ML20081G337
| ML20081G337 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/19/1983 |
| From: | James Smith DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML16162A500 | List: |
| References | |
| PROC-830819-01, NUDOCS 8311040206 | |
| Download: ML20081G337 (150) | |
Text
{{#Wiki_filter:< , , I, i ^ DUKE POWER . COMPANY , OCONEE i l NUCLEAR - l STATION , l
. EMERGENCY PLAN l IMPLEMENTING PROCEDURES :
m i , k l l -- DUKE F0WERJ j Yhy l
.. 4 i APPROVED:
J. $' Smith, Station Manager August 18. 1983 Date Approved Auru a 19_ 1983 Revision 83-6 l f$kI$po$ho$00 F 1 l
l e I TABLE OF CONTENTS
\
Emergency Telephone Numbers - (06/30/83, Rev. 11) AP/0/B/1000/01 Event Index - (10/29/82) AP/0/B/1000/02 Unusual Event - (08/10/83) AP/0/B/1000/03 Alert - (08/10/83) AP/0/B/1000/04 Site Area Emergency - (08/10/83) AP/0/B/1000/05 General Emergency - (08/10/83) AP/0/B/1000/06 Procedure for Initiating Protective Action Guides for the General Public in the Emer-gency Planning Zone - (08/10/83) AP/0/B/1000/07 Procedure for Offsite Dose Calculations by Control Room Personnel or Emergency Coordinator during a Radiological Accident - (06/09/83) AP/0/B/1000/08 Procedure for Response Actions for Accidents / Emergencies - (09/03/82) AP/0/A/1000/10 Procedure for Emergency Evacuation of Station Personnel - (05/05/82) Station Directive 2.9.1 Station Assembly and Evacuation Procedure -
, (04/14/82)
Station Directive 2.9.2 Emergency Response Organization - (06/23/82) PT/0/B/2000/04 Procedure for Establishment and Inspec' tion of the Technical Support Center - (08/09/82) PT/0/B/2000/05 Oconee Nuclear Data Transmission from TSC (09/15/82) 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)
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Revision 83 August 19, 1983
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. E2fERGENCY TELEPHONE NUlfBERS This enclosure provides a listing of telephone numbers for various personnel and agencies that may have a part in dealing with an emergency situation or providing other assistance as needed at Oconee Nuclear Station.
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.s EMERGENCY TELEPHONE NUMBERS
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i j This directory provides a listing of telephone numbers for various personnel and agencies that may have a part in dealing with an emergency situation or providing other assistance as needed at Oconee Nuclear Station. TABLE OF CONTENTS NOTITICATION OF AGENCIES, CRISIS MANAGEMENT TEAM, KEY COMPANIES. . . . 1- 5 I RMERGENCY FACILITT LOCATIONS. . . . . . . . . . . . . . . . . . .... 6 OCONEE TELEPHONE ACCESS CODES. . . . . . . . . . . . . . . . . ..... 7 TECHNICAL SUPPORT CENTER. . . . . . . . . . . . . . . . . . . . .... 8 - 10 OPERATIONAL SUPPORT CENTER. . . . . . . . . . . . . . . . . . . .... 9 HEALTH PHYSICS CENTER. . . . . . . . . . . . . . . . . . . . . ..... 8
. COMMUNICATIONS COORDINATION. . . . . . . . . . . . . . . . . . . . . . . 10 CRISIS MANAGEMENT CENTER. . . . . . . . . . . . . . . . . . . . . . . 11 - 13 GENERAL OFFICE SUPPORT CENTER . . . . . . . . . . . . . . . . . . . . . 12
, BACEUP CRISIS MANAGEMENT CENTER - (Liberty). . . . . . . . . . . . . . . 13
- CRISIS NEWS CENTER. . . . . . . . . . . . . . . . . . . . . . . . . 14
- NUCLEAR REGULATORY COMMISSION. . . . . . . . . . . . . . . . . . . . . . 5 "1 ,
! NRC HEALTH PHYSICS NETWORK TELEPHONES. . . . . . . . . . . . . . . . . . . 15 3 DUKE EMERGENCY RADIO. . . . . . . . . . . . . . . . . . . . . . ..... 16 EMERGENCY NUMRFRM -*Pickens County. . . . . . . . . . . . . . . . . . . . 17 EMERGENCY NUMBERM - Oconee County. . . . . . . . . . . . . . . ...... 18 f
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, OCONEE NUCLEAR STATION l NUMBER CODE FOR IDENTIFYING PERSONNEL / ACTIVITIES TO BE NOTIFIED CODE
- 1. NUCLEAR REGULATORY COMMISSION by Red Phone within one hour.
- 2. UNIT COORDINATOR /0PERATIONS DUTY ENGINEER who will notify:
f i : A. Superintendent of Operations i B. Station Manager / Emergency Coordinator (or alternate as listed in number 11.) C. Nuclear Production Duty Engineer who will notify: - 704-373-5491
- 1. Corporate Communications '
- 2. Crisis Management Organs.zation
(
; 3. STATION MANAGER ... . .......... . . . . . ..
-i J. Ed Smith, Office . . ...... . . . . . . . . . .. Ext. 1211 Home
... .......... . . . . . .. 654-2866
- 4. BABCOCK AND WILCOI RESIDENT ENGI1EER
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j Bill Street, Office 1
. . ......... . . . . . . .. Ext. 1140
., Home ... ................. 868-2158 (If Bill Street cannot be reached, call)
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,, L. H. Williams, Office . . ................ Ext. 1459 i
Home . . .............. . . . 654-3213 l
. 5. STATION HEALTH PHYSICIST /DUIT HEALTH PHYSICIST C. T. Yongue, Office . . ...... . . . . . . . . . . . Ext. 1234
, .i Home . . . . . . . . . . . . . . . . . . . . 868-9411 , l9 9 ' s i
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.i 6. SOUTH CAROLINA DEPARTMENT OF HEALTH AND ENVIRONMENTAL CONTROL, (Warning Point State of South Carolina) -]~~
Bureau of Radiological Health (0800-1700). . . . . .. .. . 758-5548 Answering Service after hours, weekends, holidays. .... . 758-5531
- State Emergency Operations Center, Columbia, S.C. . . 758-2826
- Forward Emergency Operations Center, Clemson, S. C. . . Duke Ringdown Alternate Number . . . .. 654-9371
- NOTE: These numbers are to be used once the State has established their Emergency Operations.
- 7. COUNTY EMERGENCY PREPAREDNESS AGENCIES
; Oconee County Emergency Preparedness . . . . . . . ... . . Duke Ringdown j Alternate Number - 24 hour, page 251 638-3097 Alternate Number - 24 hour, page 251 638-3678 Pickens County Emergency Preparedness. . . . .. . . . . . . Duke Ringdown Alternate Number - (0830-1700) 878-7808 Alternate Number - 24 hour, page 77 878-2421
- 8. COUNTY 'R N TF'S DEPARTMENTS
.' b.
i Oconee County (24 hours) . . . . . . . . . . . . . . . . . . Duke Ringdown
. Alternate Number . . ..... 638-3678 Pickens County (24 hours) . . . . . . . . . . . . . . . . . Duke Ringdown Alternate Number . . ..... 87'8-2421 1
Alternate Number . . ..... 855-1666 Alternate Number . . . . . . .878-3500
- 9. MEDICAL ASSISTANCE y Oconee Memorial Hospital Ambulance Service . .. . ..... 882-4611 Oconee Memorial Hospital Switchboard / Supervisor or Nursing . 882-3351 Additional Medical assistance may be provided through the
! following institutions: l Pickens County Ambulance Service . . . . . . . . . ..... 868-2373 Cannon Memorial Hospital / Supervisor of Nursing . . ...... 878-4791 Easley Baptist Hospital / Supervisor of Nursing . . ...... 859-6365 i
- 10. FIRE ASSISTANCE
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i Oconee. County Rural Fire Protection Association . . . . . . . 638-5846 m
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l iioods or Forest Fire (Oconee County, Oakway Tower) . . . . . . 972-3600 - lj Woods or Forest Fire (Pickens County, Woodall Mt. Tower) . . . 868-9056
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! (If the first person cannot be reached, go to the next person down 's' e list until one person is contacted) 1 Emergency Coordinator / Station Manager J. E. Smith, Office . . . . . ............. Ext. 1211 Home . . . . . . . . ........... 654-2866 Superintendent of Technical Services ~
T. B. Owen, Office . . . . . ............ Ext. 1213 Home . . . . . . ............ 882-1499 Superintendent of Maintenance J. M. Davis, Office . . . . . ............ Ext. 1227 Home . . . . . . ............ 647-9721 1 Superintendent of Operations l l J. N. Pope, Office . . . . . ............ Ext. 1210 1 Home l
. . . . . . ............ 882-3866 e
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- 12. WATER DEPAR'l?fENTS l
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- Should releases of radioactive effluent into Lake Keowee or lake Hartwell j potentially effect municipal water intakes or exceed technical specifi-I cations. Contact the appropriate authorities as indicated below:
Lake Keowee m Seneca, H. J. Balding, Office . . . . . . . . . . . . 882-8359 Home . ...... . . . . . . 882-1005
- Lake Hartwell City of Clemson Mayor of Clemson, Office ..... ......... 654-2636 Home ...... ......... 654-1785 (If the mayor cannot be reached, call one of the following)
Clemson Administrator's Office . .......... 654-2636 Home . . .......... 654-6263 Clemson Filter Plant (0700-1700) .......... 654-1550
. , Clemson University President's Office . . ....... . . . . . ... 656-3413 654-2466 Home . . . ...... ........, 656-2340
' Security - Police (24 hours) . . .......... 656-2222 (If the President cannot be reached, call) -
Clemson University Physical Plant (0800-1630) . . . . 656-2186 Anderson Water Works (24 Hr. Number) . . . . . . . . . . . 226-9676 AGENCIES THAT MAY RESPOND TO AN EMERGENCY AT THE OCONEE NUCLEAR STATION LAW ENFORCEMENT l S. C. Highway Patrol (Greenville, S.C.) . ........ 235-7471 S. C. Enforcement Division (Columbia, S.C.) ....... 758-6000 FBI (Columbia, S.C.) . . . . (24 hours). . . . . . . . . 254-3011 L; BOMB DISPOSAL , l t Explosives ordinance Disposal Control . . . ....... 751-5126 _, , (Fort Jackson, Columbia, S.C.) {'% - 1 3 ,<f l1
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, RADIATION AND CONTAMINATION j REACTS, Department of Energy (Oak Ridge, Tennessee) . . 615-482-2441 i (24 hr. number - after 1700 ask for Beeper number) . . 241
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DOE Emergency Radiological Monitoring Team (Aiken, S.C.) . 725-3333
.4 (24 hrs.)
N. C. Division of Emergency Management . ......... 919-733-3861
- 4 (Warning Point - State of North Carolina) (24 hrs)
Georgia Department of Natural Resources
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Environmental Radiation Program . .......... 404-656-4300 (Warning Point - State of Georgia) (24 hrs.) NUCI. EAR REGUI.ATORY C019 FISSION NRC Operationa Center (via Bethesda Central Office) . . . 202-951-0550 j NRC Operations Center (via Silver Spring Central Office) . 301-427-4056 Health Physics Network to NRC Operations Center ..... 22 Health Physics Network to NRC, Region II 23
!' NRC Operator (Via Bethesda Central Office) . . . . . . . . 301-492-7000 US NRC, Region II (Operations Center) . . . . . . . . . . . 404-221-4503 US NRC, Oconee Resident Inspectors . . ... . . ...... 882-5363
, Ext. 1108 Jack Bryant Home 882-4527 Dolan Falconer Home ~ 654-6693
, BUS TRANSPORTATION Anderson Retail Office (24 hour number) . . . . . . . . . . 224-6363 (Contact Ken Kernodle, Jerry Whitfield)
NATIONAL WEATHER SERVICE - METEOROLOGICAL BACK-UP S011RCE l Greenville-Spartanburg Weather Service . . . . (24 hour) . 877-6998 C i
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'l OCONEE NUCLEAR STATION
- CRISIS cot!!!UNICATIONS 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 1 and 2 Control Room. The corporate emergency organization will operate from the Crisis !!anagement Center located in the Visitors Center and Oconee Training Center.
is ElfERGENCY FACILITY LOCATIONS Technical Support Center - Control Rooms 1 and 2 --
; Operational Support Center - Control Room 3 ~
Crisis Manasement Center - Oconee Training Center Alternate Location: Liberty Retail Offica a 8 Crisis News Center - Keowee-Tozaway Visitors Center
- Alternate Location- Liberty Retail Office 1,
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'i OCONEE NUCLEAR STATION i TELEPHONE DIRECTORY .
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i Seneca Lines 882-5363 I (803) 882-5368 882-5369 882-5370 g 882-5371 Easley Lines 859-0108 (803) 859-0113 859-0116 Anderson Line 224-8376 l (803) Six Mile Line 868-2717 (803)
,' Dial Code 80 (Charlotte General Office)
(Micro-Wave) 80-188 (Catawba) 80-212 (McGuire) 80-115 (Cherokee) 3 0 Attendant (To access Bell Line)
. 9 Seneca --
60 Easley e 61 Anderson 63 Six Mile I 3 l, '
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l 1 N 9 OCONEE NUCLEAR STATION t* 1 4 CRISIS PHONE DIRECTORY i 4 i
.i TECHNICAL SUPPORT CENTER a
I Telephone Number 882-5363
. Outside Station POSITION /NAME Line Number Emergency Coordinator . . . . . . . . ....... 882-7076 1211 'i Supt. of Operations . . . . . . . . . . . . . ... 1210 Supt. of Technical Services . . .......... 1213 i
i i Supt. of Maintenance ............... . 1227 f Supt. of Administration . . . . . . . ....... 1212 t NRC Resident Engineer . . . . . . . . . . . . . FTS 677-9309 1108 B&W Resident Engineer . . . . . . . . . . . . . . . 1140 Station Health Physicist ............. 1234
, HEALTH PHYSICS CENTER 1276, 1480 Field Monitoring Coordinator ........... 1417 Data Report Coordinator (Off-Site Dose Projection) 1138 Dose Coordination to CMC . . . . ....... 1236 j FTS Line to NRC ............... .
677-9309
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j Surveillance and Control Coordinator ....... 1519
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.a . g Support Functions Coordinator . . . . . . . . . . . . 1179 i: ._ 1 l4 .J i '. l Rev. 11, 6/30/83
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) 882-5363 .; Outside Station i Line Number i
1 TECHNICAL SERVICES GROUP (Located in Computer Room CR 1&2) Performance . . . . . . . . . . . . . . . ..... 1409 Licensing and Projects ......... ..... 1229 h istry . . . . . . . . . . . . ......... 1220 OPERATIONAL SUPPORT CENTER 1387 3 (Support group consists of Health Physics, Chemistry, Maintenance, l Safety Operations group) i Dosimetry Recorda ............... 1178 Operational Support Center Coordinator . . . . 1216 Mechanical Maintenance Engineer ....... 1223 Mechanical Maintenance Supervisor . . . . 1440 1 I & F. Engineer . ............... 1219 I & E Supervisor . . . ......... 1189 [ Health Physics Support . . . ......... - 1190 Dose Control .............. -- 1178 S & C Coordinator . . . . . . . . . . . . 1365, 1579
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Support Function Coordinator. . . . . . . 1179 Chemistry Support . ... . . . . ....... 1165 Medical Support ............... 1151-
, Clerical . . . . . . . . . . . . . . . . . . . 1387
', Operations Group i
, Unit iP3 Operations Offices ....... .1277
, 1214 1221
; Nuclear Equipment Operators (Unit 1 & 2 Emergencies) 1333
} Nuclear Equipment Operators (Unit 3 Emergencies) 1388 -
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I 1 1 Rev. 11, 6/30/83
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4 Unit 1 . . . . . . . . . . . . . . . . . . . . . . . . . . 1261, 1335 4 4 Unit 2 . . . . . . . . . . . . . . . . . . . . . . . . . . 1321, 1206 3 . Unit 3 . . . . . . . . . . . . . . . . . . . . . . . . . . 1278, 1357 Shift Supervisor (Unit 1 & 2) .............. 1272, 1316 - Unit 3 . . . . . . . . . . . . . . . . . 1392 l COMMUNICATIONS COORDINATION Data Transmission Coordinator. . . . ........... 1409
- Data Release (Vax Computer Program). . . . . .......
. ~1669 1670
, Telecopier (Technical Support Center). . . . . . . . . . . 1314 Offsite Communicator . .................. 1244 TSC Clerical Support . .................. -
1233 Emergency Response . ................... 'I111 EMERGENCY COUNT ROOM (Located in Visitor's Center). . . . . . . 1763, 1764 O o l l /- a , 1 4 e . I [ [ l . 1
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OCONEE NUCLEAR STATION CRISIS PHONE DIRECTORY CRISIS MANAGDfENT CENTER
'f PRIVATE ONS
, POSITION /NAME LINE SWITCHBOARD 4
RECOVERY MANAGER ,: State of S.C. (FEOC Line) 654-9367 1713 (Duke Line) 882-9801 SCHEDULING / PLANNING 1711 1712 RADIOLOGICAL SUPPORT 882-8148
, Bureau of Radiological Health (Duke Line) 882-959f, (FEOC Line) 654-9371 OEFSITE RADIOLOGICAL COORDINATOR 1705
$ 1706 TECHNICAL SUPPORT . . . . . . . . . . . . . 882-8650 1714 1715 1716 i ,
1717 DESIGN AND CONSTRUCTION SUPPORT. ..... 882-8650 1726
; 1727 1728 4
ADMINISTRATION AND LCGISTICS . ....... 882-9208 1707
^ 1708
~ 1709 i 1710
! DATA COORDINATION TELECOPIER . . . . . . . . . . . . . . . . . . . 1718 1719 1700 ADVISORY SUPPORT NUCLEAR REGULATORT COMtfISSION . . . . . FTS 677-9314 1725 1716 1717 i
BABCOCK & WILCOX (NSSS SUPPLIER) . . . . . . . . - 1714 1715 CORPORATE HEADQUARTERS
'i b (Contact with the Governor) 4 3 i A. C. Thies t .
704-373-4249 W. R. Owen 704-373-4120 Rev. 11, 6/30/83
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. OCONEE NUCLEAR STATION CRISIS PHONE DIRECTORY GENERAL OFFICE SUPPORT CENTER /,
WACHOVIA CENTER RECOVERY MANAGER (Room 1010) (Speaker Phone) 704-373-7951 (Dedicated line to State Director) 704-373-5743 SCHEDULING / PLANNING (Room 1010) 704-373-5731 704-373-7949 RADIOLOGICAL SUPPORT (Room 2390) 704-373-7790 704-373-5444 704-373-3003 0FFSITE RADIOLOGICAL COORDINATOR (Room 1222) 704-373-3141 704-373-6265 704-373-6150 NRC FTS LINE 371-6804 TECHNICAL SUPPORT (Room 1704) 704-373-5177 704-373-5235 704-373-5236 ADMINISTRATION AND LOGISTICS (Room 0925) 704-373-3121 704-373-3122 704-373-3123 NUCLEAR REGULATORY COMMISSION (Room 1488) 704-373-2689 704-373-7405 704-373-7406 ELECTRIC CENTER DESIGN AND CONSTRUCTION SUPPORT (Room 32, 3rd Floor) 704-373-4662 704-373-5304 1 04-373-5305 704-373-2825 POWER BUILDING CRISIS NEWS GROUP - DUKE (Rooms 5010, 5012, 5014) 704-373-4023 704-373-5584 704-373-3107 704-373-2864 704-373-7303 S.C. PUBLIC INFORMATION OFFICERS (Rooms 5020, 5022)
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704-373-7302-704-372-9818* 704-372-9824 704-372-0970
- Dedicated line to State Center
(. Rev. 11, 6/30/83
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OCONEE NUCLEAR STATION 3 CRISIS PHONE DIRECTORY BACKUP CRISIS MANAGEMENT CENTER T.TRERTY RETAIL OFFICE, LIBERTY, S.C. AREA CODE - 803
.: Telephone Number RECOVERY MANAGER 843-2751 SCHEDULING / PLANNING 843-2752
- 1 PUBLIC INFORMATION OFFICERS
- 843-2753 1 -
State of South Carolina 843-2754 t Oconee County 843-2755 Pickens County DESIGN AND CONSTRUCTION 843-2701 843-2702 TECHNICAL SUPPORT 843-2703 843-2704 0FFSITE RADIOLOGICAL COORDINATOR 843-2705 843-2761 2 ADMINISTRATION AND LOGISTICS 843-2762
.j 843-2763 1
HEALTH PHYSICS /RADWASTE 843=2764 843-2765
, GOVERNMENT AGENCIES
- 843-6935
' ' NRC 843-9014 State of South Carolina Oconee County l Pickens County
- NOTE: Call any one of the numbers listed to reach the desired representative.
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OCONEE NUCLEAR STATION i i CRISIS PHONE DIRECTORY
, CRISIS NEWS CENTER I,
KE0 WEE-T0XAWAY VISITORS' CENTER Telephone Number 882-5363 Private ONS Position /Name Line Switchboard
- CRISIS NEWS DIRECIOR 882-0601 1430
. tiary Cartwright 882-5620 1431 1720 1721 1722 1723 1724 C019fERCIAT. NEWS !!EDIA 882-6514 (Active Numbers) 882-6515 For drill purposes only 882-6519 882-6520 882-6522 ColefERCIAL NEWS IfEDIA 882-6529 (Inactive Numbers) 882-6530 Activated only during an 882-6533 actual emer8ency 882-6535 --
882-6536
.,t 882-6538 882-6540
- 882-6541 882-6543 382-6544 i NRC/ STATE /COUNTT PUBLIC INFORtfATION OFFICERS (PIO'S)
- NRC 882-8094*
i Oconee County 882-4505*
. Pickens County 882-6744*
882-5537* State of S.C. (FECO Line) 654-9363 (Duke Line) 882-6746 i
- Note: NRC, Oconee County or Pickens County may be reached on any one of these phones.
D 4 Bev. 11, 6/30/83 1
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r 15 - 1 NRC HEAI.TH PHYSICS NETWORK TEI.EPHONES I i ! j 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
)
4 Operations in an emergency but can be used for daily voice traffic and fac-simile transmittal. 1
. The Station has jacks for the HPN phones in the Performance Office (Control
} Room 1 & 2) and in the Oconee Training Center.
The phone is used normally with the exception; NO DIAI. TONE OR RLNGING IS HEARD.
, In addition, ringing only lasts 30 seconds, so after 30 seconds if the party I has not answered, you must hang up and redial.
i For convenience, the codes most often used are listed below: HPN Phone Code
- 1. NRC region 2 (Atlanta) office 23
- 2. NRC headquarters (24 hours) 22
- 3. B&W Research Center 83
- 4. Oconae NRC Resident Inspector 72
- 5. Oconee Nuclear Station 73
- 6. All NRC region 2 Resident. Inspectors 26
- 7. All region 2 Operating Nuclear Plants 25 In addition, the callina Party may " conference" any phones during conversation by simply dialing the appropriate code (s). Any number of stations may be added
; in this manner.
