ML20085N351
| ML20085N351 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire  |
| Issue date: | 06/07/1983 |
| From: | Glover M DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20085N329 | List: |
| References | |
| PROC-830607-01, NUDOCS 8311100369 | |
| Download: ML20085N351 (115) | |
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Form 34731 (1041)
(Formerly SPD 10021)
. DUKE POWER COMPANY (1) ID No: RP/0/A/5700/01 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD 0 Incorporated (2) STATION:McGuire Nuclear Station -
, (3) PROCEDURE' TITLE: Notification of Unusual Event
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(4) PREPARED 3Y: M. S'. Glover DATE: 5/31/83 (5) REVIEWED BT: DATE: $ ~2.-73 Cross-Disciplinary Review By: N/R:
(6) TEMPORAEI APPROVAL (IF NECESSARY):
3y: (SRO) Date:
By:. Date: !
(7) APPROVED BY: Date: / 3
//
(8) MIS N 7.AMEOUS:
Reviewed / Approved By: Date:
i Reviewed / Approved By: Date:
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I 8311100369 831107 \
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i e DUKE POWER COMPANY McGUIRE NUCLEAR STATION i NOTIFICATION OE UNUSUAL EVENT 1.0 Symptoms 1.1 This condition exists whenever unusual events are in process or have occurred which indicate a potential degradation of the level of safety of the plant.
2.0 Immediate Actions 2.1 Automatic None 2.2 Mami= 1 9
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 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 Cla'ssification Guide Flowchart and Enclosure 4.2, List of Initiating Conditions, Emergency Action Levels, and 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.
/ 3.2 The Emergency Coordinator shall assure that all actions I
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( 1 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.
i, 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 necessary, refer to Station Directive 3.8.1.
/ 3.3 The Emergency Coordinator shall assure prompt (within about 15 minutes of declaring the emergency) notification of _the North Carolina State and Local County Warning Pointa indicated on Enclosure 4.3. He shall also assure notification of all other personnel listed in Enclosure 4.3.
NOTE I See Enciosure 4.4, Telephone Listing; for notification, telephone numbers / radio codes /pager codes.
NOTE 2 See Enclosure 4.5, Warning Message: Nucle'ar Facility to State / Local Government, for information to be provided to State / County Warning Points.
l NOTE 3 See Enclosure 4.6, Emergency Plan Message Format i for information to be provided to Nuclear l Production Duty Engineer.
l l / 3.4 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 shalt utilize the Opeator Aid Computer (OAC) " Nuclear-23" program to assess the i
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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.
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/ 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, Department of Etman 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 (REH) to the population of: (EPA Protective r Action Guidelines).
3.5.1 Whole body <1, thyroid <5,' NO protective action is !
required. Monitor environmental radiation levels to verify. 6
, 3.5.2 Whole body 1 to <5, thyroid 5 to <25, reco==and seeking shelter and wait for further instructions. Consider evacuation particularly for children and pregnant women.
Monitor enviror:matal radiation levels. Control access to affected areas.
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NOTE If this is the projected dose evaluate Site Area Emergency and General Emergency Initiating Conditions and Emergency Action Levels.
.I 3.5.3 Whole body 5 and above, thyroid 25 and above, recommend
==ndatory evacuation of populations in the affected s
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PAGE 4 0F 4 areas. Monitor environmental radiation levels and adjust area for mandatory evacuation based on these levels.
,t Control access to affected areas.
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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 detemine 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 su e ry to county and state authorities, notified in Step 3.3, followed by written summary within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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 4.4 Telephone Listing 4.5' Warning Nessage: ' Nucle'ar 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/5700/01 J ,
5 ENCLOSURE 4.1 PACE 1 OF 1 .
EMEHGENCY CLAS$4FICAllON GUIDE FLOwCilART e
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ENCLOSURE 4.2 :
PAGE 1 0F 5 - 2 LIST OF INITIATING CONDITIONS, EMERGENCY ACTION LEVELS, AND s.
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ASSOCIATED EMERGENCY PROCEDURE / DOCUMENT -
i Initiating Conditions Emergency Action Level (EAL) , Emergency Procedure / Document ;,
4.2.1 Emergency Core Cooling Safety Injection signal verification EP/1/A/5000/01, EP/2/A/5000/01 -
by redundant indication and indication
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Initisted (SI) and 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, r' occurred. EP/1/A/5000/04 EP/2/A/5000/04, -
AP/1/A/5500/35, AP/2/A/5500/35 C 4.2.2 Radiological effluent EMF 49, 50, 35, 36, 37 Alarm indicating Tech Specs 3/4.11. Environmental l Technical Specificetion limits exceeded.
Technical Specification Limits exceeded. Tech Specs, HP/0/8/1009/09, )f ;
HP/0/8/1009/10 HP/0/8/1009/05 i - ie .
- 4.2.3 Fuel Damage Indication
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- i a. High coolant activity a.'>1 pC1/ gram Dose Equivalent I-131 or AP/1/A/5500/IS, AP/2/A/5500/18,
- sample exceeding Tech. >100 pC1/ gram gross activity.
Specs. E- .
l NOTE: These calculations avaf1-
. able from counting faci-
- lity on request. -
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- b. Failed fuel monitor b. Increase in I-131 concentration by t indicates Mechanical Clad 7pC1/m1 over a 30 minute period, or,
- Failure greater than 1% to 5%. 1-131 concentration is in the range
! or 0 1% equivalent fuel of 70pC1/ml to 350 pCi/ml verified by -
, failures within 30 minutes. increased EMF-48 readings and labora-i tory analysis. 1 l 4.2.4 Abnormal coolant tempera- Figure 2.1-1 Tech Specs exceeded AP/1/A/5500/05, AP/2/A/5500/05 =
- ture and/or pressure or and Core Subcooling Monitor less j abnormal fuel temperature than acceptable. (Below Curve)
) outside of Technical Spect- Verified as necessary by redundant i fication Limits. Instrumentation. (e.g, narrow and wide ,
i range pressure / temperature subcooling monitors) .
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ENCLOSURE 4.2 3 PAGE 2 0F 5 . ,
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Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document c
- 4. 2. 5 - Exceeding either primary / >1GPM' total P/S leaka0e EP/1/A/5000/02, EP/2/A/5000/02, ;
secondary leak rate >500 GPO from any S/G .EP/1/A/5000/04, EP/2/A/5000/04, J requiring shutdown by >10GPM Identified 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. ,
,(c 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, 1 related system to close, EP/1/A/5000/03, EP/2/A/5000/03 .
following reduction of
.appilcable pressure. (Prl-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 [:
loss of onsite AC power or blickout load sequencers ',
capability. actuated. . '
. 4.2.8 Loss of containment inte- Anyautomaticcontaihnentisolation AP/0/A/5500/24 ,
grity requiring shutdown by valve found to be open and inoperable Tech Specs (3/4.6.1). and unisolable or both air lock doors or penetration (s) on falla leak lock test inoperable, per Tec h Specs when con-tainment integrity required. .
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Loss of engineered safety AP/1/A/5500/19, AF/2/A/5500/19,
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4.2.9 ESF actuation system found inoperable feature or fire protection or Fire Suppression Water System AP/1/A/5500/21, AP/2/A/5500/21, i.
system function requiring found inoperable per Tech Specs. AP/1/A/5500/20, AP/2/A/5500/20, shutdown by Tech Specs Tech Specs 3/4.5, 3/4.7.10, (e.g., malfunction, personnel 3/4.7.11 :
error, or procedural inadequacy). {
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. ,' ENCLOSURE 4.2 ,
PAGE 3 0F 5 Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document - '
4.2.10 Fire within the plant Observation or fire detection alarm Station Directi'e v 2.11 # -
lasting more than 10 with confirmT5g observation of a
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minutes. fire lasting more than 10 minutes. '-
i 1 4.2.11 Indications or alarms on Loss of process or affluent radiation OP/0/A/6700/03, Tech Spacs 3/4.3 process or affluent para- monitoring system or Loss of all
, meters not functional in meteorological instrumentation onsite <; -
1 Control Room to an extent or Loss of all radio / telephone communi- i requiring plant shutdown citions capability offsite. j l or other significant loss . . ,
! of assessment or communica- ! !
tion gapability (e.g., all E meteorological instrumenta- '
tion, or radio networks).
4.2.12 Security threat or As notified by Security Force. Station Security Plan attempted entry or -
attempted sabotage.
- 4.2.13 Natural phenomenon being experienced or projected beyond usual levels.
a j a. Any earthquake felt (<.089H, <.0539 V), Annunciator Alarm, in plant or detected (AD-13) on station seismic in- '
strumentation. .
- b. 50 year flood or low As observed '
- water, hurricane surge, i seiche (lake tidal wave)
- c. Any tornado on site As observed
! d. Any hurricane Winds >73 aph/from National Weather RP/0/A/5700/06, RP/0/A/5700/07 -
Service information.
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PAGE 4 0F 5 .
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Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document ,, t I
4.2.14, '
Other ha'zards being ex- l
- perienced or projected.
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- a. Aircraft crash onsite As observed
, 'or unusual aircraft
, activity over facility. l-j b. Train derailment on As observed i site. '
, c. Near site or onsite As observed '
l 'xplosion.
e .
, d. Near site or onsite As observed RP/0/A/5700/08 taxic or flammable -
! gas release.
- Turbine rotating com-
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- e. Turbine trip and observation of AP/1/A/5500/23, AP/2/A/5500/23, f
ponent failure causing a turbine malfunction or failure. Af/1/A/5500/02, AP/2/A/5500/02, i rapid plant shutdown , RP/0/A/5700/09 !
i (Loss of Condenser j ; Heat Sink). ,
I 4.2.15 Other plant conditions As determined by the Shift Supervisor / As directed by plant conditions.
j exist that in the judge- Emergency Coordinator.
j ment pf the Shift Supervisor, j the Operations Outy Engineer, i the Superintendent of Opera-l tions, or the Station Manager j warrant increased awareness ,
I on the part of State and/or
! local offsite authorities or
! require plant shutdown under .
Tech Specs requirements and I j involve other than normal con- !
trolled shutdown (e.g., cool- I
- down rate exceeding Tech Specs , ,
limity, pipe cracking found v F.
I 1
, during operation).
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RP/0/A/5700/01 -
ENCLOSURE 4.2 PAGE 5 0F 5 Initiating conditions Emergency Action Level (EAL) Emergency Procedure / Document i
s.
4.2.16 Transp'or.tation of contami- As observed. ,
RP/0/A/5700/05 nated. injured individual from site to offsite hospital.
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4.2.17' Rapid depressurization of As observed and actuation of 4.2.1 AP/1/A/5500/06,AP/2/A/5500/06 ,
secondary side. and 4.2.6 above.
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.RP/0/A/5700/01 .-.
. 'V h 2 TELEPHONE LISTING 4.4.1 Operations Outy Engineer,(PA System) '
P&T Pager -
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4.4.2 Station Manager '
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-- u Home - - System Speed - '
Home - System Speed 1
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Superintendent of Operations :. u,f 4.4.3 Home - ,/ System Speed ,
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4.4.4 Superintendent o'f Technical Services '
Home j'~S'ystemSpeed .
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4.4.5 Projects & Licensing Engineer - .' i s
. Home
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4.4.6 Nuclear Production Duty Engineer .
System Speed -
P&T Pager
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4.4.7 NCStateWarningPo(nt,'Raleigh- _ j-SystemSpeed 4.4.8 Mecklenburg County Warning Point - Primary: . Ring Down Phone Back-up: .eSysten Speed Back-up: Emergency Radio, Code: ,
4.4.9. Lincoln County Warning Point - Primary: Rinn Down Phone Back-up: . -System Speed Back-up- Emergency Radio, Code: ,
4.4.10 Catawba County Warning Point - Primary:s Back-up: ', Rina Down .. - System PhoneSpeed Back-up: , E:itergency Radio, code: _
4.4.11 Iredell County Warning Point - Primary: Rina Down Phone
. Back-upi _... - System Speed lg' Back-up: Emergency Radio,. Code: _
4.4.12 Gaston County Warning Point - Primary: Rino Down Phone ,h Back-up: . . " System Speed Back-up: Emergenc9 Radio, Code: f 4.4.13 Cabarrus County Warning Point - Primary: Ring Down Phone ' '
Back-up: - ' System Spee, Back-up: Emergency Radio, Code: ,
NOTE
- 1. Radio Code will. activate all. county radio units. (
P&T Pager, Central'nivision (Charlctte Area)
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ENCLOSURE 4.4-
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PAGE 2 0F 2
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4.4.14 N.R.C. 0perition Center, Emergency Notification System (ENS phone) 4.4:15 N.R.C. Station [tepresentative (Bill Orders) '
Office - s ..
Home s . N System Speed
_ ., Onsite Pager P&T Pager . ..
For P&T Page from Central (MNS Area) -
\,x, 4.4.16 Construction Project Manager: Constructioi l Home'. ... (vstem Speed ..
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550 Mt. Holley - j System Speed ,
4.4.17 Station Health Physicist- ,
)' rm Home- istem Speed -
P&T Pager
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4.4.18 Station Safety Supervisor j Home - , -ipstem Speed -
.. a Superintendent of Maintenanca -
4.4.19- .23.-
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N4. 4. 20 Superintendent of Administration -
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4.4.21 - Radiation Protection Section Department of Human Resources '
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'N lastructions: RP/0/A/5700/0L ENCLCSURE 4.5 J _ A. For Sender: pggg i op 4
- 1. Complete Part I for the initial Waming Message.
- 2. Complete Parts I & !! for followuo me. sages. I i
4 j S. For Receiver:
- f. Record the date, time and ycur name in the area below.
i
- 2. ~ Authenticate this message by verifying the code word or by calling back to the facil! y. (See Part i .5) i Time: Date:
1 Message Peceived By: l
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I 1. This is: Mq9ts. ire Nuclear Sestion (insert narns of fac;iity) ,
- 2. My name is:
- 3. This messago (number _ ): ,
(a) Reports a real emergene/. (
(b) . Is an exercise mecsasc.
- 4. My telephone number /axensien is: [-
- 5. Me ap authentication:
f, Verify ec<:s wer:: or cM1 back to the factity)
- 6. The class of the emergency is: (a) Nctification of Unusual Event (b) Alen (c) Site Emergene/
(d) General Emergency
- 7. This classificWen of emerpncy was declared at: (a.m./p.m.) on - (da te).
3 The initiating event' causing :f'e emergency classification is:
h.
- 9. The emergency condition: (a) Does not invcive the release of radioactive materials from .(-
the plant. ,
(b) invch,es the cctential for a relew, but no re! casa is cccur-ing. l (c) Involves a re!ena of radicactive materfal.
.. RP/0/A/5700/01.
ENCLOSURE 4.5
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, ' , ~, . '
.PAGE 2 0F 14 '
'IO. We recommend the following p.adve action: ,
(a) No protective action is recommended at this time.
(b) People living in zenes 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 dcors and windows closed.
(e) Pregnant women and children in zones evacuate to the nearest shelter / reception center.
(f) Other recommendations: -
1t. 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)* ls an exercise message Signacure (Emergency Coordinacor) 4
- 13. RELAY THIS INFORMATION TO THE PERSONS INDICATED ON YOUR ALERT PROCEDURE FOR AN INCIDENT AT A NUCLEAR FACILITY. -
NOTE: Record che name, it t anWa g n ified on Page 4_ of 4.
