ML20092B278
ML20092B278 | |
Person / Time | |
---|---|
Site: | Catawba |
Issue date: | 04/03/1984 |
From: | Tucker H DUKE POWER CO. |
To: | |
Shared Package | |
ML20092B272 | List: |
References | |
PROC-840403, NUDOCS 8406200132 | |
Download: ML20092B278 (188) | |
Text
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?R0020:22 ?RI?!uA!!!N Chan;c(s) 0 to ?RCCESS RIC0.C 0 Incorporated (2) STATION: Catawba (3) ?RCCIDURE TI*LE: Distribution of ?otassiu: Iodide Tablets in the Event of a Radici: dine Relasse (4) ?RI? ARID 3Y: -r',t r d-[ . MW 0A!E: $*II*81 (3) REVII'ED SY [h. _d DAT2: f j /- 7 Cross-Disciplinary Review By: N/R: [8--I -[
(6) TEMPORARY APPROVAL (IF NECESSARY):
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l 1 .' HP/0/3/1009/16 Ch?. POWER COMPANY CATAW3A NUCLEAR STATION DISTRI3CTION OF POTASSIUM ICDIDE TA3LETS IN THE EVENT OF A RADIGICDINE RELEASE - 1.0 PURPOSE This procedura provides information necessary to distribute Active Potassium Iodide (KI) tablets to in plant personnel in the event of . a release of radiciodine. Also, it outlines s;orage and supply information to assure sufficient quality and quantity of thyroid blocking
- material.
2.0 REFERENCES
2.1 HP/0/3/1001/09, Operation / Calibration Procedure for the Body Burden Analy:er 2.2 HP/0/3/1009/10, Sody Eurden Analysis Following Suspected Uptakes of Mixed Fission or Activation Products 2.3 System Health Physics Manual 2.4 NCRP Report No. 55; Protection of the Thyroid Gland in the Event of Releases.of Radioiodine 1977 (' 2.5 NCRP Report No. 651; Manatement of Persons Accidentally Contaminated With Radiciodine 1980 - 2.6 NUREG 0654 i 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 PRECALTIONS 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
.nsult 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 as 24 hours after an emergency will provide some protection. .
- 3.5 Discolored or disfigured tablets, tablets that save reached the
expiration date listed on the bottle, and bottles of KI with loose % tops shall be discarded. ' i 9
HP/0/3/1009/16 - Page 2.of 4 a 3.6 Hands of anyene tcuching the KI tablets =ust be free of radioactive contamination prior to taking the KI tablats. 4.0 PRCCIDGE , 4 . 4.1 Respons'ibilities For Distribution 1.1.1 The Station Health Physicist, in conjunction with available medical advice, shall control the destri-bution of KI tablets. . 4.1.2 Persons suspected of having been in the affected area prior to the detection and during the release, persons present in the affected area and persons who will enter the area while a significant amount of radioiodine is present will be instructed by the Health Physics Supervision to i==ediately register in the KI distribution center (for example, the Technical Support Center). 4.1.2.1 A significant amount of radioiodine for short duration in-plant exposure is that amount taken into the body that would result in a dose of , 10 res or more. For example, exposure to
- approximately 700 weighted HPC-hours, or 6.1 x 10
- uCi/a1 Airborne I-131 for one hour, ,
j 2 - would result in a dose of 10 rom. i (
\_- 4.1.2.2 A significant amount of radiciodine for emergency workers in the field is 70 MPC i (6.1 x 10 7 pCi/ml) I-131.
4.2 Registration of persons exposed to a significant amount of radio-iodine. 4.2.1 When persons notified by Health Physics arrive at 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 l tablet. Then issue to each person one bottle containing nine (9) KI tablets, and the package insert for the use of the tablets (refer to Enclosure 3.2 for an example of the General Manufacturers Guidelines). 4.2.2.1 Tablets are to be taken only as directed. One (1) tablet per day for the length of the emergency. 4.2.2.2 After the initial dose of KI, subsequent doses
- will be taken on a daily basis. Tablets should ..
~1 l be taken as near a 24-hour ' schedule as possible. ., ;
NOTE: For best results, emphasis must be placed upon the proper use of these - 1 tablets.- ! l m e-1
1 1
- EP/0/3/1009/16 ~
Page 3 of a a e.2.3 Table:s re=oved-fr:e full bo::le of KI should be stored in 10 ml plastic vials. The expiration data on the bottle frca which the tablets were taken and the name of the Health Physics representative shall )e recorded on the 10ml vials. Tablets stored in 10 ml plastic vials should - then be used for singla tablet initial issuance of KI to affected persons. 4.2.4 As directed by the Field Monitoring Coordinator (FMC) or the S&C Coordinator, team members shall ingest one (1) , tablet of Potassium Iodide. - 4.2.4.1 The FMC and/or S&C Coordina:or will provide the information for Enclosure 5.1 and will ensure that distribution of KI per Step 4.2.2 is accooplished by taas members. ! 4.3 Thyroid Surden Analysis Following Radiciodine Exposure 4.3.1 All persons receiving KI tablema should receive a thyroid scan. If the number of people render this step Lapractical, the 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 ., q by D/0/3/1009/10, 4.3.2 Records of thyroid scan shall be maintained per procedure. NOTE: Distribute KI before analyzing thyroid i concentration. Thyroid scans immediately . after an accident could lengthen KI dis-tribution time and cause confusion among personnel. 4.4 Storage Requirements 4.4.1 There are three major storage requirements to be obs6rved: 4.4.1.1 . Store in a temperature range of 39' to 86*F. 4.4.1.2 Store in a low humidity area (avoid direct exposure to liquids). 4.4.1.3 Store in an area protected from exposure to j light. , 3 4.4.2 Upon receiving a shipment of KI tablets, boxes shall be .
=,
opened as soon as possible and bottles examined to. ensure .y that an air-tight seal has been maintained. Sottles must *' be returned to boxes, and boxes must be sealed shut, so as '6 j to avoid exposure to light. ~~ l 4
RP/0/3/1009/16
, Page 4 of 4 ;
4.4.3 To ansure a sufficient supply of cablets, a =inimum of 1,000 bottles with la tabla:s per bo::le should be. maintained on site. 4.5 Shelf Life and Changeout of KI Tablets - 4.5.1 Thyro-31cek " table: bo::les are labeled with an expiratica date frem the factory. As tablata reach the expiratica dates, the tablets must be discarded. NOTE: Replacement tablets should be ordered at least - 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 3.1 Sample of Potassium Iodide Tablet Distribution Data Sheet 5.2 Manufacturers Guidelines for Thyro-Block Tablets and Solution i 9
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TAKE POTASS!U.'.! [UDIDE <1'iLY W i t h.'. I't' int.It:
!!r AI.T11 0FFICIAI.S TE!.L YCC. IN A ItADI A r:t a 'i Z'.tE tGENCY. ItADIDACTIVI: .i > D t .s F. u,l: r.D UM .
4 I'.ELEASED INTO T!!E A!!! P0 r. .:61 t .! !(stait,F ia i FO't.'.! OF ICDI.N12.1 t.*AN lli.' 6' PlasTl>:;' YiJi:. {
. ! IF YOt AhE TOLO I'U TAK1: T!!L:i *.thDit'i'.M. RAKE IT '
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! 100l!.4. (SEE SIDE EFFECTS tihLO'..*.i t .i INOICAr!ONS T!!Yl!OID !! LOCKING IN A !!ADIATION M*.tr.!t8iENCY O NI.Y.
OtAFCTIONO TOM U1J Uw o.dr u.forected by 'iinte ut torn;;su'.l e L.,ith .a in.e .ri. m s.. the event of a rushataan enw.rurney. 3CC; T4htrt y Aut!!!r:i ANiit'll!!.tII !:*3 . *. l: \;( tlF AtiE Ull (?l.leKit. ( r.e ..e sea.'. t awe a day Crush !..' ri.all t.i ls. n IJAlll!C: L NL!-:lt * '. i A i: t)F Arie Onelu.If ital tal.l.t e ac day. C:u:,1. fit. t.
'soludon: ADUllfS ANil(*;111.DitF..*! 1 Yl'Ait OF . AtiE Olt OL.11F.!!; Adit ti i! rop tu uni-half gf an of lie;unt el nr ult wach da) .
IIAlllES UNUi.Itt YEAit LF AGM; Add 3 drops to n ,m4il am..unt ..f Lr;uid on.;e e dav. Pari;;f dovere forms: Tals: far to day. aub . lu.c. .! . r.e twe e by :::ste or local public heatsh suit:ori.ww. . Store et con:rtaled raum temperature!wtu .i . .. t-' .. t ' . .'.-) to sti*Fl. Ecep cont 4;ner tighdy .kn . .ead us.. r tr.,n. ng i t. Do not use the si,lut;ca si it appassa 1.rs .wi.e :. ... t: . e . . ....: tus. bv.i WARtilttd l'orasslum iodide shau!J not .' asoJ hv pseid. .-I:. r.;.c ta s. 4.:. Keep out of the resch of chddrei. la ..i a f.. r et.c ..t sicrgic resction. contact a physisian ..s :he public !a. !sti u.sta.rity
+ ' a CESCRIPTION .
Each Tl!Y!tu.I1LOCKW TAlli.hT r..e.g.ne;, ... e...t ..i .* **1
# potassium iodide. .
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cittr the thyrvidC !Jni WHO 3HOULO t30T TAstc POTMsiur.t 10010C The only aitope w!.o sh..a;d aut t ... ,,. .. .n..o g.d.. nr..;w..ple wr.o knu o they .ro JAri;te is .6da 6 ba. ..~ c.' e r s P..t a v ..a. s
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HOW AND Wi!EN TO TME Poi,*4 ilt,M IQi>NC . I'otamus: loliJu AvuM t.et;u i.. ..,n. ret. d. 4.rpi teut h4 !.eulth ietficLd, ted s.,u *a u e.t.. .'.i e i i .. .aw o .4 u / 'M hs.i..a .'.lora w di sa.t 14 s ..:t u. s u t n. t :. . . ! i . .. "l:e.l.1 ' .ese
!) fursted amounta N .,J.ne. l.ar g.-i .i e . .. .!. .n. i . e . iw nk i.i tuhr rtfrits. %.u w .! g.s e.l.41 fy ; . t i.. t . t i .. ne r t n. .'t ..* l..e m..rv th.a tu it.s, . 'J,tM :.F. Li.1:5 OO bu.i!!v. a d., I!. v. ..f ; . .r. as.
e t.. . rom .-e. w f.. n 1. e.;.h* taaer 1. 3;her d.wn for aucg t r . inu .h... a N . a. (..! enet t.e fg * . t.k.. s.a.e e t ha:e t he sunitorna i.e. .I e' . .. . - . .. i. f .c a.br I ha i (, )ed era t..ld. N!e sifusta ite u.Aiscly 1,. . w w..a ..w .. i.va. a.. I the saw& L.mo yea wc;i.e iniara,t the ..e .t. l'umied.!v side rifWt: includ.. . kin t n. i. r t hs ar . ' t he hvary glands, and " ediam'* tmutak taetv. 5. . i n,t e. .tn : : tsa t. tore tseth and I;rns, s):r.ptuaa e us .a .wa.. sv:d. 4m! et.nn t.a.e5
. stan as!n upset and diarrt.rel A few pvulele !.sve en airar 6 tr..t no watt. s. a.: ~creuw s synp.
~ terns.These coul.! be frver and 3.a . ; ins. i4. .ethug f p. ta .,f tt.e face and bedv end at tia.u =vs..v ehos t nw .a..e be rath eritmr Ing imacudists medical attia.um. Taking iodade inay rarely upe overu.tites. uf ts.e t'syrreid a:tsr !. underectivity of taa thyriad b: d. i.e c. 44rgvum<nt <d t!.e . t!.yrvid gland Igoiteri. WHAT TO 0017 $10E CMCI'l CCCUR
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, P Form 'A721 110-811 I (Formerly 5P0100211 l .
ID Not !{P/0/3/1009/15 - DUKE PC'a*ER COMPA:*"I (1) PRCCIOURE PREPAR.CICN Change (s) O to , PROCES3 RECORD __ 0 Incorporated l 4 (2) STATION: CX3MA t (3) PROCCURE TITLE: CNTSI'M DOSE PICHETICtl$ - (2wwmf ?" PNE Cr l GTJIIX;5 PADIC7Cfra MNIT?.IAL CrntER 3GN t{ Pct Qt 35: C.Tr 'n2?r (4) PRZPARED SY: -. [ DATE: 2 F ff'
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'($) REVIr4ED SY: 2h DATE: J-/. * ,
Cross-Disciplinary Review 3ys N/R ) 2 M (6) TEMPORARY APPROVAL (IF NECESSARY): j By: (SRO) Dates , I Sys . Dates (7) AFFROVID SY: 'd
- Date Y 3!I[
(4) MISCELLANIQUS: Reviewed / Approved By: Dates . Reviewed / Approved By: Date: i
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n?lCi31100J/13 . CG'I PC'.T.R C0!!?ANY OATA*.2A NUC:.IAR STATICN CT73ITE DOSE PK0,JECTIONS UNCCNTROI.I.ZD RE!.ZASE 07 GASECUS R.GICACT!h !!ATERIAL - CTHi.R T:!AN THRCCGH THI !. NIT 'iEST 1.0 PURPOSE To describe an approved nethod for projecting dose comaitment frem 4 4 nchle gas or iodine release, other than a unit vent release, during an emergency. 2.0 RETERENCES
.1 Reg Gaide 1.109 2.2 Rog Guide 1.4 2.3 HP/0/3/1009/0o, Alternative. llethod for Determining Dose Rate 'n'ithin the Reactor Building 2.4 Variables used in N?/0/3/1009/1$. Letter Tila Number CN.: 13a.10 3.0 LIMITl AND PRECA!/rf0NS I
h 3.1 It is assumed that the iodine whole body dose from a release is very small campered to the icdine thyroid dose. Thus, iodine whole body dose is not considered nere. 3.2 This procedure applies to releases made frca Catawba Nuclear Station only. Many of the values contained in this proe.3duro are site specific. 3.3 This procedure considers all releases to be ground level releases. 4.0 PROCEDMRI 4.1 Acquire the following infonsation and record on saeple Enclosure 3.1. NOM: Should site meteorological data be unavailable, obtain wind speed and wind direction frce the National Vesther Service (Unitid States Government National Oceanic & Atmospheric Administration). NOTZ: If appropriate, obtain .1dvance meteorological data to calculate doses due to changing meteorological conditions. 4.1.1 Reactor Unit, date and time of reactor trip. 4.1.2 .ower tower wind speed (sph). - q 4.1.3 *
.v Tower wind direction in degrees from North (North = 0'). * ~ i 4.1.4 Tempe.*. 'ure gradient ( AT*C). .
L_ _____________.___.__._m_.___________________________.__._________________s
i l HP/0/3/1CC9/13
?.1gs 2 of 4 I l e.l.3 asdiatica ::ent::r (I.'!T 32.i or 333' rosdt. ; (Rihr) or -
calcula:ed ;4: Rafirance 2.3. l 4.1.6 Date ind time of calculaticas. , 1
- a. :stermine the Cen:aanmen: Buildin; laaks;e r :s (LR) and r$ cord it '
en sa=ple Inclosure 3.1. 4.2.1 L3 (al/hr) is the total leak rate for the containment which is one of the following: - 4.2.1.1 a "besc guess" assumption. I 4.2.1.2 the measured leak rste where suitable means are ! available; I 4.2.1.3 The design leakage rate (L2DLR) which is dator=ined i j' by: ! LRDL3 = Containment Volume
- Design Leak Constan:
= 2.83 x 10 al
- 0.0025 ,
day day 24 hr
- l s
= 2.93 x 10 ml/hr f**# 4.3 Determine the X/Q values for each point of interest downwind and record on Enclosure 5.1.
If no points have been requested, use the .5, 2, 3 and 10 mile values. 4.3.1 Locate the relative two hour downwind concentration value (CH) for each point from Enclosure 5.2 and record onto saepte Enclosure 5.1. 4.3.2 Convert these values to X/Q by,
%/Q = CH (MPN Sec/m8 )
Tower Wind speed (!!!N) 4.4 Determine the potential whole body dose from submersion in a cloud of noble aos and record on Enclosure 3.1. 4.4.1 Calculate tte whole body two (2) hour dese consitment, Dgg=Dgg*LR*X/Q*Uyg Vhere, Dgg = Whole body two (2) hour dose commitment , k ,, DR3 = Monitor dose rate *,, e- g O l
HP/0/3/1009/15 Page 3 of 4 . s
.C0 = Averags Osca; constant for nchie gases = ,
h 2.2o0;I ; SCt
- taV*hr#
21*d*3 l3 = Containment leakagi rua in .ml/hr X/Q = dispersion f actor in se /.1 8 ' (3.7E4/secauci) (1.6E 4erzsnfeVi 3g, 8 8 Ug = 2 (100 ergs /g rad) (1.2E 3g/cm ) (1C6cm /:8)
- 5.71-9 hr rad 8 al-A-sec 4.3 Determine the potential thyroid dose ir:m uptake of radioicdine and record on Enclosure 3.1. -
4.5.1 !.ocate the time plus one (1) hour after tri? on Enclosure 5.3 and record the corresponding 3acay constant on Enclosure 5.1. 4.3.2 Calculate a child's thyroid two (2) hour dose coseitsent.using time plus one (1) hoar,
- DR = DA g
- CC
- IA
- X/Q
- U 1 p' s
(, # Where. D h a thyroid two (2) hour dose commitment C = monitor dose rate uCi
- mees
- hrs DC a l'ecay Constant in e1*P1*AC for time plus one (1) hour (see Enclosurs 3.3)
!A = Leak rate la al/hr X/Q dispersion in sec/m 8 Ug = breathing rate for child times uCi to pC1 conversion factor oCi-ree a 8 sciares 8
(1.171 ke /ses) 113 bCi eroe = 1.171 1 see -vci eres
- e
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e G C_____.__ ______________________._______________.__________________________________._.__________________.____.___._______.______._____m
HP/C/3/1009/15. Page e of e . e.e De:arnine the potentially. af f acted : nss using Inclosure 3.e. Record tr.e affsc:ed :enos on Inclosure 3.3. e.7 Ccmplete Inclosure 3.5 and submit it :o :ho Data Analysis Coo rdinato r. In:ledo any cc=ments pertinent'to the evaluation of . offsite ha:ards. 3.0 INCL 0St1IS 3.1 Sa=ple Projected Offsite Cose Released From Containment 3.2 Sample Table of Two Hcur Relative Concentration Factors (C.dI 3.3 Sample Table of Iodine and Noble Docay Constant (DC) 3.4 Sample of Evalua:ica of Pluma Loca: ten 3.3 Sample Dose Assessment 3eport 1 3.6 Estimation of Containment Leak Rate g
- 9
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- HP/G/*J,1;;9/ 3 PEO.,I '"ID OTTSIT COSI 31:.IA3ID 750': CONTAIN:E.NT ,
!*ni: Date, Time at %ac:or Trip , i MIM 01C!.CGt0AI. DATA
- 1. Tower wind speed eph l
- . Tower wind direction *
- 3. Temperature gesdisnt (AT) 'C M0NITOR DATA
- 1. EMT $3A or $33/ Survey Inst. It , DR = R/hr 3
(Oircle One) NOTE: If c:ntsinment monitor inform.icion is not 'iseable, refer to Reference 2.3. 005Z CALCUIATION DATE/ TIME N , {w 1. LR st/hr
- 2. C,I1 mi. = , X/Q = soc /m 8
C0d
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- X/Q
- 3.7E-9, i
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.- '1 Nw . % ~
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- 3. D.yroid 0 hr. dose projact:,en fr m todine:
DC , by CR = DR
- CC
- I3
- X/Q * (1.17E 1). 4 i M Miles Out 02 9 2 hr Dese Commitment DEFINITICNS D.jg =* whole body 2 hour dose commitment from noble gases DRT=
thyroid 2 he dose commitment from iodine ( LR = containment leakage rate X/Q = " Chi over Q is dowwind conenntr.1tlen i;ortriction factor C = r re ative da w ind concentration - MPH W Q
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H DC = Decay constant C.13= dose rate at the containment monitor I
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. 1 - 499 HRS l-P/0/0/1309/IS . . - - - - - ._.-- ..---~-.--.--1--.----------.,
l HCLR CC HCUR CC HCUR OC hcl 2 OC HOUR OC l 0 0.0649E-05 10 0 :: .6125E 04 200 4.G7f:?O .:4 300 7.44105 04 400 7.?!09C 0" 2 5.7900E-05 102 5.6595E-04 202 6.8925E-04 302 7.453/E-94 402 7.'719?C-Ud 4 G.1506E-05 104 5.7050E-04 204 6.YO40E-04 304 7.4436E-04 404 7 9005E-04 4 1.0296E-04 106 5.7492E-04 206 4.9174E-04 306 7. 473M-04 40c * .V373E-04 / 3 1.2295E-04 100 5.7920E-04 203 6.932dE--04 308 7.4033E-04 400 7.9440E-04 10 1.4170E-04 110 5.G333E-04 210 4.9457E-04 310 7.4932C-O'4 410 7.9540E-04 12 1.5923E-04 112 5.3737E-04 212 4.9504E-04 312 7.5029E-04 412 7.9625E-04 14 1.7591C-04 114 5.9127E-04 214 6.971'iE-04 314 7 5127C-04 414 7.9722C-04 ! 16 1. 9159t*-04 116 5.5"J0 4E-0 4 23 6 6.934 ;E-O d 31.0 7.322*f t? -0 4 416 7. 9'3 0 YC-0 4 19 2.044 tie-04 110 5.9670E-04 210 4.994 E4 4 Dia 7.5221E-94 41C 7.9094E-04 20 2.::071E-04 .100 4. 0225E-04 220 7. 0 009E-04 320 7.G110E-U4 420 ~.9962E-04 22 2.343YE-04 122 6.0569E-0 4 222 7. 0212E 0 4 32.0 7.'"iS1GE-04 422 3.0060E-04 24 *2. 4757E-04 104 4. 0900E-04 ::24 7. c3*.:3. -14 301 7.54119 04 404 0.01CCC-04 24 2.6034E-04 124 6..t226E-04 ' J26 7. 0454E 4:4 322, 7.'.2737E-04 926 U.0240E-04 20 2 7272E-04 123 6 1540E-0 4 2.:0 7.L74C 'M I'! .0003ti-04 400 5.03262-04 30 2.3475E-04 130 6 1044E-04 230 7.04'.".'E 04 300 7.";G9?C-04 a19 0.0 4125-0*! 32 2.9645E-04 132 4 2140E-04 232 7.03109 04 332 7.5994804 432 0.0497C-04 34 3.0784E-04 134 6.21:4E-04 239 7.0'326E-J4 304 7.6009804 434 0.0503E-04 36 3 1993E-04 136 4.2705E-04 236 7.1042E-04 336 7.4134E-04 436 8.0440E-04
- 30 3.2975E-04 138 ~6 2975E-04 238 7.1157E- 0 4 330 7.6279E-04 430 0 07U3E-04 %, 40 3.4029E-04 140 4.3200& O4 240 7.1272E-04 310 7.4373C-04 440 0.0037C-04 4 42 3.5050E-04 142 4.3490E-04 242 7 1305E-44 342 7.6447E-04 442 8.09::2E-04 44 3 6062E-04 144 4.3741E-04 244 7.199t!E*-04 '19 4 7.M61E-0 4 444 9.1006C-04 46 3.7042E-04 144 4 39'I':E-04 244 7.1410E-04 744 7.coGM -Od 444 0 1090C-04 49 3 7999E-04 140 4.421GE-04 248 7.1721E-44 340 7.4740 5 04 440 3 1174C-04 50 3.8933E-04 150 6.4447E-04 250 7 10320-44 3G0 7.40428 04 150 0 1250E-04 52 3.9044E-04 152 4.4670E-04 252 7.1V42E-04 '152 7.490,E-04 452 0.1342C-04 54 4.0738E-04 154 6.4807E-04 254 7 2051E-04 354 7.702SE-04 454 0.1925E-04 to 4 1409E-04 156 4.5079E-04 256 7.2160 & 94 JU4 7.7120C-04 45o G.1509C-04 53 4.2460E-04 150 6.5006E-04 258 7 226aE-04 353 7.72.10E-04 450 8 1592E-04 40 4.3291E-04 140 4.5000E-04 240 7.237aE-04 360 7.7000E - 04 440 0.1475E-0 4 42 4.4100E-04 162 6 5705E-04 242 7 2403C-04 362 7.7377E-04 442 0 1757E-04 64 4.4e96E-04 144 4.5097E-04 244 7.2590E-04 '!44 7.74U9504 464 B.1040E-04 66 4.5469E-04 166 6.4085E-04 246 7.2496E-04 366 7.75G1E-04 444 a.19:3E-04 de 4.4425E-04 168 4.6249E-04 263 7.2'102C-04 363 7 7672C-04 460 e.2005C-04 i 70 4.7161E-04 170 6.4450C-04 270 7 29472-0d 370 7.7743C-04 470 U.2007C-04 72 4.7879E-04 172 4.c62/dP 272 7.2.?12C- 44 '!? 7.7554 5 01 172 2 2.149C-04 74 4.8579E-04 174 4.4799E-04 274 7.3116E-04 374 7.7Y ;M-04 474 0 2250E-04 74 4 9262E-04 176 6.6949E-04 276 7.0220 & 04 174 7.0136C-04 476 0 23 2E-04 l 78 4.9924E-04 170 6.7135C-04 270 7.0323E-04 37'] 7.0126E-04 470 3.::4(3604 00 5 0573E-04 180 4 7290E-04 200 7.3427E-04 ".00 7.021/E-04 400 B.2495C-04 02 5.1202E-04 192 4.7450E-04 2S2 7 352PC-04 332 7.3307804 402 0.2574E-04 04 5 1315E-04 184 4.7615&O4 234 7.36">2C-04 104 7.C397C-04 434 9 24*'7C-04
- U6 5.2410E-04 104 6.7770E-04 236 7.3?U45-04 396 7.d404E404 404 8 2737E 44 CO 5. ::9C9E-04 150 4.7"22E-04 2GG 7.::03'!E-04 300 7.C:',76C--04 400 0 2010C;04 ""1
()4 90 5.3551E-04 190 6.G072E-04 290 7.393M-04 '2YO ?.G445D04 490 8.2390E t04 92 5 4097E-04 192 4.a::19E-01 ::92 7.40'J7&O1 392 7.3754'4-04 492 0 2970C 44. 94 5.4627&04 194 6.0364g-04 2?4 7.412a2-94 394 7.cg40C-04 494 0,3000E-04 l 96 5 5142E-04 196 4.0507E-04 ::96 7.42E 04 394 7.397::C-04 494 0.3100&04 40 5.5611E-04 190 6.041CC-04 290 7.432dE-01 390 7.9020E-04 SYO 0.0210&O4 i I
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CUKI PC'4E3 COMPANY 5 0ATX40A NUCLIA2 3?A7 J5 l I -ov ISOLO371 !.e !
.9f/0/3/109/*3 -
l I'.*AL'JATICN 07 PL'ent LOO \T!CN I l t i 3.4.1. Acqui:e the fo11cving informa:;oa fr;: sample !.telosura 3.1 and l record on sample Enclosuro 5.3. , i
- t
. 3.4.1.1 Wind direction in degreen frem Norta (
5.4.1.2 Wind speed (sph) l f s $.4.1.3 A7 (*C) 5.4.1.4 Stabilt:y claas 3.4.1.5 Thyroid and whole bcdy done i 3.4.2. Determine tha affected zones, based on wLnd directica and wind i speed, with the following taelosi ; Table 3.1 0+3 ? tile Af fetted "onas ; k, , , Vlad Direction Affveted 2ones L C* 360' A0 I f Table 3,2 2 5 Mile Affneted %ones ( VLad Speed e 3 sph Wind Mpeed > $ eph VLad Direction , Affetted Zones Vind Direction Affected enes 0* 360' A1,ll .C1,01,t t ,T1 0.1' 22' C1, D1 22.1* 73* C1, D1, In 13.1*
- 104' C1, 01,11 F1 104.1* 1*0* Dl, Ei, F1 l
120.1*
- 1J9' 01, F1 '
130.1* 207' 01, 71, Al 2:11.1' = 2'i'. F1, A1, 31 247.l' = :s3' A1, 21 143.1' = 2948 A1, 31. C1
- ?4 1' = 12S' 31. C1 3 8.l*
- 360' 31 C1, 01
. e ,, "9 L, ...-
l .
';tM P;'..'23 C0"?nY l t C ATA'4] A '.t 2:.2...t .;7A71;.',
V E::*:.0SL*K3 J .. HP/0/3/10C1'13 . I'.'.t!.'JAT:;N *T ? .'#tt ,0JA71:N
- T cle 3.3 5 10 ?tila M fected 20n=s Vind Direction M fectad 2cnes 0.1' = 27' C2, 32 27.1' = 69' C*, D2, E2 67.1' = 13' D2, E2, F2 15.1' = 132' 02, 7.2. F2, F3 132.1' = ika' (2. F2, 73 144.1' = 162* f.2. F2. F3. A2 160.1* 201' F2, F3. 42 201.1' = 229' F2. F3. A2, 32
*29.1' = 241' F), A2, B2 241.I' = 239' A2, A3, 02 239.1' = 290' A2, A., 32, 02 190.1* 304' A3, h2, C2 304.1' = 333' 32. C2 =
333.1' = 360' 32. C2, D2 c# 3.4.3 Deterstae the protestive action autdes (PAC), hamed on the saltua 14:e4 dese(s) on Sample Enr.losure 3.1 and the following latorsattent 3.6.3.1 For deses 4 1 Res Whole lady or, 9 3 See Thyrstd Reseemend ne action. 5.4.3.2 For deseen j lal Ree Whele lady or, i ! 3=23 Ree Thyroid Reconnend evaeustion of children and pregnant women and sheltering of remainder of personnel in the affeated area, i
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W atemum 44 G .s w a m> % ,
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___._____._______________._____...__..______._____._....___________.__________._..._______________..m
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"'*A:.'.'AT:CN CT ?:.'. ':E *. !AT:GN l 3. .J.3 For doses: > 5 Roa Whole Body or, > 25 Res Thyroid Recommend Evact.ation of Population in Af fected Area.
l 3 . .'. 4 . Record only the af fected acnes re tutr1% protset.ve action en s4splo l Enclosurg 3.3 along with the reco. mend-d protor.tive actten, i i 1 l e l t { l ,, i i i l I l 8 e g- ..
