ML20081B126
| ML20081B126 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 01/18/1984 |
| From: | Foster J, Mcconnell T, Tucker H DUKE POWER CO. |
| To: | Adensam E, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| PROC-840118-01, NUDOCS 8403070352 | |
| Download: ML20081B126 (84) | |
Text
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e 4 . i i i* l IMPLEMENTING PROCEDURES MANUAL - AUDIT 1/26/84 PROCEDURE # DATE TITLE i RP/0/A/5700/01 1/5/84 Notification of Unusual Event I RP/0/A/5700/02 1/5/84 Alert -
, RP/0/A/5700/03 1/5/84 Site Area Emergency , RP/0/A/5700/04 1/5/84 General Emergency RJ/0/A/5700/05 8/3/83 Care and Transporation of Contaminated Injured Individuals RP/0/A/5700/06 2/3/83 Natural Disasters '. RP/0/A/5700/07 2/4/83 Earthquake l RP/0/A/5700/08 2/4/83 Release of Toxic or Flammable Gases 5 RP/0/A/5700/09 2/3/83 Collisions / Explosions j OP/1/A/6200/48 10/13/83 Operating Procedure for the Operation of 1 the Post Accident Liquid Sample System, Unit 1 /
OP/2/A/6200/48 10/13/83 Operating Procedure for the Operat. ion of the Post Accident Liquid Sample System, Unit 2 j; HP/0/B/1009/02 7/20/83 Alternative Methods for' Determining Dose
?
Rate within the Reactor Building HP/0/B/1009/03 7/13/83 Recovery Plan HP/0/B/1009/05 4/7/83 First Response Evaluation of Offsite Dose { From a Reactor Coolant Leak Inside Containment q, HP/0/B/1009/06 11/23/82 Procedure for Quantifying High Level Gaseous Radioactivity Release During Accident Conditions ; HP/0/L/1009/08 1/11/83 Evaluation of a Reactor Coolant Leak
,! Inside Containment
' Release of Reactor Coolant through Unit HP/0/D/1009/09 5/6/83 Vent Exceeding Technical Specifications b HP/0/B/1009/10 8/30/83 Releases of Liquid Radioactive Exceeding Technical Specifications
,' HP/1/B/1009/15 4/19/83 Unit 1 Nuclear Post Accident Containment
. Air Sampling System Operating Procedure p; HP/2/B/1009/15 4/19/83 Unit 2 Nuclear Post Accident Containment
- j Air Sampling System Operating Procedure d HP/0/B/1009/16 4/29/82 Tablets in the Event of a Radiciodine p Release PT/0/A/4600/06 1/18/84 Exercises and Drills
',' PT/0/A/4600/11 7/13/83 Functional Check of Emergency Vehicle and Equipment Station Directive 2,0.5 Rev. 4 News Release li Station Directi- 2.5.1 4/21/82 Emergency Response Training Program Station Dir
- he 3.7.3 Rev. 11 Bcab Threat i Station Dir 3.8.1 Fev. 13 Site Assembly / Evacuation
- Station Dire .8.2 Rev. 10 Station Emergency Organization
'i Rev. 9 Enclosure 1 ,, Rev. 7 Enclosure 2 - Rev. 6 Enclosure 3 i Health Physics Manual Section: po "J(y Rev. 3 18.1 Accident and Emergency Response Rev. 6 18.2 Environmental Monitoring for Emergency Conditions Rev. 3 18.3 Personnel Monitoring for En. 'ncy Conditions 8403070352 840118 - ~~ PDR ADOCK 05000369 F PDR
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'" Form 34731 (10 81) .
1 (Formerly SPD 10021) J
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DUEE POWER CWFANT (1) ID No IP/0/B/1009/05 t PROCEDURE PREFARATION Change (s) G to j FROCESS RECORD A ncorporated I 4 F d (2) STATION: moonize unclear station
~
.j (3) F30CEDURE TITLE: First mesponse Evaluation of a Beactor Coolant Leak
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d Zaside con *=4 W
- I, (4) FIDARED IT: I h*O - - DATE: 1aitu' .
f1 U (5) RETIINED BT: A# h MTE: 1o-//-f3 V Crose MP pH i 7 Eaview By: -- N/1: AP , (4) TBIPORAIT AFFROVAL (IF 1rrtemunt): il By: (330) Date: -[ ; 7 By: Date:
! ( '31 (7) AFFECTED BT: p/m J. #7?/ - J/ Data: /o/u /D p . . 1
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- t DCEE F0WER COMFAMT
,,j McGuIEE seCr. EAR STATION FIRST RESPONSE ETALUATION OF A REACTOR COOLANT LEAK USIDE CONTAIEMENT i i l 1.0 Furooes
,' ThiJ procedure is to be used to determine potentially sffected
] . steas and levels of protective action in the event of a reactor coolsat leek insida containment. 4=W4M possible release through I unit vest. l D 2.0 References c d 2.1 W/0/3/1009/02 Alternative Methods for Determining Dose Rate a ' Within the Reactor Building. O 2.2 W/0/5/1009/04 Evaluation of a Resctor Coolant Leak Inside 9 j Containment. 2.3 W/0/3/1009/09 Eslease of'dadioactive Materials Through the Unit Yeat *=a==d4=g Technical Specifications. 2.4 DA - 320/1 001, Manual of Protective Action Guides and l' Protective Actions for Nuclear Incidents.
. 2.5 Esalth Phyetes Manual Section 8.2. Exhibit 8.2-2. Page 2. Unit Yeat 4 Basta Effluent flow Data Form. ! 3.0 Limits and Precasciens . . . . . ._.
3.1 This procedure is intended to be used by Basich Physics shift personnel daring the first 60 minutes of a reactor coolant [ lenk inside containment. I! 3.2 This procedure incorporatee Environmental Protection Agency
- ~ ~~ -
(WA) Protective Action Caides (FAC's). It is important to i' P recognize that FAG's are defined in terne of projected dose. l' Projected does is the dose that would be received by the
; - population if se procactive action were taken. We protective
,', actions to be most effective, they must be instituted before exposure to the plume begins.
! 3.3 This procedure is a backup to the ' Nuclear 23' computer code 4
,j erailable to operations shift personnsl on the OAC computer 'i sad se such shall only be used in the event this computer code _ i is not available. 3.4 This procedure requires dets svailable onlr, in the Technical Support Cantar and the Centrol Room. It is recommended that w, -,-.
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- Pago 2
] . the shift technician perform this procedure in the Control fl. .o. m.>} u . ll 4,./ 3.5 This procedure may involve evacuation of the public in the l{ area surrounding McGuire Nuclear Station. The shitt
) technician will make rea - d=tions for or against evacuation I based on the outcome of this procedure. It is the responsibility of the Emergency Coordinator to evaluate these i r=*=====d=tions.
l 3.6 If say evacuatier. recommendation is made, it is advised that
. the shift t=*h=4-4== perform an assessment using reference 2.2 ! or 2.3. La order to calculate does projections.
El 3.7 This procedure should be updated (re-rus) every 15 minates II until the TSC and/or references 2.2 and 2.3 are utilised. f: c, Once a sector has been added to the list of affected areami it 'l I cammet be removed from the list. 4.0 Procedure . 4.1 Asquire the following information and record on Zacloonze 5.1. ENTE 1: Some of the following information can be obtained
) from the ' Tech Speca 04' program of the Operator Aid Cosqmter.(CAC). All information available in ' Tech l
!j specs 04!' will be denoted in the following F +:- " =e
- l. by a '(TS)' to the left of the section member. See i
l Enclosure 5.2 for steps to access ' Tech Specs 04'. 1 i
; NOTE 2: Meteorological data should be obe=4aad in the order
- . .of preference listed on Enclosure 5.1.
I q NOTE 3: Use 15 minute averages for g meteorological data. 4.1.1 e Unit affected. 4.1.2 Name of person performing *=1 1= tion. i l 4.1.3 Present time (hours after midnight) and date. I 4.1.4 Time of trip / shutdown (hours af ter midnight) and l4 date. . 4.1.5 Tian since trip / shutdown (hours). 4.1.6 Wind directics upper cover (degrees from North), G' e e
, r l
Fase 3 a . 1
- (The direction that the wind is coming from). l l
i j] Lower tower wind direction should be used only if l
.i .,f upper tower is unavailable. ! 4.1.7 Wind speed lower tower (MPE). Uprer tower wind a speed should be used only if lower tower is y unavailable.
1
! 4.1.8 Vertical camperature gradient or AT 'C (lower to Ij upper tower) from -4 to +8 sesle on esteorological
'j temperature strip chart recorder. -
.' ID.34 .1.9 Reactor b NM dose rate (IMF 51 A cr 3, whichever j is higher or reference 2.1).
I I 4.1.10 EMF 37, Unic Yeat Iodian Monitor (A CFM sad A Time , j (mis.)).
- i EUTE: This is a determination of the change in l CFM during a change in time. If ' Tech j 5pecs 04' data is used, determine A cpu from two runs of ete progrsa 5 minutes apart (A Time a 5 minutes).
4.1.11 IMF 34 Low, Unit Yeat Noble Gas Low Range moattor l. l' (CFM).
' ' I I 4.1.12 EMF 36.Eigh, Unit Vent Noble Gas High Range Monitor . ! (CFM).
I I 4.1.13 !' Unit Yest Flow (CFM). li NOTE: ' Multiply fractional flow from totaliser by i 170.500 to get flow in CFM (i.e., 951 flow l = 0.95 fractional flow). [ If totaliser is inoperable, use reference 2.5 to
} determine unit vent flow. ? 4.2 Detetuine TT (time factor) based upon time (hours) since trip /
t l shutdown from the table on Enclosure 5.1. and record on Inclosure 5.1.
; 4.3 Calculate time detenzined dose (DT) as shown on Enclosure 5.1 and record on Enclosure 3.1.
4.3.1 Calculate DT1 (time determined dose l') using (DE) i Reactor Building Dese Race x (TF) time factor.
; 4.3.2 Calculate DT2 (cias determined ciose 2) using a CPM (IMF 37) x CTM (unit vent flow) x I. 8E-6
,, + A Time.
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! 4.3.3 Calculate DT3.(t determinee dose 3).
4.3.3.1 If Dtr 36 Righ > 100 CFM. calculate DT3 h))
; \~ using CPM (DEF 3h. High) x CFM (unit Vent
~, Flow) x 3.6E-3. 4 4.3.3.2 If DEF 36 High < 100 CFM calculate DT3 i using CFM (EMF 36 Low) x CFM (Unic Vent
- j Flow) x 6.7E'7. -
4.3.4 Calemiste DT4 (time determined dose 4) using DT1 + ,
- d. - )
y DT2. . !! 4.3.5 Determine DT.
~
- 4 j 4.3.5.1 If itT4 > DT3. then DT = DT4.
ii 4.3.5.2 If DT4 < UT3. thea DT = DT3. I d S 4.4 Calculate DF (does factor) using (UT) + windepeed (US) as 'I d shown on Enclosure 5.1 and reccrd on Enclosure 3.1.
- l 4.5 Determias distances and levels of protective action based ea
! dose faster (DF) and 4T (*C) using the r.able on unntaeure 5.1. '
4.6 Determine potentially affected zones based on wind direction ll ij using the table oa Enclosure 5.1. j (T 4.7 Detetuina if sea-stagnattag meteorological conditoes exist by
- l () observing meteorolot9 a1 strip chart data. If
! [. (1) Instantaneous' wind direction has not varied over 90'
- j in the past two (2) heure, g (2) Instantaneoes wind speed has not fallen below 10 MPE
- l in the past two (2) hours, then non-stagnating conditions exist.
.j Record result on page 5 of 5 of Enclosure 5.1.
, 4.8 Checkresultsandin[o'reE.ergencyCoordinatorofyour j reco eadation..
i 5.0 Enclosures
! 5.1 Werksheet ; 5.2 QAC (Tech Specs 04) User Docutmitation '
a. 8 . 4 . I - r,. y, - , - - - . - - - _ , - .
f a i EF/0/8/1049/05
\ g
,1 \ .T. ] ,m Enclosure 5.1 a l $,'h Fase 1 of 5 l ao'a== a i
- I 1) Unit i 1
1 Farfotand by j a i J Time New hoers after midnight. Date_ j i Time of Trip /5hatdown hours after midnight. Date 3 . - . - Time since Trip /5hnsdown hours . (All meteorologiesi data is 13 minate everage) ] , Wind Directica 1) Upper tower degrees from North. {:l or 2) Lower tower degrees from North. j Utad Speed 1) Lower tower MPE j .) or 2) Upper tower MPE ,
~
l AT 1) lower to Upper tower "C <
- 1
- , or 2) For 1000 - 1600 -0.2 'C'
. or 3) For 1600 - 1000 +1.3 *
,, (TS) Reester n-4m.- Dose Este (DE) R/hr 1 (Bir 51 A or 3, whichever is higher; or reference 2.1 if EttF r> .g ,
- ! 51 mot available) .
(TS) BEF 37 & Crit -
& Time (ein.)
- ! ~ BEF 34 Low ll CFM ii
- I
[] (TS) BEF 34 Eigh I CFM + ] (TS) Unit Yeat Flow (F) I CFM (Totaliser fraction x 170.500) { 2) Determine TF (time factor) based upon time (hrs) since trip / shutdown fr a I' the table below: II .. Time (hrs) TF (time factor).
! 0 - 1.0 l 12 i
'j i L
. 1.1 - 2.0 ! ' l'[
7.1 - 5.0 27 5.1 - 10.0 42 f . 1 .
} }
i Record TF (time factor) 1 i 6
- 3) Calculate DT (time determined dose) :
f a) Df1 's DR 2 TF t
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.___------..z...._ . - . . . _ _ _ _ . _
< l HF/0/3/1009/05 1 j f,% Enclosure 5.1 i I Y) 2 Fase 2 of 5 f b) DT2 = AIMF37 xF x 4.8E-6 l ATime c) If IbiT 36 Righ >100 CPN. j DT3 = IMF36 Eigh xF z 3.6E-3 i . ._. . _ .
- t If EMF 36 Eigh <100 CPN.
*\
i UT3 = EHF36 Low xF x 6.71-7 - 3......
; d) DT4 = = DT1 + DT2 ,
e) If DT4,> DT3; DT = DT4 If DT4 < DT3; DT = DT3 UT = j . i
; 4) Calemikte DF (dese factor) based upos DT and US (wind speed). 'I DT = f,US) &I}
j
- i. ,O, DF =
- v EDTE: If US 1 1.0 mph. use US = 1.0 mph.
