ML20085N263
| ML20085N263 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire  |
| Issue date: | 09/06/1983 |
| From: | Glover M DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20085N241 | List: |
| References | |
| PROC-830906-01, NUDOCS 8311100346 | |
| Download: ML20085N263 (100) | |
Text
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r Form 34731 (10 81) /i (Formerly SPD.10r,21)
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DUKE PCWER COMPANY (1) ID No: RP/0/A/5700/01 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD 0 Incorporated l l (2) STATION: McGuire Nuclear Station . (3) PROCEDURE TITLE: Notification of Unusual Event m.] . $2
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(4) PREPARED BY: DATE: 8/31/83 (5) REVIEWED 3 . DATE: k-[8.3 *
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j Cross-Disciplinary Review By: N/ _ (6) TEMPORARY APPROVAL (IF NECESSARY): , 1 By: _ (SRO) Date: .
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(7) APPROVED BY: M ML ' f Date: 9/e//J A . (8) MISCELLANEOUS: , Reviewed / Approved By: Date:
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Reviewed / Approved By: Date:
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1.0 Symptoms *- ') 1.1, This conditien exists whenever unusual events are i[pso' cess or have
, . , e d, ' clc.currid which indicatI- a potential de'gradatiion of the ' level of safety
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// 2.1 Kanaal -- < , , m, 2'. 2.1 The Shift Supervisor shalLbe informed of an events initiating
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? 3.0 Sub'selaent Actions r, , i/
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g 3.1.In.e Shift Supervi, or/ , j - Emergency Coordinator shall assure that
' the appropriate emergerrey condition (Notification of Unusual Event,' Alerc, Site Aria Emergency, or General Emergency) is
' declared by evaluating the actual plant condition wich Enclosure
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, 4.1, Emergency Classification Guide Eloschart and Enclosure 4.2, List of Initiating Conditions, Emergency Action Levels, and
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~, ,- Associ.at,ed Emergency Procedure / Document.'
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,/ NOTE 4
,- The Shift Supervisor sh'au a"asume the function of
, ,~ the Emergency Coordinatoc ur.til the arrivel of the Station Manager or his designee at which time the Station Managek or his designee assumes the responsibility of the Emergency'Coordinatbr.
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3.2 The Emergency Coordinator a all assure that all actions k
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RP/0/A/5700/01 PAE 2 0F 4 required by the initiating Emergency Procedure (s) 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 assembly / accountability and/or evacuation of all non-essential onsite personnel appears n'ecessary, refer to Station Directive 3.8.1.
/ 3.3 The Emergency Coordinator shall assure prompt (within about 15 minutes of ceclaring 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 persos.nel listed in Enclosure 4.3. '
- NOTE 1 See Enclosure 4.4, Telephone Listing, for notification, telephone numbers / radio codes /pager codes.
NOTE 2 See Enclosure 4.5, Warning Hessage: Nuclear Facility to State / Local Government, for information l to be provided to State / County Warning Points. l l ( NOTE 3 l See Enclosure 4.6, Emergency Plan Message Format for information to be provided to Nuclear ! Production Duty Engineer.
/ 3.4 In the event a release or potential release of radioactive asterials is a threat to plant personniti or members of the general public the Emergency Coordinator shall utilize the Opeater Aid Computer (OAC) " Nuclear-23" program to assess the .
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RP/0/A/5700/01 PAGE 3_ OF 4 offsite consequences. In the event the (OAC) is not operational the Emergency Coordinator shall request Health Physics personnel to evaluate the consequences utilizing the appropri. ate Health Physics Procedure, HP/0/B/1009/05, HP/0/B/1009/06, HP/0/B/1009/08, HP/0/B/10J9/09, or HP/0/B/1009/10.
/ 3.5 The Emergency Coordinator shall provida protective action recosmendations as necessary to the affected county warning point (s) and to the North Carolina Warning Point (Emergency Operating Centers, if established) or the State Radiological Protection Section, Department of Th=an Resources (see Enclosure 4.7, Protective Action Recommendation Flow Chart) as directed oy the state, in accordance with the North Carolina 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).
3.5.1 Whole body <1, thyroid <5, No protective action is ( required. Monitor environmental radiation levels to verify. 3.5.2 Whole body 1 to <S, 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 i to affected areas. NOTE If this is the projected dose evaluate Site Area Emergency and General Emergency Initiating Conditions and Emergency Action l Levels.
- 4 *s 3.5.3 Whole body 5 and above, thyroid 25 and above, recommend mandatory evacuation of populations in the affected l
. RP/0/A/5700/01
- PAGE 4 0F 4 areas. Monitor environmental radiation levels and adjust area for mandatory evacuation based on these levels.
- Control access to affected areas.
NOTE If this is the projected dose, see General
. Emergency Procedure.
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, escalate to a more severe class or close out the emergency.
/ 3.9 The Projects and Licensing Engineeer or his designee will close ,
out the Emergency with verbal summary to those personnel and county and state authorities notified in Step 3.3, followed by written summary within 24 hours. 4.0 Enclosures ! 4.1 Emergency Classification Guide Flowchart ! 4.2 List of Initiating Conditions, Emergency Action Levels, and Associated Emergency Procedure / Document. 4.3 Notification Chart i 4.4 Telephone Listing 4.5 Warning Message: Nuclear Facility to State /Ldcal Government 4.6 Emergency Plan Message Format 4.7 Protective Action Recommendation Flow Chart. . i I l l _ - - . _ _ _ _ _ _ _ __ . . _ . _ . . . _ . . _ . - _ _ _ . _ _ _ _ ._. _ , _ ____.. _ _ _ ___ _ _ _
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A i RP/0/A/5700/01 - ENCLOSURE 4.2 PAGE 1 0F 5 i
! LIST OF INITIATING CONDITIONS, EMERGENCY ACTION LEVELS, AND i . ASSOCIATED EMERGENCY PROCEDURE / DOCUMENT ,
i i Initiating Conditions . Emergency Action Level (EAL) Emergency Procedure / Document h / I j 4.2.1 Emergency Core Cooling Safety Injection signal verification EP/1/A/5000/01, EP/2/A/5000/01 l
' Initiated (SI) and by redundant indication and indication EP/1/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, i occurred. EP/1/A/5000/04, EP/2/A/5000/04, j -
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 Technical Specification Technical Specification Limits exceeded. Tech Specs, HP/0/8/1009/09, a limits exceeded. HP/0/8/1009/10, HP/0/B/1009/05 l 4.2.3 Fuel Damage Indication: ,i < e
~
- a. High coolant activity a. >1 pCl/ gram Dose Equivalent I-131 or AP/1/A/5500/18, AP/2/A/5500/18, sample exceeding Tech. >100 pC1/ gram gross activity.
i Specs. E-l NOTE: These calculations avall-l - able from counting faci-j ,, lity on request. i
- b. Failed fuel monitor b. Increase in I-131 concentration by
, indicates Mechanical Clad 7pci/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 70pC1/m1 to 350 pCi/ml verified by j failures within 30 minutes, increased EMF-48 readings and labora-i tory analysis.
j 4.2.4 Abnormal coolant tempera- Figure 2.1-1 Tech Specs exceeded AP/1/A/5500/05, AP/2/A/5500/05 j 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 ) fication Limits. Instrumentation. (e.g narrow and wide i range pressure / temperature subcooling j monitors)
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RP/0/A/5700/01 , ENCLOSURE 4.2 PAGE 2 0F 5 i
. Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document Exceeding either primary / EP/1/A/5000/02, EP/2/A/5000/02, '
- 4.2.5 >1GPM total P/S leakage secondary leak rate >500 GPD from any S/G EP/1/A/5000/04, EP/2/A/5000/04, requiring shutdown by >10GPM Identifled Primary Leakage AP/1/A/5500/10, AP/2/A/5500/10
- Tech. Specs. or primary leak Verified by EMF readings, level control, rate requiring shutdown by make-up rate, and or chemical / radiological Tech. Specs. analysis.
l '4.2.6 Failure of a safety or Valid accoustical monitor indica- EP/1/A/5000/02, EP/2/A/5000/02, relief valve in a safety tion of valve failure. AP/1/A/5500/11, AP/2/A/5500/11, ., related system to close, EP/1/A/5000/03, EP/2/A/5000/03 following reduction of applicable pressure. (Prl- - j mary' System (NC) or Main
- Steam (SM). .
4.2.7 Loss of offsite power or Undervoltage alarms on 7KV buses AP/1/A/5500/07, AP/2/A/5500/07 i loss of onsite AC power or blackout load sequencers capability. actuated. i 4.2.8 Loss.of containment inte- Any automatic containment isolation AP/0/A/5500/24 < , grity. requiring shutdowa by valve found to be open and inoperable Tech Specs (3/4.6.1). and unisolable or both air lock doors
- or penetration (s) <
i on fall aleak locktest inoperable, per Tec F Specs when con-j tainment integrity required. , I 4.2.9 Loss of engineered safety ESF actuation system found inoperable AP/1/A/5500/19, AP/2/A/5500/19,
; 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 j 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
I - 6 RP/0/A/5700/01 ENCLOSURE 4.2 PAGE 3 0F S I , ! , Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document j 4.2.10 Fire within the plant Observation or fire detection alarm Station Directive 2.11 lasting more than 10 with confiroTng observation of a ' ! minutes. fire lasting more than 10 minutes. 4.2.11 Indications or alarms on Loss of process or affluent radiation OP/0/A/6700/03, Tech Specs 3/4.3 process or effluent para- monitoring system or Loss of all j meters not functional in meteorological instrumentation onsite j:
. Control Room to an extent or Loss of all radio / telephone communi- !
t requiring plant shutdown cations capability offsite. . or other significant loss a . of assessment or communica-
- i tion capability (e.g., all meteorological instrumenta- .
i tion,*or radio networks). ' i
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, t.
) 4.2.12 Security threat or As notified by Security Force. Station Security Plan i ! attempted entry or attempted sabotage. t 4.2.13 Natural phenomenon being exper.ienced or projected j beyon,4 usual levels. 1 j a. Any earthquake felt (<.08gH, <.053gV), Annunciator Alarm, t in plant or detected (AD-13) 4 on station seismic in-i strumentation. j b. 50 year flood or low As observed ,
! water, hurricane surge, '
{ seiche (lake tidal wave) i c. Any tornado on site As observed l d. Any hurricane Winds >73 mph /from National Weather RP/0/A/5700/06, RP/0/A/5700/07 , Service information,. I
P RP/0/A/5700/01 . ENCLOSURE 4.2 PAGE 4 0F 5
't Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document ,
i i 4.2.14 Other hazards being ex- . l perienced or projected. 6
- a. Aircraft crash onsite As observed 1 or unusual aircraft activity over facility.
, , b. Train derailment on As observed i site.
- c. Near site or onsite As observed -
l explosion. I d. Near site or onsite As observed . RP/0/A/5700/08
- , toxic or flammable
- gas release. ~
- e. Turbine rotating com- Turbine trip ahd 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). i ! 4.2.15 Other plant conditions As determined by the Shift Supervisor / As directed by plant conditions. I exist that in the judge- Erergency Coordinator. l ment of the Shift Supervisor, j' i the Operations Duty Engineer. l the Superintendent of Opera-
- tions, or the Station Manager
- warrant increased awareness
- on the part of State and/or
, local offsite authorities or l require plant shutdown under Tech Specs requirements and
, involve other than normal con-I trolled shutdown (e.g., cool-down rate exceeding Tech Specs limits, pipe cracking found j during operation). -
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RP/0/A/5700/01 ! ENCLOSURE 4.2 'l' PAGE 5 0F 5 i (
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; Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document i
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! 4.2.16 Transportation of contaal- As observed. RP/0/A/5700/05 3 i nated injured individual i from site to offsite hospital.
f ; 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. . 1 i 1-4
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RP/0/A/5700/01 i ENCLOSURE 4.4 l PAGE 1 0F 2 TELEPHONE LISTING 4.4.1 Operations Outy Engineer (PA .tes) l P&T Page - { 4.4.2 Station Hanager Home System Speed l l Home Systes Speed i 4.4.3 Superintendent of tions Home - System Speed
- 4.4.4 Superintendent of Technical Services Home @ - System Spee 4.4.5 Projects & Lice ineer, ,
Home - , System paed 4.4.6 Nuclear Production Outy Engineer stem Spee i 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: Emergency Radio, Code: G. 4.4.9 Lincoln County Warning Point - Primary: ne
. Back-up: System Spa
. Back-up: Emergency adio, Code:
4.4.10 Catawba County Warning Point'- Primary: Rin own Phone Back-up: ' System Spee Back-up: Emergency Radio, Code: 4.4.11 Iredell County Warning Point - Primary: Ocun Phone Back-up: ' System Spee Back-up: Emergency Radio, Code: 4.4.12 Gaston County Warning Point - Primary: Rin Ocwn Phone Back-up System Speed Back-up: ergency Radio, Code:~ 4.4.13 Cabarrus County Warning Point - Primary: Rin Down Phone Back-up: ' System Spa Back-up: Emergency Radio, Code: NOTE
- 1. Radio Cod 1 activate all county radio units. .
