal situation is an emergency condition. During the course of the emergency condition and as response personnel are notified, and emergency
- centers are activated (0.S.C, T.S.C., C.M.C.), the Shift 4
Supervisor is the person in charge, and assumes the position of '
.the Emergency Coordina. tor until the arrival of the Station Manager. When the St.ation Manager arrives and relieves the I
Shift Supervisor of the Emergency Coordinator function, he { becomes the person in charge or the decision maker. When the - Crisis Management Center (CMC) is activated and operational, t the Recovery Manager at the CMC is responsible for company j emergency response. ; } The Control Room at the station is the initial center for ) coordination of emergency response for all emergency conditions. For emergencies classified as Alert, Site Emergency and General 1 Emergency, the Emergency Coordinator shall activate the Tech-nical Support Center (TSC) and the Operations Support Center (OSC). l , The TSC acts in support of the command and control function of d the Control Room and provides an area for other station person-nel who have expertise in all areas of plant operation to , , support the emergency condition. This facility is equipped with i ! communication equipment, Operator Aid Computer (OAC) terminals, i line printers, off-site and on-site computer access, plant f ! drawings, specifications, manuals, procedures and other 4 materials and equipment to support its function. Personnel in the T.S.C. will be able to assess the accident condition and make responsible recommendations to the Control Room, the CMC , and off-site agencies as necessary to provide for the safety of { plant personnel and members of the general public. As the ! C.M.C. becomes operational, it will assume many of the func-l tions of the T.S.C. and will rely on the T.S.C. as a vital link l to the station. The T.S.C. will provide the C.M.C. with up-to- ! date plant parameters, which will allow this facility to perform
- its assigned tasks in accordance with the Crisis Management l Plan.
A.I.c Block Diagram of Organization Interrelationships (See CMP) l A.1.d Key Decision Making i i During the course of any emergency condition at Catawba, several j persons have the potential to be "in charge" or to be the " Key l.
- Rev. 3 l A-3 June 1983 i
1 I 6
Prior to T.S.C. activation and arrival of the Decision Maker". Station Manager, the Shift Supervisor becomes the Emergency Coordinator at the Station and is in charge. When the Station Manager arrives on-site and assumes the Emergency Coordinator
. position, he becomes the person in charge of emergency response and becomes the key decision maker. After C.M.C. is activated !
and becomes operational, the Recovery Manager is responsible i for company emergency response. 24 Hour Emergency Response l A.1.e The Catawbi Station eaiergency response organization beginning Room through the T.S.C.
~
with the Control is capaole of responding to an emerg"ency 24 hours per day, 7 days per week. Section E.2. describes the notification scheme within the station emergency response organization. A.2.a Responsibility For and Functions of Emergency Response Organization See Table A-1 of Crisis Management Plan. A.2.b Legal Basis For Authority (See State and County Plans) A.3 Agreement Letters For Emergency Response Support Appendix 5 contains letters of agreement with the following organizations: Piedmont Medical Center l Charlotte Memorial Hospital and Medical Center Municipal-County Emergency Preparedness Agency of York County Bethel Volunteer Fire Department. Clover Rescue Squad Department of Emergency Management, Mecklenburg County l Department of Emergency Management Gaston County North Carolina Department of Crime Control and Public Safety South Carolina Department of Health and Environmental Control Piedmont Emergency Medicine Associates l NOTE: Agreements with other agencies are found in the Crisis Management Plan Appendix 5. - A.4 Individual Responsible for Continuity of Resources The emergency response organization is capable of continuous (24 hour / day) operation for an extended period of time. The Recovery Manager at the Crisis Management Center is the individual responsible for assuring continuity of resources within the Crisis Management . Organization.
- Rev. 3 A-4 June 1983
B. Onsite Emergency Organization
~
B.1 Plant Staff Under Emergency Conditions Figure B.-2 shows the emergency organization of plant staff personnel ! for all shifts. The relationship of these personnel to their normal responsibilities and duties is unchanged during an emergency condition. B.2 Station Emergency Coordinhtor Initial activities at Catawba during any emergency condition are directed by the ' Shift Supervisor from the Control Room. The Shift Supervisor shall assume the functions of the Emergency Coordinator until the arrival of the Station Manager or his designee at which time the Station Manager will assume the responsibility of the Emergency Coordinator. The Emergency Coordinator will have the authority and the responsibility to immediately and unilaterally initiate any emergency actions including:
- a. Provide protective action recommendations to authorities responsible for implementing off-site emergency measures. This authority shall not be delegated to other elements of the emergency organization,
- b. Notification and activation of the Station, Corporate, County / City, South Carolina, North Carolina and the Nuclear Regulatory Commission emergency organizations having a response role.
- c. Continued assessment of actual or potential consequences both on-site and off-site throughout the evolution of the emergency condition,
- d. Effective implementation of emergency measures in the environs including protective actions for affected areas, implementation of emergency monitoring teams and facilities to evaluate the environmental consequences of the emergency condition, prompt notification and communications with off-site authorities.
- e. Continued maintenance of an adequate state of emergency preparedness until the emergency situation has been effectively managed and the station is returned to a normal or safe ,
operating condition. ! 8.3 Station Emergency Coordinator (Line of Succession) i The Emergency Coordinator function as described above in paragraph [ B.2 will later be assumed by the Recovery Manager at the Crisis Management Center as this corporate organization is staffed and ready to take over its functions. Rev. 2 B-1 Jan. 1983
.t This assumption of the Emergency Coordinator functions will take place for the - Alert, Site Area Emergency and General Emergency categories. l
- B.4 Protective Action Recommendations
[ The functional responsibilities of the Emergency Coordinator are de-scribed in paragraph B.2. Protective Action recommendations to state and local authorities is initially vested with the Shift Supervisor / Emergency Coordinator. As the Crisis Management Center becomes a operational, the Recovery Manager is the person who is - responsible i for making protective action recommendations. 4
. B.5 Minimum Staffino Requirements The positions title and major tasks to be performed by the persons.
i assigned to the functional areas of emergency activity at the station i are described below. These assignments shall cover the emergency functions in Figure B-1. The minimum on-shift staffing are as i indicated in Figure B-1. The: capability to augment on-shift l- resources after declaration of an emergency are as indicated in , j Figure B-1. The functional tasks to be performed by persons assigned 1 to the areas of emergency activity are as follows and shown in Figure l { B-2: I .i j i The Shift Supervisor on duty will ensure that all actions required by any initiating Emergency Procedure or by any emergency condition have been performed and that all actions necessary for the protection of 1 persons and property are being taken. The Shift Supervisor upon i being relieved of the Emergency Coordinator . functions shall continue i I' to take all actions necessary to ensure that any emergency situation is brought under control.. The Station Manager (Emergency Coordinator) or in his absence a designated alternate, shall have complete responsibility for i activation of the Technical Support Center and the Corporate Crisis Management - Plan. He shall staff the Technical Support Center with j i those personnel' deemed necessary to effectively assess the emergency j condition. He shall institute those procedures necessary to allow the Control Room to gain immediate control of the emergency l condition. The Station Manger will have direct communications via i
- . telephone or radio with' the Recovery Manager at the Crisis Management Center, each c.ounty Emergency Operating Center, the North and South
! Carolina State ~ Emergency Response Team. and via telephone to the 1 Nuclear' Regulatory Commission. He shall - maintain lines of i communication and consultation with these agencies . to ensure that they are informed of 'the emergency condition at all times in j accordance with the Emergency Plan, i The Superintendent of Operations when designated shall assume the duties of - the Station Manager. He will provide expertise to the [ Station' Manager ' and the Shift Supervisor regarding solutions to l i.. Rev. 2 [ B-2 Jan. 1983 f i
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-operational . problems. He shall ensure that each operating shift is manned with competent personnel trained and prepared to manage all . emergency conditions, and he shall augment his personnel resources as necessary to accoinplish this goal. He shall provide technical expertise to other members of the Technical Support Center and shall work closely with the Superintendent of Maintenance in restoring station equipment to an operational status during and after the emergency condition.