I _5) Detetuine distances and level of protective actions. based on DF f , (dose fictor) and of from the following table:
.2 i . . . . . . . ,j 0 - 4 Mile FAG's l
4T Bo action Evac Children & Pres. Somen Evac. Everyone 1 t <-4.6 <1.30E6 1.3446 - 6.49E6 >6.49E6
-0.5 11.2415 1.24E5 - 6.21I5 >6.21E5
-0.4 to -0.2 13.99E4 3.99E4 - 2.00E5 >2.00E5 i -0.1 to +0.4 2.23EA - 1.117.5 >1.11E3 12.23E4
+0.5 to +1.2 31.10E4 1.10E4 - 5.4714 25.47E4 .
j >+1.3 <6.3513 6.35E3 - 3.17E4 >3.17E4 l . i i g .._ ,
- i i i
'd 4
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ . 1
. .- . _ . - -- - . - . - . . -. . - ~ . . - . . - . - . .
t.
- f. O
'i t l - EP/o/s/1009/05 [.'c . Inclosure 5.1
'l .
J Page 3 of 5 i 9 i i 4 - 10 Mile PAG's
,j ,, , , , , , _ _
AT Wo action Evse Childres & Pres. Women Evac. Evervoos . _-0.6 <1.37E7 1.3717 - 6.80E7 >6.80E7
., -0.5 11.43E6 1.43E6 - 7.13E6 >7.13E6 i
-0.4 to -0.2 <3.29E5 3.29ES - 1.64E6 >1.64E6
-0.1 to +0.4 -
41.6015 1.60E5 - 8.0025 >6.00E5 4
'I 4.5 to +1.2 16.80E4 6.8054 - 3.41ES >3.41E5 .I J
_>+1.3 42.79E4 2.79E4 - 1.40E5 >1.40E5 4 f . 9 4 e o t i s l I t . **. , t
.4 mt tf 2
9
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4 4 , i
' wd b ._ _ . . _ _ _ _ _ _ _ _ -_ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
- _ _ _ _ . . ..-.. _ _ m __ .___ ,m.. _ ._.....m_ _ _. _ _ _ . . . _ , _ _ . _ -
l . . , _ . . - . . ~ _ _ - - . ~ ~ , . . , . - . . . . . ~ . . . - . . . - - - - . ~ . - . - - + . - - - - -- t
- l .. ', .
!i (j ,4 , ; HP/0/8/1009/05 j '1
. Enclosure 5.1
'] Pese 4 of 5 e l' j 6) Determine affected areas based on wind direction fom the table below: 1 1.6
- - Viad (degrees from 0-4 4 - 10
!i Direction North) Hile Mile
- Ree-ad= tion Recommendacios . . . ,
i.) 0- 22.5 See Wete 1_ S.E.F _
- 22.4 - 45.0 E.S.Q
] 45.1 - 67.5 E.S.0 . s.
ri 67.5 - 90.0 5.Q.P ' 90.1 - 112.5 S.Q.P.E . .. , ,, 112.6 - 135.0 5.0.P.E . . . i4 - l__ 135.1 - 157.5 0.P.E.I . - . . . !t 157.6 - 180.0 . P.E.I.J
>i 180.1 - 202.5 P.E.I.J.E.G t
; 202.6 - 225.0 E.I.J.E.G
> U 225.1 - 247.5 I.J.E.G6F lf 247.6 - 270.0 -
J.R.G.F i 270.1 - 292.5 4.F 292.6 - 315.0 G.F.E . l 315.1 - 337.5 G.F.E
'~
3?7.6 - 359.9 F.E.S l ~'. 4 '! NOTE 1: Areas A,3.C.D M,N,I. 0,R will be the recommended .t areas if any action is takes in the 0 - 4 mile radius of l j the plant. This reW= tion is independent of wind
, direction.
i
.4 I
1 9 l d w m-
_ _ _ . --~_. - 4 SP/0/3/1009/05 r
! . Enca sure 5.L l !- .
i Page 5 of 5 I
- 7) 0 - 4 miles
.{
.e,_ - _, i,.a.
j 3ecommended Population (
.i 4 - 10 miles 1
j necommeseded Arms . l Non-stagnating meteorological conditions doJdo not asist. 1 .
)
8 Signature 50TE TO IMERG DCT COORDINATOR: . i
- If the release is projected to and within one-half ( ) hour, and
; [ non-stagnating entwrological conditions exist, consider not
, rec h ing an evacuation if the pluse will have left the Energeoc~
! Protection Zone (EFE) before the population could evacuate.
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C ., ' i II HP/0/3/1009/05 Inclosure 5.2 Page 1 of I [b?? OPERATOR AID CONFUTER (TECN SPECS 05) 0SER DOCUMENTATION l
]1 1) ' Tech Specs 04' can be accessed thru CAC terminals in either the 1) .I Technical Support Center (TSC) or the 2) Computer Room.
1 ') . ] ' There are OAC terminals for both Units 1 and 2. Be certain to use i the OAC tecaimal for the appropriate Unit. 3} q
] All necessary data on the ' Tech Specs 04' computer printout will h under the ' Environmental Systeme' heading. )!
- i
- s
] 2) Procedere . ;, a) Check to see if the READY key on the printer is fully
- ON/0FF LINE
. 111mminated. If not fully illuminated. press the key one, time
! sad release.
i l b) Press the Tech Specs key of the OAC terminal. (Eey will ti l1 ' 411==i==te). i! [ c) Type 0 4 using the blue numeric keys of the OAC terminal. l4
'l b d) Press the P 3 int key of the OAC terminal. (Key will illuminate).
}
j e) Press th Enter key of the OAC ter 4nat. (Key will illuminate).
! Upon pressing Enter, printer will print data.
1 i f) When printer set.ps, prese the READT key on the printer to lj
- 05/OyF LI3E illuminate caly the " READY" portion of the key.
l g) Press the TOP OF TORM key on the printer three (3) times to
~
advance paper. Tsar off data sheet. i ee v.v --. -
. - ~ . -n . - - - - - - -
i a. 4 I d Perm 34731 l 1 (Pommty sp - - - - -.. 4 . I. 't 9 UUKE poler CtatFANT (1) ID Nos EP/0/B/1009/08
'. PROCIDORE FREPARATIM Chastge(s) O to
- 1 FROCESS RECORD L Incorporated
; i j (2) sTATrous naamize w - station h
(3) #ROCEXIRE TITLE: Evaluatica of a Beactor Coolant Leak Inside Conemin==at c h (4) FRIFARED ET: iJkmd DATE: Io 1 is lF1 l :, c: (5) RETIINED ??: v A,A-- DATE: )s /JD-JP 3
. Crose-D'el=H-- y Review By: N/1: Ass v ; (4) TIWFWAIT AFFROTAL (Ir unemany): j l, By: , * (530) Dates
,1
.n j ; (: By: Dates J
i , , V , I! (7) AFFROVID ET: ,,,,,,,/,m 7. # f- C #1 Date /c/.://E - i G . (s) weerrnmannes ; Regissed/ Approved By: Date I t i 1
- 1. Reviamed/Approvna ny: Date:
)
l. l
. +
l: l 1' lt ! :t I* l 1 t t
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j ~. . IP/0/3/1009/04 1 . 1 DUIE POWER CotfFANY
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- t. /
McGUIEE NUCLEAR STATION EVALhTION OF A IIACTOR COOLANT LEAK y INSIDE CONTA N FMT 'l 1 1.0 h This procedure describes the method for evaluating the offsite dose rate and dose in the event of a reacter coolast leak inside coa *=i - *. In addities, this procedure can provide armias messaan information to be 1 gives to State / local agencies. 2.4 References . } 2.1 Station Realth Physics hasal, Section 18.2; Environmental Monitoring ] ~ for Emergency Conditions. a 2.2 TID 14844. , 2.3 EP/0/3/1009/02, Alternative Nethods for Dete * == Dose Rate Withis the Beector am41 ding, a; ~
- 2. 4 Offsite Does Calculation Maasal (GM21). :
2.5 EP/0/3/1009/05, First Eseposse Evaluation of a Beactor Coolant Leak ' i. ' Inside Containment. e _, !- ) 2.6 Guit Data Book. - ( -~ 3.0 Limits and Precautions if , , , . l 3.1 This prsmedare is being used in as emergency situation which could , result in evacuation of areas surroemding the plaat. The procedure ll
- shall ba- done carefully and accurately. e 3.2 This procedure is written for use under abeerusi conditions'which if could involve estremely high radiation levels. Caly the, Station-a
,- Resith Physicist or his designee shesid authe,rize the use of this j procedure when needed and should provide. appropriate surveillance and
,l control of people taking the samples. 3.3 This procedure is a backup method of dose assessment to tae ' Class A l Atmospheric Dispersion Model' computer code available to Realth Physics personnel cad as such shall only be used in the event this campster cede is act available. Warning message information, however, any still be generated from this procedure. ii !* 3.4 Check tha. the counting equipment to be used has been calibrated and F7 daily response checks have been performed.
.. I l
l . 1 l "
.v - - . _ - - , ,,_m.- -_-.y.,., , --.,,-, , - ,,,.-.,-,.,,.--.,.,,e.ww-g,- -
# 9 --g.,,,,--g9.--. - , - , , ,y.-w--g----yyym----a
t 2-y .
* . 3.5 Individasis collecting the samples should be aware of the possibility of airborne contamination and high radiation levels in samplias . ! s areas. Use protective clothias, gloves, respiratory protective equipment, portable shielding, high range dosimeters, and survey 1
instruments as determined by Bealth Physics supervisor.
] 3.6 If action is takes in the 4-10 mile radius area per reference 2.5, i them wind direction should be rechecked every fifteen (15) staates to ) ensure that additional sectors have met been affected. Once a sector i has been added to the list, it cammet be removed from the list.
J i 3.7 Projected deses aheald be compared to the Ravironmental Protection Agency Protective Action Guides to deternsiae levels of protective
- action. .
1 u 4.0 Procedere 4.1 The primary method for the determination of offsite dose assesseest i is by use of the ' Class & Atmospheric Dispersion IFdel' computer a j code. Refer to the ' Class A er 7 --ic Dispersion llodel User 4 F - = tion' for instructions on the use of this code. If the computer code is met sveilab,le, coatians with the mammal procedure. , 4.2 Acquire the following information and record on Enclosure 5.4 and 5.5. s_/ NUM 1: Seen of the following information can be obtained from the
, ' Tech Specs 04' program of the operator Aid Campster (04C).
I All information available is ' Tech Specs 04' will be denoted in the folloeing procedure by a '(TS)' to the left ef the section ammber. See Enclosure 5.9 for steps to {
,' secess ' Tech Specs 04'. ,
NOM 2: Standard warnias message information to be gives to j state / local agencies will be denoted in the following { procedure by a '(141)' to the left of the section number. NUM 3: tieteorological data should be obtained in the order of
! preference listed in Enclosure 5.4
; NUM 4: Use fifteen (15) staates averages for ay meteorological 6
data.
~
'. 4.2.1 Time of Beactor trip /shmedown (hours after midnight) and 2
bu .
; 4.2.2 Time of calculation (hours after midnight) and date.
j
*mg
a 3 b ,
- , i t ,'
(lat) 4.2.3 Wini direction recorded in degrees form Nor (M tower). Lower tower wtad direction should be used by it. M
't ..n sje upper tower data is unavailable. \
] 7e 4.2.4 lower tower wind speed OlpK) (W). Upper tower wind sp W j should be used only if lower tower is unavailable. 4.2.5 Vertical temperature gradient or A T*C (Lower to Upper L '. teuer) from the -4 to +4 scale on the seteorological temperstare strip chart recorder. I- NOTE 1: The above information is used along with the 'i Table on page 1 of 3 of Easlosure 5.6 and map
; provided in Technical Support Center (TSC) to
[j determine areas affected by release. ] NOTE 2: plume direction is 180* opposite wind direction.
! (1dt!) 4.2.6 Stability class (A, B, C, D, E, F, or G) from Table I (Easlesure 5.1). S.
] (ISI) 4.2.7 Ambient air temperature (*C). Record La *F where:
'T = 9/5 x *C + 32.
(141) .'4.2.8 Precipitaties ( A iaches / A time). , 1* (14f) 4.2.9 Belease height is 33 feet above yard elevation. ID 4.2.10 Leak rate (M), which is either known leak rate or desiga
- .d leak rate.
t. \! - - M g,,g,, a Containment Velase a Design Leak Coastsat
= 2.9 x 110 'al : " -
d*1
! day x 24 hours
= 2.42 x 106'al/hr.
l l: 1 WEE: Inclosare 5 8 should be Tsed in dete==4=4== leak rate if other than design leak rate is used. I i 1 i ' 4.2.11 Bescter Building dose rate (Ettr 51 A or 5, whichever is bisher or reference 2.3). WD1E: Information in sections 4.2.12, 4.2.13, and i
- 4.2.14 is not moras11y used. It is avaiIable if
; needed for werktag with .outside agencies.
i 4.2.12 Release concentrations (Cyg and C ) free Health Physics 7 8 ' .
% I ne
- - - - - . - - ,.--,--w-,,m.... -c,. w.i. ,-. ., . --. . __,_m ..,..-_e-. ,,,y ,,--.%. -w ,,%,s% e ..--.e er - - . --
4
. J .
. sampling of the Post Accident Contatannat Air Sampling -
1 i System; or EMF data if sample results are not available, a,s I follows. ,
! ,j If EMF 39 (H) ( 100 cym,
; a) C,, = EMF 39 (L) cpm x 3.8 E-8
'er if EHF39 (H) > 100 eps
]
b) CNG = EMF 39 (R) cpu a 2 E-4 I c) y = IMF40 A cpe/4 time x 2.34 E-10
. Idhere:
g a noble gas release concentration in p/Ci/al
, C7 = I-131 equiv. release concentration in pCi/al
; 3.8 E-8 = EHF39 (L) correlation factor in.
. FCi/al/cys from reference 2.6 .
2 E-4 = EMF 39 (H) correlation factor in psi /s!!
- cys free reference 2.6 1.34 E-10 = IMF40 correlatios factor in pCi/al/cym/mia from reference 2.6 (Wtt) 4.2.13 Calculateradiologicalreleaserate(4)inCi/secusing I
s7 the following formala:
~
I a) haC y x LR x 7.86 E 4 {
, b) hy = C7 x 1R x 7.86 E-6 [ i; f' s.
c) k=(Cg + C )7 x 1R x 7.$6 E-6
- ,; J -
~
1 Were: *
.~ + i . ;
g a noble gas radiological release rate in
,! Ci/see t i
i kg= I-131 equiv radiological !release rats in Ci/sec k = radiological release racejin C1/see i . i 1R = leak rate in al/hr (section 4.2.10) ! 3 7.86 E-6 = 2.83 E4 cm /ft3 x 2.78E-4 hr/sec -
! x ?E-6 Ci/pci
', ) 4
)
All other variables saac as previously stated. b o e nemem -a.mma.-.,_ . . - . . ___ _
.s.
