ML20079K439
| ML20079K439 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 12/07/1982 |
| From: | Glover M DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20079K425 | List: |
| References | |
| PROC-821207-01, NUDOCS 8301070488 | |
| Download: ML20079K439 (119) | |
Text
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- t. Form 34731 (1041) 1 (Formerly SPD-10021) ! 7, .. ,y 3,, , ,
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DUEZ POWER C0hPANT (1) ID No: EP/0/A/5000/05 PROCEDU3E PREPARATION Change (s) O to PROCESS RECORD 0 Incorporated (2) STATION: McGuire Nuclear Station (3) PROCEDURE TITLE: Naeff4rneiem af Ununn=1 Event A .I At (4) PREPARED LY:
UMW etike Glover DATE: December 3, 1982 (5) REVIEWED BY: m_ rL.Jt3 DATE: I Z ~T'Ib Crose-Disciplinary Review By: N/R: Y (6) TEMPORARY APPROVAL (IP NECESSARY):
By: (SRO) Date:
s Ry: Data:
(7) APPROVED BY: A Date:_ /2 - 7' 2 E ^
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(8) MISr rT.T AMEOUS:
Reviewed / Approved By: Date:
Reviewed /ipproved By: Date: ^
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O 8301070488 830103
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PDR ADOCK 05000369 -
F P. D R O
EP/0/A/5000/05 Page 1 of 3
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DUKE POWER C0hPANY
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. , , ., McGUIRE NUCLEAR STATICN 37EIFICATICN OF_ UNUSUAL. EVENT .
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1.0 Symptoms -
1.1~ This condition exists whenever unusu'l a events are in process or have cecurred which indicata a potential degradation of the level of safety of the plant. ,-
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2.0 Inmedlate Actions ,
- 2.1 Autos.atic ,,-
None
, 2.2 Manual 4
2.2.1 h Shift Supervisor shall be informed of all hvents initiating this procedure. p
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s 3.0~ Subsequent-Action ,
Initial /N/A
/ 3.1 h Shift Supervisor shall assure that,the appropriate emergency
[. - condition (Notification of Unusual Event, Alert, Site Area
~] Emergency, or General Emergscy) is declared by evaluating the 7 actual plant condition with Enclosure 4.1 Emergency Classification Flowchart and /melesure 4.2. List of Initiating Conditions, Emergency Action suvels, and Associathd Emergancy Procedure /
Document.
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'/ 3.2 h Shift Supervisor shall assure that alh. actions required by the j initiating Emergency Procedure will be performed and that all actions necessary for the protection of persons cnd property are being taken.
NOTS l
If at any time in the course of events in this procedure, site avscuation or persoinal assembly / accountability appears nece'ssary, refer to Station Diractive 3.8.L.
! /
_/ 3.3 h Shift Supervisor shall assume the function of the Emergency Coordinator until the arrival of the Station' Manager or his designee at which time.the Station Manager or his designee assumes the responsibility of the Emergency Coordinator.
.5
s i EP/0/A/5000/05.
Eage 2 af 3 i
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. k) / 3.4 The Emergency Coc;dinator shall assure prompt (within about i
15 minutes of declaring the emergency) notification of the ,
North Carolina State and Local County Wrning Points indicated on Enclosure 4.3. He shall also assure notification of all other personnel listed in Enclosure 4.3.
'Q NOTE 1.
See Enclosure 4.4,-Telephone Listing, for notification, telephone numbers / radio codes /pager codes.
NOTE 2.'
See Enclosurs 4.5, Notification of Emergency Conditions, for .
information to be provided to State / County Warning Points.
NOTE 3.
See Enclosure 4.6, Emergency Plan Message Format for information to be provided to Nuclear Production Duty Engineer.
/ 3.5 In the event a release or potential release of radioactive materials is a threat to plant personnel or members of the.
I general public the Emergency Coordinator shall requesc Health Physics personnel to evaluate the consequences utilizing the appropriate Health Physics procedure, HF/0/B/1009/05, HP/0/B/1009/06, HP/0/B/1009/08. HP/0/B/1009/09 or HP/0/B/1009/10.
/ 3.6 The Emergency Coordinator shall provide protective action ,
recommendations as necessary to the affected. county' warning, [ ,
point (s) and to the North Carolina warning point (Faergency
.., D l
Operations Centers if estab}.ished) o'r the State Radiolo31 cal ~
Protection Section Department of m==n Resources \(see Enclosure 4.4 Telephoea Listing) as directed by the state in accordance with tha-North Carolina Radiological Emergency Responsa Plan. If actual '
release of rsdioactive matarials'will result in a projected dose o p-l (REM) to the population of: (EPA Protective Action Guidelines). s J.o.1 Whole body <1, thyroid <5, NO protective action is required. Monitor anvironmental radiation levels to l verify.
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l ilhole body 1 to <5, thyroid 5 to <25, recommend seeking j
(O 3.6.2 shelter and wait for further instructions. Consider
- evacuation particularly for children and pregnant women.
Monitor environmental radiation levels. Control access l , ,
((p to affected areas.
- ' + 3.6.3 ilhole body 5 and above, thyroid 25 and above, recommend i .% mandatory evacuation of populations in the affected
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j areas. Monitor environmental radiation levels and v
adjust area for mandatory evacuation based on these
\ v i 1evels. Control access to affected areas.
i NOTE i .,
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See Enclosure 4.4, Telephone Listing for
- notification.
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l /I 3.7 h Emergency Coordinator shall augment on shift resources to N'
Ta t assess and respond to the emergency situation as needed to ensure g- _
the protection of persons and property.
r S N '/ 3.8 The Emergency Coordinator will assess the Emergency Condition and i
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determine the need to remain in a Notification of Unusual Event'
% + escalate to a more severe class or close out the emergency.
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3_. 9 h Projects and Licensing Engineer or his designee will close out the Emergency with verbal sumary to county and State authorities, notified in Step 3.4, 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 '
d; ,;N '4.1 Emergency Classification Guide Flowchart J' '
' 4.2 List of Initiating Conditions, Emergency Action Levels, and Associated Emergency Procedure / Document.
4.3 Notifs):stion Chart s ,.
i . ._ 4. 4 Tele' phone Listing 1 4'. 5 Notificatirn of Emergency Conditions.
4.6 Es.orgency Plda Message Format
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. i ' j I / EP/0/A/5000/05 l Enclosurs 4.2 Page 1 of 5 LIST OF INITIATING CONDITIONS. ENERGENCY ACTION LEVELS. AND
? ASSOCIATED ENERGENCY PROCEDURE / DOCUMENT I Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document i
4.2.1 Emergency Core Cooling Safety Injection signal verification EP/1/A/5000/01. EP/1/A/5000/02
, Initiated (SI) and by redundant indication and indication EP/1/A/5000/03. EP/1/A/5000/04
. - discharge to vessel has of discharge to vessel. AP/1/A/5500/35 j( ,
occurred.
4.2.2 Radiological effluent EHF49, 50, 35. 36, 37 Alarm indicating Tech Space 3/4.11. Environmental Technical Specification Technical Specification Limits exceeded. Tech Specs. HP/0/5/1009/09, limits exceeded. HP/0/5/1009/10. HP/0/5/1009/05 4.2.3 Fuel Damage Indications
- a. High coolant activity a. >l pC1/ gram Dose Equivalent I-131 or AP/1/A/5500/18 ~
sample exceeding Tech. >100 pC1/ gram gross activity.
Specs. E-NOTE: These calculations avail-able from counting fact-
.tity on request.
- b. Failed fuel monitor b.' Increase in I-131 concentration by indicates Hechaatcal Clad 7pC1/mi over a 30 minute period. or.
Failure greater than 11 to 51 1-131 concentration is in the range or 0.11 equivalent fuel .of 70pC1/m1 to 350 pCi/ml verified by failures within 30 minutes. increased EMF-48 readings and labora-tory analysis. .
4.2.4 Abnormal coolant tempera- Figure 2.1-1 Tech Specs exceeded AP/1/A/5500/05 ture and/or pressure or and Core Subcooling Monitor less abnormal fuel temperature than accaptable. (Below Curve) outside of Technical Speci- Verified as necessary by redundant fication Limits. InstrumentatioA .(e.g. narrow and wide range pressure / temperature subcooling monitors)
('. EP/0/A/5000/05 Enclosure 4.2 i ,
Page 2 of 5 i
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Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document 4.2.5 Exceeding either primary / >lCPM total P/S leakage EP/1/A/5000/02. EP/1/A/5000/04, secondary leak rate >500 GPD from any S/G AP/1/A/5500/10 requiring shutdown by >10GPH Identified Primary 1.eakage i Tech. Specs. or primary leak Verified by EHF readings. level control, rate requiring shutdown by make-up rate, and or chemical / radiological Tech. Specs. ,
analysis.
4.2.6 Failure of a safety or Valid accoustical monitor indica- EP/1/A/5000/02. AP/1/A/5500/11 relief valve in a safety tion of valve failure. EP/1/A/5000/03 related system to close, following reduction of applicable pressure. (Pri-a mary System (NC) or Hain Steam (EN).
4.2.7 Loss of offsite power or Undervoltage alarms on 7KV buses AP/1/A/5500/07
. loss of onsite AC power or blackout load sequencers capability. actuated.
- 4.2.8 Loss of contai.nment inte- Any automatic containment isolation AP/1/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 j on a lock inoperable, cg; penetration (s) fail leak test per Tech Specs when con-tainment integrity required.
4.2.9 Loss of engineered safety ESF actuation system found inoperabic AP/1/A/5500/19. AP/1/A/5500/21 feature or fire protection cg; Fire Suppression Water System AP/1/A/5500/20 Tech Specs system function requiring found inoperable per Tech Specs. 3/4.5. 3/4.7.10, 3/4.7.11 shutdown by Tech Specs (e.g., malfunction, personnel error, or procedural inadequacy). .
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!f Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document l-f l 4.2.10 Fire within the plant Observation or fire detection alarm Station Directive 2.11 lasting more than 10 with confirming observation of a
- j. minutes.
fire lasting more than 10 minures.
, 4.2.11 Indications or alarms on Loss of process or affluent radiation OP/0/A/6700/03 Tech Specs 3/4.3 -
process or affluent para- monitoring system fut Loss of all meters not functional in meteorological instrumentation onsite Control Room to an extent cg; Loss of all radio / telephone communi-requiring plant shutdown cationa capability offsite.
- or other significant loss of assessment or communica-tion capability (e.g., all meteorological instrumenta-tion, or radio networks). -
4.2.12 Security threat or As notified by Security Force. Station Security Plan attempted entry or attempted sabotage.
4.2.13 Natural phenomenon being experienced or projected beyond usual levels.
i
- s. Any earthquake felt (<.08gH. <.0533 V). Annunciator Alarm.
in plant or detected (AD-13) on station seismic in-
! strumentation.
- b. 50-year flood or low As observed l
water, hurricane surge, seiche (lake- tidal wave)
- c. Any tornado on site As observed . .
- d. Any hurricane Winds >73 mph /from National Weather- AP/0/A/5500/29. AP/0/A/5500/30 Service luformation.
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b/ EP/0/A/5000/05 Enclosure 4.2 Page 4 of 5 Initiating Conditions Emergency Action Level (EAL) Faergency Procedure / Document 4.2.14 Other hasards being ex-parienced or projected.
- a. Aircraft crash onsite As observed or unusual aircraft activity over facility.
- b. Train derailment on As observed site.
- c. Near site or onsite As observed explosion.
- d. Near site or onsite As observed AP/0/A/5500/31 toxic or flannable gas release.
- a. Turbine rotating com- . Turbine trip and observation of AP/0/A/5500/23. AP/0/A/5500/32 ponent failure causing a turbine malfunction or failure. AP/0/A/5500/02 rapid plant shutdoun (Loss of Condenser Heat Sink).
4.2.15 Other plant conditions As determined by the Shitt Supervisor / As directed by plant conditions exist that in the judge- Emergency Coordinator.
ment of the Shift Supervisor, the Operations Duty Engineer, the Superintendent of Opers-tions, or the Station Manager warrant increased awareness on the part of State and/or local offsite authorities or require plant shutdown under ,
Tech Specs requirements and-involve other than normal con-trolled shutdown (e.g.. cool-down rate exceeding Tech Specs limits, pipe cracking found during operation).
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N'i EP/0/A/5000/05 Enclosure 4.2 j
' Page 5 of 5 Initiating Conditions faargency Action Level (EAL) Faergency Procedure / Document 4.2.16 Transportation of contami- As observed. AP/0/A/5500/27 nated injured individual from site to offsite hospital.
4.2.17 Rapid depressurization of As observed and actuation of 4.2.1 AP/1/A/5500/06 4 secondary side, and 4.2.6 above.
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c, vim iuvuiv5 Enclosura 4.4 P;ga- I cf 2 TELEPEONE LISTING
~4.4.1 Operations Duty Engineer (PA System)
P&T Pager -
4.4.2 - Station Manager Home - - System Speed -
Home - System Speed -
4.4.3 ' Superintendent of Operations -
Hone - System Speed 4.4,.4 Superintendent of Technical Services -
Home . System Speed 4.4.5 ; Projects & Licensing Engineer -
Home . - System Speed -
4.4.6 Nuclear Production Duty Engineer . ' - System Speed -
PST Pager.
4.4.7 NC State Warning Point, Raleigh - __ __,- System Speed 4.4.8 Mecklenburg County Warning Point - Primary: Rine 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 Spee/
- Back-up
- Emergency Radio, Code: ,
4.4.10 Catawba County Warning Point - Primary: Rine Down Phone Back-up:
. System Speed' Back-up: Emergency Radio, Code: ,
4.4.11 Iredell County Warning Point - Primary: Rina Down Phone Back-up: - System Speed Back-up: - Emergency Radio. Code: ,
4.4.12 Caston County Warning Point - Primary: Ring Down Phone Back-up: - System Speed Back-up: Emergency ' Radio, Code: ,
4.4.13 Cabarrus County Warning Point - Primary: Ring Down Phone Back-up: . - System Speed Back-up: Emergency Radio, Code: ,
NOTE Radio Code will activate all county radio units.
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,- 4.4.14 N.R.C. Operation Center, Emergency Notification System (ENS phone) 4.4.15 .N.R.'C. . Station Representative _ (Orders) ,
'Offica Office
'Ecce -
P&T Pager .
Page'from Central (MNS Area) or from Southern (ONS Area) -
4.4.16 Construction Protect Manager: Construction
- System Speed Bone system Speea 4.4.17 Station Health Physicist -
Home -
System Speed -
P&T Paget .
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4.4.18 Station Safety Supervisor i Home - - ' System Speed - (
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4.4.19 Superintendent of Maintenance s, . . -
i i Home .
System Speed - !
i 4.4.20 Superintendent of Administration i Home - - System speed -
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4.4.21 Radiation Protection Section Department of Human Resources k ,\) - . ,
System Speed -
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4 E.21 Q1 Al bdGdi db Enclo:uro 4.5 Page 1 of 4 ucnnian uncLEAa RTATTf4 NOTIFICATION OF EMERGENCY CONDITIONS
+ 4.5.1 Include as a siniansa, the following information to the North Carolina State Warning Point, and the six County Warning Points (Mecklenburg, Catawba, Iredell', Lincoln, Gaston, and Cabarrus).
NOTE 1: See Enclosure 4.4, Telephone Listing NOTE 2: A. Complete Part I of this format as a minimal first notification of'a reportable incident.
B. Complete Part I and II of this format to provide minimal follovup information.
PART I: Initial Emergency Massage Information [ACENOWLEDGEMENT i
TELEPHONE RESPONSE: Mecklenburg "This is McGuire Nuclear Station. Iredell Please acknowledge when you are Lincoln ready to copy Emergency Information." Cabarrus Gaston
- 1. This is McGuire Nuclear Station. Catawba
- 2. My nans is: .
- 3. This message (Number '):
--- a. Reports a real emergency.
- b. Is an exercise message..
- 4. My telephone number / extension is: .
- 5. Massage Authentication: .
- 6. The class of emergency is:
- a. Notification of an Unusual Event
- b. Alert
- c. Site Area Emergency
- d. General Emergency
- 7. This Classification of Emergency was declared at: /on .
AM/PM DATE
- 8. The initiating event causing the Emergency Classification is:
, l 4
- 9. The Emergency Condition:
- a. Does not involve the release of radioactive materials from the plant.
- b. Involves the POTENTIAL for a release, but NO release is occurring.
- c. Involves a release of radioactive material. .
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L2101At500G105 Enclosura 4.5 Pcgn 2 of 4
- 10. We recommend the following protective action:
- a. No protective action is recoinnended at this time.