*** I s
CCC FCht3 CCMPANY Pass 1 of 1 CATAWBA NUCI. EAR STAT!Ch t itP/0/ 8/1009/15
- i ENCI,05tRE 5.5 .
CCST. ASSC33? TENT RIPCRT k V.naD ..................................................................................... fower Crists Caspany Management Pl.tn Of f Site Dose Report = CATAVBA I Frepared ty Date/ Time / Irortency Critt (circle one) l Mat earolo gy , Vind Speet llPH j Wind Diroation degrees from North Vertical Temp. DLif. degrees C/100 ft. i Stability Class (circle one) A B C D E F G
! Source Ters Time Noble cas 1 131 equivalent Contaissent Red. Monitor R/hr R/hr ! ! Ccatainment Sample uC1/m1 uC1/e1
{ Unit Vent (Sample of I:tF) kC1/ rat uC1/rst 1 Curia Release Rate C1/sec . 1/sec
; Corresponds to: LOCA LOCAthroughfil.or ' , Coro damage Coro damage thre gh
- Liter
- _ Tube rupture Gas Decay Tank i New t' vel Old fuel Other _ '
Dose Projestions
.3 at 2 mi 3 et to et 2hr Doseires) based Whele lady _ . ; ,oe Centstament release Child thyroid __ ! $ al/hr I 2hr Dese(ree) bened Whele Body _
- on Unit Vent release Child thyroid t 0 cfs
)
I 2hr Dose (ree) based Whole ledy i en Steam release Child thyroid i the Dese(ree) based Vhele Body I j en rolesse Child thyroid , G }, ...................................................................................... l Tield Monitoring Data 1 1.ocation Distanee Direction Dose Rate (stem /hr) Contaminetten i (mt) khole body Child thyroid (dpe/100 cm ) { I j ......................................................................"'"............... Affected 2enes 0 2 at 2+3 mL 3=10 et 9 10 mi I (cirste senee) A0 T1 Il C101 El F1 A2 32 C2 D2 E2 T2 A3 F3 . CO?t*STS: **
- iw .
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xas Data Analysis Caordinator, Station Health Physicist
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a a' Form 34731 (10-81) (Formerty SPD.1CO21) DURE PO*a*ER COMPANY (1) ID No: HP/0/3/1000/L3 PROCEDURE PRE?ARAIICN Ch'nge(s) a a to PROCESS RECORD / Incorporated (2) STATION: Catawba (3) PROCEDURE TITLE: OFFSITE DOSE PROJECTION-UNCONTROLLED RELEASE OF RADIOACTIVE MATERIAL THROUGH THE UNIT VENT (4) PREPARED BY: [h M'. _ M DATE: b/ 5' (5) REVIEWED BY: /I.dh N C DATE: 2 * / I** W
<- y Cross-Disciplinary Review By: N/R:N"Ja (6) TEMPORARY APPROVAL (IF NECESSARY):
By: (SRO) Date: [ By: Date: (7) APPROVED BY: y l^/
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Reriewed/ Approved By: Date: Reviewed / Approved By: Date: 6tG:@?Q?/f#
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CATAW3A NUCLEAR STATICN OFFSITE DOSE PROJECTICN - UNCCNTROLLED.REI1ASE
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OF RADICAC IVE MATERIAL TiRCCGH ~~E UNIT VENT l.0 PURPOSE This procedure describes the method for projec:ing the potential offsite dose follcwing an uncontrolled release of radioactive materials :hrough the unit vent.
2.0 REFERENCES
2.1 Letter f cm Civil /Enviren= ental Division CN-1108.1,1424.00,1227.00 A: : spheric Dispersion Factor for E=ergency Planning 2.2 EPA-320/1-75-001, Manual of Protective Action Guidos and Protective Acticas for Nuclear Incidents 2.3 Regulatory Guide 1.109, Calculatien of Annual Doses 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 v- Pressurized Water Reactors , 3.0 LIMITS AND PRECAUTTONS 3.1 Use actual sample data when possible. Radiation monitor readings are susceptible to several sources of error. When endiation monitor readings are used for downwind concentra:icas, nor.. this.in the report of offsite dese 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. 4.0 PROCEDURE 4.1 Obtain the following information from the Control Rcom and record it on Enclosure 5.1 (Vent Release Data Shee:). 4.1.1 Time of reactor trip. - 4.1.2 Tower vind speed in MPH. *. - 9 (Lower tower wind speed preferred.) '4 I 1 l
3?/]/3/1009/'3 ,
. a;e 2 of 5 4
4.1.3 Direction fres which the wind is bicuing in degrees f:cm ,- North. (Uppe: :cwer wind d::2c:ien preis: red.) 4.1.4 Ta:pera:ura 3:adien: (17) in de; ees 2. 4.1.5 Ven: discharge flew rate in 2~'!. - 4.1.6 Available wea:her forecas: :nic: 2:icn. . 4.2 Determine the release cencent:stien as follows: 4.2.1 If vent sa=ple analysis is no3 available, go to Step 4.2.4 4.2.2 Obtain the follcwing vent sa=ple analysis results and record en Enclosure 5.1.
. 4.2.2.1 Date/ti=e of sa=ple.
4.2.2.2 Gross ncble gas concent:stion in 'gCi/ml. 4.2.2.3 Icdine equiislent concentra:icn (or data for calculation). 4.2.2.4 Gamma E-bar value in mev/ dis (or data for calculation). 4.2.3 Go to Step 4.3 ( . 4.2.4 Obtain the folicwing unit vent data and record on , sample Enclosure 5.1: 4.2.4.1 Date/Ti=a of collection. 4.2.4.2 EMF 36 Low and High range readings in epm (gas >. monitor). 4.2.4.3 AEMF37 reading in cpm (icdine monitor). 4.2.4.4 At in minutes for & EMF 37 reading. 4.2.4.5 Calculate release concentrations as shcun on Enclosure 5.1. 4.3 Project the impact of the release en the dcunwind 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, 5 and 10 mile, values. .
.s ~1 '4 As e=*
HP/0/3/1009/13 . Paga 3 of 5 4.3.1.1 Frem Enclosure 5.2 (Table of Two-Heur Relative .- Cencen::atien Fac: ors), loca:a :he relative two
- hour cencentra ica value (CH) for each poin:
and record en sa=ple Enclosure 5.3 (Manual Calculatien Worksheet), (Reference 2.3). 4.3.1.2 Ccavert these values :o X/Q by, - 3 CH(MPH-Sec/m f
/0
- Wind Speed (MPH) 4.3.1.3 Record results on Enclosure 5.3 (Manual Calculation Worksheet).
4.3.2 Calculate the gas and iodine dcunwind concentraticas for each poin: using the equation, Conc *
* /S
- DW #"*V V DWC where, Conc = downwind concentration (uCi/ml) 79 Coney = vent discharge concentration (uCi/ml)
Fy = vent discharge flow rate (CFM) i X/Q = disp'ersion factor in sec/m 3 U = unit c nversi ns derived frem, DWC (2.832E-2m /ft*) (0.017 nia/sec) = 4.8E-4 " *** 8 fr*
- sec Sacple 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, D *U * *
- VB G "h
- where, D
WB
= whole body gamma dose due to subme:sion in a cloud of radioactive gas (rem) = -6 W* 4 e ,, me=- M *-
I H?c 0i3/10C9/13
?:;e ; of 3 U- = uni conversion derived fr =, c J
- 3. 72; (dis / s a -uCi; ( '. ::i l . 22-2 ;)
(1.6022-o er;/MeV) (3 - rem /100 er;s)
.. 2 ,,.
dis-rse-c=2 uCi-se:-MoV 3 (,. . a. c- 1 dis-rem-cm )(2600 see) --- pCi-sec-Mev hr
*~#"" = 9.00 E2 pCi-hr-MeV NOTI: 1/2 is the constan: used (in the case of gs=ma radiati:n) when assuming tha: :he receptor is exposed to caly ene-half the ~
cloud eving to the presence of the ground, (Reference 2.4).
=
ConcD 'l ownwind concentration (WCi/ml) Time = projected duration of exposure (hrs); use 2 hours unless otherwise dire :ed. I = average gamma energy per disintegration (Mov/ dis) s~ NOTE: If 5 cannot be obtained from the sample results, the following values may be us6d: Hours from Trio 5 Ofev/ dis) 0-12 0.40 12-48 0.20 48-= 0.10 4.3.3.1 Record results on Enclosure 3.3. 4.3.4 Determine the potential child thyroid dose downwind using the iodine concentraticas calculated in 4.3.2 and the equation, D =U
- 3 7 Conc D '4
- Ti"*
where, D THY
= thyroid dose due to uptake of radioactive .
iodine (rem) . . g l w
- l l
1
-l '
HP/0/9/1009/13
._ Page 5 of 5
- U I
= c:nstants derived frc= a ch.1d's breathint :ste .. ,
(1.1722 cc/sec.), I-131 dose cenversien facter (4.39 E-3 m em/pCi), and coversien of pCi to
;Ci (10 ), crem to rem (10 ), and hrs. to sec 0
(3600 secs /hr) = 1.36Es "*' * *E - uci
- hr Concg = dOWCWind cCacentration of iodine (mci /ml)
Time = projected exposure ti=e (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 dese by two (2). 4.3.4.3 Record results of all calculations on Enclosure 5.5 (Dose Assessmant 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 worksheets and printouts used in dose calculations. 5.0 ENCLOSURIS 5.1 Sample of Vent Release Data Sheet 5.2 Sample of Table of Two Hour Relative Concentratica Factors 3.3 Sample of Manual Calculation Worksheet 3.4 Sample of Evaluation of Plume Location 5.5 Sample of Dese Assess =ent Report
- =
E 4 v* s e
. _ . , _ . . - .... ~ . . . _ - - - - - - - - . - . - - - -- - - - - - - - - -
Page 1 of 1 . ENCLCSURE 3.1
-j F3/0/3/1009/13 VENT RELEASE DATA SHEET s' .- l .
Uni: Ds:e/:ize of Rx trip / 1 ME30ROLOGICAL DATA -
- 1) Lcwer Tcwer Wind Speed M?H
- 2) Upper Tcwer Wind Direction F:cm *
- 3) Temp. Gradien: (AT) *C
- 4) Vent Flow CFM
- 3) Date/ time /
VENT SA'fPLE ANALYSIS
- 1) Total Gas uCi/mi
- 2) I-131 Equiv. uCi/ml
- 3) Gas E Mov/ dis (Gamma)
VENT MONITOR DATA
- 1) EMF-36L (lo range) CPM-
- 2) EMF-36H (hi range) CPM
- 3) AE!E-37 (iodine) CPM; at min CALCULATED DISCHARGE CONCENTRATION
- 1) G_as a (Use hi readings if EMF-36H is > 100 CPM)
Coney ,g ,= (EMF 36L CPM) = pCi/ml, or Cone'v'-hi = (EMF-36H C?M) = 2.70E7
"" CPM-ol 4.0E3 uCi uCi WC1/ml
- 2) Iodine
= faEMF-37 CPM)
Ceneg, ,7 (2.4E-10 uCi - min) = uCi/ml . At al - cpm 3 '9 W
'd y ,, ,,,w p,, 4 * * * * ~ " * ~ ' '
- e. .. * . .F
\
ENCLCSURE 5.2 e *' / , flP/0/D/ID09/93 IWO-fl0 Ult R[t.ATIVE CONCENIRATION l ACI0ftS (Cll) Icepc e n t st e s' S talal l i t y tiTstance (HTiWi----
~-
Dil'Iorence Class # (*Cl .5' . I 2 3 8e 5 6 7 8 9 !u a
- 1) < - .6 A 1. fs f -5 1.2E-6 5.90-1 #.1[-T 3 3.20-7 2.5E-7 P 00-7 1.9E-7 1.60-1 1.6E-7 1.5E-7
- 2) .6 to .5 Il-c l.St-ts 4.5E-5 1. 31 -5 6.30-6 3.90-6 2.lE-6 1. 9(.- 6 1.8E-6 8 1.lE-6 U.3t-7 7.6E-1
}
- 3) -0.fi to-0.2 0 3.nt -8 1. fs t -is 8s.9f -5 2.70-5 1.10-5 1.7E-5 9.2E-6 7.3E-6 6.0E-6 5.t1F-6 8s.3E-6
- _ _ . . . . .__.2_.._._._ __. .
{ ., -0.1 to'.4 ,[ 6. 91 - re 2.5E-4 9.6t-5 5.5t-5 3.5E-5 2.5E-5 2.00-5 1.6E-5 1.3[-5 1.lE-5 9.7E-6
- 5) 6.5 in 't.? r I.lf-3 5.l[-4 2. 0 t -'s 1.20-'s a.2E-5 6.3E-5 5.1E-5 4.3E-5 3.8f-5 3.3F-5 3.0f-5
~ . - - - - - - -- - - - - - - ~
- 6) > I.? (3 1.80-3 1.lE-3 4. 3 E-Is 2.7E-4 2.0E-4 1,.7E-4 1.30-4 1.2[-4 8.6E-5 7.8E-5 7.30-5 from other snusces or meteorological statn (Section 8s.1) teso the wind speed and time oE day to determine which row nr 081 valiens !
in esso: i I l eni . D I...I'aY _ d _Specil Flfi Bow _.E 10: 00 A.fl. - I I:00 l'.fl. N/A 3 is : no l' . f l. . - In:Un A.fl. > 15 HPil 4 ts : f ru l'. fl. - 10:00 A.fl. $ IS Hl'll 6 n e ,.
*r.',, ., , a .
I
+ #. '
f.NCLO5URE 5.3 . 111'/D/11/1009/13 . IIAllUAL cal.CDLATION WDRKSIlf.fT .
) Dist.harce Contentra tin'n (Conc )'sv: ?) Vent Discharge flow Rate: 3) Win <l Speerl:
__ ._. _ ___.pci/ml Gas..__.. f y _...__. ___ CfH HPil
' Iruline . _ _ , .pc i/ml . ! !) Iwo lionr Itclative Cone.. l'ac t ors 5) Downwinel Concentrations (f II , se .-mph /m ' X/I) = Cil/nqih ' r,et/ni ) Conr pg = Contyfy X/() - (4.Ut " ,fg) g ) gg, n) lotline H _ _. _ lli Cll ; X/fl ' _ _ _ _ _ Sec/m'3 Conc =
gg ____,____,._pcl/mi Concgg = __,,,. __ ____pci/mr *
* .. Ili Cll * ; X/f! = _,_ .._,_,__ _ 'Sec/m Cone 3 -
gg ___pCi/mi Cont gy =. _ _._., , .._ _ nC i /m !' 9 ' f1i Cll - ; X/I) = Sec/m Conc gg = pCi/ml Conc gg ,_ .,, ___pCi/m! O , ,_ , f l i Cil - ; X/f) = # 3 Sec/m -"Ci/m ConcDW " ----- Cons DW " - - -- -- - - -- "C i /
- i'
- 6) l'otentiai Whole Body Ganna Dose; 7) Potential Chile! Thyroiel Do;e; Tim" " honrs l' Tine
.. _ . . _ . . _ _ _ _ , _ Dyg = (9.00E2) ConcDW D ngy - (1.86E6) Loncy Tine I
T.
- _ _ _ _ _ _ Mev/tlis P Dyg = Il jigy =
_ _M i __ Rem Rem N MI *
. . . . _ . _ . Dyg ._ _ . _ ,
Rem 0;ggy = lien P Mi D gg a _ _ Item D giy = Icm N ........._. MI l'g g " . _. I!cm D piy " . . __ _ ____ _ _.. .. _ _ _ I t em
) - ) - )
4 I e
P.1gu 1 of : . ENCLCSURE 5.4 - HP/0/3/1009/13 .' EVAL"ATION OF PLQ!I LOCATION .- i
- 1. Acquire the following infor=acien free Enclosure 5.1 and record 0: '
Enclosure 3.5. . a) wind diractica in degrees frem north b) wind speed (=ph) c) AT (*C)
. i d) Stability Class e) thyroid and whol'a body deses
- 2. Protective action guides submitted to the Statien Health Physicist are to be made based en the calculated dose on Enclosure 5.1 and the follcwing information.
a) For doses:
> 5 Rem Whole Bcdy or, > 25 Rea Thyroid Recommend Evacuation of Population in Affected Area.
B) For doses: -- 1-5 Ree Whole Body or, 5-25 Rea Thyroid Recommend evacuation of children and pregnant women, and sheltering 4 of remainder of personnel in the affected area. i C) For doses:
< 1 Rea Whole Body or, 4 < 5 Res Thyroid -
Reccomend no action.
- 3. Determine the affected zones, based on wind directicn and wind speed, with the following tables.
Table 3.1 0-2 Mile Affected Zones Wind Direction . Affected Zone , 0* - 360' AO '
P2;s 2 of 2 ENCLCSLTtE 5.4 , HP/0/3/1009/13
- EVALUATION OF PLL?.E LOCATION .
Table 3.2 2-3 Mile Affected *cnes
'4ind Speed < 5 =ph ind Speed > 3 :ph ind . Dirse:icn Affected 'enes ind , Direction Affseted 2cnes O' - 360* A1,31,C1,D1,E1,71 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' Ei, F1 159.1* - 207* Ei, F1, Al 207.1* - 247' F1, A1, 31 247.1' - 265* A1, B1 265.1* - 298* A1, 31, C1 298.1* - 338' B1, C1 333.1* - 360' 31, C1, D1 Table 3.3 5-10 Mile Affected Zones e-Wind Direction Affected Zones # - 27* ~
0.I' . 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, 32 229.1* - 249' F3. A2, 82 249.1' - 259' A2, A3, B2 259.1* - 290* A2, A3, 32, C2 290.1' - 304' A3, 32, C2 304.1* - 333' B2, C2 333.1* - 360* B2, C2, D2 4 Record sectors requiring protective action on San:ple Enclosure 5.5 alens with the recommended protective action. g-ed e
..r ww ee* *ew* * ** N S
ENCLCSURE 3.5
, DOSE ASSESSMENT REPORT ,
RP/0/S/1009/13 , Duke Po'.'er Company Crisis Management Plan Off-Site Dese Report - Catawba * ' > \d Prepared By Date/ Time / E=argency Drill (Circle One) , Meteorology
- Wind Speed MPH
! Wind Directica Degrees from North vertical Temp. Diff. Degrees C/100ft. Stability Class (circle one) A3CDEFE i i Source Term Time Noble Gas 1-31 ea. Centainment Rad. Monitor R/hr. R/hr Centainment Sample uCi/c1' pC1/mi Unit Vent (Sample c: EMF) uC1/c1 uCi/mi Curie Release Race Ci/see Ci/sec Corresponds to: LOCA LCCA through filter Core Damage Ce,re Damage through filter Tube ruptura Gas Decay Tank New Fusi Old fuel Other Dose Projections +
' .5 mi 2 mi 5 mi 10 mi 2 hr Dose (ree) based Whole Body
- Child thyroid h @on Containment al/hr release -
2 hr Dose (ree) based Whale Body on Unit Vent release Child thyroid
$ efs
] 2 hr Dose (rea) based Whole Body - on Steam release Child thyroid 9 2 hr Dose (res) based Whole Body 4 on release Child thyroid Field Monitoring Data 4 Location Distance Direction Deze Rate (arsm/hr) Centamination (mi) Whole Body Child Thyroid (dpm/100 cm2) l Affected Zones 0-2 mi 2-5 mi 3-10 mi 9-10 mi " (Circle Zones) A0 Al 31 C1 D1 El F1 12 82 C2 D2 E2 72 A3 F3 + 4 ,9 k .,,, Comments: . 6 t t . XC: Data Analysis Coordinator, Station Health Physicist
. . . . . . . . . . ~ . . . . . - .
. - - - , - u a.. a - . ~ w .-u.+ s .,_aa _x - . _ - - --_ s-a I
i s ,
, :erm :4701 DC41)
(Fccarly SPD 1CO21) Ot*7E PC'4ER C0'!?%.! (D IO !!c: F2/0/3/1009/15 PRCC::'07.E ?REFAM710:' Chan p's) O to
?ROCES3 REC 0R3 0 :-corporated (2) STATION: Catawba (3) PRCCEOURE TITLE: Distribution of ?ocassium Iodide Tablets in the Event of a Radioicdine Relasse (4) ?RE?ARED 3Y: #,u._ h $d Mde"""r7 CATE: N I7 ' 81 (3) REVIE'4ED SY h. g OATO: J f ~/- T Cross-Disciplinary Review Sy: N/R: [ M Y 8 j (6) TEMPORARY APPROVAL (IF NECESSARY):
Sy: (SRO) Date: By: _ Date: (7) APPROVED BY: V Date: C/5M (S) MISCELIANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date:
~ ~ . _ % +sw , _ .- 9 g I .~
l
* * * '
- 2 -_^^__
em m s. _ _ _ _ _ - i
HP/0/S/1009/16 CCKE PC'4E2 CCMPANY CATXJ3A NUCLEAR STATICS DISTRI3LTICS OF POTASSIUM ICDIDE TA3LETS IN THE EVENT OF A RADI0ICDINE RELEASE - 1.0 PURPOSE , This procedure provides information necessary to distribute Active Potassium Iodide (KI) tablets to in plant personnel in the event of a release of radiciodine. Also, it outlines storage and supply information to assure sufficient quality and quantity of thyroid blocking material.
2.0 REFERENCES
2.1 TP/0/3/1001/09, Operatien/ Calibration Procedure for the Body Eurden Analyzer , 0.2 HP/0/3/1009/10, Sody Burden Analysis Following Suspected Uptakes of Mixed Fission or Activation Products 2.3 Systes Health Physics Manual 2.4 NCRP Report No. 55; Protection of the Thyroid Gland in the Event of Releases of Radiciodine 1977 2.5 NCRP Report No. 651; Manaaement of Persons Accidentally Contaminated With Radiciodine 1980 2.6 NUREG 0654 2.7 May 16, 1983 letter from L. Lewis to C. T. Yongue.
Subject:
Oconee Nuclear Station HP Procedure KP/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 as 24 hours after an emergency will provide some protection. .
=
3.5 Discolored or disfigured tablets, tablets that have reached the *' expiration date listed on the bottle, and bottles of KI with loose '4 cops shall be discarded. "' i O r - , - + -
X?/0/3/1009/16 , Page 2 of 4 - I 3.6 Hands of anycne scuching the 'KI tablets cust be free of radioactive centaminatica prior to taking :he KI tablets. 4.0 PRCCIDL*RE 4.1 Responsibilities For Distribu: ion . 4.1.1 The 3:s:1cn Health Physicist, in conjunc:icn wi:h available sedical advice, shall control the distri-bution of KI tablets. 4.1.2 Persons suspected of having been in the affected area prior to the detection and during the release, persons present in the affected area and persons who will enter the area while a significant amount of radf oiodine is present will be instrue:ed ,tnr the Health Physica Supervision to i=nediately register in the KI distributien center (for exa=ple, the Technical Support Center). 4.1.2.1 A significant amount of radiof odine for short . duration in plant exposure is that amount taken Lato the body that would resu'.t in a dose of 10 rem or more. For example, exposure to approximately 700 weighted MPC-hours, or 6.1 x 10 uC1/al Airborne I-131 for one hour, would result in a dose of 10 rom.
. 4.1.2.2 A significant amount of radioiodine 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. 4.2.1 When persons notified by Health Physics arrive at the distribution area, record appropriate data per Enclosure 5.1. 4.2.2 Vith the approval of the Station Health Physicist, the Health Physics representative shall give one (1) tablet to each person and instructions concerning the use of the tablet. Then issue to each person one bottle containing nine (9) KI tablets, and the package insert for the use of the tablets (refer to Enclosure 3.2 for an example of the General Manufacturers Guidelines). 4.2.2.1 Tablets are to be taken only as directed. One (1) tablet per day for the length of the emergency. 4.2.2.2 After the initial dose of KI, subsequent doses
- will be taken on a daily basis. Tablets should ,, 9 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, s SW t
- . . - __ . . _ ~ . . --- . ._ - . ~.
KP/0/S/lC09/16 - Page 3 of 4 4.2.3 Tablets removed frem full bc::le of KI should be a:ored in - 10 al plastic vis13. The expiratica data en the be:tle frem which the :a'lets o were :sken ind the name ci :he Health Physics represen:stive shall.be recorded on :he 10ml vials. Tablets s:ored in 10 al' plastic vials sh uld - then be used for single table: ini:ial issuance of KI :o affected persons. a.0.4 As directed by the Field Meni:cring Coordinator (FMC) or the S&C Coordinator, :aam members shall ingest one (1) - tablet of Potassium Iodide. + 4.2.4 1 The FMC and/or S&C Coordinator will provide the informatica for Enclosure 5.1 and will ensurs that distribution of KI per Step 4.2.2 is acccmplished by team members. 4.3 Thyroid Burden Analysis Following Radiciodine Exposure 4.3.1 All persons receiving KI tablets should receive a thyroid scan. If the number of people render this step impractical, the 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 KP/0/B/1009/10. 4.3.2 Records of thyroid scan shall os maintained per procedure.
. NOTE: Distribute KI before analyzing thyroid concentration. Thyroid scans immediately after an accident could lengthen K1 di -
tribution time and cause confusion among personnel. P 4.4 Storage Requirements 4.4.1 There are three major storage requirements to be observed: l 4.4.1.1 Store in a temperature range of 39' to 86*F. 4.4.1.2 Store in a low humidity area (avoid direct exposure to liquids). 4.4.1.3 Store in an area protected from exposure to light. 4.4.2 Upon receiving a shipment of KI tablets, boxes shall be .
=
opened as soon as possible and bottles examined to ensure y that an air-tight seal has been maintained. Bottles sust *, be returned to boxes, and boxes must be sealed shut, so as '4
, to avoid exposers to light. "' '
y y - - - - ---- - - -
_ - - . ~ _ . _ _ _ . . _ . _ .__ _ __ _ _ . . HP/ 0/3/100'3/16 Page 4 of 4 a f _ a.a.3 "~o ensure a sufficient supply of table:s, a mini =um of - 1,000 bo::les with la table:s per bo::le should be maintained en site. 4.3 Shelf Life and Changeout of KI Tablats - 4.3.1 Syro-31cek D table: bottles are labeled with an expiration date frem tne factory As tablet's reach the expiration dates, the tablets must be discarded. NOTT: Replacement tablets should be ordered at least three (3) months prior to the date of expiration listed on the bottles of KI. 4.5.2 Up'en receiving a shipment of KI tablets, supplies should be shifted so as to use older tablets before new tablets.
- 5.0 INCLOSURIS 5.1 Sample of Potassium Iodide Tablet Distribution Data Sheet
, 5.2 Manufacturers Guidelines for Thyro-Block TM Tablets and Solution 1 1 1 i
- O 4
6 7 e ne
fil'/0/h/1009/le ,
-~
F.n:losu e 5.1 .
,,3 . a- ,. ,. t. . .,, .. r . .g .e. .. ~. A 3 ... r , n...r ~. . .,. ., ,. ; :. , , .,. c...,.5....-... a. . *N,,T ~,
. N *
.1o .
3'. .ws DATC e T"1E OF DATE & TU:S OF NC'!EE Nt!E CEPART*!D.T sf..s..pi.c.h..'.r) n. .'08UM E INITTA!, ISSUANCE.
- en 9
1 1 M l r i 4 i t t
- 9 w
.e1 .+ .9 l
s
~ ,
f j .9 I v -,. ,- .-c- --m-.-. , - - , , + - - - - - . - ,y..r, ,,,c- . _,,-- .. w. ,.--w,.--- .,.r- --
- c. . - ~ . --,.,g . , .- - - .
J.9
; 1 4 i i *
- 3 l . ** J
- '.c . e t .t i W '
& r.u...,> w .:. u.....r ,-... __ l.._ .;
T H Y R C 3 !. C C K ' i n .:: w ;cm.,a .
! ;m ac w w:a ........a..
l :.i.:..u ner.v: i. . 7A2L2t1 va C:h u eis.1 u u e' l TAKC POTASSIUt! 10010E slNI.Y Wi!r.N i*t'lli.it:
!!EAl.T11 0FFICIALS TELL YCtl. IN A it.sDI AT t)N . C'.t EllG ENCY. ItAtlt0ACTIVI: .e t!,la g u,til.D u t.: .
I !!ELEASCO IN'*O T!!R A It I*tti'4.: Sl('.'.! !UUit,F (A 6 FO't'.t OF 10 DINT:1 t.*AN tit.!> (*!;url:.:r YrW l
. l IF YOU A '.E TOLD TU TAK! Tilts sth!!it'..*.H. r '.t'.E 1*: e ONE T!StK P.VEstY 24 llot,:.s. nts Nor 'i Aiu; IT M'1!O; .
l OFT!.N. StoltE WILI. .Nir!' !!Mt.i' Yt:0 i '. Il %IAY IN . CliEASE Titit Ills;( OF St.W. I.FFECTS.180 ini' nim; I
!?!!S f)lluu !? Yul.1 NhobV Yt.stj ati:t; .sl..Ristilt.' li) f IODIDA. ISU2 SIDE EFFKCTS IIELO'.'il i N # IN::!CAflONS T!!Yl!CID llLOCKING IN A ItApl ATioN M*.li.!tiiE.'.CY ON!.Y.