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, OCONEE NUCLEAR STATION EMERGENCT RADIO ; -l !
J The call letters W C699 identify the Emergency Radio frequency. The following i i is a listing of radio locations, unit call letters, and identifiers. Use identifiers to begin a transmission and the call letters to close out the
. radio transmission. (For example: Oconee Nuclear Station Control Room to
{, Pickens County Law Enforcement Center. Close out with WC699 off.) ONS Base Station Remotes i'l Location Unit Call Letters Identifier
- 1. Unit 1&2 Control Room WC699 Oconee Control Room
] 2. Crisis Management Center WC699 Oconee CMC i
.j 3. Technical Support Center WQC699 Oconee TSC
- Coded Squelch Radios j Location Encode Unit Call Letters Identifier
- 4. Pickens LEC 35 ENBZ-965 Pickens LEC Pickens EOC 31 INBE-487 Pickens EOC 2
, Pickens EPD 31 INBE-480 Pickens EPD
- 5. Oconee LEC 32 INBE-488 Oconee LEC
. 6. State FEOC - (Clemson) 34 EA-82139 State FEOC k: ALL ABOVE RADIOS MAY BE ACTIVATED BT ENCODING No. 30 Field Monitorina Teams ~
; Location Unit Call Letters Identifier
- 8. Field Monitor Coordinator EA82139 Leader
- 9. Field Monitor Team EA82139 Alpha 4
- 10. Field Monitor Team EA82139 Bravo 11.' Field Monitor Team EA82139 Charlie
; 12. Field Monitor Team EA82139 Delta
, 13. Field Monitor Team EA82139 Echo
- 14. Field Monitor Team IA82139 Foxtrot
, TO COMMUNICATE BETWEEN BASE STATION REMOTES (1, 2, 3), THE INTERCOM MUST BE 8,
USED: The following procedure must be used: l4 1. Push DrIERCott button and hold
- 2. Push MTIE button and hold
- 3. Send message (example, CMC to TSC) 1 4. Release both buttons to receive a response.
} -
i s Bev. 11, 6/30/83 t - _
.. : .j, _ . a- .,e.x .p W-C-n# 6,+Ag-k-3 9 -J g t - -- .:: 4 EMERGENCY OPERATION CENTER , j Pickens County I
a Primary Number 878-7808
}
EXECUTIVE GROUP
- Emergency Preparedness 878-7527 County Administrator County Council i
Legal Officer OPERATIONS GROUP
- 4 Law Enforcement 878-7494 Rescue Squad
, EMS Fire Servics 878-7409 Medical Service Health Service Dept. of Public Works ASSESSMENT
- Transportation 855-1020 Emergency Welfare Service Shelter Service Red Cross Public Information F78-4886 RADEF
,' Mental Health 878-7499 Damage Assessment .
Supply and Procurement ALTERNATE NUMBER (to any group) 868-9207 PUBLIC INFORMATION OFFICER CRISIS NEWS CENTER-ONS* State of South Carolina 882-8094 Oconee County 882-4505 Pickens County 882-5537 l NRC 882-6744
-i CRISIS NEWS CENTER LIBERTY RETAIL OFFICE
- State of South Carolina 843-2753
.. j oconee County 843-2754 I PicFens County 843-2755 b
l
- Call any one of the listed numbers to reach group desired.
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EMERGENCY OPERATION CENTER l* 4 Oconee County i i
; Primary Number (24-hour) .......... ..... 638-3097 OPERATIONS
- Fire Protection . . ....... ........ 638-2633 Police . . . . . . . ........... .... 638-2864 638-3002
- i Public Roads . . . . ....... ........
Emergency Medical Services . . . .... ..... Rescue Squads . . . .......... ..... e ASSESSMENT
- Emer8ency Welfare Services . . . ......... 638-2177 638-2482 Radiological Defense . .......... ....
Damage Assessment . . .............. EXECUTIVE GROUP
- Supervisor / Chairman County Council . . . . . . . .
638-25{ EOC Director . . . . . . . . . . . . . . . . . .. Financial Officer . . ............ .. FNF Representative . . .......... .... PUBLIC INFORMATION OFFICER CRISIS NEWS CENTER-ONS State of South Carolina 882-8094 Oconee County 882-4505 Pickens County 882-5537 NRC 882-6744
,f CRISIS NEWS CENTER LTurPTT RETAIL OFFICE 843-2753 i ; State of South Carolina 843-2754 Oconee County 843-2755' Pickens County 3 E 1
1
- Call any one of the listed numbers to reach group desired.
3 9 h- Rev. 11, 6/30/83-
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Form SPD-1002-1
._ g'~gM10M OMd DUKE POWER COMPANY s (1) ID No:AP/0/B/1000/02 PROCEDURE PREPARATION Change (s) 2 to PROCESS RECORD 2 Incorporated (2) STATION: Oconee (3) PROCEDURE TITLE: Notification Procedure - Notification of Unusual Events
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(4) PREPARED BY: - U DATE: .2/ U i (5) REVIEWED BY- M 8 /t/ m DATE: 7/ #/O Cross-Disciplinary Review By: (6) TDfPORARY APPROVAL (IF NE ): By: (SRO) Date: By: Date: (7) APPROVED BY:e - - A!M i Date: i O!D (8) MISCELLGEOUS: Reviewed / Approved By: " Date: _
- Reviewed / Approved By: Date:
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s . - AP/0/B/1000/02 Page 1 of 3 , N DUKE POWER COMPANY OCONEE NUCLEAR STATION
, NOTIFICATION OF UNUSUAL EVENTS 1.0' Svaptons Symptoms of the initiating condition determined from Enclosure 4.1, Unusual Event Initiating Conditions.
2.0 Immediate Action i 2.1 Automatic - not applicable 2.2 Manual actions are not required to be followed in any particular sequence Date/Name Time 2.2.1 The Shift Supervisor / Emergency Coordinator shall: 2.2.1.1 Appoint On-Shift Communicator (s). 2.2.1.2 Appoint individual (s) to be responsible for ' maintaining logs of the emergency noting problems I and actions taken. - 2.2.1.3 Augment support as needed. 2.2.2 The On-Shift Conusunicator(s) shall determine notification requirements by referring to Enclosure 4.1: 2.2.2.1 Notify the NRC by using the ENS Phone:-- Emergency Plan activation requires open channel communication. 2 2.2.2.2 Notify State / County government warning points by using the Message Sheet located in the .
- - - -- .- Emergency Procedures Cart in the Shift Supervisor's office, Control Room L & 2.
2.2.2.3 Complete Part I of the Message Sheet. Establish the approval process prior to releasing information l offsite. NOTE: The Emergency Ccordinator must approve the contents , of the message sheet prior to the information being i released offsite. l l 2.2.2.4 Establish authentication process. e . A pee * - T
l ! AP/0/B/1000/02 Page 2 of 3 l Date/Name Time 2.2.2.5 Use the most expeditious communication system available. Consult the Emergency Telephone Directory.
~
l 2.2.2.6 Provide updates as infocaation becomes available I (Part I and II - Message Sheet to the State / County agencies in a time frame established during the initial contact). NOTE: Initial notification to the NRC/ State of South Carolina aust be made within 15 minutes of the time the Emergency Coordinator / Shift Supervisor determined the initiating condition for activation, escalation, or de-escalation of the Emergency Plan. 2.2.2.7 Contact the Unit Operating Engineer / Operations Duty Engineer to: 2.2.2.7.1 Notify the Superintendent of Operations. 2.2.2.7.'2 Notify the Station Manager. 2.2.2.7.3 Provide the Nuclear Production Duty Engineer with the information required by Enclosure 4.2, Emergency Plan Infor-nation. 2.2.2.7.4 Provide assistance to the Shift Super-visor and serve as the Superintendent of Operations should he adrBe available. 3.0 Subsequent Action 3.1 Should plant conditions warrant, the Unusual Event emergency must be accelerated to a higher emergency classification. Use AP/0/B/1000/01, Determination of Emergency Claasification, to identify the initiating
,conditign,,gnegge.gcy classification and the appropriate procedure to implement the response required by the ONS Emergency Plan.
3.2 When plant conditions warrant, the Unusual Event emergency will be closed out. 3.2.1 The On-Shift Communicator (s) will give a verbal sunusary closing out the emergency to the State and County agencies and the NRC. 3.2.2 The Shift Supervisor shall complete the Unusual Event procedure and forward the procedure and all copies of the Message Sheet-to the Station Emergency Preparedness
-Coordinator.
g- r w - ,- --t, e
AP/0/B/1000/02 Page 3 of 3 4 Date/Name Time 3.2.3 The Emergency Preparedness Coordinator shall prepare a written susumary (for the Station Manager'*. signature) which will be forwarded to offsite agencies within 24
., hours of the time close-out was determined by the Emergency Coordinator.
4.0 Enclosures 4.1 Unusual Event Initiating Conditions 4.2 Emergency Plan Information
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e 4 ENCIIASINtE 4.I AP/0/B/1000/02 Page I of 7 , DUKE IWit CuttPANY OCONEE NUCIEAN STATitWI [ t g EllEkGENCY CLASSIFICAfl031 LEVEL: Unusual Event t t INITIATING CIN10lil011
- EttERGENCY Acil0N 81VELS IIOTIFICATILit Cold (REFEk 10 TECHNICAL SPECIFICATIONS AND i
, (EAL'S) EtENGENCY TElfl100llE DikECTottY) IflPlitiLNTING PROCEIANtES
- 3. Emergency Core Cooling System e one er more ES channels actuated with IlOTIFY: 1,2,4,6,7 TS 3.3. TS 3.5.3 IECCS) initiated and distbarged flow Indicated in A or B injection EP/0/AflS00/04 to the vessel.
- beader (LPI or NPI) on valid NCS low AP/0/3/1000/02
, pressure er RB bish pressure signal. .
- 2. Sadiological effluent TS lielts AP/0/B/1000/02 esceeded (a) Caseous effluent TS (a) 8. RIA-45 in valid alase made for NOTIFY: 1,2,4,5,6,7 TS 3.10.2 limits escceded more than one (I) bour AND NP/0/B/lG09/15 PT/0/A/230/05
. L R14-46 in valid alare mode AND 10CFR20, A PPd . B., Table II, Col. I.
110TE: TS for OIIS gaseous release is for a shared 3-Unit 3. Release rate calculations System. using vent sample analysis and flow rate data are in estens of TS limits establisi.ed I,y , itP/0/8/I009/15 * (b) Ligasi.I ef fluent TS Limits (b) I. BIA-31/34 alare setpoint estab- IIOTIFY: 1,2,4,5,6,7,12 TS 3.9 escreded lislaed in distbarge permit PT/0/B/230/01 escreded AND flow not NP/0/5/1000/42/q terminateJ.
- 2. Samples at restricted area 1.oumJary exceed limits per 10 CFR 10, Appd. 8 and 1S 3.9
i i i
* +
g EllCIDSURE 4.8 Ar/0/s/1000/02 I. Page 2 of 7 lat*E PEMER ConrANV , i
?
OC001EE IlWCIEAR STATioel . t Els.leGEsiCY CIASalFICAtleel 14 VEL: tenusual Event,
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int 11471100 CONelfloll fiskBGENCY ACT1911 11 Vela lluTIFICAT1001 ColsE (kEFER TO TEC11NICAL SPECIFICAf tostS Assu
, (EAl.'8) FJtESCE18CT TElfrilulet DIRECTUAV) IMPIDIL81TilIG PaoCEld4ES ,
- 3. Fuel Basese ladicatise ,
IIOTIFVs 3.2.4,6,7 AP/0/8/1000/02 (a) N6gh coolant activity e (a) Sample results indicate the L6tal Ts 3.I.4 sample attivity of the BCS due te nuclides EP!0/A/1800/24 with half lives longer ti.an M sin EF/0/A/1800/04 esteeds 224 / I. Iscl/el estien reatter EP/0/A/1800/27
; is critical 3-138 ettivity in the secondary side TS 3.33 of steam generator exceeds ,
1.4 pCi/el (b) Total failed fuel enreeds (b) Chemistry sample results indicate CP/0/8/2003/02 11 l-838 concentration in time BCS is in the range of 70 pCl/el to 354 pCi/el.
- 4. Abnoseat coolant temperature (1) Esceeding interim brittle fracture NOTIFY: 1.2.4,6,7 AP/0/B/1000/02 and/oc pressure O_R abnormal limit curve yy g RC pumps en EP/0/A/1800/04 fuel temperatures outside g EP/0/Afl800/06 15 lietts. TS 3.1.2 ;
(2) Esceeding 1118T limit YEN kC pumps AND (3) Shift Superviser's judgment. f1 4 l
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.g ENCIM UNE 4.1 AP/0/B/1000/02 ,
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Page 3 of 7 t DUKE PuWER COMPANY OCONEE NUCLEAR STAT 1011 I e kHERGEllCY CLASSIFICATION B4 vel.: Unusual Event INITIATilIG CONDITIO11
- Et1ERGENCY ACTIOli LEVELS NOTIFICATIOli CODE (NEETR TO TECinNICAL SPECIFICATIONS AND
. (EAL'8) DIENGENCY TEIJPilONE DIkECTokV) INPIDGENTING PROCEDukES
- t. .
- 1. Esseeding either primary to (1) Unidentified leabase esceeds i GPH NOTitY: 1,2,4,6,7 AP/0/3/l000/02 secondary leak rate TS O_R , EP/0/A/1800/04 psimasy leak rate TS. (2) Total primary Coolant leabase rate EP/0/Afl800/47 8
(identified) exceeds le GPM PT/l/2/3/A/600/10 TS 3.1.6 * (3) Any leakage esists through NCS strength boundary (except S/G tenben) (4) OTSG ti.be leabase exceeds .3 CPet (Unit it)
- 6. Failure of a relief valve in (1) A stuck open Pressurizer relief Il0TIIY: 1,2,4,6,7 AP/0/B/1000/02 a safety related system to valve will be identified by one EP/0/A/1800/04 close following reduction of or more of the following: EP/0/Afl800/06 applicable pressure. EP/0/A/IS00/04 (s) Accoustical monitor indication T.S. 2.2 puit This pertains to Pressurtner relief valve and liain Steam (b) Pressuriser level increasing relief valve. with decreasing IICS pressure ,
e (c) Quench tank temp and pressure alarms (2) A stuck open HS relief valve will be identitled by ti.e following: (a) Visual observation t
e t ENCIDSURE 4.8 AP/0/3/l000/02 Page 4 of 7 IMEE POWER CutlPANY OCONEE NUC11AN STATIuti
' is EftENCEllCY CIASSIFICATIces livEL: th. usual Event ,
INITIATi1IG CONolitosi EftEkCENCV ACTIOel 11 vel 3 NOTIFICATICBI CODE (BEFER 10 TECNNICAL SPECIFICAflue8S AND (EAL's) Etat.kCENCY TELEPl10NE DIRECTORY) INPlitENTING PROCfJll*ES ' J. Eass of offsite power g (l) Suitchyard isolatloa CR WOTIFY: 1,2,4,6,7 AP/0/8/8000/02 less of easite poner
- EP/0/A/8800/16 capability , (2) tblevisequency-unJerveltage on EP/0/A/8800/25 htB l & 2. TS 3.7
- 8. Bass of containment integrity Penetration (s) fait leak test as NOTIFY: 1,2,4,6,7 AP/0/B/4000/02 -
seguiring shutJuwm by TS. specified in TS 4.4.8 EP/0/Afl800/23 TS 3.6 Oil TS 3.7 TS 4.4.8 l l Limits as established in TS 3.6 l l exceeded l [
- 9. 1.uss of engineered safety (1) Engiacered Safety Features is0TitY: 1,2,4,6,7 AP/0/B/l000/02 8
feature er fire protection System Iomed inoperable oft EP/0/Atl800/li ' system function sequisins (TS 3.5.1, 3.5.3) EP/0/A/1800/25 shotdown by TS TS 3.5.3 (2) Fire suppression water system TS 3.5.1. Table i EM: Because of mallmaction, femaJ inoperable (incleJe Keowee TS 3.17 pcasonnes error or NyJro) (TS 3.l7) procedural inadequacy. l L
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e e i r I . EllCthSIINE 4.1 AP/0/b/1000/02 rage 5 of 7 IMME FOWEtt COMPANY I OCOIIEE NUCLEAR STAT 40ef 4 ! E89.8CEseCY CLASSIFICAflots IIVEL: tenusual Event INITI ATileG C01001T1011
- ENERGEliCV ACTluel LEVELS 160TIFICAT5011 CODE (kEtEs TO TEClullCAL SPECIFICATIONS AND (EAL'S) EMERGEIICV TEl1PHuset inil:ECToltV) IHFIAHENTil0G PNOCEDuitES 4
50.Firewithintheplantlasting Elfosts to estinguish a fire within NOTIFY: 1,2,4,6,7 AP/0/3/1000/02
- more than le minutes. . the plant lasta longer than le minutes. Er/0/AftS00/12 rse-Fire Plan NuTE: Within the plant means' Ausillary Building, Tushine tullding,-
Administration Building, Reaetor Smildius, Neowee IlyJro i i II. (a) Indications or elasse on (a) I. Loss of radiation monitoring IIOTIFY: 1,2,4,5,6,7 AP/0/3/1000/02 process or effluent parameters system per TS 3.l.6.8 EP/0/Afit00/16 not f anational in control room EP/0/A/lA00/25 to an estent requiring plant 2. Loss of computer per TS 3.1.12 kP/0/A/1800/29 l shutdown. OP/0/A/Bl01/20 (b) ' other significant loss of (b) 1. Imss of all meteorological assessment or communication assessment for more than 48 hours, tapah;lity which does not re p ire shutdown. 2. Loss of aJ telephone co m nica-tion o(liste. ;
- 12. Security threat or attemp'.e4 Shift Supervisor is made aware that the le0TIFY: 5,2,4,6,7 Ar/0/3/B000/02 entry or attempted sabotage. Safeguards Contingency Plan has been Safeauards Contingency Plan initiated.
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l CUKZ PCh'ZK CCMPANT Enclosure 4.2 CPE3ATriG Uti!! CICOTEZ1 OCCNEZ NUC'ZAR SnHCN AP/0/3/1dOO/02 l OR EMERCriCT ?!.AN ET70RMATICN Page 1 of 1 CPERAC CNS DUTT CiGOiEZ1 S'd.ALL CCNTACT: VE PH24E: (SLFEilm'EEiT CF CFS?ATICIS/ NAM FH2E: (STATICi IW4A1ER) NAW .oHCNE: 7F!.! E "d' . :---- M V4UC 5M .:FC:LCIC4 DJ7( EGIf1ESR
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- I. INITIAT!?G CCCITICI: (GINE AS C CE TO TrE EEGECf ?' AN ESGI?TICI AS ?CSSIZl E l K.uzir-R '.1I H STATIC 1 ?MAES USED To at. -etINE EERGEC/ STATUS.)
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. MTUrd.ythiavit _Visk-f Porr. SPD-1002-1 DUKE POWER COMPANY (1) ID No: AP/0/3/1000/03 PROCEDURE PREPARATION Change (s) 2 to PROCESS RECORD 2 Incorporated (2) STATION: Oconee (3) PROCEDURE TITLE: Notification Procedure - Alert A
(4) PREPARED BY: DATE: *7 f pt (5) REVIE'ED BY: ((/d#o# DATE: 7 I .73 Cross-Disciplinary Review By- N/R: (6) TEMPORARY APPROVAL (IF NE ARY): By: (SRO) Dace: By: Date: (7) APPROVED 3Y:) v -
- b. A g N -
Date: -
/0/TS (8) MISCELLANEOUS:
Reviewed / Approved By: Date: _ . _ _ Reviewed / Approved By: Date:
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_ . _ _ _ _ _ _ _______.___in--
AP/0/B/1000/03' l Page 1 of 5 l DUKE P0kT.R COMPANY OCONEI NUCI. EAR STATION ALERT 1.0 Symotons Symptoms of the initiating condition determined from Enclosure 4.1, Alert Initiating Conditions. 2.0 Immediate Action 2.1 Automatic - N/A 2.2 Manual actions are not required to be followed in any particular sequence. i Date/Name Time 2.2.1 The Emergency Coordinator / Shift Supervisor shall: 2.2.1.1 Appoint On-Shift Communicator (s). 2.2.1.2 Appoint individual (s) to be responsible for m s maintaining logs of the emergency noting problems ) and actions taken. _. 2.2.1.3 Activate the Technical Support Center (Emergency Organization Recall, Enclosure 4.3 or 4.4). 2.2.1.4 Initiate a Site Assembl'y in accordance with S.D. 2.9.1. Use Station Personnel Accountability form (located in Emergency Procedures Cart in Unit 1 & 2). 2.2.1.5 Dispatch onsite monitoring teams to assess radiation and contamination. 2.2.2 The On-Shift Communicator (s) shall determine notification requirements by referring to Enclosure 4.1: 2.2.2.1 Notify the NRC by using the ENS Phone. Emergency Plan activation requires open channel consunication. 2.2.2.2 Notify State / County government warning points by using the Message Sheet located in the Emergency Procedures Cart in the Shif t Supervisor's i office, Control Room 1 & 2. W y J v
4 AP/0/B/1000/03 Page 2 of 5 Date/Name TLae 2.2.2.3 Complete Part I of the Message Sheet. Establish the approval process prior to releasing information offsite. NOTE: The Emergency Coordinator must approve the contents of the message sheet prior to the information being released offsite. 2.2.2.4 Establish authentication process. 2.2.2.5 Use the most expeditious communication system available. Consult the Emergency Telephone Directo ry. 2.2.2.6 Provide updates as information becomes available (Part I and II - Message Sheet to the State / County agencies in a time frame established during the initial contact). NOTE: Initial notification to the NRC/ State of South Carolina must be made within 15 minutes of the time the Emergency Coordinator / Shift Supervisor determined the initiating condition for activation, escalation or de-escalation of the Emergency Plan. 2.2.2.7 Contact the Unit Operating / Operations Duty Engineer to: 2.2.2.7.1 Notify the Superintendent of Operations. 2.2.2.7.2 Notify the Station Manager ~'~1 Request Station Manager to establish the TSC according to Enclosure 4.3, Emergency Organization Recall-Normal Working Hours, if applicable.) 2.2.2.7.3 Provide the Nuclear Production Duty Engineer with the information required by Enclosure 4.2, Emergency Plan Infoe-l mation. 2.2.2.7.4 Provide assistance to the Shift Super-i visor and serve as the Superintendent of Operations should he not be available.
.~ -. - . - . . . . _ . . . - . . . .. ..
