ML20106C862
| ML20106C862 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 08/21/1984 |
| From: | Balch M DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20106C857 | List: |
| References | |
| PROC-840821-01, NUDOCS 8410240367 | |
| Download: ML20106C862 (264) | |
Text
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( ' Form 34731 (10-81) (Formerly SPD 10021) 4 DUKE POWER COMPANY (1) ID No: RP/0/A/5000/01 PROCEDURE PREPARATION Change (s) I to PROCESS RECORD 2 Incorporated (?) STATION: CATAWBA (3) PROCEDURE TITLE: CLASSIFICATION OF EMERGENCY , (4) PREPARED BY: Mike Bolch DATE: Aug. 16, 1984 (5) REVIEWED BY: h 7 M d [Mv DATE: 8!3C 8Y Cross-Disciplinary Review By: Mk N/R: 8 Al-P 9 (6) TEMPORARY APPROVAL (IF NECESSARY):. - - - - By: (SRO) Date:
.,I By: Date:
(7) APPROVED BY: W- f Date: $ l (8) MISCELLANEOUS-Reviewed / Approved By: Date: Reviewed / Approved By: Date: eW6 8410240367 840919 PDR ADOCK 05000413 F PDR [.
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DUKE POWER COMPANY i g CATAWBA NUCLEAR STATION l
., y , CLASSIFICATION OF EMERGENCY 1
- 1. 0 SYMPTOMS l i -
i 1.1 Notification of Unusual Event ; i i 1.1.1 Events are in process or have occurred which indicate a
; potential degradation of the level of safety of the plant. . ; 1.1.2 No releases of radioactive material requiring offsite j response or monitoring are expected unless,further i degradation of safety occurs. ;
r 1.2 Alert t , 1.2.1 Events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. . . . .. 1.2.2 Any releases are expected to be limited .to small fractions of the EPA Protective Action Guideline exposure levels. (- L 1.3 Site Area Emergency i 1.3.1 Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public. 1.3.2 Any releases are not expected to exceed EPA Protective Action Guideline exposure levels except near the site boundary. 1.4 General Emergency 1.4.1 Events are in process or have occurred which involve actual or imminent substantial core degradation or melting i with potential for loss of containment integrity. 1.4.2 Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area. 2.0 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. s.
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RP/0/A/5000/01 Page 2 of 2
,. (~ 2.2 . Refer to the applicable Emergency Response Procedure (RP) for the i classification found in Enclosure 4.1:
Notific$ tion of Unusual Event RP/0/A/5000/02 Alert 5
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RP/0/A/5000/03
. Site Area Rmergency RP/0/A/5000/04 General Emergency RP/0/A/5N)0/05 3.0 SUBSEQUENT ACTIONS ! 3.1 To escalate, de-escalate or close out the Emergency, compare f plant conditions to the initiating Conditions of Enclosure 4.2.
4.0 ENCLOSURES 4.1 Emergency Event List for Emergency Classes
! Event No. Psge(s) , 4.1.1 Primary Coolant Leak 1&2 '
4.1.2 Fuel Damage 3 4.1.3 Steam' Sys' tem 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 4.1.6 Loss of Alarms and/or Communication 9 4.1.9 Spent Fuel Damage 10 4.1.10 Natural Disasters and Other Hazards 11 4.1.11 Other Abnormal Plant Conditions 12 L 13 4.1.12 Contaminated and injured Individual 14 4.2 Emergency Classification Guide Flowchart M { (- 1
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Page I or 14 CAI AWitA NUCl! AR SI All0N IHIRGENCY ACT10N ILVEL*S F0ft LYL M I ..E L_ 88 .L l _. trJ me ry_C991a u t. I v a h CisH Notification or Conosal Emergency unusteal Lvent Alert Site Area imorgency
- 1. IIC Leak > 50 gpm 1. NC Leak > Total ICCS 1. Sma l l o r I.s rge R OCA
- 1. NC Leakage > Tech.
yllt! railure of ICCQ, *e Specs. LCO: capacity: .
- 2. P-S leak > 10 gpa leads to core me1L:
ENC leak > 10 gpa EyMPIONS g identiried primary eND $YMEL0_MS - leakage eP2R tow Press R4 Trip !,. a. steam line break. ePIR Low Press S/l Signal eS/I signal and Rx trip e> 500 gpd from any S/G elligh containeerit Press eHigh Containment skemidity AMg
$YMPIONS e> 1 gpa total P-S through elligh Contalsemem Siemp l evel .
Rapidly decreasing: etMf-38, 39 & Iso in alarm eN/I & NO pumps not all S/C running oAny press boundary leakage ENC Tavg 2. Several hiendred gpm P-S ,~ ePER Press leakage ANU e> 1 gpa sonidentified ePZR Level leakage ANU eN/I t' low indicatos "No AND rIow" e> asu gpm controlled loss or arrsite power: leakage at 2235 psig etMr-33 & 38: In alarm. ANQ esteam Lleio Radiation elligte Containment Sassp e> 1 gpa from NC press isolation valve at 2235 Monitor in alarm on the ePIR tow Press Alarm ePIR tow Press Rx Irip tevel psig arrected S/G. erlR Low Level Alarm 2. Small I.OCA and initially
- 2. f ailure of a PZR PORV or esteam line low Press succe ss fiel ICCS with safety valve to close S/1 signal glity eLHf .93 & 38s in alarm f ailure of NS ~ystem over rollowing a reduction or increasing Contain- .
several f oote r s, Ica:Is to sic press: mont press (ir break esteam Line 'itadiation core melt and railure of eValid acconstical in Containment). Monitor in alarm on containment: I, the arrectegl S/G. monitor indication of Sytit[gMS valve railure, elligh steam flow and elow-Low lavg AN1! - ePZR low press itx Lrip LNH Cggj jNtJLQ eUV alarm on ikV bisses ePZR Inw press S/l signal ENC temperature is rising Mll!!91 D
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ENS riow indicators show "No flow" after > 2 hoters , s L8lE r j 4
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- Pcgs 2 cr 184 i CATAW11A NUCLIAR SIA110N.
IMiltGINCY ACIl0N llVft'S 101t LYLM L1_81 ,1dd r_I taa ry__ Cog l a n t _ Le a k ( Con t i nued ) class NotilicatIon of Site Asea fuergency General [mergency Unusual Event Alert
- 3. Falliere or one S/G tsibe 3. > 50 gpm P-S leakage AMD eN9 loss or orr' site power; a steam 't isie break M SYMt. IGM 3 AND ePZR low press alarm identification of fuel ePZR low press trip damage, e P2R low level alare ePZR low press S/1 signal $yMfl0M$
et Mf'-33 4 38e in alarm Rapidly decreasing: esteam t.ino Radiation Monitor in alasm on the ENC favg arrected S/G. ePIR Press eP7R tevel A_UD elMF-33 & 384 in alarm ouV a la rm ore a l l 7 1(V bensos esteam Line Radiation Monitor isn'aelarm on time 8e . Fa lliere > 10 S/G tubes: arrected S/C Severa l fuendred gpa P-S loak: A_ND
$YMP j gMS eSteam line inw Press S/l signal nette er2R low press alasm increasirig containment ePIR low peess Rx Irip press .
ePZR low level alarm ePZR low press S/I signal Agp Aglj (if steam 1.ino becak is in contaisement) etMF-33 ar 38s in alarm of MI-$3 A and/or 8 . esteam 8.Ine liadiation . indica tes >. 3R/lir i Moni to r in .a la rm on the arrected S/G. elligh steam riow and Low-tow Inyg LN9 6NQ elMI-N8 In alarm LH9 4 S _ _ _ _ _ _ _ _ _ _ - - 'd
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Enc asisre 4.1 P ge 3 cr 14 CATAWHA NUClrAH SIAIloM-IMtRCENCY ACT10N tEvr1.'S FOR LYtMLf_81 1,h. 19t LDemage Class motirication or Site Area leergency General Emergency Uniesua l Event Alert
- 1. High coolant activity: 1. Severe loss or rieel 1. Degraded ' core willt 1. toss or 2 or 3 rission I cladding; mechanical possible loss of product barriers yltg clad falloise: coolable geometry: a potesitial for tuss, of s . > I AAC l /g ram Dose ,
rqulvalent 3-131 or a. Very liigh coolant 3rd barrier: g
> J0QMCi/ Cram activity sample ejilas!gquatg Core Coojjgig 200 p&Cl/mi to a. LOCA as identified 1000jt,C1/el See FP/l/A/SueHl/28 in rvent 4.1.1 Slte r
equivalent 1-131. Area fuergency. gross activity, item si
*Meshanini_S tas!_[a tt3nre
- b. > 0.1% increase in b. EMr-48 Indicates elig riee l railure within lacrease > 1% ruel >1000/l:l/mi 1-131 30 min. Failures within 30(>min.ptCI/ml) 40 locomplete Cont. Isol eSevgrg_Li!aLovertemetra tis.rg 96 gg 1% to 10% ruel railures as b. LOCA as identified I ri estimated by Al'/0/A/5500/38 fvent 4.1.1 Site Asea 1% to 5% riset Emergency, item #1 tallures e51 to 25% total fuel l
i< rallures (> 200jbCi/ml offe_i_t!s!! t 6809 SYdttotti 1-131)
.5% to 5% ruel raitures as ofMr-48 alarm Note: Dotosmissed by estimated,Isy AP/0/A/5500/31 etMr-53A asid/or il laboratory analysis 4 egg llote: Determissed by > 10 R/hr
- 2. NC pisap seizure leads laboratory analysis
- ANg j el-131 concentration fuel fa l liere:
increases by 4 {ffG over a 30 min.ptci/el period EYME10MS eCosita inmen t p re s s eMC pump trip alarm .
> 14.8 psig for at 96 least 2 minutes, 8!fD el-131 cusu:entration altx trip on low flow
- 2. Severe fuel Damage 4Ci/mi to j 40/
200 g l/mi of He L_0YntIsmeer.!IL!!! u eMD ! wate: Determined by > 10% fuel ra i lsere s laboratory asialysis o> 1% increase fuel railures as estimated by within 30 min. (> 40gf:l/mi {Jfg within 30 min.)
- AP/0/A/5500/31
- On
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.e51 total rieel railiares .
> $$ (not ralinees l (> 200 g i/mi 1-131) .
as estimated by j alote: Determined by . AP/0/A/5500/31 Imboratory analysis LNQ L!fD i g . . , - _ _ _ _ _ - - _ - . _ . _ _ . _
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CP/0/A/$0400/Ol' Inclusara 4. 8 P:ge 4 sr 14 CAIAWilA NUCIIAR STAIION E M(RCf NCY ACi l0N L LVi l ' S FOR [YL M I_f_.8 t .1.3 L_Be!= _Syll es!.la l !i,r e Cjpg Notificat on of Alert Site Area t eorgency General Imergency Uniestsa l Event
- 1. Failcare or a safety or 1. P-S Leak > 10 gpa 1. > 50 gpa P-S leakage N/A PORY on an S/G to close. !
- rollowing a reduction or 6000 A8M!
l SM pressure. M a steam line break a steam line break
- 2. Rapid depressurf 2stion or secosulary slee: syntions A800 .
i $yMf10!t$ Rapidly decreasiseg: identi'rication or fuel damage.
- a. S/l sigana l ENC Tavg l
- b. As observed ePZR Press EYMEjgMS ePZR tevel LIlg Rapidly decreasing:
oNC lavg j etMr-33 & 34 in alarm. ePIR Press I ePZH Level esteam Line Radiation etMF-33 & 34 in alare Monitor in alarm on esteam t.ine Hadiation the arrected S/C. Monitor its alarm on the affected S/G. eSteam line low Press S/I signal yjt!_ A80i! I lucreasing Contain-ment press (ir break eSteam lino tow Press in Coestaisemeest ). S/l sigenal witte lancreasing contairement olligte steam riow gget press i slow-Low Tavg. A898) L!!D (if steam line break is in cientainment) ofMi-53A.and/or 8 indicates > 3R/hr. . oHigh steam riow and a Iow-low lavg
# A8H8 ofMT-44 in alare.
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P;9e 5 (Er 184 CAI AWHA leuCl f AH SI Alloff IMtitCEleCY ACilOff t [Vrl 'S Ital { LYL81L E A h81:_H is!!_Med l A119n/M419 to911:a l. t.f f f!*ettLE Clas, sootirications or Site Area f eiergesicy General E me rgency unusisal Event Alert
- 1. Radiological Erriaients 1. Higla radiations level 1. Radiologic'al e r rlinesets 1. Erriuent monitor detect Tech Specs Exceeded: or high airborne con- > 50 mr/hr for 30 min. levels corresperiding p:
tamisia t ion: I.YMU!!!E Increase by a factor of IM 1 R/hr Whole Body W otMr-31. 35, 36 31, 49 1000 in radiation moeiltor
- or 50 in alare readings within station. > 5048 mr/hr Whole 9 11
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' Body for 2 mire. (or Airborne radiological SX these Invels to 5 N/hr lleyroid at the Site j M} 2. soundary:
errissents > 10X IS 1hyroidi at the site I limits (instasitas.cous boundary; canicontrolled releases cent isused Isullcating rata):
- Radiological Erreuent
' Tech. Specs, exceeded. SyMflosg! etMt-35 SLMUO893 EYeRLJH as etMr-35 . etMI-37 charige of 2800 cpe/ i (_ggg , mi.sute over any time Low Range 2 6.2 x 10 cpm low Rarige arrscale interval as determined etMr-36 I f rom recorder. trace. t
!- 5 High Range >. l.3 x to cpm Low Range 2 1.7 X 10 cpm
[ff0 g, 1 ofMr-36 High Marige 2 2.5 X 10 cpm tow Range offscalo
- 3 LllQ High Rarige , 8s.4 x 10 cpm erMr-37 t haeuso or 18e3 cpm /ministe for 30 minutes or a change or or 1430 cpm / minute for 2 minutes as determined rrom recorder trace.
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- CAI AWilA NUCi rAR ST Al l0N fHERCE10CY ACTION tTVEL'S IOR LYL!I L f _81 ml A__ Le m a_e f.J!!alW9vu _f ues t 19 tis gjass flotification or Si te Arca finergency Gene ra l roergency unustsal Event Alert
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- 1. Complete loss or 1 Complete loss or func- 1. Iransient requiring Rx trip M/A tions needed for plant with railsere to trip.,
runction needed for , i-plant Egld ghe:Wgygg: pqt ghutslowl): Additional railure or core cooling and FCCS EYMtHw!S Syt!tl M S would lead to core me @ eleO not functional einabilsty to establish . NV pump issjec t ion Hylltjo!!$ AB)g eRx remalais critical after Ally all attempts to trip the einability to maintain Itx are complete natural or forced cool- .elnability to establish down. CA riow . A190
- 2. f ailure of the Henctor of? eNo 800 neul NI ilasw indicated.
Protection System to initiate and complete eInability to establista 2. I raris ient initiated by loss a trip whicle briregs LIse kC Flow, arest Cf and CM Systems rollowed reactor suberitical: by railure or CA System f or extesided period. Core melt-eReactor remains critical 2. lHANSitNI reqtsf ring log is possible in several af ter all attempts to operation or sleastdown hours wittiesitisrate railisse trip have been completed, system with rallure to of conta irement likely: to trip: L81g Sytstto_Hs oReactor remains critecal after all attempts to eHx trip on 10-10 S/G 1evel trip have been completed. A!sp
. owide rarple S/G level'toward offscalo low on all S/G
[3D AstQ eNo CA flow indicated OH eCA pawnps tsat reasisting and caripot be restneed witisin 30 minutes B*
Q I O . CP/?/A/5000/31 s, s InclIsure C.1
- Page 7 Er 14 CAI AW8A IlOCL E Aft S T A l loll .
IMiltCIllCY AC18001 LEVEL'S FOR LYLMLA_%1.6L _LeuJ![_ foyer Clens Isoterication or Alert Site Ase4 Emesgency General toergency Usussua l Event
- 1. loss or ortsite power 1. loss or arrsite power 1. Failure or orrsite a0d
- 1. Loss or offsite Power:
estd loss or all onsite ens i to powe r yj gl_1 tote l'9 a aftd loss or all onsite AC power for > j),mJh loss of CA makeesp for' 1YMtigM AC power for 5 13_migt. MYtral_!!9s8fl. leads g lyEf[0_E3 $YMtIOMS core melt and f alliste of containment: eUV alarms on all eUV alas's on all ouV alarm on all 7 RV besses gyEP_J_0MS 7 KV buses 7 kV buses ello elle Loss or onsite power etN alarm on 4160V etN alarm on 4160V eUV alarms on all 2. basses bisse s F kV besses capabil6ty: Loss of all vital DC 2. loss of all vitil UC All0
}yMPitWIS 2.
powe r for > - j) mitt. basses for 5 1}_gitt. _
$VMEl0M e84ackout load sequefacer eMales generator lyM[{gM actuated incapable or supplying in-house loads eUV alarm on all vital eUV alism on all vital DC barses Lugg DC buses ,
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Lite LMD eCA pump ls) rail to start. e8oth D/G's inoperable LMQ L!!D _ e o
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( ,O, . CP/2/A/5000/01 reeclosure 4. I Page O Cr 14 CATAWBA leUCLEAR SIAI1086 IBMRGileCY AC19001 i LVE L'S S oft LYmLL at.1. F: f i rn_ati!Iles!!rity_Acti!!!!1 Cint) lletificatsort of Site Area Emergency General Emergency linusteal Event Alert
- 1. Fire (within protected 1. Fire poteestfally 1. Fire compensisiseg the 1. Any major internal or area) lasting more than affecting safety reenctions or safety external events (e.g.g %,
systems: systems: rires, earthquakes IO minutes: sehstavetially beyond e0bservation or a enbservation of a design levels) which W e0bservation or fire cosold casese massive detection stare ra re Eliat coteld major fire Lleat common damage to plant lastieng > 10 einestes, arrect safety systees, defeats redewsdant safety systese or systems.
- 2. Secesrity threat 2. Ongoing Security reanc t ions.
comproelse: 2. Loss or physical control
- 2. Beef stent loss or o* the facility; 98[ physical control or eAs reported by Security Force the plant: ePhysical attack on the oAttempted entry racility has reseelted Ugg erhysical attack on in occaspation of the 03 the plant inciaseling Control Room ased leelssent occespasecy of auxiliary sheetdown eAttempted sabotage As reported by Control Room and pan el s.
Security Terce, answillasy shestdown paneIs. Ugg Ul0 OfD m e e d e e O O t,
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CA B AWilA leuct I AR SI AllOff tp!nctescv Acteoss atytt'S ton LYtM L f _8' .L B I__199_e f_ A ta r o1La!W/9 r_commam i ca tLon cien - sootirication or Site Area tourgency ceneral Emergerecy SAssusua l Evesst Alert
- 1. Most or all alarms 1 Most or all alarms ll/A l 1. Instications or alarms l asmuncia tors) Inst , .,
on process or effluent l annarnica to rs ) lost. for SS minutes ppsj . parameters not functional In control Itoon to an [ 19 9 plant is not in sold sleutdowt W l extent requiring plant stasstdown g[ otlier l signi ricacit loss or DJ assessment or commiens- erlant g rases ient cation capability: initiated wlille all alarms lost.
} M {tW!S etoss or process or L9ltj of fisserit Radiation monitoring system M
eloss of all meteoro-logical inst reameesta t ion onsite AlpD einability to call Itational Weather Service for back up source or ' meterorological alata. M eloss or all radio / teleptiosse cosseenica-Lloens capability. I f i l h
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P ge 13 af 14 CAIAWILA 100C1IAR SIAIIOli fMtRCE80CY ACI1000 tEVEL'S IOH IYtM L g_ai,3,gt_SpetiLf ueI menage glasg Ilotification of General leergency IBnessua l Event Alert Site Area toergency le/A 1. Fuel damage accident 1. Major damange to spent II/A W119 release of radio- fasel in containeeset or , activity to Contalesment (seel Standliseg tsullding: or f uel llandling Beellding: HMfl0MS W HHf1R891 etMf-IS, i i. 38, 39, 40 etMf-IS, 17, 38, 39, 40 or or 42 in alare 42 in alarm 88f8! A!!9 eobservatioon or major damage eObservation of damage to to speset feeel assemblies spent riseI asseuleIy followiteep an accident in og resel harestliseg areas Lleat, , in the opinion of Llee eWater level below Shi f t Seepervisor, may leave feee l level following an resulted in damaged spent accident Ise resol leasedling f ese l . areas tisat,'in tise opinion of Liao Steift LIpq Seepervisor, may have resulted in' damaged spent fuel.
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O ItP/2/A/5000/LI i Enc 11s'tre 8s.1 Page 11 of Ise CAIAWHA NUCl_ EAR SIAllON ( Mt HCi tICY ACT I ON t [Vi t ' $ F OR LYML.f_al d,Jis: Naturas pinasters ajuashedialau ss Class flotification of Site Area teorgency Coneral Emergency Ussisual Event Alert 1.a. Earthqstako < DDE felt I a. Fa rtliqtsake > OHE: 1. Wien plant is not in 1. Asiy major intersial or cold shutdown: external events (e.g.g lo plant or detected: fi ress. eartliquakes sash-
> 0.D89 48erizontal a. Eartlwguake > SSI: stantially beyosul desig
< 0.06g llorizontal levels) which coteld catrse O!! massive common damage to
> O.15g Horizontal O!I plant systems.
> 0.053g Vertical
< 0.053g Vortical {N!
LMU
- b. take level: b. take lev'el: > H.109 vertical liigh > 580 ft. to 592.2 ft. Higt 592 ft. 59s.6s ft b. Bake tevel:
low 559.9 ft. to 550 ft. tow < 550 ft. with 5885WP available liigh > 59s.6 s ft.
- c. Any tornado on site low < 550 ft.
- c. Any tornado striking
- d. Seestained Winds > 73 mph facility 690
- d. Sustained Winds Loss of SNSWB' 2.a. Ai rcra f t crash on- approact Isog 95 mph site gr tenusual c. Sustained Wiseds > 95 mphs aircraf t activity over site 2.s Aiscraf t crash on facility affecting 2. When plant is not
- b. Traise derailed safe operation of plant ist cold sInistdown:
i onsite. a. Aircraf t crash caissing
- b. Missile impact on facility affecting damage or l'i re to Contain-i c. Seear sito or onsite safe operation of plant aant thsilding, Control Room, explosion Asaxiliary Building, fuel
- c. Ewplosion damage to lissliding or RN Intake Structure
- d. 90 ear site or onsite facility affecting toxic or flamanable safe operation of plant b. Damage from missile or gas release emplosion ceases
- d. UncontsoIIcd Inability to establish:
- e. Turbine rotatisig 1) clia rgiseg pseep injection .
componesit falltare Entry of toxic or caisses rapid plant flammablo gas into 2) CA flow
- shistdown facility affecting 3) FC or RN flow safe operatiosa of plant
- c. f r.tey of tenenntrolled
] MD e. Iurbine totating component toxic or flamanable gases fallasre caissing possetra- Into Control Houm, Cable tion of tassbisee Spreadieng Rqom, Coesta insneset casing. Besliding, Sw 6 tchgea r Room, Auxilia ry Sliestdowns l'anels or Diesel Holues, affectivig MQ safe operation of plant. 30 e*
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Enctssuro 4.1-P ge 12 af 14 CAI AWBA fluCI rAR SI All006 . EIt[RCIIICY ACIIOli LiVEt.'S FOR LYLMLL81ml.311__0ther MtfMtrMLEI.enLGotelh Lont Glast Isottrication of General reorgency Ignusua l Event Alert Si te Ares, Emes gency
- 1. ECCS Initiated: 1. Evacesation of Control 1. rvacasation of' Control 1. Other plant conditions Room anticipated or Room gis!! control of' exist, f rom whatever , ..
S/I signal veri fica tion recluired with control shestdown systems not sossrce. Eliot in the ' of sheetdown systems established reon Jeestgement of the Shig h by redundant Indication and discharge into vessel, established from local local stations in Supervisor, the Opeta M 15 minutes, t ions Duty rngitteer, ties station. Superisitefieletet of Opera-
- 2. Abnormal coolant tempera-
- 2. Other plant conditions 2. Otheir plant coswlitions tions or the Plant tiere ased/or pressears or leanagstr sehe release of abnormal Reactor roast exist that in the exist that les tioe tempera tsere: Jaadgement of time Judgencent of the Shif t larqpe amouests or radle-Shirt Supervisor, the Supervisor, tlus Opera- actfvity in a stoort time operations Duty Lions Duty l eigineer, period possible (e.g. ,
or igure 2.5-1 lech Specs Lise Superintendent of any core melt sitiestion), exceeded. Engineer, the Seeper-leitefeslent of Opera- Operations or tise Plant flanager warrant actlva- (flq gg tions, or Llie Plant leessager warrant pre- tion or ISC & CMC ecore Sub-cooling cautionary activation and monitoring tones Itang tor less than of ISC & OSC. asist a precanationary acceptable (Outsiste peablic esotificatlove. Acceptable Region) [32 L899 .
- 3. Loss of containment ,
inLegrity rectuiriese stiastdown by Tech. $pec: oAny stetonatic contaln-ment isolation valve,
- found to be open ased Inoperable and unisolable.
96 e8eth air lock doors on - a lock lesoperable, gr. penetratioens fall leak test per tech Spec when . containment integrity is reclui red. G00luftt8ED e w
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CP/r/A/5000/31
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rocIO;;ura 4.1 Page 13 er 18e CAI AWilA 800ct r AR ST AT 1088 - (MERCLIICY ACllott LEVil'5 IOR LYLRLE_81._tJ1; ot!!sr_Ahnor!HLLtlanL9 ntl11ent Icentin ed) Ginn lentification or Site Area leergerecy Gene ra l f oe rgency unusanal Event Alert C. Loss or engineered safety , -we reature or fire protection ' system reenction reegastring shutdown by lectonical Speci fica tiosis: eESr actasation system roewd inoperable. O!! er f re Protection Water System rotwed Iseoperable ror lech Spec.
- 5. Other plant coshtitions awIst thet in the Jeedge-ment or the Shirt saiper-l visor, the Operations l
Duty Esegineer, tlie Super-intciedent of Operations , or the Station Stenager eWorrent increased 'awaressess - or local anotherities E . oftegesIre pIant shestdown tander
- i lech Spec rectasirements l y etnvolve other than normat l controlled sheetsiown.
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O O RP/0/A/$4MND/;I ' I Incirsurs 4.1 g P;ge 14 Ef 14 j CAI AWBA 80UCit AH SI Allost EMERCfilCY ACI1000 tIVfL'S FOR LYENLfJa l 12L_Gentamineted_andJttlurfd Jndiridual Ele 1s
- Itatification or Site Area leergency Coperal Imergency Ustessual Eveset Alert N/A N/A N/A
- 1. Transportation of w, cositamissated Isa.jured .!
Isuelvide al from site W t to ortsite medical facility. LNG l . e 9 6 e
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t: . Form 34731 (10-81) (Formerly SPD 10021) DUKE POWER COMPANY (1) ID No:'RP/0/A/5000/02 PROCEDURE PREPARATION Change (s) 2 to f PROCESS RECORD 3 Incorporated
- (2) STATION
- CATAWBA (3) PROCEDURE TITLE: NOTIFICATION OF UNUSUAL EVENT j (4) PREPARED BY: v<t,. natch DATE: i.. is t aa r.
(5) REVIEWED BY: [ A d -s d . M e se DATE: 8/20 !8'/ Cross-Disciplinary Review By: N/R: FeW (6) TEMPORARY APPROVAL (IF NECESSARY):.' s i By: (SRO) Date:
- , ( ,
By: Date: ) (7) APPROVED BY: - u- d t Date: i I! i j j (8) MISCELLANEOUS: Reviewed / Approved By: Date: l l Reviewed / Approved By: Date: 1 1 l l l I I i i
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. . - , _ . , . , , _ _ . - _ . _ , , . . . - . _ _ . - _ . __._._,__._.-_.-_,_.,.,-..__--..,,,--_.,.-..---_.-..,.._.__.-____.,_-..m.,.-
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i e RP/0/A/5000/02 .
. (:
l DUKE POWER COMPANY , o CATAWBA NUCLEAR STATION g 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 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 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 Notifications shall be as the order of Enclosure 4.1 indicates. See RP/0/8/5000/13 for NRC Notification. NOTE: The State and County notification must be made within 15 minutes of declaration of the emergency. 3.0 SUBSEOUENT 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. O R., if there is any significant change to the situation. ; 9.R. As agreed upon with the individual agencies. 3.1.2 Use Parts I r,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.
--- ,- --., ., -.,,..,- ---..-.--,,- , ., , ~ - , - - - -
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I, RP/0/A/5000/02 3 Page 2 of 2 I e 7 3.2 Augment shift resources to assess and respond to the emergency situation as needed. 3.3 Assess he emergency condition, then remain in a Notification of Urrusuar Event, escalate to a more severe class or termirate 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 4.1 Telephone Notification List , 4.2 Emergency Message Format 4.3 Example Warning Message: Nuclear Facility to State / Local Government .
. .. s . .
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RP/0/A/5000/02 Enclosure 4.1 Page 1 of 2
.; l TELEPHONE NOTIFICATION LIST j 4.1.1 CNS Emergency Personnel Initial I
', 1. Operations Duty E ineer - Plant Page l ! P L T Pager' - A: See Current O tons work List for Home Phone Number. l
- 2. - J. W. Hampton
- Station=- Manwa ;
W. Graves l 1st Alterna l Offic ' Home 2nd Altern W. Cox Offic l ! Hom . ,,-
. . s .
l 3rd Alternat T. Smith l l Offic l i Home ( s ! 4th Alternate - A. R. Franklin l f i
! 3. License L P ts Engineer - C. L. Hartzell f Office Home q , ! ist Alternat M. E. Bolch I
Offic Home l l , \ 2nd Alternat - P. G. LeRoy l j Office * . Home s - l
. . . 4.1.2 Nuclear Production L age
** USE ENCLOSUR .
i-i l 4
=am - - - - - - - .
RP/0/A/5000/02 Enclosure 4.1 Page 2 of 2
- - . 4.1.3 State f, County Warning Points (Within 15 minutes)
*** U S E EN C LO S U R E 4.3 ***
- 2. S.C. S P: 7:30 a.m. 5:00 p.m. Weekdays A- After hours, Weekends f, Holidays l
USE ENCLOSURE 4.3 *** ,
- 3. Mecklenburg County Back-up: Emergency Radio. Code:
*** USE ENCLOSURE 4.3 ***
- 4. York Count P:
A: , Back up: Emergency Radio, Code: *
- *** U S E EN C LO S U R E 4.3 *** . '
- 5. Gaston Count
- P:
( A-Back-up: Emergency Radio, Cod
*** USE ENCLOSURE 4.3 ***
4.1.4 NRC rations Center, Bethesda, Md. (RP/0/B/5000/13) P: A: . l 9 4 mi.is i i
l t e o i l RP/0/A/5000/02 Enclosure 4.2 Page 1 of 1 DUKE POWER COMPANY CATAWBA NUCLEAR STATION NUCLEAR PRODUCTION DUTY ENGINEER EMERGENCY MESSAGE FORMAT
- 1. This is at Catawba Nuclear Station.
(Name and Title)
- 2. This is is not a drill. An X Unusual Event Alert Site Area Emergency General Emergency was declared by the Emergency Coordinator at on Unit 8 (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 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 and Company Management should be notified. ;
- 9. I can be reached at - for follow up information.
(Telephone Number) e
- 10. Additional Comments Name of Person Contacted Date Time 4
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i RP/0/ A/5000/02 Enclosure 4.3 Page 1 of 4 EXAMPLE 3 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 f,11 for follow ep 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: PARTI
- 1. This is: Catawba Nuclear Station (A 2. My name ist __ John Doe, Shift Supervisor
- 3. This message (number j ):
X (a) Reports a real emergency. (b) is an exercise messa e,
- 4. My telephone number / extension is: '
- 5. Message authentication: USE MESSACE AUTHENTICATION LIST (Verify code word or call back to f acility)
- 6. The c. ass of the emergency ist X (a) Notification of Unusual Event (b) A'ert (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 ist _ Loss of
_Offsite Power
- 9. The emergency condition: _ X (a) Does not involve the release of 3 radioactive materials from the plant.
(b) Involves the potential for a release, but no release is occurring. (c) Involves a release of radioactive material. l
4 i RP/0/A/5000/02 Enclosure 4.3 Page 2 of 4
, ( 10. We recommend the following protective action:
X (a) No protective action is recommended at this time. (b) People living in zones remain indoors with the doors and windows closed. i (c) People in zones evacuate their homes and businesses. I (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. 1here will be:
(a) A followup message , ,, , , ,
'~
. X (b) No further communications Approved for Release .
- 12. I repeat, this message:
{/. X (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 *** 7 PART11
- 1. The type of actual or projected release is: N/A .
(a) Airborne - (b) Waterborne , awy (c) Surface spill (d) Other The source and description of the release is: N/A
~
2. l l s. - 3. N/A (a) Release began /will begin at a.'m./p.m.; time since reactor trip is hours. i N/A (b) The estimated duration of the release is thours. l
,y --.
, RP/0/A/5000/02 Enclosure 4.3 Page 3 of 4
, ! 4. Dose projection base data:
Radiological release: 'N/A curies, or curies /sec. Windspeed: 5 mph Wind direction: From 180 Stability class: D ( A, B,C,D,E,F, or G) Release height: N/A Ft. - Dose conversion factor: N/A R/hr/Ci/m3 (whole body) N/A R/hr/Ci/m8 (Child Thyroid) Precipitation: 0 Temperature at the site: 72 *F
- 5. Dose projections: N/A
- Dose Commitment * . ,
Whole Body (Child Thyroid) Distance Rem / hour Rem / hour of inhalation (c .. Site boundary V' 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): N/A
- 7. Emergency actions underway at the facility include: N/A
)
1
- 8. Onsite support needed from offsite organizations: NONE i
- 9. Plant status:
. l
(, (a) Reactor is: not tripped / tripped j (b) Plar.t is at: 100 - % power / hot shutdown / cold shutdown / cooling down 1 (c) Prognosis is: sta ble/im p rovi n g/deg radi n g/u n k now n
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- l RP/0/A/5000/02 Enclosure 4.3 l Page 4 of 4 1
i i- 10. I repeat, this message: X (a) Reports an actual emergency. Approved for Release (b) is an exercise message. Emers. Coord. Time .
- 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 . procedure. (Receivers) 1. (name) (title) - 9 (date) (tinta) (warning point) -
- 2. .
(name) (title) . * (date) (time) (warning point) fl u 3. (name) (title) . i (date) (time) (warning point) - 4. (name) (title) i i (date) (time) (warning point) , 5. (name) (title) 1 (date) (time) (warning point)
~
- 6. !
(name) (title) ] (date) (time) (warning point) j j
- 7. i
,- (name) (title) i
( (date) (time) (warning point)
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I P L i Form 34731 (1041) (Formerly SPD-10021) s t I c DUKE POWER COMPANY (1) ID No:RP/0/A/5000/03 PROCEDURE PREPARATION Change (s) 2 .t o PROCESS RECORD 3 Incorporated (2) STATION: CATAWBA (3) PROCEDURE TITLE: ALERT (4) PREPARED BY: v41e. nnt e.h DATE: i ,,3 54 t on (5) REVIEWED BY: [4 M d4[w DATE: F/20 /FV , Cross-Disciplinary Review By: N/R: $ -Lf-8Y (6) TEMPORARY APPROVAL (IF NECESSARY): f By: (SRO) Date: r (i By: Date: , (7) APPROVED BY: W- Date: ff/hth (8) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: e 4 pee e i w- F
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T RP/0/A/5000/03 DUKE POWER COMPANY CATAWBA NUCLEAR STATION ALERT 1.0 SYMPTOMS o 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 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. , ,. 2tl.2 Notifications shall be as the order of Enclosure 4.1 ' indicates. See RP/0/B/5000/13 for NRC Notification. NOTE: The State and County notification muet be made within 15 minutes of declaration of the emergency. 2.1.3 Advise station personnel to activate TSC and OSC. 3.0 SUBSEQUENT ACTIONS 3.1 Accident Assessment: 3.1.1 Dispatch on site monitoring teams with associated communications equipment, see HP/0/B/1009/09. 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 l If there is any significant change to the situation. i-E . As agreed upon with the individual agencies. v 3.2.2 Use parts 1 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.
I
; __ RP/0/A/5000/03 i Page 2 of 2 1
t 3.3 Recommend Protective Action Offsite { i NOTE Protechve Action Recommendations are obtainedOAC Progre " Nuclear-23" or RP/0/A/5000/11, if the OAC is not from: operational, for Operations Personnel. 3.4 If the emergency situation is rapidly degrading then conduct a Site Assembly, see RP/0/A/5000/10. 3.5 Augment shift resources to assess and respond to the emergency situation as needed. 3.6 Assess the emergency condition, then remain in an Alert, escalate to a more severe class, reduce the Emergency Class or close out the emergency. 3.7 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 8 hours. 4.0 E%'CLOSU RES 4.1 Telephone Notification List J 4.2 ' Emergency Message Format 4.3 Example Warning Message: Nuclear Facility to State / Local Government i I
-, --w- t-w -- - , , , -
RP/0/A/5000/03 Enclosure 4.1 Page 1 of 2 TELEPHONE NOTIFICATION LIST 4.1.1 CNS Emeroency Personnel Initial
- 1. Operations Duty En i - Plant Page P L T Pager i A: See Current Operations Work List for Home Phone Number.
- 2. Station Man er - J. W. Hampton Offic ,'
Home 1st Alternate - C. W. Graves o e N 2nd Alternate - J. W. Cox
, N.. . .
. . 3rd Alternate - G. T. Smith . .
o s 4th Alternate - A. R. Franklin o ..s
- 3. Licensing & Pr ' ts Engineer - C. L. Hartzell Office -
Home x 1st Alternate - M. E. Bolch o e 2nd Alterna - P. G. LeRoy Offic < Hom
. _ 4.1. .$ Nuclear Production Du 'neer P & T Page
** USE ENCLOSUR h
m.
- - - =- ._. .
i RP/G/A/5000/03 Enclosure 4.1 Page 2 of 2 4.1.3 State & County Warning Points (Within 15 minutes)
- 1. N.C. tate. Raleigh ,
P: A:
*** US ENCLOSURE 4.3 ***
, 2. S.C. te Columbia P: 7:30 a.m. - 5:00 p.m. Weekdays A: After hours, Weekends L Holidays
*** USE ENCLOSURE 4.3 ***
- 3. Mecklenbur County -
P: A: Back-up: mergency Radio, Code:
*** USE ENCLOSURE 4.3 ***
- 4. York Cot.nty P:
A: Back-up: Emergency Radio, Code-
*** USE ENCLOSURE 4.3 ***
- 5. Gasto P:
l, A:
'- Back-up: mergency Radio, Code:
*** USE ENCLOSURE 4.3 ***
I 4.1.4 NRC Operations Center, Bethesda Md. (RP/0/B/5000/13) l
- p. g nhone) -
6 0
li ll RP/0/A/5000/03 Li Enclosure 4.2 Page 1 of 1 ll (f DUKE POWER COMPANY
~
CATAWBA NUCLEAR STATION Il - NUCLEAR PRODUCTION DUTY ENGINEER EMERGENCY MESSAGE FORMAT
- 1. This is at Catawba Nuclear Station.
4 i (Name and Title) i i
- 2. This is is not a drill. An Unusual Event -
X Alert l' Site Area Erhergency General Ernergency ^ was declared by the Emergency Coordinator at on Unit e .
. (Time) -
- 3. Initiating Condition: (Give as close to the emergency plan description as -
possible together with station parameters -used to determine emergency status.) j 4. Corrective measures being taken:
- 5. There have have not 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. i 8. The Crisis Management Team should should not be activated. ; Corporate Communications and Company Management should be notified. 3
- 9. I can be reached at for follow-up information.