, OE) 4.2.14 calculate dose conversion factors in R/hr/C1/m2 for whole j body and child thyroid using Jae following fomenlas: ,.
i
; ' c..
DCFg = 0.5 x 3.7 E10 x 3600 x f 1.3E3 x 100 x 6.2SES i j a) DCFg = 820 x E j n ues j DCFg a mole body dose conversion factor in j W/WM
, 0.5 = conversion from infinite cloud to
- semi-infinite cloud whole body dose i
)
E = average Nev/ dis fras Coast Room data j f MNE: If I cannot be obtained from sample
. resalta, the following values should be
.used.
I in Hev/ dis
' I,3
%j j Esars from Trio
< 12 0.40 12 .,44 . 0.20 -
> 44 0.10 1.3 E3 m density of air in s/ea
.1 . l Conversion factors: 3.7 E10 dis /sec Ci . . .' _
] 3604 sec/hr .;,.
i 100 ers/s + rad
, 6.25E5 Nev/ers j , DCFg = 4.39E-3 x 1112 x 1E-3 x 0.422 b) DCFg = 1.85 16 1Aiere:
{ DCFg = child thyroid dose conversion factor in ~
- R/hr/Ci/m3 I
~
=q'
l , _. ._ _
.. y j- [,* .
,, , 4.391-3 = inhalation dose factor fos child
^
[ thyroid in aram/pci, from reference 2.4"-
$N 0.422 = child breathing rate in m 3/hr, free reference 2.4 Conversion factors: , 1E12 pCi/Ci l 1E-3 rad /ared 4.2.15 hse (2) hear relative concentration (G) La sph sec/ma from Table I (Easiosare 5.1) at the site be==dary (0.5),
2, 4, 5, and 10 mile points. Record on Table I and Table II ef Eaciosare 5.5. (141) 4.2.16 Determine the child thyroid dose rats at the site boundary 5 (0.5), 2, 4, 5, ? M 10 mile poista using the fo'llowimp -
! fonsula: .
; Dg aD gg x TDCF g x 1, a G
~~
! I
. 14aere:
D CT = ckild thyroid does rate in Ram / hour
; m .
t C]J ' D ER = reacter building dose rate in Bam/ hose 4secties 4.2411) - 4 1R = leak rate in al/hr (section 4.2.10) .
.} TDCFg = I-131 @v. h dete_smined conversion
}
factor (from Teble os Esclosure 5.2) and: TDCTg =A g z 1.1M t t ' D j
+ I
.; h re:
g = I-131 activity vs. time in uci. ores
- al . pCi ,
l 1.17 E-4 = child breathing rate in m3 _ see i. 113 = coswesion factor in sci . Rem
.i.
pCi . mRea 6 -I-131 dose rate vs time in R I
/ '1, he i
\j e =,m
--__-___-__m- _ . _ _ . _ _ .
ei 't , 7 1
- i l
li = windspeed in eph (section 4.2.4) , I j *
- G = Two (2) hour relative concentration is sph e
- l 1
I(;9:( sec/a8 (section 4.2.15)
; %, - NOTE: This can be rapidly accomplished by ,
y storing in calculator assory the result of j all ambers, escept G , and them recalling j this member to saltiply by each G value k for the 0.3, 2, 4, 5, and 10 mile points ,
- d. (as shown on Table I on Inclosare 5.5).
j 0 41) 4.2.17 Detmodne child tsyroid dose at the site boundary (0.5), s 2, 4, 5, and 10 mile points by saltiplying the dose rates at.these potats (as done la section 4.2.16 and shoma os j] Table I em Inclosure 5.5) by *.ae dose assessment period 1 (in hours). s . il NDh G values based ca a two (2)heiir dose assessment 3 . period. i, Ott) 4.2.14 Datesmine the weele body ser dose rate at the site
.' besadary (0.5), 2.,4, 5, and.10 mile pointa using the, 4 following femmala:
. in
(. ) Dg a g a IR z TDCFg x aG
- Mere:
Dg a whole body s u dose rate in Ree/hr. TDCFNG = Noble gas time determined conversion factor (from
'j Table sa Inclosure 5.3) and
[.l 1
.y i TDCFyg = Ayg a 0.23E-6 -
! b W re:
g a noble gas activity vs. time in WCi . Mew al . dis t l . 23 x 10 rad a2 dis = (h) (3.7 310' .'/s/uci) (1.6 x to erm/MeV ) 6 pCi see MeV (100 erg /3. rad) (0.001293/cm 3 )(1 x 10 ,,3j,3 ) .
- J i
J 4 *
,_ -n
p 1 .
.g.
i
'. .~ *
- O NG s noble gas dose rate vs. time in R
~
L -- P All other varis' ales same as previously stated. (N!{ l NOTE: This un be rapidly accomplished by storing in calculator memory the resmit of all numbers, except
$ G, and then r-=114=- this number to saltiply by l each G velas for the 0.5, 2, 4, 5, and 10 mile
{ points (as shows on Table II am Fnefmam g 3,3) j 4.2.19 Detasadme whole body gamma dose st the site boundary
- t (0.5), 2, 4, 5, sad to mile potats by saltiplying the dose ,1 rates at these points (as does in sectica 4.2.18 and shows 1 on Table II on Eaclosure 5.*' by the dose assessment 4
8 period. (in hours) { NOTE: G values based'on a two (2) hour. dose assessment
! period.
1 3 4.3 Determine potentially affected zones based om vind direction using i Go table sa page 1 of 3 of Inclosure 5.6, and record os page 3 of 3 .
} ef t=e1==are 5.6. -
4.4 Detesmian levels of protective action by comparing projected doses to [-
~
EPA Protective Action Guides (page 2 of 3 of Esclosurs 5.6) and
! record em pega 3 of 3 of ,Eme.losure 5.6. .
! !4.5 Deteemian if asa-stagnating meteorological conditions exist by
] i i
observing meteorological strip chart data. If:
; j (1) Ins *==*=-= wind direction has not varied over 90* in the past j ==e (2) hours, and, -
3. (2) Instantaneous wind speed has not fallen below 10 MPE in the past .
] two (2) hears, them asa-stagnating conditions exist.
4 1 1 Record resmit om page 3 of 3 of Iaclosure.5.6.
's 4.6 Check resulta and inform Emergency Coordinator of your i
j recommendations.
'I 4.7 Whenever possible, sei14== environmental data in comparison with
'j calculated results to better determine plume dispersions. Record j environmental data om Enclosure 5.4 when available.
; 3013: Depending om meteorologic cenditions, field monitoring
'f teams may experience difficulty in f4nding the plume.
! ,Q Therefore, negative field results do not necessarily mesa 2 that radioactivity is not being released.
v i e 4
9
. 4.8 Calculated rssalts should be compared with those from the Crisis
, Hamagement Center (if accessible). Any discrepancies should be a
! , 7-resolved through recalculations and calculation step comparisons.
j '
. , - 4.9 IUstorical data shall be retained so that offsite dose trends can be .
] analyzed. li 4.10 Insare that Enclosures 5.4, 5.5, and 5.6 are prope::1y complaced and y resalts presented to the Station Health Physicist or his designee. { 4.11 Actual field messarementa of whole body doses will be compared to j whole body dose projections by the Data Evaluation Cocediaator. li 5.0 Eaclosares _. f 5.1 Table I, Two Bear Belative Concentration
- i 5.2 Table of I-131 Eqaivalent Time Detamined Conversion Factors i 53 Table of Noble Gas Time Determined Conversion Factors 5.4 Projected Exposure Data Sectios
] 5.5 Projected Impoeare Work Section - ) 5.6 Becommendations Data Section I,
5.7 Accident Assumptions Based on Potential l 5.8 Estiasting '*==*=i=sent Release Estas (P.F. 9.4.2) ' i 5.9 04:: (Tech Specs 04) User Decimentation 1
-b u >)
a q . I 1 2 1 j ; . - l
.+
q i I
^
i
,1 I
i 1 . . , l ~
)
0 I
. . _ . _...:..__~......_.:..._.......
- . . - . - . _ _ . . : . .. .c._ s .~. . '
f.
! , . .e .
Yh..-
~
e)
!*)
Enclosurm s.1 MF/0/3/3009/08 . ,
)
TABLE I 2 0005 EELATIVE COECEMTRATICII (CE) Stability Dietence (in sitee) , Temp. Diff('c) Close 0.5 1.0 2.0 M 4.0 M 6.0 7.0 8.0 9.0 80[ '
- l. < -0.6 '((f l.45-5 1.2E-6 5.95-7 4.15-7 3.2E-7 2.55-7 2.0E-7 1.9E-7 1.8E-7 1.55-4 4.5E-$ 1.3E-5 6.3E-6 3.95-6 2.75-6 1.9E-6 1.4E-6 1.15-6 1.6E-7 8.3E-7 1.5E-h '
-f.8E-7 (
- 2. -0.5 3.85-4 1.4E-4 4.95-5 2.7E-5 8.75-5 1.25-5 9.2E-6 7.35-6 6.0E-6 5.0E-6 4.35-6
- 3. -0.4 to -0.2 E
- 4. -0.1 to +0.4 E 6.9E-4 2.5E-4 9.65-5 5.5E-5 3.55-5 2.5F-5 2.05-5 1.6E-5 1.3E-5 1.lE-5 9.7E-6 i!
3.3E-5 3.0E-5 ll
- 5. +0.,5 to +1.2 F l.15-3 5.lt-4 2.0E-4 1.2E-4 8.25-> 6.35-5 5.1E-5 4.35-5 3.8E-5 '
0 1.8E-3 1.15-3 4.35-4 2.75-4 2.0E-4 8.75-4 1.3E-4 1.2E-4 8.6E-5 7.8E-S 7.3E-5
- 6. > +1.3
~ y
,e The temperature differentist la the difference in temperature between the upper and lower toeparature aamoore end is in degrees centrigrade. ,
These values are site-specific for HeCuire IIuclear Station. e (
.I i
i k
. - l O
9
. '4 .
~
IP/0/B/1009/08 {
- 1
,,,k c - :.
,' EscLosuus 5.2 "'
; tc i PAGE 1 0F 1 0 %
Table of I-131 Equivalsat Time Determined Conversion Factors i ancy i l Ties (hours after tris) TDCF. - . . - - - . . i 0-1 1.93 E-7
.i . ; 1.1 - 3 2.68 E-7 3 .
4 3.1 - 5 3.30 E-7
,t 5.1 - 7 ; 3.84 E-7
; 7.1 - 10 : 4.64 E-7 10.1 - 15 5.59 E-7 -
~
1 15.1 - 20 . 4.55 E-7
- 20.1 - 30 : 8.1,4 E-7
. n i
i I'
\. .'d /
30.1 - 40 i; 9.20 E-7
. 40.1 - 50 : 9.75 E-7
- I t
e !, 1 ;; . .. t ; ,.
~
2 -
) . ;
9 I j I ! j ; i . i t
) :
i . I 4 i ! . l -=. I
\
t
~w,or' e
m.
lt EP/0/f/1009/08 .- ENCLOSURE 5.3 " t I)b PAGE 1 0F 1 Table of Noble Gas Tian Determined Conversion Factors j (TDCFg)
.t .I 't 4 .
1 Time dumsrs after tris) TDCF 71 j 0-1 , 1.57 E-9 1.1 - 3 1.53 E-9
.q ;, 3.1 - 5 1.35 E-9 s
a: 5.1 - 7 1.31 E ' 5 7.1 - 10 1.54 E-9
.,' lo.1 - 15 1.7s I-9 15.1 - 20 1.90 E-9 20.1 - 30 '. -
1.93 E-9 . 30.1 - 40 1.94 E-9 O, 40.1 - 30
- f. , 1.84 E-9
' ( ,. . :- -l i
i *
's m ' t.
e e s G
.j .
e l s g.
~. j e
q - 1
]
EP/0/5/1009/08 I =Ct055aE 5.1 - PAGE 1 of 2 l I.f.;, m FROJECTED EIPOSURE DATA SEEET f! Time of trip /ehutdous hours after midnight. Date _
.i .
Time of ,.te=tattaa hours after midnight. Date .
] (All meteorological data is 15 minute averess)
,j Time (15 minate period ending time) hours after midnigh::. [' 030 Wind Directice 1) Upper tower degrees from North. [j, or 2) Lower tower degrees from North. !: Da0 Wind Speed 1) Laser romer Mrs j or 2) Upper teuer MPE AT 1) Lower to Upper tower 'C u or 2) For 1000 - 1600 -0.2 'C
- j or 3) For 1600 - 1000 +1'. 3 *C
- 4
. 080 Stability Class (AT and *=af m 5.1)
~~
i (Ts)on0 Temperature *C . c ,j. Convert *C to *F: 'F = (9/5)( 'C) +32 j Oa0 Frecipitatime, & inches /A time (
;l '
040 Balsase Enight = 33 feet
- i. ,
, Laek Race af/hr
- } . Ex. 31ds. nose ante 1/hr ij
.j .--
EMAN RELEASE CONCINTRATICES (Cg and Cg) (Fost-Ascident Cfor=4ammat Air Sampling System Samples) lI l f .s ll '* [; Groes cas (C ,) uCi/mi Lj I-131 Equiv. (C7) uC1/mi i
! Gas E ME7/ dis 9
UNEBOUR RELEASE CONCENTRATIONS (Cyg and Cg)
]
(IMF DATA)
!1 .
If IMF 39 (E) <L00 cym,
/*, Cg uCi/mi = EMF 39 (L) cpn _.,x 3.8 E-8 uCi/al/com
^ 2 Or if DtF 39 (H) > 100 cpm
( uCi/mi = DtF 39 (H) eps x 2 E-4 uCi/nl/cpa Q l g uCi/al = UfF 40 A epa /A time x 2.34 E-10 uCi/al cys/ min
,+ - -,,,-,w - ---- -- - .-, ,,,,-,--,. , --
,,,-e ,.,,,ne.,r,-n,-- -~,,--e ,,,-www-e___,ww-,,..,--e,vnee.mn,..,w,, , , - - - ....-m,_, --
.._. . _ 2 . ._. _. . ---_ . _ . _ _ _ _ _ - _ _ . . . . _ _ . . ___
a t #, 1 - sr/o/3/1009/08 . 1 . j ENCLOSURE 5.4 , t e Q^
- " PAGE 2 0F 2
...J J The (2) Hour Dose Committamat
'1 [j IODINE WDELE GAS
}
(Child Thyroid) 0.5 at. tas 0.5 mi. Esa ]_ i 2 mi. tem 2 c1. tan
- 7. 4 mi. tem
. 4 mi.- tem I 5 mi. Een 5 at. tas
,i
10 mi. tan 10 mi. , tas 1
J i , POIBF f M EAIX ICBINE CONCIETRATION t a y n2 ____. e
- i 9
% 9
. I
,j ___
4
.; s .-
5 .:a 1 1 Does Assessor Date a I .