- 2. P&T Pager, Cent Charlotte Area)
Dial 46@ em e S SM G- - se=e og e e =e' e ***6**wo 9 +e * * * ' em
1
. o RP/0/A/5700/01 ENCLOSURE 4.4 l PAGE 2 0F 2
'r ., 4.4.14 N.R.C. Operation Center, Emergency Notification System (ENS phone) 4.4.15 N.R.C. Station Re ntative (Bill Orders) Office Home . System Spe P&T Pager nsite Pager - For P&T Page rce Central (MNS A 4.4.16 Construction Project Construction l Home g as Speed 550 Mt. Ho System Sp I 4.4.17 Station Health P icist Home - System Speed P&T Pag ,
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4.4.18 Station Safety Su Home yrten Speed 4.4.19 Superintendent of intenance Home System Spee l 4.4.20 Superintendent of inistration Home Systes Speed I 4.4.21 Radiati fon Section Department of Human Resources
, System Speed Q l
l l
WARNING MESSAGE- NUCLEAR FACIUTY' TG STATELOCAC.GOVERNM s $[- Instructions: RP/0/A/5700/01 ENCLOSURE 4.5 A. For Sender: pggg op i 4
- 1. Complete Part I for the Initial Warning Message.
- 2. Complete Parts I & il for followup messages.
B. For Receiver:
- 1. Record the date, time and your name in the area belcw.
- 2. Authenticate this message by verifying the code word or by calling back to the facility. (See Part I .5)
Time: ' Date: Message Received By:
, .-- g g#, . . . , ;.....- ., . ,f.
- 1. This is: McGui e Nucien- seacien Onsert name of facility)
~
- 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. Messays authentication:
(Venfy code word or call back to the facility)
- 6. The class of the 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 (date).
- 8. The initiating event causing the emergency classification is: L" NIT AF?IC t l . o .
- 9. The emergency condition: (a) Does not involve the release of radioactive materials frcm the plant.
(b) Involves the potential for a release. but no release .7s cccurring. (c) Involves a release of radioactive material.
- RP/0/A/5700/01 ENCLOSURE 4.5 PAGE 2 0F 4
- 10. We recommend the following i,, oat:w action:
(a) No protectivs action is recommended at this time. (b) People living in zones remain Indoors with the decrs and windows closed. (c) People in zones evacuate their homes and businesses. (d) Pregnant women and children in zones remain indoors with the doors and windows closed. (e) Pregnant women and children in zones evacuate to the nearest shelter / reception center. (f) Other recommendations: *
- 11. There will be:
(a) A followup message (b) No further communications
- 12. I repeat, this message: _
PART I APPROVED FOR RELEASE (a)- Reports an actual emergency (b) is an exercise memge , Signature (Emergency Coordinacor)
- 13. REUSY THIS INFORMATION TO THE PERSONS INDICATED ON YOUR ALERT PROCEDURE FOR -
AN INCIDENT AT A NUCLEAR FACII.lTY. NOTE: Record che name, cic hat N anna g n notified on Page 4 of 4_.
- 1. The type of actual or projected reisess is:
l (a) Airborne , l l (b) Waterbome (c) Surface spill l t (d) Other
- 2. The source and description of the release is:
- 1 "o
- 3. (a) Release began /will begin at a.m./p.m.: time since reactor trip is hours.
(b) The estimated duration of the release is hours.
- - - - - - - - , _ - , . -- - - , .-----,,,.--.-,w-w3w - - - - w,m_.,, mm-_--ew.y- .w.- -
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RP/0/A/5700/01 ENCLOSURE 4.5
- 4. Does projection base date:
Radiological release: curies, or curies /sec. Windspeed: mph Wind direction: From St&ility 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 projections:
' Dose Commitment
- Wiole Body (Child Thyroid)
Oh Rem / hour Rem / hour of inhalation
'. Site boundary .
2 miles 5 miles 10 miles t hi e Integreesd Dose in Rern*
~
Distance Whole Body Child Thyroid Site Boundary 2 miles 5 miles 10 miles
- 6. Field measurement of dose rate or contamination (if available):
- 7. Emergency actions underway at the facility include:
- 8. Onsite support needed from offsite organizations:
. r ..
- 9. Plant status:
(a) Reactor is: not tripped / tripped . (b) Plant is at: % power / hot shutdown / cold shutdown / cooling down (c) Prognosis is: stable /irnproving/dtgrading/ unknown. l -.. -- - _ _ _ _ _ _ _ - . _ . _ _ . . . _ _ _ _ - _ _
~ . . RP/0/A/5700/01 F 4
- 10. I ropest, this message:
(a) Reports an actual emergency. (b) is an exercise message. PART I and II APPROVED 10R RELEASE
- 11. Do you have any questions? S18 nature (Emergency Coordinator) f .
---END OF FOLLOW-UP MESSAGE ****
C: NOTE: Record the name, title, date, time, and waming point notified. (Senders) Record the name title, date, time, and persons notified per alert procedure. (Receivers) 1. (name) (title) (data) (time) (warning point) 2. (name) (titte)
~
(date) (time) (warning point) 3. (name) _ (title) (date) - (time) (warning point)
/
( 4. (name) , (title) . (date) (time) (warning point) 5. (name) (titte) (date) (time) (warning point) 6. (name) . (titte) (date) (time) (warning point) 7. (name) (titte) (date) (time) (warning point) 8. (name) (title) (date) (time) Form 34888 (6-82) ("* IE * -- .w. - - . - - ., ,.~,, - . ,,,----,-,,,,,- w.-m ,,g-.m, .,.,, , , , , ,,.,.,-,..,,,.7-. , .,w,yy-,, , .,y,w -,_-i,.-, - - .-.. ,
RP/0/A/5700/01 ENCLOSURE 4.6 PAGE 1 0F 1 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 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 Leisis Management Center.
- 7. NRC Yes No, State _ Yes _ No, Counties Yes No, have been notified.
- 8. The C' isis 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 Comments:
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Form 34731 (10-81) (Formerly SPD 10021) 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 Statiott . (3) PROCEDURE TITLE:, Alert a f. A. (4) PREPARED BY: . . DATE: 8/31/83 (5) REVIEWED BY g M DATE: -[-M Cross-Disciplinary Review By: N/R (6) TIMPORARY APPROVAL (IF NECESSARY): By: (SRO) Date: 1 By: Date: i (7)* APPROVED BY: hh " Q Date: f/4//3 (8) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date:
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RP/0/A/5700/02 PAGE 1 0F 5 DUKE POWER COMPANY NcCUIRE NUCLEAR STATION AIIRT 1.0 S m toms 1.1 Events are in process or have occurred which involve an actual or
. potential substantial degradation of the level of safety of the plant.
2.0 Iammediate 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 Actions Initial /N/A
/ 3.1 The Shift Supervisor / Emergency Coordinator shall assure that the appropriate emergen,cy condition (Notification of Unusual Event, Alert, Site Area Emergency, or General Emergency) is declared by evaluating the actual plant condition wita Enclosure 4.1, Emergency Classification Guide Flowchart and Enclosure 4.2, List of Initiating Conditions, Emergency Action Levels, and Associated Emergency Procedure / Document.
t I i NOTE 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.
/ 3.2 The Emergency Coordinator shall assure that all actions l
I l ( I .,. , . . - - . - . . - .
RP/0/A/5700/02 PAGE 2_ 0F 5 required by the initiating Emergency Procedure (s) 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 assembly / accountability and/or evacustica of all non-essential onsite personnel appears necessary, refer to Station Directive - 3.8.1.
/ 3.3 The Emergency Coordinatdr 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 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 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 Message: Nuclear Facility to State / Local Government, for information l to be provided to State / County Warning Points. 3.4 The Emergency Coordinator in direct contact with the Technical 1 1 f i l l I . . - -
... _. _ _ _. _ - ~ __ _ _ _. _ __ _ _ _ _ _ _ ._ _ _ _ _ . _ _ .._ _ __ _
, RP/0/A/5700/02 PAGE 3_ 0F 5 Support Center and the Crisis Management Center will assess and respond to the emergency by:
3.4.1 Dispatching onsite monitoring t,eams with associated communications equipment. 3.'4.2 Providing periodic plant status updates to offsite ; authorities (at least every 15 minutes). 3.4.3 Providing periodic meteorological assessments to offsite . I- authorities and, if any releases are occuring, dose estimates for actual releases. q i i NOTE In the event a release or potential release of radioactive asterials is a threat to plant , personnel or members of the general public, the Emergency Coordinator shall utilized the Operator Aid Computer (OAC) " NUCLEAR-23" program to ass'ss a 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.
/ 3.5 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 Operating Centers, if established) or the State Radiological Protection Section, D,epartment of Htpsan Resources (see Enclosure 4.7, Protective Action Recommendation Flow Chart) as directed by the state, in accordance with the North Carolina Emergency .
Response Plan. If evaluation indicates that a potential for or
,.,,,.c, _.-m-,.,_,r-
e w w RP/0/A/5700/02 PAGE 4_ 0F 5 an actual release of radioactive materials will result in a projected dose (REM) to the population of: (EPA Protective . Action Guidelines). 3.5.1 Whole body <1, thyroid <5, NO protactive action is required. Monitor environmental radiation levels to verify. 3.5.2 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. Monitot environmental radiation levels. Control access to affected areas. . NOTE If this is the projected dose evaluate Site Area Emergency and General Emergency Initiating Conditions and Emergency Action
' Levels.
3.5.3 Whoir 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 If this is the projected dose, see General Emergency Procedure NOTE See Enclosure 4.4, Telephone Listing for notification.
/ 3.6 The Emergency Coordinator in coordination with the Recovery Manager at the Crisis' Management Cen'teh, will assess the emergency condition and determine the need to remain in an Alert l
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RP/0/A/5700/02 PAGE 5,OF 5 Status, escalate to a more severe class, reduce the emergency class or close out the emergency.
/ 3.7 The Station Manager or his designee will close out the
( Emergency with a verbal summary to those personnel and county and state authorities notified in Step 3.3, followed by a written summary within 8 hours. 4.0 Enclosures 4.1 Emergency Classification Guide Flowchart 4.2 List of Initiating Conditions, Emergency Action Levels, and~ 'ssociated 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 Message Format 4.7 Protective Action Recommendation Flow Chart
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RP/0/A/5700/02 '
. ENCLOSURE 4.2 ,
i PAGE 1 0F 5
' LIST OF INITIATING CONDITIONS, EFERGENCY ACTION LEVELS, AND ASSOCIATED EMERGENCY PROCEDURE /00CUMENT I . , Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document 4.2.1 Severe loss of fuel a. Very high reactor coolant activity Tech Specs 3/4.6.7 ; cladding, Mechanical indicated by sample activity gy, Clad failure failed fuel monitor (EMF-48) j indicatina an increase greater than 1% fuel failure within 30 minutes (increase of 70pci/mi in 30 minutes) or 5% to 253 total fuel failure indicated by 350 to 1,750pC1/m1 total I-131 coolant activity.
4.2.2 Rapid gross failure Pressurizer low pressure alarm and EP/1/A/5000/04, EP/2/A/5000/04, of on'e Steam Generator reactortripag,pressurizerlow AP/1/A/5500/07, AP/2/A/5500/07 tube with loss of off- level alarm and, n pressurizer low - site power. pressure safety injection signal
. and, undervoltage alarm on 7KV buses. EMF 32, 33, and 34 Alarm (s). .
4.2.3 Rapid failure of Steam Several hundred gpa primary to EP/1/A/5000/04, EP/2/A/5000/04 Generator tube (s). secondary leak rate indicated by:
- a. as above in 4.2.2 for pres-surizer and EMF indicators.
Steam generator level in-b. creasing in one or more generator (s) and falling in the others/due to reactor trip.
RP/0/A/5700/02 ENCLOSURE 4.2 *
'PAGE 2 0F 5 l
l Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document l l i
- 4.2.4 Steam line break with Greater than 10gpa, 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. pressuelzer pressure and level and, . 4
- 1. Steam line differential -
i pressure safety injection
- signal and increased con-tainment building pressure /
if break is in containment.
