Text

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures RP/0/A/5700/02 Re Alert, RP/0/A/5700/03 Re Site Area Emergency & RP/0/A/5700/04 Re General Emergency
	ML20085M967
Person / Time
Site:	Mcguire, McGuire
Issue date:	04/18/1983
From:	; DUKE POWER CO.
To:	;
Shared Package
ML20085M958	List: ML20085M962; ML20085M967;
References
	PROC-830418-02, NUDOCS 8311100027
	Download: ML20085M967 (94)
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(Formerty $>0 i092 U

's DUKE POWER COMPA.N: ) No:

3

PROCEDURE PREPARATION tange(s) O to PROCESS RECORD C Incorporated (I) STATION: McGuire Nuclear Statien (3) PROCEDURE TITLE: First Response Evaluation of a Reactor Coolant Leak Inside i

contain:nent (4) PREPARED BY: . w 1_ ____ DATE: C/f1 (5) REVIEWED 3Y: /// O # DATE: F-/-#3 VW Cross-Disciplinary Review By: N/R:Jop-(6) TEMPORARY APPROVAL (IF NECESSARY):

By: (SRO) Date:

( By:

Date:

(7) APPROVED BY: /._ i M?6 - .01 Daca: 9/7 /tti (8) MISCELLANEOUS:

Reviewed / Approved By: Date:

O 8311100027 831107 PDR ADOCK 05000369 F PDR

EP/0/3/1009/03 DUKE POWER COMPANY ,

McGUIRE NUCLEAR STAT CN TIRST RESPONSE EVALUATION OT A REACTOR COOLANT LEAK INSIDE CONTAI.E i

1.0 Purpose This procedure is to be used to determine potentially affected areas and levels of protective ac:1on in the event of a reactor coolant leak inside containment, including possible release through unit vent.

2.0 References 2.1 HP/0/3/1009/02, Alternative Methods for Determining Dese Ra:e Within the Reactor 3uilding. .

2.2 HP/0/3/1009/08, Evaluation of a Rese:or Coolant Leak Inside Containment.

2.3 EP/0/B/1009/09. Release of Radioactive Mate:ials Through the Unit Vent Exceeding Technical Specifications.

2.4 EPA - 520/1 001, Manual of Protective Action Guides and Protective Ac:Lons for Nuclear Incidents.

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\s 2.5 Health Physics Manual See:1on 8.2, Exhibi: 8.2-2, Page 2. Unit Vent & Weste Effluent Flow Data Form.

3.0 Limits and Precautions 3.1 This procedure is intended to be used by Health Physics shif:

personnel during the first 60 minutes of a reactor coolant leak iaside containment.

3.2 This procedure incorporates Environmental Protection Agenev l (EPA) Protective Action Guides (PAG's). It is inportant :o recognize that PAG's are defined in. terms of projected dose.

Projected dose is the dose tha: vould be received by :he population if no protec:1ve se:1on were taken. For protec:1ve actions to be sos: effective, they =us: be ins:1:uted before exposure to :he plume begins.

3.3 This procedure is a backup to the ' Nuclear 23' computer code available :o opert:icus shift personnel en the OAC computer and as such shall only be used in :he event :his co=pu:a cede is not available .

2.4 ~his procedure requires da:a available only in :he Technical Supper: Cen:e: and :he Coner:1 Roe =. : is reco= mended :ha:

e 4

. . Page 2 the shif: :echnician perform this procedure in the Con::o1 Room. .

3.5 This procedure nay involve evacuacion of :he public in :he area surrounding McGuire Nuclear S:a:Lon. The shift technician will make recommenda:1ons for'or agains: evacuation based on the outcome of this procedure. It is the responsibility of the Emergency Coordinator :o evaluate :hese r

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recommendations.

3.6 If any evacuacion recemmendation is =ade, it is advised that the shif: technician perfern an assessment usingsreference 2.2 or 2.3. in order :o calculate' dose projections.'

3.7 This procedure should be updated (re-run) every 13 minu:es until the TSC and/or references 2.2 and 2.3 are c:111:ed.

Once a sector has been added :o the list of affected areas, it.

cannot be removed fran :he list. 'h 4.0 Procedure 4.1 Acquire the following information and record on Enclosure 3.1.

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NOTI 1: Some of :he following infor=ation :an be obtained

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N from the ' Tech Specs 04' program of the Operator Aid Computer (OAC). All information available in ' Tech i

Specs 04' will be denoted in the fo11 ewing procedure by a '(TS)' o che lef: of the see: ion number. See 3 Enclosure 5.2 for steps to access ' Tech Specs 04'.

NOTI 2: Meteorological data should be obtained in :he order of preference listed on Enclosure 3.1.

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NOTI 3:

Use 13 =1:uce averages for all meteorological da:a. ,,

s 4.1.1 Uni: affected.

4.1.2 Name of person perfor=ing calculation. l 4.1.3 ? esent ti=e (hours after cidnight) and date. l 4.1.4 Time of trip /shu:down (hours af:e =1dnigh ) and date.

l a.1.5 Ti e since ::1pishu:d:wn (heurs). I 1

4.1.6 '4ind direc:i:n uppe ::ver (degrees f := Nc :h), j l

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j (The direction that the wind is coming from). l i

1 Lower tower wind direction should be used only if l upper tower is unavailable. I 4.1.7 Wind speed lower cover (MPE), Upper tower wind speed should be used only if lower cover is unavailable.

4.1.8 Vertical temperature gradient or AT *C (lower to upper cover) from -4 to -8 scale on meteorological temperature strip chart recorder.

(TS)4.1.9 Reactor building dose rate< (EMF 51 A or 3, whichever is higher or reference 2.1).

s (TS)4.1.10 EXT 37, Unic Vent Iodine Monitor (A CPM and a Time (min.)).

, NOTE: This is a determination of the change in CPM during a change in time. If ' Tech Specs 04' data is used, decamine a eps from two runs of the program 5 minutes apart (A Time = 5 minutes).

- 4.1.11 EMF 36 Low, Unic Vent Noble Gas Low Range monitor

, (C?M).

(TS)g,g.12 EMT -36 Eigh, Unit Vent Noble Gas Eigh Range Monitor

__ (CPM).

(TS) 4.1.13 Unic Vent Flow (CFM).

NOTE: Multiply fractional flow from totalizar by 170,500 to get flow in CTM (i.e. , 95% flow

= 0.95 fractional flow).

If totalizar is inoperable, use reference 2.5 to determine unit vant flow.

4.0 Determine !? (time factor) based upon time (hours) since trip /

shutdown frem the table on Enclosure 3.1. and record on Enclosure 5.1.

4.3 Calculate time determined dose (DT) as shown on Enclosure 5.1 and record on Enclosure 5.1.

4.3.1 Calculate DT1 (time determined dose 1) using (DR)

Reactor Building Dose Race x (!?) time factor.

4.3.2 Calculate DT2 (ti=a decernised dose 2) using a C?M (EMI 37) x C7M (unit vant flow) x .3E-6 ,

+ a Time.

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$h +wseeny ,

Page 4

. 4.3.3 Calculate DT3.(time determined dose 3).

4.3.3.1- If EMF 36 Eigh > 100 C?M, calculate DT3 using C?M (IMF 36 High) x C7M (unit "ent Flow) x 3.6E-3.

4.3.3.2 If EXF' 36 Eigh < 100 CPM, calediate DT3 using CPM (EMF 36 Low) x C7M (Unic Vent Flow) x 6.7E-7.

A.3.4 Calculate DT4 (time determined dose 4) using DTI +

DT2.

4.3.5 Determine DT.

4.3.5.1 If DT4 > DT3, then DT = DT4 4.3.5.2 If DT4 < DT3, then DT = DT3.

4.4 Calculate DF (dose factor) using (DT) + windspeed (WS) as shown on Enclosure 5.1 and record on Enclosure 5.1.

4.5 Determine distances and levels of protective action based on dose factor (DF) and 4T (*C) using the table on Enclosure 5.1.

4.6 Determine potentially affected zones based on wind direction using the table on Enclosure 5.1.

e 4 . 's Determine if non-stagnating meteorological conditons exist by

, \.. observing noteorological strip chart data. If:

(1) Instantaneous wind direction has not varied over 90*

in the past evo (2) hours, and (2) Instantaneous wind speed has not fallen below 10 M?E in the past eve (2-) hours , then non-stagnating conditions exist.

Record result on page 5 of 5 of Enclosure 5.1.

4.8 Check results and infern Emergency Coordinator of your reconnendations.

l-t 5.0 Enclosures 3.1 'Jorksheet l

5.2 OAC (Tech Specs 04) User Documentation

( *

. 4 EP/0/3/1009/05 Inclosute 5.1 Page 1 of 5 WORKSEZIT

1) Unic Performed by Time Now hours after midnight. Data Tira of Trip / Shutdown hours after midnight. Data Tim since Trip / Shutdown hours (All meteorological data is 15 minute average)

Wind Direction 1) Upper tower degrees from North.

or 2) Lover tower degrees from North.

Wind Speed 1) Lower tower MPH or 2) Upper cover MPE AT 1) Lower to Upper cover 'C or 2) For 1000 - 1600 .-0.2 *C or 3) For 1600 - 1000 +1.3 *C.

< (TS) Reactor Building Dose Rate (DR) R/hr (EMF 51 A or 3, whichever is higher; or reference 2.1 if EMF 51 not available)

(TS) SMF 37 A CPM A Time (min.)

EMF 36 Low C7M (TS) EMF 36 High CPM j (TS) Unic Vent Flow (F) C W. (Totalizar fraction x 170,500)

2) Determine TT (time factor) based upon time (hrs) since i: rip / shutdown fro =

the table below:

Time (hrs) TT (time factor) 0 - 1.0 12 1.1 - 2.0 -

17 2.1 - 5.0 27 5.1 - 10.0 42 l-i l

Record IF (time factor)

3) Calculate DT (time detet=ined dese) a) DTl = DR x !?

I t

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.A EP/0/3/1009/05 Enclosure 5.1 Page 2 of 5 b) DT2 = 4 EMF 37 xF x 4.8E-6 4 Time c) If EMF 36 High >100 C?M.

DT3 = EMF 36 High xF x 3.6E-3 If DE 36 High <100 CPM.

DT3 = EMF 36 Low xF x 6.7E-7 d) DT4 = = DTI + DT2 e) If DT4 > DT3; DT = DT4 If DT4 < DT3; DT = DT3 DT =

4) Calculate DF (dose fac:or) based upon DT and WS (vind speed).

DF = (WS) r

(~. DF =

NOTE: If WS 1 1.0 mph, use WS = 1.0 mph.

5) Determine distances and level of protective actions based on DF (dose factor) and 4T from the following cable:

0 - 4 Mile PAG's AT No Action Evac Children & Pres. Wenen Evac. Everrene 1-0.6 fl.30E6 1.30E6 - 6.49E6 >6.49E6

-0.5 11.24E5 1.24E5 - 6.2LE5 >6.21ES

-0.4 :o -0.2 13.99E4 3.99E4 - 2.00E5 >2.00E5

-0.1 to *0.4 12.23E4 2.23E4 - 1.11I5 > l .1 LE5

-0.5 :o +1.2 fl.10E4 1.10E4 - 5.47E4 >5.47E4

>*1.3

, 16.35E3 6.35E3 - 3.17E4 >3.17E4 f

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s HP/0/3/1009/05 Inclosure 5.1 j Page 3 of 5 1

4 - 10 l'.11e PAG's AT No Action Evac Children & Pres. Women Evac. Evervone 1-0.6 11.37E7 1.37E7 - 6.80E7 >6.80E7

-0.5 fl.43E6 1.43E6 - 7.13E6 >7.13E6

-0.4 to -0.2 13.29E5 3.29E5 - 1.64E6 >1.64E6

-0.1 to 4.4 31.60E5 1.60E5 - 8.00E5 >8.00E5

+0.5 to +1.2 16.80E4 6.80E4 - 3.41E5 >3.41ES

>+1.3 12.79E4 2.79EA - 1.40E5 >l.40E5 e

/

. HP/0/3/1009/05 Enclosure 5.1 Page 4 of 5

6) Determine affected areas based on wind direction from :he cable below:

Wind (degrees frem 0-4 4 - 10 Direction North) Mile Mile Receutmandatica Recommendation 0- 22.5 See Note 1 R.T.S.E.7,U 22.6 - 45.0 R,T.S.E.U ?

45.1 - 67.5 R.T.S.E.U,?

67.5 - 90.0 R.T,S,U,P,N,0 90.1 - 112.5 R.T,S.P,N,0 112.6 - 135.0 1 P,N,0,L 135.1 - 157.5 I,P.N,0,L 157.6 - 180.0 I,N,0,L.T,J,H

,- '180.1 - 202.5 I,N,L,J.H.C 202.6 - 225.0 I,N,L,J,H.G 225.1 - 247.5 I,J,H,G T 247.6 - 270.0 J,H,G,F 270.1 - 292.5 H,G,F.E 292.6 - 315.0 G , F', E 315.1 - 337.5 _

G,F,E,U 337.6 - 359.9 F,E.U,5 NOTE 1: Areas A,3 C.D,Q,V.M will he :he rec = mended areas if any actics is :aken in the 0 - 4 mile radius of the planc. This recc=mendacien is independen: of vind direction.

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EP/0/3/1009/05 Enclosure 5.1 Page 5 of 5

7) 0 - 4 =1les Recommended Areas Recommended Population 4 - 10 miles Recommanded Areas Reco:mnanded Population Non-stagnacing seceorological condi: ions do /do not exist.

Signature NOTE TO EMERGINCY COORDINATOR:

g If the release is proj ec:ed to end within one-half (b) hour, and non-stagnating me:acrological condi:1ons exist, consider not recommending an evacuation if :he plume vill have lef t the E=ergency Protec:1on Zone (EFZ) before the population could evacuace.

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HP/0/3/1009/05 Enclosure 5.2 Page 1 of 1 OPERATOR AID CCMPUTIR (UCE S?ECS 04)

USER DOCTMENTATION

1) ' Tech Specs 04' can be accessed thru CAC ter=inals in either the 1)

Technical Suppor: Center (TSC) or the 2) Coc:puter Room.

There are OAC to:minals for both Units I and 2. Be cer:ain to use the OAC carminal for the appropriate Unit.

All necessary data on the ' Tech Specs 04' computer printou: vill be under the 'Environmen:al Systems' heading.

2) Procedure a) Check to see if the RIADY key on the printer is fully ON/0FF LINE illuminated. If not fully illuminated, press the key one cine and release.

b) Press the Tech Soecs key of the OAC ter=inal. (Key will illuminaea).

c) Type O_ 4 using the blue nunaric keys of :he OAC terminal.

d) Press the Prin: key of :he OAC terminal. (Key will 111tuninn te) .

e) Press the En=er key of the OAC terminal. (Key will illuminate).