, .r
- r. .
Y% 4 o,o'
_% ._m._. . . . - 8 -
\' ,.
. IF/0/3/1009/08 L
- { .
Enclosure 3.5 . Page 1 of 2 (.* ; .
.y; ' MEUAL CALCUMTION WORESEEIT l.
B. j Radio W a=1 release rate (q) 8 cao. Q.,, C1/sec = CyVW z t-E x 7.86 E-6 .... .._, M f'. ,f I J Om) . j gg C1/see - C7 xu x 7.86 E-6 .i . 3 ( q Ci/ses = (Cg +C g ) x LE~- x 7.86 E-6 i
; Dees Converstes fasters for whole body (DCFg) sad child thyroid.(DCTg)
/] -
, o I/hr/C1/es = 320 x I DCFg _
I
# s DCFCT = 1.85E6 R/hr/Ci/a 1 ~'
WERE: The information on this page is not& normally used. It is ,
' available if needed for working'with outside agencies. 'l i
4 t I
+
.a n. -
1 N)
l 't
! , ., (.
. 11P/0/3/1009/03 b-.
3, Enclosure 5.5 . T Page 2 of 2
- j. Q' 3 .
\d Dose Rate and Dese Calevi, l'hild Thyroid (Escord all C. as ,r 0.5. 2. 4. 5. and 10 miles in Ta' ale I) .
y; f]' Dg=DR x3 x TDCFg x 1 _zG s W I n . core is .. , _ , ..., - ii i Table I - Child Thyroid Dose Rate and Dose t.
.I N
il Dose Rate e Dose d Stored Time y Distance a Cale. Value (Ram / hour) Period (Ram)
!i S.3. 0.5 mi. m = x =
q .. a 2 mi. x = x = '}
~
" " =
4 mi. . x .
= x
= x
=
5 ut. s 1j . .3 10 mi. x = x = ['., [* r) s
.'~.r 2
G vaines based on a two (2) hour dese, assessment period. 'l Whole Body (Basord all G values for 0.5, 2. 5. and to miles in Table II). z2 x TDCFg x 1 xG
- j ,
DUE = Dgg - i 9 l' i Store in a=1~1= tor maeory . [.] 1 Table II - Whole Body Dose Rate and Dose w
'4 ,
Stored Dose late Time Dose , 9 , Distance G Calc. Yalue (Ram / hour) Period (Rem) x = x = l _ _ S.I. 0.5 mi.
* " " = '
'I 2 at. x = x
" " -=
mi. 4 x = x
" " =
I 5 d. x = x i a a
.* to 31, 2 . x = .
/ G values based on a two (2) hour dose assessment period, t
j
- - - - _ , . . . - . . - , . .,_,er.---,4-, ~.--.,,..,--...m,-4.._.r,,,mm.., ---,~,...----c. - ,-.,_-,-..,-m -.,m---
i. . t, s ,p ., .* l HP/0/B/1009/08 _
! ,.?k ' Enclosure 5.6 l,
s ) . Page 1 of 3 1 l, ., 6) Determine affected areas based on wind direction fo m the taale below: (i ,t h ,o Utad (degrees free 0-4 4 - 10 j Direction North) Hile Mile Recommendation Reca===adation. . [. . ,i... _ . . . . . . . 0- 22.5 _ See Note 1 S.E.T _. F.; 22.6 - 45.0 E.S.0
,i 45.1 - 67.5 E.S.0 tj ,
67.5 - 90.0 S.Q.P 90.1 - 112.5 _ S.O.P.E ! .",- . 112.6 - 135.0 -. S.Q.P.E __ l.... .. 135.1 - 157.5 0.P.E.I 157.6 - 140.0 P.E.I.J
~
180.1 - 202.5 P.E.I.J.R.G 202.6 - 225.0 E.I.J.H.G { K.s 225.1 - 247.5 I.J.R.G.F l i _._. . _ . . _ 247.6 - 270.0 - - J.R.G.F . 270.1 - 292.5 ll G.F ; 292.6 - 315.0 I'G.F.E l; 315.1 - 337.5 l G.F.E l>- , . ll - 357.6 - 359.9 F.E.S _ j 2 3DTE 1: Areas A,5,C.D,5,N.I.,0,1 will be the rec-dad I
. areas if any action is taken in the 0 - 4 mile radius of the plant. This rec h ation is 4 '--- e of wind i direction.
i . l f . l l l 1
, - - . , -, -,n-
- - - - - _ - _ . . _ _ _ _ _ . b. _ _ _
i HYl010/10 onIos~ Ensl:sste Lb
~
~
~
P.ge 2. .f 3 )
~
- t -s
\
bO s y 122 is, s! J 2 - - 4 . sit li: 1g..8 . !! i
*es.3 :
=m. 1.
i
. 3 e
3 i 2 lsts! a 5: gy i 3 e
= 3 J
1 8 !=j s3 1.21!
- 5 j_ 113j =]3sj111.a l'js.l, }tilishi ! {
s [ . 3._ ' 8
} 8 t' i 5 15 d
ll 1 l ie li i-l}g !! !ji, 3 ,; u
- } j4 1 3 . jaj 34 .3 m -
=
1 3 3j is 38 41 8 1. " i 21 3 12 -* ~!!! ! 1 l 's 1 11 2 32
~
I 1 Il s 1 1
}1 i
!5 1:= 1
- 1
' j' ja[3i (( {e 1 i l 1 : *' w s[}i j
.i ij. _ l . sa[1 '
,]I lij3 i -
- J' o
1 .j 1 i 1 13 i i lii
!i 1
lal
- i ti i
.(
u '- Il IIi-f( 1 -
~ ~ ~
l a. I 11.31 11 1 1 l- 3- ai !!, - 1
- 1
- l i1~
Li 8 ,, (( 2 lij Je : 2 - 11 lj; g! 13 i , -- ., ae a 33:
} *. bb bI $4 i; I, I, f, it I, I ii =i la 1- 2 r
2 le ,i , i l,i s s-
, i 3 A 1.- aa sa ar a . e i
/ . sers e un 6
L 1
--e-_-m,,,__ w e, .,m n e y-wg w egw-,, ,%-ewwm,,,-~-,-.e.-my
- -...:. - _ _ . = - - _-
~ .
= -
ar/0/3/1009/08 Enclosure 5.4
/ Page 3 of 3 l
, .r,-d g n:.y ! 0 - 4 miles i . a c - dad Areas _ .i 8- M ad Population 1 } 4 i 4 - 10 miles n., M ad Areas __ _ l n.,-----a.a population i! ^i 2 Non-etagnating meteorological conditions do _ /do^not exist. J J j , Signature
;7 30TE TO IMERGENCT C00EDINATOR:
. . .;2 If the release is projected to end within one-half (h) hour, and
;r 7-*1=g ancierological conditions antat. consider not
! r=a====ading an evacuation if the plume will have left the Emergenc '
i Protection Zone:(EFZ) before the population could evacuate. i ~*
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33ctasung 5.7 Paes I of 3 p accInsur Awd= i MSID QN POTIETIAT. '-- 1 J9 . W ~ Destas Essia Acetdeas assimas TID-14H4 release of fission . h to the aus-S 8 .. * . 1 (1) lone et all eere ashia ses estivity ,,, ,.
- (2) SOE ed all eere Zodian asM 1sith plate oss of half of thas,,,,, ,, ,
t=1====d- Therefore, 23E ed the Zodias assivity will bs,in the j 3
=,--=*-* ansesphere. . ..,
.! I a ~~' 1 - ligesFof Ramster Caelmas asemos the release of ese remeter coolaus velens 4th .. I; * " sable gas and Zedian assivity assoaissed with operasieuNriiEECTE' , i t. feel failmen before una relaneo. t 1 ] Gee Activity assues that there is eladdias. failure entfisians to. 1 produsas in the gne say of the , p - -- asiosephore. Ar.====d is alas Ices of 105 ei all eene noble sat easivity,and 105, , j of all care Zodian activity to abs *==*=4====* -
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(a) 7320 al/k lashmen from the pump eenis and valves of the Eccs. is. ,,5, , , the ammiliary tusadias. , ,,,
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L (b) Amr Endias partities fasser ed 0.1 is used to d====4== the mamps. h Zod.ine relanned to the mui11ary building ===rh==o. . (a) as are41: sa taken for the YA abarcoal filters besamme tbs.Ya. . .. .. .
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a BFpeise laskage is the frassdam of the total =*=4-* 1ankage,that, bypa'ases.. , . the aamulas amL essapes se the a=="Th="o unfilmared., ... .. w l - same ==-et- et typass Iankegs paths are (1) tankage skremsk ===-=< , <='==*- valves that do not sens, propenly. -
- I
. (D Lankage assumi che equipmans hasah seals. . n , , ,;. .,
Air MeGuhre the ===*=4- bypees lankage is 73 ei the total containment. lankage
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- p 15/0/0/1009/08
. . '.,, , \ Enclosure 5.S Page 1 cf 7 jl namn muma nT s a CAsz or Con.-=T rmuz
.m 1 AT IITHE QCollE '
NUCIZAR STATION OR McGUIRE NUC2Ut STATION "
\
4 p%g
'M In any accident situation in lving a release of fission product activity to
- the containment atmosphere, there are two major concerns:
i .
- 1. Rains able to predict po'-*4=1 offsite doses in ha event containment
', does fail. The E - .y Manager may base a decision to evacuate or not on the potaatial effect ta the public without any indication of offsite ! releases.
i j 2. If aa=e=4-e does fail, it is necessary to estimata actual releasa l ratas in order to calenlata actual offsita doses. 1 1 To do either of the above requires an astimate of CFM leakage ratas versus
' size for a rsage of.J:entainment pressures. In order to calculate flow, either instantaneous or on a time basis, several basic assumptions must be riada j concerning the process. Theseasseptionswillte.udtogvethemost j conservative answer.
To e=Im1=ta instantaneous flow through a short pipe, ha in occase's case, or th.4 a " thick " orifice", as in McGuire's case, several assumptions
, are reqaired. These assumptions, with sa explanation, are: ,
i 1. Fallv Turbulent 71sw - In Ocomes's casa, since the pipe friction j c factor decreases with increasing velocity, the most restrictive case i rt is fully turbalast flow. In McGuire's case, the flow e-**4ciant is D.) most restrictive in the fully sarbalant region. , .
- 2. Haziams Ezoected Temperature - In both cases, since temperature is the i
sels factor affecting density of air, at a given pressure, a ==w4== temperature shosld be assumed. Since density dec=sasas with increasing j! temperstnre, the bisher the temperandre the higher the flow.
- 3. 95% Relative Inmidity - In both cases since the hishast flow rata is
; eem-M with the lowest s;-4*4c gravity, the lowest specific gravity
>! should be assumed. Since the specific gravity,of an air-water vapor is
- most closely approximated by the ratio of the density of water vapor to
! that of air, the higher the relative humidit:y the lower the specific
. gravity.
i i In addition to the preceding assumptions, several other assumptions mac be made before one can calcula a time dep-ad-at flow. These assumptions, with an explanation are: ,
- 1. Uniform - State. Uniform - 71aw Process - This typre process applies in
! boca cases and it is based on the following:
5 f" A. the control volume remains constant rela:.1ve ts the coordinata j f***** l 3. The state of the asss within the cent.ci volume may change with in but at ::7 instant of time the s ata is uniform throughout the entir:: control volume. , I
. . . - - - - - - - _ . _ _ _ J
. . . _ - -.u...- - - - - - - - - - - - - - - - - - - - - - -
.. i, EP/0/3/1009/Os
, uneta-ure 5.s Page 2 cf 7 C. .tha state of the mass crossing each of the areas of flow on tha control surface is constant with time although the mass flev gatas
{[ o ', y any be tzme varying. " j ~ l.& M 2. Ruotare Occurs At End of Accident - In both cases this is assumed in order to have a basis for initial conditions 6sids contalmaant, i.e. , j mszimum pressure and tamperature and nagligibh haat input. i
- 3. Process occars Adiabatically - ath cases, since it was previously assumed that as hast would be added W a- the release, the adiabatic assumption is the most limiting' case. This is shawa by the Second law j of Thamedynamics for a control volume, which for this case is: _
! [*1 8 2-51*1[,,*I"a*e"l'*hd*-
~
~ Considering the choices, either Q = 0 or Q < 0. If the lattar 4.:
j} gssumed,itwouldtandtodecreasE*6**whichwodlI*notbeas.limitingas I k.v.=0. 4 4. FlowoccarsIsentronicalid-Inbothcasessincef2.cionaleffectsare i n==H P le and it is bains assumed no heat transfer oceses, it is intaisively obvious that flow cza be assumed isentropic. I
- 5. TheItizzareBehavesAsAn!IdealGas-Inbothcasesthiscanbeassumed
', because at low pressure, regardless of tamperstare, the Ideal Gas Law yields good accuracy.
g i Attached are graphs that illustrata che estimated leakage ratas for Osanas
! 'v and McGairs. . In osones?s case 'rea flow versus tima g=sph illustratas the l s1as dap== dane flow that weald occur if the containment was ishized to 60 peig it the time of the fa11ers. In McGuire's case the flow versus time %rspL illustrates, the stes dependant flow that would occur if the co=*=we was pressurised to 15 psig at the esse of the failure.
j In both cases the opening ' sis'es are that of Mad *1a 40 -Pipe. ' 'a . . . .
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Enclosure 5.s Page 3 cf 7 EQUATIONE N R McGUIRE =
- - O Instantaneous now q'" =678 Td 2 l,139,.
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Vv. (Refer to Crans Tach. Paper M10) QF 8 l
.1 b re: g',a 3tandard cubic feet per minata Y = Net azpansion factor (from Table A-21)
{ d = Inside pipe diamatar, inches 3 ' i' C = n ow coefficient (from Table A-20) ' 4 Pt ' = Absolate pressure inside containment, psia
; T1 = Absolute tamperatura, *R j -
s , = specific sravity of the sas 1 S =1- .N I Pg 39 3 s ,.