j The Superintendent of Technical Services when designated shall assume , the duties of the Station Manager. He will provide expertise to the l Station Manager and the Shift Supervisor regarding solutions to operational problems. He shall provide technical expertise to the other members of the Technical Support Center 'in the areas of Health Physics, Chemistry, Performance and Reactor Engineering and in Licensing and Engineering support programs. He shall ensure that all areas of responsibility under his direction are staffed with competent personnel properly trained and prepared to support any operational emergency conditions. 1 The Superintendent of Maintenance when designated shall assume the
! duties of the Station Manager. He will provide expertise to the
! Station Manager and the Shift Supervisor regarding solutions to
- operational problems. He shall provide technical expertise to the other members of the T.S.C. in areas of Mechanical Maintenance, i Planning, Instrument and Electrical Maintenance and Materials
- Support. He will ensure that all areas of responsibility under his direction are staffed with competent personnel properly trained and
- prepared to support any operational emergency conditions.
The Superintendent of Administration when designated shall assume the duties of the Station Manager. He w:ll provide technical expertise 4 to the Station Manager and the Shif t Supervisor regarding solutions to adn.inistrative problems associated with emergency conditions at the station. He shall provide technical expertise to other members of the Technical Support Center in the areas of Security, Adminstrative Coordination and Training / Safety. He shall ensure that l all areas under his direction are staffed and prepared to manage i administrative support for any emergency condition. The Operatino Engineer shall assume the -duties of the Superintendent of Operations when so designated. He will provide technical expertise to the Superintendent of Operations and other members of
- the Technical Support Center as required. He will assist the Superintendent of Operations in coordinating Operations activities
, during the Emergency condition by developing work schedules, equi ~pment and material procurement, guidance and assistance . to the Shift Supervisor, communication with the Crisis Management Center i incident report ' preparation and other support functions as needed or required to restore the plant status to normal. He shall ensure that 4 all areas under his direction are staffed and prepared to manage operational support for any emergency condition. l Rev. 2 B-3 Jan. 1983
The Assistant Operating Engineer shall assume the duties of the Operating Engineer when so designated. He will provide technical
- expertise to the Superintendent of Operations, the Operating Engineer and other members of the Technical Support Center as required. He shall assist the Operating Engineer in assessment and evaluation of the emergency condition and in any other areas of expertise deemed necessary to the Technical Support Center organization.
The Health Physics section of the T.S.C. shall consist of the Station Health Physicist or his designated alternate, a Field Monitoring Coordinator, a Data Analysis Coordinator, Health Physics Coordinator and a Radio Operator- and other Health Physics personnel as deemed necessary by the Station Health Physicist to support the Health Physics functions during the emergency condition. NOTE: The Field Monitoring teams shall be predesignated in procedure HP/0/B/1009/04. The Station Health Physicist shcIl assume the duties of the Superintendent of Technical Services when so designated. He will provide technical expertise to the Superintendent of Technical Services, the Station Manager and other members of the Technical Support Center as required. The Health Physics section shall be responsible for gathering and compiling on-site and off-site radiological monitoring data from N.R.C., State, Corporate and Station radiological monitoring and evaluation teams and for providing this information to other members of the Technical Support Center as required. The Station Health Physicist shall provide for the calculation and distribution of off-site the dose determinations for releases of radioactive materials to atmosphere. The Station Health Physicist shall make recommendations to the Station Manager through the Superintendent of Technical Services on Protective Actions deemed necessary for limiting exposures to station personnel and members of the general public. , The Station Health Physicist shall also work closely with the appropriate members of the Corporate Crisis Management Center to ensure that radiological hazard:; during any emergency condition are minimized. The Station Health Physicist shall ensure that all areas under his direction are staffed and prepared to manage Health Physics support for any emergency condition. The Station Chemist shall assume the duties of the Superintendent of Technical Services when so designated. He will provide technical expertise to the Superintendent of Technical Services and to other members of the Technical Support Center as required. He is
- responsible for coordinating chemical technical support and for initiating necessary action to insure adequate chemical sampling and
- evaluation to support the emergency condition. The Station Chemist shall ensure that all areas under his direction are staffed and prepared to manage Chemistry support for any emergency condition.
- Rev. 2 B-4 Jan. 1983 s
The Performance Engineer shall assume the duties of the Superintendent of Technical Services when so designated. He will
. provide technical expertise to the Superintendent of Technical Services and to other members of the Technical Support Center as required. He will assure that adequate levels of technical and engineering manpower are available to: manage test procedure review, ,
carryout special test procedures, ensure control and accountability of special nuclear materials, and evaluate plant and reactor 7 performance. The Performance Engineer shall ensure that all areas ; under his direction are staffed and prepared to manage Performance ; support for any emergency condition. . The Reactor Engineer shall assume the duties of the Performance ; Engineer or the Superintendent of Technical Services when so designated. He will provide technical expertise to the Performance - Engineer and to other members of the Technical Support Center as ! required. The Reactor Engineer shall ensure that all areas under his direction are staffed and prepared to manage technical support for any emergency condition. The Licensing and Projects Engineer shall assume the duties of the Superintendent of Technical Services when so designated. He will provide technical expertise to the Superintendent of Technical Services and to other members of the Technical Support Center as required. He is responsible for coordinating station activities with regulating agencies, coordinating the reporting and investigation of all incidents and for providing review of appropriate station technical matters. The Licensing and Projects Engineer shall ensure that all areas under his direction are staffed and prepared to manage technical support for any emergency condition. The Instrument and Electrical Engineer shall assume the duties of the Superintendent of Maintenance when so designated. He will provide technical expertise to the Superintendent of Maintenance and to other members of the Technical Support Center as required. He is responsible for maintaining all station I&E equiment in an operational state. The Instrument and Electrical Engineer shall ensure that all areas under his direction are staffed and prepared to manage I&E support for any emergency condition. l The Planning Engineer shall assume the duties of the Superintendent of Maintenance when so designated. He will provide technical expertise to the Superintendent of Maintenance and to other members of the Technical Support Center as required. He is responsible for the implementation and evaluation of the Maintenance Management Program and for the adminstration of the materials procurement programs. The Planning Engineer shall ensure that all areas under i his direction are staffed and prepared to manage Planning and ' Materials support for any emergency condition, i The Mechanical Maintenance Engineer shall assume the duties of the l Superintendent of Maintenance when so designated. He will provide