(Telephone Number)
- 10. Additional Comments:
Name of Person Contacted Date Time , 7 '
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i RP/0/A/5000/03 Enclosure 4.3 Page 1 of 4
, EXAMPLE i
WARNING MESSAGE: NUCLEAR FACILITY TO STATE / LOCAL GOVERNMENT instructions: - t
! A. For Sender: ?
- 1. Complete Part I for the initial Warning Message.
- 2. Complete Parts I L li for followup messages.
B. For Receiver: l
- 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 , l 1. This is: Catawba Nuclear Station
- 2. My name is: John Doe, Shift Supervisor
- 3. This message (number 1):
X (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: Fire potentially affecting safety system
~
- 9. The emergency condition: X (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.
~ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
1* l ll RP/0/A/5000/03 Enclusuro 4.3 Page 2 of 4
- 10. We recommend the following protective action:
- I X (a) No protective action is recommended at this time. 1 (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:
X (a) A followup message . (b) No further communications
-- 12. I repeat, this message: APPROVED FOR RELEASE
- s. -
X (a) Reports an actu.11 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.
l
***END OF INITIAL WARNING MESSAGE ***
PART ll
- 1. The type of actual or projected release is: N/A (a) Airborne (b) Waterborne
.. (c) Surface spill (d) Other
- 2. The source and description of the release is: N/A
- 3. N/A (a) Release began /will begin at a.m./p.m. ; time since reactor trip is hours.
N/A (b) The estimated duration of the release is hours.
i RP/0/A/5000/03 f Enclosure 4.3 ! Page 3 of 4 ; 1 Dose projection base data:
~
- 4. i Radiological release: N/A curies, or cu ries /sec.
*I
-Windspeed: 5 mph l Wind direction: From 180' Stability class: D ( A,B,C,D, E, F, or G)
Release height: N/A Ft. Dose conversion factor: N/A R/hr/Ci/m' (whole body) N/A R/hr/Ci/m' (Child Thyroid) Precipitation: 0 Temperature at the site: 72*F
- 5. Dose projections: N/A *
- Dose Commitment
- Whole Body
~
(Chil.d Thyroid) , I Distance - Rem / hour Rem /6our of Tnhalation Site boundarv . . 2 miles 5 miles 3 10 miles
- Projected Integrated Dose in Rem
- f
; Distance Whole Body Child Thyroid
! Site bound:ry 2 miles 5 miles 10 miles
- 6. Field measurement of dose rate or contamination (if available): N/A
- 7. Emergency actions underway at the facility include: Extinguised the _ _ _
fire l~ 1
- 8. Onsite support needed from offsite organizations: None l - 9. Plant status:
(a) Reactor is: not tripped / tripped (b) Plant is at: 100% power / hot shutdown / cold shutdown / cooling down l (c) Prognosis is: sta ble/ imp rov i ng/deg radi n g/u n known 9
. - . . - . - - , - - - - . - - ,-.-nu . . - - - - . , . - - - - - - - - - - . - - - . . . - - - , - , , , - - - . - , , ,--.,..-, . , - - - - - - - - - - - -
i! 1 I i RP/0/A/5000/03 Enclosure 4.3 <; Page 4 of 4 II i
- 10. I repeat, this message: APPROVED FOR RELEASE X (a) Reports an actual emergency.
(Emerg. Coord. Time) l (b)g) is an exercise message. l
- 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 procedure. (Receivers) 1, (name) (title) (date) (time) (warning point) 2. (name) . . . (title) , . - (date) (time) (warning point) L
\ 3.
(name) (title)
- l (date) (time) (warning point) 4.
(name) (title) I (date) (time) (warning point)
- 5. '
(name) (title) (date) (time) (warning point) 6. l (name) (title) l - , (date) (time) (warning point) 7. (name) (title) i - (date) (time) (warning point)
i t 4
! l Form 34731 (10-81) '
i (Formerly EPO 10021) DUKE POWER COMPANY (1) ID No: RP/0/A/5000/04 I PROCEDURE PREPARATION Change (s) 2 to
' PROCESS RECORD 3 Incorporated (2) STATION: CATAWBA (3) PROCEDURE TITLE: SITE ARTA FMFRF7MPV (4) PREPARED BY: Mike Bolch DATE: An cr . tg_ toma (5) REVIEWED BY: /b M M e DATE: P/Jo/h*'/
Cross-Disciplinary Review Ly: L h . - N/R: I'AI" EY l(6) TEMPORARY APPROVAL.-(IF NECESSARY):' By: (SRO) Date: 3, k.- By: _ Date: (7) APPROVED BY: 's - Date: "tf)Al __ (8) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: \ l
-, ., , , . _ . - - - . . - - - - , - a, , - - - , - - - . . . + . . , - . , . - , - - . - - , n
y
-1 1 \
l RP/0/A/5000/04 DUKE POWER COMPANY
' CATAWBA NUCLEAR STATION .I SITE AREA EMERGENCY I
h I i 1.0 SYMPTOMS i i !
! 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.
2.0 IMMEDI ATE ACTIONS 2.1 Make initial notifications to individuals and organizations. l 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 and 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. See RP/0/B/5000/13 for NRC Notification. NOTE: The State and County notification must be made within 15 minutes of declaration of the emergency. 2.1.3 Advise station personnel to activate TSC and OSC. ! 2.1.4 Advise the Nuclear Production Duty Engineer to 4 activate the CMC. 2.2 Protective Action Offsite 2.2.1 Recommend to Offsite Agencies that the Alerting Sirens be l sounded and that the EBS be activated to inform the public , I of a potential for later protective actions. 2.3 Protective Action Onsite 2.3.1 Conduct a Site Assembly, see RP/0/A/5000/10. l l w , - < - , . , ---,--,-,-r----,-,- . - v.,- -- - , -an .
-n n -,-- .m-,--,- , ,-- - , ,,,- - - , --,,
Y I RP/0/A/5000/04
. Page 2 of 3 l ! t. '~ '
3.0 SUBSEOUENT ACTIONS 3.1 Accid Assessment: !
! 3.1.1 Dispatch field monitoring teams with associated communications equipment, see HP/0/B/1009/04 3.2 Give follow-up message to offsite agencies listed on 4.1.3 i 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 L ll of Warning Message Form as applicable. Mark all spaces "N/A" when rformation js "Not Apolicable" .*
- I and mark ~Later" whdn 'information is' not ' currently available. . .
3.3 Follow-up 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 available, for Operations personnel. 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.
%e
)
l I l
li l. RP/0/A/5000/04 Page 3 of 3 l l' 3.3.2 If actual release of radioactive material will result in a projected dose to the population of: Whole dy Thyroid Recommendation I <1 Rem <5 Rem No Protective Action is Required. 1 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. ' NOTE Monitor environmental radiation levels to verify and adjust recommendations as necessary. i
. Follow-up Protective Actions On-site.
3.4 - 3.4.1 Consider evacuation of non-essential station personnel, (7, see RP/0/A/5000/10. Q.- 3.5 Augment shift resources to assess and respond to the emergency . situation as needed. 3.6 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. 3.7 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 or by I phone if necessary, followed by written summary within 8 hours. ! 4.0 ENCLOSURES 4.1 Telephone Notification List . 4 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
, _ . - - - - - - , , e- -. , y, , - - . . - - - - . - - , - - - . . - . -.m e.- , ,-,,_,,,,,-..---,,,,-------,..-,,.% .
1 RP/0/A/5000/04 Enclosure 4.1 l Page 1 of 2 TELEPHONE NOTIFICATION LIST l 4.1.1 CNS Emercency Personnel Initial
- 1. Operations Duty En inear - Plant Page P L T Pager A: See Current Operations Work List for Home Phone Number.
- 2. Station Man er - J. W. Hampton Offic ",
Home ist Alternate - C. W. Graves e
. 2nd Alternate - J. W. Cox *
- o e i ( 3rd Alternate - G. T. Smith o e 4th Alternat - A. R. Franklin Office Home s ,
i 3. License & Projects Engineer - C. L. Hartzell e 1st Alternate - M. E. Bolch oe s , 2nd Alternate - P. G. LeRoy
~
4.1.2 Nuclear Production Dut i P & T Pag l- *** USE ENCLOSURE ._ { l
~ --
s RP/0/A/5000/04 Enclosure 4.1 Page 2 of 2 e 4.1.3 State r, County Warning Points (Within 15 minutes)
. (
- 1. N.C. State, R - .
P: l A:
*** U ENCLOSURE 4.3 ***
- 2. S.C. State, Columbia '
P: 7:30 a.m. - 5:00 p.m. Weekdays A: Afterhours, Week-ends r, Holidays
*** U S OSU RE 4.3 ***
- 3. Mecklenburg County A:
Back-up: Emergency Radio, Code:
*** U S E EN C LOS U R E 4.3 ***
- 4. York Count /
P: A: Back-up: mergency Radio, Code:
*** USE ENCLOSU RE 4.3 *** '
- 5. Gaston County -
P: l ~ A: l (' Back-up: mergency Radio, Ccde
*** U S E EN C LOS U R E 4.3 *** .
4.1.4 NRC Operations Center, Bethesda Md. (RP/0/B/5000/13) P: phone) m 6._ .
RP/0/A/5000/04 , Enclosure 4.3 Page 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 r,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
- 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 (b) Alert X (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 l radioactive materials from the plant. l
( (b) Involves the potential for a release, i but no release is occurring. (c) Involves a release of radioactive l material. l
RP/0/ A/5000/04 Enclosure 4.3 Page 1 of 4 EXAMPLE WARNING MESSAGE: NUCLEAR FACILITY TO STATE /LO. CAL GOVERNMENT instructions: h A. For Sender: I
- 1. Complete Part I for the Initial Warning Message.
- 2. Complete Parts I t,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: PARTI,
. 1.. This is: Catawba Nuclear Station . .
- 2. My name is: John Doe, Shift Supervisor
- 3. This message (number 1):
X (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 f acility)
- 6. The class of the emergency is: (a) Notification of Unusual Event (b) Alert X (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: Transient requiring operation of shutdown system with failure to trip.
- 9. The emergency condition: X (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.
q ,
! RP/0/A/5000/04 l-Enclosure 4.3 Page 2 of 4 l
i-
- 10. We recommend the following protective action: !
l (a) No protective action is recommended at this time. (b) People living in zones. remain indoors with the doors and windows closed. , i i (c) People in zones evacuate their i homes and businesses. i (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.
X (f) Other recommendations: Activate offsite notification system r, EBS to inform public
- 11. There will be:
X (a) A follow-up message . Ap' proved for Rdlea'se (b) No further communications
- 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 FROCEDURE FOR AN INCIDENT AT A NUCLEAR FACILITY.
***END OF INITIAL WARNING MESSAGE ***
PART ll
- 1. The type of actual or projected release is: N/A (a) Airborne (b) Waterborne Surface spill
'~~
(c) j (d) Other
- 2. The source and description of the release is: N/A l 3. N/A (a) Release began /will begin at a.m./p.m. ; time since l
reactor trip is 1/2 hours. ( l N/A (b) The estimated duration of the release is hours. l l
T ~ iE i 4 RP/0/A/5000/04 Enclosure 4.3 Page 3 of 4
- 4. Dose projection base data:
Radiological release: N/A curies, or curies /sec. l Windspeed: 5 mph Wind direction: From 180' Stability class: D ( A, B,C,D,E,F, or G) Release height: N/A Ft. Ocse conversion factor: N/A R/hr/Ci/m3 (whole' body) N/A R/hr/Ci/m' (Child Thyroid) Precipitation: 0 Temperature at the site: 72*F
- 5. Dose projections: N/A .
- Dose Commitment
- Whole Body (Child Thyrcid) ,
Distance Rem / hour of inhalation
. Rem / hour .
Site boundary 2 miles g 5 miles ( 10 miles
- Projected Integrated Dose in Rom
- Distance Whole Body Child Thyroid Site boundary
_ 2 miles 5 miles 10 miles
- 6. Field measurement of dose rate or contamination (if available): Later l 7. Emergency actions underway at the facility include: Replacing breaker
- 8. Onsite support needed from offsite organizations: None 1
~ 1
- 9. Plant status- '
l l l (a) Reactor is: not tripped / tripped j
. 1
, (b) Plant is at: 0 % power / hot shutdown / cold shutdown / cooling down l (c) Prognosis is: sta ble/ imp rovi n g/deg ra di n g/u n k n own
i j RP/0/A/5000/04 i Enclosure 4 3 Page 4 of 4 l '
- 10. I repeat, this message:
Approved for Release X (a) Reports an actual emergency. e (b)5 :s an exercise message. Emers. Coord. Time
- 11. Do you have any questions?
***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) (titte) (date) (time) (warning point) - i 2. (name) (title) . .- .- - (date) (time) (warning point) , e u 3. (name) (title) (date) (time) (warning point) 4. (name) (title) (date) (time) (warning point) 5. (name) (title) (date) _( time) (warning point) . ! (name) (title)
~
(date) (time) (warning point) , l l 7. ! (name) (title) l (date) (time) (warning point) _-- . _ . . . . _ . . . . _ . . . _ - . . _ . _ - _ ~ .- __
i l i
~ RP/0/A/5000/04 pm0TE kCTION REC 0hadEN0ATION SITE AREA DERGENCY FW CHART Page 1 of 1 ,
- (
Y a- esNe reeenumendations resguired Is me - : _i stesoffled "UNWSUAi. svesT"ep'ALgtT"7 - Rememunend that people en the g i -m
.5 k io m se <Pz be made aware of the situation,
- 2. Condwet a Site Assembly, l j
le me asnergency esessefted " SITE AngA EnERGENCY*7 Av fee e
- 3. Consider a Presaut. Eves. of t nest-essentief station pereennel.
l I*- -T__^ 6e a h 5" % um an G EieC Y" l , Mas med sentrol "2 nu. R. . of the plant been test! - kPressut. Eves i l 1. Inunediately reesmunord that people in the 2 mi. R. and 5 sei. DW seek shelter indeers i
- 2. Evesuete non eesention station personnel. 3. Follow up with a .- __ . ; .date l bened on en estensive evaluation of the two areas listed below. ;
1 I e . 3 i I P
't Core heeft Analysis le Field beenitoring Team l
- 1. . Evetvote.: e Doester, Gore,,
i . i *
. . Deite Availabief. . .
- b. NC System
""g No Yes 4
l
- c. Centeenseent .
Integrity ' Campere protested OW deses and A8y,g
- 2. Campers with the following field snessurennents with EPA PAG's C' (see 3.3.21.
reeenumeneations whsre significant . o a rolesses from eenteinsnont are . Campero the reeenunenestions eevoteced not yet taking plese: f t from these snelyse and detenenne the most appropesete. If, dose proiestmens or field nesseuressente are not availabie, deteremone settene beoed solely on eere meet enetys6s. 1. Are large amounts of Pission I Produets in Centsinment? (* CAP) 1 M SL Reesmunene shelter fee these eres h ',' R d where ovesuetion sonnet be esm- I "I'
- before plume arrival. f ,, ,
- 11. to senteenment failure eausunent? I
+ QR ?r _:- u " ;;7 I
@ C$L e
Pressut. eyesw.
- l ' to 5 mi. R. and
' I I se enes e en. :. amassa- sa se sensu en ,sena.Laemaa 10 sei. OW. .
1
._. sommuse namese es aman emmas is an es. m 1_
- me. aussene t e sense namesen. !
. eses & des stone aumssteaseos tasedese. emesse enhees e flaa! ^
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. . . e - e e emm .i
- u. .,
am.es. u.mme _a- ,- u.
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I-1 assammee .esens eseammans passe asvavah taan.)
- w asema emessa ses pues.
i j . -r , . i j 3. se teeman ams seen d'a'- poemens as tasmasamme se ad
.. ma - - ===. m ,
,, . no e ;
- t. es..e . ras a.e.e.- .
,, s
- 4. La eMa e "peff" es se&ammet 4 f. See ear summunness, sumumans amassereas fee ens --
F--*= La ene pasma ammense es ese - .
- 8. pausear sensasse een pasmassaan ademsens te amr esamma
-- toussoas paamm sammass.
Mi Ut est JUUUt Uw CATAWBA NUCLEAR STATION Enclosura 4.5 . l pegs 1 of J, I 10-MILE EMERGENCY PLANNING ZONE (EPZ) MAP [
- -m- !
k1 Zone W u . 1 _ \- ama = 52 f f , 5/ O P2 \ l
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7 i L i (~ l Form 34731 (1041) (Formerly SPD 10021)
! DUKE POWER COMPANY (1) ID Not RP/0/A/5000/05
! PROCEDURE PREPARATION Change (s) 2 to I PROCESS RECORD 3 Incorporated (2) STATION: CATAWBA (3) PROCEDURE TITLE: GENERAL EMERGENCY (4) PREPARED BY: wik. hirh DATE: Aug. 16, 1984 (5) REVIEWED BY: ,284 Y d[w DATE: 7!JO/#Y Cross-Disciplinary Review By: h N/R: F 4/+Y
-(6) TEMPORARY APPROVAL (IF NECESSARY):-
7 By: (SRO) Date:
\ ~
By: Date: (7) APPROVED BY: P- Date: @ L1 (8) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date I e l i l l l l
T i i RP/0/A/5000/05 DUKE POWER COMPANY CATAWBA NUCLEAR STATION GENERAL EMERGENCY l 1 l I 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 IMMEDI ATE ACTIONS 2.1 Make initial notific'ations 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 and TSC, ensure that all used forms are returned to the bac= of. the , notebook. - 2.1.2 Notifications shall be as the order of Enclosure 4.1 indicates. See RP/0/B/5000/13 for NRC Notification. NOTE: The State and County notification must be made within 15 minutes of declaration of the emergency. 2.1.3 Advise station personnel to activate TSC and OSC. 2.1.4 Advise the Nuclear Production Duty Engineer to activate the CMC. 2.2 Protective Actions Offsite 4 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. 2.3 Protective Action Onsite
~
j 2.3.1 Conduct a Site Assembly, see RP/0/A/5000/10. i 2.3.2 Evacuate non-essential personnel to the Evacuation 4 Relocation Centers, see RP/0/A/5000/10. l
y . l l s 1
~
.RP/0/A/5000/05 l Page 2 of 3 s
l' , i ' 3.0 SUBSEOUENT ACTIONS . c j 3.1 Accident Assessment: s
! 3.1.1 f Dispatch field monitoring teams with associated
- l con.munications equipment, see HP/0/B/1009/04.
3.2 Give follow-up messages to offsite agencies listed on 4.1.3 of - Enclosure 4.1, use the following schedule: N
.l 3.2.1 Every half hour until the emergency is closed out. i ,
l or , l If there is any significant change to the situation. 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. .
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, for Operations personnel. 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. 1 s 4
m t l y' j i
c i; i RP/0/A/5000/05 Page 3 of 3 3.3.2 If actual release of radioactive material will result in a projected dose to the population of: Whole Body Thyroid Recommendation I
<1 Rem <5 Rem No Protective Action is Required.
1 to <5 Rem 5 to <25 Rem Recommend seeking shelter and wait for further instruction. Consider ! evacuation particularly for children r, pregnant women. Control access : to affected areas.
>5 Rem ~ >25 Rem Recommend mandatory evacuation of population in the affected areas. t 7
Control access to affected areas. , NOTE-Monitor environmental radiation levels to verify and adjust
- recommendations 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 close out the emergency. ( . 3.6 The Recovery Manager at the Crisis Management Center shall close out e the emergency or recommend reduction of the emergency class by i briefing 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 ,
i
~
4.3 Example Warning Message: Nuclear Facility to State / Local Government 4.4 Protective Action Recommendation Flow Chart . 1 d 4.5 10 Mile Emergency Planning Zone (EPZ) Map l 4 l I s i l l l
l l ! RP/0/A/5000/05 Enclosure 4.1 Page 1 of 2 TELEPH'ONE NOTIFICATION LIST I 4.1.1 CNS Emergency Personnel Initial
- 1. Operations Duty E - Plant Page P L T Pager A: See Current Opera ions Work List for Home Phone Number.
- l
- 2. Station Mana - J. W. Hampton Office
. Home 1st Alternate - C. W. Graves . ~ e 2nd Alternate - J. W. Cox l 0 , . . . . l 3rd Alternate - G. T. Smith . . .
. O fic l
. 4th Alternata - A. R. Franklin e
- 3. Licensing & P ' cts Engineer - C. L. Hartzell '
Offic Hom 1st Alternate - M. E. Bolch e
- 2nd Alternate - LeRoy
- Offic i Hom 4.1.2
~~
** USE ENCLOSURE 4.2 **
l
RP/0/A/5000/05 Enclosure 4.1 Page 2 of 2 4.1.3 State & County Warning Points (Within 15 minutes)
- 1. N.C. Ralei P:
A:
*** U, ENCLOSURE 4.3 ***
I 2. S.C. State, Columbia P: 7:30 a.m. - 5:00 p.m. Weekdays A: After hours, Weekends & Holidays l
*** U S E EN C LO S U R E 4.3 ***
- 3. Mecklenbur County P:
A: Back-up: mergency Radio, Code
*** USE ENCLOSURE 4.3 ***
- 4. York County -
Back-up: Emergency Radio, Code:
*** U S E EN C LO S U R E 4. 3 ***
.' 5. Gaston Cou -
P: A: Back-up: mergency Radio, Code:
*** U S E EN C LO S U R E 4.3 ***
4.1.4 NRC Operations Center, Bethesda Md. (RP/0/B/5000/13) P: . hone) aw-e 6 s h__ _
q-ii;; LI RP/0/A/5000/05
- i Enclosure 4.2 Page 1 of 1
;' -g b ~
DUKE POWER COMPANY i CATAWBA NUCLEAR STATION
; - 0 NUCLEAR PRODUCTION DUTY ENGINEER .
EMERGENCY MESSAGE FORMAT
- 1. This is at Catawba Nucicar Station.
=; (Name and Title) i 2. This is is not a drill. An Unusual Event i Alert Site Area Emergency l X 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 (; 4. Corrective measures being taken: w
- 5. There have have not 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 and Company Management should be notified.
- 9. I can be reached at for follow-up information.
(Telephone Number) i
~
- 10. Additional Comments:
A 1 1 Name of Person Contacted Date Time ; I 1 I i L '.- l 1
RP/0/A/5000/05 Enclosure 4.3 Page 1 of 4
.. EXAMPLE WARNING MESSAGE: NUCLEAR FACILITY TO STATE / LOCAL GOVERNMENT {
Instructions: li A. For Sender: I
- 1. Complete Part I for the initial Warning Message.
- 2. Complete Parts I t, il for followup messages.
B. For Receiver: l
- 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 ~
- 1. This is:- Catawba Nuclear Station
- 2. My name is: John Doe, Shift Supervisor m.
- 3. This message (number _1_):
X (a) Reports a real emergency. 4 (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 (b) Alert p (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: Large loss of coolant accident with failure of Emergency Core Cooling System
- 9. The emergency condition: X (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.
7 I - RP/0/A/5000/05 Enclosure 4.3 - Page 2 of 4
; 10. We recomrrend the following protective action:
(a) No protective action is recommended at this time. X ( People living in zones A-O + X (5 mi. DW) remain indoors with the doors and windows closed. I (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:
X (a) A followup message , , , ,, (b) No further communications
- 12. I repeat, this message: APPROVED FOR RELEASE s.
X (a) Reports an actual emergency (Emerg. Coord. Time. ) (b) is an exercise message i
- 13. RELAY THIS INFORMATION TO THE PERSONS INDICATED ON YOUR ALERT PROCEDURE FOR AN INCIDENT AT A NUCLEAR FACILITY.
***END OF INITIAL WARNING MESSAGE ***
PART ll
- 1. The type of actual or projected release is: N/A (a) Airborne (b) Waterborne (c) Surface spill (d) Other l- 2. The source and description of the release is: N/A l
- 3. N/A (a) Release began /will begin at a.m./p.m.; time since reactor trip is 1/2 hours.
N/A (b) The estimated duration of the release is hours.
. - - , . _ , _ .~, - _ . ,. . , _ _ . _ , _ _ , _ _ _ . _ _ _ . _ _ _ . , _ _ _ _ _ . . _ . _ , _ , . _ _ _ _ _ _ _ _ _ . . , _ . . _ _ , _ . _ _ _ _ _ , _
= - .
(> i RP/0/A/5000/05 Enclosure 4.3 Page 3 of 4 i- 4. Dose projection base data: Radiological release: N/A curies, or curies /sec. Windspeed: 5 mph . Wind direction: From 180* Stability class: D (A, B,C,D,E, F, or G) Release height: N/A Ft. Dose conversion factor: N/A R/hr/Ci/m' (whole body) N/A R/hr/Ci/m' (Child Thyroid) Precipitation: 0 Temperature at the site: 72*F
- 5. Dose projections: N/A -
- Dose Commitment
- Whole Body *
(Child Thyroid) .
/ Distance Rem / hour' '
- Rem 7hBur of iWhalation
. . Site boundary . .
2 miles i 5 miles l 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): Later
- 7. Emergency actions underway at the facility include: Cooling down primary system to depressurize
- 8. Onsite support needed from offsite organizations: None
- 9. Plant status:
(a) Reactor is: not tripped /tripoed > ^ (b) Plant is at: 0 % power / hot shutdown / cold shutdown /coolino down : (c) Prognosis is: sta ble/imo rov i n g/deg ra di n g/ u n k now n
i. RP/0/A/5000/05 i Enclosure 4.3 Page 4 of 4
- 10. I repeat, this message:
x (a). Reports an actual emergency. t .. ( ls an exercise message. APPROVED FOR RELEASE
- 11. Do you have any questions?
(Emere. 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 poirif - 2. (name) , , (title) , , (date) (time) (warning point) t. v. 3. (name) (title) (date) (time) (warning point) 4. (name) (title) (date) (time) (warning point) 5. (name) (title) (date) (time) (warning point)
'6.
l (name) (title)
, (date) (time) (warning point) 7.
l (name) (title) l (date) (time) (warning point)
I swCt.osuRE 4.4 RP/0/A/5000/05 PROTECTIVE ACTION RECQtWENDATION GENERAL EMERGENCY FW CMART p,p i g g F M: ndations required le te -- ny senselflod " UNUSUAL gV . - -
- pse EVENT"eP M T*7 Recommend that posele en the g
4 = 4 to mie EPz be made aw.re of ths situateen. Conduct a Site Assembly. I Is me emergency stessefted " SITE Y a 2.
- 3. Consider a Precaut. Evoc. of AREA EMERGENCY"? non-essential station personnel.
1 IP - - T.u- _ 6e a dieERAL EBERGEieCY"] Mas physiset eentrei V ' '2 me . R. l of the plant been leet? -- Precaut. Evac . 4P
- 1. Inerediately recommend that people in the 2 me. R. and 5 me. DW seek shelter indoors
- 2. Evacuata non-essential station personnel. 3. Fellow-up with a . - - r.dation based on an entensive evaluat6on of the two areas listed below: .
1P it Core Meit Analysis is Field Monstering Team l i., Eva6usto: a. Beester Care . .* Da'ta Availablef. .
* *b. NC Systent "g
No Yes
- c. Containment Integrity r-
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Compare protected DW doses and efG Compere with the following i
' 2.
j field measurements with EPA PAG's recommonestions where significant (see 3.3.21. reiseses from containst.ent are a
- i. ir not yet taking place:
Commere the resemmendations eeve6eped irem these analyse and determine the meet a n r w eiete. 1.t den prosections or fiese _ measurements are not available. determene 1. Are large amounts of Fiss6on actions based sedely on core meet er.stysse. Products in Containment? (* GAP)
& 55 l
saut. evacu. Roosnesond shelter for these a # 2 m. . and j where evesuetion cannet be sem- - 5 =i
- befe,e piume omvei. f ,,
- 11. is sentainment failure enemnent? l OR Releesa underwav7 h 05 Presaut evasu.
9 to 5 mi. R. and
- se se name see renessesus 10 mi. DW.
me enes es sne emessaen amasam -
===mse namesa se senseesemas as one es. augma use assas ennu momew.
e esser namesen, tsmesse. ins eensas e f amna ---=== emesseer sense manasses t
- 8. Os ses _ ene poetas tg esammassas sammes is sewasses tedere essnessas plumn arrival. (Caware seammessas same .
~
eessasse werene --. - ^ pies eartve& stas.3
=ess su paa.s.
- 3. p mme en monassa .e a-me
- 3. De betaen ens rees esme&saams peamms en laeassame se ggg ,,,,,g g,,,
*****' 59 - oewnwind
,, rm anse essassses sanats e.esmessant g . Radius
' s. cas :aseec.ne, ,--- seems see . sat
- 4. La enas e 'Teff* es re&ammet
- t. Poe any essanestem. ensammme seatsertas fee see popeasstas -
ta ene pheme aspesare We ese -
- 8. PTemps&f sensames sem pupn&astas attested by est steumn e; ---- - te&assans p&ame paneses.
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i \ MlW At DUUUo v3 CATAWBA NUCLEAR STATION Enclosure 4.5 ,' 10-MILE DERGENCY PLANNING ZONE Page 1 of 1 ~ ~ (EP2) MAP
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g. F L - ' 4 Form 34731 (10-81) (Formerly SPD 10021) DUKE POk'ER COMPANY (1) ID No: RP/0/A/5000/06 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD 1 Incorporated i (2) STATION: CATAk'BA (3) PROCEDURE TITLE: NATURAL DISASTER (4) PREPARED BY: Mike Bolch DATE: Aug. 16, 1984 . (5) REVIE1JED BY: A do J M d . EATE: f/J.0/FY Cross-Disciplinary Review By: ( N/R: f"3/~N
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(6) TEMPORARY APPROVAL (IF NECESSARY):- j . By: (SRO) Date: i (~' By: Date: * (7) APPROVED BY: W- J Date: @ l (! t / / (8) MISCELLANEOUS: Reviewed / Approved By: Date: t Reviewed / Approved By: Date: , .- l t J i I
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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 Initial /N/A 2.1 Shutdown Reactor (s) , 2.1.1 Should conditions develop which jeopardise the safe operation of the reacter, take the unit (s) to hot shutdown '
. . .. . ,.- 4 DESIGN BASIS CONDITIONS~
Sustained winds High Lake Level Low Lake Level ( > 95 mph * > 593.5 Ft MSL < 550.4 Ft MSL NOTE: Seiche is same as High Lake Level.
- Wind speed information>60 mph must be obtained from NWS 2.2 Notification 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 Systsm when appropriate. 3.0 SUBSEQUENT ACTIONS - l '~ 3.1 Contact the National Weather Service at 704-399-6000 to obtain the latest forecast /information. . 3.2 If ecnditions permit, move the station vehicles inside the Turbine Building. 3.3 Close or check closed all truck and personnel access doors on the l Auxiliary and Turbine Buildings and Warehouse. I
RP/0/A/5000/06 Page 2 of 2 s i Initials /N/A
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.3.4 Minimize or stop all bandling 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, 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
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Form 34731 (10-81) . (Formerly SPD 10021) j DUKE P0k'ER COMPANY (1) ID Not RP/0/A/9000/07 PROCEDURE PREPARATION Change (s) I to PROCESS RECORD 2 Incorporated (2) STATION: CATAWBA (3) PROCEDURE TITLE: EARTMCUAKE (4) PREPARED BY: Mike Bolch DATE: Aua. 16. 1984 (5) REVIEWED BY: M2 d -r M db DATE: P/20/F'/ Cross-Disciplinary Review By: L b N/R: TWIY (6) TEMPORARY APPROVAL (IF NECESSARY):- By: - (SRO) Date: (' By: . Dates (7) APPROVED BY: f.u - Date 9!ll/!h , (d) MISCELLANEOUS: ! Reviewed / Approved By: Date Reviewed / Approved By: Dater j f ) l
1 i
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RP/0/A/5000/07 DUKE POWER COMPANY CATAWBA NUCLEAR STATION I EARTHOUAKE i 1.0 SYMPTOMS 1.1 Seismic event alarm SMA-3 on IMC8 1.2 OBE Exceeded alarm on AD-4 (B-8) 1.3 Light on Peak Shock Annunciator PSA-1575 on IMC8 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 ICE to remove the magnetic tapes from the SMA-3 recorder to evaluate and verify the magnitude of the earthquake in accordance with IP/0/8/3341/03. 2.1.3 If the earthquake intensity is >.15g horizontal and/or
>.1g 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. 3.1.2 Seismic verification may be obtained by calling the National Earthquake Information Service at (303) 236-1500. 3.2 Perform a survey of the plant structures and equipment to determine the extent of damage, if any, and re::ord in the Shift Supervisor's (, Log.
il
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l RP/0/A/5000/07 Page 2 of 2 5 3.2.1 Notify personnel from ILE and Mechanical Maintenance to assist Operations in the evaluation of earthquake damage if necessary. 3.2.2 Notify Health Physics personnel to survey the Reactor, 3 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 telephons. (TS 6.9.1.12.g) 3.4.2 If the earthquake was determined to be <OBE but recorded on station seismic instrumentation, the LLP Engineer or i delegate shall make a written report to the NRC (Reg *ional * " j . , Office) within 10 days. (TS 4.3.3.4'.2)*
- 4.0 ENCLOSURES l..
4.1 Locations of Seismic Instruments and Procedure Numbers i u l i t k ,
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- l* RP/0/A/5000/07 Enclosure 4.1
!- DUKE POWER COMPANY l, ( CATAWBA NUCLEAR STATION SEISMIC MONITORING INSTRUMENTS Type Instrument e Name Location Procedure #
'! P 1MIMT-5010 Peak Accelerograph CA Pipe to S/G 1D IP/0/B/3341/05
=t P 1MIMT-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/B/3341/05 A (1) 1MIMT-5040 Spectrum Recorder RB Basement O' IP/0/B/3341/04 i- 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 A 1MIMT-5070 Strong Motion RB Basement O' IP/0/B/3341/03 Accelerograph
, A. . ; 1MIMT-5080 Strong Motion . Ann'ulus 619 f O'-
IP/ orb /3341/03
. . Accelerograph . . ! A IMIMT-5090 Starter Unit for RB Basement O' IP/0/B/3341/01 1
(c. SMA-3 P- Passive (historical record) A - Active (remote read-out) Note 1: Also provides input to Peak Shock Annunciator (PSA1575) Note 2: Providos indication of OBE Exceeded on AD4 (B-8) in Control Room j Seismic Remote Readouts l SMA-3 Triaxial Time-History Accelerographs (Strong Motion Accelerograph System) - in standby until 0.01g acceleration starts magnetic tape recorder unit - back up power supply from built in battery. l SMP-1 Magnetic Tape Playback Unit - plays back one of three channels l at a time onto strip chart for data evaluation.
~
- PSA-1575 Peak Shock Annunciator - gives visual warning that >70% OBE (amber light) or >100% OBE (red light) has been exceeded at certain frequencies (2H to 25.4 H )
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T l Form 34731 (1041) (Formerly SPD.10021) DUKE POWER COMPANY (1) ID No: RP/0/A/5000/08 PROCEDURE PREPARATION Changs(s) O to PROCESS RECORD 1 Incorporated (2) STATION: CATAWBA
- (3) PROCEDURE TITLE: RELEASE OF T0XIC OR FIAMLE GAS i
(4) PREPARED BY: Mike Bolch DATE: Aug. 16, 1984 (5) REVIEWED BY: 8.e.k 3 M d[w DATE: P/3d/fY Cross-Disciplinary Review By l h N/R: 1-1/-U
' ' " " ~
(6) IEMPORARY' APPROVAL (IF NECESSARY):
,. By: (SRO) Date:
By: _ Date: (7) APPROVED BY: - Date: 2/!M (8) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: i O O
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. l RP/0/A/5000/08 DUKE POWER COMPANY CATAWBA NUCLEAR STATION RELEASE OF TOXIC OR FLAMMABLE GAS 1.0 SYMPTOMS 1.1 This condition exists when toxic or flammable gases released nearsite or onsite, (verified by analysis if deemed necessary) present a hazard to station personnel or property. 2.0 IMMEDI ATE ACTIONS 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 SUBSEQUENT ACTIONS .
. 3.1 The Shift Supervisor will request the Station Safety Section to .
evaluate the hazardous condition. (.-. 4 3.2 The Shift Supervisor will take appropriate actions to ensure the safety of all persons and property in the potentially affected areas. 3.2.1 Initiate a Site Assembly and/or Evacuation if necessary. 3.2.2 Notify outside services per Enclosure 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 I i
' - 3 I
'6
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i . RP/0/A/5000/08 Enclosure 4.1
/ DUKE POWER COMPANY CATAWBA NUCLEAR STATION
~
I EMERGENCY TELEPHONE NUMBERS Ambulance & Medical Piedmont Medical Center . . . . . . . (803) 329-1111 Rescue Squad Clover Rescue Squad . . . . . . . . . (803) 222-9494 Fire Department Bethel Volunteer Fire Department . . . (803) 631-4112 1 8 0
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l Form 34731 (10-81) ' (I"ormerly SPD 1002 Il DUKE POWER COMPANY (1) ID No: RP/0/A/5000/09 PROCEDURE PREPARATION Change (s) o go PROCESS RECORD 1 Incorporated (2) STATION: CATAWBA (3) PROCEDURE TITLE: COLLISION / EXPLOSION (4) PREPARED BY: Mike Bolch DATE: Aun. 16. 1984 (5) REVIEWED BY: [./ b _ M d d DATE: f/_?oI79 Cross-Disciplinary Review By: t h N/R: IO/
" ~
'*(6) TEMPORARYAPPROVAL'(IF'NECESSARI):'
By: (SRO) Date: By: Date: (7) APPROVED BY: 8 - Date: if / (8) MISCELLANEOUS: Reviewed / Approved By: Date: ( Reviewed / Approved By: Date: 1 I l-
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1 RP/0/A/5000/09 DUKE POWER COMPANY CATAWBA NUCLEAR STATION COLLISION / EXPLOSION 1.0 SYMPTOMS 1.1 Observance of the following incident onsite or near site: I 1.1.1 Aircraft crash or threatening aircraft activity , j 1.1.2 Train derailment - 1.1.3 Waterborne collision 1.1.4 Missile impact ,
- 1.1.5 Explosion 1.1.6 incident jeopardizing vital structures or safe shutdown equipment
!' ', 2.0 IMMEDI ATE _ ACTIONS , , k.. 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 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 E stinguish 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 Security for any event. 3.7 Notify applicable outside agencies as necessary. (Enclosure 4.1) t 4.0 ENCLOSURES 4.1 Emergency Telephone Numbers
- These actions may be performed concurrently as appropriate l
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RP/0/A/5000/09 l, Enclosure 4.1 DUKE POWER COMPANY CATAWBA NUCLEAR STATION EMERGENCY TELEPHONE NUMBERS Ambulance & Medical
- Piedmont Medical Center . . . ... .. (803) 329-1111 Rescue Squad
- Clover Rescue Squad . . . . . . . . . . (803) 222-9494
*Sccurity will normally initiate the call for outside medical assistance.
Fire Department Bethel Volunteer Fire Department . . . (803) 631-4112 Federal Aviation Administration - 24 Hr. Number ... .. . .. (704) 399-1041 Duke Power Company Railroad Contact - Wayne Hallman .. . .. . 78-2345 Days Home .... ... . . 1 l i
i s' Form 34731 (10-81) (Formerly SPD 10021) DUKE POWER COMPANY (1) ID No: RP/0/A/5000/10 PROCEDURE PREPARATION Change (s) I to PROCESS RECORD 2 Incorporated (2) STATION: CATAWBA (3) PROCEDURE TITLE: CONDUCTING A SITE ASSEMBLY or EVACUATION (4) PREPARED BY: Mike Bolch DATg Aug. 16, 1984 (5) REVIEWED BY: Ntd M M DATE: P/20 /FV Cross-Disciplinary Review By: t_h -
) N/R E Ol~
-(6) TEMPORARY APPROVAL (IP NECESSARY): '
By: (SRO) Dates , By: Dates . (7) APPROVED BY: U- Date: T5 //k (8) MISCELLANEOUS: Reviewed / Approved By: Dater ! Reviewed / Approved By: Dates
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, t RP/0/A/5000/10 DUKE POWER COMPANY CATAWBA NUCLEAR STATION CONDUCTING A SITE ASSEMBLY OR EVACUATION
, 1.0 SYMPTOMS 1.1 A Site Assembly 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 i j 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 . i 1.1.4 Auxiliary Building Radiation Levels
. . 1.1.4.1 Radiation levels .in unrest'ricted amas of'> 2'
- mr/hr.