OIAFCTIONC FOR U1J 1.*** o.dr m!6retted 's) *itate ut lors: pu'+c e egl'a ci.e ! .e.e the event c,f a ruduaLaon einergency. i s. 005:: T45!. t t Alit!!lt'*; ANil t'll!!.t pt:EN . *. l' \ ;l a11* AGM Uit t!I.! shit t .. :., e a.s. t ..aw., .a day L' rush l.- 31..itlil.. li. i. IJAlllE: L.NtJEle ' '. i Al; flF Af er'; i Onehalf .t,21 e el.l. 6 ..iim de.y L': w,1. lif; 4. Soluunn: ADUllfS ANil t';tll.lji!!?! ! Yl'Ait OF AliE OIL Ot.l>EIL Adil 's drop = ti, une-half gla*s uIlittel al ot.uk verli des . l !!AlllE.S UNUi.!! t i t.Aat t,P AGK. Add 3 drops to a email:.mnunt of Lt;uid onut a day. Few sif d.Here fornic Take far 10 day, unt .v. it.e. . . .! ..a.a r we e try State or local publk he.itth mutt:uro.es. Store et contruded roum temperature la ti. i i < .w! 4 t' f.J to sti F1. Ceep cons.un.*r Oghtly clos >. .aad 14 .- cf ::une ug' t. Do nut use the su!utica if it oppvass teri,.vi.e .l. . t; . e . .;....: uit httle. WARNitad Petes sinns icilide should not b ust bs p <r;n.'. . I.'. r,s.c to t...l .l. Keep out of the resch of chddre i. l.a ..i.a I ..* r ra..~ ..t ed..ros reaction. contest a phyassian i,r the Amt,1ic he66a m ua.ritv , CEScalPTION *, q Hach Tl1Y!!O.!11.0CKW TAllit.T r.. .: o;, . .. . . . ..i
'4 petsseiumIvWde. %
2ach denp of Tl!YItc.UI.GC;(iH. tit.t.Li!*, c.... n.i.,::: sing ut " i potapanuta iodade. S 6
* - . . a em m.ee
'M :!.n.t t p 5. 2 -
Ni,u 2 d 2 -
.O. . ,
g 47.# V , H0W .'C T.' d3PJM iO.N;11 W .m u t..,.asf:rini94.#,,.,..q, m ,p.,i
. aig.,a.o ...,,,,,,;n , ; . .., ,
WwP.* 6 A the iwd.no th y n rq t,vn, t. ! . i. . i.4....a ,.!6 v. f u .t. The th, rvi j un 3 ,,,a' ,, f.va. ...i. . m t..n .. i 4.. va c al.nv. - In a rad.attua vmerpa q.:.g . 6... gd.a.: ....,;. r e ,o. ,..a i, the sir. This ::ater,ag n.y ,, .,,,,. , ,, .., ........,su g ;,..y tater tav thyroad ;;:as;d g a.aa y .5 i. :.... ,:s'...u:d p... La'J ty : ot show .twJ for ys.r2 ii!.J r. o ari . rit i.ad, ' u ...s e tityread .!as.tage
!! yens ta'4e putaa nuni wd.de, it m!! fi!! w,s .s u... it.f ri,a. 4.ud 1 TL4 rtdacus the gtias ,e 6;.46 :..im. gut in.a. n u.: innt: .e 'n:!.
vittr t!.e thyroid C!ar.J. WHO SHOULO itCT TAM PufAWUu 100tc l'ho valy pv9pe shw sh..a:d not ti . i..i' . .ew.n ...a de uro ;,r..p!v wr.9 ILauw they .re 4.Lr,;4 t, .sda s i .a. ... a e c w p.,r . . . inn
.ud.de wven .f yea arg g2..rn :.w.i.rt.w s :
- s ' . ve +...! P r .L 1. u ifur
. tus9;Me. a thyru.d hwra 4tr ..: vm..:, i .* * *. .a l'a e a .a a i:.I nutatng won.ca ar.d L46 a , s.ad . :. . ;s sa um.. . . .. .. r t!.e w. 4. .
HOW ANO wilEN TO TAMF PUI A alt.M 10tst0C .
!'otewuan: olide i,hus:4 s.,, t..aei .. . .. ,a . . :- wis .p .
taubhe !.ealth offic;a:s ts J suu 's ..u .. tan'.s t .4 .* .. ..u-e . t . e r ; l hm., s. .\le.ra w di sa.t ! :.. s. :: u.s ta e i n. t :. :. t .... "he.l.1" .a.-
!) brited amounta n; :,d.ac (. i.. i a .. .t..n.i.. r .iw .rik i.i tule rifats. You w..I g.o.l 1 'y . .. t .. .. t e .. t ..: c t a. .'r ..* t.,e nwrv tt a tu it.w ;,4M !.Fe Li.1:i e0 ! so.i!!v. ent. i t!.. 6 ..f ; . a . se.as. i.at.. . I w; t.ske les;her d.ro fot . .ve,; e r . s'un .! ...i : . . s. f..! n.n t t ko a.m* it.ma i he. ici varn. wi..e v . .
- f. wl.. u p. ..;.le
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tlur thws L t.rse you a C; Le tenary t!..; .e .t. no n
'I L'uesille sede rifatiinsh..,. sin s n i. .rlto er . ' aI.c .ala atv g! ands, and ".odiam f4nuta:L. t:iets. 'a:. ..-t..s e. -.: a :.a tsa t.
ture tseth end . arcs. spagtwrt, v: arai. sw:J, and es,msL.a.es stonaasti upset and snarthrun A few peut.le have en ni; orcs tresL no uti. .u.a. - reus
- p)nym ts:ms.These could be fever und ;..at ; mios, or wil.u.c ! pe.ta .,f the face and bedv ena at tui.sa no niiviin.c... ..i beratti eopur Ing immediate muda at attu.t.urt Taking iod de eney estely 5;aut ..wera.tise; . uf ti.e t'iyr:J.'
a:t. tad. enderectivity of thJ thyrh 8 Hd...rt'.idtdWnefatid the Lt.yroid gland Igoitsr). WHAT TO 00 IF $102 CFFFC15 CCCUR
, 18 the side v!!scts are smrit wr di i.a ! .or .u. 4.e a re ertun. . top tahang potassigns :pd.de. Dwn :t pvv.ibw. s,id elat .e ..r pubisc hest'.h aaithurity fut is.strace. ..
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i n' Form 34731 (10 d1) (Formerly SPD.100211 DUKE PCliER COMPA!."( (1) ID No:HP/0/3/1009/15
?RCCEDURE PRE? ARA!!0:1 Chan;;e (s) O to PROCESS RECORD 0 Incorporated (2) STATION: CA::3HIA (3) PROCE::URE TITLE: CITSI"E DCEE PR17:I: TIC:S - (2N REI. EASE OF GASEL'US FADIC; CITE hm'4 orIER n921 nst:ca: Se e IT tr r i
(4) PREPARED 3Y: . _ , [- DATE: L /
// / ff' (5) REVIEWED SY: 2h _ IM DATE: J Cross-Disciplinary Raview By: , N/R ) 7 M I
) (6) TIMPORARY APPROVAI, (IF NECESSARY): By: (SRO) Dater By: m Dater j (7) APPROVED BY M Date 3!f[ (8) MISCELLANEOUS: Reviewed / Approved By: Date: - ,' Reviewed / Approved By: Dato h O
.* 9 # L e
.. . -_ -. - - -- ... .- _ _ . - - -= .
a I M?,0/3;*.ov3/13 .
, OCKZ PCVII 00M.*ANY % CATAW2A SCOLIA?. STATICN 0FF3ITE DOSE PROJECTICNS UNCCNTROLLED REI.ZASE OF GASICUS RADICACTI'l2 FA IRIAL .
OTHER ILIN CGCCOH T:C UNIT V2NT 1.0 PURPOSE To describe an approved =ethod for projecting dose cozmitment frem 4 . noble gas or iodine rolesse, other than a unit vent release, during I an emergency.
0.0 REFERENCES
2.1 Reg Guide 1.109 2.2 Reg Guide 1.4 2.3 HP/0/3/1009/06 Alternativi. Method for Determining Dose Rate Within the Reactor Building 2.4 Variables used in Z?/0/3/1009/15 Letter Filo Nc=ber CN.: 134.10 2 3.0 LIMITS AND PRECALTTIONS
~
k 3.1 It is assumed ,that the iodine whole body dose from a release is very small compared to the iodine thyroid dose. Thus, lodine whole body dose is not considored here. 3.2 This procedure applies to releases made frem Catawba Nuclear Station only. Many of the values contained in this proceduro are site specific. 3.3 This procedure considers all releases to be ground level releases. 4.0 PROCEDURE 4.1 Acquire the following information and record on sample Enclosure 5.1. NOTE: Should site meteorological data be unavailable, obtain wind speed and wind direction frem the National Weather Service (Unit 2d States Government - Natienal Oceanic & Atmospheric Administratten). NOTE: If appropriate, obtain advance meteorological data to calculate doses due to changing meteorological conditions, i 4.1.1 Reactor Unit, date and time of reactor trip. 4.1.2 Lower tower wind speed (sph). _, .q
..e 4.1.3 Tower wind direction in degrees from North (North = 0'), t.
4.1.4 Temperature gradient (AT*C). ,
U E?/0/3/1CC?/13 P.1ge : of 4 *
. 1.3 Radiatica ":nitor (IMT 53A or 333; reading (Rihr) or '
ca.':u.'a:ad per Rafirenca 2.3 D 4.1.6 Oate'and ti=e of calculations; . 4.2 De:semine -he Cen: sin =ont Building Isakags rati (LR) and record it en sample Inclosure 3.1. 4.2.1 LR (ml/hr) is the totsi leak rate for the contair. ment which is one of the folicwing:
- 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 leskage rato (L.7DL3) which is detarsined by:
l
- LR DL3 =
ntainmon ume
- Des 2gn Leak Constant 0.0025 day
= 2.83 x 10 ml * ,
day 24 hr
- e
=
2.95 x 10 al/hr
- kV 4.3 Determine the X/Q values for each point of interest downwind and record on Enclosure 5.1.
If no points have been requested, use the .5, 2, 3 and 10 mile values. 4.3.1 Locate the relative two-hour downwind concentratien value (CH) for each point from Enclosure 5.2 and record onto saeple Enclosure 5.1. 4.3.2 Convert these values to X/Q by, X/Q = CH (MFN-Sec/e*) Tower Wind Speed (itPh) 4.4 Determine the potential whole body dose from submersion in a cloud of noble gas and record on Enclosure 5.1. 4.4.1 Calculate the whole body two (2) hour dese ccomitment. Dyg = Dgg
- M
- X/Q
- U3g Where, Dgg = Whole body two (2) hour dose ccomitment
.- ~1 kj Dgg=Monitordoserate
- O
-O
l l
.3?/0/3/1009/15 P23e 3 of 4 10C = Average Cecay :nstant for nchle gases = ,
i
,,f 2.;o::E.: tCi * :ti/*h:8 m1*d*3 L3 = Containment leakaga 1ts in 21, he X/Q = dispersion factor in sec/m 2 '
(3.7Ea/seca tC1) (1.6E-aerasH!aV) X ADC = Ugg = 2 (100 ergs /g-rad) (1.2E-3g/cm 8
) (1E6cm a j,)
5.7E-9 hr8 -ma - rad al-R-sec 1 a.3 Determine the potential thyroid dose frem uptake of radiciodine and record on Enclosure 3.1. 4.5.1 Locate the time plus one (1) heur after tri) on Enclosure 5.3 and record the corresponding Decay Constant on Enclosure 5.1. ; 4.5.2 Calculate a child's thyroid two (2) hour dose commitment using time plus one (1) hour, ' DRT = DR3 DC
- LR
- X/Q
- U g g-- ,
' -s wh.r.,
DRT = thyroid two (2) hoar dose commitment l DR3 = monitor dose rate [ 9C1
- sven*hr8 4
DC = Decay Constant in 31
- pCi
- R for time plus one (1) hour (see Enclosure 3.3)
] LR = Leak rate in al/hr I X/Q dispersion in sec/a 8 i Ug = breathing rate for child times uCi to pCi conversion i factor oCL-res 3 8 sci ree (1.17E 4e8 /sec) 113 pCi-erom = 1.17E 1 see -9Ci-eres
,, *1 kwar
- e
*9
l I HP/0/3/1009/13. Page 4 of 4 a' e.o Detarmine the potentially affected senes using Enclosure 3.a. . Record the affected :enas on Enclosure 3.3. 4.7 Complete Inclosure 3.3 and submit it to the Data Anslysis Coordinator. Include any ecmments pertinent'to the evaluation of . offsite ha:ards. 3.0 ENC'.0SG ES 3.1 Sample Projected Of fsite Dose Released From Containment 3.2 Sample Table of Two Hour Relative Concentration Factors (Cg) 5.3 Sa=ple Table of Iodine and Noble Decay Constant (DC) 3.4 Sa..ple of Evaluation of Plume Location 3.5 Sample Dose .tssessment Report 3.6 Estimation of Containment Leak Rate h . gs. .,
- 4 e
9
i t-Page 1 o f .: . I!.C:,050RE 3.1
' y'M HP/C/3/1309/13 : ?K0JIOUD OFF3lTI CCSI RE:.!A3E3 FRC : CONT.\IN!!E .-* . !
I Unit Oste / Time of '.ascter Trip , < i l ?!ET!oaat,0Gt0Ai, DATi !
- 1. Tower wind speed eph .
i-ll . Tower wind direction
- l
- 3. Temperature gradient (AT) 'C
- 5:0NITOR DATA
- 1. E!T 33A or 335/ Survey Inst. 18 R/hr
_. DR3= (0:rcle One) NOTE: If centsinaant monitor itiform.icion is not 'aseable, refer to
. Reference 2.3. ,
i
, DOSE CALCUL\ TION DATE/Tl!!E _ ;
s fW 1. I.R al/hr
- 2. si. = , X/Q = s.ec/m 8 C.I.G CM E *** " ' X/Q = sec/m 8 !
Cy 1 si. = , X/Q = sec/s 8 CN $ ei. = , X/Q = sec/a 8
- i. A. Whole Body 2 hr. dose projection from noble gases:
by DW3 = DR3 *I.R
- X/Q
- 5.7E-9, Miles 045 ka 2 hr Oose commitment e
, e .* 9
{g ".6 e n h r 8 8 6 MhM .5 an5 &mesee, 99
Page 2 of 2 ,{ (' ed/ ENCLOSURE 3.1 HP/0/3/1009/IS PRC.!EC~ED OFFSITE DCSE RE:. EASED FRO.'! OCNTAIN}! INT S. Thyroid 2 hr. desa projectica free odine: _ . s DC , by DR = DR
- DC
- LR
- X/Q * (1.17E-1) ,
7 3 Miles Out D. 2 hr Dese Commitment
-he DEFINITICNS D,j3 m' whole body 2 hour dose ccamitment from noble gases DRT = thyroid 2 hr dare commitment from iodine k# ... I.R = containment leakage rate .
X/Q = " Chi cver Q" is dcwnwind concentratica correction facter
=
C H 2 hr relative downwind concentratica - MPH (X/Q * !!PH) DC = Decay constant . DR = 3 dose rate at the containment monitor 1
- ~. .
1 1 1 l g . - 1 t -s- . , O
- M . __
.W ~ - vgs, - , a
Y .G I f act oSust . IIP /0/Bl/ lu09/ l5 IWo-esount iltl AllVL f.ONCil43RAllON FACloHS (C ) 61
~ ~ ~ " - ~
I'cepa ra tte ro~~$tabl4ety Distance (lifies) Dlfrerence Class . (*C) .5 1 2 3 4 5 6 i e 9 to
- 1) < .6 A 1.4E-5 1.2E-6 5.90-7 4.1E-7 3.2E-7 2.5[-7 2.0[-7 1.9E-7 1.80-7 8.6E-7 l.St-t
- 2) .6 to .5 8 1.5E-4 4.5E-5 1.3E-5 6.3[-6 3.9[-6 2.iE-6 1.9t-6 1. 8s t-6 1.12-6 8.36 - 1 7. 8s t - t 3 ) -0.8s to -0.2 C 3.8E-4 1.4E-4 4.8)E-5 2.7E-5 1.7E-5 1.2[-5 9.2E-6 7.3t-6 6.0E-6 5.01-6 8s . .s t -6 s
.- =_- .--.
4 ) -0.1 tu +.4 0 6. 9 L - 8s 2.5E-4 9.6E-5 5.50-5 3. 5'E- 5 2.5E-5 2.00-5 1. 6 t'-5 1.30-5 1.lf-5 9.'IL-6
- 5) *.5 to +1.2 [ 1.10-3 5.1E-4 2.0E-4 1.2L-4 8.2[-5 6.3[-5 5.lE-5 84 . 3 0 *> 3.0E-5 3.38-5 3.00-5
- 6) > 1.2 l~ 1.80-3 1.1E-3 4.3E-4 2.7E-4 2. 0E-8s 3.10-4 1.3[-4 1.28 -8s 8.6L-5 1.08-5 't . 3 L - S f rome oilsor soustus or e otasorolo91 cal data (Section is. l j use tieo wind spos?d and tisho or d.sy to dotees.sipu wl.is.le sow os c v.a s v.,,,
8 to uno:
- .t ies.stL IMr UllL4_Enned lum .E 10
- 00 A.fl. - 8s :00 P.fl. H/A 3 4:oo P.H. - 10:00 A.ll. > 15 HPil ' 8a 8:00 4 P.ll. - 10:00 A.H. < 15 HPil 6 I
\ .) *', .. .
ENCLCSURE 5.3 PAGE 1 Cl~ 1 [
~A:.t.LC ,-
OCD2Nt* .I NC31.E CE2.3Y CCNCTcNT(DC)
. 0 - 499 HRS i NP/0/S/100o/15 h
- 1Ci.S CC HCUR 6C HCUR DC HOUR OC HOUR OC 1 0.0649E-05 100 5.4125E 04 200 6.87!:7F.- M 3'O 7.4430E-04 400 7.9109E-04 2 5.7902E-05 102 5.6595E-04 202 6. 8925E-0 4 002 7. 4537E-04 402 7.<7197E--0 4 4 8.1506E-05 104 5.7050E-04 204 6.9040E-04 304 7.4636E-04 404 7.92G5E-04 6 1.0296E-04 106 5.7492E-04 206 6.'7194E-04 306 7. 470$E-04 406 7.V373E-04 0 1.2295E-04 108 5.7920E-04 203 6.9326E-04 308 7.4833E-04 408 7.9460E-04 10 1.4170E-04 110 5.8335E-04 210 6.9457E-04 310 7.4932E-04 110 7.9540E-04 12 1.5903E-04 112 5.3737E-04 212 6.9GC6E-04 312 7.5029E-04 412 7.9625E-04 14 1.7591E-04 114 5.9127E-04 214 6.9714E-04 314 7.5127E-04 414 7.9722E-04 16 1.9159E-04 116 5.9504C-04 216 6.9340E -0" 3 L6 7.5224E-04 416 7.99092-04 19 2.064GE-04 118 5.9870E-04 210 6.9'?6CE-04 313 7.5321E-04 41C 7.9396E-04 20 2.2071E-04 120 6.0025E-04 220 7.0009E-04 320 7.5410E-01 420 7.9982E-04 22 2.3439E-04 122 6.0569E-04 222 7. 0212C- 04 322 7.551GE-04 422 3. 0 060E-04 24 2.4757E-04 124 4.0900E-04 224 7.0300E-94 324 7.5611E-04 424 8.0155E-04 26 2.6034E-04 126 6.1226E-04 22e 7.0454E-04 326 7.G707E-04 426 U. G240E--04 20 2.7272E-04 123 6.1540E-04 228 7.0L74C 44 329 7.5303E-04 429 8.0326E-04 30 2.3475E-04 130 6.1844E-04 230 7.06?2E-04 320 7.5899E-0 4 ^30 0. 0412E-04 32 2.9645E-04 132 6.2140E-04 232 7.0010E-04 332 7.5994E-04 432 8.0497E-04 34 3.0784E-04 134 6.24262-04 234 7.0926E-04 334 7.600'?E 04 434 8.05D3E-04 36 3.1893E-04 136 6.2705E-04 236 7.1042E-04 336 7.6184E-04 436 8.0668E-04
-' 38 3.2975E-04 138 6.2975E-04 238 7.1157E- 04 333 7.6279E-04 430 0.0753E-04 k 40 3.4029E-04 140 6.323CE-04 240 7.1272E-04 310 7.6373E-04 440 8.0337E-04 .1s/ 42 3.5058E-04 142 6.3493E-04 242 7.1385E-04 342 7.6467E-04 492 8.0922E-04 44 3.6062E-0 4 144 4.3741E-04 244 7.149EE-04 344 7.6561E-04 444 8.10 06C-04 46 3.7042E-04 146 6.39r13E-04 246 7.1610E-04 P46 7.6653E-04 446 8.1090E-04 49 3 7999E-04 148 6.4218E-04 248 7.1721E--0 4 340 7.4740E-01 440 3.1174E-04 50 3.8933E-04 150 6.4447E-04 250 7.1002C-04 350 7.4G42E-04 450 8.1250E-04 52 3.9046E-04 152 6.4670E-04 252 7.1942E-04 1S2 7.6935E-04 452 8.1342E-04 54 4.0738E-04 154 6.4837E-04 254 7.2051E-04 354 7.79292-04 454 8.1925E-04 So 4.1609E-04 156 6.5099E-04 256 7.2160E-94 356 7.7120E-04 456 8.1509E-04 53 4.2460E-04 158.6.5306E-04 238 7.2268E-04 353 7.7213E-04 450 8.1592E-04 60 4 3291E-04 160 6.5508E-04 260 7.2376E-04 360 7.7005E-04 460 8.1675E-04 62 4.4100E-04 162 6.5705E-04 262 7.2403E-04 362 7.7397E-04 462 8.1757E-04 64 4.1896E-04 164 6.5097E-04 264 7.2590E-04 364 7.7409E- 04 464 S.1840E-04 66 4.5669E-04 166 6.6085E-04 266 7.2696E-04 365 7.75G1E-04 464 8.1923E-04 68 4.6425E-04 168 6.6269E-04 263 7.2902E-04 368 7.7672C-04 460 8.2005E-04 70 4.7161E-04 170 6.6450E-04 270 v.2907E-04 370 7.7743E-04 470 8.2037E-04 72 4.7879E-04 172 6.o606E-0' 272 7.2012E-04 172 7.7954E-04 472 8.216?C-04 74 4.8579E-04 L74 6.6799E-04 274 7.3116E-04 374 7.7? l5E-04 474 8.2250E-04 76 4 9262E-04 176 6.6969E-04 276 7.3220E-04 376 7.8036E-04 476 8.2302E-04 78 4.9926E-04 178 6.7135E-04 278 7.3323E-04 379 7.3126E-04 478 0.24 t3E-04 80 5 0573E-04 180 6.7296E-04 200 7.3427E-04 300 7.821/E-04 480 8.2495E-04 02 5.1202E-04 182 6.7450E-04 292 7.3529E-04 332 7.3307E-04 4G2 8.2576E-04 84 5.1815E-04 184 6.7615E-04 234 7.3632E-04 284 7.C397E-04 484 8.2657E-04
- U6 5.2410E-04 106 6 7770E-04 236 7.3?34E-04 386 7.3406E-04 486 8.2737E-=04 BS 5.0909E-04 ISO 6.7922E-04 2GB 7.2335E-04 300 7.S576E-04 480 S.2318E:-04 -t ,
l {y
.g 90 5.3551E-04 190 6.G072E-04 290 7.393M-04 3YO 7.G665E-04 490 8.239EE t04 92 5. 4097E-04 192 6.8019E-0 4 292 7.40375-0 9 392 7.37545-04 492 8.2978E 1!A. .
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Page 1 of 3 CUKE PC'4ER CC:! PAS'i ( CATAWBA NUCLEAR STATICN 1-m/ ENCLOSURE 5.4 HF/0/3/1009/15 . E'.'ALUATICN OF PLC::E LCCATIC:: 5.4.1. Acquire the following information frc: sa. ple Enclosure 3.1 and record on sample Enclosure 5.5. 5.4.1.1 Wind direction in degrees frem North 5.4.1.2 Wind speed (nph) 3.4.1.3 ST (*C) 5.4.1.4 Stsbility class 5.4.1.5 Thyroid and whole bcdy dose 5.4.2. Determine the affected zones, based on wind direction and wind speed, with the following tables: Table 3.1 0-2 Mile Affected Zono.s i Vind Direction Affected Zones
't/
0* - 360* A0 Table 3.2 2-5 Mile Affected Zenos Vind Speed < 5 =ph Wind Speed > 5 mph Vind Direction Affected Zones k*ind Direction Affected Zones 0* - 360* A1,31,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' DI, El, F1 120.1* - 159' Ei, F1 159.1* - 207* El, F1, Al 207.1* - 207* F1, A1, 21 - 247.1* - 265* A1, 31 265.1* - 298* A1, 31, C1' 298.1* - 338* 31, C1 333.1* - 360* 31, C1, D1
- . .+ ~1 I ,.- .
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Pa;e 2 of 3 ._ D32 PC',.7.R C2.'!?A),Y i CATA'43A NUC22.;R .iTATI2N D ENC2* SURE 5.4 HP/0/3/10C9/15 ' EVALUATION OF ?2L71E LCCATICS Table 3.3 3-10 !!ile Af fected 2cnes Wind Direction Affected 2cnes ' O.1* - 27* 02. D2 27.1* - 69* C2, D2, E2
. 69.1* - 95* D2, E2, F2 95.1* - 132' D2, 22, 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, 32 229.1* - 249' F3, A2, 32 249.1* - 259' A2, A3, 32 259.1* - 290* A2, A;, 32, C2 290.1* - 304* A3, 32, C2 304.1* - 333' B2, C2 333.1* - 260* B2, C2, D2 s' 9 \et 5.4.3 Determine the protective action guides (PAC), based on che esicu-laced dose (s) on Sample Enclosure 5.1 and the following infornation:
5.4.3.1 For doses:
< 1 Ram 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' sheltering of remainder of persennel in the affected area.
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- EUKI PC'4ER COMPANY g CATA*.!3A' SUC:.IAR STATION
'd ESCLOSURE 3..
HP/0/3/1009/15 . EVALUATICN OF PC.'.ME LOCATION v t 5.4.3.3- For doses:
> 5 Roa Whole '3ody or, > 25 Ree Thyroid o
Recommend Evacuation of Populacion in Affected Area.
- 2.4.4. Record only the affected
- enes requiring proedtive' actien en samplo Enclosure 3.5 along with the recommaaded protective action.
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l _ . i DUKE POWER COMPANY Page 1 of 1 , CATAWBA NUCLEAR STATION . HP/0/B/1009/15 . ENCLOSURE 3.5 - DCSE ASSESSMENT REPORT
- k. Duke Crisis Ccapany Management Plan Off-Site Dose Report CATAWBA W ..... Power..................... ...........................................................
Prepared By-Date/ Time / .Ecergency Drill (circle one) - Meteorology Wind Speed MPH Wind Direction degrees from North Vertical Temp. Diff, degrees C/100 ft. Stability Class (circle one) A B C D E F G 4 Source Ters Time Noble Gas I-131 equivalent Contain=ent Rad. Monitor R/hr R/hr Ccatainment Sample VCi/mi uCi/mi Unit Vent (Sample of EMF) uC1/ml uC1/ml 4 Curie Release Rata Ci/sec C1/sec Corresponds to: LOCA LOCA through filter Coro damage Core damage thrcugh filter I Tube rupture Gas Decay Tank New fuel Old fuel Other Dose Projections 3 .5 mi 2 mi 5 mi 10 si j 2hr Dose (res) based Whole Body l' ,on Containment release Child thyroid . .
@ al/hr 2hr Dose (res) based Whole Body on Unit Vent release Child thyroid Q cfs 2hr Dose (res) based Whole Body '
on Steam release Child thyroid a the Dose (res) based Whole Body en release Child thyroid j Field Monitoring Data Location Distance Direction Dose Rate (area /hr) Contamination (mi) Whole body Child thyroid (dpe/100 cm ) ? Affected Zones 0-2 mi 2-5 si 5-10 mi 9-10 mi
-(circle zones) A0 A181 C1 D1 El F1 A2 32 C2 D2 E2 F2 A3 F3 . = ...................................................................................... l CCM.T.NTS: *, 9 \.. , ---- %
, xc: Data Analysis Coordinator, Station Health Physicist l ! l l
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Form 34731 (10-81) (Formerty SPD.10021) DUKE PC'4R COMPA17 (1) ID No: HP/0/3/1009/13 PRCCEDURE PREPARi!!ON Change (s) O to PROCESS RECORD / Incorporated (2) STATION: Catawba (3) PROCEDURE TITLE: OFFSITE DOSE PROJECTION-UNCONTROLLED RELEASE OF RADIOACTIVE MATERIAL THROUCH THE UNIT VENT (4) PREPARED BY: [h N*_ M 'JATE: 3-/ 7 (5) REVIEWED BY: /IJ N M A DATE: . / * / I*" M
<- p Cross-Disciplinary Review By: N/R:M "A.
(6) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: By: Dates (7) AFFROVED BT: lA/
- Date: /7 Y (8) MISCELIANEOUS:
Reviewed / Approved By: Date: Reviewed / Approved By: Dates j
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Ct~C PCWER COM?ASY j , CATA'.3A NCCLEAR STATICN ! 4 07FSITE COSE PROJECTICN - CSCONTROLLED ,REI1ASE . CF RADICACTIVE MATEMAL E!RCCGH THE UNIT-VENT - i i 1.0 PCR?CSE This procedure describes the method for projecting the potential offsite j dose following an uncontrolled release of radioactive materials through the unit vent.
2.0 REFERENCES
i 2.1 Letter from Civil /Enviren= ental Divisien CN-1108.1, 1434.00, 1227.C0 Atsespheric Dispersion Factor for Emergency Planning 2.2 EPA-320/1-75-001. Manual of Protective Action Guides and Protective Actions for Nuclear Incidents ! 2.3 Regulatory Guide 1.109, Calculation of Annual Coses to Man From Routine Releases of Reactor Effluents for the Purpcsc of Evaluating ; j Compliance with 10CTR50, Appendix I l 2.4 Regulatory Guide 1.4, Assumptions Used for Evaluating the Potential Radiological Consequences of 4 Imss of Coolant Accider.t for
- Pressurized Water Reactors l 3.0 LIMITS AND PRECAUTIONS 1
I 3.1 Use actual sample data when possible. Radiation sonitor 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 analysed to verify these '!! calculations. This procedure considers all releases to be ground t level releases.
!' i 3.3 This procedure applies to releases made from Catawba Nuclear Station 1-j only. Many of the values contained in this procedure are site specific.
1 4 4.0 PROCEDURE j l' 4.1 Obtain the following information from the Control Room and record it' ] on Enclosure 3.1 (Vent Release Data Sheet).
- j; ,4.1.1 Time of resctor trip. ,
e 4.1.2 Tower wind speed in MPH. "' (Lower tower wind speed preferred.) %
- i
( .-
, . . . . . --.s..- . . . . . - . .; n. , . . . , . - . . . . . .
1
= _ . - . _. -_ -.
d?/0/3/1009/'3 Pa;e 2 of 3 4.1.3 2irection from which :he wind is bleving in de;;ees f cm . North. (Upper :cwer wind dirac:ian praf arred.) - 4'.1.4 Te=perature gradien: (AT) in degrees C. 4 .1. 5 .en disch?. ge fIcv ria a in "?". - 1 4.1.6 Available weaths: forecast inic:ma icn. 4.2 Determine the release concentration as fo11ews: l 4.2.1 If vent sample analysis is not available, go to Step 4.2.4 4.2.2 Obtain the fo11cwing vent sample analysis results and record on Enclosure 5.1.