- technical expertise to the Superintendent of Maintenance and to other Rev. 2 B-5 Jan. 1983
c members of the Technical Support Center as required. He is responsible 'for preventive and actual maintenance for all station mechanical equipment and facilities. The Mechanical Maintenance Engineer shall ensure that all areas under his direction are staffed and prepared to manage Maintenance support for any emergency condi-tion. The Chief of Security shall assume the duties of the Superintendent of Administration when so designated. He will provide technical expertise to the Superintendent of Administration and to other members of the Technical Support Center as required. He is respon-sible for coordinating security, Utility Services and Food Vending Services for the Station. The Chief of Security shall ensure that all areas under his direction are staffed and prepared to manage i Security for any emergency condition. [ l The Aoministrative Coordinator shall assume the duties of the Superintendent of Administration when so designated. She will provide technical expertise to the Superintendent of Administration 4 and ta other members of the Technical Support Center as required. She is responsible for coordinating and maintaining general admini strative functions and support at the Station. The Administrative Coordinator shall ensure that all areas under her direction are staffed and prepared to manage administrative functions during any emergency condition. The Training and Safety Coordinator shall assume the duties of the Superintendent of Administration when so designated. She will provide technical expertise to the Superintendent of Administration and to other members of the Technical Support Center as required. She is responsible for coordinating the station training and safety activities plus Fire Protection and Medical Services in support of the emergency organization. The Training and Safety Coordinator shall ensure that all areas under her direction are staffed and prepared to provide needed training and safety evaluations during any emergency condition. B.6 Onsite Functional Area Interfaces See Figures B-1, B-2 and B-3 of Crisis Management Plan. - B.7 Corporate Support of Onsite Emergency Organization Corporate Mangement, Administrative and Technical Support personnel are given in Section B of the Crisis Management Plan. B.8 Contractor and Private Organization Contractor and private organizations are provided for in Section B of the Crisis Management Plan. Rev. 2 B-6 Jan. 1983
I B.9 Local Agency Support Service j i State, local and county agencies responsible for public health and i safety work through the Emergency Preparedness Agency's Emergency ' Operations Center in the affected county until the State Emergency Response Team establishes its headquarters; Mecklenburg and Gaston counties, North Carolina; York Municipal-County Emergency Preparedness Agency, York County, South Carolina. The Crisis Management Center coordinates with the agencies necessary to support l the emergency condition. Agencies that have agreed to provide support, as necessary to Catawba Nuclear Station and surrounding areas, are listed belowr B.9.a Law Enforcement, Emergency Traffic Control, Related Police Matters York County Sheriff's Department (York, SC) * " South Carolina highway Patrol (SC Highway Patrol, Dist. 4, Chester,SC)
- B.9.b Early Warning or Evacuation of the Populace
- 1. Department of Emergency, Preparedness, York Municipal-County, (Rock Hill, SC)
- 2. Department of Emergency Management, Gaston County (Gastonia,NC)
- 3. Department of Emergency Management, Mecklenburg County (Charlotte,NC)
., 4. South Carolina Department of Health and Environmental i Control, Bureau of Radiological Health (Columbia, SC) North Carolina Department of Crime Control and Public 4 5. Safety (Ral@h,NC) B.9.c Radiological Emergency Monitoring Assistance
- 1. US/D.O.E Radiological Assistance Team, Savannah River OperationsOffice(Aiken,SC)
- 2. South Carolina Department of Health and Environmental Control, Bureau of Radiological Health, (Columbia, SC)
- 3. North Carolina Department of Human Resources. Radiation Protection Branch (Raleigh, NC)
- 4. Civil Air Patrol, North Carolina Wing (Charlotte, NC)
Rev. 2 B-7 Jan. 1983
B.9.d Hospitals. Medical Support
- 1. Piedmont Medical Center (Rock Hill, SC)
- 2. Charlotte Memorial Hospital and Medical Center (Charlotte.
l'
. NC) .
- 3. Pledmont Emergency Medicine Associates (Rock Hill, SC) l l 4 REACTS Facility, 0.0.E. (Oak Ridge, Tenn.)
B.9.e Ambulance Service
- 1. Piedmont Medical Center (Rock Hill, SC)
- 2. Clover Rescue Squad (Clover, SC) !
v
~
- d.9.f fire-Fighting
- 1. Bethel Voluntaer Fire Department (Clover, SC) i B.9.g Public Health and Safety. Evaluation of the Radiological Situation.
- 1. York County Health Department (Rock Hill, SC)
- 2. South Carolina Department of Health and Environmental Control, Bureau of Radiological Health (Columbia, SC) l 3. North Carolina Deoartment of liwic.an Rnources, Radiation Protection Branch (Raliegh, NC)
~
- B.9.h Agreements have been made with local, state and federal agencies to provide fire protection, medical support, ambulance and rescue service. Implementation of the ~ emergency plans of the Emergency Preparedness Agencies of three adjacent counties will provide assistance and logistics support if evacuation of portions of the ten mile EPZ becomes necessary. The emergency i plans of the Emergency Preparedness Agencies in York County where the station is located, and in Mecklenburg and Gaston Counties, North Carolina, as they relate to the protection of
! the public who may be affected by an emergency at Catawba, all i address the following aspects: i Notification of their own personnel and other agencies 1.
- involved, including the Sheriff's Department, the Highway Patrol, police, rescue squads, fire departments and the Red
- Cross. l
- 2. Law enforcement and traffic control.
- 3. Notification or warning of persons in affected areas l 1
- 4. Evacuation, as necessary, to designated schools cr other public buildings out of the affected area, where shelter, food, overnight accommodations, communications, medical ;
care, etc. would be made available.
- 5. Assistance and cooperation with related agencies in other ;
, counties, Duke Power Company, and other state and federal agencies. Rev. 3 8-8 June 1983
i , I NOTE; Suemary written agreements with the agencies that have various responsibilities for emergency preparedness support and for emergency response in the public domain are included in the Appendix 5. a i i
~
l { t i t I i ( i 1 1 ; l 4 Rev. 1 B-9 Dec. 1981
-.-- . _ . _. ._ . . . . _ - m -__ _..__.___.m _ .._ ._..._. . _ . . . _ . .m_ ._. . _ .