! 1.1.4.2 Airborne Radiation Levels > 1 x 106 cpm by i EMF-41. l 4 1.2 A Site Evacuation is an occurance that necesultates the evacuation ! of non-essential personnel for reasons of safety, 1.2.1 Si'.e 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 evacuation. , l 2.0 IMMEDI ATE ACTIONS l._ 2.1 Site Assembly l 2.1.1 Contact the Security Shift Lieutenant or Clerk at extension 2393 to inform ,them that a Site Assembly is i being initiated. 2.1.2 The Shift Supervisor or delegate shall sound a twenty ; second blast of the Site Assembly alarm and make the
- following announcement on the plant page system
- x.
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I RP/0/A/5000/10 l Page 2 of 3 "This is the Shift Supervisor, this is a Site Assembly. This is a Site Assembly. There is/are what . In/at Where All personnel and visitors report to their assembly points (parking lot if a bomb threat)." NOTE: Assembly points are listed in Station Directive 3.0.7. 2.1.2 Repeat 2.1.1 in full. 2.2 Site Evacuation (Must be proceeded by a Site Assembly) 2.2.1 Choosing an Evacuation-Relocation $6te 2.2.1.1 Contact Health Physics Duty Supervisor for assistance in assessing the radiological hazard ! associated with the evacuation. . Plant peger no. 63-214 or 215. 2.2.1.2 Site Alpha (Transmission Lint Maintenance *
! Warehouse, Newport, S.C.) is located 4.8 miles SW of the plant.
k'- Site Bravo ( Allen Steam Station, Belmont, N.C.) 2.2.1.3 is located 10 miles NNE of the plant. , 2.2.1.4 Choose the site most opposite the direction that the wind may be carrying any expected ! release. See Enclosure 4.1. < ) 2.2.2 Contact the Evacuation Coordinator listed in Station / ! Directive 3.8.4, Enclosure 1, to inform him that an : Evacuation is being initiated. The Key to Site Alpha is kept at the Security Office in the PAP. + 2.2.3 The Shift Supervisor or delegate shall sound a twenty second blast of the Site Evacuation alarm and nake the following announcement on the plant page system:
"This is the Shift Supervisor, this is a Site F.vacuation.
-- This is a Site Evacuation. All non essential personnel proceed to Site Alpha / Bravo .
2.2.4 Repeat 2.2.3 in full. 3.0 SUBSEOUENT ACTIONS + 3.1 Notification , ! \- 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.) > 1 s 1 - i
I RP/0/A/5000/10 Page 3 of 3
-I A. York County Sheriff 327-2021 B. 5.C. Highway Patrol 385-3107 3.1.2 Notify the chosen Evacuation-Relocation Site of the expected arrival of personnel.
l A. Alpha - 373-7300 Transmission t.ine Maintenance Warehouse
- 8. 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: l "This is the Shift Supervisor, secure from Site Assembly. . i Secure from Site Assembly." 3.3.2 Repeat 3.3.1 in ful.l. . . . . . .. . . j , L . 3.4 Securing from a Site Evacuation . . 4 ( 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 j
- can return to their work location.
i' 4.0 ENCLOSURI 4.1 Wind Olrection Determination i i r a l l k S e, y yy ,- - ,_
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- T EVACUATION-RELOCATION WIND DETERMINATION RP/0/A/5000/10 Enclosure 4.1 7 Page 1 of 1
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WIND DIRECTION FROM USE THIS SITE 145* to 255' ALPHA 6.c 350* to 360* & 0* to 100* BRAVO NOTE: Wind Direction is always stated in FROM X* a given direction. Example: 180' Wind is From 180* blowing toward 0*. I e l
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Form 34731 (10-81) (Formerly SPD 10021) DUKE POWER COMPANY (1) ID No:RP/0/A/5000/11 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD 1 Incorporated (2) STATION: CATAWBA (3) PROCEDURE TITLE: PROTECTIVE ACTION RECOMMENDATIONS WITHOUT THE OAC (4) PREPARED BY: Mike Bolch DATE: Aug. 16, 1984 , (5) REVIEWED BY: [J a ,Y DATE: f/10/ Cross-Disciplinary Review By: Ck D .N/R: T-3/-IN 1
. , (6) TEMPORARY APPROVAL (IF NECESSARY): , , . . .
By: (SRO) Date:
-g By: .
Date: (7) APPROVED BY: Date: f!2t (8) MISCEIMEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: i O e %
, l I
1 (. RP/0/A/5000/11 DUKE POWER COMPANY CATAWBA NUCLEAR STATION PROTECTIVE ACTION RECOMMENDATIONS i WITHOUT THE OAC 1.0 SYMPTOMS 1.1 LOCA with 1.1.1 EMF-53A or 53B, Containment High Range Radiation Monitor, in alarm CE 1.1.2 EMF-36(L), Unit Vent Gas Monitor, in alarm. 1.2 Dose Assessment Program Nuclear-23 unavailable. - 2.0 IMMEDI ATE ACTIONS
. 2.1 Check Rx Building or Unit Vent Radiation Level as Symptom's In'dicate 2 1.1 Check the Reactor Building radiation level by either N of the following methods:
(; 2.1.1.1 Record EMF-53A and EMF-53B 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 Reactor Building). Record on Enclosure 4.2. 2.1.2 Record EMF-36(L) and EMF-36(H) readings on Enclosure 4.3. 2.2 Perform the following based on radiation levels. 2.2.1 If the Reactor Building radiatin level is 135 R/hr, continue monitoring the Reactor Building radiatin level. 2.2.2 If the Reactor Building radiatin level is > 35 R/hr,
' complete Enclosures 4.1, 4.2 and 4.4.
2.2.3 If EMF-36 (L) is 130,000 cpm, continue monitoring Unit Vent radiatin level. l~
'7 4 If EMF-36(L) is > 30,000 cpm, complete Enclosures 4.1, 4.3
- and 4.4
} } ,
i RP/0/A/5000/11 i Page 2 of 2 f, ( 2.3 Recommendations 2.3.1 Determine Protective Action Recommendations from Step 1 of I Enclosure 4.4.
.; 2.3.2 Determine the affected zone (s) from Step 2 of Enclosure ! 4.4.
I
- l 2.3.3 Always include Zone A-0 in Recommendations.
2.3.4 See RP/0/A/5000/05 (General Emergency) for Recommendation Format. 3.0 SUBSEOUENT 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 . 4.1 Clor.k and Meteorological Data Sheet 4.2 Reactor Building Data - Calculation Sheet 4.3 Unit Vent Data - Calculation Sheet 4.4 Protective Action Recommendation Worksheet 4.5 Limits and Precautions t di e==- D t. l
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l, - l DUKE POWER COMPANY CATAWBA NUCLEAR STATION
! RP/0/A/5000/11
.; ENCLOSURE 4.1
'7 CLOCK AND METEOROLOGICAL DATA SHEET Unit Protective Actions Determined By
- 1. Clock Data Time Now Date Now Time of Reactor Trip Date of Reactor Trip Hours Since Reactor Trip ,
- 2. Meteorological Data (fror. station EEB system er National Weather Service [NWS] at 704-399-6000 if EEB is not available)
Wind Direction - Upper Tower , de ,*ee.s , , . ,, .,
- - - Lower Tower degrees - .
- NWS degrees NOTE: If wind direction is indicated to be > 360* then subtract 360* and proceed.
Wind Speed - Lower Tower mph
- Upper Tower mph
- NWS mph Actual AT - Upper minus Lower Tower 'C Assumed AT - Time now of 1000 to 1600 -0.4*C
- Time now of 1600 to 1000 I
with wind speed > 15 mph -0.1'C with wind speed < 15 mph +1.3*C NOTE: Assumed AT is for use when EEB system is inoperable. AT is not available from NWS. t 6 as
I i DUKE POWER COMPANY
-i CATAWBA NUCLEAR STATION j RP/0/A/5000/11 . [ ,, -.. ENCLOSURE 4.2 l 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 Trio 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 calcula.tions. . , b) HP/0/B/1009/06 R/hr. gr
\~ ? 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 v41ue of 1.
- 5. Go to Enclosure 4.4.
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DUKE POWER COMPANY CATAWBA NUCLEAR STATION RP/0/A/5000/11
. ENCLOSURE 4.3 7
- i UNIT VENT DATA - CALCULATION SHEET
- 1. Unit Vent EMF Readings >
EMF-36(L) = cpm : v
= cpm EMF-36(H) ;
\
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 C_r -- from National Weather Service. NOTE 2: If WS < 1 mph then use s..e value of 1. :
- 4. Go to Enclosure 4.4. f i
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T-I, Page 1 of 2 j. DUKE POWER COMPANY CATAWBA NUCLEAR STATION
- RP/0/A/5000/11 l 4 '
ENCLOSURE 4.4 l . i' PROTECTIVE ACTION RECOMMENDATION WORK SHEET
- 1. Based on WDD 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 i
.. 0-5 Mile Radius Protective Action Recommendations WDD Values '_
AT: < -0.6 < 4.10E6 4.10E6 to 2.00E7 > 2.00E7
-0.6 to -0.5 5 1.10E5 1.10E5 to 5.50E5 > 5.50E5
-0.4 to -0.2 5 3.50E4 3.50E4 to 1.70E5 > 1.70E5
-0.1 to +0.4 5 2.00E4 2.00E4 to 1.00E5 > 1.00E5
+0.5 to +1.2 -< 9.80E3 9.80E3 to 4.90E4 > 4.90E4 .-
> +1.2 < 4.50E3 4.50E3 to 2.20E4 > 2.20E4 r
Consider Protective Action NO ACTION EVACUATION PARTICU- EVACUATE Recommendations LARLY FOR CHILDREN EVERYONE ANO PREGNANT WOMEN Table 1.2 . 5-10 Mile Radius Protective Action Recommendations WDD Values aT: < -0.6 < 2.00E7 2.00E7 to 1.00E8 > 1.00E8
-0.5 to -0.4 5 1.80E6 1.80E6 to 9.20E6 > 9.20E6
-0.4 to -0.2 5 4.10E5 4.10E5 to 2.00E6 > 2.00E6
.. -0.1 to +0.4 5 2.00E5 2.00E5 to 1.00E6 > 1.00E6 7
+0.5 to +1.2 5 7.90E4 7.90E4 to 3.90E5 > 3.90E5
> +1.2 5 2.90E4 2.90E4 to 1.40E5 > 1.40E5 i
Consider Protective Action NO ACTION EVACUATION PARTICU- EVACUATE r Recommendations LARLY FOR CHILDREN EVERYONE AND PREGNANT WOMEN g .,
I l Page 2 of 2 l DUKE POWER COMPANY CATAWBA NUCLEAR STATION !
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' RP/0/A/5000/11 l' ENCLOSURE 4.4
. PROTECTIVE ACTION RECOMMENDATION WORK SHEET j
- 2. Based on wind direction (WD), determine the affected zones from the tables l 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, D-1, E-1 and F-1. B. IF WIND SPEED IS > 5 MPH, SELECT THE AFFECTED ZONES FROM THE TABLES l BELOW AS APPLICABLE. Table 2.1 Table 2.2 0-5 Mile Radius Affected 5-10 Mile Radius Affected . Wind Direction Zones Wind Direction Zones 0.1 - 360 ; A-0 PLUS .. . - O.1* - 22* r C-1, D-1 0.1 - 27 ? C-2, D-2 22* - 73* O C-1, D-1, E-1 27* - 69* ----> C-2, D-2, E-2 b 73* - 108* :0-1, 0-1, E-1, F-1 69* - 95* 0-2, E-2, F-2 108* - 120* r D-1, E-1, F-1 95* - 132* - > D-2,.E-2, F-2, F-3 120* - 159' > E-1, F-1 132* - 144* O E-2, F-2, F-3 159 - 207* A 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* 7 F-2, F-3, A-2 247* - 265* 7 A-1, B-1 201* - 229 - '>F-2, F-3, A-2, B-2 265* - 298* b A-1, B-1, C-1 229' - 249' O F-3, A-2, B-2 298* - 338* = B-1, C-1 249* - 259' ; A-2, A-3, B-2 338* - 360* r 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" 7 B-2, C-2 333* - 360* O B-2, C-2, D-2 -
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Page 1 of 1 DUKE POWER COMPANY CATAWBA NUCLEAR STATION RP/0/A/5000/11 (~_ ENCLOSURE 4.5 LIMITS AND PRECAUTIONS
- 1. This procedure is to be used by Control Room Operations personnel only in the event the Operator Aid Computer is not available to perform the calculation of protective action recommendation and the Technical Support Center is not activated.
NOTE: This procedure is applicable only in the first 10 hours after the Reactor Trip.
- 2. This procedure is conservative in its ability to protect the public in that:
- a. A 45* wide plume is assumed with an additional 22
- on each side of the plume.
- b. Wind determined dose (WDD) has a built in margin of safety.
i
- c. There are three sources of meteorologicyl data:
- 1) EEB System upper and lower towers . .
- 2) National Weather Service at Charlotte Office of National Weather Service
('::s-
. 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/B/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 WD0 value tables used to determine protective action recommendations.
e l 7 -, y, . ---. y -
e 6 Form 34731 (10 81) (Formerly SPD 10021) DUKE POWER COMPANY (1) ID Nc:RP/0/B/5000/13 PROCEDURE PREPARATION Change (s) n to . PROCESS RECORD 1 Incorporated (2) STATION: cATAtini (3) PROCEDURE TITLE: Nuc NntTrTratinv urnnTumm (4) PREPARED BY: Mike Bolch DATE: A,, cr _ 16. t oR ti (5) REVIEVED BY: [/M , 4- d[w . DATE: 7/20/PY Cross-Disciplinary Review By: ) N/R:$"d/
' ' ' ^
- (6) TEMPORARY APPROVAL (IF NECE'SSARY):-
By: (SRO) Date: (.s By: . Date: (7) APPROVED BY: W- Date: 6 #!k (8) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: l~ l
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._ _ ___ __ . _ _ _ _ . _ - _ . _ . . . , _ . 2-
m2 , _ RP/0/B/5000/13 DUKE POWER COMPANY CATAWBA NUCLEAR STATION NRC NOTIFICATION REQUIREMENTS 1.0 SYMPTOMS 1.1 Plant conditions requiring NRC notification in accordance with: 10 CFR50.72,10 CFR20.205,10 CFR20.403, and 10 CFR73.71. For immediate,1 Hour and 4 Hour Notifications. 1.2 See Enclosure 4.1 for determination of appropriate notification requirement. 2.0 IMMEDI ATE ACTIONS 2.1 Complete one of the following enclosures: 2.1.1 Enclosure 4.2 " Checklist for Significant Event Notification" 0.E
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Enclosure'4.3 " Report of Serious Physical " Security Events"
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2.1.2 When reporting from Section 4.1.2.7 of Enclosure 4.1
/
NOTE: No Enclosure for reporting to Region 11 from Section 4.1.1.5 of Enclosure 4.1 2.2 Notify the NRC Operations Center by the following means: 2.2.1 Primary - Emergency Notification System Phone E 2.2.2 Alternate 2.3 Notify the NRC Region 11 Office at f any event listed in Section 4.1.1.5 of Enclosurs 4.1. 3.0 SUBSEQUENT ACTIONS 3.1 Provide follow-up notification as described below: , 3.1.1 Emergency Classes 3.1.1.1 Any further degradation in level of safety of
- the plant including those that require declaration of any Emergency Class, if such a declaration has not been previously made.
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RP/0/B/5000/13 Page 2 of 2
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.. 3.1.1.2 Any change in the Emergency Class oI 3.1.1.3 Termination of the Emergency 3.1.2 Results of ensuing evaluations or assessments of plant conditions 3.'.3 Effectiveness of response or protective measures taken 3.1.4 Information related to plant behavior that is not understood 3.2 Maintain an "Open", continuous, communications channel with the NRC Operations Center, upon request by the NRC. 3.3 Notify the following individuals within 4 hours: NOTE: The requirem'ent for direct notification in this paragraph is for all events NOT INVOLVING the declaration of an EMERGENCY CLASS. For all Emergency Plan notifications the station Licensing & Projects Engineer .is responsible, fo.c .. notifying the NRC Resident inspector. 3.3.1 Licensing r, Projects Engineer P rima ry Alternate C. L. Hart 11 'f P. G. L Office: or
~
Office: Home: Home: 3.3.2 NRC Resident inspector P rima ry Alternate P. H. Skinn P. K. VanDoorn e oe 3.4 Upon completion of this procedure, attach a completed Procedure
- Process Record Form and forward to the Licensing r, Projects Engineer for review prior to submission to Master File.
4.0 ENCLOSURES , l
. 4.1 Events Requiring NRC Notification 4.2 Checklist for Serious Event Notification 4.3 Report of Serious Physical Security Events
i RP/0/B/5000/13 Events Requiring NRC Notification Enclosure 4.1 Page 1 .of 6 4.1.1 Events Requiring "lMMEDI ATE NOTIFICATIONS": Immediateiy after notification to states and counties and not later than one hour after the time the Emergency Class was declared. 4.1.1.1 The declaration of any of the Emergency Classes specified in the Catawba Emergency Plan and 4.1.1.2 Any change from one Emergency Class to another 0L 4.1.1.3 Termination of the Emergency
- 4.1.1.4 For any incident involving byproduct, source or special nuclear material which may have caused or threatens to cause the following:
4.1.1.4.1 Individual, Exposure 3 25 Rem Whole Body t, or 3150 Rem Skin of Whole Body 9I 1375 Rem Extremities 4.1.1.4.2 Release of radioactive material in concentration which if averaged over a 24 hour period would exceed 5,000 times the applicable concentration of the limits specified in 10 CFR 20, Appendix B, Table ll. 4.1.1.4.3 Loss of one working week or more of the operation of any unit. 4.1.1.4.4 Damage to property in excess of S200,000. O
1 RP/0/B/5000/13 Events Requiring NRC Notification Enclosures 4.1 Page 2 of 6 I
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L 4.1.1.5 Notification to NRC Reginal Office, Region ll, Atlanta, GA. (see Step 2.3). Receipt of a package of radioactive materials with: 4.1.1.5.1 >0.01 uCi/100cm loose radioactive inaterial on the external surface
- or 4.1.1.5.2 >200 MR/hr. on external surface or 4.1.1.5.3 >10 MR/hr. at three (3) feet from the external surface 4.1.2 Events Requiring "ONE HOUR REPORTS":
As soon as practical and within one hour of the - occu rrence. 1 ,
- 4.1.2.1 The initiation of any nuclear plant shutdown "
; . . required bv. Technical Spe'cificatiorrs (i.a'. ~
i - Safety Limit Violation) - 4.1.2.2 Any deviation from a plant License Condition or (O' Technical Specification authorized in 10CFR50.54(x) . (Licensee may take reasonable action that departs from a license condition or a technical ' specification in an emergency when this action is - immediately needed to protect the health and safety of the public and no action consistent with license conditions and technical i specifications that can provide adequate or , equivalent protection is immediately apparent.) ; 4.1.2.3 Any event or condition during operation that i results in the condition of the plant, including - the principle safety barriers, being seriously degraded, or results in the plant being: 4.1.2.3.1 in an unanalyzed condition that
._ significantly compromises plant safety.
4.1.2.3.2 in a condition that is outside the design basis of the plant. !- 4.1.2.3.3 in a condition not covered by the plant's operating and emergency j ' i, procedu res. l (- 4.1.2.4 Any event that results or should have resulted in Emergency Core Cooling System (ECCS) l discharge into the reactor coolant system as a result of a valid signal. l
4 RP/0/B/5000/13 , Events Requiring NRC Notification Enclosure 4.1 Page 3 of 6
.f 4.1.2.5 Any event that results in a major loss of I emergency assessment capability, offsite response I capability, or communications capability (e.g.,
significant portion of control. room indication, Emergency Notification System or Offsite Notification System). 4.1.2.6 Any natural phenomenon or other external condition or any event that poses an actual threat to the safety of the plant or significantly hampers site personnel in the performance of
- duties necessary for the safe operation.of the plant, including fires, toxic gas releases or radioactive releases. i
. 4.1.2.7 Safeguard events as determined by Security personnel and Station Management'.
4.1.2.7.1 A trace investigation of a lost or unaccounted for shipment pursuant to 10 - CFR 73.27. 4.1.2.7.2 An attempt (actual or suspected) to ,. commit a theft or' uriia'wful' diversion of Special Nuclear Material. ( , 4.1.2.7.3 Any event which significantly
- threatens or lessens the eff6ctiveness of the physical security system Uncompensated one (1) hour safeguards events
- a. Confirmed Intrusion or Sabotage attempt (explicit threat).
- b. Attempted entry of unauthorized Incendiary devices into Protected A rea .
- c. Bomp Threat / Extortion Threat (Explicit Threat, includes entry into vital area (s)).
- d. Mass Demonstration, Picketing, [
Civil Disturbance (Explicit ;
- Threat, Event occurs inside the Protected Area).
I e. Loss of both CAS/SAS (Major loss
. of physical security effectiveness).
- f. Loss of Offsite Communications to LLEA (Local Law Enforcement Agency).
l t g. Loss or Degradation of Power Supply to Security Systems. s
- -,--e.,,,n m -e ,--.. - - , ---- ,-.-.-,e - - - ----,--.-m-- .-- .,,---y
Of-RP/0/B/5000/13 Events Requiring NRC Notification Enclosure 4.1 Page 4 of g
. ( h. Unavailability of minimum number of Security Force Members.
- i. Decreased effectiveness of the Physical Barriers (Vital or Protected Area) creating a major loss of physical security effectiveness.
4.1.3 Events Requiring "FOUR HOUR REPORTS"
' As soon as practical and within four hours of the ! occu rrence.
4.1.3.1 Any event found while the reactor (s) is/are shutdown, that had it been found while the reactor (s) was/were in operation would have resulted in the plant, including its principle safety barriers, being seriously degraded or being in an unanalyzed condition that signifi- - cantly compromises plant safety. 4.1.3.2 Any event or condi' ion .that results in
~ .'
I manual o'r automatic' activation of any
. . Engineered Safety Feature (ESF), includ.ng .
the Reactor Protection System (RPS). ( (However, activation of an ESF including the RPS, that results from and is part of the preplanned sequence during testing 'or reactor operation need not be reported). 1 4.1.3.3 Any event or condition that alone could have prevented the fulfillment of the safety function of structures or systems that are needed to: 4.1.3.3.1 Shutdown the reactor and maintain it in a safe shutdown condition.
- 4.1.3.3.2 Remove residual heat.
4.1.3.3.3 Control the release of radioactive material. 4.1.3.3.4 Mitigate the consequences of an accident. ! 1 I J i l 1
i i 1 4 RP/0/B/5000/13 Events Requiring NRC Notification Enclosure 4.1
<: Page 5 of 6
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.! 4.1.3.4 Any airborne radioactive release that exceeds 2 times tite applicable concentrations of the limits specified in 10CFR20, Appendix B, Table 11 in j unrestricted areas when averaged over a
- l time period of one hour.
4.1.3.5 Any liquid effluent release that exceeds 2 times the limiting combined MPC (See 10CFR20, Appendix B, Note 1.) at the point of entry into the receiving water (unrestricted area) for all radionuclides except tritium and dissolved noble gases, , when averaged over a time period of one hour. (Immediate Notifications made under this requirement also satisfy the require-ments of 10CFR20.403, Paragraph (a)(2) and (b)(2)). (See 4.1.1.4.2) . ' 4.1.3.6 Any event requiring the transport of a radioactively contaminated person to an . offsite medical' facility for tr'eatment. 4.1.3.7 Any event or situation, related to the (. ' health and safety of the public or onsite personnel, or protection of the environment, for which a News Release is planned or Notification to Other Government Agencies ;
- has been or will be made. Such an event
~ may include an onsite fatality or inadventent release of radioactively contaminated materials. N O
Y
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j RP/0/B/5000/13
't Events Requiring NRC Notification ' Enclosure 4.1 ! Page 6 of 6 ]
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4.1.4 Follow-up Notifications ) 4.1.4.1 During the course of the event, report: 4.1.4.1.1 Any further degradation in the level of safety of the plant or other worsening plant conditions, including those that require the declaration of any of the Emergency Classes, if such a delcaration has not been previously made
-! or Any change in the Emergency Class or Termination of the Emergency.
4.1.4.1.2 The results of ensuing evaluations , or assessments of plant conditions
~**
. 4.1'.4.1.3 Th'e effeciiveness of response o'r protective measures taken.
(." c;' , 4.1.4.1.4 Information related to plart behavior that is not understood. . A P p 6 l 9
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t l RP/0/B/5000/13 ENCLOSURE 4.")
;- PAGE 1 OF 3 l 1 .-
, . , CHECKLIST FOR SIGNIFICANT EVENT NOTIFICATION l 4.2.1 Complete the applicable portions of this enclosure and transmit to the NRC Operations Center as required by Enclosure 4.1 or as soon as practical. j. 4.2.1.1 State the following to the NRC Operations Center:
"THIS NOTIFICATION IS MADE IN ACCORDANCE WITH 10CFR50.72. THIS IS DUKE POWER COMPANY'S CATAWBA NUCLEAR STATION IN NRC REGION ll MAKING THE NOTIFICATION."
- 1. My Name is: My title is:
I can be called-back at -
- 2. Time of Notification Event Time EDT.
Event Date / / . NRC person notif!ed: ' M D Y
. . 3. This Notification is: Check appropr'iate box (s). -
/
- a. -Emergency Plan Declaration -Other Immediate Notification C- Notification of Unusual Event
- Alert D- Site Area Emersency
- General Emergency
- 6. -A "ONE-HOUR" Notification
.~
- c. -
-A "FOUR-HOUR" Notification
- 4. Event description and cause:
6 J W I i - l
, e s RP/0/B/50(D/13 ENCLOSURE 4.2 PAGE 2 OF y * \ 5. Plant Status:
I
- a. Unit affected: 1/2/ Both ,
- b. Power prior to event:
1
- c. Power at time of report:
- d. Unit tripped: yes/no, initiating Trip Signal:
- e. Mode description:
- f. ESF Acutation: yes/ no.
- g. Safety injection or ECCS: yes/no initiating Signal ~
l t
- h. Primary System Temperature: Hot ,
t Cold
- i. NC Flow: yes/no, NC Pump Status: A: on/off, B: on/off, -
C: on/off, D: on/off. . .i j. Heat Sink: ,
** * "- ~
- k. Pressurizer Level:
- 1. Steam Generator Level (s): A B C D
(;c,/:
*j m. Feedwater Status: Main Aux
! n. Containment Pressure: Sump Level:
- o. Equipment Failures (include Status of Safety Systems): :
1
- p. Electrical Power Supplies available:
Normal Offsite: yes/no, Busses / Loads Lost: D/G Running: yes/no, Loaded: yes/no ) 6. Status of unaffected unit: ; 1
- 7. Radioactive Release: yes/no (if yes complete this paragraph) l
- a. Release: Liquid / Gas
- b. Location / Source:
- c. Release Rate: ;
- d. Duration of Release:
- e. Stopped: yes/no *
< - f. Monitored: yes/no , ! . g. Estimated Amount Released:
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RP/0/B/5000/13 ENCLOSURE 4.2 , Pago 3 OF 3 i
- h. Affected Plant /Offsite areas affected- '
l
- i. Areas Evacuated:
J. Other Actions Taken
- 8. Other major problems (include anything unusual or not.
understood): i I 9. Planned actions / Press releases / Emergency Centers activated: i
/
- 10. Outside Agency / Personnel Notified:
1 . Counties: State (s): York yes/no N.C. yes/no Gaston yes/no S.C. ves/no Mecklenburg ves/no NRC Resident: yes/no i Corporate Headquarters: yes/no, Others: . t k l 4 es ap' I _r __ _ - . . - 7 . . _ , . , _-%,,,. ,-.-_,,.-,,-,.y - , , . , .,, , . - , _ . __r,, ,.__,,r_,_.,.m, _ _ _ w , . ,. ,.
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RP/0/B/5000/13
- j. ENCLOSURE 4.3 i
PAGE 1 OF 1 REPORT OF SERIOUS PHYSICAL SECURITY EVENTS i DATE/ TIME OF NOTIFICATION NRC PERSON NOTIFIED !' State the following to the NRC Operations Center: i "THIS NOTIFICATION IS MADE IN ACCORDANCE WITH 10CFR73.71. THIS IS DUKE POWER COMPANY'S CATAWBA NUCLEAR STATION IN NRC REGION 11 MAKING THE NOTIFICATION". 7 My Name is: My title is: I can be reached at . , 1. *DATE OF OCCURRENCE: 3.* POWER LEVEL OF UNITS:
.' 2.
- TIME OF ' OCCURRENCE:
Unit 1 - Unit 2
*lf date and tirr.e of occurrence are not known, indicate the date and time of
,C. , discovery.
- 4. DESCRIPTION OF EVENT:
- 5. SECURITY RESPONSE / COMPENSATORY MEASURES ESTABLISHED:
I
- 6. LLEA (Local Law Enforcement Agency) NOTIFIED 7 YES NO (if Yes, name organization and telephone number)
- 7. VITAL AREA (S) AFFECTED? YES NO Description of Equipment Systems Affected l
r s., i
~
Tl .3 c Form 34731 (1041) (Formerly 3PD-10021) ' DUKE POWER COMPANY (1) ID No: HP/0/R/1009/03 ~ PROCEDURE PREPARATION Change (s) O to ' - PROCESS RECORD 1 Incorporated (2) STATION: Catawba Nuclear (3) PROCEDURE TITLE: Environmental Surveillance Followino A Primary To I
! Secondary Leak t
(4) PREPARED BY: M. in DATE: T-C-S4 i i (5) REVIEWED BY: M2 7. M DATE: &( M Cross-Disciplinary Review By: N/R: 47M
,( 6) TEMPORARY APPROVAL (IF NECESSARY):
By: (SRO) Date:
, By: Date:
(7) APPROVED BY: ' Date: $ SV y , , , (8) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: i i f l
+ .. j 1
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~
h DUKE POWER COMPANY ' CATAWBA NUCLEAR STATION ENVIRONMENTAL SURVEILLANCE FOLLOWIN3 A PRIMARY TO SECONDARY LEAK , 1.0 PURPOSE 1. This procedure describes the manner 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 i 2.2 10CFR50 2.3 CNS Technical Specifications 4 1 2.4' HP/0/B/1001/02 - Sample Preparation for Counting Room Equipment 2.5 HP/0/B/1001/12 - Gaseous Wasta Sampling and Analysis < 2.6 HP/0/B/1001/13,- Liquid Wasta Sampling and . Analysis ' r.. ML 2.7 HP/0/B/1009/11 - EMF Loss 2.8 HP/0/B/1004/04 - Request for Liquid Radioactive Wasta Release 2.5 HP/0/B/1004/05 - Request for Gaseous Waste Release 3.0 LIMITS AND PRECAUTIONS i
- 3.1 Insure that all controlled releases are within limits required in l references 2.1, 2.2, and 2.3.
3.2 Sampling and batch releases shall be terminated when radioactivity . identified in two consecutive samples is below 10CFR20 limits and j counted to the lower limit of detection (LLD) for principal gamma emitters listed in Technical Specifications Table 4.11-1 and secondary activities have fallen below levels set in Section 4.0 of this procedure. t . 4.0 PROCEDURE 4.1 Upon notification that the Condensate Steam Air Ejectors (C.S.A.E.) off gas-EMF #33 has alarmed indicating a primary / secondary leak: i i j ( ? . l
~n . . . ... . - -
HP/0/B/1009/03 Pags 2 of 3 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 '~ t 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 ml liquid sample from the T.B. sump and a 4400 ml gaseous. sample from the g C.S. A.E. using new Marinelli beakers. The 3 samples shall then be submitted to the Counting ., a Room per references 2.5 and 2.6 for analysis. . 4.1.3 If the sample results find no net radioactivity above i background, refer.to reference 2.7. s 4.1.4 If the C.S. A.E. sample results indicate not radioactivity i above background, but the T.B. sump EMF 31 does not alarm ', and activity is below 10CFR20, Appendix B, Table II, Column II limits, sampling frequency sha,ll 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). 4.1.4.1 When secondary side activity samples range ('N-' , between .005 pCi/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 every twenty-four (24) hours. i 4.1.4.2 When secondary side activity samples are greater than .01 pCi/gm but less than or equal j to .03 pC1/gm of the.I-131 equivalency, then the C.S.A.E. samples shall be collected once j every eight (8) hours , and the T.B. sump i samples shall.be collected once every twelve l (12) hours. t 4.1.4.3 When secondary side activity samples are greater than .03 pCi/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. 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 2.9. 4.2 Upon notification that the T.B. sump - EMF 31 has alarmed, q indicating a primary / secondary leak: t 4 e
,m,- -m-,, ,,---.ne, - - , - - - - - - . -- - , , - ,.- ,i , - . - -. , - - -v.--r.v,,__...-.-,,-9--.. - , - . , - .-~ ~-m, , - , , . ,.,%wm
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[ g OP/0/A/6200/21 ' C- . A Pcg2 11 cf.16 ' 9, i (,t 6.2.7 Open valve "I" and fill the 50 m1 nalgene sample bott1r > labeled " DILUTION WATER SAMPLE". Then, close the valve. /
~
6.2.8 After returning to the outer room, recerd the "On Contact" i liquid and gas radiation readings on Enclosure 8.2. (Omit: ' during periodic testing). 4 >
.c1 6.2.9 If this is the last sample to be collected this trip, taka -
the samples to the Hot Lab in the sample carrier and , , 4 place in an operating fuse heod behind a 4.ead brick shield ' to await analysis. However,sif another,tample is to'be-collected, call Technician #1 at the Hot' Lab and h' ave him i' ' come down and transport the samples and the,sempleted porpion of Enclosure 8.2 up to the lab. .Then proceed pith / Section 6.2.10 to begin the collectica of 4 second sample'. ) OneofthesamplehoodsintheHotLabshod1Yb4designatedi specifically for sample storage. Ler.d bricks,should li.e' the.frontofthesamplehoodsothat'sampe%muybepla'ced '
/
behind them. ,,A';
,'1 L i , ~ J
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6.2.10 In order to begin the process o.f collecting a second v* sample perform Steps 3.2.4 trd 3.2.9. g
. . . \>., . - .. .
, , 6.2.11 Att'ach new liquid and gas rarplers 'on the side of the PALS ,
panel. New samplers are locaced in the PALS draser.', 6.2.12 Begin at Step 4.2 Panel Prep. and repeat the procedure
- f. for the new sample point.
1 A , i i , 7.0 SAMPLE ANALYSIS pl ,
'. / x \_ f 7.1 Initial Conditions (Technician #1)
.?
e
- 7.1.1 A fume hood in the Hot Lab is prfpared to ' accept a l post-accident sample: (1) the ventilation fan is en and f e
'(2) Lead bricks line the front pf the panel. !
t 7.1.2 't Two Sec lockable sample syrinps have been verified *
- i workable and evacuated. l i'
s c l l 7.1.3 A Sec vial has been evacuated and placed in the fuse hood.
. .,{
, , .3 7.1.4 A clean 50 m1 nalgene sample bot' tie has ben pl. iced in the, /\ ^ ;
l sample hood. ,
; , e l
^! .
7.1.5 Reagents to run CP/0/l,/8100/55' nave been prepared.end i
,(s (
standards have been run. ' i h i i e ', h i 7.1.6 The Gr.s Chromatograph has been started im and standardized /
\s' !
_ per CP/0/A/8100/48 Chemistry Procedure for the ! Determination of Stripped Gas by G. C. '
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f OP/0/A/6200/21 1-( .. 5 Page 12 of 16
, 7.2 Stripped Gas Samples i
CAUTION: Perform all actions involving the transfer. preparation,
- or analysis of the gas sample under the fume hood.
7.2'.1 Inject a lockable Sec syringe into the gas sampler and i withdraw lec of sample. While still under the fume hood, ! inject the sample into an evacuated Sec vial. '. i , 7.2.2 Double bag the vial. Seal tightly. Prepare a label for i the bag as follows: ; 4
. " Gas Sample Name
. Initials Date
; Actual Sample Time Sample Volume "
4 The " Gas Sample Name" and " Actual Sample Time" may be obtained from the gas sampler label. Calculate the actual j sample volume as follows: Sample Volume = 110 ml x 1 a1 = .42 al . 260 ml
- Where: 110 ml = liquid tank volume (including tubing)~
260 ml = gas tank volume (including tubing) 1 a1 = sample volume injected into vial Complete the Sample Requisition Form using the sample volume calculated above to fill in the " Sample Volume" blank on the form. This will allow Health Physics to adjust isotopic activities from diluted samples to reflect
, reactor coolant activity.
( ! ,.2.3 Using a sample carrier, transport the sample to the Health Physics Count Room, or elsewhere for gamma spectral i analysis. 7.2.4 Inject a lockable 5cc syringe into the gas sampler and withdraw Sec of sample. Lock the syringe.
. 7.2.5 Analyze the 5cc sample of stripped gas per CP/0/B/8100/48.
- No averagir* of gas samples will be done as in the procedure as only one syringe will be injected into the
{ ~' Gas Chromatograph. Results as follows: 1
*H2'X 260 ce X 1 = '.H2 X 24 = cc/km H2 ;
.11 kg 100 I.
I j Where: *. gas is determined via CP/0/8/8100/48, 260 cc: total volume of Gas Tank and tubing
- i.
- l i *.
. g
I g OP/0/A/6200/21 C- ., g Pass 13sof 16
.11 kg: reactor coolant sample size in -liquid '
tank and tubing 1/100: conversion of % to decimal Report the 0: results as follows:
- - %0 X 33800 pob = Dissolved Oxygen in liquid (ppb)
%0:
l Where: 33800pp'/% 0: is a conversion factor derived from
.01 X (0.261) X mole X 32.0a X 1 X 1000mg X 1000eob 1% 0 22.4E mole (.11E) g ppm Record the results on Enclosurc 8.2.
7.3 Liquid Sample CAUTION: Perform all actions involving the transfer, preparation, or analysis of the liquid sample in the fume hood. 7.3.1 Take 5 cc of liquid sample and prepare 'for analysis per CP/0/A/8200/,04, Chemiptry Pr;cedure for the Determinationi of
.. . f Gamma Isotopic Act!.vity. Dilute 5 cc' in a 30 cc bottle per the procedure. Report the actual samp1'e volume being counced on the sample requisition form under " Sample Volume" and submit to Health Physics so that the appropriate adjustment.of isotopic activities occurs. The calculation is as follows:
Sample Volume = 1/10 x _ 5 ml x 5 cc Total Dilution Volume Where: 5 ml = Reactor Coolant Volume diluted by the PALS. Total Dilution Volume = #12, Enclosure-8.2.(Dilution Water Added)
+ 5 ml 1/10 = Dilution Ratio from 5 cc in a 50 m1 bottle ~
5 cc = Diluted Sample Volume Double bag the yial. Seal rightly. Prepare a _ label for the bag as follows:
" LIQUID SA?!PLE NAME INITIALS DATE ACTUAL SM1PLE TI!!E SM!PLE VOLUME The " LIQUID SM!PLE NRIE" and " ACTUAL SM1PLE tit!E" can be obtained from the liquid sampler label. The "SM!PLE VOLUME" was calculated above.
e 4 4 4-- 4, . , , - . , , - , , _ , , ,- ..-s.-,, , . - - - - , , ,y - -
f OP/0/A/6200/21 C. ,. 5 Pag 2 14 of 16 i 7.3.2 .Take 5 ml of. liquid sample and analyze for Baron per-CP/0/A/8100/55. The value received must be corrected for
~
dilution as follows. j
\
First, calculate.the dilution factor:
- )
Dilution Factor = Total Dilution Volume Reactor Coolant Sample Volume Where: Total Dilution Volume = (Dilution water added per Part I, #12, Enclosure 8.2) + 5 ml REACTOR COOLANT SAMPLE VOID 1E = 5 ml Then, multiply the ppe BORON MEASURED, ie. the value obtained per CP/0/A/8100/55 by the Dilution Factor to obtain the ppm Boron in the Reactor Coolant. ppm BORON IN THE REACTOR COOLANT = ppm BORON MEASURED X DILUTION FACTOR Fill in the " Dilution Factor" and " Boron + Concentration!' blanks on Enclosure S.2. - 7.3.3 Chloride analysis CAUTION: Perform all actions which involve the transfer (' ' of the liquid sample to another container under i the fume hood. 7.3.3.1 Contact the Station Chemist at the TSC (#2531). Ask him to contact the General Office personnel (at the Crisis Management Center ' during an accident situation). Inform them that a post-accident liquid sample is to be ' transported to the Physical Sciences Building for chloride analysis on the ion-chromatograph.