. 2. liigh steam flow and to Lo Tave or Low steam pressure safety injection signal for rupture downstream of HSIV's. l ! e ; 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 gpe. lation or other indication. (i.e., AP/1/A/5500/10; AP/2/A/5500/10 sump levels) .
4.2.6 liigh radiation levels Increase by a factor of 1,000 in HP/0/8/1009/05
, or high airborne con- radiation monitor reading within tamination which in- the station.
dic'ates a severe de-gradation in the control , of radioactive materials. ,
? 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 1 power for up to 15 minutes. actuated. -
l (See Site Area Emergency { RP/0/A/5700/03, for ex-tended loss). , , ,s v. 1 4.2.8 Loss of all onsite DC DC bus undervoltage alarms on ail Tech S'pecs 3/4.8.2.3; power. buses. Tech Specs 3/4.8.2.4 ] x i *
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. - s
- 7.q RP/0/A/5700/02 ENCLOSURE 4.2 .) ~~
PAGE 3 OF 5 .s :
'. Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document .
! _ s
. 4.2.9 Calant puc:p seizure Reactor coolant pump auto trip AP/1/A/5500/04, AP/2/A/5500/04, ,
i leading to fuel failure. alarm, and reactor trip on low AP/1/A/5500/08, AP/2/A/5500/08,
; coolant fTow, and failed fuel '
DP/0/A/6150/14,AP/1/A/5500/05 monitor alarm EiiF48. AP/2/A/55CS/05 i u c-4.2.10 Complete loss or func- '
- RHR,not functional and inability AP/1/A/5500/17, AP/2/A/5500/17, tions needed for plant 3 . _ to sustain natural or forced cir- OP/1/A/6100/04, OP/2/A/6100/04 cold si.utdown. culation. .
l 4.2.11 Failure of the reactor ' Reactor remal'ns critical after e AP/0/A/5500/34 [ protection syste= ta all attempts to trip reactor. initiate and complete have been completed. - < a scram which brings ,' the reactor subcritical. 3\. 4.2.12 Fuel damage accident Observation of' damage to spent . AP/1/A/5500/25, AF/2/A/5500/25
~
N with release of radio- fuel assembly, and activity to containment - ' z1 ' ' s or fuel handling building." 1. ~ 1 EMF-16 or 17 alars er N * - 2 EMF-3 or 4 alare. ' N ', ,
- 2. EMF-38, 39, 40, or 42,. x
- alarm. ,
" N 2
- 4. 2. I's Fire, potentially affecting Observattan of a fire that'could .' x Station Directive 2.11 Series, <^ .
safety systems. - affect safety systeme. s . Tech Specs , 3/4.5' , s 4.2.14 Most or all-alarms (annur.- As observed. - OP/0/A/6350/01A ~ .' ' clators) lost. _ . S
RP/0/A/5700/02 4 ENCLOSURE 4.2 ' PAGE 4 0F 5 Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document , 4.2.15 Airborne Radiological For EMF 35 - Low Range offscale HP/0/B/1009/05
; effluents >10 times Tech Specs instantaneous High Range 1 x 10 4cpm
, limits (an instantaneous 6 rate which, if continued for EMF 36 - Low Range 2 x 10 cp , over 2 hours, would re-
, sult in about lar at the High Range 5 x 102cp ,
site boundary under average meteorological conditions or whenever effluent moni- . tors or radiological mont-toring detect these levels). l 4.2.16 Ongoing security compromise. As reported by Security force. Station Security Plan ! 4.2.17 Severe natural phenomena e RP/0/A/5700/06, RP/0/A/5700/07 being experienced or ' ' ) i projected: I Earthquake greater >0.08gH, >.053gV, Annunciator Alarm,
- a.
- than Operational (AD-13).
. Basis Earthquake Levels ' l b. F,lood, low water, hur- As observed. 1 ricane surge, seiche near design levels. (Lake tidal wave) l c. Any tornado striking As observed. facility.
- d. Hurricane winds near As observed (95 mph)/from National j design basis level. Weather Service information.
4 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. l 1 i . j i
RP/0/A/5700/02 ENCLOSURE 4.2 PAGE 5 0F 5 ! . Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document ! b. Misslie impacts from whatever source on As observed. .' l ' i facility. . . l
- c. Know explosion damage As observed.
to facility affecting i plant operation.
- d. Entry into facility As observed. .
environs of toxic or flammable gases.
]
- 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. c i ment of the Shift Super-i visor, the Operations j Duty Engineer, the . i Superintendent of Opera-I tions, or the Plant l Mana'ger warrant pre-i cautionary activation of the Technical Support i Center and near site i Crisis Management Center. j j 4.2.20 Evacuation of control As determined by Shift Supervisor / AP/1/A/5500/17, AP/2/A/5500/17,
- room anticipated or Emergency coordinator. OP/1/A/6100/04, OP/2/A/6100/04 required with control y
of shutdown systems j established from local
- station. -
l I i b *
*2. . _ . - - ..
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 Encineer Station Manaaer Superintendent of Operations Superintendent of Technical Services Projects and Licensing Encineer Station Health Physicist - i North Carolina State Warning Point Mecklenburg County Warnino Point Lincoln County Warning Point Catawba County Warnino Point Iredell County Warning Point
'Gaston County Warning Point Cabarrus County Warning Point N.R.C. via ENS (Red Phone) (Station Directive 2.8.1 and 3.1.A)
N.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) - l
- i '*.
I
l RP/0/A/5700/02 l ENCLOSURE 4.4 PAGE 1 0F 2 i i TELEPHONE LISTING l l 4.4.1 Operations Duty Engineer A System) P&T Pager 4.4.2 Station Manager Home - System Speed l Home - System Speed 4.4.3 Superintendent rations, Home System Speed 1 4.4.4 Superintendent of Technical Services - Home w System Spee 4.4.5 Projects and Lic ineer Home stem Speed 4.4.6 Station Health -
- Home System Speed P&T Pager 4.4.7 NC State Warning Point, Raleigh System Speed
! 4.4.8 Mecklenburg County Warning Point - Primary: Rin Down Phone i Back-up: System Speed Back-up: Emergency Radio, Code: i 4.4.9 Lincoln County Warning Point - Primary: ' Ocwn Phone Back-up: ' System Spee l Back-up: Emergency Radio, Code: 4.4.10 Catawba County Warning Point - Primary: Ocwn Phone Back-up: - System Spe Back-up: Emergency Radio, Code: 4.4.11 Iredell County Warning Point - Primary: n Phone Back-up: System Spee Back-up: ergency Radio, Code: 4.4.12 Gaston County Warning Point - Primary: Ocwn Phone Back-up: System Spee Back-up: Emergency Radio, Code: 4.4.13 Cabarrus County Warning Point - Primary: wn Phone Back-up: ' System Spee Back-up: Emergency Radio, Code: activate'
~
- 1. Radio Cod all county radio units.
- 2. P&T Pager, Cent al Division (Charlotte Area)
Dial -
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RP/0/A/5700/02 ENCLOSUPE 4.4 PAGE 2 0F 2 TELEPHONE LIST 4.4.14 N.R.C. Operation Center, Emergency Notification System (ENS Phone) 4.4.15 N.R.C. Station Representati Orders) Office Home System Spe P&T Pager nsite Pager For P&T Page rom Central (MNS A 4.4.16 Construction Project Manage struction Ext. Home : tem Speed - SSD, Mt. Ho System Spe 4.4.17 Superintendent of Maintana Home - System Speed 4.4.18 Superintendent of Administratio Home System Speed 4.4.19 Nuclear Production Duty Engineer System Spee P&T Page 4.4.20 Radiation Protection Secti nt of Human Resources- - ystem Speed g , e l i
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WARNING MESSAGEtlyUGLEAR FACEIDETO S1ATELOCAC e :- Instructions: 6:
*[
RP/0/A/5700/02 A. For Sender: ENCLOSURE 4.5 PAGE 1 0F 4
- 1. Complete Part i for the 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 i .5)
Time: Date: l l Message Received By: Q- J a.Qf[:.J cl. : '; % 'y:f i.i=,-Q , M&f**Q&KQ,&&* gQ_'
^
l
- 1. This is: we,,4-. v,,e ... e , <,-
(insert nirne of faclity
- 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 worc Or call back to ":e faclity)
- 6. The class of the 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 (date).
- 8. The initiating event causing the emergency classification is: "NI-' AFFEC "ID -
- 9. The emergency condition: (a) Does not invcive the release of radicactive materials from the plant (b) Involves the potential for a release, but no release is occurr;r:.
(c) Involves a re! ease of radicactive material.
M / V/ st/ .A i VU/ V4 ENCLOSURE 4.5 PAGE 2 0F 4
- 10. We recommend the following protective action:
(a) No protective action is recommended at this time. (b) Pecple living in zones remain indoors with the doc.3 and windows closed. (c) People in zones evacuate their homes and businesses. (d) Pregnant women and children in zones remain indoors with da doors and windows closed. (e) Pregnant women and children in zones evacuate to the nearest shelter / reception center. (f) Other recommendations:
- 11. There will be:
(a) A followup message (b) .No further communications
- 12. I ropest, this message: PART I APPROVED FOR RELEASE (a) Reports an actual emergency Signature (Emergency Coordinator)
(b) is an exercise message
- 13. RELAY THIS INFORMATION TO THE PERSONS INDICATED ON YOUR ALERT PROCEDURE FOR AN INCIDENT AT A NUCLEAR FACILITY. -
'"END OF INITIAL WARNING MESSAGE" NOTE: Record the name, title, date, time and Warning Point notified on Page 4 of L.
e.. - - - -
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. .. . , _ ~
PAEHt> - -- . _ -:- t f f4:'*??- - $
- 1. The type of actual or projected release is:
(a) Airbome l (b) Waterbome l (c) Surface spill (d) Other
- 2. The source and description of the release is:
- 3. (a) Release began /will begin at a.mJp.m.; time since reactor trip is hours.
(b) The estimated duration of the release is hours. l l 1
~
~
RP/0/A/5700/02 :
- 4. Does projection base data:
Radiological release: curies, or curieshoc. Windspeed: mph 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/C1/m3 (Child Thyroid) Precipitation:
~
Temperature at the site: 'F
- 5. Does projecuons:
- Dose Commitment
- _
M ole Body (Child Thyroid) Distance Rem / hour Rem / hour of inhalation Site boundary '- 2 miles 5 miles 10 miles
- Projected Integrated Dose In Rem *
~
Distance Whole Body Child Thyroid Site Boundary 2 miles 5 miles 10 miles
- 6. Field measurement of dose rate or contamination (if available):
- 7. Emergency accons underway at the facility include:
- 8. Onsite 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 / improving / degrading / unknown.
1
. . ~ , ,..,.,..., ,
ENCLOSURE 4.5 i PAGE 4 0F 4
- 10. I ropest, this message: ,
l (a) Reports an actual emergency. l PART I and II APPROVED FOR RELEASE (b) is an exerc.ise message . 1
- 11. Do you have any questions? Signature (Emergency Coordinator)
'_ . - 5.='f < MM--?#FMENGOEEUELOMT-UIEMESSAGET4WE%ARE ,
NOTE: Record the name, titie, date, time, and warning point notified. (Senders) Record the name title, date, time, and persons notified per alert procedure. (Receivers) 1. (name) (title) (date) (time) (warning point) 2. (name) (title) (date) (time) (warning point)
- 3. *
(name) (titles (date) (time). (warning point) 4. (name) (title) (date) (time) (warning point) 5. (name) (title) (date) (time) (warning point) 6. (name) (title) (date) (time) (warning point) 7. (name) .(tit!e)
'(cate)- (time) (warning point) 8.
(name) (title) (date) (time) Form 34888 (6-82) (va M ng point)
RP/0/A/5700/02 ENCLOSURE 4.6 PAGE 1 0F 1 EME.'lGENCY PLAN MESSAGE FORMAT (Nuclear Station to Nuclear Production Duty Engineer) 1
- 1. This is at McGuire Nuclear Station. l (Name and Title) l l
. 2. This is/is not a Drill. An Unusual Event Alert i 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 No, 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.
l (Telephone Numoer) I i
- 10. Additional Comments:
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4 4 Form 34731 (10-81) {Formerly SPD 10021) DUKE POWER COMPANY (1) ID No: RP/0/A/5700/03 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD o Incorporated (2) STATION: v,c ,4, v..,t.. ,..,4mn (3) PROCEDURE TITLE: < < , . . Av.. h.co. ,, i - A > (4) PREPARED BY: 'm%}%-- M_ s _ c:t avec _ DATE: 8/31/83 (5) REVIEWED DATE: k- N 3 Cross-Disciplinary Review By: N/R s (6) TEMPORARY APPROVAL (IF NECESSART): By: (SRO) Date: By: v Date: f/4/f.) (7) APPROVED BY: _ Dato: (8) MISCELLANEOUS: - Reviewed / Approved By: Date: Re31ewed/ Approved By: Date: I
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. RP/0/A/5700/03 PAGE 1 0F 5 DUEE POWER COMPANY McGUIRE NUCLEAR STATION SITE AREA EMERGENCY 1.0 Sysotoss 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 Ismediate 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 Actions Initial /N/A
/ 3.1 The Shift' Superviso'r/ Emergency Coordinator 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 Guide Flowchart and Enclosure 4.2, List of Initiating Conditions, Emergency Action Levels, and j Associated Emergency Procedure / Document.