CATAbdBA IIIBCLEAE. (.f leII 9049895 30 STArrlIIG REEMil#DGEIITS FOR EERGEIIL, ~S Position, Title on capani s ity for Additions peojer Tasks or Expertise Shift 45 min 75 min ejer rensetienes Aree (Location)
== --
Shif t Seapervisor (580) 1 . Cseet operations and Assess- Asst. shirt superv.ser (smo) 1 -- eent er operationes Aspects Centres moon operators (no) 2 -- -- j Auxiliary operators 2 -- -- l Energency Direction and ort-site e - .gi- Shirt Technical Adviser 1(1) -- w res (Emergency (2) cations shirt superviser er
- eerdineser)
Designated Faci t Ity pennager 2 . Operations Person 1 1 itotification/ Isotify licensee, ! .eemunication(3) state, tocal and Federai personnet l l t meentain communi- ' cation -- -- 1(4) I %dictogical Acciasent Assess- Crisis peonegement Recovery stoneger . l aent and support er operationes center (Coec) Senior Health Pteysics errsite pose l4eeldent Assessment Assessment (NF) Expertise 1 2, 2 ' orrsite Surveys -- 1 1 onsste tout-or-plant) 1 In-psant surveys HP Technicians 1 1
-- 1 Cheelstry/ Radio- Cheelstry Technicians 1
' cheelstry rgant System Engineering, Technical Support ShlFt Technical Advisor 1(1) Cere/Thersel Myeraulics 1 tapeir Cad Corrective Actions -- -- 1 Electrical -- -- 1 peechanica l ' Repa i r anal perchenical Desintonence/ Rad 1(1) == 1 1 Corrective Ideste Operator Actions Electrical Des intenance/ 1(1) 1 f(5) Instrassent ansi Control -- 1 ( tare) Technician . FIGUftE B-1 ( C000T. ) Rev. 2 B-10 Jan. 1963
CATAIAA INICLEA / Toil 0II MINIIeuse STAFFING REGWIRE8EENTS FOR_EDIENCEseyr i l t Position, Title on capabi l i ty for Add i t ions OEnjer Fametional Area (Location) peajor Tasks or Expertise Shift 45 fein 75 min protective Actions (In-Plant) Radiation Protection: HP Technicians 2(1) 2 2
- s. - Access Control D. HP Coverage for ropa i r, enr-rective actiers, search and rescue first aid ar fire- ,
righting
- c. Pe rsonne s moni-toring
- d. Desiastry Fi refighting -- -- Fire Local Support Brigade per Tech-nical Specifi- t ,
cations mesesse Operations and First Aid -- -- 2(1) local support f'Ite Access ControI and Security, f I re- Security Personnei AII per personneI Accommtati8ity righting, commieni. Security cations, personnei Plan accountabiIety TOTAL 10 11 15 FIGURE B-1 (Coset. ) Rev. 2 5-11 Jan. 1983 e l
, - - __ _ _ . _ _ _ _ _ _ _ . - . _ . _ , - - , _ ~ - . -
CATAWBA leuCLEAk 6iATISII MINIMUM STAFFIIIG REQUIRE 9eE4TS F0ft EstEIICEIICIES i ( !Istes: (1) May be 3:rovided by shift personnel assigned other functions. This capability may be Iloited in nature untBI roller personnel arrive on-site. (O) OveraII direction of facility response to be assumed by CseC Recovery Manager when all centers are fully menned. Cirector of minute-to-minute facility operations remains with senior senager in Technical Support Cen*er or Centrol poem. l I (3) Deny be performed by engineering side to Shif t Supervisor. , (3) Itecovery Manager position will be filled by the Foergency Coordinator sentil the Recovery Manager arrives at the CMC and assumes this function. ($) Electrical Maintenance and Instrument and Control Technicians are within the same group at Catawba. i l FIGURE 8-1 ( C081T. ) Rev. 2 8-12 Jan. 1983 e
TECHNICAL SUPPORT CENTER INTERFACES CONTROL ROOM
, ______q l CRISIS I RDINA OR l ENTE L-I 7 I I
_____________________I ,g , L________________q l l I I OPERATIONS TECH. SERVICES MAINTENANCE ADMIN. _l SUPT. SUPT. SUPT. SUPT. g .__p_______________,__J_______________________a_______________ , , OPERATWG STATION L&P l l 1&E l MECHANICAL l SECURITY - l CHEMISTRY l hRFORMA l lPLANNWG ENG4NEER - HEALTH PHYSICIST REACTOR OFFSITE TRAINING & ~ ASST. OPS. ENGINEER COMMUNICATOR SAFETY ENGINEER _ HP COORDINATOR FIRE
/
S&C BR1GADE PE RF. TECH. -
TSC LOGKEEPER OE- - OPERATIONS F ELD
-OAC COORD.
SUPPORT MONI TORING CENTE~) COORDINATOR TSC CLERKS PHASEil l O l RADIO OPERATOR N FIELD a DATA ANALYSIS MONITORING y
~
TEAMS 3z COOMOINATOR C C
=p
=m HP COORDWATOR [g
*F
\<
SUPPORT in
-s 3
-u 5 z
C. Emergency Response Support and Resources C .'1. a . Individuals Authorized to Request Federal Assistance
, See Crisis Management Plan - C.I.a C.1.b. Federal Resources Arrival Time See Crisis Management Plan - C.I.b C.1.c. Crisis Management Resources Available to Federal Response Organization See Crisis Management Plan - C.I.c C.2.a State and County Representation at Crisis Management Center (CMC)
See Crisis Management Plan - C.2.a C.2.b Local Agency Liason See Crisis Management Plan - C.2.b C.3 Radiological Laboratories - Available and Capability Laboratory facilities include mobile emergency monitoring capabilities available through the SC Department of Health and Environmental Control, Bureau of Radiological Health; NC Department of Human Resources, Radiation Protection Branch and the DOE Radiological Assistance Team. In addition, the station has an emergency vehicle and 3 other Station vehicles set op for warning and mobile-assessment purposes. Fixed facilities are available for gross counting, and spectral analysis in the station counting laboratory and at the nearby Duke Power Environmental Laboratory (45 miles) and at the Training and Technology Center. Other facilities within the Duke System at McGuire Nuclear Station (45 miles) and at Oconce Nuclear Station (160 miles) could provide further analysis support within a short period of time (1-4 hours). The above radiological laboratories are available on a 24 hour a day basis and could provide their services and equipment on demand. C.4 Emergency Support From Other Organization See Crisis Management Plan - C.4 Rev. 2 C-1 Jan. 1983
D. Emergency Classification System This section of the Catawba Emergency Plan generally describes each of the four classes of emergency. Tha four classes are as follows:
- 1. Notification of Unusual Event
- 2. Alert
- 3. Site Area Emergency
- 4. General Emergency D.1/ Emergency Classification - Initiating Conditions. Emergency D.2 Action Levels Each class of emergency is described below. Figures D-1, 0-2, D-3, D-4 show Initiating Conditions, Emergency Action Levels, F.S.A.R.
accident conditions and the appropriate Emergency Procedure / Document. NOTIFICATION OF UNUSUAL EVENT This classification applies to unusual events in progress or which may have occurred that indicate a potential degradation of the level of safety of the plant. Examples of situations or occurrences in this classification are as described in Figure D.1, Accident Conditions / Emergency procedures. Response actions for Emergencies are listed in Figure 0-1.A, Response to Emergencies. ALERT This classification applies to events that are in process or have occurred which involve an actual or potential substantial degradation in the level of safety of the plant. Examples of situations or occurrences is this classification are as described in Figure 0.2, Accident Conditions / Emergency Proce'ures. Response actions for Emergencies are listed in Figure 0.2.A, Response to Emergencies. SITE AREA EMERGENCY This classification applies to events that are in prccess or have occurred which involve actual or likely major failures of plant functions needed for protection of the public. Examples of situations or occurrences in this classification are as described i in Figure 0.3, Accident Conditions / Emergency Response. Response . actions for Emergencies are listed in Figure D.3.A, Response to Emergencies. Rev. 2 0-1 Jan. 1983
t GENERAL EMERGENCY This classification applies to events that are in process or have occurred which involve actuel or imminent substantial core Examples of situations or occurrences in this classification are described in Figure D.4 Accident Conditions / Emergency Procedures. Response actions for Emergencies are listed in Figure D.4. A, Response to Emergencies. D.3 State and Local Organization - Emergency Classification System See State and Local plans. D.4 State and Local Organization - Procedure For Taking Emergency Actions See State and Local plans. Rev. 2 0-2 Jan. 1983
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y . _ IIGURE D-1 CLASS: NOilflCAIION Cr UNOSUAL EVLCT ACCIDE%i CONDITIONS /EMEHCENCY PROCEDURES Catawba Nuclea r Stat ion Notirication Or UnusuaI roergency Action IinaI Sarety AnaIysis [me rgency Event Initiating conditions tevel (TAL) Report Section 15.0 Procedure / Document ,
- 11. Indications or alarms on Loss of process or effluent Loss or orrsite power to station AP/1/ A/5500/22, geocess or ef fluent radiation monitoring system ataxiliaries IP/1/A/5000/0:4 parameters not functional or loss or all meteorological loss of Instrument Air AP/1/A/5500/07 its Conte ol Room to an extent instrumentation onsite or requiring plant shistdown or loss of all radio / telephone ether signiricant loss or communications capability cssessment or communication orrsite, capability (e.g., plant composter, meteorologica l instrumentation).