; . 4.2.2.1 Date/ time of sample.
4.2.2.2 Gross ncbie gas concentra: ion in uCi/ml. 4.2.2.3 Iodine equivalent concent:4 tion (or data for calculation). 4.2.2.4 Gamma E-bar value in mev/ dis (or data for . calculation). 4.7 J Go to Step 4.3 4.2.4 Obtain the following unit vent data and record on ~ ~~ sample Enclosure 5.1: l , 4.2.4.1 Date/ Time of collection. 4.2.4.2 EMF 36 Low and High range readings in epm (gas I monitor). 4.2.4.3 AEMF37 reading in cpm (icdine monitor). 4.2.4.4 At in sinutes 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, 5 and 10 mils values. .
. . "1 l ..
i e J
,, op,g . AuGW'U.44 *d*M^ #
l KP/0/3/1009/13 . Pags 3 of 5 4.3.1.1 From Enclosure 5.2 (Table of Two-Hour Relative .- Concentratic: Tsctors), locata the relative two
- hour concentration value (CH) for each point and record on sa ple Enclosure 5.3 (Manual Calculatien Workshee:), (Reference 2.3).
- 4. 3 .1. 2 Convert these values to X/Q by, CH(MPM-Sec/m81
**/Q = Wind Speed (MPH) l 4.3.1.3 Record results on Enclosure 3.3 (Manual Calculation Worksheet).
4.3.2 Calculate the gas and iodine downwind concentrations for each point using the equation, ConcDW * "*V V IS
- DWC i
where, Conegg = downwind concentration (WCi/ml) Coney = vant discharge concentration (uci/ml) Fy = vent discharge flow rate (CEt) X/Q = dispersion factor in sec/m 8 - -- -- U DWC = unit conversions derived from, 8 * * " L" (2.832E-2a /ft*) (0.017 min /sec) = 4.8E-4 fr8
- sec Sample Enclosure 5.3 provides work space for this calculation.
4.3.3 Determine the potential whole body gamma dose dcwnwind using the gas concentrations calculated in 4.3.2 and the equation. Dgg =U g
- E
- Conc
- Time DW where, Dgg = whole body gamma dose due to submersion in a cloud of radioactive gas (rem)
.+ "1 +
e- ,
, , , , , . w w me e --whese.g.es--h*.m** - -4.*#'e* ** **'
EP;0/3/1009/13 . s Ps;c a of 3 Ug = unit conversion derived frem, - e 3.7EL (dis /sec-uC1)(tec/1.22-3g) (1.6022-6 erg /MeV) (g - re,m/100 ergs) dis-rem-em' 1/2 = 2.5E-1 uCi-see-MeV (2.5E-1 dis-rem-cm (2600 see) uCi-sec-Mev hr .
= 9.00 E2 uCi-hr-Mov NOTE: 1/2 is the constant used (in the case of gamma radiation) when assu=ing that the receptor is exposed to caly one-half the cloud owing to the presence of the ground, (Reference 2.4).
Coneyg = downwind concentration (WCi/ml) Time = projected duration of exposure (hrs); use - 1 . 2 hours unless otherwise directed. I = average gemma energy per disintegration (Mov/ dis)
~
NOTE: If I cannot be obtained from -he sample results, i the following values may be used: Hours from Trio 5 (Mev/ dis) 0-12 0.40 12-48 0.20 48-= 0.10 4.3.3.1 Record results on Enclosure 3.3. 4.3.4 Determine the potential child thyroid dose downwind using the iodine concentrations calculated La 4.3.2 and the equation, Dg = Ug
- Coneyj
- Tine i
.I where, D
THY
= thyroid dose due to uptake of radioactive -
iodine (ree) , e e4 r* i 1 e i s ( e ae. +ee. e *
- i e esee. p . e me. w ee. mag g ** s sempem m ee k
H2/0/ S/1009/13
, . Page 3 of 5 !! = constants derived from 4 child's breathint rate .-
7 (1.17E2 cc/sec.). :-131 dose c nversic: !s:ter (4.39 E-3 cre=/pci), and coversion of pCi to uCi (10 ), mrem to re (10 ~8), and hrs. to see (3600 secs /hr) = 1.86E6 "* uci
- hr -
ConcD = dcwnwind concentration of iodine (uCi/ml) Time = projected exposure time (hrs); use 2 hours l unless otherwise directed. 4.3.4.1 Record results en s uple Enclosure 5.3. 4.3.4.2 Project the adult thyroid desa 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 -
s 4.4.1 Record sectors on Enclosure 3.5. 4.5 Complete sample Enclosurs 5.5 and sub* sit it to the Station Health _ . _.
. Physicist. Include any comments and~information pertinent to the ~ , evaluation af offsite hazards.
4.6 Maintain a file of all worksheets and printouts used in dose a calculations.
! 5.0 ENCLCSt,1ty,3 i'
5.1 Sample of Vent Release Data Sheet i 2; 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 Iocation 5.5 Sample of Dese Assessment Report b
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INCLCSURE 5.1 HP/0/3/1009/13 ~ VENT RELIASE DATA SHIIT
- Uni: Data /:i=e et Rx trip /
ME"'EOROLOGICAL DATA '
- 1) kwer Tcwer Wind Speed MPH
- 2) Cpper Tower Wind Dirse: ion Fres *
-3) Temp. Gradient (AT) 'C
- 4) Vent Flow C7M e
1
- 5) Date/ time /
VENT SAMPLE ANALYSIS
- 1) Total Gas uCi/mi
- 2) I-131 Equiv. uCi/a1
- 3) GasY. Mev/ dis (Gamsa)
VENT ?f0NITOR DATA
- 1) LT-36L (lo range) CPM
, 2) LT -36H (hi range) CPM
- 3) ALT-37 (iodine) CPM; At min CALCULATED DISCHARGE CCNCI.!' V RATION t
i; 1) G3 (Use hi readings if LT-36N !.s > 100 CPM) 1 Cone y ,g, = (LY 36L CPM) = uCi/al, or ConcV-hi = (EMF-36M CPM) = 4.0E3 CM-s1 E 2.70E7 i uCi uC1 uCilal t i 2) h ' Cone y ,g a (ALT-37 CPM) (2.4E-10 uCi - ein)'= uCi/ml . ) At ml - cpm .* 9 a ,
.* i i
e
. .m., . . . . * -* . . = _ -**- .g . . .-. . . . -4... .
' ~ 'fo '.. , , f , */
- ESICLOSUllE 5.2 '
IIP /0/II/1009/ I3 SWO-ItotNt REEATIVE CONCENtRAT t006 I ACT0fts (Cit)
'-~
temperatesse stabliiti oTatsence (Miles) Oltrerence class (*Cl .i a 2 3 4 5 6 i e ii 10
- 1) < .6 A i . u -5 f.2E-6 5.9E-r 4.1E-r 3.2E-7 2.5E-7 2.nE-7 f.9E-T 3.80-F t.6E-F t.5E-7
- 2) .6 to .5 5-C t.5E-4 4.5[-5 1.3E-5 6.3E-6 3.9E-6 2.F'E-6 f.9E-6 1.4E-6 f.tE-6 8.3E-7 7.80-F - ,
l
- 3) -n.4 to-tv.2 'O 3.81-4 1.4[-4 4.9t-5 2.7E-5 1.7E-5 1.2E-5 9.**E-6 7.3E-6 6.0E-6 5.et-6 4.3E-6 l
%, -n.1 to*.4 E 6.9E-4 2.5E-4 9.6E-5 5.5E-5 3.5E-5 2.5E-5 2.0E-5 1.6E-5 1.3E-5 f.t[-5 ? 7f-6 }
- 5) +.5 t o
- t .2 r I.tr-3 5.1E-4 2.ut-4 1.2E-4 s.2E-5 6.3E-5 5.t[-5 4.3E-5 3.st-5 3.3r-5 3.of-5 63 > t.2 C 1.80-3 1.1[-3 4.3E-4 2.FE-4 2.0E-4 f.FE-4 f.3E-4 1.20-4 s.6E-5 7.et-5 T.3E-5 .
from atiser sneesces or acteoretogical es.ta (Sectices 4.1) esse tfie wised; speed ased time er doy to deteralese wisicts row of Ctt votesets to esse: i ilee otilway Mlsed,$pece( f Egy_f IG:left A.M. - 4:00 P.M. N/A 3 4: stet P.it - to:tMs A.M. > 15 HPM 4 4:tN9 P.M. - tit: teel A.M. - S IS MPtt
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~ IIP /0/R/lon9/13 .
HANUAL cal.CillAT1086 WimK5itCET .
') Dist.fiaire Com entratin'n (Conc,)': 7) Vent Discharile Flow Rate: 3) Wind Speed: ,
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- 6) Potential mole Body Gasumi Dese; 7) Potential Child Thyroielfinse; i I I" ~
. _ _ _ _ _ _ _ _ _ _ _ _ hours D yg_ = (9.00E2) - ConcDW - C - Time D,,,y * (1.8606) - ConcDW - Time 1' -
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- l ENCLOSCRI 3.4 ,
- HP/0/3/1009/13 .
j EVALUATION OT PLC:!E LCCAT!CN , i
- 1. Acquire the following informatica free Inclosuro 5.1 and record on Enclesure 5.5.
- a) wind direction in degrees from north ,
t b) wind speed (mph) c) AT ('C) ' l d) Stability Class e) thyroid and whole body doses
- 2. Protective action zuides subsitted to the Stati n Health Physicist are to be made based en the calculated dose en Inclosure 5.1 l and the following information.
a) For doses:
> 5 Ree Whole Body or, l > 23 Ree Thyroid Recossend Evacuation of Populat, ion in Affected Area. ,
B) For desose.- - 1 3 Ree Whole Body or, l 5 23 Ree Thyroid Reconsend evacuation of children and pregnant wesen, and sheltering of remainder of personnel in the affected area. c) For doses:
< 1 Ree Whole Body or, < 5 Ree Thyroid '
Recomoead no action. l 3. Determine the affected zones, based on wind direction and wind speed, with the following tables. Table 3.1 0 2 Mile Affected Zones Wind Direction ' Affected Zona
- l
.* "1 0*
- 340' A0 .
va p 0
l l
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3?/0/B/1009/13
- EVALCATICN CF Pt.CtE *,CCATICN .-
i I, j Table 3.2 2-5 Mile affected 'enes Wind Speed < $ er;h 'lind Speed > 3 :;t. -
'*ind . Direction Affected Zenas ',*ind Direction A!!serad *enes 1
0* - 360' A1,31,C1,D1.E1,71 0.1* - 22' C1, D1 22.1* - 73* C1, DI, El , 73.1* - 108' C1,D1,E1,F1 i 108.1* - 120' D1, El, F1 120.1* - 159' E1, Fi 139.1' - 207' E1, F1, A1 207.1* - 247' F1, A1, 31 , 247.1* - 265* A1, 31 i 263.1* - 293* A1, 31, C1 298.1' - 338' 31, C1 338.1* - 360' 51, C1, D1 i i Table 3.3 5-10 Mile Affacted Zones Wind Direction affected Zones
# 0.1* - 27' C2, D2 .
27.1* - 69' C2, 32, 12 69.1* - 93
- D2, E2, F2 95.1* - 132' D2, E2, F2, F3 l
132.1* - 144' E2, F1, F3 144.1* - 160* E2, F2, F3, A2 160.1* - 201* F2, F3. A2 I 201.1* - 229' F2, F3, A2, 22 229.1* - 249' F3 A2, 82 249.1' - 239' A2, A3, 82 239.1* - 290' A2, A3, 32 C2 290.1* - 304' A3, 32, C2 r 304.1* - 333' 32, C2 333.1* - 360' 82, C2, D2 1
- 4. Record sectors requiring protective action on Samp1s Enclosure 3.5 alens with the recommended protective action.
t e G 6 4.- .. l 9
. . .- . . . . . . . . . . ~ . - . --
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- s
,, INCtCSURE 3.3 -
{,
~ , CCSE ASSESSMI.NT REPORT l EP/0/3/1009/13 .' ;
tuke 'cuer Ccmpany Crisis Mansge=ent Plan Off-Site Dosa Report - Cataubs - i Prepared 3y Date/ Time / , Emergency Drill (Circle One) - I Meteorology j i Vind Speed MP3 Wind Direction Degrees from North Vertical Temp. 311!. Degrees C/100ft. Stability Class (Circle One) A3CDEFE Source Tara Time Noble Gas 1-31 es. 1 Containment Rad. Monitor R/hr. R/hr j Containment Sample uC1/mi' uCi/mi i Unit Vent (Sample or EMF) uCL/mi uCi/31 i Curie Release Race Ci/sec Ci/sec l Corresponds to: LCC1 LCCA through filter Core tsmage Core Damage threugh filter Tube rupture Gas Oscay Tank v New Fuel Old fuel other 4 Dose Projections
* .5 si 2 mi 3 mi 10 si 2 hr Dose (ree) based Whole W y* ,,
on Containment release Child thyroid _ ,
@ al/hr >
- 2 hr Dose (ree) based Whole Body _
on Unit Vent release l Child thyroid _ __ i
$ ch 2 hr Dose (rea) based Whole Body ;,
on Steam release Child thyroid f 2 hr Dose (ree) based Whole Body _. _ 2 on release Child thyroid 9 Field Monitoring Data Location Distance Direction Dose Rate (erse/hr) Centamination j (si) Whole Body Child Thyroid (d;m/100 cm2) 1 1 1 Affected Zones 0 2 mi 2 5 mi, 3-10 mi 9-10 mi .
', (Circle Zones) A0 Al 31 C1 D1 El F1 A2 82 C2 D2 12 F2 A3 F3 *1 h ,,e Comments: * " 6 i XC: Data Analysis Coordinator, 8tation Health Physicist * , . - , , -- , ,m._.,._ m _.__.__,,,__-,%,_-,,----,...--.y # . . ..r-,-,,. ,. % , . _ . - - . - - ._m ,-,m_ ,--.- ,%_,
Form 347*.1 (10 41) (Formerly SP0100211 DUKE pct,*ER CCMPANY (1) ID NotHP/0/0/1009/12 PRCCIDURE PREPARATICN Ciange(s) 0 to PROCESS RECORD 0 Incorporated (2) STATION: Catawba (3) PROCEDURE TITLE: Quantifying Gaseous Release Through Steam-Relief Valves Under Post-Accident Conditions (4) PREPARED SY
- 1 W M_'-- % DATE /FIs" At (5) RIVIE'4ED BY _
/)r A DATE 4./# 93 Cross-Disciplinary Review By: N/Rt ( F '-- A (6) TEMPORARY AFFROVAL (IF NECESSARY)t .
By (SRO) Dates By: Datet (7) AFFROVED BY W. Deta / -) (8) MISCELLANEQUS i
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HP/0/3/1009/12 DL'AE PC'a?.R COMPANY CATAVBA NUCLEAR STATION CUASTITYING GASCOUS RELEASE THRCCO'I ST A:t-RELIE7 VALVES UNDER POST ACCICEh? C0Z ITICNS 1.0 Pt tPost To describe a method for calculating total noble gas and radiciodine activities released through steam relief valves under post accident conditions. 2.0 RETERENCES 2.1 Catawba Nuclear Station TSAR Vol. !!, Table 11.1.1 2 2.2 Catawba Nuclear Station Computer System Documentation, Rev. 9/1/83, Sec. 3.2.19.0, Main Steam Release Monitoring 2.3 Letter free Design Engineering Providing Correlation Curves (to be added later): 2.3.1 Figure 1 - Main Steam Line Radiation Honitor Correlation curve. Correlation Factor, S' vs. Time after Reactor Shutdown. 2.3.2 Tigure 2 Maia steam Line Radiation Monitor Correlation Curve Magnified First Hour Response s' vs. Time. 2.3.3 Fisure 3 N 16 Effect on the Main 9 team Line Radiation Monitor. 2.4 ASME Steam Tables 3.0 LIMITS AND PRECAtJTIONS 3.1 The value used for specific gravity (.4 ft'/lb.) in Step 4.2.1 is an averase based on Tsat of 360*F and Psat of 1100 psia (Ref. 2.4). 3.2 The Main Steam Release Accumulator Program (MSR) calculates pounds saas (1be) losses from each steam generator loop. The followins table indicates relationship between stesa line monitors and steam generator (5/0) loop losses as calculated by MSR, (Ref. 2.2): M/M S/0 (LOOP) 26 10 S/0 A = (PORY (A) + Dump (A) + Safe (A)) 27 11 S/0 8 = (PORY (5) + Dump (3) + Safe (8) + A N PT (3)) 28 12 S/0 C = (PORY (C) + Dump (C) + Safe (C) + AFVPT (C)) 29 13 S/0 D = (PORY (D) + Dump (D) + Safe (D)) . *
** 1 3.2.1 The S/0 Loop calculations above result in overestimations of losses occurring through loope 8 and C (accounts for all **
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_ _ . _ _ _ _ _ _ . _ _ _ - - - - __ _ _ _ . _ - - _ _ _ ~ _ - . __ _ - _ - - . - _ _ _ l
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HP/0/3/1009/12 1 Page 2 of 4 ". l AW PT losses), and underestimates losses occurring through l 1 cops A and D (no AT4PT loss accountini;). ! 3.2.2 MSR Progras does not account for val.ve position modulation and overestimates steam loss approximations. Calculations
- are based on the assumption that valves are fully cpen When read to be in any condition other than ',' Closed '.
t ! 4.0 PRCCEDURE 4.1 Cbtain and record the information listed below on Maia Steam i l Gaseous Activity Release Record, (enclosure 3.1) following a steam release event..when directed:
?
4.1.1 Unit number. i 4.1.2 Date of the steam release. ; t l 4.1.3 Time the steam release started. l 4.1.4 Time the steam release ended. 4.1.5 su w line EHF readinge (R/hr). 4.1. 3.1 Use the highest steamaline ENF reading that meet slesely serresponds with steam release event time asserval. < 4.1.4 Date and time the IMF reedisse were recorded. 4.1.7 5' value for each steam *11ae EMF, (Ref. 2.3). 4.1.7.1 Use Figure 3, Nale effect es the Maia steam Line Radiation Monitor, of Easleeure 5.2, if steam release event essues within 90 seconds of , roaster trip. 4.1.7.1.1 Subtrast N te dose rate free monitor readias and apply results to Figure 2. 4.1.7.2 Use Figure 2, Mais steam Line Radiatten Monitor Carrelation Curve Magnified first hour reopense 8' vs. time, if steam release event oscurs within 40 minutes of roaster trip. 4.1.7.2.1 Lesate " hours after Ra trip" on X= amis and move up graph to sorroepending 8' value en Y= anis. 4.1.7.3 Use Figure it Maia steam Line Radiation Monitor .
- l Cerrelation Curve, if steam release event *, S essues greater than one hour after roaster trip. **
l l
ii.5/0/3iM 9 1 Page 3 of . e.'. 7.3.1 'aute "heurs af ter "(x t.sp" :n
; ma a..d =cv.* 1p gra:a ta sertspen.iing $' value on Y a: tis.
4.1.3 Total quantity of steam released in pounds :: ass t '.bm> f ecm each ste am generator icop. e.1.7 Reactor trip date and ti.me. 4.2 Calculate total gas activity released from each S/0 loop as follows: 4.2.1 A ggg,) = 3' x E.'tF (R/hr) x .D 68 +2 mimed 1he3 /0(n) x (1b)(uct)
'at.o re : A g (3) = total noble gas activity release fres 3/0 Laop A 3. C, .c D in Cartes 3' = uct/ec Xe e pivalent correlation factor R/hr from curve (Sample Enclosure 5.2)
E!!T = l lain Steaa = Line !!onitor reading in R/hr 1bsS /0(n)X = total quant'ity of steam released in ? pounds saas (1be) for S/G Loop A, 8 C, or D. Includes main steam atmosp eric dump and AW TF losses associated with 3/G loop. 1.13268 E 2101),f,ig,), = (.4 f t /1b x 28317 cc/f t' x 116 C1/ sci) 8 (1b)(uC1) constant converting pounds mass to it's cubic feet to ces and uC1 to Curiest such that unit analysis for expression balances to Curies. 4.2.2 Record noble gas activity released per 8/0 on Enclosure S.!. 4.3 Sus noble gaa activities released form contributing S/Ga as follows:
3'I IA NO *AN0(A)*'h0(3) *AN0(C)
- AN0(D)
! 4.3.2 Record sua total of noble gas activities released on l Enclosure 3.1. 4.4 Calculate the radiolodine activity released from each 8/0 loop as follows: 4.4.1 A! (n)
- AN0(n) x 0.03 Where A! (n) = total lodine act Wity released from 8/0 .
Loop A, 8, C, or D. ,, 9
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4P/0/3/1009/12 . Page 4 of ' . i[ J ' 0.03 = the fraction of the total noble gas plus icdine activity it. -he riac:or coolan: system
, tha: is equal to the raciciodine activity, (Ref. 2.1). -
4.4.2 Record the radiciodine activity release per 3/G's on - Enclosurs 3.1. . 4.5 Sum radiciodine activities released from contributing S/Gs as follows: ', 4.5.1 IA =A +A +A ' A I ICA) I(3) I(C) I(D) 4.5.2 Record sum total of radioicdine activities released on Enclosure 5.1. 4.6 Sign the appropriate line marked " Prepared 3y" en Enclosure 3.1. a.7 Record the date and time the calculations were performed on appropriate line of Sample Enclosure 5.1. 4.3 Route results (Enclosure 5.1) to Data Analysis Coordinator. 5.0 ENCLSOURES 5.1 Sample of Main Steam Gasequs Activity Release Record . 5.2 Figure 1: Xe-equivalent Conc /R/hr Correlation Curve (Ref 2.3) Page 1 cf 3 To Be Added Later Figare 2: Figure 1 plus N-16 Contributions (Ref 2.3), Page 2 of 3 to be added later Figure 3: N-16 Dose Rate to Monitor Cnly (Ref. 2.3) page 3 of 3. ., \ - to be added latter. t' 8 9 m4
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Dtikl' l'OWilt COMPANY CAI AWflA flUt,t [ All ST Ail 0N Pnege I o f' I $ (/'. llP/0/!!/1009/12 Tf4CLOStlPE 3.1 i flAIN SilAtt GASf0HS ACilVi1Y RilIA5f. ftfCollp fin te/ I lenn .___/ fieric t o r I t'i p flate/ lime ,,_..,/._...___. Prepared By . _ _ . . _ _ _ _ . 4 I' nit Sleam Itulcase Steam t.ino Time S' Hain Stcom HC(n) fire) flo . limo Intervn) kini toes A f* t o r sucj/gc ite t en se flotilo uns Activi ty lodine Activity sta W Stop 'ti/(h r; itis tE7' frip ~ ft/ rer ' itse Holeased Per S/G no tensed Per S/G pate time time time (Isrs ) Cteries Curles
.voI l A I . . . . . . . . - _ . __ _ _ _ _ _ ._ . ___
S/G._t 15 ) . . _ _ . _ . _. _ __ ____ . _ _ _ _ . .._ _ .. _ -_ _ - - _ . ._ _ _ S/ti (C1 . - . _ _ __ . . . _ _ . _ _ _ . _ _ _ _ __ S/ G .t.01_. .. ___._ ._ . _ . . _ . - _ . . . _ _ . . . . - A " A cr f4G 1 Da to/ T lino , / lteac t o r I n 6 p pa te/ I lme . _ , , , , , ./_,._,_ I'repa red fly _._ ,, Unil Steam Release Steam Iine Ilme S' liain Steam HGln) f(n) tio . . time Intesval !1onitors A f~ tes r incl /cc Itclease flotile ca s Act iv i t y lodine Activity Start Stop it/hr Da t c/ . Irlp it/ tie- f lem ftolented Per S/G lleleased Per S/G lhe t e time time time ( firs ) Caerles Cetries
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1 l l s' 1 Form 34731 (10-31) (Fermerly SPD-10021) DUKE PO'ER CCMPANY (1) ID No: lip /0/B/1009/09~ PROCE",URE PREPARATION Change (s) e _to PROCESS RECORD f Incorporated (2) STATION: Catawba (3) PROCEDURE TITLE: GUIDELINES FOR ACCIDENT AND DfERGENCY RESPONSE (4) PREPARED BY: ). t_ S DATE: 8- 8-[ (5) REVIEWED 3Y d [/ M M M b c- ' % TE: 8-/f"
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V Cross-Disciplinary Review By: N/R: h w m (6) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO) Data: By: Data: (7) APPROVED BY: w- Dato: 0!# (8) MISCELLANEOUS: Reviewed / Approved By: Data: Reviewed / Approved By: Date: O h
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N?/U2f'.009/09 DUKE PCW2R COMPANY l CATAWBA NUC* EAR STAT:CN l GUIDELINES FCR ACCIDENT l' AND EMERGINCY RESPONSI l t 1.: FU3 POSE 1.1 To provide guidance for notificatien/ activation of the Health Physics Organinetion in the event of an emergency situatien. 1.2 To assure proper assignment of responsibility. 1.3 To give general guidance for initial response of the Health physics organi:stien. 1.4 To give general guidance for continuing response of the Health Physics organization. 2.0 REFERE' CES 2.1 HP/0/3/1009/04, Environmental Monitoring for Emergency Conditions Within the Ten Mile Radius of Catawba Nuclear Statien 2.2 HP/0/B/1009/05, Personnel Monitoring for Emergency Conditiens. 2.3 HP/0/B/1009/06, Alternative Method for Determining Dose Rate Within the Reactor Building. 2.4 HP/0/3/1009/07 In-plant Particulate and Iodine Monitering Under Accident Conditions. 2.5 HP/0/3/1009/08, Contaminatica Control During Transportatica of Contaminated Injured Individuals. ' 2.6 HP/0/3/1009/10, Body Burden Analysis Follcwing Suspected Uptakes of Mixed Fissien or Activation Products. 2.7 HP/0/1009/12, Quantifying Gaseous Releases Througn Steam Relief Valves Under Post-Accident Ccnditions. 2.8 HP/0/B/1009/13, Off-Site Dose Projection - Uncontrolled Release of Radicactive Material Thr= ugh the Unic Vent. 2.9 HP/0/B/1009/14, Off-Site Dose Projection - Uncentrolled Release of Liquid Radioactive Material. 2.10 HP/0/B/1009/15, Off-Site Dose Projection - Uncontrolled Release of Gaseous Radioactive Material Other,Than Through the Unit Vent. .
.* ~1 .e
l HP/0/3/1009/09 f. Page 2 of 3 j,- 2.11 HP/0/3/1009/16, Distribu:ica of Pc:sssiu= Icdida Tablets in the l.' Event of a Radioscdine Releaso. 2.12 HP/0/3/1009/17, Nuclear Post Acciden: Contain=ent Air System {, Opera:ica. 2.13 HP/0/3/1009/19, Emergency Radio System Cperations, M.aintenance, and Cc==unica icas. 2.14 Catawba Nuclear Station Emergency Plan. , 2.15 System Health Physics Manual 2.16 Catawba Nuclear Station, Station Directive 3.8.4, Onsite Emergency Organi=ation 3.0 LIMITS AND PRECACTIONS 3.1 This procedure shall caly be initiated at the direction of Health Physics Supervisien. 3.2 This procedure may be initiated in part or whole, depending on the type and severity of emergency. 3.3 This procedure provides general guidance for initial response. Any particular situation may require actions not addressed in this procedure. . 3.4 For incidents occurring during backshifts, Health Physics shift personnel shall bw responsible for en-sita response caly until directed otherwise by the Statien Health Physicist. 4.0 PROCEDURE 4.1 Upon notificatien of an emergency condition, the Station Health Physicist shall activate the Health Physics organization by notifying one or all of the following: 4.1.1 Surveillance and Control Coordinater. 4.1.2 Support Functions Coordinator. 4.1.3 Staff Coordinator. 4.1.4 Shift Technician (To adviso, if during back shift). 4.2 Individual coordinators will notify alternates and supervisors to be under their direction during the emergency, and will make arrangements through the supervisors for the notification of non-exempt personnel. . . 4.3 If the emergency is classified above the Notification of Unusual
- N Event category, the Station Health Physicist shall proceed to the g Technical Support Center (TSC), and coordinate the overall Health --
g Physics respense. Enclosures S.2 and S.3 provide general guidelines for response. ~
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HP/0/3/1009/0) Page 3 of 3 ,. 4.4 When notified to respond to an e=orgency. the Survatilanca ina Centrol' Ccordinator shall assu=e al:ernata responsibility for cha Station Health Physicist, and shall activate the S&C Coordinator identified in Reference 2.15 who will act acco'rding o Enclosuras . 5.4 and 5.5. 4.5 When no:ified to respond :o an emergency, the Suppor: Funct:ans Coordinator shall assume alternate responsibility for the Sta:ica Health Physicist and shall activate the Support Functions Coordinator identified in Reference 2.16 who will act according to Enclosures 5.6 and 5.7. 4.6 When notified to respond to an emergency, the Staff Coordinator shall act according to Euclosures 5.8 and 5.9. ' 4.7 When notified to respond to an emergency, the Field "onitoring Coordinator shall act according to Enclosures 5.10 and 5.11. 4.8 When notified to respond to an emergency, the Operation Support Center (CSC) Supervisor shall act according to Enclosures 3.12 and 5.13. 5.0 ENCLOSURES 3.1 Guidelines For Planned Emergency Exposures i 5.2 Station Health Physicist - Initial Response 5.3 Station Health Physicist - Continuing Response 5.4 Surveillance and Contro!. Ccordinator - Initial Response 5.5 Surveillance and Contrcl Coordinator - Continuing Response 5.6 Support Functions Coordinator - Initial Response 5.7 Support Functions Coordinator - Continuing Response 5.8 Staff Data Analysis Coordinator - Initial Response 5.9 Staff Data Analysis Coordinator - Continuing Response 3.10 Field Monitoring Coordinator - Initial Response 3.11 Field Monitoring Coordinator - Continuing Response 5.12 OSC Supervisor - Initial Response 3.13 OSC Supervisor - Continuing Response 3.14 Reserve Personnel / Personnel Monitortng Leader Response
, 3 4 5.15 OSC Response Personn<1 Doze Record Forn '..
5.16 Procurement of Helicopters for aerial Environmental Surveillance . i
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l i l Page 1 cf'; HP/0/3/1009/09 *' 1 INCLCSCRE 3.1 . l'
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1.0 Obtain the verbal er wri::an appr: val of the I ergency Coordina:cr to - exceed planned =axinu= li=i:s. 2.0 If i: is necessary :o renecy a si ua: :n irmer.iatelv canardcus to life and orcoer:v, an individual (Ocke P:wer perscanel, or Cutsids Services) may receive expcsure up to: Whole Body 5 rems (25 rem)* Skin of the Whole Sedy 30 rems (125 rem)* or Thyroid Extremities 75 re=s
- Ocses up to this li=i =ay be authorized by the Recovery Manager.