NOTE 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.
- f *.
/ 3.2 The Emergency Coordinator shall assure that all actions i
l l
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l RP/0/A/5700/03 PAGE 2 OE 5 3 i required by the initiating Emergency Procedure (s) will be perfor=ed and that all actions necessary for the protection of persons and property are being taken. NOTE The Emergency Coordinator shall consider the need for site assembly / accountability and/or evacuation of all non-essential onsite personnel. See Station
.2 Directive 3.8.1.
/ 3.3 The Emergency Coordinator shall recommend to offsite authorities that the following actions take place:
3.3.1 Activate the Alert & Notification System (Sirens and the Emergency Broadcast System) to make area residents aware of the situation. 3.3.2 Request the general public in a 2 mile radius area around McGuire (Zon s' A, B, C, D and Q,) to go indoors and monitor : Emergency Broadcaist Stations for continued updates on the situation.
/ 3.4 The Emergency Coordinator shall assure prompt (within about 15 minutes of declaring the emergency) not fication 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 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 Management. Center (CMC) shall be in accordance with Enclosure 4.6 O O GW9 v .- yw+,n -m e -,,.e m. -.iww ,--y -p-, ,_--,,,.,.#,_. .-,.-m-, -.---,._-,,,,,__,..-.---,y._. , , _ _ , , , + ,.,,..-.g..-m-,-, - , .,,y---my--..-,,, , - _ - - ,, g.,-,,,., .
RP/0/A/5700/03 PAGE 3_ 0F 5 NOTE 2 See Enclosure 4.i, Telephone Listing, for notification, telephone numbers / radio codes /pager codes. NOTE 3 See Enclosure 4.5, Warning Message: 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 the Onsite and Offsite monitoring teams'with associated communications equipment. 3.5.2 Providing me'tieorological and dose estimates to offsite authorities for actual releases via a dedicated individual or automated data transmission. 3.5.3 Providing release and dose projections based on available plant condition information and foreseeable contingencies to offsite authorities. r 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 utilized the Operator Aid Computer (OAC) " NUCLEAR-23" program to assess the offstte. consequences. In the event the (OAC) is not operational the Emergency Coordinator shall request Health Physics personnel to evaluate the
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RP/0/A/5700/03 PAGE 4 0F 5 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 -
Operating Centers, if established) or the State Radiological Protection Section, Department of Hn==n Resources (see Enclosure , 4.7, Protective Action Recommendation Flow Chart) as directed by the state, in accordance with the North Carolina 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 Whole body <1, thyroid <5, NO protective action is
. required. Manitor 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. Monitor environmental radiation levels. Control access to affected areas. l 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 l area for mandatory evacuation based on these levels. Control access to affected areas. NOTE See Enclosure 4.4, Telephone Listing for notification. .
- - - 1 RP/0/A/5700/03 PAGE 5 OF 5
/ 3.7 The Emergency Coordinator in coordination with the Recovery Manager, at the Crisis Management Center, will:
3.7.1 Provide a dedicated individual for plant status updates to offsite authorities and periodic press briefings. 3.7.2 Make availab.1.e senior technical and management staff onsite for consultation with the NRC and, State on a , periodic basis. 3.7.3 Assess the emergency condition and determine the need to remain in a Site Area Emergency, escalate to a more severe class, reduce the emergency class, or close out the emergency.
/ 3.8 The Recovery Manager at the Crisis Management Center will close .
out or recommend reduction of the emergency class, by briefing , of those personnel and offsite authorities notified in Step 3.4
. at the Crisis Managhaent Center or by phone if necessary, , ;
followed by written summary within 8 hours. 4.0 Encicsures 4.1 Emergency Classification Guide Flowchart 4.2 List of Initiating Conditions, Emergency Action Levels, and Associated l Emergency Procedure / Document. l l 4.3 , Notification Chart 4.4 Telephone Listing 4.5 Warning Message: Nuclear Facility to State / Local Government 4.6 Emergency Plan Message Format 4.7 Protective Action Recommendation Flow Chart l l l l l l
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t 6 i . , RP/0/A/5700/03 . ENCLOSURE 4.I PACE 1 0F 1 EME AGENCY CLASSIFICATION GUIDE F LowCHART a -- twa =, c a us esoav unusuae sysas e.wij seus amaa sessnesesce pamanat assangag2 u ammu=== raensaavsaan maee a.ca s ome,e nue mamie enmaave enmaav contamv asas sava smeau toes ee centaess accament aunt en t aase enaas coca occune aeso consamunas i seco=oa n taas secomecu s.namism summ eneene se ocal omeassa suam asassaar erscw ecainm om enaeaav evaises "^*""one e anuna oe a sieam ce ,s v cae,a,o e, re,n,e,a- - ^ 8s .. ,,~,,,a.ssa u.t
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**"a*c*o*m'e*a*o'n"*a*me"io"e as ceact esawaen enassaan oness osamana reen un ese& me sawean osaans esmo nason sues eeoume nesuout consassensamt mouessaan 3e assessauas Coat Coasesseuses eueL onesamt eseoeCatsoas savgag &ces of euit CtaedMeso Otomane comS We Necesette tom &oss se 3 of 3 eenSeces eeseG4aCI
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e om ama ese asuaso en vue savasone sea reoveceeve acaeces etnoetessee mas enoescien vo ec escasseo 1 outseos vue saa oneasionaw 1, es toss ce soeuscowa suaeviones eastume os meacreaenove vaaaseems sectamedeo oesearsom oe anaasesar asnusause seemassem oe escav neat on n Csewnv svaisu io nnea ss ane co crease ertase sauvootme ersvensa mmun e natuas te enut oomm svsva nas on tw e an uma a sceau me=Ca enmoe sus asacrea scaans ecowsmuen come n vascaans aseenisoaak ennums oe ; succenaveCat atseen*Weoes a* Tee eso come omasaos Come Coot esso aseo esastur Gustate ;
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- sees raae os es aws ectaase=o aCuevasumue sus asC anavon seaa mua ncy Cau se ne ano me sass oe a mme.a aseounis ce e
, asaee on asaus answon toCu sue Canses uanas.sess as Ca Nis a umu S me sua*u se Lauf tosease,aus on usuancs os a stasacaC rown s en a suone senaa , sag e ss e s aulieuseele& & uh ag eenagent ecclef eCaleGSG ft atuG Pubsteh t . e8 o asey C&sett es&& 1 . Pt aset somaleauvres estatat a I E CeeheC AL Id Igen Pues eC Nt ase Seed sel6 se sua g euNe )' 1 LP8C.ef tuwe 4 we eC usu ASWue Meetes=46ef a sneau =unuat sels aseo e s uminut o s u se.u e nown j 3 enape . Pense: A e , mmne u emu ,estee see e uneas Cusa coeu g Ad.%. st e su. . w 4 a ese esee $ soubPse At 3 e e M
RP/0/A/5700/03 ENCLOSURE 4.2 ^ PAGE 1 0F 6 LIST OF INITIATING CONDITIONS, EMERGENCY ACTION LEVELS, AND ASSOCIATED EMERGENCY PROCEDURE / DOCUMENT 4 . Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document i l 4.2.1 Known loss of coolant Pressurizer low pressure reactor trip EP/1/A/5000/02,EP/2/A/5000/02
- i accident greater than and pressurizer low pressure safety makeup pump capacity. Tn~}ectionsignalandhighcontainment ,
I : buildingpressure3NSP5040,5050, , 5060, 5070) and high containment j . building sueF Tevel (NIPS 260, 5270) : ! and high containment humidity, 4~ TN5P5400,5410) and EHF 38, 39, and 40 alarm. 4.2.2 Degraded core with pos- Inadequate Core Cooling: AP/1/A/5500/05, AP/2/A/5500/05 i sible loss of coolable 5 centrally located thermocouples indicate geometry (indicators core exit temperature greater than 1200*F. -
- should* include instru- For Mechanical Clad Failures
- mentation to detect Greater than 25% failed fuel indicated !
inadequate core cooling, by greater than 1,750pci/m1 1-131 con-coolant activity and/or centration.
- containment radioactivity For Severe Fuel Over Temperature
- i' 1 l 1evels). From 1% to 10% failed fuel indicated l by 1,300 to 13,000pci/m1 1-131 l : , concentration.
For Fuel Melt: From .5% to 5% failed fuel indicated by 1,180 to 11,800pC1/m1 1-131 concentration. ! 4.2.3 Rapid failure of steam Pressurizer low pressure alarm and EP/1/A/5000/04 EP/2/A/5000/04 l generator tubes with loss reactor trip, and pressurizer low AP/1/A/5500/07, AP/2/A/5500/07 j of offsite power (e.g., level alarm, and EHF 32, 33, and 34 i several hundred gpm pri- alarm, and undervoltage alarms on i mary to secondary leak 7KV buses, and steam generator water rate). level rapidly increasing in one or l
- more steam generators fa111pg in the j others, a_nd n pressurizer leve' rapidly j decreasing, (NCP5151, 5160 '2) i and possible lifting of s~c. .,enera-l tor PRV's and/or safety valves.
l i
1
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RP/0/A/5700/03 ENCLOSURE 4.2 ~ ' PAGE 2 0F 6 { j Initiating Conditions Emergency Action Level (EAL) 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 level. 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 (NSP5040, 5050, 5060, 5070) and . 4 EMF SIA and/or B alare, or hTali steam flow and to Lo Tavg or low steam pressure safety injection
- signal, and EMF 48 alarm.
I' 4.2.5 Loss of offsite power and- No voltage on ETA and ETB and EP/1/A/5000/09, EP/2/A/5000/09 loss of onsite AC power No voltage on ATA and ATB ~
- for morb than 15 minutes. ,
l j 4.2.6 Loss of all vital onsite DC bus undervoltage all buses W Tech Specs 3/8.2.3, 3/8.2.4
- , DC power for more than 15 indications as in 4.2.5 above.
]
. minutes i .
I 4.2.7 Complete loss of any Inability to establish charging pump OP/1/A/6100/04, OP/2/A/6100/04, ' function needed for plant injection, a,nd Inability to establish AP/1/A/5500/17, AP/2/A/5500/17 hot shu,tdown. emergency feedwater flow, or Inability to establish service water 710w, and l Inability to establish component
; cooling water flow.
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 immediately evident). i. i j . . .-
) .
RP/0/A/5700/03 ENCLOSURE 4.2 - PAGE 3 0F 6 Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document , I ! 4.2.9 Major damage to spent Observation of major damage to one AP/1/A/5500/25, AP/2/A/5500/25 j 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 and IEMF-16 & 17, 2 EMF-3 or 4 or F)tf -38, i l damages fuel or water 39, 40 or 42 alarms. - - i loss below fuel level). I -
- 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 ' j . systems. system or function. :
- , 4.2.11 Most or all alarms As determined by the Shift Supervisor / OP/0/A/6350/01A i
! (annunciators) lost and Emergency Coordinator. plant transient initiated '. , or in progress. . i j 4.2.12 Airborne radiological For EMF 35 Low Range, offscale 3 HP/0/8/1009/05, HP/0/8/1009/09
- . effluent monitors detect High Range 8 x 10 cpm. !