- 12. Security threat or attempted As notified by Security force. Station Security cnt ry or a ttempted sabotage. Plan AP/0/A/5500/33 l
- 13. Natural phenomenon being Tornado. Flitsile impact, Gwperienced or peojected beyond us'. sal levels Artalysis
- c. Any earthquake rett in 3 (<.089H. <.053gV), Annunciator RP/0/A/5500/07 plant or detected or Alarm station seismic instrumentatlon.
D. 50-yea r riood or Inw wa ter, b. As observed. RP/0/A/5500/06 husricane sierge, se icien (lake tidal wave).
- c. Any tornado on site c. As observed. RP/0/A/5500/06 C. Any hurricano d. Winds > 13 mph from Natiotsal RP/0/A/5500/06 Wea the r Se rv i ce i n fo rma t i on I ts . Other haza r ds beinal G rperienceo or projected,
- p. Aircraf t crash rinsite or a. As observed. RP/0/A/5500/09 unussia l a i rcraf t activity
. over racili ty. .
As observed. , , RP/u/A/5500/09
- Il,/,yy'i s
- b, . b. , . .. . .. ,,. . .
. ! p'/, g EM. ,,Slowr(site i ra in de ra el"i onalte lment onsi
,, '.t.*te.d
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FIGURE D-1 CLASS: NOTIFICATION C' '8NUSUAL EVENT ACCIDENT CONDITIONS /EME CY PROCEDURES Cattvba Nuctsar Staticn Notification or Unusual Emergency Action Final Sarety Analysis Eme rgency , Event Initiating Conditions Level (EAL) Report Section 15.0 P rocedure/ Document
- 15. Cther plant conditions As determined by the Shirt As applicabi,e exist that in the Supe rv i so r/ Eme rgency Coo rd i na to r.
Judgement or the Shif t Supervisor, t he Ope ra t ions Du ty Eng i nee r, the Super-intendtnt or Operations or the Station Manager warrant increased awa reness or Local authori ties or rcqui re plant shutdown under Technical Specifi-cGtion requi rements or - involve other than norma l controlled shutdown (e.g., cooldown rate exceeding Technical Specification limits, pipe cracking round during operation).
- 16. Transportation of con- As observed. : Station Di rective trainated injured 2.11.1 Individual from site HP/0/B/1009/06 t3 orrsite medical rccility.
- 17. G pid depressurization As observed. Accidental Dep ressuriza t ion EP/1/A/5000/01 cr seconda ry side, or Main Steam System EP/1/A/5000/1D D.3.4 Rev. 3 June 1963
CATAWBA NUCLEAR ..ATION F igura D.2. A Respor.e to Emergercies . I State and/or Local Orrsite Authority Actlens C_lCfts . Licensee Ac_Rons .
- 1. Promptly inform State and/or loca' 1. Provide fire or security LE3T assistance i f reque s ted. ;
authorities or alert status and
' lass Desqription reason for alert as soon as '
discovered. 2. Augment resources and bring v:nts are in process or have - primary response centers
- c urr2d which involve an 2. Augment resources and activate and EBS to standby status.
!. ctu)I or potential substantial on-site Technical Support Center igrcdJtion of the level of and on-site operational support 3. Alert to standby status key OrGty of the plant. Any cen te r. Bring Emergency Operations emergency personnel including ogs3ces expected to be Facility (EOF) and other key monitoring teams and icitsd to small f ractions of emergency personnel to standby associated communications.
- he ETA Protective Action status.
uid3line exposure levels, 4. Provide confirmatory orrsite
- 3. Assess and respond, radiation monitoring and utgast ingestion pathway dose
- 4. Dispatch on-site monitoring teams projections ir actual releases orpos? cr 'orrsite alert is and associated communications, sustantially exceed technical e i1) essure that emergency specification limits.
Provide periodic plant status : ernennal are readily available 5. O retrand ir situation becomes updates to orrsite authorities 5. rscalate to's moro severe cro 53rious or to perform (at least every 15 minutes). Class, ir appropriate. Cnri rS3 tory radiation monitoring r r2 quired, and (2) provide 6. Provide periodic meteorological 6. M6fntain alert status until frsito cuthorities current assessments to orrsite authorities verbal closeout or reduction totus inf 7rmation. and, if any releases are occurring, or emergency class. dose estimates for actual releases.
- 7. Escalate to a more severe class, if a pp rop r i a te.
OR
- 8. Close out or recommend reduction in a.
emergency class by verbal summa ry to - orrsi 3 authorities followed by written summa ry within 8 hours or closout or class reduction. Rev. 2 Jan. 1983 D-4
flCURE D-2 CLASS: #RT ACCIDENT CONDITIONS /EF 'NCY PROCEDURES Cat:wb3 Cuclear Station Alert Emergency Act
- rinal Safety Analysis Eme rgency initiating Conditions Level (EAL) Report Section 15.0 Procedu re/ Document 1 Severe loss or fuel a. Very high coolant activity Loss of Coolant Accident EP/1/A/5000/01 cladding. Mechanical sample indicating an EP/1/A/5000/1C Clad ra llure, increase of 70psCi/mi in EP/1/A/5000/28 30 minutes gr 350 to 750 AP/0/A/5500/31 jugCi/mi total 1-131 coolant AP/0/A/5500/18 activity.
- b. railed fuel moni tor (EHr48) gr lab analysis indicates increase greater than 1%
ruel railures within 30 minutes SI 5% to 25% total . fuel ra l e u re.
- 2. Rapid gross railure of Pressurizer low pressure alarm Steam Generator Tube Rupture EP/1/A/5000/01 one Steam Generator tube and reactor trip and pressurizer E?/1/A/5000/1E with loss or orrsite low level a la rm and pressurizer EP/1/A/5000/10 power, low pressure safety injection EP/1/A/5000/04 signal and undervoltage ala rm on AP/1/A/5500/07 7KV buses. [Hf 33 arsd 34 radiation ala rms.