- b. People living in zones remain
. indoors with doors an'd windows closed.
- c. Pecple 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.
Other recommendations:
f.
- 11. There will be:
- a. A followup message
- b. No further comennications
- 12. I repeat, this message:
- a. Reports an actual emergency.
- b. Is an exercise message.
- 13. Relay this information to the persons indicated in your alert pro-cedures for an incident at McGuire Nuclear Station.
NOTE: Record the Name, Title, Date Time, and Warning Point at end of Part II.
l PART II: Followup Emeraency Massaae Information l 1. The type of actual or projected release ist
- a. Airborne
- b. Waterborne
- c. Surface spill
- d. Other
- 2. The source and description of the release is:
i
- 3. a. Release began /will begin at a.m./p.m.; time since l
reactor trip is hours,
- b. The estimated duration of the release is hours.
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32sV/A/60ud/V3 Encloruro 4.5 Pega 3 of 4 l, 4. Dose projection base data:
Radiological release: curies, or curies /sec.
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Wind speed: mph Wind direction: From Stability class: (A.B.C.D.E.F. or G) e Release height: Ft.
Dose conversion factor: R/hr/Ci/Ms (whole body) t R/hr/C1/Ms (Child Thyroid)
- l. Precipitation Temperature at the site: "F
- 5. Dose projections:
- Dose Commitment
- l Distance Whole Body (Child Thyroid)
Ram / hour Rem / hour of inhalation Site Boundarv 2 miles
, 5 miles i 10 miles
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- Projected Integrated Dose In Ram
- Distance Whole Body Child Thyroid Site Boundarv 4
1 2 miles 5 miles 4 10 miles
- 6. Field measurement of dose rate or contamination (if available):
- 7. Emergency actions underway at the facility include:
- 8. Onsite support needed from offsite organizations:
- 9. Plant status:
- a. Reactor is: not tripped / tripped
- b. Plant is at: % power / hot shotdown/ cold shutdown / cooling down
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} c. Prognosis is: stable / improving / degrading / unknown.
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EP/0/A/5000/05 Enclorura 4.5 nage A .af =4
- 10. I repeat, this message:
, a. Reports an actual emergency,
- b. Is an exercise message.
- 11. Do you have any questions?
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- END OF FOLLOW-UP MESSAGE ***
NOTE: Record the name, title, date, time, and warning point notified.
(1) Co - nicacor l
(Name) (Title) l Mecklenburg (Data) (Time) (Warning Point)
(2) Communicator (Name) (Title)
Gaston
, (Date) (Time) (Warning Point)
(3) Communicator (Name) (Title)
-- , Iredell i j (Warning Point)
(Date) (Time)
(4) Communicator (Name) (Title)
Catawba (Data) (Time) (Warning Point)
(5) Co - icator (Name) (Title)
Lincoln (Data) (Time) (Warning Point)
(6) Communicator (Name) (Title)
Cabarrus (Date) (Time) (Warning Point)
(7) Communicator (Name) (Title)
North Carolina (Data) (Time) (Warning Point)
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_e , e , .u ww , o, Enciccurs 4.6 Pags 1 cf 1 EMERGENCY PLAN MESSAGE FORMAT ,
D, (Nuclear Station to Nuclear Production Duty Engineer)
- 1. This is at McGuire Nuciaar 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 precedure description as possible together with station parsmaters used to determine emergency status) 1 4 Corrective Measures Being Taken:
v i
- 5. There Have/Have Not been any injuries to plant personnel. ;
j
- 6. Release of radioactivity: Is/Is not taking place, and is/is not affecting the Crisis Management Center.
- 7. No, State Yes _ No, Counties Yes No, NRC _ Yes l have been notified.
! 8. The Crisis Management Team should/should not be activated. Corporate Communications and Company Management should be notified (Unusual Event Only).
1
- 9. I can be reached at for follow-up information.
(Telephone Number) j 10. Additional Connants:
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" Form 34731 (1041)
(Formerly SPD 10021)
DUKE POWER COMPANT (1) ID No: EP/0/A/5000/06 PROCEDURE PREPARATION Change (s) v to PROCESS RECORD 0 Incorporated i (2). STATION: McGuire Nuclear Station i
l (3) PROCEDURE TITLE: n..
'l ' 1 l
(4) PREPARED BY:
Whww. m _. DATE: me k=v 1. 1982 ,
(5) REVIEWED BY: u--
rhid DATE: /7 -E- fL Cross-Disciplinary Review By: N/R: EI (6) TEMPORARY APPROVAL (IF NECESSARY):
By: (SRO) Date:
By: Datas (7) APPROVED BY: 2 Dato: /8 "~/-8 d- .
(8) MISCELLANIQUS:
Reviewed / Approved By: Date:
Reviewed /Appecreed By: Date:
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EP/0/A/5000/06 P g3 1 cf 4 DUKE POWER COMPANY
, ] McGUIRE NUCLEAR STATION
, AT.RRT 1.0 Symptoms 1.1 Events are in process or have occurred which involve an actual'or i
potential substantial degradation of the level of safety of the plant.
2.0 Immediate Action 2.1 Automatic None 2.2 Manual 2.2.1 The Shift Supervisor shall be informed of all events initiating this precedure.
3.0 Subsequent Actions Initial / N/A
/ 3.1 The Shift Supervisor shall assure that the appropriate emergency condition (Notification of Unusual Event, Alert, Site Area Emergency, or General Emergency) is declared by evaluating the acutal plant condition with Enclosure 4.1 Emergency Classifi -
. cation Flowchart and Enclosure 4.2 List of Initiating Conditions.
Emergency Action Levels, and Associated Emergency Procedure /
Document. ,
/ 3.2 The Shift Supervisor stiali ensure that all actions required by the initiating Emergency Procedure will be performed and that all actions necessary for the p'rotection of persons and property are being takan.
NOTE If at any time in the course of events in this procedure, site evacuacion or personnel assembly / accountability appears necessary, refer to Station Directive 3.8.1.
/ 3.3 The Shift Supervisor shall assume the function of the Emergency Coordinator until the arrival of the Station Manager or his designee, at which time the. Station Manager or his designee assumes the responsibility of the Emergency Coordinator.
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EP/0/A/5000/06 l P:33 2 cf 4 l l
/ 3.4 The Emergency Coordinator shall assure prompt (within about 15 l ainutes of declaring the emergency) notification of the North l 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 4
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, Telephona Listing, for notification, telephone numbeta/rsdio codes /pager codes.
NOTE 3 See Enclosure 4.5, Notification of Emergency Conditions, for information to be provided to State / County Warning Points.
/ 3.5 The Emergency Coordinator in direct contact with the Technical Support Center and the Crisis Management Center will assess and respond to the emergency by:
3.5.1 Dispatching onsite monitoring tasas with associated' co==m4 cations equipment.
3.5.2 Providing periodic plant status updates to offsite authorities (at least every 15 minutes).
3.5.3 Providing periodic meteorological assessments to offsite I
suthorities and, if any releases are occurring, 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 Energency Coordinator shall request Health Physics personnel to evaluate the consequences utilizing the appropriate Health Physics procedure, HP/0/B/1009/05. HP/0/3/1009/06 HP/0/B/1009/08, r
,] HP/0/3/1009/09, or HP/0/B/1009/10.
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EP/0/A/5000/06 Pzg3 3 of 4 I / ~3.6 The Emergency Coordinator shall provide protective action recomendations as necessary to the affected county warning point (s)
[
- .and to the North Carolina warning point (Emergency Operations Centers if established) or to the state Radiological Protection Section, Department of mnnan Resources (See Enclosure 4.4, Telephone Listing) as directed by the state in accordance with the North Carolina Radiological Emergency response plan. If evaluation indicates that a potential for 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, ree m d 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
, y, mandatory evacuation of populations in the affected areas.
Monitor environmental radiation levels and adjust area
' for ==adatory evacuation based on these levels. Control access to affected areas.
NOTE See Enclosure 4.4 for Telephone Listing for i
notification.
/ 3.' 7 The Emergency Coordinator in coordination with the Recovery Manager at the Crisis Management Center, will assess the emergency condition and determine the need to remain in an Alert Status, escalate to a more severe class, reduce the emergency class or close out the emergency.
/ 3.8 The Station Manager or his designee will close out the Emergency with a verbal summary to County and State authorities notified in Step 3.4, 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 />.
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-EP/0/A/5000/06 Paga 4 of 4 4
l 4.0 Enclosures 4.1 Faergency Classification Guide Flowchart
[
V 4.2 List of Initiating Conditions, Emergency Action Levels, and Associated i
Emergency Procedure / Document.
4.3 Notification Chart.
4.4 Telephone Listing.
4.5 Notification of Emergency Conditions.
4.6 Emergency Plan Message Formet 1
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- , V} Enclosure 4.2 Page 1 of 5
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LIST OF INITIATING CONDITIONS ENERGENCY ACTION LEVELS AND
[
i : ASSOCIATED EMERGENCY PROCEDURE / DOCUMENT Initiating Conditions Emergency Action Level (EAL) Emergency Procedure /Documsut 4.2.1 Severe loss of fuel a. Very high coolant activity cladding Mechanical sample indicating an increase of l Clad Failure. 70pci/m1 in 30 minutes or 350 to 1.750pC1/mi total 1-131 Coolant ,
i Activity.
i
- b. Failed fuel monitor (EHF-43) or Tech Specs 3/4.6.7 lab analysis indicates increase greater than 11 fuel failures within 30 minutes or 51 to 251 total fuel failure.
l 4.2.2 Rapid gross failure Pressuriser low pressure alarm and EP/1/A/5000/04. AP/1/A/5500/07 of one Steam Generator reactor trip and, pressurizer low i , tube with loss of off- level alarm and pressuriser low site power. pressure safety injection signal and, undervoltage alarm on 7KV buses. EHF 32, 33, and 34 Alarm (s).
l 4.2.3 Rapid failure of Steam Several hundred spa primary to EP/1/A/5000/04
]
Generator tube (s). secondary leak rate indicated by
- a. as above in 4.2.2 for pres-
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suriser and EHF indicators.
- b. Steam generator level in-L1 creasing in one or more generator (s) and falling in i the others/due to reactor trip.
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M Enclosure 4.2 ' '
Page 2 of 5 i
Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document;
- 4.2.4 Steam line break with Creater than 10 gym. rapidly de- EP/1/A/5000/04. EP/1/A/5000/03 significant primary to creasing reactor coolant Tavg.
secondary leak rate. pressurizer pressure and level -
and,
- 1. Steam line differential l' ~
pressure safety injection signal and increased con-tainment-building pressure /
' if break is in containment.
< 2. High steam flow and to La Tavg or law steam pressure safety injection signal for y
ruptura downstream of MSIV's.
4.2.5 Primary coolant leak Leak >50gpa as indicated by calcu-- EP/1/A/5000/02. AP/1/A/5500/10 rate greater than 50 gpm. lation or other indication. (i.e.,
sump levels) 4.2.6 High radiation levels Increase by a factor of 1.000 in HP/0/3/1009/05 or high airborne con- radiation monitor reading within tamination which in- the station.
i dicates a severe de-gradation in the control of radioactive materials.
4.2.7 Loss of offsite power and Undervoltage alarm on 7KV buses. AP/1/A/5500/07
' loss of all onsite AC and blackout load sequencers power for up to 15 minutes. . actuated.
- I (See Site Area Emergency EP/0/A/5000/07, for ex-tended loss).
, 4.2.8 Loss of all onsite DC DC bus undervoltage alarms on all' Tech Specs 3/4.8.2.3 power. buaea. Tech Specs 3/4.8.2.4-4.2.9 Coolant pump seizure Reactor coolant pump auto trip AP/1/A/5500/04. AP/1/A/5500/08 leading to fuel failure. alarm, and reactor trip on low OP/0/A/6150/14. AP/1/A/5500/05 coolant flow, and failed fuel monitor alarm DfF48.
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EP/0/A/5000/06
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' Enclosure 4.2 Page 3 of 5 Initiating conditions Emergency Action Level (RAL) Emergency Procedure / Document 4.2.10 Complete loss of func- RHR not functional and inability AP/1/A/5500/17. OP/1/A/6100/04 tions needed for plant to sustain natural or forced cir-cold shutdown. culation.
i 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.
i a scram which brings the reactor subcritical.
4.2.12 Fuel damage accident Observation of damage to spent AP/1/A/5500/25 with release of radio- fuel assembly, and activity to containment j or fuel handling building. 1. ENF-16 and 17 alarm.
, 2. EHF-38, 39, 40, or 42 alarm.
Station Directive 2.11 Serias. 'i 4.2.13 Fire potentially affecting Observation of a fire that could safety systems, affect safety systems. Tech. Specs 3/4.5 .
4.2.14 Host or all alarms (annua- As observed. OP/0/A/6350/01A
. clators) lost. ,
4.2.15 Radiological effluents For EMP35 - Low Range offscalg greater than 10 times High Range 1 x 10 cpm Tech Specs instantaneous 6 limits (an instantaneous For EHF36 - Low Range 2 x-10 gym HP/0/B/1009/05
' rate which, if continued High Range 5 x 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 lar at the site boundary under average meteorological conditions or whenever offluent moni-i tors or radiological moni-toring detect these levels).
4.2.16 Ongoing security compromise. As reported by Security force. Station Security Plan
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EP/0/A/5000/06
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/ Enclosure 4.2 .
Page 4 of 5 Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document j
4.2.17 Severe natural phenomena AP/0/A/5500/30 AP/0/A/5500/29 being experienced or projected:
- a. Earthquake greater >0.08gH, >.0533 V. Annunciator Aldra, than Operational (AD-13).
Basis Earthquake Levels
- b. Flood, low water, hur- As observed.
ricane surge, seiche near design levels.
(Lake tidal wave)
- c. Any tornado striking As observed, facility.
- d. Hurricane winds near , As observed (95 mph)/from National design basis level. Weather Service information.
4.2.18 other hazards being ex- AP/0/A/5500/32,AP/0/A/5500/31 perienced or projected. AP/1/A/5500/23
, s. Aircraft crash on As observed.
facility.
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- b. Missile impacts from As observed.
whatever source on facility.
- c. Know explosion damage As observed.
to facility affecting plant operation.
- d. Entry into facility As observed.
environs of toxic or flammable gases.
- e. Turbine failure Turbine trip and observation of causing casing pena- turbine malfunction or failure.
tration.
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EP/0/A/5000/06' i. , ej
- L/ Enclosure 4.2 -d
' ' Page 5 of 5 i !
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( Emergency Procedure / Document i
f Initiating Conditions Emergency Action Level (EAL) .
4.2.19 other plant conditions As determined by Shift Supervisor / As. dictated by Plant Conditions.
- exist that in the judge- Emergency Coordinator.
ment of the Shift Super-t visor, the Operations Duty Engineer, the Superintendent of Opera-tions, or the Plant Manager warrant pre-cautionary activation of the Technical Support Center and near site '
Crisis Management Center.
4.2.20 . Evacuation of control As determined by Shift Supervisor / AP/1/A/5500/17. OP/1/A/6100/04 room anticipated or Emergency Coordinator, required with control of shutdown systems established from local station.
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EP/0/A/5000/06 ;
Encitsurs 4.3 l
~Page 1 ef 1 _
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NOIIFICATION/ ACTIVATION
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AURT 1 i
Notify / Activate the following personnel /cr Eteergency Centers for all Initiating . 1 Conditions listed in Enclosure 4.2. (See Enclosure 4.4 for Telephone Listing)
NUfIPY/ ACTIVATE NOTIPICATION COMPLETE-INITIAL i Shift Supervisor Operations Duty Engineer
. Station Manaaer Superintendent of operations Superintendent of Technical Services Pro 1ects and Licensing Ensineer Station Health Physicist 5
North Carolina State Warnina Foint Mecklenburn County Warning Point i iincoln Count
- Warning Point Catauba Certy Warnine Point Iredell County Warning Point
! Caston County Warning Point Cabarrus Cemty Warning Point N.R.C. via ENS (Red Phone)
N.R.C. Station Representative i Construccion Proiset Manager Superintendent of Maintenance Superintendent of Administration i Activate T.S.C. (Station Directive 3.8.2)
Activate 0.S.C.' (Station Directive 3.8.2)
-Activate C.M.C. (Inclosure 4.6) 6 i
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EP/0/A/5000/06 "
' Enclorura 4.4-4sge '1 wf 6
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TELEPHONE LISTING 4.4.1 Operations Duty Engineer (FA System) '
P&T.Pager -' ,
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- 4. 4. 2 . Station Manager ~
Home -- - System Speed - ' '
'Home - - System Speed -
4.4.3 Superintendent of Operations -
-Home - - System Speed .