3.0 If it is necessary to save lires or orevent loss of lives and/or extensive d =a2e to erecertv, an individual may volunteer to receive exposure up :o: Whole Body 25 rems (75 rem)* Skin of the Whole B=dy 150 rems or Thyroid Extremities 375 rems
- Doses up to this limit may be authorized by the Recovery Manager, Station Manager or Emergency Coordin.stor.
4.0 If nossible, the individual (s) should be selec:ed 'oy tha following conditions: 4.1 Personnel shculd be volunteers or professional rescue personnel. 4.2 Personnel sheuld be broadly familiar with the potential consequences of such exposure. 4.3 Vccen capable of reproduction should not take part in these actions. 4.4 All factors being equal, volunteers above the age of 15 should be selected. 5.0 Exposure shall be maintained ALARA. 6.0 Internal exposurs should be minimized by the use of the best available respiratory protection, and the contamina:ica should be controlled by the use of available protective clothing. 7.0 Exposures below the guidelines of Section* 3.0 may require an occupational penalty. *
,, 1 3.0 Exposures above the guidelines of Section 3.0 should be authorized by the ,
Recovery Manager, Station Manager or Emergency Coordinator and will
- require a medical decision as to whe: hor the individual may continue in ,
radiological work and should be limited to ence in a lifetime. - h ee
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1 9.0 Plannec e=e:gency deses shall be racc: cad, es:inatad if necessary, and included in the indi'tidual's expcsure hist:r'/ racerd. 10.0 Repor:s of planned e=ergency expcsures shall be reportad as per Catawba Nuclear Station Directive 2.3.1 (?.eporting Raquirecents ). i
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6 Page i of 1 ; . HP/0/3/1009/09 ~ ENC *2S2*RE 5.2 STATION HEA*Td PHY3:C:ST
- N T AL 225?CNS2 5.2.1 Assemble suppcrting materials and take to TSC. - j, 3.2.2 The Station Health Physicist shall as necessary:
5.2.2.1 Establish the exposure li=it for blanket dose extension, for Exposure Class 1 to a maximum of 1000 mRam/qtr; for Exposure Class 3 to a maxinum of 2500 cRes; for Exposure ;
. Class 2 personnel (pregnant females) they shall not be extended above their 500 mrem limit, and should be reassigned to work 1ccations in the Administration Building until radiation levels are evaluated. ~
5.2.2.2 Govern planned emergenty expcsures by Enclosura 3.1 (Guidelines For Planned Emergency Exposures). 3.2.2.3 Cocedinate the overall Health Physics response. 3.2.2.4 Rece= mend protective action en-site for assembled personnel and those with work duties. 5.2.2.5 Recommend off-site protective action to the Emergency Cocrdinator until the CMC (Crisis Management Center) is activated. 4 5'.2.2.6 Initiate, as necessary, HP/0/B/1009/16, Distribution of Potassium Iodide Tablet in the Event of a Radioactive Release. r . t 4 e4
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- i. 5.2.1 In:arfaca with the CMC when 1: is activated. *
( 5.2.2 Coordins:a Health Physics shif: ro:stion and augmentatien of - perscnnel and equip = ant. ~ s 5.3.3 Should evacuation be required; coordinate the identificatien of "Non-Essential" personnel with other TSC groups. ; 5.3.3.1 All females should be given first consideration due to limited use in a radiological exposure situation. 4 5.3.3.2 Sufficient personnel should be retained to support need for backup personnel. 5.3.4 Direct trending of available information to support Health Physics TSC respcase. 5.3.5 When CMC is in place, continue Protective Action assessment and recommendations as a confirming response. e O e
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l * HP/0/3/1009/09 , ENCLOSURE 3.4 I.- SC3'lE:*. LANCE AND CON 7.0L CCCIDINATCR N!TIAL RISP'"*? I 3.a.1 Asse=ble supporting = ate:121s and take to TSC., i 3.a.2 Establish radiological access centrols for the Sta: ion and Cen::a1 Roem. 5.4.2.1 Initiata, as necessary, HP/0/3/1009/07, In-Plant Particulate and Iodine .'!cnitoring Under Accident . Conditions. 5.a.2.2 Initiate, as necessary, HP/0/3/1009/03, Contaminatien Control During Transportation of Centaminated Injured Individuals. 3.4.2.3 Initiate discussions by need for Buddy System for radiological conditions. 5.L.3 If the emergency is classified above the Notification of Unusual Event category: 5.4.3.1 Send the folleving personnel as necessary to the Operations Support Center (CSC): 5.4.3.1.1 One Supervisor to coordinato Health Physics suppo'rt and communicate with the TSC and shall act according to Enclosures 5.12 and 5.13. 3.4.3.1.2 One Technician to provide job coverago (sampling, operation maintenance, etc.). 5.4.3.1.3 Two Technicians to monitor and report plant radiological status. 5.4.3.1.4 Two Technicians to previde fire / medical emergency / rescue tesm/ damage control coversgs. 5.4.3.1.5 Direct sufficient personnel to the Adninis :a-tica Building, CRC office, as staging area. 5.4.3.2 Identify a Supervisor er Lead Technician to Reserve Personnel / Personnel :!cnitoring Laader and he/she shall ac: according to Enclosure 3.14 5.4.3.3 Proceed to the TSC and coordinate Surveillanca and Control response, with emphasis upon OSC activities. 5.4.3.4 Request TSC Security staff to provide locations of officers remaining on pos:. Evaluate exposure potential
- for these officers and re' commend protective actices as
- necessary. g 9
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I . Page 1 of 1 HP/0/3/1003/09 i* ENCLOSURE 5.5 .-
,i*'MT.IL* LNCE AND CCST2CL CCCRDINATOR CCNTIN'J!SG RISPC.NSE 5.5.1 The S&C Coordinater shall, 2s necessary: ,
5.5.1.1 Initiate thrcugh RP/?M Leader HP/0/3/1009/05, Persennel . j Mcnitoring for Emergency Ccaditicas, when a site assembly ' cccurs due to rac ological conditions. 5.5.1.2 Initiate, as necessary, HP/0/3/1009/17, Nuclear Post . Accident Containment Air Systems Operation. ' 5.5.0 Provide direction and support to the OSC Health Physics Supervisor: 5.5.2.1 Coordinate in plant and on-site monitoring in support of TSC needs. 5.5.2.2 Keep CSC Supervisor appraised of TSC events and activities that may require CSC response (planned maintenance, operation,~ sampling). 3.5.2.3 Coordinate with OSC and TSC groups to ensure adequate pre-planning occurs te limit radiation exposures. , 5.5.2.4 Obtain additional emergency kit items and supplies to support OSC if needed. 5.5.3 Monitet dose rate in TSC. Initiate discussion with Station Health Physicist on the need to evaluata the TSC should dose rate exceed 5 mR/hr and be expected to continue. t .
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Page 1 of 1 _ f *, . H?.10/3/1009/09 ESC'CS G I 5.5 ! .- 33VE!I.'.l
. :CE AND CCS 20', CCCROISATCR :
CCSTIS*.*ING 2ES?C55E f i 5.5.1 The S&C Coordinator shall, as ne:essary ! 5.3.1.1 Initiate through RP/FM I,eader HP/0/3/'009/05, Persennel Monitorin; for E.argency Cenditions, when a site assecbly occurs due to rad: clog::a1 conditions. 5.5.1.2 Initiate, as necessary, HP/0/3/1009/17, Nuclear Post . Accident Containment Air Syster.s Cperation. 5.5.0 Provide direction and support to the OSC Health Physics Supervisor: 5.5.2.1 Coordinata in plant and on-site monitoring in support of TSC needs. 5.5.2.2 Keep CSC Supervisor appraised of TSC events and activities that may require CSC response (planned maintenance, operation, sampling) . 5.5.2.3 Coordinate with CSC and TSC groups to ensure adequate pre-planning occurs to limit radiation exposures. , 5.5.2.4 Obtain additional emergency kit items and supplies to support GSC if needed. 5.5.3 Monitor dose rate in TSC. Initiate discussion with Statiion Health Physicist on the need to evaluate the TSC should dose rate exceed 5 mR/hr and be expected to continue.
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t-. HP'0/3/1009/09 - ENCLOSURE 5.6 : SUPPCRT T*JNOTICNS CC020'NATCR , INITIAL RESPONSE !
. I i' ! 5.6.1 Assemble supporting :starials and ta'ce to TSC. ;
, 5.6.2 Ivaluate the need to establish an altarnata loca:ica for sa=ple , analysis. 5.6.3 Establish a count room sample priority list if emergency radiological , sampling is in progress or is goin;, to begin. , 5.6.4 Initiate, as necessary, HP/9/3/1007'13, 3cdf Burden Analysis Following Suspected Uptake of '!ixed Tissio: or Activation Products. 5.6.5 If the emergency is classified above :he Natification of t.'nusual Event category: 5.6.5.1 Establish alternate dosime:ry issue points for personnel and high range dosimetry, as necessary. 5.6.5.2 Issue blanket dose extensions for OSC personnel, to the limit sstablished by the Station Health Physicist. . 5.6.5.3 Provide representatives from Dosimetry and Escords Control in the OSC to:
, 5.6.5.3.1 Record the following information on the OSC Response Personnel Dose Record Form (Sample Enclosure 5.14) as'esorgency response personnel enter the OSC.
5.6.5.3.1.1 Name 5.6.5.3.1.2 Health Physics Badge Numbers 5.6.5.3.1.3 Social Security Number i 5.6.5.3.1.4 Birthdate 5.6.5.3.1.5 Age 5.6.5.3.1.6 Exposure Class 5.6.5.3.1.7 Vorh Group 5.6.5.3.1.8 Quarterly and yearly dose to date 5 . 6. 5 . 3 .1. 9 Permissible lifetime dose 5.6.5.3.1.10 ' Total lifetime dose to date *
.., ~1 NOTE: This may be obtained at the first .
available opportunity. - , i
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. I 5.6.5.3.0 As persensel return -to OSC ires entering a '
radiation field, desize:ars shall be checked f:: re:aroing and the felicwin; information recorded , . , en ths OSC Respense Persennel tess Record Form (Sa=ple Inclosure 3.14): 5.6.5.3.2.1 Da:e, Time . I [-- 4 5.6.5.3.2.2 Dosimeter Reading . d 5.6.5.3.2.3 Retotal of quarterly dose. 3.6.5.4 ?:cceed to the TSC and cocrdinate Support Function ,J Respense. J
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e . RP/0/3/1009/09 ls , INCLOSURE 5.7 ,'. SUPPORT FUNCTIONS CCORDINATOR , CONTINUING RESPONSE , 5.7.1 Ensure collection and :etentien of collected sa=ples is adequate to . reconstruct data folicwing the e=e:gency.
! l l 3.7.0 Acquire additienal anti-centamination clothing, dtsimetry, respiratory or monitoring . equipment from:
Existing Station Stock CF.C. Admin and Logistics Groups 5.7.3 Direct implementation of HP/0/B/1001/12 Technical Specification
, Gasecus Waste Sampling and Analysis as necessary to collect '
centain=ent and unit vent s1=ples. All sampling will lui coordinatad with OSC Health Physics personnel to determine habitability and RWP requirements. 5.7.4 Retrieve radiation instrumentatien frca Instrument Issue area and , stage in URC of fice, f t e t i 5 9
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HP/0/B/1009/09 ENCLCSURE 5.3 STAFF (CATA ANALYSISS C00?.0:NATCR
*SITIAL RE5FCN3E 5.3.1 Assembla supporting materials and take to TSC. * ;,
5.3.1.1 Review any assessments made using RP/0/A/50C3/11. 5.3.2 Inicia e cho following precadures as necessary. 5.8.2.1 HP/0/3/1009/13, Off-Site Dese Projection - Uncontrolled -
. Release of Radioactive Material through the Unit Vent.
5.8.2.2 RP/0/3/1009/14, Off-Site Dose Projection - Uncontrolled Release of Liquid Radioactive Material. 5.3.2.3 HP/0/ 3/1009/15, Off-Site Cese Projection - Uncontrolled Release of Gaseous Radioactive Material other than through the Unit Vent. 5.8.3 Assume the duties of the Data Analysis Coordinator if the emergency is classified above the Notification of Unusual Event Category and: 5.8.3.1 Proceed to the TSC. 5.8.3.2 Initiate activation of the Field Monitoring Organization by notifying the Field Monitoring Coordinator to respond according to Enclosure 5.10 and 5.11. 5.8.3.3 Initiate the folicwing procedures as necessary: 5.8.3.3.1 KP/0/B/1009/06, Alternate Methods fer. Determining Dese Rates Within the Reactor Building. 5.8.3.3.2 HP/0/3/1009/12, Quantifying Gaseous Release through Steam Relief Valves Under Post-Accident Conditions. 5.8.3.4 Provide special evaluation in areas such as shielding, off-site consquences of a containment loss or steam generator tube rupture, BBA, etc. 4 S
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Page 1 of 1 , HP/0/3/1003/d9 ENCLOSURE 3.9 ,
. STAFF (DATA ANALYSIS) CCCRDINATCR !.
CONTISC:NG RE3FCSSE 3.9.1 E*/alusta the need ec .;acalcilata desa projectiens based upen: I, . 1 3.9.1.1 Kacun changes in meterological status (vind speed, wind direction, AT, percipi:stien) . 3.9.1.2 Known changes in EMF readings.
. 3.9.1.3 Projected change in meterological conditions.
3.9.2 Evaluate total effect of dose projections when making multiple . releases (contairment, vent releases, occ.).
- - 3.9.3 Evaluate
- : a1 effect of dose projections when releases are expected i to centinue for lenger than two heurs, or to otherwise be affected j by extended evacuation times. '
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Page 1 of 1 . ; HP/0/B/1009/09
- ENCLOSURE 3.10 , .
? 2L "CNITOR:NG CCCROINATCR { ' !N T!AL RESPCNSE 5.10.1 Assemble supporting materials and take to TSC.
I 3.10.1 Initial Raspense ! 5.10.0.1 Activate the field monitoring organiastion by: 3.10.0.1.1 Notifying the TSC Radio Operator to report to the TSC and initiate HP/0/B/1009/19 Emergency Radio Operations, Maintenance and Ccemunications. 5.10.2.1.2 Selecting nine (9) Catawba Nuclear Statica Field Monitoring Team (FMT) members to be organi:ed as follows: Team Call Sign Number of Members Transeortation Alpha 2 Land Vehicle Bravo 2 Land Vehicle Charlie 2 Land Vehicle Delta 2 Land Vehicle Echo 1 Helicopter 5.10.2.1.3 Instruct TUT's to complete checkout steps from HP/0/B/1009/04, Environmental Moni-toring for Emergency Conditions Within the Ton Mile Radius of Catawba Nuclaar Station. 5.10.2.0 Cbtain plant radiological status and evaluate'the potential or existence of an off-site release of radioactive material (liquid or gasecus). 5.10.2.3 Obtain meterological information and determine initial sample direction. 5.10.2.4 Determine the need for serial environmental surveillance based on plant radiological status and meterological information. 5.10.2.4.1 If immediately needed, obtain helicepter support per Enclosure 5.15, Procurement of Helicopters for Aerial Environmental Surveillance. 5.10.2.4.2 If the possibility exist for future need, put helic:pter support on standby per . Enclosure 5.15.
.. ~1 5.10.2.5 Proceed to the TSC. -
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Page 1 of 2 , HP/0/3/1009/09 ENCLOSURE 5.11 FIELD MCSITORING CCCRDINATCR i CONTIN
- JING RES?CN32 5.11.1 Continuing Respense -
5.11.1.1 Dispatch FMT's based on plant radiological status and matarological information to sample locatiens listed in HP/0/3/1009/04 5.11.1.1.1 Plume location strategy should be to send FMT's back and forth across sectors to locate the plume. Only after the plume is located should detailed field monitoring begin. 5.11.1.2 Direct and implement field monitoring strstagies by: 5.11.1.2.1 Reviewing plant radiological status, field data and meterological information approximately every 15 minutes for changes which might affect field monitoring. strategies. 5.11.1.2.2 Directing FMT's to monitor locatiens. 5.11.1.2.3 Instructing T:!T's to take, as needed, special samples per HP/0/B/1009/04. 5.11.1.3 Advise the Data Analysis Coordinator to field monitoring results. 5.11.1.4 Maintain an up-to-date 10 mile radius map by: 5.11.1.4.1 Posting current FTM locations. 5.11.1.4.2 Posting latest instrument survey results for each monitoring location. 5.11.1.4.3 Illustrating approxim.sta plune shape and
, location.
3.11.1.5 !!aintain an organized file of all sample results/ data generated frem FIG
- activities.
5 . *.1.1. 5 :!aintain F107 equipment and supplies including protective clothing, liquid nitrogen, etc. ; and schedule shift coverage. 3.11.2 CMC Turnover 5.11.2.1 Cnce CMC is established,* coordinate turnover of FMT's to
- C::C control. *
.* ~7 5.11.2.2 Turnover of TSC FMT's to CMC Control shall occur at the .
intersection of SC 274 and SC 49. Should plume location - 1 interfere, alternate turnover location may be est4blishad. J
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1' ENCLCSt.7E 5.12 - CPERATION SUPPORT CENTER . p HIAL"3 PHYSICS SUPE 3:30R - INITIAL RESPONSE A e
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. Assemote supporting catorials and take to 05C.
1 ' 5.12.2 Contact OSC Operation Supertisor and coordinate Health Physics } aupport for 05C activities. Assist in ioplementation of RP/0/3/5000/12. [ 5.12.3 Provide immediate job coverage as necessary. Give due consideration to the fact that plant conditions may be unstable and radiological ; conditions unknown. 5.12.l. Provide immediate Health Physics coverage as necessary to support I Fire Brigade, damsgo control, medical emorgency and other emergency , ; activities. l 4 5.12.5 Direct technicians to obtain preliminary radiological infor::iation , available in Control Roem. ' t. l 5.12.5.1 Emphasis should be placed upon determining the areas of r l the plant experiencing increasing radiation levels. . .3 1 , 1 5.12.6 Based upon initial Control Room indications, direct technicians to monitor and report radiological status which will support OSC activities. .; - 5.12.7 Establish control over all OSC personnel radiation exposure and { limit to blanket dose extension levels. '
; 5.12.7.1 All activition which cause these levels to be approached ; or exceeded, require pre-pianaing and coordinatiun with i
TSC 54C Coordinator. >
- 5.12.8 Diract assignment of additional dosimetry to provide adequate i
! monitoring for the conditions expected, f i
, 5.12.9 Direct the use of protective clothing to limit the spread of I
contamination consister.t with the conditions expected, i i 3.12.10 Obtain additional instrumentation to support OSC activities ; ! (Teletector, neutron instrument alpha instrument, friskers), if j j' necessary. l l 5.2.11 Require each exit from 05C to Auxiliary Building be proceeded by a briefing on task to be,done and radiological conditions expected *
- when applicable. -
! 5.2.12 Coordinate Health Physics activities for assessment and repair teams , in accordance with RP/0/3/5000/12. , , k
- l $.2.13 Post blanket dose extension valves. .. "'I i
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li?/0/3/1009/C9 f ,,- ENC *.03CEE 5.13 . t 0?I3AT:0N SUFFCRT CINT!R HEALTH ?h"lS:CS SC?I2*.*:S03 - CCNTINUING .US?CNSE { l 3.13.1 :!aintain routine c:ntac: ut:h TSC SIC Coordinator :o pr: vide update on CSC sc:ivities and :s recai*.e plan: status raperts. , 5.13.2 Gbtain thru $5C Functions Coordinator :dditional dosimetry / protective clothing / emergency kit items necessary to support OSC activities. 3.13.3 Coordinate OSC activities requiring pre-planning. 5.13.3.1 E=phasis should be placed upon: Cosize:ry (Vhole Body a Extremities) Protective Cic:hing Route to and from task Respiratory equipment Need for Buddy System because of safety hanard (esdiological and non-radiological) Establishing dose limits and/or dose rate considorations for high exposure jobs on unknown situations Communications equipment Additional monitoring instrumentation i 3.13.4 . Monitor dose rate in OSC. Shculd General Area reach 3 mR/hr., initiate discussion with S&C Ccordinator en the need to evacuate the OSC, should dose rate be expected to continue. 5.13.3 All RE-ENTRY efforts should considor the special problers that may i exist High gsmma fields Increased Beta fields <
- High Contamination levels High airborne rad levels e
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Page 1 of 1 , HP/0/3/1009/09 . ENCI. cst'RE 5.14 ' RESERVE PERSCNNEL/ PERSONNEL MONITCRING LEADER , 3.14.1 Assemble all Health Physics personnel not initially required for emergency response. Non essential personnel sbould'be evalustad for ~ use in the emergency. 5.14.2 Identify personnel and/or personnel monitoring te4=s for the following locations. 5.14.2.1 All on-site assembly areas are identified in Station . Directive 3.0.7. 5.14.2.2 PAP Area. 1' 5.14.2.3 Construction Personnel Exit Area (Brass Gate). 5.14.2.4 Evacuatten Facility (Alpha or 3ravo). Tr.o cenitoring teams if both location are used. 5.14.3 Initiate, as necessary, HP/0/B/1009/05, Persennel Menitoring for Emergency Conditions. 5.14.4 Initiate random monitoring of vehicles located in the upper and lower parking lots starting with vehicles nearest the affected unit. The sonitoring team identified in Step 5.14.2.4 should bs used for this purpose. 5.14.5 Coordinate with the TSC Surveillance and Control Coordinator on relocating personnel monitoring teams if background radiation
- renders normal menitoring locations unfit.
t 5.14.6 Supervise Health Physics efforts at the Evacuation Facility (s) as per Reference 2.3. 5.14.7 Provide direction to reserve Health Physics personnel: 5.14.7.1 Direct and control personnel in the staging area (DRC office in the Administration Building). 5.14.7.2 Coordinate with surveillance and Control Cecedinator to provide addition manpower, as necessary. 5.14.7.3 Coordinate with Support Finctions coordinator to provide additional manpower, as ascessary. 5.14.7.4 Direct activities of Field Monitoring Tease if relieved by CMC personnel. . 5.14.7.5 Begin scheduling activities for Health Physics personnel. 5.14.6.P' Support CSC Supervisor with major activities as required. *
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"'/0/3/1009/09 . closure 3.15
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l- ! C3C RI3FCSSI ?IR3;SS!*.0035 .,ICORD FCR:! l , l d e I Sa::'e : HP Bad;e No.: Social Security No.: Exposure Class l . Birthdate: Age: 1.*ork Group:
- Quarterly Dose to Date: crem
** Yearly Dose to Dates mrom Per:sissable Lifetime Dose to Date: mrem Total Lifetime Dose to Date: mrom Date/ Time Dosimeter Reading
- Quarterly Dose Total Comments Out (ares) In (teren) ;
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** Current Yearly Dose eram Plus Today's Dosimeter Dose stem. .* 9 % , 1
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- . fura.ish :ne he'.icep:ar upon reques: 2nd in addi:icasi helicep ar vi:nin sin hcurs folicwing no:ifica:icn. Cnce a helicepter is requestad, there is 2 :2ximum elapsed :ime of three hours for the helicep:ar to arri e at ,
C2:suba Nuclear S:atica or c:her dispatched locatiens. l i Helicopter service is limited to dayligh: hours and adequa:e flying t.eather. ne helicopters will hold three people, the pilot and two passengers. To l perform survays, instrumentation may limit the passenger space. 1 !/ To obtain helicopter (s) for emergency service contacc: 4 Office Houe
- 1. 3. A. Turpin l 2. L. k'. Johnson S
- 3. L. !!. k~hisenant I
- 4. D. ?!. Staggs NOTF.: These contacts are in Duke Power Co=pany Transeission Deat.,
Line Division. The microwave extension for the offica nambers is 220. . j. i l l { S 4
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a Form 34731 (10-31) (Formerty SPO-1CO21) DUKE PC'JER COMPANY (1) ID,No: HP /0/3 /1009/08 ' ~ PROCEDURE PREPARATION Change (s) O to PROCESS RECORD 0 Incorporated (2) STATION: CATXJBA (3) PROCEDURE TITLE: CONTAMINATION CONTROL DURING TRANSPORTATION OF CONTAMINATED INJURED INDIVIDUALS (4) PREPARED BY: C ,kb m , mm . _) DATE: MARCH 29, 1984 (5) REVIE'JED 3Y: ~.t / .1 *
- / DATE: .5 - M - yv Cross-Disciplinary Review By: N/R: 3oM (6) TEMPORARY APPROVAL (IF NECESSARY):
By: (SRO) Date: By: _ . Date: - (7) APPROVED BY: ls' - ,/ Date: 3!3[ (8) MISCELLANEQUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: I
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HP/0/3/1009/03 DUKE PC'4ER COMPANY CATNi3A NUCLEAR STATION' . CCN~T!INATICN CONTROL DUR!NG TRANSPCRTATICN OF CCNTA'!INA3D INJURED INDIVIDUALS 1.0 PURPOSE i To provide guidance for the control of radioactive contamination due to transportation of a contaminated injured individual (s): A. At the accident scene. B. In the First Aid Recm. C. In the Ambulance. Di During initial treatment in the hospital.
2.0 REFERENCES
2.1 HP/0/B/1000/05, Delineation of RCZ's 2.2 HP/0/B/1003/31, Operation and Calibration: Eberline Model E140N Portable Count Rate Meter 2.3 BP/0/B/1004/06, Personnel Decontamination 2.4 HP/0/3/1004/21 Equipment Decontamination 2.5 HP/0/3/1009/02, Investigation of Possible Overexposure, Personnel Contamination and/or Unusual Radiological Occurrences 2.6 HP/0/B/1009/10: 9ed7 Burden Analysis Following Suspected Uptakes of Mixed Fission and Activation Products 2.7 Catawba Nuclear Station Emergency Plan 2.8 NCRP Report No. 65 2.9 10 CTR 20 .103 (a) (1) 3.0 LIMITS AND PRECALTIONS 3.1 Lifesaving first aid and the preservation of vital functions shall have priority over contamination control. 3.2 If a wound (s) is contaminated, a BBA shall be administered per reference 2.6 at the first opportunity after proper medical attention has been given. 3.3 Appropriate respiratory equipment shall be used to prevent or
- minimize internal exposure in any planned rescue attempt. - ' 9 3.4 %
Utilize as few people as necessary for the rescue and treatment of - t contaminated injured individuals.
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HP/0/3/1009/08 . Page 2 of 6 / 3.3 Ensure that all personnel involved in the rescue and treatment of contaminated injured individuals receive proper monitoring and decont amination, if necessary. ' 3.6 If the emergency vehicle is found to be contaminated, that vehicle may be released if needed for assistance in life thre'atening situations and be decontaminated to below acceptable limits at the first opportunity as per Reference 2.4 - 3.7 Ensure that valuables which are collected from the injured persen are monitored and turned over to security. 3.8 Ensure that the tamper seal on the Medical Decontamination Kit has not be broken. Inventory the kit if it has. 3.9 Ensure that Security has been notified. 3.10 Ensure that HP Duty Supervisor has been notified if injury occurs during backshift. 3.11 Body excretions and vomitus should be collected in separate containers (or bags) and transported with the injured person to the hospital. Containers should be labeled with the type of sample, date and time of collection. All bodily effluents should be returned to Health Physics for radiological analysis.
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4.0 PROCEDURE - - 4.1 Control at Accident Scene 4.1.1 Incapacitated Victims 4.1.1.1 Have victim brought to the RCZ exit nearest the accident scene. 4.1.1.2 Have rescue werkers place injured on stretcher in such a way as to minimize cross contamination. 4.1.1.3 Once victim is on stretcher, cover him/her with blanket securely to prevent the spread of contamination while in motion. 4.1.1.4 Ensure a Health Physics representative is available in the First Aid Room to assist medical personnel. 4.1.2 Minor Injuries 4.1.2.1 For victims with minor injuries, have them exit
- their work area in the normal fashion. .* ~1 4.1.2.2 Accompany victim to Contaminated Change Room and -
i monitor with available frisker. If l contamination is found, decontaminate in * ' accordance with Reference 2.3, using Contaminated l Change Room facilities. l 1 l
l HP/0/3/1009/08 Page 3 of 6 . 4.1.2.3 Have victim report to Contaminated First Aid Rocm (Auxiliary Building) to receive any additional treatment. - 4.1.3 If sceident occurred in a normally non-contaminated area and the possibility of accident induced contamination exists, control access to the area as per Reference 2.1. 4.1.4 After victim (s) have been evacuated from accident site and ? taken to Contaminated First Aid Room, smear survey the route taken. If contamination is found, post area as such and take appropriate steps for decontamination. 4.2 Control in the Contaminated First Aid Room 4.2.1 Prepare victim laydown areas by covering them with a protective covering before placing victim down. 4.2.2 Prepare sufficient facilities for the storage of contami-nated waste generated during first aid treatment. 4.2.3 Ensure that all personnel in the First Aid Room are wearing anti-contamination clothing appropriate for the levels of contamination expected. 4.2.4 Upon victia(s) arrival, collect their dosimetry and place in polyethylene bag for subsequent evaluation. 4.2.5 Line the covered victim laydown area (s) with blankets if available and place victim (s) there. 4.2.6 Personnel Monitoring 4.2.6.1 Victims in Anti-C Clothing 4.2.6.1.1 Assume all victims in Anti-C's have surface contamination. 4.2.6.1.2 Remove Anti-C's by cutting midline and peeling to each side. 4.2.6.1.3 Place disrobed victim on clean blanket and fold A.fI-C's V into blanket that was previously under victim. 4.2.6.1.4 Proceed to monitor entire body surface with an E140N and HP-210 probe. 4.2.6.1.5 hoto contamination levels on
- Personnel Contamination and ' ~1 Decontamination survey sheets.
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4 HP/0/3/1009/08 . Page 4 of 6 , 4.2.6.2 Victims in Street Clothing 4.2.6.2.1 Mcnitor victim with E140N and HP-210 probe.
- 4.2.6.2.2 If contamination is found, remove clothing by cutting ::ridlina and peeling to the sides.