- 3. Rapid failure or more than Severa l hundred gpa prima ry to Steam Generator Tube Rupture EP/1/A/5000/IE 10 Steam Generator tubes, seconda ry leak rate indicated EP/1/A/5000/01 by:
- a. Pressurizer low pressure alarm and reactor trip and pt essurizer low level alarm and pressurizer low pressure safety injection signal a_nd undervoltage a la rm on i KV buses.
EHf 33 and 34 radiation a l a rms ,
- b. Steam Generator level increa sing in one or mo re g6tne ra to r( s ) and falling in the others due to a reartur trip.
- Rev. 3 D.4.1 June 1983
flCURE D-2 CLASS: ALERT ACCIDIC2T CONDITIONS / EMERGENCY PROCEDURES Catawba Nuclear Station Alert Emergency Action final Sarety Analysis Emergency Initiating Conditions Level (EAL) Report Section 15.0 Procedure / Document
- 4. Steam line break *sith signi- Creater than 10 gpm, rapidly Steam Genesator Tube Rupture CP/1/A/5000/01 ficant primary i.o secondary decreasing reactor coolant Minor Secondary System Pipe IP/1/A/5000/1E Icak rate. Tavg. pressurizer pressure Break and sevel and: Major Secondary System Tube FP/1/A/5000/1D Hupttere
- a. Steam line dirrerential EP/1/A/5000/2E pressure safety injection signal and increased Containment Building ,
pressure if break is in containment.
- b. High steam flow arid Lo-Lo Tavg, or low steam pressure sarety injection signal for rupture downstream or MSIV's.
- 5. Primary coolant leak rate Leak > 50 gpm as indicated 5y Partial l o s t. af Reactor Coolant EP/1/A/5000/01 I greater than 50 gpm. calculation or other riow Loss of Reactor Coolant from EP/1/A/5000/1C indication. (i.e., sump Small Ruptured Pipes AP/1/A/5500/to level). Loss ol' Coolant Accident
.6. .High radia t ion levels or increase by a factor nr 1000 Waste Cas Decay Tank Rupture IP/1/A/5000/01 in sadiation monitor reading Steam Generator lobe Rupture llP/0/8/ 009/0g liigh airborne contamination which indicates a severo within the station loss or Coolant Accident ilP/0/DJ 009/13 digradation in the control (P/1/A,3000/1C or radioactive materials. EP/1/A/5000/IE
- 7. Less o r o rrs i to powe r sjnf* Undervoltage alarm on 7 kV Loss or orr-site power to E P/1/A/5000/Ota less or all onsite AC power busos jtj}d blacitotet load station auxiliaries (StaLiore AP/1/A/5500/07 ror up to 15 minutes. (See sequencers actuated. Clock-out)
Sito Area Emergency RP/0/A/5000/04 ror extended loss.) 1 1 . 84 . 2 Rev. 2 Jan. 1983
-~ . - . - . .
FIGURE D-2
-CLASS: ALERI ACCIDENT CONDITIONS /EMERGLNCY PIOCEDURES Catawba Nuclea r Station Emergency Action Final Sarcty Analysis Emergency Alert Procedure / Document Initiating Conditions level (EAl) Report Section 15.0
- 1. css of all onsite DC power. DC bus utidervoltage alarms. Tech. Specs.
- 8. 3/4.8.2.3 on all buses.
Tech. Specs. 3/4.8.2.4
~
Reactor coolant pump auto trip Partial loss of Reactor Coolant AP/1/A/5500/08,
- 9. Ccolant' pump seizure leading EP/1/A/5000/28,
.to fuel railure, a l a rm a_Od reac to r t r i p on low flow l.-
coolant riow a,nd railed fuel Single Reactor Coolant Pump AP/1/A/5500/01
- monitor on EMF-48 indicating Locked Rotor increase greater thasi 1% f~uc t railures within 10 ministes or 5% total fuel ra i l u re s. ._
RifR not functional and inability loss or Instrument Air AP/1/A/5500/22,
- 10. Complete loss or lunctions Loss of Off -Si te Power 1P/1/A/5000/04, needed for plant cold to maintain natural or forced AP/1/A/5500/19 shutdown. ci m ulation.
= - =
Reactor remains critical af ter EP/1/A/5000/03 l
- 11. Failure of the reactor.
all attempts to trip reactor 3 protection system to initiate nod complete a have been completed. tcram which brings the reac to r subcri t ica l . EMI-15, 17, 38, 39, 40 or 42 Fuel llandling Accident EP/l/A/5000/01,
- 12. fuel damage accident with release or radioactivity to Radiation alare und observation inadvertent Loading or fuel csntainment or f'uol handling of damage to spent fuel Assembly into an improper AP/1/A/5000/18 building. assembly following an accident Position AP/1/A/5500/25 in fuel handling areas that. EP/1/A/5000/2E is the opinion of the Shift Supervisor, may have resulted !
in damaged spent fuel. Tech. Specs,
- 13. Fire potentially arrecting Observation or a fire that 3/4.7.10 and 11 safety systems, could arrect safety systems.
Most or all a't a rms As observed, l.oss or Orr-Site Power EP/1/A/5000/04 l
- 14. AP/1/A/5500/07 (annunciators) fost. '
D.4.3 Rev. 2 Jan. 1983 4
TICURE D-2 CLASS: # 'T ACCIDENT CONOITIONS/EM (CY PROCEDURES Cattwb3 Nucicar Staticn
. Alert Emergency Action Final Safety Analysis Eme rgency .
Initiating Conditions Level (EAL) Report Section 15.0 Procedure / Document
- 15. Ai rborne radiolog ica l EMr-35 Low Range off-scale Waste cas Decay Tank Rupture EP/1/A/5000/01 effluents greater than 4 Liquid Waste Storage Tank Rupture EP/1/A/5000/1C 10 times Technical Speci- High Range 2 1 x to cpm Steam Generator Tube Rupturs HP/0/8/1009/13 fications instantaneous HP/0/8/1009/14 limits (an instantaneous 6 EP/1/A/5000/IE rate which, ir continued EMF-36 Low Range 2 2 x 10 cpm
. over 2 hours, would result .
2 in about 1 er at the Site High Range 2 5 x to cpm Boundary under average meteorological conditions or whenever errivent monitors or radiological monitoring detect these levels).
- 15. Ongoing Security As reported by' Securi ty Force. Station Security compromise. Plan
- 17. Severe naturai phenomona being experienced or
, projected.
- a. Earthquake greater a. > 0.06gH, > 0.0539V, RP/0/A/5500/07 than Operational Basis Ala rms ( AD-4)
Zarthquake Levels
- b. riood, low water, b. As observed. RP/0/A/5500/06 1,urricane surge, seiche near design levels. (Lake tidal wave),
- c. Any tornado striking c. As observed. Tornado Missile Impact RP/0/A/5500/06 racility.
- d. Hurricane winds near d. Winds > 95 mph from RP/0/A/5500/06
' design basis level. National Weather Service I n fo rma t ion.
- 18. Other hazards being experienced or projected:
- a. Ai rc ra f t cra sh on a. As observed. Tornado Misslie impact RP/0/A/5500/09 racility,
- b. Misslie impacts from whatever source on racility. .
- c. Known explosion damage c. As observed. RP/0/A/5500/09 to racility arrecting plant operation.