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4.4.4 Superintendent of Technical Services - ', '.* ' " ' ~
Home - - System Speed i 4.4.5 Projects and Licensing Engineer - .
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Home - - System Speed I
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4.4.6 Station Health Physicist.-
- Home . - System. Speed - / * -
P&T Pager. , s
'NC State Warning Point, Raleigh
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4.4.8 Mecklenburg County Warning Point - Primary: Ring Down Phone Y i.
Back-up: -
System Speed C' s % '..
Back-up: Emergency Radio,'. Code: ..
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4.4.9 Lincoln County Warning Point - Primary: ' Ring Down Phone f -Q . X
-Back-up: '. Li b-33' stem Speed - i c Back-up: 2msTgee.cy*?.edio, d3 N: -
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4.4.10 Catawba County Warning Point - Primary: Ring Down'? hone Back-up? . _,( *- System Speed:
Back-up: -Emergescy Radie, '
Code: _
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. 4.4.11- Iredell County Warning Point - Primary: 'R W nnwn Fhece,, ,v Back-up: . - SysterrSpeed -
s Back-up: Emergency Radio ' Code: _
4.4.12 Caston County Warning Point - Primary: Ring Down Phone , , 3 Back-up: . - System Spud *'-
.Back-up: Emergency Radio, Code: M ^\.s',
N'A . ,
. 's , N 4.4.13 Cabarrus County Warning Point - Primary: Rine Dcwn ? hone) - ,
' y Back-up: , 07 stem Speek .-
Back-up: Emergency Radio, Code: _e - '"
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NOTE s Radio Code will activate 1- , ,.
all county radio units. *
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- Enclo:ura 4.4 2
- s. -- Page .2 of
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TELEPHONE LIST
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s th? '4.4.14 N.R.C.' Operation Center, Emergency Notification System (ENS Phone) e N.L^.I:. Station Representative (Orders) f.I 4'.4.15 ,
c Office Office i L Home -
} P&T Pagar -
i Page from Central (MNS t.rea) -
or from Southern (ONS Area) - -
i 9.4.16 Construction Project Manager Construction . Ext.
Home : . - System Speed - or
- f 3 . Systens Speed -
.s y 0.4.17 Supe intendent of Maintenance
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Home - - System Speed - ,
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+ 4.4.18 Superintendent of Mministratio-
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Home - - System Speed - ,
Nuclear Production Duty Engineer - System Speed '
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4.4.20 Radiation Protection Section, Department of Human Resources-7, 4 , . . - System Speed -
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EP/0/A/5000/06 r,
Enticouro 4.5 J! age 1 af 4 McGUIn NUCLEAR STATION
' NOTIFICATION OF EMERGENCY CONDITIONS N
4.5.1 Include an a minimiss, the following information to the North Carolina State Warning Point, and the six County Warning Points, (Mecklenburg, Catawba Iredell, Lincoln, Gaston, and Cabarrus).
! NOTE 1: See Enclosure 4.4, Telephone Listing i NOTE 2t A. Complete Part I of this format as a minissi first notification of a reportable incidant.
i B. Complete Part I and II of this format to provide i
minimal followup informatica.
PART It Initial Emertency Messate Information / ACKNOWLEDGEMENT TELEPHONE RESPONSE: Mecklenburg i>
"This is McGuire Nuclear Station. Iredell f' Please acknowledte when you are Lincoln ready to copy Emersency Information." Cabarrus Gaston i
i 1. This is McGuire Nucisar Station. Catawba ,
- 2. My name is: .
3 A 3. This message (Number J:
- s. Reports a real emergency.
I
- b. Is an exercise message.
! 4. My telephone number / extension is: .
t e 5. Message Authentication .
- 6. The class of emergency ist i s. Notification of in Unusual Event
- b. Alert
- c. Site Area Emergency lj
- d. General Energency
- 7. This Classification of Emergency was declared at: /on .
AN/PM DATE The initiating event causing the Emergency Classification is:
8.
i
- 9. The Energency Condition:
7
- a. Does not involve the release of radioactive materials from the plant.
- b. Involves the PorENTIAL for a release, but NO release is occurring,
- c. Involves a release of radioactive material.
j . .
l EP/0/A/5000/06 Enciscura 4.5 Page 2 of 4 i
^ 10. We recommend the following protective action:
.c a. No protective action is recommended at this time.
j
- b. People living in zones remain ,
indoors with doors and windows closed.
- c. People in zones ETACUATE their homes and businesses.
- d. Pregnant women and children in zones remain indoors'with the doors and windows closed.
I e. Pregnant women and children in zones evacuate to the nearest shelter / reception center.
l ,
- f. Other rec e dationes
(
- 11. There will be:
- a. A followup message
- b. No further communications
- 12. I repeat, this message:
- a. Reports an actual emergency.
- b. Is an exercise message.
13. Relay this information to the persons indicated in your alert pro-l cadures for an incident at McGuire Nuclear Station.
NOTE: Record the Name. Title, Date, Time, and Warning Point at and of Part II.
PART II: Followup F.marsency Messaae Information
- 1. The type of actual or projected release is:
- a. Airborne
- b. Waterborne
- c. Surface spill
- d. Other
- 2. The source and description of the release is:
- 3. a. Release began /will begin at a.m./p.m.; time since reactne trip is hours.
. b. The estimated duration of the release is hours.
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I EP/0/A/5000/06
)l Enciesurs 4.5 l .
2 age 3 of 4
- 4. Dose projection base data:
Radiological release: curies, or curies /sec.
\
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v' Wind speed: aph Wind direction: Frou Stability class: (A.B.C.D.E.F. or G) l Release height: Ft.
l Dose conversion factor: R/hr/Ci/Ms (whole body) 1/hr/C1/Ms (Child Thyroid)
Precipitation Temperature at the site: 'F
- 5. Dose projections
I
- Dose Commitment
- i Distance Whole Body (Child Thyroid) t l Emm/ hour Rea/ hour of inhalation Site Boundary l
2 miles 5 miles 10 miles
- Projected Integrated Dose In Ram
- Distance ? hole Body Child Thyroid i1 ll Site Boundari 2_ miles 5 miles 10 miles
- 6. Field measurement of dose rate or contamination (if available):
- 7. Emergency actions underway at the facility include:
- 8. Onsite support needed from offsite organizations:
- 9. Plant status:
- a. Reactor is: not tr<pped/trfpped
- b. Plant is at: % power / hot shutdown / cold shutdown / cooling down
_- c. Prognosis is: stable / improving / degrading /unknavn.
- O
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EP/0/A/5000/06 Encleeuro 4.5
. Rage, 4 of. 4 3 10. I repeat, this message:
/ a. Reports an actual emergency.
- b. Is an exercise message.
- 11. Do you have any questions?
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- END OF FOLLOW-UP MESSAGE ***
NOTE: Record the name, title, date, time, and warning point notified.
(1) Communicator (Name) (Title)
Mecklenburg (Date) (Time) (Warning Point)
(2) Communicator (Name) (Title)
Caston (Data) (Time) (Warning Point)
(3) Cosaunicator
- (Name) (Title)
Iredell
, (Date) (Time) (Warning Point)
(4) Communicator (Name) (Title)
Catauba (Date) (Time) (Warning Point)
(5) Communicator (Name) (Title)
Lincoln (Data) (Time) (Warning Point)
(6) Communicator (Name) (Title)
Cabarrus (Data) (Time) (Warning Point)
(7) Communicator (Name) (Title)
North Carolina (Data) (Time) (Warning Point) k i
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w .- w o + n s- . qws em O
r.P/0/A/5000/06 1 Enciscurs 4.6 i Pag 2 1 of 1 EMERGENCY PLAN MESSAGE FORMAT
.] (Nuclear Station to Nuclear Production Decy Engineer) x.y
{
l 1. This is at McGuire Nucisar Station.
(Name and Title) l
- 2. This is/is not a Drill. An Unusual Event
. Alert
_ Site Area Pnegency .
General Emergency was declared by the Emergency Coordinator at on Unit Number .
(Time) ,
1
- 3. Initiating Condition: (Give as close to the emergency procedure description as possible together with station paramatars used to determine emergency status) i 1
j I
- 4. Corrective Measures Being Taken:
J
- 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.
5 7. NRC Tes No, State Yes No. Counties Yes No, have been notified.
- 8. The Crisis Management Team should/should noc be activated. Corporate l
Commanications and Company Management should be notified (Unusual Event Only).
l-
- 9. I can be reached at for follow-up information.
(Telephone Number) 1
- 10. Additional Comments:
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O
\ _, / Form 34731 (10-81)
(Formerly SPD 10021)
DUEE POWER COMPANT (1) ID No: EP/0/A/5000/07 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD 0 Incorporated (2) STATION: McGuire Nuclear Station (3) PROCEDURE TITLE: Site Aram harennev
- A*ljg%$n -
(4) PREPARED BY: . ke Glover DATE: December 3, 1982 (5) REVIEWED BY: f50 8/ DATE: (~2. -I~
Cross-Disciplinary Review By: N/R: 7 (6) TEMPORART APPROVAL (IF NECESSARY):
By: (SRO) Date:
h By: Date:
(7) APPROVED BY: Date: /Z - 2 ,9 L l
(8) MISCELIREQUS:
I
- Reviewed / Approved By: Date:
Reviewed / Approved By: Data:
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EP/0/A/5000/07 Prgs 1 cf 4 m
- ', DUKE POWER COMPANY MCGUIRE NUCLEAR STATION SITE AREA EMERGENCY i
l 1.0 Symptoms l.
1.1 Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public.
'2.0 Immediate Action 2.1 Automatic None
, 2.2 Manual l
2.2.1 The Shift Supervisor shall be informed of all events initiating this procedure.
3.0 Subsequent Actions Initial /N/A
/ 3.1 The Shift Supervisor shall assure that the appropriate emergency
( condition (Notification of Unusual Event. Alert, Site Area i
Emergency, or General Emergency) is declared by evaluating the f.
actual plant condition with Enclosure 4.1, Emergency Classification Flowchart and Enclosure 4.2. List of Initiating
! Conditions Emergency Action Levels, and Associated Emergency i
Procedure / Document.
l
/ 3.2 The Shift Supervisor shall ensure that all actions required by the initiating Emergency Procedure will be performed and that all actions necessary for the protection of persons and property are being taken.
NOTE If at any time in the course of events in this procedure, site evacuation or personnel assembly / accountability appears necessary, refer to Station Directive 3.8.1.
l
/ 3.3 The Shift Supervisor shall assume the function of the Emergency Coordinator until the arrival of the Station Manager or his designes at which time the Station Manager or his designee assumes
~
the responsibility of the Emergency Coordinator.
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EP/0/A/5000/07 Paga 2 of 4
/ 3.4 The Paergency Coordinator shall assure prospe (within about 15 1 I
minutes of declaring the emergency) notification of the North .I Carolina State and Local County Warning Points indicated on Enclosure 4.3. He shall also assure notification of all other personnel listed in Enclosure f. 3.
l NOTE 1 ;
l Activation of the Technical Support Center (TSC), Operations Support Center (OSC), shall be in accordance with Station Directive 3.8.2. Activation of the Crisis Management Center l (CMC) shall be in accordance with Enclosure 4.6.
NOTE 2 See Enclosure 4.4, Telephone Listing, for notifiestion, telephone numbers / radio codes /pager codes.
NOTE 3 See Enclosure 4.5, Notification of Emergency Conditions.to be provided to State / County Warning Points.
/ 3.5 The Emergency Coordinator in direct contact with the Technical Support Center and the Crisis Management Center will assess and respond to the emergency by:
3.5.1 Dispatching the Onsite and Offsite Monitoring teams with l associated communications.
3.5.2 Providing meteorological and dose estimates to offsite authorities for actual releases via a dedicated individual or automated data transmission.
3.5.3 Providing release and dose projections based on available plant condition information and foreseeable contingencies to offsite authorities..
NOTE In the event a release or potential release of radioactive asterials is a threat to plant personnel or members of the general public, 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, i HP/0/B/1009/08 HP/0/B/1009/09. HP/0/B/1009/10.
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EP/o/A/5000/07 Paga 3 of 4
/ -3.6 The Emergency Coordinator shall provide protective action recommendations as necessary to the affected county warning point (s) and to the North Carolina Warning Point (Emergency Operations Centers if established) or the Radiological Protection Section, Department of Human Resources (see Enclosure 4.4 Telephone Listing) as directed by the state in accordance with the North Carolina Radiological Emergency response plan. If l
evaluation indicates that a potential for or an actual release of l radioactive materials will result in a projected dose (RDI) to the popuistion of: (EPA Protective Action Guidelines).
3.6.1 Whole body <1, thyroid <5, NO procactive action is requiret Monitor environmental radiation levels to verify.
3.6.2 Whole body 1 to <5, thyroid 5 to <25, ree - d seeking
- shelter and wait for furthe- instructions, consider evacuation particularly for children and pregnant women.
Monitor environmental radiation levels and adjust area for mandatory evacuation based on these levels. Control i access so affected areas.
3.6.3 Whole body 5 and above, thyroid 25 and above, recomend 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.
/ 3.7 The Emergency Coordinator in coordination with the Recovery Manager, at the Crisis Management Center, will provide or make available:
3.7.1 A dedicated individual for plant status updates to offsite authorities and periodic press briefings.
3.7.2 Senior technical and management staff onsite available for consulation with the NRC and State on a periodic basis.
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EP/0/A/5000/07 P:gs 4 cf 4 w ..
/ 3.8 The Emergency Coordinator in coordination with Recovery Manager at the Crisis Management Center, will assess the emergency condition and determine the need to remain in a Site Area Emergency, escalste to a more severe class, reduce the emergency class, or close out the emergency.
/ 3.9 The Recovery Manager at the Crisis Management Center will closa 3
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 Notification of Emergency Conditions.
4.6 Emergency Plan Message Format l
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\M Enclosure 4.2 Page 1 of 6 LIST OF INITIATING CONDITIONS. ENERCENCY ACTION LEVELS, AND i ASSOCIATED ENERGENCY PROCEDURE / DOCUMENT Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document 4.2.1 Known loss of coolant Pressuriser low pressure reactor trip EP/1/A/5000/02 accident greater than and pressurizar low pressure safety makeup pump capacity. injection signal and high containment building pressure. (INSP5040. 5050 5D60. 5070) and high containment -
! building sump level. (INIP5260. 5270) and high containment humidity.
(INSP5400. 5410) and EHF 38. 39, and
~
40 alarm.
4.2.2 Degraded core with pos- Inadequate Core Couling:. AP/1/A/5500/05 sible loss of coolable 5 centrally located thermocouples indicate geometry (indicators core exit temperature greater than 1200*F.
should include instru- For Hechanical Clad Failuret mentation to detect Creater than 251 failed fuel indicated inadequate core cooling, by greater than 1.750pC1/m1 I-131 con-coolant activity and/or centration. .
containment radioactivity For Severs Fuel Over Temperature:
levels). From 11 to 101 failed fuel indicated by 1.300 to 13.000pC1/ml I-131 +
concentration.
For Fuel Helt From .51 to 51 failed fuel indicated by 1.180 to 11.800pci/m1 1-131 concentration.
4.2.3 Rapid failure of steam Pressurizar low pressure alarm and EP/1/A/5000/04. AP/1/A/5500/07 generator tubes with loss reactor trip, and pressurizer lov of offsite power (e.g., level alarm, and EHF 32, 33, and 34 several hundred gpa pri- alarm, and undervoltage alarms on mary to secondary leak 7KV buses, and steam generator water rate). level rapidly increasing in one or more steam senerators falling in the others, and pressurizer level rapidly decreasing. (INCP5151. 5160. 5172) i and possible lifting of steam genera-tor PRV's and/or safety valves.
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( ) EP/0/A/5000/07 Enclosure 4.2 - ) 4 j 6
' Page 2 of Initiating Conditions Paergency Action Level (EAL) Emergency Procedure / Document I. .
4.2.4 Steam line break with Rapidly decreasing reactor coolant EP/1/A/5000/03 Tavg. pressuriser pressure and level.
greater than 50gpm pri-mary to secondary leakage Steam line differential pressure and indication of fuel safety injection signal, and High damage, containment building pressure, if steamline break is in containment (INSP5040, 5050. 5060. 5070) and ENF 51A and/or B alarm, or high steam flow and Lo Lo Tavg or low steam pressure safety injection j signal, and ENF 48 alarm.