4.2.6.2.3 Plate disrobed victim on clean , blanket and fold clothing into blanket that was previously under victim. 4.2.6.2.4 Resurvey victim. 4.2.6.2.5 Fill out Personnel Contamination and Decontamination Survey Sheet. (Enclosure 5.1). NOTE: Now, victim (s) can be handled according to their contamination level. 4.2.7 Health Physics in conjunction with medical personnel will determine if victim decontamination should be initiated or if immediate transporation to hospital is necessary.
- 4. 2. 8_ If decontamination is to be initiated in accordance with Reference 2.3, attempt to use shower, if victim cannot be showered, perform decontamination utilizing damp towels and wiping specific areas.
4.2.9 After decontamination, resurvey victim and complete (Enclosure 5.1). 4.2.10 Prior to victims laydown on ambulance seteccher, insure that the area is securely covered with a protective covering. 4.2.11 Pass victims through double doors of Contaminated First Aid Room to ambulance personnel, being sure to minimize the spread of contamination. i 4.2.12 Prior to loading on ambulance, cover all contaminated victims (ex: blankets, sheets), and cover necessary areas of the arbulance to minimize the spread of contamination. 4.2.13 Have a Health Physics Technician and Nurse (if~ available) accompany the contaminated victim to the hospital with the following items: , , Victim's Personnel Contamination and Decontamination Survey .+ 1 Sheet (Enclosure 5.1) E140N and HP-210 Probe g
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HP/0/3/1009/08 Page 5 of o , SCTE: If there is significant contaminatien.
- additional support should be dispatched to hospital.
4.3.14 First Aid aces should be posted for radiatica and contaminatien present until decontamination can be i perfor=ed. 4.3 Control in the Ambulance
. 4.3.1 Refer to (Enclosure 5.1) to obtain degree of contamination present. Contamination control can be determined with the use of this information.
4.3.2 Ensure that ambulance personnel are adequately dressed for , degree of' contamination present. 4.3.3 Provide polyethylene bag for disposal of all items coming in contact with the victim and return to Catawba Nuclear 4 Station for decontamination or disposal. 4.3.4 Upon arrival at hospital, secure bags appropriately. 4.3.5 Instruct ambulance personnel in proper Health Physics practices chile involved in treating the contaminated injured individual. 4.3.6 Upon victims transfer from ambulance to hospital, see that all doors and windows of ambulance are secured and post as a potentially contaminated area until further monitoring j can be performed. 4.4 Control During Initial Treatment In Hospital 4.4.1 Ensures that all personnel in the treatment area are wearing proper dosimetry, and that dosimetry has been i properly labeled and that dose cards have been filled cr.t 1 before returning them to Health Physics for evaluation. 4.4.2 Control or minimize spread of contamination when entering facility as not to hinder access to emergency room in , regards to non-radiological patients and personnel. 4.4.2.1 RCZ should be set up in accordance with Reference 2.1 at the entrance of the treatment area. 4.4.2.2 Ensure that floor covering is taped to the floor of the , treatment area. , 4.4.2.3 Ensure that ventilation ducts in the treatment .
- 9 area are secured by placing a covering over them. g I
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HP/0/3/1009/08 , Page 6 of 6 , a.a.3 Centrol or =ini=ine spread of contamination in regards to t:33tOent. 4.4.3.1 P.cnitor persennel and equipment leaving the , treatment area. 4.4.3.2 Insure that all perscanel in the treatment aros are wearing anti-centamination clothing appropriate for the levels of contamination present and that diagnostic equipment is properly co'ered. v 4.4.3.3 Prepare sufficient facilities for the storage of contaminated waste generated during treatment. 4 4.1.4 During treatment, depending on urgency of treatment, instruct hospital personnel in proper Health Physics practices by radiological advisement and assessment. NOTE: Do not interfere with treatment. 4.4.5 After treatment, monitor room and equipment. If contaminated, initiate decontamination. This procedure involves proper wrapping and tagging of materials. Transportation of contaminated materials should be a consideration. 5.0 ENCLOSURES 5.1 Sample of Personnel Contamination and Decontamination Survey Sheet e 9 v' [
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4 - 1 Name of Inditidual . _ . . . . . HP 624.': Number Individual's Super 1.s:: , W:k T c". Job Descriptica (3'JP/SK'i?) _ I Cause of Persennel Cents., ins:ica i e . 1 Check and answc: in the .: pace ~colew: ( ) Ac: ton recormended :o preven a racurrunce of Persennel' C0r.:4tJ ina t iC3. ( ) ;mcentamina:!cn Mathed used in "t . uui.cncamina:icn cf Pe:sonnel. i - - _ . . . - . . . . . . . . . . . . . _ i Use additicesl thouts as t!'act:s.ey. i use the reverse for :cicording . ,n .actna'.ti.a . ..v t. : :. or. P n::venu t . Usa additienal snee:a as necessary durin:; :e..:,.it.iai:ta:2.r- a: :'e r v une ' . . it? Ins ur.un:s 's,*:.ed: T/; n %n.-he r E7./F.
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DUKE ?C'4ER CCM?.CY (1) ID No:HP/o/3/1009/05 PRCCEDURE PRE?A?ATION Change (s) C _ _:o ' 2RCCESS RECCRD 2 Incorporated (2) STATICN: Catawba (3) PROCEDURE TITLE: Personnel / Vehicle Monitoring For E:: ergency Conditions (4) PREPARED BY: A- >> 22A DATE: / - 2 .7- /? (3) REVIE*JED 3Y: /##'r57 DATE: !-28 Cross-Disciplinary Review By: /2/M [ N/R: (6) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: By: __ Date: (7) APPROVED BY: . .
.e 4 .W7 _ Date: $-2N-SN (8) MISCELLANEOUS:
Reviewed / Approved By: Date Reviewed / Approved By: Date: 1 s 1 e h 4 1
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HP/0/3/1009/05 ,-
- GI PCWER COMPANY CATAWBA SUCCAR STATION PERSCNNEL/VEHICE MONITORING '
! :CR E'iERGENCY CONDITICNS - 1.0 PGPOSE To provide guidance for personnel and vehicle monitoring during a site evacuation resulting from a radiological emergency. , 2.0 REFEREN'CES i 2.1 HP/0/B/1003/31'. Operation and Calibration: Eberline Model E-140N
- Portable Count Rate Meter 4
- .2 HP/0/3/1004/06, Personnel Decontamination 2.3 HP/0/3/1004/21 Equipment Decontamination i 2.4 HP/0/3/1009/09, Guideline for Accident and Emergency Response i
2.5 HP/0/B/1009/16, Distribution of Potassium Iodide Tablets in the . Event of a Radiciodine Rglease i 2.6 RP/0/A/3000/10, Conducting a Site Assembly or Evacuation 2.7 Station Directive 3.0.7, Site Assembly / Evacuation i 2.8 Station Directiva 3.8.3, Contamination Provention, Contr'J1, and
! Decontamination Responsibilities 1 ) 2.9 Catauba Nuclear Station Emergency Plan 2.10 System Health Physics Manual -
i 3.0 LIMITS AND PRECAUTIONS i 3.1 If survey teams are expected to be exposed to I-131 in excess of 10 l MPC (9 x 10 8 aci/el), and as directed by S&C Coordinator, each t team member should ingest one tablet of Potassius Iodide. ( ) 3.2 Ensure that the Radia': ion Monitoring equipment has been battery t checked and source response checked as per HP/0/3/1003/31. . 3.3 If emergency vehicle is found to be contaminated as per Catsuba Nuclear Station Directive 3.8.3, Section 6, and alternative transportation is not available, that vehicle may be 4 released if needed for assistance and be decontaminated to below acceptable limits at the first opportunity as per Catawba Nuclear . Station HP/0/B/1004/21 Equipment Decontamination. t , , q
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4.1 Tc.s Surveillance and C:ntr:1 Cecrdinat:r sha'1 dasi.; nata a supervisor or lead technician to assune the responsibilities of the Reserve Personnel / Personnel Menitoring Leader (R?/?M Leader). 4.1.1 The RP/PM Leader shall be raspensibla for perscnnel nenitoring when an evacuati:n occurs due : a radiological incident and other respcasioill:1es 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 ccpa for friskers. 4.1.3 The RP/PM Leader shall also arrange for monitoring of the assembly points and initista actica when dose rates approach 2 mr/hr. , 4.2 The RP/RM Leader shall dispatch an Emergency Personnel Monitoring Team to the following locatrions upoa initiation of a site assembly resulting from a radiological incident.
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l 4.2.1 Personnel Access Portal (PAP) 1 4.2.2 Construction Personnel Exit Area (Brass Gate). 4.2.3 All on-site assembly points as listed in Reference 2.7. 1 NOTE: Manpower shall be supplied with respect to the nature of 'j the accident and the availability of Health Physics Personnel. l j 4.2.4 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 i Decontamination Responsibilities and an Personnel Monitoring Kit. 4.2.5 Upon reaching their designated locations, the survey teams shall verify their position with the RP/PM Leader. 4.2.6 The Construction Personnel Exit Area Team shall insure all personnel receive proper monitoring leaving via this exit during evacuation. 4.2.7 The PAP Area Survey Team shall insure that the portal socitoirs are used properly and provide additional sonitoring 2 in order to expedite evacuation. . 4 9 h
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HP/0/3/1009/05 Page 3 of 4 , s If an individual is found to be centaminated as per Catawba
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4.2.8 - Nuclear Station Directive 3.S.3, the survey team shall: ' 4.2.3.1 Dress the individual in the appropriate protective clothing and when time permits, ' decentaminate as per Catawba Nuclear Station HP/0/3/1CC4/06. 4.2.3.2 Notify the RP/FM Leader of all cases of persennel centamination. 4.2.9 Survey teams will be supplemented, relieved or secured as directed.
, 4.2.10 Survey teams will monitor dose rates at exit areas.
Should dose rates exceed 2 mr/hr, team will initiate discussica with RP/PM Leader to expedite any evacuatica through that exit point. 4.2.11 The RP/PM Leader should notify the Surveillance and Control Coordinator of all action taken. 4.3 The RP/PM Leader shall assemble another Emergency Monitoring Team upon initiation of a site assembly frca a radiological incident for randos monitoring of espicyes vehicle and when site evacuation is - initiated, dispatch this team to the Evacuation Facility (site Alpha: Transmission Line Maintenance Warehouse near Hwy SC 274 and SC 161. Site Bravo: Allen Steam Station, Hwy NC 273, South of Belmont). . NOTE: Monitoring equipment for vehicles is located in the Personnel Monitoring Kit located in the PAP area. 4.3.1 If a vehicle is found to be contaminated as per Catawba Nuclear Station Directive 3.8.3, the survey team shall: 4.3.1.1 Prevent further movement of the vehicle. 4.3.1.2 Post the vehicle as a contaminated area. 4.3.1.3 Provide general information on contamination surveys to the RP/PM Leader. 4.3.1.4 Monitor all vehicles in the area for contamination. 4.3.1.5 Decontaminate Vehicle using best method (s) available on property owned by Duke Power Company that does not drain to a water system. 4.3.2 Upon site , evacuation and notification of Evacuation Facility (Alpha or Bravek), the RP/PM Leader shall: .
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4.3.2.1 Move with the monitoring team to the Evacuation Facility. '.6
HP/0/3/1009/05 Psgs 4 of 4 l 4.3.2.2 Locate Personnel Survey Kit at evacuatica c Tacility r.d prepare to scnitor inecming - persennel. Persennel Survey Kit storsgs locaticas are identified en the Evacuation
- Facility Layout Craving., Enclosure 5.1.
4.3.2.3 Supervise the ::enitoring and release of persennel as described in Steps 4.2.3 through , 4.2.9 and 4.2.10. 4.3.2.4 List all personnel's names, social security ., number and Health Physics badge number on * ' Evacuation Personnel Dose Record Sheet, Enclosure 5.2. This form should be used for
; dose commitment at a later time.
4.3.2.5 Supervise monitoring of employne vehicles and take action as appropriate per Step 4.3.1. 4.3.2.6 Notify Surveillance and Control Coordinator of r.11 actions taken. 4.4 If background radiation readings render friskar a:td/or portal monitor useless, the RP/PM Leader shall:
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! 4.4.1 Discuss with the Surveillance and Control Coordinator relocating the personnel sonitoring location a location of lower background. 4.4.2 Procure from the Temporary Administration Building at 20
! watt portamoble radio for communication with the OSC. ;
Check operability of the radio. l 4.4.3 !!ove with the monitoring teams to an area of lower
- background where personnel control can be maintained and prepare to monitor personnel.
4 4.4.4 Supervise the monitoring and release of personnel as described in Stepe 4.2.3 through 4.2.9 and 4.2.10. 4.4.5 Supervise monitoring of employee vehicles and take actions as appropriate per Step 4.3.1. 1 4.4.6 Notify Surveillance and Control Coordinator of all actions taken.- 1 3.0 L W 8URE8 5.1 Evaeustion Facilities Layout Drawings 3.2 Evacuation Personnel Dese Record, . J , 4
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Form 34731 (10 31) (Formerly SPD 1CO21) DUKE PC*a'IR CCM?M.T (1) ID No: HP/0/B/1009/0/. '
?RCCEDURE PRE?A?aTICN Change (s) O co PROCESS RECORD 0 Incorporated (2) STATION: CATAWBA j (3) PROCEDURE TITLE: ENVIRON! ENTAL MONITORING FOR EMERGENCY CONDITIONS WITHIN THE TEN MILE RADIUS OF CATAWBA !."JCLEAR STATION
(!*) PREPARED BY: M DATE: )~/ 1 ($) REVIEWED BY; -
/ - & DATE: - [T -h j Cross-Disciplinary Review By: N/R: 3.7 Jr.4 (6) TEMPORARY APPROVAL (IF NECESSARY):
By: (SRO) Date By: . Dates . - (7) APPROVID BY: 'd-I Date i o Y (8) MISCELIANIQUS: Reviewed / Approved By: Dates Reviewed / Approved By: Date: t t; t e% 9
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I HP/0/3/1009/04 DUKE PCWER CCMPANY CATAV3A NUCLEAR STATICN - ENVIRONMENTAL MONITOR *NG PCR EMERGENCY CCNDITIONS WIT *iIN T'{E
""EN MII.E RADIUS CP CATAW3A SUCI. EAR STATION 1.0 PURPOSE To provide a method for identifying gaseous plumes or liquid effluent, and obtaining field data indicative of the radiation exposure.co the general public following a suspected uncontrolled release of radioactivity.
This procedure shall also be implemented by the Crisis Management Center once it is activated.
2.0 REFERENCES
2.1 HP/0/B/1000/06 Emergency Equipment Functional Check and Inventory 2.2 HP/0/B/1002/04 Collection of Operational Environmental Weekly Samples 2.3 HP/0/B/1002/05 Collection of Operational Environmental Monthly Samples 2.4 KP/0/8/1002/06 Collection of Operational Environmental Quarterly Samples 2.5 HP/0/5/1002/08 Collection of Operational Environmental Semimonthly Semples 2.6 KP/0/B/1002/10 Collection of Operational Environmental Semiannual Samples 2.7 KP/0/B/1003/05 Operating and Calibration Procedure: Eberline Model PIC-6A Portable Ion Chamber 5 2.8 KP/0/3/1003/12 Operating and Calibration Procedure: Eberline Model E-520 Portable Beta Gamma Geiger Counter
, 2.9 HP/0/8/1003/17 Operation and Calibration Procedure Canberra Series - 10 Portable MCA 2.10 HP/0/8/1003/31 Operation and Calibration: Eberline Model E140N Portable Count Rate Meter 2.11 HP/0/B/1009/16 Distribution of Potassium Iodide Tablets in the Event of a Radiciodine Release 2.12 HP/0/8/1009/19 Emergency Radio System Operations, Maintenance and Communications .. "1 '6 te
li?/0/3/1009/04
?tge 2 of 3 2.0 LI'!!TS AND ?3ECAC:C':S 3.1 The Field Menitoring Teams (FMT) should park vehicles templetaly of f the ::ad shen samplin;. ~
3.2 Tour (4) FMTs consistin; of two (2) tachat: tans per taam and ons (l' helic:pt<r team (1 person) if necessary shall be formed as folicws: Teim Call Signs Transoortation Alpha Land Vehicle 3ravo Land Vehicle Charlie Land Vehicle i Delta Land Vehicle Echo Helicopter l 3.3 Each FMT shall use particulate masks and protective c1cching whenever activity justifies it or when directed by the Field Mcnitoring Coordinator (FMO). 3.4 If the team members are expected to be exposed to I-131 in excess of 70 tiPC (63 x 10 uCL/ml), and directed by the FMC, each team member should ingest a tablet of potassium Lodido per Reference 2.11. 3.5 Environmental sampling during emergency conditions shall not replace, but rather supplement normal environmental monitoring. 3.6 Each Fiff shall maintain open radio communications with the FMC per l Reference 2.12. If to becemos inoperable, call in sample results I en a ehene at (LakeWylie/ Charlotte), Gaston County) ock Hill and Fort Mill). 3.7 If any equipment becomes inoperable, notify the FMC and wait for further instructions. 3.8 Annual training in the use of this procedure ind the associated equip-ment and instrumentation shall be conducted and documented en TSR-10. 3.9 Portable MCA's shall be picked up at the Health Physics instrument issue point when directed by the FMC. Ensure that the dewars are adequately filled per Reference 2.9. 3.10 When returning kits to the Emergency Kit Storage Room, perform in equipment inventory check using the Environmental Survey Kit Checklist (Reference 2.1). Note deviations and forward to the Respiratory / Instrument Calibration Supervisor. 4.0 PROCECURE
'*1 Activation .
4.1.1 L.pon notiggoaton sad '**DIY (IMC), the FUT members shalb , v* e se mM
HP/0/3/1009/06 Page 3 of 3 g l a.1.1.1 Raport to the Health Physica aria en the , 509' elevation (on back shtfts report to l Administration 3uilding) and wait for furtaar instructions f rem the FMO. , 4.1.1.2 Report to the Emergency Kit Sccrage Room in the Tsoperary Administratica Building to get Environments 1 Survey Kits. 4.1.1.3 Ensure the Portsble Power Generator is* operational and the gas can is fully fueled (Reference 2.1). 4.1.1.4 Ensure the tamper seal on the Environmental
- Survey kits have not been broken and inventory i any that have (Reference 2.1), i 4.1.1.5 Den TLD and pocket dosimetry and fill out dose cards.
A 4.1.1.6 Bsttery and source check survey instruments and portable MCA for proper operation (References 2.7, 2.8, 2.9, 2.10). T 4.1.1.7 Ensure the portable radios are functional before leaving (Reference 2.12). 4.1.1.4 Obtain emergency vehicles as directed in Enclosure 5.8. . l 4.1.1. 9 Each Edr will proceed to the survey point
- assigned by the FMC (Enclosure 5.3).
l ! 4.2 Locating and Tracking the Plume 4.2.1 At the assigned survey point, the FMT shall perform a general area Beta vs. Seta Gemme survey. This method should be used to locate center and width of plume. 4.2.1.1 Record date, time, location and dose rate (ar/hr) on the yield Monitoring Data Sheet (Enclosure 5.4). 4.2.2 If survey results are less than or equal to expected background, call in the results to the FMC and wait for further instructions. l 4.2.3 If survey results are greater than background, take
- protective actions as necessary. Then, if directed, take l an air sample (volume should be > 10' el) equipped with a l Silver Zeolite Cartridge and particulate filter.
l , . 4.2.3.1 Insert cartridge with arrow pointing in. ,, "1
** y l
l
HP/0/3/1009/Ca Psga 4 of 3 - 4.2.3.2 insert filter paper with s=cotn side f acing
. out.
4.2.3.3 Calculate required sample time per Enclosure 3.3. - 4.2.3.4 Vaan air sa=ple is c =pleted. place the Silver 2ealite Cartridge n a poly b32 for analysis. 4.2.J.3 Place filter in a separate poly bag, label and retam for later analysis. 4.2.3.6 Follow instructions on the Field Monitoring Team W .h Shiet and the attached Operator Guidelines (Enclosure 5.6) to record air sample information and analy:e the cartridge on ths Cinberra-10. 4.3 Special Sampling, as directed: 4.3.1 All sampling outside of Auxiliray, Service and Turbine Buildings should be done in convinction with Operations Support Center (OSC) personnel. 1 4.3.2 Take smears and place them in separate poly bags, label and retain for later analysis. l 4.3.3 Count smears on E140N and record on Field !!onitoring Data l Sheet (Enclosure 5.4). Call in results to D!C.. 4.3.4 Collect water samples in cubitainers using good Health j Physics practices and label and retain for later analysis. 4.3.5 Place TLD's in the environment. 4.3.6 Retrieve and replace air sample and/or TLD's that are already located in the environment. Locations are listed ,. in Enclosure 5.1. Place samples in separate poly l bags, label and retain for later analysis. 4.3.7 Collect broad leaf vegetation sample (one square meter) label and retain for later analysis (Reference 2.12). 4.3.8 Collect shoreline sediment sample (one litar) label and retain for later analysis (Reference 2.6). 4.3.9 Collect milk sample (one full cubitainer) label and retain for later analysis (Reference 2.3). Locations are listed in Sample Enclosure 3.2. 4.4 Turnover 4.4.1 Each n!T shall be relieved as directed by the n!C.
.* 9 4.4.2 Inform the relief n!T of the equipment inventory status. % : - ii
.- . _ ~ - - . - _ - - ..-. . . . - - ..- ._ - . _ . _ - - - .. . - - .-_- - - .
t i HP/0/3/1009/04 { Page 5 of 5 "? e ! .. I i 4.a.3 Direct the relief T'!T to den T*2's and pocket dosimetry "
. r.d fill out dose caris. l j 4.4.4 Return all samples to the Emergency. Kit Storage Roem i ss directed by the T'!C. - \ -
- 4.4.5 Turn in all dsts sheets to the T'!C or his designee.
1 5.0 ENCL 0st;RES i > 1 5.1 ' Air Sampler, TLD. and Water Sample Locations l E 5.2 Milk Sample Locations i a 5.3 Predetermined Sampling Leestions i a
; 3.4 Sample of Tield Monitoring Data Sheet ,
5.5 Sample Time Required For Minimus Sample Volume j 5.6 Sample of Field !!onitoring Team Vork Sheet For Determining Iodine
- j. Activity l r-j ,
5.7 TSC Field Monitoring Organization i i : 3.8 Emergency Vehicles ! 1-L l I ( [ i j i
. r e ,
f l
?
- e ;
5 e% 3
*4 j 1 e .s 5
e t ee
l l l l Page 1 of 3 , DGE PC'4ER C2MPANY CATX43A SL*2 LIAR STATION
- HP '0 / 3 /10C9;'Ca 250'23 3 I 3.1 AIR SAMPLER, TLD, AND '4AUR SA:!?tZ L2 CAT 2S3
~
Air Samole Locatiens (need key C?D-1)
) "'en e & Radius (Mi) & , Descrietion A0 1 1 Hwy 274-N, right Liberty Hill Rd., right in fork to end (Air CNS #200, need key).
A0 1 5 Left at Steam Production entrance on Concord Rd., left on Old Concord Rd., right on , Acacia Rd., left on Crepe Myrtle Rd., left on Blue Bird Ln., through gate to end (Air CSS 9201, need key). 31 3 1 Hwy 49-N, right Hwy 160, right at Tega Cay sign (98), right before Tess Cay entrance inta Duke Power Ccmpany substation (Air ' CNS #212, need key), j C2 10 $ Hwy 274-5, left Hwy 161, right Mt. Gallant Rd. I (195), right Hwy 21-121 By-Pass, right on , Hwy 72 - 121 By-pass, left on dirt road (Trash Pile Rd.) across fros Wayne's Auto Cervice, so to Duke Power Company substation-(Air CN8 #217 need key). [ A0 1 26 ,Behind Catawba Nuclear Station over1cok (Air r CNS #203, need key). l TLD Locations I. Site Boundary TLD's Zone & Radiug (Hi) & Descrintion A0 1 44 Hwy 274-N, right Liberty Hill Rd., risht in fork, pass softball field to large rocks I at fence on right. TLD is on fence (TLD CNS #222). t A0 1 1 Hwy 274 N, right Liberty Hill Rd., right - in fork to end (TLD CN8 #200, neel key).
, A0 1 3 Left at Steam Production entrance on Concord Rd., left on Old Concord Rd., right on Acacia Rd., left on Crepe Hyr:1e Rd.,
- left on Blue Bird Ln., through gate to end . *
(TLD CNS #201, need key). ,, 9 A0 1 8 Left at Steam Production entrance on ' ,,, I Concord Rd., left on Old Conceri Rd. , right ' on Acacia Rd. , left on Crepe !!yrtle Rd. Go - l ' to first drive on right past Paradise P1., TLD across road (TLD CNS #202). l
<e
Psge 2 og 3 , Ct.U. PCVER CC.'!PANY ' CATA'48A Nt;CLIAR STAT:CN + HP/0/3/1009/04 ISC:.2SRZ 3.1 AIR SA.'!PLZR. TLD. AND '4ATER SA!!PLE LOCATICN3
.!cne 5 Rsdius ('!i) 1 Descriptien A0 1 11 Lef t at Steam Production entrance on Concord Rd., left on Old Concord Rd.,
right on Acacia Rd., left on Crepe Myrtle Rd. TLD is .1 miles on l 1 eft in curve (TLD CNS #223). A0 1 14 Left at Steam Production entrance on Concord Rd., left on Old Concord Rd., , right on Acacia Rd. TLD .2 miles on l right (TLD CNS d224). A0 1 43 Left at steam Production entrance on Concord Rd., left on Old Concord Rd. to l end. TLD on fence on left (TLD CNS d203). A0 1 17 Left at Steam Production entrance on Concord Rd. to first transmissicn tower on left after bridge (TLD CNS 0228). l A0 1 20 Left at Steam Production entrance on '
, Concord Rd., TLD on left across, bridge just past fence (TLD CNS #226).
A0 1 23 Left at Steam Production entrance on Concord Rd., TLD on left at beginning at guardrail posts (TLD CNS #204). A0 1 26 Behina Catawba Nuclear Station overlook i (TLs CNS #203). A0 1 29 Left at Steam Production entrance on Concord Rd., TLD at Shady Shore Dr. on ' right corner at Bethel Community Clubhouse sign (TLD CNS #227). A0 1 32 Right at steam Production entrance on Concord Rd., TLD at first dirt left (Valetake Dr.) on right c.orner (TL3 CNS #223). A0 1 33 TLD on top of hill at Catawba Nuclear Station Construction entrance on North side of street (TLD CNS #206). i A0 1 38 Hwy 274 N, right at Liberty tiill Rd., right in fork to third power line on right, walk . about 200 yds. South along boundary fence. ,, q TLD on fence (TLD CNS 9227). , A0 1 41 Hwy 274 N, ri4ht at Liberty Hill Rd., go *~~ '
.3 miles (right in fork) TLD on fence on .
right (TLD CMS n207). 1
<0
l . 1 ! I hp 3 t ! l Ct.TE PCVER CC:!PANY a l l CATAW3A Nt.* CLEAR STATION .- , j lip!0/3 /1009/ 0 I l ISOL2$ E 3.1 j l AIR SA:PLIR, TLD. AND WATIR SX:PI. LOCATICNS
'one 4 Relius Cli) 1 0 se.rtp:10n
- l l.
!!. 4 5 .111e TLD's l f
l T1 4 4 hy 40-N to River Mills Plantation rear i entrance at Robinwood Rd. TLD behind green building on right corner ' (TLD CN8 #J230). . l ! F1 4 6 Hwy 49 N to River Hills Plantation front entrsnee guardhouse (TLD CNS tk231). ; i A1 4 2 hy 47 N to intersection of Pleasant Hill ; Rd. (1109), TLD on power line (TLD CNS #232). i At 4 4 hy 49 N, right Plessant Hill Rd. (1109), l right Youngblood Rd.(1102), left Zoar Rd. ! (1103), right Thomas Rd. (1104), TLD behind second house on right (TLD CNS #233). i 32 4 2 Hwy 49 N, right Hwy 160 to Home Federal l Sayinse and Lean on leit. TLD on left rear serner of building. (TLD CNS #234). , 31 4 3 Hwy 49 N, right Hwy 160, right en Das Rd.- 1 (99), last gravel right in sharp surve l before Lake dy11e Dee, left through fence ; to substation. TLD on right of inner i substation fence (TLD CN8 4235). C1 4 1 Hwy 274 8, left !!t. Gallant Rd. (193), i left India Hook Rd. (30) to 8.C. Wildlife ! Resources Dept (TLD CNS #236). l C1 4 3 Hwy 274 8, lef t tit. Gallant Rd. (193). I right Homestead Rd. (437) to end, TIA straight ; aeroes intertestion of Twin Lakes Rd. (TLD t CNE #237). ! C1 4 5 Hwy 274 5, lef t !!t. Gallant Rd. (193), right W. Oak Dr. (962) to end at fork. TLD on left et fense (TLD CN8 d238). : D1 3 1 Hwy 274 8 se carter Lumber Co., T!A en fense near gate (TIA CNS #239). ! D1 4 2 Nwy 274 5, right Campbell Rd. (80), left on
- Paraham Rd. (34) to transmission tower en r185t, T!A on brein power pele (TLD CNS #240). S !
D1 3 4 Hwy 274 8, right Campbell Ad (80) for # 't about 3 elles ?!A en left at beginning of , herse fence (TLD CN8 r/261). <
f: c, j l~ 1 , Page a of 5 , l DUKE PCVER CCMPANY CATAV3A hVCLEAR STATION e' HP/0/8/1009/04 ' l ENCLCSCRE S.1 > l ' ' AIR SAMPLER. TI.D. AND WATER SA:fPLE,LCCATIONS i 2:ne & Ridius (M1) 1 Dasertetten
- hy 49 5, right Parsham Rd. (,34) to El 5 2 transmission tower en left siter bridge 1 (TLD CSS 9242).
El 5 3 Hwy 274 N, left Hwy 33, left Kingsberry I!' Ad. f,114) to transmission tower on left (TLD CNS #243). F1 4 1 Hwy 274 N, left Hwy 35 to Bethel School. TLD cn side of small building in back (TLD CSS n244). F1 4 3 Hwy 274 N left on G envista Rd. to Crowder Creek Boat Landing, TLD to East of parking tot (TLD CNS d245). 32 8 1 Hwy 49 N, right Carowinds Blvd. (1441), left Choate Cir., TLD on inside of fence left of tha guardhouse (TLD CNS #244), 31 3 '1 Nwy 49 N, right Hwy 160, right Tesa Cay sign (94), right before Tega Cay entrance into Duke Power Company substation (TLD - CS8 0212). 32 7 4 Hwy 49 N, right Hwy 140 to Fort Hill, right Lee St., left Self St., TLD at Fort Hill Hunicipal Water Supply behind
$prings Hill (TLD CNS 9267).
