ML20050E249
| ML20050E249 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/09/1982 |
| From: | Parker W DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML16162A349 | List: |
| References | |
| PROC-820309-01, NUDOCS 8204130143 | |
| Download: ML20050E249 (150) | |
Text
._. . - -
TABLE OF CONTENTS O Emergency Telephone Numbers - (03/01/82, Rev. 6)
AP/0/A/1000/01 Event Index - (03/09/82)
AP/0/A/1000/02 Unusual Event - (03/09/82)
AP/0/A/1000/03 Alert - (03/09/82)
AP/0/A/1000/04 Site Area Emergency - (03/09/82)
AP/0/A/1000/05 General Emergency - (03/09/82)
AP/0/A/1000/06 Procedure for Initiating Protective Action Guides for the General Public in the Emer-gency Planning Zone - (03/09/82)
AP/0/3/1000/07 Procedure for Offsite Dose Calculations by Control Room Personnel or Emergency Coordinator during a Loss of Coolant Accident - (02/26/82)
AP/0/A/1000/08 Proce, dure for Response Actions for Accidents /
Emergencies - (10/15/81)
AP/0/A/1000/10 Procedure for Emergency Evacuation of Station Personnel - (02/02/82)
Station Directive 2.9.1 Station Assembly and Evacuation Procedure -
(08/20/81, Original Issue)
Station Directive 2.9.2 Emergency Response Organization and Training -
(08/20/81, Original Issue)
Station Directive 5.1.3 Personal Injury Procedure - (10/19/81)
PT/0/B/2000/04 Procedure for Establishment and Inspection of the Technical Support Center - (03/01/82)
CP/1/A/2002/04A Post Accident Liquid Sampling of the Reactor Coolant System (12/01/81)
CP/2/A/2002/04A Post Accident Liquid Sampling of the Reactor
- Coolant System (12/01/81)
CP/3/A/2002/04A Post Accident Liquid Sampling of the Reactor Coolant System (12/01/81)
CP/1/A/2002/04B Post Accident Liquid Sampling of the Low Pressure Injection System (12/01/,81)
EPM 001/A Revision, March 9, 1982 8204130143 820402 PDR ADOCK 05000269 F PDR
Page 2 4.a l
1 Table of Contents (Implementirg Procedures - Continued)
U CP/2/A/2002/04B Post Accident Liquid Sampling of the Low Pressure Injection System (12/01/81)
CP/3/A/2002/04B Post Accident Liquid Sampling of the Low Pressure Injection System (12/01/81)
CP/0/B/4003/01 Procedure for Environmental Surveillance Following a Large Unplanned Release of Gaseous Radioactivity - (08/20/81)
CP/0/B/4003/02 The Determination of Plume Direction and Sector (s) to be Monitored Following'.a Large Unplanned Release of Gaseous Activity - (08/20/81)
HP/0/B/1009/09 Procedure for Determining the Inplant Airborne Radioiodine Concentration During Accident Conditions - (07/09/81)
HP/0/B/1009/10 Procedure for Quantifying Gaseous Releases Through Steam Relief Valves Under Post-Accident Conditions - (07/08/81)
, HP/0/B/1009/11 Projection of Offsite Dose from the neon-trolled Release of Radioactive Materials V Through a Unit Vent - (07/08/81)
HP/0/B/1009/12 Distribution of Potassium Iodide Tablets in
, the Event of a Radiciodine Release - (03/02/82)
HP/0/B/1009/13 Procedure for Implementation and Verification for the Availability of a Back-Up Source of Meteorological Data - (07/08/81)
HP/0/B/1009/14 Project Offsite Dose from Releases other than Through a Vent - (01/29/82)
HP/0/B/1009/15 Procedure for Quantifying High Level Gaseous Radioactivity Releases During Accident Condi-tions - (08/07/81)
HP/0/B/1009/16 Procedure for Emergency Decontamination of l Personnel and Vehicles on-site and from l Off-site Remote Assembly Area - (03/02/82)
IP/0/B/1601/03 Environmental Equipment Checks - (02/25/81), j l
JM/ MET /AT/WD/WS 07.00 Weekly Check and Calibration Procedure for O the Meteorological Monitoring System - (03/02/81, Rev. 0)
EPM 001/A Revision, March 9, 1982
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1 EMERGENCY TELEPHONE NUMBERS '
il This directory provides a listing of celephon'e utsbers for various personnel and agencies that may have a part in dealing'.with an emergency situation or providing other a'ssistance as needed 'at Oconee Nuclear Station.
/ /
/ ,
TABhEOFCONTENTS s
NOTIFICATION OF AGENCIES, CRISIS MANAGEMENT TEAM, KEY COMPANIES ..... 1 - 5 EMERGENCY FACILITY LOCATIONS .....................'................... 6 *l
\v OCONEE TELEPHONE ACCESS CODES- ...................................... 7 TECHNICAL SUPPORT CENTG. , . . . . . . . . . ;. . . . s. . . . . . . . . . . . . . . . . . . . . . . . . . 8 - 10 rs OPERATIONAL SUFFORT CENTER . . . . . . . . . . . . . . . ., . . . . . . . . . . . . . . . . . . . . . . . . . . 9 HEALTH PHYSICS CENT'.s ...........................'..................... 8 CRISIS MANAGEMENT CENTER ............................................ 11 - 13 BACKUP CRISIS MANAGEMENT CENTER - (Liberty) . ...!..................... 14
~
CRISIS NEWS CENTER AT OCONEE .................'........................-15 .
i NUCLEAR REGULATORY COMMISSION ...'.................................... 5 NRC HEALTH PHYSICS NETWORK TELEPHONES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . '.- 16 OCONEE EMERGENCY RADIO .............;.........................'.. 4.... 17 EMERGENCY NUh3 EJ.S' ,P ickens County . . / .:.~. . . . . . . . . . . . . . .'. . . . . . . . . . '. . . 18 EMERGENCY NUMBERS <- Oconee County . . . S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 s ,
\ '
'OsT l f '
. Rev. 6, 3/1/82
t
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Superintendent of Technical Services T. B. Owen, Office . . . ............. .
s Home . . . . .......... . . . .
Superintendent of Maintenance J. M. Davis, Office . . . .............. v Home . . . . ..............
Superintendent of Operations J. N. Pope, Office . . . . .............
Home . . . . . .............
Superintendent of Administration i J. T. McIntosh, Office . . .............
} Home . . . ...... .......
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- 12. CRISIS MANAGEMENT CENTER ACTIVATION The Duke Power Crisis Management Organization will be notified for all Alert, Site Area Emergency, or General Emergency class emergencies. The Crisis Management Organization is notified by contacting one of the persons listed below. If the first person can not be reached, go to the next person O down the list until one person is contacted. The person contacted is re-sponsible for implementing the Crisis Management Plan notification require-ments.
Manager, Nuclear Production Division H. B. Tucker, Office . . .
Home . . . .
l l Vice-President, Steam Production W. O. Parker, Jr., Office . .............
Home . . .............
l Manager, Technical Training Center R. M. Koehler, sffice . . .
Home . . . .
............. i Steam Production Operations Duty Man . . . . . . . . . .............
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- 6. SOUTH CAROLINA DEPARTMENT OF HEALTH AND ENVIRONMENTAL CONTROL, BUREAU OF RADIOLOGICAL EEALTH (Warning Point State of South Carolina)
Director, Heyward G. Shealy, Office ... . .... ...
Answering Service After Hours . .. .. .. ..
Home ............
- 7. COUNTY CIVIL DEFENSE AGENCIES Oconee County Director, Walter B. Purcell ........
Pickens County Director, William D. Evett, Office . ...
(After hours can be reached through the Sheriff's Office)
- 8. COUNTY SHERIFF'S DEPARTMENTS Oconee County (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) . . . ..... ..... ...
Pickens County (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) . . ...............
- 9. MEDICAL ASSISTANCE Oconee Memorial Hospital Ambulance Service . .......
Oconee Memorial Hospital Switchboard / Emergency Room ...
- 10. FIRE ASSISTANCE Oconee County Rural Fire Protection Association .....
Woods or Forest Fire (Oconee County, Oakway Tower) . . . .
Woods or Forest Fire (Pickens County, Woodall Mt. Tower) .
- 11. TECHNICAL SUPPORT CENTER ACTIVATION (If the first person can not be reached, go to the next person down the list until one person is contacted)
Emergency Coordinator / Station Manager J. E. Smith, Office . . . ..............
Home . . . . .......... ....
Assistant Station Manager G. E. Vaughn, Office .. . ......... ....
Home . . . ...... . .... ...
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l' DUKE POWER COMPANY OCONEE NUCLEAR STATION NUMBER CODE FOR IDENTIFYING PERSONNEL / ACTIVITIES TO BE NOTIFIED NOTE:
Telephone. notifications of emergencies including emergency tests or drills to the NRC and other off-site agencies are not considered complete until direct voice contacts are made with the responsible representatives of the agencies being notified. If the call is made after hours and the agencies' answering service is on duty, request for the duty person to call back as soon as they can be reached.
Otherwise, the leaving of a message is not considered a complete notification.
CODE I.
NUCLEAR REGULATORY COMMISSION by Red Phone within one hour.
2.
UNIT COORDINATOR /0PERATIONS DUTY ENGINEER who will notify: A,B,C A.
Superintendent of Operations and Station Manager B. Steam Production Duty man . . . . . . .' . .......
C.
Corporate Communications (Unusual Event only) . . . .
- 3. STATION MANAGER . . . .
O- J. Ed Smith, Office . .
Home . . .
4.
BABCOCK AND WILCOX RESIDENT ENGINEER Bill Street, Office . ..
Home . . . ..
(If Bill Street cannot be reached, call)
L. H. Williams, Office . ...'........ ......
Home . .
5.
STATION HEALTH PHYSICIST / DUTY HEALTH PHYSICIST C. T. Yongue, Office . . .
Ilome . . . ..
Ac h
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4 13. WATER DEPARTMENTS Should releases of radioactive effluent into Lake Keowee or Lake Hartwell potentially effect municipal water intakes or exceed technical specifi-cations. Contact the appropriate authorities as indicated below:
Lake Keowee l f~$llf-Seneca, H. J. Ba1 ding, Office . . . . . .......
Home . . . . . . ....... f,.s Lake Hartwell l'~~
City of Clemson -
p.
,+ +<
Mayor of ~Clemson, Office . . . . . .......... .1 Home . . . . . . ......... 1,'- e.
(If the mayor cannot be reached, call one of the following
~
.. _. A .z- .
Clemson Administrator's Office . . ......... cj g . s .
Home . . . ....,..... : ; p? e.
-' :,a/4 e t/
Clemson Filter Plant (0700-1700) . ......... :
y' .'-
', c-
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)
Clemson University jpf .
p-President's Office . ....... ......... :,e . . )-
y Home . . .... . . . .........
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(If the-President cannot be reached, call) h ~' '. : :
Clemson University Physical Plant (0800-1630) . . . . 4 Anderson Water Works (24 Hr. Number) . . . . .......
.: . v..
AGENCIES THAT MAY RESPOND TO AN EMERGENCY AT THE OCONEE NUCLEAR STATION -IU -
's
. - *- ti-
LAW ENFORCEMENT -
S. C. Highway Patrol (Greenville, S.C.) . . ....... Os : - 1 e.
S. C. Enforcement Division (Columbia, S.C.) ....... ' '~ y ,. . ?
Communications Check-Officer-of-the-Day
_-{?
...... ., if ^- .
. ' .wN-FBI (Columbia, S.C.) . . . . .... . . . ....... .. g
. . .t BOMB DISPOSAL J. - . :;. .
Explosives Ordinance Disposal Control (Fort Jackson, Columbia, S.C.)
. . . ....... 'f.'.M;.
. 4 RADIATION AND CONTAMINATION ,
REACTS, Department of Emergency (Oak Ridge, Tennessee) . .
(24 hr. number - after 1700 as for Beeper number) . .
DOE Emergency Radiological Monitoring Team (Aiken, S.C.) .
N. C. Division of Emergency Management . .. . . .....
(North Carolina State Warning Point - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) .
Georgia Department of Natural Resources Environmental Radiation Program . .... . ... ..
Communication Check: -
Bill Cline . . . . (0800-1700) . . . . . . . . .
Jim Setser . . . . (0800-1700) . . . . . . . . .
Georgia Civil Defense (0800-1700) ~0pErations-Section . .
After Hours - Duty Officer .............
NUCLEAR REGULATORY COMMISSION
~
NRC Operations Center (via Bethesda Central Office) ... 301-492-8111 NRC Operations Center (via Silver Spring Central Office) . 301-427-4056 Health Physics Network to NRC Operations Center ..... *22 (Touch-Ton 22 (Rotary Di NRC Operator (Via Bethesda Central Office) . . . . . . . . 301-492-7000 US NRC, Region II . . . . . . . . . . . . . . (24 hr.). . 404-221-4503 US NRC, Oconee Reside,nt Inspector ,
BUS TRANSPORTATION Oconee County School Superintendent (0800-1600) .....
(If Superintendent cannot be reached call)
Bus Supervisor, Ralph Robinson (0645-1630) . . . . . . . .
Home .....
Anderson Retail Office (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> number) . . . . . . . . . .
NATIONAL WEATHER SERVICE - METER 0 LOGICAL BACK-UP SOURCE Greenville-Spartanburg Weather Service . .. . (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) .
J
o OCONEE NUCLEAR STATION CRISIS COMMUNICATIONS DIRECTORY The crisis directory is intended for use should the Oconee Emergency Plan require implementation. Both station and corporate level telephone numbers .__
are provided. The station's emergency organization will operate from the Technical Support Center near the Units I and 2 Control Room. The corporate emergency organization will operate from the Crisis Management Center located in the Visitors Center and Oconee Training-Center.
j EMERGENCY FACILITY LOCATIONS Technical Support Center - Control Rooms 1 and 2 Operational Support Center - Control Room 3 Crisis Management Center - Oconee Training Center Alternate Location: Liberty Retail Office Crisis News Center - Keowee-Toxaway Visitors Center Alternate Location: Liberty Retail Office
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OCONEE NUCLEAR STATION TELEPHONE DIRECTORY ACCESS CODES Seneca Lines Ea s Anderson Line .
I Six Mile Line Dial Code (Micro-Wave)
(Charlotte General Office)
(Catawba) -
.) (McGuire)
(Cherokee)
Attendant (To access Bell Line)
Seneca Easley Anderson Six Mile
F f
q OCONEE NUCLEAR STATION CRISIS PHONE DIRECTORY TECHNICAL SUPPORT CENTER Tele hone Number Outside S POSITION /NANE Line Number Emergency Coordinator . ...............
J. E. Smith G. E. Vaughn, Alternate ... ........
Supt. of Operations . ....... ........
J. N. Pope .
Supt. of Technical Services . . ......... .
T. B. Owens Supt. of Maintenance J. M. Davis Supt. of Administration . .............
J. T. McIntosh NRC Resident Engineer . . .............
W. H. Orders B&W~ Resident Engineer . ..............
B. W. Street L. H. Williams, Alternate Station Health Physicist ..... ........
C. T. Yongue HEALTH PHYSICS CENTER .
Environmental Surveillance Coordinator ......
J. J. Sevic Data Evaluation / Report Preparation Supervisor ..
(Off-Site Dose Projection)
C. Harlan Surveillance and Control Coordinator .......
M. D. Thorne Support Functions Coordinator . . . ........
- J. A. Long s
Dosimetry Records . ........ .... ... .
CONTF,0L ROOM Unit 1 . . ...... . ....... .. ..
Unit 2 . . . . . . . . . ........ ...
Unit 3 . . . . . . . . . . . . . . . . . ...
Shift Supervisor (Unit 1 & 2) ........
Unit 3 . . . . . . . . ...
TELECOPIER Technical Support Center . ..........
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<N OCONEE NUCLEAR STATION l
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\Q CRISIS PHONE DIRECTORY CRISIS M AGEMENT CENTER Private ONS Position /Name Line Switchboard v .
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RECOVERY MANAGER y!
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-1 H. B. Tucker .. .tg .y.p . , w . , . ..g. ' . M:n.... <" :
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W. O. Parker ~'
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R. M. Koehler -
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SCHEDULING / PLANNING MANAGER Ud '-
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R. W. Bostian j $ '. .
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Alternates: 4 ' - D '. #: 'M " " .I-i.?$ ' ~ , -'.
F. C Hayworth ? :',-'
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J. C. Leathers J e .
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HEALTH PHYSICS /RADWASTE MANAGER 7 K. 'r , ~. g -
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W. A. Haller 5 ^ ' ~ '
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' . .'.&. . W. J 5 ) . 84
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Alte rna te s : 3 I.''.~ -m -
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R. C. Futrell - .
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B. E. Davis e : -;- . 3 v
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R. T. Siinril E.- - . -J s
- .s TECHNICAL SUPPORT -
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.64 K. S. Canady .. 3 .
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H. T. Snead .
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W. A. Coley 1 - . .' '
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.. .... -. ' . .. . .. . i DESIGN AND CONSTRUCTION SUPPORT ' '- t ~ .c s. :-
4 MANAGER <--'
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m - 1 J. L. Elliot ' ~ ^
- . 2. . I * ' : : . "? . . " .: 1 Alternates:
D. L. Freeze S. K. Blackley l
C. J. Wylie S. B. Hager l
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Telephone Number Private U. S Position /Name
- Line Switchboard 0FFSITE RADIOLOGICAL COORDINATOR L. Lewis (Offsite Dose Projection)
Alternates:
W. P. Deal M. S. Tuckman ADMINISTRATION AND LOGISTICS MANAGER J. T. Moore Alternates:
R. F. Smith E. D. Morton R. H. Lynn S. M. Kessler R. N. Johnson ADVISORY SUPPORT i
Nuclear Regulatory Commission J. P. O'Reilly Alternate:
F. J. Long Babcock & Wilcox (NSSS Supplier)
J. D. Phinney Alternate:
R. B. Kosiba CORPORATE HEADQUARTERS (contact with Governor)
A. C. Thies Alte rna te :
W. H. Owen DATA COORDINATION (Telecopier)
GENERAL OFFICE SUPPORT CENTER .
Health Physics and Radwaste 2390 Wachovia Center
. . _ . , . - - . _ _ _ _ . _ . _ _ _ - = . _ _ - _.___ .- _ _ ___._ - -____
t GENERAL OFFICE SUPPORT CENTER (Continued) l Technical Support l 1760 Wachovia Center Design and Construction Electric Center
. Third Floor, Room 32 Recovery Manager Wachovia Center Room 1680 (Speaker Phone)
Scheduling and Planning Wachovia Center Room 1680
. Administration and Logistics Wachovia Center Room 1514
- f. Crisis News
/ Power Bldg.
5th Floor
- Offsite Radiol ' al Coordinato Wachovia Center Room 2384 l l
Nuclear Regulatory Commission Wachovia Center Room 1728 __
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OCONEE NUCLEAR STATION CRISIS PHONE DIRECTORY BACKUP CRISIS MANAGEMENT CENTER LIBERTY RETAIL OFFICE, LIBERTY, S.C.
. AREA CODE - '
Telephone Number RECOVERY MANAGER SCHEDULING / PLANNING PUBLIC INFORMATION OFFICERS State of South Carolina Oconee County , -
Pickens County DESIGN AND CONSTRUCTION TECHNICAL SUPPORT 0FFSITE RADIOLOGICAL COORDINATOR ADMINISTRATION AND LOGISTICS HEALTH PHYSICS /RADWASTE GOVERNMENT AGENCIES NRC ,
State of South Carolina Oconee County Pickens _
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1 OCONEE NUCLEAR STATION n
CRISIS PHONE DIRECTORY l
CRISIS NEWS CENTER KE0 WEE-T0XAWAY VISITOR'S CENTER
'l Tele hone Number Private ONS l Position /Name Line Switchboard CRISIS NEWS DIRECTOR Mary Cartwright Alternate:
Ira Kaplan COMMERCIAL NEWS MEDIA (Active Numbers)
- For drill purposes only COMMERCIAL NEWS MEDIA (Inactive Numbers)
Activated only during an actual emergency i NRC/ STATE / COUNTY PUBLIC INFORMATION OFFICERS (PIO'S)
NRC State of South Carolina l Oconee County '
Pickens County D
e
.,w-
s e NRC HEALTH PHYSICS NETWORK TELEPHONES ,
The NRC's Health Physics Network (HPN or Black Phone) connects all Nuclear Power Plants and Fuel Facilities to NRC Regional Offices and to NRC Head-quarters Operations Center. The phone is intended to support Health Physics Operations in an emergency but can be used for daily voice traffic and fac-simile transmittal.
There are four points at Oconee Nuclear Station which can access the HPN net-work. The station has jacks for the HPN phones in the Units 1&2 Control !
Room area, the Unit 3 control Room area, and in the training center. Any of l accessedbythe1l$kislocatedintheNRCrlesidentinspectorsoffice.these 1
The phone is used normally with the exception; NO DIAL TONE OR RINGING IS HEARD.
In addition, ringing only lasts 30 seconds, so after 30 seconds if the party has not answered, you must hang up and redial. )
A complete directory of HPN telephone numbers and services are with each phone. :
1 For convenience, the codes must often used are listed below:
HPN Phone Code
- 1. NRC region 2 (Atlanta) office
- 2. NRC headquarters (og) d
- 3. B&W Research Center
- 4. Oconee NRC Resident Inspector
- 5. Oconee Nuclear Station l
- 6. All NRC region 2 Resident Inspectors
- 7. All region 2 Operating Nuclear Plants In addition, the calling party may " conference" any phones during conversation by simply dialing the appropriate code (s). Any number of stations may be added in this manner. .
Any problems w' is j$one system should be reported to Southern Bell in Green- i ville at es ..; s :
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- s OCONEE NUCLEAR STATION EMERGENCY RADIO
/"?' .
The dall letters identify the Emergency Event Radio frequency. The following is a listing of radio locations, unit call letters, and identifiers.
Use identifiers only in transmission (For example, message may start with
" Control Room to Alpha" and response will be Alpha to Control Room).
ONS Base Station Remotes Location Unit Call Letters Identifier
- 1. Unit 1&2 Control Room Control Room
- 2. Crisis Management Center CMC (Training Center)
- 3. Technical Support Center TSC Coded Squelch Radios (NOTE: Above 3 Base Stations can activate squelch to the following radios by dialing encoding numbers.)
Location Encode Unit Call Letters Identifier
- 4. Pickens Co. (LEC) -
Pickens Co.
Pickens Co. (Courthouse) Pickens Co.
Pickens Co. (C. D. Office) Pickens Co.
- 5. Oconee County (LEC) Oconee Co.
- 6. State FEOC - Clemson State FEOC ALL ABOVE RADIOS MAY BE ACTIVATED BY DIALING ENCODING NO.
Field Monitoring Teams Location Unit Call Letters Identifier
- 8. Field Monitor Coordinator Leader -
- 9. Field Monitor Team Alpha
- 10. Field Monitor Team Bravo
- 11. Field Monitor Team Charlie
- 12. Field Monitor Team Delta
- 13. Field Monitor Team Echo
- 14. Field Monitor Team Foxtrot TO COMMUNICATE BETWEEN BASE STATION REMOTES (1, 2, 3), THE INTERCOM MUST BE USED' The following procedure must be used: ,
l
- 1. Push INTERCOM button and hold
- 2. Push MIKE button and hold i
- 3. Send message (example, CMC to TSC)
- 4. Release both buttons to receive a response. ,
b EMERGENCY OPERATION CENTER ,
Pickens County Primary Number .. ... . ....... .......
EXECUTIVE GRO'P U County Administrator . .. ... .........
EOC Director . . . .. . . .... ..... ...
OPERATIONS GROUP
- i Fire . ....... ......... ......
Police . ... .... ........... . ..
Public Roads . ... . ........ ......
Emergency Welfare Services . . ..........
i Damage Assessment .... ....... .....
Radiologi' cal Defense . ......... .....
Rescue Squads .. ... ........ .....
PUBLIC INFORMATION'0FFICER CRISIS NEWS CENTER-ONS
- State of South Carolina Oconee County Pickens County
. NRC
{
CRISIS NEWS CENTER LIBERTY RETAIL OFFICE
- State of South Carolina Oconee County Pickens County ~ ~ ~
NRC , ,
- Call any one of the listed numbers to reach group desired.
W
s EMERGENCY OPERATION CENTER l .
Oconee County Primary Number (24-hour) .. . ......... ...
OPERATIONS
- l Fire Protection .. .. .............
i l Police . . . . . . . .. .......... ...
Public Roads . .. . .. .............
Emergency Medical Services . . ..........
1 Rescue Squads . .. .. .......... ...
ASSESSMENT
- i .
Emergency Welfare Services .
i xeg Radiological Defense . .............. !
Damage Assessment . ... ............
EXECUTIVE GROUP *
! Supervisor / Chairman County Council . . . . . . . .
I l EOC Director . . . . .. .......... ...
Financial Officer . .. ............. .
FNF Representative . .. .............
PUBLIC INFORMATION OFFICER CRISIS NEWS CENTER-ONS
- State of South Carolina Oconee County Pickens County NRC CRISIS NEWS CENTER LIBERTY RETAIL OFFICE
- State of South Carolina Oconee County Pickens County .
( NRC v'
- Call any one of the listed numbers to reach group desired.
m INFORMATICR DNLY
- Form SPD-1002-1 DUKE PO'JER COMPANY (1) ID No: AP/0/A/1000/01 PROCEDURE PREPARATION Change (s) N/A to PROCESS RECORD N/A Incorporated (2) STATION: Oconee Nuclear Station (3) PROCEDURE TITLE: Initial Determination of Emergency Action Level s 0 i >
(4) PREPARED BY: la DATE: I[M (5) REVIEWED BY: DATE: 7 1
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Cross-DisciplinaryReviewBy(: N/R: M_
(6) TEMPORARY APPROVAL (IF NECESSARY):
By: (SRO) Date:
g ) By: m n Date:
(7) APPROVED BY: s1 k % Date:
4 (8) MISCELLANEOUS: -
Reviewed /Aprv. ' By:'9,7 - Date: S A Cf //
Reviewed / Approved By: Date:
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FORM SPD-1001-2 l - DUKE POWER COMPANY NUCLEAR SAFETY EVALUATION CHECK LIST j
l ) (1) STATION: h UNIT: 1 2 3 i U' pTiiERj .. ct #_./ s -
l i (2) CllECK LIST APPLICABLE TO: M / o / // / ,j e ,c o / a /
/ /' / ~/
(3) SAFETY EVALUATION - PART A The item to which this evaluation is applicable represents:
Yes No V A change to the station or procedures as described in the FSAR; or a test or experiment not described in the FSAR7 If the answer to the above is "Yes", attach a detailed description of the item being evaluated and an identification of the affected section(s) of the FSAR.
(4) SAFETY EVALUATION - PART B Yes No / Will this item require a change to the station Technical Specifications?
If the answer to the above is "Yes," identify the specification (s) affected and/or attach the applicable pages(s) with the change (s) indicated.
(5) SAFETY EVALUATION - PART C As a result of the item to which this evaluation is applicable:
[ \
(" / Yes No e' Will the probability of an accident previously evaluated in the FSAR be increased?
Yes No / Will the consequences of an accident previously evaluated in the FSAR be increased? ,
Yes No / May the possibility of an accident which is different than any already evaluated in the FSAR be created?
Yes No v' Will the probability of a malfunction of equipment important to safety previously evaluated in the FSAR be increased?
Yes No / Will the consequences of a malfunction of equipment important to safety previously evaluated in the FSAR be increased?
No #
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Yes May the possibility of malfunction of equipment important to safety different than any already evaluated in the FSAR be created?
Yes No Will the margin of safety as defined in the bases to any Technical Specification be reduced?
If the answer to any of the preceding is "Yes", an unreviewed safety question is involved. Justifygeconclusionthatanunreviewedsafety question is or is not involved. httach additional pages as ne essary.
(6) PREPARED BY:
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DATE: %$ 9 /M (7) REVIEWED BY: DATE: 3 (8) Page 1 o /
yA e 5 q' -
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AP/0/A/1000/01 l Page 1 of 1 i:t l :
DUKE POWER COMPANY
!-I OCONEE NUCLEAR STATION
', s< .
' INITIAL DETERMINATION OF EMERGENCY ACTION LEVEL l
' I
1.0 Symptoms
The symptoms of an Emergency Action Level will vary according
- to the event. The severity of an event will determine the level of emergency.
l 2.0 Immediate Action 2.1 Automatic - NA 2.2 Manual -
2.2.1 Certain types of events require specific procedures.
Following is a list of those covered by AP/0/A/1000/08.
, 1) Vehicular Accident
- 2) Medical Emergency
- 3) Natural Disasters
- 4) Fire
- 5) Civil Disturbance
- 6) Radiological Spills
- 7) Bomb Threat
- 8) Other Emergency Situations If the event in question is one of the above then refer to AP/0/A/1000/08. However the event could still be an Emergency Action Level Event and so the Administrative Requirements should also be met using the EAL Abnormal Procedure. In that case both AP's can be utilized.
2.2.2 If the event is not one listed in 2.2.1, using Enclo-sure 4.1, identify The Emergency Action Level and Initi-ating Condition that best describes the event and proceed using the proper procedure.
3.0 Subsequent Action N/A 4.0 Enclosures t
4.1 Em,ergency Action Levels with. Initiating Conditions and Symptoms.
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Oconsa Nuclear Station 'Page 1 of g
, AP/0/A/1000/01 Enclosure 4.1 4
Unusual Event Initiating Condition Symptoms and Indications
- 1. Energency Cor,e Cooling initiated (co 1. Redundant actuation verification - Rn incident with positive finding that Module Control Room - ES Channels 1-8.
initiation is NOT spurious. ES actu-ates and discharges to vessels. .
- 2. Radiological effluent Technical Speci- 2. A. Any of the following gaseous efflu-fication limits exceeded: ent monitors in valid alars = ode
. for more than 1 hour:
A. Gaseous effluent instantaneous '
release rate Iechnical Specifi- RIA - 37, 38, 43, 44, 45, 46, 47, 48,,
cation limits exceeded for one 49
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(1) hour. ' ~
Interim Radwaste Building -
- 3. Liquid effluent concentration. RIA-52.
Tdchnical Specification limit *
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exceeded for 15 minutes. 3. Any of the following liquid efflu-ent =enitors in valid alarm mode -
for more than i hour: .
RIA - 33, 34, RIA-54 _-
- 3. Fuel damage indication: 3. A. Dose equivalent I-131 activity con-centration greater than Tim 4e in A. High coolant activity sample (e.g. Technical Specifications or exceeding coolant technical speci-fication for iodine spike) . (High 3. Laboratory analysis which indicates Reactor Coolant Sample Activity) an. increase in failed fuel of 0.1%
in 30 minutes~
- 3. Failed fuel =enitor (?WR) indicates increase greater than O.1 equiva-lent fuel failures withing 30 min-utes. (Failed fuel sa=pling).
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Oconee Nuclear Station Page 2 of J
'. AP/0/A/1000/01 , , . , _
Enclosure 4.1 l I ~
Unusual Event Initiating Condition Symptoms and Indications
- 4. Abnor=al coolant temp'erature and/or 4. Narrow range, wide range RCS pressure pressure or abnormal fuel temperatures indication; outside of techn4"1 specification Narrow range, wide range RCS tempera-limits (> 2500 psig) i ture indication; Incore thernoccuple temperature indi-cation; .
(, , . . _ , _ _ , ,
- ~ - ~ ~
Subcooled margin monitors
- 5. Exceeding either primar7/ secondary 5. A. LLei, PZR RB su=p, EAWT, LAWT level ,
leak rate hechnical specifications or RCS pressure and RB pressure.
pri=ary leak rate technical specifi- PT/1/2/3/A/600/10 - Reactor Coolant cations. (> 10 gym total P/S leakage) Leakage.
A. Pri=ary - requiring shutdown B. RIA 40; RIA 16, 17;.
B. Primary to secondary Unit 1 > 0.30 Chemistry Analysis ,
gym.
C. RIA 40; RIA 16, 17; Chemistry Analysis
- 6. Failure of a safety or relief valve in 6. A. RCS pressure a sr.fety related system to close fol- RV tailpipe temperatures loving reduction of applicable pres- QT temperature level and pressure sure. PZR level __
A. RCS System B. Main steam pressure, visual inspec-tion, RC temperature and pressure B. Main Steam l
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Cconco Nuclear Station 'Pago 3 of 21 AP/0/A/1000/01 l
_ Enclosure 4.1 Unusual Event Initiating Condition Symptoms and Indications
- 7. Loss of offsite power or loss of on- 7. A. Underfrequencies - undervoltage on 230 K7 buses.
site AC power capability. ,
1 A. Loss of offsite power . 3. Underfrequencies - undervoltage on MF3.
- B. Loss of on-site AC power
- 8. Loss of conta b ant integrity requir- 8. Any automatic containment isolation
-~ ~
ing shutdown by gechnical specifica- valve fouhd'to be' inoperable, or any -
tions. penetration fails 2.ts leak test as specified in the Technical Specifica-tions.
- 9. Loss of engineered safety feature or 9. A. Engineered Safety Features System fire protection system function re- found inoperable. _
quiring shutdown by technical speci-fications (e.g. , malfunction, per- 3. Fire Suppression Water System found sonnel error, or procedural inade- inoperable. (Note that technical quacy).
specifications now include Keowee Hydro).