, 4.2.5 Loss of offsite power and Undervoltage alarna on 7KV buses. AP/1/A/5500/07 loss of onsite AC power ;
for more than 15 minutes.
4.2 6 Loss of all vital onsite Blackout load sequencers actuated. Tech Specs 3/8.2.3. 3/8.2.4 DC power for mora than 15 .DC bus undervoltage all buses and minutes, indications as in 4.2.5 above.
4.2.7 Complete loss of any Inability to establish charging pump OP/1/A/6100/04. AP/1/A/5500/17 function needed for plant injection and Inability to establish hot' shutdown. emergency feedwater flow, ogE I nability to establish service water flow, and' Inability to establish component '
cooling water flow.
4.2.8 Transient requiring opera- Reactor' remains critical after all EP/1/A/5000/01. AP/0/A/5500/34 tion of shutdown systema attempts to trip reactor have been with failure to scram completed.
(continued power genera-tion but no core damage immediately evident).
5.2.9 Hajor damage to spent Observation of major damage to one AP/1/A/5500/25 fuel in containment or or more spent fuel assemblies, or fuel handling building spent fuel pool water below fuel (e.g., large object level, or ENF16, 17, 38, 39. 40 damages fuel or water or 42 alarm.
loss below fuel level).
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- Enclosure 4.2 Page 3 of 6 N/-
Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document 4.2.10. Fire compromising the Observation of a major fire Tech Specs 3/4.5 Station Directive 2.11 Series
' function of safety that defeats redundant safety systems, system or function.
4.2.11 Most or all alarms As determined by the Shift Supervisor / OP/0/A/635'0/01A (annunciators) lost and Emergency Coordinator.
plant transient initiated 1
or in progress.
i' i 4.2.12 Effluent monitors detect For EHF35 Low Range, offscale i levels corresponding to High Range 8 x 10 cym.
j greater than 50 nr/hr (See Note 1) for 1/2 hour or greater than 500 mr/hTW.B. for For EHF36 Low Range 3 x 10 cpy HP/0/B/1009/05. HP/0/B/1009/09 two minutes (or five times High Range 7 x 10 cpm
- these levels to the thy- (See Note 1)
' roid) at the site boundary for adverse meteorology For EHF37 Change of 143 cps / minute '
{ (See Note 2). for 30 minutes or a
' f change of 1430 cpm / minute .
for 2 minutes (See Note 1).
j NOTE 1: These values are worst casa calculations and may not reflect more
' favorable weather conditions.
NOTE 2: These dose rates are projected based on other plant-parameters (e.g..
radiation level in containment with leak rate appropriate for existing contain-ment pressure) or are measured in the -
environs. (EPA Protective Action Guide-lines are projected to be exceeded out-side the site boundary).
3
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Enclosure 4.2 . (li '
Page 4 of 6
+ Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document i
. 4.2.x3 Inninent loss of phy- Physical attack on the plant involving Station Security Plan
' sical control of plant. taminent occupancy of control room and auxiliary shutdown panels.
- 4.2.14 Severo natural pheno- AP/0/A/5500/29. AP/0/A/5500/30 mena being experienced or projected with plant not in cold shutdown.
4.2.14.1
! Earthquake greater than (>.15gH. >.lgV) se determined by moni-SSE (Safe Shutdown Earth- toring seismic instrumentation.and .
quake) levels, recording devices. (SNP-1)
} 4.2.14.2 1 Plood low water. hurri- As determined by Shift Supervisor /
cane surge, seiche greater Emergency Coordinator.
than design levels (lake tidal waves) or failure of protection of vital j
equipment at lower levels.
l . 4.2.14.3 Susteined winds or torna- (>95 mph) as observed or documented does in excess of design by the National Weather Service levels. Information.
4.2.15 other hazards being ex- AP/0/A/5500/32. AP/0/A/5500/31 perienced or projected with plant not in cold shutdown.
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Enclosure 4.2 Y t Page 5 of 6
- Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document y
4.2.15.1 l
Aircraft crash affecting Aircraft crash causing damage or
- vital structures by in- fire to
- Containment Building.
- pact or ffre. Control Room. Auxiliary Building.
Puel Building, c.: Intake Structure.
I 4.2.15.2 Severe damage to safe Loss of functions needed for hot j shutdown equipment from shutdown as in 4.2.7.
} ,
missiles or explosion.
i 4.2.15.3 Entry of uncontrolled Entry of uncontrolled or toxic or flammable gas s into flammable gases into: Control Room. '
vital areas. Entry of Cable Spreading Room. Containment uncontrolled toxic Building. Switchgear Room. Safa gases into vital areas Shutdown Panels or Diesel Rooms.
i where lack of access to the area constitutes a safer.y problem.
4.2.16 Other plant conditions As determined by Shift Supervisor / As dictated by Plant Conditions.
exist that in the judge- Emergency Coordinator.
ment of the Shitt Super-visor, the Operations Duty Engineer, the Super-intendant of Operations.
or the Plant Manager war-rant activation of emer-gency centers and moni-toring teams and a precautionary public notification to the public near the site.
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' %' Enclosure 4.2 Page 6 of 6 i Initiating Conditions Emergency Action Level (EAL) Faergency Procedure / Document 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- .
down systems not established ,
from local stations in 15 minutes. ,
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E P/ 0/ A/ 5000/ 07 Encicsurs 4.3 Pass 1 of 1 NOIIPICATION/ ACTIVATION G uERAL EMERG H CT 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 NUfIPICATION COMPLETE-INITIAL Shift Supervisor Operations Duty Engineer
' Station Manater Superintendent of Operations Sugarjatendent of Technical Services -
Projects and Licensing Engineer Station Health Physicist North Carolina State Warning Point Mecklenburi County Warning Point Lincoln County Warning Point Catawba County Warning Point
[ Iredell County Warning Point Gaston County Warning Point
+
p Cabarrus County Warnine Point
.j South Carolina State Warning Point N.R.C. via ENS (Red Phone) e N.R.C. Station Representative Superintendent of Maintenance Superintendent of Administration Construction Proiect Mansaar Activate T.S.C. (Station Directive 3.8.2)
Activate 0.S.C. (Station Directive 3.8.2) ;
l Activate C.M.C. (Enclosure 4.6)
i?i d/ A/ $v00/ 07 Enclosure 4.4 4
Pag 2 1 of 2 TELEPHONE LISTING 4.4.1 Operations Duty Engineer (PA Systen)
~. - P&T Pager 4.4.2 Station Manager _
Home - - System Speed -
Hoce - - Systes Speed -
- 4.4.3 Superintendent of Operations -
Home
- S faces Speed 4.4.4 Superintendent of Ttehnical Services -
Home - - Systen Speen 4.4.5 Projects and Licensing Engineer -
Hone - - Systes Speed -
4.4.6 Station Health Physicist - l Home - - System Speed -
P&T Pager 4.4.7 NC State Warning Point, Raleigh - _,. - System Speed -
4.4.8 Mecklenburg County Warning Poi $te - Primary:- Ring Down Phone Back-up: - System Speed Back-up: Emergency Radio, Code: .
Ol
,' ~ s' 4.4.9 Lincoln County Warning Point - Primary: Rine Down Phone Back-up: . - System Spee/
Back-up: Emergency Radio, Code: ,
4.4.10 Catawba County Warning Point - Primary: Rine Down Phone Back-up: . . - System Speed
. Back-up: E=ergency Radio, Code: _
4.4.11 Iredell County Warning Point - Primary: Rine Down Phone Back-up: .'- Systen Speed
-Back-up: E::tergency Radio, Code: .
4.4.12 Caston County Warning Point - Primary: Ring Down Phone Back-up: . - System Speed Back-up: Emergency Radio, Code: ,
4.4.13 Cabarrus County Warning Point - Primary: Rine Down l' hone Back-up: . - Systen Speed Back-up: E=ergency Radio, Code: ,
NOTE Radio Code will activate
- l. all county radio units.
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P gn '2 cf 2 TELEPHONE LIST
'4.4.14 SC State' Warning Point - -
4.4.15 N.R.C. Operation Center, Emergency Notification System (ENS Phone) 4.4.16 N.R.C. Station Representative (Orders) ~'
' Office Office Home -
P&T;Iager - ,
PaSe from Central (MNS Area) -
or from Southern (ONS Area) -
4.4.17 Construction Project Manager Construction . Ext.
Home : system Speed -
- System Speed - ,
- 4.4.18 Superintendent of Maintenance j Home - - System Speed -
s 4.4.19 Superintendent of AA=4nistration Home -
l/
, System Speed -
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4.4.20 Nuclear Production Duty Engineer - System Speed ','
' P&T Pager (7% 4.4.21 Radiation Protection Section, Department of Human Resources-
- System Speed -
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FP/ 04 A/ 5vuu/ v7 Encissuro 4.5 Peg 2 1 0F 4 MCGUIRE NUCLEAR STATION NOTIFICATION OF EMERGENCY CONDITIONS
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a 4.5.1 Include as a mini ==, the following information to the North Carolina State Warning Point, the six County Warning Points, (Mecklenburg, Catawba, Iredell, Lincoln, Gaston, and Cabarrus) and the South Carolina Warning Point.
NOTE 1: See Enclosure 4.4, Telephone Listing NOTE 2: A. Complete Part I of this format as a minimal first notification of a reportable incident.
B. Complace Part I and II of this format to provide minimal followup information.
PART I: Initial Emergency Massage Information [ACINOWLEDGEMENT Mecklenburg TELEPHONE RESPONSE:
"This is McGuire Nuclear Station. Iredell Please acknowledge when you are Lincoln ready to copy Emergency Information." Cabarrus Gaston Catawba
- 1. This is McGuire Nuclear Statien.
- 2. My name is: .
- 3. This message (Number ):
h a. Reports a real emergency.
Is an exercise message.
b.
- 4. My telephone number / extension is:
- 5. Massage Authentication:
- 6. The class of emergency is:'
4
- a. Notification of an Unusual Event
- b. Alert i,
- c. Site Area Emergency
- d. General Emergency The Classification of Emergency was declared at: /on .
7.
AM/FM DATE
- 8. The initiating event causing the Emergency Classification is:
9 .* The Emergency Condition:
- a. Does not involve the release of radioactive materials free the plant.
- b. Involves the POTENTIAL for a release, but NO release is c
occurring.
- c. Involves a release of radioactive material.
'l
, - , _ - _ _ _ - _,r. - -_ - . . - - - - r
CP/0/A/5000/07 Enclecurs 4.5 Page 2 0F 4 l
I l
% 10. We recommend the following protective action:
I a. No protective action is recommended at this time.
- b. People living in zones remain l
indoors with doors and windows closed.
- c. People in zones EVACUATE l
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 follovup message l-
- b. No further communications l
- 12. I repeat, this message:
- a. Reports an actual emergency.
- b. Is an exercise message..
')
"~~ 13. Relay this information to the persons indicated in your alert pro-l cedures for an incident at McGuire Nuclear Station.
NOTE: Record the Name. Title, Date. Time, and Warning Point at end of Part II.
PART II: Follovuo Emergency Message Information
- 1. The type of actual or projected release is:
- a. Airborne
- b. Waterborne
- c. Surface spill
- d. Other
- 2. The source and description of the release is:
l 3. a. Release began /will begin at a.m./p.m.; time since reactor trip is hours.
- b. The estimated duration of the release is hours.
s
F.P/0/A/5000/07 Enciscura 4.5 Page 3 0F 4 4 Dose projection base data:
-g Radiological releases _ curies, or curies /sec.
Wind speed: aph Wind direction: Froa Stability class: (A,B.C.D.E.F. or C) l Release height: Pt.
Dose conversion factor: R/hr/Ci/Ms (whole body)
R/hr/Ci/Ms (Child Thyroid)
Precipitation Temperature at the site: 'F l
l 5. Dose projections:
- Dose Commitment
- j Distance Whole Body (Child Thyroid)
Rem / hour Rea/ hour of inhalacion l Site Boundary 2 miles 5 miles 10 miles
-N (A./
- Projected Integrated Dose In Res*
Distance Whole Body Child Thyroid r
i Site Boundary 2 miles t
5 miles 10 miles i
- 6. Field measurement of dose rate or contamination (if available):
l 7. Emergency actions underway at the facility include:
- 8. Onsite support needed from offsite organizations:
- 9. Plant status:
- a. Reactor is: not tripped / tripped
- b. Plant is at: % power / hot shutdown / cold shutdown / cooling down
- c. Prognosis is: stable / improving / degrading / unknown.
l 4
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EP/0/A/30uG/07 Encicturs 4.5 Prgs 4 0F 4
- 10. I repeat, this messages
- a. Reports an actual emergency.
- b. Is an exercise message.
- 11. Do you have any questions?
i.
- END OF FOLLOW-UP MESSAGE ***
i' BOTE: Record the name, title date, time, and warning point notified.
i (1) Communicator (Name) (Title)
Mecklenburs (Data) (Time) (Warning Point) l (2) Conaunicator (Name) (Title) l
' Gaston (Data) (Time) (Warning Point)
(3) Communicator (Naas) (Title)
Iredell (Date) (Time) (Warning Point)
(4) Communicator pl
(~-
(Name) (Title)
Catawba (Date) (Time) (Warning Point)
(5) Communicator (Name) (Title)
Lincoln (Data) (Time) (Warning Point)
(6) Communicator i (Name) (Title)
Cabarrus (Date) (Time) (Warning Point)
(7) Communicator (Name) (Title)
North Carolina (Data) (Time) (Warning Point)
(8) Conaunicator (Name) (Title)
South Carolina (Data) (Time) (Warning Point)
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EP/0/A/5000/07 Enclssurs 4.6 4
Page 1 of 1 DfERGENCY PLAN MESSAGE FORMAT l (Nuclear Station to Nuclear Production Duty Engineer)
L'. This is at McGuire Nuclear Station.
(Name and Title)
- 2. This is/is not a Drill. An Unusual Event i
Alert l Site Area Emergency General Emergency was declared by the Emergency Coordinator at on Unit Number .
(Time)-
2 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 _ Tes No. Counties Yes No, have been notified. ,
- 8. The Crisis Management Team should/should not be activsted. 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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t Form 34731 (10-81)
(Formerly SPD-10021)
DUEZ POWER COMPANT (1) ID No: EP/0/A/5000/08 PROCEDURE PREPARATION Change (s) o to PROCESS ?.ECORD n Incorporated (2) STATION: McGuire Nuclear Statisa (3) PROCEDURE TITLE: n.... 1 m....,.,
i / [,
(4) PREPARED BY: /mk. r:1nw.cNWf% DATE: Dae-her 3. 1982 (5) REVIEWED BY: W8) 3 ATE: 12 -T~ID Cross-Disciplinary Review By: N/R:
(6) TZMPORARY AFPROVAL (17 NECEJSART):
By: __(SRO) Date:
/9 By: Date:
(7) AFPPOVED BY / Dato: /3 ' 7' @l (8) MISCELLANIOUS:
Reviewed / Approved By: Date:
Reviewed / Approved By: Date: _
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y DUKE POWER COMPANY \ %, -} [ j McGUIRE NUCLEAR STATION s 4 I GENERAL EMERGENCY
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1.0 Symptoms g 1.1 Events are in process or have occurred which tuvolve actual or i minant g substantial core degradation or melting with potential for loss o'f: con- M
> e 1 tainment integrity.
2.0 Immediate Action ., *Y 2.1 Automatic -
None )
2.2 Manual ,
2.2.1 The Shift Supervisor shall be informed of all events initiating r
s s
this procedure. .
3.0 Subsequent Actions Initial /N/A
- / 3.1 The Shift Supervisor shall assure that the appropriate emergency l condition (Notification of Unusual Event, A". ort, Site Area l
Emergency, or General Emergency) is declared by'avaluating the
}/
- actual plant condition with Enclosure 4.1. Emergency -
Classification Flowchart and Enclosure 4.2. List of 'Initiatita -
- s Conditions, Emergency Action Levels, and Associated Emergency Procedure / Document. ~
v
/ 3.2 The Shife Supervisor shall ensure that all action's required
> by the initiating Emergency Procedure will be performed .
and that all actions necessary'for the protection of persons and property are being.taken.
NOTE If at any time in the course of events in this procedure, site evacuation or pertonnel assembly / Y accountability appears necessary, refer to Station Directive 3.8.1.
/ 3.3 The Shif t Supervisor shall assume the function of the Esmegency CoordinatoruntilthearrivaloftheStat1onManagero'rhis s ,
designes, at which time the Station Manager or his de'signes m assumes the responsibility of the Emergency Coordinator.