; 1 -
Eg = Relative hamidity . I j (~N Pg = Saturated vapor prussari of stama at T, conditions
; vv ) -
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- 1. In dee= M aint C, it is assumed there exists fully turbulant flow:
now versas Time N = MET 1 = S3.3A Pyk = Constaat k = 1.4 - j TV k1 = Constant 3 I (Rafer to Crana Tech Paper M10) ap W = .325 Yds t. s N iihare: W = Mass floe anta Ibm /sec 3 Y = 5et expansion fac.or.(from Table A-21) - [ d = Inside pipe A4mtar, inchas a i C = now coeffient (from Table A-44) e I-
.i ,
( , y = Specific volume i, _, Assumptions: The assa flow rata remains constant with a short interval at stas.
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< > EP/0/3/1009/0 . Enclosure 5.5 - Page 1 of 1
; ,c OPERATOR AID C0tfPUTIE (TECE SPECS 04)
~
USEE DOCmfE3TATION j 1) ' Tech Specs 04' can be accessed thru CAC terminate in either the 1) Technical Support Center (TSC) or the 2) Computer Room. I 6 There are OAC terminals for both Units 1 and 2. Be certain to use the OAC te M n=1 for the approprince Unit.
. All necessary data on the ' Tech Specs 04' computer printout will be 1
- under the 'Invironmental Systems' heading.
i . { 2) Procedure a) Check to see if the READT key on the printer is fully
,05/077 LINE 411n=4n=ced. If not fully illuminatal, press the key one time and release.
- i. h t .
b) Press the Tech Soecs key of the OAC terminal. (Key will - 411n=4n=ra). ,,
.I
- r i c) Type 0 4, using the blue numeric keys of the OAC terminal.
f d) Press the Print key of the OAC terminal. (Eey will illuminate). + l l t e) Press the Enter key of the OAC terMnal. (Key will ; 111cainete). Upon pressing Enter, printer will print data. i 4 l f) When printer steps, press the 2EADY key on the printer to ON/0FT LIHE -
') illuminate only the " READY" partion ,of the key.
-' g) Press the TOP OF FORM key cu the printer three (3) tines to advance paper. Tsar off data sheet. 1
I4 l . t
! ,g . ' D-WM Form 34731 110-81)
(Formerty SPD 10021) i DUKE POWER COMPANY (1) ID No: HP/0/3/1009/09 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD t. Incorporated (2) STATION: McGuire Nuclear Station
' Release of Radioactive Materials Through Unit vent (3) PROCEDURE TITLE:
I Exceeding Technical Specifications [ (4) PREPARED BY: #hd. DATE: ,n 1i c I r1
't (5) REVIEWED BY: A,#
- DATE: /o -/p- f 3 V
Cross-Disciplinary Review By: N/R: A> (6) TDtPORARY APPROVAL (IT NECESSARY): i By: (SRO) Date:
,m y -l By: Date:
J p-l (7) APPPMED BY: /,.= .7. M .? 6 eff Date: .c/N/77
; < i (8) MISCELLANEDUS:
Reviewed / Approved By: Date: _
~
Reviewed / Approved By: Date: 9
?
4 t a s i I t
- I gN
_ _ _ _ _ . _ _ _ _ _ _ _ _ _ - ____2.__ _ . - _ - - - - - _ - _ - - - - - . - - - - - - -
4 s4 z;p& t AY IMAGE EVALUATION
,t 4
\n TEST TARGET (MT-3)
////#// /.,7/gf Ny~fflit'g7/ Y W sy,, NQ/ lllQs
+ %
,.o -
EM li,i [:c NS I B2 x l.25 1.4 1.6 4 150mm > 4 6" -
+ek*%// /!4%
# $///
v
$o[4.
Q 4p
Y , 1 sh4 o Yht\k,'M c'I % g),77/N'l IMAGE EVALUATION TEST TARGET (MT-3) [\/ ,N .[ 6
- f;g
%s W' 'k,
_ l_jjg g24 a 1,1 fE Me
!!J1 1.25 1.4 1.6 4- - 150mm >
4- 6" >
/
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%,, f+4 %
9,.7Q$ g,,
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- _ ~ _ . _ _ . . . . _ _ . _ . _ ~ _ . _ _ _ _ . _.
.. s e
HP/0/3/1009/09
.) g DUKE POWER COMPANT l McGUIRE NUCLEAR STATION RELEASE OF RADI0 ACTIVE MATERIALS THROUGH UNIT VENT EXCIEDING TECHNICAL SPECIFICATIONS .
^!
- 1.0 Purpose
; This procedure describes the method for calculating the potential d offsite dose rate and dose following a release of radioactive materials through the unit vent. In addition, this procedure can provide warning nessage infornation to be given to state / local j agencies.
2.0 References j 2.1 Station Health Physics Manual, Section 18.2; Environmental N Monitoring for Emergency Conditions. 2.2 Health Physics Manual Section 8.2, Exhibit 8.2-2, Page 2 Unit
. Vent & Waste Effluents Flow Data Form.
l 2.3 10CFR20, Appendix B. Table II. - '8 2.4 McGuire System Descriptions.
- i
- 2.5 Unit Da.a Book
.: y 2.6 NRC Regulatory Guide 1.4 2.7 Offsite Dose Calcula, tion Manual (ODCM) 2.8 HP/0/B/1009/05,,First Response Evaluation of a Reactor Coolant j Laak Inside Containment. j 3.0 Limits and Precautions j 3.1 This procedure is being used in an emergency situation which could result in evacuation of areas surrounding the plant.
.} The procedure shall be fully understood and calculations shall be done carefully and accurately.
f ' 3.2 This procedure is written for use under abnotaal conditions a which could involve extremely high radiation levels. Only the
' Station Health Physicist or his designes shall m thorize the f use of this procedure when needed and snall, provide j spyropriate surveillance and control of people taking samples.
. 3.3 This procedure is a backup method of dose assessment to the
' Class A Atmospheric Dispersion Model' computer code available
-, to Health Physics. personnel and as such shall only be used in s
'J
en t ' b Pcg2.2 the event this computer ode i not available. Warning i ,.3 message information. however, may still be generated from this o .n
<j, procedure. i o .' ?
3.4 Check that the counting equipment to be used has been 5 calibrated and daily response checks have been performed. 3.5 Individuals collecting the samples shall be aware of the
] possibility of airborne contamination and high radiation
,$ levels in sanpling areas. Use protective clothing, gloves, J - respiratory protective equipmeet, portable shielding, high
. range dosimeters, and survey instruments as determined by Health Physics.
3.6 If action is taken in the 4 - 10 mile radius area per ] reference 2.8, then wind direction shall be rechecked every 0 fifteen (15) minutes to ensure that additional sectors have not been affected. Once a sector has been added to the list.
.it cannot be removed from the list. .
3.7 Projected doses shall be compared to the Environmental Protection Ageccy Protective Action Guides to determine l'evels of protective action.
+
i 4.0 Procedure
- - 4.1 The primary method for the determination of offsite dose I assessment is by using the ' Class A Atmospheric Dispersion Model' computer code. Refer to the ' Class A Atmospheric Dispersion Model User Documentatioc' for instructions on the use of this code. If the computer code is not available, continue with the manual procedure.
4.2 Acquire the following information and record on Enclosure 5.2 and/or 5.3. NOTE 1: Some ci the following information can be obtained from the ' Tech Specs 04' program of the Operator Aid
, Computer (OAC). All information available in ' Tech Specs 04' shall be denoted in the following
, procedure by a '(TS)' ro the left of the section i number. See Enclosure 5.5 for steps to access ' Tech Specs 04'.
t 9 m .,f 4
- _ _ . - -- --- - 2 --. . - - - . -_ ..- ': . .~. .
.i s ,
i Pegs 3 l
- NOTE 2: Standard warning message information to be given to state / local agencies shall be denoted in the i
3g following procedure by a '(W)' to the left of the
;i section ntmber.
a Meteorological data shall be obtained in the order NorE 3: a
- of preference listed in Enclosurs 5.2.
s. J NOTE 4: Use fif teen (15) minute averages for all d meteorological data. 4.2.1 Time of Reactor trip / shutdown (hours af ter midnight) l .] and date.
.; 4.2.2
- Time of calculation (hours af t.c nidnight) and date.
4.2.3 Sample time (hours after midnight) and date. I ) 4.2.4 Wind direction recrrded in degrees from North (upper tower). Lower tower wind direction shall be used only if upper tower data is unavailable. (m) 4.2.5 Lower tower wind speed (MPR) (W). Upper tower wind
~l direction shall be used only if lower tower data is unavailable.
4.2.6 Ver;:1 cal temperature grad one or AT*C (Lower to ta n j T
;} Upper tower) from the -4 to +8 scale oz the
meteorological temperature strip chart recorder.
NOTE 1: The above information is used along with
!l the Table on page 1 of 3 of Enclosure 5.4 f
and map lprovided in Technical Support >! Center (TSC) o determine areas affected 1 by re1 ease. NOTE 2: Plume direction is 180* opposite wind I ]. , direction. III 4.2.7 Stability! class (A.B.C,'D E.F. or G) from Table I i i (Enclosure; 5.1) . '
- I ) 4.2.8 Ambient air temperaturei (*C). . Re ord in *T where:
*F = 9/5 *C % 32.
III 4.2.9 Precipitation (Ainches!/btime)
! ID) 4.2.10 Dischargeflowrate(F)ffromun'itventshichis j obtained by multip1ying,the fractional flow from totali=er by 170,500 to get .' low in C7M. (i.e. 952 flow = 0.95 fractional flow).
,N
.J i
.i t j Pese 4 i \
- t NOTE 1: I the unst vent flow totalizer is
! inoperable, flow can be determined by t ; D. ,
4 J : .1 reference 2.2. l .s V (WM) 4.2.11 Release height of unit vent is 142 feet above yard elevation.
$ NOTE: Information in sections 4.2.12, 4.2.13, l and 4.2.14 is not normally used. It is available if needed for working with 3
outside agencies. I 4.2.12 Discharge concentrations (Cg and C7 ) from Health Physics sampling of unit vent; or EMF data if sample (4 i results art. not available, as follows: Li
-1
- .I If EMF 36(H) <100 cym, 1 a) Cg = IMF36(L) cpu x 3.8 E-8 or if IMF36(H) >100 epa,
. b) Cg = ENT36(R) cpm x 2 E-4
- i j g c) C 1
= EMr37 4 c,a/4 time x 2.34 E-10 i *3/ Where: 'i Cg = noble gas discharge concentration in uCi/s1 C = I-131 equiv. discharge concentration in 7
j . uC1/mi 3.8 E-8 = EMF 36 (L) correlatica factor in t uCi/al/cys from reference 2.5 q 2 E-4 = EMF?6 (R) correlation factor in j uci/al/cyn from reference 2.5 i ' 2.34 E-10 = EMT37 correlation factor in uC1/al/cys/ min from reference 2.5 lj N ) 4.2.13 Calculate radiological release rate (Q) in C1/sec using the following formula: l;
=C g x F x 4.72 E-4 l ,) Qg b) I" I* * '*
t 't .
, c) Q.= (Cyg + C7 ) x F x 4.M E4
, - ,,m.- . - , . -, , , , - . . - - ,
__ .____. . . _ . - . - . i 1 i -[ st \
- i -
, Pcg3 5 Where: l
_l p.*3.;) gg = nome gas radiological release rate in C1/sec
; 1
] Q g = I-131 equiv radiological reicase race in C1/sec l Q = radiological release rate in Ci/sec
; 4.72 E-4 = 2.83 E4 ca sfggs x 1.67 E-2 min /sec x 1E-6 Ci/uci All other t ariables same as previously stated. .' 4.2.14 Calculate dose conversion factors in R/hr/Ci/m3 for j whole body and child thyroid using the following
) formulam: al DCFgg = 0.5 x 3.7 E10 x 3600 x E
- 1.3E3 x 100 x 6.25E5 Ei DCI , = 820 x I
. a) 4.
Where: ms l j,'; - DCF WB
= Whole body dose conversion factor in W 1/hr/C1/m8 l 0.5 = conversion from infinite cloud to semi-infinite cloud whole body dose
.: . i I = average Mev/ dis from Count Room data
- l . _ _ _ _
n . .} NOTE: If E cannot be obtained from sample ,j results, the following values shall be O used. Hours from Trip E in Mav/ dis e
< 12 0.40 3
=> 12 - 48 0.20
> 48 0.10 1.3 E3 = density of air in g/a8 l Conversion factors:
t' 3.7 E10 dis /sec
- C1 3600 sec/hr
^'
. < - 100 erg /g
- rad
/ 6.25I5 Mev/ erg
8'*= mm, .,4 .-. . . - - . - . . w,.m- . I
.t t
, . Ptg3 6 DCFg = 4.39E-3 x 1E12 x LE-3 x 0.422 j b) DCFg = 1.85 E6 3_ _
{ -l' yyage. i j ' DCFg = child thyroid dose conversion factor in R/hr/C1/m3 4.39E-3 = f nhalation dose factor for child thyroid l in ares /pci. from reference 2.7 i 0.422 = child breathing rate in a8 /hr, from reference 2.7 }
- K Conversion factors:
d IE12 pCi/Ci . LE-3 rad /arad' 4.2.15 Two (2) hour relative concentration (CR) in aph * ), sec/a8 from Table I (Enclosure 5.1) at the site 4 i boundary (0.5), 2, 4. S. and 10 mile points. Record 1 on Table I and Table II of Enclosure 5.3. 4.2.16 , Determine child thyroid dose rate using one of the I following formulas:
;; KOII: If C values is determined from unit vent
'] 3 ll Tj sampling, use the following for miz:
ji ,) Dg = 874 x F x C x 1 x CE 7 ii ' w NOTE: Calculations are not required if (l discharge concentration is less than t l: 10CTR20, Appendix 3, Table II (I-131, o II-10 uci/al; Ie-133, 3E-4 uci/al)
'i
'! 'Aere: l Dg = child thyroid dose rate in Rem /hr. 874 = 0.422 =8 x 4.39E-3 area x LE6 pCi x IE-3 ren x 472 al/sec/Cni
, he pC1 uC1 aren i!
F = discharge flow ra:e in CD8 (section 4.2.10) s .
-w' l
l l
_. m . _ .. - --._,w,-..-.,.mm.. _ .m_ ._
.{'
9% \
! !. Pega 7
.. C7 = I-131 equiv. discharge concentration in uCi/al'
, (section 4.2.12)
,, W = windspeed in sph (section 4.2.5) 1 -i:1 l G = Two (2) hour relative concentration in aph
- i sec/as (section 4.2.15) d 4
{j OR NOTE: If EMF readings are being used, determine j child thyroid dose race using the , following foramla: l.