Upon pressing Inter, prin:e: vill prin data.

f) ' Mien printer stops, press :he Pl.ADY key on :he prince :o ON/0FF LINE illuminate only the "RIADY" portien of :he key.

g) Press the TOP OF FCRM kay on :he prin:e :hrae (2) :ines ::

advance paper. Tez: off data shee:.

_. 1 Form SPD-1 DUKE POWER COMPANY (1) ID No: HP/0/B/ LOO 9/lO PROCEDURE PREPARATION Change (s) O to PROCESS RECORD A Incorporated (2) STATION: McGuire Nuclear Station (3) PROCEDURE TITLE:

Releases of Licuid P=d4_oactive Materials Exceediise Technical Specifications 6,.

(4) PREPARED BT:

_ . _Yum .

DATE: 9 &4 93 (5) REVIEWED BT: bM .DATE: 77/h //, /0 PJ Cross-Disciplinary Review By: N/R: M~

(6) TEMPORARY APPROVAL (IF NECESSARY):

By:

(SRO) Data:

By:

Date:

(7) APPROVED BY:

fu&s //*.* ( ..s. M Data: 1//#/[f (8) MISCELLANEDUS:

Reviewed / Approved By: Date:

Reviewed'/ Approved By: Data:

EP/0/B/1009'!O l

DUKE PCh*ER CCMPAh'Y McGUIRE NUCI. EAR STATI0r.

RELEASES OF LIQUID RADICACTI"E !9m!ALS EXCEEDING TECHNICAL SPEC TICAT!ONS 1.0 Purpose This procedure describes the methods for calculating the radionuclide concentration-se area vnter supply intakes fe.

. i-c ,

an accidental liquid release, and the subsequent actions te be taken when the concentration exceeds Tecanical Specificatien?.

2.0 References I 2.1 Station H.P. Manual Section 18.2; Environmental Monitorint for Emergency Conditions.

2.2 EMF Unit Data Book.

2.3 10CFR20 Appendix B.

2.4 Station H.P. Manual, Section 16.3; Survey Documentation.

2.5 Travel time and dispersion characteristics of Mountain Island Lake, Duke PWR/80-02.

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3.0 Limits and Precautions 3.1 This procedure is be r g used in an Emergency situation which could result in shutdown of area water supply intakas. The procedure should be fully understood and used carefully and accurately.

3.2 This procedure is written for use under abnormal conditions which could involve extremely high radiation levels. Only Health Physics management should authorize the use of this procedure when needed and should provide appropriate surveillance and control of people taking the samples.

3.3 Check that the counting equipment to be used has been

( calibrated and daily response checks have been performed.

3.4 Individuals collecting the samples should be aware of the l

possibiliev of airborne cont =htion and high radiation levels in sampling areas. Use protective clothing, gloves, l respiratorv protective equipment, portable shielding, high-range dosimetert, and survey instruments as determined by

, Health Physics supervision.

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i 3.5 Collect samples, count samplas and calculate activities in acecreance with reference 2.4 Pro:adures

.1 Health Physics will collect and evaluate samples as per refarence 2.1.

!. 2 Health Physics will determine the discharge point

enec-- . tion from EMF data and/or samples taken.

- 0T** : For EMF data see conversion graphs for CPM te uC1/=1 located in Unic Data Book (Reference 2.2).

. .$ Ihe Offtice Dose Assessment Team will determine the potential

a=ination of area water supplies using Enclosure 5.1 ITransit Time /Radionuclide Concentration Calculations) and samtling data from Health Physics, a.4 If data indicates that a release thru the CCW to :.ake Norman will exceed 10CFR20 Appendix B Limits, at affected area water intakes, the Emergency Coordinator shall:

4.4.1 Request maximum possible water flow at Cowans Ford

, Hydro Station from System Load Dispatcher.

4.4.2 Notify the area water supply pumping stations to w.

cease pumping operations until the contaminatica levels have passed or have been diluted to within acceptable limits. Tech. Spec limits from 10CFR20 Appendix B, for unknown mixture is 3 x 10 , or table II if isote,e analysis is available.

4.5 If data indicates that a release thru the Conventional Waste Water Treatment Pond to the Catawba River will exceed 10CFR20, Appendix B limits at the Charlotte Water intakes, the Emergency Coordinator shall:

4.5.1 Request minimum water flow at Cowans Ford Hydro Station and Mountain Island Dam from System Load Dispatcher.

"0TE: Transit time to Charlotte Water Department l intakes is approx 1=atelv 79 davs with NO FLOW thru Cowans Ford.

4.5.2 Notify the Charlotte Water Department that a release of radioactive materials has occurred into the

\. Catawba River and that sampling and evaluation of I

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Page samples is being undertaken. In the event that sampling cenfirns that contamination levels at the Charlotte d etake win a::ceed 10CT!.20, Appendix B li=its, request the Charlotte Water Departnent to cease pumping operations during the period of time contaminated water supplies are passing the Charlotte pur.p. ni; stat: = intakes (see Enclosure 5.2).

4.6 At the request ef the Erargency C9ordinator thru the Station Health Physicist, Health Physics will sample and evaluate the concentration ef entamination in the Catawba River near the discharge peint.

4.7 The people n:tified ir the appropriate Emergency Procedures (EP/0/A/500'..~. i.', 33, or 34) will be responsible to decide what protective measure should be enkan in the interest of public health and safety.. The state agency is responsible for appropriate long-term publ1e health action (North Carolina Department of Crime Control and Public Safety).

._ 4.8 Actual field measurements of whole body doses will~be compared to whole body dose projections by the Data Evaluation Coordinator.

5.0 Enclosures 5.1 Transit Time /Radionuclide Concentration Calculations.

5.2 - Emerger.cy Plan Implementing Procedures Telephone List.

4 a R

0 HP/0/B/1009/10 F.NCLOSi'RE 5.1 TRANSIT TIMES /RADIONUC!.IDE CONCE:."" RATION CALCL'LATICNS Descristien Tr:nsit -ines ani r.tcieruclide concentrations for a relense of racioactive natarial from McGuire Nuclear Station release poir.c to the water intakes of Huntersville Davidson, Charlotte, and fron McGuire '

I'uclear Station to the Catawba River and Charlotte water intake.

Dilution Fort:ula McGuire Discharge Water Transit Required Point Intake Time (hrs) Constant (D) 4 0.22 #1 CCW Discharge Huntersv111e #1 Davidson 11 0.22 to Lake 0.22 #2 Norman Charlotte 8 4 0.33 #3 Conventional Charlotte Waste Water (See Note 1) (See Note 2)

Treatment Point to the Catawba _

River NOTE L: Transit time assumes 4 unic Cowan's Ford operation.

N Formulas: #1 C=EM) ,

M

2 C = E -(D)

G

3 C=Eh)

F Where:

C = Radionuclide Concentration at area water supply intake I ( Ci/ml)

E = Discharge Point Concentration'(+Ci/ml)

[

D = Dilution Constant M = McGuire CCW Flow in ef s, (1 Unit Operation,1 Pump = 712 f

cfs, 2 Pumps = 1424 cfs, 3 Pumps = 1931 efs, 4 .

I Pumos = 2263 cfs)

F = Cowans Ford flow in efs (Request flow race in cis from system dispatcher).

G = M or 7, whichever is greater, NOTE 2: Dilution constant was derived from a " Mountain Island Dye j

Study" conducted by Duke Power Company in 1978 and 1979 and published in a complete report by 'the title of " Travel !! e and Dispersion Characteristics of Mountain Island Lake".

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i 8 HP/0/3/1009/10 I

ENCLOSURE 5.2 i

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I EMERGENCY PLAN IMPLEMENTING PROCEDURES TILIPHONE LIST 1

Charlotte Water River Pumping Station Administration Building l Curtis Frederick - Plant Super. (Work) !

l Emergency Radio Call Sign .

Huntersv11"e Water Pumping Station (Home)

Robert Cobb Paul Reynolds (Home)

Jarry Johnson (Office)

(Home)

(Office)

Richard French (Town Manager)

(Home)

Davidson Water Pumping Station Nancy McCornac - Mayor (Office) j (Home)

Frank Ellington (Home)

(Home)

Baxter Fisher Civil Preparedness- Bob Manning (Hor P

Bill Brannon s

Health Physics Shift Technician O

yi eed Form SPD-1002-1 DUKE POWER COMPANY (1) ID No:RP/0/A/5700/01 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD 0 Incorporated (2) STATION: McGuire Nuclear Station (3) PROCEDURE TITLE: Notification of Unnen=1 N.n *

. /. .=

(4) PREPARED BY:

zAs M. S. Glover h DATE: 4/14/83 g

(5) REVIEWED BY: em A DATE: Y - /f-E"f Cross-Disciplinary Review By: N/R: W.3 (6) TEMPORARY APPROVAL (IF NECESSARY):

By: (SRO) Date:

By: Date:

(7) APPROVED BY: ,

Date: $V/N//J (8) MISCELLANEOUS:

Reviewed / Approved By: Date:

~

RP/0/A/5700/01

. PAGE 1- 0F 3 DUKE POWER COMPANY McGUIRE NUCLEAR STATION NOTIFICATION OF UNUSUAL EVENT 1.0 Symptoms 1.1 This condition exists whenever unusual events are in process or have occurred which indicate a potential degradation of the level of safety of the plant.

2.0 Immediate Actions .

2.1 Automatic. -

None 2.2 Manual 2.2.1 The Shift Supervisor shall be informed of all events initiating this procedure.

3.0 Subsequent Action Initial /N/A

/ 3.1 The Shift Supervisor shall assure that the appropriate emergency

, condition (Notification of Unusual Event, Alert, Site Area Emergency, or General Emergency) is declared by evaluating the actual plant condition with Enclosure 4.1. Emergency Classification Flowchart and Enclosure 4.2, List of Initiating Conditions, Emergency Action Levels, and Associated Emergency Procedure /

Document.

/ 3.2 The Shift Supervisor shall assure that all actions required by the initiating Emergency Procedure will be performed and that all actions necessary for the protection of persons and property are 4 being taken.

NOTE If at any time in the course of events in this procedure, site evacuation or personnel assembly / accountability appears necessary, refer to Station Directive 3.8.1.

/ 3.3 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 Station Manager or his designee assumes the responsibility of the Emergency Coordinator.

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RP/0/A/5700/01 PAGE 2 0F 3 l

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/ 3.4 The Emergency Coordinator shall assure prompt (within about 15 minutes of declaring the emergency) notification of the North Carolina State and Local County Warning Points indicated on Enclosure 4.3. He shall also assure notification of all other

< personnel listed in Enclosure 4.3.

NOTE 1.

See Enclosure 4.4, Telephone Listing, for notific'ation, [

telephone numbers / radio codes /p,ager codes. 7 NOTE 2. .

See Enclosure 4.5, Warning Massage- Nuclear Facility to State / Local Government, for information to be provided'to State / County Warning Points.

NOTE 3.

See Enclosure 4.6, Emergency Plan Massage Format for information to be provided to Nuclear Production Duty Engineer.

/ 3.5 In the event a release or potential release of radioactive materials is a threat to plant personnel or members of the general public the Emergency Coordinator shall utilize the Operator Aid Computer (OAC) " NUCLEAR-23" program to assess the offsite consequences. In the event the (OAC) is not operational the Emergency Coordinator shall request Health Physics personnel to evaluate the consequences utilizing the appropriate Health Physics procedure HP/0/B/1009/05, HP/0/B/1009/06, HP/0/B/1009/08 HP/0/B/1009/09 or HP/0/B/1009/10.

/ 3.6 The Emergency Coordinator shall provide protective action recommendations as necessary to the affected county warning point (s) and to the North Carolina warning point (Emergency

. Operations Centers if established) or the State Radiological Protection Section, Department of Human Resources (see Enclosure 4.4 Telephone Listing) as directed by the state in accordance with the North Carolina Radiological Emergency Response Plan. If actual release of radioactive naterials will result in a projected dose (REM) to the population of: (EPA Protective Action Guidelines).

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RP/0/A/5700/01 PAGE 3 0F 3

(. 3.6.1 Whole body <1, thyroid <5, NO protective action is required. Monitor environmental radiation levels to verify.

3.6.2 Whole body 1 to <5. thyroid 5 to <25, reconnend seeking shelter and weit for further instructions. Consider evacuation particularly for children and pregnant women.

Monitor environmental radiation levels. Control access to affected areas.

3.6.3 Whole body 5 and above, thyroid 25 and above, recommend (

mandatory evacuation of populations in the affected 7 areas. Monitor environmental radiation levels and adjust area for mandatory evacuation based on these levels. Control access to affected areas.

+

NOTE See Enclosure 4.4, Telephone Listing for notification.

/ 3.7 The Emergency Coordinator shall augment on shift resources to assess and respond to the emergency situation as needed to ensure the protection of persons and property.

/ '3.8 The Emergency Coordinator will assess the Emergency Condition and determine the need to remain in a Notification of Unusual Event, i escalate to a more severe class or close out the emergency.

j. / 3.9 The Projects and Licens2.ng Engineer or his designee will close out the Energency with verbal susmary to county and State authorities, notified in Step 3.4,^followed by written summary within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.0 Enclosures 4.1 Emergency Classification Guide Flowcharc 4.2 List of Initiating Conditions, Emergency Action Levels, and Associated Emergency Procedure / Document.

4.3 Notification Chart 4.4 Telephone Listing 4.5 Warning Massage: Nuclear Facility to State / Local Government 4.6 Emergency Plan Message Format f

a

~:,,,,.,,,,,--., ..,.r ..m, m.m,. , . . _ . - _ - ,-,.._., .- ,...-- .. . .

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RP/0/A/5700/01 .

ENCLOSURE 4.1- L PAGE' 1 0F 1 >

l

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eNRene e e8004 JeOuAt F ftOne teT E 10 j ew e Se:S HOSPe s At j e d .e. se I - __ --____ _ _ - - _ _ - _ _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - _ - _ _

i

,. (

RP/0/A/5700/01 ENCLOSURE 4.2 '

PACE 1 OF 5 LIST OF INITIATING CONDITIONS, EMERGENCY ACTION LEVELS, AND.

ASSOCIATED EHERGENCY PROCEDURE / DOCUMENT Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document i

4.2.1 Emergency Core Cooling Safety Injection signal verification EP/1/A/5000/01, EP/2/A/5000/01 Initiated (SI) and by redundant indication and indication EP/l/A/5000/02. EP/2/A/5000/02, discharge to vessel has of discharge to vessel. EP/1/A/5000/03. EP/2/A/5000/03,

occurred. EP/1/A/5000/04, EP/2/A/5000/04, AP/1/A/5500/35, AP/2/A/5500/35 4.2.2 Radiological effluent EHF49, 50, 35, 36, 37 Alarm indicating Tech Specs 3/4.11. Environmental Tec nical Specification Technical Specification Limits exceeded. Tech Specs. HP/0/B/1009/09, limit 0 exceeded. HP/0/B/1009/10. HP/0/B/1009/05 4.2.3 Fuel Damage Indication

a. High coolant activity a. >l pC1/ gram Dose Equivalent I-131 or AP/1/A/5500/18, AP/2/A/5500/18,

sample exceeding Tech. >100 pC1/ gram gross activity.