D.4.4 Rev. 3
- June 1983
IICURE D-2 CLASS: ALER. ACCIDE%T CONDITIONS /EMERCENCY PROCEDURES Catawba Nuclear Sta t ion Alert Emergency Action Fina1 Sarety Anatysis Esergency lEltioting Conditions . Level (EAL) Report Section 15.0 Procedure / Document
- d. Entry into f,cility d. As observed RP/0/A/5500/08 environs of toxic or riammable gases.
O. Turbine railure causing e. Turbine trip and Loss or External Electric Load RP/0/A/5500/09 casing penetration, observation of turbine and/or Turbine T rip ma l funct ion or a la rm.
- 19. Cther plant conditions exist As determined by Shif t Supervisor As dictated by
- that in the , judgement or the rmergency Coordistator Plant Conditions Shirt Supos visor, the Operations Duty Engineer, the Superintendent or Operations, Or the Plant Manager wareant precautionary activation or Technical Support Center and near-site Crisis Management Canter, t
- 20. Evacuation of Control Itnpin As determined by Sitif t Supervisor AP/l/A/55HO/IT g anticipated or required with Emergency Coordinator OP/1/A/6100/Of4 l centrol of shutdown systems established from local station.
D.4.5 Rev. 2 Jan. 1983
- - - - - - __.________--_.a
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. e t s *g e ,
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/r oi y n
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rrd a pu c oa l s r e l aie oae n ditts T eo ds psn areo ll n a vt dl e e nraio . S A.rg t yu e dd urr abo ce a ps eb rl asna nn m myeswc bSl g . douh ca itsm d r l R 3.e tea ar d aa i st il e gi e o neo ar A m Si n sl ne n - EDE L Ceo s n o miuo rrts tso eaom. cciE rit ) op s ias es tm, d vosi itewr haa lrau nspt eaS nit cvt orea osst rol alf b ead n sl n e e . o bi yf c tbo. esi e rsrdso n 5 D Urt Nu i t ooa fhts unaer ohrt0 r e sen i e n t o er. aia otr aoeri to tci ed eoron ea aorlhwut
- ge c ntsa sceiE n i naio rtn tt o l vn oi octooc Ais A iu eeps( d ogt addJ oia e lli eao tr ulhu Brn ayy rTo- n na po is msaas r i p tyal - W op e y cc ry a hic euisrpnnC euus nt eo uc o8e d
A e l enn teeat cri t eor ettdi eoam aptr onef r T s s ttee nttei s ton asea s N dacim d et n A e n eiinl C R e pi g g msrr mssg-i e s atu pi m ic ut phr erh r imavs vi in idr veo aa srsnhs l p e gi e i s ic oree rrmm unnna s ioo etnp dc s snm dade kat otrda osf c oerota ati rsonr ran sf l mrhil _ L Poee Aooar A Dmc Dsa( Msw Pefit Pbi Ei C e o pw c
. . . . . . . . . 0 _
1 2 3 4 5 6 7 8 9 1 _ y e c ct) n rn i na2e o oo l eh(r i mi b gt a ty t u el r a t s ad p va .on ee,s uuetn . aur cto mrdmtcdml aes htori c oldtsy i . eueaaa cu,he snehvtos ti rasfbecl r asntteaens t o e utAea e rd pc vd eaa r mgere cior boeri svue slldepvl u eeen a) nrorn tfo I eiufaoei h Y C eoiehxi o cvaeteteb e(rrs idrst t aosdstioeu - N n onrn cr io taeaavhta E o ri fteue stsi reuota C i p rsootst rn)i rtrude - R t hon nooi e s e o3 u ai pa pt E o ncjon rps hitm(q s ui M i iiaiosPx t n ,ertf4ter e )e s E r hmtie er net - s s A s g ew ctsA a r yncaPee focad oi hel s ii(idr sio a E e adl ueeEnn tethe s,rv l R D eeftl 8 e eas cnrnsroh . C A srk cedl t s srnetnaouorg . s tritereep o oaor aoeio pu - E s nul nt ede p pl pupsntih o _ T a ec aoycic r rcsssr art)r - I l vcrl rnxux u ueesiertei5h S G E u o ppa eG e f Pd r ad po s s w(t IIlll ! - > ' < ,
s FICURE D-3 CLASS: SITE AREA F 'GENCY ACCIDENT CONDITIONS /EMERG PROCEDURES < c=tswb3 Nuclear Stetien Sito Area Emergency Emergency Action Final Safety Analysis Eme rgency. Initiating Conditions Level (EAL) Repo rt Sec t ion .15.0 Procedu re/ Document
=
- 1. Known loss or coolant Pressurizer low pressure Accidental Depressue ization of EP/1/A/5000/01 Cccident greater than reactor trip and pressurizer the deactor Coolant System. EP/1/A/5000/1C makeup pump capacity. Iow pressure sarety injection Lo;r or Coolant Accident. AP/1/A/5500/10-signal and high containment Par 6ial Loss of Reactor Coolant EP/1/A/5000/2E building pressure, (INSP- Flov.
5040, 5050, 5060, 5070) and high containment building sump level, (INIP-5260, 5270) and high containment humidity,
- (INSP-5400, 5410) eDd EMF 38, 39 and 40 rad ia t ion a l a rm.
- 2. Degraded core with possible Inadeouste Core Cool ina Complete Loss of Forced Reactor EP/1/A/5000/01 loss or cooleple geometry Coolant . Flow, Major Reactor AP/0/A/5500/31 (Indicators should include a. Core exit the rmocoup e e s Coolant System Pipe Rupture, AP/0.*A/5500/04
. instrumentation to detect indicate > 1200*F. Pa rt i a l Loss or Reactor Coolant EP/1/A/5000/28 inadequate core cooling, Flow. EP/1/A/5000/1C coolant activity and/or b. Rx vessel level W/R containment radioactivity indicates < Full gllh levels), any NC pump on and abnorea1 containoent conditions RDd core exit the rmocoup les
> 700*F.
- c. (later)
Mechanical Clad Failure
> 25% ralled fuel indicated by > 1750 g i/mi 1-131.
Severe Fuel Ove rtempe ra tu re i 1% to 10% ralled fuel indicated I by 1300 to 13,000p6Ci/mi 1-131. Fuel Melt
.5% to 5% railed ruel indicated by 1180 to 11,800jeci/mi 1-131.
D.5.1 Rev. 3 June 1983
& j* ii' :!
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FICURE D-3 CLASS: SITE AREA EP' 'ENCY ACCIDENT CONDITIONS /EMERCEI 'RDCEDUP.ES C3ttwbs Nuctear Section Sita Area Emergency Emergency Action Final Esfety Analysis Eme rgency . Initicting conditions Level (EAL) Report Section 15.0 Procedure / Document
- 8. Transient requiring operation Reactor rema ins critica l arter EP/1/A/5000/03 cf shutdown systems with all attemps to trip reactor have failure to scram (continued been completed.
power qsneration but no core Camage immediately evident).
- 9. Major damage to spent fuel EMF-15, 17, 38, 39, 40 or 42 Fuel Handling Accident AP/1/A/5500/25 l in containment or fuel Radiation alarm and observation Tornado Missile impact, Spent EP/1/A/5000/2E handling building (e.g., or major damage to spent fuel Fuel Analysis large object damages ruel assemblies or water level below
- l cr water loss below fuel fuel level rollowing an accident level). In fuel handling areas that, in the opinion or the Shift Supervisor, may have resulted in damaged spent fuel.