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EP/0/A/5000/08 s Pega 1 of a
.m / 3.4 The Emergency Coordinator shall assure prompt ( within about 15 Q- ,
minutes of declaring the emergency) notification of the North Carolina State and Local. County Werning Points indicated on Enclosure 4.3. He shall also assure notification of all other personnel listed in Enclosure 4.3.
- i. .,_,N .
NOTE 1 Activation of the Technical Support Center (TSC) and iA Operations Support Center (OSC) shall be in accordance with i
l '7 s_ : Station Directive 3.8.2. Activation of the Crisis Management Center (CMC) shall be in accordance with Enclosure 4.6.
NOTE 2 w See Enclosure 4.4. Telephone Listing, for notification, telephone numbers / radio codes /pager codes.
NOTE 3
,. See Enclosure 4.5, Notification of Emergency Conditions to be
. Provided to State / County Warning Points.
1 / 3.5 The Emergency Coordinator in direct contact with the Technical Support Center and the Crisis Management Center will assess and respend to the emergency by:
3.5.1 Dispatching the onsite and offsite monitoring tasas with associated communications.
I ; 3.5.2 Provide meteorological and dose estimates to offsite authorities for actual releases via a dedicated individual or automated data trans -
mission.
3.5.3 Provide re~, ease and dose projec uons based on available plant condition information and fore-seeable contingencies to offsite authorities.
"" NOTE 3 In the event a release or potential release of radioactive materials is a threat to plant personnel or members of the general public, ras Emergency Coordinator i
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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_ ____2 _ . . , , . , . _ _ _ , , , . _ _ _ , . _ . _ _
EP/0/A/5000/08 Ptgs 3 of 4
/ 3.6 The Emergency Coordinator shall provide protective action N recommendations as necessary es the affected county warning point (s) and to the North' Carolina Warning Point (Faergency Operations Centers if established) or to state Radiological
, Protection Section, Papartment of h=an Resources (See Enclosure 4.4,. Telephone Listing) as directed by the state in accordance with the North Carolina Radiological Emergency Response Plan. If evaluation indicates that a potential for an actual release of ,
radioactive meterials will result in a projected dose (REM) to the population of: (EPA Protective Action Guidelines) 3.6.1 his body <1, Thyroid <5, No protective action is required. Monitor environmental radiation levels to verify.
3.6.2 h is 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 4
levels. Control access to affected areas.
3.6.3 h ie 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 affectied areas.
NOTE See Enclosure 4.4 Telephone Listing for notification.
/ 3.7 The Emergency Coordinator in coordination with the Recovery Manager, at the Crisis Management Center, will provide or make available:
3.7.1 A dedicated individual for plant sestus updates to offsite authorities and periodic press briefings.
3.7.2 Senior technical and management staff onsite avail-able for consultation with the NRC and State on a periodic basis.
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EP/0/A/5000/08 Ptg3 4 of 4
/ 3.8 The Emergency Coordinator in coordination with the Recovery Manager at the Crisis Management Center will assess the emergency condition and determine the need to remain in a General Emergene:y, reduce the emergency class, or close out the emergency.
/ 3.9 The Recovery Manager at the Crisis Management Center will close out the emergency or.reco - ed reduction of the Emergency class by briefing the offsite authorities at the .
Crisis Management Center or by phone if necessary, followed by written summary within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
4.0 Enclosurtas 4.1 Emergency Classification Guide Flowchart 4.2 List of Initiating Conditions, Emergency Action Levels, and Associated Emergency Procedure / Document.
4.3 Notification Chart.
I i 4.4 Telephone listing.
l 4.5 Notification of Emergency Conditions.
- . 4.6 Emergency Plan Message Formac 4.2 1
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[ EP/0/A/5000/08 Enclosure 4.2 -
, Page 1 of 6 i LIST OF INITIATING CONDITIONS. EMERGENCY ACTION LEVELS. AND
! ASSOCIATED EMERCENCY PROCEDURE / DOCUMENT f 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 rea/hr Whole Body or
- 5 rea/hr Thyroid at the site boundary under actual meteoroloaical conditions.
NOTE 1: These dose rates l are projected base on
! plant parameters (e.g..
radiation levels in con-i-
. tainment with leak rate
- appropriate for existing containment pressure with some confirmatton from I
af fluent monitors) or are -
measured in the environs.
l
! NOTE 2: Consider evacuation I only within about 2 miles of the sits 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-I tective Action Guideline exposure levels are predicted l to be exceeded at longer distances.
l l 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 tial loss of 3rd barrier. .4.2.1. and incomplete contain-a (e.g., loss of prim'ry . ment isolation.
-coolant boundary, clad-failure, and high poten- 2. Loss of coolant accident as iden-l tial for loss of contain- tified in Site Area Emergency 4.2.1 ment integrity). andContainmentMonitoragares(EMP51A and/or B) greater than 10 R/hr and con-l
-tainment pressure greater than 14.8 psig for at least 2 minutes.
i l
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. EP/0/A/5000/08 j
" Enclosure 4.2 Page 2 of 6 i
Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document l
4.2.3 Loss of physical con- Physical attack of the facility has Station Security Plan, trol of the facility. resulted in occupation of the con-trol room and auxiliary shutdown NOTE: Consider 2 mile facility, precautionary evacuation.
l 4.2.4 Other plant conditions As determined by the Shift Supervisor / As dictated by plant conditioo9 e exist. from whatev.r Emergency Coordinator and verified by source..that in the judge- EAL's defined in Implementing Procedures i ment of the shift super- utilized up to this point.
! visor, the Operations Duty ,
I Engineer, the Superinten-dent of Operations, or the Plant Manager make release of large amounts of radio- '
activity in a short time
- period possible (e.g., any core melt situation).
a
- a. For core melt sequencca where significant re-leases are not yet taking place and large
, amounts of fission pro-l ducts are not yet in the containment atmos-phare, consider 2 mile precautionary evacua-tion. Considet 5 mile downwind aga.:uation (45 to 90 sector) if large c. mounts of fission products (greater than Cap acti-vity) are in the con-tainment atmosphere.
Recommend sheltering in other parts af the plume exposure Emer-gency Planning Zone under this circumstance.
, ,.. . . . _ _ _ . _ ._. . . , . . _. ..._..._..,..._._..2 . . . _ . . . . . . . , . . __ .
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- { EP/0/A/5000/08 (-
Enclosure 4.2 '- ;
4
' Page 3 of 6 !
1 Initiating Conditions Emergency Action 1.evel (EAL) Emergency Procedure / Document
- b. For core melt se-quences where wigni-ficant releases from containment are not yet taking place and containment failure leading to a direct atmospheric release is likely in the se-quence but not immi-neat and large amounts of fission products in 8 addition to noble gases are in the con-tainment atmosphere, consider precautionary evacuation to 5 miles and 10 mile do p ind avgcuation (45 and.
90 sector),
- c. For core melt ae-quences where large amounts of fission products other than noble gases are in the containment atmosphere and con-tainment failure is judged feminent, re-commend shelter for those areas where evacuation cannot be completed before transport of acti-vity to that loca- -
tion.
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) EP/0/A/5000/08 j
' Enclosure 4.2 -
i Page 4 of 6 l
Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document i
i d. As release informa-l tion becomes available adjust these actions in accordance with dose projections, time available to evacuate and esti- a mated evace tion times given current conditions.
I
- e. Example Sequences:
- 1. Small and large Safety injection signal plus reac-LOCA's with fail- tor trip and:
- ure of ECCS to per-
~
form leading to 1. Safety injection and RHR t severe core de- pumps not running, gradation or melt.
Ultimate failure 2. Flow indications for safety of containment injection read "0".
likely for melt sequences. (Seve- 3. High containment sump level.
ral hours likely to be available For Severe Fuel Over Temperatures 3 to complete pro- Greater than 101 failed fuel tective actions indicated by greater than unless containment 13,000pci/m1-131 concentration.
is not isolated).
i For Fuel Nelt Conditions:
Creater.than 51 failed fuel- -
)' , indicated by greater than 11,800pC1/mi I-131 concentration.
t
[ \ EP/0/A/5000/08 #
J
\s_ / Enclosure 4.2 .
Page 5 of 6 r
i Initiating conditions Emergency Action Level (EAL) Emergency Procedure / Document l
- 2. Transient ini- Reactor trip on Lo Lo Steam Generator AP/1/A/5500/06. EP/1/A/5000/04 l level and wide range generator levels tlated by loss
- of feedwater and toward offscale low on all steam generators i condensate sys- and emergency feedwater flow indica-
, teme (principle tors indicate "0" flow ogt emergency heat removal sys- feedwater pumps not running and can-tem) followed by not be restored within 30 minutes cg; l
- failure of emer- >31 reactor power and loss of both j gency feedwater main feedwater pumps, manually trip
- system for ex- reactor.
l tended period.
j (Core melting is possible in seve-ral hcurs with ultimate failure i of containment i likely if the core melts).
l 3. Transient requir- Reactor remains critical after all AP/0/A/5500/34 ing operation of attempts to trip the reactor are complete and flow indicators on i shutdown systems with failure to safety injection and RHR show "0" scram. Core dam- flow after initiation (NVP5440 age is likely. MDP5190. 5191. 5180. 5181 Additional failure NIP 5120. 5450) og; shfety injec-of the core cool- tion and RER pumps not running i ing and makeup with safety injection initiated, system would lead to core melt, i
t I
l 1 EP/0/A/5000/08 Enclosure 4.2 -
)
I Page 6 of 6 Initiating Conditions Emergency Action Level (EAL) Emergency Procedure / Document f
- 4. Failure of offsite Undervoltage alarms on 7KV buses and AP/1/A/5500/07
! and onsite pouer blackout load sequencers actuated and along with total auxiliary feedwater pump (s) . fail to loss of emergency start.
feedwater makeup capability for several hours.
Would lead to eventual core melt and likely failure of con-tainment.
I 5. Small LOCA and Pressuriser low pressure reactor trip EP/1/A/5000/02. AP/1/A/5500/05
! initially suc- and pressuriser low pressure safety cessful ECCS. injection signal and RHR flow indica-Subsequent fail- tors show "O" flow after shift to RHR .
ure of containment is attempted and for greater than 2 heat removal sys- hours (NDP5190. 5191. g180. 5181) and tem over several Reactor Coolant (NC) T is rising.
I hours could lead and containment air handling system to core melt and falls to function.
likely failure of containment.
NOTE: For melt se-quences or for failure
! of containment isola-tion systems the likely failure mode is melt through with release of gases.
4.2.5 Any major internal or ex- As determined by the Shif t Supervisor / As dictated by plant conditions.
ternal events (e.g., fires. Emergency Coordinator.
ecrthquakes substantially beyond design levels) which could cause massive cosmon damage to plant systems.
e %
-F.P/0/A/5000/08 Enciccura 4.3 Page 1 of 1
. NOTIFICATION / ACTIVATION cENERAL EMERGENCY Notify / Activate the following personnel /or Emergency Centers for all Initiating Conditions listed in Enclosure 4.2. (See Enclosure 4.4 for Telephone Listing)
NOTIFY / ACTIVATE NOTIFICATION COMPLETE-INITIAL
! Shife Supervisor Operations Duty Engineer ___
o Station Manager Superintendent of Operations Superintendent of Technical Services
' Projects and Licensing Engineer Station Health Physicist North Carolina State Warning Point Mecklenburg County Warning Point Lincoln County Warning Point Catawba County Warnine Point Iredell County Warnine Point Gaston County Warning Point Cabarrus County Warning Point
/ South Carolina State Warn 4ne Point N.R.C. via ENS (Rad Phone)
N.R.C. Station Representative Superintendent of Maintenance Superintendent of Administration Construction Project Manager Activate T.S.C. (Station Directive 3.8.2)
Activate 0.S.C. (Station Directive 3.8.2) 4 Activate C.M.C. (Enclosure 4.6)
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IP/0/A/5000/08 Enclosura 4.4 Page 1 'of 12
,_s TELEPHONE LISTING 4.4.1 Operations Duty Engineer (PA System)
P&T Pager 4.4.2. Station Manager Home - - System Speed Home - - System Speed 4.4.3 Superintendent of Operations -
Home - . - System Speed 4.4.4 Superintendent of Technical Services -
Home - System Speed 4.4.5 Projects and Licensing Engineer - . . j Eeme - - System Speed i
\
4.4.6 Station Health Physicist - ,- -
Home - system Speed -
P&T Pager 4.4.7 NC State Warning Point, Raleigh -' - System Speed -
4
, 4.4.8 Mecklenburg County Warning Point.? Primary: Rina Down Phone 9- Back-up: - Systen Speed
,_s Back-up: Emergency Radio, Code: ,
(/ 4.4.9 Lincoln County Warning Point - Primary: Rine Down Phone Back-up: . - System Spee/
Back-up: Energency Radio, Code: _.
4.4.10 Catawba County Warning Point - Primary: Rine Down Phone Back-up: - System Speed Back-up: Emergency' Radio, Code: ,
4.4.11 Iredell County Warning Point - Primary: . Ring Down Phone Back-up: - System Speed Back-up: Emergency Radio, Code:.,
4.4.12 Caston County Warning Point - Primary: Ring Down Phone Back-up: .' - System Speed Back-up: Emergency Radio, Code: _
4.4.13 Cabarrus County Warning Point - Primary: Ring Devn Phone
' Back-up: . - Systen Speed Back-up: Emergency Radio, Code: _'
NOTE Radio Code . till activate all county radio units.
1 r
EP/0/A/5000/08 Enciaturs 4.4 Page 2 of 2 TELEPHONE LIST O ,- -
4.4.14' SC State Warning Point -
4.4.15 N.R.C. Operation Center, Emergency Notification System.(ENS Phone)~-
4.4.16 N.R.C. Station Representative (Orders)
Office.
Office Home -
P&T Pager .
Page from Central (N2(S Area) -
or from Southern (ONS Area) -
4.4.17 Construction Project Manager Construction - _ ,
Home : - System Speed { or -
system Speed - j 4.4.18 Superintendent of Ms.intenance i Home - l System Speed -
s 4.4.19 Superintendent of Adninistration '
Ecce - * - System Speed - '
4.4.20 Nuclear Production Duty Engineer - . - System Speed - $
I P&T Pager ' *
- r*. )y 4.4.21 Radiation Protection Section, Department of Human Resources-
~~~*
%_< - System Speed - ,
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EP/0/A/5000/08
'nei ==== 4.5
?
Page 1 0F 4 MCGUIRE NUCLEAR STATION NOTIFICATION OF EMERGENCT CONDITIONS Q _ Include as a mini ==, the following information to the North Carolina 4.5.1 State Warning Point, the six County Warning Points (Mecklenburg, Catawba, Iredell, Lincoln, Gaston, and Cabarrus) and the South Carolina Warning Point.
4 NOTE 1: See Enclosure 4.4, Telephone Listing NOTE 2: A. Complete Part I of this format as a minimal first notification of a reportable incident.
B. Complete Part I and-II of this format to provide minimal followup information.
PART I: Initisi Emersency Message Information ACKNOWLEDGEMENT TELEPHONE RESPONSE: Mecklenburg "This is McGuire Nuclear Station. Iredell Please acknowledae when you are Lincoln ready to copy Emeraency Information." Cabarrus Gaston L. This is McGuire Nuclear Station. Catawba
- 2. My name is: .
- 3. This message (Number ):
ic) . ., a. Reports a real emergency.
.2
" b. Is an exercise message.
l 4. My telephone number / extension is: .
- 5. Massage Authentication: .
- 6. The class of emergency is:
- a. Notification of an Unusual Event
- b. Alert
- c. Site Area Eastgency
- d. General Emergency
- 7. The Classification of Emergency was declared at: /on .
AM/FM DATE r
l 8. The initiating event causing the Emergency Classification is:
I
- 9. The Emergency Condition:
- a. Does not involve the release of radioactive materials from the planc.
- b. Involves the POTENTIAL for a release, but NO release is occurring.
l c. Involves a release of radioactive material.
l I
F.P/0/A/5000/08
% % ..o y Page 2 0F 6
+ 10. We recomend the following protective action:
O s. No protective action is recommended at this time.
- b. People living in zones remain indoors with 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 reco===adations:
i
- 11. There will be:
'i a. A followup message t
- b. No further communications
- 12. I repeat, this message:
1 l a. Reports an actual emergency.
- b. Is an exercise message.
< . f}
O 13. Relay this information to the persons indicated in your alert pro-cedures for an incident at McGuire Nuclear Station.
i NOTE: Record the Name, Title, Date, Time, and Warning Pofat at end of i Part II.