AP/0/B/1000/03 Page 3 of 5 Date/Name Time 2.2.2.8 Contact Security to: 2.2.2.8.1 Recall Duty Personnel per Enclosure 4.4, Emergency Organizat. ion Recall-Backshifts, Holidays, Weekends, if applicable. 2.2.2.8.2 Provide access control to Control Rooms 1 & 2, 3 -- TSC and OSC. 2.2.3 Personnel arriving in the Technical Support Center shall relieve Operations personnel of peripheral duties ordinarily assigned to their section. These persons will be provided direction from the Emergency Coordi.:ator/ Shift Supervisor until he is relieved by the Station Manager / alternate once the Technical Support Center is operational. NOTE: FACE-TO-FACE TURNOVER IS REQUIRED. 2.2.3.1 Health Physics - provide radiological assessment and evaluation, provide offsite dose evaluations, onsite and offsite monitoring, sampling and analysis of gaseous effluents. 1 2.2.3.2 Performance provide nuclear / thermal assessment and release plant status data to General Office via computer. 2.2.3.3 Operational Support Center Coordinator - provide manpower to augment support as required by ONS Energency Plan. -- 2.2.3.4 Chemistry - provide sampling and analysis of liquid effluents. 2.2.3.5 Maint'enance provide I&E and Mechanical support. 2.2.3.6 Communications: NRC - Eicensing State of South Carolina - Offsite Communicator County Agencies - Offsite Communicator Crisis Management Center - Data Coordinator 2.2.3.7 Administration - provide medical, security, and clerical support. Assume responsibility for 3 establishment of the Technical Support Center ) per Procedure IT/0/3/2000/04. Assume responsi- / hility for Personnel Accountability per' S.D.1.9.1.
AP/0/B/1000/03 Page 4 of 5 Date/Name Time 3.0 Subsequent Action 3.1 Technical Support Center operational. 3.2 The Emergency Coordinator / Station Manger (alternate) shall assume "overall control" of the emergency and take the following actions: 3.2.1 Provide for continuous staffing of the Technical Support Center and Operational Support Center should it become necessary to man the emergency facilities longer than 12 hours. 3.2.1.1 Maintain station accountability and dose control for all essrgency response personnel through the Operational Support Center. 3.2.2 Implement the approval process for release of information to offsite county and state agencies. 3.2.3 Determine emergency classification. 3.2.3.1 khen plant conditions warrant, accelerate to a higher classification. Use AP/0/B/1000/01, Determination of Emergency Classification, to identify the appropriate initiating condition, the emergency classification, and procedure to implement the response required by the ONS Emergency Plan. 3.2.3.1.1 Provide a verbal summary to the State and County agencies and a written summary within eight (8) hours of the Alert Emergency. 3.2.3.2 khen plant conditions warrant, the Alert Emergency classification aay be de-escalated to a lower classification or closed out. 3.2.3.1.1 Recomend reduction in emergency class or close-out during the verbal summary to offsite agencies followed by a written summary within eight (8) hours of the ' class reduction or close-out. 9 9
. . _ . - . . - --.. . -,_. . 7 ., , -
o . AP/0/B/1000/03 - Page 5 of 5 _ Date/Name Time 3.2.4 Provide update of emergency status to include the following: Briefin;; at least every half-hour. Request OSC Coordinator to provide information from briefing to OSC personnel. Provide sequence of events information to emergency personnel. Assess flow of information (i.e., timely, accurate, concise, pertinent). Plant data system information - trending available. Make a allable news releases from the Crisis News Center. 3.3 The Emergency Preparedness Coordinator shall be responsible for the Ccepleted Procedure Process Record of notification procedures initiated by the Control Room and/or Technical Support Center. 3.4 The Emergency Preparedness Coordinator shall prepare a written summary (for the Station Manager's signature) which will be forwarded to offsite agencies should de-escalation be determined by the Emergency Coordinator.
}I 3.5 Crisis Management Center operational. #
3.5.1 Recovery Manager relieves Emergency Coordinator of the responsibility for making protective action recommendations and notif*. cations to offsite authorities, including NRC. 3.5.2 Recovery Manager relieves Emergency Coordinator of the responsibility of Emergency Management which Tnc'ludes: 3.5.2.1 Emergency Classification - escalation /de-escalation 3.5.2.2 I.ong-range planning
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3.5.2.3 Recovery i 4.0 Enclosures 4.1 Alert Initiating Conditions 1 4.2 Emergency Plan Information 4.3 Emergency Organization Recall - Normal Working Hours { 4.6 Emergency Organization Recall - Backshifts, Weekends, Holidays s
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h IR*E IW LR C WirANT OCONEE NUCIF.AR STAfl0N Farlesure 4.8 Ar/0/p/B000/01 LIIERGEllCT CIASSIFICATION IJ. VEL: A11RT Page I of 6 INITIATIIIG CONDITION EllFRGENCY ACTION LEVELS (EAL'S) NOTiflCATION Cone (RIIER in TECllNICAL SFEClflCATIONS AND IllERCLyri TLI.El110NE DIRECTORY) INPIRIENTING 11NN ElRIRES
- l. , Severe less of fuel claddlagt llorif f: 1, 2, 6, 7 AP/0/8/1000/0)
(e) Very Llah ccolant activity Er/0/A/1800/24 sample LP/0/AflR00/27 EP/0/A/IA00/Ii Total failed imel exceeds CP/0/R/2003/02
, l. I. todine I-831 concentrat6en is be-
. 51 tween 350 pCI/ml and 1770 pCl/mi
- 2. Failed feel percentage 2. Chemistry laboratory analysis shows increases by 11 In 30 min. an increase in 1-115 coerentration in the primasy coolant of 70 pCl/el la a IIOTE: Fuel damage mechanism is 30 min, period of time.
mechanical clad istlere er a iIow-induced IaiEure. Esample Coelaat pump selaure lead-
,, las to leet failure.
- 2. Rapid gross f ailure of one DTSG l. RfA 16. IF, 40 high alare; AND NOTIFY: 1, 2, 6, 7 tube WITN less of offsite power. AP/0/8/9000/0)
- 2. 125T level decreasing; AND I.r/0/A/1800/04 (11UTE: Leak greater than 10 spa and
-~ EP/0/A/1800/IP i less than 200 gym) 3. Er/0/Afl800/16 Ilndervoltage - underfrequency on ilFB I and Hf B 2. AllD
- 4. RCS Leak Rate calculatloa
- 3. Rapid failure of steam generator I. RfA 16, 17, 40 high alare; AND NOTIFY: 1, 2, 6 F t tube (s) AP/0/B/1000/03 j 2. EP/0/A/lR00/04 Iscreasing 55 sump level _AND e EP/0/A/1800/l?
, IluTE: 1.eak greater than 50 gym but less than 200 gym primary to 3. Rapidly elecreasing pressurlaer secondary.
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O DUKE FUWt.R CttlFANY 00tHIEE NUCLEAR STATloll Entlasure 4.1 AP/0/R/1000/0) EtERGENCY CLASSIFICATioll LEVELt AIIRT rage 3 of 6 INITI ATING CollplTI0li EHF,RGENCY ACTl001 11VELS (EAl.'S) NOTiflCATION CODE (Reft.R 10 TECHNICAL SI't.CIFICATIONS ANil EHERGENCY TELErNONE DikECTORT) Itirl.EllENTING PR00.EINIRE5
- 8. Loss of all onsite DC power. l. Low voltste on all DC buses OR leollt T: 1, 2, 6, 7 Ar/0/p/1000/03 EP/0/A/1800/16 N01E: An alert shall be declared as 2. DC buses onavailable to be closed. EP/0/A/1800/38 soon as a loss of DC power occurs. A SAE shall be de-
) , clared If the loss lasts for more than 15 minutes.
e 9. Coolant pump selaure leading to le0 Tit T: 1, 2, 6, 7 feel failure (included in Alert #1)
- 10. Complete loss of any function needed I. Residual heat removal system no. IIOTIFT: I, 2, 6, 7 Ar/0/s/1000/0) for plant cold shutdown, functional; O_R EP/0/A/1800/16 Er/0/A/1800/14
- 1. Inabflity to sustain either natural EP/0/A/1800/29
! or forced circulation. Er/0/A/1800/33 EP/0/A/1800/06 Er/0/A/1800/OR a ..
- 18. Failure of the reactor protection 1. Reactor remains critical after trip IIOTIIT: 1, 2, 6, 7 Ar/0/s/1000/0)
. system to initiate and complete a AllD EP/0/A/1800/23 scram which brings llie reactor F.r/0/AflB00/28 4
. subcritical. 2. Bode remain out.
, 12. Feel damage occident with release of fl0 TIFT: 6, 2, 6, 7 Ar/0/B/1000/0) radioactivity to: Er/0/A/1800/13 EP/0/Afl800/24 (a) Containment (s) RIA-4, liigh starm rT/0/A/230/01 m
i (b) Spent-fuel pool (b) RIA-41, Alert stare s , I
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y- - ., ( / IRRE l'0WER CottrANY OCONEE NUCl. EAR STAit0N Enclosure 4.1 AP/0/8/1000/01 EMERGEllCY CEASSillCAT1011 LEVEL: _ Al.ERT rage 4 of 6
't
- j __ __
INITIAfilIG CONDiil0lt EMERGENCY ACTION l.EVELS (F.Al.'S) IluflFICAtl0N CIIDE (REFER 70 TECHNICAL SI'ECIFICATIONS AND EHERGENCY 1F.lirHollE DIRECTORY) IllPI.EllENilNG l'ROCF.IIURES
- 13. Fire potentially affecting safety 1. Fire alare in vital areas and visual NOTIFY: I, 2, 6, 7 AP/0/8/1000/01 systems, observation of fires affecting safety ONS Pre-Fire Plan related systems AND a
t
- 2. Shift Supervisor's judgment.
l 14. liest or all alarms (anannciators) 1. Visual observation by the Control Itoom 100 TIFT: I, 2, 6, 7 Ar/0/R/1000/01 .' lost in the Control Room Operator Er/U/A/1800/16 F.r/0/A/lR00/29 Er/0/A/1800/11 Er/0/A/Is00/14
- 15. Radiological effluents escceding ten NOTIFf: 1, 2, 6 F .
(le) times TS T J *
* (a) Giscous effluents (a)l. III A-46 in valid alare mode vertiled AP/0/8/1000/01 by RIA-45. Er/0/A/IS00/24 'I Pf/0/A/230/01
- 2. Itelease rete calculations using TS 3.10.3 f* vent sample analysis and flow rate Hr/0/II/1009/l)
, data are in escess of Ilmits estabitsbed by MF/0/B/1009/I5 t
(b) Llysid ef fluents (b)l. le a RIA-31/34 alarm setroint iloilFY: I, 2, 6, 7, 12 Nr/0/3/1000/62/Q established in distbarge permit TS 3.9 .l i
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'! 2. Isolation valve falls to close i
, and flow is not terminated ,
- 3. Samples at restricted area bounda-ry escred 10 m limits per 10CFR20 Appd. E and TS 3.9.
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ENERGEllCY CIAS5tflCATiell 11 VEL: A11RT Page 6 of 6 INITIATING CONCITIull EllERGENCY ACTIoll lf. vel.S (EAL'S) IIOTIFICAf foll CimE (RF.lER 70 1F.CHNICAL Slf7CIFICAilhWiS AND Elit.RGENCY TElil190NE DiltECToltY) littlitfENilNG l'ROCf.lHmES
- 19. Other plant conditions that warrant 1. Determined by the Shift Supervisor / NOTIFY: 1, 2, 6, 7 As dictated by plent can-precautionary activation of the TSC Station ttanager. ditions.
and placing the CHC and other key emergency personnel en standby.
- 29. Evacuation of contral room antici- 1. Same as initiating condition. Il0Tif f: 1, 2, 6, 7 AP/0/ft/1000/03
.j poted er required with control of DNS Pre-Fire Plan shutdown systems established from 2. Evacuation of Control Room I & 2 local stations. would necessitate relocating the
, TSC to the nearsite CHC.
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..6s s sso. - .-<v - .. .os DUKE PCWZZ CONPANT Enciosure 4 2 QPERArtfG CTI; ENcCrggg CCCNEE NUC. EAR STATION AP/0/3/1000/ 03 01 E(ERGETCT PLAN ETTORMATICN Page 1 of I CPERATICNS DUTT CIGCCEI SHALI. CONTACT:
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INFORMATION ONLY For:n SPD-1002-1 C0;M,0'> COM DUKE POWER COMPANY (1) ID No:AP/0/3/1000/04 PROCEDURE PREPARATION Change (s) 2 to PROCESS RECORD 2 Incorporated (2) STATION: Oconee (3) PROCEDURE TITLE: Notification Procedure - Site Area Emergenev
. 0 (4) PREPARED BY Am.d / DATE: O / b (5) REVIEWED BY: h DATE: /- /T3 Cross-Disciplinary Review By: N/R:
(6) TEMPCRARY APPROVAL (IF NE ARY): By: (SRO) Date: By: Date: (7) APPROVED BY:w b A fl M Date: s
/c 73 (8) MISCELLANEOUS:
Reviewed / Approved By: Date: Reviewed / Approved By: Date: --
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AP/0/B/1000/04 Page 1 of 6 DUKE PokT.R COMPANY OCONF.E NUCI. EAR STATION SITE AREA EMERGENCY 1.0 Svapcoms . Symptoms of the initiating condition determined from Enclosure 4.1, Site Area Emergency Initiating Conditions. ... _ _ _ _ 2.0 Immediate Action 2.1 Automatic - N/A 2.2 Manual actions are not required to be followed in any particular sequence. Date/Name Time 2.2.1 The Emergency Coordinator / Shift Supervisor shall: 2.2.1.1 Appoint On-Shift Communicator (s). 2.2.1.2 Appoint individual (s) to be responsible for ; maintaining logs of the emergency noting problems and actions taken. 2.2.1.3 Activate the Technical Support Center (Emergency Organization Recall, Enclosure 4.3 or 4.4). 2.2.1.4 Initiate a Site Assembly in accordance with S.D. 2.9.1. Use Station Personnel Agno.untability form (located in Emergency Procedures Cart in Unit 1 & 2). The Shift Supervisor shall have the discretion to determine if a Site Evacuation will take place prior to the complete establishment of the Technical Support Center.
'2.2.1.S Dispatch onsite and offsite monitoring teams to assess radiation and contamination.
2.2.1.6 Provide protective action recommendations to offsite agencies within 15 minutes of the classification of a Site Area Emergency according to Procedure AP/0/B/1000/06. Recommend immediately: NOTE: Protective Action recommendations.are the sole responsibility of the Emergency Coordinator (Shift Supervisor or Station Manager). 3 e l
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AP/0/B/1000/04
, Page 2 of 6 Date/Name Time 2.2.1.6.1 Activate the Alert & Notification System 2.2.1.6.2 Broadcast an Emergency Broadcast System Message alerting area residents of the problems at the station and ask that they monitor EBS for further information.
2.2.2 The On-Shift Communicator (s) shall determine notification requirements by referring to Enclosure 4.1: 2.2.2.1 Notify the NRC by using the ENS Phone. Emergency Plan activation requires open channel communication. 2.2.2.2 Notify State / County government warning points by using the Message Sheet located in the Emergency Procedures Cart in the Shift Supervisor's office, Control Rcom 1 & 2. 2.2.2.3 Complete Parts I & II of the Message Sheet as information becomes available. Establish the approval process prior to releasing infecmation offsite. NOTE: The Emergency Coordinator must approve the contents of the message sheet prior to the information being released offsite. 2.2.2.4 Establish authentication process. 2.2.2.5 Use the most expeditious communication system available. Consult the Emergency Telephone Directory. 2.2.2.6 Provide updates (Part I and II - Message Sheet to the State / County agencies in a time frame established during the initial contact).
. NOTE:
Initial notification to the NRC/ State of South Carolina must be made within 15 minutes of the time the , , Emergency Coordinator / Shift Supervisor determined the initiating condition for activation, escalation or de-escalation of the Emergency Plan. 2.2.2.7 Contact the Unit Operating / Operations Duty Engineer to: 2.2.2.7.1 Notify the Superintendent of Operations. 2.2.2.7.2 Notify the Station Manager. (Reguest Station Manager to establish the TSC according to Enclosure 4.3, Emergency Organization Recall-Normal Working Hours, if applicable.)
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Page 3 of 6 Date/Name Time i 2.2.2.7.3 Provide the Nuclear Production Duty Engineer with the information required by Enclosure 4.2, Emergency Plan Infor-mation. 2.2.2.7.4 Provide assistance to the Shift Super-visor and serve as the Superintendent of Operr.tions shou 1.d he not be available. 2.2.2.8 Contact Security to: . 2.2.2.8.1 Recall Duty Personnel per Enclosure 4.4, Emergency Organization Recall-Backshifts, Holidays, Weekends, if applicable. 2.2.2.8.2 Provide access control to Control Rooms 1 & 2, 3 -- TSC and OSC. 2.2.3 Personnel arriving in the Technical Support Center shall relieve Operations personnel of peripheral duties ordinarily . assigned to their section. These persons will be provided direction from the Emergency Coordinator / Shift Supervisor until he is relieved by the Station Manager / alternate once the Technical Support Center is operational. ' NOTE: FACE-TO-FACE TURNOVER IS REQUIRED. 2.2.3.1 Health Physics provide radiological assessment and evaluation, provide offsite dose evaluations, onsite monitoring, sampling and analysis of gaseous effluents. 2.2.3.2 Performance-providenuclear/ therm [ assessment and release plant status data to General Office via computer. 2.2.3.3 Operational Support Center Coordinator provide manpower to augment support as required by ONS Emergency Plan. 2.2.3.4 Chemistry - provide sampling and analysis of liquid effluents. l 2.2.3.5 Maintenance provide I&E and Mechanical support. 2.2.3.6 Communications: l NRC - Licensing State of South Carolina - Offsite Communicator T County AC encies - Offsite Communicator ,/ Crisis Management Center - Data Coordinator
1 1 l AP/0/B/1000/04- l Page 4 of 6 Date/Name . Time 2.2.3.7 Administration provide medical, security, and clerical support. Ass'ume responsibility for establishment of the Technical Support Center per Procedure PT/0/B/2000/04. Assume responsi-bility for Personnel Accountability per S.D. 2.9.1. 3.0 Subsecuent Action 3.1 Technical Support Center operational. 3.2 The Emergency Coordinator / Station Manger (alternate) shall assume "overall control" of the emergency and take the following actions: 3.2.1 Evacuate non-essential personnel as shown in S.D. 2.9.1. i Provide for continuous staffing of the Technical Support Center and Operational Support Center should it become necessary to man the emergency facilities longer than-12 hours. 3.2.1.1 If necessary, secure bus transportation from the Duke Retail Office, Anderson. (Consult Emergency Telephone Directory) 3.2.1.2 Follow Procedures outlined in SD 2.9.1, AP/0/B/1000/10, and HP/0/B/1009/16. 3.2.1.3 Maintain station accountability and dose control for all emergency response personnel through the Operational Support Center. ' 3.2.2 Provide protective action recommandations to offsite agencies per Procedure AP/0/B/1000/06. This responsibility may not be delegated. 3.2.2.1 Implement the approval process for release of information to offsite county and state agencies. 3.2.3 Determine emergency classification. 3.2.3.1 Should plant conditions warrant, accelerate to a higher classification. Use AP/0/3/1000/01, Determination of Emergency Classification, to identify the appropriate initiating condition, the energency classification, and procedure to implement the response required by the ONS Emergency Plan. 3.2.3.1.1 Provide a verbal summary to the State and County agencies and a written summary within eight (8) hours of the Site Area Emergency.
AP/0/B/1000/04 Page 5 of 6 Date/Name Time 3.2.3.2 When plant conditions wartant, the Site Area Emergency classification may be de-escalated to a lower classification or closed out. 3.2.3.2.1 Recommend reduction in emergency class or close-out during the verbal summary to offsite agencies followed by a written summary within eight (8) hours of the class reduction or close-out. 3.2.4 Provide update of emergency status to include the following:
-Briefing at least every half-hour. Request OSC Coordinator to provide information from briefing to OSC Personnel.
Provide sequence of events information to emergency personnel. Assess flow of information (i.e., timely, accurate, concise, pertinent). Plant data system information - trending available.
!!ake available news releases from the Crisis News Center.
3.3 The Emergency Preparedness Coordinator shall be responsible for ~ Completed Procedure Process Record of notification procedures established by the Control Room and/or Technical Support Center. 3.4 The Emergency Preparedness Coordinator shall prepare a written summary (for the Station !!anager's signature) which will be forwarded to offsite agencies should de-escalation be determined i by the Emergency Coordinator. --- - j 3.5 Crisis !!anagement Center operational. l 3.5.1 Recovery !!anager relieves Emergency Coordinator of the responsibility for making protective action recommendations and notifications to offsite authorities, including NRC. 3.5.2 Recovery !fanager relieves Emergency Coordinator of the responsibility of Emergency !!anagement which includes: 3.5.2.1 Emergency Classification - escalation /de-escalation including written summaries. 3.5.2.2 T.ong-range planning l 3.5.2.3 Recovery
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AP/0/B/1000/04 Page 6 of 6 l Date/Name Time 4.0 Enclosures 4.1 Site Area Emergency Initiating Conditions 4.2 Emergency Plan Information 4.3 Emergency Organization Recall - Normal Working Hours 4.4 Emergency Organization Recall - Backshifts, Weekends, Holidays
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INClJrSifRE 4,9 AP/0/R/1003/04 Page I of 8 EsctJosuaK 4.1 IM*E POWF.R CollPANT 8 OCONF.E NUClIAR STAfl0N ENERGEllCT CIASSIFICAfloll LEVEL: Site Area f.mergency IlllTIATillG CollDifl0ld EM.RGENCY ACTION liVLt.S INITlflCATION CODE (RF.f f.R 10 TF.CIINICAl. Slf.CIFICAil0NS AND (F.AL's) ENERGENCY TELErl10NE DIRF.010RT) tilPl.FJtENTING l'RUCEIRmES i
- 1. Emown loss of Coolant Accident I. Nigh RR pressure, high RB sump Il0 TIFT: 1,2,6,7 AP/0/8/1000/04 l greater than makeup pump capacity level, RIA 4 Nigh alasm, OR LP/0/A/1800/04 EP/0/A/1800/06
- 2. Decrease in RCS pressure AND AP/0/8/1000/07*
AP/0/B/1000/06
- 3. Loss of subcooling margin.
4 Full llPI s'ad pressuriser level decreasing.
- 2. Degraded core with possible Notiff: 1,2,6,7 AP/0/8/1000/04 loss of coolable geometry. IIP /0/R/1009/15
' CP/0/8/2003/02 (a) Flow-induced (s) 1. Sample resnits indicate gar AP/0/B/1000/07*
activity in the primary roolant AP/0/B/1000/06 (b) Fuel over-temperature (b) .l. Incore thermocouple readings
. greater than 100'F and
- 2. Excess hydrogen in containment or RC sample and
, 3. Sample results indicate I-131 't' concentration is between 1300 pCl/el to 3000 pCl/ml.