A. Engineered Safety Feature
- 3. Fire Protection System ,
- 10. Fire lasting = ore than 10 minutes: 10. A. Observation A. Onsite 3. Observation
- 3. Offsite (surrounding the station)
Oconon Nuclear Station ^ page 4 of 21 AP/O/A/1000/01 Enclosure 4.1
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', Unusual Event l Initiating Condition Symptoms and Indications !
- 11. Indications of radiation monitoring 11. Loss of Radiation Monitoring Systemi process and effluent parameters which Loss of Meteorological Equipment; require plant shutdown or significant Significant Loss of Communication to loss of vital assessment- or communi- ; offsite . capability.
. cation equipment.
1
- 12. Security threat or-attempted entry 12. A. Security force declares initiation or attempted sabotage. of Security procedure A. Bomb / explosive or missiles B. Security force declares iniciation of Security procedure B. Subversive activity attempted
- 13. Natural pheno =enon being experienced 13. A. Seismic Recording System start indi-or projected beyond usual levels: cation and alars.
A. Any earthquaka (> .05 g design B.Observatiobofevent -
acceleration). -
C. Observation of event
- 3. 50-year flood or low water, hurri-cane surge, seiche (lake tidal D. Observation of event wave) .
C. Any tornado near site D. Any hurricane (> 74 =ph) - - - - 1. - - - .
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,' Oconce Nuclear Station ' Page 5 of 21 l AP/0/A/1000/01 Enclosure 4.1 l l 4 1 j Unusual Event l
- Initiating Condition Sy
- nptons and Indications i
- 14. Other hazards being experienced or 14. A. Observation of event projected:
B. Observation of explosion or warning-A. Aircraft crash on-site or unusual .
from ;off.gite aircraft activity over facility.
C. Observat' ion of explosion or warning B. Near or on-site explosion from offsite
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C. Near or on-site toxic or finm able .._D. Decrease in Condense hacut s; gas release of a nagnitude that Main Turbine Vibration; ,
threatens personnel. Turbine Generator Trip I D. Turbine rotating component failure causing rapid plant shutdown.
- 15. Other plant conditions: 15. A. Shift Supervisor's Discretion A. Conditions that warrant increased B. Shift Supervisor's Discretion; awaren'ess of part of state and/or R.O.'s discretion local offsite. authorities. ..
B. Conditions that require shutdown i under technical specifications.
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- 16. Transportation of conenmhated injured 16. Sane as initiating condition individual from site to offsite. -
- 17. Rapid depressuri:stion of PWR second- 17. MS pressure; ary site. RC ta=perature and pressure FDW flow i
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Oconsa Nuclear Station ' Page 6 of 21 1
AP/0/A/1000/01 Enclosure 4.1 l
j A
Amt e
I INITIATING CONDITION SDfPT01f5 AND INDICATION i
- 1. Severe loss of fuel cladding: 1. A. Very high collant activity sample (e.g., 300 uCi/cc equivalent of I-131)
. i
- 3. Decrease in reactor coolant flow.
l Control Room indication.
J l
l C. kose parts nonitor indicates particles in reactor coolant system. .
_ . . -_ -_ Rapid gross failure of one stean
- 2. 2. Reactor trip on low pressure;.- - - - - i generator tube with loss of off '
RIA 16 or 17 and 40 high alarm; , I site power from all sources loss of RC inventory via pressurirer. -i (OTSG Tube) level; , . .
Increasing SG level on affacted SG; .
undervoltage alarss on nain feeder
, s buses; transfer of anv414ary power to stand pr by buses; load shed of non-essential loads; TDENP start switchyard isolation; Keowee turbiife generatoTe=ergEhP.y 8
start __
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Oconte Nuclear Statian
' Page 7 of 21 AP/ 0/A/10'00/01 Enclosurc'4.1 f
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, AT2RT INITIATING CONDITICI STMPTCMS AND INDICATION
- 3. Rapid failure of more than 10 3. I.ow RC pressure alarm; steam generator tubes (e.g. , several low PZ1 level alars; hundred gpm pri=ary to sec.cudary RIA 16 or 17 and 40 high ala=s leak rate) . ; (Control Room indication);
increasing SG level on affected SG (Control 3oom indication);
decreasing reactor coolant inventory via pressurizer level & RC pressure (Control Rocs' indication);
eventual reactor tripcon low RC.
pressure; -
excessive RC =akeup flow.
- 4. Steam line break with significant 4 Rapid decrese in MS pressure, Elec.
E.'F , ireater than 10 gpm) primary
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loaCPTflevel, RC pressure and TCi7 to secondary leak rate or MSIV mal- reactor trip on low pressure or high
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function. ~
power; increase reactor building' pressure and temperature (inside break); )
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__ actuation of ES channels 1-6; actuation of ES channels 1 and 2.
- 5. Pri=ary coolant leak rate greater 5. RCS leakage rate shows leak rate; than 50 gpm. decreasing per level (prior to EP injection pu=p start);
increasing pressure in reactor build-ing, visual observation with T7 camera; l
IIST level decreasing = ore than normal; R3 sumps - HAWT & LAWT level.
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Oconsa Nuclear Station Page 8 of 21 AP/0/A/1000/01 Enclosure 4.1 l
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ALERT INITIATING CONDITION SYMPTCMS AND INDICATION l
- 6. High radiation levels or high air- 6. Increase of RIA readings in affected borne cone =4 ation which indicates areas (RIA's around vent header or a severe degradation in the control gas decay room); plant area iodine of radioactive natarials (e.g., or particulate airborne concentration increase by a factor of 1000 in greater than 1000 mpc.
direct radiation readingo).
- 7. Loss of off-site power and loss of 7. Load rejection reactor trip; all on-site Ac power for up to 15 switchyard isolation on 2/3 undervolt g ninutes (loss of Keowee not credible and underfrequency - Keowee emergency so not considered). start; transfer of anvdHmries to standby
_ . _ . . . . . . . _ . buses- in. - 2L-sac ; d - ad4= te. 1" d* " -
tion is loss of voltage on main feeder buses; .
reactor coolant pumps . trip;-
ES actuation on low RC pressure; -
- 8. Loss of on-site DC power. 8. Control Ro6m Indication:
statalam indication DC trouble and
.._;__ . _ . _ . ._ $_ _ batter 7 hreakers ogen;_____
low voltage on DC buses DA, DB; DC trouble on EPSL.
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- 9. Coolant pump seizure leading to fuel 9. Reactor coolant pump auto trip alar =;
failure. reactor trip on flux / flow /i= balance; chemistry analysis per sample request
! indicate fuel clad breakdown; prior to pump seizure, high vibration alarm.
. Ocones Nuclear Station 'Page 9 of 21 AP/0/A/1000/01 Enclosure 4.1 Of N -
it m
. INITIATING CCNDITION STMPTOMS AND INDICATION l 10.- Co=plete loss of all' functions for 10. ECCS systems are not operational, loss, plant cold shutdown. of HPI, LPI, RBS , RBCU, redundant indication in Control Room; i
- natural-circulation can not be obtained.
. 11. Failure of the reactor protection 11. Reactor remains critical aiter. trip ..,
system to initiate and complete a Rods remain out.
scram which brings the rea: or '
suberidcal.
- 12. Fuel da= age accident with release of 12. A. RIA's 2, 3, 4 alars Building l
radi'cactivity to contai= ment or fuel isolation (Control Room indica-- (
handling building. tion and local) ,
A. Contai =ent 3. RIA clarm 6 (Control Room indica ~
ation and local)
- 3. Fuel handling building (SFP)
C. .2 A T m --1 4 15, 7, 10 (c'e -aT C. Auxiliary Building Room indication).
- 13. Fire potentially affecting safety 13. Visual observation - fire alars in systems. safety related areas.
- 14. Most or all alar =s (annunciators) 14. Visual observation by operator; lost. loss of computer;-
RC pressure and ta=perature still available on chart recorders in control Room, incore ther=occuples can be read manually.
Oconso Nuclear Station ~ Page loo f 21 AP/0/A/1000/01 Enclosure 4.1
! ALERT 0[
INITIATING CONDITION STMPTOMS AND INDICATION
- 15. Radiological effluents greater than 15. High radiatida alar =s on RIA's 18,15, 10 times Technical Specifications 13, 45, 44, 43 for longer than 15 instantaneous 11 sits (an instantane- ninutes.
cus rate which, if continued over 2 ;
- hours, would result in about i na at the Site Boundary under average '
meterological conditions or whenever
_. effluent. monitors or radiological . - . . . - . . _ _ . . . . . _ .
=onitoring detect these levels).
- 16. Ongoing Security compromise. 16. Determined by Security Force - event
. resulting in adversaries commandeering, an area-of -tha-plant. but not-control of shutdown capability.
- 17. Severe natural pheno =ona being 17. Visual observation experienced or projected A. Earthquake greater than Opera-ltional Basis Earthquake Levels .
(>.05g)
E. Floody. low water, hurricane surge, seiche near design levels (lake tidal wave) _
l C. Any tornado striking facility D. Hubcane winds near design -
basis level ( > 95 =ph) . .
Oconsa Nuclear Station ' Page 11of 21.
AP/0/A/1000/01 Enclosure 4.1 l
I i
ALERT INITIATING CONDITION STMPTOMS AND INDICATION I
- 18. Other hazards being e.7 erienced 18. Visual observation.
or projected:
A. Aircraf t crash on facility i '
B. Missile i= pacts from whatever source on facility C. Known explosion damage to j facility affecting plant opera- '
tion D. Entry into facility environs of toxic or fla==able gases E. Turbine failure causing casing penetration.
- 19. Other plant conditions exist that 19. As determine'd by the Shift Supervisor in the jud5 =ent of the Shift Super-visor, the Operations Duty Engineer, the Superintendent of Operations, or-the Plant Manager warrant pre-cautionary activation of Technical Support Center and near-site Crisis Manage =ent Center.
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- Cconsa Nuclear Station Page 12cf 21 AP/0/A/1000/01 ,
. 1 Enclosure 4.1
)
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- Sita Area Emergency i Initiating Conditions Symptons and Indications f
- 1. Known loss of coolant accident greater 1. Reactor trip on low pressure, than makeup pu=p capacity (any leak- L?I ES actuation; agey 500 gpm) . HPI ES actuation; .
l
. Reactor building at=osphere indications 8
. of high pressure, humidity, etc.;
Continued loss of RC inventory-no pressurizer level; Eigh reactor building su=p indication; High reactor coolant pu=p vibration -
indicating voids in RCS; High reactor building nressure
{
- 2. Degraded core with possible loss of 2. Subcooling monitor and high incore coolable geometry (indicators should thermocouple readins; Tg&TC di- .
inclu'de instn: mentation to detect verging; inadequate core cooling, coolant SAT monitor indicates no subcooling; n activity and/or radioactivity levels). Chemistry results on sample request J indicate failed fuel; Reactor cu.ua:.ng .uf s n:.gn a.:. arm,
~ ~ ~ ' - - '
RIA's 2, 3, 4, 5; , .
Low reactor coolant flow
- 3. Rapid failure of more than 10 steam 3. Reactor trip on low pressure; generator tubes with loss of off-site Pressurizer low level alars; ,
power (e.g. , seversi hundred gpm pri- Undervoltage alarus on main feeder
=ary to secondary leak rate). buses; Transfer of auxiliaries to standby buses; Continued loss of RC inventory beyond HPI capacity, pressurizer level de-creasing l ._ ..
Ocones Nuclear Station Page i1of 21
\
AP/0/A/1000/01 l Enclosure 4.1 )
i .
s Site Area E=ergency Initiating Conditions Sy=ptoms and Indications
- 4. PWR steam line break with greater than 4. A. 1) Decreasing reactor coolant pres-sure, PZR level, Tave A. 50 gpm pri=ary to secondary leakage
, 2) RIA 16 or 17 and 40 high alar =s B. 50 spm primary to secondary leakage !
and indication of fuel da= age. , 3) Stabilized PZR level on HPI l initiation.
I 3.1) all of above plus chemistry re-sults positive on failed fuel analysis
- 2) Possible high Reactor Building
. . _ _ _ - _ _ _ _ _ . . _ . _ . . _pressura_.and_ta=ner e" " _. . . _ _ _ .
- 5. Loss of off-site power and loss of on- 5. Continued undervoltage on main feeder site AC power for = ore than 25 minutes. buses; realig _ent of CCW-8 for gra- _
vity flow to Keovee tailrace; load shed of all non-essential loads in preparation for emergency start of Keowee Hydro Station and transfer to standby buses.
- 6. Loss of all vital on-site DC power for 6. Continued DC trouble alar =s ir. Control more than 25 minutes. Room; DC trouble alar =s on E=ergency Power Switching Logic; Loss of So=e Computer Indications
- 7. Co= place loss of any functions needed 7. Inability to establish e=argency feed-for plant hot shutdown. water or auxiliary service water flow.
Oconsa Nuclear Station ' Page 14of if AP/0/A/1000/01 Enclosure 4.1 Site Area Emergency Initiating Conditions Symptoms and Indications
- 8. Transient requiring operation of shut- 8. RPS, ES Channels trip with failure of down systems with failure to scram of RI trip function. (Eighly improba- 1 (continued power generation but no core ble) damnge i= mediately evident). - , l
)
- 9. Major damage to spent fuel 9. A. 1) RIA's 2, 3 high alarm A. In contai- mat (e.g., water loss 2) Gaseous indication of radiation below fuel level) from RB CMS..
B. In Fuel Handling Building (SFP) (e . B. 1) RIA 6 high alarm in Spent Fuel g., large object da= ages fuel) Pool
- 2) RIA 41 -(SFP gas) e me_
e
- 10. Fire compromising the functions of the 10. Visual observation; fire detector in-safety systems. dications as listed in Technical Specifications.
- 11. All alarms (annunciators) lost for more 11. Visual observation of event.
than-15-minutas-and plant is not in cold shutdown or plant transient initi- e ated while all alarms lost. _
h e- s ame- e e up e* g eee p-e e we == we- e as emumme e e mo e a om eese 6h
. Oconee Nuclear Station ' Page 15 of 21 AP/0/A/1000/01 Enclosure 4.1 l
! Site Area E=ergency Initiatine Conditions Symptoms and Indications
- 12. Accidental Release of Gases. 12. A. Effluent monitors detect levels corresponding to greater than 50 =R/hr for 1/2 hour or greater than 500 mR/hrl.3.
for two minutes (or five times these levels to the thyroid) ,
l at the site boundary for
.. _. _ . . adverse meteorology. _..._.. _ _
B. These dose rates are projected based on other plant parameters I (e.g., radiation level in containment with leak rate appropriate for existing containment pressure) or are
- measured in the environs.
C. EPA Protective Action Guide- ~
. lines are projected to be
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exceeded outside the site boundary.
e WG l
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Oconce Nuclear Station Page 16of 21 AP/0/A/1000/01 Enclosure 4.1 Site Area E=ergency Initiating Conditions Symptoms and Indications
- 13. Tmminent loss of physical control 13. Subversive activity; of the plant. determined by Security Supervisor; Teminent loss of Control Room and Auxiliary Shutdown Panels.
- 14. Severe natural phenomena being 14. A. Seismic Trigger Statalarm experienced or projected with plant not in cold shutdown. B. Visual Observation
. A. Earthquake greater than SSE C. Visual Observation or Meteoro-levels. -
logical indications in Control Room.
B. , Flood, low water, hurricane surge, seiche greater than design levels or failure of protection of vital equipment _
.at lower levels.
. Oconen Nuclear Station ~ Page 17 of 21 AP/0/ A/1000/01 Enclosure 4.1 l
l Site Area Emergency Initiating Conditions Symptoms and Indications
- 15. Other hazards being, experienced or 15. A. Visual Observation projected with plant not in cold shutdown. B. Visual Observation A. Aircraft crash affecting vital C. Visual Observation Chemistry structures by i= pact or fire. Results of samples in areas.
B. Severe da= age to safe shutdown 4 equipment from missiles or explosion.
C. Entry of uncontrolled fla=mable gases into vital area. Entry of uncontrolled toxic gases into vital areas where lack of a'ecess to the area constitutes a
. safety problem.
- 16. Other plant conditions exist that in 16. As directed by E=ergency Coordinator the judge =ent of the Shift Super-visor, the Operatiras Duty Engineer, the Superintendent of Operations or the Plant Managec varrant activation of emergency centers and monitoring teams and a precautionary public no tification.
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, Ocones Nuclear Station Page 18of 21 AP/0/A/1000/01 Enclosure 4.1 l
1 Site Area Emergency Initiating Conditions Symptoms and Indications
- 17. Evacuation of control room and 17. As directed by E=argency Coordinator control of shutdown systems not and Shift Supervisor.
established from local stations in 15 minutes.
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Oconca Nuclear Station 'Page 19of 21 AP/0/A/1000/01
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Enclosure 4.1 1
l General Emergency.
Initiating Condition Symptoms and Indications
- 1. Accidental Release l. A. Effluent monitors detect level
~
corresponding to I rem /hr W. B.
or 5 rem /hr thyroid at the site boundary under actual meteorolo-gical conditions.
B. TI$ese dose rates are projected based on other plant parameters (e.g., Radiation levels in the contai - nt pressure with some
' confirmation from effluent moni-cars or are measured in the en -
virons.
NOTE: Consider evacuation only within about 2 miles of the site boundary unless these site boundary levels are exceeded by a factor ~
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 .
Protective Action Guide- I line exposure levels are I I
predicted to be exceeded at longer distances.
- 2. Loss of 2 or 3 fission product bar- 2. A. Loss of prdw coolant boundary j riers with a potential loss of third ,
barrier B. Clad failure l
l C. Eigh potential for loss of contain-l ment integrity after an accident.
M)
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. Oconsa Nuclear Station ' Pago 20 of 21 AP/0/A/1000/01
, Enclosure 4.1 l General Emergency -
Initiating Condition Symptoms and Indications
- 3. Loss of physical control of the faci- 3. As determined by Security Force lity (Note: Consider the 2 mile pre-cautionary evacuation). l s
- 4. Other plant conditions exist, from 4. A. Small and large LOCA's with failure whatever source, that make release of ECCS to perform leading to se-of large a=ounts of radioactivity in vere core degradation or =elt in a short period of time possible. from minutes to hours. Ultimate Core celt situation. ,
failure of contain=ent likely for melt sequences. (Several hours likely to be available to com-plate protective actions unless con-tainment is not isolated.) .
i B. Transient initiated by loss of l
- - feedwater and condensate systems i
... (principal heat removal system) followed by failure of emergency. -:
- _- feedwater system for extended .
period.
Core melting possible in several ,
hours. Ultimate failure of con- !
emi - nt if core melts.
C. T-nn ai an b wa=4-4 3 marnH m of shutdown systems with failure to scram which results in. core damage or additional failure of core cooling and makeup systems (which could lead to core =elt.)
- D. Failure of off-site and on-site power along with total loss of !
emergency feedwater makeup capa-bility for several hours. Would ;
lead to eventual core =elt and j '
likely failure of contain=ent.
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, , , , Oconte Nuclear Station 'Page 21of 21 AP/0/A/1000/01 Enclosure 4.1 General Emergency Initiating Condition Svmotems and Indications
- 4. (Continued)
E. Small LOCA and initially success-ful ECCS. Subsequent failure of containament heat removal systems over-several--hours-could 4ead to---
core melt and likely failure of containment.
NOTE: Most likely conta1==ent failure node is melt-through with re-lease of gases only for dry coneminmant. Quicker release expected for failure of con-cainmant isolation system for any PWR.
- 5. Any major internal or external events 5. A. Visual observation fire alar =s con-
. . that could cause massive common damage trol room.
to plant systems.
B. Seismic Trigger A. Fires
. B. Earthquakes (substantially beyond design basis.)
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INFORMATE ONLY O Form SPD-1002-1 DUKE POWER COMPANY (1) ID No4P/0/A/1000/02 PROCEDURE PREPARATION Change (s) N/A to PROCESS RECORD N/A Incorporated (2) STATION: Oconee Nuclear Station (3) PROCEDURE TITLE: Emergency Action Level (EAL) - UNUSUAT. EVENT -
(4) PREPARED BY: DATE: 8 [ /M (5) REVIEWED BY w DATE: J g j7 Cross-Disciplinary Review By: N/R: M (6) TEMPOPARY APPROVAL (IF NECESSARY):
By: (SRO) Date:
) By: m Date:
(7) APPROVED BY: 4 , Date: 3 9 21 (8) MISCELLANEOUS:
Reviewed /Apprefed By: 'G rM_ Date:
//
- /A Reviewed / Approved By:
Of Date:
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FORM SPD-1001-2 DUKE POWER COMPANY NUCLEAR SAFETY EVALUATION CHECK LIST (1) STATION: // L rt/ p ,
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UNIT: 1 2 3
.\ pTHEjir: ,4 4 /_ .
(2) CHECK LIST APPLICABLE TO: M//d /// //doo /o 1; '
~/ /' / /
(3) SAFETY EVALUATION - PART A The item to which this evaluation is applicable represents:
Yes No V A change to the station or procedures as described in the FSAR, or a test or experiment not described in the FSAR?
If the answer to the above is "Yes", attach a detailed description of the item being evaluated and an identification of the affected section(s) of the FSAR.
(4) SAFETY EVALUATION - PART B Yes No _I/Will this item require a change to the station Technical Specifications?
If the answer- to the above is "Yes," identify the specification (s) affected and/or attach the applicable pages(s) with the change (s) indicated.
(5) SAFETY EVALUATION - PART C As a result of the item to which this' evaluation is applicable:
Yes No Will the probability of an accident previously evaluated in the FSAR be increased?
Yes No / Will the consequences of an accident previously evaluated in the FSAR be increased?
Yes No / May the possibility of an accident which is different than any already evaluated in the FSAR be created?
Yes No 7 Will the probability of a malfunction of equipment important to safety previously evaluated in the FSAR be increased?
Yes No Will the consequences of a malfunction of equipment important 'to safety prev:.ously evaluated in the FSAR y be increased? ~
Yes No May the possibility of malfunction of equipment important to safety different than any already evaluated in the FSAR be created?
. Yes No /Will the margin of safety as defined in the bases to any Technical Specification be reduced?
l If the answer to any of the preceding is "Yes", an unreviewed safety question is involved. Justify t e conclusion that an unreviewed safety question is or is not involved ttach additional pages as necessary.
(6) PREPARED BY: _[> DATE: %7 #-- /
(7) REVIEWED BY: DATE: 7 l qdw cth6fv (8) Pag 1 of /
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' AP/0/A/1000/02 Page 1 of 3 DUKE POWER COMPANY O
s_,) OCONEE NUCLEAR STATION EMERGENCY ACTION LEVEL (EAL) - UNUSUAL EVENT
1.0 Symptoms
The symptoms of an Unusual Event will vary according to the initiating conditions. Enclosure 4.1 defines the different conditions and gives specific symptoms of each of the same.
2.0 Immediate Action 2.1 Automatic - NA ,
2.2 Manual Date/Name .
Time 2.2.1 If at any time during this event the Emergency Plan is deactivated, proceed.directly_to Step 3.1.
2.2.2 Initiate immediate remedial action necessary to protect the health and safety of personnel, minimize the radiation and contamination hazards and minimize damage to the station. Record actions and results on Enclosure 4.4, Plant Data and Status Information.
, (-~s)
\_ / 2.2.3 If radiation or contamination is involved, direct Health Physics to evaluate hazards and recommend methods of con-trolling radiological problems. Record data and recom-mendations on Enclosure 4.4, Plant Data and Status Information.
2.2.4 If a possibility of an offsite dose exists as a result of this event, evaluate the need for an offsite dose calcu-lation.
NOTE: AP/0/B/1000/07 is for the Control Room use only for dose calculation. The Health Physics Section will use H.P. procedures if they perform the cal-culation.
2.2.5 Determine from Encicsure 4.1, Unusual Event Initiating Conditions, the most descriptive initiating condition for the event.
2.2.6 Appoint an individual to be responsible for keeping records of the emergency and to notify offsite agencies and company personnel.
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. AP/0/A/1000/02 Page 2 of 3 2.2.6.1 Notify company personnel and offsite authorities of the nature of the plant' conditions using
\v Enclosure 4.1, Unusual Event Initiating Conditions, as a guide for notification. Refer to the Emer-gency Telephone Listing in the Implementing Procedures manual for the telephone number that corresponds to the notification code under each initiating condition.
2.2.6.2 Enclosure 4.3, Message Format, is to be used in notifying staff and offsite authorities for both initial and followup contacts. Off-site notifications should be accomplished within 15 minutes of the identification of the EAL. Establish update time frame with offsite agencies.
2.2.6.3 Record actions taken and events as they occur on Enclosure 4.4, Plant Data and Status Information. - --
2.2.7 Proceed using proper proceddres to bring the pla.nt to a stable, safe condition.
'~
3.0 Subsequent Action (O
V y 3.1 When plant conditions warrant, The Unusual Event Emergency should be accelerated to a more severe classification or closed out. Both of these actions require a verbal summary to offsite authorities. Use only one of the following steps depending upon whether the event is escalating or being terminated. .
3.1.1 If the event is escalating, use Enclosure 4.2, Guide for Es-calation, to identify the appropriate EAL. When a new EAL
, is identified, advance to the new EAL abnormal procedure.
From the time a new EAL is identified, all offsite author-ities should be notified within 15 minutes.
3.1.2 When closing out an Unsual Event Emergency, notify all per-sonnel and authorities previously notified in Step 2.2.6 that the event is terminated.
3.1.3 A copy of Enclosure 4.3, Message Format, must follow the verbal contact to offsite authorities within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.2 In the event that Protective Action Guides need to be issued to offsite authorities, this event must first be escalated to a General Emergency.
l 4.0 Enclosures N- 4.1 Unusual Event Initiating Conditions with Associated Symptoms, FSAR, Tech. Spec. and EP References l
l AP/0/A/1000/02 )
Page 3 of 3 4.2 Guide for Escalating an Unusual Event 4.3 Mes:: age Format l 4.4 Plant Data and Status Information l
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OCONEE NtlCl. EAR STATION Page I ol 9 i i
AP/0/A/1000/02 I ENClisSURE 4.1 i UNUSilAl. EVENT
. . _ _ _ .. ._ - . . . . _ _ . _ _ _ . .a. . _., . . _ _ _ ..
Linur.na l Evesat s O(once Nuclear Station Final Emergency Procedurc/shnum.ni in s t s.s t ing Con.li t ions , Symp t om:. S.sfety An.nlysis Report Section_ 14.1 s
- 1. Fmergen.y Cuse Cooling initiat- He.lun.lant actuatios verifications -kZ Inaalve s t ent oper.stion of ECCS during EP/0/A/1800/04, T.S.I.:8 j c.I (ru i nr i .lcsat witta positive flu.lule Cont aal No . - ES Cliannels 1-8 Power Operation, I.ui.s of Reactor T . S . :1.5. 'l Coolant from sm.sll snpture.1 pipe.
tenling tlaat insti.ition is NOT
- i. pus s ons ) . LS astes.stes an.1elis-a lea a ge a. t u vesse1.
N..t s t i r.s t s on Co.le : 1-2-4-6-/
)
- Na.lsulog s t al es t inent Tet tin i r.i t A. Gaseous eflinent instantaneous retrase W.sste cas Dec.sy T.suk kupture; EP/0/A/1800/24, T.S.I.lu, 4 Spetslesatson limits escce.leil: e ate Tettinical Specilicat ion. limits 1.isguid Waste Storage Tank kupture T.S.3.9 excee!cd for one (1) hour, i Any of the l'ollowing gascons efiluvut
?
monituss ist valid alasm minie f or more than i hour: HlA - 31, 38, 44, 44, 45, 46, 41, 48, 49. Interim R.ntwaste linil. ling - Hl A 52.
Nut e i ii .et s on Co.le: 1-2-5-6-7 i h. 1.i'anid ef fluent tourentration. Terh-sairal Speci f ic.at ion limits excecile.1 for 15 minutes.
Any of the followsug liqui.I cifluent su.as i t o s s i n v.a l i d a l a s ies essente lor sisus e s taan I hour: HIA 'll, 34; HlA 54 1-2-5-6-1-l'1 1'
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OCONEE NilCI.EAN" STATION Page 2 of 9 ,
AP/0/A/1000/02 .
ENCll)SilRE 4.I IJNtlSUAL EVENT linusu.sl Event s Oconee Nuclear Station l'issal Emergency l'roca*.lise t line esi.ii sit luitsating Cunlitions Symptoms Safety Analysis ReporL Section 14.1
] _ . . _ _ . _ . . -- _ _ _ . _ _ . ._ _. . . . _ . _
f I. Furl it..m..gc enlat.ition: A. I)ose equivalent 1-131 activity I.uss of Coolant Arcident EP/0/A/1800/04 T.S.l.i.4 i
u,urent rat ion great er tisan limit EP/0/II/1800/24 T.S . 3. l's A. Ilsgh s uolant activity sample in Teclinical Specific.stions. EP/0/A/In00/27 g (e.g., rx.cr. ling ruolant
] tes tinical sperit irat ion tur ,
- i u.l e ur spike). (lligli kcart us-
! Coulant S.mpic Activity)
! Notslaratson Cole: 1 4 /
- 7 4
- 4. Al.uusesi Coulant temperature N.srrow range, wiele riesige HCS linessure Accialental Depressurization of Hear- EP/0/A/1800/04, T.S.'t.l.2 a n.1/ u a perssuae us alsnus ma l indicalion; narrow range, wiele range for Coulant System; l.uss of Forreal EP/0/A/ IB00/Ots, 4 lurl tempesainics outsiele ul HCS temperature infication; inrose Heactor Coolant Flow; i.oss of Coul-
- icelusia al specifiration limits thermuruuple temperature inlication; ant Accialent.
j ('s2%DO g.s s g) buleruuteil margin munit ors. ,
2 Notsiisatson Co.le: 1-2-4-6-1 2
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OCONEE NtlCl.LAN STATION Page i ul 9 AP/0/A/1000/02 ENCI.0SilHE 4.1 UNilSilAl. EVENT tessusual Event s Oconee Nucle.ar Station Final . Emesgency Proccituar/16cument lus t iat iseg Cunilit ions Symptoms S.stely Analysis Report Section 14.1
'. Exa rceling e s t her prim.ss y/secusul- A. l.8)ST, PZH, kli sumps llAVr, l.AVr Accielental -1)cpressurization of Heactor El'/0/A/1800/04 T.S.'s. th ary Ic.sk sate tesimical specili- level. RCS pressure assil Hit Coulasit System (kCS) EP/0/A/1800/l?
- s.stions or prim.ssy leak rate pressure. PT/l/2/3/A/600/10 -
t ro linsc.el sperilis at ions. (>10 Heactor Coulant Leakage, spm t u t .s i P/S leakage)
A. Ps-imas y -scipsa r ing shut.luwn 15 . HlA 40; HlA 16, 17; Chemistsy
, Analysis HIA 54 15 . Ps ima:y io ses on.14s y tinit i 20.50 gpm C. kl A 40; Hl A 16,17; Cliemist s y .
Analysis HIA 54 N. t e i is at ion Co.le: 1-2-4-6-/
- b. F.a s i n s e u l . s.stety or selict A. RCS psessure, NV t.siipipe temper.s- 1.oss al Coulant Accilent EP/0/A/lH00/04 T.S.2.2 valve i n .: s.s f et y e clat e el syst rais Lasse s, iff t emperatsste level asul E!*/0/A/ Itt00/06
. to s l u:,c fiellowing reatuct ion of psessure, PZH level. EP/0/A/lR00/08 applirabic psessusc. -
11 . H. sin steam pressure, visiaal in-A. NCS Syst em spestion HC temperature anil pressure it . fl. sin Stram N.e t i l i s .si s uas Co.le: 1-2-4-6-/
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l OCONEE Ntk:1. EAR STATION P.sge 4 of 9 4
AP/0/A/1000/02 3 ENCL.nSURE 4.1 UNilSilAl. EVENT 1 unusu.at Events Oconce Nuclear St.stion Final Emergency 1*rocediasc/lbs ument lustiating Conditions Symptoms Safety Analysis Report Section 14.1
) __ .
/. loss of of f sit e gu>wer or loss al A. Iln.lcrire.guencies - un lervoltage ess 1.oss of Offsite Power to Station EP/0/A/1800/ Its T.S. l. 7 I
onsite AC P..wes cagohtisty. 2'50 KV biases. Auxiliaries EP/0/A/1800/25 A. l.oss of ulisite power 15 . ' lin.lcri s e.guestcies - assulervult age aus ,
NFil .
f it . l.u:.s ut on-site AC power Noteieaatson Co.le: 1-2-6-7
- l 1
- n. loss ud sonsaanment icitegrity Any autom.atic contasument isolation El'/0/A/1800/2'l T.S.'s.6 s e.gui ring sleut luwn ley t ectinical valve found to be inoperable, or any T.S.I.7 ,
sperilis at ions. pructr. Lions tails its le.sk test as
. T.S.4.4.1 specilic.i in the Technic.al Specifica-Lions a N..t s i s a .a t s uas I:u lc l-2-4-6-7 l
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- OCONEE NUCI.EAI4 STATION Page 5 of 9 .