- They should contact A. M. Deak for workload clearance. Also, ask the Station Chemist to fill out a Chemical Sciences Analysis Request Form, Enclosure 8.9 for the sample.
. ?
s 7.3.3.2 A hard copy of the gamma spectrum and tritium data as well as the sample volume should be. . transferred to the Physical Sciences Building l + "~ Radiation Protection Officer (J. S. Isaacson) ' or her designee. A telecopy can be sent to the ' Technical Training Center. , i 7.3.3.3 Tranfer 20 ml t 5 ml of sample from the liquid ( - sample to a 50 ml nalgene bottle. x
% 4
( 0P/0/A/6200/21 C .. A Pcg2 15 of 16
, 7.3.3.4 _ Double bag the bottle. Seal rightly. Label the bag as follows:
" LIQUID SAMPLE NAE INTIAL DATE ACTUAL SAMPLE TIME DILITTION FACTOR The " ACTUAL SAMPLE TIME" and " DILUTION FACTOR" may be obtained from Enclosure 8.2. Place the bag in a shielded container for transport.
7.3.3.5 Once the sample shipment has been authorized by the Radiation Protection Officer, the sample shipment should be sent to the Physical Sciences Building in care of the Radiation Protection Officer. The dilution water sample obtained in Step 6.2.7 should also be sent for analysis at this time. 7.3.3.6 When the sample results are.obtained record the results on Enclosure 8.2. 7.4 Ifthedil'utionprovesinadequateforanyoftheaboveprocedures
~
contact the Station Chemist or his designee. 7.5 Report all results in the Primary Chemistry Legal Log. In an accident (', situation results should be relayed by phone to the Station Chemist at the TSC as soon as possible. Phone number. 2531. 7.6 Clean the liquid and gas samplers under the fume hood: Remove and replace the septum in the gas sampler. Flush the liquid sampler with Super Q water. 7.7 With Enclosure 8.2 in a plastic bag, exit the Auxiliary Building. Check out through the Operation's Support Center. 7.8 Transport Enclosure 8.2 to the Station Chemist at the TSC. 8.0 ENCLOSURES
, 8.1 Initial Conditions Checklist 8.2 PALS Data Sheet
,_ 8.3 Valve Alignment 8.4 Correction of Dilution Volume 8.5 PALS Control Panel L'ayout 8.6 Valve Sequence Table 1 ..
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. OP/0/A/6200/21 1
{: ' . - Pass 16 of.16
.8.7 General Information-F. -
- 8.8 Operation's Supply Valves to the PALS Valve Alignment 8.9 Chemical Sciences Analysis. Request Form
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l )ff f Pags 1 of 2 i'
- C ENCLOSURE 8.1 A OP/0/A/6200/21 INITIAL CONDITIONS CHECKLIST
- j. 1 -
Date: / / l .PART I. (Verifying the System's Ability to Function) Initial /Date l
- 1. Verify that the Post Accident Liquid Sampling System /
Periodic Test, PT/1/A/4208/08 is current prior to - sampling. PART II. (Interfacing Groups), Initial /Date lI
- 1. Contact Ooerations (complete at TSC).
f l (a) If this is an accident situation. the containment / t should have been isolated by an ST signal. Verify that the signal has been cleared. Initial /Date . CAUTION: -Warn Operations not to open any sample lines until Chemistry has realigned valves in the NM lab. Opening containment isolation sample valves too early could . increase radi& tion levels'in the NM ' lab. ' ' (b) Request permission to open the desired valves out I of the list below. Place a check beside the sample ' point (s) to be used. ' NC Hot Lee A Unit 1 Unit 2 Check Hot Leg Smpl Hdr Cent Isol INM26B 2NM26B Hot Leg A Sepl Cont Isol 1NM22A 2NM22A NC Hot Leg C Hot Leg Smpl Hdr Cont Isol 1NM26B 2NM263 Hot Leg C Smpl Cont Isol 1NM2!A 2NM25A ND Pump 1A Discharge Unit 1 Unit 2 '
*ND Pump 1A Disch Smpi Live Isol INM39 2NM39
, - t ND Pume 1E Discharge Unit 1 Unit 2 ;
*ND Pump 1B Disch Smpi Line Isol INM40 2NM40 i
- Verify with Operations that the respective A or B Train is in service.
- Initial / Time (c) Verify with Ope.rstions that 1KC Essential Supply /
Header "lA" is in operation for Unit i Sampling. For Unit 2: 2KC "2A" is required. i t.. 6 9
T . _ . i L ( - ENCLOSURE 8.1 OP/0/A/6200/21 g A Peg 2 2 of 2 i _{ INITIAL CONDITIONS CHECKLIST Date: / / Initial / Time f (d) Request permission to open or to have an operator open the following Operations valves in order to provide cooling water fl~ow to the panel. These valves are locked closed. The keys should be obtained prior to proceeding to the panel. / Unit 1 Unit 2 l Post Accident Liquid Sample Panel Ex Inlet 1KCAS 2KCA8 Post Accident Liquid Sample Panel Hx Outlet 1KCA10 2KCA10 (e) Verify Power Panel Boards 1KXPA and 1KXPB are energized / for Unit 1 Sampling. (Unit 2 Later) 2. Contact Radwaste Chemistrv (Cooplete at TSC). . Initial /Date
., . Notify Radwaste Chemistry that the PALS panel will be -
/
operated. . Waste Liquid from the panel is pumped to WEFT Sump "A". .
- 3. Contact Health Physics (. Complete at TSC) Initial /Date
($ ; (a) Request Health Physic's Coverage for obtaining a / post-accident liquid sample. Initial /Date (b) Verify Health Physic's ability to count a sample in / the Count Room or elsewhere. PART III. (Required ~ Equipment) Check
- 1. Technician #2 should have the following items before departing to the NM lab: '
(a) The PALS panel keys (A set of keys are located in
, the Secondary Supervisor's office and the Cold Lab) -
[ (b) A Working Copy of OP/0/A/6200/21 with Enclosure 8.1 1 l completed. (c) A High Radiation Area Key for the NM Lab. , (d) A Shielded Sample Carrier j i 1 !- l Initial / Data i ! - / e
1 (' ENCLOSURE 8.2 OP/0/A/6200/21 f ( Pags 1 of 4 j
, PALS DATA SHEET
- s. -
(Circle One) NC Loop A - C Data (Page I of II) Initial /Date
/
PART I. (Complete at Control Panel) TIME
- 1. pH meter standardized
- 2. Radiation Field (Background) mR/hr
- 3. Time sample purge started.
4 Minutes required for stabilization of temperature. mins. (Estimated sample travel time)
- 5. Samole Temocrature: Tcl 'C
- 6. Cooling Water Temperature: Tc2 . *C
- 7. Radiation field (with sample flow), .
. . mR/h6ur ' *
- 8. Radiation due to samole. (a71 - (a21 mR/ hour
,. 9. Pressure at isolation. .
psig k
- 10. Time sample purge isolated
- 11. Actual samole time. (d101 - (d4 minutes)
- 12. Dilution water added mis
- 13. pH of samule
- 14. Radiation reading after panel flush mR/ hour
- 15. Radiation reading on contact with samplers.
(Omit during Periodic Testing.) Gas mR/ hour Liquid mR/ hour h
. ,y _ - . , _ _
r-
s Page 2 of 4 (. f s ENCLOSQRE 8.2 \
, OP/0/A/6200/21 PALS DATA SHEET i
(Circle One) NC Loop A - C Data (Page II of II) Initial /Date
/ .
PART II. (Complete at-Hot Lab) TIME
- 1. Hydrogen Concentration ec/k2H 2
- 2. Oxygen Concentration ppb-
- 3. Boron Concentration ppm B
- 4. Dilution Factor
- 5. Chloride Concentration ppb C1"
- 6. Gamma Spectral Analysis (Gas) (Attach H.P. Data Sheet)
- 7. Gamma Spectral Analysis (Liquid) (Attach H.P. Dat Sheet) . .-
i In an accident situation. the results from this data sheet should be forwarded to the Station Chemist at the Technical Support Center as soon as possible. TSC phone number - 2531. (.s _7, Initial /Date
/
l 4
+ we 6
l' i I a 1 - O N
Pags 3 of 4 C- ENCLOSURE 8.2 C OP/0/A/6200/21 PALS DATA SHEET (~ -
. 'N. (Circle One)
ND Loop A - B Data (Page I of II) i Initial /Date
/
PART I. _( Complete at Control Panel) TIME
- 1. pH meter standardized- !
- 2. Radiation Field (Background) mR/hr
- 3. Time sample purge started.
- 4. Minutes required for stabilization of temperature. mins.
(Estimated sample travel time) ' E
- 5. Samole Temperature: Tcl "C I
- 6. Cooling Water Temperature: Tc2 . 'C
, ,.7. Radiation field (with sample flde)* - *
- mR/htur
- 8. Radiation due to samole. (d71 - (d21 mR7 hour
- 9. Pressure at isolation psig ,
?
- 10. Time sample purge isolated *
- 11. Actual samele time. (ul01 - (da minutes)
- 12. Dilution water added mis l
- 13. o_M of samole
- 14. Radiation reading after panel flush mR/ hour I
l
- 15. Radiation reading on contact with samplers.
i (Omit during Periodic Testing.) Gas mR/ hour l Liquid mR/ hour , l; 8 5 I
/. I k >
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9
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ENCLOSUR.E 8.2 OP/0/A/6200/21 ( Paga 4 of 4- I l PALS DATA SHEET r ~.
- t, -
(Circle One) l
'I ND Loop A - B Data (Page II of II) i-i Initial /Date
- i /
1 { PART II. (Complete at Hot Lab) TIME
- 1. Hydrogen Concentration ec/kg H, -
- 2. Oxygen Concentration ppb
- 3. Baron Concentration ppm B 4 Dilution Factor
- 5. Chloride Concentration ppb C1'
- 6. Gamma Spectral Analysis (Gas) Mttach H.P. Data Sheet)
- 7. Gamma Spectral Analysis (Liquid)
, (Attach H.P. Data Sheet) , . .
In an accident situation, the results from this data sheet should be forwarded to the Station Chemist at the Technical Support Center as soon as possible. TSC phone number - 2531. Initial /Date
/
O
.- ow G
T 9 l 1 - i ;- M
,. , - . - ------a ,-- - .,,,-,n - - . - - . --g- -
i i DUKE P0TER CCMPANY l Form 18768 (R8-81) ( ATAWBA NUCLEAR.STATZON
\ ENCLOSURE 5.3
(
\
I OP/0/A/6200/21 (Unit 1) j VALVE ALIGNMENT LOCATION i VALVE NO* VALVE NAME POSITION INITIAL l nB-543 EE-54 I INH 342 PASP Domin Supply Flow Meter Influent Rm. 238 THROTILEI nB-543 EE-54 1NM343 PASP Demin. Supply Isol to Sep1 Hdr Rm. 238 OPEN 1 nB-543 EE-54 I INM351 PASP Air Eductor Isolation From VI Rm. 238 OPEN l aB-543 EE-54 l 1NM298 Nitrogen Supply to PASP Rm. 238 OPEN
; i5-5*3 EE-54 1NM393 PASP Effluent to WEFT Sump A Isol Rs. 238 OPEN aB-543 EE-54 INM321 PASP Liquid Tank Effluent to WEFT Rm. 238 THROTTLE:
i aB-543 EE-54 1NM334 PASP Calibration Tank Vent to Aux Bldg Exhaust Rm. 238 CLOSED
, aS-343.EE-54 i *.
1NM328 "PASIS Sample Line Nitrogen Supply Isolation Rm. 238 OPEN 1KC099 LB-543 EE-54 Post Accident Liquid Sample Panel Hx Inlet Rm. 238 OPEN ( ' 1NM425 Calibration Tank Drain
,LB -5 45 Rm. 238 t.E. CLOSED 4 ' .LB-543 EE-54 OPEN 1NM424 Nitrogen Inlet Isolation to Liquid Tank Rm. 238 INM-I Fost Accicent Liquio Sample Panel Domin LB-543 EE-54 ,l
- Water Sample 4
RM. 238 CLOSED INM-J Post Accident Liquid Sample Panel Dilution TB-543 EE-54
- Flow Sample
- Rm. 238 CLOSED INM-A Post Accident Liquid Sample Panel Nitrogen (B-543-EE-54 CLOSED
- Supply Drain j Rm 238 I .
- Valves which will be added per NSM CN-10068.
j.- Unit 2 Valve Alignment (Later) 1
-l j
4 l 1 1
& q
1 ... _ .
/
( A ENCLOSURE 8.4 OP/0/A/@;00/21 f
\
CORRECTION OF DILUTION VOLUME To correct the dilution volume, divide the radiation reading after panel flush
, by 3 rem /hr. Then multiply this by the initial dilution volume to obtain the desired dilution volume in Section 4.6.3.
. Example:
Initial Dilution Volume = 250 ml Radiation reading after panel flush = 12 rem /hr (12000 mR/hr)
- then 12 rem /hr x 250 ml 5 1000 ml
.3 Go back to Section,4.2 and repeat the sample sequence. In Step 4.6.3, use the new dilution volume which was calculated as in the example above.
([ - eem 9 e O 9 em r [ \ - I L l
! ENCLOSURE 8.5 l'u t- t ur 4 1 - OP/0/A/6200/21 i FALS CONTROL PANEL LAYOUT ( l \ . I
~
l DRAIN OFF RESET PANEL PREP, i !
-Oc 6O-
.o.6A 6 '6666 FLUSH . /
-o nn o R SAMPLE RECIRC.
s. A.,~ u L - SAMPLE
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g P:ga1ef3 g ENCLOSURE 8.6 OP/0/A/6200/21 VALVE SEQUENCE TABLE Pushbutton Function Activation Valves 1.0 Panel-Prep 1NM313. 1NM312, 1NM315 1NMSV0311, INH 311, INM310, INM314, 1NMSV3201 . 1.1 Calibrate H INM333, INM332 1.2 Purge H INM330, INM338, INM307, 1NM305 1.3 Flush H 1NH331, INM338, 1NM307, INM309 1.4 Drain H INH 338, 1NM307, INM305 , 2.0 Sample Recire. 1ECA9,1NM294, IN!!324, INM319,1NM313, IN!!312, 1NM315, 1NMSV0311, 1NH314 , 2.1 Increase H Puts air to INM320 (INMSV3201) g3 2.2 Decrease . H Vents 1N!!320
\c. (IN!!SV3200) 3.0 Sample Trap 1KCA9, 1NM294, INH 324 INM319,1NH313, IN!!312 INMSV0311, 1NM314 1
1 3.1 Pressurize M INM319 3.2 Trap M INM324 4.0 Depressurization 1NH317, 1NM315
- , 4.1 Gas Stripping Start M 1NM325, 1NM327 -
4.2 Gas Stripping Stop M INM325, INM327 i 5.0 Liquid Sample 5.1 Grab Sample M INM318, IN!!325,1NM329 1N!!SV0336 5.2 D.M. Plow Meter Start M INH 341, 1NH346 f i 5.3 D.!!. Plow Meter Stop M INM341, INH 346
, - . - . . . _ - . - _ _ ,_..,c- - , , ,_ - ,_ -- - .,.__r_ ._. , m. ~ ., , , r___
<r . l Pega : of 3 ENCLOSURE 8.6 CP/0/A/6200/21 VALVE SEQUENCE TABLE Pushbutton Function Activation Valves 5.4 Mixing H INH 340, 1NM346 5.5 pH H INMSV0336 5.6 Trap Open M INM315, 1NM312, INMSV0311. INM324, INH 319, 1KCA9, INM345, INM322 5.7 Trap Close M INM315. INM312, 1NMSV0311 6.0 Liquid Sample Prep - (Step incorporated into Step 5.0) 7.0 Liquid Sample II 1NM324, INH 319, 1KCA9, l .. . . - . '
- 1NM345,1NM322. 1NM348 *
. 1NMSV0350, 1NM346
-- 7.1 Trap Open .
H INM319, INH 346, 1NM309 {~ ( INM304, 1NM376 I t 7.2 Trap Close M INMSV0350 8.0 Flush 8.1 Gas Tank M INH 316, INH 312, INM308, 1NM309 8.2 Probes M 1MN331, 1NM338, 1NM307, 1NM309 8.3 Dilute Tank M INH 347, INH 301, INM309
~ ' _
8.4 Liquid Tank M INM331. 1NM329, 1NM325, INM319. 1NM322 9.0 Drain ( 9.1 Dilute Tank M INM376, 1NM348. 1NM304, INH 305
+.
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. Pega 3 cf 3 ENCLOSUR58.6 OP/0/A/6200/21 l VALVE SEQUENCE TABLE ~
Pushbutton Function Activation Valves 9.2 Gas Line M INM323, INM315, INH 312, INM308, INH 305 9.3 Gas Tank M INM323, 1NM315, INH 317, 1NM325, INM329, ' 1NM338, INM307, 1NM305 9.4 Probe Refill & System Vent M INM331, 1NM338, 1NM307, 1NM309, 1NM312, 1NM313 INH 346, 1NM348, 1NM313, INMSV3200 LEGEN'D : M- Momentarily depressing the button initiates the function. i H- The function will operate as long as the pushbutton is. depressed. i N- Indicates that the valve is de-energized when the pushbutton is depressed. , h
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Pag 2 1 cf 2 i \ ENCLOSURE 8.7 ( I OP/0/A/6'200/21 .
~!
l GENERAL INFORMATION 1 -
- l. PALSPanelkocation: Unit 1 - (Room 238, Col. FF-55, AB-543) i
- i .
Unit 2 - (Room 248, Col. FF-59, AB-543) See page 2 of this enclosure for a general arrangement drawing.
- 2. Telephone Number at Control Panel - Ext. 2109
- 3. Breaker Information:
i Unit 1 i j Tdr. Breaker Como/ Breaker Description Location t 1KXPA #3 Post Accident Sampling AB 554' Sample Pump and Sol. CC-57 4 Vivs. 1 1KXPB #34 Post Accident Liquid
- AB 554 t Sampling Control Panel CC-56' * *
*1KXPA #22 Post Accident Air AB 554
- Sampling Control Panel CC-57 e
*The Post Accident Air Sampling Control Panel .is under Health Physic's control.
4 k Unit 2 (Later)
- 4. Area Radiation Monitor - 1 EMF-2 is located in Room 238.
- 5. Station Chemist phone number at TSC - 2531.
- 6. Sample Line Vdlumes Unit 1 ,
NC Loop A to PALS - 9.0 gallons NC Loop C to PALS - 7.6 gallons ND Loop A to PALS - 10.0 gallons ND Loop B to PALS - 13.0 gallons Unit 2 (Later) t l . 9
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k l ( ENCLOSURE 8.7
- OP/0/A/6200/21 cENERAL INFORMATION
( Page 2 of 2
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; DUKE POWER COMPASY ,l Form 18768 (R8-80 4
(.CATAWBANCCLEARSTATION ENCLOSURE ,8,.8 k
, }. , OP/0/A/6200/21 l OPERATION'S SUPPLY VALVES - VALVE ALIGNMENT t VALVE NO.
- LOCATION VALVE NAME POSITION INITIAL
- i, ,
i , - F - Unit 1 PALS Supply Valves s AB-553 GG-56
! IVI230 Root Isol. Rm. 200 OPEN i
AB-543 EE-53 1VI86 Aux. Bldg. 543 Elev. VI Supply Rs. 217 OPEN
)
AB-543 FF-54 1YM436 Post Accident Unit 1 Sample Isol. Rm. 238 OPEN AB-543 FF-54 1YM256 YM Header Isol Rm. 238 OPEN AB-550 FF-54 1GN110 N2 t Unit 1 Gas and Liquid Sample Panels Isolation Rm. 233 OPEN . 1KCA6 Post Accident Liquid Sample Panel Ex Inlet AB 546. EE-54 LOCKED Rs. 238 CLOSED
;1KCA10 Post Accid,ent Liquid Sample Panel Ex Outle.t '
. AB 546. EE-54 LOCKED .
Rm. 238 dLOSED Unit 2 PALS Supply Valves AB-3*3 s '2VI402 Liquid Sample Panel Supply Isol. OPEN AB-543 2VI230 Unit 2 Aux. Bldg. Root Isol. OPEN AB-543 2VI86 Aux Bldg 543 Elev. VI Supply OPEN AB-543 FF-6C 1YM437 Post Accident Unit 2 Sample Isol. Rm. 248 OPEN AB-543 FT-57 1YM140 YM Header Isolation Re. 200 OPEN s AB-550 FF-6C 1GN111 N2 t Unit 2 Gas and Liquid Samplu Panois Isolation Rm. 248 OPEN 2KCA8 Post Accident Liquid Sample Panel Hx Inlet AB, 543, LOCKED EE-FF, 60-61 CLOSED l 2KCA10 Post Accident Liquid Sample Panel Hx Outlet AB, 543 LOCKED l EE-FF, 60-61 CLOSED 1 NOTE: The valves listed above all belong to Operations. Contact Operations if a valve is found in an incorrect position. I 4 m
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l l- CATAWBA NUCLEAR STATION DIRECTIVE 3.8.4 (TS) e . REV. NO. 8 DATE 3-/.T*bY APPROVAL kb
/ /~" l !
DUKE POWER C j- CATAWBA NUCLEAR STATION ! ONSITE EMERGENCY ORGANIZATION 1.0 PURPOSE
- . To define the role of the Emergency Coordinator and other members of the j onsite Emergency Organization in implementing the station Emergency Plan
- and to provide for augmentation of the normal operating shift during an i
emergency situation.
2.0 REFERENCES
2.1 , Catawba Nuclear Station Emergency., Plan .
. i .
2.2 Catawba Nuclear Station Operations Management Procedure 1-8,
" Authority and Responsibility'of Licensed Reactor Operators and Licensed Senior Reactor Operators" h 2.3 Station Directive 2.8.1 (TS) " Reporting Requirements" l
2.4 Station Directive 3.0.7 (TS), Site Assembly / Evacuation. ' 3.0 RESPONSIBILITIES . 3.1 Shift Supervisor - All emergencies are initially handled by the l! Shift Supervisor. The Shift Supervisor on duty will ensure that all { immediate actions required by station emergency or abnormal i 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 .
1 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. i The Shift Supervisor shall then continue 'to take actions necessary l to ensure that the emergency situation'is brought under control.
~
i 3.3 Recovery Manager - The responsibilities of the Emergency Coordinator will be assumed by the Recovery Manager at the Crisis Management Center (CMC) as this organization is staffed and ready to assume its e
CNS Dir ctiira 3.8.4 Pass 2 of 13 function. This assumption of the Energency Coordinator functions by the Recovery Manager, will take place for the Alert, Site Emergency 7 and-General Emergency classifications.
.. N The Emergency 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 DtTTIES 4.1 Shift Supervisor / Emergency Coordinator - immediate duties include the following: 4.1.1 Determine from the initiating conditions what Emergency . Class the Station is in. j 4.1.2 Declare the Emergency as necessary and assume control as the Emergency Coordinator. 4.1.3 Assign someone from the shift to begin the notifications as per applicable precedure. 4.1.4 Take necessary on-site remedial actions. 4.1' 5 . Initiati activitation 'of the Technical Suppott Cohter' and Operations Support Center. . 4.1.6 Providing protective action recommendations to authorities responsible for implementing offsite emergency measures. 2 NOTE: This authority and responsibility shall not be delegated to other elements of the station emergency organization. 4.2 Station Manager / Emergency Cocedinator - relieves the Shift Supervisor of the Emergency Coordinator's duties and assumes the responsibility for implementing the station Emergency Plan including: 4.2.1 Staffing the Technical Support Center and Operations Support Center with those personnel deemed necessary to effectively assess the emergency condition, j 4.2.2 Instituting those procedures necessary to allow the Control Roce to gain immediate control of the emergency situation. 4.2.3 Notification and activation of Crisis Management Team, county and state organiza.tions and the Nuclear Regulatory Commission. 4.2.4 Providing protective action recommendations to authorities responsible for implementing off-site emergency measures. l i ( , i f n
-m- - , , - , , . . . - , - , ~ - , , ---...---w-,- --.,1,~--%-~e-r--- ...-,r,r-,--.--,,-n,, , - - - , ~ - , - - , - - . . , - < - ,,,-,--.-,v----,,_ , ,-e,e.,wr- ~ , . - , . , . . , .-- , ,-
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!~ ' NOTE: This authority and responsibility shall not be
']j delegated to other elements of the station
. emergency organization.
7 4.2.5 Continued maintenance of an adequate state of emergency-preparedness until the emergency situation has been
- j- effectively managed and the station is returned to a normal i or safe operating condition.
! 4.3 Technical Support Center Staff - The Technical Support Center (TSC), l t location shown in Enclosure 4, will be activated and staffed to i support the control roce and coordinate emergency and/or recovery i efforts with offsite groups, corporate headquarters, state and local l government and the NRC. The station operating staff is used as the
,; TSC staff in the emergency situation as deemed necessary by the
- ' Emergency Coordinator. Individuals With a TSC function will have a ji routine function that is similar to their role in an emergency.
;i 4.3.1 Operations Group:
- A. The Superintendent of Operations when designated, l, shall assume the duties of the Station Manager. He will provide expertise to the Station Manager and the l Shift Supervisor regarding solutions to operational l ,
. , problems. He shall ensure that sach. operating shift
- is manned with competent personnel trained and. -
- prepared to manage all emergency situations, and he shall augment his personnel resorces as necessary to accomplish this goal. He shall provide technical j
f expertise to other members of the TSC and shall work. closely with the Superintendent of Maintenance in
- restoring station equipment to an operational status during and after the emergency condition. This j
1. individual shall be the first alternate to the Emergency Coordinator in the event the Statica Manager l is unavailable. + B. The Operatin: Enmineer 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 TSC as required - and maintain contact with Operations personnel in the Control Room. C. The Assistant Operatina Enmineer shall assume the duties of the Operating Engineer when so designated. ! He will provide technical expertise to the Superintendent of Operations, the Operating Engineer l and other members of the TSC as required and maintain s ! contact with the Operations personnel stationed in the Operations Support Center (OSC). l l l l i [
. l
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. . -. .. . _ . - = . _ - -. . . - - . -
' ~
CNS Directiva 3.8.6 ~ Pag [4cf13
. s
- y. 4.3.2 Technical Services Group:
- A. The Superintendent of Technical Services shall assume
;. T -
the duties of the Station Manager when so designated. 4 He will provide expertise to the Station Manager and the Shift Supervisor (via the Operating Engineer)
, regarding solutions to operational problems.' He shall '
- 1 provide technical expertise to other members of the TSC in the areas of Health Physica, 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 condition. This individual shall be the second d alternate to the Emergency Coordinator in the event the Station Manager is unavailable. B. The Health Physics Section of the TSC l I 1. The Station Health Physicist shall assume the
, duties of the Superintendent of Technical j
Services when so designated. He will provide
, technical exper1;isc t,o the Superintendgnt of . . .- ,
- Technical hervices, the Station Manager and other members of the TSC as requirnd. He will
- 3 provide for the calculation and distributin of l off-site dose determinations for releases of radioactive materials to the atmosphere sad make '
l recommendations to the Station Manager through i the Superintendent of Technical Services on '
; Protective Actions necessary for limiting exposure to station personnel and members of the 1
public. The Station Health Physicist shall also a work closely with the appropriate members of the Crisis Mar.agement Center to assure that radiological hazards during any emergency ' situations are minimized. The Station Health Physicist shall ensure that all areas under his i direction are staffed and prepared to manage Health Physics support for any emergency condition.
~
j -
- 2. Health Physics S&C Coordinator shall coordinate and direct the actions of in plant radiological j monitoring teams and provide data on plant j ,_ '
radiological status. _J 1 j 3. H. P. Suonort Coordinator shall direct the actions of the remainder of the Health Physics functions. i h 4. Data Analysis Coordinator shall provide for the calculation and distribution of Off-site Dose f projections and field monitoring information , e 1 ? \ k
.~
l , l -. . l . .. . .. .. ..
. CN8 Directive 3.8.4 Page 5 cf 13 s
4
- assessable by Health Physics personnel and relay this to the Station Health Physicist.
(r The Data Analysis Ccordinator shall also direct l-the Field Monitoring Coordinator as necessary to evaluate dose projects versus field data.
- 5. Field Monitorinz Coordinator shall direct the actions of the field monitoring teams in gathering both on-site and off-site radiological
? data and make this information available to the Data Analysis Coordinator or Station Health Physicist. Constant communications will be asintained by a Radio Operator or by the use of plant or commercial telephone lines to the field teams. j C. The Station Chemist shall assume the duties of the j Superintendent of Technical Services when so
- 2 designated. He will provide technical expertise to i the Superintendent of Technical Services and to other members of the TSC as required. He is responsible for i .
coordinating chemical technical support and for
.- initiating neces'sary action to enture adequate' . *
, chemical sampling and evaluation to support the emergency condition.. The Station Chemist shall ensure i that all areas under his direction are staffed and
! prepared to manage Chemistry support for any emergency
{ , condition.
- D. The Performance Enzineer shall assume the duties of the Superintendent of Technical Services when so
; designated. He will provide technical expertise to i the Superintendent of Technical Services ar.d to other j members of the TSC as required. He will assure that I
adequate levels of technical and engineering manpower are available to: manage test procedure review, carryout special test procedures, insure control and ]i accountability of special nuclear materials, and ! evaluate plant and reactor performance. A i Test Enmineer shall assist the Performance Engineer in the evaluation of plant systems and transmission of
' information to the CMC. A Performance Technician (s) -
i will operate the TSC Operator Aid Computer Terminal to post and update plant status. This information will be transmitted through the VAX computer to other
!.- users. The Performance Engineer shall ensure that all I areas under his supervision are staffed and prepared i to manage Performance support for any energency l . condition. .
l E. The Reactor Enmineer shall assume the duties of the j < Performance Engineer when so designated. He will j provide technical expertise to the Performance
- s 4
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CNS Directivs 3.8.4 Page.6 cf 13
- Engineer and to other members of the TSC as required.
The Reactor Engineer shall ensure that all areas under his direction are staffed and prepared to manage i technical support for any emergency condition. l l F. The Licensina and Proiects Enmineer shall assume the , , , duties of the Superintendent of Technical Services i when so designated. He will provide technical ! expertise to the superintendent of Technical Services l and to the members of the TSC'as required. -He is responsible for coordinating station activities with 4 l reg 41 sting agencies, coordinatim:; the reporting and j t investigation of all incidents and for providing review l ! of appropriate station technical matters. The l License and Projects Engineer shall ensure that all ' l areas under his direction are staffed and prepared to
- manage technical support for any emergency condition.
j G. TSC Lonkeener shall record events that occur from the l time of activation of the TSC and shall be directed by l 1 the Emergency coordinator. This individual will be an ! engineer from the station's Projects group. ! I , , , * , , H. 'Offsite Communicator shall.make followup, notifications' s i to State and/or County E0C's. The Offsite . ! 1 Communicator will proceed to the Control Room when the il 1 TSC is activated to assist with notifications until i the Station Manager assumes duties of the Emergency 8 f',' Coordinator. This individual shall be an engineer' i ! from the Station's Licensing and Projects Group. s 4 4.3.3 Station Services Group ! i . i A. The Superinteedent of Station Services when designated I
- shall assume the duties of the Station Metager. He (
will provide techical expertise to the Station Manaser ' and to the Shift Supervisor (via the Operating ' l
- Engineer) regarding solutions to administrative !
j problems associated with emergency canditions at the i j station. He shall provide technical expertise to 4 other members of the TSC in the area of Contract ! j Services, Security, Training and Safety, and ' i i i
' Administrative Coordination. He shall ensure that all -
' areas under his direction are staffed and prepared to j manage administrative support for any emergency
- l condition. This individual shall be the 12EE1h
- i alternate to the Emergency Coordinator in ths event -
{ j the Station Manager is unavailable. i l B. The Security and Contract Coordinator shall assume the ! ) - duties of the Superintendent di Station Services when 4 l so designated. He will provide technical upertise to ; the Superintendent of Station Services and to other
~
- 1
\ l j e I, i { ;
- 1 ,
, (
. CNS Directivo 3.8.4 Pass 7 cf 13 i l
sesbers of the TSC as required. He is responsible for l coordinating Security and Contract Services for the '
,e '
station. The Security Chief shall ensure that all .
- t. -
areas under his direction are staffed and prepared to t esmage Security and Contract Services for any i . emergency condition. C. The Administrative Coordinator shall assume the duties of the Superintendent of Station Services when so , designated. She will provide technical expertise to the Superintendent of Station Services and to other 1 members of the TSC as required. She is responsible for coordinating and maintaining general adminstrative , functions and for contacting the TSC clerk (s) as needed. The Administrative Coordinator shall ensure 4 that all areas under her direction are staffed and prepared to manage administrative functions during any i emergency condition. D. The Train 4== and Safety Coordinator shall assume the 3
, duties of the Superintendent of Station Services when i
so designated. She will provide technical expertise
! to the Superintendent of Station Services and to other i meabers of the TSC as required. She is responsible ,
j . . for coordinating 'the statida training and safety'
; activities, Fire Protection and Medical Services in :
j support of the emergency organiastion. The Training [ n and Safety Coordinator shall ensure that all areas i I 4 under her direction are staffed and prepared to provide needed training and safety evaluations during ; j any emergency condition.
; 4.3.4 Maintenance Group l A. The Superintendent of Mainten ece when designated, shall assume the duties of the Station Manager. He !
will provide technical emportise to the Station 'e Manager and the Superintendent of Operations regarding i solutions to operational problees. He shall provide l l technical espertise to other seebers of the TSC in l' areas of Mechanical Maintenance, Planning. Instrument '
, and Electrical Maintenance, and Materials Support. He ;
will insure that all areas of responsibility under his . 1 direction are staffed with competent personnel l properly troised and prepared to support any ' { operational emergency condition. This ladividual ! l._ shall be the 3 g { alternate to the Emergency ' Coordinator in the oyent the Station Manager is ! ! , usavailable, l I
\
) 3. The Mechanical Maintenance r== beer shall assues the ! !~ duties of the Superintendent of Maintenance when so i designated. He will provide technical expertise to l the Superintenden*: of Maintenance and to other sesbers ! \ i ni I 1 9 nv--nn~--e<,r-e- , -n-,, - -r-,-n,- ,---,nw-,--,nww -,,-,-mv-.-ww,--,-w-w- ,v-,ew,-,, v--e,--~,,-vn,w- -,,,nn,,,~rwc-e ,-- mne m
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j CNS Dircetiva 3.8.4 Pagn 8 cf 13 l l l of the TSC as required. He is responsible for j preventative and actual maintenance for all station . s C mechanical equipment and facilities. The Mechanical
~'
~
Maintenance Engineer shall insure that all areas under his direction are staffed and prepared to manage maintenance support for any emergency condition. C. The Planning Engineer shall assurae the dutias 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 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 condition. 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 respcasible for- . -
' maintaining all st'ation I&E equipment in an operational state. The I&E Engineer will be the station contact with the Transmission Department personnel in the event of loss of offsite power. 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 l Enclosure 5, shall be activated by the Emergency Coordinator in accordance with the applicable Emergency-Procedure. The 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.S.C. shall be under the direct supervision of a Shift Supervisor designated by the Emergency Coordinator. 4.4.2 The Operations Support Center shall include as a minimum-the following personnel: A. Operations: Operators on shift who are not actually
, assigned to the control room and additional operations people on site or called out as required by the Shift Supervisor or Station Manager.
4 B. Essit.h Physics: A Health Physics Supervisor and five a technicians as deemed necessary by the Station Health Physicist. The Health Physics Supervisor shall work l- - I- - _,
" una utrcctiva 4.5.* Pcg3 9 of 13 closely with the Shift Supervisor in charge and shall maintain contact with the HP S&C Coordinator in the TSC.
, ( C. 0ther station groups as necessary.
4.4.3 In the event that the Operations Support Center becomes environmentally uninhabitable due to radiological or other conditions, the OSC shall move to the rear of the Control Room or te,other facilities as applicable. 1 5.0 ACTIVATION OF EMERGENCY ORGANIZATION , 5.1 Phased Activatien of T.S.C. Organization 5.1.1 Selectod station personnel are notified of situations classit'ied as Unusual Events by Emergency Response Procedure, RP/0/A/5000/02. These individuals shall then respond as appropriate and shall notify any additional personnel in their organization to respond as needed. At the Alert class or greater TSC activation is required, either full or partial as deemed necessary by the Station Manager. 5.1.2 To effectively respond to an $mergen,cy situation and to , , ,
.; avoid, unnecessary personner fros'being act'ivated,"'the TSC
. . is divided into a Phase I and II organization, with other .
TSC personnel as needed. The Station Manager may activate Phase I separately or both Phase I and II jointly (Phase II is never activated without prior activation of Phaso I). 5.1.3 See Enclosure 6 for Notification Mechanism. 5.2 Phase I of the Technical Support Center 5.2.1 thase I of the Technical Support Center organization shall be staffed and organized as indicated below or as deemed necessary by the Station Manager. NOTE: See Enclosure (1) for TSC organization. 5.2.2 Personnel assigned to Phase I of TSC shall be capable of supplementing the on-shift Emergency Response within 30 to 45 minutes of notification. - A. The Station Manager / Emergency Coordinator B. Group Superintendents C. Station Health Physicist . D. Performance Engineer E. Instrument and Electrical Engineer ,, F. Offsite Communicator G. Fielding Monitoring Coordinator H. Data Ant 195.3s Coordinator I. S & C Coordinator i WP 4
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GNS dircctive 4.0.4 Pago 10 of 13 5 J. HP Support Coordinator [. K. Test Engineer N 5.2.3 .In the event that the Technical Support Center becomes environmentally uninhabitable due to radiological or other
, conditions and the Control Room remains secure (habitable),
Phasa I of the T.S.C. shall move inside the Control Room
, area. In the event the Control Room also becomes I
unintabitable due to radiological or other conditions, Phase I of the T.S.C. shall move to the Administration
- j. Building or to other facilities as applicable.
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 Manager. 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 Security & Contract Coordinator I. The Training and Safety Coordinator ( 5.3.2 Personnel assigned to Phase II of TSC shall be capable of supplementing the on-shift Emergency Response within 45 to 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 Site Evacuation 5.4.1 At the Site Area Emergency class, Group Superintendents shall develop a list of all essential personnel that will remain onsite. , ! 5.4.2 Health Physics shall determine the habitability of the TSC
& Control Room for the protection of station personnel remaining onsite after the Site Evacuation.
5.5 Other TSC Personnel
. 5.5.1 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: s l
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; A. The Administrative Coordinator
- B. The Planning Engineer
. C. Clerks as needed, determined by Group Superintendents ! D. TSC Logkeeper i' 'E. Radio Operator 5.6 OSC Notification 5.6.1 Operations personnel will be notified by the Operation's Duty Engineer or someone designated either by station phone or home phone as required.