- l. levels corresponding to greater than 50 mr/hr (See Note 1)5 i for EMF 36 Low Range 3 x 10 cpm I for 1/2 hour or greater High Range 7 x 10 cpm than 500 mr/hr W.B. for (See Note 1) two minutes (or five times i these levels to the thy- For EMF 37 Change of 143 cpe/ minute rold) at the site boundary for 30 minutes or a
; for adverse meteorology change of 1430 cpe/ minute
{ TSeeNote2). for 2 minutes (See Note 1). NOTE 1: These values are worst case I calculations and may not reflect more j favorable weather conditions. 1 1 1 i i i j l i
RP/0/A/5700/03
~
ENCLOSURE 4.2 ^ PAGE 4 0F 6 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 l rate appropriate for existing contain- ,
- ment pressure) or are measured in the
! environs. (EPA Protective Action Guide- i' ! lines are projected to be exceeded out-side the site boundary). 4.2.13 Imminent loss of phy- Physical attack on the plant involving Station Security Plan ,
- sical control of plant. imminent occupancy of control room and
, auxiliary shutdown panels. } 4.2.14 Severd natural pheno- a RP/0/A/5700/06, RP/0/A/5700/07 I mena being experienced '
! or projected with plant
. not in cold shutdown.
l 4.2.14.1 4 q~ Earthquake greater than (>.15gH, >.lgV) as deteral'ed n by mont-SSE (Spfe Shutdown Earth- toring seismic instrumentation and 1 . quake) levels. recording devices. (SMP-1) 4.2.14.2 j Flood, low water, hurri- As determined by Shift Supervisor / cane surge, seiche greater Emergency Coordinator.
- than design levels (lake tidal waves) or failure l of protection of vital equipment at lower levels.
1 4.2.14.3
-{
j Sustained winds or torna- (>95 mph) as observed or documented . does in excess of design by the National Weather Service levels. Information. ,
4 RP/0/A/5700/03 ENCLOSURE 4.2 PAGE 5 0F 6 Initiating 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 with plant not in cold . shutdown.
> =
4.2.15.1 j Aircraft crash affecting Aircraft crash causing damage or ! vital structures by in- fire to: Containment Building, , pact or fire. Control Room, Auxiliary Building, ! Fuel Building, or Intake Structure. 4.2.15.2 Severe damage to safe Loss of functions needed for. hot i shutdown equipment from shutdown as in 4.2.7. . 1 missiles or explosion. 4.2.15.3 Entry of uncontrolled Entry of uncontrolled or toxic or flammable gases into flammable gases into: Control Room, i' vital areas. Entry of Cable Spreading Room, containment uncontrolled toxic Building, Switchgear Room, Safe t gases into vital areas Shutdown Panels or Diesel Rooms. 4 where lack of access to the area constitutes a safety problem. 1
l
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l ,
^
RP/0/A/5700/03 AG b 6 j
- Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document 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 I 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 i notification to the
! public near the site. ,
j .: t-
; 4.2.17 Evacuation of control As determined by Shift Supervisor / OP/0/A/6350/02, AP/1/A/5500/17,
! room and control of shut- Emergency Coordinator. . AP/2/A/5500/17 down systems not established i from local stations in
' 15 minutes. ,
I , i i ..
}
1 )
)
J I i
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RP/0/A/5700/03 ENCLOSURE 4.3 i PAGE 1 0F 1 NOTIFICATION / ACTIVATION l GENERAL EMERGENCY ! 1 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 Outy Engineer . Station Manaaer Superintendent of Operations Superintendent of Technical Services Projects and Licensino Engineer Station Health Physicist North Carolina State Warning Point - Mecklenburg County Warnino Point Linccin County Warning Point Catawba County Warnino Point " Iredell County Warning Point - Gaston County Warnino Point Cabarrus County Warning Point South Carolina State Warnino Point N.R.C. via ENS (Red Phone) (Station Directive 2.8.1 and 3.1.4) N.R.C. Station Representative Superintendent of Maintenance Superintendent of Administration l l Construction' Project Manager ! Activate T.S.C. (Station Directive 3.8.2) Activate 0.S.C. (Station Directive 3.8.2) l Activate C.M.C. (Enclosure 4.6)
. <4 1
l l l RP/0/A/5700/03 l TELEPHONE LISTING 4.4.1 Operations Duty Engineer (PA System) P&T Pager
- 4. 4. 2 Station Manager l Home - System toeed -
Home - - System Speed - l 4.4.3 Superintendent of erations Home ' System Speed 4.4.4 Superintendent ' hnical Services - Home - System Spee 4.4.5 Projects and ineer . i Home ' System peed 4.4.6 Station Heal Home
-k' System Speed -
P&T Pag -- 4.4.7 NC State Warning Point, Raleigh - System Speed 4.4.8 Mecklenburg County Warning Point - Primary: Rin Phone Back-up: System Speed Back-up: Emergency Radio, Code: 4.4.9 Lincoln County Warning Point - Primary: Ri own Phone Back-up: ~ System Spee
- Back-up: Emergency Radio, Code:
4.4.10 Catawba County Warning Point - Primary: own Phone Back-up: ~$ystem Spee Back-up: Emergen adio, 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 Ocwn Phone Back-up: System Spee Back-up: Emerg adio, Code: 4.4.13 Cabarrus County Warning Point - Primary: Phone Back-up: System Spe Back-up: erg adio, Code: 1 NOTE
- 1. Radio Co 1 activate '-
all county dio units. '
- 2. P&T Pager, r arlotte Area) 1 1
RP/0/A/5700/03 ENCLOSURE 4.4 PAGE 2 0F 2 TELEPHONE LIST 4.4.14 SC State Warning Point - 4.4.15 N.R.C. Operation Center, Emergency Notification System (ENS Phone) 4.4.16 N.R.C. Station Representative 11 Orders) Office Home ' System Spee P&T Pager site Pager For P&T Page from Central (MNS Area 4.4.17 Construction Project Manager constructio O Ext . b ystem Spee
- 4. 4. ' 8 Superintendent of Maintenanc Home ystem Speed .
4.4.19 Superintendent of Administr Home stem Speed 4.4.20 Nuclear Production Outy Engineer - System Speed P&T Page -- - 4.4.21 Radiation Protection Section, Department of Human R urces-l System Speed - - l i e t . \ 1 l G
---,___-- __,_ .,.- - -__,w-mem -- --
-w_ v w o- e , _ www--
W# WARNINGIIIESSAGE:NUCLEARFACILITYTUS1 ATE 60CAC.GOVERNM= M" instructions: RP/0/A/5700/03 A. For Sender: GCLOSURE 4.5 PAGE 1 0F 4
- 1. Complete Part I fer the initial Warning Message.
- 2. Complete Parts 1 & ll for followup messages.
B. For Receiver:
- 1. Record the date, time and your name in the area below.
- 2. Authenticate this message by verifying the code word or by calling back to the facility. (See Part ! .5)
Time: Date: v. Message Received By:
$. $ .N&W&WY+ O% M N2 J ?Y
- 1. This is: McGuire Nuclear Stacion Onsert name of *actity)
- 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 were er cui cacx to me fac:lity)
- 6. The class of the emergency is: (a) Notificaticn of Unusual Event (b) Alert (c) Site Emergency (d) Ge.,eral Emergency
- 7. This classification of emergency was declared at: (a.m./p.m.) on (date).
- 8. The initiating event causing the emergency classification is: *2iIT AFFECD -
. t .
- 9. The emergency condition: (a) Does not involve the ralease of radioactive materials frcm the plant.
(b) involves the potential fcr a release. but no release is cccurri. c. __( c) Involves a re! ease of radioactive material.
RP/0/A/5700/03 - l 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. (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 neerest shelter / reception center. -* (f) Other recommendations:
].
- 11. There will be: i (a) A followup message l 1
(b) No further communications PAE! I APPROVED FOR RELEASE
- 12. I M % N .
(a) Reports an actual emergency
. Signature (Laergency Coordinator.
is an exercise message T (b)
- 13. RELAY THIS INFORMATION TO TH2 PERSONS INDICATED ON YOUR ALERT PROCEDURE FOR AN INCIDENT AT A NUCLEAR FACILITY.
'"END OF INITIAL WARNING MESSAGE"*
NOTE: Record the name, title, date, ci::te and Warnina Point notified on ? ace 4 of 4.
.*es&c%m--z,
,A - , __ .._._..~m ~.w PAREIIT ~ ' ~.. .
~. =- _'. . 7. ~._: " ' J E'M~FT! -
- 1. The type of actual or projected reisesa is:
(a) Airborne (b) Waterborne i. 1 (c) Surface spill . s (d) Otner
- 2. The source and desenption of the release is:
- 3. (a) Release bogen/will begin at a.mJp.m.: time sirce reactor trip is hcurs.
(b) 7e estimated duration of the release is hours. . We en -e 9 y -- -- - , . , - , , - . - - -- - ,-,., - , , . ,n-,n--- r w- -,,e- , , - - , - , , - - ,,--,,,,,-,,,,-,,,m-.--,-,--,ww.,, -
,-,,,e,
RP/0/A/5700/03 - ENCLOSURE 4.5
- 4. Does projection base date:
Radiological release: curies, or curies /sec. Windspeed: mph Wind direction: . From . i (A,B,C,D,E,F, or G) Stability class: Reiseen heght: Ft. Does c:mverson factor: R/hr/Cl/m3 (wholebody) R/hr/C1/m3 (Child Thyroid) . - 1 Precipitrions -- Temperature at the site: 'F *
- 5. Dese protections:
- Dose Commitment +
Whole Body (Child Thyroid) Disance Rem / hour Rem / hour of inhalation
- Site boundary 2 miles -
5 miles 10 miles ..
'Proiested Intsysand Does in Rem
- Distance Whole Body Child Thyroid Site sea mtary 1 2 miles 1 5 miles ' i 1.) miles
- 6. Field measurement of dose rete or contamination (if available):
1 I i.
- 7. Emergency actions underway at the facility include:
- 8. Onsite support needed frorn offste organizations:
l l
- 9. Pisint status:
(a) Reactor is: not tripcod/ tripped
~
(b) Plant is at: % power / hot shutdown / cold shutdown / cooling down (c) Prognosis is: stable / improving / degrading / unknown. G
. - e e me o l
- . _ _ . - . . _ _ , _ _ _ _ . _ _ _ . _ _ _ . . _ ~ . . _ _ . . _ . . _ _ _ _ . . _ _ _ _ _ _ . _ . . _ _ . _ _ _ _ _ _ _ _ _ _ , . _ _ _ _ _ . , _ . _ . . _ _ , . . _ . _ _ . _ _ _ _ _ _ _ _ . _ . _ . . _ . ,
l l RP/0/A/5700/03 ~ ENCI.0SURE 4.5
- 10. I ropest, this message: PE 4 0F 4 (a) Reports an actual emergency.
(b) is an exercise message. PART'I and II APPROVID FOR REI. EASE
- 11. Do you have any questions? Signature (E=argency coordinator)
?'D WC?YE ji.e 32 l s de h "4~ 3 i$Je W ;{iI?.;.J M DN111 es ci C$.. _h .} . ':fk [.1C$dh
. NOTE: Record the name, title, date, time, and woming point notified. (Senders)
Record the name title, date, time, and persons notified per alert procedure. (Receivers)
- 1. .
(name) .(title) ,
- i (date) (time) (warning point) 2.
(name) (titie) (cate) (time) (warning point)
- 3. -
(name) (titie) (date) (time) .- (warning point)
- 4. ~
(name) (titie) (cate) (time) (warning point) ! 5. (name) (title) (cate) (time) (warning point)
. 6.
p (name) (tittel z, (date) (time) (warning pcint) 7. j (name) (title) (cate) (time) (warning point) l 8. 1 (nasse) (title) l Warning point) i (da:a) (time) l Form 34888 {6-821 l
. a.
. RP/0/4/5700/03 ENCLOSURE 4.6 PAGE 1 0F 1 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 . 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. CorrectiveMeasuresBeingTakeni
- 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.
i 7. NRC Yes No, State _ Yes No, Counties Yes No, have been notified.
- 8. The Crisis Management Team should/should not be activate'. d 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 Comments:
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I Form 34731 (1041) (Formerly SPD 10021) DUKE POWER COMPANY (1) ID No:RP/0/A/5700/04 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD 0 Incorporated * (2) STATION: McGuire Nuclear Station (3) PROCEDURE TITLE: General Emergency lik r $l - (4) PREPARED BY: M. ( R.N*S.'gW_ Glover DATE: 8/31/83 (5) REVIEWED BY:. DATE: [-bN Cross-Disciplinary Review By: N/R:N (6) TEMPORARY APPROVAL,(IP NECESSARY): . By: (SRO) Date: By: Date: . j (7) APPROVED BY: r b r - Date: 9/s P.2 * (8) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: N
- I .*s m-,ee-+ -_g- -w,p ,wy w ww-wt-e-7y -y = - r---*,_---wy-wwp ------or-rw-----yw-wm-*v v v w --mw. , . -- ---cw a ,-- e- ea y ---%e,--y -e7%q 99__,_p7
RP/0/A/5700/04
. PAGE 1 0F 5 DUKE POWER COMPANY McGUIRE NUCLEAR STATION GENERAL EMERGLNCY 1.0 Syisotoss 1.1 Events are in process or have occurred which involve actual or iminent substantial core degradation or melting with potential for loss of -
containment integrity.