(c) Fuel melt conditions (c) 1. Incore thermocouple readings a are above 2300'F
- 2. Samples results inelicate 1-135 concentration la l>etween 1180 pCl/el to ll,800 ICl/el.
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ENCIDSURE 4.1 AP/0/R/10tN)/04 Page 2 of 8
'Dt*E POWER C(glPANY EftERGEIICY CLASSIFICA110ll 1.EVEL: Site Area Emergeny INITIATillG CONDlilotl DtERGENCY ACTION liVEl.S N0flFICATION CODE (RF.fF.R 70 TECHNICAL. SI'ECIFICATIONS AND (F.AL'S) DtER05.NCY TElil1k)NE DIRECTORY) IMPLDtF.NTING l'ROCEIMIRES
- 3. Rapid fallume of steso generator 1. Reactor trip on low itCS pressure NOTiff: I,2,6,7 AP/0/R/10h/04 tube leak (greater than 200 spa) AND
~ F.P/0/A/1800/04 1[li_5 less of offsite power. EP/0/A/1800/14
- 2. Ileactor pressure decreasing uncon- EP/0/A/1800/16 trollably with Tgyg tonstant @ EP/0/A/1800/17
+
EP/0/A/1800/29
- 3. RIA 16/17 and 40 Nigh alare AND - EP/0/AflR00/28 Al'/0/A/1000/076
- 4. No significant increase in RB AP/0/B/1000/06 pressure and sump level @
- 5. RIA 4 Nigli alare g
- 6. Unde voltage-underfre<luency alarms in the 230 KV switthyard.
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- 4. Ilot appIlcable to PtEl system
, 5. Steam line break with greater 1. Reacter tely on low RCS pressure AND IIOTif Y: 1,2,6,7 AP/0/B/1000/04 than 50 spe primary to EP/0/A/1800/04 secondary leakage and 1:edication 2. RCS pressure and T ecreasing uncon- EP/0/A/10M/08 of fuel damage. AVG trollably g EP/0/A/1800/IP CP/0/B/2001/02
- 3. RIA 16/17 and 40 Nigh alarm and AP/0/B/1000/07*
AP/3/B/1000/06
- 4. Chemistry sample analysis indicates
- fuel damage - I-131 concentration between le pCl/ml to 350 pCl/ml
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- l ENClhSISE 4.1 AP/0/R/1000/04 rage 3 of a IRRE FUWF.R CIWirANY OCONEE NHCl.f.AR STATION EERGEllCT ClASSIFICA180ll 11 VEL: Site Area F. merge s tulil AilllC C01101T1011 EHERGENCY ACilull 11VELS Il0TIFICATION CODE (REIER TO 1FCNN10Al. SrECIFICATlfplS AND (EAL'5) ENERGENCT TE1111NMIE DIRECTORY) IHrt.f.NENilNG FROCEMIRF.S
- 6. l.oss of of fsite power AllD 1. Undervoltage on main feeder buses-- Il0 TIFT: 1,2,6,7 AP/0/p/1000/e4 less of omalte AC power Tor FIFBI and HIB2 AND
~ Er/0/A/1800/14 mese than 15 minutes. fr/0/A/1800/16
- 2. Keowee Hydro falls to start either EP/0/A/1800/24 manust or automatic EP/0/A/1800/29
' AP/0/ft/1000/Ola Ar/0/p/B000/06
, l. I.ess of all vital onsite DC 1. DC bus undervoltage slaims (all 100 TIFF: 1,2,6,7 AP/0/B/1000/04 power for more than 15 buses) AND
_ EP/0/A/1800/lfe minutes EP/0/A/1800/31
- 2. DC alare on Emergency Power AP/0/8/1000/07*
Switching Logic. AP/0/B/1000/06
- 8. Complete loss of any function I. Inadequate high pressure injection NOTIFY: I,2,6,7 Ar/0/p/Is00/04 needed for plant hoe shutdown flow Olt EP/0/A/1800/07 EP/0/A/1800/14
. 2. Condenser not available and steam EP/0/A/1800/20 generator bypass valves not operable F.r/0/A/1900/28
' Olt
~ Er/0/Afl800/30 AP/0/8/l000/Ol*
- 3. Ilo feedwater flow and no emergency Ar/0/B/1000/06 j feedwater flow.
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- ENCIMa*E 4.1 Ar/0/3/1000/04
. raar 4 of R IMEE INNER C0ttrANT OCollEE NUCl.F.AR STATHHI EN RGENCT CLASSillCATICII 1.EVEL: Site Area Emegen_cy INITIAfillC CoelulTION ENERGENCT ACil0N l.EVEl.S NOTIFICAtl006 CODE (pf.tER 10 TECHN'CAI. SPF.CIFICAtl(IN5 AND (EAL'S) ENERGENC1 TELE 11NMIE DIRECTORY) IHr.,itENilNG FROCEIMmf.S
- 9. Trsestent regelring operation 1.- Two or more pr5 channels trip A_ND WOTIFT: 1,2,6,7 Ar/0/9/ID00/04 el shutdown systems with Ar/0/3/1800/04 faltere to scram. 2. Control rods do not drop into core EP/0/Afl800/28 ASSigerfl001: Continued power g Ar/0/8/1000/07*
Bo*erstion and no - Ar/0/B/1000/06 core damage lamediately 3. Chemistry sample analysis indicates evident. 1-135 concentration less than 70 pCl/el. AND
- 4. Shift Supervisor's opinion that a transient is la progress.
- 10. Ilsjer damage to spent fuel: IIOTIFT: 1,2,6,7 AP/0/s/1000/04 (s) Centainment (a) RfA 2, 3, 4, 49 Nigh Alarm with Er/0/A/1800/13 gaseous sample results indicating F.r/0/AflR00/24' of f site dose comparable to EAL's EP/0/A/1800/23 shown in SAE ft). Wr/0/8/1009/l5 Ar/0/n/1000/01h
' .. (b) Fuel Mandling Building (b) RfA 6 Nigh Alarm in Spent Feel Fool AP/0/B/1000/06 08 IIUTE: Large object damages RfA 41 Nigh Alarm with gaseous feel er water loss effluent sample results indicating i below Ime.1 level in - offsite dose comparable to EAL's either A or B. shown in SAE fl3. OE-Shift Supervisor's judgment. s k
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l.NCIDSISE 4.8 AP/0/R/1000/04 rage 5 af A iMEE FOWER CullPANY OCONEE NtlCIIAR STATIUII ElERGFICT CIASSIFICAtl001 B4 VEL: SRArea Emergen,g h INiflAflRC CINIDITION ElERGENCY ACTICII l.EVELS IPIT:FICATitWI C0tt. (RElf R To TF.CHNICAl. SI'ECIFICATIONS ANil (EAl.'S) F.lERGENCY TE'EI'IR*E DIRECTORY) litrillENTING PROCERNSF.S II. Fire compromising the fonctions I. Otservation of a fire that has NOTIFft 1,2,6,7 Ar/0/8/B000/04 et safety systems. caused the loss of redundant safety (*S Pre-fire rien , system trains or functions. Ar/0/8/l000/016 Ar/0/8/1000/06
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! 12. Ilsat er all alarms (annunicatters) 3. All alesse lost for 15 minutes AlfD IIOTIFY: 1,2,6,7 AP/0/8/1000/04 j' lost and plant transient initiated Er/0/AflR00/14 or la progress. 2. Shift Supervisor's judgment that a F.r/0/A/lR00/16 transient has occurred or is in EP/0/AflR00/29 progrese I.P/0/A/ lR00/ 38 Ar/0/R/1000/016
. Ar/0/8/1000/06
- 13. Accidental release of gases NOTIFY: 1,2,6,7 Ar/0/8/1000/04
')
- (e) Etfluent mentters detect (a) RIA 45 and 46 In valld alare made ur/0/n/1009/15 ,
levels corresponding to greater {WlO Br/0/8/1009/II then 50 mR/llr for 30 min. or Gaseous effluent sample analysis AP/0/8/1000/Of* 3: ester than See mit/IIr WR for . snows 1-131 cynivelent concentra- Ar/0/8/l000/06 two minutes (or five times these Lion and noble gases (Re-133, etc) levels to the thyreld) at the being released results in 50 mR/hr alte boundary for adverse WR for 30 min or $00 mR/Nr for meteorelegy 2 min.
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l' ENCIDSimE 4.0 AP/0/R/1000/04 Page 6 of 8
, INEE POWER CtNIPANT OCENefi NUC11AR STAil0N EtERGEllCT CLASSIFICAfl0li l& VEL: Site Area Emerge:Lcy INiilATING CON 0lil0N EHERGENCY ACil006 11VELS NOTIFICATION CODE (ItEEER TO TE.CHNICAl. SPEClflCAilHNS AND (EAL'5) ENERGENCT TELEPIIONE DIRECTORT) INP11HENilNG PROCEDURES
- 13. Accidental release of gases (Cont'd)
(b) These dose rates are projected (b) Reading er dose rate outside R8 NP/0/B/1009/14
, hosed on other plant parameters coupled with RB teak rete results er are measured in the environs in calculated dose rate at esclusion
.' area boundary greater than 50 mit/Nr
, EXAllPl4: Radiation level In WB for 30 minutes or 500 mR/Nr WB containment with leek rate speropriate for esisting for 2 min. OR-containment pressure. Radiation Monitoring Teams measure CP/0/g/4003/gl thyroid dose rates (1-131 equiv) AP/0/B/1000/37*
greater than: , AP/0/B/1000/06
- 250 mit/Nr (9 a 10 e iscl/ml for 30 min, t Olt 2500 mR/Nr (9 a 10 isCl/el for 2 min.
at the esclusion eres boundary.
- 14. Ismeinent lose of physical control of I. Physical attack on the plant Il0 TIFT: 1,2,6,7 AP/0/9/1000/04 the plant, involving imminent occupancy Safeguards Contingency Plan ei the control room, ausillary AP/ Ops /1000/07*
shutdown ranels, or other vital AP/0/9/1000/06 steas as defined by the ONS Sefcguards Contingency Plan. e
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s 3 , J s f.NCl>61mE 4.1 Ar/0/R/1000/04 rage 7 of 8 IMEE ROWER CEttrANY OCOMf.E NUCIEAR STAT 1011 t#ERGEIICT CIASSIFICAfl0Il 11 VEL: Site Area EmergencJ INITIAillIG C01101T1011 ENERGENCY ACiloll IEVF.I.S NOTIFICAtl0N Cllit. (RF.fl.R 10 IF.CllNIC SIECIFICATIONS AND (F.Al.'S) EtIERGENCY 1Elli'110NE DIRECTORY) IH1'litti.N11NG PROCF.!Amt.S
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l5. Severe natural phenomena gloilFY: 1,2,6,7 AP/0/8/8000/94 l being esperienced er projected with plant not in cold shutdown. (a) finnimum Ilypothetical (a) Greater than .50 g es detesmined by EP/0/A/IR00/09 Eartingnahe monitoring seismic lustrumentation recording devices. (b) Fleed/ low water / lake (b) Shift Supervisor's judgment and EP/0/A/lR00/15 seithe creating failure ehservation. of protection of vital e plyment. (c) Tornade er sustained winds (c) Winds in excess of 95 mph as Er/0/AflR00/10 in encess of desfan levels determined free the INS. Ar/0/8/1000/07a
', 16. Other hasards being esperienced lloilf Y: 1,2,6,7 Ar/0/R/1000/04 er projected with plant not in EP/0/A/1800/02
. cold shutdown. F.r/0/A/lRo0/23 Er/0/A/1800/25 (a) Alterait crash affecting (a) Aircraft crash causing damate er EP/0/A/lR00/16 vital structures by impact. fire in: ItB er CR, Aux. Bldg., Ar/0/p/1000/07*
or fire Fuel Nandlies ties ., TB, Intake Ar/0/R/1000/06 Structures, or Switchyard. i
! (b) Severe damage to safe shut- (b) 1.ess of functions needed for hot a down epipment f ree alssiles shutdown (SAE No. 8) er esplosion.
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ENCitiSilRE 4.1 AP/0/8/ISOS/04 Page A of 4 INRE 111WER CitfrANT OCONEE NtfCIIAR STAtloll 8 EHFEENCY CLASSIFICATION 1.EVEL: site Area Emergen$y INITIATING C011D171148 EMERGENCY ACT1018 IIVEl.3 IIOTIFICAT10ll cone (REf r.It 10 TECIINICAL SPFCIFICATHNIS AIND (EAL'5) FJtERGEleCY TEl.EPIIONE DIstECTURT) IllPl,EMENTING PINM.T.ntNIES
- 16. (Continued)
(c) Entry of uncontrolled lisamable (c) Entry of toale or flemmiable gases gases into vital stess where late: CR or cable spreeding reces Istk of access to the area or RB er switchgear rene or safe constitutes a safety problem shutdown panels. IF. Other plant conditions esist 1. As determined by the Shift Surer- IIOTIFT 1,2,6,7 Dictated by plant conditions. that warrant activation of wiser /Stetten Manager the TSC and CMC. Offsite monitoring and public notift-cation initiated. *
- 10. Eversetten of control room 1. As determined by the Shift Super- IIOTIFT 1,2,6,7 Ar/0/3/I000/04 and control of shutdown visor / Station Manager. EP/0/AllOM/12 systems not established from Ar/0/B/ LOOS /0F*
local statione in 15 mins. 2. TSC would relocate to the CMC ff AP/0/9/l#00/06 Control Room i & 2 were evacuated. IInitiating condItton only - ~~ s t e 9 o E 1
e DUKE PCWER CCMPANT Enclosure 4.2 CPCRA*=rG CNIT Eica m CCCNEE NUC:. EAR STAHCN AP/0/3/10CO/04 OR D0!2CETCT Pt.Mt ETTORMACCN Page 1 of I ~ CPE2ATICNS DUTT CIGETEEE SHALI. CCNTACT: WE PH2E: (SWIVTEGiT CF CFE?ATICIS) NAM PH2E: (STATIC 4 PANAGER)
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jNFORMATION ONLY ro m SPo-1002-1 CONTROL COPY DUKE POWER COMPANY (1) ID No: AP/0/B/1000/05 PROCEDURE PREPARATION Change (s) 2 to PROCESS RECORD 2 Incorporated (2) STATION: Oconee (3) PROCEDURE TITLE: Notification Procedura - General Emergency (4) PREPARED BY: h s DATE: 7/-/![A (5) REVIEWED BY: 88 ATE: 7 I/f3 Cross-Disciplinary Review By: N/R: (6) TEMPORARY APPROVAL (IF nee ,r.sSARY): ,,s, By: (SRO) Date: By: Date: (7) APPROVEDBY:b btw!AM ,- Dace: N,/16./ Y2 (8) MISCELL Wr.0US: Reviewed / Approved By: Date: Reviewed / Approved By: Date: 4 8 @ G &e g # 1
~
AP/0/B/1000/0, ' Page 1 of 6 DUKE POWER COMPANY OCONEE NUCI. EAR STATION GENERAI. EMERGENCY l i Symptoms Symptoms of the initiating condition determined from Enclosure 4.1, General Emergency Initiating Conditions. i 1 2.0 Insediate Action 2.1 Automatic - N/A 2.2 Manual actions are not required to be followed in any particular sequence. Date/Name Time 2.2.1 The Emergency Coordinator / Shift Supervisor shall:
- 2.2.1.1 Appoint On-Shift Communicator (s). '
)
2.2.1.2 Appoint individual (s) to be responsible for .) ' maintaining logs of the emergency noting problems and actions taken. 2.2.1.3 Activate the Technical Support Center (Emergency Organization Recall, Enclosure 4.3 or 4.4). 2.2.1.4 Initiate a Site Assembly in accordancowith S.D. 2.9.1. Use Station Personnel Accountability
- form (located in Emergency Procedures cart in Etit 1 & 2). The Shift Supervisor shall have the discretion to determine if a Site Evacuation will take place prior to the complete establishment of the Technical Support Center.
2.2.1.5 Dispatch onsite and offsite monitoring teams to assess radiation and contamination. 2.2.1.6 Provide protective action recommendations to offsite agencies within 15 minutes of the classification of a General Emergency according to Procedure AP/0/B/1000/06. Recosamend immediately: NOTE: Protective Action recommendations are the sole responsibility of the Emergency Coordinator (Shift Supervisor or Station Manager). w e
AP/0/B/1000/05 Page 2 of 6 Date/Name Time 2.2.1.6.1 Activate the Alert & Notification System 2.2.1.6.2 Broadcast Emergency Broadcast System Message 2.2.'. 6.3 Shelter the two-mile sector surrounding the Oconee Nuclear Station and, 2.2.1.6.4 Depending on time of day, shelter as follows: 10 am - 4 pm = 5 raile downwind in a 90* plume 4 pm -10 am = 5 mile out in a 360* plume 2.2.2 The On-Shift Communicator (s) shall determine notification requirements by referring to Enclosure 4.1: 2.2.2.1 Notify the NRC by using the ENS Phone. Emergency Plan activation requires open channel communication. 2.2.2.2 Notify State / County government warning points by using the Message Sheet located in the Emergency Procedures Cart (located in the Shift Supervisor's office, Control Room 1 & 2). . 2.2.2.3 Complete Parts I & II of the Message Sheet. Establish the approval process prior to releasing information offsite. NOTE: The Emergency Coordinator m_ust approve the contents of the message sheet prior to the information being released offsite. 2.2.2.4 Establish authentication process. 2.2.2.5 Use the most expeditious communication system available. Consult the Emergency Telephone
~
Directo ry. 2.2.2.6 Provide updates (Part I and II - Message Sheet to the State / County agencies in a time frame established during the initial contact). NOTE: Initial notification to the NRC/ State of South Carolina j must be made within 15 minutes of the time the Emergency Coordinator / Shift Supervisor determined the initiating condition for activation, escalation or de-escalation of the Emergency Plan. 1 e
I s 1 AP/0/B/1000/05 Page 3 of 6
's l Date/Name l 2.2.2.7 Contact the Unit Operating / Operations Duty Engineer to:
2.2.2.7.1 Notify the Superintendent of Operations. 2.2.2.7.2 Notify the Station Manager. (Request Station Manager to establish the TSC according to Enclosure 4.3, Emergency Organization Recall-Normal Working Hours, if applicable.) 2.2.2.7.3 Provide the Nuclear Production Duty Engineer with the information required by Enclosure 4.2, Emergency Plan Infor-nation. 2.2.2.7.4 Provide assistance to the Shift Super , visor and serve as the Superintendent of Operations should he.not be available. 2.2.2.d Contact Security to: i 2.2.2.8.1 Recall Duty Personnel per Enclosure 4.4, Emergency Organization Recall-Backshifts, Holidays, Weekends, if applicable. 2.2.2.8.2 Provide access control to Control Rooms 1 & 2, 3 -- TSC and OSC. 2.2.3 Personnel arriving in the Technical Support Center shall relieve Operations personnel of pe'ripheral duties ordinarily assigned to their-section. These persons will be provided direction'from the Emergency Coordinator / Shift Supervisor until hre is relieved by the Station Manager /attarnate once the Tec:nical Support Center is operational. NOTE: FACE-TO-FACE TURNOVER IS REQUIRED.
~
2.2.3.1 Health Physics - provide radiological assessment and evaluation, provide offsite dose evaluations, onsite sonitoring, sampling and analysis of gaseous effluents. 2.2.3.2 Performance - provide nuclear / thermal assessment and release plant status data'to General Office via computer. 2.2.3.3 Operational Support Center Coordinator - provide manpower to augment support as required by ONS Emergency Plan. [ l .
,j l -
, L 4 - +w - -
__.7 . I AP/0/B/1000/05 Page 4 of 6 Date/Name Time 2.2.3.4 Chemistry - provide sampling and analysis of liquid effluents. 2.2.3.5 Maintenance - provide I&E and Mechanical support. 2.2.3.6 Commuunications: NRC - Licensing State of South Carolina - Offsite Comununicator County Agencies - Offsite Comununicator Crisis Management Center - Da u Coordinator 2.2.3.7 Administration - provide medical, security, and clerical support. Assume responsibility for establishment of the Technical Support Center per Procedure PT/0/B/2000/04. Assume responsibility for Personnel Accountability per S.D. 2.9.1. 3.0 Subseouent Action 3.1 Technical Support Center operational. 3.2 The Emergency Coordinator / Station Manger (alternate) shall assume "overall control" of the emergency and take the following actions: 3.2.1 Evacuate any personnel not directly involved in the control i of the emergency. Provid, for continuous staffing of the Technical Support Center and Operational Support Center should it become necessary to man the emergenc7Tacilities longer than 12 hours. 3.2.1.1 If necessary, secure bus transportation from the Duke Retail Office, Anderson.
. . . 1.21.2, follow Procedures outlined in SD 2.9.1, AP/0/B/1000/10, and HP/0/B/1009/16.
l 3.2.1.3 Maintain station accountability and dose control l for all emergency response personnel through the Operational Support Center. I 3.2.2 Provide protective action recommendations to offsite agencias per Procedure AP/0/B/1000/06. This responsibility may not be delegated. 3.2.2.1 Implement the approval process for release of l information to offsite county and state agencies. l
\
l AP/0/B/1000/05 l Page 5 of 6 -m Date/Name Time 3.2.3 Determine emergency classification. 3.2.3.1 When plant conditions warrant, the General
~ Emergency classification may be de-escalated to i
a lower classification or closed out. 3.2.3.1.1 Recommend reduction in emergency class or close-out during the verbal summary to offsite agencies followed by a written summary within eight (8) hours of tte class reduction or close-out. 3.2.4 Provide update of emergency status to include the following: Briefing at least every half-hour. Request OSC Coordinator to provide information from briefing to OSC Personnel. Provide sequence of events information to emergency personnel. Assess flow of inf'ormation (i.e., timely, accurate, concise, pertinent).
, Plant data system information - trending available. ,
Make available news releases from the Crisis News. Center. 3.3 The Emergency Preparedness Coordinator shall be responsible for Completed Procedure Process Record of notification procedures established by the Control Room and/or Technical Support Center. 3.4 The Emergency Preparedness Coordinator shall prepare a wrftten summary (for the Station Manager's signature) which will be forwarded to offsite agencies should de-escalation be determined by the Emergency Coordinator.
. 3.5 . Crisis Man Ma==at. Center operational.
3.5.1 Recovery Manager relieves Emergency Coordinator of the responsibility for making protective action recommendations and notifications to offsite authorities, including NRC. 3.5.2 Recovery Manager relieves Emergency Coordinator of the responsibility of Escrgency Management which includes: 3.5.2.1 Emergency Classification - escalation /de-escalation includiy, eitten summaries. _ 3.5.2.2 Long-range planning 3.5.2.3 Recovery
, _ _ _ , . - , _ , _ . _ ~ . . - . . - .