5.6.2 Health Physics personnel will be notified by the Station Health Physicist either by station phone or home phone as ! required. ! 6.0 EMERGENCY ORGANIZATION SUPPORT 6.1 " Clerical assistance for the Station Manager and the four station superintendents will be provided by one of their normally assigned clerks. Notification of this individual will be made by the - Administrative Coordinator. 6.2 Food and beverage will be supplied to the TSC and OSC as approprints >
,for the time of day.- After initial. staffing of .the .TS,C and OSC, s
" ~ .
coffee and snack material will be provided by the Administrative f group. ~ ,
. 6.3 Station Fire Brigade 6.3.1 The fire brigade will have its normal functions of fire fighting in an emergency situation as needed.
6.3.2 In the event of an emergency requiring activation of the Technical Support Center Phase I & II, the Station Fire Chief or his designee shall make frequent reports to the Training and Safety Coordinator regarding the status of any - fires. 6.3.3 The Station Fire Chief or his designes shall also coordinate and direct the services of any outside fire departments called upon to assist in fire fighting on station property. : 6.4 Stat' ion Security ' 6.4.1 The security force will have its normal function of station ,. security in an emergency situation. ' ( 6.4.2 In the event of an emergency requiring activation of the J Technical Support Center Phase I & II, the Security Shift Lieutenant or his designee shall make frequent reports to the Security and Contract Coordinator regarding the status j of any security violations, threats or civil disturbances. 1 i i n 4 I 9
u;ss Utrective J.o.* Peg 2 12 or la 6.4.3 The Security Shift Lieutenant-shall also coordinate and direct the services of any outside law enforcement agencies ( called upon to assist in an emergency situation. 6.4.4 The Security Shift Lieutenant shall inform the Security and Contract Coordinator in the TSC of the status of Site . Assembly /Evacustion. 6.5 Evacuation Coordinator 6.3.1 In the event of a site evacuation, the Evacuation Coordinator shall be the overall person in charge at the l evacuation site. A. This position reports to the Emergency Coordinator or his designee for matters pertaining to personnel disposition, and status of the evacuation. B. All evacuated supervisory personnel will in turn report to the Evacuation Coordinator. 6.5.2 The Emergency Coordinator chall notify the Evacuation Coordinator of the need for a Site Evacuation.
, ,7.0 . TRAINING & DRILLS .
7.1 Initial Training * { 7.1.1 Training will be provided for Onsite Emergency Organizations personnel listed in Enclosures 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. I 7.2 Annual Training 7.2.1 Emergency Organization personnel will receive annual ' overview retraining as per part 0 of the Emergency Plan. 7.3 Drills Practica drill sessions will be held for each group within
~
- 7.3.1 the organization to allow the individuals to perform their ,
assigned functions. 7.3.2 The drill instructor will make corrections of performance as needed, during the drill. 1 _ 7.3.3 The drill scenario, participants names and evaluation will ' be documented and any deficiencies will be corrected.
r - du otrcctiva 3.6.+ PKg3 13 or 13 8.0 ENCLOSURES (, Enclosure (1) Technical Support Center Staff - Phase I & II Enclosure (2) Technical Support Center Telephone Activation Enclosure (3) Operations Support Center Personnel Enclosure (4) TSC Location Enclosure (5) OSC Location Enclosure (6) Notification Mechanism
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, COOROtNATOA P: J, W. HAMPTON A: C W. GRAVES ONSITE E40EftGE8eCY ORGANIZATION 4 g ygg,H'. SMfi,g gg,g TECH 000 CAL SUPPOAT CENTER STAPP SO304 ENCL 01 AEVISeces S l
EVACUATION P: C L JEpsSEN COORO. l
,a A: B. MOSELY E.FEESER I . 1 . . I . I OPE RATIONS TECH. SE RVICES MAINTENANCE STAf TON SERveCES P: C W. GRAVIS P: J W. CON P- G T. SMsTH P: A. R. FRA80KL100 A: f. E. CAAWPOAO A: W. P. OEAL A: D.R.AOGEAS A: T. K. AIEDEUIEDN C.W. AAUSE E H. CHAREST R s. WILSON J. A. LAN00000G l i H. KNUTI W.F.OEAVEA , W W thCOLLOUGH P. C. 00r UGULTV
- 2. TOWER C L HART 2 ELL .
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OPERAT60eG ENGA. HE ALTH PHYSICS CHEMISTRY PE RFORMA8eCE LICEleSE & P: T. E. CRAWFORD P: W. P. DE AL P: R H.CHAAEST P: W. F. OE AVE R
- PROJECTS A: C E.GAUSE A: R. L.CLEGAMER 4: LO. EVANS A: R.S.ABERNATHY P: C.L HARTZELL j J. H. KNUT8 G.T.GenOs A. L PAsesTER O. M. ROSINSON. A: P.N.AnACK O.70WER A. OUCKWOAT > S. ORESSLE R P.LE GOY l . 1 . . l .. ~l .. l . l ..
- 4. P. EX30AOlseATO8 OATA ANALYS8b H. P. COORDINATOR AEACTOR EpsGA. PE RFOAAAA80CE ISE PL.AlefesseG GAECHA800 CAL S&C COORDINATOA SUPPORT P: D. M ROSINSON
- TECH. P: O A ROGERS P: R 5 WILSON P: W W.tesCOLLOUGH P: H. P. RAsINVALE P: R. D. K 008ARD P: G. A. VANOE AVELDE A: E W. BELLAMY P: J. L. LOWERY A: J. O. LEE A: O. L LAN00000G A: C. O. STEELE O.WELLBAuge C te SAHRAS J.to STACKLEY A COK W. L Apertes A: L O. SCHLISE A: G. L COUAT8eEY A: F. L WILSON P. N. ""* RA M.HAWES A: G. FORO J 40 CARAEftON R.BLESSIfeG A ASHLEY I? HuseTER l q tuCEV ,, l ,, y
- O. StelTH TEST ENG400EER ~ . SECUntTY AORA8MISTRATIVE IR880 48AFETY P: A. SHATNAGAA . P: T. K. A8eOERSOes COOAOI80ATOR P: P. C GAsA80ULTV t
A: A. A JO9fES A: J H. ROACH P: J. A. LApettleeG A: D. L WATE AS ASST. OPE A. EfeGA. FBELO SAONITOnl80G 2. L TAYLOR
- L J. RYLEY N. J. GONE iT P: A II CASLE' COOAOlfeATOR l A: J. 5. LAY G.G.BAARETi A: GL L R$1TCHELL P:EV WRAY L A88 *$ $
- 83. H. SeiLLE R A: R.LhlVARD J. E. THRE ATT
. l l P: PRIMARY TSC LOGKEEPE R OFFSaTE y TRA885 DEPT. TSC CLERK g P: 0.C GOOLSeY COIARAUNICATOR P: J ASHE P: Y. H JACKSON 1 A: ALTERNATE P: A GA AYCOCK SAOtO OPE RATOR
- A: A: W. L KELLER P GEResEROTH P. GE RRALO P: O. E. SE XTON A: J. C, AOAAAS .
T. L. NAHAY A: A. PROCTOR O.C.ROWELL A: T. W. 01)OceOHUE E. CREDISHAW C AlTCH6E
* - PHASE I
" - PHASE H a
L . - 'l ,1 S.D. 3.6.4 Rev. S ONSITE EMERGENCY ORGANIZATION Enclosure 2 TELEPHONE ACTIVATION Page 1 of 4 All telephone numbers will be AREA CODE 803 unless otherwise noted. o Emergency Coordinator /Statien Manager i P: J. W. Hampton 0: ll H: j A: C. W. Graves 0: H: 'i A: J. W. Icx 0: H: A: G. T. Smith 0: , H: A: A. R. Franklin 0: K' i Suoerintendent of Ooerations Suoerintendent of Technical Service i P: C. W. Graves 0: P: J. W. Cox 0: H: R: A: T. E. Crawford 0: A: W. P. Deal 0: H: H: A: C. E. Muse ' 0: A; R. H. Charest
- 0: .
H: H: A: J. H. Knuti 0: A: W. F. Beaver 0: H: H: A: D. Tower 0: A: C. L. Hartzell 0: ( H: H: Suoerintendent of Station Services Suoerintendent of Maintenance P: A. R. Franklin 0: P: G. T. Smith 0: l H: H: A: T. K. Anderson 0: A: D. R. Rogers 0: I H: H: A: J. A. Lanning 0: A: R. B. Wilson 0: H: H: A: P. McAnulty 0: A: W. W. McCollough 0: H: H: NOTE P: Primary A: Alternace 0: Office H: Home - 6
_ _. ._ , _ . ..._ _. __ - ,.-_ _ - ~.- __._m w _- - , j s 1, l I S.D. 3.8.4 Rev. 3 ; ONSITE EMERGENCY ORGANIZATICF Enclosure 2 l TELEPHONE ACTIVATION Page 2 of 4 All telephone numbers will be AREA CODE 803 unless otherwise noted. I f f ..
'l Ocerating Engineer Asst. Ooerating Engineer i P: T. E. Crawford 0: P: R. N. Casler 0:
H: H: A: C. E. Muse 0: A: G. Mitchell. 0: , H: H: I !! A: J. H. Knuti 0: A: W. H. Miller 0: l H: H: - ,i A: D. Tower 0:
;! H:
I I Health Physics Field Monitoring Coordinator P: W. P. Deal 0: P: C. V. Wray 0: H: H: , A: R. L. Clemmer 0: A: R. L. Rivard 0: I H: ~
. H
, A: G. T. Mode ,0: Ai J. E. Threact 0: H: H: ( Data Analysis Coordinator H. P. Suecort Coodinator l . P: R. D. Kinard 0: P: G. A. Vandervelde 0: H: H: i A: G. L. Courtney 0: A: F. L. Wilson 0: i H: H: A: P. N. McNamara 0: - l H: , l l Chemistry Licensing & Protects Engineer P: R. H. Charest 0: P: C. L. Hartzell 0: H: H: i A: L. D. Evans 0: A: F. N. Mack 0: H: H: A: B. Painter 0: A: S. W. Dressler 0: - H: H: A: A. Duckworth 0: A. P. G. LeRoy 0: H: H: Performance Engineer Radio Oeerator P: V. F. Beaver 0: P: D. E. Sexton 0: H: H: A: R. Abernathy 0: A: T. V. O'Donohue 0: H: H: A: D. M. Robinson 0: l H: 1
i l i S.D. 3.8.4 Rev. 8 l ONSITE EHERGENCY ORGANIIATION Enclosure 2 i TELEPHONE ACTIVATION Page 3 of 4 All telephone numbers will be AREA CCDE 803 unless otherwise noted. =$ Reactor Engineer Performance Technician P: D. M. Robinson 0: P: M. Sahms 0: H: H: > A: S. M. Bellamy 0: A: J. Lowery 0: H: H: A: M. Hawes 0: A: G. Ford 0: H: H: A: D. Wellbaum 0: A: R. Ashley 0: , H: H: A: R. Blessing 0: A: T. Hunter 0: H: H: l A: D. Smith 0: I H: i A: D. Lucey 0: ! H: , Planning Engineer I&E Engineer P: R. Wilsor. 0: P: D. R. Roge'sr ' 0: l H: H: A: D. Lanning 0: A: J. Lee 0: l H: H: ' 7~ i A: R. Cox 0: A: J. Stackley 0: ; H: H: : Mechanical Engineer Security & Contract Coordinator , t P: W. W. McCollough 0 P: T. K. Anderson 0: j H H: ; A: C. D. Steele 0: A: J. Roach 0: H: H: A: W. L. Anfin 0: A: L. Ryley 0: H: H: Administrative Coordinato Training & Safety P: J. fanning 0: P: P. McAnuity 0: _ H: H: A: J. Lay 0: A: D. Waters 0: ' l H: H: l -- A: G. Andrews 0: A: J. Gossett 0: H: H: A: d. Barrett 0: H: , NOTE P: Primary A: Alternate 0: Office H: Home i
l S.D. 3.8.4 Rev. 8 CNSITE EMERGENCY ORGANIZATION Enclosure 2 j TILEFHONE ACTIVATION Page 4 of 4 l All telephone numbers will be AREA CCDE 803 unless otherwise noted. TSC Logkeeper * , TSC Clerks l P: D. C. Goolsby 0: P: Y. Jackson 0: ( H: H: A: J. Adams 0: A: W. Keller 0: H: H: A: T. Nahay 0: A: P. Gerrald 0: H: H: A: D. Rowell 0: Of fsite Communicator H: A- C. Ritchie 0: P: J. M. Aycock 0: H: H: A: P. W. Germeroth 0: H.P. Coordinator S&C l H: A: E. M. Crenshaw 0: P: H. F. McInvale 0: H: H: l A: R. Proctor 0: A: L. D. Schlise 0: H: H: Tes: Engineer P: A. S. Bhatnagar 0: ( _. H: A: R. A. Jones 0: H: A: Z. L. Taylor 0: H: 1 l Evacuation Coordinator P: C. L. Jensen 0: Beepe H: A: B. J. Moseley 0: Beepe H: A: E. L. Feeser 0:
. .. Beepe H:
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- Page 2 of 3 f- DUKE POWER COMPANY i CATAWBA NUCLEAR STATION -
ENCLOSURE 5.4 HP/0/B/1009/15 EVALUATION OF PLUME LOCATION . Table 3.3 5-10 Mile Affected Zones Wind 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, A3, B2, C2 290.1* - 304* A3, B2, C2 304.1* - 333' B2, C2 333.1* - 360* B2, C2, D2 ( 5.4.3 Determine the protective action guides (PAG), based on the calcu-lated 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 Rem Thyroid
'~
Recommend evacuation of children and pregnant women and 4 sheltering of remainder of personnel in the affected area. l i . l
~ ' ' ~
1 B Page 3 of 3
~,- DUKE POWER COMPANY CATAWBA NUCLEAR STATION ENCLOSURE 5.4 HP/0/3/1009/15 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 effected zones requiring protective action on sample Enclosure 5.5 along with the recommended protective action. k, '
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ry7 'I1-DUKE POWER COMPANY Page 1 of 1 CATAWBA NUCLEAR STATION
! HP/0/B/1009/15 i ENCLOSURE 5.5
- f. DOSE ASSESSMENT REPORT
, .( ake Power Crisis Company Management Plan Off-Site Dose Report -
CATAWBA Prepared.By Date/ Time / Emergency Drill (circle one) I __....._____..________......._______.___.............._______.....____.._______.._____ _ Meteorology - Wind Speed MPH l Wind Direction degrees from North Vertical Temp. 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 Semple VCi/ml UCi/ml Unit Vent (Sample of EMF) DCi/ml uCi/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 , (T ml/hr s
i 2hr Dose (rem) based Whole Body en Unit Vent release Child thyroid
@ cfm 2hr Dose (rem) 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
! 3 (mi) Whole body Child thyroid (dpm/100 cm ) ,- Affected Zones 0-2 mi ' 2-3 mi 5-10 mi 9-10 mi (circle zones) A0 Al B1 C1 D1 El F1 A2 B2 C2 D2 E2 F2 A3 F3 i .. ____.................___....______________.....__............_____.___...__________ l COMMENTS: I xc: Data Analysis Coordinator, Station Health Physicist 1
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Form 34731 (10-81)
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(Formerly SPD 10021) DUKE POWER COMPANY (1) ID No: HP/0/B/1009/16 ,
. PROCEDURE PREPARATION Change (s) O to ,
i PROCESS RECORD Incorporated 1 i (2) STATION: Catawba Nuclear (3) PROCEDURE TITLE: Distribution Of Potassium Iodide Tablets In The Event Of A Radiciodine Release (4) PREPARED BY: bk 'hi . '- -_e - DATE: 3 - G - T(4 (5) REVIEWED BY: /A/ 2 )L./c. DATE: /- / -#V , Cross-Disciplinary Review By: N/R: 4 7. M (6) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: ' p;) By: Date: (7) APPROVED BY: g
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'6 b HP/0/B/1009/16 g DUKE POWER COMPANY , C CATAWBA NUCLEAR STATION '
DISTRIBUTION OF POTASSIUM IODIDE TABLETS IN THE EVEhT OF A RADI0 IODINE RELEASE
~
1.0 PURPOSE - l' This procedure provides information necessary to distribute Active Potassium 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
2.1 KP/0/B/1001/09, Operati n/ Calibration Procedure for the Body Burden Analyzer 2.2 HP/0/B/1009/10, Body Burden Analysis Following Suspected Uptakes of - Mixed Fission or Activation Products 2.3 System Health Physics Manual 2.4 NCRP Report' No. 55; Frotection of the Thyroid Gland in the Event of Releases of Radiciodine 1977 (' 2.5 NCRP Report No. 65; Management of Persons Accidentally Contaminated With Radionuclide 1980 2.6 NUREG 0654 2.7 May 16, 1983 letter from L. Lewis to C. T. Yongue.
Subject:
Oconee Nuclear Station HP Procedure HP/0/B/1009/12, File: GS/05-750.01. 3.0 LIMITS AND PRECAUTIONS 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 ' 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 late ar 24 hours after an emargancy will prcside some protection.
l 3.5 Discolored or disfigured tablets, tablets that have reached the i , expiration date listed on the bottle, and bottles of KI with loose tops shall be discarded. M
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EP/0/B/1009/16 Paga 2 of 4- -t j 3.6 Hands of anyone touching the KI tablets must be free of radioactive i contamination prior to taking the KI tablets. (~ . 4.0 PROCEDURE 1 4.1 Responsibilities For Distribution .! I j- 4.1.1 The Station Health Physicist, in conjunction with j available medical advice, shall control the distri-i 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 f 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 Supervision to immediately register in the KI. distribution center (for-I 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 dose of - 10 rem or more. For example, exposure to approximately 700 weighted MPC-hours, or 6.1 x 10 uCi/ml Airborne I-131 for.one hour, would result in a dose of 10 ram. 3 ge Aic 4.1.2.2 A significant amount of radiciodine for emergency workers in the field is 70 MPC
- (6.1 x 10 ' UCi/ml) I-131.
. 4.2 Registration of persons exposed to a significant amount of radio-iodine, f i 4.2.1 When persons notified by Health Physics arrive at the .
- distribution 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 i nine (9) KI tablets, and the package insert for the use 4 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 j (1) tablet per day for the length of the l emergency.
~'
4.2.2.2 After the initial dose of KI, subsequent doses will be take on a daily basis. Tablets should J 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.
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{ - HP/0/B/1009/16 Pags 3 of 4 , 4.2.3 ' Tablets removed from full bottle of KI should be stered in f 10 al. plastic vials. The expiration date on the botrie . js C, . from which the tablets were taken and the name of the l 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 l affected persons. - -
- 4.2.4 As directed by the Field Monitoring Coordinator (FMC) or I the S&C Coordinator, team members shall ingest one-(1) tablet of Potassium Iodide. ,
n 4.2.4.1 The FMC and/or SSC 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 Analys2s Following Radioiodine Exposure 4.3.1 All persons receiving KI tablets should receive a thyroid -
; scan. If the number of people render this step impractical, ,
th'e Count Room Supervisor will select a representative sample of persons listed on Enclosure 5.1 who received KI tablets. NOTE: Subsequent action involving thyroid burden analysis should follow guidelines established (] by HP/0/B/1009/10. s , 4.3.2 Records of thyroid scan shall be maintained per i procedure. NOTE: Distribute KI before analyzing thyroid [ concentration. Thyroid scans immediately ; i 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). l l 4.4.1.3 Store in an area protected from exposure to ' '- light. ?
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4.4.2 Upon receiving a shipment of KI tablets, boxes shall be opened as soon as possible and bottles examined to ensure i l that an air-tight seal has been maintained. Bottles must ) t i
~ be returned to boxes, and boxes must be sealed shut, so as l to avoid exposure'to light.
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HP/0/B/1009/16 Pega 4 of 4 4.4.3 'To ensure a sufficient supply of tablets, a minimum of 7 1,000 bottles with 14 tablets per bottle should be i . maintained on site. 4.5 Shelf Life and Changeout of KI lablets 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 i three (3) months prior to the date of expiration listed on the bottles of KI. 4.5.2 Upon receiving a shipment of KI tablets, supplies should , be shifted so as to use older tablets before new tablets. 5.0 ENCLOSURES 5.1 Sample of Potassium Iodide Tablet Distribution Data Sheet 5.2 Manufacturers Guidelines for Thyro-Block " Tablets, and Solution
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.. 4 Enclosure 5.1 i- -l POTASSIUM IODIDE TABLET DISTRIBUTION DATA SHEET I
HP BADGE DATE & TIME OF DATE & TIME OF NUMBER NAME DEPARTMENT SUSPECTED EXPOSURE INITIAL ISSUANCE l e O f [ l l - l
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111'/0/E/1099/10 Enclosure 5.2 Page 1 of 2 s a
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THYR $ BLOCK" poTaskuu como (crenounced poe TASS +em EYEetHfyed) (attweviated: 10) TABLETS and AOLUTION U.S.P. TAKE POTASS!UM IODIDE ONLY WHEN PUBLIC HEALTH OFFICIALS TELL YOU. IN A RADIATION EMERGENCY. RADIOACTIVE 10 DINE COULD BE RELEASED INTO THE AIR. POTASSIUM IODIDE (A FORM OF IODINE) CAN HELP PROTECT YOU.
, IF YOtt ARE TOLD TO TAKE THIS MEDICINE.TAKE IT ONE TIME EVERY 24 HOURS. DO NOT TAKE IT MORE OFTEN. MORE WILI. NOT HELP YOU AND MAY IN-CF. EASE THE RISK OF SIDE EFFECTS. DO NOT TAKE THIS DRUG IF YOU KNOW YOU ARE ALLERGIC TO '
IODIDE. (SEE SIDE EFFECTS BELOW.) ~ s INDICATIONS ((' THY!tO!D DLOCKING IN A RADIATION EMERGENCY ONI.Y. DIRECTIONS FOR USE Use only as directed by State or localpublic health authoritics in the e vent of a radiation emergency. DOSE Toblete: ADULTS AND CHILDREN 1 YEAllOF AGE OR OLDER: One ill tablet once a day. Crush for smallchildren. BABIES UNDER 1 YEAR OF AGLL One. half (1/2) tablet once a day. Crush first. Solution: ADULTS AND CHILDREN 1 YEAR OF AGE OR OLDER: Add 6 drops to orw-half glaes of liquid and drirA each day. BABIES UNDER 1 YEAR OF AGE. Add 3 drops to a small amount of liquid once a day. For c.*l dm se ,'ortnr Take for 10 days unless directed otherwise by Sta.c or local pubbe health a1thorities.
~
Store at c^-trol! d room temperoture between 15' and 30'C(f.9* to SG'Fl. Keep container tightly closed and protect from light. Do not use the solution ifit appears brownish in the noule of the bottle. WARNING Potas siurn u.d.de should not be used by peeple at:s rgic to iodsde. Keep out of the reach of children. la case of overdose or allergic reaction. centset a physician or the public health authority. y DESCRIPTION Each Tl!YlttFDLOCKTM TABLFT contains 130 mg of l i potasam iod:ac. Each drop c.! THYRO.BLOCKT5' SOLUTION cont ains !!! mg of , potassm iod.J.* j -
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- HOW POTASSIUM IODICE WORMS Certain forms of iodine help your thyroid gland work right. Most >
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. people got the iodias they ased from foods like iodized salt ur '
fish. The thyroid can " store" or hold saly a certain amount of , ioditie. In a rad 6auen emergency, rednesetive iodine may be released in ' the air. This material may be breathed or swallowed. It may , enter the thyroid gland and damage it h damage would pro. bebly not show itself for years. Children are most likely to have i i thyroid damage. i If you take poe ==== iodide'. It will filkup your thyroid gland. , C This reduces the char.co that harmful redaunctive iodine wiu - g enter the thyroid gland. ' ' . > WHO SHOULD NOT TAKE POTASSIUM IODIDE N only people who should not take potassium iudide are people , who know they are suergic to iodade. You may take potewium iodade even if you are takird mediciase for a thyroid problen. (for ', exernple. a thyroid hormone or antithyroid drugl. Pregnest and nursing women and babies and ciuldren may also take clas drug. ( HOW AND WHEN TO TAKE POTASSIUM IODIDE . [ Potassium lodido abould be taken se soon as possible apr ; s public hen!th officaals tei! you. You should take one dose every 24 , hours. More ws!! not help you because the thyroid can " hold" om l> Iim;ted amounts of iodame. Larger doses will increase th risk (' of sade effects. You will probably be told not tu take the drug for.
, ,~
more than 10 days. SIDE EFFECTS
'~ UsuaUy. side effects of potassium iodide happen when people ,
take higher doses for a long time. You shoukt he careful not to . trhe more than the recomraended dose or ta t te it for lune r than , ' you are told. Side eflects are uahkely because of the low dvoe and ,' the short tirne you will be talung the drug. Possible side effects laclude elda raahee. owelling of the ulivery glands, and 'iodamm" (mi tallic tast e, burning mouth ami thrust. . sort teeth and gums, symptoms of a head cold, and sonstimes stomach upset and diarrbee). ' N A few people have en allergic rescuan with mon seride'symp-te:ns. These ca.uld be fever and joint pains, or aweihng of parta vi ' ' the face and body r.id at times severe shortness wi bros th requtr. j ing ime ediate medu.a! attention. , l Tahir.g iodice naay rarely cause overactivity of the thyrnid i gbnd. underactiv$tv of the thyroid glar.d. or enlargement of the j thyroid gland (goitt.rl. WHAT TO DO IF SIDE EFFECTS OCCUR l If the side elicett are severe or if you have an allergs riartk/n. 1 stop takmg potassium iodide. Then, if ponible, cau a ductor te pub!w health authura:y for instructions. 1 HOW SUPPLIED ] TllYitO.DLOCKW TABLETS (Putassium I.idiJe. U.S.I'. bot ti tics c! 14 taWts (NDC.0037 0472 201 Each white, sound, act, red ' 1 tab!r. contains 130 mg potassium iodida. J l TilYllCLif t.( CKW SOLUTION (Potsassurn lo ab .WAtwn. i U.S P.I30 n.S1 C c 1 light.resistan(, mea ural drop diapriamg ' urots 8NDC O'*;7 42nMS) 1 sch drop contama 21 mg potamum ] x
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, Forra 34731 (1041) -
i (Formerly SPD 10021) i l l DUKE POWER COMPANY (1) ID No: OP/0/A/6200/21 PROCEDURE PREPARATION ange(s) O to ! PROCESS RECORD Incorporated ;
*_ ion #1
\ (2) STATION: Catawba ,
1 k (3) PROCEDURE TITLE: Operating Procedure for the Post Accident Liquid i _g' Sampling Systems
.(4) PREPARED BY: , am DATE: 7- [-[
\ (5) REVIEWED BY: M[ d e, TE: f fV i ,' Cross-Disciplinary Ravi By: [N O/2
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. By: (SRO) Date: , .r7 By: a / Date: ,
j, (7) APPROVED BY: Y* Date: I / 5! )
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( / ' ' (8) MISCELLANEOUS: Reviewed / Approved By: Date: I Reviewed / Approved By: Date: t I e
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( .. (. OP/0/A/6200/21 DUKE' POWER COMPANY CATAWBA NUCLEAR STATION ' OPERATING PROCEDURE FOR THE POST ACCIDENT LIQUID SAMPLING SYSTE!!S 1.0 PURPOSE - i The purpose of the Post Accident Liquid Sampling Systems are to provide a { method for promptly obtaining reactor coolant samples under a nuclear ' reactor accident condition. l Samples acquired during accident conditions -(normal sample points are not . usable due to high radiation conditions) will aid in the evaluation of information related to: i
- 1) The extent of core damage which has occurred or is occurring.
- 2) Types and quantities of fission products released to containment liquid and gas phases.
- 3) Reactor Coolant Chemistry and Radiochemistrv.
, 2 . ,0 LIMITS AND PRECAUTIONS . .
i 2.1 In an accident situation the decision to collect a post-accident i e sample will originate from the Technical Support Center. The ka management involved in this decision should take two factors into consideration in making this decision: (a) Has the situation stabilized to a degree so as to minimize the risk to individuals involved in the sampling? (b) From the present information available, has the system j
, stabilized to a degree that a representative samole may.be ;
obtained? ' 2.2 The PALS panel should only be used undsr the following circumstances: '
- (a) Caution: 1/2 EMF 4* ct. '.. e flow for readings' to be
, valid. ' - )
The Reactor Coolant System (NC) Gross Specific d Activity is expected to be or is known to be greater than : 200 pCi/ml. This corresponds to a reading on 1/2 EMF 48 of ! equal to or greater than 1.64 x 105 counts per minute. " (Correlation factor from HP/0/B/1000/10 is 1.22 x 10'8
, (uCi/ml)(CPM))
(b) Primary Systems Sample Sinks 1A and 1B are inaccessible due ; to the radiation levels or for other identified reasons. 2 i t i ! u 9
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l ( A f OP/0/A/6200/21 5 Psg2 2 of 16 - l (c) The Station Chemist or his designee has requested that the PALS panel be put in service. l (d) The PALS panel is being run for monthly operational
. verification, maintenance, or training purposes.
(e) When use of the normal Primary Sample systems will create a Radiation Exposure problem in the NM Lab. . 2.3 The undiluted sample volume is 5.0 ml and the final dilution volume shall be controlled between 250-3500 ml. 2.4 Health Physics personnel must perform continuous radiation monitoring during sampling at the liquid sample or control panel. During an accident situation, Health Physics personnel from the OSC , must monitor all personnel entering the Auxiliary Building. 2.5 When handling radioactive samples, good laboratory practices are F essential to prevent radioactive contamination of personnel, equipment, and physical structures. Reference applicable SWRP(s) ~ and RWP(s). ; 2.6 Individuals that have been trained on this procedure are qualified .
, to use this procedure.
- Individuals'shall be trained.'at a-dinimum
- frequency of (6) months. -
2.7 Due to the nature of this procedure, a Working Copy shall be used to ensure compliance. 3.0 PANEL PREPARATION ' 3.1 Initial Conditions 3.1.1 In order to. expedite the process, the Primary Supervisor or his designes should send two Chemistry Technicians to collect the sample. The technicians should be chosen taking into consideration the following: ~ (a) Being qualified on the PALS procedure (b) Being respiratory qualified (c) Age - (d) Accumulated Exposure (e) Sex (f) Phys.ical Strength - Their responsibilities are outlined below: . Technician if1-(a) Checks the Initial Conditions Checklist from '" OP/0/A/6200/21 at the TSC and returns the checklist ' " to Technician #2. (b) Informs Health Physics at the OSC that he/she will be traveling to the Hot Lab. - E - r - - -- ---- - - - - - - * - - = - - - - - - ~ *
-p " f OP/0/A/6200/21 ('
. . 5 Paga 3 of 16 (c) Dresses out as necessary.
3, (d)- Travels to the Hot Lab and prepares for the analyses. (e) Transports samples from the NM Lab to the Hot Lab, if necessary. (f) Analyzes the samples. (g) Reports results by phone to the Station Chemist at
, the TSC and returns to the OSC.
(h) Transports the completed data sheet to the Station . Chemist at the TSC. Technician #2 (a) Obtains the PALS panel keys. (Location: Secondary Supervisor's Office or Cold Lab) (b) Dresses out as directed by Health Physics at the OSC. (c) Health Physics plans out a path to be taken to the NM Lab, Not Lab, Count Room and to exit the Auxiliary Building. (d) Travels to the NM Lab and uses the PALS to collect l liquid and gas samples. 1 (e) Transports the samples to the Hot Lab. (f) Assists in the analysis of samples, if 'necessary. (g) Reports results by phone to-the Station Chemist at , , the. TSC and retukns to the OSC. * '. *
~
3.1.2 (Technician #1) . Verify the Initial Conditions Checklist (Enclosure 8.1) at the TSC and return it to Technician #2 at the OSC. 3.1.3 (Technician #1) - Inform Health Physics at the OSC of your plans to travel to the Hot Lab. Inform Health Physics that travel to the outside east backside of the
, Auxiliary Building may be required in order to calibrate the Gas Chromatograph. Also, inform them that you may transport the sample from the NM Lab to the Hot Lab.
~ Dress out as required by Health Physics. The Hot Lab may
'be locked so bring the key.
3.1.4 (Technician #1) - In the Hot Lab, prepare for the sample analyses required in Section 7.0 of OP/0/A/6200/21. 3.1.5 (Technician #2) - Obtain the PALS panel keys from the
, , Secondary Supervisor's office or the Cold Lab key box. -
i 3.1.6 (Technician #2) - Report to the OSC and inform Health Physics of plans to obtain a post-accident liquid sample. Dress out as required by Health Physics. Health Physics personnel will decide the route to be taken to the PALS panel, the route to carry sample to the Hot Lab and Count Room, and the exit route back to the OSC. They will also
~
address stay times (1-2 hours at' the PALS Control Panel) and protective radiological dress and equipment. A Health Physics technician must be with any Chemistry personnel 1 entering the Auxiliary Building at all times. Remember: The buddy system is in effect. l
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3.1.7 (Technician #2) - Travel to the NM lab with Health Physics coverage to collect a sample using the PALS panel. Remember to bring the required equipment listed on { Enclosure 8.1, Part III. g' 3.2 Control Panel Preparation (Technician #2 - 543' Elev. NM Sample Room) 3.2.1 Close the following valves: Unit 1 Unit 2 - NC Hot Leg Sep1 Ndr to Radiation INM29 2NM29 g Monitor
- NC Hot Leg Sample HX 1A Outlet INM264 2NH264 3
NC Hot Leg Sample HX IB Outlet 1NM278. 2NM278 1
, .c ND Smpl HX Outlet INM265 2NM265 0.
3.2.2 Open the following Operations valves: Unit 1 Unit 2 Post Accident Liquid Sample I Panel Ex Inlet -1KCA8 2KCA8-
- Post Accident Liquid. Sample Panel Hx Outlet IKCA10 2KCA10 3.2.3 Call the Control Room and obtain the official time on the
(;_ Control Room clocks. Set the clock near the PALS panel to the cort.ct time. 3.2.4 Contact the Control Room and have them open the appropriate valve (s) listed below to obtain the desired sample. Reference Enclosure 8.1, Part 1(b). , NC Hot Leg A Unit 1 Unit 2 Hot Leg Smpl Hdr Cont Isol. INM26B 2NM26B Hot Leg A Sepl Cont. Isol. INM22A 2NM22A NC Hot Ler B Hot Leg Smp1 Hdr Cont. Isol. INH 26B 2NM26B Hot Leg C Sep1 Cont. Isol. INM25A 2NM25A
~
ND Pume 1A Discharge ', ND Pump 1A Disch Sep1 Line Isol. INM39 2NM39 ND Pumo IB Discharge ND Pump 1B Disch Smpi Line Isol. INM40 2SM40 ! 3.2.5 Turn the position selector knob to " RESET" position. Place the key in the keylock power switch and turn to the right. (" Sample Position"). Press " Reset" button. , 1 + l I - L
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'OP/0/A/6200/21
- Page 5 of 16
( 3.2.6 Place the toggle switch for the dilution water meter to
~
"0N".
3.2.7 Place the toggle switch for the radiation monitor to "0N". ,; Turn the scale switch to " BAT" to check the battery. The needle should travel to full scale. Turn the scale switch to "mR/ hour". The " Rem / hour" scale may be used if readings are off.the scale. .If the radiation monitor is . not functional, rely on Health Physics surveys to determine access to the sample panels. t i 3.2.8 Push in the pH probe " Standardize" knob.
, 3.2.9 Select the system to be sampled with the system selector -
RX COOLANT (refers to NC Hot Leg), RX SUMP (refers to ND Pump. Discharge).
,, 3.2.10 Verify that the pH 6.86 buffer solution has been changed within the last 30 days by referencing Enclosure 6.8 from OP/0/A/6200/11. This enclosure is located in a notebook
-in the PALS drawer.
~
~4.0 ' PANEL OPERATION (Technician #2) 4.1 Initial Conditions 4.1.1 Section 3.0 is complete with the Enclosure 8.1. signed off. '
4.2 Panel Prep (Position 1) 1 4.2.1 Turn the selector knob to the " PANEL PREP" position. 4.2.2 Press the " SELECTION POWER - ACTIVATE" button. 4.2.3 Press the " PURGE" button, hold for 1 minute and release. 4.2.4 ' Press the " DRAIN" button and hold for 30 seconds then release. 4.2.5 Press the " CALIBRATION" button and hold until the pH meter stabilizes.
. 4.2.6 -Adjust the pH meter to the known pH of the standard. ~
Record the time on Enclosure 8.2. .
- 4. 2. 7 . Press the " PURGE" button for 30 secor' id then release.
4.2.8 Press the "FLCSH" button and hold unti, che pH meter stabilizes (pH of dominorslized water) then [' release. (1 to 3 minutes). 4.2.9 l Press the " PURGE" button for 30 seconds and release. < l 4.2.10 Press the " DRAIN" button for 30 seconds and release. l !
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g OP/0/A/6200/21 '. C , i Page 6 of 16 4.2.11 Record the radiation monitor reading on Enclosure 8.2. t (Background) 4.3 Sample Collection (Position 2) 4.3.1 Turn the selector knob to " SAMPLE RECIRC", Position 2. 1 4.3.2 Press the." SELECTION POWER - ACTIVATE" button. The . radiation monitor should show an increased activity level l as the sample enters the liquid panel. Tcl should also i show a temperature increase as liquid enters the panel. Record the starting time on Enclosure 8.2. 4.3.3 Press the " INCREASE FLOW" button gently to adjust flow such f that Tel stabilizes close to 37*C. If Tcl goes above 60*C, sample is not being cooled sufficiently. Press the
" DECREASE FLOW" button and if temperature -still increases, turn the selector knob to " RESET", press the " RESET" button and turn " POWER KEY" to a vertical position. Call the-Primary Supervisor or his desigdee.
The " INCREASE FLOW" button increases sample flow and thus increases the sample temperature, Tcl, as long as it is
, ,,. depressed. .
4.3.4 If Tel stabilizes below 37'C, depress the "I'SCREASE" button for not more than 1 second. Let Tcl stabilize. Repeat this step until 37'C is reached. 4.3.5 When the sample temperature stabilizes (5-8 minutes), record the minutes required for stabilisation, the temperatures of Tel and Tc2, and times on Enclosure 8.2. 4.3.6 Purge the sample for twice the amount of time it took Tcl to stabiliz,e. 4.3.7 ' Turn the selector knob to " SAMPLE", Position 3. 4.4 Sample (Position 3) 4.4.1 Press the " SELECTION POWER - ACTIVATE" button.
, 4.4.2 Monitor the temperature gauge and when Tcl stabilizes -
record the radiation readings on Enclosure 8.2. 1 4.4.3 Subtract the initial background activity, (Section 4.2.11) from sample activity found during Tcl stabilization (Section 4.4.2) and record on Enclosure 8.2. This is the radiation due'to the sample.
. 4.4.4 Press the " PRESSURIZE" button momentarily. When the pressure stabilizes record the reading on Enclosure 8.2.
Record-this time as the " Time Sample Purge Isolated" on
' Enclosure 6.2.
Y . ?
T g OP/0/A/6200/21 C ,. A Page 7 of 16 4.4.5 Press the " TRAP" buttor. momentarily. i -: 4.4.6 - Take the rime Sample Purge Isolated" (#10) from Enclosure'8.2 and subtract " Minutes Required for Stabilization of Temperature" (#4) to obtain the time the sample actually left the system. Record on Enclosure 8.2. 4.4.7 Turn the selector knob to "DEPRESSURIZATION AND GAS 4 STRIPPING", Position 4.
. 4.5 Depressurization and Gas Stripping (Position 4) 4.5.1 Verify that the vacuum gauge on the control panel shows at least 25 inches mercury.