PART II: Followup Emergency Message Information
- 1. The type of actual or projected release is:
- a. Airborne
- b. Waterborne
- c. Surface spill l
- d. Other ,
- 2. The source and description of the release is: ,
- 3. a. Release began /will begin at a.m./p.m.; time since reactor trip is hours.
- b. The estimated duration of the release is hours.
1 ,
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EP/0/A/3000/08 v.,1a .,3 4.5 Page 3 0F 4
- 4. Dose projection base data:
Radiological release: curies, or curies /sec.
n-
) Wind speed: aph Wind direction: Fros-
' Stability class: (A,B,C.D.E.F. or G)
Release height: Ft.
+
Dose conversion factor: R/hr/C1/Ms (whole body)
R/hr/C1/Ms (Child Thyroid)
Precipitation Temperature at the site: 'T 3
- 5. Dose projections:
- Dose Commitment
- 1 Distance Whole Body (Child Thyroid)
Rem / hour Rem / hour of inhalation Site Boundarv 2 miles 5 miles
.. 10 miles
.c
- Projected Integrated Dose In Rea*
> n
. (.,
I Distance Whole Body Child Thyroid 2
Site Bo d-ey 2 miles 7
5 miles
'i 10 miles
- 6. Field measurement of dose rate or cont -in= tion (if available):
- 7. Emergency actions underway at the facility include:
- 8. Onsite support needed from offsite organizations:
- 9. Plant status:
- a. Reactor ist not tripped / tripped
- t. Plant is at: % power / hot shutdown / cold shutdown / cooling down
- c. Prognosis ist stable / improving / degrading / unknown.
o
- i
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EP/0/A/5000/08 m.,1-. O Page 4 0F 4
., 10. I repeat, this message: ,
- s. Reports an actual emergency.
- b. Is an exercisa message.
- 11. Do you have any questions?-
- END OF FOLLOW-UP MESSAGE ***
f i'
NOTE: Record the name, title, date, time, and warning point notified.
(1) Communicator (Name) (Title)
~
Mecklenburs (Date) (Time) (Warning Point)
(2) Communicator (Name) (Title)
Gaston (Data) (Time) (Warning Point) v (3) Co - festor (Name) (Title) a Iredell
, (Date) (Time) (Warning Point)
- i. . - (4) Communicator (Name) (Title)
Catawba (Date) (Time) (Warning Point)
- (5) Co===mi cator
- -i (Name) (Title)
Lincoln 4 (Date) (Time) (Warning Point) 3 (6) Communicator (Name) (Title)
Cabarrus (Data) (Time) (Warning Point)
(7) Communicator (Name) (Title) 3 1
North Carolina (Data) (Time) (Warning Point)
(8) Communicator (Name) (Title)
' South Carolina (Date) (Time) (Warning Point)
O
., - -- ,._m., . _ . . _ _ . .. _ , , _ . _ . _ _ _ _ . , . , , _ , , , , _ ,
EP/0/A/5000/08 Encitsura 4.6 Page 1 of 1 EMERGENCY PLAN MESSAGE FORMAT' m
.] (Nuclear Station to Nuclear Production Duty Engineer)
- i
- 1. This is at McGuire Nuclear Station.
(Name and Title)
- 2. This is/is not a Drill. An Unusual Event Alart Site Area Emergency General Emergency was declared by the Emergency Coordinator at on Unit Number .
(Time)
- 3. Initiating Condition: (Give as close to the emergency procedura description as possible together with station parameters used to determine emergency status) .
t
- 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 Tes No, State Yes No, Counties Yes No,
- have been notified.
. 8. The Crisis Management Team should/should not be activated. Corporate li 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:
l l -
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STATION DI .IVE 3 8,
' = -
APPROVAL _
DATE ORIGINAL ISSUED 2/12/80 REVISION 9 DATE /J./3/f2 i i DUKE POWER COMPANY McGUIRE NUCLEAR STATION SITE ASSEMBLY AND EVACUATION i
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.
1 RESPONSIBILITT 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:
i-A. Fire out of control B. High radiation levels in Auxiliary Building (unplanned) p C. High airborne particulate or gas levels (radioactive, toxic or flammable) in Auxiliary Building.
D. ECCS initiated due to primary system failure.
E. Security breach / Bomb Threat l
\- NOTE: If at any time in the course of this directive.
the Emergency Coordinator deems a Site Evacuation is necessary, he should proceed directly to page 5 IMPLEMENTATION - SITE EVACUATION.
- 2. The Energency Coordinator (or his designee) shall deterciine whether or not a subsequent evacuation is warranted after evaluating the situation in regards to personnel safety. Examples:
A. Fire spreading out of control with potential for reducing containment integrity or damaging essential systems / components.
B. Any unplanned increase in whole body exposure >2.0 ares /hr 3 encompassing a majority of the exclusion area.
- Y
. , . - .---v ---m-.-- . -. - - - , - , , - -# , .-, ..+._-
t 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 evac-untion facility is to be utilized based u M implications of the emergency (radiological, chemical, fire, security, etc.) and meteorological conditions (wind direction, precipitation, etc.). See Enclosure 1. Evacuation Routes.
IMP N ENTATION - SITE ASSEMBLY
- 1. The Shift Supervisor or his designes shall sound a twenty second blast of the Site Assembly alarm and make the following announcement on the plant page system:
(
l "This is a Site Assembly. This is a Site Assembly. There is/are in/at All personnel and visitors
) what where report to their assembly points."
g
\
E> 2. Repeat Step 1 in full.
l
( At this time, all personnel shall report to their super. visors at their assembly _
i 3.
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 the protected area) if activated, and will be allowed normal passage ,
thru the Personnel Access Portal.
B. Normal passage thru the Personnel Access Portal (PAP) shall not be restricted -
during a Site Assembly, however, the Emergency Coordinator may request the Security Shift Lieutenant to secure the PAP if the emergency condition warrants.
C. Af ter normal working hours, on weekends, or anytime the Mainistration offices are normally unoccupied, all personnel outside the protected area
__ shall assemble in the canteen.
I 5
6 l
l
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l
.-m NOTE: During routine drills, the PBI Operator and assigned security posts at the SAS, CAS, VAP, PAP, and Fuel Receiving shall remain at their assigned stations.
- 4. . Supervisors, upon accounting for their people shall report to their Section Heads, who in turn, upon receiving accounts from all their supervisors shall report to their respective superintendent or superintendent's clerks.
- 5. The superintendents or their clerks Senior QA Engineer, and the Construction Project Manager, after receiving accounts from their section heads sha11' report to the Superintendent of Administration who in turn, after receiving these reports shall notify the Station Manager and the 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 minutes of the start of an emergency I requiring Site Assembly. During the emergency, accountability of all onsite individuals will be maintained by supervision.
NOTE: Commencing fifteen (15) minutes after initiation of a Site Assembly, 7
the superintendents Senior QA Engineer, and the Construction Project
\ . Manager should begin personnel status reports to the Superintendent i of Administration who in turn, will notify the Station Manager and Shift Supervisor. These status reports should be continued at fifteen (15) minute intervals until all personnel are accounted for.
i
- 6. Search and rescue of missing personnel will be at the discretion-of the Energency Coordinator, and shall take into account the emergency situations that
- i. may be encountered such as radiological hazards, fire, toxic gases or other I
conditions that may involve personnel safety. Station Fire Brigade 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, on weekends, or anytime the Administration offices are l normally unoccupied, the senior person in each section shall be responsible for the personnel in his group and shall report to the Shift Supervisor when all personnel are accounted for.
l 1
f l
- 8. When the condition warranting Site Assembly has been removed or staliilized to the point where it is no longer a personnel hazard and normal personnel traffic will not hinder any subsequent recovery actions as determined by the Emergency Coordinator, he shall secure from the Site Assembly via the station FA System.
l IMPLEMEtrIATION - SITE EVACUATION
- 1. As per Step 3 of Responsibility for Implementation, determine the evacua-i tion facility to be utilized. See Enclosure 1 Evacuation Routes.
. 2. The Shift Supervisor or his designes 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."
( Repeat Step 2 in full.
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- 4. Request 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 Laka Norman within the exclusion area. (See Enclosure 3) (Station l Security will work with the County Police in directing traffic to the evacuation facility designated.)
I
- 5. Continue to repeat Step 2 at 3 minute intervals until notification that tha site is in fact evacuated.
- 6. At this time, all non-essential personnel shall evacuate to the designated evacuacion facility by their designated route utilizing their individual private vehicles with the following exceptions:
(1) In the event road conditions (severe weather) or a release of radioactive materials has affected use of prhete vehicles, all l non-essential personnel shall proceed to the designated evacuation
. facility by foot.
1 1
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(2) In the event the situation does not involve a release of radioactive asterials or contamination of the site area, the Emergency Coordinator any allow non-essential personnel to leave the site in their vehicles l
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 S'hift 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 procacted area or evacuate to the designated evacuation facility.
NOTE: If there is radiological cone ==4 nation of equipment and personnel Health Physics Emergency Environmental survey teams shall be provided in accordance with the Station Health Physics Manual, Section 18.2 (Environmental Monitoring for Emergency Conditions). Emergency Personnel survey teams shall be provided in accordance with Station Health Physics Manual, Section 18.3 (Personnel Monitoring for Emergency Conditions).
\
- 7. Steam 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 Mainistration who will.in turn inform the Shif t Supervisor and the Emergency Coordinator of the evacuation status.
NOTE: Commencing thirty (30) minutes after initiation af a Site evacuation, the Superintendent of M=4nistration shall begin personnel status reports to the Shift Supervisor and Emergency Coordinator. These status reports should be continued at fifteen (15) minute intervals until all personnel are evacuated and accounted for.
- 8. Af ter normal working hours, on weekends, or anytime the M=4nistration offices are normally unoccupied, the senior person in each section shall be responsible for the personnel in his group and shall report to the Shif t Super-visor when all evacuated personnel are accounted for.
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- 9. The Emergency Coordinator in coordination with the Recovery Manager at the Crisis Management Center will provide instructions to Steam Production and Construction supervision regarding the further disposition of evacuated personnel. In the event evacuated personnel must remain at the evacuation facilities for an extended period of time, the Recovery Manager shall provide for their. care and disposition.
10~. When the emergency condition requiring Site Evacuation no longer exists, the Emergency Coordinator shall secure from the Site Evacuation.
4 1
ENCLOSURES
- 1. Assembly Points
- 2. Evacuation Row.er. to Training and Technology Center Center and Cowan's Ford Dam
- 3. Site Evacuation Traffic Control Telephone List I.
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'j I STATION DIRECTIVE 3.8.1
! ENCLOSURE 1 i
ASSEMBLY POINTS l
WITHIN OUTSIDE RESPONSIBLE 1
CROUP PROTECTED AREA PROTECTED AREA SUPERVISION A. Operations Operation's Office Operations Admi'n. Shift Supervisor f
Building Office '
1 I NOTE: Control Room Operators remain on station.
B. Admin Services
- 1) Administrative Person- PAP at Exit Corridor Training Room Superintendent of nel and Training Administration l
! Services Personnel i
, 2) K-Mac K-Mac Storage Area at PAP Training Room K-Mac Supervisor
- 3) Security Security Office Assembly Training Room Sec. Shift Lieut.
f
'- Room (CAS, SAS, and. PAP Remain on Post)
- 4) Visitors Escorted - with escort Training Room Sec. Shift Lieut.
i NOTE: Visitors assigned unescorted access shall be assigned to i a responsible group by security personnel during initial badging procedure.
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- STATION blVE3.8.1 -
ENCLOSURE 1 (CONTINUED)
ASSEMBLY POINTS I WITHIN OUTSIDE RESPONSIBLE CROUP PROTECTED AREA PROTECTED AREA SUPERVISION C. Tech Services
- 1) Projects & Licensing. Performance Trailer Superintendent's Office P&L Engineer NRC Personnel Onsite
- 2) Performance Performance Trailer Superintendent's Office Performance Supv.
1 3) Chemistry CT Lab Superintendent's Office Station Chemist i
- 4) Health Physics HP Lab Auxiliary Count Room Sta. Health Phy.
HOTE 1: If radiation levels within the HP Lab are excessive.
l Health Physica shall report to HP trailer.
! HOTE 2: If the emergency has radiological implications. Health Physica escorts shall take their visitor to the PAP.
I i
D. Maintenance f 1) Mechanical (SMS, SSD) Assembly Room in Shop Superintendent's Office Hafnt. Engineer l 2) ISE IAE Shop Superintendent's Office I&E Engineer I
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- 3) Planning Planners Office Superintendent's Office Planning Engineer l
NOTE: Any Transmission Department personnel assigned to the l
Station Maintenance Department shall assemble with the group / crew they are assigned to.
- E. QA QA Office ALove CT Lab Senior QA Engineer's Office 4. A.. Engineer F. Construction Home Base Headquarters Home Baee Headquarters Construction Ngr.
C. Station Hanager Control Room Manager's Office
- Station Manager
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- % .s STATION DIRECTIVE 3.8.1 .
ENCLOSURE 3 c
, , SITE EVACUATION TRAITIC AND LAKE CONTROL TELEPHONE LIST , ,
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A. Hecklenburg County Police - 374-3333 '* v s
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STATION DIRECTIVE 3.7.3 ATTACHMENT NO. 2 9 N REVISION 7 DATE / J/
APPROVAL ,
d , A' s
' s BOMB THREAT SEARCE PLAN AND CHECK SHEET t
- La the evenc a bomb threat received included information about the location of the t . bomb, this area should.be searched first.- If the bomb threat contained no information about the bomb location, the following search plan will be utilized:
J j NOTE: (1) Health Physics coverage of some areas and search personnel any be required. Contact Health Physics for support in these areas.
I (2)' The Energency Coordinator shall designate search plan priorities based I
, on available information. Areas that are known to be inaccessible for long periods of time i.e.: Containment, filter and domineraliser i rooms, should not be given priority for search.
I _
(3) For locked areas where keys are not available from the Shift Supervisor or Health Physics, the appropriate personnel in charge of
/
the area shall be contacted for access.
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4' SF. ARCH COMPLETED AP.EA RESPONSIBILITY INITIALS TDR Vital Electrical / Cable Rooms Fire Brigade
- All Other Station " Vital" Security
, Areas i (fnit 1. Fuel Building Fire Brigade
[ '[ Unit 2. Fuel Building Fire Brigade i ,,
U.ir,1 Containment Bldg. Fire Brigade i
L (all elevations) init 2 Contain==nt Bldg. Fire Brigade
, (all elevations)
Auxiliary Bids. Elv. 695 Fire Brigade t Auxiliary B143. Elv. 715 Fire Brigade 3
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< STATION DIRECTIVE 3.7.3 ATTACEMINT No. 2
~N PAGE 2 BOMB THREAT SEARCH PLAN AND CHECK SHEET CONTINUED SEARCH COMPLETED i AREA RESPONSIBILITT 15ITIALS TDS i
Auxiliary Bldg. & Service Fire Brigade Bids. Elv. 733 and Elv. 739 i Auxiliary Bldg. & Service Fire Brigade j Bids. Elv. 750 A-414=ry Bldg. & Service Fire Brigade Bldg. Elv. 760, 767. 777 (Q.A. Darkroca. Planning.
Ventilation Room)
Auxiliary Bldg. Elv. 786 Fire Brigade Unit 1 Inboard / Outboard Fire Brigade Doghouse
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- (.' Unic 2 Inboard / Outboard Fire Brigade
. a. Doghouse -
Unit 1, 2. Turbine Bldg. Fire Brigade Elv. 739 .
j Unit 1. 2, Turbine Bids. Fire Brigade Elv. 760 Unit 1. 2 Turbine Bids. Fire Brigade
! Elv. 790
,, All Extremely High Radiation Health Physics Areas Station Grounds "Inside" Security _
Protected Area l
Turbine Building. Service Security Building, Auxiliary Building, i and Containment Building Roof's
, and Structures Intaka Structure Security RadWaste Solidification Health Physics "N
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STATION DIRECTIVE 3.7.3 ATTACHMENT 2
- PAGE 3 l
BOMB THREAT SEARCH PI.AN AND CHECK SHEET CONTINUED SRAlf'18 COMPI.ETED AREA RESPONSIBILITY INITIALS TIME j Contaminated Parts Whse. Health Physics Safa Shutdown Pacility Security i
All Trailers - Inside Security Protected Area Warehouse #5 Security Interim Waste Building Health Physics t
011-Storage House Security Bulk H2 St rese House Security
(
! Bulk N Se rage House Security 2
4
. 'g, Bulk 0 Storage House Security 2
u i All Construction Buildings Security (Inside Protected Area)
I Inside PWST Missile Shield Security
- (Unit 1 and 2)
AA=inistrative Building Security Trailers and Grounds near Security i Admin. Bldg. (Outside
- Protected Area) i 2
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STATION DIRECTIVE 3.8.1 APPROVAL 'M.A #9/ C /lw" DATE ORIGINAL ISSUED 2/12/80 REVISION 8 DATE n/</ /yz DUKE POWER COMPANY McGUIRE NUCLEAR STATION SITE ASSEMBLY AND EVACUATION f
OBJECTIVE
.i 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.