- 1 j b)
Dg = 2I-7 x EMF 37& cum x F x 1 L 3 Atime W d 4 Where: h 2E-7 = 874 res*al'a *s min x 2.34 E-10 uCi* sin 8 1 uCi*hr*ft *see al
- cpm
.j EMF 37Acpu = cnange in cya per change in time (min) ., Atime
;I !; NOTE: If ' Tech Specs 04' data is used, dete'rmina ll A cys from two runs of the program 5 I
l ainutes apart (A Time = 5 minutes). V All other variables same as previously stated. jj
- 4.2.16.1 Using one of the above equations, l ,I determine the child thyroid do-se rats at
[ the site boundary (0.5), 2, 4, 5. srd 10 ?j ,_ mile points. (, NOTE: This can be rapidly accomplished
.1 3 by storing in calculator memory j
the result of all numbers, j except G , and then recalling j this number to multiply by each
. G value .for the 0.5, 2, 4, 5, l and 10 mile points (as shovu on Table I on Enclosure 5.3).
} 4.2.17 Determine child thyroid dose at the site boundary (0.5), 2, 4, 5, and 10 mile points by multiplying the dose rates at these points (as done in section 1
8 J l
.9
.s )
fcg3 8 l-4.2.16.1 and shown on Table I on Enclosure 5.3) by l the dcae assessment period (in hours). [$3 NOTE: CH values based on a evo (2) hour dose t ., i assessment period. , l ( ) 4.2.18 Derarmine whole body ganma dose race using one of the following form:las: NOTE: If gg value is determined from unit vent j . sampling, use the following formula: c 3 b =
- 3 x CR a) wB 0.387 x F x CNG
- W s,
h -l
- . Where:
;t .?
4 D UB
= Whole body sww dose rate in Ram /hr.
?] Jj 0.387 = 820 E*m1* dis x 4.72E-4 a s ,g, hr.uC1.Mov ft'.sec 1 4
- ! E = average Mov/ dis from Count Room data
,i NOTE: If E cannot be obtained from sample I results, the following values shall be
' n l' used.
.l _
- j Ecurs from Trip E in Mov/ dis
!! < 12 0.40 12 - 48 0.20 i1 , > 48 0.10
- I All other variables same as previously stated.
t
- .j OR NOTE: If ENF readings are being used, determine 1
d whole body dose rate using e-m of the ij . following formulas: l If EMF 36(H) < 100 cps,
- = 1.43E-4 x EMF 36(I.) cpm x F x Y x 1,, x CH 4
b) WB W
] Where:
I 1.47E-8 = 0.387 R*r:8*m1* dis
- min x 3.8E-8 uCi/nl/ cpm hr'sec*;Ci*Mev'ft3 9
*m-- T- -*---- - . - - w -. 9 - --e- g -ey--e.-q--w -
r ---iw y yp.we -p - m w--y- es.- - -y-. -g-----m -- --% --w-%9 -----v' vy -> ww- * --m'- w- -.er-n
.. \ ; Pcg3 9 All other variables same as p'reviously stated.
dh Or if DfF36(H) > 100 cpa, j Q:g -
,)
= 7.74E-5 x Df736(H)cpa x F x E x xG 1
1 1 Uhere: -i 2 7.74E-5 = 0.387 1*a8 'al* dis *ain x 21-4 uC1/al/cys 1 l3 hr*sec*uCi*Mav*ft8 H
- j All other variables same as previously stated.
d 4.1.18.1 Using one of the above equations, I determine the whole body dose rate at the ] j site boundary (0.5), 2, 4, 5, and 10 mile - ] points, j IWfE: This can be rapidly accomplished by storing in e=1-1= tor w ry j the result of all numbers.: ) 3 except 3 , and then recalling this nuabar to multiply by each ]O] q
~
3 value for the 0.5, 2, 4, 5 and 10 mile points (as shown on p Table II on Enclosure 5.3). Ono 4 .2.19 lj Determine whole body gaar.a dose at the site boundary
- j (0.5), 2, 4, 5, and 10 mile points by multiplying ,
j the dose rates at these points (as done in section j 4.2.18.1 and shown on Table II of Enclosure 5.3) by the dose assessment period (in hours), j NOII: G values bued on a two (2) hour dose
. assessment period.
4.3 Octermine potentially affected zonas based on wind direction
; using the table on page 1 of 3 of Enclosure 5.4 and record on i
j , page 3 of 3 of Enclosure 5.4 I - 4.4 Determine levels of protective action by comparing projected doses to EPA Protective Action Guides (page 2 of 3 of l1 l! Enclosure 5.4) and record on page 3 of 3 of Enclosure 5.4. !! 4.5 Determine if non-stagnating meteorologiesi conditions exist by 3 observing meteorological strip chart data. If:
}
. v
.= ,
Peg 2 10 (1) Instantaneous wind direction has not varied over 90* in the past two (2) hours, and
; (2) Instantaneous wind speed has not fallen bclow 10 MPR in the past two (2) hours, then non-stagnating conditions exist. Record result on page 3 of 3 of Enclosure 5.4.
4.6 Check results and inform Emergency Coordinator of your recomendations. l 4.7 Whenever possible, ut!Jise environmental data in comparison with calculated results to better determine plume dispersions. 2 Record environmental data on onclosure 5.2 when available. NOTE: Depending on meteorologic condicions, field
- sonicoring teams any experience difficuiry in finding the plume. Therefore,. negative field
[ results do not necessarily mean that radioactivity is not being relo. sed. 4.8 Calculated results shd.1 he compared with thosa from the Crisis Management Center if accessible. Any discrepancies f shall be resolved through recalculations and a=1 ~1= tion step i;
} comparisons.
4.9 Historical data shall be retained so that offsite dose trends { i can be analyzed. .
; 4.10 Insure that caciosure 5.2. 5.3, and 5.4 are properly complaced
, and results presented to Station Health Physicist or his designee. ,
j 4.11 Actual field measurements of whole body doses shall be
, compared to whole body dose projections by the Data Evaluation y ,
, Cocedinator.
5[.0 Enclosures 4 5.1 Table I. Two Hour Relative Concentration i 5.2 Unit vent aslease Data Sheet 5.3 Manual Calculation Worksheet i i* 5.4 Recommendations Section l- .
}
l' 5.5 OAC (Tech Specs 04) User Documentation. e f g g . h i
.- .. .-..,,-,m- - - . - . _ , , - , . - , . , , . . ,
.,.,y--- .-..------e,,wy - e--w-y- ---wr-m'---'--'-'~-----+y-'g'-
.. w,. . .. .- .r E . J a '. '. . - . . . . . . ,
.......J. . . .d. . . . u O '.J ' - 4. * '. t .: T.u i . . , .
s . . , - n . i
\ Q} '.Y . .),
Enclosu. .I IIP /0/B/1009/09
' TABLE 1 i 2 HOUE RELATIVE CollCEMTEATI005 (CH)
. Stability Distance (in elles) i Temp. Diff(*C) Class 0.5 1.0 2.0 3.0 M 5.0 6.0 7.0 8.0 9.0 10.0
~
!. < -0.6 A 1.4E-5 1.2E-6 5.9E-7 4.lE-7 3.2E-7 2.5E-7 2.0E-7 1.9E-7 1.8E-7 1.6E-7 1.5E-7
- 2. -0.5 C 1.5E-4 4.5E-5 1.3E-5 6.3E-6 3.9E-6 2.7E-6 1.9E-6 1.4E-6 1.lE-6 '
8.3E-7 7.8E-7
- 3. -0.4 to -0.2 D 3.8E-4 1.4E-4 4.9E-5 2.7E-5 1.7E-5 1.2E-5 9.2E-6 '7.3E-6 4.0E-o 5JR-6 4.3E-6
. 4. -0.1 to +0.4 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 1.lE-5 9.7E-6 :
- 5. 40.5 to +1.2 F 1.1E-3 5.1E-4 2.0E-4 1.2E-4 8.2E-5 6.3E-5 5.1E-5 4.3E-5 3.8E-5 3.3E-5 3.0E-5 f
- 6. > +0.3 C 1.8E-3 1.lE-3 4.3E-4 2.7E-4 2.0E-4 .1.7E-4 1.3E-4 1.2E-4 8.6E-5 7.8E-5 7.3E-5 l
i The temperstare differential la the difference in temperature ] between the upper and lower tempera:ure sensora and is in degrees ' centrigrade. t These values are site-specific for McCuire Nuclear Station. i i e I l l
^'
___..-.c.-___ _ - _ _ . _ - _ . _ _m . _ _ . . _ . . . _ . . _ _ . a r - HP/C/3/1009/09
- i Enclosure 5.2
'! 4. . . Fage 1 of 2
- ? w .
i UNIT VENT RELEASE DATA SHEET Time of trip / shutdown hours after midnight. Date Time of a=1 -1= tion hours after midnight. Date Sample Time hours after midnight. Date (All meteorological data is 15 aiuuta average.) (l 'ine(1$ min. period ending time) hours after midnight. n~ l (W) Wind direction 1) Upper tour degrees from North p, a or 2) Lower tower degrees from North .i ' .j . (W) Wind Speed 1) Lower tower MPii or 2) Upper tower MPH d AT 1) Lower to Cpper tower *C 'I or 2) For 1000 - 1600 -0.2 *C
', or 3) For 1600 - 1000 +1.3 *C n
- l (W) Stability Class (AT and Enc. 5.1) lj (TS)(W) Temperature *C t': '7 = (9/5) ('c ) +32 = 'T ll '
.4
)
(W) Precipitation A inches /A time CFM (Totaliser fraction x 170,500) (TS) Unit Vent Flow (F) (W) Release Height = 142 ft. . l i KNOWN RELEASE CONCENTRATIONS (Cyg and C7)
; (Vent Samples) -
f Gross Gas U*g) uC1/mi
) I-131 Equiv. (C g) ~ uC1/nl l _.
I Gas E Mav/ dis j UNKNOWN RELEASE CONCENTRATIONS (C NG had C7 )
.i (EMF Data) y 17 EMF 36/H) < 100 cym,
[ Cg uC1/n1 = EMF 36 (L) cpm x 3.8 E-6 uCi/al/cpe Or if EMF 36(H) > 100 cps i C uCi/mi = EMF 36(H) cpm x 2~E-4 uCi/ml/cpc NC C . uC1/al = EiT37npa/Atine r. 2.34E-10 uct/ml - v cps / min
.I 4 j ,. HP/0/B/1009/09 i Enclosure 5.2 n.., , Page 2 of 2
] , ,
. ' ,;?
N Two (2) Hour Dose Commitment j Iodine Noble Gas 'i (Child Theroid) ' (Whole Body) 'b ', 0.5 mi. Rea 0.5 mi. Rem j e-
. 2 mi. Ram 2 mi. Ram
- 4 mi. Ram 4 mi. Rem !
7! 5 mi. Ram 5 mi. Ram
's 10 mi. Ram 10 mi. Rea
.] i
- ' EITIRotOENTAL DATA (If Available)
.i Point i Dose Rate Iodine Concentration t P g'
~. /
o it - g a : (I - l! ._ 3 4 Dose Assessor Date 4 I e v-0 l *
~
}
..m .m., , . _ . _ _ _ , _ _ . ._.. _ . . , _ _ _ . . _ . _ . _ . _ . . _ , . _ , . . _ , _ , _ _ _ . . _ , _ , _ _ . , _ , , , , , _ , _ , . _ _ _ _ _ , _ , , , , , _ _ _ _ _ , _ _ , . , . . _ _ _ _ ._.
I j 4 4
. HP/0/3/1009/09 i Enclosure 5.3 j ,f', Page 1 of 4
(.
, MANUAL CALCULATION WORESHEET t
a -i Radiological release rate (Q) l (=) .
- l. g Ci/sec = CNC xF x 4.72E-4 lt (m) .
- a Ci/s =C xr x 4.721-4 4
.t 1
- f. ( }Q Ci/sec = (Cg + Cg) x F x 4.72 E4 i
.- Dose Conversion factors for whole body (DCFg) and child thyroid (DCFg) y
)DCFr_ 1/hr/C1/m8 = 820 x I 5
I }DCFg = 1.85E6 1/hr/C1/a8 1 ,I . , . . . ,' NOTE: The information on this page is not normally used. It is l j available if needed for working with outside agencies. 4
+
e W
.i 6 e '
l h/0/3/1009/09 Enclosure 5.3
; 4'h Ps,ge 2 of 4 i
- Dose Race and Dose Calculations
_t 2 Child Thyroid (Record all G values for 0.5, 2, 4, 5. and 10 miles in Tabic !). 5 If using sample results, 3 _. D = 874 x F xC x 1 xG a) CT I
. y
- .' ~
J- Store in calculator memory 1 q If using DIF37 reading, (use only if sample results are not available) !j! .
! Dg = 2E-7 x DIF37&cm xF x 1 x3 b) .c & Time
- [ Stors in calculator esmory
.z-
- i
( v, - g. Table I - Child Thyroid Dose Race and Dose Stored Dose Rate Time Dose l Distance G Cale. Value (Ram / hour) Period (Rem) . S.B. 0.5 ti. x = x = x . L.i 2 mi. x = x =
; 4 e. x - = x - = 1 1 " "
j 5 d. x = x =
! 10 mi. x = x =
I.) G values based en a two (2) hour dose assessment period. I 4 t i - t 1 D v-----, ,--e--, -
_.____u_. __ _ _- _. _ _. . _ . _ _ _ _ _ __ i 4 5 HP/0/B/1009/09 Enclosure 5.3 i ,G Page 3 of 4
} Whole Body (Record all G values for 0.5, 2, 4, 5 and 10 miles in Table IP .
5 If using sample results, i
,)
Dgg = 0.387 x F xC g xE x 1 x "I a W ,i MIE: Use IMF36 only if semple results are not available. Use E h listed on next page. O fj ff using D:F36 reading and EMF 36(!!) < 100 cou,
)
}
b) Dgg = 1.47E-4 x EMF 36(Low)cym xF xI x 1 :G V
' " ~~~
' Store in calculator memory i 1
I
- .1
- If using ENT36 reading and EMF 36(5) > 100 cym, .. u '
xF x 'E ' x xG 1
,) Dg, = 7.74E-5 x EMF 36 (Eigh) cps 1 W
~
if - Store in calculator memory , i, ,i Table II - Whole Body Dose Rate and Doge 11 l' (WM) Stored Dese Race Time Dose Distance G Calc. Value (Ran/ hour) B
' Period l (Rem) 4 lI i i .