Specs. E-HOTE: These calculations avail-able from counting faci-lity on request.

b. Failed fuel monitor b. Increase in 1-131 concentration by indicates Hechanical Clad 7pC1/mi over a 30 minute period, or, Failure greater than 1% to 5% I-131 concentration is in the range

or 0.1% equivalent fuel of 70pci/m1 to 350 pC1/ml verified by failures within 30 minutes. increased EHF-48 readings and labora-i tory analysis.

4.2.4 Abnormal coolant tempera- Figure 2.1-1 Tech Specs exceeded AP/1/A/5500/05, AP/2/A/5500/05 ture and/or pressure or and Core Subcooling Monitor less abnormal fuel temperature than acceptable. (Below Curve) outside of Technical Speci- Verified as necessary by redundant i fication Limits. Instrumentation. (e.g. narrow and wide 1 range pressure / temperature subcooling monitors)

.s

f O \

i RP/0/A/5700/01 ENCLOSURE 4.2 PACE 2 0F 5 Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document 4.2.5 Exceeding either primary / >lCPN total P/S leakage EP/1/A/5000/02, EP/2/A/5000/02, l secondary leak rate >500 CPD from any S/C EPfl/A/5000/04, EP/2/A/5000/04,

requiring shutdown by >10 CPM Identified Primary Leakage AP/1/A/5500/10, AP/2/A/5500/10 i Tech. Specs. or primary leak Verified by EHF readings, level control, rate requiring shutdown by make-up rate, and or chemical / radiological Tech. Specs. analysis.

4.2.6 Failure of a safety or Valid accoustic *. monitor indica- EP/1/A/5000/02. EP/2/A/5000/02,

,~

relief valve in a safety tion of valve t'ailure. AP/1/A/5500/ll, AP/2/A/5500/ll, related system to close. EP/1/A/5000/03, EP/2/A/5000/03 following reduction of applicable pressure. (Pri-mary System (NC) or Main Steam (SM).

l 4.2.7 Loss of offsite power or Undervoltage alarms on 7KV buses AP/1/A/5500/07, AP/2/A/5500/07 loss of onsite AC power or blackout load sequencers l capability. actuated.

j 4.2.8 Loss of containment inte- Any automatic containment isolation AP/0/A/5500/24 grity requiring shutdown by valve found to be open and inoperabic l

Tech Specs (3/4.6.1). and unisolable or both air lock doors on a lock inoperable, or penetration (s) fail leak test per Tech Specs when con-tainmeat integrity required.

4.2.9 Loss of engineernd safety ESF actuation system found inoperable AP/1/A/5500/19, AP/2/A/5500/19, l feature or fire protection or Fire Suppression Water System AP/1/A/5500/21, AP/2/A/5500/21,

system function requiring found inoperable per Tech Specs. AP/1/A/5500/20 AP/2/A/5500/20,

. shutdown by Tech Specs Tech Specs 3/4.5, 3/4.7.10, (e.g., malfunction, personnel 3/4.7.11 error, or procedural inadequacy).

I e d ... *o i

7

, RP/0/A/5700/01 EHCLOSURE 4.2 PAGE 3 0F 5 1 Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document -

~

4.2.10 Fire within the plant Observation og; fire detection alarm Station Directive 2.11 lasting more than 10 with confirming observation of a

! minutes. fire lasting more than 10 minutes.

1 l 4.2.!! Indications or alarms on Loss of process or effluent radiation OP/0/A/6700/03 Tech Specs 3/4.3 process or effluent para- monitoring system oj; Loss of all meters not functional in meteorological instrumentation onsite Control Room to an extent or Loss of all radio / telephone communi-requiring plant shutdown cations capability offsite, j or other significant loss of assessment or communica-tion capability (e.g..'all meteorological instrumenta-tion, or radio networks).

, 4.2.12 Security threat or As notified by Security Force. Station Security Plan

, attempted entry or attempted sabotage.

4.2.13 Natural phenomenon being i

experienced or projected

beyond usual levels.

i a. Any earthquake felt- (<.08gH, <.053gV), Annunciator Alarm.

in plant or detected (AD-13) on station seismic in-

! strumentation.

l b. 50-year flood or low As observed water, hurricane surge,.

4 seiche (lake tidal wave)

, c. Any tornado on site As observed 1

d. Any hurricane Winds >73 mph /from National Weather RP/0/A/5700/06, RP/0/A/5700/07 Service information,

. 6 ... h 1

4 RP/0/A/5700/01 ENCLOSURE 4.2 PAGE 4 0F 5 Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document 4

4.2.14 Other hazards being ex-perienced or projected.

a. Aircraft crash onsite As observed 4

or unusual aircraft activity over facility. ,

b. Train derailment on As observed site.

c. Near site or onsite As observed explosion.

d. Near site or onsite As observed -

RP/0/A/5700/08 toxic or flammable

! gas release.

1

e. Turbine rotating com- Turbine trip and observation of AP/1/A/5500/23, AP/2/A/5500/23, ponent failure causing a turbine malfunction or failure. AP/1/A/5500/02, AP/2/A/5500/02, rapid plant shutdown RP/0/A/5700/09 (Loss of Condenser Heat Sink).

1 4.2.15 Other plant conditions As determined by the Shift Supervisor / As directed by plant conditions.

I exist that in the judge- Emergency Coordinator.

i ment of the Shift Supervisor, the Operations Duty Engineer.

l the Superintendent of Opera-

, tions, or the Station Hanager 4 warrant increased awareness

on the part of State and/or t local offsite authorities or require plant shutdown under Tech Specs requirements and involve other than normal con-l trolled shutdown (e.g., cool-i down rate exceeding Tech Specs

limits, pipe cracking found during operation).

4 I.

, 1

! . . s 4

RP/0/A/5700/01 -

ENCLOSURE 4.2 PAGE 5 0F 5 Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document 4.2.16 Transportation of contami- As observed. RP/0/A/5700/05 nated injured individual from site to offsite hospital.

4.2.17 Rapid depressurization of As observed and actuation of 4.2.1 AP/1/A/5500/06. AP/2/A/5500/06 secondary side. and 4.2.6 above.

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RP/0/A/5700/01 _

ENCLOSURE 4.4 PAGE 1 0F 2 TELEPHONE LISTING 4.4.1 Operations Duty Engineer (PA System) 1 P&T Pager 4.4.2 Station Manager Home - System Speed Home - System Speed -

4.4.3 Superintendent of Operations -

Home - M - System Speed 4.4.4 Superintendent

ical Services -

Home ' System Spee ,

4.4.5 Projects & Licens En inner - M j Home - System Speed -

4.4.6 Nuclear Production Duty Engineer System Speed P&T Pager 4.4.7 NC State Warning Point, Raleigh - - System Speed 4.4.8 Mecklenburg County Warning Point - Primary: Down Phone Back-up: ' System Spee Back-up: Emergency Radio, Code:

4.4.9 Lincoln County Warning Point - Primary: Rin Down Phone Back-up: ' System Speed Back-up: Emergency Radio, Code:

4.4.10 Catawba County Warning Point - Primary: Ring Down Phone Back-up: M ' System Spe Back-up: Emergency Radio, Code:

4.4.11 Iredell County Warning Point - Primary: Rin Down Phone Back-up: System Spee Back-up: Emergency Radio, Code:

4.4.12 Gaston County Warning Point - Primary: Rin Down Phone Back-up: - System Spe Back-up: Emergency Radio, Code:

4.4.13 Cabarrus County Warning Point - Primary: R Down Phone Back-up: ' System Speed Back-up: dio, Code:

NOTE

1. Radio Code T v111 activate all county radio units.

2. P&T Pager, Central Division (Charlotte Area)

Dial h

RP/0/A/5700/01 _

ENCLOSURE 4.4 PAGE 2 0F 2 4.4.14 N.R.C. Operation Center, Emergency Notification System (ENS phone) 4.4.15 N.R.C. Station Repre tive (Bill Orders)

Office Home System Sp P&T Page site Pager -

For P&T Page from Central (MNS Are t Manager: Construction Ext 4.4.16 Construction P Home System e ystem Speed Station Health

~ ,

4.4.17 Home System Speed ,

P&T Page 4.4.18 Station Safety Suoervisor Home - System Speed 4.4.19 Superintendent o d tenance h ,

Home - System Speed 4.4.20 Superintendent of Administration Home ^ System paed Radiation Protection Sectign Department Human Resources 4.4.21 <

- System Speed

M WARNING MESSAGE 5 NUCLEAR FACIUT1!ETG SIATEdOCAl" GOVERNMEM insations: RP/0/A/5700/01 ENCI.05URE 4.5 A. For Sender: PAGE 1 0F 4

1. Complete Part I for the Initial Warning Message.

2. Complete Parts I & li for followup messages.

B. For Receiver:

i 1. Record the date, time and your name in the area below.

2. Authenticate tnis message by verifying the code word or by calling back to the facility. (See Part I .5)

?

Time: Date: 7 Message Received By:

~

.. W i f C C T : PARTE: - .. .

. 'T.Tr#2f!-W

1. This is: McGuire Nuclear station unsert name of faciityl

2. My name is:

3. This message (number._.):

(a) Reports a real emergency.

(b) . Is an exercise message.

4. My telephone number / extension is:

5. Message authentication:

(venty coce word or call sacx to :he factity)

I

6. The class of the emergency is: (a) Notification of Unusual Event l

I i

(b) Alert (c) Site Emergency (d) General Emergency

7. This classification of emergency was declared at: (a.m./p.m.) on (date).

8. The initiating event causing the emersency classification is:

9. The emergency condition: (a) Oces not involve tne release of radioactive materials from the plant.

(b) Invcives tne octential for a reMase, but no release is occurring.

(c) Involves a release d8 radioactive material.

EY/V/A/ [VV/VA ENCLOSURE 4.5 _

PAGE 2 07 4

10. We recommend the following prctective action:

(a) No protective action is recommended at this time.

(

(b) People living in zones remain indoors with the doors and windows closed.

(c) People in zones evacuate their homes and businesses.

(d) Pregnant women and children in zones remain indoors with the

. doors and windows closed.

(e) Pregnant women and children in zones evacuate to the nearest shelter / reception center. -

(f) Other recommendations:

1

11. There will be:

--(a) A followup message (b) No further communications

12. I repost, this message: PAF.T I APPROVED FOR RELEASE (a)- Reports an actual emergency (b) is aa exercise message Signatura (Emergency Coordinator)

13. RELAY THIS INFORMATION TO THE PERSONS INDICATED ON YOUR ALERT PROCEDURE FOR AN INCIDENT AT A NUCLEAR FACILITY.

"END OF INIT!AL WARNING MESSAGE ~

PART il- I '

1. The type of actual or projected reisees is:

6 (a) Airborne I

(b) Waterborne (c) Surface spill I

(d) Other

2. The source and description of the release is:

3. (a) Release began /will begin at a.m./p.m.; time since reactor trip is hours.

(b) The estimated duration of the release is houn.

(

<_, -r,- -w,-,---,-wn, - , - - - - , --m--- -n--, ,-+

-w-

.s. , , , .m 2 , . . , w .

ENCLOSURE 4.5 ~

PAGE 3 - 0F 4 ,

4. . Dose protection base data: l curies, or curies /sec. !

Radiological release:

Windspeed: mph k

Wind direction: From Stability class: (A,B,C,D,E,F, or G)

Release height: Ft.

Dose conversion factor: R/hr/CI,'m3 (whole body)

R/hr/Ci/m3 (Child Thyroid)

Precipitation:

Temperature at the site: 'F

5. Dose projections:

' Dose Commitment

Whole Body (Child Thyroid)

Distance Rem / hour Rem / hour of inhalation Site boundary 2 miles 5 miles 10 miles

Protecad integrated Dose in Rem

Distance Whole Body Child Thyroid Site Boundary L ,

2 miles 5 miles 10 miles

6. Field measurement of does rate or comamination (if available):

7. Emergency accons ue--- _, at the facility include:

l

8. Oneits support needed from offsite organiastions:

9. Plant status:

(a) Reactor is: not tripped / tripped (b) Plant is at: % power / hot shutdown / cold shutdown / cooling down (c) Prognosis is: stable /im proving / degrading /unk nown.

ENCLOSURE 4.5 '

PAGE 4 0F 4

10. I repeat, this message:

(a) Reporte an actual emergency.

(b) 1: en exercise message.

PART I and II APPROVED FOR RELIASE

11. Do you have any questions? Signature (E=ergency coordinator) y 9.I- %1ty-%%'END10EFOEr.QW-USMESSA NOTE: Record the name, title, date, time, and warning point notified. (Senders)

Record the name title, date, time, and persons notified per alert procedure. (Receevers) 1.

(name) (title) 1 (date) (time) (warning point) 1 2.

(name) (title)

(date) (time) (warning point) 3.

(name) (title)

(date) - (time) (warning point) 4.

(name) (title)

(cate) (time) (warning point) 5.

(name) (title)

(date) (time) (warning point) 6.

(name) (title)

(date) (time) (warning point) l

7. __

(name) (title)

(date) (time) (warning point) 8.

(name) (title)

( (date) (time) Form 34888 (6-82)

(Warning Point)

-. - =_ . - - _ _ _ _ - - - . . - . - _ - -

RP/0/A/5700/01 ~

ENCLOSURE 6.6 PAGE 1 0F 1 EMERGENCY PLAN MESSAGE FORMAT

(

1 (Nuclear Station to Nuclear Production Duty Engineer)

1. This is at McGuire Nuclear Station.

(Name and Title)

2. This is/is not a Drill. An Unnsual Event Alert 4

Site Area Emergency .

General Emer'gency }

vas declared by the Emergency Coordinator at on Unit Number .

~

(Time)

3. Initiating Condition: (Give as close to the emergency procedure description as possible together +-ith station parameters used to determine emergency status) j 4 Corrective Measures Being Taken:

5. There Have/Hase Not been any injuries to plant personnel.

6. Relasse of redioactivity: Is/Is not taking place, and is/is not affecting the Crisis Management Center.

.7. NRC Yes No, State Yes No, Counties Yes No, have been notified.

8. The Crisis Management Team should/should not be activated. Corporate l Comications and Company Management should be notified (Unusual Event only). l

9. I can be reached at for follow-up information.

(Telephone Number) l

10. Additional Comments:

i i l l

l i

- , . , - ,-_n , - . - .,.---.,,.y.. - . . . - ,.,v. ,,..,...-,..-.cm.m 7 .-,r,-. 9 ..,,,,w.. 1- - --. y m .- , p.----,-vm-,-e 4,

Porn SPD-1002-1 DUKE POWER COMPANY (1) ID No: RP/0/A/5700/02 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD 0 Incorporated.