4.5.2 Press the " SELECTION POWER-ACTIVATE" button. Vait at j least 60 seconds and then verify the Incoming Sample ; Pressure gauge reads 0 t 10 psig pressure. , 4.5.3 Press the " GAS STRIPPING START" button momentarily beneath the water totalizer and monitor the vacuum gauge. Press the " GAS STRIPPING STOP" button momentarily when the vacuum gauge needle reads 19 1 inch mercury. If 1 inch is . not achieved,'a new stripped gas sam *ple will need'to'be'taken
-(i.e.) start from Section 4.2.
4.5.4 Turn the selector knob to " LIQUID SAhPLE", Position 5. (* V. 4.6 Liquid Sample (Position 5)/ Liquid Sample Prep (Position 6) 4.6.1 Press the " SELECTION POWER-ACTIVATE" button. 4.6.2 Press the " GRAB SAMPLE" button momentarily. 4.6.3 Preset the dilution water flow totalizer for 250 ml and " press the " RESET" button. Press the " START" button,and
'let the dilution continue to completion. Record the dilution volume on Encl.osure 8.2 4.6.4 Press the " LIQUID SAMPLE PREP-MIXING" button and hold for 10 seconds.
. 4.,6.5 Press the " LIQUID SAMPLE-pH" button, momentarily. Allow -
the meter to stabilize. 4.6.6 Record the pH reading on Enclosure 8.2. . 4.6.7 Press the " GAS SAMPLE - TRAP OPEN" button momentarily. Wait 10 seconds. 4.6.8 Press th' e" GAS SAMPLE - TRAP CLOSE" button momentarily. 4.6.9 Turn the selector knob to position 7 " LIQUID SAMPLE". t .
! .C {OP/0/A/6200/21Prgs 8 of 16 h
4.7 Liquid Sample (Position 7) {r
- 4. 7.1 - Press the " SELECTION P0h'ER-ACTIVATE" button.
4.7.2 Hold the " LIQUID SAMPLE-TRAP OPEN" button for 30 seconds. 4.7.3 Immediately after 30 seconds, press the " LIQUID SAMPLE-TRAP CLOSE" button momentarily. Wait 30 seconds. 4.7.4 Turn the selector indu to " FLUSH", Position 8. 4.8 Flush (Position 8) 4.8.1 Press the " SELECTION POWER-ACTIVATE" button. 4.8.2 Press the " FLUSH STEP" button momentarily and wait 1 minute. The first flush light should be lit. (Gas Tank). 4.8.3 Press the " FLUSH STEP" button momentarily and wait for the pH and conductivity meters to read the pH of demineralir.ed water, 2-3 minutes. Second flush light should be lit. (Probes) .
,, . 4.8.4 Press the " FLUSH STEP buttoA momentarily and wait 4 '
. minutes . Third flush light should be lit. (Dilution Tank) 4.8.5 Press the " FLUSH STEP" button momentarily and wait, 1
,, minute. Fourth flush light should be lit. (Liquid Tank) 4.8.6 Press the " FLUSH STEP" button momentarily. This
~
terminates the flushing cycles and the " COMPLETE"
^ " light turns on.
4.8:7 Turn the selector knob to " DRAIN", Position 9. 4.9 Draisc(Position 9) 4.9.1 Press the " SELECTION POWER-ACTIVATE" button. 4.9.2 Press the " DRAIN STEP" button momentarily and wait 8 minutes. First drain light should be lit. (Dilution Tank).
. 4.9.3 Press the " DRAIN STEP" button momentarily and wait 1 -
minute. The second drain light should be lit. (Gas Line) 4.9.4 Press the " DRAIN STEP" button momentarily and wait 3 minutes. The third drain light should be lit. (Gas Tank) 4.9.5 Press the " DRAIN STEP" button momenta~rily and wait 1 - minute. The fourth drain light should be lit. (Probe refill and system vent). 4.9.6 Press the " DRAIN STEP" button momentarily. This terminates the draining cycles and the " COMPLETE" light is illuminated.
[T' _ _ . _ t f . Ef 'OP/0/A/6200/21
.A .. A Paga 9 cf 16 ; 4.10 Roset ;- 4.10.1 Turn the selector knob to " RESET" and press the " RESET" button.
4.10.2 If the " PUMP SUMP" light is lit, it indicates the sump has L water in it. Turn the SYSTEM POWER KEY to the left to-l operate the sump pump. .The " PUMP ON". light will light and remain on until the pump has stopped. 4.10.3 After the " PUMP COMPLETE" light turns on, indicating that the pump has stopped, turn the SYSTEM POWER KEY to the right to re-energize the PALS. 4.10.4 Contact the Control Room and have them close the sample valves opened in Section 3.2.4 4.10.5 Record the radiation level after flushing on Enclosure 8.2. If the field at the panel is greater than 3 Rem /hr. (3000 mR/hr.), go to Section 5.0. 4.10.6 If this is the last sample to be coll'ected this trip. . proceed to Section 4.11, Sample Panel Shutdown.. If other samples are to be c6Jlcceed this trip proceed td 'Section 6.0, Sample Retrieval. 4.11 Sample Panel Shutdown ( 4.11.1 Turn the SYSTEM POWER KEY to the vertical off position
~
and turn the position selector knob to " RESET". 4.11.2 Place the panel keys in a plastic bag with Enclosure 8.1 (NC or ND Loop data). , 4.11.3 Turn the toggle switch for the dilution water meter to "0FF". 4.11.4 Turn the toggle switch for the radiation monitor to "0FF". 4.11.5 Pull out the pH probe standardize knob. 4.11.6 Proceed to Section 6.0, Sample Retrieval. 5.0 DECONTANINATION 4 5.1 Repeat the panel Flush. Drain and Roset Modos: Sections 4.7.4 through 4.10.3. 5.2 If the level is less than 3 Rem / hour, turn the SYSTEM POWER KEY to the vertical position and continue with Section 4.10.6. If however,
- - the radiation level remains greater than 3 Rem / hour, go back to
- Step 4.2 and reptat the sequence using a larger dilution volume based on the caltulations of Enclosure 8.4 a
t I
=
hi y r - OP/0/A/6200/21 C- .. Page 10 of 16 I 6.0 SAMPLE RETRIEVAL l
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l r g.- 6.1 Initial Conditions i 6 .1.1 - A gas and degassed liquid sample are in the gas and liquid samplers, respectively through the completion of Section 4.0. 6.1.2 Health Physics personnel are providing continuous monitoring of the area.
' 6.2 Sampling 6.2.1 Take two labels from the PALS drawer. Till out the labels-as follows (including the required information):
Label one: " Liquid Sample Name Initials Date Actual Sample Time Dilution Water Added " Label the other: " Gas Sample Name . Initials
~.
Actual Sample Time' " ~ The " Actual Sample Time" and " Dilution Water Added"'may be found on Enclosure 8.2, #11 and #12, respectively. (, 6.2.2 Take a 56 al Nalgene sample bottle from the PALS drawer. Label it as follows:
" Dilution Wate- lample Date "
6.2.3 Take the completed labels and place each one on a plastic bag. Place another plastic bag inside of each of the two
" labeled plastic bage. These will be used later for double bagging the samples.
CAUTION: Do not approach the samplers on the sample panel until a Health Physics Technician has surveyed the area. Do not relay solely on the _ PALS panel's radiation monitor (1NMMT5350) as an indication the radiation in the area. (Ocit during periodic testing). 6.2.4 Approach the samplers located on the sides of the sample ' panel. If possible, have the Health Physics Technician take an contact readings on each sample vessel. (Omit during periodic testing). i 6.2.5 Detach the quick-disconnects on each sample vessel. Place l- the samplers in the labeled plastic bags. Seal tightly. 6.2.6 Place the samplos in the sample carrier. l -
- l. -
k4 HP/0/B/1009/03 Pega 3 of 3 I .! 4.2.1 The Health Physics Shift Technician on duty shall initiate r the T.B. 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.
4.2.2 The Health Physics Shift Technician on duty shall collect - a 3500 m1 liquid saaple using a new Marinelli beaker. The sample shall then be submitted to the Counting Room per reference 2.6. NOTE: If T.B. sump sample results indicate net activity above background and, EMF-33 is out of service, refer to 4.1.2. 4.2.3 If the T.B. sump sample results indicate no net activity above background, refer to reference 2.7. 4.2.4 If the T.B. sump sample results indicate net radioactivity above background, notify Operations and Radwaste Chemistry per T.B. Sump Sample Log (Sample Enclosuge 5.2). 4.2.4.1 Chamistry 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
/" > 2.6 and 2.8.
(. . 4.2.4.3 Sampling frequency of WC Mixing and Settling 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 new liquid Marinelli beaker and submitted to the Counting Room per references 2.4 and 2.6. 5.0 ENCLOSURES 5.1 Sample Enclosure C.S. A.E. Sample Log 5.2 Sample Enclosure T.B. Sump Sample Log O t
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DUKE P0hT.R COMPANY l CATAWBA NUCLEAR STATION ] HP/0/B/1009/03 j SAMPLE ENCLOSURE 5.1 ,
, h ,
-C.S.A.E. SAMPLE LOG -
'This 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 Condensate Steam Air Ejector (EMF-33), record the following: Operations Rep. Date/ Time / H.P. Rep. Receiving Call '
- 2. Unit # .
Remarks: l 1
- 2 i
- 3. If C.S.A.E. Sample results indicate net radioactivity above background, (s. notify.
Radweste Chemistry Rep. Date/ Time / i
. +
; Operations Rep. Date/ Time /;,
.* t Notified by H.P. Rep.
i .] i 4. The sampling frequency may change during the primary / secondary leakage, a j i 4 as deemed necessary by supervision. Record all changes below. ' Initiated New Health Physics : i H.P. Sampling Frequency Shift Technician j l Supervisor Once Every Date/ Time Recordina Chanze : i j Hours On / j i,_ t Hours on / i Hours On / l- Hours On / ! 4 j l Hours On / ' Hours On / . t 4 4 6 l h
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o 1 1 Pags 2 of 2 l 1 DUKE POWER. COMPANY CATAWBA NUCLEAR STATION. HP/0/B/1009/03 4' c SAMPLE ENCLOSURE 5.1 C.S.A.E. SAMPLE LOG Sample Once Date/ Time Per Hrs. of Sample Signature Remarks - f a a 9 9 1 (* 1 .... i h f d 1 I 6 i
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DUKE POWER COMPANY
-CATAWBA NUCLEAR STATION HP/0/B/1009/03 SAMPLE ENCLOSURE 5.2.
; T.B. SUMP SAMPLE LOG -
I This form is to be used any time a primary to secondary leak is indicated. p -
- 1. Upon notification from Operations that a primary to secondary leak is indicated per Turbine Building Sump (EMF-31), record the fcilowing: ;
Operations Rep. Date/ Time / H.P. Rep. Receiving Call i
- 2. Unit #
4 Remarks: 1 ! 3. If T.B. Sump Sample results indicate radioactivity above 10CFR20 Table r" II Col. II, notify the following representatives that-batch releasing is b required: 4 i Radwaste Chemistry Rep. Date/ Time -/ l Operations Rep. Date/ Time / Notified by H.P. Rep. f
, 4. The sampling frequency may change during the primary / secondary leakage, j as deemed necessary by supervision. Record all changes below.
Initiated New Health Physics H.P. Sampling Frequency Shift Technician Supervisor Once Every Date/ Time Recording Chanze Hours On / 3 , Hours On / 1 Hours On / i-Hours On / , l Hours On / .
'" t
- Hours On / -
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DUKE POWER COMPANY CATAWBA NUCLEAR STATION HP/0/B/1009/03 SAMPLE ENCLOSURE 5.2 T.B. SUMP SAMPLE LOG Sample Once Date/ Time Per Hrs. of Sample Signature Remarks f I 6 g P I L s l r em i i
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,, ' Form 34731 (10 81)
(Formerly SPD-10021) DUKE POWER COMPANY (1) ID No: HP/0/B/1009/05 PROCEDURE PREPARATION Change (s) O to ' s PROCESS RECORD 3 Incorporated (2) STATION: Catawba Nuclear - (3) PROCEDURE TITLE: Personnel / Vehicle Monitoring For Emeraency Conditions (4) PREPARED BY: 4lP7. M e. l . bl DATE: T-G-44
- I (5) REVIEWED BY: M 7. /t,4 DATE: / -l-/V Cross-Disciplinary Review By: N/R: / 7 M (6) TEMPORARY APPROVAL (IF NECESSARY):
! Bye (SRO) Date:
l . f By: Date: , (7) APPROVED BY: W Date: II y i '
?
(8) MISCELLANEOUS: ' 4 Reviewed / Approved By: Date: Reviewed / Approved By: Date: i i f i I
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s HP/0/B/1009/05 i DUKE P0hTR COMPANY
" CATAWBA NUCLEAR STATION 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 REFERENCES
f 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 Response 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 i 2.8 Station Directive 3.8.3, Contamination Provention, Control, and l Decontamination Responsibilities 2.9 Catawba Nuclear Station Emergency Plan i 3 2.10 System Health Physics Manual 3.0 LIMITS AND PRECAtTTIONS 3.1 If survey teams are expected to be exposed to I-131 in excess of 70
~
MPC (6.1 x 10 ' pCi/ml), 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 Reference 2.1. 3.3 If emergency vehicle is found to be contaminated as per Reference 2.8, Section 6, and alternative transportation is not available, that vehicle may be released if needed for assistance and be decontaminated to below acceptable limits at the first opportunity as per Reference 2.3. , I
HP/0/B/1009/05 Pago 2 of 4 4.0 PROCEDURE 1
, [ 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 - 1 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 ccpm for friskers. 4.1.3 The RP/PM Leader shall also arrange for monitoring of the assembly points and initiate action when dose rates reach 2 mr/hr. 4.2 The RP/PM Leader shall dispatch an Emergency Pers,onnel Monitoring Team to the following locations upon initiation of a site assembly resulting from a radiological incident. . 4.2.1 Personnel Access Portal (PAP) fl 4.2.2 Construction Personnel Exit Area (Brass Gate). NOTE: Manpower shall be supplied with respect to the nature of the accident and the availability of Health Physics Personnel. # 4.2.3 Each survey team shall have a copy of HP/0/B/1009/05 Personnel Monitoring for Emergency Conditions, Catawba ' Nuclear Station Directive 3.8.3 Contamination and Decontamination Responsibilities and an Personnel Monitoring Kit. 4.2.4 Upon reaching their designated locations, the survey teams shall verify their position with the RP/PM Leader. 4.2.5 The Construction Personnel Exit Area Team shall insure all personnel receive proper monitoring leaving via this exit during evacuation. 4.2.6 The PAP Area Surv'ey Team shall insure that the portal monitors are used properly and provide additional monitoring 1 - in order to expedite evacuation. l t f l l l L i
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l - 7 l[ HP/0/B/1009/05
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Pega 3 of 4 i-
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l '4.2.7 If an individual is found to be contaminated as per Refer-i ence 2.8,.the survey team shall: 4 I (' ' . U 4.2.7.1 Dress the individual in the appropriate
, protective clothing and when time permits,
; decontaminate as per Reference 2.2.
t ' t _
'l 4.2.7.2 Notify the RP/PM Leader of all cases of personnel ,
contamination. 4.2.8 Survey teams should be supplemented, relieved or secured as directed.
- 4.2.9 Survey teams shall monitor dose rates at exit areas.
+
Should dose rates exceed 2 mr/hr, team shall initiate
'{ discussion with RP/PM Leader to expedite any evacuation through that exit point.
4.2.10 The RP/PM Leader should notify the Surveillance and
, Control Coordinator of all actions taken.
4.3 The RP/PM Leader shall dispatch a team to monitor sight assembly t 3 points as listed in Reference 2.7. ~ 4.4 The RP/PM Leader shall assemble another Emergency Monitoring Team i upon initiation of a site assembly from a radiological incident for random monitoring of employee vehicle and when site evacuation is ; initiated, dispatch this team to the Evacuation Facility (site f Alpha: Transmission Line Maintenance Warehouse near Hwy SC 274 and [ t SC 161. Site Bravo: Allen Steam Station, Hwy NC 273, South of Belmont). NOTE: Monitoring equipment for vehicles is located in the
- Personnel Monitoring Kit located in the PAP area.
- 4.4.1 If a vehicle is found to be contaminated as per Reference i
t 2.8, the survey team shall 4.4.1.1 Prevent further movement of the vehicle. ! 4.4.1.2 Post the vehicle as a contaminated area. i 4.4.1.3 Provide general information on contamination surveys to the RP/PM Leader. 4.4.1.4 Monitor all vehicles in the area for contamination. i 4.4.1.S Decontaminate Vehicle using best method (s) - available on property owned by Duke Power - Company that does not drain to a water system. ' 4.4.2 Upon site evacuation and notification of Evacuation Facility (Alpha or Bravo), the RP/PM Leader shall move ( the monitoring team to the Evacuation Facility who shall: i 1
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iT ' HP/0/B/1009/05 Paga 4 of'4 ' I 4.4.2.1 Locate Personne1' Survey Kit at evacuation - Facility and prepare to monitor incoming j (# , personnel. Personnel Survey Kit storage { locations are identified on the Evacuation Facility Layout Drawing,(Enclosure 5.1).
\, -
4.4.2.2 Supervise the monitoring and release of - personnel 4.2.10. as described in Steps 4.2.3 through
- 4.4.2.3 List all personnel's names, social security number and Health Physics badge number on
} Evacuation Personnel Dose Record Sheet, (Enclosure 5.2). This form should be used for '
dose commitment at'a later time. { 4.4.2.4
; Supervise monitoring of employee vehicles and take action as appropriate per Step 4.3.1.
4.4.2.5 Notify RP/PM Leader or S & C Coordinator of all actions taken. , 4.5 If background radiation readings render frisker and/or pohtal monitor useless, the RP/PM Leader, shall: 4.5.1 : Discuss with the Surveillance and Control Coordinator relocating of lower background. the personnel monitoring location to a location , 1 4.5.2 Procure from the Temporary Administration Building a 20 watt portasoble radio for communication with the OSC. Check operability of the radio,
, 4.5.3 Nove the monitoring teams to an area of lower background monitorpersonnel where personnel.control can be maintained and prepare to r
4.5.4 Supervise the monitoring and release of personnel as i described in Steps 4.2.3 through 4.2.10. 'l 4.5.5 ; i Supervise monitoring of employee vehicles and take actions as appropriate per Step 4.3.1. , 4.5.6 > Notify taken. Surveillance and Control Coordinator of all actions i, 5.0 ENCLOSURES' 5.1 I Sample of Evacuation Facilities Layout Drawings , 5.2 Sample of Evacuation Personnel Dose Record ) I l 6 1 u, - l ' l m---,my,. , ,-,. .-- - --,,,-v,--y----- - , -+-e---
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Pogo 1 of 3 a ( llP/0/B/1'009/05 - i g Enclosure 5.1 s Evacuation Facility Layout Drawing h - - _ .; _ _ _ _ _ _n. _ __ _ _ _ _a _ _ _ _ _ _ r, _____a______r
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Page 2 of 3 HP/0/B/1009/05 c Enclosure 5.1
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. HP/0/B/1009/05 Enclosure 5.1
'FlAST Ano ME C.6EATa O N h l
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Enclosure 5.2 HP/0/B/1009/05 Paga of s EVACUATION PERSONNEL DOSE RECORD
- . i i NAME SOCIAL 'H.P. ' DOSE COMMENTS l SECURITY BADCE- (aram)
NUMBER NUMBER ,
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Form 34731 (1041)
- (Formerly SPD 10021) -
DUKE POWER COMPANY (1) ID No: HP/0/B/1009/07 PROCEDURE PREPARATION Change (s) O .to PROCESS RECORD 1 Incorporated 4 (2) STATION: Catawba Nuclear (3) PROCEDURE TITLE: In-Plant Particulate And Iodine Monitoring Under
- Accident Conditions (4) PREPARED BY: fFf . DATE: T - G - T 84 (5) REVIEWED BY: M? h DATE: / -t - / 4' Cross-Disciplinary Review By: N/R: J. 7 M (6) TEMPORARY APPROVAL (IF NECESSARY):
By: (SRO) Dete: By: Date: (7) APPROVED BY: y V
/ Date: [
i i (8) MISCELLANEOUS: Reviewed / Approved By: Date: l Reviewed / Approved By: Date: i I 1 i i 1 l
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; HP/0/B/1009/07
[ , DUKE POWER COMPANY CATAWBA NUCLEAR STATION i IN-PLANT PARTICULATE AND IODINE MONITORING UNDER ACCIDENT CONDITIONS l 1.0 PURPOSE To provide a method of particulate and iodine assay in the plant under accident / emergency 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 HP/0/B/1003/02 - Operating and Calibration Procedure: Low Volume, Portable Air Samplers 2.3 HP/0/B/1009/16 - Distribution of Potassium Iodide Tablets in the Event of a Radiciodine Release 2.4 Catawba Nuclear Station Emergency Plan - Section I.2
2.5 NUREG-0694
TMI - Related Requirements for New Operating Licenses 3.0 LIMITS AND PRECAUTIONS 3.1 This procedure is written for use only under abnormal accident / emsrgency conditions when normal methods of quantifying iodine are not available. 3.2 Purging of silver zeolite 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 from I-131 in excess of 70 MPC (6.1 x 10 pCi/ml), and directed by the S&C Coordinator, technicians should ingest one tablet of Potassium Iodide as per Reference 2.3. 3.5 Respiratory protective equipment should be used where possible to
, limit uptakes.
l l l
.-. _ _ _ _: _ _ _. _ - l
_ = - . _ . . . . . . _ _ v,_.
, E- 'i
't .v,'
HP/0/B/1009D7 '+
,' ,i Pega 2 cf 3 '
e 4.0' PROCEDURE
,4.1 Sample Collection and Preparation 4.1.1 Using filter paper and'a silver zeolite cartridge, collect a representative sample per references 2.1.and 2.2.
Qn . ' w - 4.1.2 Remove and separate the filter and the cartridge. Place-each in an individual sample bag and label accordingly. 4.1.3 In order to remove unwanted (i.e.; Xenon,' etc.) gases from the cartridge, purge as follows: y 4.1.3.1 Remove the cartridge from the sample bag and place it in a sample holder with a clean filter. 4.1.3.2 Orientthesampleholdersuchthat\flowwillbe in the same direction as during collection. , NOTE: Care should be taken,since a high i purge flow rate could~cause a release of Radioactive Iodine from the cartridge. 4.1.3.3 Crack open cl$e parge valve until a low purge i rate is noticed. Purge for about one third the time of sample durstion at low purge flow. i
, V 4.1.3.4 Remove the carttiage and place in a clean sample '
' bag. Mark the bag with original sample informa-tion, and note the purge data and time. 4.1.4 Transport samples to an adequate sample lcisunting location, i and complete the top portion of the Emergency Particulate / } Iodine Assay Form (Enclosure 5.1). 1 4.2 Iodine Activity Determination '
.1 4.2.1 With the cartridge still in the bag determine'the dose rates; at 1/2 inch from the inlet face of the cartridge.
4.2.1.1 For samples reading > .1 ares /hr above2 j ' background on a low range survey instrument, record the dose rate on Enclosure 5.1. NOTE: Derivations of formulas used on Enclosure 5.1 are provides on i Enclosure 5.2. i 4.2.1.2 For samples reading <.1 ares /hr above background, use an RM-14/HP-260 or equivalent to L determine corrected counts per minute (ceps). l t I ,
\'
7 Q. ~ > Y HP/0/B/1009/07 h;c4 - Pcg3 3 cf 3 a .c , . , o s - c. c' Divide the ccps by 3600 (or other correction
!' j factor if available) to determine area /hr, and ., dY , record on Enclosure 5.1. ! ) -
l 4.2.2 Complete the " Iodine Activity" section of Enclosure 5.1 to N. ' - l.' determine Iodine Activity. ' l t -c s - 4.3 Particulate Activity Determination (Gross)
,, 4.3.1 Remove the filter paper from bag for counting.
4.3.2 If a scalor is available, use it to count the filter paper and record results and other necessary data on Enclosure
, 5.1.
5
+i" 4.3.3 If a scalor is not available, use an RM-14/HP-210 or n' ,
equivalent and record the average corrected counts per minute. If no efficiency factor is available, use 10. i t 4.3.4 Complete the " Particulate Activity" section of Enclosure 5.1 to determine particulate activity. 4.3.5 Return the filter paper to its bag. 4.4 Sample and data handling 4.4.1 Attach the samples to a copy of the completed Enclosure 5.1 and hold for possible further analysis. 4.4.2 Notify appropriate personnel of results. 5.0 ENCLOSURES
,,, 5.1 Sample of Emergency Particulate / Iodine Assay 5.2 Derivation of Activity Calculation Formulas s .e,
\' \
.. ~ t c *- i
\ \
L \ 4 \ g e s l_h
7 j HP/0/B/1009/07 )
. Enclosure 5.1 '
l 3 : i l EMERGENCY PARTICULATE / IODINE ASSAY l i
;, . I. Sample Location Date 1 ;- . Start Time Performed By.
j Stop Time Air Sampler Typa/No. / _
! Sample Duration Flow Rate.
Sample Volume ( l ft* = 2.83E4 cc-) IDDINE ACTIVITY Instrument Type /No. / Sample Dose Rate @ 1" = mram/hr (A) x 28.2 Iodine Activity = = uCi (B) cc Where: A = Sample Dose Rate in mres/hr B = Sample Volume in cc (or al) (. PARTICULATE ACTIVITY Instrument Typa/No. / Background Efficiency Factor , Total Counts + Count Time = cpm cpm - Background = ccpm (A) x (B) x 4.5E-7 Gross Particulate Activity = = (C) pCi cc
.a Where: A = cepm 3 = Efficiency Factor in dpm/ cpm C = Sample Volume in cc (or ml)
Remarks: i _ ( l
, , . - . , , - .-, .- ,s. . - , ,
HP/0/B/1009/07 Enc 1csura 5.2 Pag 2 1 of 2 r DERIVATION OF ACTIVITY CALCUIATION FORMULAS
~
- 1. Iodine Activity I-131 5 = .19 Mt.V for beta -
volume of cartridge, v = wr*h
= w'(1.13 in x 2.54 cm/in)* x (1.04 in x 2.54 cm/in)
= 67.76 cm 8 mass of cartridge, m = 4 oz x 28.35 gm/oz = 113.4 gm density of cartridge, p = m = 113.4 gm = 1.67 gm/cm 8 v 67.76 cm' thickness of cartridge, x = 1.67 gm/
- x (1.04 in x 2.54 cm/in)
= 4.41 gm/cm 8 ,
.19 HeV beta particle energy range = 40 mg/cm 8 .
(p. 123, Rad Health Handbook) absorption coefficient, y= 1 = .025 cm 8/mg 40 mg/cm' s self absorption correction: (p. 136, Principles of Radioisotope Methodology, Third Ed.)
-px fs=1-e fs = self absorption coefficient px y = absorption coefficient, em'/mg x = sample thickness, mg/cm'
.025 cm8 /mg x 1000 mg/gm x 4.41 gm/cm*
, fs = 1 - e = .009
.025 cm3 /mg x 1000 mg/gm x 4.41 gm/ca' I mR/hr x 87.8 erg /rm x 1R x 1 MeV x 1 hr x 1 uCi
-6 R 1000 mR 1.6 x 10 erg 3600 sec 3.7 x 10' dps x d x 113.4 gm = .245 pCi
. .19 MeV so, .245 uCi = .245 pC1/mR/hr 1 mR/hr 4
4 e - -
i HP/0/B/1009/07 c Enclecura 5.2 : Pcg2 2 cf 2 s 4
. . DERIVATION OF ACTIVITY CALCULATION FORMULAS i
.245 uCi/mR/hr = 28.2 vCi/mR/hr
.009 mR/hr x 28.2 vC1/mR/hr = uCi-
, CC CC assume 1 mR = 1 mrem
; 2. Particulate Activity
-7 ccom x dom / cpm x 4.5 x 10 uCi/ dom = UCi cc cc
- 1 e
6
\. e t
6 t J W P 4 6 9 i
. m i
s - ,- ,, - ,, , - e - e
7 l I Form 34731 (10 81) (Formerly SPD-10021) DUKE POWER COMPANY (1) ID No: HP/0/B/1009/12 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD I Incorporated (2) STATION: Catawba Nuclear (3) PROCEDURE TITLE: Ouantifving Gaseous Release Through Steam-Relief Valves Under Post-Accident Conditions (4) PREPARED BY: W. } DATE: T - Co - T 4 (5) REVIEWED BY: _ LXd 2 / DATE: -/ -N Cross-Disciplinary Review By: N/R: /. ? N.A (6) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: (. By: Date: (7) APPROVED BY: Q W- Date: I/h f / (8) MISCELLANEOUS: . Reviewed / Approved By: Date: Reviewed / Approved By: Date: 9 l
5
,- HP/0/B/1009/12 i
DUKE F AER COMPANY CATAWBA NUCLEAR STATION
-QUANTIFYING GASEOUS RELEASE THROUGH STEAM-RELIEF VALVES UNDER POST-ACCIDENT CONDITIONS 1.0 PURPOSE To describe a method for calculating total noble gas and radiciodine activities released through steam-relief valves under post-accident i
conditions.
2.0 REFERENCES
2.1 Catawba Nuclear Station FSAR Vol. II, Table 11.1.1-2 and 11.1.1-4 2.2 Catawba Nuclear Station Computer System Documentation, Rev. 9/1/83, Sec. 3.2.19.0, Main Steam Release Monitoring i
! 2.3 ,Intter from Design Engineering Providing Correlation Curves i
dated April 30, 1984 CN-1229.01
!! 2.3.1 Figure 1 - Main Steam Line Radiation Monitor Correlation 'l Curve. Correlation Factor, S' vs. Time after
<l '
, Reactor Shutdown.
A ,' e 2.3.2 Figure 2 - Main Steam Line Radiation Monitor Correlation Curve Magnified First Two Minutes Response S' vs.. Time. - 2.4 ASME Steam Tables 4 3.0 LIMITS AND PRECAUTIONS d 3.1 The value used for specific gravity (.4 ft'/lb.) in Step 4.2.1 is i, , an ave rage based on Tsat of 560'T and Psat of 1100 psia, (Ref. 2.4). i 3.2 The Main Steam Release Accumulator Program (MSR) calculates pounds mass (lba) losses from each stsam generator loop. The following ' table indicates relationship between steam line monitors and steam ' generator (S/G) loop losses as calculated by MSR, (Ref. 2.2): IEMF / 2 EMF S/G (LOOP)
- 26 10 S/G A = (PORV (A) + Dump (A) + Safe (A)) ;
27 11 S/G B = (PORY (B) + Dump (B) + Safe (B) + AFWPT (B))
'28 12 S/G C = (PORV (C) + Dump (C) + Safe (C) + AFVPT (C))'
29 13 S/G D = (PORV (D) + Dump (D) + Safe (D))
- 3.2.1 The S/G Loop calculations above result in overestimations of losses occurring through loops B and C (accounts for all b
y + -
. - +~. - , , . , -, . - . .
l[L HP/0/B/1009/12 Page 2 of 4
/ } ' AFWPT losses), and underestimates losses occurring through P
f loops A and D (no AFWPT loss accounting), 3.2.2 MSR Program does not account for valve position modulation , and overestimates steam loss approximations. Calculations .- are based on the assumption that valves are fully open { when read to be in any condition other than " Closed". I 3.3 Reporting requirements of Station Directive 2.8.1 and HP/0/B/1009/02 shall be evaluated to ensure that the Shift. Supervisor and/or the Licensing Engineer are informed of the requirements. 4.0 PROCEDURE l 4.1 Obtain and record the information listed below on Main Steam Gaseous Activity Release Record, (enclosure 5.1) following a steam release event, when directed: 4.1.1 Unit number. 4.1.2 Date of the steam release. . 4.1.3 Time the steam release started.
. 4.1.4 Time the steam release ended.
4.1.5 Steam-line EMF readings (R/hr). 4.1.5.1 Use the highest steam-line EMF reading that most closely corresponds with steam release event time interval. 4.1.6 Date and time the EMF readings were recorded. 4.1.7 S' value for each steam-line EMF, (Ref. 2.3). 4.1.7.1 Use Figure 2, Main Steam Line Radiation Monitor Correlation Curve Magnified first two minutes response S' vs. time, if steam release event occurs within two minutes of reactor shutdown. 4.1.7.1.1 Locate " hours after Rx trip" on X-axis and move up graph to corresponding S' value on Y-axis. 4.1.7.2 Use Figure 1, Main Steam Line Radiation Monitor Correlation Curve, if steam release event occurs greater than two minutes after reactor trip.
HP/0/B/1009/12 Page 3 of 4 r
; g- 4.1.7.2.1 Locate " hours after Rx trip" on i H ,
X-axis and move up graph to ' corresponding S' value on Y-axis. 4.1.8 Total quantity of steam released in pounds mass (Iba) from each steam generator loop. '
) 4.1.9 Reactor trip date and time.
~
4.2 Calculate total gas activity released from each S/G loop as follows: 4.2.1 A *
- NG(n) I / #) * "S/G(n) 3 y 68 U 2 (C W ec)
(Ib)(pCi) Where: ANG(n) = t tal n ble gas activity release from S/G 4 Loop A, B, C, or D in Curies S' = pCi/cc Xe - equivalent. correlation factor R/hr from curve (Sample Enclosure 5.2) EMF = Main Steam - Line Monitor reading in R/hr IbmS /G(n)X = total quantity of steam released in pounds mass (Ibe) for S/G Loop A, B, 6' h ' C, or D. Includes main steam atmospheric dump and AFWTP losses associated with S/G loop. 1.13268 E-2 (C1)(ce) = (.4 ft'/lb x 28317 cc/ft' x IE-6 Ci/pCi) (Ib)(DCi) constant converting pounds mass to ft'; cubic feet to ce; and pCi to Curies;- such that unit analysis for expression balances to Curies. 4.2.2 Record noble gas activity released per S/G on Enclosure 5.1 4.3 Sum noble gas activities released form contributing S/Gs as follows:
.3.1 IA "A +
NG NG(A) + ANG(B) NG(C) + NG(D) 4.3.2 Record sum total of noble gas activities released on Enclosure 5.1. 4.4 Calculate the radioiodine activity released from each S/G loop as follows: 4.4.1 AI (n) " k'G(n) x 0.0003 Where: AI (n) = t tal iodine activity released from S/G Loop A, B, C, or D. I
j; 1 l HP/0/B/1009/12 j~ Page 4 of 4 O.0003 = the fraction of the total noble gas plus iodine activity in the reactor coolant system that is equal to the radiciodine activity;
, corrected for partition from water to steam (Ref. 2.1). _
4.4.2 Record the radioiodine activity' release per S/G's on 1 Enclosure 5.1. 4.5 Sum radioiodine-activities released from contributing S/Gs as follows: 4.5.1 EA =A +A +A +A I I(A) I(B) I(C) I(D) 4.5.2 Record sum total of radioiodine activities released on Enclosure 5.1. 4.6 Sign the appropriate line marked " Prepared By" on Enclosure 5.1. 4.7 Record the date and time the calculations were performed on appropriate line of Sample Enclosure 5.1. 4.8 Route results (Enclosure 5.1) to Data Analysis Coordinator.
. 5.0 ENCLSOURF.S
(_ 5.1 Sample of Main Steam Gaseous Activity Release Record 5.2 Figure 1: Main Steam Line Radiation Monitor Correlation Curve Figure 2: Main Steam Line Radiation Monitor Correlation Curve Magnified First Two Minutes b o r w s
Duur POWLR COMPANY rcye e we
- CATAW8A NUCLEAR STAtt0Il 8 IIP /#/2/1009/12 ENCLOSURE 5.1 11AIN STEAM CASEOUS ACilVITY RELEASE CECORD Dete/ Time /
CGCctor Trip Date/ Time / Prepared By l l lA ) (A ) l s' NG(n) f(n) Unit Steam Release Steen Line Time Main Stese Noble Gas Activity ledine Activity No. Joe Interviil Moni goy After LeC l/CC Release Start Stop R/hr Datef irly R/6er Iba Released Per S/G Released Per S/G Date Time time Time (hrs) Curles Curles S/G fAl S/G 151 ifc__1C I S/G foi A = A = NG l< Dete/ Time / Reactor trip Date/ Time _/ ,____ Propered By 1A I (A ) Unit Steam Release Steam Line Time S' Main Steam NGin) 1(n) No. _ Tim 9 Jnterval_ _ .. ._ ,Mqnllo rs _ ,, After oc.i /_cq Release Noble ces Activity lodine Activity Start Stop It/h r Date/ Trip R/hr Ibn Italeased Per S/C Released Per S/C Date Time time Time (hrs) Curles Curles 7/_c_ n L _._ .
}/_G__(111 SLC_LCJ ._ ____
S_/G tD L __ __. __ A = A w NC I D
e ny.
i 4 i Pags 1 of 2 4' DUKE POWER COMPANY i CATAWBA NUCLEAR STATION i , HP/0/5/1009/12 ENCLOSURE 5.2
'i Main Steam Line Radiation Monitor Correlation Curves. Correlation Factor, S' vs.
Time After Reactor Shutdown See Figure 2 for first. 2 minutes of noble gas release. 8,. . . I i . i 9 , , , i _. . e . . .
, . ... . _ . . . . _ _ _ . _ . . . . . , . = , .u.. . . s . . . . . . . . , . .. .....-._=.r...--_a __......s=._
- . , . . :: ;. - -- - w .__-
, l .: .i= ::.=_.:+ _ := .: n .: a:.g. =: _.s_:..- _ __ .l . _ ....
. . .; .. l . .
_ --=__-=.
. l
- 2. .u _
. . .= :.
; i _ .:._--:~....,---- :-
l-.......__.- . . = _ _ = . _ _ _ - . = - = _ . _..: =_ .
, - - . . .. .w.
, t . .. . . - _ . _ . ... . . ..
o . . .i. . -
, ... ... . . . . . . . . ._p- .. _.. .i ,. . .. .
- y +..:..=- ..n =: ...,.p_..
F = .. :==..-u .y = l . S,..--.. _- :=. .
=
=.:_.
__ _ _; ;.= = -- _: - .--l
=1.2x10, .=__ __= ::. .: :-4.
= n g-- __ ___ _q_. : :.: _:u : . . . -
=
.::p~
_ _ _._. ..__ _=.:r-- .- - ._ . . _ _ _ . . F2. .r._TM H rs _ _ _
= . . ..
i _ i . . _ _ _ l__ i i
..i.__ _i_. __ .
p_ , . - _ .. _ _.___ _ _ i-
,.1j
..i.._
3 . /
- 7 ( , , ... f. . , ... . .. i. . . i..__ , ~ . . . _ .
,....- i .. i . . r _ . . _. ,. : :.._: . _;
fi __, . . .
;- r : =. - .A. - . .:=- - ,= . ::.- .= ! : r - = : . -- l : = '=.t= . ; - : - . . : . - 6 : = == e - :.i. . = D . __ ;: _ =; .
--..--_-.--=[-
p .: _,u - _ -- - i -- = - ==i-- _ -._- a ,
...==_.._._
_2___
, .f _. ,i. ., ..... . . . . . . . _ . , _ .._, ...,...:,,, . . . . ._ .
, u f , ._ . . . _ i . . . .. .. m . + .-... . m... 6- . . 6 ..:.;..._..._i.._..___-,- . , . e _. __ .u.
; i a -. :_ m _=-+x. m .r. r u-- . '.-= + -+ . :_e .- m.:: v r s _- =.-! = sme_ i- s.
- - _m.--r = j
=a _.= =up. - -; .:
, y :. J. 8s . == - ;- - - t ==.z .i. = * : .: n = r..=_ = _ : = w . . - _=_. :.~.: ..: + : .= :
y:- .= m. - .= - h .___... ___.:. :.
- _ _ . .= _ _ . ::.r __ _ : ..:. : . . u r-._.-. : __ ---_. ..;.