PART.II
- 1. The type of actuel or projected release is: *
(a) Airbome >
(b) Waterbome (c) Surface spill (d) Other
- 2. The source and description of the ts!sess is:
j i 3. (a) Release bogen/will begin at a.mdp.m.; time since reactor trip is hours.
1 (b) The estimated duration of the release is hours.
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, RP/0/A/5700/01 ENCLOSURE 4.5
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- 4. Dose projection base deta:
, / 3, Radiological release: curies, or curies /sec.
Windspeed: mph Wind direction: From i .
Stability class: (A,8,C,D,E,F, or G) .
Releam height: Ft.
Dom conversion factor: R/hr/Cl/m3 (whole body)
R/hr/Cl/m3 (Child Thyroid)
Precipitation:
Temperature at the site: 'F '
- 5. Dose protections:
'Does Commitment
- Whole Body (Child Thyroid)
Distance Rem / hour -
P p' hour of inhalation Site boundary 2 miles 5 miles 10 miles ,
' Projected ineysted Dose 'n Rem
- Distance Whole Body Child Thyroid Site Soundary 2 miles 5 miles 10 miles
- 6. Field measurement of does rate or contamination (if aveilable):
- 7. Emergency accons u- 1. a; at the fenility include:
- 8. Onsite support needed from offaits orgentzstions:
- 9. Mant status:
(a) Reector is: not tripped / tripped (b) Plant is at: % power / hot shutdown / cold shutdown / cooling down (c) Prognosis is: stableilmproving/ degrading / unknown.
RP/0/A/5700/01 ENCLOSURE 4.5
- s. : .v, ... .s .
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. a . .. . pg .
4.' ' 0F 4' ' ' ' '
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- 10. I ropest, this message
~
') (a) Reports an actual emergency. _ ____
(b) is an exercise message. PART I and II APPROVED FOR RELEASE
- 11. Do you beve any questions? Signature (Emergency Coordinator) -~
- ,-END OF FOLLdW-UP MESSAGE *** '
NOTE: Record the name, tide, date, time, and woming 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) (title)
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(date) - (time)- (warning point) 9
- 4. ,
(name) (title)
(date) (time) (warning point) 5.
(name) (title)
(date) (time) (warning point) 6.
(name) (title)
(date) (time) (warning noint) 7.
(name) (title) .
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( (date) (time) (warning point) 3.
(name) (Cicle)
(date) (time) Form 34888 (6-82)
(W 3 Point) l
., .. . . . . .. .,7 . ..c , .
.RP/0/A/5700/01- h. .
ENCLOSURE 4.6 -
PAGF L '0F, 1
- j _.
J EMERGENCY PLAN MESSAGE FORMAT (Nuclear Station to Nuclear Production Duty Engineer),
- 1. This is at McGuire Nuclear Station.
(Nace and Title)
- 2. This is/is not a Ort 11. 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 cicae to the emergency prccedure description as possibler together with station parameters used t'o determine emergency status) r s .
- 4. Corrective Measures.Being Taken:
- 5. There Have/Have Not been any injuries to plant personnel.
- 6. Release of radicactivity: 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.
- . (Telephone Number) l
- 10. Additional Comments:
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.i Form 34731 (1041)
- (Formeriy SPD 1002 Il -
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DUKZ POWER CCMPANY (1) ID Not RP/0/A/5700/02 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD - 0 Iricorporated -
(2) STATION:Mecnten Nuclear station (3) PROCEDURE TITLE: Alert (4) PREPARED BY: DATE: 5/31/83 (5) REVIEWED BY: 6 DATE: [-2-73 :
Cross-Disciplinary Review By:_ N/R:
(6) TEMPORARY APPROVAL (IT NECESSARY):
By: (SRO) Date:
By: Date:
(7) APPROVED BYi Date: I/
//
3 (8) MISCELI.ANEQUS:
Reviewed / Approved By: Date:
Reviewed / Approved.By: Date:
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RP/0/X/5700/02
.. .. . .. .. . PAGE 1.0F 5 .
,/ '
DUKE POWER COMPANY McGUIRE NUCLEAR STATION ALERT 1.0 Synetons 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 Insediate 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 S'hift Supervisor / Emergency Coordinator shall assure that i the appropriate emergency condition (Notificatice of Unusual Event, Alert, Site Area Emergency, or General Emergency) is declared by evaluating the actual plant condition with Enclosure 4.1, Emerge 2cy Classification Guide Flowchart and Enclosure 4.2, fist of Initiating Conditions, Emergency Action Levels, and Associated Emergency Procedure / Document.
NOTE l The Shift Supervisor shall assume the function of the Emergency Coordinator until the arrival of the Station Manager or his desigaee at which time the Station Manager or his designee assumes the responsibility of the Emergency Coordinator.
I l / 3.2 The Emergency Coordinator shall assure that all actions t
. - _ _ . . _ _ . _ , _ , . . _ _ _ _. __---_ ___ _____ ~_ -
'I -
.1 - -
RP/0/A/5700/02-PAGE 2 0F -
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required by the initiating I'mergency Procedure (s) will be performed and that all actions necessary for the protection of 1 j
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 necessary, refer to Station Directive 3.8.1.
/- 3'.3 The Emergency Coordinator shall' assure prompt' (within about 15 '
sinutes 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), -- '
l 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 to be provided to State / County Warning Points.
I 3.4 The Emergency Coordinator in direct contact with the Technical 5
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. . - - - - t RP/0/A/5700/02 .
. PAE. 3 0F 5 .
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Support Center and the Crisis Management. Center will assess and respond to the emergency by:
I r-3.4.1 Dispatching onsite sonitoring teams with associated ceamunications 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 authorities and, if any releases are occuring, dose estimates for actual: releases.
NOTE In the event a release or potential release of radioactive materials is a threat to plant personnel or members of the general public, ,
the Emergency Coordinator shall utilized the
' Operator Aid Computer (OAC) "NUCIZAR-23" program to assess the offsite consequences.
In the event the (OAC) is not operational the Emergency Coordinator shall request Health Physics personnel to evaluate the consequ'ences utilizing the appropriat'e 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 rect ====adations 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 Reco-dation Flow Chart) as directed by the state, in accordance with the North Carolina Emergency Response Plan. If evaluation indicates that a pctential for or
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RP/0/A/5700/02 . - -
PAGE~4 0F 5 '
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an actual release of radioactive matarials will result in a projected dose (REM) to the population of: (EPA Protective
, Action Guidelines).
t 3.5.1 Whole body <1, thyroid <5, NO protective action is l required. Monitor environmental radiation levels to !
~
verify.
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3.5.2 Wole 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 t to affected areas.
NOTE If this is the projected dose evaluate Site Area Emergency and General Emergency Initiating Conditions and Emergency Action -
I,evels .
3.5.3. Whole body 5 and above, thyroid 25 and above, recommend i 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 Cris'is Management Center, will assess the I emergency condition and determine the need to remain in an Alert
- -. - . - - - . - . , - . .. , . . . - . . . - - - - - - . . . . ~ , . . - - .
-RP/0/A/5700/02
. . PAGE 5,OF 5 . ..
,m
/ ;
,/ Status, escalate to a more severe class, reduce the emergency class or close out the emergency.
l l
/ 3.7 The Station Manager or his designee will close out the 4 Emergency with a verbal summary to County and State authorities notified in Step 3.3, followed by a written summary within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
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 4.4 Telephone Listing
- 4.5 Warning Message: Nuclear Facility to State / Local Government 4.6 Emergency Plan Message Format 4.7 hrotective Action Recommendation Flow Chart e
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RP/0/A/5700/02 L .
ENCLOSURE 4.1
- PACE 1 OF -1 i
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- y as EMERGENCY Cl ASSIFICATION guide FLOWC lART -- -- -- * :
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RP/0/A/5700/02 -
ENCLOSURE 4.2 PAGE 1 0F 5 LIST OF INITIATING CONDITIONS, EMERGENCY ACTION LEVELS, AND ASSOCIATED EMERGENCY PROCEDURE / DOCUMENT Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document i 4.2.1 Severe loss of fuel a. Very high coolant activity
- cladding, Mechanical sample indicating an increase of '
Clad failure. 74 C1/mi in 30 minutes or 350 to 1,750pC1/m1 total'I-131' Coolant ,
Activity.
b Failed fuel monitor (EMF-48) or Tech Specs 3/4.6.7 ..
lab analysis indicates increase ~
greater than 1% fuel failures .
within 30 minutes or 5% to 25% ,
total fuel failure.
4.2.2 . Rapid gross failure Pressurizer, low pressure alarm and EP/1/A/5000/04, EP/2/A/5000/04, l of one Steam Generator AP/1/A/5500/07, AP/2/A/5500/07 tube with loss of off- reactor trip @and, level alarm pressurizer a - pressurizer low low site power. pressure safety injection signal and undervoltage alarm on 7KV Eiiie,s. EMF 32, 33, and 34 ATarm(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- '
I surizer and EMF indicators.
- h. Steam generator' level in-creasing in one or more
- generator (s) and falling in j the others/due to reactor trip.
l Y
- - - - - - - - - - - - - ~ '
_ 2 . _ t um 2 c__ m - .
. i I '
RP/0/A/5700/02 -
ENCLOSURE 4.2 .
PAGE 2 0F 5 .
Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document ,
! 4.2.4 Steam line break with Greater than 10 gps, rapidly de . EP/1/A/5000/04, EP/2/A/5000/04, l significant primary to creasing reactor coolant Tavg, EP/1/A/5000/03, EP/2/A/5000/03 -
1 secondary icak rate. pressurizer pressure and level aM. .
i 1. Steam line differential pressure safety injection -
, . signal and increased con-tainment building pressure /
if break is in containment. -
) -
! 2. High steam flow and to Lo . . I i Tavg or Low steam pressure ~
safety injection signal for rupture downstream of MSIV's.
l i 4.2.5 Primary coolant leak Leak >50gpm 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
- 4.2.6 High radiation levels Increase by a factor of 1,000 in llP/0/2/1009/05 or high airborne con- radiation monitor reading within -
I tamination which in- the station.
i dicates a severe de-l gradation in the control of radioactive materials. '
i 4.2.7 Loss of offsite power ag Undervoltage alarm on 7KV buses, EP/1/A/5000/09, EP/2/A/5000/09 ,
i loss of all onsite AC and blackout load sequencers power for up to 15 minutes. actuated.
(See Site Area Emergency RP/0/A/5700/03, for ex-
- tended loss).
J
] 4.2.8 Loss of all onsite DC DC bus undervoltage alarms nn aH Tech Spect 3/4.8.2.3, '
power, buses. Tech Specs 3/4.8.2.4 4
j .
j ..
-. _ . .....,.c . . . . - . . . . .
.: p.
. ..)~
RP/0/A/5700/02 's #
ENCLOSURE 4.2 PAGE 3 0F 5 ,_
Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document 4.2.9 Coolant pump seizure Reactor coolant pump auto trip AP/1/A/5500/04, AP/2/A/5500/04, leadipg to fuel failure. alarm', and reactor trip on low AP/1/A/5500/08, AP/2/A/5500/08, coolant l ow, and fajied fuel .OP/0/A/6150/14, AP/i/A/5500/05 . l monitor alarm EHF48. AP/2/A/5500/05 l 4.2.10 Complete loss of func- RHR not functional and inability AP/1/A/5500)17,AP/2/A/5500/17, tions needed for plant to . sustain natural or. forced cir- OP/1/A/6100/04,OP/2/A/6100/04' ;
cold shutdown. culation. ,
~
4.2.11 Failure of the reactor Reactor remains critical after AP/0/A/5500/34
~
protection system to all attempts to trip reactor -
initiate and complete have been completed.
a scram which brings I
! the reactor subcritical. , ,
4.2.12 Fuel. damage accident Obser.vation of damage to spent AP/1/A/5500/25, AP/2/A/5500/25 l with r'elease of radio- fuel assembly, and y activity to containment i or fuel handling building. 1. 1 EMF-16 or 17 alarm or -
l 2 EMF-3 or 4 alare.
l . 2. EMF-38, 39, 40, or 42 .
alarm.
4.2.13 Fire potentially affecting Observation of a fire that could Station Directive 2.11 Series, I safety systems, affect safety systems. Tech Specs 3/4.5 4.2.14 Most or all alarms (annun- As observed. OP/0/A/6350/01A clators) lost.
mm 4 .
. .a.....n.-=_..-
i s /
i RP/0/A/5700/02 k - ' -
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 offs,cale HP/0/8/1009/05 .
effluents >10 times
! Tech Specs instantaneous High Range 1 x 10 4cpm limits (an instantaneous 6 rate Alch, if continued For EMF 36 - Low Range 2 y 10 cpm .
over 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, would re- .
sult in about ler at the High Range 5 x 102 cp, site boundary under average ,'
meteorological conditions or whenever effluent mont-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 Severp natural phenomena RP/0/A/5700/06, RP/0/A/5700/07 being experienced er projected:
- a. Earthquake greater >0.089H, >.053gV, Annunciator Alare,
- than Operational (AO-13).
j 8 asis Earthquake Levels l
I b. Flood, low water, hur- As observed.
1 ricane surge, seiche i near design levels.
j (Lake tidal wave)
- c. Any tornado striking As observed.
j facility.
- d. Hurricane winds near As observed (95 mph)/from National ,
design basis level. Weather Service information.
4.2.18 Other hazards being ex- RP/0/A/5700/08, RP/0/A/5700/09, .
- perienced or projected. AP/1/A/5500/23 AP/2/A/5500/23 1
4
- a. Aircraft crash on As observed.
~
] facility. '
b)*
RP/0/A/5700/02 ENCLOSURE 4.2 -
PAGE 5 0F 5 -
i 4
InitiatingCondjtions Emergency Action Level (EAL) Emergency Procedure / Document t
, b. Missile impacts from As observed. .
whatever source on '
facility.
l .
- c. Know explosion damage As. observed.
to facility affecting 1
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.
l 4.2.19 Other plant conditions As determined by Shift Supervisor / As dictated by Plant Conditions. .
1 exist that in the . judge- Emergency Coordinator.
L ment of the Shift Super- ,
1 visor, the Operations -
Duty Engineer, the
' l Superintendent of Opera-tions, or the Plant -
Manager warrant pre-cautionary activation i of the Technical Support i Center and near site
! Crists' Management Center. '
i 4.2.20 Evacuation of control As determined by Shift Sopervisor/ AP/1/A/5500/17,AP/2/A/5500/17, '
l room anticipated or Emergency Coordinator. . OP/1/A/6100/04,OP/2/A/6100/04 j required with control '
of' shutdown systems i
established from local station.
1 1 .
e - -
- I .
RP/0/A/5700/02 .
l s s. . ., . . ENCLOSURE. 4.3 l
/9
! 1 PAGE 1 0F 1 q NOTIFICATION / ACTIVATION ALERT Notify / Activate the folicwing 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 Encineer Station Manaaer Superintendent of Operations -
Superintendent of Technical Services Projects and Licensing Engineer Station Health Physicist North Carolina State Warning Point
/ Mecklenburo County Warning Point Lincoln Coun,ty Warnino Point Catawba Ccunty Warnino Point Iredell County Warning Point Gaston County Warning Point Cabarrus County Warnino Point N.R.C. via ENS (Red Phone) (Station Directive 2.8.1 and 3.1.4) l-N.R.C'. Stati'n~ o Representative Construction Project Manager Superintendent of Maintenance Superintendent of Administration Activate T.S.C. (Station Directiva 3.8.2)
Activate 0.S.C. (Station Directive 3.8.2)
Activate C.M.C. (Enclosure 4.6) 1 l
- .. RP/0/A/5700/02' s
j3N OSURE 4 .