C2 7 3 Hwy 274 5, right on Herlong Ave. to Piedmont Hedical Center emergency entranse to beek of hospital. TLD on fense at back right earner of Liquid Onyson storage area (TLD CN8 #244). C2 10 3 Hwy 274 5 to Nwport, left at stop light, right on Rawlinson Rd., left Hwy 3 right on Neckte 31vd. (901) to end, left on Hwy 12, ri Wayne'ght s AutoonServise, dirt roads. just to Duke aeroes from Power r t company Substation (TLD CNS #217). C2 4 6 Nwy 274 8, lef t Hwy tel, right Rawlinson Rd. (34), left Nwy 3 to Rock Mill Career .
- Development Center, TLD in tranesission tower (TLD CNS 4:49).
*, q l
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_ _ _ _ . _ . . _ _ _ _ . _ _ _ _ _ . . . . _ _ _ . . _ . _ _ . _ _ _ _ _ _ _ _ . . _ _ . _ _ _ _ . . . _ _ _ _ _ _ _ _ _ _ ___.____.___._____.m. _ . _ _ . _ . . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ . . _ _ _ . . . . _ _ _
I Page 3 of 3 DUKE PCWER CCMPANY
- CATAVBA NUCLEAR STATICN .-
H?.'0 / 3 /1009 / Ca 1 INCLCSURE 3.1 j AIR SAMPLER, T*.D.
. AND WATER SAMPLE LOCATIONS 2cne & Radius (Mi,) No. Descriotien -
D2 10 a Hwy 274-S. right Ca pbell Rd.,(dC), left
, Hwy 49-S, left Rd. 64, left Hwy 3. Go to Duke Pcwer Company appliance Center on f left. TLD on fence in back (TLD CNS #250). .
E2 10 2 Rwy 35 into C1over, TLD at Duke Power Company Appliance Center in rear lot on inner fence (TLD CNS #251). Water Samole Locations I < F3 14 4 Hwy 27a-N, right Pole Branch Rd. (279), right Hwy 273 into Belmont, right Catawba St., left at next light to Belmont Municipal Water Supply (Water CNS #213). C2 7 2 Hwy 274-S, left Hwy 161, right Mt. Gallant Road (193) to end. Rock Hill Municipal . Water Supply across intersection on left (Water CNS #214). j 32 7 6 Hwy 49-N, right Hwy 160 to Fort Mill, right Lee St., left Self St., go to Fort Mill Municipal Water Supply behind Springs Mill (Water CSS #213). A0 1 46 Left exiting Steam Production entrance on-Concord Rd., left just after canal bridge. Go to pier (water CNS #208, need key). 31 4 5 Hwy 49-N, right Ewy 160, right Dam Rd. (99), left Gray Rock Rd. (251) to Lake Wylie Dam. Walk through plant to upstream side of the dam (water CNS #211). 31 4 6 Hwy 49-N, right Ewy 160, right Dam Rd. (99), left Gray Rock Rd., (251) to Lake Wylie Dam. Ride or walk to river access on downstream side of dam. C2 7 8 Ewy 274-S left Mt. Gallant Rd. (193), left Hwy 161, left Cherry Rd. (Hwy 21), left on dirt road at Fort-Rock Drive-In to end, go right to Rock Hill Municipal water intake. A1 4 6 Hwy 49-N, left at Camp Steere sign after crossing Buster Boyd Bridge (Water CNS #215). t6 ~ ( - y I
Page 1 of.1 a
~
CCKZ FCWER COMPANY CAT.*N?A NCC*. EAR STAT:C!' HP.0/L,1039/01 ESCLCSCRI 5.2
- ! ILK S.U!?LE LOCAT* CSS -
22p,g Radi:s (Mil '! ilk - D1 6 M Hwy 274-S, right Kwy 161, left Rd. 1080 to ' Pursley Dairy. D2 8 M Hwy 274-S, right Hwy 161, left Scism Dairy and Equipment Co. (CASE sign). E2 6 M Hwy 274-N, left Hwy 55, left Clinton Dairy Rd. F1 3 M Hwy 274-N, right Lake Wylie Rd. (1099) to first house on left, (Ingram Richmond residence). F2 7 M Hwy 274-N, Kwy 55, right Paraham Rd. (34), left Hwy 557. Barnett Dairy 1 mile on left. D1 7 M Hwy 274-S to Newport, left at stop light, right Adnah Church Rd. (81). Woods Dairy 1.5 miles on.left. _ F2 13 M Hwy 274-N, left Hwy 55, go through Clover,5C. Right on Lloyd White Rd. (143), left on Crowders Creek Rd. (1103), next paved right (1125). Cates Dairy is half mile on left. 1 3 6
.N '6-v* *e F
Page 1 of 10 EUKE PCVER COMPANY ~ CATAW3A NUCLEAR STATICN . EP/0/3/1009/04 E.';CLOSCRE 5.3 PREDETERMINED SAMPLING LCCATIONS Radius (Mi) Zcne No. Descrietien A0 1 1 Hwy 274-N, right Liberty Hill.Rd., right in fork to end (TLD & Air CNS #200, need key). A0 1 2 Hwy 274-N, right Lake Wylie Rd. (1099), right at Hudson Rd. fork, right at Commodore Pl. fork, left on Tioga Rd. to end. A0 2 3 Hwy 274-N, right Lake Wylie Rd., (1099), lef t fork after paveoent ends, .on Hudsen Rd. to end. A0 2 4 Hwy 49-N, right Pleasant Hill Rd. (1109), right Youngblood Rd. (1102) to dead end at Catawba Yacht Club. A0 1 5 Left exiting Steam Production entrance on Concord Rd., left on Old Concord Rd..'righ't on Acacia Rd., left on Crepe Myrtle Rd., left on Blue Bird Ln. through gate to and (TLD & Air CNS #201, need key). A0 1 6 Hwy 49-N, right Pleasant Hill Pd. (1109), right Youngblood Rd. (1102), left on Snug Harbor Rd. (1357), right Coze Cove Rd. (1434) to end. A0 2 7 - Hwy 49-N, right Pleasant Hill Rd. (1109), right Youngblood Rd. (1102), to intersection of Snug Harbor Rd. (1357). A0 1 8 Left exiting Steam Production entrance on Concord Rd., left on Old Concord Rd., right on Acacia Rd., left on Crepe Myrtle Rd. Go to first drive on right past Paradise Pl. , TLD across road (TLD CNS #202). A0 1 9 Hwy 49-N, right Pleasant Hill Rd. (1109), right Youngblood Rd. (1102), left Snug Harbor Rd. (1357) to end. i A0 2 10 Hwy 49-N, right Pleasant Hill Rd. (1109), right Youngblood Rd. (1102), left Snug l Harbor Rd. (1357), stay on Snug Harbor at I Kalabash ',Rd. Fork, take first gravel left . (Crosshavens Dr.) after fork to the end , (, (Beware of dogs). v v ~ w -w ~
Page 2 of 10 , LUKE PCWER COMPANY
- i CATX4BA SUCLEAR STATION -
l HP/0/3/1009/04 ESCLCSURE 3.3 PREDETERMINED SAMPLING LOCATIONS Zone Radius (Mil & Descristica
~
A0 1 11 Left exiting Steam P cduction entrance on Concord Rd., left on Old Concord Rd., right on Acacia Rd., left on Crepe Myrtle Road. TLD is .1 miles on left in curve (TLD CNS ,
#223).
A0 1 12 Hwy 49-N, right Pleasant Hill Rd. (1109),
-right Youngblood Rd. (1102), left McKee Rd (1100), right Bankhead Rd. to end.
A0 2 13 Hwy 49-N, right Pleasant Hill Rd. (1109), right Youngblood Rd. (1102), left McKee Rd. (1100), right Bankhead Rd. to intersection of Bessbrook Rd. A0 1 14 Left exiting Steam Production entrance on Concord Rd., left on Old Concord Rd., right on Acacia Rd. TLD .2 miles on right (TLD CNS'#224). A0 1 15 Left exiting Steam Production entrance on Concord Rd., take first dirt fork to left on Kingsberry Dr., Stop at Commodore Yacht Club. A0 1 16 Left exiting Steam Production entrance on Concord Rd. to last big curve before pave-ment ends. A0 1 17 Left exiting Steam Production entrance on Concord Rd. to first transmission tower on left'after bridge (TLD CNS #225). A0 1 18 Left exiting Steam Production entrance on Concord Rd., go to end and turn right on Sandlapper Rd. Stop at transmission tower. A0 2 19 Hwy 274-S, left Allison Creek Rd. (1081) to end of pavement. A0 2 20 Left exiting Steam Production entrance on Concord Rd. TLD on left across bridge, just past fence (TLD CNS #226). A0 1 21 Left Hwy 274-S, left Allison Creek Rd. .
- (1081), left Spratt Rd., to end (Beware'of q l dogs).
A0 2 22 Hwy 274-S, left Allison Creek Rd. (1081) to i intersection of Bardale Rd. - I
Page 3 of 10 CCKE PC'iER COMPANY CATA'43A NUCLEAR STATICN . HP/0/3/1009/04 .- ENCL::SURE 3.3 FREDE"'ERMINID S.dPLING LOCATICNS Zone Radius (Mi) & ::escriotien A0 1 23 Left exiting Steas Production entrance en Concord Rd. TLO cn left at beginning of
' guardrail posts (TLD CNS #:'CA).
A0 1 24 Hwy 274-S, left Allisen Creek Rd. (1081), left at Spratt Rd., left Morrison Rd., then right in next 2. forks, left in next fork to end. A0 2 25 Hwy 274-S, left Allison Creek Rd. (1081), to intersection of Spratt Rd. A0 1 26 Behind Catawba Nuclear Station overlock (TLD and Air CNS #205, need key). A0 1 27 Right exiting Steam Production entrance on Concord Rd., first dirt left on Valelake Rd., left in fork to end. A0 2 28 Hwy 274-S, left.Allison Creek Rd. (1081) to intersection of Colina Rd. A0 1 29 Left exiting Steam Production entrance on Concord Rd. TLD at Shady Shore Dr. on right corner at Bethel Community Clubhouse sign (TLD CNS #227). A0 1 30 Right exiting Steam Production entrance on Concord Rd., first dirt left on Valelake Rd., right in f.ork to end. A0 2 31 Hwy 274-S to intersection of Campbell Rd. (80). A0 1 32 Right exiting Steam Production entrance on Concord Rd. TLD at first dirt left (Valelake Dr.) on right corner (TLD CNS #228). A0 1 33 Right exiting Steam Production entrance on Concord Rd., left on dirt road (Pine Pt. Dr.) just before Granny's Restaurant, stop
.5 miles.
A0 2 34 Hwy 274-S to Big Allison Creek bridge. A0 1 35 TLD on top of hill at intersection of Catawba Nuclear Station Construction entrance and Road 1132 (TLD CNS #206). , A0 1 36. Right exiting Steam Production entrance to ' ' transmission line just before Granny's % Restaurant on Concord Rd. (1132). . l
i e Page 4 of 10 , DUKE PCWER CCMPANY CATAW3A NUCLEAR STATICN .' HP/0/B/1009/04 ENCLCSURE 5.3 FREDETE2 MINED SAMPLING LCCATICNS 2cne Radius Ofi) A N Descriction A0 2 37 Hwy 274-N, left Liberty Hill Rd., take first left and go to end. A0 1 38 Hwy 274-N, right at Liberty Hill Rd., right in fork to third transmission line on right, walk about 200 yds. South along boundary fence. TLD is on fence (TLD CNS #229). A0 1 39 Hwy 274-N, right at iL'berty Hill Rd., right in fork to third transnission line on right. A0 2 40 Right exiting Steam Production entrance on Concord Rd. to end. Right on Hwy 274-N for 1 mile. A0 1 41 Hwy 274-N, right at Liberty Hill Rd., go .8 miles (right in fork), TLD on fence on right (TLD CNS #207). A0 1 42 Hwy 274-N, right at Lib,erty Hill Rd., right
~ . in fork, go to softball field en, trance.
A0 2 43 Hwy 274-N, right Lake Wylie Rd. (1099), right Beaver Creek Trail to end. A0 1 44 Hwy 274-N, right at Liberty Hill Rd., right in fork, pass softball field to large rock piling on fence. TLD is on fence (TLD CNS
#222).
A0 1 45 Left exiting Steam Production entrance, left on Old Concord Rd. to end. TLD on fence on left (TLD CNS #203). A0 1 46 Left exiting Steam Production entrance on Concord Rd. Turn left just after canal bridge. Go to pier (water CNS #208, need key). Al 3 1 Hwy 49-N to NC side of Buster Boyd Bridge. Al 4 2 Hwy 49-N to intersection of Pleasant Hill Rd. (1109), TLD on trensaission. tower (TLD . I CNS #232). ,, 3 A1 5 3 Hwy 49-N to Steele Creek Vol. Fire Dspt. on '6 right. ! l v ~ - -
Pa;e 5 of 12 , DUK PC.'4ER COMPANY CATAW3A NUCLIAR STATION J a HFf0/3/1CG3/C-INCLOSURE 5.3 PREDEE R'!!NED SAMPLING LCCAT 0SS "cne Radius (Mil No. Descrietion Al a a Ewy 49-N, right Pleasant Hill,Rd fl109), right Youngolood Rd. ( *.10 2 ) , left Ocar Rd. (1105), right inomas xd. (1104, TLD behind second house on right in pines (TLD CNS ,
#233).
A1 5 5 Hwy 49-N, right Pleasant Hill Rd. (1109, right Youngblood Rd. (1102), left Hamilton Rd. (1106) to intersection of Hwy 160. A1 4 6 Hwy 49-N, left at Ca=p Steere sign after crossing Buster 3cyd Bridge (Water CNS ;)215). A2 10 1 Hwy 49-N, stop one mile past Westinghouse Blvd. at Roberts Systems 8500 on left. A3 10 1 Hwy 49-N, right Carowinds Blvd. (1441), left Ewy 51 to Pineville, stop near Sugar Creek bridge. 31 3 1 Hwy 49-N, right Hwy 160, right on Gold Hill Rd. (98) at Tega Cay sign, right before Tega Cay entrance on gravel road into Duke Power Company substation (TLD & Air CNS #212, need key). B1 2 2 Hwy 49-N, right Pleasant Hill Rd. (1109), right Youngblood Rd. (1102), lef t !!cKee Rd - (1100)., left Bankhead Rd., left Bessbrook Rd. to end. 31 4 3 Hwy 49-N, right Hwy 160, right on Das Rd. (99), last gravel right in sharp curve before Lake Wylie Dam, left through fence to substation, TLD on right of inner substation fence (TLD CNS f)235). B1 2 4 Hwy 49-Nj right Hwy 160, right on Gold Hill
- Rd. (98) at Tega Cay sign, enter Tegs Cay following Tega Cay Dr., right Windjammer Dr., ", -) ;
{ 6 miles, Right at circle, Left Kiwi Point '6 - 1 to end. "' i i
t
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Page o of 10 DUKE POWER COMPANT CATAWBA NUCLEAR STATICN _ HP/0/3/1009/04 INCLCSCRE 3.3 r.uarirRMINED SAMPLING LCCATICNS
~ena Radius (Mil No. Descristica .
31 4 5 Hwy 49-N, right Hwy le0, right Cam Rd. (99), left Gray Rock Rd. (251) to Lake Vylie Dam. Walk through plant to upstream side of the dam (water CNS #211). 31 4 6 Hwy 49-N, right Hwy 160, right Dam Rd. (99), left Gray Rock Rd. (251) to Lake Wylie Dam. Go to river access en downstream side of dam. B2 8 1 Hwy 49-N, right Carowinds Blvd. (1441), left Choate Circle, TLD cn inside of fence left of the guardhouse (TLD CNS #246). 32 4 2 Hwy 49-N, right Hwy 160 to Home Federal Savings and Loan on left. TLD on left rear corner of building (TLD CNS #234).
~ 32 5 -
3 Hwy 49-N, right Hwy 160, left on Gold Hill Rd. (98) at Home Federal Savings and Loan, stop at intersection of Whitley Rd. , 32 10 4 Hwy 49-N, right Carowinds Blvd. (1441), left Hwy 51 to Pineville, right Hwy 521 (Polk St.) in Pineville, right on Dorman Rd., stop at state line. 32 5 5 Hwy 49-N, right Hwy 160, right Sutton Rd. (49) to intersection of Gray Rock Rd. (251). 32 7 6 Hwy 49-N, right Hwy 160 to Fort Mill, Right Lee St., left Self St. TLD at Fort Mill Municipal Water Supply on right behind Springs Mill (TLD CNS #247, also Water CNS
#213).
32 10 7 Hwy 49-N, right Hwy 160 through Fort Mill to the Sugar Creek bridge. C1 4 1 Hwy 274-S, left Mt. Gallant (195), left India Hook Rd. (30) to SC Wildlife , Resources Dept. (TLD CNS #236). *
.s ~1 Cl 5 2 Hwy 274-S, left Mt. Gallant Rd. (195), go . ^
beyond India Hook to Red Burketts Body Shop ,- 3 on right.
P3;s 7 of 10 D!,TJ. PCWER COMPANY a CATAW3A NUCLEAR STATION .- HF/0/3/1009/CL ESCLCSURE 3.3 FREDETERMINED SAMPLING LCCATIONS Cone Radius (Mil No. Descri tion - 01 4 3 Hwy 274-S, left Mt. Gallant Rd. (195), right Mc=estead Rd. (657) to end. TLD straight across intersection of Twin L'akes Rd. (TLD CNS 1237).
- C1 5 4 Hwy 274-S, left Mt. Gallant Rd. (195),
right Homestead Rd. (657) to end. C1 4 5 Hwy 274-S, left Mt. Gallant Rd. (195), right W. Oak Dr. (962) to end at fork. TLD on left at fence (TLD CSS #)238). C1 5 6 Hwy 274-S, left Mt. Gallant Rd. (195), right at York County Museum (653) to end at SC Nat nal Guard Armory. C1 5 7 Hwy 274-5 to Carter Lumber Co. C2 10 1 Hwy 274-S, left Hwy 161, left La fork on _ , Celanese Rd. (50) to intersection of Springdale Rd. C2 7 2 Hwy 274-S, left Hwy 161, right Mt. Gallant Rd. (195) to end. Go to Rock Hill Municipal Water Supply across intersection on left (Water CNS #214). C2 7 3 Hwy 274-S, right on Herlong Ave. to Piedmont Medical Center emergency entrance to back of hospital. TLD on fence at back right corner of Liquid Oxygen storage area (TLD CNS #248). C2 10 4 Hwy 274-S, left Hwy 161, right Mt. Gallant Rd. (195), right Hwy 21-121 By pass to Fast Fare on left at intersection of Springstaen Rd. C2 10 5 Hwy 274-5 to Newport, left at stop light, right on Rawlinson Rd. , left Hwy 5, right on Heckle Blvd. (901) to end, left on Hwy 72, right on dirt road across from Wayne's Auto Service. Go to Duke Power Company , substation (TLD & Air CNS #217, need key).
.s '1 i C2 8 6 Hwy 274-S, left Hwy 161, right Rawlinson '
., Rd. (56), left Hwy 5 to Rock Hill Career ' - l Development Center, TLD on transmission ~ l tower (TLD CSS #249). ! l I
)
Page S of 10 DC'G PCWER COMPANY - CATAWEA NUCLEAR STATION - HP/ 0 '3 /1C09/Ca ISC'_CSCRE 5.2 PREDETIr!INID SA'!PLING LOCATIONS Cene Radius (Mi'. & Descrittica 02 10 7 Hwy 274-3, left Hwy 161, right Adnah Church Rd. (51), right on Hwy 5, left on Eas: view Rd. (102) to intersection of Oak Park Rd. (103). C2 7 8 Hwy 274-S, left Mt. Gallant Rd. (195), lef: Hwy 161, left May 21, left on dirt road at Fort-Rock Drive-In to end, go right to Rock Hill Municipal Water Intake. D1 5 1 Hwy 274-S to Carter Lumber Co. TLD on fence near gate (TLD CNS !)239). D1 4 2 Hwy 274-S, right Campbell Rd. (80), left Paraham Rd. (54) to transmission tower on right, TLD on power pole (TLD CNS (!240). D1 5 3 Hwy 274-S, right Campbell Rd. (80), left Parsham Rd. (54), next right on Rd. 315 to _ Allison Creek bridge. D1 5 4 Hwy 274-S, right Campbell Rd. (80) for about 3 miles, TLD on left at beginning of horse fence (TLD CNS (1241). D2 10 1 Hwy 274-S, left Hwy 161, right Adnah Church Rd. (81), right Hwy 5, quick left on Eastview Rd. (102), right Holland Rd. (157), right Turkey Farm Rd. (1172), left Russell Rd. (536), go .2 miles. D2 10 2 Hwy 274-S,'left Hwy 161, right Adnah Chruch Rd. (SI), right Hwy 5, left Billy Wilson Rd. (1451), right Turkey Farm Rd. (1172) to Fishing Creek bridge. D2 10 3 Hwy 274-S, right Campbell Rd. (80), left Hwy 49-S, stop at Pantry before entering York. D2 10 4 Hwy 274-S', right Campbell Rd. (80), left .
- l Hwy 49-S, left Rd. 64, left Hwy 5. Go to *,,
._ q I Duke Power Company Appliance Center on ,
left. TLD on fence in back (TLD CNS #250). %_ l 1 l
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Page 9 of 10 . DUKE PCWER C011PANY '_ CATAW3A NUCLEAR STATICN HP!0/3/1009/04 ENCLCSCRE 5.3 PREDETER.'1INEC S.C!PLING LOCATICNS n3 Eadius ("fi & Description 22 10 5 Hwy 274-S, right Cacpbell Rd. (30), ' aft . 49-S, right Old Limestene Rd. (172) to end. El 5 1' Hwy 274-S, right Campbell Rd. (30) to intersection of Hwy 49. El 3 2 Hwy 49-S, right ?arsham ?.d. (54) to transmission tower en left after bridge (TLD CNS :)242). El 5 3 Hwy 274-N, left Hwy 35, left Kingsberry Rd. (114) to transmissien tower en left (TLD CNS 1243). El 5 4 Hwy 274-N, left Hwy 55 to intersection of. Kingsberry Rd. (114). i E2 5 1 Hwy 274-S, right Campbell Rd. (80), right Paraham Rd. (54) to intersection of
~
Dr. Nichols Rd. (319). E2 10 2 Hwy 274-N, left Hwy 55 into Cicver, go to Duke Power Company Appliance Center en left. TLD on fence in back (TLD CNS i):51). E2 10 3 Hwy 274-N, left Hwy 35 to Pantry at intersection of Hwy 321 in Clover (behind Pantry). F1 4 1 Hwy 274-N, left Hwy 35 to Bethel School. TLD on side of small building in back (TLD CNS :)244). F1 5 2 Hwy 274-N, left Hwy 55, right Bethel School Rd. (152) to intersection of Hollandale Dr. F1 4 3 Hwy 274-N left on Glenvista Rd. to Crowder Creek boat landing, TLD to east of parking lot (TLD*CNS #245). . F1 4 4
.* 9 Hwy 49-N to River Hills Plantation rear ,
entrance at Robinwood Rd. TLD behind green building on right corner (TLD CNS d230). -
, 99 v
P
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Page 10 of 10 . DUKE PCWER COMPANT . CATAWBA NUCLEAR STATION HP/0/3/1009/04 ENCLCSCRE 3.3 PRIDEHRMINED SAMPLING LOCATIONS
~ *cna Radius (MiT No. Descristien F1 3 3 Hwy 49-N, left Sherer Church Rd. te end.
F1 4 6 Hwy 49-N to River Hills Plantation entrance guardhouse (TLD CNS #231). 4 F1 5 7 Hwy 49-N, left Montgomery Rd. at the River Rat Restaurant. Stop in horseshoe curve near lake. F2 10 1 Hwy 274-N, left Hwy 537, right Ridge Rd. (27) to Bowling Green Presbyterian Chruch. F2 3 2 Hwy 274-N, left Hwy 557 to Pine Greve Baptist Chruch. F3 10 1 Hwy 274-N, left Hwy 557, next paved right on
-^
Oakridge Rd. at Bethel Fire Dept. (Rd. 435) to intersection of Hwy 274 (in NC). F3 10 2 Hwy 274-N, right Pole Branch Rd. (279) to Friendship Baptist Church on left. ! F3 10 3 Hwy 274-N, right Pole Branch Rd. (279), right Hwy 273 to Allen Steam Plant Bridge. F3 14 4 Hwy 274-N, right Pole 3 ranch Rd. (279), right Hey 273 into Belmont, right Catawba St., left at next light to Belmont Municipal Water Supply (Water CNS #218). s O h m% v ) G
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_ __ _ _ _ _ ~ _ _ - _ . . . Page 1 of 1 , DUKE PCWER COMPANY
~
CATN43A SUCLEAR STATICN
- HP/0/ 3/1009 /01.
INCLCSURE 3.1 FIELD MONITORING DATA SHEET 1 Date Team Members / Call Sign / Inst. Type /No, / - Smear Sample Location Time Survey Taken Dese Rate (mR/hr) Activity (CCPM) , 4 9 i
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Pa;e 1 of 1 "CKZ PCWER C0!!PANY
- CATA'43A NUCLEAR STATICN .'
liP/0/3/1009/04
- ENCLOSURE 3.5 SE!PLE TIME RIOUIRED FOR MINIMC1 SAMPLZ VOLUME FLO'i RATE MI.NIMC1 RI;CIRED SX1PLING TIME IN !!INL'"ES CT:1 LPl!
.5 = 14 ...... ...... . . . . 71 1.0 = 28 . . . ...... ........36 1.5 = 42 . . ..... . . . . . .. .. . . 24 2.0 = 36 . . . .... . .. ... . . . . 18 2.5 = 70 . . ... . ...... . .. . . 15 3.0 = 54 . . ... . ... . . . .. . 12 3.5 = 99 . . . ... . ........ . 11 4.0 = 113 . . . ...... ... . . . . . . 9 4.5 = 127 . . . . . . . ...... .. . . . S NOTE: When estimating time required to get a minimum volume of 1 x 10' mi if flow rate for the air sampler in use is not on table, go to next Lower flow rate. The LPM are rounded off to the conservative side.
i Example: Air Sampler flow rata = 106 LPM. Minimum time 11 minutes l'
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l J l DUKI PGWER COMPANY Pago_1 of 2 CATAW3A NCULIAR STATION , HP/0/B/1009/04 . ENCLOSURE 5.6 .-
?! ELD MCNITORING TEAM WCRK SHEET FCR DETIRMINING ICDINE AC*IVITI Team Members Date Air Sa=pler No.
Team Call Sign Canberra No. AIR SAMPLE !NFORMATION ANALYSIS RESCLTS" A B C D E F Sample ID. Air Sampler Flow Rate Iodine Activity Dese Rate Results l No./ Time / Location Run Time (Min) (LPM) :licrocuries/ml mrem /hr Reported By:
/ /
! / /
/ / / / / / / / / /
([ / /
/ / / / ; / / / / / /
t
/ / / /
1
/ / / /
I' Column A) Number of sample / Time it was Taken/ Sampling Location (ex. A0-2-10). Column B) Length of time the air sampler ran.
. Column C) Air sampler meter flow rate.
Column D) Activity from Canberra. , Column E) Dose rate from ';anberra.
- Column F) Signature of person that calls in results to E!C. ' 9 "
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) h 49
CUIS PCVER COMPANY Page 2 of 2 CATAWBA NUCLEAR STATION HP/0/3/1009/04 : ENCLCSURE 5.6 OPERATCR GUIDELINES .' 3.6.1 !!CA a .d Detector Set-Up 5.6.1.1 Disconnect DC pcuer cord from unit. . 5.6.1.2 Turn the contras switch ca the front of the uni: clockwise to the ON =ede. 2 5.6.1.3 Place sample holder with Na-22 check source onto the detector. 5.6.1.4 Press TEST SYSTE!!. . 3.6.1.5 Press ENTER to begin test. 5.6.1.6 If test failed, press CLEAR ENTRY and re=ove the instrument from service. 5.6.1.7 If test passed, press ENTER. 5.6.2 Collecting and Steasuring Filter Cartridges NOTE: Record da:a on Field Monitoring Team Work Sheet for Determining Iodine Activity (Sample Enclosure 5.6). 5.6.2.1 Press ANALYZE FILTER SAh!PLE. 5.6.2.2 Press ENTER. s. 5.6.2.3 For each sample: 5.6.2.3.1 Place cartridge with the recognizable side toward the detector (in small poly bag) in sample holder. 5.6.2.3.2 Put detector and sample holder in shield. 5.6.2.3.3 Press ENTER to accept ID number. 5.6.2.3.4 Press ENTER to accept current Flow Rate (LP!!). Otherwise, change number and press ENTER. 5.6.2.3.5 Press ENTER to accept current Flow Time (min). Otherwise, change number and press ENTER. 5.6.2.-3.6 If the volume is determined to be :co small, resample, press ENTER and return to Step 5.6.2.3. 5.6.2.3.7 Press ENTER to start Collect / Analyze. 5.6.2.3.8 Report / Record Iodine activity (uCi/ml) and dose race (mrom/hr). 5.6.2.3.9 Press NENT SA'!PLE. q 5.6.2.3.10 Label the cartridge and retain for la:ar analysis. '6-
'J ,
3.6.3 After sampling completion, turn the contract switch counter-clockwise to . the STAND-3Y mode-
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Primary: C. V. Wray f[kIJj _$ . .I[ ,,.,, . ..
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Alternates: R. L. Rivard Qf,, .
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J. E. Threa.. "'2.:,f. . . .. V. ' . ' .. S. .' $ I i'g'. .. ' ' ,; ' N ~.~ w . '.
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TSC Radio Opersecrs: }>., ? .",.-+, #-if. : , . ,' ..3-,.
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T. W. O'Donohue
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Field :!anitoring Teams: All Health Physics personnel with Field ?!onitoring Training. ( .. s g 9
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Page 1 of.1 DC'G PC'4ER CO)!PANY
- CATAk"dA NUCEAR STATION .