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RESPONSIBILITY FOR IMPLEMENTATION
- 1. The Shift Supervisor / Emergency Coordinator shall determine whether or not a Site i Assembly is warranted based upon the severity of the energency condition in regards I to personnel safety. Examples:
i A. Fire out of control B. High radiation levels in Auxiliary Building (unplanned)
C. High airborne particulate or gas levels (radioactive, toxic or flasunable) in Auxiliary Building.
D. ECCS initiated due to primary system failure.
E. Security breach / Bomb Threat NOTE: If at any time in the course of this directive, j the Emergency Coordinator deems a Site Evacuation
' is necessary, he should proceed directly to page 5.
l IMPL1! MENTATION - SITE EVACUATION.
- 2. The Emergency Coordinator (or his designee) shall decernine whether or not a subsequent evacuation is warranted after evaluating the situation in regards to personnel safety. Examples:
A. Fire spreading out of control with potential for reducing l
containment integrity or damaging essential systems / components.
B. Any unplanned increase in whole body exposure >2.0 area /hr encompassing a majority of the exclusion area.
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C. Any airborne contamination in excess of concentrations set forth in 10CF120, Appendix B. Table II, within the exclusion area.
D. Toxic or flammable gases within the exclusion area.
4 E. Bomb Threat
- 3. The individual commencing the Site Evacuation shall determine which evac-ustion facility is to be utilized based upon implications of the emergency (radiological, chemical, fire, security, etc.) and, meteorological conditions (wind directica, precipitation, etc.). See Enclosure 1. Eva m tion Routes.
IMPLEMENTATION - SITE ASSEMBLY
- 1. The Shift Supervisor or his designee shall sound a twenty second blast of the Site Assembly alarm and make the fonowing 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 what where report to their assembly points."
- 2. Repeat Step 1 in full.
- 3. At this time, all personnel shall report to their supervisors at their assembly points shown in Enclosure 1. (Assembly points are provided to assist supervision i 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 the protected area) if activated, and will be allowed normal passage thru the Personnel Access Portal.
l B. Normal passage thru the Personnel Access Portal (PAP) shall not be restricted during a Site Assembly, however, the Emergency Coordinator may request the Security Shift Lieutenant to secure the PAP if the emergency condition warrants.
C. After normal working hours, on weekends, or anytime the Administration offices are normally unoccupied, all personnel outside the protected area shall assemble in the canteen.
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NOTE: During routine drills, the PSI Operator and assigned-
security posts at the SAS, CAS,~VAP, PAP, and Fuel Receiving shall remain at their assigned stations.
- 4. Supervisors, upon accounting for their people shall report to their Section Heads.
who in turn, upon receiving accounts from all their supervisors shall report to I l
their respective superintendent or superintendent's clerks.
1
- 5. 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 Station Manager and the Shift Supervisor. All individuals onsite at the time of the emergency shall be accounted for andthe names of missing individuals shall be identified within 30 minutes of the start of an emergency requiring Site Assembly. During the emergency, accountability of all onsite individuals will be maintained by supervision.
~
NOTE: Commencing fifteen (15) minutes after initiation of a Site Assembly, the superintendents, Senior QA Engineer, and the Construction Project Manager should begin personnel status reports to the Superintendent of Administration who in turn, will notify the Station Manager and Shift Supervisor. These status reports should be continued at fifteen (15) minute intervals until all personnel are accounted for.
I
- 6. Search and rescue of missing personnel will be at the discretion of the I Emergency Coordinator, and shall take into account the energency situations that may be encountered such as radiological hazards, fire, toxic gases or other conditions that may involve personnel safety. Station Fire Brigade personnel trained in rescue procedures and accompanied by Health Physics personnel during radiological situations, shall be utilized for search and rescue of missing personnel.
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- 7. After normal 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 Shift Supervisor when all personnel are accounted for.
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- 8. When the condition warranting Site Assembly has been removed or stabilized to the point where it.is no longer a personnel hazard and nornal personnel
- traffic will not hinder any subsequent recovery actions as determined by the Emergency Coordinator, he shall secure from the Site Assembly via the station PA System.
IMPLEMENTATION - SITE EVACUATION ,
- 1. As per Step 3 of Responsibility for Implementation, determine the evacua-tion facility to be utilized. See Enclosure 1. Evacuation Routes.
- 2. The Shife 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 Das
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! (2) proceed offsite/home."
- 3. Repeat Step 2 in full.-
- 4. Request 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 evacuation facility designated.)
- 5. Continue to repeat Step 2 at 3 minute intervals until notification that the sita is in fact evacuated.
- 6. At this time, all non-essential personnel shall evacuate to the designated
[
evacuation facility by their designated route utilizing their individual private
- vehicles with the following exceptions
, (1) In the event road conditions (severe weather) or a release of radioactive materials has affected use of private vehicles, all non-essential personnel shall proceed to the designated evacuation facility by foot.
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(2) In the event the situation does not involve a release of radioactive materials or contamination of the site area, the Emergency Coordinator may allow non-essential personnel to leave the site in their vehicles I and proceed offsite/home.
(3) Control Room personnel shall stay on station, evacuate to the Scandby 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, i
- NOTE: If there is radiological contamination of equipment and personnel, Health Physics Emergency Environmental survey teams shall be per:1ded in accordance with the Station Health Physics Manual. Section 18.2 (Environmental i
Monitoring for Emergency Conditions). Emergency Personnel survey teams shall be provided in accordance with Station Kealth Physics Manual, Section 18.3 (Personnel Monitoring l
for Emergency Conditicus).
i
- 7. Steam 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 will in turn inform.the Shift Supervisor and 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 Shift Supervisor and Emergency Coordinator. These status reports should be continued at fif teen (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-l responsible for the personnel in his group and shall report to the Shift Super-visor when all evacuated personnel are accounted for.
I
- 9. The Emergency Coordinator in coordination with the Recovery Manager at the Crisis Management Center will provide instructions to Steam Production and Construction supervision regarding the further disposition of evacuated personnel. In the event evacuated personnel must remain at the evacuation facilities for an extended period of time, the Recovery Manager shall provide for their care and disposition.
- 10. When the emergency condition requiring Site Evacuation no longer exists, the Energency Coordinator shall secure from the Site Evacuation.
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.! ENCLOSURES Ii l' 1. Assembly Points
- ! 2. Evacuation Routes to Training and Technology Center Center and Cowan's Ford Dam-j 3. Site Evacuation Traffic Control Telephone List v3 l1 l!
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'w STATION DIRECTIVE 3.8.1 ENCLOSURE 1 ASSEMBLY POINTS WITHIN OUTSIDE. RESPONSIBLE PROTECTED AREA PROTECTED AREA SUPERVISION CROUP A. Operations Operation's Office Operations Admin. Shift Supervisor Building Office NOTE: Control Room Operators remain on station.
- b. Admin Services Administrative Person- PAP at Exit Corridor Training Room Superinten. lent of 1) net and Training Administration Services Personnel K-Hac K-Mac Storage Area at PAP Training Room K-Mac Supervisor 2)
- 3) Security Security Office Assembly Training Room Sec. Shift Lieut.
Room (CAS, SAS, and PAP Remain on Post)
- 4) Visitors Escorted - with escort Training Room Sec. Shilt Lieut.
NOTE: Visitors aseigned unescorted access shall be assigned to a responsible group by security personnel during initial badging procsdure.
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STATION DIRECTIVE 3.8.1 ENCLOSURE 1 (CONTINUED)
ASSEMBLY POINTS WITHIH OUTSIDE RESPONSIBLE GROUP PROTECTED AREA PROTECTED AREA SUPERVISION 1 C. Tech Services
- 1) Projects & Licensing. . Performance Trailer Superintendent's Office P&L Engineer NRC Personnel Onsite Performance Performance Trailer Superintendent's Office Performance Supv.
4 2)
- 3) Chemistry CT Lab Superintendent's Office Station Chemist
- 4) Health Phyrics HP Lab Auxiliary Count Room Sta. Health Phy.
NOTE 1: If radiation levels within the HP Lab are excessive.
Health Physics shall report to HP trailer.
NOTE 2: If the emergency has radiological implications. Health Physics escorts shall take their visitor to the PAP. ,
i D. Maintenance
- 1) kchanical (SMS. SSD) Assembly Room in Shop Superintendent's Office hint . Engineer l 2) I&E ISE Shop Superintendent's Office IAE Engineer
- 3) Planning Planners Office Superintendent's Office Planning Engineer NOTE: Any Transmission Department personnel assigned to the Station hintenance Department shall assemble with ,the group / crew they are assigned to.
E. QA QA Office Above CT Lab Senior QA Enginect's Office Q. A. Engineer F. Construction Unit i1 Truck Corridor Brass Shack Construction Mgr.
G. Station knager Control Room knager's Of fice Station knager
STATION DIRECTIVE 3.8.1 ENCLOSURE 2 Evacuation Routes to Training and Technology Cantar and Cowan's Ford Dam I g >
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STATION DIRECTIVE 3.8.1~
ENCLOSURE 3 SITE EVACUATION TRAFFIC AND LAKE CONTROL TELEPHONE LIST i
A. Mecklenburg County Police - 374-3333
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4 Fonn 34731 (1041)
(Pennerty SPD 10021)
DUIE F0WER COMPANT (1) ID No HP/0/B/1009/15 FROCIDURE PREFARATIN Change (s) 0 _to PROCESS RECORD o Incorporated (2) STATIN: McGaire h at - Station Maal - Post-Maidant Contaiasmat Air *1 214aa j (3) FROCIDURE TITI2:
system operating Procedars (4) FREPARED BT: /. i,WL /l /Md ALTE: si/n /92
- DATE: // py[g 2. -
(5) REVIEWED ET:
crossetecip aavise ny: n/x: b
- (6) TEMPCEART AFFEDFAL (TF NA8Y):
ny: (sao) Dace:
ay: Date:
(7) AFFEDFED IT: Date: /// /s (s) wrarrt72 m m us navissed/ L __. c sy: Date:
navissed/ Approved ny: Deca:
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EP/0/3/1009/15
. DOEI POWER COMPANT ;
McGUIII EUCLEAR STATIDE a EUCLEAR POST-ACCIDENT CONTANEf! AIX j SAMPLING SYSTEM OPERATI5G PROCIDURE 1.0 Purpose
- 1.1 This procedure describes.the operation of the Nacimer Post Ae*4d==e t ame=4-e Air Sampling System in order to promptly obtata a containamat air sample under a ancImar reactor =e*4d==e condicina to:
1.1.1 Esiep r=d4 =ed a= exposure less than three (3) Emms whole body dose and eighteen and thg x ; =sers (18 3/4) Rams to autremities for pereoanal taking samplas, 1.1.2 Provide information related to the estant of core damage that has occurred or any be m .'as during aa mee4d==e and 1.1.3 Determine the types and quane4e4== of f4==4a=
products released to the aane=4====e --- "- -. and which any be released to the environment.
2.0 References 2.1 Duke Power Company Euclear Statica Post-Accident Cone =4 - e Air Sampling System Mammal.
2.2 USERC t.-1-?-ry Guides 1.3 and 1.4.
2.3 Station Realth Physics Manual. Section 13.1, Wandling.
Storage, and Disposal of nadiamettve Sources.
2.4 Station Esalth Physica Manual, Section 12.1, operation Procedure for the Nacisar Data -4400 GeLi System.
2.5 Station N--* g Manual. Procedure CP/0/A/8200/05 Enclosure 6.3, Directives for Personnel Conduct in the Hot Laboratory.
2.6 Station N--*g Manual. Procedure CP/0/3/8600/19 Sectica 4.3, 7. - +=" of Thia ==Mata Solution for Post-Aedd==e Gas Sampling.
3.0 Equismen.c 3.1 Equipment required per sampia.
1 Naisene 500 al bottia of Na0E with accompanying vial of Nas $so s*SEsc .
'We-4. w .= 7 p.-.,n, -y, . - . - . - - . , . ,. , _ . , . . , . .
- Fese 2 1 Walgens 500 al thiconiftte sample bottlo.
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1 100 al gas bomb.
1 Stop watch.
1 Shielded container. ;
NOTE: All above equipment is located in the Health Physics Shift Lab in the file drawer labelled " Poet W a4 % c Gas Sampling Equipment", except the ah4m1AmA container d ich is located in the cabinet under the fame hood. All equipment below is u the ^-4g Not Lab.
1 100 al saa bomb .
1 salgene 60 mi bottle.
2 Embber septums.
1 Syringe.
I 1000 al graduated cylinder.
2 50 al graduated cylinder I 100 mi beaker Tyson cubig (approximately one foot in langth).
4.0 Tina leguired 4.1 Sampling unst be completed in less than three (3) hours from the time a decision is unde to take a sampia.
4.2. The sampling-cycle will require two.(2) Health Physics personnel -ry. 1mately one (1) hour per sample, of dich approximately tan (10) ainutes will be spent in the sample
' panel area.. One person will operate the control penal d ila the other will perform transit duties to and from the sampla penal.
5.0 Limits and Precauti _ons l 5.1 only the Station Besith Physicist or his designee can authorize the use of this procedure when needed and should provide 4,..ys;. ate surv=411 ==e= and control of personnel l taking the samples. Entry and azit route to sample panel and control penal area to be determined by EP surveys.
5.2 Inform the Shift Supervisor that saa sampling will be performed and that one Hs Analyser will be inoperabia during sampling. The Shift Supervisor will be notified as to which Hs Analyser is in use per step 6.7.
. - - . . . ? -- - -. --.- - - - - - - - - - -
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,- ycg,3 5.3 Personnel commmaications can be achieved by using extension I 4330 at locartsa 9054 mhW,6 h 4325 at location DD55.
! 5.4 h Tras Area Evacuation mode shall not be used.
5.5 Tha Past Sample Dilution mode shall not be used.
l 5.6 h Samela Line Select Switch shall not be used.
5.7 h tactre Pump must never be used at any pressure other than 0" of Eg.
5.8 Moving the Selector Switch from one mode to another scope all carrent systaa operations. Depressing the Activate panhbuttoa starts operation of the newly selected mode.
5.9 h Radistica Monitor on the control panel will provide i background levels of radiation prior to,~during, and after sampling, and an indication of contamination within the system or panel for progressive samples.
5.10 If the needle of the Radiation Monitor " pets out" on the upper and of the aster scala while the lower scals (ur/hr) is being used, immediately turn the selsetor knob to the higher seals (r/hr).
5.11 If the Radiation Monitor reading cannot be reduced below 1_66 I/hr (see Enclosars 8.2. Tahia II) by purging the system with' Ns, (ses 7.1-steps 7.1.1 thru 7.1.12), do not recurs to tha sample pomel, but contact the Station Health Phys 1cist i m taly for further instructions.
i 5.12 If thieselfate comes in contact with the skin during
! preparation (see 6.0, step 6.3), transferal (see 6.0, step 6.10), or dilution (see 7.0, steps 7.6.8. 7.6.9, and 7.6.11) ,
unsk the affected area as soon as possible with soap sad inkssers water.
t l
5.13 Dilate sagles in accordance with Esalth Physics practices for h=ad14ng radioactive meterials.
5.16 Treat and decome==4==to all spills immediately.
5.13 Dispose of syringes, septums, rubber slaves, etc., in radweste receptacles.
5.16 If problems with the radiation monitor are evident (i.e. no indication of radiation on ths matar) notify the Station Realth Physicist prior to contacting IAE at extension 4420 for I
, -. - .=
Pago 4 cociscanco. Turn ths 5 Inctor Switch to tho 0FF da and discontinue sempligt until the,probles is corrected. Ones
- corrected, contines the procedure where left off.
5.17 If problems with the pressure and/or temperature gauges are evident (i.e. no indication on a seter or no variances during sampling) notify the Station Health Physicist prior to conemeting IAE se extension ser assisr=m =. Tarn the Selector Switch to the 0F? sede and discaccinue sampling = edi the probles is corrected. Once corrected, continue the procedure where left off.
5.18 Projected doses. to person performing transit duties are listed on Table I of Enclosure 8.2.
5.19 one copy of this procedure is required for each souple etken.