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AP/0/B/1000/05 Page 6 of 6 4.0 Enclosures 4.1 General Emergency Initiating Conditions 4.2 Emergency Plan Information 4.3 Emergency Organization Recall - Normal Working Hours 4.4 Emergency Organization Recall - Backshifts, Weehnds, Holidays t
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- Ar/c/B/100n/05 Fame 2 of 5 IMME PIMER CeterANY
- OCOIIGE RUCIIAR STAT 10ll EIGRGENCY CIA 551flCAitoll 11 VEL:, GFJIERAL F.le.RGEIICT IRITIATIIIG COIIDITIDII EllERGElICY ACTION l1 VERS IIlliiFICAT1011 CODE (REff.R TO TFCIINICAL SPECIFICAiltMIS AIIO FJIERGEIICT TEllrIIINIE DIRLCTOIIT) IHrlJMNilIIG 11ttKLIMlpE5 (F.AL'S) i
- 2. Imes of two of three fission
-t product barriers with a poten- 1m55 0F CnIffAlWHLWT
_ ., tiet less of the third barrier. (b) Fallere of cladding and I. Status in.Ilcates that all
* .' containeemt with potential coatsinernt penettettens y less of primary coolant are not valved off or boundary. closed.
?
(c) Failure of containment and 2. Steneline break westream i peleary ceslant boundary from main steam step valve tatth potential less of and itSSV malfunctlen. cledding.
. "1. 3. Steneline break er step
, 1101E: Recause et the ree- velve failure with steam
- ' plestty of this initi- generater tube leek.
- l. = ating coedillon, the judgment of the Shif t LASS OF FileMAltf COOLAlli motlIIDAltT Superviser will always
! serve es en EAL. I. Righ RR pressure I 2. Illah RR building sump level i 3. Less of subteeling margin
! 4. RfA 16/IP or 4R lilth Alere ,
i . j'i, 5. Its pressure lacreases and approaches 59 psig and less
- of RR spray or cooling units.
- j. 6. Reacter reelant system pressure decreasing uncontrollably with
. ! . Tgyg constant, ,
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k Ar/0/R/1000/05 Pase 3 of 5 IM*E l'tA4R CtwirANY OctmLE MUC11AR STATION EIERGENCY CIAsstrICATIOel LEVEL: GF.NERAL Etit'RGENCY
' 180T15ICAilull CODE (pl.iLR TO ILCHNICAL SrLCilit.AiloNS AND i INITIATIllG CONDITICII EIERGENCY ACTION RJ. vel.S (EAL'5) EttERGENCY TElit1 tulle DIRECTORT) Ittri.Elt.NTING l'ROCEIMMES
- 3. Loss of physical control of Physical altark on the 180T 851 1, 2, 6, 7 AP/0/8/t000/05 g the facility. plant has resulted in safeguards Contingency Plan unauthorized personnel AP/0/3/1000/06 IIOTE: Conalder 2-mile occupying the control precautionary room oc any other vitan
. evacuation. areas as descalbed in the Safeguards Contingency Plan.
- h. Other plant conditione esist Shift Supervisor's/ Emergency 180 Tiff I, 2, 6. T AP/0/B/1000/05 from utsatever source that make Coordinator judgment . Ar/0/p/1000/06 release of large amounts of Ar/0/B/1000/076 a radioactivity in a sleort time As dictated by enregency
-j period poselble.
.I ' ..- EXAMPLE: Any core melt situation.
i
- 5. Cose Melt and dispersal of sig- IfOTIFY: 1, 2, 6. F AP/0/R/4000/05 As dictated by the emeenenry
(- )) nificant radioactivity. (a) Small and lasse LOCA's with (e) 1. LOCA EAL's established AP/0/B/1000/07*
' failure of ECCS to perform in SAE fl AP/0/R/1lm /06 leading to severe core degrad- A_ND 3
e etion or melt in from minutes 2. Failure of the lirl system
. to hours. Ultimate failure AND .,[. ) of containment likely for 3. Failure of tee LPI system.
l% melt se ,sences. e
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II&ft: Several hours Ilhely to be avellable to , complete protective g action unless con-
) .I tainment is not isolated. ,
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AP/0/R/1000/05 Page 4 of 5 IM*E l'in4.R CielPANY 000 NEE NUCLEAR stall (Ni EtN.RGENCY CLASSIFICATIoli 1.EVF.L GENERAL Etr.RGENCY lillTIATIlic COIIDlil0N F.NERGENCY ACil0N 11VELS N0ilFICAil0N CfMW. (RF.fER TO TECHNICAL. SPECitICAllfWIS AND (F.AL' S) ENERGENCT TFt1PINNIE lilRF.CTORV) INPtiftENilNG l'RfsCEllullES
.I 5. Core melt and dispersal of (b) 8. Loss of main condenser A_ND
. significant radioactivity.
- 2. No emergency feedwater AND
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(b) Transient inittsted by loss of feedvater and 3. No NPI condensste systems oft
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followed by failure of
;. emergency feeduster 1. Loss of mein condenser AND
, system for an estended Period. Core melting 2. No escegency feedwater A_ND possible in several hours. 3. 8tuccessful NPI AleD
- 4. 30 minutes has elapsed I
.I OR
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- l. 30 minutes has elspacJ
,j 2. No LPI g /_0R,
. r;
. .' j 3. No coergency feedwater.
(c) Transient rey drinR opers- 1. RCS pressure greater than 3 tion of shutdown systems safety valve setroint g with fallese to scree whleh results in core danese or 2. Rapidly increasing contala-seditional fallere of core ment pressure OR 1 '. cooling and askeup systems.
^,' 3. Rapidly increasing containment s INFTE: Would lead to AND core melt 4. Reactor remains critical ll 6
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AP/0/8/Inoc/oS Page 5 el 5 IMEE ITMR C(Itll'ANV OCONEE NLILif.AR STAllON EIIEllGENCT CLASSIFICATICII 11 VEL: GENERAL FJEncENCY lillilAfillG CDIIDliloll EfERGEllCY ACilull I.EVELS IIOTIFICAfloll CODF. (REf f.R TO TECHNICAL SPF.CIFICAll0NS Allp
. (EAL'S) F.llERGF.IICY TF.LEl'110NE DIRECiollT) litrlJ.llENillIG PINEFlWNES (d) Failure of offette and (d) 1. Undervoltage on llfBI and ensite power along with HfB 2 alarms for greater
- total loss of emergency than 2 hours Aun
- feedwater make capability 2. Reow.e Ilydro falla to start for several hours. (either manual or automatic)
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, g IluTE: Would lead to even- 3. EFW piump(af fall to start taal core melt and likely failure of contelament (e) Small IDCA and inillally (e) 1. A small or lorg LOCA has occur-successful ECCS. Subse- red AND quent f ailure of contala- ,2. Containment temperature is es-
ment heet removal systems cessive and is ristes cit ever several hours could 3. Contalisment coollas is inade-lead to core melt and quate and has been for more likely failure of centsin- than 30 min. AND meat. 4 Shift Supervisor'el udgment.
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i 6. Ilot applicable to Twit plants
- 7. Any major laternal er esternal llollfY: 13,6,7 AF/i/5/iiid/65 events which could cause matsive As dictated by emergency candillans 3' .(l=,' cessese damage to plant systems.
4 (a) Fires (a) Visual observation and Shift Ar/0/B/1000/016
'*"*, Superviser's judgment. Ar/0/B/100r/06
' 4 (b) Earthquake (19E)
, .15g (structures constructed on overburden)
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l DUEZ POWER COMPANT Enclosura 4.2 CPE1 c mc UNI; ENG U IER OCONIZ NUCLEAR S*A* ION AP/0/B/1000/05 01 EMERGINCT P!AN INTOP2iATION Paga 1 of 1 OPERATIONS DUTT ENGUIZE SHALL CONTACT:
& PH:NE: l LSUPSItGEGNT CF CPSATICNS) ) - PM PHCNE:
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- 1. THIS IS AT NUC:. EAR STATICN.
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- 2. Tr(IS IS IS fCT A MILL. AN _t.NUSUAL EVENT _ ALERT JITE MEA EERGECY
,GEERAL. EERGECf MAS M SY TIE EERGENCY C:CRDINATCR AT CN t. NIT'llt. PEER -
- 3. INITIATI?G CCCITICN: (GIVE AS CLCSE 10 TrE EERGECY 81.AN IESCRIPTICN AS PCSSIE!.5 ierER WITH STATICN PF#EIE-di USED TO ETENINE EERGENCY STATUS.)
- 4. N~TIVE W.ASUE5 EEI?G T!JGIN:
- 3. T-ERE fiAVE _fiAVE NOT EEEl ANY IN'!.lRIE3 TO PL8NT PESC?NEL.
- 3. E.J.ASE CF PADICACTIVIT/ IS TAKING PtX E IS _._.IS PCT Ar- . i?G C1:.
E.J.ASE CF RACIC/CT/IT/ IS fC7 TAKLNG PtXE.
- 7. NCTI; CAT *C43 t'AG: (NRC YE3 'C) (STATE _ 53 NO)(C:1NTIdS l
_YE3__fC) I. TSC /CT/ATIC4 E3 NO. IF YES, P*-'tM STATICN MANAGER TO INITIATE E9.GECf RESPCNSE.
- 7. hT NFCE TO C:NT/C C:M'ANY M8WGli!EIT AND NTE C:M4JNICATICNS.
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DUKE POWER COMPANY (1) ID No: AP/0/B/1000/06 PROCEDURE PREPARATION Change (s) 2 to PROCESS RECORD ? Incorporated (2) STATION: Oconee (3) PROCEDURE TITLE: Procedure for Initiating Protective Action Guides for the General Public in the Emergency Planning 7one s R (4) PREPARED BY: -/ e __ DATE: 7 U (5) REVIEWED BY: b [u DATE: /7. e#3 Cross-Disciplinary Review By: 'o 7 W /R:
# f- /
(6) TEMPORARY APPROVAL (IF NECESSARY): By: (SRO) Date:
, By: Date:
(7) APPROVED BY 4A A d Date: 50 b.h_, (8) MISCELLANEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: I l I' l s . _ . . . . . _ . _ , . _ _
AP/0/B/1000/06 Page 1 of 2 OCONEE NUCLEAR STATION PROCEDURE FOR INITIATING PROTECTIVE ACTION GUIDES FOR THE GFl.'ERAL PUBLIC IN THE EMERGENCY PLANNING ZONE 1.0 Svmptoms 1.1 Should radioactive releases (or potential for release) produce exposures in excess of the Protective Action Guides in Enclosure 4.1 beyond the station boundaries, it will be necessary to provide protective action recommendations to the affected sectors of the Emergency Planning Zone. 2.0 Immediate Actions 2.1 Automatic 2.1.1 Not applicable 2.2 Manual 2.2.1 Site Area or General Emergency class emergencies have the ) potential for requiring Protective Actions in the Emergency Planning Zone. 3.0 Subsequent Actions 3.1 Emergencv Response Organizations Not In Overation -- Should the situation arise when a release (or a potential for a release exists) of radio-activity will generate doses in excess of Protective Action Guides (Enclosure 4.1) and the various offsite emergency response facilities are not established, the Shift Supervisor or Station Manager (Emergency Coordinator) would proceed as follcws: 3.1.1 , Consult Enclosure 4.2 (Protective Action Recommendations Flow Chart). 3.1.2 Determine the present Emergency Classification. . 3.1.3 Follow recommendations as recommended by Flow Chart for people living in the two mile and five mile area surrounding the Oconee Nuclear Station. 3.1.4 Provide protective action recommendations to Oconee County and Pickens County Emergency Preparedness Agencies. The County agencies have the responsibility for the protection of the general public in their county. Notify the S. C. warning point of the recommended protective action. T
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AP/0/B/1000/06 Page 2 of 2 3.1.5 Begin to project actual exposure levels to the general public and determine action required by dose calculation: 3.1.5.1 Control Room - Procedure AP/0/B/1000/07 3.1. 5. 2 Technical Support Center - Health Physics procedures for calculating offsite dose. 3.1.6 Re-evaluate earlier protective action recommendations using offsite monitoring measurements (if available), current meteorology, and core / reactor coolant system / containment status. 3.1.7 Contact Oconee County and Pickens County Emergency Operation Centers to update them on the revised recommendation. Notify the S. C. warning point. 3.2 Emergency Response Organizations in Operation -- It is anticipated that a deterioration of an emergency situation classified as a Site Area or General Emergency would generate the need for Protective l Actions for portions of the Emergency Planning Zone. 3.2.1 The emergency response organizations (Technical Support Center, Crisis Management Center, State Forward Emergency Operations Center and the County Emergency Operations Centers) would be in operation. 3.2.2 The Crisis Management Center through the Recovery Manager will make recommendations to the State Forward Emergency Operations Center for the areas requiring Protective Actions. The Recovery Manager will use Enclosures 4.1 (Protective Action Guides) and 4.2 (Protective Action Recommendation Flow Chart) to immediately assess the actions needed to protect the public. ---- 3.2.3 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 (through the Governar's office) would initiate protective action recom-sendations to the public. 4.0 Enclosures 4.1 Protective Action Guide 4.2 Protective Action Recommendation Flow Chart d w - m m M
9 9 8 i : ENCI.0StHtE 4. I
.I'l!OT,Ep[ lye ACrlijN CtllDES AP/0/H/1000/06 j j Itcronsmendeel prot ect ive act ions to avoiel whole body and t hyroid dose f rom expostare: 'o a gaseous plume.
Projertcil Dose (Hens) ta the l'opulat ion Recomumendel ActionsId' Comunent s No protective action respaired. Previously recomunended { Wluile body < l State may issue an ailvisory to seck shelter and protective actions niay be Thysold aw.a l t further instaurtions or to voluntarily reconsidered or terminated. I
<5 evaruptc.
ilonitor environmental radiation levels. Whole lio.ly I to <5 Seek shelter and await f ur ther inst ruct ions. Consider evacuation particularly for ehildresi and pregnant womesi. Thysol.1 5 at <25 Ilonitor environmental radiation levels. Control access. Conduct aiandatory evacuation of populations in the Seeking shelter would he Whole 1. oily 5 and above predetermined area, Ilonitor environmental radiation levcis and adjust an alternative if evacuation 1hyroid 25 and above were s.ot inunediately pos-area for mandatory evarnation based on these levels. sible. Control access. I'roject eil Dose (Hem) t o En.orgency Team Workers Whole liody 5 Control exposure of emergency tcais a cmhcra to these Skin of Whole llody Although respirators and or Thyroid 'lu levels except for lifesavisig anissions. (Appropriate stable iodine should he Extiemities 75 controls for emergency workers, inclinic time limita- used where effertive to tions, respirators, and stahic i nili nc. ) cmcrgency team workers, thyroid dose may not he a Whole body 25 Control exposur$ of emergency team members perform-Skin of Whole llody limiting f actor for life- ' ing lifesaving agissions to this level. (Control of saving inissions. or.Thysoid 150 Liene of exposure will be most ef terlive.) Ext remit ics :175 Vul.tlHTARY llASIS OHl.y I* ihese act ions are reconnaendeel for planning purposes. must t ake existing casolitiens into considerat lon. Ps otect ive act ion decisions at 'the t ime of the incident s e Q , e
. r AP/0/B/1000/06 .
ENCI.OSURE 4.2 ! . . PflOTECTIVE ACTION llECOMMENDATION FLOW CilAftT ' i
* ' OCONEE NUCLEAR STATION !
IS Tile EMEllGENCY CL ASSIFiED UNUSUAL EVENT OR ALE 11T7 : NO RECOMMENDATIONS REQUIRED e - fNO IS 11tE EMERGENCY CLASSIFIED ** SITE AflEA EMERGENCY ;
~
11ECOMMEND TO OFFSITE AUTilORITIES TilAT PEOPLE IN Tile 2 i MILE AllEA BE MADE AWARE OF Tile Sl10ATION AND MONilOR EBS , gNO FOR FullTalER INFOftMATION. ASSEMBLE AND EVACUATE NON i ESSENilAL STATION PEllSONNEL. ' CLASSIFICATION IS A GECIAL EMERGENCY I iMMEDIATELY RECOMMEND TilAT PEOPL E IN Tile 2 MILE AREA ANO 6 MILE DOWNWIND GO INDOORS, CLOSE ALL WINDOWS AND DOORS. TURN OFF VENTILA flON EOulPMENT, AND MONITOR EDS FOR INFORMATION. AS SOON AS POSSIBt E. FOLLOWUP Tills RECOMMENDAllON WITil ONE BASED ON AN EXTENSIVI EVALUATION OF Tile TWO AllE AS LISTED DELOW. ASSEMBLE AND EVACUATE NON ESSEtAllAL STAllON PEllSONNEL. . I COMPARE PilOJECTED DOWNWIND DOSES AND FIELD MONITOillNG . EVALUATE COflE/f1EACTOR COOLANT SYSTEM / CONTAINMENT STAT- ! TEAM MEASUREMENIS WITil EPA PAG g *S (Enc. 4.1) DE1EftMINE US AND COMPAllE Wllll Tile FOLLOWING PitESELECTED flECOMMEN- i APPflOPRIATE ACTIONS. MENDATIONS. COMPAftE lilE IlECOMMENDATIONS DEVELOPED FHOM 11lESE lWO FOll CollE MELT SEQUENCES WilERE SIGNIFICANT RELEASES FROM ANALYSIS AND DETEllMINE Tile MOST APPflOPlilAlE OF Tile TWO. CONTAINMENT AllE NOT YET TAKING PLACE AND LAllGE AMOUNTS IF DOSE PflOJECIlONS Oft FIELD TEAM MEASullEMENTS AllE NOT <-- OF FISSION Pl. )UCTS AllE NOT YET IN CONTAINMENT ATMOS AVAILAHLE, DETEllMINE ACllONS BASED SOLELY ON CORE MELT h PilEllE, HECOMMEs.1 A 2 MILE PitECAUTIONARY EVACUATION AND ANALYSIS. SilELIElllNG TO 5 MILES. IlECOMMEND EVACUATION TO 2 MILES AND TO 6 MILES DOWNWIND IF FISSION PilODUCT ACTIVITY GilEAT-I ER TilAN GAP ACTIVITY IS BN CONTAINMENT ATMOSPilERE. BEFORE MAKING A FINAL DETERMINATION CONSIDER TilESE CON- h SillAINTS:
- 1. PLUME ARRIVAL TIME VERSUS EVACUATION TIME ESTIMATE 'FOR CORE MELT SEOUENCES WilEllE SIGNIFICANT IlELEASES FROM 100 NOT EVACUATE Tile PUBLIC **l illE PLUME). CONTAINMENT AllE NOT YET TAKING PLACE AND CONTAINMENT FAILullE IS LIKELY BUT NOT IMMINENT, AND LAllGE AMOUNIS OF
- 2. DO BillOGE & ROAD CONDITONS P.'IESENT AN IMPED l MENT TO ,
EVACUATION 7 i FISSION PitODUCTS IN ADDITION TO NOBLE GASES AllE IN CONT AlN.
- 3. Wit L WE AillER CONDillONS INill84T EVACUATION? MENT ATMOSPilEftE, CONSIDER Pil[CAUTIONAllY EVACAIlON TO 5
- 4. CAN STATE / LOCAL AGENCl[S PilYSICALLY SUPPOllT Tile flE- .
MILES AND 1010 MILES DOWNWIND. COMMENDATIONS?
- 6. IS lills A PUFF" OR CONTINUOUS RELEASE 7 FOR CORE MELT SEQUENCES WilEllE LARGE AMOUNIS OF FISSION PilODUCTS lil ADDITION TO NOULE GASES ARE IN Tile CONTAIN-M[NT A1MOSPilEllE AND CONTAINMENT FAILUllE IS JUDGED IMMl-NENI, ItECOM*4END Sil[L1Eli FOll TilOSE AllE AS WilEllE EVAUA-lluN CANNOT.. COMPI E1ED ll[FullE lilAlr2Olli OF ACTIVITY q
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CONTROL COPY 8885 mw i ( ' +. !. Form 34731 (10-81) I.. (Formerly SPO.10021) . t DUEE POWER CCHPANT (1) ID No: AP/0/B/1000/07 PROCEDURE PREPARATION _ Change (s) - to
, , PROCESS RECORD -
Incorporated (2) STATION: OCONEE NUCLEAR STATION l (3) PROCEDURE TITLE: Procedure for Offsite Dose Calculation by Control Room )
. Personnel or Emergency Coordinator During a Radiological Accident (4) PREPARED BT: bm DATE: M \k -
(5) REVIEWED BT: ATE: , ~~ h 3 Cross-D linary .. dd j/ L N/R: v y y (6) TEMPORART APPROVAL (IF NECESSART).*/ By: (SRO) Date: i) By: Date: (7) APPROVED BT: n Ad Date: b - (8) MIS N 1AMEQUS: . naviewed/1;,. ..; ay: k b b )
- Date: G Eeviewed/i;;::.;l By: 7 Date: [r-[- [8 S
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1 sM0 AP/0/B/1000/07 ' x.:, PROGDURE FOR OFFSITE DOSE CALCEATIONS . BY CONTROL ROOM PERSONNEL OR EMERGENCY COORDINATOR DGtING A RADI0IDGICAL ACCIDENT LO Symptoms : 1 1.1 RIA-4 reading increasing with indications of a loss of coolant accident. . - 1.1.1 RIA-4 reading < 30R/hr (Case A)
. 1..
1.1.2 RIA-4 reading > 30R/hr (Case B) 1.2 RIAs-44, 45 and 46 increasing with indications of a radiological accident. (Case B). 2.0 Immediate Action CASE A , 2.1 Antreatic s 2.1.1 None 2.2 Manual 2,.2.1 None 3.0 Subsequent' Action 3.1 Deploy monitoring teams CASE B i I ! 2.0 Immediate Action 2.1 Antomatic ' 2.1.1 RIA-45 high =Imm will secure a Beactor Building Purge if in progress.
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2.2.1. This procedure is intended to provide on-shift personnel, and membert of the Technical Support Center a means of projecting offsite exposure levels for radiological acci-dents at-Oconee Nuclear Station. These dose projections can be made based upon the source of the release to the unit vent, Reactor R=4Wrg atmosphere and available
, meterological data. It is intended that projections made by this procedure vanld be conservative and precede-infor-nation 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. BOTE: 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., 2.2.2 The meteorology data needed to calculate offrire dose shonld be obtained from the tower. Data not available from this primary source should be obtained from its back up source. These back up sources are the river and Fational Weather Service. All meteorologTdata obtained from the tower or river umst be a 15 minute average. National Weather Service data is a standard observation and is not a 15 minate average. _ .,_? '
i 3- AP/0/B/1000/07 . 1 1 2.2.2.1 The following are conversion formulas for the p.,
- w. .z.z ,
meteorological data obtained from the National
- Weather Service Office at the Greenville-Spartanburg Airport. (Vumber is listed in the Emergency
' ~ Telephone' Directory).
sph = 1.15 (Enots) 4 = (9/5'C) + 32 i l 2.2.3 2he need for protective action should be reassessed every hour. The Control Room will complete the Offsite Dosa l Calculation every hour until the Technical Support Center is operational and are relieved by the Health Physics Center. Wind direction and speed will be rechecked every 15 minates to ensure additional sectors have not been affected ^~4ag daytime (1000-1600 hrs.). ;P '
, NOTE: Once a sector has been determined to be affected, ~
then it cannot te removed from the list of' . affected sectors. 2.2.4 Complete the proper enclosure for the existigconditions. I. Inclosure 4.1 - LOCA With Vent Release
- 2. Inclosure 4.2 - IOCA; No Vent Release
- 3. Inclosure 4.3 - Vent Release; No LOCA l 4. Enclosure 4.6 - Computer Dose Assessment Program 2.2.5 Complete Enclosure 4.5 (Stability Class). This information is used in the "varning message" to offsite agencies. l 3.0 Subs s t. Actions l
l 3.1 Notify -the proper-agencies per AP/0/B/1000/05 (Notification Procedure - General Emergency). . .7'
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. - 4- AP/0/B/1000/07 t .