Al*/0/A/1000/02 !
ENCI.OSURE 4.I IINtiSUAL EVENT lluusu.el Evruts Oconce Nuclear Station Final Emergesa y Procceluse/lkeru un luiti.stang Cou.litions Symptoms S.sfety Analysis Report Sectiosa 14.1
- 9. 1.uss of enginecueil safety lea- A. Engineareal Safety Features Systeini la>ss at extersial etertrical 10a.1. I'P/0/A/1800/16 T.S.3.5.3 tuse or isse protection system found inoperalsle. l.oss of of f site power to stationi EP/0/A/1800/25 T.S.1.Il f unc t ion s ospairing sleutdown 1.y auxiliaries.
t ra l.uiral spcr il irat ions (e.g. , 11 . Fire Supleression W.ater System !
maltuustion, personucI error, found inoperatale. (Note tiiat
.. p a us e.lu s a l i n.e.lcapsacy ) . te(linical specifications now incluele Keowce Ilydro).
A. Enganecer.1 S.alcty Fe.eLuse ,
I Notilaratiusa Code: 1-2-4-6-/
15 . Fase Psulaation System Notileralion Code: 1-2-6-7 i
- 10. F a s s- 1.ast ing mus e t isan 10 A. Olisc i v.a t ion El'/0/A/lR00/12 minut es :
- 15. Olsse rva t ion I A. Ousite Not s l a s at suas Co.le 1 (> - 7 .
, 16 . Olisate (s.us s uunding tise s t Ji iust)
Not s t e s .st iuse Co le: 1 ( 10 s
N .
OCONEE NUCl.EAN STATION Page 6 ol 9 AP/0/A/1000/02 .
ENCIDSilkE 4.1 .
UNUSUA!. EVENT
- - - . ~ - . . -
11uen.u.a t Event s Oconee Nuclear Stations Final Emergency Proccilies e/ou.'umcut initiatisig Con.letions Symptoms Safety Analysis Report Section 14.1
- 11. in.lia.it ions ut s ailiat ion mont - less of H.siliation Honitoring System; i.oss of Offsite Power to Station EP/0/A/lH00/16 turing peoerss anil cillnent Loss of Hetcosulogical Equipment; Auxiliaries; less of lustrument Air EP/0/A/1800/25 '
l p.orametens wlii le acquire plant Significant loss of Communication to EP/0/A/1800/29 l r.hutilown os sigu s t ar.sul loss ut offsite capaleility. OP/0/A/ Ilo:l/20 v it al assessa. ut on aommunica-t ion c pe o pment .
N..tiairatinn Co.le: 1-2-6-7 (5)
- 12. Sri n r i t y a lie r.s t or attempic.I A.- Scrurity force electares initiation Station Security Plan eutey un altropicil sabotage, of proper security proccitusu.
l A. Blumi./ explosive or missiles it . Security force declar'es initiations of proper seturity proccelure.
al . Suleven sive as L ivity at t empicil N..t i l ie .it i un Co.le: 1 4.- /
. . . , , . - ~ ~ . . . . . . . - - - . . ~ - - . . . - - - . . - . _ . _..._. . . _ _ . . , . _ _
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s OCONEE NUCl. EAR STATION P.a ge 1 un 9 AP/0/A/1000/02 ENCI.OSURE 4.I UNilSUAI. EVENT lluusu.s i Events Oconce Nuclear St.stion Final Emergency Procciture/ pot u.e nt initiateng Conilations Symptoms S.afety Analysis Report Section 14.1 l 't . N.st us al phraumruuss being ex- A. Seismic Hrcositing System start Tornaito, Missile impact EP/0/A/1800/09 per irurent us projerted laeyonia indication and alasm. El*/0/A/2800/10 usual levels: EP/0/A/1800/15 Is . Observation of event EP/0/Afl800/19 A. Any c.a s t is.paake (<.05 g de- AP/0/A/000/
sign art eles.st ion) C. Observation of event ONS Fire Plan ll . 50 ye.as l luual or l ow w.s t e r , p. Obsesv.stion of event liussitane surge, seithe (lake t id.sl w.sve)
C. Any l os sa.s.lu ur.or site.
11 . Any laureir.aue (>14 mph)
Nutsitratsose Code: 1-2-6-7 .
- 14. Ottics li.aeas ds lica ng experient ral A Obsesv.ation of event Tushine Trip, Tu Isine Trip with EP/0/A/1800/02 ur ps u jre tril' -
F.silure of Generatur liteaker to EP/0/A/1800/07 Open
!! . Observation of explosion or A. Ae s tralt reash on-site or warning from olisite.
suiin.ua l a i s s ra l t artsvaty oves lasility. C. Observation of explosion or ,
Not a f s t at ion Co.le: 1-2-6-7 . w.asning inom offsite. .
1s . Nr.a r os un-sit e explosion. it. Drrrease in Condenser Vatuum; Notslit.ation Code: 1-2-6-7 Hain Tushine Vibratioss; Tushine Ccueratos Trip.
C. Neas us on site toxir or flausu.ble gas scleasr of a magn i t iale t b.s t t b s e.s t rus ,
pcesunuri.
Notafisation Code; l-2-6-1
. _ _ _._ . . _ _ . . . . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ . _ _ . _ _ _ _ _ . . . _ _ . _ _ _ . _ . . . . _ _ . ~ . . _ _ .
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OCONEE NilCLEAR STATION Page it ui 9 AP/0/A/1000/02 ENCI.OSURE 4.1
'* UNUSUAL EVENT a
4" j.
Unusu.sl Evruts Oconee Nuclear Stat ion Final Emergency Procal lure /lbs ument
-( Safety Analysis Hcport Section 14.I v luiesating Cou.litions Symptom.
~
- 14. . J t:unt i nue.1)
- 16. Tualeine notatsug compoucut I-lastume t.eussug rapiti pl.sht '
t slaut slown.
Nut s lia t iuan Co.l ?: 1-2-44,-7 + -
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A. Staitt Supervisur's lliscretion As als rected lay pl. int a un.li-i I
tions. ,
A. Cou.fi t sous tie.it w.s t rau t. i na- ' 15.' Slaith Supervisur's 1)iscrefion.T e es ca:.c.I aw.sa cuess of part of H.O.'s iliscretiore.
a t.al e anet/or tur.nl olisite autisur e t ics.
15 . run.ls t ions ti .st s esgui s c mi ut -
i
.luvia un.lcr s ca linia a l speci-
! Iseatsons.
N.et s i ir.s t ion Co le: 1-2-4-6-1 0
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OC6Nt.E NHCLEAR !TATIOld Page 9 a8 9
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s a '- AP/0/A/lupo/02 A y
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LNCIDSukE 4.1 ' ' '-
s \ llNUSUAL EVENT (t , .~
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unusual Evre.nu Oconee Nuclear Statiosa Final ,
E.sergrocy Proca$lutr'/IEn umes.t g ,
la s t i.at s us Con.le t ions Symptoms S.afety Analysis Report Sect iosa 14.1 - - ,
j %. ,
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i lin, ' ingunpos t .et enn el re utami.ia teil S.sme n f astt ialiseg cosulitions.
l g s u jo e r.1 s ee.ls w a.lu.s l d rum s e t e t o s j s A
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N.,8iIinatium Code: W6-1 *
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l 81. k.epeel Jrpe rmsur izat aon' of 1*WN . itS pressuse;-kC temper.sture and Accialcutal elcpsessesrizat iop_ uf it.sen EP/0/A/lR00/08 ,f ;
l Sci un.l.a s y s i t e , ,
pressuse;~ flW flow. Steam System, l. ass tot' F3 tern.a t I.uad EP/0/A/IB00/16 j w j . .
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or Tuileine Trap El*/0/Afib00/02
{
N.,8 s 8 e r.st s uu Co.le: 1-2-4-6-7 '
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OCOfdLE NUL' LEAR STAfl01s I*a ge I ul is ,
Ap/0/A/1000/02 i thCIDSl*E 4.2 GtilDE tt>1t ESCAll.flON iluusssal 1.vs:ut s Alest Site Area Emergrury Cesicial Emes gru. y I. toca gesu y Cuse l'uoling isei- 5. primary ruolant leak rate gerater .l. Know loss et coolaut arc s.lcut 4. Othes plant run.litsuun teatril D u asui. Brut ustia pusi- than 50 gimi. greater Eliais makeup pump a apa- exist, drum wh.atevre j t eve lin.fing slaat a ssit iet s une city (any leakage > $00 gled. ms.uare, t iaa t w.s ke s c le.s a.e 8
- i a IsoT spur suses. LS actu.ites of lasse amounta ut an.1 densh.assen to vessel. radioat s swat y in . si.us ig je4*f a u.I o $ % iasse* ge.ebh e la i e' I Case acit situatsun. ,
l 1, H+1sulogiaal clllurut Teste- 1, . lin gle t.Jiat ion levels or 1.igla air- 12. Arri.lental Release el Cases 1. Arsci.trut al Welease l uisal Sprastia.stsons limits Isos sac cosatamissalines winis ts isadicat es ,
c ae rs .lc.1: a arvese dest.sdatiou its the outson A. Efilucut monitors detect A. Elf 6uurt muustush j o f s a.l a uaa- t i ve m.a t e r i a l s (e. g . , levels correspon ling to .let ra t Irvel aus-A. diescous elllurut ises t ant - .iurrease I.y a lactor of 1000 in gre. ster thans 50 suk/hr lur responding to I s ra./
auruus release sate Teth- .tierta sa.lsation readings). 1/2 hour or gerater than hr W.ll. or 5 sem/ls ,
uiral Sperstasatsues limit. 500 amil/lar W.B. for two min- s hymni.I .it the sete I cnice.tc.l los une (1) hour. 15. k.a.liulogir.nl efflucuts gerater than utra (or live times ti. cme boun.lasy und.s to t ames Technical Speritiratiusas levels to the thysoid) at .sc a s.a t sci cos u lug e. a t is . l.a .gie s .1 c l i t uru t courrutsa- instantancuus limit s (asi i sss t ant - the site honudary for .ad- run.li t ions .
tsun. Teal.uarat Sectili- aucous r.at e bleis ta, il rositinued over vesse meteurulogy.
satson lies t a exa ce. led los- 2 1.ours, wout.1 sesult ise alout I mk 4. Othes plant s on.ls e sous '
l*s m e nu e ra.. at al.e Site Ituundas y under aver.sge B. These duse retrs .sre panject- exist , laum whateves j meteutulugical cou.litions or wl.cuever c.I hased ou uti.cr plant para- muusar, t ieat m. eke t elllucut mineit urs as s a.li u l ugis .s l meters (e.g., redsatsusa level scleas.c c1 lange l mouseitoring eletect Llirse levels. ise ruent a t uame nt wath Ir.ek r.ste amounts al sadsu-
, appsun.riate lor existang suss- att iv i t y su .a sleus t t a s umeset perssuse) es .ese per sent ut t e mie .
measu s ed s ee t he a-asv a s uus . pos s ils i c . Cuse melt l 1..
(Cont inucil) metuatinu.
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] t) CONTE nuclear STATION Page 2 al 9
! Al'fu/A/4000/02
! ENCIOSUkE 4.2 [
CulDt' FOR ESCAl.ATION j . . . . . . _ . . _ . _ -_ _ . _ _ __._. ..- _ _ _ _ _, ._ _
i llan:.ual Evrut s Alert Site Asea Emergeury 4 cur:41 F=cagruay ;
j ._ _ . - . . _ _ _ . - . . _ _ __ _ - . _ _ . - _ _ _ _ . _ _ . . . .
l j 12. C. EPA l*rotective Aation Gessde-i liucs are paujericJ tu 1.c !
- earce.fr.1 outs tile the ma te l 1.uussJ.a a y . >
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l L t ur l t. gc indseatsun 1. Severe Summ ut luct cl4JJing: 2. Ibegra. led ruse wille possible loss 2. l. usa ul' 2 or 'l denssou peu- 6 el ruut ble grumetsy (judicaturm Jus t b.str eers, wa lle a p..t re.-
- A. Il s gle s uolant as t ivit y sam- A. Vesy higle routesat as t ivit y m.saple bleussid sut t uale issst a sement at s e.u t ial lums ut t hi s.1 1..se a era .
! par (e.g., caser.lssag tuul- (e.g., 100 pCi/tr equivalcut ut to detect a si4Jc gu.e t e t u s e ruo l- !
l ul teel.uiral sprasficati l-Ill) sug, roulant Ittsvity and/ue ,
, dus s o.ls uc sp a hr ). (Ili gt. sailicattivity Irvels). i kraeIus Os.ulant S mple I j'
Aitsvisy) t
[
i 4. Al.nusmal ruulant scoperatuse 8. Severe loss al lesel cl4JJeug: 2. lA graded cure witis possihic lush 2. Imam el 2 e 1 temmium pen- l*
} an.8/us persmusr os aleuss s mal-at tout.shte geometsy. (inderaturm .lurt learricrm witte a p..tra-l lurl tema.raatuses untasle of A. Very leigla coulasat as t ivity sample ml.ould iurassJe innt reamculat sun t ail loss ul ties s.1 B..as s a rs . {
j' t re lua s e .s l spre s t a t a t s ues (e.g., 300 microCi/rc equivalcut to detect iu4Jcquate suse roul- j
. I s m a t a ( > 2',00 ps i g ) ul 1-l.11) isag, coulant activity an.1/ur .
I radiuartsvity levels).
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I OCON6E NUCl.EAk STATION Page 3 e1 *f
,Ap/0/A/1000/02
. ENClint*E 4.2 GUIDE 61* ESCALATION *
' l slu.u.a.s t Eva ut 6 Alest Site Area &mergency Crescral l~mergrees y I
- _ _ _ _ , _ _ . .._ _ _ _ _ _ _ _ ,_-_, _, _. t
- 9. Coulant 3. ump seizuse ic4 lang to f uel 7
lailure.
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} ' , . Exareding cast.cr prsmary/ 3. N apiel failuse of more tieau lo steam 1. Kusuu loss of coulant actedrut 4. Ottier plant s on.l e t iums
- sreundasy Ic.ak rate teal.netal geurrator lui.es (e.g., seves al laund- gre. ster Llaan makeup pump rap 4- exist, I s om win et rvre sou s i c ,
sg.cra lis .st ie.us or pa ssary Irak erd gpm psimary to secondasy Icak city (any leakage >500 gg ). t inat make triease el 14sgr tale t ro leseie 41 spcri t icat sous. rate).
amoussi s el r4 lauds t ovs t y ise I
I l DIO gg.as tot al P/5/ leakage) a slaust pessoJ ut tear.
- 5. l'rimary toolant leak rate greater 3. Rapid failuse of more tliasa ID Cose acit satu.eti..u.
A. Pa s m.a s y - e r gu e r s ug slant - tt:4sa 50 gpas, st eam grises at or tulars wella loss
- 41..wu a,I off-site power (e.g., sevce.sl 11 . h amas y t u se-rund.ary thei t i 6. liigli radiat iosa levels ear liegte air- laun.f r eei gpiin ger ima s y t o scrou.lar y
) 20. 5 0 gg.a. lausuc rs utamanat sun kleia la i sidicat es Icak rate).
i 4 sevese degra.lat ions ici ti e- rosat rol ,
I el f.ediuattive m.aterials (e.g., in- 4. lW ste.am liuc las rak willa ge rat-i re r.she ley a f.st tur of 1000 in dises-t er tisau:
rd.fi44 iou scadisigs)
A. 50 gem primary t o setou.a.es y i I ra k.s ge 14 , 50 gges p:imaa y Las sea ease.l.:s y leakage and indiratiou ul g luci dam. age.
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l l OCilNt.E NUClEAlt STATlosi l' arc 4 al '8 i AP/0/AfI000/02
- i kNCIDSt*E 4.2-
! Gull >E Hilt ESCALATION
- t
', llousual 6.wrni a Alert Site Area Fmergency Crueral l' cogen y [
l 8. . Failuse el 4 34tely relief ,
valve en mafety relatcJ
', sy te- to tau >e followsus
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i e cel.a a sua ui 43.g.1 i r a b l e t i
pscasusc. t 1
i I l A. ItCS Symira l
' 35 . te4su Stram 1 .
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I i l l 1. Russ ut olisese 1.uwer or loss 2. l(4piel giuss failuse of one steam 5. l.uss of all-site power 421 loss 4. Other plant s un.I n t eunu !
- of s.assse AC powrs capal.ility. generatus t ut.c wilia loss of allaite of on-site AC power f or miss e exist, Ison whatever a.ous r.
- power f ram all monarces.. (OTSG Tul.c) .tl4n 25 minutes. Elsat make sclease ut 14syc
- A. loss ut offuste 1.uwer
- amounts ut ra linae liwit y ('
j its .s slaus t pee inal ut t ime It . loss ut a.u-site power ut time possel.tr. s ..s e j '
melt situatina.
T. 1. ass of of f-sit e luswer asul larse ut
+
all on-site AC power for up to 15 i
, minutes (lass ut Kruwee suit trelitsle i so put consides cel). ;
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(MONLE NtM:11 Alt STATION Page 5 el_9 i
) AP/0/A/IDou/02 .
ENCinSUHE 4.2 CUllE FOl( ESCAIATioll ,
j . -.._ _____._ . . _ - - , _ _ . _ . . . _ .
Unusual Events Alert Site Area Emesgruty Ccueral imregrury t
- 8. Im a of e.,utaisnerut sutegrity (. . llagli radiat ion levela or higla aist orne ti. Otleer hazards lieing expersesised 2. Loss al 2 or l lismium pau-j' sreguissug shut. lown ley terhui- contaminations whith indiaates .4 severe or projectrJ with pleut uut in stuct har r sers wit ti a pnt ru-colJ shutJuwn.
s al ag*re i t s s'.s t s uus. .legradation in the rosstrol of radiu- tial loss ut tisisil 8..sssirs.
estive m.sterials (e.g., isu se.ase ley a ,
larter of 1000 in *litert r.adiation scad- !
ings).
4 I
- 9. 1.u:.m u t ru g e nre e rd ma t el y A ca - 10. Cumplete tuss of all luuttions lur 7. Complete loss ul' any functions 4. Other planet s ve lit ia us tuse or essar pretr(taun myntra plant ru i d . nleut elown . sierJc.I lor pl.sut hot shutduwu. cxist, laum whatevre suu s e . , I lunassuu s cegue s sus shut.l wu ley that mube scle sr ul 1.a s gr j t rs huse al ag cs e lis et suess (e.g. amounth u t s .sel s aat t s'v i t y f m.eltuunti no, pronunnel etrus, s ei 4 shost peria.I al I s em-
.. e peuerdural s ua.lc.gu.st y ) . el time possible. Cuse melt s a t u.it s un.
A. Lugiserrir.1 Sa f ety Fr.sturr ,
a St . Fa sc l'a utro t sun System .
- 14. tiost or .sil 414em (aunuuriators) lost. II. All alasms (aununciaturm) lost fur more tiaan 15 minutes .sud plant is uut ins ruld shutluwu or plant tsaussent i s. i t i a t e.1 ,
while all alarms lost.
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OCONEE NilCIIAN STATION P.sge 6 al 9 Al'/0/A/1000/02 ENCIDSURE 4.2
- GulDE FOR ESCAl.ATION i Hun:.ua l Event s Alert Site Area Emergency General Fwagreu y l t
1u. tese lasting muse than to 18. Fire potentially allerting safety 10. Fire compromising ti.e inurtions 4. Ot tact I'l an t sun.lsteuns ,
j minutes: systems. ut the safety systems. exist, l'aum whateves sonase, !
that m.ske retrase ul 8 ege !
A. Ousste amounts el r.s.lio. art e vil y ;
in a sliort peaio.1 ut t iw 4
11 . Oils s te (sur rousadisig t he pos sitale . Cuae melt
, statson) situation.
- 5. Any ma jor int.'a n.s l r exteenal events ti..at . ..u i .I e.ause massive . .n .l..m r.c tu plant systems.
A. Fires 11 . Eartlequ.skes (sul.st u-t i a i i y locyon.1,.les a gn lea s i s ) .
Notify: 1-2-a-/-it-it-12 ,.
li. in.lsaations ul s adi .s t i on sm.n i - f. liigh railiat ion levels or higla air- 82. Accialental Hele.ase of Cases 2. I.uss ut 2 us 3 l i r.s a.nei ps ..-
t us ing ges oe css .au.1 clilucut lausne runtamination whiels in.ficates -
durt I.a rs s ea's wa lle .e p..t cee-p.a s met er s wtai n te requise plant a severe degrmJatiosi isi the runt sul tial less ut this.11. ssire.
slin t .l..wn o r siguilirant loss ut r.adioactive matesials (e.g., in-ul wi t .a t auscsa. ment ur reeman- rs ease ley a tartor of 1000 is .lisect se a r.st s uas repi egwnt . ra lid t insi rea.li ngs ) .
1 (1:unt iseiscil) I
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- n OCbHEE NUCilAN STATION l' age F ul 9 Al*/0/ A/ I0')0/02 LNCIDSURE 4.2 t CllllE luk LSCAIATION lanusuai Events AleaL Si t e A a ca l'.me r geury Ccurra1 Facegensy
- 45. Nadiological e f fluents gicater tasan 10 times Trtlinical Specilitations isastantaneous limita (an i saht aut - -
aneous rate wisicia, si continucJ aver i 2 14ours, would result jos alsout I mk .
j at tiec Site lloundary unJer average mrtcurological cosadit sens or wiscuever
( cillesent m.assiturs or ra.liulogical
! m nitesing ilctect ti. cme levels). !
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w j 12. Scaus6ty tiiscat o r .s t t empl e.1 16. Ongoing Scturity Cumpsomshe. 13. Imenincut Russ of playsical 't . l.uss of 1.leysical a unt oul ut i j rat s y or .et t empicil maleatoge. Cosat rol of tiae plant. the facilsty (Na.te: Cous s.le s j tlie 2 mile pscrautiunacy i A. ILm.i/explussvc or missiles 17. Evaru.ation of (ontrol soum an.1 evacua t ion ) .*
runt rol of blautduwes systems not i ll . Suleves a s wc at t i vs t y at t rap- estalelisteed f eum lucal statiussh i s sl. in l$ maissutes.
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OCONEE NUCl. EAR STATiuN p.sge 8 of 9 Al*/0/A/1000/02 ENCIDSURE 4.2 CulDE FOR ESCAI.ATION unusual Events Alert Site Area Emessenry General Eieregency ,
t Nat ural g.l.cn..mcuun f.eing es- i l
- 11. 11. Severe natural phenumussa lieing ex- 14. Severe natural phessomena lacing 5. Any major intren.61 or per srae r.1 or ps uje<:ted locyund perienteil ur psojected (See specif ic experieure.1 or projected walls caternal events ti.at s ou l.1 j usu.s t leve l si; aundatis,ns) plant not ins rol.1 minutelown cause m.asseve aomeon elamage
- to pl.sut systems.
j A. 'Any casthsuake ( < .05 g Jc- '
4 s a gu as s eles at sun) A. I?iscs I
i
- 15 .
- u yr.s e llund or low wates, 15 . Ea r t i..sia.s kes ( r s.l.st ass-t 1.uss'as nc surge, sesehe t i.sily bryuse.1 lcs ir.u
( l .s h e tslal wave) h.e s i s ) , g C. Any t oe s.Jslu uPar sitC li, Any 1.ussir.aue (> 74 mpts) l l
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- 14. Olbre h.se.as.ls hesug espers- IM. Olleet har.srits beisig caperieurcel or 15. Otiser h.szas ds I,eing czper sented 4. Other pl.snt run.latsuus rnic.I us pauleited: . projected: co projected wills plant not in exist, f rom what ever s ..us e r, colet shutiluwn: th.st makes scle.sse ul lange
.smount s ut e a lio.es t a v s 4 y A. Asarsatt t r.asti oss-as i t e us A. Asterait oss facility. its .a slaus t perio.1 !
nuusu.al aistraft attivity A. Airrrait crasis eldrrting ovre 1.as s i s t y . B. Missile imp.scts trum whatever vital structures by ampart i bossa re un f acility. or fire.
H. Neas or on-site caplusion.
)'
i C. Known emplusion dam.sge to facility B. Severe el.sm.sge t u sale shut-C. Nr.ar or on-sste Lunar ur allertang plant us.c r a t ioss . .luwse a sguipnersel from missiles (Cunt inue.1) l
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! i OrONEE NLM:1. EAR STATION l' age 9 el 9 ;
i Al*/0/A/1000/02 i
! ENClJISSUkE 4.2 i CUIDE FOR ESCALATION l
j - . _ _ _ . . . _ _ . . . ~ . . . __ _ _. . . - . _ _ _ _. . ,
j lluusual Evesets Alert Site Area Emesgency Crneral Emesgeniy j _ . _ _ _ _ . . , _ . ._ . . . - - . _..__._.,___ _ -
! i l am.m..le l e ga s re t c.e se s.1 e or explosion. i
. m.s gu i t uile t i..s t a la r ca t rum D. Entry into facility envirous l pcssunnel, ut tuair or llamm. state g.ases. C. Ent s y el unrunt rolical fl.amm-l aisle gases into vital arra. g l Is . Tuil.suc sut.itsug component E. Tustaine failure rausing raming Entry el uncontrolle.1 tunic k l '
l .s s l u s e e du:. tug s apiel pl.sut prsert rat ion. g.ases isolo vital .ert'as inlica e [
j al.ut lown, lack of acccus tu tlic area runstituten a salcty pse,istem.
I '. . ' Ot i.c r pl ant'~iiiu~.li t'iiisinT--~~
~~~" ~~
i A. Cusuls a suum 4 ts.st warrant ina s cabr.1 aw.as raarsu ul I
j p.s e t ul s t .e t c .enil/us 5 I lue .sI uli s a e e .saul aullaus - I
)
4 etses. l r
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l It . 4'un.fi t e uns t li.e t requirc *
! r.leut lown un.le: a ca finia al ;
1 :.pca e i e a at i uns. i 1 >
i s. . Tsauspustats.n ut tontanssiate.1
- i s u j u s e.1 i n.l s v s lu.s l Issen site i tu ulle.ite.
- II. N.ep s et .lepe rr.
- .ur i zal s on u t g j IVR meson.lasy hatc. l t
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a: , w .,. w a , . - i E'; CLOSURE 4.3 Message Format CR CATE TT.vE MESSAGE No.
- 1. g
" 2. TJC CMC D Ortil 3. 4 Telephone Authentication
_' O E=argency
, 5. ACCI CIT I!.TcP3ATICN l j Initial
\
,_ ,3 Follow-up Time Unit Emergency Condition 6. CFTSI~E N0*I?! CATION Ev ry minute (s) Time Pickens Time Ocenee Time S.C. State Time Other
- 7. EMERCENCT C1.ASSITICA!!0N 8. Pt. ANT STATUS 9. PROGNOSIS (3ased on Plant Infor=ation)
O Unusual Event O Stable O Escalating Esergency O Alert O Improving ,
O De-escalating Emergency O Site Area Emergency O Degrading O Termination O General Emergency 0 Not Known O Not Known RADiot.cc! cat. T't?OWAT*f t .
- 10. 'r' m" 11. Rate of Release Curies /see 13. ME*ECRCI,0GT C Actual Wind Speed =ph O Proj ected a of Release ind Direction (from) o O Airborne .
O Vaterborne Release Duration Stability Class
- 12. Assume Ground Release Precipitation Form No 14 EST!!'ATES QUANTITY CONCENTRA!!ON
- 19. SECTCR(S) AFTEC ED s Noble Gas f ; Oconee 5mi
\.'s / -131 (equivalent) 10mi Particu,l ate Pickens Smi
- 13. Actual - Site Soundary 2mi 531 1031 10mi ,
- 16. Projected - Site 3 dry. 2mi 5m1 10m1
- 17. Integrated 221 5m1 10mi IS. Surf ace Radiation Contamination Estimate
- 1. Does ng involve the release of radioactive =aterial from the station or involve the public.
- 2. Involves the potential for the release of radio-active, but no radioactive sacerial has been released.
- 3. Does involve the release of some radioactive sacerial from the station, but at a level below that ,
considered a public hazard. l 1
4 Does i=volve the release of radioactl.4 aterials froc.
the station at a level at which protective action is advisable.
_^
- m. OTHIR INTCRMA!!CW .-
- 22. 03: IZ'.'IR3: 3!'E .;: r. NA:. :Ctc<Z': 5 : (Report to C.: unties uf:r:sti:n listed is 1 3 13. 23. 21. 22.)
(Report to State all inf:r=at:.:n 2vailable.)
AP/0/A/1000/02 l ENCLOSURE 4.4 V .
DUKE POWER COMPANY OCONEE. NUCLEAR STATION .
PLANT STATUS (Circle) Oconee NUCLEAR STATION UNIT Unusual Event - Alert PLANT DATA AND STATUS DATE Site Emer. - Gen. Emer. INFORMATION TIME Control Room TSC -
i.
HPC OSC 4
By Title
a
+
3 d mi N
1 Form SPD-1002-1 DUKE POWER COMPANY (1) ID No: AP/0/A/1000/03 PROCEDURE PREPARATION Change (s) N/A to PROCESS RECORD N/AIncorporated (2) STATION: Oconee Nuclear Station (3) PROCEDURE TITLE: Emergency Action Level (EAL) - ALERT
- O (4) PREPARED BY: DATE: [ 1--
(5) REVIEWED BY: DATE: , 7 'y ,$l _
w v
( 7 y Cross-Disciplinary Review By: N/R: k (6) TEMPORARY APPROVAL (IF NECESSARY):
By: (SRO) Date:
By- Date:
(7) APPROVED BY: / u.g Date: . 9\R (8) MISCELLANEOUS:
Reviewed /Apprcecd By: # p h Or Date:/ /SM/A Reviewed / Approved By: Date:
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w FORM SPD-1001-2 DUKE POWER COMPAhT NUCLEAR SAFETY EVALUATION CHECK LIST
[m\ (1) STATION: h UNIT: 1 2 3 Q) .&
(2) CHECK LIST APPLICABLE TO: M//)0}HE)l:
/ AL//o do/6 3 (3) SAFETY EVALUATION - PART A The item to which this evaluation is applicable represents:
Yes No # A change to the station or procedures as described in the FSAR; or a test or experiment not described in the FSAR?
If the answer to the above is "Yes", attach a detailed description of the item being evaluated and an identification of the affected section(s) of the FSAR.
(4) SAFETY EVALUATION - PART B Yes No / Will this item require a change to the station Technical Specifications?
If the answer to the above is "Yes," identify the specification (s) affected and/or attach the applicable pages(s) with the change (s) indicated.
(5) SAFETY EVALUATION - PART C As a result of the item to which this evaluation is applicable:
Yes No / Will the probability of an accident previously evaluated in the FSAR be increased?
Yes No ' Will the consequences of an accident previously evaluated in the FSAR be increased? ~
Yes No V May the possibility of an accident which is different than any already evaluated in the FSAR be created?
Yes No ' Will the probability of a malfunction of equipment important to safety previously evaluated in the FSAR
- be increased?
Yes No Will the consequences of a malfunction of equipment important to safety previously evaluated in the FSAR f be increased?
Yes No May the possibility of malfunction of equipment important to safety different than any already evaluated in the FSAR be created?
Yes No V Will the margin of safety as defined in the bases to any Technical Specification be reduced?
If the answer to any of the preceding is "Yes", an unreviewed safety question is involved. Justify ble conclusion that an unreviewed safety question is or is not involved [ l Attach additional pages as necessary.
(6) PREPARED BY: M/ w CM DATE: s7 L O (7) REVIZWED BY: /t DATE: ,4 2 l 4 f '/ / ~
<b M f (8) Page 1 of [ j sf . '
46M l p s. e i
4
, AP/0/A/1000/03 Page 1 of 3 p DUKE POWER COMPAhT 1
\ OCONEE NUCLEAR STATION
[
EMERGENCY ACTION LEVEL (EAL) . ALERT k
1.0 Symptoms
The symptoms of an Alert will vary according to the initiating conditions. Enclosure 4.1 defines the different conditions and gives specific symptoms of each of the same.
2.0 Immediate Action ,
2.1 Automatic - NA 2.2 Manual Date/Name Time 2.2.1 If Hazardous Radiological conditions or the potential for such conditions exist, initiate a site assembly using S. D. 2.9.1. Record results on Enclosure 4.4, Station Personnel Accountability. Take immediate remedial action to insure the health and safety of personnel, minimize radiation and contamination problems, and minimize damage to the plant. Record actions taken on Enclosure 4.5,
,__ Plant Data and Status Information.
j (x,_,/ i 2.2.2 If radition or contamination is involved, dispatch onsite monitoring teams with necessary communication equipment to assess and recommend methods of controlling or contain-ing radiation and contamination. Record action taken and -
results of survey on Enclosure 4.5, Plant Data and Status Info rmation.
2.2.3 If a possibility of an offsite dose exists as a result of this event, evaluate the need 'for an offsite dose cal-culation.
i NOTE: AP/0/B/1000/07 is for the Control Room use only for dose calculation. The Health Physics Section will use H.P. procedures if they perform' the cal-culation.
2.2.4 Determine from Enclosure 4.1, Alert Initiating Conditions, the most descriptive initiating condition for the event.