S.B. 0.5 mi. x = ; x =
" = '" =
,. 2 mi. x - x (( 4 mi. x " = x ;" , = 'l 5 mi. x " = x I" =
" x '"
?
10 mi. x = = -- .l l';< l G values based on a two (2) hour dose assessment period. _, v--m .na ,-, - - -m-m, ,,--,-,-w,v-- . w ee,,n- - - - , -- - - -
~
, 4 5 I.
' \
l HP/0/B/1009/09 i , Enclosure 5.3 Page 4 of 4 l W NOTES:
.i i 1) If Hi-Range IMF reads greater than 100 cys, use Hi-Range reading.
If Ri-Range EMF reads less than 100 cym, use Lo-Range reading. i n .,,.-
- 2) Use E data from sample results. If sample results 4re not available, :se e
the following approxinctions: p
; Time From Trin E .i f,,12 hours 0.40 Nav/ dis.
4 12 - 48 hours 0.20 MeV/ dis.
, > 48 hours 0.10 MeV/ dis.
e
\
~.
l o! l J 1 l I
' w#
- _ _ - - .. . .-.....~ .-' . . . . . .. . .:- . 2. . - . - - - . . - -_--
1 3 .( i 1 l _. .
} g HP/0/B/1009/09 4
a q .. :- Enclosure 5.4 ij Page 1 of 3
't ,i 6) Determine affected areas based on wind direction form the table below:
- i;i p, Wind (degrees free 0-4 4 - 10 Direction North) Mile Mile
- f. ,_
Rec - dation Rececmandation 9 0- 22.5 See Note 1 S.E.F n . 22.6 - 45.0 E.s 1Q [] 45.1 - 67.5 E.S.Q i) 67.5 - 90.0 S.Q.P
- 90.1 - 112.5 S.Q.P.E _
, 112.6 - 135.0 S.Q.P.E h .. .. 135.1 - 157.5 0.P.E.I _-
t. 157.6 - 180.0 P.E.I.J , _ 180.1 - 202.5 P.E.I.J.H.G ,t
, '? -
202.6 - 225.0 E.I.J.H.O
..- _ 225.1 - 247.5 I.J.E.G.T 247.6 - 270.0 J.H.G.T 270.1 - 292.5 G.T 232.6 - 315.0 -
G.F.E ,4 315.1 :- 337.5 G.T.E i . 1 337.6 - 359.9 T.E.S l1 - n. L! NOTE 1: Areas A,B,C,D,M,N,L,0,R will be the recommended . 1< . j areas if any action is taken in the 0 - 4 zile radius of (- the plant. This recommendatic,a is independent of wind dir-etion. e i. I, 1
.. .-- . . .--._ _-,,_ ,._- _ -. - __ ._.. _--, ,_._. ..._-._-_ _ .._..___ _...__ .-- .., _ _ _ _ _ _,.._, . . - , . , . - , . , - - , , _ . ~ _ , - - - - . _ .
j 4 1 BP/C/B.Luowfoy Enclosure 5.4 Page 2 of 3
! 2.
ca
.2 )
2 12 :2 j - 3 fj j ' 2 4 ... 3 . . 8 32= 3s foli g .: e 1.jI i.i 3-2 1 i
.1) 318- isi,!!!i 2 1
i . :-i ji-s{ el]:: =1I:si 81: 4.ler !
- ! : ij i .
8-r5 1 1:51 1
- 2 3- 2:
i s -- il ,
=i 11! !
2 . , 1 12 . mi [il 1: 1. : 2,, ,, . .s N ! = 5 l 5 r5 5# g a
- : 2 - f< . :
1 1 =
= 1 t .si -
'1 si gg
- , J 3
~
3 . 4 s,
]!.
3 jI i.:s
~
g 81-3 - a i 2 - li i, !.!1 ! - 1 r- 1 ]
~
I s1 11 2 .2 s i -t'1 i i
}:
- 1 fi ( J {
! [3,i
. 2 1..
i . - *
- -I .1 = .
i :i.:g =g es - 3{ - 3g I I3 3 i i.e 8 4 4] j - u
- s s . .t . ,
I.,=,, _ 3: y, 3 :, 11- 3 ;i 8 3,1 2 1 I I Il lji
- I, I:I - 8 4
1 j,3 ij- 13 gi-- 8j,31 1:
-.1
. ii
-lji i!* -.
M4g5I 5
= as . - is a
l, ! - : 'I j !! L E 3,
- 8 .. m.
lj. 2. h.] j3 j
- - 4
- . Je s
11
.l na a *Is 2!3
~
,Il 31 i
3^ j~ '.' . . jj
- d 3g 1, 1, 1, '[ 1, '1 81 -
2 3, - .: i le .: i s 8 ~~3 1 3 1
.: i iK
.: i ii iE 33 iK i f l-,8 8 '
li l 3.M. t.
. - sm med e -
me--*-----nwwwwppy-ew T- 't"*-7'v'-""'B""'""'yW~tw'-
- . -. . . . 2. . . - - - - - _:__ ....-. ..- :- _ . _-- . . .
= - -
.( , ,
~
Il . . HF/0/.3/1009/09 s a .G > Enclosurs 5.4
- 6, --;
. ei Fase 3 of 3 4
/. 7) 0 - 4 miles u Recommended Areas _ Recossended Population 4 j 4 - 10 miles ,- Re--wa Areas 'e
! Recommended Population
,. i. i: Non-stagnating meteorological conditions do /do not . m ist. c.! y.. , 4 .
- 1 Signature WD!I TO IISIGIECT COORDINATOR:
If the release is projected to end within one-half (h) hour. t
' p.Qn, and non-stagnating meteorological conditions exist consider
..c,i .
.~
l! not recommending an evacuation if the plurm will have left the i:
- l Eastgency Protection Zone (EFZ) beforu the population could li r evacuate.
i e a 4 . e e I
- 5 i
i B 1
- /
O e
[ .c
~
i EP/0/B/1009/09 Enclosure 5.5
,g , Page 1 of 1
] Y. [d OPERATOR AID COMPUTER (TECH SPECS 04) d USER DOCUMENTATION i 4 1) ' Tech Specs 04' can be accessed thru OAC terminals in either the 1) j Technical Support Center (TSC) or the 2) Computer Room. 1 - There are OAC terminals for both Units 1 and 2. Be certain to use the Cic
;- terminal for the typroprince Unit.
a , / All necessary data on the ' Tech Specs 04' computer printout wi3.1 be un: y y the 'Environsmutal Systems' heading. li q
- j 2) Procedure P a) Check to see if the READY key on the printer is fully CN/0FF LINE illuminated. If not fully illuminated, press the key one time and rolesse. .
'3 : b) Press the Tech Specs key of the OAC terminal. (Key will illuminata).
c) Type 0,4 using the blue numeric key of the OAC terminal.' 'j d) Press the Print key of the OAC terminal. (Key will 4ttum<n te), ~i o
! e) Press the Enter key of the OAC terminal. (Key will illuminate).
o 3 Upon pressing Inter, printer will print data. l f)
- When printer stops, press the READY key on the printer to
, ON/0FF LINE i illuminate only the "READT portion of the key.
4 g) Pt'ess the TOP OF FORM key os the printer three (3) times to advancc paper. Tear off data sheet.
~
l l
-y,,-, ,, -,.,wy-y -e.a- ,,r7,-p. .-m-- -,,,,w g -- w. - , . _ _ - _m __a -
_ _ _ _ 'l . -. .- _ . . _ _ . . _ _ j <" .
~
.p,
(# Form 34731 (10 81) (Formerly SPD 10021)
- l l{ DUKE POWER COMPANY , (1) ID No: PT/0/A/4600/06 q PROCEDURE PREPARATION -
Change (s) O to
- + PROCESS RECORD 0 Incorporated j
- 1 f.
(2) STATION: McGuire Nuclear Statioe ] (3) PROCEDURE TITLE: hecimes and De111s Ar An
/f&gw^ --
(4) PREPARED BY: M. S. Glover DATE: 1/16/84 (5) REVIEWED BY: DATE: / !/ b n Cross-Discipli Review By: N/R: 'i (/ ' !j (6) TEMPORARY APPROVAL (IF NECESSARY): j; 7.g By: (SRO) Dato:
- j. l . By: Date:
ff (j
,(7) APPROVED BY: /m 4. /h6[.nM Date: ///Y!fY g 7 / i
!i (8) MISCELuME005: !{ r.wieved/ Approved By: Date: I.sviewed/Apprsved By: Date: l 4 I 6 l
' ~. -
t 4 T..
. e
. - , , - - , _ .-..7 , , , , , . -r ,. - , - . . , . , , . . , , . , , , , . _ _ _ , ~ , _ , . , _ , . _,,.__..y, _ , .p, . - - , ,-,....-,_-.,.,y._ , _ _ _ _ _ -_
- 4- . c .
l PT/0/A/4600/06 PAGE 1 0F 5 i h- DUKE POWER COMPANY McGUIRE NUCLEAR STATION I EXERCISES AND DRILLS i y . . 1.0 Purpose
}
} This procedure provides for periodic exercises / drills to be conducted to evaluate major portions of the emergency response capability, and to develop j and maintain key skills. Corrective actions and recommendations identified as a result of an exercise or drill will be corrected, and records j maintained in accordance with this procedure. j 2.0 References
. 2.1 McGuire Nuclear Station Emergency Plan
+! 3.0 Time Required h 2 hours
'! 4.0 Prerequisite Tests N/A 5.0 Test Equipment
]
.. (4., )
< N/A 1
g- 6.0 Limits and Precauti;ns .i 1 6.1 F.xercise scenario's should be varied from year to year to test it l; emergency team response ta many of the initiating conditions listed in ProceduresRP/0/A/5700/01,RP/0/A/5700/02,RP/0/A/5700/03,and
; RP/0/A/3700/04.
6.2 Exercises should be scheduled to start between 6:00 P.M. and midnight ll 'I: and another between midnight ano 6:00 A.M. once every six years. - i 6.3 Drills should be conducted more frequently than exercises and shall be
- t j supervised and evaluated by a drill instmetor.
jj 7.0 Required Station Status
; N/A 8.0 Preraquisite System Conditions f
,; N/A -l 9.0 Test Method N/A
*M.,
.)
PAGE OF
+e -
+>.w1 -- y eq. y w -
,. m -- ,w y-.we,pyum,-g - - + --e,,- ---v. + w ----yw.-w---ww-#w w w
-~
'~
_. ^ .. . :..- . ~ .--.-. . .: q- .s-l PT/0/A/4600/0@ t PAGE 2 0F 5 k i 6 10.0 Lata Required "I D Enclosure 13.1, Exercise / Drill Format and Critique Findings Enclosure 13.2, Exercise / Drill, Controller / Evaluator Report
} )
11.0 Acceptance Criteria 11.1 Completion of required exercise or drill 'sid the subsequent critique. 12.0 Procedure 12.1 Exercises 12.1.1 A full-scale exercise is an event that tests the integrated
} ; capability and a major portion of the basic elements existing l within emergency preparedness plans and organizations. A 3 full-scale exercise shall include mobilization of state and local personnel and resources adequ:.re to verify the 1 capability to respond to an accident scenario requiring ] response. A full-scale exercise will be supervised and . ! evaluated by a qualified exercise director. A full-scale exercise will be held no less than once every 5 years.
l 12.1.2 A small-scale exercise is an event which tests the adequacy
; of communication links, establishes that response agencies at f the utility and local level understand the emergency action I levels, and test at least one other component (e.g.: medical 1
or offsite monitoring) of the emergency plan. A small-scale ll4 exercise will be conducted each year that a full-scale
~
j exercise is not held at the station. A small-scale, exercise will be supervised and evaluated by a qualified exercise ]' director. 12.1.3 An exercise will simulate an emergency that results in ll offsite protective actions and requires response by offsite l agencies. lI 12.1.4 An axercise scenario shall provide for a critique of the exercise by all concerned personnel and organizations. {
. 12.2 Drills l
I: 12.2.1 A drill is a supervised instruction period aimed at testing,
- developing and maintaining skills in a particular operation.
A drill is often a component of an exercise. A drill will be l l, % supervised and evaluated by a quplified drill instructor: i i PAGE ~ OF 1 i
_ _ m _ - . _ _ . _ _ _ . . cc .f* 1 PT/0/A/4600/06 PAGE 3 OF 5 {).i i t.%.., 12.2.2 Drills will be conducted at the frequencies indicated below: y *. (a) Communication drills with state and local government located within the 10 mile Emergency Planning Zone shall be conducted monthly. This co-mication check will j} } include contact 6 th the NRC headquarters via the ENS j (Emergency Notifiention System) telephone and the NRC 3 Region II Office, Telephone 404/221-5238 from the ] s Control Room and TSC. d (b) Communication drills with Federal emergency response 4 organizations and states within the 50 mile Injestion d Pathway shall be conducted quarterly.
.l.
] (c) hmication drills with state and local emergency operations centers and field assessment teams shall be }
- conducted annually.
.i .:i /'
-w NOTE: Sample message information for the above communication drills shall test the ability to
'l;; understand the content of messages. l! 't l ', (d) Fire drills shall be conducted in accordance with i l, Station Directive 2.11.1 and documented by the Safety
- i .- Department.
j (e) Medical emergency drills involving a simulated j contaminated individual shall be conducted annually. l This drill will involve participation by the North l5i Mecklenburg Ambulance Service and the North Mecklenburg j Rescue Squad and Charlotte Memorial Hospital, A i communication check to Oak Ridge REACTS as the provider
; of backup medical support shall be cenducted during this I drill.
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\ __. _ _ g' q' PT/0/A/4600/06 PAGE 4 0F 5 .I il fM D
- I (f) A radiological monitoring drill involving onsite cad i offsite radiological monitoring teams will be conducted
, annually. The monitoring teams will actually collect and analyze air samples, as appropriate. Soil,
. ?. vegetation and water sampler will not be taken as this i is done on a weekly basis at the station. The exercin
$ controllers will provide them simulated analysis results a
G indicative of contamination or plume location. li (g) Health Physics drills shall be conducted semi-annually which involve response to, and analysis of, simulated fj elevated airborne and liquid samples and direct 9 radiation measurements in the environment.
'I l
(h) Health Physics drills shall also be conducted annually which involve analysis of inplant liquid samples with
$ actual radiation levels, includir.g use of the l;
s
"^ .l post-accident sampling system.
I
! (i) Site assembly drills shall be conducted semi-annually.