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.. 3.2 Deploy onsite and offsite monitoring teams per AP/0/B/1000/05
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(Notification Procedure - General Emergency). . 4.0 Enclosures 4.1 Offsite Dose Calculation - IOCA Vent Release 4.2 Offsite Dose CaIculation - LOCA; No Vent Release 4.3 Offsite Dose Calculation - Vent Release; No LOCA 4.4 Survey Instrument Correlation . 4.5 Stability class.
. 4.6 offsite Dose Calculation - Using Computer '-
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Checked with Control Copy Paga 1 cf 8 . Tian/Date - - HCLOSURE 4.1 e 3,, v" .-s OCONEE NUCLEAR STATION , 0FFSITE DOSE CALCUIATION LOCA WITH VENT REIZASE AP/0/B/1000/07 Unit. Calculation performed by - TIME DATE --
~
- 1) A) Now /
B) Incident / C) Hours Since Incident
- 2) Neteorology Data - 15 minute average.
NOTE: Sources of data are listed in order of perference. If the ? first choice is unavailable, use the second. choice, etc. Fill 'J,h in only one blank for each data point. . (A) AT(*F) 1) Tower *F
- 2) Use a AT of 0.4'T if tower AT is not available.
(B) Wind Direction 1) Tower * -
- 2) Biver *
- 3) National Weather Service *
(C) Wind Speed 1) Tower sph
- 2) River upk
- 3) National Weather Service sph l NOIE: National Weather Service data is a standard observation, not a 15 l minute average and is updated only once per hour.
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l- ENCIOSURE 4.1 AP/0/3/1000/07 .
- 3) Calculate TF (time factor) based. upon time (hours) since incident from the table below and reco,rd value. _
Time Since Incident Time
'Im Bours Factor (TF) 0-1.0 0.28 1.1-2.0 O.36 -
2.1-5.0 0.60 TF = '. .. 5.1-10.0 0.94 10.1-20.0 1.50
- 4) Reactor Building DR (dose rate) by either a) or b).
l 1 a) Containment high range radiation monitor (RIA-57 or RIA-58) R/hr j b) PIC-6-A (or sinT=* hand held survey instrument) reading x correlation value (Encl. 4.4). - Survey Inst. r Corr. value = DR R/hr. NOTE: A reading on the survey instrument < 0.3 R/hf~would indicate that the release source term used for the " warning message" 1 to offsite agencies is a gay activity release.
- NOTE: A reading on the survey instrument > 0.3 R/hr would indicate '
that the release source term used for the "varaing message" l to offsite agencies is a design basis accident.
- 5) Deterunne through which unit vent (s) (if any) activity is being released.
Vent releases mer occur on all three units' vents. simultaneously since
- the Oconee w 14= q Building is one enclosure with three vents.
Vent release on Unit (s) .
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Page 3 of 8 . # ENCLOSURE 4.1 g. AP/0/B/1000/07 .
- 6) Record the following information for the affected unit (s) vent monitors identified in Step 5.~-
Unit 1 Unit 2 Unit 3 Unit Vent Flow (Ev) (A0946) cfm cfm cfm i , RIA-45 (A1679) cpm cpm cya RIA-46 (if > 10 cpe) (A1680) cps cpu 'cpe l RIA-44* (R-1678) a) -Start of time period
-count rate cpe cpe cpm b) -end of time period
-count rate cpe cpm eps c) -A time sin sin sin
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$:i l NOIE: If the RIA Chart is used as a reference, use the 15. minute interval IIN Mn= the last hour that had the greatest increase in RIA-44 counts.
RIA-44 rate of increase any be read directly from the plant computer. (R-1678)
- 7) Ifniciply unit vent flow times the RIA readings and add to the results as
- follows for the affected units vents.
a) Noble' Gas (NG) RIA-45 Fv z RIA-45 (eps) U-1 x = ' U-2 x = U-3 x = total RIA-45 =
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. . Page 4 of 8 ENCLOSURE 4.1
- ,S AP/0/B/1000/07 ,
RIA-46 Fv x RIA-46 (eps) ,_ ,, l . U-1 x = . . U-1. - x = , _ W3 x = . t total RIJ.-46 = . NG = [tstal RIA-45 x 1.71 F-dl + [ total RIA-46' x 6.82E-41 NG = (record this value on Step 8c)- b) Iodine Vent (Iv) RIA-44 1' p , ,A RIA-44 (com) a time (min) . O x
~
. U-1 =
U-2 x = U-3 x = total RIA-44 = - It = total RIA-44 x 2.76E-7 It =
- 8) Calculate DT by completing Step A through C. !
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a) Building Iodine (IRB) Igg = DR (Step 4) x Tir (Step 3) : In* . . _ . _ . _ _ . b) Total Iodine (IT) -
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2 3 ._ Pcs2 5 of 8 - -
. ENCLOSUPZ 4.1 h.;.
..y.i t
AP/0/B/1000/07 - - c) Total Iodine (I )Tvs Noble Gas (NG) Ig (Step 8b) = _ , NG (Step 7a) = Dr = if I I > NG, DT = I if I igNG, Dr = N,G 1
. DT z. .
- 9) Is time of day betweea 1000 hrs and 1600 hrs (10:00 an and 4:00 pm)? - ,
. If yes, 30 to Step 10. ,
t If no, go to Step 14.
- 10) Calculate W (wind determined dose) based upon Dr (Step 8c) and WS (wind speed).
W = l F.n. i
- 11) Decemine distances and level of protective actions based upoa W (Step 10) D -
and W 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 M. Follow across the row from left to right until the box cone =4=4ar the calculated W value is reached. Read dava the vertical columa to find the appro-priate actions and the corresponding distances. from the plant.
l l . d w
-v e
'T
$ . - . d . gn
4, 44y
.___ __ _ ___.__l_ *
~ -* * * * * * ' * " ' ' " ' '
. n . .,, ; . . .... , u . ., .
. ...,..,~:..... l
,v %: K~ ';*:,%,.,. ;. ..
. ':.Wl " W. . . . . . .. ~ , . , . .. % d $ s h 4 4 y - i s.W .. W..-.
...@Q ,.. ,i;~' l%A LD,j;%}%$,.,. .:~ @ l 2l....
...a_ . =. _ .nm n w.+a .wi.a;w .
)-
.~
Page ( of 8
. ENCLOSURE 4.1 4 " )
AP/0/B/1000/07 .. l
-1 a2*F W W DW W i A) -* to -1.3 12.09E5 2.09E5 to 7.8E5 7.8E5 to 3.9E6 >3.9E6 l B) -1.2 to -1.0 15.4E3 5.4E3 to 2.70E4 2.7E4 to 3.2E5 >3.2E5 C) -0.9tto -0.4 12.09E3 2.09E3 to 1.04E4 1.04E4 to 7.4E4 >7.4E4 D) -0.3 to +10.0 St.08E3 1.08E3 to 5.4E3 - 5.4E3 to 3.2E4 >3.2E4 No, action Evacuate children Evacuate every- Evacuate
. procedure and pregnant vou- one 0-4 miles everyone
! is com- en 0-4 miles (Downwind areas 0-4 miles plated (Downwind areas with suffiz 1) (Downwind with suffix 1) area with suffiz 1) i No action for Evacuate chil- Evacuate 4-10 miles dren and preg- everyone nant. women 4-10 4-10 miles 4
miles (Downwind (Downwind 4
-' areas with suffiz areas with.
- 2) suffix 2)
Example: If AT'F is -1.1 and W is 2.9E4, evacuate everyone from 0-4 miles and children and pregnant women from 4-10 miles.
- 12) a) Is wind speed > 5 mphi_
O If yes, use table in Step 12 b. - G If no, assume Sectors A1, B1, CI, D1, El, and F1 are affected.. Then use Table 12b to determine additional areas to be evacuated out beyond 4 miles. f b) Wind direction (from) and wind speed - 15 minute. average. 1 Reverify every 15 minutes. , 1st 15 min. average *; ' aph . . . . 2nd 15 mia. average *; aph , , _ , 3rd 15 mia. average *; myk )
~
. - l
. . -- m . _ 1 1. m.m -
..~e. - _ -.-- . _ .,,m m., , _.
Page 7 cf 8 ,' ENCLOSURE 4.I'~ Q
%d AP/0/B/1000/07 .
i 4th 15 min. average *; sph . 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 j 103* - 127' E, P 127' - 174* A,E,F ;:%,
l 174* - 182* A,. F 182* - 215* A, B, F - l 215' - 256' A, B 256' - 270* A,B,C ~ . 270* - 298* B, C 298* - 344' B,C,D 31-4' - 15' C, D c) Eatter prd== of areas on evacuation map to be evacuated .
- 13) Combine the numbers determined in Step 11 witit the letters from Step 12 to det'm M an whick sectors of evacuation map to evacuate.
Children and pregnant women Everyone
'the 2 mile Emergency PT-ias Zone on the evacuation map will, always BOTE: -
be evacuated if evacuation of any area is r-4=d.
?
e - , ,
~ : .ns m=.umy .wr :~c .s , n.-,-a.- _ .z;: ;.; w ;::=x -v
. ,.. c , . rw~, . .. a. ; _ ..
w . w.. m ..va . . : ~:o d_u. m s w + n_ s s a u;. % s m u n g.;;.1.xg y x,.._.g Page 8 of 8
"% .x ENCLOSURE 4.1 AP/0/B/1000/07 .
- 14) Use the table,below if time of day is not between 1000 hrs and 1600 hrs.
Apply the DT value from_ Step 8 on the table below. Read the corres-FMa* action in the column to the right and record. Dr PROTECTIVE ACTION
< 610 -
Ne protective action is necessary , 610 to.3100 Evacuate children and pregnant women a to 4 miles in all directions (all areas with number suffix 1) 3100 to 15600 Evacuate everyone o 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
+ . --
suffir 2)
> 15600 Evacuate everyone O to 10 miles in all directions. (All areas with number
, suffixes 1 and 2)
Children and pregnant women --
~
l Everyone t l NOTE: The 2 mile Emergency Planning Zone on sae :racation map will always be evacuated if evacuation af a;.q ,oa is required. Additional Notes or Comments
*e
i
- w. -. _ .. - - -- _. _ - . - . . . . , . - , . - . - - - . . . ~ = . ,
._ ...m, ?ug '
Checked with Control Ccpy Paga 1 of.6 l i Time / Data - . l ENCLOSURE 4.2 4 p.r..v :+ OCONEE NUCTIAR STATION *.. l OFFSITE DOSE CALCULATION l j IOCA; NO WJIT REIEASE AP/0/B/1000/07 i [ Unit l l . Calculation performed by - 1 *
- 1) A) Now /
B) Incident / - C) Nours Since tam % t
- 2) Meteorology Data - 15 minute average.
I NOTE: Sources of data are listed in order of perference. first choice is unavailable, use the second choice, etc. Fill in: only one blank for esclL data point. - If the
,-[j (A) AT(*F) 1) Tower 'F
- 2) Use a AT of 0.4'F if tower AT is not available.
(B) Wind Direction 1) Tower * -
- 2) River *
- 3) National Weather Service
- i (C) Wind Speed 1) Tower sph l 2)- River myk
- 3) National Weather Service sph t
NOTE: National Weather Service data is a standard observation, not a 15 l d ante average.
. , i'
'.; '?-
s
mew 9.c - r ..--....vs e.mm ,;s w w m m .R.u w y usc.6x ., & g m ; & Page 2 of 6 elf - ENCLOSURE 4.2 AP/0/B/1000/07 .
- 3) Calenlate TF (time factor) based upon time (hours) since incident from the table below and reco ,rd value.
I Time Since Incident Time
'Im Hours Factor (TE) 0-1.0 0.28 1.1-2.0 4 0.36 -
~
2.1-5.0 0.60 TF = ' 5.1-10.0 0.94 10.1-20.0 1.50
- 4) Reactor Building DR (dose rate) by either a) or b).
a) Containment high. range radiation monitor (RIA-57 or RIA-58) i R/hr.
.g b) PIC-6-A (or *>ilar hand held survey instrument). reading x correlation value (Encl. 4.4).
Survey Inst. x Corr. value
- DR R/hr.
NOTE: A r== ding on the survey instrument < 0.3 R/htwould indicate ' that the release source term used for the " warning message" tar offsite agencies is a gap activity release. t NOTE: A reading on the survey instrument > 0.3- R/hr would indicate that the release source term used for the " warning message" to offsite agencies is a design basis accident.
- 5) Calenlate DT (time determined dose)
Dr = Da x Tr
- 6) Is. time of day betsaen 1000 hrs and 1600 hrs (10:00 amt and 4:00 pm)?
If yes, go to Step 7. If no, go to Step 11.
- 7) &T=1=te DW (vind determined dose) based upon DT (Step 5) and WS (wind speed).
.g-
.s y NN, . .. .EBXTJI"#SSINf53rthf5NYNYZMdiSSN$WRE6NMb
.. .. u,....-..,m,
..y 3 n.y.,r.-.g . - .,.~. . . w e .s. y l
_w. _ ~ _ . ... -
. . g - _
'5DNA3$sD$M
_.w.w,. _,- . Page.3 of.ii - ENCL 0SURE 4.2 4 tw.f AP/0/B/1000/07 . l 8) Determina distances and level of protective actions based upon DW (Step 7) and AT*F from table below: ~- Number suffix of areas on evacuation map to be evacuated: Children and pregannt women Everyone j Find the horizontal row corresponding to the AT*F. Follow acros.s the- . row from left ta right until the box containing the calculated Dd'- value is reached. Read down the vertical column to find the appro-priate actions and the corresponding distances from the plant. AT*F DW DW DW DW A) -= to -1.3 S.09E5 2.09E5 to 7.8E5 7.8E5 to 3.9E6 >3.9E6 B) -1.2 to -1.a p.4E3 5.4E3 to 2.70E4 2.7E4 to 3.2E5 >3.2E5 .p. . p.y.- C) -0.9 to -0.4 S.09E3 2.09E3 to 1.04E4 1.04E4 to 7.4E4 >T.4E4 'N D) -4.3 to +10.0 p.08E2 1.08E3 to 5.4E3 5~.4E3 to 3.2E4 >3.2E4 l No action Evacuate children Evacuate every ~ Evacuate procedure and pregnant won- one 0-4 miles everyone is com- en 0-4 miles (Downwind areas 0-4 miles - plated (Downwind areas with suffiz 1) (Downwind with suffix 1) area with suffix 1) > I No action for Evacuate chil- Evacuate
, 4-10 miles dren and pres- everyone nant women 4-10 4-10 miles miles (Downwind (Downwind areas with suffix areas with-
- 2) suffix 2)
Example: If AT'F is -1.1 and DW is 2.9E4, evacuate everyone from 0-4 adles and children and pregnant women from 4-10 miles.
. s 8
'J kb.
G.T
Ode?w JAeng @rF#X M T yree w -g % eT~~'t w ev.cy m vFudc m e r @$.nt'~ncirg
- . : e--
x _~ _-._~, w y .e x _ w - m : - n e w n n :- _ _ M c;. -_.; a ; e : Page 4 of 6
,u t ENCLOSURE 4.2 AP/0/B/1000/07
- 9) a) Is wind speed > 5 sph?
O If yes,.use table in Step-9 b. - 0 If no, assume Sectors A1, B1, C1, D1, EI, and F1 are affected. Then use Table 9b to-determna additional areas to be evacuated out beyond 4 miles. b) Wind direction (from) and wind speed - 15 minute average. Reverify every 15 minutes.- ~ 1st 15 min.' average _ *; _ _ sph 1 2nd 15 min. average *; aph
- 3rd 15 min. average *; sph 4th 15 min. average *; aph Find the wind direction and follow across the row to find the letter prefixes of the areas on the evacuation map to be evaca-ated and record.
Wind Direction Eatter Prefixes of
. (From) Areas to be Evacuated .
15* - 41' C,D,E , 41* - 67* D, E 3 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, R - 256* - 270* A,B,C 270* - 298* B,' C 298* - 244' B, C, D 344* - 15* C,, D
.= . - , , , ,-
, w. . . wen.. e mm . .a.:.. w . m m m m s w , m v e n x:.1 7 m.;~~ m .v ~ '~g; Q : _w _ gg. - , _ _ . m . ,._ ef . .-
.a ._.m
_ e. u o L. j_2 . ._ a u-g. . ., a Page 5 of Ei ' i ENCLOSURE 4.2 g; AP/0/B/1000/07 . c) Letter prefixes of areas on evacuation map to be evacuated .
- 10) Combine the numbers. determined in Step 8 with the letters from Step 9 to determine which sectors of evacuation map to evacuate.
Children.and pregnant women Everyone i NOII: The 2 mile Emergency PJ.anning Zone on the evacuation map will always be evacuated if evr.cuation of any area is required.
- 11) Use the table below if time of day is not between 1000 hrs and 1600 hrs.
Apply the DT value frontStep 5 on the table below. Read the corres-ponding action in the column to the right and record.
.L '
Dr PROTECTIVE ACTION shG
=.; ;
$ 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 suffiz 1) 3100 to 15600 Evacuate everyone O to 4 miles in all 6 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 O to 10 miles in all directions. (All areas with number suffixes I and 2)
Children and pregnant women Everyone NOTE: The 2 mile Insegency P1 - 4= Zone on the evacuation map will always ,
. .)
be evacuated if evacuation of any area is required. f.j,h
. v.c i.;
-gg = * ~ i w - q, --a e + .oe- - t -n--s -r<rm avs- . w -
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_;a, ; _ s.. .: Page 6 of 6-DCI,0 SIDE' 4.2 AP/0/B/1000/07 . 1 Additional Notes or Cemments~ O " DDW mA44e g
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Checked contral copy Paga 1 cf.7 .' - l Time /Date . ! ENCLOSURE 4.3 Q tiSj-OCONEE NUCLEAR STATION 0FFSITE DOSE CALCUIATION VENT RELEASE; NO LOCA
~-
AP/0/B/1000/7 Unit Calculation performed by
~
l
- 1) A) Now /
- 5) Incident /
C) Hours Since Incident
- 2) Meteorology Data - 15 minate average.
NOTE: Sources of data are listed in order of perferimee. If the .4.Q first choice is unavailable, use the second choice, etc. Fill q~ y in only one blank for each data point. - (A) AT('F) 1) Tcuer 'F
- 2) Use a AT of 0.4'F if tower AT is not available.
(B) Wind Direction Tower * -
- 1) --
River
- 2)
- 3) National Weather Service *
(C) Wind Speed 1) Tower sph
- 2) River sph National Weather Service
- 3) sph- -
NOTE: National Weather Service data, is a standard observation, not a 15 minute average and is updated only once per hour. j T-
, k * . _A
<.,m. . ..#, , ;*, . - i 7. ' ( ,. i; ,/1. 3 ' .L' .
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l
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xG c.'=-u ;a:::h i Page 2 of 7
% H CLOSURE 4.3 f
AP/0/B/1000/07 . i 1
- 3) Determine through which unit vent (s) (if any) activity is being released. ;
Vent releases may occur on all three units' vents simultaneously since I the Oconee AmdWry Building is one enclosure with three vents. Vent release on Unit (s) .
- 4) Recorti the following information for the a'ffected unit (s) vent monitors Adentified in Ste'p 3. .
Unit 1 Unit 2 Unit 3 Unit Vent Flow (Fv) (A0946) cfm cfm cfm RIA-45 (A1679) cpu cpm cpu RIA-46 (if > 10 cpe) (A1680) cps eye cps RIA-44* (R-1678) u, '.? a) -Start of time period
-count rate cpm cpm cps b) -end of time period
-coun: rate cps cps eps c) -A time ' min ein. ein
-A. cpm .
NON: If the RIA Chart is used' as a reference use the 15 minute interval Man the last hour that had the greatest increase in RIA-44 counts. RIA-44 rate of increase may be read directly from the computer. (R-1678) ] i
- 5) !!niciply unit vent flow times the RIA readings and add to the results as i follows for the affected units' vents.
a) Noble Gas (NG) . Fr x RIA-45 (com)~ a
.. *$ 5 S U-2 =
- U-3 x =
\ ! to M RIA 4 = l t__ _ __ _
Msa,,;+;;1;J +ww:a: -: a:<:.1 - 1:. ne k; % ,L.,. a 2 .u.:., y ,(.
. -_ g :.: :,+: f . f :
Pagm'3 cf 7 , O
~
ENCLOSURE 4.3 M.n ,3 AP/0/B/1000/07 ,
. RIA-46 Pr x RIA-46 (cpe)
U-I x = U-2 x = U-3 x = . total RIA-46 = NG = [ total RIA-45 x 1.71 E-8] + [ total RIA-46 x 6.82E-41 NG = (record this value on Step 6) b) Iodine Vent (IT) RIA-44 g , ,a RIA-44 (com) a time (min) U-1 x = , U-2 x = U-3 x = total RIA-44 = __
~
IT = total RIA-44 x 2.76E-7 I= g (record this value on Step 6)
- 6) Calculata Dr by comparing Total Iodine (I )T vs Noble Gas (NG)
II (SC8P Sb) = NG (Step 5a) = _ Dr = if > NG, Dr = I , ' if I NG, Dr = NG DT =
- 7) . Is time of day between 1000 hrs and.1600 hrs. (10:00 an and 4:00 pm)?
If yes, so to Step 8. - If no, so to Step 12. , J Ctte.;
. %i:7
- - - _ _ - - - - . - - - -- ----z-R _
--~ibmdsw== rmwnmen&~ymmmmwFerW*~"?""MW"W'M *~WM** I 5 gmay. : ,. 3;-~_a.n. . . ht,(
;aa.% g & M-w 5m ure.':?A N N-e h ..a2L M;;a b Page 4 of 7 l
l
- ENCIOSURE 4.3 AP/0/B/1000/07 .
- 8) Calculate DW (wind deter =4a-d dose) based upon DT (Step 6) and WS (wind speed).
DW
=h . . _ . _ _ . . .. . _ . - .