.._ - :.5. .f - _.
_: _ .==.u .i:
= =- :.: . .. ._- . .-..=:. ; ,
_ _-. _7. -- __- . .-r = _._ ...,_
,m_.,..__,
,_ _ . - f .
2 _ _
- - - - __I ____
_= .__--- . : _.-- -
. ,_ _- . a = -.
___ _ , _ ._p _ _ .;_._ _ _ . _ 1 _.. _. ~._.. _ . ' . > . _ _ . . _ ._._ _ _ je t e - oc .:o 30 +.' ss s.o b 4 Time (Hrs) Figure 1 - Main steam line radiation monitor correlation curve. Correlatien Factor, i
. S' vs. time af ter reactor shutdown. .
~
where S' = Xe-133 Ecuivalent Concentration (uti/cc) - l Pbnitor Dose Rate (R/Hr) To obtain the Xe-133 equivalent concentration in the main stear line at tir,'e T. ruitiply the train steam line re :ic,tien ronitar rc.-: .. . _
nf ,
.# ot .
DUKE POWER' COMPANY
- t. CATAWBA NUCLEAR STATION t
HP/0/B/1009/12 ENCIASURE 5.2
" Main Steam Line Radiation Monitor Correlation Curve Magnified First 'No Minutes Response S' vs Time r .
v
- c. _
, . . . . r . . t . . .-
. .:. i . . - r = - =-
s i .= = != .i. _:.- : - .
...-:...-I :- . . :- :g :. i.s- =::..
--, - - - - - i.=.k.w it.i
, i 6
. -. =l-*
i . - . ._ .. ._-
, .s '.. - -r l . . ..r w.
i -
. . ._ :.._ ==. -
- i. . . . :. : .-.--
- . . _ .... i . __-....r.:. _: :2 t...__ : . _...
- =
,....._t
.. ._ . 1. _. . .. .. . . . .....
_ -.... _ _ ..__ _._ _ .. i. .
,....._...i,..__
_ . . .. l . _ . t - s . . .t . i :::, . . . . .. . .. . z . r . .=. : . . .= :.=. :.~ :.. = - J , . . . - -. . .
. . :.: -- - - e . . - . . -
-.. . --- - -.. _. : :i. . . . : == -
2 . .. .
- i. .
., ,-.n.. . . .. _
e
._-. = - .. . :. . n . . _:. . .
2 .
._u
.-4. i. =
= .=_._._=.:.= .. _.._
. _ . . _ _ _: . _ _ :_ __=_
- .,c
_ .__. _i _.. i.__._ __,,. ,
...___i__
j .._...____i .____..___.____..
. p_ _ _ . . _ _ _ _ ,
10 *10 LO S'.,'. ICC /20 Time (Seconds) Figure 2 - i 1 ' Main steam line radiation monitor Correlation Curve Magnified first 2 mir.ute response S' vs. time (0 to 120 seconds) after reactor shutdovn. Note: At 45 seconds and beyond N-16 activity is negligible.
, - - ,,,,,--e. - M
f'lF 1
. {.
l I ( e Form 34731 (10-81) s (Formerly SPD 10021) '
'I
! DUKE POWER COMPANY (1) ID No: HP/0/B/1009/13 l PROCEDURE PREPARATION Change (s) 0 .to
~
j PROCESS RECORD 2 Incorporated ' { (2) STATION: Catawba Nuclear (3) PROCEDURE TITLE: Offsite Dose Projection - Uncontrolled Release Of l Radioactive Material Through The Unit Vent (4) PREPARED BY: M. DATE: T- C - T4 (5) REVIEWED BY: M7 43,4 DATE: /-#-/V Cross-Disciplinary Review By: N/R: 41 M (6) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO) Date:
, . . By: Date:
(7) APPROVED BY: G L'- Date: ff /h ii (8) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: b e e
O HP/0/B/1009/13 DUKE POWER COMPANY CATAWBA NUCLEAR STATION OFFSITE DOSE PROJECTION - UNCONTROLLED RELEASE OF RADIOACTIVE MATERIAL THROUGH 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 Letter from Civil / Environmental Division CN-1108.1, 1434.00, 1227.00 Atmospheric Dispersion Factor for Emergency Planning 2.2 EPA-520/1-75-001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents 2.3 Regulatory Guide 1.109, Calculation of Annual Dose's to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I 2.4 Regulatory Guide 1.4, Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for ( . Pressurized Water Reactors 4 3.0 LIMITS 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, note this in the report of offsite dose assessment. 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. 3.4 Reporting requirements of Station Directive 2.8.1 and HP/0/B/1009/02 shall be evaluated to ensure that the Shift Supervisor and/or the Licensing Engineer are informed of the requirements.
. 4.0 PROCEDURE 4.1 Obtain the following information from the Control Room and record it j
en Enclosure 5.1 (Vent Release Data Sheet). 4.1.1 Time of reactor trip. 4
r t EP/0/B/1009/13 l' Pags 2 of 5 J
- 4.1.2 Tcaer wind speed in MPH.
(Lower tower wind speed preferred.) 4.1.3 Direction from which the wind is blowing in degrees from North. (Upper tower wind direction-preferred.) 4.1.4 Temperature gradient (AT) 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. 4.2.2.1 Date/ time of sample. 4.2.2.2 Gross noble gas concentration in uCi/ml. 4.2.2.3 Iodine equivalent concentration (or data for calculation). 4.2.2.4 Gamma E-bar value in mev/ dis (or data for (' calculation). . t 4.2.3 Go to Step 4.3 4.2.4 Obtain the following unit vent data and record on sample Enclosure 5.1: . 4.2.4.1 Date/ Time of collection. 4.2.4.2 EMF 36 Low and High range readings in cpm (gas monitor). 4.2.4.3 AEMF37 reading in cpm (iodine monitor). 4.2.4.4 at in minutes for AEMF37 reading. 4.2.4.5 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 downwind as follows.
- NOTE
- If no points have been requested, use the .5, 2,
- e- 5 and 10 mile values.
l l
- l'
' HP/0/B/1009/13 Pega 3 cf 5 l
I- 4.3.1.1 From Enclosure 5.2 (Table of Two-Hour Relative Concentration Factors), locate the relative two , hour concentration value (CH) for each point and record on sample Enclosure 5.3 (Manual Calculation Worksheet), (Reference 2.3). 4.3.1.2 Convert these values to X/Q by, ' CH(MPH-Sec/m') X/Q = Wind Speed (MPH) 4.3.1.3 Record results on Enclosure 5.3 (Manual Calculation Worksheet). 4.3.2 Calculate the gas and iodine downwind concentrations for each point using the equation, Conc DW " "*V *Fy
- X/Q
- UDWC where, Conc DW " """ " " "" *"* * * * ' " ( " 'I" } "
Coney = vent discharge concentration (uCi/ml) Fy = vent discharge flow rate (CFM) X/Q
= dispersion factor in sec/m' U
DWC = unit c nyersions derived from, (2.832E-2m /ft') (0.017 min /sec) = 4.8E-4 " **" 3 ft'
- see Sample Enclosure 5.3 provides work space for this calculation.
4.3.3 Determine the potential whole body gamma dose downwind using the gas concentrations calculated in 4.3.2 and the equation, Dg3 =U G * *
""DW
- Time where, D
WB
= whole body gamma dose due to submersion in a cloud of radioactive gas (rem) b n ,
HP/0/B/1009/13 Paga 4 of 5 Ug = unit Conversion derived from, 1 t- 3.7E4 (dis /sec-pCi)(1cc/1.2E-3g) (1.602E-6 erg /MeV) (g - rem /100 ergs)
- 1/2 = 2.5E-1 -
DCi-sec-MeV (2.5E-1 s-rem-cm')(3600 see) pCi-sec-Mev hr
= 9.00 E2 VCi-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).
Conc DW
""" " * ""*"**** * (" 'I"1) -
Time = projected duration of exposure (hrs); use 2 hours unless otherwise directed. 5 = average gamma energy per dicintegration (Mev/ dis) NOTE: If E cannot be obtained from the sample results, the following .alues may be used: Hours f;om Trip 5 (Mev/ dis) 0-12 0.40 , 12-48 0.20 48-= 0.10 4.3.3.1 Record results on Enclosure 5.3. j 4.3.4 Determine the potential child thyroid dose downwind using the iodine concentrations calculated in 4.3.2 and the l equation, D THY
=U a
. Conc DW
- Time 7
where, D THY
= thyroid dose due to uptake of radioactive iodine (rem) i 4
, -_ ,m._ , . _ _ . _ m _ . . - . , . - . _ . . . _, .
p j HP/0/B/1009/13 i . Pags 5 of 5
= constants derived from a child's breathing rate
.j U 7 ff (1.17E2 cc/sec.), I-131 dose conversion factor ~L - . (4.39 E-3 mrem /pC1), and coversion of pCi to j pCi-(100), mrem to rem (10 ~8), and hrs. to sec (3600 secs /hr) = 1.86E6 "' - uci
- hr
[ Conc = D wnw nd concentration of iodin'e (pCi/ml) Time = projected exposure time (hrs); use 2 hours unless 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). 4.3.4.3 Record results of all calculations on Enclosure 5.5 (Dose Assessment Report). 4.4 Determine the potentially 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 w'orksheets and printouts used in dose calculations. 5.0 ENCLOSURES 5.1 Sample of Vent Release Data Sheet 5.2 Sample of Table of Two Hour Relative Concentration Factors 5.3 Sample of Manual Calculation Worksheet 5.4 Sample of Evaluation of Plume Location 5.5 Sample of Dose Assessment Report e
%k '
l 1
11' Pags 1 of 1
; ENCLOSURE 5.1 HP/0/B/1009/13 VENT RELEASE DATA SHEET l- '
Date/ time of Rx trip / Jnit - KETEOR0 LOGICAL DATA Lower Tower Wind Speed MPH 1)
- 2) Upper Tower Wind Direction From
- 3) Temp. Gradient (AT) 'C
- 4) Vent Flow CFM
- 5) Date/ time /
I VE!C SAMPLE ANALYSIS i
- 1) Total Gas pCi/ml
- 2) 1-131 Equiv. yCi/ml
- 3) Gas E Mev/ dis (Gamma) i VENT MONITOR DATA
- 1) EMF-36L (lo range) CPM
- 2) EMF-36H (hi range) CPM AEMF-37 (iodine) CPM; at min 3)
CALCULATED DISCHARGE CONCENTRATION
- 1) Gas (Use hi readings if E:iF-36H is > 100 CPM)
Cone y ,3,, = (EMF 36L CPM) = uCi/ml, or Conc = (EMF-36H CPM) = V-hi 2.70E7
"~" 4.0E3 pCi DCi pC1/ml - 2) Iodine Coney ,g = (AEMF-37 CPM) (2.4E-10 vCi - min) = UCi/ml At ml - cpm 9
ENCL _0SURE 5.2 HP/?/f/1009/13 TWO-HOUR,lt[LAllVE CONCENTRAT ION FACTORS (CH)
.Iemperature Sti6Tilty Distance (Miles)
Cli fG rence Class 5 6 7 8 9 to 2 3 4 (*C) .5 1 2.5E-7 2.0E-7 1.9E-7 1.8E-7 1.6E-7 1.5E-7
.6 A 1.4E-5 1.2E-6 5.9E-7 4.lE-7 3.2E-7
- 1) <
2.7E-6 1.9E-6 1.4E-6 1.1E-6 8.3E-7 7.8E-7 B-C 1.5E-4 4.5E-5 1.3E-5 6.3E-6 3.9E-6
- 2) .6 to .5 1.7E-5 1.2E-5 9.2E-6 7.3E-6 6.0E-6 5.0E-6 4.3E-6
- 3) -0.4 to-0.2 D 3.8E-4 1.4E-4 4.9E-5 2.7E-5 2.5E-5 2.0E-5 1.6E-5 1.3E-5 1.1E-5 9.7E-6 E 6 9E-4 2.5E-4 9.6E-5 5.5E-5 3.5E-5
- 4) -0.1 to+.4 6.3E-5 5.1E-5 4.3E-5 3.8E-5 3.3E-5 3.0F-5 i 1.1E-3 5.1E-4 2.0E-4 1.2E-4 8.2E-5
- 5) +.5 to +1.2 1.7E-4 1.3E-4 1.2E-4 8.6E-5 7.8E-5 7.3E-5 1.8E-3 1.1E-3 4..E-4 1 2.7E-4 2.0E-4
- 6) > 1.2 C f rom other sources or meteorological data (Section 4.1) use the wind speed and time or day to determine vl:Ich row or Cil values to use:
Wlpd.Speg Row # ((me Of Day 3 N/A 10:00 A.H. - is:00 P.M. > 15 HPil 4 4:00 P.H. - 10:00 A.M. $ 15 HPH 6 84:00 P.H. - 10:00 A.M. s I
..._.y .. w .n : .
. .y. ,.,..ey..
~ - 9 I
P ge I cr 1
. [NCLCSURE 5.3 HP/0/B/1009/13 MANUAL CALCULAT ICN WORKSil[E T
- 1) Discharge Concentration (Conc y): 2) Vent Discharge Flow Ram: 31 Wind Speed Cas = cl/mi FV = CFM MPil lodine = cl/mi
- 4) Jwo Hogr Relative Conc. Factors (CH = sec-sph/a s X/Q = CH/ mph = sec/a s Cil = ; X/Q = Sec/m8 G Mi 5) Downwind Concentrations:
CH = ; X/Q = Sec/m8 G M1 Conc QW = Conc y o FV o X/Q o (4.7E-4) l Cil = ; X/Q = Sec/ms4 Mi A) Ces 8) Iodine CH = ; X/Q = Sec/m G 8 Mi Conc DW = aCl/mi conc DW = AsCl/mi Conc DW = 4Ci/mi . Conc DW = 4:l/mi Conc DW = MI/mi conc DW = mCl/ml Conc DW = dl/ml Conc DW = t i/mi 6-) Potential Whole Body Comma Dose: 7) Potential Child Thyroid Dose: (MD = (9.00E2) o Conc DW o E o Time Time = hours D M = (1.86E6) o Conc DW o Time E= Mev/ dis DWB = Rem 4 - MI. D illy = Rem DWB = Rem G MI. D THY = Rem DWil = Rem 4 Ml. D illy = Rem DWB = Rem e MI. D illy = Rem
' f a
s / (,. I
._ .. i
t Pags 1 of 2 li . . { ENCLOSURE 5.4
;} HP/0/B/1009/13 .; EVALUATION OF PLUME LOCATION 4
Ac' quire the following information from Enclosure 5.1 and record on
~
7 1. Enclosure 5.5. a) wind direction in degrees from north - b) wind speed (mph) 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 following information, a) For doses:
> 5 Rem Whole Bcdy or, '
> 25 Rom Thyroid Recommend Evacuation of Population in Affected Area.
1 B) 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. C) For doses:
< 1 Rem Whole Body or,
< 5 Ren Thyroid i
Recommend no action. 3.
~
Determine the affected zo'nes, based on wind direction and wind speed, with the following tables. Table 3.1 0-2 Mile Affected Zones Vind Direction Affected Zone l 0* - 360* A0 l i l l . m
._ ._ -- ,-w w-v-- --
-e-r r-
3 Pags 2 of 2 Lg-1' . 1 ENCLOSURE 5.4
', HP/0/B/1009/13
- j. . EVALUATION OF PLUME LOCATION b' ~ h' .
~
Table 3.2 2-5 Mile Affected Zones t Wind Speed > 5 mph j Wind Speed < 5 mph - Affected Zones Wind Direction Affected Zones i Wind Direction A1,B1,C1,DI,E1,F1 0.1' - 22* C1, D1 O' - 360* - 73' C1, D1, El 22.1' 73.1' - 108' C1,D1,E1,F1 108.1* - 120' D1, El, F1 120.1* - 159' El, F1 159.1* - 207* El, F1, A1 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 3.3 5-10 Mile Affected 2ones' Wind Direction Affected Zones
- 27' C2, D2
'k O.1*
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 F2, F3, A2 160.1* - 201* F2, F3, A2, B2 201.1* - 229' F3, A2, B2 229.1* - 249' A2, A3, B2 249.1' - 259' A2, A3, B2, C2 259.1' - 290* A3, B2, C2 290.1* - 304* 304.1* - 333' B2, C2 333.1* - 360' B2, C2, D2
- Record sectors requiring protective action on Sample Enclosure 5.5 along with
.;j ,
4. the recommended protective action.
*.~ ;.
5 e
.-4
?
- ENCLOSURE 5.5
'F DOSE ASSESSMENT REPORT i HP/0/B/1009/13 1 ,j Duke Power Company Crisis Management Plan Off-Site Dose Report - Catawba
'I
/
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 Source Term Time Noble Gas 1-31 ea. Containment Rad. Monitor R/hr. R/hr Containment Sample DCi/ml WCi/ml Unit Vent (Sample or EMF) DCi/ml uCi/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 2 hr Dose (rem) based Whole Body on Containment release Child thyroid 4
f: @ ml/hr p (n. ......................................... 2 hr Dose (rem) based Whole Body j on Unit Vent release Child thyroid , @ cfm 2 ht Dose (rem) based Whole Body on Steam release Child thyroid 1 2 hr Dose (rem) based Whole Body on release Child thyroid 1 Field Monitoring Data Location Distance Direction Dose Rate (mram/hr) Contamination l (mi) Whole Body Child Thyroid (dpm/100 cm2) l l Affected Zones 0-2 mi 2-5 mi 5-10 mi 9-10 mi l, (Circle Zones) A0 Al B1 C1 D1 El F1 A2 B2 C2 D2 E2 F2 A3 F3 l Comments:
~.
XC: Data Analysis Coordinator, Station Health Physicist 4 m ,. ,,----,..,e= , .--w.--- _. ,,- g
}. , _ _-
- i.
- 1 1
l I l e 1 i
. . Form 34731 (10-81) !. N (Formerly SPD-10021) i I
l DUKE POWER COMPANY (1) ID No: HP/0/B/1009/14 PROCEDURE PREPARATION Change (s)_ 0 to f PROCESS RECORD 1 Incorporated I l l (2) STATION: Catawba Nuclear i 4 (3) PROCEDURE TITLE: Health Physics Actions Following An Uncontrolled i Release Of Liquid Radioactive Material (4) PREPARED BY: $1. DATE: T-G-T4 (5) REVIEWED BY: 144/ 7. M DATE: /-t-/v Cross-Disciplinary Review By: N/R: ,/ 7 e44 (6) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: (" By: Date: (7) APPROVED BY: w- Date: h (8) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date:
.c f
9 I 4
--c - )
I i- I HP/0/B/1009/14 I
. (- ,
DUKE POWER COMPANY j CATAWBA NUCLEAR STATION l HEALTH PHYSICS ACTIONS FOLLOWING AN ) UNCONTROLLED RELEASE OF LIQUID RADIOACTIVE MATERIAL 4 1.0 PURPOSE This 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 Control Room Unit Data Book
~
2.3 10CFR20, Appendix B, Table II, Column 2 2.4 CNS FSAR Sections 2, 11, 12 and 15 2.5 CNS Technical Specifications Sections 3/4.3, 3/4.11 and 5.0 Q' 2.6 Letter to Master File CN-1227.00 Dilution Factor - Rock Hill Intake from Design Engineering dated February 23, 1983 2.7 CNS Emergency Plar. 3.0 LIMITS AND PRECAUTIONS 3.1 The full implementation of this procedure should be used in emergency situations that could result in the contamination and possible shutdown of area water supply intakes. 3.2 Full implementation of the protective actions in this procedure require station management authorization. 3.3 This procedure is for use under abnormal conditions and results in conservative recommendations. 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 3.5 Transit time from CNS to .the nearest municipal water intake is reduced from three days to one-half day under extreme l meteorological conditions (Ref CNS FSAR 2.4.12). - w -, - - - - - - , , ~ -
HP/0/B/1009/14 Pags 2 of 3 l 3.6 Reporting requirements of Station Directive 2.8.1 and HP/0/B/1009/02
, shall be evaluated to ensure that the Shift Supervisor and/or the ,. , Licensing Engineer are informed of the requirements.
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 affluent 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
'if release is made from other than through Waste Liquid System, if possible.
4.1.3 Collect representative sample from Environmental Sampling Pier (Location Site #A0 1 46) at Station Service Water-4 Discharge-Canal and analyze sample for c'oncentration. 4.1.4 Should utilize most restrictive (highest) concentration from applicable procedure Steps 4.1.1, 4.1.2, 4.1.3 above. (~1 4.2 Determine the potential for contamination of area water supplies a i using Enclosure 5.1 (Transit Time /Radionuclide Concentration Calculations) and sampling data from Health Physics. 4.3 If data indicates that a release made through the Station Service Water 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 System Load Dispatcher (to extend transit time).
NOTE: Transit time to Rock Hill water intake is approximately 14 days with NO FLOW through Lake Wylie Dam, (based on dam leakage rate). 4.3.2 Request Field Monitoring Teams (FMT) to track the release
'-t
'by sampling and evaluation of sample concentrations taken from discharge point at Environmental Sampling Pier j
(Location Site # A0 1 46), above Lake Wylie Dam (Location Site # B1 4 5), directly below Lake Wylie Dam (Location. Site # B14 6), and at Rock Hill municipal water intake structure (Location Site # C2 7 8), per Ref. 2.1, as deemed necessary. NOTE: Transit time is calculated as three days under normal meteorological conditions with all units ( in operation at Lake Wylie Hydro Station. l i
,~
l . HP/0/B/1009/14
.I E] Pcgas3.of 3 (
1 t 4.3.3 Notify (through the State) the area water supply pumping stations that a release of radioactive materials to Lake 1 . e
. Wylie has occurred and that limited protective actions .
- (sampling and analysis) are being taken. j 4.3.3.1 In the event that sampling confirms the l contamination levels at area water intakes will .
exceed 10CFR20, Appendix B Table II, Column 2 . limits, request (through the state) that area water pumping stations cease operations during the period of time cortaminated water is passing 1 t the pumping station intakes (see Enclosure 5.2). 4.3.4 Request System Load Dispatcher regulate flow through dam as required. I q NOTE: Maximum flow through dam will allow'" boxcar" to . pass critical areas in least time.
'A , ..
4.4 Discontinue environmental surveillance efforts when concertration (contamination levels) indicate that protective actions are no longer appropriate. e b 5.0 ENCLOSURES \, 5.1 Transit Time /Radionuclide Concentration Calculation i I( s
.x-A g
> m.,
l
' N 9
I N e
~
1 r
?
. 1 i
h e % =
'w
- y s ';
j s j
- s .
l c .g
, 3 9
. _ _ . _ - ,. . _ - ~ _ _ . . _ _ _ _ _ _ __ _.. _,, . - . -
'v 4-q ^N sq DUKE POWER COMPANY Paga 1 of 2 1
4 CATAWBA NUCLEAR STATION _ 54
', 4~ 44 -
t s HP/0/B/1009/14 {l,i
!. (^ ",. i - SAMPLE ENCLOSURE 5.1 TRANSIT TIME /RADIONUCLIDE CONCENTRATION CALCULATION mo- -
cy 4%ig i 'Is%* i , w. . DESCRIPTION A a Transit tjme(s) and radionuclide concentration (s) for an uncontrolled release of liquid radioactive materials from a Catawba Nuclear Station release point - to.tka municipal (or industrial) water intake structures of Rock Hill, Celanese '
. Fibers. Company (Rock Hill), Fort Mill and Springs Mills, Inc.-(Fort Mill).
NOTE #1: All municipal or industrial water intake concentration calculations are based on Rock Hill water intake sampling point unless specified otherwise by Station Health Physicist or Emergency Coordinator. s . CNS Discharge Formula Test Water Transit Time Dilution ( 1 ) Formula Point Criteria Intake (NOTE #2) Factor ft' Recuired viNU/LSystem Conc and Vol Rock Hill 3 days 4 x 10 '
~
#1
-(dischs header) known other than Ccnc and Vol Rock Hill 3 days 4 x id #2
*VL System known -
via WL System Conc and Vol Rock Hill 3 days 4 x 10 #3
.(dischg header) unknown (f_
other than Conc and Vol Rock Hill 3 days 4 x 10I' #3 WL System unknown NOTE #2: Transit time assumes all units in operation at Lake Wylie Hydro Station. RR, FORMULAS: #1 - Cg = C, x D x (time (RR, + RRd)
- s RR d
#2 -
C, = C, x D x Vk
#3 -
C, = C, x D x V (see NOTE #3) Where: Cw = Radionuclide concentration at municipal water intake (uci/ml) q, C, = Undiluted discharge point concentration (uci/ml)
~
D = dilution factor (4 x 10 ' )
, ft' time = taken from WL Release Worksheet (sec) - (time WMT pump is running) 4
- l
(
=
DUKE POWER COMPANT - Pag 9 2 of 2 .
-CATAWBA NUCLEAR STATION HP/0/B/1009/14 SAMPLE ENCLOSURE 5.1 TRANSIT TIME /RADIONUCLIDE CONCENTRATION CALCULATION e - ( ,
RR, = effluent release rate (cfs) - (from VL Release Worksheet)~ RR d
= RL (and RN) flow rate (s) (cfs) .
RR, = dilution variable (no units) RR. a . Vk = known volume (ft') V = 13,268,000 ft' (discharge canal volume) c
~8 cfs/gpm (Xgpm)
Conversion Factors: cfs = (2.22'x 10 i ft' = gal /7.481 i NOTE #3: When using formula #3, must assume entire contents of discharge canal as effluent release and evaluated sample concentration as C, (Undiluted effluent concentration). . 1 g/ f g l
= meaA b
- 9 6
% 8 i
. l
~ j
. - l
i , Form 34731 (10-81) i (Formerly SPD 10021) ' DUKE POWER COMPANY (1) ID No: HP/0/B/1009/15 , PROCEDURE PREPARATION Change (s) O to PROCESS RECORD 1 Incorporated
-(2) STATION: Catawba Nuclear (3) PROCEDURE TITLE: Uncontrolled Release Of Gaseous Radioactive Material Other Than Through The Unit Vent (4) PREPARED BY: "M. DATE: i- (o - il 4
'(5) REVIEWED BY: M /A4 DATE: /-/-ev
, Cross-Disciplinary Review By: N/R: J. 7,/L4-b *
, (6) TEMPORARY' APPROVAL (IF NECESSARY): ,
I-By: (SRO) Date:
,, By: Date:
(7) APPROVED BY: W- ~ Da t.? : 3S y a . , (8) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: i Y j *$ J 9 O e r e
7 i
- i
. HP/0/B/1009/15
'i #
, DUKE POWER COMPANY -
CATAWBA NUCLEAR STATION OFFSITE DOSE PROJECTIONS i l UNC0hTROLLED RELEASE OF GASEOUS RADIOACTIVE MATERIAL OTHER THAN THROUGH THE UNIT VENT - T i
; 1.0 PURPOSE To describe an approved method for projecting dose commitment from a noble gas or iodine release, other than a unit vent release, during an emergency. - 'i
2.0 REFERENCES
2.1 Reg Guide 1.109 2.2 Reg Guide 1.4 2.3- HP/0/B/1009/06, Alternative Method for Determining Dose Rate Within the r Reactor Building ~ 2.4 Variables used in HP/0/B/1009/15, Letter Fi.le Number CN.: 134.10 3.0 LIMITS AND PRECAUTIONS * (1' (.; 3.1 It is assumed that the whole body dose from a release is very small ' 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, i 3.3 This procedure considers all releases to be ground level releases. p 3.4 Reporting requirements of Station Directive 2.8.1 and HP/0/B/1009/02 i shall be evaluated to ensure that the Shift Supervisor and/or Licensing Engineer are informed of the requirements. 4.0 PROCEDURE 4.1 Acquire th'e following information and record on sample Enclosure 5.1. NOTE: Should site meteorological data be unavailable, obtain . wind speed and wind direction from the National Weather " Service (United States Government - National Oceanic & Atmospheric Administration). i NOTE: If appropriate, obtain advance meteorological data to L calculate doses due to changing meteorological conditions. l , 4.1.1 Reactor Unit, date and time of reactor trip. 4.1.2 Lower tower wind sperd (mph).
't
__,_- _ - +, . , . , . _ ..,__,._,,.__,,,,,+y _ e-
HP/0/B/1009/15 Pags 2 of 4 s 4.1.3 Tower wind direction in degrees from North (North = 0*).
. 4.1.4 . Temperature gradient ( AT* C) .
4.1.5 Radiation Monitor (EMF 53A or 53B) 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 (ml/hr) is the total leak rate for the containment which is one of the following: 4.2.1.1 a "best guess" assumption, 4.2.1.2 the measured leak rate where suitable means are available; 4.2.1.3 The design leakage rate (LRDLR) which is determined by: - LR = Containment Volume
- Design Leak Constant DM
- 1. .
= 2.83 x 10 ml
- 0.0025
- day .
^
[ day 24 hr s
= 2.95 x 10 ml/hr 4.3 Determine the X/Q values for each point of interest downwind and record on sample Enclosure 5.1. '
If no points have been requested, use the .5, 2, 5 and 10 mile values. 4.3.1 Locate the relative two-hour downwind concentration value ' (CH) for each point from sample 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/m*) Tower Wind Speed (MPH) 4.4 Determine the potential whole body dose from submersion in a cloud of noble gas and record on sample Enclosure 5.1. 4.4.1 Calculate the whole body two (2) hour dose commitment, D WB M
- ADC
- LR
- X/Q = UNG s.
y _ ,
y -
..;_ g HP/0/3/1009/15 j -
Paga 3 cf 4 1 Where. A. Q. D WB
= Whole body two (2) hour dose _ commitment -
f DR g = Monitor dose rate I ADC = Average' Decay constant for no'ble gases = - 2.2622E-2 uCi
- MeVahr2 l_ al*d*R s
LR = Containment leakage rate in al/hr X/Q = dispersion factor in sec/m' (3.7E4/sec*uci) (1.6E-6 ergs /MeV) , U NG
= ( 00 ergs /g-rad) (1.2E-3g/cm') (1E6cm*/m*)
5.7E-9 hr*-m* - rad mi-R-sec 4.5 Determine the potential thyroid dose from uptake of radioiodine and record on sample 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. b,, - 4.5.2 Calculate a child's thyroid two (2) hour dose commitment using time plus one (1) hour, DR T = DR g
- DC
- LR
- X/Q
- U y Where, DR T
= thyroid two (2) hour dose commitment DR g = monitor dose rate pCi
- mrem a hr"
, DC = Decay Constant in ml
- pCi
- R for time plus one (1) hour (see ' sample Enclosure 5.3)
LR = Leak rate in ml/hr X/Q dispersion in sec/m 3 ' i Ug = breathing rate for child times uCi to pCi conversion factor pCi-rem m 3 -pCi-rem ! (1.17E-4m3/sec) 1E3 uCi-mrem = 1.17E-1 Sec -uCi-mrem 1
! I
~- - , - -
.w +~r ,
w e --- , , -- - r
; 1
. g' HP/0/B/1009/15 j Peg 2 4 of 4 -{.
.4.6 Determine the potentially affected area using Enclosure 5.4. Record ; 7 the affected zones on Enclosure 5.5.
i . 4.8 Complete sample Enclosure 5.5 and submit it to the Data Analysis I-Coordinator. Include any comments pertinent to the evaluation of offsite hazards. 5.0 ENCLOSURES ,
-j 5.1 ' Sample Projected Offsite Dose Released From Containment 1
l 5.2 . Sample' Table of Two Hour Relative Concentration Factors (C ) H j 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 m 6 0
'9 A_._ _m_> - . - , - . . , e - y - - - . , _ _ _ . .
,
- l*~.
4 6 Page 1 of 2 i
, ([I. ENCLOSURE 5.1 -
HP/0/B/1009/15 PROJECTED OFFSITE DOSE RELEASED FROM COSTAINMEhT Unit Date/ Time of Reactor Trip / - METEOROLOGICAL DATA l
- 1. Lower Tower wind speed sph'
- 2. Upper Tower wind direction
- 3. Temperature gradient (AT) *C MONITOR DATA
- 1. EMF 53A or 53B/ Survey Inst. # , DRg = R/hr (Circle One)
NOTE: If containment monitor information is not useable, refer to Reference 2.3.
- DOSE CALCULATION DATE/ TIME
!. - 1. LR ml/hr 1 (% j 2. m.= /Q = sec/m 8 CH@ , ? 8 mi. = , X/Q = sec/m CH@ CH E --
"** ' O" **"I"
' 8 mi. = , X/Q = sec/m CH@ A. Whole Body 2 hr. dose projection from noble gases: by D = DRg *LR
- X/Q
- 5.7E-9, WB Miles Out pWB 2 hr Dose Commitment
(
's
- ~ --,,w.e .s- ,,-w- ,,vr ,, - - , , , - - ,,g -
e - - - - - y- ~----r,,-,w,-
T l l- i
. Page 2 of 2 i ENCIDSURE 5.1 ' '
HP/0/B/1009/IS ' PROJECTED OFFSITE DOSE RELEASED FROM C0hTAIhMhT B. Thyroid 2 hr. ' dose projection from iodine: ' DC , by DR T = DR g
- DC
- LR
- X/Q *-(1.17E-1), -
Miles Out DT 2 hr Dose Committment ; E DEFINITIONS - .
~
D = WB whole body 2 hour dose commitment from noble gases (f) DRT = thyroid 2 hr dose commitment from iodine ' LR = containment leakage rate i X/Q = " Chi over Q" is downwind' concentration correction factor l C = r re ative H wnw nd concentration - MPH (X/Q
- MPH)
DC = Decay constant I. DRg = dose rate at the containment monitor l i
?
[ 8 1 f- i db I e P
-, , e , - - - , - - . , , - -, --
.. A INCL U% . t IIP /0/0/1009/15 f
TWO-HOUR REL.ATIVE CONCEN1RAllON IAC10RS lC l H Iempe ra ture Stabseity Distance (Mises) i Cifference class (*C) .5 1 2 3 4 5 6 7 8 9 15
- 1) < .6 A 1.4E-5 -1.2E-6 5.9E-7 4.1E-7 3.2E-7 2.5E-7 2.00-7 1.9E-7 1.8E-7 1.6E-7 1.5E-7
- 2) .6 to .5 8 1.5E-4 4.5E-5 1.3E-5 6.3[-6 3.9E-6 2.7E-6 1.9E-6 1.4E-6 1.1E-6 8.3E-7 7.8L-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.or-6 5.0E-6 4.3r-6
- 4) -0.1 to +.4 D 6.9E-4 2.5E-4 9.6E-5 5.5E-5 3.5E-5 2.50-5 2.0L-5 1.6F-5 1.30-5 1.1[-5 9.70-6
- 5) +.5 to +1.2 E 1.1E-3 5.1E-4 2.OE-4 1.2[-4 8.20-5 6.3f-5 *> .1 E 's 4.30-5 1.81-5 3. 3 L *; 3 . s e c ',
- 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 8.6[-5 7.8E-5 7.3L-5 f rom other sources of sr.cteorological data (Section 4.1) use the wand speed and time or day to deters. sine which row or C valves to use: la JJ.sge_pr pay Witid Socest Rq d to:lita A.H. - 4:00 P.H. N/A 3 .
23 : 0 0 P.H. - 10:00 A.ll. > 15 Hl'H #s 4:00 P.M. - 10:00 A.H. f 15 HPli 6 a m __ . _ .m.-_ _ - _---a
- n.
- 1 i
ENCLOSURE 5.3 PACE 1 of 2 cj ! TACLE
'! IODINE & NOBLE DECAY CONSTANT (DC)
'f ,. 0 - 498 HRS i ;- HP/0/0/1009/15 - HOUR DC HOUR .DC If00R DC HOUR DC s HOUR DC
~
a 2.0649E-05 100 5.612SE--04 200 6.8707E-04 300 7.4430E- 04 400 7.9109E -04 4 2 5.7902E-05 102 5.6595E-04 202 6.0925E 04 302 7.9537E-04 '102 7.9197E -04 4 8 1504E-05 104 5.7050E-04 204 6.9060E-04 304 7.4636E-04 404 7.92GSE-04 6 1.0296E-04 106 5.7472E -04 206 6.9199E-09 306 7. 9735E-04 406 7.Y373E-04 i 8 1.2295E-04 100 5.7920E-04 200 6.9326E-04 30l; 7.'.eDae-0.i 400 7.9460u-09 10 1.4170E-04 11C 5.0335E-04 210 6.94U7E- 09 310 7.9932E-04 410 7.9590E-04 12 1.5933C-04 112 ' 5.3737E-04 212 6.'?UD4E-i) f 312 7.5029E-04 412 7.9635E-09
! 14 1.7591E-04 114 5.9127E-04 214 6.9719E-09 319 7 5127E-04 #114 7.9722E-04 16 1 9159E-04 116 5.9504C-04 216 6.'?H90E-04 316 7.5229E-09 416 7.9809E-04 18 2 064GE-04 110 5.9870E -04 210 6. 996GE- 09 310 7.5321E-04 418 7.9396E-04 20 2 2071E-04 120 6.0225E 04 220 7.0009E-04 320 7.5410E- 04 420 7.9982E-04 22 2 3439E-04 122 6.0569E-09 222 7. 0212E- 09 322 7.!Tc;,1GE-04 '122 0 0 06HE-04 .