\
? .
'< ./ TELEPHONE LISTING 4.4.1 Operations Duty Engineer _(PA System)
P&T Pager - ,>-
4.4.2 Station Manager Home -
f Home - _
fSysteiSpeed-System Speed -
j _
4.4.3 Superintendent of Ooerations'- - /
Home - ? System Speed 8
( 4.4.4 Superintendent of Technical Services -
~
Home 3 System Speeo 4.4.5 ,
Projects and Licensing Engineer Home - ] - System apeed
(
4.4.6 Station Health Physicist'- N-Home - /- System Speed -
P&T Pager l
4.4.7 NC State Warning Point, Raleigh - _
l- System Speed 4.4.8 Mecklenburg County Warning Poir.t - Primary: Rino Ocwn Phone Back-up: - -
' System Speed Back up: Emergency-Radio, Code:
4.4.9 Lincoln County Warning Point - Primary: Rino Ocwn Phone Back up: __ - Systera Speed -
Back up: Emergency Radio, Code:
4.4.10 Catawba County Warning Point - Primary: Ring Ocun Phone
. Back-up: : 1 - System Speed Back-up: Emergency Radio, Ccde. ,
4.4.11 Iredell County Warning Point - Primary: Ring Down Phone Back-up: '~" - System Speed
- - Back-up: Emergency Radio, Code:
4.4.12 Gaston County Warning Point - Primarj: Ring Ocwn Phone 7 - System Speed Back-up:
Back-up: Emergency Radio, Code: ,
4.4.13 Cabarrus County Warning Point - Primar/: Ring Down Phone
- Back-up: . _. O - System Speed Back-up: Emergency Radio,' Code:
MW l
- 1. Radio Code ,w F activate all county radio units. y
- 2. P&T Pager, Central Division (Charlotte Area) .
3 -
. Dial - ;- - -
j 4
- +. . RP/0/A/5700/02 .
- ENCLOSURE 4.4 ~
0F- 2
. PAGE 2 TELEPHONE LIST ,
- 1
- 4.4.14 N.R.C. Operation Center, Emergency Notification System (ENS Phone) . !
I j 4.4.15 N.R.C. Station Representative (Bill Orders) .
N
~
Office
! Home - ,4 System Speed
! P&T Pager , Onsite Pager -
For P&T Page from Central (MNS Area) 4.4.16 Construction Project Manager Construction __.. Ext.
Home : .. /_ System Speed -
)
550, Mt. Holley . ,
7- System Speea 4.4.17 Superintendent of Maintenance -
l Home
]SystemSpeed-
's
, 4.4.18' Superintendent of Administration \ \ .
Home - ' System Speed -
'4.4.19 Nuclear Production Outy Engineer - 7
- System Speed - \- -
P&T Pager _
4.4.20- Radiation Protection Section. Department of Human Resources-
,- System Speed - - '
t S
. 6 02 I
y -- p
$ M h?$} % L h h$ .
i O, Instructions: , RP/0/A/5700/02 i INCI.0SURE 4.5 A. For Sender: 4 PAGE 1 0F
- 1. Comp!:t:: Part I for the Initial Warning Message, f 2. Comp!ste Parts I & il for followup messages.
B. For Receiver:
- 1. Reccrd the date, time and your name in the aret below.
i
- 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:
my - ~ - -. ., - , m n. -
- , - - . - -.c.
.gQTjfNj'$lk, ., --h hde$m'yydfA$*WM:.,,gkg.
{ 7/[. X awg;w{y,[d5W%".p..a,;
dta b ..se_.u n$yrg wwa{,s .a ; k s ; v a %- m w - m- .~ .-M
- 1. This is: w-c,s - 'r... 'o ,- e-,
- tinurt n3me or rac:iirv)
- 2. My name is:
- 3. This messay (number __.):
(a) Recorts a rest emergener.
-(b) is an exerciso message. .
-, ' s 4 My telephene number /exension is: _ f
- 5. Mc= cgs authenticaricn:
(Verify code werd er cail back to te faci!!e/)
- 6. The class of the emergency is:_ (a) Nctification of Unusual Event (b) Alert I (c) Site Emergene/
(d) General Emergency i 7. This classification of emergen%y was declared at:
(a.m./p.m.) on (date).
- 8. The initiating event causing the emerge.q classificatica is:
l l
- 9. The emergency cendition: (a) Oces not invcive the release of radioactive materials frcm
. the plant. . . - -
l _
-(b) Invohrs the ;ctmtial for a re! casa, but no release is cccurMng.
InvoNes a re!es:e of rcdicactive material.
i _(c)
- i RP/0/A/5700/02
! ENCLOSURE 4.!
,PAGE 2 0F 4-
.10. We recommend,the following protsenve action:. .
_s - -
No protective action is recommended at this time.
(a) ,
(b) People twino in zones remain indoors with the doors and .;.icows closed.
People in zones (c) 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 recommendathms:
- 11. There will be: '
(a) A followup message ,
(b) No further communications
- 12. I repeat, this message: PART I APPROVED FOR RFT.EARE (a) Reports an actual emergency Signature (Emergency Coordinacor)
(b) Itan exercise mesunge
- 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, citle, date time and Warning Point notified on Paste 4 of 4.
l
%RTli
- 1. The type of actual or projected release is:
(a) Airborne (b) Waterborne (c) Surface so:ll (d) Other
- 2. The source and description of the reieses is:
i
- 3. (a) Release bogen/will begin at a.mdp.m.; time since reactor trip is hours.
Ib) The estimetod duration of the release is. hours. ,
f e
, , , , , . -- - , . , - - - - - - - , - - , , , - . . , _ _ . . , - - - - - , - - , - - , - - - - , - - - - , , - ------,.-,,-.,--,,,----,-,.,-..nn~,-- . - , , - , - , - - - , , , - , - , - . , ,,,n--,a
=! RP/0/A/5700/03 ENCLOSURE 4.5 PAGE- 3 0F 4 Radiological release: curies, or
( curies /sec.
Windspeed: mph
!: Wind direction: From
- 4 i Stability class: (A,8,C,0,E,F, or G) -- .__
Release height: Ft. --
Dose commrsion factor: 'R/hr/Ci/m3 (whole body)
R/hr/CI/m3 (Child Thyroid)
Precipitation:
Temperature at the site: 'F
- 5. Does projections:
' Dose Commitment
- _
Whole Body (Child Thyroid)
Distance Rem / hour Rem / hour of inhalation Site boundary 1
2 miles 5 miles 10 miles l
^^ 4 J Intsyntad Dose in Rem
- Distertce Whole Body Child Thyroid Site Boundary 2 mile 5 miles 10 miles -
- 6. Field measurement of does rets or contamination (if evailable):
- 7. Energency actione underway at the facility include:
- 8. Onsite support needed from offsite organiastions:
~
- 9. Plant status:
j (a) Reactor is: not tripped / tripped , ,
(b) Plant is at: % power / hot shutdown / cold shutdown / cooling down (c) Prognosis is: stable / improving / degrading / unknown.
. . - . - . - . - . _ _ _ . . ~ _ - - . . _ . . - . . _ , - _ . , . - . - . _ . - . - _ - _ _ . .
I l
~ ~
l RP/0/A/5I00/02 ENCLOSURE 4.5 )
. 10.' l'repoet, this message: . , . PAGE 4 0F '4 . 1
' Reports an actual emergency. .
- '] (a)
PART I and II APPROVED FOR MmE- ---
(b) is an exercise message.
- 11. Do you have any questions? Si8 nature (Emergency Coordinacor)
?
..,<. _ .Q :;c DJ"* ENII OF FOLLOW-UP MESSAGE **N'~ 7._g!GC -.M.
NOTE: Record the name, title, date, time, and warning point notified. (Senders)
Record the name titie, date, time, and persons notified per alert procedure. (Receivers) 1.
(name) (title)
[date) (time) (warning point) 2.
(name) (title)
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.-. RP/0/A/5700/02 ENCLOSURE 4.6
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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 _ .
- 3. Initiating Condition:- '(Give as close to the emergency procedure a=:eription 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.
Yes ' 'No' 'I
- 7. NRC , 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.
(Telephone Number)
- 10. Additional Comments:
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Form 34731 (1041)
(Formerly SPD-1002-1) - - -- -
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DUEE. POWER COMPANY (1) ID No: RP/0/A/5700/03 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD 0 Incorporated (2) STATION: McGuire Nuclear Station ,
(3) PROCEDURE TITLE:_ Site Area. Emergency
\d- in e T0'7h .
(4) PREPARED BY: M._S. Glover _ ._ DATE: 5/31/83 (5) REVIEWED BY: -
DATE: b - 2 ~I3 Cross-Disciplinary Review By: N/R: _
(6) TEMPORARY APPROVAI. (IF NECESSART):
By: -(SRO) Date:
Hy: Dates (7) APPROVED NY: 'Date: I b (8) MISCELLANEDUS:
i / /
Reviewed / Approved By: Date:
Reviewed / Approved By: Date:
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RP/0/A/5700/03
.. ,,PAGE 1.OF. S~ ~
i ' .l DUKE POWER COMPANY 1 McGUIRE NUCLEAR STATION SITE AREA EMERGENCY 4
1.0 Symptoms 1.1 Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public.
2.0 Immediate 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 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
~ 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.
~
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3.2 ' The' Eme'rgency Coordinatior' s'hal'l' assure that all actions -
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RP/0/A/5700/03~ >
PAGE 2 0F 5
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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 The Emergency Coordinator shall consider the need for site assembly / accountability and/or evacuation of all non-essential onsite per_s_onnel. See Station Directive 3.8.1.
I
/ 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 genera'l public in a 2 mile radius area around McGuire (Zones A, 3, C, and qi) to go indoorn an~d'aoditor r ' -
Emergency Broadcast Stations for continued updates on the situation.
/ 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 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 $e'in'accordance Yith Enclosure'4.6'
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RP/0/A/5700/03' -
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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 Stata/ Local Government, for information to be provided t'o 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 tran==4ssion.
3.5.3 Providing release and dose projections based on available plant condition information and foreseeable contingencies to offsite'aatharities.
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 offsite consequences.
In thd event 'the' '(OAC) is not operational the '
Emergency Coordinator shall request Health Physics personnel to evaluate the o
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._.- . _. _ a _. _ ._ _ _ _ .. ._. _
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RP/0/A/5700/03 ' - - ' : '-
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/ 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) d i 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 ther 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 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.
3.6.3 Whole body 5 and above, thyroid 25 and above, recommend
(
l mandatory evacuation of populations in the affected areas. Monitor environmental radiation levels and adjust area for mandatory evacuation based on these levels.
Control access to affected areas.
NOTE See Enclosure 4.4, Telephone Listing for notification.
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s / 3.7 The Emergency Coordinator in coordination with the Recovery
, Manager, at the Crisis Management Center, will:
4 3.7.1 Provide a dedicated individual for plant status updates to offsite authorities and periodic press briefings.
3.7.2 Make available senior technical and management staff onsita 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 offsite authorities at the Crisis Management Center er by phone if necessary, fellowed by written sumeary within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
l 4.0 Enclosures l
4.1 Emergency Classification Guide Flowchart 4.2 List o'f 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 t.ction Recommendation Flow Chart
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ENCLOSURE 4.1 '
6
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RP/0/A/5700/03 ENCLOSURE 4.2 - :
PAGE 1 0F 6 _
! i LIS1 0F INITIATING CONDITIONS, EMERGENCY ACTION LEVELS, AND ASSOCIATED EMERGENCY PROCEDURE / DOCUMENT +
Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document g 4.2.1 Known' loss of coolant Pressurizer low pressure reactor trip EP/1/A/5000/02, EP/2/A/5000/02 '
accident greater than and pressurizer low pressure safety l makeup pump capacity. Tiijection signal and high containment ,
- y buildingpressure7NSP5040,5050, .
5060, 5070) building sr.,4Tand high containment Tevel,'(NIPS 260, 5270) '
and high containment. humidity, i
i TN5P5400,5410) and EMF 38, 39, and 40 alare. ,
4.2.2 Degraded core with pos- Inadeo'uate Core Coolina: AP/1/A/5500/05, AP/2/A/5500/05 sible' loss of coolable 5 centrally located theraccouples indicate l geometry (indicators core exit temperature greater than 1200*F.
should include instru- For Mechanical Clad failure:
mentation to detect Greater than 25% fallad fuel indicated
, inadequate core cooling, by greater than 1,750pC1/m1 I-131 con-
! coolant activity and/or centration. i containment radioactivity for Severe Fuel Over Temperature:
- levels). From 1% to-10% failed fuel indicated <
l by 1,300 to 13,000pci/m1 1-131 concentration.
! For Fuel Melt: . ,
From .5% to 5% failed fuel indicated j by 1,180 to 11,800pC1/m1 1-131 .
t j
concentration.
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n i 4.2.3 Rapid. failure of steam Pressurizer low presdure alarm and EP/1/A/5000/04, EP/2/A/5000/04
] generator tubes with loss reactor trip, and pressurizer low AP/1/A/5500/07, AP/2/A/5500/07
- l of offsite power (e.g., level alarm, and EMF 32, 33, and 34 i several hundred gpa pri- alarm, and undervoltage alarms on mary to secondary leak
! 7KV buses, and steami generator water s
) -
rate), level rapidly increasing in one or
! more steam generators falling in the '
l others, a_nd n pressurizer level rapidly j .
decreasing, (NCPS151, 5160, 5172)
- and possible lifting of steam genera-1 tor PRV's and/pr safety valves.
J l
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_ . _a s
(.w' .
. RP/0/A/5700/03 ENCLOSURE 4.2 '
.PAGE 2 GF 6 , ,
Initiating Conditions Emergency Action Level (EAL) Emergency Pracedure/ Document
. s . ,
! 4.2.4 Steam line break with Rapidly decreasing reactor coolant EP/1/A/5000/03,EP/2/A/5000/03 .
I greater than 50gpa pri- Ta~vg, pressurizer pressure ar.' level. -
i mary to secondary leakage Steam line differential pressure 1 I and indication of fuel safety injection signal, ag High .
i damage. containment building pressure, if '
l -
steamline break is in containment ,
(NSP5040, 5050, 5060, 5070) and .
EMF SIA and/or B alare, or high -
steam flow and Lo Lo Tave or low steam pressure safety injection j , ,
- , signal, and EMF 48 alarm.
1
- 4.2.5 Loss of offsite power a_nd n Undervoltage alares on 7KV buses. AP/1/A/550d/07, AP/2/A/5500/07 4 loss of onsite AC power ,
l for more than 15 minutes. .
l t I 4.2.6 Loss of all vital onsite Blackout load sequencers actuated. Tech Specs 3/8.2.3, 3/8.2.4 '
! DC power for more than 15 DC bus undervoltage all buses and .
l minates. indications as in 4.2.5 above. I i 4.2.7 Complete loss of any Inability to estab11sh charging pump OP/1/A/6100/04,OP/2/A/6100/04, ,
! function needed for plant injection, and Inability to establish AP/1/A/5500/17, AP/2/A/5500/17 '
i hot shutdown. emergency feEdwater flow, or Inability I to establish service water 710w, and -
(
! Inability to estab11sh component i cooling water flow. . .