These drills shall provide for the capability to account for all individuals onsite at the time of the emergency
- and to ascertain the names of missing individuals within
.1, 1 30 minutes of the start of an emergency condition. The capability to account for onsite individuals continuously after the initial accountability shall be included. (j) Semi-Annual Emergency Center Activation Drills will be =I conducted. This drill will provide for the notification and activation of the Technical Support Center (TSC) and
,j j
the Operations Support Center (OSC). Cae of the Activation Drills conducted each year will be satisfied
] ^ by the annual exercise provided in Paragraph t2.1. -
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' PAGE OF
,e- -- - - . - .w- , , . - y..._.-.-- ,-,,...-- -e9 - - - - - - . ,-y, y,pr--- , , , - + - , , - , ,,
sb' d' PT/0/A/4600/06 PAGE 5 0F 5
; .C " i 12.2.3 File Enclosure (s) 13.1 and 13.2 with completed procedure
]j Y process record. 1
~!
i 13.0 Enclosures ] 13.1 Exercise / Drill Format and Critique Findings
- f. .
13.2 Exercise / Drill, Controller / Evaluator Report.
?
2 li '] i d
.i 1
.T i!
e p i~f ] l
- ]
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PAGE OF
, . --m-, ,- , ,. .yf---m-,e e +. m--y v..--. - - -w- --u.w -
~-
- f. 9' l PT/0/A/4600/06 j ENCLOSUEE 13.1 PAGE 1 0F 3 l
OU EXERCISE /DRILI FORMAT AND CRITIQUE FINDINGS l 'J i 1.0 Classification of Exercise / Drill. (Check appropriate box) O-Emersener E=ercise, 12.1 Commurication Drill (state and local government within 10 mile .; EPZ and MRC Headquarters and Region II Office from the Control
- 't
.j Room and TSC), 12.2.2.a. (monthly)
J
- ] . -
Commamication Drill (Emergency response organizations and state j within 50 mile I.P.Z.), 12.2.2.b. (quarterly)
~
Communication Drill (state and local Emergency Operations Centers and Field Assessment Teams), 12.2.2.c. (annually)
- .~..
Medical Emergency Drill,12.2.2.e. (annually) l 0- n 4tatomicat naattart== oritt. 22.2.2.f. (ananally) Health Physics Drill, 12.2.2 3. (semi-annually) i Health Physics Drill, 12.2.2.h. (annually) [' Site Assembly Drill, 12.2.2.1. (semi-annually)
! - Emergency Center (TSC/OSC) Activation Drill (Semi-annually) 2.0 Drill Instructor / Exercise Director ; (Name) ! Critique Director:
- i. { (Name)
! 3.0 Date/Tise Exercise / Drill to be conducted: /
(Date) (Time) -
*3s ,
I .) ~ PAGE OF l
PT/0/A/4600/06 ENCEOS11PE 13.1 i PAGE 2 0F 3
; ln.;
.; . , 4.0 Exercise / Drill Objectives: *
, 'JI 1
i i 5.0 Plant system / ares (s) affected: i i
?
1
. 6.0 Work groups to be involved:
M. m
'l _ -! 7.0 Time sequence of postulated events:
l 1 1 ( i s
! C- 8.0 Assigned Observers (Controllers / Evaluators) and their station:
i; j __ e ie lI j 9.0 Critique to be conducted at:
/ _
; (Date) (Time)_ (Location) t j 10.0 Personnel to attend critique:
4
; 11.0 Critique Findings, Re::c:.sendations, Required Acc. ion (s), Etc. :
i i - I e j
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PT/0/A/4600/06 ENCLOSURE 13.1 PAGE 3 0F 3
~~.%
8 > 12 0 Corective Actions Taken: (List actions taken to ensure all findings in 11.0
'~~
above are identified and corrected): 4 i NOTE: Include all Exercise / Drill data or other information provided as an attachment. .4 i l (Drill Instructor / Exercise Director) (Signature) (Critique Director) T
.) (Signature)
V t o s .j . ,1 e es i i! t 'i I
/
O-PAGE OF
\ . . - - ... -. . - - . . . - . - _ ~ . . . - - . - . . . _ . i l _ PT/0/A/4600/06 l ENCLOSURE 13.2
, PAE 10F 1 I '
I, EXERCISd/ DRILL CONTROLLER / EVALUATOR REPORT
~ 5.
j 1.0 Drill Classification: 2.0 Summary of Exercise / Drill: 1 j 3.0 Exercise / Drill initf.:ted: (Date)
/
(Time) j 4.0 Observation / Comments / Recommendation: 'I 1 _
,- ' 5.0 Exercise / Drill completed at: / ; ( (Date) (Time)
- 4 Controller / Evaluator (Signature) 1 l!
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ti e k 1 i
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O PAGE OF
c _ f STATION DIerCTIVs 3.8.2 l REVISION 7 DATE iInit4 __ APPROVALe LL u eh e '. LaCLOSURE 2
,j PACE 1 0F S i
l TECHNICAL SUPPORT CENTER .
~
A
/ '*
SUPERINTENDENT OF OPERATIONS / '** *I* *I ' l NOTE: The Station Manaser or his P: G. Cage 0:
-designes will contact one [ H:
of the Superintendents who will then contact the / A: D. Bradshaw 0: H:
. r-ining Superintendents. I. A: G. Gilbert 0:
Each Supe-intendent will contact the appropriate
/ A: 3. Travis H:
personnel in his area of ,/ A: J. Silver 0: responsibility. f " it . SUPERINTENDENI 0F f 7""*
- TE"HNICAL SERVICE '
Sea Page 3 of 5
/ g/ P: T. c:cconne !
/- H:
A: M. Sample 0: I f [! - H: i [' - - } CONTRCt. ROOM ENERGENCY COORD. ! /. A: R. Michael 0.
\M / At J. Boyle 0:
H: i
, l/
/ A See Page 4 of 5
[ SUPERINTENDENT OF
/7/ s.
/ ..
MAINrENANC: / I / P: D. Rains 0 3 p H l STATION MANAGER EMERGENCY COORD.
/
g A: R. Rider 0: B A: A. Figuarna O P: M. McIntosh 0: H H8 \ A: R. White 0 a: G. Case 0: H: C: \
'A: T. t:ccennell 0: \ .
SUPEnifrENDENI 0F \ p,g, ~5 A D. Rains 3: 0:
-=
ADMINI:lTRATIVE CLRV. [ 3,, of 5 3: F: L. Weaver 0: D As L. Weaver 0: H: . H: A: D. Harrington 0: H: A: C. Fish 0: H: $- A: V. Spearman 0: ,
- H:
0: Office - H: 3one ,
f. ENCLOSURE 2 4 PAGE 2 0F 5 n..- - T E C H N I C A L. SUPPORT C E hit T E R QPER ATIO NS OSC C00RDINAIOR ! i SEE ENCLOSURE 3 ! SUPERI.M ENT OF ASST. OPERiTING OPERATIONS OPmN MNEER
. . , , ENCINEER
_f
.) See Page 1 of 5 P: D. Bradshav 0 P: N. McCraw 0:
R: R: A: G. Gilbert 0: A: .L. Firebaugh 0: Et H: A: B. Travis 0: A: D. Buagardner a: t- . H: Hs l' - At M. Kiaray 0: I
. ' H: l , A: J. Silver 0: i 3:
l 9
~~
l- ? . l
. j - , . .
0: Office H: Home
r .
. ENCLOSUxE 2 '
j PACE 3 0F 1 , TECHNIC AL SUPPORT CENTER
- i. .em .3 _
,7
"* * # 8 '"
TECHNIC AL SERVICES " P: M. G1.over 0:
, H*
A: R. Euch 0: H: PROJECIS & LICENS . A: M. Pacetti 0: 3:
~
- M. Sample O A: P. Deyo 0:
H A: E. Estep 0 0FFSI"'E H COMMUNICATIONS A: D. Mendezoff 0 P T. kesa 0: H - A: S. McInni:: C j s HEALTF FETSICS A: M. Claytos 0-3: 3 . A: M. Nazar ,0
/: R:
SUPERIUTENDENT OF #,,.. A': J., Foster 0: NRC RESIDENT TECHNICAL SERVICES E NOTIFICATION ONLY i
,. A: G. Terrell O
/ ,
H: B. Orders 0:
.;j A: P. Huntley 0: H:
P&T Page t
.i METdI Onsite Pa::e -
! P:,R. Michael 0: H: A: T. *dall , 0: i. H: H REACTOR 3G GEER
. P: D. Marquis 0:
H: I
- A: M. Kitlan 0:
l- . PERFolt4ANCE . H: A: S. Brown 0: P: J. Boyle 0: H: H: A: G. Calbreath C: H: PERF022:ANC:: A: D. Marquis 0: TECH 3ICIAN H: P: ?.. Grag: 0:
.- H:
- A: S. Brever 0:
H: ( . A: R. Hemphill 0: j / f ". m H: A: J. Arends 0: H:
ENCLOSURE 2 PAGE _4_ 0F 5
- & TECHNIC AL support CENTER I8 M AINTEN ANCE .
DISTRUMENT & ELECTRICAL i R. White 0: f P: R: A: K. Raece 0:
's
.' H:
\ A: B. Hr.*t 0:
H: s 51'ERINTENDENT OF pt,gggrig. MAINTENANCE
- . A. % eros O See Page 1 of 5 H
[ . ), - A: M. Mills 0 R
/
A: C. Drye 0: H: A: R. Norcutt 0: R:
. A: T. Ryan 0:
- R:
MECHANICAL P: R. Rider 0: . H: A: D. M-tes 0: H: A: W. Harris 0: H: A: E. Beaver 0: H: 0: Office , H: Home
} .
O
P . . . } f l
- ENCLOSURE 2 PAGE 5 0F 5 TECHNIC AL SuppcRT CENTER A D M I N I S T R'A TI O N -
CONTRACT SERVICES P: C. Fish 0: H A: M. Hagee j H TSC LOG RF00RDER A: E. Fne O L - H P: C. McConnell 0: A: T. Beal 0 SUPERINTENDENT ADMINIS -
- i. OF ADMINSTRATION COORDINATOR A: J. Hinson See Page 1 of 5 P: V. Spearman 0 A: M. Campbell H:
,g A: W. Kelley 0:
A: P. Parkar E M CAL M PORT P B. Hu-tphries O I H
. TRAINING & SAFETT A: D. Cornelius 0 H
P: D..Harrington 0 A: N. Rome 0 H: H A: J. Almond 0 i H A: T. Parker 0 H A: L. Baker 0 H SED-NOTIFICATION ONLT l. C. York - Division Ifanager,
, , . 0:
H: (* 0: OfficI- H: Home
s-CICI.OSURE 3 OPERATIONS SUPPORT CENTER. _
.?s l STATION DIRECTIVE 3.8.2
, . REVISIDH 6 APPROVAL M_ DATE '
I i i i 4 OSC COORDINATOR '
'OSC STAFF SIIIFT TECHNICAL UNIT #1 1. h x. Operators on slM
- SUPERVISOR SUPPORT P N. McCrav and call-out personnet CENTER. A H. Kieray 2. Ilealth Physt.'.s (S&C !
' Supervisor and II.P.
, As D. Bumgardnar I Techs., see Station p H. P. Hanual Section
- 5.3)
P As
.D. Bumgardner H. Klarey % 3. Maintenance *
- 4. I&E4
' A N. McCraw 5. Chemistry *
- 6. Other 1.e.. {
Westinghouse, SSD, SHS, - l etc.*
- Expertise to be drawn i from each area to support the emergency i condition. I I
i I a i l
a o p '* c q'c, UNIT E D STATES [$, NUCLE AR REGULATORY COMMISSION } 3
/gl. )E W ASHINGTON, D. C. 20555 March 2,1984 %, ...../
50-369/370 William B. ficGuire MEMORANDUM FOR: Chief, Document Manageme. anch, TIDC FROM: Director, Division Of Rules and Records, ADM
SUBJECT:
REVIEW 0F UTILITY EMERGENCY PLAN DOCUMENTATION The Division of Rules and Records has reviewed the attached document and has determined that it may now be mAde publici available.
/
. M. Felton, Director ivision of Rules and Recor Office of Administration 2/[
/
Attachment:
As stated / e
~
lA -.- .. ,_ _ _ . . . . _ . _ _ . ._ _ _ _ . . _ _ _ . _ _ _. -g, a . E
' DUKE POWER GOMPAVY P.O. box 33:80 $ CHARLOT1T. N.C. 98949 Tauer,soms j HALB. TUCKER
- ' ==*=====n (704) 07
- >463 February 10, 1984 i
Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regularpry Commission Washington, D. C. 20'.5 ,; Attention: Ms. E. G. Adensam, Chief
; Licensing Branch No. 4
, Re: McGuire Nuclear Station Docket Nos. 50-369, 50-370 j
Dear Sir:
3 Enclosed for NRC Staff use and re'.-iew are two copies of the latest revision to the following McGuire Nu;1 ear Station Emergency Plan Implementing Precedures:
-i
- 1) HP/0/B/1009/05 "First Response Evaluation of a Rcector Coolant Leak inside Containment" (changes 0-0, dated October 21, 1983) i
- 2) HP/0/B/1009/08 " Evaluation of a heactor Coolant Leak inside Containment" (chani;es 0-2, dated October 21, 1983) i
- 3) HP/0/B/1009/09 " Release of Radioactive Materials through Unit Vent
. Exceeding Technical Specifications" (changes 0-2, dated October 21, 1983)
A) PT/0/A/4600/06 " Exercises and Drills" (changes 0-0, dated January 18, 1984) ,i i 1 5) Station Directive 3.8.2 - Enclosure 2 (Revision 7, dated January 17, 1984) I'
, Enclosure 3 (Revision 6, dated January 17, 1984) l Also attached are two copies of the Emergency Plan ImplementD g Procedures Index. Please verify that your manual is current with the attacned list.
'}
] Please delete privacy material in the form of personal telephone numbers prior ll to placing any material in t.he public document room, specifically:
1?
- 5) Enclosure 2 - Technical Support Center, pages 1 of 5 to 5 cf 5 These revisions are being submitted in accordance with 10 CFR 50.54(q) and do not decrease the effectiveness of the Emergency Plan Implementing Procedures.
By copy of this letter, one copy of each of the above documents is being provided to the NRC, Region II. Very truly yours, S' hh(/ Hal B. Tucker [{ I I En res -
.r. 7 I
t Mr. Harold R. Denton, Director i February 10, 1984
' Page 2 i
1 l cc: (w/ enclosure) Mr. James P. O'Railly, Regional Administrator
, U. S. Nuclear Regulatory Commission 1 Region II 101 Marietta Street, NW, Suite 2900 ; Atlanta, Georgia 30303 ! (w/o enclosure)
Mr. W. T. Orders a NRC Resident Inspector
-I McGuire Nuclear Station V
r 1 e 9 9 e Y +e i:
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