24 2 4757E-04 124 6 0903E-04 224 7.0333E-04 324 7.5611E-09 424 8.015GE-04 26 2 6034E-04 126 6.1226E-04 'E26 7. (1459E-04 326 7.G707E- 04 4'?6 0.0240E-04 20 2 7272C-04 123 6 1540E-04 22U 7.0574E-34 320 7.GD03E-04 420 8.0326E-04 ' 30 2.O'f75E-04 130 6 1894E-04 230 7. 06928 09 7'30 7.5099E -04 430 8. 0912E-04 32 3.0784E-04 34 2.9645E-04 132 6 2140E-04 232 7.0310E-04 332 7.5994E-09 432 8.0497E-04' 134 6.;?q26E-04 234 7. 09:'cE- 09 339 7.600VE-O'9 934 0.0583E-04 36 3.1893E-04 136 6 2705E-04 236 7.1042E-04 336 7.4109t -04 4'.16 8.0660E-04 g 30 3.2975E-04 138 6 297LE-09 230 7 1157E- 09 .J33 /.r:279E-04 430 8.0753E-04 40 3. 4029E-04 140 6.323CE 04 240 7.1272E- 04 310 7.6373E-04 490 8.0037E-04 42 3.5058E-04 142 6.3493E-04 242 7.13G5FM9 342 7.6447E-04 442 0.0922E-04 9'l 3.6062E-04 149 6.3741L-04 244 7.ie198E-09 3'M 7.6561E-U'i 494 8.1006E-04 46 3.70'l2E-04 146 6.3933E-Del 296 7.1610h- 09 396 7.6655E-04 446 8.1090E-04 90 3.7999E-04 148 6.921ee-04 24e 7.1721C-04 390 7.679aE-04 448 e.117,iE-04 50 3.8933E-04 150 6.4447E-04 250 7.1U32E-09 300 7.6092E-04 450 0.1250E-04 52 3.9846E-04 152 6.'1670E-04 252 7.1992C-04 352 7.693SE-04 452 8.1342E-04 54 4.0730E-04 154 6.4097E-04 254 7.205J L 09 359 7.792CE--04 '154 0.1425E-04 56 4.1609E-04 156 6.5099E-04 256 7.2160E-04 356 7.7120E- O'l 456 8.1509E-09 58 4.2460E-04 150 6.5306E-04 258 7.2268E-09 353 7.7213E-04 458 8.1592E-04 60 4 3291E-04 160 6.550CE-04 260 7.2376E-04 360 7.7305E-04 460 8.1475E-04 62 9.4103E-04 162 6.5705E-04 262 7.2403E-09 362 7.7397E- 04 462 8.1757E-04 64 4.4096E-04 164 6.5097E-04 264 7.2590E-04 364 7.743VE-04 464 8.1840E-04 66 4.5669E-04 166 6.6085E-04 266 7.26'?6L"-09 366 7.7581E-04 '166 8.1923E-04 68 4 6425E-04 168 6.4269E-04 268 7.2802C 04 369 7.7672E-04 468 8.2005E-04 70 4.7161E-04 170 4.6950E-04 270 7.2907C--09 370 7.7763E-09 470 8.2007E-04 72 4.7879E-04 172 6 6626E-04 272 7.3012C-04 372 7.7859E-09 472 8.2169E-04
~
74 4.8579E-04 174 6.679'?E-04 27'l 7.3116E- 09 379 7."'91Ut~ 09 '174 8.2250E-04 76 4.9262E-04 176 6.6969E-04 276 7.3220E-04 376 7.Co?/r 06 476 0.2332C-04 78 4.9926E-04 170 6.7135E-04 270 7.33211E 09 373 7.3126E 04 '178 8.2413E-04 80 5.0573E-04 180 6.729BE-04 200 7.3927C-09 2l00 7.lE'un 44 400 8.2495E-04 1
~
02 5.1202E-04 182 6.715DE-04 282 7. 3529E-09 302 7.930A.-04 402 0.2576E-04 i 04 5.1815E-04 184 6.7615E--04 204 7.34321"-04 304 7.C397tc 04 434 8.2657E-04 t 86 5.2910E-04 106 6.7770E-04 236 7.3739E- 09 306 7.3906F 09 4G6 8.2737E-04 00 5.2909E-04 1G0 6.7922E-04 280 7.3835E-04 300 7.C'JG<.L: Oq 400 8.2818E-09 M 92 5.4097E-04 192 6.8219E-04 292 7.4037E D':90 5.3551E-04 392 7.P.'".,0 OS 492 8.2970E-09190 6 94 5.4627E-04 194 6.0364E- 04 294 7. 4133E- 99 379 7.uce0E--04 494 8.305GE.-04 96 5.5142E-04 196 6.0507E-04 296 7.4220E-04 396 7.!W't2E-O': 496 8.3133E-04 98 5.5641E-04 198 4.0640E-04 290 7.9338E-O'l 3'/S 7.7020E-04 490 0 321GE-04
.s Page 1 of 3
- e. DUKE POWER COMPANY i-
~ CATAWBA NUCLEAR STATION ENC 10SURI 5.4 HP/0/B/1009/15 EVALUATION OF PLUME 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 speed (mph) 5.4.1.3 AT (*C) 5.4.1.4 Stability class 5.4.1.5 Thyroid and whole body dose 5.4.2. Determine the affected zones, based on wind directi.on and wind speed, with the following tables: Table 3.1 0-2 Mile Affected Zones f' 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 Wind Direction Affected Zones O' - 360* A1,B1,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* 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 ! O I l M
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Ni l Station Dircativs 3.8.4 R;v. 4 Inclosure (3) ONSITE EMERGENCY ORGANIZATICK OPERATIONS SUPPORT CEhIIR i p.. -. --- Co m 0L I RMM i l I i 4
, ,,. 4 . - .. . . .
1 I TECRNICAI, I SUPPORT i .- (1 . l CE m R I I h----------- - + OPERAT- ASST. M . P . w. - - ---
------9
, COORD- l
- ING ENG INA*DR ,
l t l l l OPERATIONS SUPPORT CE E R l
- L - - - - - *SEIFT SUPERVISOR I
, AUXILIARY HEAI.TH PHYSICS I OPERATORS I On-Shif and On- H . P . Supe rvis er .o. - - - - - - --I Site Operators not Supervisor and 5 s actually assigned technicians :c be
! to the Control assigned by Station l Room and other Health Physicis: as i.. Operations needed f rons E.P. personnal called- duty list. out as deemed l necessary by the Health Physics Technicians I Emergency Coord-
^
inator or Supt. of Operations
'~
e I
- - . ~ . . - . . . . - . - . . - . . . . . . ... .. . . ... . .
~
.- , . . . . - , - . - - . - .-,. ,:,-.-._-.- ._,.--,-.,,.-,-.-,----,--,L-...,, - , , - . . . . -
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% TO CONTROL ROOM ,
O OPERATOR M M ER CATAMA NELEAR STATIM G O TECHNICAL SUPPORT CENTER COMMUNICATIONS 8 R. T TECH. P X MAINT. STA. P - PRINTER L - SUPPLY LOCKER SE RV. 82 @ - TELECOPIER
@ - R ADIO $ - COPIER X
-l PLANT /TSC ANNOUNCER I-SUPT AREA
---- MOVEA8LE PARTITION g 3_ _ _ _ _ _ _ o STATUS BOARD gg 8@
g*, TEST & O'O
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- OPS. ENG R. PE RF. ENG R. NSSS I & E ENGR.
w ,g o ADMIN. m Qp COORo. o e o lo o l 3- , gg 2 ASST. OPS. ENGR. RX. ENG' R. L & P ENGR. STA. CHEMIST $ OD o o e o el o g 1 g= j 3-_____ DATA g}_ _ _ _ _ _ _TRN. & _________{- STA.H.P. ANALYSIS SECURITY SAFETY g c o oes o o- I og l
- 1 NRC AREA
$&C SUPPORT PLANNING ..
i cOORo. COORD. ENGR. MECH. ENGR. l lO Ol o o o o ll o *O
'N H'gT7* OFFSITE COMMUNICATOR'.
- i o el I" r, +' A TYPES OF COMMUNICATIONS O - PLANT PHONE RINGDOWN PHONE Q - EMERG.NOTIFICATIM @ - OPERATIONSINTERCOM SYS. TO NRC
$ OUTSIDE LINE k ~ LINE TO RECOVERY MGR. O FEDERAL TELEPHONE SYSTEM
Station Directive 3.8.4 Rev. 6 Enc 30sure (5)
~
CATAWBA NUCLEAR STATION OPERATIONS SUPPORT CENTER I 8 I . I t . 1 I I 1 -
' CONTROL ROOM . l I
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v I t e
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e OPE RATIONS SUPPORT CENTER l 4 i 4 I teQ6 i
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l l f a l
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. CAMeA W.UAR STATION C g ONSITE EE RGENCY ORGANIZATION
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Enclosure 6 page 1 of 1 ,
f s
'f- Form 34731 (10-81)
(Formerly SPD 10021) DUKE POWER COMPANY (1) ID No:HP/0/B/1000/06 PROCEDURE PREPARATION Chanse(s) 1 to ! , PROCESS RECORD % Incorporated l (2) STATION: Catawba Nuclear t (3) PROCEDURE TITLE: Emeroency Ecutoment Functional Check and Inventory ' 4 (4) PREPARED BY:. 7eI l 7?f. DATE: I-4-i9 -
~
- (5) REVIEWED BY
- 24.4/ 2 DATE: / W Cross-Disciplinary Review By: N/R: 47u ;
t' I (6) TEMPORARY APPROVAL (IF NECESSARY):. - By: (SRO) Date: By: Date: f (7) APPROVED BY: W' Dato: /h ' (8) MISCELLANEOUS: 4 Reviewed / Approved By: Date: - j Reviewed / Approved By: Date: P i P i l 1 4 l i i i I l , 6 3 (
^
! ~ l .
l HP/0/B/1000/06 I DUKE POWER COMPANY CATAWBA NUCLEAR STATION EMERGENCY EQUIPMENT FUNCTIONAL CHECK AND INVEhTORY 1.0 PURPOSE To provide for the availability and readiness of Emergency Equipment. .
2.0 REFERENCES
2.1 HP/0/B/1005/08; Respirator Quality Assurance 2.2 HP/0/B/1009/19; Emergency Radio Systes Operations, Maintenance and Communications 2.3 Catawba Nuclear Station Directive 2.11.13 2.4 Catawba Nucicar Station Directive 3.2.2 i 2.5 Catawba Nuclear Station Directive 3.3.3 ! 2.6 Catawba Nuclear cation Emergency Plan ' 2.7 Catasha Nuclear Station Technical Specifications 6.8.1
- h 2.8 Duke Power Company Radio Operator's Manual 2.9 Maintenance of Silver Zeolite Air Sampling Cartridges Letter; Tile: CN-768.01 2.10 10CTR 50 Appendix E -
2.11 Technical Manual for Groban Gasoline Generators ( j 3.0 LIMITS AND PRECAtTTIONS [ 3.1 Operation of Portable Generators 3.1.1 Avoid operating the unit while hands are wet or while
, standing in water. ~
3.1.2 Generators shall not be started while equipment is plugged into generator. I 3.2 Silver zeolite cartridges shall be discarded if the seal has been ! broken. i e F l . l
,. - - ~ . . - , - - , . - , . ~ - , . - - . - - . e-,, . , ,- , , , -- - - - , - - - , , . , , , , , , _ , - . - - - ,,n,._- ,,, , ,-- .,,. ,-.n. - , - ,_ ,-.-
l 1 HP/0/B/1000/06 Pegs 2 of 7 ) l 3.3 any radiation monitoring equipment (located in an emergency kit) that f must be removed from service for any reason shall be replaced ', within four hours from the time it is removed from the kit. 3.4 Any emergency kit used during training or for drill purposes shall be reinventoried as soon as possible. The individual responsible for the training or drill shall be responsible for inventory and restocking of all on-site kits. 3.4.1 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 4.1.1.1 Portable generators shall bs considered i acceptable for use if: 4.1.1.1 The oil level is at an acceptable
- level per Reference 2.13.
f 4.1.1.2 The generator starts and runs for at least 5 minutes. 4.1.1.3 The generator stabilizes after a portable air sampler is plugged into each of the generator outlets. 4.1.1.2 If generator is acceptable, shut off generator + and remove any excess gasoline from the gas tank. 4.1.1.3 Document the operability of the generators in the appropriate column on the Monthly / Quarterly , i Emergency Equipment Check Sheet (Enclosure 5.1). 4.1.2 Two-Way I,ow Band FM Radios 4.1.2.1 The radios shall be considered acceptable for j use if:
'~
4.1.2.1.1 Each radio transaits a message to another radio. 4.1.2.1.2 Each radio receives a message from another radio. 4.1.2.2 Document the operability of the radios in the ! appropriate area on Enclosure 5.1.
- m --. *- - - - - , , - - - - , -
n n n-e-, + - - . - - - - - - ,-r,-- - - - - - - - ---n,- -
---r +-w+-
- -.. . ._. . - . .= - ..
l
- , HP/0/B/1000/06 !
Paga 3 cf 7 i l s.
, 4.1.2.3 Inoperable radios shall be removed from service.
g' Contact Toddville Communication Shop Planner s- for instructions on disposition ~for repair. 4.1.3 Batteries. 4.1.3.1 All batteries shall be considered acceptable for use if: 4.1.3.1.1 The battery tester needle indicates "scod" when the battery is tested. 4.1. 3 .1. 2 The battery appears to be in good physical condition (no dents, , corrosion, etc.). 4.1.3.2 Document battery check on Enclosure 5.1. . 4.1.4 Portable Survey Instruments 4.1.4.1 Portable Survey Instruments shall be considered acceptable for use if: t . . 4.1.4.1.1 The instrument battery checks. 4.1.4.1.2 The instrument source checks in accordance with the instrument's operation procedure (located in the i .- emergency kit). 4.1.4.1.3 The instrument has no apparent
- physical damage.
4.1.4.1.4 The instrument's calibration date is current.
! 4.1.4.2 Document the instrument's operability on Enclosure 5.1.
4.1.5 Portable Air Samplers i I 4.1. 5 .1 Air Samplers shall be considered acceptable for use if: - 4.1.5.1.1 The sampler operates when plugged _ into an electrical outlet. - l 4.1. 5 .1. 2 The calibration date on the sampler is current.
~
4.1. 5 .1. 3 The sampler has no apparent physical damage. e i
- I
y i HP/0/B/1000/06 Pag) 4 cf 7 4.1.5.2 Document the sampler's operability on Enclosure
-(' .. 5.1.
'I 1; 4.1.6 Respiratory Equipment l 4.1.6.1 Respiratory equipment shall be considered acceptable for use if:
, 4.1.6.1.1 The equipment is in accordance with .
criteria stated in Reference 2.1. 4.1.6.1.2 The Emergency Self-Contained Breathing Apparatus (SCBA) are available at the following, locations: Locations Minimum Units Control Room 2 Upper Personnel Hatch 2 Lower Personnel Hatch 2 Health Physics Respiratory Storage Area , 8 4.1.6.1.3 Six large cylinders of breathing air (minimum of six hours used for 5 people) are located in the I- Control Room along with 5 airline respirators and associated airline hoses. ' 4.1.6.2 Document operability of respiratory equipment
- in accordance with Reference 2.1.
4.2 Quarterly Emergency Equipment Inventory / Inspection 4.2.1 Emergency equipment k'its shall be inventoried quarterly and after each use using the appropriate Emergency Equipment Kit Checklist (Enclosures 5.4 - 5.13) 4.2.1.1 Consult the Emergency Equipment Kit Location i
' Sheet (Enclosure 5.2) for the locations of each -
kit.
'~
4 2.1.2 Perform monthly checks as in Steps 4.1.1, ' 4.1.3, 4.1.4, 4.1.5, 4.1. 6. 4.2.1.3 The quarterly operability check on two-way low band radios shall be performed as follows: 4.2.1.3.1 Radios shall be checked from a l point 10 miles from the plant in I accordance with Reference 2.8. l l I N a
. _ _ . - - - ~
I . I l HP/0/B/1000/06 Page 5 cf 7 1 i i
' ' 4.2.1.3.2 Contact shall be made from the base 'l ,
station in the TSC to each of the I radios. I 4.2.1.3.3 Each of the radios shall make contact with the base station. NOTE: Base' Call Sign - KNHB-778 Radio Call Signs - KB36274 (Alpha, Bravo, Charlie, Delta, Echo, Foxtrot) 4.2.1.3.4 Document operability of radbas on Enclosure 5.1. 4.2.1.4 Perform a functional check of the dosimeter charger / reader. The charger is acceptable for use if the charger light illuminates. , 4.2.1.5 Ensure that the leak and source check dates on ; the dosimeters are current. 4.2.1.6 Ensure that the TLD's are the appropriate ones , for the current quarter. [ ~ 4.2.1.7 Ensure the Potassius Iodide tablets have not ' exceeded their expiration date. 4.2.1.8 Ensure the seal on the silver zeolite cartridge , packet is not broken and the cartridges are not ' damaged. 4.2.1.9 Ensure that all procedures are current with the Control Copy. . 4.2.1.10 Ensure the flashlight bulb illuminates properly. . 4.2.1.11 Check all protective clothing for tears, rips a or holes, cracks in rubber, missing snaps, broken - : zippers, etc. , ! f
"~ 4.2.1.12 If any deviations are found, they shall be -
noted in the deviation section of the - applicable Emergency Equipment Kit Checklist (Enclosure 5.4 - 5.13). 4.2.1.12.1 Give a brief description of the deviation in this section. 4.2.1.13 Document any deviations on the Emergency Equipment Deviation Authorization Sheet 4 (Enclosure 5.14). 9 ee *
, - ,- - - - - - . nmv . ,. +,nr.,--m----m -----.,-,-m -
- - - , . , . , - - ,,,p..,~ -~ , y.-. , . - - , -,w ,,, - , , ae,,,.-m- w.- re e
( HP/0/B/1000/06 Pcge 6 of 7 I r' 4.2.1.14 The Technician shall sign off Enclosure 5.14
- and the appropriate checklists (Enclosures 5.4 - 5.13) and forward to the i Respiratory / Instrument Calibration (R/IC)
[ Supervisor. i { 4.2.2 Weather Information Check i 4.2.2.1- Quarterly a call shall be placed to the National Weather Service located in Columbia, SC at 803-794-2330 or 803-794-2593. If these 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. - 4.2.2.2 Obtain the same information from the Control Room. 4.2.2.3 Record this information on the Weather Information Form (Enclosure 5.2). 4.2.2.4 Compare the information from the Contirol Room and the Weather Bureau. If differences are found greater than 22' in wind direction and/or M 50% in wind speed, the difference shall be Ca documented on Enclosure 3.14. 4.3 Deviation Authorization 4.3.1 The Station Health Physicist shall be made aware of any deviation recorded on Enclosure 5.14. 4.3.2 The Station Health Physicist shall have evaluated the consequences the deviation may have upon the capability to respond to an emergency situation. 4.3.3 Enclosure 5.14 shall be used to state the action taken to remedy the deviation, and to state the justification for ,
. taking that action.
4.3.4 Sign off the PT printout and forward as per Reference 2.3. 4.4 Upon completion of this procedure all required documentation will be filed in the Emergency Equipment Functional Check and Inventory Log, until the end of the quarter.
~
4.4.1 At the end of the quarter all of the required documentation will be forwarded to the Station Health Physicist (KP) for review. 4.4.2 After review by the Station H.P., the documentation shall be forwarded to Master File * ' I .
HP/0/B/1000/06 s Paga 7 cf 7
,.' 5.0 ENCLOSURES l 5.1 Sample of Monthly / Quarterly Emergency Equipment Check Sheet 5.2 Sample of Emergency Equipment Kit Location Sheet 5.3 Sample of Weather Information Form 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 i
5.8 Sample of Personnel Survey Kit Checklist (Evacuation Facility) 5.9 Sample of Emergency Medical Kit Checklist (First Aid Room) 5.10 Sample of Emergency Medical Kit Checklist (Piedmont Medical Center) 5.11 Sample of Operations Support Center Kit Checklist i 5.12 Sample of Technical Support Center Kit Checklist [ ( 5.13 Sample of Fuel Transfer Kit Checklist
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5.14 Sample of Emergency Equipment Deviation Authorization Sheet
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e l Pcgn 1 cf 2 l CATAWBA NU; LEAR STATION l MONTdLY/QUARTIRLY EMERGENCY EQUIPMEhT CHECK SHEET HP/0/B/1000/06 ENCLOSURE 5.1
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4' 4l ql 8 Comments / Signature /Dat Environmental Survey Kit -A Environmental Survey Kit - B Environmental Survey Kit -C Environmental Survey Kit -D Environmental Survey Kit -E Recovery Kit - Allen Recovery Kit - Transmission Line Maint. Recovery Kit - Security Pap Area Recovery Kit - Construction Personnel Area Personnel Survey Kit -Allen {- Personnel Survey Kit - Transmission Line Maint. t ersonnel Survey Kit - Security Pap Area Personnel Survey Kit - Construction Personnel Area Emergency Medical Kit - First Aid Room Emergency Medical Kit - Piedmont
, Medical Center -
3perations Support Center Kit Technical Support Center Kit Fue1 Transfer Kit k e 6
. - . . -. ~. - -. . . . . - - ., . _ . - - . .. ..- ..- _... - ..
Pess 2 of'2 MONTHLY / QUARTERLY EMERGENCY EQUIPfGNT CHECK SHEET HP/0/B/1000/06 j ENCIDSURE 5.1 f.s : e GASOLINE GENERATORS s i Benerator Number Comments Signature / Data i 1 f l . j PORTABLE RADIO TRANSMITTER - RECEIVERS 1 j Radio Call Sign Comments Signature /Date j ,
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CATAWBA NUC'.2AR STATION EMERGENCY EQUIPMENT LOCATION SHEET
, HP/0/B/1000/06 ENCICSURE 5.2 KITS LOCATION Recovery Kits (4)
Evacuation Facilities (2) Allen Steam Station Transmission Line Maintenance Building Security Pap Area Temp. Admin. Building Construction Personnel Access Area Temp. Admin. Building Environmental Survey Kits (Vehicle) (4) Temp. Admin. Building Environmental Survey Kit (Helicopter) (1) Temp. Admin. Building Personnel Survey Kits (4) Evacuation Facilities (2) Allen Steam Station Transmission Line Maintenance Building Security Pap Area Temp. Admin. Building Construction Personnel Access Area Temp. Admin. Building Emergency Medical Kit (2) Aux. Building 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. Building k
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1 CATAWBA NUCIZAR STATION ' WEATHER INFORMATION HP/0/B/1000/06
- r. ENCLOSURE 5.3 k.1 s National Weather Service ,
Control Roos s ' Wind Direction x
, Wind Speed Cloud Cover Time ,
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*- CATAWBA NUCLEAR STATION t A RECOVERY KITS CHECKLIST HP/0/B/1000/06
, ENCIASURE 5.4 l
l (. l ( MININUM I'!T.M AMOUNT 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 i Dose Cards 25
' TLD Badges 6
, Dosimeter Charger 1 Boundary Ribbon or Rope (50 yd. roll) 1 i Masking Tape (roll)
- 1 Rain Suits (set) 2
( Protective Clothing (set) 2 Poly Bass (Various) 12 A Caution Signs w/ inserts 2 Lezal Pad 1 Instrument /Seear Survey (pad) 1 Pens - 2 Grease Pencil 1 i I 1 Full Tace Respiratior With High Efficiency Filters 2 First Aid Kit 1 l Potassium Iodide Tablets Trans. Line Maint. 275 bottles Security PAP 150 bottles Temp. Admin. Bldg. 150 bottles (,- _ f Allen Steam Station 275 bottles y i KI Distribution Data Sheet 100 ! Seears (box) 1 NuCon Seears 30 ; i Flashlight 1 Batteries (Size D) 10 t Scissors 1 Medication Envelopes Trans. Line Maint. 100
- j Security PAP 60 -
Temp. Admin. Blds. 60 . Allen Steam Station 100 ' HP/0/B/1003/12 1 HP/0/B/1009/16 e 1 i ! This Kit has been inventoried and Steps 4.2.1.4 through 4.2.1.14, if - ( applicable, have' been completed. ,a A._g o ,' , Signature /Date , I !
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%A ny Deviations will be documented on the Emergency Equipment Deviation Authorization Sheet (Sample Enclosure 5.14). {
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Pcg21 cf 2 s CATAWBA NUCLEAR STATION ENVIRONMENTAL SURVEY KITS CHECKLIST HP/0/3/1000/06 ENCLOSURE 5.5 [ MINIMUM ITEM AMOUNT DEV.* List of Contents 1 Eberline E-520 w/HP-270 Probe 1 l Eberline E-140N w/HP-210 Probe (or equivalent) 1 Exempt Source 1 1 .! Portable MCA** Eberline PIC 6A 1 Emergency Radio Transmitter / Receiver 1 ! ( Radeco H809V Air Sampler 1 Gasoline Generator (Gasoline in-Safety Cabinet) 1. l Low /High Range Pocket Dosimeter (0-500 mR), (0-5R) 2 each q 25 1 Dose Cards 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 Bass (Various Sizes) 6' Masking Tape (roll) 1 '
Limnological Sampler 1 Cubitai.wrs 6 f_' ' 1 Liter Wide Mouth Bottles 5 Stopvatch 1 Flashlight i Batteries (Size D) 14 Batteries (9 volt) 4 Silver Zeolite (CP-100G or GY-130) Filter Cartridges and Particulate Filters 30 i Filter Cartridges Labels & Bass 100 Smears (box) 1 30 i NuCon Smears ; Instrument / Smear Survey (pad) 1 Map of Ten Mile Zocs Sectors 1 Legal Pad 1 Pen 2 Permanent Marker 1 Hand Spade -1 -)1 Grease Pencil and refills 1 Dime Roll 1 l
- 1. ,'
Scissors Rain Suits 3 Telephone location maps 1
- Field Monitoring Data Sheet 20 Field Monitoring Work Sheet 20 i
KI Tablet Distribution Data Sheet 1 Radio Operator Manual 1 CPD1 Key 1 Cotton Liners (pairs) 5 SLED Badges (Personal - Vehicle) 4 _ 1 HP/0/B/1009/04 89
- ___--._A_-_-____ . - _ _ . - - _ . _ _ _ _ . - _ _ _ _ _ _ _
Peg 3 2 of 2 CATAWBA NUCLEAR STATION ENVIRONMENTAL SURVEY KITS CHECKLIST f-
.HP/0/B/1000/06 ENCLOSURE 5.5 4 MINIMUM AMOUNT DEV.*
ITEM 1 I 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 This Kit has been inventoried and Steps 4.2.1.4 through 4.2.1.14, if applicable, have been completed. Signature /Date
- Any Deviations will be documented on the Emergency Equipsient Deviation Authorization Sheet (Sample Encicsure 5.14).
**This instrument is stored and maintained in the Health Physics Counting Room Area.
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CATAWBA NUCLEAR STATION : ENVIRONME! CAL SURVEY KITS CHECKLIST (Halic:pter) l HP/0/B/1000/06 j ENCLOSURE 5.6 ; I,. MINIMUM 4 ITEM AMOUNT DEV.* List of Contents 1 Eberline PIC-6A 1 Eberline E-520 v/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 (Size D) 10 Batteries (9 volt) 4 { Ear Plugs (pairs) 6 Map of Ten Mile Zone Sectors 1 : Legal Pad 1 Pen 2 l Rain Suits 2 i Instrument / Smear Survey (pad) 1 '
- h.L Emergency Radio Transmitter / Receiver 1 HP/0/B/1003/05 1 ;
HP/0/B/1003/12 1 i HP/0/B/1009/19 1 i HP/0/B/1009/04 1 HP/0/B/1009/16 1 l 1 i I l i c i This Kit has been inventoried and Steps 4.2.1.4 through 4.2.1.14, if l applicable, have'been completed. ! l 4 l. Signature /Date ,
*Any Deviation will be documented on the Emergency Equipment Deviation Authorization Sheet (Sample Enclosure 5.14).
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-- . l Paga 1 of 2 CATAWBA NUCLEAR STATION 1 PERSONNEL SURVEY KITS CHECKLIST l HP/0/B/1000/06 I ENCLOSURE 5.7
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MINIMUM ITEM AMOUNT DEV.* 1 List of Contents 1 ! Eberline E-140N w/HP-210 Probe (or equivalent)*** 2 f Sample flide 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 l Dose Cards 25 ; TLD Badges 2 l Dosimeter Charger 1 Full Face Respirator With High Efficiency Filter 2 Potassium Iodine Tablets (bottle) 2 KI Distribution Data Sheet 1 Protective Clothing (Full set) 6 Boundary Ribbon or Rope (50 yd. roll) 1 Caution Signs w/ inserts 4 .i Masking Tape (roll) 1 Poly Bass (Various) 6 i Smears (box) 1 NuCon Smears 25 Instrument / Smear Survey (pad) 1
, /- Pens 2 Grease Pencil & Refills 1 Legal Pad 1 Scissors 1 Rain Suits 3 Decon Kit
- 1 '
- 1) Red Con
- 2) Rad Wash '
- 3) Paper Towels -
- 4) Scrub Brush e
- 5) Cotton Swabs
- 6) Fingernail Clippers ~ ,
- 7) Phischex (125 al) -
Batteries (Size D) 10 Station Directive 3.8.3 1 - , HP/0/B/1003/31 'or HP/0/B/1003/11 1 - HP/0/B/1004/06 1 ,
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HP/0/B/1009/05 . 1
- HP/0/B/1009/16 1 +
HP/0/B/1009/19** 1 i C i e D
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_.1 Pcg2 2 of 2 l CATAWBA NUCLEAR STATION
- PERSONNEL SURVEY KITS CHECKLIST j HP/0/B/1000/06 ENCLOSURE 5.7 y
This Kit has been inventoried and Steps 4.2.1.4 through 4.2.1.14, if applicabis, have been completed. Signature /Date
*Any Deviation will be documented on the Emergency Equipment Deviation Authorization Sheet (Sample Enclosure 5.14).
**Only the Construction Personnel access area shall have an Emergency Radio and procedure.
***The Security PAP Area shall have (3) E-140N w/EP-210 Probe or equivalent and Sample Slide Tray. The Construction Personnel Access Area shall have (2) E-140-N w/HP-210 Probe or equivalent and shall not have a Sample Slide Tray.
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L CATAWBA NUCLEAR STATION PERSONNEL SURVEY KITS CHECKLIST ' (EVACUATION FACILITY)
, HP/0/B/1000/06 ENCLOSURE 5.8 ~
MINIMUM ITEM AMOUNT DEV.* I i List of Contents 1 Eberline E-140N w/HP-210 Probe (or equivalent) 3 Exempt Source _ 1 Lou /High Range Dosimeters (0-500 mR), (0-5R) 4 each Dose Cards 25 TLD Badges 4 Dosimeter Charger 1 Potassium Iodide Tablets (bottle) 2 KI Tablet Distribution Data Sheet 1 Medication Envelopes 3 Protective Clothing (Full Set) 6 Boundary Ribbon or Rope (50 yd. roll) 1 1 Caution Signs w/ inserts 4 Masking Tape (roll) 1 Poly Bags (Various) 6 Smears (box) 1 Instrument / Smear Survey (pad) . 1 Pens 2 ; Grease Pencil & Refills 1 Legal Pad 1 - Decon Kit i d 7$ 1- 1) Rad Con
- 2) Rad Wash
- 3) Paper Towels I
- 4) Scrub Brush
- 5) Cotton Swabs
- 6) Fingernail Clippers
[ 1
- 7) Phischex (125 al)
Scissors 1 Disposable Coveralls 40 Station Directive 3.8.3 1 Evacuation Personnel Dose Record { 50 t Catawba Nuclear Station Telephone Directory 1 . Batteries (Size D) 10 , HP/0/B/1003/31 or HP/0/B/1003/11 1 ' HP/0/B/1004/06 , HP/0/B/1009/05 1 1 __
-);
- HP/0/B/1009/16 1 l
"~ k This Kit has been inventoried and Steps 4.2.1.4 through 4.2.1.14, if I applicable, have been completed. i 4
I Signature /Date
*Any Deviation will be documented on the Emergency Equipment Deviation ,
Authorization Sheet (Sample Enclosure 5.14). l l s
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l? CATAnfBA NUCIIAR STATION EMERGENCY MEDICAL KIT' CHECKLIST !- FIRST AID ROOM HP/0/B/1000/06 ENCLOSURE 5.9 i-
~
MINIMUM ITEM AMOUNT DEV.* List of Contents 1 Eberline E-140N w/HP-210 Probe (or equivalent) 1 Exempt Source 1 Poly Bass (various sizes) 6 Smears (box) 1 Nucon Smears 25 Protective Clothing (Full Set) 4 Rain Suits ' 2 Tape, Radioactive Material 1 Tape, Masking 2" 1 Tape, Duct 2" 1 g Instrument /Saear Survey (pad) I j Pens 2 l Legal Pad 1 Caution Signs w/ inserts 3 Radioactive Material Tags 50 Scissors 1 Poly for Ambulances (bundles) 3 Protective Clothing for Ambulance Drivers (Sets) 2 Batteries (Size D) 4 c HP/0/B/1003/31 or HP/0/B/1003/11 1
.( HP/0/B/1004/06 1 HP/0/B/1009/03 1 1 4
This Kit has been inventoried and Steps 4.2.1.4 through 4.2.1.14, if applicable, have been completed. i Signature /Date
*Any Deviation sill be documented on the Emergency Equipment Deviation Authorization Sheet-(Sample Enclosure 5.14). .
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L CATAWBA NUCLEAR STATION l: EMERGENCY MEDICAL KITS CHECKLIST TIEDM0!fr MEDICAL CEhTER l HP/0/B/1000/06 ENCLOSURE 5.10 MINIMUM 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 1 Poly Bass (various sizes) 14 j Smears (box) 1
, NuCon Smears 25 Tape, Radioactive Material l ' 1 Tape, Masking 2" ]
2
. Tape, Duct 2" 2 Instrument / Smear Survey (pad) 1 Caution Signs w/ inserts 5 Rad Rope 1 1 TLD Badges 10 l Pocket Dosimeters (0-500mR) 10 Dose Cards 25 Desimeter Charger 1 Radioactive Material Tags 50 Floor and Vent Covering i Disposable Coveralls 25 Disposable Shoe Covers (pairs) 25
',', Cubitaners 5
Decon Kit 1
- 1) Rad Con
- 2) Rad Wash
- 3) Paper Towels
- 4) Scrub Brush
- 5) Cotton Swabs
- 6) Fingernail Clippers
- 7) Phischex (125 al)
Cotton Gloves (pairs) 50 Rubber Gloves (pairs) 20 Batteries (Size D) 8 Grease pencils (box) 1 HP/0/B/1003/31 or HP/0/B/1003/11 1 HP/0/B/1003/12 1 - HP/0/B/1004/06 ' - 1 HP/0/B/1009/08 1 _ This Kit has been inventoried and Steps 4.2.1.4 through 4.2.1.14, if applicable, have been completed. Signature /Date -
*Any Deviation will be documented on the Emergency Equipment Deviation -
\
Authorization Sheet (Sample Enclosure 5.14). s 3 a _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _
1 Pass 1 of 2 CATAWBA NUCLEAR STATION OPERATIONS SUPPORT CENTER KITS CHECKLIST HP/0/B/1000/06 ENCLOSURE 5.11
- MINIMUM ITEM AMOUNT DEV.*
4 List of Contents 1 Protective Clothing (Set) 40 Full Face Respirators with High Efficiency Filters 10 Flashlights 11 Batteries (Size D) 34 Batteries (9 volt) 20 Eberline PIC 6A 5 RM-14 tJ/HP-210 Probe 1 E-140N w/HP-210 Probe (or equivalent) 1 Exempt Source 1 Camera (Polaroid) 1 Polaroid Film Pacs 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 Bags (various sizes) 50 Radeco H809V Air Sampler - 3
.-.. Silver Zeolite (CP-100G or GY-130) Filter Cartridges
[\ and Particulate Filters 30 Filter Cartridge Labels 30 Potassium Iodide Tablets (bottle) 20 KI Distribution Data Sheet 4 10 HP/0/B/1003/02 1 HP/0/B/1003/05 1 HP/0/B/1003/31 or HP/0/B/1003/11 1 HP/0/B/1004/06 1 OSC Response Personnel Dose Record 25 Decon Kit 1
- 1) Rad Con
- 2) Rad Wash
- 3) Paper Towels
- 4) Scrub Brush
- 5) Cotton Swabs -
i
- 6) Fingernail Clippers
- 7) Phisobox (125 al)
Instrument / Smear Survey (pad) 1 - i ',_ Telephone 2 Post-Accident Containment Air Sampling Equipment Kit 1 Pen (box) 1 Grease Pencil (and refills) (box) 1 Extension Cord (50 ft.) 2 Extension Cords (25 ft.) 2
- Stopwatch 2 Large Battery Lanterns 4 Status Boards-(set) 1 6
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f2 CATAWBA NUCII.AR STATION OPERATIONS SUPPORT CENTER KITS CHECKLIST HP/0/B/1000/06 ENCLOSURE 5.11 MINIMUM ITEM AMOUNT DEV.* j l l OSC Response Personnel Dose Record Forms 100 l i i Smears (box) 1 , i ! ( J l i This Kit has been inventoried and Steps 4.2.1.4 through 4.2.1.1.4, if applicable, have been completed. .i
)
Signature /Date
*Any Deviation will be documented on the Emergency Equipment Deviation :
Authorization Sheet (Sample Enclosure 5.14). l 4 e o Y G
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Pega 1 of 2 CATAWBA NUCLEAR STATION TECHNICAL SUPPORT CENTER KIT CHECKLIST HP/0/B/1000/06 ENCLOSURE 5.12 MINIMUM 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 l Eberline PIC-6A 3 E-140N w/HP-210 Probe (or equivalent) 1 Exempt Source 1 Radeco H809V Air Sample 1 Dosimeter (0-100R), (0-SR) 6 each Dose Cards 25 Silver Zeolite (CP-100G or GY-130) Filter Cartridges and Particulate Filters 30 1 Filter Cartridge Labels 25 Dosimeter Charger 1 Potassium Iodide Tablets (bottle) 25 Boundary Ribbon or Rope (50 yd. roll) 1 Caution Signs w/ inserts . 3 , Red Tape 2 - Smears (box) 1 Poly Bags 6 Masking Tape (Roll) 1 i ( Pen 2 Legal Pad 1 , Grease Pencil (and refills) 1 Flashlights 8 Batteries (Size D) 30 Batteries (9V) 12 Small Sample Bottles 10 Rain Suits 6 Decon Kit 1
- 1) Rad Con
- 2) Rad Wash
- 3) Paper Towels
- 4) Scrub Brush '
- S) Cotton Swabs
- 6) Fingernail Clippers -
- 7) Phischex (125 ml)
Instrument / Smear Survey (pad) 1 !
~
Request for Exposure Extension Forms 15 - Aux. Bldg. Drawings (set) 1 HP/0/B/1003/02 1 i HP/0/B/1003/05 1 HP/0/B/1003/12 1 HP/0/B/1009/16 1 HP/0/B/1003/31 or HP/0/B/1003/11 1 HP/0/B/1004/06 1 _ .-y ,
3 I Pag 2 2 of 2 CATAWBA NUCIIAR STATION TECHNICAL SUPPORT CLVIT.R KIT CHECKLIST HP/0/B/1000/06 ENCLOSURE 5.12 e- l
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This Kit has been inventoried and Steps 4.2.1.4 through 4.2.1.14, 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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7' Pcg31 of 2 CATAWBA NUCLEAR STATION FUEL TRANSFER KIT CHECKLIST
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HP/0/B/1000/06 -r ENCLOSURE 5.13 , MINIMUM ITEM AMOUNT DEV.* List of Contents 1 Shoe Covers: disposable (pair) 20 rubber (Pair) 6 Gloves: disposable (bundle) 1 surgeons (box) 1 rubber (pair) 6 Coveralls: disposable 4 - cloth 6 Hoods 4 Wet Suit 2 Hard Hat 3 Full Face Respirators with High Efficiency Filters 2 Radeco H809V Air Sampler 1 Eberline E-140N w/HP-210 Probe (or equivalent) 1 Eberline PIC-6A 1 Eberline E-520 w/HP-270 Probe 1 Exempt Source 1 Silver Zeolite Cartridges and Particulate Filters 10 Labels for Filters and Cartridges 10 Potassium Iodide Tablets (Bottle) 30 (.'s TLD Badge Low /High Range Dosimeter (0-500 mR), (0-SM 5 5 acch - ' 1 Dose Card 25 Dosimeter Charger 1 Weather-Proof Caution Signs with Inserts 4 Radioactive Waste Signs (4" x 6") 12 Caution: Radiation / Radioactive Material Tags 12 50 yd. Roll of Barricade Tape (Magenta & Yellow) 4 Step Off Pads 3 Poly Bags 12 Hand Gardening Spade 1 ; Wide Mouth Sample Bottles 4 ' Plastic Sample Bottles 12 Kimwipes (box) 2 NuCon Seears 100 - ' Copy of NAC-1 D'rawings (Prints) 1 Copy of Loading and Unloading Instructions 1 l l - Duct Tape (Roll). 2 Masking Tape (1" and 2" Rolls) leach Contact Pyrometer with Probe 2 Safety Glasses 5 Binoculars 1 Tool Kit 1 Batteries (9 Volt) 4 Flashlights 2 Batteries (Size D) 18 Steno Pad with 2 Mechanical Lead Pencils 1 Pencil Refills 1 4 %
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I'! ~ Paga 2 of 2 CATAWBA NUCLEAR STATION FUEL TRANSFER KIT CHECKLIST l HP/0/L/1000/06 ENCLOSURE 5.13 MINIMUM ITEM AMOUNT DEV.* Grease Pencils 2 All Purpose Harker 2 Scotch Tape Roll and Dispenser 1 Roll of Dimes 1
. Gasoline Generator (Gasoline Stored in Safety Cabinet) 1 Instrument /Saear Survey (pad) 1 HP/0/B/1003'/02 1 HP/0/B/1003/05 1 HP/0/B/1003/12 1 HP/0/B/1009/16 1 HP/0/B/1003/31 or HP/0/B/1003/11
( ,
.s This Kit has been inventoried and Steps 4.2.1.4 through 4.2.1.14, if applicable, have been completed.
Signature /Date
*Any Deviation will be documented on the Emergency Eq'tipment Deviation Authorization Sheet (Sample Enclosure 5.14).
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