2.2.5 Activate:the Technical Support Center. Use Enclosure 4.6 or 4.7, Emergency Organization Recall. Have the Station Manager (or Emergency Coordinator alternate) bring the Crisis Management Team to a standby alert status.
-(s_,/ .
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AP/0/A/1000/03
.; Page 2 of 3 (N )
Date/Name Time 2.2.6 Appoint an individual to be responsible for keeping records of the emergency and to notify offsite agencies and company personnel.
, 2.2.6.1 Notify company personnel and offsite authorities of the nature of the plant conditions using Enclosure 4.1, Alert Initiating Conditions, as i
a guide for notification. Refer to the Emergency
. Telephone Listing in the Implementing Procedures Manual for the telephone number that corresponds to the notification code under each initiating condition.
2.,2.6.2 Enclosure 4.3, Message Format, to be used in notifying staff and offsite authorities for both initial and followup contacts. Offsite notifi-cations should be accomplished within 15 minutes of the EAL. Establish update time frame with offsite agencies.
2.2.6.3 Record actions taken and events as they occur on Enclosure 4.5, Plant Data and Status Information.
The Control Room will be responsible for notifi-cation of offsite authorities and for recording events as they occur until the Techincal Support (v) Center is fully activated and operational. After that time, the Technical Support Center will be responsible for recording events and notifying offsite agencies. -
2.2.7 Technical Support Center is fully activated and operational.
2.2.8 Operational Support Center is activated and operational.
2.2.9 Evacuate all station areas where unexpected exposures to greater than 2.5 mrem /hr or 40 MFC-HRS could result.
NOTE: If such exposures apply to areas outside the RCA, initiate a station evacuation as per S. D. 2.9.1, AP/0/A/1000/10, and HP/0/B/1009/16, and evaluate the need for event escalation.
2.2.10 Proceed.through use of the proper procedures to bring the plant to a stable safe condition. Record actions taken on Enclosure 4.5, Plant-Data and Status Information.
3.0 Subsequent Action:
(n 3.1 Mien plant conditions warrant, the Alert emergency should be de-escalated or escalated to the next emergency action level.
. _ -. . _ _. - _ = . .. ._. - __. . . . . _ - -
AP/0/A/1000/03 i Page 3 of 3 )
Date/Name Time -
4 NOTE: Use Enclosure 4.2, Guide for Escalation, to identify the
- proper EAL if a change is warranted. From the time a new EAL is identified, all offsite authorities should be notified within 15 minutes.
3.2 In the event that Protective Action Guides need to be issued to l
offsite authorities, this event must be escalated to a General Emergency.
3.3 In the event the emergency is to be terminated, de-escalate to an Unusual Event.
3.4 De-escalation requires the concensus of the Nuclear Regulatory Com-mission and the state of South Carolina.
4.0 Enclosures 4.1 Alert Initiating Conditions 4.2 Guide for Escalation 4.3 Message Format
) 4.4 Station Personnel Accountability 4.5 Plant Data and Status Information 4.6 Emergency Organization Recall - Normal Working Hours -
4.7 Emergency Organization Recall - Backshifts, Holidays, Weekends 4
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i l OCONEE NUCl. EAR STATION l'a ge I of 9 g ,
i AP/0/Afl000/0) !
LNCIDSul(E 4. I l
j AlLRT 1
l Alest Osunce Nuclear Stat iuss Irissal Emergency l*ruccJusc/th a nnesit j l
inetsatsug Conlissuns Symptums Safety Analysis keport Section 14.1 I. S vese Summ uf fuel s14J.lang; .A. Vesy hagia tuotant activity less of Coolant Accideset; il4med on EP/0/A/lH00/04 i mample (e.g., 300 pCi/cc Chemistry Analysis LP/0/A/lR00/27 N. l s i a s .s t i osa C. lc I-2-6-7-11-82 c.guivalent of I-131) LI'/0/A/1800/ I I ;
85 Ik c re4a.e in s e.sctor coulant flow. l Contaul kuum indsration.
- . l.ouse parts smessitor indicates pastitles ist reat ter ruolmaat
- system.
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N.sp s .1 g a umn lasturr us s. sac steam Mc44tus trap on low pseumsase; klA 16 Steam Generat or Tul.e kupt ure and LP/0/A/1800/04
! ge nr a al us t ules* w 6 t h less ut uli- e. s 8 7 anJ 40 liigis alases; less of kC loma of olisite power. EP/0/A/1800/14 aste powes laum .sil moursem anventusy via psensussger level; in- LP/0/A/1800/lb loiha. Tul,r) a scamang SG level uss af fecte.1 SG; LP/0/A/1800/l? l un.les vol t age a l a s ms un m.s s u f oe.lcr FP/0/A/1800/29
' l-2*f,-7-Il-12 N..t s i s a .el s on Co.lc f.uses; t s aunier of musilias y power to l
! ma andt,y 1,umes; load bleed el non-j rasential lo.sJs; TlHWP st a s t ;
a.ws t alaya:J isolat ion; Kruwce i t ass ia e ne ge-sec ra t us a reme rgency mi a s t i l
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I OCl*EE NilCIEAN STAT!M Page 2 of 9 AP/0/AflOOO/0)
ENClDSUNE 4. I g .
Al.ERT AI. s t (konce Nuclear Stat suu Fenal Emergenty Pruscluir/D...umrut inetsatsus Cualetions Symptums Sa f e t y An.slys is kepun t Sec t ios 14.1
- 6. kaps.1 tailuse ul .ar tisasi 80 tow RC pressure stare; low P2R level Steam Generatur Tulee kaptune EP/0/A/1800/04 a
str geurs tus tul.rs (e.g., alass; klA 16 or 17 and 40 taigli alasms EP/0/A/1800/IT s.veral 8.uu.lsr.1 gpm prem.ary tu (Coutsut kuum iss larat ions); increasing i,e s cu.las y leak sate). 56 level un affetted SC (Coutsul Muum is lat at is.n) lcrreasing scat tur tuulant N..t t i s s at suu Cu.le: l-2-6-1-11-12 anventury via psessurizer level & NC psensuse (Control kuum indst.stion),
eventu.sl scat-tos trip un low kC I f
garssure excessive RC m.skeup flow.
klA-40 se. ads allstalc.
I
- 4. *.t r ..e l ouc 8.s rab w e lle signife- Hagei.I decrease su ttS pressuse, Elec. Steam Generatur Tul.c Nuptuse; Hissur '
EP/0/ A/1800/04
. aut (c. g. , gicat r r alian 10 gpm) lead, PZR frvel, NC psessure and TC; Srtundasy System Pipe lireak; Plajor EP/0/A/1800/08 s.esmesy to sca ou.la s y leak sate or erartur trip usa low persaure'us lasgli Secundary System l'ipe kupt use EP/u/A/1800/l?
IlusV m llen.sion, puwer; sucerase scatter I.uilding pscasuse and temperatute (iusi.le i N..I o l is .st le.n Co.le: 1-2-6-7-14-12 1.a rak); at t uat ion ul ES al anuels 1-6; !
attu.etion el ES tia.suncls I an.1 2.
. e l
,. Pasm.asy oculant leak satr ger.st+ NCS leakage rate slauws leak rate; ele- Partial.luss ut kc.sttur Coulant EP/0/A/1800/04 re s taan 50 spm. i ar.asing per level (prior to HP iss jec- Flow; loss of kcactor Coulant true tsuu pump start); susic.sseng pressuse Small !!uptuscJ Pipes; loss of' Coul-N..I s i s e .el e on Co.le 4-6-1-1l-12 su scattua louilding; visual ut. serv.s- ant Attident aseu auutinur.l:
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- 43CONEE Nth
- 1.EAN KTAfl0N P. age 'l of 9 l AP/0/Afl000/01
+ ENCIDMikE 4. t ,
i' AI.ENT !
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. . _ . _ . . i Aless Oronce Nuclear Station Final Eme rge set y 1*ror r.lu s r/lhet ument g I
.inesisting 4"uulsasuus Symptuma Salcty Analysis koros t ScrLiuss 14.1 j with TV ramera; IDST level Jerreasing ,
j more Lt ass seosmal; N8 sumps - IIAVf an [
1 IAVI' level . I i t i' .
t i L l
5 s. . Ils gle s aJ s a t s wes levelb or leigle inescase of NIA readings i s. Wste Can Decay Tank Nupture; Steam EP/0/Afl800/24 f.
asel.osuc . ..nt m e na t ion wis i t te in- .stirracJ ascas (NIA's around went Generator Tube kupture; 3.oss of
.l s e .et ra . srvesc legralation in 1.ca.ic t er gas Jcray rouen); Coolant Accident !
- si e suussui al s davastive plant area iodinc or p. articulate
- m arse.sla (e.g., ssee s ease ley a .sisluerne 4 unt rut s at iusa great es tinass .
1 8 .tur el 1000 in Jarret radi- 1000 ml.c. i j .et s..a s tadiuss) .
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N..a a i s e at i..n 4:uale : 1 d.- i- I l - 12
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load sejettiun
- rr.sa-t ur t rip; swe t a le- i.ons u f oi l-s i t e powe r t o St a t ion .
/. l.uus us all-mile power and tuss EP/0/A/1800/14 j j .4 all .u aitr AC luwer for up y.esJ smulation un 2/3 undesvolt and un- Auxiliaries (Station tilack-out) EP/0/A/1800/16
- t e. 14 e s aus t en ( l u s ul Kruwer .lci s repsena y - Kruwce remergensa y st aa t EP/0/Afl800/25 +
3 sue t e a r lsisir su not suussJescd). transfer el auxiliaries to stanJhy EP/u/A/8800/29 j l.uses iss - 21 ser.; s anscJia t e indira-l j N..ladisation ru.lc . l-2-d.-/-11-12 Leon in lums ul weltage on main feeder !
, 1.usrs; se.se tor s oulaset gunsps t rip; ES '
I as t as.st inu use low HC pressiss e; ECOS I '
stasts ou ES.
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. DCtH6EE hlaCl.EAk STATION Page 4 of 9 ;
AP/0/Afluno/01 t i ENCIMilkE 4.I !
Al } kT Al st a t Ocusace Nuclear Stat ion Fium t '6sergesicy Prorr. lure /shers-mrut j f ue s s at a ng rm-is e a uns Sympte.=6 Saf ety Auslysis kcpus t Sections 14.1 -
- at . less ut un sale IJC power. Cent rol kuuas laularat inas; statalesm EP/0/A/1800/16 i in.lsa 41iosi 1)C t runstate mod 1.at tery kP/0/A/1800/38
! N.stiliratsun tble 1-2-6-7-11-42 insc4kers open; low voltage on (JC lauses i liA, Dil,liC troutele on EPSI..
1
! *s . s'..u l an t pump sc e au rs- le.sdius tu kcas tus coolant pump auto trip alare; Partial less of ke ctor Coolant EP/0/A/1800/06 lawl 14aluer. scartur trip ese ilus/Ilow/imialause; Flow; Single kcactor Cool.aut Pump al.cmist s y analys e s per sample se. guest 1.osked Rotor P:..s e l s s at sua Co.le t 1-2-6-1-11-82 andatate fuel a-led leseakJuwn; prior to pump seszure, leigte vilarat susa alasm.
t les. Cum.ple t e fuss ut .all luustions i tTS syst ras are aeot operatiosa.s!, Russ EP/0/A/1800/16 1 los plant s ulJ St.us due,n liPI, EPI, kHS, kHCU, trJun.lJHt ihalica* EP/0/Afl800/14 l
tson in Centrol kuum; natier.al ti ra ssla- EP/0/A/1800/29 i N..t a l a s .a t s un C.-l.- l-2-6-1-11-12 isuu rannot lee olet .s i nrJ . EP/0/A/1800/38
.i EP/0/A/1800/06 j
EP/0/A/1800/08 1
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! stDNEE hilCljAk STATION Page $ of 9 f
! AP/0/A/luo0/0) 4 ENCIDStakE 4. 5 f AlikT ;
! Alest Oconce Nuclear Station Final Emergency Procc.lurc/lk.s um. us !
Inst e at ing C n.ls t ioum Symptoms Salety Analysin keport Settson 14.1
[
, e s . F e lu c ut s tic rrastor preset- k<atter ermaius critical alter t rip. EP/0/Afl800/01 l as..a syntam to instiate an.1 sum- kwlm tre sin out . LP/0/AflB00/21 !
i pirae a mer4. i.I. i s le 1.t i ngs t 1.e k l sra.4 r so.4.ssitsial.
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if t u. l . lam.ege aesi.l.nt wette selc me A. klA's 2, 3, 4 alasm. Building Fuel Mandling Accidesit; l ua.lve s t en t
~ El*/0/A/I800/13 !
- a s a.isuas a evit y t u e untais ment isolatiuss (Control kuum in.lica- Is.Jiang of Fuel Assemi.ly into an Ll/0/A/1800/24 f
{ ue luc t I.ae.Ji a ng 1.u s tJ ang.
tion and local). Improper Position [
]
A. s: t ainecut es . klA 6 alasm (Control koom indira-t sua and los al) i is . har t 1. n.Il i ng 1.u e l.l e ng (Si t*) l 1
C. klA II, 15, 7, 10 alarm. (Control !
} a. A.eailias y ILees 1.lis g koum in.lical ion) !
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OQW6LL let#:llAk STATIOsl l' age 6 a.i 9 [
AP/0/Afl000/03 !
EleCIDSt*E 4. I f A11NT !
f Aless Oconee liutlear St.at ness Final Emergeury Proce.lus c/lk.a u u na j = f us s i.t s us l' n. lit se.us symptoms Salety Analysis keport Sectium 14.8 4
l i. Faer potratsally aliccting sairey Visual observatson - fire aless in
, sy st ress . saf ety relatcJ ascas 1
.- N..a i f a ra t s e.a Ca le : 8-2-6-7-88-82 I .
. _ . , ,_.n. . ---. .- - - . . .
- 14. tk.se or all 4 lasses (annuut iatos s) Vssual observat ion by operator; loss 1.oss of off-site power. EP/u/A/lRoo/14 i l os. t . ul a amputer; EC pressure asul ta:mpera- EP/0/Afl800/lb
! tuse still available en thest seterJets LP/0/A/lR00/29
{ N I s i s s a t a..u 4:o.l * ; l-2-6-7-88-12 s ee Coat s al Houe, intore thermorouples EP/0/A/8800/38 San be sc4J manu.sily.
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! OClahtL NUClk.Ak STATIOff l' age F of 9
! AP/0/A/10t:0/0) l ENCIAG*E 4. I f i Al1N f -
I 1
i f A 1. s t ikonce Nierlear Stativu Fiesal Esmergency l's ee rdure/lkee nme-ut lus t a,et es.g tals& suun Sympeten Safety Assalysis Nepos t Sect soes 14.1
_ _ _ . . . . ~. _ _ _ . . _ - _ _ _ . ___.
l, s '. it ..Is uluge. ! rli lewut a ge cat er H a gle redsatia.a alasms on NIA's is, 15 Waste Gas Ikray Tank Nupture; 8.iegu iel l'P/0/A/1800/24 !
4 8. a lo see m Trol.nesal Speriss- it, 45, 44, 43 lur longer t han 15 Waste storage Tastk kapture, Steam j ratsuun inst ant uruum limita (au manutes. Generator Tul.e Nupture; loss of j s us t an t asere.us r a a r wie s t le, il Coolant AtcsJcut ;
e..utiu r.1 uver 2 lua.sm, m.ulJ !
arault au l ut I aJe at ale Sate
, 41..uu.l.s s y u.=Ir a average meteus ulug--
! e s 4 8 s und e t s ue s ur ut.cucver I l ri f lewut ames.s t us s ut sa.laulugital *
. .us tos ing . ire re a ll.cse leveln).
1 Nulsiesetse.u Code: 1 le I l - 12 I 4
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j is. . esug..s ug Sri us s l y s umig.e ses se. licarensued 4.y Secursty Forse event Stati.,es Security I'lau e rsult ing su selves maries (usumass.lces ing -
! . N. 4 e l s e .al e..* Coulr 1 i. I l - 8 2 ass .ssra of Else plant leut asut toutsul of sleut J..wu rapaleiI Ly.
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UCuptE NUC11Ak STAitost Page 8 el 9 AP/0/Att000/0) .
l.hCIDSUNE 4.5 Al.ENT l Alcat Oconee Iliaclear Stat ioss Fissa! Emergraty Proceduse/lk 'macut !
j.
lustsatsug C.u.Jiteous Syngtoms Safety Analysis Repurt Section 14.3 I i
j e J. Seves e mas ua al g.l.cs.omossa 1.e 6:sg A. Visesal (Sacrvatiusa LP/0/A/IS00/09 l i cas.cs ars.o r.1 us projes scJ LP/0/A/IS00/l% ;
! II . Vssual Ot.scrwation El*/0/A/ IS00/ 50 A. E4s tl..g.e4be great er llease [
EP/0/A/8800/25 -
!' ah.co.e4eunal R4 sin Eastiguake C. Vasual Olenesvation
- El*/0/A/as00/19 8.svels (* . O's g). AP/0/A/1000/
I 18 Vssual (&merwatium St . &leuol, low water,I.urriraue Tursi4Jo Missile lap.act, Sprut Fuel 3
a.us gc , be s t l.c ucar desigee Assalysis I
trvels (labc is.lel wave) '
t . .
l 4:. Any lueu4J str a k asig f at ility [
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i . 18 II.n s 6e mus wenJ ucar design i I..s m a s I rwe l (< 9". mple) . !
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3 N..t il e s 44 son CoJc; ' l-2-t,-1-il- 82 i sh. sie l.c s 1444s.1:. l.c e ng caper icosa cil Vanisal bl nervat son j ne po ulce s cel; i h
I A. Asser.sts asas.l. au larilsey Tornadu Missile impart , Speset Fuel l l Aasalysis ,
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uuden:E isOClJAR STATION l' age 9 el 9 i
AP/0/A/1000/01 l ENClisSl*E 4.I I All.kT l . . . . . . . - - --. - - . . - - - . - - . . . - - - . - - _ _ . . - - - _ _ -. __ .. .
Alest Oconoce Nuclear Statinu >inal Emergency l*roccluse/lbeumaut lastsatens iba.3st8a"* hy=Pt**s Salety Analysis liepart Secteum 14.t Is . tutsy ente tacility ruvarann ut suais e.r limamsel.le gaben .
F. Tu e le s sw.lasiusr emumsug luss of Enternal Electric Im448 avul/
sameng p.entrates,u. ur Tusleine Trip N..I s i s e .al s. n l'uele: 1-2-6-7-11-12 84 ass t.c. p l ane t s ome.li t s uam ra i n t As di s erted ley l*lant C..n. lit i..us I I.a t s u 4 8.c j u.lgreernt ut tiec Lt. set feupeevimus, slee upwaatsuam Iwa y Engsurre , llw Sun.cs sat rnJent l 1 ..I s yr s .st s n:. , as ti.c l*laut l Bl n.eger was s.ent pareautionasy l as4avaisun ui Tre l.n a r.s l Suppus t s'. sat rs au l ser.st-m e le. Os a si s it ses ge em ua Cent rs .
i N..I s i s e al s..n 4*uele 1-2-6-7-88-12 1
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AP/0/A/1000/01 i ENCIDSlJkE 4.2 s [
GUlbE l'ON ESCAIAtlON i i ) i
- - - - . - - - - - . . - - - - - . - . - - .- . - I Alert Site Area Emergency General Emergency Unusual Event
- s. :.rvr e e lua el luct cle.t. ling: 2. begr4Jed cure with possiiste less 2. Ims s o f 'a or 3 fisasun pro.luct 1. Fuel Jamage inlicatsun:
of ruolable gmmet ry (in.lat atoe s laarriers with a potential loss St.oulJ inc lu.le inst rumentat ion to el third learrier. A. liigh toolant at t ivit y s.emaile r Jet es t inadesguate sos e cooling, (e.g. , exs ce. ling e scolant soolant actively an.8/or radio- terl.nical specificataan tus ;
es t avit y Irwels). loline spikr). (llegte kr.eatur Coulant Sample Attivity).
i
- 1. leap s .1 g s un 14aluer el one steam L Imss ut oil-site power and loss of 4. Ottier plant runda t ions esist , 7. less of offsite powes us loss '
- g. s.e s .s t ur s ul e w e t te loss el all- un-sste AC power for moor ti.an 25 from whatever svarse, that make of onsite AC power a.epability.
I %ste powes iss.m all suurnes eninn t ra. sclease el large amounts al 10r % Tub.l. radio 4rtivity in a shust period A. l.uss el olisite powes of time possible. Core melt situation. fl . loss el on-site. AC puwes
~ . . _ . . _ _ . . . . _ _ . - , _ .
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- s. Isaped las tus e al m.oa c tlaan IU l. Knuwn luss of ruolant arciJent 4. Other plant runJiLions exist. 5. Eareciling ci t t.cr p s im.a s y/ sci an.4-str genesatus tubra (e.g., gsrater thaes make.ap paump rapacit y laea whatever sourre, that make dry leak rate teahniaal aperi-i,.vcs l I.un.lse.1 gge primary tu (any Ic4kage > 500 gpe). release of large am nint s of fications or prsmary Irak sate t i sc un.l.asy Ir k 44tc). ra.liuartivity is 4 short per sial technical specifications. l = 10 of time possible. Core melt gle total P/S leakage) 5 situation. .
4 A. Prim.sry - tregui ring sinen -
Juwn f f
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- 18 . Prim.ary t u bea un.l.ory thai t I
>0.10 gpm iont ispar.1:
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i UCONEE NUCif.Ak STATION . l' age 2 ,el 9 AP/0/A/ju00/01 ,
. lasclJtit*E 4.2 ,
Gl1IDE 6t>lt t.SCAI.ATION /
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4 Alcst . Sete Asca Fmesgenry Cencral Emergrney ljuusual Fveset ) i i . . . . - . _ _ . , _ _. _ . ..-._._ ._ .- _ . . . . _ _ _ . . _ . _ - . !
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} 4 Str.se lanc l.erek with signifi- 1, Itapid f ailuse of' more chais to 2. Imms et 2 or 3 lission product S. Exceedisig eittier prim.as y/scre,u 1- !
..t (e.g., giraser ll.4a 10 spel generatur tubes with less of barriers wills a potential loss el any Irak rate teal.uir.el spreits-i pasm.esy tu aroun.lasy leak rate .el f -site powe r (e.g. , several staird leartirr. cat aosas or primas y leak s.ej r os it:;lV ewiluni t sun. 1.undrcJ gle primas y to mess. net- testanical specilir tions. (> 80
.a r y icek ratc). . gpes tut.a t l'/S/ trakage),
j 4.,IW stram line lescah with greater ,
t i..au ., A. l*r amary - arepsi s eng .l.nl.l..wu I
A. 50 gie ps imas y to setundary li . 1*r assa ry t o scruu.a.s s y lim i t I !
leak.sgr .
> 0.F8 gne ;
- - i i ll . 50 gem pria.esy tu sea uuJ.s s y g l Icak.sge an.1 isadication ul ;
i duel damage. t 1 4 4 r i !
.. l*s ense y s uulaul l e .ek r.st e ge r.a t - 1. Kuawen,luss el a colant ari*ident 4. Otl.er plant aen. lit iness exist , I. Emessenty Core Couting init e.es - !
rs th.eu Su gym. ge rater tisau en.skrup pusep e aper s t y f rom wl.atever suurse, t heat m.ake cel (ru suridcut we t ta gues s t ive 4 Las.y Ic4kage > SCO gpe), retrase of lasse maaset s el lisplisig tlaat issitiation is leur
! s adsoat t ivit y in a si. ort perio.1 spurious. ES da t uatc4 u.I .t i s- !
ut time possible. Cure melt a la s ges t o vessel .
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OCtJNEE NUCl.EAN STATION "Page 3 ofv9 o >
AP/u/Afloo0/04.
LNCIDSuid 4.2 A
- CUIDE tok ESCAI.ATibN N - '
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4 Alert Site Area Emergency Cencral Emesgreicy tinusual Event *
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- l _ _ . _ _ . . . - . _ . . . _ . . _ _ _ _ . _ _ _ . __;.__._._ ,
- s. . lii gte r a.liat ioet levels or higts 12. A(cadental Release of Cases 1. Accidental Hrtrase ,
.sashusue runtamination which in- <[' <.
I dir.stes 4 arvere .legra.lation in A. Efiluent manitors detect A Effluent mosastors Jetect level ,
, ti.e sonesul ni radioactive levels cussespunJing to corresponding to I rem /
s.it er i a l s (e.g., incre.ame by a gre. ster than 50 mik/hr f or hr W.8 ur S trm/hr thyroid - '
laitos el lbon in disert r a.l i - A I/2 hour or greaterJ han .s t the sate,luun.la'ay under \"*g *i atson aradangs). 500 mH/h r W. S . f o r t wo' . . ara wal aset eurologir.nl .condi- ^ % '
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minutes (or five ti.nes ti.ese' t i on s . ' % 1,. -
levels to ti.e thysoid) at r
,* . s the site houndary for advesse metrusology,
- 4. Other plant runditions exist, trums wk.atever sousrc, t h.s t s
y ..
make release of large amounts ,
-J is . Thesc['Joserates.sreproject- of radioactivity in a short i , . ed .!fded un all.er plant para- perio.1 of time possible, s. j
' meters (e.g.,Ja.liation level Core melt situation. -
s su containas nt with leak rate ;
appropriate for entsting tun- ,
tainment pressure) or are '
=" measured in the environs.
m + , .
f C. t a'A Prot ect ive Act ion Guide- - '*
_M lines .nse psujette.1 to he %
- s. exarcJed outside the site f.ounJ.a y.
. _ .2 _ __ _ _ . . . _ _ . _ _ _ _ _ _ ___ .__.._h_.. . . . . _ _ _ _ _ _ _
/. 4.uw. us oil-mite power and loss 'a . l.oss of all-site power gata loss 4. Other plant ronditions exist, from 1. l.oss of off-site powei- un loss !
ul . sit un-site AC power for up of on-site AC power fur more th.au wis stever source, t hat make release o f on-s i t e W power s'.spal.i l i t y j to 15 msunics (loss .st Kruwee 25 minutes, ut large amutants of radecactivity not a i r.ls tele su not runs i .le s r.8 ) .- iss a shoa t perical of t ime possil lr. A. l.oss ut of f-site pwes
- 's s Core melt situation.
. Is . Loss of on-site AC p..wes
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l Os1)liLE NUCilAlt STATION l' age 4 of 9 i AP/0/Aflouu/03 '
, ENCIAaSl*E 4.2 i
CHIDE 11* FSCABATit>N .
i i Alces Site Area Emergesuy
- Cesectal Emes gency Unusanal Event
, n. 8.un.s ut on-m a t e 13C i.uwe r . is . loss ut all vstal on-site IM' power 4. Ottier plant ronda t ions esist, l for more than IS manutes. ' f ream wl.atever suerte, tisat make i
^
release of image amounts of radioactivity in a sl.os t per st l of time possibir. Cure melt i
, situation. I f f 1
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7 l *s . Coul ut p.m.p se sius e leading to 2. liegra.fc.I rore witle possitale firms of 2 Lums of 2 or ~l lission 3. Fuel damage isplication: [
! luel failuse. s uolable geomet ry (andicaturm should product leaariess with a include instrumentation to detect potential loss og thir.1 A. liigh coolarat attevity mampic inadeepeate core cooling, ruolasat laa r r i e r . (e.g., estredeux soulant ac t ivit y an.1/or s aaliuart svity levels. tral nical spes ii st at sun las io.line spebe). (lis e;te lir.se Ios Coulant S. ample Astswely).
lo. Completc loss ul lunttions 5. loss of off-site power and less el 4. Other plant, renditions exist, 9. 1.uss of esigineerr.1 s.alety lea- .
los plant s old sleut.luun. un-site AC power for muse th.us 25 from whatever suuste, Lt.at make tuse or fire protewteun systre minuten, release of large amuunts of f unct ion treguireng shutdown sadioactivity in a short period I.y teel.nital specifications
- l. Completc. loss of any Innstions el tsee possible. Cuse smelt (e.g., mallunation, personurl ,
ner. led lur plant laut sleu t down . situation. error, or pausrducal s ua.lc.iu.st y .
II. Fvainatson al centsul sue.m and a unt s ul ut shut d..was systres not ,
, estalslister.1 I som lural stations '
su IS minutes.
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i OCONtE NOCI. EAR STATIUN Pase S et 9 Al*/0/A/1000/01 ENC 11ELRE 4.2 GullsE l'Olt ESCAIATION .
Alcet Site Area 1:mergenty General Emergenty Ussusual Event i II. I'.siluse us ti.c reartus proter- 2. . Ilegraaled rare with possitale loss 4. Other plant s'endit ions exist , 9. loss uf rugineerrJ safety tr + ,
esun systre to initiate and rum- ut coulable'geometsy (indiratass from wlatever seurar, that make tuse or f ase peutet t suy system [
, pletc a sesam whseh lerisegs the should include isast rument at son release of large amounts of f unt t ions r e.ps e r iseg shas atuwu ley i e r.si t u s suhe e s t is a l . to detert ina.lequate rose routing, radivartivity in a short periud t ra tanical spcs t f arai sons (r ,s;. .
roulant ac tivity anJ/us radio- of time possible. Cuse melt u.allunation, pessonncI rerue, aativity levels). s i t ssa t ion . ur proccJural i naJceguae y ) .
- 8. Trasssirnt sr.gui ring operat ion of f shut down systems wille fealuse to i sasam (runtinued power generation f' leu t no rote Jamage ismicJia t el y cvident).
- 11 Fuci .l....sgr ac c i dent wish re- 9. Hajor J mage to spent luel L lassu of 2 or i d ission psuJus t 4. Al.nusual roulant teopcsatuse
- 1. .sur ut s adioat t ivit y t u s on-i l>ar rica s wills a potent ial loss and/or presssere or el.noa m41 t a s um. nt us luct handling leuild- A. Isesantainment (e.g., water of third learsier, fuel tropesatures outside of l sng. , loss below luct level) trahuiral specilstation l a m e t s.
(>2500 psig) l 1 II . In Fuel llandling Bueldsug (SFP)
(r.g., las ge elejert stamages f uel .
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a l. tisc putsutsally 4tlettisag 10. tise rumpromising t he inantions of 5. Any majus int eru.nl or exi ca n.sl 10 Fire last ing more el .en 10
..e l e t y s ys t em:. . the safety systres. cvesets that t'ould cause m.sssive' minuta.s:
sommun .lamage to liiant systres. l A. Onsite l
11 . Offsste (sursoun.la.x Ll.c station 4
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I i t 6CONFE NUC11AR STATION ; page 6 el 1 Ap/0/A/1000/03 l 4
F.NCl.OSlJME 4.2 l CUlDE FOX ESCAIATION .
3 Aless Site Area Emesgency Central Emergeury llrsusual Event
- 41. . tsom t u s .s i l a l a s ms (annuncia- *.. 1.ums of all-mite power and loss of 5. Any major internal or esternal 9. Imma el engincese.t malrty tr.e-a us :. ) lust. un-site AC g.ower for more than 25 events that could cause e,sssive tuse ur f a se protet t iun myst e m manutes, ts.mim.u damage to plant systems. fuustsua requirsag shut. lown I.y tethuiral aperificalsuum ( e . g .. . !
- r. . 1.uss ut all vstal on-site DC power sma l luna t ium, pe s sunser t r e s us , .
lus more lisau 15 minutes. ur issue rJusal in.a.lc.gu.ery) . !
i
- 1. Complete loss el .any feinstions --
A. Engincesed $ dirty Scatuse ner.le.1 f or plant hut sleutdown.
4 8. Fire piutection Systew 8
- 11. All alarms (annuarsators) lost lor more than 15 minutes and plant es not in cold shutdown or plant tsansient initiated while .sil alasms lost. !
I *. . H .liulugis.si cittuvats gscaler 12. 4tridental Helease al C.sses 8. Atridental kelease 2. H4Jeologisal ellturnt Trihns..il L t.an in t imes Tes linical Sperit s- Sper i l ira t iosa I s m i t s cat er.ic.l; !
satsuus inst ant aneous limits (an A. Efilment monitors detect A. Effluent monstura detert sunt ant aurous rat e whsc h, il levels currumponding tu level corresponding to I sem/ A. Camrous efflurut inatant nc- ,
enutinued over 2 hunts, would grrates than 50 mH/hr for far W.B. or 5 res/hr thyruid ous release rat e Tril nis al sranit an about I mR at the Site 1/2 hour or gecater thase at the site buuni.esy under Spra ilicat ion I smit a rhe rr.lc.1 It.uund.es y un.les avesage metrurulog 500 mR/hr W.ll. for two at tesal meteorologic al rendi- for one (1) huus.