4.2.8 Transient requiring opera- Reactor remains critical atter all EP/1/A/5000/01,EP/2IA/5000/01,
, tion of shutdown sy:.tems attempts to trip reactor ha.ve been AP/0/A/5500/34
{ with failure to scram completed.
j (continued power genera-
- tion but no core damage -
immediately evident). ,
}
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( ) i 1 RP/0/A/5700/03 'F n -
ENCLOSURE 4.2
- PAGE 3 OF 6 TalETating Conditions Emergency Action Level (EAL) '
Emergency Procedure / Document ,
4.2.9 Major damage to spent Ob'servation of major' damage to one AP/1/A/5500/25, AP/2/A/5500/25 .
fuel in containment or or more spent fuel assembities, 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 EMF -38, .
6
- . damages fuel or water 39, 40 or 42 alarms. '
loss below fuel level).
~
. 4.2.10- Fire compromising the Observation of a major fire Tech Specs 3/4.5, ,
function of safety that defeats redundant safety Station Directive 2.11 Series
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systems. system or function.
! 4.2.11' Most or all alarm:. As' determined by the Shift Supervisor / OP/0/A/6350/01A
! (annunciators) lost and Emergency Coordinator.
plantTtransient initiated '
i or ir. progress.
) 4.2.12 Airborne radiological for EMF 35 Low Range, offscale HP/0/8/1009/05, HP/0/8/1009/09
.; effluent monitors detect High Range !! x 10 3cpm. >
j levels corresponding to i
greater than 50 mr/hr (See Note 1)b For EMF 36 Low Range 3 x lD cpm 1
for 1/2 hour o_t greater High Range 7 x 10 3cpm .
, than 500 nr/hr W.8. for (See Nota 1) i two minutes (or five times
{ these. levels to the thy- For EMF 37 Change of 143 com/ minute -
! rold).at the site boundary for 30 minutes or a .
for adverse meteorology change of 1030 cpa/ minute c TSeeNote2). for 2 minutes (See Note 1).
NOTE 1: These values are worst case
- calculations and may not reflect more l favorable weather conditions.
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RP/0/A/5700/03 M -
ENCLOSURE 4.2 PAGE 4 0F 6 .
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Initiatjng Conditions Emergency Action Level (EAL) Emergency Procedure / Document NOTE 2: These dose rates are projected ? .
j
- , based on other plant parameters (e.g. ,
radiation level in containment with leak' rate appropriate for existing contain- f.
. ment pressure) or are measured in the environs. (EPA Protective Action Guide- '
lines are projected'to be exceeded out- '
side the site boundary).
~
j 4.2.13 Imminent loss of phy- Physical attack on the plant involving Station Security Plan '-
. sical control of plant. imminent occupar y of control room and ' *
- auxiliary shutdown panels. .
j .
4.2.14 Severe natural pheno-l PP/0/A/5700/06, RP/0/A/5700/07 ':
i mena being experienced or projected with plant -
>- P not in cold shutdown. !
g.
4.2.1 4 1 l
, Earthquake greater than (> 15gH, >.lgV) as determined by moni- '
- SSE (Safe Shutdown Earth- toring seismic instrumentation and quake) levels. recording devices. (SMP-1) 4.2.14.2 '
l Flood, low water, hurri- As det' ermined by Shift Supervisor /
cane surge, seiche greater Emergency Coordinator.
3 than design levels (lake '
i tidal' waves) or failure '
of protection of vital '
equipment at lower levels.
) 4.2.14.3 '
Sustained winds or torna- (>95 mph) as observed or documented i does in excess of design b'f the National Weather Service
- levels.*
Information.
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RP/0/A/5700/03
..s EKOLOSbRE 4.2 ,
PAGE 5 0F 6
- Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document [
1 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 Aircraft crash affecting Aircraft crash causing damage or '
i vital.. structures by in-fire to: Containment Building.
- pact or fire. Control Room, Auxiliary Building, ' '
Fuel Building, or intake Structure.
4.2.15.2 6 Severe damage to safe Loss of functions needed for hot T.
. shutdown equipment from shutdown as in 4.2.7.
l missiles or explosion. '
4.2.15.3 Entry of uncontrolled Entry of uncontrolled or toxic or .,
flammable gases into flammable gases into; Control Room. -
vital / areas. Entry of Cable Spreading Room, Containment uncontrolled toxic Building, Switchgear Room, Safe <
l gases into vital areas Shutdown Panels or Diesel Rooms. ..
where lack of access to . 7' the area constitutes a '
I safety problem. -
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. . . . ,..__m_.
RP/0/A/5700/03 k i 4 l ENCLOSURE 4.2 .-
PAGE 6 0F 6
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Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document
- .: s ..
- 4. 2.16 - Other plant conditions As determined by Shift Supervisor / As dictated by Plant Conditions. s v '
exist that in the judge- Emergency Coordinator. ,
ment of the Shift Super-visor, the Operations .
Duty Engineer, the Super- -
Intendent of Operations, or th) Plant Manager war- -
i rant activation of emer- ~
gency centers and moni- - .
toring. teams and a . .
precautionary public notification to the public near the site.
}
'; 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 ;
i 15 minutes.
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~. . . . ENCLOSURE 4.3 .. 1
/1 T PAGE 1 0F 1 I
)
NOTIFICATION / 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) l NOTIFY / ACTIVATE NOTIFICATION COMPLETE-INITIAL Shift Supervisor Operations Duty Encineer Station Manaaer Superintendent of Operations Superintendent of Technical Services Projects and Licensino Encineer Station Health Physicist Forth Carolina Stata'Warnina Point ~
Mecklenbura County Warning Point Lincoln County Warnina Point Catawba County Warning Point l
Iredell County Warnina Point Gaston County Warnina-Point Cabarrus County Warnina Point South Carolina State Warnino Point N.R.C. v'ia ENS (Red Phone) (Station Directive 2.8.1'and 3.1.4)
' N.R.C. Stiation Representati' ve. '"
Superintendent of Maintenance Superintendent of Administration
( Construction Project Manaaer Activate T.S.C. (Station Ofrective 3.8.2)
Activate 0.S.C. -(Station Directive 3.E,.2)
Activate C.M.C. (Enclosure 4.6)
, . . . i ...-
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. r- - , , .RP/0/A/5700/03 - ,
ENCLOSURE 4.4
- PAGE~ 1 0F 2
,/']
TELEPHONE LISTING 4.4.1 Operations Outy Engineer (PA System)
P&T Pager - ~ ' ' ~ j -
4.4.2 Station Manager - ,
! System Speed - \
Home - 1 Home - - System Speed - )
4.4.3 Superintendent of Operations -
Home -
1)-
~~7 System Speed -
4.4.4 Sverintendent of Technical Services , _
Home - _
l > System Speed -
4.4.5 Projects and Licensing Engineer -
Home- ~ > ' System Speed
.7 4.4.6 Station Health Physicist ~
flome - /- System Speed -
P&T Pager ,/
i
. \
4.4.7 NC State Warning Point, Raleigh - !_ System Speed -
4.4.8 Hecklenburg County Warning Point - Primary: Ring Down Phone '
Back-up: . - System Speed Back-up: Emergency Radio, Code: ,
4.4.9 Lincoln County Warning Point.- Primary: Ring Down"Phone --
Back-up: -
System Speed -
Back-up: Emergency Radio, Code:
4.4.10 Catawba County Warning Point - Primary: Ring Ocwn Phone
Back-up: ' Systea Speec' Ecck-up: Emergency Radio, Code: ,
4.4.11 Iredell County Warning Point - Primary: Rino 0'own Phone Back-up: '.- System Speed Back-up: Emergency Radio, Code: ,
._ 4.4.12 Gaston County Warning Point - Primary: Rinq Down Phone Back-up: _
~ ? System Speed Back-up: Emergency nadio, Code: ,
4.4.13 Cabarrus County Warning Point - Primary: Ring Down Phone Back-up: 1-782-2123 - System Speed Back-up: Emergency Radio, Code: ,'
NOTE
- 1. - Radio. Code 3 fl activate
... all county radio un.its' . . .
a
- 2. P&T Pager, Central Division (Charlotte Area)
Dial - ,3 -
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>. .- . -RP/0/A/5700/03 - --
! ENCLOSURE 4.4
- j. ,-s
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PAGE 2' 0F 2__- .
l TELEPHONE LIST i
~ --- - - ._
l 4.4.14 SC State Warning Point -
)' '
4.4.15 N.R.C. Operation Center, Emergency Nctification System (ENS Phone) 4.4.16 N.R.C. Station Representative (Bill Orders) '
Office - -
._ Home - -- '- System Speed -
I.
P&T Pager . ..,'Onsite Pager - . . -
N '
For P&T Page from Ceritral (MNS Area) -
. - - '/
4.4.17 Construction Project Managar Construction ,f" Ext.
Home : .' ~ T 3vstem Speed '
550, Mt. Holley . - System Speed - _ ,
4.4.18 Superintendent of Maintenance 7 Home .
j - System Speed -
4.4.19 ' Superintendent of Administration ,
Home'- . System Speed -
4.4.20 Nuclear Production Duty Engineer - System Speed ~~
P&T Pager _ .
4.4.21 Radiation Protection Section, Department of Human Resourcas-
~~
. System Speed -
F e
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I h kIk h2tlIMA khth h h h ,
- i
) Instructions: RP/0/A/5700/03 ENCL 0stras 4.5
. A. For Sender:
PACE 1 0F 4 .
- 1. Complete Part I for the initial Warning Message.
- 2. Complete Parts I & 11 for followup mecsag:.s S. 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:
e.
Message Received By:
- . 5 $$ ?
- 1. This is: McGuire Nuclear Stacica ,
ilnsert name of facii:y)
- 2. My name is:
- 3. This messaga (number __):
(a) Reports a real emengener.
(b) is an exercise message.
- 4. My telephona number /extensien is: /
- 5. Me:.aga authentication:
(verity eco werd cr cati back :o me racility)
- 6. The class of the emersen:y is: _(a) Notificaticn of Unusual Event
_.(b) Alert (c) Site Emergenef (d) General Emergene/
- 7. This c!arsification of emer7:ncy war dec!ared at: (a.m /p.m.) on _ (date).
- 8. The initiating event causing the emeniency classif'ation is:
- 9. The emergency condition: (a) Oces not involve the relaua of radioactive materials from
+
the plan . . , . _
(b) Involve tne po cntial for a re! cue, but no re!em is cccurring.
(c) Invcives a re!caca of rcdicactive material. .
~ ' ' ' '
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..e.-- .u > - , , .- RP/0/A/5700/03i DICLOSURE 4.5 -
- PAGE- 2 0F 4- -*
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 childrh 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 repset, this message: PART I APPROVED FOR RELEASE (a) Fisports an actual emergency Signature (E:nergency Coord.inator)
- (b). Is an exercise messege -
- 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 Warnin- Point notified en Pa-e 4 of 4
-, g@2fgh--+----~~~ .
~- ~ PART IC ? ' . '. ' - -
. n.0 9..L9 "
. .~
- 1. l'he type of actual or projected release is:
(a) Airborne (b) Waterbome .
. (c) Surface spill .
=
fd) Other
- 2. The source and descripdon of the release is:
3.- _(s) Reieses bogen/will begin n a.m./p.m.; time since reactor trip is hours.-
(b) The estimated duration of the release is hours.
. > h
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RP/0/A/5700/03- .. .- .
~
ENCLOSURE 4.5
..: ~ PAGE 3 OF ' 4 -'
/ > 4. Dose prosecuan bene dets:
?
Radiological release: curies, or curies /sec.
Windepeed: mph Wind direction: . From .
Stability class: (A,B,C,D,E F. or G) - - -
Release height: Ft. - - - - -
Dose conversion factor: R/hr/Cl/m3 (whole body)
R/hr/CI/m3 (Child Thyroid) ,
Precipitation: -
f Temperature at the site: 'F
- 5. Dose protecnons: -
- Does Commitment
- Whole Body (Child Thyroid)
U Rem / hour Rem / hour of inhalation Site boundarv 2 miles -
t 5 miles )
10 miles .
- Protoceed integrated Dose in Rem
- l Distence Whole Body Child Thyroid Site Boundary 8 2 miles 1 5 miles 13 miles
- 6. Field mesourement of doetreto or com sminscon (if avestable):
- 7. Emergenicy accons underway at the facility include:
l }
- 8. onsite support needed from offsite organizadons:
- 9. Plsert status:
(a) Reactor is: not tripped / tripped
_( b) Plant is at: % power / hot shutdown / cold shutdown / cooling down (c) ' Prognosis isi stable / improving / degrading /urtienown.
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RP/0/A75700/03 ENCLOSURE 4.5 T rN, 10. I repast, this message: PAGE 4 0F___4
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(a) Reports an actual emergency.
(b) is an exercise message. PART I and II APPROVED FOR #"mE
- 11. Do you have any questions? Signature (Emergency Coordinator) -
NNUEl(.[Mh Ed e . dei r.lg a fl.ie Wfab',1:sNv. < et :: e' dji. d.[A[f_j' .}._. h y M _
NOTE: Record the name, title, date, time, and warning point notified. (Sanders) _
Record the name title, dets, t;rne, and persons notified per alert procedure. (Receivers) .
l 1.
(name) (title) ,
I (date) (time) (warning point) I 2.
(name) (titie)
(date) (time) (waming point) 3.
(name) (titis) .
(date) (time) (waming point) 4.
(name) .
(titie)
(cate) (ttme) (waming point) 5.
(name) (titie)
(date) (time) (waming point)
. 6.
(name) (title) a (date) (time) (weming point) 7.
(name) (titie)
(cate). (timeb (wamingpoint) '
8.
(name) (title)
(data)-' (time) (warning point) l
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Form 34888 (6-82) .
. _ _ . , _ . _ _ - _ . , . , , _ ., , ,,m, . , . . . _ _ , , , , , ,, , , - . , . . , , ,,w-, ,_ _ - _ - . .
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.. ... . . . RP/0/A/5700/01 -
- pgg -1 d 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 statfort 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'Managemerit 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.
(Telephone Number)
- 10. Additional Comments:
, .. 4
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Form 34731 (10 81)
(Formerly SPD 10021)
DUKE POWER COMPANY (1) ID No: RP/0/A/5700/04 PROCEDURE PREPARATION Changa(s)0 to PROCESS RECORD 0 Incorporated (2) STATION: McGuira Nuclear Station ;
(3) PROCEDURE TITLE: General Emergency .
nr hl fy M.'S.
- ) %
(4) PREPARED BY: over, _ , DATE: 5/31/83
~
(5) REVIEWED 3T: DATE: - d-. - 2 '~d3 Cross-Disciplinary Review By: N/
(6) TEMPORARY APPROVAL (IF NECESSARY):
By: ,(SRO) Date:
By: -
Date:
(7) APPROVED BY: Date:
/ '
D -
(8) MISr:ELLANEOUS:
Reviewed / Approved By: Date:
I.