ID. Fire compromising the Observation of a major rire that Tech. Specs. Functions of safety systems. defeats redundant safety system '3/4.7.10 and 11 or functions.
- 11. Most or all alarms As determined by the Shirt Supe rvi so r/ AP/1/A/5500/07 (annunciators) lost for Emergency coordinator. EP/1/A/5000/04 more than 15 minutes and a plant is not in cold shutdown cr plant t rans ient initiated while all a la rms lost.
- 12. Erriuent monitors detect For EMF Low Range, Waste Decay Tank Rupture HP/0/B/1009/13 levels corresponding to orrscale Liquid Waste Storage Tank HP/0/B/1009/14 High Range Rupture EP/1/A/5000,*1C f renter than 50 ar/hr forhour gr greater than 500 > 8 x 10 8 cpm d
cr/hr Whole Body for two (See Note 1) I Ginutes (or rive times these levels to the thyroid) For EMF Low Range, 5 ct the site bounda ry > 3 x 10 cpm for adverse meteorology. High range l ( See Note 2) 1
> 7 x 10 cpm (See Note 1) !
For EMF Change of 143 cpa/ minute for 30 minutes or a change or 1430 cpe/ minute for 2 minutes. ( See Note 1) D.5.3 Rev. 3 June 1983
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FIGURE D S 3 ~ CLASS: SITE AREA EMFoCENCY ACCIDF4T CONDITIONS /EMERCEF 'ROCEDURES Catcwb3 Nuclear Station . Emerg;ncy Action rin38 Sarcty Analysis Eme rgency Sito Area Emergency
- Initiating Conditions Level (EAL) Report Section 15.0 Procedure / Document
+
NOTE 1: These values are worst case calculations and may not reflect more revorable weather conditions. NOTE 2: These dose rates are projected based on other plant parameters (e.g.. radiation level in containment with leak rate appropriate for existing , containment pressure) or a re measured in the envi rons. ( EPA Prctective Action Guidelines are projected to be exceeded outside the site bounda ry. )
' . Station Security
- 13. imminent loss or physical Physical attack on the plant control of the plant. Including imminent occupancy of Plan Cont ro l Room and auxi l ia ry AP/1/A/5500/17 shutdown panels.
- 14. Severe naturn i phenomenn being experienced or projected with plant not in cold shutdown.
- a. Earthquake greater than (>.15gH. >.1gV) as determined by RP/0/A/5500/07 SSE (Safe Shutdown monitoring seismic instrumentation Ea rthqua ke) levels. and recording devices,
- b. Flood, low water, As determined by Shirt Supervisor RP/0/A/5500/06 hurricane surge. Emergency Coordinator seiche greater than design levels (lake tidal waves) or railure or protection or vital equipment at lower levels,
- c. Winds in excess or Winds > 95 mph frne National. Tornado Missile Impact RP/0/A/5500/06 design levels. Wea the r Se rv i ce I nfo rma t ion.
D.5.4 Rev. 3 June 1983 w
FIGURE D-3 CLASS: SITE AREA EP"'9ENCY ACCIDECT CON 0lTIONS/EMERCE PROCEDURES Catcwb2 Nucicer Staticn Emergency Action final Safety Analysis E.'e rgency Sita Area Emergency , faitioting Conditions Level (EAL) Report Section 15.0 Procedu re/ Document Cther hazards being experienced Tornado Missile '=ance, Spent ruel
- 15. Analysis sr projected with plant not in esid shutdown.
O. Aircraf t crash arrecting Aircrert crash causing damage or RP/0/A/5500/09 vitsi structures ty fire to Containment Building, impact or fi re. Cont ro l Room, Aux i l i a ry Bu i ld i ng, ruel Building or intake Structure,
- b. Severe damage to safe Loss of functions needed for. hot RP/0/A/55GU/09 shutdown equipment from shutdown as in item 7.
missiles or explosion.
- c. Entry or toxic or Entry or uncontrolled toxic or RP/0/A/5500/08 riammable gases into riammable gases into Control Room, vital a rea s . Cable Spreading Room, Containment Building, Swi tchgea r Room, Auxil ia ry l Shutdevn Panels or Diesel Rooms.
As determined by Shirt Supervisor As d'ctated by
- 16. Cther plant conditions exist Plant Conditions that in the Judgement of the Emergency Coordirator.
Shirt Supervisor, the Operations Duty Engineer, the Superintendent of Operations er the Plant Manager warrant activation of emergency c;nters and monitoring teams cnd a precatitionary public notification.
- 17. Ivacuation of Control Room As determined by Shif t Supervisor AP/1/A/5500/17 cnd control or shutdown Eme rgency Coo rd ina to r. OP/0/8/6100/13 tystems not established -
from loca6 stations les 15 minutes. D.5.5 Rev. 3 June 1983 9 4 4l
~
- ._ . ._ _ _. .- . _--.-...._m . - _____ .. . _ . . _ - _ -_ _ __ , .. _
m , , I CATAWBA NUCLEA ,TATION 2 rigure D.4. A Response to Emergencies . State and/or Local Offsite - Authority Act ions Class Licentee_ Actions GENERAL EMERCENCY 1. Promptly inform State and/or local 1. Provide any assistance requested, orrsite authorities of general
- Class Description energency status and reason for 2. fctivate immediate public notirl-emergency as soon as discovered cation of emergency status and Events are in process or have occurred ( Pa ra l le l notification of State / Local). provide public periodic updates, which involve actual or imminent ,
Cubstantial co re deg rada t ion o r 2. Augment resources by activating 3. Recommend sheltering for 2 mile molting with potential for loss or on-site Technical Support Center, radius and 5 miles downwind and Containment i n teg r i ty. Releases can on-si te Operationa l Support Center assess need to extend distances, be rSotonably empected to exceed EPA and near-site Crisis Management Consider advisability of . Prctictive Action Guidelines exposure Center (CMC). evacuation (projected time ' levels orrsite for more than the available vs. estimated immeticte site a rea. 3. Assess and respond, evacuation time. )
- Puroogg 4. Dispatch on-site and orrsite 4. Augment resources by activating monitoring teams and associated prima ry response centers.
, Purpose of the general emergency communications, decierotion is to ( t ) initiate 5. Dispatch key emergency personnel predetermined protective actions for 5. Dedicate an individual for plant including monitoring teams and the public, (2) provide continuous status updates to orrsite authorities associated communications.
. 0cC3ssment or information from and periodic press briorings (perhaps i f icantee and of fsite organization meJewrements, (3) initiate additional Joint with orrsite authorities). 6. Dispatch other emergency personnel to duty stations meatures as indicated by actual or 6. Make senior technical and management within 5 mile radius and alert '
potcntial releases, (4) provide starr onsite available for consultatinn all others to standby status. centultation with orrsite authorities with NRC and State on a periodic i cnd (5) provide updates for the basis. 7. Provide ortsite monitoring public through orrsite authorities, results to licensee, DOE and
- 7. Provide meteorological and dose others and Jointly assess them}}