4 6.0 Prereonisite System conditions HOTE: Steps in skich person is required to go to the senple panel will be denoted by asterisks (**) to the left of the section number.
Initial / Time .
/ 6.1 Obtain Post-Accident Control Panel key and key
- C415A from Health Physics shift Lab (Ecou #954, level 767)' to unlock H2 Monic r Panel (either train A or 3).
/ 6.2 Obtain thiosulfate package from the fils drawer labelled "? cst-Accident Gas Sengling Equipment" in the Health Physics shift Leb (Roem #954, Level 767).
f The package consists of bottles labelled "2.42E-3 NaCE" with vials attached to the side labelled l
l "Q.3003 ga Na2 320s*$Hzo ."
/ 6.3 Prepare thiosulfate solution per chemistry procedure CP/0/3/8600/19, section 4.3, r=1r' g all precautions listed therein. -(CP/0/3/8600/19 with sampling equipment in Shift Lab.)
/ 6.4 Yarify that breaker #41 on breaker panel 1EJ is closed to provide pcvar to the system. The panel is I
at location MM56 on level 750. Contact Shift Supervisor before closing breaker.
/ 6.5 Verify that H Monic 2 r is in the Standhv mode. If
. .. . . . - - , - . . . .. .. ... -....-- ... -. -- . . . .A . . . . . . . . . __
l
~
~
~
Pego 5 H Monic r is n2t in tha St.:ndhv noda, uso the 2
alternata train. The H 2 M**iE*# * ** # * 'L 4* "'E location CC53 on level 750, and train 3'at CC53 on level 733.
/ 6.6 Open sample line inlet solenoid valve to divert cone =%t atmosphere to the sample panel by depressing the black N pushbutton located on the E2 Monitor Panel andar the Seele touted to PAMS Panel labal. Accompanying red power light shculd.
energiza.
/ 6.7 Open sample line outist solenoid valve by turning the Isolation Yalve Onen key lock switch, located on the H Monitor Panel, t the N position.
2
/ 6.8 chtain courshnt atmosphere by earning sa:: role Location Selector, located on the E M *i"
- P***1' 2
to Pos. #1. Ace ==panying red power light shculd energize.
/ 6.9 Notify shift supervisor at extension as to which train is in use.
/ " 6.10 Pour concents into the thiosulfate tank, which is as top of the sampla panal (location CCS2, level 733).
Leave the cap off of the thiosulfata tank after transferring the chiosulfaca.
l
/ **
6.11 verify that all four servica valves are open before operation. These are the DI. VI, and N2 '"1***
located on the outside upper left sido of the sampla panel, and the T3 valva located on the inside upper center of the sa=ple panel. These valves are opened by rotating the black switchea countar-clock:sise oce-quartar turn to the upward position.
/ 6.12 Plug in vacunn pu=p. (Racaptacia is located benanth the friskar hesida Hydrogen Analyzer Panel.) Vacuu:a m should energize.
NOTZ: 6.13 thru 6.22 concars initial centrol panel setrings. Control p - 1 is at locatien CC53, level 750.
/ 6.13 The Samole volume Select zust be set on Scall.
I
. . . - . - -~ - - -- --. - - - - - . -
~
Paga 6
'/ 6.14 Th2 Dilution 7als:ne Salect =st ha ccc on Larto.
./ M1 A e '-~ Sertech smaec h La che off m 4.
/ 6.16 Move the Sysrem Purte toggle switch to the Nor=Al position.
/ , 6.17 Mave the Refill cos31e switch to the off (devn)
Position. ,
-/ 6.18 Turn the TC Switch to oosition 1. which is the thersoccuple setting to nessure sa:xple line tersperature. Position 2 vill zaasure anbient te:xperature within the sa=ple panel.
/ 6.19 Turn Inv Lock Swiceh to Pever on. Pcver on light should energits.
/ 6.20 Turn the Radiation Manitor g by moving the toggle switch (located below the meter) to the Uo poattien.
/ 6.21 Turn the selector to 1ATT and verify that the needle is in the " red test region" on the right end of the f
scale. If reading is below the test region, notify the Station Health Physicist prior to contacting IAZ at extension' for assistance. Do not cont 1=ne until IAE verifies that the proble:m is corrected.
/ 6.22 Select the appropriata :ste so that the needle is on-the meter scale by first turning the selector k=ob to higher scale (r/hr) and, if necassary, to lower scale (=r/br) .
7.0 coerating Procedure NOIZ 1: All steps in the operating procedure are
- cary unless othervise specified.
NOTI 2: Steps in which person is required to. go to the sa=ple panel vill be denoted by astarisks (**) to the left of the section ac=ber.
NOIZ 3: The three sig=-off lines en each of steps l
l 7.1.3 thru 7.1.11 are used per step 7.6.5
! ss necessary.
7.1 System Purge j' / 7.1.1 Turn Select Switch to Svstes Parte.
/ 7.1.2 Move Norsel-Sa= ole Purte toggle switch to l
. . . _ . . . -, - . . . .L . -- - - - . .- - - . - . _ . .._
r I
e
Fag 3 7 Samolo Purne.
l /
- /
/ , 7.1.4 Depress Evse pushbutton (Erse light should
/ ,
energize) and watch the pressure gauge slowly
/ drop to -25" of Hz.
! / 7.1.3 Uban pressare reaches -15" of Hz depress the
/ scos pushbottoa.
l /
/ 7.1.6 Press down and release the Gas Purze toggle
/ switch and watch the pressure gange rather
/ swiftly rise to +10" of Ha.
/ 7.1.7 Uhan pressure r==ch== *10" Hz, depress the h ,
, / pushbutton.
. /
, / 7.1.8 Depress the Activata and then the Evac
/ pushbuttons and watch the pressure 3 saga drop
/ to 0" of Hz.
/ 7.1.9 Uhen pressure r==eh== 0" of Hz, depress the
/ Stoo p--hk-tton.
/ *
/ 7.1.10 Depress g pushbutton and wait for thirty
/ (30) seconds.
/
/ 7.1.11 Depress Stoo pushbutton.
/
/
/ 7.1.12 Move Normal-Sample Purse toggle switch to Norus1.
/ 7.1.13 Tara Selector Switch to Solutica N--=aut.
/ 7.1.14 Attach the TS ===y1= bottle to the sample 4 panel by inserting the plastic hose into the bottle which is located on the lower left sida
. of the panel. Attach the gas sample bomb to l the sample panel on the lower right side of Penal.
.. . = . . . . . . . .
e
l
- Pcge 8
/ 7.1.13 Itacord the Radistica Monit r reading as a
'--h _ 'Jafammass whers apeagded e Enclosure 8.1. l
/ 7.1.16 Record sample line temperature reading for l
, . sample volume calculations where specified on l
Enclosure 8.1. Proceed to section 7.2.
7.2 Solution Chansecur
, / 7.2.1 Depress Activate pushbutton. ,
! / 7.2.2 Depress Flush p -' 8 Eton and hold thirty (30) seconds.
/ 7.2.3 Depress Purne pushbuttaa and hold thirty (30)
W=.
/ ___
7.2.4 Depress g pushbutton and hold for thirty (30) seconds.
i
/ 7.2.5 Nove the Eefill toggle switch to g, (up) positica and wait two (2) minutes and than nove toggle switch back to E (down) position.
/ 7.2.6 Tura Selector Switch to Dilution volume Eveenation and proceed to sectica 7.3.
7.3 Dilution volume Evacuation
/ 7.3.1 Depress the Activate pushbutton and watch the pressure gange drop to -25" of Ha,
/ 7.3.2 Uhen pressure reaches -15" of Ha. tura Selector i Switch to Sample Rectre and proceed to sectica 7.4 7.4 sample Recire )
/ 7.4.1 Depress Activate pushbutton and wait for five (5) =4==e== .
/ 7.4.2 Note pressure gauge reading on sample inlet 1 l
line, and record where specified on Zaclosure l 8.1.
/ 7.4.3 Depress Sample pushbutton and wait for one (1)
. sinate.
/ 7.4.4 Depress g tpushbutton and wait for tea (10) .
seconds.
/ 7.4.5 Enter cima of sample trap where specified on Enclosure 8.1.
I
=
l
~ . . . - . - . - - . - .
Page 9 *
/ _ 7.4.6 Tura S-leet-r Swit*h es Samoin Dilution and proceed to section 7.5.
7.5 Sample Dilution
/ 7.5.1 Depress Activate pushbutton.
/ . 7.5.2 Depress Slow pushbutton and watch pressure g.Jage rise , slowly to 0" of Hz.
~
/ 7.5.3 When pressure reaches 0" of Es. dep.'ess the l
Seos pashbutton.
/ 7.5.4 Depress the lectre pushbutton and wait for five (3) ainstes.
/ **7.5.5 Close the gas sample bomb outist valve, unit five (5) =*=da and close the inlet valve.
/ 7.5.6 Depress the Stoo pushbutton.
/ 7.5.7 Tura Selector Switch to solution ^=---* and proceed to sectica 7.6.
7.6 Samples Collection
/ 7.6.1 Depress Activate pushbutton.
/ 7.6.2 Simultaneously depress and hold the E M pushbutton and the Emotv pushbutton for five (5) ainutes. TS should transfer into the T5 sample bottle.
/ 7.6.3 Depress Purse pushbutton and hold one (1) ainats.
/ 7.6.4 Depress T5 Sample Grab r " P .
/ 7.6.5 Tara Selector Switch to System Parme and repeat steps 7.1.3 thru 7.1.11 as needed to reduce radiation levels within the sample panel to as I
near the bach.. 4 level (listed on
.yy..y.iate Enclosure) as possibia, or until no l
l noticeable decrease is observed on the Eadiation Monitor from one 33 purge to the next. Escord the Radiacion Monitor reading where specified on Enclosure 8.1.
NOTE: At this point, sample penal controller can proceed to Chemistry Hot Lab.
/ ** 7.6.6 Unplug vacuna pump. (Receptacle is located l
~ ~ ~ * * * * * * ~ ~ ~ ~ ~
,_ . _ . . . . . . ..- . - . . . . *w-==~~>- -
e e
. : Paga 10 '
t t under the frisker b~esida the Hydrogen Analyser Pumal.) t
/ 7.6.7 Tightly cap the TS sample bottle and d4=eaa==et the gas sample bomb from the sample panel.
. Radioactive soortes are to be handled according to Sectica 13.1 of the Statica Esalth Physics Manual.
/ 7.6.8 Place the TS Sample Bottia and the gas sample bomb into sh4=1 dad container and transport to the chemistry Hot lab (Boos #1105. level 775).
Place the samples in the designated =h4=1 dad area provided for hot samples.
/ 7.6.9 Transfer the thiosulfate solution into a 1000 al graduated cylinder to determine the chiosulfata diluttoa volume (TDV). Record this valna where specified on Enclosure 8.1. Use standard chemistry laboratory cachniques, and precasticas per Chemistry procedure CP/0/A/8200/05 Enclosurs 6.3 (Enclosure is posted in the Hot Lab).
/ _
7.6.10 Transfer fifty (50) el of the thiosulfata-l sampla into a sixty (60) al Malgens bottle -
using techniques and precautions referenced in 7.6.9. Tightas cap onto the aumpin bottle.
/ 7.6.11 Transfer the prepared thiosulfata sample and gas sample bomb to the H.P. Count Room (Ecos
- 947A, level 768) for analysis. Samplas will be analyzed per Station 3.P. Manual Sectica 12.1, Operating Procedure for the NueT==e Dats 6600 GeLi Systan. Sample data on Enclosure 8.1 of this procedure will be required for analysis.
/ 7.6.12 If additional sample dilation is required for GeLi counting, perform the dilutions in the chemistry Hot lab per techniques and precantions referenced in Section 7.6.9, until samples are suitable for analysis. ' Dilation O
! . . Pase A1 -
t
! factors used will be datornised by the Couac
~
' h7spervisor or his designee. and valmas inserted where specified on Enclosure 8.1.
-/ 7.6.13 Excess samples are to be disposed of per
==*J=1*=~ referenced in 7.6.8.
/ _
7.6.14 If another comeMn===e air sample is needed.
repeat Steps 6.2. 6.3. 6.10. and 6.12 and begin
,c -- 9. at Sectica 7.1.
/ 7.6.15 If no =ddie4a==1 comed ====e air semples are needed, turn Selector Switch to g .
/
7.6.16 . Turn Env Lock Switch to of,(. f
/ 7.6.17 -Claes semple line valves Iry depressing g pushbuttom om 2E Monitor Panel. The .- ' ' _ t E ---
is under the Samole Easted to PAMS Panel label.
/ 7.6.18 Close sample line outlet solenoid valve by e= ming the Isolation valve Osen key lack settch located on the E Monitor Panel, to the 2
g position.
/ 7.6.19 Turn Samole Location Selector, located on the R2 Monitor Panel, to M . Lock H2 N"" ***
Panel.
/ " 7.6.20 Close all four (4) service valves by turning one-quarter turn c.lockwise.
/ 7.6.21 Notify Shift Supervisor of sampling completica and that the Is Analyser used during sempling is operable.
/ 7.6.22 Notify the Station Realth Physicist when semple
- analyses are complace.
I 8.0 r= tm 8.1 Sample Data Skiest 8.2 Table. I - Projected Does to Person Performing Transit Duties Table II - M=w4-== A11amable Dose Este in Sample Panel Area-8.3 Entry and Exit Esote to Sample Panel t
- - - . - - - - - - - - - - - -~ - ~
- . , - , , . --.---,,,-.a . - , - - . - - , - , . , - ,- - - - - - , , - , ,
IP/0/3/1009/15 ansamamme44 Page 1 of 1 SAMFLE DATA SEIIT Eames Dates Time of Sample Traps nadiation Meafter Reading per 7.1.15:
Radiatica Meatter Reading per 7.6.3:
Sample Line Temperature (*F):
I (TC Fosition 1 Only)
Time of Thiosulfate Sample Analysis __
. Time of Ces Sample Analysis Sample Volume (SV)
,, ,g,3, 293 + (5/9) ( *F - 32) (14.7 + F "Is) 293 14.7 SV =.
cc .
First N-1 fate Dilution Factor (TDT g)
, TDFg= W TDT DFg= ,
l Second Thiosulfate Dilation Factor (TDF2 )
gy , DF gx si of sample al of DI water DF2*
1 NOTE: TDF will be determined by Count Room Supervisor or his designes, 2
es necessary.
- I
'% - . . . . - - . . . . . . - - . - -- - = = - + . - ___
7....
, . . - , . . . -- , . , , , , - .-,-c,.
IF/o/s/ loot /15 Esalosure 8.1 Fase 2 of 2 First Gas Dilation Facto: (GDFg )
i y .
&* 1 8
4 10 1 . GDr 8 1
Second Gas Dilaston Factor (GDF2)
GDF a GDF. z cc of sample l 2 ,
Ii ec container voluma t.
i j GDF2*
i2 t
?
[
WOTE: GDF will be detetuined by Count Room Supervisor or his destgese, 2
at necessary.
f.
l l
i .'i I.
i c
i i
I l
l l
l l,
l .
p
- + . . ~ -s-w 1 a-
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c.
s s ,s e o -
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m EP/0/3/1009/15 ,
.,,, n. wi s.2 ,
Page 1 of 2
'J'
,s
(/ >
t y g ., >
p :
,y Table I - Projseted Dosa to Person Partorming Transit Duties. 1 -
n
- 1- r,
)
Tims' Post-Accident Gours) ', . Does (1) 0;'
0 i 3.041 , s 1
, 1.977 ,
2 1.429 ,
' ~~
3 .
-s 1.125 1
4 ,( .,
0.912 5 '.- \
O.821 10 , 0.517 ,
24 -
, O.231 ,
k-NOTE: Any dose at a tima not listed caihe datarained by .
crose-raferencing on the graph. (Graph oO nest page).
.v (
h vertical axis is the fraction of the Tia=1,= 0 dose. ,f h horizontal axis is the time in hours post-accident. ,' N Tabla II a' Maz1mma Allouable Dose. Esta- in $4mpis Fanal' Area.
' ~
In rafarence to Section 5.10:
(z 1 )( 11 hr.) =31 ,
hr. 60 .
I ' 4 x = 16.36 ,
% \
hr s
I z = 16 1
' s
, hr h re:
I = angium ab.ca*ble dose rata in 1/hr 11 ,
W = tdas in semple panel ares 1:: tours, which includes: ,
1 minate transit to and from sample penal 10 minutas at sample panel ,
31 = allouable whole body dose par quarter 9
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