Reviewed / Approved By: .Date:
1 N
N '
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. RP/0/A/5700/04 - .
PAGE- 0F 5 -
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- (m _
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DUKE POWER COMPANY
- McGUIRE NUCLEAR STATION GENERAL EMERGENCY 1.0 Symptoms 1.1 Events are in process or have occurrend which involve actual or iminent substantial core degradation or melting with potential for loss of containment integrity.
2.0 Insediate 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 Accions Initial /N/A
/ 3.'1 The Shift Supervisor / 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 Ihitiating-Conditions, Emergency Action Levels, and Associated Emergency Procedure / Document. -
4 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 Emerge.:7 Coordinator.
/ 3.2 Upon declaration of a General Emergency, the Emergency
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, PAGE 2_ 0F 5 .
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~ ~ 'j 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 radius (Areas, A, B, C, and Q) and 5 miles downwind' (90* Sector) of the station. (See Enclosure 4.8, McGuire Protective Action Zones) Provide a follow-up recommendation as soon as possible safter evaluating the specific plant conditions, offsite dose projections and field monitoring team seasurements 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 .
1 minutes of declaring the emergency) notification of the North l
l Carolina State and Locr1 County Warning Points indicated on l
Enclosure 4.3. He shall also assure notification of all other l
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. ~l j d. to D4d k g
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. _. .PAGE 3 0F 5 , .
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NOTE 2 See Enclosure 4.4, Telephone Listing, for notification, telephone numbers / radio codes /pager n . _.
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 S'pport u Center and the Crisis Management Center will assess and.
t 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 ac,tual releases via a dedicated individual or automated data transmission.
I 3.5.3 Providi2g 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, the' Emergency Coordinator shall utilized the Operator Aid Computer (OAC) " NUCLEAR-23" program to assess the offsite consequences.
In the event the (OAC) is not operational the Emergency Coordinator shall request Health l Physics personnel to evaluate the consequences utilizing the appropriate Health .
1 me,me ee . .e .e oo. o . _w.eev *= o" e= = ~ = * ** '"* *~
- 6
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y RP/0/A/5700/04.~ ~-
l PAGE 4 0F 5
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Physics Procedure, HP/0/B/1009/05, 4
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 flesources (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 b le body <1, thyroid <5, NO protective action is required. Monitor environmental udiation levels to verify.'
I 3.6.2 b le body 1 to <5, thyroid 5 to <25, recomrend seeking shelter and wait for further instructions. Consider evacuation particularly for children and pregnant women. ,
Monitor environmental radiation levels. Control access to affected areas. '
i 3.6.3 b le body 5 and above, thyroid 25 and above, recommend mandatory evacuation of populations in the affected areas. Monitor environmental radiation levels and adjust area for mandatory evacuation based on these levels.
Control access to affected areas.
NOTE See Enclosure 4.4, Telephone Listing for notification.
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499 gbg, kN IMAGE EVALUATION ((gj Y
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1 RP/0/A/5700/04 -
u PAGE 5 0F 5 .
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(O / 3.7 The Emergency Coordinator in coordination with the Recovery r
-] Manager, at the Crisis Management Center, will:
j, 3.7.1 Provide a dedicated individual for plant status updates to offsite 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 offsite authorities at the Crisis Management Center or by phone if necessary, followed by written summary within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
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 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 \./
4 ENCLOSURE 4e1 ,
i PAGE 1' 0F 1 -}
t 'y EMEftGENCY CLASSsF8 CATION GulDE FLOWCHART
- i 4
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as asseseneeAt empheaAv 4 6 As AAf e i (
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va .\ ace re mo.e a seo Ance Cossta a.s aanos
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adAaon paaemos To erases etast oss i meteasa os amoeoacrewevv to cosev neesesessi on eut t eensectesso Coht aessedeNT om euGL seageotesso sult eHeen .
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tesuataswe6a s tee nstaceo on estosac reo mette avesess es o eenes. santesouases i etaose seor ses cota enuspowes cuesy asas sat tv os vosso esses =
saaese asseecos cout o cause asassewa 3
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1 i seannantesso enecAuveossaar , manmantesso acTowas sess ee rees eans os es aNs ceanassuo enome evnasswaa,nounce reeat
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es to sne cuan es ses An sees says reneoo ecessett. ea e. asev cone aset t araanu ces seoussoswo usenausseva n sacnnecat ano '
a i ecassow nsousne savuassoses -
e esewotwa usnam suase monuat j coesa mit t a o snu newee tnAn.s.e.oni ocene Aveoes of e=oeveount com AuenAseo enuuseu so . . 5 1 os e best cocteelat ea 1 i 1 ,
4
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) RP/0/A/5700/04 W .
l .
ENCLOSURE 4.2 ~
PACE 1 0F 6 LIST OF INITIATING CONDITIONS, EMERCENCY ACTION LEVELS, AND
- e .' ASSOCIATED EMERCENCY PROCEDURE / DOCUMENT l 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 1 res/hr Whole Body or
. 5 res/hr Thyroid at the -
site boundary under act4a1 _ meteorological conditions.
l ~
! HOTE 1: These dose rates ,
i i are projected base on I plapt parameters (e.g.,
. radiation levels in con-tainment with leak rate -
appropriate for existing containment pressure with some confirmation from
, affluent monitors) or are i measured in the environs. .
NOTE 2: Consider evacuation -
only within about 2 miles of the. site boundary unless these levels are exceeded by a fac-tor of 10 or projected to con- '
tinue for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> or EPA Pro- ,
tective Action Guideline exposure levels are predicted to be exceeded at longer distances.
i 4.2.2 Loss of 2 of 3 fission pro- 1. Loss of coolant accident as HP/0/B/1009/05. AP/1/A/5500/05.-
duct barriers with a poten- identified in Site Area Emergency AP/2/A/5500/05
! tial loss of 3rd barrier, 4.2.1, and incomplete contain .
(e.g., loss of primary ment isolation. '
coolant boundary, clad-'
failure, and high poten- 2. Loss of coolant accident as iden-tial for loss of contain- tified in Site Area Emergency 4.2.1, -
ment integrity).
andContainmentMonitoragarna(EHF51A and/or B) greater than 10 R/hr and con- -
tainment prescure greater than 14.8 peig '
.e for at least 2 minutes. ,
, i. .,
l '
- i I '. ,
RP/0/A/5700/04 ENCLOSURE 4.2 PACE 2 OF 6 . j 1
Initiating Conditions Emergency Action Level (EAL) Emergency Procedure /Docueent .f l.
a 1
o .,
[ .1 ' 4.2.3 .
Loss of physical con- Physical attack of tue facility has Station Security Plan. -
, . trol of the facility, resulted in occupation of the con- -
prol room and auxiliary shutdown -
t NOTE: Consider 2 mile facill'ty.
p ! precautionary evacuation. ,
t 4.2.4 other plant conditions As determined by the Shift Supervisor / As dictated by plant conditions.
exist, from whatever Epergency Coordinator and verified by '
l .
e source, that in the judge- EAL's defined in implementing Procedures j I ment of the shift super- utilized up to this point. '
I visor, the Operations Duty j l Engineer, the Superinten- ,. .
dent of Operations, or the Plant Manager make release of large amounts of radio- -
l activity in a short time -
i '
period possible (e.g. , any ,'
- core melt situation). -
- a. For core melt sequences >
! where significant re-leases are not yet taking place and large i amounts of fission pro- !
I ducts are not yet in
! the containment atmos-J phere, consider 2 mile .
- precautionary evacua- ,',
tion. Consider 5 mile downwind agacuation .
! (45" to 90 sector)
- if large amounts of ~
- j. fission products (greater than Cap acti-
~
, ; ylty) are in the con-
, , tainment atmosphere.
- Recommend sheltering in i other parts of the ( '
plume exposure Emer-
. g&ncy Planning Zone -
under this circumstance. _j.
[ - ,
a . -
,m
(. ', -
i RP/0/A/5700/04 ' ~
ENCLOSURE 4.2 .
PACE 3 0F 6
- Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document .
I i .
- b. For core melt 'se- ,
! quences where signi-l ficant releases from containment are not i
, yet taking place and i:
t l
containment failure leading to a direct <
atmospheric release
- is likely in the se- L ,
, quence but not immi-
.nent and large amounts
.of fission products in
! addition to noble l l .
gases are in the con-
< . tainment atmosnha-e.
cone'*:. paecautionary evscuation to 5 miles awd 10 mile downwind
.escuation (45 and
- ! 30* sector).
- c. For core melt se-quences where large amounts of fission products other than
' l
. noble gases are in i
. the containment atmosphere and con-tainment failure is judged imminent, re-I commend shelter for '
)
- -those areas where
! ,j evacuation cannot be completed before g'
i transport of acti- <
, 'vity to that loca-tion.'
1 i :
, .....:_._....u.._. . . ;. : 2. .L. m_.o .w. '_:.c _ _ .. - .
cu l s RP/0/A/5700/04 ENCLOSURE 4.2
, PAGE 4 OF 6 Init$a, ting Conditions Emergency Action Level (EAL) Emergency.Frocedure/ Document-e
- d. As release informa- .
I tion becomes available -
f adjust these actions i in accordance with dose projections. -
. time available to ,
evacuate and esti- '
i mated evacuation '
times given current conditions. ,
t e j e. Example Sequences ;
.i 1
- 1. Small and large Safety injection signal plus reac-l LOCA's with fail- tor trip and:
ure of ECCS to per-form leading to 1. Safety injection and RHR severe core de- pumps not running, gradation or melt.
2.
Ultimate failure Flow indications for safety .
l of containment injection read "0".
likely for melt
, sequences. (Seve- 3. High containment sump level. '
ral hours likely ,
l ~to be available For Severe Fuel Over Temperature:
to complete pro- , Greater than 10% failed fuel
' , tective actions indicated by greater than .
unless containment 13,000pci/ml-131 concentration.
is not isolated).
. For Fuel Helt Conditions:
l Greater than 51 failed fuel
'! indicated by greater than
- 11,800pC1/ml I-131 concentration.
a
- ~ - ~ - ' '
. . . . . . : _ ;.- ._;.L _ . : .
' RP/0/A/5700/04 " -
ENCLOSURE 4.2 .
j PACE 5 0F 6 Emergency Action Level (EAL)
~
Initiating Conditions Emergency Procedure / Document.
i 2. Transient ini- Reactor trip on Lo Lo Steam Generator AP/1/A/5500/06 AP/2/A/5500/06 :
i, ;
tiated by loss level and wide range generator levels EP/1/A/5000/04. EP/2/A/5000/04 l of feedwater and toward offscale low on all steam generators condensate sys- and emergency feedwater flow indica- c.
- tems (principle _ tors indicate "0" flow or emergency s heat removal sys- feedwater pumps not running and can- '
j ! tem) followed lyy not be restored within 30 minutes o,r i failure of emer- >3% reactor power and loss of both gency feedwater main feedwater pumps, manually trip .
l system for ex- reactor. -
tended period.
(Core melting is possible in seve- t .
ral hours with .
ultimate failure of containment '
i likely if the core melts).
4 3. Transient requir- Reactor remains critical after all AP/0/A/5500/34 j ing operation of attempts to trip the reactor are
- shutdown systems complete and flow indicators on i with failure to safety injection and RHR show "0" scram. Core dam- flow after initiation (NVP5440,
, age is likely. NDP5190, 5191. 5180, 5181, Additions 1 failure HIP 5120, 5450) g safety injec-i of the core cool- tion and RHS pumps not runninig
! ing and makeup with safety injection initiated. -
system would lead
{
to core melt.
t J .
i i
I I
) .
,9 M
=
' e j Rr/0/A/5700/04 '
i ENCLOSURE 4.2 f PACE 6 0F 6
.I
. 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' j and onsite power blackout load sequencers actuated and 1 ; along with total auxiliary feedwater pump (s) fail to u
,I Insa of emergency' start. ,
feedwater makeup
~
capability for several hours.
7 Would lead to .
, eventual core -
! melt and likely
!. I failure of con-4 4
tainment. .
- 5. Small LOCA and Pressurizar low pressure reactor trip EP/1/A/5000/02 EP/2/A/5G00/02y *
- initially suc- land pressarizer low pressure safety AP/1/A/5500/05, AP/2/A/5500/05?.
, cessful ECCS. injection signal and RHR flow indica-I 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,' H 81) and tem over several Reactor Coolant (NC) T is rising, l hours could lead and containment air handling system i
j to core melt and fails to function.
, likely failure of j containment. -
NOTE: For melt ae-I quences or for failure i
of containment isola-l tion systema, the likely failure mode is melt i through with release of gases.
l 4.2.5 Any major internal or ex- As determined by the Shift Supervisor / Aa dictated by plant conditions,.
l ternal events (e.g., fires, Emergency Coordinator, j earthquakes substantially beyond design levels) which could cause massive common '
l . damage to plant systenis. ,
i kA
- l i
RP/0/A/5700/04' . <'-
.. ..r< .
. - -. ENCLOSURE 4.3 -
- > -m PAGE 1 0F 1
..\
it *
/
NOTIFICATION / ACTIVATION GENERAL EMERGENCY 9
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 Encineer Station Manacer Superintendent of Operations Superintendent of Technical Services Projects and Licensino Encineer Station Health Physicist North Carolina State Warning Point Mecklenbura County Warnina Point Lincoln County Warnino 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. Stat'fon Representative Superintendent of Maintenance Superintendent of Administration Construction Project Manager Activate T.S.C. (Station Directive 3.8.2)
Activate 0.S.C. (Station Directive 3.8.2) ,
Activate C.M.C. (Enclosure 4.6)
p-i
. 1 s
, . :. ~ .
! .. 3 ..r .
.. .. m. - , -
RP/0/A/5700/04 .
{ ENCLOSURE 4.4
..- . ,. .e. ..
.- pggg 3 y g.. .. .-
_ g.s TELEPHCNE LISTING i
'.y 4.4.1 Operations Outy Engineer (PA System)
P&T Pager - J 2 ---
i
~
4 4.4.2 Station Manager f Home - ,- System Speed - T Home - ,- System Speed - )
j 4.4.3 Superintendent of Goerations - ' .,
Home . J Systes Speed 4.4.4 Superintendent of Technical Services -- _ .
.. Home -- J,' System Spee d 4.4.5 Projects and Licensing Engineer - . _ .
Home - ,> System Speed -
4.4.G Station Health Physicist .
Home -
,-ays' tem Speed - '
/
P&T Pager 4.4.7 NC State Warning Point, Raleigh - "f- System Speed -
J 4.4.8 Mecklenburg County Warning Point - Primary: Rina.0cwn Phone Back-up: 1/< System Speed Back-up: Emergency Radio, Code:
4.4.9 Lincoln County Warning Point - Primary: Rina Ocwn Phone Back-up: < System Speef Back-up: Emergency Radio, Code ,
4.4.10 Catawba County Warning Point - Primary: Rina Down Phone Back-up: . System Speed Back-up: Emergency Radio, Code: ,
4.4.11 Iredell County Warning Point - Primary.: Rina Down Phone
' -- System Speed
~
Back-up:
Back-up: Emergency Radio, Code: ,
4.4.12 Gaston County Warning Point - Primary: Ring Down Phone J :-- System Speed
~
Back-up:
Back-up: Emerger.cy Radio, Code: ,'
4.4.13 Cabarrus County Warning Point - Primary: Rina DownPhone Back-up: - System Speed Back-up: Emergency Radio, Code: ,
NOTE
- 1. Radio Cod'e Mll activate all county radio units.