(2)', STATION: McGuire Nuclear Station 4

(3) PROCEDURE TITLE: Alert-nA. l ,

fW

. ~bS.Glover (4) PREPARED BY: DATE: 4/14/83 .:

(5) REVIEWED BY: u bd ..

DATE: Y //,(~ N )

Cross-Disciplinary Review By: N/R: V4 (6) ITMPORARY APPROVAL (IT NICESSARY):

By: (SRO) Date:

By: Date:

(7) APPROVED BY: Date: V ///8J

\ (8) MISCELLANEOUS:

Reviewed / Approved By: Date:

G l l

'Q l 1

_ _ . - - - . . . . _ - __._. . . _ _ _ . _ _ . _ _ _ - _ . . ~ . _ _ _ _ _ _ _ , . _ _ _ . _ . _ _ _ . _ . . , . _ _ _ . _ _ . . . . , _ . .

_ ._. - _ _ _ - _-_ - _- -= . .- -. . . -.

~

RP/0/A/5700/02 PAGE 1 0F 4

( DUKE POWER COMPANY McGUIRE NUCLEAR STATION ALERT 1.0 Symptoms 1.1 Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant.

'..0 Immediate Action '

t 2.1 Automatic -

None 2.2 Manual 2.2.1 The Shift Supervisor shall be informed of all events initiating this procedure.

3.0 S6bsequent Actions Initial / N/A

/ 3.1 The Shift Supervisor shall assure that the appropriate emergency condition (Notifics*; ion of Unusual Event, Alert, Site Area Emergency, o ; General Emergency) is declared by evaluating the acutal plant condition with Enclosure 4.1 Emergency Classification Flowchart and Enclosure 4.2, List of Initiating Conditions, Emergency Actioa Levels, and Associated Emergency Procedure / Document.

/ 3.2 Tha Shift Supervisor shall ensure that all actions required by the initiating Emergency Procedure will be performed and that all actions necessary for the protection of persons and property are' being taken.

NOTE If at any time in the course of events in this procedure. site evacuation or. personnel assembly / accountability appears necessary, refer to Station Directive 3.8.1.

/ 3.3 The Stift Supervisor shall assume the function of the Emergency Coordinator until the arrival of the Station Manager or his v

~

RP/0/A/5700/02 PAGE _ 2 0F 4 i

( designes, at which time the Station Manager or his designee assumes the responsibility of the Emergency Coordinator.

/ 3.4 The Emergency Coordinator shall assure prompt (within about 15 minutes of declaring the emergency) notification of the North Carolina State and Local County Warning Points indicated on Enclosure 4.3. He shall also assure notification of all other personnel listed in Enclosure 4.3.

f NOTE 1 ?

?

Activation of the Technical Support Center (TSC), and .~

Operations support Center (OSC) shall be in accordance with Station Directive 3.8.2. Activation of the Crisis Managsment Center (CMC) shall be in accordance with Enclosure 4.6.

NOTE 2 i See Enclosure 4.4 Telephone Listing, for notification, telephone numbers / radio codes /pagar codes.

NOTE 3 See Enclosure 4.5, Warning Massage: Nuclear Facility to State / Local Government, for information to be provided to State / County Warning Points.

/ 3.5 The Emergency Coordinator in direct contact with the Technical Support Center and the Crisis Management Center will assess and respond to the emergency by:

3.5.1 Dispatching onsite monitoring teams with associated communications equipment.

3.5.2 Providing periodic plant status updates to offsite authorities (at least every 15 minutes).

3.5.3 Providing periodic meteorological assessments to offsite authorities and, if any releases are occurring, dose estimatss for actual releases.

NOTE In the event a release or potential release of radioactive materials is a threat to plant personnel or members of the general public, the Emergency Coordinator shall utilize the Operator Aid Computer (OAC)

(

.. ,.---. , , . _ _ - . _ . . . , _ -_ . . . _ 1- _ _ . , , . - , - _ , _ ,

~~

RP/0/A/5700/02 PAGE 3 0F 4

" NUCLEAR-23" program to assess the offsite consequences.

In the event the (OAC) is not operational the Emergency Coordinator shall request Health Physics personnel to evaluate the consequences utilizing the appropriate Health Physics' procedure, HP/0/B/1009/05,

-HP/0/B/1009/06, HP/0/B/1009/08, HP/0/B/1009/09, or HP/0/B/1009/10.

. / 3.6 The Emergency Coordinator shall provide protective action recommendations as necessary to the affected county warning point (s) and to the North Carolina warning point (Emergency

(

f Operations Centers if established) or to the state Radiological Protection Section, Department of Human Resources (See Enclosure 4.4, Telephone Listing) as directed by the state in accordance with the North Carolina Radiological Paargency response plan. If evaluation indicates that a potential for or an actual release of radioactive materials will result in a projected dose (REM) to the population of: (EPA Protective Action Guidelines).

3.6.1 Whole body <1, thyroid <5, NO protective action is required. Monitor environmental radiation levels to verify.

3.6.2 Whole body 1 to <5, thyroid 5 to <25, recommend seeking shelter and wait for further instructions. Consider evacuation particularly for children and ptegnant women.

Monitor environmental radiation levels. Control access to affected areas.

3.6.3 Whole body 5 and above, thyroid 25 and above, recommend mandatory evacuation of populations in the affected areas.

Monitor environmental radiation levels and adjust area for mandatory evacuation based on these levels. Control access to affected areas.

NOTE See Enclosure 4.4 for Telephone Listing for notification.

/ 3.7 The Emergency Coordinator in coordination with the Recovery Manager at the Crisis Management Center, will assess the emergency condition u d determine the need to remain in an Alert Status,

o .

RP/0/A/5700/02 PAGE 4 0F 4 y escalate to a enre severe class, reduce the emergency class or close out the emergency.

/ 3.8 The Station Manager or his designee vill close out the Emergency with a verbal sunmaary to County and State authorities notified in Step 3.4, followed by a written summary within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

4.0 Enclosures 4.1 Faergency Classification Guide Flowchert 4.2 List of Initiating Conditions, Faergency Action Levels, and Associated Emergency Procedure / Document. ?

4.3 Notification Chart. -

4.4 Telephone Listing.

4.5 Warning Massage: Nuclear Facility to State / Local Government 4.6 Emergency Plan Massage Format e

, . , , _ ,. __ _ _ , , _ _ _ . _ , , _ _ ,.__m__ _ __ _ _ . _ _ , ,,.._m, , _ . , .~,,_m _. _ _ _ .__

f ,

s RP/0/A/5700/02 A I

ENCLOSURE 4.1 PACE 1 0F 1 EME RGENCY CLAS$1FICATION GutDE FLOWCHART -*

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RP/0/A/5700/02 ENCLOSURE 4.2 PACE 1 0F 5 LIST OF INITIATING CONDITIONS, EMERCENCY ACTION LEVELS, IND l ASSOCIATED ENERCENCY PROCEDURE / DOCUMENT Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document

! 4.2.1 Severe loss of fuel a. Very high coolant activity

cladding Hechanical sample indicating an increase of Clad Failure. 70pC1/mi in 30 minutes or 350 to 1,750pCi/mi total I-131 Coolant Activity.

i

b. Failed fuel monitor (ENF-48) or Tech Specs 3/4.6.7 lab analysis indicates increase greater than 11 fuel failures within 30 minutes or 5% to 25%

total fuel failure.

4.2.2 Rapid gross failure Pressurizer low pressure alarm and EP/1/A/5000/04, EP/2/A/5000/04, of one Steam Cenerator reactor trip and, pressurizer low AP/1/A/5500/07 AP/2/A/5500/07 tube with loss of off- level alarm and, pressurizer low l site power. pressure safety injection signal i

and, undervoltage alarm on 7KV buses. EHF 32, 33, and 34 Alarm (s).

i 4.2.3 Rapid failure of Steam Several hundred gpm primary to EP/1/A/5000/04. EP/2/A/5000/04 Cenerator tube (s), secondary leak rate indicated by:

a. as above in 4.2.2 for pres-1 surizer and ENF indicators.

, b. Steam generator ler:1 in-

,; creasing in one or more

generator (s) and falling in the others/due to reactor trip.

)

i

. ..i.'..

,e i RP/@/A/5700/02 ENCLOSURE 4.2 PACE 2 0F 5 Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document 4.2.4 Steam line break with Creater than 10gpe, rapidly de- EP/1/A/5000/04 EP/2/A/5000/04, significant primary to creasing reactor coolant Tavg. EP/1/A/5000/03. EP/2/A/5000/03 i secondary leak rate. pressurizer pressure and level and,

, 1. Steam line differential pressure safety injection signal and increased con- .

tainment building pressure /

if break is in containment.

2. High steam flow and to Lo l Tava or Low steam pressure -

safety injection signal for

rupture downstream of MSIV's.

4.2.5 Primary coolant leak Leak >50gpa as indicated by calcu- EP/1/A/5000/02. EP/2/A/5000/02,

rate greater than 50 gym. 'lation or other indication. (i.e., AP/1/A/5500/10. AP/2/A/5500/10 l sump levels)

4.2.6 High radiation levels Increase by a factor of 1,000 in HP/0/B/1009/05 l or high airborne con- radiation monitor reading within j tamination which in- the station, j dicates a severe de-l gradation in the control

! of radioactive materials.

1 4.2.7 Loss of offsite power and Undervoltage alarm on 7KV buses, EP/1/A/5000/09 EP/2/A/5000/09

loss of all onsite AC and blackout load sequencers j power for up to 15 minutes. actuated.

(See Site Area Emergency j RP/0/A/5700/03, for ex-tended loss).

i 4 . '2. 8 Loss of all onsite DC DC bus undervoltage alarms on all Tech Specs 3/4.8.2.3, i power, buses. Tech Specs 3/4.8 2.4

..t ....

l

- p RP/0/A/5700/02 ENCLOSURE 4.2 PACE 3 0F 5 Initiating Conditio,ns Emergency Action level (EAL) Emergency Procedure / Document 4.2.9 Coolant pump seizure Reactor coolant pump auto trip AP/1/A/5500/04 AP/2/A/5500/04, leading to. fuel failure. alarm, and reactor trip on low AP/1/A/5500/08, AP/2/A/5500/08, coolant flow, and failed fuel OP/0/A/6150/14. AP/1/A/5500/05 monitor alarm ENF48. AP/2/A/5500/05 4.2.10 Complete loss of func- RHR not functional and inability AP/1/A/5500/17, AP/2/A/5500/17, tions needed for plant to sustain natural or forced cir-- OP/1/A/6100/04, OP/2/A/6100/04 l cold shutdown. culation.

4.2.11 Failure of the reactor Reactor remains critical after AP/0/A/5500/34 l protection system to 'all attempts to trip reactor

! initiate and complete have been completed.

a scram which brings the reactor suberitical.

4.2.12 Fuel damage accident Observation of damage to spent AP/1/A/5500/25 AP/2/A/5500/25 with release of radio- fuel assembly, and activity to containment or fuel handling building. 1. 1EHF-16 or 17 alarm or 2 EMF-3 or 4 alarm.

2. ENF-38, 39, 40, or 42 alarm.

, 4.2.13 Fire potentially affecting Observation of a fire that could Station Directive 2.11 Series, safety systems, affect safety systems. Tech Specs 3/4.5 3

4.2.14 Most or all alarms (annun- As observed. OP/0/A/6350/01A clators) lost.

l .

+

"a

. . ! . .. le

r RP/0/A/5700/02 ENCLOSURE 4.2 PACE '4 OP 5 Initiating Conditions Emergency Action Level (EAL)- Paergency Procedure / Document 4.2.15 Airborne Radiological For EMP35 - Low Range offscale HP/0/B/1009/05 effluents >10 times 4

. Tech Specs instantaneous High Range 1 x 10 cpm limits (an instantaneous 6 rate which. if continued For EMP36 - Low Range 2 x 10 cpm over.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , would re- -

2

. sult in about lar at the High Range 5 x 10 cpm i site boundary under average i meteorological conditions i or whenever. effluent moni-j tors or radiological moni-toring detect these levels).

4.2.16 Ongoing security compromise. As reported by Security force. Station Security Plan 4.2.17 Severe natural phenomena RP/0/A/5700/06. RP/0/A/5700/07 being experienced or projected:

a. Earthquake greater >0.08gH. >.053gV. Annunciator Alarm, i than Operational (AD-13).

Basis Earthquake Levels

b. Flood, low water, hur- As observed.

ricane surge, seiche near design levels.

j (Lake tidal wave) l c. Any tornado striking As observed.

i facility,

d. Hurricane winds near As observed (95 mph)/from National design basis level. nienther Service information.

4.2.18 other hazards being ex- RP/0/A/5700/08. RP/0/A/5700/09, perienced or projected. AP/1/A/5500/23. AP/2/A/5500/23

a. Aircraft crash on As observed.

facility.

1

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.g RP/0/A/5700/02 -

ENCLOSURE 4.2 PACE 5 0F 5 Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document

~

t

b. Missile impacts from As observed.

whatever source on facility.

i

c. Know explosion damage As observed.

to facility affecting

plant operation.

d. Entry into facility As observed.

environs of toxic or flassable gases.

t

e. Turbine failure Turbine trip and observation of causing casing pene- turbine malfunction or failure.

tration.

. 4.2.19 other plant conditions As determined by Shift Supervisor / As dictated by Plant Conditions.

exist that in the judge- Emergency Coordinator, ment of the Shift Super-visor, the Operations Duty Engineer, the Superintendent of Opera-tions, or the Plant Manager warrant pre-4 cautionary activation

, of the Technical Support

! Center and near site Crisis Management Center.

j .

4.2.20 Evacuation of control As determined by Shif t Supervisor / AP/1/A/5500/17. AP/2/A/5500/17 j room anticipated or Emergency Coordinator. OP/1/A/6100/04, OP/2/A/6100/04 l required with control of shutdown systems

, established from local station..

. s I

. . e.l 6.e e

RP/0/A/5700/02 ENCLOSURE 4.3 PAGE 1 0F 1

\

NOTIFICATION / ACTIVATION ALERT Notify / Activate the following personnel /or Emergency Centers for all Initiating Conditions listed in Enclosure 4.2. (See Enclosure 4.4 for Telephone Listing)

NOTIFY / ACTIVATE NOTIFICATION COMPLETE-INITIAL Shift Supervisor ,

,}

Operations Duty Engineer .