, ieal ton.lsesons us whentver el- minentes (or live times these Lions. . i linent monitues os s.a.liulugsral levels to the Lleyroi.8) at the am.u s t us ing alci rs t these levels). sete hunndasy lur adverse 11 . 1.iqusd elliurnt sonsrutsatiun metrusology, 11 . Thesc .luse rates are projrsted Tett.nical Speril es at suu ledsr.1 on other plant p.esa- limita cas e e .lc l less I 's '
16 . These . lose rates .sse arters (e.g., kalketion irvels minuteb.
pe ujetteil leased oss ot her in t he tunt.sisament wille leak t plasil par.sartees (e.g., sale approposate lur existing r.nliation level in rontain- (tuntinued) '
ment wille leak rate appiapriate lus existing (a uset innril)
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a OGWLE NLKl.EAk STATitWi Page 7 ot' 9 AP/0/A/ loco /03 i ENCL.DS11NE 4.2 GullE tbH ESCAl.ATION 1
Alest Sste Area Emergenty General Emergese<y (busual Event '
- 12. it. tuntianasent pressure) ur are I. B. runtainment psessuse with son.c measurcJ in the envisons. confismation from effluent monitors or are measurrJ in C. EPA Protrative Attiun Guide- the environs.
lines are protested to be l exaceded outside toundasy. t l
s e. . esuguing Sec ur it y s ompromise, l's. Immeincut loss of physical control 3. l.oss of physical contral of the 12. Sca urity tiercat ur at t ra.pe rd of the plant. l'acility (Note: Consider the 2 entry or attrmpted sahutayc.
mile precaution.ary evacuatsun).
- 17. Ev.stuation of runtrol room and 6 A. Boel./esplosive or marsiirs cont rul ut shutdown systems not !
j cstatslishcil Isues lutal stat ions iss 18 . Subvre sive at t ivit y .et t e mpt j 15 minutes. A t t emple.1 i
..___.-.. ,_. . . . . . . . . _ _ _ . . _ _ _ _ _ - . _ _ _ _ .__..___.,_.4-._ ._ . . _ . . , _ _ _ . _ _ _ .
- 11. Sevcsc natusal phenu na l>cirg 14. Sevese phrnomena beisig 5. Any major internal er caternal 11. Natural phraumenen heing ex- '
i reprsirntr.1 us pa u g et t eil esperienir.1 or peujet trJ wit h events that soulit cause m.assive perscuerd ur peujette.1locyun.1 plant not su cold shutduwn. c ~ n .lamage to plant systems. usual levels:
A. Eas t h peake ge r.al er lla.ssa oprs as innal liasia. Eas th- A. Fiscs
- A. Any ca r t h.piake' ( e .u'. g .l. -
.gu he levels (>.05 g) sign artriesateen) >
, 18 . E.arthquakes (substantially
- 15 F l u. 1, luw w at es , busciranc locyond lesign leasis ). 15 . S0 year f lood or low water, suegc, :.rie be near design huraitane musse, se sa br Irvels llake ti.l.el wave) (lake tidal wave)
(aoutinneJ)
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OCohtE NUClfAlt STATION l' age 8 of 9 1 AP/0/Afl000/03 Ehe'!Jast*E 4.2 I GUlbE FOR ESCALATION !
. ~ . _ _ __ _ . . _ _ _ -_-. __. _ _ . . _ . - . . _ . . . - _ _ _ _ _ - ..
Air,t Site Area Emergenry General Imergency thousual Event I . . _ . . . . . . . . _ . _ _ _ _ . . _ _ _ _ _ _ . _ . - _ . _ . _ . . . ._
ll. C. Any tesnado meas site 4
D. Any tourricane () 14 oph) h
. _. . _ _ _ . . . _ _ - _ _ ._~ _ . _ _ . .
i en. s>thes 1.aeasJa 1.esng experienced 15. Ot her is.nz.ss els 1,ca ug expes-icas e.1 4. Oti.er plant runJitions exist, 14. Other harards locing exproience.1 ,
os psules tr l: projected witis plant. ssut in rol.1 from whatever suusce, that make ur psujerted: ,
~
shutdown. retrame of large amounts of !
A. As te s. sit a s able un lasklity radicartivity kn a sbort period A. Aircraf t crash un-6str us A.
l Airre. sit reash affecting vital ud time possible. Cure melt unusual aistrait osa t o v a t y F 18 . fisssele ampai t s f ruin wisat ever stsuttuses ley ampact us' lise. s i t as.s t iosa, over facility. [
! suus s e un 1.or s l i t y 4
~
15 . Sevese d.smage to safe shut- II . Near or on-site explus. inn. ;
s' . Enuun raplussun .lamage to down retusement fram miss43rs :
las s i s t y .silca l ing plant ur explussuu. l C. Near us on-site tuzsa us !
, .opcsatson I Ildeemalale gas trIr.sse ut 4 C. Ent s y s.1 anrunt rolicJ llam- ma gni t as.lc that t he rat esis -
. H. Entry sestu lasility coevirons mahle games isstu vital asca. persusencl.
ul tuair or ll amial le gases Entry el unsuntrolle.1 toxic g.ases intu vital airas bl cse 11. Tushine rotat ing s amt.un. us ,
E. Tushine 1.ss ius e s ausing rasissg latk ul .scress to the arra la s inse f.ansing saps.1 gelant (
penetaation. runstitutes a salety prut. lcm. shutdowes. 1
. . _ _ . _ . _ . _ ~ . . . . _ _ _ _ _ . . . . _ . . _ . _ __ . _ _ _ _ . . _
sas. Oil.cs plant aun.latsous exist 16. tit her pl.sut s undit auses exist that 4. Other plant renditions exist, l 's . Other plant s undi t ions : !
that in t ier julg ment ut the ass ti.e judgruent of the Shelt from whatever suurre, Eliat make '
Shsit Supes vi:.us , the Oper.s-- Supes visor, t he Operat ions I)ut y release of large amounts of A. Cun.ls t euns t hat wars ns in-e son:. Ihat y Engineer, the t I e ..nl i nneil) {auntinued) (run t i nue.8 ) (runtinued)
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4M' fat.E NUCl).Ak STAT 10el Page 9 el 9 AP/0/A/1000/O'l i thCLOStikE 4.2 s l Ctlli)E Fa* ESCALATION 1
a 1
- - . ~. . - . . - _ - - - . . . . .
7 Alrat Site Area Emergency Ccneral Fmergency lla asual Event -
I's; Fugsucer, the Supraintendent ul' it,. Supe r i nt en.freit ut Operatiuses us 4. radioactivity an a sleost perio.1 li. A. terasrel'w.esenema a ut p.ast of tagare'.s t ie.ns, us- ' llas- Plant ti.e Pl.ssat itausger . warrant activa- el time pohhilate. Core melt ut state aul/os lau al Ft.au.eges war s ant p e re ant i uss.s r y L ion of escrgreat y (casters an.1 situation. ettsste autleuritirm g a tiv.atsuu ut Teil.nir.nl Suppost m.,ui ture ng teams and a precaut ion-4:rutcr _ and near-sit e Cr s sis as y public nutilicat suse. II . Cou.li t luns t i..e4 a r.pe n e sia.t v H.ne.e ge men a tien a r s' . 'down undes 4 et leu e e I 6pe a e -
)
iarations.
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Enclosure 4;3 Message Format Cg OATE UM EOSACE NC.
- 1. g v 2. TSC !
C:s -
O Drin 3- '-
Telephone Authentication S
.g 5. ACC :E*fT t?rr03rNAnCN O follow-up Time Unit Emergency Condition 6. CFTSI"! NCM TICAC CN
, , Every sinute(s) Time Pickens
'(
- Time Ccones Time S.C. State Time Cther
- 7. E MPCENCY CLASS!?ICA!!0N 8. P1A.*fT STATUS 9. PRCCNCSIS (Based on Plant Information)
C Unusual Event O Stable O Escalating Emergency C Alert O Improving C Ce-escalating Emergency C site Area faargency Q Degrading O Tsreination C . General Emergency Q Not Kacun Q Not Known RA0101CC! CAL IN?cM"c't-
-10. "t" 11.' Rate of Release Curies /see 13. METECRC1CCT l O Actual Wind Speed sph 0 Projected Th of the
. Wind Direction (from) '
C 'eab na Release Duration Stability Class
- 12. Assume Ground Release Precipitation Form No 14 ESTI?'AT!S QUANT!!T CCNCENTRATION
- 19. SECTCRf5) AFTEC*!D
, y Noble Cas Cconee $ai
'- I-131 (equivalent) i Particu,la ce Pic' kens Sai
- 13. Actual - Site Soundary 2mi $ai 10mi g i :
- 16. Projected - Site 3 dry. 231 Sai 10mi
- 17. Integrated 231 Sat 10mi
- 18. Surface Radiation Contamination Estimate ,
- 20. PROT!CM*IT AC TCN 'ECCMME!!!JATTCNS:
- 1. Does ng involve the release of radioactive material
, from the station or involve the public.
I
- 2. Involves the potential for the release of radio-
- active, but no radioactive material has been released.
- 3. Does involve the release of some radioactive material from the station, but at a level below that considered a public hazard.
- 4 Does involve the release of radioactive sacerials from the station at a level at which protective action is advisable.
=
l- 21. CTEER INTCR2'.C!CH j
~
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%. 75E 1?!*l!R5E $0! .CR f; ;n:NAL OMNTS: (Report to Counties infor= stun listed in 1-9.17. O 21. M.)
(Report to State all int:r:atua. available . )
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i Enclosurg -
' 8) ATE . , _ _ _ . . ,
STATI_ Oft PFRScrudL A(10tHTAB11.ITY
- F.Pt ? T!FIC itAff. NI4tBER M select NMtE NUMBER INClaim
- Ruter TElil'lW3NE FEf fl E CROUP T1.I ErtkusE t'i tti E A.lein a s t rat ion !
Techneral Services
! C nt ras t Sesvsces: i
! R -It ac Performance: -
.- L Sau t lec t s: Sesurity Environmental: _
Training & Safety:
Licensing & Projects:
Aleinistrative Design Engineering . . _
NRC i
& rvitrs:
W " L'8 ficalth Physics: _
Visienss' Center: Chemistry: _
Eruvec flydro:
Ollie r s :
' Station Visitors.
Receptionist I.ol,by Ses u r s t y 1.ol.by _ _ . _ , FtkiE s TOTAL TEDINICAL SERVICf.S C900F --
others:
, Qu_ality Assurance t i t1E: TOTAT. Aftt!NISTRATION CROUP -
U.LT a a t jgns Station Supp ~ ort
-Division
. Opcsators On-Shift: TIHE: Station Support Division Total: , ;
Fugineers/ Start: .
Others: '
Training Center: __.
'~
, lif.W Pctsannel: --- 2 E-4
- ! til1.c
- s : -
BECINNING ENDIleG Othets Total: I
- TIHE
- TIME: TOTAL PEOPl.E OW-SITE: 7 y
- _ _ .. N Tittt::_ TOTAL. OPERATIO!!$ CROUP Unaccounted Personnel C oug Action Ta b Person Reporting Tc hplo.nc j 3 x
fl a ine rience ,
.---k >
3 l'I.sunang & flaterials: e- *
- . - - - - o o
17.E : o RFitARKS: o ti ehinical Maintenance:
System flatntrnance
! Suppor t :
S..l.st.it ion ti.eintenance: ,
oi l.c e s :
e TIME: TOTAL MAINTENANCE CROUP
, AP/0/A/1000/03 fx DUKE POWER COMPAhT
( OCONEE NUCLEAR STATION
{
ENCLOSURE 4.5
_ PLANT STATUS (Circle) OCONEE NUCLEAR STATION UNIT Unusual Event - Alert PLANT DATA AND STATUS DATE Site Emer. - Gen. Emer. IhTORMATION TIME Control Room TSC HPC OSC 9
\v By
[) Title Q-) -
1 l
l
OCOf1F.E t,UCl,EAlt S1 ATIO!!
EMERGENCY ORGANIZATION RECAI,1, NORilAI, WOltKING llOllRS Enclosure 4.6 IINIT OPERATING El1GINEER ' -
SillFT SilPERVISOR f HRC (RED Pilot 1E)
{
v l Sill'ERifiTEf3 DENT OF
' OPERATIONS 4
OFFSITE AGENCIES Y
ASST. STATION STATION ttANAGER CRISIS MANAGEllENT HANAGER f ORGAf31ZAT10tl Y ~~ ~
lf lf SUl'ERifl'IEf4 DEN i' O -
,UPERINTENDENT OF ';UPERif3TEtil)EN T OF TECll. SERVICES ADfitillSTRATIOl3 MAINTENAllCE
-h llealth Physics --k :nvironmental i I&E Administrative Services
-> re"-nce i.icens inR .,na y NRC Resiaent
-> sec l,.,,, , c.,1 nainten.,nce
_P Sarcty and
_p 1,., i n i ,,,..
Pro j ec t s Inspector Pinnning and
_p Che,.ist,, - naterinte
_p cen t ,.,c , Se , v , .e, nabcock & Wilcox Representative
Ef!EP.G"..'1CY ORGAtitzATION RECA1.L ,
(BACKS:iWT, WEEEEf3DS, llot.IDAYS) ,
Enclosure 4.7 OPEIIATIONS DUTY c' ENG I N F.F.R SIIIFT SUPERVISOR NRC (RED PIIONE) g I D SUPERINTENDEt3T OF s
-v:
"" * " ""S
-f STATIntl .tlAtlAGER CRISIS tlANACEtlENT ORGANIZATloti D OFFSITE 2 <
AGEllCIES
~
ASST. STATIOtt
' tlAtlAGER
" ^
kNbIlbfUfb NbhlkkS
,_ SUI'ERIFITENDENT OF ~g V . tlAlt!TErlANCE F Planning 6 tialetlal SWITCllBOARD
';UI'ERINTENDErlT OF ADilINISTRATIOtt
- Security at the Switchboard will reen11 Duty Per onnel ansIr,ned to varioun nections.
TECIINICAL SERVICES tlAltlTENATICE ADtil HIS IR ATIOri
-f IIcal th Physics ~f , , , 'j ["
INE Ailm i n . Services ol IL I at g l'e r f o rma nce Biolorint L !!eclia n lea i f fla liit ena nc e 3 1,1 censing and NRC Rentdent V Projects Innpector k Itabcock 6 f Wilcox Emerr,cucy Prep.
I'nn rel t nn t n r .
\ .
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~
(
i Form SPD-1002-1 INFORMA50N G
DUKE POWER COMPANY (1) ID No: AP/0/A/1000/04 PROCEDURE PREPARATION Change (s) N/Ato PROCESS RECORD N/A Incorporated Oconee Nuclear Station (2) STATION:
(3) PROCEDURE TITLE: Emergency Action Level (EAL) - SITE AREA EMERGENCY (4) PREPARED BY: k DATE: 8 [
(5) REVIEWED BY:
V DATE: J9 A f '
/
Cross-Disciplinary Review By: N/R: $
(6) TEMPORARY APPROVAL (IF NECESSARY):
By: (SRO) Date:
(Oj By: A n Date:
(7) APPROVED BY: j Date: 3 h (8) MISCELLANE0US:
Reviewed /J.pproved By: '#7#
~l;;7 7
_ Date: _7/e A
//
Reviewed / Approved By: Date:
! O
, FORM SPD-1001-2 DUKE POWER COMPANY
, NUCLEAR SAFETY EVALUATION CHECK LIST ON (1) STATION: h UNIT: 1 2 3 pTHE)t: gh .
k (2) CHECK LIST APPLICABLE TO: N/o /AL/ 5 /> a m /d /4/
/ / '-l '(
(3) SAFETY EVALUATION - PART A The item to which this evaluation is applicable represents:
Yes No # A change to the station or procedures as described in the FSAR, or a test or experiment not described in the FSAR?
If the answer to the above is "Yes", attach a detailed description of the item being evaluated and an identification of the affected section(s) of the FSAR.
(4) SAFETY EVALUATION - PART B Yes No / Will this item require a change to the station Technical Specifications?
If the answer to the above is "Yes," identify the specification (s) affected and/or attach the applicable pages(s) with the change (s) indicated.
(5) SAFETY EVALUATION - PART C As a result of the item to which this evaluation is applicable:
(0
' Yes No V Will the probability of an accident previously evaluated in the FSAR be increased?
Yes No / Will the consequences of an accident previously evaluated in the FSAR be increased?
Yes No / May the possibility of an accident which is different than any already evaluated in the FSAR be created?
Yes No 7 Will the probability of a malfunction of equipment important to safety previously evaluated in the FSAR be increased?
Yes No / Will the consequences of a malfunction of equipment important to safety previously evaluated in the FSAR be increased?
Yes No V May the possibilit'y of malfunction of equipment important to safety different than any already evaluated in the FSAR be created?
Yes No Will the margin of safety as defined in the bases to any Technical Specification be reduced?
If the answer to any of the preceding is "Yes", an unreviewed safety question is involved. Justifyj he conclusion that an unreviewed safety question is or is not involved. Attach additional pages as necessary.
(6) PREPARED BY: Mh k ,, DATE: d 9 /7/
(d\
(7) REVIEWED BY: DATE: 3
/
(8) Page 1 of
/
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4 AP/0/A/1000/04
. Page 1 of 3 g DUKE POWER COMPANY s_- OCONEE KUCLEAR STATION -
1 EMERGENCY ACTION LEVEL (EAL) - SITE AREA EMERGENCY
1.0 Symptoms
The symptom of a Site Emergency will vary according to the initiating conditions. Enclosure 4.1 defines the different conditions and gives specific symptoms of each of the same.
2.0 Immediate Action 2.1 Automatic - NA 2.2 Manual Date/Name Time 2.2.1 If Hazardous Radiological conditions or the potential for such conditions exist, initiate a site assembly using Station Directive 2.9.1 record results on Enclosure 4.4, Station Personnel Accountability. Take immediate remedial action to insure the health and safety of personnel, minimize radiation and contamination problems, and minimize damage to the plant. Record actions taken on Enclosure 4.5,
('~'} Plant Data and Status Information.
V 2.2.2 If radiation or contamination is involved, dispatch onsite monitoring teams with necessary communication equipment to s
assess and recommend methods of controlling or containing radiation and contamination. Record action taken and results of survey on Enclosure 4.5, Plant Data and Status Information.
1 2.2.3 If the possibility of an offsite dose exists as a result of this event, evaluate the need for an offsite dose calculation.
NOTE: AP/0/B/1000/07 is for the Cont'rol Room use only for dose calculation. The Health Physics Section will use H.P. procedures if they perform the calculation.
2.2.4 Determine from Enclosure 4.1, Site Area Emergency Initiating Conditions, the most descriptive initiating condition for the event.
2.2.5 Activate the Technical Support Center (if not already activated). Use Enclosure 4.6 or 4.7, Emergency Organiza-
- ion Recall.
, Have the Station Manager (or Emergency Coor-dinator alternate) to activate the Crisis Management Team.
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s 4
AP/0/A/1000/04 Page 2 of 3 Date/Name f' 's Time 2.2.6
( ) Appoint an individual to be responsible for keeping records
\-
of the emergency and to notify offsite agencies and company
. personnel. .
2.2.6.1 Notify company personnel and offsite authorities of the nature of the plant conditions using Enclosure 4.1, Site Area Emergency Initiating Conditions, as a guide for notification. Refer to the Emergency Telephone Listing in the Implementing Procedures Manual for the telephone
. number that corresponds to the notification code under each initiating condition.
2.2.6.2 Enclosure 4.3, Mesrige Format, is to be used in notifying staff anu offsite authorities for both -
i initial and followup contacts. Offsite notifi-cations should be accomplished within 15 minutes of the identification of the EAL. Establish update time frame with offsite agencies.
2.2.6.3 Record actions taken and events as they occur on Enclosure 4.5, Plant Data and Status Information.
, The Technical Support Center will be responsible cs for notification of offsite authorities and for
( ) recording events as they occur until the Crisis
\s_ / Management Center is fully operational either nearsite or remote from site. Once the Crisis Management Center is fully operational, offsite authorities will be contacted by the Crisis Management Center. The Technical Support Center will continue with record keeping and plant updates to the Crisis Management Center.
2.2.7 Technical Support Center is fully activated and operational.
2.2.8 Operational Support Center is activated and operational.
2.2.9 Evacuate all non-essential personnel per Procedure AP/0/A/1000/10.
, 2.2.10 Start the Control Room Ventilation System if radioactivity 2
exists outside the RCA.
2.2.10.1 Have Technical Support Center personnel read dosimetry every hour, Record readings d
on Enclosure 4.8, Record of Dosimetry Readings.
-~s 2.2.11 Insure that Senior Members of plant staff onsite are
( ) available for consultation with NRC on a periodic basis.
\_ /
- 2.2.12 Insure that an individual is dedicated to periodic briefings with news media. This individual would be a member of the Crisis Management Team. -
, AP/0/A/1000/04 Page 3 of 3
! Date/Name Time n'
'~-
2.2.13 Proceed through use of the proper procedures to bring the plant to a stable, safe condition.
3.0 Subsequent Action 3.1 When plant conditions warrant, the Site Area Emergency should be de-escalated or escalated to the next emergency action level. In the
] event that close-out is warranted, de-escalate to an Unusual Event.
NOTE: Use Enclosure 4.2, Guide for Escalation, to identify the
> proper EAL if a change is warranted. .From the t.ime a new EAL is identified all offsite authorities should be notified within 15 minutes.
3.2 In the event that Protective Action Guides need to be issued to offsite authorities as identified in AP/0/A/1000/06, this event must be
! escalated to a General Emergency.
NOTE: Only the Emergency Coordinator and/or the Recovery Manager 1 may issue PAG.
3.3 De-escalation requires the concensus of the Nuclear Regulatory Com-mission and the state of South Carolina.
O
\ !
4.0 Enclosures J
4.1 Site Area Emergency Initiating Conditions 4.2 Guide for Escalation 4.3 Message Format i
4.4 Station Personnel Accountability 4.5 Plant Data and Status Information 4.6 Emergency Organization Recall 4.7 Emergency Organization Recall 4.8 Record of Dosimetry Readings i
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s OCONEE hllCIEAR STATION Page I of 7 .
AP/0/A/IDOO/04 ENCIDSukE 4.1
- SITE ANEA l.NEHCENCY Site Asra incagency Oconee Naclear Station Final l u s t i.e t s us Cun.fi t s..n m Symptoms Safety Analysise Nepurt Section 14.1 Emergency Proce. lure /Durument e . kn..wn lusa el roulant aerident kr ctor trip on low pressure; 8.Pl ES Accidental Depressurization of tl.e E P/0/ A/ Is00/04 g e r.s t e s than m keisp pump capa- astuatanes; itPI ES actuation; reactor kractor Coulant System; 4.ums of El*/0/A/1800/06
- a say (any leakage > 500 gpm). 1.u n iding atmospl.ere s esdicat iossa of Coulant Ars.ident; Partial I.ons of I high psensure, lusmid s t y , et c. ; kractor Cuolant flow Nus i l i t .s t e un Cuele l*6 Il-12 cont issued lumm ul kC inventusy-nu presmierlaer level; i.i gl. s e.st t ur 1,uilding sushp inlication; leigh scarter coulant pump vibt.et ioss-isodicat ing vui.ls su RCS; liigh reactor 4.uil. ling presmuse
- _ . - -. -. - - - - - ~ . .
/. Isega a.lc.I ros e wills possiiste loss Subiouling munitor and higli incure Complete I.uss of Forced Heactor EP/0/A/1800/04 ul coulat.le geometry (in.licators thesmucouple scadings; Tg 8. T Coolant Flow,ti.sjur Heattur Coolant EP/0/A/1800/06 ml.uulig inc lu.le i nst r umental isui to .tiverging;SATmonitorindica[esno System Pipe Hupture: Partial Loss ut EP/0/A/1800/II
.le t re- t iss.a.lc.gua t e a us e s uolisag, mula uuling; clienist ry results oss Reactor Coolant Flow EP/0/Afl800/27
.uulant attsvity n.8/or ralio- sample s c pscat indicate faile.1 luel; attivity levels). reattur I.uilding klA's high alarm, klA's high alarm, RIA's 2, 3, 4, 5; Not i l it a t ion Cu.le : 1-6 Il-12 low Heastor Coulant flow .
f I. H.ap s al f.e s ins e to muse t h.sn 10 Nc.ss t ur t r ip oss low premmasse; psessur- Arcident.nl licpsessuriaatsun of Maiss EP/0/Afl800/04
. :.a c generat ur lui.es wit h loss tare low icvel al.ssm; uu.le r vul t a ge Steam System; Steam Generator Tube EP/u/Afl800/14
.ul ull-mile powes (e.g., arver.sl .s l .a s ms ; use m.siis Ice ler I.uses ; -t ras.sfer kupturc EP/0/A/1800/16 f.un.ls e.1 gym ps im.a s y s u mes on.la r y ul musiliarses tu standby 1.uses; cun- EP/o/A/8800/17 ,
I c.. It astr). tsnue.1 loss of NC inwrntury lseyoned llPI *EP/0/A/1800/29 ti..t i l is at suu Co le: 1-6 11-82 sap.scaty, pressusizer level decreasing
..- _ - . . . ' .EP/0/A/1800/08
. . . - . . . - , _ _ _ _ _ - . _ l
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i OCONLE letX:1.EAN STATION Page 2 of 7 AP/0/AfI000/04 LNCIDSURE 4.! ,
SITE AkEA EtlENGENCY
. ~ _ . - _ - . _ _ _ _ _ J__._ __ _ .. _
Sa t e Asca Eancs grus y Grance Nuclear St ations Fisi.nl lus t i.at ing Cos lit ions Symptoms Safety Analysis keport Section 14.8 Emesgency l'rateduse/lkst eement
- 4. IM stram line a cab witta gre.st- A. 1) laccreaming reactor coolant Steam Generator Tulee kupture: Acci- LP/0/A/1800/04 #
cs 4 8:an psessuse, PZH Icwel, T alental !)cpressurization or keactor kP/0/A/latx)/08
- 2) klA 16 os 87 and 40 taigE" Conlant System EP/0/A/1800/ 4 7 {
A. *0 gg.m psim.ery to secun.l ry
, al.orms leakage 3) Stal ilizcal Pik level use llPI initiation. .
- h. 50 gem primasy to scron.lasy is . 8) AI! ut al.ove plus clienist ry Ic k. age u se.1 i n.f i a a t i on o f remnits positive on laile<l luct .l m. age. fact analysis
- 2) Possilste liigla kcactor fluilding Nut ilis'at sos Co.le : l-6 Il-l'. pressure and tempesaturc
.. l .. m of ull-mate powes and Roma Cunt inneal aus.lcrwultage on main Iceder I.ons of Coulant,Arcident; less of Er/0/A/1800/14 g ol un-s e l e AC power lur image l>umes; scalignerait of CCW-8 for oil-site power to Stations EP/0/A/1800/16 ,
et..in 25 menntes. ga svit y flow to Kcowcc tailrace; LP/0/A/1800/25 load steed of all non-essential loads EP/0/A/1800/29 N.eL il is at iun Co le: 1-I**l- 11-12 in prep.asatiou for emergency start ut Ecowce fly 41ro St 44 iosi ased 4 r.susler to st.an.lley 1,nses.
.. 1.n = = og all wit.el on-site l< i:ent inned IC t ruulate alasms in Contrul EP/0/A/1800/16 p..wc r fut mosc t asan 15 minutes. Hoom; I)C t s oula t e .s t a s ms osa Eme r gency EP/0/A/8800/31 Power Swittleing 1.ugir; 1.oss of samme Nul e i e s'as son Co.le: 1-i 15-12 i:ompu t e r Isa.lia a t ions
.a - , . - - - . . iww -. . .w%...-%,_. ._. .
. _ - - ...-w. -.-.w.
- .. . - - . ._. - . - . ~ . .- - .. .. - . -- . _ - - . - . . . . . _ - .-- - . . . . . ~
f
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l i OCONt:E isVCI.EAN STATION Page 3 of 7 AP/0/A/1000/04 i ENCIDSLlHE 4. 5 SITE ANEA Ettt.HCENCY Sstr Are.s imesgency Oconee Nuclear Stations Final lustiassng Con.litsonn Symptoms Safety Analysis keport Section 14.5 tw rgency Prose *1usc/Dosument
- t. 4'omplete lumn of any lussot iossa ,
- nce.lcal f or pl.snt hot s hu t downs . In.steilit y to estal,limla escrgency
$ lee.lwater uf auxiliary servite water Notilis.stion Co.le: 1 -in Il-12 flow HPs, ES Channels Trip with lailuse of Hm. Trip funeLion.
- . (highly improtsalale).
e HPS, ES Channels Trip witis failure al !
ii . Tsansient rreinerang upcsation of a.i.ut elown symi cou wi tti f ailure to km Tasp function (laighly improteatste).
mssam (s out inucal pows a genera-
! I s oes lent seu a us e el.sm.sge immac li-
, .st c ly ru s.lcut ) .
- l
- Nut il ic.st ion Ceule
- 1-6 11-82 ,
, 9 fl.s gos .iam.sge to sprut luci A. I) . HlA's 2, 3, high alarm fuel ll.snJting Arrilent; Tosnalo }.P/0/ A/1800/ l')
- 2) Csmeous in.licat ion ut s aili- tiimmile Impact Spent Fuel Analysis EP/0/A/th00/24 A. In santainernt (e.g., water .stion from Htt CtlS. EP/0/A/1800/23 lu s s I,c l ow l asc i Irvel)
I It . 1) HIA 6 leigh al.stm in Spent Fuel ,
Is . In Fuel ll.sn.Iling liuil ling Puol ;
y (SFI') (e.g., l.ssgv object 2) HlA 41 (SFP gan) i
. lam.s ge n luci)
~
N..t i t irat ion Co.le: 1-6 11-12
-n
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i OCONEE NUClf.AN STATiuN Page 4 of 7 AP/0/A/1000/04
, ENCIDSUNE 4.1
- SITE AREA ErlEkCENCY i
l . . - . . . . _ _ . _ . _ . . . . _ _.
- . s t r Asca Imergruay Oconee Nuclear Station Final lustsating Cunlitions Symptoms Safety Analysis Nrport Section 14.I Emergency Pruredure/lkernewnt tu, t s e e a umprominisig the functions Visu.s t clemervat ion; f i r e ele t ec t or i ssdi- AP/0/Af l000/05
. ut a l.c malcty mystems. s'atsuns am listed in Teshnical Specili- Pre-Fis e Plan i s as iosis i N..tilir.ettun Code: l-ta Il-12
- 18. A l l .s i .s s es (anunuriators) lost Visu.sl chsesvation of event EP/0/A/8800/14 los nous e t h.su l's misint em anal EP/0/A/1800/Ife p l .s u s is seut s es cu l .1 minu t dows EP/0/A/IB00/29
, ee n p l .su t t s assa i en t initiated ,
EP/0/A/lH00/31
! whste all .elasma lost.
N..I e i a s .s t s on Co.le : l-de 15 - 8 2 If Asti.lcutal Hele.sme ut C.smen A. Elfluent musiiturs detect levels Waste Can Decay Tank Hupture; 1.4. psi.I EP/0/A/1800/24 cursemponding to greater than Waste Storage Tasilt 1(up t u s e; i.oss et ,
50 mR/hr for 1/2 leuur or greater Coulant Accident th.sn 500 mH/hr W.B. for two minuten (ur live timeu theme levels to else thyroid) at alie site houndasy for adverse meteorology.
II . These dose r. stem are projected h.sme.1 on other plant p.anameterm i (e.g., s adia t ions level in sun-
, tasument wit h leak rate appro-priate for enabling containment psessuar) or are measuscJ iss C..s.t , ss, sed .
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OCONEE NUCl. EAR STATION Page 5 of 7 AP/0/A/1000/04 ENCIDSUHE 4.1
- SITE AREA EttERCENCY Sete Arca Emergesuy Oconce Nuclear Station Final luitiating Cun.litions Symptoms Safety Analysis Neport Section I4.1 teesgency Procedure /thatument time cuvisons.
, =
- 0. EPA Protective Action Guidelisses are projectcJ to 1.e exceeded out-mide tise site 1,oundary.
i Bl. Imiaincut loss ut physical con- Subves sive activity; determissed by Station Security Plan a sul al the plant. Secursty Supervisor; Insuincut loss
- t us Cont rol f(ouse and Auxiliary hieut-
- Nsetilscation Code; l-6-7-8-11-12 ilown Pana t h 5
lt . :;cve s e na t ur a l phesa.inien.s 1.c i ng A. Scimmic Trigger Statalarm Turnado Hissile Impact, Spent. Fuel EP/0/A/IB00/09 c apes s ene r.1 us' ps u jet t e.1 wi t h Analysis EP/0/A/1800/10 plant uut in tul.1 s. hut eloon 15 Visua! Ob.crvation EP/0/A/1800/15 EP/0/A/1800/25 A. Ear t h.psake great er t hars SSE C. Visual ohnervations or tieteur- EP/0/A/1800/19 levrls. ological iss. lit at ions iss Cont rol EP/0/A/1800/07 Ituum it . t lu.ul, low wat er , hass ricane aus gc, neit he greater Llsan
.lc u i ges levels or I.silure of 1.s ut e,4 4 inn el vi t al ceguipsacut
.s t lower levels. ,
I N..t i l s e .st iuss Code : 1-6 15-12
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OCONEE NUCilAR STATION Page 6 of 7 AP/0/A/1000/04 ENCLOSUNE 4.I i
SITE AREA EMERGENCY .