- 2. P&T Pager, . Central Division (Charlotte Area)
Dial .
"4 y., .
-+
'~
~~. RP/0/A/5700/04 ENCLOSURE 4.4 '
2'
-.PAGE' 2- 0F -
~
~ TELEPHONE LIST
(; -l,\
~
- - ~
- 4.4.14 SC State Warning Point -
1
-4.4.15 N.R.C. Operation Center, Emergency Notification System (ENS Phone) l
.4.4.16 N.R.C. Station Representative (Bi_ll Orders)
Office - N ._
Home ., ' System Speed -
P&T Pager - ,'Onske Pager _ /
For P&T Page frc:n Central (MNS Area) - __ j s '
/
4.4.17 Construction Project Manager- Construction . "~
? Ext.
Home : ' - ~System
~ ~ " Speed -
550, Mt.- Holley >- System Speed -
4.4.18 Superintendent of Maintenance - Q ~~s
- System Speed -
Home .
j
'K x 4.4.19 Superintendent of Administration - i \
Home '. f - System Speed -
4.4.20 Nuclear Production Outy Engineer - jSystem Speed P&T_Pager ,
_ _s .
4.4.21 Radiation Protection Section, Department of Human Resources-
'-' 7 System Speed' -
a
( -
. _ - I~
! ,_.- - .~
h _..... , .._.
7iid.M__. a >. : i j -: r.1 h, ' +
l .
- (i. . hitl[ois-fd;:(Nh.,
. w
.tYINeyh. i:,
Instructions: -.
79jgjff;,7 g,q
' \ r:n.os a.5
/ A For Sender: PM:- 1 0F 4
- f. Complete Part I for the Initial Warning Memp.
t 2. Complete Parts I & 11 for followup mess.:ca l, S. For Receiver:
- 1. Record the date, time and your name in the area below.
' " ' - G
- 2. Authenticats this message by verifying the ice word c > .
.I^ '<
Time: Date: . . _
Message Received By: . _ _ . _
=g. f h_ . . . . - %Ju_ _ _ _ _ . . . ,~..___..% . , , ._ __ ._ . ,
- 1. This is: wre > -o % $o,- e,,- %
(Inser name of fac:lity)
- 2. My name is: ,,
- 3. This me: sage (number _.):
(a) Reports a real emergency.
(b) is an exercise message.
- 4. My telephcne number /extensien is: , .
~. 1
- 5. Messan authenticaticn: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ .
(verify ecee werd ce a i ;v :o en L . ed
'*~
- 6. The c! ass.cf the emergency is: (a) Notificatico cf U-(b) Alert (c) Site Emergency (d) General Emergc cy
- 7. This classification of emeryncy was declared at- - (a. -
- 8. Tt i initiating event causing the emer5ency clas.:ificatica is: , _ _ _ . _ , _ _ _ _ .
O WM*
- 9. The emergency conditicn: (a) Oces rb t inv. ' ,
' c ,;rrc_"
, J' the pt.:.-
(b) to (c) !.
. , RP/0/A/570'0/04 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 doors and windows closed.
(c) People in zones evacuate their homes and businesses.
(d) Pregnant women and children in zones remain indoors with the doors and windows closed.
-(e) Pregnant women and children in zones evacuate to the nearest shelter / reception center.
(f) Other recommendations:
- 11. There will be:
(a) A followup message (b) No further communications
- 12. I repast, this message:
PART I APPROVED FOR RELEASE
_ (a) Reports an actual emergency (b) is an exercise message Signacure (Emergency Coordinatop)
- 13. RELAY THIS INFORMATION TO THE PERSONS INDICATED ON YOUR A!.ERT PROCEDURE FOR AN INCIDENT AT A NUCLEAR FACILITY.
- END OF INITIAL WARNING MESSAGE ***
l NOTE: Record the name, title, date, time and Warning Point notified on Page 4 of 4 l ~
PART II
~
- 1. The type of actual or projected release is: -
(a) Airbome
,,(b) Waterborne (c) Surface spill (d) Other
- 2. The source and description of the reisess is:
- 3. (a) Reisees began /will begin at a.mdp.m.; time since reactor trip is hours.
(b) The estimetod duration of the reisess is hours.
. . - . .- ... m o e== g-e ew=mme-- *ww- * * * * * = * - 9-e
RP/0/A/5700/04 -
ENCLOSURE 4.5
- . - , ^
pAgg 3- 0F ~4
- 4. .,Does orojection base deta: , , , .
.g , .
- Radiological rolesse: ___ curies, or curies /nc.
Windspeed: mph
. Wind direction: From 4
' --~~
(A,B,C,D,5,F, or G)
~-
Stability class:
Release height: Ft.
Dose converson factor: R/hr/Cl/m3 (whole body) l R/hr/C!/m3 (Child Thyroid)
~ ~
Precipitation:
Temperature at the site: 'F -
- 5. Dose projecnons:
' Dose Commitment
- Whole Body (Child Thyroid)
Distance Rem / hour Rem / hour of inhalation i Site boundary 2 miles 5 miles
/ 10 miles
- ' Projected Integrated Dose in Rem
- Distance Whole Body Child Thyroid i
Site Boundary 2 miles 5 miles 10 miles l -
- e. Field measurt.mont of dose rate or contamination (if available):
- 7. Emergency actsons underway at the facility include:
- a. onsne support needed from offsne organizations:
- 9. PIant status:
i
! 2 (a) Reactor is: nottripped/ tripped I . .
(b) Plant is at: % power / hot shutdown / cold shutdown / cooling down l (c) Prognosis is:. stable / improving / degrading / unknown.
l
1
. RP/0/A/5700/04 ENCLOSUPI 4.5 '
10.~ l ropest, this message: PAGE' ~4' '0F -4
~
(a) R'e ports an actual emergency.
PART I and II Approved for Releas E ' ~
~
J (b) is an exercise message.
Signature ( E:nergency Coordinator )
-irnFC 0 C#ve ***ENG OF FOLLOwr-UP MESSAGEN*Wu ~. * + . - -&-Je# .
NOTE: Record the name, title, date, time, and woming point notified. (Senders)
Record the narne title, date, time, and persons notified per alert procedure. (Receivers) --
1.
, (name) (title) 1 l
(date) (time) (warning point) 2.
(name) (title)
(date) (time) (warning point) 3.
(name) -
(titfe)
( (date) (time) (warnins point) 4.
(name) (title)
(date) (time) (warning point) 5.
(name) (title)
(date) (time) (warning point) 6.
, (name) (title) 1 Idate) (time) (warning point) 7.
(name) (title)
(date) (time) (warning point) 8.
(namel (title)
(date) (time) Form 34888 (6-82).
(warning point)
-+-e===*.====. . . . == = ~ e w - - . - - - - - - , - - - . - ,.-n.-- -,.,,,.n. -, ,n- , - - ,..- - . - . ,--w.~... . , . - . - . - - , , - - . - - - - - - - _ , , - - - - - , , -- .- , , - .
RP/0/A/57'00/04 ENCLOSURE 4.6 '
PAGE I: OF - 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 Orill. An Unusual Event
_ Alert
_ Site Area Emergency
" ~
_ General Emergency was declared by the Emergency Coordinatoe 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 elen notified.
- 8. The Crisis Management' Team should/should not be activated. Corporate Communications and Company Management should be notified (Unusual Event only).
- 9. I can be reached at for follow-up information.
(Telephone Number)
- 10. Additional Comments:
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. RP/0/A/5700/04 4 ' >
- ENCLOSURE 4.8' -
PAGE. 1 0F 1 ,
'I
,o
~
MCGUIRE PROTECTIVE ACTION ZONES e
Q
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y y 3 g3 p 3 (Formerly SPD 1003 DUEE PC'JER COMPANY (1) ID No: HP/0/B/1009/09 PROCEDUKE PREPARATI0t! Change (s) O to PROCESS RECORD 2 Incorporated (2) STATION: McGuire Imaclear Station (3) PROCEDURE TITLE:_ Release of Radioactf.ve Materials " trough Unit Vent Exceeding Paehn4em1 Emme4#4en*4nne (4) PREPARED BY: //4MNL DATE: .r/q//3 (5) REVIEWED BY: 4 ,_ illL - C DATE: . .r'-r #3 rs Cross-Dise.iplinary Review By:
- N/R:'-A . . .:.:
(6) TEMPORARY APPROVAL (IP NECESSARY):
By: (SRO) Date:
By: Date:
(7) APPROVED BY: 4s .d. /7D bM/ Date: .i"M. /h y ,
(8) MISCELLANEDUS:
Reviewed / Approved By: Date:
Reviewed / Approved By: Datt:
I
- 5. .
i e
w e
- 9 -
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-.---mwve--ww.=-m-we----p-w.---repg+-pe-%wvw.-w,,.ywe- w-Ny.-------
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'. . HP/0/B/1009/09 n
I DUKE POWER COMPANY McGUIRE NUCLEAR STATION RELEASE OF RADIOACTIVE MATERIALS THROUGH UNIT VENT EECZEDING TECHNICAL SPECIFICATIONS
-8 1.0 Purpose This procedure describes the method for calculating the potential offsite dose rate and dose following a release of radioactive macertals through the unit vent. In addition, this procedure can provide warning message information to be given to state / local agenc es.
2.0 References .
2.1 Station Health Physics Manual Section 18.2; Environmental Monitoring for Emergency Conditions.
2.2 L'ealth Physics Manual Section 8.2, Exhibit 8.2-2 '
Page 2. Unit Vent.& Waste Effluents Flow Data Form. ;
2.3 10CFR20, Appendix B, Ta,ble_II.
2.4 McGuire System Descriptions.
2.5 Unit Data Book 2.6 NRC Regulatory Guide 1.4 l
2.7 Offsite Dose Calculation Manual (ODCM) '
! 2.8 HP/0/5/1009/05, First Response Evaluation of a Reactor Coolant
[ Leak Inside Containment. '
3.0 Limits and Precautions 3.1 This procedure is being used in an emergency situation which could result in evacuation of areas surrounding the plant.
The procedure shall be fully understood and calculations shall be done carefully and accurately.
3.2 This procedure is written for use under abnormal conditions which could involve extremely high radiation levels. Only the Station Health Physicist or his designee should authorize the use of this procedure when needed and should provide appropriate surveillance and control of people taking samples.
3.3 Check that the counting equipment to be used has been calibrated and daily response checks have been performed.
l
Pcg3 2 3.4 Individuals collecting the samples should be aware of the possibility of airborne contamination and high radiation T
I levels in sempling areas. .Use protective clothing, gloves, respiratory protective equipment, portable shielding, high range dosimeters, and survey instruments as determined by
_._. . Health Physics.
3.5 If action is taken in the 4 - 10 mile radium aree per reference 2.8. then wind direction should be rechecked everv 15 minutes to ensure that additions 1 sectors have not been affected. Once a sector has been added to the list, it cannot be removed from the list.
3.6 Projected doses should be compared to the Environmental ,
Protection Agency Protective Action Guides to determine levels of protective action.
4.0 Procedure 4.1 Acquire the following information and record on Enclosure 5.2 and/or 5.3.
NOTE 1: Some of the following information can be obtained from the ' Tech Specs 04' program of the Operator Aid
, Computer (OAC). All information available in ' Tech Specs 04'_will be denoted in the following procedure by a '(TS)' to the left of the section number.. See Enclosure 5.5 for steps to access ' Tech Specs 04'. l NOTE 2: Standard warning message information to be given to state / local agencies will be denoted in the following procedure by a '(WM)' to the left of the section number.
l NOTE 3: Meteorological data should be obtained in the order of preferenes listed in Enclosure 5.2.
NOTE 4: Use 15 minute averages for all. meteorological data.
(
4.1.1 Wind direction recorded in degrees from North (upper' tower). Lower tower wind direction should be used l only if upper cover data is unavailable.
I*} 4.1.2 Lower tower wind speed (MPR) (W). Upper cover wind L direction should be used only if lower cover data is unavailable.
4.1.3 7ertical temperature gradient or AT*C (lower to
,p. gego .- - 3m-w -mouse.. e*
---_
- e e = *
- e**- *rea b
.g.-w.--w,y - ,-. .+ --, v.m. , . _,-.-,,.m. _m. ,gr.-- _ 7,- ,. , . , _ ,, .,,e, - _ , - , , - . , . , , . - , . , - . + . . , mme.-,_ - , . ,,w- c. ,, ,,.,,,,m, --- m-w..--,-we., ,
> -y i - Pcg3 3 it
, upper tower) from the -4 to +8 scale on the meteorological temperature strip chart recorder.
NOTE 1: This information is used along with Table on Enclosure 5.4 and map provided in Technical Support Center (TSC) to determine areas affected by release.
NOTE 2: Plume direction is 180* opposite wind direction.
( }
4.1.4 Stability class (A.B.C.D,E,F, or G) from Table I (Enclosure 5.1).
( ) 4.1.5 Ambient air temperature (*C). Record in *F where:
- F = 9/5 *C + 32.
( ) 4.1.6 Precipitation
( ) 4.1.7 Dischargs flow rate (F) from unit vent which is obtained by multiplying the fractional flow from totalizar by 170,500 to get flow in CFM. (i.e. 95%
flow = 0.95 fractional flow).
NOTE 1: If the unit vent flow totalizar is inoperable, flow can be determined by reference 2.2.
( ' NOTE 2: , Release height of unit vent is 142 feet above yard elevation.
NOTE: Information in sectiona 4.1.8, 4.1.9 and 4.1.10 is not normal 17'used. It is available if needed for working with outside agencies. .
4.1.8 Discharge concentrations (C and C7 ) from Health NG Physics sempling of unit vent; or DfF data if , sample results are not available, as follows: ,
If EMF 36(H) <100 cym, C
NG
= EMF 36(L) cya x 3.8 E-8 or if EMF 36(H) >100 cym,
- gg = M6(H) cya x 2 E4 C7 = EMF 37 A cps /A time x 2.34 E-10 Whers:
Cg = noble gas discharge concentration in uCi/al
__- 3.8 E-8 = EMF 36 (L) correlacion factor in
- s ,
1.
, Pcgo 4 5 .
, uC1/al/ cpm from reference 2.5
/
, 2 E-4 = EMF 36 (H) correlation factor in t
uCi/al/cpa from reference 2.5 2.34 E-10 = EMF 37 correlation factor in uCi/al/cpa/ min from reference 2.5
} 4.1.9 Calculate radiological release race (Q) in C1/sec using the following formula:
~
Q,, = C,, x r x 4.72 E-4 Q7 =C x F x 4.72 E4 7
Q = (gg + C7 ) x F x 4.72 E4 Where:
bG = noble gas radiological release rate in Ci/sec Q7 = I-131 ,equiv radiological release este in C1/sec Q = radiological. release race in C1/sec 4.72 E-4 = 2.83 E4 cm8 /ft8 x 1.67 E-2 min /sec x II-6 C1/uci All other variables same as previously stated.