Station Manager Superintendent of Operations Superintendent of Technical Services Proieces and Licensing Engineer Station Health Physicist North Carolina State Warning Point Mecklenburg County Warning Point

,~ Lincoln County Warning Point Catawba County Warning Point Iredell County Warning Point Gaston County Warning Point Cabarrus County Warning Point N.R.C. via ENS (Red Phone)

M.R.C. Station Representative Construction Project Manager Superintendent of Maintenance Superintendent of Administration

. Activate T.S.C. (Station Directive 3.8.2) _

Activate 0.S.C. (Station Directive 3.8.2)

Activate C.M.C. (Enclosure 4.6)

RP/0/A/5700/02 ENCLOSURE 4.4 PAGE 1 0F 2 TELEPHONE LISTING 4.4.1 Operations Duty Engineer (PA System) -

P&T Pager 4.4.2 Station Manager Home - System Speed - '

l Home System Speed -

4.4.3 Superintenden tions ,- D Home - System Speed

4.4.4 Superintende f Technical Services - -

I Home - System Spee li 4.4.5 Projects and Licensin Engineer Home System Speed 4.4.6 Station Health Physicist Home - - System Speed -

P&T Page

! 4.4.7 NC State Warning Point, Raleigh - System Speed 4.4.8 Mecklenburg County Warning Point - Primary: Rin Down Phone Back-up: ' System Speed Back-up: Emerg ncy Radio, Code:

4.4.9 Lincoln County Warning Point - Primary: Rin Down Phone Back-up: System Spe Back-up: Emergen dio, Code 4.4.10 Catawba County Warning Point - Primary: R own Phone Back-up: ' System Sp Back-up: Emergency Radio, Code:

4.4. 11 Iredell County Warning Point - Primary : Rin Down Phone Back-up: System Sp Back-up: Emergency Radio, Code:

4.4.12 Gaston County Warning Point - Primary: Rin Down Phone l Back-up: System Spe Back-up: Emergency Radio Code:

4.4.13 Cabarrus County Warning Point -

Primary: Rin Down Phone Back-up: System Speed Back-up: Emergency Radio, Code:

NOTE

1. Radio Code Y E ll activate all county radio units.

2. P&T Pager, Central Division (Charlotte Area)

Dial -

,---,-,,eww-,m--. .,, - + ,- -, _ _ _ _ w w ww , _ ,,

~

RP/0/A/5700/02 ENCLOSURE 4.4 PAGE 2 0F 2 TELEPHONE LIST 4.4.14 N.R.C. Operation Center, Emergency Notification System (ENS Phone)

N.R.C. Station Representative Orders) 4.4.15 Office Home System Sp P&T Pager Onsite Pager For P&T Page from Central (MNS Area) ti Ext.

4.4.16 Construction Project Manager eed Home : ystem ystem Speed 4.4.17 Superintendent of Maintenan Home - ystem Speed -

4.4.18 Superintendent of Administration stem Speed -

Home Nuclear Production Duty Enginee - System Speed 4.4.19 P&T Pager 4.4.20 Radiation Protection Section, Department of Human Rasources-

' System Speed g -

l

~7 ~WARNINGMESSAGE-NUCLEAR'FACEJTW e S1ATBEOCACG0h Instructions: RP/0/A/5700/02 ENC;.05UFI 4.5 A. For Sender: ? AGE 1 OF 4

1. Complete Part I for tne Initial Warning Message.

2. Complete Parts I & 11 for followup messages, B. For Receiver:

1. Record the date, time and your name in the area below.

2. Authenticate this message by verifying the code word or by calling back to the facility. (See Part ! .5)

Time: Date:

Message Received By:

(ll ART E

~

~ ~ ~ 7 '; i.%.% VAT MW'

1. This is: v-c.nd-. wy . - c - ,-e n _

onse- narne of taanty

2. My name is: _

3. This message (number _.):

~

(a) Reports a real emergency.

(b) is an exercise message.

4 My telephone number / extension is:

5. Message authentication:

(venty cooe were or call eacx to tne fa:Hirv)

6. The class of de emergency is:_ (a) Notification of Unusual Event (b) Alert (c) Site Emergency (d) General Emergency

7. This classification of emergency was declared at: (a.m./p.m.) on (datel.

8. The initiating event causing the emergency classification is:

9. The emergency condition: (a) Does not involve the release of radioactive materials from the plant.

(b) Invcives the potential for a release, but no release is occurring.

(c) Involves a release of radioactive material.

RF/0/A/5700/02 ENCLOSURE 4.5 PAGE 2 0F 4 -

10. We recommend the following protective action:

(a) No protective action is recommended at this time.

\

(b) People living in zones remain indoors with the doors ;

and windows closed. 1 l

(c) People in zones evacuate their homes and businesses, j (d) Pregnant women and children in zones remain indoors with the j doors and windows closed. ,

l (e) Pregnant women and children in zones evacuate to the nearest i shelter / reception center.

? l

. (f) Other recommendations: -

2 i

l

11. There will be:

(a) A followup message (b) No further communications

12. I repeat, this message: PART I APPROVED FOR RELEASE (a) Reports an actual emergency Signature (Emergency Coordinacor)

(b) is an exercise message

13. RELAY THIS INFORMATION TO THE PERSONS INDICATED ON YOUR ALERT PROCEDURE FOR AN INCIDENT AT A NUCLEAR FACILITY.

l ***END OF INITIAL WARNING MESSAGE" 3- PARTil ;+

1. The type of actuel or projected reisees is:

(a) Airborne (b) Waterborne (c) Surface spill (d) Other

2. The source and description of the release is:

3. (a) Reisase began /will begin at a.m./p.m.: time since reactor trip is hours.

(b) The estimated duration of the release is hours.

l

RP/0/A/5700/02

4. Does projection base data:

Radiological release: curies, or curies /sec.

Windspeed: mph Wind direction: From Stability class: (A,B,C,D,E,F, or G) -

Release height: Ft.

Dose conversion factor: R/hr/Cl/m3 (whole body)

~

R/hr/Cl/m3 (Child Thyroid)

Precipitation: }

Temperature at the site: 'F

5. Dose g%h :

' Dose Commitment * ,

Whole Body (Child Thyroid)

Distance Rem / hour Rem / hour of inhalation ,

Site boundary l 2 miles 5 miles 10 miles 27.., ; integrated Dose in Rem

Distance Whole Body Child Thyroid Site Boundary 2 miles 5 miles

- 10 miles

6. Field mesmroment of does rete or conteminecon (if available):

7. Emergency accons underway at the facility include:

8. Onsite support needed from offsite organizations:

9. Plant status:

, (a) Reactor is: not tripped / tripped Y (b) Plant is at: % power / hot shutdown / cold shutdown / cooling down (c) Prognosis is: stable / improving / degrading / unknown.

l

RP/0/A/5700/02

10. I ropest, this messege: P F 4 -

(a) Reports an aca. sal emergency.

PART I and II APPROVED FOR RELEASE

'\ (b) is an exercise message.

11. Do you have any questions? Signature (Emergency Coordinator) ry: Fd!E @R"J*END'OFFOLLOW-UPMESSAGE_SWKL9CM NOTE: Record the name, title, dets, time, and warning point notified. (Sanders) '

Record the nome title, date, time, and persons notified per alert procedure. (Receivers) 1

1. l 1

(name) (title) r (date) (time) (warning point) 2.

(name) (title)

(date) (time) (warning point)

3. *

(name) (title)

(date) (time)- (warning point) 4.

(name) (title)

(date) (time) (warning point) 5.

(name) (titie) l l (date) (time) (warning point) 6.

(name) (title) l (date) (time) (warning point) 7.

(name) (title)

(date) (time) (warning point) 8.

(name) (title)

(date) (time) pogg g3 (warning point)

RP/0/A/5700/02 ENCLOSURE 4.6 PAGE 1 0F 1 N

EMERGENCY PLAN MESSAGE FORMAT (Nuclear Station to Nuclear Production Duty Engineer)

1. This is at McGuire Nuclear Station.

(Name and Title)

2. This is/is not a Drill. t.s Unusual Event Alert ?

t Site Area Emergency .;

General Emergency was declared by the Emergency Coordinator at on Unit Number .

(Time)

3. Initiating Condition: (Give as close to the emergency procedure description as possible together with station parameters used to determine emergency status)

4. Corrective Measures Being Taken:

5. 'There Have/Have Not been any injuries to plant personnel.

6. Release of radioactivity: Is/Is not taking place, and is/is not affecting the Crisis Management Center.

7. NRC Yes No, State Yes No, Counties Yes do, have been notified.

8. The Crisis Management Team should/should not be activated. Corporate Communications and Company Management should be notified (Unusual Event Only).

9. I can be reached at for follow-up information.

(Telephone Number)

10. Additional Cosaments:

. .__ _ . . _ _ ._ _ . _ . _ - . _ . _ . _ _ _ _ _ _ _ _ _ _ _ . , L _. . _ _. . , _ _ _ _ _ _ _ _ . _ . _ . _ _ . . . . . _ _ _ _ _ _ . _ _

Torm SPD-1002-1 DUKE POWER COMPANY (1) ID No: RP/0/A/5700/03 PROCEDURE PREPARATION Change (s) 0 to PROCESS RECORD 0 Incorporated (2) STATION: McGuire Nuclear Station (3) PROCEDURE TITLE: Site Area Emergency

_n, bl m gi-v Am~. r (4) PREPARED BY:_ n. S / Glover DATE: 4/14/83 .-

(5.) REVIEWED BY:

7 L~ b i DATE: */-//f / ?)

Cross-Disciplinary Review By: N/R: Y #-)

(6) TEMPORARY APPROVAL (IF NECESSART):

By: (SRO) Date:

By: Date:

7 (7) APPROVED BY: Date: 9 // f >

(8) MISCELLANEOUS:

Reviewed / Approved By: Date:

RP/0/A/5700/03 PAGE 1 of 4 i

\ '

DUKE POWER COMPANT MCGUIRE NUCLEAR STATION SITE AREA EMERGENCY 1.0 Svuotons 1.1 Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public.

2.0 Immediate Action 2 2.1 Automatic j None 2.2 Manual 2.2.1 The Shift Supervisor shall be informed of all events initiating this procedure.

3.0 Subsequent Actions Initial /N/A

/ 3.1 The Shift Supervisor shall assure that the appropriate emergency condition (Notification of Unusual Event Alert, Site Area Imergency, or General Emergency) is declared by evaluat,ing the actual plant condition with Enclosure 4.1 Laergency Classification Flowchart and Enclosure 4.2. List of Initiating Conditions, Emergency Action Levels, and Associated Emergency Procedure / Document.

/ 3.2 The Shife Supervisor shall ensure that all actions required by the initiating Emergency Procedure will be perfotned and that all ,

actions,necessary for the protection of persons and property are being taken.

NOTE If at any cine in the course of events in this procedure, site evacuation or personnel assembly / accountability appears necessary, refer to Station Directive 3.8.1.

/ 3.3 The Shift Supervisor shall assume the function of the Emergency

4

, RP/0/A/5700/03 PAGE 2 of 4

( Coordinator until the arrival of the Station Manager or his designee at which time the Station Manager or his designee assumes the responsibility of the Energency Coordinator.

/ 3.4 The Energency Coordinator shall assure prompt (within about 15.

minutes of declaring the emergency) notification of the North Carolina State. and South Carolina State Warning Points and Local County Warning Points indicated on Enclosure 4.3. He shall also assure notification of all other personnel listed in Enclosure 4.3. ;

=

NOTE 1 Activation of the Technical Support Center CSC), Operacious 4

Support Center (OSC), shall be in accordance with Station Directive 3.8.2. Activation of the Crisis Management Center (CMC) shall be in accordance with Enclosure 4.6.

NOTE 2

, See Enclosure 4.4, Telephone Listing, for notification, telephone numbers / radio codes /pager codes.

NOTE 3

, See Enclosure 4.5, Warning Massage: Nuclear Pacility to State / Local Governannt, for information to be provided to State / County Warning Points.

/ 3.5 The Emergency Coordinator in direct contact with the Technical Support Center and the Crisis Management Center will assess and respond to the samtgency by:

3.5.1 Dispatching the Onsite and Offsite Monitoring teams with associated co-mications.

! 3.5.2 Providing astoorological and dose estimates to offsite authorities for actual releases via a dedicated individual or automated data transmission.

i r

,-. , - . - , - - - . . _ - - , , - - - - , _ .- ,,-...-.-,,._.y.,m..,-

_ , _ .,,,_-,.-.}. .-_,.m-,-.m.. - .w. . . - . _

v

~.

RP/0/A/5700/03 PAGE 3 of 1

\ 3.5.3 Providing releue and dose projections based on available plant condition information and foreseeable contingencies to offsite authorities.

NOTE -

In the event a release or potential release of radioactive materials is a threat to plant personnel or members' of the general public, the Emergency Coordinator

- shall utilize the Operator Aid Computer (OAC)

"NUCLhR-23" program to assess the offsite consequences.

In the event the (OAC) is not operational the Emergency !

Coodinator shall request Health Physics perscunal to evaluate the consequences utilizing the appropriate Health Physics procedure. HP/0/B/1009/05 HP/0/B/1009/06, HP/0/B/1009/08. HP/0/B/1009/09 HP/0/B/1009/10.

/ 3.6 h Emergency Coordinator shall provide protective action ree - dations as necessary to the affected county warning point (s) sad to the North Carolina Warnin's Point (Emergency Oparations Centers if established) or the Radiological Protection Section Department of Human Resources (see Enclosure 4.4 Telephone Listing) as directed by'the state in accordance with the North Carol.na Radiological Emergency response plan. If evaluation indicates that a potential for or an actual release of radioactive materials will result in a projected dose (REM) to the population of: (EPA Protective Action Guidelines).

3.6.1 h is body <1, thyroid <5, NO protective action is I required. Monitor environmental radiation levels to verify.

3.6.2 Whole body 1 to <5, thyroid 5 to <25, recommend seeking shelter and wait for further instructions, consider evacuation particularly for children and pregnant women.

l I

Monitor environmental radiation levels and adjust area t

for mandatory evacuation b'ased on these levels. Control access to affected areas.

l l

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l i

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o -

RP/0/A/5700/03 PAGE 4 of 4 3.6.3 Whole body 5 and above, thyroid 25 and above, recosamend mandatory evacuation of populations in the affected areas. Monitor environmental radiation levait and-adjustarea'formandatoryevacuationbasedonthNsey levels. Control access to affected areas. .

NOTE See Enclosure 4.4, Telephone Listing for notification.

/ 3.7 The Emergency Coordinator in coordination with the Recovery [

Manager at the Crisis Management. Center, will provide or make ; <

available:

r 3.7.1 A dedicated individual for plant status updates to offsite authorities and periodic grass briefings.'

3.7.2 Senior technical and management staff onsite available for consulation with the NRC and State on a perdedic basis. ;-

.w

/ 3.8 The Emergency Coordinator in coordination with Recovery Manager at the Crisis Management Center, will' assess the emergso n condition !

and determine the need to r== min in a Site Area Emergency, -

escalate to a more severe class, raduce the emergency class, or close out the emergency..

/ 3.9 The Recovery Manager at the Crisis Management Center will close out or recommend reduction of the emergency class, by briefing of offsite authorities at the Crisis Management Center or by phone if necessary, followed by written summary within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

4.0 Enclosures ,

4.1 Emergency Classification' Guide Flowchart i 4.2 List of Initiating Conditions, Emergency Action Levels, and Associated t Emergency Procedure / Document.