. 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. . 4 3.0 Subsequent Actions - Initial /N/A -
/ 3.1 The Shift Supervisor / Emergency Coordinator shall assure that the appropriate emergency condition (Notifica*. ion of Unusual Event, Alert, Site Area Emergency, or General Emergency) is declared by evaluating the actual plant condition with Enclosure 4.1, Emergency Classification Guide Flowchart and Enclosure 4.2, List of Initiating Conditions, Emergency Action Levels, and Associated Emergency Procedere/ Document.
NOTE 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.
/ 3.2 Upon declaration of a General Emergency, the Emergency e
- w -- ------ --
RP/0/A/5700/04 PAGE 2 0F 5 Coordinator shall immediately recommend to offsite authorities, sheltering (remain indoors with the doors and windows closed, and ventilation equipment turned off, monitor Emergency Broadcast networks) of the general public within the 2 mile i radius (Areas, A, B, C, D, and Q) and 5 miles downwind (90' : Sector) of the station. (Utilize Enclosure 4.8, McGuire l Protective Action Zones to determine those areas affected to 5 ! miles downwind). Provide a follow-up recommendation as soon as . possible after evaluating the specific plant conditions, offsite dose projections and field monitoring team measurements as they , become available. (See Enclosure 4.7, Protective Action Recommendation Flow Chart).
/ 3.3 The Emergency Coordinator shall assure that all actions required by the initiating Emergency Procedure (s) will be performed and that all actions necessary for the protection of persons and property are being taken. '
, NOTE-Immediately conduct a Site Assembly and subsequent evacuation off all non-essential onsite personnel in accordance with Station Directive 3.8.1.
/ 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 l 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 trisis Managemint; Center (CMC) i shall be in accordance with Enclosure 4.6. l
RP/0/A/5700/05 PA E 3 0F 5 NOTE 2 See Enclosure 4.4, Telephone Listing, for notification, telephone numbers / radio codes /pager codes. NOTE 3 See Enclosure 4.5, Warning Message: 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 the Onsite and Offsite monitoring teams with associated communications equipment. . 3.5.2 Providing meteorological and dose estimates to offsite authorities-[for actual releases via a dedicated individual or automated data transmission . 3.5.3 Providing release 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, I the Emergency Coordinator shall utilized the l l Operator Aid Computer (OAC) " NUCLEAR-23" t l program to assess the o"fsite consequences. t In the event the (OAC) is not operational the 1 ^ Emergency Coordinator shalI request Health Physics personnel to evaluate the consequences utilizing the appropriate Health - l
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RP/0/A/5700/04 PAGE 4 0F 5 Physics Procedure, HP/0,s/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 Operating Centers, if established) or the State Radiological Protection Section, Department of Human Resources (see Enclosure 4.7, Protective Action Recommendation Flow Chart) as directed by the state, in accordance with the North Carolina 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 Whole body <1, thyroid <5, NO protective action is required. Monitor environmental radiation levels to vdrify. ,- 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. f l Monitor environmental radiation levels. Control access to affected areas. l 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 SeeEnclosure4.4,Telephon'ehistingfornotification.
^
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RP/0/A/5700/04 PAGE 5 0F 5 1
/ 3.7 The Emergency Coordinator in coordination with the Recovery Manager, at the Crisis Management Center, will:
3.7.1 Provide a dedicated individual for plant status updates to offsitt authorities and periodic press briefings. 3.7.2 Make available senior technical and management staff onsite for consultation with the NRC and State on a , periodic basis. 3.7.3 Determine the need to remain in a General Emergency, reduce the emergency class, or close out the emergency.
/ 3.8 The Recovery Manager at the Crisis Management Center will close out or recommend reduction of the emergency class, by briefing of those personnel and offsite authorities notified in Step 3.4 at the Crisis Management Center or by phone if necessary, followed by written summary within ,8 hours. ,
'4.0 Enclosureg ,
4.1 Emergency Classification Guide Flowchart 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 Message: Nuclear Facility to State / Local Government 4.6 Emergency Plan Message Format 4.7 Protective Action Recommendation Flow Chart 4.8 McGuire Protective Action Zones
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i RP/0/A/5700/04 *
. ENCLOSURE 4.2 *
. PAGE 1 0F 6 LIST OF INITIATING CONDITIONS, ENERGENCY ACTION LEVELS, AND ASSOCIATED EHERCENCY 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 ren/hr Whole Body or 5 res/hr Thyroid at the site boundary under .
actual meteorological I conditions. NOTE 1: These dose rates are projected base on i plant parameters (e.g., radiation levels in con-i 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 4 levqls are exceeded by a fac-tor of 10 or projected to wn-tinue for 10 hours or EPA Pro-1 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 Are.a Emergency AP/2/A/5500/05 tlal loss of 3rd barrier, 4.2.1, and incomplete contain-(e.g., loss of primary ment isolation. coolant boundary, clad-i failure, and high poten- 2. Loss of coolant accident as iden-tial for loss of contain- tified in Site Area Emergency 4.2.1, ment integrity). andContainmentHonitorajarms (EHF51A and/or B) greater than 10 R/hr and con ~ cain.iant twem:are greater than 14.8 psig . for at l a. .it i uinutes.
- RP/0/A/5700/04 ENCLOSURE 4.2
- PACE 2 0F 6 Initiating Conditions Emergency Action Level (Ei') 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 A. Stermined by the Shift Supervisor / As dictated by plant conditions. exist, from whatever Emergency Coordinator and verified by EAL's defined in Implementing Procedures source that in the judge- ' 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 }arge amounts at radio-activity in a short time , period possible (e.g., any , core melt situation). , a. For core melt sequences ' where significant re-leases are not yet
- taking place and large
.. amounts of fission pro-I ducts are not yet in the containment atmos-phere, consider 2 mile s precautionary evacua-tion. Consider 5 mile downwind evacuation .
(45 to 90" sector) . If large amounts of ! fission products 4 (greater than Cap acti-I vity) are in the con-
- tainment atmosphere.
I Recommend sheltering in 4 other parts of the l plume exposure Emac-gency Planning Zo..a under this circumstance.
RP/0/A/5700/04 ENCLOSURE 4.2 . PACE 3 OF 6 Initiating Conditions Emergency Action Level (EAL) Emerger.cy Procedure / Document
- b. For core melt se-quences where signi-ficant releases from containment are not ~
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 i addition to noble gases are in the con- , , , , tainment atmosphere, consider precautionary , i evacuation to 5 miles . and 10 mile downwind evacuation (45 and j 90 sector). 1 c. For core melt se-quences where large
.. amounts of fission 1
products otlier than , noble gases are in i - the containment ] atmosphere and con-j tainment failure is judged imminent, re-1 commend shelter for j those areas where evacuation cannot l be completed before transport of acti-vity to that loca-tion. 5
-e
RP/0/A/5700/04 ENCLOSURE 4.2 , PACE A 0F 6 Initiating Conditions Emergency Action Level (EAL) 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 2 times given current conditions.
- e. Example Sequences:
! 1. Small and large Safety injection, signal plus reac-j , 1.0CA's with fail- tor trip and:
- ure of ECCS to per- ,
form leading to 1. Safety injection and RllR - severe core de- pumps not running. i gradation or melt. Ultimate failure 2. Flow indications for safety of containment injection read "0". likely for melt sequences. (Seve- 3. liigh containment sump level. .
.- ral hours likely to be available For Severe Fuel Over Temperature:
to complete pro- Creater than 10% failed fuct tective actions indicated by greater than unless containment 13,000pci/mi-131 concentration. i is not isolated). For Fuel Helt Conditions: Greater than 5% failed fuel
! indicated by greater than i ll.800pci/m1 1-131 concentration.
e D
a l , RP/0/A/5700/04 ENCLOSURE 4.2 , i PAGE 5 0F 6 Initiating Conditions Emergency Action Level (EAL) Emergency Proceduce/ Document
- 2. Transient ini- Reactor trip on Lo Lo Steam Cenerator AP/1/A/5500/06, AP/2/A/5500/06 clated by loss level 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 og; emergency
; heat removal sys- feedwater pumps not running and can-tem) followed by not be restored within 30 minutes fyt failure of emer- >3% reactor power and loss of both gency feedwater main feedwater pumps, manually trip system for ex- reactor.
j tended period. j (Core melting is
. possible in seve-ral hours with ,,,. ,
ultimate failure of containment
- likely if the
. core melts).
1
- 3. Transient requir- Reactor remains critical after all AP/0/A/5500/34 ing operation of attempts to trip the reactor are shutdown systema complete and flow indicators on with failure to safety injection and RHR show "0"
) .. scram. Core dam- flow after initiation (NVP5440, age is likely. NDP5190, 5191, 5180, 5181, Additional failure HIP 5120, 5450) $gt safety injec- ,
i of the core cool- tion and RHR pumps not running
! ing and makeup with safety injection initiated.
1 system would lead to core melt. i i
4 i RP/0/A/5700/04 ' ENCLOSURE 4.2 , PAGE 6 0F 6 Initiating conditions Emergency Action Level (EAL) Emergency Procedure / Document
- 4. Failure of offsite Undervoltage 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 total auxiliary feedwater pump (s) fail to
, loss of emergency start.
feedwater makeup capability for several hours. Would lead to eventual core j melt and likely j 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 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 *5180. 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 containment. , l NOTE: For melt se-l quences or for failure j of containment isola-l tion systems, the likely I failure mode is melt j through with release
- of gases.
1 4.2.5 Any major internal cr ex- As determined by the Shift Supervisor / As dictated by plant conditions. )l ternal events (e.g., fires, Emergency Coordinator. earthquakes substantially i heyond design levels) which could cause massive common damage to plant systems. i .
. _ . __ . . _ . ~ ._ . . . . . _ .. . _ _ . _ _ _ _ _ .
RP/0/A/5700/04 ENCLOSURE 4.3 PAGE 1 0F 1 N9TIFICATION/ ACTIVATION GENERAL EMERGENCY 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 Enaineer . Station Manacer - Superintendent of Operations Superintendent of Technical Services Projects and Licensino Engineer Station Health Pnysicist North Carolina State Warnino Point -
- Mecklenburg County Warning Point Lincoln County Warnino Point
~'
Catawba County Warning Point - . 4 Iredell County Warning Point - Gaston County Warning Point Cabarrus County Warning Point South Carolina State Warning Point N.R.C. via ENS (Red Phone) (Station Directive 2.8.1 and 3.1.4) N.R.C. Station Representative Superintendent of Maintenance Superintendent of Administration Construction Project Manager Activate T.S.C. (Station Directive 3.8.2) Activate 0.5.C. (Station Ofrective 3.8.2) Activate C.M.C. (Enclosure 4.6) l
- t.".
l
, .,,- -. .m _ _ , _ , ._. ,. __ . . ~ _e_-.,_ _. , , - _ ...r..__...m. _ , , __ . .y,,,.,_,,....._._.,__.__,__._,_,r ,.,,,,% .._,_ . , _. , _ .m
RP/0/A/5700/04 ENCLOSURE 4.4 PAGE 1 0F 2 TELEPHONE LISTING 4.4.1 Operations Duty En ystem)
, P&T Pager -
4.4.2 Station Manager Home - - System Speed Home - - System Speed 4.4.3 Superintendent of 0 erations Home ' System Spee 4.4.4 Superintendent ical Services - Home - System Spee 4.4.5 Projects and Licensing Engineer . Home Q -System Speed 4.4.6 Station Health P cis Home stem Speed P&T Pag 4.4.7 NC State Warning Point, Raleigh - System Speed
~
4.4.8 Meck'lenburg County Warning Point - Primary: Rin Down Ppone Back up: System Spee
. Back-up: mergency Radio, Code:
4.4.9 Lincoln County Warning Point - Primary: in Down Phone
~
Back-up: ' System Spe Back up: Emergency Radio, Code: 4.4.10 Catawba County Warning Point - Primary: Ri Ocwn Phone Back up: ' System Spee Back up: :mergency Radio, Code: 4.4.11 Iredell County Warning Point - Primary: own Phone Back-up: System Sp Back-up: Emergency Radio, Code: 4.4.12 Gaston County Warning Point - Primary: in Down Ph,one Back-up: - System Speed Back-up: Emergency Radio, Code: 4.4.13 Cabarrus County Warning Point - Primary: Ri Down P!)cne Back-up: - System Spee Back-up: Emerge Radio, Code: NOTE
- 1. Radio CodEdill activate -
all county radio units.