Se t e Arca Energrucy Ocossee Nuclear Stat ion Fissal luit s t ing Co split ions Symptoms Safety Analysis Repost Section 14.8 Emergesary Procedure /lbtuacut s ', . set tie r te.se.s r.in I.cing experiented A. Visual Otscrvations Turnado Missile Impact, Spesst Fuel A. EP/0/A/1800/2, EP/0/A/ tdoc/9 or prujerte.1 witia plant.not its Analysis ;
sul.1 sliutdown. 11 Visual Oleservations II . EP/0/ A/1800/10. EP/0/ A/ IMOO/ l's j A. A i s rr.s i t vs.sals atletting wit- C. Visual
- Clsemistry Hemults C. EP/0/A/lH00/23 EP/0/A/IBu0/J's j .sl minuttusem Isy impact or of samples iss areas. i Isec.
it . Seve r"e l.smage t o ha f e blust-slown e .psipmesst Isom missilen ur capiumiuu i s' . Futry ut un4outsullrd llamm-alele g.such i sit as wit.al area. ,
Entsy of untoutsulle1 toxic gauch into vital asram wiscre las k ut as tems to Llic area aunstitutru .s m.s f et y prulsica.
N..s i l i s a t i on t'u.le : 1-6 18-12 i s. . Otlics plant sonlitions exist As eli terte.1 lay Emes gency Coordin.st ur.
As dictated lay Plant Con.ls t inum s i.a t in LIc .gu.lgement of tisc
'd. : I t Supesvimur, tasc Opesatiussu Ousy Esigenres, Blie Superintesadent
..I Oprsatiuns os L lic l'l a n t H.sua-Ecs w.setant at 4 iv.st iuss ol' cmer-I genry s out ers and musait ur nsag tc ms an.1.a p:re aut iusi.sa y pulia ic n..titisatinn.
N..t :1 ir.si s on Co.le: l -t.- / 12 4
. _ _ _ _ _ _ . . _ . . _ _ . . . _ - _ . _ . . _ _ . . _ . . - - _ . _ _ _ . _ . - _ _ _ _. _ _ _ _ _ . . _ _ _ . _ _ _ . ~ . _ . . . . . . . . . . . . . -- . _ _ - - - . _ . _ - _ _ . _ . _.
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{ 'i OCONLE NUCl.EAN STATION Page 7 ol i AP/0/A/I000/04 ,
ENCIDSUkE 4.1 SITE AHEA EtttkGENCY [
r b
Sete Asc4 Inicageury Occuee Nuclear Station Fional .
i luis sating a:on Is t sous Symptomm Safety Analysis Report Section 14.1 Emicrgrury Prosedure/th umu.ut i St. Ev anation of toutrut suons 4ed An .liretted lay Emergency Coordinator EP/0/A/1800/12 a ..ut s ul of sleut down systems not anil Slai t t Supervasor. i v6 8 41.l i sticJ l e uas local stations }
in 15 mountra. -
I N..t a t e s .it s un Code : 1-6 11-12 }
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OQmEE NUCl.EAN STATION l' age I of 8 Al*/0/A/1000/04 ENCL 31SUkE 4.2 .
Cull >l: 60H ESCAI.ATION 4
Se t e Area Fmergeset y Grueral Emergeicy unusual Event Alert
- 1. Known loss al roulant accidcat 4. Other plant conditions exist, from 5. Eareeding either primary / secondary 3. Espid tailuse of muse tisan su ger. ster tian makeup pump capa- whatever source, that make release leak rate teclailral specificatious steam generator tut.cs (e.g., ,
eity (any leak.sgc.) 500 gpm). of large amounts of radioactivity ur primary leak rate terlinical several hus dred spm pa im.is y to in a short period of time possible. speritarations. (> 10 gimi total secon.14 y Icak rate).
Cure melt s it ua t ions. P/S leakage) j 5. l*rimary coulant leak e.ite gerat A. Primary - re< pairing shutdown er than 50 ggen.
B. Primary to secundary Unit I>
0.30 gpm
_........n __ ._ . . _ _ _ _ _ _ _ . _ _ . . _ .
. ' . llegralc.Beusc with possitale loss 2. 1.uss ut 2 or 3 fission psodurt 3. Fuel damage indscation: 1. Sevese loss of fuel lad. ling:
ut roulabic grometry (in.litators 1.arriers with a putential loss el [
j t.l.uulit ine:lude instrumentation third I.arrier. A. Iligh coolant .ictivity saisiple 9. Coolant Peassp se i xie r e- li Joseg g tu .le t ec t in.edc.gnate sore conl- (e.g., cureciling coolant t etti- to luel tailusc.
ing, i no l .an t .ntsvity an.1/or nical specific.itsois for iodine ,
s..liu.estivity 1:vels). spike). (Iligh Nc. actor Coolant Sampic Activity).
- 1. leapiel f.eiluse ut more thase 10 2. 1.nss of 2 on 3 fission product 5. Exceeding citi.er paim.iry/secondasy I. H.apid failure of more ti..in su sacan genesator tubes with loss learrien s .sith a potent ial loss of Icak sate technical specifications steam generator tut.
to gge total secundary Icak sate).
leak, rate). 1*/S leakage) routinued: untinued:
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OCONEE NUCLEAR STATION Page 2 of 8 Al'/0/A/ID00/04 ENCIDSI*E 4.2 i Cull)E FON ESCAl.ATION Site Ase.s E=cagensy G :secral En.crgesscy Unusual Event Alert
- 5. A. Primary-requiring shutdown 5. Pramasy ruolant leak rate gecat-er Llian 50 gge, 16 . Primary to secondary Unit >
0.30 gge
- 4. Ivic steam line lascak with great- 2. loss of 2 or 3 fission product 5. Exceeding either prim.sry/s,erondary 4. Steam line barak with sigusta-e r t h.en barriers with a potential loss leak rate testiusral 6peraficataons caut (e.g., gseater than lo gg.)
of al.iral barrier. or primary le.sk' rate technical primary to serr.nelasy Ir k saar i A 50 gpm psimary to scrunlary specli ira t s os.a . (> 10 glius total o f NSIV asa l t uut t insi.
Irakage 1*/S leakage)
IL 'au gpm pa sm.as y t o secondary A. Primary-requiring shutatowss Ic.ek.ege and isidicalion of luci 4.ima ge , 15 . Prissary to accendary linit I) 0.30 gpm
._ _ ____.. . . _ _ _ __. _ _ _ _ . . _ . _ i
'n . l...ss ut oil-site power and loss 4. Other plant coseditions exist, 7. loss of off6 site power or loss 04 2. Napid gross failuse of one stram '
ul un-hite AC powes for more f rom wisatever source, t h.s t oss-sit e AC power capability. generator tulee with la.as ul utt-t ie.us 25 ma nul es, make selease of large amounts of bite power from all suustra radio.ntivity in a short period A. 'I.oss of off-site power (OTSC Tabe) of time possible. Cose melt s a t isa t ion . II . l.oss ut on-mite AC power 10. Congolete loss at .sil f uu* t sons '
for plant told shutdown.
continued: runtinued:
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OCONEE WilCIE.Ak STATION page 3 of 8 AP/0/A/1000/04 ENCIDSUWE 4.2 i GUIDE FOH ESCALATION
~
Site Ase.i 1.mesgenty General Emergency Unusual Eveset Alert
- 9. Loss of engineered safety feature 7. I.oss of all-site p we, .d or fire protection system function less of all on-ss te AC giowre requiring shutdown by teclinical for up to 15 m6nutes (Russ s.1 i specifications (e.g., malfunction, Erowre not credshic so not '
personnel error, or procedural considered). !
in.sJequa cy ) . , ,
I
power f or mos e t ie.sn 15 minutes. tross whatever source, that make or fire protection system function
. selease of large amounts of requiring shutdown by technical radioactivity in a short period specifications (e.g., m.situnction, of time possible. Core melt personnel error, or prnacdural ,
. situation. inadequacy).
l
- 1. trumplete loss of assy fus:(tions 4. titlia r islant con.litions exist, 9. less of engineered safety feature 10. Complete' loss of all f um t iuns
- needc.! for pl.snt hos shutdown. from whatever source, that ude or fire g rotection system f unction for plant cold shut.luwn. [
sclease of I.orge amounts el requiring shutdown by technical i radioattivity in a sl. ort period specifications (e.g., malfunction, 14. Ptost or all alarms (annuncianne ) l l ut time possible. Core melt pensonnel errur, un prosedural lost. t
- situalion. inadeesu.a ry ) . [
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OC6 NEE hilCl. EAR STATibN Page 4 ul 8
, AP/0/A/lUOO/04 LNClinSilkE 4.2 CtJIDE FOR ESCAl.ATION Sste Aera Emcagency Ccucral Emergency thtusual Event Alert
~ . _ . . _ _ _ _ . _ _-...__ ;
M.* Teansient. s c gua ra ng uperat ions of 4. Other plant conditions esist, 9. less of engineered safety feature ll. Fa s tus e of t he reas t us ges ot e a -
, shut.lowes systems with failure to laum whatever source, that make or fire protection system function t ion s y s t em t u insliate an.1 .
saram (suntanned power gesieration selease of lasse amounts of requiring shutouwu by terhuical tumplete a arran woesth* brings 1.u t sio acae .lamage immediately r.adioactivity in a she.t period specifications (e.g., malfunation, ti.e reactor subcratical.
rvi.lcut ) . of time possible. Cure melt s personeel ers or, or pa uce. lural situatson. 'ina.lequacy).
- s . ft gue .l.smage to speset d isc i 2. I.oss of 2 or 3 fission product 4. Ahnurm.sl coulant temperatuse anJ/ 82. Fuel damage arcsdent with 1.arriers with a potential loss or pressure or al, normal fuel release of radicartivsty to A. fu contain rut (e.g., water .
t ee.peratures out si.le of techairal containment es fuel han.Ilsus
, loss heluw incI level) specification limsts (>2500 psig). building. '
it . In Fuct al.au.lling linil.lisag ,
(St P) (e.g , , lasse objeat i
.lamagra inct)
- 10. t'e s e rompa aneis e ssg t he fuurtions S. Any major intersial or external 10. Fine lasting aeore than 10 miseules 13. Fire potentially affraseng r ut the salcty systres. events that could cause massive safety systems, aimanon damage to plant sysicos. A. Onsite i S. Ofinite (suerounding the Station)
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OCONEE NUCLEAR STATION s Page 5 ol' 8
\ Ap/0/A/1000/04 ' '
ENCI.0St*E 4.2 -
3 i
, GUIDE FON ESCAl.ATION s \ t .,
Sake Asea imergency Genes.sl Emergency Unusual Event Alert ,.
si. All%Imens (anuunciatuss) lost 5. Any major internal or external 9. Loss of engineered salety feature 14. Host,os all alasms (aununci-f or ' muse t han 15 minutes and events that could cause massive or tire protectiusa systra lunction .itoes) lost '
plant is uut an s old shutdown s ommeoss' damate to plant systems, requiring shutdown by technical us plant tsansient initiated specifications (e.g., mitfunction, winste all al.sim:. lost. '
personnel error, or procedural .-
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inadequacy). ,
1
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- A. Engineered Safety Feature w
A II . Fire Protection System II. Ae ridental Helease of G.sses 1. Accidental Helcase ,
- 2. Radiological ettluent Terhuical 6. liigh radiation IrveQ us higli
. V g Specification limits exreceled: ais tiorne contamination whos h A .' Elliucnt munituus detect A. Ellluent mupilots detect level indicates a sevea r ih gr.e.l.at son levels aussespuuJing to consespasaling to I rem /he V/B. A. G.ameous eft'tuent instantaneous in the control of radio.attive
- greatre thasi 50 mH/hr for or_5 res!lia altsoid at the site release rate Technical Speci- materials (e.g., incre.ase ley
- 1/2 1.nus na g e ra t e r t h.sn 500 hounda ry ~under at tual art rur- ficatiosi limits excreded for a tactor of 1000 is direct i
r t/lis W. ll . tur two minutes a
ological ronditions. one (1) leuur. rael 4tiosa readtags). x
,(os Isve L surs these jewels tu the thyroid) at the site B. Liquid ef flurnt content ration 1.uuud. s y f or . adverse meteor- '
Teahuical Specification limits s ulogy, , exceeded fos 15 minutes.
it . These dose satra are prisject- d * 'k' l r4 leased un other pl. ant p.a ra- s % '3 I
l
=ctres (e.g. , s adiat sw. level in tuniainment uith leat Y% L'
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- s ie pp...psiaic nor esis,iing runtasumcut peonisse) or ase c -
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410tH6EE NUCl. EAR STATiool Page 6 of a 1 AP/0/A/1000/04 l ENCllEURE 4.2
- CulDE FOR ESCAI.ATION l
i j hele Area Emesgrury G neral Emergency Unusual Event Alcat i S .* C. El'A l'a utes t e ve Act ion Guide-f lesses ase projected to lee , ,
} cu re:Jed out side time site l 1.ounda a y .
1
. ._._. i j . 3 8. Immuinrut loss ut playsical son- 1. l.oss el playsical control of Slee 12. Security tiarcat or attempted 16. Ouguing Security asumpromise.
- ts.I ut alie plant. facility (Note
- Consider Elie entry or attempted saliotage
- 2 mile precautionary evacuation). t A. fluels/ explosive e.r missiles i
- ^ B. Suleversive activit y at tempt-j ed.
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OCONEE NUClf. Alt STATION page 7 of a ;
Al*/0/Afl000/04 EleclasukE 4.2 GulDE FtMt ESCAl.ATioli
. . . . _ _ . _ _ _ _ _ __ . . , . . . . y Sete Area E=cagracy General Emergeney linusual Event Alert !
j
- 14. Srvere saat us al phraumena being 5. Any enajor intessoa! or esternal 13. Natural pleenomenon 1.cing ex- 17. Severe natieral piernumen.a I.cing l capesienar.1 or projected wille events that could cause massive periene.J or projected I.cyond emperienced or projested pl ut not in told shutdown. e ommon Jamage to plasit systems. usisal levels. j l
A. Fires A. Any cattle guake ( .05 g A. Eastle.gesake gscater than !
Jesissa acceleratione) Operational Basis Eastleginat -
Is. Eastinen hes (substantially levels ( .05 g) 8.cyond design basis). B. 50 year flood or low water, H. Flood, low wates, barese' n. F hurricane surge, seittae hist ge, seit lee saca r des a gse (lake tidal wave) levels (take tidal wavr)
C. Any tornado near site 11 . Any hurricasse ( 74 mph) j l*s, estlier 14z.ss.ls being experiente.1 4. Other plant cosidit iosis esist , 44. Other leazJrds being expericosted 18. Other hazarels being expcrecia.W '
os projesacJ with plant not in Ison whatever source, that make or projet-ted: or projected: !
s ol.1 sleut down. sclease of large amounts of ,
j radioact ivit y ise a short period A. Aircraft crash on-site or A. Aircraft crash on 14cilely [
A. Airrrait ca. ash affecting of time possilate. unassual aircraf t activity l vital sisuctiarcs by impact over facility. B. Missile impatts fium wIi.ites.s j us lisc. ' source on fat-ility.
. B. Nea'r vai-site emplosiosi. l Is . Sevesc . lam. age to sale shut- C. Know emplosion Jam.ege en to -
i down c.pa s parut trum missiles C. Near er on-site touic or cility affecting plant opre e- [
un explosson. llammahle gas rete.ese of a tion, j
! m.a gni t anic t ie.a t f le re4 Lens i pc sessaie! .
l e ..na a sencJ: runiisaucJ anontenurJ !
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OCONLE NUCIEAlt STATION Page 8 of 8 ;
AP/0/A/1000/04
- ENCIDSt*E 4.2 ,
GilllE FOll ESCAl.ATION a - - _ . . . - - .- .
i Seie Arc.s Emcrgenty Gruer.s! Eacrgency Uuusual Event -
Alert
- 14. 4:. East s y el una out selicJ tlam- 84. D. Turbine rotating component 18. D. Entry into facility enviso n. I i al.le g men into vital asca. failure causing rapid plant of toxic or fl sun.ible g.ase:. .
l Entry ul untuntrolled tusse shutJuwn. , l j gm.rs intu vital areas E. Turbine failure c.auning l ut.e s e lask ul access tu caming penetratiuse. !
tiee are.s sunstitutes a l
, salcty paulalam. -
a f
j H.. oil.es plant run.litanus exist 4. Other plant conditions exist, 15. Other plant conditiosas: 19. Other plant run.litions exist j that en the jn.lgreent o f al.e from ul.atever muurre, that m.ske that in Llee juilgemesit o f t i.e l Sisite Supesvisor, alie Opera- release of large amounts of A. Conditions that warraint i ss- Shilt Supervisor, LI.c oper.s- ,
eiusis linty kusinerr, tise Su- saJioactivity in a sliott perio.1 creased awareness on part of tions thaty Engineer, the
, l'es s ut en.icnt ui Oier.stions t of time possible. Core melt state and/or loc.al offsite Superintendent al Opes.ations, 4
us II.c Plant flan.eges warr.snt situation. autloori t ies. or t he l*lasit Hass.sges w.as sant '
, as t ivat eine ut emea grua y ren- precautionary attivation el i tess .anil m.usitorsag teams 18 . Conditions iliat respaire sleut- Tethsiical Support Cent er .in.1 i i .en.1 a persantinnary publir
.luwn naider technical speci- secar-site Crisin Managem.ne e us i t is .st ion. i icaliosis. Ocsiter.
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n'0. hY 3-^- A?/0/A/1000/04 Cn Enclosure 4.3 3A .-, ,
. . . - ,ssa...
- ,:0.
- 1. "E 2. 75C -
CMC 3 Orill 3. 4
, Telephone Au thentic a tio n g 3. AC !*E'i'" I'TTCF?A**04 C Tollow-up Tise Unit tsergency condition 6. Crr$tn troM-+cA-*:?
Every sisute(s) Time Picxans Time Cconee Time S.C. State Time Other
- 7. E m C OCT C' ASS!7! CATION d. PLA:fT $*AT'*3 9. PRCCNCSIS (34 sed on Plant hformacien'J.
C Tnusual Ivant Q stable C Escalati=g Emergency C Aler: O Improving D De-escalaciss Isergency C Site Area Emerge:cy Q "egrading C *ermination C Canaral E=argency Q Not hva C Not Isown
?M I0t0GTOAi t'P M **c?rt
- 10. ?" ' 5 " 11. Rate of Release Curies /sec 1J. ME*ICRot0CT C Ac:ual Wind Speed =ph O Projected Time of Release C Airborne Wind Direction (from)
C ..aterborne Release Duration stabill:7 Class Yes
- 12. Assume cround telease Precipitation Fors No 14 IS*!MA N S OCANTt*' CONCIT"!A*t0N
- 19. SEC"CM S) AFTEC 5')
/[\ Noble Cas
- t C) - I-131 (equivalent)
Oconee 321 Particulate Pickens $31
- 13. Actual . 51:e Boundary mi 531 1031 1031 is. Proj ected - Site 5 dry. hi fui 1031
- 17. heagrated 2s1 Szi 10e1
- 13. Jurface Radiation Contamination Zati= ace
- 23. ?'C*TC""*'.*! AC"*?N TECM:'" AMONS :
- 1. Does m involve che release of radioactive =aterial from :Se station or invoIve the public.
- 2. hvolves the :ocanttal for the release of radio-active, but to racioactive :acart.a1 has been released.
- 3. Oees i=volve the release of so=e radioactive material fres the station, but at a level belov that considered a public hazard.
6 Sees i=volve the release of radioactive materials from ete station at a level at v'n i:h protective action is advisable. l a
. 0 N ;' TORM.C: % , -
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- 2. .e . ..-- .. .. ... .. ....g wwe -- : (Repor: i -
- s 0:ucties ir.fer:acu n 113:'.,'3=,e.N,**' *.,
q,, ,, gg, , ,;. ,ng 7 2 ;33 gya ,
Enclosure 4.4 t'AT E- - ~ ~ ~ ~ ~ ~ ~ ~ ' ' ~ ~ ~ ~ ~ ~ ' ' ' ~
STATION FFRSONNEl, Acr 0LWTARil. lit HC ttAK2 NIM.FR menhcr CRot PP TF.lf rHONE FEOrt.E "^ " " '
, _ _ _ _ _ . _ _ _ _ _ . _ _ _ . . . _ _.__ _ _Cfour _ _ _ __ __n I t?nONE_, _, __ pf,t T
^ "' I""
Terhnical Services Contraat Services:
K -tt ir Ferformance: ~
Southern Sciurity Environmental:
-t
[ Training T. Safety:
O Licensing T. Projects: _
3 Atministrative Design Engineering _ _ _ _ _ - -
-# Services: NRC Wertro ficalth rhysics:
Q n.
Visitors' Center: _
Chemistry: _ __ _ _ _ _ _ _ _ _ . _ _
1 Kewee flydra:
Others: ____
Station Visitors: . __ - - . .
Receptionist Lnbby _
Scrurity I.nbby _ ttHE TOTAL. TECIINICAt. SFRVICF.S CROUP - - -
Ot tee r s :
Quality Assurance Ti t:E: _
TOTAT,AftflNISTRATION CROtfr " - - - - -
Operations Station Support .
liiilsTon - ~~
Operators On-Shift: TIHE: Station Support Division Total: _ _ . _ . , _
Engineers / Staff:
- Others:
Training Center:
BJ.W Personnel: -- --
others: gggggggggic nigig Ng Otheas Total: -
7-TtHE: TlHE: TOTAL FEOPLE ON-S;1E:
11ME: TOTAL,OPERATIOt33 CROtif .
Unaccounted Personnel Croup. Actinn Taken Ferson Report _ing fclerfu.n .
liaintenance * ,
Planning 1. Platerials: - - - - - - -
15.E :
~
RrttARKS :
tiarhanical ifaintenance:
System flaintenante Suppert:
Substat ion Plaintenance:
- others:
TIME: TOTAL MAINTENANCE CROUP
{ l
AP/o/A/1000/04 l .
DUKE P0kIR COMPANY OCONEE NUCLEAR STATION Enclosure 4.5
\
PLANT STATUS (Circle) OCONEE NUCLEAR STATION UNIT Unusual Event - Alert PLANT DATA AND STATUS DATE Site Emer. - Gen. Emer. INFORMATION TIME Control Room TSC HPC OSC By Title O
AP/0/A/1000/0!.
DUKE POWER COMPANY i
7s OCONEE NUCLEAR STATION
/
' \
'v/ ENCLOSURE 4.5 PLANT STATUS (Circle) OCONEE NUCLEAR STATION UNIT Unusual Event - Alert PLANT DATA AND STATUS DATE Site Emer. - Gen. Emer. INFORMATION TIME Control Room TSC HPC OSC
\
c )
V h
By 1 0
\ ) Title l
} q )t,bCI.EAltSTATION i -
(j EttERCE( ,JRCANIZATIOtl RECAI.I.
NoldtAI. WORKltlG 110UltS g Enclosure 4.6 IINIT OPERATIllG GI tHIR SilIFT SllPERVISOR NRC (RED Pil0NE) r SilPERIllTEr3DEllT OF OPERATIOllS OITSITE AGEllCI ES
. 7F ASST. STATIOli PIANAGER STATION MANAGER f ' CRISIS MANAGEllENT ORGANIZATION Y .--
1Y N(
Sul' ERIN I'E!1 DENT 0 -
iUPERINTENDENT OF SUPERINTENiiENT Ol' TECil. SERVICES tlAINTENANCE ADtlINISTRATI0tl
-k llealtli Playsics :nv i ronunenta l I&E
_g Administrative r , Services
-k Performance
~g Meclianical F tlaintenance Safety and
~g 1.lcensing and HitC Resident -
Tra in inn F Pro j ec t s luspector Plattning and Cliem i s t ry Materials g ,
llalicock & Wilcox Representative
_ \
- f. OC';: LEE ?;U,CM-gR S'ZATIO!! 'AP/0/A/1000/04 ,
E!!ERCE: ICY Or !ATI0tl RECA1.L ) .
n (BACKS?.WT,'k s 5HDS, HOLIDAYS) (d ,
Enclosure 4.7 .
OPERATIO!!S DUTY e ErlGillEER SHIFT SUPERVISOR NRC (RED Pil0NE) v .
SilPERIflTEllDErlT OF nt>Fi! ATi nf M STATI0fl MANAGER CRISIS MANAGEMENT ORGANIZATIOf3 0FFSITE AGEllCIES ASST. STATION l ' MAtlAGER bbklk!I!! k!k!hlk!bS
,_% SUPERINTENDEllT OF ~g V . MAINTENANCE F Planning & Material SWITCNBOARD SUPERINTENDENT OF ADrilNISTRATION ,
- Security at time Switchboard will recall Duty Per onnel assigned to various sections.
TECNilI CAI.
SERVICES MAINTEllANCE ADMIIIISIRATIO!!
-k IIca t tle Physics f . .". . . ' . .". . " "" I w 5Tirrion h ,
I&E F, Admin. Services
_.- l'erformance filol og i s t L licc han Ica i f Ma liitenance
~
. l.icenalng and NRC Resident Projects i n sinec t o r lIlalcock 6 Wilcox _
__. Emergency Prep.
. finn rel i nn t n r
ll i
AP/0/A/1000/04 i
RECORD OF DOSIMETER READINGS j ENCLOSURE 4.8 Name S.S. Number Section ' Group Date/ Time Dosimeter Reading i
?
NOTE: Turn over to Section Head at shift rotation during emergency conditions.
s .
. , . , _ _ . , . . . - _ , - . . . _ - - - _ - . . , . ~ - . _ . . . , . . . . _ _ , _ _ , _ _ _ _ . _ . - - _ . , _ - . . _ _ _ _ _
i .
INFORMElE W m Form SPD-1002-1 DUKE POWER COMPANY (1) ID No: AP/0/A/1000/05 PROCEDURE PREPARATION Change (s) N/A to PROCESS RECORD N/A Incorporated -
(2) STATION: Oconee Nuclear Station (3) PROCEDURE TITLE: Emergency Action Level (EAL) - GENERAL EMERGENCY ,
l . .
(4) PREPARED BY: M DATE: d M (5) REVIEWED BY: DATE: 3 71, f /1 Cross-Disciplinary Review By: N/R: d (6) TDiPORARY APPROVAL (IF NECESSARY):
By: (SRO) Date:
By: _ Date:
(7) APPROVED BY: l
\
b3 % Date: 3 9 "L-(8) MISCELLANEOUS:
Reviewed /Appr:ccd By: fff_ Date:T/9/f2.
_/'
U f Reviewed / Approved By: Date:
1 l
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, FORM SPD-1001-2 l NUCLEAR SAFETY EVAt.UATION CHECK LIST (1) STATION: da_u-- UNIT: 1 2 3
'N OTHEFj , g/f -
(2) CHECK LIST APPLICABLE TO: >$l///) /19-//30 a/o f
~/ / /' /
(3) SAFETY EVALUATION - PART A The item to which this evaluation is applicable represents:
Yes No / A change to the station or procedures as described in the FSAR; or a test or experiment not described in the FSAR?
If the answer to the above is "Yes", attach a detailed description of the item being evaluated and an identification of the affected section(s) of the FSAR.
(4) SAFETY EVALUATION - PART- B Yes No Will this item require a change to the station Technical Specifications?
If the answer to'the above is "Yes," identify the specification (s) affected and/or attach the applicable pages(s) with the change (s) indicated.
(5) SAFETY EVALUATION - PART C As a resul: of the item to which this evaluation is applicable:
O V (v) Yes No Will the probability of an accident previously evaluated in the FSAR be increased?
Yes No VWill the consequences of an accident previously evaluated in the FSAR be increased?
Yes No gMay the possibility of an accident which is different
. than any already evaluated in the FSAR be created?
Yes No V Will the probability of a malfunction of equipment important to safety previously evaluated in the FSAR be increased?
Yes No Will the consequences of a malfunction of equipment important to' safety previously evaluated in the FSAR be increased?
Yes No May the possibility of malfunction of equipment ;
i portant t'o safety different than any already evaluated )
in the FSAR be created? i Yes No Will the margin of safety as defined in the bases to any Technical Specification be reduced? j If the answer to any of the preceding is "Yes", an unreviewed safety question is involved. Justify the conclusion that an unreviewed safety l question is or is ot involved. /1ttach additional pages as necessary. l (6) PREPARED BY: b / DATE: d/ b-./
(7) REVIEWED BY: d DATE: 9 7A by (8) Page 1 f [
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, AP/0/A/1000/05 Page 1 of 3 1
, l DUKE POWER COMPANY
/] OCONEE NUCLEAR STATION EMERGENCY ACTION LEVEL (EAL) - GENERAL EFERGENCY
1.0 Symptoms
The symptoms of a General Emergency will vary according to the initiating Enclosure 4.1 defines the different conditions and gives specific symptoms of each of the same.
2.0 Immediate Action 2.1 Automatic - NA .
2.2 Manual Time /Name Date 2.2.1 If Hazardous Radiological conditions or the potential for such conditions exist, ~ initiate a site assembly using Station Directive 2.9.1 record ~risults on Enclosure 4.4, Station Personnel Accountability. Take immediate remedial action to insure the health and safety of personnel, minimize radiation and contamination problems, and minimize damage to the plant. Record actions taken on Enclosure 4.5, Plant Data and Status Information.
2.2.1.1 If radiation or contamination is involved, contact the Station Health Physicist or his Designee to initiate the displacement of Onsite
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and Offsite Monitoring Teams and assess and recommend methods to control Radiological Hazards.
Record Actions,taken on Enclosure 4.5, Plant Data and Status Information.
2.2.1.2 If the possibility of an offsite dose exists as a result of this event, evaluate the need for an offsite dose calculation.
NOTE: AP/0/B/1000/07 is for t.he Control Room use only for dose calculation. The H.P. Section will use H.P. Procedures if they perform the calculation, 2.2.1.3 Issue Protective Action Guides to offsite author-ities per AP/0/A/1000/06 only if the Crisis Management Team is not available to do so.
2.2.2 Determine from Enclosure 4.1, General Emergency Initiating Conditions, the most descriptive initiating condition for i /'~'N the event.
AP/0/A/1000/05
. Page 2 of 3 Time /Name Date O 2.2.3 Activate the Technical Support Center (if not already Q activated). Use Enclosure 4.6, Emergency Organization Recall. Have the Station Manager (or Emergency Coordinator alternate) to activate the Crisis Management Team.
2.2.4 Appoint an individual to be responsible for keeping records of the emergency and to notify offsite agencies and company personnel.
2.2.4.1 Notify company personnel and offsite authorities of the nature of the plant conditions using ,
Enclosure 4.1, Site Area Emergency Initiating Conditions, as a guide for notification. Refer to the Emergency Telephone Listing in the Imple-menting Procedures Manual for the telephone number that corresponds to the notification code under each initiating condition.
2.2.4.2 Enclosure 4.3, Message Format, is to be used in notifying staff and offsite authorities for both initial and followup contacts. Offsite notifi-cations should be accomplished within 15 minutes of the identification of the EAL. Establish update time frame with offsite agencies.
2.2.4.3 Records actions taken and events as they occur on Enclosure 4.5, Plant Data and Status Informa-tion. The Technical Support Center will be responsible for notification of offsite authori-ties and for recording events as they occur until the Crisis Management Center is fully operational either nearsite or remote from site.
Once the Crisis Management Center is fully operational, offsite authorities will be con-tacted by the Crisis Management Center. The Technical Support Center will continue with record keeping and plant updates to the Crisis Management Center.
2.2.5 'lechnical Support Center is fully activated and operational.
2.2.6 Operational Support Center is activated and operational.
2.2.7 Evacuate all non-essential personnel per Procedure AP/0/-
A/1000/10.
2.2.8 Start the Control Room Ventilation System if radioactivity exists outside the RCA.
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Q 2.2.8.1 Have Technical Support Center personnel read dosimetry every hour. Record readings on Enclosure 4.8, Record of Dosimetry Readings.
, AP/0/A/1000/05 4 .
Page 3 of 3 Time /Name
, Date 2.2.9 Insure that Senior Members of plant staff onsite are
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available for consultation with NRC on a periodic basis.
2.2.10 Insure that an individual is dedicated to periodic briefings with news media. This individual would be a member of the Crisis Management Team.
2.2.11 Proceed through use of the proper procedures to bring the
- plant to a stable, safe condition.
4 3.0 Subsequent Action 3.1 When plant conditions warrant, the General Emergency should be de-escalated to a lower class emergency.
. NOTE: Use Enclosure 4.2, Guide for Escalation, to identify the change in initiating conditions. From the time the event is identified to be de-escalated, all offsite authorities should be notified within 15 minutes.
3.2 Terminate the emergency after de-escalating to an Unusual Event.
3.3 De-escalation requires the concensus of the Nuclear Regulatory - ---
Commission and the State of South Carolina.
O 4.0 Enclosures 4.1 General Emergency Initiating Conditions 4.2 Guide for Escalation i
4.3 Message Format
, 4.4 Station Personnel Accountability 4.5 Plant Data and Status Information 4.6 Emergency Organization Recall - Normal Hours 4.7 Emergency Organization Recall - Backshift, Holidays, Weekends
- 4.8 Record of Dosimetry Readings
r________. . _ _ __ _ ._. .. _._ _ . _ _ __. _ _ . _ _ _ _ _ _
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OCONEE NUCLEAR STATION Page I of 6 AP/0/A/1000/05 LNCII)SURE 4.1 G neral Emicrgeney Ocouee Nuclear Station l'inal .
init iat ing comlitions Symptoms Safety Analysis Report Section 14.1 Emergency Procedure /Doeument I. Ateilcutal kelease A. Effluent monitors detect level Waste Cas llecay Tank Rupture; Liquid EP/0/A/1800/24 4.orresponding to I rem /hr W.B. Waste T.ank Nupture;
- Notily: 1-2-6-1-11-12 or 5 res/hr thyroid at the site 1.oss of Coolant Accident boundary under actual meteor-ulogical conditions.