4.3 Notification Chart. , . y I' 4.4 Telephone Listing. ~

1, t 4.5 Warning Message: Nuclear Facility to State / Local Governskut 4.6 Emergency Plan Massage Format .i g \

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w RP/0/A/5700/03 ENCLOSURE 4.2 PACE 1 0F '6 .

LIST OF INITIATING CONDITIONS, EMERCENCY ACTION LEVEL.S. AND ,

A3SOCIATED f21ERCENCY PROCEDURE / DOCUMENT .

Initiating Conditions ,

Emergency Action Level (EAL) Emergency Procedure / Document i

4.2.1 Known loss of coolant ' Pressurizer low pressure reactor trip EP/1/A/5000/02. EP/2/A/5000/02

accident greater than and pressurizar low pressure safety makeup pump capacity. Injection signal and high containment building pressure. (NSP5040, 5050, j 5060, 5070) and hish containment j building sump level, (NIP 5260, 5270) i and high containment humidity.

l TESP5400,5410) and EHF 38, 39, and 40 alare.

4.2.2 Degraded core with pos- Inadequate Core Coolina: AP/1/A/5500/05, AP/2/A/5500/05

, sible loss of coolable 5 centrally located thermoccuples indicate a

, geometry (indicators '

-core exit temperature greater than 1200*F.

I should include instru- For Hechanical Clad Failures i i mentation to detect creater than 251 failed fuel indicated inadequate core cooling, by greater than 1,750pC1/m1 1-131 con-coolant activity and/or centration. ,

, containment radioactivity For Severe Fuel Over Temperatures levels). From 11 to 101 failed fuel indicated by 1,300 to 13,000pC1/ml I-131 concentration.

For Fuel Helt l From .51 to 51 failed fuel indicated j by 1.180 to 11,800pC1/m1 1-131 a

concentration.

1 j 4.2.3 Rapid failure of steam Pressurizer low pressure alarm and EP/1/A/5000/04, EP/2/A/5000/04

generator tubes with loss reactor trip, and pressurizer low AP/l/A/5500/07 AP/2/A/5500/07 )

4 of offsite power (e.g., level alarm, and EHF 32, 33, and 34 '

several hundred spo pri- alarm, and undervoltage alarms on mary to secondary leak 7KV buses, and steam generator water <

rate). level rapidly increasing in one or 1 more steam generators falling in the j others, and pressurizer level rapidly P decreasing (NCP5151, 5160, 5172) j i and possible lifting of steam genera-tor PRV's and/or safety valves.

k j .......en f

7 ,- .l RP/0/A/5700/03 ENCLOSURE 4.2 PAGE 2 0F 6 +

i Initiating Conditions Emergency Action Level (GAL) - ' Emergency Procedure / Document 4.2.4 Steam line break with Rapidly decreasing reactor coolant EP/1/A/5000/03. EP/2/A/5000/03

greater than 50gpa pri- Tavg. pressurizer pressure and l'evel, n

!. mary to secondary leakage Steam line differential pressure and indication of fuel safety injection signal, and High damage. containment building pressure. If steamline break is in containment .

l

^

(NSP5040. 5050, 5060. 5070) and EHF 51A and/or B alarm, og high steam flow and to La Tavs or low steam pressure safety injection signal, and EHF 48 e . arm.

4.2.5 loss of offsite power ryjl,' Undervoltage alarms on 7KV buses. AP/1/A/5500/07, AP/2/A/5500/07 loss of onsite AC power' for more than 15 minutes. ,

4.2.6 Loss of all vital onsite Blackout load sequencers actuated. Tech Specs 3/8.2.3.,3/8.2.4 DC power for more than 15 DC bus undervoltage all buses and minutes, indications as in 4.2.5 above.

1 4.2.7 Complete loss of any Inability to establish charging pump OP/1/A/6100/04, OP/2/A/6100/04, j function needed for plant injection, and Inability to establish AP/1/A/5500/17. AP/2/A/5500/17 l hot shutdown. emergency feedwater flow, oj[ Inability j to establish service water flow, and j Inability to establish component j cooling water flow.

i 4.2.8 Transient requiring opera- Reactor remains critical after all EP/1/A/5000/01. EP/2/A/5000/01,

tion of shutdown systems attempts to trip reactor have been AP/0/A/5500/34 with failure to scram completed. .

(continued power genera-

tion but no core damage j immediately evident).

]

4 N -

ele .tt' all a

~

m .

RP/0/A/5700/03

- ENCLOSURE 4.2 PAGE 3 0F 6 .-

Initiating conditions Emergency. Action Level (EAL) Emergency Procedure / Document ,

4.2.9 Hajor damage to spent Observation of major damage to one AP/1/A/5500/25. AP/2/A/5500/25 fuel in containment or or more spent fuel assemblies, and/or fuel handling building spent fuel pool water below fuel level (e.g., large object ar.d IEHF-16 & 17, 2 EHF-3 or 4 or EHF -38

~ damages fuel or water 39,40or42alarys..

loss below fuel level). ,

4.2.10 Fire compromising the observation of a major fire Tech Specs 3/4.5 function of safety that defeats redundant safety Station Directive 2.11 Series systems. system or function.

4.2.11 Host or all alarms As determined by the Shift Supervisor / OP/0/A/6350/01A (annunciatora) lost and Emergency Coordinator.

' plant transient initiated j or in progress.

4.2.12 Airborne radiological For EHF35 Low Range, offscale HP/0/B/lD09/05. HP/0/B/lD09/09 4

effluent monitors detect High Range 8 x 10 cpm.

levels corresponding to (See Note 1)5 greater than 50 mr/hr For EHF36 Low Range 3 x 10 cpm g for 1/2 hour oj; greater High Range 7 x 10 cpm than 500 nr/hr W.B. for (See Note 1) i two minutes (or five times j these levels to the thy- For EHF37 Change of 143 cpm / minute roid) at the site boundary for 30 minutes or a for adverse meteorology change of 1430 cpm / minute (See Note 2). for 2 min'utes (See Note 1).

NOTE 1: These values are worst case calculations and may not ref. lect more favorable weather conditions.

I 1

1

,$ 4 h e *9 'f

,f* .[

e RP/0/A/5700/03 ENCLOSURE 4.2 PAGE 4 OF 6 ,

i Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document NOTE 2: These dose rates are projected based on other plant parameters (e.g.,

radiation level in containment with leak rate appropriate for existing contain-ment. pressure) or are measured in the i

environs. (EPA Protective Action Cuide-lines are projected to be exceeded out-side the site boundary).

4.2.13 Inminent loss of phy- Physical attack on the plant involving Station Security Plan sical control of plant. 1susinent occupancy of control room and

, auulliary shutdown panels.

4.2.14 Severe natural pheno- RP/0/A/5700/06 RP/0/A/5700/07 ;

mena being experienced or projected with plant

not in cold shutdown.

3 4.2.14.1 Earthquake greater than (>.153 H >.lgV) as determined by moni-SSE (Safe Shutdown Earth- toring seismic instrumentation and quake) levels, recording devices. (SMP-1) 4.2.14.2 Flood, low water, hurri- As determined by Shift Supervisor /

l cana surge, seiche greater Emergency Coordinator.

l than design levels (lake j tidal waves) or failure 3

of protection of vital .

4 equipment at lower levels.

4

! 4.2.14.3

Sustained winds or torna- (>95 mph) as observed or documented does in excess of design by the National Weather Service levels. Information.

,nl . j

RP/0/A/5700/03 ENCLOSURE 4.2 PEE 5 0F 6 .

~1nitiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document 4.2.15 other hazards being ex- RP/0/A/5700/08. RP/0/A/5700/09

! perienced or projected j with plant not in cold shutdown.

4.2.15.1 *

Aircraft crash affecting Aircraft crash causing damage or vital stnictures by in- fire to: Containment Building.

pact or fire. Control Room. Auxiliary Building.

Fuel Building, or . Intake Structure.

i 4.2.15.2' '

l Severe damage to safe loss of functions ne'eded for hot

, shutdown ejuipment from shutdown as in 4.2.7.

j missiles or explosion.

I 4.2.15.3 i Entry of uncontrolled Entry of uncontrolled or toxic or

, flammable gases into flammable gases into: Cor. trol Room, vital areas. Entry of Cable Spreading Room. Containment uncontrolled toxic Building. Switchgear Room. Safe l gases into vital areas Shutdown Panels or Diesel Rooms.

where lack of access to the area constitutes a safety problem.

j i

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RP/0/A/5700/03

, ENCLOSURE 4.2 PACE 6 0F 6 .

Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document ,

l 4.2.16 Other plant conditions As determined by Shift Supervisor / As dictated by Plant conditions.

exist that in the judge- Emergency Coordinator.

ment of the Shift Super-visor..the Operations Duty Engineer, the Super-intendent of Operations, or the Plant Manager war-rant activation of emer- , ,

gency centers and moni-toring teams and a .

precautionary public notification to the public near t'a site.

3 4.2.17 Evacuation of control As determined by Shif t Supervisor / OP/0/A/6350/02. AP/1/A/5500/17 i

room and control of shut- Emergency Coordinator. AP/2/A/5500/17 down systems not established from local stations in 15 minutes.

)

i t

1 i

9

.6 , .

RP/0/A/5700/03 ENCLOSURE 4.3 PAGE 1 0F 1

(

NOTIFICAIION/ ACTIVATION GEFERAL EMERGENCY Noti',/ Activate the following personnel /or Emergency Centers for all Initiating Conditions listed'in Enclosure 4.2. (See Enclosure 4.4 for Telephone Listing)

NOTIFY / ACTIVATE NOTIFICATION COMPLETE-INITIAL Shift Supervisor Operations Dutv Engineer q Station Manager Superintendent of Ooerations Superintendent of Technical Services Projects and Licensing Engineer Station Health Physicist North Caro 14nm State Warning Point Mecklenburg Countv Warnina Point Lincoln County Warning Point Cataubk County Warning Point Iredell County Warning Point Gaston County Warning Point Cabarrus County Warning Point South Caro 14== State Warning Point N.R.C. via ENS (Red Phone)

N.R.C. Station Ranresentative Superintendent of Maintenance Superintendent of AA=4nistration Construction Project Manager Activate T.S.C. (Station Directive 3.8.2) -

Activate 0.S.C. (Station Directive 3.8.2)

Activate C.M.C. (Enclosure 4.6)

g?/0/A/5700/03 ENCLOSURE 4.4 pact. 1 OP 6 Tvt WHOSE LIS G O l 4.4.1 Operations Dut? En estem) 4 P&T Pager 4.4.2 Station Manage i Home - System Speed Home System Speed 4.4.3 Superintendent o Rome erations %

" System Speed

~

4.4.4 Superintendent of Te hnical Services - ,

Home - #ystem Spee ,

2 4.4.5 Projects and Licensing Engineer {

Ecme System Spee 4.4.6 Station Esalth P st < /

Ho:2e tem Speed ,

P&T Page 4

4.4.7 NC State Warning Point, Raleigh - System Speed -

4.4.8 Mecklenburg Councy Warning Point - Primary: Down Phone 1

Back-up: System Spee Back-up: Emergency Radio, Code:

4. 4. 9 Lincoln County Warning Point - Primary: Devn Phone Back-up: System Speed Back-up: Emergency Radio. Code:

4.4.10 Cacada Coung WaM W ~ Devn Phone

~

3 p, Radio de 4.4.11 Iredell County Warning Point - Pr138T7 Back p System Speed mergenC7 Radio, Code:

4.4.l9* Gaston County Warning PO D E . Primary- Phone 3ackWp: System 3 peed I Back-up: Emergenc? Radio, Code:

4.4.13 Cabarrus Count? Waruing Po 25 Primary: ?hene 3ack-up: ' System Speed Back-up: :sergenc7 Radio, Code:

NOTE i Radio Code bl*** **

all county radio unus.

2. P&T Pager, Ce er ton (Charlotte Area)

~-

RP/0/A/5700/03 ENCLOSURE 4.4 4 PAGE 2 0F 2 i

TELEPHONE LIST I

4.4.14 SC State Warning Point 4.4.15 N.R.C. Operation Center, Emergency Notification System (ENS Phone) 1 4.4.16 N.R.C. Station Representative (Bill Orders)

Office Home System S l P&T Pa ice Pager ,

For P&T Page from Central (MNS Area) .;

4.4.17 Construction Project Manager _ Construction Ext. ~r.

Home : ystem Sp System Speed 4,4.18 Supe.rintendent of Maintenan Home System Speed 4.4.19 Superintendent of AA4"4*tra Home stem Speed 4.4.20 Nuclear Production Duty Engineer - System Speed P&T Page 4.4.21 Radiation Protection Section Denartment of Human Resources- _.

ystem Speed i

w-mm.a ar nw- e-mm--m m-w w om-w-e-,--o,- - -a , - w- ne--w--,_ _ _ - - - - - - - - - - - _ _ _ _ a- - - - - - - _ - - - _

.C 1 WARNINGWAGE:NUCtEARFACIEIUS.TGSlNTEEOCRdM instructions:

RP/0/A/5700/03 A. For Sender: ENCI,OSURE 4.5 PAGE 1 0F i

1. Complete Part I for the Initial Warning Message.

2. Complete Parts I & 11 for followup messages.

S. For Receiver-

1. Record the date, time and your name in the area be!ow.

2. Authenticate this message by verifying the code word or by calling bacx to tne facility. (See Part i .5)

Time: Date: :

Message Received By:

MGk%A.. ',6 ? ] .. . . PARTEM~

1. This is: McGui:e Nuclear Staciet:

tinsert name of facdity)

2. My name is:

l l

3. This message (number _.):

(a) Recorts a neal emergency.

(b) is an exercise message.

4 My telephone number /extansion is:

5. Message authentication:

(venty coae wora or can sacx to :ne facdity)

( 6. The efans of the emergency is: (a) Notification of Unusual Event (b) Alert (c) Site Emergency (d) General Emergency

7. This efassification of &T+ pq was declared at: (a.m./p.m.) on (date).

8. The initiating event causing the emergency classification is:

l

9. The emergency condition: (a) Oces not invcive tne release of racicactive materials '*cm

ne :: tant.

(b) Involves the ::otential for a release, cut no release is cecurnng.

(c) Involves a release of radioactive material.

^

RP/0/A/5700/03 ENCLOSURE 4.5 PAGE 2 OF 4

10. We recommend the followmg WLv action:

(a) No protective action is recommended at this time.

(b) People living in zones remain indoors with the doors and windows closed.

(c) People in zones evacuate their homes and businesses.

(d) Pregnant women and children in zones remain indoors with the doors and windows closed.