- 9) Dee==ine distances and level of protective actions based upon DW (Step 8) and ATT from table below:
Number suffix of areas on evacuation map to be evacuated: - Nid- and pregnant women . Everyone _ Fi.nd the horizontal row corresponding to the AT*F. Follow across the row fres left to right until the box cone =4ning the calculated DW value is reached. Read down the vertical column to find the appro-
- Y' priate actions and the corresponding distances from the plant.
AT*F DU DW - DU DW A) -* to -1.3 12.09E1 2.09E5 to 7.8E5 7.815 to 3.9E6 >3.9E6 B) -1.2 to -1.0 ,g.4E3 5.4E3 to 2.70E4 2.7E4 to 3.2E5 ~ >3.2E5 I C) -0.9 to -0.4 12.09E3 2.09E3 to 1.04E4 1.04E4 to 7.4E4 >7.4E4 D) -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- Evacuata procedure and pregnant voe- one 0-4 miles everyone is com- en 0-4 miles (Downwind areas 0-4 miles plated (Downsind areas with suffix 1) (Downwind with suffir 1) area with suffix 1) No action for Evacuate chil- Evacuate 4-10 miles dren and pres- everyone nant women 4-10 4-10 miles ailes (Dowavind (Downwind areas with. suffix areas with
- 2) suffix.2)-
m
-~=neew.w -
.,..,.n:-,=,-
- m .:.,..mmmy ep gwe g-te m g m yq3-ym
. ,,g tn,g:;,-;~
... . . s . .- .. ._ .. . , . . . . . . . . . . . _
Page 5'of f , ENCIOSURE 4.3 t.. c . . AP/0/B/1000/07 . . Example: If AT*F is -1.1 and DU is 2.9E4, evacuate everyone from 0-4 miles and children and pregnant women front 4-10 miles.
~
- 10) a) Is wind speed > 5 mph?
D. If yes, use table in Step 10 h. G If no, assume Sectors A1, B1, C1, D1,'EI, and F1 are affected. Then use Table 10b to determine additional areas to be evacuated.out beyond 1 4 miles. b) Wind direction (from) and wind speed - 15 minute average. Beverify every 15 minutes. 1st 15 min. average *; aph 2nd 15 min. average *; aph t l 3rd 15 min. average *; uph, .KT l 4th 15 min. average *
; mph l _
l l find the wind direction. and follow across the row to find the _ l letter prefixes of the areas on the evacuation map to be evaca- , ated and record. S% T. r o y .ng,,
l . . b;== e s*y,w wc. m im c+w J.m f m-1 .t.= ~ w -r &~'R-- ~ w, _r._-h v se - uN'R_.,pem ?"'W;7Z
-_2 , . e. _weg.
., .. _ Page 6 of 7 g INCLOSURE 4.3 AP/0/B/1000/07 . !
l l 1
. 1 Wind Direction Letter Prefixes of i
(Eros) Areas to be Evacuated ( _ . - - - -- l __ 15* - 41' C, D, E l 41* - 67* D, E 67* - 103* D, E, Y 1 103' - 127' E, F ., 127' - 174* A,E,F 174* - 182* A, T 182* - 215' A,B,F 215' - 256' A, B 256* - 270* A, B, C 270* - 298* B, C 298* - 344' . B, C, D i 344* - 15' C, B c) . Ietter prefixes of areas on evacuation may to be mcuated : 1
- 11) Combine the numbers determined in Step 9 with the letters from Step 10 to, determine which sectors of evacuation may to evacuate.
. . ._ _ Children and pregnant women
. . Everyone- ...
NOTE: The 2 mile Emergency Pl==4=g. Zone on the evacuation map will always be evacuated if evacuation of any area is required.
- 12) Use the table below if time of day is not between 1000 hrs and 1600 hrs.
Apply the DT value from Step 6 on the table below. Read the corres-3g M4== action in the columa te the right and record. d
.- , . , , , - . - - , , . . , _ , _ _ _ , ._.._____.____._,______u-_
1M sie?M cBNGe %:a.;:Ad M&_ ubs:+2%eM ir..ev... - zaQskihhn.n _4f_d;gy;.k 1 s
)
PageTofi , ,' l ! ENCL 0SURE 4.1 6dL l Tpt-i AP/0/3/1000/07 . Dr PROTECTIVE ACTION
' ~
( < 610 No protective action is necessary l 610 to 3100 Evacuate children and pregnant women 0 to 4 M1** in all directions (all l areas witit number suffir 1) 3100 to 15600 Evacuate everyone O to i miles in.all I directions. (All are.s with number., suffix 1). Evacuate children and .. l I pregnant women 4-10 miles in all directions. (All areas with ansber suffir 2)
> 15600 ~
Evacuate everyone O to 10 miles in all directions. (All areas with number suffixes 1 and 2)
..r -
Children and pregnant women m - 4:Eh Everyone NOTE: The 2 mile Emergency Pl=a4=g Zone on the evacuation map will always be evacuated if evacuation of any area is required.
~~
Additional Notes or Comments e 4 h" ' Q, ~%. g 9 6
,_.____,,_,_,,,___.,__N ' ,ot-eew'w--e-
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LHLCKLD CUNIRUL COPY
. .. 4 Page 1 of I ~
Date ._ . l ENCLOSURE 4.4 SURVEY INSTRUMENT CORRELATION CURVE ' TUfE VS. CORRELATION FACTOR II 10 ., _ AP/0/B/1000/07
. .._. . _ . _..~.
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Date . - Checked Control Copy . ENCLOSURE 4.5 STABILITY CLASS
.1
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AP/0/B/1000/07
- 1) AT Stability Class . _ . _ _ . _ . _ _ _ .
-= to -1.3 A
-1.2 to -1.0 C s .
-0.9 to -0.4 2.. . .D .
-0.3 to +0.9 E -
+1.0 to +a F l
NOTE: Circle current atmospheric stability class. This information is used in the " warning message" to offsite agencies. 4 h* c e e f
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Page 1 of 2 Checked With Control Copy Time /Date ENCIOSURE 4.6 OCONEE NUCLEAR STATION
' 0FTSITE DOSE CALCULATION USING C0tfPUTER DOSE ASSESSlfENT PROGRAN Unit '
Calculation Performed By
- 1. Dose Assessment Program (DAP) is general panel program 23 and is available from all panels. The available options are select and abort.
- 2. Upon. initial entry, all inputs associated with the dose assessment procedure will be displayed. Values for the last four (4) items displayed are manual inputs and therefore must be entered by the operator. These =mn:*21 inputs must be entered in all three (3) computers, with correct data for that
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- 3. Ta insert values for the manual inputs, the line finder should be positioned to the appropriate ites and the value keyed in. If the line finder is not positioned go a valid line, the "Posa LF" message will be blinked.
l Shutdown time must be entered in military time (HHtitt) and shutdown date must be entered in a !!t!DDTI formt. Shutdown time and date will be validity checked and if found to be invalid, the instruction message will be blinked. 4 e
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ENCLOSURE-4.6
- 4. After all necessary inputs have been entered, the operator may initiate the dose assessment by positioning the line finder to the designated line and pressing the ENTER button. If any inputs are found to be invalid, the following message will be output on the VIDEO and DAP will turn off:
DUE TO INVALID DATA, DOSE ASSESSMENT CANNOT BE DETERMINED AT THIS TIME
- 5. After initiation,' DAP will printout on the typer associated with the calling Panel the inputs, calculated time factor, corrected dose rate value, stability class and the recommended protection actions to be taken.
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I.~ hPORMATION OK_Y CON"ROL COPY Form 34731 i10-81) (Formerly SPD-10021) DUKE POWER COMPANY (1) ID No: CP/1/A/2002/04C PROCEDURE PREPARATION Change (s) O to PROCESS RECORD 1 Incorporated (2) STATION: Oconee Nuclear Station (3) PROCEDURE TITLE: Ooeratine Procedure for the Post Accident Licuid Samoling (PALS) System (4) PREPARED BY: /- N , DATE: _ 7I26 [X3 I (5)' REVIEWED BY: r - DATE: 7 7
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! / l Cross-Disciplinary Review By: 4 _jmea N/R: (6) TEMPORARY APPROVAL (IF NECES Y): By: (SRO) Date: By: A Date: (7) APPROVED BY , Date: 9 M T3 (8) MISCELLGEOUS: Reviewed / Approved By: Date: Reviewed / Approved By: Date: l
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o Page 1 of 13 2 l Checked Control Copy l , Date j DUKE POWER COMPANY OCONEE NUCLEAR STATION OPERATING PROCEDURE FOR THE i POST ACCIDENT LIQUID SAMPLING (PALS) SYSTEli 1.0 Purpose The Post Accident Liquid Sampling System (PAIS) provides the capability to promptly obtain a reactor coolant system sample under a nuclear reactor accident condition. Sample acquisition during accident conditions will provide information to evaluate the extent of core damage which has occurred or is occurring through knowledge of reactor coolant chemistry and radiochemistry. 2.0 Limits and Precautions 2.1 The PAIS will be used to sample the reactor coolant system under the following conditions: N 2.1.1 Post Accident. j 1 2.1.2 Inaccessibility of Primary Sampling Area due to radiation levels. I
- 2.1.3 Request from the Station Chemist or his designee.
2.2 UNDER ACCIDENT CONDITIONS, VALVE ALIGNME.IS Y SHALL NOT-BE MADE AND SAMPLES SHALL NOT BE TAKEN WITHOUT PRIOR AUTHORIZATION FROM THE l TECHNICAL SUPP0T CENTER (TSC)! (Containment Isolation valves may be I closed upon ES Actuation). [ 2.3 UNDER ACCIDENT CONDITIONS, DO NOT AITEMPT ANY PHASE OF SAMPLING OR l , ANALYIS WITHOUT HEALTH PHYSICS APPROVAL AND COVERAGE! 2.4 Radiation exposure to an individual during all phases of sampling should be limited so as not to exceed a quarterly accumulative exposure of 3 rems whole body; 7.5 rems skin of wholebody; or 18 3/4 rems extremities respectively. All personnel will need prior authorization from TSC to knowingly exceed any exposure limit. The exposure received may require an occupational exposure penalty and/or a medical decision as to whether an individual can continue in radia-tion work. 2.4.1 If necessary to remedy a situation inneediately hazardous to life and property, the Planned Emergency Exposure for Duke .). Power Personnel will not exceed 5 rems wholebody; 30 rems ./ skin of wholebody; or 75 rems extremities.
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' CP/1/A/2002/04C 3 Page 2 of 13 i
2.4.2 If necessary to save lives or prevent loss of life and/ or extensive damage to property (voluntary basis only), the Planned Emergency Exposure for Duke Power Personnel will not exceed 25 rems wholebody; 150 rems skin of wholebody; or 375 rems extremities. 4-2.4.3 For Outside Services Personnel the Planned Emergency Exposure will not exceed 5 rems wholebody; 30 rems skin of wholebody; 75 rems extremities; or 15 rems other single organ. 2.5 Portable shielding, remote handling equipment, video equipment, etc., shall be used where practical during sampling, sample preparation, and sample analysis.
. 2.6 Chemistry personnel shall operate only those valves followed by (C) in this procedure. If ES signal requires containment isolation during use of this procedure, Operations and Chemistry Personnel should be aware of any pressure remaining in sample lines or sampling panel.
2.7 Working copy must be compared to control copy before use and sign off steps (Initials / Time) completed as procedure progresses.
- 3.0 Procedure J
NOTE: In order to maintain the PAIS in operable condition at all times, the requirements on Enclosure 5.2, PALS Semi-annual Calibration Checklist must be done semi-annually and be current prior to Post Accident sampling. Enclosure 5.1, Post Accident Authorization for Operation of PALS, must be completed prior to Post Accident sampling. _ . 3.1 Preparation for Sampling 3.1.1 Valve Alignments 3.1.1.1 Notify Shift Supervisor that operation of the PAIS is being initiated by Chemistry. Chemistry l' will select either Enclosure 5.5 for a RCS sample or Enclosure 5.6 for a RBNS sample, check it against the control copy, and take it to the responsible individual in Operations (designated by the Shift Supervisor) for completion. Request Operations to complete Step 3.1 of the selected enclosure. / 1 3.1.1.2 The following valves are electrically controlled ' by the PALS Control Panel: RCS Sample: IRC-179 (C) Reactor Building Normal Sump Sample: 1 LWD-1026 (C) 1 LWD-1028 (C)
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, Page 3 of 13 l Return Line to Reactor Building Emergency Sump (either sample): ILP-121 (C)
. Demin. Water: 1DW-278 (C) (RCS Sample Line Flush) 1DW-280 (C) (RBNS Sample Line Flush) 3.1.1.3 The following valves are operated manually at the Sampling Panel by Chemistry personnel. They must be verified open prior to use of the panel.
Initials / Time Instrument Air Supply Isolation / IIA-2423 Panel Instrument Air Isolation / Nitrogen Supply Isolation IN-262 / Panel Nitrogen Isolation / Cooling Water Supply Isolation 1DW-282 / Demin Water Supply Isolation IDW-281 / Panel Demin Water Isolation /
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3.1.1.4 The following should be verified as noted prior to -' periodic testing (not required for accident conditon): i ILWD-1029 Low Point Drain (LPI Room) closed and capped - 1RC-177 Kigh Point Vent (next to Sfspling Panel) closed and capped ILP-110 Emergency Sump Line Drain (LPI Roos)
. closed
( ILP-111 Emergency Sump Line Drain Tell-tale (LPI l Room) Closed and capped l l LDW-278 Remote Starter (LPI Room) "0N" ILWD-1028 Remote Starter (LPI Room) "0N" 1DW-91 Reactor Building Normal Sump Line Flush (LPI Room) Closed I
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3.1.2 Health Physics Notification Contact Health Physics and ask for surveillance person prior to going to Control Panel. / 3.1.3 Additional Requirements Record specific conductivity of buffer solution from
-, Primary Chemistry Data Log. Pick up glass syringes and sample carrier from Primary Lab (or Radwaste Lab, whichever is more accessible), and take stop watch and i panel keys to Control Panel. -
/
3.2 Panel Preparation NOTE: If any item on panel is not clearly identified, refer to Enclosures 5.3 and 5.4 (Control Panel Diagrams). 3.2.1 Turn the main selector knob on the control panel to
" Reset". Place key in System Power Switch and turn clockwise. (Panel lights should come on.) Press " Reset" button.
3.2.2 Place the toggle, switches for the dilution water meter and dilution gas meter to "0N". 3.2.3 Place the toggle switch for the radiation monitor to "0N" and turn the scale select to "res/hr". If the radiation monitor is not functional, HP coverage is sufficien+; to operate the panel. (If this is a routine test, sutait a WR for repair). 3.2.4 Place the temperature probe selector to position 1. 3.2.5 Move the conductivity meter to " Measure" position. 3.2.6 Push in the pH meter standardize knob. 3.2.7 Select the system to be sampled - Reactor Coolant System or Reactor Building Normal Sump - with the system selector. 3.2.8 If RCS is to be sampled, open' sample regulator valve at [ cooler outlet approximately h turn open. If RBNS is to be sampled, open sample regulator valve at cooler outlet approximately 4 turns open. Adjustments may be made in Step 3.4.5, if TC-1 indicates greater than 190*F. / l 1 3.3 Panel Operation (Position 1) Panel Prep 3.3.1 Turn the Operation Selector' switch to the PANEL PREP. position. 3.3.2 Momentarily depress the SELECTION PoteT.R ACTIVATE pushbutton.
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3.3.3 Depress the PURGE pushbutton for about 1 minute 10 seconds. 3.3.4 Depress the DRAIN pushbutton for about 1 minute 10 seconds. 3.3.5 Depress the CALIBRATE pushbutton and hold until the conduc-1 tivity and pH meter readings stabilize. 3.3.6 Record the conductivity rsading pahos/cm.
The conductivity should correspond with the specific conductivity of the pH standard measured in the lab. If not, contact Station Chemist or Primary Supervisor. (If this is a routine test, initiate a Work Request for repair.
For an accident condition, personnel should move to a lower background area during this time, if one is available). NOTE 1: Conductivity probe has a cell constant of 10 and has 10% inherent error. NOTE 2: Multiply conductivity meter reading by 1000 to obtain specific conductivity value. 3.3.7 Adjust the pH meter to the known pH of the standard. / 3.3.8 Depress the PURGE pushbutton for about 30 seconds. 3.3.9 Depress the FLUSH pushbutton until the conductivity and pH meter readings stabilize. 3.3.10 Depress the PURGE pushbutton for about 30 seconds. ' 3.3.11 Depress the DRAIN pushbutton for about 60 seconds. 3.3.12 Repeat Steps 3.3.9, 3.3'.10, 3.3.11 and then continue to Section 3.4. ,
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3.4 Panel Operation (Position 2) Sample Recire 3.4.1 Request Operations complete Steps 3.2 and 3.3 of the enclosure selected in 3.1.1.1.
, ,3.4.2 , ,T, urn ti,he Operation Selector switch to the SAMPLE RECIRC.
position. I 3.4.3 Record the PALS or HP radiation monitor reading (background). Watch radiation monitor reading for an increase as sample enters the panel. l 3.4.4 Momentarily depress the SELECTION POWER ACTIVATE pushbutton. 3.4.5 Observe that the SAMPLE INLET and SAMPLE OUTLET indicating lights are lit. Record the starting time .
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l' [r . CP/1/A/2002/04C Page 6 of 13 3.4.6 If TC-1 goes above 190'F, sample is not being sufficiently cooled. Turn selector to " Reset". Press " Reset" button and turn Power key to vertical position. Contact Station Chemist or his designee. (For an accident condition i personnel should move to a lower background area during this time, if one is available.) If TC-1 is less than 190*F, record the temperature . 3.4.7 If sample recire. is done during the semi-annual check, a visual inspection of accessible portions of the system i should be performed for the purpose of identifying any external leakage during testing. Work requests shall be written promptly to eliminate any leakage found. 3.4.8 Turn the selector knob to " Sample", position 3. 3.5 Panel Operation (Position 3) Sample 3.5.1 Turn the temperature selector to TC-2. 3.5.2 Momentarily depress the SELECTION POWER ACTIVATE pushbutton. 3.5.3 Observe that the SAMPLE INLET and SAMPLE OUTLET indicating lights are lit. 3.5.4 Monitor the temperature gauge and when TC-2 stabilizes, record the temperature .
- 3.5.5 Record the PALS or HP radiation reading . Sub-tract the initial background reading from sample radiation l
reading and record. l 3.5.6 Press the 1) TC-2 Stabilize Activate button; when pressure ! , reading stabilizes, record . 3.5.7 Press the 2) Pressure Stabilize Activate button and record time sample flow stops . 3.5.8 Request Operations to complete Step 3.4 of the enclosure selected in 3.1.1.1. j 3.6 Panel Operation (Position 4) Depressurization l l 3.6.1 Turn the Operation Selector switch to the DEPRESSURIZATION l position. 3.6.2 Press the " Reset" button on the gas flow totalizer to zero . 1 the readout. Preset the counter on the totalizer to 99999. 3.6.3 Momentarily depress the SELECTION POWER ACTIVATE pushbutton.
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, Page 7 of 13 j . X l 3.6.4 Observe that the DI WATER and SAMPLE OUTLET indicating j lights are lit.
3.6.5 Verify the pressure gauge on the instrument panel indicates
-25 inches of Mercury. Wait about 60 seconds.
4 3.6.6 Press the START button on the N2 Preset Counter and observe the PRESS /VAC gauge. When the gauge needle just begins to move press the STOP button on the Na Preset Counter.
- 3.6.7 Continue to make small N2 adds, by repeating 3.6.6 until i the PRESS./VAC gauge reads about 0-2 inches.
3.6.8 Flip the Preset Counter POWER toggle switch to the OFF
, position.
3.6.9 If "5" inches is exceeded, as read from the PRESS./VAC gauge, a new sample will need to be taken. I 3.7 Panel Operation (Position 5) Liquid Sample 3.7.1 Turn the Operation Selector switch to the LIQUID SAMPLE position. i 3.7.2 Momentarily depr'ess the SELECTION POWER ACTIVATE l pushbutton. N I 3.7.3 Observe that the DI WATER and SAMPLE OUTIII ' indicating s
=
lights are lit. 3.7.4 Depress the LIQUID SAMPLE ACTIVATE 1) Log conductivity and l hold until the conductivity meter stabilizes. Record the specific conductivity . 3.7.5 Press both LIQUID SAMPLE ACTIVATE 1) Log conductivity and
- 2) Log pH buttons and hold until pH meter stabilizes.
Record pH . 3.7.6 Press the GAS SAMPLE 1) ACTIVATE button and hold for 1 second. 3.7.7 Momentarily depress the 3) DILUTED GAS SAMPLE GRAB pushbutton. 3.8 Panel Operation (Position 6) Liquid Sample Prep-3.8.1- Turn the Operation Selector switch to the LIQUID SAMPLE PREP position. 3.8.2 Momentarily depress the SELECTION POWER ACTIVATE - pushbutton. 1 -J
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3.8.3 Momentarily depress the ACTIVATE TO DESIRED mL VOLUME pushbutton and observe the^ SAMPLE ALIQUOT register advance
, one count (0.70 ml).
, 3.8.4 Press the " Reset" button on the dilution water flow totalizer and preset the meter for desired dilution (in 250 ml increments from 250-3500 mls). Press the " Start" button and let the dilution continue to co.apletion. Record the
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dilution volume . 3.~8.5 Press the Activate Mix button and hold for about 15 seconds. 3.9 Panel ' operation (Position 7) Liquid Sample 3.9.1 Turn the Operation Selector switch to the Liquid Sample position. 3.9.2 Press the SELECTION POWER ACTIVATE button. 3.9.3 Press Activate button. Wait 45 seconds (for levels in dilution cylinder and grab sampler to equalize). 3.9.4 Momentarily depress the DILUTED SAMPLE GRAB pushbutton. Wait 10 seconds.- 7 3.10 Panel Operation (Position 8) Flush 3.10.1 Turn the Operation Selector switch to the FLUSH position. 3.10.2 Press the SELECTION POWER ACTIVATE button. 3.10.3 Press the FLUSH ACTIVATE button and wait 4-i minutes. (Observe that the first FLUSH light and the SAMPLE OUTLET indicating light are both lit.) 3.10.4 Press the FLUSH ACTIVATE button and monitor pH and conduc-tivity meters until they reach equilibrium of desineralized water (approximately 10 minutes). Observe second flush light is lic.'
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l 3.10.5 ' Press the FLUSH ACTIVATE pushbutton and wait 3 minutes. l i (Observe the third FLUSH light is lit.)- 3.10.6 Press the FLUSH ACTIVATE pushbutton and observe the COMPLETE light is. lit. l 3.11 Panel Operation (Position 9) Drain 3.11.1 Turn the Operation Selector switch to the DRAIN position. 3.11.2 Momentarily depress the SELECTION POWER ACTIVATE y pushbutton. Press ACTIVATE and observe that the first
-DRAIN light is lit.
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. CP/1/A/2002/04C
. Page 9 of 13 .