B. These dose rates are projected li.ased on other plant parameters (e.g., Nadiation levels in the containment with leak rate I appropriate for existing contain- '
ment pressure with some confism-
.stion from effluent monitors or are measured in the environs).
NOTE: Consider evacuation only within about 2 miles of the site boundary unless these site l>oundary levels are exceeded by a factor of 10 or pro- .
jected to continue .
i for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> or El'A Protective Action l Cuideline exposuse levels are predicted
[ Lo be exceeded at long-er distances. ,
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OCONEE NilCLEAR STATION l' age 2 of 6
, AP/0/A/1000/05
- t ENCIDSUNE 4.1 6curral Emergriny Oconee Nuclear Station l'inal lustiating Conditious Symptoms Safety Analysis Heport Section 14.1 Emergency Procedure /tGcument
- 1. loss of 2 or 'l fission product A. 1.uss of primary coolant boundary Imss of Coolant Accident; Steam EP/0/A/1800/04 learriess with a potential loss Generator Tube Hupture us tleis.1 barrier. 18 . Clad I?ailure N..t i l y : I-6 14-12 C. liigh potential for loss of contain-ment integrity after an accident.
- s. 1.ums ut physsaal contsul of the As detesmined by Security Force Ep/0/A/1800/25 8.erility (NOTE: Consider the 2 EP/0/A/18L3/12 meir precautionasy evaiuation).
. Nut s t y: 1-6 ll-12
- 4. Other pl. ant eonditions exist, A. Small and large IDCA's witta less of Coolant Accident; As alictated by plant conditions t e um winat ever source, that make tailure of ECCS to perform Steam Generator Tube Hupture; sclease ut large amuunts of leading to severe core degrad- Wste Gas Decay Tank Rupture e .liu.sctivity in a s.hort period ation or melt in from minutes us time possible. Cuse melt to hours. Uitimate failure s i t u.it i un : of containment likely for melt se-quences. (Several hours likely to be available to complete protect-ive attions unless containment is l not isolated.)
l I Cun t i nue.1) (Continued)
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i OCONEE NUCl. EAR STATION Page 3 of 6 AP/0/A/1000/05
, ENCLOSukE 4.1 l ncra gc .c Oconee Nuclear Statia.n Final
, lustiatihg Conditions Symptoms Safety Analysis Report Section 14.8 Enc 85ency Procedure /Ducument
- 4. (t:out a nne 1) Is . Transient initiated by loss of Hajor Secondary System Pipe Itupture; El'/0/A/ 8800/04 leedwater and condcasate systems 1.oss of Coolant Accident; EP/0/Afl800/14 htsly: 1-6 11-12 (principal heat removat system) Loss of Normal Feedwater Turbine EP/0/A/1800/28 lollowed I,y failure of emergency Trip EP/0/A/1800/08 feedwater system for extended EP/0/A/1800/19 j pe r i cal . El*/0/A/1800/07 Core melting possible in several hours. Ultimate failure of con-tainment it core melts. .
C. Transicut re piirinc operation of g shutdown systems with failure to ,
scram which results in core damage ;
or additional failure of core cool-iug and makeup systems (which could s lead to core melt.)
D. Failuse of oil-site and on-site Loss of Ofs-stte Powes to Station EP/0/Afl800/14 powes along with total loss of Auxiliaries EP/0/A/1800/16 cmergency feedwater makeup EP/0/A/1800/28 capdIbilkty for severak liours.
Would lead to eventual core melt and likely tailure al containment.
(Coutinued) l 4
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) OCONEE NUCl. EAR STATION Page 4 of 6 -
AP/0/A/1000/05 t.NCIDSUNE 4.1 skneral Emergency Oconee Nuclear Station Fisaal Initiating Cun.litions Symptoms Safety Analysis Report Section 14.1 Emergency Procedure /l)ocuawnt E. Sm. ell thCA and initially success- 1.uss of Heactor Coolant trom Small.
Ital ECCS. Subsequent failure of Ruptured Pipe; I contaisuncut laeat removat system 1.oss of Coolant Accident
! uver several hours could lead to core melt and likely failure of containment.
NOTE: Host likely containment r . failure so.le is melt-
- Liaruusts with sele.ase of gases only for dry containment. Quicker release expecteil f or failure of containment isolation system for any
- wu. s l * '
.. A .y m.ajur, int ern.al ur external A. Visual observation fire alarms con-
, e*ve ut h that roulal cause massive trol rocas
- s umamun it.im.ege to pl. ant syst ems.
Bl . Seismic Trigger >
A. l'ises
- is . E i tle.suakes (sul stantially beyun.1 ichign I. sis).
N..t i l y : 1-6 Il-12 g
.. - . . _ , . . - . - -m. .-w-. . --e.--o . - . = - .- .
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, OCONEE NUCl. EAR STATION Page 5 ol b f
AP/0/A/1000/05 ,
ENCLusukE 4.8
~
G nc ra t t w rgent y Oconee Nuclear Station Final
- Ins t iat ing Cumis t ions .ymptoms Safety Asialysis kepart Section I4.1 Emergency Procedure /lkcument 8'!on rg a jys . A tt sings. Li>/0/A/1800/04 A. For rust melt me.guesaces wlacre msguilirant releasen f rom rusi-t a issmcsit are neut yet takang plat e an.1 las ge amoussts ut lis-sion peulu ts .ere not yet in 1 the toutainment atmun.phere, t onni les 2 mile precautionary cvat ua t iusa. Consi.ler 5 mile ,
iluwnwise.1 evat nat iosa (45" to 90* nrtior) il 1.a r ge amuuant s
.. I limssoas prmlus is (gicater tisan g.sp activity) ase in the runtainment atmosphere. kccum-men.1 slicitering iss other parts of the plume caposure Emergency Planning Zone un.ler this cirriam stance.
I 11 For rose melt sequentes where s s gni fit' ant releases f rom cuss-t a isemen t ase asol yet taking ,
plae c .ssiel roastaisissutsit failuse Ic.siling tu a .ti s et t 4 t ames-
- piectic release is likely in the sequcinc lut not imminent anel j l.s tge .am..unt s ul liksion gas o-
.in. t s in .a.l.li t ion t o noble g.ases ase ins runtainment atmos-pl.cs e, s ons a lcr pret.aut iusa.ory e
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, OCONEE NUCl.EAN STATION P. age 6 Of 4. !
l Al*/0/A/I000/05 I
! ENCI.OSUNE 4.t -
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2 Ocs.eral Lacrgeucy ocunee Nuclear Statius Fanal i l lu6taating Con.lstions syngit ums Safety Analysis Neport Section 14.1 Emergesecy Pruce. lure /lkcument l*s..I ce t a ve As t iaisis (Cout 'd.)
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milca tiownwin.1 eVafuatkun (kh* I tu 90' acclur). I t
t C. 6ur tus e ac ti sequesices wisere i 1.isge muunts of fission pro- !
j .lurth utiser tiaan su,lele gaben l t
ase is tlic sositainment atmos-gelecrc asul a usst aianamesit atmes-31.cs e an.1 a sutt ainment failure i
.s s e gu.lged inemineset , recum- '
mun.1 minciter for Linuse areas +
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wl.csc evasualiuss cannot lie re mgelr t r.1 lec t ure t r.anageurt of *
} da t ivit y to lla.st luration.
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in aa a us el. ant e wi tts dose gesu- t jet t j usas, t see availaisle tu ;
i ev.as u.st e an.1 cat ima t e.1 ev.arss- t j .at insa 4 iones givres s ur rcut run- l l ditsuus.
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OCONEE NUCl.EAN STATION page 2 of (,
Ap/0/A/ ID00/05 EhCIA)SukE 4.2 Grs.co.el Emcrgency linusal Event Alert Site Area Emesgrency L loss ut 2 or 'l tensiosi product 1. Fuel damage indication: 1. Severe loss of fuel cladding: 1. Known loss of coolasat .sisidcut +
1.ar r aers wills a putential luss greater thase m.skeup pump e. spa-4 u s t h e r.1 6. r r ict. A. liigli coolant activity sample 1. kapid failure of muere Elian 10 city (any Irakage > 500 grael.
1 (e.g., estee. ling coolant Leth- steam generator tulnes (e.g.,
seical specification tur iodine several hundred gie paim.ary to 2. 1)cgra. led rose with 3.uss Isle loss spike). (liigle Neoctor Coulant secondary leak rate). of coolable geometry (inderaines Sample Attivity) sliould isiclu.lc inat s sement.st a an ,
j 4. Steam line lireak witia signiti- to detect inade.guate coac suul- !
- 4. Alenusmal coolant temperature enJ/ caut (e.g., gecater then lo gpm) ing, cool.nt activity an.1/u or pressure or alanusmal fuel primary to secondary leak rate or re.licactivity levcis).
flSIV malfunctiosa.
temperatures outside of technical specification limits (> 2500 psig) 3. Napi.I failure ut muse elan su
- 9. Coolant ginassip siezuse lea. ling to st eam ge sacrat or t estics we tl6 l .ss
- 9. Imss of engineercJ saf ety f eature fuel failure. of oil-site power (e.g. , scves al or fire protectiosi system function hundrcJ gpm prim ry to secun.14e y acquarang shutdown ley teclinica! 12. Fuel damage accident witte release leak rate).
specific 46 tons (e.g., malfunc- of radiuoctivity to containament tion, persos,inel error, or pro- or fuel handling 1.nilating. te . l' Wit steam line bre.sk we t te girat -
s edural in.edequacy). er Elian:
A. Engissected Safety Feature A. 50 gin primary tu .ceun.lasy le.skage it . Fise psolca tion Systein 18 . $0 gpm primary to accou.l.ary leak.sge 4eul inJacatsun ut luel damage. i
's . Plajor elamage to spent inel A. In containment (e.g., water loss below luct level)
(Continued) l
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OCONEE hilCl. EAR STAT 16N Page 3 of to ;
AP/0/A/1000/05 ENCIDSt*E 4.2 skure I Emessensy lluusal Event Alert Site Area Emergesity
, 9. R. In Fuel ll.sndlisag thail.linig (SFP) (e.g., large ut.grat damages luel) l
- - - - _ . . t i s . ' l u:.s of goliym e ra l s uut s ul of' t lee 12. Scosrit y threat or at tempted cut ry 16. Ongoing Security compromise. I 'l . luminent loss of physia.si sou-latility (Nutc; fusasi.lcr (lee 2 or 4LLrmpted sabotage. t rol of the pl. ant.
maic pers usionasy ev.stuation).
A. Isomb/coplosive or missiles j 11 . Subversive activity attempted
- a. W.stiara t phenomesson being experienc-ed or projected beyon.1 usual levels:
l A. Any c.s Lluguake (> .05.g designa
! are cle r a t icas) i i
! II . 50 year flood or too water.
, leurricane surge, scea he 7
(lake tidal w.sve)
I C. Any t orn.s.lo nea r s s t e i 18. Any hurricane (> 14 mph) 4
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i OCONEE NUCl.EAN STATION l' age 4 of 6 AP/0/A/1000/05 i
ENCIASUME 4.2 tkucr.el Ea.essency unusal Event Alest Site Area Emergeucy
- 4. usher Plant s ondit ia,ns exist , I. Emergency Core Cooling initiatcJ 2. Rapid gross failure of one steam 1. Known loss of cool. int asci.lcut 8 som wl.atever suus s e, Eliat make (to incilent with positive find- generator tube with loss of of f- greater ti au makeup pump c.ap.-
s elca:.c of large amounts of ing iniitiation is NOT spurious, site power from all sources cit y (any Irakage > 500 gr ).
ut tsme p..ssil.le. Core melt ES actu.ites and discharges to (OTSG Tube) s.stuation. vessel. 5. I.oss of off-site 3.uwer gn.1 loss
- 2. ka.liological effluent Technical 3. kapid failuse of more than 10 al on-site AC powes for mose Sperification limats exceeded. s t a .am gesse s a t o r t ulees (e . g . , than 25 miinutes.
several hundscJ g m piimary to A. 1:4scous efflurait instantan- secondary leak satel. 6. l. ass of all vital s.n-nate isG cous selease rate Technical power f or mos e t han 45 minutes.
Specification limits exer 1- 5. Primary coolant leak rate greater ed for one (I) laour. Lisan 50 glas. 7. Cumplete Inss of any lusations seceded for plant I.u t shu t .lowin .
it . Liquid ettluent concentra- 6. liigh radiat ion levels or high tion. Teahnical Specilaca- ainburne contamination whicia 8. Transient triguiring operasson ul Lion limits exceeded 15 indicates a severe degradation shutdown systres witti tailisse tu minutes. in the control of railioactive -
saram (continucJ powes gence.stion materials (e.g., incscase by a lust no core .laan.sge immacds.st ely S. Exceeding either psim.sry/ tactor of 1000 isi direct radia- evident).
secondary icek rate teclanical tion readings).
specifications or primasy leak ,
sate techniuel specifications. 15. Ot her hazards incisig expre s cin ed
(> 10 gpm total P/S leakage) 7. l.oss of off-site power and loss or projected witta plant not in of all on-site AC power f or up to cold shutdown.
A. Prim.as y - s egui ring shut- 15 minutes (loss el Keowce not down credible so siot cosesiderrd). A. Ai rc r. sit crash affre-ting vital street t ures hy impact or li n e.
11 . Psin.ory to secondary Unit I
> 0.:10 gpm. 8. l.oss of on-site 1)C power.
it . Severe damage t o sair shut. town
- 10. Complete loss of all functions eqis i g.nesit Isom missiles os for plant cold shutdown. explosion.
II. F.silure of the reactor protectiosi systras to isiitiate anel complete (Contsuned)
- a scram whitle brings the rc. actos sulecritica1. (Cont a nne.1) (Cont inne.Il
~
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i.
! OCONEE NtlCIEAlt STATION page 5 of 6
$ AP/0/A/1000/05 ENCLOSURE 4.2 -
- r y . . - . . - - - _ _ . _ . _ _ - . . . . _ _ - . . - . _
Grueral Emesgency Unusa! Event Alert Site Area Emergeury
- 1. less of offsite power or loss of 18. Other hazards being experienced 15. C. Entry of uncontrolled llam-site AC power capability, or projected. mable gases into vital rea.
Entsy of uncontentle.1 taxis A. l.oss ut offsite power A. Aircraft crasis on facility. gases into vital ascas wtwac ,
lack of access to ti.c .nse.a B. l.oss of on-site AC power B. Hissile impacts from whatever constitutes a salary ;
source on l'acility. psoblem.
4 C 9. laass el engineered safety feature
- ce fire protection system function C. Known emplosion . lam. ige to se.gniring shutlown l>y technical facility allecting plant lie. Otier plant cosulitions esist specifications (e.g., mallunction, operation. Llaat in the judge ment of t he-personnel error, or prote. lural Shif t Supervisor, tlic ogws.it ions ,
innade guacy). -
D. Entry into latilit envi a.;ai I)uty Engineer, the Supes intVndeset '
l of toxic or Alana h4e gases, of Oper. L eons or al.c Plant II.ana-
- 10. Fire lasting more than 10 minutes. ger warrant activat ion or rmer-E. Turbine failure c.insing . gency cesiters .sud monit oring d
- 14. Othes hazards being experiesired casing penetration. teams an.1 a precautionasy pulilie-or projected: . sout i fic a t ion.
- 19. Other plant conditions caist A. Aircraft crash on-site that in the judgment of the.
or unusual aircraft activity Shift Supervisor, the Operations over facility, thaty Engineer, Llee Superinten-
- dent et Operations, or tiae Pl.snt
- 8. Near or uni-site explosion. Hanager warrasit airecaution.ry activatioes el Tethanir.el Suppart C. . Nc.ar or on-site toxic or flam- Center and near-site Crists m ble gas release of a Hanagement Center.
magnituele alsat tiercatens .
- personnel.
j .,
- 11. Tus t ine rotat insg e camposae sit l.silure caussug rapid plasit
, shu t elown . .
/
P'
O h U
4)CONEE NUCl.EAM STATanN Page 6 el 6 AP/0/A/1000/05 i ENCthSt*E 4.2 1
skue s a l t.mc r ges.. y lleiusal Event Alert Site Area Emergency ,
i
.. Any m4jor intesual ir'estesual 10. Fire lasting more tiease 10 m'anutes: 13. Frre potentially allecting 10. Fire compsuinising al.c lusicteuns evcut s al at suiald s'ause masseve safety systems. of Llae selety systems.
. ommon .l .ge t o pl.sut systems. A. Onsite . ,
A. Fases 14. ecUse natural phenoncua Ising II. All alarms (esisiossit iat ees s).l st '
11 . Olisite (surrounding the experiessteJ or projected wills for more tisan l$ manutet an.1 16 . E.e s t l..pa b c.[(subst ant ially Station) plant not in cold slautdown. plant is not ins rol.1 shut.lowie !
1.cyon.1 lcs s ges le.as i s . ) l 't . Nstural phenomenoss being experi- er plant t r ans o cest initiated ;
catted or projette.1 1.cyoned usual A. Earthquake gir. iter tisan SSE e,le i t e a l.s a ns R os a .
levels: levels.
A. Any cart hqu.ske (>.05 Jesign 14. Severe saatural plu seomresa la. sear.
acceler.stion) 8. Flood, low v. iter, hurricane espesiented or peujrated witis surge, seithe gre.ater than plant seut an cold shut.lowes.
- 3. 50 year flood or low w. ster, design levels or tailiare ot' hurricanc' s'orge, seithe (lake protection of vital equip- A. Earttuguake great er t han SSF tidal wave). ment at inwe s levels. levels. i 1
C. Any tornada sacar site C. Sustained winds or tosuadoes B. FlooJ, low w. ster, l.ussitane.
iss excess ut draign levels surge, seis ke great rr t han .
. 11 . Any hurrirane (> 74 mpts). (greater Llaana 95 mph). demian levels or I.esture of protection el vital repsismiant
- 17. Severe natural phenomena heing at lower levels.
esperienced or projecte.1:
C. Sasst.aincJ wispis as t aa s 4 l..rs A. E.srtlieguake greater alian isi catess el design levels Operat ional liasis Eartisqualis- (gs cates' lisass 95 mg.ls). r levels (> .05' g)
! B. Flood, low wates, hurriraue surge, scia tie accar .lcsigu levels (lake ts.t.nl wave)
C. Any torna lo st rikisig f aci-lily I). Ilierricane wanJs sicar Jessgs 14 mis level (> 95 mph).
L .- . <
- l
- t, *"**7 *
- 3*' '
- P #7 U j .%/ i L V /, *J )
?*
..1.*.**V.*
.. T T ..w h gy
/ MESSAGE FORM.C -
I
' Enclosure 4.3 C1 .
OAT C.'S 535A0Z NC.
1..j TSC
- 1. w g _
r 'Cw, '
3-
3 Orill
' Telephone Auchentication C Isergency ,
, 3, ACCn ct TNTO?{AMON w !aic141 C Tollow-up Time "nie hergency Condition 6. C m i n Non ?!CAn 0N T.vtry sinute(J) T1=e Pich -s -
/ e Time Oconee Time S.C. 3tata Time Other
/,
- 7. DEICUCT CIASSt7tCAMON 8. PLA:rr S AT"5 9. PRCCNOSIS (3ased on Plant hformacien)
C 7cusual Zvent C Stable C Eseziacin6 hergenc7 C Alarc , -$ / O Improving C De-escalac1 g Zuergency .
O *erminacion C Jica Arts hertency O Oegrading C Canaral hergency Q Not Kanwn' ,/ O Not Known '
+ - l I
- 4 s a
- s 2AO!3!.CCITAi t*m ANN- < .
- 10. "' m 11. Race'of Release _ Cartas/sec / 13. itE*ECR0t0GT Q ' Actual Ti== at., Release' Wind Speed gh O ; Proj ected $ y
- C Airbo. se ~
. find Direction (from)
C ..acerborne Relaaze Duration
- i stabilicy Class r ,
12., .ssume Ground Kalasse , ?recipication Form No f' ,
II. . I5*I ".A*IS OCANT!** CONCINTRATICl*
- 19. SIC"0R(S) AFTTC"I3 i Noble Gas
\ Oconee Sai N - I-131 (equivalanc) _ _ _
,y Particula ca Fickena 531 13 . Actual - Sica 3oundary .
Sni* $m1 10a1 .,031
- 16. Projected - site 3 dry. 2s1 hi 1031
- 17. Stegrated 131 331 10a1 -
13 . Surface 3adiation Cantamination !stimata d
- 10. ?'C*TC""N AC**0N ECMO A**0NS : .
[' . ,
i 3
- 1. Ocas et involve the release of radione:1ve material
. from the scacion or invoIve the public.
/
. Isvolves the -ocential for tha release of radio-active, but no racicactive =acerial has been relaased.
- 3. Does i=volve the release of some radioactive ' /
material from the scacion, but ac a level belaw ct.at considered a public hazard. , ,
s -
4 Ooes involve the release of radioactive sacerials from the station at a level at vnich protective actiors is
~ '
advisable.
.r N ?
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', y. .
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1
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- 2. ' 32 ?.E'lIRSI i!:I -b c . ;; ::: A . :0:cr: 3: (lenor: :o 0 un:1es t:for:acion *ia:ed i: .-4, 19, :0, 21 r:2.,
(Re:or: :: Staca all i.:f st- 2:Lon avai.la:le.'e *
,-'f k
,P' ,
Enclosupe 4.4 vAir _.___ __.- . . _ - - -
STATION rERSormEL ACl'WNTARIll1Y \
DEPrGTING ' - '-'
pry pitric flAPfE N!HPFR Mumler rscup 1F.I FritONE PEOPl.E HOilE NIHnER tamit FR ggggp TLt ErtW FNMF Administration Terhnical Services Contrart Servires:
K-tin Performance:
~ ~ ~ ~
Santhern*Sesurity .
Environmental: _ _ . . _ . .
Treining & Safety: __ -
Licensing & Projects:
A<!ministrative Design Engineering _ _ . _ _ _
Serv <cs: NRC Wometro llcalth Physics: . _ _ _ _ _ .
Vici'nts' Center:
Chemistry:
Kenwee Ilydro: - - -
Others:
Station Visitors: _
Rereptionist Lobby Scrurity Lohliy [ TitEs TOTAL TFCllNICAL SERVICF.S CROUP -
Others:
Quality Assurance TittE: _ TOTAT. ADHINISTRATION CROUP ____ .-
917 t a t j ons, y, b Operators On-Shift:
TIttE: Station Support Divistan Total: _ _ _ _ _ . . _
Engineers / Staff:
Others:
i Training Center:
B&V Personnel: _ _ __
UthPF5:
BEGINNING ENDING Othens Tntal:
TIHE: TIME, TOTAL. PEOPl.E ON-SITE:
Tt HT:: TOTAL, OPERATIONS CROUP Unaccounted Personnel Crong Action Taken Person Reporting cphone fla i n t enance -- - - - -- - - - -
Planninr, & flaterials: - - - - -
IKE:
R Et1 ARKS:
flas hanical ifaintenance:
System flaintenante Suppert:
Substation Haintenance:
. i Others:
TIME: TOTAL HAINTENANCE GROUP { l
. AP/0/A/1000/05
,- DUKE POWER COMPANY OCONEE NUCLEAR STATION Enclosure 4.5 i
PLANT STATUS (Circle) OCONEE NUCLEAR STATION UNIT Unusual Event - Alert PI. ANT DATA AND STATUS DATE !
Site Emer. - Gen. Emer. INFORMATION TIME i
k e
)
1,
) By i
Title 1
L i
(
Etif.RGEtiCY ORGAtIIZATIO!I RECAI.I.
Il0RitAl. WORKitiG ll0URS Enclosure 4.6 Uti1T OPERATit1G Et1Gi tIEER '
SIIIFT SUPERVISOR tlRC (RED Pil0NE) sr StiPERIllTEllDEFIT OF OPERATIO!1S OFFSITE' AGE!ICIES Y
ASST. STATIOri STATION FIANAGER CRISIS tlAtlAGEPIEllT tlANAGER f- ORGAtIIZATI0li lf ~ ~ ' ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
lf lf SUPERitiTElit)htif 0 -
jppjRIth bHI)EtW OF
~~
SUPERI!ITEFIDEllT OF lTECll. SERVICES _flAltiTEllANCE , ADtlIIIISTRATIOti
-k IIcal tli Playsics nvironmental I&E g g r Services
-h Performance
~
tiechan ica l
. 11a in t enatice b Safety and I.lcensing and NRC Resident -
f Tra in ing Prolcets Inspector
', Planning niid Cliemist ry - !!aterials
___ g g
- Babcock & Wilcox' Representative
(DACKSiiWTo WEEEEllDS, Il0LIDAYS) ,
En~ closure 4.7 OPERATintiS DUTY r ENGINEER SIIIFT SUPERVISOR !!RC (RED Pil0NE)
V SUPERINTEllDENT OF .
" " " ^ ""
-f STATI0tj ittAt1AGER CRISIS MANAGEttEt1T ORGANIZATIOli 0FFSITE AGENCIES AF ASST. STATION
~ MANAGER h,[:III}}U[I;"NbNINS
,_ SUPERit1TEt! DENT OF -
V . MAINTENANCE Planning 6 Material SWITCilt10ARD
._ SUPERINTENDENT OF
._ ADMINISTRATION
- Seciarity at the Switchboard will reen11 Duty Per onnel assigned to varioun sections.
TEC!ll11CAI, SERW CES HAINTENAtlCE ADMillISIRATION IIenith Physics " '" "" '
-f F nim.e v ,", 4 e e
k statlau 4 ,
I6E F , Admin. Services
_
- PerIormance Biolonist tjeclian ien 1 Ha liitenatic e I,1censitig and NRC Residelit Projects III8PUCIUE ,
.Ilabcock 6 Wilcox
_ Emergeticy Prep.
Con rel I nn t n r
i OCONEE NUCLEAR STATION i
- AP/0/A/1000/05 ENCLOSURE 4.8 RECORD OF DOSIMETER READINGS i NAME S.S. NUMBER l SECTION GROUP Date/ Time Dosinieter Reading 1
i j_ =
i I
f NOTE: Turn over to Section Head at shift. rotation during emergency conditions.
~
~~
INFORMATIDN DNi_Y Form SPD-1002-1 <
DUKE POWER COMPANY (1) ID No: AP/0/A/1000/06 PROCEDURE PREPARATION Change (s) NA to PROCESS RECORD NA Incorporated (2) STATION: Oconee (3) PROCEDURE TITLE: Procedure for Initiating Protective Action Guides For the General Public in The Emegency Planning Zone (4) PREPARED BY: b DATE: d (/ /2 (5) REVIEWED BY:
- d, '
s DATE:
/
9/ [R
/
Cross-Disciplinary Review By: N/R: n (6) TEMPORARY APPROVAL (IF NECESSARY):
By: (SRO) Date:
ps By: A Date:
(7) APPROVED BY: fW / LW~~ Date: i b (8) MISCELLANEOUS:
Reviewed / Ape m ed By: u,o, #M, Date:
T,k,/gz Reviewed / Approved By: _ Date:
l o .
l 1
. FORM SPD-1001-2 DUKE POWER COMPANY NUCLEAR SAFETY EVALUATION CHECK LIST (1) STATION: '
// W' UNIT: 1 /2/ / 3, OTHER: //-f'/8 /s9-//Ce c /A k' (p) v (2) CHECK LIST APPLICABLE TO: / / / /
(3) SAFETY EVALUATION - PART A The item to which this evaluation is applicable represents:
Yes No / / A change to the station or procedures as described in the FSAR; or a test or experiment not described in the FSAR?
If the answer to the above is "Yes", attach a detailed description of the item being evaluated and an identification of the affected section(s) of the FSAR.
(4) SAFETY EVALUATION - PART B Yes No # Will this item require a change to the station Technical Specifications?
If the answer to the above is "Yes," identify the specification (s) affected and/or attach the applicable pages(s) with the change (s) indicated.
(5) SAFETY EVALUATION - PART C
, As a result of the item to which this evaluation is applicable:
b
\
Yes No V Will the probability of an accident previously evaluated in the FSAR be increased?
Yes No / Will the consequences of an accident previously evaluated in the FSAR be increased?
Yes No " May the possibility of an accident which is different than any already evaluated in the FSAR be created?
Yes No Will the probability of a malfunction of equipment important to safety previously evaluated in the FSAR g be increased?
Yes No Will the consequences of a malfunction of equipment important to. safety previously evaluated in the FSAR j be increased?
Yes No May the possibility of malfunction of equipment important to safety different than any already evaluated in the FSAR be created?
Yes No Will the margin of safety as defined in the bases to any Technical Specification be reduced?
If the answer to any of the preceding is "Yes", an unreviewed safety question is involved. Justify t question is or is otinvolved.yeconclusionthatanunreviewedsafety Attach additional pag s as necessary.
(6) PREPARED BY: c 'w
- # DATE: J / f;2./
i (7) REVIEWED BY: TE DATE: /% A'2 ---
Os - - /
l "
t-c d m uAN 4u (8) Page 1 of /
/ .,a&Zhl '
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AP/0/A/1000/06 l Page 1 of 2 l 1
OCONEE NUCLEAR STATION 1
PROCEDURE FOR INITIATING PROTECTIVE ACTION GUIDES FOR THE GENERAL PUBLIC IN THE EMERGENCY PIJ5NING ZONE 1.0 Symptoms 1.1 Should radioactive releases that would produce exposures in excess of the Protective Action Guides in Enclosure 4.1 carry beyond the station boundaries, it will be necessary to take protective actions in the affected portions of the Emergency Planning Zone.
2.0 Immediate Actions 2.1 Automatic 2.1.1 Not applicable 2.2 Manual 2.2.1 General Emergency class emergencies have the potential for requiring Protective Actions in all, or more likely, a portion, of the Emergency Planning Zone. Lower classes of emergencies would be escalated to a General Emergency before Protective Actions would be required.
3.0 Subseouent Act-ions (Emergency Resconse Oreanizations in Operation) ..
3.1 In the majority of cases, it is anticipated that a deterioration of an emergency situation classified as an alert or site emergency would generate the need for a General Emergency and Protective Actions for portions of the Emergency Planning Zone.
3.2 The emergency response organizations (Technical Support Center, Crisis Management Center, State Forward Emergency Operations Center, and County Emergency Gperations Centers) would be in opera tion.
3.3 The Crisis Management Center through the Recovery Manager will make recommendations to the State Forward Emergency Operations Center for the areas requiring Protective Actions. Protection of the General Public in the Emergency Planning Zone is the responsibility of the State.
3.4 Based upon Duke Power's recommendations and direction from the Bureau of Radiological Health of the S. C. Department of Health
' and Environmental Control, the State would initiate protective actions for the necessary portions of the Emergency Planning Zone.
i l
1
= - _ _ _ _ - _ _ - _ _ _ _ -
AP/0/A/1000/06 ,
Page 2 of 2 i
3.0 Subseouent Actions (Emerrency Resoonse Organizations Not in Operations) 1 3.1 Should the situation arise where an off-site release of l radioactivity will generate doses in excess of Protective Action l Guides and the various offsite emergency response facilities are not established, the Shift Supervisor and/or Station Manager (Emergency Coordinator) would proceed as follows:
3.1.1 Project exposure levels to the general public, and determine sectors requiring Protective, Action.
3.1.1.1 Control Room - AP/0/B/1000/07 3.1.1.2 Technical Support Center - Health Physics Offsite Dose Procedures 3.1.2 Notify the Oconee County Emergency Preparedness Agency <
l and the Pickens County Civil Defense Agency of the emergency situation. Recommend protective actions for the effected areas using Enclosure 4.1 as a guide. The Directors of the county emergency agencies have the responsibility for the protection of the general public in their county. Notify the State Emergency Operations Center in Columbia of the protective action guides.
Use Procedure AP/0/A/1000/05 for guidance.
4.0 Enclosures 4.1 Protective Action Guides e
f .,
- Pd ENCI' 4.1 PROTECTIVE ACTION ClllDES Recommended protective actions to avoid whole body and thyroid dose from exposure to a gaseous plume, s Projected Dose (Hem) to -
the Population Recommended Actions (* Comments No protective action required. Previously recommended Whole body <1 State may issue an advisory to seek shelter and protective actions may be await further instructions or to voluntarily reconsidered or terminated.
Thyroid <5 evacuate.
ifonitor environmental radiation levels.
Seek shelter and await further instructions.
Whole body 1 to <5 Consider evacuation particularly for children and pregnant women.
Thyroid 5 ot <25 Honitor environmental radiation levels.
Control access. ,
Conduct mandatory evacuation of populations in the Seeking shelter would be Whole body 5 and above predetermined area. an alternative if evacuation Honitor environmental radiation levels and adjust were not immediately pos-Thyroid 25 and above area for mandatory evacuation based on these levels. .sible.