(e) Pregnant women and chiioren in zones - evacuate to the nearest shelter / reception conter. , ,_

(f) Other recommendations: -

11. There will be:

(a) A followup message (b) No further communications

12. I repeat, this message: PART I APPROVD FOR RELEASE (a) Reports an actual emergency Signature (Faergency Coordinaccr)

(b) is an exercise message I

13. RELAY THIS INFORMATION TO THE PERSONS INDICATED ON YOUR ALERT PROCEDURE FOR AN INCIDENT AT A NUC:. EAR FACILITY.

- - END OF INITIAL WARNING MESSAGE ~

4C5741. ;~m rm~.PARTIE - - ' _ - - . ],]'fj

1. The type of actual or protected reieuse is:

(a) Airborrn (b)- Waterborne i

I (c) Surface spill ,

a (d) Other

2. The source and h es. of the reisess is:

3. (a) Reisess bogen/will begin se_a.mdp.m.: time since reactor trip is hours.

(b) The estrmeted duration of the reisess is hours.

me c --- ..:--sw-.- -- ,,-%--.w- , , . , - , . - - - - - - , - - - , - - - - - - - - ,, - , , , - , - .-,,.-v.

~ .

RP/0/A/5700/03 -

ENCLOSITRE 4.5

4. Dose projecnon base date:

" 3 0# '

'\ Radiological releess: curies, or curies /sec.

Windspeed: mph Wind direction: From Stability class: (A.E.C,D,E,F, or G)

Release height: Ft. '

Dose converson factor: R/hr/CI/m3 (whole body)

R/hr/CI/m3 (Child Thyroid) =

s.

j-Precipitation:

Temperature at the site: 'F

5. Dose propostions:

Dose Commetment*

M Sody '

(Child Thyreid)

Disance Rem / hour Rem / hour of inhalecon Site bounderv I I 2 miles - l ,

4 5 miles I i 10 miles

' Proposed ineground Dose in Rem

Distence l Whole Body l Child Thyroid Site Bounderv i 8 7 miles 1 I 5 miles I i 10 miles

6. Field measuvunent of dose rees or contemmation (if evasiebie):

L

7. Emergency estions undenemy at the feeility insiude:

8. Oneste support needed from offsite organizenons:

9. Plaint status:

(a) Reactor is: not tripped / tripped (b) Plant is at: % power / hot shutdown /ccid snutdown/ cooling cown (c) Prognosis is: stacle/ improving / degrading / unknown.

,-,-,-,---m . - , - - - , - . ,.._-,-,-,-_,,n_n., _ . . , - , - . . , _ . , - . _ , , _ . .

,,,,n,,,_-. .. . ,_wg , _n_,,,,.. ,, ,

RP/0/A/5700/03

, 10. I ropest, this message: F 4

,\

(a) Reports an actual emergency.

(b) is an exercise message. PAC I and !! APPROC FOR FI.IASI

11. Do you have any quWons? Signature (Isergesey coereinator)

[NY-NM((Eh 301 e dei-EIII.le W ;;[d if.;J 6i-A%1e1:::i Uf--_ h-j!f2bl5h:.[EYM _

NOTE: Record the name, tide, data, time, and woming point notified. (Senders)

Record the name tite, date, time, and persons nonfied per alert procedure. (Receivers)

1. s (name) .(title)

J..

~1 -E~

(date) (t ime) (warning point) 2.

(name) (title)

(date) (time) (waming point) 3.

(name) (title)

(date) (time) (warning point) 4.

(name) (title)

(osto) (ume) (warning point 5.

(name) (trtie)

(cate) (time) (warning point)

. 6.

(name) (titie)

{

a (cate) (time) (warning point) 7.

(name) (titie)

(cate) (time) (warning point) 8.

(name) (title)

(date) ( 1me) Orarning point)

Form 34888 (6-821

. o RP/0/A/5700/03 ENCLO3URE 4.6 PAGE 1 0F 1 EMERGENCT PLAN 'iESSACE FORMAT I

(Nuclear Station to Nuclear Production Duty Engineer) 1 l

l i

1. This is at McGuira Nuclear Station.

(Naam and Title)

This is/is not a Drill. An

2. Unusual Event ,

-Alert .

Site Area Emergency -

_ General Emergency was declared by the Emergency Coordinator at on Unit Number .

(Time)

3. Initiating Condition: (Give as close to the emergency procedura description as possible together with station parameters used to determine amargency status)

4. Corrective Measures Being Taken:

5. There Have/Have Not been any injuries to plant personnal.

6. Release of radioactivity: Is/Is not taking place, and is/is not affecting the Crisis Management Cantar.

7. NRC Yes No, State Yes No, Counties Yes No, have been notified.

8. The Crisis Management Tass should/should not be activated. Corporate Con ==mications and Company Management should be notified (Unusual Event only).

9. I can be reached at for follow-up infonaation.

(Talephone Number)

10. Additional Comments:

i

. o Form SPD-1002-1

\

DUKI POWER COMPANY (1) ID No: RP/0/A/5700/04 PROCEDURE PREPARATION . Change (s) v to PROCESS RECORD 0 Incorporated (2) STATION: McGuire Nuclear Station (3) PROCEDURE' TITLE: General Energency

_., , ln -

PREPARED BY: S.y(Glover f

+ ~ %m (4) DATE: 4/14/83 Q (5) REVIEWED BY: I

,m b DATE: 4,//J"772 Cross-Disciplinary Review By: N/R: V4 (6) TEMPORARY APPROVAL (IF NECESSARY):

By: (SRO) Date:

By: Data:

(7) APPROVED BT:

Date: V//// P ?

(8) MIST'FTTA m 05:

Reviewed / Approved By: Date:

s

. u RP/0/A/5700/04 PAGE 1 0F 4 DUKE POWER COMPANY McGUIRE NUCLEAR STATION.

,N GENERAL EMERGENCY 1.0 Symptoms 1.1 Events are in process or have occurred which involve actual or i==4nant substantial core degradation or salting with potential for loss of con-tainment integrity.

2.0 Immediate Action 2.1 Automatic 3y:

Nona ?

-s-2.2 Manual 2.2.1 h Shift Supervisor shall be informed of all events initiating this procedure.

3.0 Subsequent Actions Initial /N/A

/ 3.1 h Shift Supervisor shall assure that the appropriate emergency condition (Notification of Unusual Event Alert Site Area Emergency, or General Beergency) is dhclared by evaluating the actual plant condition with Enclosure 4.1. Emergency Classification U and Enclosure 4.2. List of Initiating Conditions, Imergency Action Levels, and Associated Emergency 1 l

Procedure / Document.

/ 3.2 h Shift Supervisor shall ensure that all actions required j by the initiating Emergency Procedure will be. performed and that all actions necessary for the protection of persons ;

and property are being taken.

l NOTE If at any time in the course of events in this procedure, site evacuation or personnel assembly /

accountability appears necessary, refer to Station Directive 3.8.1. <

j

/ 3.3 h Shift Supervisor shall assume the function of the Emergency Coordinator until'the arrival of the Station Manager or his designee, at which time the Station Manager or his designes assumes the responsibility of the Emergency Coordinator.

l l

l l l

l l

. l

RP/0/A/5700/04 PAGE 2 0F 4

/ 3.4 The Emergency Coordinator shall assure prompt (within about 15 s'

minutes of declaring the emergency) notification of the North Carolina State and South Carolina Warning Point and Local County Warning Points indicated on Enclosure 4.3. He shall also assure notification of all other personnal listed in Enclosure 4.3.

NOTE 1 Activation of the Technical Support Center (TSC) and Opehacions Support Center (OSC) shall be in accordance with Station Directive 3.8.2. Activation of the Crisis

.7 Management Center (CMC) shall be in accordance with 3 Enclosure 4.6. 3 NOTE 2 See Enclosure 4.4, Telephone Listing, for notification, telephone numbers / radio codes /pagar codes.

NOTE 3 See Enclosure 4.5, Warning Massage: Nuclear Facility to State / Local Government, fer information to be provided to State / County Warning Points.

/ 3.5 The Emergency Coordinator in direct' contact with the Technical Support Center sad the Crisis Management Center will assess and respond to the emergency by:

3.5.1 Dispatching the onsite and offsite monitoring teams with associated c-=4 cations.

3.5.2 Provida meteorological sad dose estimates to offsite authorities for actual releases via a l dedicated individual or automated data trans-i l , mission.

l 3.5.3 Provide release and dose projections based on

, available plant condition information and fore-l seeable contingencies to offsite authorities.

NOTE l In the event a release or potential release of radioactive materials is a threat to plant pe'rsonnel or members of the general public, the Emergency i Coordinator shall utilize the Operator /td Computer (OAC) " NUCLEAR-23" progrsa to assess the offsite i~

i l

l

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RP/0/A/5700/04 PAGE 3 0F 4 co.tsequences. In the event the (OAC) is not operational the Emergency Coodinator shall request l Health Physics personnel to evaluate the consequences )

ut1}izing the appropriate Health Physics procedure, !

HP/0/B/1009/C5, HP/0/B/1009/06, HP/0/B/1009/08 HP/0/B/1009/09, or HP/0/B/1009/10. !

/ 3.6 The Paargency Coordinator shall provide protective action recommendations.as necessary to the affected county warning point (s) and to the North Cardlina Warning Point (Emergency p Operations Centers if established) or to state Radiological y Protection Section Department of Human Resources (See Enclosure "n 4.4, Telephone Listing) as directed by the state in accordance with the North Carolina Radiological Emergency Response Plan. If evaluation indicates that a potential for an actual release of radioactive materials will result in a projected dose (REM) to the population of: (EPA Protective Action Gnid=14nma) 3.6.1 Whole body <l, Thyroid <5, No protective action is required. Monitor environmental radiation levels to verify.

3.6.2 Whole body 1 to <$ Thyroid 5 to <25, recommend seeking shelter and wait for further instructions.

Consider evacuation particularly for children and pregnant women. Monitor environmental radiation levels. Control access to affected areas.

3.6.3 Whole body 5 and above, Thyroid 25 and above, recommend usadatory evacuation of populations in the affected areas. Monitor environmental radiation levels and adjust area for Mandatory evacuation based on these levels. Control access to affected areas.

NOTE See Enclosure 4.4 Telephone Listing for notification. -

t n

RP/0/A/5700/04 PAGE 4 0F 4

/ 3.7 The Emergency Coordinator in coordination with the Recovery y Manager, at the Crisis Management Center, will provide or make available:

3.7.1 A dedicated individual for plant status updates to offsita authorities and periodic press briefings.

3.7.2 Senior te* w ~1 and management staff onsite available for consultation with the NRC and State on a periodic basis.

/ 3.8 The Emergency Coordinator in coordination with the Recovery Manager at'the Crisis Management Center will assess the 3 emergency condition and determine the need to remain in a 7 General Faergency, reduce the emergency class, or close out the emergency.

/ 3.9 The Recovery Manager at the Crisis Management Center will close out the emergency or ree et reduction of the Emerg6.cy class by briefing the offsite authorities at the Crisis Management Center or by phone if necessary, followed by written summary within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

4.0 Eoclosures 4.1 Emergency Classification Guide Flowchart 4.2 List of Initiating Conditions.,Inargency Action Levels, and Associated Emergency Procedure / Document.

4.3 Notification Chart.

4.4 Telephone listing.

4.5 Warning Message: Nuclear Facility to State / Local Government 4.6 Emergency Plan Massage Format 0

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. I.t. !.! !

. . !.!. i.s. ' !.

. I.i a a s : e s ! ! ! !! !

.-.e*. -- , w,r g..s.,, , ,.,,--- -

3 -

-->._,,,.,.,,.,,,.-,,%,--,--.-----,-,-,,,,---,--..,--,,,_,,.,..,,-,.,----m ,,e v,-,-- - ,-

'~ *

( .

RP/0/A/5700/04 ENCLOSURE 4.2

. PME 1 0F 6 ,

LIST OF INITIATINC CONDITIONS. ENERCENCY ACTION LEVELS AND ASSOCIATFD EMERCENCY PROCEDURE / DOCUMENT Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document 4.2.1 Effluent monitors detect As observed by control room personnel. HP/0/B/1009/05 levels corresponding to I rem /hr Whole Body or 5 ren/hr Thyroid at the site boundary under actual meteoroloalcal conditions.

l NOTE 1: These dose rates are projected base on

plant parameters (e.g.,

radiation levels in con-

, tainment with leak rate appropriate for existing containment pressure with some confirmation from effluent monitors) or are measured in the environs.

! NOTE 2: Consider evacuation

only within about 2 miles of the site boundary unless these 3 levels are exceeded by a fac- .

l tor of 10 or projected to con-j tinue for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months or EPA Pro-

tective Action Cuideline exposure levels are predicted to be exceeded at longer distances.

4.2.2 Loss of 2 of 3 fission pro- 1. Loss of coolant accident as HP/0/B/1009/05. AP/1/A/5500/05, duct barriers with a poten- identified in Site Area Emergency AP/2/A/5500/05 tial loss of 3rd barrier. 4.2.1, and incomplete contain-(e.g., loss of primary inent isolation.

, coolant boundary, clad-failure, and high poten- 2. Loss of coolant accident as iden-tial for loss of contain- tified in Site Area Emergency 4.2.1 i ment integrity).

' andContainmentMonitoragarms(EHF51A and/or B) greater than 10 R/hr and con-tainment pressure greater than 14.8 peig for at least 2 minutes. , g; 4, hl 'tf i

RP/0/A/5700/04 ENCLOSURE 4.2 PAGE 2 0F- 6 '

4 l Initiating Conditions Emergency Action Level (EAL). Emergency Procedure / Document 4.2.3 Loss of physical con- Physical attack of the facility has Station Security Plan.

- trol of the facility. resulted in occupation of the con-trol room and auxiliary shutdown NOTE: Consider 2 mile facility.

precautionary evacuation.

4.2.4 other plant conditions As determined by the. Shift Supervisor / As dictated by plant conditions.

i exist, from whatever Emergency Coordinator and verified by l source, that in the judge- EAL's defined in Implementing Procedures ment of the shift super- . utilized up to this point.

visor, the Operations Duty Engineer, the Superinten- '

dent of Operations, or the' Plant Manager make release of large amounts of radio-activity in a short time .

period possible (e.g., any 1 core melt situation).

a. For core melt sequences where significant re-leases are not yet j 'taking place and large

amounts of fission pro-ducts are not yet in the containment atmos-phere, consider 2 mila l precautionary evacua-tion. Consider 5 mile downwind agacuation l (45* to 90 sector) if large amounts of 4

fission products

! (greater than Cap acti-

} vity) are in the con-tainment atmosphere.

Recommend sheltering in i other parts of the plume exposure Emer-gency Planning Zone under this circumstance, til ill k

[" ,, ' , , , ,

RF/0/A/5700/04 ENCLOSURE 4.2 PACE 3 0F 6 e-Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document

b. For core melt se-quences where signi-

, ficant releases from -

, containment are not 1

yet taking place and containment failure leading to a direct atmospheric release

is likely in the se-quence but not immi-nent and large amounts of fission products in addition to noble I

gases are in the con-tainment atmosphere, consider precautionary evacuation to 5 miles and 10 mile dognwind g evacuation (45 and '

90 sector).