} 4.1.10 Calculate dose conversion factors in R/hr/C1/m3 for whole body and child thyroid using the following formulas:
l DCFg = 0.5 x 3.7 E10 x 3600 x E l.3E3 x 100 x 6.25E5 i
l l
DCFg = 820 x I Where:
, DCF WB
= Whole body dose conversion factor in R/hr/Ci/a8 l 0.5 = conversion from infinite cicud te semi-infinite cloud whole body dose I = average Mov/ dis from Count Room data
.--w - - -
y . , , , -_., . . ,m__ c..-.m__,_,.,,ey- - . , ,. , . , , - - , .,,,__-____,,,y
^
. - ~ . . . . . . .
Pcsa 5 1 -
NOTE: If E cannot be obtained from sample results, the following values should be used.
Hours from Trip E in Mev/ dis 1 12 __
0.40 ,
12 - 48 0.20
> 48 0.10 1.3 E3 = density of air in g/a s Conversion factors:
3.7 E10 dis /sec
- Ci 3600 sec/hr 100 erg /g
- rad 6.25E5 Mev/ erg DCFg = 4.39E-3 x IE12 x IE-3 x 0.422 DCFg = 1.85 E6 Where:
DCFg = child thyroid dose conversion factor in 8
R/hr/.C1/s 4.39E-3 = inhalation dose factor for child thyroid in ares /pci, from .
r,eference 2.7 0.422 = child breathing race in 38 /hr, from reference 2.7 Conversion factors:
1E12 pCi/C1 1E-3 rad / mrad 4.1.11 Two (2) hour relative concentration (CH) in aph
- sec/as from Table I (Enclosure 5.1) at the site boundary (0.5), 2, 5, and 10 mile points. Record on Table I and Table II of Enclosure 5.3.
( ) 4.1.12 Determine child thyroid dose rate using one of the e
following formulas:
NOTE: If C7 value is determined from unit vent sampling, use the following formula:
Dg = 874 x F x C7 x 1 x CH W
NOTE: Calculations are not required if l
. _ . . _. s. , , , , . . . . .
e c--y-- . - --- , - . - - - . ,--. . . ,,,-,--,. . , - , __---..-,.---....r-- . , - - - - . , . . . _ . - . . , , -% - - -.- . - - . , - , - - . . - - - . - - - - - - -
! *
- Pegn 6 I l dischtrga etne:ntration is loss then 3 . . .
1
- 10CFR20, Appendix B. Table II (I-131, 1 IE-10uCi/al;Xe-133,3E-4uCi/ml) 73 .
) Where:
ti -
bg = child thyroid dose rate in Rem /hr.
'. 874 = 0.422 38 x 4.39E-3 ares x IE6 pCi x IE-3 rea x 472 al/sec/CFM hr pC1 uCi aren F = discharge flow rate in CTM (section 4.1.7)
C7 = I-131 equiv. discharge concentration in uC1/mi
,, (section 4.1.8)
W = windspeed in aph (section 4.1.2)
CH = Two (2) hour relative concentration in aph
- sec/m3 (section 4.1.11)
SE NOTE: If ENT readings are being used, determine child thyroid dose rate using the following formula:
Where:
~
2E-7 = 874 res*al's8 'ain x 2.34 E-10 uCI* min uCi*hr*ft8'sec -- ml
- cpm EMF 37acom = change in cpa per change in time (min)
Atime NOTE: If ' Tech Specs 04' data is used, determine a eps from two runs of the program 5 minutes apart (A Time = 5 minutes).
All other variables same as previously stated.
4.1.11.1 Using one of the above equations, 'N determine the child thyroid dose race at the site boundary (0.5), 2, 5, and 10 mile points.
NOTE: This can be rapidly' accomplished by storing in calculator memory ~
I t
. the result of all numbers, ,
l excepting CH, and then recalling !
, this number to multiply by each j i
I 1
I . _ - . _ _
4
._g .
Pago 7 1
CH value for the 0.5, 2, 5, and
- ,7 10 mile points (as shown on
-l i
~h:j t.
Table I on Enclosure 5.3).
I I I 4.1.13 Determine child thyroid dose at the r*.cc boundcrv (0,5), 2, 5, and 1,0 mile points by multiplying the dose rates at chase points (as done in section 4.1.11.1 and shown on Table I on Enclosure 5.3) by the dose assessment period (in hours).
~
-NOTE: CE values based on a two (2) hour dose assessment period.
I*) 4.1.14 Determine whole body gamma dose rats using one of the following formulas:
NOTE: If gg value is determined from unit vent sampling, use the following formula:
Dg = 0.387 x F x gg x E x1x G W
Where:
Dg = Whole--body gamma dose rate in Rsm/hr.
8 0.387 = 820 1*m1* dis x_4d2E-4 :a
- min
. hr*uci'Mev ft 3 *sec I = average Mev/ dis from Count Room data NOL*E: ~If I cannot be obtained from sample
,, results, che following values shosid be used.
Hours from Trip Y in Mev/ dis
< 12 0.40 12 - 4d 0.20
> 48 0.10 All other variables same as previously stated.
R,-
ECTE: If EMF readings are being used, determine whole body dose race uring one of the following formulas:
l If EMF 36(3) < 100:pa, l
1 - _ - -
J =
.; , Page i j Dg3= 1.43E-8 x EMF 3 f " :-- : ? x I x 1,x CH
] 4 C.. < \
W d b, !
Where:
! 1.47E-8 = 0.387 R*a3 *al' dis
- min x 3.8E-8 uCi/al/cpa a; hr'sec*uci'Mov'ft3
~
All other variables same as previously stated.
Or if ENF36(H) > 100 cpa, Dg = 7.74E-5 x EhT36(H)cma x F x Y x 1 x CH W
, Where:
7.74E-5 = 0.387 R*a 8*m1* dis
- min x 2E-4 uC1/al/cpa hr'sec*uci'Mev'ft8 All other variables sans as previously stated.
4.1.14.1 Using one of the above equations, g decernine the whole body dose race at the site boundary (0.5), 2, 5, and 10 mila points.
N012: ,
This can be rapidly accomplished l by storing in calculator.mencry the result of all numbers,
~
excepting CE, and then recalling this number to multiply by each CH value for the 0.5, 2, 5, and 10 mile points (as shown on Table II on Enclosure 5.3).
, } 4.1.15 Determine whole body gamma dose at the site boundary (0.5), 2, 5, and 10 mile points by multiplying the '
dose rates at these points (as done in section .
I 4.1.14.1 and shown on Table II of Enclosure 5.3) by the dose assessment period (in hours).
{
NOTE: CH values based on a two (2) hour dose assessment period.
4.2 Determine potentially affected zones beead on wind direction ,
6 using the table oc Enclosure 5.4 and record on Enclosure 5.4.
4.3 Determine levels of protective action by comparing projected doses to EPA Protective Action Guides (page 2 of 3 on l Enclosure 5.4) and record on Enclosure 5.4.
f
)
a , Pago 9 5
ij 4.4 Determine.if non-stagnating meteorological conditions exist by 7;
.. m
,. observing meteorological strip chert data. If:
~
M [J . ; - (1) Instantaneous wind direction has not varied over 90*
- in the past two (2) hours, and
, (2) Instantaneous wind speed has not fallen below 10 MPH ij in the past two (2) hours, then non-stagnating conditions exist. Record result on page 3 of 3 of Enclosure 5.4.
4.5 Check results and inform Emergency Coordinator of your recommendations.
4.6 Whenever possible, utilize environmental data ir comparisca with calculated results to better determine plume dispersions.
Record environmental data on enclosure 5.2 when available.
NOTE: Depending on noteorologic conditions, field monitoring tasas may experience difficulty in finding the plume. Therefore, negative field results do not necessarily mean that radioactivity is not being reler. sed.
4.7 Calculated results should-be compared with those from the Crisis Management Center if accessible. Any discrepancies should be resolved,through recalculations and calculation step comparisons. --
4.8 Historical data shall be retained so that offsite dose trends i can be analyzed.
l , 4.9 Insure that enclosure 5.2, 5.3, and 5.4 are properly completed and results presented to Station Hesich Physicist or his designes.
4.10 Actus1 field measurements of whole body doses will be compared to whole body dose projections by the Data Evaluation Coordinator.
5.0 Enclosures 5.1 Table I, Two Hour Relative Concentration 5.2 Unit Vent Release Data Sheet !
l 5.3 Manual Calculation Worksheet i
, 5.4 Table of Potentially Affected Zones 5.5 OAC (Tech Specs 04) User Documentation l
~'
- . - _ , ..-----..J_-.___-._
( \ 4 l i ) . .
Enclosu '% ft f
HP/0/B/luos/09 TABLE I 2 HOUR RELATIVE CONCENTEATION (CH)
Stability Distance (in miles) l Temp. Diff(*C) Class 0,5 1.0 2.0- 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0
- l. < -0.6 A 1.4E-5 1.2E-6 5.9E-7 4.!E-7 3.2E-? 2.5E-7 2.0E-7 1.9E-7 1.8E-7 1.6E-7 1.5E-7 1.5E-4 4.5E-5 J.3E-5 6.3E-6 3.9E-6 2.7E-6 1.9E-6 1.4E-6 1.1E-6
~
- 2. -0.5 C 8.3E-7 7.8E,7 l 3. -0.4 to -0.2 D 3.8E-4 1.4E-4 4.9E-5 2.7E-5 1.7E-5 1.2E-5 9.2E-6 7.3E-6 6.0E-6 5.0E-6 4.3E-6
- 4. -0.1 to +0.4 E 6.9E-4 2.5E-4 9.6E-5 5.5E-5 3.5E-5 2.5E-5 2.0E-5 1.6E-5 1.3E-5 1.lE-5 9.7E-6
- 5. +0.5 to +I.2 F 1.lE-3 5.!E-4 2.0E-4 1.2E-4 8.2E-5 6.3E-5 5.lE-5 4.3E-5 3.8E-5 3.3E-5 3.0E-5
- 6. > +1.3 C 1.8E-3 1.lE-3 4.3E-4 2.7E-4 2.0E-4 1.7E-4 1.3E-4 1.2E-4 8.6E-5 7.8E-5 i 7.3E-5 l
J,
, s The temperatura differential is [he difference in temperature between the upper and lower temperature sensors and is in degrees
, centrigrade.
]
j These valuee are alte-specific for McGuire Nuclear Station.
I 1
t 1
I l
. t i
HP/0/B/1009/09 Enclosure 5.2 i
f (9
- x. /
Page 1 of 2 UNIT VENT RM. FAME DATA SHEET i
Time of trip / shutdown hours after midnight. Date Time of calculation hours after midnight. Date Sample Time hours after midnight. Date --
(All meteorological data is 15 minute average.)
Time (15 min. period ending time) hours after midnight (WM) Wind direction 1) Upper tower degrees from North.
or 2) Lower tower degrees from North.
(WM) , Wind Speed 1) Lower tower MPH or 2) Upper tower MPH AT 1) Lower to Upper tower
- __ C or 2) For 1000 - 1600 -0.2 "C or 3) For 1600 - 1000 +L.3 'C (WM) Stability Class (AT and Enc. 5.1)
(TS)(WM) Temperature *C
'F = (9/5) (*C _) +32 i
- F (WM) Frecipitation (TS) Unit Vent Flow (F) CFM (Totalizer fraction x 170.500)
(WM) Release Height = 142 fc.
NG and C7 )
KNOWN RM FAME CONCENTRATIONS (C (Vent Samples)
Gross Gas (Cg) uCi/mi I-131 Equiv. (C )
7 uCi/mi i
Gas E Mav/ dis UNKNOWNRELEASECONCENTRATIONS(gg and C7 )
(EMF Data)
IF EMF 36(H) < 100 cym.
NC uCi/a1 = EMF 36(H) epa x 2 E-4 uCi/al/cpa C
7 uCi/a1 = EMF 37Acpa/Atime x 2.34E-10 uci/a1 cpa/ain J
,. e- e e. *m e wen- ==w+ -e.==.e-.y .
r s z,
.1 .
l -
RP/0/B/1009/09 Enclosure 5.2
>; ,g .
Page 2 of 2
't s. /
Two (2) Hour Dose Comalement Iodine , Noble Gas (Child Thyroid) (Whole Body) 0.5 at. Rea 0.5 mi. Ram -
2 mi. Ram 2 mi. Rea 5 31. Rea 5 mi. Rea 10 mi. Ram 10 mi. Rea ENVIRONMENTAL DATA (If Available)
Point # Dose Rate
- Iodine Concentration 9
~
Dose Assessor Date l
9 8
I
, , ,p =* * * * ' *** #* **
HP/0/B/1009/09 j
'. Enclosure 5.3' i
( ,
Page 1 of 3 it
{ MANUAL CALCULATION WORKSHEIT 1
l$ _ . . .
- t .
Radiological release rate (Q)
(m) .
Qsc C1/see - C,e xF x 4.72E-4 i.
(W) .
Qg Ci/sec = C 7 xF x 4.72E4
(
Ci/sec = (Cyg+3)xFx4.72E-4 4
Q Dose Conversion factors for whole body (DCFWB) at i child thyroid (DCFg)
( )DCFy,. 1/hr/C1/a8 = 820 x E
( }DCFg = 1.85E6 R/hr/Ci/m3 NOTE: The information on this page is not normally used. It 'is available if needed for working with outside agencies.
N..
I M
G
.A 9'
. _ _ = _ , . _ _ _ . - _ _ - , , - . _ . - - . _ . - . - - . . - - - . - .
1
- s l
~
I
, HP/0/3/1009/09 f %
, Enclosure 5.3 a
} Page 2 of 3 4
Does Rate and Dose Calculations i
Child Thyroid (Record all G values for 0.5, 2, 5, and 10 milas in Table I).
Dg = 874 x F xC x 1 xG 7
. g Store in calculator memory If using EMF 37 reading, (use only if sample results are not available)
= 2E-7 x EMF 37Aepa Dg xF x_" 1 xG
& Time
~
Store in calc $alator memory Table I - Child Thyroid Dese R' ate and Dose (141)
Stored Dose Race Time Dose Distance G Calc. Value (Rem / hour) Period (Rea)
S'.3. 0.5 mi. x = x =
2 x " "
mi. ;=
x =
- d. x " "
5 = x =
10 mi. x - =
x " =
a -
G values based on a two (2) hour dose assessment period.
Whole Body (Record all G values for 0.5, 2, 5 and 10 miles in Table II).
Dg = 0.387 x F xC *C
- l
- NC W
Store in calculator memory .,,
,.m., _ , . _ _ . _ . -
-.v------.-. - , - - - - - . - - y-. - . _ , -., -- - ,
+
t l
HP/0/B/1009/09 Enclosure 5.3 Page 3 of 3 _ ,
' / , ::0TE: Use EMF 36 on1} if sample results are not available. Use E listed below.
If using EMF 36 reading and EMF 36(H) < 100 cym, D
WB
= 1.47E-8 x DfF36(Low)cpa xF xE x 1 xG W
Store in calculator assory . - _
If using EMF 36 reading and EMF 36(H) > 100 cpa, _
D WB
= 7.74E-5 x EMF 36 (High) cya xF xI x 1 xG W
Store in calculator memory Table II - Whole Body Dose Race and Dose (WM)
- Stored Dosa Race Time Dose Distance G Calc. Value (Rea/ hour) Period (Rea)
- S.B. 0.5 mi. x = x =
l mi. " "
2 x = x =
! d. " "
i 5 x = x =
! 10 mi. x = x ." =
G values based on a two (2) hour dose assessment period.