- 2. P&T Pager, Centra ision (Charlotte Area)
Dial - '~
\ . .
l
! RP/0/A/5700/04 -
I ENCLOSURE 4.4 PAGE 2 0F 2 TELEPHONE LIST 4.4.14 SC State Warning Point ' 4.4.15 N.R.C. Operation Cente.*, Emergency Notification System (ENS Phone) 4.4.16 N.R.C. Station Representative (Bill Orders) Offic Home System Spee P&T Pag , site Pager - For P&T Page from Central (MNS Area) I 4.4.17 Construction Project Manager tructic Ext. l Home : peed 550, Mt. System Spee - i 4.4.18 Superintendent of Maintenan l d Home - System Speed ; 4.4.19 Superintendent of Administrati Home - System Speed 4.4.20 Nuclear Production Outy Engine System Speed P&T Page 4.4.21 Radiation Protection
- artment of Human Resources-
' System Speed Q M
t
. r .
9 GN WARNINGNONCEAfEFACIUITTGSVETEEON ' s :- ':: %, . 1 3l Instrudom RP/0/A/5700/Ca 03 A. For Sender: p 3 7
- 1. Complete Part I for the 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 ecde word or by calling back to the facility. (See Part I .3)
Time: Date: . Message Received By: __ hY$YdEMNNNNh1N$YW3MCY$shT M NOT35NDNNbj
- 1. This is: v -c. .e -- v.. - -
',e- e ,-e--
Onsert narne or racditys
- 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:
(Verify coce werd or ad bacx to ne fac:li:v)
- 6. The class of the emergency is: (a) Notification of Unusual Event (b) Alert (c) Site Emergency (d) General Emergency
- 7. This classification of einergency was declared at: (a.m./p.m.) on (date).
- 8. The initiating event causing the amergency classification is: CT A??ECTED -
~
.I
- 9. The emergency condition: (a) Oces not invcive the release of radicactive materials frem the plant.
(b) Involves tne ::otential for a release, but no release is occurr .;. (c) Involves a release of radicactive material,
RP/0/A/5700/04 ENCLOSURE 4.5 PAGE 2 0F 4
- 10. We recommend the following protective action:
(a) No protective action is recommended at .his time. (b) People living in zones remain indoors with the doce. 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: , [ . l l l 11. There will be: l (a) A followup message (b) No further communications
- 12. I repeat, this c:essage: -
PART I APPROVED FOR RELEASE (a) Reports an actual emergency (b) is an exercise message -
. Signature (Emergency Coordinat:qd
- 13. RELAY THIS INFORMATION TO THE PERSONS INDICATED ON YOUR ALERT PROCEDURE FOR AN INCIDENT AT A NUCLEAR FACILITY.
***END OF INITIAL WARNING MESSAGE ***
NOTE: Record the name, title, date, time and Warning Point notified on Page 4 of 4 i
..'.- [
. , ,: _ .. .. .- . .. -[ .
l 1. The type of actual or projected release is: (a) Airbome-(b) Waterbome (c) Surface spill (d) Other
- 2. The source and description of the release is: ___
- 3. (a) Release began /will begin at a.m./p.m.: time since reactor trip is hours.
~
(b) The estimated duration of the release is hours.
,e-.
,m m---,..w_. , , , , , , , , , - - - -+.---ww. -- 9, ,e.y ,y - - -- m-,,, _,-,
RP/0/A/5700/05
- 4. Dose projection base data:
Radiological release: curies, or curies /rw. Winospeed: mph 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 Cornmitment' Wiole Body (Child Thyroid)
Distance Rem / hour Rem / hour of inhalation Site boundary 2 miles 5 miles . 10 miles .
' Projected latograted Dose In Rem *
- Distance Whole Body Child Thyroid Site Boundary i 2 miles 1 5 miles 10 miles
- 6. Field measurement of dose rate or contamination (if available):
- 7. "T swi actions underway at the facility include:
- 8. Onsite support needed from offsite organizations:
- 9. Plant status:
(a) Reactor is: not tripped / tripped (b) Plant is at: % power / hot shutdown / cold shutdown / cooling down (c) Prognosis is:. stable / improving / degrading / unknown.
RP/0/A/5700/04 ENCLOSURE 4.5 PAGE 4 0F 4
- 10. I ropest, this message:
(a) R'eports an actual emergency. (b) is an exercise message.
- 11. Do you have any questions?
.3 TC ; ;3,-G , 21-1~;4%yl:ND OFE OROW'-UPMEESSAGNvWNEWY51Tish%
~
NOTE: Record the name, title, date, time, and warning point notified. (Senders) 1 Record the name title, date, time, and persons notified per alert procedure. (Receivers) l 1. (name) (title) , (date) (time) (warning point) .
- 2. ._
(name) (title) (date) (time) (warning point) ,
- 3. _
(name) (title) (date) (time) (warning point)
~
~
4. (name) - - (title) (date) (time) (warning point)
~
(name) (title) (date) (time) (warning point) 6. (name) (title) (date) (time) (warning point) 7. (name) (title) (date) (time) (warning point)
- 8. _
(name) (title) (date) (tine) Form 34888 (6-82) (varning point)
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- O RP/0/A/5700/04 ENCLOSURE 4.6 i PAGE 1 0F 1 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 . 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
- 4. Corrective Measures Being Taker 6
- 5. There Have/Have Not been any injuries to plant personnel.
- 6. Release of radioactivity: Is/Is not tak'ing place, and is/is not affecting the i 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 Communications and Co.1pany Management should be notified (Unusual Event Only).
- 9. I can be reached at for follow-up information.
(Telephcne Numoer)
- 10. Additional Comments:
- 1 'e a mm a m w a e
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- PS/0/A/5700/04 '
s ENCLOSURE 4.8 PAGE 1 0F 1 NI.C G UIR E PROTECTIVE ACTION 2CNES e O . I
.-./
n.~J ,e .
,y na +L e .x y. ..
a ,.. s _ a
~ sh . s l &. al '\ k,wh f e .-Y a.
.vi 9m r *J 4e a; m# *: 2
("^, }4
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- a. .c i= m c > , c- ,
- .w
=
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a .,
. -w > 3r- . i %
v;r. 2.0 mres/hr encompassing a majority of the exclusion area.
C. Any airborne contamination in excess of concentrations set forth in 10CFR20, Appendix B, Table II, within the exclusion area.
D. Toxic or flammable gases within the exclusion area.
E. Bomb Threat ,
- 3. The individual e-- -H= the Site Evacuation shall determine which evacuation facility is to be utilized. based upon implications of the emergency (radiological, chemical, fire, security, etc.) and meteorological conditions (wind direction, precipitation, etc.). See Enclosure 2, Evacuation Routes to the Training and Technology Center and Cowan's Ford Dam.
IMPLEMENTATION - SITE ASSEMBLY
- 1. The Shift Supervisor or his designee shall sound a twenty second blast of the Site Assembly Alarm and make the following announcement on the plant page system:
"This is a Site Assembly. This is a Site Assembly. There is/are in/at . All personnel and visitors onsite are to what where report to your,immediate supervisor or assembly point."
- 2. Repeat Step 1 in full.
- 3. At this time, all personnel shall report to their supervisors or their assembly points shown in Enclosure 1. (Assembly points are provided to assist supervision in accounting for their personnel).
A. Superintendenta and their clerks and the Station Manager's clerk shall assemble in their offices (outside the protected area) or the TSC (inside the protected area) if activated, and will be allowed normal passage thru the Personnel Access Portal. i i _ . . ~ . . - . - _ . _ _ - _ . . _ . . - _ . - - . _ _ _ . _ _
. . /
3 B. Normal passage thru the Personnel Access Portal (PAP) shall not be restricted during a Site Assembly, however, the Emergency Coordinator may - request the Security Shift Lieutenant to secure the PAP if the emergency condition warrants. C. After normal working hours, on weekends, or anytime the Administration offices are normally unoccupied, all personnel outside the protected area < shall assemble in the canteen. NOTE: During routine drills, the PBX Operator and assigned Security personnel at their assigned posts, shall remain at their stations. I
- 1
- 4. Supervisors, upon accounting for their people shall report to their Section Heads, who in turn, upon receiving accounts from all their supervisors shall report to their respective superintendent or superintendent's clerks.
- 5. The superintendants or their clerks, Senior QA Engineer, and the Construction Project Manager, after receiving accounts from their section heads shall report to the Superine=adant of Ad=inistration who in turn, after receiving these reports shall notify the Emergency Coordinator (Station Manager or Shift Supervisor) All individuals gasite at the time of the emergency shall be accounted for and the names of missing individuals shall be identified within 30 mintues of the start of an emergency requiring Site Assembly.
After a Site Assembly is completed and a plant emergency condition continues to exist, accountability of all personnel onsite will be maintained by individual supervision. NOTE: Commencing fifteen (15) minutes after initiation of a Site Assembly, the Superintendents, Senior QA Engineer, and the Construction Project Manager should begin personnel status reports to the Superintendent of Administration who in turn, will notify the Emergency Coordinator (Station Manager or Shift Supervisor). These status reports should be continued at fifteen (15) minute intervals until all. personnel are accounted for. , , , i l 6. Search and rescue of missing personnel will be at the discretion of the Emergency Coordinator, and shall take into account the emergency situations i __ _ _ , _ _ _ _ _ _ _ . _ _ _ . . ~ . _ . _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ __._,.___ _._________
4 that may be encountered such as radiological hazards, fire, toxic gases or
.other conditions that may involve personnel safety. Station Fire Bridade personnel trained in rescue procedures and accompanied by Health Physics personnel during radiological situations, shall be utilized for search and rescue of missing personnel.
- 7. After normal hours, or anytime the Administration offices are normally unoccupied, the senior person in each section shall be responsible for the personnel.in his group, and shall report to the Shift Supervisor when all personnel are accounted for.
i
- 8. When the condition warranting Site Assembly has been removed or stabilized to the point where it is no longer a personnel hazard and normal personnel traffic will not hinder any subsequent recovery actions, the Emergency Coordinator shall secure from the Site Assembly via the station PA System.
IMPLEMENTATION - SITE EVACUATION .
- 1. As per Step 3 of Responsibility forplementation, determine the evacuation .
. facility to be utilized. See Enclosure 2, Evacuation Routes to the Training and Technology Center and Cowan's Ford Dam.
- 2. The Shift Supervisor or his designee shall sound a twenty (20) second blast of the Site Evacuation Alarm and make the following announcement on the plant page system:
"This is a Site Evacuation. This is a Site Evacuation. All designated s
non-essential personnel are to: -
, (1) proceed to: .
Training Center /Cowans Ford Dam (2) peoceed offsite/home."
- 3. Repeat Step 2 in full.
* / .
- 4. If deemed necessary by the Emergency Coordinator or Shift Supervisor, request the Mecklenburg County Police to assist in traffic control near and around .
l 5 McGuire Nuclear Station and to assist in the control of boating areas on lake
~
Norman withir. the exclusion area. (See Enclosure 3) (Station Security will
-work with the County Police in directing traffic to the evacuation facility designated.)
- 5. Continue to repeat Step 2 at 3 minute intervals until notification from plant supervision that the site is in fact evacuated.
- 6. At this time, all non-essential personnel shall evacuate to the designated evacuation facility. (See Enclosure 2). All personnel shall utilize their individual private vehicles with the following exceptions:
(1) In the event road conditions (severe weather) or a release of radioactive materials has affected.use of private vehicles, all non-essential personnel shall proceed to the designated evacuation facility by foot. (2) In the event the situation does not involve a release of radioactive materials or cone ==4antion of the site area, the Emergency Coordinator may allow non-essential personnel to leave the site in their vehicles and proceed offsite/home. (3) Control Room personnel shall, stay on station, evacuate to the Standby Shutdown Facility, or to the evacuation facility as directed by the Shift Supervisor. In the event the Technical Support Center becomes uninhabitable, the Emergency Coordinator may direct that he and the Superintendents move into the Control Room protected area or evacuate to the designated evacuation facility. NOTE: If there is radiological contamination of equipment and personnel, ,,. Health Physics Emergency Environmental survey teams shall be provided in accordance with the Station Health Physics Manual, Section 18.2 (Environmental Monitoring for Emergency Conditions). Emergency Personnel survey teams shall be provided in accordance with Station Health Physics Manual, Section 18.3 (Personnel Monitoring for Emergency Conditions).