HP/0/3/1009/01 ENCLOSURE 3.3 E!:ERGENCY VEHIC ES The two designated emergency vehicles are the Operatiens pick-up truck and the - Technical Services vehicle used pri=arily by Chemistr*f. These .-- vei -les _ are to be obtained (as directed by the E!C) by getting, the keys :rpo co front desk Security Officer. A set of all keys to station vehicles shall be maintained by Security at the Personnel Access Portal (PAP). Obtain any other Station vehicles (if availabie) as directed by the Dh. Voluntary use 'of personnal vehicles is another alternative' that may be considered. ( ~% L . a h l 6
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CATAWBA NUCLEAR STATION DIRECTIVE 3.8.4 (TSi REV. NO. 7 DATE di-/"bTb ; AP?ROVAL / /w) i
,f " i /
DUKE P0kT.R C .! PANT . CATAk'3A NUCLEAR STATICS CNSITE EMERGENCY ORGANIZATIOS 1.0 PURPOSE To define the role of the Emergency Coordinator and other members of the Onsite Emergency Organization in implementing the station Emergency Plan and to provide for augmentation of the normal operating shift during an emergency situation.
2.0 REFERENCES
2.1 Catawba Nuclear Station Emergency Plan 2.2 Catawba Nuclear Station Operations Management Procedure 1-8,
" Authority and Responsibility of Licensed Reactor Operators and Licensed Senior Reactor Operators" 2.3 Station Directive 2.8.1 (TS) " Reporting Requirements" 2.4 Catawba Nuclear Station Operations Management Procedure 2-15 " Notification of Proper Authority".
2.5 Station Directive 3.0.7 (TS), Site Assembly / Evacuation. 3.0 SPECIFIC RESPONSIBILITIES i 3.1 Shift Supervisor - All emergencies are initially handled by the , Shift Supervisor. The Shift Supervisor on duty will ensure that all immediate actions required by station emergency or abnormal procedures, applicable to the situation, are performed and that all actions necessary for the protection and safety of personnel and property are being taken. - 3.2 Emergency Coordinator - The Shift Supervisor shall assume the function of the Emergency Coordinator until the arrival of the Station Manager or his designee at which time the functions of the Emergency Coordinator are transferred to the Station Manager or his designee. The Shift Supervisor shall then continue to take actions necessary to ensure that the emergency situation is brought under control. ' 9
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3.3 Recovery Manager - The responsibili. ties of the Emergency Coordinator - i will be assumed by the Recovery Manager at the Crisis Management .
-- - , - - - - - w w , m
Csnter (CMC) as this organization is staffed a..d ready to assume its function. This assumption of the Emergency Coordinator functions by , the Recovery Manager, will take place for the Site Area Emergency ,- and General Emergency classifications. - The 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 DUTIES _. a.1 Shift Supervisor / Emergency Ccordinator - i= mediate duties include the following: 4.1.1 Determine from the initiating conditions what Emergency Class the Station is in. 4.1.2 Declare the Emergency as necessary and assume control as the E=ergency Coordinator. 4.1.3 Assign someone from the shift to begin the notifications as per applicable procedure. 4.1.4 Take necessary on site remedial actions. 4.1.S Initiate activitation of the Technical Support Center and Operations Support Center. 4.1.6 Providing protective action recommendations to authorities responsible for implementing offsite emergency measures. NOTE: This authority and responsibility shall not be delegated to other elements of the station emergency organization. 4.2 Station Manager / Emergency Coordinator - 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. 4.2.2 Instituting those procedures necessary to allow the Control Room to gain .immediate control of th* emergency situation. 4.2.3 Notification and activation of Crisis Management Team, county and state organizations and the Nuclear Regulatory Commission. 4.2.4 Providing protective action recommendations to authorities responsible for implementir.g off-site emergency measures. +
.s ~1 NOTE: This authority and responsibility shall not be ,
delegated to other elements of the station 'L- ,1 emergency organization. l 1
--- - _ . . _ . . , ~ , . - - - , , - - - - _ _ . . - -- - - - , -
Continusd maintencnco of an adequate state of snergency 4.2.5 preparedness until the emergency situation has been , effectively managed and the station is returned to a normal l or safe operating condition. ,. 4.3 Technical Support Center Staff - The Technical Support Center (TSC). location shown in Enclosure 4, will be activated and staf fed to support the control room and coordinate emergency and/or recovery efforts with offsite groups, corporate headquarters, state and - local government and the NRC. The station operating staff .. s used as the TSC staf f in the emergency situatten as deemed necessary by the Emergency Coordinator. Individuals with a TSC function will have a routine function that is similar to their role in an emergency. 4.3.1 Operations Group: A. The Suoerintendent of Oeerations when designated, shall assume the duties of the Station Manager. He will provide expertise to the Station Manager and the Shift Supervisor regarding solutions to operational problems. He shall ensure that each 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 expertise to other members of the TSC and shall work closely with the Superintendent of Maintenance in restoring station equipment to an operational statua during and after the emergency condition. This individual shall be the . s first alternate to the Emergency Coordinator in the event the Station Manager is unavailable. B. The Operatina 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 and other members of the TSC as required and maintain contact with the Operations Supervisor in the Operations Support Center (OSC). 4.3.2 Technical Services Group: A. The Superintendent of Technical Services shall assume the duties of the Station Manager when so designated.
- He will provide expertise to the Station Manager and .+ 9 i
the Shift Supervisor (via the Operating Engineer) . l l l l
I rogsrding solutions to operational problems. He shall provide technical expertise to other members of the J TSC in the areas of Health Physics. Chemistry. Performance ' ] and Reactor Engineering and in Licensing and Engineering ' support progra=s. 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 alternate to the - Emergency Coordinator in the event the Station , Manager is unavailable. S. The Health Physics Section of the TSC
- 1. The Station Health Physicist shall assume the duties of the Superintendent of Technical Services when so designated. He will provide technical expertise to the Superintendent of Technical Serviccs, the Station Manager and other members of the TSC as required. He will provide for the calculation and distributin of offsite dose determinations for releases of radioactive materials to the atmosphere and make recommendations to the Station Manager through the Superintendent of Technical Services on Protective Actions necessary for limiting exposure to station personnel and members of the public. He shall also be responsible for directing decontamination activities. The Station Health Physicist shall
- also work closely with the appropriate members of the Crisis Management Center to assure that radiological hazards during any emergency situations are minimized. The Station Health Physicist shall ensure that all areas under his direction are staffed and prepared to manage Health Physics support for any emergency condition.
- 2. Health Physics S&C Coordinator shall coordinate and direct the actions of in plant radiological monitoring teams and provide data on plant radiological status.
- 3. H. P. Support Coordinator shall direct the actions of the remainder of the Health Physics functions.
- 4. Data Analysis Coordinator shall provide for the calculation and distribution of Off-site Dose projections and field monitoring information assessable by Health Physics personnel and relay this to the Station Health Physicist. .
.+ 9 ^
se I I
The Data Analysis Coordinator shall also direct ' the Field Monitoring Coordinator as necessary . l to evaluate dose projections versus field data. ,
- 3. yield Monitoring Coordinator shall direct the actions of the field monitoring teans in gathering. both on-site and of f-site radiological data and make this inforqation available to the Data Analysis Coordinator or Station Health -
Physicist. Constant ec==unications will be maintained by a Radio Coerator or by the use of plant or cc=mercial telephone lines'to the field teams. C. The Station Chemist shall assume the duties of the Superintendent of Technical Services when so designated. He will provide technical expertise to the Superintendent of Technical Services and to other members of the TSC as required. e is responsible for coordinating chemical technical support and for initiating necessary action to ensure adequate chemical sampling and evaluation to support the emergency condition. The Station Chemist shall ensure that all areas under his direction are staffed and prepared to manage Chemistry suppcrt for any emergency condition. D. The Performance Engineer shall assume the duties of the Superintendent of Technical Services when so designated. He will provide technical expertise to ( ' the Superintendent of Technical Services and to other J members of the TSC as required. He will assure that adequate levels of technical and engineering manpower are available to: sanage test procedure review, carryour special test procedures, insure control and accountability of special nuclear materials, and . evaluate plant and reactor performance. A Test Enzineer shall assist the Performance Engineer in the avaiuation of plant systems and transmission of information to the CMC. A Performance Technician (s) 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. l The Performance Engineer shall ensure that all areas under his supervision are staffed and prepared to manage Performance support for any energency condition. E. The Reactor Engineer shall assume the duties of the Performance Engineer when so designated. He will provide technical expertise to the Performance 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 .+ ~1 technical support for any emergency condition. 4 g, l l 1
l F. The Licensing rnd Proiccts Enginesr shall assume the duties of the Superintendent of Technical Services when so designated. He will provide technical expertise to the superintendent of Technical Services I and to the members of the TSC as required. He is responsible for coordinating station activities with regulating agencies, coordinating the reporting and investigation of all incidents and for providing review of appropriate station technical =stters. The . License and Projects Engineer shall ensure that all __ areas under his direction are staffed and prepared to manage technical support for any emergency condition. I G. TSC Lonkeeper shall record events that occur from the time of activation of the TSC and shell be directed by the Emergency Coordinator. This individual will be an engineer from the station's Projects group. , H. Offsite Communicator shall make followup notifications to State and/or County ECC's. This i individual shall be an engineer from the Station's Licensing and Projects Group. 4.3.3 Administrative Group: A. The Superintendent of Station Services when designated shall assume the duties of the Station Manager. He will provide techical expertise to the Station Manager sad to the Shift Supervisor (via the Operating r Engineer) regarding solutions to administrative problems associated with emergency conditions at the station. He shall provide technical expertise to other members of the TSC in the area of Contract Services, Security, Training and Safety, and Administrative Coordination. He shall ensure that all areas under his direction are staffed and prepared to 4 i sanage administrative support for any emergency
< condition. This individual shall be the fourth alternate to the Emergency Coordinator in the event the Station Manager is unavailable.
B. The Security and Contract Coordina:or shall assume the duties of the Superintendent of Station Services when i so designated. He will provide technical expertise to the Superintendent of Station Services and to other l j members of the TSC as required. He is responsible for l coordinating Security and Contract Services for the i station. The Security Chief shall ensure that all l areas under his direction are staffed and prepared to manage Security and Contract Services for any I emergency condition., = C. The Administrative Coordinator shall assume the duties ,, 1 i of the Superintendent of Station Services when so ], designated. She will provide technical expertise to - l 4 l 1
, ~. . . - -, - , - - - , -- -~------,w----..--,-- - - - - - , . - - - , -
ths Superintendent of Station Servicas and to other , memb rs 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 that all areas uncer her directicn are staf fed and ) prepared to manage administrative functions curing any ! emergency condition. I D. The Training and Safety Cecedinator shall assume the l duties of the Superintencent of 5tation.Servicas vnen so designated. She will provice tecnnical expertise to the Superintendent of Station Services and to other members of the TSC as required. She is responsible l for coordinating the- station training and safety ) activities, Fire Protection and Medical Services in support of the emergency organization. The Training and Safety Coordinator shall ensure that all areas under her direction are staffed and prepared to provide needed training and safety evaluations during any emergency condition. 4.3.4 Maintenance Group: A. The Superintendent of Maintenance when designated, shall assume the duties of the Station Manager. He will provide technical expertise to the Station Manager and the Superintendent of Operations regarding solutions to operational problems. He shall provide technical expertise to other members of the TSC in areas of Mechanical Maintenance, Planning, Instrument and Electrical Maintenance, and Materials Support. He will insure 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 third alternate to the Emergency Coordinator in the event the Station Manager is unavailable. B. The Mechanical Maintenance Engineer shall assume the duties of the Superintendent of Maintenance when so designated. He will provide tnchnical expertise to the Superintendent of Maintenaace and to other members of the TSC as required. He is responsible for preventative and actual maintenance for all station mechanical equipment and facilities. The Mechanical Maintenance Engineer shall inture that all areas under his direction are staffed and prepared to manage maintenance support for any e:sergency condition.
.. ~1 I ^ *9 -- , a. c. - - . . - . , a , , ,- .a
- .- _ = . _ - - - _ - _ - ._ .- . - -
C. The Planning Engineer shall assume the duties of the Superintendent of Maintenance when so designated. He , will provide technical expertise to the Superintendent
- of Maintenance and to other memoers 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 supeort 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 responsible for maintaining all station ISE equipment in an operational state. The Instrument and Electrical Engineer shall ensure that all areas under his direction are staffed and prepared to manage I&E support for any emergency condition. ] 4.4 Operations Support Center Staff i 4.4.1 The Operations Support Center (OSC), location shown in i Enclosure 5, shall be activated by the Emergency Coordinator in accordance with the applicable Emergency Procedure. The
.f- OSC 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 OSC shall be under the supervision of a Shift Supervisor or other Operations Group 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. B. Health Physics: A Health Physics Supervisor and five technicians as deemed necessary by the Station Health Physicist. The Health Physics Supervisor shall work closely with the Shift Supervisor in charge and shall maintain contact with the HP S & C Coordinator in the TSC. C. Other station groups as necessary.
- e 4.4.3 In the event that the Operations Support Center becomes ' ~1 environmentally uninhabitable due to radiological or other conditions, the OSC shall move to the rear of the Control '. "'
Room or to other facilities as applicable. ' l ~ t t
5.0 ACTIVATICN CF EMERGENCY ORGANIZATICS 5.1 Phased Activation of T.S.C. Organization , 5.1.1 Selected station personnel are notified of situations . classified is Unusual Events by E=ergency Response Procecure. RP/0/A/5000/02. These individuals shall then respond as appropriate and shall notify any additional pericanel in their orgsni:stion to respond as needed. At - the Alert class or greater. TSC activation is required, ilther full or partial as deemed necessary by.the Station Manager. 5.1.2 To effectively respond to an emergency situation and to - avoid unnecessary personnel from being activated, 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 Phase I). 5.1.3 See Enclosure 6 for Notification Mechanism. 5.2 Phase I of the Technical Support Center 5.2.1 Phase I of the Technical Support Center organization shall be staffed and organized as indicated below or as deemed necessary by the Station Manastr. 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. Station Manager /Esergency 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 Analysis Coordinator I. S & C Coordinator J. Support Coordinator K. Test Engineer 5.2.3 In the event that the Technical Support Center becomes environmentally uninhabitable due to radiological or other conditions and the Control Roon remains secure (habitable). Phase I of the TSC shall move inside the Control Room area. In the event the Control Room also becomes
- uninhabitable due to radiological or other conditions.
- Phase I of the TSC shall move to the Administration .* 9 Building or to other facilities as applicable. .,,
'S
i 5.3 Phaso II of ths Tcchnical Support Ccntor i 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.
f A. Operating Engineer Assistant Operating Engineer
< B. '
C. The Station Chemist , D. The Reactor Engineer - E. Perfor:sance Technician (s)
- P. The Licensing & Projects Engineer
- G. The Mechanical Maintenance Engineer H. The Security & Contract Coordinator I. The Training and Safety Coordinator l i 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 TSC shall move to the
- i i Administration Building or to other facilities as 1
applicable, when directed by the Station Manager. 5.4 other TSC Personnel 5.4.1 Full activation of the TSC is as shown in Enclosure (1). Other personnel not specified as part of the Phase I and .i [- II staff but still necessary for TSC are as indicated below: A. The Administrative Coordinator : B. The Planning Engineer C. Clerks as needed, determined by Group Superintendents l D. TSC Logkeeper E. Radio Operator { 5.4.2 This group shall be activated as soon as practicable. i i i 5.5 OSC Notification 5.5.1 Operations personnel vill be notified by the Operation's Duty Engineer or someone designated either by station phone or home phone as required. > 5.5.2 Health Physics personnel vill be notified by the Station Health Physicist or alternate 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 t*, d _m- , .._r, , , _ - , . . _ r
w..a w i! 3C L .' 4 ..O.+ (dge la Of 14 clerks. Notifica: ion of this individual will be made by the Administrative Coordinator. 6.2 Fecd and beverage will be supplied to :he TSC and CSC as
- appropriate for the :ise of day. Af ter initial staf fing of the TSC and OSC, coffee and snack material vill be provided by the Administrative group. ,
6.3 Station Fire 3rigade y, 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 activitation of the a 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. l ( 6.3.3 The Station Fire Chief or his designee shall also j coordinate and direct the services of any outside fire I departments called upon to assist in fire fighting on l station property, i 6.4 Station Security 6.4.1 The securf y force will have its normal function of ) l l station security in an emergency situation. ,' r 6.4.2 In the event of an emergency requiring activation of the Technical Papport Center Phase I & II, the Security Shift Lieutenant or his designee shall make frequent reports to the Security and Contract Coordinator regarding the status of any security violations, threats or civil disturbances. 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 / Evacuation. 6.5 Evacuation Coordinator 6.5.1 In the event of a site evacuar!? m, the Evacuation Coordinator shall be the ovo245' person in charge at the evacuation site. O
.s ~1 9 -9 }}p> :. .
k A. This position reports to the Emergency Coordinator or his designee for matters pertaining to personnel
~
disposition, and status of the evacuation. ,
~ ~
- 3. All evacuated supervisory personnel will in turn report to the Evacuation Coordinator.
o.5.2 The Emergency Coordinator shall- noti (y the Evacuation
~ Coordinator of the need for a Site Evacuation. -
7.0 7.AINING S CRILLS . 7.1 Training
- 7.1.1 Training will be provided for Onsite Emergency Organizations personnel listed in Enclosure 1 of this directive as per Station Directive 2.5.2 (TS).
7.1.2 Operations personnel, Security personnel and Fire Brigade members will receive training as a part of their regular shift training or as scheduled by the Training Coordinator. 7.2 Annual Training 7.2.1 All Emergency Organization personnel will receive annual overview retraining as per part 0 of the Emergency Plan. 7.3 Drills 7.3.1 Practica drill sessions kill be held for each group within 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. 7.3.3 The drill scenario, participants names and evaluation will be documented and any deficiencies will be corrected. 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 .
.+ ~1.
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- tMERGENCY COOADINATOA P: J. W. HAMPTON A: C.W. GRAVES J. W. COM ONSITE LMEHGtNCY OHGAt412AI4084 G. T. 5MITH A. R. f AANKLtN TLCHNtCAL LorrOeti CENILM 5f Af f S O 3 5 4 t NCL fil htVtS40td i I
EVACUATBON COORD. P: C L JENSEN A: 8 MOSELY E.FEESER TECH.5ERVICES M Alfelk N Af 4CE ADMIN SERVICES OPE AATIONS P.A R FRANKitN P: J W COM P e. I t. MATH P C w GRAVES A: D it HOGE HS A: T. K. ANDE RSON A- T. E. CR Awf 0AD A: W. P. DE AL H 18 wtLSON J A. L ANmNG C. W. MUSE R. H. CHAAE ST W.F.SEAVER w w udry e OHGH P C M(ANut iY I J H. SLNUT8 O TOWER C. L HARTZELL j
.. . .. . s u .., _
! OPEiATING ENGR HE ALTH PHYS 4C5 CHEMISTRY PEnf0AMANCE LICENSE & P. T. E. CR Awf 0AD P: W P. DE AL P: A. H. CHAREST P: W. F. SE AVE R PROJECT S P: C, L HARTZE LL A: C. E. MUSE A: R. L CLEhMER A: L. D. EVANS A: A.S.ASERNATHY J. H KNUT4 G. T. h00E A. L. PAINTER O. M. ROS8N50N A: F. N M ACK D TOwf R A. OUCKWOATP 5. ORE SSLE R P LEhov l l l l l I . l . l . l .. .. l . [ .. RE ACTOA ENGR. M Af ORMANCE 4&E Pt At4t414G MECHANICAL
- 4. P. COOAD6 NATO 8 DATA ANAL (SIS H. P. COOAOlNATOR P: D. M. ROSass50N TECH. P. D R. ROGE h5 P H #s wit LON r w w P4cCOL iOOGai
, 5&C COOADtNATOR SUPf0RT P: J L LOWERY P: H F.MclNVALE P: A. D. KINARD P: G. A.VANDERVELDE A: 5, W. SE LLAMY A: J. D. LEE A. D L L ANiett4G A: C.D.SikERE O. WE LLDAUM C M SAHMS J M. 5TACKLEY H CO A W L. ANF AN A: L D SCHLISE A: G, L COUATNEY A: P. L WgLSON P. N. MsMAMAAA M.HAwt5 A: G. f OMD A.SLE554NG R. ASHLEY J M CAMERON g
T. HUNTER I D. LUCEY ** l l D. 5 mat h SECURITY ADMINIS T H A16Vg THteG & SA& ETi TEST ENGlosEER ~ P: T. E ANDE H50td W HOtteATON E' E E UA#ddLI P: A. SHATN AGAR
**
- A: J H. ROACH P: J A LArdialNG A: D L.WAIEfts A: A. A. JONES L. J. Ryt t y . N J GOSSE T)
ASST OPE A ENGR. FlE LD MONITOAlesG Z. L TAYLOA A; J 5 L AY G G BAHHFT P: A N CASLER COOADINATOR G. L. ANuRtws P: C. v. WR Ay A: & L MITCHELL W H MILLE A A: R.LRgVARD , l
.THAEATT OffssTE TSC Ct E f4K P: PR6 MARY 15C LOGKEEPE R COMMUNICATOR P: V. H JAC A LON l A: ALTERNATE P: D. C.GOOL58Y P: J. M AYCOCK A: W.L.kkLLEH P. GE HH AL D P: D E SEXTON A: J. C. ADAMS A: H.PHOCTOR D C. HOwlt L A: T. W. OT)ONOHug L L. NAH AY E . CRENSH AW C HtTCHis * - PHASE I ** - PHASE il 's o 3
Enclosure 2 CSSITE EMERGENCY ORGANI::ATION TELEPHCNE, ACTIVATION Page 1 of 4 , j All telephone nusoer will be anless otherwise noted. Emergency Coordinator / Station Manager .
- i
?: J. W. Hamp:en 0:
H: A: C. W. Graves 0: l ~ H: A: J. W. Cox 0: H: A: G. T. Sci:h 0: H: A: A. R. Franklin 0: H: Superintendent of Operations Suoerintendent of Technical Service P: J. W. Cox 0: P: C. W. Graves 0: H: H: A: W. P. Deal 0: A: T. E. Crawford 0: H: H: A: R. H. Charest 0: I A: C. E. Muse 0: H: H: A: W. F. Beaver 0: A: J. H. Knuti 0: H: H: A: D. Tower 0: A: C. L. Hartzell 0: H: _ H: , i 1 ( Superintendent of Station Services Suoerintendent of Maintenance P: G. T. Smith 0: l P: A. R. Franklin 0: H: H: A: D. R. Rogers 0: 1 A: T. K. Anderson 0: H: H: A: J. A. Lanning 0: A: R. B. Wilson 0: H: H: 0: A: W. W. McCollough 0: A: P. McAnulty 1 H: H: - I 0: Office H: Home NOTE P: Primary A: Alternate l
.- 7 i
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'E EPHCNE AC'! VAT:CN ?13e 2 of e All telephone nu=bar sill be AREA CCCE 303 anles s othe. .ua nct c.
Oversting Engineer As n . Coerning E:Mineer .
?
E. Crrsfora '- 1. N. C a s '. > - H. 3 A. C. E. Muse 0: A. 3- Mitche'.1 2: 2
- u. . .
A. .. H. h.u : 1 0: A- 7 'i . " :. _ ' + r . J-H- A. 2. !;.er 0: H: Health Physics Field Monitoring Coordinator a.-..... r +,.
,'s 44/ 4 'i- r ?: V. P. Deal 0:
d: ew f E. .Nh'e . , . s.
~ ?: C. V. Wray 0:
H: W c. fi = t -.s . A: R . L. C le:r:me r 0: 25 9 ' .l - A: R. L. Rivard 0: H: M'M'. k% i ~ f H: A: G. T. Mode 0: H: [-S.:-:^'((
, . ., . 3.
A: J. E. Threatt 0: H:
.. W, y- .W .; g +
Data Analysis Coordinator fkN":'.D
..: 3 , .' H. P. Support Coodinator .,.., 4,*+ s-" . .G.,p, .aq.
P: R. D. Kinard 0: e ,....1, b , ..; P: G. A Vandervelde 0: H: C
.w, .
1, e:' ." '.4 3 - a- H: A: G. L. Courtney 0:
~
e, 'p A: F. L. Wilson 0: H: H: A: P. N. McNamara 0: M o./ ~$..O ~- s ..
- 5 . '.;
i .~: f.5 5 ' ' . ~- ..~:*.- .? H: Licensin & Pr 'ects En ineer A: J. M. Cameron 0: H: 3 t' .;'.f. O,. I' . .*C,. O,.',c. ,^. . P: C. L. Hartzell 0: 9
,' ;. . .~ ,
Chemistry . .aw. 1
." .y.. H:
- Qy ry: .i - A: F. N. Mack 0:
P: R. H. Charest 0: I.,- J D : V fi H: H: 0:
.g9MI}..I A: S. W. Dr<3ssler 0:
A: L. D. Evans - H g[.;. F -!ig' g,ij '.?;;.'- H: 69 ; A: P. G. LeRoy 0: A: B. Painter 0: ..difdN.y.~
?
n W. e: y .. . 4 H: H:
, p , f$,g A: A. Duckworth 0: e .e % d'%.cfg.. -
se Radio Ooerator H. . y.;
....,,s 4' 3. ,6 1 %sw 4;,.) : .:...u ~',. '. . q.. ;. P: D. E. Sexton 0:
Performance Engineer : H:
"Q@v<e.',42,s.:A; . a .. , ..s,,. .e.. ,., .. -
- A: T. W. O'Donohue 0:
P: W. F. Beaver 0: g~ ,. gg' . . . y.,f .. H: H: s:. M r .: .-t ' A: R. Abernathy 0:
$(' { S. ::. -
m H: q.. g' ,.3s.;Le..y.y. ~ .' A: D. M. Robinson 0: L m
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6 H: >g. ,f,. -a -ir .. e-c - L'1' *E'af..y. . .?
1 Enclosure ; l CSSITE EMERGENCY ORGANIZATICN TELE?HtNE ACTIVATICS ?1ge 3 Jf - l A;. telephone nuccer wt'l be AREA CODE 303 iniess othersise noted. Reactor Engineer ?erformance Technician l
- . " Rcb.nsca 2. 3 '
S a ncs 0- f' l
- d. H. l A. 5 :-i . 3 e l ;1=y 0: ?: J. uc.ery O.
H: H: A. 1 H rs e s 0: A. S. Tara : l 1 A. J. 4e;;boum u. .s . R. u .r-H: H: A: R. B less tng 0: A: T. Hunter 0: R: H: A: D. Smith 0: H: A: D. Lucey 0: H: Planning Engineer ISE Engineer P: R. Wilson 0: P: D. R. Rogers 0: H: H: A: D. Lanning 0: A: J. Lee 0: H: H: A: R. Cox 0: A: J. Stackley 0: H: H: Mechanical Engineer Securit & Contract Coordinator l P: W. W. McCollough 0 P: T. K. Anderson 0: H H: A: C. D. Steele O A: J. Roach 0: H: H: A: W. L. Anfin 0: A: L. Ryley 0: H: H: Administrative Coordina Training & Safety P: J. Lanning 0: i P: P. McAnulty 0: H: H: A: J. Lay 0: A: D. Waters 0: H: H: A: G. Andrews 0- i - A: J. Gossett 0:
!I A: G. Barrett 0-H:
H: 9 NOTE P: Pr ima ry A: Alternate 0: Office Home .
TEI.ZPHOST. ACTIVA!!O.N ?a;e 4 of a All telephone nuobers will be AREA CODE 303 unless otherwise acted. l l * ! TSC Logkeener TSC Clerks . l
- ?
- D. C. Geoiscy 0: ?: -
Jackscn 0: H: H: A: J. Adams 0: A: W. Keller C: I tr . u. A: T. Nahay 0: A: ?. Gerrala 0: H: M: A: D. 3:<.e'1 . 0: H: Offsite Ccm=unicator A: C. Ritchie 0: H: l P: J. M. Aycock 0: H.P. Coordinator S&C H:
- P
- P. V. Germeroth 0: P: H. F. McInvale 0:
- H: H:
5 A: E. M. Crenshaw 0: A: L. D. Schlise 0: H: H: A: R. Proctor 0: _ H: Test Engineer i ) P: A. S. Bhatnagar 0: i ! H: l A: R. A. Jones 0: N: ( A: Z. L. Taylor 0: H: - I I i Evacuation Coordinator . P: C. L. Jensen 0: - Beeper-H: A: B. J. Moseley 0: , Beeper
- H.
A: E. L. Feeser 0: ) Beeper H: 1 I i s O I -
Incissuro (3) CNSITE EMERGENCY CRGANIZATION
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OPERATIONS SUPPCRT CE.W:.R .- I
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CONTROL I ROOM I i 1 8 i
, I I TECHNICAL I SUPPORT L
l ' CENTER ." l I ASST. M . P . *- - ----------g h-----------
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- OPERAT- COORD- g ING ENG INATOR y i
i I I i - OPERATIONS SU? PORT CENTER t ' t - - - - - - *SEIIT SUPER'.*ISOR I I AUXILIARY HEALTH PHYSICS I OPERATORS I On-Shif. and On- M.P. Supervise- 4. - ----- -J Site Operators not Supervisor and 5
- ', actually assigned to:hnicians to be to the Control assigned by Sta: ton Room and other Health Physicis: as Operations needed from H.P.
personnal called- du:y list. out as deemed necessary by the Health Physics Technicians Emergency Coord- < inator or Supt. * " of Operations +
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.s % TO CONT.i OL ROOM .
L Y G OPS. CATAWS A NUCLE AR STATION 4 O O TECHNICAL SUPPORT CENTER TECH. o A > E . MAINT. o MANAGER O ADMIN. m 2 Q]p
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_________{ STA.H.P. ANALYSIS SECURITY SAFETY g o oee o o l Ong i PJitC Allt A SUPPORT S & C COORD. COORD. PLANNING MECH. E NGR. l OO l 0 0 O lO l . l .
% FIELO MONT. l ' \ COORD. OFFSITE COMMUNICATOR g l
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l Station Directive 3.3.4 Rev. 6 Inclosure (5) CATAWBA NUCLEA A STATION s OPERATIONS SUPPORT CENTER I 8 : l . I I 1 I I I I CONTROL ROOM g 1 s-g o a' O OPERATIONS SUPPORT CENTER AUXILLARY BUILDING EL 594 , ,
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9 5n f e 2 6TIQ6 IUIY ENGR. StPT. (PERATI0tS $8 a ASST. G U ATIG S D E . O i 9
= 9 g -IEE BE. TRNISHISSIQ1 fEP. 5 P T.ff0nm ;0!11CIN -SlPT. PRINIDIANE-- -KOINIICAL ENGR. l KACIOR B E . TEST B ' -Pl# FLING ENGR. l filTMW'& BE.
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