Control access.
Projected Dose (Rem) to Emergency Team Workers
- Whole body 5 Control exposure of emergency team members to these Although respirators and Skin of Whole Body levels except for lifesaving missions. (Appropriate stable iodine should be or Thyroid 30 controls for emergency workers, include time limita- used where effective to Extremities 75 tions, respirators, and stable iodine.) emergency team workers, thyroid dose may not be a Whole body 75 Control exposure of emergency team members perform- limiting factor for life-Skin of Whole Body ing lifesaving missions to this level. (Control of saving missions.
or Thyroid 150 time of exposure will be most effective.)
Extremities 375 VOLUNTARY BASIS ONLY
(')These actions are recommended for planning purposes. Protective action decisions at the time of the incident must take into consideration the impact of existing constraints.
INFORMATION ONLY O Form SPD-1002-1 DUKE POWER COMPANY (1) ID No: AP/0/B/1000/07 PROCEDURE PREPARATION Change (s) O to PROCESS RECORD 0 Incorporated OCONEE NUCLEAR (2) STATION:
(3) PROCEDURE TITLE: Procedure for Of fsite Dose Calculations by Control Room Personnel or Emergency Coordinator During A Loss of Coolant Accident (4) PREPARED BY: [MA/% DATE: c2 - 2 /, -[A (5) REVIEWED BY: DATE: ,2.[76[cP V Cross-Disciplinary ~ Review By: t</ 6 N/R:
(6) TEMPORARYAPPROVAL(IFNECESSARY):/
_ By: (SRO) Date:
[N By: Date:
(7) APPROVED BY: -a Date: "'M b " 1 (8) MISCELLANEOUS:
Reviewed /' - --By: N [h-4 Date: a Reviewed M By: gauct#l Date: 1 - Ab -h 2 V /
O v
l a
s
. /- AP/0/B/1000/07 l
PROCEDURE FOR OFFSITE DOSE CALCULATIONS BY CONTROL ROOM PERSONNEL OR EMERGENCY COORDINATOR DURING A LOSS OF COOLANT ACCIDENT
', 1.0 Symptoms s
4 1.1 RIA-4 reading increasing with indications of a loss of coolant accident.
1.1.1 RIA-4 reading < 30R (Case A) 1.1.2 RIA-4 reading > 30R (Case B) 2.0 Immediate Action 4 CASE A -- -
l 2.1 Automatic 2.1.1 None' 2.2 Manual 2.2.1 None 3.0 Subsequent Action 3.1 Deploy monitoring teams CASE B k
- 2.0 Immediate Action i 2.1 Automatic i
a 2.1.1 None ,
2.2 Manual .
! 2.2.1 Determine the reactor building dose rate by either of the
! following methods. Record dose rate on Enclosure 4.1, Step 3.
f i
2.2.1.1 Containment high range radiation monitor.
\
s/
m 2.2.1.2 Survey with a calibrated Eberline PIC-6A (or a similar hand held survey instrument) at one foot l
l
AP/0/B/1000/07 from the reactor building wall and four feet off
,-- the floor in the Reactor Building Purge Fan Room on the sixth floor of the Auxilliary Building of
[(_,/) the affected unit.
NOTE: A reading on the survey instrument ranging from <0 to 0.3R would indicate that the release source term is a gap activity release.
NOTE: i A reading on the survey instrument range from 0.3R to 3R would indicate that the release source term is a design basis accident.
2.2.2 This procedure is intended to provide on-shift personnel and members of the Technical Support Center a means of projecting offsite exposure levels for radiological ac-cidents at Oconee Nuclear Station. These dose projections can be made based upon the source of the release to the Reactor Building atmosphere and available tower meterologi- - _ .
cal data. It is intended that projections made by this procedure would be conservative and precede information available from field monitoring teams and the assumption of offsite dose projection responsibility by the Crisis Management Center. Recommendations for evacuation of offsite areas are to be made based on the calculations completed in this procedure.
NOTE: Health Physics personnel in both the Technical Support Center and the Crisis Management Center may use alternate means for projecting offsite dose when their organizations are-operational.
NOTE: If site meteorological data is not available, the data can be obtained from the National Weather Service office at the Greenville-Spartanburg Airport. (Number is listed in Emergency Telephone Directory).
The following are conversion formulas for the meteorological data obtained from the National Weather Service:
l mph = .869 (Knots)
- F = (9/5'C) + 32 2.2.3 The need for protective action should be reassessed every hour. The Control Room will complete the Offsite Dose
! Calculation every hour until the Technical Support Center is operational and are relieved by the Health Physics
(()g
}
Center.
l
l , AP/0/B/1000/07
! . i t
2.2.4 Complete Enclosure 4.1, Offsite Dose Calculation.
I 3.0 Subsequent Actions 1
- 3.1 After notifying the Station Manager of the results of the Offsite
! Dose Calcualtion, the Shift Supervisor / Emergency Coordinator will '
l provide the recommendations to the following agencies and record in ,
i Enclosure 4.1, Step 12. '
! 3.1.1 Pickens County Civil Defense l 3.1.2 Oconee County Emergency Preparedness
- 3.1.3 S. C. Bureau of Radiological Health i
- 3.2 Deploy onsite and offsite monitoring teams.
4.0 Enclosures 4.1 Offsite Dose Calculation 4.2 Survey Instrument Correlation 3
1 k
1 k
^
i d
1 J
6 A
f 4
1 i i e
i
! l t
i
AP/0/B/1000/07 f
- Page 1 of 5 )
1 1
ENCLOSURE 4.1 OCONEE NUCLEAR STATION v
0FFSITE DOSE CALCUI.ATION Unit Calculation performed by
- 1) Time now Date now Time of incident Date of incident Time (hours) since incident Wind speed mph Wind Direction (from) .1T F Weather conditions
- 2) Calculate TF (time factor) based upon time (hours) since incident from the table below and record value .
i Time Since Incident Time Time Since Incident Time In Hours Factor (TF) In Hours Factor (TF)
O.2 0.20 10 0.94 0.3 0.22 15 1.22 0.5 0.24 20 1.50 0.7 0.26 30 2.0 1.0 0.28 50 2.7 1.5 0.32 70 3.3 2.0 0.36 ; 100 4.2 3.0 0.44 ! 150 5.2 5.0 0.60 : 200 6.0
- 7.0 0.74 l 300 6.6
{ 500 6.6 4
- 3) Reactor Building DR (dose rate) by either a) or b).
a) Containment high range radiation monitor rem /hr.
! b) PIC-6-A (or similar hand held survey instrument) reading x correlation j
value (Encl. 4.2).
i i Survey Inst. x Corr. value = DR rem /hr.
! 4) Calculate DT (time determined dose)
Q DT = DR x TF L -- l
. AP/0/B/1000/07 Page 2 of 5
- 5) Is wind speed > 15 mph?
-O b) If yes, go to Step 7.
If no, go to Step 6.
- 6) Is time of day between 1000 hrs and 1600 hrs (10:00 am and 4:00 pm)?
If yes, go to Step 7.
If no, go to Step 11.
- 7) Calculate DW (wind determined dose) based upon DT and WS (wind speed)
DW =
y
- If WS 1 1.0 mph, use WS = 1.0 mph.
- 8) Determine distances and level of protective actions based upon DW and ,
AT*F from table below:
Number suffix of areas on evacuation map to be evacuated:
Children and pregnant women Everyone Find the horizontal row corresponding to the AT*F. Follow across the p row from left to right until,the box containing the calculated DW E 1 value is reached. Read down the vertical column to find the appro-V priate actions and the corresponding distances from the plant.
= to -1.3 12.09ES 2.09E5 to 7.8E5 7.8E5 to 3.9E6 >3'.9E6
-1.2 to -1.0 15.4E3 5.4E3 to 2.70E4 2.7E4 to 3.2E5 >3.2E5
-0.9 to -0.4 12.09E3 2.09E3 to 1.04E4 1.04E4 to 7.4E4 >7.4E4
-0.3 to +10.0 11.08E3 1.08E3 to 5.4E3 5.4E3 to 3.2E4 >3.2E4 No action Evacuate children Evacuate every- Evacuate procedure and pregnant wom- one 0-4 miles everyone is com- en 0-4 miles (Downwind areas 0-4 miles pleted (Downwind areas with suffix 1) (Downwind with suffix 1) area with suffix 1)
No action for Evacuate chil- Evacuate 4-10 miles dren and preg- everyone nant women 4-10 4-10 miles i
(Downwind areas (Downwind l
\ with suffix 2) areas with d .
suffix 2)
Example: If AT*F is -1.1 and DW is 2.9E4, evacuate everyone from 0-4 miles and children and pregnant women from 4-10 miles. I l
L
AP/0/B/1000/07
- Page 3 of 5
- 9) ~ a) Is wind speed > 3 mph?
i If yes, use table'in Step 9 b.
If no, assume sectors A, B, C, D, E, and F of evacuation map are affected.
-b) *
~ Wind direction (from) .
Find the wind direction and follow across the row to find the letter prefixes of the areas on the evacuation map to be evacu-ated and record.
Wind Direction Letter Prefixes of (From) Areas to be Evacuated 15 - 41* C,D,E 41* - 67* D, E 67 - 103 D,E,F 103* - 127* E, F 127* - 174* A,E,F 174* - 182* A, F 182 - 215 A,B,F 215* - 256 A, B 256* - 270* A,B,C 270* - 298* B, C 298* - 344* B,C,D 344* - 15 C, D -
c) Letter prefixes of areas on evacuation map to be evacuated .
- 10) Combine the numbers. determined in Step 8 combined with the letters from Step 9 to determine which sectors of evacuation map to evacuate.
Children and pregnant women
'Everyone
- The 2 mile Emergency Planning Zone on the evacuation map will always be
.g evacuated if evacuation 'of a,ny area is required.
,. AP/0/B/1000/07 Page 4 or 5
- 11) Use the table below if WS is 1 15 mph and time of day is not betwen
(
t i 1000 hrs and 1600 hrs.
\ '
Apply the DT value from Step 4 on the table below. Read the corres-ponding action in the column to the right and record.
DT PROTECTIVE ACTION 5 610 No protective action is necessary 610 to 3100 Evacuate children and pregnant women 0 to 4 miles in all directions (all areas with number suffix 1) 3100 to 15600 Evacuate everyone 0 to 4 miles in all directions. (All areas with number suffix 1). Evacuate children and pregnant women 4-10 miles in all directions. (All areas with number suffix 2)
> 15600 Evacuate everyone 0 to 10 miles in all directions. (All areas with number suffixes 1 and 2)
(v) Children and pregnant women Eve ryone The 2 mile Emergency Planning Zone on the evacuation map will always be evacuated if eva~cuation of any area is required.
- 12) Persons contacted and provided the protective action recommendations from Case B subsequent Actions, Step 3.0.
NAME POSITION PHONE NO. TIME CONTACTED a) b)
c) d)
, e)
\m/
)
4 i
AP/0/B/1000/07.
Page 5 of 5 Additional Notes or Comments 4
Y 4
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1 SURVEY INSTRUMENT CORRELATION CURVE
- Page 1 of TIME VS. CORRELATION FACTOR j 10 ENCLOSURE 4.2 l
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TIME (HRS. AFTER INCIDENT)
W on Form SPD-1002-1 ntu M_ ATION O'ffbY DUKE POWER COMPANY (1) ID No: HP/0/B/1009/12 PROCEDURE PREPARATION Change (s) I to PROCESS RECORD NA Incorporated (2) STATION: Oconee (3) PROCEDURE TITLE: Distribution of Potassium Iodide Tablets in the Event of a Radiolodine Release (4) PREPARED BY: /*Jr / Mc h DATE: 'C /2. [ 8'L (5) REVIEWED BY: M,w DATE: 2 " 2 8 - @ 7.-
Cross-Disciplinary Rev v By: N/R: 4 (6) TEMPORARY APPROVAL (IF NECESSARY):
By: (SRO) Date:
O- By- n Date:
(7) APPROVED BY: h ig , Date: 2N (8) MISCELLANEOUS:
Reviewed / Approved By: [','e , // Date: vi tr/ d-Reviewed / Approved By: // 'Date:
O I
HP/0/B/1009/12 v)
DUKE POWER COMPANY OCONEE NUCLEAR STATION DISTRIBUTION OF POTASSIUM IODIDE TABLETS IN THE EVENT OF A RADI0 IODINE RELEASE 1.0 Pu rpose This procedure provides information necessary to distribute Active Potassium Iodide (KI) tablets to inplant personnel in the event of a release of radioiodine. Also, it outlines storage and supply information to assure sufficient quality and quantity of thyroid blocking material.
2.0 References 2.1 NCRP Report No. 55; Protection of the Thyroid Gland in the Event of Releases of Radioiodine 1977 2.2 NCRP Report No. 65; Management of Persons Accidentally
[ Contaminated with Radioiodine 1980 2.3 Body Burden Analysis procedure 2.4 System Health Physics Manual 2.5 NUREG 0654 1
3.0 Limits and Precautions 3.1 Persons who are allergic to KI must not receive these tablets.
3.2 Nursing mothers who receive KI tablets must be advised to use nutrient substitutes (ex: milk or a formula) for children for the duration of the ten-day tablet use period.
l l 3.3 Personnel must be advised not to deviate from prescribed dosages and dosage rates.
3.4 Best results will be achieved when KI tablets are administered
, immediately (within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) after an exposure, although adminis-l tration as late as 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after an emergency will be of (limited) value.
3.5 Discolored or disfigured tablets, tablets that have reached the l s_ expiration date listed on bottles, and bottles of KI with loose tops shall be discarded.
I t .
3.6 Hands of personnel must be free from contamination prior to taking I'_s\
t KI tablets.
V) 4.0 Procedure 4.1 Responsibilities for Distribution 4.1.1 Persons suspected of having been in the affected area prior to detection and during the release, persons present in the affected area, and persons who will enter the area while a significant amount of radioiodine is present will be instructed by the Station Health Physicist to immediately register in the KI distribution center (for example, the Technical Support Center (TSC) for each unit).
NOTE: A significant amount of radioiodine in this case
- is that amount taken into the body that would result in a quarterly permissible occupational dose, or more. For example, exposure to 4.6 x 10 8 pCi/ml airborne iodine for one hour would result in such an exposure. This corresponds to 520 MPC-brs which is the quarterly limit.
4.2 Registration of persons exposed to a significant amount of radioiodine 4.2.1 When persons notified by Health Physics arrive at the distribution area, record appropriate data per Enclosure 5.-l.
4.2.2 The Station Health Physicist or his designee should give one (1) tablet to each affected person and instructions con-cerning the use of the tablet. Then issue to each affected
~
~
person one bottle containing nine'(9) KI tablets, and the package insert for the use of the tablets (refer to Enclo-sure 5.2 for an example of the package insert).
4.2.2.1 Tablets are to be taken only as directed. One (1) tablet per day for ten (10) days is the recommended dosage.
4.2.2.2 After the initial dose of KI, subsequent doses will be taken on a daily basis. Tablets should be taken as near a 24-hour schedule as possible.
NOTE: For best results, emphasis must be j placed upon the proper use of these i tablets.
4.2.3 Tablets removed from full bottles of KI should be stored in 10 ml plastic vials. The expiration date on the battle from which the tablets were taken and the name of the Health Physics representative must be recorded on the 10
.\ .
ml vials. Tablets stored in 10 ml plastic vials should then be used for the single tablet initial issuance of KI to affected persons.
1 l
, 4.3 Thyroid Burden Analysis Following Radioiodine Exposure
- /~'s
\
'\ _,/ 4.3.1 All personnel receiving KI tablets should receive a thyroid scan. If the number of people render this step .
impractical, the Count Room Supervisor should draw a l representative sample of persons listed on Enclosure 5.1 who received KI tablets.
NOTE: Subsequent action involving thyroid burden analysis should follow guidelines established in the System Health Physics Manual.
4.3.2 Records of thyroid scan should be maintained per procedure.
NOTE: . Thyroid scans immediately after an accident could lengthen KI distribution time and cause confusion among personnel. Distribute KI before analyzing thyroid concentration.
4.4 Storage Requirements 4.4.1 There are three major storage requirements to be observed:
4.4.1.1 Store in a temperature range of 59 to 86 degrees F.
[ } 4.4.1.2 Store in a low humidity area (avoid direct
\d exposure to liquids).
4.4.1.3 Store in an area protected from exposure to light.
4.4.2 Upon receiving a shipment of KI, boxes should be opened as soon as possible and bottles examined to ensure that an airtight seal has been maintained. Bottles must be returned to boxes, and boxes must be sealed shut, so as to avoid exposure to light.
4.4.3 To ensure a sufficient supply of tablets, a minimum of 1,000 bottles with 14 tablets per bottle should be main-tained on-site.
4.5 Shelf Life and Changeout of KI Tablets 4.5.1 Thryo Block " tablet bottles are labelled with an expiration date from the factory. As tablets reach the expiration dates, the tablets must be discarded.
- NOTE
- Replacement tablets should be ordered at least three (3) months prior to the date of expiration
(}
\._J listed on the bottles of KI.
l I
1
i 4 t
, . t i -
f 4.5.2 Upon receiving a shipment of KI tablets, supplies should be shifted so as to use older tablets before new tablets.
l l 4.5.3 After the radioiodine emergency, tablets in the 10 ml plastic vials must be discarded.
I i
- 5.0
Enclosure:
- 5.1 Potassium Iodide Tablet Distribution Data Sheet i
5.2 Package Insert for Thyro-Slock TM
, Tablets and Solution 1
i-i e
4 1
1 J
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i 1
l 4
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- , _ . . - . . - , _ - - - - , -, ._- _ _.-, - . .,_ ..._. - - - , , - , _ . _-. .. . . _ . . _ . _ ~
s
,- ENCLOSURE 5.1
'sx.- . POTASSIUM IODIDE TABLET DISTRIBUTION DATA SHEET HP BADGE DATE & TIME OF DATE & TIME OF NUMBER NAME DEPARTMENT SUSPECTED EXPOSURE INITI.E ISSUANCE 6
7'.
i t,
Nv 9
i N
~
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(( Enclosure 5.2 .
Page 1 of 2 TM Package Insert for Thyro-Block Tablets and Solution t
I d P.u.nt Package insert For s
THYRO. BLOCK" '
r\
.w (POTASSIUM 100000
- (pronovaced poo. TASS +um EYE.otHsyed)
{ . (seereviated: KI) i TABLETS and SOLUTION U.S.P.
s N
(
IF YOU ARE TOLD TO TAKE THIS MEDICINE. TAKE IT ONE TIME EVERY 24 HOURS. DO NOT TAKE IT MORE
' OFTEN. MORE WILL NOT HELP YOU AND' MAY IN.
' CREASE THE RISK OF SIDE EFFECTS. DO NOT TAXB THIS DRUG IF YOU KNOW YOU ARE AtLRRGIC' TO IODIDE. (SEE SIDE EFFECTS BELOW.)
INDICATIONS \
THYROID BLOCKING IN A RADIATION EMERGENCY'
/ ONLY.
DIRECTIONS FOR USE Use only as directed by State or local public health authorities in the event of a radiation emergency.
DOSE Tableta: ADULTS AND CHILDREN 1 YEAR OF AOE OR OLDER: One (1) tai >let once a day. Crush for smallchudren. '
BABIES UNDER 1 YEAR OF AGE:
One. half (1/2) tablet once a day. Crush' first.
' solution: . ADULTS AND CHILDREN 1 YEAR OF AGE OR OLDER: Add 6 drope to one.
g half glass ofliquid and drink each day.
BABIES UNDER 1 YEAR OF AGE:
Add 3 drops to a small ===t of liquid once a day.
For alldesere forms: Take for 10 days unless drected o'.herwise i
by State or local public health authorities.
I Stue at controlled room tempetsture besween 15' and 30*C (59' 1
to 86'F). Keep container tightly closed and protect from Eght.
Do not use the solution ifit appears brownsh in the nozzle of ehe kth
\'
s WARNING 'N
- Posessium iodade sheadd not be used bypeople cuergsc to iodide.
, Keep out of the reach of chudren. In case of overdose or allergic reaction, contact a physician or the public health authrity.
I DESCRIPTION Each THYROraLOCKW TABLET containe 130 mg of
. ., y .
Each dro p - ' p of iodide.
THYRO.BLOCKSSOLUTION contains 21 mg of i
Enclosure 5.2 ,Page 2 of 2
^
6 HOW POTASSIUM IODIDE WORKS '
Certain forms of iodine help your thyroid gland work right. Most people get the iodine they need from foods,like iodized salt or '
ilsk. The thyroid can " store" or hold only a certain amount of
/e iodine.
In a radiation emergency. radioactive lodine may be released in ,
the air. This material may be breathed or swallowed. It may enter the thyroid gland and damage it. The damage would pro.
~
bably not show itself for years. Children _are most likely to have thyroid damage.~
If you take potassium iodide, it will fill-up your thyroid gland.
nis reduces the chance that harmful radioactive iodine wi!! ;
enter the, thyroid gland.
i
- WHO SHOULD NOT TAKE POTASSIUM IODIDE The only people who should.not take potassium iodide are people who know they are allergic to iodide. You may take potassium lodido even if you are taking medicines for a thyroid problem (for -
example, a thyroid hormono or antithyroid drug). Pregnant and nursing women and babies and children may also take this drug. -
s HOW AND WHEN TO TAKE POTASSIUM IODIDE Potassium Iodide should be '=1ran as soon se possible a(ter public health officials tell you. You should take one dose every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. More will not help you because the thyroid can " hold ** on- ?
ly limited amounts of iodine. Larger doses willincrease the risk '
of side effects. You will probably be told not to take the drug for more than 10 days.
% SIDE EFFECTS Usually, side effects of potassium iodide happen when people '
take higher dosee 'or a long time. You should be careful not to take more than the reco===adad dose or take it for longer than you are told. Side effects are unlikely because of the low dose and the snort tune you will be talang the drug.
Possible side effects include skin rashes, swelling of the salivary glands, and "lodism" (metalhe tasta, barning mouth and throat, sore teeth and gums, symptoms of a head cold, and sometunes stomach upset and diarrhaal.
A few people have as allergic reaction with more serious symp-tems. name could be fever and joint pains, or sweihng of parts of the face and body and at times severe shortness of breath requir-ing immediate madu..I attention.
Taking lodido may rarely cause overactivity of the thyroid gland, underactivity of the thyroid gland. or enlargement of the thyroid gland (soitart.
WHAT TO DO IF SIDE EFFECTS OCCUR If the side effects are severe or if you have an allergic reaction, stop taking potassium iodide. Then, if possible, call a doctor or public baalth authority for instructions.
HOW SUPPLIED THYRO.BLOCKW TABLETS (Potassium Iodide. U.S.P.) bot.
ties of 14 tablets (NDC 0037 0472-20.1 Each whita. round, scored tables contains 130 mg potasemm iodide.
THYRO.BIACKm SOLUTION (Potasemm Iodide Solution.
U.S.P.) 30 ml11 fl. os.) light reenstant, m A.,. -n-; ==g
. WALLACE LA80AATOfutS Dinoson of CARTER WALLACE. INC.
Craneury. How Jersey 00512 CW-107915-10r19 issue 10rt9
l .
,I o ,o,, ,, _ INFORMATION DNLY
.j DUKE POWER COMPANY (1) ID No: HP/0/8/1009/16 PROCEDURE PREPARATION Change (s) I to j PROCESS RECORD _NA Incorporated s
(2) STATION: Oconee (3) PROCEDURE TITLE: Procedure for Emeroency Decontamination of Perennnat and Vehicles On Site and From Off-Site Remote Assembly Area (4) PREPARED BY: , DATE:
(5) REVIEWED BY: h* -DATE: 2 ~ 2. [- F Z.
Cross-Disciplinary Revi By: N/R: t1 (6) TEMPORARY APPROVAL (IF NECESSARY):
By: (SRO) Date:
'd By: A n Date:
A (7) APPROVED BY: f Date: 3 L (8) MISCELLANEOUS:
Reviewed / Approved By dA / .4 Date: [ j JQ (v jp 7 y Reviewed / Approved By: / Date:
e
>V
i
. -s i 8 i HP/0/B/1009/16 1
DUKE POWER COMPANY OCONEE NUCLEAR STATION 9 PROCEDURE FOR EMERGENCY DECONTAMINATION OF PERSONNEL d AND VEHICLES ON SITE AND FROM OFFSITE REMOTE j ASSEMBLY AREA.
1.0 Purpose
- To provide a procedure for decontamination of personnel and personal vehicles during a radiological emergency condition from both an onsite and offsite assembly area and to provide a procedure for a quarterly a audit of the decontamination supplies.
2.0 References 2.1 NUREG 0654, FEMA-REP-1, Rev. 1, Criteria for Preparation and Evalua-tion of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.
2.2 Oconee Nuclear Station Emergency Plan l O 3.0 Limits and Precautions 3.1 If the radiological emergency should occur during normal working hours, personal vehicles would not be used for evacuation purposes -
should it be' determined by the Emergency Coordinator that time to decontaminate cars would affect the safety of station personnel.
Bus transportation would be obtained from the Oconee County Bus Transportation Department by the Technical Support Center or the Crisis Management Center.
3.2 Keys to the appropriate school and cabinets should be obtained by Health Physics technicians from Security in the Control Room.
3.3 Security guards will assist in maintaining order during the exit from the station and will secure all gates to make sure egress is from the recommended exit.
4.0 Procedure 4.1 Onsite-Personnel & Vehicle Decontamination Procedure for Evacuation
)
4.1.1 Should evacuation become necessary, personnel should exit 4
the station through the Personnel Access Portal.
[ 'h/
.( s_,
4.1.2 Health Physics technicians shall perform a whole body survey of personnel with a Model E-120 Geiger Counter survey instrument and release personnel at < 2 mrem /hr to Keowee or Daniel High School. (See Enclosure 5.2)
'[ } 4.1.2.1 Personnel with dose rate survey readings greater
, \Q than 2 mrem /hr should use showers in the mainte-
- nance locker room with Health Physics supervising
{ decontamination efforts. These personnel should be released at a dose rate < 2 mrem /hr to Keowee
, or Daniel High School. (See Enclosure 5.2)
)
+ 4.1.2.1.1 Complete Enclosure 5.3 Initial Personnel
- Contamination Form for those persons contaminated to levels > 2 mrem /hr.
4.1.2.1.2 Enclosure 5.3 shall be retained by the Station Health Physicist for dose
.i assessment information.
4.1.2.2 Rotate use of showers--male at one t'ime interval, female the next time interval, etc.
4.1.3 If time permits, a hose station should be used to wash
-down-vehicles external contamination to levels of < 2 mrem /hr. Health Physics Technicians should secure hose from hose cabinets and attach hose to fire hydrants at the designated exit point from the station as shown below.
~
The Emergency Coordinator shall determine which exit to use by using meteorological information from the control g3 room together with recommendations from the Station Health
' Physicist.
b) 1. Exit from station - North 130. Administration Building Fire Hydrants.
- 2. Exit from station - South 183 - Intake road. CCW Fire Hydrant.
- 3. Exit from station South 183. 230 kv Switchyard Fire Hydrant.
4.1.3.1 Health Physics technicians with Model E-120 Geiger Counter instruments shall survey vehicles for release at < 2 mrem /hr. Health Physics will determine need for protective clothing and breathing protection to be worn by technicians.
4.1.3.2 Private vendor personnel, dressed in protective clothing (i.e. wet suits and respirators if l warranted) will wash down vehicles if required
, by H.P.
4.2 Offsite-Decontamination of Personnel and Vehicles at Keowee/ Daniel High School (See Enclosure 5.5 for maps of the schools) l
['(__,)
h 4.2.1 With the appropriate key, the Health Physics Technicians will go to the designated school. The Technician will i
establish the deconcamination area and await the evacuated
! personnel, i
') 4.2.2 Health Physics Technicians will survey personnel with
/ RM-14 instruments with thin window GM detectors and decon-
- s 3 taminate and release personnel in accordance with limits j specified in procedure HP/0/B/1005/11.
i j 4.2.3 Health Physics shall periodically collect waste water j samples for analysis using the 1 liter bottles found in j the decontamination supplies.
4.2.4 After all personnel have exited and the building is no
- longer needed, a private vendor shall decontaminate build-ing, site and private vehicles to levels < 200 dpm/100cm 2 y and < .05 mrem /hr.
~
4.2.5 Complete release card for all personnel, Enclosure 5.1.
Give one copy to individual and retain the other for personnel folder and exposure records.
4.3 Quarterly, Audit Offsite Emergency Decontamination Supplies
- 4.3.1 Once a quarter, audit the Offsite Emerge cy Decontamina-tion supplies at both Keowee and Daniel High School using Enclosure 5.4. Supplies must also be audited after each use in a drill or actual emergency upon returning to normal operating conditions.
/~\ 4.3.2 Upon completing the inventory, Enclosure 5.6 must be
)
(V filled out if any items are missing. Missing items must be replaced within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. If the missing items cannot be replaced within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the Station Health Physicist will evaluate the consequences the missing items will have -
on~0ffsite Emergency Decontamination.
4.2.3.1 Complete Enclosure 5.6 as follows:
a) under the column, Deviation Description, write the items that are missing.
b) under the column, Action Taken to Remedy Deviation, identify action taken to replace missing items.
c) under the column, Completion Date (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />),
note the date the missing items were replaced.
d) sign and date the form in the appropriate column.
]'
5.0 Enclosures .
5.1 Individual Contamination Exposure Levels U ,
l
4 i
l i
5.2 Emergency Evacuation Routes from Station
,: 5.3 Initial Personnel Contamination Record b
'l i 5.4 Decontamination Supplies Inventory List s'
L'l 5.5 D. W. Daniel High School and Keowee School it
! 5.6 Emergency Supplies Deviation Authorization Sheet i
i
+
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DUKE POWER COMPANY HP/0/B/1009/16 OCONEE NUCLEAR STATION 1 j(N .
4 Enclosure 5.1 j INDIVIDUAL CONTAMINATION EXPOSURE LEVELS -
',I
}
t I
i LICENSEE !
Date:
Duke Power Company Time:
i IDENTIFICATION INFORMATION Name: Social Security Number:
HP Badge Number: Employer:
CONTAMINATION EXPOSURE LEVELS Instrument Used:
Instrument Reading:
RM-14 with thin window detector
) Date Employee Signature Remarks Address To the individual named above:
This report is furnished to you so that you have a prompt record of your radiation contamination level.
f\
\- Copies to: G.O. HP Station Health Physicist Individual Employer Individual File Date
O O O tv T Pickens To Salm I
l 18 To Wallalla 183 g p
30 N f I 18 h 88 O 160 i
a Keouce
- E Ey School 133 y 8
'To Seneca- ( %
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U EMERCENCY EVACUATION ROUTES FROM STATION "
4l ASSEMBLY AREAS:
To be determined by Emergency Coordinator
- 1. Keowee School ,
. .x 2 Daniel liigh School d T
R Daniel -
liigh 3 Scimol D e
, , To Clemson
Enclosure 5.3 HP/0/B/1009/16
! '[/ ; OCONEE NUCLEAR STATION U I INITIAL PERSONNEL CONTAMINATION RECORD i
NAME HP BADGE INITIAL DOSE DOSE RATE (mrem /hr)
+ NUMBER RATE (mrem /hr) After Decon
1 i .
! ENCLOSURE 5.4 i s HP/0/B/1009/16 LIST OF SUPPLIES FOR DECONTAMINATION OFFSITE Date/ Initials
____/ 1 copy Station Directive 3.8.18
/ 1 copy Health Physics Procedure HP/0/B/1005/11
/ 100 min Individual Contamination Exposure forms (Enclosure 5.1)
/ 50 bars Ivory Soap
/ 2 bundles Cotton Glove Liners
/ 2 boxes PVC Gloves
/ 50 pair Disposable Shoe Covers
/ 50 pair Disposable Coveralls (Blue)
/ 50 ea. Large Poly Bags
/ 50 ea. Small Poly Bags O / 100 ea. Nucon Smears
/ 1 roll 2" Masking Tape
/ 1 roll 50~ Yard Barricade Tape (Magenta & Yellow)
/ 50 ea. Caution: Radiation / Radioactive Material Tags
/ 2.ea. Caution Sign w/ Radiation Area, Radioactive Material, and Contaminated Area Inserts
/ 10 ea. STEP OFF Pads
/ 1 gal. bottle 4324 Turco Decon Soap
/ 5 ea. Nail Brushes
. / 5 packages Cotton Swabs
/ 1 pair Scissors
/ 2 cans Hand Cream
/ 5 bottles Prell Shampoo
\_,) / 100 ea. Cloth Towels W
-,a,m .- ... ... . --.....-. - - . . - - -- . -
) ENCLOSURE 5.4 3
h HP/0/B/1009/16 LIST OF SUPPLIES FOR DECONTAMINATION OFFSITE
- (Continued)-
?
l Date/ Initials
/
- 3 ea. RM 14/15 Instruments with thin window detector
/
- 2 ea. Eberline E120 Geiger Counter
/ 5 ea. Poly Bottles - 1 liter size
/ 1 box Black Marker Pens
/ 1 box Pens
/ 1 box Pencils
/ 2 Pads Writing Tablet
- These will be located at Oconee Nuclear Station 6
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HP/0/B/1009/16 ,
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