. r .-
- 7. Nuclear Production Superintendents, the Senior QA Engineer, and the Construction Project Manager shall account for their personnel at the
- _ - . . . - - - . - - - - _ - - _ - . - . - _ _ _ _ _ - _ - . - ~ . _ - - - - . _ _
l 6 evacuation facility and report to the Superintendent of Administration who will in turn inform the Emergency Coordinator of the evacuation status. NOTE: Commencing thirty (30) minutes after ir.itiation of a Site Evacuation, the Superintendent of Administration shall begh personnel status reports to the Emergency Coordinator. These status reports should be continued at fifteen (15) ainute intervals until all personnel are vacuated and accounted for.
- 8. After6 normal working hours, on weekend =, or anytime ths Administration offices are normally unoccupied, the senior person in each section shall be responsible for the personnel in his group and shall report to the Emergency Coordinator when all evt.cuated personnel are accounted for.
- 9. The Emergency Coordinator in coordination with the Recovery Manager at the Crisis Management Center will provide instructions to Nuclear Prod' action and Construction supervision regarding the further disposition of evacuated personnel. In the event evacuated personnel must remain at the evacuation facilities for an extended period of time, the Recovery Manager shall provide for their care and disposition. ,
- 10. When the emergency condition requiring Site Evacuation no longer exists, the Emergency Coordinator shall secure from the Site Evacuation.
l ENCL 0SURES
- 1. Assembly Points
- 2. Evacuation Routes to Training and Technology Center and Cowan's Ford Dam
- 3. Telephone List
- i .
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l l STATION DIRECTIVE 3.8.1 ENCIDSURE 1
. ASSEMBLY POINTS WITHIN OUTSIDE RESPONSIBLE
. GROUP PROTECTED AREA PROTECTED AREA SUPERVISION i 1 A. Operations Operation's Office Operations Admin. Shift Supervisor Building Office kOTE: Control Room Operators remain on station. B. Admin Services I
, 1) Administrative PAP at Exit Cooridor Training Room (Admin. Bldg.) Superintendent of i
! Personnel and Administration Training Services Per'sonnel g
- 2) K-Hac Vending Trailer Training Room (Admin. Bldg.) K-Mac Supervisor
]
, (near Unit #1 Turb. Bldg.)
{ 3) Security Security Office Assembly Training Room (Admin. Bldg.) .Sec. Shift Lieut. l Room (CAS, SAS,and PAP
! Remain on Post) l f 4) Vis'itors Escorted - with escort Training Room (Admin. Bldg.) Cont. Services Coord.
) (Includes all (Visitors outside the l personnel ONSITE protected area) ! not assigned to
.a Station Group)
$ NOTE 1: Visitors assigned unescorted access shall be assigned { to a responsible group by security personnel during l initial badging procedure. The responsible group shall provide accountability for these visitors.
STATION DIRECTIVE 3.8.1 j- i ENCIDSURE 1 ASSEMBLY POINTS l* ! WITHIN OUTSIDE RESPONSIBLE CROUP PROTECTED AREA PROTECTED AREA SUPERVISION i NOTE 2: The Contract Services Coordinator shall account for unescorted visitors for all onsite areas outside the
. protected area.
{ } . I C. Tech Services
- 1) Projects & Performance Trailer Superintendent's Office P&L Engineer l
Licensing, MRC , Personnel Onsite
- 2) Performance Performance Trailer ,
Superintendent's office Performance Supv.
- 3) Chemistry CT Lab Superintendent's Office' Station Chemist
] l 4) Health Physics HP Lab Auxiliary Count. Room Sta. Health Phys. NOTE 1: If radiation levels within the HP Lab are excessive, j Health Physics shall report to HP trailer. NOTE 2: If the emergency has radiological implications Health Physics escorts shall take their visitor to the PAP. D. Maintenance ) 1) Hechanical Assembly Room in Shop Superintendent's'0ffice Haint. Engineer (SHS, SSD)
- 2) 1&E I&E Shop Superintendent's Office I&E Engineer j 3) Planning Planners Office Superintendent's Office Planning Engineer l
1 . j ..
i I STATION DIRECTIVE 3.8.1 ENCLOSURE 1
, ASSEMBLY POINTS I
i
; WITHIN . DUTSIDE RESPONSIBLE GROUP PROTECTED AREA PROTECTED AREA SUPERVISION j i 4) NSS Trailers, Unit #2 Superintendent's Office Superintendent
' ! Turbine Building
, I I i
! NOTE: Any Transmission Department Personnel assigned ts the } Station Haintenance Department shall assemble with the
' group / crew they are assigned to.
1 E. QA QA Office Above CT Lab Senior QA Engineer's Office Q.A. Engineer F. Construc' tion Hosie Base Headquarters , Home Base Headquarters , Construction Ngr. ! G. Station Hanager Control Room Manager's Office Station Hanager i i 9 i 1 1 1 i i I i i j -
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~ . STATION DIRECTIVE 3.8.1 ENCLOSURE 3 TELEPHONE LIST A. Mecklenburg County Police B. Superintendent of A<f=4 nistrati t
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i Form 34731 (1081) (Formerty SPD 10021) DUEE F0WER CGIFANT (1) ID No: up/o/E/1009/10 PROCEDURE PREFARATION Change (s) O to PROCESS RECORD A Incorporated (2) STATION: McGuire Nacisar station (3) FROCEDURE TITLE: asleases of MW hve Materic -Ha? T=ah=4-=1 3 r 4**--tions - (4) PREPARED BT: InMC - _ or 2 C DATE: ? do - P . (5) REVIEWED ET: ' >- % e l DATE: f/3M3
- Crose-Dd_ --4 =14 ==7 Review By:
N/E: 26 (6) TEMPORAI! AFFROTAL (IF NECESSARY): By: (S10) Date: , sy: - Date: p/, J, rP\ :W1 , . ./ (7) AFFRovED sT: Date: ?bo/C o - l (8) wtwimnrrs: - Reviewed / Approved By: Date: l Eaviewed/Ai y... J 3y: Date:
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l t EP/0/B/1009/10 ! DUKE Polm1 COMPANY McGUIRE NUCLEAR STATION RELEASES OF LIQUID RADI0 ACTIVE NATERIALS EECEEDING TECHNICAL SPECIFICATIONS 1.0 Purpose This procedure describes the methods for calculating the radicanclide concentration at area water supply intakes following an accidental liquid release, and the subsequent actions to be taken when the concentration exceeds Taehnical Specifications. 2.0 M erences 2.1 Station H.P. Manual Section 18.2; Environmental Monitoring for Emergency Conditions. - 2.2 EMF Unit Data Book. 2.3 10CFR20 Appendia B. 4 2.4 Station I.P. Manual, Section 16.3; Survey Documentation. 2.5 Travel time and dispersion characteristics of Mountain Island Lake Duka PWR/80-02. - 3.0 Limits and Precautions b - 3.1 This procedure shall be used in an Emergency situation which could' result in shutdown of area water supply intakas. The
' procedure shall 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 shall authorize the use of this procedure when needed and shall provide appropriate surveillance and control of people taking the samples. l 3.3 Verify counting equipment to be used has been calibrated and l daily response checks have been performed. 3.4 Individuals collecting the samples shall be aware of the possibility of airborne cont ==ination and high radiation levels in sampling areas. Use protective: clothing, gloves, respiratory protective equipment, portable shielding, high range dostasters and survey instruments as determined by a Esalth Physics supervision. 1 _ - . , . . . - - . - . - _ = , . _ . _ . _ , . _ . _ _ . -
l l Pcg3 . 3.5 Collect samples, count samples and calculate activities in accordance with reference 2.4. 4.0 Procedures 4.1 Health Physics shall collect and evaluate samples as per reference 2.1. 4.2 Er.alth Physics shall determine the discharge point concentration from EMF data and/or samples taken. NOTE: For ENF data see conversion graohs for CPM to uCi/ml located in Unit Data Book (Reference 2.2). 4.3 Tha Offsite Dose Assessment Te$a shall det.traine the potential for contamination of area water supplies using Enclosure 5.1 (Transit Time /Radionuclide Concentration Calculations) and sampling data ; rom Health Physics. 4.4 If data indicates that a release through 6he CCW to Lake Norman is likely to es ceed limits specified in 10CFR20, Appendix B, at affected area water intakes, the Emergency Coordinator shall: 4.4.1 Request maximum possibl,e water flow at Cowans Ford Hydro Station.from System Load Dispatcher. 4.4.2 Notify the area water supply pusoing station's to j cease pumping operations until the contaminatiot levels have passed or have been diluted to within acceptable limits. Tech. Spec limits taken from 10CTR20, Appendix B, for unknown mixture is 3 x 10-8, or table II if isotope analysis is available. I 4.5 If data indicates that a release that the Conventional Waste Water Treatment Pond to the Catawba River is Aikely to exceed i limits specified in 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. NOTE: Transit time to Charlotte Water Department
, int.has is approximately 79 days with NO i FLOW thru Cowans Ford.
4.5.2 Notify the Charlotte Water Department that a release of radioactive materials has occurred into the 1 I
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e Pega Catawba River and that sampling and evaluation of samples is being undertaken. In the event that sampling confirms that contamination levels at the Charlotte intake shall exceed limits specified in 10CP120, Appendix B, recommend the Charlotte Water Department cease pumping operations during the period of time cone ==4n=ced water supplies are passing the Charlotte pumping station intakes,(see Enclosure 5.2). 4.6 At the reqcest of the Emergency Coordinator thru the Station Health Physicist. Health Physics shall sample and evaluate the concentration of contamination in the Catauba River near the discharge point. 4.7 The people notified in the appropriate Emergency Procedures (EP/0/A/5700, 1, 2, 3, 4) stab.beresponsibletodecidewhat protective measure shall be taken in the interost of publi: health and safety. Th2 state agency is responsible for appropriate long-term public health actio: (North Carolina Department of, Crime Control and Public Safety). 4.8 Actual field measurements of whole body doses shall be
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compared to vbole body dose projections by rhe Data Evaluation Coordinator. 5.0 Enclosures 5.1 Transit Time /Eadicauclide Concentration c=1 & 1=tions. 5.2 Emergency Plan Implementing Procedures Telephone List. I
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n2/O/d/AUVYi&U ENCLOSURE 5.1 TRANSIT TIMES /RADIONUCLIDE CONCINTRATION CALCULATIONS Description Transit times and radionuclide concentrations for a release of radioactive material from McGuire Nuclear Station release point to the water intakes of Huntersv111e, Dah dson, Charlotte, and from McGuire Nuclear Station to the Catawba River and Charlotte water intake. McGuire Discharge Water Trsasic Dilution Focunia Point Intaka Tina (hrs) Constant (D) Raquired CCW Discharte Huntersv111e 4 0.22 #1 to Lake Davidson 11 0.22 #1 Norman Charlotte 8 0.22 #2 Conventional Charlotte 4 0.33 #3 Waste Water (See Note 1) (Saa Note 2) Treatment Point - to the Catawba River - NOTE 1: Transit tian assumes 4 unit Cowan's Ford operation. Focaulas: #1 C=Ed)
. M
#2 -
C=E4) . - G .
#3 C=Ed)
F Where: - C = Radionuclide Concentration at area water supply intaka (uci/al) E = Discharge Point Concentration (uci/al) D = Dilution Constant M = McGuire CCW Flow in efs, (2 Unit Operation, 1 Pump = 712 cfs, 2 Pumps = 1424 cfs, 3 Pumps = 1931 efs, 4 Pumps = 2263 cfs, 5 Pumps = 2492 cfs, 6 Pumps = 3204 efs, 7 Pumps = 3987 cfs, 8 Pumps = 4842 cfs. F = Cowana Ford flow in efs (Request flow rate in efs from system
- dispatcher).
G = M or F, whichever,is greater, , , NOTE 2: Dilution constant was derived from a " Mountain Island Dye Study" conducted by Duke Power Company in 1978 and 1979 and _ published in a complete report by the cicle of " Travel TIma and Dispersion Characteristic: af Mountain Island Lake". e
A - ' EP/0/3/1009/10 ENCLOSURE 5.2 i 'i ! EMERGENCY PLAN DfPL MrG PROCEDURIS TELEPHCNE LIST i Charlotte Water River Pumping Station Administration Building Curtis Frederick - Plant Super. Emergency Radio Call Sign 1 Huntersv111e Water Pumping Station l Robert Cobb Pani Raynolds Jerry Johnson
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Richard French' (Tovu Manager) j Davidson Water Pumping Station Nancy McCornac - Mayor l Trank Ellington Baxter Fisher Civil Preparedness- Bob Manning Bill 3rannon Esaith Physics Shift Technician , I l
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