] c. For core melt se-quences where large 4

amounts of fission products other than noble gases are in the containment atmosphere and con-l tainment failure la i judged imminent, re -

commend shelter for those areas where evacuation cannot

be completed before transport of acti-vity to that loca-l tion.

1 1

l .

'Id el 4

.,~

/' ,

/ .,

RP/0/A/5700/04 ENCLOSURE 4.2 4 PACE 4 OF 6 ,

Initiating Conditions Emergency Action Level (RAL)

Emergency Procedure / Document

d. As release informa- -

tion becomes available adjust these actions in accordance with dose projections, time available to , ,

evacuate and esti- ' -

mated evacuation times given current

,. conditions.

, e. Example Sequences

l. Small and large Safety injection signal plus reac-

, LOCA's with fall- tor trip ands ure of ECCS to per-

+

form leading to 1. Safety injection and RHR severe core de- pumps not running.

' gradation or melt.

Ultimate failure 2. Flow indications for safet.y of containment injection read "0". *

!. likely for melt l spquences. (Seve- 3. High containment sump level.

ral hours likely to be available'. For Severe Fuel Over Temperaturer j to complete pro- Creater than 101 failed fuel i tective actions indicated by greater than unless containment 13,000pci/ml-131 concentration.

is not isolated).

For Fuel Helt Conditions:

Creater than SI failed fuel-4 indicated by greater than I II,800pC1/ml I-131 concentration.

I *-

. ' hl isl 'd

i

~ ?. <

RP/0/A/5700/04 ENCLOSURE 4.2 PAGE 5 OP 6 ,

Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document a

2. Transient ini- Reactor trip on Lo Lo Steam Generator AP/1/A/5500/06, AP/2/A/5500/06 tiated by loss ldval and wide range generator levels EP/1/A/5000/04, EP/2/A/5000/04 of feedwater and toward offscale low on all steam generators condensate sys- and emergency feedwater flow indica-tems (principle

tors indicate "0" flow cg; emergency heat removal sys- feedwater pumps not running and can-

tem) followed by not be restored within 30 minutes $3(

failure of emer- >31 reactor power and loss of both -

gency feedwater main feedwater pumps, manually trip

! system for ex- reactor.

tended period.

(Core melting is i

possible in seve-ral hours with I ultimate failure

] of containment 2 likely if the i core melts).

{ 3. Transient requir- Reactor remains critical after all AP/0/A/5500/34 *

ing operation of attempts to trip the reactor are

' ~

shutdown systems complete and flow indicators on with failure to- safety injection and RHR show "0" scram. Core dam- flow after initiation (NVP5440, I

age is likely. NDP5190, 5191, 5180, 5181,

, Additional failure MIP5120, 5450) cyt safety injec-of the core cool- tion and RHR pumps not running ing and makeup with safety _ injection initiated, system would lead j to core melt.

l t

f 4

4 1*

'td64'4 i

m

,r :

I .

RP/0/A/5700/04 ENCLOSURE 4.2 PAGE 6 0F 6 g

. Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document

4. Failure of offsite Undervoltade alarms on 7KV buses and AP/1/A/5500/07, AP/2/A/5500/07 and onsite power blackout load sequencers actuated and along with totp1 auxiliary feedwater pump (s) fail to loss of emergency start.

i feedwater makeup 6 capability for l several hours.

Would lead to eventual core melt and likely failure of con- .

tainment.

5. Small LOCA and Pressurizer low pressure reactor trip EP/1/A/5000/02, EP/2/A/5000/02,

initially suc- and pressurizer low pressure safety AP/1/A/5500/05, AP/2/A/5500/05 j cessful ECCS. injection signal and RHR flow indica- ,

Subsequent fail- tors show "0" flow after shift to RHR ure of containment is attempted and for greater than 2 heat removal sys . hours (NDP5190,5191,gl80,5181)and tem over several Reactor Coolant (NC) T is rising, hours could lead and containment air handling system to core melt and fails to function, likely failure.of j containment.

. NOTE: For melt se-quences or for failure of containment isola- ~

tion systems, the likely

] failure mode is melt through with release of gases.

, 4.2.5 Any major internal or ex- As determined by.the Shift Supervisor / As dictated by plant conditions.

ternal events (e.g., fires. Emergency Coordinator. '

earthquakes substantially

beyond design levels) which could cause massive common 1 damage to plant systems.

I i

I'

ol iis \1 4

y 12/0/A/5700/04 ENCLOSURE 4.3

\

PAGE 1 0F 1 u

NOTIFICATION /ACTIVATICK '

GENERAL DERGENCT

. +

l Notify / Activate the following personnel /or Emergency Centers for all Initiating Conditions listed in Enclosure 4.2. (See Enclosura 4.4 for Telephone Listing) 4 NOTIFT/ ACTIVATE 'NOTiTIC1fION COMPLETE-INITIAL Shift Supervisor # l Operations Duty Engineer ns ._

fV I

~

Station Manager

Superintendent of Operations i Superintendent of Technical Services s Preiec*n and Licensing Engineer Station Health Physicist North Carolina State Warning Point Mecklenburg County Warning Point Lincoln County Warning Point Catawba County Warning Point .

Iredell County Warning Point

.Gaston County Warning Point i Cabarrns County Warning Point

_ South Carolina State Warning Point /

N.R.C. via ENS (Rad Phone) i N.R.C. Station Representative Superintendent of Maintenance Superintendent of Administration Construction Project Manager i -

Activate T.S.C. (Station Directive 3.8.2)

Activate 0.S.C. (Station Directive 3.8.2) '

Activate C.M.C. (Enclosure 4.6)

\ '

9 l i [',

s

~.

, , _ _ _ ~ . . - - - - , m , _ _ , , _ , . ,.,_,__,_,,y,, , _ , , _ , , , , _ _ _ _ .,m,_y,_

m. _ , _ . , _ . , , , , _ , _ _ _ _ , , , _ _ , , . , _

__,,,w____, , , , , , , , ,, %_s _ . . . _ _ _ , .

Instruccons: RP/0/A/5700/04 DiCLOSURE 4.5 For Sender: pggg i op 4 A.

1. Complete Part i for the Initial Warning Message.

l

2. Complete Parts I & 11 for followup messages.

I

5. For Receiver: j i

1. Record the date, tice anc your name in the area below,

' )

2. Authenticate this message by verifying the code word or by calling back to the facility. (See Part ! .5)

.=

i

Time: Date: 1 Message Received By:

9:c, L . . ; -

. Y j ?' " -j. M y y ' .

.. . . ' . '

J ~;~ ::Q':Q

1. This is: ww - w ' - -- e e * < -

Onsert flaffte of f4Cliity)

2. My name is:

3. This message (number ):

(a) Reports a real emergency.

(b) is an exer.ise menage.

4. My telephone number / extension is

5. Message authentication:

(venty caos wore er esa becx to me tac: lim l

6. The class of the er,m e.cy is: (a) Notification of Unusual Event (b) Alert l

(c) Site Emergency (d) General Emergency

7. This classification of emergency was declared at: (a.m./p.m.) on (date).

8. The initiating event causing the emergency ciassification is;

9. The emergency condition: (a) Coes not involve the release of radioactive materials frem j

I the plant.

(b) Involves the ::otential for a release, but no release is occurring.

(c) involves a release of radioactive material.

< y I

~

RP/0/A/5700/04 i ENCLOSURE 4.4 PAGE ~~

2 0F 2 TELEPHONE LIST 4.4.14 SC State War:dng Point 4.4.15 ' N.R.C. Opetation Center, Emergency Notification System (EN5 Phone) 4.4.16 N.R.C. Station Representative (Bill Orders)

Office Home - System P&T Pager site Pager

^

For P&T Page Central (hMS Area) 4.4.17 Construction Project Manager Construcci Ext. -

Home yst f i ysten Spar 'I l 4.4.18 Superintendent of Maintenan l Home Syn Speed 4.4.19 Superintendent of Admintegrati Home stem Speed 4.4.20 Nuclear Production Duty Engineer - Systen Spee P&T Page 4.4.21 Radiation Protection Section. Department.of Human Resources-

.-System Speed I

q 4

l t

I l

c I

i a

l i

! l

..---m-,-o, ,,----m-.,..e----n.m-, ,--.,na _,n.---,,----_,r, eevp-a_.--,-ww-ww---- - - -- ---- -

.7 l

~~

l RP/0/A/5700/04 j

ENCLOSURE 4.4

(

1

[

PAGE 1 0F 2 :

TELEPHONE LISTING I i .

! 4.4.1 Operations Duty Engineer (PA System)

P&T Pager l i

i 4.4.2 Station Manager

, Home - - System Speed - -

Home - System Speed I 4.4.3 Superintendent of acionp' l

} Home - Sysces Spee l

1 l 4.4.4 Superintendent of Tee 1 , Services ,'

Home System Speed ~i 1l

! 4.4.5 Projects and Licensing Engineer 1 ll Home ~ System Speed 4.4.6 Station Esalth Phfsicist ,-k

Home - System Speed P&T Page 4.4.7 NC State Warning Point, Raleigh - System Speed 4.4.8 Mecklenburg County Warning Point - Primary: Rin Down Phone Back-up: System Spee Back-up: Emergency Radio, Code:

j 4.4.9 Lincoln County Warning Point - Primary: Rin Down Phone I

Back-up: ' System Spes i

Back-up: Energency Radio, Code:

4.4.10 Catawba County Warning Point - Primary: Rin Down Phone Back-up: ' System Spee Back-up: Emergency Radio, Code:

4.4.11 Iredell County Warning Point - Primary: Rin Down Phone Back-up: -System Spee Back-up: Emer cy Radio, Code:

4.4.12 Gaston County Warning Point - Primary: Down Phone Back-up: System Spee Back-up: Radio, Code:

4.4.13 Cabarrus County Warning Point - Primary: Rin Dcwn Phone Bach-up: - System Speed i

Back-up: Emergency Radio, Code:

NOTE

1. Radio Cod 1 activate all county radio units.

2. i&T Pager, Centra sion (Charlotte Moa)

Dial .-

l

^

RP/0/A/5700/04

. ENCLO5URE 4.5 PAGE 2 0F 4

10. We recommend the following protective action:

, (a) No protective action is recommended at this time.

\

(b) People living in zones remain indoors with the doors and windows closed.

(c) People in zones evexate their homes and businesses. l (d) Pregnant women and children in zones remain indoors with the doors and windows closed.

(e) Pregnant women and children in zones , evacuate to the nearest '

shelter / reception center. ,,

(f) Other recommendations:

11. There will be:

(a) A folicwup message (b) No further commun'cations -

12. I repeet, this meessge: .

PART I TROVID FOR RTT7AME (a) Reports an actual smorgency (b) is an exercus message Signacure (Emergency Coordinacor) i

13. RELAY THIS INFORMATION TO THE PERSONS INDICATED ON YOUR ALERT PROCEDURE FOR AN INCIDENT AT A NUCLEAR FACILITY.

- - END OF INITIAL WARNING MESSAGE ***

PART 11 r-

1. The type of actual or projected release is:

(a) Ahtorne (b) Waterbome (c) Surface spill (d) Other

2. The source and descripdon of the reisese is:

3. (a) Reisese bogen/will begin at_a.mJp.m.; time since reactor trip is hours.

~

(b) The estimated duration of the reisess is hours.

--w y-,---v y y -w -,,,wem,- --,---,,--,--,w.w-m--r -

---,-- y-.,-,-

RP/0/A/5700/04 ENCLOSURZ 4.5 ~

OF 4

4. Does projection Lm deta:

Radiological reisese: curies, or curies /nc.

7

\ mph

) Windsosed:

Wind direction: From Stability class: (A,B,C,D,E,F, or G)

Reisess height: ,

Pt.

Does conversion factor: R/hr/Ct/m3 (whole body)

R/hr/C!/m3 (Child Thyroid)

F

, Precipitation: T

=

~-

Temperature et the site: *F

5. Does progestions:

'Does Commitment

VWtole Body (Child Thyroid)

Dionnoe Rem / hoar Rem / hour of inhaistion Site boundary ,

2 miles 5 miles 10 miles

'Preisesed innsyneed Does in Rem

Dietence Whole Body Child Thyroid Site Boundary i 2 miles 5 miles 10 miles 1

8. Field measurement of done com or contemenodon (if avmiable): -

7. Emergency estions underway se the feuility instude:

a. onsite support needed from offste orgenssocions:

9, Plant status:

, (a) Reactor is: not tripped / tripped (b) Plant is at: % power / hot shutdown / cold shutdown / cooling down (c) Prognoms is: stable / improving /degreding/ unknown.

RP/0/A/5700/04 ENCLOSURE 6.5 ;-

. 10. I ropest, this message: NE 4 0F 4 (a) Reports an actual emergency.

(b) is an exercise message.

Signature ( Emergency Coordinator )

i T U ; CT#.h?5M_t.***END: OE ECELOW'-Ul* MESSAMFx-r~6 NOTE: Record the name, title, dete, time, and woming point notified. (Senders)

Record the name title, dete, time, and persons notified per awt procedure. (Recewers) 1.

(name) (title) i y '

T (date) (time) (waming point) T l 2.

(name) (titie) j (date) (time) (waming point)

3. -

(name) (title)

(date) (time) (werning point) 4 (name) (title)

(cate) (time) (warning point) 5.

(name) (title)

(date) (time) (warning point) 6.

(name) (title)

(date) . (time) (warning point) 7.

(name) (title) l (date) (time) (Warning point) 8.

(name) (ti:le)

(da:e) (cime) p 3ggg g3 (warning point)

~ __ _ _. - - _ __ -_ - _____

4 e.

)e.

~

,- RP/0/A/5700/04 ENCLOSURE 4.6 PAGE 1 0F 1 7

\. EMERGENCY PLAN MESSAGE FORMAT (Nuclear Station to Nuclear Production Duty Engineer)

1. This is at McGuire Nuclear Station.

(Name and Title)

2. This is/is not a Drill. An _ Unusual Event Alert ,

Site Area Emergency ,

[

General Emergency p '

was declared by the Emergency , Coordinator at on Unit Number _ . j (Time)

3. Initiating Conditic a: (Give as close to the emergency procedure description as possible together with station parameters used to determine emerg:ncy status)

4. Corrective Measures Being Taken: ,_

5. There Have/Have Not been any injuries to plant personnel.

6. Release of radioactivity: Is/Is not taking place, and is/is not affe". ting the Crisis Management Center.

7. NRC _ Tes No, State Yes No, Counties _ Yes _ Ko, have been notified.

8. The Crisis Management Team should/should not be activated. ' Corporate Communications and Company Management should be notified (Unusual Event only).

j 9. I can be reached at for follow-uj information.

l (Telephone Number)

10. Additional Comments:

. , - .=- .--+y-+m9-wqpy .--g -

ML20085M967

Text

m W * = c w E = C w & O b M C e T=

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