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3.11.3 Wait for about 2 minutes and again depress the ACTIVATE pushbutton and observe the second DRAIN light is lit. 3.11.4 Wait for about 2 minutes and again depress the ACTIVATE pushbutton and observe the third DRAIN light is lit. 3.11.5 Wait for about 6 minutes and again momentarily depress the ACTIVATE pushbutton and observe the DRAIN COMPLETE light is lit. 3.12 Panel Shutdown and Decontamination
. 3.12.1 Turn the Sample Selector switch to the OFF position.
3.12.2 Turn the Operation Selector switch to the RESET position. 3.12.3 Momentarily depress the RESET pushbutton. 3.12.4 Turn the System Power keylock to the SUMP PUMP position for about 15 minutes (or until the pump switches itself off). 3.12.5 Turn the System Power keylock to the SAMPLE position and record the PAIS or HP Radiation Monitor meter reading . 3.12.5.1 If the radiation field at the PASP is less than 3 'N R/Hr turn the System Power keylock to the OFF , position and remove the PALS System key. ' 3.12.5.2 If the radiation field is greater than 3R/Hr repeat 3.10 thru 3.12.5. 3.12.6 If radiation level remains greater than 3 res/hr after one repeat of Section 3.10 through 3.12.5, contaEStation Chemist or his design'ee (for an accident condition
= personnel should move to a lower background area during this time,- if one is available) for permission to return to Section 3.1 and take another sample using larger dilution volume. Permission given by .
- 3.12. 7 - "Requert HP to survey the Post Accident Sampling Panel and the area around the PASP prior to sample removal to ensure the 3 R/Hr-is not exceeded.
3.13 Sampling 3.13.1 Collect 3-1.0 mi stripped gas samples at the gas grab sampler in lockable glass syringes. ' Place in plastic bag. 3.13.2- Collect 3-5.0 mi liquid samples at the liquid. grab sampler - + in. lockable glass syringes. ' Place in plastic. bag. o w - @_. ~ y+ eore. em, a w+ % w a s a. -- n
- CP/1/A/2002/04C Page 10 of 13 NOTE: Flushing of remaining sample in grab sampler is desirable if radiation levels permit. Return to Position 6 and add 200 mis demin. water to Dilution Cylinder. Continue through Position 7, cycle through Position 8 and 9 completing the second and third drain steps. Go to the grab sampler and drain the liquid out (this liquid is ng a sample-discard in PASP Sump or appropriate waste container in lab).
3.13.3 Request Operations to complete Steps 3.5 and 3.6 of the enclosure selected in 3.1.1.1. 3.13.4 Place plastic bags in sample carrier and transport to Hot Lab. Place sample carrier in operating fume hood behind a lead brick shield to await analysis. 3.14 Sample Analysis 3.14.1 Gas a 3.14.1.1 Analyze one syringe of stripped gas by Chemistry Procedure CP/0/B/2004/14A, Operation of the Fisher Model 25V Gas Partitioner for the Determi-nation of Hydrogen in Gas Samples. Calculate the results by the following method:
- 7. H2x 0 x = cc/Kg H2 3 g Where: 7. H2 is determined from CP/0/B/2004/14A 1000 cc = stripped gas bomb, volume 0.155 Kg = collected sample size 1 = conversion of percent to W decimal Report result cc/kg Ha
~3.14.1.2 Withdraw I cc of air from septum stoppered glass vial and load I cc of stripped gas into it from second syringe. Analyze by GeLi Spectral Analysis (HP/0/B/1001/14, Procedure for Nuclear Data 6600 System Operation). Activities will be reported by HP for I cc of diluted gas sample.
Calculate activity of dissolved gas in 1 ml of reactor coolant as follows: pCi in 1 cc x 1000 = Total activity from dissolved
" Tai gas in 1 ml RC.
GeLi Spectra Attached .
CP/1/A/2002/04C Page 11 of 13
'1 3.14.1.3 Reserve third stripped gas syringe for use as a backup, if needed.
3.14.1.4 Additional gas sample dilutios may be necessary i to bring amount of hydrogen or activity within range of analyses. If so, withdraw 1 cc of air from a septum stoppered glass vial and load 1 cc of the sample to be diluted into it. Be sure to record the additional dilution information so that isotope activities may be adjusted accordingly. 3.14.2 Liquid 1 3.14.2.1 Take 1 ml of liquid sample and dilute to 50 ml with Super Q water in a 60 ml poly bottle. Analyze by GeLi Spectral Analysis (HP/0/B/1001/14, Procedure for Nuclear Data 6600 System Operation). Activities will be reported by HP for 1 ml of diluted liquid sample. Calculate activity of liquid portion of reactor coolant as follows: pei/ml = activity in diluted 1 31 x
- Total Dilut on Volume
- Step 3.8.4 + 0.7 mis. j GeLi Spectra Attached .
3.14.2.2 Take 5 ml of liquid sample and analyze for boron by CP/0/A/2004/02E, Post Accident Determination of Boron Concentration Using Carminic Acid. Correct results for dilution as follows:
- Total-Gilution Volume ppm BRCS
- ppm measured x
- Step 3.8.4 + 0.7 als Boron Concentration ppe.
3.14.2.3 Take 5 mis of liquid sample and analyze for chloride by CP/0/A/2004/03C,' Post Accident Determination of Chloride by Specific Ion Electrode Using Beckman 4500 Meter. Correct results for dilution as 'in 3.14.2.2. NOTE: Chloride analysis only to be done in an , eccident situation. Chloride Concentration ppe. l t I
.s
e t __ '
- CP/1/A/2002/04C Page 12 of 13 3.14.2.4 Report re: les of liquid sample analyses in Primary Chem.stry Data Log.
3.14.2.5 Reserve third liquid syringe for use as a backup,
, if needed.
3.14.2.6 Additional liquid sample dilution may be neces-sary to bring amount of activity within range. If so, withdraw 1 al of sample from 60 mi poly bottle (from Section 3.14.2.1) and dilute to 50 ml with Super Q for analysis. Be.sure to record the additional dilution information so i that isotope activities may be adjusted accord-4 ingly. 3.14.2.7 Route completed procedure to Technical Support Center (for routine sampling to Primary Super-visor). Accepted By: 3.15 Waste Disposal 3.15 .1 Determine by detailed planning meeting the exact course of action to be taken. Under no condition will liquid or solid wastes be disposed of without prior specific HP directions. 3.15.2 Designate a sealable carboy as the " Post Accident Lab Waste" container. This container must be shielded and used as an interim liquid waste disposal container for all liquid analytical waste. 3.15 .3 In the event an area is grossly contaminatedand cannot be decontaminated, evaluate the need for shielding or protec-tive covering to prevent the spread of airborne activity. 4.0 References 4.1 NUREG-0737, Section II.B.3 4.2 DPC System Health Physics Manual 4.3 Radiological Health Handbook, U.S. Dept. of HEW (1970). 4.4 Radiation Safety Technician Training Course, N.J. Moe, ANL-7291 Rev. 1 (1972). 4.5 Post Accident Liquid Sampling System Manual, Steam Production Depart-ment, OM-267A-28 (1981)
- n. .- -
- CP/1/A/2002/04C Page 13 of 13 4.6 MNS Operating 'rocedure OP/0/A/6200/48 2 4.7 DPC Alara Manual (1980) .
4.8 ONS Emergency Plan 4.9 ONS Chemistry Manual Section 5.1 5.0 Enclosures 5.1 Post Accident Authorization for Operation of PAIS 5.2 PALS Semi-Annual Calibration Checklist 5.3 PAIS Control Panel Diagram - Left 5.4 PALS Control Panel Diagram - Right 5.5 Operations Checklist for Reactor Coolant System Valve Lineups to Post Accident Liquid Sampling System 5.6 Operations Checklist for Reactor Building Normal Sump Valve Lineups to Post Accident Liquid Sampling System. 5.7 Preparation of Thiosulfate Solution for Containment Air Post Accident Sample Panels
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Date ENCLOSURE 5.1 CP/1/A/2002/04C POST ACCIDENT AUTHORIZATION FOR OPERATION OF PALS Technician / Time
- 1. Verbal / written direction for sampling the Reactor Coolant System (RCS) has been received from the Technical Support Center' (TSC). /
Person Authorizing Sampling
- 2. The specific post-accident analysis requested by TSC: /
Sample to be taken: RCS C RBNS C / Boron Chloride Isotopic Analysis for Iodines Cesiums Noble Gases Non-Volatile Fission Products Other (Specify) --_.
- 3. Determine by detailed planning meeting the exact course of action and data required. /
- 4. Evaluate the use of portable shielding, remote handling equipment, video equipment, etc., to minimize the expo-sure to personnel while sampling. /
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- 5. Have EP determine the required respiratory equipment and protective clothing to prevent or minimize internal exposure in any Planned Emergency situation. Use high range and/or extremity dosimetry if required. /
- 6. Request HP to designate a route from PALS to the lab. /
Sample route designated:
- 7. Evaluate the use of portable shielding, remote handling equipment, video equipment, etc., to minimize the expo-sure to personnel in the lab for the required analyses. /
4 i Checked Control Copy i
~~ , Date s 1
ENCLOSURE 5.2 CP/1/A/2002/04C 1 PALS SEMI-ANNUAL CALIBRATION CHECKLIST
- 1. pH 7.4 buffer must be replaced semi-annually. Prepare 4 liters buffer by CP/0/B/2004/09C. Measure specific conductivity and report in Primary Chemistry Data Log.
Buffer Erpiration Date: Specific Conductivity: pahos/cm Technician /Date: /
- 2. Verify the 1000 ppe Boron standard currently in use in the Primary Lab will not expire prior to next semi-annual checklist.
1000 ppe Boron Std. Expiration Date: Technician /Date: / Carminic acid and 10 ppe Boron standard are to be made prior to sampling.
'}
- 3. pH and conductivity meters must be checked when buffer solution is '
renewed. Complete PALS operating sections: 3.2.1, 3.2.5, 3.2.6, 3.3.1 through 3.3.11. Turn System Power Key to vertical position to deenergize panel. Calibration Date: Technician
~~~~
4 Return enclosure to Primary Supervisor or his designee. i ! =
l e ENCLOSURE 5.3 CP/1/A/2002/04C P.U S Control Panel Diagram - Left ,_ i D R AIN OFF RESET PANE L PREP. d @ aai 4-ooo Oc. @ $ $ $ w, e.u- 5 3 0 FLUSH 9 1
- SAMPLE RECIRC.
DhM o00 hC* a 2 Mitew TC.-l b 6dn M LIQUID SAMPLE 7 3 SAMPLE h g pediv Is.L5 s M 44 f Tc7 5%bMus, Adtv tg3A i)@DNhd h Wy 6 4 M** MN"'h38 vs+s LIQUID SAMPLE PREP. OEPRES$URl2ATION 10U10 SAMPL (6AS dMh \ g n or<.t g Att,;ty PI) (%.sc.t 4t C ute.f se h ^^^^9 g g A&.ie. 6 Vdd A SAMPLE kN b" w v.tu.*a. Se, g') Ad;4 c) Steg C.wtar of' o-2." h % t u h ter b ) AAgt 4-4 P **"'* C o* h uoy u_,:rg;, dtw.We n - u t. 6D L Lt AhhcAAAos. 7.)swe.bIhter@@ ace- %c o - 3%hez En$-1o us.1 o -o sion.w.A Co SY STE'.1 POWE R IM S E L E CT C*. F OV. E R ------ O O go* , '@] @,. haate-
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SEE DR AWING NO. LO401800 FOR PANEL DETAIL
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, ENCLOSURE 5.4 CP/1/A/2002/04C i PALS Control Panel Diagram - Right l-i
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Page 1 of 4 Checked Control Copy p
. Date
_ . CP/1/A/2002/04C _. ENCLOSURE 5.5 OPERATIONS CHECKLIST FOR REACTOR COOLANT SYSTEM VALVE LINEUPS TO POST ACCIDENT LIQUID SAMPLING SYSTEM 1.0 Purpose This enclosure gives the valve lineups needed for Chemistry Personnel to sample the Reactor Coolant System (RCS). Locations of valves are given to facilitate lineups. 2.0 Limits and Precautions 2.1 RIA-54 should be in service and monitored during the course of operation of the PALS. 2.2 Demineralized water header must be in service and have at least
. 60 psi pressure'(per Station Directive 3.1.15).
3.0 Procedure Verification Date Date IniGime IniC7 Time 3.1 Ensure the following breakers are closed: 3.1.1 IL2 Skr. #39 Sampling / Control Panels Power Supply (located next to U2 sampling panel) / 3.1.2 MCC1XL Bkr. for 1DW-278 (RCS sample
.line' flush) and ILWD-1028 (RBNS Sample Line) /
~~ ~ ' "- ~' 3.2 To obtain a reactor coolant sample, the
~~
valves listed in this section should be aligned as follows: 3.2.1 1RC-84 Inside reactor building
- refer to Fill and Vent
. Procedure (OP/1/A/1103/02) to verify OPEN status. /
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, Page 2 of 4 ENCLOSURE 5.5 CP/1/A/2002/04C ,
, Verification Date Date IniGime IniGime 3.2.2 1RC-174/1RC-176 (Test Connections) and IRC-175 (High Point Vent) inside reactor building - refer to Fill and Vent Pro-cedure (OP/1/A/
1103/02) to verify CLOSED Status. / 3.2.3 Open IRC-162 inside c'esctor a building-operated from control room. / / 3.2.4 Open IRC-163 inside reactor building-operated from control room. / / NOTE: The following initial conditions must be obse rved. 3.2.5 Containment integrity is required. 3.2.6 Designate a responsible person in the Control Room to immediately . _ _ _ close the isolation valves (IRC-164 and IRC-165) if an ES actuation occurs. I 3.2.7 Record that containment isolation valves 1RC-164 and IRC-165 are open da OP/4/A/1102/20 (Shift Turnover). 3.2.8 Open IRC-164 in Unit 1 LPI Room-operated from Control Room. / / 3.2.9 Open IRC-165 in Unit 1 LPI Room-operated from Control Room. / / CAUTION: If ES actuation occurs, immediately close isola-tion valves for containment. T l isolation. / l _. - x
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. . Page 3 of 4 ENCLOSURE 5.5 CP/1/A/2002/04C Verification Date Date Init"77ime, IniE7 Time 3.3 To allow recirculation of sample, align ILP-65, return line valve to the RB Emergency Sump:
NOTE: The following initial conditions must be observed. 3.3.1 Containment integrity is required. 3.3.2 Station a responsible person in the vicinity of ILP-65 to immediately close ILP-65 if ES Actuation occurs. This person must be in constant communication with the Control Room the entire time ILP-65 is open. 3.3.3 Record that the valve is open in OP/0/A/1102/20 (Shift Turnover). 3.3.4 Open ILP-65 manual valve (located in Unit 1 LPI Room) to be operated by reach rLd from LPI/HPI
~ Hatch Room 118, 119 (behind breaker panels
- 15' south of _ _ _ _
ILP-21). / /_ 3.4 Chemistry will inform Operations when they have obtained the RCS sample in the panel and the following valves should then be realigned as follows:
. 3.4.1 . ' SLOS,E JRC-165 in Unit 1 LPI Room-operated from Control Room. / /
3.4.2 CLOSE 1RC-164 in Unit 1 LPI Room-operated from Control Room. / / NOTE: Remove the containment isolation valves (IRC-164 and IRC-165) from OP/0/A/ 1102/20 (Shift Turnover).
a v Page 4 of 4 s ENCLOSURE 5.5 CP/1/A/2002/04C Verification , Date Date IniGime IniGime 3.4.3 CLOSE 1RC-163 inside Reactor Building-operated from Control Room. / / 3.4.4 CLOSE 1RC-162 inside Reactor Building-operated from Control Room. / / 3.5 Chemistry will inform Operations when sampling has been completed. At this time, water put in the Emergency Sump Recire. Line shall be drained. (At the discretion of the Shift Supervisor). 3.5.1 Open ILP-110 Drain on Emergency Sump Recire Line (U1 LPI Room). 3.5.2 Check high activity monitor rate in Control Room for indication 's drain has been completed. ! 3.5.3 CLOSE ILP-110 Drain on Emergency Samp Recire Lina (U1 LPI Room). 3.5.4 CLOSE ILP-65 !!anual valve (located in LPI Room) operated by reach rod from ~ ~ - - LPI/HPI Hatch Room 118, 119 (behind breaker panels % 15' south of ILP-21). / / NOTE: This will regain containment integrity. Remove the contain-ment isolation valve per OP/0/ A/1102/20 (Shift Turnover). 3.6 Return completed enclosure to Chemistry personnel operating PALS. / lJ l l
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. Page 1 of 5 Checked Control Copy Date CP/1/A/2002/04C
, ENCLOSURE 5.6 OPERATIONS CHECKLIST FOR REACTOR BUILDING NORMAL SLHP VALVE LINEUPS TO POST ACCIDENT SAMPLING SYSTEM Verification Date Date IniGime Init'77ime 1.0 Purpose This enclosure gives the valve lineups needed for Chemistry Personnel to sample the Reactor Coolant System (RCS)'. Locations of valves are given to facilitate lineups.
( 2.0 Limits and Precautions 2.1 RIA-54 should be in service and monitored during the course of operation of the PALS. 2.2 Demineralized water header must be in service and have at least 60 psi pressure (per Station Directive 3.1.15). 3.0 Procedure -- - Verification Date Date Ini G ime Init'77ime 3.1 Ensure the following breakers are closed: 3.1.1 1L2 Bkr. #39 Sampling / Control Panels Power Supply (located next to U2 sampling panel) / 3.1.2 MCC1XL Bkr. #9C RB Normal Sump Sample Pump Power Suppiy.
/_
3.1.3 MCC1XL Bkr. for IDW-278 (RCS Sample line flush) and ILWD-1028 (RBNS Sample Line). / j 3.2 To obtain a reactor building normal sump sample, the following valves should be r aligned as indicated: l I
s v r
. iga 2 of 5 ENCLOSU.E 5.6 '
CP/1/A/2002/04C Verification Date Date Init./ Time InitT7?ime 3.2.1 White tag open breaker on RB Normal Sump Pump 1A. White Tag No. (Located on MCCIXL). / 3.2.2 White tag open breaker on RB Normal Sump Pump 13. White Tag No. (Located on MCC-1XL) / 3.2.3 _CLOSE ILWD-30 RB Normal Sump Pump 1A Suction. Operated by reach rod on north wall in LPI/HPI Hatch Room 118, 119. / I 3.2.4 CLOSE ILWD-33 RB Normal Sump Pump 1B Suction. Operated by reach rod on north wall in LPI/HPI Hatch Room 118, 119. / 'S 3.2.5 OPEN ILWD-1 Reactor building - normal sump line. This is an ES valve operated from the
. Control Room. / /
3.2.6 OPEN ILWD-2 Reactor building nor-mal sump line. This is an ES valve oper-ated from the Control Room. / /
, 3.3 ,To allo,w rpcir,cuJation of sample, align LP-65, return line valve to the RB Emergency Sump:
NOTE: The following initial conditions must be observed: 3.3.1 Containment Integrity is required. ( I
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. ._- - . . _ _ . . . _ . - . . - .. .c....__. . - . . . . . . . ,
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. ENCLOSURE 5.6 CP/1/A/2002/04C Ve rifi'ca tion Date Date Ini G ime Ini G ime 3.3.2 Station a responsible person in the vicinity of ILP-65 to immediate-ly close ILP-65 if ES Actuation occurs. This person must be in constant communication with the Control Room the entire time ILP-65 is open.
3.3.3 Record that the valve is open in OP/0/A/1102/20 (Shift Turnover). 3.3.4 OPEN ILP-65 Manual valve (lo-cated in Unit 1 LPI Room) to be operated by reach rod from LPI/HPI Hatch Room 118, 119 (behind breaker panels
- 15' south of ILP-21). / /
3.4 Chemistry will inform Operations when they have obtained the reactor building normal sump sample in the panel, and the following valves should then be realigned as follows: , _ _ _ 3.4.1 CLOSE ILWD-2 Reactor building normal sump line. This is an ES valve operated from the Control Room. / /
. 3.4.2 IIOSE JLkV-1 Reactor building normal sump line. This is an ES valve operated from the Control Room. / /
3.4.3 OPEN ILWD-33 RB Normal Sump Pump (1WD-2B) Suction. Operated by reach j rod on north wall in LPI/HPI Hatch Room l 118, 119. / 1 i
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- Page 4 of 5 ENCLOSURE 5.6 CP/1/A/2002/04C Verification Date Date Init./ Time Init./ Time 3.4.4 OPES ILWD-30 RB Normal Semp Pump (1WD-2A) Suction.
. Operated by reach rod on north wall in LPI/HPI Hatch Room 118, 119. /
3.4.5 Remove white tag from breaker on RB Normal Sump Pump 1B. White Tag No. / 3.4.6 Remove tag from breaker on RB Normal Sump Pump 1A. White Tag No. / 3.5 Chemistry will inform Operations when sampling has been completed. At this time, water put in the Emergency Sump Recire. Line shall be drained. (At the discretion of the Shift Supervisor). '
-)
3.5.1 OPEN ILP-110 Drain on Emergency ~/ / Sump Recire. Line (U1 LPI Room) 3.5.2 Check high activity monitor rate in Control Room for indication drain has ---- been completed. / 3.5.3 CLOSE ILP-110 Drain on Emergency Sump Recire. Line. (U1 LPI Room) / / 3.5.4 CLOSE ILP-65 Manual valve.(located i in LPI Room) operated by reach rod from LPI/HPI Hatch Room 118, l 119 (behind breaker panels
- 15' south of l
1 ILP-21). / / l l
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e
i f Page 5 of 5 l 7 ,, . l~ . ENCLOSURE 5.6 CP/1/A/2002/04C Verification Date Date Init./ Time Init./ Time NOTE: This will regain contain-ment integrity. Remove the containment isolation valve from OP/0/A/1102/20 (Shift Turnover). 3.6 Return completed enclosure to Chemistry , Personnel operating PALS. / i l l l - - - -
we j-CP/1/A/2002/04C ENCLOSURE 5.7 PREPARATION OF THIOSULFATE SOLUTION FOR CONTAINMENT AIR POST ACCIDENT SAtiPLE PANELS
~
- 1) Prepare 2 liters of 2.42 x 10 ' i sodium hydroxide by pipetting 0.25 ml of 50% NaOH into a 21 flask i making up to volume.
- 2) Transfer 500 ml t 10 mi by graduated cylinder into each of 4 500 mi poly bottles. Add 1.0 ml of chloroform to each as a preservative.
- 3) Weigh out 4 portions of .3003 2 .0012 g of sodium thiosulfate (NaS 022 5H2 0) and add one portion to each of the four bottles containing Na0H.
- 4) Label these solutions thiosulfate for containment air sampling and date.
(They are stable for 6 months). l
- 5) Keep the solutions in the Primary Chemistry Lab and sign them out to HP when requested in the Primary Sample Log for Unit 1.
/
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