NOTES:
- 1) If Hi-Range EMF reads greater than 100 cpa, use Hi-Range reading. ,
l If Hi-Range EMF reads less than 100 cya, use Lo-Range reading.
- 2) Use Y data from sample results. If sample results are not available, use the following approzdmations:
Time From Trio E y,12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 0.40 MeV/ dis.
12 - 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 0.20 Mev/ dis.
> 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 0.10 Mev/ dis.
m- -' - - - - = = ' " ' * ~ ~ - ~ - - - - ' ' - ' " - " ' ' - ' " " ' ' " " " ' ~ ' ~ * ~ * ' "
l j
. HP/0/3/1009/09 l i
,s
- Enclosure 5.4 I
/ ; Page 1 of 3 j Determine affected areas based on wind direction from the table below Wind (degrees from 0-4 4 - 10 Direction North) Mile Mile Recommendation Recommendation 0- 22.5 See Note 1 R,T,S.E.F,U 22.6 - 45.0 R.T,5,E.U.P 45.1 - 67.5 R.T.S.E.U P 67.5 - 90.0 R,T.S,U.P N,0 90.1 - 112.5 R,T.S,P,N,0 112.6 - 135.0 R,P N,0,L 135.1 - 157.5 I,P,N,0,L 157.6 - 180.0 I,N,0,L,T,J,H
~ '
180.1 - 202.5 I,N,L,J.H,G 202.6 - 225.0 I,N,L.J,H.G 225.1 - 247.5 -
I,J,H.G.F 247.6 - 270.0 J.H.G,F 270.1 - 292.5 H.G.F,E 292.6 - 315.0 C,F,E 315.1 - 337.5 G,F,E,U 337.6 - 359.9 F,E,U.S NOTE 1: Areas A,B,C.D,Q,V.M will be the recommended areas if any action is taken in the 0 - 4 mile radius of the plant.
This recommendation is independent of wind direction. ;
i I l l t' l
l l
I
~-
x.
5.hte 5.s seem anded preteettee settees to reaseo ideele h*4y and therete dee free espee e to e gemeene pliane isojected Duee (Seel to '
the foyelelles Beeeeeeeded AetteseI*I Commente i
tenete hady 48 De pteemed preteettee Setless.lb) y,..g g, , g.g Stele any Seeue se edeteery to seek shelter med easeet preteettee settees any Imyse84 el snarther Seatrinettene. 6e resenaldered er 80emiter savireneesten re40stles levete. teraiented, l
leiste body I to e3 Sei;4 shelter Se o etalaus. If seestrelate selet,
] Ceseider essennettes . Eveennete emeless sonstrelate nebe speelal easeldere48ee thyssed S to 44 84 empreetteel, should he stees ser
- eteetter emettenmental redtatten levels. eveensatsen of shtleree Castren seeese. eed pregaaet esames.
t s.
- Itiene beds 5 sed shave Ceedinet needetery eveenet8 . seekseg sheller eseeld h, p taaeller eevireement'en radiatien levele see adjeet ores se ellerenettoes 4f Thyseld M see aheve , ser esadelery eveessettee heaed en these levels. eveeeelles essee set
- Ceedret sesees. e lease 8gtely pesothle.
Frejseted Sese (Seal to .
8 Emergemey teen therbere ,
thiele body M Castret espeemare of emergeoey tese members to Stiese Attineness e s roeptretere med levele eseept for lifesseles steelees. (appropelate etable ledtee.eheneld be Thyse64 BJ5 eestrele for 'energeoey onestiere. 8eelande slee eseed ediere effeestee to lleltallees, toeptratore, med etable ledlee.) . eentret dose to -
emergemey tese eseshers, tenele body M Centret espeaisse of emergemey tese seabora perforstes thyreld dose seg met he lifesselas elseless to thle level. (Casstret of 60ee a lleittee fester for g of espeenste taill be med essentire.) lifesamleg steelese. .a 9
d mNk di oN e ba O 1
Ielthese settees are reeammended for pleanleg paarpeees. Proteettee settee deelelene et the slee of the Seeldest O 1 essa 4 6. .eselseg e.editse- s.ie e lde,eties. " = D.
j O Ne-t IIInt the slee of the 'Seeldest, eff8e8 ale may Septement less-lepeat preteettee set 8een Se keeplog neith the 4eg prieelple of solantaleleg redaatien espessaawe se laes as reasseehty sektesable.
~
4.s ,tn (c Ac 44
.I ,
?- !
. HP/0/B/iOO9/09 m, Enclosure 5.4
, y Page 3 of 3
-l
- 7) 0 - 4 miles Recommended Areas ,
~
Escommended Population 4 - 10 miles Recommended Areas Recommended Population Non-stagnating meteorological conditions do /do not exist.
Signature NOTE TO EMERGENCY COORDINATOR: -
If the release is projected to end within one-half ( ) hour, and non-stagsseing_ meteorological conditions. exist, consider.
not recommending an evacuation if the plume will have left the Emergency Protection Zone (EPZ) before the population could evacuate.
t ww . enummee = ; ae e - p
, geo * - . e.e m .
._- _ . _ _ _ - _ _ . - - , ,.,.,....,,,,.,..,.,-,___....____m._... .,. , ,,,,,. . . . - , _
1 -
. HP/0/B/1009/09 1 Enclosure 5.5 Page 1 of 1
) OPERATOR AID COMPUTER (TECH SPECS 04)
USER DOCUMENTATION
- 1) ' Tech Specs 04' can be accessed thru OAC terminals in either the 1)
Technical Support Center (TSC) or the 2) Computer Room.
There are OAC terminals for both Units 1 and 2. Be certain to use the OAC terminal for the appropriate Unit.
All necessary data on the ' Tech Specs 04' computer printout will be under the ' Environmental Systems' heading.
- 2) Procedure a) Check to see if the READY key on the printer is funy
. ON/0FF LINE inuminated. If not funy 111mminated, press the key one time and release.
b) Press the Tech Specs key of the OAC terminal. (Key will 1Huainate).
c) Type 0,4 using the blue numeric keys of the OAC terminal.
d) Press the Print key of the OAC terminal. (Key will illuminate).
O e) Press the Enter key of the OAC terminal. (Key will illuminate).
Upon pressing Enter, printer win print data.
~..
f) When printer stops, press the READY key on the printer to ON/0FF LINE illuminate only the " READY" portion of the key.
g) Press the TOP OF FORM key on the printer three (3) times to advance paper. Tear off data sheet.
--n ,--- , , . . , -- r,n. ,- , , , , - - - , , , . , . - , , . . , . - . - . , . , - - , . .
O.f g STATION DIRECTIVE 3.8.I l.
APPROVAL I k .
! ,e DATE Original Issue 2/12/80 REVISION 10 DATE d, d D
'l DUKE POWER COMPANY McGUIRE NUCLEAR STATION SITE ASSEMBLY AND EVACUATION OBJECTIVE To obtain accountability of station personnel in order to implement recovery resources and ensure personnel safety in the event of a potential or actual emergency condition onsite.
RESPONSIBILITY FOR IMPLEMENTATION
- 1. The Shift Supervisor / Emergency Coordinator shall determine whether or not a Site Assembly is warranted based upon the severity of the emergency condition in regards to personnel safety. Examples:
A. Fire out of control.
B. High radiation levels in Auxiliary Building (unplanned).
C. High airborne particulate or gas levels (radioactive, toxic or flassable) in Auxiliary Building.
D. ECCS initiated due to primary system failure.
r E. Security Breach / Bomb Threat.
NOTE: If at any time in the course of this directive, the Emergency l Coordinator deems a Site Evacuation is necessary, tie should proceed to
- Page 4, IMPLEMENTATION-SITE EVACUATION.
- 2. The Emergency Coordinator (or his designee) shall determine whether or not a subsequent evacuation is warranted after evaluating the situation in regards to personnel safety. Examples:
i l ./
r- --m- ---ttW er- r--r---,wm--wn - -- --+ - m-+m--- - - ,r-wme--
L
' ' ^ ~ --
. L. . :a I 2
-4 j
(
)'
A. Fire spreading out of control with potential for reducing containment '
intergrity or damaging essential systems / components.
B. Any unplanned increase in whole body exposure 32.0 ares /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 commencing 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.
IMPLEMILNTATION - 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 l
report to your immediate supervisor or assembly point."
- 2. Repeat Step 1 in full.
I 1
- 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. Superintendents and their clerks and the Station Manager's clerk shall assemble in their offices (outside the protected area) or the TSC (inside l '
l the protected area) if activated, and will be allowed normal passage thru the Personnel Access Portal.
l 6
- -m- , , , -,,--m ,,,--m.-- - - - - - - , - - - - -
-w---- -------~~-m.v = ,- # v'--v"-*---,-*= ==*'m'* = " ' ' * - ' *"~~-- -- ' ' ' ' - ' ' - - '-
a, ,
3
/"
] B. Normal passage thru the Personnel Access Portal (PAP) shall not be restricted during a Site Assembly, however, the Emergency Coordinator may i 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.
9 NOTE: During routine drills, the PBE Operator and assigned security posts at the SAS, CAS, VAP, PAP, and Fuel Receiving Area shall remain at their assigned stations.
- 4. Superiisors, 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 respec'tive superintendent or superintendent's clerks.
S. The superintendents or their clerks, Senior QA Engineer, and the Construction
. Project Manager, after receiving accounts from their section heads shall report to the Superintendent of Administration who in turn, after receiving these reports shall notify the Emergency Coordinator (Station Manager or Shift Supervisor) All individuals onsite 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 S'ite Assembly.
After a Site Ass,embly is completed and a plant emergency condition continues to exist, accountability of all personnel onsite will be maintained by i individual supervision.
I NOTE: Commencing fifteen (15) minutes after initiation of a Site Assembly, the Superintendents, Senior QA Engineer, and the Construction Project Manager should begiu 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.
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- 6. Search and rescue of missing personnel will be at the discretion of the Emergency Coordinator, and shall take into account the emergency situations 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 responsibl* for the personnel in his group, and shall report to the Shift Supervisor when all personnel are accounted for.
- 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.
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IMPLEMENTATION - SITE EVACUATION
- 1. As per Step 3 of Responsibility for Implementation, 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 non-essential personnel are to:
(1) proceed to: "
Training Center /Cowans Ford Dam (2) proceed offsite/home."
- 3. Repeat Step 2 in full.
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,O 4. If deemed. necessary by the Emergency Coordinator or Shift Supervisor, request a
the Mecklenburg County Police to assist in traffic control near and around McGuire Nuclear Station and to assist in the control of boating areas on Lake Norman within the exclusion area. (See Enclosure 3) (Station Security will work with the County Police in directing traffic to the svacuation 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:
4 (1) In the event road conditions (severe weather) or a release of radioactive saterials 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 contamination of the site area, the Emergency Coordinator i
say 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 accordan e with Station Health Physics Manual, Section 18.3 (Personnel Monitoring for Emergency Conditions).
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- 7. Nuclear Production Superintendents, the Senior QA Engineer, and the Construction Project Manager shall account for their personnel at the
[ evacuation facility and report to the Superintendent of Administration who
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will'in turn inform the Emergency Coordinator of the evacuation status.
NOTE: Commencing thirty (30). minutes after initiation of a Site Evacuation, the Superintendent of Administration shall begin personnel status reports to the Emergency Coordinator. These status reports should be continued at fifteen (15) minute intervals until all personnel are evacuated and accounted for.
- 8. After normal working hours, on weekends, 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 Emergency Coordinator when all evacuated personnel are accounted'for.
- 9. The Emergency Coordinator in coordination with the Recovery Manager at the Crisis Management Center will provide instructions to Nuclear Production and Construction supervision regarding the further disposition of evacuated personnel.~ In the event evac :ated personnel must remain at the evacuation facilities for an extended period of time, the Recovery Manager shall provide for their care and disposition.
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- 10. When the emergency condition requiring Site Evacuation no longer exists, the Emergency Coordinator shall secure frca the Site Evacuation. '
l ENCLOSURES l
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- 1. Assembly. Points l 2. Evacuation Routes to Training and Technology Center and Cowan's Ford Das I i 3. Telephone List
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's STATION DIRECTIVE 3.8.1 '
ENCLOSURE 1 ASSEMBLY POINTS WITIIIN OiTTSIDE RESPONSIBLE I' GROUP PROTECTED ARE.'. PROTECTED AREA SUPERVISION A. Operations Operation's Office Operations Admin. Shift Supervisor Building Office e
NOTE: Control Room Operators remain on station.
B. Admin Services
- 1) Administrative PAP at Exit Cooridor Training Room (Admin. Bldg.) Superintendent of Personnel and Administration
, Training Services
- Personnel
- 2) K-Mac Vending Trailer 4 Training Room (Admin. Bldg.) K-Mac Supervisor (Unit #1 Turb. Bldg.) {
- 3) Security Security Office Assembly ! Training Room (Admin. Bldg.) Sec. Shift Lieut.
Room (CAS, SAS,and PAP f Remain on Post) i
- 4) Visito rs Escorted - with escort i Training Room (Admin. Bldg.) Cont. Services Coord.
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(Includes all { (Visitors outside the personnel DNSITE protected area) i 8 j not assigned to j a Station Group) 1 NOTE 1: Visitors assigned unescorted access shall be assigned to a responsible grcup by security personnel during l
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STATION DIRECTIVE 3.8.1 i ENCLOSURE 1 ASSE?BLY POINTS W11HIN OUTSIDE RESPONSIBLE GROUP PROTECTED AREA PROTECTED AREA SUPERVISION initial badging procedure. The responsible group shall '
provide accountability for these visitors.
1 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 Licensing, NRC Personnel Onsite
- 2) Performance Performance, Trailer Superintendent's Office Performance Supv.
- 3) Chemistry CT Lab Superintendent's Office Statica Chemist
- 4) llealth Physics llP Lab Auxiliary Count Room Sta. Health Phys.
NOTE 1: If radiation levels within the llP Lab are excessive, Ilealth Physics shall report to llP trailer.
NOTE 2: If the emergency has radiological implications, Ilealth l Physics escorts shall take their viritor to the PAP.
D. Maintenance
- 1) Hechanical Assembly Room in Shop ' Superintendent's Office Haint. Engineer 1
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STATION DIRECTIVE 3.8.1 ENCLOSURE I ASSEMBLY POINTS WITHIN OUTSIDE RESPONSIBLE GROUP PROTECTED AREA PROTF.CTED AREA SUPERVISION (SMS, SSD) *
- 2) I&E I&E Shop Superintendent's Office I&E Engineer
- 3) Planning Planners Office Superintendent's Office Planning Engineer i
NOTE: Any Transmission Departament Personnel assigned to the Station Maintenance Department shall assemble with the group / crew they are assigned to.
E. QA Office Above CT Lab Senior QA Engineer's Office I
QA Q.A. Engineer F. Construction lione Base Headquarters Home Base Ieadquarters Construction Ngr.
. G. Station Hanager Control Room Manager's Office Station Hanager I
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STATION DIRECTIVE 3.8.1 ENCLOSURE 3 A ~~" ~
y TELEPHONE LIST -
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1 g A. Mecklenburg County Police - 374-3333 i
j B. Superintende t 4 Adssinistration -4221 or 4451 a
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